ML19261A334

Boiling Water Reactor Final Status Survey Release Record L1-010-104 West Excavation Survey Unit 1 L1-SUB-DRS

ML19261A334
Person / Time
Site:	La Crosse  File:Dairyland Power Cooperative icon.png
Issue date:	08/28/2019
From:	Yetter R LaCrosseSolutions
To:	Office of Nuclear Material Safety and Safeguards
References
LC-2019-0040
Download: ML19261A334 (223)

Text

LA CROSSE BOILING WATER REACTOR FINAL STATUS SURVEY RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS PREPARED BY / DATE: 8/28/19 R. F. Yetter III, Survey Design Specialist REVIEWED BY / DATE: 8/28/19 R. Yetter, Director, Radiol Radiological Site Closure 8/28/19 REVIEWED BY / DATE:

P. Hollenbeck,, Radiologica Radiological g Engineer APPROVED BY / DATE: 8/28/19 S.

S Zoller, Zoller FSS SS Manager FS 1

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

................................................................................................................................. 6

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

3. CLASSIFICATION BASIS................................................................................................................................. 7

4. DATA QUALITY OBJECTIVES .................................................................................................................... 10

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

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

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

8. QUALITY CONTROL...................................................................................................................................... 27

9. INVESTIGATIONS AND RESULTS .............................................................................................................. 27

10. REMEDIATION AND RESULTS ................................................................................................................... 27

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN ........................................................................ 28

12. DATA QUALITY ASSESSMENT (DQA)....................................................................................................... 28

13. ANOMALIES..................................................................................................................................................... 28

14. CONCLUSION .................................................................................................................................................. 29

15. REFERENCES................................................................................................................................................... 29

16. ATTACHMENTS .............................................................................................................................................. 30 ATTACHMENT 1 - FIGURES AND MAPS ............................................................................................................. 31 ATTACHMENT 2 - SCAN DATA............................................................................................................................. 34 ATTACHMENT 3 - SIGN TEST............................................................................................................................... 38 ATTACHMENT 4 - QUALITY CONTROL ASSESSMENT ...................................................................................... 40 ATTACHMENT 5 - CONSULTATION TRIGGERS FOR RESIDENTIAL SOIL CONCENTRATIONS................... 42 ATTACHMENT 6 - GRAPHICAL PRESENTATIONS............................................................................................. 44 ATTACHMENT 7 - SAMPLE ANALYTICAL REPORTS ......................................................................................... 48 ATTACHMENT 8 - GEL LABORATORIES ANALYTICAL REPORTS ................................................................... 49 2

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS LIST OF TABLES Table 3 Statistical Quantities for Cs-137 and Co-60 from the Characterization Survey.................................. 8 Table 4 Dose Significant Radionuclides and Mixture for Soil .......................................................................... 11 Table 4 Base Case DCGLs for Soil (DCGLS)...................................................................................................... 12 Table 4 Operational DCGLs for Soil (OpDCGLS)............................................................................................. 12 Table 5 Soil Surrogate Ratio ............................................................................................................................... 13 Table 5 Action Levels for Survey Unit L1-SUB-DRS........................................................................................ 14 Table 5 Systematic Sample Locations................................................................................................................. 16 Table 5 Judgmental 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 Soil Samples Comprising the Statistical Sample Population........................................................................................................................................................... 23 Table 7 Basic Statistical Properties of Systematic Sample Population............................................................. 23 Table 7 Off-Site Analysis Results for Sr-90 ........................................................................................................ 24 Table 7 Summary of Gamma Spectroscopy Results for Judgmental Soil Samples ........................................ 24 Table 7 Summary of Gamma Spectroscopy Results for QC Soil Samples....................................................... 25 Table 7 Sum-of-Fractions for Individual Soil Samples (Systematic and QC) ................................................. 25 Table 7 Sum-of-Fractions for Individual Soil Samples (Judgmental) .............................................................. 27 Table 16 L1-SUB-DRS Complete Scan Data ..................................................................................................... 35 Table 16 L1-SUB-DRS Sign Test ........................................................................................................................ 39 Table 16 L1-SUB-DRS QC Assessment.............................................................................................................. 41 LIST OF FIGURES Figure 16 L1-SUB-DRS Scan and Systematic Sample Locations Map............................................................ 32 Figure 16 L1-SUB-DRS Judgmental Sample Locations ................................................................................... 33 Figure 16 Quantile Plot for Cs-137 Concentration............................................................................................ 45 Figure 16 Histogram for Cs-137 Concentration................................................................................................. 46 Figure 16 Retrospective Power Curve for L1-SUB-DRS................................................................................... 47 3

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable ASP Alarm Set Point 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 HPSW High Pressure Service Water HSA Historical Site Assessment IC Insignificant Contributors LACBWR La Crosse Boiling Water Reactor LBGR Lower Bound of the Gray Region LPSW Low Pressure Service Water 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 RASS Remedial Action Support Survey RCA Radiologically Controlled Area ROC Radionuclides of Concern SOF Sum-of-Fraction TEDE Total Effective Dose Equivalent UBGR Upper Bound of the Gray Region 4

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS UCL Upper Confidence Limit 5

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS

1. EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey unit L1-SUB-DRS, L1-010-104 West Excavation (within the west portion of open land survey unit L1-010-104), 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 (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).

This survey unit 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-DRS indicate that the maximum Sum-of-Fraction (SOF), considering the concentration of all applicable Radionuclides of Concern (ROC) either by direct measurement or by inference, is equal to 0.0587 when applying the respective Operational Derived Concentration Guideline Levels (OpDCGLS) for soil.

Therefore, the null hypothesis is rejected and survey unit L1-SUB-DRS is acceptable for unrestricted release. The mean SOF when applying the respective Base Case DCGLs (DCGLS) is 0.0105. This SOF equates to a dose for the survey unit of 0.2620 mrem/yr.

2. SURVEY UNIT DESCRIPTION L1-SUB-DRS is an impacted Class 1 excavation survey unit. The survey unit consists of the underlying soil post-removal of the Radiologically Controlled Area (RCA) roadway, rail lines, storm drains, High Pressure Service Water (HPSW) lines, Low Pressure Service Water (LPSW) lines, and well water lines located in open land survey unit L1-010-104 West. The surface area of the survey unit is 1,125 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-DRS.

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FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS

3. CLASSIFICATION BASIS Based on the Historical Site Assessment (HSA) (Reference 5), survey unit L1-010-104 was identified as a Class 1 area. As survey unit L1-SUB-DRS consists of the underlying soils from the west portion of L1-010-104, it is also deemed Class 1. The following summarizes the results of the characterization surveys for survey unit L1-010-104.

The initial site characterization surveys performed by EnergySolutions were conducted between October 9, 2014, and August 6, 2015. In total, one (1) surface soil sample, fourteen (14) subsurface soil samples, and ten (10) asphalt samples were collected in the survey unit.

All samples were analyzed by the on-site gamma spectroscopy system. No ROC were detected at concentrations above Minimum Detectable Concentration (MDC) for the surface soil samples. For subsurface soil samples, Cs-137 was detected at concentrations above MDC in three (3) of the samples, at a maximum concentration of 0.051 pCi/g. Co-60 was not detected at concentrations above MDC for subsurface soil samples. Cs-137 was detected at a concentration above MDC in one (1) asphalt sample, at a maximum concentration of 0.057 pCi/g. No other ROC were identified in the asphalt samples for the characterization of this survey unit. A summary of the analyses for the surface soil, subsurface soil, and asphalt samples taken during site characterization are presented in Table 3-1.

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FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Table 3 Statistical Quantities for Cs-137 and Co-60 from the Characterization Survey Surface Soil Co-60 Cs-137

1. of Samples 1

1. >MDC 0 0 Mean (pCi/g) 0.045 0.049 Median (pCi/g) 0.045 0.049 Max (pCi/g) 0.045 0.049 Min (pCi/g) 0.045 0.049 Standard Deviation (pCi/g) N/A N/A Subsurface Soil Co-60 Cs-137

1. of Samples 14

1. >MDC 0 3 Mean (pCi/g) 0.048 0.041 Median (pCi/g) 0.048 0.042 Max (pCi/g) 0.050 0.051 Min (pCi/g) 0.043 0.027 Standard Deviation (pCi/g) 0.002 0.009 Asphalt Co-60 Cs-137

1. of Samples 10

1. >MDC 0 1 Mean (pCi/g) 0.053 0.051 Median (pCi/g) 0.054 0.053 Max (pCi/g) 0.062 0.057 Min (pCi/g) 0.042 0.037 Standard Deviation (pCi/g) 0.006 0.006 Two (2) subsurface soil samples and two (2) asphalt samples from characterization were sent to Test America Laboratories for off-site analysis. Each sample was analyzed for the full suite of initial ROC. No ROC were identified at concentrations greater than their respective MDCs.

8

Section 5.1 of the LTP states that the actual IC dose will be calculated for each individual sample result using the DCGLs from TSD RS-TD-313196-004, LACBWR Soil DCGL, Basement Concrete DCGL, and Buried Pipe DCGL, Table 4 (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 hard-to-detect (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 sur/vey 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-DRS was determined to be Class 1.

Between February 15, 2018, and February 23, 2018, a Remedial Action Support Survey (RASS) was performed in the survey unit after the excavation was complete and before FSS was performed. The purpose of the RASS was to ensure that residual radionuclide concentrations in the excavation were below the Operational DCGL for soil. 100% of the surface area of soil in the excavation was scanned using a Ludlum Model 2350-1 data logger paired with a Ludlum Model 44-10 detector. The alarm set point (ASP) was set at average background plus 3,525 cpm, which is equivalent to the Operational DCGL. Five (5) alarms were produced and verified during the RASS scan survey. Seven (7) judgmental soil samples were collected in the excavation at areas where scan alarms occurred. The seven (7) samples were analyzed using the on-site gamma spectroscopy system. Gamma spectroscopy revealed Cs-137 concentrations ranging between 5.30E-02 pCi/g and 8.13E+00 pCi/g. Co-60 concentrations ranged between 5.60E-02 pCi/g and 2.90E-01 pCi/g.

Areas that alarmed and where judgmental samples were collected were bounded and remediated to levels below the Operational DCGL. Remediation was deemed sufficient as no further alarms were produced upon rescan of the elevated areas.

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS

4. DATA QUALITY OBJECTIVES (DQO)

Final Status Survey planning and design hinges on coherence with the Data Quality Objective (DQO) process to ensure, through compliance with explicitly defined inputs and boundaries, that the primary objective of the survey is satisfied. The DQO process is described in the LACBWR LTP in accordance with MARSSIM. 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 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-DRS 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).

LaCrosseSolutions 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.

Insignificant dose contributors 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 insignificant dose contributors 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.

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FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS LTP Chapter 6, Section 6.14.1 discusses the process used to derive the ROC for the decommissioning of LACBWR, including the elimination of insignificant dose contributors (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.

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.

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, or 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 (calculation of surrogate DCGLs, investigations levels, etc.).

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. The DCGLW can be multiplied by Area Factors (AF) 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 for the end-state (basements, soils, buried pipe, above-ground 11

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS structures, and groundwater). When applied to soil, the DCGLs are expressed in units of activity per unit of mass (pCi/g).

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 Chapter 6, 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 insignificant dose contributor percentages for the most limiting basement scenario was used to adjust the DCGLs for soil to account for the dose from the eliminated insignificant contributor radionuclides.

Table 4 Base Case DCGLs for Soil (DCGLS)

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 (calculation of surrogate DCGLs, investigation levels, etc.). The Operational DCGLs (OpDCGLS) for the unrestricted release of soil are provided in Table 4-3.

Table 4 Operational DCGLs for Soil (OpDCGLS)

OpDCGLS Radionuclide (pCi/g)

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

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS 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 recorded value was used as the recorded FSS result for measurement and/or sample values that are less than MDC. Negative values were recorded as zero. 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-DRS 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 13

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS The equation for calculating a surrogate DCGL is as follows:

Equation 1 1

=

1

+ + +

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

Equation 2 1

() = = 17.31 /

1 0.502 17.39 +

() 1970.45()

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-DRS are based on the Operational DCGL and are presented in Table 5-2.

Table 5 Action Levels for Survey Unit L1-SUB-DRS 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 L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS 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. 7KHUHODWLYHVKLIW  IRUWKHVXUYH\XQLWGDWDVHWLVGHILQHGDVVKLIW ZKLFKLV

the Upper Boundary of the Gray Region (UBGR), or the DCGL (SOF of 1), minus the

/RZHU%RXQGRIWKH*UD\5HJLRQ /%*5  62)RI GLYLGHGE\VLJPD ZKLFKLVWKH

standard deviation of the data set used for survey desigQ7KHRSWLPDOYDOXHIRUVKRXOG

range between one (1) and three (3)7KHODUJHVWYDOXHWKHFDQKDYHLVthree (3). If the

H[FHHGVthree (3), then the value of three (3) ZLOOEHXVHGIRU 7KHIRUVXUYH\

unit L1-SUB-DRS, based on Cs-137 and Co-60 data for subsurface soil samples collected during characterization of L1-010-104, was calculated as follows:

Equation 3

 = 0.5/0.001 = 500 As the calculated relative shift (500) was greater than three (3), then a value of three (3) was XVHGDVWKHDGMXVWHG%RWKWKH7\SH ,HUURURU value, and the Type ,,HUURURU 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. The survey design specified fourteen (14) soil samples for non-parametric statistical testing.

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, the GPS route of the boundary of the excavation, and sixty (60) 20 by 20 grids. The systematic coordinates generated with VSP were integrated with a GPS to identify sample locations in the field. Table 5-3 lists the systematic samples collected for FSS and the corresponding GPS coordinates, based on the Wisconsin State Plane North American Datum 1983 coordinate system.

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FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Table 5 Systematic Sample Locations Sample ID Northing Easting L1-SUB-DRS-FSGS-W01-SB 571114.6130 1642058.2443 L1-SUB-DRS-FSGS-W02-SB 571114.6130 1642089.8429 L1-SUB-DRS-FSGS-W03-SB 571141.9782 1642010.8464 L1-SUB-DRS-FSGS-W04-SB 571141.9782 1642042.4450 L1-SUB-DRS-FSGS-W05-SB 571169.3434 1641963.4485 L1-SUB-DRS-FSGS-W06-SB 571169.3434 1641995.0471 L1-SUB-DRS-FSGS-W07-SB 571169.3434 1642026.6457 L1-SUB-DRS-FSGS-W08-SB 571169.3434 1642058.2443 L1-SUB-DRS-FSGS-W09-SB 571196.7086 1641979.2478 L1-SUB-DRS-FSGS-W10-SB 571196.7086 1642010.8464 L1-SUB-DRS-FSGS-W11-SB 571196.7086 1642042.4450 L1-SUB-DRS-FSGS-W12-SB 571196.7086 1642074.0436 L1-SUB-DRS-FSGS-W13-SB 571224.0737 1641995.0471 L1-SUB-DRS-FSGS-W14-SB 571224.0737 1642026.6457 Although one (1) judgmental sample was required for survey design, six (6) judgmental soil samples were collected at locations of higher scan readings. This is described in detail in Section 6 of this release record. In total, twenty (20) soil samples were collected for the FSS of survey unit L1-SUB-DRS. The coordinates for the judgmental samples are provided in Table 5-4.

Table 5 Judgmental Sample Locations Sample ID Northing Easting L1-SUB-DRS-FJGS-W01-SB 571110.341 1642056.525 L1-SUB-DRS-FJGS-W02-SB 571125.633 1642062.774 L1-SUB-DRS-FJGS-W03-SB 571132.815 1642053.991 L1-SUB-DRS-FJGS-W04-SB 571135.415 1642077.386 L1-SUB-DRS-FJGS-W05-SB 571157.199 1642045.527 L1-SUB-DRS-FJGS-W06-SB 571135.462 1642040.286 The LACBWR LTP Chapter 5, 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 (including excavations where major sub-grade structures previously resided) will be analyzed for HTD ROC. In addition, if any 16

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS sample has a SOF of 10% of the Operational DCGL or more, it must be sent for HTD ROC analysis. Only the HTD radionuclide included as ROC (Sr-90) will be analyzed in the FSS confirmatory samples. 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.

The selection of two (2) soil sample met the requirement that a minimum of 10% of the samples collected for the FSS of survey unit L1-SUB-DRS be analyzed for HTD ROC.

Sample L1-SUB-DRS-FSGS-W12-SB and L1-SUB-DRS-FSGS-W14-SB were selected.

The selected samples were sent off-site (GEL Laboratories) for analysis of the HTD ROC as specified in LTP Chapter 5, Section 5.1.

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-DRS-QSGS-W14-SB, was designated for split sample QC analysis for the FSS of this survey unit.

LTP Chapter 5, Section 5.6.4.4 and Table 5-15 specifies that for Class 1 survey units, surface scans will be performed on 100% of the surface area in the survey unit. For survey unit L1-SUB-DRS, 100% scan coverage equates to 1,125 m2. To encapsulate the entire area of the survey unit, a 20 by 20 grid pattern was overlaid on a map of the survey unit. The survey unit spanned through portions of forty-five (45) of the sixty (60) total grids. A map of the scan grid locations 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-DRS.

17

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Table 5 Synopsis of Survey Design Feature Design Criteria Basis Survey Unit Surface 1,125 m2 GPS Area x  0.001 x UBGR = SOF of 1 Number of x LBGR = SOF of 0.5 14 Systematic Samples x Type I error = 0.05 (N) x Type II error = 0.05 x   DGMXVWHG x MARSSIM Table 5.5 x Co-60: 3.83 pCi/g x Sr-90: 1970.45 pCi/g x Cs-137: 17.39 pCi/g Operational DCGLs for DCGLS and Action soil, (Surrogate Cs-137 Levels LTP Chapter 5, Table 5-6, DCGL: 17.31 pCi/g) Release Record Table 5-2 x Eu-152: 8.51 pCi/g x Eu-154: 7.89 pCi/g Scan and Direct

>Operational DCGL LTP Chapter 5, Table 5-16 Investigation Levels Scan Areal Coverage 1,125 m2 or 100% areal coverage LTP Chapter 5, Table 5-15 Number of 1 Per Sample Plan Judgmental Samples 6 Actual Number Obtained HTD ROC Analysis 2 samples LTP Chapter 5, Section 5.1 1 split sample selected at random LTP Chapter 5, Section 5.9 QC 4 Actual Number Obtained

6. SURVEY IMPLEMENTATION For survey unit L1-SUB-DRS, 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.

18

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS An FSS Supervisor performed a visual inspection and walk-down of the survey unit on February 22, 2018, prior to performing FSS. The purpose of the walk-down was to assess the physical condition of the survey unit, evaluate access points and travel paths, and identify potentially hazardous conditions.

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. A Field Log was used to document field activities and other information pertaining to the performance of the FSS. FSS field activities commenced on February 27, 2018.

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. The survey-required field activities were performed during normal working hours and concluded on March 2, 2018.

The fourteen (14) systematic soil sample locations were marked with flags based on GPS coordinates provided. Each soil sample consisted of approximately one (1) liter of soil. The 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 (CoC) process from LC-FS-PR-012, Chain of Custody Protocol (Reference 11), and in accordance with LC-FS-PR-004, Sample Media Collection for Site Characterization and Final Status Survey (Reference 12), LC-FS-PR-005, Sample Media Preparation for Site Characterization and Final Status Survey (Reference 13), and LC-FS-PR-001, Sample Storage (Reference 14).

A total of forty-five (45) scan grids, constituting a total scan coverage of 1,125 m2, or approximately 100% of the surface area in the survey unit, were established. Background was assessed in the survey unit 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-DRS, background ranged from 7,357 counts per minute (cpm) up to 11,975 cpm.

All designated scan areas as denoted on Figure 16-1 in Attachment 1 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 15), scan MDC was sufficient to detect residual radioactivity at the action level (adjusted surrogate DCGL 19

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS 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) judgmental soil samples were collected during implementation of FSS. Although no ASPs were exceeded, these judgmental samples were collected to investigate locations where scanning revealed higher readings than readings that had been observed in other scan grids (see Table 7-1). The higher readings were determined to be due to a gap in the shielding that was placed at the outside edge of the survey unit, the side closest to the Reactor Building.

The survey design specified that a minimum of one (1) sample was required for HTD ROC analysis. In total, two (2) samples (L1-SUB-DRS-FSGS-W12-SB and L1-SUB-DRS-FSGS-W14-SB) were selected for HTD radionuclide analysis.

The survey design specified one (1) sample to be collected for QC split analysis. The implementation of survey specific QC measures included the collection of four (4) samples (L1-SUB-DRS-QJGS-W06-SB, L1-SUB-DRS-QSGS-W14-SB, L1-SUB-DRS-FJGS-W03-SB SPLIT, and L1-SUB-DRS-FSGS-W05-SB SPLIT) for split sample analysis.

7. SURVEY RESULTS All areas identified in the FSS plan were scanned for elevated radiation levels. No elevated measurement locations were identified by surface scan. Table 7-1 provides an overview of the scan results for all scan grids (identified as A01 through H06), the 1 m2 scan areas around each sample location (identified as J SP01 through SP14), and QC locations (identified with a Q). Complete scan results are provided in Attachment 2.

Table 7 Synopsis of Scan Results Highest Action Logged # of Scan Judgmental Investigation Scan Area Level(1)

Reading Alarms Samples Samples (cpm) (cpm)

A01 9031 11823 0 0 0 A02 9832 11823 0 0 0 A03 8591 11823 0 0 0 A04 8781 11823 0 0 0 A05 8266 11333 0 0 0 A06 9868 11823 0 0 0 B01 9123 11823 0 0 0 B02 8992 11333 0 0 0 B03 9417 11823 0 0 0 20

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Highest Action Logged # of Scan Judgmental Investigation Scan Area Level(1)

Reading Alarms Samples Samples (cpm) (cpm)

B04 8337 14792 0 0 0 B05 8696 11333 0 0 0 B06 8436 11333 0 0 0 C01 9440 11823 0 0 0 C02 9220 11333 0 0 0 C03 10016 14792 0 0 0 C03 Q 8780 10995 0 0 0 C04 9993 14792 0 0 0 C04 Q 9109 10995 0 0 0 C05 9763 11581 0 0 0 C06 8754 11581 0 0 0 D01 10135 11823 0 0 0 D02 9636 11333 0 0 0 D03 10615 11333 0 0 0 D04 11111 11333 0 0 0 D05 9945 11581 0 0 0 D06 9501 11333 0 0 0 E01 9760 11823 0 0 0 E02 10379 11823 0 0 0 E03 12408 14792 0 0 0 E04 12785 14792 0 1 0 E05 12285 14792 0 0 0 E06 10463 15672 0 0 0 F01 10411 11823 0 0 0 F02 11591 11823 0 0 0 F03 11151 14792 0 0 0 F04 11554 15672 0 0 0 F05 12974 15672 0 2 0 F06 11224 15672 0 0 0 G01 9366 11823 0 0 0 G02 9295 11823 0 0 0 G03 11354 14792 0 0 0 G04 12805 13750 0 1 0 21

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Highest Action Logged # of Scan Judgmental Investigation Scan Area Level(1)

Reading Alarms Samples Samples (cpm) (cpm)

G05 13752 15672 0 1 0 G06 13422 15672 0 1 0 H04 10908 13750 0 0 0 H05 11219 13750 0 0 0 H06 11781 15672 0 0 0 J SP01 10414 12360 0 0 0 J SP02 10546 12360 0 0 0 J SP03 10684 12360 0 0 0 J SP04 10152 12360 0 0 0 J SP05 8703 12360 0 0 0 J SP06 9017 12360 0 0 0 J SP06 Q 9256 11581 0 0 0 SP01 11044 13698 0 0 0 SP02 9042 13698 0 0 0 SP03 9031 10882 0 0 0 SP04 9526 10882 0 0 0 SP05 7256 10882 0 0 0 SP06 8805 10882 0 0 0 SP07 8883 10882 0 0 0 SP08 10058 10882 0 0 0 SP09 7138 10882 0 0 0 SP10 8257 10882 0 0 0 SP11 8869 10882 0 0 0 SP12 8903 10882 0 0 0 SP13 8128 10882 0 0 0 SP14 7535 10882 0 0 0 SP14 Q 7972 10992 0 0 0 (1) Action Level based on the average background plus 3,525 cpm (OpDCGL equivalent).

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 fourteen (14) samples collected for non-parametric statistical testing results is provided in Table 7-

2. Gamma spectroscopy results revealed four (4) samples above MDC for Cs-137 and no samples above MDC for any other ROC. The concentration for Sr-90 was inferred based on 22

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS 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 is summarized in Table 7-3.

Table 7 Summary of Gamma Spectroscopy Results for Soil 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-DRS-FSGS-W01-SB 6.18E-02 6.27E-02 1.15E-01 2.01E-01 3.15E-02 L1-SUB-DRS-FSGS-W02-SB 7.15E-02 3.31E-02 7.01E-02 4.42E-06 1.66E-02 L1-SUB-DRS-FSGS-W03-SB 2.12E-02 6.37E-02 8.16E-02 2.77E-02 3.20E-02 L1-SUB-DRS-FSGS-W04-SB 4.28E-02 6.32E-02 0.00E+00 1.45E-02 3.17E-02 L1-SUB-DRS-FSGS-W05-SB 2.14E-02 4.23E-02 0.00E+00 4.18E-02 2.12E-02 L1-SUB-DRS-FSGS-W06-SB 4.67E-02 4.88E-02 1.72E-01 6.80E-02 2.45E-02 L1-SUB-DRS-FSGS-W07-SB 2.18E-02 9.49E-02 9.35E-03 1.91E-02 4.76E-02 L1-SUB-DRS-FSGS-W08-SB 3.67E-02 5.80E-02 1.08E-01 1.22E-01 2.91E-02 L1-SUB-DRS-FSGS-W09-SB 6.65E-02 6.83E-02 7.68E-02 0.00E+00 3.43E-02 L1-SUB-DRS-FSGS-W10-SB 5.79E-02 5.41E-02 8.93E-02 3.78E-02 2.72E-02 L1-SUB-DRS-FSGS-W11-SB 4.64E-02 3.20E-02 7.54E-02 7.91E-02 1.61E-02 L1-SUB-DRS-FSGS-W12-SB 4.51E-02 5.27E-02 4.38E-02 4.71E-02 2.65E-02 L1-SUB-DRS-FSGS-W13-SB 3.44E-02 4.70E-02 2.33E-02 5.95E-02 2.36E-02 L1-SUB-DRS-FSGS-W14-SB 6.45E-02 6.83E-02 5.72E-03 8.49E-03 3.43E-02 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 4.56E-02 4.58E-02 7.15E-02 2.12E-02 0.0172 1.06E+01 0.0043 0.1076 Cs-137 5.64E-02 5.61E-02 9.49E-02 3.20E-02 0.0162 4.83E+01 0.0012 0.0292 Eu-152 6.22E-02 7.28E-02 1.72E-01 0.00E+00 0.0512 2.36E+01 0.0026 0.0659 Eu-154 5.19E-02 3.98E-02 2.01E-01 0.00E+00 0.0547 2.19E+01 0.0024 0.0592 Sr-90 2.83E-02 2.81E-02 4.76E-02 1.61E-02 0.0081 5.47E+03 0.0000 0.0001 The off-site laboratory, GEL Laboratories, processed the two (2) samples selected for HTD ROC analysis as specified in the survey design. Samples L1-SUB-DRS-FSGS-W12-SB and 23

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS L1-SUB-DRS-FSGS-W14-SB were selected. Only the HTD ROC Sr-90 was included in the analysis. All analyses met the required MDC.

Sr-90 was not detected in the off-site analysis of samples L1-SUB-DRS-FSGS-W12-SB and L1-SUB-DRS-FSGS-W14-SB. The results are provided in Table 7-4.

Table 7 Off-Site Analysis Results for Sr-90 Result Uncertainty MDC Sample ID >MDC (pCi/g) (pCi/g) (pCi/g)

L1-SUB-DRS-FSGS-W12-SB -0.022 0.076 0.134 No L1-SUB-DRS-FSGS-W14-SB 0.103 0.092 0.153 No The on-site laboratory analyzed the six (6) judgmental soil using the on-site gamma spectroscopy system. A summary of the analytical results for the judgmental soil samples is provided in Table 7-5. Gamma spectroscopy results revealed four (4) samples above MDC for Cs-137 and no samples above MDC for any other ROC. 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.

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

L1-SUB-DRS-FJGS-W01-SB 4.07E-02 2.91E-02 1.44E-01 2.07E-01 1.46E-02 L1-SUB-DRS-FJGS-W02-SB 4.53E-02 8.40E-02 0.00E+00 1.36E-01 4.22E-02 L1-SUB-DRS-FJGS-W03-SB 4.95E-02 2.87E-02 1.63E-02 1.98E-02 1.44E-02 L1-SUB-DRS-FJGS-W04-SB 6.23E-02 5.78E-02 8.80E-02 1.22E-01 2.90E-02 L1-SUB-DRS-FJGS-W05-SB 3.02E-02 2.99E-02 8.34E-02 2.67E-02 1.50E-02 L1-SUB-DRS-FJGS-W06-SB 6.05E-02 5.28E-02 0.00E+00 0.00E+00 2.65E-02 Note: Bold values indicate concentrations greater than MDC.

The implementation of survey specific QC measures included the collection of four (4) samples (L1-SUB-DRS-QJGS-W06-SB, L1-SUB-DRS-QSGS-W14-SB, L1-SUB-DRS-FJGS-W03-SB SPLIT, and L1-SUB-DRS-FSGS-W05-SB SPLIT) for split and duplicate sample analysis. The on-site laboratory analyzed the designated QC samples using the on-site gamma spectroscopy system. A summary of the analytical results for the QC samples is provided in Table 7-6. Gamma spectroscopy results revealed three (3) samples above MDC for Cs-137 and no samples above MDC for any other ROC. The concentration for Sr-90 was inferred based on the ratio specified in Table 5-1.

24

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Table 7 Summary of Gamma Spectroscopy Results for QC Soil Samples Co-60 Cs-137 Eu-152 Eu-154 Sr-90 Sample ID (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

L1-SUB-DRS-QJGS-W06-4.24E-02 5.14E-02 2.46E-01 0.00E+00 2.58E-02 SB L1-SUB-DRS-QSGS-W14-3.05E-02 4.65E-02 9.33E-02 3.32E-02 2.33E-02 SB L1-SUB-DRS-FJGS-W03-9.89E-02 3.41E-02 1.56E-02 1.10E-01 1.71E-02 SB SPLIT L1-SUB-DRS-FSGS-W05-3.07E-02 2.51E-02 1.61E-01 8.15E-02 1.26E-02 SB SPLIT Note: Bold values indicate concentrations greater than MDC.

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

Equation 4 C1 C2 Cn

 ............ d1 DCGL1 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-DRS are provided in Table 7-7.

Table 7 Sum-of-Fractions for Individual Soil Samples (Systematic and QC)

Fraction of Operational DCGL Sample ID SOF Co-60 Cs-137 Eu-152 Eu-154 Sr-90 L1-SUB-DRS-FSGS-W01-SB 0.0161 0.0036 0.0135 0.0255 0.0000 0.0587 L1-SUB-DRS-FSGS-W02-SB 0.0187 0.0019 0.0082 0.0000 0.0000 0.0288 L1-SUB-DRS-FSGS-W03-SB 0.0055 0.0037 0.0096 0.0035 0.0000 0.0223 L1-SUB-DRS-FSGS-W04-SB 0.0112 0.0036 0.0000 0.0018 0.0000 0.0167 L1-SUB-DRS-FSGS-W05-SB 0.0056 0.0024 0.0000 0.0053 0.0000 0.0133 L1-SUB-DRS-FSGS-W06-SB 0.0122 0.0028 0.0202 0.0086 0.0000 0.0438 L1-SUB-DRS-FSGS-W07-SB 0.0057 0.0055 0.0011 0.0024 0.0000 0.0147 25

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Fraction of Operational DCGL Sample ID SOF Co-60 Cs-137 Eu-152 Eu-154 Sr-90 L1-SUB-DRS-FSGS-W08-SB 0.0096 0.0033 0.0127 0.0155 0.0000 0.0411 L1-SUB-DRS-FSGS-W09-SB 0.0174 0.0039 0.0090 0.0000 0.0000 0.0303 L1-SUB-DRS-FSGS-W10-SB 0.0151 0.0031 0.0105 0.0048 0.0000 0.0335 L1-SUB-DRS-FSGS-W11-SB 0.0121 0.0018 0.0089 0.0100 0.0000 0.0328 L1-SUB-DRS-FSGS-W12-SB 0.0118 0.0030 0.0051 0.0060 0.0000 0.0259 L1-SUB-DRS-FSGS-W13-SB 0.0090 0.0027 0.0027 0.0075 0.0000 0.0220 L1-SUB-DRS-FSGS-W14-SB 0.0168 0.0039 0.0007 0.0011 0.0000 0.0225 L1-SUB-DRS-QJGS-W06-SB 0.0111 0.0030 0.0289 0.0000 0.0000 0.0429 L1-SUB-DRS-QSGS-W14-SB 0.0080 0.0027 0.0110 0.0042 0.0000 0.0258 L1-SUB-DRS-FJGS-W03-SB 0.0258 0.0020 0.0018 0.0139 0.0000 0.0436 SPLIT L1-SUB-DRS-FSGS-W05-SB 0.0080 0.0014 0.0189 0.0103 0.0000 0.0387 SPLIT Systematic Measurements Number of Systematic Measurements = 14

1. of Systematic Measurements with SOF > 1 = 0

1. of Systematic Measurements with SOF > 0.1 (HTD Assessment) = 0 Max Individual Systematic Measurement SOF = 0.0587 Mean Systematic Measurement SOF = 0.0290 The results of the unity rule calculation for the ROC in the judgmental sample population for survey unit L1-SUB-DRS are provided in Table 7-8.

26

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Table 7 Sum-of-Fractions for Individual Soil Samples (Judgmental)

Fraction of Operational DCGL Sample ID SOF Co-60 Cs-137 Eu-152 Eu-154 Sr-90 L1-SUB-DRS-FJGS-W01-SB 0.0106 0.0017 0.0169 0.0262 0.0000 0.0555 L1-SUB-DRS-FJGS-W02-SB 0.0118 0.0048 0.0000 0.0172 0.0000 0.0339 L1-SUB-DRS-FJGS-W03-SB 0.0129 0.0017 0.0019 0.0025 0.0000 0.0190 L1-SUB-DRS-FJGS-W04-SB 0.0163 0.0033 0.0103 0.0155 0.0000 0.0454 L1-SUB-DRS-FJGS-W05-SB 0.0079 0.0017 0.0098 0.0034 0.0000 0.0228 L1-SUB-DRS-FJGS-W06-SB 0.0158 0.0030 0.0000 0.0000 0.0000 0.0188 Judgmental Measurements Number of Judgmental Measurements = 6

1. of Judgmental Measurements with SOF > 1 = 0

1. of Judgmental Measurements with SOF > 0.1 (HTD Assessment) = 0 Max Individual Judgmental Measurement SOF = 0.0555

8. QUALITY CONTROL The on-site laboratory processed four (4) split and duplicate samples (L1-SUB-DRS-QJGS-W06-SB, L1-SUB-DRS-QSGS-W14-SB, L1-SUB-DRS-FJGS-W03-SB SPLIT, and L1-SUB-DRS-FSGS-W05-SB SPLIT) 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 acceptable agreement between field split and duplicate results. Refer to Attachment 4 for data and quality control analysis results.

9. INVESTIGATIONS AND RESULTS No investigations were performed during the performance or analyses of the survey.

10. REMEDIATION AND RESULTS The purpose of the excavation of the west portion of survey unit L1-010-104 was to remove the RCA roadway, rail lines, storm drains, HPSW lines, LPSW lines, and well water lines.

The purpose of the excavation was not to support removal of contaminated subsurface soil.

27

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS

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 analytical results indicated that all samples were less than a SOF of one (1) when compared to the OpDCGLS. Additionally, the maximum activity for each ROC did not exceed 10% of their respective OpDCGLS.

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

28

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS

14. CONCLUSION Survey unit L1-SUB-DRS 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 applicable 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-DRS is 0.2620 mrem/yr TEDE, based on the average concentration of the ROC in samples used for non-parametric statistical sampling.

