ZS-2019-0090, Revised Final Status Survey (FSS) Report - Phase 2, Release Record - Waste Water Treatment Facility Survey Unit 09100

Revised Final Status Survey (FSS) Report - Phase 2, Release Record - Waste Water Treatment Facility Survey Unit 09100

ML19295G873
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	09/01/2019
From:	Massengill R ZionSolutions
To:	Office of Nuclear Material Safety and Safeguards
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ZS-2019-0090
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{{#Wiki_filter:ZION STATION RESTORATION PROJECT FINAL STATUS SURVEY RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 PREPARED BY / DATE: ______________________________________2019-09-01 R. Massengill, Radiological Engineer REVIEWED BY / DATE: ______________________________________2019-09-01 P. Giza, Radiological Engineer APPROVED BY / DATE: ______________________________________2019-09-01 D. Wojtkowiak, C/LT Manager [2]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

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

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

3. CLASSIFICATION BASIS.............................................................................................. 10

4. DATA QUALITY OBJECTIVES (DQO) ...................................................................... 11

5. SURVEY DESIGN ............................................................................................................ 15

6. SURVEY IMPLEMENTATION ..................................................................................... 21

7. SURVEY RESULTS ......................................................................................................... 22

8. QUALITY CONTROL..................................................................................................... 31

9. INVESTIGATIONS AND RESULTS ............................................................................. 32

10. REMEDIATION AND RESULTS .................................................................................. 32

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN ....................................... 32

12. DATA QUALITY ASSESSMENT (DQA) ..................................................................... 32

13. ANOMALIES .................................................................................................................... 33

14. COMPLIANCE EQUATION .......................................................................................... 33

15. CONCLUSION ................................................................................................................. 35

16. REFERENCES .................................................................................................................. 35

17. ATTACHMENTS ............................................................................................................. 36 ATTACHMENT 1 .............................................................................................................. 37 ATTACHMENT 2 .............................................................................................................. 40 ATTACHMENT 3 .............................................................................................................. 62 ATTACHMENT 4 .............................................................................................................. 65 ATTACHMENT 5 .............................................................................................................. 70 ATTACHMENT 6 .............................................................................................................. 76 ATTACHMENT 7 .............................................................................................................. 77

[3]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 LIST OF FIGURES Figure 1 - Waste Water Treatment Facility Top View from Drawing B-1024 ................................ 9 Figure 2 - Waste Water Treatment Facility after Demolition ......................................................... 10 Figure 3 - Waste Water Treatment Facility Conditions at FSS ...................................................... 10 LIST OF TABLES Table 1 - Dose Significant Radionuclides and Mixture .................................................................. 13 Table 2 - Base Case DCGLs for WWTF (BcDCGLB) from LTP Chapter 5, Table 5-3 ................ 14 Table 3 - Operational DCGLs (OpDCGLB) for WWTF from LTP Chapter 5, Table 5-4 .............. 15 Table 4 - Number of ISOCS Measurements per FSS Unit based on Areal Coverage .................... 17 Table 5 - Adjusted(1) Minimum Number of ISOCS Measurements per FSS Unit ........................ 18 Table 6 - Surrogate Ratios for Auxiliary Building ......................................................................... 18 Table 7 - Investigation Levels......................................................................................................... 20 Table 8 - Synopsis of Survey Design .............................................................................................. 20 Table 9 - Waste Water Treatment Facility - Measured Concentrations of ROC for FSS .............. 24 Table 10 - Waste Water Treatment Facility - Statistical Quantities - Systematic Measurement Population .............................................................................................. 27 Table 11 - WWTF FSS Concrete Core Sample Analysis - Surface to 0.5 inch Depth .................. 29 [4]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable AMCG Average Member of the Critical Group BcDCGL Base Case Derived Concentration Guideline Level BcSOF Base Case Sum of Fractions BFM Basement Fill Model DQA Data Quality Assessment DQO Data Quality Objective DCGL Derived Concentration Guideline Level EMC Elevated Measurement Comparison FOV Field of View FSS Final Status Survey HTD Hard-to-Detect ISOCS In Situ Object Counting System LTP License Termination Plan LBGR Lower Bound of the Gray Region MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDA Minimum Detectable Activity MDC Minimum Detectable Concentration NRC Nuclear Regulatory Commission OpDCGL Operational Derived Concentration Guideline Level OpSOF Operational Sum of Fractions QAPP Quality Assurance Project Plan QC Quality Control ROC Radionuclides of Concern SOF Sum-of-Fractions TEDE Total Effective Dose Equivalent UBGR Upper Bound of the Gray Region [5]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 UCL Upper Confidence Level WWTF Waste Water Treatment Facility ZNPS Zion Nuclear Power Station ZSRP Zion Station Restoration Project [6]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100

1. EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey unit 09100, Waste Water Treatment Facility (WWTF), 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). Final Status Survey (FSS) sample plan for survey unit 09100 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 accordance with ZSRP LTP Chapter 5, section 5.5.2.1.2 and Table 5-19, the WWTF survey unit has a MARSSIM classification of 1. Survey plans were 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 of the WWTF survey unit. As a Class 1 survey unit, ISOCS measurement locations were designated to ensure 100% areal coverage of all accessible structural surfaces within the survey unit. Based on a measurement Field of View (FOV) of 28 m2 for each ISOCS measurement, it was initially determined that fifty four (54) ISOCS measurements were required to ensure 100% areal coverage of the WWTF. Minor modifications to the designed sample plan were required based on the as-left conditions of the WWTF demolition to the 588 ft. elevation. Some measurement locations were eliminated due to the final configuration of the WWTF. Additional measurement locations were added to ensure 100% areal coverage within the survey unit. After making those adjustments to the sample plan, a total of seventy-four (74) ISOCS measurements were taken: seventy (70) systematic measurements on the floor, walls and sumps in addition to four (4) QC samples. The results for all ISOCS measurements taken in the WWTF survey unit indicate that the Sum-of-Fractions (SOF) for each measurement, considering the concentration of all applicable Radionuclides of Concern (ROC), either by direct measurement or by inference, is less than one (1) when applying the respective Operational Derived Concentration Guideline Levels (OpDCGL) for the WWTF (ZionSolutions Technical Support Document (TSD) 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey [Reference 5]). Therefore, the null hypothesis is rejected and the WWTF is acceptable for unrestricted release. [7]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100

2. SURVEY UNIT DESCRIPTION The WWTF was designed to treat non-radioactive and low-level radioactive liquid from Zion Nuclear Power Station (ZNPS) sources including building roof run-off and the Turbine Building Fire Sump, which received liquid waste from the Turbine Building Equipment and Floor Drains, and the Fuel Pool Cooling Tower Blowdown. The WWTF was designed to remove suspended solids and oil to ensure compliance with the facility National Pollutant Discharge Elimination System (NPDES) permit. Since the waste water discharge rates were variable, an equalization tank was installed. The WWTF also included other equipment such as mixing tanks, mixers, oil skimmers, flocculators, oil coalescers, clarifiers, sludge drying beds and filters. Discharge from the WWTF was by gravity to the Forebay. During ZNPS operations, liquid waste with detectable low-level radioactive contamination was processed by the WWTF. Consequently, the internal surfaces of the WWTF systems were considered to be potentially contaminated.

All systems, component and materials associated with the WWTF that were identified by radiological survey as contaminated with detectable plant-derived radioactive material were removed by ZionSolutions personnel and dispositioned and properly disposed of as radioactive waste. The remaining structure was then made Cold, Dark and Dry. Once this was complete, all remaining commodities and all structural surfaces were demolished to a depth of 3 feet below grade. Once the remaining concrete structure located below 3 feet below grade (588 foot elevation) was satisfactorily surveyed and compliance with the unrestricted release criteria was demonstrated and, contingent upon the completion of confirmatory surveys, the WWTF void was backfilled using concrete debris suitable for reuse as clean hard fill and/or clean fill from off-site. The top 3 feet of fill was soil only (i.e., concrete clean hard fill was only utilized as fill up to the 588 foot elevation). The WWTF end state consisted of concrete settling and equalization tanks, clarifiers, flocculant (FLOC) and sludge tanks with sloped bottoms as seen in the top view of the WWTF basement in Figure 1. (ZionSolutions TSD 14-014, End State Surface Areas, Volumes, and Source Terms of Ancillary Buildings [Reference 6]). [8]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Figure 1 - Waste Water Treatment Facility Top View from Drawing B-1024 The northeast portion of the WWTF contained two (north and south) Clarifiers and Flocculant Tanks and a single Sludge Holding Tank. Each Clarifier consists of a mildly sloped floor and is 8 feet wide. There is a pit with angled east and west walls and a 2.5 feet wide floor. A 6-inch opening in the East wall above the pit allows flow to the Flocculant Tank. The west wall of the Clarifier Pit has an average width of 2 feet with a depth of approximately 5 feet. The concrete spans the 18 foot, 6 inch width of the structure. Similarly, the east wall of the pit has an average width of 1 foot 6 inches plus 10 inches or 2.33 feet with a depth of 5.67 feet which with a 18 foot, 6 inch width. Between the walls, the pit floor is 2.5 feet long by 18 feet, 6 inch wide and 1 foot thick. The north and south walls of the clarifier are 10 inches thick and the north wall has an additional 10 inches thick outer layer. The north and south FLOC Tanks are 6 feet long by 8 feet wide and 1.5 feet deep. The west wall has a 6 inch opening and is only 1 foot deep. The Sludge Holding Tank wall slopes from the 587.5 foot elevation to the 583 foot elevation and has a tank interior that is 11 feet by 16 feet 10 inches. The basic decommissioning end state for the WWTF is for the walls, floor, and sumps/pits below the 588 foot elevation to remain. Most of the end state concrete below the 588 foot elevation is above the 579 foot water table. However, after FSS is complete, the floors of the structures will be perforated to ensure they can equilibrate with the water table and [9]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 will not overflow the structure at the 588 foot elevation. Figures 2 and 3 illustrate the WWTF conditions after demolition and prior to FSS. Figure 2 - Waste Water Treatment Facility after Demolition Figure 3 - Waste Water Treatment Facility Conditions at FSS

3. CLASSIFICATION BASIS The WWTF was constructed and placed into service in the fall of 1978. The design purpose of the WWTF was to receive the discharges from the fire sump and the heater bay roof drains. Due to the contamination of the fire sump (as a result of primary to secondary

[10]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 leakage), many portions of the WWTF systems contained trace levels of radioactive contaminants. Sections of the subfloor on the south side of the building were posted for radioactive materials. Additionally, due to the system design and operation, organic contaminants (mainly turbine oil) were assumed to be present throughout the building and components. Piping below the floor on the south side of the building was labeled as radioactive. The following summary of processes and incidents were obtained from the Zion Station Historical Site Assessment (HSA) (Reference 7) and other sources:

• About 10/1/1978 - the Fire Sump discharge and the Heater Bay roof drains were rerouted to the newly completed WWTF in accordance with a commitment to the EPA. The facility was designed to reduce solids in the plant discharge. (NRC IR 78-26/78-26)
• On 11/16/1996 - approximately 1000 gallons of turbine oil was sent to the Fire Sump and the WWTF. (PIF 96-4264)
• On 12/6/1996 - approximately 100 gallons of turbine oil was sent to the Fire Sump and the WWTF. (PIF 96-4665)
• 05/22/2017 - approximately 2 gallons of low level radioactive water leaked onto the ground at north end of a tent located north of the WWTF. (Condition Report ES-ZION-CR-2017-0073)
• 05/10/2018 - Routine RP survey (2018-1480) conducted in WWTF indicated contact dose rates up to 88 mRem/hr on a HIC.
• 05/24/2018 - Survey unit area classification revised from Class 3 to Class 1 in LTP to reflect the use of WWTF as a radioactive material storage area.

No initial characterization was performed on the WWTF as the systems remained active throughout decommissioning up to the point of building demolition. Based on the building design basis and the operating history, the WWTF was given an initial classification of Class 3 in the HSA. However, during decommissioning, the facility was used as a radioactive material storage area for unpackaged radioactive wastes. Consequently, LTP, Revision 2 section 5.5.2.1 and Table 5-18 identifies the WWTF as a Class 1 structure requiring 100% areal coverage.

4. DATA QUALITY OBJECTIVES (DQO)

Final Status Survey planning and design hinges on coherence with the Data Quality Objective (DQO) process to ensure, through compliance with explicitly defined inputs and boundaries, that the primary objective of the survey is satisfied. The DQO process is [11]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 described in the ZSRP LTP in accordance with MARSSIM. The appropriate design for a given survey is developed using the DQO process as outlined in Appendix D of MARSSIM. The DQO process incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis. Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition. The baseline condition is technically known as the null hypothesis. Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection. In designing the survey plan, the underlying assumption, or null hypothesis was that residual activity in the survey unit exceeded the release criteria. Rejection of the null hypothesis would indicate that residual activity within the survey unit does not exceed the release criteria. Therefore, the survey unit would satisfy the primary objective of the FSS sample plan. The primary objective of the FSS sample plan was to demonstrate that the level of residual radioactivity in survey unit 09100 did not exceed the release criteria specified in the LTP and that the potential dose from residual radioactivity was As Low As Reasonably Achievable (ALARA). ZionSolutions TSD 11-001, Technical Support Document for Potential Radionuclides of Concern During the Decommissioning of the Zion Station (Reference 8) established the basis for an initial suite of potential ROC for the decommissioning of the ZNPS. LTP Chapter 2 provides detailed characterization data that described contamination levels in the Containments and Auxiliary Building, which were the primary source of radioactive contaminants. ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms (Reference 9) evaluates the results of the concrete core analysis data from the Containments and Auxiliary Building and refines the initial suite of potential ROC by evaluating the dose significance of each radionuclide. The final ROC for the decommissioning of Zion are Co-60, Cs-134 and Cs-137 (as well as Eu-152 and Eu-154 for Containment), which are gamma emitters, and Ni-63, Sr-90 and H-3 (applicable only to Containment), which are Hard-to-Detect (HTD) radionuclides. LTP section 5.1 states that HTD concentrations will be inferred using a surrogate approach and the maximum ratios from LTP Chapter 5, Table 5-15 unless area-specific ratios as determined by actual survey data are used in lieu of the maximum ratios. LTP Chapter 6, section 6.5.2 discusses the process used to derive the ROC for the decommissioning of the ZNPS, including the elimination of insignificant dose contributors from the initial suite consistent with the guidance in Section 3.3 of NUREG-1757. Based upon the analysis of the Auxiliary Building mixture in TSD 14-019, Table 19, it was determined that Co-60, Ni-63, Sr-90, Cs-134 and Cs-137 accounted for 99.5% of all dose [12]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 in the contaminated concrete mixes. Table 1 presents the ROC for the decommissioning of Auxiliary Building structural surfaces and the normalized mixture fractions based on the radionuclide mixture. Table 1 - Dose Significant Radionuclides and Mixture

                                                         % of Total Activity Radionuclide (normalized)(1)

Co-60 0.92% Ni-63 23.71% Sr-90 0.05% Cs-134 0.01% Cs-137 75.32% (1) Based on maximum percent of total activity from Table 20 of TSD 14-019, normalized to one for the dose significant radionuclides. A fundamental precursor to survey design is to establish a relationship between the release criteria and some measurable quantity. This is done through the development of DCGLs. The DCGLs represent average levels of radioactivity above background levels and are presented in terms of surface or mass activity concentrations. Chapter 6 of the LTP describes in detail the modeling used to develop the DCGLs for structures. The End State basements are comprised of steel and/or concrete structures which will be covered by at least three feet of clean soil and physically altered to a condition which would not realistically allow the remaining structures, if excavated, to be occupied. The exposure pathways in the Basement Fill Model (BFM) are associated with residual radioactivity in floors and walls that is 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. DCGLs are calculated separately for the GW and Drilling Spoils scenarios and for the summation of both scenarios. The summation DCGL [13]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 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/yr and are calculated for each ROC and each backfilled basement. Additional information pertaining to the calculation of DCGLs for basement surfaces is provided in LTP Chapter 6, section 6.6.8. 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 WWTF is provided in Table 2. The IC dose percentage of 10% was used to adjust the WWTF BcDCGLs to account for the dose from the eliminated IC radionuclides. Table 2 - Base Case DCGLs for WWTF (BcDCGLB) from LTP Chapter 5, Table 5-3 Base Case DCGL Radionuclide (pCi/m2) Co-60 2.83E+07 Ni-63 2.89E+08 Sr-90 1.03E+05 Cs-134 2.31E+06 Cs-137 2.93E+06 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/yr 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/yr 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. [14]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 The OpDCGLs for the unrestricted release of the WWTF survey unit 09100 are provided in Table 3. Table 3 - Operational DCGLs (OpDCGLB) for WWTF from LTP Chapter 5, Table 5-4 Operational DCGL Radionuclide (pCi/m2) Co-60 5.43E+06 Ni-63 5.55E+07 Sr-90 1.98E+04 Cs-134 4.44E+05 Cs-137 5.63E+05 Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the Operational DCGL. 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 use. Control and accountability of ISOCS units was required to assure data quality. As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. The actual recorded value was used as the recorded FSS result for measurement and/or sample values that are less than Minimal Detectable Concentration (MDC). Negative values were recorded as zero. For radionuclides less than MDC, the value representing the highest abundance was selected. Results were not reported as less than MDC. Sample report summaries included unique sample identification, analytical method, radionuclide, result, uncertainty, laboratory data qualifiers, units, and the observed MDC. In accordance with the LTP, for laboratory analysis, MDCs less than 10% of the OpDCGL were preferable while MDCs up to 50% of the OpDCGL were acceptable. The maximum acceptable MDC for measurements obtained using field instruments was 50% of the applicable OpDCGL.

5. SURVEY DESIGN Guidance for preparing FSS plans was provided in procedure ZS-LT-300-001-001 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 [15]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 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. These are provided in ZionSolutions TSD 14-022, Revision 2, Addendum 1, Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures (Reference 10). As per TSD 14-022, a contamination depth of 0.5 inches (1.27 cm) was suggested for the WWTF with all the activity associated within the one-half inch layer. For the floors and walls of the WWTF, the Geometry Composer Circular Plane Template was used. A source to detector distance of 3.0 meters was selected. While several geometries where created where the source to detector distance was varied from 1 to 3 meters, only the 3 meter distance was necessary. A 90-degree collimator was used resulting in a six-meter diameter FOV that comprised 28.3 m2. Measurements that were conducted using the 3-meter source to detector geometry were indicative of surficial contamination. There are three sumps located within the WWTF of varying dimensions. In addition, the Clarifier, Flocculator Tank and Sludge Holding Tank exhibited geometries that were not well represented by the 3-meter source to detector geometry. To this end, separate geometries were designed for each using the Geometry Composer Room template. This was done to address the anomalies and best represent the geometric dimensions. ISOCS geometries are provided in Attachment 2 of this report. In section 5.5.2.2 of the LTP, the number of ISOCS measurements required in the WWTF FSS survey unit was calculated as the quotient of the ISOCS FOV divided into the surface area required for areal coverage. Table 4, which is reproduced from LTP Table 5-18, presents the FSS survey unit for the WWTF, the classification based on contamination potential, the surface area to be surveyed and the minimum number of ISOCS measurements based on a measurement FOV of 28 m2. [16]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Table 4 - Number of ISOCS Measurements per FSS Unit based on Areal Coverage Minimum Minimum # of Area Areal ISOCS FSS Unit Classification Coverage Measurements (m2) (% of Area) (FOV-28 m2) WWTF Class 1 1,124 100% 40 To ensure that the number of ISOCS measurements, based on the necessary areal coverage in a basement surface FSS unit, was sufficient to satisfy a statistically based sample design, a calculation was performed and documented in LTP section 5.5.2.2 to determine sample size using the standard method as presented in MARSSIM. If the sample size based on the statistical design required more ISOCS measurements than the number of ISOCS measurement required by the areal coverage, then the number of ISOCS measurements was adjusted to meet the larger sample size. Following MARSSIM guidance, the Type I and Type II decision errors were set at 0.05. The Upper Bound of the Gray Region (UBGR) was set at the Operational DCGLB. The Lower Bound of the Gray Region (LBGR) was set at the expected fraction of 50% of the Operational DCGLB. A reasonable value for sigma () could not be determined based on existing survey data. Therefore, a coefficient of variation of 30% was used in accordance with the guidance in MARSSIM, section 5.5.2.2. The relative shift (/) was calculated as discussed in LTP section 5.6.4.1.6. The / was greater than three for the FSS unit. Consequently, a value of three (3) was used for the WWTF as the adjusted /. From Table 5-5 of MARSSIM, the required number of measurements (N) for use with the Sign Test, using a value of 0.05 for the Type I and Type II decision errors, is 14 measurements for a / value of three (3). As previously noted, the required areal coverage for a Class 1 basement survey unit is 100%. The LTP required that sufficient measurements be taken in a Class 1 FSS unit to ensure that 100% of the surface area was surveyed (ISOCS FOV overlapped to ensure that there were no un-surveyed corners and gaps). In cases where the physical configuration or measurement geometry made the acquisition of a 28 m2 FOV difficult or prohibitive, then the FOV for the ISOCS measurement was reduced provided that the adjusted number of samples remained constant and the minimum areal coverage represented by the FSS unit classification was achieved. To ensure that were no un-surveyed corners and gaps, the number of measurements that were taken in the WWTF Class 1 FSS unit was adjusted by overlaying the center-point of the 28 m2 FOV for the ISOCS measurement on a 4 m x 4 m (16 m2) grid system. Table 5, which is reproduced from LTP Table 5-19, presents the adjusted number of ISOCS measurements that will be taken in WWTF FSS survey unit. [17]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Table 5 - Adjusted Minimum Number of ISOCS Measurements per FSS Unit Required Adjusted # of Adjusted Adjusted Areal ISOCS Areal Areal FSS Unit Classification Coverage Measurements(1) Coverage Coverage (m2) (FOV-28 m2) (m2) (% of Area) WWTF Class 1 1,124 71(1) 1,124 100% (1) Adjusted to ensure number of measurements that will be taken in Class 1 FSS units will ensure 100% areal coverage, including overlap to ensure that there are no un-surveyed corners and gaps (FOV based on a 4 m x 4 m grid system). When the survey grids were established in the WWTF, obstacles and physical constraints were encountered that prompted further adjustments to the number of samples and the FOV. Some measurements were not feasible and other measurement locations were added. After adjustments to the survey design, a total of seventy-five (75) ISOCS measurements were taken in the WWTF. The DQO process determined that Co-60, Ni-63, Sr-90, Cs-134 and Cs-137 would be the ROC in the survey unit 09100. During FSS, concentrations for HTD ROC Ni-63 and Sr-90 were inferred using a surrogate approach. Cs-137 is the principle surrogate radionuclide for Sr-90, and Co-60 is the principle surrogate radionuclide for Ni-63. The mean, maximum and 95% Upper Confidence Level (UCL) of the surrogate ratios for concrete core samples taken for the WWTF was calculated in TSD 14-019 and are presented in LTP Table 5-15 and Table 6 below. The maximum ratios were used to infer HTD concentrations during FSS. Table 6 - Surrogate Ratios for Auxiliary Building 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 09100, the surrogate OpDCGLs for Co-60 and Cs-137 were computed based on the maximum ratios from Table 6. The equation for calculating a surrogate DCGL is as follows: Equation 1 1

                         =

1 2 3

                                                                     +           +            +

2 3 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate [18]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide Using the OpDCGLs for the WWTF presented in Table 3 and the maximum ratios from Table 6, the following surrogate calculations were performed for FSS unit 09100: Equation 2 1 (137) = = 5.33 + 05 /2 1 0.002

                                                                    +

5.63 + 05(137) 1.98 + 04(90) The surrogate OpDCGL that was used for Cs-137 in FSS unit 09100 for direct comparison of measurement results to demonstrate compliance is 5.33E+05 pCi/m2. Equation 3 1 (60) = = 2.91 + 05 /2 1 180.450

                                                                  +

5.43 + 06(60) 5.55 + 07(63) The surrogate OpDCGL that was used for Co-60 in FSS unit 09100 for direct comparison of measurement results to demonstrate compliance is 2.91E+05 pCi/m2. LTP section 5.1 discusses the commitment to acquire concrete core samples at 10% of the locations where an ISOCS measurement was collected with the locations selected at random. Only HTD radionuclides included as ROC (Ni-63, Sr-90, for the WWTF) were analyzed in the FSS confirmatory samples. For the survey unit 09100, seventy-one (71) ISOCS measurements were required by the survey design. Consequently, eight (8) concrete core samples were taken and analyzed to meet the requirements of LTP section 5.1. To demonstrate compliance with the unrestricted release criteria in FSS unit 09100, the Sign Test was selected as the non-parametric statistical test. The use of the Sign Test did not require the selection or use of a background reference area, which simplified survey design and implementation. This approach was conservative since it included background Cs-137 as part of the sample set. The Elevated Measurement Comparison (EMC) does not apply to this survey unit. At ZSRP, EMC only applies to soils as all other media (structural surfaces, embedded pipe, buried pipe and penetrations) will be remediated to their applicable BcDCGL. A Prospective Power Curve was generated using MARSSIM 2000, a software package developed for the implementation of MARSSIM in support of the decommissioning license termination rule (10CFR20, Subpart E). The result of the MARSSIM 2000 computer run showed adequate power for the survey design. [19]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 For this Class 1 basement structure survey unit, the Investigation Levels for ISOCS measurement results are those levels specified in LTP Chapter 5, Table 5-25 and are reproduced below in Table 7. Table 7 - Investigation Levels Classification Direct Measurement Class 1 >Operational DCGL Table 8 provides a synopsis of the survey designs for FSS unit 09100. Table 8 - Synopsis of Survey Design FEATURE DESIGN CRITERIA BASIS Survey Unit Surface Areas 1,124 m2 LTP Ch. 5, Table 5-19

• UBGR = SOF of 1
• LBGR = SOF of 0.01 Number of Measurements
• Type I error = 0.05 71(1)

(N)

• Type II error = 0.05

                                                                                         *   / = 3 (adjusted)

MARSSIM Table 5.5 100% Areal Coverage Grid Spacing LTP Chapter 5, Sec. 5.5.2.2 (Planned for 28 m2 FOV)

• Co 5.43E+06 pCi/m2
• Ni 5.55E+07 pCi/m2 Operational DCGLs for WWTF OpDCGLB
• Sr 1.98E+04 pCi/m2 (LTP Chapter 5, Table 5-4)
• Cs-134 - 4.44E+05 pCi/m2
• Cs-137 - 5.63E+05 pCi/m2 8 Concrete Core samples HTD ROC Analysis LTP Chapter 5, section 5.1 selected for HTD ROC analysis Investigation Level >Operational DCGL LTP Chapter 5, Table 5-25 1,124 m2 or ~100% areal Scan Survey Area Coverage LTP Chapter 5, Table 5-19 coverage 5 % Duplicate ISOCS QC LTP Chapter 5, Sec. 5.9.3.1 Measurements (1) The number of ISOCS measurements designated in the survey designs is greater than the minimum number required for this survey unit, per Chapter 5 of the LTP, Table 5-19. Seventy-one (71) measurements were required to achieve 100% coverage of the WWTF.

[20]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100

6. SURVEY IMPLEMENTATION For survey unit 09100, 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 WWTF. The concrete core data was used to validate the ratios of gamma emitters to HTD ROC.

Remediation was completed on August 14, 2018. The area was cleaned and turned over for FSS. A walk-down and turnover survey was satisfactorily performed in the FSS unit in accordance with the Isolation and Control requirements of procedure ZS-LT-300-001-003, Isolation and Control for Final Status Survey (Reference 11). The turnover surveys consisted of surveys for loose surface contamination. All smear results were less than 1,000 dpm/100 cm2. The WWTF was deemed acceptable for turnover and FSS commenced August 14, 2018. There are several system pipes and penetrations embedded in the concrete basement of the WWTF that must be removed to achieve the desired end state of the survey unit. While undergoing decommissioning, it was determined that if the pipe and penetrations were removed, the WWTF basement would be susceptible to groundwater intrusion that could not be mitigated or controlled. Therefore, it was decided to forgo removal of the aforementioned piping/penetrations until the FSS of the WWTF structural concrete was complete. Once compliance was demonstrated, the pipe/penetrations were removed in a controlled manner. Surveillances performed on FSS surfaces following pipe/penetration removal demonstrated that there was no cross-contamination during the removal process. 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 for 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. The number and locations of the ISOCS shots were adjusted to ensure 100% coverage of the surfaces of the WWTF. Complete information pertaining to the ISOCS geometries used for the FSS of the WWTF basement is provided in Attachment 2 of the report. The ISOCS detector was positioned horizontal or vertical 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 3 meters from the surface with the 90-degree collimation shield installed; this orientation corresponded to a nominal FOV of 28 m2. The detector to [21]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 source distance was reduced even further to accommodate physical constraints or encountered obstructions. In this case, the FOV was reduced and 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. A SOF calculation was performed for each measurement by dividing the reported concentration of each ROC by the OpDCGL for each ROC to derive an individual ROC fraction (OpSOF). The individual OpSOF were then summed to provide a total OpSOF value for the measurement. On August 16, 2018, it was observed that during preparations for FSS, the demolition contractor had removed 1.5 feet to 2.5 feet high portions of the north wall resulting in the elimination of five (5) survey locations (#s 46-50). Additionally, location 45 was changed to address one-half of Sump #2 in conjunction with location 68. Additional ISOCS measurements were collected on walls (#s 64-66), in sumps (#s 67-69), and in clarifier/flocculants (#s 71-75) to ensure 100% areal coverage. The addition and subtraction of these measurement locations resulted in seventy (70) systematic ISOCS measurements. FSS of the WWTF was completed on August 22, 2018. Graphics in Attachment 1 identify ISOCS measurement locations and core sample locations in the WWTF. Four (4) replicate measurements were taken with the ISOCS in the WWTF at locations 9, 14, 27 and 53. 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 non-parametric statistical testing be selected for additional QC evaluation.

7. SURVEY RESULTS The SOF or unity rule is applied to the data used for the survey planning, data evaluation and statistical tests for basement surfaces since multiple radionuclide-specific measurements will be performed or the concentrations inferred based on known relationships. The application of the unity rule serves to normalize the data to allow for an accurate comparison of the various data measurements to the release criteria. When the unity rule is 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. [22]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 As described in LTP Chapter 5, section 5.10.3.2, the Sign Test was used to evaluate the measured residual radioactivity against the dose criterion. The OpSOF for each measurement was used as the sum value for the Sign Test. The Sign Test then demonstrated that the mean activity for each ROC was less than the OpDCGLB at a Type I decision error of 0.05. 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. The OpSOF for a systematic or a judgmental measurement/sample(s) could exceed one without remediation as long as the survey unit passed the Sign Test and, the mean OpSOF for the survey unit did not exceed one. Once the survey data set passed the Sign Test (using OpDCGLs), then the mean radionuclide activity (pCi/m2) for each ROC from systematic measurements along with any identified elevated areas from systematic and judgmental samples was used with the BcDCGLs to perform a mean BcSOFB calculation. The dose from residual radioactivity assigned to the FSS unit is the mean BcSOFB multiplied by 25 mrem/yr. The measurement population consisted of seventy (70) systematic and four (4) quality control locations using the ISOCS. A summary of the results of the seventy (70) ISOCS measurements taken for non-parametric statistical testing results are provided in Table 9. The concentrations for Ni-63 and Sr-90 were inferred based on the maximum ratios as specified in LTP Chapter 5, Table 5-15. The complete ISOCS gamma spectroscopy reports are presented in Attachment 6. The basic statistics for the systematic measurements are summarized in Table 10. [23]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Table 9 - Waste Water Treatment Facility - Measured Concentrations of ROC for FSS Co-60 (1) Ni-63 (2) Sr-90 (2) Cs-134 Cs-137 (1) Measurement ID OpSOF (3) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B1-09100AF-SFC-001-GD 3.74E+03 6.75E+05 3.04E+01 0.00E+00 1.52E+04 0.041 B1-09100AF-SFC-002-GD 8.66E+03 1.56E+06 2.92E+01 3.14E+03 1.46E+04 0.064 B1-09100AF-SFC-003-GD 0.00E+00 0.00E+00 4.64E+00 1.22E+03 2.32E+03 0.007 B1-09100AF-SFC-004-GD 3.27E+03 5.90E+05 2.22E+01 1.52E+04 1.11E+04 0.066 B1-09100AF-SFC-005-GD 8.16E+03 1.47E+06 4.00E+01 0.00E+00 2.00E+04 0.066 B1-09100AF-SFC-006-GD 1.42E+02 2.56E+04 6.86E+01 2.42E+03 3.43E+04 0.070 B1-09100AF-SFC-007-GD 0.00E+00 0.00E+00 3.70E+01 1.33E+04 1.5E+04 0.065 B1-09100AF-SFC-008-GD 9.46E+03 1.71E+06 2.14E+01 1.20E+04 1.07E+04 0.080 B1-09100AF-SFC-009-GD 1.22E+04 2.20E+06 6.30E+00 0.00E+00 3.15E+03 0.048 B1-09100AF-SFC-010-GD 0.00E+00 0.00E+00 0.00E+00 4.15E+03 0.00E+00 0.009 B1-09100AF-SFC-011GD 6.65E+03 1.20E+06 4.04E+01 0.00E+00 2.02E+04 0.061 B1-09100AF-SFC-012-GD 1.83E+03 3.30E+05 4.12E+01 7.52E+03 2.06E+04 0.062 B1-09100AF-SFC-013-GD 4.99E+04 9.00E+06 3.22E+01 1.53E+04 1.61E+04 0.236 B1-09100AF-SFC-014-GD 4.03E+03 7.27E+05 5.14E+01 1.63E+04 2.57E+04 0.099 B1-09100AF-SFC-015-GD 6.59E+03 1.19E+06 1.89E+01 2.37E+04 9.47E+03 0.094` B1-09100AF-SFC-016-GD 7.57E+03 1.37E+06 1.05E+01 1.03E+04 5.25E+03 0.059 B1-09100AF-SFC-017-GD 2.95E+03 5.32E+05 0.00E+00 1.96E+04 0.00E+00 0.054 B1-09100AF-SFC-018-GD 9.74E+03 1.76E+06 1.96E+01 1.24E+03 9.80E+03 0.055 B1-09100AF-SFC-019-GD 1.60E+04 2.89E+06 3.04E+01 1.35E+04 1.52E+04 0.114 B1-09100AF-SFC-020-GD 1.34E+04 2.42E+06 3.10E+01 3.01E+04 1.55E+04 0.143 B1-09100AF-SFC-021-GD 1.08E+04 1.95E+06 2.22E+01 2.51E+04 1.11E+04 0.115 B1-09100AF-SFC-022-GD 6.81E+03 1.23E+06 0.00E+00 2.63E+04 0.00E+00 0.083 B1-09100AF-SFC-023-GD 1.50E+04 2.71E+06 2.72E+01 0.00E+00 1.36E+04 0.077 B1-09100AF-SFC-024-GD 0.00E+00 0.00E+00 9.94E+00 2.39E+04 4.97E+03 0.063 B1-09100AF-SFC-025-GD 0.00E+00 0.00E+00 5.14E+01 0.00E+00 2.57E+04 0.048 B1-09100AF-SFC-026-GD 5.07E+02 9.14E+04 3.62E+01 0.00E+00 1.81E+04 0.036 B1-09100AF-SFC-027-GD 3.96E+03 7.15E+05 5.14E+01 5.46E+03 2.57E+04 0.074 B1-09100AF-SFC-028-GD 0.00E+00 0.00E+00 3.18E+01 3.20E+04 1.59E+04 0.102 B1-09100AF-SWC-029-GD 7.57E+03 1.36E+06 1.58E+01 3.72E+03 7.91E+03 0.049 B1-09100AF-SWC-030-GD 1.66E+04 3.00E+06 1.88E+01 2.11E+04 9.41E+03 0.122 B1-09100AF-SWC-031-GD 6.02E+03 1.09E+06 0.00E+00 2.33E+04 0.00E+00 0.073 B1-09100AF-SWC-032-GD 5.40E+03 9.74E+05 1.45E+01 1.59E+04 7.25E+03 0.068 [24]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Table 9 (continued) - Waste Water Treatment Facility - Measured Concentrations of ROC for FSS Co-60 (1) Ni-63 (2) Sr-90 (2) Cs-134 Cs-137 (1) Measurement ID OpSOF (3) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B1-09100AF-SWC-033-GD 1.25E+04 2.26E+06 5.48E+01 6.6+03 2.74E+04 0.109 B1-09100AF-SWC-034-GD 9.80E+03 1.77E+06 2.92E+01 0.00E+00 1.46E+04 0.061 B1-09100AF-SWC-035-GD 0.00E+00 0.00E+00 2.42E+01 7.44E+03 1.21E+04 0.040 B1-09100AF-SWC-036-GD 1.83E+04 3.30E+06 0.00E+00 5.98E+03 0.00E+00 0.076 B1-09100AF-SWC-037-GD 4.06E+04 7.33E+06 1.28E+01 0.00E+00 6.39E+03 0.1558 B1-09100AF-SWC-038-GD 8.42E+03 1.52E+06 2.22E+01 1.30E+04 1.11E+04 0.079 B1-09100AF-SWC-039-GD 4.01E+03 7.24E+05 3.04E+01 2.61E+03 1.52E+04 0.048 B1-09100AF-SWC-040-GD 9.47E+02 1.71E+05 4.00E+01 1.91E+04 2.00E+04 0.084 B1-09100AF-SWC-041-GD 1.42E+04 2.56E+06 0.00E+00 3.82E+04 0.00E+00 0.135 B1-09100AF-SWC-042-GD 2.51E+03 4.53E+05 0.00E+00 3.70E+04 0.00E+00 0.092 B1-09100AF-SWC-043-GD 5.76E+03 1.04E+06 0.00E+00 2.10E+04 0.00E+00 0.067 B1-09100AF-SWC-044-GD 0.00E+00 0.00E+00 5.82E+01 2.00E+04 2.91E+04 0.100 B1-09100AF-SFC-045-GD 3.75E+03 6.77E+05 2.60E+01 1.78E+04 1.30E+04 0.077 B1-09100AF-SWC-051-GD 4.43E+03 7.99E+05 3.04E+01 3.14E+04 1.52E+04 0.115 B1-09100AF-SWC-052-GD 7.03E+03 1.27E+06 3.34E+01 3.91E+03 1.67E+04 0.064 B1-09100AF-SWC-053-GD 4.35E+02 7.85E+04 1.32E+01 4.04E+03 6.59E+03 0.023 B1-09100AF-SWC-054-GD 5.13E+03 9.26E+05 3.62E+01 1.15E+04 1.81E+04 0.078 B1-09100AF-SWC-055-GD 2.38E+04 4.29E+06 1.94E+01 0.00E+00 9.72E+03 0.100 B1-09100AF-SWC-056-GD 6.57E+03 1.19E+06 0.00E+00 0.00E+00 0.00E+00 0.023 B1-09100AF-SWC-057-GD 6.86E+03 1.24E+06 0.00E+00 6.28E+03 0.00E+00 0.038 B1-09100AF-SWC-058-GD 1.11E+04 2.00E+06 2.24E+01 1.82E+04 1.12E+04 0.100 B1-09100AF-SWC-059-GD 6.31E+03 1.14E+06 2.48E+01 2.69E+04 1.24E+04 0.106 B1-09100AF-SWC-060-GD 0.00E+00 0.00E+00 0.00E+00 1.85E+04 0.00E+00 0.042 B1-09100AF-SWC-061-GD 0.00E+00 0.00E+00 4.58E+01 0.00E+00 2.29E+04 0.043 B1-09100AF-SWC-062-GD 1.19E+04 2.15E+06 2.84E+01 1.77E+04 1.42E+04 0.107 B1-09100AF-SWC-063-GD 0.00E+00 0.00E+00 2.74E+01 1.28E+04 1.37E+04 0.055 [25]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Table 9 (continued) - Waste Water Treatment Facility - Measured Concentrations of ROC for FSS Co-60 (1) Ni-63 (2) Sr-90 (2) Cs-134 Cs-137 (1) Measurement ID 2 2 2 2 OpSOF (3) (pCi/m ) (pCi/m ) (pCi/m ) (pCi/m ) (pCi/m2) B1-09100AF-SWC-064-GD 1.71E+03 3.09E+05 2.84E+00 1.63E+04 1.42E+03 0.045 B1-09100AF-SWC-065-GD 5.76E+03 1.04E+06 3.28E+01 0.00E+00 1.64E+04 0.051 B1-09100AF-SWC-066-GD 8.34E+03 1.50E+06 2.96E+01 0.00E+00 1.48E+04 0.056 B1-09100AF-SFC-067-GD 5.67E+03 1.02E+06 1.87E+01 9.78E+02 9.35E+03 0.039 B1-09100AF-SFC-068-GD 2.97E+03 5.36E+05 2.30E+01 5.55E+02 1.15E+04 0.033 B1-09100AF-SFC-069-GD 4.86E+03 8.77E+05 7.78E+00 3.88E+03 3.89E+03 0.033 B1-09100AF-SFC-070-GD 5.30E+03 9.56E+05 7.40E+00 0.00E+00 3.70E+03 0.025 B1-09100AF-SFC-071-GD 5.38E+03 9.71E+05 0.00E+00 2.13E+03 0.00E+00 0.023 B1-09100AF-SFC-072-GD 6.07E+03 1.10E+06 2.46E+01 2.52E+04 1.23E+04 0.100 B1-09100AF-SFC-073-GD 0.00E+00 0.00E+00 1.62E+01 0.00E+00 8.08E+03 0.015 B1-09100AF-SFC-074-GD 1.39E+03 2.51E+05 9.46E+00 1.31E+03 4.73E+03 0.017 B1-09100AF-SFC-075-GD 5.55E+03 1.00E+06 8.36E+00 2.75E+03 4.18E+03 0.033 Note (1) The surrogate OpDCGL for Cs-137 (inferring Sr-90 at the maximum ratios from LTP Table 5-15) equaled 5.33E+05 pCi/m2 (Equation 2) and the surrogate OpDCGL for Co-60 (inferring Ni-63 at the maximum ratio from LTP Table 5-15) equaled 2.91E+05 pCi/m2 (Equation 3). No ISOCS measurement result for Cs-137 or Co-60 exceeded its respective surrogate OpDCGL value. Note (2) Inferred concentrations Note (3) Compared against OpDCGL [26]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Table 10 - Waste Water Treatment Facility - Statistical Quantities - Systematic Measurement Population Individual Measurement Metrics Total Number of Systematic Measurements = 70 Number of Quality Control Measurements = 4 Number of Judgmental/Investigational Measurements = 0 Total Number of Measurements = 74 Mean Systematic Measurement SOF = 0.013 Max Individual Systematic Measurement SOF = 0.236 Number of Systematic Measurements with SOF >1 = 0 Statistical Quantities - Systematic Measurement Population MEAN MEDIAN MAX MIN STD. DEV. BcDCGL Avg Dose per ROC BcSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) ROC Co-60 7.06E+03 5.61E+03 4.99E+04 0.00E+00 8.38E+03 2.83E+07 0.000 0.006 Ni-63 1.27E+06 1.01E+06 9.00E+06 0.00E+00 1.51E+06 2.89E+08 0.004 0.110 Sr-90 2.25E+01 2.23E+01 6.86E+01 0.00E+00 1.65E+01 1.03E+05 0.000 0.005 Cs-134 1.08E+04 7.02E+03 3.82E+04 0.00E+00 1.07E+04 2.31E+06 0.005 0.117 Cs-137 1.12E+04 1.12E+04 3.43E+04 0.00E+00 8.27E+03 2.93E+06 0.004 0.096 MEAN BcSOF ASSIGNED TO SURVEY UNIT (SYSTEMATIC AVG.) = 0.013 DOSE ASSIGNED TO SURVEY UNIT (SYSTEMATIC AVG.) = 0.335 mrem/yr. The analytical results (converted to OpSOF) for all of the measurements taken in the WWTF were less than a SOF of one. [27]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 A six (6) inch concrete core sample was acquired at the eight (8) concrete core locations that were selected at random. Each core was cut into 1/2-inch pucks. The pucks represented the as left condition of the WWTF concrete to a depth of 1/2 inch at the eight (8) selected locations (see Figure 2) which were sent to Eberline Laboratories for analysis results for Sr-90, Ni-63 and gamma spectroscopy. The analysis results for the eight (8) concrete core pucks taken were received from Eberline on September 3, 2018, and the results are presented in Table 11. Each sample or 1/2-inch puck represents the concrete from the existing surface to a depth of 1/2-inch. Each of the first 1/2-inch concrete puck from each of the eight (8) concrete core samples were analyzed for all ROC, including the HTD ROC of Ni-63 and Sr-90. Cs-137 was the only ROC positively detected at concentrations greater than MDC. The maximum concentration observed was 3.81E-01 pCi/g. In accordance with LTP section 5.1, only samples with positive results (detectable concentrations greater than MDC) were assessed for HTD ratios. [28]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Table 11 - WWTF FSS Concrete Core Sample Analysis - Surface to 0.5 inch Depth Sample ID Nuclide Result Uncertainty MDA >MDC Ratios (pCi/g) (pCi/g) (pCi/g) B1-09100AF-SFC-067-CV Co-60 -3.21E-02 1.41E-01 1.81E-01 N Ni-63 6.81E-01 1.77E+00 3.02E+00 N Ni-63/Co-60 = N/A Sr-90 -6.05E-02 3.91E-01 7.09E-01 N (Ni-63/Co-60 not positively detected) Cs-134 3.78E-02 6.95E-02 1.72E-01 N Sr-90/Cs-137 = N/A Cs-137 -8.69E-02 1.68E-01 2.33E-01 N (Sr-90/Cs-137 not positively detected) B1-09100AF-SWC-031-CV Co-60 -8.91E-02 1.48E-01 1.99E-01 N Ni-63 8.74E-01 1.66E+00 2.82E+00 N Ni-63/Co-60 = N/A Sr-90 3.99E-01 4.00E-01 6.67E-01 N (Ni-63/Co-60 not positively detected) Cs-134 7.5E-03 6.34E-02 1.49E-01 N Sr-90/Cs-137 = N/A Cs-137 1.76E-01 1.84E-01 3.04E-01 Y (Sr-90 not positively detected) B1-09100AF-SFC-001-CV Co-60 6.88E-02 1.44E-01 2.69E-01 N Ni-63 6.03E-01 1.79E+00 3.06E+00 N Ni-63/Co-60 = N/A Sr-90 0.00+00 4.65E-01 8.29E-01 N (Ni-63/Co-60 not positively detected) Cs-134 -1.32E-02 1.06E-01 2.53E-01 N Sr-90/Cs-137 = N/A Cs-137 4.75E-01 2.54E-01 3.81E-01 Y (Sr-90 not positively detected) B1-09100AF-SFC-010-CV Co-60 2.45E-02 1.17E-01 1.96E-01 N Ni-63 1.55E+00 1.82E+00 3.06E+00 N Ni-63/Co-60 = N/A Sr-90 -1.49E-01 3.97E-01 7.36E-01 N (Ni-63/Co-60 not positively detected) Cs-134 3.09E-02 6.51E-02 1.32E-01 N Sr-90/Cs-137 = N/A Cs-137 1.50E-01 1.26E-01 2.01E-01 N (Cs-137/Sr-90 not positively detected) B1-09100AF-SWC-041-CV Co-60 8.14E-02 1.30E-01 1.71E-01 N Ni-63 1.74E+00 1.84E+00 3.08E+00 N Ni-63/Co-60 = N/A Sr-90 2.69E-01 4.53E-01 7.80E-01 N (Ni-63/Co-60 not positively detected) Cs-134 -6.54E-01 2.78E-01 2.01E-01 N Sr-90/Cs-137 = N/A Cs-137 -2.85E-03 1.44E-01 2.24E-01 N (Cs-137/Sr-90 not positively detected) [29]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Table 11 (continued) - WWTF FSS Concrete Core Sample Analysis - Surface to 0.5 inch Depth Sample ID Nuclide Result Uncertainty MDA >MDC Ratios (pCi/g) (pCi/g) (pCi/g) B1-09100F-SFC-068-CV Co-60 -1.34E-02 5.26E-02 1.39E-01 N Ni-63 1.41E+00 1.50E+00 2.51E+00 N Ni-63/Co-60 = N/A Sr-90 2.04E-01 3.38E-01 5.81E-01 N (Ni-63/Co-60 not positively detected) Cs-134 -3.89E-03 6.28E-02 2.06E-01 N Sr-90/Cs-137 = N/A Cs-137 3.66E-01 1.88E-01 2.69E-01 Y (Sr-90 not positively detected) B1-09100F-SWC-051-CV Co-60 -2.76E-02 1.58E-01 2.36E-01 N Ni-63 1.27E+00 1.79E+00 3.01E+00 N Ni-63/Co-60 = N/A Sr-90 2.08E-01 4.14E-01 7.19E-01 N (Ni-63 not positively detected) Cs-134 -1.55E-02 5.30E-02 2.36E-01 N Sr-90/Cs-137 = N/A Cs-137 4.90E-01 1.72E-01 2.88E-01 Y (Sr-90 not positively detected) B1-09100F-SFC-021-CV Co-60 9.18E-02 1.58E-01 2.22E-01 N Ni-63 1.90E+00 1.45E+00 2.41E+00 N Ni-63/Co-60 = N/A Sr-90 4.70E-01 4.35E-01 7.22E-01 N (Ni-63/Co-60 not positively detected) Cs-134 5.65E-02 8.51E-02 2.18E-01 N Sr-90/Cs-137 = N/A Cs-137 4.31E-01 1.87E-01 3.37E-01 Y (Sr-90 not positively detected) [30]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100

8. QUALITY CONTROL The implementation of required QC measures included the collection of four (4) additional ISOCS measurements in the WWTF for replicate measurement analysis. The complete ISOCS gamma spectroscopy reports for the replicate measurements are presented in Attachment 6. All replicate ISOCS measurements met the required acceptance criteria. The completed Replicate Sample Assessment Forms are included in Attachment 4 of this Release Record.

Two ISOCS detectors were utilized for performing FSS measurements of the WWTF: detectors 6279 and 5452. There were no QC discontinuities associated with detector 6279. However, due to inclement weather, detector 5452 did exhibit some resolution anomalies likely due to noise associated with vibrations, humidity and wet conditions (rain followed by inversions). These conditions existed principally on the low end of the spectrum (40-200 keV) resulting in the 86.5 keV Eu-155 energy peak QC data point appearing several keV lower in the spectrum (83.8 keV) while the 1274.5 keV Eu-155 peak was within tolerance. This was evident on the morning source check (8/15/18 at 10:16 AM) with peak energy of 83.76 keV. The Full Width-Half Maximum (FWHM) was acceptable and other principle peaks during operation were found acceptable based on peak location, energy and FWHM values. Identification of the cause (humidity and vibration noise) as well as identification of principle peaks during operation (Cs-137) allowed for the continued operation of the system with the lower energy (86.5 keV Eu-155) out of tolerance. As the weather improved and the inversion lifted, the system noise became less and the Post QC was within tolerance. The collected data was deemed acceptable following inspection of all the spectrums collected. On 8/17/18 the same conditions occurred during the afternoon Post QC check with the exception that there was no inversion. The conditions were primarily caused by humidity and noise induced by vibration and equipment electrical operated hydraulic motors nearby. The 86.5 keV Eu-155 peak was out of tolerance (83.8 keV). This is approximately 9 channels from the energy peak and about 3 channels out of the tolerance (~0.75 keV) bounds. Examination of the data indicated the principle peaks of interest were well within tolerance based on peak location, energy and FWHM values. The collected spectrum data after examination was found acceptable. It is important to note that the QC checks are intended as markers for additional evaluation of the spectrum, as necessary. Careful inspection of the collected data was conducted and the results determined to be acceptable based on both the examination of [31]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 the individual spectrums, the location of the principle peaks and the identified peaks and tolerances invoked by the Genie2000 software.

9. INVESTIGATIONS AND RESULTS No investigations were conducted in the WWTF.

10. REMEDIATION AND RESULTS Remediation was required prior to performance of FSS. In the case of the WWTF, remediation primarily consisted of system removal and the removal of internal structural surfaces above and below the 588 foot elevation. Following remediation, FSS was conducted successfully and met all acceptance criteria for release of the survey unit.

Chapter 4 of the ZSRP LTP states that remediation beyond that required to meet the release criteria is unnecessary and that the remaining residual radioactivity in structures was ALARA.

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN In accordance with the LTP, compliance with the unrestricted release criteria is demonstrated though a series of static measurements taken with an ISOCS. LTP section 5.5.2.2, Table 5-19 lists the WWTF as a Class 1 basement structure survey unit with a total surface area of 1,124 m2. The FSS design specified to demonstrate compliance required a minimum of seventy-one (71) static ISOCS measurements. However, only seventy (70) measurements were collected due to an interior wall being removed during demolition which resulted in the elimination of five (5) sample locations as well as the addition of four (4) measurements due to a decreased FOV. 100% areal coverage of the WWTF surfaces was maintained.

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 constraints on 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 units.

12. DATA QUALITY ASSESSMENT (DQA)

The DQO sample design and data were reviewed in accordance with ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment (Reference 12) for completeness and consistency. Documentation was complete and legible. Surveys and the collection of measurements were consistent with the DQOs and were sufficient to [32]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 ensure that the survey unit was properly designated as Class 1. The survey design had adequate power as indicated by the Retrospective Power Curve (see Attachment 5). The analytical results of all ISOCS measurements were less than an OpSOF of one. Although MARSSIM states that the Sign Test need not be performed in the instance that no measurements surpass the DCGL, the test was conducted to demonstrate coherence to the statistical principles of the DQO process. The Sign Test (Attachment 3) was performed on the data and compared to the original assumptions of the DQOs. The evaluation of the Sign Test results clearly demonstrates that the survey unit passes the unrestricted release criteria, thus, the null hypothesis is rejected. The preliminary data review consisted of calculating basic statistical quantities (e.g., mean, median, standard deviation). All data was considered valid including negative values, zeros, values reported below the MDC, and values with uncertainties that exceeded two standard deviations. The mean and median values for each ROC were well below the respective OpDCGLs. Also, the retrospective power curve shows that a sufficient number of samples were collected to achieve the desired power. Therefore, the survey unit meets the unrestricted release criteria with adequate power as required by the DQOs. The data for Co-60 and Cs-137 is represented graphically through a frequency plot and a quantile plot. All graphical representations are provided in Attachment 5.

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

14. COMPLIANCE EQUATION There are four distinct source terms for the end-state at Zion: backfilled basements, soil, buried piping and groundwater. Demonstrating compliance with the dose criterion requires the summation of dose from the four source terms (see Equation 6-11 from LTP Chapter 6, section 6-17).

The final compliance dose will be calculated using LTP Equation 6-11 after FSS has been completed in all survey units. The results of the FSS performed for each FSS unit will be reviewed to determine the maximum dose from each of the four source terms (e.g., basement, soil, buried pipe and existing groundwater if applicable) using the mean Base Case SOF of FSS systematic results plus the dose from any identified elevated areas. The compliance dose must be less than 25 mrem/yr. The dose contribution from each ROC is accounted for using the Base Case SOF (BcSOF) to ensure that the total dose from all ROC does not exceed the dose criterion. [33]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 The term for each basement includes the dose contributions from wall and floor surfaces within the basement, the dose contribution from embedded pipe within the Basement, the dose contribution from penetrations within the basement and the dose contribution from concrete fill in the basement when clean concrete debris was used as fill. Each (structural surfaces, embedded pipe and penetrations) are surveyed separately during FSS. The dose from clean concrete fill is predetermined in accordance with LTP Chapter 5, Table 5-16, which is conservatively based on a maximum allowable MDC of 5,000 dpm/100cm2. The dose from fill assigned to the WWTF is 6.400 mrem/yr, which equates to a SOF of 0.256. The BcDCGL for the WWTF accounts for the activity in the structural surface. In accordance with LTP Chapter 6, Table 6-23, no additional adjustments need to occur to the WWTF mean BcSOF to account for the contribution of residual radioactivity from basements/structures that cannot, on their own, support a water supply well but were hydraulically connected to the WWTF. The mean BcSOF for the WWTF is 0.013, which equates to a dose 0.335 mrem/yr. The mean BcSOF was then used in the following equation to calculate BcSOFBASEMENT for the WWTF. Equation 4

              =  +  +  +

where: BcSOFBASEMENT = BcSOF (mean of FSS systematic results plus the dose from any identified elevated areas) for backfilled basements BcSOFB = BcSOF for structural survey unit(s) within the basement (mean of FSS systematic results plus the dose from any identified elevated areas) BcSOFEP = BcSOF for embedded pipe survey unit(s) within the basement (mean of FSS systematic results plus the dose from any identified elevated areas) BcSOFPN = BcSOF for penetration survey unit(s) within the basement (mean of FSS systematic results plus the dose from any identified elevated areas) BcSOFCF = BcSOF for clean concrete fill (if applicable) based on maximum MDC during Unrestricted Release Survey (URS) There are no penetrations or embedded pipe associated with the WWTF basement. Consequently, the dose contribution from both (variables BcSOFEP and BcSOFPN) are zero. [34]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 The BcSOFBASEMENT value for the WWTF is then derived as follows: Equation 5

              = 0.013 + 0.000 + 0.000 + 0.256 = 0.269 The BcSOFBASEMENT for the WWTF basement is 0.269. This SOF equates to a dose of 6.735 mrem/yr TEDE to an AMCG from residual radioactivity in the WWTF basement.

15. CONCLUSION Survey unit 09100 has met the DQOs of the FSS plan. The ALARA criteria as specified in Chapter 4 of the LTP were achieved. The EMC is not applicable to structural surfaces and remediation was successfully implemented.

All identified ROC were used for statistical testing to determine the adequacy of the survey unit for FSS. Evaluation of the data shows that none of the ROC concentration values exceed the OpDCGL or any investigational levels; therefore, in accordance with the LTP Section 5.10, the survey unit meets the release criterion. The sample data passed the Sign Test. The null hypothesis was rejected. The Retrospective Power Curve showed that adequate power was achieved. The survey unit is properly classified as Class 1. The dose contribution from structural surfaces in survey unit 09100, WWTF Basement, is 0.335 mrem/yr TEDE, based on the average concentration of the ROC in samples used for non-parametric statistical sampling. The dose from embedded pipe and penetrations in the WWTF is zero and the dose from clean fill is 6.400 mrem/yr. The total dose attributed to the WWTF as a summation of all dose components is 6.735 mrem/yr. Survey unit 09100, Waste Water Treatment Facility is acceptable for unrestricted release.

16. 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 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey

[35]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100

6. ZionSolutions Technical Support Document 14-014, End State Surface Areas, Volumes, and Source Terms of Ancillary Buildings

7. Zion Station Historical Site Assessment

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

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

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

11. ZionSolutions procedure ZS-LT-300-001-003, Isolation and Control for Final Status Survey

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

17. ATTACHMENTS Attachment 1 - Additional Figures and Maps Attachment 2 - ISOCS Geometry Attachment 3 - Sign Test Attachment 4 - QC Measurement Assessments Attachment 5 - Graphical Presentations Attachment 6 - ISOCS Analytical Report Attachment 7 - Eberline Reports

[36]

ATTACHMENT 1 ADDITIONAL FIGURES AND MAPS [37]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Figure 1 - Waste Water Treatment Facility Top View from Drawing B-1024 [38]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Figure 2 - Waste Water Treatment Facility ISOCS Measurement & Core Locations [39]

ATTACHMENT 2 ISOCS Geometry [40]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Geometries As per TSD 14-022 Revision 1, a contamination depth of 0.5 inches (1.27 cm) was suggested for the WWTF with all the activity associated within the one-half inch layer. For the floors and walls of the WWTF, the Geometry Composer Circular Plane Template was used for the geometry. A source to detector distance of 3.0 meters was selected. While several geometries were created where the source to detector distance was varied from 1 to 3 meters, only the 3 meter distance was necessary. A 90-degree collimator was used resulting in a six meter diameter field of view (FOV) that comprised 28.3 m2. Measurements that were conducted using the 3 meter source to detector geometry were indicative of minimal surficial contamination. There are several (3) sumps located at the WWTF of varying dimensions. In addition, the Clarifier, Flocculator Tank and Sludge Holding Tank exhibited geometries that were not well represented by the 3 meter source to detector geometry. To this end, separate geometries were designed for each of these using the Geometry Composer Room template to address the anomalies and best represent the geometric dimensions. The Room geometry assumes surface contamination. Sump 1 (Location 67) Sump 1 is located in the NE corner of the WWTF Filter Area. It is 36.25 inches wide, 60 inches long and 55.25 inches deep resulting in an area of 8.26 m2. The Room Geometry utilizes a 180 degree FOV (collimator removed) and the measurement location is at the top center of the room. That is at the lip of the sump (floor surrounding the sump). Residual contamination was assumed to comprise 10 percent of each wall and 60 percent of the floor. Sump 2 (Location 68) Sump 2 is located central and slightly south of the A wall in the Equalization Tank room. It is 120 inches wide, 48 inches long and 24 inches deep. Due to the length of the sump, it is divided into two Room Geometry measurement locations 60 inches by 48 inches by 24 inches deep. Each location results in an area of 4.27 m2. The measurement location utilizes a 180 degree FOV is at the lip of the sump (floor surrounding the sump) at the top center of the room. Residual contamination was assumed to comprise 10 percent of each wall and 60 percent of the floor. Sump 3 (Locations 74, 75 and 69) Sump 3 is the Sludge Holding Tank Area located on the NE end of the WWTF. This Room Geometry is divided into two measurement locations 58 inches wide, 90 inches long and 53 inches deep. While the south, north and west wall slopes to the sump region (location 69), the geometry was treated as a square box resulting in conservative values for the three walls. The East wall is perpendicular. There is no real sump at the bottom, only a region the inclined walls slope towards. Each location results in a total area of 10.41 m2. The bottom was assumed square [41]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 resulting in a slightly non-conservative area estimate that is offset by the assumption of a box design whereas three of the side walls are sloping and the source to detector distance is less than the values used. A third measurement that was not required was acquired over the sump using the same geometry. In all cases, the geometry included the 180 degree FOV (collimator removed) and was centered over each 58 by 90 inch region. The sump 3 measurement (location 69) was centered over the sump. As before, the measurement location is at the lip of the Sludge Holding Tank (top elevation floor). Residual contamination was assumed to comprise 10 percent of each wall and 60 percent of the floor. Flocculator Tank Sump (Locations 72 and 73) The Flocculator Tank had been two separate compartments but during renovation, the central wall was removed as was the north wall. The Flocculator Tank was divided into two regions 76 inches wide, 103.5 inches long and 56 inches deep. Location 72 resulted in just two walls remaining. The Room Geometry accounted for this location by assuming that 50 percent of the residual contamination was present on each of the two walls. As before, the source to detector distance assumed the depth of the Flocculator tank (56 inches). The 180 degree FOV was used (collimator removed) and the measurement acquired at the lip of the Flocculator Tank (floor surrounding the tank). An area of 5.42 m2 was used. The measurement location was centered over the region. The second compartment of the Flocculator Tank (Location 73) uses the same dimensions as Location 72 above except this compartment consist of 3 walls and results in an area of 9.23 m2. Location 73 utilizes the same source to detector distance, FOV and measurement centering as Location 72. Residual contamination was assumed to reside over three walls and the floor at a 0.25 concentration. Clarifier Sump (Location 70 and 71) The Clarifier Sumps) consist of two identical locations that are 96 inches wide, 90 inches long and 60 inches deep. These locations consist of sloped walls on the east and west sides and vertical walls on the north and south sides. The Room Geometry was used for these locations. Assuming a rectangular box, the total surface area was calculated to be 19.97 m2. Adjustments were made to accommodate the area reduction due to sloping sides resulting in a surface area of 15.33 m2. However, the physical geometry conservatively assumed the sides were perpendicular. The 180 degree FOV was used with the detector located at the center of the rectangular area and at the lip of the Clarifier. [42]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility 3 WWTF1.27CM [43]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility 3 WWTF1.27CM (continued) [44]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility 3M 90D CP WWTF1.27CM (continued) [45]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility 3M 90D CP WWTF1.27CM (continued) [46]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Sump 1 [47]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Sump 1 (continued) [48]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Sump 2 [49]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Sump 2 (continued) [50]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Sump 3 [51]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Sump 3 (continued) [52]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Flocculator Tank 73 [53]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Flocculator Tank 73 (continued) [54]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Flocculator Tank 73 (continued) [55]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Flocculator Tank 72 [56]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Flocculator Tank 72 (continued) [57]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Flocculator Tank 72 (continued) [58]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Clarifier Tank [59]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Clarifier Tank (continued) [60]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Waste Water Treatment Facility Clarifier Tank (continued) [61]

ATTACHMENT 3 SIGN TEST [62]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Sign Test Waste Water Treatment Facility Survey Area 09100 Description Out Buildings Survey Unit B1-09100A-F Description WWTF Classification 1 Type I Error 0.05 # of Measurements 70 SOF

                #                                1-WS          Sign (WS) 1              0.0414            0.96           +1 2              0.0642            0.94           +1 3              0.0071            0.99           +1 4              0.0663            0.93           +1 5              0.0656            0.93           +1 6              0.0703            0.93           +1 7              0.0647            0.94           +1 8              0.0796            0.92           +1 9              0.0478            0.95           +1 10              0.0093            0.99           +1 11              0.0608            0.94           +1 12              0.0619            0.94           +1 13              0.2361            0.76           +1 14              0.0988            0.90           +1 15              0.0938            0.91           +1 16              0.0591            0.94           +1 17              0.0543            0.95           +1 18              0.0547            0.95           +1 19              0.1139            0.89           +1 20              0.1429            0.86           +1 21              0.1145            0.89           +1 22              0.0826            0.92           +1 23              0.0771            0.92           +1 24              0.0632            0.94           +1 25              0.0482            0.95           +1 26              0.0357            0.96           +1 27              0.0741            0.93           +1 28              0.1019            0.90           +1 29              0.0492            0.95           +1 30              0.1222            0.88           +1 31              0.0732            0.93           +1 32              0.0680            0.93           +1 33              0.1092            0.89           +1 34              0.0611            0.94           +1

[63]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Sign Test Waste Water Treatment System (continued) SOF

              #                                 1-WS          Sign (WS) 35            0.0395               0.96           +1 36            0.0763               0.92           +1 37            0.1515               0.85           +1 38            0.0790               0.92           +1 39            0.0482               0.95           +1 40            0.0838               0.92           +1 41            0.1348               0.87           +1 42            0.0920               0.91           +1 43            0.0671               0.93           +1 44            0.0997               0.90           +1 45            0.0774               0.92           +1 51            0.1145               0.89           +1 52            0.0643               0.94           +1 53            0.0230               0.98           +1 54            0.0775               0.92           +1 55            0.1000               0.90           +1 56            0.0226               0.98           +1 57            0.0377               0.96           +1 58            0.1001               0.90           +1 59            0.1055               0.89           +1 60            0.0417               0.96           +1 61            0.0430               0.96           +1 62            0.1074               0.89           +1 63            0.0545               0.95           +1 64            0.0453               0.95           +1 65            0.0506               0.95           +1 66            0.0564               0.94           +1 67            0.0392               0.96           +1 68            0.0330               0.97           +1 69            0.0327               0.97           +1 70            0.0252               0.97           +1 71            0.0233               0.98           +1 72            0.1007               0.90           +1 73            0.0152               0.98           +1 74            0.0166               0.98           +1 75            0.0331               0.97           +1 Number of Positive Differences (S+) =     70 Critical Value =    40 Survey Unit Meets the Acceptance Criteria

[64]

ATTACHMENT 4 QC MEASUREMENT ASSESSMENTS [65]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Replicate Measurement Assessment Survey Unit # 09100 Survey Unit Name WWTF Sample Plan # B1-09100A-F Sample

Description:

Comparison of systematic and QC ISOCS measurements of concrete floor at location #014. STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N) Cs-137 2.57E+04 1.00E+00 25,700 0.85-1.18 3.56E+03 1.00E+00 7.22 N K-40 7.60E+05 2.13E+05 4 0.5-2.0 8.85E+05 2.20E+05 0.86 Y Comments/Corrective Actions: (1)-For Cs-137, Table is provided to show acceptance criteria comparison sample had a negative value and the used to assess split samples. standard error was not reported, therefore the value of 1 was used for the comparison sample activity and standard error. The Cs-137 activity for both the standard and comparison samples were less than the respective MDC's (2.76E+04 pCi/m2 and 2.52E+04 pCi/m2 respectively). When K-40 was used to compare the standard and comparison samples, they indicated an acceptable level of agreement between the two samples. [66]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Replicate Measurement Assessment Survey Unit # 09100 Survey Unit Name WWTF Sample Plan # B1-09100A-F Sample

Description:

Sample

Description:

Comparison of systematic and QC ISOCS measurements of concrete floor at location # 009. STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N) Cs-137 3.15E+03 1.00E+00 3,150 0.85-1.18 2.14E+04 1.00E+00 0.15 N K-40 1.22E+06 2.36E+05 5 0.5-2.0 1.01E+06 2.48E+05 1.21 Y Comments/Corrective Actions: (1)-For Cs-137, the Table is provided to show acceptance criteria standard error was not reported, therefore the value used to assess split samples. of 1 was used for standard error. The Cs-137 activity for both the standard and comparison samples were less than the respective MDC's (2.4E+04 pCi/m2 and 2.14E+04 pCi/m2 respectively). When K-40 was used to compare the standard and comparison samples, they indicated an acceptable level of agreement between the two samples. [67]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Replicate Measurement Assessment Survey Unit # 09100 Survey Unit Name WWTF Sample Plan # B1-09100A-F Sample

Description:

Comparison of systematic and QC ISOCS measurements of concrete wall at location # 027. STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N) Cs-137 2.57E+04 1.00E+00 3,150 0.85-1.18 1.00E+00 1.00E+00 25,700 N K-40 1.06E+06 2.34E+05 5 0.5-2.0 1.11E+06 2.48E+05 0.95 Y Comments/Corrective Actions: (1)-For Cs-137, Table is provided to show acceptance criteria comparison sample had a negative value and the used to assess split samples. standard error was not reported, therefore the value of 1 was used for the comparison sample activity and standard error. The Cs-137 activity for both the standard and comparison samples were less than the respective MDC's (2.76E+04 pCi/m2 and 2.52E+04 pCi/m2 respectively). When K-40 was used to compare the standard and comparison samples, they indicated an acceptable level of agreement between the two samples. [68]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Replicate Measurement Assessment Survey Unit # 09100 Survey Unit Name WWTF Sample Plan # B1-09100A-F Sample

Description:

Comparison of systematic and QC ISOCS measurements of concrete wall at location # 053. STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N) Cs-137 6.59E+03 1.00E+00 6,590 0.85-1.18 3.34E+04 1.29E+04 0.20 N K-40 7.14E+05 2.03E+05 4 0.5-2.0 8.35E+05 2.04E+05 0.86 Y Comments/Corrective Actions: (1)-For Cs-137, the Table is provided to show acceptance criteria standard error was not reported, therefore the value used to assess split samples. of 1 was used for the comparison sample and standard error. The Cs-137 activity for the standard sample was less than the MDC (3.16E+04 pCi/m2). When K-40 was used to compare the standard and comparison samples, they indicated an acceptable level of agreement between the two samples. [69]

ATTACHMENT 5 GRAPHICAL PRESENTATIONS [70]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Quantile Plot for Co-60 Survey Unit: B1-09100AF

Description:

Waste Water Treatment Facility Mean: 7.06E+03 pCi/m2 6.00E+04 5.00E+04 Concentration (pCi/m2) 4.00E+04 3.00E+04 2.00E+04 1.00E+04 0.00E+00 0% 20% 40% 60% 80% 100% Percentage [71]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Quantile Plot for Cs-137 Survey Unit: B1-09100AF

Description:

Waste Water Treatment Facility Mean: 1.12E+04 pCi/m2 4.00E+04 3.50E+04 Concentration (pCi\m2) 3.00E+04 2.50E+04 2.00E+04 1.50E+04 1.00E+04 5.00E+03 0.00E+00 0% 20% 40% 60% 80% 100% Percentage [72]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Histogram for Co-60 Survey Unit: B1-09100A

Description:

Waste Water Treatment Facility Mean: 7.06E+03 pCi/m2 Median: 5.61E+03 pCi/m2 ST Dev.: 8.38E+03 Skew: 3.03E+00 45% 40% 35% 30% Frequency 25% 20% 15% 10% 5% 0% 1.00E+00 3.00E+00 5.00E+00 7.00E+00 9.00E+00 Upper End Value (pCi/m2) Upper Value Observation Observation % Frequency 4.99E+03 30 43% 9.98E+03 26 37% 1.50E+04 8 11% 2.00E+04 3 4% 2.50E+04 1 1% 2.99E+04 0 0% 3.49E+04 0 0% 3.99E+04 0 0% 4.49E+04 1 1% 4.99E+04 1 1% TOTAL 70 100% [73]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Histogram for Cs-137 Survey Unit: B1-09100A

Description:

Waste Water Treatment Facility Mean: 3.15E+06 pCi/m2 Median: 8.10E+05 pCi/m2 ST Dev.: 6.86E+06 Skew: 5.16E+00 25% 20% Frequency 15% 10% 5% 0% 1.00E+00 3.00E+00 5.00E+00 7.00E+00 9.00E+00 1.10E+01 Upper End Value (pCi/m2) Upper Value Observation Observation % Frequency 3.43E+03 15 21% 6.86E+03 8 11% 1.03E+04 8 11% 1.37E+04 11 16% 1.72E+04 14 20% 2.06E+04 6 9% 2.40E+04 2 3% 2.74E+04 3 4% 3.09E+04 0 0% 3.09E+04 2 3% TOTAL 70 100% [74]

FSS RELEASE RECORD WASTE WATER TREATMENT FACILITY SURVEY UNIT 09100 Retrospective Power Curve for Survey Unit 09100 [75]

ATTACHMENT 6 ISOCS ANALYTICAL REPORTS [76]

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

Filename: C:\GENIE2K\CAMFILES\00003478.CNF Report Generated On 8/20/2018 5:50:14 AM Sample Title B109100AFSFC001GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M9DDWWTF1.27CM 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 8/15/2018 2:30: 00 PM Acquisition Started 8/15/2018 2:31: 00 PM Live Time 600.0 seconds Real Time 601.3 seconds Dead Time 0 .21 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1.27CM DATA VALIDATED DATE Cj-7-(6 LJ-=i!---i TIME ' O " I ~ (l, V'1-r?Wy/ [77]

Peak Analysis Report 8/20/2018 5:50:14 AM Page 2

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

Detector Name: 5452A Sample

Title:

B109100AFSFCOD1GD Peak Analysis Performed on: 8/20/2018 5:50:13 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 1 297- 306 301.53 75.38 0.62 4.67E+001 4 1. 97 1. 73E+002 2 946- 963 955.47 238.87 0.80 3.72E+OD1 3 4.11 7.68E+001 3 1173- 1187 1180.46 295.11 1. 11 3.30E+001 25.20 4.30E+001 4 1398- 1414 1408.08 352.02 0.53 7.lOE+OOl 26.20 3.20E+001 5 2428- 2444 2436.70 609.17 0 .98 8.16E+001 24.47 2.14E+001 6 5832- 5855 5843.27 146 0 .82 2.15 1.56E+002 28.19 1.llE+OOl M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [78]

Interference Corrected Activity Report 8/20/2018 5:50:14 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:

B109100AFSFC001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENT IFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1.000 1460.82* 10.66 1 .06244E+006 2.1304BE+OOS Pb-212 1. 000 238.63* 43.60 2.52184E+004 2.34895E+004 Bi-214 0.439 609.32* 45.49 8.49371E+004 2.74415E+004 1120.29 14.92 1764.49 15.30 Pb-214 1. 000 295.22* 18.42 5.89874E+004 4 .59778E+004 351.93* 35.60 7.17154E+004 2.88311E+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

[79]

Interference Corrected Activity Report 8/20/2018 5:50:14 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 1.000 1 .062444E+006 2.130478E+OOS Pb-212 1.000 2.521844E+004 2.348949E+004 Bi-214 0.439 8.493714E+004 2.744147E+004 Pb-214 1.000 6.812315E+004 2.442599E+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: 8/20/2018 5:50:13 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Count-s per Second  % Uncertainty Type Nuclide 1 75.38 7.7875E-002 89.82 M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [80]

Nuclide MDA Report 8/20/2018 5:50: 14 AM Page 5

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

Detector Name: 5452A Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC001GD 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    1.649E+OOS    1. 65E+OOS  1.062E+006  7.322E+004 Co-60     1173.23    99.85    1.959E+004    1. 69E+004  2.190E+003  8.920E+003 1332.49    99.98    1.689E+004                3.741E+003  7.515E+003 Nb-94       702.65   99. 81   l.705E+004    l. 71E+004 -7.126E+003  7.838E+003 871.09   99.89    1.737E+004                9.146E+003  7.928E+003 Ag- 108m    433.90   90.50    1.802E+004    1. 80E+004  2.538E+002  8.410E+003 614.30   89.80    3.006E+004               -1.409E+004  1. 431E+004 722.90   90.80    1.977E+004               -2.157E+004  9.118E+003 Cs-134      604.72   97.62    2.754E+004    2.02E+004  -1.365E+004  l .311E+004 795.86   85.46    2.019E+004               -5.870E+003  9.243E+003 Cs-137      661.66   85. 10   2.429E+004    2.43E+004   1. 523E+004 l .136E+004 Eu-152      121.78   28.67    7.203E+004    6.45E+004   1. 483E+004 3.490E+004 344.28   26.60    6.453E+004               -4.711E+004  3.046E+004 1408 .01   21.07    6.787E+004                4.724E+004  2.937E+004 Eu-154      123.07   4.0. 4 0 5.081E+004    4.55E+004  -7:839E+003  2.461E+004 723.30   20.06    8.950E+004               -6.314E+004  4.128E+004 1274.43    34.80    4. 552E+004              -2.459E+004  2.014E+004 Eu-155       86.55   30.70    8.059E+004    8.06E+004  -9.507E+003  3.925E+004 105.31   21.10    1.052E+005                1.646E+004  5.107E+004 Tl-208      583.19   85.00    2.388E+004    2.39E+004   1.778E+004  1.120E+004 Bi-212      727.33    6.67    2.724E+005    2.72E+005  -2.355E+005  1. 2 58E+005
 +       Pb-212      238.63*  43.60    3.737E+004    3.74E+004   2.522E+004  1.777E+004
 +       Bi-214      609.32*  45.49    3.108E+004    3.11E+004   8.494E+004  1.413E+004 1120.29    14. 92   1. 618E+005               1.824E+OOS  7.515E+004 1764.49    15.30    1. 407E+005               1.384E+005  6.316E+004
 +       Pb-214      295.22*  18.42    7.070E+004    3.60E+004   S.899E+004  3.294E+004 351.93*  35.60    3.604E+004                7.172E+004  1 .665E+004 Ra-226      186.21    3.64    5.333E+005    5.33E+OOS  -l.531E+005  2.569E+005 Ac-228      338.32   11. 27   1 .638E+005   7.38E+004   9.726E+004  7.765E+004 911.20   25.80    7.376E+004                4 .861E+004 3.387E+004 968.97   15.80    1 .114E+005              -5.894E+004  5.067E+004 Am-241       59.54   35.90    7.740E+004    7.74E+004  -1.375E+005  3.763E+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

[81]

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

Filename: 6279 Report Generated On 8/16/2018 8:46:07 AM Sample Title B109100AFSFC002GD Sample Description WWTF FLOOR Sample Identification 002 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 2.826E+001 M"2 Sample Taken On 8/16/2018 8:36:00 AM Acquisition Started 8/16/2018 8:36:05 AM Live Time 600.0 seconds Real Time 601.0 seconds Dead T ime 0 . 16 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE q*_,7...-f '8 0 [82]

Peak Analysis Report 8/16/2018 8:46:07 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSFC002GD Peak Analysis Performed on: 8/16/2018 8:46:07 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- 306 301.06 75.39 0.73 1.37E+002 65.32 2.48E+002 2 579- 593 587.35 146 .96 0.42 -9.31E+OOO 28.93 7.33E+001 3 1401- 1414 1407.60 352.01 1. 06 3.51E+001 2 1 .16 2.79E+001 4 2431- 2444 2437.42 609.45 0.50 3.40E+001 14.61 7.00E+OOO 5 5835- 5856 5846.60 14 61. 70 0.90 8.55E+001 20.61 5.SOE+OOO M First peak in a multiplet region m == Other peak in a multiplet region F == Fitted singlet Errors quoted at 2 . 000 sigma [83]

Interference Corrected Activity Report 8/16/2018 8:46:07 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:

B109100AFSFC002GD 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 9.28729E+005 2.46837E+005 Bi-214 0.461 609.32* 45.49 4 .96102E+004 2.24091E+004 1120.29 14.92 1764.49 15. 30 Pb-214 0.432 295.22 18.42 351.93* 35.60 4.46742E+004 2.79323E+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

[84]

Interference Corrected Activity Report 8/16/2018 8:46: 07 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/M ... 2 ) Uncertainty K-40 0.999 9.287290E+005 2.468374E+005 Bi-214 0.461 4.961017E+004 2.240907E+00 4 Pb-214 0.432 4.467424E+004 2.793230E+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
  **********    UN I D E NT I F I E D              P E A K S     **********

Peak Locate Performed on: 8/16/2018 8:46:07 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 75.39 2.2833E-001 47.68 2 146.96 -1. 5514E-002 -310.81 M = First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma [85]

Nuclide MDA Report 8/16/2018 8:46:07 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM sample

Title:

B109100AFSFC002GD 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  1.918E+005    l.92E+005 9.287E+005    8.122E+004 Co-60      1173.23      99.85  2.410E+004    l.72E+004 -l.717E+004   1. 069E+004 1332.49      99.98  1.717E+004                8.658E+003  7.121E+003 Nb-94        702.65     99.81  1. 714E+004   1.71E+004 5.375E+002    7.583E+003 871.09     99.89  1. 870E+004              -1. 283E+004 8.222E+003 Ag-108m      433.90     90.50  2.179E+004    2.18E+004 5.226E+003    1. 011E+004 614.30     89.80  2.857E+004               -1. 515E+004 1. 328E+004 722.90     90.80  2.367E+004               -1. 019E+002 1. 073E+004 Cs-134       604.72     97.62  2.778E+004    2.43E+004 3.138E+003    1 .298E+004 795.86     85.46  2.432E+004                2.393E+004  1. 0 92E+004 Cs-137       661.66     85.10  2.618E+004    2.62E+004 1.458E+004    1 .198E+004 Eu- 152      121. 78    28.67  6.841E+004    6.84E+004 1.601E+004    3.299E+004 344.28     26.60  7.476E+004                2.089E+004  3.511E+004 1408. 01     21. 07 9.695E+004                5.880E+004  4.124E+004 Eu-154       123.07     40. 40 4.911E+004    4.80E+004 4.595E+004    2.369E+004 723.30     20.06  1.072E+005                4.616E+002  4~860E+004 1274.43      34.80  4.801E+004                5.674E+003  1.991E+004 Eu-155        86.55     30.70  7.561E+004    7.56E+004 9.828E+004    3.670E+004 105.31     21.10  9.315E+OD4               -4 .840E+004 4.497E+004 Tl-208       583.19     85.00  2.674E+004    2.67E+004 2.317E+004    1.235E+004 Bi-212       727.33      6.67  3.045E+005    3.05E+005 1 .672E+004   1. 372E+005 Pb-212       238.63     43.60  4 .693E+004   4.69E+004 4.709E+004    2.239E+004
 +      Bi-214       609.32*    45.49  2.506E+004    2.51E+004 4.961E+004    1.056E+004 1120 .29     14.92  1.972E+005                8.037E+004  8.977E+004 1764.49      15.30  1. 953E+005               1 .566E+005 8.589E+004
 +      Pb-214       295.22     18.42  1 .124E+005   4.02E+004 9.305E+004    5.327E+004 351. 93

• 35.60 4.016E+004 4.467E+004 1 .836E+004 Ra-226 186.21 3.64 4.789E+005 4 .79E+005 1.612E+005 2.284E+005 Ac-228 338.32 11. 27 1 .617E+005 8.46E+004 -1.094E+005 7.555E+004 911.20 25.80 8.459E+004 6.669E+003 3.781E+004 968.97 15.80 1.634E+005 3.923E+004 7.408E+004 Am-241 59.54 35.90 6.142E+004 6.14E+004 -4 .420E+003 2.959E+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

[86]

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

Filename: 5452A Report Generated On 8/15/2018 1:50:19 PM Samp le Title B109100AFSFC003GD Samp le Description WWTF Floor Samp le Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/15/2018 1: 40: 00 PM Acquisition Started B/15/2018 1: 40: 17 PM Live Time 600. 0 seconds Real Time 600 .7 seconds Dead Time 0 . 12 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1.27CM DATA VALIDATED DATE 1 /7.,.('6 TIME t.~~I~ Or 0 [87]

Peak Analysis Report 8/15/2018 1:50:19 PM Page 2

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

Detector Name: 5452A Sample

Title:

Bl09100AFSFC003GD Peak Analysis Performed on: 8/15/2018 1:50:18 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 (ke V) (keV) Area Uncert. Counts 1 296- 306 301.27 75.32 0.25 l .43E+001 45.88 2.15E+002 2 436- 448 440.04 110.01 0.67 1 .39E+001 37.24 1 .24E+002 3 964- 976 968.25 242.06 0.75 9.00E+OOO 24.60 5.20E+001 4 1175- 1186 1181.22 295.31 0.44 2.31E+001 20.54 3.29E+001 5 1399- 1413 1407.52 351.88 0.87 5.09E+001 22.97 2.81E+001 6 2429- 2445 2436.40 609.10 1.46 5.53E+001 24.36 2.98E+001 7 2641- 2652 2646.94 661.73 0.25 4.00E+OOO 12.88 1.50E+001 8 4476- 4489 4482.98 1120.75 0.32 1.22E+001 12.09 8.76E+OOO 9 5832- 5854 5842.57 1460 . 64 1. 95 1.40E+002 24.70 3.08E+OOO 10 7053- 7068 7060.36 1765.09 0.39 1.33E+001 11.04 5.74E+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 [88]

Interference Corrected Activity Report 8/15/2018 1: 50:19 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:

B109100AFSFC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence {keV) { %) {pCi/M"'2 ) Uncertainty K-40 1. 000 1460.82* 10 .66 9.53189E+005 1.87541E+005 Cs-137 1. 000 661.66* 85 .10 2.31830E+003 7.47264E+003 Pb-212 0.981 238.63* 43.60 6.14479E+003 l.68233E+004 Bi-214 1.000 609.32* 45.49 5.75132E+004 2.62880E+004 1120 .29* 14 .92 5.19223E+004 5. 14 465E+004 1764.49* 15 .30 7.06301E+004 5.90474E+004 Pb-214 1.000 295.22* 18 .42 4.12243E+004 3.72756E+004 351.93* 3 5.60 5.14148E+004 2.46066E+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

[89]

Interference Corrected Activity Report 8/15/2018 1 :50:19 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 9.531892E+OOS l.875413E+OOS Cs-137 1.000 2.318298E+003 7.472637E+003 Pb-212 0.981 6.144788E+003 1. 682330E+004 Bi-214 1.000 5.829444E+004 2.176128E+004 Pb-214 1.000 4.832189E+004 2.053569E+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

[90]

Interference Corrected Activity Report 8/15/2018 1:50 : 19 PM Page s

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

Peak Locate Performed on : 8/15/2018 1:50:18 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 75.32 2.3799E-002 321.28 2 110.01 2.3 104E-002 268.68 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 [91]

Nuclide MDA Report 8/15/2018 1 :50:19 PM Page 6

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

Detector Name: 5452A Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC003GD 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  9.812E+004    9.81E+004 9.532E+OOS   3.984E+004 Co-60      1173.23     99.85  l .959E+004   1.58E+004 -9.916E+003  8.920E+003 1332.49     99.98  1 .583E+004             -4.259E+003  6.983E+003 Nb-94        702.65    99. 81 1 .632E+004   1.63E+004 -1.206E+004  7.474E+003 871. 09   99.89  1.737E+004               5.811E+003  7.928E+003 Ag-108m      433.90    90.50  1.671E+004    1.62E+004 -9.963E+003  7.757E+003 614. 3 0  89.80  2.727E+004              -2.116E+004  1.292E+004 722.90    90.80  l.619E+004              -5.046E+003  7.328E+003 Cs-134       604.72    97.62  2.665E+004    1.87E+004 1.219E+003   1.267E+004 795.86    85.46  1.874E+004               4. 083E+003 8.522E+003
 +       Cs-137       661.66*   85.10  1.325E+004    1.32E+004 2.318E+003   5.838E+003 Eu-152       121. 78   28.67  6.558E+004    6.39E+004 -2.646E+004  3.167E+004 344.28    26.60  6.389E+004              -2.896E+004  3.014E+004 1408.01     21.07  7.192E+004              -8.177E+004  3.140E+004 Eu- 154      123. 07   40.40  4.644E+004    4.64E+004 -2.160E+004  2.242E+004 723. 3 0  20.06  7.220E+004              -6.019E+004  3.264E+004 1274.43     34.80  5.117E+004               4.654E+003  2.297E+004 Eu-155        86.55    30.70  7.919E+004    7.92E+004 8.860E+004   3.855E+004 105. 31   21.10  9.816E+004               6.602E+004  4.756E+004 Tl-208       583.19    85.00  2.145E+004    2.15E+004 9.244E+003   9.989E+003 Bi-212       727.33     6.67  2.076E+005    2.08E+005 1.025E+005   9.336E+004
 +       Pb-212       238.63*   43.60  2.864E+004    2.86E+004 6.14SE+003   1.340E+004
 +       Bi-214       609.32*   45.49  3.587E+004    3.59E+004 5.751E+004   l.653E+004 1120.29*    14.92  8.026E+004               5.192E+004  3.439E+004 1764.49*    15.30  8.705E+004               7.063E+004  3.632E+004
 +       Pb-214       295.22*   18.42  5.817E+004    3.26E+004 4.122E+004   2.667E+004 351.93*   35.60  3.262E+004               S.141E+004  1.495E+004 Ra-226       186.21     3.64  5.527E+005    5.53E+OOS 1.620E+005   2.666E+OOS Ac-228       338.32    11.27  1.554E+005    7.45E+004 -6.732E+004  7.345E+004 911. 2 0  25.80  7.454E+004               1.842E+004  3.427E+004 968.97    15.80  1.254E+OOS               3.226E+004  5.764E+OD4 Am-241        59.54    35.90  6.633E+004    6.63E+004 -1.919E+004  3.210E+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

[92]

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

Filename: 5452A Report Generated On 8/15/2018 12:42:09 PM Sample Title B109100AFSFC004GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/15/2018 12:32:00 PM Acquisition Started 8/15/2018 12:32:08 PM Live Time 600. 0 seconds Real Time 600.7 seconds Dead Time 0 . 11 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1 . 27CM [93]

Peak Analysis Report 8/15/2018 12:42:09 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:

B109100AFSFC004GD Peak Analysis Performed on: 8/15/2018 12:42:09 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 1 950- 961 955.83 238.96 0.47 2.90E+001 25.67 5 .40E+001 2 1175- 1189 1181. 46 295.37 0 .36 5.58E+001 22.90 2.62E+001 3 1399- 1414 1407.82 351.95 1. 33 6.81E+001 24.15 2.59E+001 4 2036- 2050 2043.51 510.88 0.71 5.40E+001 20.32 1.70E+001 5 2427- 2445 2436.43 609. 11 1.67 7.75E+001 23.07 l.65E+001 6 2642- 2654 2647.00 661.75 0.39 1 .92E+001 12.62 7.83E+OOO 7 3637- 3650 3643.88 910.97 0.30 1.82E+001 13.03 8.76E+OOO 8 5832- 5854 5844.15 1461. 04 1. 26 l.32E+002 2 4 .87 5.73E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 , 000 sigma [94]

Interference Corrected Activity Report 8/15/2018 12:42:09 PM Page 3

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Sample

Title:

B109100AFSFC004GD 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 9.01211E+005 1.866BOE+005 Cs-137 1.000 661.66* 85.10 1.11086E+004 7.43660E+003 Pb-212 1.000 238.63* 43.60 1.96716E+004 1.76983E+004 Bi-214 0.439 609.32* 45.49 8.0691BE+004 2.58977E+004 1120.29 14 .92 1764.49 15.30 Pb-214 1.000 295.22* 18.42 9.97498E+004 4.39126E+004 351.93* 35.60 6.87182E+004 2.67468E+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

[95]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1 .000 9.012113E+005 1.866800E+005 Cs-137 1.000 l.110863E+004 7.436604E+003 Pb-212 1.000 1.967159E+004 1.769828E+004 Bi-214 0.439 8.069178E+004 2.589766E+00 4 Pb-214 1. 000 7.711537E+004 2.284303E+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: 8/15/2018 12:42:09 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 4 510.88 9.0035E-002 37.61 7 910.97 3.0401E-002 71.46 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [96]

Nuclide MDA Report 8/15/2018 12:42:09 PM Page 5

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

Detector Name: 5452A Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC004GD 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. 246E+OOS   1.2SE+005  9.012E+005  5.307E+004 Co-60      1173.23    99.85  l.908E+004    l.62E+004  5.921E+003  8.661E+003 1332.49    99.98  1. 619E+004              3.271E+003  7.165E+003 Nb-94        702.65   99.81  l.740E+004    1.37E+004  1.406E+004  8.015E+003 871.09   99.89  1. 374E+004             -2.354E+004  6.113E+003 Ag-108m      433.90   90.50  1. 711E+004   l.71E+004  6.029E+003  7.959E+003 614.30   89.80  2.668E+004              -1.396E+004  1.262E+004 722.90   90.80  2.140E+004               4. 069E+003 9.936E+003 Cs-134       604.72   97.62  2.66SE+004    1.97E+004 -9.540E+003  l.267E+004 795.86   85.46  1. 972E+004              1. 523E+004 9.009E+003
 +      Cs-137       661.66*  85.10  1. 024E+004   l.02E+004  l.111E+004  4.334E+003 Eu-152       121. 78  28.67  7.235E+004    6.16E+004 -2.673E+004  3.50SE+004 344.28   26.60  6.160E+004              -8.600E+002  2.899E+004 1408.01    21.07  7.192E+004               2.773E+004  3.140E+004 Eu-154       123.07   40.40  5.209E+004    4.24E+004  2.733E+004  2.525E+004 723.30   20.06  9.287E+004              -6.473E+004  4.297E+004 1274.43    34.80  4. 238E+004              8.541E+002  l. 857E+004 Eu-155        86.55   30.70  9.238E+004    9.24E+004  1. 0SOE+OOS 4.515E+004 105.31   21.10  1. 082E+005              1. 308E+005 5.257E+004 Tl-208       583.19   85.00  2.145E+004    2.15E+004 -1. 873E+003 9.989E+003 Bi-212       727.33    6.67  2.724E+005    2.72E+005  8.251E+004  1.258E+005
 +      Pb-212       238.63*  43.60  2.783E+004    2.78E+004  1.967E+004  1.300E+004
 +      Bi-214       609.32*  45.49  2.833E+004    2.83E+004  8.069E+004  l.276E+004 1120.29    14 .92 l. 565E+005              1.307E+OOS  7.252E+004 1764.49    15.30  1. 545E+OOS              l.704E+005  7.007E+004
 +      Pb-214       295.22*  18.42  S.582E+004    3.20E+004  9.975E+004  2.549E+004 351.93*  35.60  3.202E+004               6.872E+004  l.464E+004 Ra-226       186.21    3.64  S.018E+OOS    5.02E+005 -9.577E+004  2.411E+OOS Ac-228       338.32   11 .27 1. 426E+005   7.76E+004 -3.306E+004  6.705E+004 911.20   25.80  7.759E+004               4.608E+004  3.579E+004 968.97   15.80  l. 114E+OOS             -1. 375E+005 5.067E+004 Am-241        59.54   35.90  7.430E+004    7.43E+004 -7.817E+003  3.609E+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

[97]

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

Filename: 5452A Report Generated On 8/15/2018 12:55:16 PM Samp le Title B109100AFSFC005GD Samp le Description WWTF Floor Samp le Identification Samp le Type Gamma Direct Samp le Geometry 3M90DWWTF1.27CM 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 8/15/2018 12:45:00 PM Acquisition Started 8/15/2018 12:45: 15 PM Live Time 600. 0 seconds Real Time 600.6 seconds Dead Time 0 . 10 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1.27CM [98]

Peak Analysis Report 8/15/2018 12:55 : 16 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:

B109100AFSFC005GD Peak Analysis Performed on: 8/15/2018 12:55:16 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- 306 292.07 73.02 0.40 1.63E+002 74.50 3.16E+002 2 951- 961 956.74 239.19 0.84 3.77E+001 23.35 4.13E+001 3 1174- 1191 1180.53 295 .13 0.91 6.44E+001 25.88 3.16E+001 4 1400- 1417 1407.32 351.83 1.10 8.17E+001 26.95 3.03E+001 5 2325- 2338 2331. 44 582.86 0 .93 2.56E+001 15.89 1 .34E+001 6 2429- 2443 2435.46 608.86 1. 63 6.60E+001 20.95 1 .SOE+OOl 7 3067- 3078 3072.02 768. 01 0.38 1 .14E+001 10.13 5.56E+OOO 8 3637- 3650 3643.75 91 0. 94 0.87 2.29E+001 14.84 1. llE+OOl 9 5833- 5854 5843.52 146 0. 88 0.80 1 .SOE+002 27.41 1. 04E+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 [99]

Interference Corrected Activity Report 8/15/2018 12:55:16 PM Page 3

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Sample

Title:

B109100AFSFC005GD 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 1 .01932E+006 2.06690E+005 Tl-208 1 .000 583. 19* 85. 00 1 .39787E+004 8.82655E+003 Pb-212 1 .000 238.63* 43.60 2.55892E+004 1.63774E+004 Bi-214 0.439 609.32* 45.49 6.86905E+004 2.33148E+004 1120. 29 14.92 1764.49 15.30 Pb-214 1. 000 295.22* 18.42 1.14929E+005 4.97376E+004 351.93* 35.60 8.24978E+004 3.02356E+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

[100]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1 .019320E+006 2.066896E+005 Tl-208 1.000 1 .397872E+004 8.826551E+003 Pb-212 1.000 2.55892SE+004 1.637743E+004 Bi-214 0.439 6.869053E+004 2.331476E+004 Pb-214 1.000 9. 1 24877E+004 2.583633E+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 A K S       **********

Peak Locate Performed on: 8/15/2018 12:55:16 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 73.02 2.7156E-001 45.72 7 768.01 1. 9069E-002 88.57 8 910 .94 3.8150E-002 6 4 .83 Sum M = First peak in a mult iplet region m !OS Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 000 sigma [101]

Nuclide MDA Report 8/15/2018 12:55:16 PM Page 5

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

Detector Name: 5452A Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/MA2 )

