Text

03-L1-SUB-CDR Release Record R.2 Final
	ML22269A391
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	09/07/2022
From:	Yetter R; LaCrosseSolutions
To:	; Office of Nuclear Material Safety and Safeguards
Shared Package
ML22269A395	List: ML22269A388; ML22269A390; ML22269A391; ML22269A392; ML22269A393; ML22269A394;
References
	LS-2022-0019
	Download: ML22269A391 (272)
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LACROSSESOLUTIONS LA CROSSE BOILING WATER REACTOR FINAL STATUS SURVEY RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION REVISION 2

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Digitally signed by Robert F Yetter III DN: C=US, O=EnergySolutions, CN=Robert F Yetter III, Robert F Yetter III E=rfyetteriii@energysolutions.com Reason: I am the author of this document Location: your signing location here PREPARED BY / DATE: Date: 2022-08-09 15:03:44 Foxit PhantomPDF Version: 9.7.0 R. F. Yetter III, FSS Specialist REVIEWED BY / DATE:

S. Roberts, SVP Radiological Programs Digitally signed by Scott Zoller Scott Zoller DN: C=US, OU=D&D Decommissioning, O=Energysolutions, CN=Scott Zoller, E=sgzoller@energysolutions.com Reason: I am approving this document Location:

APPROVED BY / DATE: Date: 2022-08-09 14:28:31 Foxit PhantomPDF Version: 9.4.1 S. Zoller, FSS Manager 1

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

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

2. SURVEY UNIT DESCRIPTION ....................................................................................................................... 5

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

4. DATA QUALITY OBJECTIVES ...................................................................................................................... 9

5. SURVEY DESIGN ............................................................................................................................................. 13

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

7. SURVEY RESULTS .......................................................................................................................................... 20

8. QUALITY CONTROL ...................................................................................................................................... 29

9. INVESTIGATIONS AND RESULTS .............................................................................................................. 29

10. REMEDIATION AND RESULTS ................................................................................................................... 30

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN ........................................................................ 30

12. DATA QUALITY ASSESSMENT (DQA) ....................................................................................................... 30

13. ANOMALIES ..................................................................................................................................................... 31

14. CONCLUSION .................................................................................................................................................. 31

15. REFERENCES................................................................................................................................................... 31

16. ATTACHMENTS .............................................................................................................................................. 32 ATTACHMENT 1 - FIGURE ................................................................................................................................... 33 ATTACHMENT 2 - SCAN DATA ............................................................................................................................. 35 ATTACHMENT 3 - SIGN TEST ............................................................................................................................... 40 ATTACHMENT 4 - QUALITY CONTROL ASSESSMENT ...................................................................................... 42 ATTACHMENT 5 - CONSULTATION TRIGGERS FOR RESIDENTIAL SOIL CONCENTRATIONS ................... 44 ATTACHMENT 6 - GRAPHICAL PRESENTATIONS ............................................................................................. 46 ATTACHMENT 7 - SAMPLE ANALYTICAL REPORTS ......................................................................................... 50 ATTACHMENT 8 - GEL LABORATORIES ANALYTICAL REPORTS ................................................................. 208 2

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS LIST OF TABLES Table 3 Statistical Quantities for Cs-137 and Co-60 from the Characterization Survey .................................. 7 Table 3 Off-site Analysis for Characterization Samples ..................................................................................... 8 Table 4 Dose Significant Radionuclides and Mixture for Soil .......................................................................... 11 Table 4 Base Case DCGLs for Soil ...................................................................................................................... 12 Table 4 Operational DCGLs for Soil ................................................................................................................... 12 Table 5 Soil Surrogate Ratio ............................................................................................................................... 13 Table 5 Action Levels for Survey Unit L1-SUB-CDR ....................................................................................... 14 Table 5 Systematic Sample Locations ................................................................................................................. 16 Table 5 Investigation Levels ................................................................................................................................ 17 Table 5 Synopsis of Survey Design...................................................................................................................... 18 Table 7 Synopsis of Scan Results ........................................................................................................................ 20 Table 7 Summary of Gamma Spectroscopy Results for Samples Comprising the Statistical Sample Population ........................................................................................................................................................... 24 Table 7 Basic Statistical Properties of Systematic Sample Population ............................................................. 25 Table 7 Summary of Gamma Spectroscopy Results for Investigational Samples ........................................... 26 Table 7 Summary of Off-Site Analysis Results .................................................................................................. 26 Table 7 Summary of Gamma Spectroscopy Results for the QC Sample ......................................................... 27 Table 7 Sum-of-Fractions for Systematic and QC Samples .............................................................................. 28 Table 7 Sum-of-Fractions for Investigational Samples ..................................................................................... 28 Table 16 Survey Unit L1-SUB-CDR Complete Scan Data .............................................................................. 36 Table 16 Survey Unit L1-SUB-CDR Sign Test .................................................................................................. 41 Table 16 Survey Unit L1-SUB-CDR QC Assessment ........................................................................................ 43 LIST OF FIGURES Figure 16 Survey Unit L1-SUB-CDR Systematic Sample Locations Map ...................................................... 34 Figure 16 Quantile Plot for Cs-137 Concentration ............................................................................................ 47 Figure 16 Histogram for Cs-137 Concentration ................................................................................................. 48 Figure 16 Retrospective Power Curve for Survey Unit L1-SUB-CDR ............................................................. 49 3

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable DQA Data Quality Assessment DQO Data Quality Objective DCGL Derived Concentration Guideline Level DCGLS Soil Derived Concentration Guideline Level FSS Final Status Survey GPS Global Positioning System HSA Historical Site Assessment HTD Hard-to-Detect IC Insignificant Contributors LACBWR La Crosse Boiling Water Reactor LBGR Lower Bound of the Gray Region LTP License Termination Plan MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration NaI Sodium Iodide OpDCGLS Soil Operational Derived Concentration Guideline Level QAPP Quality Assurance Project Plan QC Quality Control RA Radiological Assessment ROC Radionuclides of Concern SOF Sum-of-Fractions TEDE Total Effective Dose Equivalent UBGR Upper Bound of the Gray Region UCL Upper Confidence Limit 4

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS

1. EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey unit L1-SUB-CDR, Stack, Pipe Tunnel, Reactor Plant Generator Plant Area (RPGPA) Excavation, has been generated in accordance with LaCrosseSolutions procedure LC-FS-PR-009, Final Status Survey Data Reporting (Reference 1) and satisfies the requirements of Section 5.11 of the La Crosse Boiling Water Reactor License Termination Plan (LACBWR LTP) (Reference 2).

An FSS sample plan for this survey unit was developed in accordance with LaCrosseSolutions procedure LC-FS-PR-002, Final Status Survey Package Development (Reference 3), the LACBWR LTP, and with guidance from NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) (Reference 4).

Survey unit L1-SUB-CDR has a MARSSIM classification of 1. A survey plan was designed based upon use of the Sign Test as the nonparametric statistical test for compliance. Both the Type I () and Type II () decision error rates were set at 0.05. As a systematic sample population, fourteen (14) soil samples were acquired from the survey unit. In addition, soil scanning was performed on 100% of the total surface area in the survey unit. The analytical results for all soil samples taken in survey unit L1-SUB-CDR indicate that the maximum Sum-of-Fractions (SOF), considering the concentration of all applicable Radionuclides of Concern (ROC) either by direct measurement or by inference, is equal to 0.4594 when applying the respective Operational Derived Concentration Guideline Levels (OpDCGLS) for soil. Therefore, the null hypothesis is rejected and survey unit L1-SUB-CDR is acceptable for unrestricted release. The mean SOF when applying the respective Base Case DCGLs (DCGLS) for soil is 0.0408. This SOF equates to a dose for the survey unit of 1.0190 mrem/yr.

2. SURVEY UNIT DESCRIPTION Survey Unit L1-SUB-CDR is an impacted Class 1 excavation survey unit within open land survey unit L1-010-101. The survey unit consists of the underlying soil post-removal of the Pipe Tunnel, RPGPA, and Stack foundations. The surface area of the survey unit is 431 m2.

The boundary of the survey unit and the location of the soil samples were defined using a Global Positioning System (GPS). Refer to Attachment 1 of this report for figures and maps depicting survey unit L1-SUB-CDR.

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS

3. CLASSIFICATION BASIS Based on the Historical Site Assessment (HSA) (Reference 5), survey unit L1-010-101 was identified as a Class 1 area. As survey unit L1-SUB-CDR consists of the underlying soils from L1-010-101, it is also designated as Class 1. The following summarizes the results of the characterization survey for survey unit L1-010-101.

The initial site characterization surveys performed by EnergySolutions were conducted between October 9, 2014, and August 6, 2015. In total, twelve (12) surface soil samples and eighteen (18) subsurface soil samples were collected in the survey unit. All samples were analyzed by the on-site gamma spectroscopy system. For surface soil samples, Cs-137 was detected at concentrations above Minimum Detectable Concentration (MDC) in all twelve (12) samples, at a maximum concentration of 1.07E+00 pCi/g, and Co-60 was detected at concentrations above MDC in two (2) samples, at a maximum concentration of 2.87E-01 pCi/g. For subsurface soil samples, Cs-137 was detected at concentrations above MDC in eight (8) of the samples, at a maximum concentration of 1.61E-01 pCi/g. Co-60 was not detected at concentrations above MDC for subsurface soil samples. A summary of the analyses for the surface soil and subsurface soil samples taken during site characterization are presented in Table 3-1.

Five (5) surface soil samples and two (2) subsurface soil samples from characterization were sent to Test America Laboratories for off-site analysis. A summary of the off-site analyses is presented in Table 3-2.

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Table 3 Statistical Quantities for Cs-137 and Co-60 from the Characterization Survey Surface Soil Co-60 Cs-137

of Samples 12

>MDC 2 12 Mean (pCi/g) 8.00E-02 2.15E-01 Median (pCi/g) 5.80E-02 1.00E-01 Max (pCi/g) 2.87E-01 1.07E+00 Min (pCi/g) 4.80E-02 3.20E-02 Standard Deviation (pCi/g) 6.60E-02 2.96E-01 Subsurface Soil Co-60 Cs-137

of Samples 18

>MDC 0 8 Mean (pCi/g) 7.80E-02 6.60E-02 Median (pCi/g) 5.20E-02 5.40E-02 Max (pCi/g) 5.16E-01 1.61E-01 Min (pCi/g) 4.70E-02 3.30E-02 Standard Deviation (pCi/g) 1.09E-01 3.50E-02

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Table 3 Off-site Analysis for Characterization Samples L1010101- L1010101- L1010101- L1010101- L1010101- L1010101- L1010101-Radionuclide CJ-GS- CJ-GS- CJ-GS- QJ-GS- QJ-GS- QJ-GS- QJ-GS-002-SS 009-SS 010-SS 001-SB 001-SS 002-SB 002-SS H-3 3.64E-01 4.41E-01 3.77E-01 1.38E+00 C-14 8.96E-01 6.76E-01 6.79E-01 6.77E-01 Fe-55 2.43E+00 2.19E+00 2.15E+00 4.19E+00 Ni-59 1.85E+00 1.90E+00 1.75E+00 2.01E+00 Co-60 2.40E-02 4.00E-02 2.86E-01 2.40E-02 1.80E-02 1.70E-02 1.50E-02 Ni-63 3.04E+00 3.04E+00 2.93E+00 3.32E+00 Sr-90 3.35E-01 4.40E-01 3.38E-01 3.57E-01 Nb-94 2.00E-02 2.00E-02 2.50E-02 1.50E-02 1.20E-02 1.10E-02 1.00E-02 Tc-99 5.79E-01 5.87E-01 6.20E-01 5.21E-01 Cs-137 2.33E-01 1.85E-01 4.13E-01 2.00E-02 1.47E-01 1.49E-01 5.90E-02 Pm-147 8.00E-01 3.17E+00 7.72E-01 9.78E-01 Eu-152 5.60E-02 5.60E-02 6.20E-02 5.00E-02 3.40E-02 4.00E-02 3.30E-02 Eu-154 1.61E-01 1.81E-01 2.47E-01 1.43E-01 1.12E-01 1.09E-01 9.60E-02 Eu-155 6.60E-02 5.00E-02 5.70E-02 4.40E-02 4.40E-02 4.00E-02 3.60E-02 Np-237 1.90E-02 6.00E-03 1.90E-02 1.60E-02 Pu-238 4.60E-02 3.90E-02 4.10E-02 4.00E-02 Pu-239/240 2.30E-02 2.30E-02 2.20E-02 1.60E-02 Pu-241 1.97E+00 1.83E+00 1.95E+00 2.09E+00 Am-241 5.80E-02 4.20E-02 5.10E-02 1.50E-02 1.60E-02 1.70E-02 2.00E-02 Am-243 2.30E-02 2.10E-02 2.90E-02 1.70E-02 Cm-243/244 2.10E-02 1.90E-02 1.40E-02 2.20E-02 Note: Bold values indicate concentration greater than MDC. Unbolded values indicate the MDC value. All values in pCi/g. Blank cells indicate that a particular radionuclide was not included in the analysis.

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Section 5.1 of the LTP states that the actual Insignificant Contributor (IC) dose will be calculated for each individual sample result using the DCGLs from Table 4 of TSD RS-TD-313196-004, LACBWR Soil DCGL, Basement Concrete DCGL, and Buried Pipe DCGL (Reference 6) for soil. If the IC dose calculated is less than the IC dose assigned for DCGL adjustment, then no further action will be taken. If the actual IC dose calculated from the sample result is greater than the IC dose assigned for DCGL adjustment, then a minimum of five (5) additional investigation samples will be taken around the original sample location. Each investigation sample will be analyzed by the on-site gamma spectroscopy system and sent for HTD analysis (full suite of radionuclides from LTP Table 5-1). As with the original sample, the actual IC dose will be calculated for each investigation sample. In this case, the actual calculated maximum IC dose from an individual sample observed in the survey unit will be used to readjust the DCGLs in that survey unit. If the maximum IC dose exceeds 10%, then the additional radionuclides that were the cause of the IC dose exceeding 10% will be added as additional ROC for that survey unit. The survey unit-specific DCGLs used for compliance, the ROC for that survey unit, and the survey data serving as the basis for the IC dose adjustment will be documented in the release record for the survey unit.

An assessment of the results of continuing characterization confirmed that the IC dose is unchanged (dose less than 2.5 mrem/yr).

Based upon review of the historical information, the results of the characterization survey data, and completion of a final Survey Unit Classification Worksheet, the correct final classification of survey unit L1-SUB-CDR was determined to be Class 1.

4. DATA QUALITY OBJECTIVES (DQO)

FSS planning and design relies on a properly executed 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, utilized in accordance with MARSSIM, is described in the LACBWR LTP. The appropriate design for a given survey was developed using the DQO process as outlined in Appendix D of MARSSIM. A summary of seven steps of the DQO process are outlined as follows.

The DQO process incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis. Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition. The baseline condition is technically known as the null hypothesis. Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection. In designing the survey plan, the underlying assumption, or null hypothesis was that residual activity in the survey unit exceeded the release criteria. Rejection of the null

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS hypothesis would indicate that residual activity within the survey unit does not exceed the release criteria. Therefore, the survey unit would satisfy the primary objective of the FSS sample plan.

The primary objective of the FSS sample plan is to demonstrate that the level of residual radioactivity in survey unit L1-SUB-CDR did not exceed the release criteria specified in the LTP and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA).

EnergySolutions TSD RS-TD-313196-001, Radionuclides of Concern during LACBWR Decommissioning (Reference 7) established the basis for an initial suite of potential ROC for decommissioning. LTP Chapter 2 provides detailed characterization data that describes the results of surveys taken of soil. Surface and subsurface soil samples were taken in each impacted open land survey units and analyzed for the presence of plant-derived radionuclides. The results of surface and subsurface soil characterization in the impacted area surrounding LACBWR indicate that there is minimal residual radioactivity in soil.

IC were determined consistent with the guidance contained in Section 3.3 of NUREG-1757, Volume 2, Revision 1, Consolidated Decommissioning Guidance - Characterization, Survey, and Determination of Radiological Criteria, Final Report (Reference 8). In all soil and concrete scenarios, Cs-137, Co-60, Sr-90, Eu-152 and Eu-154 contribute nearly 100%

of the total dose. The remaining radionuclides were designated as IC and are eliminated from further detailed evaluation. Therefore, the final ROCs for LACBWR soil, basement concrete and buried piping are Cs-137, Co-60, Sr-90, Eu-152 and Eu-154.

LTP, Section 6.14.1 discusses the process used to derive the ROC for the decommissioning of LACBWR, including the elimination of IC from the initial suite. Table 4-1 presents the ROC for the decommissioning of soil at LACBWR and the normalized mixture fractions based on the radionuclide mixture.

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Table 4 Dose Significant Radionuclides and Mixture for Soil Fraction of Total Activity Radionuclide (normalized)(1)

Co-60 0.064 Sr-90 0.098 Cs-137 0.829 Eu-152 0.005 Eu-154 0.003 (1) Based on maximum percent of total activity from Table 22 of RS-TD-313196-001, normalized to one for the dose significant radionuclides.

The LTP, Section 5.2 states that each radionuclide-specific Base Case DCGL is equivalent to the level of residual radioactivity (above background levels) that could, when considered independently, result in a Total Effective Dose Equivalent (TEDE) of 25 mrem/yr to an Average Member of the Critical Group. To ensure that the summation of dose from each source term is 25 mrem/yr or less after all FSS is completed, the Base Case DCGLs are reduced based on an expected, or a priori, fraction of the 25 mrem/yr dose limit from each source term. The reduced DCGLs (i.e., Operational DCGLs) can be related to the Base Case DCGLs as an expected fraction of dose based on an a priori assessment of what the expected dose should be based on the results of site characterization, process knowledge, and the extent of planned remediation. The Operational DCGL is then used as the DCGL for the FSS design of the survey unit (e.g., calculation of surrogate DCGLs, investigation levels).

Details of the Operational DCGLs derived for each dose component and the basis for the applied a priori dose fractions are provided in LC-FS-TSD-002, Operational Derived Concentration Guideline Levels for Final Status Survey (Reference 9).

Multiple ROCs are known to be present at LACBWR. The dose contribution from each ROC is accounted for using the SOF to ensure that the total dose from all ROC does not exceed the dose criterion. A Base Case DCGL that is established for the average residual radioactivity in a survey unit is equivalent to a DCGLW. In Class 1 land survey units, the DCGLW can be multiplied by Area Factors to obtain a Base Case DCGL that represents the same dose to an individual for residual radioactivity over a smaller area within a survey unit.

At LACBWR, compliance is demonstrated through the summation of dose from five (5) distinct source terms (i.e., basements, soils, buried pipe, above-ground structures, and groundwater) for the end-state. When applied to soil, the DCGLs are expressed in units of activity per unit of mass (pCi/g).

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS For LACBWR, soil is defined as a layer of soil beginning at the surface but extending to a depth of 1 m to allow for flexibility in compliance demonstration if contamination deeper than 0.15 m is encountered. Based on characterization data and historical information, there are no expectations of encountering a source term geometry that is comprised of a clean surface layer of soil over a contaminated subsurface soil layer. EnergySolutions TSD RS-TD-313196-004 and LTP, Section 6.8 provide the exposure scenarios and modeling parameters that were used to calculate the site-specific soil DCGLs. The adjusted soil DCGLs for the unrestricted release of open land survey units as provided in Chapter 6, Section 6.16.1 are reproduced in Table 4-2. The IC percentages for the most limiting basement scenario were used to adjust the DCGLs for soil to account for the dose from the eliminated IC radionuclides.

Table 4 Base Case DCGLs for Soil DCGLS Radionuclide (pCi/g)

Co-60 10.6 Sr-90 5470 Cs-137 48.3 Eu-152 23.6 Eu-154 21.9 The Operational DCGLs are then used as the DCGL for the FSS design of the survey unit (e.g., calculation of surrogate DCGLs, investigation levels). The OpDCGLS for the unrestricted release of soil are provided in Table 4-3.

Table 4 Operational DCGLs for Soil OpDCGLS Radionuclide (pCi/g)

Co-60 3.83 Sr-90 1970.45 Cs-137 17.39 Eu-152 8.51 Eu-154 7.89 12

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the Operational DCGL. Survey instrument response checks were required prior to issuance and after the instrument had been used. Control and accountability of survey instruments was required to assure the quality and prevent the loss of data.

As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. The actual reported value was used as the recorded FSS result for measurement and/or sample values that are less than MDC. Negative values were recorded as zero. Results were not reported as less than MDC (< MDC). Sample report summaries included unique sample identification, analytical method, radionuclide, result, uncertainty, laboratory data qualifiers, units, and the observed MDC.

In accordance with the LTP, for laboratory analysis, MDCs less than 10% of the Operational DCGL were preferable while MDCs up to 50% of the Operational DCGL were acceptable.

The minimum acceptable MDC for measurements obtained using field instruments was 50% of the applicable Operational DCGL.

5. SURVEY DESIGN The level of effort associated with planning a survey is based on the complexity of the survey and nature of the hazards. Guidance for preparing FSS plans is provided in procedure LC-FS-PR-002, Final Status Survey Package Development.

The DQO process validated that Co-60, Sr-90, Cs-137, Eu-152, and Eu-154 would be the ROC in survey unit L1-SUB-CDR as presented in LTP Section 5.1. During the data analysis of the FSS results, concentrations for the HTD ROC Sr-90 are inferred using a surrogate approach. Cs-137 is the principle surrogate radionuclide for Sr-90. During characterization, both Sr-90 and Cs-137 was positively detected in all thirty (30) concrete core samples assessed in the Reactor Building, Tunnel, and Waste Treatment Building. The 95% Upper Confidence Limit (UCL) of the Cs-137 fractions was chosen to represent the overall nuclide mix for soils/buried pipe, the Reactor Building, and the Waste Gas Tank Vault. The surrogate ratio for soil is given in Table 5-1.

Table 5 Soil Surrogate Ratio Radionuclides Ratio Sr-90/Cs-137 0.502 The equation for calculating a surrogate DCGL is as follows:

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Equation 1 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide Using the Operational DCGLs presented in Table 4-3 and the ratio from Table 5-1, the following surrogate calculation was performed:

Equation 2

The surrogate Operational DCGL that was used for Cs-137 in this survey unit for direct comparison of sample results to demonstrate compliance was 17.31 pCi/g.

The action levels for survey unit L1-SUB-CDR are based on the Operational DCGL and are presented in Table 5-2.

Table 5 Action Levels for Survey Unit L1-SUB-CDR Action Level ROC (pCi/g)

Co-60 3.83(1)

Cs-137 17.31(2)

Eu-152 8.51(1)

Eu-154 7.89(1)

(1) Based on the Operational DCGL.

(2) Based on the surrogate adjusted DCGL of Cs-137 while inferring Sr-90.

The Sign Test was selected as the non-parametric statistical test. The use of the Sign Test did not require the selection or use of a background reference area, which simplified survey 14

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS design and implementation. This approach was conservative since it included background Cs-137 as part of the sample set.

The number of soil samples for FSS was determined in accordance with procedure LC-FS-PR-002. The relative shift (/) for the survey unit data set is defined as shift (), which is the Upper Boundary of the Gray Region (UBGR), or the DCGL (SOF of 1), minus the Lower Bound of the Gray Region (LBGR) (SOF of 0.5), divided by sigma (), which is the standard deviation of the data set used for survey design. The optimal value for / should range between one (1) and three (3). The largest value the / can have is three (3). If the calculated value of / exceeds three (3), an adjusted value of three (3) will be used for /.

The / for survey unit L1-SUB-CDR, based on Cs-137 and Co-60 data for subsurface soil samples collected during characterization of L1-010-101 (standard deviation of 0.03), was calculated as follows:

Equation 3

/ = (1-0.5) / 0.03 = 16.67 As the calculated relative shift was greater than three (3), a value of three (3) was used as the adjusted /. Both the Type I error (i.e., value) and the Type II error (i.e., value) was set at 0.05. The sample size from Table 5.5 of MARSSIM that equates to the Type I and Type II error of 0.05 for use with the Sign Test is an N value of fourteen (14).

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

As the survey unit was classified as Class 1, sample locations were selected based on a systematic triangular grid with a random starting point. The systematic locations of the soil samples were selected using Visual Sample Plan (VSP), in accordance with LC-FS-PR-002.

Input parameters included use of aerial photographs and the GPS route of the boundary of the excavation. The systematic coordinates generated with VSP were integrated with a GPS to identify sample locations in the field. Table 5-3 lists the systematic samples collected for FSS and the corresponding GPS coordinates, based on the Wisconsin State Plane North American Datum 1983 coordinate system.

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Table 5 Systematic Sample Locations Sample ID Northing Easting L1-SUB-CDR-FSGS-001-SB 570930.6618 1642154.6934 L1-SUB-CDR-FSGS-002-SB 570930.6618 1642175.6046 L1-SUB-CDR-FSGS-003-SB 570948.7714 1642165.1490 L1-SUB-CDR-FSGS-004-SB 570948.7714 1642186.0602 L1-SUB-CDR-FSGS-005-SB 570966.8811 1642154.6934 L1-SUB-CDR-FSGS-006-SB 570966.8811 1642196.5159 L1-SUB-CDR-FSGS-007-SB 570966.8811 1642217.4271 L1-SUB-CDR-FSGS-008-SB 570984.9908 1642081.5040 L1-SUB-CDR-FSGS-009-SB 570984.9908 1642186.0602 L1-SUB-CDR-FSGS-010-SB 571003.1004 1642091.9596 L1-SUB-CDR-FSGS-011-SB 571003.1004 1642112.8709 L1-SUB-CDR-FSGS-012-SB 571003.1004 1642154.6934 L1-SUB-CDR-FSGS-013-SB 571021.2101 1642102.4153 L1-SUB-CDR-FSGS-014-SB 571021.2101 1642123.3265 Six (6) investigational samples were collected at locations of scanning alarms. In total, twenty (20) soil samples were collected for the FSS of survey unit L1-SUB-CDR.

Inadvertently, the investigational samples were not labeled correctly, the coordinates were not collected, and the locations were not marked on the survey maps. Descriptions of where the investigational samples were collected (i.e., in what scan lanes) and how they were labeled were provided in the Field Logs. The collection of the investigational samples is described in detail in Section 6 of this Release Record.

The LACBWR LTP, Section 5.1 states that soil samples will be collected during FSS to confirm the HTD to surrogate radionuclide ratio. Ten percent (10%) of the FSS samples collected from open land survey units will be analyzed for HTD ROC. Only the HTD radionuclide included as ROC (Sr-90) will be analyzed in the FSS confirmatory samples. In addition, if any sample has a SOF of 10% of the Operational DCGL or more, it must be sent for HTD ROC analysis. For samples with positive results for both the HTD ROC and the corresponding surrogate radionuclide (Cs-137), the HTD surrogate ratio will be derived and compared against the 95% UCL ratio (see Table 5-1). If the derived ratio from the confirmatory samples exceeds the 95% UCL ratio, then the area-specific ratio as determined by actual survey data will be used.

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS The selection of five (5) soil samples (L1-SUB-CDR-FSGS-008-SS, L1-SUB-CDR-FSGS-009-SS, L1-SUB-CDR-FSGS-011-SS, L1-SUB-CDR-FSGS-012-SS, and L1-SUB-CDR-FSGS-014-SS) met the requirement that a minimum of 10% of the samples collected for the FSS of survey unit L1-SUB-CDR be analyzed for HTD ROC. Four (4) of the five (5) total samples sent for off-site HTD analysis were selected because of a sample SOF greater than the 10% threshold described in the LTP.

The implementation of quality control measures as referenced by LTP Chapter 5, Section 5.9 and LaCrosseSolutions LC-QA-PN-001, Final Status Survey Quality Assurance Project Plan (QAPP) (Reference 10) includes the collection of a soil sample for split sample analysis on 5% of the soil samples taken in a survey unit with the locations selected at random. One (1) soil sample, L1-SUB-CDR-QSGS-014-SS, was designated for split sample QC analysis for the FSS of this survey unit.

The LTP, Section 5.6.4.4 and Table 5-15, specifies that for Class 1 open land survey units, surface scans will be performed on 100% of the surface area in the survey unit. For survey unit L1-SUB-CDR, 100% scan coverage equates to 431 m2. To encapsulate the entire area of the survey unit, one hundred (100) half-meter wide scan lanes were established in the survey unit. A map of survey unit is provided in Attachment 1.

For this Class 1 excavation survey unit, the Investigation Levels for area scanning and soil sample measurement results are those levels specified in LTP Chapter 5, Table 5-16, and are reproduced below in Table 5-5.

Table 5 Investigation Levels Direct Investigation Classification Scan Investigation Levels Levels

>Operational DCGL or >MDCscan if Class 1 MDCscan is greater than Operational >Operational DCGL DCGL Table 5-6 provides a synopsis of the survey design for survey unit L1-SUB-CDR.

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Table 5 Synopsis of Survey Design Feature Design Criteria Basis Survey Unit Surface Area 431 m2 GPS x = 0.03 x UBGR = SOF of 1 Number of Systematic Samples 14 x LBGR = SOF of 0.5 (N) x Type I & II error = 0.05 x / = 3 (adjusted) x MARSSIM Table 5.5 x Co-60: 3.83 pCi/g x Sr-90: 1970.45 pCi/g x Cs-137: 17.39 pCi/g Operational DCGLs for soil, DCGLS and Action Levels (Surrogate Cs-137 LTP Chapter 5, Table 5-6, Release Record Table 5-2 DCGL: 17.31 pCi/g) x Eu-152: 8.51 pCi/g x Eu-154: 7.89 pCi/g Scan and Direct Investigation

>Operational DCGL LTP Chapter 5, Table 5-16 Levels Scan Areal Coverage 431 m2, 100% areal coverage LTP Chapter 5, Table 5-15 1 sample LTP Chapter 5, Section 5.1 HTD ROC Analysis 5 (4 with SOF > 0.1) Actual Number Obtained QC 1 split sample selected at random LTP Chapter 5, Section 5.9

6. SURVEY IMPLEMENTATION For survey unit L1-SUB-CDR, compliance with the unrestricted release criteria was demonstrated through a combination of soil scanning with a Ludlum Model 44-10 gamma detector and the sampling of soil for isotopic analysis.

An FSS Supervisor performed a visual inspection and walk-down of the survey unit on September 11, 2017, prior to performing FSS. The purpose of the walk-down was to assess the physical condition of the survey unit, evaluate access points and travel paths, and identify potentially hazardous conditions. At the time of survey, the soil in the survey unit was dry and free of any considerable constraint for the collection of samples and scan measurements.

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS FSS field activities were conducted under the FSS Sample Plan, which included DQOs, survey design, detailed FSS instructions, job safety analysis, and related procedures for reference. FSS field activities were projected to take four (4) working days to complete.

Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job. A Field Log was used to document field activities and other information pertaining to the performance of the FSS. FSS field activities commenced on September 13, 2017, and were concluded on September 18, 2017.

A total of one hundred (100) different scan lanes, constituting an areal coverage of 431 m2, were scanned using a Ludlum 2350-1 paired with a Ludlum Model 44-10 (2x 2) sodium iodide (NaI) detector. The background was established as the average of five (5) 1-minute static measurements, while maintaining the detector 6 from the soil. In survey unit L1-SUB-CDR, background ranged from 4,995 cpm up to 5,641 cpm.

All designated scan areas were scanned using a Ludlum 2350-1 paired with a Model 44-10 2x 2 NaI detector operated in the rate-meter mode and using audio response. The probe was positioned no more than 3 from the ground and was moved at a scan speed of approximately 0.5 meters per second. In accordance with RS-TD-313196-006, Ludlum Model 44-10 Detector Sensitivity (Reference 11), scan MDC was sufficient to detect residual radioactivity at the action level (adjusted surrogate DCGL of 17.31 pCi/g, which was based on the surrogate adjusted DCGL of Cs-137 while inferring Sr-90). Complete scan results are provided in Attachment 2.

Six (6) investigational samples were collected at locations of scanning alarms in scan lanes CDR14 through CDR18 and W11, W16, and W17 (see Table 7-1). Inadvertently, the investigational samples were not labeled correctly, the coordinates were not collected, and the locations were not marked on the survey maps. The six (6) investigational samples were labeled as CDR #4 and CDR-NRC 5 through CDR-NRC #9.

The fourteen (14) systematic sample locations were marked with flags based on GPS coordinates provided. Each soil sample consisted of approximately one (1) liter of soil. The soil sample media was sifted to remove stones and other media larger than one (1) centimeter in diameter. All soil samples were collected, controlled, transported, stored, and transferred to the on-site laboratory using the Chain-of-Custody process from LC-FS-PR-012, Chain of Custody Protocol (Reference 12), and in accordance with LC-FS-PR-004, Sample Media Collection for Site Characterization and Final Status Survey (Reference 13),

LC-FS-PR-005, Sample Media Preparation for Site Characterization and Final Status Survey (Reference 14), and LC-FS-PR-001, Sample Storage (Reference 15).

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS The survey design specified that a minimum of one (1) sample was required for HTD ROC analysis. In total, five (5) samples (L1-SUB-CDR-FSGS-008-SS, L1-SUB-CDR-FSGS-009-SS, L1-SUB-CDR-FSGS-011-SS, L1-SUB-CDR-FSGS-012-SS, and L1-SUB-CDR-FSGS-014-SS) were selected for HTD radionuclide analysis. Four (4) of the five (5) total samples sent for off-site HTD analysis were selected because of a sample SOF greater than the 10% threshold described in the LTP.

The implementation of survey specific QC measures included the collection of one (1) sample (L1-SUB-CDR-QSGS-014-SS) for duplicate sample analysis.

7. SURVEY RESULTS All areas identified in the FSS sample plan were scanned for elevated activity levels. A total of eight (8) alarms were verified during scanning, which prompted the collection of six (6) investigational soil samples. Table 7-1 provides an overview of the scan results for all scan lanes (identified as CDR01 through W43) and QC locations (identified with a QC).

Complete scan results are provided in Attachment 2.

Table 7 Synopsis of Scan Results Highest Action # of Logged Investigation Scan Area Level(1) Scan Reading Samples Alarms (cpm) (cpm)

CDR01 18,429 27,196 0 0 CDR02 17,420 27,196 0 0 CDR03 16,956 27,196 0 0 CDR04 18,267 27,196 0 0 CDR05 17,404 27,196 0 0 CDR06 17,423 27,196 0 0 CDR07 19,271 27,196 0 0 CDR08 18,921 27,196 0 0 CDR09 16,520 27,196 0 0 CDR10 12,365 27,196 0 0 CDR11 4,845 27,196 0 0 CDR12 5,149 27,196 0 0 CDR13 4,529 27,196 0 0 CDR14 30,902 27,196 1 3

CDR15 35,749 27,196 1 20

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Highest Action # of Logged Investigation Scan Area Level(1) Scan Reading Samples Alarms (cpm) (cpm)

CDR16 38,108 27,196 1 CDR17 46,676 27,196 1 CDR18 48,247 27,196 1 CDR19 12,203 27,196 0 0 CDR20 11,497 27,196 0 0 CDR21 12,321 27,196 0 0 CDR22 12,103 27,196 0 0 E01 10,325 27,423 0 0 E02 11,475 27,423 0 0 E03 9,392 27,423 0 0 E04 10,213 27,423 0 0 E05 10,154 27,423 0 0 E06 10,211 27,423 0 0 E07 10,541 27,423 0 0 E08 10,554 27,423 0 0 E09 10,566 27,423 0 0 E10 11,682 27,423 0 0 E11 11,012 27,423 0 0 E12 12,262 27,423 0 0 E13 11,733 27,423 0 0 E14 12,026 27,423 0 0 E15 12,594 27,423 0 0 E16 18,572 27,423 0 0 E17 15,775 27,423 0 0 E18 13,118 27,423 0 0 E19 13,103 27,423 0 0 E20 13,015 27,423 0 0 E21 12,904 27,423 0 0 E22 11,783 27,139 0 0 E23 12,448 27,139 0 0 E24 12,350 27,139 0 0 E25 14,924 27,139 0 0 21

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Highest Action # of Logged Investigation Scan Area Level(1) Scan Reading Samples Alarms (cpm) (cpm)

E26 14,183 27,139 0 0 E27 15,003 27,139 0 0 E28 13,785 27,139 0 0 E29 13,991 27,139 0 0 E30 15,243 27,139 0 0 E31 15,963 27,139 0 0 E31 QC 15,709 27,781 0 0 E32 20,983 27,139 0 0 E32 QC 16,641 27,781 0 0 E33 21,026 27,139 0 0 E33 QC 19,820 27,781 0 0 E34 19,800 27,139 0 0 E34 QC 20,269 27,781 0 0 E35 16,245 27,139 0 0 W01 14,744 27,139 0 0 W01 QC 12,971 27,781 0 0 W02 13,623 27,139 0 0 W02 QC 14,665 27,781 0 0 W03 15,236 27,139 0 0 W03 QC 15,339 27,781 0 0 W04 17,457 27,139 0 0 W04 QC 15,495 27,781 0 0 W05 14,765 27,234 0 0 W06 23,801 27,139 0 0 W07 15,830 27,139 0 0 W08 20,737 27,139 0 0 W09 26,142 27,139 0 0 W10 26,458 27,139 0 0 W11 36,821 27,139 1 1 W12 19,633 27,234 0 0 W13 26,792 27,234 0 0 W14 24,176 27,234 0 0 22

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Highest Action # of Logged Investigation Scan Area Level(1) Scan Reading Samples Alarms (cpm) (cpm)

W15 23,172 27,234 0 0 W16 29,183 27,234 1 1 W17 30,449 27,234 1 1 W18 23,237 27,234 0 0 W19 20,961 27,234 0 0 W20 16,876 27,234 0 0 W21 17,718 27,234 0 0 W22 15,917 27,234 0 0 W23 14,901 27,234 0 0 W24 16,234 27,135 0 0 W25 18,184 27,135 0 0 W26 18,609 27,135 0 0 W27 18,213 27,135 0 0 W28 18,088 27,135 0 0 W29 17,300 27,135 0 0 W30 17,452 27,135 0 0 W31 16,810 27,135 0 0 W32 16,995 27,135 0 0 W33 15,805 27,135 0 0 W34 16,613 27,135 0 0 W35 16,549 27,135 0 0 W36 18,195 27,423 0 0 W37 18,677 27,423 0 0 W38 17,445 27,423 0 0 W39 20,117 27,423 0 0 W40 20,136 27,423 0 0 W41 21,127 27,423 0 0 W42 21,625 27,423 0 0 W43 21,518 27,423 0 0 (1) Action Level based on the average background plus 22,140 cpm (from RS-TD-313196-006).

The Action Level for scanning was established as the average background plus 22,140 cpm.

The 22,140 cpm value is equal to the scanning instrumentation response to a Cs-137 23

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS concentration of 12 pCi/g. This value is equivalent to 22% of the adjusted DCGL for soil that was used before Operational DCGLs were established. Typically, the 25% IC adjusted DCGL value (13 pCi/g) is used for the Action Level calculation, but a more conservative value was selected for this survey unit.

Evaluating the logged scan data to the correct and current Action Levels based on the Operational DCGL shows that nearly all the scan measurements would have produced alarms, and in turn would have triggered the collection of additional investigational soil samples. It was discovered that background values for the scan grids for this survey unit were erroneously collected in the environmental lab and were not representative of actual background levels. The lab backgrounds ranged from 4,995 cpm to 5,641 cpm. These backgrounds are lower than the activity of scan measurements collected for FSS, which ranged from 4,529 cpm to 48,247 cpm (as shown in Table 7-1 above). If the average background for the sample locations (17,440 cpm) was applied to the scan grids, and the scan data was evaluated against the current Action Levels based on the Operational DCGL, only the same eight (8) alarms from the original survey (shown in Table 7-1) would be reproduced. Because 100% of the soil in the survey unit was scanned and no soil samples collected for FSS resulted in ROC concentrations above the Operational DCGLs, the probability of discovering an elevated soil sample is very low, even had additional investigational samples been collected.

The on-site laboratory analyzed the fourteen (14) soil samples taken for non-parametric statistical testing using the on-site gamma spectroscopy system. A summary of the results for the fourteen (14) samples collected for non-parametric statistical testing is provided in Table 7-2. Gamma spectroscopy results revealed that Cs-137 was positively identified in thirteen (13) of the systematic samples, at a maximum concentration of 6.25E+00 pCi/g.

Co-60 was identified in three (3) of the systematic samples, at a maximum concentration of 3.42E-01 pCi/g. The concentration for Sr-90 was inferred based on the ratio specified in Table 5-1. The complete gamma spectroscopy reports are presented in Attachment 7. The basic statistics for the systematic sample population are summarized in Table 7-3.

Table 7 Summary of Gamma Spectroscopy Results for Samples Comprising the Statistical Sample Population Co-60 Cs-137 Eu-152 Eu-154 Sr-90 Sample ID (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

L1-SUB-CDR-FSGS-001-SB 8.39E-02 3.70E-02 1.14E-01 5.54E-02 1.86E-02 L1-SUB-CDR-FSGS-002-SB 6.28E-02 1.77E-01 0.00E+00 3.05E-02 8.89E-02 L1-SUB-CDR-FSGS-003-SB 8.26E-02 3.30E-01 1.65E-01 2.12E-02 1.66E-01 24

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Co-60 Cs-137 Eu-152 Eu-154 Sr-90 Sample ID (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

L1-SUB-CDR-FSGS-004-SB 8.76E-02 2.44E-01 8.55E-02 2.49E-02 1.22E-01 L1-SUB-CDR-FSGS-005-SB 5.95E-02 7.85E-01 5.48E-02 0.00E+00 3.94E-01 L1-SUB-CDR-FSGS-006-SB 5.29E-02 6.35E-01 5.26E-02 2.30E-01 3.19E-01 L1-SUB-CDR-FSGS-007-SB 1.01E-01 3.44E-01 3.28E-02 4.24E-03 1.73E-01 L1-SUB-CDR-FSGS-008-SB 7.16E-02 6.94E-01 0.00E+00 3.03E-03 3.48E-01 L1-SUB-CDR-FSGS-009-SB 3.42E-01 6.25E+00 0.00E+00 7.19E-02 3.14E+00 L1-SUB-CDR-FSGS-010-SB 5.26E-02 1.11E+00 5.67E-03 9.21E-02 5.57E-01 L1-SUB-CDR-FSGS-011-SB 1.83E-01 2.80E+00 7.91E-02 6.47E-02 1.41E+00 L1-SUB-CDR-FSGS-012-SB 1.37E-01 1.60E+00 1.36E-02 5.59E-02 8.03E-01 L1-SUB-CDR-FSGS-013-SB 2.88E-02 7.18E-02 1.32E-01 1.58E-01 3.60E-02 L1-SUB-CDR-FSGS-014-SB 1.03E-01 2.28E+00 5.35E-02 5.64E-02 1.14E+00 Note: Bold values indicate concentrations greater than MDC.

Table 7 Basic Statistical Properties of Systematic Sample Population Mean Median Max Min Std. Dev. BcDCGL Avg. SOF Avg. Dose ROC (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) per ROC Per ROC Co-60 1.03E-01 8.33E-02 3.42E-01 2.88E-02 7.88E-02 1.06E+01 0.0098 0.2440 Cs-137 1.24E+00 6.65E-01 6.25E+00 3.70E-02 1.67E+00 4.83E+01 0.0257 0.6417 Eu-152 5.63E-02 5.31E-02 1.65E-01 0.00E+00 5.31E-02 2.36E+01 0.0024 0.0597 Eu-154 6.20E-02 5.57E-02 2.30E-01 0.00E+00 6.40E-02 2.19E+01 0.0028 0.0708 Sr-90 6.22E-01 3.34E-01 3.14E+00 1.86E-02 8.38E-01 5.47E+03 0.0001 0.0028 The on-site laboratory analyzed the six (6) investigational soil samples using the on-site gamma spectroscopy system. A summary of the analytical results for the investigational soil samples is provided in Table 7-4. Gamma spectroscopy results revealed that Cs-137 was positively identified in all six (6) of the investigational samples, at a maximum concentration of 1.57E+00 pCi/g. Co-60 was identified in four (4) of the investigational samples, at a maximum concentration of 8.11E-02 pCi/g. Inadvertently, Eu-152 was not included in the gamma spectroscopy analysis of the investigational samples. The concentrations for Sr-90 were inferred based on the ratio specified in Table 5-1. The complete gamma spectroscopy reports are presented in Attachment 7.

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Table 7 Summary of Gamma Spectroscopy Results for Investigational Samples Co-60 Cs-137 Eu-154 Sr-90 Sample ID (pCi/g) (pCi/g) (pCi/g) (pCi/g)

CDR #4 7.68E-02 1.52E+00 1.78E-02 7.63E-01 CDR-NRC 8.11E-02 7.16E-01 1.58E-02 3.59E-01

5 CDR-NRC 4.80E-02 7.31E-01 8.92E-03 3.67E-01

6 CDR-NRC 1.06E-02 3.87E-02 2.59E-02 1.94E-02

7 CDR-NRC 0.00E+00 1.59E-01 7.94E-04 7.98E-02

8 CDR-NRC 7.29E-02 1.57E+00 2.32E-02 7.88E-01

9 Note: Bold values indicate concentrations greater than MDC.

Samples L1-SUB-CDR-FSGS-008-SS, L1-SUB-CDR-FSGS-009-SS, L1-SUB-CDR-FSGS-011-SS, L1-SUB-CDR-FSGS-012-SS, and L1-SUB-CDR-FSGS-014-SS were sent off-site to GEL Laboratories for analysis of the full suite of radionuclides. The results are presented in Table 7-5 below. An IC dose assessment for the samples was performed. The maximum calculated IC dose is 0.2861 mrem/yr, which is below the 2.5 mrem/yr limit provided in the LTP for DCGL adjustment.

Table 7 Summary of Off-Site Analysis Results L1-SUB- L1-SUB- L1-SUB- L1-SUB- L1-SUB-CDR-FSGS- CDR-FSGS- CDR-FSGS- CDR-FSGS- CDR-FSGS-Radionuclide 008-SS 009-SS 011-SS 012-SS 014-SS (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

H-3 1.27E+00 3.39E+00 -2.87E-01 1.54E+00 2.67E+00 C-14 7.20E-01 -8.51E-01 3.52E-01 1.18E-01 1.46E+00 Fe-55 -2.22E+00 3.82E+00 -9.50E-01 -1.52E-01 5.27E-01 Ni-59 -1.72E+00 -6.49E-01 -2.54E-01 7.17E-01 -1.92E+00 Co-60 2.45E-02 6.95E-01 2.29E-01 0.00E+00 1.92E-01 Ni-63 2.73E+00 9.70E+00 1.77E+00 1.58E+00 1.95E+00 Sr-90 2.48E-01 -1.78E-01 7.87E-02 1.63E-01 7.95E-02 Nb-94 -9.84E-03 2.20E-04 1.59E-02 -7.59E-03 7.26E-03 Tc-99 -2.08E-01 -3.10E-02 -1.02E-01 3.08E-01 -7.83E-01 Cs-137 8.04E-01 1.15E+01 3.77E+00 2.21E+00 2.77E+00 26

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS L1-SUB- L1-SUB- L1-SUB- L1-SUB- L1-SUB-CDR-FSGS- CDR-FSGS- CDR-FSGS- CDR-FSGS- CDR-FSGS-Radionuclide 008-SS 009-SS 011-SS 012-SS 014-SS (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

Eu-152 -5.50E-02 -8.43E-03 1.19E-02 6.59E-02 4.72E-02 Eu-154 -1.04E-02 2.73E-02 4.26E-02 -8.13E-03 -7.85E-02 Eu-155 3.93E-02 6.39E-03 1.20E-02 -1.45E-02 -2.68E-02 Np-237 8.76E-03 -1.37E-03 1.81E-03 0.00E+00 -2.03E-03 Pu-238 1.37E-02 1.07E-01 7.90E-03 1.75E-02 1.60E-02 Pu-239/240 1.83E-04 1.18E-01 1.66E-02 1.76E-02 1.11E-02 Pu-241 -1.46E+00 2.53E+00 -1.07E+00 -8.49E-01 -9.30E-01 Am-241 2.41E-02 5.56E-01 7.71E-02 1.13E-01 7.96E-02 Am-243 6.36E-02 4.35E-02 1.07E-02 2.95E-03 1.38E-02 Cm-243/244 -1.95E-03 9.31E-03 9.30E-04 -1.59E-03 -1.92E-03 Note: Bold values indicate positively identified radionuclide activities.

The implementation of survey specific QC measures included the collection of one (1) sample (L1-SUB-CDR-QSGS-014-SS) for duplicate sample analysis. The on-site laboratory analyzed the QC sample using the on-site gamma spectroscopy system. A summary of the analytical results for the QC sample is provided in Table 7-6. Gamma spectroscopy results revealed that Cs-137 was positively identified in the QC sample. The concentration for Sr-90 was inferred based on the ratio specified in Table 5-1.

Table 7 Summary of Gamma Spectroscopy Results for the QC Sample Co-60 Cs-137 Eu-152 Eu-154 Sr-90 Sample ID (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

L1-SUB-CDR-QSGS-014-SS 7.49E-02 2.88E-01 1.18E-01 0.00E+00 1.45E-01 Note: Bold values indicate concentrations greater than MDC.

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

Equation 4 C1 C2 Cn

............ d1 DCGL1 DCGL2 DCGLn Where: Cn = concentration of radionuclide n DCGLn = DCGL of radionuclide n.

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS The results of the unity rule calculation for the ROC in the systematic sample population for survey unit L1-SUB-CDR are provided in Table 7-7.

Table 7 Sum-of-Fractions for Systematic and QC Samples Fraction of Operational DCGL Sample ID SOF Co-60 Cs-137 Eu-152 Eu-154 Sr-90 L1-SUB-CDR-FSGS-001-SB 0.0219 0.0021 0.0134 0.0070 0.0000 0.0445 L1-SUB-CDR-FSGS-002-SB 0.0164 0.0102 0.0000 0.0039 0.0000 0.0305 L1-SUB-CDR-FSGS-003-SB 0.0216 0.0190 0.0194 0.0027 0.0001 0.0627 L1-SUB-CDR-FSGS-004-SB 0.0229 0.0140 0.0100 0.0032 0.0001 0.0502 L1-SUB-CDR-FSGS-005-SB 0.0155 0.0451 0.0064 0.0000 0.0002 0.0673 L1-SUB-CDR-FSGS-006-SB 0.0138 0.0365 0.0062 0.0292 0.0002 0.0858 L1-SUB-CDR-FSGS-007-SB 0.0264 0.0198 0.0039 0.0005 0.0001 0.0506 L1-SUB-CDR-FSGS-008-SB 0.0187 0.0399 0.0000 0.0004 0.0002 0.0592 L1-SUB-CDR-FSGS-009-SB 0.0893 0.3594 0.0000 0.0091 0.0016 0.4594 L1-SUB-CDR-FSGS-010-SB 0.0137 0.0638 0.0007 0.0117 0.0003 0.0902 L1-SUB-CDR-FSGS-011-SB 0.0478 0.1610 0.0093 0.0082 0.0007 0.2270 L1-SUB-CDR-FSGS-012-SB 0.0358 0.0920 0.0016 0.0071 0.0004 0.1369 L1-SUB-CDR-FSGS-013-SB 0.0075 0.0041 0.0155 0.0200 0.0000 0.0472 L1-SUB-CDR-FSGS-014-SB 0.0269 0.1311 0.0063 0.0071 0.0006 0.1720 L1-SUB-CDR-QSGS-014-SS 0.0196 0.0166 0.0139 0.0000 0.0001 0.0501 Systematic Samples Number of Systematic Samples = 14

of Systematic Samples with SOF > 1 = 0

of Systematic Samples with SOF > 0.1 (HTD Assessment) = 4 Max Individual Systematic Sample SOF = 0.4594 Mean Systematic Sample SOF = 0.1131 The results of the unity rule calculation for the ROC in the investigational sample population for survey unit L1-SUB-CDR are provided in Table 7-8.

Table 7 Sum-of-Fractions for Investigational Samples Fraction of Operational DCGL Sample ID SOF Co-60 Cs-137 Eu-154 Sr-90 CDR #4 0.0201 0.0874 0.0023 0.0004 0.1101 28

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS CDR-NRC #5 0.0212 0.0412 0.0020 0.0002 0.0645 CDR-NRC #6 0.0125 0.0420 0.0011 0.0002 0.0559 CDR-NRC #7 0.0028 0.0022 0.0033 0.0000 0.0083 CDR-NRC #8 0.0000 0.0091 0.0001 0.0000 0.0093 CDR-NRC #9 0.0190 0.0903 0.0029 0.0004 0.1127 Investigational Samples Number of Investigational Samples = 6

of Investigational Samples with SOF > 1 = 0 Max Individual Investigational Sample SOF = 0.1127

8. QUALITY CONTROL The on-site laboratory processed one (1) duplicate sample (L1-SUB-CDR-QSGS-014-SS) using gamma spectroscopy analysis. The data was evaluated using USNRC acceptance criteria specified in Inspection Procedure No. 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring (Reference 16). There was not an acceptable agreement between standard and duplicate results using Cs-137 in the comparison. As an investigation, the samples were evaluated under the same procedure using K-40, and the sample concentrations were compared to the OpDCGL. The result of this evaluation determined that there was an acceptable agreement between standard and comparison samples using K-40, and the concentrations of Cs-137 were well below the OpDCGL. Due to the concentrations of Cs-137 reported well below the OpDCGL and the successful comparison of the results using K-40, the survey data was deemed acceptable and representative of actual radiological conditions in the survey unit. Refer to Attachment 4 for data and quality control analysis results.