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

15. REFERENCES

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

2. La Crosse Boiling Water Reactor License Termination Plan (LTP)

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 (HSA)

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 (QAPP)

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

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

13. LC-FS-PR-005, Sample Media Preparation for Site Characterization and Final Status Survey 29

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS

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

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

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 - Figures and Maps Attachment 2 - Scan Data Attachment 3 - Sign Test Attachment 4 - Quality Control Assessment Attachment 5 - Consultation Triggers for Residential Soil Concentrations Attachment 6 - Graphical Presentations Attachment 7 - Sample Analytical Reports Attachment 8 - GEL Laboratories Analytical Reports 30

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS ATTACHMENT 1 FIGURES AND MAPS 31

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Figure 16 L1-SUB-DRS Scan and Systematic Sample Locations Map 32

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Figure 16 L1-SUB-DRS Judgmental Sample Locations 33

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS ATTACHMENT 2 SCAN DATA 34

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Table 16 L1-SUB-DRS 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 162398 126195 A01 9031 8298 11823 No 44-10 162398 126195 A02 9832 8298 11823 No 44-10 162398 126195 A03 8591 8298 11823 No 44-10 162398 126195 A04 8781 8298 11823 No 44-10 357776 325246 A05 8266 7808 11333 No 44-10 162398 126195 A06 9868 8298 11823 No 44-10 162398 126195 B01 9123 8298 11823 No 44-10 357776 325246 B02 8992 7808 11333 No 44-10 162398 126195 B03 9417 8298 11823 No 44-10 162398 126195 B04 8337 11267 14792 No 44-10 357776 325246 B05 8696 7808 11333 No 44-10 357776 325246 B06 8436 7808 11333 No 44-10 162398 126195 C01 9440 8298 11823 No 44-10 357776 325246 C02 9220 7808 11333 No 44-10 162398 126195 C03 10016 11267 14792 No 44-10 357776 325246 C03 Q 8780 7470 10995 No 44-10 162398 126195 C04 9993 11267 14792 No 44-10 357776 325246 C04 Q 9109 7470 10995 No 44-10 162398 126195 C05 9763 8056 11581 No 44-10 162398 126195 C06 8754 8056 11581 No 44-10 162398 126195 D01 10135 8298 11823 No 44-10 357776 325246 D02 9636 7808 11333 No 44-10 357776 325246 D03 10615 7808 11333 No 44-10 357776 325246 D04 11111 7808 11333 No 44-10 162398 126195 D05 9945 8056 11581 No 44-10 357776 325246 D06 9501 7808 11333 No 44-10 162398 126195 E01 9760 8298 11823 No 44-10 162398 126195 E02 10379 8298 11823 No 44-10 162398 126195 E03 12408 11267 14792 No 44-10 162398 126195 E04 12785 11267 14792 No 44-10 162398 126195 E05 12285 11267 14792 No 44-10 357776 325246 E06 10463 11975 15672 No 35

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Scan Avg Action Detector Detector M2350-1 Logged Scan Location Background Level Type ID ID Result Alarms (cpm) (cpm) (cpm) 44-10 162398 126195 F01 10411 8298 11823 No 44-10 162398 126195 F02 11591 8298 11823 No 44-10 162398 126195 F03 11151 11267 14792 No 44-10 357776 325246 F04 11554 11975 15672 No 44-10 357776 325246 F05 12974 11975 15672 No 44-10 357776 325246 F06 11224 11975 15672 No 44-10 162398 126195 G01 9366 8298 11823 No 44-10 162398 126195 G02 9295 8298 11823 No 44-10 162398 126195 G03 11354 11267 14792 No 44-10 357776 325246 G04 12805 10225 13750 No 44-10 357776 325246 G05 13752 11975 15672 No 44-10 357776 325246 G06 13422 11975 15672 No 44-10 357776 325246 H04 10908 10225 13750 No 44-10 357776 325246 H05 11219 10225 13750 No 44-10 357776 325246 H06 11781 11975 15672 No 44-10 357776 325246 J SP01 9923 8835 12360 No 44-10 357776 325246 J SP01 10414 8835 12360 No 44-10 357776 325246 J SP02 10546 8835 12360 No 44-10 357776 325246 J SP02 10136 8835 12360 No 44-10 357776 325246 J SP03 10684 8835 12360 No 44-10 357776 325246 J SP03 9733 8835 12360 No 44-10 357776 325246 J SP04 9898 8835 12360 No 44-10 357776 325246 J SP04 10152 8835 12360 No 44-10 357776 325246 J SP05 8423 8835 12360 No 44-10 357776 325246 J SP05 8703 8835 12360 No 44-10 357776 325246 J SP06 9017 8835 12360 No 44-10 357776 325246 J SP06 8347 8835 12360 No 44-10 162398 126195 J SP06 Q 9256 8056 11581 No 44-10 162398 126195 J SP06 Q 9920 8056 11581 No 44-10 357776 325246 SP01 10357 10173 13698 No 44-10 357776 325246 SP01 11044 10173 13698 No 44-10 357776 325246 SP02 9042 10173 13698 No 44-10 357776 325246 SP02 8595 10173 13698 No 36

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Scan Avg Action Detector Detector M2350-1 Logged Scan Location Background Level Type ID ID Result Alarms (cpm) (cpm) (cpm) 44-10 357776 325246 SP03 8824 7357 10882 No 44-10 357776 325246 SP03 9031 7357 10882 No 44-10 357776 325246 SP04 9340 7357 10882 No 44-10 357776 325246 SP04 9526 7357 10882 No 44-10 357776 325246 SP05 7169 7357 10882 No 44-10 357776 325246 SP05 7256 7357 10882 No 44-10 357776 325246 SP06 8805 7357 10882 No 44-10 357776 325246 SP06 8278 7357 10882 No 44-10 357776 325246 SP07 8883 7357 10882 No 44-10 357776 325246 SP07 7804 7357 10882 No 44-10 357776 325246 SP08 10058 7357 10882 No 44-10 357776 325246 SP08 8517 7357 10882 No 44-10 357776 325246 SP09 7138 7357 10882 No 44-10 357776 325246 SP09 6920 7357 10882 No 44-10 357776 325246 SP10 8257 7357 10882 No 44-10 357776 325246 SP10 8043 7357 10882 No 44-10 357776 325246 SP11 8869 7357 10882 No 44-10 357776 325246 SP11 8078 7357 10882 No 44-10 357776 325246 SP12 8903 7357 10882 No 44-10 357776 325246 SP12 8201 7357 10882 No 44-10 357776 325246 SP13 8128 7357 10882 No 44-10 357776 325246 SP13 7706 7357 10882 No 44-10 357776 325246 SP14 7535 7357 10882 No 44-10 357776 325246 SP14 7489 7357 10882 No 44-10 3577783 325261 SP14 Q 7972 7467 10992 No 44-10 3577783 325261 SP14 Q 7739 7467 10992 No 37

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS ATTACHMENT 3 SIGN TEST 38

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Table 16 L1-SUB-DRS Sign Test SOF

1. 1-WS Sign (WS) 1 0.0587 0.94 +1 2 0.0288 0.97 +1 3 0.0223 0.98 +1 4 0.0167 0.98 +1 5 0.0133 0.99 +1 6 0.0438 0.96 +1 7 0.0147 0.99 +1 8 0.0411 0.96 +1 9 0.0303 0.97 +1 10 0.0335 0.97 +1 11 0.0328 0.97 +1 12 0.0259 0.97 +1 13 0.0220 0.98 +1 14 0.0225 0.98 +1 Number of positive differences (S+) 14 Critical Value 10 the Acceptance Meets Survey Unit Criteria 39

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS ATTACHMENT 4 QUALITY CONTROL ASSESSMENT 40

FSS RELEASE RECORD WGTV BASEMENT SURVEY UNIT L1-SUB-DRS Table 16 L1-SUB-DRS QC Assessment STANDARD COMPARISON Agreement Activity Standard Activity Standard Comparison Acceptable Sample ID Radionuclide Resolution Range (Low to Sample ID Value Error Value Error Ratio (Y/N)

High)

L1-SUB-DRS-FJGS-W06-SB K-40* 5.39E+00 6.69E-01 8.06 0.6 1.66 L1-SUB-DRS-QJGS-W06-SB 5.41E+00 6.66E-01 1.00 Y L1-SUB-DRS-FSGS-W14-SB Cs-137 6.83E-02 2.85E-02 2.40 0.4 2.5 L1-SUB-DRS-QSGS-W14-SB 4.65E-02 2.74E-02 0.68 Y L1-SUB-DRS-FJGS-W03-SB Cs-137 2.87E-02 2.72E-02 1.06 0.4 2.5 L1-SUB-DRS-FJGS-W03-SB SPLIT 3.41E-02 3.60E-02 1.19 Y L1-SUB-DRS-FJGS-W05-SB Cs-137 2.99E-02 2.85E-02 1.05 0.4 2.5 L1-SUB-DRS-FJGS-W05-SB SPLIT 2.51E-02 2.61E-02 0.84 Y Comments/Corrective Actions:

• K-40 was substituted in the comparison, because Cs-137 was Table is provided to show acceptance criteria used to assess split samples.

not identified in either sample.

41

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS ATTACHMENT 5 CONSULTATION TRIGGERS FOR RESIDENTIAL SOIL CONCENTRATION 42

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS 43

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS ATTACHMENT 6 GRAPHICAL PRESENTATIONS 44

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Figure 16 Quantile Plot for Cs-137 Concentration 45

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Figure 16 Histogram for Cs-137 Concentration 46

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS Figure 16 Retrospective Power Curve for L1-SUB-DRS 47

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS ATTACHMENT 7 SAMPLE ANALYTICAL REPORTS 48

1/15/2019 12:58:07PM Page 1 of6

...t,Apex-Gamma Analysis Report for L1-SUB-DRS-FSGS-W01-SB L1-010-104 WEST PACKAGE: L1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L1-SUB-DRS-FSGS-W01-SB Sample Description  : L1-010-104 WEST PACKAGE: L1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8.381E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 10:02:00AM Acquisition Started  : 2/28/2018 8:45:38AM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.6 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  : 5341 PEAK ANALYSIS REPORT Peak Analysis Performed on  : 1/15/2019 12:57:58PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 12:58:07PM Page 2 of6 Analysis Report for L 1-SUB-DRS-FSGS-W01 -SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.32 147 - 160 153.18 1. 96E+02 59.39 1. 32E+03 3.06 F 2 238.56 474 - 485 477.60 3 .11E+ 02 46 . 16 5.78E+02 1. 68 F 3 294 . 75 584 - 597 589.95 7.52 E+ Ol 30 . 81 4.85E+02 1. 75 F 4 351.81 698 - 712 704.04 1.86E+02 35 . 21 3 . 36E+02 1. 91 F 5 583 .13 1162 - 1173 1166 . 60 7.72E+Ol 22.67 1.19E+02 1. 84 F 6 609.09 1214 - 1225 1218.51 1.39E+ 02 28 . 09 1.31E+02 2.03 F 7 910.88 18 1 5 - 1831 1821 . 99 5.20E+ Ol 19.16 1. 05E+02 2 .3 4 F 8 1119 .9 8 2235 - 2244 2240 . 14 l .98E+Ol 11 . 64 6 . 81E+Ol 0.79 F 9 1460. 44 2912 - 2930 2921.00 4.97E+02 44.87 l.84E+Ol 2 . 70 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 12:57:58PM 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 76.32 1. 96E+02 59.39 1.96E+ 02 5.94E+01 F 2 238 . 56 3 .11E+02 46.16 3.11E+02 4.62E+Ol F 3 294.75 7.52E+Ol 30.81 7.52E+ Ol 3.08E+ Ol F 4 351.81 1.86E+02 35.21 8.36E+Ol 3 . 72E+Ol 1.03E+02 5.12E+ Ol F 5 583 . 13 7 . 72E+Ol 22.67 7.72E+O l 2 . 27E +Ol F 6 609.09 1.39E+02 28.09 4.12E+Ol 2.42E+Ol 9.79E+ Ol 3.71E +Ol F 7 910.88 5.20E+Ol 19 .16 5.20E+O l 1.92E+O l F 8 1119.98 1.98E+Ol 11 . 64 1. 98E+Ol 1.16E+Ol F 9 1460.44 4.97E+02 44.87 5.63E+Ol 1.71E+Ol 4.40E+0 2 4.80E+Ol M =First peak in a multiplet region m =Other peak in a multiplet region F =Fitted singlet Errors quoted at 2.000sigma

1/15/2019 12:58:0?PM Page 3 of6 Analysis Report for L 1-SUB-DRS-FSGS-W01-S8 L 1-010-104 WEST PACKAGE: L 1-SUB-DRS 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) (pCilgrams) Uncertainty K- 40 0 . 98 1460.75

• 10 . 67 5 . 72E+OO 7.00E- 01 PB-212 0 . 97 77 .11

• 17.50 3.34E- 01 l . 04E- 01 238.63

• 44.60 l . 91E - 01 3. OlE - 02 BI - 214 0.57 609.31

• 46.30 l. 35E- Ol 5 . 15E- 02 1120 . 29

• 15.10 1. 45E- Ol 8.51E- 02 1238 . 11 5. 94 1377.67 4.11 1407.98 2.48 1509.19 2 . 19 1764.49 15.80 PB- 214 0 . 97 77 .11

• 10.70 5.47E - 01 l.70E - Ol 295 . 21

• 19 . 20 l.28E - 01 5.29E- 02 351.92

• 37 . 20 1. 06E - 01 5.31E- 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 confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K- 40 0 . 985 5 . 72E+OO 7.00E- 01 PB- 212 0 . 972 l . 96E-Ol 2.89E - 02 BI - 214 0 . 578 l .37E- 01 4.41E - 02

1/15/2019 12:58:0?PM Page4 of6 Analysis Report for L 1-SUB-DRS-FSGS-W01-S8 L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

PB-214 0.973 l.22E-Ol 3.66E-02

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

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

1/15/2019 12:58:0?PM Page 5 of6 Analysis Report for L1-SUB-DRS-FSGS-W01-SB L 1-010-104 WEST PACKAGE: l 1-SUB-DRS UNIDENTIFIED PEAKS Peak locate Performed on  : 1/ 15/2019 12:57:58PM 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 . 13 2 . 14554£- 02 14.67 F 7 910.88 1. 44396£- 02 18.43 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 2.000sigma NUCLIDE MDA REPORT Nuclide library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NlB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCi/grams) (pCilgrams)

(keV)

+ K- 40 1460.75

• 10 . 67 5.72E+OO 5 . 76£ - 0 1 5.76E - 0 1

+ AR- 41 1293.64 99.16 - 2.35E+02 3 . 21£+02 3 . 21E+02

+ C0-60 1173 . 22 100 . 00 6.18£- 02 5.88£- 02 6 . 87E - 02 1332.49 100.00 4.78£- 02 5.88£ - 02

+ KR- 85 513 . 99 0.43 l.33E+Ol 1. 02E+Ol 1. 02E+Ol

+ Y- 88 898 . 04 93.70 1.63£- 02 3 . 42£-02 5.07£- 02 1836.06 99.20 - 7.72£ - 03 3 . 42£- 02

+ NB- 94 7 02. 63 100.00 2 . 40£ - 03 4 . 19£- 02 4 . 19£- 02 871. 1 0 100.00 - 4 . 63£- 02 4.27£ - 02

+ I - 131 284.30 6 . 06 -3 . 54£-01 4.3 4£-02 5.68£ - 01 364. 48 81. 20 1.87£- 03 4 . 34E - 02 636 . 97 7.27 - 2.12£ - 01 6 . 23E - 01

+ CS - 134 604 . 70 97.60 - 5 . 48£- 02 5.14£ - 02 5.4 1£ - 02 795.84 85.40 - 1. 03£-03 5.14£-02

1/15/2019 12:58:07PM Page 6 of6 Analysis Report for l 1-SUB-DRS-FSGS-W01-SB l 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCi/grams) (pCilgrams)

(keV)

+ CS-137 661. 65 85.12 6.27E-02 5.91E- 02 5.9 1E-02

+ CE- 1 44 80 . 12 1. 36 - l .62E+OO 2.70E-Ol 3.4 1E+OO 133.51 11. 09 -3.86E-02 2.70E-Ol

+ EU-1 52 121. 78 28.40 -2.70E- 02 1.06£-01 l.06E-01 344. 2 8 26.60 l . 15E-01 l .44E-01 1408 . 00 2 0.74 8 . 22E-02 2.22E-01

+ EU- 154 123 . 07 40.40 -l.14E-03 7.51E-02 7.51E-0 2 723.30 19.70 2.0lE- 01 2.27E-Ol 1274.51 35 . 50 - 5 . 39E-02 l . 59E-01

+ EU-155 86 . 54 32.80 -l.63E-02 l . 22E-01 l.22E-01 10 5 . 31 21. 80 -8.31E-02 1.46E- Ol

+ BI-214 609.31

• 46. 30 1. 35E-Ol 8 . 93E-02 8.93E-02 1120 . 29

• 1 5.10 1. 45E-01 2 . 31E-0 1 1238 .11 5.94 1.87E-01 l.07E+OO 1377.67 4.11 2.56E-01 l . 05E+OO 140 7.98 2.48 6 . 87E-01 l.86E+OO 1509.19 2 .19 -2 . 65E - 02 1.75E+OO 1764 .49 15.80 2.85E-Ol 3.23E-01

+ PB-214 77 .11

• 1 0.70 5.47E-01 l.05E-01 4 . 00E-01 295 . 2 1

• 1 9.20 l.28E-01 l.SOE-01 351.92

• 37.20 1. 06E-01 l.05E-01

+ PA-228 89 . 95 22 . 00 3.90E-01 2 . 17E-01 3.68E-01 93.35 35.00 l.70E-01 2.17E-01 105.00 16.30 -3.12E-01 4.03E-Ol 129.22 2.97 3.83E-01 2 . 13E+OO 338.32 5.30 6.39E-01 1. 39E+OO 463.00 13.80 4.50E-01 5.76£- 01 911. 23 16.70 6 . 62E - 0 1 6 . 83£- 01

+ AM-241 59.54 36.30 - 6 .64E- 02 2 . 20£-01 2 . 20 E- 0 1

+ CM-243 103 . 76 23.00 -l.OlE - 01 1 . 39£-01 1.39E-01 228 . 18 10.60 -2.14E-Ol 2 . 85E- Ol 277.60 14.00 -1. 82E- Ol 2.33E- 0 1

+ = 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

1/15/2019 2:21 :40PM Page I of6

~ ~ ~pex-Gamma Analysis Report for L 1-SUB-DRS-FSGS-W02-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FSGS-W02-SB Sample Description  : L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8.315E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 9:58:00AM Acquisition Started  : 2/28/2018 4 :22:12PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.7 seconds Dead Time  : 0.30 %

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100 - 4096 Peak Area Range (in channels)  : 100 - 4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5343 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/ 15/2019 2:21 :31PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:2 1:40PM Page 2 of6 Analysis Report for L 1-SUB-DRS-FSGS-W02-S8 L 1-010-104 WEST PACKAGE: L 1-SUB-ORS Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238 . 7 1 472 - 485 477 . 89 3.14 E+0 2 45.75 5. 72E+02 1. 85 F 2 295 . 27 585 - 595 59 0 .99 8 . 32E+Ol 30.50 3 .4 3E+02 1. 71 F 3 338. 1 2 673 - 680 676 . 68 5. 4 2E+Ol 24 . 55 2 . 00E+02 1. 45 F 4 35 1. 88 695 - 71 0 70 4 .19 1 . 96E+ 0 2 34.54 3.15E+02 1. 72 F 5 5 1 0 . 21 1 012 - 1026 102 0. 79 7 .60E+Ol 25.55 l . 68E+02 2 . 72 F 6 582.95 1160 - 1172 1166 . 23 7.09E+Ol 20.50 l.13E+ 0 2 1. 4 1 F 7 609.15 1213 - 1225 1218 . 63 1. 08E+02 24.76 1 . 06E+02 1. 83 F 8 661 . 3 7 13 1 5 - 1329 1323. 0 5 1. 07E+02 25 . 0 1 1. 28E+02 1. 98 F 9 859 . 91 17 1 6 - 1724 1720 . 08 2.06E+O l 12.54 4. 5 0 E+Ol 1. 35 F 10 91 1. 3 9 18 1 7 - 1829 1823 . 03 5.3 4E+O l 19.67 9 . 2 0 E+Ol 2.1 0 F 11 13 77 . 79 275 1 - 2760 27 5 5 . 70 l. 4 0E+O l 8 . 69 l.29E+Ol 1.21 F 12 1 460.70 29 1 3 - 2931 2921.51 5.68E+ 02 48 . 65 2 . 33E+Ol 2 . 63 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:21 :31PM 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 1 238.71 3.14E+02 45.75 3 .1 4E+02 4 . 57E+Ol F 2 295.27 8 . 32 E+ Ol 30 . 50 8.32E+Ol 3. 0 5E+Ol F 3 338 . 1 2 5.42E+ Ol 24.55 5.42E+ Ol 2 .4 5E+Ol F 4 351 . 88 1. 96E+02 34 . 54 8.36E+Ol 3.72E+Ol l . 12E+02 5. 0 8E+Ol F 5 510.21 7.60E+Ol 25 . 55 7 . 60E+Ol 2 . 55 E+Ol F 6 582 . 95 7.09E+Ol 20.50 7 . 09E+Ol 2 . 05E+O l F 7 609 .1 5 l .08E+02 24 . 76 4 . 12E+ Ol 2 . 42E+ Ol 6.6 5E+Ol 3 . 46E+O l F 8 661. 37 l.07E+02 25 . 01 6.61E+Ol 2.54E+Ol 4 . 07E+Ol 3 . 56E+O l F 9 859.91 2 . 06E+Ol 12 . 54 2.06E+ Ol l.25E+O l F 10 911. 39 5 . 3 4E+O l 1 9.67 5.34E+Ol l.97E+O l F 11 1377. 79 1 . 4 0E+O l 8 . 69 1. 40E+Ol 8 . 69E+OO F 12 1460 . 70 5 . 68E+ 02 48 . 65 5 . 63E+Ol 1 . 71E+ Ol 5 .1 2 E+02 5.16E+O l

1/15/2019 2:21:40PM Page 3 of6 Analysis Report for L 1-SUB-DRS-FSGS-W02-S8 L1-010-104 WEST PACKAGE: L 1-SUB-DRS M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCilgrams) Uncertainty K-40 1. 00 1460.75

• 10.67 6.71E+OO 7. 72E-01 CS-137 0.98 661.65

• 85.12 3.31E-02 2.90E-02 PB-212 0.55 77 .11 17.50 238.63

• 44.60 l.95E-01 3.0lE-02 BI-214 0.40 609.31

• 46.30 9.21E-02 4.82E-02 1120.29 15.10 1238 .11 5.94 1377.67

• 4 .11 4.52E-Ol 2.82E-01 1407.98 2.48 1509.19 2.19 1764.49 15.80 PB-214 0.72 77 .11 10.70 295.21

• 19.20 1.43E-01 5.30E-02 351.92

• 37.20 1.16E-01 5.31E-02 AC-228 0.30 209.28 4.40 338.32

• 11. 40 1.77E-01 8.07E-02 794.70 4.60 911. 60

• 27.70 1.78E-01 6.61E-02 964.60 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 2.000sigma

1/ 15/2019 2:21 :40PM Page 4 of6 Analysis Report for L 1-SUB-DRS-FSGS-W02-5B L1-010-104 WEST PACKAGE: L 1- SUB-DRS INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K-40 1. 000 6. 71 E+OO 7 . 72E- Ol CS - 137 0 . 987 3.3 1E- 02 2.90 E- 02 PB-212 0 . 559 l.95E- 01 3 . 0lE-02 BI - 214 0 . 406 l.02 E- 01 4. 75E- 02 PB- 21 4 0 .7 21 l . 30E - 0 1 3 .7 5E- 02 AC- 228 0.307 l .7 8E - 01 5. llE-02

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

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

1/15/2019 2:21:40PM Page 5 of6 Analysis Report for l 1-SUB-DRS-FSGS-W02-S8 L1-010-104 WEST PACKAGE: l 1*SUB-DRS UNIDENTIFIED PEAKS Peak locate Performed on  : 1/15/2019 2:21:31PM 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 5 510.21 2.11147E-02 16.80 F 6 582.95 1.96982E-02 14.46 F 9 859.91 5.72327E-03 30.42 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclldeMDA LineMDA Name (pCVgrams) (pCilgrams) (pCVgrams)

(keV)

+ K-40 1460.75

• 10.67 6.71E+OO 5.95E-01 5.95E-01

+ AR-41 1293.64 99.16 -2.60E+03 6.28E+03 6.28E+03

+ C0-60 1173.22 100.00 4.87E-02 6.02E-02 6.31E-02 1332.49 100.00 7.15E-02 6.02E-02

+ KR-85 513. 99 0.43 -4.00E+OO 1.02E+Ol 1. 02E+Ol

+ Y-88 898.04 93.70 1. 30E-03 4.04E-02 4.88E-02 1836.06 99.20 1.18E-02 4.04E-02

+ NB-94 702.63 100.00 2.31E-03 4.16E-02 4.16E-02 871.10 100.00 -2.16E-02 4.37E-02

+ I-131 284.30 6.06 2.89E-01 4.45E-02 5.85E-01 364.48 81. 20 -1.77E-02 4.45E-02 636.97 7.27 -5.0SE-01 5.87E-01

+ CS-134 604.70 97.60 -1.12E-02 4.89E-02 4.89E-02 795.84 85.40 2.78E-04 5. 40E-02

+ CS-137 661.65

• 85.12 3.31E-02 5.64E-02 5.64E-02

1/15/2019 2:21:40PM Page 6 of6 Analysis Report for L 1-SUB-DRS-FSGS-W02-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity Nuclide MDA LineMDA Name (pCi/grams) (pCilgrams) (pCi!grams)

(keV)

+ CE-14 4 80.12 1. 36 3.60E+O O 2.78 E-Ol 3 .40E+OO 1 33.5 1 11. 09 1. 12E-01 2.78E - 01

+ EU-152 1 2 1 .78 28.40 -1 .lOE-01 1.03E- 0 1 1.03E- 01 344 . 28 26 . 60 -7.03E-02 1 . 37E - 01 14 08 . 00 20.74 7.0lE-02 2.22E-01

+ EU-154 12 3.07 40.40 4.42E-06 7.36E-02 7.36E-02 723.30 19 . 70 2.07E-01 2.29E -01 1274 . 51 35.50 2.51E-0 2 1 . 61E-01

+ EU-155 86.54 32.80 -3.54E-02 1.1 7E-01 l . 17E-01 105 . 31 21. 80 - 3.08E-02 l.42E-01

+ BI-214 609.31

• 4 6.30 9.21E-02 8.62E-02 8 .6 2E-02 1120.29 15.10 2.5 1E-01 4.32E-Ol 1238 .11 5.94 -5. 71E-01 1.1 7E+OO 1377.67

• 4 .11 4.52E-01 5.00E-01 1407.98 2 .4 8 5.86E - 0 1 1 .85E+OO 1 509.19 2.19 -1. 21E+OO 1. 67E +OO 1764 .49 15 . 80 2 . 22E-01 3.2 1E-Ol

+ PB-214 77.11 10.70 4.76E-0 1 1.06E-01 4.63E-01 295.21

• 1 9 . 20 1. 43E-01 l. 1 9E-Ol 351.92

• 37.20 1.16E-01 1.06E-01

+ PA-228 89.95 22 .00 4.76E-0 1 2 . 65E-O l 4.44E-01 93 . 35 35 . 00 l.47E-01 2.65E-01 105.00 16 . 30 -2.55E-01 5 . 0lE-01 129.22 2.97 1.19E+OO 2.69E+OO 338 . 32 5.30 2.23E+OO 1.78E+OO 463.00 13.80 2.32E-0 1 7.21E-01 911.23 16.70 1.42E+OO 9.1 2E-01

+ AM-241 59 . 54 36.30 1.66E-01 2.18E-0 1 2.18E-O l

+ CM- 243 103.76 23.00 9.77E-03 1.37E-Ol 1. 37E-0 1 228 .1 8 10.60 3.59E- Ol 2 . 97E-0 1 277.60 14.00 1.66E-Ol 2.37E-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

1/15/2019 2:23:37PM Page I of6

~Jt.~~pex-Gamma Analysis Report for L 1-SUB-DRS-FSGS-W03-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FSGS-W03-SB Sample Description  : L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 9.094E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 9:31 :OOAM Acquisition Started  : 2/28/2018 12:06:37PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.5 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  : 5344 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:23:28PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/201 9 2:23:37PM Page 2 of6 Analysis Report for L 1-SUB-DRS-FSGS-W03-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. {keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.66 473 - 485 477.81 2 . 93E+02 45.86 5.80E+02 1. 92 F 2 295 .11 583 - 595 590.68 8.63E+Ol 27 . 95 4 . 02E+02 1. 28 F 3 35 1. 86 699 - 712 70 4. 15 1.63E+02 33 . 80 3 . 09E+02 1. 93 F 4 583. 1 8 1160 - 1175 1166.70 1.21E+02 26.43 1.34E+02 2.26 F 5 609 . 32 12 1 4 - 122 4 1218.97 8 . 82 E+Ol 24.64 1.21E+02 2 .0 9 F 6 911 . 18 1817 - 1829 1822.61 6 . 50E+ Ol 1 9.79 7 . 05E+Ol 2. 04 F 7 1460.61 2913 - 293 0 2921.33 4 . 80E+02 44.4 7 2 . 70E+Ol 2 . 58 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:23:28PM 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 1 238.66 2 . 93E+02 45.86 2 . 93E+02 4. 59E+Ol F 2 295 . 11 8 . 63E+Ol 27.95 8.63E+Ol 2.79E+Ol F 3 351.86 1.63E+02 33.80 8 . 36E+Ol 3. 72E+Ol 7.90E+Ol 5.03E+ Ol F 4 583.18 l . 21E+02 26.43 l . 21E+02 2 . 64 E+Ol F 5 609 . 32 8 . 82E+ Ol 24 . 6 4 4. 1 2E+Ol 2.42E+Ol 4 . 71E+Ol 3 . 45E+ Ol F 6 911 . 18 6 . 5 0E+ Ol 19.79 6 . 50E+ Ol l . 98E+ Ol F 7 1460.61 4.80E+02 44 . 47 5.63E+Ol 1. 71E+Ol 4 . 2 4E+02 4 . 77E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma

1/15/2019 2:23:37PM Page 3 of6 Analysis Report for L 1-SUB-DRS-FSGS-W03-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS 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) (pCl/grams) Uncertainty K- 40 0 . 99 1460.75

• 1 0 .67 5 . 07E+OO 6.37E- 01 PB - 212 0 . 56 77 .11 17 . 50 238.63

• 44.60 l.66E- 01 2.74E- 02 BI-214 0 . 35 609.31

• 46 . 30 5. 96E- 02 4.39E- 02 11 20 . 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. 72 77 . 11 10.70 295.21

• 19.20 1.36E-01 4 . 45E- 02 351.92

• 37 . 20 7.50E-02 4.79E - 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 confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K- 40 0.997 5 . 07E+OO 6.37E- 01 PB- 212 0 . 560 1 . 66E-0 1 2.74E- 02 BI - 214 0.350 5 . 96E - 02 4.39£- 02

1/15/2019 2:23:37PM Page 4 of6 Analysis Report for L 1-SUB-DRS-FSGS-W03-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

PB-214 0.721 1.08E-01 3.26E-02

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

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

1/15/2019 2:23:37PM Page 5 of6 Analysis Report for L1-SUB-DRS-FSGS-W03-S8 U -010-104 WEST PACKAGE: L1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:23:28PM 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 4 583.18 3 . 35558E- 02 10 . 94 F 6 9 11 . 18 l.80594E - 02 15 . 22 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 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCUgrams) (pCUgrams)

(keV)

+ K- 40 1460 . 75

• 10.67 5 . 07E+OO 5.52E - Ol 5.52E-01

+ AR- 41 1293 . 64 99 . 16 - 5 . 73E+02 1. 36E+03 1.36E+03

+ C0 - 60 11 73 . 22 1 00.00 1.86E- 02 4.82E - 02 5 . 63E - 02 1 332.49 100.00 2 . 12E- 02 4 . 82E- 02

+ KR- 85 513 . 99 0 . 43 1.38E+Ol 9.20E+OO 9 . 20E+OO

+ Y- 88 898 . 0 4 93 . 70 1 . 70E - 02 3 . 77 E- 02 4 . 15E- 02 1 836.06 99 . 20 - 1.65E- 02 3 . 77E - 02

+ NB- 94 702.63 1 00.00 7.63E- 03 3 . 90E- 02 3 . 90E-02 871 . 10 1 00 . 00 -4.34E - 02 4.12E - 02

+ I - 131 28 4. 30 6.06 3.8 6E-01 4 . 00E- 02 5 . 60E - 01 364.48 81. 20 2 . 68E- 02 4.00E - 02 636.97 7 . 27 4.54 E- 01 5 . 14E- 01

+ CS - 134 604.70 97.60 - 2.57E- 02 4 . 48E - 02 4 . 48E- 02 795.84 85.40 -4 . 42E-02 4.67E- 02

1/15/2019 2:23:37PM Page 6 of6 Analysis Report for L 1-SUB-DRS-FSGS-W03-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity Nucl/deMDA LlneMDA Name (pCilgrams) (pCilgrams) (pCi/grams)

(keV)

+ CS - 137 661 . 65 85 .1 2 6.37E-02 5 . 15E-02 5.15E-02

+ CE-144 80.12 1. 36 l.77E+OO 2.58E- 01 3 . 19E+OO 133.51 11. 09 5 . 33E-02 2.58E-0 1

+ EU-152 121.78 28.40 -3 . 81E - 02 9 . 76E-02 9.76E - 02 344.28 26.60 - 4 . 0lE-02 l .29E-Ol 1 408.00 20.74 8 . 16E- 02 2.07E-O l

+ EU-154 1 23.07 40.40 -9.17E-03 6.94E - 02 6 . 94E-02 723 . 30 19.70 2.77E -0 2 2.0 l E- 01 1274.51 35 . 50 -5 . 56E- 0 2 l.4 2E- Ol

+ EU- 1 55 86 . 54 32.80 -4 . 85E-02 l . ll E-0 1 l . ll E- 01 105 . 3 1 2 1. 8 0 - 5.84 E-02 1.34E- 01

+ BI-2 1 4 609.3 1

• 4 6.30 5.96E- 02 7.94E - 02 7.94E- 02 112 0 .29 15.10 8.07E-02 3.65E- Ol 1238 .11 5 . 94 7.69E - 0 1 l . 02E+OO 1 377.67 4 . 11 8.63E - 03 1. 03E+OO 14 0 7 . 98 2.48 6.82E-0 1 1 . 73E+OO 150 9 . 19 2. 1 9 -l .02E+OO 1. 53E+OO 17 64 .4 9 15.80 2.92 E- 01 3.08E-0 1

+ PB-214 77.11 1 0.70 5.56£- 01 9.41E-02 4. 32 E-O l 295.21

• 19.20 1.36E- 01 l.23E-0 1 351 . 92

• 37 . 20 7.50E-02 9 . 41E- 02

+ PA- 228 89.95 22 . 00 1. 55E- 01 2 . 19E-01 3.67E-01 93 . 35 35 . 00 -6 . 86E- 02 2 .1 9E- 01 1 05.00 16.30 - 9 . 82E- 0 2 4.20E - 01 129 . 22 2 . 97 - 3.62E-02 2.22E+OO 338 . 32 5.30 l.61E+OO 1. 46E+OO 4 63 . 00 13.80 3.62E-02 5 . 78E- 01 911 . 23 16 . 70 5.85E-01 6.88E-01

+ AM- 241 59 . 54 36.30 - l .33E- 02 l . 99E- 01 l . 99 E-01

+ CM- 2 4 3 1 0 3 . 76 23.00 6.78E- 02 1.29E-Ol 1.29E- 0 1 228 .1 8 10 . 60 - l.81E - 03 2 . 59E-0 1 277 . 60 1 4.00 -3.48E-02 2.19E-0 1

