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Boiling Water Reactor Final Status Survey Final Report - Phase 3, Survey Unit L1-SUB-CDR Stack, Pipe Tunnel, RPGPA Excavation (Release Record)
	ML20031C853
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	01/28/2020
From:	Yetter R; LaCrosseSolutions
To:	; Office of Nuclear Material Safety and Safeguards
Shared Package
ML20031C839	List: ML20031C840; ML20031C841; ML20031C842; ML20031C843; ML20031C844; ML20031C845; ML20031C846; ML20031C847; ML20031C849; ML20031C850; ML20031C852; ML20031C853; ML20031C855; ML20031C858; ML20031C860;
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LA CROSSE BOILING WATER REACTOR FINAL STATUS SURVEY RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 0

fS RELF.ASE RECORD ~

SURVEY UNIT Ll-SUB-CDR STACK. PIPF TUNNFI . RPGPA FXCA ATJON , ~SOLUTIONS PREPARED B\' / DATE: ~~ ""1"--

R. F. Yetter II ~pecialist

I gical Site Closure I'

1

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"iJ. . I,,-

~ d[;-f:tc,"f ,/r.e,c/e- 1/27/20 REVIEWED BY/ DATE:

P. Hollenbeck, Radiological Engineer APPROVEDBY/DAT~~~~~~~~~ *=-~-------------~a~4~~1io::.4~~~~o=-

S. Zo~l\1anager 1

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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 ...................................................................................................................................... 28

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

10. REMEDIATION AND RESULTS ................................................................................................................... 29

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN ........................................................................ 29

12. DATA QUALITY ASSESSMENT (DQA) ....................................................................................................... 29

13. ANOMALIES ..................................................................................................................................................... 30

14. CONCLUSION .................................................................................................................................................. 30

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

16. ATTACHMENTS .............................................................................................................................................. 31 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 ................................................................... 51 2

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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 Off-Site Analysis Results......................................................................................................................... 26 Table 7 Summary of Gamma Spectroscopy Results for Investigational Samples ........................................... 26 Table 7 Summary of Gamma Spectroscopy Results for the QC Sample ......................................................... 27 Table 7 Sum-of-Fractions for Systematic and QC Samples .............................................................................. 27 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

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

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

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.

5

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

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.

6

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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 7

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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.

8

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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 fraction less than 10%).

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 9

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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.

10

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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).

11

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

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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:

13

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION Equation 1 1

=

1 2 3

[( ) + ( ) + ( ) + ( )]

2 3 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide Using the Operational DCGLs presented in Table 4-3 and the ratio from Table 5-1, the following surrogate calculation was performed:

Equation 2 1

(137) = = 17.31 /

1 0.502

[(17.39 )+( )]

(137) 1970.45(90)

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

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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.

15

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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.

16

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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.

17

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION Table 5 Synopsis of Survey Design Feature Design Criteria Basis Survey Unit Surface Area 431 m2 GPS

= 0.03 UBGR = SOF of 1 Number of Systematic Samples 14 LBGR = SOF of 0.5 (N) Type I & II error = 0.05

/ = 3 (adjusted)

MARSSIM Table 5.5 Co-60: 3.83 pCi/g Sr-90: 1970.45 pCi/g 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)

Eu-152: 8.51 pCi/g 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.

18

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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 NRC #4 through 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).

19

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

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

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

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

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

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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 off-site laboratory, GEL Laboratories, processed the five (5) samples selected for HTD ROC analysis. 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. The initial full suite of ROC was included in the analysis, although only Sr-90 was required to be analyzed. All analyses met the required MDC.

Sr-90 was not detected in the off-site analysis of 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. The results are provided in Table 7-4.

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FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION Table 7 Off-Site Analysis Results Result Uncertainty MDC Sample ID ROC >MDC (pCi/g) (pCi/g) (pCi/g)

L1-SUB-CDR-FSGS-008-SS Sr-90 2.48E-01 1.80E-01 2.76E-01 No L1-SUB-CDR-FSGS-009-SS Sr-90 -1.78E-01 1.33E-01 3.06E-01 No L1-SUB-CDR-FSGS-011-SS Sr-90 7.87E-02 1.41E-01 2.51E-01 No L1-SUB-CDR-FSGS-012-SS Sr-90 1.63E-01 1.93E-01 3.25E-01 No L1-SUB-CDR-FSGS-014-SS Sr-90 7.95E-02 1.59E-01 2.86E-01 No 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 7-5. 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.

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)

NRC #4 7.68E-02 1.52E+00 1.78E-02 7.63E-01 NRC #5 8.11E-02 7.16E-01 1.58E-02 3.59E-01 NRC #6 4.80E-02 7.31E-01 8.92E-03 3.67E-01 NRC #7 1.06E-02 3.87E-02 2.59E-02 1.94E-02 NRC #8 0.00E+00 1.59E-01 7.94E-04 7.98E-02 NRC #9 7.29E-02 1.57E+00 2.32E-02 7.88E-01 Note: Bold values indicate concentrations greater than MDC.

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.

26

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

.......... .. 1 DCGL1 DCGL 2 DCGL n Where: Cn = concentration of radionuclide n DCGLn = DCGL of radionuclide n.

The results of the unity rule calculation for the ROC in the systematic sample population 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 27

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION Fraction of Operational DCGL Sample ID SOF Co-60 Cs-137 Eu-152 Eu-154 Sr-90 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 NRC #4 0.0201 0.0874 0.0023 0.0004 0.1101 NRC #5 0.0212 0.0412 0.0020 0.0002 0.0645 NRC #6 0.0125 0.0420 0.0011 0.0002 0.0559 NRC #7 0.0028 0.0022 0.0033 0.0000 0.0083 NRC #8 0.0000 0.0091 0.0001 0.0000 0.0093 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; however, due to the concentrations of 28

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION Cs-137 reported well below the Operational DCGL, no further action was taken. 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.

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 29

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION 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.

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.

30

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

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

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 31

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR STACK, PIPE TUNNEL, RPGPA EXCAVATION Attachment 8 - GEL Laboratories Analytical Reports 32

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA ATTACHMENT 1 FIGURE 33

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA Figure 16 Survey Unit L1-SUB-CDR Systematic Sample Locations Map 34

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA ATTACHMENT 2 SCAN DATA 35

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA 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

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA 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

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA 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

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA 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

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA ATTACHMENT 3 SIGN TEST 40

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA 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

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA ATTACHMENT 4 QUALITY CONTROL ASSESSMENT 42

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA Table 16 Survey Unit L1-SUB-CDR QC Assessment STANDARD COMPARISON Radionuclid Activity Standard Agreement Range Activity Comparison Acceptable Sample ID Resolution Sample ID e Value Error (Low to High) Value Ratio (Y/N)

L1-SUB-CDR-FSGS-014-SB Cs-137 2.28E+00 7.68E-02 30 0.75 1.33 L1-SUB-CDR-QSGS-014-SB 2.88E-01 0.13 N Comments/Corrective Actions: The comparison ratio is not within the agreement range. Both Table is provided to show acceptance criteria used to assess split samples have activity below the OpDCGL, though, and no further action is necessary. samples.

43

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA ATTACHMENT 5 CONSULTATION TRIGGERS FOR RESIDENTIAL SOIL CONCENTRATION 44

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA 45

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA ATTACHMENT 6 GRAPHICAL PRESENTATIONS 46

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA Figure 16 Quantile Plot for Cs-137 Concentration 47

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA Figure 16 Histogram for Cs-137 Concentration 48

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA Figure 16 Retrospective Power Curve for Survey Unit L1-SUB-CDR 49

FSS RELEASE RECORD SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA ATTACHMENT 7 SAMPLE ANALYTICAL REPORTS 50

9/14/2017 1:35:40PM Page I of6

_...,Apex-Gamma Analysis Report for L 1-SUB-CDR-FSGS-001-SB UNIT L 1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-COR-FSGS-001-SB Sample Description : UNIT L 1-SUB CDR OW13/17 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 Time : 3600.0 seconds Real Time : 3609.3 seconds Dead Time : 0.26% /

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 : 3388 PEAK ANALYSIS REPORT Peak Analysis Perfonned on : 9/14/2017 1:35:31PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/14/2017 1:35:40PM Page 2 of6 Analysis Report for L 1-SUB-CDR-FSGS-001-SB UNIT L1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak NetPeak NetArea Continuum FWHM (keV) Centroid Area Uncertainty Counts (keV)

No. start end F 1 58.14 114 - 119 116.83 3.82E+01 13.06 2.13E+02 0.71 F 2 238.55 469 - 485 477. 5 8 3.45E+02 2 6. 41 4.10E+02 2.69 F 3 338.50 671 - 683 677.44 7.04E+Ol 14. 67 1. 72E+02 2.05 F 4 352.18 699 - 710 704.78 2.10E+02 18.69 1. 24E+02 2 .65 F 5 583.30 1160 - 117 6 1 166 .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+02 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 1824.11 7.BOE+Ol 10.90 3.45E+Ol 2.88 F 9 14 61. 72 2 914 - 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+Ol 13.06 3.82E+Ol 1.31E+Ol F 2 238.55 3. 45E+ 02 26. 41 3.45E+02 2.64E+Ol F 3 338.50 7.04E+Ol 14. 67 7.04E+Ol 1.47E+Ol F 4 352.18 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 l.21E+01 1. 32E+02 2.04E+Ol F 7 662.08 1.13E+02 14.30 6.61E+Ol 1. 27E+Ol 4.69E+Ol 1. 91E+Ol F B 911. 94 7.80E+01 10.90 7 .BOE+Ol 1.09E+Ol F 9 1461.72 6.26E+02 25.40 6.26E+02 2.54E+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 Pagc3 of6 Analysis Report for L 1-SUB.COR-FSGS-001-SB UNIT L1-SUB CDR 09/13/17 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) (uCUgrams) Uncertainty K-40 0.86 1460 . 7 5

10 .67 7.96E-0 6 3. 91E- 07 CS-137 0.97 661. 65

85.12 3.70E-08 1. SlE- 08 PB-2 12 0. 56 77 . 11 17. 5 0 2 38.63

44.60 2. 07E-0 7 l .68E-08 BI-214 0.33 609 . 31

46. 3 0 1.77E-07 2 .79E-08 1120. 29 15.10 123 8 .11 5.94 1377 . 67 4.1 1 1407.98 2. 48 150 9 .1 9 2 .19 1764.49 15. 80 AC-22 8 0 . 30 20 9 . 2 8 4.40 3 38 .3 2

11. 40 2.23E-0 7 4 .69E-08 794.70 4.6 0 911. 60

2 7. 7 0 2. 52E-07 3 .57E- 08 964. 60 5.20 969. 11 1 6.60

=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 INTERFERENCE CORRECTED REPORT

9/14/2017 1:35:40PM Page4of6 Analysis Report for L 1-SUB-CDR-FSGS-001-SB UNIT L 1-SUB COR 09/13/17 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCilgrams) 0.861 7.96E-06 3.91E-07 0.971 3.70E-08 1. SlE-08

0. 560 2.07E-07 1. 68E-08 0.338 l.77E-07 2 .7 9E-08 0.303 2. 42E-07 2 .84E-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 Pages of6 Analysis Report for L 1*SUB-CDR*FSGS*001..SB UNIT L1..SUB COR 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 r,"J Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 58.14 l.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:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA Line MDA Name (uCVgrams) (uCUgrams) (uCUgrams)

(lreV)

+ 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 4.0SE-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.lBE-08 3.45E-08 4.52E-08 1836.06 99.20 -3.0SE-10 3.45E-08

+ 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-09 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

+ As-137 661. 65

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

9/14/2017 1:35:40PM Page6 of6 Analysis Report for L 1-SUB-CDR-FSGS-001-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (uCVgrams) (uCVgrams) (uCVgrams)

(keV)

+ CE-144 80.12 1.36 l.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 -l.12E-07 2. 71E-D7 1274 .51 35.50 -l.82E-D8 1.57E-07

+ EU-155 86.54 32.80 -9.33E-08 l .20E-07 l.2DE-07 105.31 21. 80 -1 .28E-08 l.43E-07

+ BI-214 609.31

46.30 1. 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 l.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 l.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 12 9. 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 6.15E-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-07

+ CM-243 103.76 23.00 7.47E-09 1.37E-07 1. 37E-07 228.18 10.60 -1. 82 E- 07 2.85E-0 7 277.60 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 Cunie MDA at 95% confidence level

9/14/2017 2:36:47PM Page 1 of7

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

Sample Description : UNITL1-SUB CDROQ/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 Geometry HOTLAB 500ml Marinelli

/

Livellme : 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 : 1.000keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/812014 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 L1-SUB-CDR-FSGS-002-SB UNIT L 1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak Net Peak NetArea Continuum FWHM (keV) start end Centroid Area Uncertainty Counts (keV)

No.

F 1 238.84 470 - 486 478.15 4.38E+02 28.22 4.00E+02 2.77 F 2 352.33 699 - 712 705.09 2.0BE+02 20.29 l. 97E+02 2.71 F 3 583.91 1159 - 1176 1168.16 l.24E+02 14.93 9.40E+Ol 3.48 F 4 609.60 1 213 - 122 8 1219.53 1. 56E+02 15.38 8.94E+Ol 2.63 F 5 662.02 1317 - 1331 132 4. 36 3 . 09E+ 02 19.56 6 .3BE+Ol 2.73 F 6 911.77 1817 - 1829 1823.78 6.41E+Ol 10 .53 4.05E+Ol 2. 62 F 7 1461.79 2 914 - 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 20.29 8.36E+01 1.86E+Ol 1. 24E+02 2.75E+Ol F 3 583. 91 l.24E+02 14.93 1. 24E+02 l.49E+Ol F 4 609.60 l.56E+02 15.38 4. 1 2E+01 l .21E +Ol 1.15E+02 1.96E+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+02 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 L1-SUB-CDR-FSGS-002-SB UNIT L1-SUB CDR 09/13/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apax\Root\Oalryland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (uCVgrams) Uncertainty CS*-137 0.97 661.65

85.12 1.77E-07 1. 77E-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 Wt mean 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 L 1-SUB-COR-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 Pagc5 of7 Analysis Report for L1-SUB..CDR-FSGS-002-SB UNIT L 1-SUB CDR 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 1 .78149E-02 16.41 Tol. 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 Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (uCUgrams) (uCUgrams) (uCUgrams)

(keV)

+ 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

+ Jco-60 1173.22 100.00 6.28E-08 5.SSE-08 6.78E-OB

_ _ _ _,,,. __ vv 1332.49 100.00 ,; ?Ol;'-f\Q 5.55E- 08

+ KR-85 513.99 0.43 1 .07E-05 9.76E-06 9.76E-06

+ Y-88 898.04 93.70 2.lOE-09 3.29E-08 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 L1-SUB CDR 09/13/17 Nuclide Energy Yield{°A) Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams) (uCi/grams)

(keV)

+ CS-134 604.70 97.60 4.48E-09 4.97E-08 5. llE-08 795.84 85.40 -l.88E-09 4.97E-08

+ I CS-137 661. 65

85.12 1.77E-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 -4.0SE-09 2.62E-07

1. 03E-07 1. 03E-07

+ ) EU-152 121.78 28.40 7.49

-6.33E-08

-2.55E-07 4.93E-07 244.69 964.00 14.44 6.84E-07 3.86E-07 1408.00 20.74 -2. 18E-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 1.56E-07

+ EU-155 86.54 32.80 5.48E-10 1.lSE-07 l. 15E-07 105.31 21. 80 2.54E-08 1. 39E-07

+ BI-214 609.31

46.30 1. 43E-07 9.13E-08 9.13E-08 1120. 29 15.10 -8.56E-08 3.81E-07 1238 .11 5.94 -1. 63E-07 l.16E-06 1377.67 4 .11 6.BOE-07 l. lOE-06 1407.98 2.48 -l .82E-07 l.66E-06 1509.19 2.19 -l .lBE-07 1. 61E-06 1764.49 15.80 2.50E-07 2.96E-07

+ PB-214 77.11 10.70 4.69E-07 1. OBE-07 4.41E-07 295.21 19.20 1. 84E-07 1. 7 6E-07 351. 92 37.20 2.95E-07 1. 08E-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-06 463.00 13.80 6.33E-08 6.22E-07 911.23 16.70 l.02E-06 7 . 55E- 07

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

+ CM-243 103.76 23.00 -8.59E-08 1. 32E-07 l.32E-07 228.18 10.60 -1.97E-07 2.62E-07 277.60 14.00 1. 94E-07 2.35E-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 2:36:47PM Pagc7 of7 Analysis Report for L1-SUB-CDR-FSGS-002-58 UNIT L1-SUB CDR 09/13/17

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

---'Apex-Gamma Analysis Report for L 1-SUB-CDR-FSGS-003-SB UNIT L 1-SUB-CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-FSGS.003-SB Sample Desaiption : UNIT L1-SUB-CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : B.792E+02 grams /

Facility : Dalryland_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 second9""

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 : 9/14/2017 3:37:37PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/14/2017 3:37:46PM Page2 of6 Analysis Report for L1-SUB-CDR-FSGS-003-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 1 238.96 472 - 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+Ol 12.63 8 .lSE+Ol 2.21 F 5 609.72 1212 - 1228 1219.77 1.36E+02 14.50 7.lSE+Ol 3.09 F 6 662 .17 1318 - 1334 1324.65 4.95E+02 23.77 7.05E+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+Ol 1.25E+Ol F 3 351.80 2.02E+02 19.92 8.36E+Ol 1. 8 6E+Ol 1.19E+02 2.73E+Ol F 4 583.42 8.85E+Ol 12.63 8 . 85E+Ol 1.26E+Ol F 5 609.72 1. 36E+02 14.50 4.12E+Ol l. 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 L1-SUB-CDR-FSGS-003-SB UNIT L 1-SUB-CDR 09/13117 NUCLIDE IDENTIFICATION REPORT Nucllde 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

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 2.0SE-08 351. 92

37.20 l.17E-07 2.69E-OB

= 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 Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty

{uCi/grams)

K-40 0.858 7.77E-06 3.83E-07

/cs-137 0.958 3.30E-07 2.26E-08

9/14/2017 3:37:46PM Page 4 of6 Analysis Report for L 1-SUB-CDR-FSGS-003-SB UNIT L 1-SUB-CDR 09/13/17 Nuclide Nuclide wtmean Wt mean 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-OB

? = 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 Pages of6 Analysis Report for L1-SUB-CDR-FSGS-003-SB UNIT L1-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 (%) Peak Tolerance Peak No. Energy (keV) 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\Library\HOTL.AB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (uCUgrams) (uCUgrams) (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 1.97E-03 1. 97£-03

+ C0-60 1173.22 100.00 8.26E-08 5.93E-08 6.69E-08 1332.49 100.00 6.49E-08 5.93E-08

+ KR-BS 513.99 0.43 l .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 -l.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 l.OlE-06 2.79E-07 3.45E-06 133.51 11.09 1.BSE-07 2.79E-07

9/14/2017 3:37:46PM Pagc6of6 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) (uCUgrams) (uCVgrams)

(keV)

+ EU-152 121.78 28.40 -7.42E-08 1. 04E-07 1.04E-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-OB 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-07 1274.51 35.50 -3.84E-08 1. 52E-07

+ EU-155 86.54 32.80 -6.28E-08 1 .20E-07 1 .20E-07 105.31 21. 80 -7.60E-09 1.46E-07

+ BI-214 609.31

46.30 l.24E-07 9. llE-08 9. llE-08 1120.29 15.10 2.86E-07 4.06E-07 1238 .11 5.94 1.65E-07 l.12E-06 1377.67 4 .11 6.SlE-07 1.0BE-06 1407.98 2 .48 1.38E-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 1. 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 2.48E-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 7.78E-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 1.40E-07 228.18 10.60 3.37E-08 2 .91E-07 277.60 14.00 1.lOE-08 2.40E-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 perform the decay correction

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

9/14/2017 4:39:55PM Page 1 of7

-~Apex-Gamma Analysis Report for L1-SUB-CDR-FSGS-004-SB UNIT L 1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-FSGS-004-SB /

Semple Description : 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 ._/

Geometry : 500ml Marinelli Live Time

3600.0 seconds Real lime : 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 Page2of7 Analysis Report for L 1-SUB..CDR-FSGS-004-SB UNIT L1-SUB COR 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 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 l.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+01 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 l. 54E+02 2.77E+Ol F 3 583.44 9.66E+Ol 13 .29 9.66E+Ol 1 .33E+O l 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 1. 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:SSPM Page4of7 Analysis Report for L 1-SUB-CDR-FSGS-004-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 ActMty Errors quoted at 1.000sigma

9/14/201i 4:39:55PM Page 3 of7 Analysis Report for L1-SUB-CDR-FSGS-004-SB UNIT L1-SUB CDR 09/13/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIOES Nuclide Id Energy Yield{°A,) 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 1.000slgma INTERFERENCE CORRECTED REPORT Nuclide Nuclide wt mean wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCUgrams)

/

CS-137 0.964 2.44E-07 7 1.98E-08 1 PB-212 0.555 2.07E-07 1 .66E-08 BI-214 0.330 1.06E-07 2.38E-08

9/14/2017 4:39:55PM Pages of7 Analysis Report for L1-SUB-CDR-FSGS-004-SB UNIT l 1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/14/2017 4:39:46PM 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 2 352.14 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~

I> '() \\

F 7 1333.32 1.20098E-02 17.30 Tol. ~ t}:1-Ub F 8 1461.79 l.79075E-01 3.98 '~~

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

},cpt; NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (uCUgrams) (uCUgrams) (uCVgrams)

(keV)

+ K-40 1460.75 10.67 7 .75E-06 1. 48E-06 1. 48E-O 6

+ AR-41 1293.64 99.16 2.9BE-03 3.29E-03 3.29E-03

+ C0-60 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 1.0lE-05 1. OlE-05 1.0lE-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 S.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 L 1-SUB COR 09/13/17 Nuclide Energy Yield(%} Activity NuclideMDA LineMDA Name (uCUgrams} (uCi/grams} (uCi/grams)

(keV)

I-131 636.97 7.27 8.18E-08 4.39E-08 5.61E-07

+ CS-134 604.70 97.60 l.13E-09 4.74E-08 4.96E-08 795.84 85.40 -4.69E-08 4.74E-08

+ CS-137 661. 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-06 133.51 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 -S. 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 1.16E-07 l.16E-07 105.31 21. 80 7.BSE-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 l.81E-06 1764.49 15.80 1. 99E-07 3.04E-07

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

+ PA-228 89.95 22.00 2.95E-07 2.44E-07 4.17E-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 2.4DE-06 338.32 5.30 1. 65E-06 1. 62E-06 463.00 13.80 1.42E-0 7 6.91E-D7 911. 23 16.70 1. 37E-06 8.62E-07

+ AM-241 59.54 36.30 -5.21E-08 2.09E-07 2.D9E-07

+ CM-243 103.76 23.00 -1.12E-07 1.32E-07 1. 32E-07 228.18 10.60 1. OSE-07 2.BlE-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 lever

9/14/2017 4:39:55PM Pagc7 of7 Analysis Report for L1-SUB-COR-FSGS-004-SB UNIT L1-SUB CDR 09/13/17

9/14/2017 5:40:49PM Page 1 of6

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

Sample Description : UNIT L 1-SUB CDR 09113/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 9.672E+02 grams

/

Facility : Oalryland_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 llme : 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 Callbration 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 1.65E+02 22.56 3.20E+02 3.65 F 3 338.84 673 - 685 678.12 7.20E+Ol 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 1.43E+02 14.96 1. 05E+02 2.65 F 6 609.43 1213- 1226 1219.20 1. 42E+02 14.95 8.65E+Ol 2.32 F 7 662.00 1316 - 1'.333 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+Ol 1. 86E+Ol 1.27E+02 2.78E+Ol F 5 583.36 1. 43E+02 14.96 1. 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 1.19E+03 36.23 6.61E+Ol 1. 27E+Ol 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+OO 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 L 1-SUB-CDR-FSGS-OOS-SB UNIT L 1-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:\Canberra\Apex\Root\Dairylend_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity 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 l.71E-08 BI-214 0.34 609.31 1120.29

46.30 1.20E-07 2.32E-08 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 1.52E-07 4.23E-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

9/14/2017 5:40:49PM Page4 of6 Analysis Report for L1-SUB-CDR-FSGS-005-SB UNIT L 1-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 1. 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 L 1-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(%) 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-Ol 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:\Canberra\Apex\Root\Dalryfand_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (uCVgrams) {uCl/grams) (uCVgrams)

(keV)

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

+ AR-41 1293.64 99.16 -3.SlE-03 4.lSE-03 4.lSE-03

+ C0-60 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. OlE-05 1.0lE-05

+ Y-88 898.04 93.70 -7.97E-11 3.47E-08 4.65E-08 1836.06 99. 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.SSE-08 5.99E-07 364.48 81.20 2.98E-08 4.SSE-08 636.97 7.27 1. lOE-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. 7 8E-08

+ CS-137 661. 65

85.12 7.85E-07 5.53E-08 5.53E-08

9/14/2017 5:40:49PM Page 6 of6 Analysis Report for L 1-SUB-CDR-FSGS-005-SB UN IT L 1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclldeMDA LineMDA Name (uCVgrams) (uCUgrams) (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 -6.0SE-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. 2 9E-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 8.41E-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 1.09E-06 1407.98 2.48 4.SBE-07 1.49E-06 1509.19 2.19 5.36E-07 1.59E-06 1764.49 15.80 3.32E-07 3.0SE-07

+ PB-214 77.11 10.70 7.0lE-07 1. 08E-07 4.45E-07 295.21

19.20 2 .43E-07 1.SBE-07 351. 92

37.20 1.14E-07 1. OSE-07

+ PA-228 89.95 22.00 7.81E-07 2.54E-07 4.38E-07 93.35 35.00 -l .70E-07 2.54E-07 105.00 16.30 2.98E-07 4.96E-07 129.22 2.97 6.87E-07 2.61E-06 338.32 5.30 1.14E-06 1. 75E-06 463.00 13.80 5.65E-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-243 103.76 23.00 9.48E-08 1. 38E-07 1. 38E-07 228.18 10.60 -1. 21E-07 2.86E-07 277.60 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 Analysis Report for L 1-SUB-CDR-FSGS-006-SB LI-SUB CDR GAMMA SPECTRUM ANALYSIS Sample Identification : L 1-SUB-CDR-FSGS-006-SB Sample Oesaiption : LI-SUB CDR 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 :30:47Ari/

Procedure : 500ml Marinelli Operator : Administrator/

Detector Name Geometry

HOTLAB /

500ml Marinelli /

Live lime : 3600.0 seconds Real lime : 3610.1 seconds Dead Time : 0.28%/

Peak Locate Threshold : 3.00 Peak Locate Range (ln 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 : 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 12:31:0BPM Page 2 of6 Analysis Report for L 1-SUB..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 1. OOE+02 15.90 l.97E+02 1. 73 F 3 352.09 700 - 710 704.61 l.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 2.07 F 5 609.71 1212 - 1225 1219.75 1. 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 - 224 7 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 2.04 F 9 1461. 79 2913 - 2 933 2923.69 5.03E+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 12:30:59PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPPIData\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 1. OOE+02 1.59E+Ol F 3 352.09 1. 69E+02 17.18 8.36E+Ol 1. 86E+Ol 8 .52E+Ol 2. 53E+Ol F 4 583.42 1. 08E+02 12.41 1. 08E+02 1.24E+Ol F 5 609.71 1. 27E+02 14.21 4.12E+Ol 1.21E+Ol 8.61E+Ol 1. 87E+Ol F 6 662 .11 8.64E+02 31.11 6.61E+Ol 1.27E+Ol 7 .98E+02 3.36E+Ol 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 2.27E+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 :08PM Page 3 of6 Analysis Report for L1-SUB-CDR-FSGS-006-58 LI-SUBCDR NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dalryland_NPP\Library\HOTlAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (uCUgrams) 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 l.78E-07 l.52E-08 BI-214 0.55 609.31

46.30 1.1 7E-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.SBE-08

=Energy line found in the specbum.

