ML19295G826

Revised Final Status Survey (FSS) Report - Phase 2, Release Record - Spent Fuel Pool/Transfer Canal Basement Survey Unit 3202

ML19295G826
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	09/01/2019
From:	Giza P ZionSolutions
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
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References
ZS-2019-0090
Download: ML19295G826 (575)

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{{#Wiki_filter:ZION STATION RESTORATION PROJECT FINAL STATUS SURVEY RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 PREPARED BY / DATE: 2019-09-01 Patsy Giza, Radiological Engineer REVIEWED BY / DATE: 2019-09-01 Jeffery Graham, Radiological Engineer APPROVED BY / DATE: 2019-09-01 D. Wojtkowiak, C/LT Manager [2]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

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

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

3. CLASSIFICATION BASIS ............................................................................................... 9

4. DATA QUALITY OBJECTIVES (DQO) ...................................................................... 19

5. SURVEY DESIGN ........................................................................................................... 23

6. SURVEY IMPLEMENTATION .................................................................................... 30

7. SURVEY RESULTS ........................................................................................................ 31

8. QUALITY CONTROL .................................................................................................... 39

9. INVESTIGATION AND RESULTS .............................................................................. 39

10. REMEDIATION AND RESULTS.................................................................................. 40

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN ...................................... 40

12. DATA QUALITY ASSESSMENT (DQA) ..................................................................... 40

13. ANOMALIES ................................................................................................................... 41

14. COMPLIANCE EQUATION ......................................................................................... 41

15. CONCLUSION ................................................................................................................. 43

16. REFERENCES ................................................................................................................. 43

17. ATTACHMENTS ............................................................................................................. 44 ATTACHMENT 1 FIGURES AND MAPS ..............................................................................45 ATTACHMENT 2 ISOCS GEOMETRY................................................................................48 ATTACHMENT 3 SIGN TEST .............................................................................................67 ATTACHMENT 4 QC MEASUREMENT ASSESSMENTS .......................................................70 ATTACHMENT 5 GRAPHICAL PRESENTATIONS.................................................................72 ATTACHMENT 6 ISOCS ANALYTICAL REPORTS .............................................................78 ATTACHMENT 7 EBERLINE ANALYTICAL REPORTS ............................................................. 558

[3]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 LIST OF FIGURES Figure 1 - Spent Fuel Pool and Transfer Canal Foundation Pad .................................................... 8 Figure 2 - Continuing Characterization Concrete Core Locations ............................................... 12 Figure 3 - Auxiliary Building Ledges ........................................................................................... 16 Figure 4 - Unit 1 Auxiliary Building Ledge Lead Shielding ........................................................ 17 Figure 5 - Unit 2 Auxiliary Building Ledge Lead Shielding ........................................................ 18 Figure 6 - Spent Fuel Pool/Transfer Canal ................................................................................... 32 LIST OF TABLES Table 1 - Spent Fuel Pool Initial Characterization Concrete Core Samples - On-Site Analysis (1)

          ...................................................................................................................................... 10 Table 2 - Spent Fuel Pool Continuing Characterization Concrete Core Samples - On-Site Analysis (2) .................................................................................................................... 13 Table 3 - Spent Fuel Pool Continuing Characterization Concrete Core Samples - Eberline Laboratory Analysis (1) ................................................................................................. 14 Table 4 - Characterization Judgmental ISOCS Measurement Statistical Quantities ................... 15 Table 5 - Dose Significant Radionuclides and Mixture ............................................................... 20 Table 6 - Base Case DCGLs for SFP/Transfer Canal (BCDCGLB) from LTP Chapter 5, Table 5-3....................................................................................................................... 22 Table 7 - Operational DCGLs (OpDCGLB) for SFP/Transfer Canal Basement (pCi/m2) from LTP Chapter 5, Table 5-4 ............................................................................................. 23 Table 8 - Number of ISOCS Measurements per FSS Unit based on Areal Coverage ................. 24 Table 9 - Adjusted Minimum Number of ISOCS Measurements per FSS Unit.......................... 25 Table 10 - ISOCS Geometry for the SFP/Transfer Canal ............................................................ 26 Table 11 - Surrogate Ratios for SFP/Transfer Canal Basement ................................................... 26 Table 12 - Investigation Levels .................................................................................................... 28 Table 13 - Synopsis of Survey Design.......................................................................................... 29 Table 14 - Spent Fuel Pool/Transfer Canal 576 foot Elevation - Measured Concentrations of ROC for FSS ................................................................................................................ 33 Table 15 - SFP/Transfer Canal Statistical Quantities - Systematic Measurement Population ..... 35 Table 16 - SFP/Transfer Canal Statistical Quantities - Systematic Measurement Population ..... 35 Table 17 - Elevated Measurement ROC Concentrations and SOFs ............................................. 37 Table 18 - Summary of ISOCS Replicate Measurements for QC ................................................ 37 Table 19 - Summary of FSS Concrete Core Analysis by Eberline ............................................... 38

[4]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable AMCG Average Member of the Critical Group BFM Basement Fill Model DQA Data Quality Assessment DQO Data Quality Objective DCGL Derived Concentration Guideline Level EMC Elevated Measurement Comparison FSS Final Status Survey HTD Hard-to-Detect IC Insignificant Contributor ISFSI Independent Spent Fuel Storage Installation ISOCS In Situ Object Counting System LTP License Termination Plan LBGR Lower Bound of the Gray Region MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration NaI Sodium Iodide OpDCGL Operational Derived Concentration Guideline Level QAPP Quality Assurance Project Plan QC Quality Control RE Radiological Engineer ROC Radionuclides of Concern SFP Spent Fuel Pool SOF Sum of Fractions TEDE Total Effective Dose Equivalent UBGR Upper Bound of the Gray Region [5]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 UCL Upper Confidence Level URS Unrestricted Release Survey ZNPS Zion Nuclear Power Station ZSRP Zion Station Restoration Project [6]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202

1. EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey unit 03202, Spent Fuel Pool (SFP)/Transfer Canal, has been generated for the Zion Station Restoration Project (ZSRP) in accordance with ZionSolutions procedure ZS-LT-300-001-005, Final Status Survey Data Reporting (Reference 1) and satisfies the requirements of Section 5.11 of the Zion Station Restoration Project License Termination Plan (LTP) (Reference 2). A Final Status Survey (FSS) package (B1-03202A-F) 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). Final Status Survey was conducted to demonstrate that the concentrations of residual radioactivity are equal to or below site-specific Derived Concentration Guideline Levels (DCGL) corresponding to the dose criterion in 10 CFR 20.1402. In accordance with ZSRP LTP Chapter 5, section 5.5.2.1.2 and Table 5-19, the SFP/Transfer Canal 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 on the SFP/Transfer Canal survey unit. The FSS of Class 1 basement survey units require ISOCS measurements over 100% of wall and floors surfaces. Forty-five (45) ISOCS measurement locations were designed assuming a Field-of-View (FOV) for the ISOCS measurement of 28 m2 and based on a 4 m x 4 m (16-meter) grid (LTP Table 5-19) to ensure sufficient overlap for 100% areal coverage. The walk down of the SFP/Transfer Canal by the Radiological Engineer (RE) identified several ISOCS locations that were not physically feasible for survey as originally designed and an additional thirty-one (31) ISOCS measurements were added to the sample plan, for a total of seventy-six (76) ISOCS measurements. See Attachment 2 for ISOCS Geometries. The results from seventy-four (74) of the seventy-six (76) ISOCS measurements taken indicate that the Sum-of-Fractions (OpSOF) for each measurement was less than one (1) when applying the respective Operational DCGLs (OpDCGL) for the SFP/Transfer Canal (see ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey [Reference 5]). However, the two results that exceeded the OpSOF were less than a BcSOF when compared against the Base Case DCGL (BcDCGL). The results also passed the Sign Test; therefore the null hypothesis is rejected and survey unit 03202 is acceptable for unrestricted release. [7]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Figure 1 - Spent Fuel Pool and Transfer Canal Foundation Pad

2. SURVEY UNIT DESCRIPTION The Fuel Handling Building was located between the Unit 1 and Unit 2 Containments and adjacent to the Auxiliary Building. The structure was designed for the storage of new and spent fuel. Major support systems that were located in the Fuel Handling Building included the SFP Heat Exchangers and SFP Skimmer Pumps. The SFP was a 63 feet long by 33 feet wide by 40 feet deep pool located in the east half of the building.

The pool was filled with borated water and contained racks for the storage of spent fuel assemblies. Spent nuclear fuel, highly irradiated reactor components and other highly radioactive debris were stored in the pool. A new fuel storage area and a fuel unloading area were located in the western portion of the building. A cask decontamination pit was located adjacent to the pool. With the exceptions of the service water, de-ionized water, control air, fire protection, nitrogen gas and service air, all of the systems within the Fuel Handling Building were radiologically contaminated internally. The SFP, the decontamination pit, and the equipment cubicles were all posted as Contaminated Areas. The spent fuel located in the SFP was packaged into dry cask storage and transferred to the Independent Spent Fuel Storage Installation (ISFSI) facility. All systems, components and materials located in the Fuel Handling Building were removed and disposed of as radioactive or non-radioactive waste as appropriate. The Fuel Handling Building structure located above the 588 foot elevation was completely demolished. The remaining structure following demolition consisted of the lower portion of the SFP and the Fuel Transfer Canal foundation floors and walls. The west wall of the SFP was reduced to ~ 6 feet in height to allow heavy equipment to enter [8]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 the SFP floor and remove the steel liner. The east wall was also completely removed to provide access to the Transfer Canal liner. The area of this structural survey unit is estimated at approximately 7,783 ft2 or 723 m2.

3. CLASSIFICATION BASIS The SFP/Transfer Canal survey unit 03202 is an impacted Class 1 basement survey unit.

The survey unit applies to the remaining concrete walls and floor surfaces. The survey unit was initially classified in accordance with the Zion Station Historical Site Assessment (HSA) (Reference 6) and verified in accordance with ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification (Reference 7). The potential for residual contamination existed throughout the Fuel Handling Building. Based on the building design basis, the operating history, as well as the areas within the building that were controlled as contaminated, all internal survey units within the Fuel Handling Building were considered to be potentially contaminated. The HSA states that there were two documented overflows of the SFP. The first occurred in April of 1991 and the second occurred in August of 1994. In addition, the HSA also noted that there was a fire in the Transfer Canal area in 1971 (pre-operational) and, that there was a potential leakage path from the pool through the "tell tales drains. Initial site characterization was performed at the Zion site in 2013. At that time, the survey of many inaccessible or not readily accessible building surfaces was deferred due to physical obstructions and/or the presence of prohibitive background from commodities. The end state structure for the Fuel Handling Building was the underlying concrete of the SFP/Transfer Canal after the steel liner had been removed. Characterization was deferred until decommissioning had progressed to the point when the surface of interest was exposed. On June 6, 2016, access was granted into the Fuel Handling Building to acquire characterization data prior to demolition. Demolition of the SFP had progressed to the point where the steel liner was removed exposing the underlying concrete on the bottom of the pool. The FSS staff attempted to scan the bottom of the pool, however the remaining source term in the Transfer Canal created radiation levels that were too high to support scan surveys. Four (4) concrete core samples were acquired in the Spent Fuel Pool on the 576 foot elevation, three on the wall and one on the floor. The analysis of these samples indicated a maximum Cs-137 concentration of 10.50 pCi/g and a maximum Co-60 concentration of 6.12 pCi/g. A summary of the on-site gamma spectroscopy results for the analysis of the concrete cores taken from the SFP floor and walls is presented in Table 1. [9]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Table 1 - Spent Fuel Pool Initial Characterization Concrete Core Samples - On-Site Analysis (1) B1-03202C-JWC-001-CV (east wall) B1-03202C-JWC-002-CV (n. wall) (2) B1-03202C-JWC-003-CV (north wall) B1-03202C-JFC-004-CV (floor) Depth Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 (in) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 0 1.840 0.109 1.660 5.680 0.239 10.500 2.780 0.192 1.550 4.930 0.437 5.680 0.5 1.090 0.104 1.180 3.770 0.191 4.800 2.310 0.192 1.010 4.280 0.485 4.280 0.5 0.111 0.073 0.072 0.164 0.147 0.160 2.500 0.164 0.440 0.306 0.166 0.221 1 0.138 0.081 0.090 0.334 0.122 0.183 2.130 0.206 0.204 0.333 0.160 0.249 1 0.087 0.096 0.100 0.296 0.181 0.149 2.960 0.130 0.540 0.278 0.045 0.115 1.5 0.118 0.083 0.102 0.274 0.165 0.136 3.340 0.121 0.363 0.294 0.180 0.186 1.5 0.155 0.092 0.086 6.120 0.168 0.812 0.266 0.186 0.222 2 0.197 0.123 0.112 5.470 0.168 0.651 0.308 0.138 0.247 2 0.125 0.121 0.145 0.158 0.140 0.132 2.700 0.169 0.378 0.354 0.169 0.133 2.5 0.134 0.105 0.089 0.238 0.124 0.159 3.020 0.142 0.339 0.270 0.256 0.195 2.5 0.148 0.390 0.140 0.749 0.084 0.173 0.542 0.111 0.161 0.329 0.138 0.270 3 0.148 0.155 0.128 0.610 0.141 0.221 0.223 0.129 0.242 3 0.232 0.125 0.155 0.470 0.102 0.206 0.216 0.159 0.181 3.5 0.305 0.165 0.172 0.590 0.172 0.160 0.300 0.120 0.170 3.5 0.212 0.118 0.149 3.880 0.142 0.650 0.247 0.168 0.167 4 0.223 0.112 0.142 0.247 0.111 0.142 4 0.208 0.109 0.066 0.228 0.046 0.166 4.5 0.226 0.118 0.143 0.230 0.126 0.166 4.5 0.183 0.143 0.142 0.338 0.146 0.224 5 0.243 0.122 0.132 0.338 0.177 0.145 5 0.159 0.129 0.065 0.359 0.151 0.185 5.5 0.174 0.117 0.095 0.408 0.128 0.233 5.5 0.059 0.049 0.054 0.406 0.168 0.184 6 0.294 0.105 0.176 6 0.154 0.076 0.091 (1) Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. (2) Puck representing 1.5 to 2 inches from core B1-03202C-JWC-002-CV destroyed during segmentation [10]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 An additional continuing characterization survey was performed on April 2, 2018. The objective of the continuing characterization survey was to assess the depth of any activation in the concrete and to ensure the correct geometry was used for the ISOCS measurements. The survey consisted of scans of the exposed concrete surfaces and the acquisition of eight concrete core samples. The entire remaining SFP concrete surface was scanned using the Ludlum Model 2360 paired with a Ludlum Model 43-93 alpha-beta probe. During the beta scan surveys, several elevated areas were identified. Additional scans were performed using a Ludlum 2350-1 data logger paired with a Model 44-10 Sodium Iodide (NaI) detector as well as an Eberline RO-20 dose rate meter. The results indicted radiation levels between 1.0 - 1.5 mR/hr on nearby ledges from the adjacent Auxiliary Building structure (see Figures 3 through 5). These radiation levels were identified as causing elevated survey results and multiple scan alarms along the east end of the SFP basement footprint. To the extent possible, the locations selected for concrete core samples were identified by the scan measurement on the surface that exhibited the highest activity. Each core was segmented into 1/2-inch concrete core pucks, which were then analyzed by the on-site gamma spectroscopy system for gamma-emitting radionuclides. The top 1/2-inch puck from each of the continuing characterization concrete core samples, representing the concrete from the exposed surface to a depth of 1/2-inch, was sent to Eberline Laboratory for analysis of the full suite of radionuclides. The purpose of the analysis was to verify that the mixture used to infer Hard-to-Detect (HTD) radionuclides was valid and conservative. The results of the analysis of continuing characterization concrete core samples are presented in Table 2. The results of the analysis of concrete cores for the full suite of radionuclides by the off-site laboratory is presented in Table 3. See Figure 2 for a graphic depiction of the sample locations. [11]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Figure 2 - Continuing Characterization Concrete Core Locations [12]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Table 2 - Spent Fuel Pool Continuing Characterization Concrete Core Samples - On-Site Analysis (2) B1-03203A-CJFC-004-CV (1) B1-03203A-CJFC-005- CV (1) B1-03202A-CJWC-006CV B1-03202A-CJFC-007-CV Depth Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 (in) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 0 2.35E-01 8.02E-02 2.26E-01 1.40E-01 1.89E-02 7.34E-02 2.28E+00 1.68E-02 3.16E+00 1.81E+00 5.45E-02 1.71E+00 0.5 1.93E-01 2.30E-02 1.61E-01 4.23E-01 2.28E-02 2.64E-02 1.05E+00 2.24E-02 1.34E+00 7.99E-01 0.00E+00 6.06E-01 0.5 0.00E+00 0.00E+00 9.48E-03 8.31E-02 1.13E-02 1.93E-01 1 9.51E-02 0.00E+00 0.00E+00 1.14E-01 1.10E-02 0.00E+00 1 4.44E-02 5.38E-02 0.00E+00 4.26E-02 0.00E+00 1.01E-01 1.5 2.16E-02 2.40E-02 5.30E-02 3.17E-02 2.97E-02 9.29E-02 1.5 0.00E+00 4.30E-02 1.28E-01 9.57E-02 2.43E-02 6.23E-02 2 2.83E-02 7.86E-03 5.59E-02 6.38E-02 0.00E+00 4.83E-02 B1-03202A-CJFC-008- CV (1) B1-03202A-CJFC-009- CV (1) B1-03202A-CJFC-010-CV B1-03202A-CJFC-011- CV (1) Depth Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 (in) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) 0 6.01E+00 2.97E-01 4.65E+00 0.00E+00 4.52E-02 2.35E-02 1.42E+01 0.00E+00 7.46E+00 7.23E-01 4.36E-02 5.15E-01 0.5 5.21E+00 7.74E-02 3.33E+00 4.06E-02 1.95E-01 8.08E-02 6.33E+00 0.00E+00 3.47E+00 5.53E-01 9.07E-02 2.45E-01 0.5 1.14E-01 0.00E+00 0.00E+00 1 1.42E-02 0.00E+00 0.00E+00 1 1.75E-01 0.00E+00 1.18E-01 1.5 2.94E-01 1.15E-01 2.02E-01 1.5 6.09E-02 1.79E-02 0.00E+00 2 1.56E-01 9.52E-02 6.79E-02 (1) Only the 1st half-inch was cut into pucks for analysis as scans of the remaining core indicated no significant residual radioactivity below the 1st half-inch. (2) Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. [13]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Table 3 - Spent Fuel Pool Continuing Characterization Concrete Core Samples - Eberline Laboratory Analysis (1) B1-03202A- B1-03202A- B1-03202A- B1-03202A- B1-03202A- B1-03202A- B1-03202A- B1-03202A-Radionuclide CJFC-004-CV CJFC-005-CV CJWC-006-CV CJFC-007-CV CJFC-008-CV CJFC-009-CV CJFC-010-CV CJFC-011-CV (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) H-3 0.00E+00 3.03E+00 3.04E+00 6.05E+00 -2.77E+00 -3.00E+00 -2.75E+00 1.44E+00 C-14 2.15E-01 6.88E-01 1.07E+00 2.09E-01 -8.16E-02 -6.03E-01 4.71E-01 6.84E-01 Fe-55 0.00E+00 1.94E-01 -6.52E-02 4.31E-03 1.03E-01 1.55E-01 -1.09E-01 -1.28E-01 Ni-59 0.00E+00 1.25E-02 1.09E-01 -1.26E-02 -9.22E-02 -4.09E-01 7.61E-02 -2.50E-01 Co-60 4.14E-02 4.56E-01 3.83E+00 1.52E+00 4.59E+00 2.15E-04 2.55E+01 9.79E-01 Ni-63 7.97E-01 7.11E-01 1.30E+01 9.79E+00 9.30E+01 3.53E-01 1.49E+01 3.14E+00 Sr-90 0.00E+00 -3.61E-02 4.82E-02 2.85E-01 1.50E-01 2.05E-01 -3.79E-01 3.66E-01 Nb-94 0.00E+00 -1.46E-02 -5.31E-02 -3.84E-02 3.20E-05 -4.96E-02 1.15E-01 -1.11E-01 Tc-99 5.77E-01 1.05E+00 8.38E-01 7.68E-01 1.01E+00 6.56E-01 8.03E-01 8.56E-01 Ag-108m 0.00E+00 -5.07E-02 5.04E-02 -9.03E-03 -4.89E-03 8.37E-02 -1.83E-01 1.27E-01 Sb-125 0.00E+00 3.92E-01 3.78E-02 -9.98E-02 1.37E-01 2.14E-01 8.39E-02 1.21E-01 Cs-134 0.00E+00 -1.61E-01 3.95E-03 6.39E-04 -3.67E-02 1.23E-02 2.62E-02 -1.21E-01 Cs-137 1.56E-01 1.69E-01 6.11E+00 1.71E+00 8.24E-01 1.02E-01 1.03E+01 4.30E-01 Pm-147 1.12E-01 1.12E-01 1.12E+00 1.20E+00 1.19E+00 5.38E-01 9.15E-01 1.57E+00 Eu-152 5.13E-02 2.90E+00 7.80E-01 9.44E-02 -7.05E-02 2.52E-01 -5.54E-02 2.63E+00 Eu-154 0.00E+00 2.27E-01 -1.47E-01 -8.61E-02 1.42E-01 -1.75E-01 -2.15E-01 1.62E-01 Eu-155 4.84E-02 1.09E+00 5.51E-01 3.97E-02 1.08E-01 -1.75E-01 1.26E-01 6.39E-01 Np-237 0.00E+00 6.46E-03 -1.79E-02 1.36E-02 9.28E-03 -8.95E-03 2.78E-02 2.24E-03 Pu-238 4.04E-02 -4.85E-02 -2.65E-02 1.23E-01 3.73E-02 2.17E-02 -2.86E-02 1.66E-02 Pu-239/240 0.00E+00 -3.64E-02 -2.12E-02 1.70E-02 6.56E-02 3.32E-02 -1.91E-02 -1.37E-02 Pu-241 2.61E+00 -1.29E+02 3.34E+00 0.00E+00 -1.11E+00 4.24E+00 3.81E-02 -4.74E+00 Am-241 2.53E-02 2.13E-02 3.05E-02 2.26E-02 3.29E-02 1.93E-02 -2.65E+00 -1.88E-03 Am-243 0.00E+00 5.20E-02 5.15E-02 3.17E-02 2.04E-02 2.09E-02 1.30E-02 1.98E-02 Cm-243/244 8.42E-03 2.13E-02 1.70E-02 0.00E+00 3.96E-02 1.93E-02 8.11E-03 3.17E-03 (1) Bold values indicate concentration greater than MDC. Italicized values indicate MDC value. [14]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Following the acquisition of continuing characterization samples; the onsite contractor continued with the remediation of the exposed concrete of the SFP/Transfer Canal by scabbling with heavy machinery. After the completion of remediation, 19 judgmental ISOCS measurements were taken of the exposed concrete in an effort to determine if remediation was sufficient. Hand scanning still indicated elevated measurements along the east edge of the concrete pad adjacent to the Auxiliary Building. It was speculated that the elevated scan measurements were due to shine from the ledges that were previously identified and not from insufficient remediation. Consequently, lead blankets were placed on the ledges (outside of the SFP/Transfer Canal survey unit) prior to taking the ISOCS measurements (see Figures 4 and 5). The nineteen (19) judgmental ISOCS measurements were collected during continuing characterization. These measurements were not designed to demonstrate compliance. The statistical quantities resulting from the characterization ISOCS measurements are presented in Table 4. The results verified that the gamma shine coming from the elevated ledge areas would not impact the successful implementation of FSS in the SFP/Transfer Canal basement survey unit as long as the shielding remained in place. Table 4 - Characterization Judgmental ISOCS Measurement Statistical Quantities MEAN MEDIAN MAX MIN ST. DEV. ROC 2 2 2 2 (pCi/m ) (pCi/m ) (pCi/m ) (pCi/m ) (pCi/m2) Co-60 8.85E+04 7.18E+04 2.24E+05 2.61E+04 5.03E+04 Ni-63 1.60E+07 1.30E+07 4.04E+07 4.71E+06 9.08E+06 Sr-90 2.57E+03 5.48E+02 1.47E+04 2.38E+01 3.70E+03 Cs-134 4.79E+04 4.11E+04 1.41E+05 2.90E+04 2.47E+04 Cs-137 1.28E+06 2.74E+05 7.33E+06 1.19E+04 1.85E+06 [15]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Figure 3 - Auxiliary Building Ledges [16]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Figure 4 - Unit 1 Auxiliary Building Ledge Lead Shielding [17]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Figure 5 - Unit 2 Auxiliary Building Ledge Lead Shielding [18]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 A FSS RE performed a visual inspection and walk-down of the survey unit on 04/02/2018 prior to performing FSS. The purpose of the walk-down was to assess the physical condition of the survey unit, evaluate access points and travel paths and identify potentially hazardous conditions. A final classification assessment was performed in accordance with procedure ZS-LT-300-001-002, Survey Unit Classification as part of the survey design for FSS. Based upon completion of Survey Unit Classification Basis for final classification, which included a review of the historical information, the results of the Characterization Survey data and completion of final Survey Unit Classification Worksheet, it was concluded that the correct classification of Survey Unit 03202 was Class 1.

4. DATA QUALITY OBJECTIVES (DQO)

Final Status Survey planning and design hinges on coherence with the Data Quality Objective (DQO) process to ensure, through compliance with explicitly defined inputs and boundaries, that the primary objective of the survey is satisfied. The DQO process is described in the ZSRP LTP in accordance with MARSSIM. The appropriate design for a given survey 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 03202 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 Radionuclides of Concern (ROC) for the decommissioning of the Zion Nuclear Power Station (ZNPS). LTP Chapter 2 provides [19]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 detailed characterization data that described contamination levels in the basements. The survey data for this basement is based on core samples obtained at biased locations with elevated contact dose rates and/or evidence of leaks/spills and analyzed for the presence of plant-derived radionuclides. ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms (Reference 9) evaluated the results of the concrete core analysis data from the Containments and Auxiliary Building and refined the initial suite of radionuclides to 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, which are gamma emitters and Ni-63 and Sr-90, which are 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 ZNPS, including the elimination of insignificant dose contributors (IC) from the initial suite. LTP section 6.5.2 also states that the Auxiliary Building basement ROC and the IC percentage of 5% for adjusting ROC DCGLs will also be applied to all other basements with the possible exception of the SFP/Transfer Canal depending on the results of continuing characterization. The results of continuing characterization indicated that the Auxiliary Building mixture was appropriate for use on the SFP/Transfer Canal concrete. Table 5 presents the ROC for the Auxiliary Building basement structural surfaces and the normalized fractions based on the radionuclide mixture. Table 5 - Dose Significant Radionuclides and Mixture

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

Co-60 0.92 Cs-134 0.01 Cs-137 75.32 Ni-63 23.71 Sr-90 0.05 (1) Based on maximum percent of total activity from Table 20 of TSD 14-019, normalized to one for the dose significant radionuclides. [20]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 A fundamental precursor to survey design is to establish a relationship between the release criteria and some measurable quantity. This is done through the development of DCGLs. The DCGLs represent average levels of radioactivity above background levels and are presented in terms of surface or mass activity concentrations. Chapter 6 of the LTP describes in detail the modeling used to develop the DCGLs for structures. The End State Basements will be comprised of steel and/or concrete structures which will be covered by at least three feet of clean soil and physically altered to a condition which would not realistically allow the remaining structures, if excavated, to be occupied. The exposure pathways in the basement fill model (BFM) are associated with residual radioactivity in floors and walls 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 DCGLs in units of pCi/m2, which are calculated using the BFM Groundwater (GW) and BFM Drilling Spoils Dose Factors (LTP Chapter 6, Tables 6-24 and 6-25). The DCGLs for basement structure surfaces are calculated separately for the GW and Drilling Spoils scenarios and for the summation of both scenarios. The summation DCGL is designated as the BcDCGL and is used during 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. 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. A surface area adjustment was required to account for the contribution of residual radioactivity in the SFP/Transfer Canal to the groundwater pathway. As discussed in section 6.5.4 of LTP Chapter 6, the SFP/Transfer Canal geometry could not support a water well and therefore, the BFM Groundwater Dose Factor was set to zero. However, there was the potential for the residual radioactivity in the SFP/Transfer Canal to contribute to the groundwater pathway by mixing with the Containment basement [21]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 through the Fuel Transfer Tube. The DCGL calculations conservatively assumed that the activity in the SFP/Transfer Canal was in both the Containment and Auxiliary Building basement simultaneously. Consequently, the DCGLs for SFP/Transfer Canal were set equal to the lower of either the Auxiliary or Containment DCGL. The Containment DCGLs were lower for all ROC and therefore, the SFP/Transfer Canal BcDCGLs were set equal to the Containment BcDCGLs. The BcDCGLs for the unrestricted release of the Spent Fuel Pool and Transfer Canal survey unit are provided in Table 6. The IC dose percentage of 5% was used to adjust the SFP/Transfer Canal BcDCGLs to account for the dose from the eliminated IC radionuclides. Table 6 - Base Case DCGLs for SFP/Transfer Canal (BCDCGLB) from LTP Chapter 5, Table 5-3 BcDCGLB Radionuclide (pCi/m2) Co-60 1.57E+08 Ni-63 4.02E+09 Sr-90 1.43E+06 Cs-134 3.01E+07 Cs-137 3.94E+07 Each radionuclide-specific BcDCGL is equivalent to the level of residual radioactivity (above background levels) that could, when considered independently, result in a Total Effective Dose Equivalent (TEDE) of 25 mrem/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 can be related to the BcDCGLs as an expected fraction of dose based on an a priori assessment of what the expected dose should be based on the results of site characterization, process knowledge and the extent of planned remediation. The OpDCGL is then used as the DCGL for the FSS design of the survey unit (calculation of surrogate DCGLs, investigations levels, etc.). Details of the OpDCGLs derived for each dose component and the basis for the applied a priori dose fractions are provided in TSD 17-004. The OpDCGLs for the unrestricted release of the SFP/Transfer Canal basement survey unit 03202 are provided in Table 7. [22]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Table 7 - Operational DCGLs (OpDCGLB) for SFP/Transfer Canal Basement (pCi/m2) from LTP Chapter 5, Table 5-4 OpDCGLB Radionuclide (pCi/m2) Co-60 3.28E+07 Ni-63 8.41E+08 Sr-90 2.99E+05 Cs-134 6.30E+06 Cs-137 8.24E+06 Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the OpDCGL. The ISOCS was selected as the primary instrument used to perform FSS of basement surfaces. 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 minimum detectable concentration (MDC). Negative values were recorded as zero. For radionuclides less than MDC, the value representing the highest abundance was selected. Results were not reported as less than MDC. Sample report summaries included unique sample identification, analytical method, radionuclide, result, uncertainty, laboratory data qualifiers, units, and the observed MDC. In accordance with the LTP, for laboratory analysis, MDCs less than 10% of the OpDCGL were preferable while MDCs up to 50% of the OpDCGL were acceptable. The maximum acceptable MDC for measurements obtained using field instruments was 50 percent of the applicable OpDCGL.

5. SURVEY DESIGN Guidance for preparing FSS plans was provided in procedure ZS-LT-300-001-001 Final Status Survey Package Development.

The ISOCS was selected as the primary instrument for performing FSS of basement surfaces. The ISOCS was selected as the instrument of choice to perform FSS of basement surfaces due to the fact that an ISOCS measurement will provide results that can be used directly to determine total activity with depth in concrete and, the surface [23]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 area covered by a single ISOCS measurement is large (a nominal FOV of 10-30 m2) which essentially eliminates the need for scan surveys. In addition, after an ISOCS measurement is collected, it can be tested against a variety of geometry assumptions to address uncertainty in the source term geometry if necessary. The source term geometry for ISOCS efficiency calibration, i.e., concentration depth profile and areal distribution of the residual radioactivity in structures, is required to generate efficiency curves (i.e., efficiency as a function of energy) for the ISOCS gamma spectroscopy measurements. The concrete cores obtained during characterization, continuing characterization and FSS provided the requisite information regarding the distribution of activity with depth for the SFP/Transfer Canal concrete. The basis for the chosen ISOCS efficiency calibrations for the FSS of the SFP/Transfer Canal concrete are documented in ZionSolutions TSD 14-022, Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures (Reference 10). Several different ISOCS geometries were developed for the SFP/Transfer Canal concrete, ranging from a 3 meter diameter source to a geometry design with a FOV of 3.14 m2. The basis for the selection of these geometries were the result of concrete core samples taken during continuing characterization which were analyzed for ROC concentrations at depth in concrete. In section 5.5.2.2 of the LTP, the number of ISOCS measurements required in each FSS unit was calculated as the quotient of the ISOCS FOV divided into the surface area required for areal coverage. Table 8, which is reproduced from LTP Table 5-18, presents the FSS unit for the SFP/Transfer Canal, 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. Table 8 - 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) SFP/Transfer Canal Class 1 723 100% 26 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. [24]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Following MARSSIM guidance, the Type I and Type II decision errors were set at 0.05. The upper boundary of the gray region 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. At the time of LTP submittal, access to the end-state surface was not possible in the SFP/Transfer Canal FSS unit. As reasonable value for sigma () could not be determined based on existing survey data, 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 relative shift (/) for the SFP/Transfer Canal was greater than three. Consequently, a value of three was used as the adjusted relative shift (/). 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. Consequently, no adjustment was necessary as the number of measurements required to meet 100% areal coverall assuming a FOV of 28 m2 was larger. 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 measurements 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 SFP/Transfer Canal 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 9, which is reproduced from LTP Table 5-19, presents the SFP/Transfer Canal FSS unit and the adjusted number of ISOCS measurements that will be taken. Table 9 - Adjusted Minimum Number of ISOCS Measurements per FSS Unit Required Adjusted # of Adjusted Adjusted Areal ISOCS Areal Areal FSS Unit Classification Coverage Measurements Coverage Coverage (m2) (FOV-28 m2) (m2) (% of Area) SFP/Transfer Canal Class 1 723 45(1) 723 100% (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 4m grid system). [25]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Forty-five (45) ISOCS measurements were originally planned as per the LTP Table 5-19. During the walk down of the SFP/Transfer Canal, several ISOCS measurement locations were determined to be not physically feasible for survey and modifications were made to the FOV to accommodate the 100% areal coverage requirement. Thirty-one (31) additional ISOCS measurements were added to the original forty-five (45) resulting in a total of seventy-six (76) ISOCS measurements required for the FSS of the SFP/Transfer Canal basement. Attachment 1, Figures and Maps illustrates the locations of the ISOCS measurements taken and Attachment 2 summarizes the ISOCS geometries that were used. A summary of the ISOCS geometries that were used for SFP/Transfer Canal FSS ISOCS measurements is presented in Table 10. Table 10 - ISOCS Geometry for the SFP/Transfer Canal Detector to

             # of ISOCS                                         Geometry Source       Collimator Locations                                   Circular-Plane (CP)

(Meters) 12 3 90 28.3m2 FOV 8 2.7 90 23.0m2 FOV 12 2 90 12.6m2 FOV 24 1.5 90 7.1m2 FOV 20 1 90 3.1m2 FOV The DQO process determined that Co-60, Ni-63, Sr-90, Cs-134, Cs-137 would be the ROC in Survey Unit 03202. During FSS, concentrations for HTD ROC Ni-63 and Sr-90 are inferred using a surrogate approach specified in LTP section 5.2.11. Cs-137 is the principle surrogate radionuclide for Sr-90 and Co-60 is the principle surrogate radionuclide for Ni-63. The mean, maximum and 95% Upper Confidence Level (UCL) of the surrogate ratios for concrete core samples taken in the SFP/Transfer Canal basement were calculated in TSD 14-019 and are presented in Table 11, which is reproduced from LTP Chapter 5, Table 5-12. Table 11 - Surrogate Ratios for SFP/Transfer Canal Basement SFP/Transfer Canal 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 03202, the surrogate OpDCGLs for Co-60 and Cs-137 were based on the maximum ratios from Table 11. The equation for calculating surrogate DCGLs is provided below: [26]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Equation 1 1

               =

1 2 3

                                                              +     +        +

2 3 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide Using the OpDCGLs for the SFP/Transfer Canal presented in Table 7 and the maximum ratios from Table 11, the following surrogate calculations were performed for FSS unit 03202; Equation 2 1 (137) = = 7.81 + 06 /2 1 0.002

                                                                              +

8.24 + 06(137) 2.99 + 05(90) The surrogate OpDCGL that was used for Cs-137 in FSS unit 03202 for direct comparison of sample results to demonstrate compliance is 7.81E+06 pCi/m2. Equation 3 1 (60) = = 4.08 + 06 /2 1 180.45

                                                                            +

3.28 + 07(60) 8.41 + 08(63) The surrogate OpDCGL that was used for Co-60 in FSS unit 03202 for direct comparison of sample results to demonstrate compliance is 4.08E+06 pCi/m2. Section 5.1 of LTP Chapter 5 states that as part of the FSS of structures, a concrete core sample will be acquired 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 and Sr-90) are analyzed in FSS confirmatory samples. For FSS unit 03202, seventy-six (76) ISOCS measurements were required by the survey design. Consequently, eight (8) concrete core samples were taken during FSS to meet the requirements of LTP section 5.1. To demonstrate compliance with the unrestricted release criteria in FSS unit 03202, 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. [27]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 The Elevated Measurement Comparison (EMC) did not apply to this survey unit. At the 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 Retrospective Power Curve was generated using MARSSIM Power 2000, a software package developed for implementation in support of the decommissioning license termination rule (10CFR20, Subpart E). The result of the MARSSIM Power 2000 program computer run showed adequate power for the survey design (see Attachment 5). For this Class 1 basement structure survey units the Investigation Levels for ISOCS measurement results are those levels specified in LTP Chapter 5, Table 5-25 and are reproduced below in Table 12. Table 12 - Investigation Levels Classification Direct Investigation Levels Class 1 > Operational DCGL Table 13 provides a synopsis of the survey design for survey unit 03202. [28]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Table 13 - Synopsis of Survey Design FEATURE DESIGN CRITERIA BASIS Survey Unit Surface Area 723 m2 LTP Ch.5, Table 5-23

                                                                *  = 0.3

• UBGR = SOF of 1
• LBGR = SOF of 0.5 Number of Measurements 76 (systematic)
• Type I error = 0.05 (N)
• Type II error = 0.05

                                                                * / = 3 (adjusted)

(MARSSIM Table 5-5) Grid Spacing 100% Areal Coverage LTP Chapter 5, Sec. 5.5.2.2 2

• Co 3.28E+07 pCi/m
• Cs-134 - 6.30E+06 pCi/m2 Operational DCGLs for OpDCGLB
• Cs-137 - 8.24E+06 pCi/m2 SFP/Transfer Canal
• Ni 8.41E+08 pCi/m2 (LTP Chapter 5, Table 5-4)
• Sr 2.99E+05 pCi/m2 8 Concrete Core samples selected for HTD ROC Analysis (LTP Chapter 5, section 5.1)

HTD ROC analysis Investigation Level >Operational DCGL (LTP Chapter 5, Table 5-25) Scan Survey Area 723 m2 or ~100% areal coverage (LTP Chapter 5, Table 5-19) Coverage QC 5% Replicate ISOCS Measurements (LTP Chapter 5, section 5.9) [29]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202

6. SURVEY IMPLEMENTATION For survey unit 03202, 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 SFP/Transfer Canal. The concrete core data was used to validate the ratios of gamma emitters to HTD ROC.

A walk down was performed by FSS personnel on 05/30/18. A turnover survey was not required to accept the SFP/Transfer Canal survey unit for FSS as the implementation of the several characterization surveys provided sufficient information pertaining to the radiological condition. These characterization surveys included smears for loose surface contamination, eight (8) concrete core samples and several biased ISOCS measurements in suspect areas. All smear results were less than 1,000 dpm/100 cm2 and all ISOCS measurements indicated an OpSOF of less than one. The results of the concrete core analysis are presented in Tables 2 and 3 of this report. The SFP/Transfer Canal was deemed acceptable for turnover and FSS commenced on 06/01/18. Field Logs (ZS-LT-300-001-001 Attachment 14) were used to document field activities and other information pertaining to the performance of the FSS. Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job. ZionSolutions TSD 14-022 provides the initial justification for the selection of reasonably conservative geometries 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. Various stand-off distances were utilized due to space constraints. The details of those geometries can be found in Attachment 2 of this Release Record. The ISOCS detector was positioned horizontal or vertical to the surface at the center-point of each selected measurement location. To achieve a nominal FOV of 28 m2, the exposed face of the detector was positioned at a distance of 3 meters from the surface with the 90-degree collimation shield installed. The detector to 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. An OpSOF calculation was performed for each measurement by dividing the reported concentration of each ROC by [30]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 the OpDCGL for each ROC to derive an individual ROC fraction. The individual ROC fractions were then summed to provide a total OpSOF value for the measurement. Four (4) replicate measurements were taken with the ISOCS on the SFP/Transfer Canal concrete during FSS. The locations selected for taking replicate measurements were at locations 004, 012, 032 and 048. 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 was applied to the data used for the survey planning, data evaluation and statistical tests for basement surfaces since multiple radionuclide-specific measurements were performed and concentrations inferred based on known relationships.

The application of the unity rule served to normalize the data to allow for an accurate comparison of the various data measurements to the release criteria. When the unity rule was applied, the DCGLw (used for the nonparametric statistical test) becomes one (1). The basement structure BcDCGLB was directly analogous to the DCGLW as defined in MARSSIM. The use and application of the unity rule was performed in accordance with section 4.3.3 of MARSSIM. As 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 1 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) can exceed one without remediation as long as the survey unit passes the Sign Test and, the mean OpSOF for the survey unit does not exceed one. Once the survey data set passes 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 can be used with the BcDCGLs to perform a mean BcSOF calculation. The dose from residual radioactivity assigned to the FSS unit is the mean BcSOF multiplied by 25 mrem/yr. [31]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Direct measurement locations were denoted on the concrete surfaces of the SFP/Transfer Canal by marking an approximate 4 meter by 4 meter grid pattern using a random start point that was overlaid over the exposed surface, providing sufficient overlap between locations to ensure 100% areal coverage. ISOCS measurement locations are shown below in Figure 6 as well as in Attachment 1. Figure 6 - Spent Fuel Pool/Transfer Canal The systematic sample population consisted of seventy-six (76) direct measurements that were acquired using the ISOCS. The concentrations for Ni-63 and Sr-90 are inferred based on the maximum ratios as specified in LTP Chapter 5, Table 5-15 (reproduced as Table 11). The complete ISOCS gamma spectroscopy reports are presented in Attachment 6. Table 14 provides the measured results for each measurement and Table 15 presents the statistical quantities. [32]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Table 14 - Spent Fuel Pool/Transfer Canal 576 foot Elevation - Measured Concentrations of ROC for FSS Co-60 Ni-63 Sr-90 Cs-134 Cs-137 MEASUREMENT ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B1-03202A-FSWC-001-GD 6.24E+04 1.13E+07 1.05E+03 0.00E+00 5.27E+05 0.083 B1-03202A-FSWC-002-GD 4.52E+04 8.16E+06 1.15E+03 1.48E+04 5.75E+05 0.087 B1-03202A-FSWC-003-GD 3.97E+04 7.16E+06 4.00E+03 0.00E+00 2.00E+06 0.266 B1-03202A-FSWC-004-GD 3.02E+04 5.45E+06 2.28E+03 1.24E+04 1.14E+06 0.219 B1-03202A-FSFC-005-GD 3.94E+04 7.11E+06 1.64E+03 3.63E+03 8.18E+05 0.115 B1-03202A-FSFC-006-GD 1.98E+05 3.57E+07 2.80E+04 1.43E+04 1.40E+07 1.843 B1-03202A-FSWC-007-GD 5.35E+04 9.65E+06 3.44E+02 1.22E+04 1.72E+05 0.037 B1-03202A-FSWC-008-GD 7.85E+04 1.42E+07 3.08E+02 1.50E+04 1.54E+05 0.041 B1-03202A-FSWC-009-GD 1.03E+05 1.86E+07 3.76E+03 1.63E+04 1.88E+06 0.269 B1-03202A-FSWC-010-GD 9.69E+04 1.75E+07 5.88E+02 5.78E+02 2.94E+05 0.061 B1-03202A-FSWC-011-GD 1.06E+05 1.91E+07 1.63E+02 0.00E+00 8.15E+04 0.036 B1-03202A-FSWC-012-GD 4.86E+04 8.77E+06 2.12E+02 1.44E+03 1.06E+05 0.026 B1-03202A-FSWC-013-GD 1.19E+05 2.15E+07 9.68E+02 2.48E+04 4.84E+05 0.095 B1-03202A-FSWC-014-GD 1.86E+05 3.36E+07 3.00E+03 2.34E+04 1.50E+06 0.241 B1-03202A-FSFC-015-GD 7.83E+04 1.41E+07 8.06E+03 1.73E+04 4.03E+06 0.538 B1-03202A-FSFC-016-GD 8.23E+04 1.49E+07 1.21E+04 0.00E+00 6.07E+06 0.797 B1-03202A-FSWC-017-GD 2.81E+04 5.07E+06 3.62E+02 0.00E+00 1.81E+05 0.030 B1-03202A-FSWC-018-GD 1.27E+05 2.29E+07 2.70E+02 3.32E+04 1.35E+05 0.054 B1-03202A-FSWC-019-GD 7.33E+04 1.32E+07 9.16E+03 3.45E+04 4.58E+06 0.610 B1-03202A-FSWC-020-GD 1.35E+05 2.44E+07 2.26E+03 1.17E+04 1.13E+06 0.180 B1-03202A-FSFC-021-GD 4.99E+04 9.00E+06 5.42E+02 2.59E+03 2.71E+05 0.047 B1-03202A-FSFC-022-GD 1.38E+05 2.49E+07 2.22E+03 4.40E+03 1.11E+06 0.177 B1-03202A-FSFC-023-GD 1.19E+05 2.15E+07 1.04E+04 1.58E+02 5.19E+06 0.694 B1-03202A-FSFC-024-GD 2.14E+04 3.86E+06 7.14E+01 3.00E+03 3.57E+04 0.010 B1-03202A-FSFC-025-GD 2.28E+04 4.11E+06 1.37E+02 0.00E+00 6.85E+04 0.014 B1-03202A-FSFC-026-GD 7.36E+04 1.33E+07 1.78E+02 4.14E+03 8.91E+04 0.030 B1-03202A-FSFC-027-GD 2.01E+05 3.63E+07 8.48E+03 1.82E+04 4.24E+06 0.595 B1-03202A-FSFC-028-GD 1.33E+05 2.40E+07 1.10E+03 1.77E+04 5.49E+05 0.106 B1-03202A-FSFC-029-GD 1.17E+05 2.11E+07 8.76E+02 1.33E+04 4.38E+05 0.087 B1-03202A-FSFC-030-GD 6.05E+04 1.09E+07 8.36E+02 3.46E+03 4.18E+05 0.069 B1-03202A-FSFC-031-GD 8.18E+04 1.48E+07 8.22E+02 0.00E+00 4.11E+05 0.073 B1-03202A-FSFC-032-GD 1.09E+05 1.97E+07 8.62E+02 7.27E+03 4.31E+05 0.083 B1-03202A-FSFC-033-GD 1.15E+05 2.08E+07 9.54E+02 0.00E+00 4.77E+05 0.089 B1-03202A-FSFC-034-GD 8.34E+04 1.50E+07 1.01E+03 4.74E+04 5.04E+05 0.092 B1-03202A-FSFC-035-GD 6.06E+04 1.09E+07 8.56E+02 0.00E+00 4.28E+05 0.070 [33]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Table 14 - (continued) - Spent Fuel Pool/Transfer Canal 576 foot Elevation - Measured Concentrations of ROC for FSS Co-60 Ni-63 Sr-90 Cs-134 Cs-137 MEASUREMENT ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B1-03202A-FSFC-036-GD 9.68E+04 1.75E+07 1.41E+03 8.28E+03 7.04E+05 0.115 B1-03202A-FSFC-037-GD 1.40E+05 2.53E+07 5.86E+03 1.05E+04 2.93E+06 0.411 B1-03202A-FSFC-038-GD 5.34E+04 9.64E+06 2.44E+02 1.22E+05 1.22E+05 0.048 B1-03202A-FSFC-039-GD 3.15E+05 5.68E+07 2.00E+04 0.00E+00 9.99E+06 1.356 B1-03202A-FSFC-040-GD 1.87E+05 3.37E+07 2.64E+03 2.85E+03 1.32E+06 0.215 B1-03202A-FSFC-041-GD 5.29E+04 9.55E+06 4.04E+02 0.00E+00 2.02E+05 0.039 B1-03202A-FSFC-042-GD 6.09E+04 1.10E+07 1.96E+02 9.82E+04 9.82E+04 0.043 B1-03202A-FSFC-043-GD 6.94E+04 1.25E+07 1.23E+03 4.44E+03 6.17E+05 0.097 B1-03202A-FSFC-044-GD 3.18E+04 5.74E+06 6.88E+01 9.41E+03 3.44E+04 0.014 B1-03202A-FSFC-045-GD 1.83E+04 3.30E+06 3.48E+01 0.00E+00 1.74E+04 0.007 B1-03202A-FSFC-046-GD 3.58E+04 6.46E+06 8.38E+01 1.45E+04 4.19E+04 0.016 B1-03202A-FSFC-047-GD 4.44E+04 8.01E+06 6.54E+01 9.52E+03 3.27E+04 0.017 B1-03202A-FSFC-048-GD 3.36E+04 6.06E+06 7.14E+01 1.17E+04 3.57E+04 0.015 B1-03202A-FSFC-049-GD 4.33E+04 7.81E+06 8.54E+01 4.26E+03 4.27E+04 0.017 B1-03202A-FSFC-050-GD 4.07E+04 7.34E+06 5.90E+02 0.00E+00 2.95E+05 0.048 B1-03202A-FSFC-051-GD 2.09E+04 3.77E+06 2.64E+01 3.33E+03 1.32E+04 0.007 B1-03202A-FSFC-052-GD 1.71E+04 3.09E+06 2.80E+01 3.34E+03 1.40E+04 0.007 B1-03202A-FSFC-053-GD 1.94E+04 3.50E+06 3.48E+01 0.00E+00 1.74E+04 0.007 B1-03202A-FSFC-054-GD 2.01E+04 3.63E+06 3.38E+01 1.07E+03 1.69E+04 0.007 B1-03202A-FSFC-055-GD 9.98E+03 1.80E+06 2.74E+01 5.92E+03 1.37E+04 0.005 B1-03202A-FSFC-056-GD 1.41E+04 2.54E+06 2.96E+01 0.00E+00 1.48E+04 0.005 B1-03202A-FSFC-057-GD 6.41E+03 1.16E+06 1.92E+01 0.00E+00 9.60E+03 0.003 B1-03202A-FSFC-058-GD 1.95E+04 3.52E+06 4.92E+01 1.07E+04 2.46E+04 0.010 B1-03202A-FSFC-059-GD 2.05E+04 3.70E+06 5.92E+01 0.00E+00 2.96E+04 0.009 B1-03202A-FSFC-060-GD 1.10E+04 1.98E+06 5.02E+00 1.01E+04 2.51E+03 0.005 B1-03202A-FSFC-061-GD 1.81E+04 3.27E+06 3.80E+01 1.91E+04 1.90E+04 0.010 B1-03202A-FSFC-062-GD 2.21E+04 3.99E+06 3.22E+01 0.00E+00 1.61E+04 0.007 B1-03202A-FSFC-063-GD 2.33E+04 4.20E+06 4.90E+01 1.14E+04 2.45E+04 0.011 B1-03202A-FSFC-064-GD 3.56E+04 6.42E+06 5.90E+01 1.38E+04 2.95E+04 0.015 B1-03202A-FSFC-065-GD 3.97E+04 7.16E+06 6.36E+01 1.47E+03 3.18E+04 0.014 B1-03202A-FSFC-066-GD 2.32E+04 4.19E+06 1.05E+02 0.00E+00 5.25E+04 0.012 B1-03202A-FSFC-067-GD 1.78E+04 3.21E+06 3.58E+01 8.38E+03 1.79E+04 0.008 B1-03202A-FSFC-068-GD 1.17E+04 2.11E+06 5.36E+01 2.20E+03 2.68E+04 0.007 B1-03202A-FSFC-069-GD 1.63E+04 2.94E+06 5.46E+01 1.68E+04 2.73E+04 0.010 B1-03202A-FSFC-070-GD 1.89E+04 3.41E+06 5.32E+01 3.01E+03 2.66E+04 0.009 [34]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Table 14 - (continued) - Spent Fuel Pool/Transfer Canal 576 foot Elevation - Measured Concentrations of ROC for FSS MEASUREMENT ID Co-60 Ni-63 Sr-90 Cs-134 Cs-137 OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B1-03202A-FSFC-071-GD 2.63E+04 4.75E+06 2.44E+01 1.34E+03 1.22E+04 0.008 B1-03202A-FSFC-072-GD 1.55E+04 2.80E+06 5.44E+01 2.74E+03 2.72E+04 0.008 B1-03202A-FSWC-073-GD 1.20E+04 2.17E+06 7.00E+01 2.05E+04 3.50E+04 0.011 B1-03202A-FSWC-074-GD 2.68E+04 4.84E+06 5.28E+01 0.00E+00 2.64E+04 0.010 B1-03202A-FSWC-075-GD 2.48E+04 4.48E+06 6.34E+01 2.66E+04 3.17E+04 0.014 B1-03202A-FSWC-076-GD 2.09E+04 3.77E+06 2.86E+01 0.00E+00 1.43E+04 0.007 Table 15 - SFP/Transfer Canal Statistical Quantities - Systematic Measurement Population Individual Measurement Metrics Total Number of Systematic Measurements = 76 Number of Quality Control Measurements = 4 Number of Judgmental/Investigational Measurements = 0 Total Number of Measurements = 80 Mean Systematic Measurement OpSOF = 0.139 Max Individual Systematic Measurement OpSOF = 1.843 Number of Systematic Measurements with OpSOF >1 = 2 Table 16 provides summary data for all systematic ISOCS measurements taken within the SFP/Transfer Canal survey unit for FSS when compared to the BcDCGLB. Table 16 - SFP/Transfer Canal Statistical Quantities - Systematic Measurement Population MEAN MEDIAN MAX MIN ST. DEV. BcDCGL Avg SOF Avg Dose ROC per ROC per ROC (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) Co-60 6.39E+04 4.39E+04 3.15E+05 6.41E+03 5.68E+04 1.57E+08 0.000 0.010 Ni-63 1.15E+07 7.91E+06 5.68E+07 1.16E+06 1.02E+07 4.02E+09 0.003 0.072 Sr-90 1.90E+03 2.28E+02 2.80E+04 5.02E+00 4.48E+03 1.43E+06 0.001 0.033 Cs-134 1.07E+04 4.20E+03 1.22E+05 0.00E+00 1.91E+04 3.01E+07 0.000 0.009 Cs-137 9.48E+05 1.14E+05 1.40E+07 2.51E+03 2.24E+06 3.94E+07 0.024 0.602 The mean SOF for the SFP/Transfer Canal basement structural FSS unit based on the mean concentration for each ROC as measured by the systematic sample population [35]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 when compared against the BcDCGLs is 0.029. This value equates to a dose of 0.726 mrem/yr. During the FSS of the SFP/Transfer Canal basement, two (2) measurements were identified where the result exceeded the OpDCGL but was less than the BcDCGL. As previously stated, the OpSOF for a systematic or a judgmental measurement/sample(s) may exceed one without remediation as long as the survey unit passes the Sign Test and, the mean OpSOF for the survey unit does not exceed one. Once the survey data set passes the Sign Test (using OpDCGLs), the mean radionuclide activity (pCi/m2) for each ROC from systematic measurements along with any identified elevated areas from systematic and judgmental samples will be used with the BcDCGLs to perform a BcSOF calculation for each surface FSS unit in a basement in accordance with the following equation. The mean BcSOF for the survey unit will then be adjusted by adding the BcSOF from the elevated areas to the mean to account for the additional dose attributed to the elevated areas. Equation 4

              =                                   +
                            =1                                         x where:

BcSOFB = SOF for structural surface survey unit within a basement using BcDCGLs Mean ConcB ROCi = Mean concentration for the systematic measurements taken during the FSS of structural surface in survey unit for each ROCi BcDCGLB ROCi = BcDCGL for structural surfaces (DCGLB) for each ROCi Elev ConcB ROCi = Concentration for ROCi in any identified elevated area (systematic or judgmental) SAElev = surface area of the elevated area SASU = adjusted surface area of FSS unit for DCGL calculation The adjusted surface area of the SFP/Transfer Canal FSS unit (SASU) is 723 m2. The surface area of each of the elevated areas equates to the FOV of the individual ISOCS measurement. Table 17 presents the elevated concentration and the calculated SOF for each ROC in each of the 2 identified elevated area. The individual elevated SOF for each [36]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 ROC were than summed to provide a total SOF adjustment due to each of the elevated measurements. Table 17 - Elevated Measurement ROC Concentrations and SOFs Elevated Area #1 - B1-03202A-FSFC-006-GD SAElev = 3.14 m2 Elev Conc 1 Co-60 = 1.98E+05 pCi/m2 SOF 1 Co-60 = 0.000 Elev Conc 1 Ni-63 = 3.57E+07 pCi/m2 SOF 1 Ni-63 = 0.000 2 Elev Conc 1 Sr-90 = 2.80E+04 pCi/m SOF 1 Sr-90 = 0.000 Elev Conc 1 Cs-134 = 1.43E+04 pCi/m2 SOF 1 Cs-134 = 0.000 2 Elev Conc 1 Cs-137 = 1.40E+07 pCi/m SOF 1 Cs-137 = 0.001 SOF 1 TOTAL = 0.002 Elevated Area #2 - B1-03202A-FSFC-039-GD SAElev = 7.1 m2 Elev Conc 2 Co-60 = 3.15E+05 pCi/m2 SOF 2 Co-60 = 0.000 Elev Conc 2 Ni-63 = 5.68E+07 pCi/m2 SOF 2 Ni-63 = 0.000 Elev Conc 2 Sr-90 = 2.00E+04 pCi/m2 SOF 2 Sr-90 = 0.000 Elev Conc 2 Cs-134 = 0.00E+00 pCi/m2 SOF 2 Cs-134 = 0.000 Elev Conc 2 Cs-137 = 9.99E+06 pCi/m2 SOF 2 Cs-137 = 0.002 SOF 2 TOTAL = 0.003 The sum of the SOFTOTAL for each of the 2 elevated measurements equals 0.004. This value is then added to the mean SOF for the SFP/Transfer Canal basement structural FSS unit of 0.029 resulting in an adjusted mean SOF for the SFP/Transfer Canal basement of 0.033. This SOF equates to a dose of 0.829 mrem/yr. This value is the dose assigned to the survey unit based on the average of the systematic measurements adjusted for the dose contribution of elevated areas. The implementation of required QC measures included the collection of four (4) additional ISOCS measurements in the SFP/Transfer Canal for replicate measurement analysis. The concentrations for Ni-63 and Sr-90 were inferred based on the maximum ratios as specified in LTP Chapter 5, Table 5-15. The replicate ISOCS measurement results are provided in Table 18. Table 18 - Summary of ISOCS Replicate Measurements for QC MEASUREMENT ID Co-60 Ni-63 Sr-90 Cs-134 Cs-137 SOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B1-03202A-FQWC-004-GD 3.05E+04 5.50E+06 9.64E+02 5.03E+03 4.82E+05 0.070 B1-03202A-FQWC-012-GD 5.24E+04 9.46E+06 1.80E+02 5.37E+03 8.99E+04 0.025 B1-03202A-FQWC-032-GD 1.15E+05 2.08E+07 1.10E+03 1.70E+03 5.45E+05 0.099 B1-03202A-FQWC-048-GD 2.56E+04 4.62E+06 5.58E+01 2.93E+03 2.79E+04 0.010 Eight (8) concrete core samples were acquired at 10% of the locations where an ISOCS measurement was collected with the locations selected at random. Only HTD [37]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 radionuclides included as ROC (Ni-63 and Sr-90) were analyzed in the FSS confirmatory samples. The top 1/2-inch puck from each of the FSS confirmatory concrete core samples, representing the concrete from the exposed surface to a depth of 1/2 inch, was sent to Eberline Laboratory for analysis of the ROC, including Ni-63 and Sr-90. The analysis results indicated no detectable activity for any of the ROC at concentrations greater than MDC. No further action or analysis was performed. The results are presented in Table 19 below. Table 19 - Summary of FSS Concrete Core Analysis by Eberline B1-03202A-FRW-C004-CV ROC Result Uncertainty MDC Co-60 2.24E-02 6.82E-02 1.06E-01 Ni-63 9.96E-01 1.66E+00 2.81E+00 Sr-90 5.60E-01 3.56E-01 5.68E-01 Cs-134 2.16E-02 4.53E-02 1.14E-01 Cs-137 1.12E-01 8.01E-02 1.24E-01 B1-03202A-FRW-C027-CV ROC Result Uncertainty MDC Co-60 9.08E-03 1.12E-01 1.02E-01 Ni-63 -9.14E-02 1.79E+00 3.10E+00 Sr-90 4.07E-01 3.98E-01 6.61E-01 Cs-134 -8.19E-02 1.04E-01 1.55E-01 Cs-137 1.52E-02 1.31E-01 1.89E-01 B1-03202A-FRF-C038-CV Co-60 8.93E-02 2.51E-01 3.11E-01 Ni-63 2.24E+00 1.82E+00 3.03E+00 Sr-90 1.89E-01 4.99E-01 8.71E-01 Cs-134 1.22E-02 1.21E-01 3.95E-01 Cs-137 3.30E-01 2.90E-01 4.66E-01 B1-03202A-FRF-C052-CV Co-60 1.02E-01 1.21E-01 2.39E-01 Ni-63 1.23E+00 1.65E+00 2.79E+00 Sr-90 3.38E-01 3.50E-01 5.84E-01 Cs-134 -3.96E-02 8.70E-02 2.32E-01 Cs-137 1.41E-01 1.57E-01 2.77E-01 [38]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Table 19 (continued) - Summary of FSS Concrete Core Analysis by Eberline B1-03202A-FRF-C057-CV Co-60 1.85E-02 7.77E-02 1.00E-01 Ni-63 7.68E-02 1.51E+00 2.60E+00 Sr-90 2.53E-01 3.33E-01 5.66E-01 Cs-134 -6.51E-03 3.32E-02 1.05E-01 Cs-137 3.90E-03 9.12E-02 1.37E-01 B1-03202A-FRFC-059-CV Co-60 8.80E-02 1.26E-01 1.61E-01 Ni-63 2.33E-01 5.04E-01 8.77E-01 Sr-90 1.44E+00 1.71E+00 2.87E+00 Cs-134 -1.73E-02 5.01E-02 1.44E-01 Cs-137 2.58E-02 1.16E-01 1.89E-01 B1-03202A-FRFC-061-CV Co-60 -4.50E-02 1.59E-01 2.31E-01 Ni-63 1.03E+00 1.71E+00 2.90E+00 Sr-90 4.66E-01 4.02E-01 6.61E-01 Cs-134 1.86E-01 2.19E-01 3.29E-01 Cs-137 1.67E-01 2.10E-01 3.55E-01 B1-03202A-FRFC-072-CV Co-60 4.07E-02 1.56E-01 1.88E-01 Ni-63 1.09E+00 1.56E+00 2.63E+00 Sr-90 6.11E-01 4.28E-01 6.88E-01 Cs-134 1.97E-01 1.69E-01 2.18E-01 Cs-137 -5.55E-03 3.31E-02 3.06E-01

8. QUALITY CONTROL The implementation of required QC measures included the collection of four additional ISOCS measurements in (Survey Unit 03202) 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.

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

[39]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202

10. REMEDIATION AND RESULTS Remediation was required prior to performance of FSS. Following remediation, FSS was conducted successfully and met all acceptance criteria for release of the survey units.

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 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 unit.

12. DATA QUALITY ASSESSMENT (DQA)

The DQO sample design and data were reviewed in accordance with ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment (Reference 11) for completeness and consistency. Documentation was complete and legible. Surveys and the collection of measurements were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 1. The survey design had adequate power as indicated by the Retrospective Power Curve (see Attachment 5). The analytical results of seventy-four (74) of the seventy-six (76) samples were less than a SOF of one. The Sign Test (Attachment 3) was performed on the data and compared to the original assumptions of the DQOs. The survey unit passes the Sign Test, and 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 the values reported below the MDC, and values with uncertainties that exceeded two standard deviations. 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 and a quantile plot. All graphical representations are provided in Attachment 5. [40]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202

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 BcSOF 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 BcSOF to ensure that the total dose from all ROC does not exceed the dose criterion. 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 SFP/Transfer Canal basement is 0.150 mrem/yr, which equates to a SOF of 0.006. Basement surface area adjustments (i.e. increases) were applied to the structure surface DCGL calculation for certain basements to ensure that the DCGLs accounted for the contribution of residual radioactivity from basements/structures that cannot, on their own, support a water supply well but were hydraulically connected to a basement that could support a well. In accordance with LTP section 5.5.6.1, this adjustment must be made to the Containment Building basements and the Auxiliary Building basement due to their hydraulic conductivity with the SFP/Transfer Canal FSS unit. As part of the final compliance equation for both Containments and the Auxiliary Building, the area-weighted mean BcSOFB for the SFP/Transfer Canal will be added to the mean BcSOFB for each Containment and the Auxiliary Building basement on an area-weighted basis in [41]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 accordance with LTP section 5.5.6.1, Equation 5-8. These adjustments are documented in the Release Records applicable to each. The mean adjusted BcSOF for the SFP/Transfer Canal is 0.033. This SOF equates to a dose of 0.829 mrem/yr. The mean adjusted BcSOF for the SFP/Transfer Canal is then used in the following equation to calculate BcSOFBASEMENT for the SFP/Transfer Canal. Equation 5

              =  +  +  +

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 SFP/Transfer Canal basement. All were physically removed and disposed of during the demolition process. Consequently, the dose contribution from both (variables BcSOFEP and BcSOFPN) are zero. The BcSOFBASEMENT value for the SFP/Transfer Canal is then derived as follows; Equation 6

              = 0.033 + 0.000 + 0.000 + 0.006 = 0.039 The BcSOFBASEMENT for the SFP/Transfer Canal basement is 0.039. This SOF equates to a dose of 0.979 mrem/yr TEDE to the AMCG from residual radioactivity in the SFP/Transfer Canal basement.

[42]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202

15. CONCLUSION Survey unit 03202 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 in accordance with the LTP Section 5.10, the survey units 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 03202, SFP/Transfer Canal Basement is 0.829 mrem/yr TEDE, based on the average concentration of the ROC in samples used for non-parametric statistical sampling as well as the dose from elevated measurements on an area-weighted basis. The dose from embedded pipe and penetrations in the SFP/Transfer Canal is zero and the dose from clean fill is 0.150 mrem/yr. The total dose attributed to the SFP/Transfer Canal as a summation of all dose components is 0.979 mrem/yr TEDE (BcSOFBASEMENT = 0.339). Survey unit 03202, SFP/Transfer Canal Basement 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

6. Zion Station Historical Site Assessment

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

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

[43]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202

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

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

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

[44]

ATTACHMENT 1 FIGURES AND MAPS [45]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL SURVEY UNIT 03202 Figure 1 - Overview of Structural Survey Unit [46]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL SURVEY UNIT 03202 [47]

ATTACHMENT 2 ISOCS GEOMETRY [48]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 General In order to perform ISOCS measurements for Final Status Surveys geometries are created as part of the efficiency calibration. TSD 14-022 Use of In-Situ Gamma Spectroscopy for Source Term Survey of End State Structures provides the approach used to derive the specific geometries to be used for FSS including geometries to be used for specific survey units. At the time that TSD 14-022 was developed access to all areas requiring FSS using ISOCS was not available. Additionally, remediation of some areas was required and continuing characterization of the remediated areas was necessary in order to determine the profile of any remaining residual radioactivity at the time that final status surveys are conducted. In the case of the SFP/Transfer Canal survey unit additional remediation and subsequent core sampling was required to quantify the remaining residual radioactivity components (including both gamma-emitting and HTD) associated with the survey unit. The core sampling also defined the depth of contamination associated with the survey unit and augments the information required for developing the geometry and subsequent efficiency for the ISOCS measurements. Discussion For the SFP/Transfer Canal, the associated survey unit is 03202. TSD 14-022, states, a methodology similar to that described for the Auxiliary Building Floor can be used to determine the parameters of a CP or ECP geometry template (for the SFP/Transfer Canal). Following remediation of the SFP/Transfer Canal concrete core samples were acquired, cut into 0.5 inch pucks and analyzed using the on-site gamma spectroscopy systems. Samples exhibiting positive radionuclide results and in accordance with Zion procedures and the SFP/Transfer Canal FSS sample plan were sent to an off-site vendor laboratory to obtain results for HTD radionuclides. Examination of the cores acquired from the remediated surfaces indicated that the residual radionuclides remaining did not extend much below the first 0.5 inches of concrete. Based on the core results a Circular Plane (CP) Geometry was selected. Because the core data below the first 1/2 inch of concrete was at or near the on-site gamma spectroscopy analysis MDC level (given the analysis time and geometry parameters), the contamination depth for the ISOCS measurements was set to 2.0 inches (5.08 cm). This depth was further quantified by performing a curve fitting action on the suspect cores results. From the core activity at depth data a spreadsheet was created. A chart was produced from the core results and the least squared fitted information from the core activity plotted over depth was noted at the cumulative 90th percentile value to identify the depth of contamination. The spreadsheets and chart are provided in this Attachment. Review of the core data results and subsequent evaluation showed that 95% of the residual radioactivity was in the top 1.5 inches of the concrete (3.8 cm). The result of the examination was used to conservatively populate the Relative Concentration of the CP geometry for the SFP/Transfer Canal over four 0.5 inch layers (of concrete) for a contamination depth of 2.0 inches. [49]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 ISOCS Measurement for Uneven Surfaces Remediation of the SFP/Transfer Canal resulted in uneven concrete surfaces over some regions of the pad. TSD 17-003 Evaluation of Efficiency Calibration Geometries for In-Situ Gamma Spectroscopy during Final Status Surveys examined conditions where a non-uniform surface exists in the ISOCS detectors field of view. It was expected that for discontinuities in the concrete that are less than or equal to 12.0 (30.48 cm) inches deep will result in an 8.0 to 9.0 percent difference in efficiency (see Table 3 of TSD 17-003) over a 28.3 m2 FOV. This was derived by comparing two efficiencies using the same FOV but varying the detector to source distance by one foot (30.48 cm) to account for the discontinuities. That is, for regions of indentations, holes or dips in the concrete reducing the 3.0 meter source to detector distance by 30.48 cm (to 2.695 meters) and using the 3.0 meter geometry will result in an 8% to 9% conservative change in efficiency. This was demonstrated for a 2.54 cm contamination thickness CP model. This Attachment contains the ISOCS geometry parameters and efficiencies used for the SFP/Transfer Canal and the geometry where the 3.0 meter source to detector distance is reduced by 30.48 cm but the FOV is maintained. Table 1.0 presents the efficiency results for a 5.08 cm concrete thickness. Table 1.0 - Spent Fuel Pool Pad Efficiency Comparison for 5.08 cm thickness Efficiency Efficiency Ratio Energy 3.0 meters 2.695 meters(3.0-30.5cm) 2.695 m/3.0 m 661.62 3.185E-06 3.43E-06 1.08 1173.2 2.422E-06 2.62E-06 1.08 1332.5 2.283E-06 2.47E-06 1.08 Table 1.0 shows that by placing the detector 30.5 cm closer to the source while maintaining the same FOV will result in the ISOCS measurement being conservative by 8.0 percent. This is essentially the same results as noted in Table 3 of TSD 17-003. The use of a 5.08 cm contamination thickness did not significantly affect the earlier results where a 2.54 cm thickness was used. Spent Fuel Pool/Transfer Canal Pad Geometries For SFP/Transfer Canal ISOCS measurements four variations of the current geometry were used. The geometries variation is the source to detector distance of 1.0, 1.5, 2.0 and 3.0 meters. This Attachment also presents the Geometry Composer parameters and efficiency associated with each of the geometries. The geometries files used for the Genie2000 Spectrum Analysis Software are named as followed: [50]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202

• 3M90D_SFP_2IN
• 2M90D_SFP_2IN
• 1.5M90D_SFP_2IN
• 1.0M90D_SFP_2IN Among some of the ISOCS units the above geometry file nomenclature may change slightly but is readily identified by the SFP term.

[51]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 SFP/Transfer/Canal Pad Cores and Cumulative Percent [52]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 SFP/Transfer/Canal Pad Cores and Cumulative Percent [53]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [54]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [55]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [56]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [57]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [58]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [59]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [60]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [61]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [62]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [63]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [64]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [65]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 [66]

ATTACHMENT 3 SIGN TEST [67]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Sign Test - Unit 1 Containment Basement Above 565 foot Elevation Survey Area 03000 Survey Area Spent Fuel Pool/Transfer Canal Survey Unit 03202 Survey Unit Bottom of SFP Classification 1 Type I Error 0.05 Number of Measurements 76 SOF SOF

   #                     1-Ws        Sign          #                   1-Ws        Sign (Ws)                                          (Ws) 1          0.083       0.92        +1          39        1.356      (0.36)       -1 2          0.087       0.91        +1          40        0.215       0.78        +1 3          0.266       0.73        +1          41        0.039       0.96        +1 4          0.219       0.78        +1          42        0.043       0.96        +1 5          0.115       0.89        +1          43        0.097       0.90        +1 6          1.843      (0.84)        -1         44        0.014       0.99        +1 7          0.037       0.96        +1          45        0.007       0.99        +1 8          0.041       0.96        +1          46        0.016       0.98        +1 9          0.269       0.73        +1          47        0.017       0.98        +1 10          0.061       0.94        +1          48        0.015       0.99        +1 11          0.036       0.96        +1          49        0.017       0.98        +1 12          0.026       0.97        +1          50        0.048       0.95        +1 13          0.095       0.90        +1          51        0.007       0.99        +1 14          0.241       0.76        +1          52        0.007       0.99        +1 15          0.538       0.46        +1          53        0.007       0.99        +1 16          0.797       0.20        +1          54        0.007       0.99        +1 17          0.030       0.97        +1          55        0.005       0.99        +1 18          0.054       0.95        +1          56        0.005       0.99        +1 19          0.610       0.39        +1          57        0.003       1.00        +1 20          0.180       0.82        +1          58        0.010       0.99        +1 21          0.047       0.95        +1          59        0.009       0.99        +1 22          0.177       0.82        +1          60        0.005       1.00        +1 23          0.694       0.31        +1          61        0.010       0.99        +1 24          0.010       0.99        +1          62        0.007       0.99        +1 25          0.014       0.99        +1          63        0.011       0.99        +1 26          0.030       0.97        +1          64        0.015       0.99        +1 27          0.595       0.40        +1          65        0.014       0.99        +1 28          0.106       0.89        +1          66        0.012       0.99        +1 29          0.087       0.91        +1          67        0.008       0.99        +1 30          0.069       0.93        +1          68        0.007       0.99        +1 31          0.073       0.93        +1          69        0.010       0.99        +1 32          0.083       0.92        +1          70        0.009       0.99        +1 33          0.089       0.91        +1          71        0.008       0.99        +1

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FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Sign Test - Unit 1 Containment Basement Above 565 foot Elevation (continued) SOF SOF

   #                    1-Ws      Sign            #                    1-Ws       Sign (Ws)                                           (Ws) 34        0.092        0.91      +1           72        0.008        0.99        +1 35        0.070        0.93      +1           73        0.011        0.99        +1 36        0.115        0.88      +1           74        0.010        0.99        +1 37        0.411        0.59      +1           75        0.014        0.99        +1 38        0.048        0.95      +1           76        0.007        0.99        +1 Number of positive differences (S+)     74 Critical Value     45 The Survey Unit   MEETS          the Acceptance Criteria

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ATTACHMENT 4 QC MEASUREMENT ASSESSMENTS [70]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Replicate Measurement Assessment Survey Unit # 03000 Survey Unit Name Spent Fuel Pool/Transfer Canal Sample Plan # B1-03202A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement locations 04, 12, 32 and 48. The standard measurement are IDs B1-03202AF-SWC-004-GD, B1-03202F-SWC-012-GD, B1-03202AF-SFC-032-GD and B1-03202AF-SFC-048-GD. The comparison measurements are IDs B1-03202AF-QWC-004-GD, B1-03202AF-QWC-012-GD, B1-03202AF-QFC-032-GD and B1-03202AF-QFC-048-GD. STANDARD COMPARISON Radionuclide Activity Standar Resolution Agreement Activity Standard Comparison Acceptable Value d Error Range Value Error Ratio (Y/N) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B1-03202AF-SWC-004-GD B1-03202AF-QWC-004-GD 2.06E+0 Cs-137 1.63E+06 8 0.6-1.66 1.06E+05 1.38E+05 1.5 Y 5 B1-03202AF-SWC-012-GD B1-03202AF-QWC-012-GD 2.17E+0 Cs-137 1.06E+06 5 0.5-2.0 8.99E+04 2.03E+04 1.2 Y 4 B1-03202AF-SFC-032-GD B1-03202AF-QFC-032-GD 6.27E+0 Cs-137 4.31E+05 7 0.5-2.0 5.49E+05 7.63E+04 0.8 Y 4 B1-03202AF-SFC-048-GD B1-03202AF-QFC-048-GD 1.31E+0 Cs-137 3.57E+04 3 0.5-2.0 2.79E+04 1.26E+04 1.3 Y 4 Comments/Corrective Actions: There was acceptable The acceptance criterion for replicate static agreement between the standard measurement and the measurements is as per the following Table. replicate measurement. Based on the professional judgment of the Radiological Engineer, the same conclusion was reached for each measurement. No further action is necessary. [71]

ATTACHMENT 5 GRAPHICAL PRESENTATIONS [72]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Quantile Plot for Co-60 Survey Unit: 03202

Description:

Spent Fuel Pool/Transfer Canal Mean: 6.38E+04pCi/m2 Quantile Plot For Co-60 3.50E+05 3.00E+05 Concentration (pCi/g) 2.50E+05 2.00E+05 1.50E+05 1.00E+05 5.00E+04 0.00E+00 0% 10% 20% 30% 40% 50% 60% 70% 80% 90% 100% Percentage [73]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Quantile Plot for Cs-137 Survey Unit: 03202

Description:

Spent Fuel Pool/Transfer Canal Mean: 9.42E+05 pCi/m2 Quantile Plot For Cs-137 1.60E+07 1.40E+07 1.20E+07 Concentration (pCi/g) 1.00E+07 8.00E+06 6.00E+06 4.00E+06 2.00E+06 0.00E+00 0% 20% 40% 60% 80% 100% Percentage [74]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Histogram for Co-60 Survey Unit: 03202

Description:

Spent Fuel Pool/Transfer Canal Mean: 6.38E+04 pCi/m2 Median: 4.39E+04 pCi/m2 ST Dev.: 5.68E+04 Skew: 1.81887451 Frequency Plot For Co-60 50 45 40 35 Frequency 30 25 20 15 10 5 0 5.78E+04 1.09E+05 1.61E+05 2.12E+05 2.64E+05 3.15E+05 Upper End Value (pCi/m2) Upper Value Observation Observation % Frequency 5.78E+04 45 59% 1.09E+05 17 22% 1.61E+05 9 12% 2.12E+05 4 5% 2.64E+05 0 0% 3.15E+05 1 1% TOTAL 76 Histogram for Cs-137 [75]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Survey Unit: 03202

Description:

Spent Fuel Pool/Transfer Canal Mean: 9.42E+05 pCi/m2 Median: 1.14E+05pCi/m2 ST Dev.: 2.24E+06 Skew: 3.39244928 Frequency Plot Cs-137 70 60 50 Frequency 40 30 20 10 0 Upper End Value (pCi/m2) Observation Upper Value Observation % Frequency 1.40E+06 65 86% 2.80E+06 3 4% 4.20E+06 2 3% 5.60E+06 3 4% 7.00E+06 1 1% 8.40E+06 0 0% 9.80E+06 0 0% 1.12E+07 1 1% 1.26E+07 0 0% 1.40E+07 1 1% TOTAL 76 [76]

FSS RELEASE RECORD SPENT FUEL POOL/TRANSFER CANAL BASEMENT SURVEY UNIT 03202 Retrospective Power Curve for Survey Unit 03202 [77]

ATTACHMENT 6 ISOCS ANALYTICAL REPORTS [78]

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

Filenarue: 5456-A Report Generated On 6/1/2018 1 :12 :14 PM Sample Title B103202AFSWC001GD Sample Description SFP/TRANSFER CANAL Sample Identification 001 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/1/2018 1: 01: 00 PM Acquisition Started 6/1/2018 1:02:12 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 5/30/2018 Efficiency ID 1M90DSFP 2IN [79]

Peak Analysis Report 6/1/2018 1 :12: 14 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSWC001GD Peak Analysis Performed on: 6/1/2018 1:12:13 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 1 126- 135 129.99 32.50 0 .86 1. 48E+002 37.04 7.29E+001 2 286- 309 301.36 75.34 0 .71 5.98E+002 139.34 1 .06E+003 3 336- 346 340.74 85.18 1 .22 7.69E+001 78.26 6.04E+002 4 1402- 1415 1408.74 352.18 0.92 6.81E+001 31.70 6.49E+001 5 2431- 2445 2437.67 609.42 1.47 6.78E+001 19.41 9.20E+OOO 6 2636- 2658 2646.18 661. 54 1. 33 9.09E+002 64.36 3.33E+001 7 4474- 4489 448 1 .52 1120 .38 0.83 3.38E+001 16.17 1.02E+001 8 4684- 4703 4693.73 1173.43 1.15 8.61E+001 23. 06 1 .29E+001 9 5321- 5339 5330.16 1332.54 1. 58 9.90E+001 19.90 O.OOE+OOO 10 5834- 5854 5844.16 1461.04 0. 94 1.29E+002 23.53 2.51E+OOO 11 7054- 7069 706 1.47 1765.37 0. 75 1.63E+001 10.59 3.75E+OOO 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 [80]

Interference Corrected Activity Report 6/1/2018 1 :12: 14 PM Page 3

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

Sample

Title:

B103202AFSWC001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

                         "'             IDENTIFIED NUCLIDES          ~ * "" r * * * * 'I> e * 'I> * * ... * * "'

• II Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1 .000 1460.82* 10.66 8.81982E+005 1.77611E+005 Co-60 1.000 1173.23* 99.85 5.58943E+004 1.56185E+004 1332.49* 99.98 6.82779E+004 1 .47714E+004 Cs-137 1. 000 661.66* 85 .10 5.27572E+005 7.355SSE+004 Eu-155 0.346 86.55* 30.70 6.02685E+004 6.25147E+004 105.31 21.10 Bi-214 1.000 609.32* 45.49 7.08224E+004 2.19856E+004 1 120.29* 14.92 1 .43506E+005 6.96859E+004 17 64.49* 15.30 8.65217E+004 5.68134E+004 Pb-214 0.439 295.22 18.42 351.93* 35.60 6.95362E+004 3.42166E+004

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

[81]

Interference Corrected Activity Report 6/1/2018 1:12:14 PM Page 4

• • • • • I N T E R F E R E N C E C O R R E C T E D 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 8.819823E+005 1. 776115E+005 Co-60 1. 000 6.243102E+004 l. 073193E+004 Cs-137 1. 000 5.275720E+005 7.355551E+004 Eu-155 0.346 6.026851E+004 6.251466E+004 Bi-214 1. 000 7.849537E+004 l. 967012E+004 Pb-214 0.439 6.953616E+004 3.421664E+004

       ? ~ Nuclide is part of an undetermined so lution X = Nuclide rejected by the interference analysis
      @ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at   2. 000 sigma

[82]

Interference Corrected Activity Report 6/1/2018 1: 12 : 14 PM Page 5

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

Peak Locate Performed on: 6/1/2018 1:12:13 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.50 2.4679E-001 25.02 2 75.34 9.9690E-001 23.30 M = First peak in a multiplet region m ~ Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [83]

Nuclide MDA Report 6/1/2018 1: 12: 14 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC001GD 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  8.525E+004    8.53E+004    8.820E+005   3.341E+004
 +      Co-60      1173.23*    99.85   l .636E+004   1. 87E+003   5.589E+004   7.303E+003 1332.49*    99.98   l .866E+003                6.828E+004   O.OOOE+OOO Nb-94       702.65     99.81   1 .829E+004   l.83E+004    l.278E+004   8.457E+003 871.09     99.89   l .866E+004                5.067E+003   8.572E+003 Ag-108m     433.90     90.50   2.782E+004    2. 1 3E+004 -1.575E+004   1 .331E+004 614.30     89.80   3.068E+004                 3.480E+003   l .462E+004 722.90     90.80   2.128E+004                 l.691E+004   9.871E+003 Cs-134      604.72     97.62   2.801E+004    2.36E+004   -4.850E+003   l.335E+004 795.86     85.46   2.364E+004                -1.200E+004   l.097E+004
 +      Cs-137      661.66*    85. 10  2.309E+004    2.31E+004    5.276E+005   l.076E+004 Eu-152      121 .78    28.67   l .435E+OOS   7.39E+004    1.074E+OOS   7.060E+004 344.28     26.60   1 .026E+OOS               -3.943E+004   4.948E+004 1408 . 01   21.07   7.389E+004                 2.249E+004   3.238E+004 Eu-154      123.07     40. 40  1 .010E+005   4.66E+004    3.373E+004   4 .968E+004 723.30     20.06   9.633E+004                 8.98SE+004   4 .469E+004 1274.43     34.80   4.658E+004                 4.071E+004   2.067E+004
 +      Eu-155       86 . 55*  30.70   l .005E+OOS   1.00E+OOS    6.027E+004   4.917E+004 105 .31    21.10   2.044E+OOS                -4.229E+004   1.007E+005 Tl-208      583.19     85.00   2.746E+004    2.75E+004    8.186E+002   l.299E+004 Bi-212      727.33      6.67   2.856E+005    2.86E+005    l .636E+005  l.323E+005 Pb-212      238.63     43.60   8.064E+004    8.06E+004    4.981E+004   3.939E+004
 +      Bi-214      609.32*    45.49   2.046E+004    2.05E+004    7.082E+004   8.819E+003 1120.29*    14.92   9.012E+004                 1.435E+005   3.931E+004 1764.49*    15.30   7.456E+004                 8.652E+004   3.008E+004
 +      Pb-214      295.22     18.42   l.675E+005    4 .82E+004   l.183E+005   8.132E+004 351.93*    35.60   4.820E+004                 6.954E+004   2.272E+004 Ra-226      186.21      3.64   1.044E+006    l. 04E+006  -5.248E+OOS   5.119E+005 Ac-228      338.32     11.27   2.429E+005    8.29E+004   -1. 571E+005  l .172E+OOS 911.20     25.80   8.289E+004                 4.123E+004   3.843E+004 968.97     15.80   1.452E+005                 3.402E+004   6.754E+004 Am-241       59.54     35.90   l.235E+005    l.24E+005   -5.873E+004   6.069E+004
       + - Nuclide identified during the nuclide identification
       * = Energy line found in the spectrum
       >=Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @ = Half-life too short to be able to perform the decay correction

[84]

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

Filename: S4S6-A Report Generated On 6/1/2018 1: 30: 36 PM Sample Title B103202AFSWC002GD Sample Description SFP/TRANSFER CANAL Sample Identification 002 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) BS - 8192 Peak Area Range (in channels) BS - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO M"2 Sample Taken On 6/1/2018 1 :20:00 PM Acquisition Started 6/1/2018 1 : 20: 34 PM Live Time 600. 0 seconds Real Time 600.S seconds Dead Time 0 .. 09 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On S/30/2018 Efficiency ID 1M90DSFP 2IN [85]

Peak Analysis Report 6/1/2018 1 : 3 0: 36 PM Page 2

• • • • • P E A K A N A L Y S I S REPORT Detector Name: 5456-A Sample

Title:

B103202AFSWC002GD Peak Analysis Performed on: 6/1/2018 1 :30:35 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 126- 139 130 .01 32.50 1. 04 1.65E+002 40. 32 7.42E+001 2 284- 308 301.48 75.37 0:96 5.98E+002 133.92 9.43E+002 3 332- 345 340.72 85.18 1. 14 1.53E+002 84.69 5.94E+002 4 1403- 1415 1408.46 352.12 0.63 5.83E+001 31.76 7.27E+001 5 2428- 2444 2437.06 609.27 1. 04 7.88E+001 24.60 2.32E+001 6 2636- 2656 2646.23 661.56 1. 34 9.91E+002 66.66 3.35E+001 7 3870- 3883 3876.27 969.07 0.60 2.16E+001 12.17 5.43E+OOO 8 4473- 4486 4479.95 1119.99 1. 89 3.40E+001 14.60 7.00E+OOO 9 4685- 4700 4692.30 1173.08 0.62 6.02E+001 16.93 3.84E+OOO 10 5321- 5340 5330.95 1332.74 1. 21 8.03E+001 20. 28 6.71E+OOO 11 5834- 5855 5844.28 1461.07 1. 75 1 .63E+002 27. 07 5.50E+OOO 12 7053- 7068 7060.44 1765.11 0.50 2.lOE+OOl 9.17 O.OOE+OOO 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 [86]

Interference Corrected Activity Report 6/1/20 18 1 : 3 0: 36 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:

B103202AFSWC002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB I ****** *

• fl I *** 1 * * * *
• IDENTIFIED NUCLIDES * * *'"' * * * ****** I I *
• II.