+ = 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

1/15/2019 2:24: 15PM Page 1 of6

~~~~pex-Gamma Analysis Report for L 1- SUB-DRS-FSGS-W04-SB L 1-010-104 WEST PACKAGE: L1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FSGS-W04-SB Sample Description  : L1-010-104 WEST PACKAGE: L1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 9.350E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 9:31:00AM Acquisition Started  : 2/28/2018 10:24:57AM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 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  : 5345 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:24:06PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:24:15PM Page 2 of6 Analysis Report for L 1-SUB-DRS-FSGS-W04-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.33 142 - 156 1 53.20 2 . 39E+ 02 62 . 89 1. 24E+03 5.14 F 2 238.59 471 - 485 477 . 66 2. 72 E+0 2 44 . 19 6 . 34E+02 1. 87 F 3 35 1. 89 699 - 711 704.2 1 1 . 37E+02 32 .0 5 3.1 4E+02 1. 77 F 4 583.00 1163 - 1171 11 66.34 5. 4 6E+ Ol 20.75 1 .15E+02 1. 65 F 5 609. 1 3 1212 - 1225 1218.59 1.26E+0 2 26.05 1.1 7E+02 1. 82 F 6 9 11. 27 1818 - 1828 1822.78 3 . 84E+Ol 16.24 8.33E+Ol 1. 31 F 7 1460 . 52 2913 - 293 0 2 921.16 5 . 24 E+0 2 46.90 4 .2 4E+Ol 2 . 56 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:24:06PM 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 76.33 2 .3 9E+02 62.89 2.39E+ 0 2 6 . 29 E+O l F 2 238.59 2.72E+02 44 . 19 2 . 72E+0 2 4 . 4 2E+O l F 3 35 1. 89 1.37E+02 32 . 05 8 . 36E+Ol 3. 72E+O l 5.39E+Ol 4 . 91 E+Ol F 4 583 . 00 5.46E+Ol 20 . 75 5 .4 6E+0 1 2.08E+ Ol F 5 609 . 13 1 . 26E+02 26 . 05 4 . 12E+O l 2 . 42E+Ol 8 . 52E+Ol 3.5 6E+O l F 6 911. 27 3 . 8 4E+O l 16.2 4 3.84E+Ol 1. 62 E+ Ol F 7 1 4 60 . 52 5 . 2 4E+0 2 46 . 90 5.63E+ Ol 1. 71E+O l 4.68E +02 4. 99E+O l M =First peak in a multiplet region m =Other peak in a multiplet region F =Fitted singlet Errors quoted at 2.000sigma

1/15/2019 2:24:15PM Page 3 of 6 Analysis Report for L 1-SUB-DRS-FSGS-W04-S8 L 1-010-104 WEST PACKAGE: L 1-SUB-DRS 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) (pCilgrams) Uncertainty K- 40 0.99 1 460.75

• 10 . 67 5 . 45E+OO 6.5 6E- 01 PB- 2 1 2 0 . 97 77 .11

• 17 . 50 3 . 6 7E- 01 9. 9 2E- 02 238 . 63

• 44.60 l.50E - 01 2.5 6E-0 2 BI - 214 0.34 6 09 . 31

• 46. 30 l.OSE- 01 4. 4 2E-0 2 1120 . 29 15.10 1238 .11 5. 94 137 7 .67 4 . 11 1 40 7 . 98 2 . 48 1509 . 19 2 . 19 17 64.4 9 15 . 80 PB- 21 4 0.5 1 77 .11

• 10 . 70 6.00E - 01 l.62E- 0 1 29 5. 21 1 9 . 20 351.92

• 3 7.2 0 4.98E - 02 4.54 E- 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 confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)

K-4 0 0 . 992 5.45E+OO 6.56E-01 PB - 212 0 . 973 l.61E - 01 2.48 E- 02 BI- 214 0.347 1. 05E- 01 4 .4 2 E- 02

1/15/2019 2:24:15PM Page4 of6 Analysis Report for L 1-SUB-DRS-FSGS-W04-S8 L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence (pCi/grams) Uncertainty PB-214 0 .511 7.07E-02 4.39E-02

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

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

1/15/2019 2:24:15PM Page 5 of6 Analysis Report for L1-SUB-DRS-FSGS-W04-S8 L1-010-104 WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:24:06PM Peak Locate From Channel  : 100 Peak Locate To Channel  : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 4 583.00 l.51694E-02 19.00 F 6 911.27 l.06571E-02 21.16 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 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pC/lgrams) (pCUgrams) (pCUgrams)

(keV)

+ K-40 1460.75

• 10.67 5.45E+OO 5.69E-Ol 5.69E-Ol

+ AR-41 1293.64 99.16 l. l 7E+02 6.66E+02 6.66E+02

+ C0-60 1173.22 100.00 1.21E-02 4.97E-02 5.SOE-02 1332.49 100.00 4.28E-02 4.97E-02

+ KR-85 513.99 0.43 7.26E+OO 8.99E+OO 8.99E+OO

+ Y-88 898.04 93.70 -l.09E-02 3.16E-02 4.53E-02 1836.06 99.20 6.31E-03 3.16E-02

+ NB-94 702.63 100.00 -7.78E-03 3.54E-02 3.54E-02 871.10 100.00 -2.13E-02 3.90E-02

+ I-131 284.30 6.06 2.59E-Ol 3.83E-02 5.39E-01 364.48 81. 20 3.06E-03 3.83E-02 636.97 7.27 l.51E-Ol 5.53E-01

+ CS-134 604.70 97.60 -2.06E-02 4.37E-02 4.55E-02 795.84 85.40 -3.90E-03 4.37E-02

1/15/2019 2:24:15PM Page 6 of6 Analysis Report for L 1-SUB-DRS-FSGS-W04-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCi/grams) (pCi/grams)

(keV)

+ CS-1 37 6 6 1.65 85 .1 2 6.32E-02 5 . 40E-02 5 .4 0E - 02

+ CE -1 44 80 .1 2 1. 36 -2.52E+OO 2 . 34 E- 0 1 3 .0lE +OO 133. 51 11. 0 9 3.52E- 02 2 . 3 4E -0 1

+ EU-1 52 12 1. 78 28.40 - 6.79E- 02 9.21 E- 02 9 . 21E - 02 344 . 28 26 . 60 -8 . 09E-02 1. 2 0E- 01 1 408.00 20.74 -6 . 83E-02 l . 80E- 01

+ EU-154 1 23 . 07 40 .40 1.45E- 02 6 . 53E-02 6 . 53E-02 723 . 30 19 . 70 6 .00E- 0 3 l. 91 E- 01 1 27 4 .5 1 35 . 50 8 . 79E-0 3 l. 26E- Ol

+ EU-1 5 5 86. 5 4 32.80 -4 . 85E-0 2 l . 05E- 0 1 l. 05E- Ol 10 5 . 3 1 21 . 80 -2 .0 0E-0 2 l. 27E-01

+ BI -21 4 60 9.31

• 4 6.30 1. OSE- 0 1 7 . 90E- 02 7 . 90E - 02 11 20 . 29 15.10 l . 42E-0 2 3 . 60E - 01 1 238 .11 5.9 4 2 . 58E- 0 1 9.62E- 01 137 7 . 67 4 .11 3 . 53E-0 1 9.86E- 0 1 1 4 0 7.98 2. 4 8 -5 . 71E-01 1. 51E+OO 150 9 . 19 2. 1 9 -5.40 E-0 1 1. 34E+ OO 1764 .4 9 1 5.80 2 . 57E - 01 2. 71E-01

+ PB- 214 77 .11

• 1 0.70 6.00 E- 0 1 9 . 09E- 02 3 . 55E-Ol 295 . 2 1 19. 2 0 9 . 84E- 02 l . 64 E- 0 1 351. 92

• 37 . 20 4 . 98E-02 9.09E - 02

+ PA- 228 89.95 22 . 00 3 . SOE- 01 2 . 02E-01 3.41E-01 93.35 35 . 00 2 .l OE- 0 1 2 .0 2E-Ol 105.00 16 . 30 1.19E-O l 3 . 80E- Ol 129 . 22 2.97 4.49E- 0 1 1. 95E+OO 338 . 32 5 . 30 9 .45E-0 1 1. 28E+OO 4 63 . 00 1 3.8 0 l.8 7E-0 1 5 . 06E- 01 911.23 16 . 70 2 . 7 4E -02 6. 74E- 01

+ AM- 24 1 59 . 5 4 36 . 30 -1 . 45E- 02 1. 90 E- 0 1 l. 90E -0 1

+ CM- 243 103 . 76 23. 0 0 4 .45E-02 1. 22E - 01 1 . 2 2E- 01 228.18 1 0. 60 -5.0lE-02 2.51 E-01 277 . 60 1 4 .00 l.5 8E -Ol 2.13E- 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

1/15/2019 2:24:56PM Page I of6

~ ~ ~pex-Gamma Analysis Report for L 1-SUB-DRS-FSGS-W05-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FSGS-W05-S8 Sample Description  : L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 9.936E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 9:27:00AM Acquisition Started  : 2/28/2018 1:15:00PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.9 seconds Dead Time  : 0.30%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100-4096 Peak Area Range (in channels)  : 100-4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5346 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:24:47PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:24:56PM Page 2 of6 Analysis Report for L 1-SUB-DRS-FSGS-WOS-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.02 147 - 160 152.59 l.92E+02 60.58 l . 37E+03 3 . 38 F 2 1 86 . 01 367 - 379 372. 51 9.0l E+Ol 38 . 56 7 . 69E+02 1. 79 F 3 238.60 470 - 485 477.68 3.43E+ 02 48 .00 6.8 4E+ 0 2 1. 90 F 4 295 . 17 587 - 595 590.78 6 . 83E+ Ol 27 . 57 2.8 7 E+02 1. 44 F 5 327.90 652 - 660 656 . 24 2 . 59E+O l 19 . 9 4 2.19E+02 1. 1 6 F 6 338.50 674 - 68 1 677. 43 4 .4 9E+O l 22 . 85 l.85E+02 1. 43 F 7 351.76 699 - 71 0 703.9 4 1.72E+ 02 33 . 59 2.81E+02 1. 68 F 8 583.06 1163 - 1171 11 66 . 47 8 . 31E+Ol 22.1 4 9. 4 9E+O l 1. 34 F 9 609. 1 8 1210 - 1228 1 218 . 69 l . 13E+02 25 . 68 1. 44E+02 2. 4 3 F 10 91 0.97 1817 - 1829 1 822.18 8.26E+ Ol 21. 33 6.66E+O l 2 . 13 F 11 968. 87 1933 - 1946 1 937.97 4. ll E+O l 18.33 l . 1 0E+02 1. 96 F 12 1 460.64 2912 - 2930 2921. 39 5 . 1 4E+02 4 5. 5 7 l .42E+Ol 2 . 57 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:24:47PM 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. 0 2 1.92E+ 0 2 6 0 .58 l . 92 E+0 2 6.06E+ Ol F 2 186 .0 1 9 . 0lE+Ol 38.56 9.0lE+Ol 3.86E +Ol F 3 238 . 60 3 . 43E+02 48.00 3 . 43E+02 4. 80E+ Ol F 4 295.17 6.83E+Ol 27.57 6 . 83E+Ol 2.76E +Ol F 5 327 . 9 0 2.59E+Ol 19 . 94 2 . 59E+Ol 1. 99E +Ol F 6 338 . 50 4 . 49E+Ol 22.85 4 . 49E+Ol 2.29E+ Ol F 7 351. 76 1. 72E+02 33.59 8 . 36E+Ol 3 . 72E+Ol 8 . 81E+Ol 5.0 l E+ Ol F 8 583 .0 6 8 . 31E+Ol 22.14 8.31E+Ol 2.2 1E+ Ol F 9 609.18 1.13E+02 25.68 4.12E+ Ol 2 .4 2E+Ol 7.22E+Ol 3 . 53E+ Ol F 10 91 0 . 97 8.26E+O l 21.33 8 . 26E+Ol 2 .13E+ Ol F 11 968.87 4. ll E+Ol 1 8 . 33 4.l l E+O l l. 83E+ Ol F 12 1460.64 5 . 1 4E+02 45 . 57 5 . 63E+O l l . 71E+Ol 4.57 E+ 02 4 . 8 7E+Ol

1/15/2019 2:24:56PM Page 3 of6 Analysis Report for L 1-SUB-DRS-FSGS-W05-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCi/grams) Uncertainty K-40 0.99 1460.75

• 10.67 5.0lE+OO 6.02E-01 PB-212 0.56 77 .11 17.50 238.63

• 44.60 1.78E-01 2.66E-02 BI-214 0.34 609.31

• 46.30 8.37E-02 4.12E-02 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 9.83E-02 4.00E-02 351 .92

• 37.20 7.66E-02 4.37E-02 RA-226 0.99 186.21

• 3.28 5.35E-01 2.31E-01 AC-228 0.60 209.28 4.40 338.32

• 11. 40 1.23E-01 6.29E-02 794 .70 4.60 911. 60

• 27.70 2.31E-Ol 6.03E-02 964.60 5.20 969. 11

• 16.60 2.02E-01 9.06E-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 confidence index threshold = 0.30 Errors quoted at 2.000sigma

1/15/2019 2:24:56PM Page 4 of6 Analysis Report for L 1-SUB-DRS-FSGS-W05-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K-40 0.998 5.0lE+OO 6.02E-Ol PB-212 0.560 1.78£-01 2.66£-02 BI-214 0.348 8.37E-02 4.12E-02 PB-214 0.719 8.84E-02 2.95E-02 RA-226 0.993 5.35E-01 2.31E-01 AC-228 0.605 1. 83E-Ol 3.92E-02

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

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

1/15/2019 2:24:56PM Page 5 of6 Analysis Report for L 1-SUB-DRS-FSGS-WOS-SB L 1-010-104 WEST PACKAGE: L 1-SUB-ORS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:24:47PM Peak Locate From Channel  : 100 Peak Locate To Channel  : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 76.02 5.33407£-02 15.77 F 5 327.90 7.18199£-03 38.56 F 8 583.06 2. 309llE-02 13.31 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCl!grams) (pCl/grams) (pCl!grams)

(keV)

+ K-40 1460.75

• 10.67 5.0lE+OO 4.77E-01 4.77E-01

+ AR-41 1293.64 99.16 7.14E+02 l.94E+03 l.94E+03

+ C0-60 ll73.22 100.00 l.82E-02 4.59E-02 5.40E-02 1332.49 100.00 2.14E-02 4.59E-02

+ KR-85 513. 99 0.43 9.82E+OO 8.74E+OO 8.74E+OO

+ Y-88 898.04 93.70 3.19E-02 2.98E-02 4.28E-02 1836.06 99.20 -2.54E-02 2.98E-02

+ NB-94 702.63 100.00 -3.27E-02 3.32E-02 3.32E-02 871.10 100.00 -9.17E-03 3.76E-02

+ I-131 284.30 6.06 -l.47E-01 3.64E-02 4.91E-01 364.48 81.20 1. 51E-03 3.64E-02 636.97 7.27 4.27E-02 4.66E-01

+ CS-134 604.70 97.60 6.33E-04 4.22E-02 4.22E-02 795.84 85.40 l.68E-02 4.62E-02

1/15/2019 2:24:56PM Page 6 of6 Analysis Report for L1-SUB-ORS-FSGS-W05-SB L1-010-104 WEST PACKAGE: L1-SUB-DRS Nuclide Energy Yield{%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCi/grams) (pCi/grams)

(keV)

+ CS-137 661.65 85.12 4.23E-02 4.90E-02 4.90E-02

+ CE- 1 44 80.12 1. 36 -2. llE- 01 2.39E-Ol 2 . 91E+OO 133.51 11. 09 2.42E-01 2.39E-01

+ EU-1 52 121. 7 8 28. 40 -7.2 1E-02 9 . 16E-02 9.16E-02 344.28 26.60 -1 . 09E-Ol l.13E-01 1 40 8 .00 2 0.74 -2 . 73E-02 1.63E-01

+ EU-154 123.07 40.40 -4.38E-02 6 . 46E- 02 6.46E-02 723.30 19 .70 4. 1 8E-02 1 . 85E- 01 1274.51 35.50 -5.62E-02 1. 24E-01

+ EU-155 86.54 32 . 80 7.27 E-03 1. 02E-01 1. 02E-01 105.31 21. 80 -9.94E - 02 1.22E-01

+ BI-214 609.31

• 46.30 8.37E-02 8.23E-02 8.23E-02 1120.29 15.10 1 .93E-01 3 .55E- 01 1238.11 5.94 1 .67E-01 9.63E-01 1377. 67 4 .11 6.40E-01 1.0lE+OO 140 7.98 2 .48 -2.29E-01 1 . 36E+OO 1509.19 2.19 2.83E-01 1.43E+OO 1764.49 15.80 7.34E-02 2.37E- 0 1

+ PB-214 77 .11 10 . 7 0 4.71E-Ol 8.2 4E- 02 3 . 97E-0 1 295.21

• 19.20 9.83E-02 8.74E-02 351. 92

• 37.20 7.66E-02 8.24E -0 2

+ PA-228 89 . 95 22.00 3.8 7E-01 2.09E-01 3 . 55E-01 93.35 35.00 1. 46E- 02 2.09E -01 105.00 16.30 -8.78E-0 2 3 .99E- 0 1 129.22 2.97 1. 50E+OO 2.19E+ OO 338.32 5.30 1 .98E+OO 1.36E+OO 46 3.00 13 .80 2.91E-0 1 5 .64E-01 911.23 16 . 70 8 . 21E-01 7.29E- Ol

+ AM-241 59.54 36.30 -1. OlE- 02 1. 83E-O l 1. 83E-01

+ CM- 2 43 103 .76 23.00 - 2.16E-03 l.16E-01 l.16E-01 228.18 10. 60 9.44E-02 2 .46E-Ol 277.60 14.00 5 . 33E-02 2.04E-01

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = MOA value not calculated

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

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

1/15/2019 2 :25:42PM Page I of6 Jt'Apex-Gamma Analysis Report for L 1-SUB-DRS-FSGS-W06-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FSGS-W06-SB Sample Description  : L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8.908E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 9:22:00AM Acquisition Started  : 2/28/2018 2:17:41PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3611.0 seconds Dead Time  : 0.30%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100-4096 Peak Area Range (in channels)  : 100 - 4096 Identification Energy Tolerance  : 1.000keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5347 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:25:33PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/ 15/2019 2:25:42PM Page 2 of6 Analysis Report for L 1-SUB-DRS-FSGS-W06-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 92.98 183 - 193 186 . 50 6.70E+Ol 39 . 25 9.05E+02 1. 48 F 2 238.76 472 - 4 85 478.00 3.39E+02 47.95 5.08E+02 2.44 F 3 295.13 587 - 596 590.71 7.98E+Ol 28 . 33 3.06E+02 1. 54 F 4 338.09 672 - 682 676.62 5.65E+Ol 25 . 12 2 . 44E +02 1. 72 F 5 352.06 700 - 708 704.54 1.41E+02 31.21 1 . 91E+02 1. 74 F 6 510.30 1015 - 1028 1020.97 8 . 54E+Ol 25.87 1 . 73E+02 2.52 F 7 582 . 94 1160 - 1171 1166.22 8 . 00E+Ol 22 .96 1.13E+02 2 . 00 F 8 609.06 1212 - 1224 1218.46 9.97E+Ol 25.17 1.43E+02 1. 86 F 9 910.78 1814 - 1829 1821 . 79 4.90E+Ol 18 . 32 8.0lE+Ol 2.48 F 10 968 . 94 1932 - 1942 1938 . 10 1.67E+Ol 12 . 25 8.36E+Ol 1. 06 F 11 1332 . 40 2660 - 2670 2664.95 2.19E+Ol 12 . 36 3 . 85E+Ol 1. 65 F 12 1460 . 47 2911 - 2929 2921.05 4. 65E+0 2 43 . 47 l . 90E+Ol 2.66 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:25:33PM 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 92 . 98 6.70E+Ol 39.25 6.70E+Ol 3 . 93E+Ol F 2 238 . 76 3 . 39E+02 47 . 95 3 . 39E+02 4.79E+Ol F 3 295 . 13 7 . 98E+Ol 28 . 33 7 . 98E+Ol 2 . 83E+Ol F 4 338.09 5.65E+Ol 25.12 5 . 65E+Ol 2.51E+Ol F 5 352.06 1.41E+02 31.21 8.36E+Ol 3 . 72E+Ol 5 . 72E+01 4 . 86E+Ol F 6 510 . 30 8.54E+Ol 25.87 8.54E+01 2 . 59E+Ol F 7 582.94 8.00E+Ol 22. 96 8 . 00E+Ol 2 . 30E+Ol F 8 609.06 9.97E+Ol 25 . 17 4 . 12E+Ol 2.42E+Ol 5.85E+Ol 3 .49E+Ol F 9 910.78 4 . 90E+Ol 18 . 32 4 . 90E+Ol 1. 83E+Ol F 10 968 . 9 4 1 . 67E+Ol 12 . 25 1 . 67E+Ol 1 .22E+Ol F 11 1332 . 40 2. 1 9E+Ol 1 2 . 36 2 .1 9E+Ol 1.24E+O l F 12 1460.47 4 . 65E+02 43 . 47 5.63E+Ol 1. 7 1E+Ol 4.09E+02 4.67E+Ol

1/15/2019 2:25:42PM Page 3 of6 Analysis Report for L 1-SUB-DRS-FSGS-W06-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCi/grams) Uncertainty K-40 0.98 1460.75

• 10.67 5.00E+OO 6.35E-01 PB-212 0.55 77 .11 17.50 238.63

• 44.60 1.96E-01 2.96E-02 BI-214 0.34 609.31

• 46.30 7.56E-02 4.53E-02 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 l.28E-01 4.59E-02 351.92

• 37.20 5.SSE-02 4. 72E-02 AC-228 0.58 209.28 4.40 338.32

• 11. 40 l.72E-01 7.71E-02 79 4.70 4.60 911. 60

• 27.70 l.52E-01 5.74E-02 964.60 5.20 969 .11

• 16.60 9.14E-02 6.73E-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 confidence index threshold = 0.30 Errors quoted at 2.000sigma

1/15/2019 2:25:42PM Page 4 of6 Analysis Report for L 1-SUB-DRS-FSGS-W06-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K- 40 0 . 988 5.00E+OO 6.35E-01 PB-212 0 . 558 1. 96E-0 1 2 . 96E- 02 BI- 214 0.345 7 . 56E-02 4.53E- 02 PB- 214 0 . 719 9 . 28E- 02 3.29E- 02 AC- 228 0 . 588 1.38E- 0 1 3 . 80E- 02

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

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

1/15/2019 2:25:42PM Page 5 of6 Analysis Report for L1-SUB-DRS-FSGS-W06-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:25:33PM Peak Locate From Channel  : 100 Peak Locate To Channel  : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 92.98 l.86204E-02 29.28 Tol. PA-228 F 6 510.30 2.37301E-02 15.14 F 7 582.94 2.22184E-02 14.35 F 11 1332.40 6. 08117£-03 28.23 Tol. C0-60 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuc/ldeMDA LlneMDA Name (pCi/grams) (pCilgrams) (pCl/grams)

(keV)

+ K-40 1460.75

• 10.67 5.00E+OO 5.45E-01 5.45E-01

+ AR-41 1293.64 99.16 1.27E+03 3.32E+03 3.32E+03

+ C0-60 1173.22 100.00 6.06E-03 5.59E-02 5.84E-02 1332.49 100.00 4.67E-02 5.59E-02

+ KR-85 513. 99 0.43 1.27E+Ol 9.08E+OO 9.08E+OO

+ Y-88 898.04 93.70 -1.33E-02 3.33E-02 4.20E-02 1836.06 99.20 -1.67E-02 3.33E-02

+ NB-94 702.63 100.00 -1.25E-02 3.69E-02 3.69E-02 871.10 100.00 -7.39E-03 4.39E-02

+ I-131 284.30 6.06 -8.97E-02 4.19E-02 5.52E-01 364.48 81. 20 2.97E-03 4.19E-02 636.97 7.27 -8.SlE-02 5.35E-01

+ CS-134 604.70 97.60 -l.43E-05 4.62E-02 4.62E-02

1/ 15/201 9 2:25:42PM Page 6 of6 Analysis Report for L 1-SUB-DRS-FSGS-W06-S8 L1 -010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity Nuclide MDA LineMDA Name (pCi/grams) (pCilgrams) (pCilgrams)

(keV)

CS-134 795.84 85.40 -3.75E- 02 4.62E-02 4.63E-02

+ CS-137 661. 65 85.12 4.88E-02 5.16E - 02 5.16E-02

+ CE-144 80.12 1. 36 1 .78 E+OO 2.53E-01 3. llE+OO 133 . 51 11. 09 2 . 45E-04 2 . 53E-01

+ EU-1 52 121.78 28 . 40 -1.70E-02 9. 96E-02 9 . 96E-02 34 4 .28 26 . 60 - 9 . 73E-02 1. 24E-01 1 4 08.00 20.74 1 . 72E-01 1 .94E-01

+ EU- 1 54 123.07 40 . 40 -3 . 26E-02 6.97E-02 6 . 97E-02 723.30 19.70 2.0lE-01 2.05E-Ol 1274.51 35.50 6.80 E- 02 1. 32E-01

+ EU-155 86.54 32.80 2 . 0lE-02 1.lOE-0 1 l.l OE-01 105.31 21. 80 3.46E- 02 1 .37E - 0 1

+ BI-214 609.31

• 46.30 7.56E-02 8.59E-02 8.59E- 02 11 20.29 1 5.10 2.12E- 02 3.87E-01 1 238.11 5.94 4 . lOE-01 1.05E+00 1377.67 4 . 11 9 . 52E-02 1 . 04E+OO 1 407.98 2.48 1. 44E+OO 1.62E+OO 1 509.19 2 . 19 -5.61E- 01 1.44E+OO 1 764.49 15 . 80 1 . SOE-01 2. 96E-01

+ PB-214 77 . 11 10.70 5.75E-01 8.29£-02 4.20E-01 295 . 21

• 19.20 1.28E-01 1 . 04E-01 35 1. 92

• 37.20 5.55E-02 8 . 29E- 02

+ PA-228 89.95 22.00 -7.77 E-03 2 . 37E-0 1 4 . 05E- 01 93.35 35 . 00 5.96E-02 2 . 37E- 01 1 05 . 00 16.30 -5.43E-02 4. 60E-01 1 29.22 2 . 97 1.40E+OO 2. 43E+OO 338.32 5 . 30 8.98E-01 1. 52E+OO 4 63.00 13.80 6.12E-02 6 . 26E - 01 911.23 16 . 7 0 8.06£-0 1 7.66E-0 1

+ AM-241 59.54 36 . 30 -2.85E-02 2.00 E- 01 2.00E-01

+ CM-243 103.76 23 . 00 - 6.05E- 02 1.28E- 01 1.28E-01 228 . 18 10 . 60 - 1. 26£-02 2.60E- 01 277.60 14.00 - 4.21E-02 2. 1 8£-0 1

+ = 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

1/15/2019 2:26:33PM Page I of6

~~~~pex-Gamma Analysis Report for L 1-SUB-DRS-FSGS-W07-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FSGS-W07-SB Sample Description  : L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8.649E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 9:16:00AM Acquisition Started  : 3/1/2018 6:16:01AM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3611.0 seconds Dead Time  : 0.30%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100- 4096 Peak Area Range (in channels)  : 100 - 4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5348 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:26:24PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:26:33PM Page 2 of6 Analysis Report for L 1-SUB-DRS-FSGS-W07-S8 L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. {keV) start end Centroid Area Uncertainty Counts (keV)

F 1 185 . 71 368 - 377 371 . 92 4 . 97E+Ol 29 . 55 5 . 56E+02 1.17 F 2 238.64 470 - 485 477 . 75 2.75E+02 44 . 86 7 . 36E+02 1. 82 F 3 2 95.10 584 - 59 5 590 . 66 9 . 77E+Ol 32.61 3 . 54E+02 2 . 14 F 4 338.36 671 - 68 5 677 . 15 7 . 71E+Ol 27 . 72 3 . 17E+02 2 . 02 F 5 351 .92 697 - 711 7 04 . 26 1 . 49E+0 2 32 . 32 3.41E+02 1. 78 F 6 583.05 1162 - 1172 1166.44 8.70E+Ol 23. 96 1. 31E+02 1. 72 F 7 609.26 1212 - 1223 1218.85 1 . 34E+02 26 . 94 1 . 08E+02 1. 79 F 8 911. 06 1818 - 1830 1822 . 37 7. 22 E+Ol 20 . 63 8 . 20E+Ol 2 . 11 M 9 964 . 86 1925 - 1944 192 9 . 94 1 . 66E+Ol 11. 35 4.95E+Ol 1. 27 m 10 968.66 1925 - 1944 1937.54 3.30E+Ol 14 . 30 5.0lE+Ol 1.28 F 11 1119.20 2234 - 2244 2238 .5 7 2 . 18E+Ol 11. 59 5 . 16E+Ol 0 . 91 F 12 1460.51 2911 - 2931 292 1.1 2 5.22E+02 45.97 1.55E+Ol 2 . 63 M ::: First peak in a multiplet region m ::: Other peak in a multiplet region F ::: Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/201 9 2:26:24PM Env. Background File  : C:\Canberra\Apex\Root\Dairyland_ NPP\Data\0000001364. CNF Peak. Energy Original Orig. Area Ambient Back.gr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 185.71 4.97E+O l 29.55 4 . 97E+Ol 2 . 95E+Ol F 2 238.64 2 . 75E+02 44.86 2.75E+02 4 . 49E+Ol F 3 295 . 10 9 . 77E+Ol 32 . 61 9.77E+Ol 3 . 26E+Ol F 4 338 . 36 7 . 71E+Ol 27 . 72 7 . 71E+Ol 2.77 E+Ol F 5 351 . 92 1. 4 9E+02 32 . 32 8.36E+Ol 3 . 72E+Ol 6 . 52E+Ol 4.93E+Ol F 6 583 . 05 8 . 70E+Ol 23 . 96 8 . 70E+Ol 2.40E+Ol F 7 609 . 26 1 . 3 4E+02 26. 94 4 . 12E+Ol 2 . 42 E+Ol 9 . 25E+Ol 3 . 62E+Ol F 8 911.06 7.22E+O l 20.63 7 . 22E+Ol 2 . 06E+Ol M 9 964.86 l . 66E+Ol 11. 35 1. 66E+O l l . 13E+Ol m 10 968 . 66 3 . 30E+Ol 14 . 30 3 . 30E+Ol 1 .4 3E+Ol F 11 1119 . 20 2 . 18E+Ol 11. 59 2 . 18E+Ol 1.16E+Ol F 12 1460 . 51 5 . 22E+02 45 . 97 5 . 63E+Ol 1 . 71E+Ol 4 . 66E+02 4.91E+Ol

1/15/2019 2:26:33PM Page 3 of6 Analysis Report for L 1-SUB-DRS-FSGS-W07-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCi/grams) Uncertainty K-40 0.99 1460.75

• 10.67 5.87E+OO 6.99E-01 PB-212 0.56 77 .11 17.50 238.63

• 44.60 l.64E-01 2.81E-02 BI-214 0.34 609.31

• 46. 30 l.23E-01 4.87E-02 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. 72 77 .11 10.70 295.21

• 19.20 l.62E-01 5.45E-02 351.92

• 37.20 6.SlE-02 4.93E-02 RA-226 0.96 186.21

• 3.28 3.38E-01 2.02E-01 AC-228 0.70 209.28 4.40 338.32

• 11. 40 2.43E-01 8.80E-02 794 . 70 4.60 911. 60

• 27.70 2.31E-Ol 6.69E-02 964.60

• 5.20 2.99E-Ol 2.04E-01 969 .11

• 16.60 l.86E-01 8.12E-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 confidence index threshold = 0.30 Errors quoted at 2.000sigma

1/15/2019 2:26:33PM Page 4 of6 Analysis Report for L 1-SUB-DRS-FSGS-W07-S8 L1-010-104 WEST PACKAGE: L 1-SUB-DRS INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)

K- 40 0 . 990 5 . 87E+OO 6 . 99E- 01 PB-212 0 . 560 1.64E-01 2 . 81E-02 BI - 21 4 0.349 1.23E- 01 4.87E-02 PB-214 0.721 1. 09E-01 3 . 66E- 02 RA- 226 0 . 961 3 . 38E-01 2.02E- Ol AC- 228 0.708 2.2 4E- 01 4.35E- 02

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

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

1/15/2019 2:26:33PM Page 5 of6 Analysis Report for L1-SUB-DRS-FSGS-W07-S8 L1-010-104 WEST PACKAGE: L1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:26:24PM 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 6 583.05 2.41660E-02 13. 77 F 11 1119.20 6. 05967E-03 26.55 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield{%) Activity NuclideMDA LineMDA Name (pCUgrams) (pCilgrams) (pCVgrams)

(keV)

+ K-40 1460.75

• 10.67 5.87E+OO 5.54E-01 5.54E-01

+ AR-41 1293.64 99.16 1. 43E+05 1.61E+06 1.61E+06

+ C0-60 1173.22 100.00 -l.86E-03 5.38E-02 5.83E-02 1332.49 100.00 2.18E-02 5.38E-02

+ KR-85 513.99 0.43 9.40E+OO 9.58E+OO 9.58E+OO

+ Y-88 898.04 93.70 2.94E-02 3.44E-02 5.12E-02 1836.06 99.20 -1. 02E-03 3.44E-02

+ NB-94 702.63 100.00 -1.86E-03 3.97E-02 3.97E-02 871.10 100.00 -6.0lE-02 4.24E-02

+ I-131 284.30 6.06 -4.42E-01 4.45E-02 5.88E-01 364.48 81. 20 -l.43E-02 4.45E-02 636.97 7.27 -9.84E-02 5.90E-01

+ CS-134 604.70 97.60 5.90E-02 4.71E-02 5. llE-02 7 95. 84 85.40 4.15E-03 4.71E-02

+ CS-137 661.65 85.12 9.49E-02 5.49E-02 5.49E-02

+ CE-144 80.12 1. 36 6.78E-01 2.65E-01 3.31E+OO

1/15/2019 2:26:33PM Page 6 of 6 Analysis Report for l 1-SUB-DRS-FSGS-W07-S8 l 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity NuclideMDA LlneMDA Name (pCi/grams) (pCilgrams) (pCilgrams)

(keV)

CE-1 4 4 133 . 51 11. 09 -1.93E - 02 2 . 65E - 0 1 2 . 65E- 01

+ EU- 152 121 . 78 28 . 40 -8.33E- 02 l . OOE-01 l. OOE -01 344 . 2 8 26 . 60 -1.6 9E -02 1 . 33 E- 01 1408.0 0 20.74 9.35E- 03 2.06E-01

+ EU -1 54 123 . 07 4 0 . 40 - 5.58E - 02 7.07E-02 7 . 07E-02 723.30 19.70 l . 52E - 0 1 2.27E- 01 1274 . 51 35.50 1. 91E- 02 1. 39 E- 01

+ EU-155 86 . 54 32.80 -1. 03E- 02 l.16E- Ol 1 . 16E- 0 1 105.31 21. 80 8.46E-02 1 .4 2E-01

+ BI-214 609 . 31

• 46. 30 l.23E- 0 1 8 . 23E-02 8 . 23E-0 2 112 0 .29 1 5.10 1. 22 E- 02 3 . 84 E- Ol 1238 . 11 5.94 - 3. 8 1E- 02 1. ll E+OO 1377. 67 4.11 3.69E- 01 1.18E+OO 140 7 . 98 2.48 7.82E-02 1.73E+OO 150 9 . 19 2.19 - 5.43E- 01 1 . 7 0E +OO 176 4.4 9 15.80 l. 53E-01 2.85E- 01

+ PB-214 77. 1 1 10 . 70 4. 44E- 01 1.02E- 01 4 . 52 E- Ol 295 . 21

• 19.20 l.62 E- 0 1 1.19E-0 1 351 . 92

• 37.20 6.51 E- 02 1. 02E -0 1

+ PA-228 89.95 22.00 6.90E- 0 1 4.05E - 01 6.9 4E- 01 93 . 35 35. 0 0 -3.47E- 0 1 4.0 5 E- 0 1 105 . 00 1 6.30 4.53E- Ol 8 . 0 lE- 01 12 9 . 22 2.97 4.49E- 0 1 4 . 13E+OO 338 . 32 5.30 1. 82 E+OO 2 . 71E+OO 46 3 .00 13 . 80 - 1.61E- 03 1.l OE+OO 911.23 16 . 70 1.56E+OO 1.53E+OO

+ AM-241 5 9 . 54 36.30 4 .2 1E- 02 2 . 12E- 0 1 2.12E-Ol

+ CM- 243 1 0 3 . 76 23.00 7.3 4E- 02 l . 36E- 0 1 1. 36E- 0 1 228 .18 1 0.60 4 . 97 E- 02 2.79E - 0 1 277 . 60 14 .00 1. 32E- 01 2.28E-O l