- =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 Wt mean Wtmean Comments Name Id Activity Activity Conffdence Uncertainty (uCi/grams)

CS-137 0. 967 6.35E-07 3.18E-08 PB-212 0.560 1. 78E-07 1. 52E-08 BI-214 0.554 1. 34E-07 2.31E-08

9/15/2017 12:31:0SPM Page4of6 Analysis Report for L 1-SUB-CDR-FSGS-006-SB LI-SUB CDR Nuclide Nuclide wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCUgrams)

PB-214 0. 711 l.26E-07 1. 87E-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

9115/2017 12:31:0BPM Pages of6 Analysis Report for L 1-SUB--CDR-FSGS-006-SB LI-SUB CDR UNIDENTIFIED PEAKS Peak Locate Performed on : 9/15/2017 12:30:59PM 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 4 583.42 2.99132E-02 11.53 F 8 1333.46 7.25996E-03 26.54 F 9 1461.79 1. 3962 6E-01 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\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (ke\;? (uCVgrams) (uCVgrams) (uCUgrams)

+ K-40 1460.75 10.67 6.65E-06 1. 42E-0 6 1.42E-06

+ )AR-41 1293. 64 99.16 7.74E-08 1.87E-07 1. 87E-07

+ C0-60 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. OBE-05 1.08£-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 -5.17£-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 97.60 -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 L 1-SUB-CDR-FSGS-006-SB LI-SUB CDR Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams) (uCUgrams)

(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 1. 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. 4 6E-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.SBE-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 1.81E-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 1.67E-07 1.14E-07 1. 96E-07 93.35 35.00 -3. 96E-08 l.14E-07 105.00 16. 30 1. 40E-07 2. 15E-07 129.22 2.97 1. 02E-07 1.17E-06 338.32 5.30 -9.93E-08 7.59E-07 463.00 13.80 9.87E-09 3.31E-07 911.23 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

@ = Helf-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 1 of7

~Apex-Gamma Analysis Report for L1-SUB-CDR-FSGS-007-SB UNIT L1-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 : 8.848E+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 lime : 3600.0 seconds Real Time : 3609.3 seconds Dead "Tlme : 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 : 3393 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/14/2017 6:41:35PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/14/2017 6:41:44PM Page2of7 Analysis Report for L 1-SUB-CDR-FSGS-007-SB UNIT L 1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak Net Peak NetArea Continuum FWHIJA No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.14 147 - 157 152.82 l.56E+02 2 9 .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 1 .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 1.10E+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. 7 5 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 1.86E+Ol 5.0SE+Ol 2.46E+Ol F 5 583.66 l.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 S.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 L 1-SUB CDR 09/13117 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apax\Root\Dalryland_NPP\Llbrary\HOTL.AB.NLB IDENTIFIED NUCLIDE$

Nuclide Id Energy Yield{°/o) Activity Activity Name Confidence (keV) (uCVgrams) Uncertainty K-40 0. 85 1460.75

10.67 6.78E-06 3.49E-07 CS-137 0. 98 661.65

85.12 3.44E-07 2.30E-08 PB-212 0. 95 77.11

17.50 2.53E-07 4.BlE-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 4.15E-07 7. 86E-08 295.21

19.20 1. 93E-07 2.88E-08 351. 92

37.20 4.94E-08 2.41E-OB

= 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 1.000slgma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCi/grams)

/c-40 0.852 6.78E-06 3,49E-07 S-137 0.9 81 3.44E-07 2.30E-08

9/14/2017 6:41:44PM Page4of7 Analysis Report for l 1-SUB-CDR-FSGS-007-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCVgrams}

PB-212 0.957 2.lSE-07 1. SBE-08 BI-214 0.345 1. 02E-07 2.44E-08 PB-214 0.966 1.06E-07 1. BOE-OB

? = 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 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 Peak No. Energy (keV} Peak Size (CPS) Uncertainty Type Nuclide F 5 583.66 3.06596E-02 12.16 f)..-id F 8 911.76 1 .78176E-02 15.44 Tol. ~

PA-228 F 9 1333. 32 1.72450E-02 15.54 c:r~J..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 Yield(%} Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams) (uCilgrams)

(keVJ

+ 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

+ C0-60 1173.22 100.00 9.23E-08 6.70E-08 7.83E-08 1332.49 100.00 1. OlE-07 6.70E-08

+ KR-85 513 - 9 9 0.43 l. 24E-05 9.79E-06 9.79E-06

+ 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 .BOE-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. 60 -1. 42E-08 4.93E-08 4.93E-08

9/14/2017 6:41:44PM Page6of7 Analysis Report for L 1..SUB-CDR-FSGS-007-SB UNIT L1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (uCVgrams) (uCi/grams) (uCUgrams)

(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 l.49E-07 2 .64E-07

+ EU-152 121.78 28.40 -7.32E-08 l.02E-07 l.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 l.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 2.51E-07 2.21E-07 873.20 11. 50 3.14E-07 3.93E-07 1004.76 17.90 l.31E-07 2.80E-07 1274.51 35 .50 4.24E-09 1. 42E-07

+ EU-155 86.54 32.80 -1.22E-08 l. 18E-07 l. lSE-07 105.31 21. 80 3.66E-08 l.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 l. 41E-07 l.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 l.77E-06 1764.49 15.80 l.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-07 351.92

37.20 4.94E-08 9.73E-08

+ PA-228 89.95 22.00 6.25E-07 2.47E-07 4.21E-07 93.35 35.00 6.83E-08 2.47E-07 105.00 16.30 l.57E-07 4.78E-07 129.22 2. 97 1.21E-06 2.41E-06 338.32 5.30 4.22E-07 1.64E-06 463.00 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 .45E-08 2.14E-07 2.14E-07

+ CM-243 103.76 23.00 7.BBE-08 1. 40E-07 1. 40E-07 228.18 10.60 6.22E-08 2.89E-07 277.60 14.00 -4.27E-08 2.29E-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 6:41 :44PM Page7of7 Analysis Report for L1-SU~DR-FSGS-007-SB UNIT L1-SUB CDR 09/13/17

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

Sample Description : L1-SUBCDR Sample Type : 500 ml Martnem Unit Sample Point Sample Size : 8.417E+02 grams Facility : Deiryland_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 : HOTLAB /

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 : 7/812014 Efficiency Calibration Description Sample Number : 3403 PEAK ANALYSIS REPORT Peak Analysis Perfonned 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 L1-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 1. 41E+02 25.19 5.91E+02 1. 96 F 2 238.80 473 - 485 478.07 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 1. 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+01 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 S.llE+Ol 8.05 l.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 Peak 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 17.20 8.36E+Ol 1. 86E+01 7.41E+Ol 2.53E+Ol F 5 583.83 4.93E+Ol 10.56 4.93E+Ol 1. 06E+Ol F 6 609.64 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 1. 27E+Ol 8.64E+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 8.0SE+OO F 11 1461. 7 6 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(%) Activity Activity Name Conlidence (keV) (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-OB 238.63

44.60 1. 6DE-07 1.48E-08 BI-214 0.57 609.31

46.30 5.43E-08 2.37E-OB 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 17 64. 4 9 15.80 PB-214 0.98 77 .11

10.70 3.89E-07 7.06E-08 295.21

19.20 1. 09E-D7 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 Nucllde Nuclide Wt mean Wt mean Comments Name Id Activity Activity Conffdence Uncertainty (uCl/grams)

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

9/15/2017 1:33:20PM Page4 of?

Analysis Report for L 1-SUB-CDR-FSGS-008-SB L1-SUB CDR Nuclide Nuclide wt mean wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCVgrams)

PB-212 0.992 l.62E-07 l.41E-08 BI-214 0.572 8.91E-08 2.22E-08 PB-214 0.988 9.52E-08 1. 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 Page5of7 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 (%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide 11 iot F

F F

F 10 11 5

9 583.83 1174.27 1332.99 1461. 76

1. 3702 9E-02 1.74501E-02 1 .41832E-02

21. 41

14. 97] L--;~

15. 77 VJ"""~~~?*,, "( r-~~~,'t) 1.41547E-01 4.47 ~-z.3

'(.,

M = First peak in a multiplet region m - Other peak in a multiplet region c;-o F = Fitted slnglet Enors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Llbrary\HOTLAB.NLB Nuclide Energy 'lleld(%) Activity Nuclide IIDA LlneMDA Name (uCVgrams) (uCUgrams) (uCUgrams)

{kell'.J

+ K-40 1460 .75 10.67 6.74E-06 1. 42E-O 6 1.42E-06

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

+ C0-60 1173.22 100.00 4.02E-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 1. 03E-05

+ Y-88 898 . 04 93.70 - . - _..,.

-? t;QR-nR ........ 2.68E-08 ,1

.I.*

&;c;'t'-"Q V-,1.1..1 \,I y 1836.06 99.20 -l .13E-08 2.68E-08

+ NB-94 702.63 100.00 -1 .06E-08 3.98E-08 3.98E-08 871.10 100.00 -1. 95E-08 4.34E-08

+ I-131 284.30 6.06 -l.97E-07 4. 45E-08 S .84E-07 364.48 81.20 8.39E-09 4.45E-08 636.97 7.27 -l .57E-07 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-SUB CDR Nuclide Energy Yield(%) Activity Nuct;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 2.15E-07 873.20 11.50 -4.25E-08 3.83E-07 1004.76 17.90 -l.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 l.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 1. 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 l . 14E-07 3.56E-07 295.21

19.20 1.09E-07 1.21E-07 351. 92

37.20 7.61E-08 1 .14E-07

+ PA-228 89.95 22.00 2.75E-07 l. lSE-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-07 463.00 13.80 1. 7 9E-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-07

+ 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.SlE-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

9/15/2017 1:33:20PM Page 7 of7 Analysis Report for l 1-SUB-CDR-FSGS-008-SB L1-SUB COR

9/14/2017 7:47:22PM Page 1 of5

~Apex-Gamma Analysis Report for L1-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 ml Marinelli Unit Sample Point Sample Size : 9.393E+02 grams/

Facility : Dairylend_NPP Sample Taken On : 9113/2017 1:54:00AM Acquisition Started : 9/14/2017 6:46:59PM Procedure : 500ml Marinelli Operator : Administrator Detector Name :HOTLAB /

Geometry ; 500ml Marinelli . /

LlveTrme : 3600.0 seconds Real Time : 3610.7 seconds Dead Time : 0.30 % /

Peak Locate Threshofd : 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 : 7/8/2014 Efficiency Calibration Description Sample Number ~ 3394 PEAK ANALYSIS REPORT Peak Analysis Perfonned on : 9/14/2017 7:47:13PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/14/2017 7:47:22PM Page 2 ofS Analysis Report for l 1-SUB-CDR-FSGS-009-SB UNIT L1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak NetPeak NetArea 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+D1 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 1.21E+01 1.25E+02 2.20E+Ol F 2 662.02 8.76E+03 95.22 6.61E+Ol 1.27E+Ol 8.69E+03 9.61E+D1 F 3 1173.89 3.56E+02 20.99 4.SSE+Ol 8.62E+D0 3.10E+D2 2.27E+Ol F 4 1333.30 3 .17E+02 18.48 3.17E+02 1.85E+Ol F 5 1461. 80 5.33E+D2 23.70 5.33E+02 2.37E+D1 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 L1-SUB-CDR-FSGS-009-SB UNIT L1-SUB CDR 09/13/17 Nuclide Id Energy Yield("A) Activity Activity Name Confidence (keV) (uCUgrams) Uncertainty C0-60 0.91 1173.22

100.00 3.18E-07 2.45E-08 1332.49

100.00 3.63E-07 2 .31E-08 CS-1 3 7 0.97 661. 65

85.12 6.2SE-06 l.83E-07 BI-214 0 .35 609. 31

46.30 l.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 In the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000slgma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wtmean Comments Name Id Activity Activity Confidence Uncertainty (uCi/grams) 00-60 0. 915 3.42E-07 1. 68E-08 CS-137 0.978 6.25E-06 1. 83E-07 BI-214 0.350 l.54E-07 2.74E-08

? = nuclide is µa;t 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

9114/2017 7:47:22PM Page4of5 Analysis Report for L1-SUB-CDR-FSGS-009-SB UNIT L 1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Perfonned on : 9/14/2017 7:47:13PM 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 5 1461.80 l.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 Yleld{°A.J Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams) (uCUgrams)

{keV)

+ K-40 1460.75 10.67 6.69E-06 1.34E-06 1. 34E-0 6

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

/ AR-41

+ C0-60 1173.22

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

100.00 3.63E-07 3.71E~08

+ KR-85 513.99 0.43 l.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 1. 28E-08 3 .07E-08

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

+ I-131 284.30 6.06 5.lOE-07 8.86E-08 1. 03E-06 364.48 81.20 5.95E-08 8.86E-08 636.97 7.27 5.36E-07 9.33E-07

+ CS-134 604.70 97.60 -l. 33E-08 5. 73E-OB 6.32E-08 795.84 85.40 -2 . llE-08 5.73E-08

+ ) CS-137 661.65

85.12 6.25E-06 6.86E-08 6.86E-08

+ CE-144 80.12 1.36 8.lOE-07 3.97E-07 4.12E-06 133.51 11. 09 5.78E-07 3.97E-07

9/14/2017 7:47:22PM Page 5 of5 Analysis Report for L1-SUB-CDR-FSGS-009-SB UNIT L1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclideMDA UneMDA Name (uCUgramsJ (uCilgrams) (uCl/grams)

(keV)

+ EU-152 121.78 28. 40 -1.70E-07 1.48E-07 1. 48E-07 244.69 7. 49 -9.98E-08 6.88E-07 Yi964.00 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 .0SE-07 247.94 6.60 -1. 68E-O 6 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 .0SE-07 1274.51 35.50 7 .19E-08 1. SOE-07

+ EU-155 86.54 32.80 -1. 20E-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 l.09E-07 1120.29 15.10 4.SlE-07 4.35E-07 1238.11 5.94 6.14E-07 1.13E-06 1377.67 4.11 3.62E-07 1.03E-06 1407.98 2.48 -2.82E-08 1.64E-06 1509.19 2.19 l.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. BOE-07 4.96E-07 8.19E-07 93.35 35.00 -4.02E-08 4.96E-07 105.00 16.30 -2.78E-07 9.95E-07 12 9. 22 2.97 2.64E-06 5.37E-06 338.32 5.30 1.32E-07 4,09E-06 463.00 13.80 9.46E-08 2.21E-06 911.23 16.70 1.llE-06 1.37E-06

+ AM-24t1 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-07 228.18 10.60 -1.39E-07 4.58E-07 277.60 14.00 2.99E-07 3.92E-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: MDAvalue is inconsistent with Currie MDAat 95% confidence level

9/15/2017 6:07:07AM Page 1 of6 Analysis Report for L1-SUB-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 L1-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 Marinenj/'"

1 Live Time : 3600.0 secondlt" Real Time : 3609.2 seconds Dead Tlme : 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 : 3396 PEAK ANALYSIS REPORT Peak Analysis Performed 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 NetPeak 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 multlplet region F = Fitted singlet Errors 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 Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 238.84 3 .11E+02 27.83 3.11E+02 2.78E+Ol F 2 352.22 2.17E+02 20.56 8.36E+Ol 1. 86E+Ol l.34E+02 2.77E+Ol F 3 609.79 1. 52E+02 15.26 4.12E+Ol 1. 21E+Ol l .11E+02 l.95E+Ol F 4 661.93 l.64E+03 41. 86 6.61E+Ol 1. 27E+Ol 1. 57E+03 4.37E+Ol 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-SUB-CDR-FSGS-010-SB UNIT L 1-SUB CDR 09/13/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairytand_NPP\Library\HOTI.AB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (ke\l) (uCUgrams) 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 17.50 238.63

44.60 1. 67E-07 l.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 nudide.

? = Manually edited nuclide.

@ = Energy llne 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 N.**""""'

U""IIWV' ~*..'t mes;; **u----

... I fllll:rG'fl Comments Name Id Activity Activity Confidence Uncertainty (uCi/grams)

A-40 S-137 0.910 0.988 5.40E-06 1.llE-06 3.22E-07 4.30E-08 PB-212 0 .555 1.67E-07 1. 56E-08 BI-214 0 .331 1. 34E-07 2.37E-08

9/15/2017 6:07:07AM Pagc4of6 Analysis Report for L 1-SUB-CDR-FSGS-010-SB UNIT L 1-SU B 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

9/15/2017 6:07:07AM Page 5 of6 Analysis Report for l 1-SUB-CDR-FSGS-010-SB UNIT L 1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Perfonned on : 9/15/2017 6:06:58AM 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 rn 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(%) Activity NuclldeMDA 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.SBE-01 1.SBE-01

+ C0-60 1173.22 100. 00 5.26E-08 5.78E-08 6.40E-08 1332.49 100.00 5.0SE-08 5. 78E-08

+ KR-85 513.99 0.43 1. 0 6E-05 1. OlE-05 1. OlE-05

+ Y-88 898.04 93 .70 -2.38E-09 2.61E-08 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 :L !'i3F.- 08 871.10 100.00 -l .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 -l.59E-07 6.33E-07

+ CS-134 604.70 97.60 l.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.SSE-08

+ CE-144 80.12 1.36 2.21E-06 2.67E-07 3.26E-06

9/15/2017 6:07:07AM Page6of6 Analysis Report for L 1-SUB-CDR-FSGS-010-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclideMDA LlneMDA Name (uCilgrams) (uCVgrams) (uCi/grams)

(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 2.0SE-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. OBE-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 l.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 l.52E-06 1509.19 2.19 -l.26E-07 l.4 5E-06 1764.49 15.80 2.53E-07 2.96E-07

+ PB-214 77 .11 10.70 2.34E-07 l.OBE-07 4.34E-07 295.21 19.20 2.27E-07 1.86E-07 351. 92 37.20 1.28E-07 1.0BE-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-07 129.22 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 l.06E-06

+ AM-241 59.54 36.30 7.51E-08 2.02E-07 2.02E-07

+ CM-243 103.76 23.00 1.61E-08 1. 38E-07 l.38E-07 228.18 10.60 l. lOE-08 2.93E-07 277.60 14.00 3. 57E -08 2.4 7E -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

. rd. 9/15/2017 7:22:01 AM Page 1 of6 a'Apex-Gamma Analysis Report for L 1-SUB-CDR-FSGS.011-SB UNIT L1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-FSGS-011-SB /

Sample Description : UNIT L 1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 7 .883E+02 grams Facility : Dalryland_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 ThreshoJd : 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 : 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 L 1..SUB-CDR-FSGS-011-SB UNIT L 1-SUB CDR 09/13/17 Peak Energy ROI ROI Peak NetPeak NetArea 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 l.85E+02 22.06 3.78E+02 2.68 F 4 609.55 1213 - 1228 1219.44 1.24E+02 15.17 l.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 l.51E+02 13.16 1. 90E+Ol 3.76 F 8 1461.53 2915 - 2933 2923.17 5.35E+02 23.49 1. OBE+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 Performed 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 4.55E+Ol 8.62E+OO 1.26E+02 1. 73E+Ol F 7 1333.24 1. 51E+02 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.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 7:22:01AM Page 3 of6 Analysis Report for L 1-SUB-CDR-FSGS-011-SB UNIT L1-SUB CDR 09/13117 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dalryland_NPP\Llbrary\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{°/o) Activity Activity 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 .80E-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 1. llE-07 3.18E-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 Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCUgrams)

9/15/2017 7:22:01AM Page4of6 Analysis Report for L 1-SUB-COR-FSGS-011-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Nuclide wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCi/grams)

/K-40 0.908 6.62E-06 3.92E-07

/ C0-60 0.931 1. 83E-07 1. 41E-08 CS-137 0.987 2.BOE-06 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 1. 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(%) Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams) (uCVgrams)

(keV)

+ K-40 1460.75

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

+ AR-41 1293.64 99 . 16 1. 38E-Ol 3 . 23E-01 3 . 23E-01

+ I C0-60 ll'/3.22 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 5.04E-06 1. 43E-05 1.43E-05

+ Y-88 898.04 93.70 1. 92E-09 4.55E-08 5.61E-08 1836.06 99.20 -l.13E-08 4.SSE-08

+ NB-94 702.63 100.00 7.SlE-09 4.BBE-08 4.88E-08 871.10 100.00 -2. 87E-08 5.14E-08

+ I-131 284.30 6.06 -l. 16E-0 6 7 .28E-08 8 .81E-07 364.48 81.20 4.82E-09 7 .2BE-08 636.97 7.27 -2. 75E-07 7.94E-07

+ CS-134 604.70 97.60 -1.BlE-08 6.26E-08 6.26E-08

+ ) CS-137 795.84 661. 65

85.40 85.12 4.63E-08 2.BOE-06 7.66E-08 6.26E-08 7.66E-08

+ CE-144 80. 12 1.36 2.13E-06 3.SOE-07 4.13E-06 133.51 11.09 3.71E-07 3 .SOE-07

+ EU-152 121.78 28.40 -1.20E-07 1. 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(%) Activity NuclldeMDA LlneMDA Name (uCUgrams) (uCVgrams) (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.SlE-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 l.70E-07

+ EU-155 86.54 32.80 4.09E-08 1. 47E-07 1. 47E-07 105.31 21. 80 -1.58E-07 l.82E-07

+ BI-214 609.31

46.30 l.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 1.32E-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. 48£-07 3.22E-07

+ PB-214 77.11 10.70 7 .45E-07 1. SOE-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 7.94£-07 4.49E-07 7.SBE-07 93.35 35.00 -5.0SE-08 4.49E-07 105.00 16.30 -6.42E-07 8.BlE-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 1. lSE-06 1. 78E-06 911. 23 16.70 1. 73E-06 1.40E-06

+ /AM-241 59.54 36.30 23.00 8.77E-08 8.19E-08 2 . 77E-07

1. 76E-07 2.77E-07 l.76E-07

+ CM-243 103.76 228.18 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 L 1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-COR-FSGS-012-SB /

Sample Description : UNIT L 1-SUB CDR 09/13/17 w Sample Type : 500 ml Marinelli Unit Semple 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 Time : 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 : 718/2014 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 Page2of7 Analysis Report for L 1-SUB-CDR-FSGS-012-58 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 1 238.73 469 - 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 l.19E+02 2.10 F 4 609.31 1211 - 1228 1218.95 l.17E+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+Ol 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 - 2 677 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+Ol 1. 86E+Ol 1. 05E+02 2.84E+Ol F 3 583.39 l.11E+02 13.88 1.11E+02 1. 39E+Ol F 4 609.31 l. l 7E+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 4.91E+Ol F 6 911.94 7.48E+Ol 10.99 7.48E+Ol 1.lOE+Ol F 7 1173.73 9.84E+Ol 12.56 4.55E+Ol 8.62E+OO 5.29E+Ol 1.52E+Ol F 8 1333.55 1.03E+02 11. 32 1.03E+02 1.13E+Ol F 9 1461.69 7.92E+02 28.73 7.92E+02 2.87E+Ol M = First peak in e 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 L 1..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(%) Activity Activity Name Confidence (keV) (uCUgrams) Uncertainty K-40 0.86 1460.75

10.67 9.97E-06 4.SSE-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 2.19 1764.49 15. 80

= 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 ~-"r'tmean Wt mean Comments Name Id Activity AcUvlty Confidence Uncertainty (uCUgrams)

K-40 0.869 9.97E-06 4.SSE-07

} CS-137 0.978 1. 60E-06 5.77E-08 PB-212 0.559 2.68E-07 2.02E-08 BI-214 0.350 1. OlE-07 2.47E-08

9/15/2017 8:23:16AM Page4of7 Analysis Report for L1-SUB-CDR-FSGS-012-SB UNIT L1-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

9/15/2017 8:23:16AM Page5 of7 Analysis Report for L 1-SUB-CDR-FSGS-012-SB UNIT L 1-SUB CDR 09/13/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/15/2017 8:23:07AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy {keV} Peak Size (CPS) Uncertainty 1ype Nuclide F 2 352. 00 2.90430E-02 27.16 Tol. PB-214~

F 3 583.39 3.09625E-02 12.46 -rl--id /

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

PA-228 F 7 1173.73 1.47027E-02 28.78 Tol. C0-60J~~~~

F 8 1333.55 2. 85811E-02 11. 00 Co-60 7 eu,.,..:.~

~

r~~

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\HOTL.AB.NLB Nuclide Energy Yield(%) Activity Nuclide IIDA LineMDA Name (uCUgrams) (uCVgrams) (uCVgrams)

(keV)

+ K-40 1460.75

10.67 9.97E-06 3.43E-07 3.43E-07

+ AR-41 ., "'.I" ""1 r A

. J . . £ j J . t.l':I 99.16 6.91E-02 4.52E-01

'i.~~l!.-U.L

+ / C0-60 1173.22 100 .00 1 .61E-09 7.87E-08 8.34E-08 1332.49 100.00 1. 37E-07 7 .87E-08

+ KR-85 513.99 0.43 8,99E-06 l.19E-05 1.19E-05

+ Y-88 898.04 93.70 -5 .94E-09 4.14E-08 5.lSE-08 1836.06 99.20 -1.16E-08 4.14E-08

+ NB-94 702.63 100.00 -7.02E-09 4.25E-08 4.25E-08 871.10 100.00 -3.52E-08 4.84E-08

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

9/15/2017 8:23:16AM Page 6 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 1.42E-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-OB 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 -l .18E-07 2.BlE-07 1274.51 35.50 5 .59E-08 1.72E-07

+ EU-155 86.54 32.80 -l .09E-07 1 .33E-07 1.33E-07 105.31 21. 80 -6.36E-08 l.63E-07

+ BI-214 609.31

46.30 1.0lE-07 1. OlE-07 l.OlE-07 1120. 29 15.10 3.84E-07 4.6BE-07 1238 .11 5.94 -7.38E-07 1. 25E-06 1377.67 4 .11 2.66E-07 l. llE-06 1407.98 2.48 1.13E-07 l.BSE-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 S. lBE-07 295.21 19.20 l .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 l.92E-07 4.29E-07 105.00 16.30 -2.66E-07 8.14E-07 129.22 2 .97 1.17E-06 4,45E-06 338.32 5.30 1. 46E-0 6 3.lOE-06 463.00 13.80 -1.27E-07 1.44E-06 911. 23 16.70 1.14E-06 1.33E-06

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

+ CM-243 103.76 23.00 -7.96E-08 1. 56E-07 1.56E-07 228.18 10.60 -3.09E-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-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 7 of7 Analysis Report for L1-SUB-CDR-FSGS-012-SB UNIT L 1-SUB CDR 09/13/17

t- 9/15/2017 9:25:38AM Page 1 of7

..:YApex-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 L 1--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 : Admlnlstrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 3600.0 seconds Real Time : 3609.4 seconds Dead 11me : 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 Page2of7 Analysis Report for L 1-SUB-CDR-FSGS-013-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 76.54 148 - 160 153.62 l.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 l.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 l.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+Ol F 2 238.79 2 .89E+02 25.01 2.89E+02 2.SOE+Ol F 3 338.50 7 .62E+Ol 13.81 7 .62E+Ol 1. 3 8E+ Ol F 4 351.86 1.52E+02 16.68 8.36E+Ol 1. 86E+Ol 6.81E+Ol 2.50E+Ol F 5 583.62 8.75E+Ol 12.82 8.75E+Ol 1.28E+Ol F 6 609.57 1. 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 1.27E+Ol 9.54E+Ol 1. 98E+Ol F 8 912.02 7.6DE+Ol 10.86 7.60E+Ol 1. 09E+Ol F 9 1461. 63 5.47E+02 23.75 5.63E+Ol 8.57E+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 9:25:38AM Page 3 of7 Analysis Report for L 1-SUB-CDR-FSGS-013-SB UNIT L1-SUB CDR 09/13/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Delryland_NPP\Library\HOTI.AB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (uCUgrams) 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. SOE-08 PB-212 0.98 77 .11

17.50 2.71E-07 4.84E-08 238.63

44.60 l. 66E-07 1. SOE-08 BI-214 0 .34 609.31

46.30 1.25E-07 2.45E-08 1120. 29 15 .10 1238 .11 5.94 1 377 . 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 Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCi/grams)

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 Page 4 of7 Analysis Report for L 1-SUB-CDR-FSGS-013-58 UNIT L 1-SUB CDR 09/13/17 Nuclide Nuclide wt mean wt mean Comments Name Id Activity Activity Confidence Uncertainty

{uCUgrams)

PB-212 0,982 1. 72E-07 l.44E-08 BI-214 0.344 1. 25E-07 2.45E-08 PB-214 0.518 7.37E-08 2.31E-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 9:25:38AM Page5 of7 Analysis Report for L1-SUB-CDR-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 F 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 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{%) Activity NuclideMDA LineMDA Name (uCVgrams) (uCVgrams} (uCUgrams)

(k*\.?