 +      K-40       1460 .82*    10.66  1 .571E+005   1.57E+005 1.019E+006     6.934E+004 Co-60      1173.23      99.85  1 .934E+004   1.55E+004 -4.246E+003    8.791E+003 1332.49      99.98  1 .546E+004                8.159E+003  6.797E+003 Nb-94        702.65     99. 81 1 .740E+004   1.53E+004 2.821E+003     8.015E+003 871.09     99.89  1 .531E+004                8.544E+003  6.897E+003 Ag-108m      433.90     90.50  1 .802E+004   1.80E+004 1. 235E+004    8.410E+003 614.30     89.80  2.716E+004                -2.648E+003  1.286E+004 722.90     90.80  1.838E+004                 1. 040E+004 8.427E+003 Cs-134       604.72     97.62  2.584E+004    1 . 92E+004 -1. 972E+004 l.227E+004 795.86     85 .46 1.924E+004                -1. 689E+004 8.769E+003 Cs-137       661. 66    85. 10 2.246E+004    2.25E+004 1. 999E+004    1.044E+004 Eu-152       121. 78    28.67  7.096E+004    6.55E+004    7.050E+004  3.436E+004 344.28     26.60  6.547E+004                -6.178E+004  3.093E+004 1408.01      21.07  7.934E+004                 1.434E+004  3.510E+004 Eu-154       123.07     40.40  4.872E+004    4.87E+004 -2.879E+004    2.356E+004 723.30     20.06  8.324E+004                 5.516E+004  3.815E+004 1274.43      34.80  5.028E+004                -1.086E+004  2.252E+004 Eu-155        86.55     30.70  8.068E+004    8.07E+004 7.201E+004     3.930E+004 105 .31    21. 10 1.078E+005                -4.341E+004  5.238E+004
 +      Tl-208       583.19*    85.00  1.246E+004    1.25E+004 1.398E+004     5.493E+003 Bi-212       727.33       6.67 2.304E+005    2.30E+005 -9.637E+004    1. 048E+005
 +      Pb-212       238.63*    43.60  2.401E+004    2. 40E+004 2.559E+004    1.109E+004
 +      Bi-214       609 . 32*  45.49  2.546E+004    2.55E+004 6.869E+004     1.132E+004 1120.29      14 .92 1 .618E+005                1.127E+005  7.515E+004 1764 .49     15 .30 1 .523E+005                7.587E+004  6.896E+004
 +      Pb-214       295.22*    18 .42 6.447E+004    3.59E+004 1 .149E+005    2.982E+004 351.93*    35.60  3.591E+004                 8.250E+004  1.659E+004 Ra-226       186.21       3.64 4.888E+005    4 .89E+005 1 .059E+005   2.346E+005 Ac-228       338.32     1 1.27 1 .449E+005   8.67E+004 8.534E+003     6.822E+004 911.20     25.80  8.670E+004                 5.477E+004  4 .035E+004 968.97     15.80  1.425E+005                 1 .609E+005 6.618E+004 Am-241        59.54     35.90  7.009E+004    7.01E+004 3.617E+004     3.398E+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

[102]

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

Filename : 5452A Report Generated On 8/15/2018 1: 37: 32 PM Sample Title B-109100AFSFCOOfrGD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 Samp le Taken On 8/15/2018 1:27:00 PM Acquisition Started 8/15/2018 1: 27:30 PM Live Time 600.0 seconds Real Time 600.8 seconds Dead Time 0.13 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1.27CM DATA VALIDATED DATE °f ~7-1'8 TIME OC,  % (J jf-: tV UJ ,,rff'j'tlf' 22-/ '-,/* ,4/7

                                                            ,11/}QL"r*.
                                                                                <-__ / _/' V

[103] 7 ZS

Peak Analysis Report 8/15/2018 1: 37: 32 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:

Bl09100AFSFC006GD Peak Analysis Performed on: 8/15/2018 1: 37:32 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 285- 305 300.91 75.23 0.65 1.17E+002 74.77 3.53E+002 2 349- 358 353.28 88.32 0.56 2.80E+001 37.19 1. 40E+002 3 738- 748 743.97 185.99 0.30 2.74E+001 24.16 4.96E+001 4 949- 961 955.25 238.81 0.81 4 .43E+001 27.86 5.67E+001 5 1400- 1415 1408.21 352.05 1. 02 6.30E+001 26.61 3.80E+001 6 2035- 2050 2043.60 510 .90 1.28 5.21E+001 18.75 1 .19E+001 7 2428 - 2443 2436.21 609.05 0.90 7.41E+001 18.54 3.94E+OOO 8 4473- 4486 4479.76 1119 .94 1. 58 2.27E+001 12.26 5.32E+OOO 9 5833- 5853 5843.64 1460.91 0.41 l .28E+002 24. 10 4.88E+OOO 10 7052

• 7067 7059.01 1764.75 1. 23 2.37E+001 11. 22 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

[104]

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Sample

Title:

B109100AFSFC006GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• i
• I * * * * * * * * * * *
• I
• 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1 . 000 1460.82* 10 .66 8.72878E+005 1. 80837E+005 'l? ~~

Eu - 155 0 .345 86.55* 30.70 2.14229E+004 2. 8764 6E+O 04 f:tc., . ~~ ~ 105.31 21.10 Pb-212 1 . 000 238.63* 43.60 3.00439E+004 1. 95047E+004 Bi-214 1. 000 609.32* 45.49 7.70951E+004 2. 14122E+004 1120.29* 14.92 9.61846E+004 5.25722E+004 1764.49* 15.30 1.26257E+005 6.05820E+004 Pb-214 0.438 295.22 18.42 351.93* 35.60 6.35973E+004 2.8734SE+004 Ra-226 1. 000 186.21* 3.64 1.97020E+OOS l .76862E+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

[105]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty

                                                                             ?~t3 K-40       1 . 000      8.728780E+005       1 . 808374E+005 tf,t...:~W Eu-155     0 .345       2.142291E+004       2. 876459E+004 -"

Pb-212 1 . 000 3 .0 04388E+004 1 .95046SE+004 Bi-214 1 . 000 8 .4 30608E+004 1 .884649E+004 Pb-214 0 .438 6.359727E+004 2.873451E+004 Ra-226 1. 000 1 .970200E+005 l.768625E+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

[106]

Interference Corrected Activity Report 8/15/2018 1:37:32 PM Page s

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

Peak Locate Performed on: 8/15/2018 1:37:32 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.23 1.9525E-001 63.82 6 510.90 8.6823E-002 36.00 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 [107]

Nuclide MDA Report 8/15/2018 1 :37:32 PM Page 6

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

Detector Name: 5452A Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC006GD 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.110E+005    l.11E+005    8.729E+005  4.630E+004 Co-60     1173.23      99.85  2.130E+004    l.72E+004   3.001E+003   9.771E+003 1332.49      99.98  l.723E+004                1 .422E+002  7.683E+003 Nb-94       702.65     99.81  1.651E+004    l.60E+OD4    l .397E+D03 7.566E+003 871. 09    99.89  1.603E+004                4.654E+D02   7.257E+003 Ag-108m     433.90     90.50  1.764E+004    1.76E+D04  -2.287E+004   8.220E+003 614.30     89.80  2.727E+004               -l.034E+D04   1.292E+004 722.90     90.80  l.977E+004                4.667E+003   9.118E+003 Cs-134      604.72     97.62  2.574E+004    1.97E+004   2.417E+003   1. 222E+004 795.86     85.46  1.972E+004               -6.315E+OD3   9.009E+003 Cs-137      661.66     85.10  2.554E+004    2.55E+004   3.428E+004   l. 198E+004 Eu-152      121. 78    28.67  6.523E+004    6.52E+004  -2.671E+004   3.149E+004 344.28     26.60  6.578E+004               -3.758E+004   3.108E+004 1408.01      21. 07 8.442E+004                7.760E+004   3.764E+004 Eu-154      123.07     40.40  4.551E+004    4 .55E+004 -3.007E+004   2.196E+004 723.30     20.06  9.120E+004                9.505E+004   4.213E+004 1274.43      34.80  5.205E+004                2.275E+004   2.340E+004
 +       Eu-155       86.55*    30.70  4.692E+004    4.69E+004   2.142E+004   2.243E+004 105.31     21.10  l.003E+005               -l .244E+004  4 .862E+004 Tl-208      583.19     85.00  2.359E+004    2.36E+004   8.273E+003   l.106E+004 Bi-212      72 7. 3 3   6.67  2.672E+005    2.67E+OD5   1 .300E+OD5  l.232E+OOS
 +       Pb-212      238.63*    43.60  2.913E+004    2.91E+004   3.004E+004   1 .365E+004
 +       Bi-214      609.32*    45.49  1.463E+004    l.46E+004   7.710E+004   5.908E+003 1120.29*     14.92  6.535E+004                9.618E+004   2.694E+004 1764.49*     15.30  6.317E+004                1.263E+005   2.438E+004
 +       Pb-214      295.22     18.42  1. 038E+OOS   3.82E+004   2.214E+004   4.951E+004 351. 93

• 35.60 3.821E+004 6.360E+004 1.774E+004

 +       Ra-226      186.21*     3.64  2.775E+005    2.77E+005   1.970E+005   1.290E+005 Ac-228      338.32     11. 27 l. 603E+005   7.22E+004   l.679E+005   7.593E+004 911. 2 0   25.80  7.216E+004               -7.720E+D04   3.308E+004 968.97     15.80  1. 200E+005               3.964E+OD4   5.496E+004 Am-241       59.54     35.90  8.063E+004    8.06E+D04   1 .784E+OD4  3.925E+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

[108]

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

Filename: 6279 Report Generated On 8/16/2018 9:02:01 AM Sample Title B109100AFSFC007GD Sample Description WWTF FLOOR Sample Identification 007 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 2.826E+001 M"2 Sample Taken On 8/16/2018 8:51:00 AM Acquisition Started 8/16/2018 8:51:58 AM 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VAUDATED DATE 9-Z-t'3 TIME O r,30 [109]

                                                     /?,~5;if0~)

Peak Analysis Report 8/16/2018 9:02 : 01 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSFC007GD Peak Analysis Performed on: 8/16/2018 9:02: 00 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area uncert. Counts 1 286- 307 300.56 75.27 1. 09 1.64E+002 62.88 2.20E+002 2 344- 353 348.83 87.33 0.40 -4.38E+OOO 31. 05 1 .04E+002 3 739- 749 744.28 186.19 0.54 2.32E+001 22.58 4.38E+001 4 1174- 1185 1179.85 295.08 0 .44 1.38E+001 16.43 2.12E+001 5 1400- 1413 1406.50 351.74 0.54 4 .32E+001 17.39 1.18E+001 6 2429- 2442 2435.98 609.09 0.51 4 .51E+001 16.91 8.89E+OOO 7 4473- 4486 4479.98 1120.06 0.47 1.40E+001 1 1. 53 7.00E+OOO 8 5834- 5854 5844.85 1461 .26 1. 73 9.08E+001 20.96 5.25E+D00 M First peak in a multiplet region m = Other peak in a multiplet region F = Fi tted singlet Errors quoted at 2. 000 sigma [110]

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Sample

Title:

B109100AFSFC007GD Nuclide Library used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

Nuclide Id Energy Yi eld Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1.000 1460.82* 10 .66 9.85537E+005 2.52945E+005 Eu-155 0 .348 86.55* 30.70 -3.55366E+003 2.52012E+004 105.31 21 .10 Bi-214 0 .748 609.32* 45.49 6.57966E+004 2.63138E+004 1120. 29* 14 .92 9.13065E+004 7.58453E+004 1764.49 15.30 Pb- 214 1 .000 295.22* 18.42 3.00458E+004 3.60736E+004 351.93* 35.60 5.50127E+004 2.39237E+004 Ra-226 1 .000 186.21* 3.64 1.89384E+005 1.88005E+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

[111]

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Nuclide Wt mean wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 9.855371E+005 2. 529445E+005 ~ fte.. - -z..~9-Eu-155 0.348 -3.553658E+003 2.520120E+004 Bi-214 0.748 6.847788E+004 2.497445E+004 Pb-214 1 .000 4.750925E+004 2.002589E+004 Ra-226 1.000 l .893836E+005 1.880048E+005

      ? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
      @ ~ Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at       2. 000 sigma
  **********      U N I D E N T I F I E D           P E A K S     **********

Peak Locate Performed on: 8/16/2018 9:02:00 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.27 2.7400E-001 38.25 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 [112]

Nuclide MDA Report 8/16/2018 9:02:01 AM Page 5

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Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC007GD 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 .853E+005   1.85E+005 9.855E+005   7.795E+004 Co-60      1173.23    99.85  2.305E+004    1.63E+004 -1.903E+004  1.017E+004 1332.49    99.98  1 .625E+004             -2.203E+003  6.661E+003 Nb-94       702.65    99.81  2.085E+004    1.96E+004 1.330E+004   9.440E+003 871. 09   99.89  1 .959E+004             -6.248E+003  8.667E+OD3 Ag-108m     433.90    90.50  2.009E+004    2.01E+004 -l,043E+004  9.261E+003 614.30    89.80  3.195E+004              -1.177E+004  1.497E+004 722.90    90.80  2.621E+004               1.314E+004  1.200E+004 Cs-134      604.72    97.62  2.927E+004    2.3SE+004 1 .325E+004  1.372E+004 795.86    85.46  2.347E+004              -6.307E+003  1.049E+004 Cs-137      661.66    85.10  2.253E+004    2.25E+004 1 .850E+004  1.015E+004 Eu-152      121. 78   28.67  6.774E+004    6.SSE+004 1 .470E+004  3.26SE+004 344.28    26.60  6.548E+004              -1. 794E+003 3.047E+004 1408.01    21. 07 1 .006E+005              1 .069E+004 4.308E+004 Eu-154      123.07    40.40  4.807E+004    4.81E+004 3.467E+004   2.317E+004 723.30    20.06  1 .187E+005              5.765E+004  5.433E+004 1274.43    34.80  5.489E+004               3.329E+004  2.335E+004
 +      Eu-155       86.55*   30.70  4.401E+004    4.40E+004 -3.SS4E+D03  2.091E+004 105.31    21.10  9.683E+004              -4.804E+004  4.680E+D04 Tl-208      583.19    85.00  2.321E+004    2.32E+004 1 .614E+004  l.058E+004 Bi-212      727.33     6.67  3.498E+005    3.SOE+OOS 1 .282E+005  1.598E+OOS Pb-212      238.63    43.60  4.873E+004    4.87E+004 4.420E+004   2.329E+004
 +      Bi-214      609.32*   45.49  2.858E+004    2.86E+OD4 6.580E+004   1.232E+004 1120.29*   14 .92 1.118E+005               9.131E+004  4. 707E+004 1764.49    15.30  1.8SSE+005               5.751E+004  8.098E+004
 +      Pb-214      295.22*   18.42  5.822E+004    2.72E+004 3.00SE+004   2.617E+004 351. 93*  35.60  2.725E+004               5.501E+004  1. 19 OE+004
 +      Ra-226      186.21*    3.64  2.969E+OOS    2.97E+OOS 1.894E+OOS   1. 374E+005 Ac-228      338.32    11.27  1.550E+005    9.35E+004 4.733E+004   7.219E+D04 911.20    25.80  9.352E+004               1.294E+004  4.227E+D04 968.97    15.80  1.513E+OOS               3.763E+004  6.805E+004 Am-241       59.54    35.90  6.292E+004    6.29E+004 -6.306E+003  3.033E+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

[113]

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

Filename: 5452A Report Generated On 8/15/2018 2:57:10 PM Sample Title B109100AFSFC008GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1. 27CM 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 8/15/2018 2:46:00 PM Acquisition Started 8/15/2018 2:47:08 PM Live Time 600. 0 seconds Real Time 601.3 seconds Dead Time 0. 21 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1.27CM [114]

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

Detector Name: 5452A Sample

Title:

B109100AFSFC008GD Peak Analysis Performed on: 8/15/2018 2:57: 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 1 296- 3 06 300.76 75. 19 0 .40 5.58E+001 48.03 2.17E+002 2 1173- 1185 1179.84 294.96 0 .46 3.17E+001 24.02 4.13E+001 3 1398 - 1415 1407.42 35 1 .86 0 .94 5.77E+001 22.90 2.24E+001 4 2428- 2443 2435.84 608.96 1. 46 6.30E+001 20.49 1 .40E +001 5 2640 - 2651 2645.37 661.34 0 .60 l .85E+001 11. 38 5.52E+OOO 6 5830 - 5854 5842.37 1460.59 1. 62 1 .66E+002 28.63 9.46E+OOO 7 7051- 7066 7058.59 1764.65 0 .65 2.61E+001 11. 25 1.86E+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 [115]

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Sample

Title:

B109100AFSFC008GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10 .66 1. 12771E+006 2.18232E+005 Cs-137 1. 000 661.66* 85.10 1. 07070E+004 6 .71 714E+003 Bi-214 0 .705 609.32* 45.49 6.56139E+OD4 2.27344E+004 1120.29 14.92 1764.49* 15.30 1. 39198E+005 6.D92l5E+004 Pb-214 1 . 000 295.22* 18.42 5.65414E+D04 4 .38301E+004 351.93* 35.60 5.81891E+OD4 2.49158E+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

[116]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1 .000 1.127712E+006 2.182323E+OOS Cs-137 1 .000 1 .0 70697E+004 6.717145E+003 Bi-214 0.705 7 .4 60854E+004 2.129963E+004 Pb-214 1 .000 5.778668E+004 2.166059E+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: 8/15/2018 2:57:10 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.19 9.3045E-002 86.03 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 [117]

Nuclide MDA Report 8/15/2018 2:57:10 PM Page 5

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

Detector Name: 5452A Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

Bl09100AFSFC008GD 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 1.590E+005     1.59E+OOS   1.128E+006  7.031E+004 Co-60      1173.23     99.85  2.198E+004     1.58E+004   9.458E+003  l.011E+004 1332.49     99.98  1. 583E+004               -7.920E+003  6.983E+003 Nb-94        702.65    99.81   l.432E+004    l.43E+004  -1.648E+004  6.472E+003 871.09    99.89  1. 800E+004               -1.322E+004  8.243E+003 Ag-108m      433.90    90.50  1.827E+004     1.75E+004   1.768E+004  8.53SE+003 614. 3 0  89.80  2.692E+004                -3.177E+003  1 .274E+004 722.90    90.80   l .754E+004              -9.051E+003  8.005E+003 Cs-134       604.72    97.62  2.543E+004     2.09E+004   1 .199E+004 l .206E+004 795.86    85.46  2.087E+004                 1 .523E+004 9.584E+003
 +      Cs-137       661.66*   85.10   8.672E+003    8.67E+003   1 .071E+004 3.552E+003 Eu-152       121.78    28.67  6.616E+004     6.62E+004  -3.843E+004  3.196E+004 344.28    26.60  6.852E+004                 1.963E+004  3.245E+004 1408.01     21 .07  9.367E+004                7.109E+004  4.227E+004 Eu-154       123.07    40. 40 4.68SE+004     4.69E+004  -2.057E+003  2.263E+004 723.30    20.06   8.230E+004                3.458E+004  3.769E+004 1274.43     34.80  4.844E+004                -2.898E+004  2.160E+004 Eu-155        86.55    30.70  7.969E+004     7.97E+004  -9.917E+003  3.880E+004 105.31    21. 10 1.026E+005                -3.002E+004  4.979E+004 Tl-208       583.19    85.00  2.388E+004     2.39E+004   3.054E+004  l.120E+004 Bi-212       727. 33    6.67  2.365E+005     2.36E+005  -l.313E+005  1. 078E+OOS Pb-212       238.63    43.60  4 .699E+004    4. 70E+004  6.272E+004  2.258E+004
 +      Bi-214       609.32*   45.49  2.498E+004     2.50E+004   6.561E+004  l. 108E+004 1120 .29    14.92  1 .605E+005               -1. 898E+OOS 7.4SOE+004 1764.49*    15.30  5.545E+004                 1. 392E+005 2.052E+004
 +      Pb-214       295.22*   18.42  6.716E+004     3.12E+004   5.654E+004  3.116E+004 351.93*   35.60  3.118E+004                 5.819E+004  1. 423E+004 Ra-226       186.21     3.64  S.399E+OOS     5.40E+OOS   3.332E+OOS  2.602E+OOS Ac-228       338.32    11. 27 l .730E+005    7.30E+004   l.554E+OOS  8.228E+004 911.20    25.80  7.297E+004                 1.221E+004  3.348E+004 968.97    15.80  1. 3 OSE+OOS               9.599E+004  6.020E+004 Am-241        59.54    35.90  9.351E+004     9.3SE+004  -6.369E+004  4.569E+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

[118]

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

Filename: 5452A Report Generated On 8/15/2018 3:13:45 PM Sample Title B109100AFSFC009GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/15/2018 3:02: 00 PM Acquisition Started 8/15/2018 3:03:42 PM Live Time 600.0 seconds Real Time 601 .3 seconds Dead Time 0 .22 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1. 27CM DATA VALIDATED DATE 9-z-te TIME~o~ g, ~:t,i.~;]~ [119]

Peak Analysis Report 8/15/2018 3:13:45 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:

B109100AFSFC009GD Peak Analysis Performed on: 8/15/2018 3:13:45 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 1 949- 961 954.65 238.66 0. 48 3.26E+001 28.27 6.34E+001 2 1177- 1189 1182.27 295.57 0.36 3.98E+001 22.73 3.22E+001 3 1211- 1221 1215.89 303.97 0.79 8.85E+OOO 17.18 2.72E+001 4 1402- 1414 1408.25 352.06 0.63 6.26E+001 24 .53 3.34E+001 5 2327- 2338 2332.31 583.08 0.43 2.35E+001 16. 11 1. 65E+001 6 2428- 2444 2436.02 609. 00 1. 26 5.67E+001 20.07 1.33E+001 7 5831- 5854 5843.44 146 0 .86 1. 31 1. 79E+002 30.90 1.49E+001 8 7051- 7066 7058.53 1764.63 0 .56 2.90E+001 11.84 1.97E+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 [120]

Interference Corrected Activity Report 8/15/2018 3:13:45 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:

B109100AFSFC009GD 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 1.21991E+006 2.35684E+005 Tl-208 1.000 583.19* 85.00 1.28037E+004 8.91782E+003 Pb-212 1.000 238.63* 43.60 2.21081E+004 1.94960E+004 Bi-214 0.705 609.32* 45.49 5.90404E+004 2.20668E+004 1120.29 14.92 1764.49* 15.30 l.54582E+OOS 6.42243E+004 Pb-214 1.000 295.22* 18.42 7 .11291E+004 4.21854E+004 351.93* 35.60 6.31955E+004 2.67567E+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

[121]

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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 1.219907E+006 2.356844E+005 Tl-208 1 .000 1.280367E+004 8.917818E+003 Pb-212 1.000 2.210806E+004 1.949604E+004 Bi-214 0.705 6.912851E+004 2.086931E+004 Pb-214 1. 000 6.547152E+004 2.259509E+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: 8/15/2018 3:13:45 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 3 303.97 1.4745E-002 194 .16 Tol. Pb-214 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 [122]

Nuclide MDA Report 8/15/2018 3:13:45 PM Page 5

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

Detector Name: 5452A Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC009GD 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  1.916E+005    1 .92E+005  1.220E+006  8.658E+004 Co-60     1173.23      99.85  2.130E+004    2.03E+004   1.236E+004  9.771E+003 1332.49      99.98  2.027E+004                1.222E+004  9.203E+003 Nb-94       702.65     99.8 1 1.594E+004    1 .59E+004 -1.970E+004  7.284E+003 871.09     99.89  1.758E+004                2.816E+003  8.034E+003 Ag-108m     433.90     90.50  l.725E+004    1 .72E+004 -l.454E+004  8.025E+003 614.30     89.80  2.532E+004               -1.033E+004  1.194E+D04 722.90     90.80  1. 879E+004               2.421E+003  8.630E+003 Cs-134      604.72     97.62  2.500E+004    2.40E+004  -4 .155E+003 1.185E+004 795.86     85 .46 2.396E+004               -1.614E+003  1.113E+004 Cs-137      661.66     85.10  2.397E+004    2.40E+004   3.145E+003  1.120E+004 Eu-152      121.78     28.67  6.799E+004    6.48E+004  -1.977E+004  3.287E+004 344.28     26.60  6.484E+004               -8.084E+004  3.061E+D04 1408.01      21.07  6.573E+004                2.316E+004  2.830E+004 Eu-154      123. 07    40 .40 4.919E+004    4.92E+004   4.512E+004  2.380E+004 723. 3 0   20.06  8.324E+004               -3.422E+004  3.815E+D04 1274.43      34.80  5.458E+004                5.808E+004  2.467E+004 Eu-155       86.55     30.70  7.810E+004    7.81E+004   6.926E+004  3.801E+004 105. 31    21. 10 9.672E+004               -5.673E+004  4.685E+004
 +       Tl-208      583.19*    85 .00 l.302E+004    l.30E+004   1 .280E+004 5.771E+003 Bi-212      727.33      6.67  2.592E+005    2.59E+005   1.351E+005  1 .192E+005
 +       Pb-212      238.63*    43.60  3.067E+004    3.07E+004   2.211E+004  1.442E+004
 +       Bi-214      609.32*    45.49  2.554E+004    2.55E+OD4   5.904E+004  1.136E+004 1120.29      14.92  1 .538E+005               1.861E+OOS  7.116E+004 1764.49*     15.30  5.728E+004                1.546E+OOS  2.144E+004
 +       Pb-214      295.22*    18.42  6.042E+004    3.39E+004   7.113E+004  2.779E+004 351. 93

• 35.60 3.387E+004 6.320E+004 1. 557E+004 Ra-226 186.21 3.64 5.311E+OOS 5.31E+005 4. 625E+OOS 2.558E+005 Ac-228 338.32 11. 27 l.561E+005 7.98E+004 1.llOE+OOS 7.381E+004 911.20 25.80 7.979E+004 3.043E+004 3.689E+004 968.97 15.80 1. 200E+005 -1. 027E+004 5.496E+004 Am-241 59.54 35.90 6.778E+004 6.78E+004 1. 472E+004 3.282E+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

[123]

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

Filename: 6279 Report Generated On 8/ l 6/.2(Jl 9 9: 18:04 AM Sample Title B109100AFSFC010GD Sample Description WWTF FLOOR Sample Identification 010 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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

                                     -z, y3 Sample Size                        _.2.....-&2-6-E + 0 01 MA2 Sample Taken on                    8/16/2018              9:08:00 AM Acquisition Started                8/16/2018              9:08:03 AM Live Time                                      600.0 seconds Real Time                                      600.8 seconds Dead Time                               0 . 13 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 9-Z-/~ TIME os~s= [124] (h~j~

Peak Analysis Report 8/16/2018 9:18:05 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSFC010GD Peak Analysis Performed on: 8/16/2018 9:18:04 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- 305 300.64 75.29 0 .81 5.56E+001 39.65 1.49E+002 2 651- 660 655.87 164.09 0 .51 9.57E-001 2 0 .25 4.50E+001 3 1401 - 1412 1406.83 351.82 0 .69 3.05E+001 18.13 2.05E+001 4 2427- 2441 2435.54 608.98 0 .78 4.03E+001 15.42 6.72E+OOO 5 5837- 5853 5844.61 1 461. 20 1. 50 7.06E+001 20.29 1.04E+001 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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Sample

Title:

B109100AFSFC010GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENT IFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 1. 000 1460.82* 10 .66 7.67109E+005 2.36467E+OOS Bi-214 0 .461 609.32* 45.49 5.87381E+004 2.39274E+004 1120.29 14. 92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 3.87972E+004 2.39430E+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

[126]

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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 7.671092E+005 2.364670E+005 Bi-214 0.461 5.873808E+004 2.392738E+004 Pb-214 0.432 3.879716E+004 2.394300E+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: 8/16/2018 9:18:04 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 9.2748E-002 71.25 2 164.09 1. 5942E-0 03 2117.23 M First peak in a multiplet region m - Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [127]

Nuclide MDA Report 8/16/2018 9:18:05 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC010GD 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  2.323E+OOS     2.32E+OOS 7.671E+OOS    1. 014E+OOS Co-60      1173.23     99.85  2.605E+004     1.89E+004 -7.722E+002   l.167E+004 1332.49     99.98  1. 885E+004               -4.605E+004  7.962E+003 Nb-94        702.65    99. 81 2.203E+004     2.12E+004 -3.092E+003   1 .003E+004 871.09    99.89  2.124E+004                -2.516E+003  9.494E+003 Ag - 108m    433.90    90.50  1.887E+004     1.89E+004 -1.121E+004   8.649E+003 614. 3 0  89.80  2.94SE+004                -2.118E+004  1.372E+004 722.90    90.80  2.299E+004                 2.854E+003  1.039E+004 Cs - 134     604.72    97.62  2.816E+004     2.35E+004 4 .148E+003   1.317E+004 795.86    85.46  2.347E+004                -3.221E+003  1.049E+004 Cs-137       661. 66   85.10  l.981E+004     1 .9BE+004 -3.798E+003  8.788E+003 Eu-152       121 .78   28.67  7.363E+004     6.4SE+004 2.595E+003    3.560E+004 344.28    26.60  6.447E+004                -7.409E+004  2.997E+004 1408. 01    21.07  1. 139E+005                8.552E+004  4.974E+004 Eu-154       123. 07   40. 40 S.305E+004     5.30E+004 1.904E+004    2.566E+004 723. 3 0  20.06  1 .041E+OOS                1. 292E+004 4.705E+004 1274 .43    34.80  6.272E+004                 4.539E+004  2.727E+004 Eu-155        86.55    30.70  7.482E+004     7.48E+004 1. S38E+003   3.631E+004 105. 31   21.10  9.601E+004                 7.540E+004  4.639E+004 Tl-208       583.19    85.00  2.649E+004     2.65E+004 2.803E+003    1.222E+004 Bi-212       727. 3 3   6.67  3.280E+005     3.28E+005 2.030E+OOS    1.489E+OOS Pb-212       238.63    43.60  4 . 769E+004   4.77E+004 3.36SE+004    2.277E+004
 +       Bi-214       609.32*   45.49  2.493E+004     2.49E+004 S.874E+004    1 .049E+004 1120.29     14 .92 1. 92 OE+OOS               1 .132E+004 8.717E+004 1764.49     15.30  2.091E+005                 3.698E+004  9.277E+004
 +       Pb-214       295.22    18.42  1. 060E+O OS   3.35E+004 -6.876E+004   S.OOSE+004 351.93*   35.60  3.353E+004                 3.880E+004  1 .504E+004 Ra-226       186.21     3.64  5.081E+005     5.08E+005 4.654E+005    2.430E+OOS Ac-228       338.32    11.27  1 .SSOE+OOS    9.35E+004 -4.845E+004   7.219E+004 911. 2 0  25.80  9.352E+004                -6.795E+004  4.227E+004 968.97    15.80  l.488E+005                 2.999E+004  6.678E+004 Am-241        59.54    35.90  6.242E+004     6.24E+004 - 4.606E+004  3.009E+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

[128]

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

Filename: 5452A Report Generated On 8/15/2018 1:24:50 PM Sample Title B109100AFSFC011GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 M"2 Samp le Taken On 8/15/2018 1:14:00 PM Acquisition Started 8/15/2018 1:14:48 PM Live Time 600.0 seconds Real Time 600.7 seconds Dead Time 0 . 12 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1 . 27CM [129]

Peak Analysis Report 8/15/2018 1:24:50 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:

Bl09100AFSFC011GD Peak Analysis Performed on: 8/15/2018 1:24:50 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 1 285- 306 290.55 72.64 0.60 1.38E+002 7 1 .34 3.02E+002 2 738- 748 743.47 185.87 0.63 2.0lE+OOl 23.74 5.09E+001 3 950- 963 955.11 238.78 0.84 4 .97E+001 28.70 5.63E+001 4 1400- 1416 1408. 30 352.07 0.58 7.57E+001 26.33 3.13E+001 5 2428- 2445 2436.56 609. 14 1. 67 7.25E+001 23.69 2.05E+001 6 2638- 2653 2645.28 66 1. 32 0.37 3.48E+001 17.73 1.42E+001 7 4474- 4487 4480.18 1120.05 0.86 1. 90E+001 12.38 7.00E+OOO 8 5833- 5854 5843.79 1460.95 1. 50 1 .36E+002 26.31 1.02E+001 9 7052- 7067 7059.03 1764.76 0 .77 2.68E+001 1 1 .64 2.17E+OOO M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [130]

Interference Corrected Activity Report 8/15/2018 1:24:50 PM Page 3

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

Sample

Title:

B109100AFSFC011GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB 5 * * * * * * * * * * * * * * * * *

• I IDENTIFIED NUCLIDES
• t a, I * * * * * * * * * * * * * * *
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1. 000 1460.82* 10 .66 9.25297E+005 1.96417E+005 Cs-137 1. 000 661.66* 85. 10 2.01814E+004 l.05534E+004 Pb-212 1. 000 238.63* 43.60 3.37166E+004 2.02074E+004 Bi-214 1. 000 609.32* 45.49 7.54807E+004 2.62763E+004 1120.29* 14.92 8.05866E+004 5.28951E+004 1764.49* 15.30 1.42849E+OOS 6.30523E+004 Pb-214 0.438 295.22 18.42 351.93* 35.60 7.64214E+004 2.92667E+004 Ra-226 1. 000 186.21* 3.64 1. 44994E+O OS l.72502E+OOS

          *=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

[131]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 9.252967E+005 1.964172E+005 Cs-137 1.000 2 .018139E+004 1.055337E+004 Pb-212 1.000 3.371663E+004 2.020741E+004 Bi-214 1.000 8.460453E+004 2.204717E+004 Pb-214 0.438 7.642136E+004 2.926674E+004 Ra-226 1.000 l.449945E+005 l.725016E+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

[132]

Interference Corrected Activity Report 8/15/2018 1 :24:50 PM Page 5

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

Peak Locate Performed on: 8/15/2018 1 :24:50 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 72. 64 2.2920E-001 51 .88 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 [133]

Nuclide MDA Report 8/15/2018 1:24:50 PM Page 6

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

Detector Name: 5452A Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC011GD 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 ) t- K-40 1460.82* 10. 66 1.551E+OOS l.55E+005 9.253E+OOS 6.835E+004 Co-60 1173.23 99.85 2.082E+004 1.55E+004 2.021E+003 9.535E+003 1332.49 99.98 1.546E+004 6.648E+003 6.797E+003 Nb-94 702.65 99. 81 1. 365E+004 1.37E+004 -1.114E+004 6.140E+003 871.09 99.89 1. 716E+004 8.532E+003 7.820E+003 Ag-108m 433.90 90.50 1. 887E+004 1 .75E+004 7.380E+003 8.839E+003 614.30 89.80 2.704E+004 -1.980E+004 1.280E+004 722.90 90.80 1. 754E+004 9.120E+003 8.005E+003 Cs-134 604.72 97.62 2.543E+004 2.00E+004 -1.162E+004 1.206E+004 795.86 85.46 1. 995E+004 -l.368E+004 9.127E+003

 +      Cs-137       661. 66

• 85. 10 l. 417E+004 l.42E+004 2.018E+004 6.303E+003 Eu-152 121. 7 8 28.67 6.487E+004 6.49E+004 -9.895E+004 3.132E+004 344.28 26.60 6.516E+004 1 .089E+004 3.077E+004 1408.01 21. 07 7.386E+004 5.736E+004 3.236E+004 Eu-154 123.07 40.40 4.726E+004 4 .73E+004 7.574E+003 2.284E+004 723.30 20.06 7.942E+004 6.083E+004 3.624E+004 1274.43 34.80 4.749E+004 l.307E+004 2.113E+004 Eu-155 86.55 30.70 8.520E+004 8.52E+004 l.159E+005 4.156E+004 105.31 21 .10 1.021E+OOS 3.470E+004 4.952E+004 Tl-208 583.19 85.00 2.359E+004 2.36E+004 1.368E+004 1.106E+004 Bi-212 727. 33 6.67 2.006E+005 2.01E+005 -l.239E+005 8.983E+004

 +      Pb-212       238.63*    43.60  2.971E+004    2.97E+004   3.372E+004   1.394E+004
 +      Bi-214       609.32*    45.49  3.101E+004    3.10E+004   7.548E+004   1.410E+004 1120.29*     14 .92 7.279E+004                8.059E+004   3.065E+004 1764.49*     15.30  6.100E+004                l .428E+005  2.330E+004
 +      Pb-214       295.22     18.42  1.035E+005    3.56E+004   3.093E+004   4.933E+004 351.93*    35.60  3.556E+004                7.642E+004   1 .642E+004
 +      Ra-226       186.21*     3.64  2.798E+005    2.80E+005   1.4SOE+005   1. 3 OlE+OOS Ac-228       338.32     11. 27 l.433E+005    7.14E+004  -8.255E+004   6.744E+004 911.20     25.80  7.135E+004                l.459E+004   3.267E+004 968.97     15.80  1 .267E+005               6.163E+004   5.829E+004 Am-241        59.54     35.90  7.261E+004    7.26E+004  -8.926E+003   3.524E+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

[134]

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

Filename: 5452A Report Generated On 8/15/2018 1: 07: 52 PM Sample Title B109100AFSFC012GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1. 27CM 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 8/15/2018 12:57:00 PM Acquisition Started 8/15/2018 12:57:50 PM Live Time 600. 0 seconds Real Time 600.4 seconds Dead Time 0 . 06 % Energy Calibration used Done On 3/15/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1.27CM DATA VALIDATED DATE 9 . .z--tB TIME 0 ' 7 5 " ~ [135] £,,~"111i~Z ~ *.

Peak Analysis Report 8/15/2018 1:07:52 PM Page 2

• • • • • P E A K A N A L Y S I S REPORT *****

Detector Name: 5452A Sample

Title:

B109100AFSFC012GD Peak Analysis Performed on: 8/15/2018 1:07:51 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 1 297- 311 301.10 75.28 0. 72 S.98E+001 54.39 2.34E+002 2 1175- 1186 1181.05 295.26 0.29 2.6SE+001 22.64 4.05E+001 3 1401- 1413 1407.14 35 1 .78 1. 01 4.57E+001 23.97 3.73E+001 4 2327- 2338 2332. 19 583.05 0.45 2.03E+001 14.91 1. 3 7E+001 5 2429- 2445 2436.97 609.24 0.72 7.19E+001 21. 38 1.31E+001 6 5832- 5855 5843.64 1460.91 1. 01 1.44E+002 24 .93 2.89E+OOO M First peak in a multiplet region m Other peak in a multiplet region F == Fitted singlet Errors quoted at 2 . 000 sigma [136]

Interference Corrected Activity Report 8/15/2018 1 : 0 7: 52 PM Page 3

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

Sample

Title:

B109100AFSFC0l2GD 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 9.81847E+OOS l .90071E+OOS Tl-208 1.000 583.19* 85.00 l.10455E+004 8.23994E+003 Bi-214 0.439 609.32* 45.49 7.48049E+004 2.40081E+004 1120.29 14.92 1764.49 15.30 Pb-214 1.000 295.22* 18 .42 4. 72888E+004 4.11411E+004 351.93* 35.60 4.60940E+004 2.52940E+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

[137]

Interference Corrected Activity Report 8/15/2018 1:07:52 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 9.818475E+005 1.900712E+005 Tl-208 1. 000 1 .1 04548E+004 8.239941E+003 Bi-214 0.439 7.480487E+004 2.400813E+004 Pb-214 1.000 4 .642176E+004 2.154738E+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: 8/15/2018 1:07:51 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 75.28 9.9728E-002 90.90 M = First peak in a multiplet region m -::; Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [138]

Nuclide MDA Report 8/15/2018 1:07:52 PM Page 5

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

Detector Name: 5452A Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC012GD 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   9.382E+004    9.38E+004     9.818E+005      3.769E+004 Co-60      1173.23     99.85   2.010E+004    l.47E+004     8.775E+003      9.171E+003 1332.49     99.98   l.468E+004                  l .829E+003     6.408E+003 Nb-94        702.65    99.81   1.495E+004    1.50E+004     7.319E+003      6.788E+003 871.09    99.89   1.737E+004                  1 .896E+003     7.928E+003 Ag-108m      433.90    90.50   l.601E+004    l.60E+004    -l .020E+004     7.409E+003 614. 3 0  89.80   2.704E+004                 -4.057E+003      l. 280E+004 722.90    90.80   1.710E+004                  8.659E+003      7.786E+003 Cs-134       604.72    97.62   2.685E+004    l.82E+004    -1.187E+004      1. 277E+004 795.86    85 . 46 1.823E+004                  7.519E+003      8.267E+003 Cs-137       661. 66   85.10   2.263E+004    2.26E+004     2.057E+004      l.053E+004 Eu-152       121. 78   28.67   7.329E+004    6.32E+004     1.721E+004      3.553E+004 344.28    26.60   6.324E+004                 -1.105E+005      2.981E+004 1408. 01    21. 07  7.756E+004                  4.062E+004      3.421E+004 Eu-154       123. 07   40.40   5.231E+004    5.23E+004    -4.067E+003      2.536E+004 723. 3 0  20.06   7.843E+004                  4 .006E+004     3.575E+004 1274.43     34.80   5.620E+004                  3.243E+004      2.548E+004 Eu-155        86.55    30.70   8.059E+004    8.06E+004     1.854E+004      3.925E+004 105. 31   21. 10  9.957E+004                  1.29DE+004      4 .827E+004
 +       Tl-208       583.19*   85.00   1. 214E+004   1.21E+004     l.105E+004      5.333E+003 Bi-212       727. 33    6.67   2.482E+005    2.48E+005     5.078E+004      l.136E+005 Pb-212       238.63    43.60   4.967E+004    4.97E+004     l. 930E+004     2.392E+004
 +       Bi-214       609.32*   45.49   2.513E+004    2.51E+004     7.480E+004      l .116E+004 1120.29     14.92   1. 565E+OOS                 l. 960E+OOS     7.252E+004 1764.49     15.30   1.279E+005                  l. 118E+005     5.676E+004
 +       Pb-214       295.22*   18.42   6.409E+004    3.56E+004     4.729E+004      2.963E+004 351.93*   35.60   3.560E+004                  4.609E+004      l .644E+004 Ra-226       186.21     3.64   5.155E+005    5.16E+005     l.531E+005      2.480E+005 Ac-228       338.32    11 .27  l. 665E+005   7.30E+004     6.600E+004      7.900E+004 911. 20   25.80   7.297E+004                 -2.564E+003      3.348E+004 968.97    15.80   1. 330E+005                 1.071E+005      6.145E+004 Am-241        59.54    35.90   6.879E+004    6.88E+004    -1.626E+004      3.333E+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

[139]

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

Filename: 6279 Report Generated On 8/14/2018 1:34:45 PM Sample Title Bl09100AFSFC013GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3MWWTF1.27CM 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 8/14/2018 1: 24:00 PM Acquisition Started 8/14/2018 1:24:44 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 7/31/2018 Efficiency ID 3MWWTF1, 27CM DATA VALIDATI:D DATE 0,--~~f 8 Tl ME to eo'"'-- , . f;, v:}fbB;nJ; ( ~ [140]

Peak Analysis Report 8/14/2018 1 :34:45 PM Page 2

• • • • • P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B109100AFSFC013GD Peak Analysis Performed on: 8/14/2018 1:34:45 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- 305 300.26 75.19 0.64 5.0lE+OOl 43.56 1.78E+002 2 1175- 1186 1180.09 295.14 0.33 7.44E+OOO 17.79 2.86E+001 3 1400- 1412 1406.58 351. 76 0.47 1.58E+001 19.25 2.93E+001 4 2431- 2442 2436.38 609.19 0.69 3.37E+001 1 4 .18 6.30E+OOO 5 4684- 4700 4692.67 1173.23 0.65 5.26E+001 16.40 4.45E+OOO 6 5324- 5338 5330.08 1332.58 0.63 4.39E+001 14.45 3.07E+OOO 7 5835- 5853 5843.36 1460.89 0.74 7.14E+001 18.00 2.62E+OOO M = First peak in a multiplet region m .... Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [141]

Interference Corrected Activity Report 8/14/2018 1:34:45 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:

B109100AFSFC013GD 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 7.73921E+005 2.06383E+005 Co-60 1 .000 1173.23* 99.85 5.26305E+004 1 .69596E+004 1332.49* 99.98 4.74735E+004 1 .60708E+004 Bi-214 0.461 609.32* 45.49 4.90889E+004 2.14885E+004 1120.29 14 .92 1764.49 15 .30 Pb-214 1 .000 295.22* 18.42 1.61390E+004 3.86822E+004 351.93* 35.60 2.00103E+004 2.46429E+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

[142]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1.000 7.739208E+005 2.063829E+OOS Co-60 1. 000 4.991329E+004 l .166532E+004 Bi-214 0.461 4.908885E+004 2.148852E+004 Pb-214 1.000 1.889268E+004 2.078371E+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: 8/14/2018 1:34:45 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 75.19 8.3556E-002 86.89 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 [143]

Nuclide MDA Report 8/14/2018 1:34:45 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3MWWTF1.27CM Sample

Title:

B109100AFSFC013GD 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 .398E+005   1.40E+OOS   7.739E+OOS  5.52SE+004
 +      Co-60      1173.23*    99.85  1 .535E+004   1.31E+004   5.263E+004  6.321E+003 1332.49*    99.98  1 .315E+004               4.747E+004  5.111E+003 Nb-94        702.65    99. 81 1 .957E+004   1.96E+004   5.526E+003  8.798E+003 871 .09   99.89  2.345E+004                1.944E+004  1 .060E+004 Ag-108m      433.90    90.50  1.905E+004    1 .91E+004 -2.899E+003  8.742E+003 614. 3 0  89.80  3.006E+004               -8.105E+003  1. 402E+004 722.90    90.80  2.296E+004                2.850E+003  1 .03BE+004 Cs-134       604.72    97.62  2.716E+004    2.5SE+004   1.530E+004  1.267E+004 795.86    85.46  2.551E+004               -8.468E+003  1.151E+004 Cs-137       661.66    85.10  2.792E+004    2.79E+004   1 .605E+004 1.285E+004 Eu-152       121 .78   28.67  7.166E+004    7.16E+004   5.594E+004  3.462E+004 344.28    26.60  7.156E+004                8.951E+003  3.351E+004 1408.01     21.07  9.681E+004                5.871E+004  4.118E+004 Eu-154       123.07    40 .40 5.122E+004    5.12E+004   1 .950E+004 2.47SE+004 723.30    20.06  1.055E+005                3.884E+004  4 .776E+004 1274.43     34.80  5.481E+004               -l.284E+004  2.332E+004 Eu-155        86.55    30.70  7.781E+004    7.78E+004   1.085E+005  3.781E+004 105. 31   21.10  9.061E+004               -S.465E+004  4.370E+004 Tl-208       583.19    85.00  2.910E+004    2.91E+004   3.057E+004  l .353E+004 Bi-212       727.33     6.67  3.090E+005    3.09E+005   3.502E+004  1 .394E+OOS Pb-212       238.63    43.60  4.777E+004    4 .78E+004  1.460E+004  2.281E+004
 +      Bi-214       609.32*   45.49  2.347E+004    2.35E+004   4 .909E+004 9.764E+003 1120. 29    14.92  1.917E+005                5.887E+004  8.70SE+004 1764.49     15.30  1.514E+005                8.690E+004  6.393E+004
 +      Pb-214       295.22*   18.42  6.630E+004    4.01E+004   1.614E+004  3.022E+004 351.93*   35.60  4.010E+004                2.001E+004  1. 833E+O 04 Ra-226       186. 21    3.64  5.162E+005    5.16E+OOS   1 .674E+OOS 2.470E+OOS Ac-228       338.32    11 .27 l.689E+005    1.16E+005   1 .199E+005 7.918E+004 911. 20   25.80  1.157E+005                3.597E+004  5.339E+004 968.97    15 .80 1.806E+005                1.118E+005  B.271E+004 Am-241        59.54    35.90  6.536E+004    6.54E+004   5.418E+002  3.156E+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

[144]

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

Filename: 6279 Report Generated On B/14/2018 2: 50:02 PM Sample Title B109100AFSFC014GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3MWWTF1 .27CM 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 8/14/2018 2: 39: 00 PM Acquisition Started B/14/2018 2:40:00 PM Live Time 600.0 seconds Real Time 600.9 seconds Dead Time 0.16 % Energy Calibration used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED oATE cz-z-te TIME m6 ~ ' [145] rZ VV/85(e,j ~~

Peak Analysis Report 8/14/2018 2: 50: 02 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:

B109100AFSFC014GD Peak Analysis Performed on: 8/14/2018 2:50:01 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 321 300.18 75.17 0 .76 6.43E+001 73.83 2. 99E+002 2 947- 959 953.28 238. 44 0 .38 2.09E+001 24. 14 4. 71E+001 3 1400- 1413 1406.86 351. 82 0 .66 4 .54E+001 20.75 2. 26E+001 4 2429- 2441 2435.43 608.95 0.31 3.29E+001 14. 81 8.12E+OOO 5 5833- 5851 5842.50 1460.67 0.94 7. 0lE+OOl 1 8.69 4.89E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [146]

Interf erence Corrected Activity Report 8/14/2018 2:5 0 :02 PM Page 3

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

Sample

Title:

B109100AFSFC014GD 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 7.60049E+005 2.13097E+OD5 Pb-212 1.000 238.63* 43.60 1.66061E+004 1 .93700E+004 Bi-214 0.461 609.32* 45.49 4.78880E+004 2.23234E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 5.76519E+004 2.77424E+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

[147]

Interference Corrected Ac tivity Report 8/14/2018 2:50:02 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1.000 7.600493E+OOS 2.130971E+OOS Pb-212 1.000 1 .66060BE+004 1 .937003E+004 Bi-214 0.461 4 .78879SE+004 2.232336E+004 Pb-214 0.432 S.765191E+004 2.774235E+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: 8/14/2018 2: SO: 01 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No . (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.17 l.0724E-001 114.75 M ,,. First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [148]

Nuclide MDA Report 8/14/2018 2:50:02 PM Page 5

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Detector Name: 6279 Sample Geometry: 3MWWTF1.27CM Sample

Title:

B109100AFSFC014GD 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  1.773E+005    1.77E+005   7.600E+005   7.400E+004 Co-60      1173.23      99.85  2.302E+004    2.17E+004   4 .032E+003  1.016E+004 1332.49      99.98  2.174E+004               -1.351E+003   9.407E+003 Nb-94        702.65     99.81  1.989E+004    1.99E+004   2.157E+003   8.959E+003 871.09     99.89  2.236E+004                1 .102E+004  1.006E+004 Ag-l08m      433.90     90.50  2.229E+004    2.23E+004   1 .695E+004  1.036E+004 614.30     89.80  3.027E+004               -1 .712E+004  l.413E+004 722.90     90.80  2.587E+004                4.510E+003   1.183E+004 Cs-134       604.72     97.62  2.657E+004    2.21E+004   1.628E+004   1.237E+004 795.86     85.46  2.208E+004                7.920E+003   9.796E+003 Cs-137       661.66     85.10  2.763E+004    2.76E+004   2.572E+004   1.270E+004 Eu-152       121.78     28.67  6.724E+004    6.59E+004   5.642E+003   3.241E+004 344.28     26.60  6.589E+004               -1. 322E+O 05 3.068E+004 1408. 01     21.07  8.01SE+004                3.241E+003   3.285E+004 Eu-154       123.07     40.40  4.694E+004    4 .69E+004 -3.288E+004   2.261E+004 723.30     20.06  1.157E+005               -2.989E+004   5.288E+004 1274.43      34.80  6.783E+004                3.014E+004   2.983E+004 Eu-155        86.55     30.70  7.647E+004    7.65E+004   4.464E+004   3.714E+004 105.31     21. 10 9.251E+004               -5.330E+004   4.465E+004 Tl-208       583.19     85.00  2.541E+004    2.54E+004   2.942E+004   1.168E+004 Bi-212       727.33      6.67  3.617E+005    3.62E+005   9.894E+004   1. 6 58E+OOS
 +      Pb-212       238.63*    43.60  3.136E+004    3.14E+004   1.661E+004   l.460E+004
 +      Bi-214       609.32*    45.49  2.639E+004    2.64E+004   4 .789E+004  l .122E+004 1120.29      14.92  1 .722E+OOS               7.002E+004   7.726E+004 1764.49      15.30  1.576E+005                9.559E+004   6.705E+004
 +      Pb-214       295.22     18.42  9.506E+004    3.64E+004  -5.188E+004   4.459E+004 351. 93

• 35.60 3.643E+004 5.765E+004 1.649E+004 Ra-226 186.21 3.64 4.876E+005 4.88E+005 8.169E+002 2.327E+OOS Ac-228 338.32 11.27 1. 700E+005 9.75E+004 8.554E+004 7.970E+004 911.20 25.80 9.751E+004 3.614E+004 4.427E+004 968.97 15.80 1. 460E+005 -4.520E+004 6.539E+004 Am-241 59.54 35.90 6.653E+004 6.65E+004 5.472E+004 3.214E+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

[149]

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

Filename: 627 9 Report Generated On 8/21/2018 8: 11 :49 AM Sample Title Bl09100AFSFC015GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/21/2018 8:01:00 AM Acquisition Started 8/21/2018 8:01:47 AM Live Time 600. 0 seconds Real Time 600.8 seconds Dead Time 0.13 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED [150] DATE 0,-2-1 '& TIME /Q/D fl. /VI e ss ~~ d/7

                                                                             ¥

Peak Analysis Report 8/21/2018 8: 11 :49 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:

B109100AFSFC015GD Peak Analysis Performed on: 8/21/2018 8:11:48 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 1 183- 193 187.76 47.07 0.43 1.lOE+OOl 22.73 4.90E+001 2 287- 305 300.84 75.34 1.28 1 .21E+002 56.17 1.97E+002 3 949- 961 954. 7 0 238.79 0.91 3.09E+001 21. 50 3.21E+001 4 1401- 1413 1407.38 351.96 0.62 2.99E+001 18.51 1.81E+001 5 2430- 2442 2436.12 609.13 0.54 2.93E+001 13.83 6.75E+OOO 6 5835- 5855 5844.33 1461 . 13 0.42 9.60E+001 19.60 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 [151]

Interference Corrected Activity Report 8/21/2018 8 '. 1 1 :49 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:

Bl09100AFSFC015GD 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 1.04101E+006 2.30924E+005 Pb-212 1.000 238.63* 43.60 2.46033E+004 l. 75625E+004 Bi-214 0.461 609.32* 45.49 4.26038E+004 2.07866E+004 1120.29 14.92 1764.49 15.30 Pb-214 0 .432 295.22 18.42 351.93* 35.60 3.79977E+004 2.42047E+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

[152]

Interference Corrected Activity Report 8/21/2018 8:1 1 :49 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 1 .000 1 .041009E+006 2.309238E+OOS Pb-212 1 .000 2.460334E+004 1 .756248E+004 Bi-214 0.461 4.260378E+004 2.078661E+004 Pb-214 0.432 3.799767E+004 2.420473E+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: 8/21/2018 8:1 1: 48 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 47.07 1. 8347E-002 206.50 2 75.34 2.0143E- 001 46.48 M = First peak in a multiplet region m "' Other peak in a multiplet region F

         -  Fitted singlet Errors quoted at       2 . 000 sigma

[153]

Nucl ide MDA Report 8/21/2018 8: 11 :49 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC015GD 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  2.934E+004    2.93E+004   1.041E+D06   O.OOOE+OOO Co-60      1173.23     99.85  2.554E+004    1.88E+004   6.593E+003   1.141E+004 1332.49     99.98  1. 883E+004              -2.378E+004   7.951E+003 Nb-94       702.65     99.81  2.021E+004    1.91E+004   6.732E+003   9.118E+003 871.09     99.89  1.912E+004                8.395E+003   8.43SE+003 Ag-108m     433.90     90.50  1.946E+004    1.95E+004  -9.383E+003   8.948E+003 614.30     89.80  2.830E+OD4               -1.904E+003   1. 315E+004 722.90     90.80  2.525E+004                2.040E+004   1.152E+004 Cs-134      604.72     97.62  2.534E+OD4    2.11E+004   2.374E+004   1.176E+004 795.86     85.46  2.112E+004               -7.811E+003   9.318E+003 Cs-137      661.66     85. 10 2.355E+OD4    2.36E+004   9.466E+003   1.066E+004 Eu-152      121. 78    28.67  6.602E+004    6.18E+004  -2.008E+004   3.180E+004 344.28     26.60  6.179E+004               -l.597E+003   2.863E+004 1408 .01    21.07  1.074E+005                7.473E+004   4.646E+004 Eu-154      123.07     40. 40 4. 781E+004   4 .78E+004  4.147E+004   2.304E+004 723.30     20.06  1.129E+005                6.169E+004   5.147E+004 1274.43     34.80  6.615E+004               -3.666E+004   2.899E+004 Eu-155       86.55     30.70  7.210E+004    7.21E+004   1.815E+004   3.495E+004 105.31     21.10  9.387E+004               -3.214E+004   4.533E+004 Tl-208      583.19     85.00  2.620E+004    2.62E+004   2.138E+004   1.207E+004 Bi-212      727.33      6.67  3.40BE+005    3.41E+005  -5.997E+004   1.553E+005
 +      Pb-212      238.63*    43.60  2.624E+004    2.62E+004   2.460E+004   1.204E+004
 +      Bi-214      609.32*    45.49  2.460E+004    2.46E+004   4.260E+004   1.033E+004 1120.29     14.92  1. 751E+005               1.242E+005   7.874E+004 1764.49     15.30  1. 902E+005               1.477E+OOS   8.335E+004
 +      Pb-214      295.22     18.42  1 .074E+005   3.47E+004   8.293E+004   5.074E+004 351. 93

• 35.60 3.467E+004 3.800E+004 1 .561E+004 Ra-226 186 .21 3.64 4.998E+005 5.00E+OOS 1 .164E+D05 2.389E+OOS Ac-228 338.32 11. 27 1 .547E+005 9.75E+004 7.367E+004 7.209E+004 911.20 25.80 9.751E+D04 1 .093E+005 4.427E+004 968.97 15.80 1.677E+005 -3.910E+004 7.625E+004 Am-241 59.54 35.90 6.572E+004 6.57E+004 -7.721E+003 3.173E+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

[154]

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

Filename: 6279 Report Generated On 8/21/2018 7:56:47 AM Sample Title B109100AFSFC016GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/21/2018 7:46:00 AM Acquisition Started 8/21/2018 7.:46:46 AM Live Time 600. 0 seconds Real Time 600.8 seconds Dead Time 0 . 13 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE °I --l.c~ '6 [155]

                                                      /c,Ji~Jf~~

Peak Analysis Report 8/21/2018 7:56:47 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSFC016GD Peak Analysis Performed on: 8/21/2018 7:56:47 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 1 295- 307 3 01. 14 75.41 1. 24 7.56E+001 47.07 1.81E+002 2 390- 399 394.03 98.63 0.44 5.07E+OOO 27.67 8.09E+001 3 949- 960 954.70 238.79 0.65 2.61E+001 22.14 3.79E+001 4 1402- 1414 1407 .98 352.11 0.38 3.61E+001 15.82 9.88E+OOO 5 5835- 5855 5845.13 1461.33 2.04 1.10E+002 22.00 2.BlE+OOO M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 ~000 sigma [156]

Interference Corrected Activity Report 8/21/2018 7:56:47 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:

B109100AFSFC016GD 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 1.19496E+006 2.60173E+005 Pb-212 1 .000 238.63* 43.60 2.08036E+004 1 .79326E+004 Pb-214 0.432 295.22 18.42 351.93* 35.60 4.59220E+004 2 .12 563E+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

[157]

Interference Corrected Activity Report 8/21/2018 7:56:47 AM Page 4

• • • • • INTERFERENC E CORRECTED REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 } Uncertainty K-40 1 .000 1. 1 9 4960E+006 2.601731E+005 Pb-212 1.0 0 0 2.080357E+004 1 .793256E+004 Pb-214 0.432 4.592201E+004 2.125627E+004

      ? = Nuclide is part of an undetermined solution X     Nuclide rejected by the interference ana lysis
      @ = Nuclide contains energy lines not used in Weighted Mean Activi ty 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: 8 /21/2018 7:56:47 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 75.41 1.2605E-001 62.23 2 98.63 8.4496E-003 545.73 Tol. Eu- 1 55 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 [158]

Nuclide MDA Report 8/21/2018 7:56:47 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC016GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (% ) (pCi/M"2 ) (pCi/M"2 ) (pCi/MA2 ) (pCi/MA2 )

 +      K-40       1460.82*    10 .66 l. 467E+005    1.47E+005   1. 195E+006 5.866E+004 Co-60      1173.23     99.85  2.457E+004     1.62E+004   O.OOOE+OOO  1. 093E+004 1332.49     99.98  1. 623E+004                7.565E+003  6.652E+003 Nb-94       702.65     99.81  2.082E+004     2. 00E+004 -1.773E+004  9.427E+003 871.09     99.89  1. 999E+004                6.873E+003  8.868E+003 Ag-108m     433.90     90.50  2.065E+004     2.06E+004   3.595E+003  9.538E+003 614. 30    89.80  2 . 642E+004              -1.289E+004  1.221E+004 722.90     90.80  2.462E+004                 5.683E+003  1.121E+004 Cs-134      604.72     97.62  2.405E+004     2.40E+004   1.034E+004  1.111E+004 795.86     85.46  2.551E+004                -5.743E+003  1.151E+004 Cs-137      661.66     85.10  2.584E+004     2.58E+004   5.253E+003  1.18DE+004 Eu-152      121.78     28.67  6.724E+004     6.72E+004   2.509E+004  3.241E+004 344.28     26.60  7.111E+004                -5.340E+003  3.329E+004 1408 .01    21. 07 8.015E+004                 1.620E+004  3.28SE+004 Eu-154      123.07     40.40  4.771E+004     4.77E+004   6.450E+003  2.299E+004 723.30     20.06  1.lOOE+OOS                -4.826E+003  5.002E+004 1274.43     34.80  5.887E+004                -2.882E+004  2.535E+004 Eu-155       86.55     30.70  7.501E+004     7.SOE+004   4.819E+004  3.641E+004 105.31     21.10  9.336E+004                -3.343E+004  4.507E+004 Tl-208      583.19     85.00  2.432E+004     2.43E+004   2.105E+004  1. 114E+OD4 Bi-212      727.33      6.67  3.230E+005     3.23E+OOS  -1.566E+005  1 .465E+OD5
 +      Pb-212      238.63*    43.60  2.785E+004     2.79E+004   2.080E+004  1 .285E+004 Bi-214      609.32     45.49  5.139E+004     5.14E+004   1.371E+004  2.372E+004 1120 .29    14.92  1.692E+005                -4.234E+003  7.576E+004 1764.49     15.30  1.379E+005                -1.575E+004  5.718E+004
 +      Pb-214      295.22     18.42  1.093E+OOS     2.50E+004   1.281E+OOS  5.174E+004 351. 93

• 35.60 2.496E+004 4.592E+004 1.076E+OD4 Ra-226 186.21 3.64 4.891E+005 4 .89E+005 6.348E+004 2.335E+OD5 Ac-228 338.32 11. 27 1.647E+005 9.75E+004 1.278E+005 7.707E+004 911. 20 25.80 9.751E+004 6.211E+004 4.427E+OD4 968.97 15.80 1. 536E+005 3.714E+004 6.92DE+004 Am-241 59.54 35.90 6.369E+004 6.37E+004 -1.358E+004 3.072E+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

[159]

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

Filename: 6279 Report Generated On 8/18/2018 10: 30:19 AM Sample Title B109100AFSFC017GD Sample Description WWTF FLOOR Sample Identification 017 Sample Type GAMMA DIRECT Sample Geometry 3MWWTF1.27CM 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 2.826E+001 MA2 Sample Taken On 8/18/2018 10 :20: 00 AM Acquisition Started 8/18/2018 10 :20:17 AM 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 9./Z-10 TIME 1D~ 0 / ' [160] _(JZ,Mt~{~

Peak Analysis Report 8/18/2018 10 :30: 19 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:

B109l00AFSFC017GD Peak Analysis Performed on: 8/18/2018 10:30:19 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 1 296- 305 300.29 75.20 0.79 6.02E+001 37.03 1.25E+002 2 2037- 2048 2042.55 510.74 0.42 2.84E+001 13 .14 5.56E+OOO 3 5836- 5856 5844.98 1461.30 1. 40 1.05E+002 22.55 6.56E+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 [161]

Interference Corrected Activity Report 8/18/2018 10:30:19 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:

B109100AFSFC017GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.14506E+006 2.64351E+OOS

       * ~ 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

[162]

Interference Corrected Activity Report 8/18/2018 10:30 : 19 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 1.000 1.145061E+006 2.643515E+005

      ? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
      @    Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at    2.000 sigma
  **********    U N I D E N T I F I E D          P E A K S     **********

Peak Locate Performed on: 8/18/2018 10:30:19 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 75.20 1.0033E-001 61.52 2 510.74 4.7402E-002 46.18 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [163]

Nuclide MDA Report 8/18/2018 10 ~30:19 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3MWWTF1.27CM Sample

Title:

B109100AFSFC017GD 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  1.960E+OOS    1. 96E+OOS  1.14SE+006  8.328E+004 Co-60       1173.23     99.85  2.651E+004    1.53E+004   2.951E+003  1 .190E+004 1332.49     99.98  1.526E+004               -1.001E+004  6.167E+003 Nb-94         702.65    99.81  1.824E+004    1.82E+004   2.305E+003  8.132E+003 871. 0 9  99.89  2.084E+004                9.073E+003  9.294E+003 Ag-108m       433.90    90.50  2.048E+004    2.05E+004  -2.373E+003  9.456E+003 614 .30   89.80  2.621E+004                2.446E+004  1.210E+004 722.90    90.80  2.156E+004                3.270E+003  9.674E+003 Cs-134        604.72    97.62  2.317E+004    2.07E+004   1 .959E+004 1.067E+004 795.86    85.46  2.066E+004               -1 .068E+004 9.083E+003 Cs-137        661. 66   85.10  2.426E+004    2.43E+004  -1 .484E+004 1.102E+004 Eu-152        121. 78   28.67  6.037E+004    6.04E+004  -2.266E+004  2.897E+004 344.28    26.60  6.241E+004               -5.588E+004  2.893E+004 1408.01     21.07  9.695E+004                5.880E+004  4 .124E+004 Eu-154        123.07    40. 40 4.270E+004    4.27E+004  -1.75SE+004  2.049E+004 723.30    20.06  9.760E+004                4.708E+004  4.380E+004 1274 .43    34.80  5.696E+004                1.009E+004  2.439E+004 Eu - 155       86.55    30.70  7.179E+004    7.18E+004   4.975E+004  3.479E+004 105. 31   21. 10 9.161E+004               -2.799E+004  4.419E+004 Tl-208        583.19    85.00  2.797E+004    2.80E+004   2.161E+004  1.296E+004 Bi-212        727.33     6.67  3.045E+005    3.0SE+OOS   1.706E+005  1.372E+005 Pb-212        238.63    43.60  4 .521E+004   4.52E+004   5.037E+004  2.153E+004 Bi-214        609.32    45.49  5.337E+004    5.34E+004   4.939E+004  2.471E+004 1120.29     14 .92 1.567E+005               -6. 717E+004 6.954E+004 1764.49     15.30  1 .381E+OOS               6.961E+004  5.726E+004 Pb-214        295.22    18.42  1 .134E+OOS   5.47E+004   1 .598E+005 5.375E+004 351. 93   35.60  5.473E+004               -1.231E+004  2.564E+004 Ra-226        186. 21    3.64  4.975E+005    4.98E+OOS   2.108E+004  2.377E+005 Ac-228        338.32    11.27  1.5SOE+005    9.21E+004   4.965E+004  7.219E+004 911. 2 0  25.80  9.210E+004                4.893E+004  4.156E+004 968.97    15.80  1.611E+005                9.429E+004  7.291E+004 Am-241         59.54    35.90  5.830E+004    5.83E+004   2.261E+004  2.803E+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

[164]

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

Filename: 6279 Report Generated On 8/18/2018 10 :15:19 AM Sample Title B109100AFSFC018GD Sample Description WWTF FLOOR Sample Identification 018 Sample Type GAMMA DIRECT Sample Geometry 3MWWTF1.27CM 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 2.826E+001 M"2 Sample Taken On 8/18/2018 10:05:00 AM Acquisition Started 8/18/2018 10:05:17 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 7/31/2018 Efficiency ID 3MWWTF1,27CM [165]

Peak Analysis Report 8/18/2018 10 :15:19 AM Page 2

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Detector Name: 6279 Sample

Title:

B109100AFSFC0l8GD Peak Analysis Performed on: 8/18/2018 10 :15:19 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 1 297- 308 301. 34 75.46 1. 10 5.85E+001 39.67 1.33E+002 2 1401- 1414 1406.98 351.86 1. 67 3.86E+001 17. 11 l.24E+001 3 2429- 2442 2436.03 609. 10 0.49 2.90E+001 13.89 7.00E+OOO 4 5836- 5855 5844.82 1 461.26 0.43 6.58E+001 17.09 2.21E+OOO M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [166]

Interference Corrected Activity Report 8/18/2018 10:15:19 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:

B109100AFSFC018GD 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 7.14436E+005 l.95697E+005 Bi-214 0.461 609.32* 45.49 4.22984E+004 2.08912E+004 1120.29 14.92 1764.49 15.30 Pb-214 0 .432 295.22 18.42 351.93* 35.60 4.91179E+004 2.29843E+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

[167]

Interference Corrected Activity Report B/18/2018 10 :15:19 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 1.000 7.14435BE+005 1. 956965E+O 05 Bi-214 0.461 4.22983SE+004 2.089120E+004 Pb-214 0.432 4.911790E+004 2.298433E+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 : B/18/2018 10 :15:19 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 75.46 9.7500E-002 67.81 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 [168]

Nuclide MDA Report 8/18/2018 10:15:19 AM Page 5

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Detector Name: 6279 Sample Geometry: 3MWWTF1.27CM Sample

Title:

B109100AFSFC018GD 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  1.255E+005    1.25E+005  7.144E+005   4.806E+004 Co-60      1173.23     99.85   2.557E+004    1.80E+004  1.483E+003   l.143E+004 1332.49     99.98   1.803E+004               9.740E+003   7.553E+003 Nb-94        702.65    99.81   1.893E+004    1.89E+004  6.195E+002   8.478E+003 871.09    99.89   2.202E+004               4.357E+003   9.882E+003 Ag-108m      433.90    90. 5 0 2.009E+004    2.01E+004  1. 743E+004  9.261E+003 614. 3 0  89.80   2.945E+004              -7.856E+003   l.372E+004 722.90    90.80   2.367E+004              -9.035E+003   1.073E+004 Cs-134       604.72    97.62   2.474E+004    1.96E+004  1. 238E+003  1.146E+004 795.86    85.46   1. 962E+004              l.438E+003   8.563E+003 Cs-137       661.66    85 .10  2.393E+004    2.39E+004  9.802E+003   1. 085E+004 Eu-152       121.78    28.67   6.185E+004    6.19E+004 -1.241E+003   2.971E+004 344.28    26.60   6.888E+004               2.196E+004   3.217E+004 1408.01     21.07   1.041E+005              -5.314E+004   4.484E+004 Eu-154       123. 07   40 .40  4.377E+004    4.38E+004  3.086E+004   2.102E+004 723. 3 0  20.06   1. 072E+005             -7. s*30E+003 4.860E+004 1274.43     34.80   5.489E+004               3.329E+004   2.335E+004 Eu-155        86.55    30.70   6.775E+004    6.78E+004  2.258E+003   3.277E+004 105.31    21. 10  8.150E+004              -7.960E+004   3.914E+004 Tl-208       583.19    85.00   2.491E+004    2.49E+004  1.512E+004   l .143E+004 Bi-212       727.33     6.67   3.045E+005    3.0SE+OOS  2.985E+003   1. 3 72E+O 05 Pb-212       238.63    43.60   4.257E+004    4.26E+004  1 .340E+004  2.021E+004
 +      Bi-214       609.32*   45.49   2.500E+004    2.50E+004  4.230E+004   l.053E+004 1120.29     14. 92  1. 694E+005              5.883E+004   7.587E+004 1764.49     15.30   1. 450E+005              7.832E+004   6.073E+004
 +      Pb-214       295.22    18.42   9.745E+004    2.81E+004  1.837E+004   4 .579E+D04 351.93*   35.60   2.808E+004               4 .912E+004  1.232E+004 Ra-226       186. 21    3.64   4.494E+005    4.49E+005 -4.174E+005   2.136E+005 Ac-228       338.32    11.27   l .584E+005   9.49E+004  1 .739E+004  7.389E+004 911.20    25.80   9.492E+004               9.283E+003   4.297E+004 968.97    15 .80  1.488E+005               6.701E+004   6.678E+004 Am-241        59.54    35.90   5.844E+004    5.84E+004  4.448E+004   2.809E+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

[169]

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

Filename: 6279 Report Generated On 8/14/2018 2:38:26 PM Sample Title B109100AFSFC019GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3MWWTF 1 .27CM 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 8/14/2018 2:28:00 PM Acquisition Started 8/14/2018 2:28:25 PM Live Time 600.0 seconds Real Time 601.0 seconds Dead Time 0.17 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE </-?-If!> Tl~O:jo [170] (i2,Jl'1/J ~ / / ~

Peak Analysis Report 8/14/2018 2: 38: 26 PM Page 2

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Detector Name: 6279 Sample

Title:

B109100AFSFC019GD Peak Analysis Performed on: 8/14/2018 2:38:26 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- 305 300.12 75.16 0. 92 5.82E+001 38.54 1.38E+002 2 949- 958 953.91 238.59 0. 95 4. 51E+001 17.99 1.59E+001 3 2429- 2440 2434.13 608.63 1. 21 2. 04E+001 13.66 8.58E+OOO 4 5832- 5853 5841.51 1460.43 1. 09 1. 01E+002 20.10 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 [171]

Interf erence Corrected Activity Report 8/14/2018 2:38:26 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:

B109100AFSFC019GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence {keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460. 82* 10.66 1.09484E+006 2.37719E+OOS Pb-212 1.000 238.63* 43.60 3.58958E+004 1 .54346E+004 Bi - 214 0 .460 609.32* 45.49 2.97297E+004 2.01982E+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

[172]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1.094837E+006 2.377194E+005 Pb-212 1. 000 3.589583E+004 l .543458E+00 4 Bi-214 0.460 2.972966E+004 2.019825E+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: 8/14/2018 2:38:26 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 1 75.16 9.7011E-002 66.22 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 [173]

Nuclide MDA Report 8/14/2018 2:38:26 PM Page 5

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Detector Name: 6279 Sample Geometry: 3MWWTF1.27CM Sample

Title:

B109100AFSFC019GD 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  2.933E+004    2.93E+004   1 .09SE+006 O.OOOE+OOO Co-60      1173.23    99.85  2.506E+004    1.62E+004   1.596E+004  l. 117E+004 1332.49    99.98  1. 623E+004              -l.467E+003  6.652E+003 Nb-94       702.65    99.81  2.142E+004    2.00E+004   4.521E+002  9.726E+003 871.09    99.89  1.999E+004                6.655E+003  8.868E+003 Ag-108m     433.90    90.50  1.884E+004    1.88E+004   1.015E+004  8.637E+003 614.30    89.80  2.438E+004               -4.847E+003  1 .119E+004 722.90    90.80  1.998E+004                6.552E+003  8.886E+003 Cs-134      604.72    97.62  2.534E+004    2.39E+004   1.3SOE+004  1.176E+004 795.86    85.46  2.386E+004                4.245E+003  1.069E+004 Cs-137      661.66    85.10  2.763E+004    2.76E+004   1.523E+004  1.270E+004 Eu-152      121. 7 8  28.67  6.616E+004    6.62E+004  -5.667E+003  3.187E+004 344.28    26.60  7.065E+004               -6.392E+004  3.306E+004 1408.01    21.07  7.528E+004                3.203E+004  3.042E+004 Eu-154      123.07    40.40  4.733E+004    4 .73E+004  3.62SE+003  2.280E+004 723.30    20.06  9.045E+004                3.151E+004  4.024E+004 1274.43    34.80  7.261E+004                4.285E+004  3.222E+004 Eu-155       86.55    30.70  7.372E+004    7.37E+004   1.006E+005  3.576E+004 105.31    21.10  9.387E+004               -9.882E+003  4 .533E+004 Tl-208      583.19    85.00  2.620E+004    2.62E+004   5.339E+003  1.207E+004 Bi-212      727.33     6.67  2.890E+005    2.89E+005   4.351E+004  1. 2 95E+O 05
 +      Pb-212      238.63*   43.60  1 .779E+004   1 .78E+004  3.590E+004  7.820E+003
 +      Bi-214      609.32*   45.49  2.845E+004    2.85E+004   2.973E+004  1. 226E+004 1120.29    14.92  1 .497E+005              -3.591E+004  6.605E+004 1764.49    15. 30 1 .636E+OOS               1.043E+005  7.003E+004 Pb-214      295.22    18.42  1.0llE+OOS    6.14E+004   5.544E+004  4.763E+004 351. 93   35.60  6.138E+004                3.484E+004  2.897E+004 Ra-226      186.21     3.64  4.938E+005    4.94E+005   2.871E+005  2.358E+OOS Ac-228      338.32    11.27  1.679E+005    9.62E+004  -5.868E+004  7.866E+004 911. 2 0  25.80  9.615E+004                3.486E+004  4.360E+004 968.97    15.80  1.536E+005                1.192E+OOS  6.920E+004 Am-241       59.54    35.90  6.332E+004    6.33E+004   l.447E+004  3.054E+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

[174]

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

Filename: 6279 Report Generated On 8/14/2018 1:47:43 PM Sample Title B109100AFSFC020GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct sample Geometry 3MWWTF1.27CM 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 8 /14/2019 1 : 37: 00 PM Acquisition Started 8/14/2018 1 : 3 7 : 41 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 7/31/2018 Efficiency ID 3MWWTF1,27CM [175]

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Detector Name: 6279 Sample

Title:

Bl09100AFSFC020GD Peak Analysis Performed on: 8/14/2018 1 : 47 :42 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- 304 299.81 75.08 0.71 4.76E+001 40.49 l.59E+002 2 948- 962 954.22 238.67 0.28 2.38E+001 25.08 4.62E+001 3 1400- 1412 1406.48 351.73 1.12 4.21E+001 14.84 4.89E+OOO 4 2428- 2442 2434.55 608.74 0.80 3.45E+001 15.00 7.50E+OOO 5 5831- 5851 5840.84 1460.26 1.45 9.70E+001 19.70 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 [176]

Interference Corrected Activity Report 8/14/2018 1:47:43 PM Page 3

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

Sample

Title:

Bl09100AFSFC020GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.999 1460 .82* 10.66 l.05139E+006 2.32206E+005 Pb-212 1. 000 238.63* 43.60 1.89458E+004 2.01813E+004 Bi-214 0.460 609.32* 45.49 5.02289E+004 2.26517E+004 1120.29 14.92 1764.49 15.30 Pb-214 0 .432 295.22 18.42 351.93* 35.60 5.34931E+004 2.04824E+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

[177]

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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 1.05 1388E+006 2.322058E+005 Pb-212 1. 000 l .894583E+004 2.018134E+004 Bi-214 0 .460 S.022888E+004 2.265172E+004 Pb-214 0 .432 S.349308E+004 2.048239E+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: 8/14/2018 1 : 47: 42 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 75.08 7.9348E-002 85.06 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 [178]

Nuclide MDA Report 8/14/2018 1:47:43 PM Page 5

• * *** NUCLIDE MD A REPORT *****

Detector Name: 6279 Sample Geometry: 3MWWTF1.27CM Sample

Title:

B109100AFSFC020GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/MA2 } (pCi/M"2)

   +      K-40       1460.82*    10 .66 2.933E+004    2.93E+004  1.051E+006  O.OOOE+OOO Co-60      1173.23     99.85  2.192E+004    2.19E+004  1.000E+004  9.606E+003 1332.49     99.98  2.426E+004               1 .343E+004 1.067E+004 Nb-94       702.65     99.81  1.673E+004    1.67E+004 -3.112E+003  7.380E+003 871.09     99.89  1.999E+004              -3.016E+004  8.868E+003 Ag-108m     433.90     90.50  1.863E+004    l.86E+004  7.020E+003  8.531E+003 614. 3 0   89.80  2.761E+004              -1 .328E+004 1.280E+004 722.90     90.80  2.225E+004               7.468E+003  1.003E+004 Cs-134      604.72     97.62  2.812E+004    2.47E+004  3.006E+004  1. 315E+004 795.86     85.46  2.470E+004              -3.229E+004  1.111E+004 Cs-137      661.66     85.10  2.584E+004    2.58E+004  1.548E+004  1.180E+004 Eu-152      121.78     28.67  6.884E+004    6.28E+004 -1.820E+004  3.320E+004 344. 2 8   26.60  6.284E+004              -2.978E+004  2.915E+004 1408.0l     21.07  9.298E+004               2.082E+004  3.927E+004 Eu-154      123. 07    40 .40 4.894E+004    3.63E+004  2.861E+004  2.361E+004 723. 3 0   20.06  1.024E+005               6.040E+004  4.620E+004 1274. 43    34.80  3.630E+004               1.209E+004  1 .406E+004 Eu-155       86.55     30.70  7.302E+004    7.30E+OD4  6.884E+004  3.541E+004 105. 31    21.10  9.131E+004               3.443E+004  4.405E+OD4 Tl-208      583.19     85.00  2.487E+004    2.49E+004  1.287E+004  1.141E+004 Bi-212      72 7. 3 3   6.67  3.041E+005    3.04E+005 -6.628E+004  1.370E+005
  +       Pb-212      238.63*    43.60  3.238E+004    3.24E+004  1 .895E+004 1.511E+004
  +       Bi-214      609.32*    45.49  2.626E+004    2.63E+004  5.023E+004  1.116E+004 1120.29     14.92  1.995E+005               8.210E+004  9.092E+004 1764.49     15.30  1.852E+005               7.332E+004  8.086E+004
  +       Pb-214      295.22     18.42  1.058E+005    l.85E+004  5.022E+003  4.998E+004 351.93*    35.60  1. 848E+004              5.349E+004  7.519E+003 Ra-226      186. 21     3.64  4.766E+005    4.77E+005 -2.176E+OOS  2.272E+005 Ac-228      338.32     11.27  l .559E+005   1.0lE+OOS -1.366E+004  7.266E+004 911 . 2 0  25.80  1 .014E+005              7.205E+004  4.624E+004 968.97     15.80  1 .632E+005              6.333E+OD4  7.398E+004 Am-241       59.54     35.90  6.159E+004    6.16E+004 -3.256E+004  2.967E+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

[179]

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

Filename: 6279 Report Generated On 8/14/2018 2:01:19 PM Sample Title B109100AFSFC021GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3MWWTF1.27CM 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 8/14/2018 1:51:00 PM Acquisition Started 8/14/2018 1 :51:17 PM Live Time 600.0 seconds Real Time 601. O seconds Dead Time 0 . 16 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1, 27CM [180]

Peak Analysis Report 8/14/2018 2:01:19 PM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSFC021GD Peak Analysis Performed on: 8/14/2018 2:01:18 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 1 296- 305 300.21 75.18 0.36 5.29E+001 39.57 1. 48E+002 2 334- 346 338.41 84.73 0.47 1.S6E+001 38.63 1. 3 SE+002 3 948- 960 952.53 238.25 0.62 3.85E+001 20.67 2.55E+001 4 1399- 1411 1405.83 35 1 .57 0.33 2.12E+001 19.51 2.78E+001 5 2430- 2441 2435.07 608.86 0.44 2.73E+D01 12.58 4.70E+OOO 6 5833- 5851 5841.78 1460.50 0.95 7.60E+001 19.95 7. 0lE+OOO M :::: First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [181]

Interference Corrected Activity Report 8/14/2018 2:01:19 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:

B109100AFSFC021GD 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 8.23801E+005 2.27769E+005 Eu-155 0.346 86.55* 30.70 1.28463E+004 3.18370E+004 105.31 21.10 Pb-212 1. 000 238.63* 43.60 3.05466E+004 1 .71476E+004 Bi-214 0 .461 609.32* 45.49 3.97588E+004 1 .89288E+004 1120 .29 14. 92 1764.49 15 .30 Pb-214 0 .432 295.22 18 .42 351.93* 35.60 2.69035E+004 2.51062E+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

[182]

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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 8.238008E+OOS 2.277694E+005 Eu-155 0 .346 1.284630E+004 3 .183700E+004 - Pb-212 1 .000 3.054661E+004 1.714759E+004 Bi-214 0.461 3.975883E+004 1.892877E+004 Pb-214 0.432 2.690352E+004 2.510622E+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 : 8/14/2018 2:01:18 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 .18 8.8130E-002 74.83 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 [183]

Nuclide MDA Report 8/14/2018 2:01:19 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3MWWTF1.27CM Sample

Title:

B109100AFSFC021GD 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 2.022E+005      2.02E+OOS   8.238E+005  8.642E+004 Co-60     1173.23      99.85  2.248E+004      l.88E+004   8.387E+003  9.88SE+003 1332.49      99.98  1. 8 83E+O 04               1.081E+004  7.951E+003 Nb-94       702.65     99.81  2.021E+004      2.00E+004  -3.32SE+003  9.118E+003 871.09     99.89  1.999E+004                  1.089E+004  8.868E+003 Ag-108m     433.90     90.50  1. 863E+O 04    1 .86E+004 -5.802E+003  8.531E+003 614. 3 0   89.80  2.830E+004                 -6.600E+003  l.315E+004 722.90     90.80  2.462E+004                  2.240E+004  l.121E+004 Cs-134      604.72     97.62  2.534E+004      2.53E+004   2.508E+004  l.176E+004 795.86     85.46  2.551E+004                 -3.367E+003  l.151E+004 Cs-137      661. 66    85.10  2.615E+004      2.61E+004   1.111E+004  l.196E+004 Eu-152      121. 78    28.67  6.322E+004      6.32E+004  -9.497E+004  3.040E+004 344.28     26.60  6.438E+004                 -3.308E+004  2.993E+004 1408.01      21. 07 9.298E+004                  5.338E+004  3.927E+004 Eu-154      123.07     40.40  4.566E+004      4.57E+004  -2.854E+004  2.196E+004 723. 3 0   20.06  1.100E+005                  7.652E+004  5.002E+004 1274.43      34.80  5.264E+004                 -1.360E+003  2.223E+004
 +       Eu-155       86.55*    30.70  5.332E+004      5.33E+004   1.28SE+004  2.555E+004 105. 31    21.10  9.096E+004                 -5.870E+004  4.387E+004 Tl-208      583.19     85.00  2.568E+004      2.57E+004   l.019E+004  1 .181E+004 Bi-212      727.33      6.67  3.090E+005      3.09E+005   9.80SE+004  1.394E+OOS
 +       Pb-212      238.63*    43.60  2.376E+004      2.38E+004   3.055E+004  1 .081E+004
 +       Bi-214      609.32*    45.49  2.071E+004      2.07E+004   3.976E+004  8.383E+003 1120.29      14.92  1. 6 92E+O 05               1.0SOE+005  7.576E+004 1764.49      15. 30 1.576E+005                  1.363E+004  6.705E+004
 +       Pb-214      295.22     18.42  9.842E+004      3.94E+004   2.265E+004  4.628E+004 351. 93

• 35.60 3.938E+004 2.690E+004 l .797E+004 Ra-226 186.21 3.64 4.750E+005 4.75E+OOS 1.923E+005 2.264E+OOS Ac-228 338.32 11. 27 1. 536E+O 05 8.60E+004 4.422E+004 7.152E+004 911. 2 0 25.80 8.603E+004 1.411E+004 3.853E+004 96 8. 9 7 15.80 1.322E+OOS -8.938E+004 5.848E+004 Am-241 59.54 35.90 6.258E+004 6.26E+004 -4.301E+004 3.017E+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

[184]

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

Filename: 6279 Report Generated On 8/14/2018 2: 26: 42 PM Sample Title B109100AFSFC022GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3MWWTF1.27CM 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 8/14/2018 2:16:00 PM Acquisition Started 8/14/2018 2:16 :40 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 7/31/2018 Efficiency ID 3MWWTF1,27CM [185]

Peak Analysis Report 8/14/2018 2: 26 : 42 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:

B109100AFSFC022GD Peak Analysis Performed on: 8/14/2018 2:26:41 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- 305 300.30 75.20 0.74 4.90E+001 4 1. 48 1.59E+002 2 334- 34 4 338.93 84 .86 0.88 4.47E+001 34.15 1 .03E+002 3 949- 961 954.13 238.65 1. 03 5.18E+001 22.46 2.82E+001 4 1175- 1185 1179 .81 295.07 0.82 1.63E+001 15.52 1 .67E+001 5 1399- 1414 1406.35 351.70 0.79 5.32E+001 18.17 9.82E+OOO 6 2325- 2336 2330.80 582.80 0.33 1.40E+001 10.78 6.00E+OOO 7 2429- 2440 2434.68 608.77 1. 31 2.23E+001 1 4. 18 1.07E+001 8 5832- 5851 5841.56 146 0.44 1. 82 9.70E+001 19.70 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 [186]

Interference Corrected Activity Report 8/14/2018 2: 26: 42 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:

B109100AFSFC022GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  . . . . . . . . . .. . . . . . . . . . . IDENTIFIED NUCLIDES           ...... .................. - .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.05148E+006 2.32227E+005 Eu-155 0.346 86.55* 30.70 3.67089E+004 2.89824E+004

                                                                                                     - ptt- ~1-i,,0 105.31        21.10 Tl-208               1.000            583 .19*      85.00     1. 05934E+004    8.25273E+003 Pb-212               1 .000           238.63*       43.60     4.12252E+004     1.90663E+004 Bi-214               0.460            609.32*       45.49     3.24282E+004     2. 10 080E+004 1120.29         14.92 1764.49         15.30 Pb-214               1.000            295.22*       18.42     3.54205E+004     3 .41 536E+004 351.93*       35.60     6.75552E+004     2.51997E+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

[187]

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 1. 0 51484E+006 2.322272E+OOS Eu-155 0.346 3.670891E+004 2.898240E+004 Tl-208 1 .000 1.059339E+004 8.252727E+003 Pb-212 1.000 4 .122520E+004 l .906629E+004 Bi-214 0.460 3.242821E+004 2.100797E+004 Pb-214 1.000 S.622774E+004 2.02775SE+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: 8/14/2018 2: 26: 41 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 Nu cl i de 1 75.20 8.1589E-002 84.73 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [188]

Nuclide MDA Report 8/14/2018 2:26:42 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3MWWTF1.27CM Sample

Title:

B109100AFSFC022GD 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  2.933E+004    2.93E+004   1.051E+006  O.OOOE+OOO Co-60      1173.23     99.85  2.076E+004    1.8BE+004   6.810E+003  9.023E+OD3 1332.49     99.98  1. 883E+004             -5.674E+OD3   7.951E+003 Nb-94        702.65    99.81  1.890E+004    1.89E+004   8.544E+003  B.466E+OD3 871.09    99.89  2.309E+004                1.255E+003  1.042E+004 Ag-108m      433.90    90.50  1.842E+004    1.84E+004   5.367E+003  8.424E+003 614. 3 0  89.80  3.006E+004              -1 .094E+004  1.402E+004 722.90    90.80  2.115E+004              - 7.134E+003  9.473E+003 Cs- 134      604.72    97.62  2.755E+004    2.43E+004   2.629E+004  1.286E+004 795.86    85.46  2.429E+004                1.D41E+004  1.090E+004 Cs-137       661.66    85.10  2.138E+004    2.14E+OD4 -6.338E+OD3   9.575E+003 Eu-152       121.78    28.67  6.B71E+004    6.44E+004   4.775E+OD4  3.314E+004 344.28    26.60  6.438E+004              -7.772E+004   2.993E+OD4 1408.01     21.07  9.681E+004              -2.535E+004   4.118E+D04 Eu-154       123.07    40.40  4.838E+004    4.84E+004 -l.755E+003   2.333E+004 723.30    20.06  9.746E+004              -2.854E+004   4.374E+004 1274.43     34.80  5.688E+004                1 .379E+OD4 2.435E+D04
 +      Eu- 1 5 5     86.55*   30.70  4 .466E+OD4   4.47E+OD4   3.671E+D04  2.122E+004 105.31    21. 10 9.927E+004                3.442E+004  4 .803E+004
 +      Tl-208       583.19*   85.00  1 .170E+004   1.17E+004   1 .059E+004 4 .826E+003 Bi-212       727.33     6.67  3.184E+005    3.18E+OD5 -1.795E+004   1. 442E+005
 +      Pb-212       238.63*   43.60  2.471E+004    2.47E+004   4.123E+004  1 .128E+004
 +      Bi-214       609.32*   45.49  2.928E+004    2.93E+004   3.243E+004  1. 267E+004 1120.29     14.92  1.630E+005                5.48DE+004  7.267E+004 1764.49     15. 30 2.043E+OD5                1.738E+005  9.041E+OD4
 +      Pb-214       295.22*   18.42  5.318E+004    2.61E+004   3.542E+004  2.365E+004 351.93*   35.60  2.608E+004                6.756E+004  1.132E+004 Ra-226      186. 21     3.64  4 .604E+OD5   4.60E+005 -3.040E+005   2.192E+D05 Ac-228       338.32    11 .27 1 .604E+005   9.75E+004 -4.386E+004   7.490E+004 911. 20   25.80  9.751E+OD4                8.779E+004  4 .427E+004 968.97    15 .80 l .379E+D05             -3.654E+004   6.134E+004 Am-241        59.54    35.90  6.501E+004    6.50E+004   4.387E+004  3.138E+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

[189]

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

Filename: 6279 Report Generated On 8/18/2018 1: 09:33 PM Sample Title B109100AFSFC023GD Sample Description WWTF FLOOR Sample Identification 023 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 2, r-3 Sample Size ~E+OOl MA2 l'k- rr/-z.~/!r Sample Taken On 8/18/2018 12:59:00 PM Acquisition Started 8/18/2018 12:59:31 PM Live Time 600.0 seconds Real Time 600.9 seconds Dead Time 0 . 14 % Energy Calibration Used Done o*n 6/9/2018 Efficiency Calibration used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM [190]

Peak Analysis Report 8/18/2018 1: 09: 33 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:

B109100AFSFC023GD Peak Analysis Performed on: 8/18/2018 1:09:33 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 1 290- 307 300.64 75.29 0.60 8.58E+001 53.01 1. 89E+002 2 2432- 2443 2437.92 609.58 0.80 2.45E+001 10 .64 l.49E+OOO 3 5840- 5856 5847. 80 1 462.00 0.83 5.83E+001 17.23 4.66E+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]

Interference Corrected Activity Report 8/18/2018 1: 09: 33 PM Page 3

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

Sample

Title:

B109100AFSFC023GD 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 .998 1460.82* 10.66 6.33818E+OOS 1.95128E+OOS Bi-214 0.461 609.32* 45.49 3.57675E+004 1.61164E+004 1120.29 14.92 1764.49 15.30

       * ~ 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]

Interference Corrected Activity Report 8/18/2018 1: 09: 33 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 0.998 6.338184E+005 l .951284E+005 Bi-214 0.461 3.576749E+004 l.611640E+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: 8/18/2018 1:09:33 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 75.29 1.4295E-001 61.80 M - First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 , 000 sigma [193]

Nuclide MDA Report 8/18/2018 1 :09:33 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC023GD 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*  1 0 .66 1. 719E+OOS   1.72E+005   6.338E+005   7.124E+004 Co-60       1173.23    99.85   2.079E+D04    1.96E+OD4   l.504E+004   9.036E+003 1332 .49   99.98   1. 963E+004              -6.248E+003   8.350E+OD3 Nb-94        702.65    99.81   1. 959E+004   1 .32E+D04  6.269E+003   8.810E+003 871. 0 9  99.89   1. 322E+OD4               8.591E+OD2   5.481E+003 Ag- 108m     433.90    90.50   1.823E+004    1. 79E+004  l .117E+OD4  8.327E+003 614. 30   89.80   2.415E+004                1 .141E+004  l.107E+004 722.90    90.80   l.785E+OD4               -2.183E+003   7.823E+003 Cs-134       604.72    97.62   2.173E+004    2.16E+004  -l.104E+D04   9.952E+003 795.86    85.46   2.164E+004               -1.031E+004   9.574E+003 Cs-137       661.66    85.10   2.738E+004    2. 74E+004  1.356E+004   1.258E+OD4 Eu-152       121. 78   28.67   5.94SE+004    5.26E+004   6.636E+003   2.851E+004 344. 28   26.60   5.264E+OD4                2.030E+003   2.405E+004 1408. 01    21.07   8.481E+004               -1 .336E+003  3.517E+004 Eu-154       123.07    40 .40  4 .060E+004   4.06E+004  -l .116E+004  1 .944E+004 723. 3 0  20.06   8.083E+D04               -l.081E+004   3.542E+004 1274. 43    34.80   5.489E+004                9.835E+003   2.335E+OD4 Eu-155        86.55    30.70   6.991E+004    6. 99E+D04  8.698E+004   3.385E+004 105. 31   21 .10  8.247E+004               -3.567E+003   3.963E+004 Tl-208       583.19    85.00   2.292E+004    2.29E+004   2.653E+004   1. 043E+D04 Bi-212       727.33     6.67   2.621E+005    2.62E+005  -3.047E+005   1.159E+D05 Pb-212       238.63    43.60   3.939E+004    3.94E+004   4.051E+004   1. 862E+004
 +      Bi-214       609.32*   45.49   l .332E+004   1.33E+004   3.577E+D04   4.687E+003 1120 .29    14.92   1 .271E+005              -5.607E+004   5.471E+004 1764.49     15. 30  1. 905E+005               6.258E+OD4   8.347E+004 Pb-214       295.22    18.42   9.049E+004    4.74E+OD4  -4.342E+004   4.230E+004 351.93    35.60   4. 736E+004               4.166E+004   2.196E+004 Ra-226       186. 21    3.64   4. 249E+OOS   4.25E+005  -8.998E+004   2.014E+005 Ac-228       338. 32   11. 27  1. 353E+OOS   9.35E+004   7.819E+003   6.235E+004 911. 20   25.80   9.352E+004                7.735E+004   4.227E+004 968.97    15.80   l.381E+D05                4 .363E+004  6.143E+OD4 Am-241        59.54    35.90   6.438E+004    6.44E+004   1 .299E+004  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

[194]

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

Filename: 6279 Report Generated On 8/18/2018 12:55 : 43 PM Sample Title B109100AFSFC024GD Sample Description WWTF FLOOR Sample Identification 024 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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

                                     'l..,~~

Sample Size 2.826-E+OOl M"'2

                                           ;z-,. [i-/z-,.. /,v Sample Taken On                    8/18/2018       12:45:00 PM Acquisition Started                8/18/2018       12:45:41 PM Live Time                                  600.0 seconds Real T ime                                 600.6 seconds Dead Time                            0 . 09 %

Energy Calibration Used.Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM [195]

Peak Analysis Report 8/18/2018 12:55:43 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:

B109100AFSFC024GD Peak Analysis Performed on: 8/18/2018 12: 55: 42 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- 306 300.99 75.37 0.31 9.92E+001 57.56 2.08E+002 2 1402- 1413 1407.92 352.09 0.70 2.90E+001 16.32 l. 50E+001 3 5838 - 5855 5846.79 1461.75 0.74 6.48E+001 16.97 2. 21E+OOO M == First peak in a multiplet region m == Other peak in a multiplet region F == Fitted singlet Errors quoted at 2 ~000 sigma [196]

Interference Corrected Activity Report 8/18/2018 12:55:43 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:

B109100AFSFC024GD 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 7.03799E+005 1.94170E+005 Pb-214 0 .432 295.22 18.42 351.93* 35.60 3.69792E+004 2.15063E+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

[197]

Interference Corrected Activity Report 8/18/2018 12:55:43 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 7.037988E+005 l .941700E+005 Pb-214 0.432 3.697919E+004 2.150627E+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: 8/18/2018 12:55:42 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 75.37 l.6532E-001 58.03 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [198]

Nuclide MDA Report 8/18/2018 12:55:43 PM Page s

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC024GD 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/M"2 ) (pCi/MA2 ) I- K-40 1460.82* 10 .66 1.251E+005 1.25E+005 7.038E+OOS 4.787E+004 Co-60 1173.23 99.85 2.138E+004 1. 72E+O 04 -7.945E+003 9.332E+OD3 1332.49 99.98 l.717E+004 -8.793E+003 7.121E+003 Nb-94 702.65 99.81 1.714E+004 1.71E+004 -4.337E+003 7.583E+003 871. 0 9 99.89 1 .776E+004 -4.113E+003 7.752E+D03 Ag-108m 433.90 90.50 1. 887E+004 1. 89E+004 1 .720E+004 8.649E+OD3 614. 3 0 89.80 2.276E+OD4 2.000E+004 1. 037E+004 722. 90 90.80 1. 960E+004 6.320E+003 8.694E+003 Cs-134 604.72 97.62 2.271E+004 2.27E+004 -3.443E+003 1.044E+004 795.86 85.46 2.432E+004 2.393E+004 1. 092E+004 Cs-137 661.66 85 .10 2.179E+004 2.18E+004 4 .970E+003 9.778E+003 Eu-152 121.78 28.67 5.662E+004 5.20E+OD4 -1 .094E+004 2.710E+004 344.28 26.60 5.200E+004 -6.672E+004 2.373E+004 1408.01 21. 07 8.907E+004 1. 173E+004 3.73DE+004 Eu-154 123. 07 40. 40 4.060E+004 4.06E+004 5.707E+003 1.944E+004 723.30 20.06 8.873E+004 5.100E+003 3.937E+004 1274.43 34.80 5.043E+004 9.331E+003 2.112E+004 Eu-155 86.55 30.70 6.851E+004 6.85E+004 5.728E+004 3.315E+004 105. 31 21. 10 8.789E+004 3.623E+004 4.234E+004 Tl-208 583.19 85.00 2.105E+004 2.10E+004 1 .180E+004 9.497E+003 Bi-212 727.33 6.67 2.621E+OD5 2.62E+005 7.077E+004 1.159E+005 Pb-212 238.63 43.60 3.939E+004 3.94E+004 1.827E+004 1. 862E+004 Bi-214 609.32 45.49 4 .741E+004 4.74E+004 l.207E+OD4 2.173E+004 1120.29 14.92 1 .811E+005 8.794E+004 8.172E+004 1764.49 15.30 1 .516E+OOS 8.702E+004 6.402E+004

 +       Pb-214      295.22     18.42  7.739E+004    2.91E+004 8.042E+003     3.575E+004 351. 93

• 35.60 2.912E+004 3.698E+004 1. 284E+004 Ra-226 186. 21 3.64 4.177E+OOS 4.18E+OOS -3.886E+004 1.978E+OOS Ac-228 338.32 11. 27 1.366E+005 7.97E+004 6.312E+004 6.301E+004 911. 20 25.80 7.971E+004 1.414E+004 3.537E+004 968. 97 15.80 1 .200E+005 9.007E+OD4 5.238E+OD4 Am-241 59.54 35.90 6.778E+004 6.78E+004 2.404E+004 3.277E+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

[199]

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

Filename: 6279 Report Generated On 8/18/2018 1:25:57 PM Sample Title B109100AFSFC025GD Sample Description WWTF FLOOR Sample Identification 025 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 2,'93 Sample Size ~- 82i5"E+001 MA2 p,...__ f I -z.;q.,f tY Sample Taken On 8/18/2018 ~:15:00 PM Acquisition Started 8/18/2018 1:15:55 PM Live Time 600.0 seconds Real Time 600.9 seconds Dead Time 0 . 16 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM [200]

Peak Analysis Report 8/18/2018 1 :25:57 PM Page 2

• • • • • P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B109100AFSFC025GD Peak Analysis Performed on: 8/18/2018 1:25:56 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 89- 98 93.70 23.55 0.69 1.16E+001 19.41 3.64E+001 2 297- 311 301.05 75.39 0.95 7.14E+001 47.45 1.66E+002 3 1401- 1414 1407.00 351.86 0.41 3.52E+001 18.45 1.78E+001 4 2432- 2445 2438.45 609.71 1.10 3.04E+001 14. 70 8.60E+OOO 5 5838- 5857 5848.16 1462.09 0.98 9.90E+001 21. 60 4 .98E+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 [201]

Interference Corrected Activity Report 8/18/2018 1:25:57 PM Page 3

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

Sample

Title:

B109100AFSFC025GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  . . . . . . . " . ' . .. . . " .... - . "     IDENTIFIED NUCLIDES            " .. ... ~ * * " * * * *

• 9 ., - - ., -* - ..

Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0 .997 1460.82* 10 .66 1.07579E+006 2.52608E+005 Bi-214 0 .461 609.32* 45.49 4 .43662E+004 2.21056E+004 1120.29 14 . 92 1764.49 15 .30 Pb-214 0 .432 295.22 18 .42 351.93* 35.60 4 .48157E+004 2.44209E+004

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

[202]

Interference Corrected Activity Report 8/18/2018 1 : 25: 57 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.997 l .075792E+006 2.526076E+005 Bi-214 0.461 4.436624E+004 2.210563E+004 Pb-214 0.432 4.481567E+004 2.442093E+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: 8/18/2018 1:25:56 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 23.55 1.9358E-002 167.16 2 75.39 l.1908E-001 66.41 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 [203]

Nucl ide MDA Report 8/18/2018 1:25:57 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B10910 0AFSFC025GD 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  1.796E+005    1 .80E+OD5 1.076E+D06           7.508E+OD4 Co-60      1173.23     99.85   2.358E+004    1 .96E+OD4 -2.582E+003          1.043E+004 1332.49     99.98   1.963E+004               -1.323E+D04          8.350E+003 Nb-94       702.65     99.81   1.893E+004    1 .89E+004 1.071E+003           8.478E+003 871.09     99.89   2.202E+004                5.222E+003          9.882E+003 Ag-108m     433.90     90.50   1. 800E+004   1.BOE+OD4   3.680E+003          8.217E+OD3 614.30     89.80   2.923E+004                2.712E+004          1.361E+OD4 722.90     90.80   2.192E+004                2.024E+D03          9.859E+003 Cs-134      604.72     97.62   2.580E+004    2.39E+004 -1.339E+004           1.198E+OD4 795.86     85.46   2.390E+004               -1.003E+003          1.D70E+004 Cs-137      661.66     85. 10  2.935E+004    2.94E+004 2.572E+004            1. 356E+004 Eu-152      121.78     28.67   6.639E+004    6.24E+004 -4.663E+004           3.198E+004 344.28     26.60   6.241E+004                8.660E+003          2.893E+OD4 1408 .0l    21. 07  8.907E+004               -3.563E+004          3.73DE+004 Eu-154      123.07     40.40   4.642E+004    4.64E+004  -2.067E+004          2.234E+OD4 723. 3 0   20.06   9.927E+004                3 . 4 5 7.E + 0 0 4 4.464E+OD4 1274.43     34.80   5.896E+004               -5.267E+D04          2.538E+004 Eu-155        86.55    30.70   7.312E+004    7.31E+004   6.395E+004          3.546E+004 105 . 31   21.10   9.109E+004               -1.074E+D04          4.393E+004 Tl-208      583.19     85.00   3.005E+004    3.00E+004   2.350E+004          1.4DOE+004 Bi-212      727.33      6.67   2.996E+005    3.0DE+005   1.713E+OOS          1.347E+OOS Pb-212      238.63     43.60   4. 291E+004   4.29E+004   4.316E+D04          2.038E+004
 +      Bi-214      609.32*    45.49   2.728E+004    2.73E+004   4.437E+004          1.167E+004 11 20.29    14.92   1. 694E+OD5               5.649E+004          7.587E+D04 1764.49     15.30   1.450E+005                1.668E+004          6.073E+004
 +      Pb-214      295.22     18.42   1. 065E+OOS   3.30E+004 -2.634E+004           5.031E+004 351. 93

• 35.60 3.302E+OD4 4 .482E+OD4 1. 479E+D04 Ra-226 186.21 3.64 4.676E+D05 4 .68E+OD5 3.068E+D04 2.227E+D05 Ac-228 338.32 11.27 1. 606E+OOS 9.63E+004 6.500E+OD4 7.500E+D04 911 . 2 0 25.80 9.629E+OD4 1.161E+OD4 4 .366E+OD4 968.97 15.80 1. 809E+OOS -1. 548E+004 8.283E+OD4 Am-241 59.54 35.90 6.698E+004 6.7DE+004 2.937E+004 3.236E+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

[204]

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

Filename : 6279 Report Generated On 8/18/2018 1:42:08 PM Sample Title B109100AFSFC026GD Sample Description WWTF FLOOR Sample Identification 026 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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

                                       '2..,l~

Sample Size 2. a~G-£+001

                                             ~

Sample Taken On 8/18/2018 Acquisition Started 8/18/2018 1:32:06 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE °t., Z-I~ TI_ME I{) '5 ~ .. JV S [205]

Peak Analysis Report 8/18/2018 1: 42: 08 PM Page 2

• ***
• P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B109100AFSFC026GD Peak Analysis Performed on: 8/18/2018 1 :42: 07 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- 314 300.83 75.33 0.64 l.21E+002 56.80 2.01E+002 2 950- 959 954.62 238.77 0.35 3.23E+001 18.51 2.37E+001 3 2431- 2444 2437.67 609.52 0.96 4.20E+001 15.71 7.04E+OOO 4 2641- 2652 2646.61 661.75 1. 21 2.20E+001 10.87 3.00E+OOO 5 5838- 5858 5847.87 1462.02 1.16 9.50E+001 19.49 O.OOE+OOO M = First peak in a multiplet region m .,... Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [206]

Int erference Corrected Activity Report 8/18/2018 1:42:08 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:

B109100AFSFC026GD 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 1 .D3209E+006 2.29963E+005 Cs-137 1.000 661.66* 85. 10 1. 81365E+004 9.22470E+003 Pb-212 1.000 238.63* 43.60 2.57710E+004 1.53242E+004 Bi-214 0.461 609.32* 45.49 6.12279E+004 2. 40744E+004 1120.29 14. 92 1764.49 15 .30

        * = 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

[207]

Interference Corrected Activity Report B/18/2018 1 :42:08 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.998 1.032087E+006 2.299626E+005 Cs-137 1. 000 1.813647E+004 9.224696E+003 Pb-212 1. 000 2.577100E+004 1.532420E+004 Bi-214 0 . 461 6.122795E+004 2.407438E+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: 8/18/2018 1: 42:07 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 75.33 2.0168E-001 46.94 M "' First peak in a multiplet region m

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

[208]

Nucl ide MDA Report 8/18/2018 1:42:08 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSFC026GD 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  2.940E+004    2.94E+004 1.032E+OD6      O.OOOE+OOO Co-60      1173.23   99.85  2.079E+004    1 .72E+004 -1 . 143E+004  9.036E+003 1332.49   99.98  1.717E+004                5.073E+002    7.121E+003 Nb-94       702.65   99.81  l.554E+004    l .55E+004 -8.177E+003    6.782E+003 871.09   99.89  l.676E+004                5.578E+003    7.251E+003 Ag-108m     433.90   90.50  1.800E+004    1.80E+004 -2.584E+004     8.217E+003 614.30   89.80  3.114E+004               -3.493E+004    l.457E+004 722.90   90.80  2.367E+004                1 .660E+004   1.073E+004 cs-134      604.72   97.62  2.980E+004    2.47E+004 -1. 167E+004    1 .399E+004 795.86   85.46  2.474E+004               -6.314E+003    1 .112E+004 Cs-137      661.66*  85.10  9.687E+003    9.69E+003   l.814E+004    3.728E+OD3 Eu-152      121.78   28.67  6.693E+004    6.69E+004 l.834E+003      3.225E+004 344.28   26.60  7.121E+004               -7.632E+004    3.333E+004 1408.01   21.07  1.108E+005               -4.009E+003    4.816E+004 Eu-154      123.07   40.40  4.730E+004    4.73E+004  -1. 245E+.004 2.279E+004 723.30   20.06  1.072E+005                7.703E+004    4.860E+004 1274.43   34.80  7.116E+004                l.589E+004    3.148E+004 Eu-155       86.55   30.70  7.590E+004    7.59E+004 6.163E+004      3.685E+004 105 .31  21.10  9.633E+004                4.522E+004    4.656E+004 Tl-208      583.19   85.00  2.982E+004    2.98E+004 3.289E+003      1 .389E+004 Bi-212      727.33    6.67  2.734E+005    2.73E+005 -2.615E+005     l .216E+005
 +      Pb-212      238.63*  43.60  2.129E+004    2.13E+004 2.577E+004      9.569E+003
 +      Bi-214      609.32*  45.49  2.527E+OD4    2.53E+004 6.123E+004      1.066E+004 1120.29   14. 92 1. 997E+005               9.11BE+004    9.105E+004 1764.49   15.30  2.000E+OD5                1. 653E+005   8.824E+004 Pb-214      295.22   18.42  1.085E+005    6.30E+004 2.624E+004      5.132E+004 351.93   35.60  6.296E+004                5.696E+004    2.976E+004 Ra-226      186.21     3.64 4.929E+005    4.93E+005 -6.135E+003     2.354E+005 Ac-228      338.32   11.27  1.628E+005    9.63E+004 -l.324E+004     7.610E+004 911.20   25.80  9.629E+004               -1. 410E+004   4.366E+004 968.97   15.80  1.563E+005               -1.077E+005    7.052E+004 Am-241       59.54   35.90  6.365E+004    6.37E+004 2.268E+004      3.070E+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

[209]

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

Filename: 6279 Report Generated On 8/ 1 4/ 2019 3 . 15:00 PM Sample Title B109100AFSFC027GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3MWWTF1.27CM 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 8/14/2018 3:04:00 PM Acquisition Started 8/14/2018 3:04:59 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE C//l-1~ [210] TIME t~'j~Y~ f £2

Peak Analysis Report 8/14/2018 3:15:00 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:

B109100AFSFC027GD Peak Analysis Performed on: 8/14/2018 3:15:00 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 1 295- 304 299.99 75.12 1. 20 8.75E+001 43.29 1.68E+002 2 333- 344 338.89 84.85 0.46 5.61E+001 38.48 1 .25E+002 3 948- 95.9 954. 0 0 238 . 62 0.55 4 .99E+001 24.35 3.91E+001 4 1398 - 1414 1406.74 351.80 0.47 6.67E+001 25.24 2.93E+001 5 2430- 2442 2435.77 609.04 1. 26 4.83E+001 16.32 6.73E+OOO 6 3636- 3649 3642.71 91 0 .76 1. 27 1 .68E+001 12.28 7.21E+OOO 7 5833- 5851 5842.60 146 0 .70 0 .41 9.BOE+OOl 19.80 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 [211]

Interference Corrected Activity Report 8/14/2018 3:15: 00 PM Page 3

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

Sample

Title:

Bl09100AFSFCD27GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  ., *"'**** II* * *

• lll ** I I I 4 IDENTIFIED NUCLIDES ..... . ................

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1. 000 1460.82* 10 .66 1 .06246E+OD6 2.33638E+OOS Eu- 155 0.346 86.55* 30.70 4.60860E+004 3.29102E+004 105.31 21.10 Pb-212 1.000 238.63* 43.60 3.96887E+004 2.04D06E+004 Bi- 214 0.461 609.32* 45.49 7.02977E+004 2.52319E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351. 93* 35.60 8.47128E+OD4 3.44864E+D04

        *=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

[212]

Interference Corrected Activity Report 8/14/2018 3: 15: 00 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Name Confidence Activity (pCi/MA2 ) Activity Uncertainty :1V ~g K-40 1 .000 1.062464E+006 2.336377E+005

                                                                                ~ -i:i-~ '\I',

Eu-155 0.346 4.608597E+004 3. 291022E+004 .. f\C..., Pb-212 1.000 3.968874E+004 2.040055E+00 4 Bi-214 0.461 7.029770E+004 2.523193E+00 4 Pb-214 0.432 8 .471277E+004 3.448644E+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: 8/14/2018 3:15:00 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Pea"k CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.12 1 .457 5E-001 49.50 6 910.76 2.7986E-002 73. 11 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 [213]

Nucl ide MDA Report 8/14/2018 3:15:00 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3MWWTF1.27CM Sample

Title:

B109100AFSFC027GD 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 2.934E+004     2.93E+004  1.062E+006     O.OOOE+OOO Co-60      1173.23    99.85  2.737E+004     2.43E+004  1.277E+004     1.233E+004 1332.49    99.98  2.426E+004                3.963E+003     1.067E+004 Nb-94       702.65    99.81  2.229E+004     2.00E+004  3.447E+003     l.016E+004 871.09    99.89  1.999E+004                1.254E+004     8.868E+003 Ag- 108m    433.90    90.50  1.967E+004     l.97E+004 -5.006E+003     9.049E+003 614.30    89.80  3. 403E+004              -9.455E+003     1 .601E+004 722.90    90.80  2.587E+004                2.097E+004     1.183E+004 Cs-134      604.72    97.62  2.940E+004     2.06E+004  5.460E+003     1.379E+004 795 . 86  85.46  2.063E+004               -l.426E+004     9.070E+003 Cs-137      661.66    85.10  2.763E+004     2.76E+004  2.572E+004     1.270E+004 Eu-152      121. 78   28.67  7.166E+004     7.17E+004  2.272E+004     3.462E+004 344.28    26.60  7.201E+004                1. 832E+ 004   3.374E+004 1408.01     21 .07 1. OOSE+O 05             -2.002E+004     4.302E+004 Eu-154      123.07    40 .40 5.184E+004     5.18E+004  4 *. 3 06E+004 2.506E+004 723. 3 0  20.06  l.171E+005                7.108E+004     5.357E+004 1274 .43    34.80  6.442E+004               -3.872E+003     2.812E+004
 +       Eu-155       86.55*   30.70  5.009E+004     5.01E+004  4.609E+004     2.393E+004 105 .31   21.10  l .026E+005               3.311E+004     4 .967E+004 Tl-208      583.19    85.00  2.594E+004     2.59E+004  2.976E+004     1.194E+004 Bi-212      727.33     6.67  3.493E+OOS     3.49E+005 -5.711E+003     1 .596E+OOS
 +       Pb-212      238.63*   43.60  2.810E+004     2.81E+004  3.969E+004     1 .297E+004
 +       Bi-214      609.32*   45.49  2.447E+004     2.45E+004  7.030E+004     1.026E+004 1120.29     14.92  1.864E+OOS                1 .169E+005    8.437E+004 1764.49     15.30  2.088E+005                1 .82SE+005    9.264E+004
 +       Pb-214      295.22    18.42  1.206E+005     4.37E+004  1.218E+005     5.735E+004 351.93*   35.60  4.366E+004                8.471E+004     2.011E+004 Ra-226      186.21     3.64  5.460E+005     5.46E+OOS  2.156E+OOS     2.619E+005 Ac-228      338.32    11. 27 1.79DE+005     1.03E+005  3.014E+004     8.423E+004 911. 2 0  25.80  1.027E+005                1.226E+OOS     4.688E+004 968.97    15.80  1.699E+005                7.460E+004     7.737E+004 Am-241       59.54    35.90  6.618E+004     6.62E+004 -6.109E+004     3.197E+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

[214]

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

Filename: 6279 Report Generated On 8/14/2018 2:14:27 PM Sample Title B109l00APSFC029GD Sample Description WWTF Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3MWWTF1 .27CM Peak Locate Threshold 3. 00 Peak Locate Range (in channels) BS - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 8/14/2018 2: 04 : 00 PM Acquisition Started 8/14/2018 2: 04 :25 PM Live Time 600.0 seconds Real Time 600.B seconds Dead Time 0 . 13  % Energy Calibration Used Done on 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATEL DATE 9-Z--/6

                                                       ~;~

TIME~*-tp, [215]

Peak Analysis Report 8/14/2018 2: 14 :27 PM Page 2

• • • • • P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B109100AFSFC028GD Peak Analysis Performed on: 8/14/2018 2:14:27 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 294- 307 300.05 75.14 0 .98 8.95E+001 5 1. 03 2.01E+002 2 388- 397 3 92. 2 7 98.19 0.33 8.31E-001 26.43 7.62E+001 3 537- 546 541.99 135.62 0.53 -1.50E+OOO 2 1. 60 5.25E+001 4 949- 958 953.98 238.61 0.33 1.78E+001 2 1. 92 4.52E+001 5 1401- 1413 1406.81 351.81 0.93 2.39E+001 17.00 1. 81E+001 6 2427- 2440 2434.32 608.68 0.79 3.36E+001 15.06 8.38E+OOO 7 5833- 5851 5842.05 1460.56 1. 74 7.77E+001 18.46 2.26E+OOO M = First peak in a multiplet region m == Other peak in a multiplet region F ;;. Fitted singlet Errors quoted at 2 . 000 sigma [216]

Interference Corrected Activity Report 8/14/2018 2 ; 14 :27 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:

Bl09100AFSFC028GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  ' ****** ti ..... .. .... '

• IDENTIFIED NUCLIDES . . .. . . ..............

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1. 000 1460.82* 10 .66 8.42730E+005 2.13092E+005 Pb-212 1. 000 238.63* 43.60 1.41746E+004 1. 75786E+004 Bi-214 0.460 609.32* 45.49 4.89518E+004 2.27061E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 3.03969E+004 2.20742E+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

[217]

Interference Corrected Activity Report B/14/2018 2: 1,1 : 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 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 8.427304E+OOS 2.130923E+OOS Pb-212 1.000 1.417459E+004 1.757864E+004 Bi-214 0.460 4. 895176E+004 2.270610E+004 Pb-214 0.432 3.039695E+004 2.207419E+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: 8/14/2018 2:1 4 :27 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.14 1 .4917E-001 57.02 2 98.19 1.3853E-003 3179.34 Tol. Eu-155 3 135.62 - 2.SOOOE-003 -1440.2 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 [218]

Nuclide MDA Report 8/14/2018 2: 14 :27 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3MWWTF1.27CM Sample

Title:

B109100AFSFCD28GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2) (pCi/M ... 2 ) (pCi/M ... 2 ) (pCi/M ... 2 )

 +       K-40       1460.82*    10 .66  1.268E+005    1.27E+005 8.427E+OOS         4.873E+004 Co-60      1173.23     99.85   2.355E+004    2.35E+004 -2.829E+003        1. 042E+004 1332.49     99.98   2.366E+004                -1.271E+002      1.037E+004 Nb-94       702.65     99.81   2.0S2E+004    2.05E+004 1 .716E+004        9.274E+003 871.09     99.89   2.160E+004                 1 .536E+004     9.676E+003 Ag-108m     433.90     90.50   l .863E+004   1 .86E+004 -l.049E+004       8.531E+003 614.30     89.80   3.006E+004                -3.232E+004      1.402E+004 722.90     90.80  2.430E+004                 -2.083E+004      1. 10SE+004 Cs-134      604.72     97.62  2.849E+004     2.67E+004 3.197E+004         1 .333E+004 795.86     85.46  2.667E+004                  2.402E+004      1.209E+004 Cs-137      661.66     85. 10 2.734E+004     2.73E+004 1.586E+004         1.256E+004 Eu-152      121. 78    28.67  6.988E+004     6.99E+004 -1. 756E+003       3.373E+004 344.28     26.60   7.246E+004                -4.383E+004      3.396E+004 1408. 01     21.07  7.528E+004                  3.203E+004      3.042E+004 Eu-154      123. 07    40.40  4.959E+004     4.96E+004 1.353E+004         2.393E+004 723. 3 0   20.06  1.lOOE+OOS                 -7.077E+004      5.002E+004 1274.43      34.80  7.261E+004                  3.990E+004      3.222E+004 Eu-155       86.55     30.70  7.599E+004     7.60E+004 6.371E+004         3.689E+004 105.31     21.10  9.863E+004                  4.617E+004      4.771E+004 Tl-208      583.19     85.00  2.404E+004     2.40E+004 2.053E+004         1.100E+004 Bi-212      727.33      6.67  3.320E+005     3.32E+OOS -l .443E+005       1.510E+005
 +       Pb-212      238.63*    43.60  2.861E+004     2.86E+004 1.417E+004         1 .323E+004
 +       Bi-214      609.32*    45.49  2.696E+004     2.70E+004 4.895E+004         1 .151E+004 1120.29      14.92  1 .630E+005                 5.048E+004      7.267E+004 1764.49      15.30  1 .514E+005                 7.821E+003      6.393E+004
 +       Pb-214      295.22     18.42  1 .093E+005    3.2SE+004 5.697E+004         5.174E+004 351. 93

• 35.60 3.2SOE+004 3.040E+004 1.453E+004 Ra-226 186. 21 3.64 5.058E+005 5.06E+005 8.97DE+004 2.419E+OOS Ac-228 338.32 11. 27 1.615E+005 1. 06E+OOS 1.169E+005 7.544E+004 911. 2 0 25.80 1.064E+005 1.692E+OD4 4.874E+004 968.97 15.80 1 .677E+005 1.llOE+OOS 7.62SE+004 Am-241 59.54 35.90 6.465E+004 6.46E+004 S.876E+003 3.120E+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

[219]

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

Filename: C:\GENIE2K\CAMFILES\00001663.CNF Report Generated On 8/20/2018 3:28:10 PM Sample Title B109100AFSWC029GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/20/2018 10:22:00 AM Acquisition Started 8/20/2018 10:22:32 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 7/31/2018 Efficiency ID 3MWWTF1,27CM JAtA vALIDATED DATE 9~z-/6 TIME 1/:2° [220]

                                                       .£1! .*- ----~"' ~r Peak Analysis Report                       8/20/2018   3:28:11 PM               Page   2

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

Detector Name: 6279 Sample

Title:

B109100AFSWC029GD Peak Analysis Performed on: 8/20/2018 3:28: 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 1 286- 295 290.66 72.79 0.64 -2.56E+001 39.62 l .67E+002 2 332- 345 339.09 8 4. 90 0.38 l.12E+001 42.96 l .63E+002 3 949- 961 954.39 238.72 0.53 3.25E+001 21.93 3.25E+001 4 1176- 1187 1181.08 295.38 0.37 1 .44E+001 18.86 2.96E+001 5 1402 - 1413 1407.35 35 1. 95 1. 19 4.0lE+OOl 19. 04 1.99E+001 6 2428 - 2444 2435.92 609.08 1. 00 5.37E+001 17.84 8.28E+OOO 7 5834- 5852 5842.82 1 460.76 0.75 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 [221]

Interference Corrected Activity Report 8/20/2018 3:28:11 PM Page 3

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

Sample

Title:

B109100AFSWC029GD 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 8.56500E+005 2.06581E+005 Eu - 155 0.346 86.55* 30.70 9.19457E+003 3.53088E+004 105. 31 21.10 Pb-212 1. 000 238.63* 43.60 2.58512E+004 l. 79337E+004 Bi-214 0.461 609.32* 45.49 7.82378E+004 2.76292E+004 1120 .29 14. 92 1764.49 15.30 Pb-214 1. 000 295.22* 18.42 3.12845E+004 4.12503E+004 351.93* 35.60 5.09666E+004 2.53724E+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

[222]

Interf erence Corrected Activity Report 8/20/2018 3:28: 11 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M ... 2 ) Uncertainty K-40 1 .000 8.565003E+OOS 2.065807E+005 Eu-155 0.346 9.194566E+003 3.530883E+004 Pb-212 1.000 2.585125E+004 1.793366E+004 Bi-214 0.461 7.823777E+004 2.762922E+004 Pb-214 1.000 4.556419E+004 2. 161149E+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: 8/20/2018 3:28: 10 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 72.79 -4.2630E-002 -154.92 M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [223]

Nuclide MDA Report 8/20/2018 3:28: 11 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM sample

Title:

Bl09100AFSWC029GD 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 2.934E+004 2.93E+004 8.565E+005 O.OOOE+OOO Co-60 1173.23 99.85 2.248E+004 1 . 62E+004 6.176E+003 9.885E+003 1332.49 99.98 1.623E+004 7.565E+003 6.652E+003 Nb-94 702.65 99.81 1.856E+004 1.86E+004 -8.643E+002 8.295E+003 871.09 99.89 2.121E+004 -2.911E+003 9.480E+003 Ag-108m 433.90 90.50 1.707E+004 1.71E+004 -8.684E+003 7.749E+003 614. 3 0 89.80 3.270E+004 -8.348E+003 1.534E+004 722.90 90.80 2.261E+004 -3.173E+003 l.020E+004 Cs-134 604.72 97.62 3.114E+004 2.88E+004 -1.256E+003 l.466E+004 795.86 85.46 2.884E+004 3.718E+003 1.318E+004 Cs-137 661.66 85.10 2.521E+004 2.52E+004 7.911E+003 l.149E+004 Eu-152 121. 78 28.67 7.090E+004 7.09E+004 4.198E+004 3.424E+004 344.28 26.60 7.845E+004 -4.466E+004 3.696E+004 1408.0l 21.07 l.168E+O 05 9.074E+004 5.120E+004 Eu-154 123.07 40.40 4.931E+004 4.93E+004 -5.811E+003 2.379E+004 723.30 20.06 1.024E+005 -3.964E+004 4.620E+004 1274.43 34.80 5.887E+004 -2.842E+004 2.535E+004

 +      Eu-155        86.55*    30.70   5.952E+004    5.95E+004    9.195E+003  2.865E+D04 105.31     21.10   9.815E+004                -4.977E+004  4.747E+004 Tl-208       583.19     85.00   2.541E+004    2.54E+004   -1.080E+003  l.168E+004 Bi-212       727.33      6.67   2.890E+005    2.89E+005   -7.123E+004  1. 295E+005
 +      Pb-212       238.63*    43.60   2.666E+004    2.67E+004    2.585E+004  1.225E+004
 +      Bi-214       609.32*    45.49   2.829E+004    2.83E+004    7.824E+004  1.218E+004 1120.29      14. 92  1.864E+005                 2.019E+D05  8.437E+004 1764.49      15.30   2.043E+005                 3.975E+004  9.041E+004
 +      Pb-214       295.22*    18.42   6.753E+004    3.32E+004    3.128E+004  3.083E+004 351. 93

• 35.60 3.316E+004 5.097E+004 l.486E+004 Ra-226 186.21 3.64 4 .983E+005 4.98E+005 8.603E+004 2.381E+OOS Ac-228 338.32 11 .27 1.668E+005 8.60E+004 -1.231E+005 7.813E+004 911.20 25.80 8.603E+004 1.345E+004 3.853E+004 968.97 15.80 1 .608E+OOS 1.027E+005 7.281E+OD4 Am-241 59.54 35.90 7.167E+004 7.17E+004 2.521E+004 3.471E+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

[224]

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

Filename: 6279 Report Generated On 8/21/2018 9:14:46 AM Sample Title B109100AFSWC030GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/21/2018 9:04: 00 AM Acquisition Started 8/21/2018 9:04:45 AM Live Time 600.0 seconds Real Time 600.7 seconds Dead Time 0 ~12 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 7~2 --{(cl TIME // /2.~._L--.. 1/2,0:JA5Seog;t*>/l~PV t;,' ' /. I/ ~.J;; A I [225]

Peak Analysis Report 8/21/2018 9:14:46 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSWC030GD Peak Analysis Performed on: 8/21/2018 9:14:46 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 1 295- 307 301.06 75.39 0 .88 3.23E+001 49.66 2.21E+002 2 336- 345 34 0. 6 9 85.30 0 .76 2.86E+001 35.02 1.21E+002 3 2429- 2444 2436.12 609.13 0 .59 4.69E+001 18.29 l.21E+001 4 2639- 2650 2644.37 661.19 0 .56 1 .14E+001 12.75 1. 16E+O 01 5 5835- 5853 5844.22 1461.11 1. 67 7.91E+001 19.62 4 .88E+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 [226]

Interference Corrected Activity Report 8/21/2018 9:14:46 AM Page 3

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

Sample

Title:

B109100AFSWC030GD 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 8.58008E+005 2.25379E+005 Cs-137 1.000 661.66* 85.10 9.40813E+003 1. 05536E+O 04 ,,I i,-z!J,..,, .....,C"-. Eu-155 0.347 86.55* 30.70 2.33903E+004 A

2. 9 0 612 E+ 0 04 f'I"-"

                                                                                                  ~<...  +"vJ 105.31      21.10 Bi-214     0.461     609.32*     45.49      6.83586E+004   2.7872BE+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

[227]

Interference Corrected Activity Report 8/21/2018 9: 14 :46 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 1 . 000 8.580081E+005 2.253791E+OOS Cs-137 1 . 000 9.408133E+003 1.055357E+004 Eu-155 0.347 2.339032E+004 2.906120E+004 Bi-214 0.461 6.835859E+004 2.787280E+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: 8/21/2018 9:14:46 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 75.39 5.3841E-002 153.71 M = First peak in a multiplet region m  ::::; Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [228]

Nuclide MDA Report 8/21/2018 9 :14 :46 AM Page 5

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Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC030GD 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   1.767E+005    1 .77E+005   8.580E+005   7.370E+004 Co-60     1173.23      99.85   2.823E+004    1 . 71E+004  1.659E+004   1 .276E+004 1332.49      99.98   1.715E+004                -1.689E+OD2   7.111E+003 Nb-94       702.65     99.81   2.229E+004    1 .87E+004   2.124E+004   1 .016E+004 871.09     99.89   1.867E+004                -2.600E+003   8.210E+003 Ag-108m     433.90     90.50   1.926E+OD4    1.93E+004    5.360E+OD2   8.845E+003 614.30     89.80   3.289E+OD4                -1.273E+004   1 .544E+004 722.90     90.80   2.364E+004                 l. 527E+004  1.072E+004 Cs-134      604.72     97.62   2.958E+004    2.30E+004   -2.018E+003   1.38BE+004 795.86     85.46   2.299E+D04                 2.114E+004   1.025E+004
 +       Cs-137      661.66*    85.10   1.686E+D04    1.69E+004    9.408E+003   7.317E+003 Eu-152      121. 78    28.67   7.32BE+004    6.83E+004    l .122E+003  3.543E+004 344 .28    26.60   6.831E+004                -4.812E+004   3.189E+004 1408.01      21. 07  1 .19BE+005                4.90DE+004   5.268E+D04 Eu-154      123.07     40.40   5.149E+004    5.15E+004   -9.3BOE+003   2.488E+004 723.30     20.06   1.070E+005                 6.914E+004   4.853E+004 1274.43      34.80   7.106E+004                -1.964E+003   3.144E+004
 +       Eu-155       86. 55

• 30.70 4.715E+004 4. 71E+004 2.339E+004 2.247E+004 105. 31 21.10 1. 012E+005 2.115E+004 4.897E+004 Tl-208 583.19 85. 00 2.720E+004 2.72E+004 9.652E+003 1.258E+004 Bi-212 727.33 6.67 3.090E+005 3.09E+005 2.546E+005 1. 394E+005 Pb-212 238.63 43.60 4 .747E+004 4.75E+004 2.127E+004 2.266E+004

 +       Bi-214      609.32

• 45.49 3.296E+004 3.30E+004 6.836E+004 1.451E+004 1120. 29 14 .92 1 .808E+D05 3.667E+004 8.16DE+004 1764.49 15.30 1 .748E+005 1 .217E+005 7.564E+004 Pb-214 295.22 18.42 1 .033E+005 5.86E+004 1.056E+OOS 4 .869E+004 351.93 35.60 5.86DE+004 -3.813E+003 2.758E+004 Ra-226 186. 21 3.64 5.029E+005 5.03E+005 -l.964E+005 2.404E+005 Ac-228 338.32 11 .27 1.BOOE+005 8.60E+004 1.D22E+005 8.472E+004 911. 2 0 25.80 8.603E+D04 -1.159E+004 3.853E+004 968.97 15.80 l.460E+005 -9.556E+004 6.539E+004 Am-241 59.54 35.90 6.825E+OD4 6.83E+004 4 .711E+003 3.30DE+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

[229]

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

Filename: 6279 Report Generated On 8/21/2018 8:59:26 AM Sample Title B109100AFSWC031GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/21/2018 8:49:00 AM Acquisition Started 8/21/2018 8:49:24 AM Live Time 600.0 seconds Real Time 600.7 seconds Dead Time 0 . 12 % Energy Calibration Used Done*on 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM [230]

Peak Analysis Report 8/21/2018 8:59:26 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:

B109lOOAFSWC031GD Peak Analysis Performed on: 8/21/2018 8:59:25 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 1 296- 305 300.60 75.27 0.92 3.14E+001 42.00 1.79E+002 2 949- 959 954.12 238.65 0.37 6.26E+OOO 2 1 .04 4.37E+001 3 1173- 1188 1180 .22 295. 17 0.91 4.0lE+OOl 19.41 l.79E+001 4 1401- 1415 1407.89 352.08 0.47 4.92E+001 18.57 1.28E+001 5 2429- 2442 2436.07 609.12 1. 02 4.94E+001 15.48 3.63E+OOO 6 5838- 5853 5845. 21 1461. 35 0.93 5.56E+001 16.15 3.41E+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 [231]

Interference Corrected Activity Report 8/21/2018 8:59:26 AM Page 3

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Sample

Title:

B109100AFSWC031GD 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 6.02912E+005 1.82797E+005 Pb-212 1. 000 238.63* 43.60 4.97840E+003 1.67540E+004 Bi-214 0.461 609.32* 45.49 7.19054E+004 2.41419E+004 1120.29 14.92 1764 .49 15.30 Pb-214 1.000 295.22* 18.42 8.70849E+004 4.4376SE+004 351.93* 35.60 6.25823E+004 2.54022E+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

[232]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1 .000 6.029118E+005 1.827973E+005 Pb-212 1 .000 4.978403E+003 1.675402E+00 4 Bi-214 0.461 7.190540E+004 2.414193E+004 Pb-214 1.000 6.862954E+004 2.204584E+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: 8/21/2018 8:59:25 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 75.27 5.2381E-002 133.64 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [233]

Nucl i de MDA Report 8/21/2018 8:59:26 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC031GD 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 .399E+005    1 . 4DE+005  6.029E+005  5.529E+004 Co-60      1173.23      99.85   2.647E+004     1.96E+004    1. 167E+004 1.188E+004 1332.49      99.98   1 .960E+004                 6.018E+003  8.339E+003 Nb-94        702.65     99.81   2.142E+004     1.82E+004     8.16DE+002 9.726E+003 871.09     99.89   1 .821E+004                  7.389E+003 7.979E+003 Ag-108m      433.90     90.50   2.332E+004     2.33E+004    1.739E+D04  1. 088E+004 614.30     89.80   3.191E+004                 -l.27DE+004  l. 495E+004 722.90     90.80   2.364E+004                  4.479E+003  1. 072E+004 Cs-134       604.72     97.62   2.755E+004     2.30E+OD4    2.328E+004  1. 286E+004 795.86     85.46   2.299E+004                  8.770E+D03  1.025E+004 Cs-137       661.66     85.10   2.389E+004     2.39E+OD4   -2.315E+D02  1. 083E+004 Eu-152       121. 78    28.67   7.052E+004     6.49E+OD4   -2.273E+004  3.405E+004 344.28     26.60   6.489E+004                 -3.252E+004  3.018E+004 1408.01      21.07   9.681E+004                  2.026E+004  4.118E+004 Eu-154       123.07     40 .40  5.077E+004     5.08E+OD4    2.051E+004  2.452E+004 723.30     20.06   1.070E+005                  l .498E+004 4.853E+004 1274.43      34.80   5.688E+004                 -3.SD7E+004  2.435E+004 Eu-155        86.55     30.70   8.187E+004     8.19E+004    5.527E+004  3.984E+004 105 .31    21.10   9.815E+004                  3.641E+004  4.747E+004 Tl-208       583.19     85.00   2.769E+004     2.77E+004    1. 688E+OD4 1.282E+004 Bi-212       727. 33     6.67   3.230E+005     3.23E+OOS    2.921E+005  1.465E+005
 +       Pb-212       238.63*    43.60   2.889E+004     2.89E+OD4    4.978E+003  1.337E+004
 +       Bi-214       609.32*    45.49   1. 948E+004    l .95E+004   7.191E+004  7.768E+003 1120.29      14.92   1. 722E+O 05                1 .152E+005 7.726E+004 1764.49      15.30   1 . 902E+005                3.42SE+004  8.335E+004
 +       Pb-214       295.22*    18.42   5.839E+004     2.89E+004    8.708E+004  2.626E+004 351. 93

• 35.60 2.889E+004 6.258E+004 1 .272E+004 Ra-226 186.21 3.64 5.542E+005 5.54E+005 5.285E+OOS 2.660E+005 Ac-228 338.32 11. 27 1. 524E+005 1.D3E+OOS 1.271E+005 7.094E+004 911. 2 0 25.80 1. 027E+005 -1.135E+005 4.688E+D04 968.97 15.80 1.536E+005 -2.811E+003 6.920E+OD4 Am-241 59.54 35.90 6.937E+004 6.94E+OD4 3.287E+004 3.356E+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

[234]

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

Filename: 6279 Report Generated On 8/21/2018 8:47:24 AM Sample Title B109100AFSWC032GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/2l/201B 8:J.7: 00 AM Acquisition Started 8/21/2018 8:.37:22 AM Live Time 600.0 seconds Real T ime 600.7 seconds Dead Time 0 . 11 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE °f 2-/0 [235] g,~:~ TIME f J~

Peak Analysis Report 8/21/2018 8:47:24 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:

B109100AFSWC032GD Peak Analysis Performed on: 8/21/2018 8:47:24 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 1 245- 255 251.04 62.89 0 .79 2.0BE+OOl 3 1. 63 9.63E+001 2 290- 305 300.53 75.26 0 .75 1 .10E+002 55.09 2.14E+002 3 949 - 961 955.13 238.90 1. 31 2.59E+001 23.28 4.llE+OOl 4 1400- 1413 1407. 3 9 351. 96 0 .85 4.25E+001 19. 81 1.95E+001 5 2430- 2443 2435.96 609.09 0 .69 3.27E+001 1 7.11 1.43E+001 6 5838- 5853 5844.85 1461. 26 0 .69 4.62E+001 1 5.48 4.82E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F "' Fitted singlet Errors quoted at 2.000 sigma [236]

Interference Corrected Activity Report 8/21/2018 8:47:24 AM Page 3

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

Sample

Title:

B109100AFSWC032GD 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 5.00764E+005 1.73364E+OOS Pb-212 1.000 238.63* 43.60 2.06293E+004 1. 88283E+004 Bi-214 0.461 609.32* 45.49 4.75834E+004 2.55744E+004 1120.29 14. 92 1764.49 15.30 Pb-214 0 .4 3 2 295.22 18.42 351.93* 35.60 5.4002SE+004 2.64462E+004 Am- 241 0. 982 59.54* 35.90 1 . 67109E+004 2.56916E+004

       *=Energy line found i n t he spectrum.
       @=Energy line not use d for Weighted Mean Activity Energy Tolerance :     10.000 keV Nuclide confidence index threshold =         0 .30 Errors quoted at 2. 000 sigma

[237]

Interference Corrected Activity Report 8/21/2018 8:47:24 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 5.007637E+005 l.733644E+005 Pb-212 1. 000 2.062930E+004 1.882828E+004 Bi-214 0.461 4.758337E+004 2.557435E+00 4 Pb-214 0.432 5.400247E+004 2.644615E+00 4 Am-241 0 .982 1 .671089E+004 2.569156E+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: 8/21/2018 8:47:24 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 2 75.26 1.8402E-001 49.89 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [238]

Nuclide MDA Report 8/21/2018 8:47:24 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC032GD 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   1.614E+005     1.61E+005 5.008E+005      6.602E+004 Co-60      1173.23      99.85   2.248E+004     l.42E+004 -1.872E+004     9.885E+003 1332.49      99.98   l.417E+004                 5.404E+003    5.622E+003 Nb-94        702.65     99.81   1.711E+004     l.71E+004 -9.279E+003     7.572E+003 871.09     99.89   2.309E+004                 l .24BE+003   1.042E+004 Ag-108m      433.90     90.50   l .820E+004    l.82E+004 l .595E+003     8.315E+003 614.30     89.80   3.048E+004                -6.758E+003    1.424E+004 722.90     90.80   2.525E+004                 1 .332E+004   l.152E+004 Cs-134       604.72     97.62   2.736E+004     2.63E+004 -2.647E+004     1. 277E+004 795.86     85.46  2.629E+004                  1 .585E+004   1. 19 OE+004 Cs-137       661.66     85.10  2.645E+004      2.65E+004 7.254E+003      1. 211E+004 Eu-152       121.78     28.67   7.001E+004     7.00E+004 1.312E+004      3.379E+004 344.28     26.60   7.156E+004                -3.022E+004    3.351E+004 1408.01      21.07   1. 005E+005               -l.779E+003    4.302E+004 Eu-154       123.07     40.40  4.950E+004      4 .9SE+004 5.964E+004     2.389E+004 723.30     20.06   1. 129E+O 05               7.913E+003    5.147E+004 1274.43      34.80   5.887E+004                 1.557E+004    2.535E+004 Eu-155        86.55     30.70   7.753E+004     7.75E+004 2.319E+004      3.766E+004 105.31     21.10   9.831E+004                -8.242E+004    4.755E+004 Tl-208       583.19     85.00  2.793E+004      2.79E+004 2.271E+003      1.294E+004 Bi-212       727.33      6.67  3.408E+005      3.41E+005 l.683E+005      1.553E+005
 +      Pb-212       238.63*    43.60  2.957E+004      2.96E+004 2.063E+004      l.371E+004
 +      Bi-214       609.32*    45.49  3.446E+004      3.45E+004 4.758E+004      1.526E+004 1120.29      14.92   l .722E+005                1 .434E+004   7.726E+004 1764.49      15.30   1. 801E+OOS                1. 3 03E+O 05 7.829E+004
 +      Pb-214       295.22     18.42   1 .127E+005    3.46E+004 8.796E+004      5.343E+004 351. 93

• 35.60 3.463E+004 5.400E+004 l.560E+004 Ra-226 186.21 3.64 5.501E+005 5.SOE+005 8.630E+005 2.640E+OOS Ac-228 338.32 11. 27 l .790E+005 9.34E+004 7.820E+003 8.423E+004 911.20 25.80 9.339E+004 7.683E+004 4.221E+004 968.97 15.80 1.608E+OOS -1. 24 3E+005 7.281E+004

 +      Am-241        59. 54*   35.90  4.230E+004      4.23E+004 l.671E+004      2.006E+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

[239]

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

Filename: 6279 Report Generated On 8/18/2018 3:18:02 PM Sample Title B109100AFSWC033GD Sample Description WWTF WALL Sample Identification 033 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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

                                     -Z. ,8-?

Sample Size .2... Q2G;e+001 M"2 Sample Taken On 8/1872018 ffe--- o/?3:07:00 rl, r PM Acquisition Started 8/18/2018 3:08:00 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE ~yo

                                                                           ~

[240] TIM~o an~s- 'P?-~ .

Peak Analysis Report 8/18/2018 3: 18 :02 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:

B109100AFSWC033GD Peak Analysis Performed on: 8/18/2018 3:18:02 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- 305 300.92 75.36 1.09 5.24E+001 43.72 1.76E+002 2 334- 344 338.14 84.66 0. 97 4. 14E+001 36.90 1.25E+002 3 946- 958 953. 3 5 238.46 o. ss 3.76E+001 23.76 3.84E+001 4 2430- 2444 2437.29 609.42 0. 52 3.49E+001 14.87 7.13E+OOO 5 5836- 5853 5844.75 1461.24 1. 25 6.36E+001 18.36 6.35E+OOO M = First peak in a multiplet region rn Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2.000 sigma [241]

Interference Corrected Activity Report B/18/2018 3:18:02 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:

B109100AFSWC033GD 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 6.91186E+OOS 2.08212E+005 .if') v~~

                                                                             'y ~

Eu-155 0.346 86.55* 30.70 3.40765E+004 3. 11 257E+004 ~~ \I' V' 105.31 21.10 Pb-212 1.000 238.63* 43.60 2.99483E+004 1 .95238E+004 Bi-214 0.461 609.32* 45.49 5.08765E+004 2.25397E+004 1120.29 14.92 1764.49 15.30

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

[242]

Interference Corrected Activity Report 8/18/2018 3:18:02 PM Page 4

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

Nuclide wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 Eu-155

1. 000 0 .346 6.911858E+005 3.407655E+004 2.082116E+005 3 . 112574E+004 f._r/"

                                                                                ~~f} ~~

Pb-212 1 . 000 2.994829E+0 0 4 1 .952379E+004 Bi-214 0.461 5.087648E+004 2.25397DE+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: 8/18/2018 3:18:02 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. 3 6 8.7288E-002 83.48 M "" First peak in a multip let region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [243]

Nuclide MDA Report 8/18/2018 3: 18: 02 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109l00AFSWC033GD 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  1.916E+005     1 .92E+005  6.912E+005   8.111E+004 Co-60      1173.23     99.85   2.251E+004     2.24E+004   l.248E+004   9.899E+003 1332.49     99.98   2.243E+004                -5.051E+002   9.751E+003 Nb-94        702.65    99.81   1 .751E+004    1 .75E+004 -3.280E+003   7.770E+003 871.09    99.89   2.163E+004                -2.083E+003   9.690E+003 Ag-108m      433.90    90.50   2.142E+004     2.14E+004  -2.758E+003   9.926E+003 614.30    89.80   3.031E+004                 2.522E+003   l.415E+004 722.90    90.80   2.466E+004                 1.774E+004   1.122E+004 Cs-134       604 . 72  97.62   2.701E+004     2.70E+004  -1.995E+004   1.259E+004 795.86    85.46   2.818E+004                 6.595E+003   1.284E+004 Cs-137       661.66    85. 10  2.824E+004     2.82E+004   2.741E+004   1 .301E+004 Eu-152       121.78    28.67   7 . 177E+004   6.45E+004   4.172E+004   3.467E+004 344.28    26.60   6.447E+004                -7.921E+004   2.997E+004 1408.01     21.07   8.481E+004                -7.483E+004   3.517E+004 Eu-154       123.07    40.40   4.957E+004     4.96E+004  -2,307E+004   2.392E+004 723. 3 0  20.06   1.102E+005                 5.360E+004   5.009E+004 1274.43     34.80   6.272E+004                 2.381E+004   2.727E+004
 +      Eu-155        86.55*   30.70   4 .905E+004    4.90E+004   3.408E+004   2.341E+004 105 .31   21.10   1 .013E+005                4.342E+004   4.904E+004 Tl-208       583.19    85.00   2.891E+004     2.89E+004   4.397E+004   1.343E+004 Bi-212       727.33     6.67   3.142E+005     3.14E+005  -8.971E+004   1.420E+005
 +      Pb-212       238.63*   43.60   2.880E+004     2.88E+004   2.995E+004   1.332E+004
 +      Bi-214       609.32*   45.49   2.563E+004     2.56E+004   5.088E+004   1.084E+004 1120.29     14 .92  1.839E+005                -5.436E+002   8.311E+004 1764.49     15 .30  1.638E+005                 1 .044E+005  7.013E+004 Pb-214       295.22    18.42   1.065E+005     5.71E+004   3.172E+004   5.031E+004 351.93    35.60   5.707E+004                 3.655E+003   2.681E+004 Ra-226       186.21     3.64   5.169E+005     5.17E+005  -2.510E+005   2.474E+005 Ac-228       338.32    11.27   1.743E+005     9.35E+004   4.046E+004   8.186E+004 911.20    25.80   9.352E+004                 4.982E+004   4.227E+004 968.97    15.80   1.611E+005                 1.745E+005   7.291E+004 Am-241        59.54    35.90   6.914E+004     6.91E+004   5.788E+003   3.344E+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

[244]

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

Filename: 6279 Report Generated On 8/18/2018 3:05:45 PM Sample Title B109100AFSWC034GD Sample Description WWTF WALL Sample Identification 034 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 z:~l

                                   --i2-:---926E'+O 01 MA2 .
                                            ,rk,.._. zr/2- ?-/19 Sample Taken On                    8/18/2018              2:55:00 PM Acquisition Started                8/18/2018              2:55:44 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE ~Z:f~ TIME ; - {2, r111s1:e~1/4 .vii [245]

Peak Analysis Report 8/18/2018 3:05:45 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:

Bl09100AFSWC034GD Peak Analysis Performed on: 8/18/2018 3:05:45 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- 305 300.16 75.17 0.83 3.99E+001 4 1 .13 1.69E+002 2 335- 345 339.90 85. 10 0.52 2.79E+001 39.17 l.48E+002 3 753- 764 758.71 189.80 0.39 3.13E+001 2 1 .16 3. 17E+001 4 949- 961 954.68 238.79 0.63 4 .21E+001 22.95 3.39E+001 5 1176- 1187 1181.55 295.50 0.35 1 . 34E+001 18.49 2.86E+001 6 1401- 1413 1407. 45 35 1 .97 0.62 4. 17E+001 18.43 1 .63E+001 7 2430- 2443 2436.01 609. 10 1. 09 2 . 46E+001 17.72 1 .94E+001 8 2641- 2652 2646.62 661.75 0.96 1 .78E+001 11. 99 7.25E+OOO 9 5835- 5854 5845.20 1461 .35 0.93 8.25E+001 19. 11 2.50E+OOO M = Fi rst peak in a multiplet region rn = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [246]

Interference Corrected Activity Report 8/18/2018 3:05:46 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:

B109100AFSWC034GD 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 8.95951E+OOS 2.21696E+OOS Cs-137 1.000 661.66* 85.10 l.46329E+004 1. 00 411E+004 Eu-155 0.347 86.55* 30.70 2.29397E+004 3.24827E+004 105.31 21.10 Pb-212 1. 000 238.63* 43.60 3.35273E+004 1.90744E+004 Bi-214 0 . 461 609.32* 45.49 3.58838E+004 2.62092E+004 1120.29 14.92 1764.49 15.30 Pb-214 1 .000 295.22* 18.42 2.91011E+004 4 .04762E+004 351.93* 35.60 S.3020SE+004 2.47697E+004 Ra-226 0.980 186.21* 3.64 2.58357E+005 1 .80129E+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

[247]

Interference Corrected Activity Report 8/18/2018 3:05:46 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 8.959507E+005 2.216963E+005 Cs-137 1. 000 1.463286E+004 1.004108E+004 Eu-155 0 .347 2.293970E+004 3.248269E+004 Pb-212 1. 000 3.352726E+004 1.907436E+004 Bi-214 0.461 3.588383E+004 2.620922E+004 Pb-214 1 .000 4.650350E+004 2.112760E+004 Ra-226 0.980 2.583573E+005 1.801293E+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

[248]

Interference Corrected Activity Report 8/18/2018 3:05:46 PM Page 5

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

Peak Locate Performed on: 8/18/2018 3:05:45 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 75.17 6.6445E-002 103.17 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [249]

Nuclide MDA Report 8/18/2018 3:05:46 PM Page 6

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC034GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/MA2 )

 +      K-40       1460.82*  10.66   1. 357E+005     1.36E+005  8.960E+005  5.314E+004 Co-60      1173.23   99.85   2.784E+004      2.43E+004  2.908E+004  1 .256E+004 1332.49   99.98   2.429E+004                 9.800E+003  1 .068E+004 Nb-94       702.65   99.81   2.055E+004      2.05E+004 -3.735E+003  9.287E+003 871.09   99.89   2.163E+004                -3.240E+003  9.690E+003 Ag-108m     433.90   90.50   2.142E+004      2.14E+004 -3.258E+003  9.926E+003 614.30   89.80   3.155E+004                -6.598E+002  1 .477E+004 722.90   90.80   2.590E+004                -4.914E+003  1 .185E+004 Cs-134      604.72   97.62   2.980E+004      2.21E+004 -7.290E+003  1 .399E+004 795.86   85.46   2.211E+004                -5.981E+003  9.810E+003
 +      Cs-137      661.66*  85. 10  1. 380E+004     1.38E+004  1. 463E+004 5.786E+003 Eu-152      121.78   28.67   7.202E+004      7.03E+004  7.503E+003  3.479E+004 344.28   26.60   7.029E+004                 1. 493E+004 3.287E+004 1408 .01  21.07   7.538E+004                -3.341E+003  3.046E+004 Eu-154      123.07   40 .40  5.165E+004      5.16E+004  4.769E+004  2.496E+004 723.30   20.06   1. 173E+005                2.701E+004  5.365E+004 1274.43   34.80   6.451E+004                 4.842E+004  2.816E+004
 +      Eu-155       86.55*  30.70   5.316E+004      5.32E+D04  2.294E+OD4  2.547E+004 105 .31  21. 10  1.053E+OOS                 8.226E+003  5.103E+004 Tl-208      583.19   85.00   2.724E+004      2.72E+004  2.359E+004  1. 259E+004 Bi-212      727. 33   6.67   3.540E+005      3.54E+OOS  2.159E+005  1.619E+005
 +      Pb-212      238.63*  43.60   2.697E+004      2.70E+004  3.353E+004  1.241E+004
 +      Bi-214      609.32*  45.49   3.919E+004      3.92E+004  3.588E+004  1.762E+004 1120.29   14 .92  1.866E+005                -3.524E+003  8.449E+004 1764.49   15 .30  1. 9 05E+O 05              7.589E+004  8.347E+004
 +      Pb-214      295.22*  18 .42  6.663E+004      3.10E+004  2.910E+004  3.037E+004 351.93*  35.60   3. 100E+004                5.302E+004  1 .378E+004
 +      Ra-226      186.21*   3.64   2.663E+005      2.66E+005  2.584E+005  1 .220E+005 Ac-228      338.32   11. 27  1.561E+005      9.21E+004  3.283E+004  7.276E+004 911 .20  25.80   9.210E+004                -2.151E+004  4.156E+004 968.97   15.80   1.702E+005                -4.520E+004  7.748E+004 Am-241       59.54   35.90   6.991E+004      6.99E+004  1 .616E+004 3.383E+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

[250]

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

Filename: 6279 Report Generated On 8/22/2018 9:03:27 AM Sample Title B109100AFSWC035GD Sample Description WWTF WALL Sample Identification 035 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 z 'f'J

                                  <~.926E+001 M"2 j?,ik'1 8/22/2018 r(ir/1~

8:53:00 Sample Taken On AM Acquisition Started 8/22/2018 8:53:26 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 1,2-1/' TIME~ g, 11,_~l 141 kf1 [251]

Peak Anal ysis Report 8/22/2018 9:03:28 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:

B109100AFSWC035GD Peak Analysis Performed on: 8/22/2018 9 ; 03:27 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- 305 300.10 75.15 0.66 3.99E+001 42.21 1.79E+002 2 334- 344 339.29 84.95 0.30 1.83E+001 36.63 1.32E+002 3 950 - 960 954.73 238.80 0.74 9.87E+OOO 22.21 4.71E+001 4 1402- 1415 1407.92 352.09 0.65 3.93E+001 18.50 1.68E+001 5 2429 - 2444 2436.75 609.28 0.47 4. llE+OOl 17.52 1.19E+001 6 5838 - 5857 5847.05 1461 .81 1. 81 8.63E+001 2 1. 38 7 . 74E+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 [252]

Interference Corrected Activity Report 8/22/2018 9: 0 3 : 28 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:

B109100AFSWC035GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB A "' * * * * * * *

• ii * * * * * * * *
• IDENT IFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2) Uncertainty K-40 0 .998 1460.82* 10.66 9.3701SE+OOS 2. 46039E+005 J4c..-2 "'2-8~9-Eu-155 0 .347 86.55* 30.70 1. 50768E+004 3. 02458E+004 105.31 21 .10 Pb-212 1.000 238.63* 43.60 7.86601E+003 1.77417E+004 Bi-214 0.461 609.32* 45.49 6.00195E+004 2.65649E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 4 .99710E+004 2.47116E+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

[253]

Interference Corrected Activity Report 8/22/2018 9:03:28 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. 998 9.370152E+005 2.460395E+005 Eu-155 0. 347 l .507678E+004 3.024578E+004 Pb-212 1.000 7.866005E+003 1 .774173E+004 Bi-214 0.461 6.001952E+004 2.656490E+004 Pb-214 0. 432 4 .997097E+004 2.471161E+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: 8/22/2018 9:03:27 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 .15 6.6495E-002 105.79 M == First peak in a multiplet region m ~ Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma [254]

Nuclide MDA Report 8/22/2018 9 : 03:28 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC035GD 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/MA2 ) (pCi/M"2 ) (pCi/M"2 )

 +      K-40       1460.82*    10.66   2.184E+OOS   2.18E+005 9.370E+OOS     9.450E+004 Co-60      1173.23     99.85   2.358E+004   1 .96E+004 -3.824E+003   1. 043E+004 1332.49     99.98   1.963E+004              -4.600E+003   8.350E+003 Nb-94        702.65    99.81   1.788E+004   1 .79E+004 2.418E+003    7.953E+003 871.09    99.89   2.043E+004              -2.749E+004   9.090E+003 Ag-108m      433.90    90.50   2.067E+004   2.07E+004 -5.388E+003    9.552E+003 614. 3 0  89.80   3.052E+004              -2.759E+004   1. 426E+004 722.90    90.80   2.367E+004               3.963E+003   1. 073E+004 Cs-134       604.72    97.62   3.033E+004   2.35E+004 7.440E+003     1. 425E+004 795.86    85.46   2.347E+004               2.876E+003   1. 049E+004 Cs-137       661. 66   85.10   2.618E+004   2.62E+004 1. 212E+004    1. 198E+004 Eu- 152      121.78    28.67   7.088E+004   6.74E+004 -3.371E+004    3.422E+004 344.28    26.60   6.745E+004              -3.414E+004   3.145E+004 1408.01     21.07   1.041E+005               6.949E+004   4.484E+004 Eu-154       123. 07   40.40   S.111E+004   5.11E+004 7.479E+003     2.469E+004 723.30    20.06   1.041E+OOS              -4.388E+004   4.705E+004 1274.43     34.80   5.271E+004              -1. 589E+004  2.226E+004
 +      Eu-155         86.55*  30.70   S.036E+004   S.04E+004 l. 508E+004    2.407E+004 1 05.31   21.10   1.032E+OOS              -1. 411E+004  4.997E+004 Tl-208       583.19    85.00   2.436E+004   2.44E+004 1. SSOE+004    1.11SE+004 Bi-212       727.33     6.67   2.996E+OOS   3.00E+OOS 2.241E+005     1.347E+005
 +      Pb-212       238.63*   43.60   3.008E+004   3.01E+004 7.866E+003     1.396E+004
 +      Bi-214       609.32*   45.49   3.260E+004   3.26E+004 6.002E+004     1.433E+004 1120. 29    14.92   2.143E+OOS               2.740E+005   9.834E+004 1764.49     15.30   1.BSSE+OOS               1. 392E+005  8.098E+004
 +      Pb-214       295.22    18.42   1.119E+005   3.20E+004 1. 381E+005    5.303E+004 351.93*   35.60   3.195E+004               4.997E+004   1.425E+004 Ra-226       186.21     3.64   5.384E+OOS   S.38E+005 l. 575E+005    2.581E+OOS Ac-228       338.32    11. 27  1.617E+005   1.16E+OOS 9.383E+004     7.555E+004 911. 20   25.80   1.159E+OOS               l.120E+OOS   S.347E+004 968.97    15.80   1.563E+OOS               7.444E+004   7.052E+004 Am-241        59.54    35.90   7.284E+004   7.28E+004 2.666E+003     3.529E+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

[255]

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

Filename: 6279 Report Generated On 8/22/2018 9:22:53 AM Samp le Title B109100AFSWC036GD Samp le Description WWTF WALL Sample Identification 036 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) BS - 8192 Identification Energy Tolerance 10.000 keV 7,8'> Sample Size *~+001

                                         ;l.,_

Sample Taken On 8/22/2018 9:13:00 AM Acquisition Started 8/22/2018 9:12:52 AM Live Time 600. 0 seconds Real Time 600.7 seconds Dead Time 0.12 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA .VALIDATED DATE J-2-t e, (2.. TIME ;,1 I5 [256] ,,~~

Peak Analysis Report 8/22/2018 9:22:53 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSWC036GD Peak Analysis Performed on: 8/22/2018 9:22:53 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 282- 305 300.76 75.32 1.16 1.92E+002 73.95 2.94E+002 2 1402- 1415 1407.76 352.05 1. 01 3.35E+001 19.46 2.15E+001 3 2035- 2046 2040.69 510.28 0 .67 2.72E+001 15.04 1. 0BE+OOl 4 2428- 2444 2436.69 609.27 0 .50 5.33E+001 18.05 8.73E+OOO 5 5837- 5853 5845.23 1461.36 1. 14 6.20E+001 19.78 1.lOE+OOl M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [257]

Interference Corrected Activity Report 8/22/2018 9:22:53 AM Page 3

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Sample

Title:

B109100AFSWC036GD 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 6.73570E+005 2.22673E+005 Bi-214 0.461 609.32* 45.49 7,77062E+004 2.79427E+004 1120.29 14.92 1764.49 15.30 Pb-214 0 .432 295.22 18.42 351.93* 35.60 4.26239E+004 2.55848E+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

[258]

Interference Corrected Activity Report 8/22/2018 9:22:53 AM Page 4

• • • • • IN T"E RF ERE NC 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 6.735699E+005 2.226733E+005 Bi-214 0.461 7.770615E+004 2.794270E+004 Pb-214 0.432 4.262394E+004 2.558476E+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 AK S      **********

Peak Locate Performed on: 8/22/2018 9:22:53 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 75.32 3.2006E-001 38.51 3 510.28 4.5340E-002 55.27 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 [259]

Nuclide MDA Report 8/22/2018 9:22:53 AM Page 5

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Detector Name: 6279 Sample Geometry: 3M90 DWWTF1.27CM Sample

Title:

B109100AFSWC036GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/M ... 2 ) (pCi/M ... 2 ) (pCi/MA2) (pCi/M"2 )

 +      K-40        1460.82*     10 .66  2.432E+005      2.43E+OOS       6.736E+005  l .069E+005 Co-60       1173.23      99. 85  2.696E+004      1.30E+004       1 .827E+004 1 .212E+004 1332.49      99.98   1. 300E+004                   -5. 411E+003  5.035E+003 Nb - 94       702.65     99. 81  1. 859E+004     1.86E+004     -5.033E+003   8.306E+003 871.09     99.89   2.202E+004                      1.554E+004  9.882E+003 Ag-108m       433.90     90.50   2.105E+004      2.11E+004     -7.649E+002   9. 741E+003 614 .30    89.80   3.351E+004                    -1.664E+D04   1 .575E+004 722.90     90.80   2.299E+004                    -4.098E+003   1.039E+004 cs-134        604.72     97.62   3.101E+004      2.75E+004     -6.707E+003   1.459E+004 795.86     85.46   2.746E+004                      5.981E+003  1.248E+004 Cs-137        661 .66    85.10   2.216E+004      2.22E+004     -2.969E+003   9.965E+003 Eu-152        121. 78    28.67   7.326E+004      7.33E+004       5.085E+004  3.542E+004 344.28     26.60   7.563E+004                      2.599E+004  3.554E+004 1408 .01     21. 07  8.907E+004                    -1 .336E+003  3.730E+004 Eu-154        123.07     40.40   5.048E+004      5.0SE+004       5.635E+003  2.438E+004 723.30     20.06   1.025E+OOS                    -6.650E+004   4.626E+004 1274.43      34.80   5.271E+004                    -1 .589E+004  2.226E+004 Eu-155         86.55     30.70   8.253E+004      8.25E+004       7.067E+D04  4.016E+004 105 . 31   21.10   1.025E+005                      3.122E+004  4.966E+004 Tl-208        583.19     85.00   3.027E+004      3.03E+004       2.985E+004  1.411E+004 Bi-212        727.33      6.67   3.189E+005      3.19E+005     - 2.058E+004  1.444E+005 Pb-212        238.63     43.60   4.708E+004      4 .71E+004      4.779E+004  2.246E+004
 +      Bi-214        609.32*    45. 4 9 2.944E+004      2.94E+004       7.771E+004  1 .274E+004 1120 .29     14.92   1.632E+005                    -9.238E+004   7.277E+004 1764 .49     15.30   l.578E+005                      9.572E+004  6.714E+004
 +      Pb-214        295.22     18.42   1.055E+005      3.62E+004       8.687E+004  4.980E+OD4 351. 93

• 35.60 3.622E+004 4.262E+004 1 .639E+004 Ra-226 186.21 3.64 5.412E+005 5.41E+005 3.480E+005 2.595E+005 Ac-228 338.32 11.27 1.763E+005 8.92E+004 1.032E+005 8.286E+004 911 .20 25.80 8.918E+004 6.767E+004 4.010E+004 968.97 15.80 1.611E+005 -2.433E+004 7.291E+004 Am-241 59.54 35.90 6.958E+004 6.96E+004 2.725E+003 3.367E+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

[260]

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

Filename: 5452A Report Generated On 8/16/2018 3:30: 51 PM Sample Title Bl09100AFSFC045GD Sample Description WWTF SUMP #2 Sample Identification 045 Sample Type GAMMA DIRECT Sample Geometry WWTF SUMP 2 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 4.270E+OOO M"2 Samp le Taken On 8/16/2018 3:20:00 PM Acquisition Started 8/16/2018 3:20:49 PM Live Time 600. 0 seconds Real Time 601 . 4 seconds Dead Time 0 . 23 % Energy .calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 8/16/2018 Efficiency ID WWTF SUMP 2 [261]

Peak Analysis Report 8/16/2018 3: 30: 51 PM Page 2

• • • • • P E A K ANALYS I s R E P O R T *****

Detector Name: 5452A Sample

Title:

B109100AFSFC045GD Peak Analysis Performed on: 8/16/2018 3:30: 51 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- 308 300.96 75.24 0.71 1.12E+002 89.24 6.81E+002 2 945- 960 953.51 238.38 0.99 1.13E+002 57.71 2.40E+002 3 1169- 1190 1178 .86 294.71 1. 00 1.60E+002 55.17 1 .58E+002 4 1398 - 1412 1406 . 15 351.54 1.18 2.13E+002 4 1. 96 7.89E+001 5 2030- 2049 2038.51 509.63 0.85 7.03E+001 40.74 9.77E+001 6 2322 - 2336 2328.49 582.12 1. 10 7.78E+001 26.37 3.32E+001 7 2423 - 2441 2433.14 608.29 1 .48 1.93E+002 40.13 6.18E+001 8 2634- 2650 2642.35 66 0 .59 1. 49 9.0SE+OOl 29.09 3.85E+001 9 3430- 3443 3436.84 859.21 0 .30 1.15E+001 17.77 2.45E+001 10 3631- 3648 3639.05 909.76 0 .83 7.86E+001 28.59 3.84E+001 11 3865- 3878 3871.59 967.90 0 .39 4.13E+001 19.26 1.87E+001 12 4466- 4481 4473.74 111 8.44 0 .59 6.94E+001 24.19 2.56E+001 13 4681- 4694 4687.32 11 71. 83 1. 02 2.52E+001 16.57 1.58E+001 14 4941- 4955 4947.68 1236.92 0 .30 3.38E+001 19. 11 1.92E+001 15 5316- 5329 5322.82 133 0 .70 1. 27 2.65E+001 13. 13 5.48E+OOO 16 5822- 5850 5836.81 1459.20 1. 75 5.39E+002 49.89 l.80E+001 17 7041- 7060 7051.05 1762.76 0.32 5.25E+001 19.65 1.2SE+001 M ;;::: Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [262]

Interference Corrected Activity Report 8/16/2018 3: 30: 52 PM Page 3

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Sample

Title:

B109100AFSFC045GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• IDENTIFIED NUCLIDES * .. .. ~. * * * * * * * * .. ... .. * ... ill ... ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"'2 ) Uncertainty K-40 0.996 1460.82* 10.66 8.01007E+005 1.01663E+005 Co-60 0.996 1173.23* 99.85 3.47909E+003 2.30104E+003 1332.49* 99.98 3.94713E+003 1.97978E+003 Cs-137 0.998 661.66* 85. 10 1. 02980E+004 3.53259E+003 Tl-208 0.998 583.19* 85.00 8.17113E+003 2.93836E+003 Pb-212 1 . 000 238.63* 43.60 1 .27190E+004 6.80119E+003 Bi-214 0.997 609.32* 45.49 3.90008E+004 9.35890E+003 1120.29* 14.92 6.22001E+004 2.22554E+004 1764.49* 15.30 6.21565E+004 2.38028E+004 Pb-214 1.000 295.22* 18.42 4.89890E+004 1.86451E+004 351.93* 35.60 3.80631E+004 9.65729E+003 Ac-228 0.560 338.32 11. 27 911.20* 25.80 3.59104E+004 1 .34431E+004 968.97* 15.80 3.20606E+004 1 .52080E+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

[263]

Interference Corrected Activity Report 8/16/2018 3: 30 : 52 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.996 8.010073E+005 1.016631E+005 Co-60 0.996 3.748039E+003 1.500754E+003 Cs-137 0.998 1.029804E+004 3.532585E+003 Tl-208 0.998 8 .1 71125E+003 2.938360E+003 Pb - 212 1.000 1.271902E+004 6.80118SE+003 Bi-214 0 .997 4.477072E+004 B.110820E+003 Pb-214 1 .000 4.037420E+004 8.575279E+003 Ac-228 0.560 3.422173E+004 1. 007215E+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

[264]

Interference Corrected Activity Report 8/16/2018 3:30:52 PM Page S

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

Peak Locate Performed on: 8/16/2018 3:30:51 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 1. 8630E-001 79.83 5 509.63 1. 1712E-001 57.98 9 859.21 1.9167E-002 154.50 14 1236.92 5.6297E-002 56.58 Sum M ;;: First peak in a multiplet region m -= Other peak in a multip let region F - Fitted singlet Errors quoted at 2.000 sigma [265]

Nuclide MDA Report 8/16/2018 3:30:52 PM Page 6

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

Detector Name: 5452A Sample Geometry: WWTF SUMP 2 Sample

Title:

B109100AFSFC045GD 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  4.863E+004    4.86E+004   8.0lOE+OOS   2.230E+004
 +       Co-60     1173.23*     99.85  3.361E+003    2.40E+003   3.479E+003   l.494E+003 1332.49*     99.98  2.397E+003                3.947E+003   9.971E+002 Nb-94       702.65     99.81  5.141E+003    5.14E+003  -2.917E+003   2.434E+003 871.09     99.89  5.455E+003                5.062E+003   2.572E+003 Ag-108m     433.90     90.50  5.711E+003    5.71E+003  -1.925E+003   2.746E+003 614. 3 0   89.80  8.174E+003               -l.710E+002   3.948E+003 722.90     90.80  6.163E+003                2.159E+003   2.929E+003 Cs-134      604.72     97.62  8.421E+003    6.42E+003   1.778E+004   4.084E+003 795.86     85.46  6.420E+003                6.277E+002   3.038E+003
 +       Cs-137      661.66*    85. 10 4 .425E+003   4.42E+003   1.030E+004   2.059E+003 Eu-152      121.78     28.67  2.043E+004    1.87E+004  -1.129E+004   1.005E+004 344. 2 8   26.60  l .872E+004              -3.437E+004   9.042E+003 1408.01      21. 07 2.304E+004               -3.703E+004   1.053E+004 Eu-154      123.07     40.40  1 .455E+004   1 .45E+004 -4.42SE+002   7.153E+003 723. 3 0   20.06  2.791E+004                1 .621E+004  l.326E+004 1274.43      34.80  1.663E+004               -1.131E+OD3   7.750E+003 Eu-155       86.55     30.70  2.138E+004    2.14E+004   1.950E+004   1.054E+004 105.31     21.10  2.917E+004               -2.036E+OD4   l .436E+004
 +       Tl-208      583.19*    85. 00 3.669E+003    3.67E+003   8.171E+003   1 .692E+003 Bi-212      727. 3 3    6.67  8.061E+004    8.06E+004   4.451E+004   3.822E+004
 +       Pb-212      238.63*    43.60  1 .022E+004   1.02E+D04   1.272E+004   4.957E+003
 +       Bi-214      609.32*    45.49  1 .016E+004   1.02E+004   3.900E+004   4.805E+003 1120.29*     14.92  2.830E+004                6.220E+004   1.294E+004 1764.49*     15.30  2.907E+004                6.216E+004   1.293E+004
 +       Pb-214      295.22*    18.42  2.556E+004    9.34E+003   4.899E+004   1.237E+004 351. 93

• 35.60 9.336E+003 3.806E+004 4 .426E+003 Ra-226 186.21 3.64 1.524E+005 1.52E+005 l.314E+004 7.464E+004

 +       Ac-228      338.32     11. 27 4.837E+004    1.81E+004   3.380E+004   2.344E+004 911.20*    25.80  1. 809E+004               3.591E+004   8.429E+003 968.97*    15.80  2.040E+004                3.206E+004   9.149E+003 Am-241       59.54     35.90  1 .476E+004   1.48E+004   1.990E+003   7.242E+003
       +    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

[266]

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

Filename: 6279 Report Generated On 8/20/2018 9:29:00 AM Sample Title B109100AFSWC051GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/20/2018 9:18:00 AM Acquisition Started 8/20/2018 9:18:58 AM Live Time 600. 0 seconds Real Time 600.9 seconds Dead Time 0 . 16 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE Cj-Z:t 0 [267] e.d:~~1~--- / JO\

Peak Analysis Report 8/20/2018 9:29:00 AM Page 2

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

Detector Name: 6279 Sample

Title:

Bl09100AFSWC051GD Peak Analysis Performed on: 8/20/2018 9:29:00 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 287- 308 301.21 75.43 0.62 1. 04E+002 68.86 2.88E+002 2 949- 959 953.99 238.62 1. 08 1.39E+001 21. 01 4.0lE+OOl 3 1400 - 1 4 15 1407.58 352 .01 0. 41 3.92E+001 21. 03 2.38E+001 4 2429- 2442 2435.57 608.99 0.54 3.88E+001 14 .58 5.22E+OOO 5 5836- 5854 5844.00 1 461.05 1.37 7.20E+001 16.97 O. OOE+OOO M :: First peak in a multiplet region m =- Other peak in a multiplet region F :: Fitted singlet Errors quoted at 2 . 000 sigma [268]

Interference Corrected Activity Report 8/20/2018 9:29:00 AM Page 3

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Sample

Title:

B109100AFSWC051GD 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 7.80724E+005 1.96110E+005 Pb-212 1. 000 238.63* 43.60 1. 10886E+004 1.68005E+004 Bi-214 0 .461 609.32* 45.49 5.64737E+004 2.22973E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 4 .98567E+004 2.77548E+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

[269]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1 .000 7.807244E+005 1 .961096E+OOS Pb-212 1.000 1. 10 8861E+004 1 .680052E+004 Bi-214 0.461 5.647366E+004 2.229728E+D04 Pb-214 0.432 4.985666E+004 2.775485E+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: 8/20/2018 9:29: 00 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty: Type Nuclide 1 75.43 1.7276E-001 66.43 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 [270]

Nuclide MDA Report 8/20/2018 9 ! 29: 00 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC051GD 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   2.934E+004     2.93E+004 7.807E+005      O.OOOE+OOO Co-60      1173.23      99. 85  2.302E+004     2.11E+004 -2.456E+004     1 .016E+004 1332.49      99.98   2.105E+004                 4.427E+003    9.06SE+003 Nb-94        702.65     99.81   1. 634E+O 04   1.63E+004 -5.458E+003     7.183E+003 871.09     99.89   1.912E+004                -1 .232E+004   8.435E+003 Ag-108m      433.90     90.50   1.967E+004     l. 97E+004 2.551E+003     9.049E+003 614. 3 0   89.80   3.171E+004                -1 .892E+004   1.485E+004 722. 9 0   90.80   1.998E+004                -3.665E+003    8.886E+003 Cs-134       604.72     97.62   2.849E+004     2.47E+004 3.141E+004      l.333E+004 795.86     85.46   2.470E+004                -1.914E+004    1.111E+004 Cs-137       661. 66    85.10   2.584E+004     2.58E+004 1.516E+004      1.180E+004 Eu-152       121.78     28.67   7.229E+004     6.39E+004 l.496E+004      3.493E+004 344.28     26.60  6.387E+004                  1.313E+004    2.967E+004 1408. 01     21.07   l.138E+005                 4 .470E+004   4 .967E+004 Eu-154       123. 0 7   40 .40 5.041E+004      5.04E+004 -1.947E+004     2.434E+004 723. 3 0   20.06  9.045E+004                 -1.517E+004    4.024E+004 1274.43      34.80  6.079E+004                 -1.727E+003    2.630E+004 Eu-155        86. 55    30.70  8.042E+004      8.04E+004 2.705E+004      3.911E+004 105. 31    21.10  1.079E+005                  l .104E+005   5.236E+004 Tl-208       583 .19    85.00   2.318E+004     2.32E+004 5.972E+003      1.057E+004 Bi-212       727.33      6.67   2.890E+005     2.89E+005 l .948E+005     1.295E+005
 +      Pb-212       238.63*    43.60   2.784E+004     2.78E+004 1.109E+004      1. 284E+004
 +      Bi-214       609.32*    45.49   2.212E+004     2.21E+004 5.647E+004      9.089E+003 1120. 29     14.92  1 .692E+005                 1.123E+005    7.576E+004 1764.49      15.30  1.636E+005                  3.403E+004    7.003E+004
 +      Pb-214       295.22     18.42  1.241E+005      3.88E+004 1.264E+005      S.910E+004 351.93*    35.60  3.877E+004                  4 .986E+004   1.766E+004 Ra-226       186. 21     3.64  5.029E+005      5.03E+OOS 2.185E+005      2.404E+OOS Ac-228       338.32     11.27  1. 524E+005     1 .06E+OOS 1.854E+004     7.094E+004 911. 2 0   25.80  1.064E+OOS                  1.072E+005    4.874E+004 96 B. 9 7  15.80  1.585E+OOS                 -7.233E+004    7.163E+004 Am-241        59.54     35.90   7.156E+004     7.16E+004 4.978E+004      3.466E+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

[271]

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

Filename: 6279 Report Generated on 8/18/2018 2:51 : 08 PM Sample Title B109100AFSWC052GD Sample Description WWTF WALL Sample Identification 052 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 Crf-7 Samp le Size ~E+OOl MA2

                                           ~       ~/z_ r/rr-Sample Taken On                    8/18/2018      2: 40: 00 PM Acquisition Started                8/18/2018      2: 41: 07 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE Cj-2-(f+/-> tJ. TIME ~ Z . ~ "

                                                             ~~l1A5&f\/<<:::-l

[272]

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

Detector Name: 6279 Sample

Title:

B109100AFSWC052GD Peak Analysis Performed on: 8/18/2018 2:51:08 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 1 296- 306 3 00. 61 75.28 0.39 4.62E+001 43.24 1 .76E+002 2 335- 354 339.20 84.92 0.45 5.27E+001 54.02 1.92E+002 3 948- 959 953.90 238.59 0.54 2.56E+001 18.92 2. 54E+001 4 1401- 1414 1407.98 352. 11 0.73 4.60E+001 17 . 13 1.00E+OOl 5 2035- 2050 2042.65 510.76 0.56 3.69E+001 14 .90 6.09E+OOO 6 2431- 2443 2436.71 609.27 0.73 3.58E+001 16.15 1.12E+001 7 2641- 2652 2646.05 66 1 .61 1. 09 2.03E+001 12.67 7.69E+OOO 8 5834- 5853 5844 .1 7 1461 .09 0.63 7.70E+001 19.44 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 [273]

Interference Corrected Activity Report 8/18/2018 2: 5 1: 08 PM Page 3

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Sample

Title:

B109100AFSWC052GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  .......... . . ..... .. i! ** **     IDENTIFIED NUCLIDES

• t .. .......... ........

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 8.36141E+005 2.23260E+005 Cs-137 1.000 661.66* 85 .10 1.67432E+004 1.06320E+004 Eu-155 0.346 86.55* 30.70 4.33398E+004 4.52291E+004 ¢)c.i--l~ *~ kt.'\,~' Vo-' 105.31 21.10 Pb-212 1. 000 238.63* 43.60 2.03636E+004 l.54230E+004 Bi-214 0.461 609.32* 45.49 5.22466E+004 2.43820E+004 1120.29 14 .92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 5.85438E+004 2.35026E+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

[274]

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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 1. 000 8.361414E+005 2.232597E+005 Cs-137 1.000 1.674319E+004 l. 063196E+00 4 Eu-155 0.346 4.333979E+004 4.522906E+004 Pb-212 1.000 2.036355E+004 l. 542297E+00 4 Bi-214 0.461 5.224662E+004 2.438196E+00 4 Pb-214 0.432 5.854381E+004 2.350256E+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
  **********     UN I D E N T I F I E D           P E A K S     **********

Peak Locate Performed on: 8/18/2018 2:5 1 :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 75.28 7.6948E-002 93.65 5 510.76 6.1521E-002 40. 36 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [275]

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Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC052GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/M"'2 ) (pCi/M"'2 ) (pCi/M"2 )

 +      K-40       1460.82*    10.66   1. 788E+005    1.79E+005   8.361E+005   7.473E+004 Co-60      1173.23     99.85   2.784E+004     2. 11E+004  7.029E+003   1. 256E+004 1332.49     99.98   2.108E+004                -2.435E+003   9.078E+003 Nb-94       702.65     99. 81  2.232E+004     1.39E+004   7.653E+003   1.017E+004 871.09     99.89   1.388E+004                -3.957E+003   5.814E+003 Ag-108m     433.90     90.50   1.866E+004     1.87E+004   1.316E+004   8.543E+003 614.30     89.80   3.114E+004                -6.758E+003   1 .457E+004 722.90     90.80   2.264E+004                 1.284E+004   l .022E+004 Cs-134      604.72     97.62   2.908E+004     2.07E+004  -1.654E+004   l .363E+004 795.86     85.46   2.066E+004                 3.911E+003   9.083E+003
 +      Cs-137      661.66*    85.10   1.430E+004     l .43E+004  1 .674E+004  6.032E+003 Eu-152      121 . 78   28.67   7.126E+004     6.19E+004   8.370E+004   3.441E+004 344.28     26.60   6.18BE+004                -8.719E+004   2.867E+004 1408.01     21.07   8.907E+004                 4.811E+004   3.730E+004 Eu-154      123.07     40 .40  4.892E+004     4.89E+004  -2.605E+004   2.359E+004 723.30     20.06   1 .025E+005                5.816E+004   4.626E+004 1274 .43    34.80   5.896E+004                 1.595E+004   2.538E+004
 +      Eu-155       86.55*    30.70   7 . 256E+004   7.26E+004   4.334E+004   3.517E+004 105.31     21.10   1.022E+005                 1.176E+005   4.951E+004 Tl-208      583.19     85.00   2.674E+004     2.67E+004   7.983E+003   1 .235E+004 Bi-212      727. 33     6.67   2.842E+005     2.84E+005   4. 876E+004  1 .270E+005
 +      Pb-212      238.63*    43.60   2.310E+004     2.31E+004   2.036E+004   1 .047E+004
 +      Bi-214      609.32*    45.49   2.997E+004     3. 00E+004  S.225E+004   1. 301E+004 1120. 29    14 .92  1. 866E+O 05               1. 572E+OOS  8.449E+004 1764.49     15.30   1.516E+005                 8.702E+004   6.402E+004
 +      Pb-214      295.22     18.42   1. 023E+O 05   2.54E+004   1.985E+004   4.823E+004 351. 93

• 35.60 2.536E+004 S.854E+004 1. 096E+O 04 Ra-226 186. 21 3.64 5.169E+005 S.17E+005 7.765E+004 2.474E+005 Ac-228 338.32 11. 27 1 .671E+005 8.62E+004 2.541E+004 7.824E+004 911. 2 0 25.80 8.615E+004 5.537E+004 3.859E+004 968.97 15 .80 1.488E+005 6.030E+004 6.678E+004 Am-241 59.54 35.90 6.914E+004 6.91E+004 -3.320E+004 3.344E+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

[276]

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

Filename: 6279 Report Generated On 8/20/2018 9:53:36 AM Sample Title Bl09100AFSWC053GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/20/2018 9:43: 00 AM Acquisition Started 8/20/2018 9:43:34 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE Cj-2-/~ [277] TIME ~'.)5" R:,f"Mit t t ~

Peak Analysis Report 8/20/2018 9:53:36 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSWC053GD Peak Analysis Performed on: 8/20/2018 9:53:36 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 1 181- 190 185.77 46.57 0 .44 9.07E+OOO 24.88 6.39E+001 2 296- 307 300.74 75.31 0 .47 l. 48E+001 46.65 2.09E+002 3 949- 972 954. 49 238.74 0 .87 5.14E+001 3 1 .10 4.76E+001 4 1401- 1413 1406.56 351.75 0 .59 2.72E+001 16.32 1.48E+001 5 2430- 2443 2436.17 609. 14 0 .34 3.84E+001 15.75 8.63E+OOO 6 5837- 5853 5845.23 1461.36 1. 27 6.58E+001 17.78 4.17E+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 [278]

Interference Corrected Activity Report 8/20/2018 9:53:36 AM Page 3

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Sample

Title:

B109l00AFSWC053GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1. 000 1460.82* 10.66 7.13916E+005 2.02508E+OOS Pb-212 1. 000 238.63* 43.60 4.08545E+004 2.56055E+004 Bi-214 0.461 609.32* 45.49 5.58916E+004 2.39093E+004 1120.29 14 .92 1764.49 15. 30 Pb-214 0.432 295.22 18.42 351.93* 35.60 3.45752E+004 2.13738E+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

[279]

Interference Corrected Activity Report 8/20/2018 9:53:36 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/MA 2 ) Uncertainty K-40 1.000 7.139164E+005 2.025076E+005 Pb-212 1.000 4.085450E+004 2.560549E+004 Bi-214 0.461 5.589157E+004 2.39093SE+004 Pb-214 0.432 3.457524E+004 2.137376E+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: 8/20/2018 9:53:36 AM Peak Locate From Channel: BS Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 46.57 1.5120E-002 274.28 2 75. 31 2.4702E-002 314.76 M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [280]

Nuclide MDA Report 8/20/2018 9:53:36 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC053GD 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   1.588E+OOS    l.59E+OOS   7.139E+005  6.474E+OD4 Co-60     1173.23     99.85   2.506E+004    l.80E+004   4.354E+002  l.117E+004 1332.49     99.98   1. 801E+004              -l.630E+004  7.543E+003 Nb-94       702.65    99.81   1.785E+004    1.79E+004  -8.328E+003  7.942E+003 871.09    99.89   1.821E+004               -2.470E+004  7.979E+003 Ag-108m     433.90    90.50   2.026E+OD4    2.03E+D04  -6.233E+003  9.345E+003 614 .30   89.80   2.963E+004               -2.528E+004  1 .381E+004 722.90    90.80   2.038E+004                2.656E+001  9.086E+003 Cs-134      604.72    97.62   2.793E+D04    2.39E+004  -1.176E+004  1 .305E+D04 795.86    85.46   2.386E+D04                4.043E+003  1 .069E+004 Cs-137      661. 66   85.10   3.165E+004    3.16E+004   6.585E+003  1. 471E+004 Eu-152      121.78    28.67   7.166E+004    6.78E+004   4.389E+004  3.462E+004 344.28    26.60   6.783E+004                4.414E+004  3.165E+004 1408 .01    21.07   1.005E+005                2.713E+004  4.302E+004 Eu-154      123.07    40.40   5.104E+004    5.10E+004   2.131E+004  2.466E+OD4 723. 3 0  20.06   9.226E+004                l.964E+003  4.114E+004 1274.43     34.80   6.079E+004               -5.418E+004  2.630E+004 Eu-155       86.55    30.70   7.800E+004    7.80E+004   2.295E+004  3.790E+004 105.31    21.10   1. OlOE+OOS              -1.0BSE+OOS  4 .889E+004 Tl-208      583.19    85.00  2.645E+004     2.65E+004   l.259E+004  1.220E+004 Bi-212      727.33     6.67  2.674E+005     2.67E+005  -1. 463E+OOS 1 .186E+005
 +       Pb-212      238.63*   43.60  3.827E+004     3.83E+004   4 .085E+004 l .806E+004
 +       Bi-214      609.32*   45.49  2.726E+004     2.73E+004   S.589E+OD4  1 .166E+004 1120.29     14.92   1 .943E+005               2.215E+005  8.836E+004 1764.49     15.30   1.801E+005                7.154E+004  7.829E+004
 +       Pb-214      295.22    18.42  1.069E+005     2.97E+004   4.154E+004  5.049E+004 351.93*   35.60  2.967E+004                 3.458E+004  l .312E+004 Ra-226      186.21     3.64  4.798E+005     4.80E+OOS  -l.167E+005  2.288E+OOS Ac-228      338.32    11.27  l.453E+005     7.06E+004  -8.447E+003  6.736E+004 911. 20   25.80  7.062E+004                 8.178E+003  3.083E+004 968.97    15.80  1.433E+005               -l.218E+004   6.407E+004 Am-241       59.54    35.90  6.937E+004     6.94E+004   3.926E+004  3.356E+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

[281]

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

Filename: 6279 Report Generated On 6 /20/2.016 10: 18 : 37 AM Sample Title B109100AFSWC054GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/20/2018 10:08:00 AM Acquisition Started 8/20/2018 10:08:35 AM Live T ime 600.0 seconds Real T ime 600.9 seconds Dead Time 0 . 15 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 9-2-{6 TIME {ft> 0 ' [282] C2-~1~

Peak Analysis Report 8/20/2018 10:18:37 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSWC054GD Peak Analysis Performed on: 8/20/2018 10:18:36 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 1 296- 305 300.99 75.37 1. 32 6.BlE+OOl 38.71 1.35E+002 2 950- 959 954.85 238.83 0 .42 1 .84E+001 19. 21 3.26E+001 3 1402- 1415 1407.79 352.06 0 .32 2.43E+001 18. 65 2.17E+001 4 2430- 2442 2435.95 609.08 1. 24 2.53E+001 14. 28 9.75E+OOO 5 5835- 5851 5842.58 146 0 .70 0 .33 6.07E+001 17. 27 4 .31E+OOO M -= First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [283]

Interference Corrected Activity Report B/20/2018 10:18:37 AM Page 3

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

Sample

Title:

B109100AFSWC054GD 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 6.57992E+005 1.95796E+005 Pb-212 1. 000 238.63* 43.60 1. 4 6109E+004 1.54661E+004 Bi-214 0.461 609.32* 45.49 3.67758E+004 2.12696E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 3.09111E+004 2.41594E+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

[284]

Interference Corrected Activity Report 8/20/2018 10:18:37 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 6.579920E+005 1.957961E+005 Pb-212 1 .000 1.461085E+004 1.546610E+004 Bi-214 0.461 3.677585E+004 2.126962E+004 Pb-214 0.432 3.091114E+004 2.415936E+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: 8/20/2018 10 :18:36 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 75.37 1.1344E-001 56.88 M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [285]

Nuclide MDA Report 8/20/2018 10:18:37 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM sample

Title:

B109100AFSWC054GD 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 1.623E+005 1.62E+OOS 6.580E+005 6.650E+004 Co-60 1173.23 99.85 2.35SE+004 2.03E+004 -2.917E+003 1. 042E+O 04 1332.49 99.98 2.034E+004 5.133E+003 8.709E+OD3 Nb-94 702.65 99.81 1.989E+004 1 .99E+004 -2.632E+003 8.959E+003 871.09 99.89 2.040E+004 -4.575E+003 9.077E+003 Ag-108m 433.90 90.50 1. 905E+004 1 .91E+004 -1.920E+004 8.742E+003 614.30 89.80 2.897E+004 -2.412E+003 1 .348E+D04 722.90 90.80 1. 998E+004 1 .792E+004 8.886E+003 Cs-134 604.72 97.62 2.617E+004 2.01E+004 1 .149E+004 1.217E+004 795.86 85.46 2.011E+004 8.595E+003 8.814E+003 Cs-137 661. 66 85.10 2.675E+004 2.68E+OD4 1 .808E+004 1. 226E+D04 Eu-152 121.78 28.67 7.090E+004 6.74E+004 4.642E+004 3.424E+004 344.28 26.60 6.735E+004 -1 .338E+004 3.141E+004 1408.01 21.07 1.005E+005 -1.957E+004 4.302E+004 Eu-154 123.07 40.40 4.996E+004 5.00E+004 -6.735E+003 2.412E+004 723.30 20.06 9.045E+004 8.113E+004 4 .024E+004 1274.43 34.80 6.783E+004 4.449E+003 2.983E+004 Eu-155 86.55 30.70 8.268E+004 8.27E+004 8.015E+004 4 .024E+004 105.31 21.10 9.911E+004 3.891E+004 4.79SE+004 Tl-208 583.19 85.00 2.289E+004 2.29E+004 -2.460E+D03 1 .042E+004 Bi-212 727.33 6.67 2.498E+005 2.50E+005 -1. 538E+OOS 1 .098E+OOS

 +      Pb-212       238.63*    43.60  2.466E+004     2.47E+004 1 .461E+004   l.125E+004
 +      Bi-214       609.32*    45.49  2.826E+004     2.83E+004 3.678E+004    1.216E+004 1120.29      14.92  1.565E+005                 8.615E+004  6.944E+004 1764.49      15.30  1.9SOE+005                 8.822E+004  8.577E+004
 +      Pb-214       295.22     18.42  1. 079E+005    3.65E+004 -9.575E+003   5.099E+004 351. 93

• 35.60 3.655E+004 3.091E+004 1.655E+004 Ra-226 186 .21 3.64 5.044E+OOS 5.04E+005 -2.451E+004 2.411E+OOS Ac-228 338.32 11. 27 1.720E+005 9.48E+004 6.450E+004 8.073E+004 911. 2 0 25.80 9.478E+004 2.981E+004 4.291E+004 968.97 15.80 1 .486E+OOS 1. 095E+005 6.668E+004 Am-241 59.54 35.90 7.389E+004 7.39E+004 -3.211E+004 3.582E+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 8/20/2018 8:58:44 AM Sample Title Bl09100AFSWC055GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/20/2018 8:48:00 AM Acquisition Started 8/20/2018 8:48:42 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 9--2-/* 0 TIME~ [287] C.t1'~==4d

Peak Analysis Report 8/20/2018 8:58: 44 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:

B109100AFSWC055GD Peak Analysis Performed on: 8/20/2018 8:58:44 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 295- 306 301.28 75.45 0.48 6.90E+001 49. 01 2.12E+002 2 1399- 1413 1406.24 351.67 1. 01 4.69E+001 19.07 1.51E+001 3 2428- 2440 2434.65 608.76 0.38 3.25E+001 14.11 6.47E+OOO 4 2638- 2649 2644.00 66 1 .09 0.64 l.18E+001 11.04 7.18E+OOO 5 5835- 5853 5843.07 1460 .82 0.74 S.83E+001 17.44 S.70E+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 8/20/2018 8:58:44 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:

Bl09100AFSWC055GD 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 6.32146E+005 1.96914E+005 Cs-137 0.999 661.66* 85.10 9.72068E+003 9. 15 33SE+003 Bi-214 0.460 609.32* 45.49 4 .73649E+004 2.13164E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 5.95492E+004 2.58083E+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

[289]

Interference Corrected Activity Report 8/20/2018 8:58:44 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/M ... 2 ) Uncertainty K-40 1.000 6.321458E+005 1 .969140E+005 Cs-137 0 .999 9.720676E+003 9.153352E+003 Bi-214 0 .460 4 .736491E+004 2.131641E+004 Pb-214 0 .432 5.954919E+004 2.580826E+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: 8/20/2018 8:58: 44 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.45 1.1503E-001 71.01 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 8/20/2018 8:58 : 44 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

Bl09100AFSWC055GD 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   1 .796E+005   l.80E+OOS    6.321E+005   7.514E+004 Co-60      1173.23    99.85   3.431E+004    2.65E+004    3.156E+004   1 .5BOE+004 1332.49    99.98   2.651E+004                 2.378E+004   1 .179E+004 Nb-94       702.65    99.81   2.082E+004    l.72E+004  -8.745E+002    9.427E+003 871 .09   99.89   1 .724E+004              - 1 .619E+004  7.495E+003 Ag-108m     433.90    90.50   2.281E+004    2.19E+004    9.679E+003   1 .062E+004 614. 3 0  89.80   3.171E+004               -l.359E+004    1. 485E+004 722.90    90.80   2.189E+004                 6.033E+003   9.845E+003 Cs-134      604.72    97.62   2.657E+004    1 .85E+004 -1.182E+003    1. 237E+004 795.86    85.46   1.B48E+004               -1.241E+004    7.999E+003
 +      Cs-137      661.66*   85.10   1.391E+004    1 .39E+004   9.721E+003   5.841E+003 Eu-152      121. 78   28.67   7.116E+004    6.97E+004  -1.861E+004    3.437E+004 344.28    26.60   6.972E+004               -3.355E+004    3.260E+004 1408.01    21.07   9.298E+004               -3.069E+004    3.927E+004 Eu-154      123.07    40 .40  5.113E+004    5.11E+004  -2.909E+004    2.470E+004 723. 3 0  20.06   1. OOBE+005                5.439E+004   4.539E+004 1274.43    34.80   6.783E+004                 5.439E+004   2.983E+004 Eu-155       86.55    30.70   8.426E+004    8.43E+004    9.170E+003   4.103E+004 105. 31   21. 10  1.0lSE+OOS                 5.498E+004   4.913E+004 Tl-208      583.19    85.00   2.670E+004    2.67E+004    2.181E+004   1.233E+004 Bi-212      727. 33    6.67   3.230E+005    3.23E+OOS    1.043E+004   1.465E+005 Pb-212      238.63    43.60   4 .792E+004   4.79E+004    4.454E+004   2.288E+004
 +      Bi-214      609.32*   45.49   2.383E+004    2.38E+004    4.736E+004   9.943E+003 1120.29    14.92   1 .891E+005                1.207E+OOS   8.572E+004 1764.49    15.30   l .902E+005                1.477E+OOS   8.335E+004
 +      Pb-214      295.22    18.42   l .017E+005   3.12E+004    1.302E+004   4.790E+004 351.93*   35.60   3.116E+004                 5.955E+004   1.386E+004 Ra-226      186.21     3.64   5.542E+005    5.54E+005    3.451E+OOS   2.660E+005 Ac-228      338.32    11 .27  1 .751E+OOS   1.14E+OOS    8.006E+004   8.225E+004 911. 2 0  25.80   1 .135E+005                3.691E+004   5.227E+004 968.97    15.80   1 .536E+005                7.729E+004   6.920E+004 Am-241       59.54    35.90   7.574E+004    7.57E+004  -9.334E+002    3.675E+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

[291]

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

Filename: 6279 Repor t Generated On 8/20/2018 9:15:01 AM Sample Title B109100AFSWC056GD Sample Description WWTF Wall Sample Identification Sample Type Gamme Direct Sample Geometry 3M90DWWTF1 . 27CM 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 8/20/2018 9:04:00 AM Acquisition Started 8/20/2018 9:04:59 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 7/31/2018 Efficiency I D 3MWWTF1,27CM DATA VALIDATED DATE Cf,--2 --j f3 TIME '":??;; [292] (£1m~;~

Peak Analysis Report 8/20/2018 9:15: 01 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:

B109100AFSWCOS6GD Peak Analysis Performed on: 8/20/2018 9:15: 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 1 295- 305 300.29 75.20 0.69 2.29E+001 47.53 2.26E+002 2 948- 961 954.32 238.70 0.60 3.04E+001 22.88 3.56E+001 3 1400- 1415 1407.83 352.07 0.47 5.54E+001 20.21 1.56E+001 4 2430- 2443 2436.80 609.30 0.85 3.27E+001 17.10 1. 43E+ 001 5 5836- 5853 5844.03 1461.06 0.62 7.20E+001 19.06 6.0lE+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 8/20/2018 9: 15 :01 AM Page 3

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

Sample

Title:

B109100AFSWC056GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  . . . . . . . .. ~ " .. .. ... . . IDENTIFIED NUCLIDES           .. * * * * * * * * * * * * * ,o fl I I' *

• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-4 0 1. 000 1460.82* 10 .66 7.80623E+005 2.17518E+005 Pb-212 1 . 000 238.63* 43.60 2.41628E+004 1. 86147E+004 Bi-214 0 . 461 609.32* 45.49 4.76253E+004 2.55636E+004 1120.29 14 .92 1764.49 15 .30 Pb-214 0 .432 295.22 18 .42 351.93* 35.60 7.03866E+004 2.77669E+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

[294]

Interference Corrected Activity Report 8/20/2018 9:15: 01 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 7.806227E+005 2.175179E+OOS Pb-212 1.000 2.416279E+004 1.861469E+004 Bi-214 0.461 4. 762533E+004 2.556360E+004 Pb-214 0.432 7.03866SE+004 2.776691E+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: 8/20/2018 9:15:01 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 75.20 3.8199E-002 207.37 M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [295]

Nuclide MDA Report 8/20/2018 9:15 : 01 AM Page s

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC056GD 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. 842E+005   1.84E+005  7.806E+OOS   7.742E+004 Co-60     1173.23    99.85   2.248E+004    2.03E+004  1.803E+004   9.885E+003 1332.49    99.98   2.034E+004               6.574E+003   8.709E+003 Nb-94        702.65   99.81   1. 821E+004   1.82E+004 -1.819E+003   8.120E+003 871.09   99.89   1. 999E+004              7.645E+003   8.868E+003 Ag- 108m     433.90   90.50   2.065E+004    2.06E+004  6.448E+003   9.538E+003 614.30   89.80   3.191E+004               9.416E+003   1 .495E+004 722.90   90.80   2.189E+004               4.962E+003   9.845E+003 Cs-134      604.72   97.62   2.868E+004    2.16E+004 -5.215E+003   1.343E+004 795.86   85.46   2.161E+004              -7.926E+002   9.560E+003 Cs-137      661.66   85.10   2.584E+004    2.58E+004 -2.026E+004   1.180E+004 Eu-152      121.78   28.67   7.242E+004    6.64E+004 -3.476E+003   3.499E+004 344.28   26.60   6.638E+004               2.053E+004   3.092E+004 1408 . 01  21.07   9.298E+004               2.255E+004   3.927E+004 Eu-154      123.07   40.40   5.005E+004    5.00E+004  3.984E+003   2.416E+004 723.30   20.06   9.746E+004              -1.844E+003   4.374E+004 1274.43    34.80   6.263E+004              -7.152E+003   2.723E+004 Eu-155       86.55   30.70   7.540E+004    7.54E+004 -2.879E+003   3.660E+004 105.31   21.10  1. 002E+005               3.119E+004   4 .850E+004 Tl-208      583.19   85.00   2.347E+004    2.35E+004 -8.184E+002   1.071E+004 Bi-212      727.33    6.67   2.890E+005    2.89E+OOS  4 .418E+004  1.29SE+005
 +       Pb-212      238.63*  43.60   2.839E+004    2.84E+004  2.416E+004   1.312E+004
 +       Bi-214      609.32*  45.49   3.442E+004    3.44E+004  4.763E+004   1.524E+004 1120 .29   14. 92 1 .532E+005              -1.694E+004   6.777E+004 1764.49    15. 30 1 .852E+005               1. 390E+005  8.086E+004
 +       Pb-214      295.22   18. 42 1 .084E+005    3.20E+004  9.175E+004   5.124E+004 351.93*  35.60   3.203E+004               7.039E+004   1 .430E+004 Ra-226      186.21    3.64   5.249E+005    5.25E+005  9.128E+004   2.514E+005 Ac-228       338.32   11. 27 1.501E+005     9.34E+004  1 .256E+004  6.976E+004 911.20   25.80   9.339E+004               3.031E+004   4.221E+004 968.97   15.80  1.561E+005                1 .630E+005  7.042E+004 Am-241        59.54   35.90   7.124E+004    7.12E+004  3.717E+004   3.449E+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

[296]

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

Filename: 6279 Report Generated On 8/22/2018 8:43: 04 AM Sample Title B109100AFSWC057GD Sample Description WWTF WALL Sample Identification 057 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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

                                     -z,r.J Sample Size                         <<;;i. 826-E+O 01 M"2
                                           ~       Y/21-/1.r Sample Taken On                    8/22/2018         8:33:00 AM Acquisition Started                8/22/2018         8:33:03 AM Live Time                                    600.0 seconds Real Time                                    600.5 seconds Dead Time                              0.08 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE q.-2-re [297] _ee:~)lj\~z~

                                                                - TIME~,

J

Peak Analysis Report 8/22/2018 8:43: 04 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:

B109100AFSWC057GD Peak Analysis Performed on: 8/22/2018 8:43:04 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 1 269- 276 272.33 68.21 0.47 2.48E+001 25.50 6.82E+001 2 295- 306 300.39 75.22 0.32 l .18E+001 46.57 2.11E+002 3 950- 961 955.51 238.99 0.53 2.50E+001 20.71 3.20E+001 4 1402- 1414 1407.52 351.99 0.79 3.66E+001 17. 11 l.34E+001 5 2430- 2444 2437.46 609.46 0.80 3.58E+001 16.50 l.13E+001 6 5839- 5855 5846.71 1461.73 1.22 6.21E+001 18.56 7.86E+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 [298]

Interference Corrected Activity Report 8/22/2018 8:43:04 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:

B109100AFSWC057GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• I ._ I * , I
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.999 1460.82* 10.66 6.75025E+005 2.09958E+005 Pb-212 1.000 238.63* 43.60 1 .99258E+004 l. 68244E+004 Bi-214 0 .461 609.32* 45.49 5.21643E+004 2.48856E+004 1120.29 14.92 1764.49 15. 30 Pb-214 0.432 295.22 18.42 351.93* 35.60 4.65496E+004 2.28678E+004 Am- 241 0.887 59.54* 35.90 1 .92372E+004 2.01873E+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

[299]

Interference Corrected Activity Report 8/22/2018 8:43:04 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 6.750250E+005 2.099583E+D05 Pb-212 1 . 000 1 .992577E+OD4 1.682444E+004 Bi-214 0.461 5.216428E+004 2.488556E+004 Pb-214 0.432 4.654955E+OD4 2.286782E+004 Am-241 0.887 1 .923720E+004 2.018728E+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: 8/22/2018 8:43:04 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 2 75.22 1.9623E-002 395.53 M = First peak in a multiplet region m : Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 00 0 sigma [300]

Nuclide MDA Report 8/22/2018 8: 43 :04 AM Page 5

• **** NUCLIDE MD A R E P O R T *****

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

Bl09100AFSWC057GD 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   2.044E+005      2.04E+005   6.7SOE+OOS   8 . 750E+004 Co-60     1173.23     99.85   2.138E+004      1 .63E+004  6.864E+003   9.332E+003 1332.49     99.98   1. 625E+004                -l.461E+004   6.661E+003 Nb-94       702.65    99.81   1 .926E+004     1.93E+004   9.657E+003   8.646E+003 871.09    99.89   2.124E+004                 -5.467E+003   9.494E+003 Ag-108m     433.90    90.50   1 .709E+OD4     1 .71E+004  1.28DE+003   7.760E+003 614.30    89.80   2.879E+004                 -2.455E+004   1 .339E+004 722.90    90.80   2.229E+004                  1.203E+004   1 .004E+004 Cs-134      604.72    97.62   2.872E+004      2.43E+004   6.282E+003   1 .344E+004 795.86    85.46   2.432E+004                 -1. 237E+004  l .092E+004 Cs-137      661.66    85.10   2.179E+004      2.18E+004  -6.341E+002   9.778E+003 Eu-152      121.78    28.67   6.653E+004      6.24E+004   4.086E+004   3.205E+004 344.28    26.60   6.241E+004                 -4.594E+004   2.893E+004 1408 .01    21. 07  8.026E+004                 -3.360E+004   3.290E+004 Eu-154      123.07    40.40   4 .691E+004     4.69E+004   5.288E+003   2.259E+004 723.30    20.06   1. 0 09E+O 05               3.089E+004   4.546E+004 1274.43     34.80   5.896E+004                  l.199E+004   2.538E+004 Eu-155       86.55    30.70   7.745E+004      7.74E+004   3.925E+004   3.762E+004 105.31    21.10   9.715E+004                  1.846E+003   4 .697E+004 Tl-208      583.19    85.00   2.518E+004      2.52E+004   3.610~+003   1 .156E+004 Bi-212      727.33      6.67  3.456E+OOS      3.46E+OOS   1.919E+005   1 .577E+005
  +       Pb-212      238.63*   43.60   2.595E+004      2.59E+004   1.993E+004   1 .19DE+004
  +       Bi-214      609.32*   45.49   3.125E+004      3.13E+004   5.216E+004   1 .365E+004 1120. 29    1 4 .92 1. 893E+005                 1. 093E+005  8.584E+004 1764.49     15.30   l.750E+005                  S.998E+004   7.575E+004
  +       Pb-214      295.22    18.42   1.090E+005      2.88E+OD4   S.764E+004   5.156E+004 351.93*   35.60   2.879E+004                  4.655E+004   1 .267E+004 Ra-226      186.21      3.64  4.898E+005      4.90E+005   9.865E+004   2.338E+OOS Ac-228      338.32    11. 27  1.639E+005      9.35E+004   1.083E+005   7.664E+004 911. 20   25.80   9.352E+004                  2.599E+004   4.227E+004 968.97    15.80   l.408E+005                 -2.374E+004   6.281E+004
  +       Am-241       59. 54*  35.90   3.211E+004      3.21E+004   1.924E+004   1. 500E+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]

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

Filename: 6279 Report Generated On 8/22/2018 8:28:15 AM Sample Title B109100AFSWC058GD Sample Description WWTF WALL Sample Identification 058 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 C,Y} Sample Size 2 e~&E+O 01 MA2

                                          #--   ?/zr/1r Samp le Taken On                   8/22/2018      8:18:00 AM Acquisition Started                8/22/2018      8:18:14 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE Cf:--2-{8 TIME / Jz.o [302] (j!, t'&z1-wJJ~

Peak Analysis Report 8/22/2018 8:28:15 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSWCOS8GD Peak Analysis Performed on: 8/22/2018 8:28:15 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 (ke V) (keV) Area Uncert. Counts 1 183- 190 186. 4 0 46.73 0.32 9.24E+OOO 20.12 4.48E+001 2 287- 306 300.71 75.30 0.43 1. 16E+002 62.16 2.43E+002 3 345- 354 349.64 8 7 .54 0.49 4.llE+OOO 3 1 .68 1.09E+002 4 1075- 1085 1079.99 27 0 .11 0.57 8.45E+OOO 12.47 1.25E+001 5 1402- 1415 1408.24 352.17 0.95 3.05E+001 17.76 1.75E+001 6 2641- 2652 2646.75 66 1 .78 0.67 1 .60E+001 11. 23 6.02E+OOO 7 5838- 5853 5845.95 1 46 1 .54 0.80 6.lOE+OOl 17.11 3.98E+OOO M First peak in a multiplet region m "'- Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [303]

Interference Corrected Activity Report 8/22/2018 8:28 : 15 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:

B109100AFSWC058GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB t, * * * * * * * *

• I * * * * * * * .,
• IDENTIFIED NUCLIDES . . . ' .................

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.999 1460.82* 10.66 6.62714E+005 1.94576E+005 Cs-137 1 .000 661.66* 85.10 1. 31718E+004 9. 3 9583E+003 . A "Z. <>z!!J Eu-155 0.348 86.55* 30.70 3.33332E+003 2. 56860E+004 ._ ~ 105 .31 21.10 Pb-214 0.432 295.22 18.42 351.93* 35.60 3.88373E+004 2.33449E+004

           *=Energy line found in the spectrum.
           @ ~ Energy line not used f or Weighted Mean Activity Energy Tolerance :                     10.000 keV Nuclide confidence index threshold =                        0.30 Errors quoted at 2. 000 sigma

[304]

Interference Corrected Activity Report 8/22/2018 8:28: 15 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 6.627144E+005 1. 945762E+005 ~--(, l)t Cs-137 1 . 000 1. 31 7183E+O 04 9. 395834E+003 -, '7@ \C-- Eu-155 0 .348 3.333324E+003 2. 568595E+004 '- A, C ~* vv Pb-214 0 .432 3.883728E+004 2.334495E+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: 8/22/2018 8:28:15 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 46.73 l.5401E-002 217.69 2 75.30 1.9405E-001 53.39 4 270. 11 1.4087E-002 147.56 M - First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [305]

Nucl ide MDA Report 8/22/2018 8:28:15 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

Bl0910 0AFSWC058GD 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/MA2 )

 +      K-40        1460.82*    10.66   1.542E+005    1.54E+005   6.627E+OD5  6.240E+004 Co-60       1173 .23    99.85   2.079E+D04    2.08E+OD4   5.834E+003  9.036E+D03 1332.49     99.98   2.307E+004                1 .116E+004 1.007E+004 Nb-94         702.65    99.81   1.824E+004    1.82E+004   1 .822E+003 8.132E+003 871. 09   99.89   1.915E+D04                4.384E+003  8.447E+003 Ag-108m       433.90    90.50   1 .949E+004   1.87E+004  -1 .539E+004 8.96DE+003 614. 3 0  89.80   2.415E+004                2.783E+004  1.107E+004 722.90    90.80   1 .875E+004              -3.219E+D02  8.27DE+003 Cs-134        604.72    97.62   2.363E+004    2.26E+004   1.821E+004  l.090E+004 795.86    85.46   2.257E+004               -1.235E+004  1.004E+004
 +      Cs- 137       661.66

• 85.10 1 .294E+004 1 .29E+004 1.317E+004 5.352E+003 Eu-152 121. 78 28.67 6.501E+004 6.50E+004 -2.239E+004 3.129E+D04 344.28 26.60 6.696E+004 3.182E+004 3.121E+004 1408. 01 21.07 9.695E+004 5.880E+004 4.124E+D04 Eu-154 123.07 40 .40 4.691E+004 4.69E+004 2.081E+004 2.259E+004 723.30 20.06 8.489E+OD4 -2.381E+003 3.745E+004 1274.43 34.80 6.087E+004 2.070E+004 2.634E+004

 +      Eu-155         86.55*   30.70   4.408E+004    4.41E+004   3.333E+003  2.095E+OD4 105.31    21 .10  9.484E+004               -3.108E+OD4  4.581E+004 Tl-208        583.19    85 .00  2.436E+004    2.44E+004   2.066E+004  1.115E+004 Bi-212        727.33     6.67   2.842E+005    2.84E+005   1.902E+005  1.270E+005 Pb-212        238.63    43.60   4.738E+OD4    4.74E+OD4   4.481E+004  2.261E+004 Bi - 214      609.32    45.49   4.948E+OD4    4.95E+004   2.911E+004  2.277E+004 1120.29     14. 92  1. 782E+OOS               1.321E+005  8.030E+D04 1764.49     15.30   l.307E+OD5               -2.175E+D03  5.356E+004
 +      Pb-214        295.22    18.42   1.034E+005    3.26E+004   6.721E+D04  4.876E+004 351.93*   35.60   3.257E+D04                3.884E+004  1.456E+004 Ra-226        186.21     3.64   4.66DE+005    4.66E+OD5   1.582E+D05  2.219E+005 Ac-228        338.32    11. 27  l.467E+005    9.07E+D04  -3.056E+004  6.806E+004 911. 2 0  25.80   9.065E+004                7.482E+004  4.084E+004 968.97    15.80   1.200E+D05                6.157E+003  5.238E+004 Am-241         59.54    35.90   6.616E+004    6.62E+004  -2.663E+004  3.196E+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

[306]

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

Filename: 6279 Report Generated On 8/21/2018 2:26:55 PM Sample Title B109100AFSWC059GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Pirect Sample Geometry 3M90DWWTF1.27CM 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 8/21/2018 2:16:00 PM Acquisition Started 8/21/2018 2:16:53 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 7--2-tfc

                                                      ;:,   TIME 1 ? ~

[307] ?K-.1:ft~f, ~

Peak Analysis Report 8/21/2018 2:26:55 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:

B109100AFSWC059GD Peak Analysis Performed on: 8/21/2018 2:26:55 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 Uncert. Counts 1 296- 310 300.25 75.19 0.63 1 .01E+002 47.94 1.62E+002 2 1176- 1187 1180.84 295.32 0.59 2.22E+001 17.77 2.08E+001 3 1400- 1411 1405 .40 351. 46 0.73 2.09E+001 15.49 1.51E+001 4 2429- 2441 2435.27 608.92 1.14 2.84E+001 11. 44 1.63E+OOO 5 5833- 5851 5842.38 1460.65 0.75 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 [308]

Interference Corrected Activity Report 8/21/2018 2:26:55 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:

B109100AFSWC059GD 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 7.58882E+005 1. 93 006E+O 05 Bi- 214 0 .461 609.32* 45.49 4.13196E+004 1 .73894E+004 1120.29 14.92 1764.49 15.30 Pb-214 1 .000 295.22* 18.42 4. 82387E+004 3.93515E+004 351.93* 35.60 2.65587E+004 2.00610E+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

[309]

Interference Corrected Activity Report 8/21/2018 2:26:55 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 7.588816E+005 1. 930058E+005 Bi-214 0.461 4.131964E+004 1. 738939E+004 Pb-214 1.000 3.103081E+004 1. 787257E+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: 8/21/2018 2:26:55 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 75.19 1.6869E-001 47.36 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 8/21/2018 2:26 : 55 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC059GD 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   2.934E+004    2.93E+004    7.589E+OD5   O.OOOE+OOO Co-60      1173.23    99.85   2.248E+004    2.17E+D04    1.039E+004   9.885E+003 1332.49    99.98   2.174E+004                 6.311E+003   9.407E+003 Nb-94        702.65   99.81   1.924E+004    1.92E+004  -1.845E+OD4    8.633E+003 871.09   99.89   2.199E+004               -1. 248E+003   9.868E+003 Ag-108m      433.90   90.50   1. 863E+004   1 .86E+004 -1.087E+004    8.531E+003 614.30   89.80   2.S93E+004               - 3.349E+D04   1.196E+004 722.90   90.80   1. 998E+004                1. 786E+OD3  8.886E+003 Cs-134       604.72   97.62   2.360E+004    1 .90E+OD4   2.688E+OD4   1. 089E+004 795.86   85.46   1 .905E+004                7.29DE+003   8.279E+OD3 Cs-137       661.66   85.10   2.456E+004    2.46E+004    1. 236E+004  1 . 117E+004 Eu-152       121. 78  28.67  6.724E+004     5.68E+004  -4.031E+004    3.241E+OD4 344.28   26.60  5.680E+004                -1.721E+004    2.613E+004 1408. 01   21.07  8.469E+004                  4.270E+004   3.512E+004 Eu-154       123.07   40.40   4.714E+004    4.71E+D04  -2.293E+OD4    2.270E+004 723.30   20.06   9.226E+004                 1. 387E+004  4.114E+D04 1274.43    34.80   7.261E+004                 3.738E+004   3.222E+004 Eu-155        86.55   30.70   7.922E+004    7.92E+004    2.902E+OD4   3.851E+D04 105.31   21.10   9.251E+004               -1. 960E+004   4.465E+004 Tl-208       583.19   85.00   2.318E+004    2.32E+004    7.307E+003   1. 057E+OD4 Bi-212       727.33    6.67  3.230E+005     3.23E+005  -1 .404E+005   1.465E+005 Pb-212       238.63   43.60  4.450E+004     4.45E+004    2.422E+OD3   2.117E+004
 +      Bi-214       609.32*  45 .49 1. 395E+004    1.40E+D04    4.132E+004   5.006E+003 1120.29    14.92  1.864E+005                  2.019E+005   8.437E+004 1764.49    15.30  1.902E+005                  7.667E+004   8.335E+004
 +      Pb-214       295.22*  18.42  5.969E+004     2.95E+004    4.824E+004   2.691E+OD4 351.93*  35.60  2.954E+004                  2.656E+OD4   1.305E+004 Ra-226       186.21    3.64  5.073E+OOS     5.07E+005    3.590E+005   2.426E+OOS Ac-228       338.32   11. 27 1. 513E+005    9.62E+004    9.150E+004   7.035E+004 911.20   25.80   9.615E+004               -6.473E+D04    4 .36DE+004 968.97   15.80  1. 379E+005                 1. 237E+005  6.134E+OD4 Am-241        59.54   35.90  6.848E+004     6.85E+004  -2.841E+004    3.312E+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

[311]

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

Filename: 6279 Report Generated On 8/21/2018 2:40:07 PM Sample Title B109100AFSWC060GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/21/2018 2: 30: 00 PM Acquisition Started 8/21/2018 2:30:05 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 7r-2-r3: TIME ~~ [312]

                                                             /2J'1M£e.Ajlf=   ~

Peak Analysis Report 8/21/2018 2:40:07 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:

B109100AFSWC060GD Peak Analysis Performed on: 8/21/2018 2:40:07 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- 305 3 01. 0 0 75.38 0.99 5.76E+001 37.53 1 .29E+002 2 949- 959 954 . 17 238.66 0.55 1.64E+001 1 9.02 3. 06E+001 3 1400- 1412 1406.05 351 .62 0.91 3.47E+001 16.05 1 . 13E+001 4 2429- 2442 2435.02 608.85 0.73 2.75E+001 13.20 5 . 53E+OOO 5 5833- 5851 5842.34 146 0 .64 1. 72 6 . 14E+001 17.56 4. 63E+OOO M == First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [313]

Interference Corrected Activity Report 8/21/2018 2:4 0 :07 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:

B109100AFSWC060GD 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 6.65332E+005 1. 9896BE+005 Pb-212 1 . 000 238.63* 43.60 l.30462E+004 1 .52727E+004 Bi-214 0.461 609.32* 45.49 3.99986E+004 1.98094E+004 1120.29 14. 92 1764.49 15.30 Pb-214 0.432 295.22 18 .42 351.93* 35.60 4.40411E+004 2.14276E+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

[314]

Interference Corrected Activity Report 8/21/2018 2:40:07 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 6.653323E+OOS 1 .989685E+005 Pb-212 1 .000 1 .304625E+004 1 .527272E+00 4 Bi-214 0.461 3.999856E+004 1 .980944E+00 4 Pb-214 0.432 4.404108E+004 2.142761E+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: 8/21/2018 2:40:07 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Pea_k CPS Peak To l. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.38 9.5980E-002 65.18 M ~ First peak in a multiplet region m - Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [315]

Nuclide MDA Report 8/21/2018 2 :40: 07 PM Page s

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC060GD 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  1.708E+005      1.71E+005 6.653E+005      7.075E+004 Co-60      1173.23      99.85  1.951E+004      l.52E+004 -l.573E+004     8.400E+003 1332.49      99.98   l.524E+004                -2.648E+004    6.158E+003 Nb-94        702.65     99. 81 1.989E+004      1.82E+004 -1.263E+004     8.959E+003 871.09     99.89  1.821E+004                 -6.0SSE+003    7.979E+003 Ag-108m      433.90     90.50  1 .610E+004     1.61E+004 1 .000E+004     7.264E+003 614. 3 0   89.80  2.491E+004                 -1.591E+004    1.145E+004 722.90     90.80  1.998E+004                  1.490E+003    8.886E+D03 Cs-134       604.72     97.62  2.383E+004      2.21E+004 l.853E+004      1. 10DE+004 795.86     85.46  2.20BE+004                 -4.496E+003    9.796E+OD3 Cs-137       661.66     85. 10 2.489E+004      2.49E+004 -1.317E+004     1.133E+004 Eu-152       121.78     28.67  6.778E+004      6.54E+004 -4.655E+003     3.268E+OD4 344.28     26.60  6.539E+004                 -2.414E+004    3.043E+OD4 1408.0l      21.07  l . 138E+O OS               1. 334E+003   4.967E+004 Eu-154       123.07     40.40  4.838E+004      4 .84E+004 2.219E+004     2.333E+004 723. 3 0   20.06  9.045E+004                  8.004E+OD3    4.024E+004 1274 .43     34.80  5.481E+004                  8.379E+003    2.332E+004 Eu-155        86. 55    30.70  7.472E+004      7.47E+004 -5.971E+003     3.626E+004 105. 31    21. 10 9.587E+004                 -4.527E+004    4.633E+004 Tl-208       583.19     85.00  2.318E+004      2.32E+004 -7.344E+003     1.057E+004 Bi-212       72 7. 3 3   6.67  3.041E+005      3.04E+005 1 .506E+005     1. 370E+OOS
 +      Pb-212       238.63*    43.60  2.467E+004      2.47E+004 1 .30SE+D04     l.126E+004
 +      Bi-214       609.32*    45.49  2.31SE+004      2.31E+004 4.000E+004      9.604E+003 1120.29      14.92  1.598E+005                  9.385E+004    7.107E+004 1764.49      15.30  1. 576E+005                 1.955E+004    6.70SE+004
 +      Pb-214       295.22     18.42  1. 0 06E+OOS    2.62E+004 1.05SE+005      4.736E+004 351.93*    35.60  2.623E+004                  4 .404E+004   1.139E+004 Ra-226       186. 21     3.64  4 .813E+005     4.81E+005 l .709E+004     2.296E+005 Ac-228       338.32     11. 27 1 .636E+OOS     1.04E+OOS 1 .447E+OOS     7.653E+004 911. 20    25.80  1 .040E+005                 2.415E+004    4.751E+004 968.97     15.80  1.511E+005                 -4.247E+004    6.795E+004 Am-241        59. 54    35.90  6.700E+004      6.70E+004 -2.527E+004     3.237E+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 S P E C T R U M A N A L Y S I S *****

Filename: 5452A Report Generated On 8/16/2018 3:30: 51 PM Sample Title Bl09100AFSFC045GD Sample Description WWTF SUMP #2 Sample Identification 045 Sample Type GAMMA DIRECT Sample Geometry WWTF SUMP 2 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 4.270E+OOO M"2 Samp le Taken On 8/16/2018 3:20:00 PM Acquisition Started 8/16/2018 3:20:49 PM Live Time 600. 0 seconds Real Time 601 . 4 seconds Dead Time 0 . 23 % Energy .calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 8/16/2018 Efficiency ID WWTF SUMP 2 [317]

Peak Analysis Report 8/16/2018 3: 30: 51 PM Page 2

• • • • • P E A K ANALYS I s R E P O R T *****

Detector Name: 5452A Sample

Title:

B109100AFSFC045GD Peak Analysis Performed on: 8/16/2018 3:30: 51 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- 308 300.96 75.24 0.71 1.12E+002 89.24 6.81E+002 2 945- 960 953.51 238.38 0.99 1.13E+002 57.71 2.40E+002 3 1169- 1190 1178 .86 294.71 1. 00 1.60E+002 55.17 1 .58E+002 4 1398 - 1412 1406 . 15 351.54 1.18 2.13E+002 4 1. 96 7.89E+001 5 2030- 2049 2038.51 509.63 0.85 7.03E+001 40.74 9.77E+001 6 2322 - 2336 2328.49 582.12 1. 10 7.78E+001 26.37 3.32E+001 7 2423 - 2441 2433.14 608.29 1 .48 1.93E+002 40.13 6.18E+001 8 2634- 2650 2642.35 66 0 .59 1. 49 9.0SE+OOl 29.09 3.85E+001 9 3430- 3443 3436.84 859.21 0 .30 1.15E+001 17.77 2.45E+001 10 3631- 3648 3639.05 909.76 0 .83 7.86E+001 28.59 3.84E+001 11 3865- 3878 3871.59 967.90 0 .39 4.13E+001 19.26 1.87E+001 12 4466- 4481 4473.74 111 8.44 0 .59 6.94E+001 24.19 2.56E+001 13 4681- 4694 4687.32 11 71. 83 1. 02 2.52E+001 16.57 1.58E+001 14 4941- 4955 4947.68 1236.92 0 .30 3.38E+001 19. 11 1.92E+001 15 5316- 5329 5322.82 133 0 .70 1. 27 2.65E+001 13. 13 5.48E+OOO 16 5822- 5850 5836.81 1459.20 1. 75 5.39E+002 49.89 l.80E+001 17 7041- 7060 7051.05 1762.76 0.32 5.25E+001 19.65 1.2SE+001 M ;;::: Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [318]

Interference Corrected Activity Report 8/16/2018 3: 30: 52 PM Page 3

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

Sample

Title:

B109100AFSFC045GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• IDENTIFIED NUCLIDES * .. .. ~. * * * * * * * * .. ... .. * ... ill ... ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"'2 ) Uncertainty K-40 0.996 1460.82* 10.66 8.01007E+005 1.01663E+005 Co-60 0.996 1173.23* 99.85 3.47909E+003 2.30104E+003 1332.49* 99.98 3.94713E+003 1.97978E+003 Cs-137 0.998 661.66* 85. 10 1. 02980E+004 3.53259E+003 Tl-208 0.998 583.19* 85.00 8.17113E+003 2.93836E+003 Pb-212 1 . 000 238.63* 43.60 1 .27190E+004 6.80119E+003 Bi-214 0.997 609.32* 45.49 3.90008E+004 9.35890E+003 1120.29* 14.92 6.22001E+004 2.22554E+004 1764.49* 15.30 6.21565E+004 2.38028E+004 Pb-214 1.000 295.22* 18.42 4.89890E+004 1.86451E+004 351.93* 35.60 3.80631E+004 9.65729E+003 Ac-228 0.560 338.32 11. 27 911.20* 25.80 3.59104E+004 1 .34431E+004 968.97* 15.80 3.20606E+004 1 .52080E+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

[319]

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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 0.996 8.010073E+005 1.016631E+005 Co-60 0.996 3.748039E+003 1.500754E+003 Cs-137 0.998 1.029804E+004 3.532585E+003 Tl-208 0.998 8 .1 71125E+003 2.938360E+003 Pb - 212 1.000 1.271902E+004 6.80118SE+003 Bi-214 0 .997 4.477072E+004 B.110820E+003 Pb-214 1 .000 4.037420E+004 8.575279E+003 Ac-228 0.560 3.422173E+004 1. 007215E+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 8/16/2018 3:30:52 PM Page S

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

Peak Locate Performed on: 8/16/2018 3:30:51 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 1. 8630E-001 79.83 5 509.63 1. 1712E-001 57.98 9 859.21 1.9167E-002 154.50 14 1236.92 5.6297E-002 56.58 Sum M ;;: First peak in a multiplet region m -= Other peak in a multip let region F - Fitted singlet Errors quoted at 2.000 sigma [321]

Nuclide MDA Report 8/16/2018 3:30:52 PM Page 6

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

Detector Name: 5452A Sample Geometry: WWTF SUMP 2 Sample

Title:

B109100AFSFC045GD 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  4.863E+004    4.86E+004   8.0lOE+OOS   2.230E+004
 +       Co-60     1173.23*     99.85  3.361E+003    2.40E+003   3.479E+003   l.494E+003 1332.49*     99.98  2.397E+003                3.947E+003   9.971E+002 Nb-94       702.65     99.81  5.141E+003    5.14E+003  -2.917E+003   2.434E+003 871.09     99.89  5.455E+003                5.062E+003   2.572E+003 Ag-108m     433.90     90.50  5.711E+003    5.71E+003  -1.925E+003   2.746E+003 614. 3 0   89.80  8.174E+003               -l.710E+002   3.948E+003 722.90     90.80  6.163E+003                2.159E+003   2.929E+003 Cs-134      604.72     97.62  8.421E+003    6.42E+003   1.778E+004   4.084E+003 795.86     85.46  6.420E+003                6.277E+002   3.038E+003
 +       Cs-137      661.66*    85. 10 4 .425E+003   4.42E+003   1.030E+004   2.059E+003 Eu-152      121.78     28.67  2.043E+004    1.87E+004  -1.129E+004   1.005E+004 344. 2 8   26.60  l .872E+004              -3.437E+004   9.042E+003 1408.01      21. 07 2.304E+004               -3.703E+004   1.053E+004 Eu-154      123.07     40.40  1 .455E+004   1 .45E+004 -4.42SE+002   7.153E+003 723. 3 0   20.06  2.791E+004                1 .621E+004  l.326E+004 1274.43      34.80  1.663E+004               -1.131E+OD3   7.750E+003 Eu-155       86.55     30.70  2.138E+004    2.14E+004   1.950E+004   1.054E+004 105.31     21.10  2.917E+004               -2.036E+OD4   l .436E+004
 +       Tl-208      583.19*    85. 00 3.669E+003    3.67E+003   8.171E+003   1 .692E+003 Bi-212      727. 3 3    6.67  8.061E+004    8.06E+004   4.451E+004   3.822E+004
 +       Pb-212      238.63*    43.60  1 .022E+004   1.02E+D04   1.272E+004   4.957E+003
 +       Bi-214      609.32*    45.49  1 .016E+004   1.02E+004   3.900E+004   4.805E+003 1120.29*     14.92  2.830E+004                6.220E+004   1.294E+004 1764.49*     15.30  2.907E+004                6.216E+004   1.293E+004
 +       Pb-214      295.22*    18.42  2.556E+004    9.34E+003   4.899E+004   1.237E+004 351. 93

• 35.60 9.336E+003 3.806E+004 4 .426E+003 Ra-226 186.21 3.64 1.524E+005 1.52E+005 l.314E+004 7.464E+004

 +       Ac-228      338.32     11. 27 4.837E+004    1.81E+004   3.380E+004   2.344E+004 911.20*    25.80  1. 809E+004               3.591E+004   8.429E+003 968.97*    15.80  2.040E+004                3.206E+004   9.149E+003 Am-241       59.54     35.90  1 .476E+004   1.48E+004   1.990E+003   7.242E+003
       +    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]

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

Filename: 6279 Report Generated On 8/20/2018 9:29:00 AM Sample Title B109100AFSWC051GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/20/2018 9:18:00 AM Acquisition Started 8/20/2018 9:18:58 AM Live Time 600. 0 seconds Real Time 600.9 seconds Dead Time 0 . 16 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE Cj-Z:t 0 [323] e.d:~~1~--- / JO\

Peak Analysis Report 8/20/2018 9:29:00 AM Page 2

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

Detector Name: 6279 Sample

Title:

Bl09100AFSWC051GD Peak Analysis Performed on: 8/20/2018 9:29:00 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 287- 308 301.21 75.43 0.62 1. 04E+002 68.86 2.88E+002 2 949- 959 953.99 238.62 1. 08 1.39E+001 21. 01 4.0lE+OOl 3 1400 - 1 4 15 1407.58 352 .01 0. 41 3.92E+001 21. 03 2.38E+001 4 2429- 2442 2435.57 608.99 0.54 3.88E+001 14 .58 5.22E+OOO 5 5836- 5854 5844.00 1 461.05 1.37 7.20E+001 16.97 O. OOE+OOO M :: First peak in a multiplet region m =- Other peak in a multiplet region F :: Fitted singlet Errors quoted at 2 . 000 sigma [324]

Interference Corrected Activity Report 8/20/2018 9:29:00 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:

B109100AFSWC051GD 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 7.80724E+005 1.96110E+005 Pb-212 1. 000 238.63* 43.60 1. 10886E+004 1.68005E+004 Bi-214 0 .461 609.32* 45.49 5.64737E+004 2.22973E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 4 .98567E+004 2.77548E+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

[325]

Interference Corrected Activity Report 8/20/2018 9:29:00 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 1 .000 7.807244E+005 1 .961096E+OOS Pb-212 1.000 1. 10 8861E+004 1 .680052E+004 Bi-214 0.461 5.647366E+004 2.229728E+D04 Pb-214 0.432 4.985666E+004 2.775485E+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: 8/20/2018 9:29: 00 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty: Type Nuclide 1 75.43 1.7276E-001 66.43 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 [326]

Nuclide MDA Report 8/20/2018 9 ! 29: 00 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC051GD 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   2.934E+004     2.93E+004 7.807E+005      O.OOOE+OOO Co-60      1173.23      99. 85  2.302E+004     2.11E+004 -2.456E+004     1 .016E+004 1332.49      99.98   2.105E+004                 4.427E+003    9.06SE+003 Nb-94        702.65     99.81   1. 634E+O 04   1.63E+004 -5.458E+003     7.183E+003 871.09     99.89   1.912E+004                -1 .232E+004   8.435E+003 Ag-108m      433.90     90.50   1.967E+004     l. 97E+004 2.551E+003     9.049E+003 614. 3 0   89.80   3.171E+004                -1 .892E+004   1.485E+004 722. 9 0   90.80   1.998E+004                -3.665E+003    8.886E+003 Cs-134       604.72     97.62   2.849E+004     2.47E+004 3.141E+004      l.333E+004 795.86     85.46   2.470E+004                -1.914E+004    1.111E+004 Cs-137       661. 66    85.10   2.584E+004     2.58E+004 1.516E+004      1.180E+004 Eu-152       121.78     28.67   7.229E+004     6.39E+004 l.496E+004      3.493E+004 344.28     26.60  6.387E+004                  1.313E+004    2.967E+004 1408. 01     21.07   l.138E+005                 4 .470E+004   4 .967E+004 Eu-154       123. 0 7   40 .40 5.041E+004      5.04E+004 -1.947E+004     2.434E+004 723. 3 0   20.06  9.045E+004                 -1.517E+004    4.024E+004 1274.43      34.80  6.079E+004                 -1.727E+003    2.630E+004 Eu-155        86. 55    30.70  8.042E+004      8.04E+004 2.705E+004      3.911E+004 105. 31    21.10  1.079E+005                  l .104E+005   5.236E+004 Tl-208       583 .19    85.00   2.318E+004     2.32E+004 5.972E+003      1.057E+004 Bi-212       727.33      6.67   2.890E+005     2.89E+005 l .948E+005     1.295E+005
 +      Pb-212       238.63*    43.60   2.784E+004     2.78E+004 1.109E+004      1. 284E+004
 +      Bi-214       609.32*    45.49   2.212E+004     2.21E+004 5.647E+004      9.089E+003 1120. 29     14.92  1 .692E+005                 1.123E+005    7.576E+004 1764.49      15.30  1.636E+005                  3.403E+004    7.003E+004
 +      Pb-214       295.22     18.42  1.241E+005      3.88E+004 1.264E+005      S.910E+004 351.93*    35.60  3.877E+004                  4 .986E+004   1.766E+004 Ra-226       186. 21     3.64  5.029E+005      5.03E+OOS 2.185E+005      2.404E+OOS Ac-228       338.32     11.27  1. 524E+005     1 .06E+OOS 1.854E+004     7.094E+004 911. 2 0   25.80  1.064E+OOS                  1.072E+005    4.874E+004 96 B. 9 7  15.80  1.585E+OOS                 -7.233E+004    7.163E+004 Am-241        59.54     35.90   7.156E+004     7.16E+004 4.978E+004      3.466E+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

[327]

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

Filename: 6279 Report Generated on 8/18/2018 2:51 : 08 PM Sample Title B109100AFSWC052GD Sample Description WWTF WALL Sample Identification 052 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 Crf-7 Samp le Size ~E+OOl MA2

                                           ~       ~/z_ r/rr-Sample Taken On                    8/18/2018      2: 40: 00 PM Acquisition Started                8/18/2018      2: 41: 07 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE Cj-2-(f+/-> tJ. TIME ~ Z . ~ "

                                                             ~~l1A5&f\/<<:::-l

[328]

Peak Analysis Report 8/18/2018 2: 51: 08 PM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSWC052GD Peak Analysis Performed on: 8/18/2018 2:51:08 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 1 296- 306 3 00. 61 75.28 0.39 4.62E+001 43.24 1 .76E+002 2 335- 354 339.20 84.92 0.45 5.27E+001 54.02 1.92E+002 3 948- 959 953.90 238.59 0.54 2.56E+001 18.92 2. 54E+001 4 1401- 1414 1407.98 352. 11 0.73 4.60E+001 17 . 13 1.00E+OOl 5 2035- 2050 2042.65 510.76 0.56 3.69E+001 14 .90 6.09E+OOO 6 2431- 2443 2436.71 609.27 0.73 3.58E+001 16.15 1.12E+001 7 2641- 2652 2646.05 66 1 .61 1. 09 2.03E+001 12.67 7.69E+OOO 8 5834- 5853 5844 .1 7 1461 .09 0.63 7.70E+001 19.44 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 [329]

Interference Corrected Activity Report 8/18/2018 2: 5 1: 08 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:

B109100AFSWC052GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  .......... . . ..... .. i! ** **     IDENTIFIED NUCLIDES

• t .. .......... ........

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 8.36141E+005 2.23260E+005 Cs-137 1.000 661.66* 85 .10 1.67432E+004 1.06320E+004 Eu-155 0.346 86.55* 30.70 4.33398E+004 4.52291E+004 ¢)c.i--l~ *~ kt.'\,~' Vo-' 105.31 21.10 Pb-212 1. 000 238.63* 43.60 2.03636E+004 l.54230E+004 Bi-214 0.461 609.32* 45.49 5.22466E+004 2.43820E+004 1120.29 14 .92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 5.85438E+004 2.35026E+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

[330]

Interference Corrected Activity Report 8/18/2018 2: 51: 08 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 1. 000 8.361414E+005 2.232597E+005 Cs-137 1.000 1.674319E+004 l. 063196E+00 4 Eu-155 0.346 4.333979E+004 4.522906E+004 Pb-212 1.000 2.036355E+004 l. 542297E+00 4 Bi-214 0.461 5.224662E+004 2.438196E+00 4 Pb-214 0.432 5.854381E+004 2.350256E+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
  **********     UN I D E N T I F I E D           P E A K S     **********

Peak Locate Performed on: 8/18/2018 2:5 1 :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 75.28 7.6948E-002 93.65 5 510.76 6.1521E-002 40. 36 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [331]

Nuclide MDA Report 8/18/2018 2: 51 :08 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC052GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/M"'2 ) (pCi/M"'2 ) (pCi/M"2 )

 +      K-40       1460.82*    10.66   1. 788E+005    1.79E+005   8.361E+005   7.473E+004 Co-60      1173.23     99.85   2.784E+004     2. 11E+004  7.029E+003   1. 256E+004 1332.49     99.98   2.108E+004                -2.435E+003   9.078E+003 Nb-94       702.65     99. 81  2.232E+004     1.39E+004   7.653E+003   1.017E+004 871.09     99.89   1.388E+004                -3.957E+003   5.814E+003 Ag-108m     433.90     90.50   1.866E+004     1.87E+004   1.316E+004   8.543E+003 614.30     89.80   3.114E+004                -6.758E+003   1 .457E+004 722.90     90.80   2.264E+004                 1.284E+004   l .022E+004 Cs-134      604.72     97.62   2.908E+004     2.07E+004  -1.654E+004   l .363E+004 795.86     85.46   2.066E+004                 3.911E+003   9.083E+003
 +      Cs-137      661.66*    85.10   1.430E+004     l .43E+004  1 .674E+004  6.032E+003 Eu-152      121 . 78   28.67   7.126E+004     6.19E+004   8.370E+004   3.441E+004 344.28     26.60   6.18BE+004                -8.719E+004   2.867E+004 1408.01     21.07   8.907E+004                 4.811E+004   3.730E+004 Eu-154      123.07     40 .40  4.892E+004     4.89E+004  -2.605E+004   2.359E+004 723.30     20.06   1 .025E+005                5.816E+004   4.626E+004 1274 .43    34.80   5.896E+004                 1.595E+004   2.538E+004
 +      Eu-155       86.55*    30.70   7 . 256E+004   7.26E+004   4.334E+004   3.517E+004 105.31     21.10   1.022E+005                 1.176E+005   4.951E+004 Tl-208      583.19     85.00   2.674E+004     2.67E+004   7.983E+003   1 .235E+004 Bi-212      727. 33     6.67   2.842E+005     2.84E+005   4. 876E+004  1 .270E+005
 +      Pb-212      238.63*    43.60   2.310E+004     2.31E+004   2.036E+004   1 .047E+004
 +      Bi-214      609.32*    45.49   2.997E+004     3. 00E+004  S.225E+004   1. 301E+004 1120. 29    14 .92  1. 866E+O 05               1. 572E+OOS  8.449E+004 1764.49     15.30   1.516E+005                 8.702E+004   6.402E+004
 +      Pb-214      295.22     18.42   1. 023E+O 05   2.54E+004   1.985E+004   4.823E+004 351. 93

• 35.60 2.536E+004 S.854E+004 1. 096E+O 04 Ra-226 186. 21 3.64 5.169E+005 S.17E+005 7.765E+004 2.474E+005 Ac-228 338.32 11. 27 1 .671E+005 8.62E+004 2.541E+004 7.824E+004 911. 2 0 25.80 8.615E+004 5.537E+004 3.859E+004 968.97 15 .80 1.488E+005 6.030E+004 6.678E+004 Am-241 59.54 35.90 6.914E+004 6.91E+004 -3.320E+004 3.344E+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

[332]

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

Filename: 6279 Report Generated On 8/20/2018 9:53:36 AM Sample Title Bl09100AFSWC053GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/20/2018 9:43: 00 AM Acquisition Started 8/20/2018 9:43:34 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE Cj-2-/~ [333] TIME ~'.)5" R:,f"Mit t t ~

Peak Analysis Report 8/20/2018 9:53:36 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSWC053GD Peak Analysis Performed on: 8/20/2018 9:53:36 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 1 181- 190 185.77 46.57 0 .44 9.07E+OOO 24.88 6.39E+001 2 296- 307 300.74 75.31 0 .47 l. 48E+001 46.65 2.09E+002 3 949- 972 954. 49 238.74 0 .87 5.14E+001 3 1 .10 4.76E+001 4 1401- 1413 1406.56 351.75 0 .59 2.72E+001 16.32 1.48E+001 5 2430- 2443 2436.17 609. 14 0 .34 3.84E+001 15.75 8.63E+OOO 6 5837- 5853 5845.23 1461.36 1. 27 6.58E+001 17.78 4.17E+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 [334]

Interference Corrected Activity Report 8/20/2018 9:53:36 AM Page 3

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

Sample

Title:

B109l00AFSWC053GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1. 000 1460.82* 10.66 7.13916E+005 2.02508E+OOS Pb-212 1. 000 238.63* 43.60 4.08545E+004 2.56055E+004 Bi-214 0.461 609.32* 45.49 5.58916E+004 2.39093E+004 1120.29 14 .92 1764.49 15. 30 Pb-214 0.432 295.22 18.42 351.93* 35.60 3.45752E+004 2.13738E+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

[335]

Interference Corrected Activity Report 8/20/2018 9:53:36 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/MA 2 ) Uncertainty K-40 1.000 7.139164E+005 2.025076E+005 Pb-212 1.000 4.085450E+004 2.560549E+004 Bi-214 0.461 5.589157E+004 2.39093SE+004 Pb-214 0.432 3.457524E+004 2.137376E+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: 8/20/2018 9:53:36 AM Peak Locate From Channel: BS Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 46.57 1.5120E-002 274.28 2 75. 31 2.4702E-002 314.76 M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [336]

Nuclide MDA Report 8/20/2018 9:53:36 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC053GD 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   1.588E+OOS    l.59E+OOS   7.139E+005  6.474E+OD4 Co-60     1173.23     99.85   2.506E+004    l.80E+004   4.354E+002  l.117E+004 1332.49     99.98   1. 801E+004              -l.630E+004  7.543E+003 Nb-94       702.65    99.81   1.785E+004    1.79E+004  -8.328E+003  7.942E+003 871.09    99.89   1.821E+004               -2.470E+004  7.979E+003 Ag-108m     433.90    90.50   2.026E+OD4    2.03E+D04  -6.233E+003  9.345E+003 614 .30   89.80   2.963E+004               -2.528E+004  1 .381E+004 722.90    90.80   2.038E+004                2.656E+001  9.086E+003 Cs-134      604.72    97.62   2.793E+D04    2.39E+004  -1.176E+004  1 .305E+D04 795.86    85.46   2.386E+D04                4.043E+003  1 .069E+004 Cs-137      661. 66   85.10   3.165E+004    3.16E+004   6.585E+003  1. 471E+004 Eu-152      121.78    28.67   7.166E+004    6.78E+004   4.389E+004  3.462E+004 344.28    26.60   6.783E+004                4.414E+004  3.165E+004 1408 .01    21.07   1.005E+005                2.713E+004  4.302E+004 Eu-154      123.07    40.40   5.104E+004    5.10E+004   2.131E+004  2.466E+OD4 723. 3 0  20.06   9.226E+004                l.964E+003  4.114E+004 1274.43     34.80   6.079E+004               -5.418E+004  2.630E+004 Eu-155       86.55    30.70   7.800E+004    7.80E+004   2.295E+004  3.790E+004 105.31    21.10   1. OlOE+OOS              -1.0BSE+OOS  4 .889E+004 Tl-208      583.19    85.00  2.645E+004     2.65E+004   l.259E+004  1.220E+004 Bi-212      727.33     6.67  2.674E+005     2.67E+005  -1. 463E+OOS 1 .186E+005
 +       Pb-212      238.63*   43.60  3.827E+004     3.83E+004   4 .085E+004 l .806E+004
 +       Bi-214      609.32*   45.49  2.726E+004     2.73E+004   S.589E+OD4  1 .166E+004 1120.29     14.92   1 .943E+005               2.215E+005  8.836E+004 1764.49     15.30   1.801E+005                7.154E+004  7.829E+004
 +       Pb-214      295.22    18.42  1.069E+005     2.97E+004   4.154E+004  5.049E+004 351.93*   35.60  2.967E+004                 3.458E+004  l .312E+004 Ra-226      186.21     3.64  4.798E+005     4.80E+OOS  -l.167E+005  2.288E+OOS Ac-228      338.32    11.27  l.453E+005     7.06E+004  -8.447E+003  6.736E+004 911. 20   25.80  7.062E+004                 8.178E+003  3.083E+004 968.97    15.80  1.433E+005               -l.218E+004   6.407E+004 Am-241       59.54    35.90  6.937E+004     6.94E+004   3.926E+004  3.356E+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

[337]

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

Filename: 6279 Report Generated On 6 /20/2.016 10: 18 : 37 AM Sample Title B109100AFSWC054GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/20/2018 10:08:00 AM Acquisition Started 8/20/2018 10:08:35 AM Live T ime 600.0 seconds Real T ime 600.9 seconds Dead Time 0 . 15 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 9-2-{6 TIME {ft> 0 ' [338] C2-~1~

Peak Analysis Report 8/20/2018 10:18:37 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSWC054GD Peak Analysis Performed on: 8/20/2018 10:18:36 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 1 296- 305 300.99 75.37 1. 32 6.BlE+OOl 38.71 1.35E+002 2 950- 959 954.85 238.83 0 .42 1 .84E+001 19. 21 3.26E+001 3 1402- 1415 1407.79 352.06 0 .32 2.43E+001 18. 65 2.17E+001 4 2430- 2442 2435.95 609.08 1. 24 2.53E+001 14. 28 9.75E+OOO 5 5835- 5851 5842.58 146 0 .70 0 .33 6.07E+001 17. 27 4 .31E+OOO M -= First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [339]

Interference Corrected Activity Report B/20/2018 10:18:37 AM Page 3

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

Sample

Title:

B109100AFSWC054GD 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 6.57992E+005 1.95796E+005 Pb-212 1. 000 238.63* 43.60 1. 4 6109E+004 1.54661E+004 Bi-214 0.461 609.32* 45.49 3.67758E+004 2.12696E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 3.09111E+004 2.41594E+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

[340]

Interference Corrected Activity Report 8/20/2018 10:18:37 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1 .000 6.579920E+005 1.957961E+005 Pb-212 1 .000 1.461085E+004 1.546610E+004 Bi-214 0.461 3.677585E+004 2.126962E+004 Pb-214 0.432 3.091114E+004 2.415936E+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: 8/20/2018 10 :18:36 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 75.37 1.1344E-001 56.88 M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [341]

Nuclide MDA Report 8/20/2018 10:18:37 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM sample

Title:

B109100AFSWC054GD 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 1.623E+005 1.62E+OOS 6.580E+005 6.650E+004 Co-60 1173.23 99.85 2.35SE+004 2.03E+004 -2.917E+003 1. 042E+O 04 1332.49 99.98 2.034E+004 5.133E+003 8.709E+OD3 Nb-94 702.65 99.81 1.989E+004 1 .99E+004 -2.632E+003 8.959E+003 871.09 99.89 2.040E+004 -4.575E+003 9.077E+003 Ag-108m 433.90 90.50 1. 905E+004 1 .91E+004 -1.920E+004 8.742E+003 614.30 89.80 2.897E+004 -2.412E+003 1 .348E+D04 722.90 90.80 1. 998E+004 1 .792E+004 8.886E+003 Cs-134 604.72 97.62 2.617E+004 2.01E+004 1 .149E+004 1.217E+004 795.86 85.46 2.011E+004 8.595E+003 8.814E+003 Cs-137 661. 66 85.10 2.675E+004 2.68E+OD4 1 .808E+004 1. 226E+D04 Eu-152 121.78 28.67 7.090E+004 6.74E+004 4.642E+004 3.424E+004 344.28 26.60 6.735E+004 -1 .338E+004 3.141E+004 1408.01 21.07 1.005E+005 -1.957E+004 4.302E+004 Eu-154 123.07 40.40 4.996E+004 5.00E+004 -6.735E+003 2.412E+004 723.30 20.06 9.045E+004 8.113E+004 4 .024E+004 1274.43 34.80 6.783E+004 4.449E+003 2.983E+004 Eu-155 86.55 30.70 8.268E+004 8.27E+004 8.015E+004 4 .024E+004 105.31 21.10 9.911E+004 3.891E+004 4.79SE+004 Tl-208 583.19 85.00 2.289E+004 2.29E+004 -2.460E+D03 1 .042E+004 Bi-212 727.33 6.67 2.498E+005 2.50E+005 -1. 538E+OOS 1 .098E+OOS

 +      Pb-212       238.63*    43.60  2.466E+004     2.47E+004 1 .461E+004   l.125E+004
 +      Bi-214       609.32*    45.49  2.826E+004     2.83E+004 3.678E+004    1.216E+004 1120.29      14.92  1.565E+005                 8.615E+004  6.944E+004 1764.49      15.30  1.9SOE+005                 8.822E+004  8.577E+004
 +      Pb-214       295.22     18.42  1. 079E+005    3.65E+004 -9.575E+003   5.099E+004 351. 93

• 35.60 3.655E+004 3.091E+004 1.655E+004 Ra-226 186 .21 3.64 5.044E+OOS 5.04E+005 -2.451E+004 2.411E+OOS Ac-228 338.32 11. 27 1.720E+005 9.48E+004 6.450E+004 8.073E+004 911. 2 0 25.80 9.478E+004 2.981E+004 4.291E+004 968.97 15.80 1 .486E+OOS 1. 095E+005 6.668E+004 Am-241 59.54 35.90 7.389E+004 7.39E+004 -3.211E+004 3.582E+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

[342]

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

Filename: 6279 Report Generated On 8/20/2018 8:58:44 AM Sample Title Bl09100AFSWC055GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/20/2018 8:48:00 AM Acquisition Started 8/20/2018 8:48:42 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 9--2-/* 0 TIME~ [343] C.t1'~==4d

Peak Analysis Report 8/20/2018 8:58: 44 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:

B109100AFSWC055GD Peak Analysis Performed on: 8/20/2018 8:58:44 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 295- 306 301.28 75.45 0.48 6.90E+001 49. 01 2.12E+002 2 1399- 1413 1406.24 351.67 1. 01 4.69E+001 19.07 1.51E+001 3 2428- 2440 2434.65 608.76 0.38 3.25E+001 14.11 6.47E+OOO 4 2638- 2649 2644.00 66 1 .09 0.64 l.18E+001 11.04 7.18E+OOO 5 5835- 5853 5843.07 1460 .82 0.74 S.83E+001 17.44 S.70E+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 [344]

Interference Corrected Activity Report 8/20/2018 8:58:44 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:

Bl09100AFSWC055GD 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 6.32146E+005 1.96914E+005 Cs-137 0.999 661.66* 85.10 9.72068E+003 9. 15 33SE+003 Bi-214 0.460 609.32* 45.49 4 .73649E+004 2.13164E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 5.95492E+004 2.58083E+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

[345]

Interference Corrected Activity Report 8/20/2018 8:58:44 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/M ... 2 ) Uncertainty K-40 1.000 6.321458E+005 1 .969140E+005 Cs-137 0 .999 9.720676E+003 9.153352E+003 Bi-214 0 .460 4 .736491E+004 2.131641E+004 Pb-214 0 .432 5.954919E+004 2.580826E+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: 8/20/2018 8:58: 44 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.45 1.1503E-001 71.01 M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [346]

Nuclide MDA Report 8/20/2018 8:58 : 44 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

Bl09100AFSWC055GD 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   1 .796E+005   l.80E+OOS    6.321E+005   7.514E+004 Co-60      1173.23    99.85   3.431E+004    2.65E+004    3.156E+004   1 .5BOE+004 1332.49    99.98   2.651E+004                 2.378E+004   1 .179E+004 Nb-94       702.65    99.81   2.082E+004    l.72E+004  -8.745E+002    9.427E+003 871 .09   99.89   1 .724E+004              - 1 .619E+004  7.495E+003 Ag-108m     433.90    90.50   2.281E+004    2.19E+004    9.679E+003   1 .062E+004 614. 3 0  89.80   3.171E+004               -l.359E+004    1. 485E+004 722.90    90.80   2.189E+004                 6.033E+003   9.845E+003 Cs-134      604.72    97.62   2.657E+004    1 .85E+004 -1.182E+003    1. 237E+004 795.86    85.46   1.B48E+004               -1.241E+004    7.999E+003
 +      Cs-137      661.66*   85.10   1.391E+004    1 .39E+004   9.721E+003   5.841E+003 Eu-152      121. 78   28.67   7.116E+004    6.97E+004  -1.861E+004    3.437E+004 344.28    26.60   6.972E+004               -3.355E+004    3.260E+004 1408.01    21.07   9.298E+004               -3.069E+004    3.927E+004 Eu-154      123.07    40 .40  5.113E+004    5.11E+004  -2.909E+004    2.470E+004 723. 3 0  20.06   1. OOBE+005                5.439E+004   4.539E+004 1274.43    34.80   6.783E+004                 5.439E+004   2.983E+004 Eu-155       86.55    30.70   8.426E+004    8.43E+004    9.170E+003   4.103E+004 105. 31   21. 10  1.0lSE+OOS                 5.498E+004   4.913E+004 Tl-208      583.19    85.00   2.670E+004    2.67E+004    2.181E+004   1.233E+004 Bi-212      727. 33    6.67   3.230E+005    3.23E+OOS    1.043E+004   1.465E+005 Pb-212      238.63    43.60   4 .792E+004   4.79E+004    4.454E+004   2.288E+004
 +      Bi-214      609.32*   45.49   2.383E+004    2.38E+004    4.736E+004   9.943E+003 1120.29    14.92   1 .891E+005                1.207E+OOS   8.572E+004 1764.49    15.30   l .902E+005                1.477E+OOS   8.335E+004
 +      Pb-214      295.22    18.42   l .017E+005   3.12E+004    1.302E+004   4.790E+004 351.93*   35.60   3.116E+004                 5.955E+004   1.386E+004 Ra-226      186.21     3.64   5.542E+005    5.54E+005    3.451E+OOS   2.660E+005 Ac-228      338.32    11 .27  1 .751E+OOS   1.14E+OOS    8.006E+004   8.225E+004 911. 2 0  25.80   1 .135E+005                3.691E+004   5.227E+004 968.97    15.80   1 .536E+005                7.729E+004   6.920E+004 Am-241       59.54    35.90   7.574E+004    7.57E+004  -9.334E+002    3.675E+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

[347]

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

Filename: 6279 Repor t Generated On 8/20/2018 9:15:01 AM Sample Title B109100AFSWC056GD Sample Description WWTF Wall Sample Identification Sample Type Gamme Direct Sample Geometry 3M90DWWTF1 . 27CM 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 8/20/2018 9:04:00 AM Acquisition Started 8/20/2018 9:04:59 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 7/31/2018 Efficiency I D 3MWWTF1,27CM DATA VALIDATED DATE Cf,--2 --j f3 TIME '":??;; [348] (£1m~;~

Peak Analysis Report 8/20/2018 9:15: 01 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:

B109100AFSWCOS6GD Peak Analysis Performed on: 8/20/2018 9:15: 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 1 295- 305 300.29 75.20 0.69 2.29E+001 47.53 2.26E+002 2 948- 961 954.32 238.70 0.60 3.04E+001 22.88 3.56E+001 3 1400- 1415 1407.83 352.07 0.47 5.54E+001 20.21 1.56E+001 4 2430- 2443 2436.80 609.30 0.85 3.27E+001 17.10 1. 43E+ 001 5 5836- 5853 5844.03 1461.06 0.62 7.20E+001 19.06 6.0lE+OOO M :; First peak in a multiplet region m = Other peak in a multiplet region F : Fitted singlet Errors quoted at 2 . 000 sigma [349]

Interference Corrected Activity Report 8/20/2018 9: 15 :01 AM Page 3

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

Sample

Title:

B109100AFSWC056GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  . . . . . . . .. ~ " .. .. ... . . IDENTIFIED NUCLIDES           .. * * * * * * * * * * * * * ,o fl I I' *

• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-4 0 1. 000 1460.82* 10 .66 7.80623E+005 2.17518E+005 Pb-212 1 . 000 238.63* 43.60 2.41628E+004 1. 86147E+004 Bi-214 0 . 461 609.32* 45.49 4.76253E+004 2.55636E+004 1120.29 14 .92 1764.49 15 .30 Pb-214 0 .432 295.22 18 .42 351.93* 35.60 7.03866E+004 2.77669E+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

[350]

Interference Corrected Activity Report 8/20/2018 9:15: 01 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 1. 000 7.806227E+005 2.175179E+OOS Pb-212 1.000 2.416279E+004 1.861469E+004 Bi-214 0.461 4. 762533E+004 2.556360E+004 Pb-214 0.432 7.03866SE+004 2.776691E+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: 8/20/2018 9:15:01 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 75.20 3.8199E-002 207.37 M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [351]

Nuclide MDA Report 8/20/2018 9:15 : 01 AM Page s

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC056GD 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. 842E+005   1.84E+005  7.806E+OOS   7.742E+004 Co-60     1173.23    99.85   2.248E+004    2.03E+004  1.803E+004   9.885E+003 1332.49    99.98   2.034E+004               6.574E+003   8.709E+003 Nb-94        702.65   99.81   1. 821E+004   1.82E+004 -1.819E+003   8.120E+003 871.09   99.89   1. 999E+004              7.645E+003   8.868E+003 Ag- 108m     433.90   90.50   2.065E+004    2.06E+004  6.448E+003   9.538E+003 614.30   89.80   3.191E+004               9.416E+003   1 .495E+004 722.90   90.80   2.189E+004               4.962E+003   9.845E+003 Cs-134      604.72   97.62   2.868E+004    2.16E+004 -5.215E+003   1.343E+004 795.86   85.46   2.161E+004              -7.926E+002   9.560E+003 Cs-137      661.66   85.10   2.584E+004    2.58E+004 -2.026E+004   1.180E+004 Eu-152      121.78   28.67   7.242E+004    6.64E+004 -3.476E+003   3.499E+004 344.28   26.60   6.638E+004               2.053E+004   3.092E+004 1408 . 01  21.07   9.298E+004               2.255E+004   3.927E+004 Eu-154      123.07   40.40   5.005E+004    5.00E+004  3.984E+003   2.416E+004 723.30   20.06   9.746E+004              -1.844E+003   4.374E+004 1274.43    34.80   6.263E+004              -7.152E+003   2.723E+004 Eu-155       86.55   30.70   7.540E+004    7.54E+004 -2.879E+003   3.660E+004 105.31   21.10  1. 002E+005               3.119E+004   4 .850E+004 Tl-208      583.19   85.00   2.347E+004    2.35E+004 -8.184E+002   1.071E+004 Bi-212      727.33    6.67   2.890E+005    2.89E+OOS  4 .418E+004  1.29SE+005
 +       Pb-212      238.63*  43.60   2.839E+004    2.84E+004  2.416E+004   1.312E+004
 +       Bi-214      609.32*  45.49   3.442E+004    3.44E+004  4.763E+004   1.524E+004 1120 .29   14. 92 1 .532E+005              -1.694E+004   6.777E+004 1764.49    15. 30 1 .852E+005               1. 390E+005  8.086E+004
 +       Pb-214      295.22   18. 42 1 .084E+005    3.20E+004  9.175E+004   5.124E+004 351.93*  35.60   3.203E+004               7.039E+004   1 .430E+004 Ra-226      186.21    3.64   5.249E+005    5.25E+005  9.128E+004   2.514E+005 Ac-228       338.32   11. 27 1.501E+005     9.34E+004  1 .256E+004  6.976E+004 911.20   25.80   9.339E+004               3.031E+004   4.221E+004 968.97   15.80  1.561E+005                1 .630E+005  7.042E+004 Am-241        59.54   35.90   7.124E+004    7.12E+004  3.717E+004   3.449E+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

[352]

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

Filename: 6279 Report Generated On 8/22/2018 8:43: 04 AM Sample Title B109100AFSWC057GD Sample Description WWTF WALL Sample Identification 057 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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

                                     -z,r.J Sample Size                         <<;;i. 826-E+O 01 M"2
                                           ~       Y/21-/1.r Sample Taken On                    8/22/2018         8:33:00 AM Acquisition Started                8/22/2018         8:33:03 AM Live Time                                    600.0 seconds Real Time                                    600.5 seconds Dead Time                              0.08 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE q.-2-re [353] _ee:~)lj\~z~

                                                                - TIME~,

J

Peak Analysis Report 8/22/2018 8:43: 04 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:

B109100AFSWC057GD Peak Analysis Performed on: 8/22/2018 8:43:04 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 1 269- 276 272.33 68.21 0.47 2.48E+001 25.50 6.82E+001 2 295- 306 300.39 75.22 0.32 l .18E+001 46.57 2.11E+002 3 950- 961 955.51 238.99 0.53 2.50E+001 20.71 3.20E+001 4 1402- 1414 1407.52 351.99 0.79 3.66E+001 17. 11 l.34E+001 5 2430- 2444 2437.46 609.46 0.80 3.58E+001 16.50 l.13E+001 6 5839- 5855 5846.71 1461.73 1.22 6.21E+001 18.56 7.86E+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 [354]

Interference Corrected Activity Report 8/22/2018 8:43:04 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:

B109100AFSWC057GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• I ._ I * , I
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.999 1460.82* 10.66 6.75025E+005 2.09958E+005 Pb-212 1.000 238.63* 43.60 1 .99258E+004 l. 68244E+004 Bi-214 0 .461 609.32* 45.49 5.21643E+004 2.48856E+004 1120.29 14.92 1764.49 15. 30 Pb-214 0.432 295.22 18.42 351.93* 35.60 4.65496E+004 2.28678E+004 Am- 241 0.887 59.54* 35.90 1 .92372E+004 2.01873E+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

[355]

Interference Corrected Activity Report 8/22/2018 8:43:04 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 6.750250E+005 2.099583E+D05 Pb-212 1 . 000 1 .992577E+OD4 1.682444E+004 Bi-214 0.461 5.216428E+004 2.488556E+004 Pb-214 0.432 4.654955E+OD4 2.286782E+004 Am-241 0.887 1 .923720E+004 2.018728E+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: 8/22/2018 8:43:04 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 2 75.22 1.9623E-002 395.53 M = First peak in a multiplet region m : Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 00 0 sigma [356]

Nuclide MDA Report 8/22/2018 8: 43 :04 AM Page 5

• **** NUCLIDE MD A R E P O R T *****

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

Bl09100AFSWC057GD 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   2.044E+005      2.04E+005   6.7SOE+OOS   8 . 750E+004 Co-60     1173.23     99.85   2.138E+004      1 .63E+004  6.864E+003   9.332E+003 1332.49     99.98   1. 625E+004                -l.461E+004   6.661E+003 Nb-94       702.65    99.81   1 .926E+004     1.93E+004   9.657E+003   8.646E+003 871.09    99.89   2.124E+004                 -5.467E+003   9.494E+003 Ag-108m     433.90    90.50   1 .709E+OD4     1 .71E+004  1.28DE+003   7.760E+003 614.30    89.80   2.879E+004                 -2.455E+004   1 .339E+004 722.90    90.80   2.229E+004                  1.203E+004   1 .004E+004 Cs-134      604.72    97.62   2.872E+004      2.43E+004   6.282E+003   1 .344E+004 795.86    85.46   2.432E+004                 -1. 237E+004  l .092E+004 Cs-137      661.66    85.10   2.179E+004      2.18E+004  -6.341E+002   9.778E+003 Eu-152      121.78    28.67   6.653E+004      6.24E+004   4.086E+004   3.205E+004 344.28    26.60   6.241E+004                 -4.594E+004   2.893E+004 1408 .01    21. 07  8.026E+004                 -3.360E+004   3.290E+004 Eu-154      123.07    40.40   4 .691E+004     4.69E+004   5.288E+003   2.259E+004 723.30    20.06   1. 0 09E+O 05               3.089E+004   4.546E+004 1274.43     34.80   5.896E+004                  l.199E+004   2.538E+004 Eu-155       86.55    30.70   7.745E+004      7.74E+004   3.925E+004   3.762E+004 105.31    21.10   9.715E+004                  1.846E+003   4 .697E+004 Tl-208      583.19    85.00   2.518E+004      2.52E+004   3.610~+003   1 .156E+004 Bi-212      727.33      6.67  3.456E+OOS      3.46E+OOS   1.919E+005   1 .577E+005
  +       Pb-212      238.63*   43.60   2.595E+004      2.59E+004   1.993E+004   1 .19DE+004
  +       Bi-214      609.32*   45.49   3.125E+004      3.13E+004   5.216E+004   1 .365E+004 1120. 29    1 4 .92 1. 893E+005                 1. 093E+005  8.584E+004 1764.49     15.30   l.750E+005                  S.998E+004   7.575E+004
  +       Pb-214      295.22    18.42   1.090E+005      2.88E+OD4   S.764E+004   5.156E+004 351.93*   35.60   2.879E+004                  4.655E+004   1 .267E+004 Ra-226      186.21      3.64  4.898E+005      4.90E+005   9.865E+004   2.338E+OOS Ac-228      338.32    11. 27  1.639E+005      9.35E+004   1.083E+005   7.664E+004 911. 20   25.80   9.352E+004                  2.599E+004   4.227E+004 968.97    15.80   l.408E+005                 -2.374E+004   6.281E+004
  +       Am-241       59. 54*  35.90   3.211E+004      3.21E+004   1.924E+004   1. 500E+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

[357]

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

Filename: 6279 Report Generated On 8/22/2018 8:28:15 AM Sample Title B109100AFSWC058GD Sample Description WWTF WALL Sample Identification 058 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 C,Y} Sample Size 2 e~&E+O 01 MA2

                                          #--   ?/zr/1r Samp le Taken On                   8/22/2018      8:18:00 AM Acquisition Started                8/22/2018      8:18:14 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE Cf:--2-{8 TIME / Jz.o [358] (j!, t'&z1-wJJ~

Peak Analysis Report 8/22/2018 8:28:15 AM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSWCOS8GD Peak Analysis Performed on: 8/22/2018 8:28:15 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 (ke V) (keV) Area Uncert. Counts 1 183- 190 186. 4 0 46.73 0.32 9.24E+OOO 20.12 4.48E+001 2 287- 306 300.71 75.30 0.43 1. 16E+002 62.16 2.43E+002 3 345- 354 349.64 8 7 .54 0.49 4.llE+OOO 3 1 .68 1.09E+002 4 1075- 1085 1079.99 27 0 .11 0.57 8.45E+OOO 12.47 1.25E+001 5 1402- 1415 1408.24 352.17 0.95 3.05E+001 17.76 1.75E+001 6 2641- 2652 2646.75 66 1 .78 0.67 1 .60E+001 11. 23 6.02E+OOO 7 5838- 5853 5845.95 1 46 1 .54 0.80 6.lOE+OOl 17.11 3.98E+OOO M First peak in a multiplet region m "'- Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [359]

Interference Corrected Activity Report 8/22/2018 8:28 : 15 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:

B109100AFSWC058GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB t, * * * * * * * *

• I * * * * * * * .,
• IDENTIFIED NUCLIDES . . . ' .................

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.999 1460.82* 10.66 6.62714E+005 1.94576E+005 Cs-137 1 .000 661.66* 85.10 1. 31718E+004 9. 3 9583E+003 . A "Z. <>z!!J Eu-155 0.348 86.55* 30.70 3.33332E+003 2. 56860E+004 ._ ~ 105 .31 21.10 Pb-214 0.432 295.22 18.42 351.93* 35.60 3.88373E+004 2.33449E+004

           *=Energy line found in the spectrum.
           @ ~ Energy line not used f or Weighted Mean Activity Energy Tolerance :                     10.000 keV Nuclide confidence index threshold =                        0.30 Errors quoted at 2. 000 sigma

[360]

Interference Corrected Activity Report 8/22/2018 8:28: 15 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 6.627144E+005 1. 945762E+005 ~--(, l)t Cs-137 1 . 000 1. 31 7183E+O 04 9. 395834E+003 -, '7@ \C-- Eu-155 0 .348 3.333324E+003 2. 568595E+004 '- A, C ~* vv Pb-214 0 .432 3.883728E+004 2.334495E+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: 8/22/2018 8:28:15 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 46.73 l.5401E-002 217.69 2 75.30 1.9405E-001 53.39 4 270. 11 1.4087E-002 147.56 M - First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [361]

Nucl ide MDA Report 8/22/2018 8:28:15 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

Bl0910 0AFSWC058GD 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/MA2 )

 +      K-40        1460.82*    10.66   1.542E+005    1.54E+005   6.627E+OD5  6.240E+004 Co-60       1173 .23    99.85   2.079E+D04    2.08E+OD4   5.834E+003  9.036E+D03 1332.49     99.98   2.307E+004                1 .116E+004 1.007E+004 Nb-94         702.65    99.81   1.824E+004    1.82E+004   1 .822E+003 8.132E+003 871. 09   99.89   1.915E+D04                4.384E+003  8.447E+003 Ag-108m       433.90    90.50   1 .949E+004   1.87E+004  -1 .539E+004 8.96DE+003 614. 3 0  89.80   2.415E+004                2.783E+004  1.107E+004 722.90    90.80   1 .875E+004              -3.219E+D02  8.27DE+003 Cs-134        604.72    97.62   2.363E+004    2.26E+004   1.821E+004  l.090E+004 795.86    85.46   2.257E+004               -1.235E+004  1.004E+004
 +      Cs- 137       661.66

• 85.10 1 .294E+004 1 .29E+004 1.317E+004 5.352E+003 Eu-152 121. 78 28.67 6.501E+004 6.50E+004 -2.239E+004 3.129E+D04 344.28 26.60 6.696E+004 3.182E+004 3.121E+004 1408. 01 21.07 9.695E+004 5.880E+004 4.124E+D04 Eu-154 123.07 40 .40 4.691E+004 4.69E+004 2.081E+004 2.259E+004 723.30 20.06 8.489E+OD4 -2.381E+003 3.745E+004 1274.43 34.80 6.087E+004 2.070E+004 2.634E+004

 +      Eu-155         86.55*   30.70   4.408E+004    4.41E+004   3.333E+003  2.095E+OD4 105.31    21 .10  9.484E+004               -3.108E+OD4  4.581E+004 Tl-208        583.19    85 .00  2.436E+004    2.44E+004   2.066E+004  1.115E+004 Bi-212        727.33     6.67   2.842E+005    2.84E+005   1.902E+005  1.270E+005 Pb-212        238.63    43.60   4.738E+OD4    4.74E+OD4   4.481E+004  2.261E+004 Bi - 214      609.32    45.49   4.948E+OD4    4.95E+004   2.911E+004  2.277E+004 1120.29     14. 92  1. 782E+OOS               1.321E+005  8.030E+D04 1764.49     15.30   l.307E+OD5               -2.175E+D03  5.356E+004
 +      Pb-214        295.22    18.42   1.034E+005    3.26E+004   6.721E+D04  4.876E+004 351.93*   35.60   3.257E+D04                3.884E+004  1.456E+004 Ra-226        186.21     3.64   4.66DE+005    4.66E+OD5   1.582E+D05  2.219E+005 Ac-228        338.32    11. 27  l.467E+005    9.07E+D04  -3.056E+004  6.806E+004 911. 2 0  25.80   9.065E+004                7.482E+004  4.084E+004 968.97    15.80   1.200E+D05                6.157E+003  5.238E+004 Am-241         59.54    35.90   6.616E+004    6.62E+004  -2.663E+004  3.196E+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

[362]

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

Filename: 6279 Report Generated On 8/21/2018 2:26:55 PM Sample Title B109100AFSWC059GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Pirect Sample Geometry 3M90DWWTF1.27CM 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 8/21/2018 2:16:00 PM Acquisition Started 8/21/2018 2:16:53 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 7--2-tfc

                                                      ;:,   TIME 1 ? ~

[363] ?K-.1:ft~f, ~

Peak Analysis Report 8/21/2018 2:26:55 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:

B109100AFSWC059GD Peak Analysis Performed on: 8/21/2018 2:26:55 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 Uncert. Counts 1 296- 310 300.25 75.19 0.63 1 .01E+002 47.94 1.62E+002 2 1176- 1187 1180.84 295.32 0.59 2.22E+001 17.77 2.08E+001 3 1400- 1411 1405 .40 351. 46 0.73 2.09E+001 15.49 1.51E+001 4 2429- 2441 2435.27 608.92 1.14 2.84E+001 11. 44 1.63E+OOO 5 5833- 5851 5842.38 1460.65 0.75 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 [364]

Interference Corrected Activity Report 8/21/2018 2:26:55 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:

B109100AFSWC059GD 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 7.58882E+005 1. 93 006E+O 05 Bi- 214 0 .461 609.32* 45.49 4.13196E+004 1 .73894E+004 1120.29 14.92 1764.49 15.30 Pb-214 1 .000 295.22* 18.42 4. 82387E+004 3.93515E+004 351.93* 35.60 2.65587E+004 2.00610E+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

[365]

Interference Corrected Activity Report 8/21/2018 2:26:55 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 7.588816E+005 1. 930058E+005 Bi-214 0.461 4.131964E+004 1. 738939E+004 Pb-214 1.000 3.103081E+004 1. 787257E+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: 8/21/2018 2:26:55 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 75.19 1.6869E-001 47.36 M -= First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [366]

Nuclide MDA Report 8/21/2018 2:26 : 55 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC059GD 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   2.934E+004    2.93E+004    7.589E+OD5   O.OOOE+OOO Co-60      1173.23    99.85   2.248E+004    2.17E+D04    1.039E+004   9.885E+003 1332.49    99.98   2.174E+004                 6.311E+003   9.407E+003 Nb-94        702.65   99.81   1.924E+004    1.92E+004  -1.845E+OD4    8.633E+003 871.09   99.89   2.199E+004               -1. 248E+003   9.868E+003 Ag-108m      433.90   90.50   1. 863E+004   1 .86E+004 -1.087E+004    8.531E+003 614.30   89.80   2.S93E+004               - 3.349E+D04   1.196E+004 722.90   90.80   1. 998E+004                1. 786E+OD3  8.886E+003 Cs-134       604.72   97.62   2.360E+004    1 .90E+OD4   2.688E+OD4   1. 089E+004 795.86   85.46   1 .905E+004                7.29DE+003   8.279E+OD3 Cs-137       661.66   85.10   2.456E+004    2.46E+004    1. 236E+004  1 . 117E+004 Eu-152       121. 78  28.67  6.724E+004     5.68E+004  -4.031E+004    3.241E+OD4 344.28   26.60  5.680E+004                -1.721E+004    2.613E+004 1408. 01   21.07  8.469E+004                  4.270E+004   3.512E+004 Eu-154       123.07   40.40   4.714E+004    4.71E+D04  -2.293E+OD4    2.270E+004 723.30   20.06   9.226E+004                 1. 387E+004  4.114E+D04 1274.43    34.80   7.261E+004                 3.738E+004   3.222E+004 Eu-155        86.55   30.70   7.922E+004    7.92E+004    2.902E+OD4   3.851E+D04 105.31   21.10   9.251E+004               -1. 960E+004   4.465E+004 Tl-208       583.19   85.00   2.318E+004    2.32E+004    7.307E+003   1. 057E+OD4 Bi-212       727.33    6.67  3.230E+005     3.23E+005  -1 .404E+005   1.465E+005 Pb-212       238.63   43.60  4.450E+004     4.45E+004    2.422E+OD3   2.117E+004
 +      Bi-214       609.32*  45 .49 1. 395E+004    1.40E+D04    4.132E+004   5.006E+003 1120.29    14.92  1.864E+005                  2.019E+005   8.437E+004 1764.49    15.30  1.902E+005                  7.667E+004   8.335E+004
 +      Pb-214       295.22*  18.42  5.969E+004     2.95E+004    4.824E+004   2.691E+OD4 351.93*  35.60  2.954E+004                  2.656E+OD4   1.305E+004 Ra-226       186.21    3.64  5.073E+OOS     5.07E+005    3.590E+005   2.426E+OOS Ac-228       338.32   11. 27 1. 513E+005    9.62E+004    9.150E+004   7.035E+004 911.20   25.80   9.615E+004               -6.473E+D04    4 .36DE+004 968.97   15.80  1. 379E+005                 1. 237E+005  6.134E+OD4 Am-241        59.54   35.90  6.848E+004     6.85E+004  -2.841E+004    3.312E+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

[367]

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

Filename: 6279 Report Generated On 8/21/2018 2:40:07 PM Sample Title B109100AFSWC060GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/21/2018 2: 30: 00 PM Acquisition Started 8/21/2018 2:30:05 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 7r-2-r3: TIME ~~ [368]

                                                             /2J'1M£e.Ajlf=   ~

Peak Analysis Report 8/21/2018 2:40:07 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:

B109100AFSWC060GD Peak Analysis Performed on: 8/21/2018 2:40:07 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- 305 3 01. 0 0 75.38 0.99 5.76E+001 37.53 1 .29E+002 2 949- 959 954 . 17 238.66 0.55 1.64E+001 1 9.02 3. 06E+001 3 1400- 1412 1406.05 351 .62 0.91 3.47E+001 16.05 1 . 13E+001 4 2429- 2442 2435.02 608.85 0.73 2.75E+001 13.20 5 . 53E+OOO 5 5833- 5851 5842.34 146 0 .64 1. 72 6 . 14E+001 17.56 4. 63E+OOO M == First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [369]

Interference Corrected Activity Report 8/21/2018 2:4 0 :07 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:

B109100AFSWC060GD 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 6.65332E+005 1. 9896BE+005 Pb-212 1 . 000 238.63* 43.60 l.30462E+004 1 .52727E+004 Bi-214 0.461 609.32* 45.49 3.99986E+004 1.98094E+004 1120.29 14. 92 1764.49 15.30 Pb-214 0.432 295.22 18 .42 351.93* 35.60 4.40411E+004 2.14276E+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

[370]

Interference Corrected Activity Report 8/21/2018 2:40:07 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 6.653323E+OOS 1 .989685E+005 Pb-212 1 .000 1 .304625E+004 1 .527272E+00 4 Bi-214 0.461 3.999856E+004 1 .980944E+00 4 Pb-214 0.432 4.404108E+004 2.142761E+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: 8/21/2018 2:40:07 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Pea_k CPS Peak To l. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.38 9.5980E-002 65.18 M ~ First peak in a multiplet region m - Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [371]

Nuclide MDA Report 8/21/2018 2 :40: 07 PM Page s

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC060GD 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  1.708E+005      1.71E+005 6.653E+005      7.075E+004 Co-60      1173.23      99.85  1.951E+004      l.52E+004 -l.573E+004     8.400E+003 1332.49      99.98   l.524E+004                -2.648E+004    6.158E+003 Nb-94        702.65     99. 81 1.989E+004      1.82E+004 -1.263E+004     8.959E+003 871.09     99.89  1.821E+004                 -6.0SSE+003    7.979E+003 Ag-108m      433.90     90.50  1 .610E+004     1.61E+004 1 .000E+004     7.264E+003 614. 3 0   89.80  2.491E+004                 -1.591E+004    1.145E+004 722.90     90.80  1.998E+004                  1.490E+003    8.886E+D03 Cs-134       604.72     97.62  2.383E+004      2.21E+004 l.853E+004      1. 10DE+004 795.86     85.46  2.20BE+004                 -4.496E+003    9.796E+OD3 Cs-137       661.66     85. 10 2.489E+004      2.49E+004 -1.317E+004     1.133E+004 Eu-152       121.78     28.67  6.778E+004      6.54E+004 -4.655E+003     3.268E+OD4 344.28     26.60  6.539E+004                 -2.414E+004    3.043E+OD4 1408.0l      21.07  l . 138E+O OS               1. 334E+003   4.967E+004 Eu-154       123.07     40.40  4.838E+004      4 .84E+004 2.219E+004     2.333E+004 723. 3 0   20.06  9.045E+004                  8.004E+OD3    4.024E+004 1274 .43     34.80  5.481E+004                  8.379E+003    2.332E+004 Eu-155        86. 55    30.70  7.472E+004      7.47E+004 -5.971E+003     3.626E+004 105. 31    21. 10 9.587E+004                 -4.527E+004    4.633E+004 Tl-208       583.19     85.00  2.318E+004      2.32E+004 -7.344E+003     1.057E+004 Bi-212       72 7. 3 3   6.67  3.041E+005      3.04E+005 1 .506E+005     1. 370E+OOS
 +      Pb-212       238.63*    43.60  2.467E+004      2.47E+004 1 .30SE+D04     l.126E+004
 +      Bi-214       609.32*    45.49  2.31SE+004      2.31E+004 4.000E+004      9.604E+003 1120.29      14.92  1.598E+005                  9.385E+004    7.107E+004 1764.49      15.30  1. 576E+005                 1.955E+004    6.70SE+004
 +      Pb-214       295.22     18.42  1. 0 06E+OOS    2.62E+004 1.05SE+005      4.736E+004 351.93*    35.60  2.623E+004                  4 .404E+004   1.139E+004 Ra-226       186. 21     3.64  4 .813E+005     4.81E+005 l .709E+004     2.296E+005 Ac-228       338.32     11. 27 1 .636E+OOS     1.04E+OOS 1 .447E+OOS     7.653E+004 911. 20    25.80  1 .040E+005                 2.415E+004    4.751E+004 968.97     15.80  1.511E+005                 -4.247E+004    6.795E+004 Am-241        59. 54    35.90  6.700E+004      6.70E+004 -2.527E+004     3.237E+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

[372]

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

Filename: 6279 Report Generated On 8/22/2018 8:03:50 AM Sample Title B109100AFSWC061GD Sample Description WWTF WALL Sample Identification 061 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 ltY~ Sample Size -z. 82 E+OOl M:J fti,.1A..,- '8""f ~ r' I"'/ I 'I Sample Taken On 8/22/2018 7:53:00 AM Acquisition Started 8/22/2018 7:53:48 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 9-cjr TIME /3?f;

                                                                            /1 ,..
                                                                           /KrtiVl/l::5S--eryt -~~Jr~ v

[373]

Peak Analysis Report 8/22/2018 8:03:50 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:

B109100AFSWC061GD Peak Analysis Performed on: 8/22/2018 8:03:49 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- 305 300.71 75.30 0.99 9.85E+001 39.70 1. 30E+002 2 948- 958 953.79 238.56 0.75 2.91E+001 20.72 3.09E+001 3 2036- 2047 2041.88 51 0 .57 0.37 2.61E+001 15.79 1.39E+001 4 2431- 2443 2436.75 609.28 0.47 2.BOE+OOl 1 1 .97 2.95E+OOO 5 5836- 5854 5845.01 1461 .30 0.58 6.40E+001 16.00 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 [374]

Interference Corrected Activity Report 8/22/2018 8:03:50 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:

B109100AFSWC061GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

   ' * * * * * * .. ... * ... * * * * ~ 5 * *

• IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) uncertainty K-40 1.000 1460.82* 10.66 6.95049E+005 1.83946E+OOS Pb-212 1.000 238.63* 43.60 2.31963E+004 l .69150E+004 Bi-214 0.461 609.32* 45.49 4.0918SE+004 1 .81418E+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

[375]

Interference Corrected Activity Report 8/22/2018 8:03:50 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 1. 000 6.950489E+005 1. 839458E+005 Pb-212 1. 000 2.319629E+004 1.691503E+004 Bi-214 0.461 4.091847E+004 1.814177E+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 NT I F I E D             P E A K S     **********

Peak Locate Performed on: 8/22/2018 8:03:49 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 75.30 l.6417E-001 40.30 3 510.57 4.3479E-002 60.54 M ~ First peak in a multiplet region m == Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [376]

Nuclide MDA Report 8/22/2018 8:03:50 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC061GD 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  2.939E+004      2.94E+004 6.950E+005   O.OOOE+OOO Co-60      1173.23   99.85   2.017E+004      1.80E+004 -9.921E+003  8.730E+003 1332.49   99.98   1.803E+004                -6.764E+003  7.553E+003 Nb-94       702.65   99.81   1. 7 51E+O 04   1.75E+004 6.013E+003   7.770E+003 871. 09  99.89   2.043E+004                 3.692E+002  9.090E+003 Ag-108m     433.90   90.50   2.086E+004      2.09E+004 -1 .328E+004 9.647E+003 614.30   89.80   2.646E+004                -1 .062E+004 1.222E+004 722.90   90.80   2.299E+004                 7.972E+003  1.039E+004 Cs-134      604.72   97.62   2.408E+004      2.35E+004 -2.011E+003  l.113E+004 795.86   85.46   2.347E+004                -1 .587E+004 1.049E+004 Cs-137      661.66   85.10   3.041E+004      3.04E+004 2.287E+004   1. 4 09E+004 Eu-152      121.78   28.67   6.867E+004      6.60E+004 2.900E+003   3.312E+004 344.28   26.60   6.598E+004                -4.615E+004  3.072E+004 1408.01   21. 07  1.006E+005                 6.414E+004  4 .308E+004 Eu-154      123.07   40. 40  4. 759E+004     4.76E+004 -3.660E+004  2.293E+004 723.30   20.06   l.041E+005                 3.702E+004  4.705E+004 1274.43   34.80   6.087E+004                 6.917E+003  2.634E+004 Eu-1 55      86.55   30.70   7.821E+004      7.82E+004 8.885E+004   3.800E+004 105.31   21.10   9.213E+004                -6.505E+004  4.445E+004 Tl-208      583.19   85.00   2.545E+004      2.54E+004 -5.307E+003  1.170E+004 Bi-212      727.33    6.67   2.894E+005      2.89E+005 -1 .510E+005 1 .296E+005
 +      Pb-212      238.63*  43.60   2.531E+004      2.53E+004 2.320E+004   1 .158E+004
 +      Bi-214      609.32*  45.49   l. 733E+004     l.73E+004 4.092E+004   6.690E+003 1120. 29  14.92   1. 600E+005               -l .549E+005 7.117E+004 1764.49   15. 30  1. 804E+005                1 .305E+005 7.840E+004 Pb-214      295.22   18.42   9.404E+004      5.64E+004 5.690E+004   4.408E+004 351.93   35.60   5.641E+004                 3.023E+004  2.648E+004 Ra-226      186.21    3.64   4.789E+OOS      4.79E+005 8.794E+004   2.284E+005 Ac-228      338.32   11. 27  1 .584E+005     7.80E+004 -8.317E+004  7.389E+004 911.20   25.80   7.800E+004                 4.147E+001  3.451E+004 968.97   15.80   1 .587E+005                1 .277E+005 7.173E+004 Am-241       59.54   35.90   6.789E+004      6.79E+004 -2.188E+004  3.282E+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

[377]

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

Filename: 6279 Report Generated On 8/21/2018 1: 19 : 31 PM Sample Title B109100AFSWC062GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/21/2018 1 :09: 00 PM Acquisition Started 8/21/2018 1 :09:29 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 7/31/2018 Efficiency ID 3MWWTF1,27CM [378]

Peak Analysis Report 8/21/2018 1 : 19: 31 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:

B109l00AFSWC062GD Peak Analysis Performed on: 8/21/2018 1:19:30 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- 308 300.92 75.36 0.32 2.69E+001 52.33 2.37E+002 2 1402- 1414 1407.95 352.10 0.38 1 .71E+001 17.01 2.09E+001 3 2431- 2442 2436.04 609.11 0.54 2.43E+001 15.36 1. 37E+001 4 5833- 5852 5842.04 146 0 .56 1. 65 7.14E+001 19.82 7.56E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2. 000 sigma [379]

Interference Corrected Activity Report 8/21/2018 1: 1 9: 31 PM Page 3

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

Sample

Title:

B109100AFSWC062GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  . . .. . . .. .. - ..... .. ........ IDENTIFIED NUCLIDES          . . . . . ........ .... . .......