+ = 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

1/15/2019 2:27:14PM Page 1 of6

~~~~pex-Gamma Analysis Report for L 1-SUB-DRS-FSGS-W08-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FSGS-W08-S8 Sample Description  : L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 9.118E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 9:11 :00AM Acquisition Started  : 2/28/2018 3:19:30PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.8 seconds Dead Time  : 0.30 %

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100 - 4096 Peak Area Range (in channels)  : 100- 4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5349 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:27:05PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:27:14PM Page 2 of6 Analysis Report for L 1-SUB-DRS-FSGS-WOB-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 185.61 368 - 375 371 . 72 5.30E+01 30.16 4.21E+02 1. 27 F 2 238.51 469 - 485 477 . 50 2.80E+02 44.90 7 . 14E+02 1. 84 F 3 295.17 583 - 598 590.79 l . OOE+ 02 31. 65 4.01E+02 2.20 F 4 338.28 671 - 684 677.00 7.44E+Ol 26.33 2 . 38E+02 2.14 F 5 351.88 697 - 708 704.19 1.98E+02 33.82 2.01E+02 2.03 F 6 582.88 1160 - 1172 1166.10 7.86E+Ol 24 . 82 l . 36E+02 2 . 56 F 7 609 .1 8 1213 - 1 225 1218.69 l.12E+02 25.17 l.23E+02 1. 71 F 8 911.04 1817 - 1827 1822.32 3 . 89E+Ol 15.80 6 . 21E+Ol 1. 51 F 9 969 .11 1934 - 1944 1938 . 44 3 .4 1E+Ol 15.73 6.16E+Ol 1. 74 F 10 14 60.69 2915 - 2929 2921.48 4 .61E+02 43.57 2.47E+Ol 2. 48 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:27:05PM 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 1 185.61 5 . 30E+Ol 30.16 5.30E+Ol 3.02E+Ol F 2 238 . 51 2.80E+02 44 . 90 2 . 80£ +02 4.49E+Ol F 3 295.17 1. OOE+02 31.65 1. OOE+02 3.16E+Ol F 4 338.28 7.44E+Ol 26.33 7.44E+Ol 2.63E+Ol F 5 351.88 1.98E+02 33.82 8 . 36E+Ol 3 . 72E+Ol l.15E+02 5.03E+Ol F 6 582.88 7.86E+Ol 24.82 7.86E+Ol 2.48E+Ol F 7 609.18 l.12E+02 25.17 4.12E+Ol 2.42E+Ol 7. llE+Ol 3.49E+Ol F 8 911 . 04 3.89E+Ol 15.80 3.89E+Ol l.58E+Ol F 9 969 .11 3 .4 1E+Ol 15.73 3 .41E +Ol l.57E+Ol F 10 1460.69 4.61E+02 43.57 5.63E+Ol 1. 71E+Ol 4.04E+02 4.68E+Ol

=

M First peak in a multiplet region

=

m Other peak in a multiplet region

=

F Fitted singlet Errors quoted at 2.000sigma

1/15/2019 2:27:14PM Page 3 of6 Analysis Report for L 1-SUB-DRS-FSGS-WOS-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS 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) (pCilgrams) Uncertainty K-40 0.99 1460.75

• 10.67 4.83E+OO 6.20E-01 PB-212 0.55 77 .11 17.50 238.63

• 44.60 1. 58E-01 2.67E-02 BI-214 0.34 609.31

• 46.30 8.97E-02 4.44E-02 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 0.72 77 .11 10.70 295.21

• 19.20 1.58E-01 5.02E-02 351.92

• 37.20 1.09E- 01 4.79E-02 RA-226 0.94 186.21

• 3.28 3.42E-01 1. 96E-01 AC-228 0.61 209.28 4.40 338.32

• 11. 40 2.22E-01 7.93E-02 794.70 4.60 911. 60

• 27.70 1.18E-01 4.83E-02 964. 60 5.20 969 .11

• 16.60 l . 83E-01 8.47E-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 confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT

1/15/2019 2:27:14PM Page 4 of6 Analysis Report for L 1-SUB-DRS-FSGS-WOS-SB L 1-010-104 WEST PACKAGE: l 1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence (pCilgrams) Uncertainty K-40 0.999 4.83E+OO 6.20E-01 PB-212 0.559 1. 58E-Ol 2.67E-02 BI-214 0.348 8.97E-02 4.44E-02 PB-214 0. 721 1.32E-01 3.47E-02 RA-226 0.944 3.42E-01 1. 96E-Ol AC-228 0.613 1.53E-Ol 3.71E-02

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

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

1/15/2019 2:27:14PM Page 5 of6 Analysis Report for L 1-SUB-DRS-FSGS-WOS-SB U-010-104 WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:27:0SPM 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 6 582.88 2.18289E-02 15.80 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuclide MDA LineMDA Name (pCi/grams) (pCVgrams) (pCVgrams)

(keV)

+ K-40 1460.75

• 10.67 4.83E+OO 5.36E-01 5.36E-01

+ AR-41 1293.64 99.16 -2.53E+03 5 .11E+03 5 .11E+03

+ C0-60 1173.22 100.00 l.32E-02 5.22E-02 5.68E-02 1332.49 100.00 3.67E-02 5.22E-02

+ KR-85 513. 99 0.43 l.12E+Ol 9.12E+OO 9.12E+OO

+ Y-88 898.04 93.70 -l.59E-03 3.0SE-02 4.47E-02 1836.06 99.20 -3.23E-03 3.0SE-02

+ NB-94 702.63 100.00 -8.32E-03 3.65E-02 3.65E-02 871.10 100.00 9.32E-03 4.27E-02

+ I-131 284.30 6.06 2.51E-01 3.97E-02 5.31E-01 364.48 81. 20 1. 58E-02 3.97E-02 636.97 7.27 -l.63E-02 5.21E-Ol

+ CS-134 604.70 97.60 -1. 96E-02 4.40E-02 4.59E-02 795.84 85.40 6.31E-03 4.40E-02

+ CS-137 661.65 85.12 5.80E-02 5.lSE-02 5.15E-02

+ CE-144 80.12 1. 36 l.37E-01 2.41E-01 3.0lE+OO 133. 51 11. 09 -1. 06E-01 2.41E-01

1/15/2019 2:27:14PM Page 6 of6 Analysis Report for L 1-SUB-DRS-FSGS-WOB-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCilgrams) (pCi/grams) (pCi/grams)

(keV)

+ EU-152 121 . 78 28.40 -7.78E-02 9.34E-02 9 . 3 4E- 02 344.28 26.60 -3.18E-02 1.22E-01 140 8.00 20.74 1.08E-01 1. 85E -01

+ EU-154 123 .07 40.40 -4.20E-02 6 . 54E-02 6.54E-02 723.30 19. 70 -4.90E-02 1.84E-Ol 1274.51 35.50 1.22E-01 1.4 7E-01

+ EU-1 55 86.54 32 . 80 - 4.21E-02 1.07E-01 1. 07E-0 1 105 . 31 21. 80 5.73E-02 1.31E- Ol

+ BI - 214 609.31

• 46.30 8.97E-02 8 . llE-02 8. llE- 02 112 0. 29 15.10 2.57 E- 0 1 3.64E-01 1238 .11 5.94 6.69E- 01 1. 05E+OO 1377.67 4 .11 -5.76E- 01 9. 15E-01 14 07.98 2.48 9 .00 E-01 1 . 54E+OO 15 09.19 2.19 - 5 . 24E-0 1 1.47E+OO 1764.49 15.80 1 . 84E-01 3 . 04E-01

+ PB-214 77 . 11 10.70 l.33E - 01 8.43E-02 4.06E-01 295 . 21

• 1 9 . 20 1. 58E-01 1 .31 E-01 351.92

• 37.20 1.0 9E-01 8 .4 3E-02

+ PA-228 89.95 22.00 1.59E-01 2 . 39E-0 1 4.05E-Ol 93 . 35 35.00 -6.20E-02 2.39E-01 105.00 16.30 2 . 90E-0 1 4.64E-01 129. 22 2.97 4.22E- 01 2 .34E+OO 338 . 32 5.30 6 . 31E-01 1.52E+OO 463.00 1 3.80 2 . 55 E-01 6 . 27E-0 1 911.23 16.70 4.62E -0 1 7.75E-01

+ AM- 2 41 59.54 36.30 -4. llE-02 1.91E-01 1.91E-01

+ CM-243 103.76 23.00 7.22E-02 1.27E-01 1 .27 E-01 228 . 18 10.60 -1.04E-01 2.56E-01 277.60 14.00 -4.82E-0 2 2. 1 2E-0 1

+ = 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

1/15/2019 2:27:54PM Page l of7

~~ ~~pex-Gamma Analysis Report for l 1-SUB-DRS-FSGS-W09-SB L1-010-104 WEST PACKAGE: l 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : l 1-SUB-DRS-FSGS-W09-S8 Sample Description  : l1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 9.613E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 9:06:00AM Acquisition Started  : 2/28/2018 7:43:47PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli live lime  : 3600.0 seconds Real Time  : 3610.6 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  : 5350 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:27:45PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:27:54PM Page 2 of 7 Analysis Report for L 1-SUB-DRS-FSGS-W09-S8 L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 185.81 365 - 376 372 .11 5.88E+ Ol 29. 00 7.12E+02 0.97 F 2 238.60 473 - 485 4 77 . 68 3 .13E+02 46.52 5 . 60E+02 1. 94 F 3 295.05 585 - 595 590.55 1.06E+02 30 . 03 2. 7 8E+02 1. 69 F 4 338.21 672 - 68 0 676 . 86 5 . 90E+Ol 23 . 35 1.98E+02 1. 31 F 5 582 . 89 1159 - 1171 1166.12 8.92E+Ol 24 . 34 1. 33E+02 2 . 03 F 6 60 8 . 98 1210 - 1227 1218 . 30 l . 19E+02 25 . 92 1. 41E+02 2.21 F 7 911 .0 3 1816 - 1 8 27 1822 . 29 5. 4 3E+ Ol 19 . 71 7.80E+Ol 2.21 F 8 1119.93 2236 - 22 4 6 22 4 0.0 4 2.54 E+ Ol 13 . 15 5 .74E+Ol 1.23 F 9 1 460.69 2914 - 2930 292 1.4 9 4. 80E+02 44 .0 7 8.50E+OO 2.6 9 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:27:45PM 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 1 185 . 81 5 . 88 E+Ol 29 .0 0 5.88E +O l 2.90E+Ol F 2 238 . 60 3.13E+02 46.52 3 . 13E+0 2 4 . 65E +O l F 3 295.05 l .06E+02 30 . 03 l . 06E+02 3.00E+Ol F 4 338 . 2 1 5 . 90E+Ol 23 . 35 5.90E+Ol 2.33E+Ol F 5 582 . 89 8 . 92E+Ol 24 . 34 8 . 92E+Ol 2 . 43E+Ol F 6 608.98 l . 19E+02 25.92 4.12E+Ol 2 . 42E+Ol 7.83E+O l 3 . 55E+Ol F 7 911. 03 5 .4 3 E+Ol 19 . 71 5 . 43E+ Ol l . 97 E+Ol F 8 1119 . 93 2 . 5 4 E+ Ol 13 . 15 2.54E+Ol 1 .32E+Ol F 9 1 4 60.69 4.80E+ 0 2 4 4 .07 5.63E+Ol 1 . 71E+Ol 4 . 2 4E +02 4.73E+Ol

=

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

=

F Fitted singlet Errors quoted at 2.000sigma

1/15/2019 2:27:54PM Page 3 of 7 Analysis Report for L 1-SUB-DRS-FSGS-W09-S8 L 1-010-104 WEST PACKAGE: L 1-SUB-DRS 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) (pCi/grams) Uncertainty K-40 0.99 1 460.75

• 10.67 4.80E+OO 5 . 98 E- 0 1 PB- 212 0.56 77 . 11 1 7.50 238 . 63

• 44.60 1. 68E - 01 2.64E - 02 BI - 214 0.57 609 . 31

• 46 . 30 9.37E - 02 4.28E - 02 1120.29

• 15. 1 0 1. 61E - 01 8.39E - 02 1238 .11 5.94 1377 . 67 4 . 11 1 4 07 .98 2 . 48 1509.19 2.19 1764.49 15.80 RA- 226 0.97 1 86.21

• 3.28 3 . 61E - 01 1. 79E - 01

• =Energy line found in the spectrum.

- =Manually added nuclide.

? =Manually edited nuclide.

@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)

K- 40 0.999 4.80E+OO 5.98E- 01 PB- 212 0.560 1 . 68E- 01 2.64E- 02 BI - 214 0.573 1. 08E- 01 3.81E- 02 RA- 226 0.974 3.61E- 01 1.79E- 01

1/15/2019 2 :27:54PM Page4 of7 Analysis Report for L 1-SUB-DRS-FSGS-W09-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS

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

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

1/15/2019 2:27:54PM Page 5 of7 Analysis Report for L1-SUB-DRS-FSGS-W09-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:27:45PM 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 3 295.05 2.95581E-02 14 .11 Tol. PB-214 F 4 338.21 1.63809E-02 19.79 Tol. AC-228 PA-228 F 5 582.89 2.47886E-02 13.64 F 7 911. 03 l.50814E-02 18.15 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 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA Line MDA Name (pCilgrams) (pCi/grams) (pCilgrams)

(keV)

+ K-40 1460.75

• 10.67 4.80E+OO 4.77E-01 4.77E-01

+ AR-41 1293.64 99.16 -1.10E+04 2.74E+04 2.74E+04

+ C0-60 1173.22 100.00 6.65E-02 5.13E-02 5.88E-02 1332.49 100.00 3.60E-02 5.13E-02

+ KR-85 513.99 0.43 1. 04E+01 8.56E+OO 8.56E+OO

+ Y-88 898.04 93.70 2.22E-02 2.90E-02 4.28E-02 1836.06 99.20 4.09E-03 2.90E-02

+ NB-94 702.63 100.00 l.lOE-02 3.61E-02 3.61E-02 871.10 100.00 -l.29E-02 3.61E-02

+ I-131 284.30 6.06 l.95E-02 3.82E-02 5 .13E-01

1/15/2019 2:27:54PM Page 6 of7 Analysis Report for L1-SUB-DRS-FSGS-W09-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity Nuclide MDA LineMDA Name (pCi/grams) (pCilgrams) (pCUgrams)

(keV)

I - 131 364 . 48 8 1. 20 2 .74E-03 3 . 82E- 02 3.82E- 02 636.97 7.27 -2.25E- 01 5 . 19E-O l

+ CS-134 604.70 97.60 1.21E- 03 4 .4 0E-02 4.40E- 0 2 795.84 85.40 4.35E - 03 4.43E- 02

+ CS-137 661.65 85. 12 6.83E - 02 5 . 00 E- 02 5 . 00 E- 02

+ CE-14 4 80 . 12 1. 36 1 .23E+OO 2 . 34E-01 2.97E+OO 133 . 51 11. 09 - 4 . 53E- 02 2.34E- 0 1

+ EU-152 121. 78 28. 4 0 - 4 . 82E-0 2 8 . 97E- 02 8.97E- 02 34 4 .28 26.60 - 3 . 98 E-Ol 1. 1 8E- Ol 1 4 08 . 00 20.74 7. 68E-0 2 1 . 69E-Ol

+ EU-15 4 1 23.07 40 . 40 -9.39E- 0 3 6 . 33E- 02 6.33E-02 723.30 19.70 - 4.21E-0 3 1.9 0E- 01 1274.51 35 . 50 -5.3 9E -02 1.30E-0 1

+ EU- 1 55 86 . 5 4 32 . 80 - 1. 31E- 02 1. 06E - 0 1 1. 0 6E-01 105 . 3 1 21. 80 -1. 02E - 0 1 1. 24E-01

+ BI- 2 1 4 609 . 3 1

• 4 6 . 30 9 . 37 E- 02 8.39E- 02 8.39E-02 1120 . 29

• 15.10 1.61E- Ol 1 .90E - 0 1 1238 .11 5.94 1.32E+OO 1. 09E+OO 1377. 67 4 .11 9.09E- 02 1 . 0lE+OO 14 07.98 2 .4 8 6 . 42E -0 1 l. 41E+OO 1 509 .1 9 2.19 - 9 . SOE- 0 2 1. 58E+OO 1764 . 49 15 . 80 1.06E-01 2 .4 5E- 01

+ PB-214 77 .11 1 0 . 70 5.57E-0 1 8.8 1E-02 4 . 0 4E-O l 295.21 19.20 9.07E- 02 l . 57 E- 01 35 1. 92 37.2 0 9 . 77E-02 8 . 8 1E- 02

+ PA- 228 89 . 95 22.00 8 . 34E- 01 2 . 74E- Ol 4 . 69E-0 1 93.35 35.00 6 .0 9E-02 2.74E- Ol 1 0 5.0 0 16 . 30 -7 . 51E- 02 5 . 06E- 0 1 129.22 2 . 97 6 . 95E-0 1 2 . 6 0E+OO 338.32 5 . 30 l .O lE+ OO 1. 72E+OO 463 . 00 13.80 - 1 . 69E-02 6.80E-Ol 91 1. 23 16 . 70 l.57E+OO 9 . 17E- 01

+ AM-24 1 59.5 4 36 . 30 5.59E - 02 1 . 92E-01 1.92E- Ol

+ CM-243 1 0 3 . 76 23.00 6 . 37 E- 02 1 . 20E- 01 1 . 20E - 0 1 228 . 18 10 . 60 - 3 . 50E - 03 2.47E-01 277.60 14 .00 3.lO E-02 2.00E - 0 1

+ = 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

1/15/2019 2:27:54PM Page 7 of7 Analysis Report for L 1-SUB-DRS-FSGS-W09-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS

1/15/2019 2:28:36PM Page 1 of6

~~~~pex-Gamma Analysis Report for L1-SUB-DRS-FSGS-W10-SB U-010-104 WEST PACKAGE: L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L1-SUB-DRS-FSGS-W10-SB Sample Description  : L1-010-104 WEST PACKAGE: L1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8.879E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 9:02:00AM Acquisition Started  : 2/28/2018 8:53:44PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3611.2 seconds Dead Time  : 0.31 %

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  : 5352 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:28:27PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:28:36PM Page 2 of6 Analysis Report for L 1-SUB-DRS-FSGS-W10-SB U-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.86 147 - 158 154.26 1. 24E+02 48 . 06 l . 12E+03 1. 84 F 2 186. 12 369 - 377 372.73 6.34 E+O l 32 . 90 4.96E+02 1. 43 F 3 238.54 471 - 485 477.55 2.77E+02 42 . 96 6 . 42E+02 1. 56 M 4 295.19 586 - 603 590.82 5.25E+Ol 21.12 l . 70E+02 0.81 m 5 299 . 65 586 - 603 599.75 2 . 61E+Ol 16.38 1.69E+02 0.81 F 6 338 . 25 672 - 680 67 6 . 94 3.94E+Ol 21 . 98 2.29E+02 1.18 F 7 351. 7 6 699 - 709 703.95 1.94E+02 34 . 43 2 . 05E+02 1. 98 F 8 582 . 97 1158 - 1171 1166.28 7 . 4 2E+O l 22 .34 1 . 67E+02 1. 46 F 9 609 . 32 1213 - 1225 1218.97 1. 20E+02 26.03 l . 15E+02 1. 95 F 10 911.50 1817 - 1828 1823 .23 5.13E+Ol 16 . 70 5 . 08E+Ol 1. 51 F 11 969 . 12 1932 - 1943 1938 .4 6 3 . 43E+Ol 16.12 6 . 79E+Ol 2 .06 F 12 1460 . 65 2914 - 2929 2921 . 41 5.03E+02 45 . 53 2 . 71E+Ol 2 . 51 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/ 15/201 9 2:28:27PM 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 76.86 1. 24E+02 48.06 1 . 24E+02 4 . 81E+Ol F 2 186.1 2 6.34E+Ol 32.90 6 .34E+Ol 3 . 29E+Ol F 3 238.54 2 . 77E+02 42 . 96 2 . 77E+02 4.30E+Ol M 4 295.19 5 . 25E+Ol 21.12 5.25E+Ol 2 . llE+Ol m 5 299.65 2 . 61E+Ol 16.38 2 . 61E+Ol 1 . 64E+Ol F 6 338 . 25 3 . 94E+Ol 21. 98 3 .94E+Ol 2 . 20E+Ol F 7 351.76 1.94E+02 34 . 43 8.36E+Ol 3 . 72E+ Ol l.10E+02 5 . 07E+Ol F 8 582.97 7.42E+Ol 22.34 7 . 42E+Ol 2 . 23E+Ol F 9 609 . 32 1. 20E+02 26 . 03 4.12E+Ol 2.42E+Ol 7 .91E+ Ol 3 . 56E+Ol F 10 911. 50 5 . 13E+Ol 16.70 5 . 13E+Ol 1 . 67E+01 F 11 969 . 12 3 . 43E+Ol 16 . 12 3 .43E+O l 1 . 61E+Ol F 12 1460.65 5 . 03E+02 45.53 5 . 63E+Ol 1 . 71E+Ol 4.47E+02 4.86E+Ol

1/15/2019 2:28:36PM Page 3 of6 Analysis Report for L 1-SUB-DRS-FSGS-W10-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCi/grams) Uncertainty K-40 0.99 1460.75

• 10.67 5.48E+OO 6.70E-Ol PB-212 0.99 77 .11

• 17.50 l.98E-01 7.77E-02 238.63

• 44.60 l.61E-Ol 2.63E-02 BI-214 0.35 609.31

• 46.30 1. 03E-01 4.65E-02 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 0.99 77 .11

• 10.70 3.24E-01 l.27E-01 295.21

• 19.20 8.46E-02 3.43E-02 351.92

• 37.20 l.07E-Ol 4. 96E-02 RA-226 0.99 186.21

• 3.28 4.21E-Ol 2.20E-01 AC-228 0.63 209.28 4.40 338.32

• 11. 40 l.21E-Ol 6.76E-02 794.70 4.60 911. 60

• 27.70 l.60E-01 5.26E-02 964. 60 5.20 969 .11

• 16.60 l.89E-Ol 8.91E-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 confidence index threshold = 0.30 Errors quoted at 2.000sigma

1/15/2019 2:28:36PM Page 4 of6 Analysis Report for L 1-SUB-DRS-FSGS-W10-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)

K-40 0.998 5.48E+OO 6.70E-01 PB-212 0.996 1.59E-01 2.SOE-02 BI-214 0.350 1.03E-01 4.65E-02 PB-214 0. 996 9.0SE-02 2 .76E-02 RA-226 0.999 4.21E-01 2 . 20E-Ol AC-228 0 .63 2 1. 53E-01 3.76E-02

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

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

1/15/2019 2:28:36PM Page 5 of6 Analysis Report for L1-SUB-DRS-FSGS-W10-SB U-010-104 WEST PACKAGE: L1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:28:27PM 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 5 299.65 7. 25134E-03 31. 38 F 8 582.97 2.06042E-02 15.06 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield{%) Activity Nuc/ideMDA LineMDA Name (pCl/grams) (pCVgrams) (pCUgrams)

(keV)

+ K-40 1460.75

• 10.67 5.48E+OO 5.59E-01 5.59E-01

+ AR-41 1293.64 99.16 3.08E+04 4 .98E+04 4.98E+04

+ C0-60 1173.22 100.00 1.lSE-02 5.14E-02 6.06E-02 1332.49 100.00 5.79E-02 5.14E-02

+ KR-85 513.99 0.43 1.19E+Ol 9 . 28E+00 9.28E+OO

+ Y-88 898.04 93.70 3.99E-02 3.14E-02 4.72E-02 1836.06 99.20 -1.91E-02 3.14E-02

+ NB-94 702.63 100.00 3.73E-02 3.91E-02 3.91E-02 871.10 100.00 -6.33E-02 4.0lE-02

+ I-131 284.30 6.06 -3.98E-02 4.21E-02 5.65E-01 364.48 81. 20 7.08E-03 4.21E-02 636.97 7.27 -1.79E-01 5.59E-01

+ CS-134 604.70 97.60 -l.02E-02 4.61E-02 4.76E-02 795.84 85.40 -1.49E-02 4.61E-02

1/15/2019 2:28:36PM Page 6 of6 Analysis Report for L 1-SUB-DRS-FSGS-W10-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity Nuc/ideMDA LlneMDA Name (pCilgrams) (pCilgrams) (pCi/grams)

(keV)

+ CS -1 37 661. 65 85 . 12 5 . 41E-02 5 . 46E-02 5 . 46E-02

+ CE-144 80.12 1. 36 -2.00E+OO 2.52E-01 3 .1 8E+OO 133.51 11. 09 -4 . 88E-02 2 . 52E-01

+ EU-1 52 12 1. 78 28 .4 0 -4.lOE-02 9.91E-02 9 . 91E-02 344.28 26 . 60 - l . 69E-01 l . 30E-01 1408.00 20 . 74 8 . 93E-02 2 . 14E-01

+ EU-154 123.07 40.40 3 . 78E- 02 7.07E - 02 7 . 07E - 02 723 . 30 19 . 70 1.55E-01 2 . 02E-01 1274.51 35.50 1.91E- 02 1.49E- 01

+ EU-155 86.54 32.80 -4.51E-03 1 . 13E-01 l .1 3E-01 105.31 21. 80 1 . 65E- 02 1 . 38E-01

+ BI -21 4 609.3 1

• 46 . 30 1. 03E-01 8 . 21E-02 8 . 21E-02 1120.29 15 .10 1.28E- 01 3.56E- 01 1238 .11 5.94 1.19E- 01 1.02E+00 1377 . 67 4 . 11 4 . 82E- 01 1. 07E+OO 1407.98 2.48 7 . 47E- 01 1. 7 9E+OO 1509.19 2.19 - 7 . 65E-01 1. 45E+OO 1764.49 15.80 3 . 20E-01 2.86E-01

+ PB-214 77 .11

• 10 . 70 3 . 24E-0 1 7.35E-02 3 . 29E-01 295.21

• 19 . 20 8 . 46E- 02 7 .3 5E-0 2 351 . 92

• 3 7 . 20 1.07E- 01 8.5 7E-02

+ PA-228 89.95 22.00 6 . 09E-01 2.98E-01 5 .1 2E-01 93.35 35 . 00 -4 . 99E-02 2 . 98E- 0 1 105.00 16 . 30 1. 4 lE-01 5 . 84E-01 129.22 2.97 1. 53E+OO 2 . 99E+OO 338.32 5 . 30 9 . 67 E-01 1 . 9 7 E+O O 463.00 13 . 80 - 4.79E-01 7 .33E-01 911. 23 16.70 1. 06E+OO 9 . 66E-01

+ AM-241 59 . 54 36 . 30 2 . 45E-02 2.02E-0 1 2.02E-01

+ CM-243 103 . 76 2 3 . 00 5 . 66E-02 1 . 32E-01 l.32E-01 228. 1 8 10.60 -7.56E-03 2 . 59E-01 277.60 14 .00 4 . 55E-02 2.21E-01