9. INVESTIGATIONS AND RESULTS Six (6) soil samples were collected to investigate alarms in scan lanes CDR14 through CDR18 and W11, W16, and W17. The investigational samples were analyzed using the on-site gamma spectroscopy system. Gamma spectroscopy results revealed that Cs-137 was positively identified in all six (6) of the investigational samples, at a maximum concentration of 1.57E+00 pCi/g. Co-60 was identified in four (4) of the investigational samples, at a maximum concentration of 8.11E-02 pCi/g. The maximum SOF for investigational samples, when compared to the Operational DCGL, is 0.1127.

29

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS

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

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN There were no addendums to the FSS plan.

12. DATA QUALITY ASSESSMENT (DQA)

The DQO sample design and data were reviewed in accordance with LC-FS-PR-008, Final Status Survey Data Assessment (Reference 17) for completeness and consistency.

Documentation was complete and legible. Surveys and the collection of samples 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 6).

The measurement results indicated that all samples were less than a SOF of one (1) when compared to the OpDCGLS.

Although MARSSIM states that the Sign Test need not be performed in the instance that no measurements surpass the Operational DCGL, the test was conducted to demonstrate coherence to the statistical principles of the DQO process. The Sign Test was performed on the data and compared to the original assumptions of the DQOs. The evaluation of the Sign Test results clearly demonstrates that the survey unit passes the unrestricted release criteria, thus, the null hypothesis is rejected. The results of the Sign Test are presented in Attachment 3.

The preliminary data review consisted of calculating basic statistical quantities (e.g., mean, median, standard deviation). All data was considered valid including negative values, zeros, values reported below the MDC, and values with uncertainties that exceeded two standard deviations. The mean and median values for each ROC were well below the respective Operational DCGLs. Also, the retrospective power curve shows that a sufficient number of samples were collected to achieve the desired power. Therefore, the survey unit meets the unrestricted release criteria with adequate power as required by the DQOs.

30

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS The mean of all identified isotopes are less than the Consultation Triggers for Residential Soil Concentration depicted in Table H.1 of NUREG 1757, Vol.1, Rev. 2 (MOU Table 1).

The full table is included in Attachment 5 of this release record.

The data for Cs-137 is presented graphically through a frequency plot and quantile plot. All graphical presentations are provided in Attachment 6.

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

14. CONCLUSION Survey unit L1-SUB-CDR has met the DQOs of the FSS plan. The ALARA criteria as specified in Chapter 4 of the LTP were achieved. The Elevated Measurement Comparison for soils was not used and remediation was not required.

All identified ROC were used for statistical testing to determine the adequacy of the survey unit for FSS. Evaluation of the data shows that none of the systematic ROC concentration values exceeds the OpDCGLS; therefore, in accordance with LTP Section 5.11, the survey unit meets the release criteria.

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 soil in survey unit L1-SUB-CDR is 1.0190 mrem/yr TEDE, based on the average concentration of the ROC in samples used for non-parametric statistical sampling.

Survey unit L1-SUB-CDR is acceptable for unrestricted release.

15. REFERENCES

1. LC-FS-PR-009, Final Status Survey Data Reporting

2. La Crosse Boiling Water Reactor License Termination Plan

3. LC-FS-PR-002, Final Status Survey Package Development

4. NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)

5. La Crosse Boiling Water Reactor Historical Site Assessment

6. RS-TD-313196-004, LACBWR Soil DCGL, Basement Concrete DCGL, and Buried Pipe DCGL 31

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS

7. RS-TD-313196-001, Radionuclides of Concern during LACBWR Decommissioning

8. NUREG-1757, Volume 2, Revision 1, Consolidated Decommissioning Guidance -

Characterization, Survey, and Determination of Radiological Criteria, Final Report

9. LC-FS-TSD-002, Operational Derived Concentration Guideline Levels for Final Status Survey

10. LC-QA-PN-001, Final Status Survey Quality Assurance Project Plan

11. RS-TD-313196-006, Ludlum Model 44-10 Detector Sensitivity

12. LC-FS-PR-012, Chain of Custody Protocol

13. LC-FS-PR-004, Sample Media Collection for Site Characterization and Final Status Survey

14. LC-FS-PR-005, Sample Media Preparation for Site Characterization and Final Status Survey

15. LC-FS-PR-001, Sample Storage

16. USNRC Inspection Procedure No. 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring

17. LC-FS-PR-008, Final Status Survey Data Assessment

16. ATTACHMENTS Attachment 1 - Figure Attachment 2 - Scan Data Attachment 3 - Sign Test Attachment 4 - Quality Control Assessment Attachment 5 - Consultation Triggers for Residential Soil Concentrations Attachment 6 - Graphical Presentations Attachment 7 - Sample Analytical Reports Attachment 8 - GEL Laboratories Analytical Reports 32

FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR ~

STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS ATTACHMENT 1 FIGURE 33

FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR ~

STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Figure 16 Survey Unit L1-SUB-CDR Systematic Sample Locations Map Legend 0 Sa mples D Survey Unit (43 1 m 2) 13 (E) 1642 102.41 53 (N) 57 1021.21 01 10 (E) 1642091.9596

/ (N) 57 1003 .1004

/

/ 14 (E) 1642123.3265

/ (N) 57 1021. 2101

/

12 (E) 16421 54 .6934 (N) 57 1003 .1 004 09 (E) 16421 86 .0602

/ (N) 570984 .9908 08-QC (E) 164208 1.504 (N) 570984.9908 05 (E) 1642 154.6934 (N) 570966 .88 11 - - --1-,i.1 06 (E) 16421 96.5159 (N) 570966 .88 11 03 (E) 16421 65 .1 49 (N) 570948 .77 14 07 (E) 164221 7.4271 (N) 570966 .88 11 01 (E) 16421 54 .6934 (N) 570930 .66 18

~ 0 ' '

N o 10 3) ., Feot Sample Locations - Pipe Tunnel LACBWRSite Genoa, WI

,-;::::=::= Date 01/30f.2019 L.\CROSSESOU-Tm,:s- Drawing 17082905.t>

34

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS ATTACHMENT 2 SCAN DATA 35

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Table 16 Survey Unit L1-SUB-CDR Complete Scan Data Scan Avg Action Detector Detector M2350-1 Logged Scan Location Background Level Type ID ID Result Alarms (cpm) (cpm) (cpm) 44-10 318218 120636 CDR01 18,429 5,056 27,196 0 44-10 318218 120636 CDR02 17,420 5,056 27,196 0 44-10 318218 120636 CDR03 16,956 5,056 27,196 0 44-10 318218 120636 CDR04 18,267 5,056 27,196 0 44-10 318218 120636 CDR05 17,404 5,056 27,196 0 44-10 318218 120636 CDR06 17,423 5,056 27,196 0 44-10 318218 120636 CDR07 19,271 5,056 27,196 0 44-10 318218 120636 CDR08 18,921 5,056 27,196 0 44-10 318218 120636 CDR09 16,520 5,056 27,196 0 44-10 318218 120636 CDR10 12,365 5,056 27,196 0 44-10 318218 120636 CDR11 4,845 5,056 27,196 0 44-10 318218 120636 CDR12 5,149 5,056 27,196 0 44-10 318218 120636 CDR13 4,529 5,056 27,196 0 44-10 318218 120636 CDR14 30,902 5,056 27,196 1 44-10 318218 120636 CDR15 35,749 5,056 27,196 1 44-10 318218 120636 CDR16 38,108 5,056 27,196 1 44-10 318218 120636 CDR17 46,676 5,056 27,196 1 44-10 318218 120636 CDR18 48,247 5,056 27,196 1 44-10 318218 120636 CDR19 12,203 5,056 27,196 0 44-10 318218 120636 CDR20 11,497 5,056 27,196 0 44-10 318218 120636 CDR21 12,321 5,056 27,196 0 44-10 318218 120636 CDR22 12,103 5,056 27,196 0 44-10 162398 126195 E01 10,325 5,283 27,423 0 44-10 162398 126195 E02 11,475 5,283 27,423 0 44-10 162398 126195 E03 9,392 5,283 27,423 0 44-10 162398 126195 E04 10,213 5,283 27,423 0 44-10 162398 126195 E05 10,154 5,283 27,423 0 44-10 162398 126195 E06 10,211 5,283 27,423 0 44-10 162398 126195 E07 10,541 5,283 27,423 0 44-10 162398 126195 E08 10,554 5,283 27,423 0 44-10 162398 126195 E09 10,566 5,283 27,423 0 36

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Scan Avg Action Detector Detector M2350-1 Logged Scan Location Background Level Type ID ID Result Alarms (cpm) (cpm) (cpm) 44-10 162398 126195 E10 11,682 5,283 27,423 0 44-10 162398 126195 E11 11,012 5,283 27,423 0 44-10 162398 126195 E12 12,262 5,283 27,423 0 44-10 162398 126195 E13 11,733 5,283 27,423 0 44-10 162398 126195 E14 12,026 5,283 27,423 0 44-10 162398 126195 E15 12,594 5,283 27,423 0 44-10 162398 126195 E16 18,572 5,283 27,423 0 44-10 162398 126195 E17 15,775 5,283 27,423 0 44-10 162398 126195 E18 13,118 5,283 27,423 0 44-10 162398 126195 E19 13,103 5,283 27,423 0 44-10 162398 126195 E20 13,015 5,283 27,423 0 44-10 162398 126195 E21 12,904 5,283 27,423 0 44-10 357776 325246 E22 11,783 4,999 27,139 0 44-10 357776 325246 E23 12,448 4,999 27,139 0 44-10 357776 325246 E24 12,350 4,999 27,139 0 44-10 357776 325246 E25 14,924 4,999 27,139 0 44-10 357776 325246 E26 14,183 4,999 27,139 0 44-10 357776 325246 E27 15,003 4,999 27,139 0 44-10 357776 325246 E28 13,785 4,999 27,139 0 44-10 357776 325246 E29 13,991 4,999 27,139 0 44-10 357776 325246 E30 15,243 4,999 27,139 0 44-10 357776 325246 E31 15,963 4,999 27,139 0 44-10 357783 325261 E31 QC 15,709 5,641 27,781 0 44-10 357776 325246 E32 20,983 4,999 27,139 0 44-10 357783 325261 E32 QC 16,641 5,641 27,781 0 44-10 357776 325246 E33 21,026 4,999 27,139 0 44-10 357783 325261 E33 QC 19,820 5,641 27,781 0 44-10 357776 325246 E34 19,800 4,999 27,139 0 44-10 357783 325261 E34 QC 20,269 5,641 27,781 0 44-10 357776 325246 E35 16,245 4,999 27,139 0 44-10 357776 325246 W01 14,744 4,999 27,139 0 44-10 357783 325261 W01 QC 12,971 5,641 27,781 0 37

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Scan Avg Action Detector Detector M2350-1 Logged Scan Location Background Level Type ID ID Result Alarms (cpm) (cpm) (cpm) 44-10 357776 325246 W02 13,623 4,999 27,139 0 44-10 357783 325261 W02 QC 14,665 5,641 27,781 0 44-10 357776 325246 W03 15,236 4,999 27,139 0 44-10 357783 325261 W03 QC 15,339 5,641 27,781 0 44-10 357776 325246 W04 17,457 4,999 27,139 0 44-10 357783 325261 W04 QC 15,495 5,641 27,781 0 44-10 162398 126195 W05 14,765 5,094 27,234 0 44-10 162398 126195 W06 14,925 5,094 27,234 0 44-10 357776 325246 W06 23,801 4,999 27,139 0 44-10 162398 126195 W07 15,131 5,094 27,234 0 44-10 357776 325246 W07 15,830 4,999 27,139 0 44-10 162398 126195 W08 14,682 5,094 27,234 0 44-10 357776 325246 W08 20,737 4,999 27,139 0 44-10 162398 126195 W09 17,438 5,094 27,234 0 44-10 357776 325246 W09 26,142 4,999 27,139 0 44-10 162398 126195 W10 17,516 5,094 27,234 0 44-10 162398 126195 W10 18,419 5,094 27,234 0 44-10 357776 325246 W10 26,458 4,999 27,139 0 44-10 162398 126195 W11 17,978 5,094 27,234 0 44-10 357776 325246 W11 36,821 4,999 27,139 1 44-10 162398 126195 W12 19,633 5,094 27,234 0 44-10 162398 126195 W13 26,792 5,094 27,234 0 44-10 162398 126195 W14 24,176 5,094 27,234 0 44-10 162398 126195 W15 23,172 5,094 27,234 0 44-10 162398 126195 W16 29,183 5,094 27,234 1 44-10 162398 126195 W17 30,449 5,094 27,234 1 44-10 162398 126195 W18 23,237 5,094 27,234 0 44-10 162398 126195 W19 20,961 5,094 27,234 0 44-10 162398 126195 W20 16,876 5,094 27,234 0 44-10 162398 126195 W21 17,718 5,094 27,234 0 44-10 162398 126195 W22 15,917 5,094 27,234 0 44-10 162398 126195 W23 14,901 5,094 27,234 0 38

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Scan Avg Action Detector Detector M2350-1 Logged Scan Location Background Level Type ID ID Result Alarms (cpm) (cpm) (cpm) 44-10 357776 325246 W24 16,234 4,995 27,135 0 44-10 357776 325246 W25 18,184 4,995 27,135 0 44-10 357776 325246 W26 18,609 4,995 27,135 0 44-10 357776 325246 W27 18,213 4,995 27,135 0 44-10 357776 325246 W28 18,088 4,995 27,135 0 44-10 357776 325246 W29 17,300 4,995 27,135 0 44-10 357776 325246 W30 17,452 4,995 27,135 0 44-10 357776 325246 W31 16,810 4,995 27,135 0 44-10 357776 325246 W32 16,995 4,995 27,135 0 44-10 357776 325246 W33 15,805 4,995 27,135 0 44-10 357776 325246 W34 16,613 4,995 27,135 0 44-10 357776 325246 W35 16,549 4,995 27,135 0 44-10 162398 126195 W36 18,195 5,283 27,423 0 44-10 162398 126195 W37 18,677 5,283 27,423 0 44-10 162398 126195 W38 17,445 5,283 27,423 0 44-10 162398 126195 W39 20,117 5,283 27,423 0 44-10 162398 126195 W40 20,136 5,283 27,423 0 44-10 162398 126195 W41 21,127 5,283 27,423 0 44-10 162398 126195 W42 21,625 5,283 27,423 0 44-10 162398 126195 W43 21,518 5,283 27,423 0 39

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS ATTACHMENT 3 SIGN TEST 40

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Table 16 Survey Unit L1-SUB-CDR Sign Test SOF

1-Ws Sign (Ws) 1 0.0445 0.96 +1 2 0.0305 0.97 +1 3 0.0627 0.94 +1 4 0.0502 0.95 +1 5 0.0673 0.93 +1 6 0.0858 0.91 +1 7 0.0506 0.95 +1 8 0.0592 0.94 +1 9 0.4594 0.54 +1 10 0.0902 0.91 +1 11 0.2270 0.77 +1 12 0.1369 0.86 +1 13 0.0472 0.95 +1 14 0.1720 0.83 +1 Number of positive differences (S+) 14 Critical Value 10 Survey Unit Meets the Acceptance Criteria 41

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS ATTACHMENT 4 QUALITY CONTROL ASSESSMENT 42

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Table 16 Survey Unit L1-SUB-CDR QC Assessment STANDARD COMPARISON Activity Standard Agreement Range Activity Comparison Acceptable Sample ID Radionuclide Resolution Sample ID Value Error (Low to UiQh) Value Ratio (YIN)

Ll -SUB- CDR-FSGS-014-SB Cs-137 2.28E+00 7.68E-02 30 0. 75 I 1.33 Ll-SUB- CDR- QSGS-01 4-SB 2.88E-0l 0.13 N K- 40 9.96E+00 4 .65E- 0l 21 0.75 I 1.33 l.02 E+0l 1.02 y Connnents/Conective Actions: The comparison ratio is not within the agreement range for Cs-13 7. When using K- Table is provided to show acceptance criteria used to assess split samples.

40 in the comparison, there is an acceptable agreement. Additionally, both samples have activity below the OpDCGL, and no finther action is necessaiy. Rc sohuion Acceptable Ratio

<4 0.4-2.5 4-7 0.5-2.0 8- 15 0.6- 1.66 16-50 0.75-1.33 51 -200 0.80- 1.25

>200 0.85- 1.18 43

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS ATTACHMENT 5 CONSULTATION TRIGGERS FOR RESIDENTIAL SOIL CONCENTRATION 44

FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR ~

STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Table H.1 Consultation Triggers for Residential and Commercial/Industrial Soil Contamination (MOU Table 1}

Except for radium-226, thorium-232, or total uranium, concentrations should be aggregated using a sum of the fraction approach to determine site-specific consultation trigger concentrations. This table is based on single contaminant concentrations for residential and commerciaVindustrial land use when using generally accepted exposure parameters. Table users should select the appropriate column based on the site's reasonably anticipated land use.

Radionuclide Residential Soil Concentration Industrial/Commercial Soil Cone en tration H-3 228 pCi/g 423 pCi/g C-14 46 oCi/g 123 000 oCi/e:

Na-22 9 oCi/g 14 pCi/g S-35 19,600 pCi/g 32,200.000 oCi/g Cl-36 6 oCi/g 10,700 oCi/g Ca-45 13,500 pCi/g 3 740 000 pCi/g Sc-46 105 pCi/2 169 pCiig Mn-54 69 oCi/g 112 oCi/g Fe-55 269,000 pCi/g 2,210,000 oCi/g Co-57 873 pCi/g 1.420 oCi/e Co-60 4 pCi/g 6 pCi/g Ni-59 20 800 pCi/g 1,230 000 pCi/g Ni-63 9,480 oCi/g 555.000 oCi/g Sr-90+0 23 oCi/g 1,070 oCi/g Nb-94 2 pCi/g 3 pCi/g Tc-99 25 oCi/g 89,400 oCi/e:

J-129 60 pCi/g 1,080 pCi/g Cs-134 16 pCi/g 26 pCi/g Cs-137+0 6 oCi/g 11 pCi/g Eu-152 4 oCi/g 7 oCi/2 Eu-154 5 pCi/g 8 pCi/g lr-192 336 pCi/2 544 pCi/g Pb-210+0 15 oCi/g 123 oCi/g Ra-226 5 pCi/g 5 pei/g Ac-227+0 10 pCi/g 21 oCi/g Th-228+D 15 pCi/g 25 oCi/g Th-232 5 pCi/g 5 pCi/2 U-234 401 pCi/g 3,310 pCi/g U-235+0 20 oCi/g 39 oCi/g U-238+0 74 pCi/g 179 oCi/g total uranium 47 mg/kg 1230 mg/kg Pu-238 297 oCi/g 1.640 oCi/2 Pu-239 259 pCi/g 1,430 oCi/g Pu-241 40,600 pCi/g 172.000 pCj/g Am-241 187 pCi/g 568 pCi/g Cm-242 32.200 pCi/g 344,000 oCi/g Cm-243 35 pCi/g 67 pCi/g 45

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS ATTACHMENT 6 GRAPHICAL PRESENTATIONS 46

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Figure 16 Quantile Plot for Cs-137 Concentration 47

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Figure 16 Histogram for Cs-137 Concentration 48

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS Figure 16 Retrospective Power Curve for Survey Unit L1-SUB-CDR Probability that the w*vey t:nit Pas e 1.0

\,

0.8 0.6 0.4 0.2 l

0.0 1)% 3)% 5)% 70% ' I,.

9) % 1 )0%110% 130% 1... 0%

True urve: t:nit ooceotratioo (percent of D GL 49

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FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS ATTACHMENT 7 SAMPLE ANALYTICAL REPORTS 50

9/14/2017 1:35:40PM Pagel of6

__.;Apex-Gamma Analysis Report for L 1-SUB-CDR-FSGS-001-SB UNIT L1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-COR-FSGS-001-SB Sample Description : UNIT L1-SUB CDR 0!}/13/17 Sample Type : 500 ml Marinelli /

Unit Sample Point Sample Size : 8.577E+02 grams/

Facility : Dalryland_NPP Sample Taken On : 9/13/2017 11:02:00AM /

Acquisition Started : 9/14/2017 12:35:19PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB /

Geometry : 500ml Marinelli Live lime : 3600.0 seconds Real Time : 3609.3 seconds Dead Time : 0.26 % /

Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 3388 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/14/2017 1:35:31PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/14/2017 1:35:40PM Page2 of6 Analysis Report for L 1-SUB-CDR-FSGS-001-SB UNIT L1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak Net Peak NetArea Continuum FWHM (keV) end Centroid Area Uncertainty Counts (keV)

No. start F 1 58.14 114 - 119 116.83 3 . 82E+Ol 13.06 2.13E+ 02 0.71 F 2 238.55 469 - 485 477.58 3.45E+02 26. 41 4.10E+02 2 .6 9 F 3 338.50 671- 683 677.44 7.04E+Ol 14. 67 1.72E+02 2. 0 5 F 4 352.18 699 - 710 704.78 2.10E+02 18.69 1.24E+0 2 2 .65 F 5 583.30 1160 - 11 7 6 11 66 . 94 8.62E+01 12 .49 9.21E+ Ol 2. 27 F 6 609.70 1211 - 1228 1219.73 1. 73E+02 16.42 1. 08E+0 2 2. 86 F 7 662.08 1318 - 1330 1324.47 1.13E+02 14.30 8.31E+Ol 2 .57 F 8 911.94 1818 - 1830 1 824.11 7.80E+Ol 10.90 3.45E+Ol 2.8 8 F 9 1461. 72 2914 - 2933 2923 . 55 6.26E+02 25.40 1 . 50E+Ol 3.18 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/14/2017 1:35:31PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted (keV) Area Uncertainty Background Uncert. Area Uncert.

No.

F 1 58.14 3.82E+01 13.06 3.82E+Ol l.31E+Ol F 2 238.55 3 . 4 5E+02 2 6. 41 3,45E+02 2.64E+Ol F 3 338.50 7 .04E+Ol 14.67 7.04E+Ol l.47E+Ol F 4 3 5 2.18 2.10E+02 18.69 8.36E+Ol 1. 86E+Ol l. 26E+02 2. 64E+Ol F 5 583.30 8.62E+Ol 12.49 8.62E+Ol l.25E+ Ol F 6 609.70 1. 73E+02 16.42 4.12E+Ol 1. 21E+Ol 1.32E+02 2 . 04E+Ol F 7 662.08 1.13E+02 14.30 6.61E+Ol 1.27E+Ol 4.6 9E+Ol 1.91E+Ol F 8 911. 94 7.BOE+Ol 10.90 7 .BOE+Ol 1.09E+Ol F 9 1461.72 6. 26E+ 02 25 .40 6.26E+ 02 2. 5 4E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma

9/14/2017 1 :35:40PM Page 3 of6 Analysis Report for L 1-SUB-COR-FSGS-001-SB UNIT L1..SUB COR 09/13/17 NUCLIDE IDENTIFICATION REPOR T Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTtAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (keV) (uCVgrams) Uncertainty K-40 0.86 1460.75 10.67

7.96E-06 3.91E-07 CS-137 0 . 97 661.65

85.12 3.70E-08 1. SlE-08 PB-212 0. 56 77 .11 17.50 238.63

44.60 2.07E-07 l.68E-08 BI-214 0.33 609.31 46.30

1.77E-07 2.79E-08 1120.29 15. 10 1238 .11 5.94 1377 . 67 4.11 1407 .98 2.48 1509.19 2.19 1764.49 15.80 AC-228 0. 30 209.28 4.40 338 . 32

11.40 2.23E-07 4.69E-08 794.70 4.60 911.60

27.70 2.52E-07 3.57E-08 964.60 5.20 969.11 16.60

= Energy line found in the spectrum.

- = Manually added nudide.

=

? Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Toferance : 1.000 keV

=

Nuclide confidence index threshold 0.30 Errors quoted at 1.000sigma INTER FEREN CE CORRECTED REPOR T

9/14/2017 1:35:40PM Page4of6 Analysis Report for L1-SUB-CDR-F SGS-001-SB UNIT L 1-SUB COR 09/13/17 Nuclide Nuclide Wtmean Wt mean Comments Name Id Activity Activity Confidence (uCilgrams) Uncertainty 0.861 7 .96E-06 3.91E-07 0.971 3 .?0E-0 8 1. SlE-0 8 0.560 2.0?E-07 l. 68E-08 BI-214 0.33B 1.77E-07 2.79E-08 AC-228 0.303 2 .42E-07 2. B4E-08

? = 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 1.000sigma

9/14/2017 1:35:40PM Page 5 of6 Analysis Report for L 1-SUB-COR-FSGS-001-SB UNIT L1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/14/2017 1:35:31PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS ('1/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 58.14 1.06097E-02 34.18 F 4 352.18 3.50660E-02 20.89 Tol.

F 5 583.30 2.39550E-02 14.49 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000slgma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canben-a\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield{3/4) Activity NuclideMDA LinellDA Name (uCVgrams) (uCUgrams) (uCVgrams)

(keV)

+ K-40 1460.75

10.67 7.96E-06 3.38E-07 3.38E-07

+ ;AR-41 1293.64 99.16 1. 30E-04 1.09E-03 1.09E-03

+ C0-60 1173.22 100.00 8.39E-08 5.45E-08 6.56E-08 1332.49 100.00 4.05E-08 5.45E-08

+ KR-85 513.99 0.43 4.92E-06 9.61E-06 9.61E-06

+ Y-88 898.04 93.70 2.lSE-08 3.45E-08 4.5 2E-08 1836.06 99.20 -3.0SE-10 3. 45F.-Ofl

+ NB-94 702.63 100 .00 -1. 74E-08 4.13E-08 4 . 27E-08 871.10 100 .00 -3.26E-08 4.13E-08

+ I-131 284.30 6 .06 -4.03E-07 4.41E-08 5.87E-07 364.48 81.20 9.14E-0 9 4.41E-08 636.97 7.27 -2.61E-07 5.69E-07

+ CS-134 604.70 97.60 -1.74E-08 5.28E-08 5.56E-08 795.84 85.40 6. llE-08 5.28E-08

+ /4-137 661.65

85.12 3.70E-08 5.69E-08 5.69E-08

9/14/2017 1:35:40PM Page 6 of6 Analysis Report for L1-SUB-CDR-FSGS-001-SB UNIT L1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (uCVgrams) (uCVgrams) (uCVgrams)

(keV)

+ CE-144 80.12 1.36 1.86E-06 2. 79E-07 3.49E-06 133.51 11. 09 3.27E-07 2.79E-07 EU-152 121.78 28.40 -6.26E-08 1.03E-07 1.03E-07

+ /

244.69 7.49 -1. 53E-07 5.04E-07 964.00 14.44 3. llE-07 4.03E-07

+ J EU-154 1408.00 123.07 247.94 20.74 40.40 6.60 1 .14E-07

-5 .32E-08

-5 .36E-07 7.23E-08 2.40E-07 7.23E-08 5.lOE-07 723.30 19.70 5.54E-08 2.06E-07 873.20 11.50 -2.0lE-07 3.53E-07 1004.76 17.90 -1.12E-07 2.71E-07 1274 .51 35.50 -1. 82E-08 1. 57E- 07

+ EU-155 86.54 32.80 -9.33E-08 1. 20E-07 1. 20E-07 105.31 21. 80 -1. 28E-08 l.43E-07

+ BI-214 609.31

46.30 l.77E-07 1.06E-07 1. 06E-07 1120.29 15.10 3.46E-07 4.37E-07 1238.11 5.94 4.46E-07 1.14E-06 1377.67 4 .11 -4.69E-07 1. lOE-06 1407. 98 2.48 9.53E-07 2.00E- 06 1509.19 2.19 7.48E-07 1. 56E-06 1764.49 15.80 2.74E-07 3.68E-07

+ PB-214 77.11 10.70 7.93E-07 1. 09E-07 4.81E-07 295. 21 19.20 1. 31E-07 1.93E-07 351.92 37.20 1. 68E-07 l.09E-07

+ PA-228 89.95 22.00 6.42E-07 2.32E-07 3.95E-07 93.35 35.00 1.0SE-07 2.32E-07 105.00 16.30 -2.78E-08 4.33E-07 129.22 2.97 -l.18E-06 2.27E-06 338.32 5.30 9.37E-07 1.53E-06 463.00 13.80 2.77E-07 6.lSE-07 911. 23 16. 70 4.12E- 07 7.79E-07

+ / AM-241 59.54 36.30 -9.00E-08 2 . lOE-07 2.lOE-0 7

+ CM-243 1 03.76 23.00 7.47E-09 1. 3 7E-07 1. 37E-07 228.18 10 . 60 -l.8 2E-0 7 2.BSE- 07 277.60 14.00 -1. 46E-07 2.32E-07

+ = Nuclide identified during the nuclide Identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

9/14/2017 2:36:47PM Page I of7

--8Apex-Gamma Analysis Report for L 1..SUB-CDR-FSGS-002..SB UNIT L1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-FSGS-002-SB /

Sample Description : UNIT L1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 9.262E+02 grams Facility : Dairylend_NPP Sample Taken On : 9/13/2017 11:06:00AM / " '

Acquisition Started : 9/14/2017 1:36:26PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Livellme : 3600.0 seconds Real Time : 3609.5 seconds Dead lime : 0.26 % /

Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100- 4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 3389 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/14/2017 2:36:38PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/14/2017 2:36:47PM Page2 of7 Analysis Report for L 1-SUB-CDR-FSGS-002-SB UNIT L 1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.84 470 - 486 478.15 4.38E+02 28.22 4. 0 0E+02 2.7 7 F 2 352.33 699 - 712 705.09 2.08E+02 20.29 1.97E+02 2.71 F 3 583.91 1159 - 1176 1168.16 1.24E+02 14.93 9.40E+Ol 3.48 F 4 609.60 1213 - 1228 1219.53 1.56E+02 15.38 8.94E+Ol 2 .63 F 5 662.02 1317 - 1331 1324.36 3.09E+02 19.56 6 .38E+Ol 2.73 F 6 911. 77 1817 - 1829 1823.78 6.41E+Ol 10.53 4. 0 SE+ Ol 2. 62 F 7 1461.79 2914 - 2934 2923.68 7.04E+02 27.02 2.25E+Ol 3.21 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/14/2017 2:36:38PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 238.84 4.38E+02 28.22 4.38E+02 2.82E+Ol F 2 352.33 2.08E+02 20. 2 9 8.36E+Ol 1.86E+Ol 1.24E+02 2.75E+Ol F 3 583.91 l.24E+02 14.93 1.24E+02 1. 49E+Ol F 4 609.60 1.56E+02 15.38 4.12E+Ol 1.21E+Ol 1.15E+02 l.96E+Ol F 5 662.02 3.09E+02 19. 56 6.61E+Ol 1. 27E+Ol 2.43E+02 2.33E+Ol F 6 911. 77 6.41E+Ol 10.53 6.41E+Ol 1. 05E+Ol F 7 1461.79 7.04E+02 27.02 7.04E+0 2 2.70E+Ol

=

M First peak in a multiplet region m = Other peak in a multiplet region

=

F Fitted singlet Errors quoted at 1.000sigma

9/14/2017 2:36:47PM Page 3 of7 Analysis Report for L 1-SUB-CDR-FSGS-002-SB UNIT L1-SUB CDR09/13J17 NUCLIDE IDENTIFICATION REPORT Nuclide Librat'Y Used : C:\Canberra\Apex\Root\Oalt'Yland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (keV) (uCi/grams) Uncertainty CS*-137 0.97 661. 65

85.12 1.77E-07 1. 77£-08 PB-212 0. 55 77 .11 17.50 238.63

44. 60 2.44E-07 1. 69E-08 BI-214 0.34 609.31

46.30 1.43E-07 2.47E-08 1120.29 15. 10 1238 .11 5. 94 1377.67 4.11 1407.98 2.48 1509.19 2.19 1764.49 15.80

= Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nudlde.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold ;: 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmean Wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCVgrams) 7 CS-137 PB-212 0.978 0.555 1.77E-07 2.44E-07 1.77E-08

1. 69E-08 BI-214 0.343 1. 43E-07 2.47E-08

9/14/2017 2:36:47PM Page4of7 Analysis Report for L1-SUB-CDR-FSGS-002-SB UNIT L 1-SUB CDR 09/13/17

? = 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 1.000sigma

9/14/2017 2:36:47PM Page 5 of7 Analysis Report for L 1-SUB-CDR-FSGS-002-SB UNIT L 1-SUB COR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/14/2017 2:36:38PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS {°A,) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS)

~~:::-

Uncertainty Type Nuclide F 2 352.33 3.44610E-02 22.19 Tol.

F 3 583.91 3.44740E-02 12.03 F 6 911. 77 l.78149E-02 16.41 AC-228 PA-228 F 7 1461. 79 l.95541E-Ol 3.84 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Enors quoted at 1.OOOsigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA LineMDA Name (uCVgrams) (uCUgrams) (uCllgrams)

(kel.1

+ K-40 1460.75 10.67 8.35E-06 1.53E-06 1. 53E-06

+ AR-41 1293.64 99.16 -6.26E-04 1.SSE-03 1.SSE-03

+ _./co-60 1173.22 100.00 6.28E-08 5,SSE-08 6.78E-08 1332.49 100.00 -

i;

?Ql;'_(\Q

- _;.a.., V V 5.55E-08

+ KR-85 513.99 0.43 l .07E-05 9.76E-06 9.76E-06

+ Y-88 898.04 93.70 2.lOE-09 3.29E-OB 4.SSE-08 1836.06 99.20 -1. 43E-08 3.29E-08

+ NB-94 702.63 100.00 -1. 04E-08 3.89E-08 3.89E-08 871.10 100.00 3.90E-08 4.58E-08

+ I-131 284.30 6.06 -4.61E-07 4.20E-08 5.65E-07 364.48 81.20 -1. 92E-08 4.20E-08 636.97 7.27 -7.41E-08 5.46E-07

9/14/2017 2:36:47PM Page 6 of7 Analysis Report for L 1..SUB-CDR-FSGS-002-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Energy Yield{°/4) Activity Nuclide MDA LineMDA Name (uCi/grams) (uCi/grams) (uCilgrams)

(keV)

+ CS-134 604.70 97.60 4.48E-09 4.97E-08 5. llE-08 795.84 85.40 -1.88E-09 4.97E-08

+ I CS-137 661. 65

85.12 l.77E-07 5 .06E-08 5. 06E-08

+ CE-144 80.12 1.36 -1. 27E-07 2.62E-07 3.23E-06 133.51 11.09 -4.05E-09 2.62E-07 28.40 -6.33E-08 1. 03E-07 1.03E-07

+

J EU-152 121. 78 244.69 7.49 -2.55E-07 4.93E-07 964.00 14.44 6.84E-07 3.86E-07 1408.00 20.74 -2. lBE-08 1. 99E-07

+ _j EU-154 123.07 40.40 -4.57E-08 7.21E-08 7 .21E-08 247.94 6.60 -8.44E-07 4.86E-07 723.30 19.70 2.70E-07 2 .14E-07 873.20 11.50 -7.24E-08 3.83E-07 1004.76 17. 90 -2.13E-07 2.56E-07 1274.51 35.50 3.05E-08 l.56E-07

+ EU-155 86.54 32.80 5.48E-10 1.15E-07 1. 15E-07 105.31 21.80 2.54E-08 1. 39E-07

+ BI-214 609.31

46.30 l.43E-07 9.13E-08 9.13E-08 1120.29 15.10 -8.56E-08 3.BlE-07 1238 .11 5.94 -1. 63E-07 1. 16E-06 1377.67 4 .11 6,80E-07 1. lOE-06 1407.98 2.48 -1 .82E-07 1.66E-06 1509.19 2.19 -1. 18E-07 1.61E-06 1764.49 15.80 2.SOE-07 2.96E-07

+ PB-214 77.11 10. 7 0 4.69E-07 1. OSE-07 4.41E-07 295.21 19.20 1.84E-07 1. 76E-07 351.92 37.20 2.95E-07 1.0BE-07

+ PA-228 89.95 22.00 3.43E-07 2.35E-07 3.94E-07 93.35 35.00 1. 39E-07 2.35E-07 105.00 16.30 3.02E-08 4.36E-07 129.22 2.97 3.56E-07 2 .30E-06 338.32 5.30 8.45E-07 1.46E-06 4 63. 0 0 13.80 6.33E-08 6.22E-07 911. 23 16.70 1.02E-06 7 . 5 5 E- 07

+ J AM-241 59. 54 36.30 6.14E-08 2.05E-07 2.0SE-07 1.32E-07

+ CM-243 103.76 23.00 -8.59E-08 1.32E-07 228.18 10.60 -1.97E-07 2.62E-07 277.60 14.00 1.94E-07 2 .35E- 0 7

+ =

=

Nuclide identified during the nuclide identification Energy line found in the spectrum

> = MDA value not calculated

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

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

9/14/2017 2:36:47PM Page 7 of7 Analysis Report for L1-SUB-CDR-FSGS-002-SB UNIT L1-SUB CDR 09/13/17

9/14/2017 3:37:46PM Page 1 of6

~Apex-Gamma Analysis Report for L1-SUB-CDR-FSGS-003-SB UNIT L1-SUB-CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample ldentlflcation : L 1-SUB-CDR-FSGS-003-SB Sample Description : UNIT L1-SUB-CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 8.792E+02 grams /

Facility : Dalry\and_NPP Sample Taken On : 9/13/2017 11:08:00AM/

Acquisition Started : 9/14/2017 2:37:25PM" Procedure : 500ml Marinelli /

Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli /

Live Time : 3600.0 secondel' Real Time : 3609.5 seconds Dead Time : 0.26 % /

Peak Locate Threshold : 3.00 Peak Locate Range (in channels)

100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 3390 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9114/2017 3:37:37PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/14/2017 3:37:46PM Page 2 of6 Analysis Report for L1-SUB-CDR-FSGS-.003-SB UNIT L1-SUB-CDR 09/13/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.96 472 - 486 478.40 4.07E+02 27.98 3.63E+02 3. 10 F 2 296.02 587 - 597 592.49 5.09E+Ol 12 .53 2.04E+02 1. 07 F 3 351.80 696 - 712 704.04 2.02E+02 19.92 2.16E+02 2.79 F 4 583.42 1161 - 1174 1167.18 8.85E+01 12.63 8 .lSE+Ol 2.21 F 5 609.72 1212 - 1228 1219.77 l.36E+02 14.50 7.1 5E+Ol 3.09 F 6 662.17 1318 - 1334 1324.65 4.95E+02 23.77 7.0SE+Ol 2.83 F 7 1461.73 2913 - 2934 2923.57 6.27E+02 25.56 2.73E+Ol 3.06 M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/14/2017 3:37:37PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 238.96 4.07E+02 27.98 4.07E+02 2.80E+Ol F 2 296.02 5.09E+Ol 12.53 5 .09E+O l 1. 25E+Ol F 3 351.80 2.02E+02 19.92 8.36E+Ol 1.86E+Ol 1.19E+02 2.73E+Ol F 4 583.42 8.85E+Ol 12. 63 8.85E+Ol l . 26E+Ol F 5 609.72 1. 36E+02 14.50 4.12E+Ol 1. 21E+Ol 9.49E+Ol 1. 89E+Ol F 6 662.17 4.95E+02 23.77 6.61E+Ol 1. 27E+Ol 4.29E+02 2.69E+Ol F 7 1461.73 6.27E+02 25.56 6.27E+02 2.56E+Ol M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma

9/14/2017 3:37:46PM Page3 of6 Analysis Report for L 1-SUB-CDR-FSGS-003-SB UNIT L 1-SUB-CDR 09/13117 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (keV) (uCUgrams) Uncertainty K-*40 0 .85 1460.75

10.67 7.77E-06 3.83E-07 CS-137 0 .95 661.65

85.12 3.30E-07 2.26E-08 PB-212 0 .54 77.11 17.50 238.63

44.60 2.39E-07 1. 76E-08 BI-214 0 .33 609.31

46.30 1.24E-07 2.SOE-08 1120.29 15.10 1238.11 5.94 1377. 67 4 .11 1407.98 2.48 1509.19 2.19 1764.49 15 .80 PB-214 0.69 77.11 10.70 295.21

19.20 8.30E-08 2.05E-08 351. 92

37.20 1.l?E-07 2.69E-08

= Energy line found in the spectrum.

- =Manually added nuclide.

? =Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance: 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmean Wtmean Comments Name Id Activity Activity Confidence (uCi/grams) Uncertainty K-40 0.858 7.77E-06 3.83E-07

/cs-137 0.958 3.30E-07 2.2 6E-08

9/14/2017 3:37:46PM Page 4 of6 Analysis Report for L1-SUB-CDR-FSGS-003-SB UNIT L1-SUB-CDR 09/13/17 Nuclide Nuclide wt mean wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCUgrams)

PB-212 0.547 2.39E-07 1.76E-08 BI-214 0.337 1. 24E-07 2.SOE-08 PB-214 0.691 9.54E-08 1. 63E-08

? = 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 1.000sigma

9/14/2017 3:37:46PM Page 5 of6 Analysis Report for l 1-SUB-CDR-FSGS-003-SB UNIT l 1-SUB-CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Perfonned on : 9/14/2017 3:37:37PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS (Oh) Peak Tolerance Peak No. Energy (kaV) Peak Size (CPS) Uncertainty Type Nuclide F 4 583.42 2.45775E-02 14.27 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Llbrary\HOTLAB.NLB Nuclide Energy Yield{°,{,) Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams) (uCVgrams)

(keV)

+ K-40 1460.75

10.67 7.77E-06 4.45E-07 4.45E-07

+ AR-41 1293.64 99.16 -8. 'JlE-04 l.97E-03 1. 97~-03

+ CO-60 1173.22 100.00 8.26E-08 5.93E-08 6.69E-08 1332.49 100.00 6.49E-08 5.93E-08

+ KR-85 513.99 0.43 1 .74E-05 l.03E-05 1.03E-05

+ Y-88 898.04 93.70 8.03E-09 3.99E-08 4.86E-08 1836.06 99.20 -6.43E-09 3.99E-08

+ NB-94 702.63 100.00 4.94E-09 3.99E-08 3.99E-08 871.10 100.00 - 1.88E-08 4.49E-08

+ I-131 284.30 6. 06 -1. 36E-07 4.32E-08 6.07E-07 364.48 81. 20 -4.40E-08 4.32E-08 636.97 7.27 -1. 31E-07 6.04E-07

+ CS-134 604.70 97.60 3.64E-09 5.00E-08 5.00E-08 795.84 85.40 -1. 52E-08 5.00E-08

+ CS-137 661.65

85.12 3.30E-07 5.60E-08 5.60E-08

+ CE-144 80.12 1. 36 1.0lE-06 2.79E-07 3.45E-06 133.51 11.09 1.85E-07 2.79E-07

9/14/2017 3:37:46PM Pagc6 of6 Analysis Report for l 1-SUB-CDR-FSGS-003-SB UNIT L 1-SUB-CDR 09/13/17 Nuclide Energy Yield(%) Activity Nucl/deMDA LlneMDA Name (uCVgrams) (uCi/grams) (uCi/grams)

(keV}

+ EU-152 121. 78 28.40 -7.42E-08 1.04E-07 l.04E-07 244.69 7.49 -3.95E-07 4.98E-07 964.00 14.44 3.71E-07 4.13E-07 1408.00 20.74 1. 65E-07 2.0lE-07

+ EU-154 123.07 40.40 2.12E-08 7.40E-08 7.40E-08 247.94 6.60 -3.68E-07 5.lOE-07 723.30 19.70 2.28E-07 2.12E-07 873.20 11.50 6.58E-08 3.80E-07 1004.76 17.90 4.93E-08 2.89E- 0 7 1274.51 35.50 -3.84E-08 l.52E-07

+ EU-155 86.54 32.80 -6.28E-08 1 .20E-07 l. 20E-07 105.31 21. 80 -7.60E-09 l.46E-07

+ BI-214 609.31

46.30 1.24E-07 9. llE-08 9.llE-08 1120.29 15.10 2.86E-07 4.06E-07 1238.11 5.94 l.65E-07 l.12E-06 1377.67 4 .11 6.51E-07 1.08E-06 1407.98 2 .48 l.38E-06 l.68E-06 1509.19 2.19 -6.36E-07 2.00E-06 1764.49 15.80 2.0lE-07 3.19E-07

+ PB-214 77 .11 10.70 7.99E-07 l.lOE-07 4. 72E-07 295.21

19.20 8.30E-08 1.23E-07 351.92

37.20 1.17E-07 l.lOE-07

+ PA-228 89.95 22.00 5.72E-07 2.45E-07 4.19E-07 93.35 35.00 2 .97E-08 2.45E-07 105.00 16.30 7.68E-08 4.72E-07 129.22 2.97 1. 36E-08 2.48 E-06 338.32 5.30 1. 25E-06 1. 67E-06 463.00 13.80 1. 24E-07 6.BlE-07 911.23 16.70 8.55E-07 7 . 7 8E-07

+ AM-241 59.54 36.30 9.0lE- 08 2.13E-07 2 .13E-07

+ CM-243 103.76 23.00 9.42E-08 1. 40E-07 l.40E-07 228.18 10.60 3.37E-08 2 .91E-07 277.60 14.00 1. lOE-08 2.40E-07

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

9/14/2017 4:39:55PM Page 1 of 7

_ _IfApex-Gamma Analysis Report for L 1..SUS-COR-FSGS-004-SB UNIT L 1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-FSGS-004-SB /

Sample De8Cription : UNIT L1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 9.107E+02 grams Facility : Dairyland_NPP Sample Taken On Acquisition Started

9/13/2017 11 :12:00AM 9/14/2017 3:39:34PM

/

Procedure

500ml Marinelli Operator Administrator Detector Name HOTLAB ..J Geometry

500ml Marinelli Live Time

3600.0 seconds Real Time : 3609.5 seconds Dead Time . 0.26 % /

Peak Locate Threshold : 3.00 Peak Locate Range (In channels) ; 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number

3391 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/14/2017 4:39:46PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/14/2017 4:39:55PM Page2 of7 Analysis Report for L1-SUB..CDR-FSGS-004-SB UNIT L 1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.84 470 - 486 478.15 3.64E+02 27.72 4.64E+02 2.75 F 2 352.14 696 - 713 704.71 2.37E+02 20.51 2.07E+02 2.89 F 3 583.44 1160 - 1176 1167.23 9.66E+Ol 13.29 8.86E+Ol 2.77 F 4 609.81 1213 - 1228 1219. 96 1.25E+02 14.23 8.36E+Ol 2.63 F 5 662.13 1315 - 1333 1324 . 58 3.95E+02 21. 64 7 .36E+Ol 3 . 05 F 6 911. 67 1816 - 1831 1823.57 8.00E+Ol 11.21 4.62E+Ol 2.80 F 7 1333. 32 2662 - 2672 2666. 77 4,32E+Ol 7.48 1.22E+O l 1. 88 F 8 1461.79 2912 - 2933 2923.68 6.45E+02 25.68 1.13E+Ol 3.24 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/14/2017 4:39:46PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 238.84 3.64E+02 27. 72 3.64E+02 2 .77E+Ol F 2 352.14 2.37E+02 20.51 8.36E+Ol l.86E+Ol 1. 54E+02 2.77E+Ol F 3 583.44 9.66E+Ol 13. 29 9.66E+Ol 1. 33E+Ol F 4 609.81 1. 25E+02 14.23 4.12E+Ol 1. 21E+Ol 8.39E+Ol 1. 87E+Ol F 5 662.13 3.95E+02 21.64 6.61E+Ol l.27E+Ol 3.29E+02 2.51E+Ol F 6 911. 67 8.00E+Ol 11.21 8.00E+ Ol 1. 12E+Ol F 7 1333.32 4.32E+Ol 7.48 4.32E+Ol 7.48E+OO F 8 1461.79 6.45E+02 25.68 6.45E+02 2.57E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma

9/14/2017 4:39:55PM Page4of7 Analysis Report for l 1-SUB-CDR-FSGS-004-SB UNIT L 1-SUB CDR 09/13/17

? :a 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 1.000sigma

9/14/201i 4:39:55PM Page 3 of7 Analysis Report for L 1-SUB-CDR-FSGS-004..SB UNIT L 1-SUB CR 09/13/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIOES Nuclide Id Energy Yield{°/4) Activity *Activity Name Confidence {keV) (uCUgrams) Uncertainty CS-137 0.96 661. 65

85.12 2.44E-07 1.98E-08 PB-212 0 .55 77 .11 17.50 238.63

44.60 2 .07E-07 1. 66E-08 BI-214 0.33 609.31

46.30 1. 06E-07 2.38E-08 1120.29 15.10 1238.11 5.94 1377.67 4.11 1407.98 2.48 1509.19 2.19 1764.49 15.80

= Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold a: 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCUgrams)

/

CS-137 0.964 2.44E-07 1.98E-08 '

PB-212 0.555 2.0 7E-0 7 1. 66E-08 BI-214 0.330 1.06E-07 2.38E-08

9/14/2017 4 :39:55PM Page S of1 Analysis Report for L1-SUB-CDR-FSGS-004-SB UNIT l 1-SUB CDR 09/13117 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/14/2017 4:39:46PM Peak Locate From Channel : 100 Peak locate To Channel : 4096 PeakCPS(%) Peak Tolerance Peak No. Energy (k*VJ Peak Size (CPS) Uncertainty Type Nuclide F 2 352.14 4.27238E-02 18.00 Tol. PB-214 /

F 3 583.44 2.68269E-02 13.77 F 6 911. 67 2.22318E-02 14.00 Tol. AC-228 . /

PA-228. ~ \ ) ~

I> '() \\

F 7 1333.32 l.20098E-02 17.30 Tol.