+ 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 2.88E-08 2.66E-08 5.46E-08 6.48E-08 5.46E-08 1332.49 100.00

+ KR-85 513.99 0.43 l.OlE-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 4.18E-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-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclideMDA LlneMDA Name (uCilgrams} (uCi/grams} (uCilgrams)

(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 -1.0SE-08 4.59E-08

+j CS-137 661. 65

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

+ CE-144 80.12 1.36 -6.14E-07 2.57E-07 3.20E-06 133.51 11. 09 -6.28E-09 2.57E-07

+ j EU-152 121.78 28.40 -1.23E-07 l.OOE-07 1.00E-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 l.8SE-07

-+ / EU-154 123.07 40.40 -4.44E-08 7.0BE-08 7.08E-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.SBE-07 1004.76 17.90 1. llE-07 2.63E-07 1274.51 35.50 -1.41E-07 1.51E-07

+ EU-155 86.54 32.80 -1. 91E-09 1. llE-07 1. llE-07 105.31 21. 80 -5.65E-08 1. 34E-07

+ BI-214 609.31

46.30 1.25E-07 8.88E-08 8.BBE-08 1120. 29 15.10 1.79E-07 3.71E-07 1238.11 5.94 l.17E-06 l.17E-06 1377.67 4.11 -1. 07E-07 9.63E-07 1407.98 2.48 1. llE-06 l .55E-06 1509.19 2.19 3.lSE-07 1.SSE-06 1764.49 15.80 3.84E-07 3.0BE-07

+ PB-214 77.11

10.70 4.43E-07 9.32E-08 3.57E-07 295.21 19.20 1. 36E-07 l.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 -4.21E-07 6.87E-07 129.22 2.97 3.39E-06 3.70E-06 338.32 5.30 3.55E-07 2.37E-06 463.00 13.80 -4.0lE-07 9.19E-07

+

J AM-241 CM-243 911.23 59.54 103.76 16.70 36.30 23.00 1.17E-06 1.43E-07

-1. SOE-08 2.02E-07

1. 2 BE-07

1. 23E-06 2.02E-07 1.28E-07 228.18 10.60 5.74E-08 2.78E-07 277.60 14.00 4.50E-08 2.20E-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 Page7 of7 Analysis Report for L1-SU B-CDR-FSGS-013-SB UNIT L 1-SUB CDR 09/13/17

9/15/201 f 10:2B:13AM Page 1 of6

'1Apex-Gamma Analysis Report for L 1-SUB-CDR-FSGS-014-88 UNIT L 1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-FSG~14-SB7 Sample Desaiption : UNIT L 1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : B.284E+02 grams /

Facility : Dalrylend_NPP

/

Sample Taken On

9/13/2017 2:18:00PM Acquisition Started : 9/15/2017 9:27:51AM Procedure : 500ml Marinelli

/

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 L1-SUB-CDR-FSGS-014-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 . 76 470 - 486 478.00 3 .11E+02 27 . 98 6 . 67E+02 2 .1 9 F 2 29 5.05 58 7 - 5 96 590.55 8 . 61E+0 1 17.43 2 . 98E+02 1.43 F 3 338 . 78 673 - 681 678.00 6.13E+Ol 15.26 2 . 00E+02 1. 42 F 4 351 . 85 698 - 71 1 70 4. 14 1 . 66E+02 20 . 87 3.07E+02 2.31 F 5 583. 5 4 1162 - 1 173 11 67 . 42 8 . 78 E+O l 1 3 . 60 1. 07E+ 02 1. 99 F 6 609.41 1211 - 1226 1219.16 9 . 92E+O l 14.18 1 . 32E+02 2 . 20 F 7 662 . 03 131 5 - 1333 1324 . 39 2 . 86E+ 0 3 54 . 78 1. 40E+02 2.38 F 8 911. 80 1816 - 1831 1823.83 7 .SBE+Ol 1 0.69 5 . l BE+Ol 2.18 F 9 1173.87 2341 - 2357 2347 . 91 1 . 03E+02 12.73 6.50E+Ol 2 . 64 F 10 1 333 . 3 7 2 660 - 2674 26 6 6 . 87 9. 7 5E+ Ol 1 0 . 96 2.27E+01 2.35 F 11 1 461. 72 2916 - 2933 2923.55 7 . 56E+02 28 . 40 3.15E+O l 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 : 9/1 5/2017 10:28:04AM Env. Background Fite : C:\Canberra\Apex\Root\Dairyland_N PP\Data\000000 1364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 238 . 76 3 . 11E+ 02 2 7. 98 3 . 11E+02 2.BOE+Ol F 2 295 . 05 8.61E+ Ol 17 . 43 8 . 61E+Ol 1. 74E+Ol F 3 338 . 78 6 . 13E+01 15.26 6.13E+Ol 1 . 53E+Ol F 4 351 . 85 1. 66E+02 20 . 87 8 .36E+O l 1. 86E+Ol 8 . 22E+Ol 2 . BOE+ Ol F 5 583 . 54 8 . 78E+Ol 13 . 60 8 . 78E+Ol 1. 36E+Ol F 6 609 . 41 9.92E+Ol 14 . 18 4.12E+Ol l . 21E+Ol 5 . 80E+Ol l . 86E+O l F 7 662 . 03 2 . 86E+03 54.78 6 . 61E+Ol 1. 27E+ Ol 2 . 79E+ 03 5 . 62E +Ol 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 . 55E+Ol 8.62E+OO 5 .80E+Ol l .54E+Ol F 10 1333 . 37 9 . 75E+O l 10.96 9.75E+Ol 1. l OE+O l F 11 1461 .72 7.56E+02 28 . 40 7 . 56E+0 2 2 . 84E+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 10:28:13AM Page4of6 Analysis Report for L 1-SUB-CDR-FSGS-014-SB UNIT L1-SUB CDR 09/13117 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCi/grams)

)<-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 l.94E-07 1. BlE-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 Page3 of6 Analysis Report for L 1-SUB-CDR-FSGS-014-SB UNIT L 1-SUB CDR 09/13/17 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) (uCVgrams) Uncertainty K-40 0 .8 6 14 60 .75

10 .67 9.96E-06 4.65E-07 C0-60 0. 90 1173.22

100.00 6.73E-08 1 .7 9E-08 1332.49

100 . 00 1. 27E- 07 l.46E-08 CS-137 0 . 97 661. 65

85.12 2.28E-06 7.68E-08 PB-212 0 .55 77.1 1 17 .50 238 . 63

44.60 1. 94E- 07 1.81E-08 BI-214 0.34 609 .31

4 6. 30 8.06E-08 2 . 60 E- 08 1120 . 29 15.10 1238.11 5.94 1 377.67 4.11 1407.98 2 . 48 15 09.19 2.19 1764.49 1 5.80 PB-214 0.72 77 . 11 10.70 295 . 21

19.20 1. 49E-07 3 . 03E- 08 351. 92

37 . 20 8.57E-08 2 . 92E-08 AC-228 0.30 209 . 28 4.40 338 . 32

11.40 2 . 0lE-07 5.04E-08 7 94 .7 0 4 . 60 911 . 60

2 7.70 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 INTERFERENCE CORRECTED REPORT

9/15/2017 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(%) 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:\Canbarra\Apex\Root\Dairyland_NPP\Llbrary\HOTLAB.NLB Nuclide Energy Y,eld{°.lo) Activity Nuclide IIDA Line IIDA Name (uCVgrams) (uCUgrams) (uCVgrams)

(keV}

1460.75 10.67 9 . 96E-06 4.78E-07 4.78E-07

+ K-40 *

+ 1293.64 99.16 1. BOE-01 l.02E+OO 1. 02E+OO

~-41 1173.22 100. 00 6. 73E-08 3.83E-08 7.20E-08

+ C0-60

1332.49

100.00 l.27E-07 3.83E-08

+ KR-85 513 .99 0.43 l. lBE-05 1. 27E-05 1.27E-05

+ Y-88 898.04 93.70 -4.0lE-09 2.75E-08 5.88E-08 1836.06 99.20 -2.92E-08 2.75E-08

+ NB-94 702.63 100.00 -2 .SBE-08 4.21E-OB 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 6.05E-08

/cs-137 661. 65 85.12 2.2BE-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 L1-SUS.CDR-FSGS-014-SB UNIT L1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity NuclldeMDA L/neMDA Name (uCVgrams) (uCUgrams) (uCVgrams)

(kellJ

+ 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.SlE-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 -1.0BE-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 8.06E-08 1.14E-07 1 . 14E-07 1120.29 1 5.10 2 .73E-08 4.57E-07 1238.11 5.9 4 3.61E-07 1. 36E-06 1377.67 4 . 11 -l.66E-07 1.lSE-06 1407.98 2.48 4.48E-07 l. 70E-06 1509.19 2.19 6.90E-07 1. 89E-06 1764.49 15.80 1.70E-07 3 .2 3E-07

+ PB-214 77.11 10.70 9 .62E-07 l.26E-07 5.50E-07 295.21

19.20 l.49E-07 1. 53E-07 351. 92

37.20 8.57E-08 1.26E-07

+ PA-228 89.95 22 .00 1.17E-06 4.78E-07 8.15E-07 93.35 35.00 -2.61E-08 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 l.51E-06

+ ~-241 59.54 36 .3 0 l. lSE-07 2 . 63E- 07 2 .63E-07

+ CM-243 103. 76 23.00 6.0BE-08 l.66E- 07 1.66E-07 228.18 10.60 -2 . 69E-08 3.70E-07 277.60 14.00 -2.78E-07 3.1 7E-07

.. == Energy

+ Nudide identified during the nuclide identification 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

9/15/20H 11:29:40AM Page I of6

__..3Apex-Gamma Analysis Report for L 1-SUB-COR-OSGS-014-SB UNIT L 1-SUB CDR 09/13/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L1-SUB-CDR-OSGS-014-SB . /

Sample Description : UNIT L1-SUB CDR 09/13/17 Sample Type : 500 ml Marinelli Unit Semple Point Sample Size : 8.946E+02 grams

/

Facility : Dalrylend_NPP Sample Taken On : 9/13/2017 2:30:00PM /

Acquisition Started : 9/15/2017 10:29:18AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB /

Geometry : 500ml Marinelli Live lime : 3600.0 seconds Real lime : 3610.1 se7s Dead 1lme : 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 Callbration Used Done On : 7/812014 Efficiency Calibration Used Done On : 7/812014 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 Page2of6 Analysis Report for L 1-SUB-CDR-OSGS-014-SB UNIT L1-SUB CDR 09/13/1 7 Peak Energy ROI ROI Peak NetPeak NetAtea Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 209 .15 415 - 426 418.79 6 . 42E+Ol 17 .8 9 3.40E+02 1. 82 F 2 238.68 4 72 - 485 477.83 3 _63E+02 26. 5 1 4.34E+02 1. 98 F 3 295 . 03 582 - 596 590.51 9.36E+Ol 17 . 09 2.74E+02 1. 97 F 4 352.22 697 - 710 704.87 1 .75E+02 17.64 1. 86E+02 1. 92 F 5 583.62 11 58 - 1174 1167.57 l . 25E+02 14.25 1.13E+02 2 . 09 F 6 609.57 1210 - 1226 1219.48 1. 28E+02 14 . 35 1 . 04E+02 2.17 F 7 662 . 07 1318 - 1333 1324 .45 4.47E+02 22.78 7 .93E+Ol 2 .43 F 8 911. 96 1818 - 1830 1824 . 15 8.23E+Ol 11. 64 4.68E+Ol 2.59 F 9 969 . 83 1935 - 1945 1939.89 3 . 28E+Ol 8.82 5 . 30E+Ol 1. 71 F 10 1121. 23 2236 - 2248 22 42.65 3 .44E+Ol 8.57 4.80E+ Ol 1. 77 F 11 1461.73 2913 - 2933 2923.58 8.39E+ 02 29 . 32 1. 05E+Ol 2.75 M = First peak in a multiplet region m = Other peak in a multiplet region F = Frtted 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\Oalryland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 209 .1 5 6.42E+Ol 17.89 6.42E+Ol l. 79E+Ol F 2 238 . 68 3.63E+02 26 .51 3.63E+02 2.65E+Ol F 3 295 . 03 9 . 36E+Ol 17 . 09 9 . 36E+Ol l.71E+Ol F 4 352.22 1. 7 5E+02 17.64 8 . 36E+Ol 1 .8 6E+O l 9 .l OE+Ol 2.56E +Ol F s 583 . 62 l . 2SE+ 02 14.25 1.25E+02 1.43E+Ol F 6 609.5 7 l.28E+02 14 . 35 4 .1 2E+O l 1. 21E+Ol 8 . 7 2E+Ol 1. 88E+Ol F 7 662 . 07 4.47E+02 2 2 .7 8 6.61E +Ol 1. 27E+Ol 3 . 8 1E+0 2 2.61E+Ol F 8 911. 96 8.2 3E+Ol 1 1 . 64 8 . 23E+Ol l . 16E+O l F 9 969 . 83 3.28E+O l 8 .8 2 3 . 28E +Ol 8 . 82E+OO F 10 1121. 23 3 . 44E+Ol 8.57 3 . 44E+Ol 8.57E+00 F 11 1461. 73 8.39E+02 29 . 32 8 . 39E+02 2 . 93E+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 11 :29:40AM Page4 of6 Analysis Report for L 1-SUB-CDR-QSGS-014-SB UNIT L1-SUB CDR 09/13/17 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCi/grams)

/K-40 o.sso l. 02E-05 4.56E-07

/ CS-137 0.973 2.88E-07 2.12E-08 PB-212 0.560 2.09E-07 1.62E-08 BI-214 0.556 1.30E-07 2.25E-08 PB-214 0 .712 1.16E-07 1. BSE-08 AC-228 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 Page3 of6 Analysis Report for L 1.SUB-COR-QSGS-014-SB UNIT L 1-SUB COR 09/13/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dalrytand_NPP\l.ibrary\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (uCVgrams) Uncertainty K-40 0 .85 1460.75

10.67 1. 02E- 05 4.56E- 07 CS-137 0.97 661. 65

85.12 2 .8 8E-07 2.12E-08 PB-212 0.56 77.11 17.50 238 .63

44.60 2.09E-07 1. 62 E- 08 BI-214 0 . 55 609.31

46.30 l .12E-07 2.44E- 08 1120.29

15.10 2 . 35E- 07 5 . 89E-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. 2 0 l .SOE-07 2.76E-08 351. 92

37.20 8 . 79E-08 2.49E-08 AC-228 0.41 209 . 28

4.40 3 . 40E-07 9.52E-08 338.32 11. 40 794.70 4 . 60 911 . 60

27.70 2.55E-07 3.65E-08 964 . 60 5. 20 969 .11

16.60 l.79E-07 4.84E-08

=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 INTERFERENCE CORRECTED REPORT

9/15/2011 11:29:40AM PageS of6 Analysis Report for L 1-SUB--COR-QSGS-014-SB UNIT L1..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(%) 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 NUCLIDE MDA REPORT Nuclide Library Used : C:\Canbena\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuclide MDA LineMDA Name (uCVgnms) (uCVgrams) (uCVgrams)

(keV}

+ K-40 1460.75

10.67 1.02E-05 2.80E-07 2.SOE-07

+ AR-41 1293.64 99.16 9.0BE-02 1.37E+OO 1. 37E+OO

+ C0-60 1173.22 100.00 -1.70E-OB 5.BOE-08 7 .06E-08 1332.49 100.00 7.49E-08 5.BOE-08

+ KR-85 513.99 0.43 l.12E-05 1.03E-05 l .03E-05

+ Y-88 898. 04 93.70 2.02E-08 3.32E-08 5.52E-08 1836. 06 99.20 -1. 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 6.24E-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 5.20E-08

+ CS-137 661. 65

85.12 2.88E-07 5.59E-08 5.59E-08

+ CE-144 80.12 1.36 3.69E-06 2.85E-07 3.47E-06 133.51 11. 09 2 .93E-08 2.BSE-07

9/1512017 11:29:40AM Page6 of6 Analysis Report for L 1..SUB-CDR-QSGS-014-SB UNIT L 1-SUB CDR 09/13/17 Nuclide Energy Yield(%) Activity Nuc/ldeMDA LlneMDA Name (uCVgrams) (uCVgrams) (uCVgrams)

(lceV)

+ EU-152 121.78 28.40 -1. SOE-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 1408.00 20.74 1.18E-07 1. 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 1004.76 17.90 8.06E-08 3.0lE-07 1274. 51 35.50 -9. llE-08 l.70E-07

+ EU-155 86.54 32.80 -4.64E-08 l . 20E-07 1. 20E-07 105.31 21. 80 1.30E-07 1.48E-07

+ BI-214 609.31

46.30 l.12E-07 9.96E-08 9.96E-08 1120.29

15.10 2.35E-07 2.74E-07 1238 . 11 5. 94 8.llE-07 l.26E-06 1377.67 4. 11 -7 .59E-07 9.99E-07 1407.98 2.48 9.90E-07 1.61E-06 1509.19 2.19 9.lSE-08 1. 50E-06 1764.49 15.80 3.37E-08 2.46E-07

+ PB-214 77.11 10.70 4 .71E-07 1 . 00E-07 4.66E-07 295.21

19.20 1. SOE-07 l.52E-07 351. 92

37.20 8.79E-08 1.00E-07

+ PA-228 89.95 22.00 5 .69E-08 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 8.51E-08 l.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-08 1. 41E-07 1. 41E-07 228.18 10.60 4.56E-08 2.92E-07 277 . 60 14.00 1.35E-07 2.37E-07

+ = Nudide 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

9/15/2011' 1:44:16PM Page 1 of8

__JfApex-Gamma Analysis Report for CDR # 4 SOIL GAMMA SPECTRUM ANALYSIS Sample Identification : CDR#4 /

Sample Description : 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 Marineni /

Live lime : 3600.0 seconds Real lime : 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 : 6/3f2014 Efficiency Calibration Used Done On : 61312014 Efficiency Calibration Description : 1.5 Marfnelll Sample Number : 3406 PEAK ANALYSIS REPORT Peak Analysis Perfonned on : 9/15/2017 1:44:07PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 .:44;16PM Page2 of8 Analysis Report for CDR#4 SOIL Peak Energy ROI ROI Peak NetPeak NetArea Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

M 1 75.84 146 - 194 152.52 6.13E+02 47.50 l.91E+03 3.08 m 2 83.67 146 - 194 168.20 1. 57E+02 40.98 2.38E+03 3.10 m 3 87.48 146 - 194 175.82 2.20E+02 41.82 2.37E+03 3.11 m 4 92.32 146 - 194 185.49 4.33E+02 44.29 2.25E+03 3.12 F 5 185.65 367 - 376 372.22 2.39E+02 35.12 1. 31E+03 1. 40 F 6 209 . 29 413 - 428 419.51 1.81E+02 38.84 1. 85E+03 2.20 F 7 238.33 468 - 486 477.61 1.17E+03 43.90 1.77E+03 1.52 F 8 294.96 586 - 605 590.92 3.96E+02 30.35 1.54E+03 1. 27 F 9 351. 56 696 - 710 704.15 8.61E+02 36.92 9.09E+02 1.49 F 10 510.41 1013 - 1029 1021. 97 2.37E+02 25.97 6.37E+02 2.15 F 11 582.78 1135 - 1172 1166.77 3.91E+02 25.44 9.19E+02 1. 74 F 12 608.94 1207 - 1226 1219.10 6.07E+02 30.06 5.52E+02 1.84 F 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 15 768.00 1532 - 1542 1537.35 6.13E+Ol 12.63 1. 51E+02 1.33 M 16 785.61 1564 - 1595 1572.57 3.84E+Ol 11.20 1.34E+02 1. 81 m 17 794.64 1564 - 1595 1590.65 4.53E+Ol 11. 79 1.17E+02 1.82 F 18 859. 77 1711 - 1726 1720.96 5.87E+Ol 11.71 1. 40E+02 1. 61 F 19 910.62 1814 - 1833 1822.70 3.34E+02 21.98 2.16E+02 2.43 F 20 933.14 1860 - 1875 1867.76 4.46E+01 13.47 1.83E+02 2.23 F 21 968.26 1926 - 1948 1938.03 1.93E+02 19.34 2. 72E+02 2.95 F 22 1119 . 78 2232 - 2247 2241.18 1.84E+02 18.32 l.80E+02 2.49 F 23 1172.67 2334 - 2357 2347.01 5.19E+02 25.74 2.37E+02 2.42 F 24 1237.19 2471 - 2488 2476.10 4.79E+Ol 11.15 2.16E+02 1. 58 F 25 1331. 84 2653 - 2675 2665.49 4.62E+02 23.72 1.44E+02 2.69 F 26 1460.12 2908 - 2933 2922.16 4.11E+03 64.78 8.77E+Ol 2.83 F 27 1728.96 3454 - 3466 3460.08 2.74E+Ol 7.37 2.25E+Ol 2.79 F 28 1763.88 3520 - 3538 3529.95 1.40E+02 12.93 2.63E+Ol 3.16 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 Perfonned on ; 9/15/2017 1:44:06PM Env. Background File : C:\Canberra'\Apex\Root\Oiaryland_NPP\Oata\0000003388.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

M 1 75.84 6.13E+02 47.50 6.13E+02 4.75E+Ol

9/15/2017 1:44:16PM Page 3 of8 Analysis Report for CDR#4 SOIL Peak Energy Original Orig.Area Ambient Backgr. Subtracted Subtracted No. (lceV) Area Uncertainty Background Uncert. Area Uncert.

m 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+OO 3.82E+02 4.SlE+Ol F 5 185.65 2.39E+02 35.12 3.67E+Ol 8.25E+OO 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+OO 1.14E+03 4.44E+Ol F 8 294.96 3.96E+02 30.35 1. OOE+Ol 5.91E+OO 3.86E+02 3.09E+Ol F 9 351. 56 8.61E+02 36.92 2.24E+Ol 5.47E+OO 8.39E+02 3.73E+Ol F 10 510 . 41 2.37E+02 25.97 1.52E+02 8.lOE+OO 8.55E+Ol 2.72E+Ol F 11 582.78 3.91E+02 25.44 2.14E+Ol 4.78E+OO 3.69E+02 2.59E+Ol F 12 608.94 6.07E+02 30.06 2.18E+Ol 4.83E+OO 5.86E+02 3.04E+Ol F 13 661.17 1. 31E+04 115.77 1. 38E+Ol 4.37E+OO 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+01 12.63 6.13E+Ol 1.26E+Ol M 16 785.61 3.84E+Ol 11.20 3.84E+01 1. 12E+Ol m 17 794.64 4.53E+Ol 11.79 4.53E+Ol 1.18E+01 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+OO 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 l.93E+02 l.93E+Ol F 22 1119.78 1. 84E+02 18.32 1. 09E+Ol 3.21E+OO 1.73E+02 1. 86E+Ol F 23 1172.67 5.19E+02 25.74 5.19E+02 2.57E+Ol F 24 1237.19 4.79E+Ol 11.15 4.79E+Ol 1.llE+Ol F 25 1331.84 4.62E+02 23.72 4.62E+02 2.37E+Ol F 26 1460.12 4.11E+03 64.78 5.78E+Ol 4.59E+OO 4.06E+03 6.49E+Ol F 27 1728.96 2.74E+Ol 7.37 2.74E+Ol 7.37E+OO F 28 1763.88 1. 40E+02 12.93 1. 38E+Ol 2.34E+OO 1.27E+02 1. 31E+Ol M :: First peak in a multiplet region m :: Other peak In a multiplet region F = Fitted singlet Errors quoted at 1.000slgma NUCLIDE IDENTIFICATION REPORT 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-40 0.92 1460.81

10.67 6.62E+OO 2.12E-Ol C0-60 0. 94 1173.22

100.00 7.78E-02 4.28E-03

9/1512017 1:44:16PM Page 4 of8 Analysis Report for COR#4 SOIL Nuclide Id Energy Vleld{%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty C0-60 0.94 1332.49

100 . 00 7.58E-02 4.35E-03 CS-137 0.96 661. 65

85.12 1.52E+OO 4.33E-02 BI-212 0.78 727.17

11. BO 7.86E-02 1.24E-02 785.42

2.00 2.13E-Ol 6.24E-02 1620. 56 2. 75 PB-212 0.57 77.11 17.50 87.20

6.30 2.96E-01 5.70E-02 89.80 1. 75 238.63

44.60 1. 48E-01 6 . 91E-03 300.09 3.41 BI-214 0.74 609.31

46.30 1.18E-Ol 6.9SE-03 768.36

5.04 1. 33E-Ol 2.75E-02 806.17 1.23 934.06

3.21 1. 75E-01 S.31E-02 1120.29

15.10 l.66E-01 1.82E-02 1155.19 1. 69 1238.11

5.94 1.26E-01 2 . 94E-02 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-01 4.63E-02 1764.49

15.80 1. 54E-01 1.67E-02 1847.44 2.12 PB-214 0.56 74.81 6.33 77 .11 10.70 87.20

3.70 5.04E-01 9.71E-02 89 . 80 1. 03 241. 98 7.49 295.21

19.20 1. 26E-Ol 1. 06E-02 351 . 92

37.20 l .53E-01 7.BOE-03 785. 91

1.10 3.SBE-01 l .13E-Ol RA-226 0.95 186.21

3.28 3.35E-O l 6.03E-02

"' 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 confldenoe index threshold = 0.30 Errors quoted at 1.000sigma INTERFERENCE CORRECTED REPORT

9/15/2017 1:44:16PM Page S of8 Analysis Report for CDR # 4 SOIL Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCUgrams)

)<-40 0.927 6.62E+00 2.12E-Ol

/ C0-60 0.945 7.68E-02 3.05E-03 X ~D-109 0.953

/ CS-137 0.964 l.52E+OO 4.33E-02 BI-212 0.785 8.07E-02 1.22E-02 PB-212 0.577 1.48E-01 6.86E-03 BI-214 0.743 1.29E-01 5.72E-03 PB-214 0.563 1.45E-01 6.25E-03 RA-226 0 . 9!:il 3 .35E- 01 6.03E-02

? = 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

9/1512017 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(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide M 1 75 . 84 l.70261E-Ol 7.75 Tol. TL-2087' rn 2 83.67 4.35682E-02 26.13 rn 4 92.32 l.06140E-01 11.81 Tol. TH-23 /

TH-2, F 6 209.29 5.01650E-02 21.51 Tol. AC-2 F 10 510 . 41 2.37633E-02 31.80 ,1'L"l,cJ F 11 582.78 1.02623E-01 7.01 Tol. TL-20rl' m 17 794.64 l.25842E-02 26.03 Sum F 18 859 . 77 1.62969E-02 19.96 Tol. TL-208 ~

F 19 910. 62 8. 89174E-02 6.96 Tol. AC-228..)

F 21 968.26 5.36037E-02 10.02 Tol. AC-2 2 8 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma r o~c c; \ ,b\:)

NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Library\ENVLIB.NLB Nuclide Energy Vleld(%) Activity NuclideMDA LineMDA Name (pCVgrams) {pCVgrams) (pCVgrams)

(keV)

+ K-40 1460.81

10.67 6.62E+OO 1. 20E-01 1. 20E-01

+ MN-54 834.83 99.97 7.04E-03 1.25E-02 1. 25E-02

+ C0-60 1173.22

100.00 7.78E-02 1.32E-02 1.56E-02 1332.49

100.00 7.58E-02 1. 32E-02

9/15/2017 1:44:16PM Page7 of8 Analysis Report for CDR#4 SOIL Nuclide Energy Y,eld{%) Activity NuclldeMDA LinellDA Name (pCVgrams) (pCUgrams) (pCVgrams)

(lreV)

+ ZN-65 1115.52 50.75 5.17E-02 3.64E-02 3.64E-02

+ KR-85 513.99 0.43 3.78E+OO 3.76E+OO 3.76E+OO

+ CD-109 88.03

3.72 5.0lE-01 5.22E-01 5.22E-01

+ CS-134 604.70 97.60 6.77E-02 1.47E-02 1. 81E-02 795.84 85.40 -3.86E-04 l .47E-02

+ CS-137 661. 65

85.12 1.52E+OO 1.63E-02 l.63E-02

+ EU-154 123.07 40.40 -3.09E-02 4.09E-02 4.09E-02 722. 30 20.00 4.82E-02 5.98E-02 873.20 12.09 5.84E-02 1. 05E-01 996.30 10.34 3.74E-02 1.36E-01 1004. '/6 17. 90 7. 97E-03 7.99E-02 1274.51 34. 40 1. 78E-02 4.57E-02

+ EU-155 8 6. 54 32. 80 2.25E-02 8.03E-02 8.03E-02 105.31 21. 80 -4.75E-02 8.44E-02

+ TL-208 72.80 2.02 -l.98E+ll 4 . 17E+09 4. 08E+ll 74.97 3.41 -7.84E+l0 2. 24E+ll 84.90 1.51 -l.49E+12 3.67E+ll 277.36 6.31 -9.98E+08 5.34E+l0 583.19 84.50 -8.66E+08 4.17E+09 763.13 1.81 l.42E+ll 1. 60E+ll 860 .56 12.42 l.57E+l0 2 . 44E+10 1093.90 0.40 -1.40E+ll 8. 72E+ll

+ BI-214 609.31

46 . 30 1.1 8E-Ol 3.00E-02 3.00E-02 768.36

5.04 1. 33E-01 1.41E-Ol 806.17 1.23 -5.23E-Ol 9.40E-01 934.06

3. 21 1.75E-01 3.lSE-01 1120.29

15.10 1.66E-Ol 7.75E-02 1155.19 1. 69 1.llE+OO 1.03E+OO 1238.11

5.94 1. 2 6E-Ol 2.38E-01 1280.96 1.47 -2.SSE-02 1.0lE+OO 1377.67 4.11 2.SlE-01 3.0SE-0 1 1401. 50 1.39 9.18E-01 8.78E-01 14 07 .98 2.48 5.49E-01 5.06E-01 1509.19 2.19 -l.lSE-01 4.81E-0 1 1661.28 1.15 7. l SE-02 6.54E-01 1729.60

3.05 1. 71E-Ol 1. 75E-01 1 76 4.49

15.80 1.54E-01 4.49E-02 1847.44 2.12 1. 65E-Ol 4.00E-01

+ PB-214 74.81 6.33 -l.89E-Ol 3.16E-02 5.40E-01 77.11 10.70 -6.07E-02 2.96E-Ol 87.20

3.70 5 .04E-01 5.25E-01 89-80 1.03 6.53E+OO 2 .41E+O O 241. 98 7.49 -2.16E-Ol 2.41E-01 295.21

19.20 1. 26E-Ol 8. 06E-02 351. 92

37 .20 1.53E-01 3.16E-02 785.91

LlO 3.88E-01 5. 72E-01

+ RA-223 81.07 15.00 4.66E-02 l.03E-01 1.90E-01 83.78 24 .80 -4.02E-01 1.03E-01 94.90 11.30 -1. 32E-03 l.97E-01 122.31 1.19 -5.76E-01 1.40E+OO

9/15/2017 1:44:16PM Page 8 of8 Analysis Report for CDR#4 SOIL Nuclide Energy Yield(%) Activity NuclldeMDA L/neMDA Name (pCVgrams) (pCVgrams) (pCUgrams)

(keV)

RA-223 144.20 3.26 2.71E-01 1. 03E-Ol 4.SOE-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.SOE-01 444.94 1.27 -5.49E-02 1. 29E+OO

+ RA-226 186.21

3.28 3.35E-Ol 3.06E-01 3.06E-Ol

+ AC-228 129.08 2.80 2.35E-02 6.lOE-02 5.80E-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-Ol 338.32 11. 40 -6.52E-02 1. 33E-Ol 409.51 2.13 -2.91E-01 7.49E-Ol 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 l.32E-Ol 1. OOE-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 -1 .53E+Ol 1.12E+Ol 168.10 0.07 -1. 80E+Ol 2.13E+Ol

+ PA-234M 766.36 0.29 8.50E-01 1.68E+OO 4.30E+OO 1001.03 0.84 -9.96E-02 1.68E+OO

+ TH-234 63.29 4.50 -5.89E-01 8.98E-Ol 1 .17E+OO 92.38 2. 60 -4.28E-02 9.03E-01 92.80 2.60 5.55E-02 8.98E-01

+ AM-241 59.54 36. 30 -4.43E-02 1. 88E-01 1. 88E-01

+ CM-243 99. 55 14 .30 4.73E-02 8.12E-02 1. 42E-Ol 103.76 23.00 -4. 81E-03 8.12E-02 117.00 10.80 6.37E-02 l.58E-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

9115/2017 3:31:44PM Page 1 of8 l"Apex-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 /

Livellme : 3600.0 seconds .