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 l.10686E+006 2.07947E+005 Co-60 1 .000 1173.23* 99.85 3.90368E+004 1.14240E+004 1332.49* 99.98 5.53809E+004 l.46751E+004 Cs-137 1 .000 661.66* 85.10 5.75097E+005 7.91683E+004 Eu-155 0.346 86.55* 30.70 1. 19875E+005 7.05784E+004 105.31 21.10 Bi-214 1.000 609.32* 45.49 8.23293E+004 2.75346E+004 1120.29* 14. 92 l.44496E+005 6.30979E+004 1764.49* 15.30 l.11803E+005 4.96098E+004 Pb-214 0.439 295.22 18.42 351.93* 35.60 5.94658E+004 3.37841E+004

       *~Energy line found in the spectrum.
       @  -  Energy line not used for Weighted Mean Activity Energy Tolerance :                 10.000 keV Nuclide confidence inde1~ threshold =                   o. 3 o Errors quoted at 2.000 sigma

[87]

Interference Corrected Activity Report 6/1/2018 1: 3 0: 36 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 1.106863E+006 2.079465E+005 Co-60 1. 000 4.520404E+004 9.014563E+003 Cs-137 1. 000 5.750971E+OOS 7.916833E+004 Eu-155 0 .346 1.198753E+005 7.057839E+004 Bi-214 1. 000 9.628856E+004 2.249331E+004 Pb-214 0 .439 5.946581E+004 3.378407E+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

[88]

Interference Corrected Activity Report 6/1/2018 1: 3 0: 36 PM Page 5

  **********      U N I D E N T I F I E D     P E AK S      *** * ***** 'J;*

Peak Locate Performed on: 6/1/2018 1 : 3 0 : 35 PM Peak Locate From Chdrmel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32. 50 2.7459E-001 2 4 .47 2 75.37 9.9732E-001 22. 38 7 969.07 3.5957E-002 56.43 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [89]

Nuclide MDA Report 6/1/2018 1: 3 0: 36 PM Page 6

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Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWCD02GD Nuclide Library Used: C: \GENIE2I~\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  l.205E+005    1.20E+OOS     1 .107E+OD6   5.101E+D04
 +      Co-60      1173.23*     99.85   9.006E+003    9.01E+D03     3.904E+004    3.625E+OD3 1332.49*     99.98   1.26SE+004                  5.538E+004    5.389E+003 Nb-94       702.65      99.81   2.047E+004    2.05E+OD4    -2.602E+003    9.547E+003 871.09      99.89   2.073E+004                  7.164E+003    9.606E+003 Ag-108m     433.90      90.50   2.992E+004    2.09E+004    -2.957E+004    1.436E+004 614.30      89.80   3.459E+004                  9.705E+D03    1.658E+004 722.90      90.80   2.092E+004                  5.670E+002    9.693E+OD3 Cs-134      604.72      97.62   2.867E+004    2.26E+OD4    -9.094E+002    1.368E+004 795.86      85.46   2.263E+004                  l.480E+OD4    l.046E+004
 +      Cs-137      661.66*     85. 10  2.252E+004    2.25E+004     5.751E+OOS    1.047E+D04 Eu-152      121. 78     28.67   l .356E+005   7.39E+004     3.028E+003    6.667E+004 344.28      26.60   9.979E+004                 -1. 02DE+005   4.807E+004 1408.01      21. 07  7.389E+004                  5.738E+004    3.238E+004 Eu-154      123.07      40.40   9.499E+004    S. 04E+004   -3.909E+004    4.669E+004 723.30      20.06   9.472E+D04                  l.415E+D04    4.388E+004 1274.43      34.80   5.035E+004                  4.343E+003    2.255E+OD4
 +      Eu-155       86 . 5 5*  30.70   l .066E+OOS   1 .07E+OOS    1. 199E+OOS   5.222E+004 105.31      21.10   1. 901E+005                -9.641E+004    9.353E+004 Tl-208      583.19      BS.DO   3.008E+D04    3.01E+004     1.303E+004    l.430E+OD4 Bi-212      727.33       6.67   2.928E+005    2.93E+005     l.338E+004    1.359E+OD5 Pb-212      238.63      43.60   7.705E+004    7.71E+D04     6.337E+004    3.760E+004
 +      Bi-214      609.32*     45.49   3.208E+004    1 .44E+004    8.233E+004    l .463E+D04 1120.29*     14. 92  7.285E+004                  l.44SE+OOS    3.068E+OD4 1764.49*     15.30   1.441E+004                  1.118E+OOS    O.OOOE+OOO
 +      Pb-214      295.22      18.42   1. 537E+OOS   4.95E+004    -4.728E+004    7.439E+004 351.93*     35.60   4.952E+004                  S.947E+004    2.338E+004 Ra-226      186.21       3.64   1.005E+006    1 .00E+006    1. 072E+OOS   4.926E+005 Ac-228      338.32      11. 27  2.373E+OOS    9.82E+004    -1 .037E+005   l.144E+005 911.20      25.80   9.815E+004                  3.708E+OD3    4.606E+004 968.97      15. 80  1.464E+OOS                  l. 499E+004   6.810E+D04 Am-241       59 .5 4    35.90   l.108E+005    1 . l lE+OOS -3.518E+004    5.431E+004
       +=Nuclide identified during the nuclide i dentification
       *=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

[90]

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

Filename: 5456-A Report Generated On 6/1/2018 1:55:36 PM Sample Title B103202AFSWC003GD Sample Description SFP/TRANSFER CANAL Sample Identification 003 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO M"2 Sample Taken On 6/1/2018 2: 45:00 PM Acquisition Started 6/1/2018 1 :45:34 PM Live Time 600 . 0 seconds Real Time 600.9 seconds Dead Time 0 . 15 % Energy Calibration used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [91]

Peak Analysis Report 6/1/2018 1 :55:36 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B10 3202AFSWC003GD Peak Analysis Performed on: 6/1/2018 1 : 55:36 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 126 - 154 129.84 32. 46 1. 01 5.66E+002 95.47 3.07E+002 2 282 - 311 301.36 75.34 1. 06 l.12E+003 192.15 l .71E+003 3 334 - 345 340.50 85.13 0 .63 1.73E+002 96.30 8.52E+002 4 950- 961 954.98 238.75 0 .63 5.38E+001 51.89 2.47E+002 5 1401- 1415 1408.08 352.02 1. 12 6.63E+001 44.07 1. 44E+O 02 6 2243- 2255 2248.64 562. 16 0 .56 2.25E+001 19.29 2.65E+001 7 2429- 2446 2437.65 609.41 1. 63 8.72E+001 28.97 3.78E+001 8 2634- 2659 2646.32 661.58 1. 44 3.46E+003 12 0. 08 3.46E+001 9 3638- 3651 3644.51 911.13 1 .38 2.24E+001 13.58 8.62E+OOO 10 4685- 4702 4692.94 1173.24 2.04 4.95E+001 18.12 9.48E+OOO 11 5322- 5341 5330.53 1332.63 1. 51 7.09E+001 18.34 4.15E+OOO 12 5833- 5855 5843.90 1460.97 1.49 1.53E+002 25. 66 2.92E+OOO 13 7052- 7067 7059.23 1764.81 1.17 3.50E+001 11.83 O.OOE+OOO M :; First peak in a mu ltiplet region m -= Other peak in a mu ltiplet region F .,,, Fitted singlet Errors quoted at 2. 000 sigma [92]

Interference Corrected Activity Report 6/1/2018 1 : 55: 36 PM Page 3

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Sample

Title:

B103202AFSWC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

  " * * * * * * * * * * * .. *"'*

• I *
• IDENTIFIED NUCLIDES * ** * .._ * * * * * * * * * * * * * *
• I Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 14 60.82* 10 .66 1.0426SE+006 1.96827E+OOS Co-60 1.000 11 73.23* 99.85 3.21343E+004 1.20394E+004 1332.49* 99.98 4.88670E+004 1.32396E+004 Cs-137 1.000 661.66* 85.10 2.00970E+006 2.51217E+005 Eu-155 0.346 86.55* 30.70 1 .35476E+005 8.02213E+004 1 05.31 21.10 Pb-212 1.000 238.63* 43.60 3.69930E+004 3.61686E+004 Bi-214 0.705 609.32* 45.49 9.11076E+004 3.21837E+004 1120.29 14.92 1764.49* 15.30 l.86320E+OOS 6.47315E+004 Pb-214 0 .439 295.22 18.42 351.93* 35.60 6.76254E+004 4.62577E+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

[93]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1. 000 1.042646E+006 1.968273E+005 Co-60 1. 000 3.970798E+004 8.907294E+003 Cs-137 1.000 2.009702E+006 2.512175E+OOS Eu-155 0.346 1. 354763E+005 8.022130E+004 Pb-212 1.00 0 3.699295E+004 3.616859E+004 Bi-214 0.705 1. 099788E+OOS 2.881832E+004 Pb-214 0.439 6.762539E+004 4.625767E+004

       ?    Nuclide is part of an undetermined so lution X = Nuclide rejected by the interference analysis
      @ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at    2. 000 sigma

[94]

rnterference Corrected Activity Report 6/1/2018 1:55:36 PM Page 5

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

Peak Locate Performed on: 6/1/2018 1:55:36 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.46 9.4328E-001 16.87 2 75.34 1 .8724E+OOO 17.10 6 562.16 3.7560E-002 85.60 9 911.13 3.7298E-002 60.66 Tol. Ac-228 M = First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted a t 2.000 sigma [95]

Nuclide MDA Report 6/1/2018 1: 55: 36 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC003GD 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   9.448E+004    9.4SE+004    1 .043E+006  3.802E+004
 +      Co-60      1173.23*   99.85   1.395E+004    1 .01E+004   3.213E+004   6.096E+003 1332.49*   99.98   1.012E+004                 4.887E+OD4   4.128E+003 Nb- 94      702.65    99.81   1.744E+004    1.61E+004   -6.695E+OD2   8.032E+003 871.09    99.89   1.608E+004                -3.467E+OD3   7.278E+003 Ag-108rn    433.90    90.50   4.352E+004    2.2BE+D04   -1.902E+OD4   2.116E+004 614.30    89.80   3.514E+004                -3.015E+004   1. 685E+004 722.90    90.80   2.280E+004                 1.788E+004   1.063E+004 Cs-134      604.72    97.62   3.424E+004    2 .14E+D04  -1.769E+OD4   1.647E+004 795.86    85.46   2.136E+004                -1.140E+OD4   9.829E+003
 +      Cs-137      661.66*   85.10   2.445E+004    2.45E+D04    2.010E+006   1.144E+004 Eu-152      121. 78   28.67   1.754E+005    8.92E+004   -1.435E+005   8.657E+004 344.28    26.60   1.325E+005                -6. 811E+004  6.440E+004 1408 .01   21. 07  8.921E+004                 6.261E+004   4.004E+004 Eu-154      123.07    40.40   1.246E+005    5.21E+004    8.381E+004   6.151E+004 723.30    20.06   1.025E+005                 4.539E+004   4.778E+004 1274.43    34.80   5.212E+004                 3.815E+004   2.344E+004
 +      Eu-155       86.55*   30.70   1.216E+005    1.22E+005    1. 355E+OD5  5.97SE+004 105.31    21.10   2.462E+005                 2.194E+004   1 .216E+005 Tl-208      583.19    85. 00  3.299E+004    3.30E+004   -6.928E+003   1.575E+004 Bi-212      727.33     6.67   2.856E+005    2.86E+005    2.143E+OD4   1.323E+OOS
 +      Pb-212      238.63*   43.60   5.814E+004    5.81E+004    3.699E+004   2.814E+OD4
 +      Bi-214      609.32*   45.49   4.088E+004    1.44E+004    9.111E+004   1. 903E+O 04 1120.29    14.92   1.660E+005                 2.271E+OD5   7.723E+004 1764.49*   15.30   1.441E+004                 1.863E+OD5   O.OOOE+OOO
 +      Pb-214      295.22    18.42   2.067E+005    7 .1 5E+004 -1.439E+005   1.009E+OOS 351.93*   35.60   7.151E+004                 6.763E+OD4   3.437E+ 004 Ra-226      186.21     3.64   1.580E+006    1.58E+006    2.599E+OD6   7.802E+OOS Ac-228      338.32    11. 27  3.121E+005    8.76E+004   -4.597E+004   1.518E+OD5 911.20    25.80   8.764E+004                 1.114E+004   4.081E+ 004 968.97    15.80   1.475E+005                 7.902E+004   6.866E+ 004 Am-241       59 .5 4  35.90   1. 420E+005   1.42E+005   -7.944E+004   6.993E+ 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
       @ c Half-life too short to be able to perform the decay correction

[96]

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

Filename: 5456-A Report Generated On 6/1/2018 2:13:2'/ PM Sample Title B103202AFSWC004GD Sample Description SFP/TRANSFER CANAL Sample Identification 004 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/1/2018 2:03:0 0 PM Acquisition Started 6/1/2018 2:03:25 PM Live Time 600 . 0 seconds Real Time 600.9 seconds Dead Time 0 .. 15 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [97]

Peak Analysis Report 6/1/2018 2:13:27 PM Page 2

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

Detector Name: 5456-A sample

Title:

B103202AFSWC004GD Peak Analysis Performed on: 6/1/2018 2:13:26 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 1 126- 150 130.17 32.54 0 .99 5.35E+002 91.22 3.11E+002 2 284- 307 301.60 75 .40 1. 25 1 .00E+003 166.20 l.48E+003 3 334- 346 340.77 85.19 1.18 2.52E+002 102.55 9.01E+002 4 2430- 2443 2436.66 609.17 1. 27 3.62E+001 23 .44 3.68E+001 5 2634- 2658 2646.36 661.59 1. 56 2.82E+003 110.05 4.99E+001 6 4685- 4701 4693.13 1173.28 1. 32 5.46E+001 16.63 4.42E+OOO 7 5323- 5338 5330.50 1332.63 0.73 4.95E+001 16. 85 6.51E+OOO 8 5835- 5855 5844.46 1461.12 0.45 l.51E+002 26. 93 8.14E+OOO 9 7053- 70 6 8 7060.29 1765.07 0.32 2.50E+001 10. 00 O.OOE+OOO M First peak in a mul t iplet region m = Other peak in a mul t iplet region F "" Fitted singlet Errors quoted at 2 . 000 sigma [98]

Interference Corrected Activity Report 6/1/2018 2:13:27 PM Page 3

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Sample

Title:

Bl03202AFSWC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * * * * * * * * * ******* I "     IDENTIFIED NUCLIDES             . .... .......'
                                                                          "             ~ .. . ' .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M ... 2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.02758E+006 2.04008E+005 Co-60 1.000 1173.23* 99.85 3.54243E+004 l .11566E+004 1332.49* 99.98 3.41340E+004 l .19368E+004 Cs-137 1.000 661.66* 85. 10 1 .63852E+006 2.06887E+005 Eu-155 0.346 86.55* 30.70 l.97316E+005 8.95443E+004 1 05.31 21. 10 Bi-214 0.705 609.32* 45.49 3.78557E+004 2.49012E+004 1120.29 14.92 1764.49* 15.30 1 .33097E+005 5.42958E+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

[99]

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Nuclide wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 } Uncertainty K-40 1. 000 1.027575E+006 2.040083E+OOS Co-60 1.000 3.482271E+004 8.150767E+003 Cs-137 1.000 1.638519E+006 2.068867E+005 Eu-155 0.346 1.973159E+005 8.954433E+004 Bi-214 0.705 5.440696E+004 2.263435E+004

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

Peak Locate Performed on: 6/1/2018 2:13:26 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 32.54 8.9162E-001 17.05 2 75.40 1.6676E+OOO 16.61 M = First peak in a multiplet region m = Other peak in a multiplet region F r Fitted singlet Errors quoted a t 2 . 000 sigma [100]

Nuclide MDA Report 6/1/2018 2:13:27 PM Page 5

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Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC004GD 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. 422E+005    l.42E+OD5   l .028E+OD6  6.188E+004
 +      Co-60      1173.23*   99.85   9.895E+003     9.90E+003   3.542E+004   4 .069E+003 1332.49*   99.98   l. 238E+004                3.413E+004   5.258E+003 Nb-94       702.65    99.81   l. 761E+004    1.76E+004   8.274E+OD3   8.118E+003 8 71. 09  99.89   1. 906E+004                7.586E+003   8.769E+003 Ag-108m     433.90    90.50   3.896E+004     1.84E+004  -4.595E+004   l .888E+004 614.30    89.80   3.150E+004                -1. 717E+O 04 1 .503E+004 722.90    90.80   l. 843E+004               -7.264E+003   8.446E+003 Cs-134      604.72    97.62   2.811E+004     2.26E+004  -5.223E+003   l.340E+004 795.86    85.46   2.263E+004                 1. 034E+004  1.046E+004
 +      Cs-137      661.66*   85.10   2.896E+004     2.90E+004   1.639E+OD6   l.369E+004 Eu-152      121.78    28.67   l. 793E+005    7.39E+004  -7.511E+004   8.851E+004 344.28    26.60   1. 350E+O 05              -5.468E+OD4   6.569E+004 1408. 01   21.07   7.389E+004                -1. 966E+004  3.238E+004 Eu-154      123.07    40. 40  1.267E+005     5.12E+004   4.027E+OD4   6.254E+004 723.30    20.06   8.249E+004                -5.014E+004   3.777E+004 1274 . 43  34.80   !=i.124E+004               7.867E+OD3   2.300E+004
 +      Eu-155        86.55*  30.70   1. 279E+O 05   1.28E+005   1 .973E+OD5  6.287E+004 105. 31   21.10   2.503E+005                -9.048E+004   l. 236E+005 Tl-208      583.19    85.00   3.247E+004     3.25E+004   3.542E+004   1. 549E+004 Bi-212      727.33     6.67   2.400E+005     2.40E+OD5  -l.425E+005   l. 095E+005 Pb-212      238.63    43.60   9.617E+004     9.62E+004   5.035E+004   4.716E+004
 +      Bi-214      609.32*   45.49   3.738E+004     1.44E+004   3.786E+004   1. 728E+004 1120.29    14.92   1. 456E+O 05               3.550E+004   6.706E+004 1764.49*   15.30   1.441E+004                 1.331E+005   O.OOOE+OOO Pb-214      295.22    18.42   2.074E+005     1 .04E+OD5 -3.314E+004   1.013E+005 351.93    35.60   1. 045E+005               -3.082E+004   5.085E+004 Ra-226      186.21     3.64   1. 365E+006    l .37E+006  8.532E+005   6.728E+005 Ac-228      338.32    11. 27  3.198E+005     8.63E+OD4  -2.383E+005   1.556E+005 911. 2 0  25.80   8.631E+004                -1.025E+004   4.014E+004 968.97    15.80   1 .297E+005                1.420E+004   5.978E+004 Am-241        59.54   35.90   1 .434E+005    l.43E+OD5   8.425E+004   7.064E+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

[101]

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

Filename: 5452A Report Generated On 6/20/2018 10 :35:25 AM Sample Title B103202AFSWC004GD Sample Description Spent Fool Pool/Transfer Canal W Sample Identification Sample Type Gamma Direct Sample Geometry 1M90D SPF 2IN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/20/2018 10:25:00 AM Acquisition Started 6/20/2018 10:25:23 AM 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 5/30/2018 Efficiency ID 1M90DSFP 2IN [102]

Peak Analysis Report 6/20/2018 10 :35:25 AM Page 2

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

Detector Name: 5452A Sample

Title:

B103202AFSWC004GD Peak Analysis Performed on: 6/20/2018 10:35:24 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 1 118- 132 124.55 31. 14 1. 40 2.76E+002 70 .68 3.37E+002 2 272- 300 29 0. 69 72.67 1.18 1.03E+003 182.16 J .S7E+003 3 324- 333 328.75 82.19 0.85 8.53E+001 80.69 6.83E+002 4 951- 960 955.28 238.82 0.56 6.66E+001 43.21 1.75E+002 5 1402- 1416 1408.42 352. 11 0.58 7.13E+001 40. 02 1.14E+002 6 2429- 2446 2437.62 609.41 1.45 9.45E+001 23.54 1.35E+001 7 2634- 2659 2646.74 661.68 1. 53 1.96E+003 93.35 5.16E+001 8 3640- 3653 3646.08 911.52 0. 40 2.41E+001 13.98 8.86E+OOO 9 4690- 4705 4696.49 1174.12 0. 47 4.70E+001 17.16 9.02E+OOO 10 5325- 5341 5332.80 1333.20 0. 85 4.28E+001 15.74 6.16E+OOO 11 5836- 5858 5846.24 1461 .56 1. 50 l.39E+002 25. 04 4.98E+OOO 12 7053- 7068 7060.31 1765.08 0. 48 2.98E+001 13.18 4.21E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F '"' Fitted singlet Errors quoted at 2 . 000 sigma [103]

Incerference corrected Activity Report 6/20/2018 10 :35:25 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:

B103202AFSWC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB

        "                            IDENTIFIED NUCLIDES

• I
• I * * * * * * * * * *
• 11 * ,11 ..
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %} (pCi/MA2 ) Uncertainty K-40 0.999 1460.82* 10.66 9.56245E+005 1.91189E+005 Co-60 0.999 1173.23* 99.85 3.06768E+004 l.14688E+004 1332.49* 99.98 2.98224E+004 1.12119E+004 Cs-137 1. 000 661. 66* 85.10 1.14253E+D06 1 .47593E+005 Eu-155 0 .329 86.55* 30.70 6.78982E+004 6.56480E+004 105.31 21. 10 Pb-212 1. 000 238.63* 43.60 4.55851E+D04 3.04662E+OD4 Bi-214 0 .705 609.32* 45.49 9.89727E+004 2.73793E+004 1120.29 14. 92 176 4.49* 15.30 1 .60401E+005 7.21093E+004 Pb-214 0 .438 295.22 18.42 351.93* 35.60 7.26672E+004 4 .24017E+004

       *=Energy line f ound in the spectrum.
       @=Energy line n ot used for Weighted Mean Activity Energy Tolerance :              10.000 keV Nuclide confidence index threshold=                   0.30 Errors quoted at 2.000 sigma

[104]

Interference Corrected Activity Report 6/20/2018 10:35:25 AM Page 4

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

Nuclide Wt mean wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.999 9.562446E+OOS 1.911892E+OOS Co-60 0.999 3.023994E+004 8.017295E+003 Cs-137 1.000 1.142531E+006 1.475933E+OOS Eu-155 0.329 6.789817E+004 6.564802E+004 Pb-212 1. 00 0 4. 558507E+004 3.04662SE+004 Bi-214 0.705 1.067127E+OOS 2.559631E+004 Pb-214 0.438 7.266724E+004 4. 240173E+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

[105]

Interference Corrected Activity Report 6/20/2018 10: 3 5:25 AM Page 5

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

Peak Locate Performed on: 6/20/2 018 10 :35:24 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 31. 14 4 .5977E-001 25.62 2 72.67 1. 71 79E+OO 0 17.67 8 911. 52 4 .0240E-002 57.90 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 [106]

Nuclide MDA Report 6/20/2018 10:35:25 AM Page 6

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

Detector Name: 5452A Sample Geometry: 1M90D- SPF- 2IN Sample

Title:

B103202AFSWC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/MA2 )

 +      K-40       1460 . 82*  10 .66  l .138E+005     1 .14E+005  9.562E+005   4.759E+004
 +      Co-60      1173.23*    99.85   1. 285F.+O 04   1 .19E+004  3.068E+004   5.541E+003 1332.49*    99.98   1 .189E+004                 2.982E+004   5.001E+003 Nb-94       702.65     99.81   1 .643E+004     l .64E+004 -8.731E+003   7.523E+003 871.09     99.89   l .840E+004                -1. 945E+004  8.432E+003 Ag-108m     433.90     90.50   3.758E+004      1. 99E+004  4.439E+003   1.819E+004 614.30     89.80   3.139E+004                 -2.469E+004   1. 4 97E+004 722.90     90.80   l .991E+004                 8.294E+003   9.183E+003 Cs-134      604.72     97.62   3.081E+004      2.34E+004  -1.413E+004   1.475E+004 795.86     85.46   2.338E+004                  1.249E+004   1 .083E+004
 +      Cs-137      661.66*    85.10   2.989E+004      2.99E+004   1.143E+006   1. 415E+004 Eu-152      121 .78    28.67   l .687E+005     7.83E+004   9.528E+003   8.323E+004 344.28     26.60   1 .209E+005                -8.221E+004   5.860E+004 1408. 01    21.07   7.832E+004                  6.474E+004   3.455E+004 Eu-154      123.07     40.40   l .189E+005     4.17E+004  -5.856E+004   5.864E+004 723.30     20.06   9.014E+004                  3.813E+004   4.158E+004 1274.43     34.80   4.166E+004                  2.748E+003   1.819E+004
 +      Eu-155       86.55*    30.70   l.050E+005      1. 05E+005  6.790E+004   5.142E+004 105.31     21.10   2.423E+005                  6.398E+004   1 .196E+005 Tl-208      583.19     85.00   2.801E+004      2.80E+004   3.155E+004   1 .326E+004 Bi-212      727.33      6.67   2.692E+005      2.69E+005  -4.667E+004   1 .241E+005
 +      Pb-212      238.63*    43.60   4.688E+004      4.69E+004   4.559E+004   2.251E+004
 +      Bi-214      609.32*    45.49   2.571E+004      2.57E+004   9.897E+004   1.144E+004 1120 . 29   14.92   1 .617E+005                 2.154E+004   7.506E+004 1764.49*    15.30   7.997E+004                  1. 6 04E+005 3.270E+004
 +      Pb-214      295.22     18.42   l .861E+005     6.36E+004  -2.420E+005   9.060E+004 351.93*    35.60   6.357E+004                  7.267E+004   3.040E+004 Ra-226      186.21      3.64   1. 264E+O 06    1. 26E+006 -3.942E+005   6.222E+005 Ac-228      338.32     11. 27  2.973E+005      9.07E+004   1. 648E+005  1. 444E+OOS 911.20     25.80   9.070E+004                  2.015E+004   4. 232E+004 968.97     15 .80  1. 365E+005                -7.133E+004   6.317E+004 Am-241       59. 54    35.90   1.480E+005      l. 48E+005  4.371E+004   7.290E+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

[107]

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

Filename: 5452A Report Generated On 6/20/2018 10:47:29 AM Sample Title B103202AFQWC004GD Sample Description Spent Fool Pool/Transfer Canal W Sample Identification QC Sample Type Gamma Direct Sample Geometry 1M90D SPF 2IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO M"2 Sample Taken On 6/20/2018 10:37:00 AM Acquisition Started 6/20/2018 10:37:27 AM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0 .08 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [108]

Peak Analysis Report 6/20/2018 10:47:29 AM 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:

B103202AFQWC004GD Peak Analysis Performed on: 6/20/2018 10:47:28 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 1 115- 147 124 .71 31.18 1.30 3.62E+002 119. 00 6.12E+002 2 271- 300 290.75 72.69 1.19 8.39E+002 197.77 1 .88E+003 3 322- 333 328.72 82.18 0.92 6.75E+001 92.71 8.24E+002 4 557- 566 561.51 140 . 38 0.27 1.87E+001 59.75 3.87E+002 5 1400- 1417 1409.82 352.45 0.83 8.28E+001 43.38 1.19E+002 6 2428- 2445 2436.76 609.19 0.85 6.08E+001 24.49 2.72E+001 7 2636- 2658 2646.79 661.70 1.62 1.82E+003 91.14 6.75E+001 8 3637- 3651 3644.02 911 .01 0.37 3.12E+001 17.19 1.48E+001 9 4688- 4703 4694.83 1173.71 0.72 5.38E+001 16.58 5.16E+OOO 10 5326- 5339 5332.32 1333.08 0.61 3.42E+001 15.71 9.84E+OOO 11 5836- 5857 5846.39 1461 .60 0.73 1.27E+002 26.33 1.26E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [109]

Interference Corrected Activity Report 6/20/2018 10:47:29 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:

Bl03202AFQWC004GD Nuclide Library use d: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB I ****** f * * * * * * *'"' * * *

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M ... 2 ) Uncertainty K-40 0.999 1460.82* 10. 66 8.76584E+005 l.96445E+005 Co-60 1 .000 11 73.23* 99.85 3.51509E+004 1.11868E+004 1332.49* 99.98 2.37799E+004 1.11040E+004 Cs-137 1 .000 661.66* 85.10 1.05984E+006 1.37910E+005 Eu- 155 0 .329 86.55* 30.70 5.37685E+004 7.45777E+004 1 05.31 21.10 Bi-214 0 .439 609.32* 45.49 6.36917E+004 2.67607E+004 1120.29 14.92 1764.49 15.30 Pb-214 0 .438 295.22 18.42 351.93* 35.60 8.44522E+004 4 .62383E+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

[110]

Interference Corrected Activity Report 6/20/2018 10:47:29 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M ... 2 ) Uncertainty K-40 0.999 8.765835E+005 l .964447E+005 Co-60 1. 00 0 2.942318E+004 7.880852E+003 Cs-137 1. 00 0 l.059837E+006 1 .379101E+005 Eu-155 0.329 5.376846E+004 7.457770E+004 Bi-214 0.439 6.369166E+004 2.676075E+004 Pb-214 0.438 8.445219E+004 4.623827E+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

[111]

Interference Corrected Activity Report 6/20/2018 10:47:29 AM Page 5

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

Peak Locate Performed on: 6/20/2018 10 :47:28 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 31. 18 6.0403E-001 32.83 2 72.69 1. 3976E+OOO 23.58 4 140.38 3.1135E-002 319.84 8 911. 01 5.1957E-002 55.13 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 [112]

Nuclide MDA Report 6/20/2018 10 :47 : 29 AM Page 6

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

Detector Name: 5452A Sample Geometry: 1M90D SPF 2IN Sample

Title:

B103202AFQWC004GD 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.719E+005    l .72E+005   8.766E+OOS    7.662E+004
 +      Co-60      1173.23*   99.85   l.006E+D04    1 .01E+D04   3.515E+D04    4.148E+003 1332.49*   99.98   1.391E+004                 2.378E+004    6.014E+003 Nb-94       702.65    99.81   l.903E+OD4    l .90E+004   8.235E+003    8.822E+003 8 71. 09  99.89   1.978E+004                 5.012E+D03    9.124E+003 Ag-108m     433.90    90.50   3.558E+004    2.10E+004    1.526E+004    1.719E+OD4 614.30    89.80   3.209E+OD4                -6.797E+003    l. 533E+004 722.90    90.80   2.102E+004                 1.934E+OD4    9.740E+003 Cs-134      604.72    97.62   2.691E+004    2.04E+004    1 .987E+003   l.280E+OD4 795.86    85.46   2.036E+004                -7.288E+002    9.325E+003
 +      Cs-137      661.66*   85.10   3.239E+004    3.24E+OD4    1 .060E+OD6   1.541E+004 Eu-152      121. 78   28.67   l.628E+D05    7.26E+004   -9.518E+004    8.026E+D04 344.28    26.60   1.2D9E+005                -1. 337E+005   5.860E+004 1408.01    21.07   7.263E+004                 5.452E+D04    3.171E+004 Eu-154      123.07    40.40   1.151E+OOS    4.89E+004   -2.38DE+004    5.676E+D04 723.30    20.06   9.51BE+004                 1.91DE+004    4.410E+004 1274 .43   34.80   4.890E+004                 2.162E+D04    2.180E+004
 +      Eu-155        86.55*  30.70   l.216E+005    1.22E+OD5    5.377E+004    5.974E+D04 105.31    21.10   2.360E+OD5                -3.634E+D05    l .165E+005 Tl-208      583.19    85. 00  3.103E+004    3. 1 0E+004  8.095E+003    1 .477E+004 Bi-212      727.33     6.67   2.895E+005    2.89E+005    1.556E+004    1. 342E-+ 005 Pb-212      238.63    43.60   9.146E+OD4    9. 1 SE+OD4  9.329E+004    4.481E+004
 +      Bi-214      609.32*   45.49   3.53SE+004    3.54E+004    6.369E+004    1.626E+D04 1120.29    14.92   1.549E+005                 1. 268E+005   7.169E+004 1764.49    15.30   1.347E+005                 7.612E+004    6.005E+004
 +      Pb-214      295.22    18.42   l.905E+005    6.88E+004    1. 508E+005   9.280E+D04 351.93*   35.60   6.879E+OD4                 8.445E+004    3.301E+004 Ra-226      186.21     3.64   1.282E+006    1.28E+006    8.942E+OD5    6.31DE+005 Ac-228      338.32    11. 27  2.992E+005    1 .0 0E+OOS  2.111E+005    1. 453E+O 05 911. 20   25.80   1.004E+OD5                 l. 043E+005   4.717E+004 968.97    15.80   1. 448E+OOS                1. 685E+005   6.729E+004 Am-241        59.54   35.90   1.433E+OD5    l.43E+005    1. 518E+005   7.057E+004
       + = Nuclide identified during the nuclide i dentification
       * ~ 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]

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

Filename: 5456-A Report Generated On 6/2/2018 8:52:44 AM Sample Title B103202AFQWC004GD Sample Description SFP/TRANSFER CANAL Sample Identification 004 QC Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 3.140E+OOO M"2 Sample Taken On 6/2/2018 8:42:00 AM Acquisition Started 6/2/2018 8:42:43 AM Live Time 600 . 0 seconds Real Time 600.8 seconds Dead Time 0 .12 % Energy Calibration used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [114]

Peak Analysis Report 6/2/20l8 8:52:44 AM Page 2

• • • • • P E A K ANALYSIS REPORT *****

Detector Name: 5456-A Sample

Title:

B103202AFQWC004GD Peak Analysis Performed on: 6/2/2018 8:52:44 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 Un cert. Counts 1 126- 137 129.67 32.42 0. 73 1.24E+002 41. 92 1. 01E+002 2 285- 311 3 01. 56 75.39 1. 25 9.98E+002 1 66.00 1.3SE+003 3 333- 345 339.89 84.97 0.65 l .95E+002 96.15 8.06E+002 4 1402- 1414 1408.49 352.12 0.71 4.30E+001 33.64 9.lOE+OOl 5 1435- 1446 1440. 11 360.03 0.66 1.87E+001 23.27 4.63E+001 6 2326- 2339 2332. 61 583.15 0.37 3.00E+OOl l8.16 1.90E+001 7 2427- 2444 2436.84 609.21 1. 54 6.84E+001 21. 81 1. 56E+O 01 8 2634- 2657 2645. 31 661.33 1. 57 8.32E+002 62.29 3.51E+001 9 3639- 3652 3645.12 911.28 0. 90 2.25E+001 l2.43 5.54E+OOO 10 4686- 4701 4692.32 1173.08 1.12 4.77E+001 16.62 7.27E+OOO 11 5323- 5337 5329.61 1332.40 0 .60 4. 39 E+001 14.47 3.13E+OOO 12 5833- 5853 5843.24 1460.81 0 .68 1. 28 E+002 25. 74 1 .05E+001 M First peak in a mul t iplet region m -= Other peak in a mul t iplet region F :::, Fitted singlet Errors quoted at 2.000 sigma [115]

Interference Corrected Activity Report 6/2/2018 8:52:44 AM Page 3

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Sample

Title:

B103202AFQWC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * ******

• I **** I* * * ** IDENTIFIED NUCLIDES *
• 11 .. * * * * * * * *
• I f .. I fl
• I Nuclide Id Energy Yield Activity Activity Name Confidence (keV} ( %} (pCi/M"2 } Uncertainty K-40 1.000 1460.82* 10.66 8.68367E+OOS 1 .90823E+OOS Co-60 1.000 1173.23* 99.85 3.09714E+004 l .10671E+004 1332.49* 99.98 3.02561E+004 1 .02684E+004 Cs-137 1.000 661.66* 85. 10 4.82941E+005 6.83463E+004 Eu-155 0.345 86.55* 30.70 1.53397E+005 8.14453E+004 105.31 21. 10 Tl-208 1.000 583.19* 85. 00 1.64464E+004 1 .01390E+004 Bi-214 0.438 609.32* 45.49 7.14658E+004 2.43452E+004 1120.29 14 .92 1764.49 15.30 Pb-214 0.439 295.22 18 .42 351.93* 35.60 4.38850E+004 3.50402E+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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• • • • • 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 8.683670E+005 1. 908234E+005 Co-60 1. 000 3.058702E+004 7.527379E+003 Cs-13 7 1. 000 4.829410E+005 6.834626E+004 Eu-155 0.345 1.533974E+005 8.144530E+004 Tl-208 1. 000 1.644644E+004 1.013898E+004 Bi-214 0.438 7.146581E+004 2.434522E+004 Pb-214 0.439 4.388500E+004 3.504019E+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

[117]

Interference Corrected Activity Report 6/2/2018 8:52:44 AM Page 5

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

Peak Locate Performed on: 6/2/2018 8:52:44 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 32.42 2.0665E-001 33.81 2 75.39 1. 6630E+OOO 16.64 5 360.03 3.1147E-002 124.50 Tol. Pb-214 9 911. 28 3.7440E-002 55.31 To l. 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 [118]

Nuclide MDA Report 6/2/2018 8:52:45 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFQWC004GD Nuclide Library used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

 +      K-40       1460 . 82*  10. 66  1.568E+005    1.57E+005    8.684E+OOS  6.916E+004
 +      Co-60      1173.23*    99.85   1.162E+004    8.47E+003    3.097E+004  4 .931E+003 1332.49*    99.98   8.470E+003                 3.026E+004  3.302E+003 Nb-94       702.65     99.81   1. 941E+004   1. 87E+004   3.813E+003  9.019E+003 871.09     99.89   1.866E+004                 9.213E+002  8.572E+003 Ag-108m     433.90     90.50   2.954E+004    1. 94E+004   2.674E+004  1 .417 E+004 614. 3 0   89.80   2.794E+004                -9.656E+003  l.325E+004 722.90     90.80   l. 943E+004               -1.184E+004  8.946E+003 Cs-134      604.72     97.62   2.654E+004    2.14E+004    5.030E+003  1.261E+004 795.86     85.46   2.136E+004                 6.747E+003  9.830E+003
 +      Cs-137      661 .66*   85. 10  2.401E+004    2.40E+004    4.829E+005  1.122E+004 Eu-152      121 .78    28.67   1. 624E+005   8.45E+004    1 .140E+004 8.008E+004 344.28     26.60   1. 034E+005               -1 .160E+OOS 4.988E+004 1408 .01    21. 07  8.445E+004                 2.458E+003  3.766E+004 Eu-154      123.07     40.40   1. 150E+005   5.04E+004   -2.765E+004  5.668E+004 723.30     20.06   8.883E+004                 1.815E+004  4.094E+004 1274.43     34.80   5.035E+004                -2.315E+004  2.255E+004
 +      Eu-155       86.55*    30.70   1. 209E+005   1.21E+005    1.534E+OOS  5.937E+004 105.31     21.10   2.295E+005                 5.278E+004  1.132E+OOS
 +      Tl-208      583.19*    85.00   1. 453E+004   1. 4 5E+004  1.645E+004  6.522E+003 Bi-212      727.33      6.67   2.625E+005    2.63E+005   -1.739E+005  1.208E+005 Pb-212      238.63     43.60   8.394E+004    8.39E+004    1 .965E+004 4.104E+004
 +      Bi-214      609.32*    45.49   2.724E+004    2.72E+004    7.147E+004  1.221E+004 1120.29     14.92   l. 350E+005                6.321E+003  6.175E+004 1764 .49    15.30   1. 306E+005                8.033E+004  5.808E+004
 +      Pb-214      295.22     18.42   1. 629E+OOS   S.48E+004   -1.012E+OOS  7.900E+004 351.93*    35.60   S.476E+004                 4.388E+004  2.600E+004 Ra-226      186.21      3.64   1. 207E+006   1.21E+006   -4.887E+OOS  5.934E+OOS Ac-228      338.32     11.27   2.461E+005    8.29E+004   -8.272E+004  1 .188E+OOS 911.20     25.80   8.289E+004                -2.398E+004  3.843E+004 968.97     15.80   1. 335E+005               -7.515E+003  6.166E+004 Am-241       59.54     35.90   1. 320E+OOS   1.32E+005    6.657E+004  6.492E+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

[119]

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

Filename: 5456-A Report Generated On 6/2/2018 2:21:08 PM Sample Title B103202AFSFCOOSGD Sample Description SFP/TRANSFER CANAL Sample Identification 005 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3 .00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/2/2018 2: 10 : 00 PM Acquisition Started 6/2/2018 2: 11 :06 PM Live Time 600. 0 seconds Real Time 600.6 seconds Dead Time 0.11 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [120]

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC005GD Peak Analysis Performed on: 6/2/2018 2:21:07 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 1 126- 135 129.99 32.50 0.64 1.69E+002 36.77 6.37E+001 2 285- 310 301.33 75.33 0.93 1 .23E+003 151 .21 1.05E+003 3 331- 356 340.25 85.06 1.13 4.28E+002 136. 61 9.95E+002 4 950- 960 955.97 238.99 0.62 2.75E+001 38.64 1. 46E+002 5 1402- 1416 1409 .18 352.29 0.67 5.83E+001 36.69 9.47E+001 6 1788- 1800 1793.40 448.35 0.53 9.02E+OOO 26.75 5.70E+001 7 2327- 2339 2332.60 583.15 0.36 3.36E+001 18.30 1.84E+001 8 2430- 2447 2438.22 609.56 0.98 5.70E+001 24.09 2.70E+001 9 2638- 2659 2647.54 661.89 1. 51 1 .41E+003 78.46 3.37E+001 10 3640- 3653 3646.57 911.64 0.33 1 .63E+001 16 .25 l.77E+001 11 3871- 3884 3877.81 969.45 0.37 2.55E+001 12.87 5.51E+OOO 12 4477- 4491 4484.10 1121.02 0.38 1.93E+001 17.11 1. 88E+001 13 4687- 4704 4696.18 1174.05 1.15 6.45E+001 20. 83 1.35E+001 14 5326- 5341 5333.80 1333.45 1. 96 5.47E+001 16.55 4.27E+OOO 15 5837- 5858 5847.90 1461.98 1 .06 1. 56E+O 02 27.31 8.20E+OOO 16 7058- 7073 7065.66 1766.41 0.66 l.91E+001 12.35 5.85E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F - Fitted singlet Errors quoted at 2.000 sigma [121]

Interference Corrected Activity Report 6/2/2018 2: 21: 08 PM Page 3

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Sample

Title:

B103202AFSFC005GD Nuclide Library Us ed: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• I * * * * * * * * * * * * * * * *
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0 .998 14 60.82* 10.66 1. 06164E+006 2.07676E+005 Co-60 0 .999 11 73.23* 99.85 4.18932E+004 l.39344E+004 1332.49* 99.98 3.77596E+004 l.18106E+004 Cs-137 1 . 000 661.66* 85. 10 8.18424E+005 l.08319E+005 Eu-155 0 .346 86.55* 30.70 3.35819E+005 l.26455E+005 105.31 21. 10 Tl-208 1. 000 583. 19* 85.00 1 .83981E+004 l.02587E+004 Pb-212 1. 000 238.63* 43.60 1. 89 060E+O 04 2.67527E+004 Bi-214 0. 999 609.32* 45.49 5.95486E+004 2.61654E+004 11 2 0.29* 14.92 8.18457E+004 7.30263E+004 1764.49* 15.30 1.01998E+O 05 6.62624E+004 Pb-214 0.439 295.22 18.42 351.93* 35.60 5.95536E+004 3.86477E+004 Ac-228 0.588 338.32 11. 27 911.20* 25.80 3.62430E+004 3.63535E+004 968.97* 15.80 9.55736E+004 4. 90043E+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

[122]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.998 1.061638E+006 2.076758E+OOS Co-60 0.999 3.948773E+004 9.009688E+003 Cs-137 1.000 8.184236E+005 1.083185E+OOS Eu-155 0.346 3.358193E+005 1.264546E+OOS Tl-208 1. 000 l.839809E+004 1.025866E+OD4 Pb-212 1. 000 1.890598E+004 2.675267E+OD4 Bi-214 0.999 6.693108E+004 2.308835E+004 Pb-214 0.439 5.955360E+004 3.864768E+004 Ac-228 0.588 5.730400E+004 2.919672E+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

[123]

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Peak Locate Performed on: 6/2/2018 2: 21: 07 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.50 2.8224E-001 2 1. 72 2 75.33 2.0554E+OOO 12.26 6 448.35 1 .5038E-002 296.49 D-Esc. M ~ First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [124]

Nuclide MDA Report 6/2/2018 2:21:08 PM Page 6

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Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide 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 .426E+005   1 .43E+005   1 .062E+006 6.207E+OD4
 +       Co-60     1173.23*    99.85  1 .592E+004   1.03E+004    4.189E+004  7.082E+003 1332.49*    99.98  1 .028E+004                3.776E+004  4.207E+D03 Nb-94      702.65     99.81  1 .636E+004   1.64E+004    6.687E+003  7.489E+003 871.09     99.89  1 .806E+004               -1.847E+003  8.268E+003 Ag-108m     433.90     90.50  3.563E+004    1.96E+004   -1.572E+004  1 .721E+004 614.30     89.80  3.047E+004                 1.207E+004  1 .452E+004 722.90     90.80  1 .962E+004               -2.211E+004  9.043E+003 Cs-134     604.72     97.62  2.811E+004    1.95E+004    3.637E+003  1 .340E+004 795.86     85.46  1.953E+004                -7.405E+002  8.913E+003
 +       Cs-137     661.66*    85.10  2.332E+004    2.33E+004    8.184E+005  1.088E+004 Eu-152     121. 78    28.67  1.329E+005    8.28E+004    5.909E+004  6.533E+004 344.28     26.60  1.131E+005                 l.592E+004  5.470E+004 1408.01     21. 07 8.280E+004                 7.426E+004  3.683E+004 Eu-154     123.07     40.40  9.243E+004    4 .02E+004  -4.475E+004  4.541E+004 723.30     20.06  8.883E+004                -9.068E+004  4.094E+004 1274.43     34.80  4.018E+004                 2.197E+003  1.747E+004
 +       Eu-155      86.55*    30.70  1.701E+D05    1.70E+005    3.358E+OOS  8.398E+004 105.31     21. 10 1.920E+D05                -5.691E+003  9.449E+004
 +       Tl-208     583.19*    85.00  l.423E+004    1. 42E+004   l.840E+004  6.374E+003 Bi-212     727.33      6.67  2.756E+005    2.76E+005   -2.322E+004  1.273E+005
 +       Pb-212     238.63*    43.60  4.394E+004    4.39E+004    1.891E+004  2.104E+004
 +       Bi-214     609.32*    45.49  3.509E+D04    3.51E+004    5.955E+004  1.613E+004 1120.29*    14. 92 1.142E+005                 8.185E+004  5.135E+004 1764.49*    15.30  9.070E+004                 1.020E+005  3.815E+004
 +       Pb-214     295.22     18.42  1. 712E+005   5.88E+004   -2.499E+004  8.315E+004 351.93*    35.60  5.878E+004                 5.955E+004  2.801E+004 Ra-226     186.21      3.64  9.146E+005    9.15E+005    8.689E+005  4.474E+005
 +      Ac-228      338.32     11. 27 2.654E+005    5.78E+004   -3.161E+004  l.284E+OOS 911.20*    25.80  5.776E+OD4                 3.624E+004  2.586E+004 968.97*    15.80  5.940E+004                 9.557E+004  2.463E+004 Am-241       59.54     35.90  l.161E+OOS    1. 1 6E+005  9.953E+004  5.696E+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

[125]

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

Filename: 5456-A Report Generated On 6/2/2018 2:40:18 PM Sample Title B103202AFSFC006GD Sample Description SFP/TRANSFER CANAL Sample Identification 006 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO M... 2 Sample Taken On 6/2/2018 2:29:00 PM Acquisition Started 6/2/2018 2: 30: 14 PM Live Time 600 . 0 seconds Real Time 603.0 seconds Dead Time 0 . 49 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [126]

Peak Analysis Report 6/2/2018 2:40:18 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B1 03202AFSFC006GD Peak Analysis Performed on: 6/2/2018 2 :40: 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 1 126- 155 129.66 32.41 0.80 3.21E+003 197.64 1 .14E+003 2 284- 308 30 1 .07 75.27 1. 00 2.52E+003 264.51 3.63E+003 3 332- 356 34 0 .22 85.05 1. 28 1.17E+003 252.55 3.58E+003 4 530- 541 534.06 133.51 0.33 -1.68E+001 122.62 1.50E+003 5 2425- 2443 2437.48 609.37 0.79 6.52E+001 46.30 1.39E+002 6 2632- 2658 2646.29 661.57 1. 44 2.42E+004 314.03 1.12E+002 7 4682- 4704 4693.11 1173.28 1. 60 2.91E+002 38.34 1.98E+001 8 5320- 5342 5331.10 1332.78 2.11 3.02E+002 35.36 2.76E+OOO 9 5833- 5855 5844.58 1461.15 1. 90 1.47E+002 25.17 2.88E+OOO 10 7052- 7067 7059.75 1764.94 0.44 2.40E+001 9.80 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 [127]

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Sample

Title:

B103202AFSFC006GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  *

• A * * * * * .. I * ,o * * * * * * *
• IDENTIFIED NUCLIDES * * * * * * * * * * * * * .. I ** * *
• I Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 1. 00211E+006 l.92265E+005 Co-60 1.000 1173.23* 99.85 1. 88975E+005 2. 91124E+004 1332.49* 99.98 2.08466E+005 2. 95488E+004 Cs-137 1.000 661.66* 85.10 1. 4 0228E+007 l.69386E+006 Eu-155 0.346 86.55* 30.70 9.16990E+005 2.69948E+005 1 0 5.31 21.10 Bi-214 0.705 609.32* 45. 49 6.80692E+004 4. 90543E+004 11 20.29 14.92 1764.49* 15. 30 1.27768E+005 5.31554E+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

[128]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 1 .002111E+006 1.9226SOE+005 Co-60 1. 000 1 .985758E+005 2.073814E+004 Cs-137 1.000 1 .402278E+007 1.693865E+006 Eu-155 0.346 9.169905E+005 2.699482E+005 Bi-214 0.705 9.552704E+004 3.604943E+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

[129]

Interference Corrected Activity Report 6/2/2018 2:40:18 PM Page 5

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Peak Locate Performed on: 6/2/2018 2:40:18 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 32.41 5.3583E+OOO 6.15 2 75.27 4 .1962E+OOO 10.51 4 133.51 -2.7972E-002 -730.62 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [130]

Nuclide MDA Report 6/2/2018 2: 40 ; 18 PM Page 6

• • • • • N U C L I D E MD A RE PORT *****

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC006GD 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  9.362E+004    9.36E+004    1.002E+006    3.760E+004
 +      Co-60      1173.23*    99.85   2.040E+004    9.20E+003    1.89DE+005    9.320E+003 1332.49*    99.98   9.195E+003                 2.085E+005    3.664E+003 Nb-94       702.65     99.81   2.105E+004    2.11E+004    2.672E+003    9.837E+003 871.09     99.89   2.490E+004                -3.189E+003    l .169E+004 Ag-108rn    433.90     90.50   1. 015E+005   2.68E+004    6.108E+003    5.015E+004 614.30     89.80   5.221E+004                -3.272E+004    2.538E+004 722.90     90.80   2.684E+004                 2.188E+002    l.265E+004 Cs-134      604.72     97.62   4.805E+004    2.98E+004   -1.457E+004    2.337E+004 795.86     85.46   2.981E+004                 1. 436E+O 04  1.405E+004
 +      Cs-137      661.66*    85. 10  4.435E+004    4.43E+004    1. 4 02E+O 07 2.139E+004 Eu-152      121 .78    28.67   2.827E+005    7.20E+004    6.838E+004    l.402E+005 344.28     26.60   2.976E+005                -l .584E+004   1.470E+OOS 1408.01     21. 07  7.195E+004                -3.270E+003    3.141E+004 Eu-154      123.07     40. 40  2.012E+005    5.21E+004    2.241E+OOS    9.979E+004 723.30     20.06   1. 21SE+005               -3.139E+004    5.728E+004 1274.43     34.80   5.212E+004                -4.974E+004    2.344E+004
 +      Eu-155       86.55*    30.70   3.158E+005    3.16E+OOS    9.170E+OOS    1.568E+005 105 .31    21 .10  3.877E+005                -8.234E+004    1.923E+OOS Tl-208      583.19     85.00   5.479E+004    5.48E+004   -1.145E+003    2.666E+004 Bi-212      727.33      6.67   3.900E+005    3.90E+OOS    4.493E+005    1 .845E+OOS Pb-212      238.63     43.60   1.776E+005    1.78E+005    7.673E+004    8.786E+004
 +      Bi-214      609 . 32*  45.49   7.740E+004    1. 44E+004   6.807E+004    3.729E+004 1120.29     14 . 92 1.895E+005                 2.795E+OOS    8.899E+004 1764.49*    15.30   1.441E+004                 1.278E+005    O.OOOE+OOO Pb-214      295.22     18.42   4. 304E+005   2.25E+005    5.613E+005    2.128E+005 351.93     35.60   2.253E+005                 2.822E+004    1 .113E+OOS Ra-226      186.21      3.64   2.337E+006    2.34E+006    7.368E+005    1 .159E+006 Ac-228      338.32     11. 27  6.888E+005    1. l OE+OOS -5.979E+005    3.401E+005 911. 20    25.80   l.097E+005                 9.579E+004    5.182E+004 968.97     15 .80  1. 871E+005                1.968E+005    8.850E+004 Am-241       59.54     35.90   2.269E+005    2.27E+005    1.085E+005    1 .124E+OOS
       +=Nuclide identified during the nuclide i dentification
       *=Energy line found in the spectrum
       > ~ Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @=Half-life too short to be able to perform the decay correction

[131]

• • • • • GAMMA S P E C T R U M ANALYSIS *****

Filename: 5456-A Report Generated On 6/1/2018 3:10:49 PM Sample Title B103202AFSWC007GD Sample Description SFP/TRANSFER CANAL Sample Identification 007 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/1/2018 3: 00 :00 PM Acquisition Started 6/1/2018 3:00:47 PM Live Time 600 , 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [132]

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

Detector Name: 5456-A Sample

Title:

B103202AFSWC007GD Peak Analysis Performed on: 6/1/2018 3: 10 :48 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- 307 301.19 75.30 1. 03 3.62E+002 105.91 6.51E+002 2 332- 346 340.61 85.15 0.70 5.59E+001 74.63 4.62E+002 3 947- 960 955.34 238.84 0.59 3.48E+001 38.80 1 .24E+002 4 1401- 1414 1407.54 351.88 0.99 3.40E+001 25.99 4.90E+001 5 2430- 2446 2437.51 609.38 1. 09 5.62E+001 23.66 2.68E+001 6 2637- 2656 2646.21 661.55 1.20 2.97E+002 38.71 2.23E+001 7 4684- 4702 4692.69 1173 .17 1. 61 9.06E+001 22.71 1.14E+001 8 5323- 5339 5330.83 1332 .71 0.82 7.07E+001 20. 86 1. 23E+001 9 5833- 5854 5843.96 1460.99 1. 52 1.39E+002 24.48 2.79E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [133]

Interference Corrected Activity Report 6/1/2018 3: 10 :49 PM Page 3

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• Sample

Title:

Bl03202AFSWC007GD 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 9.48213E+005 l .85964E+005 Co-60 1.000 1173.23* 99.85 5.87633E+004 l .54670E+004 1332.49* 99.98 4.87627E+004 l.49070E+004 Cs-137 1. 000 661.66* 85.10 1. 72269E+005 3.05467E+004 Eu-155 0.346 86.55* 30.70 4.38543E+004 5.91586E+004 105.31 21.10 Pb-212 1 .000 238.63* 43.60 2.39432E+004 2.69569E+004 Bi-214 0 .438 609.32* 45.49 5.86593E+004 2.57004E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.439 295.22 18.42 351.93* 35.60 3.46879E+004 2.70866E+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

[134]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 9.482127E+005 1 .859644E+005 Co-60 1. 000 5.357870E+004 l .073334E+004 Cs-137 1. 000 1. 722689E+005 3.054670E+004 Eu-155 0 .346 4. 385427E+004 S.91586SE+004 Pb-212 1.000 2.394323E+004 2.695686E+004 Bi-214 0 .438 5.865935E+004 2.S70036E+004 Pb-214 0 .439 3.468790E+004 2.7086SBE+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

[135]

Interference Corrected Activity Report 6/1/2018 3: 10 : 49 PM Page 5

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Peak Locate Performed on: 6/1/2018 3: 10 :48 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 75.30 6.0276E-001 29.29 M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2. 000 sigma [136]

Nuclide MDA Report 6/1/2018 3:10:49 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC007GD 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  9.143E+004    9.14E+004   9.482E+005    3.650E+004
 +      Co-60      1173.23*    99.85   1. 498E+004   l .50E+004  5.876E+004    6.610E+003 1332.49*    99.98   l .587E+004                4 .876E+004  7.002E+003 Nb-94       702.65     99.81   1. 709E+004   1 .71E+004 -6.817E+003    7.855E+OD3 871.09     99.89   l .721E+004               8.663E+003    7.843E+003 Ag-108m     433.90     90.50   2.274E+004    2.06E+OD4  -2.287E+OD4    1.077E+004 614. 3 0   89.80   3.015E+004                1. 2 OOE+O 03 1.436E+OD4 722.90     90.80   2.056E+004                1. 038E+004   9.512E+OD3 Cs-134      604.72     97.62   2.913E+004    2.16E+OD4  -4.117E+OD3    1.391E+004 795.86     85.46   2.158E+004                1. 223E+O 04  9.938E+003
 +      Cs-137      661.66*    85.10   l.843E+004    l.84E+004   1. 723E+O 05  8.430E+003 Eu-152      121.78     28.67   1.094E+005    8.11E+004  -6.228E+004    5.356E+004 344.28     26.60   8.190E+004               -3.430E+004    3.912E+D04 1408.01     21. 07  8.110E+004                4.111E+004    3.598E+004 Eu-154      123.07     40. 40  7. 739E+D04   4.94E+OD4  -2.431E+D04    3.789E+004 723.30     20.06   9.140E+OD4                2.677E+004    4.223E+D04 1274.43     34.80   4.944E+D04               -l.854E+004    2.210E+004
 +      Eu- 155      86.55*    30.70   9.641E+004    9.64E+004   4.385E+004    4.714E+004 105.31     21.10   1. 580E+OD5               7.920E+004    7.749E+004 Tl-208      583.19     85.00   2.695E+004    2.70E+004   l.620E+004    1.274E+004 Bi-212      727.33      6.67   2.625E+005    2.63E+005  -6.394E+004    l.208E+005
 +      Pb-212      238.63*    43.60   4.367E+OD4    4.37E+004   2.394E+004    2.090E+004
 +      Bi-214      609.32*    45.49   3.428E+004    3.43E+004   5.866E+004    l.573E+004 112 0 .29   14.92   1.722E+005                2.125E+004    8.033E+004 1764.49     15. 30  1.407E+OD5                9.776E+004    6.314E+004
 +      Pb-214      295.22     18.42   1. 319E+005   4.17E+004   7.15DE+004    6.349E+004 351.93*    35.60   4.173E+004                3.469E+004    l.949E+004 Ra-226      186.21      3.64   7.715E+005    7.71E+005   7.202E+OOS    3.758E+005 Ac-228      338.32     11. 27  1 .974E+005   8.70E+OD4   l.659E+005    9.445E+004 911. 2 0   25.80   8.698E+D04                8.827E+004    4.048E+D04 968.97     15.80   1 .441E+005               l.420E+OOS    6.698E+004 Am-241       59 . 5 4  35.90   9.759E+004    9.76E+004  -7.162E+003    4 .772E+004
       + = Nuclide identified during the nuclide identification
       * ~ Energy line found in the spectrum
       >=Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @ = Half-life too short to be able to perform the decay correction

[137]

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

Filename: 5456-A Report Generated On 6/1/2018 3 ~27:43 PM Sample Title B103202AFSWC008GD Sample Description SFP/TRANSFER CANAL Sample Identification 008 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/1/2018 3:17:00 PM Acquisition Started 6/1/2018 3:17:42 PM Live Time 600.0 seconds Real Time 600. 4 seconds Dead Time 0 . 07  % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [138]

Peak Analysis Report 6/1/2018 3:27:43 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSWC008GD Peak Analysis Performed on: 6/1/2018 3:27:43 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 1 126- 135 130.60 32.65 0.80 2.45E+001 21.10 3.05E+001 2 282- 308 301.89 75.47 0.92 3.19E+002 125.59 8.27E+002 3 334- 346 340.84 85.21 0.57 8.0lE+OOl 66.25 3.84E+002 4 365- 375 370.20 92.55 0.33 1.78E+001 50. 64 2.61E+002 5 949- 960 955.68 238.92 0.96 5.29E+001 30.78 7.31E+001 6 1177- 1188 11 8 1. 25 295.31 1.14 3.40E+001 24.45 4.60E+001 7 1400- 1415 1408.17 352. 04 1.43 5.23E+001 25.36 3.57E+001 8 1751- 1762 1756.88 439.22 0 .36 9.00E+OOO 16.63 2.40E+001 9 2432- 2444 2437.83 609.46 0 .34 3.48E+001 21. 86 3.22E+001 10 2636- 2655 2646.20 661.55 1.35 2.65E+002 36.17 1 .75E+001 11 3637- 3650 3643.45 910.86 1. 40 2.77E+001 13.19 5.34E+OOO 12 4475- 4488 4481.29 1120.32 1. 66 2.61E+001 14.29 8.90E+OOO 13 4684- 4702 4692.81 1173.20 1. 06 1.20E+002 24.07 7.29E+OOO 14 5321- 5341 5330.46 1332.62 0 .95 1.16E+002 24.81 1.05E+001 15 5834- 5854 5844.68 1461. 17 1. 90 1.48E+002 24.33 O.OOE+OOO 16 7053- 7068 7060.09 1765.02 0 .33 1.90E+001 8.72 O.OOE+OOO 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 [139]

Interference Corrected Activity Report 6/1/2018 3: 27: 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 REPORT *****

Sample

Title:

B103202AFSWC008GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB

  * * * * * * * * * * * * * * *

• I I *
• IDENTIFIED NUCLIDES ...... . .......... . ... ... . .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 1 .00814E+006 1.87436E+005 Co-60 1.000 1173.23* 99.85 7.76857E+004 1.68119E+004 1332.49* 99.98 7.96601E+004 1 .82587E+004 Ag-108rn 0.466 433.90* 90.50 4.03183E+003 7.47408E+003 614.30* 89.80 1.84324E+004 1 .17792E+004 722.90 90.80 Cs-137 1.000 661.66* 85.10 1.54122E+005 2.79904E+004 Eu-155 0.346 86.55* 30.70 6.27683E+004 5.34176E+004 1 05.31 21.10 Pb-212 1 .000 238.63* 43.60 3.63835E+004 2.19696E+004 Bi-214 1 .000 609.32* 45.49 3.63867E+004 2.32543E+004 1120.29* 14 .92 1.10938E+005 6.13952E+004 1764.49* 15.30 1.01152E+005 4.71138E+004 Pb-214 1 .000 295.22* 18 .42 6.14933E+004 4.52875E+004 351.93* 35.60 5.33773E+004 2.72502E+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 a t                 2.000 sigma

[140]

Interference Correcte d Activity Report 6/1/2018 3: 27 :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/MA2 ) Uncertainty K-40 1.000 1 .008138E+006 1. 874364E+OO 5 . Co-60 1. 000 7.859161E+004 1. 236770E+004 Ag-108m 0.466 1. 253944E+002 7.086596E+003 Cs-137 1.000 1. 541219E+O 05 2.799037E+004 Eu-155 0.346 6.276833E+004 5.341756E+004 Pb-212 1.000 3.638346E+004 2.196957E+004 Bi-214 1. 000 5.529315E+004 2.217061E+004 Pb-214 1.000 5.553470E+004 2.334916E+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 a t 2. 000 sigma

[141]

Interference Corrected Activity Report 6/1/2018 3: 27 :43 PM Page 5

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

Peak Locate Performed on: 6/1/20 18 3: 27: 43 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 32.65 4.0848E-002 86.08 2 75.47 5.3115E-001 39.41 4 92.55 2.9583E-002 285.29 D-Esc. 11 910.86 4.6098E-002 47.69 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [142]

N~clide MDA Report 6/1/2018 3:27:43 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC008GD 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   1.843E+004       1. 84E+004     1.008E+006   O.OOOE+OOO
 +      Co-60      1173.23*   99.85   1. 246E+O 04     1. 25E+004     7.769E+004   5.353E+003 1332.49*   99.98   1.592E+004                      7.966E+004   7.028E+003 Nb-94       702. 6 5  99.81   1.862E+004       1 .86E+004     4.293E+003   8.621E+003 871. 0 9  99.89   1 .982E+004                     3.354E+002   9.151E+003
 +      Ag-108m     433.90*   90.50   1 .264E+004      1 .26E+004     4.032E+003   5.715E+003 614.30*   89.80   1 .745E+004                     l.843E+004   8.010E+003 722.90    90.80   2.513E+004                      2.254E+004   1.180E+004 Cs-134      604. 7 2  97.62   2.830E+004       2.14E+004     -6.676E+002   1.349E+004 795.86    85.46   2.136E+004                      1.506E+004   9.830E+003 Cs-137      661.66*   85. 10  1 .655E+004      1.66E+004      1 . 541E+005 7.492E+003 Eu-152      121.78    28.67   1 .103E+005      7.80E+004      7.090E+004   5.402E+004 344.28    26.60   7.802E+004                     -1 .536E+003  3.718E+004 1408. 01   21. 07  8.110E+004                      4.561E+004   3.598E+004 Eu-154      123. 07   40.40   7.754E+004       4 .56E+004     4.776E+004   3.797E+004 723.30    20.06   1.151E+005                      1. 424E+O 05 5.408E+004 1274.43    34.80   4.559E+004                      8.434E+003   2.017E+004
 +      Eu-155       86.55*   30.70   8.436E+004       8.44E+004      6.277E+004   4 .112E+004 105.31    21.10   1.553E+005                     -2.767E+004   7.614E+004 Tl-208      583.19    85.00   2.771E+004       2.77E+004      1.203E+004   1.311E+004 Bi-212      727.33     6.67   3.265E+005       3.27E+005      2.496E+005   1 .528E+005
 +      Pb-212      238.63*   43.60   3.255E+004       3.25E+004      3.638E+004   1 .534E+004
 +      Bi-214      609.32*   45.49   3.445E+004       1 . 4 4E+004   3.639E+004   1 .581E+004 1120.29*   14 .92  8.138E+004                      l .109E+005  3.494E+004 1764.49*   15.30   l.441E+004                      1 .012E+005  O.OOOE+OOO
 +      Pb-214      295.22*   18.42   6.880E+004       3.77E+004      6.149E+004   3.196E+004 351.93*   35.60   3.772E+004                      5.338E+004   1.748E+004 Ra-226      186.21     3.64   7.328E+005       7.33E+005     -2.808E+004   3.565E+005 Ac-228      338.32    11.27   1.825E+005       9.46E+004      1.016E+003   8.700E+004 911. 20   25. 80  9.458E+004                      8.309E+004   4.428E+004 968.97    15.80   l.359E+005                     -1.874E+004   6.288E+004 Am-241       59. 5 4  35.90   1.001E+005       1 . 0 0E+005   3.002E+004   4.896E+004
       + - Nuclide identified during the nuclide identification
       * ~ Energy line found in the spectrum
       >=Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @ ; Half-life too short to be able to perform the decay correction

[143]

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

Filename: 5456-A Report Generated On 6/1/2018 2:52: 11 PM Sample Title B103202AFSWC009GD Sample Description SFP/TRANSFER CANAL Sample Identification 009 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/1/2018 2: 41: 00 PM Acquisition Started 6/1/2018 2:42:09 PM Live Time 600 . 0 seconds Real Time 601.1 seconds Dead Time 0 . 17 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [144]

Peak Analysis Report 6/1/2018 2:52: 11 PM Page 2

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

Detector Name: 54 56-A Sample

Title:

B1 0 3202AFSWC009GD Peak Analysis Performed on: 6/1/2018 2:52: 11 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 1 126- 136 129.66 32.42 0.78 1. 78E+002 50. 01 l.53E+002 2 286- 311 3 01. 42 75.36 1. 04 1. 77E+003 185.03 1.60E+003 3 331- 346 340.61 85.15 1. 06 3.13E+002 124.59 1.19E+003 4 2162- 2173 2167.87 541.97 0.51 6.38E+OOO 23.75 5.36E+001 5 2429- 2444 2436.63 609.16 1. 23 4.09E+001 29.18 5.51E+001 6 2634- 2657 2646.15 661.54 1.49 3.25E+003 117 .79 5.43E+001 7 4682- 4703 4692.58 1173.14 1.45 1.68E+002 27.38 5.33E+OOO 8 5320- 5341 5330. 18 1332.54 1. 77 1.43E+002 25. 35 4.97E+OOO 9 5833- 5856 584 4 .48 1461.12 1. 52 1 .38E+002 23.49 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 [145]

Interference Corrected Activity Report 6/1/2018 2:52:11 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:

B103202AFSWC009GD 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 9.40001E+005 l.79651E+005 Co-60 1 .000 1173.23* 99. 85 1.08810E+005 l.97847E+004 1332 . 49* 99.98 9.86425E+004 l.91806E+004 Cs-137 1.000 661.66* 85.10 1.88731E+006 2.36744E+005 Eu-155 0.346 86.55* 30.70 2.45706E+005 l .09336E+005 105.31 21.10 Bi-214 0.438 609.32* 45.49 4.27628E+004 3. 09022E+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

[146]

Interference Corrected Activity Report 6/1/2018 2: 52: 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 9.400012E+005 1.796509E+005 Co-60 1 .000 1 .035688E+005 1.377134E+004 Cs-137 1. 000 l .887314E+006 2.367441E+005 Eu-155 0 .346 2.457058E+005 1.093362E+005 Bi-214 0 .438 4.276279E+004 3.090219E+0 04

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

• Peak Locate Performed on: 6/1/2018 2:52: 11 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.42 2.9680E-001 28.08 2 75.36 2.9459E+OOO 10.47 4 541. 97 1.0639E-002 372.00 M ~ First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [147]

Nuclide MDA Report 6/1/2018 2:52: 11 PM Page 5

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC009GD 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 .843E+004    1 .84E+004   9.400E+005  O.OOOE+OOO
 +      Co-60      1173.23*  99.85   1 .124E+004    l .12E+004   1.088E+005  4.740E+003 1332.49*  99.98   1 .139E+004                 9.864E+004  4.760E+003 Nb-94       702.65   99.81   l .957E+004    1 .96E+004   4.859E+003  9.096E+003 871.09   99.89   2.177E+004                 -1.253E+003  1. 013E+004 Ag-108m     433.90   90.50   4.940E+004     2.42E+004    4.215E+004  2.410E+004 614.30   89.80   3.784E+004                  6.972E+003  1.820E+004 722.90   90.80   2.423E+004                  7.978E+003  1.135E+004 Cs-134      604.72   97.62   3.501E+004     2.59E+004    1.638E+004  1.685E+004 795.86   85.46   2.587E+004                  1.290E+004  1. 208E+004
 +      Cs-137      661.66*  85.10   2.978E+004     2.98E+004    1.887E+006  l.410E+004 Eu-152      121 .78  28.67   1. 821E+005    6.79E+004   -8.901E+004  8.995E+004 344.28   26.60   1. 721E+005                 6.188E+004  8.420E+004 1408.01   21. 07  6.790E+004                 -5.907E+003  2.938E+004 Eu-154      123.07   40. 40  l.291E+005     5.21E+004   -7.861E+004  6.376E+004 723.30   20.06   l.lllE+OOS                  5.904E+004  5.206E+004 1274.43   34.80   5.212E+004                 -2.334E+002  2.344E+004
 .,     Eu-155       86.55*  30.70   1.562E+005     1.56E+005    2.457E+005  7.702E+004 105.31   21.10   2.544E+005                  l.294E+005  1.257E+005 Tl-208      583.19   85.00   3.918E+004     3.92E+004    3.654E+004  1.885E+004 Bi-212      727.33    6.67   3.157E+005     3.16E+005   -8.561E+004  1 .474E+005 Pb-212      238.63   43.60   1. 0 97E+005   1.10E+005    2.884E+004  5.393E+004
 +      Bi-214      609.32*  45.49   4.787E+004     4 .79E+004   4.276E+004  2.252E+004 1120.29   14.92   1.709E+005                  1.784E+005  7.972E+004 1764.49   15.30   1.357E+005                  8.012E+004  6.066E+004 Pb-214      295.22   18.42   2.369E+005     1.30E+005   -9.562E+004  1. 16 OE+005 351.93   35.60   1.299E+005                  8.692E+004  6.356E+004 Ra-226      186.21    3.64   1.401E+006     1 .4 0E+006  6.268E+005  6.904E+005 Ac-228      338.32   11.27   4.051E+005     9.87E+004    l .284E+005 1. 983E+005 911.20   25.80   9.873E+004                  6.698E+004  4.635E+004 968.97   15.80   1 .622E+005                 4.421E+004  7.602E+004 Am-241       59 .54  35.90   1. 512E+005    1.51E+005    5.126E+004  7.451E+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

[148]

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

Filename: 5456-A Report Generated On 6/1/2018 2:33:48 PM Sample Title B103202AFSWC010GD Sample Description SFP/TRANSFER CANAL Sample Identification 010 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA 2 Sample Taken On 6/1/2018 2:23: 00 PM Acquisition Started 6/1/2018 2:23:46 PM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0.08 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [149]

Peak Analysis Report 6/1/2018 2:33:48 PM Page 2

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

Detector Name: 5456-A Sample

Title:

Bl03202AFSWC010GD Peak Analysis Performed on: 6/1/2018 2:33:47 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 135 130.52 32.63 1. 05 4.30E+001 26. 02 4 .50E+001 2 287- 308 301.50 75.37 1.12 4.90E+002 115.87 7.64E+002 3 334- 346 34 0 .78 85.19 1. 05 1.18E+002 73.60 4.69E+002 4 986- 1023 1018.88 254.72 0.91 1. 4 8E+001 82.91 2.95E+002 5 1399- 1416 1407.35 351.84 0.99 7.85E+001 32.18 5.SSE+OOl 6 2431- 2444 2437.34 609.34 0.28 3.62E+001 22.09 3.08E+001 7 2636- 2657 2645.93 661. 48 1. 52 5.08E+002 50.77 3.60E+001 8 3868- 3881 3874.62 968.66 0.70 1. 75E+001 13.62 1.0SE+OOl 9 4683- 4703 4692.66 1173.17 1. 10 l. 58E+002 27. 40 8.0SE+OOO 10 5321- 5341 5330.91 1332.73 1. 90 l. 34E+OD2 23.15 O.OOE+OOO 11 5834- 5855 5844.79 1461. 20 0.65 1. 19E+002 22.71 2.61E+OOO 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 [150]

• Interference Corrected Activity Report 6/1/2018 2:33:48 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:

B103202AFSWC010GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• I * *
• IDENTIFIED NUCLIDES
• l .. ............ .. .. .. Ii ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1. 000 1460.82* 10 .66 8.13273E+005 l .70023E+005 Co-60 1. 000 11 73.23* 99.85 l.02499E+005 l.95835E+004 1332.49* 99.98 9.24239E+004 1.75972E+004 Cs-137 1 . 000 661.66* 85.10 2.94927E+005 4.60792E+004 Eu-155 0 .346 8 6.55* 30.70 9.24142E+004 6.05740E+004 10 5. 31 21.10 Bi-214 0 .438 609.32* 45.49 3.78292E+004 2.35186E+004 1120.29 14.92 1764.49 15.30 Pb-214 0 .439 295.22 18.42 351.93* 35.60 8.01268E+004 3.52407E+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

[151]

Interference Corrected Activity Report 6/1/2018 2:33:48 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 1.00 0 8.132730E+005 1.700231E+005 Co-60 1. 00 0 9.692489E+004 1.30891BE+004 Cs-137 1. 000 2.949269E+005 4.607916E+004 Eu-155 0.346 9.241422E+004 6.057396E+004 Bi-214 0.438 3.782922E+004 2.351856E+004 Pb-214 0.439 8.012675E+004 3.524066E+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

[152]

Interference Corrected Activity Report 6/1/20 18 2:33 :48 PM Page 5

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

Peak Locate Performed on: 6/1/2018 2:33 :47 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol . No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.63 7.1638E-002 60.53 2 75.37 8. 1595E-001 23.67 4 254.72 2.4704E-002 559.33 8 968.66 2.9167E-002 77.84 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [153]

Nuclide MDA Report 6/1/2018 2: 33 : 48 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC010GD 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   8.746E+004      8.75E+004    8.133E+OOS     3.452E+004
 +      Co-60      1173.23*    99.85   1. 341E+O 04    l .87E+003   1.025E+005     5.828E+003 1332.49*    99.98   1. 8 66E+O 03                9.242E+004     O.OOOE+OOO Nb-94       702.65     99.81   1. 779E+004     1 .78E+004   8.288E+003     8.204E+003 871.09     99.89   2.055E+004                  -2.836E+004     9.517E+003 Ag-108m     433.90     90.50   2.758E+004      2.34E+004    3.546E+002     l. 319E+004 614.30     89.80   2.972E+004                  -5.814E+003     l. 414E+004 722.90     90.80   2.345E+004                   1. 269E+004    l.096E+004 Cs-134      604.72     97.62   2.932E+004      2.26E+004    5.787E+002     l.400E+004 795.86     85.46   2.263E+004                   6.141E+003     1.046E+004
 +      Cs-137      661.66*    85.10   2.388E+004      2.39E+004    2.949E+005     l.116E+004 Eu-152      121.78     28.67   l .283E+005     8.28E+004   -2.172E+002     6.301E+004 344.28     26.60   9.516E+004                  -1.513E+004     4.57SE+004 1408.01     21.07   8.280E+004                  -9.973E+002     3.683E+004 Eu-154      123.07     40.40   9.035E+004      4.66E+004    3.910E+003     4.437E+004 723.30     20.06  1.069E+OOS                    7.437E+004     4.996E+004 1274.43     34.80   4.658E+004                   2.654E+004     2.067E+004
 +      Eu-155       86. 5 5*  30.70   9.279E+004      9.28E+004    9.241E+004     4.533E+004 105.31     21.10   l.767E+005                  -l.187E+005     8.683E+004 Tl-208      583.19     85.00   2.605E+004      2.60E+004    9.034E+003     1.228E+004 Bi-212      727.33      6.67   3.045E+005      3.0SE+OOS    1.285E+005     l.418E+OOS Pb-212      238.63     43.60   6.484E+004      6.48E+004    l.988E+004     3.149E+004
 +      Bi-214      609.32*    45.49   3.466E+004      3.47E+004    3.783E+004     1 .591E+004 1120.29     14.92   l.499E+005                   4.196E+004     6.922E+004 1764.49     15.30   l.382E+005                   l .331E+005    6.192E+004
 +      Pb-214      295.22     18.42   l.491E+005      4.78E+004    2.424E+004     7.210E+004 351.93*    35.60   4.783E+004                   8.013E+004     2.253E+004 Ra-226      186.21      3.64   9.003E+005      9.00E+OOS    3.614E+005     4.403E+OOS Ac-228      338.32     11.27   2.401E+005      8.50E+004    l.404E+005     1.158E+005 911. 20    25.80   8.496E+004                   1. 775E+004    3.947E+004 968.97     15.80  1.486E+005                    2.848E+004     6.921E+004 Am-241       59.54     35.90   l.136E+005      l. 1 4E+005 -6.786E+003     5.571E+004
       +=Nuclide identified during the nuclide i dentification
       *=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 A N A L Y S I S *****

Filename: 5456-A Report Generated On 6/4/2018 1:31:37 PM Sample Title B103202AFSWC011GD Sample Description SFP/TRANSFER CANAL Sample Identification 011 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/4/2018 1: 20:00 PM Acquisition Started 6/4/2018 1: 21 :35 PM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [155]

Peak Analysis Report 6/4/2018 1:31 :37 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B1 03202AFSWC011GD Peak Analysis Performed on: 6/4/2018 1 :31:37 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 284- 311 3 01. 13 75.28 0.98 5.65E+002 135.46 8.93E+002 2 334- 347 338.75 84.69 0.89 6.36E+001 77.38 5.12E+002 3 1174- 1186 1181. 21 295.30 0.37 1.92E+001 24.94 5.18E+001 4 1401- 1413 1407 .36 351.84 0.37 4 .95E+001 23.25 3.25E+001 5 2426- 2445 2436.19 609.05 0.67 8.36E+001 22.54 1.24E+001 6 2636- 2654 2645.11 661.28 1. 66 1 .41E+002 31.18 3.0SE+OOl 7 3637- 3650 3643.39 910 .85 0 .45 1 .52E+001 15.36 1.58E+001 8 4681- 4701 4691.51 1172.88 1 .56 1.57E+002 27.29 7.95E+OOO 9 5318- 5339 5328.70 1332.18 1. 20 1.64E+002 28.57 1 .07E+001 10 5832- 5853 5842.26 1460.57 1. 35 1.33E+002 24.75 5.50E+OOO 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 [156]

Interference Corrected Activity Report 6/4/2018 1: 31: 37 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:

B103202AFSWC011GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * *  * * * '" *

• t *
• 4 a
• I
• t
• IDENTIFIED NUCLIDES .. ............. t ' * * ' ! '

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10 .66 9.02333E+005 l .85877E+OOS Co-60 1.000 1173.23* 99.85 1.01903E+005 l .94930E+004 1332.49* 99.98 1.13273E+005 2.16863E+004 Cs-137 1 .000 661.66* 85.10 8.15563E+004 2.05813E+004 Eu-155 0.344 86.55* 30.70 4.99376E+004 6.16184E+004 105.31 21. 10 Bi-214 0.438 609.32* 45.49 8.72804E+004 2.57661E+004 11 20.29 14.92 1764.49 15.30 Pb-214 1.000 295.22* 18.42 3.47678E+004 4. 542 70E+004 351.93* 35.60 5.04984E+004 2.50556E+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

[157]

Interference Corrected Activity Report 6/4/2018 1 : 31: 3 7 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1.000 9.023325E+005 1. 858768E+OOS Co-60 1.000 1.069838E+OOS 1.449723E+004 Cs-137 1.000 8.l55633E+004 2.058134E+004 Eu-155 0.344 4.993763E+004 6. 161 844E+004 Bi-214 0.438 8.728041E+004 2.576608E+004 Pb-214 1 .000 4.682914E+004 2.193966E+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

[158]

Interference Corrected Activity Report 6/4/2018 1 : 31: 37 PM Page 5

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

Peak Locate Performed on: 6/4/201 8 1:31:37 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 9.4162E-001 23.98 7 910.85 2.5296E-002 101 .21 Sum M ~ First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [159]

Nuclide MDA Report 6/4 /20 18 1:3 1:37 PM Page 6

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

Detector Name: 5456-A Sample Geometry : Sample Title : B103202AFSWC011GD 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 .202E+005      1 .20E+005    9.023E+OOS   S.091E+004
 +      Co-60       1173.23*    99.85   1.327E+004       l.33E+004     l.019E+OOS   5.759E+ 003 1332. 4 9*  99.98   1. 618E+004                    l.133E+005   7.158E+003 Nb-94        702.65     99.81   1.796E+004       l.80E+004   -7.106E+003    8.289E+003 871.09     99.89   2.055E+004                     2.762E+003   9.517E+003 Ag-108m      433.90     90.50   2.284E+004       2.28E+004     1. 184E+004  1.082E+004 614.30     89.80   2.972E+004                   - 1.799E+004   1.414E+004 722.90     90.80   2.280E+004                     l.781E+004   l .063E+004 Cs-134       604.72     97.62   2.634E+004       2.42E+00 4  -4.463E+003    1 .251E+0 04 795.86     85.46   2.422E+004                   -5.231E+002    l.126E+004
 +      Cs-137       661.66*    85.10   2.092E+004       2.09E+004     8.156E+004   9.673E+003 Eu-152       121.78     28 .6 7 l.208E+005       8. 1 1E+004   4.840E+004   5.927E+004 344.28     26.60   8.114E+004                   -7 . 564E+004  3.874E+004 1408. 01    21.07   8 . 921E+004                   3.460E+004   4.004E+004 Eu-154       123.07     40.40   8.366E+004       4.76E+004   -4.423E+ 004   4.103E+004 723.30     20.06   1.025E+005                     4.596E+004   4.778E+004 1274.43     34.80   4.756E+004                     1.309E+004   2.116E+004
 +      Eu-155        86.55*    30.70   1. OOOE+005      1. OOE+005    4.994E+OD4   4.894E+004 105 .31    21.10   1.760E+005                   -2.648E+004    8.647E+004 Tl-208       583.19     85.00   2.844E+004       2.84E+004     2.398E+004   1 .348E+004 Bi- 2 12     727.33      6.67   2.952E+005       2.95E+005   -l.028E+OOS    1.371E+OOS Pb-212       238.63     43.60   6.692E+004       6.69E+004     2.446E+004   3.253E+004
 +      Bi-214       609.32*    45.49   2.545E+004       2.55E+004     8.728E+004   l.131E+004 1120.29     14.92   l .709E+OOS                    1.D20E+OOS   7.972E+004 1764.49     15.30   l.588E+OOS                     1.810E+OOS   7.220E+004
 +      Pb-214       295.22*    18.42   7 . 432E+004     3.38E+004     3.477E+004   3.471E+004 351.93*    35.60   3.382E+004                     S . OSOE+004 1. 553E+C04 Ra-226       186 . 21    3.64   8.628E+005       8.63E+005     8.115E+OOS   4.215E+OOS Ac-228       338.32     11.27   l.934E+OOS       9. 76 E+004 -1.141E+005    9.242E+004 911 .20    25.80   9.757E+004                    5 . 284E+002  4.577E+004 968.97     15.80   1 .540E+OOS                  -1.218E+004    7.191E+004 Am-241        59.54     35.90   1. 085E+005      1.08E+005    7.822E+004    S.316E+004
       +=Nuclide identified during the nuclide ident ification
       *=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

[160]

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

Filename: 5456-A Report Generated On 6/4/2018 10 :44:19 AM Sample Title B103202AFSWC012GD Sample Description SFP/TRANSFER CANAL Sample Identification 012 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/4/2018 10 :33: 00 AM Acquisition Started 6/4/2018 10 :34: 18 AM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [161]

Peak Analysis Report 6/4/2018 10:44:19 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSWC012GD Peak Analysis Performed on: 6/4/2018 10:44:19 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 1 286- 311 301.07 75.27 0 .92 5.12E+002 128.58 8.52E+002 2 333- 346 341.23 85.31 0 .57 6 . 59E+001 77.49 5.21E+002 3 948- 960 955.44 238.86 0 .52 2.04E+001 38.29 1 .31E+002 4 1397- 1416 1407.96 351.99 1. 11 6.63E+001 32.12 5.47E+001 5 2326- 2337 2331.36 582.84 0 .80 2.83E+001 16.87 l.68E+001 6 2427- 2444 2435.60 608.90 1. 35 6.86E+001 23.78 2.24E+001 7 2637- 2655 2645.44 661.36 1.41 1. 84E+O 02 30 .34 l.38E+001 8 4473- 4486 4479.40 1119 .85 0.40 2.54E+001 12.93 ~.57E+OOO 9 4682- 4702 4692.06 1173 .02 1. 11 7.83E+001 20.60 7.73E+OOO 10 5319- 5338 5329.15 1332.29 1. 11 6.68E+001 22.10 l.52E+001 11 5831- 5852 5842.37 1460.59 1. 60 1. 42E+002 27.06 1.09E+001 M = First peak in a multiplet region m Other peak in a multiplet region F "' Fitted singlet Errors quoted at 2 . 000 sigma [162]

Interference Corrected Activity Report 6/4/2018 10:44:20 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:

B103202AFSWC012GD 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 14 60.82* 10.66 9.67595E+005 2.02513E+005 Co-60 1.000 11 73.23* 99.85 5.07884E+004 1.39709E+004 1332.49* 99.98 4.60357E+004 l.56817E+004 Cs-137 1.000 661.66* 85.10 1 .06922E+005 2.17986E+004 Eu-155 0.346 86.55* 30.70 5.15998E+004 6.15699E+004 1 05.31 21. 10 Tl-208 1. 000 583.19* 85.00 1 .54620E+004 9.41933E+003 Pb-212 1. 000 238.63* 43.60 l.40118E+004 2.64210E+004 Bi-214 0.733 609.32* 45.49 7.16639E+004 2.62794E+004 1120.29* 14 .92 1.08058E+005 5.56175E+004 1764.49 15.30 Pb-214 0.439 295.22 18.42 351.93* 35.60 6.76828E+004 3.45141E+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

[163]

Interference Corrected Activity Report 6/4/2018 10:44:20 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 9.675946E+OOS 2.025128E+OOS Co-60 1.000 4 .868536E+004 1. 043 155E+004 Cs-137 1.000 1. 06921 7E+O 05 2.179863E+004 Eu-155 0.346 5.159983E+004 6.156988E+004 Tl-208 1.000 1. 546198E+004 9.419334E+003 Pb-212 1.000 1.4011BOE+004 2.642096E+004 Bi-214 0.733 7.830619E+004 2.376058E+004 Pb-214 0.439 6.768283E+004 3.451414E+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

[164]

Interference Corrected Activity Report 6/4/2018 10 :44:20 AM Page 5

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

Peak Locate Performed on: 6/4/2018 10 :44: 19 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 75.27 8.5394E-001 25.10 M ~ First peak in a multiplet region m ~ Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [165]

Nuclide MDA Report 6/4/2018 10 :44:20 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC012GD 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/M2 ) (pCi/M"2 )

 +       K-40      1460.82*   10 .66  1.618E+005    1.62E+005  9.676E+005   7.168E+004
 +       Co-60     1173.23*   99.85   1.302E+004    l.30E+004  5.079E+004   S.630E+003 1332.49*   99.98   1.875E+004               4.604E+004   8.443E+003 Nb-94       702.65    99.81   1.862E+004    1.86E+004  1.018E+003   8.621E+003 8 71. 09  99.89   1.925E+004               7.320E+003   8.866E+003 Ag-108m     433.90    90.50   2.381E+004    2.25E+004  2.692E+004   1.130E+004 614.30    89.80   2.885E+004              -1.606E+004   1.370E+004 722.90    90.80   2.247E+004               l.713E+004   1.047E+004 Cs-134     604.72    97.62   2.801E+004    2.46E+004  1.443E+003   l.33SE+004 795.86    85.46   2.459E+004               3.009E+004   1.144E+004
 +       Cs-137     661. 66*  85. 10  1 .453E+004   l.4SE+004  1.069E+OOS   6.478E+003 Eu-152     121.78    28.67   1 .218E+005   7.77E+004  7.972E+004   5.978E+004 344.28    26.60   7.775E+004              -3.193E+004   3.705E+004 1408. 0 1  21. 07  8.110E+004               5.260E+004   3.598E+004 Eu-154     123. 0 7  40 .40  8.504E+004    S.04E+004 -1.702E+004   4.172E+004 723.30    20.06   1.002E+OOS               2.054E+004   4.664E+004 1274.43    34.80   5.035E+004               2.055E+003   2.25SE+004
 +       Eu-155       86.55*  30.70   9.975E+004    9.98E+004  5.160E+004   4.882E+004 105. 31   21.10   1.688E+005              -4.611E+004   8.288E+004
 +       Tl-208     583.19*   85.00   1. 328E+004   1.33E+004  1.546E+004   5.898E+003 Bi-212     727.33     6.67   3.068E+005    3.07E+005  2.058E+003   1.429E+005
 +       Pb-212     238.63*   43.60   4 .394E+004   4.39E+004  1.401E+004   2.104E+004
 +       Bi-214     609.32*   45.49   3.212E+004    3.21E+004  7.166E+004   1.465E+004 1120.29*   14. 92  6.804E+004               1.081E+005   2.827E+004 1764.49    15. 30  1. 545E+005              l.703E+005   7.00SE+004
 +       Pb-214     295.22    18. 42  1. 379E+005   4.92E+004 -2.371E+003   6.649E+004 351.93*   35.60   4.922E+004               6.768E+004   2.323E+004 Ra-226     186.21     3.64   7.882E+005    7.88E+005 -4.321E+004   3.842E+005 Ac-228      338.32    11. 27  1 .969E+005   9.64E+004 -3.155E+004   9.416E+004 911.20    25.80   9.639E+004               1.036E+005   4.518E+004 968.97    15.80   1 .452E+005              9.471E+004   6.754E+004 Am-241        59.54   35.90   l.051E+005    l.OSE+OOS  4.006E+004   5.149E+004
       +=Nuclide identified during the nuclide identification
       *=Energy line found in the spectrum
       >    Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @=Half-life too short to be able to perform the decay correction