~ 6~

F 8 1461. 79 l.79075E-01 3.98

'li M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 1.000sigma

~#

NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Vield{°A,) Activity NuclldeMDA LlneMDA Name (uCilgrams) (uCUgrams) (uCilgrams)

(keV)

+ K-40 1460.75 10.67 7 .75E-06 l. 48E-06 l.48E-06

+ AR-41 1293.64 99.16 2.98E-03 3.29E-03 3.29E-03

+ CO-60 1173.22 100.00 8. 76E-08 5.56E-08 7.13E-08 1332.49 100.00 4.98E-08 5.56E-08

+ KR-85 513.99 0.43 l.OlE-05 l .OlE-05 1. OlE-05

+ Y-88 898. 04 93.70 -8.35E-09 3.43E-08 4.92E-08 1836.06 99.20 1.06E-08 3.43E-08

+ NB-94 702.63 100.00 2.16E-08 4. llE-08 4.llE-08 871.10 100.00 5.52E-09 4.12E-08

+ I-131 284.30 6.06 -5. 78E-07 4.39E-08 5.84E-07 364.48 81.20 -5.69E-09 4.39E-08

9/14/2017 4:39:55PM Page 6 of7 Analysis Report for L1-SUB-CDR-FSGS-004-SB UNIT L1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (keV) (uCi/grams) (uCi/grams) (uCi/grams)

I-131 636.97 7.27 8.lBE-08 4.39E-08 5.61E-07

+ CS-134 604.70 97.60 1.13E-09 4.74E-08 4.96E-08 795.84 85.40 -4.69E-08 4.74E-08

+ CS-1 37 661. 65

85. 12 2.44E-07 5.53E-08 5.53E-08

+ CE-144 80.12 1.36 l.02E-06 2.59E-07 3.33E-0 6 133.51 11. 09 2.31E-08 2 .59E-07

+ EU-152 121.78 28.40 -5.91E-08 1. 02E-07 1. 02E-07 244.69 7.49 -2. 36E-07 4.98E-07 964.00 14.44 4.16E-07 4.00E-07 1408 .00 20.74 8.55E-08 1. 92E-07

+ EU-154 123.07 40.40 -7.SSE-08 7.lOE-08 7.lOE-08 247.94 6.60 -5. 32E-07 5.16E-07 723.30 19.70 5.33E-08 2 .17E-07 873.20 11.50 7.60E-08 3.57E-07 1004.76 17.90 -7.16E-10 2.SOE-07 1274.51 35.50 2.49E-08 1. SOE-07

+ EU-155 86.54 32.80 -4.65E-08 l.16E-07 1.16E-07 105.31 21. 80 7.85E-08 1.42E-07

+ BI-214 609.31

46.30 1.06E-07 9.07E-08 9.07E-08 1120.29 15.10 6.40E-08 4.04E-07 1238.11 5.94 5 .24E-07 1. 24E-06 1377.67 4 .11 2.0lE-07 1.13E-06 1407.98 2.48 7.15E-07 1. 60E - 06 1509.19 2.19 -5.91E-08 1.81E-06 1764.49 15.80 l.99E-07 3.04E-07

+ PB-214 77.11 10.70 7.83E-07 1. OSE-07 4.57E-07 295.21 19.20 2.95E-07 l.87E-07 351.92 37.20 2.14E-07 1.0SE-07

+ PA-228 89.95 22.00 2.95E-07 2.44E-07 4.1 7E-07 93.35 35.00 3 . 99E-08 2.44E-07 105.00 16.30 -2. 66E-08 4.69E-07 129.22 2.97 3.33E-07 2.4 0E-06 338.32 5.30 1. 65E-06 1. 62E-06 463.00 13.80 l.4 2 E-0 7 6. 91E-0 7 911.23 16.70 1. 37E-06 8.62E-07

+ AM-241 59.54 36.30 -5. 2 1E-08 2.09E-07 2.09E-07

+ CM-243 1 03. 7 6 2 3 .00 - 1 .12E-07 1.32E-07 1. 3 2E-07 22 8.18 10. 60 l.OSE-0 7 2.81E-07 277.60 14.00 -1.58E-07 2.31E-07

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

9/14/2017 4:39:55PM Page 7 of7 Analysis Report for L1-SUB-COR-FSGS-004-SB UNIT L 1-SUB CDR 09/13/17

9/14/2017 5:40:49PM Page l of6

__.;Apex-Gamma Analysis Report for L 1-SUB-CDR-FSGS-005-SB UNIT L1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-FSGS-005-SB /

Sample Description : UNIT L1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 9.672E+02 grams Facility : Dalryland_NPP Sample Taken On : 9/13/2017 11:16:00AM /

Acquisition Started : 9/14/2017 4:40:27PM Procedure - 500ml Marinelli /

Operator - Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli /

Live Time : 3600.0 seconds Real Time : 3610.0 se7ond Dead Tlme : 0.28%

Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4098 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance ; 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 3392 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/14/2017 5:40:40PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/14/2017 5:40:49PM Page 2 of6 Analysis Report for L 1-SUB-CDR-FSGS-005-SB UNIT L 1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.75 470 - 485 477.98 4.22E+02 30.12 5.62E+02 2.38 F 2 294.95 582 - 598 590.36 l.65E+02 22.56 3.20E+02 3.65 F 3 338.84 673 - 685 678.12 7.20E+01 15.27 2.17E+02 1. 79 F 4 352.19 696 - 712 704.82 2 .11E+02 20.69 2.75E+02 2.39 F 5 583.36 1157 - 1175 1167.06 l.43E+02 14.96 l.05E+02 2.65 F 6 609.43 1213 - 1226 1219.20 l.42E+02 14.95 8.65E+Ol 2.32 F 7 662.00 1316 - 1333 1324.32 1.19E+03 36.23 9.52E+Ol 2.60 F 8 727.90 1450 - 1463 1456.10 4.38E+Ol 9.20 4.24E+Ol 2.46 F 9 911. 41 1818 - 1827 1823.06 4.21E+Ol 9.01 3.62E+Ol 2.02 F 10 969.91 1934 - 1946 1940.04 3.00E+Ol 8.33 5.lOE+Ol 1. 83 F 11 1333.30 2662 - 2672 2666. 75 3.00E+Ol 7.21 2.39E+Ol 1. 87 F 12 1461.84 2914 - 2934 2923.80 6.96E+02 27.07 2.31E+Ol 2.99 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/14/2017 5:40:40PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 238.75 4.22E+02 30.12 4.22E+02 3.0lE+Ol F 2 294.95 1. 65E+02 22.56 1.65E+02 2.26E+Ol F 3 338.84 7.20E+Ol 15.27 7.20E+Ol 1 .53E+Ol F 4 352.19 2 .11E+02 20.69 8 . 36E+01 1. 86E+Ol 1.27E+02 2.78E+Ol F 5 583.36 l.43E+02 14.96 l.43E+02 1. SOE+Ol F 6 609.43 1.42E+02 14.95 4.12E+Ol 1. 21E+Ol 1.01E+02 1.92E+Ol F 7 662.00 l.19E+03 36.23 6.61E+01 1. 27E+01 1.12E+03 3.84E+Ol F 8 727.90 4.38E+Ol 9.20 4.38E+Ol 9.20E+OO F 9 911. 41 4.21E+Ol 9.01 4.21E+Ol 9.0lE+OO F 10 969.91 3.00E+Ol 8.33 3.00E+Ol 8.33E+00 F 11 1333.30 3.00E+Ol 7.21 3.00E+Ol 7.21E+OO F 12 1461. 84 6.96E+02 27.07 6.96E+02 2.71E+Ol

9/14/2017 5:40:49PM Page 3 of6 Analysis Report for L1-SUB-CDR-FSGS-005-SB UNIT L1-SUB CDR 09/13/17 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Cenberra\Apex\Root\Dairylend_NPP\Library\HOll.AB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) ActMty Activity Name Confidence (keV) (uCVgrams) Uncertainty CS-137 0.98 661.65

85.12 7.85E-07 3.42E-08 BI-212 0 .54 727.17

11. 80 2.41E-07 5.09E-08 785.42 2 .00 1620.56 2.75 PB-212 0.55 77.11 17.50 238.63

44 .60 2.25E-07 1.71E-08 BI-214 0. 34 609.31

46 .30 1.20E-07 2.32E-08 1120.29 15 .10 1238.11 5.94 1377. 67 4.11 1407.98 2. 48 1509.19 2.19 1764.49 15.80 PB-214 0.71 77.11 10.70 295.21

19.20 2.43E-07 3.39E-08 351.92

37.20 1.14E-07 2. SOE-08 AC-228 0 .60 209.28 4.40 338 . 32

11.40 2.03E-07 4.33E-08 794. 70 4 .60 911. 60

27.70 1. 21E-07 2.60E-08 964. 60 5.20 969 .11

16.60 l.52E-07 4.23E-08

= Energy Une found In the spectrum.

- = Manually added nuclide.

? = Manually edited nudide.

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

9/14/2017 5:40:49PM Page 4 of6 Analysis Report for L1-SUB-CDR-FSGS-005-SB UNIT L1-SUB CDR 09/13/17 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCUgrams)

I CS-137 BI-212 PB-212 0.981 0.546 0.558 7.85E-07 2.41E-07 2.25E-07 3.42E-08 5.09E-08 l.71E-08 BI-214 0.348 l.20E-07 2.32E-08 PB-214 0.712 l.60E-07 2.0lE-08 AC-228 0.600 1. 45E-07 l.97E-08

? = nuclide is part of an undetennined solution X = nuclide rejected by the interference analysis

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

9/14/2017 5:40:49PM Page 5 of6 Analysis Report for L 1-SUB-cDR-FSGS-005-SB UNIT L1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/14/2017 5:40:40PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS('1/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 5 583.36 3.95875E-02 10.50 F 11 1333.30 8.32204E-03 24.08 F 12 1461.84 1. 93391E-0l 3.89 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canbena\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield("A) Activity NuclideMDA LineMDA Name (lceV) (uCVgrams) (uCVgrams) (uCVgrams)

+ K-40 1460.75 10.67 B.13E-06 1. 46E-06 1.46E-06

+ AR-41 1293.64 99.16 -3.51E-03 4.15E-03 4.lSE-03

+ CO-60 1173.22 100.00 4.61E-08 5.77E-08 6.12E-08 1332.49 100.00 5.95E-08 5.77E-08

+ KR-85 513.99 0.43 1.13E-05 1. 0lE-05 1.0lE-05

+ Y-88 898.04 93.70 -7.97E-11 3.47E-08 4.65E-08 1836.06 g9. 2 0 -1.18E-08 3.47E-08

+ NB-94 702.63 100.00 3.54E-08 3.85E-08 3.85E-08 871.10 100.00 2.27E-08 4.54E-08

+ I-131 284.30 6.06 -7.llE-08 4.55E-08 5.99E-07 364.48 81.20 2.98E-08 4.SSE-08 636.97 7.27 l.l0E-07 5.94E-07

+ CS-134 604.70 97.60 1.16E-08 4.78E-08 5.09E-08 795.84 85.40 -7.0lE-09 4.78E-08

+ CS-137 661.65

85.12 7.BSE-07 5.53E-08 5.53E-08

9/14/2017 5:40:49PM Page6 of6 Analysis Report for L1-SUB-CDR-FSGS-005-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (uCi/grams) (uCilgrams) (uCVgrams)

(keV)

+ CE-144 80.12 1.36 -2 .SlE-06 2.73E-07 3.22E-06 133.51 11.09 1. 56E-07 2.73E-07

+ EU-152 121.78 28.40 -1. 24E-08 1. 06E-07 1.06E-07 244.69 7.49 -3.26E-07 5. llE-07 964.00 14.44 -2.34E-07 3.57E-07 1408.00 20.74 5.48E-08 1.78E-07

+ EU-154 123.07 40.40 -l.04E-08 7.42E-08 7.42E-08 247.94 6.60 -6.05E-07 5.28E-07 723. 30 19.70 -7. 88E-08 2.lOE-07 873.20 11.50 -7.62E-08 3.84E-07 1004.76 17.90 1.29E-07 2.76E-07 1274.51 35.50 -5. 76E-08 1. 37E-07

+ EU-155 86.54 32.80 2.61E-08 1 .17E-07 1.17E-07 105.31 21.80 9.66E-08 1.44E-07

+ BI-214 609.31

46.30 1.20E-07 8.41E-08 8.41 E-08 1120.29 15.10 2.42E-07 3.70E-07 1238 .11 5.94 1.69E-06 1. l 7E-06 1377.67 4 .11 4.89E-07 l.09E-06 1407.98 2.48 4.SBE-07 1.49E-06 1509.19 2.19 S.36E-07 1.59E-06 1764.49 15.80 3.32E-07 3.05E-07

+ PB-214 77.11 10.70 7.0lE-07 1. OBE-07 4.45E-07 295.21

19.20 2 .43E-07 1.SBE-0 7 351.92

37. 2 0 1.14E-07 1.0BE-0 7

+ PA-228 89.95 22.00 7.BlE-07 2.54E-07 4.38E- 0 7 93.35 35.00 -1 .70E-07 2.54E-07 105.00 16.30 2.98E-07 4.96E-07 129.22 2.97 6.87E-07 2.61E- 0 6 338.32 5.30 1.14E-06 1.75E-06 463.00 13.80 S.65E-07 8.0SE-07 911.23 16. 70 6.33E-07 7.53E-07

+ AM-241 59.54 36.30 -6.38E-09 2.lOE-07 2.lOE-07

+ CM-2 4 3 103.76 23.00 9.48E-08 l.38E-07 1. 38E-07 228.18 10.60 -1.21E-07 2.86E-07 2 77 .60 14.00 1. 83E-07 2.44E-07

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

~

9/15/201 / 12:31 :08PM Page 1 of6

___.,J]fApex-Gamma Analysis Report for L1-SUB-CDR-FSGS-006--SB LI-SUB CDR GAMMA SPECTRUM ANALYSIS Sample Identification : L 1-SUB-CDR-FSGS-006-SB Sample Description : LI-SUBCDR Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 8.500E+02 grams j Facility : Dairyland_NPP Sample Taken On : 9/15/2017 8:55:00AM /

Acquisition Started : 9/15/2017 11 :30:47Alli Procedure : 500ml Marinelli Operator : Administrator/

Detector Name Geometry HOTLAB /

500ml Marinelli /

LlveTrme : 3600.0 seconds Real Time : 3610.1 seconds Dead Time : 0.28% /

Peak Locate Threshold : 3.00 Peak Locate Range (ln channels) : 100- 4098 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 3402 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/15/2017 12:30:59PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 12:31:0SPM Page 2 of6 Analysis Report for L1-SU B-CDR-FSGS--006-SB LI-SUB CDR Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.68 469 - 485 477.84 2.94E+02 23.86 4.06E+ 02 2.14 F 2 295.63 587 - 598 591.70 l .OOE+02 15.90 l.97E+ 02 1. 7 3 F 3 352.09 700 - 710 704.61 1.69E+02 17.18 l.32E+02 1. 97 F 4 583.42 1158 - 1171 1167.17 1 .08E+02 12.41 5.64E+ Ol 2. 0 7 F 5 609.71 1212 - 1225 1219.75 l.27E+02 14.21 8.16E+ Ol 2.12 F 6 662 .11 1316 - 1333 1324.53 8.64E+02 31. 11 7.72E+Ol 2.17 F 7 1121.14 2234 - 2247 2242.47 2.97E+Ol 7.60 3.69E+Ol 1. 92 F 8 1333. 46 2661 - 2672 2667.05 2.61E+Ol 6.94 2.36E+Ol 2.0 4 F 9 1461. 79 2913 - 2933 2923. 69 S.03E+02 22. 72 1.83E+Ol 2.71 M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/15/2017 12:30:SSPM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPp\Qata\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 238.68 2.94E+02 23.86 2.94E+02 2.39E +Ol F 2 295.63 1.00E+02 15.90 l.OOE+02 1. 59E+O l F 3 352.09 1. 69E+02 17.18 8.36E+Ol l. 86E+Ol 8 .52E+Ol 2. 53E+Ol F 4 583.42 l.08E+02 12.41 l.08E+02 1. 24E+O l F 5 609.71 1.27E+02 14.21 4.12E+Ol 1.21E+Ol 8.61E+Ol 1. 8 7E+O l F 6 662 .11 8.64E+02 31.11 6.61E+Ol 1.27E+Ol 7 .98E+02 3.36E+O l F 7 1121.14 2.97E+Ol 7.60 2*. 97E+Ol 7.60E+OO F 8 1333.46 2.61E+Ol 6.94 2,61E+Ol 6.94E+OO F 9 1461.79 5 .03E+02 22.72 5.03E+02 2.2 7E+Ol M = First peak in a multiplet region

=

m other peak in a multiplet region F =Fitted singlet Errors quoted at 1.000sigma

9/15/2017 12:31:0BPM Pagc3 of6 Analysis Report for L 1-SUB-CDR-FSGS-O0EH>B LI-SUBCDR NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dalryland_NPP\Library\HOTlAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (keV) (uCVgrams) Uncertainty CS-137 0. 96 661. 65

85.12 6.35E-07 3.lBE-08 PB-212 0. 56 77 .11 17. 50 238.63

44. 60 1. 78E-07 1.52E-08 BI-214 0.55 609.31

46.30 l.17E-07 2.SSE-08 1120.29

15.10 2.14E-07 5.49E-08 1238.11 5.94 1377.67 4 .11 1407.98 2.48 1509.19 2.19 1764.49 15.80 PB-214 0 .71 77.11 10.70 295.21

19 .20 1. 68E-07 2.71E-08 351. 92

37.20 8.66E-08 2.58E-08

= Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmean Wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCi/grams) 7 CS-1 37 PB-212

o. 967 0.560 6 . 3 5E - 07

l. 7 8E-07 3.lBE-08

1. 52E-08 BI-214 0.554 l .3 4E-07 2.31E-08

9/15/2017 12:31:0SPM Page4 of6 Analysis Report for L 1-SUB-CDR-FSGS-006..SB LI-SUBCDR Nuclide Nuclide wtmean Wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCUgrams)

PB-214 0.711 1.26E-07 1. 87E-08

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

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

9/15/2017 12:31:0BPM Page 5 of6 Analysis Report for L 1-SUB-CDR-FSGS-006-SB LI-SUB CDR UNIDENTIFIED PEAKS Peak Locate Perfonned on : 9/15/2017 12:30:59PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 4 583.42 2.99132E-02 11.53 F 8 1333.46 7.25996E-03 26.54 F 9 1461. 79 l.39626E-0l 4.52 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Ubrary\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams) (uCUgrams)

(keV)

+ K-40 1460.75 10.67 6.65E-06 1.42E-06 1.42E-06

+ )AR-41 1293.64 99.16 7.74E-08 1. 87E-07 1. 87E-07

+ CO-60 1173.22 100.00 5.29E-08 5.83E-08 7.21E-08 1332.49 100.00 1.35E-08 5.83E-08

+ KR-85 513.99 0.43 8.27E-06 1.0BE-05 1 . 08E-05

+ Y-88 898.04 93.70 2.43E-08 3.03E-08 4.84E-08 1836.06 99.20 -9.56E-09 3.03E-08

+ NB-94 702.63 100.00 1. 48E-08 4.0lE-08 4.0lE-08 871.10 100.00 -5.17E-08 4.49E-08

+ I-131 284.30 6.06 -1 .38E-07 4.42E-08 5.60E-07 364.48 81.20 2.52E-08 4.42E-08 636.97 7.27 1. 48E-07 5.68E-07

+ ;s-134 604.70 9 7.60 -8.86E-10 4 . 95E-08 5.27E-08 795.84 85.40 -5. llE-08 4.95E-08

+ CS-137 661. 65

85.12 6.35E-07 5.95E-08 5.95E-08

9/15/2017 12:31:0SPM Page 6 of6 Analysis Report for L1-SUB-CDR-FSGS-006-SB LI-SUB CDR Nuclide Energy Yield(3/4) Activity NuclideMDA LineMDA Name (uCVgrams) (uCUgrams) (uCVgrams)

(keV)

+ CE-144 80.12 1.36 -2. 79E-07 2.82E-07 3.40E-06 133. 51 11. 09 5.60E-08 2.82E-07

+ EU-152 121.78 28.40 -2.46E-08 1. 09E-07 l.09E-07 244.69 7 .49 8.37E-09 5 .03E-07 964.00 14.44 1.94E-07 3.77E-07 1408.00 20.74 5.26E-08 2.0lE-07

+ EU-154 123.07 40 . 40 -4.lOE-08 7.62E-08 7.62E-08 247.94 6.60 -5.97E-07 5.14E-07 723.30 19.70 2.30E-07 2.30E-07 873.20 11.50 1.89E-09 3.96E-07 1004.76 17.90 4.43E-08 2.84E-07 1274.51 35.50 -1 .41E-07 1. 41E-07

+ EU-155 86.54 32.80 2.BOE-08 1. 23E-07 1. 23E-07 105.31 21. 80 7.19E-08 1. 46E-07

+ BI-214 609.31

46.30 1. l 7E-07 9.42E-08 9.42E-08 1120. 29

15.10 2.14E-07 2.58E-07 1238 .11 5.94 5.45E-07 1. lOE-06 1377 .67 4.11 -1. 02E-06 9.69E-07 1407.98 2.48 4.40E-07 1.68E-06 1509.19 2.19 3.55E-07 1. BlE-06 1764.49 15.80 2.57E-07 2.86E-07

+ PB-214 77.11 10.70 3.17E-07 9.41E-08 4.61E-07 295.21

19.20 1 .68E-07 1. 28E-07 351.92

37.20 8.66E-08 9.41E-08

+ PA-228 89.95 22.00 l.67E-07 1. 14E-07 1.96E-07 93.35 35.00 -3. 96E-08 1.14E-07 105.00 16.30 1. 40E-07 2. 15E-07 129.22 2.97 1. 02E-07 1. l 7E-06 338.32 5.30 -9.93E-08 7.59E-07 463.00 1 3.80 9.87E-09 3.31E-07 911. 2 3 16.70 2.27E-07 3.78E-07

+ / AM-241 59.54 36.30 8.64E-08 2.13E-07 2.13E-07

+ CM-243 103.76 23.00 6.43E-08 1. 40E-07 1. 40E-07 228.18 10.60 6.llE-08 2 . 99E-07 277.60 14.00 1.69E-08 2.46E-07

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

9/14/2017 6:41:44PM Page 1 of7

~Apex-Gamma Analysis Report for l 1-SUB-CDR-FSGS-007-SB UNIT L 1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-FSGS-007-SB /

Sample Description : UNIT L1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli /

Unit Sample Point Sample Size : 8.8481:+02 grams Facility : Dairyland_NPP Sample Taken On : 9/13/2017 1:50:00PM Acquisition Started : 9/14/2017 5:41:23PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry

500ml Marinelli /

live Time : 3600.0 seconds Real Time : 3609.3 seconds Deadllme : 0.26 % /

Peak locate Threshold : 3.00 Peak Locate Range (In channels) : 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 718/2014 Efficiency Calibration Description Sample Number : 3393 PEAK ANALYSIS REPORT Peak Analysis Perfonned on : 9/14/2017 6:41:35PM Peak Analysis From Channer : 1oo Peak Analysis To Channel : 4096

9/14/2017 6:41:44PM Page2 of7 Analysis Report for L 1-SUB-CDR-FSGS-007-SB UNIT L1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak Net Peak NetArea Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.14 147 - 157 152.82 l.56E+02 29.13 5.89E+02 2.98 F 2 238.73 469 - 485 477.93 3.74E+02 26.91 3.99E+02 2.73 F 3 295.04 582 - 597 590.52 l.20E+02 17.56 2.42E+02 2.31 F 4 352.24 697 - 709 704.91 l.34E+02 16.08 1. 66E+02 1. 86 F 5 583.66 1160 - 1176 1167.66 l.10E+02 13.42 7.85E+Ol 2.71 F 6 609.56 1213 - 1228 1219.45 1.20E+02 14.12 8.84E+Ol 2.51 F 7 662.00 1314 - 1333 1324.31 5.17E+02 24.42 8.47E+Ol 2.73 F 8 911.76 1818 - 1830 1823.75 6.41E+Ol 9.91 3.03E+Ol 2.76 F 9 1333.32 2659 - 2673 2666.78 6.21E+Ol 9.65 2.62E+Ol 2.88 F 10 1461. 75 2914 - 2933 2923.61 5.50E+02 23.86 1. 71E+Ol 3.12 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/14/2017 6:41 :35PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 76.14 1.56E+02 29.13 1. 56E+02 2.91E+Ol F 2 238.73 3.74E+02 26. 91 3.74E+02 2.69E+Ol F 3 295.04 1.20E+02 17.56 1. 20E+02 1.76E+Ol F 4 352.24 1 .34E+02 16.08 8.36E+Ol l.86E+Ol 5.05E+Ol 2.46E+Ol F 5 583.66 1.10E+02 13.42 1.10E+02 1. 34E+Ol F 6 609.56 1.20E+02 14.12 4.12E+Ol 1.21E+Ol 7.86E+Ol 1.86E+Ol F 7 662.00 5.17E+02 24.42 6.61E+Ol 1.27E+Ol 4.51E+02 2.75E+Ol F 8 911. 76 6.41E+Ol 9.91 6.41E+Ol 9.91E+OO F 9 1333.32 6. 21E+Ol 9.65 6.21E+Ol 9.65E+OO F 10 1461. 75 5.50E+02 23.86 5.50E+02 2.39E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma

9/14/2017 6:41 :44PM Page 3 of7 Analysis Report for L 1-SUB-CDR-FSGS-007-SB UNIT L1-SUB CDR 09/13/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apax\Root\Dalryland_NPP\Llbrary\HOTI.AB.NLB IDENTIFIED NUCLIDE$

Nuclide Id Energy Yield(%) Activity Activity Name Confidence (kev,J (uCVgrams) Uncertainty K-40 0. 85 1460.75

10.67 6.78E-06 3.49E-07 CS-137 0. 9B 661.65

85.12 3.44E-07 2.30E-08 PB-212 0. 95 77 .11

17.50 2.53E-07 4.81E-08 238.63

44. 60 2.18E-07 1. 67E-08 BI-214 0. 34 609.31

46.30 1.02E-07 2.44E-08 1120. 29 15.10 1238 .11 5.94 1377.67 4 .11 1407.98 2. 48 1509.19 2.19 1764.49 15.80 PB-214 0 .96 77.11

10. 70 4.lSE-07 7. 86E-08 295.21

19.20 1.93E-07 2.88E- 0 8 351.92

37.20 4.94E-08 2.41E-08

= Energy line found in the specln.lm.

- =Manually added nuclide.

? =Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000slgma INTERFERENCE CORRECTED REPORT Nuclide Nuclide wt mean Wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCl/grams)

/c-40 0.8 5 2 6.78E-06 3 .4 9E-07 S-137 0. 981 3.44E-07 2 . 30E-08

9/14/2017 6:41:44PM Page 4 of7 Analysis Report for L1-SUB-CDR-FSGS-007-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Nuclide Wt mean Wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCilgrams)

PB-212 0.957 2.lSE-07 1. S BE-08 BI-214 0.345 1.02E-07 2.44E-08 PB-214 0.966 1.06E-07 1.BOE-08

? = 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 1.000sigma

9/14/2017 6:41 :44PM Page 5 of7 Analysis Report for L1-SUB-CDR-FSGS-007-SB UNIT L1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/14/2017 6:41:35PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS (%) Peak Tolerance PeakNo. Energy (kaV} Peak Size (CPS) Uncertainty fype Nuclide F 5 583.66 3.06596E-02 12.16 f).,.=wg F 8 911.76 1 .78176E-02 15.44 Tol. Qi)

PA-228 F 9 1333. 32 l.72450E-02 15.54 G,1-06 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000slgma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yleld("A,) Activity NuclideMDA LineMDA Name (uCVgrams) (uCUgrams) (uCVgrams)

(keV)

+ K-40 1460.75

10.67 6.78E-06 3. 46E-07 3.46E-07

+ AR-41 1293.64 99.16 2.07E-03 2.49E-03 2.49E-03

+ CO-60 1173.22 100.00 9.23E-08 6.70E-08 7.83E-08 1332.49 100.00 1.0lE-07 6.70E-08

+ KR-85 513. 99 0 .43 l.24E-05 9.79E-06 a J *

"70li'-n&:

I JL..J V V

+ Y-88 898.04 93.70 2.30E-08 3.25E-08 4.89E-08 1836.06 99.20 -2.70E-08 3.25E-08

+ NB-94 702.63 100.00 -8.87E-09 3. 86E-08 3.86E-08 871.10 100.00 -4 .61E-08 4.37E-08

+ I-131 284.30 6.06 2.12E-08 4.57E-08 5.80E-07 364.48 81.20 -4.20E-09 4.57E-08 636.97 7.27 2.45E-08 5.97E-07

+ CS-134 604.70 97.6 0 -1. 42E-08 4.93E-08 4.93E-08

9/14/2017 6:41:44PM Page 6 of7 Analysis Report for L 1-SUB-CDR-FSGS-007-SB UNITL1-SUB CDR09/13/17 Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (uCVgrams) (uCi/grams) (uCi/grams)

(keV)

CS-134 795.84 85.40 2.81E-08 4.93E-08 5.13E-08

+ CS-137 661. 65

85.12 3.44E-07 5.96E-08 5.96E-08

+ CE-144 80.12 1. 36 -3.86E-06 2.64E-07 3.32E-06 133. 51 11.09 1. 49E-07 2 .64E-07

+ EU-152 121.78 28.40 -7.32E-08 1.02E-07 1.02E-07 244,69 7.49 -2.71E-07 4.93E-07 964.00 14.44 4.44E-07 3.86E-07 1408.00 20.74 3.28E-08 1.83E-07

+ EU-154 123.07 40.40 -2.02E-08 7.24E-08 7 .24E-08 247.94 6.60 -4.63E-07 5. llE-07 723.30 19.70 2.SlE-07 2.21E-07 873.20 11.50 3.14E-07 3.93E-07 1004.76 17.90 1.31£-07 2.BOE-07 1274.51 35 .50 4.24E-09 1.42E-07

+ EU-155 86.54 32.80 -1. 22E-08 1 .lBE-07 l. lBE-07 105.31 21. 80 3.66E-08 1.46E-07

+ BI-214 609.31

46.30 1.02E-07 9.57E-08 9.57E-08 1120.29 15.10 2.29E-07 4.16E-07 1238 .11 5 .94 1. 41E-07 1.09E-06 1377.67 4 .11 3.15E-07 9.99E-07 1407.98 2.48 2.74E-07 1.53E-06 1509.19 2.19 3.28E-07 1. 77E-06 1764.49 15.80 1. 50E-07 2.79E-07

+ PB-214 77 .11

10.70 4.lSE-07 9.73E-08 3.34E-07 295.21

19. 20 l.93E-07 1. 48E-0 7 351.92

37.20 4.94E-08 9.73E-08

+ PA-228 89.95 22.00 6.25E-07 2.47E-07 4.21 E-07 93.35 35.00 6.83E-08 2 .47E-07 105.00 16.30 1.57E-07 4.78E-07 129.22 2. 97 1.21E-06 2.41E- 0 6 338.32 5.30 4.22E-07 1. 64E- 0 6 463.00 13.80 3.62E-07 7.14E-07 911. 23 16.70 4.32E-07 7.73E-07

+ AM-241 59.54 36 . 30 - 7 .4 5E-0 8 2.14E-07 2.14E-07

+ CM-243 103 . 7 6 23.00 7.BBE-08 1. 40E-07 1. 40E- 0 7 228.18 10.60 6.22E-08 2 .89E- 0 7 277.60 14.00 -4.27E-08 2.29E-07

+ = Nuclide identified during the nuclide identification

.. ::: Energy tine found in the spectrum

> = MDA value not calculated

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

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

9/14/2017 6:41 :44PM Page 7 of7 Analysis Report for L1-SUB-cDR-FSGS-007-SB UNIT L 1-SUB CDR 09/13/17

9/15/2017 1:33:20PM Page 1 of7 Analysis Report for l 1-SUB-COR*FSGS-008-SB l1*SUBCDR GAMMA SPECTRUM ANALYSIS Sample Identification : L1*SUB-CDR-FSGS.008--SB .

Sample Description : L1-SUBCDR Sample Type : 500 mt Marinelli Unit Sample Point Sample Size : 8.417E+02 grams Facility : Dairyland_NPP Sample Taken On : 9/15/2017 9:05:00AM /

Acquisition Started : 9/15/2017 12:32:58PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTI.AB /

Geometry : 500ml Marinelli Live Time : 3600.0 seconds Real Time : 3609.9 seconds Dead lime : 0.28%

Peak Locate Threshold : 3.00 Peak locate Range (In channels) : 100*4096 Peak Area Range (in channels) : 100

4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 3403 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/15/2017 1:33:11PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 1:33:20PM Page2 of7 Analysis Report for L 1-SUB-CDR-FSGS-008-SB L1-SUB CDR Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.78 147 - 158 154.10 l.41E+02 25.19 5.91E+02 1. 96 F 2 238.80 473 - 485 4 78. 07 2.60E+02 23.22 3.28E+02 2.07 F 3 295.58 586 - 595 591.61 6.40E+Ol 14.50 1. 92E+02 1. 42 F 4 352 .12 697 - 712 704.66 l .58E+02 17.20 2.21E+02 1. 83 F 5 583.83 1162 - 1176 1168.01 4.93E+Ol 10.56 8.02E+Ol 2.10 F 6 609.64 1213 - 1226 1219.62 8.09E+Ol 12.37 7.19E+Ol 2.43 F 7 662.05 1317 - 1333 1324.41 9.30E+02 31.87 6.99E+Ol 2.23 F 8 1120. 67 2237 - 2248 2241. 53 4.58E+Ol 8.59 2.69E+Ol 2.49 F 9 1174.27 2344 - 2357 2348.72 6.28E+Ol 9.41 3.09E+Ol 2.32 F 10 1332.99 2660 - 2674 2666 .13 5.llE+Ol 8.05 1.34E+Ol 2.70 F 11 1461. 76 2914 - 2933 2923.63 5.10E+02 22.78 7.41E+OO 2.94 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/15/2017 1:33:11 PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peale Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 76. 78 1.41E+02 25.19 1. 41E+02 2.52E+Ol F 2 238.80 2.60E+02 23.22 2.60E+02 2.32E+Ol F 3 295.58 6.40E+Ol 14.50 6.40E+Ol 1.45E+Ol F 4 352.12 1 .58E+02 1 7 .20 8.36E+Ol 1. 86E+Ol 7.41E+Ol 2.53E+Ol F 5 583.83 4.93E+Ol 10.56 4.93E+Ol 1.06E+Ol F 6 60 9. 64 8.09E+Ol 12.37 4.12E+Ol 1. 21E+Ol 3.97E+Ol 1.73E+Ol F 7 662.05 9.30E+02 31. 87 6.61E+Ol l.27E+Ol 8.64 E+02 3 .43E+Ol F 8 1120,67 4.58E+Ol 8.59 4.58E+Ol 8.59E+ OO F 9 1174.27 6.28E+Ol 9.41 6.28E+Ol 9.41E+OO F 10 1332.99 5.llE+Ol 8.05 5.llE+Ol 8.05E+OO F 11 1461. 76 5.10E+02 22.78 5.10E+02 2.28E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma

9/15/2011 1:33:20PM Page3 of7 Analysis Report for L 1-SUB-CDR-FSGS-008-SB L1-SUBCDR NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{°/4) Activity Activity Name Confidence (ke~ (uCilgrams) Uncertainty CS-137 0 .97 661.65

85.12 6.94E-07 3.33E-08 PB-212 0.99 77.11

17 .50 2.38E-07 4.31E-08 238.63

44.60 l.60E-07 1.48E-08 BI-214 0.57 609.31

46.30 5.43E-08 2.37E-08 1120.29

15.10 3.33E-07 6.29E-08 1238.11 5. 94 1377.67 4 .11 1407.98 2.48 1509.19 2.19 1764.49 15.80 PB-214 0.98 77 .11

10.70 3.89E-07 7.06E-08 295.21

19.20 1. 09E-07 2.48E-08 351.92

37.20 7.61E-08 2.61E-08

= Energy line found in the spectrum.

- = Manually added nudide.

? = Manually edited nuclide.

@ == Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0,30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmean wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCl/grams)

J 7 CS-137 0.975 6.94E-07 3.33E-08

9/15/2017 1:33:20PM Page4 of7 Analysis Report for L 1-SUB-CDR-FSGS-008-SB L1-SUB CDR Nuclide Nuclide wt mean wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCVgrams)

PB-212 0.992 l.62E-07 1. 41E-08 BI-214 0.572 8.91E-08 2.22E-08 PB-214 0.988 9.52E-08 l.75E-08

? = 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 1.000sigma

9/15/2017 1:33:20PM Page 5 of7 Analysis Report for L1-SUB-CDR-FSGS-008..SB L1..SUB CDR UNIDENTIFIED PEAKS Peak Locate Performed on : 9/15/2017 1:33:11PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS (3/4) Peak Tolerance Peak No. Energy (keV) Peak Size {CPS) Uncertainty Type Nuclide F 5 583.83 l. 37029E-02 21. 41 11 lot -

F 9 1174.27 1.74501E-02 14.97JL;~u,<d:>~~~~-,,

F 10 1332. 99 1 .41832E-02

15. 77 '1 r-~'\-f~

F 11 1461.76 1.41547E-0l 4.47 ~ -z.3

't, M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Enors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Llbrary\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclldsMDA LlneMDA Name (uCUgrams) (uCUgrams) (uCUgrams)

(keV)

+ K-40 1460 .75 10.67 6.74E-06 1.42E-06 1. 42E-06

+ AR-41 1293.64 99.16 9.13E-08 2.26E-07 2.26E-07

+ CO-60 1173 .22 100.00 4.0 2E-08 6.13E-08 6.82E-08 1332. 49 100.00 7.16E-08 6.13E-08

+ KR-85 513.99 0.43 6.lSE-06 1.03E-05 l.03E-05

+ Y- 88 898. 04 93.70 -2.59E-08 2 . 68E- 0 8 ,1

.1. *

,l:; l;l;' _() Q v ..;.&..1 V Y 1836.06 99.20 -1 . 1 3E-08 2 . 68E-08

+ NB-94 702.63 1 00.00 -1 .06E-08 3.98E-08 3.98E-08 87 1. 10 100.00 -1. 95E-08 4.34E-08

+ I-131 284.30 6.06 -1.97E-07 4. 45E-08 S .84E-07 364.48 81.20 8.39E-09 4.45E-08 63 6.97 7.27 -1 .57E-0 7 5 .82E-07

+ CS-134 604.70 97 .60 -2.36E-08 4.74E-08 4. 74E-08 795.84 85.40 -3 .68E-08 5.14E-08

9/15/2017 1:33:20PM Page 6 of7 Analysis Report for L 1-SUB-CDR-FSGS-008-SB L1-SUBCDR Nuclide Energy Yield(%) Activity Nucl;deMDA LineMDA Name (uCVgrams) (uCVgrams) (uCVgrams)

(keV)

+ CS-137 661. 65

85.12 6.94E-07 5.81E-08 5.81E-08

+ CE-144 80.12 1.36 -1. 82E-06 2.75E-07 3.32E-06 133.51 11.09 1.35E-07 2.75E-07

+ EU-152 121.78 28.40 -5.97E-09 1.07E-07 1.07E-07 244.69 7.49 -3.93E-07 5. 03E-07 964.00 14.44 9.76E-08 3.77E-07 1408.00 20.74 -4.52E-08 1.87E-07

+ EU-154 123.07 40.40 3.03E-09 7.59E-08 7.59E-08 247.94 6.60 -5.71E-07 5.26E-07 723.30 19. 70 1. 25E-07 2.lSE-07 873.20 11.50 -4.25E-08 3.83E-07 1004.76 17.90 -1. 54E-07 2.73E-07 1274.51 35.50 -1.84E-08 1. 45E-07

+ EU-155 86.54 32.80 -8.37E-08 1. 16E-07 1.16E-07 105.31 21. 80 -1. 90E-08 1.48E-07

+ BI-214 609.31

46.30 5.43E-08 9.22E-08 9.22E-08 1120.29

15.10 3.33E-07 2.17E-07 1238.11 5 .94 6.83E-07 1.09E-06 1377.67 4 .11 l.28E-07 1.06E-06 1407.98 2.48 -3.78E-07 1.57E-06 1509.19 2.19 6.79E-08 1. 74E-06 1764.49 15.80 1.82E-07 2.56E-07

+ PB-214 77 .11

10.70 3.89E-07 1. 14E-07 3.56E-07 295.21

19.20 l.09E-07 1.21E-07 351. 92

37.20 7.61E-08 1. 14E- 0 7

+ PA-228 89.95 22.00 2.75E-07 1.15E-07 1.93E-07 93.35 35.00 7.12E-08 1. 15E-07 105.00 16.30 4.89E-08 2.25E-07 129.22 2.97 6 . 63E-07 1. 16E-06 338.32 5.30 -l.54E-07 8.07E- 0 7 463.00 13.80 1 .79E-07 3.59E-07 911. 23 16. 70 3.04E-07 3.66E-07

+ AM-241 59.54 36.30 3.31E-08 2.19E-07 2 .19E- 0 7

+ CM-243 103.76 23.00 1. 12E-07 1.43E-07 1. 43E-07 228.18 10.60 -1. 22E-07 3.00E-07 277.60 14.00 -6.00E-08 2.51E-07

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

9/15/2017 1:33:20PM Page 7 of7 Analysis Report for l 1-SUB..CDR-FSGS-008-SB l1-SUBCOR

~-...

9/14/2017 7:47:22PM Pagel of5

_..3Apex-Gamma Analysis Report for l 1-SUB-CDR-FSGS-009-SB UNIT L1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-FSGS-009-SB /

Sample Description : UNIT L1-SUB CDR 09/13/17 Sample Type : 500 mt Marinelli Unit Sample Point SampteSize : 9.393E+02 grams/

Facility : Dairyland_NPP Sample Taken On : 9/13/2017 1:54:00AM Acquisition Started : 9/14/2017 6:46:59PM Procedure : 500ml Marinelli Operator : Administrator Detector Name :HOTLAB /

Geometry : 500ml Marinelli ~

liveTrme : 3800.0 seconds" Real Time : 3610.7 seconds Dead Time : 0.30 % /

Peak Locate Threshold : 3.00 Peak locate Range (in channels) : 100- 4096 Peak Area Range (in channels) : 100 -4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 718/2014 Efficiency Calibration Description Sample Number ! 3394 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/14/2017 7:47:13PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/14/2017 7:47:22PM Page2 ofS Analysis Report for l 1-SUB-CDR-FSGS-009-SB UNIT L1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 609.33 1212 - 1227 1219.00 1. 66E+02 18.42 1.64E+02 3.43 F 2 662.02 1316 - 1333 1324.36 8.76E+03 95.22 1.78E+02 2.77 F 3 1173.89 2337 - 2357 2347.95 3.56E+02 20.99 9.19E+Ol 3.12 F 4 1333.30 2658 - 2677 2666.73 3.17E+02 18.48 2 .28E+Ol 3.26 F 5 1461.80 2913 - 2934 2923.72 5.33E+02 23.70 2. 75E+ Ol 3.19 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/14/2017 7:47:13PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 609.33 1. 66E+02 18.42 4.12E+Ol l.21E+Ol 1.25E+02 2.20E+O l F 2 662.02 8 .7 6E+03 95.22 6.61E+Ol 1.27E+Ol 8.69E+03 9.61E+Ol F 3 1173.89 3.56E+02 20.99 4.SSE+Ol 8.6 2E+OO 3.10E+02 2.27E+Ol F 4 1333.30 3.17E+02 18.48 3. 17E+02 1.BSE+Ol F 5 1461.80 5.33E+02 23.70 5.33E+02 2.37E+01 M = First peak in a multiplet region m :: Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES

9/14/2017 7:47:22PM Page 3 of5 Analysis Report for L 1-SUB-CDR-FSGS-009-SB UNIT L1-SUB CDR 09/13/17 Nuclide Id Energy Yield{%) Activity Activity Name Confidence (keV) (uCUgrams) Uncertainty CO-60 0.91 1173.22

100.00 3.18E-07 2.45E-08 1332.49

100.00 3.63E-07 2 .31E-08 CS-137 0.97 661. 65

85.12 6.25E-06 1.83E-07 BI-214 0.35 609.31

46.30 1.54E-07 2.74E-08 1120.29 15 .10 1238.11 5.94 1377.67 4.11 1407 .98 2.48 1509.19 2.19 1764.49 15.80

= Energy line found ln the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000s!gma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmean Wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCilgrams) rc0-60 0. 915 3.42E-07 1. 68E-08 CS-137 0.978 6.25E-06 1. 83E-07 BI-214 0.350 1. 54E-07 2.74E-08

? = 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 1.000sigma

9/14/2017 7:47:22PM Page4 of5 Analysis Report for L 1-SUB-CDR-FSGS-009-SB UNIT L 1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/14/2017 7:47:13PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 5 1461. 80 1. 48055E-01 4.45 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\library\HOTLAB.NLB Nuclide Energy Yie/d{°./4) Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams) (uCUgrams)

(keV)

+ K-40 1460.75 10.67 6.69E-06 1.34E-06 1.34E-06

+ 1293.64 99.16 2.79E-02 3.47E-01 3.47E-01

/ AR-41

+ CO-60 1173.22

100.00 3.18E-07 3.71E-08 7.45E-08 1332.49

100.00 3.63E-07 3.71E-08

+ KR-85 513.99 0.43 1.16E-05 1.52E-05 1.52E-05

+ Y-88 898.04 93.70 2.04E-08 3.07E-08 5.73E-08 1836.06 99.20 l.28E-08 3.07E-08

+ NB-94 702.63 100.00 -4.37E-08 4.09E-08 4.09E-08 871.10 100.00 -1. 93E-08 5 .12E-08

+ I-131 284.30 6.06 5.l0E-07 8.86E-08 1.03E-06 364.48 81.20 5.95E-08 8.86E-08 636.97 7. 2 7 5.36E-07 9.33E- 0 7

+ CS-134 604.70 97.60 -l. 33E-0B 5. 73E-08 6.32E-08

+

J CS-137 CE-144 795.84 661. 65 80.12 85.40 85.12 1.36

-2 . llE-0 8 6.25E-06 8.l0E-07 6.86E-08 3.97E- 07 5.73E-08 6.86E-08 4.12E-0 6 133.51 11.09 5.78E-07 3.97E-07

9/14/2017 7:47:22PM Page 5 of 5 Analysis Report for L1-SUB-CDR-FSGS-009-SB UNIT L1-SUB CDR 09/13/17 Nur:lide Energy Yield(%) Activity NuclideMDA UneMDA Name (uCVgramsJ (uCilgrams) (uCVgrams)

(keV)

+ EU-152 121.78 28. 40 -1.70E-07 l.48E-07 1. 48E-07 244.69 7.49 -9.98E-08 6.88E-07 v1964.00 14.44 2.52E-07 4.06E-07 408.00 20.74 -3.37E-09 1.96E-07

+ EU-154 123.07 40.40 -4.0lE-08 1 .0SE-07 1. OSE-07 247.94 6.60 -1. 68E-06 7 .97E-07 723.30 19.70 1. 02E-07 2.26E-07 873.20 11. 50 -2.72E-07 4.40E-07 1004.76 17.90 6.26E-08 3 .05E-07 1274.51 35.50 7 .19E-08 1. 50E-07

+ EU-155 86.54 32.80 -l.2DE-07 1. 52E-07 1. 52E-07 105.31 21.80 -5.75E-08 2.02E-07

+ BI-214 609.31

46. 30 1.54E-07 1.09E-07 1. 09E-07 1120 .29 15.10 4.51E-07 4.35E-07 1238.11 5.94 6.14E-07 1.13E-06 1377.67 4.11 3.62E-07 l.03E-06 1407.98 2.48 -2.82E-08 1.64E-06 1509.19 2 .19 1. OlE-06 1.91E-06 1764.49 15.80 3.09E-08 2.47E-07

+ PB-214 77.11 10.70 4.SSE-07 1 .70E-07 5.53E-07 295.21 19.20 2.56E-07 2.89E-07 351. 92 37.20 1.91E-07 1.70E-07

+ PA-228 89.95 22.00 5. 80E-07 4.96E-07 8. 1 9E-07 93.35 35.00 -4.02E-08 4.96E-07 105.00 16.30 -2.78E-07 9.95E-07 129.22 2.97 2.64E-06 5.37E-06 338.32 5.30 1.32E-07 4.09E-06 463.00 13.80 9 . 4 6E-08 2.21E-06 911.23 16.70 1.llE-06 1. 37E-06

+ AM-24~ 59.54 36.30 3.13E-07 2.94E-07 2.94E- 07

+ CM-243 103.76 23.00 -3 .04E-08 1.92E-07 1.92E-0 7 228.18 10.60 -l.39E-07 4.58E-07 277.60 14.00 2.99E-07 3.92E-0 7

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

9/15/2017 6:07:07AM Page 1 of6

~pex-Gamma Analysis Report for L1-SUS-CDR-FSGS-010-SB UNIT L 1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-FSGS-010-SB Sample Description : UNIT L 1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 9.582E+02 grams Faclllty : Dalryland_NPP Sample Taken On : 9/13/2017 2:00:00PM j Acquisition Started : 9/15/2017 5:06:46AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB /

Geometry : 500ml Marinelli";

Live Time : 3600.0 secondlf Real Time : 3609.2 seconds Dead llme : 0.26 %

Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100 -4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/812014 Efficiency Calibration Description Sample Number : 3396 PEAK ANALYSIS REPORT Peak Analysis Perfonned on : 9/15/2017 6:06:58AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 6:07:07AM Page2 of6 Analysis Report for L 1-SUB-CDR-FSGS-010-SB UNIT L 1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.84 472 - 485 478.16 3. 11E+02 27.83 4.46E+02 2.98 F 2 352.22 698 - 713 704.88 2.17E+02 20.56 2.25E+02 2.64 F 3 609.79 1210 - 1227 1219.92 1. 52E+02 15.26 9.22E+Ol 2.77 F 4 661.93 1314 - 1333 1324.17 1.64E+03 41. 86 8.75E+Ol 2 .81 F 5 1333. 44 2661 - 2674 2667.02 4.98E+Ol 8.58 2.26E+Ol 2.66 F 6 1461.52 2915 - 2932 2923.15 5.31E+02 23.52 2.0lE+Ol 3.06 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet E1Tors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/15/2017 6:06:58AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peale Energy Original Orig. Area Ambient Baclcgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 238.84 3. 11E+02 27.83 3.11E+02 2.78E+O l F 2 352.22 2.17E+02 20.56 B.36E+Ol 1.86E+Ol l.34E+02 2.77E+O l F 3 609.79 1. 52E+02 15.26 4.12E+Ol 1. 21E+Ol 1 .11E+02 1.95E+Ol F 4 661.93 1. 64E+ 03 41.86 6.61E+Ol 1.27E+Ol 1.57E+03 4.37E+O l F 5 1333 . 44 4.98E+Ol 8.58 4.98E+Ol 8.58E+OO F 6 1461.52 5 .31E+02 23.52 5.63E+Ol 8.57E+OO 4.74E+02 2.SOE+Ol

=

M First peak in a multiplet region

=

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

9/15/2017 6:07:07AM Page 3 of6 Analysis Report for L1*SUS-CDR-FSGS.010-SB UN IT L1-SUB CDR 09/13/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTI.AB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (uCVgrams) Uncertainty K-40 0 .91 1460.75

10.67 5 .40E-06 3.22E-07 CS-137 0 .98 661.65

85.12 1.llE-06 4.30E-08 PB-212 0 .55 77 .11 17 .so 238.63

44.60 1.67E-07 1. 56E-08 BI-214 0 .33 609.31

46.30 1.34E-07 2.37E-08 1120.29 15.10 1238.11 5.94 1377.67 4 . 11 1407.98 2.48 1509.19 2.19 1764.49 15.80

= Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ =Energy line not used fer Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPORT Nuclide ,v.**,..,,,.,,.. ~*..If mean .... ,,,ca,,

I.AN----

U'-HW'&' Comments Name Id Activity Activity Confidence Uncertainty (uCVgrams)

A-40 0.910 5.40E-06 3.22E-07 S-137 0.988 1. llE-06 4.30E-08 PB-212 0 .555 1.67E-07 1. 56E-08 BI-2 14 0 .331 1.34E-07 2.37E-08

9/15/2017 6:07:07AM Page4of6 Analysis Report for L1-SUB-CDR-FSGS-0 10-SB UNIT L1-SUB CDR 09/13/17

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

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

9/15/2017 6:07:07AM Page 5 of6 Analysis Report for l 1-SUS-CDR-FSGS-010-58 UNIT l 1-SUB CDF~ 09/13/17 UNIDENTIFIED PEAKS Peak Locate Perfonned on : 9/15/2017 6:06:SBAM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 352.22 3.70855E-02 20.77 Tol.

F 5 1333.44 1.38397E-02 17.21 Tol.