Real Time : 3625.3 seconds Dead Time : 0.70%/

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 : 6/312014 Efficiency Calibration Used Done On : 6/3/2014 Efficiency Cellbration Description : 1.5 Marinelli Sample Number : 3408 PEAK ANALYSIS REPORT Pook Analysis Perfonned on : 9/15i2017 3:31:34PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/15/2017 3:31 :44PM Page2 of8 Analysis Report for CDR-NRC-5 SOIL Peale Energy ROI ROI Peale NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.56 146 - 160 153 . 96 4.64E+02 40.86 l.68E+03 2.09 M 2 86.73 166 - 190 174.32 1. 43E+02 29.09 1.23E+03 1. 60 m 3 92.42 166 - 190 185 . 71 2.77E+02 35.25 l.30E+03 1. 61 F 4 1 85.72 364 - 381 372 . 35 2.78E+02 32.30 l.79E+03 1. 49 F 5 208.87 415 - 427 418.68 1. 39E+02 30.50 1.22E+03 1. 74 M 6 238.29 468 - 489 477.54 1. 24E+03 42.78 7.07E+02 1.48 m 7 241. 31 468 - 489 483.58 3.03E+02 27.27 7.52E+02 1.49 F 8 270.16 535 - 559 541.31 l.54E+02 28.25 1.54E+03 2.01 F 9 2 94.88 582 - 596 590 . 76 4.26E+02 31.11 9.76E+02 1. 45 F 10 337.88 666 - 686 676.78 2.84E+02 27.12 1. 01E+03 1. 74 F 11 351. 56 697 - 708 704.15 8.40E+02 35 .87 6.00E+02 1.54 F 12 463.05 923 - 933 927.22 8.39E+Ol 16.74 4.34E+02 0.94 F 13 510.51 1015 - 1032 1022.18 2.70E+02 25.58 5.07E+02 2.49 F 14 582.80 1158 - 1173 1166.81 4 . 10E+02 25.28 3 .40E+02 1. 70 F 15 608.95 1209 - 1228 1219.13 6.96E+02 31. 1 5 4.41E+02 1. 95 F 16 661.17 1312 - 1332 1323.61 6.69E+03 83.05 3.32E+02 1. 94 F 17 726 . 44 1449 - 1460 1454.20 7.94E+Ol 14.17 1. 72E+02 1. 57 M 18 785.03 1567 - 1595 1571.42 5.58E+Ol 11.48 1. 04E+02 1.48 m 19 794.59 1567 - 1595 1590.54 5.78E+Ol 11. 66 l.15E+02 1. 48 F 20 860.18 171 6 - 1730 1 721. 79 5 . 54E+Ol 13.78 l . 59E+02 2 . 43 F 21 910.61 1814 - 1831 1822.68 3.B9E+02 23.72 2 . 22E+02 2.32 F 22 968.51 1933 - 1946 1938 .52 l.79E+02 17.96 2.15E+02 1. 62 F 23 1119.80 2234 - 2248 2241. 23 l.24E+02 16.42 2.33E+02 1. 75 F 24 1172.71 2336 - 2354 2347.08 5.BOE+02 28.30 2.81E+02 2.37 F 25 1237 . 59 2471 - 2485 2476 . 90 6.78E+Ol 15 . 04 2 .06E+02 2.20 F 26 1331.93 2 654 - 2674 2665.67 5.35E+02 25.18 l.13E+02 2.55 F 27 1377 . 06 2748 - 2762 2755.96 5.87E+Ol 10.47 5.41E+Ol 2.59 F 28 1460.14 2908 - 2931 2922.20 4.26E+03 66.08 7.84E+Ol 2.84 F 29 1728.88 3453 - 3468 3459.92 3.64E+Ol 7 . 53 1.47E+Ol 3.39 F 30 1763 . 78 3519 - 3539 3529.75 l.78E+02 14.22 2.61E+Ol 3.35 F 31 1846.75 3689 - 3702 3695.76 2.31E+Ol 5.98 1. 75E+ Ol 1. 78 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 Perfooned on : 9/15/2017 3:31 :34PM Env. Background File : C:\Canberra\Apex\Root\Diaryland_NPP\Data\0000003388.CNF

9/15/2017' 3:31:44PM Page 3 of8 Analysis Report for CDR-NRC-5 SOIL Peak Energy Original Orig.Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background 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 l.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+01 6.41E+OO 1. 21E+03 4.33E+Ol m 7 241. 31 3.03E+02 27.27 3.03E+02 2 .73E+Ol F 8 270.16 1.54E+02 28 .25 1.54E+02 2.82E+Ol F 9 294.88 4.26E+02 31.11 1 .00E+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 l.52E+02 8.10:b:+00 l.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 . 1 5E+Ol F 16 661.17 6 . 69E+03 83.05 1. 38E+Ol 4.37E+OO 6.67E+03 8.32E+Ol F 17 726 .44 7.94E+01 14. 17 7.94E+Ol 1. 42E+Ol M 18 785.03 5.58E+Ol 11.48 5.58E+Ol l. lSE+Ol rn 19 794.59 5 . 78E+Ol 11.66: 5. 78E+Ol l.17E+Ol F 20 860.18 5 .54E+Ol 13.78 . 5.54E+01 1.38E+Ol F 21 910. 61 3.89E+02 23.72 '* l.35E+Ol 3.68E+O O 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 1.67E+Ol F 24 1172.71 5. 80E+0 2 28.30 5 .80E+0 2 2.8 3E +Ol F 25 123 7.59 6. 78E+Ol 15.04 6.78E+O l 1 .SOE+Ol F 26 1331. 93 5.35E+02 25.18 5.35E+02 2.52E+Ol F 27 1377 .06 5 .87E+Ol 10.47 5.87E+Ol 1.0SE+Ol F 28 1460.14 4.26E+03 66.08 5.78E+Ol 4 . 59E+OO 4.2 0E+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+01 F 31 1846.75 2.31E+Ol 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 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Library\ENVLIB.NLB IDENTIFIED NUCLIDES

9/15/2017 3:31:44PM Page 4 of8 Analysis Report for CDR-NRC-5 SOIL Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K-40 0.93 1460.81

10. 67 6,37E+OO 2.03E-01 C0-60 0.95 1173.22

100.00 8.07E-02 4.39E-03 1332.49

100.00 8.lSE-02 4,37E-03 661. 65 85.12 7.16E-01 2.14E-02 CS-137 0.96

6.56E-02 1.lBE-02 BI-212 0.72 727 .17

11. 80 785.42

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 l.81E-01 3.74E-02 89.80 1. 75 238.63

44.60 l.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. OlE-01 1. SlE-02 1155.19 1. 69 1238.11

5.94 1.65E-01 3.69E-02 1280.96 1. 47 1377.67

4.1 1 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. BSE-01 1. 73E-02 1847.44

2.12 l.97E-01 5.16E-02 PB-21 4 0 . 86 74.81 6.33 77.11

10.70 4.55E-Ol 4.30E-02 87.20

3.70 3.0BE-01 6.36E-02 89.80 1.03 241. 98

7.49 2.18E-01 2.04E-02 295.21

19.20 1.26E-01 l.OlE-02 351.92

37.20 1.39E-01 7.04E-03 785.91

1.10 5.22E-01 1.0BE-01 RA-226 0.96 186.21

3.28 3.70E-Ol 5 .21E-0 2 AC-228 0. 62 129.08 2.80 209.28

4.40 1. 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 2.81E-02 794.70

4.60 1. 30E-01 2.65E-02 911.60 27 .70 1. 56E-01 1.0SE-02 964.60 5.20 969.11 16.60 1.30E-01 1. 33E-02 1587.90 3.71

9/15/201Y 3:31 :44PM Page 5 of8 Analysis Report for CDR-NRC-5 SOIL

= 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 Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams) 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 l. 16E-02 PB-212 0.862 1. 4 6E-01 6.16E-03 BI-214 0.699 l.34E-Ol 5.66E-03 PB-214 0.863 l .4 2E-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

? = 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 1.000si~

9/15/2017 3:31:44PM Page6of8 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 (%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide m 3 92.42 6.27712E-02 16.06 Tel. TH-234 TH-234 F 13 510.51 3.27971E-02 22.73 Sum 1L~o\

F 14 582.80 1.08031E-01 6.61 1L"J..4)'b F 20 860.18 1. 53864E-02 24.87 /Jl,"kl, M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma t~~

NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Library\ENVLIB.NLB Nuclide Energy Yield(%) Activity Nuclide &fDA LlneMDA Name (pCVgrams) (pCVgrams) (pCVgrams)

(keV}

+

,;K-40 "

. MN-54

. - \

1460.81 834.83

10.67 99.97 6.37E+OO 9.27E-03

1. 05E-Ol 1.20E-02 l.OSE-01

1. 20E-02

+A C0-60 1173.22 1332.49

100.00 100.00 8.07E-02 8.lSE-02 1.06E-02 1.45E-02

1. 0 GE-02

3.48E-02

+ ZN-65 1115.52 50.75 6.71E-02 3.4BE-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 6.09E-01

+ CS-134 604.70 97.60 6.lSE-02 1. 41E-02 1. 63E-02 I 795.84 85.40 6.70E-04 1. 41E-02

+ CS-137 661.65

85.12 7.16£-01 1. 27E-02 1. 27E-02

+ EU-154 123.07 40.40 -5.76E-03 3.56E-02 3.56E-02 722.30 20.00 5.97E-02 5.83E-02 873.20 12.09 6.0BE-02 1.02E-Ol

9/15/201} 3:31:44PM Page7of8 Analysis Report for CDR-NRC..S SOIL Nuclide Energy Yield{°,{,) Activity NuclldeMDA LineMDA Name (pCl/grams) (pCVgrams) (pCVgrams)

(lr*VJ EU-154 996.30 10.34 -1.34E-02 3.56E-02 1. 30E-Ol 1004.76 17.90 -8.41E-03 7.63E-02 1274 .51 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+10 l.47E+09 1. 42E+ll 74.97 3.41 2.39E+ll 7.85E+l0 84.90 1.51 -l.67E+l0 1.26E+ll 277.36 6.31 2.88E+09 1. 76E+10 583.19 84 .50 4.38E+09 l.47E+09 763.13 1.81 -1.19E+10 5.63E+10 860.56 12.42 -4 .48E+09 8.85E+09 1093.90 0.40 8.67E+10 3.27E+ll

+ BI-214 609.31

46.30 l.26E-01 2.SOE-02 2.SOE-02 768.36 5.04 -1. 24E-02 2.29E-Ol 806.17 1.23 1.21E-01 9.24E-01 934.06 3.21 2.58E-Ol 4.26E-Ol 1120. 29

15. 10 1.0lE-01 7.94E-0 2 1155.19 1. 69 2.79E-01 9.55E-01 1238.11

5.94 1. 65E-01 2.02E-01 1280.96 1.47 1. 20E+OO 1. 02E+OO 1377.67

4.11 2.23E-01 1. 66E-01 1401. 50 1.39 6.98E-01 8.45E-Ol 1407.98 2.48 5.63E-01 4.77E-Ol 1509.19 2.19 -6.26E-02 4.12E-01 1661.28 1.15 3.86E-Ol 6.29E-Ol 1729.60

3. 05 2 . llE-01 1. 42E-01 1764.49

15. 80 1.BSE-01 4.27E-02 1847.44

2.12 1. 97E-01 2.18E-01

+ PB-214 74.81 6.33 l.47E+OO 2,25E-02 4.82E-Ol 77.11

10.70 4.55E-Ol 2.27E-01 87.20

3.70 3 . 0BE-01 3.57E-Ol 89.80 1.03 -7. 13E-02 2.14E+OO 241.98

7.49 2.lBE-01 9.36E-02 295.21

19.20 1. 2 6E-Ol 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 -l.19E-02 9.03E-02 94.90 11.30 -9.60E-02 1. 75E-01 122.31 1.19 1 .62E-Ol 1 .22E+OO 144.20 3.26 -2.SSE-01 4.07E-Ol 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-01 444.94 1.27 -3.66E-01 l .OOE+OO

+ RA-226 186.21

3.28 3.70E-01 3.93E-01 3.93E-Ol

+ AC-228 129.08 2.80 1.67E-01 3.85E-02 5.0GE-01 209.28

4.40 l.62E-01 2.22E-01 270.23

3.60 2.39E-Ol 4.14E-01

9/15/2017 3:31:44PM Page8of8 Analysis Report for CDR*NRC-5 SOIL Nucllde Energy Yield(%) Activity NuclideMDA LlneMDA Name (pCilgrams) (pCVgrams) (pCVgrams)

(keV)

AC-228 327.64 3.20 -3.64E-02 3.85E-02 3.86E-Ol 338.32 11.40 1. 49E-01 1. lOE-01

5.72E-01 409 . 51 2 .13 2.SOE-01 463.00 4.40 1. 39E-Ol 1. 81E-01

1.19E-01 794.70

4.60 l.30E-Ol 911. 60

27.70 1.56E-01 3.85E-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.SSE-01

+ Th-230 12.30 8.43 O.OOE+OO 1. OOE+Ol 8.40E+l0 67.60 0.37 -8.74E+OO 1.00E+Ol 168.10 0.07 9.74E+OO 1. 81E+Ol

+ PA-234M 766.36 0.29 4.58E-01 l.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 92.38 2.60 -2.22E-02 8.04E-Ol 92.80 2.60 -l.39E-Ol 7.95E-01

+ IAM-241 59.54 36.30 14.30

-1.lOE-03

-1.20E-01

1. 62E-01 7.llE-02 1.62E-01 1.26E-01

+ CM-243 99. 55 103.76 23.00 -8.41E-02 7. llE-02 117.00 10.80 4.03£-05 1.36E-01 228.18 10.60 -6.94E-02 1.21E-01 277.60 14.00 -1.71E-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

911512lJ , f 4:32:58PM Page 1 of8

_JtApex-Gamma Analysis Report for CDR-NRC-6 SOIL GAMMA SPEqTRUM ANALYSIS Sample Identification : CDR-NRG-6 /

Sample Description : SOIL Sample Type : Silt Unit Sample Point Sample Size : 3.087E+03 grams /

Facility : Diaryland_NPP Sample Taken On : 9/15/2017 1:05:00PM/

Acquisition Started : 9/15/2017 3:32:19PM Procedure : Slit Operator : Administrator /

Detector Name : DE1"01-ENV .,/

Geometry

1.5l MarineUi /

Livellme : 3600.0 seconds Real Time : 3625.2 seconds Dead lime : 0.70%)

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 : 6/312014 Efficiency Calibration Used Done On : 6/3/2014 Efficiency Calibration Description : 1.5 Merinelll 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 Page2of8 Analysis Report for CDR-NRC-6 SOIL Peak Energy ROI ROI Peak NetPeak NetArea Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

M 1 7 4.55 143 - 160 149 . 95 2. 62E+02 2 8 . 86 9 . 64E+02 1.32 m 2 7 6.90 143 - 160 154 . 64 3.23E+02 3 0.62 9.54E+02 1. 33 M 3 87.01 171 - 191 174 . 88 1. 05E+02 2 6. 70 9.93E+02 1.27 m 4 92.53 171 - 1 91 185 . 9 2 2. 60E+02 31. 79 9.13E+02 1.28 F 5 185.59 365 - 380 372.10 3.32E+02 31.29 1 .58E+ 03 1. 24 F 6 238 . 29 468 - 486 477.54 1. 1 1E+03 41. 84 1. 69E+03 1.34 F 7 269.72 53 5 - 549 540.42 1 . 74E+02 29 . 82 9.19E+ 02 2 . 28 F 8 2 94. 81 585 - 597 590 . 62 4.52E+02 31. 32 8.41E+02 1. 45 M 9 327.86 653 - 686 656 . 74 7 . 76E+Ol 19. 5 9 4 .67E+02 1.56 m 10 338.0 2 653 - 686 677.06 2.60E+02 25.56 4 . 68E+02 1. 57 F 11 351. 55 699 - 709 704.14 9.17E+02 36 . 18 4.64E+02 1. 60 F 12 46 2 .67 921 - 9 31 926 . 45 9.02E+Ol 21 . 68 4.82E+02 1. 65 F 13 510.59 1014 - 1029 1022.33 2. 91E+02 26.02 4.46E+02 2.58 F 14 582.75 1157 - 1171 1166.71 4.14E+02 25 .64 3.51E+02 1. 75 F 15 608.86 1210 - 1225 1218.94 7.16E+02 31.00 3.24E+02 1. 94 F 16 661.16 1313 - 1332 1323.59 6.71E+03 83.27 3.37E+02 1. 94 F 17 726.75 1 450 - 1460 1454.81 9.37E+Ol 15.05 1. 45E+02 1. 89 F 18 793.79 1582 - 1594 1588.93 3.54E+Ol 11. 72 1 .72E+02 1. 46 F 19 910.67 1814 - 1831 1822 . 79 3.54E+02 22.09 2 .02E+02 2.05 F 20 968.21 1925 - 1945 1 93 7 . 92 2 . 1 7E+02 19 . 36 2 . 18E+02 2 .89 F 21 1119.86 2233 - 2251 2241. 34 1.95E+02 18.85 1.97E+02 2.82 F 22 117 2. 62 2 340 - 2355 2346.92 3.12E+02 22.28 2.22E+02 2.36 F 23 1237.66 24 71 - 2482 2477.05 4.87E+Ol 1 3.30 1.77E+02 1. 63 F 24 1331. 94 2653 - 267 5 2665.67 3.36E+02 20.47 1.38E+02 2.49 F 25 1460.06 2 908 - 2931 292 2 . 03 4.29E+03 66. 2 6 6.95E+Ol 2.86 F 26 1587.51 3169 - 3183 3177.04 3.60E+Ol 8.53 3.36E+Ol 3.14 F 27 1729 . 18 3455 - 3466 3460.52 2.97E+ Ol 6.46 8.52E+ OO 2.93 F 28 1763 . 93 3521 - 353 9 3530.05 1 .58E+02 1 2.98 9 .25E+OO 3.39 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 4:32:48PM .

Env. Background File : C:\Canberra\Apex\Root\Dlaryland_NPP\Oata\0000003388.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

M 1 74 .55 2.62E+02 28.86 7.82E+Ol 9.57E+OO 1.84E+02 3.04E+Ol

9/15/201 t 4:32:58PM Page 3 of8 Analysis Report for CDR-NRC-6 SOIL Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

m 2 76.90 3.23E+02 30.62 3.23E+02 3. 06E+Ol M 3 87.01 1.05E+02 26. 70 1. 05E+02 2.67E+Ol m 4 92.53 2.60E+02 31. 79 5.07E+Ol 8 . 63E+OO 2.09E+02 3.29E+01 F 5 185.59 3.32E+02 31.2 9 3.67E+Ol 8.25E+OO 2.95E+02 3.24E+Ol F 6 238.29 1.11E+03 41. 84 3.14E+Ol 6.41E+OO l.08E+03 4.23E+Ol F 7 269.72 1. 74E+02 29.82 1. 74E+02 2.98E+Ol F 8 294.81 4.52E+02 31.32 l. OOE+Ol 5.91E+OO 4.42E+02 3.19E+Ol M 9 327.86 7 . 76E+Ol 19.59 7 .76E+Ol 1. 96E+Ol m 10 338.02 2.60E+02 25.56 9.67E+OO 5. 86E+OO 2.51E+02 2.62E+Ol F 11 351.55 9.17E+02 36.18 2 .24E+Ol 5.47E+OO 8 . 95E+02 3.66E+Ol F 12 462.67 9.02E+Ol 21.68 9.02E+Ol 2.17E+Ol F 13 510.59 2.91E+02 26.02 1. 52E+02 8.lOE+OO 1. 39E+02 2.73E+Ol F 14 582.75 4.14E+02 25.64 2.14E+Ol 4.78E+OO 3.92E+02 2.61E+Ol F 15 608.86 7.16E+02 31. 00 2.lBE+Ol 4.83E+OO 6.94E+02 3.14E+Ol F 16 661.16 6.71E+03 83.27 l.38E+Ol 4 . 37E+OO 6.69E+03 8.34E+Ol F 17 726.75 9.37E+Ol 15.05 9.37E+Ol 1.51E+Ol F 18 793.79 3.54E+01 11.72 3.54E+Ol 1. l 7E+Ol F 19 910 . 67 3.54E+02 22.09 l .35E+Ol 3.68E+OO 3.41E+02 2.24E+Ol F 20 968.21 2.17E+02 19.36 2.17E+02 1. 94E+Ol F 21 1119 . 86 1.95E+02 18.85 1. 09E+Ol 3.21E+OO 1. 84E+02 1. 91E+Ol F 22 1172.62 3.12E+02 22.28 3.12E+02 2.23E+Ol F 23 1237.66 4 . 87E+Ol 13.30 4.87E+Ol 1. 33E+Ol F 24 1331. 94 3.36E+02 20.47 3.36E+02 2.0SE+Ol F 25 1460.06 4.29E+03 66.26 5.78E+Ol 4 . 59E+OO 4.23E+03 6.64E+Ol F 26 1587.51 3,60E+Ol 8.53 3.60E+Ol 8.S3E+OO F 27 1729.18 2.97E+Ol 6.46 2.97E+Ol 6.46E+OO F 28 1763. 93 1. 58E+02 12.98 1.38E+Ol 2.34E+OO 1. 44E+02 l.32E+Ol

=

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\Diaryland_NPP\Ubrary\ENVUB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{%} Activity Activity Name Confidence (keV) (pCVgrams} Uncertainty K-40 0 .91 1460.81

1 0 .67 6.53E+OO 2 .0BE-01 C0-60 0 .94 1173.2 2

100 . 00 4.42E-02 3 . 33E-03

9/15/2017 4:32:58PM Page4of8 Analysis Report for CDR-NRC-6 SOIL Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty C0-60 0.94 1332.49

100.00 5.21E-02 3.44E-03 CS-137 0.96 661. 65

85.12 7.31E-01 2.18E-02 BI-212 0.57 727.17

11.80 7.88E-02 l.28E-02 785.42 2.00 1620.56 2.75 PB-212 0.87 77 .11

17.50 1.95E-Ol 1. 96E-02 87.20

6.30 1. 34E-01 3.45E-02 89.80 1. 75 238.63

44.60 1.32E-01 6.22E-03 300.09 3.41 BI-214 0 . 63 609.31

46.30 1.32E-01 7.0lE-03 768.36 5.04 806.17 1.23 934.06 3.21 1120.29

15.10 1. 67E-01 1. 78E-02 1155.19 1. 69 1238.11

5.94 1. 21E-Ol 3.31E-02 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 l.75E-01 3.BSE-02 1764.49

15.80 1. 65E-01 1.60E-02 1847.44 2.12 PB-214 0.79 74.81

6.33 3.33E-01 5.62E-02 77.11

10.70 3.20E-Ol 3.21E-02 87.20

3.70 2.28£-01 5.BBE-02 89.80 1.03 241.98 7.49 295.21

19.20 1. 36E-Ol 1.04E-02 351.92

37.20 1. SSE-01 7.37£-03 785.91 1.10 RA-226 0.94 186.21

3.28 4.60E-01 5.21E-02 AC-228 0.62 129.08 2.80 209.28 4.40 270.23

3.60 2.76E-01 4.78E-02 327.64

3.20 1. SlE-01 3.82E-02 338.32

11.40 1. 39E-01 1. 49E-02 409.51 2.13 463.00

4.40 1.53E-01 3.69E-02 794.70

4.60 8.13E-02 2.70E-02 911. 60

27.70 l.44E-01 9.96E-03 964.60 5.20 969 .11

16. 60 1. 60E-Ol l.47E-02 1587.90

3.71 1.68E-Ol 4.00E-02

9/15/201 t 4:32:58PM Pages ors Analysis Report for CDR-NRC-6 SOIL

= Energy Hne 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 Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCUgramsJ

) K-40 0. 91 3 6.53E+OO 2.0BE-01 ljC0-60 0.949 4. BOE-02 2. 3 9E-03 CS-137 0.9 63 7.31E-01 2.lBE-02 BI-212 0. 573 7.88E-02 1. 2 8E-02 PB- 21 2 0.874 1. 28E-01 5.8 6E-03 BI-214 0. 630 1. 41E-Ol 5 . 87E-03 PB-214 0.793 1. 48E-Ol 5 .86E-03 RA- 22 6 0 . 940 4.60E-01 5.21E-02 AC-22 8 0 . 629 1. 46E-01 6.SBE-03

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

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

9/15/2017 4:32:58PM Pagc6of8 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 )

m 4 92 .53 5.81850E-02 15.73 Tol. TH-234 * /

TH-234 F 13 510.59 3.85520E-02 19.64

~~

F 14 582 . 7 5 1.09028E-Ol 6.65 ,;Ji.Po M = First peak in a multiplet region m = Other peak in a multiplet region F = Frtted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Library\ENVLIB.NLB Nuclide Energy Yield(";(,) Activity NuclldeMDA LlneMDA Name (pCVgrams) (pCVgrams) (pCVgrams)

(keV}

+ K-40 1460.81

10.67 6.53E+OO 1.0lE-01 l.OlE-01

+ MN-54 834.83 99.97 9.19E-03 1.18E-02 l.18E-02

+ C0-60 1173.22

100.00 4 . 42E-02 1.23E- 02 l.25E-02 1332.49

100.00 5 .21E-02 1. 23E-02

+ ZN-65 1115.52 50.75 3.SlE-02 3.43E-02 3.43E-02

+ KR-85 513.99 0.43 6.72E+OO 3.18E+OO 3 . 18E+OO

+ 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-Ol 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 . 6SE-02 5.87E-02 873.20 12.09 - 2 .99E-Ol 1.0lE-01 996.30 10.34 -4.0SE-02 1. 24E-Ol

9/15/201l 4:32:58PM Pagc7 of8 Analysis Report for CDR*NRC-6 SOIL Nuclide Energy Yield(%) Activity NuclideMDA LlneMDA Name (pCVgrams) (pCVgrams) (pCVgrams)

(lreV)

EU-154 1004.76 17.90 1. 48E-02 3.59E-02 7.SlE-02 1274.51 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+l4 7. 79E+13 7 .43E+l5 74.97 3.41 1. 02E+l6 4.07E+l5 84.90 1.51 -4.78E+l4 6.64E+l5 277.36 6.31 6.57E+l3 9.30E+l4 583.19 84.50 2.00E+l4 7.79E+13 763.13 1. 81 4.15E+l5 3.0lE+lS 860. 56 12.42 3.44E+l4 4.58E+l4 1093.90 0.40 9.66E+l4 l.62E+16

+ 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 2.36£-01 4.07E-Ol 1120.29

15. 10 1.67E-Ol 8.06E-02 1155.19 1. 69 2.71E-02 9.60E-Ol 1238.11

5.94 1. 21E-01 1. 79E-01 1280.96 1. 47 6 . 64E-01 9.83E-Ol 1377.67 4.11 2.BOE-01 2.95E-01 1401.50 1.39 5.24E-Ol 8.24E-Ol 1407.98 2.48 2.53E-01 4.59E-01 1509.19 2.19 -6.92E-01 4.13E-Ol 1661.28 1.15 1.52E-Ol 5.72E-Ol 1729.60