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Unce rtainty K-40 1. 000 1460.82* 10.66 7.74424E+005 2.25100E+005 Bi-214 0.461 609.32* 45.49 3.54640E+004 2.27764E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 2.17387E+004 2.18720E+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

[380]

Interference Corrected Activity Report 8/21/2018 1:19:31 PM Page 4

• • • • • I N T E R F E R E N C E C O R R E C T E D 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 7.744236E+005 2.251004E+005 Bi-214 0.461 3.546402E+004 2.277639E+004 Pb-214 0.432 2.173873E+004 2.187200E+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: 8/21/2018 1:19:30 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 75.36 4.4792E-002 194.71 M ~ First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [381]

Nuclide MDA Report 8/21/2018 1: 19: 31 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

Bl09100AFSWC062GD 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/M"2 ) (pCi/M"2 )

 +      K-40       1460.82*  10 .66  2.137E+005     2.14E+OD5    7.744E+005   9.220E+004 Co-60      1173.23   99.85   2.192E+004     1.96E+OD4    7.688E+OD3   9.6D6E+003 1332.49   99.98   1.960E+004                  1 .189E+004  8.339E+003 Nb-94       702.65   99.81   1.924E+004     1. 92E+004 -1.372E+003    8.633E+003 871.09   99.89   2.16DE+004                -7.362E+OD3    9.676E+OD3 Ag-108m     433.90   90.50   2.0D6E+004     2.0DE+004    6.813E+003   9.248E+003 614 .30  89.80   2.984E+D04                -5.916E+003    1. 392E+004 722.90   90.80   1.998E+004                -3.665E+D03    8.886E+OD3 Cs-134      604.72   97.62   2.697E+004     2.43E+004    1 .772E+D04  1.257E+OD4 795.86   85.46   2.429E+004                  l .836E+004  1. 0 90E+004 Cs-137      661. 66  85 .10  2.320E+004     2.32E+004    1.420E+004   1.D49E+004 Eu-152      121.78   28.67   6.897E+004     6.90E+004   4.066E+OD4    3.327E+004 344.28   26.60   7.335E+OD4                 2.461E+004    3.441E+004 1408.01   21.07   1.005E+OD5                 2.291E+004    4 .302E+004 Eu-154      123.07   40 .40  4.828E+004     4 .83E+004   1.325E+OD3   2.328E+004 723.30   20.06   8.86DE+004                -4.175E+OD4    3.931E+004 1274.43   34.80   5.887E+OD4                -5.288E+004    2.535E+OD4 Eu-155       86.55   30.70   7.521E+004     7.52E+004  -3.851E+003    3.6SOE+004 105.31   21.10   9.620E+004                 4 .662E+004   4.649E+004 Tl-208      583.19   85.00   2.568E+D04     2.57E+OD4   2.927E+004    1.181E+D04 Bi-212      727.33    6.67   2.436E+OD5     2.44E+005  -2.674E+OOS    1.067E+OD5 Pb-212      238.63   43.60   4.319E+004     4.32E+OD4   5.236E+004    2.052E+004
 +      Bi-214      609.32*  45.49   3.215E+004     3.21E+OD4   3.546E+004    1.41DE+004 1120.29   14.92   1 .532E+005                3.827E+004    6.777E+004 1764.49   15.30   1 .801E+OD5                l.303E+005    7.829E+004
 +      Pb-214      295.22   18.42   1.038E+OOS     3.45E+004   4.306E+004    4 .895E+D04 351.93*  35.60   3.453E+004                 2.174E+004    1.555E+004 Ra-226      186.21    3.64   4.554E+005     4 .55E+D05 -l.195E+OD5    2.167E+OOS Ac-228      338.32   11.27   1.66BE+OD5     8.45E+004  -1.955E+OD4    7.813E+D04 911.20   25.80   8.447E+004                 9.800E+003    3.775E+D04 968.97   15.80   1.561E+D05                 8.291E+004    7.042E+004 Am-241       59.54   35.90   7.026E+OD4     7.03E+004  -1.938E+004    3.400E+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

[382]

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

Filename: 6279 Report Generated On 8/2l/20l8 1:31 :51 PM Sample Title B109100AFSWC063GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 Samp le Taken On 8/21/2018 1: 21:00 PM Acquisition Started 8/21/2018 1: 21:49 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE tf-Z-(,f-

                                                       ~ t/Asffl'JfL~

TIME~ [383]

Peak Analysis Report 8/21/2018 1: 31:51 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:

B109100AFSWC063GD Peak Analysis Performed on: 8/21/2018 1 :31:51 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- 307 300.90 75.35 0.78 3.57E+001 44.92 l .82E+002 2 347- 356 351. 22 87.93 0.41 2.36E+001 30.06 8.34E+001 3 1399- 1413 1407. 02 35 1 .87 0.29 3.25E+001 18.58 1.85E+001 4 5837- 5854 5845.29 146 1 .37 1.74 6.58E+001 17.06 2.16E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F ; Fitted singlet Errors quoted at 2 . 000 sigma [384]

Interference Corrected Activity Report 8/21/2018 1: 31: 51 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:

B109100AFSWC063GD 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 7.14067E+005 1 .95115E+005 Ac.. . -z...

                                                                                           -i-f7 R ~

Eu-155 0.347 86.55* 30.70 1. 90668E+004 2.45754E+004 105 .31 21.10 Pb-214 0.432 295.22 18.42 351.93* 35.60 4. 13438E+004 2.44083E+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

[385]

Interference Corrected Activity Report 8/21/2018 1: 31: 51 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 7.140670E+005 1. 951154E+005 Eu-155 0.347 1.906679E+004 2.457541E+004 Pb-214 0.432 4.134377E+004 2.440832E+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: 8/21/2018 1:31: 51 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 75.35 5.9520E-002 125.78 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 [386]

Nuclide MDA Report 8/21/2018 1: 31:51 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC063GD 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 .231E+005 1. 23E+005 7.141E+005 4.688E+004 Co-60 1173.23 99.85 2.554E+004 2.24E+004 -8.325E+003 1.141E+004 1332.49 99.98 2.240E+004 -8.736E+003 9.737E+003 Nb-94 702.65 99.81 2.021E+004 1. 96E+004 -1.207E+004 9.118E+003 871.09 99.89 1 .956E+004 -l.487E+OD3 8.654E+003 Ag-108m 433.90 90.50 2.045E+004 2.04E+004 1.331E+003 9.442E+003 614.30 89.80 2.919E+004 3.655E+004 1.359E+004 722.90 90.80 2.038E+004 3.514E+003 9.086E+D03 Cs-134 604.72 97.62 2.716E+004 2.34E+004 1 .275E+004 1.267E+004 795.86 85.46 2.343E+004 3.542E+003 1.047E+004 Cs-137 661.66 85.10 2.099E+004 2.10E+004 1. 371E+004 9.381E+D03 Eu-152 121. 78 28.67 6.949E+004 6.34E+004 8.572E+OD3 3.353E+004 344.28 26.60 6.336E+004 -2.51DE+004 2.941E+004 1408.01 21.07 9.298E+004 1. 788E+004 3.927E+004 Eu-154 123.07 40.40 4.885E+004 4.88E+004 1 .770E+004 2.356E+004 723.30 20.06 8.860E+OD4 -3.451E+004 3.931E+004 1274.43 34.80 6.442E+004 2.271E+004 2.812E+004 Eu-155 86.55* 30.70 3.998E+004 4.00E+OD4 1.907E+004 1. 890E+004 105.31 21.10 9.537E+D04 8.242E+004 4.608E+004 Tl-208 583.19 85.00 2.515E+OD4 2.51E+004 2.719E+004 1 .155E+004 Bi-212 727.33 6.67 2.558E+005 2.56E+005 -3.07SE+003 1 .129E+005 Pb-212 238.63 43.60 4. 498E+004 4 .50E+004 2.011E+004 2.142E+004 Bi-214 609.32 45.49 5.774E+004 S.77E+004 - 9.597E+002 2.690E+004 1120.29 14. 92 1. 661E+005 -9.743E+004 7.423E+004 1764.49 15.30 1.636E+005 1.043E+OD5 7.003E+004

 +       Pb-214       295.22   18.42   1. 063E+005   3.41E+004 6.735E+004     5.024E+OD4 351.93*  35.60  3. 410E+004                4 .134E+D04  1.533E+004 Ra-226       186.21    3.64   4.968E+005    4.97E+005 -1.133E+005    2.373E+D05 Ac-228        338.32   11. 27  1. 547E+005   9.20E+004 7.141E+004     7.209E+D04 911. 20  25.80   9.197E+OD4                7.137E+004   4.150E+004 968.97   15.80   1. 511E+005               1. 135E+005  6.795E+004 Am-241         59.54   35.90   7.145E+004    7.15E+004 -1 .953E+004   3.46DE+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

[387]

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

Filename: 6279 Report Generated On 8/21/2018 1:50:46 PM Sample Title B109100AFSWC064GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/21/2018 1: 40: 00 PM Acquisition Started 8/21/2018 1:40:44 PM Live Time 600.0 seconds Real Time 601.0 seconds Dead Time 0.17 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1 ,27CM DATA VALIDATED DATE q- Zr-/ lf TIME 0::5~ {211As,<:;~;; ~ [388]

Peak Analysis Report 8/21/2018 1: SO: 46 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:

B109100AFSWC064GD Peak Analysis Performed on: 8/21/2018 1: SO: 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 1 1401- 1414 1407.64 352.02 0 .84 3 .74E+001 17.89 1.36E+001 2 5834- 5852 5843.08 1460.82 1. 33 8 .40E+001 18.33 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 [389]

Interference Corrected Activity Report 8/21/2018 1: 50:46 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:

B109100AFSWC064GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M ... 2 ) Uncertainty K-40 1. 000 1460. 82* 10 .66 9.10739E+005 2.13897E+005 Pb-214 0. 432 295.22 18.42 351.93* 35.60 4.75131E+004 2.38286E+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

[390]

Interference Corrected Activity Report 8/21/2018 1:50:46 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 9.107389E+OOS 2.138968E+OOS Pb-214 0.432 4.751308E+004 2.382862E+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: 8/21/2018 1 :50:46 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 All peaks were identified. [391]

Nuclide MDA Report 8/21/2018 1 :50:46 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFSWC064GD 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  2.934E+004     2.93E+004 9.107E+005     O.OOOE+OOO Co-60      1173.23     99.85   1.951E+004     1.9SE+004 -1.647E+004    8.400E+003 1332.49     99.98   2.034E+004                  l .711E+003 8.709E+003 Nb- 94       702.65    99.81   1 .989E+004    1. 87E+004 -2.092E+003   8.959E+003 871. 09   99.89   l .867E+004               -1.458E+004   8.210E+003 Ag- 108m     433.90    90.50   1 .707E+004    l. 71E+004 -l.274E+003   7.749E+003 614. 3 0  89.80   2.807E+004                  2.396E+004  1 . 303E+004 722.90    90.80  2.330E+004                 -1. 077E+003  1.055E+004 Cs-134       604.72    97.62  2.449E+004      2.25E+004    l. 625E+004 l.133E+004 795.86    85.46  2.254E+004                 - 1. 662E+004 l. 003E+004 Cs-137       661.66    85 .10 2.489E+004      2.49E+004    l. 417E+003 1. 133E+004 Eu-152       121.78    28.67   7.129E+004     6.93E+004 - l. 332E+004  3.443E+004 344.28    26.60   6.926E+004                -2.801E+004   3.236E+004 1408. 01    21.07   1. 005E+005                 l. 568E+004 4.302E+004 Eu-154       123. 07   40.40   5.068E+004     5.07E+004 -2.108E+004    2.448E+004 723. 3 0  20.06   1. 04 OE+005              -3.595E+004   4.699E+004 1274.43     34.80   5.688E+004                  l.240E+004  2.43SE+004 Eu-155        86.55    30.70   8.178E+004     8.18E+004 S.062E+004     3.979E+004 105. 31   21.10   9.879E+004                -4.923E+004   4.779E+004 Tl-208       583.19    85.00  2.864E+004      2.86E+004 2.385E+004     1.330E+004 Bi-212       727. 33    6.67  3.408E+OOS      3.41E+005 2.532E+OOS     1.553E+005 Pb-212       238.63    43.60  4.655E+004      4.66E+004 -2.4BSE+001    2.220E+004 Bi-214       609.32    45. 49 4.992E+004      4 .99E+004 -8.694E+003   2.299E+004 1120.29     14 .92 1. 864E+005                  1.422E+OOS  8.437E+004 1764.49     15.30  1. 514E+OOS                  1.195E+004  6.393E+004
 +      Pb-214       295.22    18.42  1.118E+005      3.08E+004 -5.398E+004    5.296E+004 351.93*   35.60  3.075E+004                   4.751E+004  l .366E+004 Ra-226       186. 21    3.64  4.637E+005      4.64E+005 3.419E+004     2.208E+005 Ac-228       338.32    11. 27 1.740E+005      9.88E+004 7.024E+004     8.174E+004 911. 2 0  25.80  9.884E+004                   2.509E+004  4.494E+004 968.97    15.80  1.699E+OOS                 -4.357E+004   7.737E+004 Am-241        59.54    35.90  7.635E+004      7.63E+004 -5.904E+004    3.705E+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

[392]

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

Filename: 6279 Report Generated On 8/21 /2016 10 !12:39 AM Sample Title B109100AFSWC065GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1.27CM 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 8/21/2018 10 :02: 00 AM Acquisition Started 8/21/2018 10 :02:37 AM Live Time 600.0 seconds Real Time 600.8 seconds Dead Time 0.13 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE 1-?=-tJ-4 TJME!i~ j;.~~ ' .* [393]

Peak Analysis Report 8/21/2018 10: 12:39 AM Page 2

• • • • • P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B109100AFSWC065GD Peak Analysis Performed on: 8/21/2 018 10 :12:38 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- 306 300.03 75.13 0.88 1.41E+002 69.87 2.78E+002 2 1175- 1187 1180.56 295.25 0.81 2.88E+001 17 .00 1 .63E+001 3 2432- 2444 2437. 01 609.35 0. 41 3.32E+001 13 .88 5.78E+OOO 4 5835- 5853 5843.99 1461.05 0.52 6.83E+001 18 .39 4.74E+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 [394]

Interference Corrected Activity Report 8/21/2018 10 :12:39 AM Page 3

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Sample

Title:

B109100AFSWC065GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M2 ) Uncertainty K-40 1.000 1460.82* 10.66 7.40172E+OOS 2.09540E+OOS Bi-214 0.461 609.32* 45.49 4.84045E+004 2.10473E+004 1120.29 14.92 1764.49 15.30

       * = 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

[395]

Interference Corrected Activity Report 8/21/2018 10:12:39 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 7.401724E+OOS 2.095399E+OOS Bi-214 0.461 4.840446E+004 2.104730E+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
  **********      UN I D E N T I F I E D            P E A K S     **********

Peak Locate Performed on: 8/21/2018 10 :12:38 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 2.3543E-001 49.47 2 295.25 4.7917E-002 59.13 Tol. Pb-214 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [396]

Nucl ide MDA Report 8/21/2018 10: 12:39 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

Bl09100AFSWC065GD 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/MA2 )

 +       K-40       1460.82*    10.66   1.734E+005    1.73E+D05  7.402E+005  7.204E+OD4 Co-60      1173.23     99.85   2.406E+004    1.71E+004  5.758E+003  1 .068E+004 1332.49     99.98   1.715E+004              -9.929E+003  7.111E+003 Nb- 94       702.65    99.81   2.171E+004    2.04E+004  8.413E+003  9.873E+OD3 871.09    99.89   2.040E+004               6.863E+003  9.077E+003 Ag- 108m     433.90    90.50   1.842E+004    1.84E+004 -7.025E+003  8.424E+003 614. 3 0  89.80   2.807E+004               2.072E+004  1.303E+004 722.90    90.80   2.038E+004              -1. 801E+004 9.086E+003 Cs-134       604.72    97.62   2.677E+004    2.34E+D04 -2.536E+004  1.247E+D04 795.86    85.46   2.343E+004              -3.216E+003  l.047E+004 Cs-137       661. 66   85 .10  2.389E+004    2.39E+004  1. 640E+004 l.083E+004 Eu-152       121.78    28.67   6.975E+004    6.44E+D04  2.674E+004  3.366E+004 344.28    26.60   6.438E+004              -3.740E+004  2.993E+004 1408.0l     21.07   8.895E+004               4.804E+004  3.725E+004 Eu-154       123.07    40.40   5.023E+004    5.02E+004  5.530E+004  2.425E+004 723. 3 0  20.06   9.577E+D04               2.626E+004  4.289E+004 1274.43     34.80   5.688E+004               1. 259E+002 2.435E+D04 Eu-155        86.55    30.70   7.885E+004    7.88E+004  1. 014E+004 3.832E+004 105 . 31  21.10   9.636E+004               1. 347E+004 4.657E+004 Tl-208       583.19    85.00   2.67DE+004    2.67E+004  2.744E+004  1.233E+004 Bi-212       727. 3 3   6.67   3.041E+OD5    3.04E+005 -5.415E+D04  1.370E+D05 Pb-212       238.63    43.60   4.686E+OD4    4.69E+004  5.838E+004  2.235E+004
 +       Bi-214       609.32*   45.49   2.248E+004    2.25E+004  4.840E+004  9.271E+D03 1120.29     14. 92  l.692E+OD5               6.351E+004  7.576E+D04 1764. 49    15.30   1.748E+OD5              -4.096E+004  7.564E+D04 Pb-214       295.22    18.42   1.053E+005    5.70E+004  4.971E+004  4.973E+004 351.93    35.60   5.699E+OD4               3.092E+003  2.677E+004 Ra-226       186. 21    3.64   5.013E+OD5    5.0lE+OOS -4.154E+004  2.396E+005 Ac-228       338.32    11.27   1.524E+005    9.75E+004 -6.888E+004  7.094E+D04 911. 20   25.80   9.751E+D04               1.599E+004  4.427E+004 968.97    15.80   1.561E+005               1.253E+005  7.042E+004 Am-241        59.54    35.90   7.080E+004    7.08E+OD4 -1.476E+003  3.428E+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

[397]

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

Filename: 6279 Report Generated On 8/21/2018 9:58:59 AM Sample Title Bl09100AFSWC066GD Sample Description WWTF Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90DWWTF1. 27CM 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 Samp le Taken On 8/21/2018 9:48:00 AM Acquisition Started 8/21/2018 9:48:58 AM Live Time 600.0 seconds Real Time 600.8 seconds Dead Time 0.13 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 7/31/2018 Efficiency ID 3MWWTF1,27CM DATAVALIDATED DATE <j-l---{r [398] ad:~fZ20

Peak Analysis Report 8/21/2018 9:58:59 AM Page 2

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Detector Name: 6279 Sample

Title:

B109l00AFSWC066GD Peak Analysis Performed on: 8/21/2018 9:58:59 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 296- 306 300 .94 75.36 0.84 2.41E+001 40.30 1.59E+002 2 336 - 345 340.89 85.35 0.95 2.15E+001 34.42 1.22E+002 3 1403 - 1414 1408.35 352.20 0.64 1.81E+001 14.25 1.29E+001 4 2326 - 2337 2331.36 582.94 0.63 1.76E+001 10. 71 4.44E+OOO 5 2430 - 2444 2436.78 609.29 1. 33 4.09E+001 14.70 4.14E+OOO 6 5834 - 5853 5844.73 1 461.23 1.14 7.96E+001 18.73 2.37E+OOO M :=- Fi rst peak in a multiplet region m Ot her peak in a multiplet region F Fi tted singlet Errors quoted at 2 . 000 sigma [399]

Interf erence Corrected Activity Report B/21/2018 9:58:59 AM Page 3

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Sample

Title:

B109100AFSWC066GD 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 Eu-155

1. 000 0.348 1460.82*

86.55* 105. 31 10.66 30.70 21.10 8.6358SE+OOS

1. 75891E+004 2.16484E+005 2.83983E+004 ~~,_z.2-!~

Tl- 208 1 . 000 583.19* 85.00 1. 32869E+O 04 8.26447E+003 Bi- 214 0.461 609.32* 45.49 5.95186E+004 2.25773E+004 1120. 29 14 .92 1764.49 15.30 Pb-214 0.432 295.22 18.42 351.93* 35.60 2.30226E+004 1.84451E+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

[400]

Interference Corrected Activity Report 8/21/2018 9:58:59 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 8.635847E+005 2.164836E+005 Eu-155 0.348 1.758913E+004 2.839833E+004 Tl-208 1.000 1.328685E+004 8.264472E+003 Bi-214 0.461 5.951856E+004 2.257730E+004 Pb-214 0.432 2.302257E+004 1. 844509E+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: 8/21/2018 9:58:59 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.36 4.0102E-002 167.50 M == First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [401]

Nuclide MDA Report 8/21/2018 9:58:59 AM Page 5

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Detector Name: 6279 Sample Geometry: 3M90 DWWTF1.27CM Sample

Title:

B109100AFSWC066GD 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/M"2 ) (pCi/M"2 )

 +      K-40        1460.82*    10. 66  1.305E+005    l .31E+OOS  8.636E+005  5.058E+004 Co-60       1173.23     99.85   2.506E+004    1 .96E+004  8.338E+003  1 .117E+004 1332.49     99.98   1.960E+004               -4.593E+003  8.339E+003 Nb-94         702.65    99.81   2.052E+004    l .67E+004  4.003E+003  9.274E+003 871.09    99.89   1.673E+004               -7.724E+002  7.241E+003 Ag-108m       433.90    90.50   1. B84E+004   l.88E+004  -1.107E+004  8.637E+003 614.30    89.80   3.006E+004                1.279E+004  1 .402E+004 722.90    90.80   2.077E+004                1.426E+004  9.282E+003 Cs - 134      604.72    97.62   2.657E+004    1.90E+004  -4.867E+003  1 .237E+004 795.86    85.46   1.905E+004               -7.183E+003  8.279E+003 Cs-137        661.66    85.10   2.320E+004    2.32E+004   1.484E+004  1 .049E+004 Eu-152        121.78    28.67   6.616E+004    6.54E+004  -6.175E+004  3.187E+004 344.28    26.60   6.539E+004               -3.582E+004  3.043E+004 140 8.01    21.07   9.298E+004                5.338E+004  3.927E+004 Eu-154        123.07    40. 40  4.694E+004    4.69E+004  -1.146E+004  2.261E+004 723.30    20.06   9.577E+004                6.829E+004  4.289E+004 1274 .43    34.80   6.079E+004               -2.358E+004  2.630E+004
 +      Eu-155         86.55*   30.70   4.686E+004    4 .69E+004  1 .759E+004 2.232E+004 105 .31   21.10   9.734E+004               -4.472E+004  4.706E+004
 +      Tl-208        583. 19*  85.00   1 .036E+004   1.04E+004   1 .329E+004 4.156E+003 Bi-212        727.33     6.67   2.838E+OOS    2.84E+005   1 .009E+005 1.268E+005 Pb-212        238.63    43.60   4.482E+004    4.48E+004  -1 .304E+004 2.134E+004
 +      Bi-214        609.32*   45.49   2.133E+004    2.13E+004   5.952E+004  8.694E+003 1120.29     14 .92  2.187E+OOS                1 .876E+005 1.005E+005 1764.49     15 .30  2.088E+005                1 .157E+005 9.264E+004
 +      Pb-214        295.22    18 .42  9.897E+004    2.74E+004   5.040E+004  4.655E+004 351.93*   35.60   2.735E+004                2.302E+004  1.195E+004 Ra-226        186 . 21   3.64   4.798E+005    4.BOE+OOS   1 .083E+005 2.288E+005 Ac-228        338.32    11. 27  1.668E+OOS    9.75E+004   4.830E+004  7.813E+004 911.20    25.80   9.751E+004                9.012E+004  4 .427E+004 968.97    15.80   1.460E+005                l.405E+005  6.539E+004 Am- 241        59.54    35.90   6.320E+004    6.32E+004  -1.465E+004  3.048E+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

[402]

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

Filename: 5452A Report Generated On 8/16/2018 2: 37 :40 PM Sample Title B109100AFSFC067GD Sample Description WWTF SUMP #1 Sample Identification 067 Sample Type GAMMA DIRECT Sample Geometry WWTF SUMP 1 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 8.260E+OOO M"2 Sample Taken On 8/16/2018 2:27:00 PM Acquisition Started 8/16/2018 2:27:37 PM Live Time 600.0 seconds Real Time 601.1 seconds Dead Time 0 , 18 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 8/16/2018 Efficiency ID WWTF SUMPl DATA VALIDATED DATE Cj-2-tk TIME /[z f.11rtmnj7/ ~~' [403]

Peak Analysis Report 8/16/2018 2:37: 40 PM Page 2

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

Detector Name: 5452A Sample

Title:

B109100AFSFC067GD Peak Analysis Performed on: 8/16/2018 2: 37: 39 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 83- 99 91. 44 22.86 0 .33 -1.21E+001 68.62 3.63E+002 2 285- 309 299.86 74.97 0 .86 3.48E+002 132.98 9.84E+002 3 367- 376 371.39 92.85 0 .58 -2.24E+001 57.40 3.74E+002 4 672- 687 676.23 169.06 0 .59 2.63E+001 60. 11 2.91E+002 5 948- 973 955.13 238.78 0 .38 8.93E+001 74. 13 3.02E+002 6 1174- 1188 1181.12 295.28 1. 14 5.23E+001 37.90 1.07E+002 7 1398- 1415 1407. 58 351.89 1. 21 1.72E+002 42.77 8.77E+001 8 2323- 2339 2331. 04 582.76 0.38 5.23E+001 28. 17 4 .68E+001 9 2426- 2446 2435.61 608.90 1. 34 2.16E+002 39. 10 4 .62E+001 10 2637- 2652 2644.78 661.20 0.76 7.50E+001 24.03 2.30E+001 11 3636- 3649 3642.69 910.67 0.91 3.78E+001 20.96 2.62E+001 12 4473- 4487 4479.20 1119.80 1. 29 3.75E+001 19.96 2.15E+001 13 4685- 4698 4691.13 1172.78 0.64 3.58E+001 19.50 2.12E+001 14 5321- 5334 5327.88 1331.97 0.48 3.58E+001 14. 17 5.24E+OOO 15 5830- 5854 5841.92 1460.48 1. 86 3.52E+002 42.02 2.17E+001 16 7048- 7065 7057.36 1764.34 1. 29 5.45E+001 16.63 4 .50E+OOO M = First peak in a multiplet region m ~ Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 000 sigma [404]

Interference Corrected Activity Report 8/16/2018 2:37:40 PM Page 3

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

Sample

Title:

B109l00AFSFC067GD 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 5.72907E+005 8.45194E+004 Co-60 1. 000 1173.23* 99.85 5.40050E+003 2.97699E+003 1332.49* 99.98 5.83580E+003 2. 35970E+003 t V\-.,\-1.. Cs-137 1 .000 661.66* 85.10 9.35386E+003 3.20198E+003 &...1..Z, Eu-155 0.314 86.55* 30.70 -2.85779E+003 7. 32869E+003 - A i~'(.fi;> 105.31 21.10 Tl-208 1.000 583.19* 85.00 6.02658E+003 3.32876E+003 Pb-212 1.000 238.63* 43.60 1.10286E+004 9.32532E+003 Bi-214 1.000 609.32* 45.49 4 .78224E+004 1 .03982E+004 1120.29* 14.92 3.68423E+004 1 .98444E+004 1764.49* 15.30 7.04237E+004 2.22203E+004 Pb-214 1. 000 295.22* 18.42 1 .76277E+004 1 .30729E+004 351.93* 35.60 3.3754BE+004 9.97026E+003

         * ~ 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

[405]

Interference Corrected Activity Report 8/16/2018 2: 37: 40 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 (p Ci/M"2 ) Uncertainty K-40 1 .000 5.729070E+OOS 8.451937E+004 Co-60 1 .000 5.667834E+003 l.849231E+003 Cs-137 1 .000 9.353857E+003 3. 2019 77E+003 ....a. ~<;:::) Eu-155 0.314 -2.857792E+003 1. 32B691E+oo3 - A~ ...-z.:w l" r"'-7 Tl-208 1.000 6.026578E+003 3.328764E+003 I.\..~* Pb-212 1.000 1.102865E+OD4 9.325322E+003 Bi-214 1. 000 4 .911771E+004 8.508401E+003 Pb-214 1.000 2.782400E+004 7.9277SOE+003

      ? = 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

[406]

Interference Corrected Activity Report 8/16/2018 2: 3 7 : 40 PM Page 5

  **********    U N I D E N T I F I E D      PE A K S     **********

Peak Locate Performed on: 8/16/2018 2: 37: 39 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 22.86 -2.0115E-002 -568.53 2 74.97 5.8064E-001 38. 17 4 169.06 4.3784E-002 228.83 11 910.67 6.3034E-002 55.42 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [407]

Nuclide MDA Report 8/16/2018 2:37:40 PM Page 6

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

Detector Name: 5452A Sample Geometry: WWTF SUMP 1 Sample

Title:

B109100AFSFC067GD 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 5.489E+004     5.49E+004    5.729E+005  2.525E+004
 +       Co-60      1173.23*    99.85  4. 236E+003    2.48E+003    5.400E+003  1.914E+003 1332.49*    99.98  2.484E+003                  5.836E+003  1.021E+003 Nb-94        702.65    99.81  5.117E+003     5.12E+003    3.321E+003  2.409E+003 871. 09   99.89  6.039E+003                  2.488E+003  2.849E+003 Ag- 108m     433.90    90.50  5.745E+003     5.75E+003    1.611E+003  2.752E+003 614. 3 0  89.80  9.295E+003                  2.570E+002  4.495E+003 722.90    90.80  6.164E+003                  3.809E+003  2.915E+003 Cs-134       604.72    97.62  8.941E+003     6.23E+003   -3.683E+003  4.332E+003 795.86    85.46  6.235E+003                  9.776E+002  2.929E+003
 +       Cs-137       661.66*   85.10  3.758E+003     3.76E+003    9. 354E+003 1 .710E+003 Eu-152       121 .78   28.67  2.141E+004     1.93E+004    9.835E+003  1 .052E+004 344.28    26.60  1 .933E+004                -1.976E+004  9.313E+003 1408. 01    21.07  2.668E+004                  9.278E+003  1 .225E+004 Eu-154       123.07    40.40  l .522E+004    1.52E+004    1 .539E+004 7.477E+003 723. 3 0  20.06  2.829E+004                  4.077E+004  1.339E+004 1274.43     34.80  1. 609E+004                -1 .243E+004 7.429E+003
 +       Eu-155        86.55*   30.70  1. 253E+004    1.25E+004   -2.858E+003  6.091E+003 105.31    21.10  3.086E+004                 -8.573E+003  1.518E+004
 +       Tl-208       583.19*   85.00  4.899E+003     4.90E+003    6.027E+003  2.293E+003 Bi-212       727.33     6.67  8.146E+004     8.15E+004   -2.730E+004  3.845E+004
 +       Pb-212       238.63*   43.60  1. 489E+004    1. 49E+O 04  1.103E+004  7.28DE+003
 +       Bi-214       609.32*   45.49  1. 00 OE+004   1. OOE+004   4.782E+004  4 .703E+003 1120.29*    14 .92 2.816E+004                  3.684E+004  1.275E+004 1764 .49*   15.30  1.978E+004                  7.042E+004  8.139E+003
 +       Pb-214       295. 22*  18.42  2.032E+004     1 .14E+004   1.763E+004  9.704E+003 351.93*   35.60  1.141E+004                  3.375E+004  5.441E+003 Ra-226       186. 21    3.64  1.621E+005     1 .62E+005   8.487E+004  7.931E+004 Ac-228       338.32    11. 27 4 .562E+004    2.83E+004    1. OOOE+004 2.200E+004 911. 2 0  25.80  2.825E+004                  4 .444E+004 1 .345E+004 968.97    15.80  4 .226E+004                 1.904E+004  1 .998E+004 Am-241        59.54    35.90  1 .630E+004    1 .63E+004   1.708E+003  7.994E+003
       + . 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

[408]

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

Filename: 5452A Report Generated On 8/16/2018 3:17:00 PM Sample Title B109100AFSFC068GD Sample Description WWTF SUMP #2 Sample Identification 068 Sample Type GAMMA DIRECT Sample Geometry WWTF SUMP 2 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 4.270E+OOO M"2 Sample Taken On 8/16/2018 3:06:00 PM Acquisition Started 8/16/2018 3:06:59 PM Live Time 600.0 seconds Real Time 600.6 seconds Dead Time 0 . 09 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration used Done On 8/16/2018 Efficiency ID WWTF SUMP 2 DATA VALIDATED DATE 9,_?i::f= [409]

                                                         ?    TIME ic,ht~:£~    'f~

Peak Analysis Report 8/16/2018 3:17: 00 PM Page 2

• • • • • P E A K ANALYS I s R E P O R T *****

Detector Name: 5452A Sample

Title:

B109lOOAFSFC068GD Peak Analysis Performed on: 8/16/2018 3:17: 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 1 115- 126 118.64 29.66 0.33 -9.89E+OOO 59.32 3.54E+002 2 787- 796 791. 53 197.88 0.60 -7.54E-001 39.74 1.72E+002 3 944 - 972 953.41 238.35 0.59 1.93E+002 9 1. 46 4.10E+002 4 1172 - 1190 1179.42 294.85 1. 31 1.17E+002 49.03 1.43E+002 5 1343- 1357 1350.19 337.55 1. 08 3.77E+001 37.73 1.09E+002 6 1394 - 1413 1405.48 351.37 1. 27 1.79E+002 49.21 1.22E+002 7 2032 - 2047 2038.89 509.72 1. 07 6.90E+001 30.80 5.60E+001 8 2322- 2337 2329.46 582.36 0.82 5.57E+001 32.12 6.73E+001 9 2424- 2444 2433.58 608. 40 1. 02 2.19E+002 38.36 4. 14E+001 10 2632 - 2650 2641.76 66 0 . 44 0.38 1.01E+002 33.29 5.22E+001 11 3631- 3646 3638.95 909.74 1. 03 4 .87E+001 22.21 2.43E+001 12 3726- 3739 3732.12 933.03 0.38 2.25E+001 19.00 2.45E+001 13 4118 - 4131 4124.35 1031.09 0.41 6.08E+OOO 15.33 1 .89E+001 14 4468 - 4482 4475.28 1118.82 1. 25 6.22E+001 20.47 1 .48E+001 15 4937- 4950 4943.80 1235.95 0.43 2.09E+001 19.28 2.61E+001 16 5824 - 5849 5836.41 1459. 10 2.01 4.96E+002 48.81 2.44E+001 17 7043- 7059 7050.97 1762.74 1. 10 5.78E+001 16.86 4.25E+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 [410]

Interference Corrected Activity Report 8/16/2018 3:17: 00 PM Page 3

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

Sample

Title:

B109100AFSFC068GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * * * * * * * * "' * ., * * *

• I I
• IDENTIFIED NUCLIDES * * *
• I * * * * * * * * *
• lo * * ** ~

Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.995 1460.82* 10.66 7.36553E+005 9.67062E+004 Cs-137 0.998 661.66* 85 .10 1.14622E+004 4.02882E+003 Tl- 208 0.999 583.19* 85.00 5.85331E+003 3.44664E+003 Pb-212 1. 000 238.63* 43.60 2.16852E+004 1 .08550E+004 Bi-214 0.998 609.32* 45.49 4.41359E+004 9.38585E+003 1120 .29* 14.92 S.57812E+004 1.88953E+004 1764.49* 15. 30 6.84117E+004 2.07155E+004 Pb-214 1. 000 295.22* 18.42 3.59516E+004 1.61014E+004 351.93* 35.60 3.19807E+004 1.01670E+004 Ac-228 0 .562 338.32* 11. 27 2.07113E+004 2.09848E+004 911.20* 25.80 2.22403E+004 1.03368E+004 968.97 15.80

          *=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

[411]

Interference Corrected Activity Report 8/16/2018 3:17: 00 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.995 7.365530E+005 9.670620E+004 Cs-137 0.998 1 .146222E+004 4.028818E+003 Tl-208 0.999 5.853308E+003 3.446638E+003 Pb-212 1. 000 2 .16 8517E+004 1. 085495E+00 4 Bi-214 0.998 4.954685E+004 7.789089E+003 Pb-214 1 .000 3.311260E+004 8.596639E+003 Ac-228 0.562 2 . 1 94172E+004 9.272852E+003

      ? = 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

[412]

Interference Corrected Activity Report 8/16/2018 3:17:00 PM Page s

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

Peak Locate Performed on: 8/16/2018 3:17: 00 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 29.66 -1 .6483E-002 -599.78 2 197 .88 -1 .2573E-003 -5267.6 7 509.72 1 .lSOOE-001 44 .64 12 933.03 3.7500E-002 84.45 Sum 13 1031.09 1.0133E-002 252.20 15 1235.95 3.488SE-002 92.09 Sum M ; First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [413]

Nuclide MDA Report 8/16/2018 3: 17 : 00 PM Page 6

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

Detector Name: 5452A Sample Geometry: WWTF SUMP 2 Sample

Title:

B109100AFSFC068GD 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  5.290E+004      5.29E+004   7.366E+005    2.444E+004 Co-60      1173.23     99.85  6.693E+D03      5.68E+003   3.871E+003    3.160E+003 1332.49     99.98  5.682E+003                  2.966E+D03    2.64DE+003 Nb-94       702.65     99.81  5.405E+003      5.31E+003  -2.184E+003    2.566E+003 871.09     99.89  5.315E+OD3                 -1.680E+003    2.502E+003 Ag-108m     433.90     90.50  S.762E+003      S.76E+003  -3.861E+003    2.771E+003 614. 3 0   89.80  8.459E+003                 -1.698E+003    4.090E+003 722.90     90.80  6.460E+OD3                  5.494E+003    3.078E+D03 Cs-134      604.72     97.62  8.340E+003      5.56E+003  -5.172E+002    4. 043E+003 795.86     85.46  5.556E+003                  5.554E+002    2.606E+003
 +      Cs-137      661.66*    85.10  5.276E+003      5.28E+003   l.146E+004    2.484E+003 Eu-152      121. 78    28.67  2.094E+D04      1 .99E+004  1. 731E+002   1. 030E+004 344.28     26.60  1. 991E+O 04               -1. 299E+003   9.638E+003 1408.01     21.07  2.613E+004                  1. 062E+004   l. 207E+004 Eu-154      123.07     40 .40 1. 4 82E+O 04   1 .48E+004 -3.858E+003    7.288E+003 723.30     20.06  2.94SE+004                  2.768E+004    1.404E+004 1274.43     34.80  1. 537E+004                -5.732E+003    7.119E+003 Eu-155       86.55     30.70  2.132E+004      2.13E+004  -2.440E+003    1.051E+004 105. 31    21.10  3.087E+004                  2.448E+004    1.521E+004
 +      Tl-208      583.19*    85.00  S.198E+003      5.20E+003   5.853E+003    2.457E+OD3 Bi-212      727.33      6.67  8.858E+004      8.86E+004   4 .064E+004   4 .221E+004
 +      Pb-212      238.63*    43.60  1.640E+004      1 .64E+004  2.169E+004    8.0SOE+003
 +      Bi-214      609.32*    45.49  8.657E+003      8.66E+003   4.414E+004    4.055E+003 1120.29*    14. 92 2.168E+004                  5.578E+004    9.624E+003 1764.49*    15.30  1. 745E+004                 6.841E+004    7.120E+003
 +      Pb-214      295.22*    18.42  2.302E+004      1.26E+004   3.595E+004    l.110E+004 351. 93

• 35.60 1 .261E+004 3.198E+004 6.063E+003 Ra-226 186 .21 3.64 1 .598E+005 1.6DE+005 -1.983E+004 7.836E+004

 +      Ac-228      338.32*    11. 27 3.370E+004      1.42E+004   2.071E+004    1. 611E+004 911.20*    25.80  1.422E+004                  2.224E+004    6.494E+003 968.97     15.80  4.216E+004                  4 .484E+004   2.003E+004 Am-241       59.54     35.90  1. 682E+004     1.68E+004   1.S79E+003    8.269E+003
       +=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

[414]

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

Filename: 5452A Report Generated On 8/17/2018 2:08:52 PM Sample Title B109100AFSFC069GD Sample Description WWTF FLOOR Sample Identification 069 Sample Type GAMMA DIRECT Sample Geometry #3 SUMP 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 1. 041E+O 01 M"2 Sample Taken On 8/17/2018 1:58:00 PM Acquisition Started 8/17/2018 1:58:49 PM Live Time 600.0 seconds Real Time 601.1 seconds Dead Time 0 . 19 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 8/16/2018 Efficiency ID WWTF SUMP 3 DATA VAUDATED DATE tz-Z=f.t Tl~t{~ f!,DtiC* ~~ [415]

Peak Analysis Report 8/17/2018 2: 08: 52 PM Page 2

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

Detector Name: 5452A Sample

Title:

B109100AFSFC069GD Peak Analysis Performed on: 8/17/2018 2:08:51 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- 305 299.79 74.95 0 .70 2.26E+002 100.51 6.80E+002 2 740- 749 744. 28 186.07 1. 21 3.49E+001 35.16 1.21E+002 3 949- 961 954. 81 238.70 0 .76 8.08E+001 42.77 1.41E+002 4 1174- 1189 1180.40 295.10 1. 19 8.68E+D01 36.60 8.22E+001 5 1347- 1358 1353.12 338.28 0.70 1.85E+001 26 . 94 6.45E+001 6 1402- 1416 1407.66 351.92 0.91 8.73E+001 36.60 8.57E+001 7 2036- 2051 2043.29 510.82 0.95 6.08E+D01 26.72 3.93E+001 B 2324- 2339 2330.98 582.75 1. 47 5.85E+D01 24 . 51 3.05E+001 9 2429- 2446 2436.31 609.08 1. 81 1. 25E+002 3 1. 27 3.70E+001 10 2640- 2651 2645.78 661.45 0.62 2.81E+001 17 .94 2.09E+001 11 3636- 3652 3643.98 910.99 0.47 4. 46E+001 17 .56 1.04E+001 12 5831- 5856 5843.98 1461. 00 1. 54 3.26E+002 40.29 1.89E+001 M = First peak in a mul tiplet region m = Other peak in a multipl e t region F = Fitted singlet Errors quoted at 2. 000 sigma [416]

Interference Corrected Activity Report 8/17/2018 2:08:52 PM Page 3

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

sample

Title:

B109100AFSFC069GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB I ****._*** t I ********* IDENTIFIED NUCLIDES * * * * * * * * * * * * * * *

• I * *
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1 .000 1460.82* 10.66 5.9007DE+005 8.91016E+004 Cs-137 1.000 661.66* 85 .10 3.89100E+003 2.52629E+003 Tl-208 1.000 583.19* 85.00 7.48530E+003 3.26251E+003 Pb-212 1.000 238.63* 43.60 1. 10591E+004 6.12175E+003 Bi-214 0.458 609.32* 45.49 3.07274E+004 B.52824E+003 1120.29 14. 92 1764.49 15.30 Pb-214 1.000 295.22* 18.42 3.2423DE+004 1.46157E+004 351.93* 35.60 1.89695E+004 8.51333E+003 Ra-226 1.000 186.21* 3.64 4.92122E+004 5.01721E+004 Ac-228 0.564 338.32* 11. 27 1.23389E+004 1.81218E+004 911.20* 25.80 2.47965E+004 1.00026E+004 968.97 15.80

       *=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

[417]

Interference Corrected Activity Report 8/17/2018 2:08:52 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 5.900704E+005 8.910157E+004 Cs-137 1.000 3.891001E+003 2.526285E+003 Tl-208 1.000 7.485303E+003 3.262514E+003 Pb-212 1.000 1. 1 05910E+004 6.121749E+003 Bi-214 0.458 3.072741E+004 8.528241E+003 Pb-214 1.000 2.237765E+004 7.356370E+003 Ra-226 1. 000 4. 921221E+004 5.017208E+004 Ac-228 0 .564 2.188736E+004 8.757154E+003

      ? =  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

[418]

Interference Corrected Activity Report 8/17/2018 2:08:52 PM Page 5

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

Peak Locate Performed on: 8/17/2018 2:08:51 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 74.95 3.7681E-001 44.46 7 510.82 1.0125E-001 43.99 M: First peak in a multiplet region m ~ Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2. 000 sigma [419]

Nuclide MDA Report 8/17/2018 2:08:52 PM Page 6

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

Detector Name: 5452A Sample Geometry: #3 SUMP Sample

Title:

B109100AFSFC069GD 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  5.802E+004    5.80E+004 5.901E+005   2.656E+004 Co-60      1173.23    99.85  6.4SOE+003    5.90E+003 -1.897E+003  2.998E+003 1332.49    99.98  5.900E+003               4.862E+003  2.704E+003 Nb-94       702.65    99.81  5.029E+003    5.01E+003 -1.158E+003  2.349E+003 871. 0 9  99.89  5.013E+003               1.470E+003  2.318E+003 Ag-lOBm     433.90    90.50  6.016E+003    5.82E+003 -1.191E+003  2.874E+003 614. 3 0  89.80  9.095E+003              -5.755E+002  4.378E+003 722.90    90.80  5.815E+003               2.655E+003  2.722E+003 Cs-134      604.72    97.62  8.424E+003    6.43E+003 -3.101E+003  4.058E+003 795.86    85.46  6.425E+003               3.875E+003  3.004E+003
 +      Cs-137      661.66*   85.10  3.668E+003    3.67E+003 3.891E+003   1 .647E+003 Eu-152      121 .78   28.67  2.121E+004    2.12E+004 3.868E+003   1 .039E+004 344.28    26.60  2.135E+004              -4 .895E+003 1 .029E+004 1408.01    21.07  2.361E+004               9.157E+003  l .060E+004 Eu-154      123.07    40.40  l.501E+004    1.50E+004 -2.105E+003  7.357E+003 723.30    20.06  2.633E+004               l.585E+004  1 .233E+004 1274. 43   34.80  1.685E+004              -1.395E+003  7.737E+003 Eu-155       86.55    30.70  2.263E+004    2.26E+004 1 .054E+004  1.112E+004 105. 31   21.10  2.975E+004              -9.850E+003  1.459E+004
 +      Tl-208      583.19*   85.00  4.377E+003    4.38E+003 7.485E+OD3   2.015E+003 Bi-212      727.33     6.67  7.472E+004    7.47E+004 -1 .659E+OD4 3.483E+004
 +      Pb-212      238.63*   43.60  9.110E+003    9.11E+003 l .106E+004  4.370E+003
 +      Bi-214      609.32*   45.49  9.505E+003    9.51E+003 3.073E+004   4.420E+003 1120.29    14.92  4 .980E+004              5.128E+004  2.342E+004 1764.49    15.30  4 .977E+004              5.517E+004  2.294E+004
 +      Pb-214      295.22*   18.42  2.035E+004    1.18E+004 3.242E+D04   9.672E+003 351.93*   35.60  l .184E+004              1.897E+004  5.625E+003
 +      Ra-226      186.21*    3.64  8.056E+004    8.06E+OD4 4.921E+004   3.837E+004
 +      Ac-228      338.32*   11. 27 2.989E+004    1.19E+OD4 1.234E+D04   l.404E+004 911.20*   25.80  1 .194E+004              2.480E+004  S.218E+003 968.97    15.80  4.400E+004               5.712E+004  2.072E+004 Am-241       59.54    35.90  1.854E+004    1.85E+004 -1.441E+D04  9.100E+003
       + - 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

[420]

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

Filename: 6279 Report Generated On 8/18/2018 9:32:04 AM Sample Title Bl09JOOAFSFC070GD Sample Description WWTF FLOOR Sample Identification 070 Sample Type GAMMA DIRECT Sample Geometry WWTF CLARIFIER 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 1.533E+001 M"2 Sample Taken On 8/18/2018 9:22:00 AM Acquisition Started 8/18/2018 9:22:02 AM Live Time 600.0 seconds Real Time 601.0 seconds Dead Time 0.16 % Energy Calibration Used Done On 6/9/201-8 Efficiency Calibration Used Done On 8/17/2018 Efficiency ID WWTF Clarifier OATA-VAUDATED DATE 1-2-f ~ [421] ~~

Peak Analysis Report 8/18/2018 9:32:04 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:

B109100AFSFC070GD Peak Analysis Performed on: 8/18/2018 9:32:04 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- 305 300.29 75.20 1. 27 3.85E+002 89.04 4 .73E+002 2 946- 962 953.42 238.47 0.55 6.89E+001 41. 50 1 .15E+002 3 1400- 1416 1406.85 351. 82 0.88 8.78E+001 30.52 4.62E+001 4 2326- 2339 2332.50 583.22 0.39 3.57E+001 19.52 2.13E+001 5 2427- 2447 2435.93 609.08 1.30 1.10E+002 25.81 1.61E+001 6 3637- 3650 3643.34 91 0 .92 1.40 3.03E+001 14.72 8.67E+OOO 7 5834- 5855 5844. l l 1461.08 2. 01 1 .81E+002 27.63 2.60E+OOO 8 7052 - 7067 7059.66 1764.95 0.37 3.0lE+OOl 11.96 1.91E+OOO M := First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [422]

Interference Corrected Activity Report 8/18/2018 9:32:04 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:

B109100AFSFC070GD 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 5.6680SE+OOS 9.93716E+004 Tl-208 1.000 583.19* 85.00 6.92938E+003 3.87905E+003 Pb-212 1.000 238.63* 43.60 1. 23691E+004 7.71844E+003 Bi-214 0.720 609.32* 45.49 4.12814E+004 1. 08869E+004 1120.29 14.92 1764.49* 15.30 7.64679E+004 3.10020E+004 Pb-214 0.427 295.22 18.42 351.93* 35.60 2.65685E+004 1.00560E+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

[423]

Interference Corrected Activity Report 8/18/2018 9:32:04 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 5.668051E+005 9.937164E+00 4 Tl-208 1.000 6.929379E+003 3.879046E+003 Pb-212 1.000 1.23690SE+004 7.718442E+003 Bi-214 0.720 4 .514414E+004 1. 027194E+004 Pb-214 0.427 2.656853E+004 l. 005599E+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: 8/18/2018 9:32: 04 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.20 6.4207E-001 23.11 6 910 .92 5.0556E-002 48. 52 Tol. Ac-228 M = First peak in a multiplet region rn = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [424]

Nuclide MDA Report 8/18/2018 9:32:04 AM Page 5

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

Detector Name: 6279 Sample Geometry: WWTF CLARIFIER Sample

Title:

B109100AFSFC070GD 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  4. 001E+004   4. 00E+004  5.668E+005  1 .578E+004 Co-60       1173.23      99.85  8.435E+003    8.17E+003   5.301E+003  3.835E+003 1332 . 49    99.98  8.167E+003               -1.283E+003  3.665E+003 Nb-94         702.65     99. 81 7.424E+003    6.91E+003   9.580E+002  3.453E+003 871.09     99. 89 6.913E+003               -4.358E+003  3.151E+003 Ag-108m       433.90     90.50  7.341E+003    7.34E+003  -3.SOSE+003  3.478E+003 614. 3 0   89.80  1. 114E+004              -4.330E+003  5.309E+003 722.90     90.80  8.405E+003                9.087E+001  3.911E+003 Cs-134        604.72     97.62  1. 045E+004   8.93E+003  -6.890E+003  4.989E+003 795.86     85.46  8.927E+003               -1.112E+004  4.130E+003 Cs-137        661.66     85.10  9.565E+003    9.57E+003   3.701E+003  4.492E+003 Eu - 152      121.78     28.67  2.296E+004    2.18E+004  -4.591E+003  1.122E+004 344.28     26.60  2.176E+004               -4.803E+004  1. 034E+004 1408. 01     21. 07 4.123E+004                2.842E+004  1.854E+004 Eu-154        123.07     40.40  1.614E+004    1 .61E+004  1.155E+004  7.889E+003 723.30     20.06  3.835E+004               -1.757E+003  1.786E+004 1274.43      34.80  2.461E+004                7.720E+003  1.114E+004 Eu-155         86.55     30.70  2.452E+004    2.45E+004   4.080E+004  1.204E+004 105. 31    21. 10 3.240E+004                4.474E+003  1.587E+004
 +      Tl-208        583.19*    85. 00 5.453E+003    5.45E+003   6.929E+003  2.464E+003 Bi-212        727.33      6.67  1.105E+005    1.10E+005   7.518E+003  5.126E+004
 +      Pb-212        238.63*    43.60  1.173E+004    1.17E+004   1.237E+004  5.620E+003
 +      Bi-214        609.32*    45.49  1.031E+004    1.03E+004   4.128E+004  4.645E+003 1120. 29     14. 92 8.007E+004                9.110E+004  3.756E+004 1764.49*     15.30  2.678E+004                7.647E+004  9.952E+003
 +      Pb-214        295.22     18.42  3.628E+004    1.28E+004  -5.318E+004  1. 746E+004 351. 93

• 35.60 1 .281E+004 2.657E+004 5.996E+003 Ra-226 186.21 3.64 1 .804E+OOS 1.80E+OOS -3.940E+004 8.778E+004 Ac-228 338.32 11. 27 5.411E+004 3.79E+004 -5.402E+003 2.581E+004 911 .20 25.80 3.792E+004 3.807E+004 1. 774E+004 968.97 15.80 5.359E+004 2.865E+004 2.470E+004 Am-241 59.54 35.90 1. 697E+004 1 .70E+004 7.825E+003 8.294E+003

       + - 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

[425]

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

Filename: 6279 Report Generated on 8/18/2018 9 : 51 :08 AM Sample Title B109100AFSFC071GD Sample Description WWTF FLOOR Sample Identification 071 Sample Type GAMMA DIRECT Sample Geometry WWTF CLARIFIER 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 1.533E+001 M"2 Sample Taken On 8/18/2018 9: 41 : 00 AM Acquisition Started 8/18/2018 9:41:05 AM Live Time 600.0 seconds Real Time 601. 1 seconds Dead Time 0 ~17 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration used Done On 8/17/2018 Efficiency ID WWTF Clarifier DATA VALIDATED DATE£-2-t~ [426] (2.~4~

Peak Analysis Report 8/18/2018 9:51:08 AM Page 2

• • • • • PE AK ANALYS I S R E P O R T *****

Detector Name: 6279 Sample

Title:

B109100AFSFC071GD Peak Analysis Performed on: 8/18/2018 9:51: 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 1 283- 305 300.33 75.21 0.78 2.59E+002 110.87 7.26E+002 2 331- 344 339.76 85.06 1.15 6.82E+001 63.77 3.45E+002 3 546- 556 551. 25 137.94 0.25 5.33E+OOO 41.26 1.76E+002 4 699- 708 703.74 176.06 0.29 1 .33E+001 29.61 9.07E+001 5 949- 960 954.73 238.80 0.37 4.53E+001 33.57 9.27E+001 6 1399- 1415 1407.66 352.02 1. 42 5.87E+001 30. 84 5.73E+001 7 2327- 2339 2332.64 583.26 0.92 2.38E+001 18 .99 2.32E+001 8 2428- 2445 2436.83 609.30 1. 32 l.OOE+002 2 4 . 11 l.37E+001 9 3870- 3883 3876.13 969 .11 0.53 l.36E+001 13.53 l.14E+001 10 4474- 4489 4481 .27 1120.39 0.37 3.27E+001 15.36 8.34E+OOO 11 4948- 4961 4954.83 1238.77 0.44 1.15E+001 12.74 1.05E+001 12 5833- 5855 5844.75 1461. 24 1. 81 1.93E+002 28.57 2.84E+OOO M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [427]

Interference Corrected Activity Report 8/18/2018 9:5 1: 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:

B109100AFSFC071GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * * * * * * * ., ,, * * "' ' *'III* 11     IDENTIFIED NUCLIDES Nuclide                 Id                 Energy     Yield         Activity    Activity Name            Confidence                 (keV)        (%)        (pCi/MA2 )  Uncertainty
                                                                                                      ..,,c; ~'<.<0" K-40                 1 .000           1460.82*        10.66      6.03625E+005  1.03533E+005      , "v \(v Eu- 155              0 .352                86.55*     30.70      1.10907E+004  1.06044E+004 ~ e. '1'-

105.31 21.10 Tl- 208 1.000 583 . 19* 85.00 4.61700E+003 3.72651E+003 Pb-212 1.000 238.63* 43.60 8.14551E+003 6.17946E+003 Bi-214 0.759 609.32* 45.49 3.76839E+004 1.01 267E+004 1120.29* 14. 92 5.97077E+004 2.84891E+004 1764.49 15.30 Pb-214 0.427 295.22 18.42 351.93* 35.60 1.77670E+004 9. 71016E+003

          * ~ 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

[428]

Interference Corrected Activity Report 8/18/2018 9:5 1: 08 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/M"'2 ) Uncertainty K-40 1.000 6.036251E+005 1 .035333E+00 5 ~~~~~ Eu-155 0.352 1. 109069E+004 1 .060442E+00 4~~v Tl-208 1.000 4.617001E+003 3.726515E+003 Pb-212 1.000 8.145509E+003 6.179457E+003 Bi-214 0 .759 4.015444E+004 9.541841E+003 Pb-214 0 .427 1.776705E+004 9.710163E+003

      ? =    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

[429]

Interference Corrected Activity Report 8/18/2018 9: 51 :08 AM Page 5

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

Peak Locate Performed on: 8/18/2018 9:51:08 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 75.21 4.3132E-001 42.84 3 137.94 8.8881E-003 773.78 4 176.06 2.2103E-002 223.23 Sum 9 969. 11 2.2600E-002 99.78 Sum 11 1238.77 1. 9167E-002 110.81 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 [430]

Nucl ide MDA Report 8/18/2018 9:51:08 AM Page 6

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

Detector Name: 6279 Sample Geometry: WWTF CLARIFIER Sample

Title:

B109100AFSFC071GD 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  4 .243E+004   4.24E+004   6.036E+005  1 .699E+004 Co-60     1173.23    99.85  8.979E+003    8.02E+003   2.156E+002  4.107E+003 1332.49    99.98  8.024E+003                5.376E+003  3.594E+003 Nb-94       702.65   99.81  6.947E+003    6.95E+003   2.498E+003  3.214E+003 871.09   99.89  7.499E+003                9.707E+003  3.444E+003 Ag-108m     433.90   90.50  6.642E+003    6.64E+003   1.762E+OD1  3.128E+003 614.30   89.80  l .143E+004              -1.149E+OD3  5.457E+003 722.90   90.80  7.301E+003               -2.440E+002  3.359E+003 Cs-134      604.72   97.62  1.074E+004    8.69E+003   2.129E+003  5.135E+003 795.86   85.46  8.685E+003               -9.581E+D03  4.010E+003 Cs-137      661.66   85.10  8.813E+003    8.81E+OD3  -5.190E+003  4.116E+003 Eu-152      121 .78  28.67  2.296E+004    2.30E+004   7.824E+003  1.122E+004 344.28   26.60  2.411E+004               -2.402E+004  1.152E+004 1408.01    21.07  3.526E+004               -7.346E+003  1. 555E+004 Eu-154      123.07   40 .40 1.627E+004    1 .63E+004  l .768E+003 7.956E+003 723.30   20.06  3.238E+004               -l .095E+004 1 . 487E+004 1274.43    34.80  2.634E+004               -1 .846E+D03 l. 201E+004
 +       Eu-155       86.55*  30.70  1 .692E+004   1.69E+004   1.109E+004  8.238E+003 105.31   21.10  3.093E+004               -7.323E+003  l.514E+004
 +       Tl-208      583.19*  85.00  5.726E+003    5.73E+003   4.617E+D03  2.600E+003 Bi-212      727.33    6.67  9.568E+004    9.57E+004   1.691E+D04  4.386E+004
 +       Pb-212      238.63*  43.60  9.585E+003    9.59E+003   8.146E+OD3  4.549E+003
 +       Bi-214      609.32*  45.49  9.310E+003    9.31E+OD3   3.768E+D04  4.147E+003 1120.29*   14.92  3.582E+004                5.971E+004  1.543E+004 1764.49    15.30  6.232E+004                1.334E+004  2.772E+004
 +       Pb-214      295.22   18.42  3.659E+004    1.42E+004   1.295E+004  l.762E+004 351.93*  35.60  1.41SE+004                1.777E+004  6.667E+003 Ra-226      186.21    3.64  1.741E+005    1.74E+005   6.392E+004  8.465E+004 Ac-228      338.32   11.27  5.842E+004    3.56E+004   2.530E+004  2.796E+004 911. 20  25.80  3.560E+004                1. 742E+004 1 .657E+004 968.97   15.80  6.273E+004                5.796E+004  2.927E+004 Am-241        59.54   35.90  1 .735E+004   1.73E+004   6.982E+003  8.483E+003
       + = 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

[431]

• • • • • GAMM A SPE CTRUM A N A L Y S I S *****

Filename: 6279 Report Generated On 8/17/2018 3: 28: 04 PM Sample Title B109100AFSFC072GD Sample Description WWTF FLOK #72 Sample Identification 072 Sample Type Sample Geometry FLOK #72 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 5.490E+OOO MA2 Sample Taken On 8/17/2018 3:17:00 PM Acquisition Started 8/17/2018 3:18:02 PM Live Time 600.0 seconds Real Time 600.7 seconds Dead Time 0 . 12 % Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 8/17/2018 Efficiency ID WWTF FLOC TANK DATA VALIDATED DATE 7-e -V-- [432] g~f~~

Peak Analysis Report 8/17/2018 3:28: 04 PM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSFC072GD Peak Analysis Performed on: 8/17/2018 3:28:03 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 287- 308 300.83 75.33 0. 73 2.18E+002 90.19 4.84E+002 2 328- 344 339.14 84.91 0 .30 3.33E+001 66.93 3.43E+002 3 576- 585 580.55 145 .26 0. 66 8.66E+OOO 28.05 8.33E+001 4 1401- 1415 1407.06 351.88 0. 26 3.89E+001 19.99 2 .llE+OOl 5 2428- 2440 2434.16 608.64 0 .78 3.52E+001 17.44 1 .48E+001 6 2640- 2651 2645.88 66 1. 56 0. 30 1. 46E+001 10.90 5.35E+OOO 7 5833- 5854 5843.23 146 0. 86 1. 40 1. 25E+002 23.22 2.59E+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 [433]

Interference Corrected Activity Report 8/17/2018 3: 28: 04 PM Page 3

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

Sample

Title:

B109100AFSFC072GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1. 000 1460.82* 10 .66 1.40767E+006 2.87851E+OOS Cs-137 1. 000 661.66* 85.10 1.23214E+004 9.28561E+003 Eu-155 0.353 86. 55* 3 0.70 2.14163E+004 4.32693E+004 105 .31 21 .10 Bi- 214 0.464 609.32* 45.49 5.21462E+004 2.66011E+004 1120.29 14.92 1764.49 15.30 Pb-214 0 .428 295.22 18.42 351.93* 35.60 4.80842E+004 2.57207E+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

[434]

Interference Corrected Activity Report 8/17/2018 3:28: 04 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1 . 000 1.40767SE+006 2.878515E+005 Cs-137 1 . 000 1.232140E+004 9.285615E+003 Eu-155 0 .353 2. 14 1633E+004 4.326933E+00 4 Bi-214 0 .464 5.214619E+004 2.660110E+00 4 Pb-214 0 .428 4.808417E+004 2.572074E+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: 8/17/2018 3:28:03 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 75.33 3.6344E-001 41. 36 3 145.26 1.4429E-002 323.98 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [435]

Nuclide MDA Report 8/17/2018 3:28:04 PM Page 5

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

Detector Name: 6279 Sample Geometry: FLOK #72 Sample

Title:

B109100AFSFC072GD 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   l.433E+005    1.43E+005 1 .408E+006  5.648E+004 Co-60      1173.23   99.85   2.518E+004    2.19E+004 -1 .008E+004 1.117E+004 1332.49   99.98   2.187E+004               6.066E+003  9.416E+003 Nb-94       702.65   99.81   2.346E+004    2.24E+004 8.812E+003   l.072E+004 871.09   99.89   2.245E+004               1 .616E+004 1.00SE+004 Ag-108m     433.90   90.50   2.303E+004    2.30E+004 -4.578E+003  1.073E+004 614.30   89.80   3.390E+004              -8.448E+003  1.593E+004 722.90   90.80   2.661E+004               5.547E+003  1.217E+004 Cs-134      604.72   97.62   3.118E+004    2.33E+004 2.519E+004   1.466E+004 795.86   85.46   2.331E+004              -2.591E+003  1.037E+004 Cs-137      661.66*  85.10   1 .301E+004   1.30E+004 1.232E+004   5.367E+003 Eu-152      121. 78  28.67   7.338E+004    7.34E+004 4.967E+004   3.567E+004 344.28   26.60   7.960E+004              -3.091E+004  3.760E+004 1408.01   21.07   8.775E+004              -6.948E+004  3.639E+004 Eu-154      123.07   40.40   5.090E+004    5.09E+004 -1.291E+004  2.473E+004 723.30   20.06   1 .233E+005              3.284E+004  5.650E+004 1274.43   34.80   8.460E+004              -5.901E+004  3.804E+004
 +      Eu-155       86.55*  30.70   7.151E+004    7.15E+004 2.142E+004   3.488E+004 105.31   21.10   1.071E+005               3.077E+003  5.225E+004 Tl-208      583.19   85.00   2.839E+004    2.84E+004 1.386E+004   1. 316E+004 Bi-212      727.33    6.67   3.679E+005    3.68E+005 -1.365E+005  1. 685E+005 Pb-212      238.63   43.60   4.724E+004    4.72E+004 9.623E+003   2.262E+004
 +      Bi-214      609.32*  45.49   3.518E+004    3.52E+004 5.215E+004   1. 559E+004 1120.29   14.92   1.567E+005               1. 295E+005 6.913E+004 1764.49   15.30   1.856E+005               6.209E+004  8.069E+004
 +      Pb-214      295.22   18.42   1. 070E+005   3.51E+004 -2.783E+004  S.072E+004 351.93*  35.60   3.508E+004               4.808E+004  1.587E+004 Ra-226      186.21    3.64   5.399E+005    5.40E+005 l.733E+005   2.601E+005 Ac-228      338.32   11. 27  1.955E+005    1.06E+005 2.947E+005   9.264E+004 911. 20  25.80   1.057E+005               2.741E+004  4.817E+004 968.97   15.80   1.822E+005               9.619E+004  8.314E+004 Am-241       59.54   35.90   7.061E+004    7.06E+004 4.573E+004   3.455E+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

[436]

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

Filename: 6279 Report Generated On 8/17/2018 3:43:23 PM Sample Title B109100AFSFC073GD Sample Description WWTF FLOK #73 Sample Identification 073 Sample Type Sample Geometry FLOK #73 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 9.230E+OOO M"2 Sample Taken On 8/17/2018 3:33:00 PM Acquisition Started 8/17/2018 3:33:21 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 8/17/2018 Efficiency ID WWTF FLOC TANK [437]

Peak Analysis Report 8/17/2018 3:43:23 PM Page 2

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

Detector Name: 6279 Sample

Title:

B109100AFSFC073GD Peak Analysis Performed on: 8/17/2018 3:43:23 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 1 281- 310 300.56 75.26 0 .69 3.87E+002 110.52 5.61E+002 2 333- 345 340.54 85.26 1. 08 9.05E+001 52.91 2.31E+002 3 2327- 2338 2332.08 583.12 0.38 1 . 90E+001 10.30 3.00E+OOO 4 2429- 2444 2436.46 609.21 1.10 3.98E+001 16.85 1 .02E+001 5 5834- 5853 5844. 11 1461.08 0.79 9.60E+001 19.60 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 [438]

Interference Corrected Activity Report 8/17/2018 3:43:23 PM Page 3

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

Sample

Title:

B109100AFSFC073GD 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 6.40991E+OOS 1. 42189E+005 Eu-155 0. 354 86.55* 30.70 3.46150E+004 2.13914E+004 105.31 21.10 Tl-208 1.000 583.19* 85.00 8.69627E+003 4.83007E+003 Bi-214 0.464 609.32* 45.49 3.5140SE+004 1. 54542E+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

[439]

Interference Corrected Activity Report 8/17/2018 3:43:23 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 6 .40 9912E+005 l.421891E+005 Eu-155 0.354 3 .46 1496E+004 2.139136E+004 Tl-208 1.000 8.696266E+003 4 .830074E+003 Bi-214 0.464 3.514047E+004 1.545416E+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: 8/17/2018 3: 43: 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 75.26 6.446 1E-001 28 . 58 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 [440]

Nuclide MDA Report 8/17/2018 3;43:23 PM Page 5

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

Detector Name: 6279 Sample Geometry: FLOK #73 Sample

Title:

B109100AFSFC073GD 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   1.807E+004    1 .81E+004 6.410E+005   O.OOOE+OOO Co-60     1173.23     99.85   1.648E+004    1.42E+004 -1 .693E+004  7.395E+003 1332.49     99.98   l.423E+004               -3.547E+002  6.213E+003 Nb-94       702.65    99.81   1.068E+004    1 .07E+OD4 -1 .096E+003 4.739E+003 871.09    99.89   1.359E+004               -7.712E+002  6.099E+003 Ag-108m     433.90    90.50   1.277E+004    1.28E+004 -2.898E+004   5.919E+003 614.30    89.80   2.028E+004                1.161E+004  9.530E+003 722.90    90.80   1.294E+004                7.135E+003  5.795E+003 Cs-134      604.72    97.62   1.633E+004    1.41E+004 -1.124E+D04   7.612E+003 795.86    85.46   l.414E+004               -6.272E+003  6.305E+003 Cs-137      661.66    85. 10  1. 748E+004   1.75E+004 8.078E+003    8.064E+003 Eu-152      121.78    28.67   4 .49SE+004   4.10E+004 -2.731E+003   2.187E+004 344.28    26.60   4 .102E+004              -7.964E+004  1. 920E+004 1408.01     21.07   4 .639E+004               1.974E+004  1. 875E+004 Eu-154      123.07    40. 40  3.177E+004    3.18E+004 -1.900E+004   l.545E+004 723. 3 0  20.06   5.963E+004                4 .651E+004 2.676E+004 1274.43     34.80   4.098E+004                2.588E+003  l. 796E+004
 +       Eu-155       86.55*   30.70   3.210E+004    3.21E+004 3.461E+004    1. 553E+D04 105.31    21.10   6.284E+D04               -2.456E+004  3.064E+004
 +       Tl-208      583.19*   85.00   5.373E+003    5.37E+OD3 8.696E+003    2.067E+003 Bi-212      727.33     6.67   l.861E+005    1.86E+005 1. 0 05E+005  8.384E+004 Pb-212      238.63    43.60   2.818E+004    2.82E+004 1. 527E+004   1. 350E+004
 +       Bi-214      609.32*   45.49   1.859E+004    l.86E+004 3.514E+004    8.099E+003 1120.29     14.92   1. 126E+005               2.44DE+004  5.080E+004 1764.49     15.30   1.104E+005                7.990E+004  4.799E+004 Pb-214      295.22    18.42   6.938E+004    3.57E+004 1. 809E+004   3.302E+004 351.93    35.60   3.567E+OD4                3.864E+004  l.684E+004 Ra-226      186 .21    3.64   3.310E+005    3.31E+005 1.653E+005    1.596E+005 Ac-228       338.32    11.27   1.086E+005    5.96E+D04 3.878E+004    5.124E+004 911. 20   25.80   5.958E+004                3.518E+004  2.701E+004 968.97    15.80   9.550E+004               -6.774E+004  4 . 302E+004 Am-241        59.54    35.90   4 .123E+004   4.12E+D04 1.630E+OD4    2.016E+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

[441]

• • • • k********************************************************************
• GAMMA SPECTRUM A N A L Y S I S *****

Filename: 5452A Report Generated On 8/17/2018 2:26:55 PM Sample Title B109100AFSFC074GD Sample Description WWTF FLOOR Sample Identification 074 Sample Type GAMMA DIRECT Sample Geometry #3 SUMP #74 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 1.041E+001 MA2 Sample Taken On 8/17/2018 2:I6: 00 PM Acquisition Started 8/17/2018 2:16:53 PM Live Time 600. 0 seconds Real Time 601 .3 seconds Dead Time 0.22 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 8/16/2018 Efficiency ID WWTF SUMP 3 DATAVALIDATED

                                                     , /

TIME ;1()4 DATE '-)-...2 -(J-- e&sen 21 ~ [442]

Peak Analysis Report 8/17/2018 2:26:56 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:

B109100AFSFC074GD Peak Analysis Performed on: 8/17/2018 2:26:55 PM Peak Analysis From Channe 1 : 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 1 290- 307 300.81 75.20 0.46 1. 24E+002 96.02 6.66E+002 2 943- 960 955.44 238.86 1. 38 1. 22E+002 49.99 1 .54E+002 3 1400- 1415 1407.64 35 1 .91 0.84 7.70E+001 38.94 9.90E+001 4 2034- 2050 2042.05 510.51 0.87 6.26E+001 27.08 3.84E+001 5 2326- 2340 2332.64 583.16 0.77 5.65E+001 24 .60 3.25E+001 6 2426- 2446 2436.14 609.04 0.84 1. 37E+002 3 1. 63 3.13E+001 7 3638- 3651 3644.79 911.20 0.75 4.90E+001 20.69 2.lOE+OOl 8 3868- 3881 3874.66 968.67 1. 43 3.06E+001 15.40 1.04E+001 9 5830- 5857 5843.51 1460.88 1.71 3.71E+002 40.00 6.61E+OOO 10 7055- 7070 7062.02 1765.51 0.29 2.0SE+OOl 15.50 1. 25E+001 M = First peak in a multiplet region m "" Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [443]

Interference Corrected Activity Report 8/17/2018 2:26:56 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:

B109100AFSFC074GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib - BNL.NLB I' ........ .. . ..... ' * * *

• IDENTI FIED NUCLIDES . .............. . ....

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M ... 2 ) Uncertainty K-40 1. 000 1460.82* 10.66 6.71964E+005 9.29664E+004 Tl-208 1. 000 583.19* 85.00 7.23686E+003 3.26618E+003 Pb-212 1.000 238.63* 43.60 1. 66698E+004 7.35721E+003 Bi-214 0.712 609.32* 45.49 3.35890E+004 8.75974E+003 1120.29 14.92 1764.49* 15.30 2.95197E+004 2.24235E+004 Pb-214 0.433 295.22 18.42 351.93* 35.60 1 .67261E+004 8.87389E+003 Ac-228 0.562 338.32 11.27 911.20* 25.80 2.72697E+004 1 .17515E+004 968.97* 15.80 2 . 89186E+004 1 .47625E+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

[444]

Interference Corrected Activity Report 8/17/2018 2:26:56 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 6.719636E+005 9.296640E+00 4 Tl-208 1.000 7.236862E+003 3.266180E+003 Pb-212 1. 000 1.666983E+004 7.357206E+003 Bi-214 0.712 3.305021E+004 8.159258E+003 Pb-214 0.433 1.672610E+004 8.873892E+003 Ac-228 0.562 2.790928E+004 9.194137E+003

      ? = 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

[445]

Interference Corrected Activity Report 8/17/2018 2:26:56 PM Page 5

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

Peak Locate Performed on: 8/17/2018 2:26:55 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 75.20 2.0622E-001 77.60 4 510.51 1. 0431E-001 43.27 M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [446]

Nucl ide MDA Report 8/17/2018 2:26:56 PM Page 6

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

Detector Name: 5452A Sample Geometry: #3 SUMP #74 Sample

Title:

B109100AFSFC074GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/M"2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 )

  +     K-40       1460.82*    10 .66 3.674E+004    3.67E+004 6.720E+005    1.592E+004 Co-60      1173.23     99.85  6.243E+003    5.90E+003 -1.070E+003   2.895E+003 1332.49     99.98  5.900E+003                1.387E+003  2.704E+003 Nb-94       702.65     99.81  4 .960E+003   4 .96E+003 -8.689E+003  2.314E+003 871.09     99.89  5.321E+003               -5.070E+002  2.472E+OD3 Ag-108m     433.90     90.50  5.187E+003    5.19E+003 -1.405E+003   2.460E+OD3 614.30     89.80  9.017E+003                5.007E+OD2  4.339E+003 722.90     90.80  6.382E+003                2.142E+D03  3.006E+003 Cs-134      604.72     97.62  8.231E+003    6.51E+D03 1.311E+003    3.961E+003 795.86     85.46  6.510E+003               -6.291E+002  3.046E+003 Cs-137      661.66     85.10  6.751E+003    6.75E+003 4.725E+003    3.188E+003 Eu-152      121.78     28.67  2. 004E+004   1 .92E+004 1.029E+004   9.811E+003 344.28     26.60  1. 920E+004              -2.046E+OD4  9.214E+003 1408 .01    21 .07 2.701E+004                2.425E+004  1.230E+004 Eu-154      123.07     40 .40 1 .427E+004   l, 43E+004 1.030E+004   6.988E+003 723.30     20.06  2.828E+004               -1.302E+004  1.330E+004 1274.43     34.80  1 .789E+004               1.648E+003  8.259E+003 Eu-155       86.55     30.70  2.136E+004    2.14E+004 4 .279E+OD4   1.049E+004 105. 31    21.10  2.750E+004               -2.250E+004  1.347E+004
  +     Tl-208      583.19*    85.00  4.444E+003    4.44E+003   7.237E+OD3  2.049E+003 Bi-212      727.33      6.67  8.581E+004    8.58E+004 1.216E+005    4. 037E+004
  +     Pb-212      238.63*    43.60  1.048E+004    1.05E+004 1 .667E+004   5.053E+003
  +     Bi-214      609.32*    45.49  9.277E+003    9.28E+003 3.359E+004    4. 306E+003 1120. 29    14 .92 5.115E+004                5.673E+004  2.410E+D04 1764.49*    15 .30 3.365E+004                2.952E+004  1.488E+004
  +     Pb-214      295.22     18 .42 3.185E+004    1.3DE+004 1. 967E+004   1.542E+004 351. 93

• 35.60 1.301E+004 1. 673E+004 6.212E+003 Ra-226 186.21 3.64 1.453E+005 1.45E+005 -5.371E+004 7.072E+004

  +     Ac-228      338.32     11. 27 4.569E+004    1.54E+004 -2.136E+003   2.194E+004 911. 20*   25.80  1.545E+004                2.727E+004  6.972E+003 968.97*    15.80  1.918E+004                2.892E+004  8.314E+003 Am-241       59.54     35.90  1.587E+004    1.59E+004 4.938E+003    7.763E+003
       +=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

[447]

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

Filename: 5452A Report Generated On 8/17/2018 2: 39: 54 PM Sample Title B109100AFSFC075GD Sample Description WWTF FLOOR Sample Identification 075 Sample Type GAMMA DIRECT Sample Geometry #3 SUMP #75 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 1.041E+001 MA2 Samp le Taken On 8/17/2018 2:29:00 PM Acquisition Started 8/17/2018 2:29:52 PM Live Time 600. 0 seconds Real Time 601.4 seconds Dead Time 0 . 22 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 8/16/2018 Efficiency ID WWTF SUMP 3 DATA VALIDATED DATE ?-?-fJ-TfME 150.0 (Jl'/&;r:_)1>ryi'?j/~ [448]

Peak Analysis Report 8/17/2018 2: 39: 54 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:

B109100AFSFC075GD Peak Analysis Performed on: 8/17/2018 2:39:54 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 1 285- 306 299.67 74.92 0.39 l .46E+002 103.62 6.76E+002 2 948- 975 954.65 238.66 1. 21 l .20E+002 68.93 2.34E+002 3 1176- 1191 1182.80 295.70 1. 34 8.75E+001 34.84 7.15E+001 4 1346- 1359 1352.85 338.21 0.33 3.73E+001 26.20 4.87E+001 5 1401- 1417 1407.94 351.98 1. 34 1. 21E+O 02 36.63 6.85E+001 6 2324- 2340 2332.30 583.07 1. 07 5.98E+001 25.90 3.42E+001 7 2426- 2446 2436.45 609. 11 1. 80 1.08E+002 29.78 3.15E+001 8 3637- 3650 3643.29 910.82 0.74 4.93E+001 19.23 1 .57E+001 9 4471- 4487 4479.51 1119.88 0.93 4.70E+001 20.02 1.70E+001 10 5831- 5856 5844.61 1461 .15 1. 74 3.29E+002 39.20 1.30E+001 11 7053- 7069 7061. 4 0 1765.35 0. 30 3.80E+001 12.33 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 [449]

Interference Corrected Activity Report 8/17/2018 2: 39: 54 PM Page 3

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Sample

Title:

B109100AFSFC075GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

   * * ****** *** ** ***** <II

• IDENTIFIED NUCLIDES . . . . . . . .. . . . . ... . . . . . .

                                                                                                   ~

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 1 .000 1460.82* 10.66 5.95347E+005 8.77814E+004 Tl- 208 1 .000 583.19* 85.00 7.64797E+003 3.43949E+003 Pb-212 1 .000 238.63* 43.60 1. 63648E+004 9.79837E+003 Bi-214 1 .000 609.32* 45.49 2.64233E+004 7.97983E+003 1120.29* 14. 92 5.13104E+004 2.22358E+004 1764.49* 15.30 5.46760E+004 l .82718E+004 Pb-214 1.000 295.22* 18.42 3.27186E+004 1 .40389E+004 351.93* 35.60 2.61895E+004 8.9968SE+003 Ac-228 0.564 338.32* 11. 27 2.49602E+004 l.79794E+004 911.20* 25.80 2.74258E+004 1.09622E+004 968.97 15.80

         *=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

[450]

Interference Corrected Activity Report 8/17/2018 2: 39 : 54 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 5.953469E+005 8.778144E+004 Tl-208 1 .000 7.647968E+003 3.439490E+003 Pb-212 1 .000 1.636480E+004 9.798371E+003 Bi-214 1 .000 3.293619E+004 6.946806E+003 Pb-214 1.000 2.809030E+004 7.574854E+003 Ac-228 0.564 2.67575BE+004 9.359679E+003

      ?  = 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

[451]

Interference Corrected Activity Report 8/17/2018 2: 39: 54 PM Page s

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Peak Locate Performed on: 8/17/2018 2: 39: 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 74.92 2.4264E-001 71.18 M ~ First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [452]

Nuclide MDA Report 8/17/2018 2 : 39:54 PM Page 6

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Detector Name: 5452A Sample Geometry: #3 SUMP #75 Sample

Title:

B109100AFSFC075GD 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  4.915E+004    4. 91E+004  5.953E+005   2.213E+004 Co-60      1173.23     99.85   7.214E+003    5.70E+OD3   7.835E+002   3.380E+003 1332.49     99.98   5.698E+003                5.553E+003   2.603E+003 Nb-94       702.65     99.81   5.298E+003    5.30E+003  -7.274E+002   2.483E+003 871.09     99.89   5.691E+003               -1.197E+002   2.657E+003 Ag-108m     433.90     90.50   5.695E+003    5.70E+003   3.187E+002   2.714E+003 614.30     89.80   8.218E+003               -8.340E+002   3.940E+003 722.90     90.80   6.211E+003               -1.198E+OD3   2.92DE+003 Cs-134      604.72     97.62   7.640E+003    6.25E+003  -2.182E+003   3.666E+003 795.86     85.46   6.251E+003                2.746E+003   2.917E+003 Cs-137      661. 66    85.10   7.099E+003    7.10E+003   4 .175E+003  3.362E+OD3 Eu-152      121 .78    28.67   1.953E+004    1.92E+004  -1 .341E+002  9.557E+003 344.28     26.60   1.920E+004                5.701E+003   9.214E+003 1408 .01    21. 07  2.701E+004                8.392E+003   1. 230E+D04 Eu-154      123.07     40.40   1.380E+004    1.38E+004  -5.546E+002   6.750E+003 723.30     20.06   2.828E+004               -6.749E+002   1.330E+004 1274.43     34.80   1.720E+004                1.095E+004   7.914E+003 Eu-155       86.55     30.70   2.145E+004    2.14E+004   1.760E+004   1.053E+004 105 . 31   21.1 0  2.774E+004                1.873E+004   1 .359E+004
 +      Tl-208      583.19*    85. 0 0 4.720E+003    4 .72E+003  7.648E+003   2.187E+003 Bi-212      727.33      6.67   8.294E+004    8.29E+004   3.935E+004   3.894E+004
 +      Pb-212      238.63*    43.60   1 .509E+004   1 .51E+004  1.636E+004   7.359E+003
 +      Bi-214      609.32*    45.49   9.309E+003    3.89E+003   2.642E+004   4.322E+003 1120.29*    14. 92  2.914E+004                5.131E+004   1.309E+004 1764.49*    15.30   3.894E+OD3                5.468E+004   O.OOOE+OOO
 +      Pb-214      295.22*    18.42   1.909E+OD4    1 .11E+004  3.272E+004   9.038E+003 351. 93

• 35.60 1.107E+004 2.619E+004 5.241E+003 Ra-226 186.21 3.64 1.496E+D05 1.50E+005 6.771E+004 7.289E+004

 +      Ac-228      338.32*    11.27   2.729E+D04    1.35E+004   2.496E+004   1.274E+004 911. 20*   25.80   1.353E+004                2.743E+004   6.014E+003 968.97     15.80   4 .604E+D04               7.40DE+004   2.174E+004 Am-241       59.54     35.90   1 .769E+D04   l.77E+OD4   1.061E+OD4   8.671E+OD3
       + ; 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

[453]

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

Filename: 6279 Report Generated On 8/16/2018 9:38:15 AM Sample Title B109100AFQFC009GD Sample Description WWTF FLOOR Sample Identification 009 Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 (I I'\.- ~/ z 1r. ar Sample Size *z. 8:25E+001 M"2 2.-&-> Sample Taken On 8/16/2018 9:28:00 AM Acquisition Started 8/16/2018 9:28:13 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE q-c-(e:Y 0

                                                      ,'7     TIME f ? ~ '

[454] &~ ~

Peak Analysis Report 8/16/2018 9:38:15 AM Page 2

• • • • • PE AK ANALYSIS R E P O R T *****

Detector Name: 6279 Sample

Title:

B109100AFQFC009GD Peak Analysis Performed on: 8/16/2018 9:38:14 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 1 295- 307 299.84 75.09 0 .69 7.07E+001 46.97 1.81E+002 2 950- 960 954.73 238.80 0 .35 2.90E+001 20.32 3.lOE+OOl 3 1175- 1188 1180.36 295.20 1. 30 3.52E+001 18.41 1. 78E+001 4 2429- 2442 2435.83 609.05 0.85 4.88E+001 18.16 l .22E+001 5 5834- 5854 5844.66 1 461.22 1. 17 9.34E+001 20.31 2.65E+OOO M =: First peak in a multiplet region m ;; Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [455]

Interference Corrected Activity Report 8/16/2018 9:38:15 AM Page 3

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Sample

Title:

B109100AFQFC009GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10 .66 1. 01379E+006 2.48040E+005 Pb-212 1.000 238.63* 43.60 2.30954E+004 1 .66922E+004 Bi-214 0.461 609.32* 45.49 7.11429E+004 2.82775E+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

[456]

Interference Corrected Activity Report 8/16/2018 9:38:15 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 l.013794E+006 2.480395E+005 Pb-212 1.000 2.309542E+004 l .669216E+004 Bi-214 0 .461 7.114292E+004 2.827751E+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: 8/16/2018 9:38:14 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 75.09 1 .1781E-001 66.45 3 295.20 5.8648E-002 52.33 Tol. Pb-214 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [457]

Nuclide MDA Report 8/16/2018 9:38:15 AM Page 5

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Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFQFC009GD 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  1.408E+005    1 .41E+005 1.014E+006   5.571E+004 Co-60     1173.23     99.85  2.079E+004    1 .17E+004 -1 .010E+004 9.036E+003 1332.49     99.98  1.165E+O 04              -5.231E+003  4.361E+003 Nb-94       702.65    99. 81 2.055E+004    1.87E+004 -1 .150E+004  9.287E+003 871.09    99.89  1.870E+004               -6.248E+003  8.222E+003 Ag-108m     433.90    90.50  2.067E+004    2.07E+004 -1.918E+004   9.552E+003 614.30    89.80  3.553E+004               -3.294E+004  1.676E+004 722.90    90.80  2.192E+004               -5.286E+003  9.859E+003 Cs-134      604.72    97.62  3.015E+004    2.47E+004 4.787E+004    1 .416E+004 795.86    85.46  2.474E+004                5.402E+003  1 .112E+004 Cs-137      661.66    85.10  2.141E+004    2.14E+004 -1 .092E+004  9.588E+003 Eu-152      121.78    28.67  6.854E+004    6.85E+004 -1 .181E+004  3.305E+004 344.28    26.60  7.389E+004               -4.231E+004  3.468E+004 1408 .01    21.07  1.200E+005                5.256E+004  5.276E+004 Eu-154      123.07    40.40  4.778E+004    4.78E+004 -1.141E+004   2.303E+004 723. 3 0  20.06  9.760E+004               -2.770E+004  4.380E+004 1274.43     34.80  7.116E+004                6.052E+004  3.148E+004 Eu-155       86.55    30.70  7.639E+004    7.64E+004 4.827E+004    3.709E+004 105.31    21.10  9.518E+004               -2.147E+004  4.598E+004 Tl-208      583.19    85.00  2.351E+004    2.35E+004 1 .471E+004   1.073E+004 Bi-212      727.33     6.67  3.045E+005    3.05E+005 8.070E+004    1. 372E+D05
 +       Pb-212      238.63*   43.60  2.474E+004    2.47E+004 2.310E+004    1.129E+004
 +       Bi-214      609.32*   45.49  3.177E+004    3.18E+004 7.114E+004    1.391E+004 1120.29     14.92  1 .694E+005               2.192E+004  7.587E+004 1764.49     15.30  1 .855E+005               l.392E+005  8.098E+004 Pb-214      295.22    18 .42 1 .129E+005   6.12E+004 1. 571E+005   5.351E+004 351.93    35.60  6.116E+004                4.932E+004  2.886E+004 Ra-226      186.21     3.64  5.140E+005    5.14E+005 -1.801E+005   2.459E+005 Ac-228      338.32    11. 27 1.897E+005    9.90E+004 2.033E+005    8.958E+004 911.20    25.80  9.898E+004                9.113E+004  4. 500E+004 968.97    15.80  1 .563E+005               8.303E+004  7.052E+004 Am-241       59.54    35.90  6.267E+004    6.27E+004 4 .708E+004   3.021E+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

[458]

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

Filename: 6279 Report Generated On 8/18/2018 2: 31: 10 PM Sample Title B109100AFQFC014GD Sample Description WWTF FLOOR Sample Identification 014 QC Sample Type GAMMA DIRECT Sample Geometry 3M90DWWTF1.27CM 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 2 ,f>J Sample Size 2--:- S.2t>E+001 M... 2

                                          ~       r/zy/is-Sample Taken On                    8/18/2018         2:21:00 PM Acquisition Started                8/18/2018         2:21:08 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA V/~LIDATED DATE 1-2-!r [459] 21~=i~~ TIME;D~,

Peak Analysis Report 8/18/2018 2:31:10 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:

B109l00AFQFC0l4GD Peak Analysis Performed on: 8/18/2018 2:31: 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 1 267- 310 300.46 75.24 1. 05 1 .59E+002 110.62 4.48E+002 2 949- 962 954.51 238.75 0.40 3.82E+001 28.60 5.88E+001 3 1175- 1186 1180.91 295.34 0.53 1 .99E+001 18.77 2.71E+001 4 1401- 1415 1407.10 351.89 1. 00 4.34E+001 20.55 2.16E+001 5 2429- 2445 2435.95 609.08 0.42 5.15E+001 17.68 8.50E+OOO 6 5834- 5852 5844.22 1461.11 0.78 8.15E+001 18.99 2.47E+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 [460]

Interference Corrected Activity Report 8/18/2018 2: 31: 10 PM Page 3

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Sample

Title:

B109100AFQFC014GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• I
• t * * .-
• I Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 8.85304E+005 2.20109E+005 Pb-212 1.000 238.63* 43.60 3.04048E+004 2.33089E+004 Bi-214 0.461 609.32* 45.49 7.51145E+004 2.73194E+004 1120.29 14.92 1764.49 15.30 Pb-214 1 .000 295.22* 18.42 4 .32724E+004 4.13872E+004 351.93* 35.60 5.52906E+004 2.74261E+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

[461]

Interference Corrected Activity Report 8/18/2018 2:31:10 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 8.853037E+005 2.201095E+OOS Pb-212 1.000 3.040481E+004 2.330890E+004 Bi-214 0.461 7.511446E+004 2.731940E+004 Pb-214 1.000 5.162337E+004 2.286197E+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: 8/18/2018 2: 31: 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  !!-* 0 Uncertainty Type Nuclide 1 75.24 2.654 4E-00 1 69.45 M "' First peak in a multiplet region m =- Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [462]

Nucl ide MDA Report 8/18/2018 2:31: 10 PM Page 5

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Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFQFC0l4GD 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  1.345E+005    l .35E+005  8.853E+005  5.256E+004 Co-60       1173.23     99.85  2.827E+004    2. 04E+004  1.479E+004  1. 278E+004 1332.49     99.98  2.037E+004                l.299E+004  8.722E+003 Nb-94         702.65    99. 81 1. 926E+004   l .93E+004  5.081E+003  8.646E+003 871.09    99.89  2.239E+004               -4. 913E+003 1.007E+004 Ag-108m       433.90    90.50  l. 823E+004   1.82E+004  -1.533E+004  8.327E+003 614. 3 0  89.80  3.135E+004               -3.047E+004  l.467E+004 722.90    90.80  2.738E+004                1. 427E+004 1.259E+004 Cs-134        604.72    97.62  3.015E+004    2.21E+004   9.999E+002  1.416E+004 795.86    85.46  2.211E+004               -2.503E+004  9.810E+003 Cs-137        661.66    85.10  2.524E+004    2.52E+004   3.555E+003  1.151E+004 Eu - 152      121.78    28.67  6.867E+004    6.87E+004   1 .336E+004 3.312E+004 344.28    26.60  7.897E+004               -8.305E+004  3.722E+004 1408.01     21. 07 8.026E+004               -4.677E+004  3.290E+004 Eu-154        123.07    40.40  4.854E+004    4.85E+004  -6.683E+003  2.341E+004 723.30    20.06  1.227E+005                6.093E+004  5.633E+004 1274.43     34.80  5. 271E+004              -3.510E+004  2.226E+004 Eu-155         86.55    30.70  7.821E+004    7.82E+004   1.079E+005  3.800E+004 105.31    21.10  9.601E+004               -6.650E+004  4.639E+004 Tl-208        583 .19   85.00  2.749E+004    2.75E+004   1.095E+004  1.272E+004 Bi-212        727.33     6.67  3.456E+005    3.46E+005   1.415E+005  1. 577E+005
 +       Pb-212        238.63*   43.60  3.596E+004    3.60E+004   3.040E+004  1.690E+004
 +       Bi-214        609.32*   45.49  2.871E+004    2.87E+004   7.511E+004  1.238E+004 1120.29     14 .92 1.632E+005                5.672E+002  7.277E+004 1764.49     15.30  1. 750E+005               1. 218E+005 7.575E+004
 +       Pb-214        295.22*   18.42  6.493E+004    3.64E+004   4.327E+004  2.953E+004 351.93*   35.60  3. 644E+004               5.529E+004  1. 650E+O 04 Ra-226        186.21     3.64  5.384E+005    5.38E+005  -4.302E+004  2.581E+005 Ac-228         338i32    11.27  1.783E+005    l .13E+005  8.838E+004  8.385E+004 911.20    25.80  1.125E+005                5.759E+004  5.177E+004 968.97    15.80  1 .513E+OOS               7.177E+004  6.805E+004 Am-241          59.54    35.90  6.744E+004    6.74E+004   3.445E+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

[463]

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

Filename: 6279 Report Generated On 8/14/2018 3:26:02 PM Sample Title B109100AFQFC027GD Sample Description WWTF Floor QC Sample Identification QC Sample Type Gamma Direct Sample Geometry 3MWWTF1.27CM 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 8/14/2018 3:15:00 PM Acquisition Started 8/14/2018 3:16:01 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 7/31/2018 Efficiency ID 3MWWTF1,27CM [464]

Peak Analysis Report 8/14/2018 3: 26: 02 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:

B109100AFQFC027GD Peak Analysis Performed on: 8/14/2018 3:26:02 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- 305 300.29 75.20 1.16 2.20E+002 71. 06 2.54E+002 2 1174- 1186 1179.55 295.00 0.38 1. 73E+001 20 .12 3.17E+001 3 1401- 1413 1407.32 35 1 .94 0.78 3.78E+001 19.39 2.12E+001 4 2429- 2443 2435.28 608.92 0.52 3.84E+001 15.86 8.57E+OOO 5 3636- 3649 3642.19 910.63 0.81 2.18E+001 13.39 8.20E+OOO 6 5833- 5852 5842.30 1460.63 0.94 l. 03E+002 21.03 2.34E+OOO M ;;;: First peak in a multiplet region m = Other peak in a multiplet region F ;;;: Fitted singlet Errors quoted at 2 . 000 sigma [465]

Interference Corrected Activity Report 8/14/2018 3:26:02 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:

B109100AFQFC027GD 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 1.11291E+006 2.47622E+005 Bi-214 0.461 609.32* 45.49 5.59631E+004 2.40577E+004 1120.29 14.92 1764.49 15.30 Pb-214 1 . 000 295.22* 18.42 3.75862E+004 4.40633E+004 351.93* 35.60 4.80651E+004 2.56700E+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

[466]

Interference Corrected Activity Report 8/14/2018 3:26:02 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 .112912E+006 2.476216E+005 Bi-214 0.461 5.596310E+004 2.405772E+004 Pb-214 1 .000 4.540985E+004 2.218056E+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: 8/14/2018 3:26:02 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 75.20 3.6667E-001 32.30 5 910.63 3.6333E-002 61.42 Sum M First peak in a multiplet region m : Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [467]

Nuclide MDA Report B/14/2018 3 :26:03 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3MWWTF1.27CM Sample

Title:

Bl09100AFQFC027GD 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   l.296E+005    1.30E+005     l .113E+006     5.014E+004 Co-60     1173.23      99.85   3.028E+004    2.11E+004     l.207E+004      l.378E+004 1332.49      99.98   2.105E+004                  7.607E+003      9.065E+003 Nb-94       702.65     99.81   1. 890E+004   1.89E+004    -3.857E+003      8.466E+003 871.09     99.89   2.199E+004                 -7.527E+003      9.868E+003 Ag-108m     433.90     90.50   2.102E+004    2.10E+004    -1.898E+004      9.727E+003 614. 3 0   89.80   2.897E+004                  3.339E+003      1. 348E+004 722.90     90.80   2.364E+004                 -6.312E+003      1. 072E+004 Cs-134      604.72     97.62   3.063E+004    2.70E+004     6.754E+002      1. 440E+004 795.86     85.46   2.70SE+004                 -1. 4 81E+004    1.228E+OD4 Cs-137      661. 66    85 .10  2.734E+004    2.73E+004    -3.541E+002      1.256E+004 Eu-152      121. 78    28.67   7.850E+004    6.74E+004     4.439E+004      3.804E+004 344.28     26.60   6.735E+004                 -1.317E+004      3.141E+004 1408. 01     21.07  1.005E+005                   2.724E+004      4.302E+004 Eu-154      123. 07    40. 40  5.391E+004    S.39E+004    -2.121E+004      2.609E+004 723. 3 0   20.06   l.055E+005                 -3.227E+004      4 .776E+004 1274.43      34.80   6.263E+004                 -7.555E+002      2.723E+004 Eu-155       86.55     30.70   8.426E+004    8.43E+004     4 .443E+004     4.103E+004 105 .31    21.10   l.060E+005                  l .075E+005     5.141E+004 Tl-208      583.19     85.00  2.933E+004     2.93E+004     1 .129E+004     1.364E+004 Bi-212      727.33      6.67   3.137E+005    3.14E+OOS     2.024E+OOS      1.418E+OOS Pb-212      238.63     43.60  4.837E+004     4.84E+004     2.247E+004      2. 311E+004
 +       Bi-214      609.32*    45.49  2.764E+004     2.76E+004     5.596E+D04      1. 185E+O 04 1120 .29     14. 92 2.140E+OOS                   3.012E+004      9.820E+004 1764 .49     15. 30 1. 636E+005                  l.043E+005      7.003E+004
 +       Pb-214      295.22*    18.42  7.124E+004     3.48E+004     3.759E+004      3.269E+004 351. 93

• 35.60 3. 477E+004 4 .807E+004 1 .567E+004 Ra-226 186.21 3.64 5.542E+005 5.54E+005 l.284E+004 2.660E+005 Ac-228 338.32 11.27 1.679E+OOS 1.22E+OOS l .718E+004 7.866E+004 911. 20 25.80 1.222E+OOS 8.843E+004 5.663E+004 968.97 15.80 l.655E+005 -8.347E+003 7.512E+004 Am-241 59.54 35.90 7.047E+004 7.05E+004 -2.664E+003 3 .411E+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

[468]

