Text

Final Status Survey Release Record Survey Unit L1-SUB-LES
	ML19261A338
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	08/28/2019
From:	Uz M; LaCrosseSolutions
To:	; Office of Nuclear Material Safety and Safeguards
References
	LC-2019-0040
	Download: ML19261A338 (184)
	v • d • e

LA CROSSE BOILING WATER REACTOR FINAL STATUS SURVEY RELEASE RECORD SURVEY UNIT L1-SUB-LES

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 1

PREPARED BY / DATE:

8/28/19 M. Uz, Survey Design Specialist REVIEWED BY / DATE:

8/28/19 R. Yetter, Director, Radiological Site Closure REVIEWED BY / DATE:

P. Hollenbeck, Radiological Engineer APPROVED BY / DATE:

S. Zoller, FSS Manager R. Yetter, Director, Radiolo P. Hollenbeck, Radiological 8/28/19 S Zoller FSS SS SS SS SS SS S

Manager 8/28/19

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 2

TABLE OF CONTENTS 1.

EXECUTIVE

SUMMARY

................................................................................................................................. 5 2.

SURVEY UNIT DESCRIPTION....................................................................................................................... 5 3.

CLASSIFICATION BASIS................................................................................................................................. 6 4.

DATA QUALITY OBJECTIVES...................................................................................................................... 8 5.

SURVEY DESIGN............................................................................................................................................. 11 6.

SURVEY IMPLEMENTATION...................................................................................................................... 16 7.

SURVEY RESULTS.......................................................................................................................................... 18 8.

QUALITY CONTROL...................................................................................................................................... 25 9.

INVESTIGATIONS AND RESULTS.............................................................................................................. 25 10.

REMEDIATION AND RESULTS................................................................................................................... 25 11.

CHANGES FROM THE FINAL STATUS SURVEY PLAN........................................................................ 25 12.

DATA QUALITY ASSESSMENT (DQA)....................................................................................................... 25 13.

ANOMALIES..................................................................................................................................................... 26 14.

CONCLUSION.................................................................................................................................................. 26 15.

REFERENCES................................................................................................................................................... 27 16.

ATTACHMENTS.............................................................................................................................................. 27 ATTACHMENT 1 - FIGURES AND MAPS............................................................................................................. 29 ATTACHMENT 2 - SCAN DATA............................................................................................................................. 31 ATTACHMENT 3 - SIGN TEST............................................................................................................................... 35 ATTACHMENT 4 - QUALITY CONTROL ASSESSMENT...................................................................................... 37 ATTACHMENT 5 - CONSULTATION TRIGGERS FOR RESIDENTIAL SOIL CONCENTRATIONS................... 39 ATTACHMENT 6 - GRAPHICAL PRESENTATIONS............................................................................................. 41 ATTACHMENT 7 - SAMPLE ANALYTICAL REPORTS......................................................................................... 45 ATTACHMENT 8 - GEL LABORATORIES ANALYTICAL REPORTS................................................................... 46

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 3

LIST OF TABLES Table 3 Statistical Quantities for Cs-137 and Co-60 from the Characterization Survey.................................. 6 Table 4 Dose Significant Radionuclides and Mixture for Soil............................................................................ 9 Table 4 Base Case DCGLs for Soil (DCGLS)...................................................................................................... 10 Table 4 Operational DCGLs for Soil (OpDCGLS)............................................................................................. 11 Table 5 Soil Surrogate Ratio................................................................................................................................ 12 Table 5 Action Levels for Survey Unit L1-SUB-LES......................................................................................... 13 Table 5 Systematic Sample Locations................................................................................................................. 14 Table 5 Judgmental Sample Locations............................................................................................................... 14 Table 5 Investigation Levels................................................................................................................................. 15 Table 5 Synopsis of Survey Design...................................................................................................................... 16 Table 7 Synopsis of Scan Results......................................................................................................................... 18 Table 7 Summary of Gamma Spectroscopy Results for Soil Samples Comprising the Statistical Sample Population........................................................................................................................................................... 21 Table 7 Basic Statistical Properties of Systematic Sample Population............................................................. 21 Table 7 Off-Site Analysis Results......................................................................................................................... 22 Table 7 Summary of Gamma Spectroscopy Results for Judgmental Soil Samples......................................... 22 Table 7 Summary of Gamma Spectroscopy Results for QC Soil Samples....................................................... 23 Table 7 Sum-of-Fractions for Individual Soil Samples (Systematic and QC)................................................. 23 Table 7 Sum-of-Fractions for Individual Soil Samples (Judgmental).............................................................. 24 Table 16 L1-SUB-LES Complete Scan Data....................................................................................................... 32 Table 16 L1-SUB-LES Sign Test......................................................................................................................... 36 Table 16 L1-SUB-LES QC Assessment............................................................................................................... 38 LIST OF FIGURES Figure 16 L1-SUB-LES Sample Locations Map................................................................................................. 30 Figure 16 Quantile Plot for Cs-137 Concentration............................................................................................ 42 Figure 16 Histogram for Cs-137 Concentration................................................................................................. 43 Figure 16 Retrospective Power Curve for L1-SUB-LES................................................................................... 44