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = MDA value not calculated

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

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

1/15/2019 2:29:14PM Page I of6

~~~~pex-Gamma Analysis Report for L 1-SUB-DRS-FSGS-W11-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FSGS-W11-SB Sample Description  : L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8.713E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 8:55:00AM Acquisition Started  : 2/28/2018 10:27:29PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live lime  : 3600.0 seconds Real lime  : 3610.9 seconds Dead lime  : 0.30 %

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100-4096 Peak Area Range (in channels)  : 100 - 4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5353 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:29:05PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:29:14PM Page 2 of 6 Analysis Report for L 1-SUB-DRS-FSGS-W11-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 75.93 1 47 - 162 152 . 40 2.15E+02 60. 66 1. 47E+03 3 . 67 F 2 238 . 61 470 - 48 5 477.70 2 . 66E+ 02 45.37 7.64 E+02 1. 90 F 3 295. 16 583 - 595 5 9 0.77 8 . 34 E+Ol 29.00 3 . 71E+02 1. 63 F 4 35 1. 95 698 - 708 704 . 33 1. 4 8E+ 02 30 . 57 2 . 07E+02 1. 82 F 5 582.78 1160 - 11 73 1165.91 8.38E+ Ol 24.30 1 .41E+02 2 . 35 F 6 609.25 1 21 0 - 1227 1218 . 83 1 . 35E+ 0 2 26. 54 1. 4 7E+02 1. 75 F 7 661 . 30 13 1 5 - 132 9 1322 . 92 1. 0 7E+ 0 2 25.36 1 .54E+02 1. 75 F 8 91 1.20 18 1 7 - 1828 1822.65 5 . 62E+ Ol 18 . 38 7 . 48E+Ol 1. 62 F 9 1120 . 70 223 7 - 22 4 6 224 1. 57 1 . 86E+Ol 11. 72 5.32E+O l 1. 10 F 10 1332.89 2662 - 267 1 2665.91 1. 56E+ Ol 10 . 0 1 2. 77E+O l 1. 19 F 11 1460 . 63 29 1 3 - 293 0 2921.37 4. 90 E+0 2 44. 71 2.08E+O l 2. 6 4 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:29:05PM 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 75.93 2 . 15E+02 60.66 2.15E+0 2 6. 0 7 E+O l F 2 238.61 2.66E+ 02 45 . 37 2.66E+0 2 4 .54E+Ol F 3 295 . 16 8.34E+Ol 29 . 00 8 . 34 E+Ol 2.90E+ Ol F 4 351.95 1. 48E+02 30.57 8 . 36E+Ol 3.72E+Ol 6.43E+Ol 4 . 82E+ Ol F 5 582.78 8.38E+O l 2 4 .30 8.38E+Ol 2.43E+Ol F 6 609 . 25 1. 35E+02 26.54 4 . 12E+Ol 2 .4 2E+Ol 9.43E+Ol 3.59E+Ol F 7 661. 30 1 .07E+ 02 25.36 6 . 61E+Ol 2 . 5 4E+Ol 4 .13E+Ol 3.59E+Ol F 8 911. 20 5.62E +Ol 18 . 38 5 . 62E+Ol 1.84E+ Ol F 9 1120 . 70 1. 86E+O l 11. 72 1 .86E+ Ol 1. 1 7E+ Ol F 10 1 332 . 89 1. 56E+ Ol 10 . 0 1 1. 56E+Ol 1 . 00E+ Ol F 11 1460.63 4.90E+ 02 4 4 .7 1 5 . 63E+ Ol 1.71E+Ol 4.3 4E+ 02 4 . 79E+ Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma

1/15/2019 2:29:14PM Page 3 of6 Analysis Report for L 1-SUB-DRS-FSGS-W1 1-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS 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) (pCi/grams) Uncertainty K- 40 0.99 1 4 60 . 75

• 10.67 5. 43E+OO 6 . 70£-01 CS - 137 0.98 661 . 65

• 85 . 12 3.20E- 02 2 . 79£ -02 PB- 212 0.56 77 . 11 17 . 50 238 . 63

• 44.60 1. 58E- 01 2 . 81E - 02 BI - 21 4 0.58 609 . 31

• 46 . 30 1. 25E - 01 4.80E - 02 1120.29

• 1 5 . 10 1. 30E- 01 8 . 25 E- 02 1238 .11 5.94 1377 . 67 4 .11 1407.98 2 . 48 1509 . 19 2 . 19 1764. 4 9 15.80 PB-21 4 0 . 72 77 .11 10.70 295 . 21

• 19.20 1.37E- Ol 4 . 81E- 02 351 . 92

• 3 7 .20 6 . 38E- 02 4 . 79E- 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 confidence index threshold 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence (pCi/grams) Uncertainty

1/ 15/2019 2:29:14PM Page 4 of6 Analysis Report for L 1-SUB-DRS-FSGS-W11-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K-4 0 0 .9 98 5 .4 3E+ OO 6 . 70 E- 01 CS - 137 0 . 98 1 3.20E- 02 2.79E- 02 PB- 212 0 . 560 l.58E- 01 2.81 E- 02 BI-214 0.5 80 1. 2 6E-01 4.15E- 02 PB- 214 0 . 721 1. OO E- 01 3 . 39E - 02

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

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

1/15/2019 2:29:14PM Page 5 of6 Analysis Report for L 1-SUB-DRS-FSGS-W11-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:29:0SPM Peak Locate From Channel  : 100 Peak Locate To Channel  : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 75.93 5. 96811E-02 14.12 F 5 582.78 2. 32722E-02 14.50 F 8 911.20 l.56134E-02 16.35 Tol. AC-228 PA-228 F 10 1332.89 4.32689E-03 32.14 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCUgrams) (pCl/grams) (pCi/grams)

(keV)

+ K-40 1460.75

• 10.67 5.43E+OO 5.57E-01 5.57E-01

+ AR-41 1293.64 99.16 4.96E+04 1. 02E+05 1. 02E+05

+ C0-60 1173.22 100.00 4.64E-02 5.00E-02 5.73E-02 1332.49 100.00 2.75E-02 5.00E-02

+ KR-85 513.99 0.43 7.83E+OO 9.62E+OO 9.62E+OO

+ Y-88 898.04 93.70 -3.49E-02 3.41E-02 4.37E-02 1836.06 99.20 -l.84E-03 3.41E-02

+ NB-94 702.63 100.00 -2.17E-02 3.86E-02 3.86E-02 871.10 100.00 -2.80E-02 4.05E-02

+ I-131 284.30 6.06 -1.29E-01 4.22E-02 5.74E-01 364.48 81. 20 1.58E-02 4.22E-02 636.97 7.27 6.85E-03 5.90E-01

1/15/2019 2:29:14PM Page 6 of6 Analysis Report for L1-SUB-DRS-FSGS-W11-SB L1-010-104 WEST PACKAGE: L1-SUB-DRS Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCi/grams) (pCi/grams) (pCilgrams)

(keV)

+ CS-134 604 . 70 97.60 -1.45E-03 5.19E-02 5.19E- 02 795 . 84 85.40 2 . 02E-02 5 . 45E-02

+ CS - 137 661.65

• 85.12 3.20E-02 5 .62E-02 5.62E- 02

+ CE-144 80.12 1. 36 -6.37E-0 1 2.62E-01 3.28E+OO 133. 51 11. 09 8.42E-02 2.62E-Ol

+ EU- 152 1 2 1 .78 28.40 -1.09E-01 9.70E-02 9 . 70E -02 344.28 26.60 7.54E- 02 1.30E-01 14 08.00 20 . 74 - 2.76E- 03 2 . 09E-01

+ EU-154 123.07 40.40 -5. 72E-02 6.87E-02 6.87E-02 723.30 19.70 1.56E-01 2 . 08E-Ol 1274.51 35.50 7 . 91E-02 1.40E-01

+ EU- 1 55 86 . 54 32.80 2 . 85E-02 1.1 7E-01 l.17E-01 105.31 21. 80 -2 .08E-02 1 . 37E-Ol

+ BI - 214 609.31

• 46 . 30 1.25E- 01 9 . 34E-02 9.34E-02 1120 . 29

• 15.10 1.30E-01 1.99E-01 1238 .11 5.94 -2.82E - 01 1.07E+OO 1377.67 4 .11 -2 . 40E-01 8.83E-01 1407.98 2.48 -2.31E-02 1. 75E+OO 1509.19 2.19 - 3.49E-01 1 . 77E+OO 1764. 4 9 15.80 1. 24E-0 1 2 . 70 E-01

+ PB-214 77.11 10.70 6.44E-Ol 8.78E-02 4.42E-01 295 . 21

• 19 . 20 1 . 37E-01 1. 24E-01 351. 92

• 37.20 6.38E-02 8.78E-02

+ PA-228 89 .9 5 22.00 5.25E-01 3.22E- 01 5.56E-Ol 93 . 35 35 .0 0 -9 .13E-02 3 . 22E-01 105.00 16.30 -1.55E-01 6 .05E-01 129.22 2.97 1.59E+OO 3 . 17E+OO 338.32 5 . 30 4.78E-01 2.07E+OO 463.00 13. 80 5 . 69E-Ol 8.77E-01 911 . 23 16.70 1. 35E+OO 1.06E+OO

+ AM-241 59 . 54 36.30 5.75E-02 2.06E-01 2 . 06E-01

+ CM-243 103. 76 23.00 -1.68E-02 1.30E-01 1.30E- 01 228.18 10.60 -1.52E-01 2.68E-01 277.60 14.00 -1.42E-01 2.22E-Ol

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = MDA value not calculated

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

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

1/15/2019 2:29:55PM Page 1 of?

~Jti§"~pex-Gamma Analysis Report for L1-SUB-DRS-FSGS-W12-SB L1-010-104 WEST PACKAGE: L1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L1-SUB-DRS-FSGS-W12-SB Sample Description  : L1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 7.419E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 8:48:00AM Acquisition Started  : 3/1/2018 7:20:30AM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live lime  : 3600.0 seconds Real lime  : 3610.8 seconds Dead Time  : 0.30%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100 - 4096 Peak Area Range (in channels)  : 100 - 4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5354 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:29:46PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:29:55PM Page 2 of7 Analysis Report for L 1-SUB-DRS-FSGS-W12-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts {keV)

F 1 75.53 14 7 - 159 1 5 1. 60 2.33E+02 56 . 69 l .06E+03 3.86 F 2 238.38 471 - 481 477.23 l . 75E+02 39.21 5.87E+ 02 1. 36 F 3 295.14 582 - 595 590.73 l.14E+02 30.82 3 . 33E+02 1. 86 F 4 338.42 673 - 681 677.27 3.71E+O l 19 .61 2.08E+02 0.99 F 5 351.94 695 - 712 7 04. 30 l . 99E+02 33.93 2.76E+02 2 . 08 F 6 583 .10 1160 - 11 74 1166.54 6.73E+ Ol 21.15 1. 31E+02 1. 81 F 7 609 .13 1212 - 1227 1218.59 1.34E+02 26.39 l.06E+02 2 .15 F 8 661 . 62 1318 - 1330 1 323.56 1.24E+02 26 . 27 9.95E+Ol 2 .11 F 9 969 . 21 1934 - 1944 1938.65 2 .8 0E+Ol 14.20 6.29E+Ol 1. 41 F 10 1119 . 78 2233 - 2246 2239.75 3.94E+Ol 17 .4 7 7.19E+O l 2 .4 2 F 11 1 4 60 . 61 2913 - 2928 2921.33 3 .5 6E+02 38.39 2 .4 5E+Ol 2.53 F 12 1763 . 81 3523 - 3533 3527 . 68 2.73E+ Ol 11. 06 5.9 4E+OO 2.51 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:29:46PM 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 75.53 2.33E+02 56.69 2 . 33E+02 5 . 67E+Ol F 2 238.38 1.7 5E+02 39.21 1. 75E+02 3.92E+Ol F 3 295.14 1.14E+02 30.82 1 . 14E+02 3 . 08E+Ol F 4 338.42 3.71E+Ol 19.61 3.71E+Ol 1. 96E+Ol F 5 351.94 1.99E+02 33.93 8 . 36E+O l 3.72E+Ol 1 . 16E+02 5 .04 E+Ol F 6 583.10 6.73E+Ol 21.15 6.73E+Ol 2 . llE+ Ol F 7 609.13 1.34E+02 26.39 4.12E+Ol 2.42E+Ol 9.24E+O l 3.58E+Ol F 8 661. 62 1. 24E+02 26.27 6.61E+Ol 2.54E+Ol 5.79E+O l 3.65E+Ol F 9 969 . 21 2.80E+ Ol 14 . 20 2.80E+ Ol 1. 42E+Ol F 10 1119. 78 3.94E+Ol 17.47 3.94E+ Ol l.7 5E+O l F 11 1460.61 3.56E+02 38 . 39 5.63E+Ol 1.71E+Ol 2.99E+02 4 . 20E+O l F 12 1763 . 81 2.73E+Ol 11. 06 1.52E+Ol 9.80E+OO 1.21E+Ol 1.48E+Ol

1/15/2019 2:29:55PM Page 3 of7 Analysis Report for L 1-SUB-DRS-FSGS-W12-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCilgrams) Uncertainty K-40 0.99 1460.75

• 10 . 67 4.40E+OO 6.64E - Ol CS-137 1. 00 661 .65

• 85 . 12 5 . 27E- 02 3.34E- 02 PB- 212 0 . 55 77 .11 17.50 238 . 63

• 44 . 60 l.21E-Ol 2.80E-02 BI - 214 0. 76 609 . 31

• 46 . 30 1.43E- 01 5.62E - 02 1120.29

• 1 5.10 3.25E- 01 l. 4 5E - 01 1238 .11 5 . 94 1377.67 4 .11 1407 . 98 2 . 48 1509.19 2.19 1764 . 49

• 15.80 l. 4 0E-01 1 . 72E- 01 PB-21 4 0 . 72 77 . 11 10.70 295.21

• 19.20 2 . 19E- 01 6 . 04E- 02 351 . 92

• 37 . 20 l.35E - 01 5 . 90E- 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 confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT

1/ 15/2019 2:29:55PM Page 4 of7 Analysis Report for L 1-SUB-DRS-FSGS-W12-SB L1 -010-104 W EST PACKAGE: L1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)

K- 40 0 . 997 4 . 40E+OO 6.64E - 01 CS - 137 1 . 000 5.27E-02 3.34E-02 PB- 212 0 . 553 1. 21E - 01 2.80E - 02 BI - 214 0.766 1.65E- 01 5.0lE- 02 PB- 214 0 . 721 1.76E-01 4.22E - 02

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

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

1/15/2019 2:29:55PM Page 5 of7 Analysis Report for L1-SUB-DRS-FSGS-W12-SB U-010-104 WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:29:46PM Peak Locate From Channel  : 100 Peak Locate To Channel  : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 75.53 6.48268E-02 12.15 F 4 338.42 1.03000E-02 26.45 Tol. AC-228 PA-228 F 6 583.10 1.87075E-02 15.70 F 9 969.21 7.76670E-03 25.39 Tol. AC-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield{%) Activity NuclideMDA LineMDA Name (pCl/grams) (pCi/grams) (pCilgrams)

(keV)

+ K-40 1460.75

• 10.67 4.40E+OO 6.64E-01 6.64E-01

+ AR-41 1293.64 99.16 -1.99E+06 2.92E+06 2. 92E+06

+ C0-60 1173.22 100.00 4.51E-02 5.83E-02 7.54E-02 1332.49 100.00 3.71E-02 5.83E-02

+ KR-85 513.99 0.43 1.34E+Ol 1.05E+Ol 1. 05E+Ol

+ Y-88 898.04 93.70 -1. 36E-03 4.45E-02 5.46E-02 1836.06 99.20 6.83E-03 4.45E-02

+ NB-94 702.63 100.00 2.52E-02 4.63E-02 4.63E-02 871.10 100.00 -1.65E-02 4. 96E-02

+ I-131 284.30 6.06 -8.36E-02 4.99E-02 6.40E-01 364.48 81. 20 2.89E-02 4.99E-02

1/15/2019 2:29:55PM Page 6 of7 Analysis Report for L 1-SUB-DRS-FSGS-W12-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCilgrams)

(keV)

I-131 636.97 7.2 7 2.06E- 01 4.99E- 02 6 . 97E-01

+ CS - 134 604.70 97 . 60 - 5 . 91E-03 5 .4 2E- 02 5 . 63E-02 795.84 85 .40 9 . 41E-03 5 . 42E-02

+ CS -1 37 661.65

• 85 .12 5.27 E- 02 5.92E -02 5.92E-02

+ CE-144 80.12 1. 36 -1.65E+OO 2.94E - 01 3 . 73E+OO 133.51 11. 09 -1. 95E-02 2 . 9 4E- 0 1

+ EU-152 121.7 8 28 .4 0 4.38E-02 1 .1 5E - Ol l.15E-01 344.28 26 . 60 -6.61E-02 1.45E-01 1408.00 20 . 7 4 - 2 . 66E- Ol 2 . 24E-Ol

+ EU-154 123.0 7 40 . 40 4 . 71E-02 8 .1 6E - 02 8.16E - 02 723 .30 19.70 1.77E- 01 2.33E - 01 1274.51 35 . 50 9 . 21 E- 02 1.76E- 01

+ EU- 155 86.54 32.80 -1.0BE- 03 1. 3 1E-01 l.31E-01 105 . 3 1 21. 80 7 . 86E-03 l.5 7E -01

+ BI-214 609.31

• 46.30 1.43E-01 1. OOE - 01 1 . 00E-01 1120.29

• 15.10 3.25E-01 2.97E-01 1238 . 11 5.94 4.17E - Ol l.16E+OO 1377.67 4 .11 -l.82E-01 l . 15E+OO 1407 . 98 2 .4 8 -2.23E+OO l . 87E+OO 1509.19 2 . 19 3 .4 9E-02 l . 73E+OO 1764 . 49

• 15 .8 0 1. 40E-01 2 . 93E-01

+ PB- 214 77 .11 10.70 3 . 05E - 01 l . 17E-01 5 . 00E-01 295 . 21

• 19. 20 2.19E-01 1. 41E- 01 351 . 92

• 37.20 1.35E-01 1.17E-01

+ PA-228 89 . 95 22 .00 6 .92E-01 4 . BBE-01 8 . 35E-01 93 . 35 35.00 -1 .lOE- 01 4.88E-01 1 05 . 00 16.30 1.75E-0 2 9 . 25E- 01 129.22 2.97 -4.41E-01 4 . 82E+OO 338 . 32 5 . 30 1.29E+OO 3 . 12E+OO 463 . 00 13 . 80 1. 36E+OO 1 . 26E+OO 911.23 16 . 70 4. 30E-0 1 1 . 54E+OO

+ AM- 241 59 . 54 36 . 30 -8.90E-02 2 . 37E-01 2 . 37E-01

+ CM- 243 103. 76 23 .00 2.62E-02 1.SlE- 01 1.SlE- 01 228 .1 8 10 . 60 -6 . 85E-02 3.09E-01 277 . 60 14 . 00 -3 .0 9E-02 2 . 44E-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

1/15/2019 2:29:55PM Page 7 of7 Analysis Report for L1-SUB-DRS-FSGS-W12-S8 L1-010-104 WEST PACKAGE: L 1-SUB-DRS

1/15/2019 2:30:34PM Page I of7

~ Jti ~~pex-Gamma Analysis Report for L 1-SUB-DRS-FSGS-W13-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FSGS-W13-SB Sample Description  : L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 9.632E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 8:42:00AM Acquisition Started  : 3/1/2018 1:24:59AM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.5 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  : 5355 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:30:25PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:30:34PM Page 2 of7 Analysis Report for L 1-SUB-DRS-FSGS-W13-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 185.65 368 - 375 371.80 5.70E+Ol 26.52 5.15E+02 0 .69 F 2 238.59 473 - 485 477.65 3.27E+02 46.32 5. 72E+02 1. 67 F 3 295 .3 1 585 - 596 591.08 l.03E+02 30 . 29 3.55E+02 1. 59 F 4 337.96 67 1 - 681 676.35 5.02E+Ol 25.50 2.79E+02 1. 63 F 5 351.68 695 - 708 703.79 l.84E+02 35 .56 2 . 78E+02 2.34 F 6 583.06 1160 - 1173 1166.47 8.46E+ Ol 23 .5 6 1.31E+02 2.06 F 7 609.55 1214 - 1226 1 219 .43 1.24E+02 27 .88 1. 47E+02 2.29 F 8 910. 72 1817 - 18 28 1821. 68 5.09E+Ol 18.54 1. 05E+02 1. 41 F 9 1332 .2 6 2659 - 2671 2664.65 2.52E+Ol 12.83 3.79E+Ol 1. 90 F 10 1460.57 2912 - 2929 2921. 25 5.07E+02 45.64 3. 14E+Ol 2.53 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:30:25PM 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 1 185.65 5.70E+O l 26 . 52 5.70E+Ol 2.65E+Ol F 2 238.59 3.27E+02 46.32 3 .27E+02 4.63E+Ol F 3 295.31 l.03E+02 30.29 l.03E+02 3 .0 3E+Ol F 4 337. 96 5.02E+Ol 25.50 5.02E+Ol 2 . 55E+Ol F 5 351.68 1. 84E+02 35.56 8.36E+Ol 3. 72E+Ol 1.01E+02 5.15E+Ol F 6 583.06 8.46E+Ol 23 .56 8.46E+O l 2.36E+Ol F 7 609.55 l.24E+02 27 .8 8 4 .12E+Ol 2 .4 2E+Ol 8.32E+Ol 3.69E+Ol F 8 910.72 5.09E+Ol 18.54 5.09E+Ol 1. 85E+Ol F 9 1332.26 2 . 52E+Ol 12.83 2.52E+Ol l.28E+Ol F 10 14 60.57 5.07E+02 45.64 5.63E+Ol 1. 71E+Ol 4.50E+02 4.88E+Ol M =First peak in a multiplet region m =Other peak in a multiplet region F =Fitted singlet Errors quoted at 2.000sigma

1/15/2019 2:30:34PM Page 3 of7 Analysis Report for L 1-SUB-DRS-FSGS-W13-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS 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) (pCilgrams) Uncertainty K-40 0.99 1460.75

• 10.67 5.09E+00 6.20E-01 PB-212 0.56 77 .11 17.50 238.63

• 44.60 l.75E-01 2.64E-02 BI-214 0.34 609.31

• 46.30 9.95E-02 4.45E-02 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 l.53E-01 4.56E-02 351.92

• 37.20 9.04E-02 4.64E-02 RA-226 0.95 186.21

• 3.28 3.49E-01 l.63E-01

• =Energy line found in the spectrum.

- =Manually added nuclide.

? =Manually edited nuclide.

@ =Energy line not used for Weighted Mean Activity Energy Tolerance: 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence (pCilgrams) Uncertainty K-40 0.995 5.09E+OO 6.20E-Ol PB-212 0.560 l.75E-01 2.64E-02

1/ 15/2019 2:30:34PM Page 4 of7 Analysis Report for L 1-SUB-DRS-FSGS-W13-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

BI- 21 4 0 . 345 9 . 95E- 02 4 . 45E- 02 PB- 214 0 . 716 1. 22 E-O l 3 . 25E- 02 RA- 226 0 . 95 1 3. 4 9E - 01 l . 63E- Ol

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

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

1/15/2019 2:30:34PM Page 5 of7 Analysis Report for L 1-SUB-DRS-FSGS-W13-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:30:25PM 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 4 337.96 l.39485E-02 25.39 Tol. AC-228 PA-228 F 6 583.06 2. 34896E-02 13.93 F 8 910.72 l.41504E-02 18.20 Tol. AC-228 PA-228 F 9 1332.26 6.99759E-03 25.47 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigrna NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCilgrams)

(keV)

+ K-40 1460.75

• 10.67 5.09E+OO 5.31E-01 5.31E-01

+ AR-41 1293.64 99.16 -l.80E+05 2.90E+05 2 . 90E+05

+ C0-60 1173.22 100.00 1. 23E-02 4.92E-02 5.34E-02 1332.49 100.00 3.44E-02 4.92E-02

+ KR-85 513.99 0. 43 5.49E+OO 8.53E+OO 8.53E+OO

+ Y-88 898.04 93.70 2.77E-02 2.99E-02 4.49E-02 1836.06 99 . 20 -4.12E-03 2.99E-02

+ NB-94 702.63 100.00 1.05E-03 3.48E-02 3.48E-02 871.10 100.00 -1.60E-02 4.03E-02

+ I-131 284.30 6.06 1. 42E-01 4.12E-02 5.36E-01

1/15/2019 2:30:34PM Page 6 of7 Analysis Report for L1-SUB-DRS-FSGS-W13-S8 L1-010-104 WEST PACKAGE: L1-SUB-DRS Nuclide Energy Yield(%) Activity Nuc/ldeMDA LlneMDA Name (pCilgrams) (pCilgrams) (pCilgrams)

(keV)

I-1 31 364. 4 8 81. 20 1.74E-02 4.12E-02 4.12E-02 636.97 7.27 -2.96E-Ol 5.56E-01

+ CS - 13 4 604.70 97 . 60 -4.54E-02 4.46E-02 4.57E-02 795.84 85.40 - 1 . 57E-02 4.46E-02

+ CS-137 661.65 85.12 4.70E-02 5.03E-02 5 . 03E-02

+ CE-144 80 .1 2 1. 36 1 . 62E+OO 2.37E-0 1 3.05E+OO 133 . 51 11. 09 3.37E-02 2.37E-Ol

+ EU-15 2 121. 78 28.40 -3.17E-02 9 .6 0E-02 9.60E-02 344.28 26 .60 2.33E-02 1.21E-01 1408.00 20.7 4 1. 25E-Ol 1.93E-01

+ EU-154 123.07 40.40 -2 .42E-03 6 .7 7E- 02 6. 77E- 02 723.30 19.70 8.48E-0 2 1.91E-Ol 1274.51 35.50 5.95E- 0 2 1. 4 4E-01

+ EU-155 86 . 54 32.80 -3 .13E-0 2 1.06E-01 1.06E- 01 105.31 21. 80 - 2 . 6 1E-02 1 . 30E-01

+ BI-214 609 . 31

• 46.30 9 .95E.02 8 . 0 4E-0 2 8.0 4E- 02 11 20.29 1 5. 1 0 3 . 12E-Ol 3.69E-01 1 238.11 5 .94 - 1. 42E - 02 9.30E-01 1377. 67 4 . 11 - 5.55E-01 9.66E - Ol 1407.98 2 .4 8 1.04E+OO l.62E+OO 1509. 19 2. 1 9 8.96E-01 l. 36E+OO 1764 .49 15.80 6.49E-02 2 . 8 1E-Ol

+ PB- 214 77 . 11 10. 70 2.86E-01 8.65E- 02 4.llE-01 295.21

• 19 . 20 1.53E-Ol 1. 07E-Ol 351.92

• 37 . 20 9.04 E-0 2 8.65E-02

+ PA-228 89 . 95 22.00 -1.15E-01 3 . 2 7E-01 5. 4 9E- 01 93.35 35.00 - 3 . 85E-02 3.27E- 01 105 . 00 16.30 6.23E-02 6. 43E -Ol 129.22 2.9 7 9 . 48E- 0 1 3.28E+OO 338.32 5.30 3.18E+OO 2.14E+OO 463 .00 13.80 7.52E- 01 8 . 75E-0 1 911. 23 16.70 3.94E-01 l.14E+OO

+ AM-241 59 . 54 36.30 5 . 48E-02 1.90E- 0 1 1.90E-01

+ CM-243 103.76 23.00 -8.80E-02 1.24E- 0 1 1.24E-01 228.18 10.60 2.48E-01 2 . 55E-01 277 . 60 14.00 -5.38E- 03 2.05E- 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

1/15/2019 2:30:34PM Page 7 of7 Analysis Report for L 1-SUB-DRS-FSGS-W13-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS

1/15/2019 2:31:14PM Page I of7

~Apex-Gamma Analysis Report for L 1-SUB-DRS-FSGS-W14-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FSGS-W14-S8 Sample Description  : L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 9.117E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 8:31:00AM Acquisition Started  : 3/1/2018 12:21:57AM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.8 seconds Dead Time  : 0.30 %

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100- 4096 Peak Area Range (in channels)  : 100-4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5356 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:31:0SPM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:31:14PM Page 2 of7 Analysis Report for L 1-SUB-DRS-FSGS-W14-S8 L1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.82 147 - 160 154.19 1 . 49E+02 49 . 99 1. 31E+03 1. 94 F 2 92.42 183 - 192 185 .38 6.0lE+Ol 28 . 24 9.03E +02 0.62 F 3 238 .5 2 469 - 485 4 77 . 52 2.49E+02 42 . 15 7.70E+02 1. 59 F 4 295.20 583 - 595 590 .8 6 1.18E+02 32 .54 3 . 81E+02 1. 84 F 5 351.67 700 - 71 2 703.77 2.22E+02 36 .2 0 3.00E+0 2 1. 74 F 6 528.61 1054 - 1061 1057.58 1 . 78E+Ol 14.94 8 . 04E+Ol 1. 44 F 7 582 . 78 1158 - 1172 1165.90 6 . 02E+Ol 22 . 21 1 . 35E+02 2 .44 F 8 609.28 12 11 - 1224 1218.89 1. 31E+02 27 .1 5 1. 4 2E+02 1. 73 F 9 661. 46 1316 - 1330 1323.2 4 1. 58E+02 28.40 9 .4 7E+Ol 2.29 F 10 910.84 1815 - 1829 1821 .9 2 6.39E+Ol 19 . 20 7 . 50E+Ol 1. 91 F 11 1332. 58 265 9 - 2 672 266 5. 29 3.98E+Ol 14 . 20 l.71E+ Ol 2.85 F 12 1460 . 65 2913 - 2 930 2921. 41 4.4 0E+02 42 .91 4 .16E+Ol 2 . 56 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:31 :05PM 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 76.82 l.49E+02 49.99 1.49E+02 5 .00 E+Ol F 2 92.42 6 . 0lE+Ol 28.24 6 . 0lE+Ol 2 . 82E+Ol F 3 23 8 . 52 2 . 49E+02 42.15 2 . 49E+02 4 .21E+Ol F 4 295.20 1 . 18E+02 32 . 54 1 . 18E+02 3 . 25E+Ol F 5 351 . 67 2 . 22E+02 36 . 20 8 . 36E+Ol 3 . 72E+Ol 1. 39E+02 5 . 19E+Ol F 6 528 . 61 1 . 78E+Ol 14 . 94 1 . 78E+Ol 1. 4 9E+Ol F 7 582 . 78 6 . 02E+Ol 22 . 21 6 . 02E+Ol 2 . 22E+Ol F 8 609 . 28 1. 3 1E+02 27.15 4.12E+Ol 2 . 42E+Ol 8 . 95E+Ol 3 . 64E+O l F 9 661. 4 6 1 . 58E+ 02 28 .4 0 6.61E +Ol 2.54E+Ol 9 . 22E+Ol 3 . 81E+Ol F 10 910.84 6 . 3 9E+Ol 19 . 20 6 . 39E+Ol 1.92E+Ol F 11 1 332 . 58 3 .98E+Ol 14.20 3 . 98E+Ol 1. 42E+Ol F 12 1 4 60 . 65 4 . 40E+02 42 . 91 5 . 63E+Ol 1 . 71E+Ol 3 . 84E+02 4.62E+Ol

1/15/2019 2:31:14PM Page 3 of7 Analysis Report for L 1-SUB-DRS-FSGS-W14-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCilgrams) Uncertainty K-40 0.99 1460.75

• 10.67 4.59E+OO 6.08E-01 CS-137 0.99 661.65

• 85.12 6.83E-02 2.85E-02 PB-212 0.99 77.11

• 17.50 2.32E-01 7.91E-02 238.63

• 44.60 l.41E-Ol 2.49E-02 BI-214 0.35 609.31

• 46.30 1 .13E-01 4.64E-02 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 0.99 77.11

• 10.70 3.79E-01 l.29E-01 295.21

• 19.20 l.86E-Ol 5.19E-02 351. 92

• 37.20 l.31E-01 4.96E-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 confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT

1/15/2019 2:31:14PM Page 4 of7 Analysis Report for L 1-SUB-DRS-FSGS-W14-S8 L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K-40 0.998 4.59E+OO 6.08E-01 CS-137 0.994 6.83E-02 2.85E-02 PB-212 0.995 l.40E-01 2.38E-02 BI-214 0.350 1.13E-Ol 4.64E-02 PB-214 0.992 1.57E-Ol 3.47E-02

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

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

1/15/2019 2:31:14PM Page 5 of7 Analysis Report for L 1-SUB-DRS-FSGS-W14-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:31:05PM 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 92.42 l.66852E-02 23.51 Tol. PA-228 F 6 528.61 4.93106E-03 42.08 F 7 582.78 l.67194E-02 18.45 F 10 910.84 l.77426E-02 15.03 Tol. AC-228 PA-228 F 11 1332.58 l.10661E-02 17.82 Tol. C0-60 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclldeMDA LineMDA Name (pCilgrams) (pCi/grams) (pCi/grams)

(keV)

+ K-40 1460.75

• 10.67 4.59E+OO 5.82E-01 5.82E-01

+ AR-41 1293.64 99.16 -8.62E+04 l.97E+05 l.97E+05

+ C0-60 1173.22 100.00 6.45E-02 5.lOE-02 6.07E-02 1332.49 100.00 4.34E-02 5.lOE-02

+ KR-85 513.99 0.43 1. 05E+Ol 9.09E+OO 9.09E+00

+ Y-88 898.04 93.70 4.48E-02 3.16E-02 4.72E-02 1836.06 99.20 6.96E-03 3.16E-02

+ NB-94 702.63 100.00 -5.39E-03 3.80E-02 3 . 80E-02 871.10 100.00 -2.09E-02 4.04E-02

+ I-131 284.30 6.06 l.39E-01 4 .13E-02 5.55E-Ol

1/15/2019 2:31 :14PM Page 6 of7 Analysis Report for L 1-SUB-ORS-FSGS-W14-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCilgrams)

(keV)

I-131 364.48 81.20 -2.31E-02 4.13E-0 2 4.13E-02 636 . 97 7.27 1. 35E-Ol 5.44E-01

+ CS-134 604.70 97.60 -5 .47E- 03 4 .4 5E-02 4.85E-02 795.84 85.40 -2.41E-02 4. 45E-02

+ CS-13 7 661.65

• 85.12 6.83E-02 4.86E-02 4.86E-02

+ CE-1 44 80.12 1. 36 -4.61E-01 2.54E-01 3.09E +OO 133. 51 11. 09 1. 72E- 0 1 2.54E-Ol

+ EU- 152 1 2 1. 78 28.40 5.72E-03 9.73E-02 9.73E- 02 344.28 26 .6 0 -4 .02 E-0 1 1. 2 4E- 01 14 08.00 20.74 l.12E- 01 2 . 08E- 01

+ EU-154 123.07 40.40 8.49E-03 6.86E-02 6.86E-02 723 . 30 19.70 1. 62E- Ol 2.lOE-0 1 127 4. 51 35.50 1.54E-01 1 . SlE-01

+ EU-155 86.54 32.80 -5.58E-02 1. 08E-01 1.08E-01 105.31 21. 80 3 .1 2E- 02 1.34E- 01

+ BI-214 609.31

• 46.30 1.13E-01 8 .4 8E-02 8.48E-02 1120.29 15. 1 0 l.86E-0 1 3.9 1E- 0 1 1 238 . 11 5 . 94 -4.38E-01 9 . 87E-01 1377 . 67 4 .11 1.4 4E- 01 9.80E-01 1407.98 2 . 48 9 . 34E-01 1. 74E+OO 1509 .1 9 2. 19 1.49E+OO l.79E+OO 1764.49 15.80 3.83E-01 3 . 24E-01

+ PB-214 77 .11

• 10.70 3.79E-Ol 9 . 28E - 02 3.62E-01 295.21

• 19.20 l.86E- 01 1.20E-01 351.92

• 37.20 1. 31E- 01 9 . 28E - 02

+ PA-228 89 .95 22 . 00 - 2.12E-01 3 . 39E-01 5 . 69E- 0 1 93.35 35.00 2.07E-Ol 3.39E- 01 1 05.00 16.30 l . 95E-01 6 . 44E-01 129.22 2 .97 -1 . 28E+OO 3.31E+OO 338 . 32 5.30 5.34E - 02 2 .0 2E+OO 463.00 13.80 -1.1 2E-01 8.54E-Ol 911.23 16.70 5.31E-01 1.08E+OO

+ AM-241 59 . 54 36.30 -2.09E-02 2 . 00E-01 2.00E-01

+ CM-243 103 .76 23 . 00 6.42E-02 1.29E-0 1 1. 29E-01 228.18 10.60 -1. 74 E- 01 2.63E-Ol 277 . 60 14.00 6 . 76E-02 2.08E-O l

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = MOA value not calculated

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

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

1/15/2019 2:31:14PM Page 7 of7 Analysis Report for l 1-SUB-DRS-FSGS-W14-SB L1-010-104 WEST PACKAGE: l 1-SUB-DRS

1/15/2019 2:31 :56PM Page 1 of6

.Jt'Apex-Gamma Analysis Report for L 1-SUB-DRS-QSGS-W14-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-QSGS-W14-SB Sample Description  : L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 9.038E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 8:35:00AM Acquisition Started  : 3/1/2018 2:26:58AM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.7 seconds Dead Time  : 0.30%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100- 4096 Peak Area Range (in channels)  : 100-4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5357 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:31 :47PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:31 :56PM Page 2 of6 Analysis Report for L 1-SUB-DRS-QSGS-W14-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.74 14 7 - 161 154.02 1. 36E+0 2 44.58 1.41E+03 1. 46 F 2 238 . 51 457 - 485 47 7 . 50 2 . 31E+0 2 44 . 28 1.38E+03 1. 97 F 3 295 .2 8 584 - 597 591.01 1 . 17E+02 32 . 10 4 . 41E+02 1. 63 F 4 35 1 .83 698 - 711 704.08 2.53E+02 37.52 2 . 66E+02 1. 81 F 5 583.40 1159 - 1172 1167.14 6 . 82E+O l 20 . 59 1.37E+02 1. 27 F 6 609 . 24 1211 - 1225 1218 .82 1.96E+02 31. 4 1 1. 31E+02 1. 95 F 7 661. 62 13 1 8 - 1330 1323. 55 1 .28E+02 26 . 21 l . 16E+02 1. 69 F 8 911 .1 4 1818 - 1831 1822.53 3 . 93 E+Ol 15 . 68 7 . 52E+Ol 1. 4 2 F 9 968 . 94 1933 - 1944 1938.10 2 . 27E+Ol 16 . 44 1. 06E+02 1. 76 F 10 1119.73 22 3 2 - 2246 2239.64 3 . 09E+Ol 14 . 06 9.70E+Ol 0 . 96 F 11 1460.57 29 1 3 - 2931 2921. 26 4 . 48E+0 2 43 . 29 4.5 1E+Ol 2.54 F 12 1764 . 22 3523 - 3535 3528.51 4 . 18E+Ol 13. 36 3.66E+OO 2.48 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:31 :47PM 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 76.74 1.36E+02 44 . 58 1.36E+02 4.46E+Ol F 2 238 . 51 2 . 31E+02 44 . 28 2 . 31E+02 4.43E+Ol F 3 295.28 1 . 17E+02 32 . 10 1 . 17E+02 3 . 21E+Ol F 4 351 .8 3 2 . 53E+02 37 . 52 8.36E+Ol 3 . 72E+Ol 1. 69E+02 5 . 28E+Ol F 5 583 . 40 6 . 82E+Ol 20 . 59 6.82E+Ol 2 . 06E+Ol F 6 609.24 l . 96E+02 31. 41 4. 12E+Ol 2 . 42E+Ol l. 55E+02 3 . 97E+Ol F 7 661. 62 1. 28E+02 26 . 21 6 . 61E+Ol 2 .54 E+Ol 6 . 23E+Ol 3.65E+Ol F 8 911 . 1 4 3 .9 3E+Ol 15 . 68 3 . 93E +Ol 1.57E+Ol F 9 968 . 94 2 . 27E+Ol 16 . 44 2 . 27E+Ol 1 . 64E+Ol F 10 1119 . 73 3 . 09E+Ol 14 . 06 3 . 09E+Ol 1.41E+Ol F 11 1460 . 57 4 . 48 E+ 02 43 . 29 5 . 63E+Ol 1. 71E+Ol 3 . 92 E+02 4 . 66E+Ol F 12 1764 . 22 4 . 18E+Ol 13.36 1 . 52E+Ol 9.80E+OO 2 . 66E+Ol l . 66E+O l

1/15/2019 2:31:56PM Page 3 of6 Analysis Report for L 1-SUB-DRS-QSGS-W14-SB L 1-010-104 WEST PACKAGE: L 1-SUB-DRS M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCUgrams) Uncertainty K-40 0.99 1460.75

• 10.67 4.73E+OO 6.20E-01 CS-137 1. 00 661. 65

• 85.12 4.65E-02 2.74E-02 PB-212 0.99 77 .11

• 17.50 2.14E-01 7.14E-02 238.63

• 44.60 1. 32E-01 2.62E-02 BI-214 0. 77 609.31

• 46.30 1.97E-01 5.17E-02 1120.29

• 15.10 2.09E-01 9.55E-02 1238.11 5.94 1377.67 4 .11 1407.98 2.48 1509.19 2.19 1764.49

• 15.80 2.54E-01 1.59E-01 PB-214 0.99 77 .11

• 10.70 3.SOE-01 1.17E-01 295.21

• 19.20 1.85E-01 5.16E-02 351.92

• 37.20 1.62E-01 5. llE-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 confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT

1/15/2019 2:31:56PM Page 4 of6 Analysis Report for L1-SUB-DRS-QSGS-W14-S8 L1-010-104 WEST PACKAGE: L1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)

K-40 0.995 4.73E+OO 6.20E-Ol CS-137 1. 000 4.65E-02 2.74E-02 PB-212 0.992 l.29E-01 2.47E-02 BI-214 0.777 2.04E-01 4.37E-02 PB-214 0.995 l.70E-01 3.49E-02

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

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

1/15/2019 2:31:56PM Page 5 of6 Analysis Report for L 1-SUB-DRS-QSGS-W14-SB L1-010-104 WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:31:47PM 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 5 583.40 1.89449£-02 15.09 F 8 911.14 1.09179£-02 19.95 Tol. AC-228 PA-228 F 9 968. 94 6.30541£-03 36.21 Tol. AC-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCl/grams) (pCl/grams) (pCUgrams)