M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Ene,gy Yield(%) Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams) (uCVgrams)

(keV)

+ K-40 1460.75

10. 67 5.40E-06 5.48E-07 5.48E-07

+ AR-41 1293. 64 99.16 9.25E-02 1. 58E-01 1. SBE-01

+ CO-60 1173.22 100. 00 5.26E-08 5.78E-08 6.40E-08 1332.49 100.00 S.0SE-08 5. 78E-08

+ KR-85 513. 99 0.43 1. 06E-05 1. 0lE-05 1. 0lE-05

+ Y-88 898.04 93 .70 -2.38E-09 2.61E- 0 8 4.SlE-08 1836.06 99.20 -1.74E-08 2.61E-08

+ NB-94 702. 63 100.00 -4.46E-08 3.53E-08 :! . ~:!F.-0 8 871.10 100.00 -1 .68E-08 3.97E-08

+ I-131 284.30 6.06 3.66E-07 4.99E-08 6.46E-07 364.48 81.20 4.26E-09 4.99E-08 636.97 7.27 -1. 59E-07 6.33E-07

+ CS-134 604.70 97.60 1. 91E-09 4.86E-08 4.90E-08 795.84 85.40 2.08E-08 4.86E-08

+ CS-137 661. 65

85.12 1. llE-06 5.SSE-08 5.55E-08

+ CE-144 80.12 1.36 2. 21E-06 2.67E-07 3.26E-06

9/15/2017 6:07:07AM Page 6 of6 Analysis Report for L1-SUB-CDR-FSGS-010.-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity Nuclide AIDA LlneMDA Name (uCi/grams) (uCVgrams) (uCUgrams)

(keV)

CE-144 133.51 11. 09 -1. 66E-07 2 .67E-07 2.67E-07

+ EU-152 121.78 28.40 -1. 16E-07 1. 04E-07 1.04E-07 244.69 7 .49 -2.40E-07 4.86E-07 964.00 14.44 2.05E-07 3.42E-07 1408.00 20.74 5.67E-09 1.82E-07

+ EU-154 123.07 40.40 -4.52E-08 7.33E-08 7.33E-08 247.94 6.60 -4.44E-07 5.22E-07 723.30 19.70 1. 09E-07 1.86E-07 873.20 11.50 -1. 89E-07 3.38E-07 1004.76 17.90 1. 08E-07 2.SOE-07 1274. 51 35.50 9.21E-08 1.30E-07

+ EU-155 86.54 32.80 -1.34E-07 1. 14E-07 1.14E-07 105.31 21.80 3.56E-08 1.44E-07

+ BI-214 609.31

46.30 1.34E-07 9.06E-08 9.06E-08 1120.29 15.10 8.57E-08 3.77E-07 1238.11 5.94 2.52E-07 8.96E-07 1377.67 4 .11 -7.27E-08 9.22E-07 1407.98 2.48 4.74E-08 1.52E-06 1509.19 2.19 -1. 26E-07 1.45E-0 6 1764.49 15.80 2.53E-07 2.96E-07

+ PB-214 77.11 10.70 2.34E-07 1. 08E-07 4.34E-07 295.21 19.20 2.27E-07 1. 86E-07 351.92 37.20 1.28E-07 1.08E-07

+ PA-228 89.95 22. 00 3.70E-07 3.38E-07 5.74E-07 93.35 35.00 1.42E-07 3.38E-07 105.00 16.30 7.97E-08 6.72E- 0 7 129.22 2.97 2.53E-07 3.47E-06 338.32 5.30 2.12E-07 2.32E-06 463.00 13.80 3.47E-07 1. 12E-06 911. 23 16.70 1.lBE-06 1.06E-06

+ AM-241 59.54 36.30 7.SlE- 08 2 .02E-07 2.02E-07

+ CM-243 103.76 23.00 1.61E-08 1.38E-07 1.38E-07 228.18 10.60 1. lOE-08 2.93E- 0 7 277 .60 14.00 3.57E- 0 8 2.4 7E- 07

.. == Energy

+ Nuclide identified during the nuclide identification line found in the spectrum

> = MDA value not calculated

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

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

~ 9115/2017 7:22:01AM Page I of6 JJApex-Gamma Analysis Report for L 1-SUB-CDR-FSGS-011-SB UNIT L 1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-FSGS-011-SB /

Sample Description : UNIT L1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 7.883E+02 grams Facility : Dairyland_NPP Sample Taken On : 9/13/2017 2:05:00PM . /

Acquisition Started : 9/15/2017 6:21:38AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli./

live Time : 3600.0 seconds Real Time : 3610.1 s 7 s Dead Time : 0.28 %

Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100- 4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 718/2014 Efficiency Calibration Description Sample Number : 3397 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/15/2017 7:21:51AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 7:22:01AM Page 2 of6 Analysis Report for L1-SUB-CDR-FSGS-011-SB UNIT L 1-SUB CDR 09/13/17 Peale Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.84 473 - 485 478.15 3.15E+02 29.68 5.68E+02 2.81 F 2 295.23 587 - 596 590.91 7.78E+Ol 18.86 3.06E+02 1. 81 F 3 352.20 696 - 713 704.82 1.85E+02 22.06 3.78E+02 2.68 F 4 609.55 1213 - 1228 1219.44 1.24E+02 15.17 1.15E+02 2.69 F 5 661.94 1314 - 1333 1324.19 3.33E+03 59.39 1.33E+02 2.82 F 6 1173.79 2339 - 2358 2347.75 1.72E+02 14.95 5.91E+Ol 2.99 F 7 1333. 24 2657 - 2675 2666.61 1.51E+02 13.16 1.90E+Ol 3.76 F 8 1461.53 2915 - 2933 2923.17 5.35E+02 23.49 1. 08E+Ol 3.20 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Pelformed on : 9/15/2017 7:21 :51AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 238.84 3.15E+02 29.68 3.15E+02 2.97E+Ol F 2 295.23 7.78E+Ol 18.86 7.78E+Ol 1.89E+Ol F 3 352.20 1 . 85E+02 22.06 8.36E+Ol 1.86E+Ol 1.01E+02 2.89E+Ol F 4 609.55 1. 24E+02 15.17 4.12E+Ol 1.21E+Ol 8.27E+Ol 1. 94E+Ol F 5 661.94 3.33E+03 59.39 6.61E+Ol 1 .27E+Ol 3.27E+03 6.07E+Ol F 6 1173.79 1.72E+02 14.95 4.SSE+Ol 8.62E+OO l.26E+02 1.73E+Ol F 7 1333.24 1. 51E+0 2 13.16 1.51E+02 l.32E+Ol F 8 1461.53 5.35E+02 23 .49 5.63E+Ol 8.57E+OO 4.79E+02 2.50E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma

9/15/2017 7:22:01AM Page 3 of6 Analysis Report for L 1-SUB-CDR-FSGS-011-SB UNIT L1-SUB CDR 09/13/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dalryland_NPP\Llbrary\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Act,-.vity Name Confidence (keV) (uCVgrams) Uncertainty K-40 0.90 1460.75

10.67 6.62E-06 3.92E-07 C0-60 0. 93 1173.22

100.00 1.54E-07 2.14E-08 1332.49

100.00 2.06E-07 1. 87E-08 CS-137 0. 98 661.65

85.12 2 .BOE-06 9.19E-08 PB-212 0. 55 77.11 17.50 238.63

44. 60 2.06E-07 2.02E-08 BI-214 0. 34 609.31

46.30 1. 21E-07 2.86E-08 1120.29 15.10 1238.11 5.94 1377.67 4.11 1407.98 2.48 1509.19 2.19 1764.49 15.80 PB-214 0.71 77.11 10.70 295.21

19.20 1. 41E-07 3.44E-08 351.92

37.20 l.llE-07 3.lBE-08

= Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmean Wt mean Comments Name Id AC'livity Activity Confidence Uncertainty (uCVgrams)

9/15/2017 7:22:01AM Page4of6 Analysis Report for L 1-SUB-COR-FSGS-011-S8 UNIT L1-SUB COR 09/13/17 Nuclide Nuclide wt mean Wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCilgrams) jK-40 0.908 6.62E-06 3.92E-07 J CO-60 CS-137 0.931

0. 987 l,83E-07 2.80E-06

1. 41E-08 9.19E-08 PB-212 0 .555 2.06E-07 2.02E-08 BI-214 0.345 1. 21E-07 2 . 86E-08 PB-214 0. 715 l. 25E-07 2.33E-08

? = 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 1.000sigma

9/15/2017 7:22:01AM Page 5 of6 Analysis Report for L 1-SUB-CDR-FSGS-011-SB UNIT l 1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Perfonned on : 9/15/2017 7:21:51AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%} Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams) (uCVgrams)

(lreV)

+ K-40 1460.75

10.67 6.62E-06 6.21E-07 6.21E-07

+ AR-41 1293.64 99.16 1.38E-01 3.23E-01 3.23E-01

+ I C0- 60 1173.22 1332.49 100.00 100.00 1.54E-07 2.06E-07 3.96E-08 7,57E-08 3.96E-08

+ KR-85 513.99 0.43 S.04E-06 1. 43E-05 l.43E-05

+ Y-88 898.04 93.70 1. 92E-09 4.SSE-08 5.61E-08 1836.06 99.20 -1.13E-08 4.SSE-08

+ NB-94 702. 63 100.00 7.SlE-09 4.88E-08 4.88E-08 871.10 100.00 -2.87E-08 5.14E-08

+ I-131 284.30 6.06 -1.16E-06 7 .28E-08 8 .BlE-07 364.48 81.20 4.82E-09 7 .28E-08 636.97 7.27 -2.75E-07 7.94E-07

+ CS-134 604.70 97. 60 -1.81E-08 6. 26E-08 6.26E-08

+

J CS-137 CE-144 795.84 661. 65 80 . 12 85.40 85.12 1.36 4.63E-08 2.BOE-06 2.13E-06 7.66E-08 3.SOE-07 6.26E-08 7.66E-08 4.13E-06 133.51 11.09 3.71E-07 3.50E-07

+ EU-152 121.78 28.40 -1.20E-07 l.33E-07 1.33E-07

9/15/2017 *f:22:01AM Page 6 of6 Analysis Report for L 1-SUB-CDR-FSGS-011-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Energy Yield(3/4) Activity NuclldeMDA LlneMDA Name (uCUgrams) (uCUgrams) (uCUgrams)

(keV)

J EU-152 244.69 964.00 7.49 14.44

-3.35E-07 3.07E-07

l. 33E-07 6.68E-07 4.29E-07 1408.00 20.74 7.91E-08 2.43E-07

+ J EU-154 123.07 40.40 -2.97E-08 9.38E-08 9.38E-08 247,94 6.60 -6.59E-07 7 . 29E-07 723.30 19.70 -4.97E-08 2.51E-07 873.20 11. 50 -2.00E-07 4.46E-07 1004.76 17.90 -1. 20E-07 3.07E-07 1274.51 35.50 6.47E-08 1.70E-07

+ EU-155 86.54 32.80 4.09E-08 1.47E-07 1.47E-07 105.31 21. 80 -1.58E-07 1.82E-07

+ BI-214 609.31

46.30 1.21E-07 1.15E-07 1.lSE-07 1120. 29 15 .10 5.16E-07 4.95E-07 1238.11 5.94 1. 03E-06 1. 30E-06 1377.67 4.11 8.69E-07 l.32E-06 1407.98 2.48 6.61E-07 2.03E-06 1509.19 2.19 -5.43E-07 1. 92E-06 1764.49 15.80 2. 48E-07 3.22E-07

+ PB-214 77.11 10.70 7 .45E-07 1.50E-07 5.57E-07 295.21

19.20 1.41E-07 1.62E-07 351. 92

37.20 1. llE-07 1. 50E-07

+ PA-228 89.95 22.00 7.94E-07 4.49E-07 7.58E-07 93.35 35.00 -5.05E-08 4.49E-07 105.00 16.30 -6.42E-07 8.B l E-07 129.22 2.97 2.92E-06 4.66E-06 338.32 5.30 4 . 66E-07 3.37E-06 463.00 13.80 l.lSE-06 l. 78E-06 911. 23 16.70 l.73E-06 1.40E-06

+ /AM-241 CM-243 59.54 103. 7 6 36.30 23.00 8.77E-08 8.19E-08 2 . 77E-07

l. 76E-07 2.77E-07 1.76E-07

+

228.18 10.60 -2 .83E-07 4.04E-07 277.60 14.00 1.92E-07 3.30E-07

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> ::: MDA value not calculated

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

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

9/15/2017 8:23:16AM Page 1 of7 Analysis Report for L 1-SUB-CDR-FSGS-012-SB UNIT L1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-COR-FSGS-012-SB /

w Sample Description : UNIT L 1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size B.660E+02 grams Facility : Dairyland_NPP Sample Taken On : 9/13/2017 2:08:00PM /

Acquisition Started : 9/15/2017 7:22:54AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 3600.0 seconds Real Time : 3610.0 seconds Dead Tlme : 0.28 %

/

Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100-4096 Peak Area Range (in.channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 3398 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/15/2017 8:23:07AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 8:23:16AM Page2 of7 Analysis Report for L1-SUB-CDR-FSGS-012-SB UNIT L1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.73 469 - 485 477.94 4.50E+02 31.83 5.75E+02 3.05 F 2 352.00 698 - 712 704.42 1.8BE+02 21. 45 2.87E+02 2.65 F 3 583.39 1160 - 1176 1167 . 12 l, 11E+02 13.88 1.19E+ 02 2.10 F 4 609.31 1211 - 1228 1218.95 1. l 7E+02 13.95 9.40E+Ol 2.69 F 5 662.02 1314 - 1332 1324. 36 2.11E+03 47.42 l.29E+02 2.41 F 6 911. 94 1818 - 1832 1824.11 7.48E+01 10.99 4.46E+Ol 2.88 F 7 1173.73 2341 - 2355 2347.63 9.84E+Ol 12.56 5.63E+Ol 2.88 F 8 1333.55 2661 - 2677 2667.23 1.03E+02 11.32 2.14E+Ol 3.22 F 9 1461.69 2915 - 2932 2923.49 7.92E+02 28.73 1. 75E+Ol 3.05 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/15/2017 8:23:07AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 238.73 4.50E+02 31.83 4.50E+02 3.18E+Ol F 2 352.00 1.88E+02 21.45 8.36E+01 1. 86E+Ol 1. 05E+02 2.84E+Ol F 3 583.39 1.11E+02 13.88 1.11E+02 1. 39E+Ol F 4 609.31 1.17E+02 13.95 4.12E+Ol 1. 21E+Ol 7.59E+Ol 1. 85E+Ol F 5 662.02 2. 11E+03 47.42 6.61E+Ol 1.27E+Ol 2.04E+03 4.91 E+Ol F 6 911.94 7.48E+Ol 10.99 7.48E+ Ol 1. lOE+Ol F 7 1173.73 9.84E+01 12.56 4.55E+Ol 8.62E+00 5. 2 9E+Ol 1.52 E+Ol F 8 1333.55 l.03E+02 11. 32 l.03E+02 1.13E+Ol F 9 1461.69 7.92E+02 28.73 7.92E+02 2,87E+Ol

=

M First peak in a multiplet region

=

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

9/15/2017 8:23:16AM Page 3 of7 Analysis Report for L1-SUB-CDR-FSGS-012-SB UNIT L 1-SUB CDR 09/13/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPp\Llbrary\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield('1/4) Activity Activity Name Confidence (keV) (uCVgrams) Uncertainty K-40 0.86 1460.75

10.67 9.97E-06 4.55E-07 CS-137 0.97 661.65

85.12 1. 60E-06 5.77E-08 PB-212 0.55 77.11 17.50 238.63

44.60 2.68E-07 2.02E-08 BI-214 0 .35 609.31

46.30 1. OlE-07 2.47E-08 1120.29 15. 10 1238 .11 5.94 1377.67 4. 11 1407.98 2 . 48 1509.19 2. 1 9 1764.49 15. 80

= Energy llne found in the spectrum.

- = Manually added nudide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide ~*r'tmean Wt mean Comments Name Id Activity Activity Confidence (uCl/grams) Uncertainty

K-40 0.869 9.97E-06 4.SSE-07 j CS-137 0.978 1. 60E-06 5.77E-08 PB-212 0.559 2.68E-07 2.02E-OB BI-214 0. 3 50 1. OlE-07 2.4 7 E-08

9/15/2017 B:23:16AM Page4of7 Analysis Report for L 1-SUB-CDR-FSGS-012-SB UNIT L 1-SUB CDR 09/13/17

? ::: nuclide is part of an undetermined solution X ::: nuclide rejected by the interfererice analysis

@ :a: nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma

9/15/2017 8:23:16AM Page5 of7 Analysis Report for L 1-SUB-CDR-FSGS-012-58 UNIT L 1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/1512017 B:23:07AM Peak locate From Channel : 100 Peak Locate To Channel : 4096 PeakCPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 352.00 2.90430E-02 27.16 Tel. PB-214 F 3 583.39 3.09625E-02 12.46 -Tl--zd /

F 6 911. 94 2.07873E-02 14.68 Tel. AC-228/

PA-228 F 7 1173.73 1.47027E-02 28.78 Tel. CO-60J ~~~ 'tJ-t1J F 8 1333.55 2.85811E-02 11. 00 c;,0 .{;.0 ? eu,.,..:.~

M = First peak In a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPPU..ibrary\HOTL.AB.NLB Nuclide Energy Yield('1/4) Activity NuclideMDA Line MDA Name (uCUgrams) (uCVgrams) (uCVgrams)

(keV)

+ K-40 1460.75

10.67 9.97E-06 3.43E-07 3 . 43E-07

., ""Jn""'l rA

+ AR-41 .J. £ ::JJ.'U':I 99.16 6.91E-02 4.52E-01 4.52E-Ol

+ / C0-60 11 7 3.22 100.00 1 .61E-09 7.87E-08 8.34E-08 1332.49 100.00 1. 37E-07 7 .87E-08

+ KR-85 5 13.99 0.43 8.99E-06 l.19E-05 l.19E-05

+ Y-88 898.04 93.70 -5 .94E-09 4.14E-08 5.lSE-08 1836.06 99. 2 0 -l . 16E-0 8 4.14E-08

+ NB-94 702.63 100.00 -7.02E-09 4.25E-08 4.25E-08 871.10 100.00 - 3 . 5 2E-0 8 4.84E-08

+ I-131 284.30 6.06 3.0SE-07 6.12E-08 7 .SlE-0 7

9/15/2017 8:23:16AM Page6 of7 Analysis Report for L1..SUB-CDR-FSGS-012..SB UNIT L1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclideMDA LlneMDA Name (uCUgrams) (uCUgrams) (uCUgrams)

(keV)

I-131 364.48 81.20 7.69E-09 6.12E-08 6.12E-08 636.97 7.27 -1 .72E-07 7.24E-07

+ CS-134 604.70 97.60 -1 .70E-08 5.30E-08 5.30E-08 795.84 85.40 3.58E-09 5.57E-08

+ /cs-137 661.65

85.12 1. 60E-06 6.84E-08 6.84E-08

+ CE-144 80.12 1.36 1. 42£-07 3.22E-07 3.78E-06 133.51 11.09 1. 86E-07 3.22E-07

+ EU-152 121. 78 28.40 -9.95E-08 1.21E-07 1. 21E-07 244.69 7.49 -3.77E-07 5.82E-07 964.00 14.44 2.73E-07 4.llE-07 1408.00 20.74 1.36E-08 2.21E-07

+ EU-154 123.07 40.40 -7.36E-08 8.58E-08 B.58E-08 247.94 6.60 -9.60E-07 6.15E-07 723.30 19.70 5.95E-08 2.33E-07 873.20 11.50 2.32E-07 4.22E-07 1004.76 17.90 -1 .lBE-07 2.BlE-07 1274.51 35.50 5.59E-08 1.72E-07

+ EU-155 86.54 32.80 -1.09E-07 l .33E-07 1. 33E-07 105.31 21. 80 -6.36E-08 l.63E-07

+ BI-214 609.31

46.30 1. OlE-07 1 .0lE-07 1.0lE-07 1120. 29 15.10 3.84E-07 4.68E-07 1238 .11 5.94 -7.38E-07 1. 25£-06 1377.67 4 .11 2.66E-07 1.llE-06 1407.98 2.48 1.13£-07 1.85E-06 1509.19 2.19 -1. 87E-07 1.55E-06 1764.49 15.80 1.30E-07 2.97E-07

+ PB-214 77 .11 10.70 7.43E-07 1 .29E-07 5, 18E-07 295.21 19. 20 1.40E-07 2 .30E-07 351. 92 37.20 1.70E-07 1.29E-07

+ PA-228 89.95 22.00 7.12E-07 4.29E-07 7.23E-07 93.35 35.00 1.92E-07 4.29E-07 105.00 16.30 -2.66E-07 8.14E-07 129.22 2 .97 l.17E-06 4,45E-06 338.32 5.30 1.46E-06 3.lOE-06 463.00 13.80 -1.27E-07 1.44£-06 911. 23 16.70 1.14E-06 l.33E-06

+ AM-241 59.54 36.30 1. 46E-07 2.46E-07 2.46E-07

+ CM-243 103.76 23.00 -7.96£-08 1. 56E-07 1. 56E-07 228.18 10.60 -3.09£-07 3.37E-07 277.60 14.00 -2.48E-07 2.83E-07

+ = Nuclide identified during the nuclide identification

" = Energy line found in the spectrum MDA value not calculated

@ = Half~ife too short to be able to perfonn the decay correction

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

9/15/2017 8:23:16AM Page 7 of7 Analysis Report for L 1-SU B-CDR-FSGS-012-SB UNIT L 1-SUB CDR 09/13/17

9/15/2017 9:25:38AM Page I of7

. Ji'Apex-Gamma Analysis Report for L1-SUB--CDR-FSGS-013-SB UNIT L1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification ; L1-SUB-CDR-FSGS-013-SB Sample Description : UNIT L1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 8.979E+02 grams Facility : Dairyland_NPP Sample Taken On : 9/13/2017 2:10:00PM Acquisition Started : 9/15/2017 8:25:17AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 3600.0 seconds Real Time : 3609.4 seconds Dead Time : 0.26 %

Peak Locate Threshold

3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Callbratlon Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 3399 PEAK ANALYSIS REPORT Peak Analysls Perfonned on : 9/15/2017 9:25:29AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 9:25:38AM Page 2 of7 Analysis Report for L1-SUB-CDR-FSGS-013-SB UNIT L1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.54 148 - 160 153.62 1.70E+02 29.95 6,33E+02 3.99 F 2 238.79 471 - 485 478.06 2.89E+02 25.01 3.74E+02 2.47 F 3 338.50 669 - 682 677.43 7.62E+Ol 13.81 1.49E+02 1. 97 F 4 351.86 698 - 710 704.15 1.52E+02 16.68 1. 48E+02 2.00 F 5 583.62 1161 - 1173 1167.57 8.75E+Ol 12.82 6.84E+Ol 2.69 F 6 609.57 1211 - 1227 1219.47 1. 39E+02 14.54 7.02E+Ol 3.01 F 7 661. 98 1315 - 1331 1324.28 1.62E+02 15.14 8.25E+Ol 2.36 F 8 912.02 1816 - 1833 1824.29 7.60E+Ol 10.86 4.15E+Ol 3.06 F 9 1461.63 2912 - 2934 2923.37 5.47E+02 23.75 2.81E+OO 3 . 05 M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/15/2017 9:25:29AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 76.54 1.70E+02 29.95 1. 70E+02 3.00E+O l F 2 238.79 2 .89E+02 25.01 2.8 9E+02 2.SOE+O l F 3 33 8. 50 7 .62E +Ol 13.81 7 . 62E+O l l, 38E+Ol F 4 351.86 1 . 52E+02 16.68 8.36E+Ol 1. 8 6E+Ol 6.81E+Ol 2 . 5 0E+Ol F 5 583.62 8.75E+Ol 12.82 8.75E+Ol 1.28E+Ol F 6 609.57 l.39E+02 14.54 4.12E+Ol 1.21E+Ol 9.78E+Ol 1. 89E+Ol F 7 661.98 1.62E+02 15.14 6.61E+Ol 1. 2 7E+ Ol 9.54E+ Ol 1. 98E+Ol F 8 912.02 7. 60E+Ol 1 0.8 6 7. 6 0E+O l 1. 0 9E+O l F 9 14 61.63 5.47E+02 2 3.75 5.63E+Ol 8.S7E+OO 4.91E+02 2. 52E+Ol M = First peak in a multiplet region m = other peak fn a multiplet region F = Fitted singlet Errors quoted at 1.000sigma

9/15/2017 9:25:36AM Page 3 of7 Analysis Report for L 1-SUB-CDR-FSGS-013-SB UNIT L 1-SUB CDR 09/13/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dalryland_NPp\Library\HOTI.AB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{°/o) Activity Activity Name Confidence (keV) (uCVgrams) Uncertainty K-40 0.88 1460.75

10.67 5.96E-06 3.48E-07 CS-137 0.98 661.65

85.12 7.18E-08 1.50E-08 PB-212 0.98 77 .11

17.50 2.71E-07 4.84E-08 238.63

44.60 l.66E-07 1. 50E-08 BI-214 0 .34 60 9. 31

46.30 1.25E-07 2.45E-OB 1120.29 15 .10 1238.11 5.94 1377.67 4.11 1407.98 2.48 1509.19 2.19 1764.49 15.80 PB-214 0 .51 77 .11

10.70 4.43E-07 7.91E-08 295.21 19.20 351. 92

37 .20 6.56E-08 2.41E-08

= Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCVgrams)

K-40 0.884 5 .96E-06 3.48E-07

/ CS-137 0.983 7.18E-08 1.SOE-08

9/15/2017 9:25:38AM Page4 of7 Analysis Report for L 1-SUB-CDR-FSGS-013-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Nuclide wtmean wtmean Comments Name Id Activity Activity Confidence Uncertainty

{uCUgrams)

PB-212 0.982 1. 72E-07 1.44E-08 BI-214 0.344 1.25E-07 2.4SE-08 PB-214 0.518 7.37E-08 2.31 E-08

? = 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 1.000slgma

9/15/2017 9:25:38AM Pagc5 of7 Analysis Report for L1-SUB-COR-FSGS...013-SB UNIT L1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/15/2017 9:25:29AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (kaV) Peak Size (CPS) Uncertainty Type Nuclide 3 338,50 2. 11770E-02 18. 11 Tol. AC-228./

PA-228 F 5 583,62 2. 43182E-02 14.64 -o'lA'i ./

F 8 912.02 2 .11087E-02 14.29 Tol. AC-228 PA-228 M = First peak in a multiplet region m = Other peek in a multiplet region F = Fitted singlet Errors quoted at 1.0OOsigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (uCVgrams) (uCilgrams) (uCUgrams)

(keV)

+ K-40 1460.75

10.67 5.96E-06 5.06E-07 5.06E-07

+ AR-41 1293.64 99.16 -3.82E-01 5.32E-01 5.32E-01

+j C0-60 1173.22 100.00 2.BBE-08 5.46E-08 6.48E-08 1332.49 100.00 2.66E-08 5.46E-08

+ KR- 85 513.99 0.43 1.0lE-05 8.97E-06 8.97E-06

+ Y-88 898.04 93.70 2.62E-08 3.21E-08 4.57E-08 1836.06 99.20 -6.56E-10 3.21E-08

+ NB-94 702.63 100.00 1. 07E-08 3.76E-08 3.76E-08 871.10 100.00 -2. 99E-08 4.lBE-08

+ I-131 284.30 6.06 -4.lBE-07 4.41E-08 5.SSE-07 364.48 81.20 6.llE-09 4.41E-08

9/15/2017 9:25:38AM Page 6 of7 Analysis Report for L 1-SUB-CDR-FSGS-013-5B UNIT L 1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity Nuc/ideMDA LlneMDA Name (uCi/grams) (uCVgrams) (uCi/grams)

(keV)

I-131 636.97 7.27 2.41E-07 4.41E-08 5.90E-07

+ CS-134 604.70 97.60 2.36E-10 4.59E-08 4.86E-08 795.84 85.40 -1. 05E-08 4.59E-08

+ j CS-137 CE-144 661. 65 80.12

85.12 7.18E-08 5.66E-08 5 .66E-08

+ 1.36 -6.14E-07 2.57E-07 3.20E-0 6 133.51 11. 09 -6.28E-09 2.57E-07

+ j EU-152 121. 78 28.40 -1.23E-07 1. OOE-07 1. OOE-07 244.69 7.49 -4.69E-08 4.64E-07 964.00 14.44 3.36E-07 3.52E-07 1408.00 20.74 1.32E-07 1.85E-07

-+ / EU-154 123.07 40.40 -4.44E-08 7.0SE-08 7.0SE-08 247.94 6.60 -5.13E-07 4.65E-07 723.30 19.70 1. 58E-07 2.09E-07 873.20 11.50 -1.0BE-07 3.58E-07 1004.76 17.90 1. llE-07 2.63E-07 1274.51 35.50 -1.41E-07 1.SlE-07

+ EU-155 86.54 32.80 -1.91E-09 1. llE-07 1. 11E-07 105.31 21. 80 -5.65E-08 1. 34E-07

+ BI-214 609.31

46.30 1.25E-07 8.BBE-08 8.88E-08 1120.29 15.10 1.79E-07 3.71E-07 1238.11 5.94 1.17E-06 1.17E-06 1377.67 4.11 -1.07E-07 9.63E-07 1407.98 2.48 1.llE-06 1 .SSE-06 1509.19 2.19 3.15E-07 1.SSE-06 1764.49 15.80 3.84E-07 3.0BE-07

+ PB-214 77.11

10.70 4.43E-0 7 9.32E-08 3.57E-07 295.21 19.20 1. 36E-07 1.73E-07 351.92

37.20 6.56E-08 9.32E-08

+ PA-228 89.95 22.00 2.43E-07 3.60E-07 6.lOE-07 93.35 35.00 -9.87E-08 3 . 60E-07 105.00 16.30 -4. 2 1E-07 6.87E-07 129.22 2.97 3.39E-06 3.70E-06 338.32 5.30 3.SSE-07 2.37 E-06 463.00 13.80 -4.0lE-07 9.19E-07

+

/ AM-241 CM-243 91 1. 23 59.54 103.76 16.70 36.30 23.00

1. 17E-06 l.43E-07

-1. 50E-08 2.02E-07 1.28E-07

1. 2 3E-06 2.0 2E-07 1.28E-07 228.18 10.60 5.74E-08 2.7 8E-07 277. 60 14.00 4.50E-08 2.2 0E-07

+ = Nuclide identified during the nuclide identification

.. = Energy line found In the spectrum

> = MDA value not calculated

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

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

9/15/2017 9:25:38AM Page 7 of7 Analysis Report for L1-SUB-CDR-FSGS-013-SB UNIT L1-SUB CDR 09/13/17

9/15/2011 10:28:13AM Page 1 of6

___;Apex-Gamma Analysis Report for L 1-SUB-COR-FSGS-014-SB UNIT L 1-SUB COR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CD R-FSG~14 -SB/

Sample Description : UNIT L 1-SUB CDR 09/13/17 Sample Type : 500 mt Marinelli Unit Sample Point Sample Size : B.284E+02 grams /

Facility : Dairyland_NPP

/

Sample Taken On

9/13/2017 2:18:00PM Acquisition Started : 9/15/2017 9:27:51AM

500ml Marinelli

/

Procedure Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Livellme : 3600.0 seconds/

Real Time : 3610.4 seconds

_,/

Dead Time : 0.29 %

Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100-4096 Peak Area Range (in channels) : 100 -4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number :3400 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/15/2017 10:28:04AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 10:28:13AM Page2 of6 Analysis Report for L 1-SUB-CDR-FSGS-014-SB UNIT L1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.76 470 - 486 478.00 3. 11E+02 27.98 6.67E+0 2 2.19 F 2 295.05 587 - 596 590.55 8.61E+O l 17.43 2.98E+0 2 1. 43 F 3 338.78 673 - 681 678.00 6.13E+O l 15.26 2.00E+0 2 1.42 F 4 351.85 698 - 711 704.14 1.66E+0 2 20.87 3.07E+0 2 2.31 F 5 583.54 1162 - 1173 1167.42 8.78E+O l 13.60 1.07E+0 2 1. 99 F 6 609.41 1211 - 1226 1219.16 9.92E+O l 14.18 l.32E+0 2 2.20 F 7 662.03 1315 - 1333 1324.39 2.86E+0 3 54.78 1.40E+0 2 2.38 F 8 911. 80 1816 - 1831 1823.83 7.58E+O l 10.69 5 .lBE+Ol 2.18 F 9 1173.87 2341- 2357 2347.91 l.03E+0 2 12.73 6.50E+O l 2. 64 F 10 1333.37 2660 - 2674 2666.87 9.75E+O l 10.96 2.27E+O l 2.35 F 11 1461. 72 2916 - 2933 2923.55 7.56E+0 2 28.40 3.15E+0 1 2.80 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/15/2017 10:28:04AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Oata\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Backgrou nd Uncert. Area Uncert.

F 1 238.76 3 .11E+02 27.98 3 .11E+02 2.80E+O l F 2 295.05 8.61E+O l 17.43 8.61E+O l 1.74E+O l F 3 338.78 6.13E+O l 15.26 6.13E+O l l . 53E+Ol F 4 351.85 1. 66E+02 20.87 8.36E+O l l . 86E+Ol 8.22E+O l 2.80E+O l F 5 583.54 8.78E+O l 13.60 8.78E+O l 1.36E+O l F 6 609.41 9.92E+O l 14.18 4.12E+O l l.21E+O l S.80E+O l 1.86E+O l F 7 662.03 2.86E+0 3 54.78 6.61E+O l 1. 27E+Ol 2.79E+0 3 5.62E+O l F 8 911. 80 7. 58E+Ol 10.69 7.58E+O l 1. 07E+Ol F 9 1173.87 1. 03E+02 12.73 4.SSE+O l 8.62E+O O 5. 80E+Ol 1. 54E+Ol F 10 1333.37 9.75E+O l 10.96 9 . 75E+Ol 1.lOE+O l F 11 1461. 72 7.56E+0 2 28.40 7.56E+0 2 2.84E+O l M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma

9/15/2017 10:28:13AM Page 4 of6 Analysis Report for L 1-SUB-CDR-FSGS-014-SB UNIT L1-SUB CDR 09/13/17 Nuclide Nuclide Wtmean Wtmean Comments Name Id Activity Activity Confidence (uCilgrams) Uncertainty

)<-40 0 . 861 9.96E-06 4.65E-07

/ f,0-60 0 .908 1.03E-07 l.13E-08

/ CS-137 0 .977 2.28E-06 7.68E-08 PB-212 0 .558 1.94E-07 1 .81E-08 BI-214 0 .349 8.06E-08 2.60E-08 PB-214 0.720 1. 16E-07 2 .lOE-08 AC-228 0.303 2.36E-07 2.94E-08

? = 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 et 1.000sigma

9/15/2017 10:28:13AM Page 3 of6 Analysis Report for L1-SUB-CDR -FSGS-014 -S8 UNIT L 1-SUB CDR 09/13/17 NUCL IDE IDENTIFICATION REPO RT Nuclide Library Used : C:\Canberra\Apex\Root\Dairytand_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (lceV) (uCVgrams) Uncertainty K-40 0.86 1460.75 10. 67 C0-60

9.96E-0 6 4.65E-0 7 0.90 1173.22

100.00 6.73E-0 8 1.79E-0 8 1332.49

100.00 1 .27E-07 1.46E-0 8 CS-137 0.97 661.65

85.12 2.28E-0 6 7.68E-0 8 PB-212 0.55 77.11 17.50 238.63

44.60 1.94E-0 7 l.BlE-0 8 BI-214 0.34 609.31 46.30

8.06E-0 8 2.60E-0 8 1120. 29 15.10 1238.11 5.94 1377.67 4.11 1407.98 2.48 1509.19 2.19 1764.49 15.80 PB-2 14 0.72 77.11 10.70 295.21

19.20 1.49E-0 7 3.03E-0 8 351.92

37.20 8.57E-0 8 2.92E-0 8 AC-228 0 . 30 209.28 4.40 338.32

11.40 2.0lE-0 7 5.04E-0 8 794.70 4.60 911. 60

27.70 2.54E-0 7 3. 62E-08 964.60 5.20 969.11 16.60

=Energy line found in the spectrum.

- =Manually added nuclide.

? = Manually edited nuclide.

@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence Index threshold = 0.30 Errors quoted at 1.000sigma INTER FERE NCE CORR ECTE D REPO RT

9/1512017 10:28:13AM Page S of6 Analysis Report for L1-SUB-CDR-FSGS-014-SB UNIT L 1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/15/2017 10:28:04AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS ("/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 5 583.54 2.43916E-02 15.49 M ::: First peak in a multlplet region m == Other peak in a multiplet region F == Fitted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Llbrary\HOTLAB.NLB Nuclide Energy Ytttld(3/4) Activity NuclideMDA LineMIJA Name (uCVgrams) (uCVgrams) (uCVgrams)

(keV)

K-40 1460.75 10.67 9 . 96E-06 4.78E-07 4.78E-07

+ *

+ /2-41 CO-60 1293.64 1173.22 99.16 100. 00 1.80E-01

6. 73E-08 1.02E+00 3.83E-08 1.02E+00 7.20E-08

+

1332.49

100.00 1.27E-07 3.83E-08

+ KR-85 513.99 0.43 1 .lSE-05 1. 27E-05 1. 27E-05

+ Y-88 898.04 93.70 -4.0lE-09 2.75E-08 5.BBE-08 1836.06 99.20 -2.92E-08 2.75E-08

+ NB-94 702.63 100.00 -2 .58E-08 4.21E-08 4.21E- 08 871.10 100.00 -3.88E-08 4. 91E-08

+ I - 131 284.30 6.06 -3.91E-07 6.98E-08 8 . 40E-07 364.48 81.20 3.36E-09 6.98E-08 636.97 7.27 -2.23E-07 7.77E-07

+ cs-134 604. 70 97. 60 8.74E-09 5.72E-08 5.72E-08 795.84 85.40 9.54E-10 6.0SE-08

/cs-137 661. 65 85.12 2 . 28E-06 7 .31E-08 7.31E-08

+ *

+ CE-144 80.12 1.36 3.13E-06 3.41E-07 4.06E-06 133.51 11. 09 7.06E-08 3.41E-07

9/15/2017 10:28:13AM Page 6 of6 Analysis Report for L 1-SUB-CDR-FSGS-014-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclldeMDA L/neMDA Name (uCi/grams) (uCVgrams) (uCVgrams)

(keV)

+ EU-152 121.78 28.40 -3 .73E-08 1. 33E-07 l.33E-07 244.69 7.49 -1. l 7E-07 6.26E-07 964.00 14.44 5.40E-07 4.82E-07 1408.00 20.74 5.35E-08 2.03E-07

+ EU-154 123.07 40.40 5.64E-08 9 . 41E-08 9.41E-08 247.94 6.60 -2.76E-07 6. 72E-07 723.30 19. 70 3.52E-08 2.51E-07 873.20 11. 50 7.42E-08 4.36E-07 1004.76 17.90 -8.54E-08 3.28E-07 1274.51 35.50 -1.08E-07 l.70E-07

+ EU-155 86 . 54 32 . 80 -1. 02E-07 1. 41E-07 1. 41E-07 105.31 21. 80 -6.00E-08 l.74E-07

+ BI-214 609.31

46.30 8.0GE-08 l.14E-07 l.14E-07 1120.29 1 5 .10 2.73E-08 4.57E-07 1238.11 5 .94 3.61E- 07 1. 36E-06 1377.67 4 .11 -l.66E-07 1. lSE-06 1407.98 2.48 4.48E-07 1. 70E-06 1509.19 2.19 6.90E-0 7 1. 89E-06 1764.49 15.80 l . 7 0E-0 7 3.23E-07

+ PB-214 77 .11 10.70 9.62E-07 l.26E-07 S.SOE-07 295.21

19.20 1.49E-07 1.53E-07 351. 92

37 . 20 8.57E-08 l.26E-07

+ PA-228 89.95 22.00 1.17E-06 4.78E-07 8.15E-07 93.35 35.00 -2.61E-OB 4.78E-07 105.00 16.30 9.42E-08 9.22E-07 129.22 2.97 1.74E-07 5.03E-06 338.32 5 .30 1.32E-07 3.57E-06 463.00 13.80 1. 86E-06 1.73E- 06 911. 23 16 . 70 9.56E-07 1.51E-06

+ ~-241 59.54 36.30 l.lBE-07 2.63E-07 2.63E-07

+ CM-243 103.76 23.00 6.0BE-08 1. 66E-07 1. 66E-07 228.18 10.60 -2.69E-0 8 3. 7 0E-07 277.60 14.00 -2.78E-0 7 3.17E-07

+

.. == Energy Nudide identified during the nuclide identification line found in the spectrum

> = MDA value not calculated

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

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

9/15/20H 11:29:40AM Page 1 of6

--3Apex-Gamma Analysis Report for L 1-SUB-COR..QSGS-014-SB UNIT L 1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYS/S Sample Identification : L1-SUB-CDR-OSGS-014-SB . /

Sample Description : UNIT L1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 8.946E+02 grams

/

Facllity : Dairyfand_NPP Sample Taken On : 9113/2017 2:30:00PM /

Acquisition Started : 9/15/2017 10:29:18AM Procedure

500ml Marinelli Opera1or : Administrator Detector Name : HOTLAB /

Geometry : 500ml Matinelti Live Time : 3600.0 seconds Real Time : 3610.1 se7s Dead Time : 0.28%

Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance ; 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 3401 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/16/2017 11:29:31AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 11:29:40AM Page 2 of6 Analysis Report for L 1-SUB-CDR-OSGS-014-SB UNIT L 1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak NetPeak Net Area Continuu m FWHM No. (keV) start end Centroid Area Uncertain ty Counts (keV)

F 1 209.15 415 - 426 418.79 6.42E+O l 17.89 3.40E+0 2 1. 82 F 2 238.68 472 - 485 477.83 3.63E+0 2 2 6. 51 4.34E+0 2 1.98 F 3 295.03 582 - 596 590.51 9.36E+O l 17.09 2.74E+0 2 1. 97 F 4 352.22 697 - 710 704.87 1. 75E+02 17.64 1. 86E+02 1. 92 F 5 583.62 1158 - 1174 1167.57 l.25E+0 2 14.25 l.13E+0 2 2.09 F 6 609.57 1210 - 1226 1219.48 l.28E+0 2 14 .35 1.04E+0 2 2.17 F 7 662.07 1318 - 1333 1324.45 4.47E+0 2 22.78 7 . 93E+Ol 2.43 F 8 911. 96 1818 - 1830 1824.15 8.23E+O l 11. 64 4.68E+O l 2.59 F 9 969.83 1935 - 1945 1939.89 3.28E+O l 8.82 5 .30E+Ol 1. 71 F 10 1121. 23 2236 - 2248 2242.65 3.44E+O l 8.57 4.80E+O l 1. 77 F 11 1461.73 2913 - 2933 2923.58 8.39E+0 2 29. 32 1.0SE+O l 2.75 IVI = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/15/2017 11:29:31AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Oata\0000001364.CNF Peale Energy Original Orig. Area Ambient Backgr. Subtracte d Subtracte d No. (keV) Area Uncertain ty Backgrou nd Uncert. Area Uncert.

F 1 209.15 6.42E+O l 17.89 6.42E+O l l.79E+0 1 F 2 238.68 3.63E+0 2 26.51 3.63E+0 2 2.65E+O l F 3 295.03 9.36E+O l 17.09 9.36E+O l 1.71E+O l F 4 352.22 1.75E+0 2 17.64 8.36E+O l 1. 86E+Ol 9.lOE+O l 2.56E+O l F 5 583.62 1.25E+0 2 14.25 1. 25E+02 1 . 43E+Ol F 6 609.57 l.28E+0 2 14.35 4.12E+0 1 1. 21E+Ol 8.72E+O l 1. 88E+Ol F 7 662.07 4.47E+0 2 22.78 6.61E+O l 1. 27E+01 3.81E+0 2 2.61E+O l F 8 911. 96 8.23E+O l 11. 64 8.23E+O l 1.16E+O l F 9 969.83 3.28E+O l 8.82 3.28E+O l 8.82E+O O F 10 1121. 23 3.44E+O l 8.57 3.44E+O l 8.57E+O O F 11 1461. 73 8.39E+0 2 29. 32 8.39E+0 2 2.93E+O l IVI = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma

9/15/2017 11:29:40AM Page4 of6 Analysis Report for L1-SUB-CDR-QSGS-014--SB UNIT L1-SUB CDR 09/13/17 Nuclide Nuclide Wtmean Wtmean Comments Name Id Activity Activity Confidence (uCi/grams) Uncertainty

/K-40 0.8ti6 l.02E-05 4.56E-07

/ CS-137 0.973 2.88E-07 2.12E-08 PB-212 0.560 2.09E-07 l.62E-08 BI-214 0.556 1.30E-07 2 .25E-08 PB-214 0 .712 1.16E-07 1. 85E-08 AC-22B 0 .416 2.37E-07 2 .79E-08

? = 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 1.000sigma

9/15/2017 11 :29:40AM Page 3 of6 Analysis Report for L 1-SUB-CDR-QSGS-014-SB UNIT L1-SUB COR 09/13/17 NUCL IDE IDENTIFICATION REPO RT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (uCUgrams) Uncertainty K-40 0.85 1460.75 CS-137

10.67 1. 02E-05 4.56E-0 7 0.97 661. 65

85.12 2.88E-0 7 2.12E-0 8 PB-212 0.56 77.11 17.50 238.63

44.60 2.09E-0 7 1. 62E-08 BI-214 0.55 609.31 46. 30

1. 12E-07 2.44E-0 8 1120. 29

15.10 2.35E-0 7 5.89E-0 8 1238 .11 5.94 1377.67 4.11 1407.98 2.48 1509.19 2.19 1764.49 15.80 PB-214 0.71 77.11 10.70 295.21

19. 20 1.SOE-0 7 2.76E-0 8 351. 92

37.20 8.79E-0 8 2.49E-0 8 AC-228 0.41 209.28

4.40 3.40E-0 7 9.52E-0 8 338.32 11.40 794.70 4.60 911. 60

27.70 2.SSE-0 7 3.65E-0 8 964.60 5.20 969.11

16.60 1.79E-0 7 4.84E-0 8

" =Energy line found in the spectrum.

- =ManuaUy added nuclide.

? =Manually edited nuclide.

@ ::: Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV

=

Nuclide confidence index threshold 0.30 Errors quoted at 1.000sigma INTER FERE NCE CORR ECTE D REPO RT

9/1512011 11:29:40AM PageS of6 Analysis Report for L 1-SUB-COR-O SGS-014-SB UNIT L 1-.SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/15/2017 11:29:31AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS ('1/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 5 583.62 3.47497E -02 11.39 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLI DE MDA REPOR T Nuclide Library Used : C:\Canbena\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Enerr,y Yield(%) Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams) (uCVgrams)

(keV) 1460.75 10.67 l.02E-05 2.BOE-07 2.SOE-07

+ K-40 *

+ AR-41 1293.64 99.16 9.0SE-02 1.37E+OO 1.37E+OO

+ C0-60 1173.22 100.00 -1.7 0E-08 5.BOE-08 7.06E-0 8 1332.49 100.00 7 .49E-08 5.BOE-08

+ KR-85 513.99 0.43 l.12E-05 l.03E-05 l .03E-05

+ Y-88 898. 04 93.70 2.02E-08 3.32E-08 5.52E-08 1836. 06 99.20 -l. 71E-08 3.32E-08

+ NB-94 702.63 100.00 -2. 12E-08 4.00E-08 4 .00E-08 871.10 100.00 -1.34E-08 4.44E-08

+ I-131 284.30 6.06 9.0lE-08 4.78E-08 6 .2 4E-07 364.48 81.20 1. 44E-08 4 . 78E-08 636.97 7. 27 2.35E-07 6 .78E-07

+ CS-134 604.70 97.60 -6,17E-09 5.20E-08 5.25E-08 795.84 85.40 1. 48E-08 S.20E-08 85.12 2.SBE-07 5.59E-08 5 .5 9E-08

+ CS-137 661.65 *

+ CE-144 80.12 1. 36 3.69E-06 2.BSE-07 3.47E-06 133 .51 11. 09 2 .93E-08 2.85E-07

9/15/2017 11:29:40AM Page 6 of6 Analysis Report for L1-SUB-CDR-QSGS-014-SB UNIT L1-SUB CDR 09/13/17 Nuclide Energy Yield{%) Activity NuclldeM DA Line MDA Name (uCVgrams) (uCVgrams) (uCilgrams)

(keV)

+ EU-152 121.78 28.40 -1. 50E-07 1. 08E-07 l.08E- 07 244.69 7.49 -2.35E -07 5.28E- 07 964.00 14.44 -2.29E -07 4.12E- 07 1408.0 0 20.74 1.18E- 07 l.93E- 07

+ EU-154 123.07 40.40 -l. llE-07 7.54E- 08 7.54E- 08 247.94 6.60 -5.39E -07 5.32E- 07 723.30 19.70 -1. 37E-07 2.13E- 07 873.20 11. 50 -9.33E -08 3.77E- 07 1004.7 6 17.90 8.06E- 08 3.0lE- 07 1274. 5 1 35.50 -9. llE-08 1.70E- 07

+ EU-155 86.54 32.80 -4.64E -08 1. 20E-07 1. 20E-07 105.31 21. 80 l.30E- 07 1. 48E-07

+ BI-214 609.31

46.30 1.12E- 07 9 . 96E-08 9. 96E-08 1120.2 9

15.10 2.35E- 07 2.74E- 07 1238.1 1 5. 94 8.llE-0 7 1.26E- 06 1377.6 7 4. 11 -7 .59E-07 9.99E- 07 1407.9 8 2.48 9.90E- 07 l.61E- 06 1509.1 9 2 . 19 9.15E- 08 1.SOE- 06 1764.4 9 15.80 3 .3 7E-08 2.46E- 07

+ PB-214 77 .11 10.70 4.71E- 07 1.00E- 07 4.66E- 07 295.21

19.20 l.SOE- 07 1.52E- 07 351.92

37.20 8.79E- 08 1.00E- 07

+ PA-228 89.95 22.00 5 .69E-0 8 4.21E- 07 7.03E- 07 93.35 35 . 00 3.27E- 07 4.21E- 07 105.00 16.30 3.02E- 07 8.00E- 07 129.22 2.97 4.40E- 06 4 . 31E-06 338.32 5.30 4.30E- 07 2.70E- 06 463.00 13.80 8.SlE- 08 1. 15E-06 911.23 16.70 2.67E- 06 l.54E- 06

+ AM-241 59.54 36.30 - l .40E-08 2.17E- 07 2.17E- 07

+ CM-243 103.76 23.00 -5 .86E-0 8 1.41E- 07 1. 41E-07 228.18 10.60 4.56E- 08 2.92E- 07 277.60 14.00 l.35E-0 7 2.37E- 07

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

9/15/201'1' 1:44:16PM Page 1 of8

--!tApex-G8mma Analysis Report for CDR # 4 SOIL GAMMA SPECTRUM ANALYSIS Sample Identification : CDR#4 /

Sample Desaiptlon : SOIL Sample Type : Silt Unit Sample Point Sample Size : 2.916E+03 grams ./

Faclllty : Diaryland_NPP Sample Taken On Acquisition Started

9/15/2017 11:00:00AM

9/15/2017 12:43:35PM

/

Procedure : Slit Operator : Administrator Detector Name ; DET01-ENV Geometry : 1.5L Marinelli /

Live Time : 3600.0 seconds Real Time : 3626.3 seconds Dead Time : 0.72 %

Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 61312014 Efficiency Calibration Used Done On : 613/2014 Efficiency Calibration Description : 1.5 Marlnelll Sample Number : 3406 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/15/2017 1:44:07PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 .;44:16PM Page 2 of8 Analysis Report for COR#4 SOIL Peak Energy ROI ROI Peale NetPeak NetArea Continuum FWHM (keV) Centroid Area Uncertainty Counts (keV)

No. start end 1 75.84 146 - 194 152.52 6.13E+02 47.50 1. 91E+03 3.08 M

2 83.67 146 - 194 168.20 l.57E+02 40.98 2.38E+03 3.10 m

87.48 146 - 194 175.82 2.20E+02 41.82 2.37E+03 3.11 m 3 m 4 92.32 146 - 194 1 85.49 4.33E+02 44.29 2.25E+03 3.12 5 185.65 367 - 376 372.22 2.39E+02 35.12 1.31E+03 1. 40 F

209 . 29 413 - 428 419.51 l.81E+02 38.84 1.85E+03 2.20 F 6 468 - 486 477.61 1.17E+03 43.90 1.77E+03 1. 52 F 7 238.33 294.96 586 - 605 590. 92 3.96E+02 30.35 1.54E+03 1.27 F 8 9 351.56 696 - 710 704.15 8.61E+02 36.92 9.09E+02 1.49 F

510.41 1013 - 1029 1021. 97 2.37E+02 25.97 6.37E+02 2.15 F 10 11 582.78 1135 - 1172 1166.77 3.91E+02 25.44 9.19E+02 1. 74 F

F 12 608.94 1207 - 1226 1219.10 6.07E+02 30.06 5 .52E+02 1. 84 13 661.17 1313 - 1334 1323.60 1. 31E+04 115. 77 4.67E+02 1. 89 F

14 726.97 1450 - 1460 1455.25 8.83E+Ol 13.80 1.09E+02 1. 91 F

768.00 1532 - 1542 1537.35 6.13E+Ol 12.63 1.51E+02 1. 33 F 15 785.61 1564 - 1595 1572.57 3.84E+Ol 11.20 1.34E+02 1. 81 M 16 17 794.64 1564 - 1595 1590.65 4.53E+Ol 11. 79 1.17E+02 1.82 m

859.77 1711 - 1726 1720.96 5.87E+Ol 11.71 1. 40E+02 1. 61 F 18 19 910.62 1814 - 1833 1822.70 3.34E+02 21.98 2.16E+02 2.43 F

F 20 933.14 1860 - 1875 1867.76 4.46E+Ol 13.47 1.83E+02 2.23 F 21 968.26 1926 - 1948 1938.03 l.93E+02 19.34 2.72E+02 2.95 1119.78 2232 - 2247 2241. 18 1. 84E+02 18.32 1.80E+02 2.49 F 22 F 23 1172.67 2334 - 2357 2347.01 5.19E+02 25.74 2.37E+02 2.42 1237.19 2471 - 2488 2476.10 4.79E+Ol 11.15 2.16E+02 1. 58 F 24 F 25 1331. 84 2653 - 2675 2665.49 4.62E+02 23.72 1. 44E+02 2.69 1460.12 2908 - 2933 2922.16 4.11E+03 64.78 8.77E+Ol 2.83 F 26 27 1728.96 3454 - 3466 3460.08 2.74E+Ol 7.37 2.25E+Ol 2.79 F

1763.88 3520 - 3538 3529.95 1. 40E+02 12.93 2.63E+Ol 3.16 F 28 M == First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/15/2017 1:44:06PM Env. Background File : C:\Canberra\Apex\Root\Diaryland_NPP\Data\0000003388.CNF Original Orig. Area Ambient Backgr. Subtracted Subtracted Peale Energy (keV) Area Uncertaint y Background Uncert. Area Uncert.

No.

1 75.84 6.13E+02 47.50 6.13E+02 4.75E+Ol M

9/15/2017 1:44:16PM Page 3 of8 Analysis Report for CDR#4 SOIL Peale Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (ke\1 Area Uncertainty Background Uncert. Area Uncert.

rn 2 83.67 1.57E+ 02 40.98 1. 57E+02 4.lOE+ Ol m 3 87.48 2.20E+ 02 41. 82 2.20E+ 02 4.18E+ Ol m 4 92.32 4.33E+ 02 44.29 5.07E+ Ol 8.63E+O O 3.82E+ 02 4.SlE+ Ol F 5 185.65 2.39E+ 02 35.12 3.67E+ Ol 8.25E+O O 2,03E+ 02 3.61E+ Ol F 6 209.29 l.01E+ 02 38.84 1. 81E+02 3.88E+ Ol F 7 238.33 l.17E+ 03 43.90 3 . 14E+Ol 6.41E+O O 1.14E+ 03 4 .44E+0 1 F 8 294.96 3.96E+ 02 30.35 1.00E+ Ol 5.91E+O O 3.86E+ 02 3.09E+ Ol F 9 351. 56 8.61E+ 02 36.92 2.24E+ Ol 5.47E+O O 8.39E+ 02 3.73E+ Ol F 10 510.41 2,37E+ 02 25.97 1.52E+ 02 8.lOE+O O 8.SSE+ Ol 2.72E+ Ol F 11 582.78 3. 91E+02 25.44 2.14E+ Ol 4.78E+O O 3.69E+ 02 2.59E+ Ol F 12 608.94 6.07E+ 02 30.06 2.18E+ Ol 4.83E+O O 5.86E+ 02 3.04E+ Ol F 13 661.17 1. 31E+04 115. 77 1. 38E+Ol 4.37E+O O 1. 31E+04 1.16E+ 02 F 14 "726.97 8.83E+ Ol 13.80 8.83E+ Ol 1. 38E+Ol F 15 768.00 6.13E+ Ol 12.63 6.13E+ Ol 1.26E+ Ol M 16 785.61 3.84E+ Ol 11.20 3.84E+ Ol 1.12E+ Ol m 17 794.64 4.53E+ Ol 11. 79 4.53E+ Ol l.18E+ Ol F 18 859.77 5.87E+ Ol 11. 71 5.87E+ Ol 1. l 7E+Ol F 19 910.62 3.34E+ 02 21.98 1.35E+ Ol 3.68E+O O 3.20E+ 02 2.23E+ Ol F 20 933.14 4.46E+ Ol 13.47 4.46E+ Ol 1. 35E+Ol F 21 968.26 1.93E+ 02 19.34 1.93E+ 02 1. 93E+Ol F 22 1119.7 8 1.84E+ 02 18.32 1. 09E+Ol 3.21E+O O l.73E+ 02 1. 86E+01 F 23 1172. 67 5.19E+ 02 25.74 5.19E+ 02 2.57E+ Ol F 24 1237.1 9 4.79E+ Ol 11.15 4.79E+ Ol 1.llE+ Ol F 25 1331.8 4 4.62E+ 02 23.72 4.62E+ 02 2.37E+ Ol F 26 1460.1 2 4.11E+ 03 64.78 5.78E+ Ol 4.59E+O O 4.06E+ 03 6.49E+ Ol F 27 1728.9 6 2.74E+ Ol 7.37 2.74E+ Ol 7.37E+O O F 28 1763.8 8 1. 40E+02 12.93 1. 38E+Ol 2.34E+O O 1.27E+ 02 1. 31E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet EITOrs quoted at 1.000slgma NUC LIDE IDENTIFICATION REP ORT Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Library\ENVLIB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Activity Activity Name Confiderrce (keV) (pCVgrams} Uncertainty K-40 0.92 1460.8 1

10. 67 6.62E+O O 2.12E- Ol C0-60 0.94 1173.2 2

100 . 00 7.78E- 02 4.28E- 03

9/15/2017 '\:44:16PM Page4 of8 Analysis Report for COR#4 SOIL Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (ireVJ (pCVgrams) Uncertainty 100.00 7 . 58E-02 4.35E-0 3 CO-60 0.94 1332.49

4.33E-0 2 CS-137 0.96 661.65

85.12 1.52E+0 0

11. 80 7.86E-0 2 1.24E-0 2 BI-212 0.78 727.17

6.24E-0 2 785.42

2.00 2.13E-0 l 1620. 56 2. 75 PB-212 0.57 77 .11 17.50 87.20 6.30 2.96E-0 1 5.70E-0 2 89.80 1. 75 44.60 1. 48E-01 6.91E-0 3 238.63

300.09 3.4 1 609.31 46.30 1.18E-0 l 6.9SE-0 3 BI-214 0 . 74

768.36 5.04 1. 33E-01 2.75E-0 2 806 . 17 1.23 934.06 3.21 1.75E-0 l 5.31E-0 2

1.82E-0 2 1120.29

15.10 1.66E-0 1 1155.19 1.69 1238.11 5.94 1.26E-0 1 2.94E-0 2 1280.96 1.47 1377.67 4 .11 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661. 28 1.15 1729.60 3.05 1. 71E-0l 4.63E-0 2

1. 54E-01 1.67E-0 2 1764.49

15.80 1847.44 2.12 PB-214 0 .56 74. 81 6.33 77 .11 10.70 3.70 5.04E-0 1 9.71E-0 2 87.20

89.80 1.03 241. 98 7.49 295.21 19.20 1. 26E-01 1. 06E-02

7.80E-0 3 351.92

37.20 1 .53E-01 785.91 1.10 3.88E-0 1 l. 13E-0l

6 .03E-02 RA-226 0.95 186.21

3.28 3.35E-0 1

=Energy line found in the spectrum.