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

Filename: 6279 Report Generated On 8/20/2018 10:04:21 AM Samp le Title B109100AFQWC053GD Sample Description WWTF Wall QC Sample Identification QC Sample Type Gamma Direct Sample Geometry 3M9DDWWTF1.27CM 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 8/20/2018 9:54:00 AM Acquisition Started 8/20/2018 9:54:19 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 7/31/2018 Efficiency ID 3MWWTF1,27CM DATA VALIDATED DATE °/-Z-rS [469] g~;v~ TIME !.S-2t

Peak Analysis Report 8/20/2018 10 :04:21 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:

B109100AFQWC053GD Peak Analysis Performed on: 8/20/2018 10:04:21 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- 306 301 .01 75.38 0.98 5.89E+001 44.29 l .79E+002 2 1401- 1413 1407.18 3 51 .91 1. 32 4.54E+OD1 19.15 1 .76E+001 3 2429- 2442 2435.50 608.97 1. 38 3.85E+001 16.42 1.05E+001 4 2639 - 2652 2644.69 661.27 0.57 4.06E+001 14 .95 5.40E+OOO 5 5836 - 5854 5844~83 1461.26 1. 07 7.70E+001 17 .55 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 [470]

Interference Corrected Activity Report 8/20/2018 10:04:21 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:

B109100AFQWC053GD 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 8.35029E+OOS 2.03666E+005 Cs-137 1. 000 661.66* 85.10 3.34051E+004 1.29393E+004 Bi-214 0 .461 609.32* 45.49 5.60671E+004 2.48507E+004 1120.29 14 . 92 1764.49 15 .30 Pb-214 0 .432 295.22 18.42 351.93* 35.60 5.77038E+004 2.58287E+004

       * = Energy line found in t he spectrum.
       @ ~ Energy line not used for Weighted Mean Activity Energy Tolerance :     10.000 keV ID1clide confidence index threshold ~          0 .30 Errors quoted at 2.000 sigma

[471]

Interference Corrected Activity Report 8/20/2018 10:04:21 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/M"2 ) Uncertainty K-40 1.000 8.350291E+OOS 2.036659E+OOS Cs-137 1.000 3.340515E+004 l.29392SE+00 4 Bi-214 0.461 5.606710E+004 2.485066E+00 4 Pb-214 0.432 5.770376E+004 2.582872E+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: 8/20/2018 10:04:21 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 Nuc li de 1 75.38 9.8178E-002 75.19 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 [472]

Nuclide MDA Report 8/20/2018 10 : 04 :21 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90DWWTF1.27CM Sample

Title:

B109100AFQWC053GD 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  2.935E+004      2.93E+004   8.350E+OOS    O.OOOE+OOO Co-60      1173.23    99.85   2.135E+004      1. 88E+004  9.201E+003    9.319E+003 1332.49    99.98   1.883E+004                  3.134E+003    7.951E+003 Nb-94        702.65   99.81   1.890E+004      l. 89E+004  8.916E+003    8.466E+003 871.09   99.89   2.040E+004                  l.128E+004    9.077E+003 Ag-108m      433.90   90.50   1.967E+004      1.96E+004  -7.518E+003    9.049E+003 614.30   89.80   3.151E+004                 -6.051E+003    l.475E+004 722.90   90.80   1.957E+004                  l.266E+004    8.682E+003 Cs-134       604.72   97.62   2.976E+004      2.06E+004   3.351E+004    1 .397E+004 795.86   85.46   2.063E+004                 -2.808E+003    9.070E+003
 +      Cs-137       661.66*  85 .10  1.281E+004      l.28E+004   3.341E+004    5.291E+003 Eu-152       121.78   28.67   7.217E+004      6.54E+004  -l.175E+003    3.487E+004 344.28   26.60   6.539E+004                 -1.141E+005    3.043E+004 1408. 01   21. 07  1.005E+005                  2.691E+004    4.302E+004 Eu-154       123.07   40.40   5.228E+004      5.23E+004   3.771E+004    2.528E+004 723.30   20.06   8.671E+004                  3.337E+004    3.837E+004 1274.43    34.80   6.263E+004                  4.533E+004    2.723E+004 Eu-155        86.55   30.70   7.772E+004      7.77E+004   5.502E+004    3.776E+004 105.31   21.10   1.012E+O 05                 1.294E+004    4.897E+004 Tl-208       583.19   85.00   2.817E+004      2.82E+004   2.308E+004    l.306E+004 Bi-212       727.33    6.67   2.436E+005      2.44E+005  -l.057E+005    l.067E+005 Pb-212       238.63   43.60   4.701E+004      4.70E+004   4.769E+004    2.243E+004
 +      Bi-214       609.32*  45.49   2.972E+004      2.97E+004   5.607E+004    l.289E+004 1120.29    14.92   1. 7 51E+O 05               7.653E+004    7.874E+004 1764.49    15.30   1. 576E+005                 1.995E+004    6.705E+004
 +      Pb-214       295.22   18.42   1.084E+005      3.19E+004  -1 .913E+004   5.124E+004 351.93*  35.60   3.189E+004                  5.770E+004    l.423E+004 Ra-226       186.21    3.64   5.044E+005      5.04E+005  -3.002E+005    2.411E+005 Ac-228       338.32   11.27   l.700E+005      8.91E+004   l.559E+004    7.970E+004 911.20   25.80   8.905E+004                 -7.822E+003    4.004E+004 968.97   15.80   1.511E+005                 -1.166E+004    6.795E+004 Am-241        59.54   35.90   7.378E+004      7.38E+004   l.565E+004    3.577E+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

[473]

8/27/2018 10:08:51AM Page 1 of6 Analysis Report for 27-Aug-18-10001 B1-09100A-FSFC-001 CV 0.0" - 0.5 0.0" GAMMA SPECTRUM ANALYSIS Sample Identification  : 27-Aug-18-10001 Sample Description  : 81-09100A-FSFC-001CV 0.0" - 0.5" 0.0" Sample Type  ; Puck Unit Sample Point Sample Size 9.854E+01 grams Faci!:ty  : Default Sample Taken On  : 8/22/2018 8:52:00AM Acquisition Started  : 8/27/2018 9:48:45AM Procedure  : Puck_half_inch Operator  : jwelch Detector Name  : 324 Geometry  : Puck_half_inch Live Time  : 1200.0 seconds Real Time  : 1200.3 seconds Dead Time  : 0.03% Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 120- 4096 Peak Area Range (in channels)  : 120- 4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 8/9/2017 Efficiency Calibration Used Done On  : 8/27/2018 Efficiency Calibration Description DATA VALIDATED Sample Number  : 49639 DATE q...z-Jr_ Certificate Name  : Eu 155-Na22 TIME o:fo.o ' Certificate Date  : 1/30/2013 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 10:08:47AM Peak Analysis From Channel  : 120 Peak Analysis To Channel  : 4096 [474]

8/27/2018 10:08:51AM Page2 of6 Analysis Report for 27-Aug-18-10001 B1-09100A-FSFC-001 CV o.o* - o.s* 0.0" Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) 1 351.95 701 - 706 703.85 3.24E+Ol 16.35 3.91E+Ol 0.80 2 609.32 1213 - 1223 1218.21 3. 72E+Ol 17.83 3.55E+Ol 1. 24 3 661 .58 1317 - 1327 1322.70 3. 0lE+Ol 13.67 1 .39E+Ol 0.75 4 1460.89 2916 - 2928 2921.83 3. 91E+Ol 13.65 5.81E+OO 1. 90 M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K-40 0. 99 1460.82

• 10.66 4.84E+OO 1 .74E+OO Cs-137 0. 99 661.66
• 85.10 2.68E-01 1. 26E-01 Bi-211 0.8 8 351.07
• 13. 02 1.18E+OO 6.26E-01 Bi-214 1. 00 609.32
• 45. 49 5.86E-01 2.89E-01 768.36 4. 89 806. ]8 1. 26 934.06 3. 11 1120.29 14. 92 1155. 21 1. 63 1238.12 5.83 1280.98 1. 43 1377. 67 3.99 1385. 31 0 .79 1401.52 1. 33 1407.99 2.39

[475]

8/27/2018 10:08:51AM Page 3 of6 Analysis Report for 27-Aug-18-10001 81-091 OOA-FSFC-001 CV 0.0" - 0.5" 0.0" Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty Bi-2 14 1. 00 1509.21 2 . 13 1661.27 1. 05 1729.59 2. 8 8 1764.49 15.30 1847.43 2 .03 2118.51 1.16 Pb-214 1. 00 241.99 7 . 25 295.22 18 . 42 351.93

• 35. 6 0 4. 3 3E- 01 2.29E- 0 1 785.96 1. 06

     * = Energy line found in the spectrum.
     - = Manually added nuclide.
     ? = Manually edited nuclide.
     @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide                            Nuclide                        Wt mean                Wt mean      Comments Name                                  Id                           Activity               Activity Confidence                                             Uncertainty (pCilgrams)

K-40 0.999 4.84E+OO 1.74E+OO Cs-137 0.999 2.68E-01 1. 26E-01

     ?       Bi-211                              0.883                      1.18E+OO                6.26E-01 Bi-214                              1.000                      5.86E-01                2.89E-01
     ?       Pb-214                              1. 000                     4.33E-01                2.29E-01
       ?   = 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 2.000sigma

[476]

8/27/2018 10:08:51AM Page 4 of6 Analysis Report for 27-Aug-18-10001 B1-09100A-FSFC-001CV 0.0" - 0.5" 0.0" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 10:08:47AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZI ON LI B-B NL.N LB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCUgrams) (pCi/grams) (keV) An Pk 511. 00 100.00 3.88E-01 2.98E-01 2.98E-01 BE-7 477.60 10.44 -6.20E-01 1. 52E+OO 1. 52E+OO + K-40 1460.8~

• 10.66 4.84E+OO 1. 50E+OO 1.SOE+OO Co-60 1173.23 99.85 -2.74E-02 2.19E-01 2.19E-01 1332.49 99.98 9.82E-02 2.30E-01 Nb-94 702.65 99.81 6.30E-02 1.43E-01 2 .17E-01 871.09 99.89 -1.97E-02 1.43E-01 Ag-108m 79.13 6.60 -4.57E-01 1.67E-01 3.17E+OO 433.94 90.50 -1.0SE-02 1. 82E-01 614.28 89.80 2.60E-02 2.60E-01 722.94 90.80 -5.68E-02 1.67E-01 Sb-125 176.31 6.84 -3.53E-01 5.52E-01 2.23E+OO 380.45 1. 52 7.84E+OO 1 .19E+Ol 427.87 29.60 1. 87E-02 5.52E-01 463.36 10.49 1. 33E-01 1 .65E+OO 600.60 17.65 -7.73E-02 9.SBE-01 606. 71 4.98 5.06E-01 6.14E+OO 635.95 11. 22 1.21E+OO 2.0lE+OO 671.44 1. 79 9.21E-01 1.07E+01

[477]

8/27/2018 10:08:51AM Page 5 of6 Analysis Report for 27-Aug-18-10001 B1-09100A-FSFC-001 CV 0.0" - 0.5" 0.0" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCi/grams) (pCi/grams) (keV) Ba-133 79.61 2.65 -9.39E-01 3.50E-01 7.78E+OO 81.00 32.90 -3. lOE-01 5.52E-01 276.40 7.16 2.lSE-01 2.36E+OO 302.85 18 .34 2.86E - 01 9.51E-01 356.01 62.05 -3.42E-01 3.50E-01 383.85 8.94 -5.47E-01 1.75E+OO Cs-134 475.36 1. 48 l.74E+OO 2.24E-01 1. llE+Ol 563.25 8.34 3.94E-01 2.15E+OO 569.33 15.37 9.77E-02 1 .15E+OO 604.72 97.62 -8.93E-03 2.67E-01 795.86 85.46 5.39E-02 2.24E-01 801.95 8.69 -3.41E-01 2.02E+OO 1038.61 0 .99 -8.72E+OO 1 .97E+Ol 1167. 97 1. 79 -3.85E+OO 1. 08E+Ol 1365.19 3.02 -3.63E+OO 6.07E+OO + Cs-137 661.66

• 85.10 2.68E-01 l. 49E-Ol l.49E-01 Eu-152 121.78 28.67 1. 29E-01 4. 63E-01 4.63E-01 244.70 7.61 1 .88E+OO 2.25E+OO 295.94 0.45 l.90E+Ol 4.20E+Ol 344.28 2 6 .60 -3.39E-01 5.56 £ -01 367.79 0.86 5.51E-01 1 .64E+Ol 411 .12 2.24 3.40E+OO 7.94E+OO 443.96 2.83 -3.89E-01 5.56E+OO 488.68 0. 42 -1.77E+Ol 3. 96E+Ol 563.99 0. 49 1.21E+Ol 3.77E+Ol 586.26 0. 46 4.53E+Ol 5.36E+Ol 678.62 0.47 -9 .31E+OO 3.90E+Ol 688.67 0. 86 -1 .66E+Ol 1. 95E+Ol 719.35 0.28 -7.46E+Ol 5.21E+Ol 778.90 12. 96 l.02E-01 1. 32E+OO 810.45 0.32 4.63E+OO 5.84E+Ol 867.37 4.26 1.78E+OO 4. 04E+OO 919.33 0.43 4.23E+OO 4.35E+Ol 964.08 14.65 1.63E-01 1.40E+OO 1085.87 10.24 9.06E-01 2.03E+OO 1089.74 1. 73 -1.87E+OO 9.60E+OO 1112 .07 13. 69 3.90E-01 1. 30E+OO 1212.95 1. 43 2.89E+OO 1. 62E+Ol 1249.94 0.19 6.35E+Ol 1. 37E+02 1299 .14 1. 63 -7.95E+OO 1.22E+Ol 1408.01 21. 07 2.47E-01 1.00E+OO 1457.64 0.50 -8.19E-01 9.28E+Ol 1528.10 0.28 9.72E+OO 4.69E+Ol Eu-154 123.07 40.40 -9.06E-03 3.18E-01 3.18E-01 247.93 6.89 -1.08E+OO 2. llE+OO 591.76 4.95 1 .68E+OO 3.81E+OO 692.42 1. 78 -2.39E+OO 1. 1 SE+Ol 723. 30 20.06 -1. 59E-01 7.86E-01 756.80 4.52 5.64E-01 3.72E+OO 873.18 12.08 2.29E-01 l. llE+OO 996.29 10. 48 -2.81E-01 l.94E+OO

[478]

8/27/2018 10:08:51AM Page 6 of6 Analysis Report for 27-Aug-18-10001 B1-091 OOA-FSFC-001 CV 0.0" - 0.5" 0.0" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCi/grams) (keV) Eu-154 1004. 76 18.01 -3.82E-01 3.lBE-01 1. lO E+OO 1274.43 34.80 -1. 02E- 0 1 5.31E-01 1596.48 1. 80 -9.98E+OO 1.30E+Ol Eu-155 45.30 1. 31 -3.81E+OO 5.69E-01 3.24E+Ol

60. 01 1. 22 -9.95E+OO 3.29E+Ol 86.55 30.70 3.37E-02 5.69E- 01 105. 31 21.10 1.54E-01 6.67E-01 Ra-226 186. 21 3.64 1.57E+OO 4.40E+OO 4.40E+OO Pa-231 27.36 1 0 .30 1.39E+OO 3.14E+OO 3.14E+OO 283.69 1. 70 -7.39E+OO 8.37E+OO 300.07 2.47 -2.lOE+OO 7.06E+OO 302.65 2.20 2.38E+OO 7.92E+OO 330.06 1. 40 8.12E+OO 1.28E+Ol U-235 143.76 10 .96 -1.38E-Ol 2.76E-01 1. 14E+OO 163.33 5.08 -1.31E+OO 3.0SE+OO 185.71 57.20 6.42E-02 2.76E-01 202 . 11 1. 08 8.30E+OO l .53E+Ol 205.31 5 .01 -7.69E-01 2.94E+OO Arn-241 59.54 35.90 3.26E-02 l.18E+OO l .18E+OO

    +   =  Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
    >   =  MDA value not calculated
   @    =  Half-life too short to be able to perform the decay correction
    ?   =  CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[479]

0000049639.CNF Live Time :1200.000 sec Real Time :1200. 340 sec 60 start: 1: O.l(kev) stop : 4096:2047 .l(kev) Acq. start :Mon Aug 27 09:48:45 2018 55 50 45 40 35 Vl .f-J C 8 30

                         ~

25 ' 00 0.. 20 ~

                                        ~

H'

                                           ....7 u

15 10

             ~     I 500           1000          1500      2000     2500   3000                       3500    4000 channel
       ~

ROI Type: 1 [480]

8/27/2018 10:48:36AM Page 1 of7

             ~pex-Gamma Analysis Report for       27-Aug-18-1 0002 81-09100A-FSFC-001CV        0 .0" - 0.5" 0.5" GAMMA SPECTRUM ANALYSIS Sample    Identification                        : 27-Aug-18-10002 Sample    Description                           : 81-09100A-FSFC-001CV  0.0" - 0.5"   0.5" Sample    Type                                  : Puck Unit Sample    Point Sample Size                                        9.854E+01 grams Facility                                        : Default Sample Taken On                                 : 8/22/2018 8:52:00AM Acquisition Started                             : 8/27/2018 10:28:29AM Procedure                                       : Puck_half_inch Operator                                       ; jwelch Detector Name                                  : 324 Geometry                                       : Puck_half_inch Live Time                                      : 1200.0 seconds Real Time                                      : 1200.3 seconds Dead Time                                      : 0.03%

tt~ Peak Locate Threshold  : 3.00 Peak Locate Range (ln channels)

• 120 -4096 Peak Area Range (in channels)
• 120
• 4096 Identification Energy Tolerance
• 1.000 keV Energy Calibration Used Done On  : 8/9/2017 Efficiency Calibration Used Done On  : 8/27/2018 DATA VALIDATED Efficiency Calibration Description DATE 9-Z-/f:

Sample Number  : 49643 Tl ME__.;;;.,....+,'-~ Certificate Name Certificate Date

Eu155-Na22

1/30/2013 12:00:00PM 0<./v. ~ 1 PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 10:48:32AM Peak Analysis From Channel  : 120 Peak Analysis To Channel  : 4096

[481]

B/27/2018 10:48:36AM Page 2 of7 Analysis Report for 27-Aug-18-10002 B1-091 OOA-FSFC-001 CV 0.0" - 0.5" 0.5" Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) 1 238.62 472 - 480 477 .43 5. 08E+Ol 24.46 9.24E+Ol 1. 07 2 609. 34 1212 - 1223 1218.26 6. 0lE+Ol 17 .32 1. 19E+Ol 1. 46 3 661. 72 1320 - 1326 1322.97 7. 84E+OO 10 .80 2 .23E+Ol 0 .65 4 911. 55 1819 - 1826 1822 .54 l.83E+Ol 9.34 3. 45E+OO 0 .93 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty Cs-137 0.99 6 61. 66

• 85.10 7.00E-02 9.68E-02 Pb-212 1. 00 115. 18 0. 60 238.63
• 43.60 4 .17E-01 2.12E- 01 300. 09 3.30 Bi-214 1. 00 609.32
• 45.49 9.45E-01 2 .95E-01 768.36 4.89 806.18 1. 26 934.06 3. 11 1120.29 14. 92 1155. 21 1. 63 1238.12 5.83 1280.98 1. 43 1377.67 3.99 1 'JO t:: ') 1 (\ "7 0

                                      ..L..JU.J*_,..1.-                  V  *  'J 1401. 52                            1. 33

[482]

8/27/2018 10:48:36AM Page 3 of7 Analysis Report for 27-Aug-18-10002 B1-09100A-FSFC-001 CV 0.0" - 0.5" 0.5" Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty Bi-214 1. 00 1407.99 2.39 1509.21 2 .13 1661.27 1. 05 1729.59 2.88 1764.49 15.30 1847.43 2.03 2118.51 1. 16 Ac-228 0 . 99 129.07 2.42 209.25 3.89 270.24 3. 46" 328.00 2.95 338.32 11.27 409.46 1. 92 463.00 4.40 794.95 4.25 911. 20

• 25.80 6.72E-01 3. 48E-01 964. 77 4.99 968.97 15.80 1588.20 3.22

     * = Energy line found in the spectrum.
     - = Manually added nuclide.
     ? = Manually edited nuclide.
     @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide                           Nuclide                       Wt mean                Wt mean      Comments Name                                 Id                          Activity               Activity Confidence                                           Uncertainty (pCi/grams)

Cs-137 0.999 7.00E-02 9.68E-02 Pb-212 1. 000 4.17E-01 2.12E-01 Bi-214 1. 000 9.45E-Ol 2.95E-01 Ac-228 0.994 6. 72E-Ol 3.48E-01 [483]

8/27/2018 10:48:36AM Page4 of7 Analysis Report for 27-Aug-18-10002 B1-09100A-FSFC-001CV 0.0"- 0.5" 0.5"

       ?  = 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 2.000sigma

[484]

8/27/2018 10:48:36AM Page 5 of7 Analysis Report for 27-Aug-18-10002 B1-09100A-FSFC-001CV 0.0" - 0.5" 0.5ff UNIDENTIFIED PEAKS Peak Locate Performed on  : B/27/2018 10:48:32AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C :\Canberra\Apex\Root\Default\Library\ZI ON LI B-BN L. NLB Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV) An Pk 511. 00 100.00 4.17E-01 2.94E-01 2.94E-01 BE-7 477.60 10.44 -3.45E-02 1 .70E+OO 1.70E+OO K-40 1460.82 10.66 S.25E+OO 4.64E+OO 4.64E+OO Co-60 1173.23 99.85 -7.08E-02 1 .94E-Ol 1 .94E-01 1332.49 99.98 3.37E-02 2.30E-01 Nb-94 702.65 99.81 -2.21E-02 1 .65E-01 1 .65E-01 871.09 99.89 5.0lE-02 1 .97E-01 Ag-108m 79.13 6.60 1 .60E+OO 1 .71E-01 3.36E+OO 433.94 90.50 -9.57E-03 1 . 71E-01 614.28 89.80 -6 .11E-02 2.72E-01 722. 94 90.80 l.93E-01 2.47E-01 Sb-125 176.31 6.84 -4.91E-01 5. 0lE-01 2.17E+OO 380.45 1. 52 -4.09E+OO 1. 04E+Ol 427.87 29.60 -1.25E-01 5.0lE-01 463.36 10.49 -1.0lE-01 1. 33E+OO 600.60 17.65 5.44E-01 1.04E+OO 606 . 71 4.98 -1.44F.-01 6.30E+00 635.95 11. 22 2.97E-01 1.37E+OO 671.44 1. 79 5.60E+OO 1. 11E+Ol [485]

8/27/2018 10:48:36AM Page 6 of7 Analysis Report for 27-Aug-18-10002 B1-091 OOA-FSFC-001CV 0.0" -0.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (keV) (pCilgrams) (pCUgrams) (pCi/grams) Ba-133 79.61 2.65 2.81E+OO 3.14E-01 8.0lE+OO

81. 00 32.90 -1. 52E-01 5.72E-01 276. 40* 7.16 -7.38E-01 1. 83E+OO 302.85 18.34 3.65E-01 8.78E-01 356.01 62.05 7.45E-02 3.14E-01 383.85 8.94 6.73E-01 2.0lE+OO Cs-134 475.36 1. 48 4 .83E+OO 1 . 83E-01 1.16E+Ol 5 63. 25 8.34 -1 .66E+OO l.80E+OO 569.33 15.37 6.18E-02 1.28E+OO 604. 72 97. 62 -1. 5 6E-02 2.67E-Ol 795.86 85.46 -1.55E-02 l.83E-01 801.95 8.69 -1.48E-01 1.88E+OO 1038.61 0.99 2.62E-01 1. 81E+Ol 1167.97 1. 79 1.03E+OO l. 13E+Ol 1365.19 3.02 1 .66E+OO 5.18E+OO

+ Cs-137 661.66

• 85.10 7.00E-02 1 . 66E-01 l.66E-01 Eu-152 121.78 28.67 6.64E-02 4 .32E-01 4.32E-01 244. 70 7.61 -4.53E-Ol 1. 96E+OO 295.94 0.45 1 .73E+Ol 3.91E+Ol 344.28 26.60 9.93E-02 5.63E-Ol 367.79 0.86 -5.70E-01 1 .64E+Ol 411.12 2.24 2.30E+OO 7.85E+OO 443. 96 2.83 -4.85E-01 6.26E+OO 488.68 0.42 -1. 73E+OO 4 .53E+Ol 563.99 0.49 -2.44E+01 3.20E+Ol 586.26 0.46 2.09E+Ol 4.35E+Ol 678.62 0.47 1. llE+Ol 4.16E+Ol 688.67 0.86 9.09E-01 2.21E+Ol 719.35 0.28 -3.41E+Ol 6.37E+Ol 778.90 12.96 1.74E-02 1.49E+OO 810.45 0.32 4.18E+OO 5.67E+Ol 867.37 4. 26 -1.59E+OO 4.19E+OO 919.33 0.43 7.95E+OO 4 .35E+Ol 964. 08 14. 65 1. 61E-01 1. 56E+OO 1085.87 10. 24 -7.44E-01 1.88E+OO 1089.74 1. 73 -4.lSE+OO 1.07E+Ol 1112. 07 13.69 -4.30E-01 1.59E+OO 1212.95 1. 43 9.0lE+OO 1 .67E+01 1249.94 0.19 -2.40E+Ol 1. 21E+02 1299. 14 1. 63 l.82E+OO 1. 0BE+Ol 1408. 01 21. 07 6.08E-01 1.lOE+OO 1457.64 0.50 1.20E+02 9.82E+Ol 1528.10 0.28 1.SBE+Ol 7. llE+Ol Eu-154 123.07 40.40 -1. 29E-Ol 2.88E-01 2.88E-01 247.93 6.89 -8.99E-03 2. llE+OO 591. 7 6 4.95 -9 .13E-01 3.29E+OO 692.42 1. 78 -4.43E+OO 1.00E+Ol 723. 30 20.06 4 . 98E-01 1. 08E+OO 756.80 4.52 -1.85E+OO 3. 72E+OO 873.18 12.08 5.72E-02 1 .64E+OO 996.29 10.48 -3.70E - 03 l.94E+OO

[486]

8/27/2018 10:48:36AM Page 7 of7 Analysis Report for 27-Aug-18-10002 B1-09100A-FSFC-001 CV 0.0" - 0.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCJ/grams) (keV) Eu-154 1004.76 18.01 1.28E-01 2.88E-01 1.31E+OO 1274.43 34.80 -2.39E-01 5.61E-01 1596.48 1. 80 5.93E-01 9.86E+OO Eu-155 45.30 1. 31 -1.20E+OO 5.53E-01 3.14E+Ol 60.01 1. 22 -1.33E+Ol 3.16E+Ol 86.55 30.70 1. 29E-01 5.53E-01 105.31 21.10 -1.43E-02 7.16E-01 Ra-226 186.21 3.64 3.86E+OO 4.34E+OO 4.34E+OO Pa-231 27.36 10.30 1. 43E+OO 3.25E+OO 3.25E+OO 283.69 1. 70 1 .83E+OO 8.62E+OO 300.07 2.47 -7.0lE+OO 6.00E+OO 302.65 2.20 3.04E+OO 7.31E+OO 330.06 1. 40 6.93E+OO 1.20E+Ol U-235 143.76 10.96 -3.02E-01 2 . 72E-Ol 1.16E+OO 163.33 5.08 -9.94E-Ol 3.0BE+OO 185.71 57.20 2.04E-01 2. 72E-01 202 .11 1. 08 -1.0SE+Ol 1. 33E+Ol 205.31 5 .01 5.64E-01 3.21E+OO Am-241 59.54 35.90 -2.12E-01 1.12E+OO 1.12E+OO

   +    = Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
   >    = MDA value not calculated
   @    = Half-life too short to be able to perform the decay correction
   ?    = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[487]

0000049643.CNF Live Time :1200.000 sec 60 Real Tiae :1200.330 sec start: 1: O.l(kev) stop : 4096:2047 .l(kev) Acq. start :Mon AUg 27 10:28:29 2018 55 so 45 40 35 V) .j..l C: 8 30 7 25 ...""

                                ~""

20 15

                                    '"-;'         00 u            ::;-i 10                                            ~

5 500 1000 1500 2000 2500 3000 3500 4000 channel

        ~

ROI Type: 1 [488]

8/27/2018 10:08:57AM Page I of6 Analysis Re port for 27-Aug-18-1 0003 B1-091 OOA-FSFC-010CV 0.0" - 0.5" 0.0" GAMMA SPECTRUM ANALYSIS Sample Identification  : 27-Aug-18-10003 Sample Description  : B1-09100A-FSFC-010CV 0.0" - 0.5" 0.0" Sample Type  : Puck Unit Sample Point Sample Size 1.001 E+02 grams Facility  ; Default Sample Taken On  : 8/22/2018 12:40:00PM Acquisition Started  : 8/27/2018 9:48:50AM Procedure Puck_half_inch Operator jwelch Detector Name  : P40818B Geometry  : Puck_half_inch Live Time . 1200.0 seconds Real Time

• 1200.9 seconds Dead Time
• 0.08 %

Peak Locate Threshold 3.00 Peak Locate Range (in channels) . 120- 8192 u.ir? 11"1 Peak Area Range (in channels) , 120-8192 Identification Energy Tolerance , 1.000 keV Energy Calibration Used Done On Efficiency Calibration Used Done On

12/23/2017

8/27/2018 f 1/v Efficiency Calibration Description DAT,\ VALIDATED Sample Number  : 49640 DATE CJ-2-tB Certificate Name  : Eu155-Na22 TIME 01-l5 Certificate Date  : 1/30/2012 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 10:08:53AM Peak Analysis From Channel  : 120 Peak Analysis To Channel  : 8192

[489]

8/27/2018 10:08:57AM Page 2 of6 Analysis Report for 27-Aug-18-1 0003 B1-09100A-FSFC-01 OCV 0.0" - 0.5" 0.0" Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) 1 609.53 2432 - 2442 2437.27 2.38E+Ol 1 3 .20 1.65E+Ol 0.48 M " First peak in a multiplet region m: other peak in a multiplet region F : Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty Bi-214 0. 99 609.32

• 45.49 4.36E-Ol 2.48E-01 768.36 4. 89 806.18 1. 26 934.06 3. 11 1120.29 14. 92 1155. 21 1. 63 1238 .12 5.83 1280.98 1. 43 1377.67 3.99 1385.31 0 .79 1401 .52 1. 33 1407.99 2.39 1509.21 2.13 1 6 61.27 1. 05 1729.59 2.88 1764.49 15.30 1847.43 2.03 2118.51 1.16

[490]

8/27/2018 10:08:57AM Page 3 of6 Analysis Report for 27-Aug-18-10003 B1-09100A-FSFC-010CV 0.0" - 0.5" 0.0"

      * = Energy line found in the spectrum.
      - = Manually added nuclide.
     ? =Manually edited nuclide.
     @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0 .30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide                            Nuclide                       Wt mean             wt mean     Comments Name                                 Id                          Activity             Activity Confidence                                         Uncertainty (pCilgrams)

Bi-214 0.997 4.36E-01 2.48E-01

       ?   = nuclide is part of an undetennined solution X   = nuclide rejected by the interference analysis
       @   = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma

[491]

8/27/2018 10:08:57AM Page4 of6 Analysis Report for 27-Aug-18-10003 B1-09100A-FSFC-010CV 0.0" - 0.5" 0.0" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 10:08:53AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 8192 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Defa ult\Li brary\ZION LIB-BN L. N LB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi!grams) (pC/lgrams) (pCilgrams) (keV) An Pk 511. 00 100.00 2.66E-01 3.26E-01 3.26E-01 BE-7 477.60 10.44 -2.88E-01 1.80E+OO 1 .80E+OO K-40 1460.82 10.66 5.91E+OO 4.91E+OO 4.91E+OO Co-60 1173.23 99.85 -7.16E-02 1 .66E-01 1.66E-01 1332.49 99.98 7.28E-02 1.98E-01 Nb-94 702.65 99.81 1. 07E-02 1 .88E-01 1.88E-01 871. 09 99.89 l .63E-01 2.33E-01 Ag-108m 79.13 6.60 7.16E-01 1. 85E-01 6.08E+OO 433.94 90.50 -5.89E-02 1. 85E-01 614.28 89.80 -l.82E-01 2.BlE-01 722. 94 90.80 1.03E-01 2.24E-01 Sb-125 176.31 6.84 -1.43E+OO 6 .21E-01 2.43E+OO 380 .45 1. 52 -1.45E+OO 1. 09E+Ol 427.87 29.60 -1.98E-01 6.21E-01 463.36 10.49 5.SlE-02 2.03E+OO 600.60 17.65 -1. 73E-02 l.06E+OO 606.71 4.98 3.29E+OO 5.70E+OO 635.95 11. 22 4.82E-01 1.7DE+OO 671.44 1. 79 -1.46E+Ol 9.08E+OO [492]

8/27/2018 10:08:57AM Page S of6 Analysis Report for 27-Aug-18-10003 B1-09100A-FSFC-010CV 0.0" - 0.5" 0.0" Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCilgrams) (pCl!grams) (pCilgrams) (keV) Ba-133 79.61 2.65 6.57E-02 3.29E-01 1 .45E+Ol

81. 00 32.90 -6.97E-02 1 .05E+OO 276.40 7.16 1.09E+OO 2.53E+OO 302.85 18.34 7.59E-01 1. 06E+OO 356.01 62.05 -3.73E-01 3.29E-01 383.85 8.94 -7.30E-01 1 .80E+OO Cs-134 475.36 1. 48 -3.36E+OO 2 . 49E-01 1 .24E+Ol 563.25 8.34 -5.13E-01 1 .56E+OO 569.33 15 .37 -l.97E-01 9.75E-01 604. 72 97.62 -1. 85E-Ol 2.64E-01 795.86 85.46 1. 08E-01 2.49E-01 801.95 8.69 1.67E-01 2.46E+OO 1038.61 0.99 -1. 55E+01 2.33E+Ol 1167.97 1. 79 -4.92E+OO 9.26E+OO 1365.19 3.02 3.53E-02 7.70E+OO Cs-137 661.66 85.10 4.19E-02 2.49E-01 2.49E-Ol Eu-152 121.78 28.67 -1.39E-01 6.38E-01 6.38E-01 244.70 7.61 -1.34E+OO 2.30E+OO 295.94 0.45 -2.92E+Ol 4.24E+Ol 344.28 26.60 -3.04E-Ol 6.43E-01 367.79 0.86 -3.26E+Ol 1.67E+Ol 411.12 2.24 -8.31E-Ol 8.07E+OO 443. 96 2.83 -2.27E+OO 6.45E+OO 488.68 0.42 -2.81E+Ol 4.60E+Ol 563.99 0.49 -l.08E+Ol 2.64E+Ol 586.26 0.46 2.16E+Ol 4.74E+Ol 678.62 0.47 4.43E+OO 4.35E+Ol 688.67 0.86 1.39E+01 2. 15E+Ol 719. 35 0.28 3.13E+OO 6.83E+Ol 778.90 12. 96 8.82E-02 1. 20E+OO 810.45 0.32 3.53E+01 6.02E+Ol 867.37 4.26 -1.lOE+OO 5.12E+OO 919.33 0.43 5.60E+OO 4.33E+Ol 964.08 14.65 8.19E-01 l. 98E+OO 1085.87 10.24 9.38E-01 2.48E+OO 1089.74 1. 73 2.02E+OO l.47E+Ol 1112. 07 13.69 -4.43E-01 1.76E+OO 1212.95 1. 43 -1.0SE+Ol l.49E+Ol 1249.94 0.19 -2.02E+Ol 1. 33E+02 1299.14 1. 63 6.15E+OO 1. 37E+Ol 1408.01 21.07 -2.31E-01 9.03E-01 1457.64 0.50 1.10E+02 1. 03E+02 1528.10 0.28 -2.00E+Ol 7.24E+Ol Eu-154 123.07 40.40 7.97E-02 4.50E-01 4.SOE-01 247.93 6.89 8.09E-Ol 2.49E+OO S91.'76 4.95 6.90E-01 3.93E+OO 692.42 1. 78 -1.BOE+OO 9. 72E+OO 723. 30 20.06 1. BOE-01 1.0lE+OO 756.80 4.52 1.95E+OO 3.74E+OO 873.18 12.08 8.17E-01 1.93E+OO 996.29 10.48 9.23E-01 2.21E+OO

[493]

8/27/2018 10:08:57AM Page 6 of6 Analysis Report for 27-Aug-18-10003 B1-09100A-FSFC-010CV 0.0" - 0.5" 0.0" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCi!grams) (keV) Eu-154 1004. 76 18 .01 -4.53E-01 4.50E-01 1.51E+OO 1274.43 34.80 -2.73E-01 5.93E-01 1596. 48 1. 80 -5.0SE+OO 1.38E+Ol Eu-155 45.30 1. 31 -2.08E+Ol 8.74E-01 9.61E+Ol

60. 01 1. 22 -1.32E+OO 9.71E+Ol 86.55 30.70 3.02E-01 8.74E-01 105.31 21. 10 -5.95E-01 8.84E-Ol Ra-226 186.21 3.64 5.50E+OO 5.09E+OO 5.09E+OO Pa-231 27.36 10 .30 4.89E+OO 7.SOE+OO 1 .02E+Ol 283.69 1. 70 4.97E+OO 9.90E+OO 300.07 2.47 -3.64E+OO 7.50E+OO 302.65 2.20 5.25E+OO 8.83E+OO 330.06 1. 40 2.78E+OO 1. 33E+Ol U-235 143.76 10 .96 1 .24E+OO 3.22E-01 1 .64E+OO 163.33 5.08 1.88E+OO 3.4 1E+OO 185. 71 57.20 2.21E-01 3.22E-01 202 . 11 1. 08 -8.87E-01 1.60E+01 205.31 5.01 2.62E-01 3.66E+OO Am-241 59.54 35.90 -7.09E-01 3.36E+OO 3.36E+OO

   +    =  Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
   >    = MDA value not calculated
   @    = Half-life too short to be able to perform the decay correction
   ?    = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[494]

0000049640.CNF Live Time :1200.000 sec Real Time :1200. 940 sec 60 Start: 1: -0. O(kev) stop : 8192:2047.4(kev) Acq. Start :Mon Aug 27 09 :48: SO 2018 55 50 45 40 35 U'I C: 8 30 [495] 25 20 15 10 5 1000 2000 3000 4000 5000 6000 7000 8000 channel

             ~

ROI Type: 1

8/27/2018 10:48:44AM Page l of6 Analysis Report for 27-Aug-18-10004 81-091 OOA-FSFC-010CV 0.0" - 0.5" 0.5" GAMMA SPECTRUM ANAL YSJS Sample Identification  : 27-Aug-18-10004 Sample Description  : B1-09100A-FSFC-010CV 0.0" - 0.5" 0.5" Sample Type  : Puck Unit Sample Point Sample Size 1.001 E+02 grams Facility  : Default Sample Taken On  : 8/22/2018 12:40:00PM Acquisition Started  : 8/27/2018 10:28:35AM Procedure  : Puck_half_inch Operator  : jwelch Detector Name  : P408188 Geometry  : Puck_half_inch Live Time  : 1200.0 seconds Real Time  : 1200.9 seconds Dead Time  : 0.07 % Peak Locate Threshold  : 3.00 Peak Locate Range (in channels}  : 120 -8192 Peak Area Range (in channels}  : 120 - 8192

                                                                                                   /,,II Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On

1.000 keV

12/23/2017

                                             ~  8/27/2018 f         (/1,-?Ar' Efficiency Calibration Description DATA VALIDATED Sample Number                                : 49644                                      DATE q-2-rr Certificate Name                             : Eu 155-Na22                                TIME.~07 * ~-c.--

Certificate Date  : 1/30/2012 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 10:48:40AM Peak Analysis From Channel  : 120 Peak Analysis To Channel  : 8192 [496]

8/27/2018 10:48:44AM Page 2 of6 Analysis Report for 27-Aug-18-10004 B1-09100A-FSFC-010CV 0 .0" - 0.5" 0.5" Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) 1 238.60 949 - 959 954 . 49 4.30E+Ol 20.20 4.80E+Ol 0 . 97 2 351.92 1401 - 1412 1407 . 40 3.09E+Ol 17. 57 3.62E+Ol 0 .58 3 1460.92 5837 - 5851 5843.53 3.53E+Ol 13. 59 7.50E+OO 0.51 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K-40 0 .99 1460.82

• 10 .66 5 .21E+OO 2 .06E+OO Bi-211 0 .89 351. 07
• 13. 02 1. 30E+OO 7 .69E-01 Pb-212 1. 00 1 15.18 0 .60 238.63
• 43.60 4 . llE-01 2 .04E-01 300.09 3.30 Pb-214 1. 00 241.99 7.25 2 95. 22 18.42 35 1 .93
• 35.60 4 .7 6E-0 1 2 .81E-01 785.96 1. 06

[497]

8/27/2018 10:48:44AM Page 3 of6 Analysis Report for 27-Aug-18-10004 B1-09100A-FSFC-010CV 0.0" - 0.5" 0.5"

      * = Energy line found in the spectrum.
      - = Manually added nuclide.
     ? = Manually edited nuclide.
     @ = Energy line not used for Weighted Mean Activity Energy Tolerance: 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide                            Nuclide                       wt mean              wt mean     Comments Name                                 Id                           Activity             Activity Confidence                                          Uncertainty (pCilgrams)

K-40 0.998 5.21E+OO 2.06E+OO

     ?       Bi-211                              0.892                     1.30E+OO              7.69E-01 Pb-212                              1.000                     4. llE-01             2.04E-D1
     ?       Pb-214                              1.000                     4.76E-01              2.81E-01
       ?   = 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 2.000sigma

[498]

8/27/2018 10:48:44AM Page 4 of6 Analysis Report for 27-Aug-18-10004 B1-09100A-FSFC-010CV 0.0" - O.SR 0.5" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 10:48:39AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 8192 Peak CPS {°/o) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZI ON LIB-BN L. NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCi/grams) (pCi/grams) (keV) An Pk 511. 00 100.00 2.59E-01 3.00E-01 3.00E-01 BE-7 477.60 10.44 3.47E-Ol 1.52E+OO 1. 52E+OO + K-40 1460.82

• 10.66 5.21E+OO 2.08E+OO 2.08E+OO Co-60 1173.23 99.85 4.99E-02 2.52E-01 2.94E-01 1332.49 99.98 -5.58E-02 2.52E-01 Nb-94 702.65 99.81 -3.61E-02 1. 88E-01 1. 8 8E-01 871. 09 99.89 9.18E-02 2.19E-01 Ag-108m 79.13 6.60 -7.02E-01 1.92E-01 5.46E+OO 433.94 90.50 -4.09E-02 1.92E-01 614.28 89.80 -8.66E-02 3.07E-01 722. 94 90.80 -3.73E-02 2.36E-01 Sb-125 176.31 6.84 -8.52E-01 6.llE-01 2.19E+OO 380.45 1. 52 8.45E+OO l. 19E+Ol 427.87 29.60 1. 38E-01 6. llE-01 4 63. 36 10.49 4.12E-01 l. 95E+OO 600.60 17.65 1.04E-02 l.06E+OO 606.71 4.98 4.12E+D0 6.06E+OO 635.95 11 .22 -1.SlE-01 1. 56E+OO 671. 44 1. 79 3.65E+D0 l.14E+Ol

[499]

8/27/2018 10:48:44AM Page 5 of6 Analysis Report for 27-Aug-18-10004 B1-091OOA-FSFC-01 OCV 0.0" - 0.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCi/grams) (pCl/grams) (keV) Ba-133 79.61 2 . 65 -1. 29E+01 3.55E-01 1. 29E+Ol 81.00 32.90 -4.72E-01 9.92E-01 276.40 7.16 3.66E-01 2.36E+OO 302.85 18.34 2.72E-02 9.34E-01 356.01 62.05 -1. 46E-01 3.55E-01 383.85 8.94 6.05E-Ol l. 70E+OO Cs-134 475.36 1. 48 -2.82E+OO l.75E-01 1. OlE+Ol 563.25 8.34 1.27E+OO 2.64E+OO 569.33 15 .37 4.52E-01 l.34E+OO 604.72 97. 62 -1.07E-01 2. 71E-01 795.86 85.46 -2.49E-03 1. 7 5E-01 801.95 8.69 -6.42E-01 1.94E+OO 1038.61 0 .99 -6.72E-01 2.42E+Ol 1167.97 1. 79 1.79E+OO 1.64E+Ol 1365. 19 3.02 1.48E+OO 5.53E+OO Cs-137 661. 66 85 .10 9.32E-02 2. llE-01 2. llE-01 Eu-152 121. 78 28.67 -1.85E-01 5.57E-01 5.57E-Ol 244.70 7.61 -7.66E-01 2.33E+OO 295.94 0 .45 1 .87E+OO 4.34E+Ol 344.28 26.60 -6 .51E-01 6.18E-01 367.79 0 .86 -7.57E+OO 1. 71 E+Ol 411. 12 2.24 -3.67E+OO 7.83E+OO 443. 96 2.83 -2.18E+OO 6.24E+OO 488.68 0.42 3.00E+OO 3.81E+01 563.99 0.49 4.74E+OO 4.39E+01 586.26 0.46 1.90E+Ol 4.30E+Ol 678.62 0.47 -3.59E+Ol 3.61E+Ol 688.67 0.86 -2.22E+Ol 1. 45E+Ol 719. 35 0.28 4.76E+Ol 8.05E+Ol 77 8. 90 12. 96 -4.85E-01 l .20E+OO 810 .45 0.32 1.82E+Ol 6.25E+Ol 867.37 4.26 -2.28E+OO 3.95E+OO 919.33 0.43 2.99E+OO 4.95E+Ol 964.08 14.65 -1.05E+OO l.75E+OO 1085.87 10.24 -6.16E-02 l.80E+OO 1089.74 1. 73 -5.28E-Ol l.26E+Ol 1112. 07 13.69 -7.70E-Ol 1 .62E+OO 1212.95 1. 43 3.14E+OO 1 .79E+Ol 1249.94 0.19 8.82E+Ol 1. 43E+D2 1299. 14 1. 63 -4.40E-01 1 .65E+Ol 1408. 01 21. 07 -7.85E-02 8.lOE-01 1 457.64 0.50 7.41E+Ol l .07E+02 1528.10 0.28 -9.44E+OO 7.24E+Ol Eu-154 123.07 40.40 1. 91E-02 4 .0lE-01 4 . 0lE-01 247.93 6.89 3.69E-01 2.49E+OO 591. 76 4.95 1. 23E+OO 3.55E+OO 6~2.42 1. 78 -1.41E+OO 1.0 l E+Ol 723. 30 20.06 -1. 35E-01 l. lO E+OO 756.80 4 .52 -l.68E+OO 4.07E+OO 873.18 12.08 7.79E-01 l. 87E+OO 996.29 10 .48 -1.14E+OO 1. 77E+OO [500]

8/27/2018 10:48:44AM Page 6 of6 Analysis Report for 27-Aug-18-1 0004 B1-09100A-FSFC-010CV 0.0"

• 0.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCVgrams) (pCl/grams) (pCi/grams)

(keV) Eu-154 1004.76 18. 01 6.65E-01 4.0lE-01 1. 20E+OO 1274.43 34.80 5.06E-02 8.44E-01 1596.48 1. 80 5.68E+OO 1.38E+Ol Eu-155 45.30 1. 31 1.20E+Ol 8.05E-01 8.44E+Ol 60.01 1. 22 7.59E+OO 9.08E+Ol 86.55 30.70 -5.94E-Ol 8.0SE-01 105.31 21.10 3.33E-01 9.12E-01 Ra-226 186.21 3.64 2.19E+OO 4.87E+OO 4.87E+OO Pa-231 27.36 10.30 5.61E+OO 7.09E+OO 1. 08E+01 283.69 1. 70 -l.80E+OO 9.30E+OO 300.07 2.47 -2.41E+OO 7.09E+OO 302.65 2 .. 20 3.00E-01 7.69E+OO 330.06 1. 40 -1.93E+OO 1. 38E+Ol U-235 143.76 10 .96 3 .13E-01 3.19E-01 1. 65E+OO 163.33 5.08 -4.04E-01 3.20E+OO 185.71 57.20 3.04E-01 3.19E-01 202 . 11 1. 08 -1.43E+Ol 1.40E+Ol 205.31 5.01 2.17E-01 3.31E+OO Am-241 59.54 35.90 4.45E-01 3.23E+OO 3.23E+OO

    +   = Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
    >   = MDA value not calculated
   @    = Half-life too short to be able to perform the decay correction
    ?   = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[501]

0000049644.CNF Live rim, :1200.000 sec Real Ti111.e :1200.870 sec 60 start: 1: -0. O(kev) stop : 8192: 2047 .4(kev) Acq. Start :Mon Aug 27 10:28:3S 2018 55 50 45 40 35 Vl +-' C

J 8 30 25 20

                  ....;:j 15              ~      ~m rn 5

1000 2000 3000 4000 5000 6000 7000 8000 channel

      ~

ROI Type: 1 [502]

8/27/2018 10:09:14AM Page 1 of6 -=-~-~-*~pex-Gamma Analysis Report for 27-Aug-18-10005 B1-09100A-FSFC-021CV 0.0" - 0.5" 0.0" GAMMA SPECTRUM ANALYSIS Sample Identification 27-Aug-18-10005 Sample Description

• B1-09100A-FSFC-021CV 0.0" - 0.5" 0.0" Sample Type
• Puck Unit Sample Point Sample Size 1.171 E+02 grams Facility Default Sample Taken On
• 8/22/2018 12:59:00PM Acquisition Started
• 8/27/2018 9:48:56AM Procedure
• Puck_half_inch Operator
• jwelch Detector Name
• P11314 Geometry
• Puck_half_inch Live Time
• 1200.0 seconds Real Time
• 1200.3 seconds j)/

Dead Time

• 0.02%

Peak Locate Threshold

• 3.00 Peak Locate Range (in channels)

Peak Area Range (in channels) Identification Energy Tolerance 120- 8192 120- 8192 1.000 keV

                                                                                               ~-r r(lY~,i Energy Calibration Used Done On

• 12/15/2017 Efficiency Calibration Used Done On  ; 8/27/2018 DATA VALIDATED Efficiency Calibration Description DATE 9-Z-lk Sample Number  : 49641 TIME 0 ~ ,

Certificate Name Certificate Date

Eu155-Na22

12/22/2008 12:00:00PM

                                                                                      µlytpe.0JL=?;f./VJ PEAK ANALYSIS REPORT Peak Analysis Performed on         : 8/27/2018 10:09:06AM Peak Analysis From Channel        : 120 Peak Analysis To Channel          : 8192

[503]

8/27/2018 10:09:14AM Page 2 of6 Analysis Report for 27-Aug-18-10005 B1-09100A-FSFC-021CV 0.0"-0.5" 0.0" Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) 1 1460.58 5834 - 584 8 5840.24 4.17E+Ol 15.07 1. 06E+Ol 0.39 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi!grams) Uncertainty K-40 0.99 1460.82

• 10.66 4.91E+OO l.82E+OO

    * = Energy line found in the spectrum.
    - = Manually added nuclide.
    ? = Manually edited nuclide.
    @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma

[504]

8/27/2018 10:09:14AM Page 3 of6 Analysis Report for 27-Aug-18-10005 B1-09100A-FSFC-021CV 0.0" - 0.5" 0.0" INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0.990 4.91E+OO 1. 82E+OO

       ?  = 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 2.000sigma

[505]

B/27/201B 10:09:14AM Page4 of6 Analysis Report for 27-Aug-1B-10005 B1-09100A-FSFC-021CV 0.0" - 0.5" 0.0" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 10:09:06AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 8192 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCilgrams) (keV) An Pk 511. 00 100.00 1 .36E-01 2.14E-01 2.14E-01 BE-7 477.60 10.44 -4.22E-02 1 .27E+OO 1. 27E+OO + K-40 1460.82

• 10.66 4.91E+DO 1. 89E+OO 1.89E+OO Co-60 1173.23 99.85 5.31E-02 1.44E-01 1. 44E-Ol 1332.49 99.98 6.41E-02 2 . 18E-01 Nb-94 702.65 99.81 2.44E-02 1. 68E-01 1 . 72E-01 871.09 99.89 1.51E-02 l.68E-01 Ag-108m 79.13 6.60 7.32E-01 l .34E-01 2.37E+OO 433.94 90.50 -2.22E-02 1. 34E-Ol 614.28 89.80 -7.76E-02 1. 85E-Ol 722. 94 90.80 -4.93E-02 l. 37E-Ol Sb-125 176.31 6.84 5.71E-02 3.34E-01 9.47E-01 380.45 1. 52 -l.76E+OO 6.55E+OO 427.87 29.60 -9.43E-02 3.34E-01 463.36 10.49 3.57E-01 1.25E+OO 600.60 17.65 -3.74E-02 7.78E-01 606. 71 4.98 2.37E-01 3. lOE*I 00 635.95 11.22 l.84E-01 6.86E-01 671. 44 1. 79 -4.63E+OO 6.91E+OO

[506]

8/27/2018 10:09:14AM Page 5 of6 Analysis Report for 27-Aug-18-10005 B1-091 OOA-FSFC-021 CV 0.0" - 0.5" 0.0" Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCi/grams) (pCi/grams) (pCi!grams) (keV) Ba-133 79.61 2.65 -5.37E-01 l. 64E-01 5.55E+OO

81. 00 32.90 -3.31E-01 3.73E-Ol 276.40 7. 16 -4.47E-01 1 .33E+OO 302.85 18.34 -1.00E-01 4.79E-01 356.01 62.05 -2.03E-01 1. 64E-01 383.85 8.94 4.20E-01 1 .12E+OO Cs-134 475.36 1. 48 -2.38E+OO l. 42E-01 8.67E+OO 563.25 8.34 4.71E-03 l .66E+OO 569.33 15.37 3.04E-01 8.84E-01 604. 72 97. 62 -1. 86E-01 1 .42E-01 795.86 85.46 -1.33E-01 1. 78E-01 801.95 8.69 5.68E-01 1 .76E+OO 1038.61 0. 99 -3.22E+OO 1 .63E+Ol 1167.97 1. 79 -8.lOE+OO 9.22E+OO 1365.19 3.02 -5.37E+OO 4.91E+OO Cs-137 661.66 85.10 2.40E-01 2.88E-01 2.88E-01 Eu-152 121. 7 8 28.67 9.62E-02 2. 72E-01 2. 72E-01 244.70 7.61 6.65E-02 l .30E+OO 295.94 0.45 6.81E+OO 2.73E+Ol 344.28 26.60 1. 81E-01 3.82E-01 367.79 0.86 -3.26E+OO 1 .18E+Ol 411.12 2.24 -1. 86E+OO 4.97E+OO 443. 96 2.83 -4.05E+OO 3. 71E+OO 488.68 0.42 -1.60E+Ol 3.46E+Ol 563.99 0.49 4.05E+OO 2.89E+Ol 586.26 0.46 -7.24E+OO 2.64E+Ol 678.62 0.47 -1.36E+Ol 2.23E+Ol 688.67 0.86 -6.74E-01 1.59E+Ol 719.35 0.28 2.42E+Ol 4.65E+Ol 778.90 12. 96 -1.58E-01 1.24E+OO 810.45 0.32 2.30E+Ol 4.41E+Ol 867.37 4.26 -3.69E+OO 3.49E+OO 919.33 0.43 1. 57E+OO 4.09E+Ol 964.08 14.65 8.09E-02 1.09E+OO 1085.87 10.24 -4.66E-01 1. 53E*l*OO 1089.74 1. 73 1. 06E+OO 9.07E+OO 1112. 07 13.69 3.73E-02 1 .02E+OO 1212.95 1. 43 5.32E+OO 1. 18E+Ol 1249.94 0.19 2.34E+Ol 7.31E+Ol 1299.14 1. 63 -1 .88E+OO 8.74E+OO 1408.01 21. 07 2.31E-Ol 7.20E-01 1457.64 0.50 1 .32E+02 9.42E+Ol 1528.10 0.28 1 .39E+Ol 5.18E+Ol Eu-154 123.07 40.40 -3.52E-02 1. 81E-01 l. 81E-01 247.93 6.89 4 .14E-01 1. 35E+OO 591. 76 4 .95 1 .38E+OO 2.74E+OO 692.42 1. 78 -4.04E+OO 7. llE+OO 723. 30 20.06 -2.42E-01 6.19E-01 756.80 4 .52 -1.08E-01 2.lSE+OO 873.18 12.08 4.43E-01 1.44E+OO 996. 2 9 10.48 -3.62E-01 1.%E+OO

[507]

8/27/2018 10:09:14AM Page 6 of6 Analysis Report for 27-Aug-18-10005 81-091 OOA-FSFC-021 CV 0.0" -0.5" 0.0" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCl/grams) (pCilgrams) (pCilgrams) (keV) Eu-154 1004.76 18.01 2.52E-01 1. BlE-01 9.lSE-01 1274.43 34.80 -8.53E-02 5.03E-01 1596. 48 1. 80 3.77E+OO 1.03E+Ol Eu-155 45.30 1. 31 -1. 70E+Ol 4.42E-01 2.25E+Ol

60. 01 1. 22 7. 72E+OO 2.41E+Ol 86.55 30.70 3.68E-02 4.42E-01 105.31 21.10 2.91E-02 4.66E-01 Ra-226 186.21 3.64 3.65E-01 2.74E+OO 2.74E+OO Pa-231 27.36 10.30 1. 82E+OO 3.37E+OO 3.37E+OO 283.69 1. 70 -4. 72E+OO 4.52E+OO 300.07 2.47 -3.87E+OO 3.87E+0'.)

302.65 2.20 -2.92E+OO 3.89E+OO 330.06 1. 40 -4.94E-01 8.07E+OO U-235 143.76 10. 96 2. 71E-01 1. 79E-01 7.43E-01 163.33 5.08 1 .05E-Ol 1.45E+OO 185.71 57.20 5.25E-02 1.79E-01 202 .11 1. 08 -3.03E+OO 6.56E+OO 205.31 5.01 -6.17E-01 1.52E+OO Am-241 59.54 35.90 3.29E-02 8. 17E-01 8.17E-01

   +    = Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
   >    = MDA value not calculated
   @    = Half-life too short to be able to perform the decay correction
   ?    = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[508]

0000049641.CNF Live Time :1200.000 sec 60 Real rime :1200.290 sec start: 1: -0.0(kev) stop : 8192 :2047. 8(kev) Acq. start :Mon Aug 27 09: 48: 56 2018 55 so 45 40 35 Vl .j..,I C

ll 8 30 25 20 15 10 5

1000 2000 3000 4000 5000 6000 7000 8000 channel

         ~

ROI Type: 1 [509]

8/27/2018 10:48:51AM Page I of6 -=-= ~pex-Gamma Analysis Report for 27-Aug-18-10006 B1-09100A-FSFC-021CV 0.0" - 0.5" 0.5" GAMMA SPECTRUM ANAL YSJS Sample Identification  : 27-Aug-18-10006 Sample Description  : B1-09100A-FSFC-021CV 0.0" - 0.5" 0.5" Sample Type  : Puck Unit Sample Point Sample Size 1.171 E+02 grams Facility  ; Default Sample Taken On  ; 8/22/2018 12:59:00PM Acquisition Started  ; 8/27/2018 10:28:41AM Procedure

• Puck_half_inch Operator
• jwelch Detector Name . P11314 Geometry
• Puck_half_inch Live Time
• 1200.0 seconds Real Time  : 1200.3 seconds Dead Time  : 0.03%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 120- 8192 Peak Area Range (in channels)  : 120 - 8192 Identification Energy Tolerance Energy Calibration Used Done On

                                              ~ 1.000 keV
                                              , 12/15/2017 j/.d Efficiency Calibration Used Done On Efficiency Calibration Description
                                              ; 8/27/2018 DATAVAL~if Sample Number                                : 49645 Certificate Name                             : Eu155-Na22 Certificate Date                             : 12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on         : 8/27/2018 10:48:48AM Peak Analysis From Channel        : 120 Peak Analysis To Channel          : 8192

[510]

8/27/2018 10:48:51AM Page 2 of6 Analysis Report for 27-Aug-18-10006 B1-09100A-FSFC-021CV 0.0" - 0.5" 0.5" No peak analysis results available for reporting purposes. No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty

     * = Energy line found in the spectrum.
     - = Manually added nuclide.
     ? = Manually edited nuclide.
     @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide                           Nuclide                        Wt mean                 Wt mean     Comments Name                                 Id                            Activity               Activity Confidence                                              Uncertainty (pCilgrams)

[511]

8/27/2018 10:48:51AM Page3 of6 Analysis Report for 27-Aug-18-10006 B1-09100A-FSFC-021CV 0.0" - 0.5" 0.5"

       ?  = 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 2.000sigma

[512]

8/27/2018 10:48:51AM Page 4 of6 Analysis Report for 27-Aug-18-1 0006 B1-09100A-FSFC-021CV 0.0" - 0.5" 0.5" No peak search results available for nuclide analysis. NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCUgrams) (pCi/grams)

                          * (keV)

An Pk 511. 00 100.00 2.30E-01 2.19E-01 2.19E-01 BE-7 477.60 10. 44 -4 .97E-02 1.13E+OO 1 .13E+OO K-40 1460.82 10. 66 4.79E+OO 4.21E+OO 4.21E+OO Co-60 1173.23 99.85 -2.12E-02 1.70E-01 1.75E-01 1332.49 99.98 -4.40E-02 1.70E-0 1 Nb-94 702.65 99.81 4.20E-02 1 .34E-01 1.34E-01 871.09 99.89 5.55E-02 1.62E-01 Ag-108m 79 .13 6.60 5.68E-01 1 .31E-01 2.50E+OO 433.94 90.50 -1.59E-02 1.31E-01 614.28 89.80 -2.84E-01 1. 96E-01 722.94 90.80 -1.02E-01 1.67E-01 Sb-125 176.31 6.84 -2.84E-01 4.85E-01 1. llE+OO 380.45 1. 52 -5.68E+OO 6.55E+OO 427.87 29.60 1. 85E-01 4.85E-01 463.36 10. 49 -2.57E-02 1.17E+OO 600.60 17. 65 -1. 87E-02 8.68E-01 606. 71 4.98 3.63E+OO 4.43E+OO 635.95 11. 22 -1.24E+OO 8.35E-01 671. 44 1. 79 8 . 37E-01 7.52E+OO Ba-133 79.61 2.65 2.lBE+OO 2.24E-01 6.06E+OO

81. 00 32 .90 -7.22E-01 3.67E-01 276.40 7.16 6.34E-01 l.31E+OO 302.85 18.34 5.33E-01 5.98E-01 356.01 62.05 -2.83E-02 2.24E-01 383.85 8.94 2.84E-01 1.21E+OO Cs-134 475.36 1. 48 3.90E-01 1. 78E-01 8.46E+OO 563.25 8.34 -1.07E+OO 1. 75E+OO 569.33 15.37 3.80E-01 1. 07E+OO 604.72 97.62 -1. 61E-01 1.98E-01 795.86 85.46 7.12E-03 1.78E-01 801.95 8.69 4.23E-02 1.70E+OO 1038.61 0.99 -7.82E+OO 1.63E+01 1167.97 1. 79 5.92E+OO 1. 07E+Ol 1365.19 3.02 -l.12E+OO 4.41E+OO

[513]

8/27/2018 10:48:51AM Page 5 of6 Analysis Report for 27-Aug-18-10006 B1-09100A-FSFC-021CV 0.0" - 0.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCUgrams) (pCilgrams) (pCilgrams) (keV) Cs-137 661.66 85.10 1. 54E-01 2.53E-01 2.53E-01 Eu-152 121.78 28.67 -3.17E-02 2.38E-01 2.38E-01 244.70 7.61 5.76E-Ol 1. 32E+OO 295.94 0.45 -1 .70E-01 2.66E+Ol 344.28 26.60 -7.36E-02 3.13E-01 367.79 0.86 4.94E+OO 1. 05E+Ol 411.12 2.24 -9.97E-02 4.12E+OO 443.96 2.83 -1 .lOE-01 3.95E+OO 488.68 0 .42 -6.31E+OO 2.31E+Ol 563.99 0.49 -4.74E+OO 3.04E+Ol 586.26 0.46 2.09E+Ol 3.56E+Ol 678.62 0.47 6.23E+OO 2.98E+Ol 688.67 0.86 1. 06E+OO 1 .59E+Ol 719. 35 0.28 -1.35E+Ol 5.06E+Ol 778.90 12.96 3.69E-Ol 8.98E-01 810.45 0.32 4.47E+OO 4.98E+Ol 867.37 4.26 1.00E+OO 4.46E+D0 919.33 0.43 8.51E+OO 3.62E+D1 964.08 14. 65 -8.77E-01 1.14E+OO 1085.87 10. 24 5.62E-01 1.84E+OO 1089.74 1. 73 4.19E-01 9.58E+OO 1112. 07 13.69 3.73E-01 1. 02E+OO 1212.95 1. 43 3.46E+OO 1.43E+Ol 1249.94 0. 19 -2.69E+OO 8.57E+Ol 1299.14 1. 63 5.84E-02 l.02E+Ol 1408.01 21. 07 -2.21E-01 6.46E-01 1457.64 0.50 1. 20E+02 9.00E+Ol 1528.10 0.28 1. 39E+Ol 5.18E+Ol Eu-154 123.07 40.40 8.39E-02 1.65E-01 1.65E-01 247.93 6.89 2.72E-01 1.28E+OO 591. 76 4.95 -3.99E-02 2.74E+OO 692.42 1. 78 2.25E+OO 7.73E+OO 723.30 20.06 -4.20E-02 8.07E-01 756. 80 4.52 8.48E-Ol 2.98E+OO 873.18 12.08 6.44E-Ol 1. 24E+OO 996.29 10.48 -5.66E-01 1. 32E+OO 1004.76 18.01 3.76E-02 1. 03E+OO 1274.43 34.80 2.56E-01 6.29E-01 1596. 48 1. 80 -4.95E+OO 9.41E+D0 Eu-155 45.30 1. 31 -7.62E+OO 4.00E-01 2.39E+Ol 60.01 1. 22 8.43E+OO 2.29E+Ol 86.55 30.70 -l .86E-01 4.00E-01 105.31 21.10 -5.76E-02 4.20E-01 Ra-226 186.21 3.64 2.30E+OO 2.77E+OO 2.77E+OO Pa-231 27.36 10.30 1. 96E+OO 3.08E+D0 3.08E+OO 283.69 1. 70 1.68E+OO 4.66E+OO 300.07 2.47 -5.23E-D1 4.47E+OO 302.65 2.20 2.45E+OO 4.90E+OO 330.06 1. 40 2.79E+OO 7.79E+OO U-235 143.76 10. 96 1 .91E-01 1. 74E-01 8.42E-01 163.33 5.08 3.14E-01 1.55E+OO [514]

8/27/2018 10:48:51AM Page 6 of6 Analysis Report for 27-Aug-18-10006 B1-09100A-FSFC-021CV 0.0" - 0.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV) U-235 185.71 57.20 l.57E-01 1.74E-01 1 .74E-01 202 .11 1. 08 l.96E+OO 8.lOE+OO 205.31 5.01 -5.59E-01 1 .74E+OO Am-241 59.54 35.90 3.38E-01 7.75E-01 7.75E-01

   +    = Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
   >    = MDA value not calculated
   @    = Half-life too short to be able to perform the decay correction
   ?    = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[515]

0000049645 .CNF Live Time 1200.000 sec 60 Real Ti111e 1200.320 sec start: 1 -0. O(kev) Stop : 8192 2047 .S(kev) Acq. start Mon Aug 27 10:28:41 2018 55 50 40 35 Vl -1 C:

s 8 30 25 20 15 10 5

1000 2000 3000 4000 5000 6000 7000 8000 [516] channel

8/27/2018 1 :04:33PM Page 1 of6

            -~pex-Gamma Analysis Report for       27-Aug-18-10007 B1-09100A-FSWC-031CV        0.0" -0.5" 0.0" GAMMA SPECTRUM ANAL YS/S Sample    Identification                       : 27-Aug-18-10007 Sample    Description                          : B1-09100A-FSWC-031CV 0.0" - 0.5"   0.0" Sample    Type                                 : Puck Unit Sample    Point Sample Size                                       1.205E+02 grams Facility                                       : Default Sample Taken On                                : 8/22/2018 1:30:00PM Acquisition Started                           : 8/27/2018 9:49:03AM Procedure

• Puck_half_inch Operator  : jwelch Detector Name  : 352 Geometry  : Puck_half_inch Live Time . 1200.0 seconds Real Time . 1200.2 seconds Dead Time 0.02 %

Peak Locate Threshold 3.00 Peak Locate Range (in channels) 120 - 8192 Peak Area Range (in channels) 120 - 8192 Identification Energy Tolerance 1.000 keV Energy Calibration Used Done On

• 3/12/2018 Efficiency Calibration Used Done On  : 8/27/2018 Efficiency Calibration Description
• install Sample Number 49642 Certificate Name  : Eu155-Na22 Certificate Date  : 117/2013 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Peifo;med on  : 8/27/2018 10:09:06AM uATA VAUDATED Peak Analysis From Channel Peak Analysis To Channel

120

8192 DATE cr-2-1r TIME 6;2~

[517]

                                                                         £t7~~

8/27/2018 1:04:33PM Page 2 of6 Analysis Report for 27-Aug-18-10007 B 1-091 OOA-FSWC-031 CV 0.0" - 0.5" 0.0" Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) 1 185.80 739 - 750 743.93 2.09E+Ol 16.05 3.43E+Ol 0.96 2 238.72 950 - 961 955.34 2.83E+Ol 18.56 4.35E+Ol 0.78 3 352.07 1400 - 1414 1408 .28 3.65E+Ol 15.24 1.SOE+Ol 0.92 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZtON LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi!grams) Uncertainty Pb-212 0.99 115.18 0.60 238.63

• 43.60 2.14E-01 1 .45E-Ol 300.09 3.30 Pb-214 0.99 241.99 7.25 295.22 18.42 351.93
• 35.60 4 .46E-01 2.00E-01 785.96 1. 06 Ra-226 0.97 186.21
• 3.64 1.63E+OO 1 .28E+OO U-235 0.99 143.76 10. 96 163.33 5.08 185. 71
• 57.20 1.04E-01 8.16E-02 202 .11 1. 08 205.31 5.01

[518]

8/27/2018 1:04:33PM Page 3 of6 Analysis Report for 27-Aug-1 8-10007 B1-091 OOA-FSWC-031 CV 0.0" - 0.5" 0.0"

     * = Energy line found in the spectrum.
     - = Manually added nuclide.
     ? = Manually edited nuclide.
     @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide                             Nuclide                        Wt mean                 Wt mean     Comments Name                                  Id                            Activity                Activity Confidence                                              Uncertainty (pCi/grams)

Pb-212 0 .999 2.14E-01 1.45E-01 Pb-214 0 .998 4.46E-01 2.00E-01

     ?       Ra-226                              0 .974                     1.63E+OO                 1.28E+OO u-~                                  0 .9~                      1.0~1                    8.16~
     ?
                          '--~l-,"
       ?   = 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 2.000sigma #,-~-ff [519]

8/27/2018 1:04:33PM Page 4 of6 Analysis Report for 27-Aug-18-1 0007 B1-09100A-FSWC-031CV 0.0" -0.5" 0.0" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 10:09:0SAM Peak Locate From Channel  : 120 Peak Locate To Channel  : 8192 Peak CPS {°A>) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCUgrams) (pCi/grams) (keV) An Pk 511.00 100.00 1.80E-01 2.15E-01 2.15E-01 BE-7 477.60 10.44 -2.08E-01 1. 09E+OO 1. 09E+OO K-40 1460.82 10.66 3.47E+OO 3.68E+OO 3.68E+OO Co-60 1173.23 99.85 -7.35E-02 1. 75E-01 1 .93E-01 1332.49 99.98 -2.52E-02 1 .75E-01 Nb-94 702.65 99.81 3.35E-02 1. 45E-01 1.77E-01 871. 09 99.89 7.56E-02 l.45E-01 Ag-108m 79 .13 6.60 -1.80E+OO 1.46E-01 3.0lE+OO 433.94 90.50 -3.52E-02 1. 46E-01 614.28 89.80 4.29E-02 2.58E-01 722. 94 90.80 8.48E-03 l.89E-01 Sb-125 176.31 6.84 -5. 96E-02 4. 91E-01 1.34E+OO 380.45 1. 52 6.42E+OO 7.60E+OO 427.87 29.60 1 . 63E-01 4.91E-Ol 463.36 10.49 5.65E-01 l .30E+OO 600.60 17.65 8.80E-02 9.36E-01 606.71 4.98 3.82E+OO 4.80E+OO 635.95 11.22 7.21E-01 1. 37E+O 0 671. 44 1. 79 -4.0lE+OO 9.l~E+OO [520]

8/27/2018 1:04:33PM Page 5 of6 Analysis Report for 27-Aug-18-10007 B1-091 OOA-FSWC-031 CV 0 .0" - 0.5" 0.0" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV) Ba-133 79.61 2.65 4.65E+OO 2.77E-01 7.83E+OO

81. 00 32.90 -1.29E-01 5 . 65E-01 276. 40 7.16 -1.02E-Ol 1 . 56E+OO 302.85 18 .34 -6.24E-01 6 . 40E-Ol 356. 01 62.05 -1.37E-02 2.77E-Ol 383.85 8.94 -3.50E-01 l .30E+OO Cs-134 475.36 1. 48 -2.75E+OO 2 . 05E-01 7.24E+OO 563.25 8.34 -l.25E-01 1 .50E+OO 569.33 15.37 3.96E-02 9.24E-01 604. 72 97.62 8.lOE-02 2.25E-01 795.86 85. 46 -1 .21E-01 2.0SE-01 801.95 8.69 9.30E-01 2.02E+OO 1038.61 0. 99 2.46E+OO 1.58E+Ol 1167.97 1. 79 1. 37E+OO 1. 08E+Ol 1365.19 3.02 -2.58E-01 5.93E+OO Cs-137 661.66 85.10 2.45E-01 2.59E-01 2.59E-Ol Eu-152 121.78 28.67 5.66E-02 3.35E-01 3.35E-01 244.70 7.61 -3.08E-01 l.67E+OO 295.94 0.45 2.97E+Ol 3.44E+Ol 344.28 26.60 -6.63E-02 4.48E-01 367.79 0.86 4.88E+OO 1 .35E+Ol 411. 12 2.24 -l. 83E+OO 4.84E+OO 443. 96 2.83 -2.61E+OO 3.94E+OO 488.68 0.42 -5.97E+OO 2.93E+Ol 563.99 0.49 4.74E+OO 2.63E+01 586.26 0.46 9.66E+OO 4.lOE+Ol 678.62 0.47 2.55E+01 3.40E+01 688.67 0.86 6.33E+OO 1 .62E+01 719.35 0.28 1.25E+D1 5.83E+01 778.90 12.96 -1.31E-01 1 .13E+OO 810 .45 0.32 5.60E+OO 5.19E+01 867.37 4.26 2.36E+OO 3.83E+OO 919.33 0.43 -2.86E+Ol 3.68E+01 964.08 14.65 5.97E-01 l.28E+OO 1085.87 10 .24 -2.62E-01 1. 72E+OO 1089.74 1. 73 -l.84E+OO 1. 02E+Ol 1112 . 07 13.69 1. 09E-01 l .13E+OO 1212.95 1. 43 1. 1 7E+OO 1. 21E+Ol 1249.94 0.19 -6.07E+Ol 9.80E+Ol 1299.14 1. 63 1 .61E+OO 1. 22E+Ol 1408.01 21. 07 2.79E-01 7.58E-01 1457.64 0.50 9.61E+Ol 7.98E+Ol 1528.10 0 .28 2.23E+Ol 6.06E+Ol Eu-154 123.07 40.40 6.46E-03 2 . 34E-01 2.34E-01 247.93 6.89 -1.16E+OO 1.48E+OO 591. 7 6 4 .95 -l.44E+OO 2.79E+OO 692.42 1. 78 -6.SlE+OO 7.88E+OO 723.30 20.06 3.23E-Ol 8.98E-01 756.80 4. 52 1 .0lE+OO 3. 17E+OO 873.18 12.08 2.61E-Ol 1. 20 E+OO 996.29 10. 48 3.49E-01 1 .37E+OO

[521]

8/27/2018 1:04:33PM Page 6 of6 Analysis Report for 27-Aug-18-10007 B 1-091 OOA-FSWC-031 CV 0.0" -0.5" 0.0" Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCilgrams) (keV) Eu-154 1004.76 18 .01 3.SOE-01 2.34E-01 1. 04E+OO 1274.43 34.80 3.75E-Ol 6.09E-01 1596.48 1. 80 5.08E+OO 1 .13E+Ol Eu-155 45.30 1. 31 -2.90E+Ol 4.64E-01 3.07E+Ol 60.01 1. 22 -4. 71E+Ol 3.08E+Ol 86.55 30.70 -3.23E-01 4.64E-01 105.31 21.10 9.65E-02 5.23E-01 Ra-226 186.21

• 3.64 1.63E+OO 1 .97E+OO 1 .97E+OO Pa-231 27.36 10.30 9.49E+OO 5.33E+OO 5.94E+OO 283.69 1. 70 -9.33E-01 6.00E+OO 300. 07. 2.47 -3.08E+OO 5.40E+OO 302.65 2.20 -2.09E+OO 5.33E+OO 330.06 1. 40 -1.44E+OO -7. 98E+OO

+ U-235 143.76 10. 96 -1.66E-01 l. 26E-01 9.04E-01 163.33 5.08 1. 36E-01 1.93E+OO 185.71

• 57.20 1.04E-01 1.26E-01 202.11 1. 08 -3.95E+OO 9.20E+OO 205.31 5.01 -7.95E-01 2 . llE+OO Arn-241 59.54 35.90 1. OOE-01 l.16E+OO 1.16E+OO

   +    ;;;   Nuclide identified during the nuclide identification
   *      ;;; Energy line found in the spectrum
   ;>   ;;;   MDA value not calculated
   @    ;;;   Half-life too short to be able to perform the decay correction
   ?    ;;;   CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[522]

27-AUG-18-1000712£2.CNF Live Time :1200.000 sec Real Time :1200.230 sec 60 start: 1: -0. 2(kev) stop : 8192: 2046. 9(kev) Acq. start :Mon AUg 27 09: 49: 03 2018 55 so 45 40 35 V) ,1,-1 C

s 8 30 25 20 15 ~

7 a, 10 ~

                     ~
                                ~

a,

, CL 5

1000 2000 3000 4000 5000 6000 7000 8000 channel

          ~

ROI Type: 1 [523]

8/27/2018 1:05:10PM Page 1 of6

             ~pex-Gamma Analysis Report for    27-Aug-18-10008 B1-09100A-FSWC-031 CV        0.0" - 0.5" 0.5" GAMMA SPECTRUM ANALYSIS Sample Identification                        : 27-Aug-18-10008 Sample Description                           : B1-09100A-FSWC-031CV   0.0" - 0.5"   0.5" Sample Type                                  : Puck Unit Sample Point Sample Size                                      1.205E+02 grams Facility                                     : Default Sample Taken On                              : 8/22/2018 1:30:00PM Acquisition Started                          : 8/27/2018 10:28:48AM Procedure                                    : Puck_half_inch Operator                                     : jwelch Detector Name                                : 352 Geometry                                     : Puck_half_inch Live Time                                    : 1200.0 seconds Real Time                                    : 1200.3 seconds Dead Time                                    : 0.02 %

Peak Locate Threshold  : 3.00 Peak Locate Range {in channels) . 120- 8192 Peak Area Range (in channels) . 120-8192 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On 3/12/2018 Efficiency Calibration Used Done On  : 8/27/2018 Efficiency Calibration Description

• install Sample Number 49646 Certificate Name  : Eu155-Na22 Certificate Date 1/7/2013 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 10:49:01AM DATA VALIDATED Peak Analysis From Channel Peak Analysis To Channel

120

8192

[524] rz~~~ TIME o:nm DATE ?-?-<<?-

8/27/2018 1:05:10PM Page 2 of6 Analysis Report for 27-Aug-18-10008 B1-091 OOA-FSWC-031 CV 0.0" -0.5" 0.5" Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

i. 238.81 952 - 961 955. 71 2.75E+Ol 16.19 3.29E+Ol 0.87 2 295.36 1176 - 1186 1181. 67 2.29E+Ol 15.35 3.03E+01 0.62 3 351.86 1403 - 1412 1407.43 2.78E+Ol 13. 98 1.84E+Ol 0.76 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum.

NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty Pb-212 0.99 115.18 0.60 238.63

• 43.60 2. 08E-01 1.27E-01 300.09 3.30 Pb-214 0.99 241.99 7.25 295.22
• 18.42 4. 72E-01 3.25E-01 351. 93
• 35.60 3.40E-01 1.79E-01 785. 96 1. 06

     .. = Energy line found in the spectrum.
     - = Manually added nuclide.
     ? = Manually edited nuclide.
    @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma

[525]

8/27/2018 1:05;10PM Page 3 of6 Analysis Report for 27-Aug-18-1 0008 81-09100A-FSWC-031CV 0.0" - 0.5" 0.5" INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) X Bi-211 0.905 Pb-212 0.995 2.0SE-01 l .27E-01 Pb-214 0.999 3. 71E-Ol l .57E-01

       ?  = 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 2.000sigma

[526]

8/27/2018 1 :05:10PM Page4 of 6 Analysis Report for 27-Aug-18-10008 B1-09100A-FSWC-031CV 0.0" - 0.5" 0.5" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 10:49:01AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 8192 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m =Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCVgrams) (pCUgrams) (pCilgrams) (keV) An Pk 511. 00 100.00 1. 21E-01 2.06E-01 2.06E-01 BE-7 477.60 10.44 1. 03E+OO l. 47E+OO l. 47E+OO K-40 1460.82 1 0.66 3.62E+OO 4.02E+OO 4 .02E+OO Co-60 1173.23 99.85 6.26E-02 2.08E-Ol 2.0BE-01 1332.49 99.98 l.23E-01 2. llE-01 Nb-94 702.65 99.81 7.81E-02 1.45E-01 l.84E-01 871.09 99.89 1. 52E-02 l.45E-01 Ag-108m 79.13 6.60 -4.39E-02 1 .31E-01 3.09E+OO 433.94 90.50 -1.22E-01 l .31E-01 614.28 89.80 2.15E-01 2.44E-01 722.94 90.80 -3.66E-02 l.89E-01 Sb-125 176.31 6.84 9.36E-02 4.16E-01 1 .43E+OO 380.45 1. 52 l. 21E+OO 7.lOE+OO 427.87 29.60 1. 07E-02 4.16E-01 463.36 10.49 4.30E-01 1. 03E+OO 600.60 17.65 1. OlE-01 7.44E-01 606.71 4.98 2. 96E+OO 4. 62E+OO 635.95 11. 22 -1.36E-01 1. 04E+OO 671. 44 1. 79 3.0SE+OO 9.37E+OO [527]

8/27/2018 1:05:10PM Page 5 of 6 Analysis Report for 27-Aug-18-10008 B1-091 OOA-FSWC-031 CV 0.0" - 0.5" 0.5" Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV) Ba-133 79.61 2.65 1. 37E+OO 2.53E-01 7.51E+OO

81. 00 32.90 -6.23E-01 5.12E-01 276.40 7.16 -5.08E-02 1. 57E+OO 302.85 18.34 -1 .25E-01 5.58E-01 356.01 62.05 -2.llE-01 2.53E-01 383.85 8.94 5.73E-01 1. 12E+OO Cs-134 475.36 1. 48 2.47E+OO 1.44E-01 9.42E+OO 563.25 8.34 8.84E-01 1 .81E+OO 569.33 15.37 6.05E-01 1. 03E+OO 604. 72 97.62 -2.92E-03 2.lOE-01 795.86 85.46 l.66E-02 1. 44E-01 801.95 8.69 3.39E-01 1.65E+OO 1038.61 0 .99 -9.0lE-02 1.58E+Ol 1167.97 1. 79 -3.67E+OO 1.08E+Ol 1365. 19 3.02 1.52E+OO 4.75E+OO Cs-137 661.66 85. 10 1.24E-01 2.27E-01 2.27E-01 Eu-152 12 1. 78 28.67 -7.45E-03 3.16E-01 3.16E-01 244.70 7.61 3.09E-02 1.48E+OO 295.94 0. 45 3. 97E+Ol 3.SlE+Ol 344.28 26.60 8.05E-03 5.03E-01 367.79 0.86 4.41E+OO 1.40E+Ol 411.12 2.24 -5.31E+OO 5.33E+OO 443. 96 2.83 1. 05E-01 4.46E+OO 488.68 0.42 1. 34E+Ol 2.93E+Ol 563.99 0.49 9.07E+OO 3.14E+Ol 586.26 0.46 2.89E+D1 4 .28E+Ol 678.62 0.47 2.05E+Ol 3.65E+Ol 688.67 0.86 2. 96E+OO l .SOE+Ol 719.35 0.28 -1.43E+Ol 5.99E+Ol 778.90 12. 96 -4.SBE-01 9.87E-01 810 .45 0.32 -5.30E+Ol 4.lOE+Ol 867.37 4.26 -2.16E-01 3.55E+OO 919.33 0.43 -6.87E+Ol 2.77E+Ol 964. 08 14.65 2.47E-01 1.50E+OO 1085.87 10.24 4.76E-01 1. 30E+OO 1089.74 1. 73 4.00E-01 8.27E+OO 1112. 07 13. 69 -1.63E-Ol 1. 36E+OO 1212.95 1. 43 -3.50E+OO l.27E+Ol 124 9 .. 94 0.19 -4.40E+Ol 8.30E+Ol 1299.14 1. 63 -1.82E+OO 8.45E+OO 1408.01 21.07 2.23E-01 6.95E-01 1457.64 0.50 1 .13E+02 8.59E+Ol 1528.10 0.28 1 .34E+Ol 4.98E+Ol Eu-154 123.07 40. 40 -2.58E-01 2.23E-01 2.23E-Ol 247.93 6.89 -5.34E-01 1.45E+OO 591. 76 4.95 6.85E-0i 2.44E+OO 692.42 1. 78 -7.88E+OO 7.30E+OO 723. 30 20.06 5.33E-01 8.98E-01 756.80 4 .52 4 .22E-02 3.29E+OO 873.18 12.08 -2. 96E-01 1.15E+OO 996.29 10.48 6.49E-01 1.83E+OO

[528]

8/27/2018 1:05:10PM Page 6 of6 Analysis Report for 27-Aug-18-1 0008 B1-091 OOA-FSWC-031 CV 0.0" -0.5" 0.5" Nuclide Energy Yield{%) Activity NuclideMDA LineMDA Name (pCl/grams) (pCilgrams) (pCilgrams) (keV) Eu-154 1004.76 18.01 -4.96E-01 2.23E-01 1.00E+OO 1274.43 34.80 -1. llE-01 4.25E-01 1596.48 1. 80 1. 36E-01 9.04E+OO Eu-155 45.30 1. 31 1. 03E+Ol 5.06E-01 3.24E+Ol 60.01 1. 22 -2.85E+Ol 2.84E+Ol 86.55 30.70 7.82E-02 5.06E-01 105.31 21.10 5.56E-02 5.40E-01 Ra-226 186.21 3.64 4.14E+OO 3.52E+OO 3.52E+OO Pa-231 27.36 10 .30 7.47E+OO 4. 64E+OO 6.0lE+OO 283.69 1. 70 -3.60E+OO 6.25E+OO 300.07 2.47 -3.88E+OO 4.99E+OO 302.65 2.20 -2.31E-01 4.64E+OO 330.06 1. 40 3.91E+OO 9.25E+OO U-235 143.76 10.96 -3.07E-01 2.22E-01 9.47E-01 163.33 5.08 -3.40E-01 2.16E+OO 185.71 57.20 1.47E-01 2.22E-01 202 .11 1. 08 -3.22E+OO 9.09E+OO 205.31 5.01 -5.0lE-02 1.93E+OO Arn-241 59.54 35.90 -1.04E-Ol 1 . 03E+OO 1. 03E+OO

   +    =  Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
   >    =  MDA value not calculated
   @    =  Half-life too short to be able to perform the decay correction
   ?    =  CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[529]

27-AUG-18-10008l\362.CNF Live Time :1200.000 sec 60 Real Time :1200.250 sec start: 1: -0.2(kev) Stop : 8192:2046.9(kev) ACq. Start :Mon AUg 27 10: 28:48 2018 55 50 45 40 35 Vl ,1...1 C

I 8 30 25 20 15

                     ~
                     ~
                      ~    ::::::

I

                            ~

10 ~... 5 1000 2000 3000 4000 5000 6000 7000 8000 channel

         ~

ROI Type: 1 [530]

8/27/2018 1 :05:38PM Page 1 of6 Analysis Report for 27-Aug-18-10009 B1-09100A-FSWC-041CV 0.0" - 0.5" 0.0" GAMMA SPECTRUM ANALYSIS Sample Identification  : 27-Aug-18-10009 Sample Description  : B1-09100A-FSWC-041CV 0.0" - 0.5" 0.0" Sample Type  : Puck Unit Sample Point Sample Size 1.316E+02 grams Facility  : Default Sample Taken On  : 8/22/2018 8:34:00AM Acquisition Started  : 8/27/2018 10:59:43AM Procedure  : Puck_half_inch Operator  : jwelch Detector Name  : 324 Geometry  : Puck_half_inch Live Time  : 1200.0 seconds Real Time  : 1200.3 seconds Dead Time  : 0.03% Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 120

• 4096 Peak Area Range (in channels)  : 120 - 4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 8/9/2017 Efficiency Calibration Used Done On  : 8/27/2018 Efficiency Calibration Description Sample Number  : 49647 Certificate Name  : Eu155-Na22 Certificate Date  : 1/30/2013 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 11:1 9:52AM Peak Analysis From Channel  : 120 DATA VALIDATED Peak Analysis To Channel  : 4096 DATE1-?-{r TIME o~ ,

[531] ~~=e;,~/

8/27/2018 1:05:38PM Page 2 of6 Analysis Report for 27-Aug-18-1 0009 B 1-091 OOA-FSWC-041 CV 0.0" - 0.5" 0.0" Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end

• Centroid Area Uncertainty Counts (keV) 1 238.77 473 - 480 477.71 2.68E+Ol 25.86 1.32E+02 0.71 2 294.87 585 - 594 589.80 3.25E+Ol 22.65 8.50E+Ol 0.66 3 351.88 699 - 708 703.71 4.50E+Ol 21.68 6.39E+Ol 0.94 4 1461.18 2916 - 2928 2922.42 6.65E+Ol 16.77 2.98E+OO 1. 44 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum.