3.05 1.75E-Ol l.OSE-01 1764.49

15. 80 1.65E-01 2.98E-02 1847.44 2.12 2.lOE-01 3.57E-Ol

+ PB-214 74.81

6.33 3.33E-Ol l.98E-02 2.78E-Ol 77.11

10.70 3.20E-Ol 1. 45E-Ol 87.20

3.70 2.28E-Ol 3.26E-01 89.80 1.03 4.71E+OO 2.13E+OO 241. 98 7.49 -2.31E-Ol 2.17E-01 295.21

19.20 1.36E-Ol 4.96E-02 351. 92

37.20 1. SSE-01 l.98E-02 785.91 1.10 8.02E-01 1.09E+OO

+ RA-223 81. 07 15 .00 -1.16E-02 9.lSE-02 1.69E-Ol 83.78 24.80 -6.54E-03 9.lSE-02 94.90 11.30 -2.93E-02 1.75E-01 122.31 1.19 -3.00E-01 1.23E+OO 144.20 3. 2 6 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+OO

+ RA-226 186.21

3.28 4.60E-Ol 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-Ol 270.23

3.60 2.76E-Ol 2.73E-Ol 327 . 64

3 . 20 1 . SlE-01 2.0lE-01

9/15/2017 4:32:58PM Page 8 of8 Analysis Report for CDR-NRc.6 SOIL Nuclide Energy Yield(%) Activity Nuclide IIDA LlneMDA Name (pCVgrams) (pCUgrams} (pCUgrams)

(keV)

AC-228 338.32

11.40 1.39E-Ol 3.74E-02 5.BSE-02 409.51 2.13 2.23E-02 5.94E-Ol 463.00

4.40 1.53E-01 1. 93E-Ol 794.70

4.60 8.13E-02 1.67E-Ol 911. 60

27.70 l.44E-01 3.74E-02 964.60 5.20 6.74E-01 3.07E-01 969.11 16.60 1.60E-01 7.03E-02

l.64E-01 1587.90

3.71 1. 68E-01

+ Th-230 12.30 8.43 O.OOE+OO 9.95E+OO 8.54E+10 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 7.96E-Ol 1. OSE+OO 92.38 2.60 -4.59E-02 8.03E-01 92.80 2 .60 -4 .74E-02 7.96E-Ol

+ AM-241 59.54 36.30 1.89E-02 1. 69E-01 l.69E-01

+ CM-243 99.55 14.30 6.llE-03 7.21E-02 l.27E-Ol 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 1. 24E-01 277.60 14.00 -2.16E-02 9.04E-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

9/15/2017 5:34:40PM Page 1 of8 2 ~x-Gamma Analysis Report for CDR-NRC-7 SOIL GAMMA SPECTRUM ANALYSIS Sample Identification : CDR-NRC-7 Sample Description ; SOIL Sample Type : Silt Unit Sample Point Sample Size : 3.139E-+03 grams/

Facility : Diaryland_NPP Sample Taken On : 911512011 1:1s:oopif Acquisition Started : 9/15/2017 4:34:00PM Procedure : Slit Operator : Administrator Detector Name : DET01-ENV /

Geometry : 1.5L Marinelli /

Live Time : 3600.0 seconds Real Time : 3624.9 seconds Dead1ime : 0.69 %

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 : 6/3/2014 Efficiency Calibration Used Done On : 6/3/2014 Efficiency Calibration Description : 1.5 Marinelli Sample Number : 3410 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/15/2017 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 Peak Energy ROI ROI Peak NetPeak NetArea Continuum FWHM No. {keV) start end Centroid Area Uncertainty Counts (keV)

F 1 50.30 98 - 108 101. 43 8.43E+Ol 22.78 8.57E+02 0.98 M 2 74.48 144 - 160 149.82 2.46E+02 26.24 7.47E+02 1.32 m 3 76.78 144 - 160 154.40 3.45E+02 28.97 7.37E+02 1.33 F 4 185.67 363 - 378 372.26 l.95E+02 23.70 l.02E+03 1.03 F 5 238.32 469 - 486 477.61 l.19E+03 40.94 9.46E+02 1.47 F 6 270.04 535 - 547 541. 06 l.05E+02 20.01 5.21E+02 1.40 M 7 294.83 586 - 609 590. 67 4.42E+02 27.07 3.17E+02 1.60 m 8 299.61 586 - 609 600.21 1.32E+02 17.88 3.41E+02 1. 61 M 9 327.95 652 - 681 656.91 4.54E+Ol 14.06 2.67E+02 1.25 m 10 337.92 652 - 681 676. 86 2.33E+02 21.29 2.54E+02 1.27 F 11 351.55 697 - 714 704.13 8.43E+02 32.85 4.24E+02 1.52 F 12 462.91 921 - 932 926. 93 1.02E+02 15.71 1.94E+02 1. 65 F 13 510.42 1015 - 1031 1022.00 3.39E+02 23.68 2.5BE+02 2.72 F 14 582.72 1159 - 1172 1166.63 4.11E+02 24.09 1. 99E+02 1. 68 F 15 608.83 1212 - 1224 1218.89 6.1SE+02 28.56 2.00E+02 1. 93 F 16 661.22 1319 - 1328 1323.70 3.74E+02 23.31 1. 60E+02 1. 78 F 17 726.75 1449 - 1462 1454.81 l.02E+02 14 . 29 l.47E+02 1. 77 F 18 767.48 1532 - 1542 1536.31 3.45E+Ol 11.50 l.43E+02 1.43 F 19 794.12 1581 - 1598 1589.60 4.82E+Ol 11. 76 1. 80E+02 1. 67 F 20 859.83 1709 - 1728 1721. 08 9.29E+Ol 14.48 1.53E+02 2.94 F 21 910.67 1815 - 1831 1822.79 3.55E+02 21.90 l.55E+02 2.36 F 22 932.46 1858 - 1875 1866.40 6.66E+Ol 13.25 1.50E+02 2.47 M 23 963.98 1923 - 194 6 1929. 46 5.57E+Ol 11. 42 l.31E+02 1. 90 m 24 968.41 1923 - 1946 1938.32 1.72E+02 16.86 l.47E+02 1. 90 F 25 1119.68 2230 - 2248 2240.97 l.70E+02 17 .11 2.04E+02 2.07 F 26 1376.66 2747 - 2762 2755.16 6.25E+Ol 10.29 3.79E+Ol 3.99 F 27 1460.03 2908 - 2932 2921.97 3.95E+03 63.68 9.56E+Ol 2.78 F 28 1508.39 3014 - 3025 3018.73 1. 59E+Ol 5.26 2.68E+Ol 1. 62 F 29 1728.74 3453 - 3465 3459.63 2.45E+Ol 6.25 1. 94E+Ol 1. 64 F 30 1763.90 3521 - 3538 3529.99 1.22E+02 12.09 2.70E+Ol 2.52 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 Performed on : 9/15/2017 5:34:31PM Env. Background File : C:\Canberra\Apex\Root\Oiaryland_NPP\Oata\0000003388.CNF

9/15/2017 5:34:40PM Page3 of8 Analysis Report for COR-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+Ol 22.78 8.43E+Ol 2.28E+Ol M 2 74.48 2.46E+02 2 6. 24 7. 82E+01 9.57E+OO l.68E+02 2.79E+01 m 3 76.78 3.45E+02 28.97 3.45E+02 2 .90E+01 F 4 185.67 1 .95E+02 2 3 . 70 3.67E+Ol 8.25E+OO 1.59E+02 2.51E+Ol F 5 238.32 1.19E+03 40.94 3.14E+Ol 6.41E+OO 1 .16E+03 4.14E+ Ol F 6 270.04 l.05E+02 20.01 1 . 05E+02 2.00E+O l M 7 294.83 4.42E+02 27.07 l.OOE+Ol 5.91E+ OO 4.32E+02 2.77E+O l m 8 299.61 1.32E+02 17.88 1.32E+02 1.79E+Ol M 9 327.95 4.54E+Ol 14.06 4.54E+ Ol 1.41E+01 rn 10 337.92 2.33E+02 21 .29 9.67E+OO 5 .86E+ OO 2.23E+02 2.21E+Ol F 11 351.55 8.43E+02 32.85 2.24E+Ol S. 47E+00 8.21E+02 3.33E+Ol F 12 462.91 1.02E+02 15.71 l.02E+02 1. 57E+O l F 13 510.42 3.39E+02 23.68 l.52E+02 8.lOb:+00 1. 87E+02 2.SOE+Ol F 14 582.72 4 . 11E+02 24 . 09 2.14E+Ol 4 . 78E+OO 3.90E+02 2. 4 6E+Ol F 15 608 . 83 6 . 15E+02 28.56 2.18E+Ol 4 . 83E+ OO 5.93E+02 2.90E+O l F 16 661. 22 3.74E+02 23.31 1.38E+Ol 4.37E+OO 3.60E+02 2 . 37E+Ol F 17 726.75 1.02E+02 14.29 1.02E+02 1. 4 3E+O l F 18 7 67 .48 3.45E+Ol 11.50 3 .45E+ Ol 1.15E+01 F 19 794 . 12 4 . 82E+Ol 11. 76 4 .82E+Ol l.18E+Ol F 20 859.83 9.29E+Ol 14.48 9.29E+Ol 1. 45E+Ol F 21 910.67 3.55E+02 21. 90 1. 35E+Ol 3.68E+OO 3.4 2E+02 2.22E+O l F 22 932.46 6 . 66E+O l 13.25 6.66E+O l l.32E+Ol M 23 963 . 98 5.57E+01 11.42 5.57E+Ol 1.14E+Ol m 24 968.41 1.72E+02 16.86 1. 7 2E+0 2 1. 69E+ Ol F 25 1119. 68 1. 70E+02 17.11 1. 09E+Ol 3. 21E+0 0 1.59E+02 1. 7 4E+Ol F 26 1376.66 6.25E+Ol 10.29 6.25E+Ol 1. 03E+ Ol F 27 1460.03 3.95E+03 63.68 5.78E+Ol 4 . 59E+OO 3 .89E+03 6. 3 9E+Ol F 28 1 5 08 . 39 1. 59E+Ol 5 .26 1. 59E+ Ol 5.26E+OO F 29 1728.74 2.45E+Ol 6.25 2.4 5E+Ol 6. 2 5E+ OO F 30 1763. 90 1 . 22E+02 1 2 .09 1 . 3 8E+Ol 2 . 3 4E+ OO 1.08E+02 l. 2 3E+Ol 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\Diaryland_NPP\Library\ENVUB.NLB IDENTIFIED NUCLIDES

9/15/2017 5:34:40PM Page4of8 Analysis Report for CDR-NRC-7 SOIL Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty 1460.81 10.67 5.90E+OO 1.90E-01 K-40 0.90

2.75E-03 CS-137 0.97 661. 65

85.12 3.87E-02 BI-212 0.57 727.17

11. 80 8.44E-02 1.20E-02 785.42 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

3.13E-02 300.09

3.41 2.26E-01 BI-21 4 0.64 609.31

46.30 l.llE-01 6.24E-03 768.36

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

1. 44E-02 1764.49

15.80 1. 22E-Ol 1847.44 2.12 74.81 6.33 3.00E-01 5.09E-02 PB-214 0 . 72

3.0SE-02 77.11

10.70 3 .36E-01 87.20 3.70 89.80 1.03 241. 98 7.49 295.21 19.20 l.31E-01 9.0lE-03

6.61E-03 351.92

37.20 1.40E-Ol 785. 91 1.10 3.28 2.43E-Ol 3.91E-02 RA-226 0.95 186.21

AC-228 0. 67 129.08 2.80 209.28 4.40 270. 23

3.60 1.63E-01 3.lSE-02 327.64 3.20 8.68E-02 2.70E-02

1.24E-02 338. 32

11. 40 l.22E-01 409.SJ. 2.13 463.00 4.40 1. 69E-01 2.65E-02

2.67E-02 794.70

4.60 1. 09E-01 911.60

27.70 1. 42E-Ol 9.73E-03 964.60

5.20 1. 29E-Ol 2.65E-02 969.11 16.60 l .25E-01 1. 25E-02 1587.90 3.71

9/15/2017 5:34:40PM Page S of8 Analysis Report for COR-NRC-7 SOIL

= 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 (pCi/grams)

K-40 0.906 5.90E+OO 1. 90E-Ol

/ CS-1 3 7 0.970 3 . 87E*02 2.75E-03 BI-21 2 0.573 8.44E-02 l.20E-02 PB-212 0.8 26 1.40E-01 5.76E-03 BI-214 0 .643 1.14E-01 5.15E-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 lines not used in Weighted Mean Activity Errors quoted at 1.000sigma

9/15/2017 5:34:40PM Page6of8 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

F 13 1 50.30 510.42 2.34229E-02 5.18751E-02 27.02 13.40 1\r

/S'l 1.-01 F 14 582.72 1.08335E-01 6.30 "fllAli, F 20 859.83 2.58107E-02 15.59 F

F 22 26 932.46 1376.66

1. 84862E-02 1.73669E-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 9 (q\\~

NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Oiaryland_NPP\Library\ENVLIB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (keV) (pCVgrams) (pCVgrams) (pCVgrams)

+ K-40 1460.81

10.67 S.90E+OO 1.14E-01 1.14E-01

+ MN-54 834.83 99.97 -3.78E-04 1. 07E-02 1. 07E-02

+ C0-60 1173.22 100.00 -8.66E-03 1.22E-02 1.54E-02 1332.49 100.00 1.06E-02 1.22E-02

+ ZN-65 1115.52 50.75 2.90E-02 3.33E-02 3.33E-02

+ KR-85 513.99 0.43 7.35E+OO 2.61E+OO 2.61E+OO

+ CD-109 88.03 3.72 l. llE+OO 5.30E-01 5.30E-01

+ CS-134 604.70 97. 60 6.21E-02 l.24E-02 1. 43E-02 795.84 85.40 -2.29E-03 1.24E-02

+ CS-137 661.65

85.12 3.87E-02 7.31E-03 7.31E-03

+ EU-154 123.07 40.40 -2.66E-03 2.97E-02 2.97E-02 722.30 20.00 2 . 59E-02 S.44E-02

9/15/2017 5:34:40PM Page 7 of8 Analysis Report for CDR-NRC-7 SOIL Nuclide Energy Yleld(%) Activity NuclldeMDA LineMDA Name (pCVgrams) (pCUgrams) (pCVgrams)

(lreV)

EU-154 873.20 12.09 -5.03E-02 2.97E-02 8.77E-02 996.30 10.34 -3.25E-02 1. 19E-01 1004 . 76 17 . 90 9.87E-03 6.92E-02 1274.51 34.40 - 1. 65E-02 4.16E-0.2

+ EU-155 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-208 72.80 2.02 -1. 07E+20 8.38E+18 8.35E+20 74.97 3.41 l.10E+21 4.56E+20 84.90 1.51 2.14E+20 7.33E+20 277.36 6.31 2.84E+l9 9.15E+l9 583.19 84.50 2.40E+19 8.3AE+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-Ol 806.17 1.23 7.79E-02 7.80E-01 934.06 3.21 8.64E-02 3 . 69E-Ol 1120.29

15.10 1. 41E-01 8.06E-02 1155.19 1. 69 3.79E-01 8.98E-01 1238. 11 5.94 l.92E-01 2.BBE-01 1280.96 1. 47 3.65E-01 9.95E-01 1377.67 4 .11 1.93E-01 2.66E-01 1401. 50 1.39 4.89E-01 7 .BSE-01 1407.98 2.48 -2.02E-Ol 4.41E-Ol 1509.19

2.19 1. 20E-01 2.24E-01 1661.28 1.15 5.14E-01 6.38E-01 1729.60

3.05 1. 42E-Ol l.53E-01 1764.49

15.80 1.22E-01 4.lSE-02 1847.44 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-01 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. BSE-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-223 81. 07 15.00 -2.31E-02 7.54E-02 1. 52E-01 83.78 24.80 6.91E-02 8.lOE-02 94.90 11.30 5 .59E-02 1.49E-01 122-31 1.19 -3.41E-01 1.02E+OO 144.20 3. 26 1. l 6E-01 3.41E-Ol 154.19 5.59 -8.69E-02 1. 92E-Ol 269.41 13.60 9.54E-02 7.54E-02 323.89 3.90 -1. 23E-Ol 2.48E-Ol 338.32 2.78 -1. 33E-01 3.83E-Ol 444.94 1.27 -8.0BE-02 7.0lE-01

+ RA-226 186.21

3.28 2 . 43E-01 2.88E-01 2.88E-Ol

+ AC-228 129.08 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 Nuc/ldeMDA LineMDA Name (pCVgrams) (pCVgrams) (pCVgrams)

(keV)

AC-228 270.23

3.60 l.63E-Ol 3.21E-02 l.95E-01 327.64

3.20 8.68E-02 l.SOE-01 338.32

11. 40 1. 22E- Ol 4.36E-02 409.51 2.13 2.23E-01 4. 21E-01 463 . 00

4.40 l.69E-01 1.25E-01 794.70

4.60 1.09E-01 1. 86E-01 911. 60

2 7.70 1. 42E-01 3.21E-02 964 . 60

5 .20 1. 2 9E-01 l. 2 9E-Ol 969.11

16.60 1. 25E-Ol 4.29E-0 2 1587.90 3.71 4.SSE-01 2.56E-01

+ Th-230 12 . 30 8.43 O. OOE+OO 8 . 87E+OO 8 . 40E+10 67.60 0.37 -3.48E-Ol 8.87E+OO 168.10 0.07 1.14E+Ol l . 52E+Ol

+ PA-234M 766.36 0.29 -1 . 73E+OO 1. 46E+OO 3.69E+OO 1001. 03 0.84 9.24E-Ol 1. 46E+OO

+ TH-234 63.29 4.50 4.53E-01 6.84E-01 9.14E-01 92 . 38 2.60 7.27E-01 6.90E-01 92 . 80 2.60 6.98E-01 6.84E-Ol

+ AM-241 59.54 36.30 -3.0SE-02 1.43E-Ol 1. 43E-Ol

+ CM-243 99.55 14.30 4.14E-02 5 .97E-02 1.0SE-01 103.76 23.00 -3. 21E-02 5 .97E-02 117.00 1 0.80 -7 .BOE-02 1.14E-01 228 .1 8 10.60 2.lOE-02 9.81E-02 277.60 14.00 2 . 03E-0 2 7 .llE-02

+ = Nuclide identified during the nuclide identification

= Energy line found In the spectrum

> = MDA vakle 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

9/16/201 / 7 :34:12AM Page 1 of8 Analysis Report for CDR-NRC-8 SOIL GAMMA SPECTRUM ANALYSIS Sample Identification : CDR-NRC-8 /

Sample Description : SOIL Sample Type : Silt Unit Sample Point Sample Size : 3.179E+03 grams FacHity : Diaryland_NPP Sample Taken On : 9/15/2017 1:20:00PM /

Acquisition Started

9/16/2017 6:33:33AM" Procedure : Slit ./

Operator : Administrator Detector Name : DET01-ENV .,/

Geometry : 1.5L Marinelli /

Live Tlme : 3600.0 second!

Real lime : 3624.9 seconds Dead Time : 0.69%

Peak Locate Threshold : 3.00 Peak Locate Range {In channels) : 100*4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000keV Energy Calibration Used Done On : 6/3/2014 Efficiency Calibration Used Done On : 6/3/2014 Efficiency Calibration Description : 1.5 Marlnelli Sample Number : 3412 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/16/2017 7:34:03AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096

9/16/2017 7:34:12AM Page2 of8 Analysis Report for CDR*NRC.8 SOIL Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV}

M 1 74.56 141 - 193 149.98 2 .81E+02 28.58 8 . 00E+02 1.33 m 2 76.78 141 - 193 154.41 4.00E+02 33.58 7.93E+02 1.33 m 3 86.85 141 - 193 174.56 l.91E+02 25.25 7.72E+02 1. 36 m 4 92 . 47 141 - 193 1 85 . 81 2.27E+02 27.47 7.60E+02 1.38 F 5 185.51 366 - 380 371. 94 3.04E+02 30.40 l.02E+03 1. 64 F 6 209.05 415 - 424 419.04 1.11E+02 24 . 12 6 . 69E+02 1. 31 M 7 2 38.24 469 - 491 477.43 1. 28E+03 41. 50 5 .75E+02 1.50 m 8 241.43 469 - 491 483.82 2.91E+02 24.48 5,17E+02 1. 50 M 9 269.83 536 - 559 540.65 7.95E+Ol 18 . 02 3.70E+02 1.13 m 10 277.24 536 - 559 555.46 6.36E+Ol 16.59 3.02E+02 1.14 M 11 294.85 585 - 610 590.69 4 . 76E+02 28.03 3.64E+02 1. 47 m 12 299.66 585 - 61 0 600 . 32 7 . 47E+Ol 15.93 3.40E+02 1.48 M 13 327.42 633 - 683 655 .86 8.lOE+Ol 17.27 3.27E+02 1. 47 m 14 338.00 633 - 683 677 . 04 2.90E+02 23.04 2.99E+02 1. 48 F 15 351.52 697 - 710 704.08 8.41E+02 33 . 71 4.02E+02 1. 66 F 16 409.11 814 - 824 819.30 4.70E+Ol 14.97 2.86E+02 1.35 F 17 462.34 920 - 935 925.80 8.83E+Ol 16.19 3.60E+02 1. 46 F 18 510.52 1014 - 1032 1022.19 2.96E+02 22.87 3.47E+02 2.2 7 F 19 582.75 1161 - 1174 1166.70 4.41E+02 24.64 2.03E+02 1. 82 F 20 608.78 1212 - 1 22 6 1218 . 78 6.49E+02 28.96 2 .20E+02 1. 81 F 21 661.16 1316 - 1333 1323.59 1.51E+03 40.96 2 .39E+02 1.80 F 22 726 . 80 1445 - 1462 1454.92 1. 23E+02 15.65 1.91E+02 2. 12 F 23 859.80 1712 - 1728 1721. 02 9.23E+Ol 14.10 l.23E+02 2.67 F 24 910.60 1816 - 1834 1822.66 3.34E+02 21.46 1 . 98E+02 2.02 M 25 963.96 1922 - 1945 1929.43 9.25E+Ol 12.93 1 . 16E+02 2.02 m 26 968.42 1922 - 1945 1938.35 1. 72E+02 16.29 1. 21E+02 2.02 F 27 1119.62 2 2 28 - 2247 2240.87 1. 88E+02 17.59 1. 83E+02 2.17 F 28 1376.51 2749 - 2761 2754.86 4.45E+Ol 10. 1 2 5.34E+Ol 2.71 F 29 1459.96 2908 - 2935 2921.84 4.07E+03 64.31 7.53E+Ol 2.96 M 30 1619.55 3234 - 3267 3241. 15 2.97E+Ol 6. 2 3 9.47E+OO 2.41 m 31 1629.92 3234 - 3267 3261. 90 2.49E+Ol 6.07 1. 24E+Ol 2 . 41 F 32 1763.62 3519 - 3539 3529.43 1.63E+02 13.62 2.0SE+Ol 3.70 F 33 1846.41 3690 - 3701 3695.09 2.24E+Ol 5.46 7.68E+OO 1. 79 F 34 1992.64 3981 - 3994 3987.68 1. 03E+Ol 4.01 1. llE+Ol 1.16 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 : 9/16/2017 7:34:03AM Env. Background FIie : C:\Canberra\Apex\Root\Diaryland_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.Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

M 1 74.56 2.81E+02 28.58 7.82E+Ol 9.57E+OO 2.03E+02 3.0lE+Ol m 2 76.78 4.00E+02 33.58 4.00E+02 3.36E+Ol m 3 86.85 l.91E+02 25.25 l.91E+02 2.53E+Ol m 4 92.47 2.27E+02 27.47 5.07E+Ol 8.63E+OO 1.76E+02 2.88E+Ol F 5 185.51 3.04E+02 30.40 3.67E+Ol 8.25E+OO 2.67E+02 3.15E+Ol F 6 209.05 1.11E+02 24.12 l.11E+02 2.41E+Ol M 7 238.24 1.28E+03 41.50 3 .14E+Ol 6.41E+OO 1.25E+03 4.20E+Ol m 8 241.43 2.91E+02 24.48 2.91E+02 2.45E+O l M 9 269.83 7.95E+Ol 18.02 7.95E+Ol 1. 80E+Ol m 10 277.24 6.36E+Ol 16. 59 6.36E+Ol 1. 66E+Ol M 11 294.85 4.76E+02 28.03 1 .00E+Ol 5.91E+OO 4.66E+02 2.86E+Ol rn 12 299.66 7.47E+Ol 15.93 7 . 47E+Ol 1. 59E+Ol M 13 327 . 42 8.lOE+Ol 17.27 8.lOE+Ol 1.73E+Ol m 14 338 . 00 2.90E+02 23.04 9.67E+OO 5 .86E+OO 2.80E+02 2.38E+Ol F 15 351. 52 8.41E+02 33.71 2.24E+Ol 5.4 7E+OO 8.19E+02 3.41E+Ol F 16 409.11 4.70E+Ol 14.97 4.70E+Ol 1. SOE +Ol F 17 462.34 8.83E+Ol 16.19 8.83E+Ol l.62E+Ol F 18 510.52 2.96E+02 22.87 l.52E+02 8.lOE+OO 1. 44E+02 2.43E+Ol F 19 582.75 4.41E+02 24.64 2 . 14E+01 4.78E+OO 4.20E+02 2 . 51E+Ol F 20 608.78 6.49E+02 28.96 2.18E+Ol 4.83E+DO 6.27E+02 2.94E+Ol F 21 661.16 1. 51E+03 40.96 1. 38E+Ol 4.37E+OO 1. 50E+03 4.12E+Ol F 22 726.80 1.23E+02 15.65 l.23E+02 1. 56E+Ol F 23 859.80 9.23E+Ol 14. 10 9.23E+Ol 1. 41E+Ol F 24 910. 60 3.34E+02 21.46 1. 3SE+Ol 3.68E+OO 3.20E+02 2.18E+Ol M 25 963.96 9.25E+Ol 12.93 9.25E+Ol 1.29E+Ol rn 26 968.42 1. 72E+02 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+02 1. 79E+Ol F 28 1376 . 51 4.45E+Ol 1 0 .12 4.45E+O l l . OlE+Ol F 29 1459.96 4.07E+03 64.31 5.78E+Ol 4.59E+OO 4.01E+03 6.45E+Ol M 30 1619 . 55 2.97E+01 6.23 2 , 97E+Ol 6.23E+OO rn 31 1629. 92 2.49E+Ol 6.07 2.49E+Ol 6.07E+OO F 32 1763.62 1.63E+02 13. 62 1. 38E+Ol 2.34E+OO 1 .49E+D2 1.38E+Ol F 33 1846.41 2.24E+Ol 5 .46 2.24E+Ol 5.46E+OO F 34 1992.64 1. 03E+Ol 4 .01 1. 03E+Ol 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 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Oiarytand_NPP\Library\ENVLIB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCUgrams) Uncertainty K-40 0.89 1460.81

10.67 6.02E+OO l.92E-01 CS-137 0.96 661.65

85.12 1.59E-01 6.13E-03 BI-212 0. 57 727 .17

11.80 1.00E-01 l.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 l.48E-01 6.30E-03 300.09

3 . 41 1.27E-01 2.73E-02 BI-214 0.50 609.31

46.30 l.16E-01 6.31E-03 768.36 5.04 806.17 1.23 934.06 3.21 1120.29

15.10 1. 56E-01 l.61E-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 1661.28 1.15 1729.60 3.05 1764.49

15.80 l.66E-Ol 1.63E-02 1847.44 2.12 PB-214 0.94 74 .81

6 .33 3 . 56E-01 5.43E-02 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-02 295 .21

19.20 1 .40E-01 9.24E-03 351.92

37.20 1. 37E-01 6.65E-03 785.91 1.10 RA-226 0.92 186 .21

3.28 4.04E-01 4.90E-02 AC-228 0.73 129.08 2. 80 209.28

4.40 1. 28E-01 2.BlE-02 270 .23

3.60 1. 23E-01 2.79E-02 327.64

3.20 1. 53E-Ol 3.28E-02 338.32

11. 40 1. SlE-01 1. 33E-02 409. 51

2.13 1. 49E-Ol 4.76E-02 463.00

4.40 l.45E-01 2.69E-02

9/16/201, 7:34:12AM Pages of8 Analysis Report for CDR-NRC-8 SOIL Nuclide kl Energy Yield(%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty AC-228 0.73 794.70 4.60 911. 60

27.70 1.31E-01 9.37E- 03 964.60

5 . 20 2 . l l E-01 2.98E- 02 969.11

16.60 1.23E-Ol 1.20E-02 1587.90 3.71

= Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence Index threshold "" 0.30 Errors quoted at 1.000slgma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Acttvlty Activity Confidence Uncertainty (pCUgrams)

K-40 0.891 6 . 02E+OO 1. 92E-01

/ CS-1 37 0.963 1. 59E-Ol 6. 13E-0 3 BI-212 0.578 1. OOE-01 1 .30E-02 PB-212 0. 943 1. 4 7E- 01 5 . 82E-03 BT-214 0.502 1. 26E-Ol 5.53E-03 PB-214 0.942 1. 46E-Ol 5 . 08E-03 RA-2 26 0.92 4 4.04E-Ol 4.9 0E-02 AC-228 0. 737 1. 37E-Ol 5.73E-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

9/16/2017 7:34:12AM Page6 of8 Analysis Report for CDR-NRC-8 SOIL UNIDENTIFIED PEAKS Peak Locate Perfonned on : 9/16/2017 7:34:03AM 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

~~

m 4 92.47 4.89595E-02 16.34 m

F 10 18 277.24 510.52

1. 76578E-02 4.00530E-02 26.10 16.83 Tol.