. =Manually added nuclide.

? = Manually edited nudide.

=

@ Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPO RT

9/15/2017 1:44:16PM Page 5 of8 Analysis Report for CDR # 4 SOIL Nuclide Nuclide Wtmean Wt mean Comments Name Id Activity Activity Confidence (pCVgrams) Uncertainty p<-40 0. 927 6.62E+ 00 2.12E- 0l

/ CO-60 0 . 945 7 .68E-0 2 3.0SE- 03 X }:;D-10 9 0.953

,/ CS-137 0.964 l.52E+ 00 4.33E- 02 BI-212 0.785 8.07E- 02 l.22E-0 2 PB-212 0.577 1. 48E-0l 6.86E- 03 BI-214 0.743 l.29E- 01 5.72E- 03 PB-214 0.563 1. 45E-0l 6.25E- 0 3 RA-226 0. 9!:il 3 .35E- 01 6.03E- 02

? = 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 1.000sigma

9/15/2017 1:44:16PM Page6 of8 Analysis Report for CDR # 4 SOIL UNIDENTIFIED PEAKS Peak Locate Performed on : 9/15/2017 1:44:06PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS{3/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide M 1 75.84 1.70261 E-01 7.75 Tol. TL-208 7 rn 2 83.67 4.35682 E-02 26 .13 m 4 92.32 1.06140 E-01 11.81 Tol. TH-23 /

TH-2;;

F 6 209.29 5.01650 E-02 21.51 Tol. AC-2

31. 80 ,1'l..,~

TL-20 F 10 510.41 2.37633 E-02 F 11 582.78 1.02623 E-01 7.01 Tol.

m 17 794.64 l.25842 E-02 26.03 Sum F 18 859.77 1.62969 E-02 19.96 Tol. TL-208 1 F 19 910.62 8.89174 E-02 6.96 Tol. AC-228. .J F 21 968.26 5.36037 E-02 10.02 Tol. AC-228 o~ c M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet r q \,b\:J Errors quoted at 1.000sigma NUCL IDE MDA REPO RT Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\library\ENVLIB.NLB Nuclide Energy Yield(%) Activity NuclideM DA LineMDA Name (pCVgrams) (pCVgrams) (pCVgrams)

(keV)

10. 67 6.62E+0 0 1.20E-0 1 l.20E-0 1

+ K-40 1460.81 *

+ MN-54 834.83 99.97 7 .04E-03 1.25E-0 2 1.25E-0 2 100.00 7.78E-0 2 1.32E-0 2 1.56E-0 2

+ CO-60 1173.22

100.00 7.58E-0 2 1. 32E-02 1332.49

9/15/2017 1:44:16PM Page 7 of8 Analysis Report for CDR#4 SOIL Nuclide Energy Yield(%) Activity NuclldeM DA LlneMDA Name (pCVgrams) (pCUgrams) (pCVgrams)

(lreVJ

+ ZN-65 1115.52 50 . 75 5.17E-0 2 3.64E-0 2 3.64E-0 2

+ KR-85 513.99 0.43 3.78E+O O 3.76E+O O 3.76E+O O

+ CD-109 88.03

3.72 5.0lE-0 1 5.22E-0 1 5.22E-0 1

+ CS-134 604.70 97.60 6.77E-0 2 1 . 47E-02 1. 81E-02 795.84 85.40 -3.86E- 04 1. 47E-02

+ CS-1 3 7 661. 65

85.12 1.52E+O O 1.63E-0 2 1.63E-0 2

+ EU-154 1 2 3.07 40.40 -3.09E- 02 4.09E-0 2 4.09E-0 2 722. 30 20.00 4.82E-0 2 5.98E-0 2 873.20 12.09 5.84E-0 2 l.OSE-0 1 996.30 10.34 3.74E-0 2 l.36E-0 1 1004.'/6 17.90 7.97E-0 3 7.99E-0 2 1274.51 34. 40 1.78E-0 2 4.57E-0 2

+ EU-155 86.54 32. 8 0 2.25E-0 2 8.03E-0 2 8.03E-0 2 105.31 21.80 -4.75E- 02 8.44E-0 2

+ TL-208 72.80 2.02 -1. 98E+ll 4 . 17E+09 4. 08E+ll 74.97 3.41 -7.84E+ 10 2 .24E+ll 84.90 1.51 -1. 49E+l2 3 . 67E+l l 277.36 6.31 -9.98E+ 08 5.34E+1 0 583.19 84 . 50 -8.66E+ 08 4.17E+0 9 763.13 1.81 1.42E+ ll l.60E+l l 860 .56 12.42 l.57E+1 0 2 . 44E+10 1093.90 0.40 -1.40E+ ll 8. 72E+ll

+ BI- 214 609 .31

46.30 1. 18E-Ol 3.00E-0 2 3.00E-0 2 768.36

5 . 04 l . 33E-01 l.41E-0 1 806.17 1.23 -5.23E- Ol 9.40E-0 1 934.06

3 .21 l.75E-0 1 3.lSE-0 1 1120.29

15 . 10 l.66E-O l 7 .7 5E-02 1155 .19 1. 69 1. llE+OO 1.03E+O O 1238.11

5.94 1.26E-0 1 2.38E-0 1 1280.96 1.47 -2.58E- 02 1 .0lE+OO 1377.67 4.11 2.SlE-0 1 3.08E-0 1 1401.50 1.39 9.18E-0 1 8.78E-0 1 14 07.98 2.48 5.49E-0 1 5.06E-0 1 1509.19 2.19 -1. lSE-01 4.81£-0 1 1661.28 1.15 7.lSE-0 2 6 . 54E-01 1729.60

3.05 1.71E-0 1 1. 75E-01 1764.49

15.80 1.54E-O l 4.49E-0 2 1847. 44 2.12 1.65E-O l 4.00E-0 1

+ PB-214 74.81 6.33 -1.89E- 01 3.16E-0 2 5.40E-0 1 77.11 10 . 70 -6. 07E-02 2.96E-O l 87.20

3.70 5 .04E-01 5.25E-0 1 8 9 -80 1.03 6.53E+OO 2.41E+O O 241. 98 7.49 -2.16E- Ol 2.41E-0 1 295.21

19.20 1. 26E-Ol 8.06E-0 2 351. 92

37 . 20 1.53E-0 1 3.16E-0 2 785.91

LlO 3.88E-0 1 5.72E-0 1

+ RA- 223 81.07 15.00 4.66E-0 2 1.03E-0 1 1. 90E-01 83 . 78 2 4.80 -4.02E- 01 1. 03E-01 94.90 11.30 -l.32E- 03 1. 97E-Ol 122.31 1.19 -5 . 76E-01 1.40E+O O

9/15/2017 ,:44:1 6PM Page 8 of8 Analysis Report for CDR#4 SOIL Nuclide Energy Yield('1/4) Activity NuclideMDA LlneMDA Name (pCVgrams) (pCVgrams) (pCVgrams)

(keV)

RA-223 144.20 3.26 2.71E-01 1. 03E-Ol 4.80E-01 154.19 5.59 8.74E-02 2.72E-01 269.41 13.60 9.56E-02 1.llE- 01 323.89 3.90 4.19E-01 3.81E-01 338.32 2.78 -2.69E-Ol 5.50E-01 444.94 1.27 -5.49E-02 l.29E+OO

+ RA-226 186.21

3.28 3.35E-Ol 3.06E-01 3.06E-01

+ AC-228 129.08 2.80 2.3SE-02 6.lOE-02 5.BOE-01 209.28 4.40 2.28E-01 3.64E-01 270.23 3.60 4.69E-01 4.19E-Ol 327.64 3.20 -1. 48E+OO 4.56E-01 338.32 11.40 -6.52E-02 1. 33E-01 409.51 2.13 -2.91E-01 7.49E-01 463.00 4.40 1. 25E-01 4.06E-01 794.70 4.60 -9.lOE-02 2.72E-01 911. 60 27.70 1. BlE-01 6.lOE-02 964.60 5. 20 7.0lE-01 3.25E-01 969.11 16.60 1.32E-Ol 1.00E-01 1587.90 3.71 3.47E-01 2.87E - Ol

+ Th-230 12.30 8.43 O.OOE+OO 1.12E+Ol 9.04E+10 67.60 0.37 -l .53E+Ol 1.12E+Ol 168.10 0.07 -1. 80E+Ol 2 .13E+Ol

+ PA-234M 766.36 0.29 8.SOE-01 1.68E+OO 4.30E+OO 1001.03 0.84 -9.96E-02 l.68E+OO

+ TH-234 63.29 4.50 -5.89E-Ol 8.98E-Ol l .17E+OO 92.38 2. 60 -4.28E-02 9.03E-01 92.80 2.60 S.SSE-02 8.98E-01

+ AM-241 59.54 3 6. 30 -4.43E-02 1. BBE-01 1. BBE- 01

+ CM-243 99. 55 14 .30 4.73E-0 2 8.12E-02 1. 42E-Ol 103.76 23.00 -4. Bl E-03 8.12E-02 117.00 10.80 6.37E-02 1.SBE-01 228.18 10.60 -2.09E-02 1. 46E-01 277.60 14.00 -6.39E-02 1.07E-01

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

9115/2011 3:31:44PM Page 1 of8 ex-Gamma Analysis Report for CDR-NRC-5 SOIL GAMMA SPECTRUM ANALYSIS Sample Identification : CDR-NRC-5 Sample Description : SOIL Sample Type : Silt Unit Sample Point Sample Size

. ./

3.141E+03 grams Facility : Dlaryland_NPP Sample Taken On 9/15/2017 1:00:00PM ;/

Acquisition Started : 9/15/2017 2:39:28PM Procedure : Slit Operator : Administrator Detector Name : DET01-ENV Geometry : 1.5l Marinelli /

Live llme : 3600.0 seconds .

Real Time : 3625.3 seconds Dead lime : 0.70%/

Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-409 6 Peak Area Range (In channels) : 100-409 6 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 6/312014 Efficiency Calibration Used Done On : 6/3/2014 Efficiency C8llbration Description : 1.5 Marinelli Sample Number : 3408 PEAK ANALYSIS REPORT Peak Analysis Perfonned on : 9/15i2017 3:31:34PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 3:31:44PM Page 2 of8 Analysis Report for CDR-NRC-5 SOIL ROI ROI Peak NetPeak Net Area Continuum FWHM Peak Energy Centroid Area Uncertainty Counts (keV)

No. (keV) start end 146 - 160 153.96 4.64E+0 2 40.86 1.68E+ 03 2.09 F 1 76.56 86.73 166 - 190 174.32 1.43E+0 2 29.09 1. 23E+03 1. 60 M 2 166 - 190 185 . 71 2.77E+0 2 35.25 1.30E+0 3 1. 61 m 3 92.42 4 185.72 364 - 381 372 . 35 2.78E+0 2 32.30 1.79E+0 3 1.49 F

415 - 427 418.68 1. 39E+02 30.50 1.22E+0 3 1. 74 F 5 208.87 468 - 489 477.54 1.24E+0 3 42.78 7.07E+0 2 1.48 M 6 238.29 468 - 489 483.58 3.03E+0 2 27.27 7.52E+0 2 1.49 m 7 241. 31 535 - 559 541.31 1.54E+0 2 28.25 1.54E+0 3 2.01 F 8 270.16 582 - 596 590.76 4.26E+0 2 31.11 9.76E+0 2 1. 45 F 9 294.88 666 - 686 676.78 2.84E+0 2 27.12 1. 01E+03 1. 74 F 10 337.88 697 - 708 704.15 8.40E+0 2 35 .87 6.00E+0 2 1.54 F 11 351.56 923 - 933 927.22 8.3 9E+Ol 16.74 4.34E+0 2 0.94 F 12 463.05 1015 - 1032 1022.18 2.70E+0 2 25.58 5.07E+0 2 2.49 F 13 510.51 1158 - 1173 1166.81 4.10E+0 2 25.28 3 .40E+02 1.70 F 14 582.80 1228 1219.13 6.96E+0 2 31.15 4.41E+0 2 1. 95 F 15 608.95 1209 -

1312 - 1332 1323.61 6.69E+0 3 83.05 3.32E+0 2 1. 94 F 16 661.17 1449 - 1460 1454. 20 7.94E+O l 14.17 1. 72E+02 1.57 F 17 726.44 1567 - 1595 1571.42 5.58E+O l 11.48 1.04E+0 2 1.48 M 18 785.03 1567 - 1595 1590.54 5.78E+O l 11. 66 l.15E+0 2 1. 48 m 19 7 94.59 1716 - 1730 1 72 1. 79 5 .5 4E+Ol 13.78 l.59E+0 2 2.43 F 20 860.18 1814 - 1831 1822.68 3.89E+0 2 23.72 2.22E+0 2 2.32 F 21 910.61 1933 - 1946 1938. 52 1.79E+0 2 17.96 2.15E+0 2 1. 62 F 22 968.51 2241.23 l.24E+0 2 16.42 2.33E+0 2 1. 75 F 23 1119.80 2234 - 2248 2336 - 2354 2347.08 5.80E+0 2 28.30 2.81E+0 2 2.37 F 24 1172.71 2471 - 2485 2476.90 6.78E+O l 15.04 2 .06E+ 02 2.20 F 25 1237.59 2654 - 2674 2665.67 5.35E+0 2 25.18 1. 1 3E+02 2.55 F 26 1331.93 2748 - 2762 2755.96 5.87E+O l 10.47 5.41E+O l 2.59 F 27 1377.06 2908 - 2931 2922.20 4.26E+0 3 66.08 7.84E+O l 2.84 F 28 1460.14 3453 - 3468 3459.92 3.64E+O l 7.53 1. 4 7E+Ol 3.39 F 29 1728. 88 3519 - 3539 3529.75 1.78E+0 2 14.22 2.61E+O l 3.35 F 30 1763.78 3702 3695.76 2.31E+O l 5.98 1.75E+O l 1. 78 F 31 1846.75 3689 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/15/2017 3:31:34PM Env. Background File : C:\Canberra\Apex\Root\Oiaryfand_NPP\Data\0000003388.CNF

9/15/2017' 3:31:44PM Page 3 ofS Analysis Report for COR-NRC-5 SOIL Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Backgroun d Uncert. Area Uncert.

F 1 76.56 4.64E+02 40.86 4.64E+02 4.09E+Ol M 2 86.73 1.43E+02 29.09 1.43E+02 2.91E+Ol m 3 92.42 2.77E+02 35.25 5.07E+Ol 8 .63E+OO 2.26E+02 3.63E+Ol F 4 185.72 2.78E+02 32.30 3.67E+Ol 8.25E+OO 2.42E+02 3.33E+Ol F 5 208.87 1.39E+02 30.50 1. 39E+02 3.0SE+Ol M 6 238.29 1.24E+03 42.78 3.14E+Ol 6.41E+OO l.21E+03 4.33E+Ol m 7 241.31 3.03E+02 27.27 3.03E+02 2 .73E+Ol F 8 270.16 1.S4E+02 28 .25 1.54E+02 2.82E+Ol F 9 294.88 4.26E+02 31.11 l. OOE+Ol 5.91E+OO 4.16E+02 3.17E+Ol F 10 337.88 2.84E+02 27.12 9.67E+OO 5.86E+OO 2.74E+02 2.77E+Ol F 11 351.56 8.40E+02 35.87 2.24E+Ol 5.47E+OO 8.17E+02 3.63E+Ol F 12 463.05 8.39E+Ol 16.74 8.39E+Ol 1.67E+Ol F 13 510.51 2.70E+02 25.58 1. 52E+02 8.10~+00 1.18E+02 2.68E+Ol F 14 582.80 4.10E+02 25.28 2.14E+Ol 4.78E+OO 3.89E+02 2.57E+Ol F 15 608.95 6.96E+02 31.15 2.18E+Ol 4.83E+OO 6.74E+02 3.lSE+Ol F 16 661.17 6.69E+03 83.05 l.38E+Ol 4.37E+OO 6 . 67E+03 8.32E+Ol F 17 726.44 7.94E+Ol 14.17 7.94E+Ol 1.42E+Ol M 18 785.03 5.58E+Ol 11.48 5.58E+Ol 1. 15E+Ol rn 19 794.59 5.78E+Ol 11. 6~ 5.78E+Ol 1.17E+Ol F 20 860.18 5.54E+Ol 13.78 , 5.54E+Ol l.38E+Ol F 21 910.61 3.89E+02 23.72 1.35E+Ol 3.68E+OO 3.76E+02 2.40E+Ol F 22 968.51 1. 79E+02 17.96 1. 79E+02 1.80E+Ol F 23 1119.80 1.24E+02 16.42 1.09E+Ol 3.21E+OO l.13E+02 l.67E+Ol F 24 1172.71 5.80E+02 28.30 5.80E+02 2.83E+Ol F 25 1237.59 6.78E+Ol 15.04 6.78E+Ol l.SOE+Ol F 26 1331. 93 S.35E+02 25.18 5.35E+02 2.52E+Ol F 27 1377 .06 5 .87E+O l 10.47 5.87E+Ol l.OSE+Ol F 28 1460.14 4.26E+03 66.08 5.78E+Ol 4 . 59E+OO 4.20E+03 6.62E+Ol F 29 1728.88 3.64E+Ol 7.5 3 3.64E+Ol 7.53E+OO F 30 1763. 78 1. 78E+02 14.22 1. 38E+Ol 2.34E+OO 1.64E+02 1.44E+Ol F 31 1846.75 2.31E+01 5.98 2.31E+Ol 5.98E+OO M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLI DE IDENTIFICATION REPOR T Nuclide Library Used : C:\Canberra\Apex\Root\Oiaryland_NPP\Library\ENVLIB.NLB IDENTIFIED NUCLIDES

9/15/2017 3:31:44PM Page4 of8 Analysis Report for CDR~NRC-5 SOIL Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty K-40 0.93 1460.81

10.67 6.37E+00 2.03E-01 0.95 1173.22 100.00 8.07E-02 4.39E-03 C0-60

4.37E-03 1332.49

100.00 8.15E-02 0.96 661.65 85.12 7.16E-01 2.14E-02 CS-137

1.18E-02 BI-212 0.72 72 7 .17

11. 80 6.56E-02 785.42

2.00 2.87E-01 5. 95E-02 1620.56 2 .75 PB-212 0.86 77.11

17.50 2.78E-01 2.63E-02 87.20

6.30 1. 81E-01 3.74E-02 89.80 1. 75 238.63

44.60 1.45E-01 6.43E-03 300.09 3.41 BI-214 0.69 609.31

46.30 1.26E-01 6.86E-03 768.36 5.04 806.17 1.23 934.06 3.21 1120.29

15.10 1. 0lE-01 1.SlE-02 1155.19 1. 69 1238.11

5.94 1. 65E-01 3.69E-02 1280.96 1. 47 1377.67

4.11 2.23E-01 4.0lE-02 1401. 50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1. 15 1729.60

3.05 2.llE-01 4 . 41E-02 1764.49

15.80 1.85E-01 1. 73E-02 1847.44

2.12 1.97E-01 5.16E-02 PB-21 4 0 . 86 74.81 6.33 77.11

10.70 4.55E-01 4.30E-02 87.20

3.70 3.08E-Ol 6.36E-02 89.80 1.03 241.98 7.49 2.18E-01 2.04E- 0 2

1.0lE-0 2 295.21

19. 20 1.26E-01 351.92

37.20 1.39E-01 7.04E-03 785.91

1.10 5.22E-01 1. 08E-01 RA-226 0.96 186.21

3.28 3.70E-01 5 . 21E-02 AC-228 0.62 129.08 2.80 209.28

4.40 l.62E-01 3.60E-02 270.23

3.60 2.39E-01 4.45E-02 327.64 3.20 338.32 11.40 1. 49E-01 1.55E-02 409.51 2 .13 463.00 4.40 1. 39E-01 2.BlE-02 794.70

4.60 1. 30E-01 2.65E-02 911.60

27 .70 l.56E-01 1.0SE-02 964.60 5.20 969.11

16.60 l.30E-01 1.33E-02 1587.90 3.71

9/15/201 Y 3:31 :44PM Page S of8 Analysis Report for CDR-NRC-5 SOIL

= Energy line found in 1he spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPOR T Nuclide Nuclide Wtmean Wt mean Comments Name Id Activity Activity Conffdence (pCl/grams) Uncertaint y 1

K-40 0 .931 6.37E+OO 2.03E-Ol C0-60 0.956 8.llE-02 3.09E-03 CS-137 0.964 7 .16E-01 2.14E-02 X EU-155 0.303 BI-212 0.729 7.lOE-02 1.16E-02 PB-212 0.862 1. 46E-01 6.16E-03 BI-214 0.699 1.34E-Ol 5.66E-03 PB-214 0.863 1.42E-01 5.49E-03 RA-226 0.961 3.70E-Ol 5.21E-02 AC-228 0.629 1. 48E-Ol 6 .63E-0 3

? = nucllde Is part d an undetermined solution X = nuclide rejected by the interference analysis

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

9/15/2017 3:31:44PM Page 6 of8 Analysis Report for CDR*NRC-5 SOIL UNIDENTIFIED PEAKS Peak Locate Performed on : 9/15/2017 3:31:34PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS ('1/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty *Type Nuclide m 3 92.42 6.27712E-02 16.06 Tol. TH-234 TH-234 F 13 510.51 3.27971E-02 22.73 Sum 1L~t.?\

F 14 582.80 l.08031E-01 6.61 1L'µ)i F 20 860.18 l.53864E-02 24.87 /Jl,~

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

~~

NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Library\ENVLIB.NLB Nuclide Energy Yield('1/4) Activity NuclideMDA LlneMDA Name (pCilgrams) (pCi/grams) (pCUgrams)

(keV)

+

uK-40 "

. MN-54

.. - \

1460.81 834.83

10.67 99.97 6.37E+OO 9 .2 7E-03

l. 05E-01 l .20E-02

1. OSE-01 1.20E-02

+) C0-60 1173.22

100.00 8.07E-02 l.06E-02 l.45E-02 1332 .49

100.00 8 .lSE-02 1. 06E-02

+ ZN-65 1115.52 50.75 6.71E-02 3.48E-02 3.48E-02

+ KR- 85 513.99 0.43 4.94E+00 3.17E+OO 3.17E+OO

+ CD-109 88.03 3.72 - 9 .33E-02 6.09E-01 6.0 9E-01

+ CS-134 604.70 97. 60 6.18E-02 1.41E-02 1.63E-02

1. 41E-0 2

+

I CS-137 EU-154 795 .84 661.65 123.07 722. 30 85.40

85. 12 40.40 20.00 6.70E-04

7. 1 6E-01

-5.76E-03 5.97E-02 1.27E-02

3. 56E-02 l.2 7E-02 3.56E-0 2 5.83E-02 873.20 12.09 6.08E-02 1.02E-01

9/15/201} 3:31:44-PM Page 7 of8 Analysis Report for CDRMNRC-5 SOIL Nuclide Energy Yield{°/4) Activity NuclldeMDA LineMDA Name (pCVgrams) (pCl/grams) (pCVgrams)

(k*VJ EU-154 996.30 10.34 -1.34E -02 3.56E- 02 1. 30E-01 1004.7 6 17.90 -8 .41E-0 3 7.63E- 02 1274.5 1 34.40 1. 58E-02 4.38E- 02

+ EU-155 86.54

32.80 3.47E- 02 4 .03E-02 4.03E- 02 105.31 21.80 -8.66E -02 7.37E- 02

+ TL-208 72.80 2. 02 -6.84E +l0 l.47E+ 09 1. 42E+ll 74.97 3.41 2.39E+ ll 7.85E+ l0 84.90 1.51 -l.67E +l0 l.26E+ ll 277.36 6.31 2.88E+ 09 1. 76E+l0 583.19 84 .50 4.38E+ 09 l.47E+ 09 763 .13 1. 81 -l.19E+ 10 5.63E+ 10 860.56 12.42 -4.48E +09 8.85E+ 09 1093.9 0 0.40 8.67E+ 10 3.27E+ ll

+ BI-214 609.31

46.30 1. 26E-01 2.SOE- 02 2.SOE- 02 768.36 5.04 -1.24E -02 2.29E- 01 806.17 1.23 1.21E- 01 9.24E- 01 934.06 3.21 2.58E- Ol 4.26E- 01 1120.2 9

15.10 1.0lE- 01 7.94E- 02 1155.1 9 1. 69 2.79E- 01 9.55E- Ol 1238.1 1

5.94 1. 65E-01 2.02E- 01 1280.9 6 1.47 1. 20E+OO 1. 02E+OO 1377.6 7

4.11 2.23E- 01 1. 66E-01 1401.5 0 1.39 6.98E- 01 8.45E- Ol 1407.9 8 2.48 5.63E- 01 4.77E- 01 1509.1 9 2.19 -6.26E -02 4.12E- 01 1661.2 8 1.15 3.86E- Ol 6.29E- 01 1729.6 0

3.05 2.llE-0 1 1. 42E-01 1764.4 9

15. 80 1. 85E-01 4.27E- 02 1847.4 4

2.12 1. 97E-01 2.18E- 01

+ PB-214 74.81 6.33 l.47E+O O 2.25E- 02 4.82E- 01 77.11

10. 70 4.SSE- 01 2.27E- 01 87.20

3.70 3.08E- 01 3.57E- Ol 89.80 1.03 -7.13E -02 2.14E+ 00 241. 98

7.49 2.18E- 01 9.36E- 02 295.21

19.20 1.26E- 01 5.42E- 02 351. 92

37.20 1.39E- 01 2.25E- 02 785.91

1.10 5.22E- 01 4.69E- 01

+ RA-223 81.07 15.00 -2. llE-*02 9.03E- 02 1. 69E-Ol 83.78 24.80 -1. 19E-02 9.03E- 02 94.90 11.30 -9.60E -02 1. 75E-01 122.31 1.19 1.62E- Ol 1.22E+O O 144.20 3.26 -2.55E -Ol 4.07E- 01 154.19 5 . .59 -l.13E -01 2.30E- 01 269.41 13.60 -3.69E -03 9.23E- 02 323.89 3.90 3.34E- Ol 3.21E- Ol 338.32 2.78 4.43E- 01 4.79E- Ol 444.94 1.27 -3.66E -01 1.00E+O O

+ RA-226 186.21

3.28 3.70E- 01 3.93E- 01 3.93E- 01

+ AC-228 129.08 2.80 1. 67E-01 3.85E- 02 5.06E- 01 209.28

4.40 l.62E- Ol 2.22E- 01 270.23

3.60 2.39E- 01 4.14E- 01

9/15/2017 3:31:44PM Page 8 of8 Analysis Report for CDR-NRC--5 SOIL Nuclide Energy Yield(%) Activity NuclideMDA LlneMDA Name (pCilgrams) (pCVgrams) (pCilgrams)

(keV)

AC-228 327.64 3.20 -3.64E-02 3.85E-02 3.86E-01 11.40 1. 49E-01 1. lOE-01 338.32

5.72E-01 409 . 51 2 . 13 2.SOE-01 463.00 4.40 1.39E-01 1. 81E-01

1. 19E-01 794.70

4.60 1.30E-01 911. 60

27.70 1.56E-01 3.SSE-02 964.60 5.20 8.35E-Ol 3.13E-01 969.11

16. 60 l.30E-01 6.09E-02 1587.90 3.71 6.90E-02 2.55E-Ol

+ Th-230 12.30 - 8.43 O.OOE+OO 1. 00E+Ol 8.40E+10 67.60 0.37 -8.74E+00 1.00E+Ol 168.10 0.07 9.74E+OO 1.81E+Ol

+ PA-234M 766.36 0.29 4.58E-01 1. 62E+OO 3.93E+OO 1001.03 0.84 -7.97E-02 1.62E+OO

+ TH-234 63.29 4.50 2.59E-01 7.95E-01 1.03E+OO

-2.22E-02 8.04E-01 AM-241 92.38 2.60 92.80 2.60 -l.39E-01 7.95E-01

+ 59.54 36.30 -1. lOE-03 1. 62E-01 1.62E-01

+ CM-243 99. 55 14.30 -l.20E-01 7.llE-02 1.26E-01 103.76 23.00 -8.41E-02 7. llE-02 117.00 10.80 4.03E-05 1. 36E-01 228.18 10.60 -6.94E-02 1. 21E-01 277.60 14.00 -l.71E-02 8.92E-02

+ = Nuclide identified during the nuclide identification

.. = Energy line found in the spectrum

> = MDA value not calculated

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

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

911512u , 1 4:32:58PM Page 1 of8

~A pe x-G am ma Analysis Report for CDR-NRC-6 SOIL GAMMA SPEqTRUM ANALYSIS Sample Identification : CDR-NRC-6 /

Sample Description : SOIL Sample Type : Silt Unit Sample Point Sample Size : 3.087E+03 grams /

Facility

Oiaryland_NPP Sample Taken On : 9/15/2017 1:05:00PM/

Acquisition Started : 9/15/2017 3:32:19PM Procedure : Slit Operator : Administrator /

Detector Name DET01-ENV Geometry 1.5L Marinelli /

Lill8llm e : 3600.0 seconds Real11me : 3625.2 seconds Dead lime : 0.10 Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-409 6 Peak Area Range (In channels) : 100- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 6/312014 Efficiency Calibration Used Done On : 6/312014 Efficiency Calibration Description : 1.5 MarinelU Sample Number : 3409 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/15/2017 4:32:48PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 4:32:58PM Page 2 of8 Analysis Report for CDR-NRC-6 SOIL Peak Energy ROI ROI Peak NetPeak NetArea Continuum FWHM Centroid Area Uncertainty Counts (keV)

No. (keV) start end 74.55 143 - 160 149.95 2.62E+0 2 28.86 9.64E+ 02 1. 32 M 1 76.90 143 - 160 154 . 64 3.23E+0 2 30.62 9.54E+0 2 1.33 m 2 171 - 191 174.88 l.05E+0 2 26.70 9.93E+0 2 1.27 M 3 87.01 171 - 1 91 185 . 92 2.60E+0 2 31. 79 9 . 13E+02 1.28 m 4 92.53 365 - 380 372.10 3.32E+ 02 31.29 1. 58E+03 1. 24 F 5 185.59 468 - 486 477.54 l.11E+0 3 41. 84 l.69E+0 3 1.34 F 6 238.29 535 - 549 540.42 1.74E+0 2 29.82 9.19E+0 2 2.28 F 7 269.72 585 - 597 590.62 4.52E+0 2 31. 32 8. 41E+02 1. 45 F 8 2 94.81 653 - 686 656.74 7.76E+O l 19.59 4 .67E+02 1.56 M 9 3 2 7.86 653 - 686 677.06 2.60E+0 2 25.56 4.68E+0 2 1. 57 m 10 338.02 699 - 709 704.14 9.17E+0 2 36 . 18 4.64E+0 2 1. 60 F 11 351. 55 921 - 931 926.45 9.02E+O l 21.68 4.82E+0 2 1. 6S F 12 462.67 1014 - 1029 1022.33 2.91E+0 2 26. 02 4.46E+0 2 2.58 F 13 510.59 1157 - 1171 1166 . 71 4.14E+0 2 25 .64 3.51E+0 2 1.75 F 14 582.75 1210 - 1225 1218.94 7.16E+0 2 31. 00 3 .24E+02 1. 94 F 15 608.86 661.16 1313 - 1332 1323.59 6. 71E+03 83. 2 7 3 .37E+02 1.94 F 16 1450 - 1460 1454.81 9.37E+O l 15.05 l .45E+ 02 1. 89 F 17 726 . 75 1582 - 1594 1588.93 3.54E+O l 11. 72 1. 72E+02 1. 4 6 F 18 793.79 1814 - 1831 1822 . 79 3.54E+0 2 22 . 09 2.02E+0 2 2.05 F 19 910.67 1925 - 1945 1 93 7 .92 2.1 7E+0 2 19.36 2.18E+ 02 2.89 F 20 968.21 2233 - 2251 2241. 34 1.95E+0 2 18 . 85 1.97E+0 2 2.82 F 21 1119. 86 2340 - 2355 2346.92 3.12E+0 2 22. 2 8 2 .22E+02 2.36 F 22 1172 . 62 2 4 71 - 2482 2477.05 4.87E+O l 1 3.30 1. 7 7E+0 2 1. 63 F 23 1237.66 2 653 - 2675 2665.67 3.36E+0 2 20.47 1.38E+0 2 2.49 F 24 1331.94 2 908 - 2931 2922 .03 4.29E+0 3 66. 2 6 6.95E+0 1 2 .86 F 25 1460.06 3169 - 3183 3177.04 3.60E+O l 8.53 3 .36E+Ol 3.14 F 26 1587.51 3455 - 3466 3460.52 2.97E+O l 6.46 8.52E+O O 2.93 F 27 1729.18 3521 - 3539 3530.05 1.58E+0 2 12.98 9 .25E+OO 3.39 F 28 1763.93 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigme BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/15/2017 4:32:48PM Env. Background File : C:\Canberra\Apex\Root\Diaryland_NPP\Data\0000003388.CNF Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted Peak (keV) Area Uncertainty Background Uncert. Area Uncert.

No.

2.62E+0 2 28.86 7.82E+O l 9.57E+OO 1 . 84E+02 3.04E+O l M 1 74 .55

9/15/201, 4:32:SBPM Page 3 of8 Analysis Report for CDR-NRC-6 SOIL Peak Energy Origlnal Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Al8a Uncert.

m 2 76. 90 3.23E+ 02 30. 62 3.23E+ 02 3.06E+ 0l M 3 87.01 1.05E+ 02 26. 70 l.05E+ 02 2. 67E+0l m 4 92.53 2.60E+ 02 31. 79 5.07E+ 0l 8.63E+ 00 2.09E+ 02 3.29E+ 0l F 5 185.59 3.32E+ 02 31.29 3.67E+ Ol 8.25E+ 00 2.95E+ 02 3.24E+ 0l F 6 238.29 l.11E+ 03 41. 84 3.14E+ 01 6.41E+ 00 1.08E+ 03 4.23E+ 0l F 7 269.72 1. 74E+02 29. 82 1. 74E+02 2.98E+ 0l F 8 294. 81 4.52E+ 02 31.32 1.00E+ 0l 5.91E+ 00 4.42E+ 02 3.19E+ 0l M 9 327.86 7.76E+ 0l 19.59 7 .76E+01 1. 96E+0l m 10 338.02 2.60E+ 02 25.56 9.67E+0 O 5.86E+ 00 2.51E+ 02 F 11 2.62E+ 0l 351.55 9.17E+ 02 36.18 2.24E+ 0l 5.47E+ 00 8.95E+ 02 3.66E+ 0l F 12 462.67 9.02E+ 0l 21.68 9.02E+ 0l 2.17E+ 0l F 13 510.59 2.91E+ 02 26. 02 1. 52E+02 8.l0E+ 00 1. 39E+02 2.73E+ 0l F 14 582.75 4.14E+ 02 25.64 2.14E+ 0l 4.78E+ 00 3.92E+ 02 2.61E+ 0l F 15 608.86 7.16E+ 02 31. 00 2.lBE+ 0l 4.83E+ 00 6.94E+ 02 3.14E+ 0l F 16 661.16 6.71E+ 03 83.27 1.38E+ 0l 4,37E+ 00 6.69E+ 03 8.34E+ 0l F 17 726.75 9.37E+ 0l 15.05 9.37E+ 0l 1.SlE+ 0l F 18 793.79 3.54E+ 0l 11. 72 3.54E+ 0l 1.17E+ 0l F 19 910.67 3.54E+ 02 22.09 1. 35E+0l 3.68E+ 00 3.41E+ 02 2.24E+ 0l F 20 968.21 2.17E+ 02 19.36 2.17E+ 02 1.94E+ 0l F 21 1119 . 86 l.95E+ 02 18.85 1. 09E+0l 3.21E+ 00 l.84E+ 02 1. 91E+0l F 22 1172.6 2 3.12E+ 02 22.28 3.12E+ 02 2.23E+ 0l F 23 1237.6 6 4.87E+ 01 13.30 4.87E+ 0l 1. 33E+0l F 24 1331. 94 3.36E+ 02 20.47 3.36E+ 02 2.0SE+ Ol F 25 1460.0 6 4.29E+ 03 66.26 5 . 78E+0l 4.59E+ 00 4.23E+ 03 6.64E+ 0l F 26 1587.5 1 3.60E+ 0l 8.53 3,60E+ 0l 8.53E+ 00 F 27 1729.1 8 2.97E+ 0l 6.46 2.97E+ 0l 6.46E+ 00 F 28 1763. 93 1.58E+ 02 12.98 1.38£+ 01 2.34E+ 00 1. 44E+02 1.32E+ 0l

=

M First peak in a multiplet region

=

m Other peak in a multiplet region F = Fitted singlet Enors quoted at 1.000sigma NUCLIDE IDENTIFICATION REP ORT Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Llbrary\ENVLIB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{%} Activity Activity Name Confidence {keV) (pCVgrams} Uncertainty K-4D 0. 91 1460.8 1

10 .67 6.53E+ 00 2 .08E-0 1 CO-60 0 .94 1173.2 2

100 .00 4.42E- 02 3.33E- 03

9/15/2017 4:32:58PM Page4 of8 Analysis Report for CDR-NRC-6 SOIL Nuclide Id Energy Yield("/4) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty CO-60 0.94 1332.49

100.00 5.21E-0 2 3.44E-0 3 CS-137 0.96 661.65

85.12 7.31E-0 1 2.18E-0 2 BI-212 0.57 727.17

11.80 7 .88E-02 1.28E-0 2 785.42 2.00 1620.56 2.75 PB-212 0.87 77 .11

17.50 1. 95E-01 1. 96E-02 87.20

6.30 1.34E-0 1 3.45E-0 2 89.80 1. 75 238.63

44.60 1.32E-0 1 6.22E-0 3 300.09 3.41 BI-214 0 . 63 609.31

46. 30 1.32E-0 l 7.0lE-0 3 768.36 5.04 806.17 1.23 934.06 3.21 1120.29

15.10 1.67E-0 1 1.78E-0 2 1155.19 1. 69 1238 .11

5.94 1. 21E-01 3.31E-0 2 1280.96 1.47 1377.67 4.11 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661. 28 1.15 1729.60

3.05 1.75E-0 1 3.SSE-0 2 1764.49

15. 80 1. 65E-01 1.60E-0 2 1847.44 2. 12 PB-214 0.79 74.81

6.33 3.33E-0 1 5.62E-0 2 77.11

10.70 3.20E-0 l 3.21E-0 2 87.20

3.70 2.28E-0 1 5.88E-0 2 89.80 1.03 241.98 7.49 295. 21

19.20 1. 36E-01 1.04E-0 2 351.92

37.20 1. SSE-01 7.37E-0 3 785.91 1. 10 RA-226 0.94 186.21

3.28 4.60E-0 l 5.21E-0 2 AC-228 0.62 129.08 2.80 20 9.28 4.40 270.23

3.60 2.76E-0 l 4.78E-0 2 327.64

3.20 1. SlE-01 3.82E-0 2 338.32

11.40 1. 39E-01 l.49E-0 2 409 .51 2.13 463.00

4.40 1.53E-0 l 3.69E-0 2 794.70

4.60 8.13E-0 2 2 . 70E-02 911.60

27.70 1.44E-0 l 9.96E-0 3 964.60 5 .20 969.11

16.60 1. 60E-0l l.47E-0 2 1587.90

3.71 1.68E-0 l 4.00E-0 2

9/15/201 t 4:32:58PM Page S of8 Analysis Report for CDR-NRC-6 SOIL

= Energy Hne found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFER ENC E CORRECTED REPO RT Nuclide Nuclide Wtmean Wtmean Comme nts Name Id Activity Activity Confidence (pCl/grams) Uncerta inty

~ K-40 0.913 6.53E+O O 2.0BE- 01 1/C0-6 0 0.949 4.BOE- 02 2.39E- 03 CS-137 0.963 7.31E- 01 2.lSE- 02 BI-212 0.573 7.88E- 02 1.28E- 02 PB-212 0.874 l.28E- 01 5.86E- 03 BI-2 14 0.630 1.41E- 01 5.87E- 03 PB-21 4 0.793 1.48E- 01 5.86E- 03 RA-226 0.940 4.60E- 01 5.21E- 02 AC-228 0.629 1. 46E-01 6.58E- 03

? = 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 1.000sigma

9115/2017 4:32:58PM Page 6 of8 Analysis Report for CDR-NRC-6 SOIL UNIDENTIFIED PEAKS Peak Locate Perfonned on : 9/15/2017 4:32:48PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS (%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide )

4 92 . 53 5.81850E -02 15.73 Tol. TH-234 /

m TH-234 F 13 510.59 3.85520E -02 19.64 ~1,,d}

F 14 582 .75 1.09028E -0l 6.65 .Po M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLI DE MDA REPOR T Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Library\ENVLIB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCVgrams) (pCVgrams) (pCVgrams)

(keV) 1460.81 10.67 6.53E+O0 l.0lE-01 1.0lE-01

+ K-40 *

+ MN-54 834.83 99.97 9.19E-03 1.18E-02 1. 18E-02 1173.22 100.00 4.42E-02 l.23E-02 1. 25E-02

+ CO-60

1332. 49 100.00 5 .21E-02 l.23E-02

3.43E-02 3.43E-02

+ ZN-65 1115.52 50.75 3.SlE-02

+ KR-85 513.99 0.43 6.72E+00 3.18E+00 3.18E+00

+ CD-109 88.03 3.72 6.23E-02 6.12E-01 6.12E-01

+ CS-134 604.70 97.60 7.64E-02 1.39E-02 1.66E-02 795.84 85.40 -1. 44E-02 1.39E-02

+ CS-137 661. 65 85.12 7.31E-0l 1.28E-02 1. 28E-02

+ EU-154 123.07 40.40 -1. 56E-02 3.59E-02 3.59E-02 722.30 20.00 8.65E-02 5.87E-02 873.20 12.09 -2 .99E-0l 1.0lE-01 996.30 10.34 -4.0SE-02 1. 24E-01

9/15/201"/ 4:32:58PM Pagc7 of8 Analysis Report for CDR~NRC-6 SOIL Nuclide Energy Yield(%) Activity NuclldeM DA LlneMDA Name (pCVgrams) (pCilgrams) (pCVgrams)

(lreV)

EU-154 1004.7 6 17.90 1.48E- 02 3.59E- 02 7.SlE- 02 1274.5 1 34. 40 8.92E- 03 4.28E- 02

+ EU-155 86.54 32.80 -4.60E -03 7 ,llE-02 7 .llE-02 105.31 21.80 -9.02E -03 7 .46E-02

+ TL-208 72.80 2.02 5.46E+ 14 7. 79E+13 7 .43E+l 5 74.97 3.41 1. 02E+l6 4.07E+ 15 84.90 1.51 -4.78E +14 6.64E+ 15 277.36 6.31 6 .57E+1 3 9.30E+ 14 583.19 84.50 2.00E+ l4 7.79E+ 13 763.13 1. 81 4.15E+ 15 3.01E+ 15 860.56 12.42 3.44E+ l4 4.58E+ l4 1093.9 0 0.40 9.66E+ 14 1. 62E+l6

+ BI-214 609.31

46.30 1.32E- 01 2.0SE- 02 2.0SE- 02 768.36 5.04 9.72E- 02 2.32E- 01 806.17 1.23 2. 39E-01 9.21E- 01 934.06 3.21 2.36E- 01 4.07E- Ol 1120.2 9

15. 10 1. 67E-Ol 8.06E- 02 1155.1 9 1. 69 2.71E- 02 9.60E- 01 1238.1 1

5.94 1.21E- 01 1.79E- 01 1280.9 6 1. 47 6.64E- 01 9.83E- Ol 1377.6 7 4.11 2.BOE- 01 2.95E- 01 1401.5 0 1.39 5.24E- Ol 8.24E- 01 1407.9 8 2.48 2.53E- 01 4.59E- 01 1509.1 9 2.19 -6.92E -01 4.13E- 01 1661.2 8 1.15 1.52E- 01 5.72E- Ol 1729.6 0

3.05 1. 75E-01 1. OSE-01 1764.4 9

15.80 1.65E- 01 2.98E- 02 1847.4 4 2.12 2.lOE- 01 3.57E- Ol

+ PB-214 74.81

6.33 3.33E- 01 1.98E- 02 2.78E- 01 77.11

10.70 3.20E- Ol 1. 45E-Ol 87.20

3.70 2.28E- 01 3.26E- 01 89.80 1.03 4.71E+O O 2.13E+O O 241.98 7.49 -2.31E -01 2.17E- 01 295.21

19.20 1. 36E-Ol 4.96E- 02 351.92

37.20 1.SSE- 01 1.98E- 02 785.91 1.10 8.02E- 01 1.09E+O O

+ RA-223 81. 07 15 .00 -1. 16E-02 9.lSE- 02 1. 69E-Ol 83.78 24.80 -6.54E -03 9.lSE-0 2 94.90 11.30 -2.93E -02 l.75E-0 1 122.31 1.19 -3.00E -01 1.23E+O O 144.20 3.26 1.92E- 01 4.19E- Ol 154.19 5.59 3.28E- 02 2.36E- 01 26 9 .41 13. 60 7.78E- 03 9.39E- 02 323.89 3.90 -2.54E -Ol 3.25E- Ol 338.32 2.78 3.03E- 02 4.77E- Ol 444.94 1.27 -7.lOE -01 l.03E+O O

+ RA-226 186.21

3.28 4.60E- 01 3.62E- 01 3.62E- 01

+ AC-228 129.08 2.80 -4.0lE -02 3.74E- 02 5.06E- 01 209.28 4.40 -8.86E -02 3.03E- 01 270.23

3.60 2.76E- 01 2.73E- Ol 327.64

3 . 20 1. 51E-01 2.0lE-0 1

9/15/2017 4:32:58PM Page 8 of8 Analysis Report for CDR-NRC-S SOIL Nuclide Energy Yield(%} Activity Nucl/de MDA l.ineMDA Name (pCVgrams) (pCUgrams) (pCUgrams)

(keV)

AC-228 338.32

11.40 1. 39E-Ol 3.74E-02 5.85E-02 409.51 2.13 2.23E-02 5.94E-01 463.00

4.40 1.53E-01 1.93E-01 794.70

4.60 8.13E-02 1. 67E-01 911. 60

27.70 1.44E-01 3.74E-02 964.60 5.20 6.74E-01 3.07E-01 969.11 16.60 l.60E-Ol 7.03E-02 1587.90 3.71 l.68E-01 1.64E-01

8.54E+10

+ Th-230 12.30 8.43 O.OOE+OO 9.95E+OO 67.60 0.37 -4.56E+OO 9.95E+OO 168.10 0.07 2.26E+OO 1. 84E+Ol

+ PA-234M 766.36 0.29 1.29E+OO 1. 56E+OO 3.96E+OO 1001.03 0.84 -4.63E-Ol 1. 56E+OO

+ TH-234 63.29 4.50 3.00E-01 7.96£-01 1.0SE+OO 92.38 2.60 -4.59E-02 8.03E-01 92.80 2 .60 -4 .74E-02 7.96E-01

+ AM-241 59.54 36.30 1.89E-02 1. 69E-01 1.69E-Ol

+ CM-243 99.55 14.30 6.llE-03 7.21E-02 1. 27E-01 103. 76 23.00 4.86E-02 7.21E-02 117. 00 10.80 2.52E-02 1.37E-01 228.18 10.60 -2.04E-02 l.24E-01 277.60 14.00 -2.16E-02 9.04E-0 2

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

9/15/2017 5:34:40PM Page 1 of8 pex-Gamma Analysis Report for CDR-NRC-7 SOIL GAMMA SPECTRUM ANALYSIS Sample Identification ; COR-NRC-7 Sample Description

SOIL Sample Type : Silt Unit Sample Point Sample Size : 3.139E-+-03 grams /

Facility : Diaryland_NPP Sample Taken On : 9/15/2017 1:15:00P Acquisition Started : 9/15/2017 4:34:00PM Procedure : Slit Operator : Administrator Detector Name : DET01-ENV /

Geometry : 1.SL Marinelli /

Live Time : 3600.0 seconds Rea!Tlme : 3624.9 seconds Dead lime : 0.69 %

Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-409 6 Peak Area Range (in channels) : 100-409 6 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 613/2014 Efficiency Calibration Used Done On : 6/3/2014 Efficiency Calibration Description : 1.5 Marinelli Sample Number : 3410 PEAK ANALYSIS REPORT Peak Analysis Parforrnad on : 9/1512017 5:34:31PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 5:34:40PM Page 2 of8 Analysis Report for CDR-NRC-7 SOIL ROI ROI Peak Net Peak Net Area Continuum FWHM Peak Energy Centroid Area Uncertainty Counts (keV)

No. (keV) start end 98 - 108 101. 43 8.43E+O l 22.78 8.57E+0 2 0.98 F 1 50.30 144 - 160 149.82 2.46E+0 2 26.24 7.47E+0 2 1.32 M 2 74.48 76.78 144 - 160 154.40 3.45E+0 2 28.97 7.37E+0 2 1. 33 m 3 378 372.26 1.95E+0 2 23.70 l.02E+0 3 1.03 F 4 185.67 363 -

469 - 486 477.61 1. 19E+03 40.94 9.46E+0 2 1.47 F 5 238.32 547 541.06 1.05E+0 2 20.01 5.21E+0 2 1.40 F 6 270.04 535 -

586 - 609 590.67 4.42E+0 2 27.07 3.17E+0 2 1. 60 M 7 294.83 586 - 609 600.21 1.32E+0 2 17 . 88 3.41E+0 2 1. 61 m 8 299.61 652 - 681 656.91 4.54E+O l 14.06 2 . 67E+02 1.25 M 9 327.95 652 - 681 676.86 2.33E+0 2 21.29 2.54E+0 2 1.27 m 10 337.92 697 - 714 704.13 8.43E+0 2 32.85 4.24E+0 2 1.52 F 11 351.55 921 - 932 926.93 1.02E+0 2 15.71 1.94E+0 2 1. 65 F 12 462.91 1015 - 1031 1022.00 3.39E+0 2 23.68 2.58E+0 2 2.72 F 13 510.42 1172 1166.63 4.11E+0 2 24.09 1.99E+0 2 1. 68 F 14 582.72 1159 -

1212 - 1224 1218.89 6.15E+0 2 28.56 2.00E+0 2 1.93 F 15 608.83 1319 - 1328 1323.70 3.74E+0 2 23.31 1.60E+0 2 1. 78 F 16 661.22 1449 - 1462 1454.81 1.02E+0 2 14.29 1.47E+0 2 1. 77 F 17 726.75 1532 - 1542 1536.31 3.45E+O l 11.50 l.43E+0 2 1.43 F 18 767.48 1581 - 1598 1589.60 4.82E+O l 11. 76 1.80E+0 2 1.67 F 19 794.12 1709 - 1728 1721. 08 9.29E+O l 14.48 1.53E+0 2 2.94 F 20 859.83 1815 - 1831 1822.79 3.55E+0 2 21.90 1.55E+0 2 2.36 F 21 910.67 1858 - 1875 1866.40 6.66E+O l 13.25 1.50E+0 2 2.47 F 22 932.46 1923 - 1946 1929. 46 5.57E+O l 11.42 1. 31E+02 1. 90 M 23 963.98 1923 - 1946 1938.32 l.72E+0 2 16.86 1.47E+0 2 1. 90 m 24 968.41 2230 - 2248 2240.97 l.70E+0 2 17.11 2.04E+0 2 2.07 F 25 1119.68 2747 - 2762 2755.16 6.25E+O l 10.29 3.79E+O l 3.99 F 26 1376.66 2908 - 2932 2921. 97 3.95E+0 3 63.68 9.56E+O l 2.78 F 27 1460.03 3014 - 3025 3018.73 1. 59E+Ol 5.26 2.68E+O l 1.62 F 28 1508.39 3453 - 3465 3459.63 2.45E+O l 6.25 1. 94E+Ol 1. 64 F 29 1728.74 3521 - 3538 3529.99 l.22E+0 2 12.09 2.70E+O l 2.52 F 30 1763.90 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000slgma BACKGROUND SUBTRACT REPORT Peak Analysis Perfonned on : 9/15/2017 5:34:31PM Env. Background File : C:\Canberra\Apex\Root\Diaryland_NPP\Data\0000003388.CNF