[166]

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

Filename: 5456-A Report Generated On 6/4/2018 12:31:37 PM Sample Title B103202AFQWC012GD Sample Description SFP/TRANSFER CANAL Sample Identification 012Q Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/4/2018 12:21: 00 PM Acquisition Started 6/4/2018 12:21:35 PM Live Time 600 . 0 seconds Real Time 600.8 seconds Dead Time 0 . 14 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [167]

Peak Analysis Report 6/4/2018 12:31:37 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B10 3202AFQWC012GD Peak Analysis Performed on: 6/4/2018 12:31:37 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 133 129.91 32.48 0 .75 l .18E+002 52.23 2.09E+002 2 296- 311 3 01. 22 75.30 0 .92 2.24E+002 106.18 8.57E+002 3 332- 346 339.19 84.80 1. 21 l .06E+002 94.98 7.47E+002 4 432- 454 443.51 110.88 0 .25 -l.22E+002 126.24 l.05E+003 s 1401- 1414 1407.79 351.95 0 .44 2.93E+001 27.90 5.97E+001 6 2327- 2339 2333.29 583.32 0 .73 2.55E+001 15.96 1. 4 5E+001 7 2427- 2444 2436.18 609 .04 1. 68 8.28E+001 24.37 2.02E+001 8 2636- 2657 2645.24 661.31 1. 35 1.55E+002 29.70 1.70E+001 9 3637- 3650 3643.55 910.89 0.81 2.06E+001 16 .11 l.44E+001 10 4683- 4701 4692.05 1173.01 1. 07 7.39E+001 22.06 1. 41E+001 11 5320- 5338 5328.75 1332.19 0 .81 8.18E+001 18.88 2.24E+OOO 12 5833- 5854 5843.08 1460.77 0 .58 l.62E+002 25.46 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 [168]

Interference Corrected Activity Report 6/4/2018 12:31:37 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:

B103202AFQWC012GD 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 1.10332E+006 l.98081E+D05 Co-60 1.000 1173.23* 99.85 4.79307E+OD4 l.48173E+004 1332.49* 99.98 S.63798E+004 1.37779E+004 Cs-137 1.000 661.66* 85 .10 8.9995SE+004 2.D3466E+004 Eu-155 0.977 86.55* 30.70 8.36312E+004 7.64466E+004 1 05.31* 21.10 -1 .37692E+OOS 1. 45606E+005 Tl-208 1 .000 583.19* 85.00 1 .39385E+004 8.89558E+003 Bi-214 0.438 609.32* 45.49 8.64484E+004 2.74900E+004 1120.29 14 .92 1764.49 15.30 Pb-214 0.439 295.22 18.42 351.93* 35.60 2.98646E+004 2.88624E+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

[169]

Interference Corrected Activity Report 6/4/2018 12: 31: 3 7 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M ... 2 ) Uncertainty K-40 1. 000 1.103318E+006 1.980813E+005 Co-60 1. 000 5.246191E+004 1.008990E+004 Cs-137 1. 000 8.999548E+004 2.034661E+004 Eu-155 0.977 8.363124E+004 7.644662E+004 Tl-208 1.000 1. 393847E+004 8.895583E+003 Bi-214 0.438 8.644844E+004 2.748998E+004 Pb-214 0.439 2.986456E+004 2.886244E+004

      ? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
      @=Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at   2.000 sigma

[170]

Interference Corrected Activity Report 6/4/2018 12: 31: 37 PM Page 5

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

Peak Locate Performed on ; 6/4/2018 12: 31: 3 7 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV} Counts per Second  % Uncertainty Type Nuclide 1 32.48 1. 9584E-001 44.45 2 75.30 3.7308E-001 47.43 9 910.89 3.4286E-002 78.34 Tol. Ac-228 M ~ First peak in a multiplet region m Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma [171]

Nuclide MDA Report 6/4/2018 12 :31:37 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFQWC012GD 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   1.843E+004    1.84E+004    1. 103E+006  O.OOOE+OOO
 +      Co-60      1173.23*      99.85   1.651E+004    8.02E+003    4.793E+004   7.377E+003 1332.49*      99.98   8.015E+003                 5.638E+004   3.075E+003 Nb-94        702.65      99.81   1.894E+004    1. 83E+004  -4.938E+003   8.782E+003 8 71. 09    99.89   1.826E+004                 8.042E+003   8.370E+003 Ag-108m      433.90      90.50   2.323E+004    l. 90E+004  -2.403E+003   1 .101E+004 614. 3 0    89.80   3.078E+004                 8.109E+003   1.467E+004 722.90      90.80   1.903E+004                 6.185E+003   8.749E+003 Cs-134       604.72      97.62   2.782E+004    2.38E+004   -l .763E+003  1.325E+004 795.86      85.46   2.383E+004                 5.370E+003   1.106E+004
 +      Cs-137       661.66*     85.10   1 .702E+004   1.70E+004    9.000E+004   7.725E+003 Eu- 152      121.78      28.67   1 .408E+005   8.75E+004    1. 995E+O 04 6.928E+004 344.28      26.60   8.750E+004                 3.146E+004   4.192E+004 1408.01       21. 07  8.766E+004                -2.859E+004   3.926E+004 Eu- 154      123.07      40.40   9.828E+004    4.76E+004   -5.469E+004   4.834E+004 723.30      20.06   8.617E+004                -5.747E+003   3.961E+004 1274.43       34.80   4.756E+004                 2.745E+004   2.116E+004
 +      Eu-155         86. 5 5*  30.70   1.219E+005    1 .22E+005   8.363E+004   5.989E+004 105.31*     21. 10  2.416E+005                -1. 377E+005  1.193E+005
 +      Tl-208       583.19*     85.00   1.261E+004    1 .26E+004   1.394E+004   5.566E+003 Bi-212       727.33       6.67   2.705E+005    2.70E+005   -1.380E+005   1.248E+005 Pb-212       238.63      43.60   7.505E+004    7.51E+004    6.763E+004   3.660E+004
 +      Bi-214       609.32*     45.49   3.067E+004    3.07E+004    8.645E+004   1.392E+004 1120.29       14 .92  1.568E+005                -6.523E+004   7.266E+004 1764.49       15.30   1.478E+005                 1.544E+005   6.668E+004
 +      Pb-214       295.22      18.42   1.402E+005    4.59E+004   -8.603E+003   6.767E+004 351.93*     35.60   4.592E+004                 2.986E+004   2.158E+004 Ra-226       186. 21      3.64   9.388E+005    9 . 39E+OOS  5.920E+005   4.595E+005 Ac-228       338.32      11. 27  2.134E+005    9.34E+004    1 .255E+004  1 .024E+005 911.20      25. 80  9.336E+004                 9 .467E+O 04 4.367E+004 968.97      15.80   1.430E+005                 1. 417E+OOS  6.641E+004 Am-241         59.54     35.90   1.519E+005    1.52E+005    7.744E+004   7.486 E+004
       + = Nuclide identified during the nuclide identification
       * ~ Energy line found in the spectrum
       > = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @ ~ Half-life too short to be able to perform the decay correction

[172]

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

Filename: 5456-A Report Generated On 6/4/2018 1 :13:15 PM Sample Title B103202AFSWC013GD Sample Description SFP/TRANSFER CANAL Sample Identification 013 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/4/2018 1 :03:00 PM Acquisition Started 6/4/2018 1 :03:13 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 5/30/2018 Efficiency ID 1M90DSFP 2IN [173]

Peak Analysis Report 6/4/2018 1: 13:15 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B10 3202AFSWC013GD Peak Analysis Performed on: 6/4/2018 1 :13 :14 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 134 130.89 32.72 0 .44 3.39E+001 26 .19 5. llE+OOl 2 250- 261 255.94 63.98 0.84 5.41E+001 71.77 4.91E+002 3 285- 311 301. 24 75.31 0 .92 7.07E+002 163.44 1.36E+003 4 335- 346 340.10 85.03 0 .77 7.60E+001 86.43 7.12E+002 5 1401- 1414 1407.63 351.91 0 .85 3.70E+001 31.28 7.40E+001 6 2325- 2338 23 3 1 .16 582.79 1. 17 3.41E+001 19.76 2.29E+001 7 2429- 2441 2434.45 608. 61 1. 23 4.19E+001 21.68 2.81E+001 8 2634- 2656 2645.52 661.38 1. 55 8.31E+002 61.06 2.60E+001 9 3637- 3650 3643.59 910.90 0.66 1.48E+001 17.54 2.12E+001 10 4680- 4704 46 90 .96 1172.74 1. 31 1.72E+002 29 .61 1 .18E+001 11 5317- 53 3 9 5328.81 1332.20 1.78 1. 8 7E+002 31.85 l.72E+001 12 5833- 5852 5842 .34 1460 .58 1.46 1.40E+002 25. 94 7.76E+OOO 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 [174]

Interference Corrected Activity Report 6/4/2018 1:13:15 PM Page 3

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

Sample

Title:

B103202AFSWC013GD Nuclide Library Us ed: 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 9.55083E+005 1.95180E+005 Co-60 1.000 1173.23* 99.85 1.11759E+005 2.11930E+004 1332.49* 99.98 1.28794E+005 2.42622E+004 Cs-137 1.000 661.66* 85.10 4.82425E+005 6.79183E+004 Eu-155 0.346 86.55* 30.70 5.96048E+004 6.88393E+004 1 05.31 21.10 Tl-208 1. 000 583.19* 85.00 1 .86731E+004 1.10430E+004 Bi-214 0.438 609.32* 45.49 4.37002E+004 2.32370E+004 1120.29 14.92 1764.49 15. 30 Pb-214 0.439 295.22 18.42 351.93* 35.60 3.78004E+004 3.24813E+004 Am-241 0.969 59.54* 35.90 4. 09190E+004 5.48960E+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

[175]

Interference Corrected Activity Report 6/4/20 18 1 :13:15 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 9.550828E+OOS 1.951802E+005 Co-60 1 . 000 l .191314E+OOS 1.596125E+004 Cs-137 1 . 000 4.824246E+OOS 6.791829E+004 Eu-155 0 .346 5.960480E+004 6.883933E+004 Tl-208 1 . 000 l .867315E+004 1.104305E+004 Bi-214 0 .438 4.370023E+004 2.323701E+004 Pb-214 0 .439 3.780042E+004 3.248131E+004 Am-241 0.969 4.091904E+004 5.489597E+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 a t   2.000 sigma

[176]

Interference Corrected Activity Report 6/4/2018 1: 13: 15 PM Page 5

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

Peak Locate Performed on: 6/4/2018 1 :13: 14 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.72 5.6471E-002 77. 31 3 75.31 1.1780E+OOO 23.12 9 910.90 2.4722E-002 118.27 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 [177]

~uclide MDA Report 6/4/2018 1 :13:15 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC013GD 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 .371E+005   1 .37E+005   9.551E+OOS  5.931E+D04
 +       Co-60      1173.23*     99.85   1 .639E+004   1 .64E+004   1.118E+005  7.318E+003 1332.49*     99.98   2.042E+004                 1.288E+005  9.278E+003 Nb-94        702.65     99. 81  1 .926E+004   1.93E+004   -1.394E+004  8.940E+003 871.09     99.89   2.019E+004                 8.594E+002  9.335E+003 Ag- lOBm     433.90     90.50   3.102E+004    1.98E+004    1.648E+004  l.491E+004 614.30     89.80   3.260E+004                -8.366E+003  1.55BE+004 722.90     90.80   1.981E+004                 3.910E+003  9.138E+003 Cs-134       604.72     97.62   2.792E+004    2.60E+OD4    2.480E+004  1. 330E+004 795 .8 6   85.46   2.605E+004                 2.161E+004  1. 217E+OD4 Cs-137       661 .6 6*  85. 10  2.077E+004    2. 0 8E+OD4  4.824E+005  9.598E+003 Eu-152       121. 78    28.67   1.503E+OOS    7. 0 0E+OD4  1 .014E+004 7.401E+004 344.28     26.60   1.028E+005                 3.000E+004  4.958E+004 1408.0 1     21. 07  6.996E+004                 2.183E+004  3.041E+004 Eu-154       123.07     40.40   1.065E+OOS    4.85E+OD4    5.343E+004  5.244E+004 723.30     20.06   8.707E+004                -B.180E+004  4.006E+004 1274 .43     34.80   4 .851E+004                3.123E+004  2.163E+004
 +       Eu-155        86.55*    30.70   1.114E+005    1 .llE+OOS   5.960E+004  5.462E+004 105.31     21.10   2.263E+OOS                -7.359E+004  1.116E+005
 +       Tl-208       583.19*    85.00   1. 582E+004   1 .5BE+004   1.867E+OD4  7.172E+D03 Bi-212       727.33      6.67   2.976E+005    2.98E+005    4 .644E+OD4 1. 383E+005 Pb-212       238.63     43.60   8.109E+004    B.11E+004    4 .168E+OD4 3.962E+004
 +       Bi-214       609.32*    45.49   3.270E+004    3.27E+OD4    4.370E+D04  1.494E+004 1120.29      14.92   1.595E+005                -5.176E+D04  7. 400E+ 004 1764.49      15.30   1.407E+005                 8.854E+D03  6.314E+004
 +       Pb-214       295.22     18.42   1.602E+005    5.11E+004    9.768E+D04  7.765E+004 351.93*    35.60   5.112E+004                 3.780E+004  2.418E+004 Ra-226       186.21      3.64   1.134E+006    1 .13E+OD6  -6.667E+OOS  5.57DE+OOS Ac-228       338.32     11. 27  2.484E+005    l .04E+OOS   1.602E+005  1.199E+005 911. 20    25.80   1. 038E+005                2.382E+004  4.889E+004 968.97     15.80   1. 622E+OOS                4.373E+004  7.602E+004
 +       Am-241        59.54*    35.90   8.943E+004    8.94E+004    4.092E+004  4.369E+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

[178]

• • • • • GAMMA S P E C T R U M ANALYSIS *****

Filename: 5456-A Report Generated On 6/4/2018 12:51:11 PM Sample Title B103202AFSWC014GD Sample Description SFP/TRANSFER CANAL Sample Identification 014 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 3.140E+OOO M"2 Sample Taken On 6/4/2018 12:39: 00 PM Acquisition Started 6/4/2018 12:41:09 PM Live Time 600 . 0 seconds Real Time 600.9 seconds Dead Time 0.15 % Energy Calibration used Done On 3 I 15/2 018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [179]

Peak Analysis Report 6/4/2018 12: 5 1 :11 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B1 03202AFSWC014GD Peak Analysis Performed on: 6/4/2018 12:51: 11 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 1 126- 139 130.01 32.50 0 .77 2.05E+002 57.07 1. 77E+002 2 281- 307 301.25 75. 31 1. 07 9.39E+002 184.45 1.73E+003 3 329- 346 339.98 84.99 1. 20 9.02E+001 135.51 1.38E+003 4 949- 961 954.88 238.72 0.84 6.30E+001 55.42 2.67E+002 5 1402- 1414 1408. 04 352. 01 0.32 5.15E+001 36.60 1.07E+002 6 2426- 2445 2436. 05 609. 01 1. 34 8.95E+001 32.89 5.15E+001 7 2633- 2657 2645.48 661.37 1.45 2.59E+003 105.42 4.65E+001 8 3639- 3652 3645.04 911.26 0.67 2.95E+001 18.37 1.95E+001 9 4472- 4485 4478.75 1119.69 0.47 1.65E+001 13.47 1 .05E+001 10 4681- 4703 4691. 31 1172.83 1. 93 2.52E+002 34.69 1. 21E+O 01 11 5317- 5341 5328.46 1332.12 1. 34 3.17E+002 36.89 5.83E+OOO 12 5832- 5853 5841.97 1460.49 1. 53 1.38E+002 26.53 1 .05E+001 13 7051- 7066 7058. 16 1764.54 0.33 1.84E+001 12.86 7.58E+OOO 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 [180]

Interference Corrected Activity Report 6/4/2018 12:51: 11 PM Page 3

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Sample

Title:

B103202AFSWC014GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * *'"., * * !t I **** * ** * **     IDENTIFIED NUCLIDES             * * * * * * * * * * * , *

• I *
• t 1 I' Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M ... 2 ) Uncertainty K-40 1. 000 1460.82* 10.66 9.36379E+OOS l.98138E+005 Co-60 1.000 1173.23* 99.85 1.63460E+005 2.60339E+004 1332.49* 99.98 2.18708E+OOS 3.08726E+004 Cs-137 1.000 661.66* 85.10 1.50210E+006 l.90488E+005 Eu-155 0.345 86.55* 30.70 7.07874E+004 l.07259E+005 105.31 21.10 Pb-212 1.000 238.63* 43.60 4.32826E+004 3.87303E+004 Bi-214 1.000 609.32* 45.49 9.34288E+004 3.61368E+004 1120.29* 14.92 7. 01144E+ 004 5.75281E+004 17 64.49* 15.30 9.80654E+004 6.88855E+004 Pb-214 0.439 295.22 18.42 351.93* 35.60 5.25062E+004 3.82783E+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

[181]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1.000 9.363793E+005 1. 981382E+005 Co-60 1.000 1 .864201E+005 1. 990222E+004 Cs-137 1 .000 1 .502098E+006 1. 904881E+005 Eu-155 0.345 7.078741E+004 1. 072590E+005 Pb-212 1. 000 4.328262E+004 3.873027E+004 Bi-214 1. 000 8.868356E+004 2.796535E+004 Pb-214 0.439 5.250615E+004 3.827835E+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 [182]

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Peak Locate Performed on: 6/4/2018 12:51:11 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.50 3.4204E-001 27.81 2 75. 31 1.5649E+OOO 19.64 8 911.26 4.9158E-002 62.29 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

[183]

Nuclide MDA Report 6/4/2018 12:51:11 PM Page 6

• • • • • N U C L I D E MDA RE PORT *****

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC014GD Nuclide Library Us ed: 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 .8 2*  10. 66  l.574E+005    1 .57E+005     9.364E+OOS  6.950 E+004
 +      Co-60      1173.23*    99.85   1.670E+004    l.27E+004      1. 635E+005 7.471E+OD3 1332.49*    99.98   1. 274E+004                  2.187E+005  5.439E+OD3 Nb-94       702.65     99.81   2.308E+004    2.29E+004      6.57SE+002  1. 085E+004 871.09     99.89   2.292E+004                 -4.999E+003   1.07DE+004 Ag-108m     433.90     90.50   4.133E+004    2.53E+004      4.766E+003  2.006E+004 614.30     89.80   3.875E+004                   1.151E+004  1.866E+004 722.90     90.80   2.528E+004                 -l.366E+004   1.187E+004 Cs-134      604.72     97.62   3.531E+004    2.66E+004    -2.339E+004   1. 7DOE+O 04 795.86     85.46   2.657E+004                   2.344E+D04  1.243E+004
 +      Cs-137      661.66*    85. 10  2.795E+004    2.80E+004      l. 502E+D06 1 .319E+004 Eu-152      121. 78    28.67   l.780E+005    7.94E+004      3.030E+004  8.789E+004 344.28     26.60  1.389E+005                    4.760E+D03  6.761E+004 1408.01     21. 07  7.937E+004                 -9.282E+003   3.512E+004 Eu-154      123.07     40.40   l.263E+005    5.21E+004    -3.830E+004   6.234E+004 723.30     20.06   l.171E+005                   4.942E+004  5.506E+004 1274.43     34.80  5.212E+004                  -6.768E+003   2.344E+004
 +      Eu-155       86.55*    30.70   l.753E+005    1.75E+005      7.079E+OD4  8.659E+004 105.31     21.10   2.524E+005                   3.932E+005  1.247E+005 Tl-208      583.19     85.00   3.594E+004    3.59E+004      9.632E+003  1.723E+004 Bi-212      727.33      6.67   3.451E+005    3. 4 5E+005    2.226E+OOS  1.621E+005
 +      Pb-212      238.63*    43.60   6.190E+004    6.19E+004      4 .328E+004 3.002E+004
 +      Bi-214      609.32*    45.49  4.90SE+004     4 .90E+004     9.343E+004  2.311E+004 1120.29*    14.92  8.663E+004                    7.011E+004  3.757E+004 1764.49*    15. 30  9.821E+004                   9.807E+004  4.190E+004
 +      Pb-214      295.22     18.42  2.059E+005     5.93E+004    -1. 268E+O 05 1.00SE+OOS 351.93*    35.60  5.928E+004                    5.251E+004  2.826E+D04 Ra-226      186.21      3.64   l.355E+006    1. 36E+006     4.813E+OOS  6.679E+OD5 Ac-228      338.32     11.27   3.307E+005    l . 1 2E+005   9.464E+004  1.611E+005 911.20     25.80   l.122E+005                   9.112E+004  5. 31DE+004 968.97     15.80   l.765E+OOS                   1.274E+005  8.318E+OD4 Am-241       59.54     35.90   l.482E+005    1 .48E+OOS   -4.027E+004   7.300E+004
       +=Nuclide identified during the nuclide i dentification
       *=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]

• • • • • GAMMA S P E C T R U M ANALYSIS *****

Filename : 5456-A Report Generated On 6/4/2018 3:34:07 PM Sample Title Bl03202AFSFC015GD Sample Description SFP/TRANSFER CANAL Sample Identification 015 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels} 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO M.... 2 Sample Taken On 6/4/2018 3:22:00 PM Acquisition Started 6/4/2018 3:24:05 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 5/30/2018 Efficiency ID 1M90DSFP 2IN [185]

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Detector Name: 5456-A Sample

Title:

Bl0 3202AFSFC015GD Peak Analysis Performed on: 6/4/2018 3:34:06 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 154 129.95 32.49 0.95 8.49E+002 103.99 3.40E+002 2 286- 308 301.43 75.36 1.15 1.10E+003 168.23 l .54E+003 3 334- 360 340.37 85.09 1. 48 5.92E+002 178.75 l .67E+003 4 1401- 1416 1407.90 351.97 0.37 9.62E+001 55.23 2.21E+002 5 2429- 2446 2435.98 609.00 0.62 6.60E+001 37.75 8.90E+001 6 2633- 2660 2646.64 661.66 1. 51 6.95E+003 169.45 5.15E+001 7 3638- 3652 3644.65 911.16 0.33 2.35E+001 17.52 1 .85E+001 8 4475- 4488 4481.42 1120.36 0.75 3.92E+001 16.95 1 .18E+001 9 4683- 4703 4693.53 1173.38 1. 01 1.31E+002 27.44 1 .57E+001 10 5322- 5341 5331.36 1332.84 2.01 1. 06E+O 02 22.11 4.68E+OOO 11 5835- 5855 5844.88 1461.22 2.17 1.49E+002 25.27 2.76E+OOO 12 7055- 7070 7062.49 1765.62 0.86 2.02E+001 10. 12 1.84E+OOO M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [186]

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Sample

Title:

B103202AFSFC015GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * * * * * * * ******* I If

• IDENTIFIED NUCLIDES I *
• I * * * * * * * * '"' * * * * * *
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pci/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.01658E+006 l .93474E+005 Co-60 1.000 1173.23* 99.85 8.52162E+004 l.90706E+004 1332.49* 99.98 7.33324E+004 l.63424E+004 Cs-137 1.000 661. 66* 85.10 4.03510E+006 4.94467E+005 Eu-155 0.346 86.55* 30.70 4.64265E+005 1.68136E+005 105.31 21.10 Bi-214 0.999 609.32* 45.49 6.89681E+004 4.02818E+004 1120.29* 14.92 1.66521E+005 7.32592E+004 1764.49* 15.30 1.07344E+OOS 5.45918E+004 Pb-214 0 .439 295.22 18.42 351.93* 35.60 9.81303E+004 5.85027E+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

[187]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) uncertainty K-40 1.000 1. 016584E+006 1.934740E+005 Co-60 1.000 7.836420E+004 1. 240928E+004 Cs-137 1.000 4.035097E+006 4.944668E+OOS Eu-155 0.346 4.642653E+005 1. 681360E+005 Bi-214 0.999 9.625224E+004 2.964146E+004 Pb-214 0.439 9.813033E+004 S.850267E+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

[188]

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Peak Locate Performed on: 6/4/2018 3:34:06 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.49 l.4147E+OOO 12.25 2 75. 36 1.8314E+OOO 15.31 7 911.16 3.9226E-002 74.43 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 [189]

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Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC015GD 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  9.089E+004    9.09E+004  1.017E+006  3.623E+004
 +      Co-60      1173.23*  99.85  1.787E+004    1.09E+004  8.522E+004  8.058E+003 1332.49*  99.98  1 .093E+004              7.333E+004  4.530E+003 Nb-94       702.65   99.81  1 .878E+004   1.87E+004  4 .947E+003 8.702E+003 871. 09  99.89  1 .866E+004             -2.743E+004  8.572E+003 Ag-108m     433.90   90.50  5.814E+004    2.34E+004 -6.940E+004  2.847E+004 614.30   89.80  4.352E+004              -8.895E+003  2.104E+004 722.90   90.80  2.345E+004               1 .632E+004 1 .096E+004 Cs-134      604.72   97.62  4.059E+004    2.34E+004 -2.260E+004  1.964E+004 795.86   85.46  2.344E+004               1.732E+004  1.087E+004
 +      Cs-137      661.66*  85.10  3.045E+004    3.05E+004  4.035E+006  1.444E+004 Eu-152      121.78   28.67  l .742E+005   8.45E+004 -1.247E+005  8.596E+004 344.28   26.60  1 .759E+005              8.231E+004  8.611E+004 1408.01   21. 07 8.445E+004              -4.326E+004  3.766E+004 Eu-154      123.07   40.40  l .237E+005   5.63E+004 -1.008E+005  6.105E+004 723.30   20.06  l .032E+005             -3.209E+003  4.815E+004 1274.43   34.80  5.628E+004               2.055E+004  2.551E+004
 +      Eu-155       86.55*  30.70  2.240E+005    2.24E+005  4 .643E+OOS 1. 109E+005 105.31   21.10  2.523E+OOS               5.805E+004  1. 246E+005 Tl-208      583.19   85.00  4.256E+004    4.26E+004  9.269E+003  2.054E+004 Bi-212      727.33    6.67  3.135E+005    3.14E+005 -2.540E+005  1.463E+005 Pb-212      238.63   43.60  1 .093E+OOS   1.09E+005  6.749E+004  5.372E+004
 +      Bi-214      609.32*  45.49  6.135E+004    5.54E+004  6.897E+004  2.926E+004 1120.29*  14.92  9.13BE+004               1 .665E+005 3.994E+004 1764.49*  15.30  5.537E+004               1 .073E+005 2.048E+004
 +      Pb-214      295.22   18.42  2.648E+005    8.94E+004  1 .739E+OOS 1.299E+005 351.93*  35.60  8.942E+004               9.813E+004  4.333E+004 Ra-226      186.21    3.64  1 .342E+006   1.34E+006 -1.003E+006  6.611E+005 Ac-228      338.32   11. 27 4.266E+OOS    1.00E+OOS -9.584E+004  2.090E+005 911. 20  25.80  1 .00SE+OOS             -5.569E+003  4.721E+004 968.97   15.80  l .507E+OOS              8.340E+004  7.030E+004 Am-241       59.54   35.90  l .463E+OOS   1.46E+005 -8.578E+004  7.205E+004
       +=Nuclide identified during the nuclide i dentification
       *=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

[190]

• • • • • GAMMA S P E C T R U M ANll.LYSIS *****

Filename: 5456-A Report Generated On 6/5/2018 8:12:53 AM Sample Title B103202AFSFC016GD Sample Description SFP/TRANSFER CANAL Sample Identification 016 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/5/2018 8:02: 00 AM Acquisition Started 6/5/2018 8:02:51 AM 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 5/30/2018 Efficiency ID 1M90DSFP 2IN [191]

Peak Analysis Report 6/5/2018 8:12:53 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC016GD Peal:: Analysis Performed on: 6/5/2018 8:12:53 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 1 126- 156 129.78 32.45 0.89 1 .26E+003 122.80 4.24E+002 2 284- 308 301. 17 75.29 1. 03 1 .23E+003 191. 69 1. 93E+003 3 333- 345 340.11 85.03 1.22 2.35E+002 112 .30 1. 11E+003 4 1400- 1417 1407.10 351.77 0.63 1. 01E+ 002 70.71 3.53E+002 5 2324- 2337 2331.12 582.78 0.82 3.38E+001 29. 33 6.32E+001 6 2429- 2445 2436.59 609. 15 1. 75 7.76E+001 34.70 7.14E+001 7 2633- 2658 2645.60 661. 40 1.48 1.05E+004 207.96 8.32E+001 8 4682- 4702 4691.86 1172.97 1. 56 1.20E+002 26.64 1.58E+001 9 5319- 5339 5329.14 1332.29 1. 04 1.26E+002 25.04 8.15E+OOO 10 5831- 5853 5842.89 1460.72 1. 21 1.79E+002 28.39 5.75E+OOO M -= First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [192]

Interference Corrected Activity Report 6/5/2018 8:12:53 AM Page 3

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Sample

Title:

B103202AFSFC016GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * * .. * * * * * * .. .. .. ..._ ..... ill

• IDENTIFIED NUCLIDES . . . il . ill .......... .......... " ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1. 000 1460.82* 10 .66 1.22078E+006 2.20517E+005 Co-60 1.000 1173.23* 99.85 7.80297E+004 l.83810E+004 1332.49* 99.98 8.67841E+004 1.86092E+004 Cs-137 1. 000 661.66* 85.10 6.07329E+006 7.39278E+005 Eu-155 0.346 86.55* 30.70 l. 84227E+005 9.54874E+004 1 05.31 21.10 Tl-208 1.000 583.19* 85.00 1.85094E+004 1.62058E+004 Bi-214 0.438 609.32* 45.49 8.10779E+004 3.75315E+004 1120.29 14.92 1764.49 15.30 Pb-214 0 .439 295.22 18.42 351.93* 35.60 l.03299E+005 7.39951E+004

          * ~ Energy line found in the spectrum.
          @ = Energy line not used for Weighted Mean Activity Energy Tolerance :                             10.000 keV Nuclide confidence index- threshold :                               O. 3 O Errors quoted at 2.000 sigma

[193]

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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 1.220778E+006 2.205169E+OOS Co-60 1.000 8.23528BE+004 1.307724E+004 Cs-137 1.000 6.073294E+006 7.392782E+OOS Eu-155 0.346 1.842271E+OOS 9.548743E+004 Tl-208 1 .000 1.850944E+004 1.620581E+004 Bi-214 0.438 8.107787E+004 3.7531SOE+004 Pb-214 0.439 1.03299SE+OOS 7.399514E+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

[194]

Interference Corrected Activity Report 6/5/20 18 8: 12: 53 AM Page 5

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Peak Locate Performed on: 6/5/2018 8:12:53 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 32 .45 2.1022E+OOO 9.74 2 75.29 2.0454E+OOO 15.62 M = First peak in a multiplet region m ~ Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [195]

Nuclide MDA Report 6/5/2018 8:12:53 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC016GD 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      146 0. 82*  10.66  1.242E+005    1.24E+OOS     1.221E+006    5.288E+004
 +       Co-60     1173.23*    99.85  l.790E+004    1.45E+004     7.803E+004    8.074E+003 1332.49*    99.98  1. 447E+004                 8.678E+004    6.302E+003 Nb-94       702.65    99. 81 2.175E+004    2 .1 8E+004 -2.074E+004     1.019E+004 871.09    99.89  2.194E+004                  7.406E+003    1. 021E+004 Ag-108rn    433.90    90.50  6.683E+004    2.31E+004     1.596E+004    3.281E+004 614.30    89.80  4.129E+004                -2.186E+004     1. 993E+004 722.90    90.80  2.313E+004                  7.938E+003    l.080E+D04 Cs-134      604.72    97.62  4.168E+004    2.40E+004   -6.449E+003     2.018E+D04 795.86    85.46  2.402E+004                - 1. 4 OSE+O 04 1.116E+004
 +       Cs-137      661.66*   85.10  3.731E+004    3.73E+004     6.073E+006    l.787E+004 Eu-152      121.78    28.67  1 .920E+005   8.61E+004   -1.186E+OOS     9.486E+004 344.28    26.60  l .982E+005               - 5.842E+004    9.726E+004 1408. 01    21 .07 8.607E+004                  2.785E+004    3.847E+004 Eu-154      123.07    40.40  1 .368E+005   6. 01E+004    1. 087E+005   6.76 0E+004 723.30    20.06  l.032E+005                  3.043E+004    4.815E+004 1274.43     34.80  6.012E+004                  S.696E+004    2.744E+004
 +       Eu-155       86.55*   30.70  1. 415E+005   1.42E+OOS     1.842E+OOS    6.971E+004 105.31    21.10  2.739E+005                -8.475E+003     l.354E+005
 +       Tl-208      583.19*   85.00  2.572E+004    2.57E+004     1.851E+004    l.212E+004 Bi-212      727.33     6.67  2.976E+005    2.98E+OOS   -1.00lE+OOS     1.383E+005 Pb-212      238.63    43.60  l.230E+005    1.23E+OOS     6.685E+004    6.056E+004
 +       Bi-214      609.32*   45.49  5.419E+004    5 .4 2E+004   8.108E+004    2.568E+004 1120.29     14.92  2.032E+005                  2.051E+005    9.587E+004 1764.49     15.30  1.357E+005                  8.400E+004    6.066E+004
 +       Pb-214      295.22    18.42  2.842E+005    1.16E+OOS     2.124E+004    1.397E+005 351.93*   35.60  l.165E+005                  l .033E+005   5.687E+004 Ra-226      186.21     3.64  1.497E+006    1.50E+006   -6.651E+OOS     7.385E+005 Ac-228       338.32    11. 27 4 .543E+005   1.04E+OOS   -2.602E+OOS     2.229E+005 911.20    25. 80 1. 044E+005                 1 .066E+005   4.916E+004 968.97    15 .80 1. 507E+005                 5.74SE+004    7.030E+004 Am-241        59.54    35.90  1. 617E+005   1.62E+OOS     7.361E+004    7.976E+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

[196]

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

Filename: 5456-A Report Generated On 6/4/2018 10:01:48 AM Sample Title B103202AFSWC017GD Sample Description SFP/TRANSFER CANAL Sample Identification 017 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/4/2018 9:51:00 AM Acquisition Started 6/4/2018 9:51:46 AM Live Time 600. 0 seconds Real Time 600.4 seconds Dead Time 0 .07 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [197]

Peak Analysis Report 6/4/2018 10:01:48 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B1 03202AFSWC017GD Peak Analysis Performed on: 6/4/2018 10:01:47 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 1 286- 307 30 1 .06 75.27 1.11 5.08E+002 117.43 7.84E+002 2 334- 348 339.52 84.88 1.15 6.82E+001 81.91 5.58E+002 3 1400- 1415 140 7 .29 351.82 1. 21 6.33E+001 31. 63 6. 17E+001 4 2429- 2444 2435.53 608.88 0 .87 6.48E+001 24.69 2.92E+001 5 2636- 2655 2644.91 661.23 1 . 30 3.13E+002 38.51 1 .68E+001 6 3636- 3649 3642.37 910.59 0.95 1.09E+001 14.58 1 .51E+001 7 4685- 4698 4691. 41 1172.85 0.48 4.74E+001 16.85 8.59E+OOO 8 5321- 5334 5327.25 1331.81 0.34 3.76E+001 14.57 5.44E+OOO 9 5832- 5852 5841.96 1460.49 1. 54 1.72E+002 26.84 2.45E+OOO 10 7050- 7065 7057.52 1764.38 0 .78 2.32E+001 10.65 l .77E+OOO M First peak in a multiplet region m ;: Other peak in a multiplet region F "' Fitted singlet Errors quoted at 2 . 000 sigma [198]

Interference Corrected Activity Report 6/4/20 18 10:01:48 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:

B103202AFSWC017GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• I * * + I I
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1 .000 14 60.82* 10 .66 1.16822E+006 2.09024E+005 Co-60 1.000 11 73.23* 99.85 3.07632E+004 1.12049E+004 1332.49* 99.98 2.58960E+004 1.D2570E+004 Cs-137 1.000 661.66* 85.10 1 .81798E+005 3.12481E+004 Eu-155 0.345 86.55* 30.70 5.35056E+004 6.51860E+004 105 .31 21.10 Bi-214 0.705 609.32* 45.49 6.76846E+004 2.70329E+004 1120.29 14.92 1764.49* 15.30 l .23646E+005 5.75436E+004 Pb-214 0.439 295.22 18.42 351.93* 35.60 6.45323 E+004 3.38775E+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

[199]

Interference Corrected Activity Report 6/4/2018 10:01:48 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 1.168223E+006 2.090236E+005 Co-60 1.000 2.811507E+004 7.565753E+003 Cs-137 1 .000 1 .817985E+005 3.124812E+D04 Eu-155 0.345 5.350559E+004 6.518605E+004 Bi-214 0.705 7.780201E+004 2.446746E+004 Pb-214 0.439 6.453229E+004 3.387754E+D04

      ? ~ 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

[200]

Interference Corrected Activity Report 6/4/2018 10 : 01 :48 AM Page 5

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

Peak Locate Performed on: 6/4/2018 10:01:47 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 75.27 8.4714E-001 23.10 6 910.59 1. 8237E-002 133.25 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 [201]

Nuclide MDA Report 6/4/2018 10:01:48 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC0l7GD 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   8.378E+004    8.38E+004    1.168E+006  3.268E+004
 +      Co-60      1173.23*    99.85   1.211E+004    1 .08E+004   3.076E+004  5.179E+003 1332.49*    99.98   1.080E+004                 2.590E+004  4. 467E+003 Nb-94       702.65     99.81   1.812E+004    1. 81E+004   9.185E+003  8.374E+003 871.09     99.89   1.826E+004                -5.160E+003  8.370E+003 Ag-108m     433.90     90.50   2.501E+004    1 .86E+004   2.062E+004  1.190E+004 614.30     89.80   3.089E+004                 8.719E+002  1. 473E+004 722.90     90.80   1.863E+004                 4.509E+003  8.548E+003 Cs-134      604.72     97.62   2.848E+004    2.24E+004   -1 .189E+004 l. 359E+004 795.86     85.46   2.243E+004                -4.252E+002  1. 036E+004
 +      Cs-137      661.66*    85.10   1.607E+004    1 .61E+004   1 .818E+005 7.249E+003 Eu-152      121.78     28 . 67 1.167E+005    8.11E+004   -6.318E+004  5.720E+004 344.28     26.60   8.774E+004                -9.395E+004  4.204E+004 1408.01     21.07   8.110E+004                -1. 383E+005 3.598E+004 Eu-154      123.07     40 . 40 8.338E+004    5.04E+004    4.631E+004  4.089E+004 723.30     20.06   8.527E+004                 7.637E+004  3.916E+004 1274.43     34.80   5.035E+004                 1. 890E+004 2.255E+004
 +      Eu-155       86 . 55*  30.70   1 .057E+005   1.06E+005    5.351E+004  5.180E+004 105.31     21. 10  1 .691E+005               -6.497E+004  8.300E+004 Tl-208      583.19     85.00   2.927E+004    2.93E+004    3.377E+004  1.389E+004 Bi-212      727.33      6.67   2.571E+005    2.57E+005   -2.355E+005  1.181E+005 Pb-212      238 . 63   43.60   6.939E+004    6.94E+004    2.467E+004  3.376E+004
 +      Bi-214      609.32*    45.49   3.497E+004    3.50E+004    6.768E+004  l.607E+004 1120.29     14.92   1 .685E+005                3.743E+004  7.848E+004 1764.49*    15. 30  5.404E+004                 1.236E+005  1.982E+004
 +      Pb-214      295.22     18.42   1 .520E+005   4 . 86E+004  1. 374E+005 7.356E+004 351.93*    35.60   4.863E+004                 6.453E+004  2.294E+004 Ra-226      186.21      3. 64  8.009E+005    8. 0 lE+OOS  5.242E+005  3.905E+005 Ac-228      338.32     11. 27  2.102E+005    8.83E+004    7.557E+003  l. 008E+005 911.20     25.80   8.B30E+004                 6.878E+004  4.113E+004 968.97     15.80   1.681E+005                 2.275E+005  7.896E+004 Am-241       59.54     35.90   1. 075E+005   1 .07E+005  -1.334E+003  5.267E+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

[202]

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

Filename: 5456-A Report Generated On 6/4/2018 10:20:35 AM Sample Title B103202AFSWC018GD Sample Description SFP/TRANSFER CANAL Sample Identification 018 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/4/2018 10:10:00 AM Acquisition Started 6/4/2018 10: 10 :34 AM Live Time 600 . 0 seconds Real Time 600.5 seconds Dead Time 0 . 08 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M9 ODSFP 2 IN [203]

Peak Analysis Report 6/4/2018 10 : 20:35 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSWC018GD Peak Analysis Performed on: 6/4/2018 10:20:34 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 283- 308 301.07 75.27 0.88 6.60E+002 131.55 8.63E+002 2 332- 345 339.64 84.91 0.81 l .15E+002 80.46 5.45E+002 3 602- 615 608.06 152.02 0.56 3.67E+001 51.62 2.28E+002 4 1176- 1188 118 1 .38 295.35 1.15 4 .91E+001 31.86 7.69E+001 5 1214- 1223 1218.20 304.55 0.51 2.66E+001 20.44 3.44E+001 6 1399- 1413 1407.05 351.76 0.94 7. 05E+ 001 29.77 5.25E+001 7 2325- 2337 2331.53 582.88 0.29 3.33E+001 18.60 1.97E+001 8 2428- 2442 2435.62 608.90 1.17 6.83E+001 22.11 1.88E+001 9 2634- 2654 2645.25 661. 31 1. 35 2.33E+002 38.30 3.68E+001 10 4472- 4485 4478.62 1119.66 1. 35 2.12E+001 13.49 8.77E+OOO 11 4680- 4701 4691. 47 1172.87 1. 97 2.00E+002 31. 78 1. 39E+001 12 5318- 5339 5327.93 1331.98 0 .41 1.81E+002 28.37 5.50E+OOO 13 5832- 5852 5842.43 1460.61 1. 80 1.38E+002 24.27 2.50E+OOO 14 7049- 7064 7056.66 1764.17 0 .49 2.20E+001 10.63 2.0lE+OOO 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 [204]

Interference Corrected Activity Report 6/4/2018 10 :20:35 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:

B103202AFSWC018GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

  * ****** I I ***** * *** 1

• IDENTIFIED NUCLIDES * * * * * * * * * * * * * *
• I
• I
• I Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1. 000 1460.82* 10. 66 9.43196E+005 l.84493E+005 Co-60 1 . 000 11 73.23* 99.85 1. 29867E+005 2.30905E+004 1332.49* 99.98 1.24461E+005 2.19488E+004 Cs-137 1. 000 661.66* 85.10 1.35398E+005 2.75440E+004 Eu-155 0.345 86.55* 30.70 9.00794E+004 6.56762E+004 105.31 21.10 Tl-208 1.000 583.19* 85.00 1 .82070E+004 l.04128E+004 Bi-214 1 .000 609.32* 45.49 7.12654E+004 2.46217E+004 1120.29* 14.92 9.01914E+004 5.77940E+004 1764.49* 15.30 1.17035E+005 5.73257E+004 Pb-214 1.000 295.22* 18.42 8.87161E+004 5.93252E+004 351.93* 35.60 7.19285E+004 3.24729E+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

[205]

Interference Corrected Activity Report 6/4/2018 10:20:35 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 9.431965E+005 1.844926E+005 Co-60 1. 000 1.270271E+005 1.590846E+004 Cs-137 1. 000 1.353984E+005 2.754397E+004 Eu-155 0.345 9.007942E+004 6.567621E+004 Tl-208 1.000 1.820699E+004 1. 041284E+004 Bi-214 1. 000 7.996129E+004 2.106672E+004 Pb-214 1.000 7.579871E+004 2.848484E+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

[206]

Interference Corrected Activity Report 6/4/2018 10 :20:35 AM Page 5

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

Peak Locate Performed on: 6/4/2018 10 :2 0 :34 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.27 1.1006E+OOO 19.92 3 152.02 6.1245E-002 14 0 . 4 7 D-Esc. 5 304.55 4.4317E-002 76.89 D-Esc. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [207]

Nuclide MDA Report 6/4/2018 10:20:35 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC0l8GD 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   8.497E+004   8.50E+004    9.432E+005   3.327E+004
 +       Co-60     1173.23*    99.85  1 .720E+004   1.22E+004    l.299E+005   7.723E+003 1332.49*    99.98  l .218E+004                l.245E+005   5.158E+003 Nb-94       702.65     99. 81 2.076E+004    2.08E+004    1.375E+003   9.693E+003 8 71. 09   99.89  2.160E+004                 l.471E+004   1. 004E+004 Ag-108m     433.90     90.50  2.510E+004    2.26E+004   -3.537E+003   l.195E+004 614.30     89.80  3.201E+004                -1. 387E+004  1.528E+004 722.90     90.80  2.264E+004                 4 .983E+002  1.055E+004 Cs-134     604.72     97.62  2.904E+004    2.67E+004    3.327E+004   l.386E+004 795.86     85.46  2.674E+004                 1. 504E+O 04 1.252E+004
 +       Cs-137     661. 66

• 85.10 2.363E+004 2.36E+004 1. 354E+005 1.103E+D04 Eu-152 121.78 28.67 1.247E+005 7.58E+004 -4 .145E+004 6.125E+004 344.28 26.60 9.186E+004 -9.224E+003 4.410E+004 1408 .0 1 21.07 7.576E+004 3.174E+004 3.331E+004 Eu-154 123 .0 7 40.40 8.884E+004 4.94E+004 2.710E+004 4.362E+004 723.30 20.06 1. 010E+005 -6.305E+004 4.702E+004 1274.43 34.80 4.944E+004 3.199E+004 2.210E+004

 +       Eu-155       86.55*   30.70  1.023E+005    1.02E+005    9.008E+004   5.007E+004 105.31     21.10  1.818E+005                 2.931E+004   8.938E+004
 +       Tl-208     583.19*    85.00   l.462E+004   1. 46E+004   1.821E+004   6.568E+003 Bi-212     727.33      6.67   3.091E+005   3. 0 9E+005  l.400E+005   1 .441E+005 Pb-212     238 . 63   43.60   6.931E+004   6.93E+004    6.666E+004   3.373E+004
 +       Bi-214     609.32*    45.49  2.805E+004    2.81E+004    7.127E+004   1 .261E+004 1120.29*    14.92   8.041E+004                9.019E+004   3.446E+004 1764.49*    15.30   5.814E+004                l.170E+005   2.187E+004
 +       Pb-214     295.22*    18.42   8.999E+004   4.40E+004    8.872E+004   4.255E+004 351.93*    35.60  4.400E+004                 7.193E+004   2.062E+004 Ra-226     186.21      3.64   8.427E+005   8.43E+005   -3.704E+005   4.114E+005 Ac-228     338.32     11. 27  2.237E+005   9.87E+004   -1. 780E+003  1.076E+005 911.20     25.80   9.873E+004               -7.866E+003   4 .635E+004 968.97     15.80  1.518E+005                -4.972E+004   7.084E+004 Am-241       59.54    35.90  1.079E+005    l.08E+005    3.890E+004   5.287E+004
       + = Nuclide identified during the nuclide i dentification

• 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

[208]

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

Filename: 5456-A Report Generated On 6/4/2018 9 : 43:10 AM Sample Title B103202AFSWC019GD Sample Description SFP/TRANSFER CANAL Sample Identification 019 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 3.140E+OOO M""2 Sample Taken On 6/4/2018 9:32:00 AM Acquisition Started 6/4/2018 9:33:07 AM 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 5/30/2018 Efficiency ID 1M90DSFP 2IN [209]

Peak Analysis Report 6/4/2018 9:43 :10 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSWC019GD Peak Analysis Performed on: 6/4/2018 9:43: 10 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 155 130.00 32.50 0.96 7.86E+002 115.46 4.57E+002 2 285- 309 300.99 75.25 0.90 1. 43E+003 200.21 2.08E+OD3 3 330- 346 340.25 85.06 0.69 3.17E+D02 142.57 l. 52E+003 4 1176- 1188 1182.44 295.61 0.25 2.25E+001 56.58 2.94E+002 5 1402- 1414 14 07 .37 351.84 0.49 5.56E+001 50.67 2.21E+002 6 2431- 2442 2436.64 609.16 0.98 5.56E+001 29.87 6.64E+001 7 2633- 2659 2645.40 661. 35 1.49 7.91E+003 181.23 7.15E+001 8 4473- 4486 4479.28 1119.82 0.39 3.14E+001 14.07 6.62E+OOO 9 4682- 4702 46 91 .52 1172.88 0.55 1.09E+002 23.26 7.47E+OOO 10 5320- 5338 5328.72 1332. 18 1.40 l.11E+002 23.62 7.73E+OOO 11 5832- 5854 5842.72 1460.68 1. 79 1.87E+002 27.35 O.OOE+OOO 12 7050- 7065 7057.95 1764 .49 0.64 2.40E+001 13.88 8.00E+OOO 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 [210]

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Sample

Title:

B103202AFSWC019GD 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 1.27354E+006 2.16617E+005 Co-60 1.000 1173.23* 99.85 7.04195E+004 l.61104E+004 1332.49* 99.98 7.67321E+004 1.74050E+004 Cs-137 1 .000 661.66* 85.10 4.58916E+006 5.61073E+005 Eu-155 0.346 86.55* 30.70 2.49008E+005 l.22411E+005 105.31 21.10 Bi-214 1.000 609.32* 45.49 5.80750E+004 3.19633E+004 1120.29* 14.92 1.33359E+005 6.07482E+004 1764.49* 15.30 1 .27749E+005 7.45605E+004 Pb-214 1. 000 295.22* 18.42 4.07486E+004 l .02544E+OOS 351.93* 35.60 5.67568E+004 5.24861E+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 2.0 00 sigma

[211]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1. 000 1 .273537E+006 2.166168E+OOS Co-60 1. 000 7.333235E+004 1.182298E+004 Cs-137 1. 000 4.589159E+006 5.610726E+OOS Eu-155 0. 346 2.490083E+OOS 1. 224107E+OOS Bi-214 1. 000 8.111062E+004 2.644744E+004 Pb-214 1. 000 5.343355E+004 4.672163E+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

[212]

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Peak Locate Performed on: 6/4/2018 9:43: 10 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.50 1.3108E+OOO 14 .68 2 75.25 2.3824E+OOO 14 . 01 M . First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [213]

Nuclide MDA Report 6/4/2018 9:43:10 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC019GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

 +      K-40       1460.82*  10.66   1.843E+004    1.84E+004   1.274E+006  O.OOOE+OOO
 +      Co-60      1173.23*  99.85   1.279E+004    1.28E+004   7.042E+004  5.519E+003 1332.49*  99.98   1.391E+004                7.673E+004  6.022E+003 Nb-94       702.65   99. 81  2.119E+004    1.78E+004   3.181E+003  9.908E+003 871.09   99.89   1.785E+004               -2.615E+003  8.164E+003 Ag-108m     433.90   90.50   5.981E+004    2.28E+004  -3.911E+004  2.930E+004 614. 30  89.80   4 .599E+004              -1. 321E+004 2.228E+004 722.90   90.80   2.280E+004                5.788E+OD3  l.063E+004 Cs-134      604.72   97.62   4 .280E+004   2.38E+D04   3.457E+004  2.074E+004 795.86   85.46   2.383E+004               -1.669E+004  1.106E+004
 +      Cs-137      661.66*  85.10   3.495E+004    3.49E+D04   4.589E+006  1.669E+004 Eu-152      121. 78  28.67   2.050E+OOS    7.39E+D04   1.739E+004  1. 014E+ 005 344.28   26.60   1.842E+005                1.587E+005  9.026E+004 1408.01   21. 07  7.389E+004                3.638E+D04  3.238E+004 Eu-154      123.07   40.40   1.456E+005    4.66E+D04  -3.422E+D04  7.201E+004 723.30   20.06   1.062E+005                7.887E+004  4.961E+004 1274.43   34.80   4.658E+004                2.790E+D04  2.067E+004
 +      Eu-155       86.55*  30.70   1.802E+OOS    1 .8DE+005  2.490E+D05  8.90SE+004 105.31   21. 10  2.868E+005                1.226E+D05  1 .419E+005 Tl-208      583.19   85.00   4.669E+004    4.67E+004   1.797E+D04  2.261E+004 Bi-212      727.33    6.67   3.265E+005    3.27E+005   2.538E+005  1 .528E+005 Pb-212      238.63   43.60   1.240E+005    1 .24E+005  7.705E+004  6.107E+004
 +      Bi-214      609.32*  45.49   4.728E+004    4.73E+004   5.807E+004  2.223E+004 1120.29*  14.92   7.102E+004                1.334E+005  2.976E+004 1764.49*  15.30   1. 004E+005               1.277E+D05  4.301E+004
 +      Pb-214      295.22*  18.42   1. 709E+OOS   8.40E+004   4 .075E+004 8.298E+004 351.93*  35.60   8.403E+004                5.676E+004  4.063E+004 Ra-226      186.21    3.64   1. 635E+006   1.64E+006   1.637E+006  8.07BE+005 Ac-228      338.32   11.27   4.320E+005    9.40E+004   3.662E+005  2.117E+OOS 911. 20  25.80   9.398E+004               -4.722E+D04  4.397E+004 968.97   15.80   1.441E+005                8.464E+004  6.69BE+004 Am-241       59.54   35.90   1.652E+005    1.65E+005  -2.063E+005  8.152E+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]

• • • • • GAMMA S P E C T R U M ANALYSIS *****

Filename: 5456-A Report Generated On 6/4/2018 9:21: 11 AM Sample Title B103202AFSWC020GD Sample Description SFP/TRANSFER CANAL Sample Identification 020 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 3.140E+OOO MA2 Sample Taken On 6/4/2018 9: 10 : 00 AM Acquisition Started 6/4/2018 9: 11 :09 AM Live Time 600.0 seconds Real Time 601.0 seconds Dead Time 0 . 17 % Energy Calibration used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1M90DSFP 2IN [215]

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Detector Name: 5456-A Sample

Title:

B1 03202AFSWC020GD Peak Analysis Performed on: 6/4/2018 9:21: 10 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 137 130.15 32.54 0 .92 2.54E+002 54.38 1.62E+002 2 285- 306 301.09 75.27 1. 19 1.23E+003 170.10 1. 60E+O 03 3 335- 348 340.21 85.05 1 .11 2.15E+002 120.83 1.24E+003 4 506- 520 510. 05 127.51 0.73 4.92E+001 103.29 9.06E+002 5 2428- 2444 2436.24 609.06 0.42 7.35E+001 28.73 4.25E+001 6 2634- 2656 2645.34 661.34 1.49 1 .95E+003 93.48 6.0lE+OOl 7 3636- 3649 3642.47 910.62 0.35 3.46E+001 16.63 1.24E+001 8 4472- 4485 4478.26 1119.56 0.99 2.75E+001 12.19 3.50E+OOO 9 4681- 4703 4691.63 1172.91 0.85 1.94E+002 29.83 7.74E+OOO 10 5317- 5339 5328.51 1332.13 0.98 2.13E+002 31.41 8.54E+OOO 11 5831- 5853 5842.03 1460.51 2. 01 1.50E+002 25.35 2.76E+OOO 12 7049- 7064 7056.45 1764. 11 0 .75 2.60E+001 11.32 1 .96E+OOO 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 [216]

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Sample

Title:

Bl03202AFSWC020GD 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 1.02310E+006 1 .94171E+005 Co-60 1.000 1173.23* 99.85 1.26051E+005 2.18256E+004 1332.49* 99.98 1.47193E+005 2.46551E+004 Cs-137 1. 000 661.66* 85. 10 1.13304E+006 1 .46490E+005 Eu-155 0. 346 86.55* 30.70 1.68638E+005 1.00595E+005 1 05 .31 21. 10 Bi-214 1.000 609.32* 45.49 7.67566E+004 3.13870E+004 11 20.29* 14.92 1 .16851E+005 5.26345E+004 1764.49* 15.30 l .38567E+005 6.12407E+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]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Unce rtainty K-40 1.000 1 .023099E+006 1.941705E+OOS Co-60 1.000 1 .353396E+005 1.63422SE+004 Cs-137 1.000 1 .133044E+006 1.464899E+005 Eu-155 0.346 1 .686376E+005 1.005946E+005 Bi-214 1.000 9.559996E+004 2.467312E+004

       ? : Nuclide is part of an undetermined so lution X ~ Nuclide rejected by the interference analysis
      @=Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at   2. 000 sigma

[218]

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Peak Locate Performed on: 6/4/2018 9:21:10 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.54 4.2326E-001 2 1. 41 2 75.27 2.0497E+OOO 13.83 4 127.51 8.2014E-002 209.90 7 910.62 5.7695E-002 48.03 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 [219]

Nuclide MDA Report 6/4/2018 9:21 :11 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC020GD 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   9.089E+004    9. 09E+004   1.023E+006  3.623E+004
 +      Co-60      1173.23*   99.85   1.309E+004    1.31E+004    1. 261E+005 5.668E+003 1332.49*   99.98   1.494E+004                 1.472E+OOS  6.539E+003 Nb-94       702.65    99.81   2.032E+004    2.03E+004    6.856E+003  9.474E+003 871. 09   99.89   2.292E+004                -1.228E+004  1.070E+004 Ag-108m     433.90    90.50   3.896E+004    2.45E+D04    2.496E+004  1.888E+004 614.30    89.80   3.734E+004                -1 .927E+004 1.795E+004 722.90    90.80   2.453E+004                -3.717E+003  1.15DE+004 Cs-134      604.72    97.62   3.290E+004    2.69E+004   -8.878E+003  1.580E+004 795.86    85.46   2.691E+004                 1.178E+004  1.261E+004 Cs-137      661.66*   85.10   3.070E+004    3.07E+004    1.133E+006  1.456E+004 Eu-152      121. 7 8  28.67   1.886E+005    7.58E+D04    9.912E+003  9.318E+004 344.28    26.60   1.402E+005                -2.048E+OOS  6.827E+D04 1408. 01   21.07   7.576E+004                 3.263E+004  3.331E+004 Eu-154      123.07    40.40   1.346E+005    5.63E+004   -1.560E+002  6.648E+004 723.30    20.06   1 .124E+005                1.992E+004  5.274E+004 1274.43    34.80   5.628E+004                 3.214E+004  2.551E+004
 +      Eu-155        86.55*  30.70   1 .534E+005   l.53E+005    1.686E+OOS  7.562E+004 105 .31   21 .10  2.700E+005                 2.404E+005  1 .335E+005 Tl-208      583.19    85.00   3.299E+004    3.30E+D04    4 .109E+OD3 l .575E+004 Bi-212      727.33     6.67   3.569E+005    3.57E+005    1.634E+OOS  1.68DE+OOS Pb-212      238. 63   43.60   1 .026E+005   1 .03E+005  -2.359E+004  5.038E+004
 +      Bi-214      609.32*   45.49   4.242E+004    4.24E+004    7.676E+OD4  1.980E+004 1120.29*   14.92   5.492E+004                 1.169E+OOS  2.171E+004 1764.49*   15.30   5.721E+004                 1.386E+005  2.141E+004 Pb-214      295.22    18.42   2.248E+005    1. 1 0E+005  3.726E+002  1.lOOE+OOS 3 51. 93  35.60   1.100E+005                 5.041E+OD3  5.360E+004 Ra-226      186.21     3.64   1.316E+006    1.32E+OD6   -S.730E+OOS  6.483E+005 Ac-228      338.32    11. 27  3.351E+005    1. 0 5E+005 -3.596E+005  1.633E+OOS 911.20    25.80   1.054E+OOS                -4.964E+002  4.971E+004 968.97    15.80   1.747E+005                 9.341E+OD4  8.226E+004 Am-241        59.54   35.90   l. 586E+005   1.59E+OD5    5.998E+OD3  7.822E+004
       + ~ Nuclide identified during the nuclide identification
       * ; Energy line found in the spectrum
       >=Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @ ~ Half-life too short to be able to perform the decay correction

[220]

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

Filename: 5456-A Report Generated On 6/2/2018 12:55 : 56 PM Sample Title B103202AFSFC021GD Sample Description SFP/TRANSFER CANAL Sample Identification 021 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO M"2 Sample Taken On 6/2/2018 12:45:00 PM Acquisition Started 6/2/2018 12:45:55 PM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0 . 08 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID l .5M90DSFP 2IN [221]

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Detector Name: 5456-A Sample

Title:

B103202AFSFC021GD Peak Analysis Performed on: 6/2/2018 12:55:56 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 1 126- 134 129.61 32.40 0.54 4.24E+001 20.92 2.56E+001 2 285- 310 301.19 75.30 0.95 3.33E+002 112.52 6.65E+002 3 331- 345 339.67 84.92 0.93 8.14E+001 70.53 4.01E+002 4 536- 547 541. 30 135.33 0.39 8.24E+OOO 43.03 1.79E+002 5 1400- 1416 1408.25 352.06 1. 27 6.52E+001 30.34 5.28E+001 6 1473- 1484 1478.86 369.72 0.37 1 .08E+001 19.52 3.32E+001 7 2431- 2444 2437.39 609.35 1.40 6.60E+001 21.66 1 .80E+001 8 2636- 2656 2646.72 661.68 1. 36 4.64E+002 46.07 l .84E+001 9 3639- 3652 3645.76 911.44 0.73 1 .87E+001 16.41 1 .63E+001 10 4686- 4705 4694.09 1173.52 1. 29 7.09E+001 19.53 7.12E+OOO 11 5323- 5341 5332. 19 1333.05 0.93 7.75E+001 18.57 2.47E+OOO 12 5834- 5855 5845 .51 1461.38 0.35 1 .60E+002 26.84 5.50E+OOO 13 7056- 7071 7063.72 1765.93 0.55 2.31E+001 10.75 1. 92E+OOO 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 [222]

Interference Corrected Activity Report 6/2/2018 12: 55: 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 REPORT *****

Sample

Title:

B103202AFSFC021GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• I f, I I * * *
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M ... 2 ) Uncertainty K-40 1. 000 1460.82* 10.66 1. 09171E+006 2.06742E+005 Co-60 1.000 1173.23* 99.85 4.63439 E+004 l.3298DE+004 1332. 49* 99.98 5.37541E+D04 1.35735E+004 Cs-137 1.000 661.66* 85. 10 2.71405E+005 4.23041E+D04 Eu-155 0.345 86.55* 30.70 6.41332E+004 5.70315E+D04 105.31 21.10 Bi-214 0 . 704 609.32* 45.49 6.95622E+004 2.43209E+004 112 0.29 14.92 1764.49* 15.30 1 .23267E+005 S.82467E+004 Pb-214 0 .438 295.22 18.42 351.93* 35.60 6.69928E+004 3.29544E+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

[223]

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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 1.091715E+006 2.067416E+005 Co-60 1. 000 4. 997306E+004 9.499001E+003 Cs-137 1. 000 2.714052E+005 4 .230411E+004 Eu-155 0.345 6.413315E+004 5.703152E+004 Bi-214 0.7 04 7.753538E+004 2.244304E+004 Pb-214 0.438 6.699276E+004 3.295438E+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

[224]

Interference Corrected Activity Report 6/2/2018 12 : 55: 56 PM Page 5

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Peak Locate Performed on: 6/2/2018 12 :55:56 PM Peak Locate From Channel: BS Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak To l. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.40 7.0735E-002 49.28 2 75.30 5.5427E-001 33.83 4 135.33 1 .3734E-002 522.14 6 369.72 1.7955E-002 18 1 .22 9 911.44 3.1190E-002 87.70 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 [225]

Nuclide MDA Report 6/2/2018 12:55:56 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

Bl03202AFSFC021GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/MA2 )

 +      K-40       1460.82*   10.66  1. 208E+005    1.21E+OOS    l.092E+006   5.114E+004
 +      Co-60      1173.23*   99.85  1.242E+OD4     8.59E+003    4.634E+004   5.324E+003 1332.49*   99.98   8.591E+003                 5.375E+004   3.358E+003 Nb-94       702.65    99.81  1.877E+004     l.88E+004    4 .076E+003  8.691E+003 8 71. 09  99.89  1.920E+004                  9.908E+003   8.835E+003 Ag-108m     433.90    90.50  2.678E+004     2. 0 2E+004  9.65DE+003   1.278E+004 614.30    89.80  2.978E+004                 -8.219E+003   1.416E+004 722.90    90.80  2.016E+0 04                 1.194E+004   9.307E+003 Cs-134      604.72    97.62  2.827E+004     2.28E+004   -9.361E+003   1.347E+004 795.86    85.46  2.281E+004                  2.595E+003   1.055E+004
 +      Cs-137      661.66*   85.10  1 .734E+004    1.73E+004    2.714E+005   7.879E+003 Eu- 152     121. 78   28.67   l .018E+005   6.82E+004    8.999E+004   4 .975E+004 344.28    26.60   7.930E+004                -5.736E+004   3.781E+004 1408 .01   21. 07  6.823E+004                -l .002E+OOS  2.952E+004 Eu-154      123.07    40.40   7.085E+004    4.97E+004   -6.868E+003   3.462E+004 723.30    20.06   9.128E+004                 4.015E+004   4 .214E+004 1274.43    34.80  4 . 973E+004               -1 .341E+004  2.223E+004
 +      Eu-155        86.55*  30.70   9.050E+004    9.0SE+004    6.413E+004   4.419E+004 105.31    21. 10 1.454E+005                 -1 .648E+004  7.114E+004 Tl-208      583.19    85. 00  2.709E+004    2.71E+004    3.363E+004   1 .280E+004 Bi-212      727.33     6.67   2.673E+005    2.67E+005   -2.120E+OOS   1 .231E+005 Pb-212      238.63    43.60   6.103E+004    6.10E+004    7.910E+004   2.958E+004
 +      Bi-214      609.32*   45.49   2.771E+004    2.77E+004    6.956E+004   1 .243E+004 1120 .29   14.92  1.593E+005                  3.959E+004   7.385E+004 1764.49*   15.30   5.677E+004                 1. 233E+O 05 2.116E+004
 +      Pb-214      295.22    18.42  1.289E+005     4.62E+004   -5.785E+004   6.197E+004 351.93*   35.60   4.617E+004                 6.699E+004   2.170E+004 Ra-226      186.21     3.64   6.892E+OOS    6.89E+005    2.305E+005   3.347E+005 Ac-228      338.32    11. 27  2.009E+005    9. 1 SE+004  1. 778E+O 04 9.617E+004 911.20    25.80   9.150E+004                 8.636E+004   4.271E+004 968.97    15.80   1. 306E+005                l .232E+005  6.018E+004 Am-241        59.54   35.90   9.142E+004    9.14E+004   -7.447E+004   4.463E+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

[226]

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

Filename: 5456-A Report Generated On 6/2/2018 12:39:04 PM Sample Title B103202AFSFC022GD Sample Description SFP/TRANSFER CANAL Sample Identification 022 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/2/2018 1:28:00 PM Acquisition Started 6/2/2018 12:29:02 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 5/30/2018 Efficiency ID 1.5M90DSFP 2IN [227]

Peak Analysis Report 6/2/2018 12:39: 04 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC022GD Peak Analysis Performed on: 6/2/2018 12:39:04 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 133 129.88 32.47 0.79 2.44E+002 61.60 2.74E+002 2 281- 311 301.07 75.27 1.07 6.74E+002 18 0. 59 1 .53E+003 3 335- 346 340.96 85.24 0.53 8.75E+001 81.99 6.34E+002 4 1403- 1418 1408.94 352.24 0.25 4. 66E+001 41.12 1 .22E+002 5 2431- 2446 2437.23 609.31 0.89 5.31E+001 24.47 3.09E+001 6 2636- 2658 2646.80 661.70 1. 35 1.91E+003 90 .32 3.37E+001 7 3639- 3653 3645.69 911.42 0.58 3.71E+001 16.54 1 .09E+001 8 4683- 4704 4694.09 1173.52 0.94 1.92E+002 31.93 l .66E+001 9 5321- 5343 5331. 44 1332.86 0.93 2. 19E+ 002 30.27 2.64E+OOO 10 5836- 5856 5845 .10 1461 .27 1. 78 1.47E+002 24.25 O.OOE+OOO 11 7054- 7069 7061. 25 1765.31 0.50 2.21E+001 11.72 3.90E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [228]

Interference Corrected Activity Report 6/2/2018 12 : 39: 04 PM Page 3

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

Sample

Title:

B103202AFSFC022GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Ii ........ . . ' ' ... .. . ... . IDENTIFIED NUCLIDES . ..... ....... . .. . .... Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10 .66 1.00611E+006 l.87557E+005 Co-60 1.000 1173.23* 99.85 1.25821E+005 2. 31731E+004 1332.49* 99.98 1.52078E+005 2.42555E+004 Cs-137 1.000 661.66* 85.10 1.11840E+006 1.44340E+005 Eu-155 0.346 86.55* 30.70 6.88324E+004 6.59501E+004 105.31 21.10 Bi-214 0.705 609.32* 45.49 5.59537E+004 2.66591E+004 1120.29 14.92 1 764.49* 15.30 1.17989E+005 6.32958E+004 Pb-214 0.438 295.22 18.42 351.93* 35.60 4. 78302E+004 4.29243E+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.ooo*sigma

[229]

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          • • • • • • • • • • • • • • • • • • • • • • • • • • • • • ~**************************************

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M ... 2 ) Uncertainty K-40 1.000 1 .00611SE+006 1.875571E+005 Co-60 1.000 l .383506E+005 1.675542E+004 Cs-137 1.000 l .118402E+006 l.443402E+005 Eu-155 0.346 6.883239E+004 6.595012E+004 Bi-214 0.705 6.530032E+004 2.456885E+004 Pb-214 0.438 4.783018E+004 4 .292429E+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

[230]

Interference Corrected Activity Report 6/2/2018 12: 39: 04 PM Page 5

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

Peak Locate Performed on: 6/2/20 18 12: 39: 04 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.47 4.0599E-001 25.29 2 75.27 1 .1228E+OOO 26.81 7 911.42 6.1788E-002 4 4. 63 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 [231]

Nuclide MDA Report 6/2/2018 12: 39: 04 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

Bl03202AFSFC022GD 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  l.852E+004     1 .8SE+004  l.006E+006   O.OOOE+OOO
 +      Co-60      1173.23*   99.85   1.876E+004     8.97E+003   1.258E+OOS   8.493E+003 1332.49*   99.98   8.966E+003                 1.521E+OOS   3.545E+003 Nb-94       702.65    99.81   2.004E+004     2.00E+004   1.189E+004   9.324E+003 871.09    99.89   2.071E+004                -1.132E+003   9.589E+003 Ag-108m     433.90    90.50  3.576E+004      2.56E+004  -2.230E+004   1 .728E+004 614. 3 0  89.80  3.260E+004                  1.371E+004   1 .557E+004 722.90    90.80   2.563E+004                 6.069E+003   1 .204E+004 Cs-134      604.72    97.62  3.058E+004      2.66E+004   4.405E+003   1 .463E+004 795.86    85.46   2.660E+004                -1. 603E+004  1 .244E+004
 +      Cs-137      661.66*   85.10   2.346E+004     2.35E+004   1.118E+006   1.094E+004 Eu-152      121. 7 8  28.67   1 .421E+005    1 .04E+OOS  S.394E+004   6.990E+004 344.28    26.60   l. 289E+005               -6.374E+004   6.260E+004 1408.01    21.07   1 .039E+005                4.113E+004   4.734E+004 Eu-154      123.07    40.40   l.007E+005     4.78E+004   2.006E+004   4.956E+004 723.30    20.06   1.154E+005                 2.247E+004   5.418E+004 1274.43    34.80   4.784E+004                -5.039E+004   2.128E+004
 +      Eu-155       86.55*   30.70   1.054E+005     1 .0SE+OOS  6.883E+004   5.165E+004 105.31    21.10   2.048E+005                -4.792E+003   l.009E+OOS Tl-208      583.19    85.00   3.331E+004     3.33E+004   8.123E+003   1.591E+004 Bi-212      727.33     6.67   3.270E+005     3.27E+005  -1. lSOE+OOS  1.529E+005 Pb-212      238.63    43.60   7.867E+004     7.87E+004   1.108E+004   3.840E+004
 +      Bi-214      609.32*   45.49   3.695E+004     3.69E+004   5.595E+004   1.705E+004 1120.29    14.92   1.794E+005                -5.605E+004   8.391E+004 1764.49*   15.30   7.593E+004                 1.180E+OOS   3.074E+004
 +      Pb-214      295.22    18.42   1.733E+005     6.83E+004  -3.624E+004   8.421E+004 351.93*   35.60   6.832E+004                 4.783E+004   3.277E+004 Ra-226      186.21     3.64   1 .031E+006    1.03E+006   8.799E+OOS   5.057E+005 Ac-228      338.32    11.27   2.993E+005     1. 01E+005  2.888E+004   1.453E+005 911. 20   25.80   1 .012E+005                7.365E+004   4.754E+004 968.97    15.80   1 .662E+005               -6.636E+004   7.802E+004 Am-241       59.54    35.90   1.647E+005     1.65E+005  -8.274E+004   8.129E+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

[232]

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

Filename: 5456-A Report Generated On 6/2/2018 10 :31 :17 AM Sample Title B103202AFSFC023GD Sample Description SFP/TRANSFER CANAL Sample Identification 023 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/2/2018 10: 20:00 AM Acquisition Started 6/2/2018 10 :21:15 AM Live Time 600.0 seconds Real Time 601.2 seconds Dead Time 0 . 20 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1.5M90DSFP 2IN [233]

Peak Analysis Report 6/2/2018 10 :3 1 :17 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC023GD Peak Analysis Performed on: 6/2/2018 10:31 : 1 7 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 1 126- 153 129.67 32.42 0.77 1 .11E+ 003 113.48 3.86E+002 2 282- 306 3 01. 03 75.26 1. 02 8.73E+002 168.18 1.50E+003 3 333- 345 340.13 85.03 0.97 2.21E+002 94.95 7.73E+002 4 493- 502 497.33 124.33 0.79 2.26E+001 68 .13 5.00E+002 5 949- 961 954.64 238.66 1. 30 4.00E+OOl 64.65 3.81E+002 6 1401- 1415 1408.44 352. 11 0.83 1.82E+001 58.72 2.93E+002 7 2429- 2445 2436.31 609.08 0.79 6.34E+001 31.53 5.56E+001 8 2632- 2658 2645.52 661.38 1.47 8.88E+003 190.94 5.40E+001 9 3638- 3651 3644.44 911 .11 1.14 3.49E+001 15.83 1.0lE+OOl 10 4473- 4488 4481.04 1120.26 1. 09 3.90E+001 15.88 8.00E+OOO 11 4681- 4703 4691. 65 1172.91 1. 31 1.83E+002 30.82 l.42E+001 12 5320- 5341 5329 .40 1332.35 1.25 1.72E+002 29.52 1.26E+001 13 5833- 5851 5842 .41 1460.60 1.29 1.45E+002 24.71 2.37E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 000 sigma [234]

Interference Corrected Activity Report 6/2/2018 10 : 31: 17 AM Page 3

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

Sample

Title:

B103202AFSFC023GD Nuclide Library used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  " . . . . . . . . 11 - .. . . . . . . . . .

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

• I* j I
• If Nuclide Id Energy Yield Activity Activity Name confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 9.89607E+005 1 .89674E+005 Co-60 1.000 1173.23* 99.85 1 .19501E+005 2.22969E+004 1332.49* 99.98 1 .19473E+005 2.25859E+004 Cs-137 1.000 661. 66
• 85. 10 5.19658E+006 6.33997E+005 Eu-152 0.650 121. 78* 28.67 l .89795E+004 5.73782E+004 344.28* 26.60 2.49813E+004 8.08163E+004 1408.01 21. 07 Eu-155 0.346 86.55* 30.70 l .74212E+005 8.24881E+004 1 0 5.31 21. 10 Pb-212 1. 000 238.63* 43.60 2.76166E+004 4.48073E+004 Bi-214 0 .733 609.32* 45.49 6.67861E+004 3.41878E+004 11 20.29* 14 .92 1.66936E+005 6.92844E+004 17 64.49 15 .30 Pb-214 0 .438 295.22 18 .42 351.93* 35.60 l.86658E+004 6.03811E+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

[235]

Interference Corrected Activity Report 6/2/2018 10 :31: 17 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1 .000 9.896071E+005 l. 896741E+005 Co-60 1 .000 1.194872E+005 l. 586747E+004 Cs-137 1 .000 5.196584E+006 6.339967E+OOS Eu-152 0 .650 1.897946E+004 S.737787E+004 Eu-155 0 .346 1.742123E+005 8.248808E+004 Pb-212 1 .000 2.761657E+004 4.480727E+004 Bi-214 0 .733 8.639637E+004 3.065852E+004 Pb-214 0 .438 4.48454SE+003 7.405339E+004

      ? = Nuclide is part of an undetermined so lution x = Nuclide rejected by the interference analysis
      @ -  Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted a t  2. 000 sigma

[236]

Interference Corrected Activity Report 6/2/20 18 10:31:17 AM Page 5

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

Peak Locate Performed on: 6/2/20 18 10:31: 17 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.42 1.8467E+OOO 10 .24 2 75.26 1.4552E+OOO 19.26 9 911.11 5.8130E-002 45.39 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 [237]

Nuclide MDA Report 6/2/2018 10:31:17 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC023GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec . Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

 +       K-40      1460.82*    10.66  8.236E+004      8.24E+004    9.896E+005  3.192E+D04
 +       Co-60     1173.23*    99.85  1 .766E+004     1.73E+004    1.195E+OOS  7.945E+003 1332.49*    99.98  1 .726E+004                  l.195E+005  7.695E+003 Nb-94       702.65     99.81  2.019E+004      2.02E+004    1. 231E+004 9.400E+OD3 871.09     99.89  2.053E+004                  -4.448E+003  9.498E+003 Ag-108m     433.90     90.50  S.984E+004      2.58E+004    3.813E+004  2.932E+004 614.30     89.80  3.869E+004                   7.944E+003  1 .862E+OD4 722.90     90.80  2.577E+004                   5.567E+003  1 .211E+004 cs-134     604.72     97.62  3.748E+004      2.63E+004   -8.411E+003  1 .808E+004 795.86     85.46  2.625E+004                   1. 587E+002 l .227E+OD4
 +       Cs-137     661. 66*   85.10  3.118E+004      3.12E+004    5.197E+006  1 .480E+004
 +       Eu-152     121.78*    28.67  9.SS3E+004      8.15E+004    1. 898E+004 4.663E+004 344.28*    26.60  1 .351E+005                  2.498E+004  6.568E+OD4 1408.01     21.07  8 .150E+004                  7.123E+004  3.616E+004 Eu-154     123.07     40 .40 l.238E+005      5.06E+004   -8.061E+003  6. 11DE+ 004 723.30     20.06  1.127E+005                  -6.058E+004  5.283E+OD4 1274.43     34.80  5.065E+004                   1.638E+004  2.268E+004
 +       Eu-155      86. 5 5*  30.70  1.189E+005      1. 19E+005   1.742E+005  5.84DE+004 105.31     21.10  2.436E+005                  -l.523E+005  1.203E+005 Tl-208     583.19     85.00  3.999E+004      4.00E+004    6.207E+004  l.925E+004 Bi-212     727.33      6.67  3.270E+005      3.27E+005    1.111E+005  1.529E+OD5
 +       Pb-212     238.63*    43.60  7.379E+004      7.38E+004    2.762E+004  3.596E+004
 +       Bi-214     609.32*    45.49  S.004E+OD4      5. 0 0E+004  6.679E+004  2.359E+004 1120.29*    14.92  8.066E+OD4                   1.669E+005  3.454E+OD4 1764.49     15.30  1.411E+OD5                   9.922E+004  6.332E+004
 +       Pb-214     295.22     18.42  2.53SE+OOS      1.01E+005   -1.849E+004  1.243E+D05 351.93*    35.60  1. 0 09E+O 05                1.867E+004  4.908E+004 Ra-226     186.21      3.64  1.392E+D06      1.39E+006   -2.383E+005  6.859E+005 Ac-228      338.32     11.27  4.231E+OOS      1.04E+005   -1.337E+005  2.D73E+005 911. 20    25.80  1 .040E+005                  l.025E+005  4.895E+004 968.97     15.80  l .550E+005                 -8.156E+003  7.238E+004 Am-241       59.54     35.90  1 .464E+OOS     1.46E+005    5.117E+003  7.212E+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

[238]

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

Filename: 5456-A Report Generated On 6/2/2018 1: 20: 14 PM Sample Title B103202AFSFC024GD Sample Description SFP/TRANSFER CANAL Sample Identification 024 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO M"2 Sample Taken On 6/2/2018 1:09:00 PM Acquisition Started 6/2/2018 1:10:12 PM Live Time 600.0 seconds Real Time 600. 4 seconds Dead Time 0.07 %

             *Energy Calibration Used Done On             3/15/2018 Efficiency Calibration Used Done On         5/30/2018 Efficiency ID                               1 .5M90DSFP 2IN

[239]

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC024GD Peak Analysis Performed on: 6/2/2018 1:20:14 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 287- 306 30 0 .91 75.23 0.76 2.15E+002 78.57 3.76E+002 2 1176- 1189 1183.22 295.80 0.43 3.78E+001 23.25 3.52E+001 3 1401- 1419 1409.49 352.37 0.96 6.92E+001 26.58 3.18E+001 4 2037- 2049 2043.72 510.93 0.90 3.27E+001 20.41 2.63E+001 5 2430- 2445 2438.36 609.59 0.52 5.52E+001 19.76 1 .38E+001 6 2640- 2655 2647.83 661.96 1. 38 6.lOE+OOl 19.70 1.20E+001 7 4477- 4490 4483.32 1120.83 1. 34 2.75E+001 12.19 3.50E+OOO 8 5327- 5340 5333.18 1333.30 0.56 1.25E+001 9.43 3.SOE+OOO 9 5837- 5858 5847.76 1461.94 1. 50 l.81E+002 27 .67 2.71E+OOO 10 7056- 7071 7063.04 1765.76 0.42 3.00E+OOl 10.95 O.OOE+OOO M = First peak in a mul t iplet region m = Other peak in a mul t iplet region F -= Fitted singlet Errors quoted at 2 . 000 *sigma [240]

Interference Corrected Activity Report 6/2/20 18 1 : 2 0: 14 PM Page 3

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

Sample

Title:

B103202AFSFC024GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  .t *" * * * * * * * * *** * *** I

• IDENTIFIED NUCLIDES * * "' * * * * * * * " * "
• I I * * ~
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.998 1460.82* 10.66 1.24118E+006 2.17930E+005 Cs-137 1.000 661.66* 85.10 3.57197E+004 l.23092E+004 Bi-214 0.999 609.32* 45.49 5.82379E+004 2.19806E+004 1120.29* 14.92 1. 17740E+ 005 5.30486E+004 1764.49* 15.30 1.60217E+005 5.98938E+004 Pb-214 1 . 000 295.22* 18.42 6.88044E+004 4. 36954E+004 351.93* 35.60 7.10837E+004 2. 95854E+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

[241]

Interference Corrected Activity Report 6/2/20 18 1 : 20: 14 PM Page 4 ~************************************************************************

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.998 1 .241178E+006 2.179299E+005 Cs-137 1. 000 3.571972E+004 1. 230919E+O 04 Bi-214 0.999 7.657152E+004 1. 923121E+004 Pb-214 1. 000 7.036720E+004 2.449812E+004

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

Peak Locate Performed on: 6/2/2018 1 : 20: 14 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.23 3.5878E-001 36.50 4 510.93 5.4555E-002 62.34 8 1333.30 2.0833E-002 75.42 Sum M ; First peak in a multiplet region m ~ Other peak in a multiplet region F ; Fitted singlet Errors quoted at 2 . 000 sigma [242]

Nuclide MDA Report 6/2/2018 1 :20: 14 PM Page 5

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC024GD 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  9.000E+004     9.00E+004 1.241E+006      3.574E+004 Co-60      1173.23     99.85  2.148E+004     1.89E+OD4 -3.012E+003     9.856E+003 1332.49     99.98  1 .894E+OD4                 1.941E+004   8.533E+003 Nb-94       702.65     99.81  1 .705E+004    l.69E+004 -5.946E+003     7.828E+003 871 .09    99.89  1 .689E+004                 3.68DE+003   7.680E+003 Ag-108m     433.90     90.50  l .843E+OD4    1.84E+004 -1.694E+004     8.606E+003 614.30     89.80  2.761E+004                 -3.254E+002   1. 308E+004 722.90     90.80  1 .997E+004                -5.203E+D03   9.212E+003 Cs-134      604. 7 2   97.62  2.477E+004     1.99E+OD4 3.007E+003      1. 172E+D04 795.86     85.46  1.992E+004                 -3.884E+003   9.103E+003 Cs-137      661.66*    85 .10 1.315E+004     1.32E+OD4 3.572E+D04      5.784E+003 Eu-152      121. 78    28.67  8.165E+004     6.88E+OD4 3.458E+004      3.969E+D04 344.28     26.60  6.878E+004                  1. 744E+003  3.255E+004 1408. 01    21.07  7.230E+004                  5.427E+004   3.156E+004 Eu-154      123. 07    40.40  5.721E+004     5. 1 5E+OD4 1. 220E+003   2.780E+D04 723.30     20.06  8.954E+004                 -2.518E+004   4.127E+004 1274. 43    34.80  5.155E+004                 -6.826E+004   2.313E+004 Eu-155       86.55     30.70  9.576E+004     9.58E+004 4.803E+004      4.682E+004 105.31     21. 10 1 .196E+005                -1. 776E+003  5.829E+004 Tl-208      583.19     85. 00 2.436E+004     2.44E+004 1.599E+004      1.143E+004 Bi-212      727.33      6.67  2.778E+D05     2.78E+005 -1.132E+005     l.284E+OOS Pb-212      238. 63    43.60  4 . 935E+004   4.94E+004 3.456E+004      2.374E+004
 +      Bi-214      609.32*    45.49  2.544E+004     1. 4 5E+004  5.824E+004   1.129E+D04 1120.29*    14.92  5.S38E+D04                  1.177E+005   2.190E+D04 1764.49*    15.30  1.44SE+004                  1.602E+D05   O.OOOE+OOO
 +      Pb-214      295.22*    18.42  6.39SE+004     3.78E+004 6.880E+004      2.951E+004 351. 93

• 35.60 3.782E+004 7.108E+004 1. 752E+004 Ra-226 186.21 3.64 5.713E+005 5.71E+005 l.172E+005 2.758E+OOS Ac-228 338.32 11. 27 1 .624E+OD5 7.69E+004 -3.307E+D04 7.688E+004 911. 20 25.80 7.686E+D04 -9.643E+003 3.539E+004 968.97 15.80 1. 280E+005 5.532E+004 5.888E+004 Am-241 59.54 35.90 8.241E+004 8.24E+004 -l.413E+D04 4.012E+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

[243]

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

Filename: 5456-A Report Generated On 6/2/2018 1: 36: 46 PM Sample Title B103202AFSFC025GD Sample Description SFP/TRANSFER CANAL Sample Identification 025 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 7.070E+OOO M" 2 Sample Taken On 6/2/2018 1: 26: 00 PM Acquisition Started 6/2/2018 1:26:44 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 07 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1.5M90DSFP 2IN [244]

Peak Analysis Report 6/2/2018 1 : 36: 46 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B10 3202AFSFC025GD Peak Analysis Performed on: 6/2/2018 1:36:45 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 1 297- 311 301.20 75.30 0.67 8.67E+001 70.83 3.96E+002 2 335- 346 339. 61 84 .90 0.70 1.35E+001 55. 14 2.85E+002 3 952- 961 956.32 239.08 0.40 3.25E+001 24.87 5.35E+001 4 1402- 1415 1408.99 352.25 0.72 5.51E+001 23.49 2.99E+001 5 2430- 2447 2438. 46 609.62 1. 49 8.62E+001 23.04 1.38E+001 6 2639- 2656 2647.98 662. 00 1.16 1.17E+002 26.08 1.60E+001 7 3640- 3653 3646.09 911.52 0.32 l.65E+001 14 .50 1.25E+001 8 4478- 4491 4484.37 1121.09 0.47 2.19E+001 11.98 5.llE+OOO 9 4688- 4702 4695.30 1173.83 1. 01 2.96E+001 15.39 9.39E+OOO 10 5327- 5341 5334.59 1333 . 65 0.46 3.72E+001 13.01 1.78E+OOO 11 5838- 5858 5847.89 1461.97 1. 31 1.81E+002 27.51 2.49E+OOO 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 [245]

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Sample

Title:

B103202AFSFC025GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0 .998 1460.82* 10.66 1.23580E+006 2.16794E+005 Co-60 0 .999 1173.23* 99.85 1.93605E+004 1.01792E+004 1 332.49* 99.98 2.58115E+004 9.25316E+003 Cs-137 1 .000 661.66* 85.10 6.85145E+004 l.73453E+004 Eu-155 0 .345 86.55* 30.70 1.06397E+004 4.34967E+004 105.31 21. 10 Pb-212 1 .000 238.63* 43.60 2.24224E+004 1.75492E+004 Bi-214 0 .732 609.32* 45.49 9.08979E+004 2.66334E+004 1120 .29* 14 .92 9.37264E+004 5.18642E+004 1764.49 15.30 Pb-214 0.438 295.22 18.42 351.93* 35.60 5.66123E+004 2.57790E+004

         *=Energy line found in the spectrum.
         @=Energy line not used for Weighted Mean Activity Energy Tolerance :                          10.000 keV Nuclide confidence inde:~ threshold                               O. 30 Errors quoted at 2.000 sigma

[246]

Interference Corrected Activity Report 6/2/2018 1 :36:46 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M~2 ) Uncertainty K-40 0.998 1.235800E+006 2.167941E+OOS Co-60 0.999 2.289274E+004 6.847002E+003 Cs-137 1. 000 6.851453E+004 1 .73453DE+004 Eu-155 0.345 1.063973E+004 4.349666E+004 Pb-212 1. 000 2.242237E+004 1 .754922E+004 Bi-214 0.732 9.148813E+004 2.369214E+004 Pb-214 0.438 5.661234E+OD4 2.577904E+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

[247]

Interference Corrected Activity Report 6/2/2018 1 :36:46 PM Page 5

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

Peak Locate Performed on: 6/2/2018 1 : 36: 45 PM Peak Locat8 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 1. 4454E-001 81.68 7 911.52 2.7486E-002 87. 94 Tol. Ac-228 M :::: First peak i n a multiplet region m = Other peak i n a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [248]

Nuclide MDA Report 6/2/2018 1 :36:46 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC025GD 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  8.517E+004    8.52E+OD4   1 .236E+006 3.332E+004
 +      Co-60      1173.23*   99.85  1 .347E+004   7.01E+OD3   1 .936E+004 5.850E+003 1332.49*   99.98  7.014E+003                2.581E+004  2.569E+003 Nb-94       702.65    99.81  1.941E+004    1.84E+OD4   l .700E+004 9.013E+003 871. 09   99.89  1.840E+004                1. 200E+004 8.434E+003 Ag-108m     433.90    90.50  2.091E+004    1.98E+004   5.645E+003  9.846E+003 614.30    89.80  3.085E+004               -1 .228E+004 1.470E+004 722.90    90.80  1. 978E+004               2.432E+001  9.116E+003 Cs-134      604.72    97.62  2.739E+004    2.13E+004  -5.433E+003  1 .303E+004 795.86    85.46  2.131E+004               -1 .200E+004 9.796E+003
 +      Cs-137      661.66*   85.10  1. 561E+004   l .56E+004  6.851E+004  7.D13E+003 Eu-152      121. 78   28.67  9.062E+004    7.24E+004   9.507E+004  4.417E+004 344.28    26.60  7.237E+004               -3.518E+004  3.435E+004 1408. 01   21. 07 7.797E+004               -1 .276E+004 3.440E+004 Eu-154      123. 07   40.40  6.304E+004    5.06E+004   1 .560E+003 3.072E+004 723.30    20.06  8.866E+004               -7.341E+003  4.083E+004 1274.43    34.80  5.065E+004               -2.604E+004  2.268E+004
 +      Eu-155       86.55*   30.70  7.296E+004    7.30E+004   1 .064E+004 3.541E+004 105.31    21.10  1.301E+005               -2.397E+004  6.349E+004 Tl-208      583.19    85.00  2.670E+004    2.67E+004   1 .718E+004 1 .260E+004 Bi-212      727.33     6.67  2.778E+OOS    2.78E+OOS   2.293E+005  1 .284E+005
 +      Pb-212      238.63*   43.60  2.697E+004    2.70E+004   2.242E+004  1 .255E+004
 +      Bi-214      609.32*   45.49  2.650E+004    2.65E+004   9.090E+004  1 .182E+004 1120 .29*  14.92  6.434E+004                9.373E+004  2.637E+004 1764.49    15.30  1. 386E+005               1.335E+005  6.210E+004
 +      Pb-214      295.22    18.42  1.223E+005    3.35E+004   9.469E+004  5.871E+004 351.93*   35.60  3.355E+004                5.661E+004  1.538E+004 Ra-226      186 .21    3.64   5.682E+OOS   5.68E+005   2.819E+005  2.742E+005 Ac-228      338.32    11. 27 1. 786E+OOS   8.62E+004  -4.585E+004  8.499E+004 911.20    25.80   8.624E+004               5.131E+004  4 .008E+004 968.97    15.80  1 .318E+005              -1.279E+004  6.081E+004 Am-241       59.54    35.90   8.899E+004   8.90E+004   1.846E+004  4.342E+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

[249]

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

Filename: 5456-A Report Generated On 6/2/2018 1:59:52 PM Sample Title B103202AFSFC026GD Sample Description SFP/TRANSFER CANAL Sample Identification 026 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA 2 Sample Taken On 6/2/2018 1:49 : 00 PM Acquisition Started 6/2/2018 1:49: 51 PM Live Time 600 . 0 sec onds Real Time 600.5 sec onds Dead Time 0 .08 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration used Done On 5/30/2018 Efficiency ID 1.5M90DSFP 2IN [250]

Peak Analysis Report 6/2/2018 1:59:52 PM Page 2

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

Detector Name: 5456-A Sample

Title:

Bl03202AFSFC026GD Peak Analysis Performed on: 6/2/2018 1:59:52 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 1 126- 135 130.16 32.54 0.36 4.53E+001 22.91 3.17E+001 2 285- 307 3 01. 25 75.31 0.91 4.36E+002 100.16 5.34E+002 3 334- 345 340.75 85.19 0.80 5.29E+001 58.09 3.13E+002 4 947- 960 955.90 238.97 0.62 5.67E+001 34.47 8.73E+001 5 1178- 1190 1183.22 295.80 0.37 4.06E+001 25.13 4 .44E+001 6 1400- 1415 1408.37 352.09 1.24 7.48E+001 28 .43 4.22E+001 7 2329- 2340 2334.48 583.62 0.58 1.50E+001 17.33 2.40E+001 8 2430- 2446 2437.98 609.49 0.93 6.43E+001 25.09 2.98E+001 9 2638- 2655 2647.90 661.97 0.86 l.52E+002 30 .16 2.28E+001 10 3640- 3653 3646.81 911.70 0.33 3.14E+001 14.84 8.64E+OOO 11 3871- 3884 3877.47 969.37 0.56 2.59E+001 13.59 7.14E+OOO 12 4686- 4705 4695.74 1173.94 1. 66 l.17E+002 26.66 1. 75E+001 13 5324- 5344 5334.81 1333.70 1. 24 1.03E+002 22.95 7.86E+OOO 14 5836- 5859 5847.81 1461.95 2.04 1.76E+002 26.53 O.OOE+OOO 15 7058- 7073 7065.51 1766.38 0 .33 2.90E+001 10.77 O.OOE+OOO M = First peak in a mul tiplet region m = Other peak in a mul tiplet region F = Fitted singlet Errors quoted at 2.000 sigma [251]

Interference Corrected Activity Report 6/2/2018 1:59:52 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:

B103202AFSFC026GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * * * * * ..,,.