Sum C t~)

F 582.75 F

19 23 859.80 1.16657E-Ol 2.56501E-02 5.98 15.27

'1\~

4) 'tA.

F M

28 30 1376.51 1619.55 1 .23710E-02 8.24303E-03 22.71 20.98

\1,\~~

m F

31 33 1629 . 92 1846.41 6.91759E-03 6.22989E-03 24.36 24.36 Sum Sum (Jq~~

F 34 1992.64 2.86066£-03 38.90 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 Nudlde Library Used : C:\Canberra\Apex\Root\Diaryland_NPP\Library\ENVLIB.NLB Nuclide Energy Yield{%) Activity NuclldeMDA LineMDA Name (pCVgrams) (pCVgrams) (pCVgrams)

(keV)

+ K-40 1460.81

10.67 6.02E+OO 1. 04E-01 1.04E-01

+ MN-54 834.83 99.97 6 . 36E-03 1. 09E-02 l.09E-02

+ C0-60 1173.22 100.00 -9.16E-05 1.22E-02 1.54E-02 1332.49 100.00 -1. 05E-02 1. 22E-02

+ ZN-65 1115.52 50.75 6 . 66E-02 3.24E-02 3.24E-02

+ KR-85 513.99 0.43 6.41E+OO 2.68E+OO 2.68E+OO

9/161201, 7:34:12AM Pagc7 of&

Analysts Report for CDR-NRC-8 SOIL Nuclide Enervy Yield(%) Activity NuclideMDA UneMDA Name (pCl/grams) (pCllgrams) (pCVgrams)

(lntV)

+ CD-109 88.03 3.72 1.46E+OO 5.40E-01 5.40E-Ol

+ CS-134 604.70 97.60 5.47E-02 1.28E-02 l.44E-02 795.84 85.40 -3.95E-03 1.28E-02

+ CS-137 661. 65

85.12 1.59E-01 l.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 -3.4SE-03 1. 20E-Ol 1004.76 17.90 4.SlE-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. OOE+26 l.OOE+26 1.00E+26

@ 74.97 3.41 1.00E+26 1. OOE+26

@ 84.90 1.51 l.OOE+26 l.00E+26

@ 277.36 6.31 1. OOE+26 l.OOE+26

@ 583.19 84.50 1.00E+26 1. 00E+26

@ 763.13 1. 81 1.00E+26 1. OOE+26

@ 860.56 12.42 l.OOE+26 1.00E+26

@ 1093.. 90 0.40 1. 00E+26 1.00E+26

+ BI-214 609.31

46.30 1.16E-Ol 1.63E-02 l.63E-02 768.36 5.04 l.20E-01 2.lOE-01 806.17 1.23 -2.21E+OO 7.96E-01 934.06 3.21 S.77E-02 3.72E-Ol 1120.29

15.10 1. 56E-Ol 7 .66E-02 1155.19 1. 69 -3.84E-01 8.96E-01 1238.11 5 .94 2.81E-01 2.91E-Ol 1280.96 1.47 3.SOE-01 9.46E-Ol 1377.67 4.11 4.27E-01 2.92E-Ol 1401. 50 1.39 4.0lE-02 7. 81E-Ol 1407.98 2.48 9.78E-02 4.39E-Ol 1509.19 2.19 8.18E-02 4 . 36E-Ol 1661. 28 1.15 3.llE-01 6.34E-Ol 1729.60 3.05 8.SOE-02 2.SSE-01 1764.49

15.80 1. 66E-Ol 3.84E-02 1847.44 2.12 -4.45E-02 3.53E-01

+ PB-214 74.81

6.33 3. 56E-01 1.93E-02 2.48E-Ol 77.11

10.70 3.BSE-01 l.29E-Ol 87.20

3.70 4.06E-Ol 2.81E-01 89.80 1.03 4.78E+OO 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-Ol l . 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-Ol 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 CDR-NR~

SOIL Nuclide Enerrw Yield(%) Activity NuclideMDA UneMDA Name (pCVgrams) (pCUgrams) (pCVgrams)

(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-Ol 444.94 1.27 -2.61E-Ol 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 l.28E-Ol l.SlE-01 270.23

3.60 1. 23E-Ol 1. 42E-01 327.64

3.20 1.53E-01 1. 64E-Ol 338.32

11. 40 l.SlE-01 4.63E-02 409.51

2.13 l.49E-01 2.82E-01 463. 00

4.40 1.45E-01 l.82E-01 794.70 4. 60 6.42E-02 2.42E-Ol 911.60

27.70 1. 31E-Ol 3.68E-02 964.60

5 . 20 2.llE-01 1. 21E-Ol 969 .11

16.60 l.23E-01 3.86E-02 1587.90 3.71 1. 59E-Ol 2.46E-Ol

+ Th-230 12.30 8.43 O.OOE+OO 9.07E+OO 8.30E+l0 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 -1.89E-Ol l.49E+OO

+ TH-234 63.29 4.50 l.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-01

+ AM-241 59.54 36.30 -8.57E-02 l .47E-Ol 1. 4 7E-01

+ CM-243 99.55 14.30 l.SlE-02 6.16E-02 l.09E-Ol 103.76 23.00 -2.SlE-02 6.16E-02 117. 00 10.80 -1. 26E-02 l.17E-01 228.18 10.60 3.07E-02 l.02E-01 277.60 14.00 -2.21E-02 7.49E-02

+ = Nuclide identified during the nuclide ldentfficatton

= 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 1 of 10 Analysis Report for CDR-NRC-9 SOIL GAMMA SPECTRUM ANALYSIS Sample ldentificatlon : CDR-NRC-9 /

Sample Description :SOIL/

Sample Type : SiH Unit Sample Point Sample Size : 3.156E+03grams/

Facility : Diaryland_NPP Sample Taken On : 9/15/2017 2:30:00PM

/

Acquisition Started : 9/19/2017 4:03:54PM Procedure : Sitt /

Operator : Administrator Detector Name : DET01-ENV / /

Geometry : 1.SL Marinelli Live Time : 21600.0 seconds Real lime : 21760.9 seconds Dead Time : 0.74 % / " '

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 : 6/3/2014 Efficiency Calibration Used Done On : 61312014 Efficiency Calibration Description : 1.5 Marinelli Sample Number : 3421 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/19/2017 10:06:38PM Peak Analysis From Channel : 100 Peak Analysis Ta Channel : 4096

9/19/2017 10:06:47PM Page 2 of 10 Analysis Report for CDR-NRC-9 SOIL Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

M 1 74.51 141 - 204 149.88 2.13E+03 85.38 9.09E+03 1. 36 m 2 76.85 141 - 204 154.55 l.94E+03 116.59 9.15E+03 1.37 m 3 84.09 141 - 204 169 . 03 4.54E+02 57.73 1.03E+04 1. 39 m 4 86.86 141- 204 174.57 l.61E+03 100.28 9.36E+03 1.40 m 5 89.54 141 - 204 179.95 l.47E+03 121.41 1. OSE+04 1. 40 m 6 92.53 141 - 204 185.93 l.83E+03 93.91 l.05E+04 1. 41 m 7 99.31 141 - 204 199.49 2.83E+02 77. 30 9.61E+03 1.43 F 8 128.73 250 - 266 258.34 S .43E+02 84.96 l.84E+04 1.20 F 9 185.64 365 - 378 372.19 l.85E+03 99.96 l.43E+04 1.53 F 10 208.86 414 - 422 418.65 8.50E+02 85.03 8.63E+03 1.27 M 11 238.26 470 - 493 477.48 1 .1 2E+04 132.04 7 .40E+03 1.47 m 12 241. 31 470 - 493 483.57 2.11E+03 79.88 7. 08E+03 1. 47 M 13 269.85 524 - 564 540.69 9.51E+02 80.62 7.14E+03 1. 73 m 14 277.00 524 - 564 554.98 5.20E+02 68.55 7.38E+03 1. 74 M 15 294.85 585 - 610 590.71 3.54E+03 90.41 5.76E+03 1.53 m 16 299.81 585 - 610 600.62 7.4 1E+02 62.37 6.14E+03 1.54 M 17 327.52 652 - 683 656.07 4.53E+02 57.39 4.77E+03 1.44 m 18 337.92 652 - 683 676.87 2.33E+03 78.87 5.06E+03 1.45 F 19 351.52 694 - 711 704.07 6.48E+03 102.11 8.51E+03 1. 54 F 20 408 . 96 808 - 825 819.00 3 .48E+02 58.59 7.73E+03 1. 39 F 21 4 62 . 57 922 - 932 926.25 4.97E+02 64.80 4.97E+03 1. 58 F 22 510.30 1012 - 1032 1021.76 2.14E+03 74.04 6.09E+03 2.19 F 23 582.65 1157 - 1172 1166.51 4.20E+03 78.63 3.22E+03 1. 77 F 24 608.78 1212 - 1226 1218.79 5.25E+03 85.24 2.89E+03 1. 85 F 25 641.73 1279 - 1294 1284.72 2.70E+02 51.13 2. 75E+03 2.90 F 26 661. 06 1312 - 1334 1323.38 8.82E+04 299.66 3.34E+03 1. 92 F 27 726.77 1448 - 1463 1454.85 8. 72E+02 44.69 1.67E+03 2.02 M 28 754 . 73 1505 - 1601 1510.79 8.65E+Ol 29.03 1. 2 9E+03 1. 97 m 29 767.79 1505 - 1601 1536.92 5.90E+02 40.09 1.34E+03 1. 99 m 30 771. 79 1505 - 1601 1544.93 l.20E+02 21. 44 1. 32E+03 1. 99 m 31 785.11 1505 - 1601 1571. 59 4.09E+02 51.24 1. 26E+03 2.00 m 32 794.40 1505 - 1601 1590.16 6.62E+02 43.31 1.22E+03 2 .01 F 33 859.80 1713 - 1728 1721. 02 5 .39E+02 41.53 1. 41E+03 2.53 F 34 910. 50 1813 - 1832 1822.46 3.18E+D3 66.64 2.00E+03 2.21 F 35 933.62 1860 - 1875 1868 . 72 3.16E+02 40.14 1.53E+03 2.59 M 36 949.22 1 887 - 1945 1899.92 2.38E+02 32.45 1. 45E+03 2.32 m 37 964 . 08 1887 - 1945 1929.66 7.17E+02 39.23 1. 38E+03 2.33 rn 38 968 . 27 1887 - 1945 1938.05 2.00E+03 55.56 l.33E+03 2.33 F 39 1000.28 1996 - 2009 2002.09 1. 4 9E+02 33.86 1.37E+03 1. 91 F 40 1119. 48 2227 - 224 9 2240.58 1.38E+03 52. 77 2.32E+03 2.56 F 41 1172. 45 2333 - 2356 2346.57 3.16E+03 68.71 2.73E+03 2.50 F 42 1237 . 49 2468 - 2488 2476.70 5 .51E+02 43.67 2.52E+03 2.15 F 43 1331. 58 2 651 - 2678 2664.96 2.98E+03 61.58 1.43E+03 2.83 M 44 1376 . 69 2742 - 2825 2755.23 3.83E+02 30.04 5 .98E+02 2.82 m 45 1384 .22 2742 - 2825 2770_29 8.57E+Ol 19.79 5.78E+D2 2 .83 m 46 1401.01 2742 - 2825 2803.88 1.22E+D2 20.95 5.45E+D2 2.84 m 47 1407.29 2742 - 2825 2816.46 1.41E+02 21.92 5.32E+02 2.84 F 48 1459.86 2908 - 2935 2921. 63 4.14E+04 204.57 6.53E+02 2.82 M 49 1494.79 2979 - 3033 2991. 52 l.13E+02 17. 73 3.07E+02 3.38 m so 1500.86 2979 - 3033 3003.67 7.76E+Ol 16.00 2.88E+02 3.38 m 51 1508.69 2979 - 3033 3019.33 1. 99E+02 20.04 2.62E+02 3.39 F 52 1587.53 3168 - 3190 3177.08 2.90E+02 23.62 3.37E+02 3.26 M 53 1620 . 09 3232 - 3269 3242.24 1. 44E+02 17.23 2.03E+02 3.00

9/19/2017 10:06:47PM Page3 oflO Analysis Report for CDR-NRC-9 SOIL Peak Energy ROI ROI Peak Net Peak NetArea Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) m 54 1629.68 3232 - 3269 3261.44 l.28E+02 16.44 1.84E+02 3.01 F 55 1728.53 3446 - 3468 3459.22 2.59E+02 19.42 l.46E+02 3.28 F 56 1763.47 3514 - 3540 3529.13 1.13E+03 35.99 1.85E+02 3.27 F 57 1788.44 3574 - 3586 3579.09 2.53E+Ol 7.81 7.31E+Ol 1.18 F 58 1846.46 3685 - 3703 3695.20 1.54E+02 16.45 1. 28E+02 3.26 M = First peak in a multiplet region m = Other peak ln a multiplet region F = Fitted singlet Errors quoted at 1.000slgma BACKGROUND SUBTRACT REPORT Peak Analysis Perfonned on : 9/19/2017 10:06:38PM Env. Background FIie : C:\Canberra\Apex\Root\Diaryland_NPP\Data\0000003420.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) ANa Uncertainty Background 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 1.17E+02 m 3 84.09 4.54E+02 57.73 l .13E+02 1. 96E+Ol 3.41E+02 6.lOE+Ol m 4 86.86 l.61E+03 100.28 1.61E+03 1.00E+02 m 5 89.54 1.47E+03 121.41 1.47E+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 5 .43E+02 8.50E+Ol F 9 185.64 1.85E+03 99.96 1.98E+02 5.08E+Ol 1.66E+03 1.12E+02 F 10 208.86 8 . SOE+02 85.03 8.50E+02 8.SOE+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+02 68.55 5 . 20E+02 6.86E+Ol M 15 294 . 85 3.54E+03 90.41 3.54E+03 9.04E+Ol m 16 299.81 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 5.95E+Ol 3.00E+Ol 2.27E+03 8.44E+Ol F 19 351. 52 6.48E+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 5 . 86E+Ol F 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. l 7E+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 l.49E+02 3.31E+Ol 5.10E+03 9.15E+Ol

9/19/2017 10:06:47PM Page4 of 10 Analysis Report for CDR-NRC.9 SOIL Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 25 641.73 2.70E+02 51.13 2.70E+02 5. llE+Ol F 26 661. 06 8.82E+04 299.66 1. 09E+02 2.71E+Ol 8.81E+04 3.01E+02 F 27 726.77 8.72E+02 44.69 8.72E+02 4.47E+Ol M 28 754.73 8.65E+Ol 29.03 8 . 65E+Ol 2.90E+Ol m 29 767.79 5.90E+02 40.09 5.90E+02 4.0lE+Ol m 30 771.79 l.20E+02 21.44 1.20E+02 2.14E+Ol m 31 785.11 4. 09E+02 51.24 4.09E+02 5. 12E+Ol m 32 794.40 6.62E+02 43.31 6.62E+02 4.33E+Ol F 33 859.80 5.39E+02 41.53 5.39E+02 4.15E+Ol F 34 910.50 3.18E+03 66.64 7.09E+Ol 2.13E+Ol 3.11E+03 7.00E+Ol F 35 933.62 3.16E+02 40.14 3.16E+02 4.0lE+Ol M 36 949.22 2.38E+02 32.45 2.38E+02 3.24E+Ol m 37 964.08 7.17E+02 39.23 7.17E+02 3.92E+Ol m 38 968.27 2.00E+03 55.56 2.00E+03 5.56E+Ol F 39 1000.28 1. 49E+02 33.86 2 . 43E+Ol 1. SSE+Ol 1. 25E+02 3 . 73E+Ol F 40 1119. 48 1.38E+03 52.77 1. 38E+03 5.28E+Ol F 41 1172.45 3.16E+03 68.71 5 . 68E+Ol 1.85E+Ol 3.10E+03 7.12E+Ol F 42 1237.49 5.51E+02 43.67 5. 51E+02 4.37E+Ol F 43 1331.58 2.98E+03 61.58 4.0BE+Ol l.68E+Ol 2.94E+03 6.38E+Ol M 44 1376.69 3.83E+02 30.04 3.83E+02 3.00E+Ol m 45 1384.22 8.57E+Ol 19.79 8.57E+Ol 1.98E+Ol m 46 1401.01 1 .22E+02 20 . 95 l.22E+02 2.lOE+Ol m 47 1407.29 1. 41E+02 21. 92 1.41E+02 2.19E+Ol F 48 1459.86 4.14E+04 204.57 3.19E+02 2.58E+Ol 4.11E+04 2. 06E+02 M 49 1494.79 l.13E+02 17.73 1.13E+02 1.77E+Ol m 50 1500.86 7.76E+Ol 16.00 7.76E+Ol 1.60E+Ol m 51 1508.69 1. 99E+02 20.04 1. 99E+02 2.00E+Ol F 52 1587.53 2.90E+02 23 . 62 2.90E+02 2.36E+Ol M 53 1620.09 1.44E+02 17.23 1.44E+02 1. 72E+Ol m 54 1629.68 1.28E+02 16.44 1. 28E+02 1.64E+Ol F 55 1728.53 2.59E+02 19.42 2.59E+02 1.94E+Ol F 56 1763.47 1.13E+03 35.99 S.03E+Ol 1.15E+Ol 1.08E+03 3.78E+Ol F 57 1788.44 2.53E+Ol 7.81 2.53E+Ol 7.81E+OO F 58 1846.46 1.54E+02 16. 45 1.54E+02 1.65E+Ol

=

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\Oiaryland_NPP\Ubrary\ENVLIB.NLB IDENTIFIED NUCLIDES

9/19/2017 10:06:47PM Pages of IO Analysis Report for CDR-NRC-9 SOIL Nuclide Id Energy Yield(%) Activity Activity Name Confidence (kaV) (pCVgrams) Uncertainty K-40 0.86 1460 . 81

10.67 1.03E+Ol 2 . 91E-Ol C0-60 0.89 1173.22

100.00 7 .16E-02 2.37E-03 1332.49

100.00 7.44E-02 2.49E-03 CS-137 0. 94 661. 65

85.12 1. 57E+OO 4.29E-02 BI-212 0.97 727.17

11.80 1.19E-01 6.83E-03 785.42

2 .00 3.49E-Ol 4.46E-02 1620.56

2.75 1.49E-Ol 1.82E-02 PB-212 0 .98 77.11

17.50 1. 91E-01 1.32E-02 87.20

6.30 3.38E-01 2.39E-02 89.80

1. 75 1. OSE+OO 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 1.58E-Ol 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 1120.29

15.10 2.04E-01 9.lOE-03 1155.19 1.69 1238. 11

5.94 2.23E-01 1.85E-02 1280.96 1.47 1377. 67

4.11 2.41E-Ol 1. 99E-02 1401.50

1.39 2.29E-01 3.98E-02 1407.98

2.48 1.49E-01 2.35E-02 1509.19

2.19 2.48E-01 2.SBE-02 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44

2.12 2.lBE-01 2.47E-02 PB-214 0 .97 74 . 81

6.33 5.75E-01 3.25E-02 77 .11

10.70 3.13E-01 2.16E-02 87.20

3.70 5. 76E-01 4.06E-02 89.80

1.03 1. 78E+OO l.59E-01 241.98

7.49 2. su:-01 l.lSE-02 295.21

19 .20 1. 78E-Ol 6.31E-03 351.92

37.20 1. BOE-01 S.33E-03 785. 91

1.10 6.35E-01 8.lOE-02 RA-226 0 .94 186.21

3.28 4,21E-Ol 3.08E-02 AC-228 0 .52 129.08

2.80 l.68E-01 2.66E-02 209.28

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. 3?.

11.40 2.05E-01 9.lOE-03 409.51

2.13 l.BSE-01 3.lSE-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 1. 61E-02 969 .11

16.60 2.41E-01 8 . 47E-03 1587.90

3.71 2.20E-01 1. 88E-02 PA-234M 0. 48 766.36 0 .29 1001. 03

0.84 3.06E-01 9.13E-02

9/19/2017 10:06:47PM Page 6 of 10 Analysis Report for CDR-NRC-9 SOIL

= 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 REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCVgrams)

J K-40 C0-60

/ CS-137 0 .865 0.894 0.946

1. 03E+Ol 7.29E-02

1. 57E+OO 2.91E-Ol

1. 72E-03 4.29E-02 BI-212 0.974 1.26E-01 6.33E-03 PB-212 0.982 1 .97E-Ol 5.32E-03 BI- 214 0.662 1. BOE-01 3.89E-03 PB-214 0.974 l .88E-Ol 3.75E- 0 3 RA-2 2 6 0.948 4.21E-Ol 3.0BE-02 AC-228 0.528 2.14E-01 4.48E-03 PA-234M 0.488 3.06E-01 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

9/19/2017 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 : 4006 Peak CPS{%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide m 3 84.09 1 . 57785E- 02 17 . 89 (41.,~

m 6 92.53 6.68743E-02 6.78 ~:f\ q )iiJ\°'-

m m

F 14 22 7 99.31 277.00 510.30 1.30809E-02 2.40628E-02 5.43399E-02 27.36 13.19 7.62 Tol.

Tol.

Su~ob ,1 ifr-:i

~/~~ rl,t\~

F 23 582.65 1. 88106E-01 2 . 08 (} '1,)

F 25 641.73 1.24872E-02 18 . 96 M 28 754.73 4.00611E-03 33.55 (7~~

m 30 771. 7 9 5.55421E-03 17.87 ~~~~

F 33 34 859.80 910.50 2.49514E-02 1.43784E-01 7.71 2.25 s~~

F "'L'°rl M 36 949.22 1.10234E-02 13.63 S-Es~~

~1..J m 45 1384.22 3.96803E-03 23 . 08 o, i.rl M 49 1494.79 5.22390E-03 15 . 71 Sum~ t..,t~

m 50 1500.86 3.59404E-03 20.61 Sum ~l,'l...°Vi m 54 1629.68 5.90977E-0 3 12 . 88 Sum ~ -U~

F 55 1728.53 1.19886E-02 7. 50 Sum (>\iv'-\

F 56 1763.47 4.99652E-02 3.50 Sum F 57 1788.44 1. l 7059E-03 30.91

__./'

M "' First peak in a multlplet region

=

m Other peak in a multiplet region

~~x

=

F Fitted singlet Em>rs quoted at 1.000slgma NUCLIDE MDA REPORT Nudide 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(%) Activity NuclldeMDA LlneMDA Name (pCVgrams) (pCUgrams) (pCVgrams)

(keV)

+ K-40 1460.81

10.67 1.03E+Ol 5.22E-02 5.22E-02

+ / MN-54 834 . 83 99.97 9.63E-03 5.58E-03 5.58E-03

+ C0-60 1173.22

100.00 7.16E-02 6.91E-03 8.16E-03 1332.49

100.00 7.44E-02 6 . 91E-03

+ ZN-65 1115.52 50. 75 5 .75E-02 l.65E-02 1 . 65E-02

+ KR-85 513.99 0.43 5 .92E+OO 1.61E+OO l.61E+OO

+ CD-109 88.03 3.72 1.56E+OO 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 1.57E+OO 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-01 3.53E-02 3.53E-02 105.31 21.80 7.68E-03 3.82E-02

+ @ TL-208 72.80 2.02 1. OOE+26 1. 00E+26 1. OOE+26

@ 74.97 3.41 l.OOE+26 1. OOE+26

@ 84.90 1.51 1.00E+26 l.OOE+26

@ 277.36 6.31 1.00E+26 1. OOE+26

@ 583.19 84.50 1. 00E+26 l.OOE+26

@ 763.13 1. 81 1.00E+26 1.00E+26

@ 860.56 1 2 .42 1.00E+26 1 . 00E+26

@ 1093.90 0.40 1 .00E+26 1. OOE+26

+ BI-214 609.31

46.30 1.58E-Ol 1. OlE-02 1. OlE-02 768.36

5.04 1. 97E-01 5.78E-02 806.17 1.23 8.57E-02 4.22E-01 934.06

3.21 1.91E-01 1. 37E-01 1120.29

15.10 2.04E-01 4 . 65E-02 1155.19 1. 69 -1. 47E-01 4 .63E-01 1238 .11

5.94 2.23E-Ol 1.28E-Ol 1280.96 1.47 3.83E-Ol 4.87E-01 1377.67

4.11 2.41E-01 7.33E-0 2 1401. 50

1. 39 2.29E-Ol 2.09E-01 1407.98

2.48 1. 49E-01 1.16E-01 1509.19

2.19 2.48E-01 9.76E-02 1661.28 1.15 2.09E-01 2.68E-Ol 1729.60 3.05 1. 38E-Ol 1.14E-01 1764.49 15.80 2.18E-Ol 3.SOE-02 1847.44

2.12 2.lSE-01 1.0lE-01

+ PB-214 74.81

6.33 5 .75E-01 1. 58E-02 1.35E-01 77 .11

10.70 3.13E-Ol 7.22E-02 87.20

3.70 5.76E-01 1.62E-01 89.80

1.03 1.78E+OO S.81E-Ol 241. 98

7.49 2.SlE-01 4 . 70E-02 295.21

19.20 1.78E-Ol 1. 79E-02 351. 92

37.20 1. BOE-01 l.58E-02

9/19/2017 10:06:47PM Page 9 of IO Analysis Report for CDR-NRC-9 SOIL Nuclide Energy Yield(%) Activity NuclideMDA LlneftlDA Name (keV)

(pCUgrams) (pCl!grams) (pCVgrams)

PB-214 785.91

1.10 6.35E-Ol l.SBE-02 2.61E-01

+ RA-223 81.07 15.00 6.SOE-02 5.86E-02 l.OBE-01 83.78 24.80 -4.78E-Ol 5.86E-02 94.90 11. 30 -2.97E-02 l.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 5.31E-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-01

+ RA-226 186.21

3.28 4.21E-01 1 .72E-01 1.72E-Ol

+ AC-228 129. 08

2 .80 1. 68E-Ol 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 1.03E-01 338.32

11. 40 2.0SE-01 3.lSE-02 409.51

2.13 1.85E-01 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-Ol 2.07E-02 1587.90

3.71 2.20E-01 9.23E-02

+ Th-230 12.30 8.43 O.OOE+OO 5.02E+OO 1.39E+l0 67.60 0.37 -4.46E+OO 5.02E+OO 168.10 0 .07 5.38E+OO 9.41E+OO

+ PA-234M 766.36 0.29 3.35E+OO 5.19E-Ol l.90E+OO 1001.03 . 0.84 3.06E-Ol 5.19E-Ol

+ TH-234 63.29 4.50 -3.SlE-01 4.45E-Ol S.SOE-01 92.38 2. 60 9.84E-Ol 4.48E-01 92.80 2.60 l.22E+OO 4.45E-01

+ / AM-241 59.54 36.30 -9.SOE-02 8.14E-02 8 .14E-02

+ 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:c1lculated

@ :: 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 IO of 10 Analysis Report for CDR-NRC-9 SOIL

.,. ~

9/12/2u, ,* 8:00:07AM Pqc 1 of6

~Apex-Gamma Analysis Report for SUMP AREA# 1 9-9-17 GAMMA SPECTRUM ANALYSIS Sample Identification : SUMP AREA# 1 /

Sample Description : 9-9-17 Sample Type : 500 ml MarineUi -

Unit Sample Point Sample Size

9.-449E+02 grams

./

FaciUty : DEli,yland_NPP Sample Taken On : 9/9/2017 1:43:00PM Acquisition started : 9/12/2017 6:59:32AM Procedure : 500ml Marinelti Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli /

Live Time : 3600.0 seconds/"

Real Time : 3623.4 seconds DeadTime : 0.65%/

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 : 7/812014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 3344 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/12i20H 7:59:58AM PeakAnaiysis From Channel : 100 Peak Analysis To Channel : 4096