9/15/2017 5:34:40PM Page 3 of8 Analysis Report for CDR-NRC-7 SOIL Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 50.30 8.43E+O l 22.78 8.43E+O l 2.28E+O l M 2 74.48 2.46E+0 2 26. 24 7. 82E+Ol 9.57E+OO 1.6BE+0 2 2.79E+O l m 3 76.78 3.45E+0 2 28.97 3.45E+0 2 2.90E+O l F 4 185.67 1.95E+0 2 23 . 70 3.67E+O l 8.25E+OO 1. 59E+02 2.51E+O l F 5 238.32 1.19E+0 3 40. 94 3.14E+O l 6.41E+OO 1.16E+0 3 4.14E+O l F 6 270.04 l.05E+0 2 20 . 01 1.05E+0 2 2.00E+O l M 7 294.83 4.42E+0 2 27.07 l.OOE+O l 5.91E+OO 4.32E+0 2 2.77E+O l m 8 299.61 1.32E+0 2 17.88 1. 32E+02 1.79E+O l M 9 327.95 4.54E+O l 14.06 4.54E+O l 1. 41E+Ol rn 10 337.92 2.33E+0 2 21 .29 9.67E+OO 5 .86E+OO 2.23E+0 2 2.21E+O l F 11 351 .55 8.43E+0 2 32.85 2.24E+O l 5 .47E+OO 8.21E+0 2 3.33E+O l F 12 462.91 1.02E+0 2 15.71 l.02E+0 2 l.57E+O l F 13 510.42 3.39E+0 2 23.68 1.52E+0 2 8.101!:+00 1. 87E+02 2.SOE+O l F 14 582. 72 4 .11E+02 24 . 09 2.14E+O l 4.78E+OO 3.90E+0 2 2. 4 6E+Ol F 15 608.83 6.15E+0 2 28.56 2.18E+O l 4 . 83E+OO 5.93E+0 2 2.90E+O l F 16 661.22 3.74E+0 2 23.31 1.38E+O l 4.37E+OO 3.60E+0 2 2.37E+O l F 17 726.75 1.02E+0 2 14.29 1.02E+0 2 1.43E+O l F 18 76 7 .48 3.45E+O l 11.50 3.45E+O l l.lSE+O l F 19 794.12 4.82E+O l 11. 76 4.82E+O l l.18E+O l F 20 859.83 9.29E+0 l 14.48 9.29E+O l 1. 45E+01 F 21 910.67 3.55E+0 2 21. 90 l.35E+O l 3.68E+OO 3.42E+0 2 2.22E+O l F 22 932.46 6.66E+O l 13.25 6.66E+O l 1.32E+O l M 23 963.98 5.57E+O l 11.42 5.57E+O l 1.14E+O l m 24 968.41 1. 72E+02 16.86 1. 72E+02 1.69E+O l F 25 1119. 68 1. 70E+02 17 .11 l. 09E+Ol 3.21E+OO 1. 59E+02 1. 74E+Ol F 26 1376.66 6.25E+O l 10.29 6.25E+O l 1. 03E+Ol F 27 1460.03 3.95E+0 3 63.68 5.78E+O l 4.59E+OO 3.89E+0 3 6.39E+O l F 28 1508 . 39 l.59E+O l 5.26 1. 59E+Ol 5.26E+OO F 29 1728.74 2.45E+O l 6.25 2.45E+O l 6.25E+OO F 30 1763. 90 1. 22E+02 12 . 09 1. 38E+Ol 2.34E+OO 1.08E+0 2 1.23E+O l M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE IDENTIFICATION REPO RT Nuclide library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Llbrary\ENVUB.NLB IDENTIFIED NUCLIDES

9/15/2017 5:34:40PM Page4 of8 Analysis Report for CDR-NRC-7 SOIL Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty 1460.81 10.67 5.90E+00 l.90E-01 K-40 0.90

2.75E-03 CS-137 0.97 661.65

85.12 3.87E-02 0.57 727.17 11. 80 8.44E-02 1. 20E-02 BI-212

785.42 2.00 1620.56 2. 7 5 PB-212 0.82 77. 11

17.50 2.06E-01 l.86E-02 87.20 6.30 89.80 1. 75 238.63

44.60 1. 39E-Ol 6.16E-03 300.09 3.41 2.26E-01 3.13E-02

6.24E-03 BI-21 4 0.64 609.31

4 6. 30 1. llE-01 768.36

5.04 6.94E-02 2.32E-02 806.17 1.23 934.06 3.21 1120.29 15.10 1.41E-01 1.58E-02 1155 .19 1. 69 1238.11 5.94 1280.96 1.47 1377.67 4 .11 1401.50 1.39 1407.98 2 .48 1509.19

2.19 1. 20E-01 3.98E-02 1661.28 1.15 1729.60

3.05 1.42E-01 3.65E-02 1764.49 15.80 1. 22E-01 1.44E-02 1847.44 2.12 PB-214 0 . 72 74.81

6.33 3.00E-01 5.09E-02 77.11

10.70 3 .36E-01 3.0SE- 02 87 .20 3.70 89.80 1.03 241. 98 7.49 295.21

19.20 1.31E-01 9.0lE-03 37.20 1. 40E-01 6 . 61E- 0 3 351.92

1.10 785.91 0.95 186.21 3.28 2.43E-01 3.91E-0 2 RA-226

AC-228 0.67 129.08 2.80 209.28 4.40 270. 23 3.60 1.63E-01 3.lSE-02

2.70E-0 2 327.64

3.20 8.68E-02 338. 32

11.40 1.22E-01 1. 2 4E-02 409.SJ, 2 .1-3 463.00 4.40 l.69E-01 2.65E-02

2.67E-02 794.70

4.60 1.09E-01 911. 60

27.70 1. 42E-01 9.73E-03 964.60

5.20 1.29E-01 2.65E-02 969.11 16.60 l .25E-01 1. 25E-02 1587.90 3. 7 1

9/15/2017 5:34:40PM Page 5 of8 Analysis Report for CDR-NRC-7 SOIL

= Energy fine found In the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPO RT Nuclide Nuclide Wtmean Wt mean Comments Name Id Activity Activity Conffdence (pCilgrams) Uncertainty K-40 0.906 5.90E+O O 1. 90E-01

/ CS-137 0.970 3.87E* 02 2.75E- 03 BI-212 0.573 8.44E- 02 1.20E- 02 PB-212 0.826 1. 40E-01 5.76E- 03 BI-214 0. 643 1.14E- 01 5.lSE- 03 PB-214 0 .729 1. 38E-01 5.23E- 03 RA-226 0.954 2.43E- 01 3.91E- 02 AC-228 0.672 1. 31E-01 5.77E- 03

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

@ = nuclide contains energy llnes not used In Weighted Mean Activity Errors quoted at 1.000sigma

9/15/2017 5:34:40PM Page 6 of8 Analysis Report for CDR*NRC-7 SOIL UNIDENTIFIED PEAKS Peak Locate Performed on : 9/15/2017 5:34:31PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 50.30 2.34229 E-02 27.02 1\~

F 13 510.42 5.18751 E-02 13.40 .ifl 7,..C,'°j F 14 582.72 l.08335 E-01 6.30 11µ;,i>

F 20 859.83 2.58107 E-02 15.59 F

F 22 26 932.46 1376.66 l.84862 E-02 1.73669 E-02 19.90 16.46 Sum

]~

6,1,;~

M = First peak in a multiplet region

=

m Other peak in a multiplet region

=

F Fitted singlet Errors quoted at 1.000sigma

~~~

NUCL IDE MDA REPO RT Nudlde Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Library\ENVLIB.NLB Nuclide Energy Yield(%) Activity NuclideM DA LineMDA Name (pCVgrams) (pCVgrams) (pCVgrams)

(keV) 10.67 S.90E+O O l.14E-O l l.14E-0 1

+ K-40 1460.81 *

+ MN-54 834.83 99.97 -3.78E- 04 l.07E-0 2 1.07E-0 2

+ C0-60 1173.22 100.00 -8.66E- 03 l.22E-0 2 l.54E-0 2 1332.49 100.00 1. 06E-02 1.22E-0 2

+ ZN-65 1115 .52 50.75 2.90E-0 2 3.33E-0 2 3.33E-0 2

+ KR-85 513.99 0.43 7.3SE+O O 2.61E+O O 2.61E+O O

+ CD-109 88.03 3.72 1. llE+OO 5.30E-O l 5.30E-0 1

+ CS-134 604.70 97. 60 6.21E-0 2 l.24E-0 2 1. 43E-02 795.84 85.40 -2.29E- 03 l.24E-0 2 85.12 3.87E-0 2 7.31E-0 3 7.31E-0 3

+ CS-137 661.65 *

+ EU-154 123. 07 40.40 -2.66E- 03 2.97E-0 2 2.97E-0 2 722.30 20.00 2.59E-0 2 S.44E-0 2

9/15/2017 5:34:40PM Page 7 of8 Analysis Report for CDR-NRC-7 SOIL Nucllde Energy Yleld(%) Activity Nuclide MDA LlneMD A Name (pCVgrams) (pCl/grams) (pCVgrams)

(lreV)

EU-15 4 873.20 12.09 -5.03E -02 2.97E -02 8.77E -02 996.30 10.34 -3.25E -02 1 .19E-0 1 1004 . 7 6 17 . 90 9.87E -03 6.92E -02 1274.5 1 34.40 -1 .65E-0 2 4.16E -02

+ EU-15 5 86.54 32.80 6.llE- 02 6.14E -02 6.14E -02 105.31 21.80 -2.56E -02 6. 2 1E-02

+ TL-20 8 72 .80 2.02 -1.07E +20 8.38E+ 18 8.35E+ 20 74.97 3.41 1. 10E+2 1 4.56E+ 20 84.90 1.51 2.14E+ 20 7.33E+ 20 277.36 6.31 2.84E+ 19 9.15E +l9 583.19 84.50 2.40E+ 19 8.38F.+ 18 763.13 1. 81 5.91E+ 20 3.52E+ 20 860.56 12.42 5.69E +l8 5.31E+ 19 1093- 90 0.40 -3.60E +20 1. 90E+21

+ BI-214 609.31

46.30 1. llE-01 1,52E -02 1.52E -02 768.36

5.04 6.94E -02 1. 28E-01 806.17 1.23 7.79E -02 7.BOE -01 934.06 3.21 8 . 64E-0 2 3 .69E- 01 1120.2 9

15.10 1. 41E-01 8.06E -02 1155.1 9 1. 69 3 . 79E-01 8.98E -01 1238. 11 5.94 1.92E -Ol 2.88E -01 1280.9 6 1. 47 3.65E -01 9.95E -01 1377.6 7 4 .11 1.93E -01 2.66E -01 1401.5 0 1.39 4.89E -01 7 .85E-0 1 1407.9 8 2.48 -2.02E -Ol 4.41E -Ol 1509.1 9

2.19 1. 20E-0 1 2.24E -01 1661. 28 1.15 5.14E -01 6.38E -01 1729.6 0

3.05 1 . 42E-0 1 1.53E -01 1764.4 9

15.80 1.22E -01 4.15E -02 1847.4 4 2.12 2.24E -01 3.21E -Ol

+ PB-214 74.81

6.33 3.00E -01 2.17E -02 2.44E -01 77.11

10.70 3.36E -01 1. 26E-0 1 87.20 3.70 8.53E -01 5.41E -01 89.80 1. 03 3.43E+OO 1.84E+OO 241.98 7.49 -2.0BE -01 1. 85E-01 295 . 21

19.20 1. 31E-01 2.69E -02 351. 92

37.20 1. 40E-01 2.17E -02 785.91 1.10 7.38E -01 1. OOE+OO

+ RA-22 3 81.07 15.00 -2.31E -02 7.54E -02 1. 52E-0 1 83.78 24.80 6.91E -02 8.lOE -02 94.90 11.30 S .59E-0 2 1.49E -01 122.31 1.19 -3.41E -01 l.02E+ OO 144.20 3 .26 1.16E -01 3.41E -01 154.1 9 5.59 -8.69E -02 1. 92E-OJ.

269.41 13.60 9.54E -02 7.54E -02 323.89 3.90 -1. 23E-01 2.48E -01 338.32 2.78 -1. 33E-O l 3.83E -Ol 444.94 1.27 -8.08E -02 7.0lE- 01

+ RA-22 6 186.21

3.28 2.43E -01 2.88E -01 2.88E -Ol

+ AC-22 8 129.08 2.80 3.31E -01 3.21E -02 4.20E -01 209.28 4.40 1.32E -01 2.37E -01

9/15/2017 5:34:40PM Page 8 of8 Analysis Report for CDR-NRC- 7 SOIL Nuclide Energy Yield(%) Activity Nucl/deMDA LineMDA Name (pCVgrams) (pCVgrams) (pCllgrams)

(keV}

270 . 23 3.60 1. 63E-01 3.21E-0 2 1.95E-O l AC-228

1. SOE-01 327.64

3.20 8.68E-0 2 338.32 1 1. 40 1.22E-O l 4.36E-0 2

4.21E-0 1 409.51 2.13 2.23E-O l 463.00 4.40 1.69E-O l 1. 25E-01 4.60 l.09E-0 1 1. 8 6E-01 794.70

3.21E-0 2 911. 60

27.70 1. 42E-01 5 .20 1.29E-0 1 l . 29E-01 964.60

4.29E-0 2 969.11

16.60 1 .25£-01 1587.90 3.71 4.SSE-0 1 2.56E-0 1

+ Th-230 12.30 8.43 O.OOE+OO 8.87E+O O 8.40E+l 0 67.60 0.37 -3.48E- Ol 8.87E+OO 168 . 10 0.07 l. 1 4E+ Ol 1.52E+O l

+ PA-234M 766.36 0.29 -1. 73E+OO 1. 46E+OO 3.69E+O O 1001.03 0.84 9.24E-O l l.46E+OO

+ TH-234 63.29 4.50 4.53E-0 1 6.84E-O l 9.14E-0 1 92.38 2.60 7 . 27E-01 6.90E-0 1 92 . 80 2.60 6 . 98E-01 6.84E-O l

+ AM-241 59.54 36.30 -3.0SE- 02 l.43E-O l 1. 43E-01

+ CM-243 99.55 14.30 4.14E-0 2 S .97E-02 l.OSE-0 1 103.76 23.00 -3 .21E-02 5 .9 7E-02 117.00 10.80 -7 .80E-02 1. 14E-01 228. 1 8 10.60 2.lOE-0 2 9.BlE-0 2 277 . 60 14.00 2.03E-0 2 7 .llE-02

+ = Nuclide identified during the nuclide Identification

.. = Energy line found In the spectrum

> = MDA value not calculated

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

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

9/16/201 / 7:34:12AM Page 1 ofB

__...3Apex-Gamma Analysis Report for CDR-NRC-8 SOIL GAMMA SPECTRUM ANALYSIS Sample Identification : COR-NRC-8 /

Sample Description : SOIL Sample Type : Silt Unit Sample Point Sample Size : 3.179E-+-03 grams Facility : Diaryland_NPP Sample Taken On : 9/15/2017 1:20:00PM /

Acquisition Started 9/16/2017 6:33:33A M" Procedure : Slit ./

Operator : Administrator Detector Name : DET01-ENV , /

Geometry : 1.5L Marinelli /

LiveTime : 3600.0 second!

RealTrme : 3624.9 seconds Dead Time : 0.69 %

Peak Locate Threshold : 3.00 Peak Locate Range {In channels) : 100-4096 Peak Area Range (in channels) : 100-409 6 Identification Energy Tolerance : 1.000 koV Energy Calibration Used Done On : 613/2014 Efficiency Calibration Used Done On : 6/3/2014 Efficiency Callbratlon Description : 1.5 Marinelli Sample Number : 3412 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/16/2017 7:34:03AM Peak Analysis From Channel : 100 PeakAnalysis To Channel : 4096

9/16/2017 7:34:12AM Page 2 of8 Analysis Report for CDR*NRC- 8 SOIL Energy ROI ROI Peak NetPeak Net Area Continuum FWHM Peak Centroid Area Uncertainty Counts (keV)

No. (keV) start end 74.56 141 - 193 149.98 2.81E+0 2 28.58 8.00E+0 2 1.33 M 1 2 76. 78 141 - 193 154.41 4.00E+0 2 33.58 7. 93E+02 1.33 m

86.85 141- 193 174.56 l.91E+0 2 25.25 7.72E+0 2 1. 36 m 3 92.47 141 - 193 185 . 81 2.27E+0 2 27.47 7.60E+0 2 1.38 m 4 366 - 380 371. 94 3.04E+0 2 30.40 1.02E+0 3 1. 64 F 5 185.51 209.05 415 - 424 419.04 1.11E+0 2 24.12 6.69E+0 2 1. 31 F 6 469 - 491 477.43 l. 2 8E+03 41. 50 5 .75E+02 1.50 M 7 238.24 469 - 491 483.82 2.91E+0 2 24.48 5 ,17E+02 1.50 m 8 241.43 536 - 559 540 . 65 7.95E+O l 18.02 3.70E+0 2 1.13 M 9 269.83 536 - 559 555.46 6.36E+ Ol 16.59 3.02E+0 2 1.14 m 10 277.24 585 - 610 590.69 4,76E+0 2 28.03 3.64E+0 2 1.47 M 11 294.85 585 - 610 600.32 7.47E+O l 15.93 3.40E+0 2 1.48 m 12 299.66 633 - 683 655 .86 8.lOE+O l 17.27 3. 2 7E+02 1.47 M 13 327.42 633 - 683 677.04 2.90E+0 2 23.04 2.99E+0 2 1. 48 m 14 338.00 697 - 710 704.08 8.4 1E+02 33. 7 1 4.02E+0 2 1. 66 F 15 351.52 814 - 824 819.30 4.70E+0 1 14.97 2.86E+0 2 1.35 F 16 409.11 920 - 935 925 . 80 8.83E+O l 16.19 3.60E+0 2 1. 46 F 17 462.34 1014 - 1032 1022.19 2.96E+0 2 22.8 7 3.47E+0 2 2.27 F 18 510.52 1161 - 1174 1166.70 4.41E+0 2 24.64 2.03E+0 2 1. 82 F 19 582.75 608.78 1212 - 122 6 1218 . 78 6.49E+0 2 28.96 2 .20E+02 1.81 F 20 661.16 1316 - 1333 1323.59 1.51E+0 3 40.96 2 .39E+02 1.80 F 21 1445 - 1462 1454.92 1.23E+0 2 15.65 1 .91E+02 2. 12 F 22 726 . 80 1712 - 172 8 1721. 02 9.23E+O l 14.10 1. 2 3E+02 2.67 F 23 859.80 910.60 1816 - 1834 1822.66 3.34E+0 2 21.46 1.98E+0 2 2.02 F 24 1922 - 1945 1929.43 9.25E+O l 12.93 1 .16E+02 2.02 M 25 963.96 968.42 1922 - 1945 1938.35 1.72E+0 2 16.29 1. 21E+02 2.02 m 26 2228 - 2247 2240.87 1. 88E+02 17 . 59 l.83E+ 02 2 . 17 F 27 1119.62 2749 - 2761 2754 . 86 4.45E+O l 10.12 5.34E+Ol 2.71 F 28 1376.51 2908 - 2935 2921. 84 4.07E+0 3 64 . 31 7.53E+0 1 2.96 F 29 1459.96 3234 - 3267 3241. 15 2.97E+O l 6.23 9.47E+OO 2.41 M 30 161 9.55 31 1629.92 3234 - 3267 3261. 90 2.49E+O l 6.07 1. 24E+Ol 2.41 m 3.70 F 32 1763.62 3519 - 3539 3529.43 1.63E+0 2 13.62 2.05E+O l 3690 - 3701 3695.09 2.24E+O l 5.46 7 .68E+ OO 1. 79 F 33 1846.41 3981 - 3994 3987.68 1.03E+O l 4.01 1. llE+O l 1. 1 6 F 34 1992.64 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBT RACT REPO RT Peak Analysis Performed on : 9/16/2017 7:34:03AM Env. Background File : C:\Canberra\Apex\Root\Oiaryland_ NPP\Data\0000003388.CNF

9/16/201 t 7:34:12AM Page 3 of8 Analysis Report for CDR-NRC-8 SOIL Peak Energy Original Orig.Are a Ambient Backgr. Subtracte d Subtracte d No. (keV) Area Uncertainty Backgrou nd Uncert. Area Uncert.

M 1 74.56 2.81E+0 2 28.58 7.82E+O l 9.57E+OO 2.03E+0 2 3.0lE+O l m 2 76. 78 4.00E+0 2 33.58 4.00E+O . 3.36E+O l m 3 86.85 1.91E+0 2 25.25 1.91E+0 2 2.53E+O l m 4 92.47 2 . 27E+02 27.47 5.07E+O l 8.63E+OO 1.76E+0 2 2.88E+O l F 5 185.51 3.04E+0 2 30.40 3.67E+O l 8.25E+OO 2.67E+0 2 3.15E+O l F 6 209.05 1.11E+0 2 24.12 l.11E+0 2 2.41E+O l M 7 238.24 1.28E+0 3 41.50 3.14E+O l 6.41E+OO 1. 25E+03 4.20E+O l rn 8 241.43 2.91E+0 2 24.48 2.91E+0 2 2.45E+O l M 9 269.83 7.95E+O l 18.02 7.95E+O l l.80E+O l m 10 277.24 6.36E+O l 16.59 6.36E+O l 1. 66E+Ol M 11 294.85 4.76E+0 2 28.03 1 .00E+Ol 5,91E+OO 4.66E+0 2 2.86E+O l m 12 299.66 7.47E+O l 15.93 7. 47E+Ol 1. 59E+Ol M 13 327.42 8.lOE+O l 17.27 8.lOE+O l 1.73E+O l m 14 338.00 2.90E+0 2 23.04 9.67E+OO 5.86E+OO 2.80E+0 2 2.38E+O l F 15 351.52 8.41E+0 2 33.71 2.24E+O l 5 . 47E+OO 8.19E+0 2 3.41E+O l F 16 409.11 4.70E+O l 14.97 4.70E+O l 1. SOE+Ol F 17 462.34 8.83E+O l 16.19 8.83E+O l l.62E+O l F 18 510.52 2.96E+0 2 22.87 l.52E+0 2 8.lOE+OO 1. 44E+02 2.43E+O l F 19 582.75 4.41E+0 2 24.64 2.14E+0 1 4.78E+OO 4.20E+0 2 2.51E+O l F 20 608.78 6.49E+0 2 28.96 2.18E+O l 4.83E+OO 6.27E+0 2 2.94E+O l F 21 661.16 1.51E+0 3 40.96 1. 38E+Ol 4.37E+OO l.50E+0 3 4.12E+O l F 22 726.80 1.23E+0 2 15.65 l.23E+0 2 1. 56E+Ol F 23 859.80 9.23E+O l 14. 10 9.23E+O l 1 .41E+Ol F 24 910. 60 3.34E+0 2 21. 46 1. 35E+01 3.68E+OO 3.20E+0 2 2.18E+O l M 25 963.96 9.25E+O l 12.93 9.25E+O l 1.29E+O l m 26 968.42 l.72E+0 2 16 .29 1. 72E+02 1. 63E+Ol F 27 1119.62 1. 88E+02 17.59 1. 09E+Ol 3.21E+OO 1.77E+0 2 1. 79E+Ol F 28 1376.51 4.45E+O l 10 .12 4.45E+O l l.OlE+O l F 29 1459.96 4.07E+0 3 64.31 5.78E+O l 4.59E+OO 4.01E+0 3 6.45E+O l M 30 1619 . 55 2.97E+O l 6.23 2 . 97E+Ol 6.23E+OO m 31 1629. 92 2.49E+O l 6.07 2.49E+0 1 6.07E+OO F 32 1763.62 1.63E+0 2 13. 62 1. 38E+Ol 2.34E+OO 1. 49E+02 1.38E+O l F 33 1846.41 2.24E+O l 5.46 2.24E+O l 5.46E+OO F 34 1992.64 1. 03E+Ol 4.01 l.03E+O l 4.0lE+OO M = First peak in a multiplet region

=

m Other peak in a multiplet region

=

F Fitted singlet Errors quoted at 1.000sigma

9/16/2017 7:34:12AM Page 4 of8 Analysis Report for CDR-NRC-8 SOIL NUCLI DE IDENTIFICATION REPOR T Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Library\ENVllB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertaint y K-40 0.89 1460.81

10.67 6.02E+OO 1. 92E-01 CS-137 0.96 661.65

85.12 1. 59E-01 6.13E-03 BI-212 0. 57 727.17

11.80 1. OOE-01 1.30E-02 785.42 2.00 1620.56 2 .75 PB-212 0.94 77.11

17.50 2.35E-01 2.13E-02 87.20

6.30 2.38E-01 3.25E-02 89.80 1. 75 238.63 44.60 1.48E-01 6.30E-03 300.09

3.41 1. 27E-01 2.73E-02 BI-214 0.50 609.31

46.30 1. 16E-01 6.31E-03 768.36 5.0 4 806.17 1.23 934.06 3.21 1120.29

15.10 1. 56E-0 1 1.61E-02 1155.19 1. 69 1238 .11 5. 94 1280.96 1.47 1377. 67 4 .11 1401. 50 1. 39 1407.9 8 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1.66E-01 1.63E-02 1847.44 2.12 0.94 74.81 6 .33 3.56E-01 5.43E-02 PB-214

77.11

10.70 3.85E-01 3.48E-02 87.20 3. 70 4.06E-01 5.54E-02 89.80 1.03 241. 98 7.49 2.07E-01 l.82E-02

9.24E-03 295.21

19.20 1. 40E-01 351.92 37.20 1. 37E-01 6.65E-03 785.91 1.10 186.21 3.28 4.04E-01 4.90E-02 RA-226 0.92

AC-228 0.73 129.08 2. 80 209.28

4.40 1.28E-01 2.81E-02 3.60 l.23E-Ol 2.79E-02 270.23

3.28E-02 327.64

3.20 l.53E-01 338.32

11.40 1.SlE-01 1.33E-02 409. 51 2.13 1. 49E-01 4.76E-02

2.69E-02 463.00

4.40 l.45E-01

9/16/201, 7:34:12AM Page S of8 Analysis Report for CDR-NRC-8 SOIL Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty AC-228 0 . 73 794.70 4.60 911.60

27.70 1.31E-0 1 9.37E-0 3 964.60

5.20 2 . l l E-01 2.98E- 02 969.11

16.60 l.23E-O l 1.20E-0 2 1587.90 3. 71

= Energy line found in the spedrum.

- =Manually added nuclide.

? = Manually edited nudlde.

@ = Energy Une not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence Index threshold "" 0.30 Errors quoted at 1.000slgma INTER FERE NCE CORRECTED REPO RT Nuclide Nuclide Wtmean Wt mean Commems Name fd Activity Activity Confidence (pCUgrams) Uncertainty K- 4 0 0.891 6.02E+OO 1.92E-0 1

/ CS-137 0.963 1. 5 9E-Ol 6.13E-0 3 BI-212 0.578 1. OOE-01 1.30E-0 2 PB-212 0.943 1 . 47E-01 5 . 8 2E-03 BT-214 0.502 1. 26E-01 S.53E-0 3 PB-214 0.942 1.46E-O l 5.0SE-0 3 RA-226 0.924 4.04E-O l 4.90E-0 2 AC-228 0.737 1. 37E-Ol 5.73E-0 3

? = nuclide is part of an undetennined solution X = nuclide rejected by the interference analysis

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

9/16/2017 7:34:12AM Page 6 of8 Analysis Report for CDR-NRC- 8 SOIL UNIDENTIFIED PEAKS Peak Locate Performed on : 9/16/2017 7:34:03AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS rA,J Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide

~~ ~

m 4 92.47 4.89595 E-02 16.34 m 10 277.24 1. 76578E- 02 26.10 Tol. C i,~)

F 18 510.52 4.00530 E-02 16.83 Sum 5.98 F

F 19 23 582.75 859.80 l.16657 E-01 2.56501 E-02 15.27 '11~

11,-0.

M F 28 30 1376.51 1619.55 1 .23710E -02 8.24303 E-03 22.71 20.98 \,~~

rn F

31 33 1629.92 1846.41 6.91759 E-03 6.22989 E-03 24.36 24.36 Sum Sum f<t~~

F 34 1992.64 2.86066 E-03 38.90 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Enors quoted at 1.000sigma

~

NUCL IDE MDA REPO RT Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\llbrary\ENVLIB.NLB Nuclide Energy Yleld(3/4J Activity NuclldeM DA UneMDA Name (pCUgramsJ (pCVgrams) (pCVgrams)

(keV) 10.67 6.02E+0 0 1. 04E-0l l.04E-0 1

+ K-40 1460.81 *

+ MN-54 834.83 99.97 6 .3 6E-0 3 1. 09E-02 1. 09E-02

+ CO-60 1173 .22 100.00 -9.16E- 05 1 .22E-02 l.54E-0 2 1332 .49 100 . 00 -1.0SE- 02 1.22E-0 2

+ ZN-65 1115.52 50. 75 6.66E-0 2 3. 2 4E-02 3.24E-0 2

+ KR-8 5 51 3 .99 0.43 6.41E+0 0 2.68E+0 0 2.68E+0 0

9/161201, 7:34:12AM Page7 of8 Analysis Report for CDR-NRC-8 SOIL Nuclide Energy Yleld(3/4) Activity NuclideM DA UneMDA Name (pCVgrams) (pCllr,rams) (pCVr,rams)

(bV)

+ CD-109 88.03 3.72 1.46E+O O 5.40E- 01 5.40E- Ol

+ CS-134 604.70 97.60 5.47E- 02 1. 28E-02 1.44E- 02 795.84 85.40 -3.95E -03 l.28E-0 2

+ CS-137 661.65

85.12 1.59E- 01 1.03E- 02 1. 03E-02

+ EU-154 123.07 40.40 7.94E- 04 3.07E- 02 3.07E- 02 722. 30 20.00 1. 56E-02 5.48E- 02 873.20 12.09 4.83E- 02 8.88E- 02 996.30 10.34 -3.45E -03 1.20E- Ol 1004.7 6 17.90 4.81E- 03 6.94E- 02 1274. 51 34 .40 9.76E- 03 4.03E- 02

+ EU-155 86.54 32.80 -7.72E -02 6.23E- 02 6.23E- 02 105.31 21.80 3.78E- 02 6.43E- 02

+ @ TL-208 72.80 2.02 1.00E+ 26 1.00E+ 26 l.OOE+ 26

@ 74.97 3.41 1.00E+ 26 l.OOE+ 26

@ 84.90 1.51 1.00E+ 26 1.00E+ 26

@ 277.36 6.31 1. OOE+26 1. OOE+26

@ 583.19 84.50 1.00E+ 26 1. OOE+26

@ 763.13 1.81 1.00E+ 26 l.OOE+ 26

@ 860.56 12.42 1.00E+ 26 l.OOE+ 26

@ 1093.* 90 0.40 l.OOE+ 26 1.00E+ 26

+ BI-214 609.31

46.30 1. 16E-Ol 1.63E- 02 1.63E- 02 768.36 5.04 1.20E- 01 2.lOE- 01 806.17 1.23 -2.21E+ OO 7.96E- Ol 934.06 3.21 5.77E- 02 3.72E- Ol 1120.2 9

15.10 1. 56E-Ol 7.66E- 02 1155.1 9 1. 69 -3.84E -01 8.96E- 01 1238.1 1 5 .94 2.81E- 01 2.91E- Ol 1280.9 6 1.47 3.50E- 01 9.46E- Ol 1377.6 7 4.11 4.27E- 01 2.92E- Ol 1401.5 0 1.39 4.0lE- 02 7 . 81E-01 1407.9 8 2.48 9.78E- 02 4.39E- Ol 1509.1 9 2.19 8.lBE- 02 4.36E- Ol 1661. 28 1.15 3.llE-0 1 6.34E- 01 1729.6 0 3.05 8.BOE- 02 2.SSE- 01 1764.4 9

15.80 1. 66E-01 3.84E- 02 1847.4 4 2.12 -4.45E -02 3.53E- Ol

+ PB-214 74.81

6.33 3.56E- 01 1.93E- 02 2.48E- 01 77.11

10.70 3.8SE- Ol 1.29E- 01 87.20

3.70 4.06E- Ol 2.81E- 01 89.80 1.03 4.78E+O O 1. 88E+OO 241.98

7.49 2.07E- Ol 7.71E- 02 295.21

19.20 1.40E- Ol 2.82E- 02 351.92

37.20 1. 37E-01 1.93E- 02 785.91 1.10 9.17E- Ol 9.93E- 01

+ RA-223 81.07 15 .00 -4.12E -02 8.17E- 02 1.57E- 01 83.78 24.80 -2.87E -01 8.34E- 02 94.90 11.30 5.30E- 02 1. 59E-01 122.31 1.19 6.89E- Ol 1. lOE+OO 144.20 3.26 2.02E- 02 3.66E- Ol 154.19 5.59 -9.31E -02 2.03E- 01

9/16/2017 7:34:12AM Page 8 of8 Analysis Report for COR-NRC-8 SOIL Nuclide Energy Yield(%) Activity NuclideMD A LlneMDA Name (pCVgrams) (pCUgrams) (pCUgrams)

(keV)

RA-223 269.41 13.60 9.39E-03 8.17E-02 8.17E-02 323.89 3.90 2.23E-03 2.67E-Ol 338 . 32 2 . 78 9.04E-02 3.98E-01 444.94 1.27 -2 .61E-01 7.66E-Ol

+ RA-226 186.21 3.28 4.04E-01 2.80E-Ol 2.80E-01

+ AC-228 129.08 2.80 -1. 93E-01 3.68E-02 4.32E-01 209.28

4.40 1.28E-Ol l.SlE-01 270.23

3.60 1. 23E-01 1. 42E-01 327.64

3.20 1. 53E-01 1. 64E-Ol 338.32

11. 40 1. SlE-01 4.63E-02 409.51

2.13 1.49E-Ol 2.82E-Ol 463. 00

4.40 1.45E-01 l.82E-01 794.70 4. 60 6.42E-02 2.42E-01 911. 60

27.70 1. 31E-01 3.68E-02 964.60

5.20 2.llE-01 1.21E-Ol 969 .11

16.60 1. 23E-01 3.86E-02 1587.90 3.71 1. 59E-Ol 2.46E-01

+ Th-230 12.30 8.43 O.OOE+OO 9.07E+OO 8.30E+10

67. 60 0.37 3.19E+OO 9.07E+OO 168.10 0.07 l.15E+OO l .55E+Ol

+ PA-234M 766.36 0.29 2.43E+OO 1. 49E+OO 3.63E+OO 1001.03 0.84 -l.89E-01 1. 49E+OO

+ TH-234 63.29 4.50 1.34E-Ol 7.17E-01 9.44E-01 92.38 2.60 2.31E-02 7 . 22E-01 92.80 2.60 5.63E-02 7.17E-Ol

+ AM-241 59.54 36. 30 -8.57E-02 l .47E-Ol 1. 47E-01

+ CM-243 99. 55 14.30 1.SlE-02 6.16E-02 1. 09E-01 103.76 23.00 -2.SlE-02 6.16E-02 117. 00 10.BO -1. 26E-02 l.17E-01 228.18 10.60 3.07E-02 1.02E-Ol 277.60 14.00 -2.21E-02 7.49E-02

+ = Nuclide identified during the nudide Identification

= Energy line found In the spectrum

> = MDA value not calculated

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

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

9/19/2017 10:06:47PM Page I of IO pex-Gamma Analysis Report for CDR-NRC-9 SOIL GAMMA SPECTRUM ANALYSIS Sample Identification : CDR-NRC-9 /

Sample Description :SOIL /

Sample Type : SiH Unit Sample Point Sample Size : 3.156E+03 grams /

Facllfty : Diaryland_NPP Sample Taken On : 9/15/2017 2:30:00PM /

Acquisition Started : 9/19/2017 4:03:54PM Procedure Operator

SIU /

Administrator Detector Name Geometry DET01-ENV 1.5L Marinelli

/j Live Time : 21600.0 seconds Real Time ; 21760.9 seconds Dead Time : 0.74%/

Peak Locate Threshold : 3.00 Peak locate Range On channels) : 100 -4098 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 6/312014 Efficiency Calibration Used Done On : 613/2014 Efficiency Calibratlon Description : 1.5 Marinelll Sample Number : 3421 PEAK ANALYSIS REPORT Peak Analysis Periormed on : 9/19/2017 10:06:38PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/19/2017 10:06:47PM PageloflO Analysis Report for CDR-NRC-9 SOIL ROI Peak NetPeak Net Area Continuum FWHM Peak Energy ROI (keV)

(keV) end Centroid Area Uncertainty Counts No. start 1 74.51 141 - 204 149.88 2.13E+03 85.38 9.09E+03 1. 36 M

141 - 204 154.55 1.94E+03 116.59 9.15E+03 1.37 m 2 76.85 84.09 141 - 204 169.03 4.54E+02 57.73 1.03E+04 1. 39 m 3 86.86 141- 204 174.57 l.61E+03 100.28 9.36E+03 1.40 m 4 89.54 141 - 204 179.95 1.47E+03 121.41 1.05E+04 1. 40 m 5 92.53 141 - 204 185.93 1. 83E+03 93.91 1. 05E+04 1. 41 m 6 141 - 204 199.49 2.83E+02 77. 30 9.61E+03 1. 43 m 7 99.31 128.73 250 - 266 258.34 5 .43E+02 84.96 1.84E+04 1.20 F 8 185.64 365 - 378 372.19 1.85E+03 99.96 1.43E+04 1. 53 F 9 208.86 414 - 422 418.65 8.50E+02 85.03 8.63E+03 1.27 F 10 238.26 470 - 493 477.48 1 .12E+04 132.04 7.40E+03 1.47 M 11 470 - 493 483.57 2 .11E+03 79.88 7 .08E+03 1. 47 m 12 241. 31 269 . 85 524 - 564 540.69 9.51E+02 80.62 7.14E+03 1. 73 M 13 277.00 524 - 564 55 4.98 5.20E+02 68.55 7.38E+03 1. 74 rn 14 294.85 585 - 610 590.71 3.54E+03 90.41 5. 76E+03 1.53 M 15 585 - 610 600. 62 7.41E+02 62.37 6.14E+03 1.54 m 16 299.81 1.44 M 17 327.52 652 - 683 656.07 4.53E+02 57.39 4.77E+03 337.92 652 - 683 676.87 2.33E+03 78.87 5.06E+03 1.45 m 18 351 . 52 694 - 711 704.07 6.48E+03 102 .11 8.51E+03 1. 54 F 19 808 - 825 819.00 3 .48E+02 58.59 7.73E+03 1. 39 F 20 408.96 462.57 922 - 932 926.25 4.97E+02 64.80 4.97E+03 1. 58 F 21 1012 - 1032 1021.76 2.14E+03 74.04 6.09E+03 2.19 F 22 510.30 1157 - 1172 1166.51 4.20E+03 78.63 3.22E+03 1. 77 F 23 582.65 1212 - 1226 1218.79 5.25E+03 85.24 2.89E+03 1.85 F 24 608.78 1279 - 1294 1284.72 2.70E+02 51 .13 2. 75E+03 2. 90 F 25 641.73 661.06 1312 - 1334 1323.38 8.82E+04 299.66 3.34E+03 1. 92 F 26 726.77 1448 - 1463 1454.85 8.72E+02 44.69 1.67E+03 2.02 F 27 754.73 1505 - 1601 1510.79 8.65E+Ol 29.03 1. 29E+03 1. 97 M 28 767.79 1505 - 1601 1536.92 5.90E+02 40.09 1.34E+03 1. 99 m 29 771.79 1505 - 1601 1544.93 1.20E+02 21. 44 1.32E+03 1. 99 rn 30 785.11 1505 - 1601 1571.59 4.09E+02 51.24 1. 26E+03 2.00 rn 31 794.40 1505 - 1601 1590.16 6.62E+02 43.31 1.22E+03 2 .01 rn 32 1713 - 1728 1721. 02 5 .39E+02 41.53 1. 4 1E+03 2.53 F 33 859.80 910.50 1813 - 1832 1822.46 3.18E+03 66.64 2.00E+03 2.21 F 34 933 . 62 1860 - 1875 1868.72 3.16E+02 40.14 1.53E+03 2.59 F 35 949.22 1887 - 1945 1899.92 2.38E+02 32.45 1. 45E+03 2.32 M 36 1887 - 1945 1929.66 7.17E+02 39 .23 1. 38E+03 2.33 rn 37 964 . 08 1887 - 1945 1938.05 2 . 00E+03 55.56 1.33E+03 2.33 rn 38 968 . 27 1000.28 1996 - 2009 2002.09 1.49E+02 33.86 1.37E+03 1. 91 F 39 1119. 48 2227 - 2249 2240.58 1.38E+03 52. 77 2.32E+03 2.56 F 40 2333 - 2356 2346. 57 3.16E+03 68.71 2.73E+03 2.50 F 41 1172.45 2468 - 2488 2476.70 5 .51E+02 43.67 2.52E+03 2.15 F 42 1237.49 2651 - 2678 2664.96 2.98E+03 61.58 1 . 43E+03 2.83 F 43 1331. 58 1376.69 2742 - 2825 2755.23 3.83E+02 30.04 5 .98E+02 2.82 M 44 2742 - 2825 2770.29 8.57E+Ol 19.79 5.78E+02 2 .83 rn 45 1384.22 1401.01 2742 - 2825 2803.88 l.22E+02 20.95 5.45E+02 2.84 rn 46 2.84 47 1407.29 2742 - 2825 2816.46 1.41E+02 21.92 5.32E+02 m

1459.86 2908 - 2935 2921. 63 4.14E+04 204.57 6.53E+02 2.82 F 48 2979 - 3033 2991. 52 1.13E+02 17. 73 3.07E+02 3.38 M 49 1494.79 2979 - 3033 3003.67 7.76E+01 16.00 2.88E+02 3.38 m 50 1500.86 1508.69 2979 - 3033 3019.33 1.99E+02 20.04 2.62E+02 3.39 m 51 3.26 F 52 1587.53 3168 - 3190 3177.08 2.90E+02 23.62 3.37E+02 3232 - 3269 3242.24 1 .44E+02 17.23 2.03E+02 3 . 00 M 53 1620.09

9/19/2017 10:06:47P M Pagc3 oflO Analysis Report for CDR-NRC -9 SOIL Peak Energy ROI ROI Peak NetPea k NetA,ea Continuum FWHM No. (keV) start end Centroid AIN Uncertainty Counts (keV) m 54 1629.6 8 3232 - 3269 3261.4 4 1.28E+ 02 16.44 l.84E+ 02 3.01 F 55 1728.5 3 3446 - 3468 3459.2 2 2.59E+ 02 19.42 1.46E+ 02 3.28 F 56 1763.4 7 3514 - 3540 3529.1 3 1.13E+ 03 35.99 l.85E+ 02 3.27 F 57 1788.4 4 3574 - 3586 3579.0 9 2.53E+ Ol 7.81 7.31E+ Ol 1.18 F 58 1846.4 6 3685 - 3703 3695.2 0 1.54E+ 02 16.45 1.28E+ 02 3.26 M = First peak in a multiplet region m = Other peak In a multiplet region F = F'rtted singlet Errors quoted at 1.000slgma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/19/2017 10:06:38PM Env. Background FIie : C:\Canberta\Apex\Root\Diaryland_NPP\Data\0000003420.CNF Peak Energy Original Orig. Area Ambien t Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Backgro und Uncert. Area Uncert.

M 1 74.51 2.13E+ 03 85.38 1.84E+ 02 2.40E+ Ol l.95E+ 03 8.87E+ Ol m 2 76. 85 1.94E+ 03 116.59 1.94E+ 03 l.17E+ 02 m 3 84.09 4.54E+ 02 57.73 l .13E+0 2 1. 96E+Ol 3.41E+ 02 6.lOE+ Ol m 4 86.86 l.61E+ 03 100 .28 1.61E+ 03 l.OOE+ 02 rn 5 89.54 l.47E+ 03 121. 41 l.47E+ 03 1.21E+ 02 m 6 92.53 1. 83E+03 93.91 3.83E+ 02 2. 77E+Ol 1. 44E+03 9.79E+ Ol m 7 99.31 2.83E+ 02 77.30 2.83E+ 02 7.73E+ Ol F 8 128.73 5.43E+ 02 84.96 S .43E+0 2 F

8.50E+ Ol 9 185.64 1.85E+ 03 99.96 1.98E+ 02 5.08E+ 01 1.66E+ 03 l.12E+ 02 F 10 208.86 8.50E+ 02 85.03 8.50E+ 02 8.50E+ Ol M 11 238.26 1.12E+ 04 132.04 2.91E+ 02 4.48E+ Ol 1. 09E+04 1.39E+ 02 m 12 241. 31 2.11E+ 03 79.88 2. 11E+03 7.99E+ Ol M 13 269.85 9.51E+ 02 80.62 9.51E+ 02 8.06E+ Ol m 14 277.00 5 .20E+0 2 68.5 5 5.20E+ 02 6.86E+ Ol M 15 294.85 3.54E+ 03 90.41 3.54E+ 03 9.04E+ Ol m 16 299 .8 1 7. 4U:+02 62.37 7.41E+ 02 6.24E+ Ol M 17 327.52 -1.53E+ C2 57.39 4.53E+ 02 5.74E+ Ol m 18 337.92 2.33E+ 03 78.87 5.9SE+ Ol 3.00E+ Ol 2.27E+ 03 8.44E+ Ol F 19 351.52 6.48 E+03 102.11 9.74E+ Ol 3.12E+ Ol 6.38E+ 03 1.07E+ 02 F 20 408.96 3.48E+ 02 58.59 3.48E+ 02 F

5 . 86E+Ol 21 462.57 4.97E+ 02 64.80 4.97E+ 02 6.48E+ Ol F 22 510 . 30 2.14E+ 03 74.04 9.66E+ 02 5.02E+ Ol 1.17E+ 03 8.95E+ Ol F 23 582.65 4.20E+ 03 78.63 1.35E+ 02 3.lOE+ Ol 4.06E+ 03 8.45E+ Ol F 24 608.78 5.25E+ 03 85.24 1.49E+ 02 3.31E+ Ol 5.10E+ 03 9.15E+ Ol

9/19/2017 10:O6:47PM Page4 of IO Analysis Report for CDR-NRC. 9 SOIL Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted Peak Area Uncertainty Background Uncert. Area Uncert.

No. (keV) 2 . 70E+02 51.13 2.70E+0 2 5. llE+Ol F 25 641.73 8.82E+0 4 299.66 l.09E+0 2 2.71E+O l 8.81E+0 4 3.01E+0 2 F 26 661.06 8.72E+0 2 44.69 8.72E+0 2 4.47E+O l F 27 726.77 8.65E+O l 29 . 03 8 . 65E+Ol 2.90E+O l M 28 754.73 5.90E+0 2 40.09 5.90E+0 2 4.0lE+O l m 29 767.79 2.14E+O l l.20E+0 2 21.44 1.20E+0 2 m 30 771.79 5 .12E+Ol m 31 785.11 4.09E+0 2 51.24 4.09E+0 2 6.62E+0 2 43.31 6.62E+0 2 4.33E+O l m 32 794.40 5.39E+0 2 41.53 5.39E+0 2 4.15E+O l F 33 859 . 80 3.18E+0 3 66.64 7.09E+O l 2.13E+O l 3.11E+0 3 7.00E+O l F 34 910.50 3.16E+0 2 40.14 3.16E+0 2 4.0lE+O l F 35 933.62 2.38E+0 2 32.45 2.38E+0 2 3.24E+O l M 36 949.22 7.17E+0 2 39 .23 7.17E+0 2 3.92E+O l m 37 964.08 2.00E+0 3 55.56 2.00E+0 3 5.56E+O l m 38 968.27 1.49E+0 2 33.86 2.43E+O l l.SSE+O l 1.25E+0 2 3 .73E+Ol F 39 1000.28 l.38E+0 3 52.77 1.38E+0 3 5.28E+O l F 40 1119. 48 3.16E+0 3 68. 71 5.68E+O l 1.85E+O l 3.10E+0 3 7.12E+O l F 41 1172.45 5.51E+0 2 43.67 5. 51E+02 4.37E+O l F 42 1237.49 2.98E+0 3 61.58 4.0BE+O l 1. 68E+Ol 2.94E+0 3 6.38E+O l F 43 1331.58 3.83E+0 2 30.04 3.83E+0 2 3.00E+O l M 44 1376.69 8.57E+O l 19.79 8.57E+O l l.98E+O l m 45 1384.22 l.22E+0 2 20.95 1.22E+0 2 2.lOE+O l m 46 1401.01 1.41E+0 2 21.92 1. 41E+02 2.19E+O l m 47 1407.29 4.14E+0 4 204.57 3.19E+0 2 2.58E+O l 4.11E+0 4 2. 06E+02 F 48 1459.86 l.13E+0 2 17.73 1.13E+0 2 1.77E+O l M 49 1494.79 7.76E+O l 16.00 7.76E+O l 1. 60E+Ol m 50 1500.86 2.00£+0 1 m 51 1508.69 l.99E+0 2 20.04 l.99E+0 2 2.90E+0 2 23 .62 2.90E+0 2 2.36E+O l F 52 1587.53 l.44E+0 2 17.23 l.44E+0 2 1. 72E+Ol M 53 1620.09

1. 28E+02 16.44 1.28E+0 2 1.64E+O l rn 54 1629. 68 1728.53 2.59E+0 2 19.42 2.59E+0 2 1. 94E+Ol F 55 l.13E+0 3 35.99 5.03E+O l 1.15E+O l l.08E+0 3 3.78E+O l F 56 1763.47 1788.44 2.53E+O l 7 . 81 2.53E+O l 7.81E+O O F 57 1.54E+0 2 16. 45 1.54E+0 2 1.65E+O l F 58 1846.46

=

M First peak in a multiplet region

=

m Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCL IDE IDENTIFICATION REPO RT Nuclide Library Used : C:\Canberr a\Apex\Roo t\Diaryland _NPP\Ubra ry\ENVllB.N LB IDENTIFIED NUCLIDES

9/19/2017 10:06:47PM PageS of 10 Analysis Report for CDR-NRC-9 SOIL Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty K-40 0.86 1460 . 81

10.67 l.03E+ Ol 2.91E -01 CO-60 0.89 1173.2 2 100.00 7 .16E-0 2

2.37E -03 1332.4 9

100.00 7.44E -02 2.49E -03 CS-13 7 0. 94 661. 65

85.12 1.57E+ 00 4.29E -02 BI-212 0. 97 727.17

11.80 l.19E- 01 6.83E -03 785.42

2 .00 3.49E -0l 4.46E -02 1620. 56

2.75 l.49E- 01 l.82E- 02 PB-212 0 .98 77 .11 17.50 1.91E -01

1.32E -02 87.20

6.3 0 3.38E -01 2.39E -02 89.80

1. 75 1. 05E+00 9.33E -02 238.63

44. 60 2.17E -01 6.31E -03 300.09

3. 41 2.llE- 01 1.85E -02 BI-214 0 . 66 609.31

46.30 l.58E -0l 5.24E -03 768.36

5 .04 1. 97E-01 1.42E -02 806.17 1.23 934.06

3.21 1.91E -01 2.46E -02 1120.2 9

15.10 2.04E -01 9.l0E- 03 1155.1 9 1. 69 1238 .11

5. 94 2.23E -01 1.85E -02 1280.9 6 1.47 1377 .67

4 .11 2.41E -0l 1. 99E-02 1401.5 0

1.39 2.29E -01 3.98E -02 1407.9 8

2.48 1. 49E-01 2.35E -02 1509.1 9

2.19 2.48E -01 2.58E -02 1661. 28 1.15 1729. 60 3.05 1764.4 9 15. 80 1847.4 4 2.12 2.18E -01 2.47E -02 PB-21 4 0 .97 74.81 6.33 5.75E -0l 3.25E -02 77 .11

10.70 3.13E -0l 2.16E -02 87.20

3.70 5. 76E-01 4.06E -02 89.80

1.03 1. 78E+0 0 1.59E -01 241.98

7.49 2.51E -01 1. lSE-02 295.21

19.20 1. 78E-0 l 6.31E -03 351.92

37.20 1. S0E-01 5.33E -03 785.91

1.10 6.35E -01 8.l0E- 02 RA-22 6 0 .94 186.21 3.28 4.21E -0l AC-22 8

3.0BE -02 0 .52 129.08

2.80 l.68E- 01 2.66E -02 209.2B

4.40 1.65E -01 1. ?lE-02 270.23

3.60 2.46E -01 2.17E -02 327.64

3.20 l.43E- 01 1.85E -02 338. 1?.

11.40 2.0SE -01 9.l0E- 03 409.51

2.13 l.85E -0l 3.15E -02 463.00

4.40 1.37E -01 1.82E -02 794.70

4.60 2.48E -01 1. 72E-02 911. 60 27.70 964.60

5.20 2.75E -01 l.61E- 02 969 .11

16.60 2.41E -01 8.47E -03 1587.9 0

3.71 2.20E -01 l.88E- 02 PA-234M 0. 48 766.36 0.29 1001. 03

0.84 3.06E -01 9.13E -02

9/19/2017 1D:06:47PM Page 6 of 10 Analysis Report for CDR-NRC-9 SOIL

= Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@=Energ y line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPO RT Nuclide Nuclide Wt mean Wtmean Comments Name Id Activity Activity Confidence (pCVgrams) Uncertainty 0 . 865 1. 0 3E+0 l 2 . 91E- 0l

J K-40 CO-60

/ CS-137 0 .894 0.946

7. 2 9E-02

1. 5 7E+00

1. 72E-0 3 4 . 29E- 02 BI-212 0 . 974 1. 26E- 01 6 . 33E- 0 3 PB-21 2 0. 982 1 .97E-0l 5.3 2E-03 BI-214 0. 662 1. S0E- 01 3 . 89E- 03 PB-214 0 . 974 1. 8 8E-0l 3. 7 5E-0 3 RA-2 2 6 0 . 94 8 4.21E-0 1 3 . 0BE-0 2 AC-228 0 . 528 2 . 1 4E- 01 4 . 48E- 03 PA-234M 0. 48 8 3 .06E-0l 9. 13E-02

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

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

9119/2017 10:06:47PM Page 7 oflO Analysis Report for CDR-NRC-9 SOIL UNIDENTIFIED PEAKS Peak Locate Perfonned on : 9/19/2017 10:06:38PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide m 3 84.09 1. 57785E -02 17 .89 ~'I,.~

m 6 92.53 6.6874 3E-02 6.78 ~'}~ q )iv\~

m rn F

14 22 7 99.31 277.00 510.30 l.30809 E-02 2.4062 8E-02 5.4339 9£-02 27.36 13.19 7.62 Tol.

Tol.

Sutyi~ 4 i:frr}A~-!l

~~G F 23 582.65 l.88106 E-Ol 2 .08 "} '1,)