• r * * * * ,..
• r,..
• IDENTIFIED NUCLIDES * *
• T _. .. * * *
• e
• r
• II * * * * ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.998 146 0.82* 10.66 1 .20493E+006 2.09630E+005 Co-60 0.998 11 73.23* 99.85 7.61919E+004 1.84690E+004 1332.49* 99.98 7.15344E+004 1.69123E+004 Cs-137 1. 000 661.66* 85.10 8.91146E+004 2.06495E+004 Eu- 155 0.346 86.55* 30.70 4.16315E+004 4.64562E+004 10 5.31 21. 10 Tl-208 1.000 583.19* 85. 00 8.29477E+003 9.63241E+003 Pb-212 1 . 000 238.63* 43.60 3.90981E+004 2.46112E+004 Bi-214 0 . 704 609.32* 45.49 6.77375E+004 2.76727E+004 1120.29 14.92 1764.49* 15. 30 1.54907E+005 5.88539E+004 Pb-214 1 . 000 295.22* 18.42 7.37726E+004 4.72059E+004 351.93* 35.60 7.68513E+004 3.16881E+004 Ac-228 0.588 338.32 11.27 911.20* 25.80 7.03728E+004 3.38489E+004 968.97* 15.80 9.76042E+004 5.20254E+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

[252]

Interference Corrected Activity Report 6/2/2018 1 :59:52 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 0.998 1 .204934E+006 2.096300E+005 Co-60 0.998 7.365862E+004 1.247290E+004 Cs-137 1. 000 8.911464E+004 2.064951E+004 Eu-155 0.346 4.163153E+004 4.645623E+004 Tl-208 1. 000 8.294772E+003 9.632411E+003 Pb-212 1 .000 3.909805E+004 2.461120E+004 Bi-214 0.704 8.351994E+004 2.504258E+004 Pb-214 1 .000 7.589494E+004 2.631003E+004 Ac-228 0 .588 7.847174E+004 2.837232E+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

[253]

Interference Corrected Activity Report 6/2/2018 1 :59:52 PM Page 5

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

Peak Locate Performed on: 6/2/2018 1 :59:52 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peal: Tol. No. (keV) Counts per Second  % Unc ertainty Type Nuclide 1 32.54 7.5574E-002 50.53 2 75.31 7.2741E-001 22.95 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 6/2/2018 1:59:52 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC026GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/M"'2 ) (pCi/M"'2 ) (pCi/MA2) (pCi/MA2 )

 +      K-40       1460.82*    10.66  1. 8 53E+O 04   l .85E+004   1. 205E+006 O.OOOE+OOO
 +      Co-60      1173.23*    99.85  1. 8 60E+O 04   1 .41E+004   7.619E+004  8.414E+003 1332.49*    99.98  1.406E+004                   7.153E+004  6.090E+003 Nb-94       702.65     99. 81 1. 8 lOE+O 04   1 .81E+004  -8.059E+003  8.357E+003 871. 0 9   99.89  2.016E+004                  -1 .033E+004 9.313E+003 Ag-108m     433.90     90.50  2.280E+004      2.28E+004    2.608E+004  1 .080E+004 614.30     89.80  3.085E+004                   1 .887E+003 1 .470E+004 722.90     90.80  2.282E+004                   2.782E+003  1 .064E+004 cs-134      604.72     97.62  2.749E+004      2.36E+004   -3.779E+003  1 .308E+004 795.86     85.46  2.362E+004                   4.143E+003  1 .095E+004
 +      Cs-137      661.66*    85.10  l.829E+004      1.83E+004    8.911E+004  8.355E+003 Eu-152      121.78     28.67  9.440E+004      7.03E+004   -4.111E+003  4.607E+004 344.28     26.60  8.613E+004                  -2.758E+003  4.123E+004 1408 . 01   21.07  7.030E+004                   2.595E+004  3.056E+004 Eu-154      123.07     40 .40 6.715E+004      5.33E+004    5.376E+003  3.277E+004 723.30     20.06  1 .033E+005                 -5.944E+003  4.816E+004 1274.43     34.80  5.329E+004                   2.487E+004  2.401E+004
 +      Eu-155       86 . 55*  30. 70 7.492E+004      7.49E+004    4.163E+004  3.639E+004 105.31     21. 10 l .405E+005                 -6.361E+002  6.870E+004
 +      Tl-208      583.19*    85. 00 1. 559E+004     1.56E+004    8.295E+003  7.049E+003 Bi-212      727.33      6.67  3.115E+005      3. 1 2E+005  1 .333E+005 1 .452E+005
 +      Pb-212      238 . 63*  43.60  3.707E+004      3.71E+004    3.910E+004  1 .760E+004
 +      Bi-214      609.32*    45.49  3.632E+004      l .4SE+004   6.774E+004  1 .673E+004 1120 .29    14.92  1.579E+005                   1. 310E+005 7.318E+004 1764 .49*   15.30  1.445E+004                   1.549E+005  O.OOOE+OOO
 +      Pb-214      295.22*    18.42  6.973E+004      4.09E+004    7.377E+004  3.241E+004 351.93*    35.60  4.090E+004                   7.685E+004  1.906E+004 Ra-226      186.21      3.64  6.471E+005      6. 4 7E+005  3.458E+005  3.137E+005
 +      Ac-228      338.32     11.27  2.032E+005      4 .20E+004   1. 030E+005 9.730E+004 911.20*    25.80  4.202E+004                   7.037E+004  1.798E+004 968.97*    15.80  6.620E+004                   9.760E+004  2.800E+004 Am-241       59 . 54   35.90  8.899E+004      8.90E+004   -1.750E+004  4.342E+004
       +=Nuclide identified during the nuclide i dentification
       *=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]

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

Filename: 5456-A Report Generated On 6/2/2018 9:26:49 AM Sample Title B103202AFSFC027GD Sample Description SFP/TRANSFER CANAL Sample Identification 027 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.260E+001 MA2 Sample Taken On 6/2/2018 9:16: 00 AM Acquisition Started 6/2/2018 9:16:46 AM Live Time 600.0 seconds Real Time 601. 0 seconds Dead Time 0 . 17 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 2M90DSFP 2IN [256]

Peak Analysis Report 6/2/2018 9:26:49 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC027GD Peak .Analysis Performed on: 6/2/2018 9:26:48 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 1 126- 156 129.77 32.44 0 .83 8.20E+002 l05.68 3.33E+002 2 281- 307 300.96 75.24 0 .95 7.28E+002 l56.59 1. 23E+003 3 336- 345 340.16 85.04 1. 50 l .44E+002 72.77 5.18E+002 4 2325- 2339 2331.84 582.96 0.58 3.43E+001 24.45 3.97E+001 5 2428- 2443 2435.97 608.99 0.54 5.92E+001 28 .49 4.78E+001 6 2633- 2658 2645.52 661.38 1.45 7.29E+003 174.07 6.79E+001 7 4680- 4703 4691.72 1172.93 1. 65 3.21E+002 40.95 2.43E+001 8 5318- 5340 5329.18 1332.30 1.43 2.81E+002 35. 52 8.73E+OOO 9 5833- 5852 5842.85 1460.71 2.01 1.41E+002 25.79 7. 33E+OOO M = First peak in a mul t iplet region m Other peak in a mul t iplet region F

 - Fitted singlet Errors quoted at    2.000 sigma

[257]

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Sample

Title:

B103202AFSFC027GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB 11 * * * * * *

• I
• I * *
• t. * * ... " IDENTIFIED NUCLIDES * * * * * * * * * * * * * * * ,a *
• I
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1 460.82* 10 .66 9.61232E+005 l.95021E+005 Co-60 1.000 1 173.23* 99.85 2.09303E+005 3.15383E+004 1332.49* 99.98 1.94837E+005 2.91292E+004 Cs-137 1 .000 661.66* 85.10 4.24516E+006 5.19797E+005 Eu- 155 0.346 86.55* 30.70 1. 13974E+005 6.17902E+004 105.31 21.10 Tl-208 1.000 583.19* 85 .00 1.88321E+004 l.36190E+004 Bi-214 0.438 609.32* 45.49 6.20153E+004 3.07702E+004 1120.29 14.92 176 4.49 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

[258]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 9.612322E+005 1.950205E+005 Co-60 1.000 2.014965E+005 2.139850E+004 Cs-137 1.000 4.245165E+006 5.197974E+005 Eu-155 0.346 1.139742E+005 6.179016E+004 Tl-208 1.000 1.883215E+004 1.361904E+004 Bi-214 0.438 6.201532E+004 3.077020E+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

[259]

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Peak Locate Performed on: 6/2/2018 9:26:48 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 32.44 1. 3671E+OOO 12.88 2 75.24 1. 2134E+OOO 2 1 .51 M ""' First peal:: in a multiplet region m == Other peak in a multiplet region F == Fitted singlet Errors quoted at 2 . 000 sigma [260]

.Nuclide MDA Report 6/2/2018 9:26:49 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC027GD 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 1.324E+005      1 .32E+005   9.612E+005  S.694E+004
 +      co-60      1173.23*     99.85  2.308E+004      1.52E+004    2.093E+005  1 .066E+004 1332.49*     99.98  1.521E+004                   1 .948E+005 6.666E+003 Nb-94       702. 6 5    99. 81 1.994E+004      1.99E+004   -7.006E+003  9.277E+003 871. 0 9    99.89  2.197E+004                  -1. 210E+004 1 .023E+004 Ag-108m     433.90      90.50  5.35SE+004      2.34E+004   -4.787E+003  2.617E+004 614.30      89.80  3.913E+004                   4.184E+003  1 .884E+004 722.90      90.80  2.336E+004                   7.543E+003  1 .091E+004 Cs-134      604.72      97.62  3.467E+004      2.76E+004   -1 .303E+003 1.668E+004 795.86      85.46  2.765E+004                   1 .822E+004 l.297E+004
 +      Cs-137      661.66*     85. 10 3.408E+004      3.41E+004    4.245E+006  1.625E+004 Eu-152      121 .78     28.67  1.536E+OOS      8. 1 4E+004  S.132E+004  7.568E+004 344.28      26.60  1.581E+005                  -1 .188E+OOS 7.723E+004 1408 .01     21.07   8.141E+004                  4.703E+004  3.612E+004 Eu-154      123.07      40. 40 1. 0 97E+O 05   5.32E+004    4.500E+004  5.405E+004 723.30      20.06  1. 0 72E+O 05                4.435E+004  5.011E+004 1274.43      34.80   5.324E+004                  2.484E+004  2.399E+004
 +      Eu-155        86 .5 5*  30.70   9.131E+004     9.13E+004    1.140E+005  4 .459E+004 105.31      21. 10 2.144E+OOS                  -2.886E+005  1.057E+005
 +      Tl-208      583.19*     85.00   2.088E+004     2.09E+004    1.883E+004  9.696E+003 Bi-212      727.33       6.67   3.253E+005     3.25E+005   -3.521E+005  l.522E+005 Pb-212      238.63      43.60  1 .022E+005     1.0 2E+005   5.684E+004  5.015E+004
 +      Bi-214      609.32*     45.49  4.417E+004      4.42E+004    6.202E+004  2.067E+004 1120 .29     14.92  1.813E+005                  -8.312E+004  8.486E+004 1764.49      15.30  1.455E+005                   1.491E+005  6.554E+004 Pb-214      295.22      18.42   2. 373E+005    1.24E+005    1.165E+005  1 .162E+005 3 51. 93    35.60  1.238E+005                   4.620E+004  6.054E+004 Ra-226      186.21       3.64  1.227E+006      1.23E+006    1.136E+004  6.037E+OOS Ac-228      338.32      11.27   3.740E+005     1. 1 SE+005  1.520E+005  1 .827E+005 911. 20     25.80   1 .149E+005                -4.127E+004  5.442E+004 968.97      15.80   1 .721E+005                 8.014E+004  8.095E+004 Am-241        59.54     35.90   1.297E+005     1.30E+005    l. 037E+005 6.378E+004
       +=Nuclide identified during the nuclide identification
       *=Energy line found in the spectrum
       > ~ Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @=Half-life too short to be able to perform the decay correction

[261]

• • • • • GAMMA S P E C T R U M ANALYSIS *****

Filename: 5456-A Report Generated On 6/2/2018 9: 45 :35 AM Sample Title B103202AFSFC028GD Sample Description SFP/TRANSFER CANAL Sample Identification 028 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.260E+001 MA2 Sample Taken On 6/2/2018 9:35:00 AM Acquisition Started 6/2/2018 9:35:34 AM Live Time 600 . 0 seconds Real Time 600.5 seconds Dead Time 0 , 08 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 2M90DSFP 2IN [262]

Peak Analysis Report 6/2/2018 9:4 5 :35 AM Page 2

• • • • • P E A K ANALYS I S RE P O R T *****

Detector Name: 5456-A Sample

Title:

B1 03202AFSFC028GD Peak Analysis Performed on: 6/2/2018 9:45:35 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 1 126- 137 130.10 32.53 1. 13 7.26E+001 34.38 6.94E+001 2 286- 311 301. 55 75.39 1. 32 5.35E+002 116.42 6.71E+002 3 332- 346 339.63 84. 91 0.57 7.67E+001 73.79 4.45E+002 4 505- 514 509.31 127.33 0.59 1. 57E+001 42.64 1.94E+002 5 920- 929 924. 11 231.03 0.48 6.87E+OOO 29.18 9. llE+OOl 6 946- 961 954.78 238.69 0.95 7.28E+001 40. 80 1 .13E+002 7 1399- 1415 1406.77 351.69 1. 04 4.80E+001 35.79 8.70E+001 8 2035- 2048 2042.01 510.50 0.40 2.54E+001 29 .15 6.66E+001 9 2327- 2338 2332. 04 583.01 0.35 2.76E+001 19.00 2.44E+001 10 2428- 2445 2436.43 609.11 1. 40 8.66E+001 23.39 1. 54E+001 11 2635- 2657 2645.43 661.36 1. 25 9.43E+002 64.58 2.56E+001 12 3637- 3650 3643.93 910.98 0 .86 2.91E+001 15.77 1 .19E+001 13 4680- 4702 4691.46 1172.87 1. 81 2.25E+002 32.90 1.16E+001 14 5318- 5340 5328.80 1332.20 1. 35 l.75E+002 28.99 8.82E+OOO 15 5833- 5853 5841.77 1460.44 0.98 1.26E+002 23. 11 2.33E+OOO M First peak in a mult iplet region m = Other peak in a mul t iplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [263]

Interference Corrected Activity Report 6/2/2018 9:45:35 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:

B103202AFSFC028GD 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 8.58605E+005 1 .74616E+005 Co-60 1. 000 1173.23* 99.85 1.47133E+005 2.44862E+004 1332.49* 99.98 1.21347E+005 2.23031E+004 Cs-137 1. 000 661. 66

• 85.10 5.49585E+005 7.59686E+004 Eu-152 0.639 121. 78* 28.67 1.33415E+004 3.63468E+004 344.28* 26.60 6.55487E+004 5.00 8 10E+004 1408.01 21.07 Eu-155 0.346 86.55* 30.70 6.05689E+004 5.95235E+004 10 5 .31 21.10 Tl-208 1.000 583.19* 85.00 1.51457E+004 1.05925E+004 Pb-212 1.000 238.63* 43. 60 5.04852E+004 2. 94532E+004 Bi-214 0.438 609. 32* 45. 49 9.07239E+004 2.68277E+004 11 2 0.29 14.92 1764.49 15.30 Pb-214 0.439 295.22 18.42 351.93* 35.60 4.89774E+004 3.73753E+004

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1 . 000 8.586051E+005 1 .746162E+OOS Co-60 1 . 000 1.330393E+005 1 .648857E+004 Cs-137 1 . 000 5.495846E+005 7.596859E+004 Eu-152 0 .639 1 .334154E+004 3.634654E+004 Eu-155 0 .346 6.056889E+004 5.952353E+004 Tl-208 1 . 000 1 .514572E+004 1.059249E+004 Pb-212 1 . 000 5.048517E+004 2.945318E+004 Bi-214 0 .438 9.072392E+004 2.682771E+004 Pb-214 0 .439 3.900876E+004 4.619977E+004

       ? = Nuclide is part of an undetermined solution x = Nuclide rejected by the interference analysis
      @=Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at    2.000 sigma

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Peak Locate Performed on: 6/2/2018 9:45:34 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.53 1.2107E- 001 47.33 2 75.39 8.9096E- 001 21. 78 5 231. 03 1. 144 6E- 0 02 42 4 .84 8 510.50 4.2409E-002 114.55 12 910.98 4.8435E-002 54.25 Tol. Ac-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted a t 2 . 000 sigma [266]

Nuclide MDA Report 6/2/2018 9:45:35 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

Bl03202AFSFC028GD 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   8.148E+004    8.15E+004   8.586E+005    3.150E+004
 +      Co-60      1173.23*    99. 85  l.619E+004    l.53E+004   1. 471E+005   7.213E+003 1332.49*    99.98   l.534E+004                1. 213E+005   6.731E+003 Nb-94       702.65     99.81   1 .963E+004   1.96E+004  -1. 512E+003   9.124E+003 871.09     99.89   2.077E+004                7.176E+003    9.621E+003 Ag-108m     433.90     90.50   2.921E+004    2.22E+004  -1. 086E+004   1.4DOE+004 614. 3 0   89.80   3.089E+004                9.151E+002    l.472E+004 722.90     90.80   2.220E+004               -2.675E+004    1.033E+004 Cs-134      604.72     97.62   2.905E+004    2.61E+004  -l .916E+004   1.387E+004 795.86     85.46   2.611E+004                l .772E+004   1. 220E+004
 +      Cs-137      661.66*    85. 10  2.065E+004    2.07E+004   5.496E+005    9.539E+003
 +      Eu-152      121.78*    28.67   6.089E+004    6.09E+004   l.334E+004    2.930E+004 344.28*    26.60   7.788E+004                6.555E+004    3.709E+004 1408.01     21. 07  8.311E+004                l.825E+004    3.697E+004 Eu-154      123.07     40.40   7.768E+004    4.87E+004  -3.225E+004    3.803E+004 723.30     20.06   1.028E+005                l.589E+004    4.791E+004 1274.43     34.80   4 .875E+004              -2.160E+003    2.174E+004
 +      Eu-155       86. 5 5*  30.70   9.526E+004    9.53E+004   6.057E+004    4.656E+004 105.31     21.10   1. 543E+005              -6.462E+004    7.561E+004
 +      Tl-208      583.19*    85.00   l.579E+004    1 .58E+004  l.515E+004    7.152E+003 Bi-212      727.33       6.67  3.l44E+005    3.14E+005   5.140E+004    l.467E+005
 +      Pb-212      238.63*    43.60   4.416E+004    4 .42E+004  5.049E+004    2.114E+004
 +      Bi-214      609.32*    45.49   2.726E+004    2.73E+004   9.072E+004    l.221E+004 1120.29     14.92   l.705E+005                4.434E+004    7.945E+004 1764.49     15.30   l.407E+005                1 .384E+005   6.315E+004
 +      Pb-214      295.22     18.42   l.SlOE+OOS    5.82E+004  -l.331E+OD5    7.306E+004 351.93*    35.60   5.819E+004                4 .898E+OD4   2.771E+004 Ra-226      186.21       3.64  7.867E+OOS    7.87E+005   2.031E+004    3.834E+005 Ac-228      338.32     11. 27  2.392E+005    1.01E+005  -7.966E+004    1 .153E+OOS 911.20     25.80   1. 012E+005               1. 3 96E+O 04 4.756E+004 968.97     15.80   1. 749E+OOS               2.686E+005    8.235E+004 Am-241       59 . 54   35.90   1. OOOE+OOS   l. OOE+OOS  3.501E+004    4.892E+004
       + - Nuclide identified during the nuclide identification
       * = Energy line found in the spectrum
       >=Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @ ~ Half-life too short to be able to perform the decay correction

[267]

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

Filename: C:\GENIE2K\CAMFILES\00005003.CNF Report Generated On 6/8/2018 10 :33:15 AM Sample Title B103202AFSFC029GD Sample Description Spent Fuel Pad Floor Sample Identification Sample Type Gamma Direct Sample Geometry 2M90DSFP 2IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.260E+001 M... 2 Sample Taken On 6/8/2018 8:47:00 AM Acquisition Started 6/8/2018 8:47:05 AM Live Time 600. 0 seconds Real Time 600.5 seconds Dead Time 0.09 % Energy. Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 2M90DSFP 2IN [268]

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

Detector Name: 5456-A sample

Title:

B103202AFSFC029GD Peak Analysis Performed on: 6/8/2018 10:33:15 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 137 129.99 32.50 0.55 8.50E+001 30.34 5.00E+OOl 2 284- 311 301.03 75.26 1. 00 4.88E+002 l17.69 6.61E+002 3 330- 345 340.81 85.20 1. 31 7.85E+001 74.33 4.34E+002 4 822- 833 826.57 206.64 0.56 l .54E+001 35.73 1 .18E+002 5 951- 960 955. 00 238.75 1. 14 4.24E+001 31. 97 9.26E+001 6 1403- 1415 140 8. 00 352. 00 0.94 4.56E+001 30.43 6.94E+001 7 2427- 2443 2436. 14 609. 04 0.42 7.09E+001 24.92 2.71E+001 8 2637- 2656 2645.80 661.45 1. 54 7.53E+002 59.95 4.16E+001 9 4682- 4703 469 1 .92 1172.98 1. 63 1.83E+002 28.71 5.81E+OOO 10 5319- 5341 5329.49 1332.37 1. 61 1.67E+002 28.19 8.40E+OOO 11 5834- 5855 5843.35 1460.84 1. 28 1.29E+002 25.15 7.87E+OOO M = First peak in a mu ltiplet region m = Other peak in a mu ltiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [269]

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Sample

Title:

B103202AFSFC029GD 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 8.82404E+005 l.88159E+OOS Co-60 1.000 1173.23* 99.85 1.19566E+005 2.10390E+004 1332.49* 99.98 1.15412E+005 2.16020E+004 Cs-137 1.000 661.66* 85.10 4.38913E+005 6.32301E+004 Eu-155 0.347 8 6.55* 30.70 6.18892E+004 5.99088E+004 105.31 21.10 Pb-212 1. 000 238.63* 43.60 2.94162E+004 2.26807E+004 Bi-214 0 .438 609.32* 45.49 7 . 42858E+004 2.75984E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.439 295.22 18.42 351.93* 35.60 4 .66283E+004 3.19684E+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

[270]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M ... 2 ) Uncertainty K-40 1.000 8.824036E+OOS 1 .881590E+005 Co-60 1.000 1.175437E+005 1 .507193E+004 Cs-137 1.000 4.389135E+OOS 6.323007E+004 Eu-155 0. 347 6.188918E+004 5.990883E+004 Pb-212 1.000 2.941617E+004 2.268067E+004 Bi-214 0. 438 7.428583E+004 2.759843E+004 Pb-214 0. 439 4.662830E+004 3.196843E+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

[271]

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Peak Locate Performed on: 6/8/2018 10 :33 :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 32.50 1. 4168E-001 35.69 2 75.26 8.1314E-001 24.12 4 206.64 2.5689E-002 23 1 .84 M - First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [272]

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Detector Name: 5456-A Sample Geometry: 2M90DSFP 2IN Sample

Title:

B103202AFSFC029GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/MA2 )

 +      K-40       1460.82*   10 .66 l.395E+OOS     1.40E+005     8.824E+005    6.051E+004
 +      Co-60      1173.23*   99.85  l.204E+004     l.20E+004     l.196E+005    5.136E+D03 1332.49*   99.98  1. 4 79E+004                 l.154E+005    6.455E+D03 Nb-94       702.65    99.81  2.054E+004     l.99E+004     1.011E+004    9.577E+D03 871.09    99.89  l.985E+004                 - l.613E+004    9.165E+D03 Ag-108m     433.90    90.50  2.843E+004     2. 4 0E+004 -2.552E+004     1.361E+D04 614.30    89.80  3.368E+004                 -2.892E+004     1.612E+D04 722.90    90.80  2.399E+004                   3.270E+003    1.122E+D04 Cs-134      604.72    97.62  3.066E+004     2.01E+004     1. 338E+004   l.467E+D04 795.86    85.46  2.005E+004                 -3.021E+004     9.171E+003
 +      Cs-137      661.66*   85.10  2.466E+004     2.47E+004     4.389E+005    1.154E+004 Eu-152      121. 78   28.67  l.079E+005     6.60E+D04     7.952E+004    5.279E+D04 344.28    26.60  9.682E+004                 -4.762E+004     4.658E+004 1408.01    21.07  6.601E+004                   l. 538E+004   2.842E+004 Eu-154      123.07    40. 40 7.608E+004     4.78E+004     4.5061;!:+004 3.723E+D04 723.30    20.06  1 .100E+005                  8.818E+004    5.152E+D04 1274.43    34.80  4.779E+004                   1. 120E+004   2.126E+004
 +      Eu-155       86.55*   30.70  9.578E+004     9.58E+004     6.189E+004    4.682E+004 105.31    21.10  1 .565E+005                  4.732E+004    7.672E+D04 Tl-208      583.19    85.00  2.901E+004     2.90E+004   -1. 973E+003    1.376E+004 Bi-212      727. 3 3   6.67  3.253E+005     3.25E+005     l. 473E+005   l.522E+005
 +      Pb-212      238.63*   43.60  3.519E+004     3.52E+004     2.942E+004    1.666E+D04
 +      Bi-214      609.32*   45.49  3.450E+004     3.45E+004     7.429E+004    1. 583E+004 1120 . 29  14.92  l.754E+005                   l.386E+005    8.190E+004 1764.49    15.30  1.383E+005                   4.259E+004    6.193E+004
 +      Pb-214      295.22    18.42  l.427E+005     4.86E+OD4     1.058E+005    6.891E+004 351.93*   35.60  4.858E+004                   4. 663E+004   2.291E+004 Ra-226      186.21      3.64 7.735E+005     7.74E+D05     4. 241E+005   3.768E+005 Ac-228      338.32    11. 27 2.354E+005     1.01E+005     2.726E+005    l.134E+005 911.20    25.80   l .006E+005                 4. 186E+004   4.728E+OD4 968.97    15 .80 1. 487E+005                  1. 399E+D05   6.929E+OD4 Am-241       59.54    35.90   9.587E+004    9.59E+004   -4.748E+OD4     4.685E+004
       + ~ Nuclide identified during the nuclide i dentification
       * ~ Energy line found in the spectrum
       >=Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @ ~ Half-life too short to be able to perform the decay correction

[273]

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

Filename: 5456-A Report Generated On 6/8/2018 9: 10 :34 AM Sample Title Bl03202AFSFC030GD Sample Description Spent Fuel Pad Floor Sample Identification Sample Type Gamma Direct Sample Geometry 2M90DSFP 2IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.260E+001 MA2 Sample Taken On 6/8/2018 9:00:00 AM Acquisition Started 6/8/2018 9:00:32 AM Live Time 600. 0 seconds Real Time 600.5 seconds Dead Time 0. 08 % Energy-Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 2M90DSFP 2IN [274]

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Detector Name: 5456-A Sample

Title:

B1 0 3202AFSFC030GD Peak Analysis Performed on: 6/8/2018 9: 10 :33 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 1 126- 135 129.84 32.46 0.60 3.54E+001 22.11 3.16E+001 2 285- 309 301.11 75.28 0.98 3.70E+002 106.85 6.01E+002 3 1305- 1315 1310. 14 327.54 0.55 1.54E+001 22.62 4.46E+001 4 1400- 1414 1408. 07 352.02 0.44 5.77E+001 30 . 91 6.23E+001 5 2429- 2445 2436.30 609.07 0.62 6.29E+001 25.30 3.llE+OOl 6 2636- 2656 2646 .14 661.53 1.52 7.19E+002 60.27 5.23E+001 7 3638- 3651 364 4 .28 911. 07 0.77 1 .47E+001 13.98 1.23E+001 8 4684- 4702 4692 .00 1173.00 0.47 8.17E+001 22 .35 1.23E+001 9 5321- 5339 5329.56 1332.39 1.43 1 .00E+002 22.77 8.98E+OOO 10 5833- 5854 5844.02 1461. 00 1. 95 l .57E+002 25.84 2.62E+OOO 11 7052- 7067 7059.09 1764.77 0.30 2.70E+001 10.39 O.OOE+OOO M = First peak in a mul t iplet region m = Other peak in a mul t iplet region F "' Fitted singlet Errors quoted at 2.000 sigma [275]

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Sample

Title:

B103202AFSFC030GD Nuclide Library Us ed: C:\GENIE2K\CAMFILES\Z ion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1 .000 1460.82* 10.66 l.07551E+006 l.99767E+OOS Co-60 1 .000 1173.23* 99.85 5.33522E+004 1.51972E+004 13 32.49* 99.98 6.92848E+004 l.67213E+004 Cs-137 1.000 661.66* 85. 10 4. 18737E+005 6.13321E+004 Bi-214 0.705 609.32* 45.49 6.59591E+004 2.76673E+004 11 20.29 14 .92 1764.49* 15.30 l.43760E+005 5.65186E+004 Pb-214 0.439 295.22 18.42 351. 93* 35.60 5.89152E+004 3.29609E+004

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

[276]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 1. 0 75512E+O 06 1.997666E+OOS Co-60 1. 000 6.055946E+004 1.12463SE+004 Cs-137 1. 000 4.187371E+OOS 6.133206E+004 Bi-214 0. 705 8.099886E+004 2.484960E+004 Pb-214 0. 439 5.891521E+004 3.296091E+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 a t 2. 000 sigma

[277]

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Peak Locate Performed on: 6/8/2018 9: 10 :33 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.46 5.8943E-002 62.51 2 75.28 6.1612E-001 28.90 3 327.54 2.5667E-002 146.91 7 911.07 2.4475E-002 95.17 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 [278]

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Detector Name: 5456-A Sample Geometry: 2M90DSFP 2IN Sample

Title:

B103202AFSFC030GD 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   8.798E+004    8.80E+004    1. 0 76E+006  3.475E+004
 +      Co-60      1173.23*   99.85   l.586E+004    1.43E+004    5.335E+004    7.049E+003 1332.49*   99.98   1 .428E+004                6.928E+004    6.204E+003 Nb-94       702 . 65  99.81   l .835E+004   1.83E+004    2.936E+003    8.483E+OD3 871 . 09  99.89   1 .966E+004                1. 231E+002   9.071E+003 Ag-108m     433.90    90.50   3.107E+004    2.32E+004    1 .341E+004   1.493E+004 614 .30   89.80   3.078E+004                -7.309E+003    1.467E+OD4 722.90    90.80   2.319E+004                -4.286E+003    l.083E+004 Cs-134      604.72    97.62   2.951E+004    2.21E+004   -8.558E+003    1.409E+004 795.86    85.46   2.206E+004                 3.465E+003    1.017E+D04
 +      Cs-137      661.66*   85.10   2.795E+004    2.79E+004    4.187E+005    1.319E+D04 Eu-152      121 .78   28.67   1. 022E+OOS   7. 42E+004   2.420E+004    4.997E+004 344.28    26.60   9.357E+004                -2.611E+004    4.495E+004 1408.01    21. 07  7.417E+004                 4.235E+003    3.250E+D04 Eu-154      123.07    40.40   7.155E+004    4.87E+004    l.150E+004    3.496E+004 723.30    20.06   1.050E+005                 3.604E+004    4.902E+004 1274.43    34.80   4.875E+004                 9.319E+002    2.174E+004 Eu-155       86. 5 5  30.70   l.168E+005    1. 1 7E+OOS  l.D85E+005    5.734E+D04 105.31    21.10   1 .500E+005                1.202E+005    7.344E+004 Tl-208      583.19    85.00   3.040E+004    3.04E+004    2.829E+004    1 .446E+004 Bi-212      727.33      6.67  3.210E+005    3.21E+005    2.182E+004    1 .500E+005 Pb-212      238.63    43.60   6.420E+004    6.42E+004    3.156E+004    3.116E+004
 +      Bi-214      609.32*   45.49   3.679E+004    1.44E+004    6.596E+004    1.698E+004 1120.29    14.92   1.520E+005                 8.325E+004    7.023E+004 1764.49*   15.30   1. 441E+004                1. 43 8E+O 05 O.OOOE+OOO
 +      Pb-214      295.22    18.42   1. 430E+005   4.80E+004    8.676E+004    6.904E+004 351.93*   35.60   4.802E+004                 S.892E+004    2.263E+OD4 Ra-226      186.21      3.64  7.066E+005    7.07E+005    2.760E+005    3.433E+005 Ac-228      338.32    1 1. 27 2.226E+005    9.35E+004    8.064E+004    1.070E+005 911. 20   25.80   9.349E+004                -1. 246E+004   4.372E+004 968.97    15.80   l .361E+005                1. 057E+O 04  6.295E+004 Am-241       59.54    35.90   9.580E+004    9.58E+004    5.523E+004    4.682E+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

[279]

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

Filename: 5456-A Report Generated On 6/8/2018 9:21:45 AM Sample Title B103202AFSFC031GD Sample Description Spent Fuel Pad Floor Sample Identification Sample Type Gamma Direct Sample Geometry 2M90DSFP 2IN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 6/8/2018 9:11:00 AM Acquisition Started 6/8/2018 9:11:43 AM 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 5/30/2018 Efficiency ID 2M90DSFP 2IN [280]

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Detector Name: 5456-A Sample

Title:

B10 3202AFSFC031GD Peak Analysis Performed on: 6/8/2018 9: 21 :45 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 1 126- 133 129.48 32.37 0.71 1.96E+001 20.59 3.14E+001 2 283- 305 300.94 75.23 1.17 3.62E+002 96.50 5.07E+002 3 950- 959 954.90 238.73 0.27 2.42E+001 28 .22 7.68E+001 4 1174- 1188 1180.63 295.16 0.41 3.57E+001 33.02 8.23E+001 5 1402- 1415 1407.63 351.91 0.98 7.94E+001 27. 89 4.16E+001 6 1697- 1708 1702.15 425.54 0.76 1.36E+001 20. 72 3.64E+001 7 2326- 2339 2332.05 583.01 0.65 2.14E+001 18.65 2.36E+001 8 2428- 2445 2436.07 609.02 1. 28 7.82E+001 26.20 2.88E+001 9 2635- 2655 2645.25 661.31 1. 53 7.06E+002 57.95 3.68E+001 10 3867- 3880 3873.16 968.29 0.68 8.93E+OOO 13.00 1.21E+001 11 4681- 4700 46 90 .96 1172. 74 2.02 1.28E+002 25.53 9.96E+OOO 12 5320- 5339 5328.20 1332.05 1. 20 1.16E+002 23.71 7.20E+OOO 13 5831- 5854 5842.36 1460 .59 1. 21 1.82E+002 26.98 O.OOE+OOO 14 7050- 7065 7057.72 1764.43 0.63 2.30E+001 9.59 O.OOE+OOO M = First peak in a multiplet region m ; Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [281]

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Sample

Title:

B103202AFSFC031GD 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 1.24357E+006 2.13658E+005 Co-60 1 . 000 1173.23* 99.85 8.35635E+004 1. 79545E+004 1332.49* 99.98 8.02125E+004 1.76338E+004 Sb-125 0 .671 427.87* 29.60 1 .83851E+004 2.81289E+004 600.60* 17.65 2. 11142E+005 7.53018E+004 635.95 11.22 Cs-137 1 .000 661.66* 85.10 4.11412E+005 5.98383E+004 Tl-208 1.000 583.19* 85.00 1.17594E+004 1 .03414E+004 Pb-212 1. 000 238.63* 43.60 1.67953E+004 1.97591E+004 Bi-214 0.705 609.32* 45.49 8.19224E+004 2.91693E+004 1120.29 14. 92 1764.49* 15.30 1.22449E+005 5.19980E+004 Pb-214 1. 000 295.22* 18.42 6.47755E+004 6.08467E+004 351.93* 35.60 8.11135E+004 3.13057E+004

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2) Uncertainty K-40 1.000 1. 243572E+006 2.136575E+005 Co-60 1.000 8.185782E+004 1 .258082E+004 X Ag-108m 0.442 Sb-125 0.671 1. 44 0184E+O 04 2.766902E+004 Cs-137 1. 000 4.114117E+005 5.983832E+004 Tl-208 1. 000 1. 175937E+O 04 l .034143E+004 Pb-212 1. 000 1. 67952BE+004 l .975912E+004 Bi-214 0 .705 8.737003E+004 2.671465E+004 Pb-214 1. 000 7.769387E+004 2.783736E+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 a t  2. 000 sigma

[283]

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Peak Locate Performed on: 6/8/20 18 9:21 :45 AM Peak Locate From Channel : 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32 . 37 3.2712E-002 104.90 2 75.23 6.0319E-001 26.66 10 968.29 1. 4881E-002 145.58 Sum M m

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

[284]

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Detector Name: 5456-A Sample Geometry: 2M90DSFP 2IN Sample

Title:

B103202AFSFC031GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

 +      K-40       1460.82*   10.66  l. 849E+004   1.85E+004     1.244E+006  O.OOOE+OOO
 +      Co-60      1173.23*   99.85  l. 446E+004   1.32E+004     8.356E+004  6.346E+003 1332.49*   99.98  1. 322E+004                 8.021E+004  5.671E+003 Nb-94       702.65    99.81  l. 714E+004   1.71E+004    -3.342E+003  7.879E+003 871. 09   99.89  2.059E+004                  6.613E+003  9.532E+003 Ag-108m     433.90*   90.50  1. 527E+004   1.53E+004     6.013E+003  7.036E+003 614.30*   89.80  1. 832E+004                 4. 150E+004 8.442E+003 722.90    90.80  2.043E+004                 -5.0l4E+003  9.447E+003 Cs-134     604.72    97.62  3.031E+004    2.23E+004    -5.414E+002  l.450E+004 795.86    85.46  2.227E+004                 -3.788E+003  1.028E+004
 +       Cs-137     661.66*   85. 10 2.370E+004    2.37E+004     4. 114E+005 1.106E+004 Eu-152      121.78    28.67  l.002E+005    6.60E+004    -5.488E+002  4.896E+004 344.28    26.60  9.682E+004                 -3.731E+004  4.658E+004 1408.01    21.07  6.601E+004                 -2.971E+004  2.842E+004 Eu-154      123.07    40.40  7.150E+004    4.87E+004     5.648E+003  3.494E+004 723.30    20.06  9.251E+004                 -4.418E+004  4.277E+004 1274.43    34.80  4.875E+004                  1.510E+004  2.174E+004 Eu-155      86.55    30.70  1 .104E+005   1. l OE+O 05  l.189E+005  5.412E+004 105.31    21.10  1 .461E+005                 1.102E+005  7.150E+004
 +       Tl-208     583.19*   85.00  1 .612E+004   1.61E+004     1.176E+004  7.316E+003 Bi-212      727.33     6.67  2.839E+005    2.84E+005     1.541E+005  1 .315E+OOS
 +       Pb-212     238. 63*  43.60  3.205E+004    3.21E+004     1. 680E+004 1 .509E+004
 +       Bi-214     609.32*   45.49  3.617E+004    1.44E+004     8.192E+004  1 .666E+004 1120.29    14.92  1.492E+005                 -2.170E+004  6.881E+004 1764.49*   15.30  1.441E+004                  l.224E+005  O.OOOE+OOO
 +       Pb-214     295.22*   18.42  9.686E+004    3.8BE+004     6.47BE+004  4.597E+004 351.93*   35.60  3.881E+004                  B.111E+004  1.802E+004 Ra-226     186.21      3.64 7 .126E+005   7 .1 3E+005   7.591E+OOS  3.463E+005 Ac-228      338.32    11. 27 2.340E+005    9.53E+004     2.710E+005  1.127E+005 911.20    25.80   9.531E+004                 7.221E+004  4 .464E+004 968.97    15.80  1 .443E+005                 1 .180E+005 6.705E+004 Am-241       59.54    35.90   9.317E+004   9.32E+004    -2.309E+003  4 .550E+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

[285]

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

Filename: 5456-A Report Generated On 6/6/2018 3: 01: 48 PM Sample Title B103202AFSFC032GD Sample Description SFP/TRANSFER CANAL Sample Identification 032 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 6/6/2018 2:51: 00 PM Acquisition Started 6/6/2018 2:51:45 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 5/30/2018 Efficiency ID 2M90DSFP 2IN [286]

Peak Analysis Report 6/6/2018 3: 01 :48 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC032GD Peak Analysis Performed on: 6/6/2018 3: 01 :47 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 1 126- 133 129.44 32.36 0.69 2.35E+001 22.05 3.65E+001 2 284- 307 300.85 75.21 0.94 3.67E+002 lll.41 6.84E+002 3 430- 439 434.36 108.59 0.48 3.96E+OOO 44.74 2.19E+002 4 949- 959 954.18 23 8. 55 0.58 3.47E+001 33.07 l .OOE+002 5 1400- 1412 1406.33 351.58 1. 05 5.lOE+OOl 27.39 5.lOE+OOl 6 2426- 2444 2434. 61 608.65 0.76 7.29E+001 25.40 2.61E+001 7 2635- 2653 2644.25 661.06 1. 60 7.41E+002 59.76 4. 51E+001 8 3866- 3879 3872.82 968.21 0.32 2.59E+001 13.55 7.06E+OOO 9 4680- 4700 4689.62 1172.41 1.43 1.65E+002 31.91 2.42E+001 10 5316- 5338 5326.99 1331.75 1.44 l .61E+002 27 .22 6.00E+OOO 11 5829- 5850 5839. 12 1459.78 1. 76 l .33E+002 23.90 2.59E+OOO 12 7049- 7064 7056.06 1764.02 0. 29 2.20E+001 9.38 O.OOE+OOO 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 [287]

Interference Corrected Activity Report 6/6/2018 3: 01 : 48 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:

B103202AFSFC032GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.998 1460.82* 10.66 9.11275E+005 l.81413E+005 Co-60 0 .999 1173.23* 99.85 1.07558E+OOS 2.25300E+004 1332.49* 99.98 1 .11503E+OOS 2.08568E+004 Cs-137 0.999 661.66* 85.10 4.31544E+005 6.24295E+004 Pb-212 1 . 000 238.63* 43.60 2.40752E+004 2.32599E+004 Bi-214 0.705 609.32* 45.49 7.63121E+004 2.81389E+004 1120.29 14 .92 1764.49* 15.30 1. 17109E+005 5.08087E+004 Pb-214 0 .439 295.22 18.42 351.93* 35.60 5.21155E+004 2.91854E+004

           * = Energy line f ound in the spectrum.
           @ ~ Energy line not used for Weighted Mean Activity Energy Tolerance :                        10.000 keV Nuclide confidence index threshold                             0 .30 Errors quoted at 2.000 sigma

[288]

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.998 9.112748E+005 1.814129E+OOS Co-60 0.999 1. 096823E+005 1 .530535E+004 Cs-137 0.999 4.315442E+005 6.242948E+004 Pb-212 1.00 0 2.407518E+004 2.325989E+004 Bi-214 0.705 8.588802E+004 2.461592E+004 Pb-214 0.439 5.211552E+004 2.918537E+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

[289]

Interference Corrected Activity Report 6/6/2018 3:01:48 PM Page 5

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

Peak Locate Performed on: 6/6/2018 3: 01 : 47 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % uncertainty Type Nuclide 1 32.36 3.9167E-002 93.85 2 75.21 6.1186E-001 30.35 3 108.59 6.5919E-003 1131. 22 8 968.21 4.3232E-002 52.24 Sum M "" First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [290]

Nuclide MDA Report 6/6/2018 3: 01 :48 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC032GD 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  8.730E+004    8.73E+004   9.113E+OOS   3.441E+004
 +      Co-60      1173.23*   99.85  2.210E+004    1 .31E+004  1 .076E+005  1.017E+004 1332.49*   99.98  1 .310E+004               1. 115E+O 05 5.611E+003 Nb-94       702.65    99.81  1 .835E+004   l .83E+004 -3.579E+003   8.483E+003 871. 09   99.89  2.312E+004                1. SOSE+O 04 1 .080E+004 Ag- 108m    433.90    90.50  2.819E+004    2.34E+004  -1.193E+004   1 .349E+004 614.30    89.80  3.151E+004               -2.460E+004   1.503E+004 722.90    90.80  2.336E+004               -3.044E+003   1.091E+004 Cs-134      604.72    97.62  2.969E+004    2.52E+004   7.271E+003   1.418E+004 795.86    85.46  2.521E+004                7.940E+003   1.175E+004
 +      Cs-137      661.66*   85. 10 2.520E+004    2.52E+004   4.315E+005   1.181E+004 Eu-152      121.78    28.67  1 .089E+005   S.90E+004  -7.961E+004   5.329E+004 344.28    26.60  9.179E+004               -9.907E+004   4.406E+004 1408.01    21. 07 5.902E+004                6.268E+003   2.493E+004 Eu-154      123.07    40.40  7.763E+004    3.92E+004  -8.116E+003   3.801E+004 723.30    20.06  1 .050E+005              -3.461E+004   4.902E+004 1274.43    34.80  3.919E+004               -1.188E+005   1.696E+004 Eu-155       86. 5 5  30.70  1 .222E+005   1 .22E+005  1.064E+005   6.003E+004 105.31    21.10  1 .638E+OOS               6.093E+004   8.035E+004 Tl-208      583.19    85.00  3.074E+004    3.07E+004   1.617E+004   1.463E+004 Bi-212      727.33     6.67  3.210E+005    3.21E+005   3.321E+005   1.500E+OOS
 +      Pb-212      238.63*   43.60  3.712E+004    3.71E+004   2.408E+004   1.762E+004
 +      Bi-214      609.32*   45.49  3.523E+004    1 .44E+004  7.631E+004   1.620E+004 1120.29    14.92  1 .847E+005               1.364E+005   8.658E+004 1764.49*   15.30  1 .440E+004               1.171E+005   O.OOOE+OOO
 +      Pb-214      295.22    18.42  1 .476E+005   4.20E+004   2.771E+004   7.133E+004 351.93*   35.60  4.201E+004                5.212E+004   1.963E+004 Ra-226      186.21     3.64  7.798E+005    7.80E+005   5.590E+005   3.799E+005 Ac-228      338.32    11. 27 2.306E+005    9.89E+004   7.623E+004   1.llOE+OOS 911. 20   25.80  9.886E+004                2.643E+004   4.641E+004 968.97    15.80  1.583E+005                9.813E+004   7.407E+004 Am-241       59.54    35.90  1.053E+005    1. 05E+005  7.222E+004   5.158E+004
       + =Nuclide identified during the nuclide i dentification
       * ~ 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]

• • ~**********************************************************************
    • • • GAMMA S P E C T R U M ANALYSIS *****

Filename: 5456-A Report Generated On 6/8/2018 9:33:31 AM Sample Title B103202AFQFC032GD Sample Description Spent Fuel Pad Floor QC Sample Identification QC Sample Type Gamma Direct Sample Geometry 2M90DSFP 2IN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.260E+001 MA2 Sample Taken On 6/8/2018 9:23: 00 AM Acquisition Started 6/8/2018 9:23:30 AM Live Time 600. 0 seconds Real Time 600.6 seconds Dead Time 0.10 % Energy Calibration Used Dohe On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 2M90DSFP 2IN [292]

Peak Analysis Report 6/8/2018 9:33:31 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFQFC032GD Peak Analysis Performed on: 6/8/2018 9:33:31 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 134 13 0 .28 32.57 0 .88 2.79E+001 22.67 3.61E+001 2 287- 309 3 00 .67 75. 17 0 .76 3.58E+002 103.86 6.00E+002 3 334- 346 339.40 84.85 1. 56 1.20E+002 61.73 3.15E+002 4 952- 966 956.15 239.04 0 .55 4 .75E+001 42.70 1.40E+002 5 1402- 1415 1408 .32 352.08 1. 11 6.20E+001 32.38 7.20E+001 6 2327- 2340 2333.39 583.35 0 .75 2.40E+001 22.66 3.70E+001 7 2430- 2443 2436.33 609.08 0 .69 4.44E+001 25.21 4 .06E+001 8 2635- 2656 2645.57 661.39 1. 31 9.43E+002 66.06 4 . 0lE+OOl 9 3867- 3880 3873.56 968.39 0 .66 1 .13E+001 14.76 1. 57E+001 10 4681- 4704 4691.28 1172.82 2.29 1 .91E+002 30.95 1 . 20E+OD1 11 5319- 5339 5329.70 1332.43 1. 45 1 .55E+002 28.47 1 .32E+D01 12 5831- 5854 5843.63 1460.91 1. 81 l .46E+002 25.13 2.97E+OOO 13 7051- 7066 7058.21 1764.55 0 .89 2.lOE+OOl 13.46 8.00E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [293]

Interference Corrected Activity Report 6/8/2018 9:33:31 AM Page 3

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

Sample

Title:

B103202AFQFC032GD 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 9.97911E+005 1 .92362E+005 Co-60 1.000 1173.23* 99.85 1.24654E+005 2.25297E+004 1332.49* 99.98 1. 07270E+OOS 2.15089E+004 Cs-137 1.000 661.66* 85. 10 5.49295E+005 7.63724E+004 Eu - 155 0.346 86.55* 30.70 9.48303E+004 5.23254E+004 10 5.31 21. 10 Tl-208 1.000 583.19* 85. 00 1.31714E+004 l .25502E+004 Pb-212 1.000 238.63* 43.60 3.29911E+004 3.01109E+004 Bi-214 0.705 609.32* 45.49 4.65035E+D04 2. 70054E+D04 1120.29 14. 92 1764.49* 15.30 l.11806E+005 7.22138E+D04 Pb-214 0.439 295.22 18.42 351.93* 35.60 6.33917E+D04 3.46024E+004

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

[294]

Interference Corrected Activity Report 6/8/2018 9:33 : 31 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 9.979107E+OOS 1.923616E+005 Co-60 1.000 1.1SSS97E+OOS 1.555745E+004 Cs-137 1.000 S.49295SE+OOS 7.637237E+004 Eu-155 0.346 9.483027E+004 S.232538E+004 Tl-208 1.000 1 .317141E+004 1.255019E+004 Pb-212 1.000 3.299107E+004 3.011092E+004 Bi-214 0.705 5.451549E+004 2.529452E+004 Pb-214 0.439 6.339173E+004 3.460237E+004

       ?  = Nuclide is part of an undetermined so lution x   = Nuclide rejected by the interference analysis
      @   - Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at   2. 000 sigma

[295]

Interference Corrected Activity Report 6/8/2018 9:33:31 AM Page 5

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

Peak Locate Performed on: 6/8/2018 9:33: 31 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.57 4.6510E-002 81. 24 2 75 .17 5.9650E-001 29.02 9 968.39 1.8858E-002 130.48 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma [296]

Nuclide MDA Report 6/8/2018 9:33:32 AM Page 6

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

Detector Name: 5456-A Sample Geometry: 2M90DSFP 2IN Sample

Title:

B103202AFQFC032GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec . Level Name (keV) ( %) (pCi/M"2 ) (pCi /M"2 ) (pCi/M"2 ) (pCi/M"2 )

 +      K-40       1460 .8 2*  10. 66 9.594E+004     9.59E+004   9.979E+OOS   3.872E+004
 +      Co-60      1173.23*    99.85  1.673E+004     1 .67E+004  1.247E+005   7.481E+003 1332.49*    99.98  1.763E+004                 1.073E+005   7.878E+003 Nb-94       702.65     99.81  2.209E+004     2.11E+004   2.844E+003   1. 03 6E+004 871. 09    99.89  2.112E+004                 1.18SE+004   9.798E+003 Ag-108m     433.90     90.50  3.085E+004     2.37E+004  -1.895E+004   1.482E+004 614.30     89.80  3.271E+004                -1.257E+004   1.563E+004 722.90     90.80  2.367E+004                 1. 3 70E+004 1.107E+004 Cs-134      604.72     97.62  2.941E+004     2.48E+004   1.700E+003   1.405E+004 795.86     85.46  2.483E+004                 4.419E+003   1.156E+004
 +      Cs-137      661.66*    85.10  2.491E+004     2.49E+004   5.493E+005   1.167E+004 Eu-152      121.78     28.67  1.071E+005     7.61E+004   1.042E+005   5.242E+004 344.28     26.60  1.008E+OOS                -1.398E+OOS   4.856E+004 1408. 01    21. 07  7.605E+004                3.426E+004   3.344E+004 Eu-154      123.07     40.40   7.428E+004    4.87E+004   2.358E+003   3.633E+004 723.30     20.06   1.065E+OOS                7.623E+004   4.975E+004 1274.43     34.80  4.875E+004                 4.04SE+003   2.174E+004
 +      Eu-155       86.55*    30.70   7.714E+004    7.71E+004   9.483E+004   3.750E+004 105.31     21.10   1. 574E+005              -2.222E+004   7.718E+004
 +      Tl-208      583.19*    85.00   1. 996E+004   2. 00E+004  1.317E+004   9.235E+003 Bi-212      727.33      6.67   3.077E+005    3. 08E+005 -2.398E+005   l .433E+OOS
 +      Pb-212      238.63*    43.60  4.802E+004     4.80E+004   3.299E+004   2.307E+004
 +      Bi-214      609.32*    45.49   3.973E+004    3.97E+004   4.650E+004   1.845E+004 1120.29     14.92   1. 615E+005               1.131E+005   7.498E+004 1764.49*    15.30   1.007E+005                1.118E+005   4.316E+004
 +      Pb-214      295.22     18.42   1.527E+OOS    5.03E+004   7.604E+004   7.391E+004 351.93*    35.60   5.031E+004                6.339E+004   2.377E+004 Ra-226      186.21       3.64  7.774E+005    7.77E+005   4.308E+OOS   3.787E+OOS Ac-228      338.32     11.27   2.429E+005    l. OlE+OOS  1. 942E+005  1.172E+OD5 911.20     25.80   1 .012E+005               1. 056E+004  4 .756E+OD4 968.97     15.80   1 .498E+005               7.974E+004   6.984E+D04 Am-241       59.54     35.90   1.00lE+OOS    1.00E+005   2.388E+004   4 .89SE+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 per form the decay correction

[297]

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

Filename: 5456-A Report Generated On 6/6/2018 2: 40: 41 PM Sample Title Bl03202AFSFC033GD Sample Description SFP/TRANSFER CANAL Sample Identification 033 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3 .00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 6/6/2018 2:30: 00 PM Acquisition Started 6/6/2018 2: 30: 38 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 5/30/2018 Efficiency ID 2M90DSFP 2IN [298]

Peak Analysis Report 6/6/2018 2: 4 0 : 41 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC033GD Peak Analysis Performed on: 6/6/2018 2:40: 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 1 126- 135 13 0 .97 32.74 1. 29 4.87E+001 26.80 4 .83E+001 2 282- 307 3 00 .90 75.23 0.78 4 .43E+002 121.67 7.67E+002 3 471- 480 475.30 118.82 0.41 4.89E+OOO 43.08 2.03E+002 4 1175- 1187 1180.21 295.05 0.33 3.02E+001 31. 99 8.58E+001 5 1400- 1414 1407.69 351.92 1.23 6.98E+001 33 .17 7.12E+OD1 6 2427- 2444 2435. 81 608.95 1. 12 7.60E+001 25.66 2.70E+001 7 2634- 2655 2645.03 661.26 1. 44 8.2DE+002 61.43 3.29E+001 8 3636- 3651 3643.06 910 .76 0 .50 3.06E+001 19.97 2.24E+D01 9 3866- 3879 3872.64 968.16 0 .50 2.93E+001 11.68 1.73E+OOO 10 4681- 4701 4690.60 1172.65 1. 87 1.81E+ 002 31.41 1 .82E+001 11 5316- 5338 5327.75 1331.94 1. 09 1.65E+002 28.92 1 .15E+001 12 5831- 5852 584 1. 05 1460.26 1. 35 l.47E+002 25.71 5.09E+OOO 13 7049- 7064 7056.76 1764.19 1. 18 2.70E+001 12.49 4. 00E+OOO M First peak in a multiplet region m == Other peak in a mult iplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [299]

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Sample

Title:

B103202AFSFC033GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  , . . . .. . . ~ ~  . . .. . . . . . .
                                  "'         IDENTIFIED NUCLIDES          * * *.,  * * * * * * * *

• e, I ** * **

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0 .999 1 460.82* 10.66 1 .00367E+006 1.96066E+005 Co-60 0 .999 11 73 .23* 99.85 1. 17979E+O 05 2.25655E+004 1332.49* 99.98 1 .13937E+005 2.20060E+004 Cs-137 1.000 661.66* 85.10 4.77717E+005 6.76140E+004 Eu-152 0.650 121.78* 28.67 4.11987E+003 3.63283E+004 344.28* 26.60 9.53819E+004 4.79749E+004 1408.01 21. 07 Bi-214 0 .705 609.32* 45.49 7.96294E+004 2.85397E+004 1120.29 14.92 1764 .49* 15.30 1.43733E+005 6.74829E+004 Pb-214 1 .000 295.22* 18.42 S.48893E+004 5.87374E+004 351.93* 35.60 7.12685E+004 3.57472E+004 Ac-228 0.588 338.32 11. 27 911.20* 25.80 6.82108E+004 4.4926SE+004 968.97* 15 .80 1 .09772E+005 4.48826E+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 a t                 2.000 sigma

[300]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M~2 ) Uncertainty K-40 0.999 1 .003670E+006 1. 960661E+005 Co-60 0.999 1 .159072E+005 1. 575465E+004 Cs-137 1.000 4.777169E+005 6.761402E+004 Eu-152 0.650 6.520029E+003 3.379051E+004 Bi-214 0.705 8.935527E+004 2.628560E+004 Pb-214 1. 000 6.328669E+004 3.566357E+004 Ac-228 0.588 8.901187E+004 3.175229E+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 a t  2.000 sigma

[301]

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Peak Locate Performed on: 6/6/2018 2: 40 :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 Nuclide 1 32.74 8.1151E-002 55.04 2 75.23 7.3840E-001 27.46 M

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

[302]

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Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC033GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Z ion 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 .147E+005    1.15E+OOS    1.004E+006   4.808E+OD4
 +       Co-60      1173.23*   99.85  1 .919E+004    1.71E+004    1.180E+005   8.710E+OD3 1332.49*   99.98  1 .709E+004                 l.139E+005   7.606E+003 Nb- 94      702. 6 5  99.81  2.154E+004     2.11E+004    l.400E+004   1.008E+004 871. 0 9  99.89  2.112E+004                 -1.477E+004   9.798E+003 Ag- 108m    433.90    90.50  3.056E+004     2.40E+004    5.286E+003   1.468E+004 614.30    89.80  3.281E+004                 -1. 737E+004  1 .568E+004 722.90    90.80  2.399E+004                  6.871E+003   1 .122E+004 Cs-134      604.72    97.62  3.00SE+004     2.14E+004   -1.047E+004   1 .436E+004 795.86    85.46  2.141E+004                 -2.069E+003   9.851E+003
 +       Cs-137      661.66*   85.10  2.285E+004     2.29E+004    4.777E+005   1.064E+004
 +       Eu-152      121 .78*  28.67  6.171E+004     6.17E+004    4.120E+003   2.971E+004 344.28*   26.60  6.813E+004                  9.538E+004   3.222E+004 1408.01    21. 07 7.967E+004                  7.454E+003   3.525E+004 Eu-154      123.07    40.40  8.000E+004     5.24E+004    2.016E+004   3.919E+004 723.30    20.06  1 .107E+005                 9.148E+004   5.187E+004 1274.43    34.80  5.238E+004                 -6.910E+003   2.355E+004 Eu-155       86. 5 5  30.70  1. 228E+005    1.23E+OOS    1 .378E+OOS  6.036E+004 105 .31   21.10  1. 611E+005                -7.304E+004   7.903E+004 Tl-208      583.19    85.00  3 ..140E+004   3.14E+004    2.998E+004   1. 496E+004 Bi-212      727.33     6.67  3.253E+005     3.25E+OOS    1 .368E+OOS  l. 522E+OOS Pb-212      238.63    43.60  6.544E+004     6.54E+004    4.240E+004   3.178E+004
 +       Bi-214      609.32*   45.49  3.529E+004     3.53E+004    7.963E+004   1.623E+004 1120.29    14.92  1. 615E+005                 1.455E+OOS   7.498E+004 1764.49*   15.30  7.509E+004                  1.437E+005   3.034E+004
 +       Pb-214      295.22*   18.42  9.463E+004     5.09E+004    5.489E+004   4.486E+004 351.93*   35.60  5.091E+004                  7.127E+004   2.407E+004 Ra-226      186.21     3.64  8.101E+OOS     8. l OE+OOS  4.780E+005   3.951E+005
 +       Ac-228      338.32    11. 27 2.364E+OOS     3.73E+004    1.143E+OOS   1.139E+OOS 911.20*   25.80  6.703E+004                  6.821E+004   3.0SOE+004 968.97*   15.80  3.733E+004                  1.098E+OD5   1.359E+004 Am-241       59.54    35.90  1 .048E+005    1. 0SE+OOS   2.620E+004   5.134E+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

[303]

• • • • • GAMMA S P E C T R U M ANALYSIS *****

Filename: 5456-A Report Generated On 6/5/2018 10 : 26: 53 A.NI Sample Title B103202AFSFC034GD Sample Description SFP/TRANSFER CANAL Sample Identification 034 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.260E+001 MA2 Sample Taken On 6/5/2018 10:16:00 AM Acquisition Started 6/5/2018 10:16 :51 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 07 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 2M90DSFP 2IN [304]

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Detector Name: 5456-A Sample

Title:

Bl 03202AFSFC034GD Peak Analysis Performed on: 6/5/2018 10:26:52 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 286 - 306 301.10 75.28 0. 88 4.05E+002 102.20 6.08E+002 2 332 ~ 345 340.22 85.05 0. 85 1 .32E+002 66.63 3.55E+002 3 946 - 960 954.62 238.65 0.42 2.87E+001 39.33 l .23E+002 4 1286- 1314 1290.31 322.58 0 .69 -1. 15E+001 53.22 1 .56E+002 5 1402 - 1415 1407.41 351.85 0 .86 7.07E+001 30.43 5.83E+001 6 2325- 2337 2330.78 582.70 0 .83 2.80E+001 19.64 2.60E+001 7 2428- 2442 2435.23 608.81 1. 25 8.lOE+OOl 22.30 1.50E+001 8 2635- 2657 2645.08 661.27 1. 37 8.65E+002 60.94 1.65E+001 9 4472- 4486 4478.52 1119.63 0.58 2.78E+001 15.54 1.13E+001 10 4681- 4701 46 91 .39 1172.85 1.32 1 .29E+002 23.63 2.74E+OOO 11 5318- 5336 5327.60 1331.90 1. 43 1 .19E+002 23.94 7.llE+OOO 12 5832- 5851 584 1 .62 1460.41 1.89 1. 20E+002 25.53 1 .24E+001 13 7051- 7067 7058.48 1764.62 0 .28 3.llE+OOl 12.16 1 .94E+OOO M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [305]

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Sample

Title:

Bl03202AFSFC034GD Nuclide Library Us ed: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

                                    ~        IDENTIFIED NUCLIDES          * ~* 'I *  "' * * * * * * * * * * , I

• I
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1 .000 1460.82* 10 .66 8.17086E+005 1.88282E+005 Co-60 1.000 1173.23* 99.85 8.43634E+004 1.68321E+004 1332.49* 99.98 B.23429E+004 1 .78434E+004 Cs-137 1. 000 661.66* 85. 10 5.04137E+005 7.01816E+004 Eu-155 0.346 86.55* 30.70 1.03841E+005 5.65357E+004 1 0 5.31 21.10 Tl-208 1.000 583.19* 85.00 1. 53740E+004 l.09395E+004 Pb-212 1.000 238.63* 43.60 1. 98826E+004 2.7467SE+004 Bi-214 1.000 609.32* 45.49 8.48586E+004 2.54877E+004 1120.29* 14.92 1.18436E+005 6.70070E+004 17 64.49* 15.30 1.65373E+005 6.60611E+004 Pb-214 0 .439 295.22 18.42 351.93* 35.60 7.21757E+004 3.31604E+004

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

[306]

Interference Corrected Activity Report 6/5/2018 10 :26:53 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 8.170856E+005 1. 882820E+005 Co-60 1.000 8.341201E+004 1. 2244 0 OE+ 0 04 Cs-137 1.000 5.041375E+005 7.018159E+004 Eu-155 0.346 1.038415E+005 5 .653570E+004 Tl-208 1.000 1. 537400E+004 1.093953E+004 Pb-212 1.000 1.988264E+004 2.746754E+004 Bi-214 1.000 9.787961E+004 2.240995E+004 Pb-214 0.439 7.217572E+004 3.31603SE+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

[307]

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Peak Locate Performed on: 6/5/2018 10 :26:52 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.28 6.7422E-001 25.26 4 322.58 -1. 9210E-002 -46 1 .72 Sum M = First peak in a multiplet region m ~ Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [308]

Nuclide MDA Report 6/5/2018 10:26:53 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC034GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/M"'2) (pCi/MA2 ) (pCi/M"'2 ) (pCi/MA2 )

 +      K-40       1460.82*   10.66  1.664E+005    1.66E+005    8.171E+005   7.396E+OD4
 +      Co-60      1173.23*   99.85  8.653E+003    8.65E+003    8.436E+004   3.444E+003 1332.49*   99.98  1.314E+004                 8.234E+004   5.631E+003 Nb-94       702.65    99.81  1.963E+004    1.83E+D04    5.104E+003   9.124E+OD3 8 71. 09  99.89  1.829E+004                 3.672E+003   8.383E+003 Ag-108m     433.90    90.50  2.966E+004    2.12E+004    3.119E+004   l .423E+OD4 614.30    89.80  3.291E+004                 2.070E+003   1 .573E+004 722.90    90.80  2.116E+004                 2.016E+004   9.810E+003 Cs-134      604.72    97.62  3.031E+004    2.14E+004    4.743E+004   1 .450E+OD4 795.86    85.46  2.141E+004                -7.565E+003   9.851E+003
 +      Cs-137      661.66*   85.10  1.677E+004    1 .68E+004   5.041E+005   7.599E+003 Eu-152      121 .78   28.67  1.065E+005    7.22E+004   -8.469E+003   5.209E+OD4 344.28    26.60  1.024E+OOS                -7.393E+004   4.937E+004 1408 .01   21.07  7.223E+004                 2.313E+004   3.153E+004 Eu-154      123.07    40. 40 7.603E+004    5.57E+004   -3.154E+004   3.720E+OD4 723.30    20.06  9.499E+004                 3.669E+004   4.401E+004 1274.43    34.80  5.575E+004                 1 .86SE+OD4  2.524E+004
 +      Eu-155        86.55*  30.70  8.335E+004    8.33E+004    1 .038E+005  4.060E+OD4 105.31    21.10  1 .571E+OOS                6.332E+004   7.700E+004
 +      Tl-208      583.19*   85.00  1 .643E+004   1. 64E+O 04  1 .537E+004  7.470E+003 Bi-212      727.33     6.67  3.099E+OOS    3. 1 DE+005  8.539E+004   1.445E+005
 +      Pb-212      238.63*   43.60  4.506E+004    4 .51E+D04   1 .988E+004  2.159E+004
 +      Bi-214      609.32*   45.49  2.551E+004    2.SSE+004    8.486E+004   1.134E+004 1120.29*   14.92  9.177E+004                 1 .184E+005  4 .011E+004 1764.49*   15.30  5.688E+004                 1.654E+005   2.124E+004
 +      Pb-214      295.22    18.42  1.565E+005    4.54E+004    3.106E+004   7.582E+OD4 351.93*   35.60  4 .538E+004                7.218E+004   2.131E+004 Ra-226      186.21     3.64  7.874E+005    7.87E+005    2.929E+OOS   3.838E+005 Ac-228      338.32    11. 27 2.511E+OOS    9.10E+004    3.767E+005   1.213E+OOS 911. 20   25.80  9.099E+004                 3.424E+004   4.248E+004 968. 9 7  15.80  1 .476E+005                3.789E+004   6.874E+004 Am-241        59.54   35.90  1 .022E+005   1. 02E+005   3.647E+004   5.004E+004
       +=Nuclide identified during the nuclide i dentification
       *=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

[309]

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

Filename: 5456-A Report Generated On 6/5/2018 10 :08:24 AM Sample Title B103202AFSFC035GD Sample Description SFP/TRANSFER CANAL Sample Identification 035 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.260E+001 MA2 Sample Taken On 6/5/2018 9:56: 00 AM Acquisition Started 6/5/2018 9:58:22 AM 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 5/30/2018 Efficiency ID 2M90DSFP 2IN [310]

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Detector Name: 5456-A Sample

Title:

B103202AFSFC035GD Peak Analysis Performed on: 6/5/2018 10 :08:24 AM Peak Analysis From Channel: BS Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 134 130. 34 32.58 1. 02 3.43E+001 22.21 3.37E+001 2 297- 307 3 01. 22 75.30 1.10 1 .61E+002 64.83 3.67E+002 3 335- 355 339.89 84.97 0.68 9. 70 E+001 94.33 5.84E+002 4 1174- 1187 1180.62 295.16 0 .78 3. lO E+OOl 31. 28 7.70E+001 5 1399- 1416 1407.57 351.89 1. 35 7.25E+001 35.54 7.45E+001 6 1845- 1859 1851.83 462.96 1. 03 2.76E+001 25.55 4.64E+001 7 2325- 2336 233 0 .68 582.67 0.50 2.12E+001 17. 13 2.08E+001 8 2429- 2444 2436.51 609. 13 0.87 5.76E+001 25.02 3.24E+001 9 2636- 2657 2645.19 661.30 1. 36 7.35E+002 59.22 3.76E+001 10 4473- 4486 4479. 01 1119.75 0.39 2.77E+001 14.67 9.34E+OOO 11 4681- 4700 4691.67 1172.92 0.67 8.65E+001 22.85 1.25E+001 12 5319- 5339 5329.45 1332.36 1. 32 9.50E+001 23.82 1. 30E+001 13 5830- 5852 5841.83 1460.46 1.25 1.27E+002 24.46 5.75E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F -' Fitted singlet Errors quoted at 2 . 000 sigma [311]

Interference Corrected Activity Report 6/5/2018 10:08:24 AM Page 3

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

Sample

Title:

Bl03202AFSFC035GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB

  * * * * * * * *

• 1 I *** I , *
• t
• IDENTIFIED NUCLIDES . . .. . .

                                                                            ...      ~ . . . . .. . . .. . . .. .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 1 . 000 1 460.82* 10.66 8.69432E+005 1.83364E+005 Co-60 1 . 000 11 73.23* 99.85 5 .64343E+004 l.55795E+004 1332.49* 99.98 6.58238E+004 l.73220E+004 Cs-137 1 . 000 661.66* 85.10 4.28384E+005 6.19416E+004 Eu-155 0.346 86.55* 30.70 7.66051E+004 7.60321E+004 1 05.31 21.10 Tl-208 1. 000 583 .19* 85.00 1.16217E+004 9.50967E+003 Bi-214 0.733 609.32* 45.49 6.03531E+004 2.72053E+004 1120.29* 14.92 1.18068E+005 6.33436E+004 1764.49 15. 30 Pb-214 1.000 295.22* 18.42 5.62956E+004 5.75200E+004 351.93* 35.60 7.40720E+004 3.81850E+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

[312]

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1. 000 8.694319E+OOS 1. 833643E+005 Co-60 1. 000 6.063317E+004 1.158358E+004 Cs-137 1. 000 4.283839E+005 6.194163E+004 Eu-155 0.346 7.660512E+004 7.603207E+004 Tl-208 1. 000 1.16217SE+004 9.509672E+003 Bi-214 0.733 6.934117E+004 2.499728E+004 Pb-214 1. 000 6.863429E+004 3.181305E+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

[313]

Interference Corrected Activity Report 6/5/2018 10 :08:24 AM Page 5

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Peak Locate Performed on: 6/5/2018 10:08:24 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) counts per Second  % Uncertainty Type Nuclide 1 32.58 5.7120E-002 64.80 2 75.30 2.6766E-001 40 .37 6 462.96 4.5918E-002 92.73 M ~ First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [314]

Nuclide MDA Report 6/5/2018 10 :08:24 AM Page 6

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Detector Name: 5456-A Sample Geometry: Sample

Title:

Bl03202AFSFC035GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"'2 ) (pCi/MA2 )

 +      K-40       1460.82*   10.66  1 .246E+005    1.25E+005    8.694E+005   5.306E+004
 +      Co-60      1173.23*   99.85  1.601E+004     1.60E+004    5.643E+OD4   7.123E+003 1332.49*   99.98  1.747E+004                  6.582E+004   7.800E+003 Nb-94       702 .6 5  99.81  1.818E+004     1.82E+004    7.000E+003   8.399E+003 871. 09   99.89  1.947E+004                  4.221E+OD2   8.976E+003 Ag-108m     433.90    90.50   2.738E+004    2.22E+004   -2.325E+004   l.309E+004 614.30    89.80   3. 151E+004               -2.778E+003   l.503E+004 722.90    90.80   2.220E+004                 7.732E+003   l.033E+004 Cs-134      604.72    97.62   2.923E+004    2.05E+004   -l.398E+004   l.396E+004 795.86    85.46   2.051E+004                -8.468E+001   9.403E+003 Cs-137      661.66*   85.10   2.437E+004    2.44E+004    4.284E+005   l.140E+004 Eu-152      121. 78   28.67  1.075E+005     8.31E+004    3.264E+004   5.260E+004 344.28    26.60   9.401E+004                 6.598E+004   4.517E+004 1408 . 01  21. 07  8.311E+004                 7.454E+004   3.697E+004 Eu-154      123 . 07  40. 40  7.423E+004    4.58E+004   -3.841E+004   3.630E+004 723.30    20.06   9.897E+004                 1.545E+004   4.600E+004 1274.43    34.80   4.582E+004                 2.360E+004   2.027E+004
 +      Eu-155       86.55*   30.70   l.219E+005    1. 22E+005   7.661E+004   5.990E+004 105.31    21.10   l.478E+005                -8.883E+004   7.234E+004
 +      Tl-208      583.19*   85.00   l.454E+004    1 .4 5E+004  1.162E+004   6.526E+003 Bi-212      727.33     6.67   2.961E+005    2.96E+005   -4.785E+003   l .375E+005 Pb-212      238.63    43.60   6.503E+004    6.50E+004    2.960E+004   3.157E+004
 +      Bi-214      609.32*   45.49   3.713E+004    3.71E+004    6.035E+004   l .715E+004 1120 .29*  14.92   8.339E+004                 1.181E+005   3.592E+004 1764.49    15.30   1.SOlE+OOS                 1.134E+OOS   6.784E+004
 +      Pb-214      295.22*   18.42   9.225E+004    5.52E+004    5.630E+004   4.367E+004 351. 93*  35.60   5.517E+004                 7.407E+004   2.62DE+004 Ra-226      186.21     3.64   7.625E+005    7.63E+005    3.822E+005   3.713E+OOS Ac-228      338.32    11. 27  2.231E+005    9.35E+004    2.790E+004   1.073E+005 911. 20   25.80   9.349E+004                 9.397E+004   4 .372E+004 968.97    15.80   l .487E+005                4.507E+004   6.929E+004 Am-241       59.54    35.90   9.850E+OD4    9.85E+004    4.995E+004   4.817E+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

[315]

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

Filename: 5456-A Report Generated On 6/5/2018 9:45:23 AM Sample Title B103202AFSFC036GD Sample Description SFP/TRANSFER CANAL Sample Identification 036 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.260E+001 M""2 Sample Taken On 6/5/2018 9:36:00 AM Acquisition Started 6/5/2018 9:35:21 AM Live Time 600 . 0 seconds Real Time 600.5 seconds Dead Time 0.08 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 2M90DSFP 2IN [316]

Peak Analysis Report 6/5/2018 9:45:23 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC036GD Peak Analysis Performed on: 6/5/2018 9:45:23 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 1 126- 137 130.25 32.56 0.95 9.59E+001 34.78 6.91E+001 2 286- 307 300.92 75.23 1.16 6.50E+002 115.62 7.18E+002 3 330- 348 340.25 85.06 1. 05 2.12E+002 95.78 6.12E+002 4 1379- 1413 1406.88 351.72 1. 14 1.41E+002 60.08 1 .42E+002 5 2040 - 2051 2045.31 511.33 0. 54 2.62E+001 24.68 4.88E+001 6 2428- 2442 2435.54 608.88 1. 10 3.95E+001 24.28 3.75E+001 7 2634- 2657 2645. 10 661. 27 1. 39 1.20E+003 73.08 3.28E+001 8 3636 - 3649 3642.85 910.71 1. 32 3.14E+001 15.92 1 .16E+001 9 4681- 4702 4690.79 1172.70 0.82 1.43E+002 25.29 4.82E+OOO 10 5318- 5339 5328.67 1332.17 1. 71 1.46E+002 25.72 5.32E+OOO 11 5831- 5853 5841.77 1460.44 2.00 1.64E+002 26.58 3.08E+OOO 12 7050- 7065 7057.53 1764.38 0.68 2. 80E+ 001 10.58 O.OOE+OOO M First peak in a multiplet region m F

 =

Other peak in a multiplet region Fitted singlet Errors quoted at 2 . 000 sigma [317]

Interference Corrected Activity Report 6/5/2018 9:45:23 AM Page 3

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Sample

Title:

B103202AFSFC036GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  . ............ ... .... ........ . IDENTIFIED NUCLIDES           II "' * *  * * * * * * * * * .. I * * * * "

Nuclide Id Energy Yield Activity Activity Name confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1. 000 146 0.82* 10 .66 1. 11996E+006 2.05979E+005 Co-60 1. 000 11 73.23* 99.85 9.34373E+004 l.81193E+004 1332.49* 99.98 1. 00911E+OOS l.95591E+004 Cs-137 1. 000 661.66* 85.10 7.01463E+005 9.43860E+004 Eu-155 0.346 86.55* 30.70 1. 66926E+OOS 8.26249E+004 1 05.31 21.10 Bi-214 0.705 609.32* 45.49 4.13841E+004 2.59156E+004 1120.29 14.92 1764.49* 15.30 l. 49066E+005 5.75928E+004 Pb-214 0.439 295.22 18.42 351.93* 35.60 1.44186E+OOS 6.55481E+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

[318]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1 .000 1 .119957E+006 2.059789E+005 Co-60 1 .000 9.688912E+004 1.329217E+004 Cs-137 1 .000 7.014629E+005 9.438597E+004 Eu-155 0 .346 1.669261E+005 8.262487E+004 Bi-214 0 .705 5.951623E+004 2.363315E+004 Pb-214 0 .439 1.441864E+005 6.554806E+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

[319]

Interference Corrected Activity Report 6/5/2018 9:45:23 AM Page 5

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

Peak Locate Performed on: 6/5/2018 9:45:23 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.56 1. 5988E-001 36.26 2 75.23 1. 0838E+OOO 1 7.78 5 511.33 4.3733E-002 94. 04 8 910. 71 5.2355E-002 50.69 To l. Ac-228 M = First peak in a multiplet region m - Other peak in a multiplet region F = Fitted singlet Errors quoted a t 2 , 000 sigma [320]

Nuclide MDA Report 6/5/2018 9:45:23 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC036GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/MA2 )

 +      K-40       1460.82*    10 .66 9.842E+004    9.84E+004    1.120E+006   3.997E+004
 +      Co-60      117 3 .23*  99.85  1.055E+004    1 .06E+004   9.344E+004   4.392E+003 1332.49*    99.98  1.199E+004                 1.009E+005   5.056E+003 Nb-94       702.65     99. 81 1.932E+004    l.93E+004    2.914E+003   8.968E+003 871.09     99.89  2.077E+004                -5.628E+002   9.621E+003 Ag-108m     433.90     90.50  3.248E+004    2.27E+004    4.129E+003   1.564E+004 614.30     89.80  3.078E+004                -1.471E+004   1.467E+004 722.90     90.80  2.270E+004                 7.032E+003   1.058E+004 Cs-134      60 4 .72   97.62  2.923E+004    2.27E+004    8.287E+003   1.396E+004 795.86     85.46  2.268E+004                -1.120E+004   1.049E+004
 +      Cs-137      661.66*    85.10  2.352E+004    2.35E+004    7.015E+005   1.097E+004 Eu-152      121.78     28.67  1 .165E+005   8.64E+004   -1. 273E+O 04 5.710E+004 344.28     26.60  l .110E+005                9.676E+003   5.369E+004 1408.01     21. 07 8.640E+004                 4.200E+003   3.861E+004 Eu-154      123.07     40. 40 8.206E+004    S.41E+004   -4.551E+004   4.022E+004 723.30     20.06  1.057E+005                 5.378E+004   4.939E+004 127 4 .43   34.80  5.409E+004                 4.097E+004   2.441E+004
 +      Eu-155       86.55*    30.70  1.206E+005    1.21E+005    1.669E+005   5.923E+004 105.31     21.10  1.724E+005                -4.122E+003   8.465E+004 Tl-208      583.19     85.00  3.051E+004    3.05E+004    2.884E+004   1.451E+004 Bi-212      727.33      6.67  3.122E+005    3.12E+005    3.747E+004   1.456E+005 Pb-212      238.63     43.60   7.330E+004   7.33E+004    3.835E+004   3.571E+004
 +      Bi-214      609.32*    45.49  3.863E+004    1. 44E+004   4.138E+004   1.790E+004 1120.29     14.92  1.602E+005                 7.801E+004   7.432E+004 1764.49*    15.30  1. 441E+004                1. 491E+005  O.OOOE+OOO
 +      Pb-214      295.22     18.42  1. 589E+005   9. S SE+004 -9.172E+004   7.699E+004 351.93*    35.60   9.545E+004                1.442E+005   4.635E+004 Ra-226      186.21      3.64   8.874E+005   8.87E+005    4 .024E+005  4.337E+005 Ac-228      338.32     11. 27  2.667E+005   9.94E+004    5.268E+005   1.291E+005 911.20     25.80   9.944E+004                1.171E+005   4.670E+004 968.97     15.80   l.324E+OOS                2.661E+003   6.111E+004 Am-241       59.54     35.90   l.106E+OOS   1 .11E+005  -6.329E+003   5.423E+004
       +=Nuclide identified during the nuclide i dentification
       * ; 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

[321]

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

Filename: 5456-A Report Generated On 6/5/2018 9:26:18 AM Sample Title B10 3 202AFSFC037GD Sample Description SFP/TRANSFER CANAL Sample Identification 037 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.260E+001 M"2 Sample Taken On 6/5/2018 9:16:00 AM Acquisition Started 6/5/2018 9:16:16 AM 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 5/30/2018 Efficiency ID 2M90DSFP 2IN [322]

Peak Analysis Report 6/5/2018 9:26: 18 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC037GD Peak Analysis Performed on: 6/5/2018 9:26:18 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 1 126- 138 129.85 32.46 0.67 5.25E+002 92.69 5.06E+002 2 285- 311 301 . 04 75.26 1. 30 1.13E+003 198.20 1.99E+003 3 335- 346 339 . 94 84.98 0.74 l.70E+002 96.85 8.62E+002 4 1865- 1876 1870 . 33 467.58 0.67 2.20E+001 43.28 1.77E+002 5 2426- 2444 2435. 11 608.78 0.83 1.04E+002 32.89 4.92E+001 6 2633- 2658 2644.98 661.25 1.48 5.05E+003 146.58 7.69E+001 7 4680- 4703 4690.76 1172.69 1. 69 1.96E+002 30.36 8.68E+OOO 8 5317- 5339 5327.79 1331.95 1. 60 2.25E+002 31. 31 5.47E+OOO 9 5830 - 5851 5841 . 13 1460.28 0. 71 l .42E+002 24.74 2.81E+OOO 10 7046- 7061 7053.98 1763.49 0.53 1 .41E+001 8.93 1.91E+OOO M = First peak in a mul tiplet region m = Other peak in a mul tiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [323]

Interference Corrected Activity Report 6/5/2018 9:26:18 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:

B103202AFSFC037GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

  .. ....... .... ...... . ...      IDENTIFIED NUCLIDES         * * * * * * * * ,.. * '"

• I "" ~ II "' I * "'

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 9.71443E+005 l .88876E+005 Co-60 1.000 1173.23* 99.85 1.28121E+OOS 2.23076E+004 1332.49* 99.98 1.55519E+OOS 2.50026E+004 Cs-137 1.000 661.66* 85.10 2.93937E+006 3.63174E+005 Eu-155 0.346 86.55* 30.70 1. 33845E+005 8.10090E+004 1 05.31 21.10 Bi-214 0.705 609.32* 45.49 1. 08724E+005 3.68468E+004 1120.29 14.92 1 764.49* 15.30 7.50097E+004 4.79105E+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

[324]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 9.714425E+005 1.888757E+005 Co-60 1. 000 1.402640E+005 1.664541E+004 Cs-137 1. 000 2.939375E+006 3.631744E+005 Eu-155 0.346 1.338449E+005 8 .100 904E+004 Bi-214 0.705 9.619386E+004 2.920786E+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 a t  2. 000 sigma

[325]