(keV)

+ K-40 1460.75

• 10. 67 4.73E+OO 5.99E-01 5.99E-01

+ AR-41 1293.64 99.16 -1.49E+05 4.81E+05 4.81E+05

+ C0-60 1173.22 100.00 -3.46E-03 5. llE-02 5.64E-02 1332.49 100.00 3.05E-02 5. llE-02

+ KR-85 513.99 0.43 1.15E+Ol 9.44E+OO 9.44E+OO

+ Y-88 898.04 93.70 2.83E-02 3.29E-02 4.58E-02 1836.06 99.20 -5.47E-03 3.29E-02

+ NB-94 702 .63 100.00 1.14E-02 3.66E-02 3.66E-02 871.10 100.00 4.37E-04 3.70E-02

+ I-131 284.30 6.06 3.32E-01 4.25E-02 5.85E-01 364.48 81. 20 1. 77E-02 4.25E-02 636.97 7.27 2.67E-01 5.49E-01

1/15/2019 2:31:56PM Page 6 of6 Analysis Report for L 1-SUB-DRS-QSGS-W14-S8 L1 -010-104 WEST PACKAGE: L 1-SUB-DRS Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCi/grams) (pCi/grams) (pCi/grams)

(keV)

+ CS - 134 604.7 0 97 . 60 -9 . 26E-03 4.60E-02 5.34E-02 795.84 85.40 5.85E- 03 4.60E-02

+ CS - 137 661.65

• 85.12 4 . 65E- 02 5 . 00E-02 5 . 00E-02

+ CE-144 80.12 1. 36 - 2 . 60E- 01 2 . 54E-01 3.12E+OO 133. 51 11. 09 l.54E- Ol 2 . 54E-01

+ EU- 152 121.78 28.40 -1 . 30E-02 9 . 67E-02 9 . 67E-02 344.28 26.60 9 . 33E- 02 1 . 30E-01 1408.00 20.74 - 3 . 52E-02 2 . 12E-01

+ EU- 154 123.07 40 . 40 -1 . 80E-02 6 . 77E-02 6.77E - 02 723.30 19.70 3 . 52E- 02 2 . 02E-01 1274.51 35.50 3 . 32E- 02 l . 45E - 01

+ EU-155 86 . 54 32.80 - 5.44E- 02 1. 08E- 01 1 . 08E-01 105.31 21.80 - 3.43E- 03 1. 33E-01

+ BI - 214 609.31

• 46.30 1 . 97E-01 8 . 48E-02 8.48E-02 1120.29

• 15.10 2 . 09E - 01 2.84E-01 1238.11 5.94 6 . 35E-01 1. 05E+OO 1377. 67 4 .11 -1.70E- 01 1.14E+OO 1407.98 2 . 48 - 2 . 95E - 01 1 . 77E+OO 1509.19 2.19 6 . lOE-01 1.60E+OO 1764.49

• 15 . 80 2.54E-01 2 .35E-01

+ PB- 214 77.11

• 10.70 3 . 50E-01 9 . 13E-02 3 . 89E-01 295.21

• 19 . 20 l.85E-Ol l.33E-01 351.92

• 37.20 1.62E- 01 9 . 13E-02

+ PA-228 89.95 22.00 3 . 71E-01 3 . 53E-01 5 . 95E-01 93.35 35 . 00 7 . 86E-02 3 . 53E-01 105.00 16 . 30 1. 86E-01 6.76E-01 129.22 2 . 97 4 . 06E-Ol 3.54E+OO 338 . 32 5.30 2.37E+OO 2 . 36E+OO 463.00 13.80 5.75E-02 9 . 78E-01 911.23 16.70 1. 31E+OO l . 16E+OO

+ AM-241 59.54 36 . 30 -8 . 58E-02 l . 99E-01 1. 99E-Ol

+ CM-243 103.76 23 . 00 2 . 45E-02 l . 27E-01 l.27E-01 228 . 18 10.60 - 8 . 72E-02 2 . 64E-01 277.60 14.00 4 . 76E-02 2.14E-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

1/15/2019 2:32:48PM Page I of6

_..Apex-Gamma Analysis Report for L 1-SUB-DRS-FJGS-W01-SB L 1-010-104-WEST PACKAGE : L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FJGS-W01-SB Sample Description  : L1-010-104-WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8.402E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 3/2/2018 10:43:00AM Acquisition Started  : 3/5/2018 11 :05:28AM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.7 seconds Dead lime  : 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  : 5358 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:32:39PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:32:48PM Page 2 of6 Analysis Report for L1-SUB-DRS-FJGS-W01-SB L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.39 147 - 161 153 . 33 3 . 11E+02 70 . 38 l . 68E+03 3 . 91 F 2 93.19 183 - 191 186.92 l . 19E+02 47.18 9.21E+02 1. 69 F 3 185.55 369 - 377 37 1. 61 4.45E+Ol 28.96 6.74E+02 0 . 74 F 4 238.61 474 - 485 477.69 4.85E+02 54 . 28 6 . 16E+02 1. 78 F 5 2 9 5.08 584 - 606 590.61 2.18E+02 41 . 00 7 . 11E+02 2 .4 8 F 6 338.24 668 - 684 676.92 l . 27E+02 34 . 22 4. 33E+02 2.39 F 7 351.65 697 - 712 703.72 3.25E+02 42 . 65 3 . 92E+02 1. 74 F 8 5 83.0 7 116 1 - 1171 1166.48 1 .1 1E+02 26.97 1 . 35E+02 2.05 F 9 609.21 1210 - 1224 1218.75 2.29E+02 34 . 25 1 . 69E+02 1. 96 F 10 661 . 31 13 1 6 - 1328 1322.93 1 . 02E+02 25 . 11 l.44E+02 1. 62 F 11 910.91 18 15 - 1 827 1822.05 6.40E+Ol 19 . 73 8.47E+Ol 1. 85 F 12 969. 05 1934 - 1 94 3 19 38.32 4. 23E+Ol 18 . 38 9.13E+Ol 1. 70 F 13 1120. 24 2236 - 2248 2240.67 6.43E+O l 18 . 85 4. 80E+Ol 2 . 61 F 14 1460 . 35 2912 - 293 1 2920 . 82 5 . 67E+0 2 48 . 53 4 . 44E+Ol 2 . 57 F 15 1764.17 3523 - 3534 3528.41 3 . 0lE+Ol 12.26 l.26E+Ol 2 . 24 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:32:39PM 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 . 39 3 . 11E+02 70 . 38 3 . 11E+02 7 . 04E+Ol F 2 93 . 19 l.19E+02 47.18 l.19E+02 4 . 72E+Ol F 3 185 . 55 4 .4 5E+Ol 28. 96 4.45E+Ol 2 . 90E+Ol F 4 238 . 61 4 . 85E+02 54.28 4 . 85E+02 5 . 43E +Ol F 5 295.08 2 . 18E+02 41. 00 2 . 18E+02 4 . lOE+Ol F 6 338.24 1 . 27E+02 3 4 .22 l . 27E+02 3 .42E +Ol F 7 35 1. 65 3 . 25E+02 42.65 8 . 36E+ Ol 3.72E+Ol 2 . 41E+02 5.66E+Ol F 8 583.07 l.11E+02 26. 97 l . 11E+02 2 . 70E+Ol F 9 609 . 21 2 . 29E+02 34 . 25 4 . 12E+Ol 2 . 42E+Ol l . 88E+02 4 . 19E+Ol F 10 661 . 31 l.02E+02 25 .11 6 . 61E+Ol 2 . 54E+Ol 3 . 62E+Ol 3 . 57E+Ol F 11 910 . 91 6.40E+Ol 19 .73 6 . 40E+Ol l.97E+Ol F 12 969 . 05 4.23E+Ol 18.38 4 . 23E+Ol l . 84E+Ol F 13 1120 . 24 6.43E+Ol 18 . 85 6 . 43E+Ol l .88E+Ol F 14 1460 . 35 5 . 67E+02 48.53 5.63E+Ol 1 . 71E+Ol 5 . 11E+02 5 .15E+ Ol

1/15/2019 2:32:48PM Page 3 of6 Analysis Report for L 1-SUB-DRS-FJGS-W01-SB L1-010-104-WEST PACKAGE : L1-SUB-DRS Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 15 1764.17 3.0lE+Ol 12.26 1. 52E+Ol 9.80E+OO l.SOE+Ol l.5 7E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCilgrams) Uncertainty K-40 0.97 1460.75

• 10.67 6.62E+OO 7.62E-Ol CS-137 0.98 661.65

• 85.12 2.91E-02 2.87E-02 PB-212 0.97 77 .11

• 17.50 5.29E-01 1. 25E-Ol 238.63

• 44.60 2.97E-Ol 3.67E-02 BI-214 0.78 609.31

• 46.30 2.58E-Ol 5.93E-02 1120.29

• 15.10 4.68E-Ol l.39E-01 1238 .11 5.94 1377.67 4.11 1407.98 2.48 1509.19 2.19 1764.49

• 15.80 l.53E-01 l.61E-01 PB-214 0.98 77 .11

• 10.70 8.66E-01 2.04E-01 295.21

• 19.20 3.70E-01 7.21E-02 351.92

• 37.20 2.48E-01 5.94E-02 RA-226 0.93 186.21

• 3.28 3.12E-01 2.04E-Ol AC-228 0. 60 209.28 4.40 338.32

• 11. 40 4.13E-Ol l.13E-01 794.70 4.60 911. 60

• 27.70 2. llE-01 6.57E-02 964. 60 5.20 969 .11

• 16.60 2.46E-01 l.07E-Ol

1/15/2019 2:32:48PM Page 4 of6 Analysis Report for L 1-SUB-DRS-FJGS-W01-SB L 1-010-104-WEST PACKAGE: L 1-SUB-DRS

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)

K- 40 0.975 6.62E+ OO 7.62E- 01 CS -1 37 0.981 2.91E-02 2 . 87E- 02 PB- 212 0.977 3 . 0lE-0 1 3.53E- 02 BI-214 0 . 784 2 .7 6E- 01 5 . 16E- 02 PB - 2 14 0.980 3.0lE- 01 4.48E-02 RA-226 0.933 3.12E- Ol 2.04E-0 1 AC-228 0 .6 03 2 . 59E - 01 5 . 02 E- 02

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

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

1/15/2019 2:32:48PM Page 5 of6 Analysis Report for L 1-SUB-DRS-FJGS-W01-SB L 1-010-104-WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:32:39PM 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 93.19 3.30841E-02 19.81 Tol. PA-228 F 8 583.07 3.08884E-02 12 .13 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCi/grams) (pCl/grams)

(keV)

+ K-40 1460.75

• 10.67 6.62E+OO 6.50E-01 6.50E-Ol

+ AR-41 1293. 64 99.16 l .13E+l0 5.50E+10 5.50E+10

+ C0-60 1173.22 100.00 -2.19E-03 5.54E-02 6.75E-02 1332.49 100.00 4.07E-02 5.54E-02

+ KR-85 513. 99 0.43 2.76E+OO 1. 04E+Ol l.04E+01

+ Y-88 898.04 93.70 8.60E-03 3.46E-02 5.40E-02 1836.06 99.20 -3.26E-02 3.46E-02

+ NB-94 702. 63 100.00 -1.70E-02 4.57E-02 4.57E-02 871.10 100.00 -3.64E-02 4.77E-02

+ I-131 284.30 6.06 -4.07E-01 5.39E-02 7.33E-01 364.48 81. 20 -3.07E-02 5.39E-02 636.97 7.27 7.42E-01 7.32E-01

+ CS-134 604.70 97. 60 -1. 50E-03 5.43E-02 6.37E-02 795.84 85.40 -l.50E-02 5.43E-02

1/15/2019 2:32:48PM Page 6 of6 Analysis Report for L 1-SUB-DRS-FJGS-W01-S8 L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Nuclide Energy Yield(%) Activity Nucl/deMDA LlneMDA Name (pCilgrams) (pCilgrams) (pCi/grams)

(keV)

+ CS-137 661. 65

• 85 .1 2 2 . 91 E-0 2 5 . 62E-02 5.62E-02

+ CE - 144 80.12 1. 36 -4.91E-01 2.98E-0 1 3.85E+OO 133.51 11. 09 6 . 80E-02 2 . 98E-01

+ EU-152 121. 78 28.40 -l.25E-O l l.14E-01 l.14E-Ol 3 44. 28 26.60 -3.06E-02 l.60E-01 1 40 8 .00 20.74 1.44E- 01 2.43E-Ol

+ EU-154 123. 07 40.40 - 5.86E-02 8.03E-02 8.03E - 02 723.30 19.70 2.07E-01 2 . 61E-01 1 274.51 35.50 -l .67E-0 1 1.48E- Ol

+ EU-155 86 . 54 32.80 -6.02E-02 l.31E-01 l.31E-Ol 10 5.31 21. 80 3 . 24E-02 l.59E-01

+ BI-214 609.31

• 46 . 30 2 . 58E-Ol 9 . 75E-02 9.75E-02 11 20 . 29

• 15.10 4.68E-01 2.12E-Ol 1238 .11 5 . 94 1 . 05E+OO 1. 2 1E+OO 13 77. 67 4 .11 -2.19E-01 1. 20E+OO 1407.98 2. 4 8 l.21E+OO 2.03E+OO 1509 . 19 2.19 3 . 25E- Ol 2.23E+OO 1764.49

• 15.80 l.53E- Ol 2.80E- 01

+ PB-214 77 .11

• 10.70 8 . 66E-01 1. llE- 01 4 .59 E-Ol 295 . 21

• 19.20 3.70E-01 2 . lSE-01 351.92

• 37 .20 2 .48E-01 1. llE-01

+ PA-228 89 . 95 22.00 -3.95E - 0 1 1. llE+OO 1.90E+OO 93.35 35.00 6.36E-01 1. llE+OO 105.00 16.30 l.1 8E - 01 2. llE+OO 129 . 22 2 . 97 1. 72E+OO 1.lOE+Ol 338.32 5.30 6 . 74E+OO 7.51E+OO 463.00 13. 80 -7.70E-Ol 2 . 77E+ OO 911.23 16 . 70 4.08E+OO 3.49E+OO

+ AM-241 59 .5 4 36 . 30 3. 1 3 E-02 2 . 33E-01 2.33E-Ol

+ CM-243 103.76 23 .00 -1.42E-0 2 1.51E-Ol 1.51E-01 228.18 10.60 3.98E-02 3 . 0lE-01 277 . 60 14.00 1. 80E-Ol 2 . 63E-01

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = MDA value not calculated

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

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

1/15/2019 2:33:28PM Page I of6 Jt'Apex-Gamma Analysis Report for L 1-SUB-DRS-FJGS-W02-SB L 1-010-104-WEST PACKAGE : L1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L1-SUB-DRS-FJGS-W02-SB Sample Description  : L1-010-104-WEST PACKAGE : L1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8.870E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 3/2/2018 10:50:00AM Acquisition Started  : 3/5/2018 12:07:48PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.7 seconds Dead Time  : 0.30%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100 - 4096 Peak Area Range (in channels)  : 100 - 4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5359 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:33:18PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:33:28PM Page 2 of6 Analysis Report for L 1-SUB-DRS-FJGS-W02-SB L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 92.83 182 - 190 186. 1 9 7.28E+Ol 37. 72 7.69E+02 1. 27 F 2 238 .4 3 4 74 - 481 47 7 .33 2.46E+02 43.05 4.36E+02 1. 47 F 3 294 . 89 587 - 596 590.22 7.17E+ Ol 24.46 2 . 99E+02 0.99 M 4 328 .4 6 653 - 682 657 . 36 4 .42E+Ol 21. 57 2 . 04E+02 1. 62 m 5 338 . 38 653 - 682 677.19 5.80E+Ol 25.08 2 .7 9E+02 1. 63 F 6 351 . 60 698 - 710 703.63 l . 45E+02 32.32 2.85E+02 1. 90 F 7 582.91 1161 - 11 72 1166.15 7 .0 3E+O l 23.91 l . 67E+02 1. 88 F 8 609 .13 1214 - 1225 1218.59 l . 38E+02 27.09 9.38E+Ol 1. 93 F 9 91 0 .7 5 1816 - 1827 1821.75 4. 94E+ Ol 19 . 40 8.68E+Ol 2 . 20 F 10 969.20 1934 - 1943 1938.63 2 . 31E+Ol 14.35 5.42E+Ol 1. 87 F 11 1460.43 2913 - 2930 2920.98 4.90E+02 44.80 2.48E+Ol 2.65 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:33:18PM 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 92.83 7.28E+Ol 37.72 7.28 E+Ol 3.77E+O l F 2 238.43 2 . 46E+02 43.05 2.46E+02 4.30E+Ol F 3 29 4 .89 7 . 17E+Ol 24.46 7.17E+Ol 2.45E+Ol M 4 328.46 4.42E+Ol 21. 57 4.42E+Ol 2.16E+Ol m 5 338 . 38 5 . 80E+Ol 25.08 5.80E+Ol 2 .51E +Ol F 6 351 . 60 1. 45E+02 32.32 8.36E+Ol 3. 72E+Ol 6 .13E+Ol 4.93E+Ol F 7 582.91 7.03E+Ol 23 .91 7 .03E+Ol 2 . 39E+Ol F 8 609.13 1. 38E+02 27.09 4.12E+Ol 2.42E+Ol 9. 72E+Ol 3 . 63E+O l F 9 910.75 4.94E+Ol 19 . 40 4 . 94E+Ol l.94E+O l F 10 969 . 20 2.31E+Ol 14.35 2.3 1E+O l l.43E+Ol F 11 1 460.43 4.90E+02 44.80 5.63E+Ol l.71E+Ol 4.33E+02 4.80E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma

1/15/2019 2:33:28PM Page 3 of6 Analysis Report for L 1-SUB-DRS-FJGS-W02-SB L 1-010-104-WEST PACKAGE: L 1-SUB-DRS 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) (pCi/grams) Uncertainty K-40 0.98 1460.75

• 10.67 5.32E+OO 6.59E-01 PB-212 0.55 77 .11 17.50 238.63

• 44.60 1. 43E-Ol 2.61E-02 BI-214 0.34 609.31

• 46.30 l.26E-01 4.77E-02 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 0.70 77 .11 10.70 295.21

• 19.20 l.16E-01 3.98E-02 351.92

• 37.20 5. 96E-02 4.81E-02 AC-228 0.58 209.28 4.40 338.32

• 11. 40 l.78E-Ol 7.74E-02 794.70 4.60 911. 60

• 27.70 l.54E-01 6.lOE-02 964.60 5.20 969 .11

• 16.60 l.27E-01 7.93E-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 confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT

1/15/2019 2:33:28PM Page 4 of6 Analysis Report for L 1-SUB-DRS-FJGS-W02-S8 L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence (pCilgrams) Uncertainty K-40 0.984 5.32E+OO 6.59E-Ol PB-212 0.556 1. 43E-Ol 2.61E-02 BI-214 0.347 l.26E-Ol 4.77E-02 PB-214 0.708 9.28E-02 3.07E-02 AC-228 0.588 l.54E-Ol 4.lOE-02

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

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

1/15/2019 2:33:28PM Page 5 of6 Analysis Report for L1-SUB-DRS-FJGS-W02-SB L1-010-104-WEST PACKAGE : L1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:33:18PM Peak Locate From Channel  : 100 Peak Locate To Channel  : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 92.83 2.02252E-02 25.90 Tol. PA-228 M 4 328.46 1.22825E-02 24.39 F 7 582.91 1.95227E-02 17.01 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCi/grams)

(keV)

+ K-40 1460.75

• 10.67 5.32E+OO 5.57E-01 5.57E-01

+ AR-41 1293.64 99.16 -2.39E+10 6.87E+10 6.87E+10

+ C0-60 1173.22 100.00 -3.73E-02 5.37E-02 5.56E-02 1332.49 100.00 4.53E-02 5.37E-02

+ KR-85 513.99 0.43 1. 66E+Ol 9.47E+OO 9.47E+OO

+ Y-88 898.04 93.70 -2.22E-02 3.38E-02 4.45E-02 1836.06 99.20 -2.75E-02 3.38E-02

+ NB-94 702.63 100.00 1.lSE-02 3.73E-02 3.73E-02 871.10 100.00 -2.70E-02 3.98E-02

+ I-131 284.30 6.06 2.80E-01 4.77E-02 6.57E-01 364.48 81. 20 -2.lOE-03 4.77E-02 636.97 7.27 -1.06E-01 6.19E-01

+ CS-134 604.70 97.60 -3.93E-02 4.64E-02 4.92E-02

1/15/2019 2:33:28PM Page 6 of6 Analysis Report for L 1-SUB-DRS-FJGS-W02-SB L 1-010-104-WEST PACKAGE : L 1-SUB-ORS Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCilgrams)

(keV)

CS-134 795.84 85.40 -7.16E-03 4.64E-02 4.64E-02

+ CS-137 661 . 65 85.12 8.40E-02 5.81E-02 5.8 1E- 02

+ CE-144 80.12 1. 36 3.07E+OO 2.59E-Ol 3.17E+OO 133.51 11. 09 1. 86E-02 2 . 59E-01

+ EU- 1 52 121.78 28. 40 -4.49E-02 9.90E-02 9.90E-02 344.28 26 . 60 -4.36E-03 1. 37E-01 1408.00 20 . 74 -7.19E-02 1.67E-Ol

+ EU- 154 123.07 40.40 -7.78E-02 6.88E-02 6.88E-02 723. 30 19.70 1.36E-01 1.89E-01 1 274.5 1 35 .5 0 - 5.43E-02 1.43E-01

+ EU-155 86 . 54 32 . 80 -l.18E-03 1. llE-01 1. llE- 01 105.31 21. 80 3.69E-02 1.39E-01

+ BI-214 609.31

• 46.30 1.26E-Ol 7.82E-02 7.82E- 02 1120.29 15.10 5.03E-02 3.52E-01 1238 .11 5. 94 9.30E-01 1. llE+OO 1377. 67 4 .11 -4.02E-01 1. 08 E+ OO 1407.98 2.48 - 6.0lE-01 1. 40E+OO 1509.19 2. 1 9 3 . 63E-Ol 1. 48E+OO 1 764 .49 1 5.80 1.47E-01 2.78E-01

+ PB-214 77 . 11 10.70 2.73E-01 9.35E-02 4.23E-01 295.21

• 19 . 20 1.16E-01 1. 03E-01 351.92

• 37 . 20 5.96E-02 9 . 35E-02

+ PA-228 89.95 22.00 7.81E-0 1 9.78E-01 1.64E+OO 93.35 35.00 3.91E-01 9.78E-Ol 105.00 16.30 4.69E-Ol 1.90E+OO 129.22 2.97 -1.41E-01 9.76E+OO 338.32 5.30 3.22E-01 6.74E+OO 463.00 13. 80 6.29E -01 2.49E+OO 911. 23 16.70 3.61E+OO 3.25E+OO

+ AM-241 59.54 36 . 30 -8.20E-02 2 . 03E-01 2.03E-01

+ CM- 243 103.76 23.00 5 .13E-02 1. 32E-01 1 . 32E-01 228.18 10.60 1.04E-01 2.78E-01 277.60 14.00 6.08E-03 2 .1 9E-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 perfom, the decay correction

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

1/15/2019 2:34:06PM Page I of7

__.Apex-Gamma Analysis Report for L1-SUB-DRS-FJGS-W03-SB L1-010-104-WEST PACKAGE: L1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L1-SUB-DRS-FJGS-W03-SB Sample Description  : L1-010-104-WEST PACKAGE: L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8. 743E +02 grams Facility  : Dairyland_NPP Sample Taken On  : 3/2/2018 10:57:00AM Acquisition Started  : 3/5/2018 1 :09:58PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.8 seconds Dead Time  : 0.30%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100

• 4096 Peak Area Range (in channels)  : 100

• 4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5360 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:33:57PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/ 15/2019 2:34:06PM Page 2 of7 Analysis Report for L 1-SUB-DRS-FJGS-W03-S8 L 1-010-104-WEST PACKAGE : L1 -SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.36 469 - 482 477.19 l.98E+02 41. 03 7.26E+02 1. 48 F 2 295.08 585 - 595 590 . 61 9.58E+Ol 30.28 2 . 97E+02 1. 80 F 3 337.73 671- 680 675.90 3.02E+Ol 18.54 2.31E+02 0.92 F 4 351.72 698 - 711 703 . 87 l. 49E+02 30.95 3 . 15E+02 1. 45 F 5 583.07 1161 - 1172 1166 .4 9 9.39E+Ol 24.87 l . 22E+02 2 . 15 F 6 609.15 1214 - 1226 1218 . 63 1. 05E+02 25 .20 1. 37E+02 1. 79 F 7 661. 4 8 1318 - 1328 1323.28 1. 03E+02 24.36 9 . 58E+Ol 1. 72 F 8 869.80 1735 - 1746 1739 . 84 2 . 05E+Ol 11. 64 3 . 86E+Ol 1. 46 F 9 910. 83 1817 - 1830 1821. 90 5.32E+Ol 19.90 l . 05E+02 2 . 36 F 10 1332 .16 2658 - 2671 2664 .45 2 . 77E+Ol 13 . 29 3 . 50E+Ol 2 . 27 F 11 1460 . 32 2911 - 2930 2920 . 74 4.80E+02 44 . 43 3 . 00E+Ol 2.56 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:33:57PM 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 1 238.36 l.98E+02 41. 03 l . 98E+02 4.lOE+Ol F 2 295.08 9.58E+Ol 30.28 9 . 58E+Ol 3 . 03E+Ol F 3 337.73 3 .0 2E+Ol 18 . 54 3.02E+Ol l.85E+Ol F 4 351.72 l . 49E+02 30 . 95 8 . 36E+Ol 3 . 72E+Ol 6.50E+Ol 4.84E+ Ol F 5 583.07 9 . 39E+Ol 24 . 87 9 .3 9E+Ol 2 .4 9E+Ol F 6 609 . 15 1.0 5E+02 25 . 20 4 . 12E+Ol 2.42E+ Ol 6 . 38E+Ol 3.49E+Ol F 7 661 .4 8 1 . 03E+02 24 . 36 6 . 61E+Ol 2 .54 E+ Ol 3 . 71E+Ol 3 .5 2 E+Ol F 8 869.80 2.05E+Ol 11. 64 2 . 05E+Ol l.16E+Ol F 9 910 . 83 5.32E+Ol 19.90 5 . 32E+Ol 1 . 99E+Ol F 10 1332.16 2.77E+Ol 13 . 29 2 . 77E+Ol 1. 33E+O l F 11 1 460. 32 4.80E+02 44.43 5.63E+Ol 1. 71E +Ol 4.24E+02 4.76E+Ol

=

M First peak in a multiplet region

=

m Other peak in a multiplet region

=

F Fitted singlet Errors quoted at 2.000sigma

1/15/2019 2:34:06PM Page 3 of7 Analysis Report for L 1-SUB-DRS-FJGS-W03-S8 L1-010-104-WEST PACKAGE : L 1-SUB-DRS 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) (pCi/grams) Uncertainty K-40 0.97 1460.75

• 10.67 5.28E+OO 6.62E-01 CS-137 0.99 661.65

• 85.12 2.87E-02 2. 72E-02 PB-212 0.55 77 .11 17.50 238.63

• 44.60 l.17E-01 2.49E-02 BI-214 0.34 609.31

• 46.30 8.40E-02 4.63E-02 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 l.57E-01 5.0lE-02 351.92

• 37.20 6.42E-02 4.79E-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 confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

1/15/2019 2:34:06PM Page 4 of7 Analysis Report for L 1-SUB-DRS-FJGS-W03-SB L1-010-104-WEST PACKAGE: L 1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence (pCi/grams) Uncertainty K-40 0.970 5.28E+OO 6 .62E-Ol CS-137 0. 996 2.87E-02 2.72E-02 PB-212 0.552 1.1 7E-01 2.49E-02 BI-214 0.348 8.40E-02 4.63E-02 PB-214 0. 717 l.08E-Ol 3.46E-02

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

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

1/15/2019 2:34:06PM Page 5 of7 Analysis Report for L1-SUB-DRS-FJGS-W03-SB L1-010-104-WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:33:57PM 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 3 337.73 8. 37723E-03 30.74 Tol. AC-228 PA-228 F 5 583.07 2.60922E-02 13.24 F 8 869.80 5.70241E-03 28.35 F 9 910.83 1.47680E-02 18. 72 Tol. AC-228 PA-228 F 10 1332.16 7.70055E-03 23.97 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclldeMDA LineMDA Name (pCilgrams) (pCVgrams) (pCi/grams)

(keV)

+ K-40 1460.75

• 10.67 5.28E+OO 5.87E-01 5.87E-01

+ AR-41 1293.64 99.16 9.14E+09 9.59E+10 9.59E+10

+ C0-60 1173.22 100.00 -1.05E-02 5.42E-02 6.31E-02 1332.49 100.00 4.95E-02 5.42E-02

+ KR-85 513.99 0.43 9.87E+OO 9.47E+OO 9.47E+OO

+ Y-88 898.04 93.70 -l.46E-02 3. llE-02 4.69E-02 1836.06 99.20 -2.21E-02 3. llE-02

+ NB-94 702.63 100.00 -5.SOE-03 3.83E-02 3.83E-02 871.10 100.00 5 .13E-03 4.0SE-02

1/15/2019 2:34:06PM Page 6 of7 Analysis Report for L1-SUB-DRS-FJGS-W03-S8 L1-010-104-WEST PACKAGE : L1-SUB-DRS Nuclide Energy Yield(%) Activity NuclldeMDA LineMDA Name (pCi/grams) (pCilgrams) (pCi/grams)

(keV)

+ I - 131 284.30 6 . 06 2.79E-01 5.17E-02 6.44E - 01 364 . 48 8 1. 20 9.85E-03 5.17E-02 636.97 7.27 4.91E-01 6.82E-Ol

+ CS-134 604 . 70 97.60 -3.66E -0 2 4.81 E-02 4.81E-02 795.84 85.40 1 . 54E-02 4.86E-02

+ CS-137 661 . 65

• 85.12 2.87E-02 4.90E-02 4. 90E-0 2

+ CE-144 80.12 1. 36 l. l 6E+OO 2.70E-Ol 3.22E+OO 133. 51 11. 09 l.42E - Ol 2.70 E-O l

+ EU-152 121. 7 8 28. 40 -7 .83E- 02 l . 02E-01 l .0 2E-01 344.28 26 . 60 -l.65E-02 l.26E-01 1408.00 20.74 l. 63E-02 2.21E-01

+ EU-154 123.07 40.40 1.98E-02 7.25E- 02 7.25E-02 723. 30 19.70 -7.86E-02 2.06E - 01 1274 .5 1 35.50 4.21E-02 l .44E - Ol

+ EU-155 86.54 32 . 80 -l.12E-01 1. llE-01 l. ll E-0 1 105.31 21.80 -4.83E-0 2 1.41E-01

+ BI-214 609.3 1

• 46.30 8.40E-02 8.70E-02 8 . 70E-02 1120.29 15.10 -l. 85E-03 3.81E-01 1238 .11 5.94 -1.09E-01 9.82E-Ol 1377. 67 4 .11 3.84E-Ol l.06E+OO 1407.98 2.48 1.37E-01 l.85E+OO 1509.19 2.19 l.91E-Ol l.71E+OO 1764.49 15 . 80 3.65E-Ol 3.06E-01

+ PB-214 77 .11 10 .7 0 3.83E-0 1 9 . 82E-02 4.34E-01 295 . 21

• 19.20 l.57E-01 l.06E-01 351.92

• 37.20 6.42E-02 9 . 82E-02

+ PA-228 89.95 22.00 2.44E+OO l . OOE+OO 1. 71E+OO 93.35 35.00 3 .09E-Ol 1 .00E+OO 105 . 00 16 .30 - 3.58E-Ol l .98E+OO 129.22 2.97 -2.07E+OO 1.05E+Ol 338.32 5.30 -3.18E+OO 6.24E+OO 463. 00 13. 80 6.90E-01 2.68E+OO 911. 23 16.70 1. 58E+OO 3.58E+OO

+ AM-241 59.54 36.30 -7.9 5E -02 2.07E-01 2.07E-01

+ CM- 243 103.76 23 .0 0 1.53E-03 l.34E-01 1.34E-01 228 . 18 10.60 1.42E-02 2 . 72E-01 277.60 14.00 9.03E-02 2.21E-Ol

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

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

1/15/2019 2:34:06PM Page 7 of7 Analysis Report for L1-SUB-DRS-FJGS-W03-SB L1-010-104-WEST PACKAGE : L 1-SUB-DRS

1/15/2019 2:34:45PM Page I of7

~ ~~~pex-Gamma Analysis Report for L 1-SUB-DRS-FJGS-W04-SB L1-010-104-WEST PACKAGE : L1-SUB-DRS GAMMA SPECTRUM ANALYS/S Sample Identification  : L1-SUB-DRS-FJGS-W04-SB Sample Description  : L1-010-104-WEST PACKAGE: L1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 7.423E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 3/2/2018 12:33:00PM Acquisition Started  : 3/5/2018 2:53:0SPM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.7 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  : 5361 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:34:36PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:34:45PM Page 2 of7 Analysis Report for L 1-SUB-DRS-FJGS-W04-S8 L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76.16 14 7 - 161 152.87 3.68E+02 71.02 l.67E+03 3.42 M 2 87.26 167 - 191 175.06 l.18E+02 43.98 1. 04E+03 1. 62 m 3 92.73 167 - 191 186.00 1.19E+02 44.84 1. 04E+03 1. 63 F 4 185 . 81 364 - 376 372 .13 1 .62E+02 47.78 9.12E+02 2.36 F 5 209.16 411 - 426 418.81 7.29E+Ol 37.78 1. 08E+03 1. 62 F 6 238.60 472 - 485 477.6 8 5 .07E+0 2 57.34 7.73E+02 1. 88 F 7 295.03 584 - 597 590.52 l.58E+02 37.54 5.14E+02 1. 96 F 8 338.37 671 - 682 677 .17 1. 01E+02 33.06 3.41E+02 2.28 F 9 351.81 695 - 711 704.05 2 .70E+0 2 40.13 4.68E+ 02 1. 71 F 10 46 2 .86 920 - 930 926.10 3.8 4E+Ol 17.23 1. 61E+02 0. 96 F 11 583.14 1161 - 1170 1166.63 1. 53E+02 29.41 1. 35E+02 1. 62 F 12 609.23 1213 - 1226 1218.79 1.77E+02 31. 48 1.64E+02 2.03 F 13 661.49 1318 - 1328 1323.30 1.30E+02 27 . 91 1.31E+02 1. 85 F 14 727.27 1449 - 1459 1454. 83 3.62E+Ol 17.10 9.28E+Ol 1. 65 F 15 911.08 1816 - 1830 1822.39 9.56E+Ol 24.14 1. 23E+02 2.13 F 16 968. 80 1933 - 1943 1937.81 4.55E+Ol 19 .4 3 1.02E+02 1. 87 F 17 1119.81 2234 - 2245 2239.79 3.91E+Ol 17.45 7.20E+Ol 2.24 F 18 1460.47 2912 - 2930 2921. 04 6.49E+0 2 52.15 3.20E+Ol 2.59 F 19 1763.98 3523 - 3535 3528.03 3.34 E+Ol 13.40 2.33E+Ol 1. 91 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:34:36PM Env. Background File  : C:\Canberra\Apex\Root\Oairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 1 76.16 3.68E+02 71. 02 3.68E+02 7.lOE+Ol M 2 87.26 l.18E+0 2 43.98 l . 18E+02 4.40E+Ol m 3 92.73 1.19E+0 2 44.84 1.19E+02 4.48E+Ol F 4 185.81 l. 62E+0 2 47.78 1. 62E+02 4.78E+Ol F 5 209.16 7.29E+Ol 37.78 7 .29E+Ol 3.78 E+ Ol F 6 238 . 60 5.07E+02 57.34 5.07E+02 5.73E+Ol F 7 295.03 1. 58E+02 37.54 1.58E+02 3.75E+Ol F 8 338.37 1. 01E+02 33.06 1. 01E+02 3.31E+Ol F 9 351. 81 2.7 0E+02 40.13 8.36E+O l 3.72E+Ol 1.87E+02 5.47E+Ol F 10 4 62. 8 6 3.84E+Ol 17.23 3.84E+Ol 1 .72E+Ol

1/15/2019 2:34:45PM Page 3 of7 Analysis Report for L 1-SUB-ORS-FJGS-W04-S8 L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.

F 11 583.14 1.53E+02 29.41 1.53E+02 2.94E+Ol F 12 609.23 1.77E+02 31. 48 4.12E+Ol 2.42E+Ol 1.36E+02 3.97E+Ol F 13 661. 4 9 1.30E+02 27.91 6.61E+Ol 2.54E+Ol 6.36E+Ol 3.77E+Ol F 14 727. 27 3.62E+Ol 17.10 3.62E+Ol 1.71E+Ol F 15 911.08 9.56E+Ol 24.14 9.56E+Ol 2.41E+Ol F 16 968. 80 4.55E+Ol 19.43 4.55E+Ol 1.94E+Ol F 17 1119.81 3.91E+Ol 17.45 3.91E+Ol 1.75E+Ol F 18 1460.47 6.49E+02 52.15 S.63E+Ol 1. 71E+Ol 5.93E+02 5.49E+Ol F 19 1763.98 3.34E+Ol 13.40 1.52E+Ol 9.80E+OO l.83E+Ol l.66E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCilgrams) Uncertainty K-40 0.98 1460.75

• 10.67 8.70E+OO 9.39E-01 CS-137 0.99 661.65

• 85.12 5.78E-02 3.45E-02 BI-212 0.60 727.17

• 11. 80 2.59E-01 1.23E-01 785.42 2.00 1620.56 2.75 PB-212 0.96 77 .11

• 17.50 7.12E-01 1.45E-01 238.63

• 44.60 3.52E-01 4.38E-02 BI-214 0.77 609.31

• 46.30 2. llE-01 6.27E-02 1120. 29

• 15.10 3.22E-01 1.44E-01 1238 .11 5.94 1377. 67 4.11 1407.98 2.48 1509.19 2.19 1764.49

• 15.80 2 .12E-01 1.93E-01 PB-214 0.97 77 .11

• 10.70 1.16E+OO 2.37E-01 295.21

• 19.20 3.04E-01 7.38E-02 351. 92

• 37.20 2.17E-01 6.46E-02 RA-226 0.97 186.21

• 3.28 1.29E+OO 3.86E-01 AC-228 0.78 209.28

• 4.40 4.66E-Ol 2.43E-01 338.32

• 11. 40 3.68E-Ol 1. 23E-01

1/15/2019 2:34:45PM Page 4 of?

Analysis Report for L 1-SUB-ORS-FJGS-W04-SB L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty AC-228 0.78 794.70 4.60 911 . 60

• 27. 70 3 .57E-01 9.lSE-02 964.60 5.20 969 .11

• 16.60 2 .99E-01 l.29E-Ol

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K-40 0.987 8 . 70E+OO 9 . 39E-01 CS-137 0. 996 5.78E-0 2 3 .4 5E-02 BI - 212 0.604 2 . 59E-Ol l.23E-Ol PB- 212 0. 960 3 . 69E-01 4.20E-02 BI-214 0.774 2.27E-01 5.51 E-0 2 PB - 214 0.975 2.67E-01 4.77E-02 RA-226 0 . 975 l.29E+OO 3 . 86E-Ol AC-228 0.780 3.54E-O l 6 . 16E-02

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

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

1/15/2019 2:34:45PM Page 5 of7 Analysis Report for L 1-SUB-DRS-FJGS-W04-S8 L 1-010-104-WEST PACKAGE: L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:34:36PM 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 2 87.26 3.27350E-02 18.66 Tol. EU-155 m 3 92.73 3.30422E-02 18.85 Tol. PA-228 F 10 462.86 l.06665E-02 22.44 Tol. PA-228 F 11 583.14 4.25829E-02 9.59 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCl/grams) (pCl/grams) (pCilgrams)

(keV)

+ K-40 1460.75

• 10.67 8.70E+OO 6.92E-01 6.92E-Ol

+ AR-41 1293.64 99.16 -5.17E+l0 1. 33E+ll 1. 33E+ll

+ C0-60 1173.22 100.00 6.23E-02 6.lSE-02 8.28E-02 1332.49 100.00 -3.81E-03 6.lSE-02

+ KR-85 513.99 0.43 1.66E+Ol 1.26E+Ol 1. 26E+Ol

+ Y-88 898.04 93.70 -1.60E-04 4.38E-02 6.13E-02 1836.06 99.20 2.60E-03 4.38E-02

1/15/2019 2:34:45PM Page6 of7 Analysis Report for L1-SUB-DRS-FJGS-W04-S8 L1-010-104-WEST PACKAGE : L 1-SUB-DRS Nuclide Energy Yield(%) Activity Nuc/ldeMDA LineMDA Name (pCi!grams) (pCi/grams) (pCilgrams)

(keV)

+ NB-94 702.63 1 00.00 7 . 22E- 03 4. 85E- 02 4 .85E-02 87 1.1 0 100.00 - 4.26E- 0 2 5.3 1E-02

+ I-131 284 . 30 6.06 -7.00E- 01 6 . 55E-0 2 8 . 72E - 0 1 36 4 . 4 8 81. 20 -2.30E-02 6 . 55E-02 636.97 7 . 27 5 . 36E-02 8.89E-Ol

+ CS-134 6 04. 70 97.60 -l.81E- 02 6.61E-02 6 . 61E- 02 795.84 85.40 - 3.79E- 02 6 . 66E-0 2

+ CS -13 7 661. 65

• 85.12 5.78E-02 6 . llE-0 2 6 . ll E-0 2

+ CE-144 80.12 1. 36 -4 . llE-01 3.48E-01 4 . 41E+OO 133. 5 1 11. 09 -8.73£-03 3.48E-0 1

+ EU-152 121.78 28 . 40 - 7.22 £-0 2 1. 32£-01 1. 32E-O l 344.28 26.60 -3.82E-02 l.80E- Ol 1408 . 00 20.7 4 8.80E-02 2.70£-01

+ EU-154 123.07 40.4 0 - 3 .2 3E- 02 9.39E-02 9 . 39E-02 723.30 19.70 l.44E-01 2.72E-01 127 4. 51 35 .50 1. 22E-0 1 2.06E-O l

+ EU-155 86.54 32.80 -1. 53E-02 l.52E-01 1 . 52 E- 01 105.31 21. 80 -1. 32£-02 1 .79£-01

+ BI-214 609.31

• 46.30 2 . llE-01 l.08E-01 1. 08E-01 1120. 29

• 15 . 10 3.22E- 01 2 . 79E-Ol 1238 . 11 5.9 4 -2.31E-01 1.36E+OO 1377.67 4 .11 7. 1 5E-0 1 1. 38E+OO 1407.98 2.48 7 . 35E-0 1 2 . 26E+OO 1 509.19 2.19 3.97£-01 2 . 22E+OO 1764 .49

• 1 5.80 2. 12 E- 01 3.51£-01

+ PB- 214 77 . 11

• 10.70 1.16E+OO 1. 34 £- 01 5.2 1E-01 295 . 21

• 19.20 3.04£-01 1.74E-01 35 1 .92

• 37.20 2 .17E-01 1.34E-01

+ PA-228 89.95 22. 00 3.49E+ OO 1.38E+OO 2 . 36E+OO 93 . 35 35.00 2.79£-01 1. 38E+OO 105 . 00 16.30 -4.09E-01 2 .5 3E+OO 129.22 2.97 7.0lE+OO 1.37 E+Ol 338.32 5.30 5.34E+OO 9 . 15E+OO 463.00 13. 80 -3.16E+OO 3.47E +OO 911. 23 16.70 6.61E+OO 4.83E+OO

+ AM-24 1 59.54 36 . 30 1.92E-01 2. 71£- 01 2.71E-01

+ CM-24 3 103.76 23 . 00 -3 .0 0E-02 1 . 71E-01 1.71E-01 228 . 18 10 . 60 -1.80E-02 3.58E-01 277.60 14.00 -1.1 6E- 0 1 3 .0 2E-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

1/15/2019 2:34:45PM Page 7 of7 Analysis Report for L 1-SUB-DRS-FJGS-W04-SB L 1-010-104-WEST PACKAGE : L 1-SUB-DRS

1/15/2019 2:35:25PM Page I of7