~~~

F 25 641.7 3 1.2487 2E-02 18.96 M 28 754.73 4.0061 1E-03 33.55 rn 30 771. 79 5.5542 1E-03 17.87 ~t1'tu g F

F 33 34 859.80 910.50 2.4951 4E-02

1. 43784E -01 7.71 2.25 s~~

'1.,~

M 36 949.22 l.10234 E-02 13.63 S-Esc ~

rn 45 1384.2 2 3.9680 3E-03 ~ZJ 23.08

()\ i;r'}

M m

49 50 1494.7 9 1500.8 6 5.2239 0£-03 3.5940 4E-03

15. 71 sum e~ t..:1--~

rn 54 20.61 Sum t{J'Z..-vt F 55 1629.6 8 1728.5 3 5.9097 7E-03 l.19886 E-02

12. 88 Sum ~ -1.l~

7. 50 Sum F 56 1763.4 7 4.9965 2E-02

(>'iv~

3.50 Sum F 57 1788.4 4 l.17059 E-03 30.91

__./'

M = First peak In a multlplet region

=

m Other peak in a multiplet region

=

F Fitted singlet

~~x Em>t'S quoted at 1.000sigma NUC LIDE MDA REPO RT Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Llbrary\ENVLIB.NLB

9/19/2017 10:06:47PM Page 8 oflO Analysis Report for CDR-NRC-9 SOIL Nuclide Energy Yield('1/4) Activity NuclldeMD A LlneMDA Name (pCVgrams) (pCVgrams) (pCVgrams)

(keV)

+ K-40 1460.81

10.67 1.03E+0l 5.22E-02 5.22E-02

+ 834.83 99.97 9.63E-03 5.58E-03 5.58E-03

/ MN-54 100.00 7.16E-02 6.91E-03 8.16E-03

+ CO-60 1173.22

1332.49 100.00 7.44E-02 6.91E-03

1 . 65E-02

+ ZN-65 1115.52 50.75 5 .75E-02 l.65E-02

+ KR-85 513.99 0.43 5 .92E+0D 1.61E+00 1.61E+00

+ CD-109 88.03 3.72 1.56E+00 3.04E-01 3.04E-01

+ CS-134 604.70 97. 60 7.81E-02 6.48E-03 7.78E-03 795.84 85.40 6.73E-04 6.48E-03

+ j CS-137 661.65

85.12 l.57E+00 6.92E-03 6.92E-03

+ j EU-154 123.07 40.40 -9.78E-04 1. 84E-02 1.84E-02 722. 30 20.00 5.23E-02 2.77E-02 873.20 12.09 -1.17E-03 4.69E-02 996.30 10.34 6.70E-02 6.17E-02 1004.76 17.90 3.63E-02 3.62E-02 1274.51 34.40 2.32E-02 2.12E-02

+ EU-155 86.54 32.80 -1. 03E-0l 3.53E-02 3.53E-02 105.31 21.80 7.68E-03 3.82E-02

+ @ TL-208 72.80 2.02 1.00E+26 1. 00E+26 1. 00E+26

@ 74.97 3.41 1.00E+26 1.00E+26

@ 84.90 1.51 1.00E+26 1.00E+26

@ 277.36 6.31 1. O0E+26 1. 00E+26

@ 583.19 84.50 1. 00E+26 1.00E+26

@ 763.13 1. 81 1. 00E+26 1. 00E+26

@ 860.56 12.42 1.00E+26 1. 00E+26

@ 1093.90 0.40 1. 00E+26 1.00E+26 609.31 46.30 1.58E-0l l.0lE-02 1.0lE-02

+ BI-214

768.36 5.04 1. 97E-0l 5.78E-02

4 .2 2E-01 806.17 1.23 8.57E-02 3.21 1.91E-0l 1. 37E-01 934.06

4 . 65E-02 1120.29

15.10 2.04E-01 1155.19 1.69 -1. 4 7E-0l 4. 63E-01 1238 .11 5.94 2.23E-0l 1.28E-01

4.87E-01 1280.96 1. 47 3.83E-01 1377.67

4 .11 2.41E-01 7.33E-02

1. 39 2.29E-01 2.09E-01 1401.50

1407.98

2.48 1. 49E-0l l.16E-01 2.19 2.48E-01 9.76E-02 1509.19

1661.28 1.15 2.09E-01 2.68E-0l 1729.60 3.05 1.38E-0l l.14E-01 1764.49 15.80 2.18E-0l 3.50E-02 2.12 2.18E-01 1. 0lE-01 1847.44

1. 58E-02 1. 3SE-01

+ PB-214 74.81

6.33 5 .75E-01 77 .11 10.70 3.13E-0l 7.22E-02

l.62E-01 87.20

3.70 5.76E-01 1.03 1.78E+00 5.81E-01 89.80

4.70E-02 241.98

7.49 2.SlE-01 19.20 l.78E-0l 1. 79E-02 295.21

l.58E-02 351.92

37.20 1. 80E-0l

9/19/2017 10:06:47PM Page 9 of 10 Analysis Report for CDR-NRC-9 SOIL Nuclide Energy Yleld("/4) Activity NuclideMDA LlneMDA Name (pCUgrams) (pCl/grams) (pCVgrams)

(lreV)

PB-214 785.91

1.10 6.35E- Ol 1.58E- 02 2.61E- Ol

+ RA-223 81.07 15.00 6.SOE- 02 5.86E- 02 1. 08E-01 83.78 24.80 -4.78E -01 5.86E- 02 94.90 11.30 -2.97E -02 1.12E- 01 122.31 1.19 3 . 22E-01 8.08E- 01 144.20 3.26 2.76E- 01 2.72E- Ol 154.19 5.59 4.76E- 02 1. 53E-01 269.41 13 . 60 S.31E- 02 6.26E- 02 323.89 3.90 -6.44E -02 2.13E- 01 338.32 2.78 3.21E- 02 3.14E- 01 444.94 1. 27 -7.30E -03 7.02E- Ol

+ RA-226 186.21

3.28 4.21E- 01 1 . 72E-01 1. 72E-01

+ AC-228 129. 08 2 .80

l.68E-O l 2.07E- 02 2.46E- 01 209.28

4.40 1.65E- Ol 8.72E- 02 270.23

3.60 2.46E- Ol 1.02E- 01 327.64

3.20 1. 43E-01 l.03E-0 1 338.32

11. 40 2.0SE- 01 3.lSE- 02 409.51

2.13 1.85E- Ol 2.79E- 01 463.00

4.40 1. 37E-01 9.95E- 02 794.70

4.60 2.48E- Ol 6.18E- 02 911.60 27.70 2.16E- Ol 2.84E- 02 964.60

5.20 2.75E- 01 6.71E- 02 969.11

16.60 2.41E- 01 2.07E- 02 1587.9 0

3. 71 2.20E- 01 9.23E- 02

+ Th-230 12.30 8.43 O.OOE+OO 5.02E+O O l.39E+ l0 67.60 0.37 -4.46E+ OO 5.02E+O O 168.10 0 .07 5.38E+O O 9.41E+O O

+ PA-234M 766.36 0.29 3.35E+O O 5.19E- Ol l.90E+O O 1001.0 3

0.84 3.06E- Ol 5.19E- Ol

+ TH-234 63.29 4.50 -3.SlE -01 4.45E- Ol S.80E- 01 92.38 2. 60 9.84E- 01 4.48E- 01

92. 80 2.60 1.22E+O O 4.45E- 01

+ / AM-241 59.54 36.30 -9.SOE -02 8.14E- 02 8.14E- 0 2

+ CM-213 99.55 14.30 2.19E- 02 3.66E- 02 6.33E- 02 103.76 23.00 -2.47E -04 3.66E- 02 117.00 10.80 1. lBE-02 7.04E- 02 228.18 10.60 6.SSE- 03 6.40E- 02 277.60 14.00 -1. 89E-02 4.64E- 02

+ = Nuclide identified during the nuclide Identification

= Energy line found In the spectrum

> = MDA value not c:c1Jculated

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

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

9/19/2017 10:06:47PM Page 10 of 10 Analysis Report for CDR-NRC-9 SOIL

9/12/2t,,.- 8:00:07AM Page 1 of6 ex-Gamma Analysis Report for SUMP AREA # 1 9-9-17 GAMMA SPECTRUM ANALYSIS Sample Identification : SUMP AREA# 1 Sampl e Descri ption

9-9-1 7 /

Sample Type : 500 ml MarineUi

Unit Sample Point Sample Size

9.449E+02 grams

./

Facility : Daifyland_NPP Sample Taken On : 9/9/2017 1:43:00PM Acquisition Started : 9/12/2017 6:59:32AM Procedure : 500ml Marinem Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli /

Live Time : 3600.0 secon ds/

Real Time : 3623.4 seconds Dead nme : 0.65 %/

Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100-4 096 Peak Area Range (In channels) : 100-4 096 Identification Energy Tolerance : 1.000k eV Energy CaHbration Used Done On : 7/812014 Efficiency Calibration Used Done On : 7/8/20 14 Efficiency Calbration Description Sample Number : 3344 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/12/20'i7 7:59:58AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/12/2017 6:00:07AM Page 2 of6 Analysis Report for SUMP AREA # 1 9-9-17 NetP eak NetA rea Continuum FWHM Peale Energy ROI ROI Peale Area Uncertainty Counts (keV}

(keV} start end Centroid No.

4.41E +03 129. 67 1.25E +04 2.89 F 1 59.4 8 112 - 126 119. 52 2.43 246. 48 6,31E +02 116. 68 1. 56E+ 04 F 2 122. 98 239 - 253 1.10 292. 14 1.84 E+02 72.0 8 5.89E +03 F 3 145. 81 290 - 295 2.75 1324 .30 1. 47E+ 05 385. 75 2.01E +03 F 4 661. 99 1314 - 1333 3.09 2347 .92 7.21 E+03 87.0 9 4.00E +02 F 5 1173 .88 2337 - 2358 2.22 2551 .57 6.24E +Ol 12.2 7 1.11 E+02 F 6 1275 . 71 2543 - 2557 3.16 2666 .65 6.17E +03 79.0 5 7.77E +Ol F 7 1333 .26 2655 - 2677 3.15 2923 .55 6.87E +02 27.1 8 4.46E +Ol F 8 1461 . 72 *2913 - 2933 M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/12/2017 7:59:SSAM 364.CNF Env. Background File : C:\Canberra\Apex\Root\Oalryland_NP?\Data\0000001 Amb ient Backgr. Subtracted Subtracted Peak Energy Original Orig. Area Uncert.

Background Uncert. Area (keV} Area Uncertainty No.

4.41E +03 1.30 E+02 F 1 -59.4 8 4.41 E+03 129 . 67 1.17 E+02 116. 68 6.31E +02 F 2 122 . 98 6.31E +02 7.21 E+O l 72.0 8 l.84E +02 F 3 145. 81 1.84 E+02 3.86 E+02 385. 75 6.61E +Ol 1.27 E+O l l.47E +05 F 4 661. 99 1.47 E+05 8.75 E+O l 87.0 9 4.55E +Ol 8.62E +OO 7.16E +03 F 5 1173 .88 7.21 E+03 l.23E +Ol 12.2 7 6.24E +Ol F 6 1275 .71 6.24E +Ol 7.90 E+O l 79.0 5 6.17E +03 F 7 1333 .26 6.17 E+03 2.72 E+O l 27.1 8 6.87E +02 F 8 1461 . 72 6.87E +02 M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 1.OOOsigma

9/12/2 01' 8:00:07AM Page 3 of6 Analysls Report for SUMP AREA# 1 9-9-17 NUC LID E IDENTIFICATION REP OR T Nuclide library Used : C:\Canberra\Apex\Root\Oairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUC UDE S Nuclide Id Energy Yletdr./4) Activity Activity Name Confidence (keV) (uCVgrams) Uncertainty K-40 0.86 1460 .75 10.67 CO-6 0

7.93E -06 3.83E -07 0.92 1173 .22

100.0 0 7.30E -06 1. 97E-0 7 1332 .49

100.0 0 7.03E -06 2.0lE -07 CS-1 37 0.98 661. 65 85.12 CE-1 41

l.0SE -04 2.SSE -06 0.97 145.4 4

48 . 40 7.42E -08 AM-241 0.99 2.91E -08 59.54

36.30 5.77E -06 2.57E -07

= Energy Une found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used fer Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index th1"8&hold = 0.30 El'T0f'S quoted at 1.000sigma INT ERF ERE NCE CO RRE CTE D REP OR T Nuclide Nuclide Wtme an Wt mean Cor11ments Name Id Activ ity ActM ty Confidence (uCi/grams) Unce rtaint y K-40 0.860 7.93E -06 3.83E -07

.JI, CO-60 0.921 7.16E -06

.,,14 CS-1 37 l .41E- 07 0.982 l.OSE -04 2.BS E-06 CE-1 41 0.978 7.42E -08 AM-241 2. 91E-0 8 0 .999 5.77E -06 2.57E -07

9/12/2017 8:00:07AM Page 4 of6 Analysis Report for SUMP AREA # 1 9-9-17

? = 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 1.000sigma

9/12/2017 8:00:07AM Page S of6 Analysis Report for SUMP AREA# 1 g.g..17 UNID ENTI FIED PEAKS Peak Locate Perfonn ed on : 9/12/2017 7:59:58AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak No. Energy (keV) Peak Sae(C P~ Uncertamw Type Nuclide F 2 122.9 8 1.752 37E-O l 18.50 Tol. EU-1 54"' {u,-_"l..>(}

F 6 1275. 71 1.733 98E-0 2 19.65 ({ tJq M = Fir&t peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nudide Library Used : C:\Canberra\Apex\Root\Oalryland_NPP\Library\HOTLAB.NLB Nuclide Energy Y,e/d(3/4) Activity Nuc/ideMDA UneM DA Name (uCVgrams) (uCVgrams)

(keV) (uCl/grams)

+ K-40 1460 . 75 10.67

7.93E -06 5.14E -07 S.14E -07

+ AR-41 1293 . 64 99.16 2.12E +03 S . 69E+0 3 5.69E +03

+ CO-60 1173. 22

100.0 C 7.30E -06 6.81E - 08 1. 38E-0 7 1332. 49

100.0 0 7.03E -06 6.81E -08

+ KR-85 513.9 9 0.43 3.49E -05 5.29E -05 5.29E -0S

+ Y-88 898.0 4 93.70 l.17E -07 5.29E -08 1.68E -07 1836. 06 99.20 -2.23 E-08 5. 2 9E-08

+ NB-94 702.6 3 100.0 0 6.99E -08 l.l l E-07 1.llE -07 071.1 0 100.0 0 -l. 3 8E-07 l.45E -07

+ I-131 284.3 0 6 . 06 -1. 66E-0 6 3. 36E-0 7 3 .87E- 06 364.4 8 81.20 -1. 68E-0 7 3,36E -07 636. 97 7.27 -1.14 E-0 6 3. 2 7E-0 6

+ CS-13 4 604 . 70 97.60 8.86E -08 1. 4 7E-07 1. 85E-0 7 795 .84 85.40 -1.03 E-08 1.47E -07

+ CS-13 7 661 . 65 85 . 12

1.0SE-04 2.04E -07 2 . 04E-0 7

9/12/2017 8:00:07AM Page 6 of6 Analysis Report for SUMP AREA# 1 g..g..17 Yield(%) Activity NuclldeMDA Line IIDA Nuclide Energy (uCVgrams) (uCVgrams) (uCVgrams)

Name (keV) 80.12 1.36 6.08E -07 l.24E - 0 6 1. 21E-0 5

+ CE-14 4 133 . 51 11.09 1.20E -07 1.24E -06 121. 78 28.40 6.02E -07 2 . 75E-0 7 4.88E -07

+ EU-15 2 244 . 69 7.49 -1. 55E-0 7 2.26E -06 14.44 -3 . 38E-0 7 1.19E -06 964.0 0 1408 . 00 20.74 -l.45 E-07 2.75E - 07 123.0 7 40.40 2.57E -07 2.6 7E-07 3.43E -07

+ EU-15 4 247.9 4 6 . 60 -4.37 E-06 2.73E -06 723.3 0 19.70 4.77E -08 ?,77E -07 873.2 0 11.50 -5.02 E-07 1. 27E-0 6 1004. 76 17.90 2.86E -07 8.96E -07 35.50 2.17E -07 2.67E -07 1274. 51 86 . 54 32.80 -1 .84E- 07 4.56E -07 4.56E -07

+ EU-15 5 21.80 -l. 40E-0 7 6. 2 7E-07 105 . 31 609.3 1 46.30 2.llE -07 3.88E -07 3.88E -07

+ BI-21 4 15.10 -2 . 65E-0 7 l.04E -06 1120 . 29 5.94 6.0lE -07 l. 7 0E-06 1238 .11 1377 . 67 4 .11 -4 . 88E-0 8 1. 45E-0 6 1407. 98 2.48 -1.21 E-06 2.30E -06 2.19 -7 . 17E-0 7 2.41E -06 1509. 19 15.80 3 . 72E-0 7 4.32E -07 1764. 49 77 .11 10.70 1. 20E-0 6 5.64E -07 1.61E -06

+ PB-21 4 295 . 21 19.20 2.14E -07 9.76E -07 351.9 2 37.20 5.68E -09 5 .64E- 07 89.95 22 .00 6 . 3SE-0 6 3.19E -06 5 .24E- 06

+ PA-22 8 93.35 35.00 1.91E -06 3.19E -06 105.0 0 16.30 -2.36 E-06 6.66E -06 129 . 22 2.97 9.96E -06 3.69E -05 338.3 2 5.30 2.57E -05 3.0SE -05 463 . 00 13.80 1 . lSE-0 5 l.79E -05 911. 23 16.70 2.21E -06 7.64E -06 36.30 5 . 77E-0 6 8.22E -07 8.22E -07

+ AM-24 1 59.54

103.7 6 23.00 1.53E -07 5.97E -07 5.97E -07

+ CM-24 3 228.1 8 10.60 2. 1 9E-07 l.58E -06 277.6 0 14.00 2 . 23E-0 8 l.32E -06

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

I. 9/12/2017 9:02:19AM Page 1 of6

~pex-Gamma Analysis Report for SUMP AREA# 2 9-9-17 GAMMA SPECTRUM ANALYSIS Sample Identification : SUMPAREA#2 Sample Description : 9-9-17 ./

Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 8.825E+02 grams Facility : Dairyland_NPP Sample Taken On : 9/9/2017 1:48:00PM Acquisition Started : 9/12/2017 8:D1:36AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli /

Live lime : 3600.0 seconds Real lime : 3631.8 seconJ Dead llme . 0.88%/

Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 718/2014 Efficiency Calibration Used Done On : 7/812014 Efficiency Calibration Description Sample Number : 3345 PEAK ANALYSIS REPORT Peak Analy-sis Perfonned on : 9/12/2017 9:02:10AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/12/2017 9:02:19AM Page 2 of6 Analysis Report for SUMPAREA#2 9-9-17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM (keV) start end Centroid Area Uncertainty Counts (keV)

No.

F 1 59.22 112 - 125 119.00 1. 43E+03 135.85 1.83E+04 2.54 F 2 186.45 365 - 377 373.40 4.83E+02 109.72 2.29E+04 1. 20 F 3 662.01 1315 - 1333 1324.34 2.62E+05 514.29 2.49E+03 2.75 F 4 1173.93 2339 - 2358 2348.02 2 .61E+03 52.83 l.73E+02 3.10 F 5 1333.29 2657 - 2677 2666.71 2.41E+03 49.91 5.89E+Ol 3. 09 F 6 1461. 66 2912 - 2933 2923.43 5.35E+02 23.56 l.93E+Ol 3.17 M = First peak In a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/12/2017 9:02:10AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peale Energy Original Ori9. Area Ambient Backgr. Subtracted Subtracted (keV} Area Uncertainty Background Uncert. Area Uncert.

No.

F 1 59 .22 1. 43E+03 135.85 1 .43E+03 1. 36E+02 F 2 186.45 4.83E+02 109.72 4.83E+02 l.10E+02 F 3 662.01 2.62E+05 514.29 6.61E+Ol 1.27E+Ol 2.62E+05 5.14E+02 F 4 1173.93 2.61E+03 52.83 4.55E+Ol 8.62E+OO 2.57E+03 5.35E+Ol F 5 1333.29 2.41E+03 49.91 2.41E+03 4. 99E+Ol F 6 1461.66 5.35E+02 23.56 5.35E+0 2 2.36E+01 M =First peak in a multiplet region m =Other peak in a multiplet region F =Fitted singlet Errors quoted at 1.000sigma

9/12/2017 9:02:19AM Page 3 of6 Analysis Report for SUMP AREA# 2 9-9-17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{%) Activity Activity Name Confidence (keV) (uCilgrams) Uncertainty K-40 0.87 1460. 75

10.67 6.61E-06 3.44E-07 C0-60 0 .91 1173. 22

100.00 2 .BOE-06 8.91E-08 1332.49

100.00 2.94E-06 9.68E-08 CS-137 0 .97 661.65

85.12 2.00E-04 5.43E-06 RA-226 0 .99 186.21

3.28 3 ,23E-06 7.40E-07 AM-241 0.98 59.54

36.30 2.03E-06 2.05E-07

= Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nucllde.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuc/lde Wtmean wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCUgrams)

K-40 0. 8 7 6 6 . 61E- 06 3. 4 4E-0 7

.?, CO-GO 0 . 912 2 . 8 6E- 0 6 6.SSE- 08

~

CS-137 0 . 979 2 .00E-04 5 . 43E-06 RA-226 0.991 3.23E- 06 7. 40E-0 7 AM-241 0.984 2,0 3E-0 6 2 .0 SE- 07

9/12/2017 9:02:19AM Page4of6 Analysis Report for SUMP AREA# 2 9-9-17

? = nuclide is part of an undetennined solution X = nuclide rejected by the interference analysis

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

9/12/2017 9:02:19AM Page 5 of6 Analysis Report for SUMP AREA# 2 9-9-17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/12/2017 9:02:10AM Peak Locate From Channel : 100 Peak Locoto To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified.

M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Ubrary Used : C:\Canberra\Apex\Root\Oairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity Nuc/ideMDA LineMDA Name (keV) (uCUgrams) (uCUgrams) (uCVgrams)

+

-41 K-40 0-60 1460.75 1293.64 1173.22 1332.49 10.67 99.16 100.00 100.00 6.61E-06

-l.24E+03 2.80E-06 2.94E-06 3.80E-07 6.34E+03 6.16E-08 3.80E-07 6.34E+03 9.91E-08 6 . 16E-08

+ KR-85 513.99 0.43 6.67E-05 7.22E-05 7.22E-05

+ Y-88 898.04 93.70 1. 03E-07 4.17E-08 l.18E-07 1836.06 99.20 -1. 99E-08 4.17E-08

+ NB-94 702.63 100.00

4 .14E-08 8.6BE-08 8.6BE-08 871.10 100.00 -7.62E-08 l.02E-07

+ I-131 284.30 6.06 4.21E-06 4.63E-07 5.28E-06 364.48 81.20 -2.23E-07 4 .63E-07 636.97 7.?. 7 -4.67E-06 4.08E-06

+ CS-134 604. 70 97.60 6.38E-08 1. 07E-07 2.32E-07 795.84 85.40 6.99E-09 1. 07E-07

+ /cs-137 661.65

85.12 2.00E-04 2.35E-07 2.3!5E-07

+ CE-144 80.12 1.36 1. 34E-05 l.67E-06 1.64E-05 133.51 11.09 1.04E-06 1. 67E-06

+ EU-152 121. 78 28.40 5.85E-07 2.51E-07 6.SOE-07

9/12/2017 9:02:19AM Page 6 of6 Analysis Report for SUMPAREA#2 9-9-17 Nuclide Energy Yield(%) Actlvlt.y Nuc/ldeMDA LineMDA Name (uCi/grams) (uCUgrams) (uCVgrams)

(keV)

EU-152 244.69 7 .49 -4.67E-07 2.SlE-07 3.06E-06 964.00 14.44 -1. 88E-07 8.17E-07 1408.00 20.74 -4.46E-08 2.51E-07

+ EU-154 123.07 40.40 1. 42E-07 2.17E-07 4.57E-07 247.94 6.60 -2.00E-06 3.73E-06 723. 30 19.70 2.21E-07 4.62E-07 873.20 11.50 5.70E-07 8.97E-07 1004.76 17.90 -1.80E-07 6.33E-07 1274.51 35.50 2.66E-07 2.17E-07

+ EU-155 86.54 32.80 3.55E-07 6.17E-07 6.17E-07 105.31 21. 80 4.07E-07 8.48E-07

+ BI-214 609.31 46.30 1.42E-OB 3.67E-07 4.86E-07 1120. 29 15.10 -2.23E-07 7.61E-07 1238.11 5.94 8.09E-07 1. 36E-06 1377.67 4.11 l.95E-07 1. 2BE-06 1407.98 2.48 -3. 72E-07 2.lOE-06 1509.19 2.19 7.91E-07 2.0SE-06 1764.49 15.80 4.42E-07 3.67E-07

+ PB-214 77 .11 10.70 1.SSE-07 7.73E-07 2.17E-06 295.21 19.20 -1. 48E-07 1. 33E-06 351 . 92 37.20 4.48E-07 7.73E-07

+ PA-228 89.95 22.00 2.49E-06 4.40E-06 7.24E-06 93.35 35.00 -2.97E-07 4.40E-06 105.00 16.30 -1.78E-06 9.26E-06 129.22 2.97 9.18E-06 5.09E-05 338.32 5.30 2.86E-05 4.30E-05 463.00 13.80 2.92E-05 2.59E-05 911. 23 16. 70 2.96E-06 5.75E-06

+

/ AM-241 CM-243 59.54 103.76

36.30 23.00 2.03E-06

-7 .68E-07

1. 05E-06 8 . 03E-07 l.OSE-06 8.03E-07 228.18 10. 60 -3.78E-07 2.17E-06 277.60 14.00 -8.85E-07 1.78E-06

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum MDA value not calculated

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

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

~

FSS RELEASE RECORD - REVISION 2 SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION LACROSSESOLUTIONS ATTACHMENT 8 GEL LABORATORIES ANALYTICAL REPORTS 208

w*@...* lLaboratories LLC 0 PO 8°" W712 CMJ1estan SC 29-1:7 a member of The GEL Group INC 2~4sJ8av.1gelload Cha1ius1011.SC2!14Q7 P 84~.~M.8171 F 84'i766.1171!

gel.com January 22, 2018 Mr. Jason Q. Spaide LaCrosseSolutions S460 l State Hwy 35 Genoa, Wisconsin 54632 Re: LACBWR Site Restoration Project Work Order: 441560

Dear Mr. Spaide:

GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for the sample(s) we received on October 30, 2017. This original data report has been prepared and reviewed in accordance with GEL's standard operating procedures.

Our policy is to provide high quality, personalized analytical services to enable you to meet your analytical needs on time every time. We trust that you will find everything in order and to your satisfaction. If you have any questions, please do not hesitate to call me at (843) 556-8171, ext. 4453.

Sincerely,

~

Kaitlyn Stone for Edith Kent Project Manager Purchase Order: 672583 Enclosures 111111111111111 IIIUI IIU 111

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel

.com Certificate of Analy sis Report for ENRG070 LaCrosseSolutions, LLC (672583)

Client SDG: 441560 GEL Work Order: 441560 The Qualifiers in this report are defined as follows:

A quality control analyte recovery is outside of specified acceptance criteria

- Analyte is a Tracer compound

- Analyte is a surrogate compound U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOO.

Where the analytical method has been perfonned under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the Certificate of Analysis The designation ND, if present, appears in the result column when the analyte concentration is not detected above the limit as defined in the 'U' qualifier above.

This data report has been prepared and reviewed in accordance with GEL Laborato ries LLC standard operating procedures. Please direct any questions to your Project Manager

, Edith Kent.

Reviewed by

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843} 556-8171 -www.gel.com Certificate of Analysis Report Date: January 22, 2018 Company; LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-008-SB Project: ENRG07001 Sample ID: 441560001 Client ID: ENRG070 Matrix: Soil Collect Date: 15-SEP-17 09:05 Receive Date; 30-OCT-17 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U --0.00162 +/-0.00252 0.00585 0.010 pCi/g HAKB 01/17/18 0951 1731815 The following Prep Methods were petformed:

Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LYTI 10/31/17 0808 1731648 The following Analytical Methods were petfonned:

Method Description Analyst Comments ASTM C 1475-00 Modified Surrogateffracer Recovery Test Result Nominal Recovery% Acceptable Limits Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 97.7 (15%-125%)

Notes:

Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critica1 Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - {843) 556-8171 -www.gel.com Certificate of Analysis Report Date: January 22, 2018 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. fason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-009-SB Project: ENRG07001 Sample ID: 441560002 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-17 13:54 Receive Date: 30-OCT-17 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Np, Solid "Dry Weight Corrected" Neptuniwn-237 U -0.00137 +/-0.00298 0.00659 0.010 pCi/g HAKB 01/17/18 0951 173 1815

~~~-------~~-----~-- ________ _____________

The following Prep Methods were performed:

Method Description Analyst

,,..,.:.- Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LYTI 10/31/17 0808 1731648 The following Analytical Methods were performed:

Method Description Analyst Comments ASTM C 1475-00 Modified Surrogatetrracer Recovery Test _____

Result Nominal

_:__~:_:_:___ Recovery%, Acceptable Limits Americiwn-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 100 (15%-125%)

Notes:

Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit

GEL LABORATORIES -LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: January 22, 2018 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632 Contact Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-011-SB Project ENRG07001 Sample ID: 441560003 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-l 7 14:05 Receive Date: 30-OCT- l 7 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U 0.00181 +/-0.00451 0.008 0.010 pCi/g HAKB 01/17/18 0950 1731815 The following Prep Methods were performed:

Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021. LYTI l0/31/17 0808 1731648 The following Analytical Methods were performed:

Method Description Analyst Comments ASTM C 1475-00 Modified Surrogate/Tracer

- ~ ~ - - -Recovery - - ~ - -Test - - - - - - -- - - * - - - - -* - - --

Result Nominal Recovery% Acceptable Limits_

Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 94.4 (15%-125%)

Notes:

Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com Certificate of Analysis Report Date: January 22, 2018 Compan y: LaCrosseSolutions Address : S460 l State Hwy 35 Genoa, Wisconsin 54632

Contact:

~-fr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-012-SB ----

Project: ENRG07001 Sample ID: 441560004 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-17 14:08 Receive Date: 30-OCT-17 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U 0.00 +/-0.00357 0.00694 0.010 pCi/g HAKB 01/ 17/18 0950 1731 81 5 The following Prep Methods were performed:

Method Description Analyst Date Diy Soil Prep Time Prep Batch Dry Soil Prep GL-RAD-A-021 LYTI 10/31/17 0808 1731648 The following Analytical Methods were performed:

Method Description __ __ _ _ _ _ _ _ _ _ A=n=a_ly~s~t~C~o_m=m~e_n~ts~ - - - - - - - - -

ASTM C 1475-00 Modifaid --

Surrogateffracer Recovery Test _R

_e_s_u_lt_ _N_o_m_i_n a_l Recovery% Acceptable Limits Americium-243 Tracer Alphaspec Np, Solid "Diy Weight Corrected" 101 (15%-1253/4)

Notes:

Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit

GEL LABO RATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com Certificate of Analysis Report Date: Jariuary 22, 2018 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-014-SB Project: ENRG07001 Sample ID: 441560005 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-l 7 14: 18 Receive Date: 30-OCT- l 7 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method

- - - - - - - - - - - -- - -- - -- - ~ -- - - -- - - -- - - -

Rad Alpha Spec Analysis Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U -0.00203 +/-0.00347 0.00748 0.0IO pCi/g HAKB 01/17/ 18 0950 1731815 The following Prep Methods were performed:

Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 -;Lc-;Y""'T,..,.l------,-;;I0'""

/3c:-

l/"17

'; ;-------.0..

80;c-;;8,---01:::7,:-:

31;--;c 6-;-;

48c---- - - - - -- -

The following Analytical Methods were performed:

Method _ _ _ Description _______ _____ _ _ __ _ Analyst Comments ASTM C 1475-00 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable 1:-,imit~

Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 103 (15%-125%)

Notes:

Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: January 22, 2018 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: NRC #4 Project: ENRG07001 Sample ID: 441560006 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-17 13 :45 Receive Date: 30-OCT-17 Collector: Client Parameter Qualifier - - --

Result Uncertainty MDC RL Units PF OF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U 0.000544 +/-0.00512 0.00964 0.01 0 pCi/g HAKB 01/17/18 0950 1731815 The following Prep Methods were performed:

Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LYTI 10/31/17 0808 1731648 The following Analytical Methods were performed:

Method Description Analyst Comments ASTM C 1475-00 Modified Surrogateffra cer Recovery Test Americium-243 Tracer

- -- - -- ---*-- - - - -Result

-- - Nominal __ Rec~very% Acceptable Limits Alphaspec Np, Solid "Dry Weight Corrected" 94.7 (15%-125%)

Notes:

Counting Uncertainty is calculated at the 95% confidence level (1 .96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: January 22, 20I 8 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: Sump Area#l Project: ENRG07001 Sample ID: 441560007 Client ID: ENRG070 Matrix: Soil Collect Date: 09-SEP-1713:43 Receive Date: 30-OCT-17 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Np, Solid "Dry Weight Corrected

Neptunium-237 U 0.000475 +/-0.00384 0.00727 0.010 pCi/g HAKB 01/17/18 0950 1731815

_Th_e_fo_l_lo_w_i~ng~P_re_._p_M_eth_o_ds_w_er_e_.p~e_rfi_o_rm

_ ed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LYTI 10/31/17 0808 1731648 The following Analytical Methods were performed:

Method Description Analyst Comments ASTM C 1475-00 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% .. Acceptable Limits Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 102 (15%-125%)

Notes:

Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit

GEL LABO RATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 -www.gel.com QC Summary Reoort Date: January 22, 2018 LaCrosseSolutions Page 1 of 2 S4601 State Hwy 35 Genoa, Wisconsin

Contact:

Mr. Jason Q. Spaide Workorder: 441560 Parmname NOM Sample Qual ___Q~C0 _ _U:::.n=*==*ts=---'---RP=--=Dc..:'1/4

..:co__ ---"-'

RE =-=C::.'1/4

.:=--=o'------'R

=--=a=cn::,g:.::e:...._-'--'A=n'-"ls=--=t---=D~*=te~T=im=c_e Rad Alpha Spec Batch 1731815 QC1203952679 441559001 DUP Neptunium-237 U -0.00303 U 0.00432 pCi/g NIA N/AHAKB 01/17/18 09:53 Uncertainty +/-0.00419 +/-0.00468 QCJ203952680 LCS Neptunium-237 1.45 1.54 pCi/g 106 (75%-125%) 01/17/18 09:51 Uncertainty +/-0.0514 QC1203952678 MB Neptunium-237 u -0.0024 pCi/g 01/17/18 09:53 Uncertainty +/-0.00332 Notes:

Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

The Qualifiers in this report are defined as follows:

- Analyte is a Tracer compound

< Result is less than value reported

> Result is greater than value reported BD Results are either below the MDC or tracer recovery is low FA Failed analysis.

H Analytical holding time was exceeded J Value is estimated K Analyte present. Reported value may be biased high. Actual value is expected to be lower.

L Analyte present. Reported value may be biased low. Actual value is expected to be higher.

M M if above MDC and less than LLD M REMP Result> MDC/CL and< RDL NIA RPO or %Recovery limits do not apply.

NI See case narrative ND Analyte concentration is not detected above the detection limit NJ Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Q One or more quality control criteria have not been met. Refer to the applicable narrative or DER.

R Sample resuiis are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.

UI Gamma Spectroscopy--Uncertain identification UJ Gamma Spectroscopy--Uncertain identification

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 -www.gel.com QC Summary Workorder: 441560 Paie 2 of 2 Parmname NOM Sample Qual QC Units RPO% REC% Range Anlst Date Time UL Not considered detected. The associated number is the reported concentration, which may be inaccurate due to a low bias.

X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier y Other specific qualifiers were required to properly define the results. Consult case narrative.

I\

RPD of sample and duplicate evaluated using +/-RL. Concentrations are < 5X the RL. Qualifier Not Applicable for Radiochemistry h Preparation or preservation holding time was exceeded N/A indicates that spike recovery limits do not apply when sample concentration exceeds spike cone. by a factor of4 or more or %RPD not applicable.

A The Relative Percent Difference (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptance criteria when the sample is greater than five times (5X) the contract required detection limit (RL). In cases where either the sample or duplicate value is less than SX the RL, a control limit of+/- the RL is used to evaluate the DUP result.

Indicates that a Quality Control parameter was not within specifications.

For PS, PSD, and SDILT results, the values listed are the measured amounts, not final concentrations.

Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the QC Summary.

Radiochemistry Technical Case Narrativ e LaCrosseSolutions, LLC (ENRG )

SDG #: 441560 Product: Alphaspec Np, Solid Analytical Method: ASTM C 1475-00 Modified Analytical Procedure: GL-RAD-A-032 REV# 21 Analytical Batch: 1731815 Preparation Method; Dry Soil Prep PrCl)aration Procedure; GL-RAD-A-021 REV# 22 P[eJ>aration Batch: 1731648 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 441560001 LI-SUB-CDR-FSGS-008-SB 4415600 02 LI-SUB-CDR-FSGS-009-SB 441560003 LI-SUB-CDR-FSGS-011-SB 4415600 04 LI-SUB-CDR-FSGS-012-SB 441560005 LI-SUB-CDR-FSGS-014-SB 441560006 NRC#4 441560007 Sump Area #1 1203952678 Method Blank (MB) 1203952679 44155900l(L1-010-101-FS-GS-C06-SB) Sample Duplicate (DUP) 1203952680 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

Data Summary:

There are no exceptions, anomalies or deviations from the specified methods.

All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedur es fo~ initial calibration, continuing calibration, instrument controls and process controls where applicab le.

Product; Dry Weight Preparation Method: Dry Soil Prep Preparatjon Procedure: GL-RAD-A-021 REV# 22 Prwaration Batch; 1731648 The following samples were analyzed using the above methods and analytica l procedure(s).

GEL Sample ID# Client Sample Identification 441560001 LI-SUB-CDR-FSGS-008-SB 441560002 LI-SUB-CDR-FSGS-009-SB 441560003 LI-SUB-CDR-FSGS-011-SB 441560004 LI-SUB-CDR-FSGS-012-SB GEL Laboratortes u.c PO l!QI 30712 O.rles!On, SC 29417 2040 8MQe Read Chatleston, SC 29407 P843 5511171 F 843.781.1178 www.gel.com

441560005 LI-SUB-CDR-FSGS-014-SB 441560006 NRC#4 441560007 Sump Area#)

The samples in this SDG were analyzed on an "as received " basis.

Data Summary:

All sample data provided in this report met the acceptan ce criteria specified in the analytica l methods and procedur es for initial calibratio n, continui ng calibration, instrume nt controls and process controls where applicab le, with the followin g exceptio ns.

Miscellaneous Information Additional Comments These samples are re-logs. Data transferr ed from Batch# I 714238.

Certification Statement Where the analytical method has been perfonne d under NELAP certification, the analysis has met all of the requirem ents ofthe NELAC standard unless otherwis e noted in the analytica l case narrative.

GEL Laboratories UC POBaK30n2 Qlarlewlion,SC.29417 2040SavegeRoad Clw.rl891Dn,SC29407 PBQ.55U171 F84&7118.1178 www.get.com

Pagc: _ _1 or Project #: '-,K. 8:-J ~s, YE I

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, Samples requiring chemical pretem1ll on at proper pH?

Sampfe.l O'urld0Ja 1~ "1ld:_3.c!J.Q/r, U,Y11fdSi

~-- --- --- --!

If Yes, MEncorcs or Soil Kits p.rcsenl7 Yes_N o_ (lfyes. cnkl: toVOAPreezu)

Do VOA vials contain acid pR1Servati0117Ycs . No_N/A ., (U'-- , aelectNo) 7 Do any samples rcquilC Volatile VOA vials &cc ofhcndspace? Yes No_N /A Annly1il?

S11111ple ID's and conlainers ntfected:

U7a 11141 teas alr.eled:

8 Samples received within holding tim117 Sample ID's on COC maci:h ID'I on Sm,te D>'s 111111 -'lhim allecwl:

9 bottles?

Date 8t tlmo on COC IIID.lch dote & tilllC 10 on bolllea?

Number of containers n:cci~ match 11 number indicated on COC?

Am sample conlaillCll idcntiliab/11 as 12 om. vldcd?

COC fonn is properly sl1ned in 13 rel uislllldm:ce!Yed sections?

Conmml* (Use Ccindn1111llon Facm lfnffiled):

GL-CHL-SR-001 Rev 5

List of current GEL Certific1ttions as of 22 January 2018 State Certification Alaska UST-0110 Arkansas 88-0651 CLIA 42D0904046 California 2940 Colorado SC000I2 Connecticut PH-0169 Delaware SC00012 DoD ELAP/ ISO 17025 A2LA 2567.01 Florida NELAP E87156 Foreign Soils Pennit P330-15-00283,P330--15-00253 Georgia SC000l2 Georgia SDWA 967 Hawaii SC000I2 Idaho Chemistry SC00012 Idaho Radiochemistry SC00012 Illinois NELAP 200029 Indiana C-SC-01 Kansas NELAP E-10332 Kentucky SDWA 90129 Kentucky Wastewater 90129 Louisiana NELAP 03046 (Al33904)

Louisiana SDWA LA18001 I Maryland 270 Massachusetts M-SC0l2 Michigan 9976 Mississippi SC00012 Nebraska NE-OS-26-13 Nevada SC000122018-1 New Hampshire NELAP 205415 New Jersey NELAP SC002 New Mexico SC00012 New York NELAP 11501 North Carolina 233 North Carolina SDWA 45709 North Dakota R-158 Oklahoma 9904 Pennsylvania NELAP 68-00485 Puerto Rico SC00012 S.Carolina Radchem 10120002 South Carolina Chemistry l0120001 Tennessee TN02934 TexasNELAP T104704235- I 7-12 UtahNELAP SC000122017-25 Vermont VT87156 Virginia NELAP 460202 Washington C780 West Virginia 997404

c§'tijl ILaboratories LLc

!'C E-o* S0712 Charleston S(: Z.*4 *7 a member of The GEL Group INC :~4) St.*,'IIQtRo~d Cha~~Slon $C2ll417 P 8<1'., 5S6.8171 F 84'>.766.1 !7ll gel.com November 27, 2017 Mr. Jason Q. Spaide LaCrosseSolutions S4601 State Hwy 35 Genoa, Wisconsin 54632 Re: LACBWR Site Restoration Project Work Order: 436541

Dear Mr. Spaide:

GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for the sample(s) we received on October 30, 2017. This original data report has been prepared and reviewed in accordance with GEL's standard operating procedures.

Our policy is to provide high quality, personalized analytical services to enable you to meet your analytical needs on time every time. We trust that you will find everything in order and to your satisfaction. If you have any questions, please do not hesitate to call me at (843) 556-8171, ext. 4453.

Sincerely,

~

Kaitlyn Stone for Edith Kent Project Manager Purchase Order: 672583 Enclosures p~IHI IIIIIIWII II II 111111111111111

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report for ENRG070 LaCrosseSotutions, LLC (672583)

Client SDG: 436541 GEL Work Order: 436541 The Qualifiers in this report are defined as follows:

A quality control analyte recovery is outside of specified acceptance criteria

- Analyte is a Tracer compound

Analyte is a surrogate compound U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.

UI Gamma Spectroscopy --Uncertain identification Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the Certificate of Analysis.

The designation ND, ifpresent, appears in the result column when the analyte concentration is not detected above the limit as defined in the 'U' qualifier above.

This data report has been prepared and reviewed in accordance with GEL Laboratories LLC standard operating procedures. Please direct any questions to your Project Manager, Edith Kent.

Reviewed by Page 2 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company : LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-008-SB Project: ENRG07001 Sample ID: 436541001 Client ID: ENRG070 Matrix: Soil Collect Date: 15-SEP-17 09:05 Receive Date: 30-OCT- I 7 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americiwn-241 u 0.0241 +/-0.0289 0.0444 0.400 pCi/g BXA4 11/21/17 1420 1718468 Americiwn-243 0.0636 +/-0.0393 0.0173 0.400 pCi/g Curium-243/244 u -0.00195 +/-0.0134 0.0327 o.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptuniwn-237 u 0.00876 +/-0.0993 0.211 0.400 pCi/g BXA4 11/21/17 1036 1718469 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutoniwn-238 0.0137 +/-0.0181 0.0137 0.400 pCi/g BXA4 11/21/17 0927 1718470 3 Plutonium-239/240 u 0.000183 +/-0.0135 0.0301 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 u -1.46 +/-2.30 4.06 5.00 pCi/g BXA4 11/24/17 0825 1718471 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 u -1.72 +/-1.60 2.53 5.00 pCi/g TXJl 11/17/17 0846 1715764 5 Gamma, Cs137, Co60, Nb94, Eul52, Eu 154, Eul55 "Dry Weight Corrected" Cesium-137 0.804 +/-0,115 0.0481 1.00 pCi/g MXRl 11/16/17 1037 1714268 6 Cobalt-60 u 0.0245 +/-0.0399 0.088 pCi/g Europiwn-152 u -0.055 +/-0.0747 0.138 pCi/g Europiwn-154 u -0.0104 +/-0.0838 0.171 pCi/g Europium-155 u 0.0393 +/-0.0717 0.151 pCi/g Niobiwn-94 u -0.00984 +/-0.024 0.0438 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontiwn-90 u 0.248 +/-0.180 0.276 0.400 pCi/g KSDl 11/16/17 1612 1717213 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium u 1.27 +/-5, 11 8.88 10.0 pCi/g BXM4 11/16/17 0717 1715582 8 Liquid Scint Cl 4, Solid "As Received" Carbon-14 u 0.720 +/-2.36 4.01 5.00 pCi/g BXM4 11/13/17 1325 1715576 9 Liquid Scint Tc99, Solid "As Received" Technetlum-99 u -0.208 +/-0.744 1.29 2.00 pCi/g CXS7 11/14/17 0644 1715726 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" lron-55 u -2.22 +/-4.73 6.51 10.0 pCi/g TXJ l I 1/18/17 0422 1715698 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 3 of 45

GEL LABO RATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-008-SB Project: ENRG07001 Sample ID: 436541001 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Niclcel-63 U 2.73 +/-1.99 3.27 5.00 pCi/g nm 11/17/17 2218 1715705 12 The following Prep Methods were performed:

Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LYTl 10/31/17 0808 1714238

_T he following Analytical Methods were perfonned:

Method _______ Description --- - - - *- *-*

Analyst Comments DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni- I 6 DOE HASL 300, 4.5.2.3/Ga-OI-R 7 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified 8 EPA 906.0 Modified 9 EPA EERF C-0 I Modified lO DOE EML HASL-300, Tc-02-RC Modified II DOE RESL Fe-I , Modified 12 DOE RESL Ni-I, Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 81.7 (15%-125%)

Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 57.4 (15%-125%)

Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 104 (15%-125%)

Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 81.1 (15%-1253/4)

Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 81.1 (15%-125%)

Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected' 96.4 (25%-125%)

Strontium Carrier GFPC, Sr90, Solid "Dry Weight Correcred" 86.6 (25%-125%)

Techncttum-99m Tracer Liquid Scint Tc99, Solid*As Received" 88.9 (15%-125%)

lron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected 76.7 (15%-125%)

Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 77.4 (25%- 125%)

Notes:

Page4 of45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.c om Certificate of Analysis Report Date: November 27, 2017 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-008-SB Project: ENRG07001 Sample ID: 436541001 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Colwnn headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 5 of 45

GEL LABORATORIES LLC 2040 Savage Road Char1eston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR -FSGS-009-S B Project: ENRG07001 Sample ID: 436541002 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-17 13:54 Receive Date: 30-OCT-17 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americiwn-241 0.556 +/-0.101 0.026 0.400 pCi/g BXA4 11/21/17 1423 1718468 Arnericium-243 0.0435 +/-0.0276 0.0 I 94 0.400 pCi/g Curium-243/244 U 0.00931 +/-0.016 0.014 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptuniwn-237 U -0.0376 +/-0.0484 0.168 0.400 pCi/g BXA4 11/21/17 1036 1718469 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 0.107 +/-0.0432 0.0207 0.400 pCi/g BXA4 11/21/17 0927 1718470 3 Plutonium-239/240 0.118 +/-0.0456 0.0238 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U 2.53 +/-2.28 3.80 5.00 pCi/g BXA4 11/24/17 0856 1718471 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U -0.649 +/-1.18 2.02 S.00 pCi/g TXJ1 11/17/17 0847 1715764 5 Gamma, Cs 137, Co60, Nb94, Eul52, Eu 154, Eul55 "Dry Weight Corrected" Cesium-137 11.5 +/-0.274 0.0568 1.00 pCi/g MXRI 11/16/17 1037 1714268 6 Cobalt-60 0.695 +/-0.0863 0.0429 pCi/g Europium-152 U -0.00843 +/-0.109 0.1% pCi/g Europium-154 U 0.0273 +/-0.0674 0. 139 pCi/g Europium- 155 U 0.00639 +/-0.0949 0.177 pCi/g Niobium-94 U 0.00022 +/-0.0202 0.0382 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.178 +/-0.133 0.306 0.400 pCi/g KSDI 11/16/17 1412 1717213 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U 3.39 +/-5.26 8.95 10.0 pCi/g BXM4 I 1/16/17 0804 1715582 8 Liquid Scint Cl4, Solid "As Received" Carbon-14 U -0.851 +/-2.20 3.81 5.00 pCi/g BXM4 11/13/17 1408 1715576 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U -0.031 +/-0.809 1.40 2.00 pCi/g CXS7 11/14/17 0716 1715726 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" lron-55 U 3.82 +/-5.00 6.72 lO.O pCi/g TXJI 11/18/ 17 0509 1715698 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 6 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration

- - - -- - - - - - -- - - -- -- - - Project - - -- - - - - - - - - - - - - - - - - * *- - - -*- - -

Client Sample ID: LI-SUB-CDR-FSGS-009-SB Project: ENRG07001 Sample ID: 436541002 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC

- -- -- - - -- -"--- - - -- - -- -- ~- -- -- -* -RL -- - - - -

Units PF DF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 9.70 +/-2.31 3.33 5.00 pCi/g T}(J\ 11/ 18/17 1230 17 15705 12 The following Prep Methods were perfonned:

Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LYTI 10/31/17

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

0808 1714238 The following Analytical Methods were performed: ___ _ __ _ __ _ _ ___ __ _ _ _ _ *** - - -- *** _ ____ _ .._ _

Method __ ___ __D _e_s_c_ri~p_ti_o_n _ __ __ _ _ _ __ _ ___ Analyst Comments 1 DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu- 11-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-I 6 DOE HASL 300, 4.5.2.3/Ga-01-R 7 EPA 905.0 Modified/DOE RP501 Rev. I Modified 8 EPA 906.0 Modified 9 EPA EERF C-01 Modified 10 DOE EML HASL-300, Tc-02-RC Modified II DOE RESL Fe-I, Modified 12 DOE RESL Ni-I, Modified Surrogateffra cer Recovery Result Nominal Recovery% .. Ac~eptable Limits Americium-243 Tracer Alphaspec Isotopic Am24 l Am243, Cm243/244, 64.8 (15%-125%)

Solid 'Dry Weight Corrected' Curium-243/244 Tracer Alphaspec Isotopic Am24I Am243, Cm243/244, 93.8 (15%-125%)

Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected' 105 (15%-125%)

Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 86.8 (15%- 125%)

Corrected" Plutonium-242 Tracer Liquid Scint Pu24 l, Solid "Dry Weight Corrected" 86.8 (15%-125%)

Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected' l06 {25%-125%)

Strontium Carrier GFPC, Sr90, Solid 'Dry Weight Corrected' 91.7 (25%-125%)

Tecimecium-99m Tracer Liquid Scint Tc99, Solid ' As Received" 86.7 (15%-125%)

lron-59 Tracer Liquid Scint Fe55, Solid "Dry Weig.lit Corrected" 72.5 (15%-125%)

Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected' 76.6 (25%-125%)

Notes:

Page 7 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843} 556-8171 -www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632 Contact Mr. Jason Q. Spaide Project: LACBWR Site Restoration Proj ect Client Sample ID: LI-SUB-CDR-FSGS-009-SB Project: ENRG07001 Sample ID: 436541002 Client ID: ENRG070

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

Parameter

- -- - - - - - -Qualifier --------

Result Uncertainty MDC

-- ~ - - - - - - RL Units

- - - -- - -- PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 8 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gef.com Certificate of Analysis Report Date: November 2 7, 2017 Company: LaCrosseSolutions Address; S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-01 I-SB Project ENRG07001 Sample ID: 436541003 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-l 7 14:05 Receive Date: 30-OCT-17 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 0.0771 +/-0.033 0.022 0.400 pCi/g BXA4 11/21/17 1423 1718468 Americium-243 U 0.0107 +/-0.017 0.0235 0.400 pCi/g Curium-243/244 U 0.00093 +/-0.00972 0.0203 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U -0.0325 +/-0.0948 0.243 0.400 pCi/g BXA4 11/21/17 !036 1718469 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U 0.0079 +/-0.0156 0.0264 0.400 pCi/g BXA4 11/21/17 1838 1718470 3 Plutonium-239/240 U 0.0166 +/-0.0209 0.0322 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U -1.07 +/-1.97 3.48 5.00 pCi/g BXA4 11/24/17 0928 1718471 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U -0.254 +/-1.37 2.66 5.00 pCi/g TXJI 11/17/ 17 0847 1715764 5 Gamma, Cs 137, Co60, Nb94, Eu 152, Eu 154, Eu155 "Dry Weight Corrected" Cesium-137 3.77 +/-0.234 0.0693 1.00 pCi/g MXRI 11/16/17 1038 1714268 6 Cobalt-60 0.229 +/-0.0834 0.0443 pCi/g Europium-152 U 0.0119 +/-0.0827 0.160 pCi/g Europium-154 U 0.0426 +/-0.0915 0.224 pCi/g Europium-155 U 0.012 +/-0.0464 0.102 pCi/g Niobium-94 U 0.0159 +/-0.0193 0.0489 pC:i/e Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0787 +/-0.141 0.251 0.400 pCi/g KSDI 11/16117 1412 1717213 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U -0.287 +/-5.02 8.86 10.0 pCi/g BXM4 11/16/17 0851 1715582 8 Liquid Scint C14, Solid "As Received" Carbon-14 U 0.352 +/-2.31 3.95 5.00 pCi/g BXM4 11/13/17 1450 1715576 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U -0.102 +/-0.816 1.41 2.00 pCi/g CXS7 11/14/17 0748 1715726 10 Liquid ScintFe55, Solid "Dry Weight Corrected" Jron-55 U -0.95 +/-4.87 6.67 10.0 pCi/g TXJl 11/18/17 0556 1715698 II Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 9 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.geLcom Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mt*. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-011-SB Project: ENRG07001 Sample ID: 436541003 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units Rad Liquid Scintillation Analysis

--- - PF DF Analyst Date Time Batch Method Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 U 1.77 +/-2.04 3.44 5.00 pCi/g 11/18/17 T}{JI 1246 1715705 12

_T_h_e_fo_I_lo_w_i~ng~P_re~p_M_eth

_ o_ds_ w_er_e~p_e_ni_o_rm_ed_:_ _ __ _ _ _____ __ _ _ __ _ _ ____ __ _ __

Method Description Analyst Date Time Prep Batch Dry Soil Prep ....,0ry

,,---=-so~ilc-cPrep G,,,.

L....,-RA~D-

,-A.,....-...,.

02~1~ ---=-L=YT==I- -- ...,.1-=-o,=31,..,./1,..,,7,---- -....,-,

08""'0-=-

s ----,-,17=1...,.

42'"'3.,,.8- --- - * - - - -

The following Analytical Methods were performed:

- - --****- *-*H*- -* -- - - - -

Method Description Analyst Comments DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-I 6 DOE HASL 300, 4.5.2.3/Ga-0I-R 7 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified 8 EPA 906.0 Modified 9 EPA EERF C-0 I Modified 10 DOE EML HASL-300, Tc--02-RC Modified II DOE RESL Fe--1, Modified 12 DOE RESL Ni-I , Modified Surrogate/Tracer Recovery Test Result _No~na!.__ Re_c_ov_e_ry

- - -- -- * - -* - ~0_1/o__A__c_c_e~p_ta_b_Ie_ L

_ im

_1*_ts.

Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 87.5 (15%-125%)

Solid "Dry Weight Corrected' Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 84.5 (15%-125%)

Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 89.4 (15%-125%)

Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 93.3 (15%-125%)

Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 93.3 (15%-125%)

Nickel Carrier Gamma Ni59, Solid "Ory Weight Corrected" 101 (25%-125%)

Strontium Carrier GFPC, Sr90, Solid ' Dry Weight Corrected" 87.9 (25%-125%)

Technelium-99m Tracer Liquid Scint Tc99, Solid "As Received' 86.7 (15%-125%)

lron-59 Tracer Liquid Scint Fe55, Solid "Dry WeiBht Corrected" 76.3 (15%-125%)

Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 75 (25%-125%)

Notes:

Page 10 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S460 I State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-01 I-SB - - ---- - -- - -- - - -- --

Project: ENRG07001 Sample ID: 436541003 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (I.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 11 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR -FSGS-012-S B Project: ENRG07001 Sample ID: 436541004 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-17 14:08 Receive Date: 30-OCT-17 Collector: Client

- ---- -- - --Qualifier Parameter

- -- --Result - -- -- - ---- -- ------- ----- - -- ---- ----- ---- -

Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 0.113 +/-0.0404 0.0109 0.400 pCi/g BXA4 ll/21/17 1423 1718468 Americium-243 U 0.00295 +/-0.0164 0.03 14 0.400 pCi/g Curium-243/244 U -0.00159 +/-0.011 0.0267 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U -0.0197 +/-0.0427 0.131 Q.400 pCi/g BXA4 11/21/17 1036 1718469 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U 0.0175 +/-0.020 0.025 0.400 pCi/g BXA4 11/21/17 0927 1718470 3 Plutonium-239/240 U 0.0176 +/-0.0218 0.0316 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U -0.849 +/-2.14 3.75 5.00 pCi/g BXA4 11/24/17 1000 1718471 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U 0.717 +/-0.723 0.770 5.00 pCi/g TIU! 11/17/17 0848 1715764 5 Gamma, Cs 137, Co60, Nb94, Eu 152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 2.21 +/-0.168 0.0537 1.00 pCi/g MXRl 11/16/17 1038 1714268 6 Cobalt-60 Ul 0.00 +/-0.0734 0.0345 pCi/g Europium-152 U 0.0659 +/-0.0981 0.191 pCi/g Europium- 154 U -0.00813 +/-0.104 0.206 pCi/g Europium-155 U -0.0145 +/-0.0681 0.137 pCi/g Niobium-94 U -0.00759 +/-0.023 0.0428 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.163 +/-0.193 0.325 D.400 pCi/g KSDl 11/16/17 1412 1717213 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U 1.54 +/-5.18 8.98 10.0 pCi/g BXM4 11/16/17 0938 1715582 8 Liquid Scint C14, Solid "As Received" Carbon- 14 U 0.118 +/-2.33 3.99 5.00 pCi/g BXM4 11/13/17 1532 1715576 9 Liquid Scint Tc99, Solid"As Received" Technetium-99 U 0.308 +/-0.751 1.28 2.00 pCi/g CXS7 I 1/14/17 0820 1715726 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U -0.152 +/-4.83 6.55 I0.0 pCi/g TXJI 11/18/17 0644 1715698 II Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 12 of 45

GEL LABO RATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project

- - - -- - - - - -- - -- - - - - - - - -- --=--

Client Sample ID: LI-SUB-CDR-FSGS-012-SB Project: ENRG07001 Sample ID: 436541004 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF OF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 U 1.58 +/-1.93 3.25 5.00 pCi/g TIO! 11/17/17 2307 1715705 12 The following Prep Methods were perfonned:

Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LYTI 10/31/17 0808 1714238 The following Analytical Methods were perfonned:

Method ___D_e_s_c r_ip~t_io_n_ __ ______ __ _

I AnalystComm ents - -- -- - ~ - - - -

DOE EML HASL-300, Am-05-RC Modified 2 AS1M C 1475-00 Modified 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-I 6 DOE HASL 300, 4.5.2.3/Ga-0 1-R 7 EPA 905.0 Modified/DOE RP501 Rev. I Modified 8 EPA 906.0 Modified 9 EPA EERF C-01 Modified 10 DOE EML HASL-300, Tc-02-RC Modified II DOE RESL Fe-1, Modified 12 DOE RESL Ni-I, Modified Surrogate/fra cer Recovery Test Americium-243 Tracer

-*-*..*-** - *****- *-* -- - -- - --- ---Result

- -- -- * -Nominal

- - Recovery~_ __~cceptable Limits Alphaspec Isotopic Am241 Am243, Cm243/244, 80.4 (15%-125%)

Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 64.3 (15%-125%)

Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" IOI (15%-125%)

Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 89.6 (15%-125%)

Corrected" Plutonium-242 Tracer Liquid Scint Pu24I, Solid "Dry Weight Corrected" 89.6 (15%-125%)

Nickel Carrier Gamma Ni59, Solid "Dzy Weight Corrected' 106 (25%-125%)

Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 79 (25%-125%)

Technetium-99m Tu1ccr Liquid Scint Tc99, Solid *As Received" 89.1 (15%-125%)

Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 80.4 (15%-125%)

Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 77.4 (25%-125%)

Notes:

Page 13 of 45

GEL LA BORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR -FSGS-012-S B - * *- --

Project: ENRG07001 Sample ID: 436541004 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (I .96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 14 of 45

GEL LABORA TORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR -FSGS-014-S B Project: ENRG07001 Sample ID: 436541005 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-17 14:18 Receive Date: 30-OCT-17 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method

'------- --------C------ - - - - - - - - - --

Rad Alpha Spec Analysis .

Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 0.0796 +/-0.0363 0.0193 0.400 pCi/g BXA4 11/21/17 1423 1718468 Americium-243 U 0.0138 +/-0.0219 0.0303 0.400 pCi/g Curium-243/244 U -0.00192 +/-0.00848 0.0221 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U 0.0144 +/-0.0632 0.114 0.400 pCi/g BXA4 11/21/17 1036 1718469 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U 0.016 +/-0.0219 0.0298 0.400 pCi/g BXA4 11/21/17 0927 1718470 3 Plutonium-239/240 U 0.0111 +/-0.0196 0.0298 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U -0.93 +/-2.61 4.58 5.00 pCi/g BXA4 11/24/17 !031 1718471 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U -1.92 +/-1.40 2. 14 5.00 pCi/g TXJI 11/17/17 1044 1715764 5 Gamma, Cs 137, Co60, Nb94, Eu 152, Eu 154, Eul55 "Dry Weight Corrected" Cesium-137 2.77 +/-0.213 0.0799 1.00 pCi/g MXRI 11/16/17 1039 1714268 6 Cobalt-60 0.192 +/-0.076 0.0714 pCi/g Europium-152 U 0.0472 +/-0.0913 0.193 pCi/g Europium-154 U -0.0785 +/-0.103 0.174 pCi/g Europium-155 U -0.0268 +/-0.0783 0.153 pCi/g Niobium-94 U 0.00726 +/-0.0324 0.0674 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0795 +/-0. 159 0.286 0.400 pCi/g KSDI 11/16/17 1412 1717213 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U 2.67 +/-5.29 9.08 10.0 pCi/g BXM4 11/16/17 1025 1715582 8 Liquid Scint C14, Solid "As Received" Carbon-14 U 1.46 +/-2.31 3.90 5.00 pCi/g BXM4 11/ 13/ 17 1614 1715576 9 Liquid Scint Tc99, Solid "As Received" Tecimetium-99 U -0.783 +/-0.902 1.60 2.00 pCi/g CXS7 11/14/l 7 0853 1715726 lO Liquid Scint Fe55, Solid "Dry Weight Corrected" lron-55 U 0.527 +/-4.81 6.53 10.0 pCi/g TXJI 11/18/17 0731 1715698 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 15 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-014-SB Project: ENRG07001 Sample ID: 436541005 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF OF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid ScintNi63, Solid "Dry Weight Corrected" Nickel-63 U I. 95 +/-2.33 3.92 5.00 pCi/g TI(JI I 1/17/17 2323 1715705 12 The following Prep Methods were performed:

Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-02 1 LYTI 10/31/17 0808 1714238 The following Analytical Methods were performed:

Method - -=O--'e~sc~r~iP~t=io=n' - - - - - - - - - - - - - Analyst Comments .

DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOEEML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-I 6 DOE HASL 300, 4.5.2.3/Ga-0I-R 7 EPA 905.0 Modified/DOE RP501 Rev. I Modified 8 EPA 906.0 Modified 9 EPA EERF C-0 I Modified 10 DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-I, Modified 12 DOE RESL Ni-I, Modified Surrogateffracer Recovery Test Result Nominal _Re~very% Acceptable Limits Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 70.1 (15%-125%)

Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 65.2 (15%-125%)

Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 92.1 (15%-125%)

Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 72.7 (15%-125%)

Corrected" Plutonium-242 Tracer Liquid Scint Pu24 I, Solid "Dry Weight Corrected" 72.7 (15%-125%)

Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 111 (25%-125%)

Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 89.2 (25%-125%)

Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 84.4 (15%-125%)

lron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 77.4 (15%-125%)

Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 65.5 (25%-125%)

Notes:

Page 16 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-CDR-FSGS-014-SB Project: ENRG07001 Sample ID: 436541005 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 17 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company : LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: NRC #4 Project: ENRG07001 Sample ID: 436541006 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-17 13:45 Receive Date: 30-0CT- l 7 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF .DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 2.03 +/-0.169 0.0306 0.400 pCi/g BXA4 11/21/17 1423 1718468 Americium-243 0.137 +/-0.0539 0.0159 0.400 pCi/g Curium-243/244 0.0483 +/-0.0288 0.0281 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 . U -0.0226 +/-0.0556 0.166 0.400 pCi/g BXA4 11/21/1 7 1036 1718469 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 0.622 +/-0.106 0.0283 0.400 pCi/g BXA4 11/21/17 0927 1718470 3 P!utonium-239/240 0.6 I 5 +/-0.106 0.0325 0.400 pCi/g Liquid Scint Pu24l, Solid "Dry Weight Corrected" P!utonium-241 6.57 +/-2.57 4.09 5.00 pCi/g BXA4 11/24/17 1103 1718471 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U -0.195 +/-1.37 2.46 5.00 pCi/g TXJI l 1/17/17 1045 1715764 5 Gamma, Cs 137, Co60, Nb94, Eu 152, Eu 154, Eul55 "Dry Weight Corrected" Cesium-137 171 +/-0.867 0.135 1.00 pCi/g MXRl 11/16/17 1121 1714268 6 Cobalt-60 18.8 +/-0.346 0.0593 pCi/g Europium-152 U -0.0959 +/-0.283 0.512 pCi/g Europium-154 U 0.165 +/-0.176 0.218 pCi/g Europium-155 U 0.0694 +/-0213 0.380 pCi/g Niobium-94 U 0.0541 +/-0.0447 0.081 9 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 3.55 +/-0.340 0.201 0.400 pCi/g KSDl 11/21/17 0658 1717213 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U 2.09 +/-5.32 9.17 10.0 pCi/g BXM4 11/16/17 1112 1715582 Liquid Scint Cl 4, Solid "As Received" Carbon-14 U -0.44 +/-2.37 4 09 5.00 pCi/g BXM4 11 /1 3/1 7 1655 1715576 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 7.92 +/-1.13 1.58 2.00 pCi/g CXS7 l 1/15/17 0736 1715726 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" lron-55 U 2.45 +/-4.99 6.75 10.0 pCi/g TXJ l 11/18/17 0818 1715698 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 18 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolu tions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: NRC#4 Project: ENRG07001 Sample ID: 436541006 Client ID: ENRG070 Parameter Qualifier

- ------ - - -- - MDC Result Uncertainty

- --*- RL - - ---Units - ---PF DF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 50.4 +/-3.53 3.28 5.00 pCi/g DUI 11/18/17 1302 1715705 12 The following Prep Methods were performed:

Method Description Analyst Date Prep Batch Time Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LYTI 10/31/17 0808 1714238 The following Analytical Methods were performed:

Method _ _ D_e_sc_n~*P~t_io_n_ _ _ _ _ _ _ _ ___ _ _ _ _ - - - - - -~A=n=a=ly<-=s=t Comments - -- - -- -

DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475--00 Modified 3 DOE EML HASL-300, Pu-I I-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-1 6 DOE HASL 300, 4.5.2.3/Ga-0t-R 7 EPA 905.0 Modified/DOE RP501 Rev. I Modified 8 EPA 906.0 Modified 9 EPA EERF C-01 Modified 10 DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-I, Modified 12 DOE RESL Ni-I , Modified Surrogate/fra cer Recovc:ry Test Result Nominal Recove!}'% Acceptable Limits Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 9 1.4 ( 15%-125%)

Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am24I Am243, Cm243/244, 68.1 (15%-125%)

Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 82.5 ( 15%-125%)

Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 81.9 (15%-125%)

Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 81.9 (15%-125%)

Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 95.9 (25%-125%)

Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 77.7 (25%-125%)

Technetium-99m Tracer Liquid Scint Tc99, Solid *As Received" 93.5 (15%-1253/4) lron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 72.9 (15%- 125%)

Nickel Carrier Liquid Scint N i63, Solid "Dry Weight Corrected' 79.8 (25%-125%)

Notes:

Page 19 of 45

GEL LABO RATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address; S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: NRC #4 Project: ENRG07001 Sample ID: 436541006 Client ID; ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity . RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 20 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: Sump Area #1 Project: ENRG07001 Sample ID: 436541007 Client ID: ENRG070 Matrix: Soil Collect Date: 09-SEP-17 13 :43 Receive Date: 30-OCT- l 7 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 10.4 +/--0.389 0.0181 0.400 pCi/g BXA4 11/21/17 1423 1718468 Americium-243 0.436 +/-0.0907 0.0145 0.400 pCi/g Curium-243/244 0.110 +/-0.0411 0.0229 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U -0.00443 +/-0.0638 0.151 Q.400 pCi/g BXA4 11/21/17 1036 1718469 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 2.55 +/-0.198 0.0192 0.400 pCi/g BXA4 11/21/17 1005 1718470 3 Plutoniwn-239/240 2. 73 +/--0.205 0.0191 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 41.0 +/-2.86 3.09 5.00 pCi/g BXA4 11/24/17 1135 1718471 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U 1.70 +/- 1.41 3.09 5.00 nm pCi/g 11111111 1045 1115764 s Gamma, Cs 137, Co60, Nb94, Eu 152, Eu 154, Eu155 "Dry Weight Corrected" Cesium-137 193 +/-1.30 0.182 1.00 pCi/g MXRl 11/16/17 1122 1714268 6 Cobalt-60 12.3 +/-0.406 0.0788 pCi/g Europium-152 U -0.0371 +/-0.413 0.701 pCi/g Europium-154 0.557 +/-0.321 0.264 pCi/g Europium-155 U 0.0995 +/--0.252 0.482 pCi/g Niobium-94 U 0.00158 +/-0.0591 0.107 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 4.24 +/--0.332 0.143 0.400 pCi/g KSDI 11/21/17 0658 1717213 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium u 2.46 +/-5.19 8.92 10.0 pCi/g BXM4 11/16/17 1159 1715582 8 Liquid Scint C14, Solid "As Received" Carbon-14 u 0.446 +/-2.34 4.01 5.00 pCi/g BXM4 11/13/17 1737 1715576 9 Liquid Scint Tc99, Solid "As Received" Tcchnetium-99 2.33 +/-0.974 1.56 2.00 pCi/g CXS7 11/15/17 0808 1715726 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" lron-55 u --0.263 +/-4.66 6.35 10.0 pCi/g TXJI 11/18/17 0905 1715698 II Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 21 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 27,2017 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: Sump Area #I Project: ENRG07001 Sample ID: 436541007 Client ID: ENRG070 Parameter Qualifier Result Uncertainty Rad Liquid Scintillation Analysis

- -- ---- -MDC- -- - RL

-- - -- Units

- -PF-- DF - - Analyst Date

-- Time Batch Method Liquid ScintNi63, Solid "Dry Weight Corrected" Nickel-63 183 +/-5.79 3.09 5.00 pCi/g nm 11118111 1319 1115705 12 The following Prep Methods were performed:

Method Description Analyst Date Time Prep Batch Diy Soil Prep Dry Soil Prep GL-RAD-A-021 LYTI 10/31/17 0808 1714238 The following Analytical Methods were performed:

Method _D~es_c_r1~*P~ti~o_n_ _ _ __ _ _ _ _ _ __ __ _ __ ____ ~ An ~ a=l.._y=st~C

~o=m==m=e~n=ts I DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu-I I-RC Modified 4 DOE EML HASL-300, Pu-I I-RC Modified 5 DOE RESL Ni-I 6 DOE HASL 300, 4.5.2.3/Ga-OI-R 7 EPA 905.0 Modified/DOE RP501 Rev. I Modified 8 EPA 906.0 Modified 9 EPA EERF C-01 Modified IO DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-I, Modified 12 DOE RESL Ni-I , Modified Surrogate/f racer Reco~ery . Test - - - --*-*- ___ _____ _______ .. _ _ _R_e_su_I!_ .. Nominal _ Recov~_____ Acceptable Limits Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, I 14 (15%-125%)

Solid 'Dry Weight Corrected' Curium-243/244 Tracer Alphaspec Isotopic Am24 I Am243, Cm243/244, 75.3 (15%-125%)

Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected' 100 (15%-125%)

Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 108 (15%-125%)

Corrected" Plutonium-242 Tracer Liquid Scint Pu241 , Solid "Dry Weight Corrected" 108 (15%-125%)

Nickel Carrier Gamma Ni59, Solid "Diy Weight Corrected" 107 (25%-125%)

Strontium Carrier GFPC, Sr90, Solid "Diy Weight Corrected" 86.6 (25%-125%)

Technetium-99m Tracer Liquid Scint Tc99, Solid

As Received" 90.9 (15%-125%)

Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected' 78.3 (15%-125%)

Nickel Carrier Liquid Scint Ni63, Solid "Diy Weight Corrected" 82.5 (25%-125%)

Notes:

Page 22 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 -www.gel.com Certificate of Analysis Report Date: November 27, 2017 Company : LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: SumpArea #l Project: ENRG07001 Sample ID: 436541007 Client ID: ENRG070 Parameter Qualifier Result Uncertainty _ _ MD _ C_ _ _RL _ _ __U_ni_ts_ _ P_F_ ?F Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor Le/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 23 of 45

GEL LABO RATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 -www.gel.com QCSu mman : Reoort Date: November 27, 2017 LaCrosseSolutlons S4601 State Hwy 35 Page l of 7 Genoa, Wisco sin

Contact:

Mr. Jaso Q. Spaide Workorder: 436541 Parmname ____ NOM - -* Sample Qual QC Units RPDo/o REC0/o Range Anlst Date Time Rad Alpba Spec Batch 1718468 ------- ---- ---

QCl203918 724 436541001 DUP Americium-241 u 0.0241 0.0305 pCi/g 37.1 (0% - 100%) BXA4 11/21/17 14:23 Uncertainty +/-0.0289 +/-0.021 Americium-243 0.0636 u 0.00265 pCi/g 57.8 (0%- 100%)

Uncertainty +/-0.0393 +/-0.0171 Curium-243/244 u -0.00195 u -0.00152 pCi/g NIA NIA Uncertainty +l-0.0134 +/-0.00674 QCl203918 725 LCS Americium-241 0.980 0.900 pCi/g 91.8 (75%-125%) 11121117 14:23 Uncertainty +/-0.100 Americium-243 u 0.00409 pCi/g (75%-125%)

Uncertainty +l-0.0115 Curium-243/244 1.24 1.09 pCi/g 87.5 (75%-125%)

Uncertainty +/-0.109 QCI203918723 MB Americium-241 u 0.00156 pCi/g 11/21117 14:23 Uncertainty +l-0.00866 Americiwn-243 u 0.0125 pCi/g Uncertainty +/-0.0223 Curium-243/244 u -0.00213 pCi/g Uncertainty +l-0.00643 Batch 1718469 QC12039l8 727 436541001 DUP Neptunium -237 u 0.00876 u -0.0104 pCi/g NIA NIA BXA4 11/21/17 10:36 Uncertainty +l-0.0993 +/-0.0441 QCl203918728 LCS Neptunium -237 8.79 9.12 pCi/g 104 (75%-125%) 11/21/17 10:36 Uncertainty +/-0.870 QC1203918726 MB Neprunium-237 u -0.0224 pCi/g 11/21/17 10:36 Uncertainty +l-0.0436 Page 24 of 45

GEL LA BORATORIES LLC 2040 Savage Road Charleston, SC 29407 -(843) 556-8171 -www.gel.c om QC Summa!:!

Workorder: 436541 Page 2 of 7 Parmname NOM Sam~le Qua) QC Units RPD% REC3/4 Range Anlst Date Time Rad Alpha Spec Batch 1718470 - -- * - - - -

QC1203918730 436541()01 DUP Plutonium-238 0.0137 u 0.00898 pCi/g 12.8 NIA BXA4 11/21117 10:37 Uncertainty +l-0.0181 +l-0.0129 Plutoniurn-2391240 u 0.000183 u 0.00325 pCi/g NIA NIA Uncertainty +l-0.0135 +l-0.00914 QC1203918731 LCS Plutonium-238 u 0.0141 pCilg 11121/17 10:06 Uncertainty +l-0.0166 Plutonium-2391240 0.984 0.921 pCi/g 93.7 (75%-125%)

Uncertainty +l-0.116 QC!2039l8729 MB Plutoniurn-238 u -0.00125 pCi/g 11121/17 10:06 Uncertainty +l-0.0107 Plutoniurn-2391240 u 0.00394 pCilg Uncertainty +l-0.0148 Batch 1718471 - -- -

QC1203918733 436541001 DUP Plutoniurn-241 u -1.46 u -1.61 pCi/g NIA NIA BXA4 11124117 12:38 Uncertainty +/-2.30 +/-2.25 QC1203918734 LCS Plutonium-241 35.9 33.8 pCi/g 94.2 (75%-125%) 11/24117 13:10 Uncertainty +/-3.12 QC1203918732 MB Plutonium-241 u -0.755 pCi/g 11124117 12:06 Uncertainty +l-2.64 Rad Gamma Spec Batch 1714268 QC 1203908226 436541001 DUP Cesium-137 0.804 0.939 pCi/g 15.5 (O"/o-20%) MXRI 11/16117 12:28 Uncertainty +/-0.115 +/-0.0985 Cobalt-60 u 0.0245 u 0.0247 pCi/g NIA NIA Uncertainty +/-0.0399 +l-0.0356 Europium-152 u -0.055 u -0.0378 pCilg NIA NIA Uncertainty +l-0.0747 +l-0.0542 Page 25 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summ a!!

Workorder : 436541

- - - - - - - ------ *- Page 3 of 7 Parmname - - - - - - - -- - - - -- --*- --- -

NOM Sam2le Qual QC Units RPD'1/4 REC% ~ Anlst Date Time Rad Gamma Spec Batch 1714268 Europium-15 4 u -0.0104 u -0.00504 pCi/g NIA NIAMXRl ll/i 6117 12:28 Uncertainty +l-0.0838 +l-0.0758 Europium-15 5 u 0.0393 u 0.0182 pCi/g NIA NIA Uncertainty +l-0.0717 +l-0.0401 Niobium-94 u -0.00984 u 0.0183 pCilg NIA NIA Uncertainty +l-0.024 +l-0.0209 QCl203908227 LCS Americium-2 41 488 510 pCi/g 104 (75%-125%) 11116117 12:02 Uncertainty +l-11.2 Cesium-137 175 177 pCi/g 101 (75%-125%)

Uncertainty +l-3.38 CobaJt-60 139 138 pCilg 98.9 (75%-125%)

Uncertainty +l-3.57 Europium-15 2 u 0.586 pCi/g Uncertainty +l-1.49 Europium-15 4 u -0.552 pCi/g Uncertainty +l-1.06 Europium-15 5 u -0.821 pCilg Uncertainty +l-1.36 Niobium-94 u 0.246 pCi/g Uncertainty +l-0.491 QCl203908225 MB Cesium-137 u 0.00657 pCi/g 11/16117 11 :23 Uncertainty +/-0.0157 Cobalt-60 u 0.00816 pCi/g Uncertainty +l-0.0136 Europium-15 2 u -0.00798 pCi/g Uncertainty +l-0.0366 Europium-15 4 u -0.0148 pCilg Uncertainty +l -0.0406 Europium-15 5 u -0.00742 pCilg Uncertainty +/ -0.0261 Page 26 of 45

GEL LABO RATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 -www.gel.com QC Summa!:!

Workorder: 436541 Page 4 of 7 Parmname NOM Sam2Ie Qual QC Units RPD% REC% Range A11lst Date Time Rad Gamma Spec Batch 1714268 Niobium-94 u -0.000682 pCilg MXRl ll/16/17 11:23 Uncertainty +/-0.0149 Batch 1715764 ---- *-- --- ---- - --

QCl203911889 436541001 DUP Nickel-59 u -1.72 u -1.05 pCi/g NIA NIA TXJl 11/17/ 17 11 :58 Uncertainty +l-1.60 +l-1.55 QC1203911890 LCS Nickel-59 93.6 90.0 pCi/g 96.2 (75%-125%) 11/17/17 11 :59 Uncertainty +l-6.15 QC120391 !888 MB Nickel-59 u 0.485 pCilg 11/17/ 17 10:46 Uncertainty +/-0.578 Rad Gas Flow Batch 1717213 -~--- -- --

QC1203915501 436541005 DUP Strontium-90 u 0.0795 u 0.169 pCi/g NIA NIA KSDl 11/16117 14:13 Uncertainty +/-0.159 +l-0.154 QC1203915502 LCS Strontium-90 13.8 12.1 pCi/g 87.5 (75%-125%) 11/16/17 14: 13 Uncertainty +/-0.695 QC 1203915500 MB Strontium-90 u 0.0523 pCi/g 11/16/17 14:13 Uncertainty +l-0.140 Rad Liquid Sciatillatioa Batch 1715576 QCl203911442 436541001 DUP Carbon-14 u 0.720 u -0.498 pCi/g NIA NIABXM4 11113117 19:02 Uncertainty +l-2.36 +/-2.19 QC12039l 1444 LCS Carbon-14 140 139 pCi/g 99.3 (75%-125%) I 1113/17 20:26 Uncertainty +l-4.50 QC 1203911441 MB Carbon-14 u 1.49 pCi/g 11/13117 18:19 Uncertainty +/-2.26 Page 27 of 45

GEL LABO RATORIES LLC 2040 Savage Road Char1eston, SC 29407 - (843) 556-8171 -www.gel .com QCSu mman :

Workorder: 43654)

Page 5 of 7 Parmname NOM Samj!le Qual QC Units RPD0/4 REC 0/4 lunge Anlst Date Time Rad Liqid Scintillation Batch 1715576 QC1203911443 436541001 MS Carbon-14 260 u 0.720 246 pCi/g 94.8 (75%-125%) BXM4 11/13/17 19:44 Uncertainty +/-2.36 +/-8.17 Batch 1715582 -- - - - - - - - - - -

QC1203911462 436541001 DUP Tritium u 1.27 u 0.0497 pCi/g NIA N/ABXM4 11/16/17 13:33 Uncertainty +l-5.1 t +l-5. 14 QCl203911464 LCS Tritium 53.7 50.4 pCi/g 93.9 (75%-125%) 11/16117 15:07 Uncertainty +l-7.27 QC1203911461 MB Tritium u 1.06 pCi/g tl/16117 12:46 Uncertainty +l-5.16 QC1203911463 436541001 MS Tritium 108 u 1.27 95.0 pCilg 87.7 (75%-125%) 11116117 14:20 Uncertainty +/-5.11 +l-14.1 Batch 1715698 ------* ---- - - -- - -

QC1203911707 436541 001 DUP Iron-55 u -2.22 u -0.891 pCi/g NIA NIA TXJI lt/18/17 10:40 Uncertainty +l-4.13 +l-4.89 QCl203911708 LCS lron-55 126 128 pCi/g 101 (75%-125%) 11118117 11 :27 Uncertainty +/-6.70 QC1203911706 MB lron-55 u 3.13 pCi/g 11/1 8117 09:52 Uncertainty +l-4.38 Batch 1715705 QC1203911729 436541001 DUP Nickel-63 u 2.73 u 0.745 pCi/g NIA NIA TXJI 11118117 00:28 Uncertainty +l-1.99 +/-1.80 QCl203911730 LCS Nickel-63 85.9 94.! pCilg 110 (75%-125%) i 1/18/17 00:45 Uncertainty +/-4.66 Page 28 of 45

GEL LABORATORIES LLC 2040 Savage Road Charteston, SC 29407 - (843) 556-8171 -www.gel .com QC Summary Workorde r: 436541

-- - -- -- - - ~- Page 6 of 7 Parmname NOM Sample Qual QC Units RPD% RECo/e Range Anlst Date Time R*d Liqid Scintillation Batch 1715705 QC12039l 1728 MB Nickel-63 u 2.30 pCi/g DOI 11/18/17 00:12 Uncertaint y +/-1.95 Batch 1715726 QCl203911766 436541001 DUP Technetium -99 u -0.208 U 0.425 pCi/g NIA NIA CXS7 ll/14/17 11:02 Uncertaint y +/-0.744 +/-0.826 QC1203911767 LCS Technetium -99 34.2 25.9 pCi/g 75.8 (75%-125% ) 11/15/ 17 06:31 Uncertaint y +/-1.19 QC1203911765 MB Technetium -99 u -0.368 pCi/g 11/14/ 17 l0:30 Uncertaint y +/-0.624 Notes:

Counting Uncertaint y is calculated at the 95% confidence level (l .96-sigma) .

The Qualifiers in this report are defined as follows:

Analyte is a Tracer compound

< Result is Jess than value reported

> ResuJt is greater than value reported BD Results are either below the MDC or tracer recovery is low FA Failed analysis.

H Analytical holding time was exceeded J Value is estimated K Analyte present. Reported value may be biased high. Actual value is expected to be lower.

L Analyte present. Reported value may be biased low. Actual value is expected to be higher.

M M if above MDC and less than LLD M REMP Result > MDC/CL and < RDL NIA RPO er %Recovery limits do not apply.

Nl See case narrative ND Analyte concentrati on is not detected above the detection limit NJ Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Q One or more quality control criteria have not been met. Refe1 to lhe applicable narrative or DER.

R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.

UI Gamma Spectrosco py-Uncerta in identificati on Page 29 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 -www.gel .com QC Summary Workorde r: 436541 Page 7 of 7 Parmnam e NOM Sample Qua! QC Units RPO% REC% Range Anbt Date Time UJ Gamma Spectroscopy--Uncertain identification UL Not considered detected. The associated number is the reported concentration, which may be inaccurate due to a low bias.

X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier y Other specific qualifiers were required to properly define the results. Consult case narrative.

RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL. Qualifier Not Applicable for Radiochemistry.

h Preparation or preservation holding time was exceeded N/A indicates that spike recovery limits do not apply when sample concentration exceeds spike cone. by a factor of 4 or more or %RPO not applicable.

"' The Relative Percent Difference (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptance criteria when the sample is greater than five times (5X) the contract required detection limit (RL). In cases where either the sample or duplicate value is less than 5X the RL, a control limit of+/- the RL is used to evaluate the DUP result

Indicates that a Quality Control parameter was not within specifications.

For PS, PSD, and SDILT results, the values listed are the measured amounts, not fmal concentrati ons.

Where the analytical method bas been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the QC Summary.

Page 30 of 45

Radioch emistry Technic al Case Narrativ e LaCross eSolutio ns, LLC (ENRG)

SDG #: 436541 Product : Alphasp ec Isotopic Am241 Am243, Cm243/244, Solid Analytic al Method : DOE EML HASL-300, Am-05-RC Modified Analytical Procedure; GL-RAD-A-011 REV# 26 Analytic al Batch; 1718468 Prepara tion Method ; Dry Soil Prep Prepara tion Procedu re: GL-RAD-A-021 REV# 22 Preparation Batch: 1714238 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 436541001 Ll-SUB-CDR-FSGS-008-SB 436541002 LI-SUB-CDR-FSGS-009-SB 436541003 LI-SUB-CDR-FSGS-011-SB 436541004 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 SumpA rca#l 1203918723 Method Blank (MB) 1203918724 43654100l(LI-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203918725 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

Data Summa ry; All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.

Technical Information Recounts Sample 436541001 (LI-SUB-CDR-FSGS-008-SB) was given additional clean-up steps and recounted in order to remove suspected interferences. The recount is reported.

Product: Alphaspec Np, Solid Analytical Method: ASTM C 1475-00 Modified Analytical Procedure: GL-RAD-A-032 REV# 21 Analytical Batch: 1718469 P0Bax30712 QwJ1eslon,SC29417 2040SavageR0ed Chatlts1Dn,SC29407 Pl43.55U171 FIQ.788.1171 www.119J.com

Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1714238 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 436541001 LI-SUB-CDR-FSGS-008-SB 436541002 LI-SUB-CDR-FSGS-009-SB 436541003 LI-SUB-CDR-FSGS-011-SB 436541004 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 SumpAr ea#l 1203918726 Method Blank (MB) 1203918727 436541001(LI-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203918728 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

Data Summary:

There are no exceptions, anomalies or deviations from the specified methods. AH sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable.

Product: Alphaspec Pu238, 239/240, Solid Analytical Method: DOE EML HASL-300, Pu-11-RC Modified Analytical Procedure: GL-RAD-A-011 REV# 26 Analytical Batch; 1718470 Preparati on Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1714238 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Cljent Sample Identification 436541001 LI-SUB-CDR-FSGS-008-SB 436541002 LI-SUB-CDR-FSGS-009-SB 436541003 LI-SUB-CDR-FSGS-011-SB 436541004 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 Sump Area #1 1203918729 Method Blank (MB}

1203918730 436541001 (LI-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203918731 Laboratory Control Sample (LCS)

Pa~~( fftorle s u.c P0Boxaon2 Clwleslon,SC29417 2040SaVllltlloeCI Chatlaton,SC29407 P843.55U171 Fl43.7111,1178 www.aa1.com

The samples in this SDG were analyzed on a "dry weight" basis.

Data Summary:

All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.

Technical Information Recounts Sample 436541003 (LI-SUB-CDR-FSGS-011-SB) was recounted due to a peak shift. The recount is repo1ted.

Product: Dry Weight Preparation Method; Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1714238 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 436541001 LI-SUB-CDR-FSGS-008-SB 436541002 LI-SUB-CDR-FSGS-009-SB 436541003 LI-SUB-CDR-FSGS-01 I-SB 436541004 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC #4 436541007 SumpAr ea#l The samples in this SDG were analyzed on an "as received" basis.

Data Summary; There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable.

Product; Gamma, Csl37, Co60, Nb94, Eu 152, Eu154, Eul55 Analytical Method; DOE HASL 300, 4.5.2.3/G a-0l-R Analytical Procedure; GL-RAD-A-013 REV# 27 Analytical Batch: I714268 Preparation Method; Dry Soil Prep Preparation Procedure; GL-RAD-A-021 REV# 22 Preparation Batch: 1714238 PO lb 30n 2 Charles\on, SC 29417 2040 Savage Road Chal1e8ton, SC 29407 P 8'3 5511171 F 1143.781.1171 www.ge1.com

The following samples were analyzed using the above methods and analytica l procedure(s).

GEL Sample ID# Client Sample Identification 436541001 LI-SUB-CDR-FSGS-008-SB 4365410 02 Ll-SUB-CDR-FSGS-009-SB 4365410 03 LI-SUB-CDR-FSGS-011-SB 4365410 04 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-0 I 4-SB 4365410 06 NRC#4 4365410 07 Sump Area#l 1203908225 Method Blank (MB) 1203908226 4365410 0l(LI-SU B-CDR- FSGS-00 8-SB) Sample Duplicat e (DUP) 1203908227 Laborato ry Control Sample (LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

Data Summary; There are no exceptions, anomalies or deviations from the specified methods

. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedur es for initial calibration, continuing calibration, instrume nt controls and process controls where applicab le.

Qualifier Information Qualifier Reason Analyte Sample Client Sample Results are considered a false UI Cobalt-60 436541004 LI-SUB-CDR-FSGS-012-SB positive due to high peak-width.

Product; Gamma Ni59, Solid Analytical Method: DOE RESL Ni-I Analytical Procedure: GL-RAD-A-022 REV# 18 Analytical Batch: 1715764 Preparation Method; Dry Soil Prep Preparation Procedure; GL-RAD-A-021 REV# 22 Preparation Batch: 1714238 The following samples were analyzed using the above methods and analytica l procedure(s).

GEL Sample ID# Client Sample Identific ation 436541001 Ll-SUB-CDR-FSGS-008-SB 4365410 02 Ll-SUB-CDR-FSGS-009-SB 436541003 LJ-SUB-CDR-FSGS-011-SB 4365410 04 LJ-SUB-CDR-FSGS-012-SB 436541005 Ll-SUB- CDR-FS GS-0 I 4-SB 4365410 06 NRC#4 4365410 07 Sump Area #1 1203911888 Method Blank (MB)

Pa~q JJton esu.c PO Bol 30712 Cllarlnllon, SC 29417 2~ Savage Road Char1eston, SC 29407 P843.5511.8171 FIMUIL1178 www.gel.com

12039118 89 43654100 1(LI-SUB -CDR-FS GS-008-S B) Sample Duplicate (DUP) 12039118 90 Laborator y Control Sample {LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

Data Summary:

There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptanc e criteria specified in the analytical methods and procedure s for initial calibration, continuin g calibration, instrumen t controls and process controls where applicable.

Product; GFPC, Sr90, Solid Analytical Method: EPA 905.0 Modified/DOE RP501 Rev. I Modified Analytical Procedure: GL-RAD- A-004 REV# 19 Analytica l Batch: I 717213 Preparation Method; Dry Soil Prep Pcmaration Procedure: GL-RAD-A-021 REV# 22 Preparation Batch; 1714238 The following samples were analyzed using the above methods and analytical procedure (s).

GEL Sample ID# Client Sample Identification 436541001 LI-SUB-C DR-FSGS -008-SB 43654100 2 LI-SUB-C DR-FSGS -009-SB 43654100 3 LI-SUB-C DR-FSGS -011-SB 43654100 4 LI-SUB-C DR-FSGS -012-SB 43654100 5 LI-SUB-C DR-FSGS -014-SB 43654100 6 NRC#4 43654100 7 Sump Area#]

12039155 00 Method Blank (MB) 1203915501 436541005(LI-SUB-CDR-FSGS-O 14-SB) Sample Duplicate (DUP) 12039155 02 Laborator y Control Sample (LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

Data Summary ;

All sample data provided in this report met the acceptanc e criteria specified in the analytical methods and procedure s for initial calibration, continuin g calibration, instrumen t controls and process controls where applicable, with the following exceptions.

Tochnical Information Recounts Sample 436541001 (LI-SUB- CDR-FSG S-008-SB ) was recounted due to results more negative than the three sigma TPU. The second count is reported. Samples 43654100 6 (NRC #4} and 43654:00 7 (Sump Area #i) were verified by recounting at least five days from the separation date. The recounts are reported.

Pa~\fJ ,tOl'le s u.c P0Box30m! Cherleston,SC29417 2040Savlgelload CharllSUln,SC29407 P84USU171 F843.7111L1178 www.gal.com

Product: Liquid Scint Pu241, Solid Analytical Method: DOE EML HASL-300, Pu-1 I-RC Modified Amllytical Procedure: GL-RAD-A-035 lUN# 19 Analytical Batch: 1718471 Preparation Method; Dry Soil Prep Prmaration Procedure; GL-RAD-A-021 REV# 22 Preparation Batch: 1714238 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 436541001 LI-SUB-CDR-FSGS-008-SB 436541002 LI-SUB-CDR-FSGS-009-SB 436541003 Ll-SUB-CDR-FSGS-011-SB 436541004 LI-SUB-CDR-FSGS-012-SB.

436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 Sump Area # 1 1203918732 Method Blank (MB) 1203918733 43654100l( LI-SUB-CD R-FSGS-00 8-SB) Sample Duplicate (DUP) 1203918734 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

Data Summary:

There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable.

Product: Liquid Scint Cl 4, Solid Analytical Method; EPA EERF C-01 Modified Analytical Procedure: GL-RAD-A-003 REVff ?5 Analytical Batch: 1715576 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 436541001 LI-SUB-CDR-FSGS-008-SB 436541002 LI-SUB-CDR-FSGS-009-SB 436541003 LI-SUB-CDR-FSGS-011-SB 436541004 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 Sump Area #1 POBax30712 Cllerleslon,SC29417 2040SlvageRDld Clwlaston.SC29407 P84S5511171 fl43.7118.1178 www.gel.tom

1203911441 Method Blank (MB) 1203911442 43654100l(LI-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203911443 436541001(LI-SUB-CDR-FSGS-008-SB)Matrix Spike (MS) 1203911444 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on an ltas received" basis.

Data Summary:

All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.

Miscellaneous Information Additional Comments The matrix spike, 1203911443 (LI-SUB-CDR-FSGS-008-SBMS), aliquot was reduced to conserve sample volume.

Product; LSC, Tritium Distillation, Solid Analytical Method; EPA 906.0 Modified Analytical Procedure: GL-RAD-A-002 REV# 22 Analytical Batch: 1715582 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 436541001 LI-SUB-CDR-FSGS-008-SB 436541002 LI-SUB-CDR-FSGS-009-SB 436541003 LI-SUB-CDR-FSGS-011-SB 436541004 LI-SUB-CDR-FSGS-012-SB 436541005 LJ-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 Sump Area#l 12039 11461 Method Blank (MB) 1203911462 436541001(LI-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203911463 436541001(LI-SUB-CDR-FSGS-008-SB) Matrix Spike (MS) 1203911464 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on an "as received" basis.

Data Summary:

All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.

Mi~celhmeous Information Additional Comments The matrix spike, 1203911463 (LI-SUB-CDR-FSGS-008-SBMS), aliquot was reduced to conserve sample POb30712 CtwlellDn,SC29417 2040Sava;elad Clwlesl:On,SC29407 P8435511171 FIM3.711L1178 www.ge1.co111

volume.

Product: Liquid Scint FeSS, Solid Analytical Method: DOE RESL Fe-1, Modified Analytical Procedure: GL-RAD-A-040 REV# 13 Analytical Batch: 1715698 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Pre_paration Batch: 1714238 The following samples were analyzed using the above methods and analytical procedure (s).

GEL Sample ID# Client Sample Identification 436541001 LI-SUB-CDR-FSGS-008-SB 436541002 LI-SUB-CDR-FSGS-009-SB 436541003 LI-SUB-CDR-FSGS-011-SB 436541004 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 43654100 7 Sump Area#l 12039]17 06 Method Blank (MB) 1203911707 436541001(LI-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203911708 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

Data Summary:

There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable.

Product: Liquid Scint Ni63, Solid Analytical Method: DOE RESL Ni-I, Modified Analytical Procedure: GL-RAD-A-022 REV# 18 Analytical Batch: 1715705 Preparati on Method; Dry Soil Prep Pre.paration Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1714238 Pa~ rles uc PO Box 30n2 a-rteston, SC 29417 2D40 Savage Road Cllarl8st0n, SC 29407 P&Q.551.1171 Fl43.7&1178 www.ge1.com

The following samples were analyzed using the above methods and analytical procedure (s).

GEL Sample ID# Client Sample Identification 436541001 LI-SUB-CDR-FSGS-008-SB 436541002 LI-SUB-CDR-FSGS-009-SB 436541003 LJ-SUB-CDR-FSGS-011-SB 43654100 4 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 SumpAr ea#l 1203911728 Method Blank (MB) 1203911729 43654100 l(LI-SUB -CDR-FS GS-008-S B) Sample Duplicate (DUP)

]2039117 30 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

Data Summary:

All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuin g calibration, instrument controls and process controls where applicable, with the following exceptions.

Technical Information Recounts Samples 436541002 (LI-SUB-CDR-FSGS-009-SB), 436541003 (LI-SUB-CDR-FSGS-011-SB

), 43654100 6 (NRC #4) and 43654 l 007 (Sump Area# I) were recounted to verify sample results. Recounts are reported.

Product: Liquid Scint Tc99, Solid Analytical Method: DOE EML HASL-300, Tc-02-RC Modified Analytical Procedure; GL-RAD- A-059 REV# 5 Analytical Batch; 1715726 The following samples were analyzed using the above methods and analytical procedure (s).

GEL Sample ID# Client Sample Identification 436541001 LJ-SUB-CDR-FSGS-008-SB 436541002 LI-SUB-CDR-FSGS-009-SB 436541003 LI-SUB-CDR-FSGS-011-SB 436541004 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 Sump Area#l 1203911765 Method Blank (MB) 1203911766 436541001(Ll-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 12039ll7 67 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on an "as received" basis.

Pa~esu.c PO Bax30n2 Cla1eslon, SC 29417 2040 SavaQe fad Char1est0n, SC 29407 www.ae1.com

Data Summary:

All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.

Technical Information Recounts Sample 1203911767 (LCS) was recounted due to low recovery. The recount is reported.

Samples 436541006 (NRC #4) and 436541007 (Sump Area #1) were recounted to verify sample results. Recounts are reported.

Certification Statement Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless otherwise noted in the analytical case narrative.

PO Box 30712 Cllatleslon, SC 29417 2040 Sa\'11111 Road Chart881Dn, SC 29407 P 843.551.8171 F &Q..781.1171 www.ge1.com

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2040 Savage Road Chuleston, SC 29407

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l Chain of cusiady dol:ulllCllts included wllhshi t?

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5 Sample coniainers imac1 and sealed? lme Appl!Clbla: Soeb lnoken Danop d canrlllner Latins caa111i,,.,. Olher(~r:rib e}

(i 5amplcs n:quiring chemical pccservation at proper pH?

I! Yes, Are Encores Ol' Soil Kits present? Yes _

No_ (rt yes, tw: to VOA.Freezer)

Do VOA vials cantain acid preservation? Yes .

Do any samples require Volatile No_ NIA. (II llllko011111, a,Jcct No) 7 VOA vials free ofheadspace?Yes Analysis? No_ N/A Sample ID's and containers affected:

8 Samples received wilhln holding time? JD'a 1111,I ..... affccled:

!) Sample JO's on COC matdt ID's on boUles?

Dace & lime on COC match dace & time s.i,,p!o lD'I affccled:

10 on bottles?

Number of eon111lners ~ivc d ma1eh 11 number indicaicd on COC?

Aze sainplc comaincrs identifiable as 12 G idcd?

COC fo.nn is properly 1igned in 13 rclin ui1hcd/rcccived sections?

Comments (Use Contl11111tlon Porm 1f l!eedcd):

Gl*CHL-SR-001 Rev 5 Page 44 of 45

List of current GEL Certifications as of 27 Novembe r 2017 State Certification Alaska UST-011 0 Arkansas 88-0651 CLIA 42009040 46 Califomi a 2940 Colorado SC00012 Connecti cut PH-0169 Delaware SC00012 DoD ELAP/ 1SO17025 A2LA 2567.01 Florida NELAP E87156 Foreign Soils Permit P330--15 -00283,P 330-15--0 0253 Georgia SC00012 Georgia SDWA 967 Hawaii SC00012 Idaho Chemistry SC00012 Idaho Radiochemistry SC00012 Illinois NELAP 200029 Indiana C-SC--01 Kansas NELAP E-10332 Kentucky SOWA 90129 Kentucky Wastewater 90129 Louisiana NELAP 03046 (AI33904)

Louisiana SDWA LA170010 Maryland 270 Massachu setts M-SC0l2 Michigan 9976 Mississip pi SC00012 Nebraska NE-OS-2 6-13 Nevada SC00012 2018-l New Hampshir e NELAP 205415 New Jersey NELAP SC002 New Mexico SC00012 New York NELAP 11501 North Carolina 233 North Carolina SOWA 45709 North Dakota R-158 Oklahom a 9904 Pennsylvania NELAP 68-00485 Puerto Rico SC00012

$.Carolin a Radchem 10120002 South Carolina Chemistry 10120001 Tennessee TN02934 TexasNE LAP TI04704 235-17-1 2 UtahNEL AP SC00012 2017-24 Vermont VT87156 Virginia NELAP 460202 Washingt on C780 West Virginia 997404 Page 45 of 45

v t e Letter Sequence Request
CAC:000083, (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance Administration Questions Answers Results Approval, Approval, Approval, Approval Other: ML18247A211, ML19008A394, ML19008A395, ML19008A396, ML19008A397, ML19008A405, ML20195A857, ML21050A309, ML21281A171, ML23055A028, ML23055A029, ML23067A100
MONTHYEAR2022-10-20 [Table View]

ML22269A391

Text

SUMMARY

SUMMARY

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