Interference Corrected Activity Report 6/5/2018 9:26:18 AM Page 5

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

Peak Locate Performed on: 6/5/2018 9:26:18 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) counts per Second  % Uncertainty Type Nuclide 1 32.46 8.7527E-001 17.65 2 75.26 1 .8790E+OOO 17.58 4 467.58 3.6667E-002 196.72 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [326]

Nuclide MDA Report 6/5/2018 9:26:18 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC037GD 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  9.225E+004    9.22E+004   9.714E+005  3.688E+004
 +      Co-60      1173.23*   99.85  1.431E+004    1 .22E+004  1 .281E+005 6.270E+003 1332.49*   99.98  1.221E+004                1. 555E+005 5.168E+003 Nb-94       702.65    99.81  l.932E+004    l .93E+004  2.463E+002  8.968E+003 871. 09   99.89  2.181E+004                6.029E+003  1 .014E+004 Ag-108m     433.90    90.50  5.222E+004    2.35E+004   7.056E+004  2.550E+004 614.30    89.80  4 .081E+D04              -3.903E+004  1. 968E+004 722.90    90.80  2.352E+004                2.367E+004  1.099E+004 Cs-134      604.72    97.62  3.733E+004    2.63E+004   1.057E+004  1. 801E+004 795.86    85.46  2.628E+004                l.966E+003  1.229E+004
 +      Cs-137      661.66*   85.10  3.613E+004    3.61E+004   2.939E+006  1.727E+004 Eu-152      121.78    28.67  1.780E+005    8.80E+004  -2.111E+005  8.786E+004 344.28    26.60  1.595E+OD5               -9.869E+004  7.793E+004 1408 .01   21.07  8.799E+OD4                5.679E+004  3.941E+004 Eu-154      123.07    40.40  1.252E+005    4.87E+004  -4.507E+004  6.180E+004 723.30    20.06  1.043E+OD5                1.129E+004  4.866E+004 1274.43    34.80  4. 875E+OD4               1.510E+004  2.174E+004
 +      Eu-155       86.55*   30.70  1.233E+005    1.23E+OOS   1.338E+005  6.057E+004 105.31    21.10  2.571E+005               -6.309E+004  l .270E+005 Tl-208      583.19    85.00  3.870E+004    3.87E+004   4.319E+004  1 .861E+004 Bi-212      727.33     6.67  2.937E+005    2.94E+OOS   4.245E+004  1 .363E+005 Pb-212      238 .6 3  43.60  1.100E+005    1.lOE+OOS   1.274E+005  5.407E+004
 +      Bi-214      609.32*   45.49  4.732E+004    4.73E+004   1.087E+005  2.224E+004 1120.29    14 .92 l.958E+005                2.206E+005  9.210E+004 1764.49*   15.30  5.674E+004                7.501E+004  2.117E+004 Pb-214      295.22    18.42  2.379E+005    1.24E+OOS   1.447E+OOS  1.165E+005 351. 93   35.60  1.245E+OOS                1.566E+004  6.087E+004 Ra-226      186.21     3.64  1.341E+006    1.34E+006   l.329E+OOS  6.607E+OOS Ac-228      338.32    11. 27 3.787E+005    1.04E+OOS  -4.944E+004  1.851E+005 911. 20   25.80  1. 045E+OOS               2.706E+004  4.923E+004 968.97    15.80  1. 721E+OOS               1.876E+003  8.095E+004 Am-241       59 .5 4  35.90  1. 828E+005   1 .83E+005 -4.073E+004  9.030E+004
       + r- 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 ANALYSIS *****

Filename: 5456-A Report Generated On 6/5/2018 8:28:13 AM Sample Title Bl03202AFSFC038GD Sample Description SFP/TRANSFER CANAL Sample Identification 038 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/5/2018 8:18:00 AM Acquisition Started 6/5/2018 8: 18 :12 AM 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 5/30/2018 Efficiency ID l.5M90DSFP 2IN [328]

Peak Analysis Report 6/5/2018 8:28:13 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC038GD Peak Analysis Performed on: 6/5/2018 8:28:13 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 1 126- 134 13 0 .09 32.52 0 .57 2.49E+001 22.14 3.51E+001 2 287- 310 30 0 .83 75.21 1. 16 3.84E+002 107.15 6.21E+002 3 334- 345 34 0 .63 85. 16 0.64 7.28E+001 59.97 3.30E+002 4 951- 960 955.15 238.79 0.65 l.41E+001 28.62 8.39E+001 5 1173- 1187 1181.49 295.37 0.32 5.89 E+001 30.06 5.81E+001 6 1401- 1416 1407.63 351.91 1. 23 7.35 E+001 28.99 4.35E+001 7 2325- 2338 2331. 40 582.85 0.65 4.05E+001 20.59 2.35E+001 8 2429- 2444 2436.60 609.15 1. 43 9.07E+001 24.70 2.03E+001 9 2636- 2656 2645.26 661.32 1. 42 2.09E+002 34.57 2.52E+001 10 4683- 4700 4691.54 1172.88 1. 06 7.36E+001 21. 08 1.14E+001 11 5319- 5338 5328.88 1332.22 1. 54 8.69E+001 22.15 1.0lE+OOl 12 5831- 5855 5842.08 1460.52 1. 52 1. 81E+O 02 26.91 O.OOE+OOO M .,,. First peak in a mul tiplet region m = Other peak in a mul tiplet region F = Fitted* singlet Errors quoted at 2 . 000 sigma [329]

Interference Corrected Activity Report 6/5/2018 8:28:13 AM Page 3

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Sample

Title:

B103202AFSFC038GD 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 1.23845E+006 2.13214E+005 Co-60 1.000 1173.23* 99.85 4.81204E+004 1.43038E+004 1332.49* 99.98 6.02587E+004 1.608 8 6E+004 Cs-137 1.000 661.66* 85. 10 1.22210E+005 2.49947E+004 Eu-155 0.346 8 6.55* 30. 70 5.72861E+004 4.85644E+004 105.31 21.10 Tl-208 1.000 583.19* 85. 00 2.23990E+004 1.16955E+004 Pb-212 1.000 238.63* 43.60 9.71970E+003 1.98096E+004 Bi-214 0.438 609.32* 45.49 9.56105E+004 2.84597E+004 1120.29 14.92 1764.49 15.30 Pb-214 1.000 295.22* 18.42 1. 07023E+005 5.72533E+004 351.93* 35.60 7.54837E+004 3.21205E+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

[330]

Interference Corrected Activity Report 6/5/2018 8:28:13 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 l.238445E+006 2.132138E+005 Co-60 1. 000 5.347918E+004 l.068986E+004 Cs-137 1. 000 1 .222102E+OOS 2.499473E+004 Eu-155 0.346 S.728606E+004 4.856444E+OD4 Tl-208 1. 000 2.239902E+004 l.169547E+OD4 Pb-212 1. 000 9.719696E+003 1 .980957E+OD4 Bi-214 0.438 9.561052E+004 2.845973E+D04 Pb-214 1. 000 8.303414E+004 2.801309E+D04

      ? = 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

[331]

Interference Corrected Activity Report 6/5/2018 8:28:13 AM Page 5

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

Peak Locate Performed on: 6/5/2018 8:28:13 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.52 4.1563E-002 88.79 2 75.21 6.4019E-001 27.89 M = First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma [332]

Nuclide MDA Report 6/5/2018 8:28:13 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC038GD 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.852E+004    1 .85E+004   1.238E+006   O.OOOE+OOO
 +      Co-60      1173.23*     99.85  1.493E+004    l .49E+004   4.812E+004   6.578E+003 1332.49*     99.98  1 .549E+004                6.026E+004   6.809E+003 Nb-94        702.65     99 .81 1 .973E+004   l .90E+004   1.268E+003   9.170E+003 871.09     99.89  1 .901E+004                4.918E+003   8.737E+003 Ag- 108m     433.90     90.50  2.464E+004    2.25E+004    l .959E+004  1 .171E+004 614.30     89.80  3.310E+OD4                 1. 108E+O 02 l .582E+004 722.90     90.80  2.249E+OD4                 8.384E+003   1.047E+004 Cs-134       60 4 . 72  97.62  2.931E+004    2.48E+004   -l.006E+004   l.399E+004 795.86     85.46  2.479E+OD4                 2.721E+003   1.153E+004
 +      Cs-137       661.66*    85.10  1.984E+004    l.98E+OD4    l.222E+005   9.130E+003 Eu-152       121.78     28.67  9.596E+004    7.42E+OD4   -l.556E+OD4   4 .684E+004 344.28     26.60  8.215E+004                 3.160E+004   3.924E+004 1408.01      21.07  7.425E+004                -4.918E+004   3.253E+004 Eu-154       123.07     40.40  6.750E+004    5.82E+004    1. 79DE+004  3.294E+004 723.30     20.06  1.010E+005                 2.103E+004   4.702E+004 1274.43      34.80  5.819E+004                 6.631E+004   2.645E+004
 +      Eu-155        86.55*    30.70  7.655E+004    7.66E+004    5.729E+004   3.721E+004 105.31     21 .10 l.422E+005                 8.471E+004   6.956E+004
 +      Tl-208       583.19*    85.00  1.621E+004    1. 62E+004   2.240E+004   7.357E+003 Bi-212       727.33      6.67  3.115E+005    3.12E+005    8.583E+004   l.452E+005
 +      Pb-212       238.63*    43.60  3.321E+D04    3.32E+004    9.720E+003   1.567E+004
 +      Bi-214       609.32*    45.49  3.012E+004    3. 0 1E+004  9.561E+004   l.363E+004 1120.29      14.92  l.633E+OD5                 2.144E+005   7.584E+004 1764.49      15.30  1. 435E+005                l.441E+005   6.453E+004
 +      Pb-214       295.22*    18.42  8.219E+004    4.23E+004    1.07DE+005   3.864E+004 351.93*    35.60  4.225E+004                 7.548E+OD4   1.974E+004 Ra-226       186.21      3.64  6.849E+D05    6.85E+005    4.995E+005   3.325E+005 Ac-228       338.32     11. 27 l.946E+005    9.52E+004    1. 241E+005  9.299E+004 911. 20    25.80  9.524E+004                 9.618E+003   4.459E+004 968. 9 7   15.80  1.528E+D05                 8.549E+004   7.131E+004 Am-241        59.54     35.90  9.377E+004    9.38E+004    l .337E+004  4.581E+004
       +=Nuclide identified during the nuclide i dentification
       *=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

[333]

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

Filename: 5456-A Report Generated On 6/4/2018 2:26:16 PM Sample Title B103202AFSFC039GD Sample Description SFP/TRANSFER CANAL Sample Identification 039 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/4/2018 2:16:00 PM Acquisition Started 6/4/2018 2:16:13 PM Live Time 600.0 seconds Real Time 602. 1 seconds Dead Time 0.35 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1 .SM90DSFP 2IN [334]

Peak Analysis Report 6/4/2018 2:26:16 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC039GD Peak Analysis Performed on: 6/4/2018 2:26:15 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 1 126- 156 129.86 32.47 0.91 l.76E+003 165.72 8.73E+002 2 285- 307 301. 27 75.32 0.92 l.58E+003 218.50 2.67E+003 3 332 - 347 340.32 85.08 1. 44 3.67E+002 158.23 l.95E+003 4 2430- 2446 2436.21 609.05 1. 21 5.52E+001 45.43 1.47E+002 5 2633- 2657 2645.90 661. 48 1. 53 1. 71E+004 266.19 1. 53E+002 6 4680- 4704 4692.36 1173.09 1. 70 4.57E+002 48.40 3.13E+001 7 5317- 5343 5329.65 1332.41 1. 81 4 .82E+002 45.25 6.75E+OOO 8 5624- 5637 5630.86 1407 .71 0.81 1 .30E+001 7.21 O.OOE+OOO 9 5832- 5854 5843.40 1460.85 1. 88 l .34E+002 25. 88 8.55E+OOO 10 7052- 7067 7059.20 1764.80 1. 07 2.42 E+001 10.83 l.76E+OOO M =- First peak in a mul tiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [335]

Interference Correcte d Activity Report 6/4/2018 2: 26: 16 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:

B103202AFSFC039GD 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 9.20053E+005 1 .94291E+005 Co-60 1. 000 1173.23* 99.85 2.98569E+005 3.96440E+004 1332.49* 99.98 3.34281E+005 4.12181E+004 Cs-137 1. 000 661. 66

• 85.10 9.99405E+006 1.21028E+006 Eu-155 0.346 86.55* 30.70 2.88795E+005 l.37307E+005 10 5.31 21.10 Bi-214 0.705 609.32* 45.49 5.82189E+004 4.83872E+004 1120.29 14.92 1764.49* 15 .30 1. 29416E+005 S.87308E+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

[336]

Interference Corrected Activity Report 6/4/20 18 2: 26: 16 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1 . 000 9.200532E+005 l .942911E+005 Co-60 1 . 000 3.157297E+005 2.857281E+004 Cs-137 1 . 000 9.994047E+006 l .210278E+006 Eu-155 0 .346 2.887947E+005 l .373075E+005 Bi-214 0.705 8.700616E+004 3.734509E+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

[337]

Interference Corrected Activity Report 6/4/2018 2: 26: 16 PM Page 5

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

Peak Locate Performed on: 6/4/20 1 8 2:26:15 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV} Counts per Second  % Uncertainty Type Nuclide 1 32.47 2.9262E+OOO 9.44 2 75.32 2.6276E+OOO 13.86 8 1407.71 2.1667E-002 55.47 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [338]

Nuclide MDA Report 6/4/2018 2:26:16 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC039GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

 +      K-40       1460.82*   10.66  1. 479E+005   l. 4 8E+005   9.201E+005  6.467E+004
 +      Co-60      1173.23*   99.85  2.619E+004    1. 4 3E+D04   2.986E+D05  1.221E+004 1332.49*   99.98  1. 429E+004                 3.343E+005  6.205E+003 Nb-94        702.65   99.81  2.466E+004    2.47E+D04   -1.223E+004   l .164E+004 871.09   99.89  2.814E+004                -8.384E+OD3   1 .330E+004 Ag-108m      433.90   90.50  8.600E+004    2.77E+D04     1 .487E+004 4.239E+004 614.30   89.80  5.535E+004                  3.809E+D03  2.695E+D04 722.90   90.80  2.774E+004                -1.817E+OD4   1.310E+004 Cs-134       604.72   97.62  5.189E+004    3.02E+D04   -4 .979E+OD3  2.528E+D04 795.86   85.46  3.020E+004                -1.983E+003   1.424E+004
 +      Cs-137       661.66*  85.10  5.037E+004    5.04E+004     9.994E+D06  2.439E+004 Eu-152       121.78   28.67  2.443E+005    8.32E+004   -1 .071E+005  1 .210E+005 344.28   26.60  2.514E+005                -1. 115E+005  1.238E+005 1408 .0 1  21.07  8.320E+004                 2.120E+004   3.701E+004 Eu- 154      123.07   40.40  1.729E+005    5.15E+004   -3.101E+004   8.563E+004 723.30   20.06  1.219E+005                -2.103E+D05   5.743E+004 1274.43    34.80  5.155E+004                -2.247E+004   2.313E+004
 +      Eu-155        86.55*  30.70  2.009E+005    2.01E+005    2.888E+OOS   9.941E+004 105.31   21.10  3.309E+005                -l.862E+OD5   1.639E+005 Tl-208       583. 19  85.00  5.773E+004    5.77E+OD4    1. 295E+004  2.812E+OD4 Bi-212       727.33    6.67  3.674E+005    3.67E+OD5   -2.347E+004   1. 732E+005 Pb-212       238.63   43.60  1 .577E+005   l .58E+005  -3.883E+OD4   7.792E+D04
 +      Bi-214       609.32*  45.49  7.728E+004    5.40E+004    5.822E+004   3.721E+OD4 1120.29    14.92  2.087E+005                -4.881E+003   9.858E+004 1764.49*   15. 30 5.400E+004                 1.294E+OD5   1. 978E+004 Pb-214       295.22   18.42  3.647E+005    1 .95E+OD5   1.305E+005   1.799E+005 351.93   35.60  1 .948E+005                5.749E+OD4   9.600E+OD4 Ra-226       186.21    3.64  1 .963E+006   1 .96E+OD6   1.915E+D06   9.714E+OD5 Ac-228       338.32   11.27  5.808E+005    1 .24E+OOS  -2.174E+OD5   2.861E+005 911.20   25.80  l .237E+005                4.681E+D02   5.881E+OD4 968.97   15.80  1 .721E+005               -1. 887E+003  8.093E+OD4 Am-241        59.54   35.90  1 .944E+005   1 .94E+OOS  -6.908E+003   9.611E+D04
       +=Nuclide identified during the nuclide i dentification
       * - 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

[339]

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

Filename: 5456-A Report Generated On 6/4/2018 2: 47: 22 PM Sample Title B103202AFSFC040GD Sample Description SFP/TRANSFER CANAL Sample Identification 040 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/4/2018 2:35:00 PM Acquisition Started 6/4/2018 2: 37: 20 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 5/30/2018 Efficiency ID 1.5M90DSFP 2IN [340]

Peak Analysis Report 6/4/2018 2:47:22 PM Page 2

• • • • • P E A K ANALYSIS REPORT *****

Detector Name: 5456-A Sample

Title:

B103202AFSFC040GD Peak Analysis Performed on: 6/4/2018 2:47:21 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 136 13 0.12 32.53 1. 00 l .55E+002 38.84 7.77E+001 2 286- 311 301.66 75.42 1. 23 7.95E+002 135.36 8.90E+002 3 332- 345 340.13 85.03 0.86 l.20E+002 82.38 5.70E+002 4 364- 375 370.94 92.73 0.89 4.57E+001 63.98 3.90E+002 5 1403- 1416 1408.55 352.14 1. 04 7.80E+001 34.78 8.00E+OOl 6 2430- 2445 2437.64 609.41 0 .34 8.53E+001 27 .37 3.37E+001 7 2634- 2657 2646.94 661.73 1.48 2.26E+003 99.16 4.93E+001 8 4684- 4705 4694.06 1173.52 1. 39 2.73E+002 35.77 l.29E+001 9 5321- 5343 533 1. 16 1332.79 1. 85 2.86E+002 35.33 6.31E+OOO 10 5835- 5856 5845. 61 1461.40 1. 56 1 .63E+002 27.07 5.50E+OOO 11 7055- 7070 7062.80 1765.70 0 .31 1 .58E+001 11.91 6.25E+OOO 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 [341]

Interference Correcte d Activity Report 6/4/2018 2: 47: 22 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:

B103202AFSFC040GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib- BNL. NLB

  * * * * * * * * *

• I * *
• t I I
• t
• IDENTIFIED NUCLIDES *** * ********* **** it **

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"'2 ) Uncertainty K-40 0 .999 1460.82* 10.66 1.11226E+006 2. 08922E+O 05 Co-60 1 .000 1173.23* 99.85 1.78542E+005 2. 74045E+004 1332.49* 99.98 1.9 8 060E+005 2.91721E+004 Cs-137 1.000 661.66* 85. 10 1.32127E+006 l.68954E+005 Eu-155 0.346 8 6.55* 30.70 9.42177E+004 6.75526E+004 10 5. 31 21. 10 Bi-214 0.705 609.32* 45.49 8.98982E+004 3.0807 8 E+004 1120.29 14.92 1764.49* 15.30 8.41121E+004 6.39438E+004 Pb-214 0.438 295.22 18.42 351.93* 35.60 8.01025E+004 3.79524E+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 a t                  2. 000 sigma

[342]

Interference Corrected Activity Report 6/4/2018 2: 47 : 22 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.999 1.112259E+006 2.089222E+OOS Co-60 1. 000 1. 876920E+OOS 1.997358E+004 Cs-137 1. 000 1. 321272E+006 1.689536E+OOS Eu-155 0.346 9.421767E+004 6.755260E+0 04 Bi-214 0.705 8.880813E+004 2.775449E+0 04 Pb-214 0.438 8. 010249E+004 3.795236E+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

[343]

Interference Corrected Activity Report 6/4/2018 2: 47: 22 PM Page 5

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

Peak Locate Performed on: 6/4/2018 2:47:21 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.53 2.5887E-001 25.01 2 75.42 1. 3250E+OOO 17 .03 4 92.73 7.6090E-002 140 .15 M = First peak i n a multiplet region m = Other peak i n a multiplet region F

         -  Fitted singlet Errors quoted at     2. 000 sigma

[344]

Nuclide MDA Report 6/4/2018 2: 47: 22 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC040GD 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  1.208E+005     1.21E+OOS    1. 112E+006  5.11SE+004
 +      Co-60      1173.23*    99.85  1 .649E+004    l. 36E+004   1.78SE+005    7.360E+003 1332.49*    99.98  1.359E+004                  l.981E+005   5.857E+003 Nb-94        702 . 65  99.81  2.261E+004    2.26E+004   -l.364E+002    1 .061E+D04 871. 09   99.89  2.582E+004                  l.459E+004   1.214E+004 Ag-108m      433.90    90.50  3.814E+004    2.58E+004     5.833E+003   1.846E+004 614.30    89.80  3.645E+004                -9.165E+003     l .750E+D04 722.90    90.80  2.577E+004                 4.679E+OD3    1.211E+004 Cs-134       604.72    97.62  3.571E+004    2.93E+004   -2.327E+004    1.719E+004 795.86    85.46  2.927E+004                 2.857E+003    1.377E+004
 +      Cs-137       661.66*   85.10  2.894E+004    2.89E+004    1 .321E+OD6   1 .368E+004 Eu-152       121.78    28.67  1 .303E+005   9.85E+004     7.294E+004   6.403E+004 344.28    26.60  1 .210E+005               -6.581E+004    5.864E+004 1408.01     21. 07 9.845E+004                 2.504E+004    4.464E+004 Eu-154       123.07    40.40  9.063E+004    4 .59E+004  -2.111E+004    4.451E+004 723.30    20.06  1.160E+005                -l.503E+004    5.451E+D04 1274.43     34.80  4.586E+004                -3.878E+004    2.029E+004
 +      Eu-155        86.55*   30.70  1 .050E+005   l .05E+OOS   9.422E+004    5.144E+004 105.31    21. 10 1 .859E+005               -l. 750E+004   9.140E+004 Tl-208       583.19    85.00  3.591E+004    3.59E+004    6.336E+004    1.721E+004 Bi-212       727.33     6.67  3.597E+005    3.60E+005    1.502E+005    1. 693E+005 Pb-212       238.63    43.60  8.144E+004    B. 1 4E+004  5.332E+004    3.979E+004
 +      Bi-214       609.32*   45.49  3.787E+004    3.79E+004    8.99DE+004    1 .751E+004 1120.29     14.92  1 .908E+005                2.033E+004    8.962E+004 1764.49*    15.30  9.242E+004                 8.411E+004    3.899E+004
 +      Pb-214       295.22    18.42  1.844E+005    5.34E+004   -2.729E+004    8.975E+004 351.93*   35.60  5.340E+004                 8.010E+004    2.531E+004 Ra-226       186.21     3.64  9.591E+OOS    9.59E+005    3.838E+OOS    4.697E+OOS Ac-228       338.32    11.27  3.019E+005    l .20E+005   2.480E+005    l.467E+005 911.20    25.80  1.199E+005                 5.990E+004    5.693E+004 968.97    15.80  1. 777E+OD5                7.452E+004    8.373E+004 Am-241        59.54    35.90  l. 103E+005   1.lOE+OOS   -1 .lOOE+OOS   5.407E+004
       +=Nuclide identified during the nuclide i dentification
       * ~ 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

[345]

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

Filename: 5456-A Report Generated On 6/4/2018 3:09:58 PM Sample Title B103202AFSFC041GD Sample Description SFP/TRANSFER CANAL Sample Identification 041 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO M""2 Sample Taken On 6/4/2018 2:59:00 PM Acquisition Started 6/4/2018 2:59:56 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 5/30/2018 Efficiency ID l.5M90DSFP 2IN [346]

Peak Analysis Report 6/4/2018 3:09:58 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B1 03202AFSFC041GD Peak Analysis Performed on: 6/4/2018 3:09:57 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 136 130 .73 32.68 0.77 5.0lE+OOl 28.85 5.39E+001 2 282- 308 301. 60 75.40 0.76 3.75E+002 116. 08 6.84E+002 3 335- 345 340.43 85.11 0.73 5.93E+001 56.37 3.07E+002 4 951- 961 955.12 238.78 0.77 5.04E+001 31. 30 8.06E+001 5 1400- 1415 1408.53 352.13 0.48 7.79E+001 29.09 4.41E+001 6 2328- 2340 2333.74 583.43 0.27 2.89E+001 15.91 1.21E+001 7 2430- 2444 2437.17 609.29 0.34 6.46E+001 22.72 2.24E+001 8 2636- 2656 2646.76 661.69 1.42 3.46E+002 40. 62 l .84E+001 9 2904- 2915 2909.10 727.28 0.97 2.00E+OOl 11.87 6.00E+OOO 10 3637- 3650 3643.86 910.97 0.33 1.53E+001 12.56 8.74E+OOO 11 4477- 4490 4483.61 1120.90 0.37 2.0SE+OOl 14. 13 9.45E+OOO 12 4685- 4704 4693.99 1173.50 1. 26 7.03E+001 22.64 1.57E+001 13 5322- 5340 5331.32 1332.83 0.79 8.81E+001 22.66 1 .19E+001 14 5834- 5855 5844.98 1461. 24 1. 90 1.51E+002 26.27 5.53E+OOO 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 [347]

Interference Corrected Activity Report 6/4/20 18 3: 09 ~ 58 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:

B103202AFSFC041GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib- BNL. NLB

  . ......... . . . . . . . ]I *** -

• IDENTIFIED NUCLIDES * * * * * * * * * * * * * * * * ,f,
• I Ii Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 1 .000 1460.82* 10.66 1.03671E+006 2.01059E+005 Co-60 1 .000 1173.23* 99.85 4 .59666E+004 l.524 8 6E+004 1332.49* 99.98 6.10855E+004 l .64505E+004 Cs-137 1.000 661.66* 85. 10 2.02316E+005 3.39993E+004 Eu-155 0.346 86.55* 30.70 4.6657SE+004 4.53427E+004 105.31 21. 10 Tl-208 1. 000 583.19* 85.00 1. 59600E+004 9.00313E+003 Bi-212 1. 000 727.33* 6.67 1.5604SE+OOS 9.43759E+004 Pb-212 1.000 238.63* 43.60 3.47665E+004 2.23112E+004 Bi-214 0 .732 609.32* 45.49 6.80906E+004 2.53097E+004 1120.29* 14.92 8.79864E+004 6.09041E+004 176 4.49 15.30 Pb-214 0.438 295.22 18 .42 351.93* 35.60 8.00391E+004 3.25125E+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 a t                2.000 sigma

[348]

Interference Corrected Activity Report 6/4/2018 3: 09: 58 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 1.036705E+006 2.010587E+005 Co-60 1.000 5.295360E+004 1.118320E+004 X Ag-108m 0.405 Cs-137 1. 000 2.023162E+005 3.399933E+004 Eu-155 0.346 4.665753E+004 4.534273E+004 Tl-208 1.000 l .596002E+004 9.003134E+OD3 Bi-212 1. 000 1 .560450E+005 9.437595E+004 Pb-212 1. 000 3.476647E+004 2.231118E+004 Bi-214 0.732 7.102055E+004 2.337192E+004 Pb-214 0.438 8.003908E+004 3.251254E+004

      ?  = Nuclide is part of an undetermined so lution X    Nuclide rejected by the interference analysis
      @  ; Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at   2. 000 sigma

[349]

Interference Corrected Activity Report 6/4/2018 3: 09: 58 PM Page 5

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

Peak Locate Performed on: 6/4/20 18 3: 09: 57 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 32.68 8.3482E-002 57.61 2 75 .40 6.2461E-001 30.97 10 910.97 2.S434E-002 82.29 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 [350]

Nuclide MDA Report 6/4/2018 3:09:58 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC041GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec . Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 )

 +      K-40       1460.82*     10.66  1 .218E+005   l .22E+005  1. 037E+006 5.162E+004
 +      Co-60      1173.23*     99.85  1 .812E+004   1 .63E+004  4.597E+004  8.175E+003 1332.49*     99.98  1 .634E+004               6.109E+004  7.233E+003 Nb-94        702 . 65   99.81  1 .877E+004   1 .88E+004  1.691E+004  8.691E+003 871.09     99.89  1.901E+004               -1.270E+004  8.737E+003 Ag-108m      433.90     90.50  2.360E+004    8.90E+003  -3.831E+003  1.119E+004 614.30*    89.80  1.555E+004                3.449E+004  7.052E+003 722.90*    90.80  8.901E+003                1 .146E+004 3.675E+OD3 Cs-134       604.72     97.62  2.837E+D04    2.26E+004  -1.868E+003  1 .352E+004 795.86     85.46  2.260E+004               -2.336E+003  1. 044E+O 04
 +      Cs-137       661.66*    85. 10 1. 735E+004   1.74E+004   2.023E+005  7.884E+OD3 Eu-152       121 .78    28.67  l.022E+005    8.27E+004  -1.942E+004  4.998E+004 344.28     26.60  8.266E+OD4                2.265E+004  3.949E+D04 1408.01      21. 07 8.486E+004                4.959E+004  3.784E+004 Eu-154       123.07     40. 40 7.260E+004    5.15E+004   3.145E+003  3.549E+004 723.30     20.06  1. 092E+005               6.645E+004  5.108E+004 1274.43      34.80  5.155E+004               -8.213E+003  2.313E+004
 +      Eu- 155       86. 5 5*  30.70  7.235E+004    7.23E+004   4.666E+004  3.511E+004 105.31     21.10  l. 447E+005              -1.878E+004  7.080E+004
 +      Tl-208       583.19*    85.00  l. 217E+004   1.22E+004   1.596E+004  5.335E+003
 +      Bi-212       727.33*     6.67  1 .212E+005   l.21E+005   1.560E+005  5.003E+004
 +      Pb-212       238. 63*   43.60  3.352E+004    3.35E+004   3.477E+004  1.583E+004
 +      Bi-214       609.32*    45.49  3.070E+004    3.07E+004   6.809E+004  1. 392E+004 1120.29*     14.92  8.791E+004                8.799E+004  3.816E+004 1764.49      15.30  1 .593E+005               1.815E+005  7.241E+004
 +      Pb-214       295.22     18.42  1 .342E+005   4 .19E+004  1.797E+005  6.465E+004 351.93*    35.60  4.185E+004                8.004E+004  1.954E+004 Ra-226       186.21      3.64  6.645E+005    6.64E+005   2.179E+005  3.223E+005 Ac-228       338.32     11. 27 1 .861E+OOS   8.13E+004  -1.306E+005  8.877E+004 911.20     25. 80 8.133E+004                3.752E+004  3.763E+004 968.97     15.80  1 .507E+005               1.339E+005  7.022E+004 Am-241        59.54     35.90  9.172E+004    9.17E+004   2.610E+D04  4 .478E+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

[351]

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

Filename: 5456-A Report Generated On 6/5/2018 8:44:42 AM Sample Title B103202AFSFC042GD Sample Description SFP/TRANSFER CANAL Sample Identification 042 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 kev Sample Size 2.826E+001 MA2 Sample Taken On 6/5/2018 8:34:00 AM Acquisition Started 6/5/2018 8:34:40 AM Live Time 600 .. O seconds Real Time 600.3 seconds Dead Time 0 . 05 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [352]

Peak Analysis Report 6/5/2018 8:44:42 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B1 03202AFSFC042GD Peak Analysis Performed on: 6/5/2018 8:44 :41 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 1 126- 133 129.58 32.40 0 .49 1. 13E+001 19.00 2.77E+001 2 296- 307 301.21 75.30 1. 03 1. 47E+002 67.95 3.99E+002 3 336- 357 340.92 85.23 0.31 1.55E+002 87.61 4.68E+002 4 949- 976 955.50 238.88 0.70 7.36E+001 52.44 1.36E+002 5 1177- 1188 1182.10 295.52 0.79 2. lOE+ OOl 26.24 6.00E+OOl 6 1402- 1414 1407.71 351.93 0.34 3.86E+001 23.97 3.94E+001 7 2324- 2336 2330.10 582.53 0.38 2.58E+001 19.74 2.72E+001 8 2430- 2443 2436.91 609.23 1.11 5.55E+001 19.81 1.55E+001 9 2636- 2654 2645.43 661.36 0.74 1.66E+002 33.95 3.59E+001 10 3729- 3742 3735.07 933.77 0. 31 1 .63E+001 12.33 7.66E+OOO 11 4473- 4486 4479.67 1119 .92 0.33 3.lOE+OOl 14.18 7.00E+OOO 12 4684 - 4700 4692.25 1173.06 1. 00 8.68E+001 23.76 1 .72E+001 13 5320 - 5339 5329.41 1332.35 0. 54 9.26E+001 23.31 1.24E+001 14 5832- 5854 5843.00 1460.75 1.20 1 .58E+002 25.95 2.69E+OOO M "" First peak.in a mul tiplet region m Other peak in a mul tiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [353]

Interference Corrected Activity Report 6/5/2018 8:44:42 AM Page 3

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

Sample

Title:

B103202AFSFC042GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"'2 ) Uncertainty K-40 1.000 1460.82* 10. 66 l .09330E+006 2.02775E+OOS Co-60 1.000 1173.23* 99.85 5.73880E+004 l.63655E+004 1332.49* 99.98 6.48227E+004 l.71237E+004 Cs-137 1.000 661.66* 85.10 9.82435E+004 2.3287SE+004 Eu-155 0.346 86.55* 30.70 1.26081E+005 7.55914E+004 105.31 21.10 Tl-208 0.999 583.19* 85.00 1.4388SE+004 l.11431E+004 Pb-212 1.000 238.63* 43.60 5.21190E+004 3.80825E+004 Bi-214 0.732 609.32* 45.49 5.91088E+004 2.22457E+004 1120.29* 14 .92 1.34216E+005 6.23164E+004 1764.49 15.30 Pb-214 1. 000 295.22* 18.42 3.89233E+004 4.90415E+004 351.93* 35.60 4.02044E+004 2.57774E+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

[354]

Interference Corrected Activity Report 6/5/2018 8:44:42 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1 .093302E+006 2.027748E+005 Co-60 1.000 6.093711E+004 1.183112E+004 Cs-137 1.000 9.824352E+004 2.328746E+004 Eu-155 0.346 1. 2 608 llE+O 05 7.559136E+004 Tl-208 0.999 1.438852E+004 1 . 114 310E+OD4 Pb-212 1.000 5.211899E+004 3.808247E+004 Bi-214 0.732 6.759822E+004 2.095078E+004 Pb-214 1. 000 3.992711E+004 2.281738E+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

[355]

Interference Corrected Activity Report 6/5/2018 8:44:42 AM Page 5

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

Peak Locate Performed on: 6/5/2018 8:44:41 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV} Counts per Second  % Uncertainty Type Nuclide 1 32.40 1.8835E-002 168.15 2 75.30 2.4549E-001 46.14 10 933.77 2.7240E-002 75.46 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [356]

Nuclide MDA Report 6/5/2018 8:44:42 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC042GD Nuclide Library Us ed: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/M"'2 ) (pCi/M"'2 ) (pCi/M"2 ) (pCi/M"2 )

 +      K-40       1460.82*   10.66   9.045E+004     9.04E+004    1 .093E+006 3.588E+001
 +      Co-60      1173.23*   99. 85  1 .782E+004    1.70E+004    5.739E+004  8.017E+003 1332.49*   99.98   l .704E+004                 6.482E+004  7.575E+003 Nb-94       702.65    99.81   1.994E+004     1.82E+004  -1.822E+004   9.270E+003 871.09    99.89   1.821E+004                -1 .290E+003  8.331E+003 Ag-108m     433.90    90.50   2.278E+004     2.06E+004    5.009E+003  1.078E+004 614.30    89.80   2.962E+004                -9.886E+003   1. 4 08E+004 722.90    90.80   2.058E+004                  2.040E+003  9.507E+003 Cs-134      604.72    97.62   2.745E+004     2.47E+004  -1.020E+004   1.306E+004 795.86    85.46   2.470E+004                -6.264E+003   1.148E+004
 +      Cs-137      661.66*   85.10   2.309E+004     2.31E+004    9.824E+004  1.075E+004 Eu-152      121. 78   28.67   9.246E+004     7.91E+004  - 8.275E+004  4.506E+004 344.28    26.60   7.913E+004                -4.010E+004   3.770E+004 1408.01    21.07   8.227E+004                  4.916E+004  3.650E+004 Eu-154      123. 07   40.40   6.597E+004     3.71E+004    1.952E+004  3.215E+004 723.30    20.06   9.402E+004                  4 .730E+004 4.347E+D04 1274.43    34.80   3.709E+004                -3.645E+004   1.588E+004
 +      Eu-155       86.55*   30.70   1.146E+005     1 .15E+005   1 .261E+005 5.620E+004 105.31    21.10   1. 448E+O 05                5.163E+OD4  7.082E+004
 +      Tl-208      583.19*   85.00   1. 703E+004    1 .70E+004   1 .439E+004 7.763E+003 Bi-212      727.33     6.67   2.730E+005     2.73E+005  -9.476E+004   1 .258E+005
 +      Pb-212      238.63*   43.60   5.965E+004     5.96E+004    5.212E+004  2.887E+OD4
 +      Bi-214      609.32*   45.49   2.572E+004     2.57E+004    5.911E+004  l .142E+004 1120.29*   14 .92  7.421E+004                  1.342E+005  3.125E+004 1764.49    15 . 30 1.344E+005                  1 .235E+005 5.991E+004
 +      Pb-214      295.22*   18 .42  8.000E+004     3.79E+004    3.892E+004  3.749E+004 351.93*   35.60   3.793E+004                  4.020E+004  l.756E+004 Ra-226      186.21     3.64   6.478E+005     6.4BE+OOS  -1.834E+OOS   3.137E+005 Ac-228      338.32    11. 27  2.011E+005     9.40E+004    l.184E+005  9.620E+004 911.20    25.80   9.399E+004                  4.292E+004  4.392E+004 968.97    15 .80  l.481E+005                  2.484E+003  6.886E+004 Am-241       59 . 54  35.90   9.431E+004     9.43E+004   1.568E+004   4.603E+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]

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

Filename: 5456-A Report Generated On 6/5/2018 1 : 33: 34 PM Sample Title B103202AFSFC043GD Sample Description SFP/TRANSFER CANAL Sample Identification 043 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/5/2018 1:22:00 PM Acquisition Started 6/5/2018 1: 23: 33 PM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [358]

Peak Analysis Report 6/5/2018 1: 33 : 34 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC043GD Peak Analysis Performed on: 6/5/2018 1:33:34 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 126- 134 130.07 32.52 0.66 5.03E+001 26 .41 4.67E+001 2 287- 308 301.39 75.35 1.22 3.78E+D02 109.51 6.99E+002 3 332- 356 339.87 84.97 0.95 2.15E+002 106.19 6.28E+002 4 949- 961 955.19 238.80 0.35 3. 54E+001 37.85 l. 23E+002 5 1175- 1186 1181.84 295.46 0.80 3.75E+001 28.87 6.55E+001 6 1401- 1416 1408.16 352 .04 1. 25 7.98E+001 33.78 6.82E+001 7 2430- 2445 2438.22 609.55 0.83 7.80E+001 23.49 2.00E+OOl 8 2636- 2657 2646.58 661.64 1.44 1.04E+003 66.86 1 .93E+001 9 4684- 4703 4693.40 1173.35 0.63 9.99E+001 26. 15 2.0lE+OOl 10 5323- 5341 53 3 1 .68 1332.92 1. 87 1 .04E+002 22.33 6.49E+OOO 11 5834- 5855 5845.11 1461.28 1. 64 1 .65E+002 26.52 2.78E+OOO 12 7056- 7071 7063.16 1765.79 0.94 1. 69E+D01 11.49 5.08E+OOO M First peak in a mu ltiplet region m = Other peak in a multiplet region F "" Fitted singlet Errors quoted at 2. 000 sigma [359]

Interference Corrected Activity Report 6/5/2018 1:33:34 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:

B103202AFSFC043GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * * * * *

• I * * * * * * * * * *
• IDENTIFIED NUCLIDES . . .............. . . . ..,. ~ .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.13964E+006 2.07956E+005 Co-60 1.000 1173.23* 99.85 6.59308E+004 1 .80493E+004 1332.49* 99.98 7.23732E+004 l.66513E+004 Cs-137 1 .000 661.66* 85.10 6.17024E+005 B.39660E+004 Eu-155 0.345 86.55* 30.70 1. 74984E+005 9.31865E+004 105.31 21.10 Pb-212 1.000 238.63* 43.60 2.50205E+004 2.70658E+004 Bi-214 0 .705 609.32* 45.49 8.29071E+004 2.68880E+004 1120.29 14.92 1764.49* 15.30 9.07717E+004 6.20746E+004 Pb-214 1.000 295.22* 18.42 6.94455E+004 5.45804E+004 351.93* 35.60 8.30148E+004 3.75626E+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

[360]

Interference Corrected Activity Report 6/5/2018 1: 33: 34 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 1 .139637E+006 2.079556E+005 Co-60 1. 000 6.941111E+004 1 .22386SE+004 Cs-137 1. 000 6.170244E+OOS 8.396596E+004 Eu-155 0.345 1. 749842E+005 9.318651E+004 Pb-212 1.000 2.502055E+004 2.70658SE+004 Bi-214 0.705 8.414961E+004 2.467286E+004 Pb-214 1. 000 7.865362E+004 3.094292E+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

[361]

Interference Corrected Activity Report 6/5/2018 1: 33: 34 PM Page 5

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Peak Locate Performed on: 6/5/2018 1:33: 34 PM Peak Lo cate From Channel: 85 Peak Lo cate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.52 8.3797E-002 52.53 2 75.35 6.3081E-001 28.93 M = First peak in a multiplet region m ~ Other peak in a multiplet region F ~ Fitted singlet Errors quoted a t 2 . 000 sigma [362]

Nuclide MDA Report 6/5/2018 1: 33: 35 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC043GD 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  9.239E+004     9.24E+D04  1.140E+006    3.686E+004
 +      Co-60      1173.23*  99.85  2.009E+004     1.25E+004   6.593E+004   9.154E+003 1332.49*  99.98  1 .247E+004                7.237E+004   5.288E+003 Nb-94       702.65   99.81  1 .606E+004    l.61E+004 -2.845E+004    7.330E+003 871.09   99.89  2.184E+004                9.710E+003    1 .015E+004 Ag-108m     433.90   90.50  3.069E+004     2.20E+004 -9.986E+003    l .473E+004 614.30   89.80  3.057E+004               -3.167E+004    1.455E+D04 722.90   90.80  2.201E+004                2.177E+004    1.022E+004 Cs-134      604.72   97.62  2.927E+004     2.43E+004 -l.442E+004    1.397E+004 795.86   85.46  2.427E+004                4.448E+003    1.127E+004
 +      Cs-137      661.66*  85.10  1. 819E+004    1.82E+004  6.170E+005    8.296E+003 Eu-152      121.78   28.67  1.149E+OOS     7.48E+004  1 .339E+005   5.626E+004 344.28   26.60  1. 036E+005               3.330E+004    4.996E+004 1408.01   21. 07 7.485E+004                3.223E+004    3.280E+004 Eu-154      123.07   40.40  8.021E+004     4.92E+004 -3.090E+004    3.927E+004 723.30   20.06  9.885E+004                2.710E+004    4.589E+004 1274.43   34.80  4.923E+004               -4 .983E+003   2.195E+004
 +      Eu-155       86.55*  30.70  1. 387E+005    1.39E+OOS  1.750E+005    6.827E+004 105 .31  21.10  1. 568E+OOS               3.6D5E+004    7.683E+004 Tl-208      583.19   85.00  2.918E+004     2.92E+004  3.51DE+004    1. 3 84E+004 Bi-212      727.33    6.67  2.981E+005     2.98E+005 -1.769E+004    1.384E+005
 +      Pb-212      238.63*  43.60  4.371E+004     4.37E+D04  2.502E+D04    2.090E+004
 +      Bi-214      609.32*  45.49  2.996E+004     3.00E+D04  8.291E+D04    1. 354E+004 1120.29   14.92  1.595E+005                7.095E+004    7.392E+004 1764.49*  15.30  8.532E+004                9.077E+D04    3.540E+004
 +      Pb-214      295.22*  18.42  8.461E+004     5.19E+OD4  6.94SE+004    3.980E+004 351.93*  35.60  5.186E+004                8.301E+004    2.452E+004 Ra-226      186.21    3.64  8.039E+005     8.04E+005  4 .236E+005   3.918E+005 Ac-228      338.32   11.27  2.44SE+OOS     9.26E+OD4 -2.849E+OD3    1.179E+OOS 911. 20  25.80  9.258E+004                2.644E+004    4.322E+004 968.97   15.80  1.513E+005               -5.606E+OD4    7.046E+004 Am-241       59.54   35.90  1.024E+005     l.02E+005  2.387E+OD4    5.010E+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

[363]

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

Filename: 5456-A Report Generated On 6/5/2018 1:18:06 PM Sample Title Bl03202AFSFC044GD Sample Description SFP/TRANSFER CANAL Sample Identification 044 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 6/5/2018 1:07:00 PM Acquisition Started 6/5/2018 1: 08: 04 PM Live Time 600 . 0 seconds Real Time 600.5 seconds Dead Time 0 , 08 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [364]

Pec.~k Analysis Report 6/5/2018 1 :18:06 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC044GD Peak Analysis Performed on: 6/5/2018 1:18:05 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 1 126- 137 130.96 32.74 1.19 1 .66E+002 54.29 1 .92E+002 2 297- 307 301.38 75.34 1. 04 4.91E+001 67.67 4.57E+002 3 332- 346 339.59 84.90 0.85 7.34E+001 69.09 3.89E+002 4 1401- 1413 1407 .88 351.97 0.26 2.06E+001 24.73 5.04E+001 5 2328- 2340 2333.63 583.41 0.28 1 .78E+001 19.55 2.93E+001 6 2431- 2445 2437.37 609.34 1.01 4.44E+001 19.22 1.66E+001 7 2639- 2654 2646.78 661.70 1.06 5.83E+001 23.27 2.57E+001 8 4687- 4700 4693.36 1173.34 0.39 4.lSE+OOl 14.31 3.50E+OOO 9 5324- 5340 5332.47 1333.12 0.73 5.40E+001 15.50 1.99E+OOO 10 5834- 5857 5844.79 1461. 2 0 1. 80 1 .82E+002 26.98 O.OOE+OOO M = First peak in a mu ltiplet region m  :: Other peak in a mu ltiplet region F  :: Fitted singlet Errors quoted at 2 . 000 sigma [365]

In~erference Corrected Activity Report 6/5/2018 1: 18: 06 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:

B103202AFSFC044GD 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 14 6 0.82* 10.66 1 .25534E+006 2.15679E+005 Co-60 1 .000 11 73.23* 99.85 2.73966E+004 9.69479E+003 1332.49* 99.98 3.77659E+004 1 .12519E+004 Cs-137 1 .000 661.66* 85. 10 3.44594E+004 l .43529E+004 Eu-155 0 .345 86.55* 30.70 5 .96894E+004 5.74627E+004 1 05.31 21. 10 Tl-208 1 .000 583.19* 85. 00 9.88975E+003 l .09567E+004 Bi-214 0 .438 609.32* 45.49 4.72003E+004 2.12036E+004 112 0.29 14.92 1764.49 15.30 Pb-214 0 .439 295.22 18.42 351.93* 35.60 2.14756E+004 2.59458E+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

[366]

InLerference Corrected Activity Report 6/5/2018 1 : 18 :06 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 1. 255339E+006 2.156791E+005 Co-60 1. 000 3.181464E+004 7.344584E+003 Cs-137 1. 000 3.445938E+004 1.435295E+004 Eu-155 0.345 5.968945E+004 5.746270E+004 Tl-208 1. 000 9.889752E+003 1.095672E+004 Bi-214 0.438 4.720030E+004 2 .120364E+004 Pb-214 0.439 2.147557E+004 2.594577E+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 a t 2.000 sigma

[367]

In~erference Corrected Activity Report 6/5/2018 1 : 18: 06 PM Page 5

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

Peak Locate Performed on: 6/5/2018 1 : 18: 05 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.74 2.7639E-001 32. 74 2 75.34 8.1757E-002 137.96 M = First peak in a multiplet region m ~ Other peak in a multiplet region F Fitted singlet Errors quoted at 2.000 sigma [368]

Nu~lide MDA Report 6/5/2018 1:18:06 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC044GD Nuclide Library Us ed: 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  1.866E+004     1.87E+004    l.255E+006   O.OOOE+OOO
 +       Co-60     1173 .23*   99.85  8.537E+003     7.55E+003    2.740E+004   3.375E+003 1332.49*    99.98  7.554E+003                  3.777E+004   2.831E+003 Nb-94       702. 6 5  99.81  1.775E+004     l. 77E+004  -6.129E+003   8.173E+003 871.09    99.89  l.982E+004                  6.945E+002   9.133E+003 Ag-108m     433.90    90.50  2.201E+004     2.11E+004   -4.273E+003   1. 039E+O 04 614.30    89.80  2.759E+004                  4. 944E+002  1.307E+004 722.90    90.80  2.111E+004                  3.800E+003   9.774E+003 Cs-134      604.72    97.62  2.669E+004     2.0BE+004   -9.897E+003   1 .268E+004 795.86    85.46  2.085E+004                  9.415E+003   9.556E+003
 +       Cs-137      661.66*   85.10  1. 865E+004    l.87E+004    3.446E+004   8.527E+003 Eu-152      121.78    28.67  1.061E+OOS     7.00E+004   -7.907E+003   5.188E+004 344.28    26.60  7.003E+004                 -4.619E+004   3.315E+004 1408. 01    21. 07 7.67SE+004                  3.581E+004   3.375E+004 Eu-154      123.07    40.40  7.530E+004     5.38E+004    S.180E+004   3.682E+004 723.30    20.06  9.389E+004                 -4.012E+004   4.341E+004 1274.43     34.80  5.377E+004                 -2.751E+004   2.422E+004
 +       Eu-155       86.55*   30.70  9.178E+004     9.18E+004    5.969E+004   4.479E+004 105.31    21.10  1. 526E+O 05               -S.628E+004   7.473E+004
 +       Tl-208      583.19*   85.00  1. 768E+004    1. 77E+004   9.890E+003   8.084E+003 Bi-212      727.33     6.67  2.932E+005     2.93E+005    1. 792E+O 05 1.359E+OOS Pb-212      238.63    43.60  5.963E+004     5.96E+004    5.480E+004   2.886E+004
 +       Bi-214      609.32*   45.49  2.709E+004     2.71E+004    4.720E+004   1. 211E+004 1120 .29    14.92  l.496E+005                  3.910E+004   6.896E+004 1764.49     15.30  1.315E+005                  7.392E+004   5.851E+004
 +       Pb-214      295.22    18.42  1. 252E+O 05   4 .22E+004   1. 652E+004  6. 010E+ 004 351. 93*  35.60  4.216E+004                  2.148E+004   1. 967E+004 Ra-226      186.21     3.64  7.113E+005     7. 11E+005   1.lOOE+OOS   3.454E+OOS Ac-228      338.32    11. 27 1. 804E+OOS    9.70E+004    2.142E+003   8.586E+004 911.20    25.80  9.698E+004                  7.215E+004   4.542E+004 968.97    15.80  1. 396E+005                 1.156E+005   6.463E+004 Am-241       59.54    35.90  l.152E+005     l. 1 5E+005 -1.733E+004   5.650E+004
       +=Nuclide identified during the nuclide i dentification
       *=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

[369]

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

Filename: 5456-A Report Generated On 6/7/2018 3:04:43 PM Sample Title Bl03202AFSFC045GD Sample Description SFP/TRANSFER CANAL Sample Identification 045 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA,2 Sample Taken On 6/7/2018 2:54:00 PM Acquisition Started 6/7/2018 2:54:41 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 5/30/2018 Efficiency ID 3M90DSFP 2IN [370]

Peak Analysis Report 6/7/2018 3: 04: 43 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC045GD Peak Analysis Performed on: 6/7/2018 3: 04 :43 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 284- 305 300.86 75.21 1. 40 2.03E+002 77.75 3.49E+002 2 948- 962 955.70 238.93 0.49 7.03E+001 32.22 6.57E+001 3 1176- 1186 11 81 .31 295.33 0.52 1. 4BE+001 21.14 4.03E+001 4 1399- 1416 1407.61 351.90 0.37 6.71E+001 24.39 2.49E+001 5 2327- 2340 2333.07 583.27 1.21 2.45E+001 14.69 1 .05E+001 6 2428- 2446 2437.15 609.29 0.31 6.llE+OOl 21. 40 1 .59E+001 7 4684- 4699 4692.38 1173.10 0 .98 2.90 E+001 14.58 8.00E+OOO 8 5323- 5336 5329. 01 1332.25 1. 85 2.50E+001 14.25 9.02E+OOO 9 5832- 5853 5843.78 1460.95 1. 26 1 .77E+002 27.37 2.69E+OOO 10 7054- 7069 7 061. 44 1765.36 0 .33 2.23E+001 11.60 3.69E+OOO M = First peak in a mul tiplet region m = Other peak in a mul tiplet region F ""- Fitted singlet Errors quoted at 2. 000 sigma [371]

Interference Corrected Activity Report 6/7/20 18 3:04:43 PM Page 3

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

Sample

Title:

B103202AFSFC045GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

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

• l * * * * * * * * * * * *
• I * * *
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.22286E+006 2.16584E+005 Co-60 1 .000 1173.23* 99.85 1. 9142 8E+O 04 9.74708E+003 1332.49* 99.98 1. 74600E+004 l .00588E+004 Tl-208 1 .000 583.19* 85.00 1.36491E+004 8.34811E+003 Pb-212 1.000 238.63* 43.60 4.97262E+004 2.41615E+004 Bi-214 0.705 609.32* 45.49 6.48897E+004 2.40391E+004 1120.29 14.92 1764.49* 15.30 1. 19656E+OOS 6.29304E+004 Pb-214 1. 000 295.22* 18.42 2.72918E+004 3.93613E+004 351.93* 35.60 6.97723E+004 2.77179E+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 a t         2.000 sigma

[372]

Interference Corrected Activity Report 6/7/2018 3: 04: 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 REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 1.222865E+006 2.165838E+005 Co-60 1 .000 1. 832784E+004 6.999848E+003 Tl-208 1. 000 1. 364907E+004 8.348106E+003 Pb-212 1. 000 4.972620E+004 2.416148E+004 Bi-214 0.705 7.186358E+004 2.245642E+004 Pb-214 1. 000 5.569001E+004 2.266270E+004

      ? :  Nuclide is part of an undetermined so lution X: Nuclide rejected by the interference analysis
      @~Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at   2 .000 sigma

[373]

Interference Corrected Activity Report 6/7/2018 3: 04 :43 PM Page 5

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

• Peak Locate Performed on: 6/7/20 18 3: 04: 43 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.21 3.3804E-001 38.34 M ~ First peak in a multiplet region m ~ Other peak in a multiplet region F ; Fitted singlet Errors quoted at 2 . 000 sigma [374]

Nuclide MDA Report 6/7/2018 3: 04 : 43 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC045GD 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  9.031E+004    9.03E+004   1.223E+006     3.583E+004
 +       Co-60     1173.23*     99.85  1.246E+004    1 .25E+004  1.914E+004     5.338E+003 1332.49*     99.98  1.357E+004                1.746E+004     5.840E+003 Nb-94       702 . 65   99.81  l.702E+004    l .70E+004 -7.613E+003     7.810E+003 871 . 09   99.89  1.754E+004               -1.487E+003     7.993E+003 Ag-108m     433.90     90.50  1.998E+004    2.00E+004  -2.261E+004     9.378E+003 614.30     89.80  2.597E+004                l. 319E+003    l.225E+004 722.90     90.80  2.016E+004                5.062E+003     9.301E+003 Cs-134      604.72     97.62  2.552E+004    1.99E+004  -1.477E+004     1.209E+004 795.86     85.46  l.989E+004               -6.857E+003     9.078E+003 Cs-137      661.66     85.10  2.475E+004    2.48E+004   1.523E+004     1.158E+004 Eu-152      121.78     28.67  7.933E+004    6.45E+004   6.897E+003     3.850E+004 344.28     26.60  6.453E+004               -7.301E+004     3.040E+004 1408.01      21. 07 8.387E+004                2.137E+004     3.731E+004 Eu-154      123.07     40.40  5.683E+004    4 .08E+004  2.507E+004     2.759E+004 723.30     20.06  9.042E+004               -l.215E+004     4.167E+004 1274.43      34.80  4.078E+004               -7.674E+003     1.773E+004 Eu-155       86.55     30.70  9.399E+004    9.40E+004   7.269E+004     4.590E+004 105.31     21.10  1.213E+005               -6.489E+004     5.905E+004
 +       Tl-208      583.19*    85.00  1.146E+004    1.15E+004   1 .365E+004    4.975E+003 Bi-212      727.33      6.67  2.502E+005    2.50E+OOS  -1 .306E+005    1.145E+005
 +       Pb-212      238 . 63*  43.60  3.392E+004    3.39E+004   4.973E+004     l.600E+004
 +       Bi-214      609.32*    45.49  2.842E+004    2.84E+004   6.489E+004     1.277E+004 1120.29      14.92  l.609E+005                4.521E+003     7.460E+004 1764.49*     15.30  7.385E+004                1.197E+005     2.967E+004
 +       Pb-214      295.22*    18.42  6.496E+004    3.37E+004   2.729E+004     2.998E+004 351.93*    35.60  3.374E+004                6.977E+004     1.546E+004 Ra-226      186.21      3.64  5.739E+005    5.74E+005   4.114E+005     2.767E+005 Ac-228       338.32     11. 27 1.646E+005    8.23E+004  -3.198E+004     7.796E+004 911. 2 0   25.80  8.229E+004                9.903E+004     3.808E+004 968.97     15.80  1.384E+005                8.659E+003     6.402E+004 Am-241        59 . 54   35.90  8.069E+004    8.07E+004   1.934E+004     3.922E+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

[375]

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

Filename: 5456-A Report Generated On 6/7/2018 2:46:55 PM Sample Title B103202AFSFC046GD Sample Description SFP/TRANSFER CANAL Sample Identification 046 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/7/2018 2:36: 00 PM Acquisition Started 6/7/2018 2:36:54 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 5/30/2018 Efficiency ID 3M9 ODSFP 2 IN [376]

Peak Analysis Report 6/7/2018 2:46:56 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC046GD Peak Analysis Performed on: 6/7/2018 2:46:55 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 1 287- 305 300.96 75.24 0.81 1.90E+002 74.08 3.50E+002 2 333- 345 339.41 84.85 0.68 4.30E+001 53.17 2.49E+002 3 951- 962 955.38 238.85 1. 04 3.98E+001 25.69 4.92E+001 4 1176- 1186 1181.11 295.28 0.36 4.31E+001 20 .15 2.39E+001 5 1402- 1414 1408.14 352. 04 0.41 4.22E+001 23.31 3.38E+001 6 2036- 2049 2043.75 510. 94 1.43 4.38E+001 18.34 1.42E+001 7 2326- 2340 2333.03 583.26 0.41 2.82E+001 15.39 1.08E+001 8 2428- 2444 2435.98 609. 00 0.83 7.63E+001 19.87 6.72E+OOO 9 2637- 2652 2645.28 661.32 0.92 7.llE+OOl 20. 08 9.94E+OOO 10 3638- 3651 3644.01 911. 00 1. 04 3.llE+OOl 14.09 5.90E+OOO 11 4685- 4702 4692.46 1173. 12 0.37 6.60E+001 19.55 9.00E+OOO 12 5324- 5339 533 0 .12 1332.53 0.42 4.40E+001 15.03 4.00E+OOO 13 5832- 5853 5843.37 1460.84 1.17 l .52E+002 25.51 2.77E+OOO 14 7051- 7066 7058.92 1764.73 0.60 l .91E+001 11.19 3.89E+OOO M = First peak in a mul t iplet region m = Other peak in a mul t iplet region F - Fitted singlet Errors quoted at 2 . 000 sigma [377]

Interference Corrected Activity Report 6/7/2018 2:46:56 PM Page 3

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

Sample

Title:

Bl03202AFSFC046GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  "' . . . . . . . . . . . . . . .... .      IDENTIFIED NUCLIDES          * *

• I * * * * * * * * * * * *
• I I
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.04988E+006 l.98155E+005 Co-60 1.000 11 73.23* 99.85 4.35666E+004 1.33687E+004 1332.49* 99.98 3.07597E+004 1.07928E+004 Cs-137 1.000 661.66* 85 .10 4.19647E+004 1 .28847E+004 Eu-155 0.345 86.55* 30.70 3.49811E+004 4.38331E+004 105.31 21.10 Tl-208 1. 000 583.19* 85.00 l.57203E+004 8.77707E+003 Pb-212 1. 000 238.63* 43.60 2.81307E+004 l.87299E+004 Bi-214 0.705 609.32* 45.49 8.10407E+004 2.32469E+004 1120.29 14.92 1764.49* 15.30 1 .02477E+005 6.05784E+004 Pb-214 1 . 000 295.22* 18.42 7.97493E+004 3.93967E+004 351.93* 35.60 4.38930E+004 2.52417E+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 a t               2. 000 sigma

[378]

Interference Corrected Activity Report 6/7/2018 2: 46: 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 REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M~2 ) Uncertainty K-40 1 .000 1.049879E+006 1.981547E+005 Co-60 1 .000 3.581314E+004 8.397711E+003 Cs-137 1 .000 4.196472E+004 1.288470E+004 Eu-155 0.345 3.498112E+004 4.383305E+004 Tl-208 1. 000 1.572026E+004 8.777066E+003 Pb-212 1. 000 2.813073E+004 1.872994E+004 Bi-214 0.705 8.379225E+004 2.170369E+004 Pb-214 1. 000 5.432840E+004 2.125357E+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

[379]

Interference Corrected Activity Report 6/7/20 18 2: 46: 56 PM Page s

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

Peak Locate Performed on: 6/7/2018 2: 46: 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 75.24 3.1703E-001 38.95 6 510.94 7.3075E-002 41. 82 10 911. 0 0 5.1836E-002 45.32 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [380]

Nuclide MDA Report 6/7/2018 2:46:56 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC046GD 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 9.208E+004    9.21E+004   1.050E+006  3.671E+004
 +      Co-60      1173.23*   99.85  1.360E+004    1.00E+004   4.357E+004  5.90SE+003 1332. 49*  99.98  1.002E+004                3.076E+004  4 .064E+003 Nb-94       702. 6 5  99.81  1.928E+004    1.88E+004  -4.860E+003  8.937E+003 871.09    99.89  1.882E+004               -1. 516E+004 8.633E+003 Ag-108m     433. 9 0  90.50  1.974E+D04    1.97E+004  -5.248E+003  9.258E+003 614.30    89.80  2.889E+004               -1. 679E+003 1. 371E+004 722. 9 0  90.80  2.219E+004                1. 100E+004 1.031E+004 Cs-134      604.72    97.62  2.617E+D04    2.13E+D04   O.OOOE+OOO  1.242E+OD4 795.86    85.46  2.131E+004                1.459E+004  9.786E+003
 +      Cs-137      661.66*   85 .10 1 .219E+004   1.22E+004   4.196E+004  5.298E+003 Eu-152      121 .78   28.67  8.849E+D04    7.22E+004   6.401E+004  4.308E+OD4 344.28    26.60  7.216E+004               -5.006E+004  3.422E+004 1408.01    21.07  8.040E+004               -5.317E+004  3.557E+004 Eu-154      123.07    40 .40 6.149E+004    4.83E+004   3.749E+004  2.992E+004 723.30    20.06  1 .036E+005               1. 300E+005 4.825E+004 1274.43    34.80  4.827E+004               -1. 096E+004 2.147E+004
 +      Eu-155       86.55*   30.70  7.118E+004    7.12E+004   3.498E+004  3.449E+004 105. 31   21.10  1.220E+005               -7.642E+004  5.943E+004
 +      Tl-208      583.19*   85.00  1.171E+004    1 .17E+004  l.572E+004  5.099E+003 Bi-212      727.33     6.67  3.053E+005    3.05E+005  -4.537E+004  1 .420E+005
 +      Pb-212      238.63*   43.60  2.795E+004    2.80E+004   2.813E+004  1 .302E+004
 +      Bi-214      609.32*   45.49  1.942E+004    1 .94E+004  8.104E+004  8.271E+003 1120.29    14.92  1.714E+005                1.068E+005  7.984E+004 1764.49*   15.30  7.615E+004                1. 02SE+OOS 3.082E+004
 +      Pb-214      295.22*   18.42  5.150E+004    3.59E+004   7.975E+004  2.325E+004 351.93*   35.60  3.593E+004                4.389E+004  1.656E+004 Ra-226      186.21     3.64  5.946E+005    5.95E+005   6.701E+005  2.871E+005 Ac-228      338.32    11.27  1 .710E+005   9.32E+004   6.861E+004  8.114E+004 911. 20   25.80  9.322E+004                7.219E+004  4.354E+004 968.97    15.80  1 .396E+005               6.496E+004  6.463E+004 Am-241       59.54    35.90  8.740E+004    8.74E+004   6.786E+003  4 .258E+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

[381]

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

Filename: 5456-A Report Generated On 6/7/2018 2:29:19 PM Sample Title B103202AFSFC047GD Sample Description SFP/TRANSFER CANAL Sample Identification 047 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 6/7/2018 2:18:00 PM Acquisition Started 6/7/2018 2:19 :17 PM Live Time 600 . O seconds Real Time 600.7 seconds Dead Time 0 . 12 % Energy Calibration Used Done *on 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [382]

Peak Analysis Report 6/7/2018 2:29:19 PM Page 2

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

Detector Name: 54 56-A Sample

Title:

B103202AFSFC047GD Peak Analysis Performed on: 6/7/2018 2:29:19 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 297- 307 301.21 75.30 0 .76 1 .10E+002 53.60 2.53E+002 2 333- 345 340.49 85. 12 1. 01 4.76E+001 48.89 2.09E+002 3 365- 375 370.36 92.59 0 .45 1 .98E+001 38.46 1 .47E+002 4 949- 960 955.69 238.92 0 .41 4.63E+001 26.75 5.27E+001 5 1176- 1186 1181.75 295.44 0 .69 1 .53E+001 20.06 3.57E+001 6 1400- 1415 1407.83 351.96 1. 07 4.40E+001 25.70 4.00E+OOl 7 1438- 1449 1443.30 360.82 0 .30 6.79E+OOO 16.52 2.42E+001 8 1497- 1508 1502.73 375.68 0 .47 2.09E+001 16.31 1.81E+001 9 2037- 2048 2042.52 510.63 0 .37 2.70E+001 20.21 3.00E+OOl 10 2429- 2443 2436.37 609.09 0 .40 6.44E+001 22.27 2.06E+001 11 2640- 2653 2645.71 661.43 0 .59 5.54E+001 20.37 1.66E+001 12 4683- 4700 4692.52 1173.13 1.39 6.72E+001 18.91 6.78E+OOO 13 5322- 5338 5329.55 1332.39 0 .61 6.38E+001 17.56 4.25E+OOO 14 5833- 5854 5843.66 1460 .92 1. 97 1 .42E+002 26.98 1.07E+001 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 [383]

Interference Corrected Activity Report 6/7/2018 2: 29: 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 REPORT *****

Sample

Title:

Bl03202AFSFC047GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * ****** *** j .... . . . . . .      IDENTIFIED NUCLIDES           I' a *

• o, 9 e
• e * * <I * * - 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 ANALYSIS *****

Filename: 5456-A Report Generated on 6/7/2018 1: 06:23 PM Sample Title B103202AFSFC048GD Sample Description SFP/TRANSFER CANAL Sample Identification 048 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/7/2018 12:55 : 00 PM Acquisition Started 6/7/2018 12: 56: 22 PM Live Time 600 . 0 seconds Real Time 601.0 seconds Dead Time 0 . 16 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [388]

Peak Analysis Report 6/7/2018 1 :06:23 PM Page 2

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

Detector Name: 5456-A Sample

Title:

Bl03202AFSFC048GD Peak Analysis Performed on: 6/7/2018 1:06:23 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 1 286- 307 300.87 75.22 1. 16 2.28E+002 83.47 4 .02E+002 2 950- 961 956. 11 239.03 0 .33 2.99E+001 27. 62 6.41E+001 3 1175- 1187 1181.19 295.30 0. 72 2.73E+001 22.02 3.58E+001 4 1401- 1414 1407.74 351.93 0 .97 4.14E+001 24.11 3.76E+001 5 2362- 2373 2367.93 591.98 0 .29 3.00E+OOO 11.49 1.20E+001 6 2429- 2445 2437.32 609.33 0 .96 8.27E+001 21.43 l.03E+001 7 2637- 2654 2645.42 661.35 1. 05 6.0SE+OOl 21.06 l .55E+001 8 4475- 4488 4481.23 1120.31 0 .49 2.31E+D01 10. 74 1 .92E+OOO 9 4685- 4699 4692.51 1173.13 0 .65 4.17E+001 16.61 9.28E+OOO 10 5320- 5338 5329.83 1332.46 0 .30 5.93E+001 17.35 4.75E+OOO 11 5833- 5854 5843.24 1460.81 1. 38 1.34E+OD2 24.83 5.5DE+OOO 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 [389]

Interference Correcte d Activity Report 6/7/2018 1 : 06: 23 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:

B103202AFSFC048GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * * * * * * * * * * *

• I * * * .. '" IDENTIFIED NUCLIDES . . ... ....... . . . .. . ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 14 60.82* 10.66 9.20670E+005 l.89011E+005 Co-60 1.000 11 73.23* 99.85 2.75399E+004 l.11817E+004 1332.49* 99.98 4.14196E+004 l.25760E+004 Cs-137 1.000 661.66* 85.10 3.57036E+004 1 .31553E+004 Tl-208 0.884 583.19* 85.00 1 .68308E+003 6.45084E+003 Pb-212 1 .000 238.63* 43.60 2.11222E+004 l.98313E+004 Bi-214 0.732 609.32* 45.49 8.78806E+004 2.51054E+004 11 20.29* 14.92 9.98009E+004 4.71370E+004 17 64.49 15.30 Pb-214 1.000 295.22* 18.42 5.04180E+004 4.15410E+004 351.93* 35.60 4 .3016SE+004 2.59982E+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 6/7/2018 1: 06: 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 REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2) Uncertainty K-40 1.000 9.206697E+005 l.890108E+005 Co-60 1. 000 3.366799E+004 8.356330E+003 Cs-137 1.000 3.570363E+004 1.315529E+004 Tl-208 0.884 1.683083E+003 6.450845E+003 Pb-212 1.000 2.112219E+004 l.983132E+004 Bi-214 0.732 9.051476E+004 2.215853E+004 Pb-214 1.000 4.509964E+004 2.203804E+C04

      ? = 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

[391]

Interference Correcte d Activity Report 6/7/2018 1: 06 : 23 PM Page 5

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

Peak Locate Performed on: 6/7/2018 1: 06: 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 75.22 3.8079E-001 36.53 M

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

[392]

Nuclide MDA Report 6/7/2018 1:06:23 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC048GD 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  l.219E+005    l.22E+OOS    9.207E+005  5.160E+004
 +      Co-60      1173.23*   99.85  1. 312E+004   l. 11E+004  2.754E+004   5.666E+003 1332.49*   99.98  l.110E+004                4.142E+004   4.606E+003 Nb-94        702.65   99.81  1. 702E+004   1. 59E+004  2.461E+003   7.810E+003 871.09   99.89  1.590E+004               -3.100E+003   7.174E+003 Ag-108m      433.90   90.50  2.034E+004    l.98E+004   2.102E+002   9.554E+003 614.30   89.80  2.924E+004               -l.211E+004   1.389E+004 722.90   90.80  1. 977E+004               1.487E+004   9.106E+003 Cs-134       604.72   97.62  2.791E+004    2.20E+004  -5.241E+003   l .329E+004 795.86   85.46  2.198E+004                l .178E+004  l .012E+004
 +      Cs-137       661.66*  85.10  l.539E+004    l .54E+004  3.570E+004   6.898E+003 Eu-152       121. 78  28.67  8.849E+004    6.44E+004   5.183E+004   4.308E+004 344.28   26.60  6.653E+004               -1. 224E+O 05 3.140E+004 1408 .01   21.07  6.436E+004               -1.482E+004   2.756E+004 Eu-154       123.07   40. 40 6.183E+004    5.79E+004  -3.012E+004   3.009E+004 723.30   20.06  8.862E+004                3.027E+004   4.078E+004 1274.43    34.80  5.792E+004               -9.674E+003   2.630E+004 Eu-155        86.55   30.70  9.753E+004    9.7SE+004   l.243E+OOS   4 .767E+004 105.31   21. 10 1.294E+005               -3.408E+004   6.310E+004
 +      Tl-208       583.19*  85.00  l.163E+004    l .16E+004  1. 683E+003  5.057E+003 Bi-212       727.33    6.67  2.617E+OOS    2.62E+005   8.502E+004   l .202E+005
 +      Pb-212       238.63*  43.60  3.143E+004    3.14E+004   2.112E+004   l.476E+004
 +      Bi-214       609.32*  45.49  2.269E+004    2.27E+004   8.788E+004   9.908E+003 1120.29*   14 .92 4.588E+004                9.980E+004   1. 709E+O 04 1764.49    15.30  1.703E+005                2.091E+005   7.791E+004
 +      Pb-214       295.22*  18.42  6.403E+004    3.77E+004   5.042E+004   2.951E+004 351.93*  35.60  3.769E+004                4.302E+004   1.744E+004 Ra-226       186.21    3.64  5.946E+005    5.95E+005   4.634E+OOS   2.871E+005 Ac-228       338.32   11. 27 1 .791E+005   8.52E+004   6.099E+004   8.520E+004 911.20   25.80  8.517E+004               -3.540E+004   3.951E+004 968.97   15.80  1.333E+005                1.336E+005   6.150E+004 Am-241        59.54   35.90  8.696E+004    8.70E+004   9.029E+004   4.236E+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

[393]

• • • • • GAMMA S P E C T R U M ANALYSIS *****

Filename: 5456-A Report Generated On 6/7/2018 1: 20 : 44 PM Sample Title B103202AFQFC048GD Sample Description SFP/TRANSFER CANAL Sample Identification 048 QC Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 6/7/2018 1: 10:00 PM Acquisition Started 6/7/2018 1: 10 :42 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 5/30/2018 Efficiency ID 3M90DSFP 2IN [394]

Peak Analysis Report 6/7/2018 1: 20: 44 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFQFC048GD Peak Analysis Performed on: 6/7/2018 1: 20 :44 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 297- 309 301.07 75.27 0.54 8.59E+001 58.71 2.91E+002 2 335 - 345 340.04 85. 01 0.55 6.29E+001 46 .26 1 .94E+002 3 947- 960 955.28 238.82 0. 70 4.23E+001 27.98 5.57E+001 4 1401- 1415 140 7.85 351.96 0.64 7.02E+001 24.04 2.58E+001 5 2325- 2337 2330.80 582.70 0.32 2.27E+001 13.74 9.33E+OOO 6 2428- 2445 2436.28 609.07 0.92 6.88E+001 18.13 4.19E+OOO 7 2638- 2652 2644.52 661. 13 1. 12 4 .73E+001 20 .69 2.07E+001 8 4474- 4487 4480.50 1120.13 0.37 2 .13E+001 12.64 6.71E+OOO 9 4684- 4698 46 9 1 .84 1172.96 1.76 3.69E+001 16.61 l .llE+OOl 10 5323- 5337 5330.93 1332.73 0.54 3.81E+001 14. 11 3.86E+OOO 11 5832- 5853 5843.04 1460.76 1.09 l.44E+002 25.73 5.54E+OOO 12 7051- 7066 7058.44 1764.61 0.52 2.lOE+OOl 11. 50 4.00E+OOO M = First peak in a mul t iplet region m ; Other peak in a mul t iplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [395]

Interference Corrected Activity Report 6/7/2018 1 : 2 0 : 44 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:

B103202AFQFC048GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  ' ' ...................... IDENTIFIED NUCLIDES           .. 4 ~ * * * * .. * * * * * * * * * * . ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10 .66 9.96234E+005 l.97435E+005 Co-60 1.000 1173.23* 99.85 2.43328E+004 l.11369E+004 1332.49* 99.98 2.66673E+004 l.00954E+004 Cs-137 1. 000 661. 66* 85 .10 2.79392E+004 l.26660E+004 Eu-155 0. 345 86.55* 30.70 5.11315E+004 3.89803E+004 10 5.31 21.10 Tl-208 1.000 583.19* 85.00 1.26247E+004 7.80205E+003 Pb-212 1.000 238.63* 43.60 2.98825E+004 2.03676E+004 Bi-214 1.000 609.32* 45.49 7.31096E+004 2.11691E+004 1120.29* 14 .92 9.20351E+004 5.51265E+004 1764.49* 15.30 1.12615E+OOS 6.23160E+004 Pb-214 0 .439 295.22 18.42 351.93* 35.60 7.29732E+004 2.75959E+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

[396]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 9.962341E+005 1 .974350E+005 Co-60 1.000 2.561428E+004 7.479696E+003 Cs-137 1. 000 2 . 793920E+004 1.266598E+004 Eu-155 0.345 5.113148E+004 3.898028E+004 Tl-208 1. 000 l .262469E+004 7.802046E+003 Pb-212 1. 000 2.988249E+004 2.036760E+004 Bi-214 1. 000 7.892951E+004 1.883757E+004 Pb-214 0.439 7.297324E+004 2.759588E+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 a t   2.000 sigma

[397]

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Peak Locate Performed on: 6/7/2018 1: 20 :44 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.27 1. 4320E- 0 01 68.33 M ~ First peak i n a multiplet region m = Other peak i n a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [398]

Nuclide MDA Report 6/7/2018 1: 20: 44 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFQFC048GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

 +      K-40       1460.82*   10.66  1.229E+OOS    1.23E+005    9.962E+005   5.212E+004
 +      Co-60      1173.23*   99.85  1 .410E+004   9.74E+003    2.433E+004   6.155E+003 1332.49*   99.98  9.745E+003                 2.667E+004   3.926E+003 Nb-94        702. 65  99.81  1.606E+004    l .61E+004   1.343E+004   7.330E+003 871.0 9  99.89  1.902E+004                 1.002E+003   8.735E+003 Ag-lOBm      433.90   90.50  1.824E+004    1 .82E+004  -4.989E+003   8.506E+003 614.30   89.80  2.610E+004                -S.449E+003   1.232E+004 722.90   90.80  2.036E+004                 2.063E+004   9.398E+003 Cs-134       604.72   97.62  2.418E+004    1 .96E+004   2.935E+003   1.142E+004 795.86   85.46  l.964E+004                -1.626E+004   8.954E+003
 +      Cs-137       661.66*  85.10  1.660E+004    1 .66E+004   2.794E+004   7.502E+003 Eu-152       121. 78  28.67  8.230E+004    6.66E+004    7.072E+003   3.999E+004 344.28   26.60  6.878E+004                -5.634E+004   3.252E+004 1408. 01   21.07  6.661E+004                 1.026E+004   2.868E+004 Eu-154       123. 07  40 .40 5.928E+004    5.11E+004    6.353E+004   2.881E+004 723.30   20.06  8.862E+004                 2.066E+004   4.078E+004 1274.43    34.80  5.110E+004                 3.249E+004   2.289E+004
 +      Eu-155        86.55*  30.70  6.033E+004    6.03E+004    5.113E+004   2.906E+004 105. 31  21.10  1.239E+OOS                 9.484E+004   6.035E+004
 +      Tl-208       583.19*  85.00  1.058E+004    1.06E+004    1.262E+004   4.538E+003 Bi-212       727.33    6.67  2.532E+005    2.53E+005    5.220E+004   1.159E+005
 +      Pb-212       238.63*  43.60  3.074E+004    3.07E+004    2.988E+004   1.441E+004
 +      Bi-214       609.32*  45 .49 1.564E+004    1.56E+004    7.311E+004   6.381E+003 1120.29*   14.92  7.309E+004                 9.204E+004   3.070E+004 1764.49*   15.30  7.576E+004                 1. 126E+005  3.062E+004
 +      Pb-214       295.22   18.42  1.162E+OOS    3.23E+004    9.817E+004   5.562E+004 351.93*  35.60  3.231E+004                 7.297E+004   1.475E+004 Ra-226       186.21    3.64  5.465E+005    5 .4 7E+005 -1.375E+005   2.631E+005 Ac-228       338.32   11. 27 1. 751E+OOS   8.23E+004   -5.557E+004   8.320E+004 911.20   25.80  8.229E+004                 3.706E+004   3.808E+004 968.97   15.80  1.268E+005                 3.343E+004   5.821E+004 Am-241        59.54   35.90  8.200E+004    8.20E+004   -4.427E+004   3.988E+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

[399]

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

Filename: 5456-A Report Generated On 6/7/2018 12:52: 11 PM Sample Title B103202AFSFC049GD Sample Description SFP/TRANSFER CANAL Sample Identification 049 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"'2 Sample Taken On 6/7/2018 12:42: 00 PM Acquisition Started 6/7/2018 12:42: 10 PM Live Time 600. 0 seconds Real Time 600.8 seconds Dead Time 0 , 12 % Energy Calibration Used Done On 3 I 15/201s Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [400]

Peak Analysis Report 6/7/2018 12:52: 11 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC049GD Peak Analysis Performed on: 6/7/2018 12:52: 11 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- 307 301 .22 75.31 0.90 1.08E+002 54.99 2.68E+002 2 334- 350 340.42 85. 11 1.12 7.80E+001 60.77 2.70E+002 3 950- 963 955.16 238.79 0.53 4.49E+001 29.16 6.0lE+OOl 4 1401- 1415 1407.79 351.95 1. 25 5.27E+001 24.84 3.53E+001 5 2038- 2049 2043.33 510.83 0.61 1 .88E+001 18.78 2.72E+001 6 2326- 2337 233 1 .01 582.75 1. 11 2.47E+001 14.22 1. 03E+001 7 2429- 2444 2436.47 609.12 0.92 4.91E+001 21.44 2.19E+001 8 2637- 2654 2646.10 661.53 1. 08 7.24E+001 21.73 1.36E+001 9 4683- 4700 469 1 .52 1172.88 1. 33 6.50E+001 16.12 O.OOE+OOO 10 5323- 5339 533 0 .46 1332.61 0.94 6.29E+001 18.74 8.07E+OOO 11 5834- 5854 5843.32 1460.83 1. 27 1 .36E+002 25.17 5.68E+OOO 12 7051- 7066 7058.49 1764.62 0.34 3.00E+OOl 10.95 O.OOE+OOO 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 [401]

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Sample

Title:

B103202AFSFC049GD 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 9.40152E+005 l.91810E+005 Co-60 1.000 1173.23* 99. 85 4 .29025E+004 l.11826E+004 1332.49* 99.98 4 .39921E+004 l .35641E+004 Cs-137 1.000 661.66* 85.10 4 .27430E+004 1 .38214E+004 Eu-155 0 .345 86.55* 30.70 6.34157E+004 5.09924E+004 105.31 21.10 Tl-208 1.000 583. 19* 85. 00 1.37745E+004 8.08852E+003 Pb-212 1.000 238.63* 43.60 3.17169E+004 2.12479E+004 Bi-214 0.705 609.32* 45.49 5.21212E+004 2.36238E+004 1120.29 14.92 1764.49* 15.30 1.60880E+005 6.01416E+004 Pb-214 0.439 295.22 18.42 351.93* 35.60 5.48097E+004 2.72836E+004

        *~Energy line found in the spectrum.
        @ = Energy line not used for Weighted Mean Activi ty Energy Tolerance :              10.000 keV Nuclide confidence index threshold                    0.30 Errors quoted a t           2.000 sigma

[402]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 9.401518E+OOS 1.918103E+OOS Co-60 1. 000 4.334338E+004 8.628374E+003 Cs-137 1. 000 4.274300E+004 1.382139E+004 Eu-155 0.345 6.341574E+004 5.099240E+004 Tl-208 1. 000 1. 3 774 54E+004 8.088524E+003 Pb-212 1.000 3.171691E+004 2.124787E+004 Bi-214 0.705 6.665892E+004 2.198833E+004 Pb-214 0.439 5.480967E+004 2.728364E+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

[403]

Interference Corrected Activity Report 6/7/2018 12: 52: 11 PM Page 5

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Peak Locate Performed on: 6/7/2018 12: 52: 11 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 75.31 1.7997E-001 50.92 5 510.83 3.1304E-002 99.99 M First peak in a multiplet region m - Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma [404]

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Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC049GD 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  1.252E+005     l.25E+005   9.402E+005  5.325E+004
 +      Co-60      1173.23*   99.85  1.786E+003     1.79E+003   4.290E+004  O.OOOE+OOO 1332.49*   99.98  l .336E+004                4.399E+004  5.733E+003 Nb-94       702.65    99.81  1 .861E+004    1.BOE+004  -2.011E+003  8.606E+003 871 .0 9  99.89  1 .797E+004                1 .830E+004 8.212E+003 Ag-108m     433.90    90.50  2.010E+004     1.83E+004   9.020E+003  9.437E+003 614.30    89.80  2.771E+004                -1. 722E+004 1.313E+004 722.90    90.80  1 .833E+004               -1. 573E+004 8.384E+003 Cs-134      604.72    97.62  2.638E+004     2.13E+004   4.264E+003  1. 252E+004 795.86    85.46  2.131E+004                 1.115E+003  9.786E+003
 +      Cs-137      661.66*   85.10  1 .473E+004    1.47E+004   4 .274E+004 6.565E+003 Eu-152      121.78    28.67  8.068E+004     7.29E+004  -4.434E+004  3.917E+004 344.28    26.60  7.596E+004                -1.053E+005  3.611E+004 1408 .0 1  21. 07 7.289E+004                 3.072E+004  3.182E+004 Eu-154      123 .0 7  40. 40 5.668E+004     S.20E+004   3.132E+003  2.751E+004 723.30    20.06  8.201E+OCl4               -1 .027E+005 3.747E+004 1274.43    34.80  5.201E+004                -5.714E+003  2.334E+004
 +      Eu-155       86.55*   30.70  7.994E+004     7.99E+004   6.342E+004  3.887E+004 105.31    21. 10 1 .253E+005                7.793E+004  6.108E+004
 +      Tl-208      583.19*   85. 00 1. 0 81E+004   1.08E+004   1.377E+004  4.652E+003 Bi-212      727.33     6.67  2.805E+005     2.81E+005   1.837E+005  1.296E+005
 +      Pb-212      238.63*   43.60  3.204E+004     3.20E+004   3.172E+004  1.507E+004
 +      Bi-214      609.32*   45.49  3.l24E+004     1. 45E+004  5.212E+004  1.418E+004 1120.29    14.92  1.582E+005                 2.223E+003  7.323E+004 1764.49*   15.30  1. 451E+004                1.609E+005  O.OOOE+OOO
 +      Pb-214      295.22    18.42  1.152E+005     3.73E+004   7.446E+004  5.512E+004 351.93*   35.60  3.730E+004                 5.481E+004  l.724E+004 Ra-226      186.21     3.64  6.031E+OOS     6.03E+OOS  -7.329E+004  2.914E+005 Ac-228      338.32    11. 27 1.824E+005     8.73E+004   6.807E+004  8.684E+004 911. 20   25.80  8.726E+004                -9.194E+003  4.056E+004 968.97    15.80  l.589E+OOS                 6.535E+004  7.427E+004 Am-241       59.54    35.90  7.750E+004     7.75E+004  -8.255E+002  3.763E+004
       + : Nuclide identified during the nuclide i dentification
       * : 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

[405]

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

Filename: 5456-A Report Generated On 6/2/2018 10: 02:21 AM Sample Title B103202AFSFC050GD Sample Description SFP/TRANSFER CANAL Sample Identification 050 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2. 830E+001 MA2 Sample Taken On 6/2/2018 9:52: 00 AM Acquisition Started 6/2/2018 9:52:19 A.IV! Live Time 600. O seconds Real Time 600 . 4 seconds Dead Time 0. 07 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [406]

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Detector Name: 5456-A Sample

Title:

B1 03202AFSFC050GD Peak Analysis Performed on: 6/2/2018 10:02:21 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 1 126- 134 129.98 32.50 0.93 6.43E+001 23.83 3.07E+001 2 164- 176 167.03 41.76 0.47 5.99E+OOO 34.53 1.10E+002 3 296- 307 301.13 75.28 0.82 1 .08E+002 64.04 3.63E+002 4 1401- 1415 1407.47 351.87 1.26 6.55E+001 25.90 3.55E+001 5 2430- 2443 2436.19 609.05 0.85 5.21E+001 20.92 1 .89E+001 6 2635- 2657 2645.33 661.33 1.26 5. 01E+ 002 49.14 2.62E+001 7 3637- 3650 3643.88 910.97 0.41 1.06E+001 14.04 1.34E+001 8 4473- 4486 4479.89 1119 .97 0.65 l.50E+001 14.63 1. 40E+001 9 4682- 4699 4690.96 1172.74 1.23 6. lOE+ OOl 15.62 O.OOE+OOO 10 5319- 5337 5327.89 1331.97 0.35 5.90E+001 15.36 O.OOE+OOO 11 5831- 5853 5842.32 1460.58 1.26 1.71E+002 28.60 8.57E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [407]

Interference Corrected Activity Report 6/2/2018 10:02:21 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1. 182119E+006 2.223649E+OOS Co-60 1. 000 4.07298SE+004 7.785636E+003 Cs-137 1. 000 2.957559E+OOS 4.58660BE+004 Bi-214 0.732 5.646088E+004 2.178893E+004 Pb-214 0.439 6.815966E+004 2.906297E+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

[408]

Interference Corrected Activity Report 6/2/2018 10:02 :21 AM Page S

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

Peak Locate Performed on: 6/2/20 18 10 :02:21 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 Nuclide 1 32.50 1. 0718E-001 37.06 2 41 .76 9.9784E-003 576.81 3 75.28 1. 8058E-001 59. 10 7 910.97 1. 7708E-002 132. 10 Tol. Ac-228 M ~ First peak in a multiplet region m ~ Other peak in a multiplet region F Fitted singlet Errors quoted a t 2 . 000 sigma [409]