NUCLIDE /DENT/FICA TJON REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K-4 0 0.98 1460 .82

• 10 .66 6 .17E+OO 1.64E+OO Pb-212 0.99 115.18 0 .60 238.63
• 43.60 1 .65E-Ol 1 .61E-01 300.09 3.30 Pb-214 0 .99 241.99 7.25 295. 22
• 18.42 5.46E-01 3.90E-01 351.93
• 35.60 4 .49E-0 1 2.28E-01 785.96 1. 06

[532]

8/27/2018 1:05:38PM Page 3 of6 Analysis Report for 27-Aug-18-10009 B1-091 OOA-FSWC-041 CV 0.0" - 0.5" 0.0"

     * = Energy line found in the spectrum.
     - = Manually added nuclide.
     ? = Manually* edited nuclide.
    @ = Energy line not used for Weighted Mean Activity Energy Tolerance: 1.000 keV Nuclide confidence index threshold= 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide                             Nuclide                       Wt mean              Wt mean     Comments Name                                  Id                           Activity             Activity Confidence                                          Uncertainty (pCilgrams)

K-40 0.980 6.17E+OO 1.64E+OO X Bi-211 0.900 Pb-212 0.997 1 .65E-01 1.61E-01 Pb-214 0.994 4.74E-Ol 1.97E-01

      ?    =  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 2.000sigma

[533]

8/27/2018 1:05:38PM Page4 of6 Analysis Report for 27-Aug-18-10009 81-09100A-FSWC-041CV 0.0" - 0.5" 0.0" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 11 :19:52AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 4096 Peak CPS (0/o) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB Nuclide Energy Yield{°/o) Activity NuclideMDA LineMDA Name (pCVgrams) (pCUgrams) (pCi/grams) (keV) An Pk 511.00 100.00 2.66E-Ol 2.25E-01 2.25E-01 BE-7 477.60 10.44 2.84E-02 l .31E+OO 1. 31E+OO + K-40 1460.82

• 10.66 6.17E+OO 8.76E-01 8.76E-Ol Co-60 1173.23 99.85 8.62E-02 1 .85E-01 1.85E-01 1332.49 99.98 l.OlE-01 l.91E-01 Nb-94 702.65 99 . 81 2. 71E-02 1.39E-01 1. 51E-01 871. 09 99.89 2.41E-02 1. 39E-Ol Ag-108m 79.13 6.60 3.07E-01 1. 34E-01 2.87E+OO 433.94 90.50 -5.75E-03 1.34E-01 614.28 89.80 -8. 72E-02 1.88E-01 722.94 90.80 -8.99E-02 1.72E-01 Sb-125 176 . 31 6.84 -2.91E-01 4.59E-01 1.67E+OO 380.45 1. 5?. -?..69E-O l 8 . lOE+OO 427.87 29.60 2.57E-01 4 . 59E-01 463 . 36 10.49 2.98E-01 1. 3SE+OO 600.60 17.65 3.65E-01 7.95E-Ol 606. 71 4.98 2.88E+OO 4.31E+OO 635.95 11. 22 -2.82E-02 1. 23E+OO 671. 44 1. 79 -4.23E+OO 6.49E+OO

[534]

8/27/2018 1:05:38PM Page 5 of6 Analysis Report for 27-Aug-18-10009 B1-091 OOA-FSWC-041 CV 0.0" - 0.5" 0.0" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCi!grams) (pCi!grams) (keV) Ba-133 79.61 2.65 3.40E+OO 2.50E-01 7.22E+OO

81. 00 32.90 5.79E-03 5 . ll E-01 276.40 7. 16 -3.59E-01 1.61E+OO 302.85 18.34 3.56E-03 6 . ll E-01 356.01 62.05 -6.49E-02 2.50E-01 383.85 8.94 -1.76E-01 1 .40E+OO Cs-134 475.36 1. 48 3.14E-Ol l .25E-01 8. 71E+OO 563.25 8.34 -2.32E-01 1.31E+OO 569.33 15.37 2.09E-01 8.28E-Ol 604. 72 97.62 -3.16E-02 1 .98E-01 7 95. 8 6 85.46 -3.08E-02 1 .25E-01 801.95 8.69 -3.75E-01 1. 46E+OO 1038.61 0 .99 l .17E+Ol 1. 82E+Ol 1167.97 1. 79 2.54E-01 9.14E+OO 1365.19 3.02 -4.44E-01 4.84E+OO Cs-137 661. 66 85. 10 4.84E-02 l. 92E-01 1.92E-01 Eu-152 121. 7 8 28.67 -4.57E-02 3.27E-01 3.27E-01 244.70 7.61 1.88E-01 1. 73E+OO 295.94 0.45 -4.21E-01 3.34E+Ol 344.28 26. 60 -1.59E-01 4.31E-01 367.79 0.86 -3.86E+OO 1. 32E+Ol 411.12 2.24 -9.79E-01 5.37E+OO 443. 96 2.83 4 .llE-02 4. 43E+OO 488.68 0.42 2.37E+OO 3. llE+Ol 563.99 0.49 -l.29E+Ol 2.08E+Ol 586.26 0.46 2.69E+Ol 3.85E+Ol 678.62 0.47 -5.62E+OO 2.85E+Ol 688.67 0.86 -3.28E+OO l.SOE+Ol 719.35 0.28 1 .67E+Ol 5.48E+Ol 778.90 12.96 -5.23E-Ol 9.23E-01 810.45 0.32 -l.45E+Ol 4.25E+Ol 867.37 4.26 8.0SE-02 2.90E+OO 919.33 0.43 -1 .19E+Ol 2.88E+Ol 964.08 14.65 1. OlE-01 9.08E-Ol 1085.87 10.24 6.61E-01 l. 76E+OO 1089.74 1. 73 4.45E-01 9.62E+OO 1112. 07 13. 69 5.0SE-01 1.30E+OO 1212.95 1. 43 2.22E+OO 1.17E+Ol 1249.94 0.19 3.45E+Ol 1.02E+02 1299. 14 1. 63 5.54E+OO 9.99E+OO 1408.01 21.07 -1. OSE-01 7.86E-01 1457.64 0.50 -1.69E+Ol 8.66E+Ol 1528.10 0.28 3.18E+OO 4 .54E+Ol Eu-154 123.07 40.40 -3.30E-02 2.33E-01 2.33E-01 247.93 6.89 -2.58E-01 l .70E+OO 591.76 4.95 -5.64E-01 2.28E+OO 692.42 1. 78 1. 46E+OO 6.88E+OO 723. 30 20.06 -1.75E-01 8.lOE-01 756.80 4.52 3.53E-01 2.88E+OO 873.18 12.08 -6.52E-01 l.03E+OO 996.29 10.48 -4.47E-01 l.54E+OO

[535]

8/27/2018 1:05:38PM Page 6 of6 Analysis Report for 27-Aug-18-1 0009 B1-091 OOA-FSWC-041 CV 0.0"

• 0.5" 0.0" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi!grams) (pCi!grams) (pCilgrams)

{keV) Eu-154 1004.76 18.01 4.23E-01 2.33E-01 9.78E-01 1274.43 34.80 -1. 5 9E-Ol 4.61E-01 1596.48 1. 80 -2. llE+OO 9.73E+OO Eu-155 45.30 1. 31 -l .65E+OO 4.48E-01 2.50E+Ol 60.01 1. 22 -5.69E+OO 2.44E+Ol 86.55 30.70 9 .13E-02 4.48E-01 105.31 21.10 -2.03E-01 5.00E-01 Ra-226 186.21 3.64 1.40E+OO 3.SlE+OO 3.51E+OO Pa-231 27.36 10.30 l.SlE+OO 2.73E+OO 2.73E+OO 283.69 1. 70 4.43E-01 7.15E+OO 300.07 2.47 -1.SlE+OO 4.84E+OO 302.65 2.20 2. 96E-02 5.08E+OO 330.06 1. 40 1. 05E+OO 9.44E+OO U-235 143.76 10.96 -l.41E-02 2.20E-01 8.80E-01 163.33 5.08 -1.61E+OO l.97E+OO 185. 71 57.20 4.34E-02 2.20E-01 202 .11 1. 08 -1.32E+OO l.OBF.+01 205.31 5.01 -l.05E+OO 2.31E+OO Am-241 59.54 35.90 -2.07E-01 8.28E-01 8.28E-Ol

   +    =  Nuclide identified during the nuclide identification
   *     = Energy line found in the spectrum
   >    =  MDA value not calculated
   @    =  Half-life too short to be able to perform the decay correction
   ?    =  CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[536]

• 27-AUG-18-10009C17.CNF Live Time :1200.000 sec 60 Real Time :1200.330 sec start: 1: O. l(kev)

Stop : 4096: 2047 .1(kev) Acq. start :Mon Aug 27 10:59:43 2018 55 50 45 40 35 VI ,1,-1 C: 8 30 25 20 C) 15 10 5

                 ,~

0 500 1000 1500 2000 2500 3000 3500 4000 channel

         ~

ROI Type: 1 [537]

8/27/2018 1:06:11PM Page 1 of6 Analysis Report for 27-Aug-18-1 0010 B1-09100A-FSWC-041CV 0.0" - 0.5" 0.5" GAMMA SPECTRUM ANALYSIS Sample Identification  : 27-Aug-18-10010 Sample Description  : B1-09100A-FSWC-041CV 0.0" - 0.5" 0.5" Sample Type  : Puck Unit Sample Point Sample Size 1.316E+02 grams Facility  : Default Sample Taken On  : 8/22/2018 8:34:00AM Acquisition Started  : 8/27/2018 11 :23:32AM Procedure

• Puck_half_inch Operator
• jwelch Detector Name
• 324 Geometry Puck_half_inch Live Time 1200.0 seconds Real Time 1200.3 seconds Dead Time
• 0.03 %

Peak Locate Threshold

• 3.00 Peak Locate Range (in channels)  : 120- 4096 Peak Area Range (in channels)  : 120- 4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On Efficiency Calibration Used Done On

8/9/2017

8/27/2018 g,r Efficiency Calibration Description Sample Number  : 49651 Certificate Name  : Eu 155-Na22 Certificate Date  : 1/30/2013 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 11 :43:34AM Peak Analysis From Channel  : 120 DATA VALIDATED or-0 DATE 9~ZjJ:

Peak Analysis To Channel

• 4096

                                                                                                                    \

[538] ~~p:~£/TIME

8/27/2018 1:06:11PM Page 2 of6 Analysis Report for 27-Aug-18-10010 B 1-091 OOA-FSWC-041 CV 0.0" -0.5" 0.5" Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) 1 352.01 699 - 708 703. 96 7.SOE+Ol 21. 62 3.61E+Ol 1. 44 2 609.59 1213 - 1224 1218.76 5.21E+Ol 16.70 1.37E+Ol 0.72 3 14 61. 00 2915 - 2928 2922.05 7.35E+Ol 18.23 7.00E+OO 1. 22 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K-40 0 .99 1460.82

• 10.66 6. 81E+OO 1. 79E+OO Bi-211 0 .86 351. 07
• 13. 02 2. 05E+OO 6.76E-01 Bi-214 0.99 60 9. 32
• 45.49 6. 14E-Ol 2. lOE-01 768.36 4.89 806.18 1. 26 934.06 3. 11 1120.29 14.92 l:!.55.21 1. 63 1238.12 5.83 1280.98 1. 43 1377.67 3.99 1385.31 0.79 1401. 52 1. 33 1407.99 2.39 1509.21 2.13 1661.27 1. 05

[539]

8/27/2018 1:06:11PM Page 3 of6 Analysis Report for 27-Aug-18-1 0010 B1-091 OOA-FSWC-041 CV 0.0"

• 0.5" 0.5" Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty Bi-214 0.99 1729.59 2.88 1764.49 15.30 1847.43 2.03 2118.51 1.16 Pb-214 0 .99 241.99 7.25 295.22 18.42 351.93
• 35.60 7.4 8E-01 2.47E-0 1 785.96 1. 06

      * = Energy line found in the spectrum.
      - = Manually added nuclide.
     ? = Manually edited nuclide.
     @=Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold= 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide                             Nuclide                       wt mean                Wt mean      Comments Name                                   Id                          Activity               Activity Confidence                                            Uncertainty (pCi/grams)

K-40 0 .995 6.81E+OO 1. 79E+OO

     ?       Bi-211                               0 .869                    2.0SE+OO                6.76E-01 Bi-214                               0. 995                     6.14E-01               2.lOE-01
     ?       Pb-214                               0 .999                    7.48E-01                2.47E-01
       ?   =  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 2.000sigma [540]

8/27/2018 1:06:11PM Page 4 of6 Analysis Report for 27-Aug-18-10010 B1-09100A-FSWC-041CV 0.0" - 0.5" 0.5" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 11:43:34AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCUgrams) (pCi!grams) (keV) An Pk 511. 00 100.00 3.44E-01 2.41E-01 2.41E-01 BE-7 477.60 10.44 1.20E-01 1. 36E+OO 1. 36E+OO + K-40 1460.82

• 10.66 6.81E+OO 1 .24E+OO 1. 24E+OO Co-60 1173.23 99.85 -2.16E-02 1 .58E-01 l .90E-01 1332.49 99.98 -4.46E-02 l.58E-01 Nb-94 702.65 99.81 5.81E-03 1.54E-01 1.54E-01 871.09 99.89 6. 71E-02 l .81E-01 Ag-108m 79.13 6.60 1 . lOE+OO 1. 09E-01 2.75E+OO 433.94 90 .50 -3.15E-02 1. 09E-01 614.28 89.80 1.42E-02 2.19E-01 722.94 90.80 -2.88E-02 1. 51E-01 Sb-125 176.31 6.84 6.17E-02 3.95E-01 1 .64E+OO 380.45 1. 52 -1.66E+OO 8.29E+OO 427.87 29.60 -3. 96E-02 3.95E-Ol 463.36 10.49 -3.lOE-01 1.06E+OO 600.60 17.65 1 .72E-01 8.24E-01 606. 71 4.98 -2.42E-01 4.57E+OO 635.95 11. 22 -9.88E-02 1 .12E+OO 671. 44 1. 79 9.94E-02 7.29E+OO

[541]

8/27/2018 1:06:11PM Page 5 of6 Analysis Report for 27-Aug-18-10010 B1-091 ODA-FSWC-041 CV 0.0" - 0.5" 0.5" Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCi!grams) (pCi!grams) (pCi/grams) (keV) Ba-133 79.61 2.65 3.26E+OO 2.60E-01 6. 71E+OO

81. 00 32.90 -1.98E-01 4.52E-01 276.40 7.16 2.58E-01 1.74E+OO 302.85 18.34 2.27E-01 7.0lE-01 356. 01 62.05 -8.67E-02 2.60E-Ol 383.85 8.94 3.99E-Ol l.40E+OO Cs-134 475.36 1. 48 -2.41E+OO l . 63E-01 8.57E+OO 563.25 8.34 9. 72E-02 1.75E+OO 569.33 15.37 6.34E-02 9.86E-01 604.72 97. 62 -2.0lE-02 1.78E-01 795.86 85.46 -6.96E-02 1.63E-01 801.95 8.69 2.82E-01 1.74E+OO 1038.61 0.99 -2.89E+OO 1.78E+Ol 1167.97 1. 79 4.19E+OO 1.14E+Ol 1365.19 3.02 -9.72E-Ol 4.55E+OO Cs-137 661.66 85.10 O.OOE+OO l. 59E-01 l.59E-01 Eu-152 121.78 28.67 3.76E-02 3.53E-01 3.53E-01 244.70 7.61 5.26E-02 1.75E+OO 295.94 0.45 2.50E+Ol 3.56E+Ol 344.28 26. 60 9.96E-02 4.42E-01 367.79 0.86 1 .63E+OO 1.33E+Ol 411 .12 2.24 3.41E+OO 6.0lE+OO 443.96 2.83 -5.43E-Ol 3.95E+OO 488.68 0.42 3.06E+OO 3.06E+Ol 563.99 0.49 1. llE+Ol 3.lOE+Ol 586.26 0.46 6.39E+OO 3. 72E+Ol 678.62 0.47 3.79E-01 2.78E+Ol 688.67 0.86 8.00E+OO 1.86E+Ol 719. 35 0.28 8.07E+OO 4.77E+Ol 778.90 12. 96 3.12E-02 9.91E-01 810.45 0 .32 2.29E+OO 3.97E+Ol 867.37 4 .26 2.77E+OO 4.25E+OO 919. 33 0.43 1.53E+Ol 3.58E+Ol 964. 08 14.65 -4.03E-01 1.02E+OO 1085.87 10.24 -7.0SE-02 1. 28E+OO 1089.74 1. 73 -8.35E+OO 7.19E+OO 1112. 07 13 .69 1. 92E-01 1. 02E+OO 1212.95 1. 43 -3.40E+OO l. 29E+Ol 1249.94 0.19 -2.09E+Ol 7.22E+Ol 1299.14 1. 63 1.52E+OO 9.56E+D0 1408.01 21. 07 3.D7E-01 9.lBE-01 1457.64 a.so -5.23E+OO 8.98E+D1 1528.10 0.28 1. 36E+Ol 5.66E+Ol Eu-154 123.07 40.40 l. 87E-02 2.50E-01 2.SOE-01 247.93 6.89 l.29E+OO 1.83E+OO 591. 7 6 4.95 -1.67E+OO 2.75E+OO 692.42 1. 78 6.05E-01 9.34E+OO 723. 30 20.06 -6.03E-02 6.83E-01 756.80 4 .52 3.80E-01 2.69E+OO 873.18 12.08 2.81E-01 1.42E+OO 996. 2 9 10. 48 5.30E-01 1.54E+OO

[542]

8/27/2018 1:06:11PM Page 6 of6 Analysis Report for 27-Aug-18-10010 B1-091 OOA-FSWC-041 CV 0.0" -0.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCUgrams) (pCUgrams) (pCi/grams) (keV) Eu-154 1004.76 18.01 -3.97E-01 2.SOE-01 6.92E-01 1274.43 34.80 2.91E-01 5.31E-01 1596.48 1. 80 O.OOE+OO 1.70E+OO Eu-155 45.30 1. 31 -2.45E+OO 4.56E-01 2.45E+Ol 60.01 1. 22 -8.70E+OO 2.66E+Ol 86.55 30.70 1.51E-01 4.56E-01 105.31 21.10 2.37E-01 5.85E-01 Ra-226 186.21 3.64 8.59E-Ol 3.53E+OO 3.53E+OO Pa-231 27.36 10.30 1. 16E+D0 2.51E+OO 2.51E+OO 283.69 1. 70 -8.08E-01 6.20E+OO 300.07 2.47 -4.19E+OO 5.32E+OO 302.65 2.20 1.89E+OO 5.84E+OO 330.06 1. 40 -3.0BE+OO 9.08E+OO U-235 143.76 10. 96 3.41E-Ol 2.26E-01 9.78E-01 163.33 5.08 -l.13E+OO 2.20E+OO 185. 71 57.20 7.67E-02 2.26E-01 202 . 11 1. 08 -3.53E+OO 1.04E+Ol 205.31 5.01 4.96E-01 2.39E+OO Arn-241 59.54 35.90 l. 53E-01 9.63E-01 9.63E-01

   +    = Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
   >    = MDA value not calculated
   @    = Half-life too short to be able to perform the decay correction
   ?    = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[543]

27-AUG-18-l00108F8D.CNF Live Ti me 1200. 000 sec 60 Real Time 1200.320 sec start: 1 O. l(kev) stop : 4096 2047. l(kev) Acq. start Mon Aug 27 11: 23: 32 2018 55 50 45 40 35 II) +-' C: 8 30 25 ~

                      ~

20 15 10 5 0 500 1000 1500 2000 2500 3000 3500 4000 channel

      ~

ROI Type: 1 [544]

8/27/2018 1:06:41PM Page 1 of6 ---===~.~pex-Gamma Analysis Report for 27-Aug-18-1 0011 B1-09100A-FSWC-051 CV 0.0" - 0.5" 0.0" GAMMA SPECTRUM ANALYSIS Sample Identification  : 27-Aug-18-10011 Sample Description  : B1-09100A-FSWC-051CV 0.0" - 0.5" 0.0" Sample Type  : Puck Unit Sample Point Sample Size 1.109E+02 grams Facility  : Default Sample Taken On  : 8/22/2018 2:05:00PM Acquisition Started  : 8/27/2018 1D:59:49AM Procedure  : Puck_half_inch Operator  : jwelch Detector Name  : P40818B Geometry  : Puck_half_inch Live Time  : 1200.0 seconds Real Time  ; 1200.9 seconds Dead Time

• 0.07 %

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) - 120 - 8192 Peak Area Range (in channels)

• 120 - 8192 Identification Energy Tolerance
• 1.000 keV Energy Calibration Used Done On
• 12/23/2017 Efficiency Calibration Used Done On 8/27/2018 Efficiency Calibration Description Sample Number 49648 Certificate Name
• Eu155-Na22 Certificate Date
• 1/30/2012 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 11:19:52AM DATA VALIDATED Peak Analysis From Channel Peak Analysis To Channel

120

8192 DATE f-Z'-fr OTIMEO?-_r~ \

[545] 0-=,,~,if.~~

8/27/2018 1:06:41 PM Pagel of6 Analysis Report for 27-Aug-18-10011 B1-091 OOA-FSWC-051 CV 0.0" -0.5" 0.0" Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) 1 295.47 1176 - 1185 1181. 77 2.25E+Ol 15.73 3.50E+Ol 0 .34 2 351.86 1402 - 1412 1407.19 2.91E+Ol 17.08 3.59E+Ol 0 .35 3 661.65 2639 - 2652 2645.69 4.60E+Ol 16.16 l.40E+Ol 1. 35 4 14 61. 32 5840 - 5851 5845.12 1.81E+Ol 11. 81 l .18E+Ol 0 .46 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Actfvity Name Confidence (keV) (pCilgrams) Uncertainty K-4 0 0. 96 1460.82

• 10.66 2.41E+OO l.59E+OO Cs-137 1. 00 661.66
• 85.10 4.34E-Ol 1.61E-01 Pb-214 0. 99 241. 99 7.25 295.22
• 18.42 5.27E-01 3. 78E-01 351.93
• 35.60 4.04E-01 2.46E-Ol 785.96 1. 06

     * = Energy line found in the spectrum.
     - = Manually added nuclide.
     ? = Manually edited nuclide.
     @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.UOOsigma

[546]

8/27/2018 1:06:41PM Page 3 of6 Analysis Report for 27-Aug-18-10011 B1-09100A-FSWC-051 CV 0.0" - 0.5" 0.0" INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams} K-40 0. 961 2.41E+OO 1. 59E+OO Cs:-137 1. 000 4.34E-01 1. 61E-01 X Bi-211 0.904 Pb-214 0.997 4.41E-Ol 2. 06E-01

       ?   = 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 2.000sigma

[547]

8/27/2018 1:06:41PM Page4 of6 Analysis Report for 27-Aug-18-10011 B1-09100A-FSWC-051CV 0.0" - 0.5" 0.0" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 11:19:52AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 8192 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCilgrams) (pCl!grams) (pCi!grams) (keV) An Pk 511. 00 100.00 3.09E-01 2.94E-01 2.94E-01 BE-7 477.60 10.44 -1. BOE-01 1. 56E+OO 1. 56E+OO + K-40 1460.82

• 10.66 2.41E+OO 2.23E+OO 2.23E+OO Co-60 1173.23 99.85 -3.91E-02 1.92E-01 2.07E-01 1332.49 99.98 7.89E-02 l .92E-01 Nb-94 702.65 99.81 1. 60E-02 1. 38E-01 l.38E-01 871.09 99.89 -5.96E-02 1.84E-01 Ag-108m 79.13 6.60 -1.42E+D0 2.09E-Ol 4 .84E+OO 433.94 90.50 -1.02E-02 2.D9E-Ol 614.28 89.80 -2.35E-01 2.39E-01 722.94 90.80 3.81E-02 2.34E-01 Sb-125 176.31 6.84 -1.40E+OO 5.86E-D1 2.07E+OO 380.45 1. 52 -5.35E+OO 1.16E+D1 427.87 29.60 l .88E-01 5.86E-01 463.36 10.49 3.SlE-01 1. 76E+OO 600.60 17.65 -1.48E-01 9.36E-01 606.71 4. 98 2.95E+OO 4.97E+OO 635.95 11. 22 -4.53E-01 1. 40E+OO 671. 44 1. 79 1 .48E+OO 9.16E+OO

[548]

8/27/2018 1:06:41PM Page 5 of6 Analysis Report for 27-Aug-18-10011 B1-091 OOA-FSWC-051 CV 0.0" - 0.5" 0.0" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCUgrams) (pCUgrams) (pCilgrams) (keV) Ba-133 79.61 2.65 -1. 83E+OO 3.15E-01 1 .17E+Ol

81. 00 32.90 7.45E-02 9.33E-01 276.40 7.16 -1 .33E+OO 1. 85E+OO 302.85 18.34 3.16E-01 8.24E-01 356.01 62.05 -2.58E-01 3.15E-01 383.85 8.94 -1.41E+OO 1. 81E+OO Cs-134 475.36 1. 48 -4.14E+OO 2.21E-Ol 1.06E+Ol 563.25 8.34 1.34E+OO 2.26E+OO 569.33 15.37 -1.34E+OO 9.44E-01 604. 72 97.62 -4.48E-02 2.21E-01 795.86 85.46 -3.95E-02 2.31E-01 801.95 8.69 -7.1 3E-01 2.53E+OO 1038.61 0.99 8. 96E+OO 1.84E+Ol 1167.97 1. 79 4.69E+OO 1.04E+Ol 1365.19 3.02 5.35E+OO 8.69E+OO

+ Cs-137 661. 66

• 85.10 4 .34E-Ol 1 . 68E-01 l. 68E-01 Eu-152 121. 78 28.67 1 .29E-01 5.53E-01 5.53E-01 244.70 7.61 -4.43E-02 2.24E+DO 295.94 0.45 1.57E+Ol 4.12E+Ol 344.28 26.60 4.SOE-01 6.80E-01 367.79 0.86 5.75E+OO 1.65E+Ol 411.12 2.24 -2.81E+OO 8.20E+OO 443.96 2.83 6.65E-01 6.46E+OO 488.68 0.42 -1.82E+OO 4.36E+Ol 563.99 0.49 -2.82E+OO 3.68E+Ol 586.26 0.46 2.87E+Ol 4.20E+Ol 678.62 0.47 -2.64E+Ol 3.61E+Ol 688.67 0.86 -7.74E+OO 2.12E+Ol 719.35 0.28 -6. 96E+OO 7.lOE+Ol 778.90 12.96 5.57E-01 1.15E+OO 810.45 0.32 1.95E+Ol 6.38E+Ol 867.37 4.26 2.98E+OO 4.62E+OO 919.33 0.43 2.16E-01 4.47E+Ol 964.08 14.65 2.55E-01 1.54E+OO 1085.87 10. 24 -1.lSE+OO 1.73E+OO 1089.74 1. 73 -5.91E+OO l.08E+Ol 1112. 07 13. 69 1. 06E-01 l.70E+OO 1212.95 1. 43 -2.16E+Ol 1. 34E+Ol 1249.94 0.19 3.98E+Ol 9.71E+Ol 1299.14 1. 63 2.38E+OO 8.87E+OO 1408.01 21. 07 O.OOE+OO 8.89E-01 1457.64 0.50 6.76E+Ol 8.59E+Ol 1528.10 0.28 -4.06E+01 7.66E+Ol Eu-154 123.07 40. 40 -1.03E-01 3.74E-01 3.74E-01 247.93 6.89 -1 . 24.E +OO 2.26E+OO 591. 76 4 .95 1. 52E+OO 3.20E+OO 692.42 1. 78 7.94E+OO 1.06E+Ol 723.30 20.06 1 .94E-01 1.06E+OO 756.80 4 .52 -8.99E-01 4.32E+OO 873.18 12.08 4.63E-01 1. 52E+OO 996.29 10 .48 -1.90E-01 2.20E+OO

[549]

8/27/2018 1:06:41PM Page 6 of6 Analysis Report for 27-Aug-18-10011 B1-091 OOA-FSWC-051 CV 0.0" - 0.5" 0.0" Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCi!grams) (keV) Eu-154 1004.76 18.01 -l.95E-01 3.74E-01 9.87E-01 1274.43 34.80 9.23E-02 6.60E-Ol 1596.48 1. 80 l.71E+OO 8.25E+OO Eu-155 45.30 1. 31 8. 96E+OO 8.17E-01 7.35E+Ol

60. 01 1. 22 l.86E+Ol 8.44E+Ol 86.55 30.70 4.79E-Ol 8.79E-01 105.31 21.10 -3.06E-01 8.17E-Ol Ra-226 186.21 3.64 -2.45E-01 4.35E+OO 4.35E+OO Pa-231 27.36 10.30 4.66E+OO 6.07E+OO 8.86E+OO 283.69 1. 70 4.50E+OO 9.18E+OO 300.07 2.47 -7.59E+OO 6.07E+OO 302.65 2.20 9.37E-01 6.86E+OO 330.06 1.40 -5.86E-Ol 1.1 7E+Ol U-235 143.76 10. 96 -7.51E-02 2 . 86E-01 l.49E+OO 163.33 5.08 3.42E-01 3.17E+OO 185.71 57.20 1.66E-01 2.86E-01 202 .11 1. 08 2.46E+OO 1. 31E+Ol 205.31 5.01 -8.08E-01 2.82E+OO Am-241 59.54 35.90 -5.lBE-01 2.89E+OO 2.89E+OO

   +    =  Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
   >    =  MDA value not calculated
   @    =  Half-life too short to be able to perform the decay correction
    ?   =  CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[550]

27-AUG-18-10011368.CNF Live Time 1200.000 sec 60 Real Time 1200.890 sec start: 1 -0.0(kev) stop : 8192 2047.4(kev) Acq. Start Mon AUg 27 10: S9: 49 2018 40 35 V) C:

J 8 30 25 20 15

                          ~   ....

J, a..

                              ~         ::iJ, u

1000 2000 3000 4000 5000 6000 7000 8000 channel

         ~

ROI Type: l [551]

8/27!2018 1 :07:10PM Page 1 of6 ____,._,: :5--~. f r\pex-Gam ma Analysis Report for 27-Aug-18-10012 B1-09100A-FSWC-051CV 0.0" - 0.5" 0.5" GAMMA SPECTRUM ANALYSIS Sample Identification  : 27-Aug-18-10012 Sample Description

• B1-09100A-FSWC-051CV 0.0" - 0.5" 0.5" Sample Type
• Puck Unit Sample Point Sample Size 1.109E+02 grams Facility
• Default Sample Taken On  ! 8/22/2018 2:05:00PM Acquisition Started  : 8/27/2018 11:23:37AM Procedure  : Puck_half_inch Operator  : jwelch Detector Name  : P40818B Geometry  : Puck_half_inch Live Time  : 1200.0 seconds Real Time  : 1200.9 seconds Dead Time  : 0.07%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 120- 8192 Peak Area Range (in channels)  : 120- 8192 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On

• 12/23/2017 Efficiency Calibration Used Done On
• 8/27/2018 Efficiency Calibration Description Sample Number 49652 Certificate Name
• Eu155-Na22 Certificate Date ' 1/30/2012 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 ii :43:40AM UATAVAUDATED Peak Analysis From Channel Peak Analysis To Channel

120

8192 DATE 9-e. -1 r TIME O};-l>~

[552]

                                                                            .rzA~tf~~

8/27/2018 1:07:10PM Page 2 of6 Analysis Report for 27-Aug-18-10012 B 1-09100A-FSWC-051 CV 0.0" - 0.5" 0.5" Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts {keV) 1 295.33 1177 - :!.187 1181. 22 2.79E+Ol 15 . 81 2.82E+Ol 0.42 2 352.03 1400 - 1413 1407.85 3 . .'.?.lE+Ol 16 . 78 2.78E+Ol 0.87 3 1461. 08 5839 - 5850 5844.16 2.00E+Ol 11. 05 8.00E+OO 0. 96 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence {keV) (pCi/grams) Uncertainty K-40 0 .98 1460 .82

• 10.6 6 2 .67E+OO 1.49E+OO Pb-214 0 .99 241. 99 7.25 295.22
• 18.42 6 .53E-01 3.85E-01 351. 93
• 35.60 4.47E-01 2.44E-01 785. 96 1. 06

     * = Energy line found in the spectrum.
     - = Manually added nuclide.
    ? = Manually edited nuclide.
    @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma

[553]

8/27/2018 1:07:10PM Page 3 of6 Analysis Report for 27-Aug-18-10012 B1-09100A-FSWC-051CV 0.0" - 0.5" 0.5" INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0.989 2. 67E+OO 1. 49E+OO X Bi-211 0.863 Pb-214 0.999 5.0 6E-Ol 2. 06E-01

      ?   ==  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 2.000sigma

[554]

8/27/2018 1:07: 1OPM Page4 of6 Analysis Report for 27-Aug-18-10012 B1-09100A-FSWC-051CV 0.0" 0.5" 0.5" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 11 :43:40AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 8192 Peak CPS(%) Peak Tolerance Peak No. Energy (keV} Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCUgrams) (pCi!grams) (pC/lgrams) (keV) An Pk 511. 00 100. 00 3.SlE-01 2.77E-01 2.77E-01 BE-7 477.60 10.44 2.lOE-01 1. 75E+OO 1. 7 5E+OO + K-40 1460.82

• 10.66 2.67E+OO 1.BSE+OO l. 85E+OO Co-60 1173.23 99.85 l. 56E-01 2.27E-01 2.42E-01 1332.49 99.98 3.76E-02 2.27E-01 Nb-94 702.65 99.81 -1.69E-01 1 .23E-01 1.23E-01 871.09 99.89 1.37E-01 2.04E-01 Ag-108m 79.13 6.60 -1.lOE+OO 1 .79E-01 5.37E+DO 433.94 90.50 -3.91E-02 1 .79E-01 614.28 89.80 -1.86E-01 2.23E-01 722. 94 90.80 -2.26E-01 2.0BE-01 Sb-125 176.31 6.84 -l. 79E-01 5.86E-01 2.02E+OO 380.45 1. 52 2.85E+OO l .06E+Ol 427.87 29.60 2.83E-Ol 5.86E-01 463.36 10.49 -4. 68E-Ol l.63E+OO 600.60 17.65 -5.03E-01 1. OlE+OO 606.71 4.98 3.06E+OO 4.67E+OO 635.95 1 1. 22 -9. 71E-01 l.49E+OO 671. 44 1. 79 8.47E-01 9.16E+OO

[555]

8/27/2018 1:07:10PM Page 5 of6 Analysis Report for 27-Aug-18-10012 B1-091 OOA-FSWC-051 CV 0.0" - 0.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCi/grams) * (pCilgrams) (keV) Ba-133 79.61 2.65 -4.33E+OO 2.94E-01 l. 28E+Ol

81. 00 32.90 -3.07E-01 9.33E-01 276.40 7.16 -8.59E-01 1. 96E+OO 302.85 18 .34 -l .78E-01 8.06E-01 356. 01 62.05 -4 .92E-03 2.94E-Ol 383.85 8.94 3.32E-Ol 1. 78E+OO Cs-134 475.36 1. 48 -3.24E+OO 2.07E-01 1.lOE+Ol 563.25 8.34 l.34E+OO 2.0BE+OO 569.33 15.37 -7.29E-01 9.75E-01 604. 72 97.62 -3.73E-02 2.07E-01 795.86 85.46 -l.69E-02 2.44E-01 801.95 8.69 6.21E-02 2.08E+OO 1038.61 0. 99 -1. 0 lE+Ol 2.02E+Ol 1167.97 1. 79 4.15E+OO l. 21E+Ol 1365. 19 3.02 3.12E+OO 6.94E+OO Cs-137 661.66 85. 10 8.44E-02 2.87E-Ol 2.87E-01 Eu-152 121.78 28.67 3.93E-01 5.65E-01 5.85E-01 244.70 7.61 2.51E-02 2.12E+OO 295.94 0.45 2.27E+01 4.07E+Ol 344.28 26.60 -4.61E-01 5.65E-01 367.79 0.86 -l.18E+Ol l .76E+Ol 411 .12 2.24 7.00E-01 6.0BE+OO 443. 96 2.83 3.04E+OO 6.29E+OO 488.68 0.42 -3.26E+Ol 3.53E+Ol 563.99 0.49 l.34E+Ol 3.45E+Ol 586.26 0.46 4.05E+Ol 4.50E+Ol 678.62 0.47 -l.39E+Ol 2.85E+Ol 688.67 0.86 -l.03E+Ol 2.00E+Ol

                     '719.35             0.28          1.81E+Ol                      6.55E+Ol 778.90             12. 96         6.96E-02                     1. 02E+OO 810.45              0.32        -8.98E+OO                      5.64E+01 867.37              4 .26       -1.87E+OO                      3.95E+OO 919.33             0.43          l.09E+Ol                     4.29E+Ol 964.08             14.65        -4.66E-01                      1. 58E+OO 1085.87             10.24        -2.86E-01                      l.73E+OO 1089.74              1. 73         5.93E+OO                     l. 1 4E+Ol 1112. 07            13.69          l. OlE+OO                    l.65E+OO 1212.95              1. 43       -8.67E+OO                      1. 34E+Ol 1249.94              0.19        -l.32E+02                      1. 03E+02 1299.14              1. 63       -7.14E+OO                      9.89E+OO 14 08 . 0 1         21. 07         2.51E-01                     l.13E+OO 1457.64              0.50          4.73E+Ol                     8.22E+Ol 1528.10              0.28          3.67E+01                     8.16E+Ol Eu-154      123.07             40. 40        2.25E-Ol       4. 12E-Ol      4.12E-01 247.93              6.89         2.26E+OO                      2.45E+OO 591.76              4 .95         l .38E+OO                    3.55E+OO 692.42              1. 78        7.00E+OO                      1. OOE+Ol 723.30             20.06          1. 86E-01                    l.02E+OO 756.80              4.52          1.lOE+OO                     4 .65E+OO 873.18             12.08          6.32E-01                     1 .64E+OO 996. 29            10.48         5.66E-01                      2.07E+OO

[556]

8/27/2018 1:07:10PM Page 6 of6 Analysis Report for 27-Aug-18-10012 B 1-091 OOA-FSWC-051 CV o.o* - o.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCi/grams) (pCi/grams) (keV) Eu-154 1004 .76 18.01 -1.llE+OO 4.12E-01 9.87E-01 1274.43 34.80 -2.83E-01 4. 97E-01 1596.48 1. 80 5.12E+OO 1. 25E+Ol Eu-155 45.30 1. 31 1 .21E+Ol 8.0lE-01 8.44E+Ol 60.01 1. 22 5.62E+O l 8.84E+Ol 86.55 30.70 1. 57E-01 8.0lE-01 105.31 21.10 -2.17E-01 8.23E-01 Ra-226 186.21 3.64 6.43E-01 4 .16E+OO 4.16E+OO Pa-231 27.36 10.30 1.63E+OO 6.51E+OO 9.lOE+OO 283.69 1. 70 4.37E+OO 8.SBE+OO 300.07 2.47 1. 21E+OO 6.51E+OO 302.65 2.20 8.23E-01 6. 71E+OO 330.06 1.. 40 -6.34E+OO 1 .05E+Ol U-235 143.76 10. 96 -3.84E-D1 2.58E-D1 1. 26E+OO 163.33 5.08 3.48E-01 2.99E+OO 185.71 57.20 -l.24E-01 2.58E-01 202 .11 1. 08 -3.14E+OO l .16E+Ol 205.31 5.01 -1.60E+OO 2.42E+OO Am-241 59.54 35.90 l. 12E+OO 3.03E+OO 3.03E+OO

   +    =  Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
   >    =  MDA value not calculated
   @    =  Half-life too short to be able to perform the decay correction
   ?    =  CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[557]

27-AUG-18-1001274A5.CNF Live Time :1200.000 sec 60 Real Time :1200. 900 sec start: l: . -0. O(kev) stop : 8192: 2047. 4(kev) Acq. start :Mon AUg 27 11: 23: 37 2018 55-50 45 40 35 V> +-' C:

s 8 30 25-20 15 ~

                          ~

I

                             ~

10 5-1000 2000 3000 4000 5000 6000 7000 8000 channel

         ~

ROI Type: 1 [558]

8/27/2018 11:20:16AM Page 1 of6 Analysis Report for 27-Aug-18-10013 B1-09100A-FSFC-067CV 0.0" - 0.5" 0.0" GAMMA SPECTRUM ANALYSIS Sample Identification  : 27-Aug-18-10013 Sample Description , B1-09100A-FSFC-067CV 0.0" - 0.5" o.o* Sample Type  : Puck Unit Sample Point Sample Size 9.620E+01 grams Facility  : Default Sample Taken On  : 8/22/2018 9:20:00AM Acquisition Started  : 8/27/2018 10:59:55AM Procedure  : Puck_half_inch Operator  : jwelch Detector Name  : P11314 Geometry  : Puck_half_inch Live Time  : 1200.0 seconds Real Time  : 1200.3 seconds Dead Time  : 0.02% Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 120- 8192 Peak Area Range (in channels)  : 120-8192 Identification Energy Tolerance . 1.000 keV Energy Calibration Used Done On . 12/15/2017 Efficiency Calibration Used Done On . 8/27/2018 Efficiency Calibration Description Sample Number  : 49649 Certificate Name '. Eu155-Na22 Certificate Date  : 12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 11 :20:09AM Peak Analysis From Channel  : 120 DATA VALIDATED Peak Analysis To Channel  : 8192 DATE 9~2-rr [559] ~~

8/27/2018 11:20:16AM Page 2 of6 Analysis Report for 27-Aug-18-10013 B1-091 OOA-FS FC-067CV 0.0" -0.5" 0.0" Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) 1 238.90 951 - 960 955.19 2 .40E+01 15.26 3.00E+Ol 0 . 52 2 583. 17 2326 - 2335 2330.81 1. 25E+Ol 8.52 5.00E+OO 0.28 3 609.22 2429 - 2441 2434.90 2.20E+Ol 11 . 90 9.94E+OO 0.40 4 1460.40 5833 - 5845 5839.55 3.23E+01 14 .50 1.55E+01 0.35 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi!grams) Uncertainty K-40 0. 97 1460. 82

• 10 .66 4.62E+OO 2.12E+OO Tl-208 1. 00 583.19
• 85 .00 1. 15E-01 7. 96E-02 Pb-212 0. 98 115. 18 0 .60 238.63
• 43.60 2. 17E-01 1 .43E-01 300.09 3.30 Bi- 214 0 .99 609.32
• 45.49 3. 91E-01 2. 17E-01 768.36 4 .89 806. 18 1. 26 934.06 3 .11 1120.29 14.92 1155. 21 1. 63 1238.12 5.83 1280.98 1. 43 1377.67 3.99 1385.31 0. 79

[560]

8/27/2018 11 :20:16AM Page 3 of6 Analysis Report for 27-Aug-18-10013 81-091 OOA-FSFC-067CV 0.0" - 0.5" 0.0" Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty Bi-214 0 .99 1401.52 1. 33 1407.99 2.39 1509.21 2 .13 1661.27 1. 05 1729.59 2.88 1764.49 15 .30 1847.43 2.03 2118. 51 1. 16

     * = Energy line found in the spectrum.
     - = Manually added nuclide.
     ? = Manually edited nuclide.
     @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold= 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide                          Nuclide                       Wt mean                Wt mean     Comments Name                                Id                         Activity                Activity Confidence                                           Uncertainty (pCilgrams)

K-40 0 . 972 4.62E+OO 2. 12E+OO Tl- 208 1. 000 1. 15E-01 7.96E-02 Pb-212 0 .989 2.17E-01 1. 43E-01 Bi-214 0 .999 3.91E-01 2.17E-01

      ? = 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 .000sigma

[561]

8/27/2018 11 :20: 16AM Page 4 of6 Analysis Report for 27-Aug-18-10013 B1-091 OOA-FSFC-067CV 0.0" - 0.5" 0.0" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 11 :20:09AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 8192 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCi!grams) (pCl/grams) (keV) An Pk 511. 00 100.00 3.08E-01 2.64E-01 2.64E-01 BE-7 477.60 10.44 7.31E-01 l. 63E+OO 1. 63E+OO + K-40 1460.82

• 10.66 4 .62E+OO 2.60E+OO 2.60E+OO Co-60 1173.23 99.85 4.34E-02 2.0lE-01 2.0lE-01 1332.49 99.98 9.89E-02 2.20E-01 Nb-94 702.65 99.81 l . llE-01 2.04E-01 2.04E-01 871.09 99.89 8.67E-02 2.19E-01 Ag-108m 79.13 6.60 2.13E+OO 1. 56E-Ol 3.45E+OO 433.94 90.50 2 . 91E-02 1.56E-01 614.28 89.80 -1.65E-01 2.lSE-01 722.94 90.80 1.llE-01 l. 90E-01 Sb-125 176.31 6.84 -3.39E-01 3.92E-01 1. 13E+OO 380.45 1. 52 2.48E+OO 9.80E+OO 427.87 29.60 -2.07E-01 3.92E-01 463.36 10. 49 -8.30E-01 1.26E+OO 600.60 17.65 1.25E-01 8.86E-01 606.71 4.98 3.88E+OO 5.21E+OO 635.95 11. 22 7.70E-01 1. 7 8E+OO 671. 44 1. 79 3.13E-01 7 . 59E+OO

[562]

8/27/2018 11:20:16AM Page 5 of6 Analysis Report for 27-Aug-18-10013 B1-09100A-FSFC-067CV 0.0" - 0.5 0.0" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCJ/grams) (pCilgrams) (pCilgrams) (keV) Ba-133 79.61 2.65 2.46E+OO 2.47E-01 8.14E+OO

81. 00 32.90 -1 .00E+OO 5.08E-01 276. 40 7 .16 -1.30E+OO 1. llE+OO 302 . 85 18.34 -l.30E-Ol 6.92E-01 356. 01 62.05 -1.90E-01 2.47E-0 1 383.85 8.94 8.36E-01 1.54E+OO Cs-134 475.36 1. 48 -1.73E+OO 1. BOE-01 l.06E+Ol 563.25 8.34 3.44E-01 1.85E+OO 569.33 15.37 -l.60E-02 9.43E-01 604.72 97.62 -4.59E-02 2.30E-01 795.86 85.46 -3.72E-02 1. BOE-01 801.95 8.69 9.15E-01 1 .88E+OO 1038. 61 0.99 6.46E+OO 2.08E+Ol 1167.97 1. 79 -1.23E+Ol 9.81E+OO 1365 .19 3.02 3.36E+OO 7.46E+OO Cs-137 661.66 85 .10 l.76E-0 1 2 . 62E-Ol 2.62E-01 Eu-152 121.78 28.67 -6.69E-02 3.06E-01 3.06E-01 244.70 7.61 7.85E-01 1. 70E+OO 295.94 0.45 3.33E+OO 2.83E+Ol 344.28 26.60 3.55E-01 5.78E-01 367.79 0.86 6.35E+OO l .67E+Ol 41 1.12 2.24 1. OOE+OO 5.21E+OO 443.96 2.83 9.82E-01 4.52E+OO 488.68 0.42 3.66E+OO 3.05E+Ol 563.99 0.49 -1.48E+Ol 3.03E+Ol 586.26 0.46 3.70E+OO 4.51E+Ol 678.62 0.47 -5. llE+OO 2.89E+Ol 688.67 0.86 -6.92E+OO 1 .51E+Ol 719.35 0.28 1 . 71E+Ol 6.61E+Ol 778.90 12. 96 -8.lOE-01 l. 09E+OO 810.45 0.32 -7.53E+Ol 3.00E+Ol 867.37 4.26 -1.88E+OO 4.44E+OO 919.33 0.43 9.21E+OO 3.98E+01 964. 08 14.65 1. 35E-01 1.55E+OO 1085.87 10.24 1. 68E-01 1. 97E+D0 1089.74 1. 73 -7.80E+0D 1. lOE+Ol 1112.07 13.69 -5.52E-01 1. 41E+OO 1212.95 1. 43 -3.93E+OO 1. 52E+Ol 1249.94 0.19 5.71E+Ol 1. 17E+02 1299.14 1. 63 5.97E+OO 1.33E+Ol 1408.01 21.07 4 .92E-01 1.09E+OO 1457.64 0.50 l. 46E+02 1. 10E+02 1528 .10 0.28 l .69E+Ol 6.30E+Ol Eu-1 5 4 123.07 40.40 -l .39E-02 2 , 38E-01 2.38E-01 247.93 6.89 -6.45E-01 1. 61E+OO 591.76 4. 95 -3.00E+OO 2.76E+OO 692.42 1. 78 6.0lE+OO 9.77E+OO 723. 30 20.06 2.0lE-01 8.60E-01 756.80 4.52 -1. 96E+OO 3.27E+OO 873.18 12.08 4.14E-01 1.92E+OO 996.29 10.48 5.91E-01 2.07E+OO

[563]

8/27/2018 11:20:16AM Page 6 of6 Analysis Report for 27-Aug-18-10013 B1-091 OOA-FSFC-067CV 0.0" - 0.5" 0.0" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV) Eu-154 1004.76 18.01 1.75E-01 2.38E-01 l.06E+OO 1274.43 34.80 -5.16E-02 4.90E-01 1596.48 1. 80 -2.07E+OO 7.0SE+OO Eu-155 45.30 1. 31 7.04E+OO 4. 72E-01 2.91E+Ol

60. 01 1. 22 5.67E+OO 2.84E+Ol 86.55 30.70 l.55E-01 4 .98E-01 105.31 21.10 -5.78E-02 4 . 72E-01 Ra-226 186.21 3.64 2.06E+OO 3.00E+OO 3.00E+OO Pa-231 27.36 10.30 2.34E+OO 3.24E+OO 3.24E+OO 283.69 1. 70 4.20E+OO 6.84E+OO 300.07 2.47 -5.70E+OO 4 . 72E+OO 302.65 2.20 6.97E-Ol 5.76E+OO 330.06 1. 40 5.84E+OO 9.48E+OO U-235 143.76 10 . 96 -3.06E-01 l .90E-01 8.31E-01 163.33 5.08 7.45E-01 2.07E+OO 185. 71 57.20 1.52E-01 1.90E-01 202 .11 1. 08 -1.40E+OO 9.13E+OO 205.31 5.01 -1.lOE+OO 2.15E+OO Am-241 59.54 35.90 -2.09E-01 9.61E-01 9.61E-01

   +    ;;;;  Nuclide identified during the nuclide identification
    *      = Energy line found in the spectrum MDA value not calculated Half-life too short to be able to perform the decay correction
   ?    ;;;;

CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level [564]

0000049649 .CNF Live Time :1200.000 sec Real Tiae :1200.270 sec 60 start: 1: -0. O(kev) stop : 8192: 2047 .S(kev) Acq. start :Mon Aug 27 10: 59: 55 2018 55 50 45 40 35 VI C: 8 30 25 20 15 CD D.. 10 """" C> ' 0 CD 5 0 1000 2000 3000 4000 5000 6000 7000 8000 channel

        ~

ROI Type: 1 [565]

8/27/2018 11 :44:05AM Page 1 of6

~ ~pex--Gamma Analysis Report for     27-Aug-18-10014 B1-091 OOA-FSFC-067CV       0.0" - 0.5" 0.5" GAMMA SPECTRUM ANAL YS/S Sample Identification                         : 27-Aug-18-10014 Sample Description                            : B1-09100A-FSFC-067CV  0.0" - 0.5"   0.5" Sample Type                                  : Puck Unit Sample Point Sample Size                                  : 9.620E+01 grams Facility

• Default Sample Taken On
• 8/22/2018 9:20:00AM Acquisition Started
• 8/27/2018 11 :23:43AM Procedure
• Puck_half_inch Operator
• jwelch Detector Name
• P11314 Geometry
• Puck_half_inch Live Time  : 1200.0 seconds Real Time
• 1200.4 seconds Dead Time  ; 0.03 %

Peak Locate Threshold  : 3.00 Peak Locate Range {in channels)  : 120 - 8192 Peak Area Range (in channels)  : 120 - 8192 r Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 12/15/2017 Efficiency Calibration Used Done On  : 8/27/2018 Efficiency Calibration Description Sample Number  : 49653 Certificate Name  : Eu155-Na22 Certificate Date  : 12/22/2008 12:00:00PM PEAK ANAL YS/S REPORT Peak Analysis Performed on  : 8/27/2018 11:44:01AM DATA VALIDATED Peak Analysis From Channel Peak Analysis To Channel

120

8192 DATE Cj-2 -It:

[566] (2,~ ~~?;;,,/

8/27/2018 11 :44:05AM Page 2 of6 Analysis Report for 27-Aug-18-10014 B1-091 OOA-FSFC-067CV 0.0" - 0.5" 0.5" Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts {keV) 1 238.76 950 - 961 954.64 4.43E+Ol 16.96 2.15E+Ol 0.8 9 2 1460.56 5835 - 58 4 6 5840.17 2.75E+Ol 11. 60 5.03E+OO 0 .39 M = First peak in a multiplet region m = Other peak in a multiplet region F ;;; Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K-40 0.98 1460.82

• 10.66 3. 94E+OO 1.70E+OO Pb-212 0.99 115 .18 0.60 238.63
• 43.60 4. 0lE-01 1 .67E-01 300.09 3.30

      * ;;; Energy line found in the spectrum.
      * ;;; Manually added nuclide.
      ? = Manually edited nuclide.
    @ = Energy line not used for Weighted Mean Activity Energy Tolerance: 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma

[567]

8/27/2018 11 :44:05AM Page 3 ofti Analysis Report for 27-Aug-18-10014 B1-09100A-FSFC-067CV 0.0" - 0.5" 0.5" INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0 .9 89 3 .9 4E+OO 1.70E+OO Pb-212 0. 99 7 4.0lE- 01 1.67E- 01

       ?  :;; 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 2.000sigma

[568]

8/27/2018 11 :44:0SAM Page 4 of6 Analysis Report for 27-Aug-18-10014 B1-09100A-FSFC-067CV o.o* - 0.5" 0.5" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 11:44:01AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 8192 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB Nuclide Energy Yield{%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCi!grams) (pCilgrams) (keV) An Pk 511. 00 100.00 3.30E-01 2. 72E-01 2. 72E-01 BE-7 477.60 10. 44 6.84E-01 1. 43E+OO 1. 43E+OO + K-40 1460.82

• 10.66 3.94E+OO 1. 62E+OO 1 .62E+OO Co-60 1173.23 99.85 -2.00E-01 2.13E-01 2.13E-01 1332.49 99.98 l.41E-01 2.SSE-01 Nb-94 702.65 99.81 1.17E-01 1 .64E-01 1. 82E-01 871. 09 99.89 7.36E-02 1.64E-01 Ag-108m 79.13 6.60 -2.70E-01 1 .43E-01 2.88E+OO 433.94 90.50 -2.41E-02 1.43E-01 614.28 89.80 -l.81E-01 2.48E-01 722. 94 90.80 1. 26E-01 2.40E-01 Sb-125 176.31 6.84 3.95E-01 3.60E-01 1. 30E+OO 380.45 1. 52 -9.69E-01 7.74E+OO 427.87 29.60 - 1 .56E-01 3.60E-01 463.36 10 .49 1 .44E+OO 1.62E+OO 600.60 17 .65 -7.13E-02 8.54E-01 606.71 4.98 1.96E+OO 5.21E+OO 635.95 11. 22 1.12E-02 1.60E+OO 671.44 1. 79 -8.53E-01 8.0lE+ OO

[569]

8/27/2018 11:44:05AM Page 5 of6 Analysis Report for 27-Aug-18-10014 B1-091 OOA-FS FC-067CV 0.0" - 0.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCUgrams) (pCilgrams) (keV) Ba-133 79.61 2.65 4.47E-01 2.35E-01 7.15E+OO 81.00 32.90 -1. 66E-01 4 .95E-Ol 276.40 7.16 l. 13E-01 1. 50E+OO 302.85 18.34 3.13E-01 7.16E-01 356.01 62.05 -l. 49E-01 2.35E-01 383.85 8.94 -9.50E-02 1. 36E+OO Cs-134 475.36 1. 48 4.06E-01 2.38E-01 9.46E+OO 563.25 8.34 -8.05E-01 l.66E+OO 569.33 15.37 -l.08E+OO 9.05E-01 604. 72 97.62 -8.55E-02 2.38E-01 795.86 85.46 6.65E-02 2.55E-01 801.95 8.69 -8.68E-01 l.88E+OO 1038.61 0 .99 -l.12E+Ol 1. 35E+Ol 1167. 97 1. 79 -8.22E+OO l.19E+Ol 1365. 19 3.02 1. 92E+OO 5.98E+OO Cs-137 661. 6 6 85.10 1. 20E-01 2.29E-01 2.29E-01 Eu-152 121.78 28.67 -l.17E-01 2.95E-01 2.95E-01 244.70 7.61 l.03E+OO l. 70E+OO 295.94 0.45 5.18E+OO 2.93E+Ol 344.28 26.60 -l.81E-01 4. 07E-Ol 367.79 0.86 -4.94E+OO 1.40E+Ol 411.12 2.24 6.36E-02 6.64E+OO 443. 96 2.83 1. 76E+OO 5.45E+OO 488.68 0.42 2.03E+OO 2.93E+Ol 563.99 0.49 -2.19E+Ol 2.55E+Ol 586.26 0.46 8.52E+OO 4.25E+Ol 678.62 0.47 -3.19E+Ol 3.75E+Ol 688.67 0.86 3.39E+OO 2.15E+Ol 719. 35 0.28 4.26E+Ol 6.61E+Ol 778.90 12.96 2.62E-02 1. 02E+OO 810.45 0. 32 -3.76E+Ol 4. 23E+Ol 867.37 4.26 -2.35E+OO 4. 04E+OO 919.33 0. 43 -2.21E+Ol 3.98E+Ol 964.08 14. 65 -2.51E-Ol l.27E+OO 1085.87 10. 24 -2.04E+OO l.63E+OO 1089.74 1. 73 2.84E+OO 8.84E+OO 1112. 07 13. 69 -1.lOE+OO l.24E+OO 1212.95 1. 43 -3.93E+OO 8.94E+OO 1249.94 0.19 -3.03E+Ol l.17E+02 1299 .14 1. 63 9.95E-01 l.25E+Ol 1408.01 21. 07 4.22E-01 1. 03E+OO 1457.64 0.50 7.26E+Ol 9.23E+Ol 1528 .10 0.28 l. 13E+Ol 5.44E+Ol Eu-154 123.07 40.40 -2.66E-03 2.2":'E-01 2.27E-01 247.93 6.89 7.49E-01 1 .67E+OO 591.76 4 .95 -2.43E+OO 2.63E+OO 692.42 1. 78 2.48E+OO 9.04E+OO 723. 30 20.06 5.82E-01 l.09E+OO 756.80 4 .52 -l.17E-01 3.63E+OO 873.18 12.08 6.97E-01 l .43E+OO 996.29 10 .48 3.15E-01 1. 72E+OO [570]

8/27/2018 11:44:05AM Page 6 of6 Analysis Report for 27-Aug-18-10014 B 1-091 OOA-FSFC-067CV 0.0" -0.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi!grams) (pCilgrams) (pCilgrams) (keV) Eu-154 1004.76 18.01 -1.37E-01 2.27E-01 9.44E-01 1274.43 34.80 2.36E-Ol 5.75E-01 1596.48 1. 80 -4.59E+OO 7.05E+OO Eu-155 45.30 1. 31 8.13E+OO 4.38E-01 3.00E+Ol

60. 01 1.22 -1. 50E+Ol 2.64E+Ol 86.55 30.70 1. 88E-01 4.92E-01 105.31 21.10 -2.51E-02 4.38E-01 Ra-226 186.21 3.64 1 .54E+OO 3.14E+OO 3.14E+OO Pa-231 27.36 10.30 1. 50E+OO 4.15E+OO 4.15E+OO 283.69 1. 70 2.96E+OO 6.71E+OO 300.07 2.47 -5.51E+OO 4. 72E+OO 302.65 2.20 l .62E+OO 5.86E+OO 330.06 1. 40 5.90E-01 8.93E+OO U-235 143.76 10. 96 -4.61E-01 1 . 95E-01 7.91E-01 163.33 5.08 7.14E-Ol 2.16E+OO 185. 71 57.20 8.80E-02 1.95E-01 202 .11 1. 08 -4.98E+OO 8.82E+OO 205.31 5.01 -9.82E-01 1 .78E+OO Am-241 59.54 35.90 -1.82E-01 9.26E-01 9.26E-Ol

   +    =  Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
   >    -  MDA value not calculated
   @    =  Half-life too short to be able to perform the decay correction
   ?    =  CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[571]

0000049653.CNF Live Time :1200.000 sec Real Time :1200.360 sec 60 start: 1: -0.0(kev) stop : 8192 :2047. B(kev) Acq. start :Mon AUg 27 11: 23 :43 2018 55-50-45-40-35-Ill +-' C: ~ 8 30-25-20-15- ..."" I 10-5- 1000 2000 3000 4000 5000 6000 7000 8000 channel

       ~

ROI Type: l [572]

8/27/2018 11:20:12AM Page 1 of6

             ~pex-Gamma Analysis Report for     27-Aug-18-10015 B1-09100A-FSFC-068CV        0.0" - 0.5" 0.0" GAMMA SPECTRUM ANALYSIS Sample Identification                         : 27-Aug-18-10015 Sample Description                            : B1-09100A-FSFC-068CV  0.0" - 0.5"   0.0" Sample Type                                   : Puck Unit Sample Point Sample Size                                      8.219E+01 grams Facility                                     . Default Sample Taken On

• 8/22/2018 1:40:00PM Acquisition Started  : 8/27/2018 11 :00:02AM Procedure  : Puck_half_inch Operator  : jwelch Detector Name  : 352 Geometry  : Puck_half_inch Live Time  : 1200.0 seconds Real Time  : 1200.2 seconds Dead Time  : 0.02 %

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 120- 8192 Peak Area Range (in channels}  : 120- 8192 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 3/12/2018 Efficiency Calibration Used Done On  : 8/27/2018 Efficiency Calibration Description  : install Sample Number 49650 Certificate Name . Eu 155-Na22 Certificate Date . 1/7/2013 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 11:20:07AM Peak Analysis From Channel  : 120 DATA VALIDATED Peak Analysis To Channel  : 8192 DATE c; -Z-lk [573] a?:111:Ja+Tl~~~ ~~ .

8/27/2018 11:20:12AM Page 2 of6 Analysis Report for 27-Aug-18-10015 B1-09100A-FSFC-068CV 0.0" - 0.5" 0.0" No peak analysis results available for reporting purposes. No background subtract performed on this spectrum. w NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty

     * = Energy line found in the spectrum.
      - = Manually added nuclide.
     ? = Manually edited nuclide.
     @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold ;; 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide                            Nuclide                       wt mean                 wt mean     Comments Name                                 Id                           Activity                Activity Confidence                                             Uncertainty (pCilgrams)

[574]

8/27/2018 11 :20:12AM Page 3 of6 Analysis Report for 27-Aug-18-10015 B1-09100A-FSFC-068CV 0.0" - 0.5" 0.0"

       ?  = 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 2.000sigma

[575]

8/27/2018 11 :20: 12AM Page4 of6 Analysis Report for 27-Aug-18-1 0015 B1-09100A-FSFC-068CV 0.0" - 0.5" 0.0" No peak search results available for nuclide analysis. NUCLIDE MDA REPORT Nuclide Library Used  : C :\Can berra\Apex\Root\Defau lt\Library\ZION LI B-B NL. NLB Nuclide Energy Yield{%) Activity NuclideMDA LineMDA Name (pCUgrams) (pCi/grams) (pCilgrams)

                          * (keV)

An Pk 511. 00 100.00 3 .13E-01 3.lSE-01 3.15E-01 BE-7 477.60 10.44 9.22E-02 1. 99E+OO 1.99E+OO K-40 1460 .82 10.66 5.66E+OO 5 .13E+OO 5.13E+OO Co-60 1173 .23 99.85 -1. 26E-02 2.21E-01 2.21E-Ol 1332.49 99.98 1. 48E-01 2.84E-01 Nb-94 7 02. 65 99.81 -6.35E-02 2.15E-01 2.15E-01 871.09 99.89 7.24E-02 2.40E-01 Ag-108m 79.13 6.60 -1 .38E+OO 1. 86E-01 3. 72E+OO 433.94 90.50 8.0lE-02 2.lOE-01 614.28 89.80 1.64E-01 3.37E-01 722. 94 90.80 8.36E-02 l.86E-01 Sb-125 176.31 6.84 4.57E-01 6.lOE-01 2.0lE+OO 380.45 1. 52 -1.34E+00 9.89E+OO 427.87 29.60 2.77E-01 6.lOE-01 463.36 10 .49 -4.lOE-01 1.79E+OO 600.60 17 .65 -2.64E-01 1. 02E+OO 606. 71 4.98 3. 71E+OO 6.27E+OO 635.95 11.22 -3.99E-01 1. 53E+OO 671. 44 1. 79 4.33E-01 1.13E+Ol Ba-133 79.61 2. 65 -1.71E+OO 3.37E-01 9.lOE+OO

81. 00 32.90 2.31E-01 6.89E-01 276.40 7.16 1. 31E+OO 1.91E+OO 302.85 18.34 3.21E-01 8.lOE-01 356.01 62.05 8.63E-02 3.37E-01 383.85 8.94 1. 48E-01 1. 69E+OO Cs-134 475.36 1. 48 -4.23E+OO 2 . 45E-01 1 .23E+Ol 5 63. 25 8.34 -1. 69E+OO 2.05E+OO 569.33 1 5 .37 -3.63E-01 1 .55E+OO 604.72 97.62 -1 .76E-01 2.64E-01 795.86 85.46 3.40E-02 2.45E-01 80 1. 95 8.69 -1.73E+OO 1 .97E+OO 1038.61 0 .99 8.45E+OO 2.06E+Ol 1167.97 1. 79 -1.16E+OO 1. 05E+01 1365.19 3.02 5.58£-01 4.28E+OO

[576]

8/27/2018 11:20:12AM Page 5 of6 Analysis Report for 27-Aug-18-10015 B1-091 OOA-FS FC-068CV 0.0" -0.5" 0.0" Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCUgrams) (pCilgrams) (pCi!grams) (keV) Cs-137 661.66 85.10 1. 85E-01 3.33E-01 3.33E-01 Eu-152 121.78 28.67 -6.94E-04 3.95E-01 3.95E-Ol 244.70 7.61 -5.81E-01 1. 83E+OO 295.94 0.45 8.85E+OO 3.62E+Ol 344.28 26.60 -7.73E-01 5.22E-01 367.79 0.86 -5.02E+OO 1.74E+Ol 411 .12 2.24 -5.95E+OO 6.27E+OO 443.96 2.83 4.46E-01 5.94E+OO 488.68 0.42 -5.28E+OO 4.05E+Ol 563.99 0.49 1.60E+Ol 3.74E+Ol 586.26 0.46 2.80E+Ol 4.73E+Ol 678.62 0.47 9.49E+OO 3.62E+Ol 688.67 0.86 -2.03E+Ol 2.38E+Ol 719.35 0.28 -2.81E+Ol 4.83E+Ol 778.90 12.96 9.34E-01 1. 94E+OO 810.45 0.32 2.35E+OO 5.69E+Ol 867.37 4.26 -1. 92E-01 4.98E+OO 919. 33 0.43 -2.89E+Ol 4.37E+Ol 964. 08 14.65 3.18E-01 2.04E+OO 1085.87 10.24 8.38E-01 2.04E+OO 1089.74 1. 73 '.2.03E+OO 1 .43E+Ol 1112. 07 13.69 9.56E-01 1 .83E+OO 1212.95 1. 43 8.64E+OO l .78E+Ol 1249.94 0.19 5.83E+Ol 1. 30E+02 1299.14 1. 63 4.97E+OO 1.35E+Ol 1408.01 21.07 2.45E-Ol 9.14E-01 1457.64 0.50 1.23E+02 1.10E+02 1528.10 0.28 1. 96E+Ol 7.31E+Ol Eu-154 123.07 40.40 -4.09E-02 2.74E-Ol 2.74E-01 247.93 6.89 3.15E-01 2.07E+OO 591.76 4.95 -1.15E+OO 3.29E+OO 692.42 1. 78 -1.59E+OO 1. 23E+Ol 723. 30 20.06 3.79E-01 8.42E-01 756.80 4.52 2.48E+OO 4.47E+OO 873.18 12.08 5.36E-01 1. 92E+OO 996.29 10.48 1.88E-01 2.42E+OO 1004.76 18. 01 6.79E-01 1. 30E+OO 1274. 43 34.80 -5.SOE-02 6.23E-01 1596.48 1. 80 3.19E+OO 1.19E+Ol Eu-155 45.30 1. 31 -4.37E+OO 5 . 30E-01 4.17E+Ol 60.01 1. 22 -7.93E+OO 4.52E+Ol 86.55 30.70 7.62E-04 5.42E-01 105.31 21.10 -1. 60E-01 5.30E-01 Ra-226 186.21 3.64 6.29E-01 4.26E+OO 4.~6E+OO Pa-231 27.36 10 .30 1 .08E+Ol 5.97E+OO 8.81E+OO 283.69 i. 70 -i. 691'.:+00 8.00E+OO 300.07 2.47 -1.21E+OO 5.97E+OO 302.65 2.20 1.18E-01 6.61E+OO 330.06 1. 40 5.89E+OO 1 .31E+Ol U-235 143.76 10. 96 2.50E-01 2 , 78E-01 1. 16E+OO 163. 33 :i. 0 8 1.86E-01 2.26£+00 [577]

8/27/2018 11:20:12AM Page 6 of6 Analysis Report for 27-Aug-18-10015 81-091 OOA-FSFC-068CV 0.0" - 0.5" 0.0" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCUgrams) (pCilgrams) (keV) U-235 185 .-71 57.20 1. 41E-01 2.78E-01 2.78E-01 202 .11 1. 08 -1.48E+OO 1. 27E+Ol 205.31 5.01 -1.37E+OO 2.61E+OO Am-241 59.54 35.90 -9.BSE-01 1 .51E+OO 1.51E+OO

   +    = Nuclide identified during the nuclide identification
    *    = Energy line found in the spectrum
   >    = MDA value not calculated
   @    =  Half-life too short to be able to perform the decay correction
    ?   = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[578]

0000049650.CNF Live Tiae :1200.000 sec Real Time :1200.220 sec Start: 1: -0. 2{kev) Stop : 8192:2046.9(kev) ACq. Start : Mon Aug 27 11: 00: 02 2018 55 50 45 40 35 Vl +-' C: ~ 8 30 25 20 15 10 5 1000 2000 3000 4000 5000 6000 7000 8000 [579] channel

8/27/2018 11:43:57AM Page l of6

              ~pex-Gamma Analysis Report for     27-Aug-18-10016 B1-09100A-FSFC-068CV         0.0" -0.5"  0.5" GAMMA SPECTRUM ANAL YS/S Sample Identification                          : 27-Aug-18-10016 Sample Description                             : B1-09100A-FSFC-068CV  0.0" - 0.5"   0.5" Sample Type                                    : Puck Unit Sample Point Sample Size                                       8.219E+01 grams Facility                                      : Default Sample Taken On

• 8/22/2018 1:40:00PM Acquisition Started
• 8/27/2018 11:23:50AM Procedure
• Puck_half_inch Operator jwelch Detector Name 352 Geometry Puck_half_inch Live Time 1200.0 seconds Real Time 1200.2 seconds Dead Time
• 0.02 %

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) 120- 8192 Peak Area Range (in channels) 120 - 8192 Identification Energy Tolerance

• 1.000 keV Energy Calibration Used Done On  : 3/12/2018 Efficiency Calibration Used Done On  : 8/27/2018 Efficiency Calibration Description  : install Sample Number  : 49654 Certificate Name  : Eu155-Na22 Certificate Date  : 1/7/2013 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on  : 8/27/2018 11 :43:53AM Peak Analysis From Channel  : 120 Peak Analysis To Channel  : 8192

[580]

8/27/2018 11:43:57AM Page2 of6 Analysis Report for 27-Aug-18-10016 B1-09100A-FSFC-068CV 0.0" - 0.5" 0.5" Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) 1 1461.17 5839 - 5852 5845.07 2.SOE+Ol 11.17 4.00E+OO 0.43 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma No background subtract performed on this spectrum. NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV} (pCilgrams) Uncertainty K-40 0.98 1460.82

• 10.66 4.16E+OO l.89E+OO

     * = Energy line found in the spectrum.
      - = Manually added nuclide.
     ? = Manually edited nuclide.
     @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma

[581]

8/27/2018 11:43:57AM Page 3 of6 Analysis Report for 27-Aug-18-10016 B1-09100A-FSFC-068CV 0.0" - 0.5" 0.5" INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0.980 4.16E+OO 1.89E+OO

       ?  = 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 2.000sigma

[582]

8/27/2018 11:43:57AM Page4 of6 Analysis Report for 27-Aug-18-10016 B 1-091 OOA-FSFC-068CV 0.0" - 0.5" 0.5" UNIDENTIFIED PEAKS Peak Locate Performed on  : 8/27/2018 11 :43:53AM Peak Locate From Channel  : 120 Peak Locate To Channel  : 8192 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m :a Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Default\Library\ZION LIB-BNL.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCUgrams) (pCilgrams) (pCi!grams) (keV) An Pk 511. 00 100.00 9.32E-02 3.19E-01 3.J,9E-01 BE-7 477.60 10.44 l.79E-01 1.71E+OO 1.71E+OO + K-40 1460.82

• 10.66 4.16E+OO l.88E+OO 1.88E+OO Co-60 1173.23 99.85 -l.32E-01 1.26E-01 2.05E-01 1332.49 99.98 -4.llE-02 1. 26E-01 Nb-94 702.65 99.81 -3.33E-02 1 .92E-01 2.22E-01 871. 09 99.89 -6.47E-02 1. 92E-01 Ag-108m 79.13 6.60 -5.24E-01 2.lOE-01 3.86E+OO 433.94 90.50 1.45E-01 2.lOE-01 614.28 89.80 l.48E-01 2.89E-01 722. 94 90.80 -1.31E-01 2.56E-01 Sb-125 176.31 6.84 -6.81E-01 6.24E-01 1. 68E+OO 380.45 1. 52 -1.0lE+Ol 8.09E+OO 427.87 29.60 6.06E-02 6.24E-01 463.36 10.49 -l.88E-01 1.70E+OO 600.60 17.65 5.27E-01 1. 32E+OO 606.71 4.98 -3.36E-01 5.37E+OO 635.95 11. 22 9.92E-01 2. 0lE+OO 671.44 1. 79 2.89E+OO 7.85E+OO

[583]

8/27/2018 11:43:57AM Page S of6 Analysis Report for 27-Aug-18-10016 B1-091 OOA-FSFC-068CV o.o* -o.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCUgrams) (pCi/grams) (pCl/grams) (keV) Ba-133 79.61 2.65 4.37E-01 3.07E-01 9.56E+OO

81. 00 32.90 -8.23E-01 6.80E-Ol 276.40 7.16 -4.69E-01 1.83E+OO 302.85 18.34 -1.14E-02 7.94E-01 356.01 62.05 -1.15E-01 3.07E-01 383.85 8.94 -3.97E-01 1 .64E+OO Cs-134 475.36 1. 48 -5.40E+OO 2.35E-01 1 .lOE+Ol 563.25 8.34 -5.47E-02 2.21E+OO 569.33 15.37 -5.68E-01 1 .12E+DO 604. 72 97. 62 1.45E-01 2.83E-Ol 7 95. 8 6 85.46 4.00E-02 2.35E-01 801.95 8.69 -1.0lE-01 2.53E+OO 1038.61 0.99 9.86E+OO 2.19E+Ol 1167.97 1. 79 -1.47E+OO 1.05E+Ol 1365.19 3.02 2.23E+OO 6. 96E+OO Cs-137 661.66 85.10 l,95E-01 3.04E-01 3.04E-01 Eu-152 121. 78 28.67 -2.89E-02 4.02E-01 4.02E-01 244.70 7.61 -3.78E-01 1. 86E+OO 295.94 0.45 9.87E+OO 3.73E+Ol 344.28 26.60 1. 18E-02 5.49E-Ol 367.79 0.86 5 .17E+OO l .69E+01 411.12 2.24 -3.25E+OO 8.79E+OO 443. 96 2.83 -2.02E+OO 5.24E+OO 488.68 0.42 -2.04E+Ol 3.51E+Ol 563.99 0.49 6.95E+OO 3.86E+Ol 586.26 0.46 3.75E+Ol 5.46E+Ol 678.62 0.47 l.76E+Ol 3.62E+Ol 688.67 0.86 1.71E+Ol 2.54E+Ol 719.35 0.28 3.39E+Ol 9.43E+Ol 778.90 12. 96 -2.42E-01 1. 52E+OO 810.45 0.32 2.48E+OO 5.69E+Ol 867.37 4.26 2.88E+OO 5.20E+OO 919.33 0.43 -6.35E+Ol 4.92E+Ol 964.08 14.65 9.92E-Ol 1. 69E+OO 1085.87 10.24 -l.08E+OO l.90E+OO 1089.74 1. 73 4.97E+OO 1.21E+Ol 1112. 07 13. 69 -8.87E-01 1.65E+OO 1212.95 1. 43 -1.05E+Ol 1.35E+Ol 1249.94 0.19 -5.89E+OO 1.22E+02 1299.14 1. 63 -2.73E+OO 1.35E+Ol 1408.01 21.07 -4.29E-01 7.89E-01 1457.64 0.50 8. 96E+Ol 1. 01E+02 1528.10 0.28 2.61E+Ol 8.15E+Ol Eu-154 123.07 40.40 -1.17E-01 2 , 89E-01 2.89E-01 247.93 6.89 -4.35E-Ol 1. 87E+OO 591. 76 4.95 -2.19E+OO 3.58E+OO 692.42 1. 78 -5.56E+OO 1. 27E+Ol 723. 30 20.06 6.16E-01 1.26E+OO 756.80 4.52 2.23E-+00 4.28E+OO 873.18 12.08 4.97E-01 1.92E+OO 996.29 10.48 2.SOE-01 2.12Et00

[584]

8/27/2018 11:43:57AM Page 6 of6 Analysis Report for 27-Aug-18-10016 B1-091 OOA-FS FC-068CV 0.0" -0.5" 0.5" Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCi/grams) (pCi/grams) (keV) Eu-154 1004.76 18. 01 5.28E-01 2.89E-01 1 .18E+OO 1274.43 34.80 1. 31E-01 7 .13E-01 1596.48 1. 80 4. 25E+OO 1.33E+Ol Eu-155 45.30 1. 31 -1.74E+OO 6.02E-01 3.80E+Ol 60.01 1. 22 -2.88E+Ol 5.03E+Ol 86.55 30.70 2.39E-01 6. 73E-01 105.31 21.10 -8.68E-02 6.02E-01 Ra-226 186.21 3.64 l.35E+OO 4.lOE+OO 4. lOE+OO Pa-231 27.36 10.30 8.26E+OO 6.08E+OO 7.96E+OO 283.69 1. 70 4.0lE+OO 8.65E+DO 300. 07 2.47 -8.63E+OO 6.08E+OO 302.65 2.20 -2.87E+OO 6.34E+OO 330.06 1. 40 4.03E+OO 1. OlE+Ol U-235 143.76 10. 96 -4.74E-01 2.61E-01 1. OOE+OO 163.33 5.08 l.31E+OO 2.36E+OO 185.71 57.20 3.06E-02 2.61E-Ol 202 .11 1. 08 2.66E-02 1. 38E+Ol 205.31 5.01 1.77E-01 2.69E+OO Am-241 59.54 35.90 -6.72E-01 l , 68E+OO 1.68E+OO

    +   = Nuclide identified during the nuclide identification
    *     = Energy line found in the spectrum
    >   = MDA value not calculated
   @    ;   Half-life too short to be able to perform the decay correction
    ?   ;   CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[585]

0000049654.CNF Live Tiaie :1200.000 sec Real Time :1200.220 sec 60 start: 1: -0 .2(keV) stop : 8192: 2046. 9(kev) Acq. start :Mon Aug 27 11: 23: 50 2018 55-50-45-40-35-V) ,1,-1 C

I 8 30-25 20-15 10 5

1000 2000 3000 4000 5000 6000 7000 8000 channel

         ~

ROI Type: 1 [586]

ATTACHMENT 7 EBERLINE REPORTS [587]

EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD Q EBERLINE OAK RIDGE, TENNESSEE 37830

~                       ANALYTICAL                                                       PHONE (865) 481-0683 FAX (865) 483-4621 EBS-OR-44289 September 19, 2018 Patricia Giza Zion Solutions, LLC 101 Shiloh Blvd Zion, IL 60099 CASE NARRATIVE Work Order# 18-08150-0R SAMPLE RECEIPT This work order contains eight solid samples received 08/29/2018. Samples were analyzed for Total Strontium, Tritium, Nickel-63 and by Gamma Spectroscopy.

CLIENT ID LABID CLIENT ID LABID B 1-091 OOA-FSFC-067CV 18-08150-04 Bl-09100-FSWC-041CV 18-08150-08 Bl-09100A-FSWC-031CV 18-08150-05 Bl-09100A-FSFC-068CV 18-08150-09 B 1-091OOA-FSFC-001 CV 18-08150-06 B 1-091 OOA-FSWC-051 CV 18-08150-10 Bl-09100A-FSFC-010CV 18-08150-07 B 1-091 OO-FSFC-021 CV 18-08150-11 ANALYTICAL METHODS Total Strontium was analyzed using EIChroM Method SRWOl Modified. Tritium was performed using Method LANL ER-210 Modified. Nickel-63 was performed using Method ASTM 3500-Ni Modified. Gamma Spectroscopy was performed using EPA Method 901.1 Modified. Laboratory qualifiers are as follows: U - Result is less than the MDA. ANALYTICAL RESULTS Combined Standard Uncertainty is reported at I -sigma value. Minimum Detectable Activity (MDA) values for data represented in this report are sample-specific. MDA measurements are determined based on factors and conditions including instrument settings, aliquot size and matrix type. Page 1 of3 [588]

ANALYTICAL RESULTS CONTINUED TOTAL STRONTIUM Samples were prepared by digesting with acids as appropriate. Strontium recovery carriers were added to the samples. Chemical separations were conducted using selective extractions. Strontium precipitate was mounted on tared filter media. Chemical recovery was determined by Strontium carrier mass determinations. Samples were counted by gas flow proportional counting and corrected for Yttrium-90 ingrowth. Samples demonstrated acceptable results for all Total Strontium analyses. Strontium-90 results are reported from Total Strontium. 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 transferred into round-bottomed distillation flasks and attached to single stage stills. A portion of each middle distillation fraction was transferred to a liquid scintillation vial and diluted with tritium free water. 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 [589]

ANALYTICAL RESULTS CONTINUED GAMMA SPECTROSCOPY CONTINUED Samples demonstrated acceptable results for all gamma-emitting radionuclides as reported. Some samples demonstrated results that are greater than the method detection limit. These results are reported from the Canberra Gamma Apex "Nuclide MDA Report" and are not positive. These results are qualified as non-detect (U). The method blank demonstrated acceptable results for all radionuclides as reported. Results for the Cobalt-60, Cesium-13 7 and Potassium-40 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-137 laboratory control sample demonstrated an acceptable percent recovery. CERTIFICATION OF ACCURACY I certify that this data report 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

  --. desi1i~ee to be accurate as vg*/ed by the following signature.

\.

                 *-~--._                       /1
                                       -z:~7 /

__)

                              ~ . ,  0
                       ,,,_,                 )

M.R. McDougall Laboratory Manager Date: 9/19/2018 Eberline Analytical wants and encourages your feedback regarding our performance providing radioanalytical services. Please visit http://eberlineanalytical.com/ to provide us with feedback on our services. Page 3 of 3 [590]

Prittted: 9/19'/2818 11 :25 AM Page 1 of 12 Report To: Work Order Det<1ils: 18-08150 Eberline Analytical Patricia Giza Zion Solutions SOG:! Purchase Order: i 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Category:  ! ENVIRONMENTAL Zion, IL 60099 Sample Matrix: I so Lab Sample 1 Client Sample / Receipt I Analysis j Batch I II i Report ID I Type 1 ID Date [ Date  ! Date ' ID I Analyte Method Result I cu CSU MDA Qualifier Units 18-08150-01 LCS KNOWN 08/29/18 00:00 i 8/29/2018 I 9/2/2018 I 18-08150 J Tritium LANL ER-210 Modified I 2.22E+02 I 8.00E+OO I pCi/g t-1_8_-0_8_1_50-_0_1--+J__L_c_s_+-_s_P_IK_E_ _ _ _ _ _ _ _ _-t--_08_1_29_11_8__0_0_:o_o--+1_8_12_9_12_0__ 18 I 91212018 I 18-08150 I Tritium LANL ER-210 Modified 1.96E+02 1 7.53E+oo 1 _II 1.33E+01 1 5.11E+oo i pCi/g 8/29/2018 I  ! 1 18-08150-02 MBL BLANK 08/29/18 00:00 9/2/2018 1a-0~_15_0-+-!__T_r_iti_um _ _ _ _LA_N_L_E_R_-2_1_o_M_o_di_fie_d_1-1 1 _2_._s2_E_+_oo __+1 _2_.9_6_E_+_o_o_ _ 2._97_E_+ _ __oo_,...1_4._98_E_+_o_o~...--u-~"--'-pC_i...cig ___ 18-08150-03 DUP I B1-09100A-FSFC-067CV 08/22/1809:20 I 8/29/2018 i 91212018 i 18-08150 I Tritium LANLER-210Modified 1 1 l__1._8_5_E_+_oo_,...1_2._9o_E__+_o_o-+l_2_.9_0E_+_o_o--+l_4_.9_3_E+_o_o--+_ _u_-il pCi/g 1 18-08150 I 1 18-08150-04 I DO I B1-09100A-FSFC-067CV 08/22/18 09:20  ! 8/29/2018 I 9/2/2018 J Tritium LANL ER-210 Modified I 1.30E+OO I 2.88E+OO I 2.88E+OO \ 4.92E+OO U ipCi~ 18-08150-05 t---T-R-G-+--B-1--0-9-1-00-A--F-S_W_C ___ 0_3_1_C_V_ _ _ _ t--0-8/-2-2/-18._13-:3_0_[,--8/-29-/-20_1_8-il-9-/2-/2-0-18---il-18---08_1_5_0-ij--T-ri-tiu_m_ _,t--_LA_N_L_E_R ___ 2_10_M_o_d_ifi_1e-d--+,-2-.6-6-E-+0-0: 3.01E+OO I 3.01E+OO  ! 5.06E+OO U I pCi/g 18-08150-06 J TRG I B1-09100A-FSFC-001CV 08/22/18 08:52 / 8/29/2018 / 9/2/2018 r 18-08150 I Tritium LANL ER-210 Modified I 1.51E+OO  : 2.94E+0-0--+(-2-.9-4_E_+o-o--+)-5-.0-1_E_+o ...-o-;---u--+i--p-C--i,-g-

,_1_8_-0_8_15_0-_0_1~,--T_R_G_+--_B_1_-0_9_10_o_A_-F_S_F_c_-0_10_c_v         _ _ _ _ ,___08_12_2_11_8_1_2_:4_o--+I 8/29/2018                 I  9/2/2018  ! 18-08150     l        Tritium               LANL ER-210 Modified                 5.53E-01      I     2.84E+OO      I     2.84E+OO        I   4.90E+OO            u          I   pCi/g 18-08150-08            I    TRG      i    B1-09100-FSWC-041CV                              08/22/18 08:34           I 8/29/2018 I           9/2/2018  i 18-08150     I        Tritium               LANL ER-210 Modified            i    1.16E+OO            3.00E+OO      \     3.00E+OO        !   5.15E+OO            U          !   pCi/g 18-08150-09                 TRG      I    B1-09100A-FSFC-068CV                             08/22/1813:40            I 8/29/2018 [ 9/2/2018            I 18-08150 J            Tritium               LANL ER-210 Modified J 1.14E+OO 1

f-2.95E+OO J 2.95E+00 .-06_E_+_OO_ _ _u_~---p-C-i/_g_ __, t-1-8--0-8-15_0-_1_0_'[--T-RG--t-!,-B-1--0-9-10_0_A--F-S_W_C_-0_5_1_C_V_ _ _-t--_08-/2_2_/1_8__1_4-:0_5_f_8_/2_9_/2-0-18-+f-9i-2/_2_01-8--+l-1-8--0-8-1-50-+/--T*-rit-iu_m_--t_LA_N_L_E_R_-2_1_0_M_o_d_ifi_ed--;-f-1-.1-1E_+_o_o--r!-2-.8-7-E+_o_o_/_2_.8_7_E-+0_0_/,-4-.9-3_E_+_OO _ _ _u_......,...l__p__C_i/g*- 18-08150-11 I TRG  ! B1-09100-FSFC-021CV 08/22/1812:59 I 8/29/2018 I 9/2/2018 ! 18-08150 J Tritium LANL ER-210 Modified I 4.08E+OO f 3.13E+OO I 3.14E+OO i 5.17E+OO U I pCi/g I l I  ! ' l -*----*----**- L____:- - - I  ! 1---1-8--0-8-15-0--0-1--+--L-C-S-.f---K-N-O_W_N---------l--08-/2_9_/1_8_0_0_:0-0--+!-8-/2 ......9.../*2-0~9/3/2~8-08150-t--Nickel ASTM 3500-Ni Modi~ 1.54E+03 f 4.62E+01,-li- - - - ' - ,- - - - + - - - - ~ - - - p C i / g 18-08150-01 I LCS I SPIKE 08/29/18 00:00 8/29/2018 f 9/3/2018 [ 18-08150 I Nickel-63 ASTM 3500-Ni Modified I 1.51E+0_3_i,_1_.2_9_E-+0_1_1--8-.-96_E_+_0_1--~[-2.-99_E_+_O_O_ _ _ _ _/___ 1 pC_i_/g___, 18-08150-02 MBL \ BLANK 08/29/18 00:00 i 8/29/2018  ! 9/3/2018 I 18-08150 I Nickel-63 ASTM 3500-Ni Modified ~5E-01 1 1.65E+OO I 1.66E+OO I 2.90E+OO I U i pCi/g l-1-8--0*-8*-15_0-_0_3____ D_U_P_.f---B-1--0-9_10_0_A ___F_S_F_C--0-67_C_V_ _ _ _ ,1-_08-,2-2-,1-8_0_9-,2-0_[_8_/2_9_/2_0_18~'1 9/3/2018 [ 18-08150 [ Nickel-63 ASTM 3500-Ni Modified j 2.14E+OO i 1.83E+OO I 1.83E+O-O~-r-3.-04_E_+_oo-il---u ~------;c;~ 18-08150-04 DO B1-09100A-FSFC-067CV 08/22/18 09:20 \ 8/29/2018 I 9/3/2018 [ 18-08150  ! Nickel-63 ASTM 3500-Ni Modified I 6.81E-01 f 1.77E+OO i 1.77E+OO I 3.02E+OO  ! U I pCi/g 18-08150-05 TRG B1-09100A-FSWC-031CV 08/22/18 13:30 J 8/29/2018 [ 9/3/2018 I 18-08150 I Nickel-63 ASTM 3500-Ni Modified [ 8.74E-01 1.66E+OO 1 1.66._E_+_o_o-+-!-2.-82_E_+_o_o-+i--u----'r1---'-pC_i_c/g___ , 1---1_8_-0_8_15_0_-o_s--+I__ T_RG _ _ _B_1-_0_9_1o_o__ A_-F_S_F_c-_0_0_1c_v_ _ _.........., __ 1 08_12_2_11_8_0_8_:5_2_+i_8_12_9_12_0_18_-+l_9i3/2018 i 18-0815_0-i!-__ N_ic_ke_l-_6_3_+__  ! 1 A_s_T_M_3_5o_o_-N_i_M_o_d_ifi_ed_ _s_.o_3E=-=01=====1-=7=9E=+=o=o=:1==1=.7=9E=+=o=o:=--+':_3_.o_s__ E_+o_o_l _':!....___,_ _P~_ii§l__ 18-08150-07 TRG i B1-09100A-FSFC-010CV 08/22/18 12:40 l 8/29/2018 I 9/3/2018 I 18-08150 I Nickel-63 ASTM 3500-Ni Modified 0 i 1.55E+OO 1.82E+OO f 1.82E+OO 1 3.06E+OO  ! U l pCi/g 1---1-8--0-8_1_5_0-_0__8---',--T-RG--+--B-1--o-9_10_0_-F_s_w_c___ 04_1_c_v_ _ _ _,1-_08-/2_2_/1_8_08:34 I 8/29/2018 I 9/3/2018 I 18-08150 I Nickel-63 ASTM 3500-Ni Modified I 1.74E+OO  ! 1.84E+OO -t-1-1._84_E_+_oo*-+-[-3.-08_E_+_o_o--;l...--u---+:--'-pC-i-'/g_____ 1B-08150-09 TRG B1-09100A-FSFC-06-8C_V _ _ _ _, __ 08_/_22-,1-8_1_3_:4-0-,l-8_/_29-/2_0_1_8*+1-9,-3,-2-01-8--+l-1S-_0_8*-1-50-+1--N-ic_k_e_1_-6_3_ ASTM 3500~Ni Modified I 1.41 E+OO i 1.50E+OO l 1.50E+o__ o_+!_2_.5_1E_+_o_o--+j__u___+i-~p__ C_iig::~ I 8/29/2018 j913/2018 I 1 l-1-8--0-8-15-0--1-0--i---TR-G--+--B-1--0-91_0_0-A--F-S_W_C_-0_5_1_C_V_ _ _-l--08-/2_2_/1-814:05 18-08150 N-ic-ke-1--6-3-+--A-S_T_M_3_5_00---Ni Modified I 1.27E+OO 1.79E+OO 1 1.79E+OO i 3.01E+OO i U i pCi/g 18-08150-11 1 TRG  ! B1-09100-FSFC-021cv 08/22/18 12:59  ! 8/29/2018 i 9/3/2018 I 18-08150  ! N-ic_k_e-l-6--3--+--A-S_T_M_3_5_0_0--N-i-M-od-ifi-,e-d-1!--1-.9-0_E_+o-o--+!-1-.4-5-E-+0-0-+--1-.4_6_E_+_oo-+--2.-4-1E_+_o_o__:f---u--c--pC_i_/g---1 1 1 CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANAL YT!CAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [591]

Printed: 9/19/201811:25 AM Page 2 of 12 Report To: Work Order Details: 18-08150 Eberline Analytical Patricia Giza Zion Solutions SDG: Purchase Order: 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab Client Sample

                                                                                                                       !/   Receipt Date 1'

Analysis Date i! Batch ID

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I Analyte Method I Result

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                                                                                                                                                                                                                                                                                        .      CSU I

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Qualifier Ii Report Units ID ID Date 18-08150-01 I LCS KNOWN 08/29/18 00:00 I 8/29/2018 j 8/31/2018  ! 18-08150 ] Strontium-90 EIChroM SRW01 Modified j 4.99E+01 1 2.SOE-01  ! I  ! I pCi/g 18-08150-01 LCS / SPIKE 08/29/18 00:00 I 8/29/2018 / 8/31/2018 I 18-08150 J Strontium-90 EIChroM SRW01 Modified  ! 4.55E+01 l1.80E+OO I 1.59E+01 J 8.06E-01 i l__P~~9_ _ 18-08150-02 MBL I BLANK 08/29/18 00:00 [ 8/29/2018 i 8/31/2018 I 18-08150 I Strontium-90 EIChroM SRW01 Modified I -9.51E-02 I 5.15E-01 i 5.16E-01 i 9.33E-01  ! U I pCi/g

=1=8=-0=8=1=50=-0=3=:1===D=U=P=-:t-1_____

B~1_--0_9-_1-0_~o_A-_--F~S_F-_C-_--0_6-_7~C~V~~~~~~~=*:~-0-8~/2~2~/1~8~0~9_:-2_0-_:1_8_i2_9_i2_0_18-+!_8_i3_1_i2_0_18--+1_1_8_-0_8_1:50=:1==S=tr=o-n __t=iu=m=-9=0=:=-E:I_C=h-r_o=M=S=R=W=0=1=M=o=d=ifi-,_e_d_-++---_-2=.2=8=E=-0=1~-fl-4-.3-8-E--0=1=:i_4_.4_5_E_-o_1_1:==8-=16=E=-=01==:1===u===:i===p=C:i/~g----1 18-08150-04 I DO B1-09100A-FSFC-067CV 08/22/18 09:20 / 8/29/2018 / 8/31/2018  ! 18-08150 / Strontium-90 EIChroM SRW01 Modified / -6.05E-02 i 3.91E-01 ! 3.91E-01 J 7.09E-01 I U ) pCi/g ,_1_8-_0_8_15_0-_0_5__,_I_ _ T_R_G-+-I-B-1--0-9-10_0_A--F-S_W_C_-0_3_1_C_V_ _ _ _ ,__08-/2_2_/1_8_1_3-:3-0----+f-8-/2_9_/2018 I 8/31/2018 I 18-08150 I Strontium-90 EIChroM SRW01 Modified 3.99E-01 [ 4.00E-O!__j 4.24E-01 I 6.67E-01 i U I pCi/g 18-0-81_5_0--0-6_,..I_T_R_G__ ,!_ _ B1---09_1_00A-FSFC-001CV 08/22/18 08:52 I 8/29/2018 I 8/31/2018 I 18-08150 I Strontium-90 EIChroM SRW01 Modified O.OOE+OO 4.65E-01 i 4.65E-01 i 8.29E-D1! U I pCi/g 1--1-8--0-8-15_0-_0_7_,_ _ _ _,il--B-1--0-9-10_0_A--F-S_F_C--0-10-C--V----<---08-/2_2_/1_8_1_2_:4_0......;i 8/29/2018 T-RG I 8/31/2018 I 18-08150 / Strontium-90 EIChroM SRW01 Modified i -1.49E-01 1 3.97E-01 1 4.00E-01 / 7.36E-01 i U 1 1 pCi/g 18-08150-08 I TRG I B1-09100-FSWC-041CV 08/22/18 08:34 I 8/29/2018 I 8/3~ 18-08150 I Strontium-90 EIChroM SRW01 Modified I 2.69E_-_0_1_,1_ _ 1 4._5_3E_-_01_+--_4_.6_3E_-_0_1-'j __1_.8_0_E_-0_1_1_ _ u __1_ _P_C_iig_---t 1--1-8--0-8-15-0--0-9-+[--T-R_G_;...I_B_1_-0_9_10_0_A--F-S_F_C_-0_68--C-V----~-08-/2_2_/1_8_1_3_:4_0--+j-8-/2_9_/2-0~ 8/31/2018 I 18-08150 I Strontium-90 EIChroM SRW01 Modified 2.04E-01 I 3.38E-01 I 3.45E-01 I 5.81E-01 J U l pCi/g ,__1_8_-0_8_15_0_-1_0_,I_ _TR_G_ _ _s_1-_0_9_1o_o_A_-F_s_w_c_-o_s_1_c_v_ _ __, __ 08_12_2_,1_8_1_4_:o_5_!,_8_12_9_12_0_18-+-8_t3_1_12_0_18~-'-1_8_-0_8_15_o-+rl_s 1 __ 1r_on_11_*u_m_-9_o--+_E_1_c_hr_o_M_S_R_w_o_1_M_o_d_ifi_ed_~_2_.08E-01 / 4.14E-01 I 4.21E-01 J 7.19E-01 / u I pCitg 18-08150-11 TRG B1-09100-FSFC-021CV 08/22/1812:59 I 8/29/2018 I 8/31/2018 I 18-08150 Strontium-90 EIChroM SRW01 Modified I 4.70E-01  ! 4.35E-01 I 4.65E-01 I 7.22E-01 I U  ! pCi/g i I  : I I I i I i 18-08150-01 LCS KNOWN 08/29/18 00:00 I 8/29/2018 I 8/29/2018 i 18-08150--)--i--Co_b_a--11--6-0._,___EP_A_9_0--1-.1-M_o_d-ifi-ed--+[-2-.6-2E--+-02--i,-1-.0-2-E-+0--1-1*-----,!------+-----,1-- - p - C ~ 1--1-8--0-8-15--0--0-1-;---l-C_S_ _ _K_N_O_W_N_ _ _ _ _ _ _ _ _ ,, _ 08/29/1800:00 _ I 8/29/20181 8/29/2018 [ 18-08150 Cesium-137 EPA901.1 Modified I 1.94E+02 ' 7.96E+OO I [ pCi/g t-1-s-_0_8_15_0-_0_1--+,--L-c-s-+---S-PIK-E---------,1--08-,2-9-/1_8_0_0_:o-o--+1-8-,2-9-,2-o-18--+i-8-/2_9_/2_0_18-+l-1-8--0-8-1-50--+l--c-o-ba-lt--6-o--1_-_-_-E=P=A=9=o=-1__ ___--c,-:_-_-_-_-_-_~+-,

                                                                                                                                                                                                                          .1_M_o_d_ifi_ed_--+1_2_.4_7_E_+_o_2--:;_1_.9_6_E_+_o1_+-i_2_._33_E_+_o_i"-,1_,-_-_s-_8-_3-E=-+=-o_o

_ 1=-=-=--P'-C~i-'ccg=-=--=: 18-08150-01 i LCS f SPIKE 08/29/1800:00 [ 8/29/2018 [ 8/29/~8-08150 I Cesium-1:37 EPA901.1 Modified  ! 1.60E+02 / 1.47E+01 I 1.68E+01 / 2.04E+OO pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/ 481-0683 FAX 865/ 483-4621 [592]

Printed: 9/19/2018 11 :25 AM Page 3 of 12 Report To: Work Order Details: 18-08150 Eberline Analytical Patricia Giza Zion Solutions Purchase Order: SDG:I I 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Category: I ENVIRONMENTAL Zion, IL 60099 Sample Matrix: \ so Lab Sample II Client Sample / Receipt Analysis I Batch I I I f I l I i Report ID I Type ID Date  ! Date Date , ID Analyte Method Result I CU l CSU i MDA j Qualifier Units 18-08150-02 I MBL I BLANK 08/29/1800:00 I 8/29/2018 8/29/2018 I 18-08150 I Actinium-228 EPA901.1 Modified I 6.72E-03 I 1.22E-01 i 1.22E-01 !i 1.99E-01 Ir-*--~~--'-----'---1 U pCi/g 1 _1_a-__0_81_5_0_-0_2_+_M_BL_-ii__ BL_AN_K_ _ _ _ _ _ _ _ _ _1--_0_8_12_91_1_8_00_:_oo_+-i_8_/2_9_12_01_8-+-_8_12_91_2_01_8-+-i_1_8-_0,8150 I Silver-108m EPA901.1 Modified I 2.45E-03 i 3.44E-02 ' 3.44E-02 4.18E-02 I u pCi/g 18-08150-02 j MBL I BLANK 08/29/1800:00 ! 8/29/2018 8/29/2018 i 1a-0815ClTAmericium-241 EPA901.1 Modified I -1.96E-01 I 9.53E-02 i 9.58E-02 I 1.07E-01 I U pCi/g 18-08150-02 MBL BLANK 08/29/18 00:00 I 8/29/2018 8/29/2018 i 18-08150 ! 8 ~ 3 3 --+--E*-PA-90-1-.1-M--od-ifi-,e-d-~,l-1-.5-2-E--04~+1--4*-.9-8E---02-+--4-.9-8-E--o-2-! 6.98E-0*-2--+j--U-~--p-C-i/g---1 18-08150-02 MBL I BLANK 08129/18 00:00 J 8/29/2018 8/29/2018 / 18-08150 I Bismuth-214 EPA 901. 1 Modified 1 4.58-E--0-2-,,-7-.-39-E--0-2-,e---7.-40-E--0-2-;.-/-1-.2-7E---0-1-+--U--i--pC-i-/g_ _, 18-08150-02 MBL BLANK 08/29/18 00:00 I 8/29/2018 8/29/2018  ! 18-08150 1, Cobalt-60__ EPA 901.1 Modified 11 1.41E-02 I 2.39E-02 I 2.39E-02 ' 4.53E-02 I U I pCi/g 18-08150-02 MBL BLANK 08/29/1800:00 I 8/29/2018 8/29/20181 18-08150 Cesium-134 EPA901.1 Modified I -3.34E-02*-'-,-4.-0-1E---02-+-j-4-.0-1E---02-+i-5-.2-0-E--o-2---1-,--u--:--"-p-C-'i/g'---1

                                                                                                                                                                                         *------jll---------+----------~~---'-----*

18-08150-02 [ MBL I BLANK 08/29/18 00:00 I 8/29/2018 8/29/2018 I 18-08150 I Cesium-137 1 EPA 901.1 Modified -1.25E-02 ! 3.21E-02 I 3.21E-02 ! 4.63E-02 J U I pCi/g

=1=8-=0=8=15=0=-0=2==:!===M=B=L=====B=LA=N=K===================:==08=/2=9=/1=8=0=0=:o=o=:i=8=/2=9=/2=0=18=:=8=/2=9=/2=0=18=:1=1=8=-0=8=1=50=:1==E=ur=op=iu=m=-=1=52:=--1__E_P_A_9_0_1_.1_M_o_d_ifi_ed_-+t._2_.4_4_E_-0_2---1-l_1_.2_o_E_-0_1-+-:1_ _

1._2o_E_-0_1_1,__ 1._40_E_-_01_+-I__u__+:__P,__C_ii-=g_ _1 18-08150-02 I MBL BLANK 08/29/18 00:00 I 8/29/2018 8/29/2018 I 18-08150 I Europium-154 EPA 901.1 Modified 2.36E-02 i 6.72E-02 1 6.73E-02 ! 7.27E-02 I U pCi/g 18-08150-02 MBL I BLANK 08/29/1800:00 I 8/29/2018 8/29/20181 18-08150 I Europium-155 EPA901.1 Modified / -5.02E-02 / 4.71E-02 i 4.72E-02 / 1.05E-01 U J pCi/g

=1=8-=0=8=15=0-=0=2=:===M=B=L=====B=LA=N=K===================:===08=/2=9=/1=8=0=0=:o=o=:!=8=/2=9=/2=0=18===8=/2=9=/2=0=18-~+k-1_8-_0-8150 ~lmium-166m EPA 901.1 Modified I 5.93E-03 l 5.48E-02 i 5.48E-o!_] 5.39E-02 U i---p-C-i/g===-1*

1--1_a-_0_8_15_0_-0_2-+i__M_B_L_+-_B_LA_N_K _ _ _ _ _ _ _ _ _ _ __ 08_12_9_/1800:oo I 8/29/2018 8/29/2018 1 18-08150 ~dine--~ EPA901.1 Modified I 2.26E-02 1 1.85E-01  ! 1.85E-01 I 2.52E-01 u , pCi/g 1 i---1_8_-0_8_15_0-_0_2-+__M_B_L_+-_B_LA_N_K _ _ _ _ _ _ _ _ _-1__ 08_12_9_11_8__0_0_:o_o-+l_8_12_9_/2_0_18-+_8_12_9_12_018 [ 18-0815~otassium-40 EPA901.1 Modified I -5.20E-02 l 3.64E-01 I 3.64E-01 I 5.78E-01 u /pCi~- 18-08150-02 MBL i BLANK 08/29/18 00:00 I 8/29/2018 8/29/2owl 18-08150 I Manganese-54 EPA 901.1 Modified I -2.06E-02 2.37E-02 2.38E-02 I 5.16-E--0-2_,_ _ U_--;l----'-p-C-i/g'----I

=1=8-=0=8=15=0=-0=2=:===M=B=L==:1==B=LA=N=K==================::==08=/2=9=11=8=0=0=:o=o=:1=8=/2=9=/2=0=18=:=8=/2=9=/2=0=18=:1::-__1-8--0-8-1-50-+I-N-i-=ob-iu_m___