9/12/2017 8:00:07AM Pagc2 of6 Analysis Report for SUMPAREA# 1 Q..9-17 Peak Energy ROI ROI Peale NetPeak NetArea Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 59.48 112 - 126 119.52 4.41E+03 129.67 1.25E+04 2.89 F 2 122.98 239 - 253 246.48 6.31E+02 116.68 l.56E+04 2.43 F 3 145.81 290 - 295 292.14 1.84E+02 72.08 5.89E+03 1.10 F 4 661. 99 1314 - 1333 1324.30 1. 4 7E+05 385.75 2.01E+03 2.75 F 5 1173.88 2337 - 2358 2347.92 7.21E+03 87.09 4.00E+02 3.09 F 6 1275.71 2543 - 2557 2551.57 6.24E+Ol 12.27 1.11E+02 2.22 F 7 1333 . 26 2655 - 2677 2666.65 6.17E+03 79.05 7.77E+Ol 3.16 F 8 1461. 72 2913 - 2933 2923.55 6.87E+02 27.18 4.46E+Ol 3.15 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 Perfonned on : 9/12/2017 7:59:58AM env. Background File : C:\Canberra\Apex\Root\Oairyland_NP?\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 , 59.48 4.41E+03 129 . 67 4 .41E+03 1.30E+02 F 2 122.98 6.31E+02 116.68 6.31E+02 1. l 7E+02 F 3 145. 81 l.84E+02 12.08 l.84E+02 7.21E+Ol F 4 661.99 1. 47E+05 385.75 6.61E+Ol 1.27E+ Ol l.47E+05 3.86E+02 F 5 1173.88 7.21E+03 87 . 09 4.55E+Ol 8.62E+OO 7.16E+03 8.75E+Ol F 6 1275.71 6.24E+Ol 12.27 6.24E+Ol 1.23E+Ol F 7 1333.26 6.17E+03 79.05 6 .17E+03 7.90E+Ol F 8 1461.72 6.87E+02 27.18 6.87E+02 2.72E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma

9/12/201 t 8:00:07AM Page3 of6 Analysis Report for SUMP AREA# 1 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) (uCVgra111$) Uncertainty K-40 0.86 1460.75

10.67 7.93E-06 3 . 83E-07 C0-60 0.92 1173.22

100 . 00 7 . 30E-06 1.97E-07 1332.49

100.00 7.03E-06 2 .0lE-07 CS-137 0 . 98 661 . 65

85.12 1. 0SE-04 2.85E-06 CE-141 0 . 97 145.44

48 . 40 7.42E-08 2.91E-08 AM-241 0.99 59.54

36.30 5.77E-06 2.57E-07

= Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

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

K-40 0.860 7. 93E- 0 6 3 . 83E- 07 A C0-60 o. 92 1 7 . 16E-06 1.41E-07

.,11 CS-137 0.982 1.0SE-04 2 .BSE-06 CE-141 0.978 7.42E-0 8 2 . 91E-08 AM-241 0.999 5. 77E-0 6 2 . 57E- 07

9/12/2017 8 :00:07AM Pagc4of6 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 Sof6 Analysis Report for SUMP AREA# 1 9- 9-17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/12/2017 7:59:58AM 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 2 122.98 1.75237E-Ol 18.50 Tol. EU-154 en ~"l..>()

F 6 1275.71 1.73398E-02 19.65 0, tJq 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 Nudide Library Used : C:\Canberra\Apex\Root\Dalryland_NPPU.ibrary\HOTLAB.NLB Nuclide Energy Y,e/d(%) Activity NuclideMDA UneMDA Name (uCVgrams) {uCl/grams) (uCl/grams)

(keV)

+ K-40 1460 . 75

10.67 7.93E-06 5.14E-07 5.14E-07

+ AR-41 1293.64 99.16 2.12E+03 5.69E+03 5.69E+03

+ C0-60 1173.22

100.0C 7.30E-06 6.81E-08 1. 38E-07 1332.49

100.00 7.03E-06 6.81E-08

+ KR-85 513.99 0.43 3.49E-05 5.29E-05 5.29E-05

+ Y-88 898.04 93.70 1.17E-07 5.29E-08 1.68E-07 1836 . 06 99.20 -2.23E-08 S. 2 9E-08

+ NB-94 702.63 100.00 6.99E-08 l.llE-07 1.llE-07 071.10 100.00 -l. 3 8E-07 l.45E-07

+ I - 131 284.30 6.06 -1. 66E-06 3 .36E-07 3.87E-06 364.48 81.20 -1.68E-07 3.36E-07 636.97 7.27 -1.14E-06 3.27E-06

+ CS-134 604.70 97.60 8 . 86E-08 l.47E-07 1.85E-07 79 5 .84 85.40 -1. 03E-08 1.47E-07

+ CS-137 661 .65

85 . 12 1.0SE-04 2 .04E-07 2 .04E-07

9/12/2017 8:00:07AM Page6of6 Analysis Report for SUMP AREA# 1 9-9-17 Nuclide Energy Yield(%) Activity NuclldeMDA LlnellDA Name (uCVgrams) {uCVgrams) (uCVgrams)

(keV)

+ CE-144 80 . 12 1. 36 6 . 08E-07 1.24E-06 l.21E-05 133.51 11.09 1.20E-07 l.24E-06

+ EU-152 121 . 78 28.40 6.02E-07 2.7SE-07 4.88E-07 244 . 69 7.49 -1.SSE-0 7 2.26E-06 964.00 14.44 -3.38E-07 l.19E-06 1408 . 00 20.74 -1. 4SE-07 2.75E-07

+ EU-154 123.07 40.40 2 . 57E-07 2.67E-07 3.43E-07 247.94 6.60 -4.37E-06 2.73E-06 723.30 19.70 4.77E-08 ?.77E-07 873.20 11.50 -S.02E-07 1. 27E-06 1004.76 17.90 2.86E-07 8.96E-07 1274.51 35.50 2.17E-07 2.67E-07

+ EU-155 86 . 54 32.80 -1 . 84E-07 4.56E-07 4.56E-07 105 . 31 21.80 -1. 40E-07 6.27E-07

+ BI-214 609.31 46.30 2 . llE-07 3.88E-07 3.88E-07 1120.29 15.10 -2.65E-07 l.04E-06 1238 .11 5.94 6.0lE-07 l.70E-06 1377 . 67 4.11 -4 . 88E-08 1. 45E-06 1407.98 2.48 -l.21E-06 2.30E-06 1509.19 2.19 -7. 17E-07 2.41E-06 1764.49 15.80 3 . 72E-07 4.32 E-07

+ PB-214 77 .11 10.70 1. 20E-06 5.64E-07 l.61E-06 295.21 19.20 2 . 14E-07 9.76E-07 351. 92 37.20 5.68E-09 5 .64E-07

+ PA-228 89.95 22.00 6 . 35E-06 3.19E-06 5 .24E-06 93.35 35.00 1 . 91E-06 3.19E-06 105.00 16.30 -2.36E-06 6.66E-06 129.22 2. 97 9 . 96E-06 3.69E-05 338.32 5.30 2.57E-05 3.0SE-05 463 . 00 13.80 1.lSE-05 1. 79E-05 911. 23 16.70 2.21E-06 7.64E-06

+ AM-241 59.54

36 . 30 5 .77E-06 8 . 22E-07 8.22E-07

+ CM-243 103.76 23.00 1. 53E-07 5.97E-07 5.97E-07 228.18 10.60 2.19E-07 1. 58E-06 277.60 14.00 2.23E-08 1.32E-06

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MOA value not calculated

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

? = CAUTION: MDA value is Inconsistent with CUrrie MOA at 95% confidence level

9/12/2017 9:02:19AM Page 1 of6

-Analysis Report far 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 Facility

8.825E+02 grams

Dairyland_NPP

/

Sample Taken On : 9/9/2017 1:48:00PM Acquisition Started : 9/12/2017 8:01:36AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli /

Live lime : 3600.0 seconds./

Real lime :3631.8s/

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 Anal;,-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 Net Peak Net Area Continuum FWHM (keV) Centroid Area Uncertainty Counts (keV)

No. start end 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 1.73E+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 S.3SE+02 23.56 1.93E+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 Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted (keV) Area Uncertainty Background Uncert. Area Uncert.

No.

F 1 59.22 1. 43E+03 135.85 l.43E+03 1. 36E+02 F 2 186.45 4.83E+02 109.72 4.83E+02 1.10E+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 5.3SE+02 2.36E+Ol 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 2.0SE-07

= 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 Wt mean wt mean Comments Name Id Activity Activity Confidence Uncertainty (uCUgrams)

K-40 0.876 6.61E-06 3.44E-07

?, C0-60 0 .912 2.86E-06 6.5 5E-08

.,Ps CS-137 0.979 2.00E-04 5 . 43E-06 RA-226 0.991 3.23E-06 7.40E-07 AM-241 0.984 2.03E-06 2.0SE-07

9/12/2017 9:02:19AM Page4 oftS 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 Pages of6 Analysis Report for SUMP AREA# 2 9-9-17 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/1212017 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 Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LinelADA Name (keV} (uCUgrams) (uCUgrams) (uCUgramsJ

+

-41 K-40 0-60 1460.75 1293.64 1173.22 1332.49 10.67 99.16 100.00 100.00 6.61E-06

-1.24E+03 2.SOE-06 2.94E-06 3.BOE-07 6.34E+03 6.16E-08 3.SOE-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 .lSE-07 1836.06 99.20 -1.99E-08 4.17E-08

+ NB-94 702.63 100.00 4.14E-08 8.68E-08 8.68E-08 871.10 100.00 -7.62E-08 l.02E-07

+ I-131 284.30 6.06 4.21E-06 4.63E-07 5.2BE-06 3 64.48 81.20 -2.23E-07 4 .63E-07 636.97 7.?. 7 -4.67E-06 4.0SE-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-131 661. 65

85.12 2.00E-04 2.35E-07 ~.3!:iE-07

+ CE-144 80.12 1.36 l.34E-05 l.67E-06 1.64E-05 133.51 11.09 l.04E-06 1. 67E-06

+ EU-152 121.78 28.40 5.85E-07 2.SlE-07 6.SOE-07

9/12/2017 9:02:19AM Page 6 of6 Analysis Report for SUMPAREA#2 9-9-17 Nuclide Energy Yield(%} Activity NuclldeMDA LlneMDA Name (uCVgrams) (uCUgrams) (uCVgrams)

(keV)

EU-152 244.69 7 .49 -4.67E-07 2.51E-07 3.06E-06 964.00 14.44 -1.88E-07 8.17E-07 1408.00 20.74 -4.46E-08 2.SlE-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-08 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 1.95E-07 1. 28E-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. OSE-06 8 . 03E-07 1.0SE-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 SURVEY UNIT L1-SUB-CDR NORTH LOADING AREA ATTACHMENT 8 GEL LABORATORIES ANALYTICAL REPORTS 51

..Mi*

_.....I Laboratories LLc l'OBo,;i~712 Cl'<Uteston SC29417 a member of The GEL Group INC 2[14(1 ~vagi; l!Oad Chati~sw1. sC29407 P 84~.nM.8171 F 84',.766.1178 gel.com January 22, 20 l 8 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 Ill Ill Ill lllllll II 111111111111111

GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis 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 LOD.

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 Laboratories 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 : LaCrosseSol utions Address: S460 1 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-l 7 09:05 Receive Date: 30-0CT-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 173 1815 The following Prep Methods were performed:

Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GlrRAD-A-021 LYTI I0/31/ 17 0808 1731648 The following_Analytical Methods were performed:

Method ---=D~e=s=cn=*p=t=io=n'--- - -- - - - Analyst Comments ASTM C 1475-00 Modified Surrogate/Tracer Recovery Result Recovery% Acceptable Limits Americium-243 Tracer Test Alphaspec Np, Solid "Dry Weight Corrected"

- - --- -Nominal

- -- -- 97.7 (15%- 125%)

Notes:

Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma}.

Column headers are defined as follows :

DF : Dilutio n Factor Le/LC: Critical Level DL : Detect ion 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: 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: 30-0CT-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 -0.00137 +/-0.00298 0.00659 0.010 pCi/g HAKB 01/17/18 0951 1731815 The following Prep Methods were performed:

Method Description Analyst Date Time Prep Batch Dry Soil Prep DrySoilPrepGL-RAD-A-021 LYTl 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°/o Acceptable Limits Americium-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 LABO RA TORIES 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-17 14:05 Receive Date: 30-0CT-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 0.00181 +/-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 1 YT! *---=-10"'1c.:31"'11c::1:----o=s=os.c-----c-:11:;c3-:-,164,-:-;:-s- - - - -

The following Analytical Methods were performed:

Method Description -~------- Analyst Comments ASTM C 1475-00 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limit~.

Arnericium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 94.4 (15%-125%)

Notes:

Counting Uncertainty is calculated at the 95% confidence level (l.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 : S460I State Hwy 35 Genoa, Wisconsin 54632

Contact:

lVu-. 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: 30-0CT-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 Time Prep Batch Dty Soil Prep Dry Soil Prep GL-RAD-A-021 LYTI 10/31/17 0808 1731648 The following Analytical Methods were performed:

Method Des.c""r""ip=t=io=n' - - - - - - __ __ - - - - - - - ----'-A=n=a=-Jy--=s'-'-

t -=C=om=m=e=n=ts,_

1 AS1M C 1475-00 Modified Surrogate/fracerRecovery Test - - - - - - - - - - - - - - - - - - Result_ Nominal __ Recov~ % __ Acceptable Limits Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 101 (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 RA TORIES 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-014-SB Project: ENRG07001 Sample ID: 441560005 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-17 14: I 8 Receive Date: 30-0CT-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 -0.00203 +/-0.00347 0.00748 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 LYT! 10/31/17 0808 1731648 The following Analytical Methods were performed:

Method Description _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Analyst Comments ASTM C 1475-00 Modified Surrogate/Tracer Recovery __T_es_t * -*--***-- _ _ _____________R_e_su_lt___ N_om_i_n~- -Recovery% ..... Acceptable_~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 C Iient Sample ID: NRC #4 Project: ENRG0700I Sample ID: 441560006 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-17 13 :45 Receive Date: 30-0CT-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 0 1/ 17/18 0950 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 173 1648 The following Analytical Methods were performed:

Method Description Analyst Comments ASTM C 1475-00 Modified Surrogate/fracer Recovery :r_e_s_

t ---- - - --------------- - Result - ~ominal_____ _Recovery% Acceptable Limits Americiurn-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 94.7 (1 5%--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 LA BORATORIES 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: Sump Area#l Project: ENRG07001 Sample ID: 441560007 Client ID: ENRG070 Matrix: Soil Collect Date: 09-SEP-l 7 13:43 Receive Date: 30-0CT-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 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 pe_rn_o_rrn_e_d_:_______

Method Description _:_A""n,.,,a,_.ly..,,st"---C=o=m=me."e=nts=-_____________

ASTM C 1475-00 Modified Surrogate/Tracer Recovery __ Test ________________ ________Result ___~ominal _ Re~very~ 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 LA BORA TORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 -www.gel.com QC Summary Report Date: January 22, 2018 LaCrosseSolutions Page 1 of 2 S4601 State Hwy 35 Genoa, Wisconsin

Contact:

Mr. Jason Q. Spaide Workorder: 441560 Parnmame . ____________ NOM ___ Sample Qual _ _ _Q_C_ *- Units

RPD%

- REC% Range Anlst Date Time Rad Alpha Spec Batch 1731815 --------- ---- *----

QC 1203952679 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 QC1203952680 LCS Neptunium-237 1.45 1.54 pCi/g 106 (75%-125%) 01/17/18 09:51 Uncertainty +/-0.0514 QC 1203952678 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 defmed 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 1 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 RPD or '%Recovery limits do not apply.

N1 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 Sampie resuits 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 Workonler: 441560 Page 2 of 2 Parmname NOM Sample -~ - - -QC"'"-"'c.. . __ _U

=:.cn=i=ts,__--'RP 0

==-=D_,_!..o_....:RE

.. =-"

C'--'o/,-"-o- --=R=:a=ng!_ 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 Summacy package, or Project Manager concerning this qualifier y Other specific qualifiers were required to properly define the results. Consult case narrative.

A 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 NIA indicates that spike recovery limits do not apply when sample concentration exceeds spike cone. by a factor of 4 or more or %RPD 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 (SX) 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 petfonned under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the QC Summary.

Radiochemistry Technical Case Narrative 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 Preparation Procedure; GL-RAD-A-021 REV# 22 Preparation Batch; 173 I 648 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 441560002 LI-SUB-CDR-FSGS-009-SB 441560003 LI-SUB-CDR-FSGS-01 I-SB 441560004 LJ-SUB-CDR-FSGS-012-SB 441560005 LI-SUB-CDR-FSGS-014-SB 441560006 NRC#4 441560007 Sump Area #I 1203952678 Method Blank (MB) 1203952679 44155900l(Ll-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 procedures fo~ initial caJibration, continuing calibration, instrument controls and process controls where applicable.

Product; Dry Weight Prmaration Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Prmaration 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 441560002 LI-SUB-CDR-FSGS-009-SB 441560003 LI-SUB-CDR-FSGS-011-SB 441560004 LI-SUB-CDR-FSGS-012-SB GEL Laboratories u.c PO Boll 30712 ainsto11, SC 29'17 2040 8avaQt Read ChatlestDn, SC 29407 P 84'5518171 F 843.7111.1178 www.gel.com

441560005 LI-SUB-CDR-FSGS-014-SB 441560006 NRC#4 441560007 Sump Area #1 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.

Miscellaneous Information Additional Comments These samples are re-logs. Data transferred from Batch# 1714238.

Certification Statement Where the analytical method has been perfonned under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless otherwise noted in the analytical case narrative.

GEL I.Aboratortes u.c PO b 30n2 Olartellon, SC 29417 2040 Sav8at Road Charleston, SC 29407 P843 lil5H171 Faa:,m.1111 www.gel.com

Page: _ _ I of ,_ GEL Chain of Custody and Analytical Request GEL laboratories, I.LC Project,: i..lrC &,J A.s, TE

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- GEL Chain of Custody and Analytical Request GELL.aboratories,LLC 2040 Savage Road GEL Quote#: **See www.gel.com for GEL's Sample Acceptance SOP** Charleston, sc 29407 COC Number II>: ' GEL Work Order Number. Phone: (843) SS6-8171 PO Number: Ci,1 a~8°t..'3 Fax: (843) 766-1178 Client Name: La.,Cros.~ S O ( ~--\-;oV\ Phone:#: {d"'R. /,.,&'f- '{c'lc;<l Sample An~ysb Requested <~I (Fill in the number of containers for each test)

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Mountain Clialn of Custody Slgnahlre5 Sample Sbtpplnt and Delivery DetaUs Relinquished By {Signcdl 0..tc _Time ReceiYCd. by (sip!CdJ Dale T;- . GEL PM:

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leave field bb.uk C WHITE-= LABORATORY YELLOW = FILE PINK .., CLIENT

ma! ILaboratories LLca SAMPLE RECEIPT & REVIEW FORM Date Received:

FedEx Express Courier Other' Sl,spoctR Bll2llrd J11fannndon *

.!! i *If Net Couals > IOOi:PIII on wnples not marked "ndl01clivc", conlli:t the Rllcllation Slifciy Oroup for further

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la package, COC, and/or Sa lea nwked HAZ1 Slllllp!e 8-!pt Cdecrta Shipping containcn received intact and 1

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Chain of custody doc:umcn11 included 2

wilh shipment?

Prmemrlon MtlhQd: \Vet lea Ice Poc:lc:a Dty Ice on <>ct,er.

3 Sampica requiring cold presecvlllion witldn (0 .s 6 de

C)'l" *11111eq1r:rac- ""'m:onlld Ill Ccblus 4 Daily checlt perfonned and passed on JR Temper~ture Device Serial #:-J.....u.~--=i~-

tanperature gun? , .....lbO'~"'paaeurs Dnl<1Slmll (II ~oMeJ:

5 Sample conllliners ln111e1 and sealed?

, Samples fflllliring dicmieal pccmtYlllion at proper pH?

If Yes, MEncorcs or Soil Kits p.tcmll7 Yes_No_ (Kycs. cakc toVOAPreem)

Do VOA vials contain 11cid proservation?Yes . No_N/A. (lflllboM,*lectNo)

Do any samples 111quim Vollllilc VOA vials free ofheadspace? Yes No_NIA 7

Anllly1il? Sample ID's and conlainers affected:

8 Sianplcs reeaivcd within liolding time?

Sample lD's on COC match lD's on 9

boules?

Dall: & time on COC llllltch date & lime 10 on boulca?

Number or containers received motch SlmJlloJO~ llffce1edr 11 ttuinbcr indicated on COC?

Arc sample conlaiDCD identifiable as 12 GEL vldcd?

COC l'orm is properly signed in 13 rell uishcdhcccived 1ee1ions?

Onnmenls (Use Conllnuallan Form Ir nffiled):

GL.CHL*SR-001 Rev 5

List of current GEL Certifications as of 22 January 2018 Stete Certification Alaska UST-0110 Arkansas 88-0651 CLIA 4200904046 California 2940 Colorado SCOOOI2 Connecticut PH-0169 Delaware SC00012 DoD ELAP/ ISO l 7025 A2LA 2567.01 Florida NELAP E87156 Foreign Soils Permit P330-15-00283,P330-15-00253 Georgia SC00012 Georgia SDWA 967 Hawaii SC00012 Idaho Chemistry SCOOOI2 Idaho Radiochemistry SC00012 Illinois NELAP 200029 Indiana C-SC-01 Kansas NELAP E-10332 Kentucky SDWA 90129 Kentucky Wastewater 90129 Louisiana NELAP 03046 (AI33904)

Louisiana SDWA LA180011 Maryland 270 Massachusetts M-SC012 Michigan 9976 Mississippi SC00012 Nebraska NE-OS-26-13 Nevada SC000122018-I 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 10120001 Tennessee TN02934 TexasNELAP T104704235-17-12 UtahNELAP SC000122017-25 Vermont VT87156 Virginia NELAP 460202 Washington C780 West Virginia 997404

tffl=II ILaboratories LLc PO EoiS0712 Charleston S(:2f*4'7 a member of The GEL Group 1Nc : )4Hit.*,-:.o~ Ro~d Charl~61Cn SC 2~407 P 84'~ 5So.8171 F B4S.766.1!78 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) 556-8 I 71, ext. 4453.

Sincerely,

~

Kaitlyn Stone for Edith Kent Project Manager Purchase Order: 672583 Enclosures p~illl llHIII II II lllll 11111111111

GEL LABO RA TORIES LLC 2040 Savage Road Charleston SC 29407 - (643) 556-8171 - www.gel.com Certificate of Analysis Report for ENRG070 LaCrosseSolutions, 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 LOO.

UI Gamma Spectroscopy--Uncertain identification 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 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: l 5-SEP-17 09:05 Receive Date: 3 O-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 U 0.0241 +/-0.0289 0.0444 0.400 pCi/g BXA4 I l/21/17 1420 1718468 Americium-243 0.0636 +/-0.0393 0.0173 0.400 pCi/g Curium-243/244 U -0.00195 +/-0.0134 0.0327 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptuniurn-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" Plutonium-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 TXJI 11/17/17 0846 1715764 5 Gamma, Cs 137, Co60, Nb94, Eu 152, Eu 154, Eul 55 "Dry Weight Corrected" Cesium-137 0.804 +/-0.115 0.0481 1.00 pCi/g MXRI 11/16/17 1037 1714268 6 Cobalt-60 U 0.0245 +/-0.0399 o:088 pCi/g Europium-152 U -0.055 +/-0.0747 0.138 pCi/g Europium-154 U -0.0 I 04 +/-0.0838 0.171 pCi/g Europium-155 U 0.0393 +/-0.0717 0.151 pCi/g Niobium-94 U -0.00984 +/-0.024 0.0438 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.248 +/-0.180 0.276 0.400 pCi/g KSD1 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" Jron-55 U -2.22 +/-4.73 6.51 10.0 pCi/g TXJI 11/18/17 0422 1715698 II Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 3 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-008-SB Project: ENRG07001 Sample ID: 436541001 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 2.73 +/-1.99 321 5.00 pCi/g TXJI 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 10/3 1/17 0808 1714238 The following Analytical Methods were performed: -- - -- -*--- - - ---- - -

Method -=D~e=s-=-

cr°"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-1 1-RC Modified 4 DOE EML HASL-300, Pu-1 1-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 JO DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-I, Modified 12 DOE RESL N i- I, Modified Surrogate/fracer Recovery Test *-- - - ---**-- - __ -~ __!lesult_ . .. 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%)

Plutoniwn-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 81.1 (15%-125%)

Corrected" Plutonium-242 Tracer Liquid Scint Pu24 l , Solid "Dry Weight Corrected" 81. l (15%- 125%)

Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 96.4 (25%-125%)

Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 86.6 (25%-125%)

Technetlum-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%- 125~0)

Notes:

Page4 of45

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 C lient ID: ENRG070 Parameter Qual!fier 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-SB Project: ENRG07001 Sample ID: 436541002 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-17 13:54 Receive Date: 30-0CT-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 0.556 +/-0.101 0.026 0.400 pCi/g BXA4 11/2 1/ 17 1423 1718468 Americium-243 0.0435 +/-0.0276 0.0194 0.400 pCi/g Curium-243/244 U 0.00931 +/-0.016 0.014 Q.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-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 5.00 pCi/g TXJI 11/17/17 0847 171 5764 5 Gamma, Cs137, Co60, Nb94, Eul52, Eu154, 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 0.196 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 +l-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 11/16/17 0804 1715582 8 Liquid Scint Cl 4, Solid "As Received" Carbon- 14 u -0.851 +/-2.20 3.8 1 5.00 pCi/g BXM4 I 1/13/ 17 1408 1715576 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 u -0.03l +/-0.809 1.40 2.00 pCi/g CXS7 11/ 14/17 0716 171 5726 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" lron-55 u 3.82 +/-5.00 6.72 10.0 pCi/g T){Jf 11/18/17 0509 1715698 II 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 Proje<-1 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 TIU \ 11/ 18/17 1230 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 . LYT! 10/31/17 0808 1714238 The foHowing Analytical Methods were perfonned: _______ -- - --- - - - -* -- - - -*-*-*- -- ... _ _ _ , _ ____ _

Method _ * - - *

Description _ ___ _______ - - -'A c..:::

n=al,...y=

st~C=o=m

= m~e=n=ts~.- - ___ _ _

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 RPSOI 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/Tracer Recovery__ Test - ----*-*- - ___ .._ .. _ _____ _ __ Resul!____ Nominal . Recov~ry% . Ac~eptable Limits Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 64.8 (15o/o-125%)

Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 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 I, Solid "Dry Weight Corrected" 86.8 (15%-125%)

Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 106 (25%-125%)

Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 91.7 (25%-125%)

Technetium-99m Tracer L1qu1d Scint Tc99, Solid*As Received" 86.7 (15%-125%)

Iron-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 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 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.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-01 I-SB Project: ENRG07001 Sample ID: 436541003 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-l 7 14:05 Receive Date: 30-0CT-17 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am24I Am243, Cm243/244, Solid "Dry Weight Corrected" Americiurn-241 0.0771 +/-0.033 0.022 0.400 pCi/g BXA4 11121/17 1423 1718468 Americium-243 U 0.0107 +/-0.017 0.0235 0.400 pCi/g Curiurn-243/244 U 0.00093 +/-0.00972 0.0203 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected

Neptuniurn-237 U -0.0325 +/-0.0948 0.243 0.400 pCi/g BXA4 11/21/17 1036 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 DUI 11/17/17 0847 1715764 5 Gamma, Cs 137, Co60, Nb94, Eul52, Eul54, 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 11/16/17 1412 1717213 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U -0.287 +/-5.02 8.86 IO.O pCi/g BXM4 11/16/17 0851 1715582 8 Liquid Scint Cl 4, 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 -O. I02 +/-0.816 l.41 2.00 pCi/g CXS7 Il/14/17 0748 1715726 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U -0.95 +/-4.87 6.67 10.0 pCi/g TXJI 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.gel.com 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 PF OF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 U 1.77 +/-2.04 3.44 5.00 pCi/g nm 11118/11 1246 111s1os 12 The following Prep Methods were performed:

Method Description _____ _ _ Analyst Date Time Prep Batch L

~YT~I~ - - - 10/31/17 - ~- -~-'-,----- *-- - - -

Dry Soil Prep Dry Soil Prep GL-RAD-A-021 0808 1714238

_Ille following An~)ytical Methods were J>erfonned:

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

Method Description Analyst Comments DOE EML HASL-300, Am-OS-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 s 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--0 I Modified 10 DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-I , Modified 12 DOE RESL Ni-I , Modified Surrogate/Tracer Recovery _ Test____ -*- - - - *- - **- * *--

_ _ Result___Nominal _ Recove~ __Acceptable Limits.

Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 87.S (IS'Yo-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 (15o/o-l25%)

Corrected" Plutonium-242 Tracer Liquid Scint Pu24 l, Solid "Dry Weight Corrected" 93.3 (1 5%-125%)

Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 101 (25%-125%)

Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 87.9 (25%-125%)

Technelium-99m Tracer Liquid Scint Tc'J\I, Solid "As Received" 86.7 (15%-125%)

lron-59 Tracer Liquid Scint Fe55, Solid "Dry Weieht 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: 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: 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: LaCrosseSol utions 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 2-SB Project: ENRG07001 Sample ID: 436541004 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-17 14:08 Receive Date: 30-0CT-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" Arnericium-241 0.113 +/-0.0404 0.0109 0.400 pCi/g BXA4 11/21/17 1423 17 18468 Americium-243 U 0.00295 +/-0.0164 0.0314 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 0.400 pCi/g BXA4 11/21/17 1036 1718469 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U 0.01 75 +/-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 IOOO 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 T){J ) 11/17/17 0848 1715764 5 Gamma, Csl37, Co60, Nb94, Eu152, Eul54, Eul55 "Dry Weight Corrected" Cesium-1 37 2.21 +/-0.168 0.0537 1.00 pCi/g MXRI 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 0.400 pCi/g KSDI 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 171 5582 8 Liquid Scint Cl 4, Solid "As Received" Carbon-14 U 0.118 +/-2.33 3.99 5.00 pCi/g BXM4 11/13/17 1532 171 5576 9 Liquid Scint Tc99, Solid "As Received" Tcchnetium-99 U 0.308 +/-0.751 1.28 2.00 pCi/g CXS7 11/14/17 0820 1715726 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" lron-55 U -0.152 +/-4.83 6.55 10.0 pCi/g TXJ I 11/18/17 0644 1715698 II Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 12 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. Spaidt:

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 DF 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 performed:

Method Description Analyst Date Time Prep Batch Dry Soil Prep **-,,0ry

=--~so --,i~l Pre

=--p-,G==L-

~-RA~D=----,

A--02

=-c-1 -- LYTI - - -1~0~/3~1/~1=7 - *- - - - - - * * - -

0808 1714238

_pie following Analytical Methods were performed: __ _ * - * * - - - - ~- -- - - - -- - ---- - - - -- ----- - -- -- ***- -

Method - --"DCC.. e-'-'s'-"c=ri'-"-p""'=n tio = --- - -- - Analyst Comments ___ __ __ _ __ _ _

1 DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modifi ed 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOE EML HASL-300, Pu- 11-RC Modified s DOE RESL Ni- I 6 DOE HASL 300, 4.5.2.3/Ga-OI-R 7 EPA 905.0 Modified/DOE RPSOl 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 N i-1, Modified Surrogateffracer Recovery Test __ ______ B:esult __ Nomin~__ _Recovery% ..... Acceptable Limits Americium-243 Tracer 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 Alpha.,pec Np, Solid "Dry Weight Corrected" 101 (15%-125%}

Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 89.6 (15%-1 25%)

Corrected' Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 89.6 ( 15%-125%}

Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 106 (25o/o- 125%}

Strontium Carrier GFPC, Si90, Solid "Dry Weight Corrected" 79 (25%-1 25%)

Technetium-99m T111cer Liquid Scint Tc99, Solid

As Received' 89.1 (15%- 125%}

lron-59 Tracer Liquid Scint FeSS, 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: 84601 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 DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (l.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 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 Matrix: Soil Collect Date: 13-SEP-17 14:18 Receive Date: 30-0CT-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 0.0796 +/-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 11/21/1 7 0927 1718470 3 Plutonium-239/240 U O.Olll +/-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 /24/1 7 1031 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 TIO! 11 /17/17 1044 1715764 5 Gamma, Cs137, Co60, Nb94, Eul52, Eul54, Eu155 "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-1 52 U 0.0472 +/-0.09 13 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 C 14, Solid "As Received" Carbon-14 U 1.46 +/-2.31 3.90 5.00 pCi/g BXM4 11 /13/17 16 14 171 5576 9 Liquid Scint Tc99, Solid "As Received" Tecimetium-99 U -0.783 +/-0.902 1.60 2.00 pCi/g CXS7 11 /14/ 17 0853 1715726 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" lron-55 U 0.527 +/-4.81 6.53 10.0 pCi/g TIO ! 11/ 18/17 0731 1715698 II 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: November27,2017 Company: LaCrosseSolutions Address: S460I 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 Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 U 1.95 +/-2.33 3.92 5.00 pCi/g TXJ I 11/17/17 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-021 LYTI 10/31/17 0808 1714238

.The following_Analytical Methods were perfonned: _ __ * - - -*- -- - - -- -- * - - - - -- --- -

Method Description __ __ _ _ _ _ __ _ Analyst Comments I 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 DOERESLNi-1 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 10 DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe- I, Modified 12 DOE RESL Ni-I, Modified Surrogateffracer Recovery _Te~!___ _ __.._ _ _*- --**- -- - * *- -*****Result _ __ Nomi~~ - _Recovery% _ 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 "Dly 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 l , Solid "Dry Weight Corrected" 72.7 (15%-125%)

Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 111 (25%-1 25%)

Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 89.2 (25%-1 25%)

Technetium-99m Tracer Liquid ScintTc99, Solid "As Received" 84.4 (15%-125%)

Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 77.4 (l 5o/o- I 25%)

Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 65.5 (25o/o- l25%)

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: Ll-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 of45

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 _ u_ n_it_s _ P_F_ . DF Analyst J?ate 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 171 8468 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/.ll/17 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 171 8470 3 Plutonium-239/.l40 0.615 +/-0.106 0.0325 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 6.57 +/-2.57 4.09 5.00 pCi/g BXA4 11 /24/17 1103 171 8471 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 11/17/17 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 MXRI 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 0.2 18 pCi/g Europium-155 U 0.0694 +/-0213 0.380 pCi/g Niobium-94 U 0.0541 +/-0.0447 0.0819 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 KSDI 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 8 Liquid Scint C14, Solid "As Received" Carbon-14 U -0.44 +/-2.37 4.09 5.00 pCi/g BXM4 11/13/17 1655 1715576 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 7.92 +/-1.13 1.58 2.00 pCi/g CXS7 11/15/17 0736 1715726 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" lron-55 U 2.45 +/-4.99 6.75 10.0 pCi/g TXJ I 11/18/17 08 18 17 15698 JI 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: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632 Contnct: 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 Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 50.4 +/-3.53 3.28 5.00 pCi/g TXJI 11/18/17 1302 17 1570S 12 The following Prep Methods were performed:

Method Description Analyst Date Time Prep Batch Dry Soil Prep ------,D

=-ry

---=-

S~oi-cc l P=-re-p--G=L

~-~RAD--c=--A

,--0

=2~1- ----- LYTI - ~10~/~31-/1~7~ - - 0~80~8- -1~7-14~2-38-- -- -- -~ -

The followin~ Analytical Methods were performed: * - - - -- - - -- - -- - *- - *- -- ~ - -- _ __

Method Description ___ _ _ _ _ ______ _ - - -* ___ Analyst C ~~o_m_m~e=n=ts~-- - - -

I DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 147S-OO 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 90S.O Modified/DOE RPSOI 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 Surrogate/fracer Recovc:ry _ Test ---*- * - - - -- -*- *--

_Result ___ Nominal ___ Recovery% AcceptableUmits Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 9 1.4 ( 15%- 125%)

Solid "Dry Weight Cornx:ted" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 68.1 (15%-125%)

Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid 'Dry Weight Corrected' 82.S (15%-1 25%)

Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 8 1.9 (15o/o-125%)

Corrected" Plutonium-242 Tracer Liquid Scint Pu241 , Solid "Dry Weight Corrected" 81.9 (15%-1 2S%)

Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 95.9 (25o/o- 12S%)

Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 77.7 (25%-125%)

Technetium-99m Tracer Liquid Scint Tc99, Solid ' As Received" 93.S (15%-125%)

lron-S9 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 72.9 ( 15%-12S%)

Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected' 79.8 (25o/o-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, 201 7 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 OF 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-l 7 13:43 Receive Date: 30-0CT-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 10.4 +/--0.389 0.0181 0.400 pCi/g BXA4 I lf'l l/ 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 o.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 17 18470 3 Plutonium-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 17 18471 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U 1.70 +/-1.41 3.09 5.00 pCi/g nm w11111 1045 17 15764 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu 154, Eu155 "Dry Weight Corrected" Ccsium-137 193 +/-1.30 0.182 1.00 pCi/g MXRI 11/16/17 1122 1714268 6 Cobalt-60 12.3 +/-0.406 0.o788 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 KSD I 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 11 59 1715582 8 Liquid Scint Ct 4, 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, So!id "Dry Weight Corrected" lron-55 U -0.263 +/-4.66 6.35 10.0 pCi/g TXJI 11/18/17 0905 1715698 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 2 1 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: ENR.G07001 Sample ID: 436541007 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-63 183 +/-5.79 3.09 5.00 pCi/g T){JJ 11/18/ 17 1319 1715705 12 The following Prep Methods were performed:

Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RA[)..A..02 1 LYTl 10/31/ 17 0808 1714238 The following Analytical Methods were performed:

J\1ethod --'D

~ es=cc:..r1"'*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-I I-RC Modified 4 DOE EML HASl,.300, Pu-It-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 EERFC-01 Modified 10 DOE EML HASi,.300, Tc-02-RC Modified 11 DOE RESL Fe-I , Modified 12 DOE RESL Ni-I, Modified Surrogate/fracer Reco~ery . Test *- ---- -*-- **-**-- _ ___ _ **- - - ** - - Result_ __ Nominal -

Recov~ ___ _Acceptable Limits Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 114 (15o/o-125%)

Solid "Dcy Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 75.3 ( 15%-125%)

Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 100 (lWo-125%)

Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid 'Dcy Weight 108 ( 15%-125%)

Corrected" Plutonium-242 Tracer Liquid Scint Pu24 I, Solid "Dry Weight Corrected" 108 ( l So/o- 125%)

Nickel Carrier Gamma N i59, Solid "Dry Weight Corrected" 107 (25%- 125%)

Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 86.6 (25%-125%)

Technetium-99m Tracer Liquid Scint Tc99, Solid ' As Received" 90.9 ()So/o- 125%)

lron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected' 78.3 (15%- 125%)

Nickel Carrier Liquid Scint Ni63, Solid "DI)' Weight Corrected" 82.5 (25%-1 25%)

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 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 23 of 45

GEL LABO RATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 -www.gel.com QC Summan: Report Date: November 27, 2017 LaCrosseSolutlons Pa&e J of 7 S4601 State Hwy 35 Genoa, Wiscoasin

Contact:

Mr. Jason Q. Spaide Workorder: 43654)

- - - -- - - - -- - -- - - - ~ -

Parmname _ _ _ _ __ _ NOM _ __ Sample Qual ~ Units RPD"lo REC% Range Anlst Date Time Rad Alpha Spec Batch 1718468 *~ --* ---* *--*-*-- ---

QCl203918724 436541001 DUP Americium-241 u 0.0241 0.0305 pCi/g 37-1 (0%-100%) BXA4 11/21/17 14:23 Uncertainty +l-0.0289 +l-0.021 Americium-243 0.0636 u 0_00265 pCi/g 57.8 (O"/o - 100%)

Uncertainty +l-0.0393 +/-0.0171 Curium-2431244 u -0.00195 u -0.00152 pCi/g NIA NIA Uncertainty +l-0.0134 +l-0.00674 QC1203918725 LCS Americium-241 0.980 0.900 pCi/g 91.8 (75o/o-125%) 11/21/t 7 14:23 Uncertainty +l-0.100 Americium-243 u 0.00409 pCi/g (75o/o-l 25%)

Uncertainty +1-0_01 t 5 Curium-243/244 1.24 1.09 pCi/g 87.5 (75%-125%)

Uncertainty +l-0.109 QC1203918723 MB Americium-24 t u 0.00156 pCi/g ll/21/17 14:23 Uncertainty +l-0.00866 Americiwn-243 u 0.0125 pCi/g Uncertainty +l-0_0223 Curium-243/244 u -0.00213 pCi/g Uncertainty +l-0.00643 Batch 1718469 - - -*- - **-- - - - ---

QCl203918727 436541001 DUP Neptunium-237 u 0.00876 u -0.0104 pCi/g NIA NIA BXA4 11/21117 10:36 Uncertainty +l-0.0993 +l-0.0441 QCl203918728 LCS Neptunium-237 8.79 9.12 pCi/g 104 (75%-125%) 1I /21/17 10:36 Uncertainty +/-0.870 QC1203918726 MB Neptunium-237 u -0.0224 pCi/g 11/21/17 10:36 Uncertainty +l-0.0436 Page 24 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 -www.gel.com QC Summa!:!

Workorder: 436541 Page 2 of 7 Parmname NOM Sam~le Qual QC Units RPD% _REC% Range Anlst Date Time Rad Alpha Spec Batch 1718470 -*-- - - - * - - - - -- - -

QC1203918730 436541001 DUP Plutonium-238 0.0137 u 0.00898 pCi/g 12.8 NIA BXA4 11/2 l/l 7 10:37 Uncertainty +/-0.0181 +l-0.0129 Plutoniurn-2391240 u 0.000183 u 0.00325 pCi/g NIA NIA Uncertainty +l-0.0) 35 +l-0.00914 QC120391873l LCS Plutonium-238 u 0.0141 pCilg 11/2 1117 10:06 Uncertainty +l-0.0166 Plutonium-2391240 0.984 0.921 pCi/g 93.7 (75%-125%)

Uncertainty +l-0.11 6 QC1203918729 MB Plutoniurn-238 u -0.00125 pCi/g 11/21117 10:06 Uncertainty +l-0.0107 Plutoniurn-2391240 u 0.00394 pCi/g Uncertainty +l-0.0 148 Batch 1718471 -- -- --- - - --- -- - - - - ---

QC1203918733 436541001 DUP Plutonium-24 1 u -1.46 u -1.6] pCi/g NIA NIA BXA4 11/24/17 12:38 Uncertainty +/-2.30 +l-2.25 QC1203918734 LCS Plutonium-241 35.9 33.8 pCi/g 94.2 (75o/o-125%) 11/24117 13:10 Uncertainty +l-3.12 QCl203918732 MB Plutonium-241 u -0.755 pCi/g 11124117 12:06 Uncertainty +l-2.64 Rad Gamma Spec Batch 1714268 - - -

QC 1203908226 436541001 OUP Cesium-137 0.804 0.939 pCi/g 15.5 (OO/o-20"/o) MXRI 11/16117 12:28 Uncertainty +/-0.1 I 5 +l-0.0985 Cobalt-60 u 0.0245 u 0.0247 pCi/g NIA NIA Uncertainty +l-0.0399 +l-0.0356 Europium-152 u -0.055 u -0.0378 pCilg NIA NIA Uncertainty +/-0.0747 +/-0.0542 Page 25 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summa!.!

Workorder: 436541 Page 3 of 7 Parmname NOM Sample~ QC

- -Units

-- - RPD%

- -- ---- - - - - *Date - - -Time

* RECo/o -~ - Aolst Rad Gamma Spec Batch 1714268 Europium-154 u -0.0)04 u -0.00504 pCi/g NIA NIAMXRI l)/j 6/17 12:28 Uncertainty +l-0.0838 +l-0.0758 Europium-155 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 QC I203908227 LCS Americium-241 488 510 pCi/g 104 (75%-125%) 11116117 12:02 Uncertainty +l-11.2 Cesium-137 175 177 pCi/g 101 (75o/o-125%)

Uncertainty +l-3.38 Cobalt-60 139 138 pCilg 98.9 (75o/o-125%)

Uncertainty +l-3.57 Europium- t 52 u 0.586 pCi/g Uncertainty +l-1.49 Europium-154 u -0.552 pCi/g Uncertainty +l-l.06 Europium-155 u -0.821 pCi/g Uncertainty +/-1.36 Niobium-94 u 0.246 pCi/g Uncertainty +/-0.491 QC l203908225 MB Cesium-137 u 0.00657 pCi/g lt/16/17 11 :23 Uncertainty +l-0.0157 Cobalt-60 u 0.00816 pCi/g Uncertainty +l-0.0136 Europium-152 u -0.00798 pCi/g Uncertainty +l-0.0366 Europium-154 u -0.0148 pCi/g Uncertainty +l-0.0406 Europium-155 u -0.00742 pCi/g Uncertainty +l-0.0261 Page 26 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 -www.gel.com QC Summa!.!

Workorder: 436541 Page 4 of 7

-- NOM

-- REC 0.4 Parmname SamJ!le~ QC Units RPD% Range Anlst Date _ Time Rad Gamma Spec Batch 1714268 N iobium-94 u -0.000682 pCi/g MXR I 11/16117 ll :23 Uncertainty +l-0.0149 Batch 1715764 - - - - - - - -- - - - - ----------

QC12039 11889 436541001 DUP Nickel-59 u -1.72 u -1.05 pCi/g NIA NIA nm 11/17/ 17 11 :SS Uncertainty +/-1.60 +l-1.S5 QCl20391 1890 LCS Nickel-59 93.6 90.0 pCi/g 96.2 (75%- 125%) 11/17/ 17 11:59 Uncertainty +l-6.15 QC 1203911888 MB Nickel-59 u 0.485 pCi/g 11/17/ 17 10:46 Uncertainty +l-0.518 Rad Gas Flow Batch 1717213 - - -- * - - - - - - - - -- *- - - - - - - - - -

QC l203915501 436541005 DUP Strontium-90 u 0.0795 u 0.169 pCilg NIA NIA KSDI 11/16/ 17 14:13 Uncertainty +l-0.1 59 +/-0. 154 QC\203915502 LCS Strontium-90 13.8 12.1 pCi/g 87.5 (75%-1 25%) 11/16/ 17 14: 13 Uncertainty +/-0.695 QC1203915500 MB Strontium-90 u 0.0523 pCi/g 11/16/17 14:13 Uncertainty +/-0.140 Rad Liquid Sci*tillatioa Batch 1715576 --- - - - - - -- -

QC1203911442 436541001 DUP Carbon- 14 u 0.720 u -0.498 pCi/g NIA N/ABXM4 11/13/ 17 19:02 Uncertainty +/-2.36 +l-2.19 QC12039 11444 LCS Carbon-14 140 139 pCi/g 99.3 (75%- 125%) 11/13/17 20:26 Uncertainty +l-4.50 QC1203911441 MB Carbon-14 u 1.49 pCi/g 11/13/ 17 18:19 Uncertainty +/-2.26 Page 27 of 45

GEL LABO RATORIES LLC 2040 Savage Road Charleston, SC 29407 -(843) 556-8171-www.gel.com QC Summa!!

Workorder: 436541 Page 5 of 7

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

Parmname NOM Sample~ QC Units RPD%, REC% Range Anlst Date Time Rad Liq*id Scintill1tion Batch 1715576 QC12039I 1443 436541001 MS Carbon-14 260 u 0.720 246 pCi/g 94.8 (75%-125%) BXM4 ll/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 11116/17 13 :33 Uncertainty +/-5.11 +/-5.14 QCl203911464 LCS Tritium 53.7 50.4 pCi/g 93.9 (75o/o-125%) 11/16/17 15:07 Uncertainty +l-7.27 QC1203911461 MB Tritium u 1.06 pCi/g 11/16117 12:46 Uncertainty +l-5.16 QC1203911463 436541001 MS Tritium 108 u 1.27 95.0 pCilg 87.7 (75o/o-125%) 11/16117 14:20 Uncertainty +/-5.11 +/-14.1 Batch 1715698 - - - - ~ ~----------- - -

QC120391 1707 436541001 DUP Iron-55 u -2.22 u -0.891 pCi/g NIA NIA TXJl 11/1811710:40 Uncertainty +l-4.73 +/-4.89 QCl203911708 LCS lron-55 126 128 pCi/g IOI (75%-125%) ll/18117 11 :27 Uncertainty +l-6.70 QC1203911706 MB lron-55 u 3.13 pCi/g ll/18/17 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 +/-1.99 +l-l.80 QCl203911730 LCS Nickel-63 85.9 94.l pCilg 110 (75o/o-125%) i 1/18117 00:45 Uncertainty +/-4.66 Page 28 of 45

GEL LABO RA TORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 -www.gel.com QC Summa!:!

Workorder: 436541 Page 6 of 7 Parmname NOM Sam~le Qual QC Units RPD% REC% Ran2e Anlst Date Time Rad Uq*id Scintillatioa Batch 1715705 QCl203911728 MB Nickel-63 u 2.30 pCi/g TXJI 11/18117 00:12 Uncertainty +l-1.95 Batch 1715726 - --- -------

QCl203911766 436541001 DUP Technetium-99 u -0.208 u 0.425 pCi/g NIA NIA CXS7 11/14117 11 :02 Uncertainty +/-0.744 +/-0.826 QC1203911767 LCS Technetium-99 34.2 25.9 pCi/g 75.8 (75%-125%) 11/15117 06:31 Uncertainty +l-1.19 QC1203911765 MB Technetium-99 u -0.368 pCi/g 11114/17 10:30 Uncertainty +/-0.624 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

> 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 AnaJyte 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 RPD 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. Refef to the appiicabie 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 Spectroscopy-Uncertain identification Page 29 of 45

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder: 436541 Page 7 of 7 Pco.

=- a"-'

rm = n=

am= e_ _ _ _ ________-"N-'-O "'"M

~ ---°" Sa"'m

="-

pc-=

le__,Q"'-'u=a=l _ ____,,Q...:C= ----=

U.:;;cn""its"'-_~RP

=-=D'-'"c.cl,*__R

= EC

.=-..:

"1,.=c.

o_ Range Aalst Date Time VJ 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.

A RPO 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 NIA indicates that spike recoveiy 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 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.

Page 30 of 45

Radiochemistry Technical Case Narrative LaCrosseSolutions, LLC (ENRG)

SDG #: 436541 Product: Alphaspec Isotopic Am241 Am243, Cm243/244, Solid Analytical Method: DOE EML HASL-300, Am-05-RC Modified Analytical Procedure; GL-RAD-A-011 REV# 26 Analytical Batch; 1718468 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 SwnpArea#l 1203918723 Method Blank (MB) 1203918724 436541001(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 Summary; All sample data provided in this report met the acceptance criteria specified in the analyticaJ 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 Pa~ l.Mlffl:Orles u.c P0Bac30712 a.r.ion.SC:29417 2040Savlgellcld Chlrleston,SC:29407 Pl43.55U171 Fl43.7111,.1178 www.1191.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 SumpArea#l 1203918726 Method Blank (MB) 1203918727 436541001(L1-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. 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: Alpbaspec Pu238, 239/240, Solid Analytical Method: DOE EML HASL-300, Pu- 11-RC Modified Analytical Procedure: GL-RAD-A-011 REV# 26 Analytical Batch; 1118470 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-0 12-SB 436541005 LI-SUB-CDR-FSGS-01 4-SB 436541006 NRC#4 436541007 SumpArea # l 1203918729 Method Blank (MB) 12039)8730 43654100l(LI-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203918731 Laboratory Control Sample (LCS)

PO l!Ol aon2 Clwlemn, SC 29417 2040 SMgt Read Chat.aston, SC 29407 P843.55U171 F143.711.1178 www.ge1.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-01 I-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 l-SB 436541004 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 SumpArc:a#I 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, Cs137, Co60, Nb94, Eu 152, Eu154, Eul55 Analytical Method; DOE HASL 300, 4.5.2.3/Ga-Ol-R Analytical Procedure; GL-RAD-A-013 REV# 27 Analytical Batch: 1714268 Preparation Method; Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1714238 P0lbt30n2 Clwl8Mon,SC29417 2040SavaQtRoaO Chaa1el1Dn,SC29407 P8435561171 FB43-781.1178 www.ae1.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 436541004 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 SumpArea#l 1203908225 Method Blank (MB) 1203908226 43654l00I(LI-SUB-CDR-FSGS-008-$B) Sample Duplicate (DUP) 1203908227 Laboratory Control Sample (LC$)

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.

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 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 Ll-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 SumpArea#l 1203911888 Method Blank (MB)

PO Box 30712 Clwleston, SC 29417 2040 Savage Raad ChlrtlSIDn, SC 29407 P843SiU171 F843,7a1178 www.gel.com

1203911889 436541001(LI-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203911890 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: GFPC, Sr90, Solid Analytical Method: EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Analytic.al Procedure: GL-RAD-A-004 REV# 19 Analytical Batch: 1717213 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 Sump Area#]

1203915500 Method Blank (MB) 1203915501 436541005(LI-SUB-CDR-FSGS-014-SB) Sample Duplicate (DUP) 1203915502 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, 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 recounted due to results more negative than the three sigma TPU. The second count is reported. Samples 436541006 (NRC #4) and 436541007 (Sump Area # j) were verified by recounting at least five days from the separation date. The recounts are reported.

Pa~Cff10rles u.c P0Box30m! Clwleslon,SC29417 2040Sav1Qtlad Charleston,SC29407 P843.55U171 FIM3.7&1178 WWW.flll.com

Product: Liquid Scint Pu241, Solid Analytical Method; DOE EML HASL-300, Pu-11-RC Modified Analytical Procedure: GL-RAD-A-035 REV# 19 Analytical Batch: 1718471 Preparation Method; Dry Soil Prep Preparation Procedure; GL-RAD-A-021 REV# 22 Pre11aration 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 Sump Area#l 1203918732 Method Blank (MB) 1203918733 436541001(LI-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203918734 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

Data Summaa:

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 15 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-STJB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 SumpArea#l Pa~\fffDrtes u.c P0Bax30712 CMrlmJn,SC29417 2040Sl',IQ9Roed C1w1es1Dn,SC29407 PM.15511171 Fl43.7118.1178 www.gt1.com

1203911441 Method Blank (MB) 1203911442 436541001(LI-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203911443 436541 OOI(LI-SUB-CDR-FSGS-008-SB) Matrix Spike (MS) 1203911444 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, wHh 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 LJ-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 Sump Area#l 1203911461 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 analyt icaJ methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.

Miscelhmeous Information Additional Comments The matrix spike, 1203911463 (LI-SUB-CDR-FSGS-008-SBMS), aliquot was reduced to conserve sample POb30n2 ci.rie.n,SC29417 2040SMgelad Charlest0n.SC29407 P843fi511171 F843.718.1178 www.1191.com

volume.

Product: Liquid Scint FeS5, Solid Analytical Method: DOE RESL Fe-1, Modified Analytical Procedure; GL-RAD-A-040 REV# 13 Analytical Batch: 1715698 PreJ>aration 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 436541007 Sump Area#l 1203911706 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 Preparation Method; Dry Soil Prep PreJ>aration Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1714238 Pa~~rfes u.c POBaK30712 °*111lon,SC29417 2040SIYIQ&Aoad Chnston,SC29407 Pl43.55U171 F843.7'1.1178 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 LI-SUB-CDR-FSGS-011-SB 436541004 LI-SUB-CDR-FSGS-012-SB 436541005 LI-SUB-CDR-FSGS-014-SB 436541006 NRC#4 436541007 SumpArea#l 1203911728 Method Blank (MB) 1203911729 436541001(1,1-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203911730 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, continuing 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), 436541006 (NRC #4) and 436541007 (Sump Area# 1) 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 anaJyzed using the above methods and analyticaJ 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#!

1203911765 Method Blank (MB) 1203911766 436541001(Ll-SUB-CDR-FSGS-008-SB) Sample Duplicate (DUP) 1203911767 Laboratory Control Sample (LCS)

The samples in this SDG wer.: analyzed on an "as received" basis.

Pa~rlesLLC P0Bax30n2 Qwleslon,SC2!M17 2040Slvagtfflm Clalestlln,SC29407 PM3.55H171 FM3.781.1171 WIIIW.Qll.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.

Pa~CfftOrles u.c PO Bor 30712 a.wi.ton, SC 29417 2040 SMat Rold Char1811Dn, SC 29407 P 843.551.8171 F IIQ.711.1118 www.aa1.com

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Comments (U,e Contlnumtlon PonD tr 11£Cdcd):

Gl-cHL-SR-001 Rev 5 Page 44 of 45

List of current GEL Certifications as of 27 November 2017 State Certification Alaska UST-0110 Arkansas 88-0651 CLIA 42D0904046 California 2940 Colorado SC00012 Connecticut PH-0169 Delaware SC00012 DoD ELAP/ IS017025 A2LA 2567.01 Florida NELAP E87156 Foreign Soils Permit P330-15-00283,P330-15--00253 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 SDWA 90129 Kentucky Wastewater 90129 Louisiana NELAP 03046 (AI33904)

Louisiana SDWA LA170010 Maryland 270 Massachusetts M-SC012 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 SOWA 45709 North Dakota R-158 Oklahoma 9904 Pennsylvania NELAP 68-00485 Puerto Rico SC00012 S.Carolina Radchem 10120002 South Carolina Chemistry 10120001 Tennessee TN02934 TexasNELAP T104704235-17-I2 UtahNELAP scooo 122017-24 Vermont VT87156 Virginia NELAP 460202 Washington C780 West Virginia 997404 Page 45 of 45

@@ Line 2: / Line 2: @@
 | number = ML20031C853
 | issue date = 01/28/2020
-| title = Boiling Water Reactor Final Status Survey Final Report - Phase 3, Survey Unit L1-SUB-CDR Stack, Pipe Tunnel, Rpgpa Excavation (Release Record)
+| title = Boiling Water Reactor Final Status Survey Final Report - Phase 3, Survey Unit L1-SUB-CDR Stack, Pipe Tunnel, RPGPA Excavation (Release Record)
 | author name = Yetter R
 | author affiliation = LaCrosseSolutions, LLC

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Latest revision as of 09:03, 20 February 2020

Text

SUMMARY

SUMMARY

Dear Mr. Spaide:

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Dear Mr. Spaide:

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