Nuclide MDA Report 6/2/2018 10: 02 :21 AM Page 6

• • • • • N U C L I D E MD A RE PORT *****

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC050GD 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  1.493E+005       1. 49E+005   1.182E+006   6.530E+004
 +      Co-60      1173.23*   99.85  l.786E+00 3      1 .79E+003   4.026E+004   O.OOOE+OOO 1332.49*   99.98  1.891E+003                    4.124E+004   O.OOOE+OOO Nb-94       702.65    99.81  1.757E+004       1 .76E+004   6.792E+003   8.084E+003 871 . 09  99.89  1.797E+004                    3.409E+003   8.212E+003 Ag-108m     433.90    90.50  2.556E+004       1. 79E+004  -3.528E+003   1.217E+004 614.30    89.80  2.819E+004                    3.378E+003   1.336E+004 722.90    90.80  1.789E+004                   -2.878E+004   8.166E+003 Cs-134      604.72    97.62  2.541E+004       2.11E+004   -5.902E+003   1.204E+004 795.86    85.46  2.108E+004                   -4 .082E+003  9.672E+003
 +      Cs-137      661. 66*  85.10  2.131E+004       2.13E+004    2.958E+005   9.8SSE+003 Eu-152      121. 7 8  28.67  9.286E+004       7.67E+004    6.518E+004   4.526E+004 344.28    26.60  8.352E+004                   -l.863E+004   3.990E+004 1408 .0 1  21. 07 7.675E+004                    3.134E+003   3.37SE+004 Eu-154      123 .0 7  40.40  6.466E+004       5.63E+004    1.694E+004   3.1SOE+004 723.30    20.06  8.201E+004                   -7.381E+004   3. 747E+004 1274.43    34.80  S.630E+004                   -4.697E+003   2.549E+004 Eu-155       86.55    30.70  1. 072E+005      1 . 07E+005  1 .090E+005  5.249E+004 105.31    21.10  1.365E+OOS                   -2.704E+004   6.669E+004 Tl-208      583. 19   85.00  2.610E+004       2.61E+004    2.883E+004   1.229E+004 Bi-212      727.33     6.67  2.753E+005       2.75E+005    6.SOOE+004   1.270E+005 Pb-212     238.63    43.60  5.665E+004       5.66E+004    6.904E+004   2.737E+004
 +      Bi-214      609.32*   45.49  2.934E+004       2.93E+004    5.534E+004   1.323E+004 1120.29*   14 .92 9.997E+004                    6.48SE+004   4 .413E+004 1764.49    15.30  1 .512E+005                   1 .609E+005  6.833E+004
 +       Pb-214     295.22    18.42  1 .361E+005      3.74E+004    1 .082E+004  6.555E+004 351.93*   35.60  3.740E+004                    6.816E+004   1.729E+004 Ra-226     186.21     3.64  6.785E+OOS       6.78E+005    5.670E+OOS   3.290E+OOS Ac-228      338.32    11. 27 1.967E+005       7.8SE+004    5.322E+004   9.400E+004 911.20    25.80  7.854E+004                    2.485E+004   3.620E+004 968.97    15 .80 1.479E+OOS                    l.277E+OOS   6.876E+004 Am-241       59.54    35.90  9.173E+004       9. 1 7E+004  7.035E+004   4.474E+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 per form the decay correction

[410]

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

Filename: 5456-A Report Generated On 6/7/2018 2:12: 11 PM Sample Title B103202AFSFC051GD Sample Description SFP/TRANSFER CANAL Sample Identification 051 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/7/2018 2:02: 00 PM Acquisition Started 6/7/2018 2:02:09 PM Live Time 600.0 seconds Real Time 600.6 seconds Dead Time 0 . 11 %

             . Energy Cal.ibra t ion Used Done On            3/15/2018 Efficiency Calibration Used Done On           5/30/2018 Efficiency ID                                 3M90DSFP 2IN

[411]

Peak Analysis Report 6/7/2018 2 : 12 :11 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC051GD Peak Analysis Performed on: 6/7/2018 2:12:10 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- 308 301.37 75.34 0.81 5.45E+001 57.61 2.94E+002 2 814- 823 818.56 204.64 0.39 5.34E+OOO 20. 07 4.17E+001 3 949- 960 954.51 238.63 0.69 2.72E+001 28.10 6.68E+001 4 1175- 1187 118 1 .38 295.34 0.88 3.44E+001 24.42 4.36E+001 5 1400- 1415 1407.40 351.85 1. 29 5.19E+001 24.89 3.41E+001 6 2430- 2444 2436.26 609.07 1. 41 5.19E+001 20. 81 1.91E+001 7 2640- 2652 2645.85 661.46 0.36 2.24E+001 16.38 1 .66E+001 8 3636- 3649 3642.79 910.70 0.82 2.30E+001 13.00 7.00E+OOO 9 5832- 5853 5842.61 1460.65 1. 43 1.60E+002 25.30 O.OOE+OOO 10 7052- 7067 7059.15 1764.79 0.54 2.39E+001 11 .04 2.07E+OOO M m

 =

First peak in a mul t iplet region Other peak in a mul t iplet region F = Fitted singlet Errors quoted at 2.000 sigma [412]

Interference Corrected Activity Report 6/7/20 18 2: 12: 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 REPORT *****

Sample

Title:

B103202AFSFC051GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Z ion Lib-BNL.NLB

  . ....... .. ...... .. " .... . IDENTIFIED NUCLIDES          ~ r "' "' * * * * * * * * ,. * " * "' ,. *

• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1. 000 1460.82* 10.66 1.10336E+006 l.99034E+005 Cs-137 1. 000 661. 66* 85. 10 1.32501E+004 9.80140E+003 Pb-212 1. 000 238.63* 43.60 1.92161E+004 2. 01049E+004 Bi-214 0. 705 609.32* 45.49 5.50933E+004 2.30863E+004 1120.29 14. 92 17 64.49* 15.30 1.28349E+005 6.00807E+004 Pb-214 1. 000 295.22* 18.42 6.35699E+004 4.63176E+004 351.93* 35.60 5.39394E+004 2.72847E+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

[413]

Interference Corrected Activity Report 6/7/2018 2: 12: 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 1.103356E+006 1.990341E+OOS Cs-137 1.000 1.325006E+004 9.801396E+003 Pb-212 1.000 1.921614E+004 2. 010493E+004 Bi-214 0. 705 6.451810E+004 2.155013E+004 Pb-214 1.000 5.64203SE+004 2.350897E+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 a t 2.000 sigma

[414]

Interference Corrected Activity Report 6/7/2018 2:12 :11 PM Page 5

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

Peak Locate Performed on : 6/7/20 18 2: 12: 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 75.34 9.0812E-002 105.72 2 204.64 8.8918E-003 376 .12 8 910.70 3.8333E-002 56.53 Sum M First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2. 000 sigma [415]

'Nuclide MDA Report 6/7/2018 2:12:11 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC051GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/MA2 ) (pCi/M"2 ) (pCi/MA2 ) (pCi/MA2 )

  +      K-40       1460 . 82*  10.66  l.866E+004     1.87E+004    1.103E+006   O.OOOE+OOO Co-60      1173.23     99.85  2.284E+004     1.97E+004    2.088E+004   1 .053E+004 1332.49     99.98  l.971E+004                  2.097E+004   8.908E+OD3 Nb-94       702.65     99.81  1.793E+004     l.66E+004    1. 410E+OD4  8.262E+003 871.09     99.89  1.662E+004                  2.398E+003   7.536E+003 Ag-108m     433.90     90.50  1.824E+004     1.82E+D04   -1.631E+004   8.506E+003 614.30     89.80  2.61DE+004                 -1.423E+OD4   l.232E+004 722.90     90.80  1.854E+D04                  4.552E+003   8.491E+003 Cs-134      604.72     97.62  2.552E+OD4     2. 0 4E+004 -7.074E+003   1.209E+004 795.86     85.46  2.038E+D04                  3.335E+003   9.320E+003
  +      Cs-137      661.66*    85. 10 1.458E+D04     1. 46E+004   1.325E+004   6.489E+003 Eu-152      121 .78    28.67  8.280E+004     6.39E+004    8.022E+002   4.024E+004 344.28     26.60  6.385E+OD4                 -3.17DE+004   3.006E+004 1408 .01    21.07  8.04DE+004                  6.839E+004   3.557E+004 Eu-154      123.07     40.40  5.942E+OD4     4.31E+004    3.077E+004   2.888E+004 723.30     20.06  8.396E+OD4                 -1. 537E+OD4  3.844E+004 1274.43     34.80  4.307E+OD4                  2.167E+004   1 .887E+D04 Eu-155       86.55     30.70  9.498E+004     9.SOE+004    8.080E+004   4.64DE+004 105.31     21.10  1.211E+OD5                 -4.750E+OD3   5.899E+004 Tl-208      583.19     85.00  2.512E+OD4     2.51E+004    1. 521E+004  1.181E+D04 Bi-212      727.33      6.67  2.532E+005     2.53E+005    1. 064E+O 05 1.159E+005
  +      Pb-212      238.63*    43.60  3.226E+OD4     3.23E+OD4    1. 922E+O 04 l.517E+004
  +      Bi-214      609.32*    45.49  2.914E+OD4     2.91E+004    5.509E+004   1. 313E+D04 1120.29     14. 92 1.554E+D05                  l.176E+OOS   7.184E+004 1764 .49*   15.30  5.958E+OD4                  1.283E+OOS   2.254E+D04
  +      Pb-214      295.22*    18.42  7.021E+004     3.7SE+004    6.357E+004   3.260E+004 351.93*    35.60  3.754E+D04                  5.394E+004   1.736E+D04 Ra-226      186.21      3.64  5.66DE+005     5.66E+005   -2.314E+004   2.728E+D05 Ac-228      338.32     11.27  1. 6D3E+005    7.62E+004   -1. 67SE+004  7.576E+004 911.20     25.80  7.619E+004                  6.487E+004   3.502E+004 968.97     15.80  l.408E+005                  1. 7 93E+OOS 6.524E+D04 Am-241       59.54     35.90  8.447E+OD4     8.45E+004    8.108E+003   4.112E+004
        +=Nuclide identified during the nuclide i dentification
        *=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

[416]

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

Filename: 5456-A Report Generated On 6/7/2018 10:36:46 AM Sample Title B103202AFSFC052GD Sample Description SFP/TRANSFER CANAL Sample Identification 052 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 2.830E+001 M... 2 Sample Taken On 6/7/2018 10: 26: 00 AM Acquisition Started 6/7/2018 10: 26:44 AM Live Time 600. 0 seconds Real Time 600.3 seconds Dead Time Energy Calibration Used Done On 3/15/2018 Efficiency Calibration used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [417]

Peak Analysis Report 6/7/2018 10:36 : 46 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC052GD Peak Analysis Performed on: 6/7/2018 10:36:45 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 30 1 .62 75.41 0.85 S.32E+001 51. 20 2.52E+002 2 947- 961 954.97 238.74 0.99 S.06E+001 25. 63 3.94E+001 3 1400- 1419 1407.68 351.92 1.48 8.83E+001 27 . 14 2.77E+001 4 2037- 2048 2042.30 510.58 0.51 l.79E+001 19.43 3.0lE+OOl 5 2328- 2339 2333.40 583.35 0.45 2.63E+001 16.58 1 .67E+001 6 2429- 2443 2436.74 609.18 0.85 5.36E+001 22.24 2.44E+001 7 2641- 2652 2646.20 661.55 0. 31 2.38E+001 14.88 1 .22E+001 8 3640- 3653 3646.49 911.62 0.80 2.17E+001 11. 64 4.33E+OOO 9 4474- 4487 4480.46 1120.11 0. 71 1.99E+001 14.60 l .21E+001 10 4687- 4700 4693.64 1173.41 0 .34 2.56E+001 12.78 5.39E+OOO 11 5322- 5335 5328.74 1332.19 0 .44 2.50E+001 13.31 7.00E+OOO 12 5834- 5855 5843.06 1460.77 1. 53 1. 41E+002 25 .41 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 [418]

Interference Corrected Activity Report 6/7/2018 10:36:46AM 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:

B103202AFSFC052GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * * * * * * * * * * * *

• I *
• I
• IDENTIFIED NUCLIDES * ~ I
• I * * * * * * *
• a * * * *
• 1 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10. 66 9.68927E+005 l .94368E+005 Co-60 1.000 11 7 3 .23* 99.85 1.69090E+004 B. 54703E+003 1332. 49* 99.98 1.74750E+004 9.40470E+003 Cs-137 1 .000 661.66* 85. 10 1.40680E+004 8.95167E+003 Tl-208 1 .000 583.19* 85. 00 1.46639E+004 9.40407E+003 Pb-212 1.000 238.63* 43.60 3.58035E+004 l.90188E+004 Bi-214 0.732 609.32* 45.49 5.69959E+004 2.46105E+004 1120.29* 14.92 8.58675E+004 6.34837E+004 1764.49 15.30 Pb-214 0.439 295.22 18.42 351.93* 35.60 9. 18214E+004 3.18196E+004

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

[419]

Interference Corrected Activity Report 6/7/2018 10 :36:46 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 9.689270E+005 1.943681E+005 Co-60 1.000 1.716503E+004 6.325194E+003 Cs-137 1.000 1.406802E+004 8.951672E+003 Tl-208 1.000 1.466388E+004 9.404070E+003 Pb-212 1.000 3.580352E+004 1. 901878E+004 Bi-214 0.732 6.076796E+004 2.294653E+004 Pb-214 0.439 9.182137E+004 3.181960E+004

       ? = Nuclide is part of an undetermined so lution X = Nuclide rejected by the interference analysis
      @ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at   2.000 sigma

[420]

Interference Correcte d Activity Report 6/7/2018 10:36:46 AM Page 5

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

Peak Locate Performed on: 6/7/2018 10:36:45 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 8.8672E-002 96.24 4 510.58 2.9757E-002 108.82 8 911.62 3.6122E-002 53.72 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 [421]

Nuclide MDA Report 6/7/2018 10:36:46 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC052GD 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.223E+005    l. 22E+005    9.689E+005  5.184E+004
 +      Co-60      1173.23*   99.85  1. 027E+004   l. 03E+004    l.691E+004  4.240E+003 1332.49*   99.98  1. 198E+004                 l.747E+004  5.046E+003 Nb-94       702.65    99.81  1. 844E+004   l.66E+004   - 8.185E+002  8.521E+003 871 .0 9  99.89  l. 662E+004                 l. 402E+004 7.536E+003 Ag-108m     433.90    90.50  l. 730E+004   l.73E+004   -3.597E+003   8.035E+003 614.30    89.80  2.771E+004                -4.276E+003   l.313E+004 722.90    90.80  2.111E+004                  l.536E+004  9.774E+003 Cs-134      604.72    97.62  2.596E+004    l.96E+004     3.347E+003  1 .231E+004 795.86    85.46  l.964E+004                -2.187E+003   8.954E+003
 +      Cs-137      661.66*   85.10  l.252E+004    l.25E+004     l.407E+004  S.459E+003 Eu-152      121 .78   28.67  8.170E+004    6. 4 5E+004   l .288E+004 3.968E+004 344.28    26.60  6.453E+004                -5.156E+004   3.040E+004 1408.0 1   21.07  8.040E+004                  4.620E+004  3.557E+004 Eu-154      123.07    40.40  5.727E+004    4.73E+004     3.774E+004  2.781E+004 723.30    20.06  9.558E+004                  4.067E+002  4.425E+004 1274.43    34.80  4.728E+004                -5.341E+003   2.098E+004 Eu-155       86.55    30.70  9.345E+004    9.34E+004     4.091E+004  4.563E+004 105.31    21.10  l.187E+005                -6.308E+003   5.779E+004
 +      Tl-208      583.19*   85.00  l.344E+004    l .34E+004    l.466E+004  S.968E+003 Bi-212      727.33     6.67  3.076E+OOS    3.08E+005     2.211E+OOS  l .432E+OOS
 +      Pb-212      238.63*   43.60  2.670E+004    2.67E+004     3.580E+004  l.239E+004
 +      Bi-214      609.32*   45.49  3.214E+004    3.21E+004    5.700E+004   l.463E+004 1120.29*   14.92  9.391E+004                 8.587E+004   4.111E+004 1764.49    15.30  1.342E+OOS                  l.233E+005  5.983E+004
 +      Pb-214      295.22    18.42  l.097E+005    3.63E+004     l.468E+005  5.236E+004 351.93*   35.60  3.631E+004                  9.182E+004  1. 675E+004 Ra-226      186.21     3.64  5.33SE+005    5.33E+005     l.851E+005  2.56SE+OOS Ac-228      338.32    11. 27 l.573E+OOS    8.37E+004   -5.577E+003   7.426E+004 911. 20   25.80  8.374E+004                -8.511E+003   3.880E+004 968.97    15.80  l.320E+005                 1.237E+005   6.086E+004 Am-241       59.54    35.90  7.780E+004    7.78E+004     4.477E+004  3.778E+004
       +=Nuclide identified during the nuclide i dentification
       *=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

[422]

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

Filename: 5456-A Report Generated On 6/7/2018 1:34:52 PM Sample Title B103202AFSFC053GD Sample Description SFP/TRANSFER CANAL sample Identification 053 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken on 6/7/2018 1:24:00 PM Acquisition Started 6/7/2018 1:24:50 PM Live Time 600 . 0 seconds Real Time 600.9 seconds Dead Time 0 . 15 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN Do.\" ~ o.\;c\.aAc:J G>.~ 7/9 It~ 3*.o.:i. [423]

Peak Analysis Report 6/7/2018 1:34:52 PM Page 2

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

Detector Name : 5456-A Sample

Title:

B1 03202AFSFC053GD Peak Analysis Performed on: 6/7/2018 1:34:51 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 1 288- 306 301. 11 75.28 1.20 1.88E+002 70.36 3.11E+002 2 951- 960 955.23 238.81 0. 73 3.84E+001 24.03 4.66E+001 3 1175- 1187 1181.34 295.34 1. 28 3.74E+001 22.83 3.46E+001 4 1402- 1416 1407.93 351.98 1. 28 6.09E+001 23.81 2.71E+001 5 2326- 2337 2331. 48 582.87 0.38 2.02E+001 16. 10 1. 78E+O 01 6 2428- 2444 2435.85 608.96 1. 64 6.33E+001 20 .33 l.28E+001 7 2638- 2651 2645.45 661.36 0.87 2.96E+001 15.29 1.04E+001 8 4685- 4698 469 1. 92 1172.98 1.42 2.75E+001 12.26 3.50E+OOO 9 5321- 5335 5328.57 1332 .14 1.22 3.0lE+OOl 12.96 3.87E+OOO 10 5831- 5853 5842.92 1460 .73 1. 00 l. 47E+002 24.25 O.OOE+OOO 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 [424]

Interference Corrected Activity Report 6/7/2018 1:34:52 PM Page 3

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

Sample

Title:

B103202AFSFC053GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB f ........ . . ........... IDENTIFIED NUCLIDES *

• t * * * * *
• I * * * * .t I Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10 .66 1. 01374E+006 l.88978E+005 Co-60 1.000 11 73.23* 99.85 1.81518E+004 8.22162E+003 1332.49* 99.98 2.10622E+004 9.21276E+003 Cs-137 1 .000 661.66* 85. 10 1.74723E+004 9.26742E+003 Tl-208 1 .000 583.19* 85. 00 l.12484E+004 9.07023E+003 Pb-212 1 .000 238.63* 4 3 .60 2.71563E+004 l.75510E+004 Bi-214 0.437 609.32* 45.49 6.71983E+004 2.30594E+004 1120.29 14.92 17 64.49 15.30 Pb-214 1.000 295.22* 18.42 6.92454E+004 4.36661E+004 351.93* 35.60 6.33873E+004 2. 67594E+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

[425]

Interference Correcte d Activity Report 6/7/2018 1 :34:52 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"' 2 ) Uncertainty K-40 1 . 000 1. 013 73 9E+006 1 .889783E+005 Co-60 1 . 000 l.944205E+004 6.134159E+C03 Cs-137 1 . 000 1. 74723SE+004 9.267421E+003 Tl-208 1 . 000 1.124837E+004 9 .070225E+003 Pb-212 1 . 000 2.715633E+004 l .755100E+004 Bi-214 0 .437 6.719831E+004 2.305937E+004 Pb-214 1 . 000 6.498664E+004 2.281593E+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

[426]

Interference Corrected Activity Report 6/7/2018 1 :34:52 PM Page 5

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

Peak Locate Performed on: 6/7/2018 1 :34:51 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 3.1359E-001 37.40 M ~ First peak in a multiplet region m = Other peak in a multiplet region F ; Fitted singlet Errors quoted at 2 .000 sigma [427]

Nuclide MDA Report 6/7/2018 1:34 : 52 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFCOS3GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

 +       K-40      1460.82*    10 .66  l.866E+004     1. 87E+004  1.014E+D06   O.OOOE+OOO
 +       Co-60     1173.23*    99.85   8.680E+003     8.68E+003   1.815E+004   3.447E+D03 1332.49*    99.98   9.806E+003                 2.106E+D04   3.957E+003 Nb-94       702.65    99. 81  l.66SE+004     1.66E+OD4  -2.347E+003   7.622E+D03 871.09    99.89   l. 861E+004                3.237E+003   8.53DE+003 Ag-108m      433.90    90.50  1. 850E+004     1.8SE+004   1 .790E+OD3  8.636E+003 614.30    89.80  2.723E+004                  l. 498E+OD3  1.288E+004 722.90    90.80  2.183E+004                  1.052E+OD4   1.014E+D04 Cs-134      604.72    97.62  2.552E+004      1.99E+004  -1.200E+004   1 .209E+004 795.86    85.46  1. 989E+004                -2.726E+003   9.078E+OD3
 +       Cs-137      661.66*   85. 10  l. 203E+004    1.20E+004   1.747E+OD4   5.216E+OD3 Eu-152      121.78    28.67   8.027E+004     6.39E+004  -7.1D4E+003   3.897E+D04 344.28    26.60  6.38SE+004                 -3.155E+OD4   3.006E+OD4 1408. 01    21. 07 6.661E+004                 -3.367E+D04   2.868E+OD4 Eu-154      123.07    40.40  S.683E+004      4.52E+004   5.322E+OD3   2.759E+004 723.30    20.06  9.805E+004                  3.383E+OD4   4 .549E+004 1274.43     34.80  4.523E+004                  2.26SE+D04   1.995E+004 Eu-155       86.55    30.70  9.213E+004      9.21E+004   5.632E+D04   4.497E+004 105.31    21.10  1.120E+005                  1.059E+D04   5.443E+004
 +       Tl-208      583.19*   85.00  1.375E+004      1 .37E+OD4  1.12SE+004   6.121E+003 Bi-212      727.33     6.67  2.805E+005      2.81E+005  -8.387E+D04   1. 296E+O OS
 +       Pb-212      238.63*   43.60  2.586E+004      2.59E+OD4   2.716E+004   1.197E+004
 +       Bi-214      609.32*   45.49  2.SOOE+004      2.SOE+OD4   6.720E+004   1.106E+004 1120.29     14.92  1.636E+005                  2.184E+005   7.595E+OD4 1764.49     15.30  1.465E+005                  1.088E+OD5   6.601E+004
 +       Pb-214      295.22*   18.42  6.366E+004      3.36E+004   6.925E+004   2.933E+OD4 351.93*   35.60  3.356E+OD4                  6.339E+004   1. 537E+OD4 Ra-226      186.21     3.64  S.418E+005      S.42E+005   7.389E+OOS   2.607E+OOS Ac-228       338.32    11. 27 1.557E+005      8. 08E+004  6.419E+004   7.35DE+004 911. 2 0  25.80   8.081E+004                 4.855E+004   3.734E+004 968.97    15.80  1. 4 08E+O 05               8.989E+004   6.524E+004 Am-241        59.54    35.90   8.2DOE+004     8.20E+OD4   3.278E+004   3.988E+OD4
       + = Nuclide identified during the nuclide i dentification
       *=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

[428]

• • • • • GAMMA S P E C T R U M ANALYSIS *****

Filename: 5456-A Report Generated On 6/6/2018 10:30:21 AM Sample Title B103202AFSFCOS4GD Sample Description SFP/TRANSFER CANAL Sample Identification 054 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/6/2018 10:20:00 AM Acquisition Started 6/6/2018 10:20:20 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 06 % Energy Calibration Used Done On 3/lS/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [429]

Peak Analysis Report 6/6/2018 10 ~30:21 AM Page 2

• • • • • P E A K A N A L Y S I S RE PORT *****

Detector Name: 5456-A Sample

Title:

B1 03202AFSFC054GD Peak Analysis Performed on: 6/6/2018 10:30:21 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 1 287- 311 301.09 75.27 0 .76 1 .95E+002 83. 17 3.72E+002 2 402- 412 407.13 101 .78 0 .39 -3.lOE+OOO 33. 92 1. 22E+002 3 950- 974 956.08 239.02 0.38 5.19E+001 43.64 1.01E+002 4 1177- 1188 1181.72 295.43 0.75 4.28E+001 19.91 2.22E+001 5 1401- 1414 1408.21 352.05 0.54 4.83E+001 21. 05 2.27E+001 6 2427- 2444 2436.80 609.20 0.47 7.04E+001 22.02 1 .56E+001 7 2640- 2652 2646.68 661.67 0 .41 2.87E+001 14 . 35 8.28E+OOO 8 4685- 4698 4691.62 1172.91 0 .75 2.58E+001 12.66 5.19E+OOO 9 5323- 5337 5329.54 1332.38 0 .55 3.45E+001 13.36 3.51E+OOO 10 5832- 5854 5843.35 1460.84 1. 49 1. 32E+002 22.98 O.OOE+OOO 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]

Interference Corrected Activity Report 6/6/2018 10: 30:21 AM Page 3

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

Sample

Title:

B103202AFSFCOS4GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

  * * * *

• e * *
• II *
• e e II *
• II
• e IDENTIFIED NUCLIDES . .. .. ........... . ....

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10 .66 9.10335E+005 1 .77091E+005 Co-60 1.000 1173.23* 99.85 1. 70387E+004 8.46931E+003 1332.49* 99.98 2.41079E+004 9.53832E+003 Cs-137 1. 000 661.66* 85.10 l.69656E+004 8.71857E+003 Pb-212 1.000 238.63* 43.60 3.67169E+004 3 .14331E+004 Bi-214 0.438 609.32* 45 .49 7.48251E+004 2. 50730E+004 1120.29 14. 92 1764.49 15.30 Pb-214 1. 000 295.22* 18.42 7.91628E+004 3. 89672E+004 351.93* 35.60 5.02303E+004 2.33226E+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 a t                    2. 000 sigma

[431]

Interference Corrected Activity Report 6/6/2018 10 :30:21 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1. 000 9.103349E+005 1.770912E+005 Co-60 1. 000 2.015515E+004 6.333075E+003 Cs-137 1. 000 1.696556E+004 8.718572E+003 Pb-212 1. 000 3.671692E+004 3.143310E+004 Bi-214 0 .438 7.482509E+004 2.507297E+004 Pb-214 1.000 S.786107E+004 2.001201E+004

      ? =  Nuclide is part of an undeterm.ined solution X ~  Nuclide rejected by the interference analysis
      @=Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at   2.000 sigma

[432]

Interference Corrected Activity Report 6/6/2018 10:30:21 AM Page 5

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

Peak Locate Performed on: 6/6/2018 10 :30:21 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 Nuclide 1 75.27 3.2530E-001 42.61 2 101.78 -5.1716E-003 - 1093. 1 M ~ First peak in a multiplet region m ~ Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2. 000 sigma [433]

Nuclide MDA Report 6/6/2018 10:30:22 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

Bl03202AFSFC054GD 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 .866E+004   1.87E+004   9.103E+OD5   O.OOO E+OOO
 +      Co-60      1173.23*  99.85  9.992E+003    9.22E+003   1.704E+004   4.103E+003 1332.49*  99.98  9.221E+003                2.411E+004   3.664E+003 Nb-94       702.65   99.81  1. 683E+004   1. 68E+004 -5.701E+003   7.716E+003 871. 09  99.89  1. 797E+004               5.410E+003   8.212E+003 Ag-108m     433.90   90.50  1.938E+004    l.94E+004   l.477E+004   9.076E+003 614.30   89.80  2.79SE+004               -1.689E+004   l .325E+004 722.90   90.80  1.937E+004                1. 083E+004  8.905E+003 Cs-134      604.72   97.62  2.596E+004    1.84E+004   1. 076E+003  1.231E+004 795.86   85.46  1. 835E+004              -1.931E+004   8.309E+003
 +      Cs-137      661.66*  85. 10 1. 087E+OD4   1 .09E+004  1.697E+004   4.637E+003 Eu-152      121. 78  28.67  7.881E+OD4    7.13E+004   4 . 011E+OD4 3.824E+004 344.28   26.60  7.12SE+004                6.622E+004   3.376E+004 1408 .01  21. 07 7.485E+004                5.813E+004   3.280E+004 Eu-154      123.07   40. 40 5.435E+004    5.2DE+004   l .840E+004  2.635E+004 723.30   20.06  8.771E+004                4.573E+004   4.032E+004 1274.43   34.80  5.201E+004                2.115E+004   2.334E+004 Eu-155       86.55   30.70  9.110E+004    9.11E+004   7.401E+003   4 .446E+004 105.31   21. 10 l .142E+005               3.729E+004   5.550E+004 Tl-208      583.19   85. 00 2.395E+004    2.40E+OD4   9.452E+003   l .122E+004 Bi-212      727.33    6.67  2.726E+005    2.73E+005   1 .077E+005  1 .257E+005
 +      Pb-212      238.63*  43.60  4.984E+004    4.98E+OD4   3.672E+004   2.396E+004
 +      Bi-214      609.32*  45.49  2.781E+004    2.78E+OD4   7.483E+004   l.247E+004 1120.29   14 .92 1. 739E+005               1.316E+OD5   8.110E+004 1764.49   15.30  1.465E+005                1.008E+OD5   6.601E+004
 +      Pb-214      295.22*  18.42  5.071E+004    2.99E+004   7.916E+004   2.285E+004 351.93*  35.60  2.986E+004                5.023E+004   1.352E+004 Ra-226      186.21    3.64  5.139E+005    5.14E+005   4.134E+005   2.468E+005 Ac-228      338.32   11. 27 1.703E+005    9.32E+004   2.872E+004   8.080E+004 911.20   25.80  9.322E+004                8.918E+004   4.354E+004 968.97   15.80  1 .371E+005               5.90SE+004   6.340E+004 Am-241       59.54   35.90  8.002E+004    8.00E+OD4   3.376E+004   3.889E+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

[434]

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

Filename: 5456-A Report Generated On 6/6/2018 10 :43:54 AM Sample Title B103202AFSFC055GD Sample Description SFP/TRANSFER CANAL Sample Identification 055 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"'2 Sample Taken On 6/6/2018 10:33: 00 AM Acquisition Started 6/6/2018 10:33:53 AM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time OJ06 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M9 ODSFP 2 IN [435]

Peak Analysis Report 6/6/2018 10 :43:54 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC055GD Peak Analysis Performed on: 6/6/2018 10 :43:53 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 cent roid (keV) (keV) Area Uncert. Counts 1 128- 144 138 .40 34.60 1. 67 l .56E+002 32.20 3.29E+001 2 297- 307 302.09 75.52 0.69 8.31E+001 52.35 2.48E+002 3 1398- 1417 1408.32 352. 08 0.43 8.34E+001 24.13 1.76E+001 4 2037- 2048 2042.95 510 .74 0 .32 7.00E+OOO 18.92 3.30E+001 5 2429- 2446 2437.86 609.47 0.62 6.28E+001 21.25 1.52E+001 6 2640- 2651 2645.26 661.31 0.40 2.36E+001 16.14 l.44E+001 7 4686- 4699 4692.57 1173.14 1. 21 2.31E+001 13.02 6.90E+OOO 8 5833- 5854 5843.99 1461. 00 1. 24 1.48E+002 25.93 S.50E+OOO 9 7052- 7067 7059.47 1764.87 1. 38 2.90E+001 10.77 O.OOE+OOO 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 [436]

Interference Corrected Activity Report 6/6/2018 10:43:54 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:

Bl03202AFSFC055GD 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 1.01729E+006 l .99487E+OOS Cs-137 1.000 661.66* 85.10 1.39236E+004 9.67662E+003 Bi-214 0.705 609.32* 45.49 6.67919E+004 2.39666E+004 1120.29 14.92 1764.49* 15.30 l .55529E+OOS 5.90900E+004 Pb-214 0.439 295.22 18.42 351.93* 35.60 8.67319E+004 2.86828E+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

[437]

Interference Corrected Activity Report 6/6/2018 10:43:54 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 1. 017295E+006 1.994873E+005 Cs-137 1.00 0 1. 392364E+004 9.676617E+003 Bi-214 0.705 7.932758E+004 2.220935E+004 Pb-214 0.439 8.673192E+004 2.868276E+004

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

Peak Locate Performed on: 6/6/2018 10 :43:53 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 34.60 2.6013E-001 20.63 2 75.52 1. 3844E-001 63.03 4 510.74 1.1667E-002 270.31 7 1173.14 3.8500E-002 56.38 Tol. Co-60 M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [438]

Nuclide MDA Report 6/6/2018 10:43:54 AM Page 5

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC055GD 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   1.217E+005     l .22E+005    1.017E+006   5.154E+004 Co-60      1173.23     99.85   2.456E+004     2.44E+004     9.983E+003   1.139E+004 1332.49     99.98   2.443E+004                   2.289E+004   1 .127E+004 Nb-94        702 . 65  99.81   1 .757E+004    1.76E+004     1. 6 71E+004 8.084E+003 871 . 09  99.89   l .776E+004                -9.185E+003    8.103E+003 Ag- 108m     433.90    90.50   l . 744E+004   1. 74E+004  -2.167E+004    8.104E+003 614.30    89.80   2. 771E+004                  4.606E+003   1.313E+004 722.90    90.80   1 .997E+004                  l. 063E+004  9.204E+003 Cs-134       604.72    97.62   2.606E+004     2.20E+004     5.921E+003   1 .236E+004 795.86    85.46   2.198E+004                   1.123E+004   l .012E+004
 +      Cs-137       661.66*   85. 10  1.412E+004     1.41E+004     1.392E+004   6.261E+003 Eu-152       121 . 78  28.67   7.625E+004     6.62E+004   -8.218E+004    3.696E+004 344.28    26.60   6.620E+004                 -5.767E+004    3.124E+004 1408.01     21.07   8.216E+004                   4.494E+004   3.645E+004 Eu-154       123 .0 7  40.40   5.511E+004     5.20E+004     1.860E+004   2.673E+004 723.30    20.06   8.952E+004                   4 .516E+003  4.123E+004 1274.43     34.80   5.201E+004                   2.115E+004   2.334E+004 Eu-155        86. 5 5  30.70   9.158E+004     9. 1 6E+004   4.186E+004   4.470E+004 105.31    21.10   1.198E+OOS                 -5.114E+004    5.830E+004 Tl-208       583.19    85.00   2.335E+004     2.33E+004     1.157E+004   1. 092E+O 04 Bi-212       727.33     6.67   2.753E+005     2.75E+005     1.658E+005   1.270E+005 Pb-212       238. 6 3  43.60   4 .831E+004    4.83E+004     3.964E+004   2.320E+004
 +      Bi-214       609.32*   45.49   2.760E+004     1. 4 5E+004   6.679E+004   1 .236E+004 1120.29     14 .92  1.452E+005                   5.906E+004   6.673E+004 1764.49*    15 . 30 1 .451E+004                  1. SSSE+OOS  O.OOOE+OOO
 +      Pb-214       295.22    18.42   1 .046E+OOS    2.98E+004     4.088E+004   4.982E+004 351.93*   35.60   2.980E+004                   8.673E+004   l.349E+004 Ra-226       186.21     3.64   5.442E+005     5.44E+OOS   -5.114E+OOS    2.619E+005 Ac-228       338.32    11.27   1 .603E+005    9.64E+004   -3.683E+004    7.576E+004 911. 20   25.80   9.637E+004                   8.375E+004   4.511E+004 968.97    15.80   l .444E+005                  5.972E+004   6.702E+004 Am-241        59. 54   35.90   7.790E+004     7.79E+004   -7.212E+003    3.783E+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

[439]

• • • • • GAMMA S P E C T R U M ANALYSIS *****

Filename: 5456-A Report Generated On 6/7/2018 3:18 : 14 PM Sample Title B103202AFSFC056GD Sample Description SFP/TRANSFER CANAL Sample Identification 056 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/7/2018 3:06:00 PM Acquisition Started 6/7/2018 3:08:13 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 5/30/2018 Efficiency ID 3M90DSFP 2IN [440]

Peak Analysis Report 6/7/2018 3:18: 14 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC056GD Peak Analysis Performed on: 6/7/2018 3:18:14 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 306 3 01. 21 75.30 1. 27 7.81E+001 53.55 2.68E+002 2 946- 974 954.89 238.72 1. 26 9.67E+001 44.43 8.43E+001 3 1174- 1187 1180.10 295.02 0.66 1.88E+001 24.38 4.72E+001 4 1400- 1415 1407.05 351.76 0.96 7.41E+001 25. 35 2.89E+001 5 2431- 2444 2436.82 609.20 1. 07 4.47E+001 20.36 2.13E+001 6 5323- 5336 5329.10 1332.27 0.73 3.34E+001 12.28 1.61E+OOO 7 5832- 5854 5842.55 1460.64 1. 28 1 .79E+002 28.40 5.75E+OOO 8 7049- 7064 7056. 12 1764.03 0.43 1 .71E+001 12.88 7.94E+OOO M "' First peak 1.n a mult iplet region m "' Other peak in a mult iplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [441]

Interference Corrected Activity Report 6/7/2018 3: 18 : 14 PM Page 3

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

Sample Ti t le: B103202AFSFCOS6GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB r * * * * * * * *

• I * *
• t I * * !I
• IDENTIFIED NUCLIDES * * * * * * * * !I
• I' I * * ' I Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"'2 ) Uncertainty K-40 1.000 1460.82* 10 .66 1.23610E+006 2.23336E+005 Pb-212 1.000 238.63* 43.60 6.83340E+004 3.32949E+004 Bi-214 0.705 609.32* 45.49 4.75081E+004 2.23714E+004 1120.29 14.92 1764.49* 15.30 9.14691E+004 6.94366E+004 Pb-214 1. 000 295.22* 18.42 3.47602E+004 4.54368E+004 351.93* 35.60 7.70655E+004 2.90988E+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

[442]

Interference Corrected Activity Report 6/7/2018 3: 18: 14 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1.236096E+006 2.233359E+005 Pb-212 1. 000 6.833399E+004 3. 329485E+004 Bi-214 0.705 S.164225E+004 2 .129351E+004 Pb-214 1. 000 6.476090E+004 2.450439E+004

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

Peak Locate Performed on: 6/7/2018 3: 18: 14 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.30 1. 3020E-001 68.54 6 1332.27 5.5643E-002 36.79 M = First peak in a multiplet region m ~ Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [443]

Nuclide MDA Report 6/7/2018 3:18: 14 PM Page 5

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC056GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

 +      K-40       1460.82*   10.66  1.260E+OOS    1.26E+005 1.236E+006      5.369E+004 Co-60      1173.23    99.85  2.329E+004    2.33E+004 -1.335E+004     1.07SE+004 1332.49    99.98  2.512E+004                 l.410E+004   l.161E+004 Nb-94       702. 6 5  99.81  l.757E+004    1.66E+004 -2.397E+003     8.084E+003 871. 09   99.89  l .662E+004               -1. 4 54E+003 7.536E+003 Ag-108m     433.90    90.50  2.022E+004    2.02E+004    1.810E+004   9.496E+003 614.30    89.80  2.648E+004                -9.075E+003   1. 251E+O 04 722.90    90.80  2.036E+004                -6.448E+003   9.398E+003 Cs-134      604.72    97.62  2.638E+004    2. 04E+004 -l.433E+004    1.252E+004 795.86    85.46  2.038E+004                -l.356E+004   9.320E+003 Cs-137      661.66    85.10  2.648E+004    2.65E+004    1. 489E+004  1 .244E+004 Eu-152      121. 78   28.67  8.037E+004    6.45E+004    l. 696E+004  3.902E+004 344.28    26.60  6.453E+004                -1.338E+OOS   3.040E+004 1408.01    21 .07 7.860E+004                 4.522E+004   3.467E+004 Eu-154      123.07    40 .40 5.579E+004    4.73E+004 1.705E+004      2.707E+004 723.30    20.06  9.474E+004                -4.392E+004   4 .383E+004 1274.43    34.80  4.728E+004                -4.837E+004   2.098E+004 Eu-155       86.55    30.70  9.656E+004    9.66E+004    l .012E+005  4.719E+004 105. 31   21.10  1. 201E+OOS               -2.342E+004   5.849E+004 Tl-208      583.19    85.00  2.395E+004    2.40E+004 -4.215E+002     1 .122E+004 Bi-212      727.33     6.67  3.169E+005    3. 1 7E+005 2.085E+OOS    1.478E+005
 +      Pb-212      238.63*   43.60  4.825E+004    4.82E+004    6.833E+004   2.317E+004
 +      Bi-214      609.32*   45.49  2.970E+004    2.97E+004 4 .751E+004     1.341E+004 1120.29    14.92  1.525E+OOS                 8.000E+004   7.042E+004 1764.49*   15.30  1.016E+OOS                 9.147E+004   4 .357E+004
 +      Pb-214      295.22*   18.42  7.434E+004    3.46E+004 3.476E+004      3.467E+004 351.93*   35.60  3.463E+004                 7.707E+004   l.591E+004 Ra-226      186.21     3.64  5.827E+005    5.83E+005 1 .966E+OOS     2.BllE+OOS Ac-228      338.32    11.27  1.67SE+OOS    7.78E+004 5.29BE+004      7.939E+004 911. 20   25.80  7.776E+004                 8.799E+004   3.581E+004 968.97    15.80  1.444E+005                 1.323E+005   6.702E+004 Am-241       59.54    35.90  8.116E+004    8.12E+004 -4.434E+002     3.946E+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

[444]

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • ~ ******************
        • GAMMA S P E C T R U M ANALYSIS *****

Filename : 5456-A Report Generated On 6/7/2018 3:35:56 PM Sample Title B103202AFSFC057GD Sample Description SFP/TRANSFER CANAL sample Identification 057 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 6/7/2018 3:25: 00 PM Acquisition Started 6/7/2018 3:25:54 PM Live Time 600 , 0 seconds Real Time 600.5 seconds Dead Time 0 , 08 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 2M90DSFP 2IN [445]

Peak Analysis Report 6/7/2018 3:35:56 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC057GD Peak Analysis Performed on: 6/7/2018 3:35:55 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 1 248- 258 253.40 63.35 0.98 3.lOE+OOl 36.66 1.28E+002 2 296- 306 300.66 75.17 0.58 4.02E+001 51. 36 2.58E+002 3 345- 355 349.74 87.43 0.25 -1 .66E+OOO 41. 40 1 .80E+002 4 948- 959 954 . 73 238.68 1. 37 4.23E+001 26. 05 5.07E+001 5 1176- 1186 1180 .75 295.19 0.75 4.34E+001 20. 71 2.66E+001 6 1401- 1416 1408.28 352.07 1.20 7.25E+001 24.91 2.75E+001 7 1865- 1876 1870.33 467.58 0.65 9.56E+OOO 13.60 1 .44E+001 8 2325- 2340 233 1 .73 582.93 0.37 4.13E+001 18.79 1 .57E+001 9 2428- 2444 2435.79 608.95 0.86 7.45E+001 20.70 1 .0SE+OOl 10 5321- 5334 5327.39 1331. 85 0.79 2.40E+001 9.80 O.OOE+OOO 11 5831- 5853 5842.00 1460.50 1.71 1.41E+002 26.50 8.75E+OOO 12 7049- 7064 7056.99 1764.25 1.11 3.49E+001 12.88 2.09E+OOO M m

 =

First peak in a mu ltiplet region Other peak in a mu ltiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [446]

Interference Corrected Activity Report 6/7/2018 3: 35: 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 REPORT *****

Sample

Title:

B103202AFSFCOS7GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib- BNL. NLB I ****** I !I * * * * * * * * **'"' IDENTIFIED NUCLIDES !ill

• I I .., * * * * * *'" * * * * * *,
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"'2 ) Uncertainty K-40 1.000 1460.82* 10.66 9.65125E+005 l .99539E+005 Eu-155 0.348 86.55* 30. 70 -1.29486E+003 3. 22949E+004 1 05.31 21. 10 Tl-208 1.000 583.19* 85. 00 2.27043E+004 l.06725E+004 Pb-212 1.000 238.63* 43.60 2.93210E+004 l.86822E+004 Bi-214 0.705 609.32* 45.49 7.80914E+004 2.36307E+004 1120.29 14. 92 1764.49* 15. 30 1.85856E+005 7.01623E+004 Pb-214 1 . 000 295.22* 18. 42 7.87400E+004 3.96693E+004 351.93* 35.60 7.40598E+004 2.80745E+004 Am-241 0.977 59.54* 35.90 2.37241E+004 2.84333E+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

[447]

Interference Corrected Activity Report 6/7/20 18 3: 35: 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/MA2 ) Uncertainty K-40 1.000 9.651251E+005 1.995389E+005 Eu-155 0 .348 -1.294861E+003 3.229487E+004 Tl-208 1.000 2.270431E+004 l.067248E+004 Pb-212 1.000 2.932099E+004 1.868222E+004 Bi-214 0 .705 8.907033E+004 2.239469E+004 Pb-214 1.000 7.562166E+004 2.291617E+004 Am-241 0 .977 2.372406E+004 2.843331E+004

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

Peak Locate Performed on: 6/7/2018 3:35:55 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 2 75.17 6.6998E-002 127.76 7 467.58 l .5937E-002 142.17 Sum 10 1331.85 4.000DE-002 40.82 Tol. Co-60 M = First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted a t 2 . 000 sigma [448]

Nuclide MDA Report 6/7/2018 3:35:56 PM Page 5

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC057GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/M2 ) (pCi/MA2 } (pCi/MA2 ) (pCi/M"2 )

 +       K-40       1460.82*    10. 66 1.502E+005     1 .50E+005  9.651E+005  6.588E+004 Co-60      1173.23     99.85  2.121E+004     1 .9BE+004  1.681E+D04  9.723E+003 1332.49     99.98  1.982E+004                 6.414E+OD3  8.973E+003 Nb-94       702.65     99.81  1.418E+004     l.42E+004  -1.686E+D03  6.397E+003 871.09     99.89  1.610E+004                -7.643E+D03  7.29DE+003 Ag-lOBm     433.90     90.50  1.930E+004     l.93E+004  -2.553E+002  9.047E+003 614.30     89.80  2.709E+004                -5.311E+D03  1.283E+004 722.90     90.80  2.169E+004                 1. 34SE+004 1.007E+004 cs-134      604.72     97.62  2.570E+004     2.07E+004  -1.046E+004  1.219E+004 795.86     85.46  2.074E+004                -3.720E+003  9.517E+003 Cs-137      661. 66    85.10  2.426E+004     2.43E+D04   9.606E+003  1.134E+004 Eu-152      121.78     28.67  7.532E+004     6.37E+004  -4.0BOE+004  3.652E+004 344.28     26.60  6.371E+004                -6.624E+004  3.002E+004 1408.01     21. 07 6.815E+004                -5.929E+003  2.949E+004 Eu-154      123.07     40. 40 5.360E+004     5.06E+004  -2.540E+004  2.599E+004 723.30     20.06  9.819E+004                 9.573E+004  4.561E+004 1274.43     34.80  S.060E+004                 3.480E+004  2.266E+004
 +       Eu-155       86.55*    30.70  S.534E+D04     5.53E+004  -1.29SE+003  2.661E+004 105.31     21. 10 1.167E+OOS                 1 .997E+003 5.682E+004
 +       Tl-208      583.19*    BS. OD 1.386E+004     l .39E+004  2.270E+004  6.186E+003 Bi-212      727.33      6.67  3.054E+005     3.0SE+OOS  -3.BOOE+004  1 .422E+005
 +       Pb-212      238 . 63*  43.60  2.764E+004     2.76E+004   2.932E+004  1 .288E+004
 +       Bi-214      609.32*    45.49  2.251E+D04     2.25E+004   7.809E+004  9.836E+003 1120.29     14.92  1.448E+005                 1 .103E+OOS 6.662 E+004 1764.49*    15.30  5.926E+004                 1.859E+005  2.243 E+004
 +       Pb-214      295.22*    18.42  5.267E+004     3.33E+004   7.874E+D04  2.388 E+004 351.93*    35.60  3.332E+OD4                 7.406E+004  1 .528 E+004 Ra-226      186.21      3.64  5.308E+D05     5.31E+005   3.573E+OOS  2.55S E+005 Ac-228      338.32     11. 27 1. 484E+OOS    8.23E+004  -3.872E+004  6.989 E+004 911. 2 0   25.80  8.230E+004                 5.285E+004  3.813 E+004 968.97     15.80  l. 361E+D05                l.417E+OOS  6.29S E+004
 +       Am-241       59 .5 4*  35.90  4.60DE+004     4.60E+004   2.372E+004  2.196 E+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

[449]

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

Filename: 5456-A Report Generated On 6/6/2018 2: 18: 36 PM Sample Title B103202AFSFC058GD Sample Description SFP/TRANSFER CANAL Sample Identification 058 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/6/2018 2: 10 : 00 PM Acquisition Started 6/6/2018 2: 08: 34 PM Live Time 600. 0 seconds Real Time 600.9 seconds Dead Time 0. 15 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [450]

Peak Analysis Report 6/6/2018 2: 1 8:36 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC058GD Peak Analysis Performed on: 6/6/2018 2:18:36 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 134 130.37 32.59 0.89 3.63E+001 23.70 3.97E+001 2 288- 306 3 01. 02 75.26 0 .98 l.43E+002 72.55 3.46E+002 3 333- 350 340.26 85.06 0.66 7.55E+001 62.08 2.73E+002 4 948- 962 956.37 239.09 0 .57 5.16E+001 28. 86 5. 44E+001 5 1402- 1415 1407.99 352. 00 1 .10 5.84E+001 22.70 2.56E+001 6 2037- 2050 2042.52 510.63 0.31 4.02E+001 20. 05 2.18E+001 7 2326- 2337 2331.84 582.96 0.40 2.00E+OOl 16.13 1. 80E+001 8 2425- 2443 2436.11 609.03 0.57 8.88E+001 21.28 7.18E+OOO 9 2637- 2651 2645 . 13 661 .28 0.57 4.17E+001 17.38 l.13E+001 10 3635- 3648 364 1 .56 910 .39 0.93 3.47E+001 14 .06 5.29E+OOO 11 5830- 5852 5841.86 1460.47 0.39 1.50E+002 24.49 O.OOE+OOO M ; First peak in a mu ltiplet region m = Other peak in a mu ltiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [451]

Interference Corrected Activity Report 6/6/2018 2: 18: 36 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:

B103202AFSFC058GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB 4 * * * * * * * * * * * * * * * + I I

• IDENTIFIED NUCLIDES ********* i * * * * **

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) {pCi/MA2 ) Uncertainty K-40 1. 000 14 60.82* 10. 66 1.03432E+006 l .91300E+005 Cs-137 1.000 661.66* 85. 10 2.46254E+004 1. .06786E+004 Eu-155 0.345 86.55* 30. 70 6.13428E+004 5.19329E+004 105. 31 21. 10 Tl-208 1 .000 583.19* 85. 00 l .11393E+004 9.08103E+003 Pb-212 1. 000 238.63* 43.60 3.64857E+004 2.12554E+004 Bi-214 0.437 609.32* 45.49 9.43696E+004 2.52996E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.439 295.22 18 .42 351.93* 35.60 6.07825E+004 2.55338E+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

[452]

Interference Corrected Activity Report 6/6/2018 2: 18: 36 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 1.034323E+006 1. 912999E+005 Cs-137 1 .000 2.462541E+004 1. 067864E+004 Eu-155 0.345 6.134282E+004 5.193295E+004 Tl-208 1. 000 1.113929E+004 9.081030E+003 Pb-212 1. 000 3.648571E+004 2.125540E+004 Bi-214 0 .437 9.436962E+004 2.529955E+004 Pb-214 0.439 6.078245E+004 2.553385E+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

[453]

Interference Corrected Activity Report 6/6/2018 2: 18: 36 PM Page 5

  *********

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

Peak Locate Performed on: 6/6/2018 2: 18 : 36 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.59 6.0581E-002 65.19 2 75.26 2.3891E-001 50.61 6 510.63 6.7009E-002 49.86 10 910.39 5.7854E-002 40.50 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 [454]

Nuclide MDA Report 6/6/2018 2:18:36 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC058GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec . Level Name (keV) (%) (pCi/M ... 2 ) (pCi/M ... 2 ) (pCi/M ... 2 ) (pCi/MA2 ) K-40 1460.82* 10.66 1.866E+004 1 .87E+004 1.034E+006 O.OOOE+OOO Co-60 1173.23 99.85 2.284E+004 1 .91E+004 2.159E+004 1.053E+004 1332.49 99.98 1.910E+004 1.957E+004 8.606E+003 Nb-94 702.65 99.81 1. 827E+O 04 1 .69E+004 -9.879E+003 8.436E+003 871.09 99.89 1. 685E+004 6.290E+002 7.653E+003 Ag-108m 433.90 90.50 1. 798E+004 1.80E+004 -8.487E+003 8.374E+003 614. 3 0 89.80 2.807E+004 7.506E+002 1.331E+004 722.90 90.80 2.036E+004 8.727E+003 9.398E+003 Cs-134 604.72 97.62 2.751E+004 2.20E+004 -2.148E+003 1.309E+004 795.86 85.46 2.198E+004 1. 075E+004 1 .012E+004

 +       Cs-137      661.66*   85.10  1.289E+004       1.29E+004      2.463E+004      5.646E+003 Eu-152      121.78    28.67  8.037E+004       6.88E+004     -1.976E+004      3.902E+004 344.28    26.60  6.878E+004                     -3.384E+004      3.252E+004 1408.01     21. 07 7.675E+004                      3.111E+004      3.375E+004 Eu-154      123.07    40.40  5.691E+004       5.29E+004     -1 .756E+003     2.762E+004 723.30    20.06  9.130E+004                      2.463E+003      4.211E+004 1274.43     34.80  5.290E+004                      2.296E+004      2.379E+004
 +       Eu-155       86.55*   30.70  8.189E+004       8.19E+004      6.134E+004      3.985E+004 105.31    21.10  1.189E+005                     -5.925E+004      5.785E+004
 +       Tl-208      583.19*   85.00  1. 380E+004      1.38E+004      1.114E+004      6.147E+003 Bi-212      727.33     6.67  2.907E+005       2.91E+005      2.182E+005      1 .347E+005
 +       Pb-212      238.63*   43.60  3.105E+004       3.11E+004      3.649E+004      1.457E+004
 +       Bi-214      609.32*   45.49  2.015E+004       2.02E+004      9.437E+004      8.639E+003 1120.29     14.92  1. 467E+005                     3.315E+004      6.748E+004 1764.49     15.30  l. 442E+005                     1. 448E+005     6.482E+004
 +       Pb-214      295.22    18.42  1 .125E+005      3.15E+004      7.058E+004      5.375E+004 351.93*   35.60  3.152E+004                      6.078E+004      1.435E+004 Ra-226      186.21     3.64  5.750E+005       5.75E+005      2.524E+005      2.773E+005 Ac-228      338.32    11. 27 1 .724E+005      9.19E+004      2.380E+005      8.183E+004 911.20    25.80  9.193E+004                      4.930E+004      4.290E+004 968.97    15.80  1 .444E+005                     1. 088E+005     6.702E+004 Am-241       59.54    35.90  8.456E+004       8.46E+004      2.390E+004      4.116E+004
       + ~ Nuclide identified during the nuclide i dentification

• 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

[455]

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

Filename: 5456-A Report Generated On 6/6/2018 10: 17 :38 AM Sample Title B103202AFSFC059GD Sample Description SFP/TRANSFER CANAL Sample Identification 059 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/6/2018 10:06:00 AM Acquisition Started 6/6/2018 10 :07:36 AM Live Time 600. 0 seconds Real Time 600.4 seconds Dead Time 0 .07 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [456]

Peak Analysis Report 6/6/2018 10 :17:38 AM Page 2

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

Detector Name: 54 56-A Sample

Title:

B103202AFSFC059GD Peak Analysis Performed on: 6/6/2018 10:17:37 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 285- 307 301.25 75. 31 0.95 2. 01E+ 002 77.97 3.39E+002 2 948- 962 955.61 238.90 0.80 2.65E+001 29.70 6.75E+001 3 1402- 1414 1407.89 351.97 0 .45 3.94E+001 22.44 3.16E+001 4 2431- 2444 2437.38 609.35 1 .13 6.30E+001 21.72 2.00E+OOl 5 4474- 4487 4480.44 1120. 11 0.50 2.40E+001 9.80 O.OOE+OOO 6 5325- 5338 533 1 .20 1332.80 0.34 1.71E+001 11 .06 4.91E+OOO 7 5833- 5854 5843.86 1460.96 1. 76 1.43E+002 25 .54 5.SOE+OOO M == First peak in a mu ltiplet region m Other peak in a mu ltiplet region F == Fitted singlet Errors quoted at 2 . 000 sigma [457]

Interference Corrected Activity Report 6/6/2018 10:17:38 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:

B103202AFSFC059GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

  * ,.. * * * *

• I "' * * "' * * * * * * *
• IDENTIFIED NUCLIDES .. ........ .. . . .... .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pci/MA2 ) Uncertainty K-40 1 .000 1460.82* 10.66 9.82797E+005 l.95759E+005 Pb-212 1.000 238.63* 43.60 l .87414E+004 2 .12247E+004 Bi-214 0.732 609.32* 45.49 6.69398E+004 2.44403E+004 1120.29* 14. 92 1.03771E+005 4.31719E+004 17 64.49 15.30 Pb-214 0.439 295.22 18.42 351.93* 35.60 4.10286E+004 2.42465E+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

[458]

Interference Corrected Activity Report 6/6/2018 10 :17:38 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 9.827973E+005 l .957595E+005 Pb-212 1.000 1.874139E+004 2 .122468E+004 Bi-214 0.732 7.587876E+004 2.126865E+004 Pb-214 0.439 4.102865E+004 2.424647E+004

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

Peak Locate Performed on: 6/6/2018 10 : 1 7:37 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.31 3.3463E-001 38.83 6 1332.80 2.8485E-002 64.70 M - First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [459]

Nuclide MDA Report 6/6/2018 10:17:38 AM Page 5

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC059GD 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 .217E+005   1. 22E+OOS    9.828E+005  5.153E+004 Co-60     1173.23    99.85  1 .970E+004   1.97E+004     1. 922E+003 8.955E+003 1332.49    99.98  2.168E+004                  2.058E+004  9.892E+003 Nb-94       702.65   99.81  1. 626E+004   1. 63E+004  -1. 295E+O 02 7.429E+D03 871 .09  99.89  1. 708E+004               -4.152E+003   7.768E+003 Ag-108m     433.90   90.50  1.876E+004    1.88E+004     7.270E+003  8.764E+003 614.30   89.80  2.831E+004                -1. 303E+003  1 .342E+004 722.90   90.80  2.016E+004                -4.836E+003   9.301E+003 Cs-134      604.72   97.62  2.690E+004    1 .81E+004  -2.737E+004   1.278E+004 795.86   85.46  1. 808E+004               -1.604E+004   8.174E+003 Cs-137      661.66   85.1 0 2.341E+004    2.34E+004     2.968E+004  1.091E+004 Eu-152      121 .78  28.67  7.892E+004    7. 0 9E+004   3.372E+004  3.829E+004 344.28   26.60  7.156E+004                  1.505E+004  3.392E+004 1408.01    21.07  7.087E+004                -2.564E+003   3.081E+004 Eu-154      123.07   40 .40 5.549E+004    5.38E+004     3.546E+004  2.692E+004 723.30   20.06  9.130E+004                  5.618E+004  4 .211E+004 1274.43    34.80  S.377E+004                -1 .887E+004  2.422E+004 Eu-155       86.55   30.70  9.150E+004    9.15E+004     1.033E+005  4.466E+004 105. 31  21.10  1 .180E+005               -3.959E+004   5.740E+004 Tl-208      583.19   85.00  2.36SE+004    2.37E+004     1.519E+004  1.107E+004 Bi-212      727.33    6.67  2.645E+005    2.64E+OOS     3.438E+004  1. 216E+005
 +       Pb-212      238.63*  43.60  3.433E+004    3.43E+004     1. 874E+004 1.621E+004
 +       Bi-214      609.32*  45.49  2.878E+004    l .1 7E+004   6.694E+004  1.295E+004 1120.29*   14.92  1.170E+004                  1. 038E+005 O.OOOE+OOO 1764.49    15.30  1.663E+OOS                  1. 984E+005 7.588E+004
 +       Pb-214      295.22   18.42  1 .069E+005   3.46E+004     1.921E+004  5.092E+004 351.93*  35.60  3.463E+004                  4.103E+004  1.591E+004 Ra-226      186.21    3.64  S.064E+OOS    5.06E+005    1. 097E+005  2.430E+005 Ac-228      338.32   11. 27 1 .724E+005   8.30E+004     6.205E+003  8.183E+004 911. 20  25.80  8.302E+004                  2.684E+004  3.844E+004 968.97   15.80  1.320E+005                -5.817E+004   6.086E+004 Am-241       59.54   35.90  8.311E+004    8.31E+004     6.108E+004  4.043E+004
       + = Nuclide identified during the nuclide i dentification

• 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

[460]

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

Filename: 5456-A Report Generated On 6/7/2018 1:55:08 PM Sample Title B103202AFSFC060GD sample Description SFP/TRANSFER CANAL Sample Identification 060 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels} 85 - 8192 Peak Area Range (in channels} 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/7/2018 1:44: 00 PM Acquisition Started 6/7/2018 1:45:06 PM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0 . 09 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [461]

Peak Analysis Report 6/7/2018 1:55:08 PM Page 2

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

Detector Name: 5456-A Sample

Title:

Bl03202AFSFC060GD Peak Analysis Performed on: 6/7/2018 1: 55:07 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 1 196- 203 199.57 49.89 0.32 6.90E+OOO 23.55 6.31E+001 2 296- 311 301.10 75.27 1.19 l.47E+002 60. 78 2.56E+002 3 336- 348 340.36 85.09 0.61 5.84E+001 47 .16 1. 88E+O 02 4 948- 961 955.26 238.82 0.59 4. 13E+001 30 .49 6.87E+001 5 1259- 1268 1263.83 315.96 0.87 l. 48E+001 12.42 l .02E+001 6 1400- 1416 1408.39 352. 10 1.45 4.73E+001 24. 71 3.37E+001 7 2326- 2337 2331.81 582.95 1. 41 2.17E+001 14 .85 l.33E+001 8 2429- 2444 2436.91 609.23 0 .58 6.50E+001 19. 49 9.98E+OOO 9 3638- 3651 3644.54 911.14 1. 08 2.llE+OOl 15.14 l .29E+001 10 4474- 4487 4480.14 1120.04 0.94 3.18E+001 15.47 l .02E+001 11 5323- 5336 5329.62 1332.41 0.65 2.42E+001 10.82 l.77E+OOO 12 5834- 5854 5844.00 1461.00 0.42 l.25E+002 27 .28 l.63E+001 M = First peak in a mul t iplet region m = Other peak in a mul t iplet region F = Fitted singlet Errors quoted at 2.000 sigma [462]

Interference Corrected Activity Report 6/7/2018 1: 55: 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 REPORT *****

Sample

Title:

B103202AFSFC060GD Nuclide Library used: C:\GENIE2K\CAMFILES\Zion Lib- BNL . NLB

   * * * * * * * *

• t ** * *
• t - *
• I
• IDENTIFIED NUCLIDES . ..... ....... ... . . . ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1 . 000 1460.82* 10.66 8.60293E+005 2.02451E+005 Eu-155 0.345 86.55* 30. 70 4.75072E+004 3. 94920E+004 105.31 21. 10 Tl-208 1.000 583.19* 85. 00 1.20781E+004 8.39492E+003 Pb-212 1.000 238.63* 43.60 2.91839E+004 2.20705E+004 Bi-214 0.732 609.32* 45.49 6.90965E+004 2.23149E+OD4 1120.29* 14.92 l .37533E+OOS 6.77857E+004 1764.49 15.30 Pb-214 0 .439 295.22 18.42 351.93* 35.60 4.92236E+004 2.68807E+004 Am-241 0.862 5 9.54* 35.90 S.7138SE+003 l .95316E+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

[463]

Interference Corrected Activity Report 6/7/2018 1 : 55: 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 1.00 0 8.602930E+005 2.024509E+005 Eu-155 0 .34 5 4.750724E+004 3.949202E+004 Tl-208 1.00 0 1.207809E+004 8.394917E+003 Pb-212 1 .00 0 2.918391E+004 2.20704BE+004 Bi-214 0 .732 7.57879DE+004 2.119590E+004 Pb-214 0 .439 4. 922359E+004 2.688074E+004 Am-241 0 .862 5.713850E+003 1.95315BE+004

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

Peak Locate Performed on: 6/7/2018 1 : 55: 07 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 2 75.27 2.4566E-001 4 1. 23 5 315.96 2.4600E-002 84. 15 Sum 9 911.14 3.5245E-002 71 .61 Tol. Ac-228 11 1332 .41 4.0385E-002 44.65 Tol. Co-60 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [464]

Nuclide MDA Report 6/7/2018 1:55 : 08 PM Page 5

• • • • • N U C L I D E MD A RE PORT *****

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC060GD 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  1.964E+005      1 .96E+005  8.603E+005    8.886E+004 Co-60      1173.23    99.85  1.943E+004      1.94E+004   1 .650E+003   8.822E+003 1332.49    99.98  2.000E+004                  1 . 101E+004  9.055E+003 Nb-94       702.65    99.81  1.92BE+004      1.64E+004  -1 .580E+003   8.937E+003 871 .0 9  99.89  1.638E+004                  2.004E+003    7.417E+003 Ag-108m     433.90    90.50  1.850E+004      l.85E+004   1 .431E+004   8.636E+003 614.30    89.80  2.686E+004                 -6.263E+003    1.270E+004 722.90    90.80  1 .977E+004                -7.512E+003    9.106E+D03 Cs-134      604.72    97.62  2.383E+004      2.28E+004  -6 . 549E+003  1.125E+004 795.86    85.46  2.284E+004                  1. OllE+O 04  1.055E+004 Cs-137      661.66    85. 10 2.426E+004      2.43E+004   2.510E+003    1.133E+004 Eu-152      121.78    28.67  7.614E+004      6.32E+004   3.669E+004    3.690E+004 344.28    26.60  6.317E+004                 -9.059E+004    2.972E+004 1408.01    21. 07 6.661E+004                 -2.3BOE+004    2.868E+004 Eu-154      123.07    40. 40 5.334E+004      5.33E+004  -1.733E+003    2.584E+004 723.30    20.06  8.952E+004                 -6.845E+004    4.123E+004 1274.43    34.80  5.871E+004                  3.377E+004    2.669E+004
 +      Eu- 155      86.55*   30.70  6.185E+004      6.18E+004   4.751E+004    2.982E+004 105.31    21.10  l.111E+005                 -1.153E+O 05   5.395E+004
 +      Tl-208      583.19*   85.00  1.210E+004      1.21E+004   1. 2 OBE+O 04 5.296E+003 Bi-212      727.33     6.67  2.672E+005      2.67E+005   3.397E+004    1. 23 OE+005
 +      Pb-212      238.63*   43.60  3.408E+004      3.41E+004   2.918E+004    1.608E+004
 +      Bi-214      609.32*   45.49  2.201E+004      2.20E+004   6.910E+004    9.566E+003 1120.29*   14.92   8.699E+004                 1. 375E+005   3.765E+004 1764.49    15.30   1. 3 93E+O 05              1.341E+005    6.238E+004
 +      Pb-214      295.22    18.42  1. 108E+O 05    3.79E+004   1. 712E+O 04  5.289E+004 351.93*   35.60   3.793E+004                 4.922E+004    1.756E+004 Ra-226      186.21     3.64   5.838E+005     5.84E+005   6.657E+005    2.817E+005 Ac-228      338.32    11. 27 1.751E+005      9.19E+004. 9.160E+004    8.320E+004 911. 2 0  25.80   9.193E+004                 9.960E+004    4.290E+004 968.97    15 .80  1 .169E+005                5.011E+004    5.326E+004
 +      Am-241       59.54*   35.90   3.351E+004     3.35E+004   5.714E+003    l.563E+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

[465]

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

Filename ; 5456-A Report Generated On 6/7/2018 10 ~24:23 AM Sample Title B103202AFSFC061GD Sample Description SFP/TRANSFER CANAL Sample Identification 061 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 6/7/2018 10 : 14 : 00 AM Acquisition Started 6/7/2018 10 : 14 :22 AM Live Time 600 . 0 seconds Real Time 600.5 seconds Dead Time 0 .08 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [466]

Peak Analysis Report 6/7/2018 10:24:23 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC061GD Peak Analysis Performed on: 6/7/2018 10:24:22 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 1 290- 311 300.93 75.23 0.54 2.37E+D02 75.35 3.15E+002 2 950- 961 955.38 238.84 0.81 5.00E+OOl 27. 84 5.70E+001 3 1350- 1359 1354.11 338.53 0.30 1.37E+001 15.34 1.93E+001 4 1401- 1444 1407.54 351.88 1. 29 7.81E+001 43.82 5.89E+001 5 2038- 2051 2043.38 510.85 1. 43 3.73E+001 19.41 2.07E+001 6 2325- 2338 2331. 36 582.84 0.86 3.89E+001 16.32 9.llE+OOO 7 2429- 2445 2436.83 609.21 0.72 5.41E+001 18.24 8.88E+OOO 8 2640- 2656 2647.25 661.81 1. 67 3.22E+001 19.71 2.08E+001 9 3637- 3650 3643.90 910.97 1. 24 2.63E+001 14.18 8.70E+OOO 10 4474- 4487 4480.82 1120.21 0.36 2.53E+001 14.02 8.67E+OOO 11 4687- 4700 4693.03 1173.26 0.98 2.lSE+OOl 15.45 1.35E+001 12 4945- 4958 4951.63 1237.91 0.62 1. 52E+001 9.07 1.82E+OOO 13 5324- 5337 5330.10 1332.52 0.85 3.0lE+OOl 12.30 2.92E+OOO 14 5834- 5854 5844.16 1461.04 1. 97 1.47E+002 25.75 5.25E+OOO 15 7051- 7066 7058.46 1764.61 1. 72 2.92E+001 11.72 1. 78E+OOO M ~ First peak in a multiplet region m ~ Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma [467]

Interference Corrected Activity Report 6/7/2018 10:24:23 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:

B103202AFSFC061GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib - BNL . NLB

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

• I ,t I ,II * * * * * * * * *.," * ... ,...,

Nuclide Id Energy Yield Activity Activity Name Confidence (keV} (%) (pCi/MA2 } Uncertainty K-40 1 .000 1460.82* 10.66 1. 01214E+006 l .98173E+005 Co-60 1.000 1173.23* 99.85 1.42024E+004 1.02609E+004 1332.49* 99.98 2.10254E+004 8.76371E+003 Cs-137 1.000 661.66* 85. 10 1. 90424E+004 l.18672E+004 Tl-208 1.000 583.19* 85.00 2.16556E+004 9.45449E+003 Pb-212 1. 000 238.63* 43.60 3.53570E+004 2.04993E+004 Bi-214 1. 000 609.32* 45.49 5.75125E+004 2.05793E+004 1120.29* 14.92 1.09529E+005 6.12740E+004 1764.4 9

• 15.30 1.56684E+005 6.41028E+004 Pb-214 0.439 295.22 18 .42 351.93* 35.60 8.11928E+004 4. 73874E+OD4 Ac-228 0.552 338.32* 11. 27 4.42783E+004 5.00160E+004 911.20* 25.80 5.96829E+004 3.25878E+004 968.97 15.80

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

[468]

Interference Corrected Activity Report 6/7/2018 10 :24:23 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1.012140E+006 1.981726E+005 Co-60 1. 000 1. 8147SSE+004 6.663955E+003 Cs-137 1. 000 1.904240E+004 1.186719E+ 0 04 Tl-208 1. 000 2.165563E+004 9.454493E+003 Pb-212 1. 000 3.535696E+004 2.049927E+004 Bi-214 1. 000 7.074461E+004 1. 866328E+ 0 04 Pb-214 0.439 8.119282E+004 4.738736E+OD4 Ac-228 0.552 5.509222E+004 2.730372E+OD4

      ? ~ 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 a t 2.000 sigma

[469]

Interference Corrected Activity Report 6/7/2018 10:24:23 AM Page 5

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

Peak Locate Performed on: 6/7/2018 10 :24:22 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol . No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.23 3.9530E-001 31. 77 5 510.85 6.2241E-002 5 1. 98 12 1237.91 2.5294E-002 59.74 Sum M = First peak in a multiplet region m Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [470]

.Nuclide MDA Report 6/7/2018 10: 24:23 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC061GD 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 .177E+005   1.18E+005    1. 012E+006   4 .952E+004
 +      Co-60      1173 .23*   99.85  1 .520E+004   8.30E+003    1 .420E+004   6.707E+003 1332.49*    99.98  8.301E+003                 2.103E+004    3.205E+003 Nb-94       702 . 65   99. 81 1 .626E+004   1.63E+004    3.524E+003    7.429E+003 871 . 09   99.89  1 .922E+004                1 .732E+004   8.836E+003 Ag-108m     433.90     90.50  1 .901E+004   1.90E+004   -l .968E+004   8.890E+003 614.30     89.80  2.437E+004                 2.432E+003    1 .145E+004 722.90     90.80  2.055E+004                 2.121E+004    9.493E+003 Cs-134      604.72     97.62  2.312E+004    2.31E+004   -2.771E+003    1 .089E+004 795.86     85.46  2.347E+004                 1.918E+004    1 .086E+004
 +      Cs-137      661 . 66*  85. 10 1 .726E+004   1.73E+004    1. 904E+004   7.829E+003 Eu-152      121. 78    28.67  7.881E+004    6.14E+004    2.560E+004    3.824E+004 344.28     26.60  6.141E+004                -2.672E+004    2.884E+004 1408 .0 1   21.07  7.485E+004                 2.212E+003    3.280E+004 Eu-154      123 .0 7   40.40  5.542E+004    4.63E+004    1. 502E+O 0_4 2.688E+004 723.30     20.06  9.217E+004                 8.924E+004    4.255E+004 1274.43     34.80  4 .627E+004               -7.133E+002    2.047E+004 Eu-155       86.55     30.70  9.126E+004    9. 1 3E+004  4.978E+003    4.454E+004 105 .31    21.10  1.147E+005                 1.193E+004    5.577E+004
 +      Tl-208      583.19*    85.00  1.115E+004    1 .11E+004   2.166E+004    4.821E+003 Bi-212      727.33      6.67  2.617E+005    2.62E+005   -3.532E+004    1.202E+005
 +      Pb-212      238.63*    43.60  2.981E+004    2.98E+004    3.536E+004    1.395E+004
 +      Bi-214      609.32*    45.49  2.172E+004    2.17E+004    5.751E+004    9.423E+003 1120.29*    14.92  8.116E+004                 1. 0 95E+O 05 3.473E+004 1764.49*    15.30  5.449E+004                 1. 567E+O 05  1.999E+004
 +      Pb-214      295.22     18.42  1 .076E+OOS   7.14E+004    8.543E+004    5.129E+004 351.93*    35.60  7.141E+004                 8.119E+004    3.430E+004 Ra-226      186.21      3.64  5.523E+005    5.52E+005    3 . 774E+005  2.660E+005
 +      Ac-228      338.32*    11.27  8.001E+004    4.27E+004    4.428E+004    3.564E+004 911.20*    25.80  4. 268E+004                5.968E+004    1 .827E+004 968.97     15.80  1.396E+005                 3.622E+004    6.463E+004 Am-241       59.54     35.90  8.200E+004    8.20E+004    1.541E+004    3.988E+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 per form the decay correction

[471]

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

Filename: 5456-A Report Generated On 6/7/2018 10 :08 : 19 AM Sample Title B103202AFSFC062GD Sample Description SFP/TRANSFER CANAL Sample Identification 062 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/7/2018 9:58: 00 AM Acquisition Started 6/7/2018 9:58: 17 AM Live Time 600 . 0 seconds Real Time 600.3 seconds Dead Time 0 . 04 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 3M90DSFP 2IN [472]

Peak Analysis Report 6/7/2018 10 :08:19 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B10 3202AFSFC062GD Peak Analysis Performed on: 6/7/2018 10:08:18 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- 307 301.33 75.33 0.63 2.28E+002 86.39 3.97E+002 2 334 - 345 34 0. 76 85.19 0.76 4.52E+001 47.70 2.07E+002 3 614 - 623 618.35 154 .59 1. 00 8.76E+OOO 24.12 6.02E+001 4 949- 963 955.25 238. 81 0.91 5.39E+001 31. 91 6.91E+001 5 1176- 1188 1182.17 295.54 0.33 3.18E+001 22.79 3.72E+001 6 1400- 1413 1407.68 351 . 92 0.42 3.19E+001 22.95 3.61E+001 7 2325- 2339 2332.67 583.17 1. so 4.23E+001 19.61 1.88E+001 8 2430- 2444 2437.02 609.25 1. 22 S.93E+001 20.72 1.67E+001 9 2641- 2652 2646.30 661.57 0 .76 2.73E+001 14 .82 1.07E+001 10 5834- 5854 5843.88 1460.97 1. 64 1 .64E+002 26.44 2.78E+OOO 11 7054- 7069 7061.60 1765.40 0.32 2.32E+001 10 .67 1.80E+OOO 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 [473]

Interference Corrected Activity Report 6/7/2018 10: 08: 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 REPORT *****

Sample

Title:

Bl03202AFSFC062GD 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 1.13257E+006 2.07199E+005 Cs-137 1.000 661.66* 85.10 l.61061E+004 8.96369E+003 Eu-155 0.346 86.55* 30.70 3.67205E+004 3. 94436E+004 105.31 21.10 Tl-208 1.000 583.19* 85.00 2.35358E+004 l. 12861E+004 Pb-212 1 .000 238.63* 43.60 3.80983E+004 2. 33890E+004 Bi-214 0.705 609.32* 45.49 6.30223E+004 2. 32842E+004 1120.29 14.92 1764.49* 15.30 1. 24444E+005 5.80884E+004 Pb-214 1.000 295.22* 18.42 5.88406E+004 4.32260E+004 351.93* 35.60 3.31313E+004 2.44456E+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

[474]

Interference Corrected Activity Report 6/7/20 18 10: 08:19 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.132568E+006 2. 071 989E+OOS Cs-137 1.000 1.610607E+004 8.963695E+003 Eu-155 0.346 3.672045E+004 3.944365E+004 Tl-208 1.000 2.353580E+004 l.128608E+004 Pb-212 1.000 3.809830E+004 2.338897E+004 Bi-214 0.705 7.152495E+004 2.161255E+004 Pb-214 1.000 3.936123E+004 2.127856E+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

[475]

Interference Corrected Activity Report 6/7/2018 10 :08 : 19 AM Page 5

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

Peak Locate Performed on ~ 6/7/2018 10 :08: 18 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 75.33 3.7937E-001 37.95 3 154.59 1.4601E-002 275.29 M ~ First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [476]

Nuclide MDA Report 6/7/2018 10:08:19 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC062GD Nuclide Library Us ed: 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  9.250E+004    9.25E+004   1.133E+006   3.692E+004 Co-60      1173.23     99.85  2.284E+004    2.22E+004   1.618E+004   1.053E+004 1332.49     99.98  2.220E+004                2.214E+004   1.016E+004 Nb-94       702.65     99.81  l.721E+004    1.54E+004  -3.861E+003   7.902E+003 871.09     99.89  1.539E+004               -4.390E+003   6.922E+003 Ag-108m     433.90     90.50  1.811E+004    1.81E+004   4 .636E+003  8.441E+003 614.30     89.80  2.819E+004               -3.513E+003   1 .336E+004 722.90     90.80  2.236E+004                1.570E+004   l .040E+004 Cs-134      604.72     97.62  2.530E+004    1.94E+004  -1. 2 87E+004 l .198E+004 795.86     85.46  1.939E+004               -8.431E+003   8.829E+003
 +      Cs-137      661.66*    85.10  1.181E+004    1.18E+004   1. 611E+004  5.107E+003 Eu-152      121 .78    28.67  8.220E+004    6.66E+004  -1. 310E+004  3.994E+004 344.28     26.60  7.125E+004               -8.284E+003   3.376E+004 1408 .01    21.07  6.661E+004                4.445E+004   2.868E+004 Eu-154      123.07     40. 40 5.871E+004    4.63E+004   4.768E+004   2.853E+004 723.30     20.06  9.966E+004                1.340E+004   4.629E+004 1274.43     34.80  4.627E+004               -4.993E+004   2.047E+004
 +      Eu-155       86.55*    30.70  6.336E+004    6.34E+004   3.672E+004   3.058E+004 105. 31    21.10  l.172E+005               -2.114E+004   5.701E+004
 +      Tl-208      583.19*    85.00  l.496E+004    1 .SOE+004  2.354E+004   6.729E+003 Bi-212      727.33      6.67  2.932E+005    2.93E+005   6.786E+004   1.359E+005
 +      Pb-212      238.63*    43.60  3.487E+004    3.49E+004   3.810E+004   1.648E+004
 +      Bi-214      609.32*    45.49  2.710E+004    2.71E+004   6.302E+004   1.211E+004 1120.29     14.92  l. 482E+005               1. 049E+O 05 6.823E+004 1764.49*    15.30  5.497E+004                1. 244E+O 05 2.023E+004
 +      Pb-214      295.22*    18.42  6.532E+004    3.70E+004   5.884E+004   3.016E+004 351.93*    35.60  3.699E+004                3.313E+004   1 .709E+004 Ra-226      186.21      3.64  5.761E+OOS    5.76E+OOS   2.678E+005   2.778E+005 Ac-228      338.32     11. 27 1.682E+005    8.45E+004  -1. 250E+O 05 7.974E+004 911 .20    25.80  8.446E+004                7.637E+004   3.916E+004 968.97     15.80  1.420E+005               -1. 622E+004  6.584E+004 Am-241       59.54     35.90  7.955E+004    7.95E+004   5.907E+004   3.865E+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

[477]

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

Filename: 5456-A Report Generated On 6/5/2018 2:03:26 PM Sample Title B103202AFSFC063GD Sample Description SFP/TRANSFER CANAL Sample Identification 063 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO M"'2 Sample Taken On 6/5/2018 1 :52: 00 PM Acquisition Started 6/5/2018 1 :53:25 PM Live Time 600. 0 seconds Real Time 600.3 seconds Dead Time 0 .05 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1.5M90DSFP 2IN [478]

Peak Analysis Report 6/5/2018 2:03:26 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC063GD Peak Analysis Performed on: 6/5/2018 2:03:25 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- 306 301.25 75. 31 0.56 8.40E+001 47. 35 2.10E+002 2 336- 345 340.47 85.12 0.91 2.lOE+OOl 39.73 1 .65E+002 3 950- 962 955.56 238.89 0.56 5.05E+001 29.54 6.25E+001 4 1176- 1187 1180.96 295.24 0.36 2.00E+OOl 21.15 3.60E+001 5 1402- 1416 1408.06 352.01 1. 34 5.88E+001 22.68 2.42E+001 6 2038- 2053 2045.20 511. 3 0 1.11 3.25E+001 23.62 3.55E+001 7 2325- 2336 2330.95 582.74 0.78 2.00E+OOl 15.22 1.50E+001 8 2429- 2446 2437.68 609.42 0.89 5.27E+001 21. 28 1.83E+001 9 2640- 2654 2646.68 661.67 1. 04 4.20E+001 18.48 1.50E+001 10 3638- 3652 3644.81 911. 20 0.50 3.30E+001 11.49 O.OOE+OOO 11 4475- 4488 4481.72 1120.43 0.65 1. 46E+001 10.99 5.45E+OOO 12 4686- 4702 4693.92 1173.48 0.47 3.73E+001 16.19 8.73E+OOO 13 5325- 5338 5331.07 1332.77 0.61 3.27E+OD1 13.33 4.34E+OOO 14 5833- 5856 5844.69 1461.17 2. 04 1. 85E+002 28.03 2.89E+OOO M First peak in- a mu ltiplet region m ;: Other peak in a mu ltiplet region F "" Fitted singlet Errors quoted at 2 . 000 sigma [479]

Interference Corrected Activity Report 6/5/2018 2: 03: 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 REPORT *****

Sample

Title:

Bl03202AFSFC063GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

   * * * * * * * * * * * * * * 'O ~ ,. 11 a

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10 .66 l.26687E+006 2.21146E+005 Co-60 1.000 1173.23* 99.85 2.43676E+004 l.07660E+004 1332.49* 99.98 2.26436E+004 9.41726E+003 Cs-137 1.000 661.66* 85.10 2.45890E+004 1 .12141E+004 Eu-155 0.346 86.55* 30.70 1.65293E+004 3.14486E+004 1 05. 31 21.10 Tl-208 1.000 583.19* 85.00 l. 10280E+004 8.51527E+003 Pb-212 1.000 238.63* 43.60 3.48318E+004 2 .11447E+004 Bi-214 0.733 609.32* 45.49 5.55916E+004 2.34071E+004 112 0.29* 14. 92 6.22845E+004 4.73298E+004 1764.49 15.30 Pb-214 1.000 295.22* 18.42 3.63354E+004 3.88536E+004 351.93* 35.60 6.04224E+004 2.52151E+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

[480]

Interference Corrected Activity Report 6/5/20 18 2: 03: 26 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 1.266873E+006 2.211462E+005 Co-60 1. 000 2.339094E+004 7.088180E+003 Cs-137 1.000 2.458898E+004 l .121412E+004 Eu-155 0.346 1.652928E+004 3.144861E+004 Tl-208 1. 000 1.102800E+004 8.515270E+003 Pb-212 1.000 3.483185E+004 2.114471E+004 Bi-214 0.733 5.690689E+004 2.098149E+004 Pb-214 1.000 5.328405E+004 2.115135E+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

[481]

Interference Corrected Activity Report 6/5/2018 2:03:26 PM Page 5

  **********    U N I D E N T I F I E D    P  EA KS      **********

Peak Locate Performed on: 6/5/2018 2:03:25 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.31 1.3997E-001 56.39 6 511. 3 0 5.4142E-002 72. 70 10 911. 2 0 5.SOOOE-002 34.82 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 , 000 sigma [482]

Nuclide MDA Report 6/5/2018 2:03:26 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC063GD 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  9.429E+004    9.43E+004   1.267E+OD6 3.788E+004
 +       Co-60     1173.23*    99.85  1.321E+OD4    9.7DE+003   2.437E+OD4 5.721E+OD3 1332.49*    99.98  9.698E+003                2.264E+OD4 3.911E+003 Nb-94       702.65    99. 81 l.686E+004    l.69E+OD4   1.924E+D03 7.737E+OD3 8 71. 09  99. 89 1 .94DE+004               1 .478E+D04 8.933E+003 Ag-108m     433.90    90.50  1 .711E+D04   1.71E+OD4  -2.699E+D04 7.948E+003 614.30    89.80  2.737E+D04               -6.714E+OD3 1. 296E+O 04 722.90    90.80  2.D16E+004                8.86SE+OD3 9.307E+OD3 Cs-134      604.72    97.62  2.455E+004    2.30E+004  -7.577E+OD3 l.161E+004 795.86    85.46  2.302E+004                1.142E+004 1.065E+004
 +       Cs-137      661.66*   85.10  l.427E+004    l.43E+004   2.459E+OD4 6.342E+OD3 Eu-152      121 .78   28.67  7.621E+004    6.27E+004   l.088E+004 3.697E+004 344.28    26.60  6.266E+D04               -S.009E+004 2.949E+D04 1408.01     21. 07 8.809E+004                8.48DE+004 3.945E+004 Eu-154      123.07    40.40  5.416E+004    4.78E+004   8.258E+003 .2.627E+D04 723.30    20.06  8.777E+004               -5.486E+004 4.038E+004 1274.43     34.80  4.784E+004                1. 316E+D04     2.128E+004
 +       Eu-155        86.55*  30.70  5.219E+004    5.22E+004   l.653E+004 2.503E+004 105.31    21.10  1.153E+005                2.179E+004 5.610E+004
 +       Tl-208      583.19*   85.00  1.270E+004    1. 27E+004  1.103E+004 5.601E+003 Bi-212      727.33     6.67  2.673E+005    2.67E+005  -3.794E+D05 1.231E+005
 +       Pb-212      238.63*   43.60  3.126E+004    3.13E+004   3.483E+OD4 1. 470E+004
 +       Bi-214      609.32*   45.49  2.982E+004    2.98E+D04   S.559E+004 1 .349E+004 1120.29*    14.92  6.734E+004                6.228E+004 2.788E+004 1764.49     15.30  1 .361E+005               8.675E+004 6.084E+004
 +       Pb-214      295.22*   18.42  6.218E+004    3.10E+004   3.634E+004 2.863E+004 351.93*   35.60  3.099E+OD4                6.042E+004 l.410E+004 Ra-226      186.21     3.64  5.388E+005    5.39E+OOS  -5.23SE+D04 2.595E+005 Ac-228       338.32    11. 27 1 .609E+005   8.35E+004  -5.644E+OD4 7.616E+OD4 911.20    25.80  8.347E+004                5.864E+004 3.870E+004 968.97    15.80  1 .SSOE+OOS               9.527E+D04 7.238E+004 Am-241         59.54   35.90  7.607E+004    7.61E+OD4   1.770E+OD4 3.696E+004
       +    Nuclide identified during the nuclide i dentification
       * = 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

[483]

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

Filename: 5456-A Report Generated On 6/5/2018 2:18:31 PM Sample Title B103202AFSFC064GD Sample Description SFP/TRANSFER CANAL Sample Identification 064 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/5/2018 2:09: 00 PM Acquisition Started 6/5/2018 2:08:30 PM Live Time 600 . 0 seconds Real Time 600.3 seconds Dead Time 0 .04 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1.5M90DSFP 2IN [484]

Peak Analysis Report 6/5/2018 2: 1 8:31 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC064GD Peak Analysis Performed on: 6/5/2018 2:18:3 1 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- 307 30 1. 48 75. 37 1. 03 1. 46E+002 76.64 3.65E+002 2 515- 524 519.23 129.81 0.57 2.60E+001 30.30 9.00E+OOl 3 665- 676 669.26 167.31 0. 75 3.03E+001 27.40 6.27E+001 4 947- 960 955.48 238.87 0. 55 5.49E+001 29. 87 6. llE+OOl 5 1176- 1187 118 2. 18 295.54 0. 41 3.40E+001 22.38 3.60E+001 6 1401- 1414 1408.06 352. 01 0. 52 4.36E+001 23. 95 3.54E+001 7 2326 - 2339 2332.80 583.20 0. 69 2.93E+001 17.03 1. 57E+001 8 2430- 2445 2436.96 609.24 1. 02 7.02E+001 23.30 2.18E+001 9 2639- 2653 2646.45 661.61 1. 12 5. 04E+ 001 16.30 5.56E+OOO 10 3637- 3650 3643.77 910.94 0.61 2.89E+001 15.78 l. 11E+001 11 4686- 4701 4693.92 1173.48 0.76 5.79E+001 18.86 1.0lE+OOl 12 5321- 5338 533 0 .34 1332.59 0.27 4.81E+001 18.45 1 .09E+001 13 5834- 5854 5844.36 1461.09 1. 67 1 .58E+002 26.59 5.25E+OOO M