94--1---E-P--A 901.1 Modified I -7 .33E-03 j 3.28E-02 I 328E-02 i 5.03E-02 U ' pCi/g 18-08150-02 M13L ! BLANK 08/29/18 00:00 ! 8/29/2018 8/29/2018 I 18-08150 f Lead-210 EPA 901.1 Modified I 6.44E-02_J 7.27E-01 ,* 7.27E._-_0_1_+i_1_.2_1E_+_o_o_+__u_---1-;---'-P_C_iig_ _ 1 18-08150-02 MBL BLANK 08/29/1800:00 I 8/29/2018 8/29/2018 I 18-08150pad-212 EPA901.1 Modified I 7.38E-02 I 5.70E-02 1 5.71E-02 [ 9.94E-02 U I pCi/g 18-08150-02 MBL BLANK 08/29/18 00:00 f 8/29/2018 8/29/2018 [ 18-08150 1 Lea_d-_21_4___,___E_PA 901.1 Modified I 6.46E-02 [ 7.52E-02 i 7.53E-02 [ 1.29E-01 U I pCi/g 18-08150-02 MBL j BLANK 08/29/1800:00 I 8/29/2018 8/29/2018 l 18-08150 i Promethium-145 EPA901.1 Modified I 8.69E-02 ~~*~---0-1-i---1.-89-E--0-1-,---u-~/'--p-C-i/-g---1 ,__1_8_-0_8_15_0-_0_2~,--M_B_L_ _ _B_LA_N_K _ _ _ _ _ _ _ _ __,__08_!2_9_11_8_0_0_:o_o_if_8_i2_9_12_0_18-+-8-/2_9_i2_0_18--+1_1_8_-0_*_8_15_0-+i_R_a_d_iu_m_-2_2_6___,_ _ EPA 901.1 Modified i 4.58E-02 i 7.39E-02 I 7.4~_E-_0_2_ _1_.2_7_E_-0_1_ _ _ u_1 _ _P_C_iig_ _, _1_8_-0_8_150_-0_2_+__ M_B_L_!--_B_LA_N_K_ _ _ _ _ _ _ _ _ _ l__ o8_i2_9_11_8_0_o_:o_o~,l_8_12_9_12_0_18_-i__8_12_9_/2,_018 I 18-08150 I Antimony-125 EPA901.1 Modified---! 6.06E-02 i 9.73E-02 l 9.74E-02 1.61E-01 U p~ 18-08150-02 MBL I BLANK 08/29/18 00:00 I 8/29/2018 8/29/201~8150-I-'-Thorium-234 EPA 901.1 Modified I 1.85E+OO  ! 7.02E-01 J 7.08E-01 1.33E+OO U pCi/g 18-08150-02 MBL I BLANK 08/29/1800:00 I 8/29/2018 8/29/2018 I 18-0~_ti_allium-20':__ EPA901.1 Modified I 1.06E-0111J)6E-0~6_E-_0=1==~==1=.6=1=E=-0=1=:====U===;==~--p-C-i/g___ _ l-1-8--0-8-15-0--0-2-+I--M-B_L_,,_I-B-LA_N_K----------1--08-/2_9_/1-800:00  ! 8/29/2018 8/29/2018 [ 18-08150 ' Uranium-235 EPA 901.1 Modified I -2.74E-01i-4.37E-01 I 4.38E-01 2.89E-01 U  : pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [593]

Printed: 9/19/201811:25 AM Page 4 of 12 Report To: Work Order Details: Patricia Giza 18-08150 Eberline Analytical Zion Solutions Purchase Order: SDG: 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab ID I. Sample Type 1' Client ID Sample Date

                                                                                                            / Receipt / Analysis I Date i Date I    Batch ID       I J

Analyte Method Result i I CU I j CSU MDA Qualifier i Report Units 1 18-08150-03 I DUP I B1-09100A-FSFC-067CV 08/22/18 09:20 i 8/29/2018 I 8/29/2018  ! 18-08150 I Actinium-228 EPA 901.1 Modified 2.59E-01 J 3.81E-0_1_ _,__3_.8_2_E-_0_1~-7_.2_1_E_-0_1__ i, 11 __ u___1,...__P_C_il_g_-1 __1_8_-o_8_1_5o_-o_3_,I__D_U_P_+-!_0_1_-0_9_1o_o_A_-F_S_F_c_-o_s_1c_v_ _ _ _ __ 08_1_22_11_8_0_9_:2_0_,!_8_12_9_t2_0_1_8..,.I_8_12_9_12_0_18-+_18_-0_8_1_50-+l_s_il_ve_r_-1_0_8m_-1 __E_P_A_9_0_1_.1_M_o_d_ifi__ ed_-+_-2_.1_7E-02 !1.34E-()1 I 1.34E-01 1.52E-01 u___.:-:__p_C_itg_ _, 1 1 18-08150-03 / DUP I B1-09100A-FSFC-067CV 08/22/1809:20 I 8/29/2018 / 8/29/2018 I 18-08150 I Americium-241 EPA901.1 Modified 8.33E-02 I 1.06E-01 L1.06E-01 3.02E-01 U pCi/g ,_1_8-_0_8_1_50--0-3-tl--D-U-P-+-I-B-1--0-9_10_0_A_-F_S_F_C_-0_67_C_V_ _ _ _,__ I 08-/2_2_/1_8_0_9_:2-0--;[ 8/29/2018 8/29/2018 ~8-08150 I Barium-133 EPA901.1 Modified -5.63E-02i 1.54E-01 I 1-.54-E--0-1--1-.92-E--0-1--;~-u-...,--p-Ci-/g-*-*- 1 18-08150-03 I DUP I B1-09100A-FSFC-067CV 08/22/1809:20 I 8/29/2018 8/29/2018 18-08150 I Bismuth-214 EPA901.1_M_o_d-ifi-,e-d---+,-5-.5-6_E_-0_1__ 1 3.16E-01 I 3.18E-01 5.30E-01 i pCi/g i--1-8-_0_8_1_50--0-3_J__D_U_P_ _ _B_1_-0_9_10_0_A--F-S_F_C_-0_67_C_V_ _ _ _ l-_08_n_2-,1-8_0_9_:2_0_l_8_/2_9_/2_0_1_8_-+8-n_9_n_0_18-+-18--0-8-1-50-+I--C-o-ba-lt--6-0--I--E-P-A001-.1-*M--o-d-ifi-e-d-+il--8-.9-1-E*--o-2--;,1-1-.4-8-E--0-1--jl--1.-48-E--0-1-,--1.-99-E---01-*--u--,l--p-C-i/_g__ 1 - - - - - - - + - - - - - + - - - - - - - - - - - - - - - - - - - - - - - + - - - - + - - - - + - - - - - - - l - - - - - - - - - - - + - - - - - + - - - - - - - - - + - - - - - + - - - -!----'--.:.._-1 18-08150-03 I DUP B1-09100A-FSFC-067CV 08/22/1809:20 ; 8/29/2018 8/29/2018 I 18-08150 I Cesium-134 EPA901.1 Modified [ 7.45E-03 6.34E-02 6.34E-02 1.49E-01 U I pCi/g 1--1_8_-0_8_15_0_-0_3_I__ D_U_P_+__-B_1_-0_9_1o_o_A_-F_S_F_c_-o_s1_c_v_ _ _ _ 1-_08_12_2_11_8_0_9_:2_o_+l_8_12_9_J2_01~ I 8/29/2018 i 18-08150 I Cesium-137 EPA901.1 Modified II 1.76E-01 ;I, 1.84E-01 I 1.84_E_-0_1--1_3_._o4_E_-0_1_ _ , _ i_ _u_ _ ,..I_ _cp_C_it.c.g__ 1 18-08150-03 I DUP I B1-09100A-FSFC-067CV 08/22/18 09:20 i 8/29/2018 I 8/29/2018 I 18-08150 I Europium-152 EPA 901.1 Modified , 2.02E-01 4.74E-01 i 4.74E-01 4.44E-0_1-+i__u__*-'ri_..cp_C_ii.c.g_ -** 18-08150-03 I DUP I B1-09100A-FSFC-067CV 08/22/18 09:20 I 8/29/2018 I 8/29/2018 18-08150 I Europium-154 EPA 901.1 Modified  ! 2.66E-01 1 2.70E-01_J_2___ 71-E--0-1--+-2.-35-E--01 i U pCi/g 18-08150-03 / DUP I B1-09100A-FSFC-067CV 08/22/18 09:20 / 8/29/2018 I 8/29/2018 / 18-08150 / Europium-155 EPA 901.1 Modified 1* 2.37E-01 2.26E-01  ! 2.27E-01 3 72~,---u-'"i-~pC-i/_g__ _ 18-08150-03 j DUP 81-091 OOA-FSFC-067CV 08/22/18 09:20 I 8/29/2018 I 8/29/2018 I 18-08150 :-1-H-o-lm-iu-m---16_6_m-+--E-P_A_9_0_1.-1-M_o_di-fie-d--+-I,-1.-84-_E---01-i-l-1-.7-6E---0-1-+I-1-.7-7-E--0*1*---i*--1:-87-E-:0-1-!I---u--+I--p-Ci~ 18-08150-03 I DUP 1 1 1-s-1--o-9-1-oo-A---FS_F_C_-0_6._7_c_v_____ __o_8_/2-2/-18-09-:2_0_!Bf29no18 i 8/29/2018 I 18-08150 J lodine-129 EPA901.1 Modified 2.56E+OO i 1.54E+00--1!c--1-.5-4_E_+_oo-+---1.-73_E_+_o_o-+1---u---:---pC--i-/g-- 18-08150-03 I DUP B1-09100A-FSFC-067CV 08/22/1809:20 l 8/29/2018! 8/29/2018 I 18-081~;;;::;;o EPA901.1 Modified I 6.23E+O~~_E:~~8E+OO 1 1.86E+OO i r--pciig-- 18-08150-03 I DUP I B1-09100A-FSFC-067CV 08/22/1809:20 I 8/29/2018 I 8/29/2018 ~8150 I Manganese-54 EPA901.1 Modified I -6.75E-03 / 1.34E-01 I 1.34E-01 / 2.06E-01 i U i pCi/g 18-08150-03 I DUP B1-09100A-FSFC-067CV 08/22/1809:20 I 8/29/2018 J 8/29/2018  ! 18-08150 I Niobium-94 EPA901.1 Modified i3.17E-02  ! 1.15E-01 1 1.15E-01  ! 1.64E-01 i U I pCi/g  : 18-08150-03 I DUP B1-09100A-FSFC-067CV 08/22/1809:20 I 8/29/2018 I 8/29/2018 j 18-08150 I Lead-210 EPA901.1 Modified I 3.12E+OO 1.92E+OO j 1.92E+OO j 3.57E+OO , U I pCi/g __ ,__1_s-_0_8_15_o_-o_3__,l__ o_u_P_+-l_s_1_-0_9_10_o_A_-F_S_F_C_-o_s1_c_v_ _ _ _,___08_12_2_11_8_0_9_:20  ! 8/29/2018 I 8/29/2018 I 18-08150 U..:..~ EPA901.1 Modified I 2.05E-01 i 1.77E-01 I 1.78E-01 I 2.87~1 pCitg 18-08150-03 I DUP B1-09100A-FSFC-067CV 08/22/1809:20Tat29/2018 I 8/29/2018 I 18-08150 I Lead-214 EPA901.1 Modifi~5.31E-~-:'i?E-01'1 3.18E-01 / 4.92E-01 / / pCi/g 1a-08150-03 I DUP B1-09100A-FSFC-067CV 08/22/18 09:20 I 8/29/2018 I 8/29/201~8-0815o] Promethium-145 EPA 901.1 Modified ' -1.90E-01 I 4.16E-01  ! 4.16E~ 5.83E-01 1 U i pCi/g i--1-8--0-8-15_0-_0_3-+I--D-U-P-i-l-B-1--0-9_10_0_A--F-S_F_C--0-67_C_V_ _ _-'l--08-/2-2-/1_8_0_9:20 I 8/29/20181 8/29/20181 18-081sol Radium-226 EPA901.1 Modified I 5.56E_:-_91 i 3.16E-01 i 3.18E-01 [ 5.30E-01 i -~~ 1--1_8__-0_8_15_0-_0_3_ 1 l__ o_u_P_ i,_s_1_-0_9_1_oo_A_-_FS_F_c_-o_s_1_c_v_ _ _ _ ~_o_81_2_21_18_09_,20 [ 8/29/2018 I 8/29/2018 I 18-08150 I Antimony-125 ~901:.1._Modifi~~E-02 _I 2.45E:01 j 2.45E-01 I 4.17E-01 I u r pCi/g 18-08150-03 [ DUP 1 B1-09100A-FSFC-067CV 08/22/18 09:io  ! 8/29/2018 i 8/29/2018 f 18-08150 f Thorium-234 EPA 901.1 Modified j 2.37E+OO j 2.73E+OO I 2.73E+OO i 4.57E+O()T U f pCi/g i--1-8--0-8-15-0--0-3-+[--o-u_p_"'!-B-1--0-9_10_0_A_-F_S_F_C--0-67_c_v----i1---08-,2-2-,1-8_0_9_:2-o-+!-8-/2-9/2018 I 8/29/20181 18-08150 Thallium-208 r:;:;:I EPA901.1 Modified~E-01 l3.29E-01! 3.29E~ 6.55E:01 1 u pC_i~g_ _ 18-08150-03 [ DUP I B1-09100A-FSFC-067CV 08/22/18 09:20 I 8/29/2018 i 8/29/2018 I 18-08_1_5._0_,_U_r_a_ni-um---2-35-I--E-P_A_9_01-.-1-M-odified 1 I 9.42E-01 ' 1.98E+OO i 1.98E+OO , 9.87E-01 i U I pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [594]

Printed: 9/19/2018 11 :25 AM Page 5 of 12 Report To: Work Order Details: Eberline Analytical Patricia Giza SDG: 18-08150 Zion Solutions Purchase Order: 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab 1 Sample 1 1 Client Sample i,' Receipt I Analysis I Batch I I cu I' Report ID 1 Type 1 ID Date I Date I Date I ID i Analyte Method Result CSU MDA Qualifier Units 1-1_a-_0_8_15_o_-04_-+I__D_o_-+l_s_1_-0_9_1o_o_A_-F_S_F_c_-o_s1_c_v_ _ _ _ __ 1 o8_J2_2_,1_8_0_9_:2_o_+J-8_12_9_12_0_18-+l_8_12_9_12_0_18-+!_1_8_-0_8_1_5o_+! Actinium-228 EPA901.1 Modified 4.45E-01 5.22E-01 i 5.22E-01  ! 9.56E-01 u  ! pCi/g , 18-08150-04 DO B1-09100A-FSFC-067CV 08/22/1809:20 ! 8/29/2018 l 8/29/2018 I 18-08150 iSilver-108m EPA901.1 Modified I -3.28E-02  ! 1.28E-01 j 1.28E-01 l 1.42E-01 U ~ i _ i g__  ! 18-08150-04 DO B1-09100A-FSFC-067CV 08/22/1809:20 / 8/29/2018) 8/29/2018 / 18-08150 : Americium-241 EPA901.1 Modified .1 1.09E-01  ! 2.36E-01  ! 2.36E-01 I 3.33E-01 U * ~_<::~ I 18-08150-04 i DO I B1-09100A-FSFC-067CV 08/22/1809:20 I 8/29/20181 8/29/2018 j 18-08150 I Barium-133 EPA901.1 Modified I 3.48E~~9.14E-~- 9.14E-02-+-i-1-.9-8E---0-1-rl--U--+l-~p.Ci/g i 18-08150-04 DO / B1-09100A-FSFC-067CV 08/22/18 09:20 I 8/29/2018 I 8/29/2018 I 18-08150 I Bismuth-214 EPA901.1 Modified  ! 9.19E-01 ' 3.03E-01 I 3.07E-01 I 3.92E-01 I pCi/g 18-08150-04 ,I ___ D_o_-+!_s_1_-0_9_1_oo_A_-_FS_F_c_-o_s_1_c_v_ _ _ _,__0_81_2_21_18_09_,2_0_I 8/29/2018 I 8/29/2018 II 18-08150 i Cobalt-so EPA901.1 Modified I -3.21E-02 i 1.41E-01 ! 1.41E-01 I 1.81E-01 I u ~~ 18-0815!J-04° DO  ! B1-09100A-FSFC-OB7CV 08/22/1809:20 ) 8/29/2018 i 8/29/2018 18-08150--;l--c-e-s-iu-m--1--3-4--;--EP-A-90-1-.1-M--o-d-ifi-ed--!3.78E-02 ) 6.95&021El.95E-02--!,1--1.-72-E--0-1-+-l--u---+-1-i-p_C-i/.g~-- 1 18-08150-04 DO B1-09100A-FSFC-067CV 08/22/1809:20 i ~ 8/29/2018 I 18-08150 I Cesium-137 EPA901.1 Modified [ -8.69E-02 I 1.68E-01 I 1.68-E--0-1~rl-2-.3-3-E--0-1~;,--U--,...--'-p-C-i/g__ _ 18-08150-04 I DO B1-09100A-FSFC-067CV 08/22/1809:20  ! 8/29/2018 I 8/29/2018 I 18-08150 I Europium-152 EPA901.1 Modified I 3.5~E-01 ~~ 3.86~_1_+-[_4_.2_5E_-_0_1_+l__u_-+1_ _ PC_i_lg_ _, 1--1_8_-0_8_15_0-_04_-+I__D_o_--+-_s_1-_0_9_1o_o_A_-F_S_F_c-_o_s1__c_v_ _ ___, __ 1 08_t2_2_11_8_0_9_:2_o_+l_812912018 I 8/29/2018 , 18-08150 I Europium-154 EPA 901.1 Modified 8.63E-02 i 3.97E-01 13WE-01 i_2_._15_E_-0_1_,_,__u_ _ , __p_C_i_l_g_ _. 18-08150-04 j DO B1-09100A-FSFC-067CV 08/22/1809:20  ! 8/29/2018 / 8/29/2018,1 18-0815~ropium-155 EPA901.1 Modified J 1.83E-01 / 2.74E-01 / 2.75E-ii'11 3.77E-01 / U pCi'.!!.__ 18-08150-04 DO B1-09100A-FSFC-067CV 08/22/1809:20 [ 8/29/2018  ! 8/29/2018 I 18-081!;_~mium-166m EPA901.1 Modified j-MOE-02 l~9E-01 I 2.29E-01 1.96E~__u_-+1_ _ PC_il_g__ _ 18-08150-04 I DO 11 B1-09100A-FSFC-067CV 08/22/1809:20 ! 8/29/2018 I 8/29/20181 18-08150 I lodine-129 EPA901.1 Modified i 2.51E+OO !1.57E+QO I 1.58E+OO I 1.80E+OO I U I pCi/g l--1-8--0-8-15-0--04--1--D-O---'rl-B-1-_0_9_10_0_A_-F_S_F_C--06-7_C_V----ll---08-/2_2_/1_8_0_9_:2-0-+-8-/2_9_/2-0-18_;rl-8-/29/2018 I 18-0_8~~ Potassium-40 EPA 901.1 Modified 9.74E+OO I 2.66E~Ooi2:111::-:aof2.4o8ool_____l,---p-C-i/g____ _ 18-08150-04 DO B1-09100A-FSFC-067CV 08/22/1809:20 I 8/29/2018 I 8/29/2018 I 18-08150 I Manganese-54 EPA901.1 Modified  ! -6.01E-02 r-~01 ) 1.78E-01 U i---p-C-i/g-- 18-08150-04 DO B1-09100A-FSFC-067CV 08/22/18 09:20 8/29/2018 I 8/29/2018 I 18-08150 I Niobium-94 EPA 901.1 Modified I -1.47E-01 i 1.38E-01 1 1.38E-01 i 1.53E-01 ,'-__u____,l_ _ pC:~ 18-08150-04 DO B1-09100A-FSFC-067CV 08/22/18 09:20 8/29/2018  ! 8/29/2018 I 18-08150 I Lead-210 EPA 901.1 Modified 2.29E+OO 2.25E+OO [ 2.26E+OO I 3.89E+OO j U pCi/g 1--18--0-8-1-50--04--1--D-O--+I*-B-1--0-9_10_0_A--F-S_F_C_-0_6__ 7C-V----1---08-/-22-/-18_0_9-,2-0--!-8-/-29-/2_0_1_8-+j-8-/2_9_/2-0-18-+--18--0-8-1-50-+I--L-e-ad---21-2--+---EP-A-901.1 Modified I 4.72E-01 !1 2.92E-01 / 2.93E-01 I 4.65E-01 I pCi/g 18-08150-04 DO B1-09100A-FSFC-067CV 08/22/18 09:20 8/29/2018 I 8/29/2018 18-08150 I Lead-214 1 EPA 901.1 M-;;-d-i-fie-d--1

                                                                                                                                                                                                                     +- -_-8.-.03. EE--0 1 ii  3. 24EE--0 1 ; 3. 26EE--0 1 1 1

4 . 60EE--0 1 1 f'pci/g 18-08150-04 I DO B1-09100A-FSFC-067CV 08/22/18 09:20 8/29/2018 I 8/29/2018 18-08150fPromethium-145 EPA 901.1 Modified 3 69 0 1 4 17 0 1 1 4 17 0 1 11 5 27 0 1 1 U  ! pCi/g 18-08150-04 i DO B1-09100A-FSFC-067CV 08/22/1809:20 8/29/2018 I 8/29/2018 18-08150 I Radium-226 EPA901.1 Modified I 9.19E-01 I 3.03E-01 1 3.07E-01 i 3.92E-01 1 pCi/g 1

-1*8---08_1_5_0--04-,--D-o--+l-s-1--o-9_1_00-A---FS_F_C_-0_6_7_C_V_ _ _ _ __o_s_,2_21-18-09-,2-o-1--8/-29/2018                  I   8/29/2018 , 18-08150              Antimony-125         EPA 901.1 Modified        I     3.87E-02        .J  2.59E-01     I 2.59E-01     +-;-4.-5-5E---01-,..I--U--+i- * - p C i ~

18-08150-04 DO B1-09100A-FSFC-067CV 08/22/1809:20 8 ~ 8/29/2018 I 18-08150 Thorium-234 EPA901.1 Modified J 3.48E+OO 2.31E+0~2E~~6-E-+O-O-t[---U--;---p-C-i/-g - 18-08150-04 I DO B1-09100A-FSFC-067CV 08/22/1809:20 8/29/2018  ! 8/29/2018 18-08150 Thallium-208 EPA901.1 Modified I 8.14E-01 I 3.51E-mf:i~54E-01 , 7.61E-01f--i--U-~,--p--C-i/_g_ 18-08150-04 j DO B1-09100A-FSFC-067CV 08/22/1809:20 8/29/2018 i 8/29/2018 I 18-08150ILJranium-235 EPA901.1 Modified j1.95E-01 i 1.86E+OO i1.86E+OO  ! 1.02E+OO I U i pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [595]

Printed: 9/19/2018 11 :25 AM Page 6 of 12 l-----------'R..;.e:.cpc:o:.:.r/..:.T,;:::o:_ _ _ _ _ _ _ _ _ _-1----------,-------'W."-o:.:rk;..:...::0.;.;rd:..:e-+rD::.e::..:t=aiccls:...:- - - - - - - - - - - - - - - 1 1 Patricia Giza 18-08150 Eberline Analytical Zion Solutions Purchase Order: SDG: 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab II Sample II Client Sample Receipt : Analysis!i Batch Analyte Method 1. Result / CU / CSU I MDA Qualifier / Report 1---ID_ _+-_Ty:..:p_e_"-_ _ _ _ _ _ 1D_ _ _ _ _ _I-_ _ D_at_e_ _+-_D_a_te_..;.i_ _ D_at_e_..;.l_ _ 1D_-+------l---------+------+l------+----i-----+---+--U-n_it_s_-l _;i____:p_C_it.::.9__1 1 1-1_8_-0_8_1_50-_0_5--+I_ _ T..;_R..;_G_,LI_s_1_-0_9_1o_o_A_-F_s_w_c:_-_03_1..:.c_v_ _ _-1-_08_12..:.2_,1_8_1_3_:3_o_f_8_12_9_12_0_1_8+[_8_t2_9_12_0_18-+_18_-0_8_1_50-+_A_ct_in_iu_m_-_22_8--l--E-P_A_9_o_1_.1_M_o_d_ifi_ed_-+_5_.3_3_E-_0_1--+l_s_.1_4_E_-0_1_i_6_.1_5_E_-0_1--ll_1_.0_8_E_+_oo_1--_u_ 18-08150-05 TRG B1-09100A-FSWC-031CV 08/22/1813:30 8/2912018 I 8/29/2018 18-08150 Silver-108m EPA 901.1 Modified -5.31E-02  ! 1.74E-01  : 1.74E-01 j 1.84E-01 J U j pCi/g 18-08150-05 TRG B1-09100A-FSWC-031CV 08/22/18 13:30 / 8/29/2018  ! 8/29/2018 I 18-08150 Americium-241 EPA 901. 1 Modified J 2.06E-01 1 1.81E-01 j 1.81E-01 J 8. 10E-01 I U J_-+p_C_iig=---* 1_1_8_-0_8_1_50-_0_5--+--T_R_G_'-I_s_1_-0_9_10_o_A_-F_s_w_c_-_03_1_c_v_ _ _ _1-_08_12_2_,1_8_1_3_:3_0--+i_8_12_9_12_0_18_,l_8_t2_9_12_0_18-1.-18_-0_8_1_5o_,_s_a_ri_um_-1_3_3--1_ _E_P_A_9_0_1_.1_M __o_d_ifi_ed_ _l:-_1_.8_o_E-_0_3-1,'_1_. 78E-02 I 7 .78E-02 i 3.29E-01 1 u  ! pCi~ .__1_8_-0_8_1_5o_-o_5--+I_ _ T_R_G_'-l_s_1_-0_9_10_o_A_-F_s_w_c_-_03_1_c_v_ _ _--+_08_12_2_11_8_1_3_:3_o--+l-8_t2_9_12_0_1_8-+f-8_1_2_9_12_0_18--1-_18_-0_8_1_50-1__s_is_m_u_th_-2_1_4--1 _ _E_P_A_9_0_1_.1_M __o_d_ifi_ed_ _ l-1_5_.8_2_E-_0_1-+l-2_.5_5_E_-0__1--ll_2_.5_6_E_-0_1_i-+_4._18_E_-_01_+-1 -----1l _____c.P_C_ilg=-----1 18-08150-05 Ij TRG II B1-09100A-FSWC-031CV 08/2211813:30 I 8/29/2018 I 8/29/2018 18-08150 Cobalt-60 EPA901.1 Modified iI 1.21 E-01  !, 1.55E-O~ 1.55E-01 . 2.05E-01 I.I '1 U I

                                                                                                                                                                                                                                                                                                                              '       pCi/g 18-08150-05 ;          TRG            / B1-09100A-FSWC-031CV                              08/22/1813:30         i   8/29/2018 / 8/29/2018          I  16-08150          Cesium-134                EPA901.1 Modified          I/     5.77E-02 1 9.43E-02              .1  9.43E-02 l         1.97E-01 :           U I

pCi/g 1--1-8--0-8-1-50--0-5--+--T-R_G_,__B_1_-0_9_1o_o_A--F-s_w_c___ o3_1_c_v_ _ _ _ 1-_08-,2-2-,1-8_1_3_:3-0+T-8-,2-9-,2-o-1--8+l-8-,2-9-,2-o-18-+-1s._0_8_1_5o-+-c-e-s-iu-m--1-3.-7-I--E-P_A_9_0_1_.1_M_od_ifi_ed--+-2-.7-5-E--o-1-,i-2-.20E-01 1 2.21E--o--1-+-/-3-.5-5E---o-1-+1--u--+i--'-PC-i-'/g_._ 1 1 _1_S-_0_8_1_50-_0_5--+--T-R_G_"-_B_1_-0_9_10-0-A--F-S_W_C---03_1_C_V_ _ _-l--08-/2_2_/1_8_1_3-:3-0--',-8-/2_9_/2-0-18 I 8/29/2018 I 16-08150 i Europium-152 EPA901.1 Modified J -9.96E-02 I 4.22E-01 I 4.22E-01 i 5.32E-01 I--U---:...1---'p-C-i/"-g---1 1 16-08150-05 I TRG I B1-09100A-FSWC-031CV 08/22/1813:30 I 8/29/2018 i 8/29/2018 18-08150 I Europium-154 EPA901.1 Modified -1.60E-02 I 3.64E-01 [ 3.64E-01 i 2.86_E-_0_1--+l_ _u_ __,,1_--'-P_C-'iig_ _. 18-08150-05 I TRG I B1-09100A-FSWC-031CV 08/22/1813:30 / 8/29/2018 / 8/29/2018 16-08150 / Europium-155 EPA901.1 Modified 2.44E-01 I 3.08E-01 i 3.09E-01  ! 5.22E-01 / U i pCi/g l--1-8--0-8-1-50-_0_5--+--T-R_G_,;___8_1_-0_9_10_0_A--F-S_W_C___ I 03_1_C_V_ _ _ _ t--08-/2-2-/1_8_1_3-:3-0--+-8-/2-9-/2-0-1-8 8/29/2018  ! 18-081_5_0--+1-H-o-lm..:.iu_m___1_6_6_m-+--E-P_A_9_0_1._1_M.-o-di-fie-d--l-l-1.-8-1E---01-il--2-.10E-01  ! 2.11E-01 I 2.53E-01 I U I pCi/g

"-;"ii*--o-8-1-5D--05--+,--r*R--G--1-l-s-1--o-9-10_0_A--F-s_w_c___

4 o3_1_c_v_ _ _ _1-_08_/_22-,1-8_1_3-,3-o--+-8-/-29-/2_0_1_8 l_8_/2-9*-,2018 I 18-08150  ! lodine-129 EPA 901.1 Modified  ! -2.00E-01 I 8.57E-01 i 8.57_E_-0_1_,i__ 1 1._07_E_+_oo_.;.. 1 _ _u_ _,_i-===p=C=i/=g===: 18-08150-05 1 TRG I B1-09100A-FSWC-031CV 08/22/1813:30 I 8/29/20181 8/29/2018 18-08150 l Potassium-40 EPA 901.1 Modified 1.09E+01 ' 2.69E+OO ' 2.75E+OO I 2.37E+OO I 1 I pCi/g 1 18-08150-05 1 TRG B1-09100A-FSWC-031CV 08/22/18 13:30 I 8/29/2018 I 8/29/2018 18-0815C>IM.anganese-54 EPA 901.1 Modified / -5.41E-02 1.28E-01 / 1.28E-01-1:_-==1-=87=E=-0=1==:,===U====/===p=C=i,=g==: 1 1--1_8_-0_8_1_50-_0_5--1_ _ T_R_G_,1,__s_1_-0_9_10_o_A_-F_s_w_c_-0_3_1_c_v_ _ _-1 _ _ 08_12_2_11_8_1_3_:3_o-+!_8_12_9_/2018 I 8/29/2018 I 18-08150 I Niobium-94 EPA901.1 Modified j 1.~1E-03 , 1.17E-01 ~E-01_j 1.90E-01 l___ u __[_ _.:,_P_C_itg'---* 1 1--1_s._0_8_1_5o_-0_5--1_ _ T_R_G_+-_s_1_-0_9_10_o_A_-F_s_w_c_-_03_1_c_v_ _ _ _1-_08_12_2_,1_8_1_3_:3_0--1-!_8_12_9_12_018 I 8/2912018 18-08150 i Lead-210 EPA 901.1 Modified 1 2.67E+oo I 3.o~~.03E+Oo I 5._1_1_E_+_oo_1--1I_ _u__+i_,_ep_C_it_g"-- 1S-o815o-o5 TRG I B1-09100A-FSWC-031CV 08/2211813:30 I 8/29/2018 i 8/29/2018 16-08150 l Lead-212 EPA 901.1 Mo__d_ifie__d_ _,_I_1_.0_9E+OO i 3.85E-01 I 3.89E-Q1i5.75E-01 1 pCi/g 18-08150-05 TRG '1 B1-09100A-FSWC-031CV 08/22/1813:30  ! 8/29/2018 I, 8/29/2018 18-08150 1i' Lead-214 EPA 901.1 Modified 1.16800/3.94E-01 / 3.98E-01 / 6.51E-01 /  ! pCi/g

                                                                                                                                                                                                                                                                                                                        ---i,'----'--~--

......_18_-0_8_1_50_-_o5--!--T_R_G_J__s_1_-0_9_10_o_A_-F_s_w_c_-_03_1_c_v_ _ _-1 __ 0_8i_22_,_18_1_3_:3_0_l:_8i_29__,2_0_1_8..jl_8_i29/2018 1 18-08150 J Promethium-145 EPA901.1 Modified 8.81E-02  ! 5.62E-01 I 5.62E-01 i 7.59~~ u ,___.:,_P_C_itg_ _, 1--18_-0_8_1_50-_05--!l!--_T_R_G_+-_s_1_-0_9_10_o_A_-F_s_w_c_-_03_1_c_v_ _ _ _1-_0_81_22_,_18_1_3_:3_0--!_81_29_12_0_1_8-+l_8_t_29_12_0__1_8-~081_~adium-2~6_ EPA901.1 Modified I 5.82E-01 I 2.55E-01 I 2.56E-01 I 4.18E-01  ! 1 pCi/g 16-08150-05 I TRG B1-09100A-FSWC-031CV 08/22/1813:30 8/29/2018 I 8/29/2018 f 18-08150 I Antimony-125 EPA901.1 Modified I 1.27E-01  ! 3.64E-01 i 3.64E-01 ; 5.91E-01 'I- --U--'i--'-p-C_i_/g--

• --18--0-8-1-50--05--!l--'--T-R_G_ _,_1_8_1_-0_9_1O-O-A--F-S_W_C ___03_1_C_V_ _ _-1.._0_8/-22_/_18_1_3-:3_0,--tl-8t-29-/-20_1_8..jj_8_/29/2018 I 1S-08150J Thorium-234 __E_P_A_9_0_1_.1_M_o_d-ifi*e-d--~~80E+OO !3.07E+OO i 3.0_9E_+_o_o_,!__5_.5_3E_+_o_o__,,!_ _u _ _l,_ _.:,_p_C_iig__ _

18-08150-05 I TRG I B1-09100A-FSWC-031CV 08/22/18 13:30 !si29/2018 I 8/29/2018 18-08150 [ T ~ I ~ EPA 901.1 Modified 6.84E-01 I 3.42E-O"li3~43E-01  ! 6.50E-01 I pCi/g 1---18---08-1-50---05_11--_T_R_G_-J-_8_1_-0_9_1O-O-A--F-S_W_C ___ 03_1_C_V_ _ _ _,__ 0_8/-22-/-18_1_3-:3-0--!)'--8/-29/2018 I 8/29/2018 I 18-08150  ! Uranium-235 EPA 901.1 Modified -1.91 E+OO ~6E+OO : 1.97-E+_o_o-"!-1-.2-2-E-+0_0___,1_ _ u _ _:,--'-p-C-i/g _ __, CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANAL YT!CAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [596]

Printed: 9/19/2018 11 :25 AM Page 7 of 12 Report To: Work Order Details: Patricia Giza 18-08150 Eberline Analytical Zion Solutions SDG:

                                                                                                                                                                                                                                            ;;~.'".~se Order:             677118 Final Report of Analysis                                                                                             101 Shiloh Blvd                                                                                         Analysis Category:                 ENVIRONMENTAL Zion, IL 60099                                                                                               Sample Matrix:                so I                                                                                                                                                                                            !

Lab ID II Sample / Type , Client ID Sample Date [ Receipt / Analysis Date  ! Date 1* I Batch ID I,!

                                                                                                                                                                                                          ,       Analyte                     Method                    Result  [      cu     I      CSU         I       MDA            Qualifier I      Report Units 18-08150-06            TRG             B1-09100A-FSFC-001CV                                                   08/22/18 08:52                     [ 8/29/2018        I  8/29/2018      I   18-08150 [ Actinium-228                  EPA 901.1 Modified             6.96E-01  j  5.20E-01   i   5.21E-01       I    9.63E-01             U      :       pCi/g 18-08150-06            TRG             B1-09100A-FSFC-001CV                                                   08/22/1808:52                      I 8/29/20181          8/29/2018118-08"1501                Silver-108m             EPA901.1 Modified             -8.90E-03  l   1.23E-01  1--1.-2-3*-E--0-1-,--i-2.-3-6E---01-s----U===:j-::_-::_-::_-p_c_*-~-!l--

18-08150-06 TRG B1-09100A-FSFC-001CV 08/22/1808:52 J 8/29/2018 I' 8/29/2018 / 18-08150 I Americium-241 EPA901.1 Modified *-...1.51E+OO 1 5.51E-01  ! 5.56E-01 I 5.48E-01 U ' pCi/g 1-1-8--0-8-1-50_-0_6_I__ T_R_G_ _ _B_1_-0_9_10_o_A_-F_S_F_C_-o_o_-1_c-_v-::_-::_-::_-::_-::_-::_-::_=,'=-::_-0_8-::_12-::_2-,_1-::_8-::_o-8::_5-2~-,1-_8_12_91_2_01_8-+i_8_12_91_2_01_8~,I_1_8-_0_81_5_o_l_.s__a_nu_m_-_13_3_ __E_P_A_9_0_1_.1_M_o_d_ifi_ed_-+_4_.01~ 1.41E-01 1 L 1.41-~-0=1==i==4=.5=3=E=-0=1=::===u===11~__-_-_-'-p=C=il_g~_-_~11 18-08150-06 I TRG I B1-09100A-FSFC-001CV 08/22/1808:52 ! 8/29/2018 I 8/29/2018 I 18-08150 I Bismuth-214 EPA901.1 Modified  ! 1.28E+OO I 4.80E-01 f 4.85E-01 I 7.91E-01  !  ! pCi/g 18-08150-06 I 18-08150--0-6*-,--TR_G TRG I B1-09100A-FSFC-001CV

                                     / _B-1--0-91--0-0A 08/22/18 08:52 ! 8/29/2018 [ 8/29/2018                                 I    18-08150 I         Cobalt-60

___F_S_FC---0-01_C_V_ _ _--ll--08-/2_2_/1_8_0_8_:5-2-i/--8-/2_9_/2-0-18-+-i-8-/2_9_/2-0-18-+-/-1-8--0-8-15-0--ll--c-e-si_u_m--1-3_4_ _ _E_P_A._9_0_1_.1_M_o_d_ifi-ed-l -1.32E-02 EPA 901.1 Modified  ! 6.88E-02  ! 1.44E-01 i 1.06E-01 [ 1 1.44E-01 1.06E-01 1 2.69E-01 j 2.53E-01 I U U I I pCi/g pCi/_g__

• -1-8=-0=8=1_5_0-_:o:6::i===T=R=G==:1==B=1=-0=9=10=0=A=-F=S=F=C=-0=0=1C=V========:==08=/-2-2=/1=8=0=8=:5=2=::=8=/2=9=/2=0=1_8-~*,1=8=/2=9=/2=0=18=:1=_1-8=-0=8=1=50=:1==C=e=s=iu=m=-1=3=7---__E_P_A_901.1 Modified i 4.7~_E-01 j 2.54E-01 I 2.55E-01 i,--3.-81-E--0--1-i----1**--p-C1-'/g--

18-08150-06 i TRG i B1-09100A-FSFC-001CV  ! 08/22/18 08:52 I 8/29/2018 8/29/2018 [ 18-08150 I Europium-152 EPA 901.1 Modified / -2.46E-01  : 7.68E-01 1 7.69E-01 6.70E-01 U I pCi/g t-1-8--0-8-1-50-_0_6~,I--T-R-G---1j-B-1--0-9-10_0_A--F-S_F_C_-0_0_1C_V_ _ _ _,_ 08/22/1808:52 I 8/29/2018 I 8/29/2018 I 18-08150 I Europium-154 EPA901.1 Modified G5E-01 i 5.40E-01 i 5.40E~01!-3-.3-3-E--0-1_ _ _ U_--1[--pC~

~~8150-06 /                TRG       I    B1-09100A-FSFC-001CV                                                   08/22/18 08:52                      I 8/29/2018        / 8/29/2018 / 18-08150 , Europium-155 1,                           EPA 901.1 Modified       I     3.53E-02  I  3.15E-01       3.15E-01       /    5.93E-01       j     U      I       pCi/g 18-08150-06            TRG             B1-09100A-FSFC-001CV                                                  08/22/1808:52                       I 8/29/2018 I 8/29/2018 I                18-08150    1   Holmium-166m             EPA901.1 Modi~                 4.53E-02  \3.32E-01     ~E-01              :    2.90E-01             U      i       pCi/g 18-08150-06            TRG       [    B1-09100A-FSFC-001CV                                                   08/22/18 08:52                      ! 8/29/2018 [. 8/29/2018             I   18-08150i         lodine-129             EPA 901.1 Modified       [     2.88E-01  1 9.57E-01    i   9.58E-01       i    1.30E+OO      l      U              pCi/g 18-08150-06       i    TRG       I    B1-09100A-FSFC-001CV                                                   08/22/1808:52                       ! 8/29/2018 i 8/29/2018 .                18-0815QPotassium-40                     EPA901.1 Modified        I    1.41E+01   J  3.49E+OO -[3.57E+OO           :* 3.22E+OO         I                    pCiig 18-08150-06      I     TRG       /    B1-09100A-FSFC-001CV                                                   08/22/1808:52                       i 8/29/2018 I 8/29/2018 I                18-08150    I   Manganese-54             EPA901.1 Modified        j~2E~01            1.67E-01   I   1.67E-01       /    3.03E-01       /     U              pCi/g 18-08150-06       I    TRG       !    B1-09100A-FSFC-001CV                                                   08/22/18 08:52                      : 8/29/2018 I 8/29/2018 I                18-08150    I     Niobium-94             EPA 901.1 Modified       1    -2.40E-02     1.80E-01   [   1.80E-01            2.72E-01             U I

pCi/g 18-08150-06 I TRG B1-09100A-FSFC-001cv 08/22/18 08:52  ! 8/29/2018 ! 8/29/2018 I 18-08150  ! _Le_a_d_-_2_10__ ,____E_P_A_9_01_._1_M_odified I 4.35E+oo  : 5.26E+OO (5.27E_+_o_o-i[ __8_.8_0E_+_o_o_1___u_--+j====pc __ii_g___ 18-08150-06 TRG I B1-09100A-FSFC-001CV 08/22/18 08:52  ! 8/29/2018 l 8/29/2018 J 18-08150  ! Lead-212 EPA 901.1 Modified  ! 7.27E-01 I 3.28E-01 I 3.30E-01 I 9.84E-01  ! U l pCi/g ,____1_8_0_8-15_0-_0_6---;-j--T-RG--;--B-1--09_1_0._0A---F-SF_C___00_1_C_V_ _ _ _ ,_0_8_/2-2/_1_8_08-:-52---;!8f2912018 i 8/29/2018 I 18-08150 I Lead-214 EPA901.1 Modified / 1.51E+OO  ! 4.43E-01 /4.50E-01 i 7.29E-01 !pCi/g-- 18:08150-06 TRG B1-09100A-FSFC-001CV 08/22/1808:52 I 8/29/2018 8/29/2018 I I 18-08150 I Promethium-145 EPA901.1 Modified I -3.70E-01 ~11~1j9.03E---01-~l---U--+i--p-*C-i/_g__ t-1-8--0-8-15_0-_0_6__,cl--T-RG---+I--B-1--0-9-10_0_A--F-S_F_C--0-0-1C-V----lf---08-/2_2_/1_8_0._8_:5_2_j8129!2oislslz912018 I 18-08150 I Radium-226 EPA901.1 Modified [128E+OO 4.80E-01 4.85E-01 I 7.91E-01 1

                                                                                                                                                                                                                                                                                                                                                  !       pCi/g 18-08150-06            TRG       I B1-09100A-FSFC-001CV                                                      08/22/18 08:52 I 8/29/2018 i 8/29/2018                                  i    18-08150    I   Antimony-125             EPA 901.1 Modified       !1.1iE-01       !  4.68E-01   f   4.6!lE-01i--7.-34---E--0-1-;...i--U--ii---p-C-i/_g_ _

18-08150-06 TRG I B1-09100A-FSFC-001CV

---

+----t---------------1------

08/22/18 08:52 I 8/29/2018 I 8/29/2018  ! 18-08150 I Thorium-234 EPA901.1 Modified j8.47E+OO  ! 6.49E+OO 1 6.51E+OO I 1.07E+01 I U pCi/g 18-08150-06 TRG I B1-09100A-FSFC-001CV 08/22/18 08:52 I 8/29/2018 I 8/29/2018 *1 18-08150 i Thallium-208 EPA 901.1 Modified I 9.93E-01 I 4.65E-01 i 4.68E-01  ! 9.53E-01 I U l pCi/g t-1-8--0-8-15-0--0-6~,I--TR-G--;--I-B-1--0-9-10_0_A--F-S_F_C--0-0-1C--V----ii--08-/2_2__/1_8_0_8_:5-2-+!-8-/2_9_/2--0-18i 8/29/2018 , 18-08150 I Uranium-235 EPA901.1 Modified I 5.10E-01 , 2.17E+OO I 2.17E+OO 1 1.50__E_+__O_O_ _,_,l_ _u_ _ _ _p_C_i_/g_ __, CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERUNE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [597]

Printed* 9/19/201811*25AM Page 8 of 12 Report To: Work Order Details: 18-08150 Eberline Analytical Patricia Giza Zion Solutions SDG: Purchase Order: 677118 Final Report of Analysis 101 Shiloh Blvd Analysis r,,t,,~~n,* ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so I I Lab Report cu ID Result i1 CSU MDA / Qualifier/

                                                                                                                                                                                                                                                                                            '           i Units 18-08150-07         I  TRG      !    B1-09100A-FSFC-010CV                           08/22/1812:40 I 8/29/2018 8/29/2018     I                I   18-08150    I    Actinium-228            EPA901.1 Modified           I   6.40E-01       3.60E-01 I 3.61E-01 I 7.20E-01 !                     U     I pCi/g

=1=8-=0=8=15=0=-0=7=:===TR=G===:1==B=1-=0=9=10=0=A-=F=S=F=C-=0=10=C=V========::===08=/2=2=/1=8=1=2==4=0=:1=8=/2=9=/2=0=18=:=8=/2=9=/2=0=18=:1=1=8=-0=8=-15-§J-+-s*-il-ve-,--1-08_m_..,_ _E_P_A_9_0_1_.1_M_o_d_ifi-ed--+l-6-.9-9-E--0-3-+!--6-.2-6-E--02 -+l-6-.2-6E---02--1-1-.0-7-E--0-1--ljllipc~

18-08150-07 f TRG B1-09100A-FSFC-010CV 08/22/1812:40 I 8/29/2018 i 8/29/2018 I 18-08150 I Americium-241 EPA901.1 Modified I 9.55E-02 : 2.26E-01 I 2.26E-01 I 3.02E-01 i U :P~ 1--1-8--0-8-15_0-_0_7-l-l--TR-G--+- 11 -B-1--0-9-1O-O-A--F-S_F_C--0-10-C-V----ll--08-/2_2_/1_8_1_2-:4-0-+!-8-/2_9_/2-0-18--+j-8-/2-9-/2-0-18-+1-1-8-_0_8_15-0-+i-B-a-,i-um---1-33-+--E-P_A_9_0_1_.1_M_o_d_ifi-ed--+I--4-.6-9-E--0-2-rl-1-.6-1-E--0-1-+!-1-.6-1-E--0-1-+-r--csoE-01iU 1 i pCi/g 15_0-_0_1-+/--T-RG-~/,._-B-1--o-9-10-o-A--F-S-F-C--o-10-c-v----ii--08-/2_2_/1_8_1_2_:4-0-1-l-8-/2_9_/2-0-18-+/-8-/2_9_/2-0-18-+i-1-8--0-8-15-o-+J-s-is-m-u-th--2-1 *--E-P_A_9_o_1__1_M_o_d-ifi-ed--l 8.23E-01 / 2.42E-01 ! 2.45E-01 : 3.09E-01 / 1--1-s._0_8__  ! pCi/g 1------+----+-------------1------~,-----i,----+----+,  :-:--i----~c----;------ 18-08150-07 I TRG B1-09100A-FSFC-010CV 08/22/1812:40 l I 8/29/2018 8/29/2018 j 18-08150 I 0 Cobalt-60 EPA 901.1 Modified I 2.45E-02 1.17E-01 i 1.17E-01 I 1.96E-01 I U  ! pCi/g ,--18--0-8-1-50--07--;j--T-R-G-+--B-1--0-9_10_0_A_-F_S_F_C_-0_1_0C-V----l--08-/-22_/_18_1_2-:4_0_!_8_/_29-/2-0-1-8+l-8-/2_9_/2-0-18--i!-18--0-8-1-50-rl-C-e-s-iu-m--1-3-4--l--EP-A-90-1-.1-M-o-d-ifi-e-d--+l-3-.0-9-E---o-2-+!-6-.5-1_E_-O~ 6.51E-02 j__ 1._32_E_-0_1_,_ _u_-;:___p__c__il_g_ 1--18--0-8_1_50--07--l--T-R-G-+ 1-B-1--0-9-10_0_A--F-S_F_C_-0_1_0C_V ______ 08_/_22_/_18_1_2_:4_0_l_8_/_29-/2_0_1_8,~8-/2_9_/2_0_1_8+ll-18--0-8-1-50--;i.-c-e-s-iu-m--1-3_7_1--EP-A-9_?=1=.1=M=o=d-i_fi-e:d:_-+fl-1-.50E-01 1.26E-01 1.27E-_01_,1__2_.0_1E_-_0_1-,..__u_ _l___ PC_i_lg_ _ 1------+----1--------------1-------+----+----+----r----------11----------+--- i 1--1-8--0-8-15_0-_0_7-t-l--TR-G--+-I-B-1--0-91_0_0-A--F-S-FC---o-10-c-v-----l-+--08-/2_2_/1-812:40 ,'I--8/-29-/-20_1_8_,1_8/-29-/-20_1_8_,__18---08_1_5_0 Europium-152 EPA901.1 Modified 1.82E-02 4.03E-01  ! 4.03E-01 I 3.76E_-0_1_,_ _u_ _l___ PC_i_lg___ 1--1_8_-0_8_15_0-_0_1-1-I__TR_G_~lr_s_1-_0_9_1o_o_A-_F_S_F_c-_0_1o_c_v_ _ _ _ -+-_08_12_2_118~~I 8/29/2018 I 8/29/2018 1

                                                                                                                                                !   18-08150 I Europium-154                  EPA901.1 Modified          !   -1.46E-01       3.52E-01      1  3.52E-01     I  1.89E-01       1    u      ~~

18-08150-07 TRG / B1-09100A-FSFC-010CV 08/22/1812:40 I 8/29/2018 j 8/29/2018 i 18-08150 / Europium-155 EPA901.1 Modified i 2.34E-01 I 2.14E-01 !2.14E---o-1-+/-3-.1-7-E--0-1-+!--u--'1 pCi/g 18-08150-07 I TRG I B1-09100A-FSFC-010CV 08/22/1812:40 I 8/29/2018 8/29/2018 I 18-08150 I Holmium-166m EPA901.1 Modified I 8.03E-02 1.67E-01 j 1.67E-o1l 1.70E-01 1 U  ! pCi/g

• -1-8--0-8-1-50--07--fl--T-R_G_.,...I-B-1--o-9_10_o_A_-F_S_F_C_-0_1_oc-v----*--08-,-22-,1-8_1_2_:4_0_i_8_/_2_9_/2_0_1_8-1-8-,2-9-,2-o-18-1-l-18--0-8-1-50-1-i--10-d-in-e--1-29--1---EP-A-90-1-.1-M-o-d-ifi-ed--,I-2-.0-4-E+_o_o--i*-1-.30E+OO I 1.31 E+OO i 1.50E+oo I u ipCi/g 18-08150-07 TRG B1-09100A-FSFC-010CV 08/22/1812:40 [ 8/29/2018 8/29/2018 I 18-08150 I Polassium-40 EPA 901.1 Modified  ! 6.06E+OO 1 2.11E+ool 2.13E+OO [ 2.41E+OO r--i---;c~

18-08150-07 TRG B1-09100A-FSFC-010CV 08/22/1812:40 I 8/29/2018 , 8/29/2018 I 18-08150  ! Manganese-54 EPA 901.1 Modified I -4.44E-02 1 1.16E-01 I 1.16E-01 I 1.71E-01 J U i p~ 18-08150-07 TRG B1-09100A-FSFC-010CV 08/22/1812:40 I 8/29/2018 1 8/29/2018 I 18-08150 j Niobium-94 EPA 901.1 Modified I 7.20E-02 i 9.03E-02 I 9.04E-02 f 1.71E-01 r--Ui pCi/g 1-1-8--0-8-1-50--0-7--ff--T-R_G_,__B_1_-0_9_10_0_A_-F_S_F_C_-0_1_0C-V----t--08-/2_2_/1_8_1_2_:4-0--.l-8-/2_9_/2_0_1_8+-8-/2_9_/2-0-18-t-f-18--0-8-1-50-t-/--L-e-ad--2-1-0--1--E-P_A_9_0_1-.1-M_o_d-ifi-ed--+j-2-.3-6E_+_O_O_f1.92E+ool 1.93E+OO / 3.32E+OOI U / pCi/g 1-:-:-:~-:-:-:~-:~-;---~-:-~-,. .--:-:-:~-:-:~-~-:-::-:-:-~-:~-:-~~-~----,--~:-;-::-,:-:-:-:-::-~~,1-:-;:-:-;:~:: I :;::;:~::Et:::~ : 18-08150-07 TRG B1-09100A-FSFC-010CV 08/22/18 12:40 8/29/2018 8/29/2018 [_18-08150 I Promethium-145

                                                                                                                                                                        ~:: : :~ ::::~::: ~:::--:-:--!-:.--:~::~: : :::~::~ : ~: :~w__::_:;;~

EPA 901.1 Modified  !.I -3.09E-02 I 3.77E-01 3.77E-01 1 5.34E-01 ' U i  :~:;: pCi/g 18-08150-07 I TRG j B1-09100A-FSFC-010CV 08/22/1812:40 !8f2912018  ! 8/29/2018 I 18~50-T-R~dium-226 EPA901.1 Modified 8.23E-01 ] 2.42E-01 I 2.45E-01 , 3.09-E--o-1-1-j----i1*-~p-C-i/g-- 18-08150-07 I TRG J B1-09100A-FSFC-010CV 08/22/1812:40 I 8/29/2018 ! 8/29/2018 I 18-08150 I Antimony-125 EPA901.1 Modified I -3.29E-01 1 2.31E-01 I 2.31-E--0-1~,i-3-.0--1--E*--0-1--1--u--,i--p-C-i/g---t 1 ,_1_S-_0_8_1_50-_0_7_ _ _ T_R_G_+-I_s_1_-0_9_1o_o_A_-F_S_F_C_-0_1o_c_v_ _ _ _*__ 08_!2_2_,1_8_1_2_:4_o_l_8_12_9_12_0_1-+8j 8/29/2018 i 18-0815~]__:rhorium-23_4_ ~ A 901.1 Modified ~05E-01 I 2.16E+OO T2.wE+ool 2.95E+_o_o~___u_~.._ _ pCi/g 18-08150-07 TRG B1-09100A-FSFC-010CV 08/22/1812:40 I 8/29/2018 I 8/29/2018 I 18-08150 I Thallium-208 EPA901.1 Modified I 4.28E-01: 3.13E-01 i 3.14E-01 I 6.17E-01 U  ! pCi/g 18-08150-07 i TRG I B1-09100A-FSFC-010CV 08/22/1812:40 I 8/29/2018  ! 8/29/2018 I 18-081scil-u~-;nium-235 EPA901.1 Modified i 1.39E-01[ 1.51E+oo: 1.51.E+ool-a-:-42E-::o*-1*---u--c-l__p_C,_i/_g__ CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/ 481-0683 FAX 865/ 483-4621 [598]

Printed: 9/19/2018 11 :25 AM Page 9 of 12 Report To: Work Order Details: 1----P-at-r-ic-ia_G_i_z_a-~---------+------S-D_G_:,----i_1_8_-0_8_1_5_0_ _ _ _ _ _ _ _ _ _ _ _ _---1! Eberline Analytical 1----------------------1----------,----------------------------.,I 1---Z_io_n_S_o_lu_t_io_n_s____________+ _ _P_u_rc_h_as_e_O_rd_er:+--_6_7_7_1_1_8________________________11 , Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTAL Zion, IL 60099 Sample Matrix: SO I Sample ! I Ii Lab Client Sample Receipt I Analysis Batch j' Method / Result  ! CU / CSU MDA ./ Qualifier / Report ID  ! 1 Type \ ID Date Date I Date  : ID 1 Analyte I f  : Units 18-08150-08 I TRG  ! B1-09100-FSWC-041CV 08/22/18 08:34 I 8/29/2018 j 8/29/2018 I 18-08150 I Actinium-228 EPA 901.1 Modified 8.33E-01 I 4.15E-01 l_4_._18_E_-0_1_i--_6._65_E_-_01_+-l_ _ _+i__pc...C_il-=-g--l' 18-08150-08 I TRG I B1-09100-FSWC-041CV 08/22/1808:34  ! 8/29/2018 ! 8/29/2018 j 18-08150 I Silver-108m EPA901.1 Modified -1.94E-02 I 1.40E-01 I 1.40E-01 1.58E-01 i u __,____r>__C.i~ 18-08150-08  ! TRG I B1-09100-FSWC-041CV 08/22/18 08:34 I 8/29/2018 I 8/29/2018 I 18-08150 ~icium-241 EPA 901.1 Modified I -6.59E-01 j 3.62E-01 i 3.64E-01 4.60E-01 I U pCi/g 18-08150-08 I TRG I B1-09100-FSWC-041CV 08/22/1808:34 f 8/29/2018 i 8/29/2018 I 18_-_o8_1_5_0-11__ B_ar_iu_m_-1_3_3_1--_E_PA_90_1_.1_M_od_ifi_,e_d_! -1.98E-02 1 6.11E-02 ~E-oz-r-,-3.-44-E---01-+,*--u-----;L---pc~

• -1-8--0-8-15_0-_0_8--fl--T-R-G-+-i-B-1--0-9-10-0--F-S_W_C___ 04_1_c_v_ _ _ _1---08-/2_2_/1_8_0_8_:3-4--;i 8/29/2018 f 8/29/2018 !18-08150 J Bismuth-214 EPA901.1 Modified I 1.23E+0~~01 ~4_E_-_01_i:-_2_.2_5E_-_0_1-;1_ _ _ _ _ _ _P_C_ii_g__,,

18-08150-08 j TRG B1-09100-FSWC-041CV 08/22/1808:34 1 8/29/2018  ! 8/29/2018118-08150 I Cobalt-60 EPA901.1 Modified 8.14E-02 I 1.30E-01 I 1.30E-01 I 1.71E-01 U I pCi/g

                                                                                                             ! 8/29/2018 I 8/29/2018 I 18-08150             I                                                                                                   1 l-1-8--0-8-15-0--0-8-'cj--T-R-G-+---B-1--0-9-10-0--F-S_W_C___   04_1_C_V_ _ _ _l--_08-,2-2-,1-8'08:34                                                             Cesium-134            EPA901.1 Modified         I  -6.6~!      2.78E-01    r-2-.8-0-E--0-1-!_2___       01-E--0-1-i--1--u--1---p-C-i/_g__,,

18-08150-08 j TRG B1-09100-FSWC-041CV 08/22/1808:34 J 8/29/2018 I 8/29/2018 j 18-08150 I Cesium-137 EPA901.1 Modified ~E-oii---'11A4E-01i 1.44E-01 i 2.24E-01 I U I pCi/g 18-08150-08 I TRG ' B1-09100-FSWC-041CV 08/22/1808:34 8/29/2018 I 8/29/2018 j 18-08150 i Europium-152 EPA901.1Modified ~E-011 2.97E-01 I 2.97E-01 *-!-4-.9-9E---o-1-:-l--u--,---p-c*--i-/g___ 18-08150-08 I TRG i B1-09100-FSWC-041CV 08/22/18 08:34 I 8/29/2018 [ 8/29/2018118-08150 I Europium-154 EPA 901.1 Modified I -2 64E-01 I 3 62E-01 I 3.62E-01 i 2.71E-01 I U pCi/g 18-08150-08 / TRG 1* B1-09100-FSWC-041CV 08/22/1808:34  : 8/29/2018 j 8/29/2018 1 18-0815D_J Europium-155 EPA901.1 Modified J 1.~3E-01 ! 3:12E-01 j 3.12E-~-+-1::_5___ 1-7_-E_--::_o-1_-~,/-_-::_-::_-::_u-::_-::_-::_~--=-~--=--pC_i_/g_ _, 18-08150-08 I TRG B1-09100-FSWC-041CV 08/22/18 08:34 I 8/29/2018 I 8/29/2018 1 18-08150 ] Holmium-166m EPA 901.1 Modified l -8.52E-03  : 2.08E-~!_1_2_.0_8E_-0_1_ _ _ 2._49__E_-0_1_;--i__u__ j _ _p_<::it_g__ 18-08150-08 I TRG j B1-09100-FSWC-041CV 08/22/1808:34 i 8/29/2018 i 8/29/20181 18-08150 i lodine-129 EPA901.1 Modified I 6.42E-01 I 7.30E-01 I 7.31E-01 I 1.01E+OO i U pCi/g 18-08150-08  ! TRG I B1-09100-FSWC-041CV 08/22/18 08:34 j 8/29/2018 I 8/29/2018 I 18-08150 I Potassium-40 EPA901.1 Modified I 1.19E+01 I 3.29E+OO ~00 ji--4_.o_2_E__+_oo_+-----+----'p--'C.._ii-=-g-e-1-8--0-8-15-0--o*-8-r-j--TR-G--+-j-B-1--0-91-0-0--F-S-W-C--0-4_1_C_V_ _ _ _1,-o_8_/2_2_/1_8_0_8_:34-I 8/29/2018 I 8/29/2018 I 18-08150 j Manganese-54 EPA901.1 Modifi~ 7.19E-02 I 1.22E-01 I 1.22E-01 i 2.16E-01 1 U i" pCi/g 18-08150-08 I TRG B1-09100-FSWC-041CV 08/22/1808:34 I 8/29/2018  ! 8/29/2018 I 18-08150 I Niobium-94 EPA901.1 Modifi-;;;;--1 -2.24E-02  ! 1.08E-01 I 1.08E-0-1-+-1-.6-6-E--0-1--fj--u---i-~p-C~ 18-08150-08 I TRG B1-09100-FSWC-041CV 08/22/1808:34 I 8/29/2018  ! 8/29/2018 I 18-08150 I Lead-210 EPA901.1 Modified I 4.43E+OO !2.BBE+OCJl2.89E+OO I 5.12E+OO I U pCi/g 18-08150-08 I TRG B1-09100-FSWC-041CV 08/22/1808:34 I 8/29/2018 I 8/29/2018 I 18-08150 ! Lead-212 * -~901.1 Modif~ 7.92E-01 I 2.57E-01 I 2.60E-01 9.05E-01 I U pCi/g 1_1_8-_0_8_15-0--0-8--fj--T-R-G-t--B-1--0-9-10-0--F-S_W_C___ 04_1_c_v_ _ _ _,1--_08-/2_2_/1_8_0_8_:34*-: 8/29/2018 j 8/29/2018 I 18-08150 I Lead-214 EPA901.1 Modified !1.44800i 3.90E-01 [ 3.97E-01~--7--E--0-1-+i---,---p*C--i/g___ 18-08150-08 j TRG I B1-09100-FSWC-041CV 08/22/1808:34 [ 8/29/2018 j 8/29/2018 I 18-08150 i Promethium-145 EPA901.1 Modified I -2.98E-02 I 5.54E-011 5.54E-01 : 7.13E~01i U pCi/g

• -1-8--0-8-15_0-_0_8-+[--T-RG--+-I,-B-1--0-9-10-0--F-S_W_C___ 04_1_c_v_ _ _ _ ,___08-,2-2-,1-8_0_8_:3-4-il8/29/2018Tsf2912018~150 I Radium-226 EPA901.1 Modified!U3E+OO I 2.97E-01 1 3.0-4-E*--o-1--'- 2___2_5_E--o-1-'i-_ _ _,_ _p_C-i/_g_ _

1 ,__1_a-_0_8_15_o_-o_8_1__ T_R_G_i-l_s_1-_0_9_1o_o_-F_s_w__c_-_04_1_c_v_ _ _ _ ,,___00_12_2_11_8_0_8_:3_4~1 8/29/2018 i 8/29/2018 II 18-08150 i Antimony-125 ___§PA 901.1 Modified I 1.85E-01 I 3.20E-01 i 3.20E-01 i 5.3_7E_-_01_ -~i__u_-<___PC_i_tg_ _, 18-08150-08  ![ TRG [ B1-09100-FSWC-041CV 08/22/1808:34 i 8/29/2018 I 8/29/2~-08150 i Thorium-234 EPA901.1 Modified I 6.44E+oo  ! 2.90E+OO /...!:'.l~~~-o~/,._5_.1__ 8E_+_o_o_,!__u_ _,___P_c__ itg_ _ 18-08150-08 , TRG B1-09100-FSWC-041CV 08/22/1808:34 I 8/29/201818/29/2~ 18-08150 I Thallium-208 EPA901.1 Modified I 5.23E-01 I 4.10E-01 j 4.10E-01 , 7.33E-01 , U pCi/g 1 _1_8-_0_8_15-0--0-8-+I--TR-G--+-B-1--0-9-10-0--F-S_W_C___ 04_1__ 1

3-4--+!-8-/2_9_/2-0-18, 8/29/2018 I 18-08150 c_v_ _ _ _ 1----08-/2_2_/1_8_0_8__ I Uranium-235 EPA901.1 Modified  ! -1.02E+OO i--u-;E+oO!mE+OOi~E+OO:--u----p--C-i/g--

CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANAL YT!CAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [599]

Printed: 9/19/201811:25 AM Page 10 of 12 Report To: Work Order Details: Patricia Giza 18-08150 Eberline Analytical ----=---=---::--::---------------1-------~r----=:=cr-:-::--------------------11 Zion Solutions Purchase Order: SDG: 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTAL Zion, IL 60099 Sample Matrix: SO Lab Sample I Client Sample Receipt i Analysis ! Batch I 1 1 i . I Report 11 i Date i ID I Analyte I Result 1' 1 [  : ID Type ID Date Date Method CU 1 CSU j MDA '. Qualifier I Units 1 I 18-08150-09 l1_ _T_R_G_+l_s_1_-0_9_1_oo_A_-F_S_F_c_-o_s_8_Cv_ _ _ _+-_0_81_22_,_18_13_:4_o_l1--8t_29_1_20_1_8-1l_81_29_12_0_1_8-1J_18_-_08_1_5_0-1l_A_c_lin_iu_m_-_2_28_1--_E_PA_9o_1_.1_M_od_ifi_,e_d__,l_3_.o_4_E_-o_2-+i-2_._53_E_-o_1_;-..!_2._5_3E_-_01_,lr_1_.0_2E_+_o_o-+1___u__,.l_~PC_i--'tg~- 18-0815D-ogj TRG I B1-09100A-FSFC-068CV 08/22/1813:40 I 8/29/2018 8/29/2018 I 18-08150 I Silver-108m EPA901.1 Modified I 5.70E-03 1.33E-01 I 1.33E-01 l 1.54E-01  : U I pCi/g 1, 18-08150-09 TRG I B1-09100A-FSFC-068CV 08/22/1813:40 I 8/29/2018 8/29/2018 I 18-08150 I Americium-241 EPA 901.1 Modified  ! -4.51E-02 2.72E-01 2.72E-01 I 3.53E-01 U I pCi/g I t--1-8--0-8-1-50-_0_9~'--T-R-G-+-l-s-1--o-9_10_o_A_-F_S_F_C___0-6-8C-V----I--08_/_22-,1-8_1_3-:4-0 I 8/29/2018 8/29/2018 I 18-08150 I Barium-133 EPA901.1 Modified  ! 1.16E-02 9.13E-02 , 9.13E-02 I 2.53E-01 I U! -~c~ 18-08150-09 ! TRG J B1-09100A-FSFC-068CV 08/22/1813:40  ! 8/29/2018 1 8/29/2018 J 18-08150 I Bismuth-214 EPA901.1 Modified 9.12E-01 1 4.46E-01 4.48E-01 J 8.16E-01 1 1 pCi/g __ t--1-8--0-8-1-50---0-9--+--T-R-G--cl B1-09100A-FSFC-068CV 08/22/1813:40 I 8/29/2018 i 8/29/2018118-08150 f Cobalt-60 EPA901.1 Modified I -1.34E-02 I 5.26E-02_j 5~~E-02 I 1.39E-01 l U pCi/g t--1-8-_0_8_1_50--0-9--+f--T-R-G-+-j-B-1--0-9-10_0_A--F-S_F_C_-0_6_8C-V----1---08-/2_2_/1_8_1_3-:4-0--;.l-8-/2_9_/_2_0_18-+l-8-/2_9_/_2_0_18-+,-18-_0_8_1_50-+j-Cesium-134 EPA901.1 Modified I -3.89E-03  : 6.28E-02 j 6.28E-02  ! 2.06E-01 i U  ! pCi/g t--1-8-_0_8_1_50--0-9,--+I--T-R-G-!--I-B-1--0-9_10_0_A_-F_S_F_C_-0_6_8C-V----l--08-/2_2_/1_8_1_3_:4-0--+I 8/29/2018 I 8/29/2018 ~o I Cesium-137 EPA901.1 Modified i3.66&01!i.ssE-01  ! 1.89E-01  ! 2.69E-01  ! pCi/g 18-08150-09 I TRG I B1-09100A-FSFC-068CV 08/22/1813:40 i 8/29/2018 8/29/2018 I 18-08150 I Europium-152 EPA 901.1 Modified I -9.52E-01  ; 7.96E-01 I 7.98E-01 I 4.71E-01 1 U I pCi/g 1 I _1_8_-0_8_1_5o_-o_9--+--T_R_G_-1-l_s_1_-0_9_1o_o_A_-F_S_F_C_-0_6_8c_v_ _ _ _1--_08_12_21_1_8_1_3_:4_o_l_8_12_9_!2_0_1_8 8/29/2018 I 18-08150 I Europium-154 EPA901.1 Modified i -1.26E-01 I 4.10E-01 4.10E-01 , 2.41E-01 I u I pCi/g __ 18-08150-09 TRG I B1-09100A-FSFC-068CV 08/22/18 13:40 I 8/29/2018 I 8/29/2018 f 18-08150 / Europium-155 EPA 901.1 Modified i 3.23E-02 J 1.45E-01 / 1.45E-01 I 4.08E-01 I U pCi/g 18-08150-09 TRG I B1-09100A-FSFC-068CV 08/22/1813:40 j 8/29/2018 i 8/29/2018 I 18-08150 I Holmium-166m EPA901.1 Modified I 2.07E-01 I 2.44E-01 I 2.44E-01 ' 2.24E-01 I U I pCi/g 18-08150-09 TRG I B1-09100A-FSFC-068CV 08/22/1813:40 I 8/29/2018 i 8/29/2018 [ 18-08150 f lodine-129 EPA901.1 Modified I 2.52E+OO I 1.64E+oo11.64E+OO 1.96E+OO : U I pCi/g t--1-8--0-8-1-50--0-9-f--T-R-G-+-1-B-1--0-9-10_0_A--F-S_F_C--0-68_C_V_ _ _ _ l--08-/2_2_/1_8_1_3-:4-0-+,-8-/2_9_/2-018 i 8/29/2018 [ 18-08150  ! Potassium-40 EPA901.1 Modi~Y4E+OO I 2.69E+OO 2.73E+OO [ 2.82E+(i{)t  ; pCi/g 18-08150-09 1 TRG  ! B1-09100A-FSFC-068CV 08/22/1813:40f 8/29/2018 j 8/29/2018 I 18-08150 I Manganese-54 EPA901.1 Modified f -3.53E-02 I 1.42E-01 1.42E-01 ~3E-01 i U I pCi/g 18-08150-09 TRG I B1-09100A-FSFC-068CV 08/22/1813:40 i 8/29/2018 J 8/29/2018 i 18-08150 i Niobium-94 EPA 901.1 Modified I 8.37E-03 i 1.34E-01 I 1.34E-01 I 2.20E-01 ' U I pCi/g 18-08150-09 ii TRG f B1-09100A-FSFC-068CV 08/22/1813:40 i 8/29/2018 I 8/29/2018  ! 18-08150 I Lead-210 EPA901.1 Modi~___J 3.53E+OO i 2.43E+OO  ! 2.44E+OO i 4.40E+OO  ! U I pCi/g

• -1-8--0-8-15_0-_0_9--+--T-R_G_,I B1-09100A-FSFC-068CV 08/22/1813:40 I 8/29/2018 I 8/29/2018 i 18-08150 I Lead-212 EPA 901.1 Modified  ! 3.79E-01 1 2.91E-01  ! 2.91E-01 j 4.41E-01 I U I pCi/g 1-1-8--0-8-1-50--0-9--+--T-R_G_.,_!-B-1--0-9_10_0_A_-F_S_F_C_-0_68_C_V_____,__

1 08-/2_2_/1_8_1_3_:4_o_l 8/29/2018 i 8/29/2018 I 18-08150 I Lead-214 EPA901.1-Modified I 3.53E-01 1 3.14E-01 I 3.14E-01l~E--:Q1! U i pCi/g ,_1_8_-0_8_1_5o_-o_9--+__ T_R_G_ _ l_s_1_-0__9_10_o_A_-F_S_F_c_-0_68_c_v_ _ _ _ _ _ o8_12_2_11_8_1_3_:4_0__,.l_8_12_9_12_o_18__,_f_8_i2_9_12_o_18-+l_18_-0_8_1_5o_,i Promethium-145 EPA901.1 M o d ~ 4.89E-01 4.89E-01 i 7.59E-01 i u I pCi/g * - ,_1_8_-0_8_1_50-_0_9--+_-T_R_G_.;-.!_s_1_-0_9_10_o_A_-F_S_F_c_-0_68_c_v_ _ _ _ _ _ o8_12_2_11_8_1_3_:4_o-+i_8_12_9_12_o_18_,_J_8_/2_9_i2_018 I 18-08150 [ Radium-226 EPA 901.1 Modified I 9.12E-01 4.46E-01  ! 4.48E-01  !~E-0_1_:_ _ _ _ _ P~~ 18-08150-09 TRG i B1-09100A-FSFC-068CV 08/22/18 13:40 I 8/29/2018 I 8/29/2018 l 18-08150 I Antimony-125 EPA 901.1 Modified I -5.78E-02 (3.39E~01 I 3.39E-01 : 5 76E-01 I U pCi/g l-1-8*--0-8-15-0--0-9~1'--T-RG--;!,--B-1-_0_9_10_0_A_-F_S_F_C--0-68_C_V_ _ _ _ _ _ 08-/2_2_/1_8_1_3_:4-0-;i 8/29/2018 i 8/29/2018 I 18-08150 Ill Thorium-234 EPA901.1 Modified 1~+00  : 2.64E+00-~':.:'.:_0~_J:uio8ooi u pCi/g 18-08150-09 I TRG I B1-09100A-FSFC-068CV 08/22/1813:40 ! 8/29/201818/29/2018 I 18-08150 Thallium-208 EPA901.1Mod~ 6.90E-01 1 3.70E-01 I 3.72E-01 i 7.96E-01 I U I pCi/g 1-1-8--0-8-15-0--0-9-+--T-R_G_'I~,-B-1--0-9-10_0_A--F-S_F_C_-0_68_C_V_ _ _ _ ,__ 08-/2_2_/1_8_1_3,_:4_0_l_8_/2_9_/2_0_18-+[-8-/2_9_/2*-o-18-+[-18-08150 I Uranium-235- ~ P A 901.1 Modified i -6.20E-o;-] 2.10E+OO I 2.10E+OOiLl5E+cioTu--!--P~ CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL I I EBERLINE I 601 ANAL YT!CAL CORPORATION SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [600]

Printed: 9/19/2018 11 :25 AM Page 11 of 12 .: I Report To: Work Order Details: 18-08150 Eberline Analytical Patricia Giza Zion Solutions Purchase Order: SDG:i 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab I. Sample Type I Client ID Sample Date I! Receipt I I Date I Analysis Date i! Batch ID

                                                                                                                                                            ,i I      Analyte                    Method I      Result i      CU
                                                                                                                                                                                                                                                  'l CSU i
                                                                                                                                                                                                                                                                    !    MDA I  Qualifier
                                                                                                                                                                                                                                                                                              Report Units ID           I                                                                                                       I               I                                                                                                  I                                          f 18-08150-10         I   TRG        I    B1-09100A-FSWC-051CV                       08/22/1814:05          I 8/29/2018       I  8/29/2018    !  18-08150 I   Actinium-228             EPA901.1 Modified          I    1.18E+OO  i 5.62E-01     :  5.65E-01      I  1.18E+OO  i     U      I   pCi/g 1-1_8_-o_8_15_0-_10--,1__    T_R_G_+-[_s_1_-0_9_1o_o_A_-F_s_w_c_-0_5_1_c_v_ _ _-1-_08_12_2_11_8_1_4_:o_5~,l_8_t2_9_t2_0_18--+l_8__   12912018 I 18-08150 j Silver-108m                    EPA901.1 Modified          I    5.40E-02     9.37E-02    ! 9.37E-02        i  2.02E-01 '     u       [  pCi/g 18-08150-10 / TRG / 81-09100A-FSWC-051CV                                                                                    I 08/22/1814:05 I 8/29/2018 8 / 2 ~ 18-08150 1 Americium-241                                        EPA901.1 Modified              -7.50E-05   I 1.62E-01     i 1.62E-~7E-01               j     U      I   pCi/g 1

t-1-8--0-8-15-0---10--f--T-RG--+-1-B-1--0-9-10_0_A--F-S_W_C_-0_5_1_C_V_ _ _-1--08-/2_2_/1_8_1_4-:0_5_i_8_/2_9_/2-0-18--+j-8J29/2018 1 I 18-08150 t Barium-133 EPA901.1 Modified I -3.36E-02  ! 8.65E-02 I 8.65E-02 I 3.88E-01 iLJI pCi/g 18-08150-10 TRG  ! 81-09100A-FSWC-051CV 08/22/1814:05 i 8/29/2018 I 8/29/2018 i 18-08150 1-B-is_m_u_th---21-4--<,-..-EP-A-90-1-.1-M_o_d-ifi-,e-d--+J-1-.38E+OO 4.07E-01 I 4.13E-o,l 6.04E-01 i i pCi/g 18-08150-10 I TRG I 81-09100A-FSWC-051CV 08/22/1814:05  ! 8/29/2018 I 8/29/2018 I 18-08150 I Cobalt-60 EPA 901.1 Modified I -2.76E-o2 [1.58E-0.1_J 1.58E-01 [ 2.36E-01 i u---: __ P~- 18-08150-10 I TRG I 81-09100A-FSWC-051CV 08/22/1814:05 / 8/29/2018 / 8/29/2018 I 18-08150 I Cesium-134 EPA901.1 Modified J -1.55E-02 I 5.30E-02 i 5.30E-02 i 2.36E-01 / U pCi/g t-1-8--0-8-15-0--1-0--f--T-RG--i-l-B-1--0-9-10-0-A--F-S-W-C--0-5-1-C-V----1--08-/2-2-/1_8_1_4-:0_5_l8/2912018 ! 8/29/2018 I 18-08150 I Cesium-137 EPA901.1 Modified ~OE-01T1~2E-01 ~-01 12.SSE-01  ! pC~ 18-08150-10 TRG I 81-09100A-FSWC-051CV 08/22/1814:05 i 8/29/2018 I 8/29/2018 I 18-08150 ~opium-152 EPA901.1 Modified 8.85E-02 I 5.33E-01 i 5.33E-01 i 6.45E-01 I U I pCi/g 18-08150-10 I TRG I 81-09100A-FSWC-051CV 08/22/1814:05 I 8/29/2018 I 8/29/2018 [ 18-08150 I Europium-154 EPA901.1 Modified -9.48-E-02 ~07E-01 I 4.07E-01 [ 3.34E-01 [ U l____p~~- 18-08150-10 j TRG i 81-09100A-FSWC-051CV 08/22/1814:05 i 8/29/2018 / 8/29/2018 ! 18-08150 I Europium-155 EPA901.1 Modified -4.61E-02 ' 3.38E-01 I 3.38E-01 / 5.45E-01 ' U / pCi/g 18-08150-10 TRG I B1-09100A-FSWC-051CV 08/22/1814:05 I 8/29/2018 I 8/29/2018 I 18-08150 f Holmium-166m EPA901.1 Modified f 1.08E-02 j 2.49E-01 I 2.49E-01 I 2.70E-01 i U ' pCi/g 18-08150-10 ' TRG I 81-09100A-FSWC-051CV 08/22/1814:05 i 8/29/2018 ! 8/29/2018 118-:08150] lodine-129 EPA 901.1 Modified r~E-01 IB.77E~ 8.77E-01 l 1.21E+OO i u l__!,_~ i

=1=8=-0=8=15=0=-1=0=:1===T=RG===:1==8=1-=0=9=10=0=A=-F=S=W=C=-0=5=1=C=V==========08=/2=2~i1_8_1_4:0_5 I 8/29/2018 8/29/20181 18-08150 i Potassium-40 EPA901.1 Modified I 1.14E+01 3.06E+OO 3.11800i3.15E+OO i I pCi/g 18-08150-10 TRG I B1-09100A-FSWC-051CV 08/22/18 14:051 8/29/2018 ! 8/29/2018 I 18-08150 I Manganese-54 EPA 901.1 Modified l -1.77E-01 1.67E-01 i 1.68E-01 ! 2.10E-01 i U pCi/g 1---1-8--0-8-15-o--1-o--1---TR-G--+-j-s-1--o-91_0_o_A--F-s-w-c--o-5-1-c-v----1--08-/2_2_/1_8_1_4_:o-5--+l-8-,2-9-,2-o-18-;I 8/29/2018 I 18-08150  ! Niobium-94 EPA901.1 Modified i 1.19E-01 006E-01 [ 1.06E.:_(J_1__j 2.12E-01  ! u I

I pCi/g 18-08150-10 TRG  ! 81-09100A-FSWC-051CV 08/22/1814:05 I 8/29/2018 I 8/29/2018 I 18-08150 ! Lead-210 EPA 901.1 Modified I 3.84E+001 -3.3\lE:-oo-i~+OO I 5.95E+OO i U i p~ t-1-8--0-8-15-0--1-0-+--TR-G-~,-I-B-1--0-9-10-0-A--F-S-W-C--0-5-1-C-V----1--08-/2-2-/1--8-1-4:05 I 8/29/2018 I 8/29/2018 ! 18-08150 I Lead-212 EPA901.1 Modified I 7.72E-01 3.05E-01 J 3.08E-01 I 6.48E-01 I I pCi/g 18-08150-10 I TRG I B1-09100A-FSWC-051CV 08/22/1814:05  ! 8/29/20181 8/29/2018 I 18-08150 I Lead-214 EPA901.1 Modified 1.22E+OO  ! 4.49E-01 J 4.54E-01 [ l M E - 0 ~ / - - p C i / _ g__ 11--18--0-8.-1-50--10---<j--T-R-G--~j-B-1--0-9_10_0_A--F-S_W_C___ 05_1_C_V_ _ _-+--08-/-22-/1814:05 I 8/29/2018 I 8/29/2018 I 18-08150 I Promethium-145 EPA901.1 Modified -2.04E-02 l 6.28E-::0_1_i5.28E-Oli823E-01 I U I pCi/g 18-08150-10 I TRG I 81-09100A-FSWC-051CV 08/22/1814:05  ! 8/29/201818'2912018 l_~_:98150 I Radium-226 EPA901.1 Modified I 1.38~3E-01  ; 6.04E-01!-- I pC_if!__ 18-08150-10 I TRG I 81-09100A-FSWC-051CV i 08/22/1814:05 I 8/29/2018 8/29/2018 ) 18-08150 I Antimony-125 EPA901.1 Modified 1.98E-01 I 4.35E-01 I 4.35E-01 I 7.08E-O'!i U  ! pCi/g t-1-8--0-8-1-50---10---!!--T-R-G-,!,--B-1--0-9_10_0_A--F-S_W_C___ 05_1_C_V_ _ _-l--08-/-22-/1_8_1_4-:0-5---!l-8-/2_9_/2_0_1_818:129/2018 I 18-0815D Thorium-234 EPA901.1 Modified 4.67E+OO i 5.04.E+OO-r 5.05E+OO [ 8.42E+OO i U i pCi/g 18-08150-10 1 TRG I 81-09100A-FSWC-051CV 08/22/1814:05 I 8/29/2018 I 8/29/2018  ! 18-08150 I Thallium-208 EPA 901.1 Modified [ 7.01E-01~68E-01 , 3.70E-01 I 4.92E-01 jpc;,;;-- t--18--0-8-1-50---10---!--T-R-G--:--[-B-1--0-9-10-0-A--F-S-W-C---05_1_C_V_ _ _ _,__ 08-/-22-/1_8_1_4-:0-5---!!-8-/-29-/2_0_1_8-+[-8-/29/2018 I 18-08150 ! Uranium---2-35-,~-E-P-A-901.1 Modified I -3.61E-01 1.89E+OO 1.89E+OO I 1.27E+OO i u i ~ / - g-CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [601]

Printed: 9/19/2018 11:25 AM Page 12 of 12 Report To: Work Order Details: Patricia Giza 18-08150 Eberline Analytical Zion Solutions SOG:i Purchase Order: I 677118 ----------------------- Final Report of Analysis 101 Shiloh Blvd Analysis Category: J ENVIRONMENTAL Zion, IL 60099 Sample Matrix: I SO Lab I Sample Sample Receipt I Analysis I Batch I!  ! 1 I li I I Analyte Method Result cu CSU MDA 11: Quarn Report ID I Type Date I Date I

                                                                                                                      'I     Date        1 ID f
                                                                                                                                                                                                                                                                , ier i    Units 18-08150-11         TRG          B1-09100-FSFC-021CV                          08/22/18 12:59        I                 I 812912018 8/29/2018 i 18-08150                      l  Actinium-228 EPA 901.1 Modified       I  1.11E+OO      5.51E-01      5.54E-01  I 1.14E+OO  !      U      I    pCi/g 18-08150-11         TRG I

B1-09100-FSFC-021CV I l I 08/22/18 12:59 i 012912010 -------------**+--E_P_A_9_01_._1 812912010 1 18-08150 l Silver-108m _M_od_ified I 2.12E-02  ; 1.~_E..:.~~ ! 1.92E-01 ,__ u__ i ~~~- 18-08150-11 TRG B1-09100-FSFC-021CV 08/22/18 12:59 - - - - - +1- - 012912018- +812912018 18-08150 I Americium-241

                                                                                                                                             ---..;.--------+--E_P_A_9_0_1_.1_M_o_d_ifi_ed    _ _ l -9.98E-01    ;  3.95E-0.1._j 3.99E-01 !   4.38E-01 1       U      J    pCi/g 18-08150-11 I       TRG 1 B1-09100-FSFC-021CV                                 08/22/18 12:59 [ 8/29/2018 I 812912018                   I   18-08150 I Barium-133          EPA 901.1 Modified       j 7.90E-02    i  1.00E-01 I 1.00E-011      3.49E-01i U             I    pCi/g 1----~

I 18-08150-11 r-----+i-B-1--0-9_10_0_-F_S_F_C_-0_2_1_cv*-----+-------i----,--------------I---E-PA-90-1-.1-M-od-ifi-,e-d--l9.08E-()1 TRG 08/22/18 12:59 I 012912010 I 812912018 I 18-08150 I Bismuth-214 4.27E-01 i 4.30E-01 [ 7.76E-01 1  ! pC~ 18-08150-11

            -    I  TRG     I    B1-09100-FSFC-021CV                          08/22/18 12:59 I 8/29/2018 i 812912018 I 18-08150 I I

Cobalt-60 EPA901.1 Modified I 9.18E-02i'-158E-01 i 1.58E-01 i 2.22E-01 I U i pCi/g 18-08150-11 I TRG I B1-09100-FSFC-021CV I

                                                                          ,-------+----+-----+----+------+--E-P_A_9_0_1-.1-M._o_d-ifie-d--+-/-5-.65~E-0 08/22/18 12:59 I 012912010 8/29/20181 18-08150 / Cesium-134                                                                     21    8.51E-02   ,i 8.52E-02  / 2.18E-01   )     U           pCi/g 18-08150-11 lI      TRG          B1-09100-FSFC-021CV                                                                 !

08/22/18 12:59 f 8/29/2018 8/29/2018 I 18-08150 f Cesium-137 EPA901.1 Modified ~~~~~E-01 I 1.88E-~~7E-01  : l pCi/g 18-08150-11 !  ! TRG I B1-09100-FSFC-021CV 08/22/1812:59  ! 8/29/2018 J 812912018 I I 10-08150 I Europium-152 EPA 901.1 Modified I. -2.91E-~_1_j 5.30E-01 I 5.30E-01 I 6.22E-01 U I pCi/g 18-08150-11 I TRG I B1-09100-FSFC-021CV 08/22/1812:59 I I 8/29/2018 8/29/2018 J 18-08150 I Europium-154 EPA901.1 Modified I 2.92E-02  ; 3.09E-01 ' 3.09E-01 i 3.13E-01 J U pCi/g 18-08150-11 I

         - - + - - TRG
                    - - + - i-B-1--o-9-10_0_-F_S_F_C_-0_2_1c-v-----+-08-/2_2_/1_8_1_2_:5-9_j_,._8_/2_9_/2-0-18--i!--8-/2_9_/2-0-18-+=+l-1-8--0-8-15-0--'~-~r?pium-155     EPA901.1 Modified        i  -1.54E-01  !  3.10E-01    1 3.10E-01i~E-01               u      !    pCi/g 18-08150-11      i  TRG     I    B1-09100-FSFC-021CV                          08/22/18 12:59        ! 8/29/2018       I   8/29/2018 I 18-08150 I Holmium-166m             EPA 901.1 tv1ociffieci!-=ii2i=:-::0212.45E-01         I 2.45E-01 i 2.37E~;u---1                  pCi/g 18-08150-11      I
                 !  TRG     J    B1-09100-FSFC-021CV                          08/22/1812:59         I 8/29/2018       I   8/29/2018    I   18-08150       i   lodine-129  EPA 901.1 Modifi~~E-0~~6E-01                          1 8.36E-01 I  1.08E+O~ i       U     )_ _  P~l!l__

18-08150-11 TRG j B1-09100-FSFC-021CV 08/22/1812:59 1 8/29/2018 18/29!2018-118-08150 j Potassium-40 EPA901.1 Modified I 9.90E+OO i 2.40E+OO i 2.46E+OO i 1.44E+OO ! . pCi/g

         --+---~I-18-08150-11 I TRG             _s_1-_0_9_10_0__
                                             -F_S_F_C_-0_2_1c_v_ _ _ _ _,__                         1 00_12_2_11_0_1_2_:5_9___8_i2_9_t2_0_10-+i_0_12_9_t2_0_10-+i_1_8_-0_8_15_
                                                                                                                                                    ..o-ii Manganese-54   EPA 901.1 Modifi:0 2.18E-02-- /           1~23E-01   !  1.23E-01 1  2.05_E-01  ~~--P~L-18-08150-11     I   TRG     1    B1-09100-FSFC-021CV                                                                 i 08/22/1812:59 I 8/29/2018 8/29/2018 j 18-08150 ~bium-94                                     EPA901.1 Modified        ~02 !            1.29E-01   I  1.29E-01 I  2.03E-01  !      U      :    pCi/g I
         ---+----<--B-1--0-9-10-0--F-S_F_C_-0_2_1c-*v-----*--08-/2_2_/1_8_1_2_:59 18-08150-11         TRG                                                                             I                l 8/29/2018 8/29/2018              I   18-08150       I    Lead-210   EPA901.1 Modi~ 2.25E+OO                I  3.14E+OO   I  3.15E+OO I  5.40E+OO  1      U      !pCilg 18-08150-11      i  TRG          B1-09100-FSFC-021CV                          08/22/1812:59         ! 8/29/2018       I   8/29/2018    I   18-08150       I    Lead-212   EPA901.1 Modified        ~2E-01        !  3.63E-01    j 3.64E-01  j 5.88E-01j               !    pCi/g I 8/29/2018 I

-* --+----+-B-1--0-9-10-0--F-S_F_C_-0_2_1C-V-----l--08-/2_2_/1_8_1_2:59 18-08150-11 18-08150-11 18-08150-11 I' i TRG TRG TRG [ B1-09100-FSFC-021CV I 8/29/2018 08/22/1812:59 i 8/29/2018 8/29/2018 B1-09100-FSFC-o21c-*v-----*--08_/_22-,-10*-1-2-:5_9_j 8/29/2018~18/29/2018 I I I 18-08150  ! Lead-214 18-0815CJIP~ethium-145 18-08150 ~Radium-226 EPA901.1 Modifiedl1lIBE-:;:-OO EPA901.1 Modified EPA901.1 Modified

                                                                                                                                                                                                  !Z29E-01
                                                                                                                                                                                                   ' 9.08E-01 I

3.07E-01

                                                                                                                                                                                                          --~,-----;------

5.86E-01 4.27E-01 1 I I 3.12E-01 5.86E-01 4.30E-01 I I I 4.81E-01 i 7.83E-01 7.76E-01 I r---T U i I i

• pCi/g pCi/g pCi/g 18-08150-11 I! TRG B1-09100-FSFC-021CV 08/22/18 12:59 ! 8/29/2018 ~29/2018 I 18-0S150!Antimony-125 EPA 901.1 Modified I 1.70E-01 i 3.75E-01 I 3.76E-01 i 6.17E-01 J U . pCi/g

          --+----+--B-1--0-9-1-00---F-SF-C---02_1_C_V 18-08150-11     I TRG                                          _ _ _ _-J--0-8-/2-2/_1_8_12-:5_9_.;-I-8-/2-9/-2-01-8-ij 8/29/2018        'I 18-08150!Thorium-23<:_ _ _     E~A 901.1 Modifi~~~_!l_E_..-~-L-3.03E+OO             [  3~~~o~~~~~.:':.~_ _l__!,_~'.~-

18-08150-11 I TRG B1-09100-FSFC-021CV 08/22/1812:59  ! 8/29/20181 8/29/2018 18-08150 j Thallium-208 EPA 901.1 Modified I 5.92E-01 I 4.56E-01  ! 4.57E-01 l 8.27E-01 I U I pCi/g 18-08150-11 l TRG B1-09100-FSFC-021CV 08/22/1812:59 i 8/29/2018, ai29/2018 i 18-08150 ' Uranium-235 EPA901.1 Modified [ -4.77E-01 I 1.84E+OOi1.84E+OO I 1.32E+OO [ U i pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [602]

ZS-WM-131 Revision 0 ZIONSOLUTIONSLLC An EnergySofutions Company Infonnation Use REC'D AUG 2 9 2018 Attachment 1 - Chain-of-Custody Form Sample LO Sample Matrix Sample Sample Container Sample Date Sample 18 Analysis Type

                                                                                                                                           'J Preservative Remarks Log                    Type                                                Time Vol    Unit     Type      Qty B1-09100A-FSFC-067CV                NA          Concrete Concrete 57.94 cm 3    Puck      l       08-22-2018   0920   5 ROC-H3        None      96.20g, 0-1/2'"

s Bl-09100A-FSFC-031CV NA Concrete Concrete 57.94 cm 3 Puck l 08-22-2018 1330 5 ROC-H., None 120.52g, 0-1/2" BI-09100A-FSFC-001 CV NA Concrete Concrete 57.94 cm3 Puck l 08-22-2018 0852 5 ROC-H3 None 98.54g, 0-1/2" B 1-09100A-FSFC-010CV NA Concrete Concrete 57.94 cm3 Puck l 08-22-2018 1240 5 ROC-H3 None 100.IOg 0-1/2" Bl-09100-FSFC-04 ICV NA Concrete Concrete 57.94 cur' Puck 08-22-2018 0834 None 131.64g l 5 ROC-H3 0-1/2" B1-09IOOA-FSFC-068CV NA Concrete Concrete 57.94 cm3 Puck l 08-22-2018 1340 5 ROC-H3 None 82.19g 0-1/2" B 1-09 IOOA-FSFC-05 I CV NA Concrete cm3 JD Concrete 57.94 Puck l 08-22-2018 1405 5 ROC-H3 None 110.94g 0-1/2" B1-09100-FSFC-021CV NA Concrete Concrete 57.94 cm3 Puck l 08-22-2018 1259 5 ROC-H3 None 117.07g 0-1/2" [603]

P//;;_

      ~                                                                                                                                                      ZS-WM-131 Revision 0 ZIONSOLUTIONSuc    An Eno,gySa/Uf/ontColl'fl"n1 Information Use Attachment 1 - Chain-of-Custody Form Sample ID             Sample             Matrix   Sample           Sample Container        Sample Date Sample Analysis Type Preservative  Remarks Log                        Type                                                 Time Vol     Unit      Type      Qty Bl-09100A-FSFC-067CV             NA             Concrete Concrete 57.94   cm3     Puck      !      08-22-2018   0920   5ROC ~          None       96.20g.

l!:!a: vv B1-09100A-F~C-031CV NA Concrete crn3 Concrete ~ Puck  ! 08-22-2018 ill!! 5 ROC-HJ ~ 120.52g. 0-112" B1-09100A-FSFC-001 CV NA Concrete Concrete 57.94 cm3 Puck  ! 08-22-2018 0852 5ROC-HJ None 98.54g. 0-1/2" B l-09100A-FSFC-OIOCV NA Concrete Concrete 57.94 cm3 Puck  ! 08-22-2018 1240 5ROC-HJ None 100.tOg

                ~                                                                                                                                 ~

w B1-09100-F~C-04ICV NA Concrete Concrete cm3 fil.:2f ~  ! 08-22-2018 ~ SROC-HJ ~ 131.64g

                                                                                                                                                  ~

B1-09100A-FSFC-068CV NA Concrete Concrete 57.94 cm3 ~  ! 08-22-2018 fill! 5ROC-Hi None 82.19g I 0-1/2" B1-09100A-F~-OS1CV NA Concrete Concrete 57.94 cm3 Puck  ! 08-22-2018 ~ SROC-Hi ~ 110.94g 0-1/2" B1-09100-FSFC-021CV NA Concrete Concrete ~ cm3 Puck  ! 08-22-2018 1259 SROC-H;i None 117.07g 0-1/2" [604]

ktl'U AUl:i i ~ 2018 ZS-WM-131

          - ~
        /

Revision 0 ZIONSOLUTIONS An EnergySofutions Company LLC 1 os 1 5 0 Infonnation Use Laboratmy: Date Submitted To Lab: Ship Container No.: Cooler Temperature: Eberline Labs NIA NIA Relinquished by: Date; Time: Received by: Date: (mm/dd/yyyy): Time: Jack Mucia 08-28-2018

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Relinquished by: Date Time: Received by: Date: (111111/dcl/yyyy):

  *t?    \                                         (mm/dd/yyyy):

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                                                                             *-r  fet*l Relinquisl~ed by:                                   Dafe              Time:       l Rec;eJ~ed by:                    Dale: (111111/<ld/yyyy):

(mm/dd/yyyy):

      --~:ck Relinquished byr                                    Date              Time:
                                                                                 ~/

• Rdceivcd by, (mm/dd/yyyy):

Comments PO# ANALYSIS 5 ROC HTD-H3 PRIORITY 7 day turnaround PO# 677118 [605]}}