,.Apex-Gamma Analysis Report for L1-SUB-DRS-FJGS-W05-SB L1-010-104-WEST PACKAGE : L1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FJGS-W05-SB Sample Description  : L1-010-104-WEST PACKAGE : L1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8.420E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 3/2/2018 12:43:00PM Acquisition Started  : 3/5/2018 3:55:17PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.8 seconds Dead Time  : 0.30%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100 - 4096 Peak Area Range (in channels)  : 100-4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5362 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:35:16PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:35:25PM Page 2 of7 Analysis Report for L 1-SUB-DRS-FJGS-W05-SB L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 87.12 170 - 181 174 . 79 8.31E+Ol 39.57 9.77E+02 1. 4 6 F 2 238.45 469 - 485 477.38 3.03E+02 46 . 15 6.93E+02 2 . 03 M 3 295.09 587 - 605 590 . 63 8.13E+Ol 27.91 2.69E+02 1. 53 m 4 299.99 587 - 6 05 600.43 3.31E+Ol 22.06 3 . 26E+02 1. 5 4 F 5 338.06 672 - 681 676.55 7.22 E+Ol 26 . 29 2.09E+02 1. 80 F 6 35 1. 72 699 - 708 703.87 1 . 66E+02 31. 83 1 .79E+02 1. 76 F 7 582 . 97 1160 - 1172 1166.28 9.22E+Ol 24.28 1.43E+02 1. 76 F 8 609 .13 1209 - 1225 1 218 . 60 1.13E+02 27 .04 1 .60E+02 2.46 F 9 66 1 .2 4 1317 - 1332 1322 . 80 1.03E+02 24.87 1.37E+02 2.09 F 10 911.1 0 1816 - 1828 1822.44 6 . 49E+Ol 20 . 22 9.37E+Ol 1. 79 F 11 11 20.26 2236 - 2247 2240.7 1 2.17E+ Ol 14. 00 5 . 80E+Ol 1. 90 F 12 14 60 .4 6 2911 - 2930 292 1. 03 5 . 15E+02 4 6 .12 3 . 00E+Ol 2 . 71 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:35:16PM 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 87.12 8.31E+Ol 39.57 8.31E+Ol 3 . 96E+Ol F 2 2 38.45 3 . 03E+02 46 . 15 3.03E+02 4 .62E+Ol M 3 295 . 09 8.13E+Ol 27.91 8 . 13E+Ol 2 . 79E+Ol m 4 299.99 3.31E+Ol 22 . 06 3.31 E+Ol 2.21E+Ol F 5 338 . 06 7. 22E+Ol 26 .29 7 . 22E+Ol 2 . 63E+Ol F 6 351. 72 1 . 66E+02 31. 83 8.36E+Ol 3 . 72E+O l 8.21E+Ol 4 . 90E+Ol F 7 582 . 97 9 . 22E+Ol 24.28 9.22E+Ol 2.43E+Ol F 8 609.13 1 . 13E+02 27 . 04 4 . 12E+Ol 2.42E+Ol 7 . 23E+Ol 3.63E+Ol F 9 661.24 1 . 03E+02 24 . 87 6.61E+Ol 2.54E+Ol 3.73E+Ol 3.55E+Ol F 10 911 . 10 6.49E+ Ol 20 . 22 6.49E+Ol 2 . 02E+Ol F 11 1120. 26 2.17 E+O l 14.00 2 . 17E+Ol 1.40E+O l F 12 1460.46 5 . 15E+0 2 4 6 .12 5.63E+Ol 1 .7 1E+Ol 4.59E+02 4.92E+Ol

1/15/2019 2:35:25PM Page 3 of7 Analysis Report for L 1-SUB-DRS-FJGS-W05-S8 L 1-010-104-WEST PACKAGE: L 1-SUB-DRS M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCi/grams) Uncertainty K-40 0.98 1460.75

• 10.67 5.94E+OO 7.17E-01 CS-137 0.97 661.65

• 85.12 2.99E-02 2.85E-02 PB-212 0.55 77.11 17.50 238.63

• 44.60 l.86E- Ol 2.98E-02 BI-214 0.58 609.31

• 46.30 9.88E-02 4.99E-02 1120.29

• 15.10 l.58E-01 l.02E-01 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 1.38E-01 4.79E-02 351.92

• 37.20 8.42E-02 5.04E-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 confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT

1/15/2019 2:35:25PM Page4of7 Analysis Report for l 1-SUB-DRS-FJGS-W05-SB L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K-40 0.987 5.94E+OO 7.17E-01 CS-137 0.974 2.99E-02 2.85E-02 PB-212 0.557 1.86E-01 2.98E-02 BI-214 0.582 1.lOE-01 4.48E-02 PB-214 0.717 l.12E-01 3.47E-02

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

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

1/15/2019 2:35:25PM Page 5 of7 Analysis Report for L 1-SUB-DRS-FJGS-W05-S8 L1-010-104-WEST PACKAGE : L 1-SUB-DRS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:35:16PM Peak Locate From Channel  : 100 Peak Locate To Channel  : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 87.12 2.30748E-02 23.82 Tol. EU-155 rn 4 299.99 9.20322E-03 33.29 F 5 338.06 2.00549E-02 18.21 Tol. AC-228 PA-228 F 7 582.97 2 . 56192E-02 13.16 F 10 911.10 l.80198E-02 15.58 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 2.000sigma NUCLIDE MDA REPORT Nuclide library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCVgrams) (pCVgrams) (pCi/grams)

(keV)

+ K-40 1460.75

• 10.67 5.94E+OO 6.lOE-01 6.lOE-01

+ AR-41 1293.64 99.16 9.15E+10 1.68E+ll 1. 68E+ll

+ C0-60 1173.22 100.00 2.26E-03 5.21E-02 6.78E-02

1/15/2019 2:35:25PM Page 6 of7 Analysis Report for L1-SUB-DRS-FJGS-W05-S8 L1-010-104-WEST PACKAGE : L1-SUB-DRS Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCilgrams)

(keV)

C0-6 0 1332.49 100.00 3.02E- 02 5.21E-02 5.2 1E-02

+ KR-85 513. 99 0 . 43 1.41E+Ol 1. 05E+Ol l. 05E +Ol

+ Y-88 898.04 93 . 70 2.91E-02 3.24E-0 2 5.3 1E-02 1 836.06 99.20 - 2 . 25E-02 3.24E-02

+ NB-94 702.63 100.00 5 . 17E-03 4.12E-02 4. 1 2E-02 87 1 . 1 0 1 00.00 3.66E- 02 4.63E - 02

+ I-131 284 . 30 6 . 06 -7.82E-03 5 . 13E- 02 6.99E-0 1 364.48 8 1. 20 - 2 . 71 E-0 2 5 .13E- 02 636.97 7.27 l.25E-01 7 . 3 1E- 0 1

+ CS-1 34 604.70 97.60 -8.26E-04 5.1 4E- 02 5.14E-02 795.84 85 .4 0 3.39E-02 5.25E-02

+ CS -1 37 661.65

• 85.12 2 . 99E- 02 5.71E-02 5.71E-02

+ CE-144 80.12 1. 36 2 . 97E+OO 2.68E-01 3.37E+OO 133.51 11. 09 - 2.09E- 01 2.68E-01

+ EU-152 121. 78 28 .4 0 -2.00E-02 l.04E-O l l .04 E-O l 344.28 26.60 -1. 37E- 01 1 . 31E-01 14 08 . 00 20.74 8.34E-02 2.19E-O l

+ EU-15 4 12 3 . 07 40.40 2.67E-02 7 . 39E-0 2 7.39E-02 723.30 1 9.70 2.16E - 02 2. llE-01 1274.51 35.50 -l .59E- Ol l.45E- 01

+ EU- 155 86.54 32 .8 0 - 7 . 58E- 02 l.17E-01 1.1 7E- 01 1 05.31 21. 80 - 2.28E-02 1. 44E-01

+ BI - 214 609.31

• 46. 30 9.88E-02 9.78E-02 9 . 78E-02 1120.29

• 15.10 l.58E- Ol 2.24E-01 1238 .11 5 .94 - 3 . 09E- 01 l.lOE+OO 1377 . 67 4 .11 -6.76E-01 1.1 2E+OO 1407.98 2 . 48 6.97E- 01 1. 83E+OO 1509.19 2.19 2 . 86E-01 1. 80E+OO 1764.49 1 5 . 80 2 . llE-01 3.17E-Ol

+ PB-214 77 .11 1 0 . 70 7 . 48E- 01 8.76E-02 4.64E-0 1 295.21

• 1 9 . 20 1. 38E-01 9.62E-02 351. 92

• 37 . 20 8.42E- 02 8.76E - 02

+ PA-228 89.95 22.00 7.32E-01 l.08 E+OO 1. 8 2E+OO 93 . 35 35.00 -l.41E-01 1. 08 E+ OO 1 05.00 1 6 . 30 -1. 20E+OO 2 . 09E+OO 1 29.22 2 . 97 4.94E+OO 1 . 09E+Ol 338.32 5.30 6.37E+OO 7 . 02E+OO 463.00 13.80 7 .0 3E- 01 2 . 9 1E+OO 911.23 1 6 .7 0 -8.84E-01 3 . 61E+OO

+ AM-241 59.54 36.30 - l . 37E- 01 2.16E-Ol 2. 1 6E -01

+ CM- 2 43 10 3.76 23 . 00 -5.94E-02 1. 37E-01 1. 37E-0 1 228.18 1 0.60 -1 .18E-Ol 2.75E-0 1 277.60 14.00 - 2 . 82E- Ol 2.30E- Ol

1/15/2019 2:35:25PM Page 7 of7 Analysis Report for L 1-SUB-DRS-FJGS-WOS-SB L 1-010-104-WEST PACKAGE : L1-SUB-DRS

+ = 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

1/15/2019 2:36:01PM Page I of7

~ Jti ~~pex-Gamma Analysis Report for L 1-SUB-DRS-FJGS-W06-S8 U-010-104-WEST PACKAGE : L 1-SUB-DRS GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FJGS-W06-S8 Sample Description  : L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8.805E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 3/2/2018 1:09:00PM Acquisition Started  : 3/5/2018 5:01:35PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli LiveTime  : 3600.0 seconds RealTime  : 3610.2 seconds Dead Time  : 0.28 %

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100 -4096 Peak Area Range (in channels)  : 100-4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5363 PEAK ANALYSIS REPORT Peak Analysis Performed on 1/15/2019 2:35:52PM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

1/15/2019 2:36:01PM Page 2 of7 Analysis Report for L 1-SUB-DRS-FJGS-W06-SB L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 76 . 81 147 - 161 154 . 17 2.16E+02 57. 62 1 .30E+03 2.78 F 2 238 .4 9 472 - 485 477 .4 5 2.72E+02 44.81 6.73E+02 1. 70 F 3 295 . 25 586 - 596 590.94 1.02E+02 29.13 3.37E+02 1. 33 F 4 337.92 672 - 680 676.27 5 .4 5E+Ol 22.97 2. 1 3E+02 1. 20 F 5 35 1. 71 699 - 709 703.85 1.58E+02 33.26 2.80E+02 1. 67 F 6 510.30 1012 - 1030 1020. 96 9.90E+Ol 28.59 2. 1 5E+02 3.56 F 7 582.95 1159 - 1172 1166.25 9. 09E+Ol 24.55 1.54E+02 1. 88 F 8 609 . 04 1 213 - 1223 1218.42 1.39E+02 27.23 9.85E+Ol 1. 79 F 9 911. 07 1815 - 1829 1822.38 5.97E+Ol 20.46 9.87E+Ol 2.25 F 10 1120.09 2235 - 2245 2240.37 2.33£+0 1 12.82 4.48E+Ol 1. 45 F 11 1331 . 70 2657 - 2668 2663.55 2 . 22E+ Ol 11. 77 3.00E+O l 1. 75 F 12 1460 .44 2914 - 2930 2920.99 4.92E+02 45.20 3.29E+Ol 2.53 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 1/15/2019 2:35:52PM 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. 81 2.16E+02 57.62 2 .1 6E+02 5.76£+01 F 2 238.49 2. 72E+02 44.81 2.72E+02 4.48E+Ol F 3 295.25 1. 02E+02 29.13 l .0 2E+02 2.91E+Ol F 4 337.92 5.45E+Ol 22 .9 7 5 .4 5E+Ol 2.30E+Ol F 5 351 .7 1 1. 58E+02 33.26 8.36E+Ol 3. 72E+Ol 7.39E+Ol 4.99E+Ol F 6 510 . 30 9.90E+Ol 28.59 9 . 90E+Ol 2 . 86E+Ol F 7 582.95 9.09E+Ol 24 . 55 9.09E+Ol 2 .4 6E+Ol F 8 609.04 l.39E+02 27.23 4.12E+Ol 2.42E+Ol 9.73E+Ol 3.64E+Ol F 9 911 . 07 5.97E+Ol 20 .4 6 5.97E+Ol 2.05E+Ol F 10 1120 . 09 2.33E+Ol 12.82 2 . 33E+Ol l.28E+Ol F 11 1331. 70 2 . 22E+Ol 11 . 77 2 . 22E+Ol l.18E+Ol F 12 1460 .4 4 4.92E+02 45 . 20 5.63E+Ol 1. 7 1E+Ol 4 . 36E+02 4.83E+Ol

1/15/2019 2:36:01PM Page 3 of7 Analysis Report for L 1-SUB-DRS-FJGS-W06-S8 L 1-010-104-WEST PACKAGE : L 1-SUB-DRS M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCilgrams) Uncertainty K-40 0.98 1460.75

• 10.67 5.39E+OO 6.69E-01 PB-212 0.99 77.11

• 17.50 3.47E-01 9.54E-02 238.63

• 44.60 l.59E-01 2.75E-02 BI-214 0.57 609.31

• 46.30 1. 27E-01 4.82E-02 1120.29

• 15.10 1.62E-01 8.93E-02 1238.11 5.94 1377. 67 4 .11 1407.98 2.48 1509.19 2.19 1764.49 15.80 PB-214 0.99 77.11

• 10.70 5.68E-01 l.56E-01 295.21

• 19.20 1.66E-Ol 4.80E-02 351.92

• 37.20 7.25E-02 4.91E-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 confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT

1/15/2019 2:36:01 PM Page 4 of7 Analysis Report for L 1-SUB-DRS-FJGS-W06-SB L1-010-104-WEST PACKAGE : L 1-SUB-DRS Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K-4 0 0.984 5.3 9E+OO 6.69E-0 1 PB- 212 0 . 994 1 . 68E- 01 2.65E - 02 BI - 21 4 0 . 578 1 . 35E- 01 4 .24 E- 02 PB- 21 4 0 . 99 4 1. 28E - 01 3.36E- 02

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

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

1/15/2019 2:36:01 PM Page 5 of7 Analysis Report for L 1-SUB-DRS-FJGS-W06-S8 L 1-010-104-WEST PACKAGE : L 1-SUB-ORS UNIDENTIFIED PEAKS Peak Locate Performed on  : 1/15/2019 2:35:52PM 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 4 337.92 1. 51307E-02 21. 09 Tol. AC-228 PA-228 F 6 510.30 2.75019E-02 14.44 F 7 582.95 2.52598E-02 13.50 F 9 911.07 l.65735E-02 17.14 Tol. AC-228 PA-228 F 11 1331.70 6.15329£-03 26.57 Tol. C0-60 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pC/lgrams) (pC/lgrams) (pCi/grams)

(keV)

+ K-40 1460.75

• 10.67 5.39E+OO 5.76E-01 5.76E-Ol

+ AR-41 1293.64 99.16 3.85E+l0 2. 05E+ll 2. 05E+ll

+ C0-60 1173.22 100.00 5.51£-03 5.41E-02 6.07E-02 1332.49 100.00 6.05£-02 5.41E-02

+ KR-85 513.99 0.43 -2.05E+OO 9.69E+OO 9.69E+OO

+ Y-88 898.04 93.70 3.84E-02 3.20E-02 4.79E-02 1836.06 99.20 -1. 24E-02 3.20E-02

+ NB-94 702.63 100.00 -3.38E-02 3.89E-02 3.89E-02 871.10 100.00 -1.69£-02 4.12E-02

1/15/2019 2:36:01PM Page 6 of7 Analysis Report for L 1-SUB-DRS-FJGS-W06-S8 L 1-010-104-WEST PACKAGE : L 1-SUB-DRS Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCilgrams)

{keV)

+ I -1 31 284.30 6.06 2.35E-02 4.86E-02 6.82E-01 364.48 81.20 -3.96E-02 4. 86E-02 636.9 7 7 .27 4.45E-01 6 . 81E-Ol

+ CS-134 604.70 97.60 8.86E-02 4.73E-02 4.95E-02 795 . 8 4 85.40 1. 76E-02 4.73E-02

+ CS - 137 661.65 85 .1 2 5 . 28E-02 5.37E-02 5.37E-02

+ CE-144 80 . 12 1. 36 - 6.54E -0 1 2. 72E-Ol 3.26E+OO 133.51 11. 09 4.17E-02 2. 72E-01

+ EU-15 2 1 21 .78 28.40 - 2.23E-0 2 1 .03E- Ol 1. 03E-01 344 . 28 26 . 60 -1. 30E-01 l.31E-Ol 1 408 . 00 20.74 -4 .77E-02 2 . 22E-Ol

+ EU-154 1 23.07 40 . 40 - 7.63E- 0 3 7 . 27E- 02 7 . 27E-02 723 . 30 1 9 . 70 - l.99E-02 l.98E- 0 1 1 274.5 1 35.50 -7.80E-03 l.42E- Ol

+ EU-155 86.54 32.80 -l.1 4E-02 l . 13E-01 l.13E-01 105.31 21.80 -8.51E-02 1. 33E-0 1

+ BI-214 609.31

• 46.30 l . 2 7E-Ol 7.86E-02 7.86E- 02 11 20.29

• 1 5.10 l.62E -01 l.88E-01 1 238. 11 5.94 1. 20E+OO l.16E+OO 1377. 67 4 .11 2 . 31E-0 1 l.OlE+OO 14 07.98 2.48 -3 . 98E-01 l .8 5E+00 1 509.19 2.19 7.50E-01 l.64E+OO 1764.49 15.80 2 .36E-O l 3.15E- Ol

+ PB-214 77.11

• 10.70 5.68E -01 9.20E-02 3.82E-01 295.2 1

• 1 9.20 1. 66E-01 l.12E-01 35 1. 92

• 37 . 20 7.25E-02 9.20E-02

+ PA-228 89.95 22.00 l.52E+OO 1. 05E+OO l.81E+OO 93.35 35.00 -6.36E-01 l.05E+OO 1 05.00 1 6 . 30 - 6.57E -01 l.99E+OO 129.22 2.97 5.50E+OO l.lOE+Ol 338.32 5 . 30 4.66E+OO 6.90E+OO 463.00 1 3.80 -5.99E-Ol 2.76E+OO 911.23 16.70 6.17E+OO 3.78E+OO

+ AM-241 59.54 36.30 2 . 35E-02 2 .02E-Ol 2.02E-Ol

+ CM-243 103. 76 23 . 00 2.39E-03 l . 28E-O l 1.28E-01 228 .1 8 1 0.60 1. 08E-01 2.80E-01 277.60 14.00 1.02E-01 2.23E-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

1/15/2019 2:36:01 PM Page 7 of7 Analysis Report for L1-SUB-DRS-FJGS-W06-SB L1-010-104-WEST PACKAGE : L 1-SUB-DRS

10/ 18/2018 8:52:08AM Page I of?

...t,Apex-Gamma Analysis Report for L 1-SUB-DRS-FSGS-W05-SB SPLIT

\

02/27/18 - 0927 GAMMA SPECTRUM ANALYSIS Sample Identification  : L 1-SUB-DRS-FSGS-W05-SB SPLIT Sample Description  : 02/27/18 - 0927 Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 9.496E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 2/27/2018 9:27:00AM Acquisition Started  : 10/16/2018 3:15:50PM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 3600.0 seconds Real Time  : 3610.7 seconds Dead Time  : 0.30%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100 - 4096 Peak Area Range (in channels)  : 100-4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5072 PEAK ANALYSIS REPORT Peak Analysis Performed on  : 10/18/2018 8:51:59AM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

10/18/2018 8:52:08AM Page 2 of7 Analysis Report for L 1-SUB-DRS-FSGS-W05-S8 SPLIT 02/27/18 - 0927 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 1 86 . 2 0 365 - 376 372. 90 5 . 75E+Ol 29.63 6 .40E+0 2 1.13 F 2 23 8. 81 472 - 485 478.09 2.96£+0 2 47.88 5.75E+02 2.5 1 F 3 295 .0 8 586 - 595 590 . 62 8 . 03E+ Ol 29.85 3 . 17E+ 02 1. 64 F 4 352. 00 697 - 708 704 . 44 1.55E+0 2 33.09 2 . 37 E+02 2 . 21 F 5 4 63 . 37 922 - 931 927 .13 2.15E+ Ol 13.38 1. 03E+02 0 .8 9 F 6 583.42 1161 - 11 7 3 11 67 .18 7 . 36E+Ol 22. 1 3 1. 04 E+02 2 . 16 F 7 60 9 . 55 1212 - 122 8 1 219 . 43 1 .3 0E+0 2 27.03 1.14E+02 2 . 65 F 8 662. 0 1 131 8 - 1332 1 324 . 33 1. 01 E+0 2 25 . 56 1. 24 E+02 2 . 73 F 9 846 . 77 16 87 - 1697 1 693 .8 0 2.12E+Ol 1 2.76 5 . 22E+O l 1. 4 1 F 10 911 . 00 1815 - 1829 1 822 . 24 7. 02E+Ol 20 . 5 1 8 . 25E+Ol 2 . 22 F 11 1119 . 76 2236 - 2247 2239 . 69 2 . 0 5E +Ol 6. 1 3 6 . 00E+Ol 0. 66 F 12 1 4 61.13 29 1 3 - 2930 2922 . 37 5.05E+02 4 5.39 1 . 76E+Ol 2 . 85 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 10/18/2018 8:51:59AM 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 1 186.20 5.75E+ Ol 29.63 5 . 75E+ Ol 2 . 96E+ Ol F 2 238 . 81 2.96E+ 02 47 . 88 2 . 96E+02 4.79E+Ol F 3 295.08 8.03E+Ol 29 . 85 8 . 03E+ Ol 2.99E+Ol F 4 352.00 1. 55E+02 33.0 9 8.36E+O l 3. 72E+Ol 7. llE+ Ol 4 . 98E+Ol F 5 463 . 3 7 2. 1 5E+Ol 13 . 38 2 . 15E+ Ol 1. 3 4E+O l F 6 5 83. 4 2 7.36E+Ol 22.13 7.36E+O l 2.21E+ Ol F 7 609.55 1. 30E+02 27.03 4 . 12E+O l 2.42E+Ol 8 . 93E+ Ol 3.63E+O l F 8 662.01 1 .01E+02 25 . 56 6 . 61E+O l 2.54 E+Ol 3 . 48E+ Ol 3.60E+ Ol F 9 846 . 77 2. 1 2E+ Ol 12.76 2 . 12E+ Ol l .28E+Ol F 10 911. 00 7.02E+Ol 20 . 5 1 7 .0 2E+ Ol 2. 05E+ Ol F 11 1 119. 76 2.05E+ Ol 6 . 13 2. 0 5E+O l 6 .13E+OO F 12 14 61. 1 3 5.05E+02 45.39 5.63E+O l 1. 71E+Ol 4.49E+ 02 4.85E+O l

10/18/2018 8:52:08AM Page 3 of7 Analysis Report for L 1-SUB-DRS-FSGS-W05-S8 SPLIT 02/27/18- 0927 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 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) (pCilgrams) Uncertainty K-40 0.97 1460.75

• 10.67 5.15E+OO 6.26E-01 CS-137 0.98 661. 65

• 85.12 2.51E-02 2.61E-02 PB-212 0.55 77.11 17.50 238.63

• 44.60 1.61E-01 2.73E-02 BI-214 0.57 609.31

• 46.30 1. 08E-01 4.45E-02 1120.29

• 15.10 1.32E-01 3.99E-02 1238 .11 5.94 1377. 67 4.11 1407.98 2.48 1509.19 2.19 1764.49 15.80 PB-214 0. 72 77 .11 10.70 295.21

• 19.20 1. 21E-01 4.54E-02 351.92

• 37.20 6.47E-02 4.54E-02 RA-226 1. 00 186.21

• 3.28 3.57E-01 l.85E-01

• =Energy line found in the spectrum.

- =Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT

10/ 18/2018 8:52:08AM Page 4 of 7 Analysis Report for l 1-SUB-DRS-FSGS-W05-SB SPLIT 02/27/18 - 0927 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K-4 0 0.978 5 . 15E+OO 6.26E-01 CS - 137 0.980 2. 51E- 02 ,./ 2.61E-02 PB- 212 0 . 556 1 . 61E- 0 1 2.73E- 02 BI- 21 4 0 .57 3 1. 2 2E - 01 2 . 97E- 02 PB- 21 4 0 .7 20 9 .29E- 02 3 . 21E-02 RA- 226 1. 000 3.57E- 01 1. 85E- 01

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

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

10/18/2018 8:52:08AM Page 5 of7 Analysis Report for L1-SUB-DRS-FSGS-W05-SB SPLIT 02/27/18 - 0927 UNIDENTIFIED PEAKS Peak Locate Performed on  : 10/18/2018 8:51:59AM 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 5 463.37 5. 96221E-03 31.16 Tol. SB-125 PA-228 F 6 583.42 2.04390E-02 15.04 F 9 846.77 5.89133E-03 30.09 F 10 911. 00 1.94957E-02 14 . 61 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 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCl/grams) (pCl/grams) (pCUgrams)

(keV)

+ K-40 1460.75

• 10.67 5.lSE+OO 5.06E-01 5.06E-01

+ @ AR-41 1293.64 99.16 1.00E+26 1.00E+26 1.00E+26

+ C0-60 1173.22 100.00 -1.45E-02 4. 91E-02 ......- 5.34E-02 1332.49 100. 00 3.07E-02 4.91E-02

+ KR-85 513.99 0.43 1.35E+Ol 8.90E+OO 8.90E+OO

+ Y-88 898.04 93.70 1. 7 SE-01 1.58E-01 1.87E-01 1836.06 99.20 -3.07E-02 1.58E-01

+ NB-94 702.63 100.00 -4.18E-03 3.49E-02 3.49E-02 871.10 100.00 -3.97E-02 3.54E-02

10/18/2018 8:52:08AM Page 6 of7 Analysis Report for L 1-SUB-DRS-FSGS-WOS-SB SPLIT 02/27118 - 0927 Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCilgrams) (pCilgrams) (pCl/grams)

(keV)

+ I-131 284.30 6.06 9.27E+07 1. 44E+07 2 . 07E+08 364.48 81. 20 -l. 24E+07 l.44E+07 636 . 97 7 . 27 -5.21E+07 l . 91E+08

+ CS-1 34 604.70 97.60 -2.4 7E-03 5.23E-02 5 . 23E- 02 795.84 85 .40 l.31E - 02 S.59E-02

+ CS - 137 661.65

• 85.12 2.51E-02 4. 99E-02 / 4.99E- 02

+ CE - 144 80.12 1. 36 2.45E+OO 4 .00E-01 S . 17E+OO 133.51 11. 09 3 .46E-02 4.00E- 01

+ EU-15 2 121.78 28 .40 -6.lOE-02 9 .1 8E-02 II 9 .1 8E-02 244.69 7 .49 - 3 . 07E- 01 4.29E- 01 964.00 14 . 44 3 . 67E-01 3.62E-01 1408.00 20.7 4 l.61E-01 l .83E- 0 1

+ EU - 154 123.0 7 40.40 -3.59E-02 6. 61E-02 ./ 6.61E- 02 247.94 6.60 -S.5 6E - 01 4 . 45E- Ol 723. 30 19.70 -1. 4 9E-Ol l.85 E- Ol 873 . 20 11. so 8 .15E- 02 3 . 33E- 01 1004.76 17.90 -l.l OE-01 2 . 60E-Ol 1 27 4.51 35.50 -3.59E-02 l.36E-01

+ EU-155 86.54 32.80 -5. 24E- 02 l.13E-01 l.13E-Ol 105.31 21. 80 -9.94E- 02 1. 37E-O l

+ BI-214 609.31

• 46 .30 l . 08E-Ol 7.98E - 02 7 . 98E-02 1120.29

• 15 . 10 l . 32E-01 2.02E- 01 1238 . 11 5.94 6 . 1 7E-01 1. 02E+OO 1377 . 67 4 . 11 - 1.2SE- Ol 1. 04E+OO 1407.98 2 . 48 1. 30E+OO 1.48E+OO 1 509.19 2 .19 l . 80E-03 l.47E+OO 1 764 .49 15.80 2 . 25E-01 2 . 74E-01

+ PB- 214 77 . 11 10.70 7 . 13E-01 8.32E-02 4.0 6E-01 295 . 21

• 19 . 20 l.21E-01 9.83E-02 351. 92

• 37 . 20 6.47E-02 8 . 32E-02

+ @ PA-228 89.95 22 .00 l.O OE+26 1 . 00E+26 l .OOE+26

@ 93 . 35 35 . 00 l.OOE+26 l.OOE+26

@ 105 . 00 16.30 l.OOE+26 1.00E+26

@ 129.22 2 . 97 l.OOE+26 1.00E+26

@ 338 . 32 5 . 30 l . OOE+26 1. OOE+26

@ 463 . 00 13 . 80 l . OOE+26 l.OOE+26

@ 91 1. 23 1 6.70 l . OOE+ 26 1.00E+26

+ AM-241 59 . 54 36 . 30 4.18E-02 l . 99E-01 1. 99E-01

+ CM-243 103.76 23 . 00 -2.70E-02 l . 22E-01 l . 22E-01 228 .1 8 1 0 . 60 -l.15E-O l 2.37E-Ol 277 . 60 14 . 00 -S.21E-02 2.07E-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

10/18/2018 8:52:08AM Page 7 of7 Analysis Report for L1-SUB-DRS-FSGS-W05-SB SPLIT 02/27/18 - 0927

10/18/2018 8:48:11AM Page I of5 Analysis Report for L 1-SUB-DRS-FJGS-W03-S8 SPLIT 03/02/18

• 1057 GAMMA SPECTRUM ANALYSIS Sample Identification  : L1-SUB-DRS-FJGS-W03-S8 SPLIT Sample Description  : 03/02/18 - 1057 Sample Type  : 500 ml Marinelli Unit Sample Point Sample Size 8.518E+02 grams Facility  : Dairyland_NPP Sample Taken On  : 3/2/2018 10:57:00AM Acquisition Started  : 10/16/2018 9:35:44AM Procedure  : 500ml Marinelli Operator  : Administrator Detector Name  : HOTLAB Geometry  : 500ml Marinelli Live Time  : 1800.0 seconds Real Time  : 1805.1 seconds Dead Time  : 0.28%

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 100 - 4096 Peak Area Range (in channels)  : 100

• 4096 Identification Energy Tolerance  : 1.000 keV Energy Calibration Used Done On  : 7/8/2014 Efficiency Calibration Used Done On  : 7/8/2014 Efficiency Calibration Description Sample Number  : 5066 PEAK ANALYSIS REPORT Peak Analysis Performed on 10/18/2018 8:48:01AM Peak Analysis From Channel  : 100 Peak Analysis To Channel  : 4096

10/18/2018 8:48:11AM Page 2 of5 Analysis Report for L 1-SUB-DRS-FJGS-W03-S8 SPLIT 03/02/18 - 1057 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)

F 1 238.38 473 - 484 477 . 24 l.17E+02 29 .14 2.2 1E+02 1. 97 F 2 582 . 70 1160 - 1172 1165. 75 4.36E+Ol 15 . 69 4.60E+ Ol 1. 72 F 3 609.35 1 215 - 1225 1219.03 5 . lOE+Ol 17.10 4.03E+Ol 2.07 F 4 662.07 1318 - 1330 1324.46 5 . 43E+Ol 18.39 5.85E+Ol 2.36 F 5 1460.98 2913 - 2932 2922.08 2.04E+02 29 . 11 l.90E+Ol 2. 64 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on  : 10/18/2018 8:48:01AM 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 1 238.38 l.17E+02 29.14 l . 17E+02 2 . 91E+Ol F 2 582.70 4.36E+Ol 1 5 . 69 4.36E+O l l.57E+Ol F 3 609 . 35 5 . lOE+Ol 1 7. 1 0 2.06E+Ol l. 21E+Ol 3.04E+O l 2.lOE+ Ol F 4 662 . 07 5.43E+Ol 1 8.39 3.31E+Ol l.27E+Ol 2.12E+Ol 2.23E+O l F 5 1460.98 2.04E+02 29 . 11 2.82E+Ol 8.57E+OO l.76E+ 02 3.03E+ Ol M = First peak in a multiplet region

=

m Other peak in a multiplet region

=

F Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES

10/18/2018 8:48:11AM Page 3 of 5 Analysis Report for L 1-SUB-DRS-FJGS-W03-SB SPLIT 03/02/18 - 1057 Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K- 40 0 . 99 1 460 . 75

• 1 0 . 67 4 . 51E+OO 8 . 16E-Ol CS - 137 0 . 97 661.65

• 85 . 12 3 . 41E - 02 3.60E- 02 PB- 212 0.55 7 7 . 11 1 7 . 50 238.63

• 44.60 l.41 E- 01 3. 60E- 02 BI - 214 0 . 35 609 . 31

• 46.30 8.22E- 02 5 . 69E- 02 1120 . 29 15.10 1238 . 11 5 . 94 1377 . 67 4 . 11 1 407.98 2.48 1509 . 19 2 . 19 1764. 4 9 1 5. 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 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)

K- 40 0 . 991 4.51 E+OO 8 . 16E- 01 CS -1 37 0 . 972 3.41 E- 02 3 . 60E- 02 PB- 212 0 . 5 53 l . 41 E-Ol 3 . 60E- 02 BI- 214 0 . 350 8 . 22E - 02 5 . 69E- 02

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

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

10/18/2018 8:48:11AM Page 4 of 5 Analysis Report for L1-SUB-DRS-FJGS-W03-S8 SPLIT 03/02/18 - 1057 UNIDENTIFIED PEAKS Peak Locate Performed on  : 10/18/2018 8:48:01AM 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 2 582 . 70 2 . 42295E- 02 1 7 . 99 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used  : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCilgrams)

(keV)

+ K- 40 1460 . 75

• 10.67 4 . 51E+OO 8 . 17E- 01 8 . 17E-01

+ @ AR-41 1 293.64 99 . 16 1. 0 0E+26 1.00E+26 1 . 00E+26

+ C0- 60 1173 . 22 100 . 00 9 . 89E-02 6 . 98E-02V 9 . 42E- 02 1332 . 49 100 . 00 - 1. 44E-02 6 . 98E-02

+ KR- 85 513 . 99 0 . 43 7 . 90E+OO 1. 4 7E+Ol 1.47E+Ol

+ Y- 88 898 . 0 4 93.70 1.16E-01 2 . 20E-01 2 . 92E-01 1836 . 06 99 . 20 - 4 . 76E- 02 2 . 20E-01

+ NB -94 702 . 63 1 00.00 - 8 . 33 E- 03 4 . 98E-02 4 . 98E-02 871.10 100.00 -2 . 66E-02 6 . 66E-02

+ I-1 3 1 284 . 30 6.06 8 . 42E+06 1. 81E+07 2 . 41E+08 36 4.4 8 81. 20 1 . 23E+06 1. 81E+07 636.97 7.27 2 . 55E+07 2.49E+08

+ CS - 134 604 . 70 97.60 - 1 . 0 4E- 01 8 . 66E-02 8 . 66E-02 795.84 85.40 -4 . 42E-03 8. 7 2E- 02

+ CS - 137 66 1. 65

• 85.12 3.4 1E- 02 6. 93E- 02/ 6 . 93E-02

+ CE - 144 80.12 1. 36 5 . 48E+OO 6.26E-01 8 . 03E+OO 133 . 51 11. 09 7 . 27E-02 6.26E-01

10/1 8/2018 8:48:11AM Page 5 of5 Analysis Report for L 1-SUB-DRS-FJGS-W03-SB SPLIT 03/02/18

• 1057 Nuclide Energy Yield(%) Activity Nuc/ldeMDA LineMDA Name (pCi/grams) (pCi/grams) (pCilgrams)

(keV)

+ EU- 152 1 21.78 28 . 40 l . 56 E- 02 1 . 47E - Ol / l . 47E- 01 244 . 69 7.49 -3.95E- 01 6 . 61E- 01 964 . 00 14.4 4 8 . 47E - 02 4 . 83E-Ol 1 408 . 00 20.74 l.98E - 02 3 . 16E- 01

+ EU- 154 123.07 4 0 . 40 - 4 . 34 E- 02 1. 04E- Ol l 1.04E- 01 247.9 4 6 . 60 - 7.69E- 0 1 7 . 26E- 01 723.30 19.70 2 . 4 4E- 01 3 . 21E- 01 873.20 1 1 . 50 -l .OS E- 0 1 6 .l OE - 01 1 00 4 .76 17 . 90 1. 4 9E- 0 1 4.04E - 01 1274.51 35 . 50 1. lOE- 01 2.14E - 01

+ EU- 155 86 . 54 32.80 - 8 . 51E-02 l.77E- 01 1 . 77E - 01 1 05 . 31 21. 80 - 6.SOE- 02 2 . 08E- 01

+ BI - 2 14 6 09 . 31

• 4 6.30 8.22 E- 02 9.92E- 02 9 . 92E- 02 1120 . 29 15 .1 0 - l . l SE- 01 5.16E- Ol 1238 . 11 5 . 94 6 . 87E- 01 l . 43E+OO 1377 . 67 4 . 11 5 . 92E- 01 1 . 31E+OO 1407 . 98 2 . 48 1 . 60E- Ol 2 . 56E+OO 1 5 09.19 2 .1 9 5 . 51 E- 01 2 . 23E+OO 1764. 4 9 15 .8 0 4 . 45E - 01 4 . 97E- 01

+ PB- 214 77 . 11 1 0 . 70 2 . 09E- 01 l . 40E- 01 6 . 23E- 01 295 . 21 19.20 4.79E- 02 2 . 54E- Ol 351 . 92 37.20 l. 23E - 01 1. 40E- 01

+ @ PA- 228 89 . 9 5 22 . 00 l. OO E+26 l. OOE+26 1.00E+26

@ 93 . 35 35 . 00 1.00E+26 l.OOE+26

@ 1 05 . 00 16 . 30 l.OOE+2 6 1. OOE+26

@ 1 29 . 22 2 . 97 1. OOE+26 1. OOE+26

@ 338 . 32 5.30 l . OOE+ 26 1. 00E+26

@ 46 3.00 1 3.80 l. OOE+ 26 1.00E+26

@ 911.23 16.70 1. OOE+26 1.00E+26

+ AM- 241 59.54 36 . 30 l . 24E - 01 3 . 13E- Ol 3 . 13E- 01

+ CM-2 43 103 . 76 23 . 00 6 . 37E- 02 1. 8 7E- 01 l.87E- 01 228.18 1 0.60 6 . 63 E- 02 3 . 9 1E- 01 277.60 1 4 . 00 -l. 48 E- Ol 3 . 07 E- 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

FSS RELEASE RECORD L1-010-104 WEST EXCAVATION SURVEY UNIT L1-SUB-DRS ATTACHMENT 8 GEL LABORATORIES ANALYTICAL REPORTS

fflij11 /Laboratories LLC a member of The GEL Group INC Cl:arl.ston SC 2~*4.*,

P 64:5!-G~FI F 84: 7i .(. 1*1~

gel.com April 17, 20 18 Mr. Jason Q. Spaide LaCrosseSolutions S460 I State Hwy 35 Genoa, Wisconsin 54632 Re: LACBWR Site Restoration Project Work Order: 446394

Dear Mr. Spaide:

GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results fo r the sample(s) we received on March 22, 20 18. 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) 556-81 7 1, ext. 4453 .

Sincerely, Edith Kent Project Manager Purchase Order: 672583 Enclosures

.!JIii 11111111111 111111 .111111 111111111 i

GEL LABO RA TORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report for ENRG070 LaCrosseSolutions, LLC (672583)

Client SDG: 446394 GEL Work Order: 446394 The Qualifiers in this report are defined as follows:

• A quality control analyte recovery is outside of specified acceptance criteria

• • Analyte is a Tracer compound

• • Analyte is a surrogate compound U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.

UI Gamma Spectroscopy--Uncertain identification Where the analytical method has been 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 age 2 of 27

GEL LABORATORIES * .C 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 17,2018 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-LES-FSGS-001-SB Project: ENRG07001 Sample ID: 446394001 Client ID: EN RG070 Matrix: Soil Collect Date: 02-FEB- 18 13:45 Receive Date: 22-MAR-18 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method

~ad Gas Flow Proportional Counting

iFPC, Sr90, Solid "Dry Weight Corrected" arontium-90 U 0.0364 +/-0.0927 0. 159 0.400 pCi/g KSDI 04/02/18 1804 1749761 fhe following Prep Methods were performed:

vfethod Description Analyst Date Time Prep Batch

)ry Soil Prep Dry Soil Prep GL-RAD-A-021 JXOI 03/22/18 1330 1749454 The following Analytical Methods were performed:

\1ethod Description Analyst Comments EPA 905.0 Modified/DOE RP501 Rev. I Modified

,urrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits itrontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 93 (25%-1 25%)

\Totes:

ounting 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 age 3 of 27

GEL LABORATORIES . _C 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 17, 2018 Company: LaCrosseSolutions Address : S460 I State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q . Spaide Project: LACBWR Site Restoration Project Client Sample ID: L 1-SUB-LES-FSGS-O 12-SB Project: ENRG07001 Sample ID: 446394002 Client ID: ENRG070 Matrix: Soil Collect Date: 02-FEB-18 14:45 Receive Date: 22-MAR-18 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method lad Gas Flow Proportional Counting

]FPC, Sr90, Solid "Dry Weight Corrected" itrontium-90 U 0. 115 +/-0.110 0.183 0.400 pCi/g KSDI 04/02/ 18 1804 1749761 fbe following Prep Methods were performed:

"1.ethod Description Analyst Date Time Prep Batch

)ry Soil Prep Dry Soil Prep GL-RAD-A-021 JXOI 03/22/ 18 1330 1749454 The following Analytical Methods were performed:

\1ethod Description Analyst Comments EPA 905.0 Modified/DOE RP501 Rev. I Modified

urrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits

,trontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 97.7 (25%- 125%)

IJotes:

ounting Uncertainty is calculated at the 95% confidence level (J .96-sigma).

Col umn 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 age 4 of27

GEL LABORATORIES l .C 2040 Savage Road Charleston SC 29407. (843) 556-8171 . www.gel.com Certificate of Analysis Report Date: April 17, 2018 Company: La Crosse Solutions Address: S460 l State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: LI-SUB-DRS-FSGS-Wl2-SB Project: ENRG07001 Sample JD: 446394003 Client ID: ENRG070 Matrix: Soil Collect Date: 27-FEB-I 8 08:48 Receive Date: 22-MAR-18 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method lad Gas Flow Proportional Counting JFPC, Sr90, Solid "Dry Weight Corrected"

trontium-90 U -0.0222 +/-0.0755 0.134 0.400 pCi/g KSDI 04/02/18 1805 1749761 rhe following Prep Methods were performed

"1ethod Description Analyst Date Time Prep Batch

)ry Soil Prep Dry Soil Prep GL-RAD-A-021 JXOI 03/22/ 18 1330 1749454 The following Analytical Methods were performed:

\.1ethod Description Analyst Comments EPA 905.0 Modified/DOE RP501 Rev. I Modified

urrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits

,trontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 102 (25%-125%)

1/otes:

=:ounting 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 age 5 of 27

GEL LABORATORIES 1..._C 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 17, 2018 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L 1-SUB-DRS-FSGS-W 14-SB Project: ENRG07001 Sample JD: 446394004 Client ID: ENRG070 Matrix: Soil Collect Date: 27-FEB-18 08:31 Receive Date: 22-MAR-18 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method lad Gas Flow Proportional Counting

iFPC, Sr90, Solid "Dry Weight Corrected" itrontium-90 U 0. 103 +/-0.0922 0.153 0.400 pCi/g KSD l 04/02/ 18 1805 174976 I fne following Prep Methods were performed:

\11ethod Description Analyst Date Time Prep Batch

)ry Soil Prep Dry Soil Prep GL-RAD-A-021 JXOI 03/22/18 1330 1749454 The following Analytical Methods were performed:

\1ethod Description Analyst Comments EPA 905.0 Modified/DOE RP501 Rev. I Modified

,urrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits itrontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 95 .3 (25%-125%)

~otes:

ounting 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 age 6 of 27

GEL LABORATORIES L_.:

2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 17, 2018 Company: LaCrosseSolutions Address: S460 I State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-SUB- I 03-AJGS-002-SB Project: ENRG07001 Sample JD: 446394005 Client ID: ENRG070 Matrix: Soil Collect Date: 23-FEB-18 14:03 Receive Date: 22-MAR-18 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method lad Alpha Spec Analysis

\lphaspec Isotopic Am24 I Am243, Cm243/244, Solid "Dry Weight Corrected" l.mericium-241 U -0.0132 +/-0.0259 0.0722 0.400 pCi/g HAKB 03127/18 0906 1749552 l.mericium-243 U 0.00638 +/-0.0667 0.139 0.400 pCi/g

urium-243/244 U 0.00 +/-0.0161 0.0239 0.400 pCi/g

\lphaspec Np, Solid "Dry Weight Corrected"

./eptunium-237 U -0.000991 +/-0.00238 0.00548 0.0 10 pCi/g HAKB 03/27/18 1346 1749553 2

\lphaspec Pu238, 239/240, Solid "Dry Weight Corrected"

'lutonium-238 U 0.0149 +/-0.0293 0.0406 0.400 pCi/g HAKB 03/27/ 18 0906 1749554 3

'lutonium-239/240 U 0.0193 +/-0.0341 0.0517 0.400 pCi/g jquid Scint Pu241, Solid "Dry Weight Corrected"

'lutonium-241 U -0.703 +/-2.45 4. 19 5.00 pCi/g HAKB 03/28/ 18 1012 1749555 4 lad Gamma Spec Analysis 3amma Ni59, Solid "Dry Weight Corrected"

./ickel-59 U -0.244 +/-1.24 2.43 5.00 pCi/g TXJI 04/05/18 1346 1751598 5 3amma, Cs I 37, Co60, Nb94, Eu 152, Eu 154, Eu 155 "Dry Weight Corrected"

esium-137 UI 0.00 +/-0.0497 0.0593 1.00 pCi/g MXRI 03/27/18 0857 1749466 6

obalt-60 U -0.00529 +/-0.031 I 0.067 pCi/g

,uropium-152 U -0.0117 +/-0.07 19 0. 125 pCi/g

uropium-154 U 0.0772 +/-0. I 05 0.263 pCi/g

,uropium-155 U -0.0189 +/-0.0641 0.128 pCi/g

./iobium-94 U -0.0208 +/-0.0256 0.0432 pCi/g lad Gas Flow Proportional Counting 3FPC, Sr90, Solid "Dry Weight Corrected" itrontium-90 U 0.00765 +/-0.0638 0. 112 0.400 pCi/g KSDI 04/02/18 1805 1749761 7 lad Liquid Scintillation Analysis

,SC, Tritium Distillation, Solid "As Received"

-ritium U -0.61 +/-3 .32 5.89 10.0 pCi/g MXH8 03/30/18 1228 1750348 8

.iquid Sein! C 14, Solid "As Received"

~arbon- 14 U 0.0595 +/-2.30 3.95 5.00 pCi/g BXM4 03/29/18 2124 1750468 9

.iquid Scint Tc99, Solid "As Received"

• echnetium-99 U -0. 162 +/-0.818 1.42 2.00 pCi/g CXS7 04/15/18 0915 1753302 10

.iquid Scint Fe55, Solid "Dry Weight Corrected" ron-55 U 6.70 +/-4 .91 7. 15 10.0 pCi/g TXJ l 04/12/18 0954 1751579 11

,iquid Scint Ni63, Solid "Dry Weight Corrected" age 7 of 27

GEL LA BORA TORIES L-~

2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 17, 20 18 Company: LaCrosseSolutions Address: S4601 State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-SUB- l 03-AJGS-002-SB Project: ENRG07001 Sample ID: 446394005 Client JD: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method lad Liquid Scintillation Analysis jquid Scint Ni63, Solid "Dry Weight Corrected"

.Jickel-63 U -1.38 +/-1.70 3.08 5.00 pCi/g TXJ I 04/07/18 0535 1751578 12 rhe following Prep Methods were performed:

viethod Description Analyst Date Time Prep Batch

)ry Soil Prep Dry Soil Prep GL-RAD-A-02 1 JXOl 03/22/ 18 1330 1749454 The following Analytical Methods were performed:

\1ethod Description Analyst Comments DOE EML HASL-300, Am-05-RC Modified ASTM C 1475-00 Modified DOE EML HASL-300, Pu-l 1-RC Modified DOE EML HASL-300, Pu- I I-RC Modified DOE RESL Ni-I DOE HASL 300, 4.5.2.3/Ga-01-R EPA 905.0 Modified/DOE RP501 Rev. I Modified EPA 906.0 Modified EPA EERF C-01 Modified 0 DOE EML HASL-300, Tc-02-RC Modified DOE RESL Fe-I , Modified 2 DOE RESL Nr-1, Modified

,urrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits

\mericium-243 Tracer Alphaspec Isotopic Arn24 I Am243, Cm243/244, 65.8 (15%- 125%)

Solid "Dry Weight Corrected"

urium-243/244 Tracer Alphaspec Isotopic Am24l Am243, Cm243/244, 23 .9 (15%-125%)

Solid "Dry Weight Corrected"

\mericium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 99 (15%-125%)

'lutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 69.2 ( 15%- 125%)

Corrected"

'lutonium-242 Tracer Liquid Scint Pu24 I, Solid "DI)' Weight Corrected" 69.2 ( 15o/o-125%)

.J ickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" IOI (25%-125%)

itrontium Carrier GFPC, Sr90, Sohd "Dry Weight Corrected' 102 (25%- 125%)

rechnetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 89.7 (15%- 125%)

ron-59 Tracer Liquid Scint Fe55 , Solid "Dry Weight Corrected" 73 (15%- 125%)

.Jickel Carrier Liquid Scint Ni63 , Solid "DI)' Weight Corrected" 78.5 (25%- 125%)

1/otes:

age8of27

GEL LABORATORIES L_.:

2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 17, 2018 Company: LaCrosseSolutions Address: S460 I State Hwy 35 Genoa, Wisconsin 54632

Contact:

Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-SUB- l 03-AJGS-002-SB Project: ENRG0700 1 Sample ID: 446394005 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF OF Analyst Date Time Batch Method

ounting Uncertainty is calculated at the 95% confidence level (1.96-sigma).

Column headers are defined as follows:

OF: 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 age 9 of 27

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Reoort Date: April 17, 2018 LaCrosseSolutions Page I c S4601 State Hwy 35 Genoa, Wisconsin

Contact:

Mr. Jason Q. Spaide Workorder: 446394 Parmname NOM Samele Qual QC Units RPO% REC% Range Anlst Date Tim Rad Alpha Spec 3atch 1749552 QC 1203994922 446394005 DUP Americium-24 I u -0.0132 u -0.0035 1 pCi/g NIA NIAI-IAKB 03127118 09:

Uncertainty +l-0.0259 +l-0.0242 Americium-243 u 0.00638 u 0.0305 pCilg NIA NIA Uncertainty +l-0.0667 +l-0.0396 Curium-2431244 u 0.00 u -0.0104 pCilg NIA NIA Uncertainty +/-0.0161 +l-0.0348 QC 1203994923 LCS Americium-241 1.93 1.92 pCilg 99.7 (75%-125%) 03/27118 09:(

Uncertainty +/-0.210 Americium-243 u 0.0107 pCi/g (75%- 125%)

Uncertainty +l -0.021 Curium-2431244 2.41 2.18 pCi/ g 90.6 (75%-125%)

Uncertainty +/-0.222 QC 1203994921 MB Americium-24 I u -0.00837 pCi/g 03/27118 09:(

Uncertainty +/-0.0286 Americium-243 u -0.00824 pCi/g Uncertainty +l-0.0156 Curium-2431244 u 0.0056 pCilg Uncertainty +l-0.021 3atch 1749553 QC1203994925 446394005 DUP Neptunium-23 7 u -0.00099 1 u -0.00103 pCi/g NIA N/AI-IAKB 03/27118 13:4 Uncertain!) +/-0.00238 +/-0.00201 QC1203994926 LCS Neptunium-237 1.48 1.67 pCi/g 113 (75%-125%) 03/27118 13 :4 Uncertainty +l-0.0554 QC I203994924 MB Neptun ium-237 u 0.00128 pCi/g 03127/18 13:4 Uncertainty +l-0.00307 age 10 of 27

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summar:Y Workorder: 446394 Page 2 1 Pa rm name NOM Samele Qua! QC Units RPO% REC% Range Anlst Date Tin Rad Alpha Spec 3atch 1749554 QCJ203994928 446394005 DUP Plutonium-238 u 0.0149 u 0.0153 pCilg NIA NIAHAKB 03127/18 09 Uncertainty +l-0.0293 +l-0.0271 Plutonium-239/240 u 0.0 193 u -0.00484 pCilg NIA NIA Uncertainty +l-0.0341 +l-0.0146 QCl203994929 LCS Plutonium-238 u 0.0177 pCi/g 03/27118 09:

Uncertainty +l-0.0314 Plutonium-239/240 1.94 1.95 pCi/g 101 (75%- 125%)

Uncertainty +l-0.242 QCI203994927 MB Plutonium-238 u -0.00134 pCi/g 03127/18 09:

Uncertainty +l-0.031 Plutonium-2391240 u 0.000335 pCilg Uncertainty +l-0.0248 3atch I 749555 QCJ20399493 I 446394005 DUP Plutonium-241 u -0.703 u 0.613 pCi/g NIA NIAHAKB 03128118 14::

Uncertainty +l-2.45 +l-2.2 1 QC1203994932 LCS Plutonium-241 69.5 73.9 pCilg 106 (75%-125%) 03/28/18 16::

Uncertainty +/-3.53 QC I203994930 MB Plutonium-24 1 u 0.20 1 pCilg 03128/ 18 12:

Uncertainty +l-2.47 Rad Gamma Spec 3atch 1749466 QC I 203994728 446394005 DUP Cesium-137 Ul 0.00 u 0.00075 1 pCi/g NIA N/AMXRI 03/28/18 08: ~

Uncertainty +l-0.0497 +l-0.0237 Cobalt-60 u -0.00529 u 0.000415 pCilg NIA NIA Uncertainty +l-0.03 11 +l-0.0206 Europium- 152 u -0.0117 u -0.00698 pCi/g NIA NIA Uncertainty +l-0.07 19 +l-0.0584 age 11 of 27

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 446394 Page 3 c Parmname NOM Samele Qual QC Un its RPDo/o REC% Range Anlst Date Tirr Rad Gamma Spec 3atch 1749466 Europium-154 u 0.0772 u 0.0134 pCi/g NIA N/AMXR I 03128/18 08 Uncertainty +l-0.105 +l-0.0852 Europium-155 u -0.0189 u 0.0436 pCilg N IA NIA Uncertainty +l-0.064 1 +l-0.057 Niobium -94 u -0.0208 u -0.00613 pCilg N IA NIA Uncertainty +l-0.0256 +l-0.0242 QC1203994729 LCS Americium-241 488 570 pCi/g I 17 (75%-125%) 03/28/1809:

Uncertainty +/-14.9 Cesium- 137 173 169 pCilg 97.4 (75%-125%)

Uncertainty +l-3.33 Cobalt-60 132 130 pCilg 98.2 (75%-125%)

Uncertainty +l-3.47 Europium-152 u 1.53 pCilg Uncertainty +l-1.41 Europium-154 u -0.542 pCi/g Uncertainty +l-1.02 Europium- I 5 5 u 0.586 pCi/g Uncertainty +I-I .36 Niobium-94 u -0.00958 pC i/g Uncertainty +l-0.436 QCJ203994727 MB Cesium-137 u -0.00512 pCi/g 03/27/18 08::

Uncertainty +l-0.0 117 Cobalt-60 u -0.00268 pCi/g Uncertainty +l-0.020 Europium-152 u -0.0119 pCi/g Uncertainty +l-0.035 Europium-154 u -0.00315 pCi/g Uncertainty +l-0.0481 Europium- I 55 u -0.0146 pCilg Uncertainty +l-0.0396 age 12 of 27

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summar~

Workorder: 446394 Page 4 o Parmname NOM Samele Qual QC Units RPO% REC% Range Anlst Date Tim Rad Gamma Spec 3atch 1749466 Niobium-94 u 0.00616 pCilg MXRI 03127/18 08:

Uncertainty +l-0.0 189 3atch 1751598 QC1203999565 446394005 DUP Nickel-59 u -0.244 u -0.487 pCilg NIA NIA TXJI 04/05118 14:.

Uncertainty +/-1 .24 +l-0.632 QC 1203999566 LCS Nickel-59 94.2 80.5 pCi/g 85.5 (75%-125%) 04105/18 14::

Uncertainty +l-6.36 QC1203999564 MB Nickel-59 u -0.0478 pCilg 04/05/18 13:'

Uncertainty +l-0.562 Rad Gas Flow 3atch 1749761 QC1203995445 446394005 DUP Strontium-90 u 0.00765 u -0.0628 pCi/g NIA NIA KSDI 04102/1 8 18:(

Uncertainty +l-0.0638 +/-0. 11 3 QC J203995446 LCS Strontium-90 20.6 22.5 pCilg 109 (75%-1 25%) 04102/18 I 6:~

Uncertainty +/-1 .23 QC 1203995444 MB Strontium-90 u 0.0166 pCilg 04102/18 18:C Uncertainty +l-0.0585 Rad Liquid Scintillation 3atch 1750348 QC 1203996820 446394005 DUP Tritium u -0.61 u 0.3 12 pCi/g NIA NIAMXH8 03130/18 14: I Uncertainty +l-3.32 +l-3.67 QC 1203996822 LCS Tritium 58.0 48.4 pCilg 83.5 (75o/o- l 25%) 03131/18 07:5 Uncertainty +/-9.46 QC1203996819 MB Tritium u 0.765 pCilg 03130118 13 :2 Uncertaint) +/-3. I 4 age 13 of27

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summari Workorder: 446394 Page 5 of Parmname NOM Sam~le Qual QC Units RPO% REC% Range An lst Date Timi Rad Liquid Scintillation 3atch 1750348 QC 1203996821 446394005 MS Tritium 126 u -0.61 109 pCi/g 86.4 (75%-1 25%) MXH8 03/30/ 18 15 :(

Uncertainty +/-3.32 +/-11.3 3atch 1750468 QC1203997027 446394005 DUP Carbon- 14 u 0.0595 u -0.396 pCi/g NIA NI ABXM4 03/29118 22::

Uncertainty +l-2 .30 +l-2.24 QC1203997029 LCS Carbon- 14 135 122 pCil g 90.3 (75%-125%) 03/29118 23:'.

Uncertainty +l-4.52 QC 1203997026 MB Carbon-14 u -0. 109 pCil g 03/29118 22:(

Uncertainty +l-2.24 QC1203997028 446394005 MS Carbon- 14 272 u 0.0595 257 pCi/g 94.4 (75%-1 25%) 03129/18 23: 1 Uncertainty +l-2.30 +l-9. 15 3atch 1751578 QC1203999522 446394005 DUP Nickel-63 u -1.38 u -0. 199 pCi/g NIA NI A TXJI 04107/18 06:(

Uncertainty +l -1. 70 +/- 1.92 QC 1203999523 LCS Nickel-63 85.3 88.7 pCi/g 104 (75%- 125%) 04107118 06:2 Uncenainty +l-4.13 QC 1203999521 MB Nickel-63 u -0.145 pCi/g 04107118 05:5 Uncertainty +l-1.64 3atch 1751579 QC1203999525 446394005 DUP lron-55 u 6.70 u -0.191 pCi/g NI A NI A TXJ I 04110/ 18 00:2 Uncertainty +l-4.9 1 +l-2.2 1 QCJ203999526 LCS lron-55 I 16 90.1 pCi/g 77.9 (75%-125%) 04110/18 0 1:2 Uncertainty +l-4.16 age 14 of 27

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 446394 Page 6 o l'armname NOM Sample Qual QC Units RPO% REC% Range Anlst Date Tim Rad Liquid Scintillation 3atch I 75 I 579 QC1203999524 MB lron-55 u -0.888 pCi/g TXJI 04/09/1823:

Uncertainty +/-2.03 3atch 1753302 QC I204003340 446394005 DUP Technetium-99 u -0.162 u -0.35 1 pCi/g NIA NIA CXS7 04/ 15/ 18 10:

Uncertainty +/-0.8 18 +/-0.766 QC1204003341 LCS Techneti um-99 31.7 24.6 pCi/g 77.7 (75%-125%) 04/ 15/ 18 I 0:

Uncertainty +/-1.26 QC I204003339 MB Technetium-99 u -0.265 pCi/g 04/ 15/1809:

Uncertainty +/-0.678 Notes:

Counting Uncertainty is calculated at the 95% confidence level ( 1.96-sigma).

The Qualifiers in thi s report are defined as follows:

• • Analyte is a Tracer compound

< Result is less than value reported

> Result is greater than value reported BO Results are either below the MDC or tracer recovery is low FA Failed analysis.

H Analytical holding time was exceeded J Value is estimated K Analyte present. Reported value may be biased high. Actual value is expected to be lower.

L Analyte present. Reported value may be biased low. Actual value is expected to be higher.

M M if above MDC and less than LLD M REMP Result > MDC/CL and < RDL NIA 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. Refer to the applicable narrative or DER.

R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOO.

UI Gamma Spectroscopy--Uncertain identification age 15 of 27

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 446394 Page 7 o Parmname NOM Sample Qual QC Units RPO% REC% Range Anlst Date Tim UJ Gamma Spectroscopy--Uncertain identification UL Not considered detected. The associated number is the reported concentration, which may be inaccurate due to a low bias.

X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier y Other specific qualifiers were required to properly define the results. Consult case narrative.

I\

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 recovery limits do not apply when sample concentration exceeds spike cone. by a factor of 4 or more or %RPO not applicable.

" The Relative Percent Difference (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptance criteria when the sample is greater than five times (5X) the contract required detection limit (RL). In cases where either the sample or duplicate value is less than 5X the RL, a control limit of+/- the RL is used to evaluate the DUP result.

• Indicates that a Quality Control parameter was not within specifications.

For PS, PSD, and SOILT 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 requirem ents of the NELAC standard unless qualified on the QC Summary.

age 16of27

Radiochemistry Technical Case Narrative LaCrosseSolutions, LLC (ENRG)

SDG #: 446394 Product: Alphaspec Isotopic Am241 Am243, Cm243/244, Solid Analytical Method: DOE EML HASL-300, Am-05-RC Modified Analytical Procedure: GL-RAD-A-011 REY# 26 Analytical Batch: 1749552 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1749454 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 446394005 L2-SUB-I 03-AJGS-002-SB 1203994921 Method Blank (MB) 1203994922 446394005(L2-SUB- l 03-AJGS-002-SB) Sample Duplicate (DUP) 1203994923 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.

Miscellaneous Information Manual Integration Manual integration of alpha spectroscopy spectra I 203994923 (LCS) was performed to fully separate counts in Regions oflnterest which would have been biased.

Product: Alphaspec Np, Solid Analytical Method: ASTM C 1475-00 Modified Analytical Procedure: GL-RAD-A-032 REV# 21 Analytical Batch: 1749553 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1749454 PO Box 30712 Charleston, SC 29417 2040 Savage Road Cl'larleston, SC 29407 P 843,556.8171 f 843.766.1178 m.911.com

The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 446394005 L2-SUB-J 03-AJGS-002-SB 1203994924 Method Blank (MB) 1203994925 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP) 1203994926 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: Alphaspec Pu238, 239/240, Solid Analytical Method: DOE EML HASL-300, Pu-11-RC Modified Analytical Procedure: GL-RAD-A-011 REV# 26 Analytical Batch: 1749554 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1749454 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 446394005 L2-SUB- I 03-AJGS-002-SB 1203994927 Method Blank (MB) 1203994928 446394005(L2-SUB- I 03-AJGS-002-SB) Sample Duplicate (DUP) 1203994929 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: Dry Weight Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: J 749454 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com

The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample JD# Client Sample Identification 44639400) LJ-SUB-LES-FSGS-00 I-SB 446394002 L 1-SUB-LES-FSG S-012-SB 446394003 L 1-SUB-DRS-FSGS-W 12-SB 446394004 LI-SUB-DRS-FSGS-Wl4-SB 446394005 L2-SUB- I 03-AJGS-002-SB 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, Eu155 Analytical Method: DOE HASL 300, 4.5.2.3/Ga-O 1-R Analytical Procedure: GL-RAD-A-013 REV# 27 Analytical Batch: I 749466 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: I 749454 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 446394005 L2-SUB-I 03-AJGS-002-SB 1203994727 Method Blank (MB) 1203994728 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP) 1203994729 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.

Qualifier Information Qualifier Reason Analyte Sample Client Sample Results are considered a false UI Cesium-137 446394005 L2-SUB-l 03-AJGS-002-SB positive due to no valid peak.

PO Box 30712 Char1eston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com

Product: Gamma Ni59, Solid Analytical Method: DOE RESL Ni-I Analvtical Procedure: GL-RAD-A-022 REV# 18 Analytical Batch: 1751598 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1749454 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample JD# Client Sample Identification 446394005 L2-SUB- I 03-AJGS-002-SB 1203999564 Method Blank (MB) 1203999565 446394005(L2-SUB- I 03-AJGS-002-SB) Sample Duplicate (DUP) 1203999566 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. I Modified Analytical Procedure: GL-RAD-A-004 REV# 19 Analytical Batch: 1749761 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1749454 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 446394001 L l -SUB-LES-FSGS-00 I -SB 446394002 L l-SUB-LES-FSGS-012-SB 446394003 L I-SUB-DRS-FSGS-Wl2-SB 446394004 Ll-SUB-DRS-FSGS-WJ4-SB 446394005 L2-SUB- l 03-AJGS-002-SB 1203995444 Method Blank (MB) 1203995445 446394005(L2-SUB- l 03-AJGS-002-SB) Sample Duplicate (DUP) 1203995446 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843..556.8171 F 843.766.1178 www.1111.com

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 Pu241, Solid Analytical Method: DOE EML HASL-300, Pu-I I-RC Modified Analytical Procedure: GL-RAD-A-035 REV# 19 Analytical Batch: 1749555 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1749454 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sam pie JD# Client Sample Identification 446394005 L2-SUB- I 03-AJGS-002-SB 1203994930 Method Blank (MB) 1203994931 446394005(L2-SUB- I 03-AJGS-002-SB) Sample Duplicate (DUP) 1203994932 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: LSC, Tritium Distillation, Solid Analytical Method: EPA 906.0 Modified Analytical Procedure: GL-RAD-A-002 REV# 22 Analytical Batch: 1750348 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 446394005 L2-SUB-103-AJGS-002-SB 1203996819 Method Blank (MB) 1203996820 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP) 1203996821 446394005(L2-SUB- I 03-AJGS-002-SB) Matrix Spike (MS) 1203996822 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on an "as received" basis.

PO Box 30712 Char1eston, SC 294, 7 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.get.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 1203996822 (LCS) was recounted due to low recovery. The recount is reported.

Miscellaneous Information Additional Comments The matrix spike, 1203996821 (L2-SUB- l 03-AJGS-002-SBMS), aliquot was reduced to conserve sample volume.

Product: Liquid Scint C14, Solid Analytical Method: EPA EERF C-01 Modified Analytical Procedure: GL-RAD-A-003 REV# 16 Analytical Batch: 1750468 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample JD# Client Sample Identification 446394005 L2-SUB-I 03-AJGS-002-SB 1203997026 Method Blank (MB) 1203997027 446394005(L2-SUB- l 03-AJGS-002-SB) Sample Duplicate (DUP) 1203997028 446394005(L2-SUB- I 03-AJGS-002-SB) Matrix Spike (MS) 1203997029 Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on an "as received" basis.

Data Summary:

All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.

Miscellaneous Information Additional Comments The matrix spike, 1203997028 (L2-SUB- I 03-AJGS-002-SBMS), aliquot was reduced to conserve sample volume.

Product: Liquid Scint Ni63, Solid Analytical Method: DOE RESL Ni-1, Modified PO Box 30712 Charteston, SC 29417 2040 Savage Road CharlestDn, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com

Analytical Procedure: GL-RAD-A-022 REV# 18 Analytical Batch: 1751578 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1749454 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 446394005 L2-SUB- l 03-AJGS-002-SB 1203999521 Method Blank (MB) 1203999522 446394005(L2-SUB- I 03-AJGS-002-SB) Sample Duplicate (DUP) 1203999523 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 Fess, Solid Analytical Method: DOE RESL Fe-I, Modified Analytical Procedure: GL-RAD-A-040 REV# 13 Analytical Batch: 1751579 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1749454 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sam pie JD# Client Sample Identification 446394005 L2-SUB-I 03-AJGS-002-SB 1203999524 Method Blank (MB) 1203999525 446394005(L2-SUB- l 03-AJGS-002-SB) Sample Duplicate (DUP) 1203999526 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 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.oet.com

Sample 446394005 (L2-SUB-103-AJGS-002-SB) was recounted to verify sample results. Recount is 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: 1753302 The following samples were analyzed using th e above methods and analytical procedure(s).

GEL Sample JD# Client Sample Identification 446394005 L2-SUB- J 03-AJG S-002-SB 1204003339 Method Blank (MB) 1204003340 446394005(L2-SUB- I 03-AJGS-002-SB) Sample Duplicate (DUP) 1204003341 Laboratory Control Sample (LCS)

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.

Certification Statement Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless otherwise noted in the analytical case narrative.

PO Bax 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.111.com

~~__....__u, L hC 84' g,, S,tt 1~=1111 Laboratories LLC gel.com Chemistry I Radiochemistry I Radiobioassay I Specialty Ana!Y'ics

~o~~~:~:~:*;: ~LLL Charleston. SC 29407 Chain of Custod and Anal ical Re uest t.fl/{t:, 3 9 Phone: (843) 556-s111

- - -- GEL Project Manag_er:__ ~ Fax: (843) 766-1178 Collected By:

Phone #

Fax #

-- rr Should tllls

~an1p1itie considered:

Sample Analysis Requested <51 (Fill in the number

~

~

,.5

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. . ... for.each

. of contain~

~1a~ ~ I ~I I ~I _QI ~I ~ -..' ~~ttvejyPe(6)_,

test)

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...., .. .:* Note: e~;~ple 1:i"

~~: l;- ~ ~quired'fodample, '.

specific QC'\ t' f'

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L I I I I I DC <0.C(~~i

,)o- ~7 Chain of Custody Signatures (Sutiject to S11rt:barge)

Relinquished By (Signed) O~lc Time Received by (signed) Date Time OJ~J_q.fy Levet4 2 2 3 3 For Lah Rccei1*ine_ C)sc On~v: Custody Seal Intact? [ ] Yes LJNo Cooler Temp: _ _ °C

>Jf'dr,sainple }hipping-antiileliv:try tf~alls, see Sample Receipt & l(_eview/tJi'Jtl (SR/l) .. 88,mple Collection Time Zone: ( JEastern l ] Paciffo JdCentral [ J Mountain [ JOther:

1.) Chain of Custody Nu mber ~ Client D<tennincd 2.) QC Codes: N ~ Norm.ii S*mple, TR = Trip Blank. Fil* Field Duplicate, ED ~ Equipment Blank, MS

• Matri., Spike Sample. MSO = Ma1rix Spike Ouplica1e Samp le. G = Gr.,b. C ~ Comrosi1c J.) Field Filtered: for liquid matrices, indicate wi1h n - Y - for yes the so1nplc was field filtered or- N - for sample wos no1 licld filtered .

4.) Ma1rix Codes: O\Vn Orinking \\'a1<r, GW-<lroundwo1er. SW*Surface Water, \YW* \Vastc Wa1er. w ~ watcr, MI.- Misc Liquid. SO* Soil. SD- Scdimcn1, St,.Sludgc. SS~&>tid Waste, 0 - 0il, F~f iltcr, P " Wipc. U* Urinc. J.'* Fccat. N$Nosal 1s.) Sample Analysis Requc,ted: Anal)1ical method <<:quested (i.e. 82608, 60IOBn470A) and number of eo ntoinc~ pro,*ided for each (i.e. 82608

• 3, 6Q/08!i470,1 - 1).

6.) l'rescrvotive Type: HA

• Hydrochloric Acid, NI

• Nitric Acid, SH

• Sodium Hydroxide. SA

• Sulfuric Acid. AA

• Ascorbic Acid, IIX

• Hc.,ane, ST ~ Sodium Thiosulfate. lfno prcscrv01ive is added ~ lca"c field blank 1,)Are there any known orj,ossible hazards !Listed Waste I !Other J associated with these samples? LW= Listed Waste OT= Other/ Unknown CO = Corrosive (FX.P and U-listed wa.ttes.) (i.e.: Higflllow pH. asbestos, beryllium. irritants, other RCRA Metnls RE = Reactive Waste code(s): mis<;. health hazards, etc.)

As=' Arsenic Hg=Mercury

Description:

Ba=Barium Se- Selenium ITSCA Reimllltrrf Cd=Cadmium Ag- Silver PCB = Poiychlorioated Cr= Chromium MR= Miscellaneous biphenyls Pb=Lead RCRAmetals

mD /Laboratories LL~ / ( SAMPLE RECEIPT & REVIEW FORM Date Received:

FedEx Express

---

Cm:.::'

~ UPS le Appticablc:

Field Services Courier Other Carrier and-Tracking Number 77£17 1'1-'l~ 3:Zf'o Suspected Bamnl lnfonnaUon

,!! 0 *If Net Counts > I OOcpm on sample, not rmrked "radioactive", contact the Radiation Safety Group for further

,... Z investigation.

Shi as a DOT Hazardous? Hazard Class Shipped: UN#:

Muimum Net Counts Observed* (Observed Counts* Arca Background Counts): _....,...__CPM / mR/Hr COC/Samples malked or classified as radioactive?

OassHled as: Rad 1 Rad 2 Rad 3 If yes, select Hazards below, and contact the GEL Safety Group.

PCB's Aamrmble Foreign Soil RCRA Asbestos Bceylliwn Other.

Is ackage, COC, and/or Samples maikcd HAZ?

Sample Receipt Criteria Commenls/QuaHflers (Required for Non-Conforming Items)

Circle Applicable: Seals broken Damaged container uaking container Other (deoaibe)

Shipping containers received intact and 1

sealed?

Chain of custody documents included 2

with shipment?

Pn!servalion Method: Wet Ice Ice Packs Dry ice on Other.

3 Samples requiring cold preservation within (0 5 6 deg. C)'/* *a11 tcrnpcrarun,,; are ncorded in Celsius 4

Daily check performed and passed on IR Temperature Device Serial #:-=-4-<~--"-1-:..-.

temperature gun? S=ndary Tempcmur< Device Serial I (If Applic:ablo):

Circle Applicable: Seals broken Darnos<d container uaking container Other (describe)

S Sample containers intact and sealed?

Sample ID's and Containers Affected:

Samples requiring chemical preservation 6

at proper pH?

If Yes, Are Encores or Soil Kits present? Yes_ No_ (Ifycs, take to VOA Freezer)

Do VOA vials contain acid preservation? Yes No_ NIA. (lfunlmown, select No)

Do any samples require Volatile VOA vials free ofheadspace? Yes No_N/A 7

Analysis? Sample ID's and containers affected:

ID'* and tests affected:

8 Samples received within holding time?

s.,,.,1e !D's and containers affected.:

Sample !D's on COC match !D's on 9

bottles?

Sample !D's affected:

10 ~::i:e:i;e on COC match date & time Sample ID'* all'ected:

Number of containers received match 11 number indicated on COC?

Arc sample containers identifiable as 12 GEL rovided?

COC form is properly signed in 13 relinquished/received sections?

Conuneots (Use Continuation Form if needed):

GL-CHL-SR-001 Rev 5 age 26 of27

List of current GEL Certifications as of 17 April 2018 State Certification Alaska 17- 018 Arkansas 88-0651 CLIA 42D0904046 California 2940 Colorado SC00012 Connecticut PH-0169 Delaware SC00012 OoD ELAP/ ISO 17025 A2LA 2567.01 Florida NELAP £87156 Foreign Soils Pennit P330 00283, P330- 15-00253 Georgia SCOOOl2 Georgia SOWA 967 Hawaii SC00012 Idaho Chemistry SCOOOl2 Idaho Radiochemistry SC00012 Illinois NELAP 200029 Indiana C-SC- 01 Kansas NELAP E- 10332 Kentucky SOWA 90129 Kentucky Wastewater 90129 Louisiana NELAP 03046 (Al33904)

Louisiana SDWA LA180011 Maryland 270 Massachusetts M- SCOl2 Michigan 9976 Mississippi SC00012 Nebraska NE-OS 13 Nevada SCOOO 122018- I New Hampshire NELAP 205415 New Jersey NELAP SC002 1---

New Mexico SCOOOl2 New York NELAP I 1501 North Carolina 233 North Carolina SDWA 45709 North Dakota R- 158 Oklahoma 9904 Pennsylvania NELAP 68- 00485 Puerto Rico SCOOOl2 S. Carolina Radiochem 10120002 South Carolina C hemistry 10120001 Tennessee TN 02934 Texas NELAP Tl04704235 13 Utah NELAP SC000122018- 26 Vennont VT87 156 Virginia NELAP 460202 Washington C780 West Virginia 997404 age 27 of 27