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

[485]

Interference Corrected Activity Report 6/5/2018 2: 18: 31 PM Page 3

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

Sample

Title:

B103202AFSFC064GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib- BNL. NLB

  * * * * * * * * * *  * * * * *

• I
• t
• IDENTIFIED NUCLIDES * * * * * * * * * * * *
• I * * *
• l
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1 .000 1460.82* 10.66 l .07961E+D06 2.04717E+005 Co-60 1.000 1173.23* 99.85 3.78617E+004 1 .26977E+004 1332.49* 99.98 3.33360E+004 l .30618E+004 Cs-137 1.000 661. 66* 85.10 2.95276E+004 l.01785E+004 Eu-152 0.618 121.78* 28.67 2.20172E+004 2.60382E+004 344.28* 26.60 5.992SSE+004 3.43636E+004 14 08.01 21.07 Tl-208 1.000 583.19* 85.00 1.61971E+004 9.6125BE+003 Pb-212 1 .000 238.63* 43.60 3.78480E+004 2. 15019E+004 Bi-214 0.438 609.32* 45.49 7.40088E+004 2.61201E+004 11 20.29 14.92 1764.49 15.30 Pb-214 1 . 000 295.22* 18.42 6.18799E+004 4.18678E+004 351.93* 35.60 4.47758E+004 2.56215E+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

[486]

Interference Corrected Activity Report 6/5/2018 2: 18: 31 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 1. 079610E+006 2.047167E+005 Co-60 1.000 3.566282E+004 9.1046SOE+003 Cs-137 1.000 2.952756E+004 1 .017853E+004 Eu-152 0.618 1. 592013E+004 2.420524E+004 Tl-208 1.000 1. 619706E+004 9.612580E+003 Pb-212 1. 000 3.784BOOE+004 2.150189E+004 Bi-214 0.438 7.400881E+004 2.612015E+004 Pb-214 1. 000 4.078164E+004 2.550919E+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

[487]

Interference Corrected Activity Report 6/5/2018 2: 18 : 31 PM Page 5

  ********* '*    U N I D E  N T I F I E D    P E A K S     **********

Peak Locate Performed on : 6/5/2018 2: 18 : 31 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 75.37 2.4377E-001 52.40 3 167.31 5.0511E-002 90.41 10 910.94 4.8167E-002 54. 60 Sum M ~ First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 000 sigma [488]

Nuclide MDA Report 6/5/2018 2: 18 : 31 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC064GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 )

 +      K-40       1460.82*    10. 66 1.167E+OOS      1. 1 7E+005  1.080E+006     4.911E+004
 +      Co-60      1173.23*    99.85  1.37SE+004      1.37E+004    3.786E+004     5.990E+003 1332.49*    99.98  1.574E+004                   3.334E+004     6.934E+003 Nb-94       702. 6 5   99.81  1.844E+004      1.47E+004   -l .202E+004    8.526E+D03 871.09     99.89  1.470E+004                  -2.080E+004     6.585E+003 Ag-108m     433.90     90.50  2.068E+004      2. 07E+004   1.651E+003     9.734E+003 614.30     89.80  2.911E+004                  -9.901E+003     1.383E+004 722.90     90.80  2.14SE+004                   1.686E+004     9.950E+003 Cs-134      604.72     97.62  2.779E+004      2.22E+004   -1.255E+004     1.323E+004 795.86     85.46  2.218E+004                   1.382E+004     1.023E+004
 +      Cs-137      661.66*    85.10  9.279E+003      9.28E+003    2.953E+D04     3.848E+003
 +      Eu-152      121.78*    28.67  4.204E+004      4.20E+004    2.202E+004     1 .988E+004 344.28*    26.60  4.890E+004                   5.993E+004     2.259E+004 1408 .01    21. 07 7.030E+004                   5.088E+OD4     3.056E+004 Eu-154      123.07     40.40  5.59SE+004      S.1SE+OD4    2.00BE+004     2.717E+004 723.30     20.06  9.710E+004                   6.180E+004     4.505E+004 1274.43     34.80  5.155E+004                   8.888E+OD3     2.313E+004 Eu-155       86.55     30.70  9.090E+004      9.09E+OD4    1.828E+OD4     4.439E+004 105.31     21. 10 1.166E+005                   4.547E+OD4     5.678E+004
 +      Tl-208      583.19*    85. 00 1.345E+004      1.34E+OD4    1 .620E+OD4    S.976E+003 Bi-212      727.33      6.67  2.854E+OOS      2.85E+OD5   -1 .567E+OOS    1. 321E+OOS
 +      Pb-212      238.63*    43.60  3.131E+004      3.13E+004    3.785E+004     l. 472E+004
 +      Bi-214      609.32*    45.49  3.092E+004      3.09E+OD4    7 .401E+004    l.403E+ 004 1120.29     14.92  1.552E+OOS                   2.226E+005     7. 181E+ 004 1764.49     15.30  1.435E+005                   1.441E+005     6.453E+004
 +      Pb-214      295.22*    18.42  6.202E+004      3.65E+004    6.188E+D04     2.855E+004 351.93*    35.60  3.654E+004                   4 .478E+D04    l.688E+004 Ra-226      186.21      3.64  5.628E+005      5.63E+OOS    4 .326E+D05    2.715E+005 Ac-228      338.32     11. 27 1. 7 07E+O 05   9.52E+004    1.104E+OD5     8.104E+004 911.20     25.80  9.524E+004                   3.925E+003     4 .459E+004 968.97     15.80  1.550E+005                   1 .195E+D05    7.238E+004 Am-241       59 . 5 4  35.90  8.006E+004      8.01E+004   -6.874E+002     3.895E+004
       +=Nuclide identified during the nuclide identification
       *=Energy line found in the spectrum
       > = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @=Half-life too short to be able to perform the decay correction

[489]

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

Filename: 5456-A Report GeneraLed On 6/6/2018 8: 17 :37 AM Sample Title B103202AFSFC065GD Sample Description SFP/TRANSFER CANAL Sample Identification 065 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 7.070E+OOO M"2 Sample Taken On 6/6/2018 8:07:00 AM Acquisition Started 6/6/2018 8:07:35 AM 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 5/30/2018 Efficiency ID l.5M90DSFP 2IN [490]

Peak Analysis Report 6/6/2018 8: 1 7:37 AM Page 2

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

Detector Name: 5456-A Sample

Title:

Bl03202AFSFC065GD Peak Analysis Performed on: 6/6/2018 8:17:37 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 137 129.81 32.45 1. 12 2.06E+002 58.92 2.20E+002 2 290- 306 30 0 .72 75.18 0.68 1.31E+002 88.26 5.81E+002 3 1401- 1416 140 7 .81 351. 95 0.38 5.58E+001 25. 68 3.62E+001 4 2036- 2050 204 4 . 12 511.03 0.84 4.13E+001 22.04 2.67E+001 5 2327- 2340 2333.23 583.31 0.45 3.13E+001 16.50 l .27E+001 6 2429- 2449 2439.04 609.76 1. 20 7.74E+001 21. 57 1 .06E+001 7 2641- 2656 2648.17 662.04 1. 72 5.43E+001 21.93 2.07E+001 8 4687- 4705 4696.97 1174 .24 0.93 6.58E+001 21. 36 l.42E+001 9 5326- 5342 5334.35 1333.59 1.21 5.37E+001 17 .85 8.32E+OOO 10 5837- 5860 5848.44 1462.11 1. 95 l.74E+002 26.38 O.OOE+OOO 11 7060- 7075 7067.03 1766.76 0.75 2.13E+001 12.39 5.75E+OOO M = First peak in a mul t iplet region m F

 -  Other peak in a mul t iplet region
 =  Fitted singlet Errors quoted at     2 . 000 sigma

[491]

Interference Corrected Activity Report 6/6/2018 8:l7:37AM 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:

B103202AFSFC065GD Nuclide Library Us ed: C:\GENIE2K\CAMFILES\Zion Lib- BNL. NLB

  'II * , * * * * * *

• I' * *
• I I I * '"
• IDENTIFIED NUCLIDES * * * .. * * ......... .. . . Ii *
• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.997 14 60.82* 10.66 1.19132E+006 2.08154E+005 Co-60 0.998 11 73.23* 99.85 4.30076E+004 l .43885E+004 1332.49* 99.98 3.72256E+004 l.27350E+004 Cs-137 1.000 661.66* 85.10 3.18100E+004 l.33989E+004 Tl-208 1.000 583.19* 85.00 l.72985E+004 9.35527E+003 Bi-214 0.703 609.32* 45.49 8.16513E+004 2.47692E+004 1120.29 14.92 1764.49* 15.30 1. 13524E+005 6.68280E+004 Pb-214 0. 438 295.22 18.42 351.93* 35.60 5.73471E+004 2.79254E+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

[492]

Interference Corrected Activity Report 6/6/2018 8:17 : 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 REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.997 1.19131BE+006 2.081537E+005 Co-60 0.998 3.976540E+OD4 9.536257E+003 Cs-137 1. 000 3.18100DE+004 1.339887E+004 Tl-208 1. 000 1.729848E+004 9.355268E+003 Bi-214 0. 703 8.550096E+004 2.322522E+004 Pb-214 0 .438 5.734708E+004 2.792539E+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

[493]

Interference Corrected Activity Report 6/6/2018 8:17:37 AM Page s

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

Peak Locate Performed on: 6/6/2018 8: 17 :37 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.45 3.4345E-001 28.59 2 75.18 2.1830E-001 67.39 4 511.03 6.8775E-002 53.41 M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [494]

Nuclide MDA Report 6/6/2018 8:17:37 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC065GD 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  1.853E+004    1.85E+004    1.191E+006   O.OOOE+OOO
 +      Co-60      1173 .23*   99.85  1.673E+004    1. 3SE+004   4.301E+004   7.479E+003 1332.49*    99.98  1.351E+004                 3.723E+004   5.819E+003 Nb-94        702.65    99.81  1.741E+004    1.69E+004    1.026E+002   8.008E+003 871.09    99.89  1.689E+004                 1. 219E+004  7.680E+003 Ag-108m      433.90    90.50  2.000E+004    2. 00E+004  -2.209E+004   9.393E+003 614.30    89.80  2.877E+004                -9.943E+003   l.366E+004 722.90    90.80  2.215E+004                 1.686E+003   1.030E+004 Cs-134       604.72    97.62  2.699E+004    1.87E+004    1.471E+003   1.283E+004 795.86    85. 46 1. 868E+004               -9.281E+003   8.483E+003
 +      Cs-137       661.66*   85.10  1.723E+004    l .72E+004   3.181E+004   7.822E+003 Eu-152       121 .78   28.67  1.061E+OOS    7.66E+004   -1.317E+004   5.192E+004 344.28    26.60  7.661E+004                 5.395E+004   3.646E+004 1408. 0 1   21.07  7.976E+004                 1.442E+004   3.529E+004 Eu- 154      123. 0 7  40.40  7.494E+004    4.97E+004    5.205E+004   3.666E+004 723.30    20.06  1.018E+005                 2.329E+004   4.740E+004 1274.43     34.80  4.973E+004                -4.583E+004   2.223E+004 Eu-155        86.55    30.70  1 .187E+005   1. 1 9E+005  1 .248E+OOS  5.828E+004 105.31    21.10  1. 487E+005                1.581E+004   7.284E+004
 +      Tl-208       583.19*   85.00  1 .252E+004   1.25E+004    1.730E+004   5.514E+003 Bi-212       727.33     6.67  3.115E+005    3.12E+005    1.352E+OOS   l.452E+005 Pb-212       238.63    43.60  5.679E+004    5.68E+004    3.393E+004   2.746E+004
 +      Bi-214       609.32*   45.49  2.448E+004    2.45E+004    8.165E+004   1.081E+004 1120.29     14 .92 1.671E+005                 6.891E+004   7.777E+004 1764.49*    15.30  8.723E+004                 1. 135E+O 05 3.639E+004
 +      Pb-214       295.22    18.42  1.167E+005    3.81E+004   -4.785E+004   5.591E+004 351.93*   35.60  3.806E+004                 5.735E+004   1.764E+004 Ra-226       186.21     3.64  6.935E+005    6.94E+005    3.841E+005   3.369E+OOS Ac-228       338.32    11. 27 1.892E+005    8.49E+004   -6.173E+003   9.030E+004 911. 20   25.80  8.487E+004                 3.221E+004   3.940E+004 968.97    15.80  1.612E+005                 1.537E+005   7.551E+004 Am-241        59. 5 4  35.90  1.216E+005    1.22E+005   -6.458E+002   5.970E+004
       + = Nuclide identified during the nuclide i dentification
       *=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

[495]

• • • • • GAMMA S P E C T R U M ANALYSIS *****

Filename: 5456-A Report Generated On 6/6/2018 8:31:39 AM Sample Title B103202AFSFC066GD Sample Description SFP/TRANSFER CANAL Sample Identification 066 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/6/2018 8:21: 00 AM Acquisition Started 6/6/2018 8:21:38 AM Live Time 600 . 0 seconds Real Time 600.3 seconds Dead Time 0 ~04 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1 .SM90DSFP 2IN [496]

Peak Analysis Report 6/6/2018 8:3 1 :39 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC066GD Peak Analysis Performed on: 6/6/2018 8: 31 :39 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 1 166- 174 170.23 42.56 0.77 1 .03E+001 20.20 4.28E+001 2 296- 307 301.49 75.37 0.84 7.78E+001 55.96 2.79E+002 3 952- 962 956.83 239.21 0.52 3.38E+001 28. 89 7.12E+001 4 1405- 1416 1410.55 352.64 0.73 3.04E+001 21.17 3.06E+001 5 2431- 2448 2439.36 609.84 0 .40 7.52E+001 22.54 1.58E+001 6 2641- 2657 2648.65 662.16 1. 28 8.97E+001 23.60 1 .53E+001 7 3639- 3652 3645.54 911. 38 1. 05 2.93E+001 14.61 8. 74E+OOO 8 3873- 3886 3879.01 969.75 1. 23 2.31E+001 13.86 8.89E+OOO 9 4478- 4491 4484.92 1121.23 0.77 1.75E+001 10.43 3.SOE+OOO 10 4692- 4705 4698.35 1174.59 1.19 3.15E+001 15.25 9.55E+OOO 11 5328- 5343 5336.02 1334. 01 0.44 3.72E+001 13.95 3.79E+OOO 12 5839- 5860 585 0.51 1462.63 1. 52 1.58E+002 27.50 8.31E+OOO 13 7058- 7073 7065.25 1766.31 0.56 2.18E+001 12.99 6.16E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F "" Fitted singlet Errors quoted at 2 . 000 sigma [497]

Interference Corrected Activity Report 6/6/2018 8:31:39 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:

B103202AFSFC066GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  ... ......... . .. JI _, * * * **     IDENTIFIED NUCLIDES          * ., *

• I * * * * * * * * * * * * * * ,.

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.995 1460.82* 10.66 1. 0798 9E+O 06 2.10381E+005 Co-60 0.997 1173.23* 99.85 2.05714E+004 l.01078E+004 1332.49* 99.98 2.58080E+004 9.89631E+003 Cs-137 1.000 661.66* 85.10 5.25163E+004 l.51891E+004 Pb-212 0.999 238.63* 43.60 2.33430E+004 2.03038E+004 Bi-214 0.998 609.32* 45.49 7.92598E+004 2.56043E+004 112 0.29* 14.92 7.49379E+004 4.50456E+004 1764.49* 15.30 l.16655E+005 7.00020E+004 Pb-214 0. 438 295.22 18.42 351.93* 35.60 3.12066E+004 2.23280E+004 Ac-228 0.588 338.32 11.27 911.20* 25.80 6.56490E+004 3.32584E+004 968.97* 15.80 8.72269E+004 5.28849E+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

[498]

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M ... 2 ) Uncertainty K-40 0.995 1. 079887E+006 2.103807E+005 Co-60 0.997 2.324506E+004 7.071342E+003 Cs-137 1.000 5.251635E+004 1 .518913E+004 Pb-212 0.999 2.334298E+004 2.030378E+004 Bi-214 0.998 8.173536E+004 2.121301E+004 Pb-214 0.438 3.120656E+004 2.232800E+004 Ac-228 0.588 7.176434E+004 2.815381E+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 a t 2.000 sigma

[499]

Interference Corrected Activity Report 6/6/2018 8:31:39 AM Page 5

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

Peak Locate Performed on : 6/6/2018 8:31:39 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 42.56 1. 7 083E-0 02 197.05 2 75.37 1.2972E-001 71.90 M =- First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [500]

Nuclide MDA Report 6/6/2018 8:31:39 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC066GD Nuclide Library Us ed: 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. 447E+005   1.45E+OOS   1 .080E+006  6.310E+004
 +      Co-60      1173.23*   99.85  l. 288E+004   9.60E+003   2.057E+004   5.557E+003 1332.49*   99.98  9.605E+003                2.581E+004   3.864E+003 Nb-94       702.65    99.81  1. 741E+004   1. 62E+004  7.193E+003   8.008E+003 871.09    99.89  l.620E+004               -1.753E+003   7.333E+003 Ag-108m     433.90    90.50  1.929E+004    1.93E+004   5.533E+001   9.038E+003 614.30    89.80  2.989E+004               -2.010E+004   1.422E+004 722. 90   90.80  1.978E+004               -1. 906E+004  9.116E+003 Cs-134      604.72    97.62  2.719E+004    2.38E+004  -2.690E+003   1.293E+004 795.86    85.46  2.382E+004               -1.814E+002   1.105E+004
 +      Cs-137      661. 66*  85.10  1.514E+004    1.51E+004   5.252E+004   6.779E+003 Eu-152      121. 78   28.67  7.981E+004    7.30E+004  -3.611E+004   3.877E+004 344.28    26.60  7.295E+004               -5.038E+004   3.464E+004 1408 .0 1  21.07  7.613E+004               -1.215E+004   3.348E+004 Eu-154      123 .0 7  40.40  5.769E+004    4.38E+004   4.956E+004   2.804E+004 723.30    20.06  8.954E+004               -3.657E+004   4.127E+004 1274.43    34.80  4.377E+004               -6.501E+003   1.925E+004 Eu-155       86.55    30.70  9.008E+004    9.01E+004   7.776E+004   4.398E+004 105 .31   21. 10 1.183E+005                4.287E+004   5.763E+004 Tl-208      583.19    85. 00 2.362E+004    2.36E+004  -1 .175E+004  1 .106E+004 Bi-212      727.33     6.67  2.700E+005    2.70E+005   1 .052E+005  1 .244E+005
 +      Pb-212      238.63*   43.60  3.191E+004    3.19E+004   2.334E+004   1 .502E+004
 +      Bi-214      609.32*   45.49  2.783E+004    2.78E+004   7.926E+004   1.249E+004 1120.29*   14. 92 5.540E+004                7.494E+004   2.191E+004 1764.49*   15.30  9.370E+004                1.167E+005   3.962E+004
 +      Pb-214      295.22    18.42  1.196E+005    3.33E+004   3.037E+004   5.733E+004 351.93*   35.60  3.335E+004                3.121E+004   1.528E+004 Ra-226      186.21     3.64  5.399E+005    5.40E+OOS   3.189E+005   2.600E+OOS
 +      Ac-228      338.32    11. 27 1.680E+005    4.23E+004  -2.464E+004   7.967E+004 911.20*   25.80  4.230E+004                6.565E+004   1.811E+004 968.97*   15.80  7.221E+004                8.723E+004   3.100E+004 Am-241       59.54    35.90  7.845E+004    7.84E+004   2.430E+003   3.815E+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

[501]

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

Filename: 5456-A Report Generated On 6/6/2018 8:45:20 AM Sample Title B103202AFSFC067GD Sample Description SFP/TRANSFER CANAL Sample Identification 067 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels} 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO M""2 Sample Taken On 6/6/2018 8:35:00 AM Acquisition Started 6/6/2018 8:35:19 AM Live Time 600 . 0 seconds Real Time 600.2 seconds Dead Time 0 .04 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration used Done On 5/30/2018 Efficiency ID 1 .5M90DSFP 2IN [502]

Peak Analysis Report 6/6/2018 8:45:20 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B1 03202AFSFC067GD Peak Analysis Performed on: 6/6/2018 8:45:20 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- 311 301. 61 75.40 0.68 9.51E+001 58.74 2.64E+002 2 332- 346 340.34 85.09 0.74 4.13E+001 51 .81 2.16E+002 3 952- 961 956.30 239.08 0.40 2.08E+001 25.66 6.02E+001 4 1176- 1187 1182.28 295.57 1. 05 2.49E+001 18.55 2.41E+001 5 1351- 1362 1355.83 338.96 0.75 2.76E+001 17.26 1.84E+001 6 1401- 1419 1409.36 352.34 0.50 6.31E+001 25.91 3.09E+001 7 2039- 2051 2045.34 511. 34 1. 41 1.77E+001 20. 85 3.43E+001 8 2329- 2342 2334.72 583.68 0 .91 3.86E+001 16.08 9.44E+OOO 9 2434- 2446 2439.72 609.93 0 .62 3.42E+001 20. 34 2.58E+001 10 5329- 5342 5335.14 1333.78 0 .94 1 .76 E+001 11.48 5.40E+OOO 11 5839- 5860 5849.26 1462 .31 1 .76 l .64E+002 27. 02 5.15E+OOO 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 [503]

Interference Corrected Activity Report 6/6/2018 8:45:2 0 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:

B103202AFSFC067GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  * * * * * * *

• re .. *'"* fl I * * ** IDENTIFIED NUCLIDES .................. . .. .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.996 1460.82* 10.66 1.12191E+006 2.09079E+OOS Eu-155 0.346 86.55* 30.70 3.25428E+004 4.13043E+004 1 0 5.31 21. 10 Tl-208 1 .000 583.19* 85. 00 2.13255E+004 9.25191E+003 Pb-212 1. 000 238.63* 43.60 1.43361E+004 1 .78625E+004 Bi-214 0.437 609.32* 45.49 3.60816E+004 2.18808E+004 11 20.29 14. 92 1764.49 15. 30 Pb-214 1.000 295.22* 18. 42 4.53334E+004 3.44986E+004 351.93* 35.60 6.47849E+004 2.85653E+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

[504]

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0 .996 1 .121913E+006 2.090793E+005 Eu-155 0.346 3.254276E+004 4.130429E+004 Tl-208 1.000 2.132548E+004 9.251907E+003 Pb-212 1 .000 1. 433612E+004 1.786252E+004 Bi-214 0 .437 3.608155E+004 2.188081E+004 Pb-214 1. 000 5.687317E+004 2.200193E+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

[505]

Interference Corrected Activity Report 6/6/2018 8:45:2 0 AM Page 5

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

Peak Locate Performed on: 6/6/2018 8:45:20 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 75.40 1. 5848E-001 61. 77 5 338.96 4.5987E-002 62.55 Tol. Ac-228 7 511.34 2.9479E-002 117.90 10 1333.78 2.9330E-002 65.26 M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2.000 sigma [506]

Nuclide MDA Report 6/6/2018 8:45:20 AM Page 6

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Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC067GD 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  1.158E+005    1 . 1 6E+005  l.122E+006   4.863E+004 Co-60      1173.23    99.85  2.240E+004    2.24E+004     1. 967E+004  1 .031E+004 1332.49    99.98  2.253E+004                  l. 785E+004  1 .033E+004 Nb-94       702.65    99.81  1.630E+004    1 .63E+004   -6.898E+003   7.455E+003 871.09    99.89  1.643E+004                 -1.199E+003   7.451E+003 Ag-108m     433.90    90.50  1.893E+004    l.89E+004     1. 140E+004  8.856E+003 614.30    89.80  2.664E+004                  1.433E+004   1.259E+004 722.90    90.80  1.898E+004                  1.858E+003   8.719E+003 Cs-134      604.72    97.62  2.532E+004    2. 0 4E+004  -2.423E+004   1.200E+004 795.86    85.46  2.040E+004                  8.387E+003   9.340E+003 Cs-137      661.66    85. 10 2.517E+004    2.52E+004     1.796E+004   1.180E+004 Eu-152      121.78    28.67  7.962E+004    6.53E+004    -1.763E+003   3.868E+004 344.28    26.60  6.531E+004                  l.526E+004   3.082E+004 1408 .0 1  21.07  7.976E+004                  1.442E+004   3.529E+004 Eu-154      123 .0 7  40.40  5.742E+004    4.27E+004     3.602E+004   2.790E+004 723.30    20.06  8.122E+004                 -8.448E+004   3.711E+004 1274.43    34.80  4.269E+004                 -5.260E+004   1 .871E+004
 +      Eu-155       86.55*   30.70  6.713E+004    6.71E+004     3.254E+004   3.250E+004 105.31    21. 10 l. 139E+005                -1. 4 63E+004 5.541E+004
 +      Tl-208      583.19*   85.00  1. 078E+004   l.08E+004     2.133E+004   4.642E+003 Bi-212      727.33     6.67  2.389E+005    2.39E+005    -1.790E+005   l.089E+005
 +      Pb-212      238.63*   43.60  2.910E+004    2.91E+004     1.434E+004   1. 3 62E+004
 +      Bi-214      609.32*   45.49  3.171E+004    3.17E+004     3.608E+004   1.443E+004 1120 .29   14. 92 1. 579E+005                 6.361E+004   7.318E+004 1764.49    15.30  1. 361E+005                 9.414E+004   6.084E+004
 +      Pb-214      295.22*   18.42  5.168E+004    3.74E+004     4.533E+004   2.338E+004 351.93*   35.60  3.737E+004                  6.478E+004   l.730E+004 Ra-226      186.21     3.64  5.343E+005    5.34E+005     1. 837E+004  2.572E+005 Ac-228      338.32    11. 27 1.727E+005    8.35E+004     1. 719E+O 05 8.204E+004 911.20    25.80  8.347E+004                 -1. 393E+004  3.870E+004 968.97    15. 80 1.507E+005                  1. 048E+O 05 7.022E+004 Am-241       59 .5 4  35.90  7.800E+004    7.80E+004    -5.572E+003   3.792E+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

[507]

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

Filename: 5456-A Report Generated On 6/6/2018 8:57:40 AM Sample Title B103202AFSFC068GD Sample Description SFP/TRANSFER CANAL Sample Identification 068 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/6/2018 8:47:00 AM Acquisition Started 6/6/2018 8:47:38 AM Live Time 600 . 0 seconds Real Time 600.2 seconds Dead Time 0 , 04 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID l .5M90DSFP 2IN [508]

Peak Analysis Report 6/6/2018 8:57:40 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B10 3202AFSFC068GD Peak Analysis Performed on: 6/6/2018 8:57:40 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- 306 301.65 75.41 1 .12 8.77E+001 45.38 l .8BE+002 2 952- 962 956.38 239.10 0 .74 5.50E+001 24.57 4.00E+OOl 3 1177- 1190 1182.55 295.64 0 .34 3.30E+001 24.20 4.lOE+OOl 4 1405- 1417 1410.50 352.63 0 .66 2.09E+001 21.17 3.41E+001 5 2430- 2447 2439.40 609.85 0 .94 5.21E+001 18.04 8.93E+OOO 6 2642- 2656 2648.90 662.22 0 .37 4.59E+001 15.35 4.13E+OOO 7 3874- 3887 3880.32 970.08 0 .31 1 .77E+001 11.40 S.29E+OOO 8 5838- 5860 5849.75 1462.44 1. 84 l .88E+002 29.80 8.66E+OOO 9 7060- 7075 7067.32 1766.83 0.79 1 .90E+001 8.72 O.OOE+OOO M ;;. First peak in a mu ltiplet region m = Other peak in a mu ltiplet region F = Fitted singlet Errors quoted at 2. 000 sigma [509]

Interference Corrected Activity Report 6/6/20 18 8:57 :40 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:

Bl03202AFSFC068GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0. 996 1460.82* 10.66 l.28966E+006 2.32787E+005 Cs-137 0. 999 661.66* 85. 10 2.68650E+004 9.55147E+003 Pb-212 1. 000 238.63* 43.60 3.79472E+004 1 .80384E+004 Bi-214 0. 703 609.32* 45.49 5.49066E+004 2.01343E+004 1120.29 14 .92 176 4.49* 15.30 l. 01506E+005 4.72785E+004 Pb-214 0 .999 295.22* 18.42 6.00674E+004 4.50417E+004 351.93* 35.60 2.15100E+004 2.20306E+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

[510]

Interference Correcte d Activity Report 6/6/2018 8:57:40 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.996 1.289664E+006 2.327867E+005 Cs-137 0.999 2.686504E+004 9.551468E+003 Pb-212 1. 000 3.794715E+004 l.803838E+004 Bi-214 0.703 6.206051E+004 1.852444E+004 Pb-214 0.999 2.895353E+004 1 .979021E+004

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

Peak Locate Performed on: 6/6/2018 8:57:40 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 .4618E-001 51.74 7 970.08 2.9511E-002 64.40 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [511]

Nuclide MDA Report 6/6/2018 8:57:40 AM Page 5

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC068GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi /M"2 ) (pCi/M"2 ) (pCi/MA2 )

 +      K-40       1460.82*    10 .66 1.493E+005    1. 49E+005   l. 290E+006 6.541E+004 Co-60      1173.23     99.85  2.076E+004    2.08E+004 -4.153E+003    9.497E+003 1332.49     99.98  2.227E+004                 1.171E+004  1.020E+004 Nb-94        702.65    99.81  1.741E+004    1.74E+004 3.108E+002     8.008E+003 871.09    99.89  1 .798E+004                6.877E+003  8.225E+003 Ag-108m      433.90    90.50  1 .697E+004   1.70E+004 2.532E+003     7.879E+003 614.30    89.80  2.614E+004                -6.277E+002  1 .234E+004 722.90    90.80  1. 958E+004               -4.715E+003  9.018E+003 Cs-134       604.72    97.62  2.352E+004    2. 1 3E+004 2.203E+003   1. 110E+004 795.86    85.46  2. 131E+004                9.377E+002  9.796E+003
 +      Cs-137       661.66*   85.10  8.543E+003    8.54E+003    2.687E+004  3.479E+003 Eu- 152      121.78    28.67  7.465E+004    6.53E+004    6.027E+004  3.619E+004 344.28    26.60  6.531E+004                -4.239E+004  3.082E+004 1408 . 01   21.07  7.030E+004                 2.476E+004  3.056E+004 Eu- 154      123 . 07  40.40  5.253E+004    5.15E+004    3.967E+004  2.546E+004 723.30    20.06  9.042E+004                 6.769E+004  4.171E+004 1274.43     34.80  5.155E+004                 2.382E+004  2.313E+004 Eu-155        86.55    30.70  8.725E+004    8.73E+004    5.287E+004  4.257E+004 105 .31   21.10  1.141E+005                 1.131E+OOS  5.554E+004 Tl-208       583.19    85.00  2.301E+004    2.30E+004 2.767E+004     1.076E+004 Bi-212       727.33     6.67  2.592E+OOS    2.59E+005 -7.803E+004    l.190E+005
 +      Pb-212       238.63*   43.60  2.412E+004    2.41E+004 3.795E+004     1 .113E+004
 +      Bi-214       609.32*   45.49  2.163E+004    1.45E+004 5.491E+004     9.386E+003 1120.29     14. 92 1. 467E+OOS               -5.755E+004  6.754E+004 1764.49*    15.30  1. 446E+004                1 .0lSE+OOS O.OOOE+OOO
 +      Pb-214       295.22*   18.42  6.862E+004    3.51E+004 6.007E+004     3.185E+004 351.93*   35.60  3.506E+004                 2.151E+004  1.614E+004 Ra-226       186.21     3.64  5.298E+005    5.30E+005 2.747E+005     2.550E+005 Ac-228       338.32    11.27  1.558E+OOS    8.49E+004 -5.340E+003    7.360E+004 911. 20   25. 80 8.487E+004                 3.138E+004  3.940E+004 968.97    15.80  1.343E+OOS                 2.796E+004  6.207E+004 Am-241        59 . 54  35.90  7.485E+004    7.48E+004    3.083E+004  3.635E+004
       +=Nuclide identified during the nuclide i dentification
       *=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

[512]

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

Filename: 5456-A Report Generated On 6/6/2018 9: 10: 35 AM Sample Title B103202AFSFC069GD Sample Description SFP/TRANSFER CANAL Sample Identification 069 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 7.070E+OOO M"2 Sample Taken On 6/6/2018 8:59: 00 AM Acquisition Started 6/6/2018 9 :00 :33 AM Live Time 600. 0 seconds Real Time 600.3 seconds Dead Time 0 . 04 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1.5M90DSFP 2IN [513]

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Detector Name: 5456-A Sample

Title:

B1 03202AFSFC069GD Peak Analysis Performed on: 6/6/2018 9:10:34 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 288- 306 301.60 75.40 1. 02 1.43E+002 69.29 3.13E+002 2 625- 634 629.99 157.50 0 .32 6.77E+OOO 23.94 5.92E+001 3 953- 963 957.54 239.38 0 .32 9.29E+OOO 23.74 5.37E+001 4 1402- 1417 1409.29 352.32 0 .79 5.0lE+OOl 25.60 3.79E+001 5 2327- 2338 2332.06 583.02 0 .76 2.24E+001 13.27 8.65E+OOO 6 2432- 2445 2438.95 609.74 1 . 13 5.50E+001 19.42 1. 40E+001 7 3640- 3654 3647.12 911. 78 1. 25 3.42E+001 14.38 5.85E+OOO 8 4688- 4701 4694. 91 1173 .73 0.34 1.43E+001 15.55 1 .58E+001 9 5838- 5860 5849.24 1462.31 1. 73 1.68E+002 26. 82 2.97E+OOO 10 7059- 7074 7066.28 1766.57 0.50 2 .40E+001 9.80 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 [514]

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Sample

Title:

Bl03202AFSFC069GD 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 0.996 1460.82* 10 .66 1.15056E+006 2.09073E+OOS Tl-208 1 .000 583.19* 85. 00 1.23558E+004 7.48498E+003 Pb-212 0 .999 238.63* 43. 60 6.41392E+003 1 .64313E+004 Bi-214 0 .704 609.32* 45.49 5.80115E+004 2.16306E+004 1120.29 14.92 1764.49* 15.30 1.28207E+005 5.33383E+004 Pb-214 0.438 295.22 18.42 351. 93* 35.60 5.14864E+004 2.7562SE+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

[515]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.996 1.150563E+006 2.090734E+005 Tl-208 1. 000 1.235583E+004 7.484977E+003 Pb-212 0.999 6.413922E+003 1 .643129E+004 Bi-214 0.704 6.792544E+004 2.004503E+004 Pb-214 0.438 5.148643E+004 2.756251E+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

[516]

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

Peak Locate Performed on: 6/6/2018 9:10:34 AM Peak Locate From Channel: 85 Peak Locate To channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.40 2.3895E-001 48.33 2 157.50 1.1288E-002 353.43 7 911.78 5.6917E-002 42.10 Tol. Ac-228 8 1173 .73 2.3750E-002 109 .15 Sum M ; First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [517]

Nuclide MDA Report 6/6/2018 9:10:35 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC069GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2 ) (pCi/M ... 2 ) (pCi/M"2 ) (pCi/M"2 )

 -;-    K-40       1460.82*  10.66  9.598E+004    9.60E+004      1. 151E+O 06 3.873E+004 Co-60      1173.23   99.85  2.328E+004    2.01E+004      2.059E+003   1.07SE+004 1332.49   99.98  2.012E+004                   1.636E+004   9.122E+003 Nb-94       702.65   99. 81 1.591E+004    1.59E+004    -1.154E+004    7.262E+003 871.09   99. 89 1. 901E+004                  l.007E+004   8.737E+003 Ag-108m     433.90   90.50  2.000E+004    1.94E+004      9.982E+003   9.393E+003 614.30   89.80  2.651E+004                 -1.725E+004    1 .253E+004 722.90   90.80  1.939E+004                   1.057E+004   8.919E+003 Cs-134      604.72   97.62  2.444E+004    2.20E+004      2.260E+003   1.156E+004 795.86   85.46  2.197E+004                   1.680E+004   1.012E+004 Cs-137      661. 66  85.10  2.580E+004    2.58E+004      2.731E+004   1. 211E+004 Eu-152      121. 78  28.67  7.952E+004    6.72E+004      9.734E+OD4   3.863E+004 344.28   26.60  6.723E+004                   l. 495E+004  3.178E+004 1408 .01  21.07  8.320E+004                   3.037E+004   3.701E+004 Eu-154      123.07   40. 40 5.524E+004    4.78E+004    -2.256E+003    2.682E+004 723.30   20.06  8.59SE+004                   1.011E+004   3.948E+004 1274.43   34.80  4.784E+004                 -l. 99SE+002   2.128E+004 Eu-155       86.55   30.70  8.616E+004    8.62E+004      8.232E+004   4.202E+OD4 105.31   21.10  1.077E+005                 -6.163E+004    5.231E+004
 +      Tl-208      583.19*  85. 00 9.964E+003    9.96E+003     1.236E+004    4.234E+003 Bi-212      727.33    6.67  2.536E+005    2.54E+005    -l.074E+OOS    1.162E+005
 +      Pb-212      238.63*  43.60  2.794E+004    2.79E+004     6.414E+003    l.304E+D04
 +      Bi-214      609.32*  45.49  2.459E+004    1 .45E+004    5.801E+004    1.087E+004 1120.29   14. 92 1 .593E+005                 9.964E+OD4    7.385E+004 1764.49*  15. 30 1 .446E+004                 1. 2 82E+005  O. OOOE+OOO
 +      Pb-214      295.22   18. 42 1 .028E+005   3.88E+004    -5.178E+004    4.892E+004 351.93*  35.60  3.883E+004                  5.149E+004    1. 802E+004 Ra-226      186.21    3.64  4.956E+005    4.96E+005    -4.485E+OOS    2.379E+OOS Ac-228      338.32   11. 27 1 .573E+005   8.82E+004     3.440E+004    7.434E+004 911. 20  25.80  8.825E+004                  6.024E+004    4.109E+004 968.97   15.80  1.293E+005                  9.884E+003    5.953E+004 Am-241       59.54   35.90  7.389E+004    7.39E+004    -2.712E+004    3.587E+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

[518]

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

Filename: 5456-A Report Generated On 6/6/2018 9:28:34 AM Sample Title Bl03202AFSFC070GD Sample Description SFP/TRANSFER CANAL Sample Identification 070 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/6/2018 9:18:00 AM Acquisition Started 6/6/2018 9:18:33 AM Live Time 600 . 0 seconds Real Time 600.3 seconds Dead Time 0 . 05 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID l .SM90DSFP 2IN [519]

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Detector Name: 5456-A Sample

Title:

B1 03202AFSFC070GD Peak Analysis Performed on: 6/6/2018 9:28:34 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 297- 311 30 1 .77 75.44 0.45 5.49E+001 62.45 3.18E+002 2 950- 961 956.17 239.04 0.34 3.18E+001 25. 91 5.42E+001 3 1179- 1189 1183.69 295.92 0.66 l .14E+001 19.23 3.36E+001 4 1403- 1417 1409.38 352.35 0.99 4.04E+001 24.98 3.96E+001 5 2329- 2342 2334.90 583.73 1. 11 2.90E+001 18.07 l.90E+001 6 2432- 2447 2439.58 609.89 1. 38 5.90E+001 19.51 1.20E+001 7 2642- 2656 2648.61 662.15 1. 31 4.55E+001 16.40 7.50E+OOO 8 2907- 2918 2912.81 728.20 0.60 1 .68E+001 11.53 6.22E+OOO 9 3642- 3655 3648.87 912.22 0.58 2.34E+001 12.87 6.60E+OOO 10 4690- 4703 4696.45 1174.11 1.17 2.54E+001 14.00 8.60E+OOO 11 5329- 5342 5335.84 1333.96 0.30 3.0SE+OOl 12.67 3.50E+OOO 12 5840- 5860 5850.03 1462.51 0.60 1. 76E+O 02 28.57 7.73E+OOO M =- First peak in a mu ltiplet region m = Other peak in a mu ltiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [520]

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Sample

Title:

B103202AFSFC070GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB I e *<I* e <I* *. *

• e * ... * ** e IDENTIFIED NUCLIDES
• _. * *
• I' e *
• e *
• e * * * * *
• I Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.995 146 0.82* 10 .66 1. 20704E+006 2.21936E+005 Co-60 0.998 11 73.23* 99.85 1.66132E+004 9.25236E+003 1332.49* 99.98 2.11552E+004 8.95255E+003 Ag-108m 0.403 433.90 90.50 614.30* 89.80 3.15196E+004 l.10871E+004 722.90* 90.80 9.62440E+003 6.70161E+003 Cs-137 1. 000 661.66* 85. 10 2.66470E+004 1.01238E+004 Tl-208 1 .000 583.19* 85.00 1 .60437E+004 1.01768E+004 Pb-212 1. 000 238.63* 43.60 2.19751E+004 1.82348E+004 Bi-214 0.437 609.32* 45.49 6.22215E+004 2.18909E+004 1120 .29 14.92 1764.49 15.30 Pb-214 1 . 000 295.22* 18.42 2.07655E+004 3.51345E+004 351. 93* 35.60 4 .14889E+004 2.65145E+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 a t                2.000 sigma

[521]

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Nucli de Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0 .995 1.207042E+006 2.219358E+005 Co-60 0 .998 1.895897E+004 6.433789E+003 Ag-108m 0 .403 9.624402E+003 6.701610E+003 Cs-137 1 . 000 2.664703E+004 1. 012382E+004 Tl-208 1 . 000 1. 604367E+004 1.017679E+004 X Bi-212 0 .999 Pb-212 1 . 000 2.197512E+004 1.823482E+004 Bi-214 0 .437 4 .322233E+004 2.557415E+004 Pb-214 1 .000 3.396928E+004 2. 116 419E+004

      ? = Nuclide is part of an undetermined so lution X ~ Nuclide rejected by the interference analysis
      @=Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at   2. 000 sigma

[522]

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Peak Locate Performed on: 6/6/2018 9:28:34 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 75.44 9.1564E-002 113.68 9 912.22 3.9000E-002 54.98 Sum M = First peak i n a multiplet region m ~ Other peak i n a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [523]

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Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC070GD 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 .372E+005    1.37E+005    1 .207E+006  5.935E+004
 +      Co-60      1173.23*   99.85  1.222E+004     8.97E+003    1.661E+004   5.227E+003 1332.49*   99.98  8.969E+003                  2.116E+004   3.546E+003 Nb-94       702.65    99.81  1. 861E+O 04   1.78E+004    1.033E+004   8.609E+003 871 .0 9  99.89  1. 777E+O 04                3.315E+003   8.119E+003
 +      Ag-108m     433.90    90.50  1. 893E+004    9.20E+003   -7.089E+003   8.856E+003 614.30*   89.80  1. 2 01E+004                3.152E+004   5.283E+003 722.90*   90.80  9.201E+003                  9.624E+003   3.825E+003 Cs-134      604.72    97.62  2.455E+004     2. 1 7E+D04 -3.61DE+003   1.161E+004 795.86    85.46  2.17SE+004                  3.015E+D03   1.002E+004
 +      Cs-137      661.66*   85.10  1.057E+004     1.06E+004    2.665E+004   4 .493E+003 Eu-152      121.78    28.67  7.803E+004     6.72E+004    5.856E+004   3.788E+004 344.28    26.60  6.723E+004                  1 .043E+003  3.178E+004 1408.01    21.07  8.649E+004                  3.123E+D04   3.866E+004 Eu-154      123.07    40.40  5.416E+004     5.24E+D04   -5.418E+003   2.627E+004 723.30    20.06  9.548E+004                 -7.040E+004   4.424E+004 1274.43    34.80  5.243E+004                  3.704E+OD4   2.357E+004 Eu-155       86.55    30.70  8.887E+004     8.89E+004    2.686E+004   4.338E+004 105.31    21.10  1.073E+OOS                 -1. 028E+005  S.211E+004
 +      Tl-208      583.19*   85.00  1. 469E+O 04   1 .47E+D04   1.604E+D04   6.598E+003 Bi-212      727.33*    6.67  1.253E+005     1. 25E+005   1.31DE+OOS   5.207E+004
 +      Pb-212      238.63*   43.60  2.83SE+004     2.84E+004    2.198E+004   1 .324E+004
 +      Bi-214      609.32*   45.49  2.371E+004     2.37E+D04    6.222E+004   1 .043E+004 1120 .29   14.92  1 .671E+005                 6.066E+OD4   7.777E+004 1764.49    15.30  1 .435E+005                 l. 441E+005  6.453E+004
 +      Pb-214      295.22*   18.42  5.879E+004     3.91E+004    2.077E+004   2.693E+004 351.93*   35.60  3.913E+004                  4.149E+004   1.818E+004 Ra-226      186. 21    3.64  5.194E+005     5.19E+OD5    2.595E+OOS   2.498E+OOS Ac-228      338.32    11. 27 1.551E+005     8.89E+004   -1.163E+OOS   7.323E+004 911.20    25.80  8.891E+004                  1.346E+004   4.142E+004 968.97    15.80  1.l98E+OOS                  6.448E+OD4   5.482E+004 Am-241       59. 5 4  35.90  7.579E+004     7.58E+OD4   -2.659E+OD4   3.682E+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

[524]

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

Filename : 5456-A Report Generated On 6/6/2018 9:42:41 AM Sample Title B103202AFSFC071GD Sample Description SFP/TRANSFER CANAL Sample Identification 071 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken on 6/6/2018 9:32:00 AM Acquisition Started 6/6/2018 9:32:39 AM 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 5/30/2018 Efficiency ID 1.5M90DSFP 2IN [525]

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Detector Name: 5456-A Sample

Title:

B103202AFSFC071GD Peak Analysis Performed on: 6/6/2018 9:42:40 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- 307 30 1. 59 75.40 1. 05 7.55E+001 49.69 2.26E+002 2 949- 961 955.98 238.99 1.20 4. 06E+001 28.78 6.14E+001 3 1401- 1415 1409.01 352.25 0.94 4.81E+001 23.77 3.19E+001 4 1543- 1554 1548.97 387.24 0.63 2.lOE+OOl 17.15 2.lOE+OOl 5 2329- 2341 2334.16 583.54 0.38 2.71E+001 16.47 1.49E+001 6 2430- 2446 2438.70 609.67 0.79 5.98E+001 22.47 2.13E+001 7 2641- 2653 2647.31 661.83 0.91 2.09E+001 15.10 1 .31E+001 8 5836- 5858 5846.71 1461. 68 1.17 1. 47E+002 27.02 8.82E+OOO 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 [526]

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Sample

Title:

B103202AFSFC071GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.999 1460.82* 10.66 1 .00753E+006 2.04583E+005 Cs-137 1. 000 661.66* 85 .10 1 .22270E+004 8.96194E+003 Tl-208 1. 000 583.19* 85.00 1.49593E+004 9.28468E+003 Pb-212 1. 000 238.63* 43.60 2.79923E+004 2.03714E+004 Bi-214 0.438 609.32* 45.49 6.30019E+004 2.48700E+004 1120.29 14.92 17 64.49 15.30 Pb-214 0.438 295.22 18.42 351. 93* 35.60 4.93902E+004 2.56619E+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

[527]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.999 1 .007531E+006 2.045826E+005 Cs-137 1.000 1.222696E+004 8.961945E+003 Tl-208 1. 000 1.495927E+004 9.284676E+003 Pb-212 1. 000 2.799226E+004 2.037145E+004 Bi-214 0.438 6.300189E+004 2.487000E+004 Pb-214 0 .438 4 .939019E+004 2.566190E+004

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

Peak Locate Performed on: 6/6/2018 9:42:40 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 75.40 1. 2584E-001 65.81 4 387.24 3.SOOOE-002 81. 66 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [528]

Nuclide MDA Report 6/6/2018 9:42:41 AM Page 5

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC071GD 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. 523E+005   1.52E+OOS   1.00BE+006  6.688E+004 Co-60      1173.23     99.85  2.493E+004    2.38E+004   3.438E+003  1.158E+004 1332.49     99.98  2.375E+004                2.631E+004  1.094E+OD4 Nb-94       702.65     99.81  1. 776E+004   1.60E+004   1.758E+004  8.184E+003 8 71. 09   99.89  1. 596E+004               9.200E+003  7.214E+003 Ag-108m     433.90     90.50  1. 917E+004   1.88E+004   1.006E+004  8.978E+003 614.30     89.80  2.773E+004                O.OOOE+OOO  1.314E+004 722.90     90.80  1.878E+004                1.939E+003  8.617E+003 Cs-134      604.72     97.62  2.699E+004    2.20E+004   1.346E+003  1.283E+004 795.86     85.46  2.197E+004                8.181E+003  1.012E+004
 +      Cs-137      661.66*    85.10  1.316E+004    1.32E+004   1 .223E+004 5.788E+003 Eu-152      121. 78    28.67  7.454E+004    6.53E+004  -6.D35E+004  3.614E+004 344.28     26.60  6.531E+004               -3.904E+004  3.082E+004 1408 .01    21. 07 7.976E+004                3.273E+004  3.529E+OD4 Eu-154      123 .0 7   40.40  5.387E+004    4.16E+004   3.739E+004  2.613E+004 723.30     20.06  8.315E+004                4.464E+003  3.807E+004 1274.43     34.80  4.157E+004               -1 .115E+004 1 .815E+004 Eu-155        86.55    30.70  8.624E+004    8.62E+004   4.136E+004  4.206E+004 105.31     21.10  1.176E+005               -1.681E+003  5.726E+004
 +      Tl-208      583.19*    85.00  1.311E+004    1 .31E+004  1.496E+004  5.809E+OD3 Bi-212      727.33      6.67  2.389E+005    2.39E+005   1.869E+004  1 .089E+005
 +      Pb-212      238.63*    43.60  3.117E+004    3.12E+004   2.799E+004  1 .465E+004
 +      Bi-214      609.32*    45.49  3.113E+004    3.11E+OD4   6.300E+004  1 .414E+004 1120.29     14.92  1.524E+005                2.735E+004  7.041E+004 1764.49     15.30  1.411E+005                1.008E+005  6.332E+004
 +      Pb-214      295.22     18.42  1.053E+005    3.54E+004   6.082E+004  5.019E+004 351.93*    35.60  3.539E+004                4.939E+OD4  1 .631E+004 Ra-226      186.21      3.64  5.399E+OOS    5.40E+005   2.407E+005  2.600E+OD5 Ac-228      338.32     11. 27 1.707E+005    8.82E+004   3.655E+004  8.104E+004 911.20     25.80  8.825E+004                4.318E+004  4.109E+004 968.97     15.80  1.331E+OOS                5.215E+004  6.144E+OD4 Am-241        59 . 54  35.90  7.662E+004    7.66E+004   6.241E+004  3.723E+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

[529]

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

Filename: 5456-A Report Generated On 6/6/2018 9:56:31 AM Sample Title Bl03202AFSFC072GD Sample Description SFP/TRANSFER CANAL Sample Identification 072 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3 .00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7. 070E+OOO M"' 2 Sample Taken On 6/6/2018 9:44:00 AM Acquisition Started 6/6/2018 9:46:29 AM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1.5M90DSFP 2IN [530]

Peak Analysis Report 6/6/2018 9:56: 31 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B103202AFSFC072GD Peak Analysis Performed on: 6/6/2018 9:56:30 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- 307 301. 02 75.26 0.92 1.24E+002 79.81 3.90E+002 2 332- 345 340.67 85.17 0.33 7.72E+001 51.94 2.17E+002 3 739- 749 743.67 185 .92 0.86 1.55E+001 23.91 5.35E+001 4 948- 962 956.29 239.07 0.96 5.21E+001 31. 69 6.89E+001 5 1401- 1416 1408.84 352.21 0.43 5.00E+OOl 25.19 3.60E+001 6 2428- 2443 2436.76 609.19 0.92 5.llE+OOl 21. 29 2.09E+001 7 3638- 3651 3644.24 911.06 0.40 1.45E+001 15.84 1.75E+001 8 5833- 5856 5844.98 1461.25 1.40 1 .72E+002 28 .01 5.98E+OOO 9 7055- 7070 7062.98 1765.75 0.49 2.21E+001 12.62 5.90E+OOO M "" First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [531]

Interference Corrected Activity Report 6/6/2018 9:56:31 AM Page 3

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

Sample

Title:

B103202AFSFC072GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• a 4 ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1. 000 1460.82* 10 .66 l .17736E+006 2.17240E+005 Eu-155 0. 346 86.55* 30.70 6.07329E+004 4.26359E+004 105.31 21.10 Pb-212 1. 000 238.63* 43.60 3.59600E+004 2.26308E+004 Bi-214 0 .705 609.32* 45.49 5.38912E+004 2.33546E+004 1120.29 14 .92 1764.49* 15.30 1.18016E+005 6.80538E+004 Pb-214 0 .438 295.22 18.42 351.93* 35.60 5.13614E+004 2.71525E+004 Ra-226 1.000 186.21* 3.64 1.13207E+005 1. 75876E+005

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

[532]

Interference Corrected Activity Report 6/6/2018 9:56:31 AM Page 4

• • • • • I N T E R F E R E N C E C O R R E C T E D 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 .177363E+006 2.172404E+005 Eu-155 0.346 6.073288E+004 4.26358SE+004 Pb-212 1.000 3.596003E+004 2.263077E+004 Bi-214 0.705 6.064761E+004 2.209001E+004 Pb-214 0.438 S.136144E+004 2.715246E+004 Ra-226 1.000 1.132066E+OOS 1.758765E+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

[533]

Interference Corrected Activity Report 6/6/20 18 9:56:31 AM Page 5

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

Peak Locate Performed on: 6/6/2018 9:56:30 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 75.26 2.0599E-001 6 4 .58 7 911 .06 2.4167E-002 109.22 Tol. Ac-228 M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted a t 2 . 000 sigma [534]

Nuclide MDA Report 6/6/2018 9:56:31 AM Page 6

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSFC072GD 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   1.290E+005     1.29E+005   l.177E+006  5.523E+004 Co-60      1173.23    99.85   2.572E+004     2.35E+004   2.541E+004  1.197E+004 1332.49    99.98   2.351E+004                 1.555E+004  1.082E+004 Nb-94       702.65    99.81   1. 758E+004    1 .62E+004  6.169E+003  8.097E+003 871.09    99.89   1.620E+004                 1 .776E+003 7.333E+003 Ag-108m     433.90    90.50   1.697E+004     1.70E+004  -1.424E+004  7.879E+003 614.30    89.80   2.784E+004                -1. 723E+004 1. 320E+004 722.90    90.80   2.091E+004                 1.119E+004  9.680E+003 Cs-134      604.72    97.62   2.444E+004     2.02E+004   2.747E+003  1. 156E+004 795.86    85.46   2.016E+004                -9.033E+002  9.222E+003 Cs-137      661.66    85.10   2.470E+004     2.47E+004   2.722E+004  1.156E+004 Eu-152      121. 78   28.67   7.682E+004     6.02E+004  -1.010E+004  3.728E+004 344.28    26.60   6.024E+004                -1 .105E+005 2.828E+004 1408.01    21. 07  7.797E+004                 6.445E+004  3. 440E+ 004 Eu-154      123.07    40.40   5.431E+004     4.97E+004   2.924E+004  2.63SE+004 723.30    20.06   9.299E+004                 4.612E+004  4.299E+004 1274.43    34.80   4.973E+004                -1.146E+004  2.223E+004
 +      Eu-155       86.55*   30.70   6.539E+004     6.54E+004   6.073E+004  3.163E+004 105.31    21.10   1. 122E+O OS               2.235E+004  5.459E+004 Tl-208      583.19    85.00   2.377E+004     2.38E+004   2.404E+004  1 .114E+004 Bi-212      727.33      6.67  2.829E+005     2.83E+005  -1.066E+005  1.309E+OOS
 +      Pb-212      238.63*   43.60   3.390E+004     3.39E+004   3.596E+004  1.601E+004
 +      Bi-214      609.32*   45.49   3.019E+004     3.02E+004   5.389E+004  1.367E+004 1120.29    14.92   1 .524E+005                4.948E+004  7.041E+004 1764.49*   15.30   8.840E+004                 1. 180E+005 3.697E+004
 +      Pb-214      295.22    18 .42  1 .042E+005    3.80E+004   2.510E+004  4.965E+004 351. 93*  35.60   3.801E+004                 5.136E+004  1. 761E+O 04
 +      Ra-226      186.21*     3.64  2.915E+005     2.92E+005   l.132E+OOS  1.359E+005 Ac-228      338.32    1 1. 27 l.543E+005     8.96E+004   4.238E+004  7.286E+004 911.20    25.80   8.956E+004                 6.013E+004  4 .175E+004 968.97    15 .80  1.392E+005                 1.126E+005  6.450E+004 Am-241       59. 5 4  35.90   7.106E+004     7.11E+004  -7.534E+004  3.445E+004
       + ; Nuclide identified during the nuclide identification
       * = Energy line found in the spectrum
       >=Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
       @ = Half-life too short to be able to perform the decay correction

[535]

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

Filename: 5456-A Report Generated On 6/7/2018 9:43:22 AM Sample Title B103202AFSWC073GD Sample Description SFP/TRANSFER CANAL Sample Identification 073 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/7/2018 9:29:00 AM Acquisition Started 6/7/2018 9:33:20 AM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0 . 09 % Energy* Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID 1 .SM90DSFP 2IN [536]

Peak Analysis Report 6/7/2018 9:43:22 AM Page 2

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

Detector Name: 5456-A Sample

Title:

Bl0 3202AFSWC073GD Peak Analysis Performed on: 6/7/2018 9:43:21 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 1 287- 306 301. 07 75.27 1. 04 2.10E+002 78.37 3.79E+002 2 948- 960 955.14 238.79 0.45 1. 62E+001 27 .17 6.28E+001 3 1402- 1417 1407.78 351.95 1. 27 4.36E+001 23.58 3.14E+001 4 2036- 2048 2042.24 510.56 0.43 1. 44E+001 20. 79 3.56E+001 5 2429- 2442 2436.38 609.09 1. 04 4.34E+001 18.91 1.66E+001 6 3638- 3651 3644.36 911.09 1.15 2.95E+OD1 12.51 3.SOE+OOO 7 4474- 4487 4480.23 1120.06 0.61 3.25E+OD1 12.98 3.5DE+OOO 8 5323- 5336 5329.84 1332.46 0.42 3.20E+OD1 11. 31 O.OOE+OOO 9 5834- 5854 5843.57 1460.89 1. 24 l. 14E+OD2 23.42 5.79E+OOO 10 7054- 7069 7061. 38 1765.34 2.06 2.SOE+OOl 10.00 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 [537]

Interference Corrected Activity Report 6/7/2018 9:43:22 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:

B103202AFSWC073GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB f * * *

• t
• ii
• f I *
• JI * * *
• JI
• IDENTIFIED NUCLIDES . .......... ...... " . .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA 2 ) Uncertainty K-40 1 .000 1460.82* 10.66 7.81556E+OOS 1 .74020E+005 Pb-212 1.000 238.63* 43.60 1.11753E+004 l.88335E+004 Bi-214 1. 000 609.32* 45.49 4.57682E+004 2.06753E+004 1120.29* 14.92 1 .39102E+OOS 5.66685E+004 17 64.49* 15.30 1 .33496E+005 5.44583E+004 Pb-214 0.438 295.22 18.42 351.93* 35.60 4.47837E+004 2.52497E+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

[538]

Interference Corrected Activity Report 6/7/20 18 9:43:22 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 7.815559E+005 l.740199E+005 Pb-212 1. 000 l. 117530E+004 1.883351E+004 Bi-214 1.000 6.539521E+004 1.829421E+004 Pb-214 0.438 4.478374E+004 2.524970E+004

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

Peak Locate Performed on: 6/7/2018 9:43: 21 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Pea_k Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.27 3.5073E-001 37.24 4 510.56 2.3933E-002 144 .76 6 911.09 4.9167E-002 42.41 Tol. Ac-228 8 1332.46 5.3333E-002 35.36 M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [539]

Nuclide MDA Report 6/7/2018 9:43:22 AM Page 5

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

Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC073GD 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/MA 2 ) (pCi/MA2 )

 +      K-40       1460.82*     10.66   1.262E+005     1. 26E+005  7.816E+005   5.383E+004 Co-60      1173.23      99.85   2.284E+004     2.28E+004   1. 712E+004  1.054E+004 1332.49      99.98   2.468E+004                 l. 200E+004  1.140E+004 Nb-94       702.65      99.81   1.630E+004     1.50E+004   1. 347E+004  7.455E+003 8 71. 09    99.89   1.496E+004                -2.684E+003   6.716E+003 Ag-108m     433.90      90.50   1.752E+004     1.75E+004   8.498E+003   8.151E+003 614.30      89.80   2.458E+004                -2.672E+004   1.156E+004 722.90      90.80   1.750E+004                 9.268E+003   7.978E+003 Cs-134      604.72      97.62   2.257E+004     1. 87E+004  2.058E+004   1 .062E+004 795.86      85.46   1.868E+004                 3.919E+003   8.483E+003 Cs-137      661.66      85. 10  2.580E+004     2.58E+004   3.509E+004   1 .211E+004 Eu- 152     121. 78     28.67   7.528E+004     5.91E+004   l .425E+004  3.650E+004 344.28      26.60   6.164E+004                -2.226E+004   2.898E+004 1408 . 01    21.07   5.908E+004                 9.921E+003   2.495E+004 Eu- 154     123 . 07    40. 40  5.342E+004     4 .59E+004 -9.569E+003   2.591E+004 723.30      20.06   7.721E+004                -1 .598E+004  3.510E+004 1274.43      34.80   4.586E+004                 2.477E+004   2.029E+004 Eu- 155       86 . 5 5  30.70   9.194E+004     9.19E+004   2.593E+004   4.491E+004 105.31      21.10   1.159E+005                -2.491E+004   5.641E+004 Tl-208      583.19      85.00   2.004E+004     2.00E+004   2.220E+004   9.274E+003 Bi-212      727.33       6.67   2.232E+005     2.23E+005   9.652E+004   l.OllE+OOS
 +      Pb-212      238.63*     43.60   3.132E+004     3.13E+004   1.118E+004   1.473E+004
 +      Bi-214      609.32*     45.49   2.636E+004     1. 44E+004  4 .577E+004  l .175E+004 1120.29*     14. 92  5.528E+004                 1. 391E+005  2.185E+004 1764.49*     15. 30  1. 445E+O 04               1. 335E+005  O.OOOE+OOO
 +      Pb-214      295.22      18. 42  l. 056E+005    3.58E+004   4 .307E+004  5.036E+D04 351.93*     35.60   3.577E+004                 4 .478E+004  l .650E+004 Ra-226      186.21       3.64   5.607E+005     5.61E+005   1.896E+005   2.704E+005 Ac-228      338.32      11.27   1. 434E+005    7.91E+004   6.650E+004   6.739E+D04 911.20      25.80   7.913E+004                 2.952E+004   3.653E+D04 968.97      15.80   1.19BE+005                 9.471E+004   5.482E+D04 Am-241        59.54     35.90   8.796E+004     8.80E+004   5.398E+004   4.290E+D04
       + ~ Nuclide identified during the nuclide i dentification
       * = 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

[540]

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

Filename: 5456-A Report Generated On 6/7/2018 9:25:18 AM Sample Title B103202AFSWC074GD Sample Description SFP/TRANSFER CANAL sample Identification 074 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/7/2018 9:14:00 AM Acquisition Started 6/7/2018 9:15: 16 AM Live Time 600 . 0 seconds Real Time 601. 0 seconds Dead Time 0 . 16 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration used Done On 5/30/2018 Efficiency ID l.5M90DSFP 2IN [541]

Peak Analysis Report 6/7/2018 9:25:18 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B1 03202AFSWC074GD Peak Analysis Performed on: 6/7/2018 9:25: 18 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 1 257- 264 260.00 65. 00 0.33 -3.88E+OOO 32.74 1. 30E+002 2 296- 308 301.13 75.28 1. 04 1. 28E+002 56.86 2.58E+002 3 337- 346 341. 19 85.30 0.88 2.90E+001 42.45 1.85E+002 4 951- 960 955.20 238.80 1. 42 4 .80E+001 22.61 3.SOE+OOl 5 1400- 1416 1408.04 352.01 0.73 4.48E+001 21.69 2.32E+001 6 2327- 2339 2332.21 583.05 0.44 2 . 65E+001 15.42 l .25E+001 7 2430- 2443 2436.73 609.18 0.93 5.13E+001 19.43 1 .57E+001 8 2640- 2652 2645.94 661.48 1. 04 4.53E+001 16.84 9.75E+OOO 9 3636- 3650 3643.12 910.78 0.55 2.46E+001 14.41 9.43E+OOO 10 4475- 4488 4481.92 1120.48 0.53 2.lOE+OOl 9.17 O.OOE+OOO 11 4686- 4701 4693.71 1173.43 0.49 4.28E+001 14.12 2.17E+OOO 12 5323- 5337 5330.59 1332.65 0.58 3.70E+001 14 .05 3.98E+OOO 13 5834- 5855 5844.95 1461 .24 1. 03 1 .28E+002 24.22 5.17E+OOO 14 7052- 7067 7059.86 1764.97 1. 50 2.00E+OOl 8.94 O.OOE+OOO 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 [542]

Interference Corrected Activity Report 6/7/2018 9:25:18 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:

B103202AFSWC074GD 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 8.74928E+005 l.82331E+005 Co-60 1 . 000 1173.23* 99.85 2.80031E+004 9.49623E+003 1332.49* 99.98 2.56665E+004 9.95267E+003 Cs-137 1 . 000 661.66* 85. 10 2.64882E+004 l.03586E+004 Eu-155 0 .346 86.55* 30. 70 2.28061E+004 3.36907E+004 105.31 21. 10 Tl-208 1. 000 583.19* 85. 00 1 .46226E+004 8.70366E+003 Pb-212 1. 000 238.63* 43.60 3.31142E+004 l.64921E+004 Bi-214 1. 000 609.32* 45.49 5.41016E+004 2 .14895E+004 1120.29* 14.92 8.98971E+004 3.98896E+004 1764.49* 15.30 l .06783E+005 4. 85149E+004 Pb-214 0 .438 295.22 18.42 351. 93* 35.60 4.60081E+004 2.34642E+004 Am-241 0 .953 59.54* 35.90 -2.91891E+003 2.46568E+004

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

[543]

Interference Corrected Activity Report 6/7/2018 9:25:18 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 8.749276E+005 1 .823311E+005 Co-60 1 .000 2.688963E+004 6.870544E+003 Cs-137 1 .000 2.648825E+004 l .035858E+004 Eu-155 0.346 2.280611E+004 3.369066E+004 Tl-208 1. 000 l .462257E+004 8.703659E+003 Pb-212 1. 000 3.311424E+004 l .649214E+004 Bi-214 1. 000 6.804449E+004 1 .762607E+004 Pb-214 0.438 4.600809E+004 2.346419E+004 Am-241 0.953 -2.918913E+003 2.465680E+004

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

Peak Locate Performed on: 6/7/201 8 9:25:18 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 75.28 2.1350E-001 44.39 9 910.78 4.0956E-002 58.64 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 [544]

Nuclide MDA Report 6/7/2018 9:25:18 AM Page 5

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Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC074GD 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. 161E+005   1 .16E+OOS   8.749E+005   4.880E+004
  +     Co-60      1173.23*   99.85   7.451E+003    7.45E+003    2.800E+004   2.841E+003 1332.49*   99.98   9.879E+003                 2.567E+004   4.001E+003 Nb-94       702.65    99.81   1. 591E+004   l .59E+004  -6.415E+002   7.262E+003 871.09    99.89   1. 689E+004                3.822E+003   7.680E+003 Ag-108m     433.90    90.50   l. 765E+004   l .76E+004   l. 472E+004  8.218E+003 614.30    89.80   2.576E+004                -1.671E+004   1.215E+004 722.90    90.80   1. 997E+004               -3.221E+003   9.212E+003 Cs-134      604.72    97.62   2.421E+004    l .97E+004  -1.016E+004   1.144E+004 795.86    85.46   1. 968E+004               -2.659E+003   8.983E+003 Cs-137      661. 66*  85.10   1. 134E+004   1. 13E+004   2.649E+004   4.877E+003 Eu-152      121.78    28.67   7.823E+004    6.33E+004    7.913E+002   3.798E+004 344.28    26.60   6.334E+004                -1.618E+004   2.983E+004 1408 .01   21. 07  8.486E+004                 7.801E+004   3.784E+004 Eu-154      123.07    40. 40  5.460E+004    5.33E+004   -6.339E+004   2.649E+004 723.30    20.06   8.866E+004                -3.614E+004   4.083E+004 1274.43    34.80   5.329E+004                 3.956E+004   2.401E+004
  +     Eu-155       86.55*   30.70   5.524E+004    5.52E+004    2.281E+004   2.656E+004 105.31    21. 10  1.187E+005                 5.840E+004   5.781E+004
  +     Tl-208      583.19*   85.00   1.194E+004    1.19E+004    1.462E+004   5.224E+003 Bi-212      727.33     6.67   2.804E+OOS    2.80E+005   -1. 629E+004  1.296E+005
  +     Pb-212      238.63*   43.60   2.215E+004    2.21E+004    3.311E+004   1.014E+004
  +     Bi-214      609.32*   45.49   2.561E+004    l. 1 6E+004  S.410E+004   1.138E+004 1120.29*   14 .92  1.158E+004                 8.990E+004   O.OOOE+OOO 1764.49*   15 .30  1 .44SE+004                1. 0 68E+005 O.OOOE+OOO
  +     Pb-214      295.22    18 .42  1 .063E+005   3. 1 6E+004  6.302E+004   5.072E+004 351.93*   35.60   3.162E+004                 4.601E+004   1.442E+004 Ra-226      186.21     3.64   5.575E+005    S.57E+OOS    2.717E+005   2.688E+005 Ac-228      338.32    11.27   1.543E+005    8.35E+004    1. 734E+O 04 7.286E+004 911. 20   25.80   8.347E+004                 1. 466E+O 04 3.870E+004 968.97    15.80   1.331E+005                 1. 251E+004  6.144E+004
  +     Am-241       59.54*   35.90   4.288E+004    4.29E+004   -2.919E+003   2.042E+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

[545]

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

Filename: 5456-A Report Generated On 6/7/2018 9:11:17 AM Sample Title B103202AFSWC075GD Sample Description SFP/TRANSFER CANAL Sample Identification 075 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy To lerance 10.000 keV Sample Size 7.070E+OOO M"'2 Sample Taken On 6/7/2018 9:01:00 AM Acquisition Started 6/7/2018 9:01:15 AM Live Time 600 . 0 seconds Real Time 601.0 seconds Dead Time 0 . 17 % Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 5/30/2018 Efficiency ID l .5M90DSFP 2IN [546]

Peak Analysis Report 6/7/2018 9:11: 17 AM Page 2

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

Detector Name: 5456-A Sample

Title:

B1 0 3202AFSWC075GD Peak Analysis Performed on: 6/7/2018 9:11:17 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 287- 311 3 01 .05 75.26 1.13 2.28E+002 91.46 4.51E+002 2 334- 346 339.21 84.80 0.45 5.69E+001 53.40 2.47E+002 3 951- 960 955.28 238.82 0.41 2.62E+001 24.32 5.38E+001 4 1400- 1416 1407.50 351.88 0.41 6.61E+001 22.92 2. 09E+001 5 2430- 2444 2436.45 609.11 0.96 3.80E+001 18.76 1. 70E+001 6 2638- 2653 2645.23 661.31 1. 68 5.43E+001 22.93 2.57E+001 7 4474- 4487 4480.79 1120.20 0 .39 1.34E+001 15.12 1.56E+001 8 4684- 469 8 4691.70 1172.93 1. 88 4.82E+001 14.60 1. 79E+OOO 9 5323- 5337 5330.31 1332.58 0 .62 3.64E+001 14.50 5.61E+OOO 10 5833- 5853 5842.67 1460.67 1. 28 1.30E+002 22.80 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 [547]

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Sample

Title:

Bl03202AFSWC075GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  .. ..... - ... .... ... ,r * - .. . . IDENTIFIED NUCLIDES          * " ~ "  * * * .. * * * * * " ,. ,.. * "" ~ I' Nuclide             Id                Energy     Yield        Activity            Activity Name         Confidence               (keV)        (%)       (pCi/M"2 )        Uncertainty K-40             1.000           1460.82*        10 .66    8.89541E+005        l .74109E+005 Co-60            1. 000          1173.23*        99.85     3.15119E+004        9.86937E+003 1332.49*        99.98     2.52280E+004        l.02536E+004 Cs-137           1.000              661. 66*     85. 10    3.1787SE+004        l.39539E+004 Eu-155           0.345                86.55*     30.70     4.48732E+004        4.30388E+004 105.31       21. 10 Pb-212           1.000              238.63*      43.60     1.80434E+004        1.70299E+004 Bi-214           0.733              609.32*      45.49     4 .00031E+004       2.03480E+004 1120.29*        14.92     5.74889E+004        6.48624E+004 1764.49         15.30 Pb-214           0.438              295.22       18.42 351. 93*     35.60     6.78293E+004        2.59164E+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

[548]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1.000 8.895410E+005 1. 741087E+OOS Co-60 1.000 2.848987E+004 7.110654E+003 Cs-137 1.000 3.178748E+004 l. 395392E+004 Eu-155 0.345 4.487318E+004 4.303875E+004 Pb-212 1 .000 l. 804337E+004 1. 702995E+004 Bi-214 0 .733 4.156980E+004 1. 941502E+004 Pb-214 0 .438 6.782926E+004 2.591638E+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

[549]

Interference Corrected Activity Report 6/7/2018 9: 11 :17 AM Page 5

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

Peak Locate Performed on: 6/7/2018 9: ll: 17 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Ene.rgy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.26 3.8081E-001 40.03 M : First peak in a multiplet region m = Other peak in a multiplet region F : Fitted singlet Errors quoted at 2 . 000 sigma [550]

Nuclide MDA Report 6/7/2018 9: 11 :17 AM Page 6

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Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC075GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec . Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

 +      K-40       1460.82*    10.66   1.852E+004    1.85E+004   8.895E+005   O.OOOE+OOO
 +      Co-60      1173.23*    99.85   6.610E+003    6.61E+003   3.151E+004   2.420E+003 1332.49*    99.98   1.105E+004                2.523E+004   4.588E+003 Nb-94       702. 6 5   99.81   1.531E+004    l.53E+004  -1.921E+004   6.961E+003 871.09     99.89   1.712E+004               -2.673E+003   7.792E+003 Ag-108m     433.90     90.50   1.880E+004    1.88E+004   7.900E+003   8.794E+003 614.30     89.80   2.403E+004               -6.666E+003   1 .129E+004 722.90     90.80   2.091E+004                2.974E+003   9.680E+003 Cs-134      604.72     97.62   2.329E+004    2.24E+004   9.919E+002   1 .098E+004 795.86     85.46   2.239E+004                2.662E+004   1.034E+004
 +      Cs-137      661. 6 6*  85. 10  1.850E+004    1.85E+004   3.179E+004   8.457E+003 Eu-152      121. 78    28.67   7.991E+004    6.53E+004  -6.493E+004   3.882E+004 344.28     26.60   6.531E+004               -5.101E+004   3.082E+004 1408 . 01   21.07   7.797E+004                4.124E+004   3.440E+004 Eu-154      123. 07    40.40   5.623E+004    4 .38E+004 -2.728E+004   2.731E+004 723.30     20.06   9.382E+004               -2.769E+004   4 .341E+004 1274.43     34 .80  4. 377E+004              -2.438E+004   1.925E+004
 +      Eu-155       86.55*    30.70   6.855E+004    6.86E+004   4.487E+004   3.321E+D04 105.31     21.10   1.154E+005                9.819E+003   5.616E+004 Tl-208      583.19     85.00   2.656E+004    2.66E+004   4.139E+004   1 .253E+D04 Bi-212      727.33      6.67   2.804E+005    2.80E+005   9.462E+004   1 .296E+D05
 +      Pb-212      238. 63*   43.60   2.691E+004    2.69E+004   1. 804E+004  l .252E+004
 +      Bi-214      609.32*    45. 49  2.738E+004    2.74E+004   4. 000E+004  1 .226E+004 1120.29*    14.92   1.047E+005                5.749E+004   4.654E+004 1764.49     15.30   1.309E+005                1.174E+O 05  5.825E+004
 +      Pb-214      295.22     18.42   l.056E+005    3.01E+004  -1.853E+OD4   5.036E+004 351.93*    35.60   3.007E+004                6.783E+004   1. 365E+004 Ra-226      186. 21     3.64   5.553E+005    5.SSE+OOS  -1. 838E+O 05 2.677E+005 Ac-228      338.32     11. 27  l .566E+005   7.69E+004   5.00SE+004   7.398E+004 911.20     25.80   7.686E+004               -5.284E+004   3.539E+004 968.97     15.80   1 .318E+005               4.357E+004   6.081E+004 Am-241       59.54     35.90   8.460E+004    8.46E+004  -2.279E+004   4.122E+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

[551]

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

Filename: 5456-A Report Generated On 6/7/2018 8:51:34 AM Sample Title B103202AFSWC076GD Sample Description SFP/TRANSFER CANAL Sample Identification 076 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/7/2018 8:40:00 AM Acquisition Started 6/7/2018 8:41:32 AM 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 5/30/2018 Efficiency ID 1.SM90DSFP 2IN [552]

Peak Analysis Report 6/7/2018 8:51:34 AM Page 2

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Detector Name: 5456-A Sample

Title:

B103202AFSWC076GD Peak Analysis Performed on: 6/7/2018 8:51:34 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 306 300.97 75.24 0.37 2.lOE+OOl 52.43 2.72E+002 2 333- 346 340.76 85.19 0.46 3.82E+001 55.93 2.70E+002 3 949- 959 954. 91 238.73 0. 70 3.00E+OOl 22.45 4 .00E+OOl 4 1177- 1187 1181 .18 295.29 0.97 2.54E+001 19.19 2.76E+001 5 1401- 1413 1407.63 351.91 0.43 3.99E+001 19.77 2.llE+OOl 6 2325- 2336 2330.60 582.65 0.77 1. 95E+O 01 14 .61 1 .35E+001 7 2427- 2444 2435.50 608.88 0.40 6.19E+001 21.54 l .61E+001 8 2639- 2652 2645.25 661.31 1.12 2.45E+001 14.85 9.52E+OOO 9 5321- 5334 5327.73 1331.93 1. 58 3.13E+001 12.03 1 .75E+OOO 10 5832- 5851 5841.58 1460 .40 1.47 1. 16E+O 02 22.24 2.36E+OOO 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 [553]

Interference Corrected Activity Report 6/7/20 18 8:51:34 AM Page 3

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Sample

Title:

B103202AFSWC076GD 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 7.91183E+005 l.66950E+OOS Cs-137 1.000 661.66* 85.10 1. 432 71E+004 8.86199E+003 Eu-155 0.346 86.55* 30.70 3.00347E+004 4.44142E+004 105.31 21.10 Tl-208 1.000 583.19* 85.00 1. 07704E+004 8.17529E+003 Pb-212 1.000 238.63* 43.60 2.06712E+004 l .58427E+004 Bi-214 0.437 609.32* 45. 49 6.51928E+004 2.40143E+004 11 20 .29 14.92 "1 764. 49 15.30 Pb-214 1. 000 295.22* 18.42 4.60832E+004 3.56303E+004 351.93* 35.60 4.09576E+OD4 2.13326E+OD4

       * = 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

[554]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1 .000 7.911830E+005 1 .669499E+005 Cs-137 1 .000 1 .432706E+004 B.861994E+003 Eu- 155 0.346 3.003474E+004 4.441420E+004 Tl-208 1.000 1.077039E+004 8.175289E+003 Pb-212 1. 000 2.067115E+004 1.584274E+004 Bi-214 0.437 6.519276E+004 2.40142BE+004 Pb-214 1. 000 4. 231015E+004 1.830290E+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

[555]

Interference Corrected Activity Report 6/7/2018 8:51:34 AM Page 5

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

Peak Locate Performed on: 6/7/20 18 8: 51 :33 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 75.24 3.4986E-002 249.77 9 1331.93 5.2083E-002 38.49 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [556]

Nuclide MDA Report 6/7/2018 8:51:34 AM Page 6

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Detector Name: 5456-A Sample Geometry: Sample

Title:

B103202AFSWC076GD 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 )

 *I     K-40       1460 . 8 2*  10. 66  8.221E+004    8.22E+004   7.912E+005   3.185E+004 Co-60      1173.23      99.85   2.328E+004    2.33E+004   2.763E+004   1. 075E+004 1332.49      99.98   2.351E+004                2.062E+004   1.082E+004 Nb-94       702.65      99.81   1. 571E+004   1. 50E+004 -1.725E+003   7.163E+003 871.09      99.89   1.496E+004                1.083E+003   6.716E+003 Ag-108m     433.90      90.50   1.778E+004    1. 71E+004 -8.833E+003   8.284E+003 614.30      89.80   2.773E+004               -5.042E+003   1.314E+004 722.90      90.80   1.705E+004               -4.127E+003   7.753E+003 Cs-134      604.72      97.62   2.399E+004    1.92E+004  -3.345E+003   1.133E+004 795.86      85.46   1.919E+004               -1. 378E+003  8.737E+003
 +      Cs-137      661.66*     85. 10  1.225E+004    1.22E+004   1. 433E+004  5.332E+003 Eu-152      121. 78     28.67   8.289E+004    6.37E+004  -4.415E+004   4.031E+004 344.28      26.60   6.367E+004               -6.609E+004   3.000E+004 1408.01      21. 07  6.608E+004               -1. 866E+004  2.845E+004 Eu-154      123.07      40.40   5.924E+004    4 .69E+004 -6.464E+003   2.882E+004 723.30      20.06   7.823E+004               -3.050E+003   3.561E+004 1274.43      34.80   4.686E+004                2.549E+004   2.079E+004
 +      Eu-155       86.55*     30.70   7.273E+004    7.27E+004   3.003E+004   3.530E+004 105.31      21.10   1 .208E+005              -1. 055E+004  5.888E+004
 +      Tl-208      583.19*     85.00   1 .207E+004   1 .21E+004  1 .077E+004  5.289E+003 Bi-212      727.33       6.67   2.200E+005    2.20E+OOS  -1 .558E+OOS  9.942E+004
 +      Pb-212      238.63*     43.60   2.411E+004    2.41E+004   2.067E+004   1.112E+004
 +      Bi-214      60 9 .32*   45 . 49 2.836E+004    2.84E+004   6.519E+004   1. 275E+O 04 1120.29      14.92   1 .496E+005               1. 411E+O 05 6.899E+004 1764.49      15. 30  1. 459E+005               1.495E+005   6.572E+004
 +      Pb-214      295.22*     18.42   5.372E+004    2.85E+004   4.608E+004   2.440E+004 351. 93*    35.60   2.847E+004                4 .096E+004  1. 285E+004 Ra-226      186.21       3.64   5.879E+005    5.88E+005   S.032E+005   2.840E+005 Ac-228      338.32      11. 27  1.645E+005    7.69E+004  -2.262E+004   7.794E+004 911.20      25.80   7.686E+004               -4.523E+003   3.539E+004 968.97      15.80   1.368E+005                1.223E+005   6.330E+004 Am-241       59.54      35.90   8.828E+004    8.83E+004   3.247E+003   4.306E+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

[557]

ATTACHMENT 7 EBERLINE ANALYTICAL REPORTS [558]

EBtRI.INE /\NAL YT I CAL COhr'OR.~:10,' 601 SCARtOf:{, 1/0:\,J 0'\K R!:>Gi:'. T!:1~Nr.SSEL: ;,7;,"o

                      ~.3EHVICF.S                                                      Pl*IONE (8{>5) l,.fll--d;iP.,i f.A.X (86G) '*-C3* lt{,?I EBS-OR-43935 July 11, 2018 Patricia Giz.a Zion Solutions, LLC 101 Shiloh Blvd Zion, IL 60099 CASE NARRATIVE Work Order# 18-06057-0R SAMPLE RECEIPT This work order contains eight solid samples received 06/14/2018. Samples were analyzed for Total Strontium, Tritium, Nickel-63 and by Gamma Spectroscopy.

CLIENT ID LAB ID B 103202AFRWC004CV 18-06057-04 BI 03202AFRWC027CV 18-06057-05 B 103202AFRFC0072V 18-06057-06 B 103202AFRFC057CV 18-06057-07 B 103202AFRFC06 l CV 18-06057-08 B 103202AFRFC038CV 18-06057-09 B 103202AFRFC052CV 18-06057- l 0 B 103202AFRFC059CV 18-06057-11 ANAi .YTICAL METHODS Total Strontium was analyzed using EIChroM Method SRWOI 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 [559]

ANALYTICAL RESULTS CONTINUED IOTAL STRONTIUM Samples were prepared by digesting with acids and diluting as appropriate. Aliquots were removed from dilution followed by adding Strontium recovery carriers to the samples. Chemical separations were conducted using selective extractions. Strontium precipitated was mounted on tared filter media. Chemical recovery was determined by Strontium carrier mass determinations. Samples were counted by gas flow proportional counting and corrected for Yttrium-90 ingrowth. Samples demonstrated acceptable results for all Total Strontium analyses. Strontium-90 results are 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 an acceptable relative percent difference and normalized difference. 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 sti1ls. A portion of each middle distillation fraction was transferred to a liquid scintillation vial and cocktail was added. Samples were then counted by beta liquid scintillation. Samples demonstrated acceptable results for all Tritium analyses. The Tritium method blank demonstrated an acceptable result. Results for the Tritium duplicate demonstrated a high relative percent difference; however, nonnalized 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 dilutions and were placed in an appropriately sized beaker. 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 an acceptable relative percent difference and nonnalized difference. 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/aliquot of each homogenized sample to a standard geometry container. Samples were counted on High Purity Germanium (HPGe) gamma ray detectors. Page 2 of 3 [560]

AN1 LYTICAL RESULTS CONTINUED QAMMA SPECTROSCOPY CONTINUED Samples demonstrated acceptable results for all gamma-emitting radionuclides as reported. Some results demonstrated slightly high method detection limits. Some samples demonstrated results that are greater than the method detection limit. These results are reported from the Canberra Gamma Apex "Nuclide MDA Report and are not positive. These results are qualified as non-detect (U). The method blank demonstrated acceptable results for all radionuclides as reported. Results for the Bismuth-214 and Potassium-40 replicate demonstrated an acceptable relative percent difference and normalized difference. Results for the Cobalt-60 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 1 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 _____dcsignee to be accurate as verified by the following signature. M.R. McDougall Laboratory Manager Date: 7/11/2018 Eberline Analytical wanls and encourages your feedbuck regarding our performance providing radioanalyticul services. Please visit http://eberlineanalytical.com/ to provide us with feedback on our services. Page 3 of3 [561]

Printed: 71111201B 1:04 PM Page 1 of 12 Report To: Worl< Order Details: Patricia Giza SDG: 18-06057 Eberline Analytical Final Report of Analysis

                                                                                      -*~***"' - Zion
                                                                                                  ------Solutions 101 Shiloh Blvd
                                                                                                                       .. *-*--* **-*     ~  *- -**
                                                                                                                                                                                    -- Analysis. Category: _

Purchase Order.

                                                                                                                                                                                    ...*-** ----**-   --                   677118 ENVIRONMENTAL ________ - - - *-*-**--*-

Zion, IL 60099 Sample Matrix: SO - Lab Sample Client Sampi. Receipt Analysis Batch Report ID Type ID Date Date ~ ID Anatyte Method Result cu CSU MDA Ot;altfier Units _!~~~- _ LCS KNOWN _ *--* _ _ _ _ *- . 0611"!~0.0:IJO ~1~8-~~0;!_ _1!:~7 ....... T_ri~-- . __LANLER-210Modlfia<1 2.26E+02 8.12E+OO '-* _ £:?ila _ _1 ~ ~ 1

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~ - o e ~. ~TRG -----                           a1cmowRFcoonv                       ~ 06/05~8 i2:39 =-- ~ ~ ~ 5 1 2 0 1 a - ~ ~ : , *-..                         ~T-riii~~~ _LANL eR-210                  M~l-          1.22e-01 ~ -     3:03i~a: -         a-:-03E~D __ s ~            _:..=_ l!.. -~ ~___-;cug~----
...2..8-06057-07 : _ TRG                __ ~~2AFRFC057CV                                  05/05/18 10:15 ' .*6/1-41'2018 , 8(15/2018 __ 18-06057 *. ___ Tfffium .... _ LANL ER-210 Modified                        i   -2.01E+OO .       2.96E..OO _ _. . 2.96E+OO           5.28E<<l0 _      2!._ -* __ -~i!!!_ _

_ 18-06057-08_1 TRG _.:.. ~10320~~~CV .1--. 0~51~~ __- tl/1412018 _ 6/15/2~ 18-0605~.. __T_'!!.'u!!!__.* -~~R-210Modlfled _ l_2.36E+DO ----~:~:!_E_:_~-. _3:~~:_~ 5.39E-t<l0 U _ !_?~~-- 18-06057-09 :__ TRG __ B103202AfRFC038CV _ 06/05/1814:20 6/1412018. 6/1~~~-!B-0605~- .. _.~!'.':'_~. _ ~LER-210Modified i 5.53E--01. * .. 3.09~~':- --~~-'-00 . 5.33E+OO __ * ~-. ___pC_!!g__ _ 1&-ll6057-10 _~~----B103202AFRFC052CV ~1808:~ - ~~018. 6/15/2018 , ~ ** ___ :r~m LANLER-210Modilied _..;... ~~ - -~-~~E~- 3.17E+OO---'- 5.40E+OO ___u ___ pC~g ,..*. --2~~_!-.!!.__TRG - _!:1~~02AFRFC059CV 06f05/1809:~ -~.:1~ _!!1~-~!l-06~_ .. ___Tri)iu~-* l.ANLER-210Modilied . O.OOE+OO 3.01E+OO :2.01e:~_ _:-23E+OO -- u_ . _pCi/g -* ,_18-06057-01 :----*- LCS

                                          -. - -KNOWN 06/1411800:00 6114/2018. 6/1512018 ' 1S-06057
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i~~7-~-:~G _ B103202AFRFC052CV 06/05/1808:30 6/1412018 6/15/2018 18-06057 ____ Nlcke1~3 _ ~ASTM3500-NiModified :__.!_~E+OO . __1.:_~+00 __ _1~~ _2?9E+00 U * ~~9 * *. 18-06057-11 TRG B103202AFRFC059CV 06/05/'18 09:27 6/14/2018 : 6/1512018 18-06057 Nickel-83 ASTM 3500-Ni Modified 1.44E+OO 1.71E+OO 1.71E+OO 2.S7E+OO U pCl/g CU-Counting Uncertainty.CSU-Combined Standard Uncertainty (1-slgma);MDA=Mlnlmal Detected Ac:tivlty;LCSmL.aboratory Control Sample;M61.2Blank;DUP~Dupllcate;TRG---Normal Sample;OO=Ouplleate Orlglnal;U=Non-datect EBERi_lNE EBERLINE ANAL YTl CAL CORPORATION _ __.:_:....::._;_;__________________

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

[562]

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

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                          -~     LCS LCS
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                              '~\                                    ANALYTICAL                                   601 SCARBORO ROAD OAK RIDGE, TN 37830                                              865/481-0683                    FAX 865/483-4621 et                                                                                                                                   [563]

Printed: 7111n0181:04 PM Page3of12 Report To: Patricia Giza 18-06057 Eberline Analytical ,-, -- -*-**~w- .. --*. ------- ** * **** *- SDG: Final Report of Analysis Zion ---

                                                                    ...... ._.. Solutions 101 Shiloh Blvd
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                                                                                                                                                                                                               --* .,677118
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ENVIRONMENTAL Zion, IL 60099 Analysis Cetego,y: Sample M-;trix;-*-* SO - *-*- **- * ** **-* ** - ** *** * - -- * ** - --- Lab Sample Client Sample Receipt Analysis Batch Analyt& Method Result CU CSU MDA *. Qualifier . Report 10 Type ID Dal'& Date Date ID Units CU-Counting Uncertalnty;CSll=Combined Standard Uncertainty (1*igma);MDA=Mlnimll Omicted ActJvlty;LCSQLabontory Control Sample;MBL=Blank;DUp..[Juplicate;TRG-Normal Sample;!XFDuplica.te Origlnal;U=Non-deteet EBERLINE I . . __RUNE ANALYTICAL CORPORATION

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

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Printed: 7/11/2018 1:04 PM Page4of 12 Report To: We'* Oroer Details: Patricia Giza SDG: 18-06057 Eberline Analytical Zion Solutions Purchase Order: 677118 Final Report of Analysis

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

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"""tS-06067-03 , DUP B10320WRWC004CV-**----05i31/1815:10 ; 611412018' 6/1-4/2018 1&-06057 ~-* Cobatt-60-'---EPA901.1Modified *-;, 1.00E-Ot. - 7 . 2 1 ~ ' 7 ~ - 1 ~ 1

• U -pCi/g *

-i6-06057 - -OUP-' ~ 0 2 A F ~ ~ - --05/31/1815:10 i 6/14/2018 .6/14/2018 :1s':oe057: Cesium-134 EPA901.1 Mod,fied ' -6.6SE-05 -,-4.62E-02 4.62E-02 1.13E-01 u .- pCl/g * *-

~?::.03--i---Y~*

B103202AFRWC004CV

                                                                   -    *-~-

05/3111815:10

                                                                                            ; 6/14/2018     6/1412018
                                                                                                                                  .. _    ,_ _ _ _ .,. -                                                                                                                             18-06057_: .~~~E._ ...... EPA901.1 Modified
                                                                                                                                                                                               -- '      - - - ~ - * - - - -* - - - - -
                                                                                                                                                                                     ! 3.76E-02 ; 6.76E-02              6.76E-02      1.17E-01   ._u_ _.

pCt/g _ ~ 0 5 ~ *. : ~ P_ _!1~02AFRWC004CV _ -.-:==- ~111815-;10-76/1~

• 6/14~018 18-08057 ~~~~ EPA90Ll Modified _-J --t.27E-O~ -- 2.92E-01 :- -2::S2e.01 2.35E-D1~ _ ~ __ **-- pCi/g _

18-06057-()3 ; DUP , B103202AFRWC004CV 05/31/1815:10 : 6/1,4/2018: 611412018 . 18-06057 Europium-154 EPA901.1 Modified I -8.90E-02

• 2.02E-01 . 2.02E-01 1.19E-01 .--U

_ _. -*-pCi/g _ 18-06057-03

• 18-06057-03 OUP DUP
• B103202AFRWC004CV * -*05/31/1815:10 B103202AFRWC004CV _ _ _ ~15~1412018 : 6/14/2018_ ..2!:!;_06~*.' ~olmi~~~ '-- EPA 901.1 Mad_!!i:8~ _ . _ ~ _ *

                                                                                                                                            --- ** --       - -- -***----* --~--1.41E-01 6/1412018 ** 6/1412018

• 18-06057; Europlum-155-EPA901.1Modlfled

                                                                                                                                                                                             ----*--**     1.11E-01 ' t.11E-01

_!_:?)~ _ 1.01E-01 2.18E-01 . U 1.03E-01 __ u______ ~ pCi/g 18-06057-03' DUP B103202AFRWC004CV 05/31/1815:10 6114/2018 6/14/2018: 18-06057 : Jodlne-129 EPA901.1Modllied  : 3.55E-02 8.82E.02 ~8~E-02_:_.~~ - ~ _ ; ~ g - 18-06057-03 DUP . B103202AFRWC004CV - * -

• 05/31/1815:10 : 6/1412018. 611-412018
• 1&-06057
• P01assium-40
• EPA901.1 Mod'rfied 6.41E+OO 1.38E+OO 1.42E<{)O B.35E-01 ___ .... : pC~.

~057-03 1_ DUP___::Ji103202AFRWC004CV-*-- - -05f.JW~-6fW2018;&Mi2018 - ~ 7 i Ma~~~~PA901.1Mod~ __ .* 6.6SE-~-=5.1)E-02. 5.12E-02 2.07E.01 u. _ ._ __E~~- 18-06057~~: OUP 01~~~ ~111a1s:10_ "!1'~~1412018 ._18-06057 ; Nioblum-94_'--~1.1Modiffed~9aE-02 :_ 6.67&02 _. 6.67E-02 ~~ ~ . ~C~L. _1a-~-~- '. -~p B103202AFRWC004C~-- - - 05/31/1815:10 ! 6/14/2018

• 6/14/2018 18-0~-*- -~a~210 EPA901.1 Modified_;_ 2.13E~_:_1_;22E+OO 1.23E+OO -- 1.86E+OO u_ __pCl/g 18--06057-03 ,__ __DU!:__ B10~FRWC004CV . 05/31/1815:10 : 6/1412018: 6/14/2018 _1e~_:_ .~~d-21~*-'- EPA901.1M~: 4.3~J*.* __1,41~' 1.43E.01 . 4.21E-01 _ _ _ _. __ PC~_

18-06057-03 : DUP B103202AFRWC004CV . _,__-05/31/1815:~.

• 6/14/2018 .~~1~-~06057 * - ~ _ '- -~-~ocftfied i ..2.:59E-01 1.97~1 2.01E-01 _2:_88~~1_-'___ * - ' . _1.Ci/g .. _

18-06057-03. \ DUP . B103202AFRWC004CV _05131/1815:10 ; 6/1412016 . 6tl412018 1!!-06057 : Promethium-145 EPA901.1 Mocfdied 1 -1.28E-02 ; 1.34E.01 1.34E-01 1.73E-01 U pCi/g 18-06057-0J;DUP- B103202AFRWC004CV '-~~~15:10

• 8/1412018' 6 1 1 ~ ~ ~ 7 , Radium-226 EPA901.1 Mocfdied  :....!.4BE-01 . _2.19E-01 2.22E-01 . 3.91E.Q~ : _ _ _ _ pCilg _

18-06057-03 DUP -, B103202AFRWC004CV 05131/1815:10; 6114/2018. 6/14/2018 18-06057' Antimony-125 EPA901.1~odified 1 1.16E--01 1.54E.01 , 1.55E-01 2.64E-01 U pCi/g ~osi.oJ: ~131e32o2AFRWC004CV- -- 05,131/1815:10 ~ 1 8 ' 6/~8-1~7_:*__T'2orfum-234 ~~~~ - ;_1.59E*OO . __!;_72E+<JO : ~ - J 87E+OO_ _ t; pCi/g__ _ -ra:oeo~'.ouP-, B103202AFRWCD04CV_____ 0&131/1815:10 6/14/2018' 6/14/2018 16-06057 . Thelfium-208 EPA901.1 Mocflfied

                                                                                                                                                     - - -EPA901.1
                                                                                                                                                                 - - - -Macllfled
                                                                                                                                                                           - - * --*------i--

3.8ZE-01 2.52E-01

• 2.53E-01 4.51E--01

                                                                                                                                                                                                                                     -5.11E-01 U
                                                                                                                                                                                                                                       - - - -- U- -- - pCl/g pCilg 18.()6057-03 ,   DUP       B103202AFRWC004CV                               05/31/1815:10     8114/2018, 6/1412018         18-06057         Urantum-235                               ; 4.77E-01          5.53E~1 :     5.54E.01 CU=Counting Uncertainty;CSU=Comblnad Stl11ncl11rd Uncertainty (1*igma];MDA*Mlnlmlll Det11eted Activlty,LCS=Laboratory Control Sample;MBL=Btank;DUP=Duplicate;TRG=Normat Sample;DO-Duplieate Original;U=Non-detec:t EBERLINE                                                           EBERLINE ANALYTICAL CORPORATION
                 ~                          ANALYTICAL                                  601 SCARBORO ROAD OAK RIDGE, TN 37830                                      865/481-0683                  FAX 865/483-4621

[565]

Printed: 7/11/2018 1:04 PM Page5of 12 Report To; Worf< Order Det8ils: Patricia Giza SDG: 18*06057 Eberline Analytical ....... ---*-***--- _.. .-- .. _.. * *-- _____ _ __ _ _ _ _ _ __ *. f.'t1_'!3_h1!._s__e__ q_~1?_-** ______ 677-1.:1!_______ . __ --**-- __________ .......

                                                                 . ---Zion Solutions ,,_,

Final Report of Analysis --~ .... 101 Shiloh Blvd

                                                                       ---------.                                *- .. ****-- __ -- ----- __ Analysis Category:.                                                  __ENVIRONM~TAI::_ __ .... ___________ ... _

Zion, IL 60099 Sample Matrix: SO 13-06057-04 I DO B103202AFRWC004CV 05/3111815:10 6/1-412018 : 6/14/2018 18-06067 . Actlniwn-228 EPA901.1 Modified 3.94E-01

• 3.02E-01 3.02E-01 5.50E-01 U pCi/g

                                                                                                                                                                                                               ~.91E~ ** 7.03&02 - 7.03&02                                                         U *-

18-06057-04 I 18-06057-04 ; DO  : B103202AFRWC004CV DO _ _ _e"'io320iAFRWC004CV"- . * .. - - 05/31118 15:10 : 6/1412018 , 6/14/2018 tisiiine 1s:10- 6/1412018- 5/14/2018 18-06057 ' Silver-1~ - 18-06057 : __!.~'. EPA901.1 Modlfi~ Amertdum-241 _3P~!O~~-~ifl~ . *_- :1 :-26e"'.o( 1.46E-01

                                                                                                                                                                                                                                                            --9.74E--02 ---*

--,A6E-01 -~&~!._ ---=-~:~~ .*-. -*pCi/g pc;;;-*--

18-06057-04 , . DO _ _ ~~~C004CV __ *- _ _ 05/31/1815:10 : 6/14/2018 _ 6/14/2018 Barium-133 EPA901.1 Modllled 6.15E--02 4.76E.()2 4.77E.()2 1.72E-01 U pCilg 18-06057*04 ! DO 06057-04 . - - - - - - - - * --- --- --- e1032-02AFRWCD04CV O:i/3111e 15:10 '. 8/14/2018 6/14/2018 1s.osos1

                                                                                                                 . ***- ---  --**----**- - - - - - M~difted-Blsmuth-214                EPA.sou
                                                                                                                                                                                      ..... _.             .* "s.ii1i--01 ** *. 1.ne-01 *: 1.01e.o1 4.13E-01
                                                                                                                                                                                                                                                                                --                 ------pe~g---             -
                .__DO        B103202AFRWC004CV                    05/31~12...J._61~_6114/20!!._ .                    !.~~        ~*!!...SO                       -~A!?l-.~-~od~- - ,---~~~ -                                     6.82E-02 i_ 6.82E-02            1.0~~::?!.____ --~-- ___ pCilg

~057-04 i _E£...._ B103202AF~~---- _05!3111815:to : 6/1~~ _!il1~018: 1 ~ 7 : _ (;e$io.m--1~-- -~~_!l~~~d __ 2!;1~~2-- ~53E-02_' 4.53E-02 1.14E-01.___ IJ_____ pCilg __ 18-061)57-04 . 00 B103202AFRWC004C~--- _ _ ~513111825_:!0 , 6 1 1 ~ . 2 _ ~ ~ ~ 7 Ce$ium-13~--~!°A_90~.1-~~~ _ . 2-1_!§*0~-' 8.01E--02 , ~~- ~E_:O~- ___u____ _pC~ 18--06057-04 00 B1032D2AFRWC004CV 05/31/1815:10 . 6/14/2018 6/14/2018 18-06067 '. Eurapiurn-152 EPA901.1 Modified -6.95E-02 1.66E--01 1.68E-01 2.53E*01 U pCi/g 18-08057-04 r D0- 8103202AFRWC004CV -05/31/1615~10 ': 6114/2018 , 6114/2018 .tS-06057:Eurqiium--154 -EPA901-:;-;o~- ' .-1-~25~1 . , "io\e-01 '. 2.01E-01 _ 1.isE--01" " =-u--_~-:-:-_ pcvg*:~ 18-06057-04 DO B103202AFRWC004CV 05131/1815:10 ; 6/14/2018 6/1412018-18-060S7 --E~~55 '- EPA901.1 M~~ -:-- :3~9E-02 'T.34E-01 ' 1.34E-01 2.1-'IE.()1 u pCilg 18-06057-04!-~ *, - Bt03202AFRWC004CV*------ - 05/3111815:10 . 6114/2018 6/1412018 18-06057 t Holrniurn-166m EPA 901.1 Modj,;""d * * -- i."22&02 ** - Ll9io1°* Ll9E*01

• 1.07E- - U- - - p:;i/g 1-----4-------------

18-06057~4 DO

                                                ----*._.. L-       -* ---*

B103202AFRWCD04CV - - -- _.__05!31/1815:10 6/1412018, 6114/2018 18-06057 lodine-_~,_-~A9~1_:1Mod~--+-~-6E-02 _ 8.89E-02 :_!:OOE--02_ _ 1 ~ - - ~ -*- pCilg _ 18--06057-04 DO B103202AFRWC004ty_____ . _ ~ ~ 15:10_ 6/14120.!!_ 6114/2018 18-0605~~~~111-40 _ ~EPA~~~~~ified __ :--5.3.3E+OO . 1.43E+OO 1.45E+OO 1.50E~---* _ _ _ p:;ilg _ ~~6057-04  ! DO 81~~~004CV- . __ -~815:10 . 6/14/20~ _611412018 __ 18-06057....:.._M~ganes&-54 EP~~~d~ed- __ 1.~~-,-6.:.496-02 : 6.49E-O~ ~~ _ ---~--__L:;~- 18-06057-04 DO B103202AFRWC004CV 05/31/1815;10 . 6/14/2018 6114/2018 18-06057 Niobiurn--94 EPA 901.1 Modified ' -1.31E-02 . 6.00E-02 : 6.00E-02 . 9.11E-02 U p::t/g 16-08057-04 Do B103202AFRWC004CV

                                         - - ---  - --L--- -----

05131118 1s:10

• 6/1-412018 - e,14/20,0 1a.06057____Lead-210 _._.EPA901._1M~ffied - *; 1.1ee+oo

                                                                                                  .              . . - - _____.........__._...        .... I..--,...._.............. ~

1.40e+oo "'"'uoe+oo -

                                                                                                                                                                                            ....- - - - ~ ... - - - - * -- - - - - - - - -                   . -
                                                                                                                                                                                                                                                                 ~;oo *
                                                                                                                                                                                                                                                                                                - u - - pCiia-18-06057-04 1     DO       B103202AFRWC004CV                    05131'18 15:10 ' 6/1412018: 6/1412018 : 18-06057 .                     Lead-212                 EPA901.1 Modified                             3.27E-01         1.15E-01        U6E--01     ,   2.84E-01                                   .         pCi/g

~~i~o---B103202AFRWC004CV--*-* 0513111815:10 ieiwi,1a:* -8/14/201S. 18-06057' Laad-214 EPA901.1 Modified * ,-6~~1-,~ . 1.87E.01 3.76E-01 . pCi/g - ~57-04 DO B103202AFRWC004CV D5/3U1~6IW2018-* 15/1412018 1&-06057 *: Promelhlurn-145 ~-901.t Modlfi~- .; -1.31E-=01 : 1.41E-01 1.41E-01 1~59E-01 --*u- - ~ -

6/14/2018 *. ~ 8 ~~ -Radiurn-226 18-05057-04 DO B103202AFRWC004CV 05/31/1815:10 EPA901.1 Moolfied

                                                                                                                                                                 ---*-**----,-----                          : e.91E-01 : 1.77E-01 ' 1.81E-01 4~,i'iii;'-*-- .
                                                                                                                                                                                                                                                                                                                     -~ -

18-06057-04 DO B103202AFRWC004CV 05/31/1815:10 , 611412018

• 6/1412018 . 18-06057 Anttmony-125 EPA901.1 Modified

~-27E-02

                                                                                                                                                                                                                                               - ----- --- --- --pCl/g 2.03E--01 : 2.!l3E-01           2.92E-01                            U

,_1.8-060_57_-04_'._~ ~ B103202AFRWC004CV 0!5131/1815:10  : 611"ll2018 ; 6/1412018 . 18--06057 Toorium-234_-I-_ _ EPA 901.1 Modified 2.18E+OO 1.40E+OO

• 1.40E+OO 2.06E+OO U pCl/g 18-06057-04 1 DO B103202AFRWC004CV 05/31/1815:10 ; 6114/2018" 6114/2018 18-06057-: -~;;;:.208 EPA(l01.1 *M.:;-dlfi~ *=*-~;- 3.66E~ 2.04E--Ot 2.05E.()1 3.31E-01 ._ pCi/g _

18-06057-04  ! DO ---B-10_3202AF ___R_WC_004C __v_______ 05131/1815:10 : 6114/2018 ** 6/1412016- 18-06057

• Uranlum-235 EPA 901.1 Modified ' -7.0BE-02 7.67E-01  ; 7.67E-01 5.34E-01 U pCilg CU=Counting Uncenalnty;CSU=Combinec! Standard Uncertainty {1-eigma):MOA=Minlmal Detected Activity;LCS=laboratoTY Control Salnpk>;MBL=Blank;OUP,,Oupllcate;TRG=Nonnal Sample;OO=Dupllr;ata Original;U=Non-detect EBERLINE EBERLINE ANALYTICAL CORPORA TIO!\'.

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

[566]

Printed: 7111/20181:04 PM Page 6 of 12 ReDOII.To: !Mm- Order De/aHs: Eberline Analytical Patricia Giza Zion Solutions

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

18-06057 SDG:.... ----------- .., .. ____ Purchase -Order: ---- 6n118. _ _ *--****-* .... __

                                                                                                                                                                                                                                                             .. ,.............. ~

Final Report of Analysis ..~!_Q_1 __Sh_H~_h:...:B=l;..::.vd.::..______ -**- ___ --** _ .. Analysis Catefl<)ry: ENVIRONMENJ:.~!::.___ ---*** Zion, IL 60099 Sample Matrix: SO Lab  : Sample Client Sample R*celp? Analysis Batch Analyle Method Result cu CSU MDA . OLlalifter . Report Unit& ID Type ID Date Date

• Date 1D

~ ----- TRG 18-06057-05 18--06057-05 ; TRG B103202AFRWC027CV _B_!.~~~£"- __

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

05/31/1814:50 . 6/1412018 ' 6,11412018 . 18-06057 .* Aetinlum-228 _!]5131118_14:50

• 6/1412(118 : 6f1412018 . 13-06057 *- S11\/er-108m _

                                                                                                                                                                                       ..* §~A90.1..:_1_Mod"died_,.* 2~E-02 .~.13E-O~--- 4.13E-01 __

EPA901.1 Modified  : -1.77E.02 ' 1.18E.01 ' 1.16E-01 6.71E-01 1.24E-01

                                                                                                                                                                                                                                                                                                          .      U U.
                                                                                                                                                                                                                                                                                                                        . pCi/g pCi/g -

18-06057-05 '. 18-06057-05 TRG TRG B103202AFRWC-027CV B103202AFRWC027CV 05/31/18 14:50 05/31/18 14:50 6/14/2018 6/14/2018

                                                                               ------ **---* -6/14/2018 6/1412018
                                                                                               *--         .-----~

__ __ 18-06057 Americium-241

• _,. 18--06057 - ---*
• EPA 901.1 Modified -J. -4.08E-02 ! 2.02E-01
• 2.02E-01 Barium-133 .......EP.b:9<i,. ,i".;i;;-ciified. __:.. 7.sae-02 _: 1.S-tE-02
• 1.55e:oi- .usE-:0,---u- -~;,g-* .

2.62E.01 U

• pCi/g *-

~ 6 0 ~ : . TRG B103202AF~WC027CV_ _ _ _ ,._~~~;~- . ~1412018; 6/14/2018 . 1B-06tl57_:~is~~4 '-* __5PA~~~odifled - *

• 4.70E-01 . 3.06E-01 -~*0!~1_ _:i~3~~ _. _':I__ ---- p~i/g 18-06057-05 ._TR~- B103~'VC027~--- -~~~~- 6/14/2018 6/1412018 1 ~ _ . __ cobatt~-- -* EPA901.1 Modified '. 9.0SE-03 1.12E-01 1.12E-01 1.02E-01 U pCilg

-8.19E-02 ~E-01 ~ 1.04E.01 ..

18-06057-05 18-06057-05 ; TRG TRG B103202AFRWC027CV 05/.31/1814:50 6114/2018 6114/2018 18--06057 . Cesium.134

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

B1~02AFRWC027~-- - - ~_!11814:50 - ~4/2018 a 6/14/2018 __...!_B-~.:_7___ _ ? ~ - __E~A.901.1 M~~- i -~02~~E-0..2__.~_..2.;3~1- _ EPA901.1 Modified 1.55E-01 1.89E-01

                                                                                                                                                                                                                                                                                                               . U
                                                                                                                                                                                                                                                                                                          *.* --~ _ ._

pCUg .*

                                                                                                                                                                                                                                                                                                                             ~C:"~--

18-06057-05 TRG 81032()2AFRWC027CV 05/3111814:50 : 6/1412018 ' 6/14/2018 18-06057 Eurnpium-152 EPA901.1 Modified . -2.70E-03 . 3.99E-01 : 3.99E-01 3.67E-01 U pCi/g 18-06057-05 : TRG

• B103202AFRWC027CV

                                                              .-i,........-*-----              --*

05131/1814:50 . 6/14/2018 , 6/14/2018 . 18-06057 . Europium-154 i--- - * - - EPA901.1 Modified

                                                                                                                                                                                                                            . 2.31E-01 3.04E-01 . 3.04E.01 1.91E-01
                                                                                                                                                                                                                                                                                                       - * , _ _ _ _ _, _ ~ - ' * - - -

U pCi/g 18-06057-05-*, TRG B103202AFRWC027CV - t -

• 05/3111814:50 : 6114/2016 . 6/1412018 : 18-06057 ' Europlum-155- ~ EPA901.1 Modified  : 1.22E-01 ' 2.29E-01 . 2.29E.01 3.13E.01 U ' pCilg -

 ------- -                                           - - _ ........ *--i.---          - --- - - - -                          - - - - * - * - - - - - - -*---~* ---*--*-*---------- - - - * - - - - _....._______, .--... - - * - - - -

18-06057-05 ' TRG B103202AFRWC027CV 05/31118 14:SO 6/14/2018 . 611412018 . 1$-06057-'- Holmium-166m EPA 901.1 Modified , -4.93E-02 1.71 E-01 1.71E.01 1.51E-01 . U pCl/g 1 ~ *: -TRG--B1.03202.AFRWC027CV 05/3111814:50 . 61'1412018 611412018

• 18-06057. lodine-129 EPA901.1M~--6.34E-02 -- 1.08E..01- , - ~ - 0 1* **-~54E *--u-- --pCVg __ _

~6057-05            .* TRG        - B103202AFRWC027CV - - - ._05/31f1814:50                   . 6/14/2018 : &1412018 . .18-06057                  Polasslum-40 -- EPA901.1 Modified: 5.28E+OO :- 1.84E+OO .                                                                   1.86E+OO       2.16E+OO --- - -             -pCi/g- -

18-06057-05 . TRG B103202AFR~C027CV

                                                                            *-----t 05/31/1814:50     6/14/2018 6/14/2018 18-06057-~~~ . ~A~1.2.~o~-.~E-03 ; 1.09E-01
                                                                                                                                                                                                                                                                       . 1.09E~1- 1 . 7 0 ~ - ~                         .

pCi/g 18-06057.05 '. TRG __ _!3~03202AFRWC027CV 05/31/1S 1-4;50 : 6114/2018 ' 6/14/2018 : 18-06057 . N i o ~ - EPA901.1 Modified , 2.49E-02 '. 1.06E-01 1.06E-01___ _~ ~ - - . _u__ pCi/g 18-06057-05 r TRG B103202AFRWC027CV 05/31/1S 14:SO '. 6/1"412018 : 6/1412018 : 18-06057 Lead-210 EPA901.1 Modl!lecl 1.50E+OO . 1.60E+OO 1.60E+OO 2.66E+OO U pCi/g _!.8-06057-05 * . -T~B103202AFRWCD27CV- ---** - 05/3111814:50 ; 6/1412018 efw201's°"18-06057 - Lead-212** ,__.EPA001~1M;;;iffied " **4.59E-01 1.54E~'._-. : ~ ~ - - ~ ~ ~ - U . pCilg _ 1 18-06057-05 TRG 8103202AFRWCWCV- - ---- - ..... 05131/1814:50 ' 6/14/2018: 8/1412018: 18-06057 Lead-2H ~ EPA901.1 Modified 6,77E.01 2.32E-01  : 2.35E-01 4.24E-01 pCl/g 18-06057-05 TRG B103202AFRWCOZ7CV_.. - - . 05/31/1814:50 *; 6114/2018 ** 6/1"412018 --~ ~u,,;.145 ,_ EPA901~1 M ~ *u7E--03 : 1.35E-01 . 1.35E-01~2.10&-01--U- - ' pCllg - 18-06057-05 TRG B103202AFRWC027CV - ~ ~ 4 ~ - : 611412018' 6114/2018

• 18--06057 Radium-226 1 - - EPA 901.1 Modlfled  : 4.70E.01  : 3.0SE-01 ~E-01 5.43E-01 u pCi/g *-

18-06057-05 TRG B103202AFRWC027CV- **- - -05/31/1814:50 '. 6114/2018. 611412018. 18-06057. An1imony-12s**'--EPA901.1 Modffied + 6.90E-02 1 2.55E-01  : 2.55E-01 . 4.39E.01 U- pCUg - 18-06057-05 TRG 8103202AFRWC02~- ._. 05/31/1814~-:~,e~* 6/1412018 18-06057 ; Thorium-234- -EPA901.1 Modlfled 8.53E.01 2.00E+oo~oE-::00- 2.76E-+-00 u  : - pCVg-*

                      - - - **                                                     ----         - - - . - - - - - - - Y- *- _                                                ..... - .......--... .. _.... **- - - * -- -                                     . -            - - - * * - - * * - - * .. - - - - - - -

,_2~057-05 TRG B103202AF~C027CV_____ 05/31/18 14:~_ ~ 6/14/2018 : 6/1412018 18-06057 ; _ ~OilJm~.** ._...~A_!l~~ified -~ . 3 ~ 3.01E-~ __...2;_02~ __:i-7:._E~

• _ U _ _ pCi/g .

18-06057-05 TRG 8103202AFRWC027CV 05/31/1814:50 : 6/14/2018

• 6/1412018 16-06057 Uranium-235 EPA901.1 Modified 1 -8.20E-01 ; 1.53E+OO 1.54E+OO 7.56E-01 U pCllg CU..Counting Uncertalnty;CSU-Combined Standard Uncertainty (1-slgma);MDA=Mlni111'111 Onectad Activity;LCS-t.aboratory Control Sample;MBL=Blank;OUf'c.Dupflcato;TRG=Normal Sample;DOcDupllc.ate Origlnal;U~on-detect EB E RL ! ~*~ E EBERLINE ANALYTICAL CORPORATION ANALYTICAL 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621

                 ~                                                                                                                           [567]

Printed: 7/11/2018 1:04 PM Page7 of 12 RllporlTo: Patricia Giza SDG: 18-06057 Eberline Analytical Zion Solutions PUTChase Order: 677118

                                                                                                ,, *----*-* * - - - - *-**----*-¥ Final Report of Analysis                                                                     101 Shiloh Blvd                                                                   Analysis Category:
                                                                                                                                                                                     . . -,. 5-;;~ ,.Matrix: .                       . SO ENVIRONMENTAL
                                                                                                                                                                                                                                                                 ~                       --

Zion, IL 60099 18-060~7-06 _TRG_. __ 8.~~~~~~00!2V__,_ *. _ *--~181!"~ : 6/1412018

• sn4/2~8 ___1fl:-0~057 __ A:fln}~~-=-~- ... !§:~A.92.!_:~o~--- ~<E_E:0!__ -~9E-0'!___ 5.SOE-01 _9~L--~ _P~~

l',06057-06' TRG *.. 8.1032~~FR_

CO~~ _ _ _ _316/05/181~~ ~ :~40)~~ _1_8-0_6?_5~ *-- Silver-1~~- EPA 901.1 Modified 1.26E-01 1.36~-0~ **- __ :~~~~- _ 2A2E--01 _ ~ ____ pCilg _

18-06057-06 ; l'RG B103202AFRFC0072V 06/05"1812:39 6n4/2018 6/14/2018 \8-06057 Ameridum-241 EPA901.1 Modified i -5.95&01 . 2.58E-01 2.SOE-01 3.49E-01 U ..!>C:i!!I.. *- 1S-06057-06 : TRG

                                 *B103202AFRFC0072V -
                                                         - ---* , .,.. _ _ _ u - * - * -r -
                                                                                             - 06/0&1812-:i) 6/14/2018 6/14/2018 18-06057 .

• Barium-133 -

EPA901,1 Modified

-1.34E-02 ,

• 5.53E-02 5.53E-02 3.83E-01 U

                                                                                                                                                                                                                                                                                                                            * - ~ ......_

pCi/g _,._,._, 0605~TRG __ B103202AFRFC0072V *. -- _ __ ~18~2~9~14~ 6114/201~ _..!._8-06~--~-is!'l~~-~1~ ~P~90~ M_o~ffi~ _ __:::!_E-!!.__:~ ~ _ _ 3~~~1-_~~E-01 __ -~ - - ---~;/~--* 18-06057-0B TRG B103202AFRFC0072V 06/05/1812:39 6114/2018 . 6/14/2018 18-06057 . Cobalt-SO EPA901.1 Modified ~.07E-02 . 1.56E-01 1.56E-01 1.88E-01 U pCi/g

      *- - - -      - - - - * - - - * ~ ........-      ... * , - -         ---- ~ --    * ._                                            r _ _ _ _ ._    n * * - ** * - -  ** L.......* *

• _ ..- ._,. _ _ * - * - - * . , . . . . - - * - - - ' " " - ~- - - *,._,,,._.,~. . . . , . - - - - - - * - - - - * -* * *** - - -- ** * - -

18-06057-06 : TRG ~~~.?.J072V __ _ __?!f~39  ; 6/14/2018 6/14~~ _!_8:06057_._ Ce~~-13':_'--.E~~_'.l~1;2._~~~~.,:~..!._ ,._}:69E41 _._1~~_2:_1~-0_1_._L!_ ____ !_C~ . . ~ 18-06057-06 : TRG B103202AFRFC0072V ..... ~ ~ - T R G _ _B103~RF~~~ _ -*-* _ 06/05/1812:39 06/05/1812:39 6/14/2018 . 6/14/2018

• 18-06057 . Cesium-137

. 6114/2018: 6114f2'!1~_2~7.- ~ropium-152_ -~~90~-~~o~~~- '

EPA 901.1 Modified

                                                                                                                                                                                                     --.-.   - - *- 3.BBE-02* -5.55E-03 '. 3.31E-02 : 3,31E-02
                                                                                                                                                                                                                                   ---~----             , 3.72E-01
                                                                                                                                                                                                                                                                           **---               ... - - -* -~-* -****---**-* *- -

3.72E-01 _ ~ E ~ ___ _ 3.06E-01 U u_ _____ ~~~-- pCi/g ~~'.~G B103202AF~C0072V__ . _ 06/0511812;39 ; 6114/2018' 6/14/2018 1 ~ ! _ - ~...£.~~154-~A~1.1M~ified _* -~-~2_E-01 '. 2.83E-01 ~~~ - - ~ --~~g __ ,_~8~7-06 : _ TRG ____ _!~3202AF~:C0072':'.'.____, _ _ . 06/05/1812:39 : _ 6 1 ~ 6/14/2~8 . 18-06057 . Europiurn-155 EPA901.1 Modified 7.1BE-01 . 2.BDE-01 2.83E-01 4.43E-01 U pCUg 18-06067-06 18-06057-08 ,

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

TRG B103202AFRFC0072V TRG B103202AFRFC007ZV

                                                                      -*-*------                 06/05/1812:39
                                                                                                                *--6/1412018 6/1412018 1!',06057 . Holmium-166m
                                                                                                                             -  --*----**-**---lodlne-129
                                                                                                                               -----**.1!',06057 .-* -----

06/05/1812:38 ; 611412018: 6114/2018

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

EPA901.1 Modlfled EPA901.1 Modified

                                                                                                                                                                                                           ------1-----**
                                                                                                                                                                                                                           . 1.03E-01 ; 2.6ZE-01 ~ - 0 1
                                                                                                                                                                                                                                    - - *-----* *--.--' 1.31E+OO
                                                                                                                                                                                                                            , -3.00E+OO

• 1.61E+OO ; 1.62E..00 2.15E-01

___ U U

                                                                                                                                                                                                                                                                                                                                    * ,

• pc;;g*-

                                                                                                                                                                                                                                                                                                                                  .             pCi/g 11',06057-06 :    TRG           B103202AFRFC0072V                                           06/05/18 12:39 '. 611412018    6114/2018 : 18-06057 . Pota!lsium-40                       EPA901.1 Modified                      6.96E+OO               , 2.00E+OO .            2.03E<-OO              1.73E+OO .                              pCi/g 1&-06057-06 \ -TR_G        ,    B103202AF_j~-~2V-=-=---:--=- ~-OM!SI~ ~ ~ - ' 6/14/2018 . 6/~,4/2018                                   16-06057-' _M:_n~~~                   -*EPA 9(Ji:1 Modified                     ; ~.37E-03 ; ' 1. 11E-01 -- ~ _ 1.76E-01 __ -~- _ * - . pCl/g ..
,- 1~~~~ _ . B103202AFRF~- ,                                                                     06/05/1812:39 ; 6/1412018 6/1412018        11',06057      Niobium-94                      EPA 901.1 Modlfled             ~ 1,15E-02                           1.42E-01           1.42E-01              1.99E-01         U                      pC!:'.9 .

1S-06057-06 ; TRG B103202AFRFC0072V 06/05f\812:38 . 611-4/2018 6/1-412018 18-06057 L~-210 EPA901.1 Modified ' 2.74E-01 : 2.48E+OO : 2.48E+OO 3.96E-+ U pCi/g

-I~~:;!)6 . TRG-:_-~~32-~_RFC0072V~--~=-:=- - 06~1~2:39 .; 611412018. 6/14/2018 -~057 :- ,__!::~~2- - - ~~~_!l01.1 ~~~- '. 6.95E-01 ; 4.24E-02.__:~35E~- 6.66E:)2__ *----- --* .. P~~- _-

,_!_~:__2~---~~03202AF~:_~OO.!~Y.,___ __ 06/05/1~2~.: 6114/2018. 6/1412018 18-08057, Lead-214 EPA901.1Modlfled  : 5,41E-01 , 3.91E-01 3.92E-01 6.21E-01 U --~1/g- _ ,__,!!:06057-06 TRG _ _~1D:32~FC0072V 06/05/1812:39 i 6/1412018: 6/1412018 18-00057 ~ 8 1 1 1 ~ - EPA90L!Modified  ; -6.88E.:?2._~-~-'-~02__ 7.29E-01

• __u__ :___ pCllg_

18-06057-06 TRG B1~~~F~~ _,.__06/05/1812:39 ! 6/1412018' ~ ~4E0~!__2~7 _ ~~~~~ _ -* EP~~--1 Mod'rlled_ , _5.51E-01 :_ 3.SOE-01 _ ' 3.51E-01_ 6~1______u______ pCi/g 18-06057-06 TRG___ B1032~2AF~F_l:_CXl_?~-- _ 06/05/1812;39 611412018. 6/14/2018 . 18-06057-~~-r,y-125_.__!.~!_!!~1_'!'~~'!1- -1.05E-01 4.94E-01 4.94£-01 7.32E--01 U pCi/g 18-06057-06 TRG B103202AFRFC0072V 06/05/1812:39 611'112018 6114/2018 18-06057 : Thorlum-234 EPA901.1 Modified -4.93E+OO 2.38E+OO , 2.39E+OO 3.28E-t-OO U pCi/g. -

                                                                                                                                                                                                                                                            -- ~~O~-?.!....' ~~- 7.69E-01

• _ _u ____ pCl/g -*-

  -    -   - - - * - - - - - - * - -~ - -                     -*                                                                                       ~- - -           -,--             - w*' '"'"  _.._, - - - - **- - - - - ' - - - - -

18-06057-05 TRG B103202AFRFC0072V 00/05118 12:39 i 6114/2018 , 6n4/2018 18-06057 ThaUlum-208 EPA 901.1 Mod'rfied 7.21E-02 18-06057-06 : TRG B103202AFRFC0072V... - - I 06/05/1812:39 ; 8/14/2018 6/1412018 . 18-06()57- -u~;;;;;::235- **-EPA901.1 Modified 1.19E+OO 2.22E+OO i 2.22E+OO 1.17E+OO u pCi/g ClFCounllng Uncer1ainty;CSU-Combined standar<l Uncertainty (1-sigma);MDA~Minimal D..tected Actlvlty;LCs-labon.tory Control Sample;MBL~Blank;DUP=Ouplkate;TRG=Norrnal Sample;[)();Duplicata Origin*l;U=<Non-<letect EBERLINE ANAL YT I CAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [568]

Printed: 7/11/20181:04 PM Page 8of1Z Report To: Patricia Giza SDG: 18-06057 Eberline Analytical L-, ----w--.. .--....----- .. -.......... . Zion Solutions Purchase Order. 677118

                                                                    --- . . . --** -* - ---                                                   ---*- . .--- ___----*  *-**-****~- --.--...---**--.*---       ..- -* *- - -- - -                   ~- -- ,,                               ............................... . . .

Final Report of Analysis '---~Shiloh Blv!l..* ----*-*- --**- _________ *- Analysis Category: Sample Matrix:

                                                                                                                                                                                                 ..       ENVIRONMENTAL
                                                                                                                                                                                                         *so ----* - - *-

Zion, IL 60099 Lab Sample Client Sample RecRipt Analysis Batch Analyte Method Result CU CSU MDA Q:,aflrier Report ID Type ID Dal* Date Dare ID Units 18-06057-07 TRG B103202AFRFC057CV 06/05/1810:15  ; 6/14/2018 6/14/2018 18-00057 Adinlum-228 EPA901.1 Modified 3.05E-01 2.91E-01 2.91E.01 5.47E-01 U pCl/l.l 18-06057-07 18-06057-07

                . _;~~:~---~-)1~~~~~!_CV-=:~ ~~~8_!0:15 TRG ---~-~~2AF~FC057CV

-af14fl~~ .*!!.4~~-

06/05/1.8~0:15 _ ~~ _!1_~1~- 18--0~57- ~3n~er-.1c.m, _ ~-- _!_S-0605.! --~ric~~~-

                                                                                                                                                                   ~p~ ~;-~-M~~~ _:_.~-:-80E-03 ~ 4.52~ ~. ~ 4.52E-02-~_8~~~~- .
                                                                                                                                                                -~9!_)1 ..!_~o-dilied__ _. -* ~:~2._ _!3_7~-01 _ _!!7E-01__ --~~E~°..!_ ** - - ~

__u:*-~--=--pa~

                                                                                                                                                                                                                                                                                          *- _!'_~ __

18-06057--07 TRG B103202AFRFC057CV 06/05/1810:15 . 6/W2018

• 6/14/2018 18-06057 Barium-133 EPA901.1 Modified  : 7.0SE-03 6.5-'IE-02 6.54&02 1.21E-01 U pCi/g 18-06057
• TR.-~-~---: B1~202A~_l'COfilCV --- - * - - ' -~ 1 s 6/f41.i!ot8- . 6/1~2.18 1 1~06057 . -=-~-~lrth-21~
• EPA 90~_1.Mo~ed .. __ ; e74E--_D_!_ _- ~ 1 ~ _._2~~~1- --~:1"_1E.-:11;..-: ~~- *.. ___ ... pCVg 18-06057-0:..._.~~-~~2!J~~FC057EV 06/05/181~:~--- ~ ~ 1 ~ ~ ~ _ 18-06057 Co_~'.~~_ ...!:!'.~~~-~-Modifie~-- 1.85E-02 : 7.TJE-02 7.77E-02 t.OOE-01 u pCi/g 16-06057-07 -~~ _ -~03~<!._2AF~FC057CV 06/05/1810:15 6/14/2018, 6/1-4/2018 __ 18-06057 :_ Cesium-134 _ * - EPA901.1 Modified .* -6.51E-03 : 3.32E--02
• 3.32E-02__ 1.ose.:02..._ -* -~ ____ pCUg -

- 1 ~ : ~ - _ !_RG. ___B~'!_~~~~~ 06/05/18 10:15 ; _6114/201~ *. 6114/ZO~B_18-~~ ,_~esh~-~-. _ EPA 901.1 Modi!led i 3.90E-03 ; 9.12E-0.2 __ _!.12E-02 __ 1.37E-01 ____':_ _______ pCi/g 18-06057-07 TRG 8103202AFRFC057CV 06/05H810:15 .' 6/14/2018 I_.,.... . 6/14/2018 ___ 18-06057 _ __ : _ EtZOpium-152

                                                                                                                                                  ._..._. _ _, __ EPA901.1         _ _ _ _ _ _! 2.04E-01
                                                                                                                                                                   , __. , , . _Modified                     -    .      2.82E-01

_ _ _,.,.-.,. , 2.82E-01

                                                                                                                                                                                                                                             .... - - - - -2.90E-01
                                                                                                                                                                                                                                                              - - - - *_. __,._U.... _,.      - ... -    pCl/g -

18-08057~' __TR_G___ . _ ~~03202AFR_F_C_057CV______-l-_06A)5!1 _ _s_1_0_:1_s __' 6 / 1 ~ 6/14/2018 _ 18-06057 ___ Europium-154 ,_ EPA901.1 Modified . _ -2.03E--~.89E-01 __ : _ t.89E--01 1A8E-01 .* U **- ___ pCVg _ 18-06057-07 TRG B103202AFRFC057CV 06/05/18 10:15 6/1412018 : 6114/2(118 18-08057 Europium-155 EPA901.1 Mod'rtied 3.06E-01 ; 1.61E-01 1.52£:-01 2.53E*01 pCVg ,___ _ _ -t"' --M -- - - . . . . ,---- ---*-- *--- --* *--------- * ---- -.-..." ,- - * ~-- ---- *-.--* - - .----**-------** . . .~.. , ,.__ *

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

18-06057-07 ' TRG B103202AFRFC057CV 06/0511810:15 : 6114/2018

• 6/1412018 1S.06057 Holrnium-166m EPA901.1 Modified  ; 6.79E-02 ' 1.34E-01
• 1.34E-01 1.0SE-01 U pCilg

~6057-07 , TRG -~ B103202AFRFC057CV - - --+-06/05/--1_s_1_0_,,_s_._611_4!20__ 1a _ 611_4J20 _ !!1__1_a-0~~~!:~~ _ L-EP~~:.~_dlfied _ _ .: 7.44E-02 : 7.64E-O~: 7.65E-02 __ 1_.1_7E_~ _u __ _P~--- 18-06057-07 ' TRG 8103202AF~~C_057_CV _ _, 06/05/1810:15 6/1412018 ~~~~:-~~~~::"~. _ ~PA901.:!_"!l~lfl_!:~ 5.42E+-OO ." .......!_.47~-. ~~~45E+<l0 * - - - - - - - ~ - 18-06057.07 '- -~-G ____ e_1_0J2_02AF __ RF_c_os_rc:v ________ OSI0_51"!!3_~~- : ~14/2018 611~~-1_&-06_057_~ _M_ar,g_a~~~ >- _EP_A_!ilO __ 1 .1 M~di_fi_ed _; _ 3.01e_-02_; __ _____8.00E_._-02_ _ ~~E-_01___ .. _u _ . --~~- -*. 8._08E-02 18-06057-07 __TR_G __._.;_B1~~R~C-_O_c5_7CV.:.__ _ _ _l-_06Al_51_1_8_1_o:_1s__,' 6114/2018 ' 6/1412018 . 18-06057 ' Niobium-&! EPA901.1 Modified  : 6.67E-03 : 7.09E-0.2 _.. _!;09E-O!_ -~6~-01-.,. _ _ u_ _ pCilg _ 18-06057-07 TRG B103202AFRFC057CV _ ___._08/05/1_ 810:15 '6/1412018 6114/2018 _18-06057. Lead~ -** EPA901.1Mod'med __* 1.23E+OO .* 9.17E-01 . 9.19E~1___!:64E+<l~ ... .* .!:l..._. _ pCUg__ ~8-06057-07'T rao*- 8103202AFRFC057CV --1-06-/05/_1810:15 6/14/2018 . 6114/2018 18-06057 Lead-212 EPA!I01.1 Modllled . 3.74E-01 1.26E--01 . 127E-01 2.58E-01 pCVg

• 18-06057-07 ; TRG B~~.E.2!-f'RFC~2cv - - 06/DSJ181Cl:15 "1.6114/2018 6/1412_01.:.:8_ _1e.._06.:.:05.:..~. ___L_ea_d-_2_1~_::_e_P_A~t_.1_M_o_dili_ed_L 6.tOE-01 __ 1._12_e_-01 __,_~~:£1 _ _2~7E-O!_ ____ --* £~L 18-06057-07 ; TRG . B103202AFRFC057CV 06/0511810:15 6/14fl018 6/14fl018 18-06057 ' Prornethium-145 EPA901.1 Mod'cfied . 7.31E*D2 : 9.4SE-02 ' 9,46E-02 1.59E-01 . U . pCl/g 18-06057-07; ~ - -B1032D2AFRFC057CV +-06/05/1-.:._8_1_0:15. _6_/1_412_018 - 6114/2018 18-06()57 Radiin-226*- ~PA-90-1:-;* Modified '~---6-.1-4-E-0_1_.__-2-.6-1_E __:!J

___1____-~E-01 __ --~J 1E-01 ** ~----_- =---p-c11g-**-

,~--..fJ7-
-                 __ T-RG---~ a103202AFRFC057cv                         06/0511810:15 &14/2018~4f..2018-18..Q6057 -Antimony..125 .. "EPA901.1 Modffied
                         . . . . ------ -------'-------1-----------,-----~                                                                     ------ -**-- -* -----.....----.,....               : 7.16E-02              1.66E-01       '.
                                                                                                                                                                                                                                                 -----------**--***-u -----. ~~---

1.66E-01 2.97E-01 pertg*** .. 18-0e057--07 ;_2.RG -~~~RFC057CV _ O&J0511810:!:.__ ~4/2018 _!1~ 18-06057 _Thori~- -~~~0.!.:_1_MO!f1fi~ ~. 9.19E~_1.48E+OO '. 1.48E+OO __2:!3~ __ ':I_ . . 18-06057--07 _ _T_RG _ _ _B_10_3_"1D2N_-~~C057CV 06/05/1810:15

• 6/14/2018. 611412018 0 18-060!5!._~~llum-208 ._ EPA901.1 Modlfiad ' 3.37E-01 2.36E-01 *.* ~-~E-01 4.52E-01 U pCllg 18-06057-07 TRG B103202AFRFC057CV 06/05/1810:15 6/14/2018 : 6/1412018 18-06057 Uranium-235 EPA901.1 Modified 1.79E-01 ! 9.62E-01 9.62E--01 5.34E-01 U pCilg *-

CU-Counting Uncertalnty;CSU=Cotnblned Standard Unc,,rtainty {1-6fgmaJ;MDA=Mlnlmal Detected Actlvity;LCS=Laboratory Control Sample;MBLsBlank;DUP:Dupllcatlt;TRG=Nom,al Sample;DO,,Dupllca._. Orlginal;UsNon-detec:t EBERLINE EBERLINE ANALYTICAL CORPORATION

§) ANALYTICAL 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621

[569]

Printed: 7/11/20181:04 PM Page9 of 12 RepartTo: Worl< Omer Details: Patricia Giza SDG: 18-06057 Eberline Analytical Zion Solutions

                                                                                                               .. ****** **- ~**-
                                                                 ,. , ,.,,,,,.-O .O A * " # -- ' *,._, - - - - - - * * - - * - - * * - - - - *** '  *
                                                                                                                                                                                   .. Purchase Order:-*- 677118                           ____ ***-

Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTAL . . Zion, IL 60099 S~;,pha Matrix:

• SO . -

Lab Sample Client s~mple Rec&lpt Analysis Batch Analyte Method Result CU CSU MDA Qualifier Report ID Type 10 Date Date Date ID Uni1$ ....~ ~ - - } l ' l ~ - . B103202AFRFCll62~- ------* -~~8~8=~-~~~a31~~~~6?5~ ----~-~~~-~8- . EPA901.1 Modified ...!:.~~. _ 6;70E--0_1_ - 6.70~--0_1_ - _1.11E+OO ___ _u -- pC1/g _ ~7--08 _ *- ~~ - --*~103202AFRFC061CV - - 0Ml5/18~~42 _;~:~8 ~18 ~8-06~5Z_ ____~er~1(!m _ EPA901.1 Modified - ' -~.25E-03  : _ 1.98E-01 . _!!~~-?~.. _!~8~E~! _ _ _u _ .. pCVg _ 1B-06057-08 TRG B103202AFRFC061CV_'- 06/0~~08:42  : 6114120~ ~~. 18-CJ!05~ Ame~~1- *. EPA90UMo<ified  : -9.tOE-01 - ~ ~ ~ - - 3.43E--01_ ~.59E-Ot_ *--- U .* pCi/g _ ,_ 18-06057-0S . TRG . B103202AFRFC061CV 06lo.5/1808:42 6/1-412018 6/1-412018 18--06057 Barium-133 EPA901.1 Modified . 4.58E-02 9.13E-02 . 9.131,.02 5.23E-01 U pCi/g - - * * * - * - - * * - - - - - - - *- ---1-- -------**- --------------~-- . ------* -*-* ...- ........--..*--- -----*- - - - - - --- - - . --- --*--*--- -* - - *- 18-06057-08 . TRG 8103202AFRFCD81CV 06/05/18 08:42 , 6/14/2018 . 6114/2018 18-06057

• Blsmutb-214 EPA901.1 Modilied , 3.62E-01 : "4.61E-01 4.62E-01 7.B6E-01 . U pCi/g 18-06057-08 ,

,,____~--~ " TRG

                          ~---- ---- -

B103202AFRFC061CV ___!8-06057-08 '..*TRG~B103202AFRFC061CV_~0610611808:42 Oti/0.511800:42

                                                                                                      . 6/1412018 6/'14/2018
                                                                                                        ~114120!£ 18.08057 6/1412018. 18-06057; Cobalt-60 * - i - EPA901.1 Modified Cesium-134 ___ EPA901.1Modified ~1.86E-01 ,

-4.SOE-02 .

1.51lE*01 . 1.59E-01 2.19E-01 *... ~-f!E~1 _3~~!- 2.3tE-O~ U

                                                                                                                                                                                                                                                                                                -~-

pCi/g * - pCi/g

~~~_!~-                      *--~~02AFRFC06~CV                     Q6l(l5/18D8:"42                          611~?~- 6/14/2018

• 1~~--' -~~iu~3~- ~~~0~.!'."~
• 1.67E-01 _2.1_~! - .E~-1 _____a~~~--~- pCi/g

_!_~6057~. ~G- _ ~202AF~C061CV 06/05/18_~~"4~ 6114/2018. 6/1'41201~. _.2_B-~ .~ _E~ium-m_ ':_~~o~~d_ _  ! 2.62E-01 6.16E-01 6.161:-01 7.00E--01 U . pCl/g ~~!!._.'.. TRG . _!:123~061CV__ - -

• _ 06/05~:~, 6/1412018 _* 6/1-412018 1&-06057 . Europium-154 . --~~~~1.1 Modified ..a.28E--02 1.65E-01 ___ 1.65E--01 _ 3.56E-01 __ U. _ pCi/g *-

18-08057-08 TRG B103202AFRFC061CV 06/05/18 08:42 6/14/2018 6/14/2018 18-06057. ; _ Europium-155 **- ~~~1~Modified__ 6.40E-01 3.64E-01 _3.65E-01.. ~ 5 ~ - __ Y._ pCi/g ,.._28-06057-08 -*~ -=-TR~--- -B1~RFC061CV 06/0~~£"~141201_~.T 6/1-412018 18-06057. --~o~.!!:!~6m EPA901.1 Modllled , -t.49E-01 . 3.17E-01 *- 3.17E-01 _ ~.s6~_!_- _u_ _ pCVg 18-06057-08 TRG B103202AFRFC061CV 06/06/1808:42 6114/2018 6/14/2018. 18-06057 : lodlne-129 EPA901.1 Mocfr!ied  ! --4.35E+OO I 2.24E+OO ' 2.25E+OO 1.73E+OO _. u.__ . pCl/g 18-06057--08 ; i.-- --* TRG B103202AFRFC061CV * - ' - 06J0511808:42

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

• 6/1412~6/14/2018: 1s.o6057. Potassiurn--iD EPA901.1Modified ' 6.78E+OO j 2.29E+OO : 2.31800

__........- ~ - - - - - - * - - - _ _ _ .., - - - - - ... - - - - 2.23E+OO i-----*---- pCi/g 18-06057-06 ' TRG . B103202AFRFC061CV OB/05118 08:42 ; 6114/2018 6114/2018 . 18-06057 lllanganese-64 EPA901.t Modified  ! 5.02E-02 . 1.57E--01 . 1.S7E-01 2.7DE-01 U , pCi/g ~6057-08 TRG B103202AFRFC061CV - 06/05/18 08:42-611412018 611412018 16-06057 Niobium EPA901.1 Modified ' -1.3"E-01 1 1.BSE-01 . 1.85E-01 2.sse-01 u .- pCi/g - - - - . . --.--- . . -- -B1D320~~C061CY._

 ~7~ TRG
                                - -----------L----*-**___        ~1808:42 ,_ 6/1412018:
                                                                                                                                              -       --*--* --~ - -------

6!_14/201~~- - - ~ ~ ~ - _ EPA901.1Modilied L::!b4E+OO

                                                                                                                                                                                                                                ---------.---                               ------ -*~-..*--------.':.-

3.90E+OO _:~1E+OO _ ! ~ __u__- - ~ - 18--06057-08 :~ - - _ _!!._03202AFRFC061~-"--~6Al5/'1808:42 _6114/2018. 6/1412~ ~~---!:_.88.<!:~1!.. EPA9~12_~ j t.13E+-00 3.86E-01 3.91E-01 6.14E-01 U . pCilg 18-06057~ _'_!_~--~~_FRFC061CV _ 06/05/1808:42 : 6/14/2018. 6/1412018. 18-06057' L.ead-214 EPA901.1 Modiffad . 1.29E+OO : 5.756-01 * ...:.:!!~..-- 7.24E-01_ _ _ _ _ _ _ pCllg __ _ 18-08057-08 . . .TRG 8103202AFRFC061CV 06/05118 08:42 .- 6114/2018 :- 6 / 1 ~ 18-06057  : Prcm;thiurn-1~ EPA 901.1 Modified 1 -3.00E-01 .-6.91E-01 6.92E-01 9.99E-01 U pCVg

,_ _ _ _ -             -- --                                ~L--.                                                                       .          *--*****---,-,-~                                                                        - - - _ _ _ _ _ _ _ _ _ _ _ ,... . . - . . . - - .. - - - - - -

18-06057-0B_,.. TRG _ ---~~RFC061CV _._ywost1808:42 811412018. 6/14/2018 ___ 16-06057 * .* Radium-22~--* EPA901.1 Mod'dled i 3.62E-01 : 4.61E-01 . 4.62E-01.... 7.S6E-01 _ _ U __ pCi/g _ 1-----,-....------- 18-06057-08 18-06057-08 . TRG TRG B103202AFRFC061CV B103202AFRFC081CV OBJ05/18 08:42 OBJ05/180B:42 . 6/1412018 . 6114/2018 , 18-06057

                                                                                                       . 6tl412018 ' 6/14/2018 18-06057                    Antimony-125 Thor1um*234
                                                                                                                                                                          - -EPA901.1       --"*Modifiad EPA 901.1 Modified
                                                                                                                                                                                                          -           . --~----,

i

                                                                                                                                                                                                                          --4.85E-02
                                                                                                                                                                                                                         --4.03£+00 5.47E-01 2.57E+OO 5.47E-01 2.58E-+-OO 8.34E--01 4.32E+-OD .

U U pCVg pCilg 18-06057-08-'TRG*- *- B103202AFRFC061CV 06/05/1800:42-.611412018 6114/2018' 18-00057 *,,,;liiu;;;.208-~ EPA901.1 Modified l 4.19E-01  ; 6.04E-01 -*6.04E-01 9.91E *-u- ~l/g-18-06057-08 TRG B103202AFRFC061CV*-- 06/05/1808:42 :stW20~141iots 18-06057

• Uraniurn-235,__ EPA901.1Modifled i *2.90E+OO 2.93E+OO *. 2.93E+OO 1.54E-I-OO
• U --.. pCJ/v-CU=CounUng Unc9rtllinty;CSU..COmblned Standard Uneerainty (1-slgma);MDA*Mlnlmal Detected AclMty;LCS=labonltory Control Sample;MBL~Blank;DUP=Duplicate;TRG~Nonnal Sample;OO=Oupllcate Orlg'inal;U*Non-detect EBERLINE EBERLINE ANALYT1CAL CORPORATION

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

[570]

Printed: 7/11/2018 1:04 PM Page 10 of 12 Report To: Patricia Giza SDG: 18-06057 Eberline Analytical ----677118

                                                                           ... _.. *- Zion Solutions          -- -- ,.___ *---*** ... .                                                   Purchase Order:

Final Report of Analysis 101 Shiloh Blvd Analysis Catt,gory: ENVIRONMENTAL -- -

                                                                              - zion, 1L soogg                                                                                             sample Matrix:              SO               * *                        * *-      -

Lab Sample Client Sample Receipt Analysis Batch Qualifier* Analyte Method Result cu CSU MDA ID Type 10 Date Date Date ID 18-06057-09 TRG... B103202AFRFC038CV 06/05/18 14:20 6114/2018 6/14/2018 1~6057 Actinium*2W_ ---~~~1.1 Modified _ _ !:~~:')1 . _'::~~_:?)___ 7.85~_!_ _ ~E+OO . _ U -** ___ pCi/g ---* _____ _, --t---- *-*-*----- u 18-06057-09 ---~-~ _ B1~R~C~CV - - - __ 06/05/181420

• 611412018 . 611412018
• 18-06057 snver-10&n EPA 901.1 Modified , -2.soe-02 . 2.,oe-01 2.1oe-01 3.00E-01 pe;19 18-06057-09 TRG B103202AFRFC03BCV _y~_a_14_:20__ . 6/14/2018 6114/2018-1~?~ .. ~~~~1 EPA901.1Modified _*_-7.67E--02 -~*~~1::_01 **2..65E-01 __ 3:!.6E-01 _ _u __ __ pCi/g ..

,~ ...... - - - - --i,.. ... ---

• 18-06057-0!I : TRG B103202AFRFC038CV OS/05/1_8_14_:20_ _6_1_1412_0_18 __61_1~1~- ~~!l5!. -* -~~'!';:!33 EPA901.1 ~ _ ~E:<!_1 _. 3.82~_:':1 _ - ~ . _4.42E-0.:1_,__ ~ - - -- .pCi/g -* _

18-0605?~ ~. -.-~G-. _a_1032_02Af,~_Fc_oo_~cv____ _ ~e/0511_8_1_4:~ 6/1~2018

• 611_412_0~~~6~ , ~i!".:'~.:~.14 E~~901.~dllied _ _1.7~~~ _ -~~-01_ __6~661::~1._~E+OO_ --- pCi/g .

1~~~. ~G__ ___ B_10_32_0_2A!RFC038CV *---+-061D511_ ._ ! . 1 ~*- ~ . 6/1-412018. 1~6057 ., _ _9>~1t-~ EPA901.1Modffied , 8.93E-02 2.51E-01 2.51E-01 3.11&01 -**-U ___ pCilg ___ 18--06057-09 ._ TR_G ____ s1_0~_02AF _ _R_F_C~3.!.C_v___ ~814:20  : 6/14/2018 ' 6/14/2018 . . Y!.~~ ... _ C:_es11:_n:134 EPA 901.1 Mocfrfied  ! 1.22E-02 121e-01 1.21e-01 3.95~~.!.._ __ u__ _ pcug 18-06057-09 TRG B1D3202AFRFC038CV ---i--06/05-/1614:20 . ~ . 6/14/2018. 1~~7---~~:_13_7_ _ _ EP_A~01.1!fiod111ed i 3.30E-01 '. ~-~?!. ,__2.*.~- 4.66E:()1 _ _':!_ __ .. pCVg 06057~ TR_G_' _B!_~202AFRFC038CV . 06/05/1814:20 . 6/14/2018

• 6/'14120~~--*-*EU'Opium-152 , _.!_PA_~Modifiad - ' - ~ ~ - --*~~1 .. _4.B3E-Ot _ ~~9~~ . _ u __ * - pCilg_

18-06057-09 , TRG B103202AFRFC038CV _ _ ___, 06/0511814:20 6/1412018 6/1412018 ~06_057 _ _ -~~P!*.".!1.*_1~ EPA901.1 Modffia<f  ; 2.16E-01 4.61E-01 4.61E-01 3.10E-01 _ ~ - __ pci/g. 18-06057-09 ; TRG B103202AFRFC038CV 06/05/1814:20 6114/2018 5114/2018 18-06057 Europium-155 EPA901.1 Modified  : 3.41E-02 . 3..18E-01 *. 3.1BE-01 4.87&01 U pCi/g 1~~7_-09_-_- .~-T=-R-=-G-_-_*_*-_e_~-2-~--_RF ____C~038CV~~~========:i--~-.- -~-81;4_:-2_0=-

                                                                                                   - -6/14/2018 . ei,-4/2-01-8-;8:_0605!... _H_oi~~~-166m                               EPA 901.1 Mocfrfied   '    -5.705-02          ~~E--01          ~  4.50E-01       2.32E-01     ,_u_.* ,__ pevg tS-06057-09 ; TRG_ _ B103202AFRFC03_BCV                  _ _ _ _ _ _ _06I05t_18 1420 , 6/1412018 , 6/14/2018 , 18-06057                                           lodlne-129          EPA901.1 Modified          -{;.52&02              1.12E-01         1.12E-01      1.69E-01        U           pCilg 18-06057-1?9_!            _!~~-- . __!!032_0_2AF_R_!"C03_8C_V                . 0~_61_-_1s_1_4_:20  ' 6/1412018 _611_~1!_: _-1_8-_-o_so                        :J'~;;i,;:.w            EPA 901 :1 Modlfled  _. 929E+~_:- ~.~E:00                      4.09E+OD _ MBE-+-00 :__ ___ ___ ,- pCi/g __

18-08057--09 : TRG B103202AFRFC038CV ----l-06!_0_5118 14:20 6/1 "'2018 , 6114/2018 . 1S.0~7 . : Manganese-54 EPA 901.1 Modified , -6.71 E-02 . 2.42E-01 2.42E-01 3.80E-01 U I'_~~ 1B-06057-091_TR_G_ - B103202AFRFC038CV 06/05/1814:20 6114/2018 !'11412018 18-06057 Niobium-94 - EPAsoi:1 Modi!lec  ! -1.38E-01 : 2.12E-01 2,13E.01- 2.96E-01 U pCi/g 18-06057-09 TRG B103202AFRFC038CV ~~-~ 6/14r.101(~ 6/14/2018 1 ~ - * ~-L~d-21~ EPA901.1 Modified ~O . 2.01E+00~01E~ 3.24E.00 * ---~- ___ pCi/g

                                                                             -~1~1~~~__!~120_1_8_. ~120_1s_. ~-0505_7_ -** leacl-212                                                    E_PA901.1  Modified    '. 8.06E-01 .            3.18E-01 _ *-~-~~~ _ ~ -* _ .. pCl/9 18-06057--09~ R G 18-06057-09 ;

TRG B103202AFRFC038CV B1032D2AFRFC038CV

                                                        --- - -                 OS10

__51_1e_1_4:20.;.__61:.:.1:.:.4/20...c.;.1:.:.a:.:.;..

_61_1_4l20_1_s .~e-_os_os_1_. - ~~d:2:~-

                                                                                                                                                                                 - 4_ _

EPA 901.1 Modified , 1.25E+OO 4.52E-01 4.57E-0_2.__~.05Et-OO _ _ _ _ _ pCi/g 1e..00~_1-09 ___ . __TR_G _ . S1032D2AFRF~_v_ ---i--06PJ511- 8 14:20  ; 6/14/2D18 ; 6/14/2018 _ _ 18-0~-- !_ro_m_e!h~n,-~ -EPA901.1 M ~ -~E-01 ; 2 ~ - _.3_:13E-01 ._ 2~~~!-~- __ pCi/g 18-06057-09 ; TRG B103202AFRFC038CV 06/05/1814:20 8/14/2018 ; 611-412018 18-06057 Radium-226 --~PA 9£~odilied , -2:_~E~~ ; __ 6.60E-D_! _ _ 6_:66E-OJ _ 1.09E+OO . _ _ _ _ *- pCl/g 18,.06057-09 .-TRG - -B10 3202AFRFC038CV 18-06057-09 ; ...!R~ ___ B~~c_o_38_cv ______ 06/05/111 14:20 OMJ_~ _ a_1_ 6/1412018 : 6/1412018 18-06057 4:2_0_: 6114/2018

• 6/14/2018. 18-06057
• Amlmony-125 ihorh.1m-2~

EPA901.1 Modified

                                                                                                                                                                                        ~!)~;,;._Modified - ,

5.37E--01 6.06&01 6.06E-01 ... ~~-01 _ _~ - - -* pCil!l_

                                                                                                                                                                                                                   ~2E+OO _;_. 2.45800 _ _ 2~4~~ . . 3.84E+OO . _ - ~ _ -

• _ pCi/g 18-06057-09 , TRG B103202AFRFC038CV 06/05/181420 , 6114/2018 6/14/2018 18-08057 , Thallium-208 EPA 901.1 Modified 6.52E-01 8.71E-01 8.72E-01 1.34E+OO U pCl/g 18-06057..()9 TRG 8103202AFRFC038CV ()611J5i18 14:20 6/1'1/'2018 , 6114/2018 : 18-06057 Uranlum-235 EPA 901.1 Modffiecr*-; 4.49E-02 . 2.33E+OO 2.33E.OO 1.3SE-+-OO U pl;l/g CU=Ccuntlng Uncertalnty:CSU=Comblned Standard Uncertainty (1-61gmal;MDA=Minimal Detec1ad Acltvlty;LCS=Laboratory Control Sample;MBL=Blank:DUP,,Ouplicate;TRG,.Nonnal Sample;OC),,DupUcate Orlginal;U=Non-<letact EBERLINE EBERLINE ANALYTICAL CORPORATl0\'-1 ANALYTICAL 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621

                       ~                                                                                                                                        [571]

Printed: 7/11/2018 1:04 PM Pa~1e 11 of 12 Report To: Patricia Giza SDG: 18-06057 Eberline Analytical H""' _ . . ............ _ , . _ , . . _ . , * . ,, , , . , * . MO**

                                                           ---* Zion Solutions-----**-*-**---_ __ ______ ___ _ _. Purchase Order:
                                                                                                                                                    **. * - -  ~  00,0 - * **. - - -- -- * * * --......* * * . . **  * -,, ,. ~ - ... ,*                                    ...

_ 6771_18_____________ _ 0 -* ***- * , . * , ...... . .. . . . . . . . .. . . . _ . . * .- . ---. ** 0 Final Report of Analysis 101 Shilo~~!~--- . -- -- ---- ___ .... _ *-* _,__AnalysisCategory: ___ ENVIRONMENTAL ____ _ Zion, IL 60099 Sample Matrix: SO Lab Sample Client Sample Receipt Anal)l5is Batch Report Analy1e Method Result cu CSU MDA Qualifier Units ID Type ID Oaht Date Date ID - ~ : ~:_TR~- B103202AFRFC052CV _,_06l0~~~30_:_611~0~4121J18 ~8~--~n~22!_ EPA901.1Mod~~-- 5.56E-01 -~10~.!.. ~~--9.98E-01 .... -Y. _____ pe11g_ _ !_~-~ '. ~ -~~~2AFRFC052CV_ ~~~-. _!~~018 .. 6/'1412~-~ .2.~ _' -~~ver-108m _ ~~;!__M~ified _ __:_~:~8E*~- --* 1-.3BE.OI _i 1.38E-01 1.55E-~~- __ 1:' .... _ _ PC~- 18-06057-10 18-06057-10 TRG TRG B103202AFRFC052CV B1032D2AFRFC052CV

                                                 - - ---                       ------... :-------*--~'*---- --*---*--

06/05/1808:30

• 6/1412016 61'1~18 06/05/1808:30 . 6114/2018 6/1412018 . 16-06057 : Barium-133 1S-06057 : Amencium-241 EPA901.1 Modified EPA901.1 Modified

                                                                                                                                                                                                                                               . -2.!i7E-01
                                                                                                                                                                                                                                               . -6.94E-02
                                                                                                                                                                                                                                                          -          ---*-3.11E-01 2.29E-01 3.11E.01
                                                                                                                                                                                                                                                                                                  -2.29E-01         -                                _ ..... ______

3.47E-01 . 3.06E-01 U - pCi/g __

                                                                                                                                                                                                                                                                                                                                                                              .*_l!_ * - ..* pCVg__

18-06057-10~ 6114/20.iB &114120,a- !S:06057* -* B~m~tlt-214- - EPA901~- ;-9.58~1 - - *4.0SE-01 5.!~~-~-- ____ 0 TRG ' B1032D2AFRFC052CV 06/D5118 08:30 ... 4.00E--01 ~Vg _ 18-06057-10 TRG B103202AFRFC052CV ~ 5 7 ~ 0 - :_ -=-TRG -* ~8~202AFRFC052CV. _ _ _18-06057-10 ; TRG _: B103202AFRFC052CV

                                                      -=-       06/05/18 08:30 06/05/18 08~0                    = ; 6/1412018                     6114/2018
                                                                                                      .6/14/2018 *. si1,iia';"s-1ioeos1 '."
                                                            . 06/05/1808:30 _i 6/14/2018 : 6114/2018 18-06057 18.06057 .         Cobatt-60-*
                                                                                                                                                                -~.~~~1~

Ceslum-137 EPA901,1 Modified EPA 901.1 Modilied . . --3.96E-02

                                                                                                                                                                                                                                               ; - 1.02E-01 EPA901.1 Modi!iad ......,... 1.41E-01 -.*- 1.57E-01
                                                                                                                                                                                                                                                                     - 1.21E-01 8.70E-02 1.21F.-01 8.71E-02 1.57E.01 2.39E-01 2.32E-01 2.77E.01 U

U __ U pCilg pCVg_ pCi/g

                                                                                                                                                                                                                                                                                                                                                                                                      ~~

~8-08057-10 -~~~ __B~2AFRFC052CV

• _ ~16_08:30 _ ~~o~~ ~~1_!~_.,_~~~, Eu~;;;-,;.152 EPA 901.1 Modified _ _;_.:.2.35E.02 - - ~ -- , 4.10E-01 5.12E~J___ .*. -~ _ _ pCVg ~~

18-06057-10 ; TRG , B103202AFRFC052CV 06/05/1808:30 L61!"'2018, ~4/20~~06~-- ~uropium-~ EPA901.1 Mocfdied 2.45E.01 3.17E-01 3.17E-01 2.61E.01 U pCi/g

• 00057-W-+ffiG___B103202AFRFC052CV 06/05/18 08:30 , 6/14/2018 6/14/2018 18-05057 ' Europium-155 ~.A901.1 M~iii~.;**-*:e.ese-02 ~.35E-01 : 2.35E-01 3.95E-01 U pCi/g. *-

~06257-10 .. , _ ~G___ __!!032J2AFRFC052CV 06/05118 OB:30 ' 6/1"l/2018 611412{11_~ ~~7 :~miu~-166m EPA90t.1 Mod~~--;- -1.48E-01 2.85E--01 2.85E.01 2.07E-01 *- U ~ pC~~ ~ 7 - 1 0 _' TRG ___ B1032D2AFRFC052CV 06/05/1808:30 : 6/1412018 6/1412~ . .2.._8-0~?, ~ne-1!~-'--~901.1_Mo~_*_:~..!:.~ . _ 1.65!._~1- -~~1_.~~e-01 _____u_ - - __pCilg 18-06057-1£_ _ -~~- _ B103202AFRFC052CV 06/05/1806:30 :_611412018: ~~4':'!018 _ 18-06057 :. Potassium~ _ EPA901.1 Modified _ , : _ ~~ __2~~-'_2:14E+OO 1.75E+OO _ _ ---*--* ~

• 18-06057-10 ; TRG B103202AFRFC052CV 06J05/1808:30 l 6/1412018 6/1412018 18-06057 Manganese-54 EPA901.1 Modified 9AOE-02 1.29E-01 1.29E-01 2.34E-01 U pCl/g

                                                                                                     -6,'1-4/2018 .,6/1ffl18-* IB-06057 -N!oblum-94 1------- - --- -

18-06057-10 :--TRG - B103202AFRFCD52CV 18-06057-10 ; TRG

                                            -~

B103202AFRFCOS2CV 00/05/1808:30 06/05/1808:30 6114/2018 6114/2018 18-06057 Lead-210 EPA901.1 Modified EPA901.1 Modifted

                                                                                                                                                                                                                                               ! 5.91E-02 1.95E+OO
                                                                                                                                                                                                                                                                         . 1.23E-01 2.24E<-OO . 224E+OO 123E*01                                           2.14E-01 3.25E+OO U

U pCl/g -- pCi/g

 ;~7-10 (_TR~-               B10:~~RFC052CV                     06/0S/1806:30                      ' 6114/2018                     8/1<1/2018  -~7~--~ead-212                                           EPA901_:~~ed                         _'     3.77E-01 ___ 2.74E-01 -- 2.74E.01                                                                        -~..~E--01  . __ _ u___ ._pCi/g_~

18-06057-10 TRG B103202AFRFC052CV 06/05/1808:30 '. 6114/20~, 611412018 1~-0605~- _L1;_ad-21~ ~ 9 0 1 , ! ~ ~ - '. 3.46E--01 -~_EE~1 __ 4.~E-01 ~~- _ -~ _ _ _ pCUg_

• 18-06057-10 '

18-06067-10 TRG~03202AFRFC052CV TRG B103202AFRFC052CV 06/05/1808:30 06.05(1808:30 6/1<l/2018. 6114/2018 6/14/2018' 8114\12~~~ 16-06057

• Promethlum-145

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

EPA901.1 Modified

                                                                                                                                                               ~dlum-_E~ ..__ ~ ~ ~ - - ; 9.58E-0~---~-05E.01 -~~ ~~ -----*- -*- pCl/g_
                                                                                                                                                                                                                                                ;   -8.53E-02
                                                                                                                                                                                                                                                                ---        2.52E-01
                                                                                                                                                                                                                                                                                   ---------*--**---~-*-   2.52E.01                                           3.20E.Ot           U             pCi/g 18-06057-10 : TRG - B103202AFRFC052CV                            OMJ5/180B:30                            6114/2018 6114/2018 18-06057                             Antimony--125                          EPA901.1 Modified                       '   -1.70E-01              3.54E-Ot                         3.54E-01                                          4.96E-01           U              pCi/g

- * * - - - - - _ _ _ .,. * - . - - - - - -- _ _ _ _ _ _ _ _ . ..., - i - - I - - - .- ~ * - ** *- - - - - *-..---- - - ---* 18-06057-10 TRG B103202AFRFC052CV 06/05/18 08:30 8/1412018 . 6/1412018 16-06057 Tho~um-234 EPA 901.1 Modffied 4.90E+OO 2.64E+OO 2.65E+OO 4.02E+OO U pCl/g ~ ~ O _ :_ ~ --~~~2AF~~ OfiKJS/1808:30_ 6/1412018: 6114120~- ~-Th~num-~:-.1PA901:ir.i~ - ~-- 3.40E-01 - ~ e ~ . 4.39E-01 -7.64E-<2.1__ u~-peu;- = 18-06057-10 TRG 8103202AFRFC052CV 06/05/1808:30 6/1-4/2018' 6114/2018. 18-06057 Uranfum-235 EPA901.1 Modified 4.39E-01 1.25E+OO 1.25E+OO 9.13E-01 U pCl/g CU=Counting Uncertalnty;CSUcComblned Standard Uncertainty j1 -slgma);MDA=Minlmal Detec!Atd Ac:tivity;LCS=Laboratcry Control Sarnple;MBL=Blank;DUP=Duplicate:TRG-Normal Sample:DO-Ouplleata Orlglnal;U=Non-<I tteet EBERLINE EBERLINE ANALYTICAL CORPORATION ANALYTICAL 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621

               ~                                                                                                                                              [572]

Printed: 7111/20181:04 PM Page 12 of12 Report To: lo'itirlc OrrJer Details: Patricia Giza 18-06057 Eberline Analytical SDG: Final Report of Analysis Zion Solutions 101 Shiloh Blvd

                                                                                                                  -****--..--- -**-. ...    .. *-* .. *-* *-  **- --**-              Purchase Order:

677118

                                                                                                                                                                                                                      *-- ------- ------~-                 ,.,_. ,_ ---------*--             ......-     --       *-

Analysis Category: *- -

• ENVIRONMENTA,~. **-* -- -* - ----~**--- --

Zion, IL 60099 Sample Matrix: so Lab Sample CUent Sample Receipt Analysis Batch Analyte Method Res~lt CU CSU MDA Qualifl&r , Report 10 Type JD Date Date Date ID Unifi! 18-08057-1_!_ . --~~~ ___B ~ ~ ~ R F C ~ _ **- + 0_~18 ?9.!7.__ .-~1412_0~8 6114/2018 18-06057 : ActlnltJm-~ *-

• EPA901.1 Molfdied _  : * . 5 . ~ - 3.99E-01 __.___ 4.00E-01 **-*- 7.92E-l:1 _ _ _ U _ _ _ ..E_Cilg _

18-06057-11 , TRG B103202AFRFC059CV __ 06/0511809:27 6/1412018 6/14/2018 18-06057 , Silver-10Bm EPA901.1 Mocfdied ' 4.14&02 1.07&01 1.07E-01 130E-01 U pCi/g -~S?:-.£i ::*~. TRG~ * ~~32~!_FC059CV 06/05118 09:27 .. ~,~~~o~ __e.114~8. 16-06057 : Arnenclnn-2:'~ =E~~91_)1_i~~-°-'!:.~~ i_ :7.31E-02 _ 2~~~ -.* 2.16E-01 ** ~]:.§~~I=- u __ _ -* pCi/g - ~~.::!.!.- __!R~- B10~FC059CV_ - - --~5118, ()9-~ -* ..6!!_41201~- ~~4~-~- 18-06067 ' Barium-133 EPA 901.1 M~if"~ _ _ ; _::*~~: -~~-?3_ ~~E-02  ; ___1:~~:~ - _u__ - pCl/g - - _1~~~-1.!.._: _~G--~~2AFRFC~c:y ____ _ **- _ ~ 1 8 ~:2~-- * -*~~412~1!_ .!~018 _* *-1~.2.___!lls~~. _ -~~-1-M~d~- _ _;_ 8.65E-01 . ~.13E~ _ _ 3~1. _ __6:'!8E-01 _ -- - - *.* y<?L_ 18-06057-11 _ ____!~G-* _ ~103202AFRFC059CV _t~'2~f18093? _ 6/1412018 ** ~~4f2018 18-06057 Co~lt~?- _ ':!:~~M~_i~d  : _8.BOE-02 _ 1.26E-01 *. 126E-01 ___ 1.61E-01 __ U _ _ pCi/g

.18-06057-11 '.                  TRG           8103202AFRFC059CV                 06/05/1809:27           6/14/2018    6/1412018       18-06057

• Cesium-134 EPA901.1 Modif",ed -1.73E-02 5.016--02 . 5.015-02 1.44E-01 U pCl/g i - - - ... - - - - : - - - - - - - *- - * * - - - - - _ _ ___ _ _ ,._ __ -* --- -* ,* *

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

1ll-06057-11 . TRG B103202AFRFC059CV 06/05/1809:27 6/1412018 6/1412018 1&-06057 : Cesium-137 EPA901.1 Modified  : 2.58E-02 . 1.166--01 : 1.16E-01 1.89E-01 U pCi/g ~001-11*:- -TRG ~ *e1ixi202AFRFC059CV oorosMB rszl- *-;;;;41i2ora E~~p1-;:;~1ii"" ooi°:-i-M~-~ u - ---;;c;;; -

                                                                    *-       -                                       51141201s

• 1a-osos1-: EPA .2.20e-o,-. -- ~~ - 4.44e-0,
• J.10E::ci1*. - -

18-06057-11 .,. - TRG _,_ eioi202AFRFC059CV

                                                                       -     - 06/05118 09:27 ' 6/14/2018 ' 6/1412018                 18-06~ Europium-154 EPA 901.1 Motfrtied
                                                                                                                                                                                      *- .--*--*-*-*-        *1.28E-01         2.75E-01
                                                                                                                                                                                                                         ..------~ ..._.          ___

2.75E-0i'*-*-*-1$1E::01' -

                                                                                                                                                                                                                                                                 --**    -- ---**         u-- -*
                                                                                                                                                                                                                                                                                                       '    pCl/g

~~-1~ _ _!~G- __ 6103202/>FRFC~ _ _ ~~~:27 _ : _6/141201!3 ' - ~ ~06.?!7__ Europru_~ . _EPA901.1 Mo~",'_l , .. 1.56E-01. . ~ ~ * - -* ~-'~-8~ __3.~0E::<'1 _ _~ - - _ pCV; _ ,_1&-0605.7_:!::_ .. TRG - - 8103202AFRFC059CV_ - - -~~~~-~2._~ . 6~14/2018 ~~~ _:!-!'6E_5I.._~o~ium-166~-~g~~~:_2-~~ 1.88E-01 1.89E-01_ ~~1 ~ . pCl/g. _

 ..!..~~~ . _ ~~- _                            8103202A!°RFC059CV

• 06/0511809:27 _ 61'1412018' 6/14/2018 *. . 18-06057 . _lodin... 129 _-- _EPA801.1_Modified _ i 1.49E-01 ____ 9.73&02 . 9.76£-02 _ 1.68E-01 ._ u __ _ pCi/g 18-06057-11 TRG 8103202AFRFC059CV 06/05118 09:27 6/1412018 . 6/1412018 18-06057 Potassium-40 EPA901.1 Modified ' 6.70E+OO . 1.91E-+OO : 1.95E..OO 1.83E+oo pCi/g i----- ...... _ . , . _ . _ _ _ __ _ _ - * -* - . . . . . * - - - * - - -  : ---* - - - - - ,.._ - - - - - . - - * - - - - - - - - - - - -* ------- - - - - -- * - - - - - - -

_!_~6057-11 __ ; __~ - ' - _B103202AFRFC~- _ - - _ ~~~ ~:2::.__. ~4120.!_B: .6/1412~18' 18-060~~~n~~ese-54 EPA90~M~~~- .i -~~::_02 _ _?-~ _ 7.9BE-02 1.67E-01 __ u_.:__ pCVg __ _

~'!~.7:11 ' _ ~ _!1~RFC059CV                                                     o~~~' ~ ~ 8 - 6/1412018                              18-06057             Niobium.-94            EPA901.1 Modified           8.89E-02 _ *  ...2-~~-* ~.:?~ ..-2.:~~!.                                     U                pCilg_ _

_ ~ ~ 1 1 _ . : _ ~ G - - B10J20ZAFRFC059CV _ ~ ~ ? _ __ . 5!_~!!3 , 6/1412~1*~ .. : _ ~ 7 Lead-210 EPA 901.1 Modmad 1.9"E+-OO _ . ...3.:EE."'°~: ~ _ . 3.801:-+00- * .~-- pCi/g 18-06057-11 TRG B103202AFRFC059CV 06AJ5/18 09:27 . 6/1412016. 611412016 18-06057 Lead-212 EPA901.1 Modified 5.13&01 . 1.69E-01 1.71E-01 J.17E-01 *- . _ _ pCi/g *- 18--06057"i1 *- TRG B103202AFRFC059CV- 06t05/11! ~ :-~ 0 1 e- : 6/14/:ro1a - : - ~ - ' Leacl-214 '*- c.. EPA901.1 Modified --;- 5.57E--01  : 2.25E-01 ' 2.27E-01 J.49E-01 ' pCi/g 18-06D57-11 TRG B103202AFRFC059CV 06/05/1809:27

6/1<112018: 6/14/2018 18-06057 . Promelhlum-145 EPA90U Modified

                                                                                                                                                                                                           - - - -1.30E-01
                                                                                                                                                                                                         ; 6.26E-02
                                                                                                                                                                                                                                    --*----------- 1.30E-01          2.17E-01
                                                                                                                                                                                                                                                                                         -U - - *pCl/g         -     ........

~57-11 1-----*- . .-. --~--B103202AFRFC059CV

                           - - --                         ------ __ . .06/05/1809:27
                                                                                  . ._______ ,       ~

6/14/2018: 6/14/2018

                                                                                                                   .                  16-06057"*:         Radlum-226              EPA.901.tMod~i              B.65E~1 **;~'E--01-~
                                                                                                                                                                                                       -**- . - - - - - - - * - - - -- - - --      3.16&01            6.0BE-01
                                                                                                                                                                                                                                                                                          *---- --- -*      pct.lg
---~*- *--------------------.--

18-06057-11 18-06057-1~ _ TRG TRG B103202AFRFC059CV B103202AFRFC059CV O&ID5/1809:27 6114/2018' 6M412018 ceJ0511.~_09~. _6!:!_~~~B _ .!_8.:_06057__ 18-06057 . Antimony-125 Thonum-234 EPA901.1 Modified EPA901.1 Modified l 1.19E-01 1.65E-<l1 _ . 2.fOE+OO..: .. 2.00E+<lO _ 2.00E+OO t.65E-01 4.01E-01 _ 2.90E+OO _ U U

                                                                                                                                                                                                                                                                                                     '**--- pCi/g
                                                                                                                                                                                                                                                                                                     . - - pCi/g      _

18-06057-11 18--06057-11 TRG TRG B103202AFRFC059CV B103202AFRFC059CV 06/05/1809:27 06/05/1809:27 6114/2018 6/14/2018 6/1412018 6/1412018 1B-06057 :

                                                                                                                                     .18-06057     :

Thallium-208 Uranium-235 EPA901.t Modffled

                                                                                                                                                                                             ----~

EPA901.1 Modified 5.82E-01 1.89E+OO 3.B1E-01 1.22E+OO 3.82E-01 1.22E+OO 5.82E--01

                                                                                                                                                                                                                                                                         - - -- U-8.44E-01 U                pCilg pCi/g CUcCountlng Uncerialnty;CSU=Comblned Standard Un~ertalnty (1-sigma);MDA:Mlnlmal o.toctvd Acllvlty;LCS=Laboratory ContrQI Sample;MBL=Blank;DUP..Dupl;c.te;TRG-Nonnal Sample;DO=Dupllcate Origlnal;U=Non-<letect ERLINE                                      EBERLINE ANALYTICAL CORPORATION                             _____;___________________

ANALYTICAL 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/4Bl-0683 FAX 865/483-4621 [573]

ZS-WM-131 18-06057 Revision 0 Information Use REC'D JUN 14: 2018 Attachment I - Chain-of-Custody Farm Sample ID Sample Matrix Sample Sample Container Sample Date Sample Time Analysis Preservative Remarks Log Type Type Vol Unit Type Qty

                                                                                                                                .mJmg D103202AFRWC004CV   '!:Y.A Concrete Concrete   57.94   cm3     Puck        !   5,!Jl/2018     1510      HTD         None      0.0-0.5"'

11U3g B103202AFRWC0.27CV N/A Concrete !;;2ncrete ~ cm3 Puck  ! 5/31/.2018 1450 HTD None 0.0--0.5"' 133.92g D103202AFRFC0072V N/A Concrete Concrete 57,94 cm3 Puck  ! 6/5/2018

                                                                                               .rn.2      HTD         None       0.0-0.5

164.58g B103202AFRFCOS7CV ~ Conc(!tc Concrete 57.94 cm3 Puck  ! 6/5/2018 1015  !!IQ None 0.0--0.5" 120.65g 8103202AFRFC061CV m ~oncrete Concrete 57.94 cm3 Puck 1 6/5/2018 0842 HTD None 0.0-0.5" 100.40g BI03202AFRFC038CV ~ Concrete Concrete 5L2! cm3 ~  ! 6/S/2018 1420 .um None 0.0-0.5" 82.32g 0 D103202AFRFCOS2CV ~ Concrete Concrete 57.94 cm3 Puck l 6/5/2018 0830 nm None 0.0--0.5" llS.91 \ B103:Z02AFRFCOS9CV NIA Concrete Concrete 57.94 cm3 Puck  ! 6/5/2018

                                                                                               .om        .um         None       0.0-0.S" I                                       i-----

Iv

                             ---           --         ~
                                                        - --            -    If
                          ~

[574]

ZS-WM-131 Revision 0 Information Use Laboratory: Date Submitted To Lab: Ship Container No.: Cooler Temperature: Eberline Labs Relinquished by: Date Time: Received by: Dale: (mm/dd/YYY}'): Time: 06113/1018 JackMucia

                                             /~D   Received by:                                 Date: (mm/dd/yyyy):

Ii/So Time: fed,tJ.{;'tefOve1n/ + Time: 08/6 Time: Comments ANALYSIS Full Suite-HTD RE: Email to Mike McDougall 18 ~* 06 0 57 PRIORITY 24 hour turnaround P0#677118 REti> JUN 1 2018 *' [575]}}