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 4

LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable DQA Data Quality Assessment DQO Data Quality Objective DCGL Derived Concentration Guideline Level DCGLS Soil Derived Concentration Guideline Level FSS Final Status Survey GPS Global Positioning System HSA Historical Site Assessment IC Insignificant Contributors LACBWR La Crosse Boiling Water Reactor LBGR Lower Bound of the Gray Region LTP License Termination Plan MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration NaI Sodium Iodide OpDCGLS Soil Operational Derived Concentration Guideline Level QAPP Quality Assurance Project Plan QC Quality Control RASS Remedial Action Support Survey ROC Radionuclides of Concern SOF Sum-of-Fraction TEDE Total Effective Dose Equivalent UBGR Upper Bound of the Gray Region UCL Upper Confidence Limit

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 5

1.

EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey unit L1-SUB-LES, an excavation within open land survey unit L1-010-103, 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

,DQG7\\SH,,GHFLVLRQHUURUUDWHVZHUHVHWDW$VDV\\VWHPDWLFVDPSOHSRSXODWLRQ

using a random start point, 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-LES 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 0.0549 when applying the respective Operational Derived Concentration Guideline Levels (OpDCGLS) for soil. Therefore, the null hypothesis is rejected and survey unit L1-SUB-LES is acceptable for unrestricted release. The total SOF for all ROCs when applying the respective Base Case DCGLs (DCGLS) for soil is 0.01. This SOF equates to a dose for the survey unit of 0.2495 mrem/yr.

2.

SURVEY UNIT DESCRIPTION L1-SUB-LES is an impacted Class 1 excavation survey unit within open land survey unit L1-010-103. The survey unit consists of the underlying soil post-removal of the Low Specific Activity (LSA) Building, Septic Tank, Eat Shack Foundation, Oily Water Tank, Circulating Water Intake & Discharge piping, Main Transformer Substation as well as associated system lines. The surface area of the survey unit is 1,336 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-LES.

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 6

3.

CLASSIFICATION BASIS Based on the Historical Site Assessment (HSA) (Reference 5), open land survey unit L1-010-103 has been identified as a Class 1 area. The facilities within this survey unit were all used in the operation or support of the LACBWR nuclear steam system. As survey unit L1-SUB-LES consists of the underlying soils from L1-010-103, it is also designated as Class

1. The following summarizes the results of the characterization surveys for survey unit L1-010-103.

The initial site characterization surveys performed by EnergySolutions were conducted between October 9, 2014, and August 6, 2015. A total of seven (7) surface soil samples, and twenty-five (25) subsurface soil samples were taken. All samples were analyzed by the on-site gamma spectroscopy system. Cs-137 was detected above Minimum Detectable Concentration (MDC) at a maximum concentration of 0.161 pCi/g for the surface soil samples. No other ROC was identified for surface soil samples. For subsurface soil samples, no ROC were detected at concentrations above MDC. A summary of the analyses for the surface soil and subsurface soil samples taken during site characterization are presented in Table 3-1.

Table 3 Statistical Quantities for Cs-137 and Co-60 from the Characterization Survey Surface Soil Co-60 Cs-137

of Samples 7

>MDC 0

1 Mean (pCi/g) 0.059 0.069 Median (pCi/g) 0.050 0.054 Max (pCi/g) 0.099 0.161 Min (pCi/g) 0.048 0.048 Standard Deviation (pCi/g) 0.019 0.041 Subsurface Soil Co-60 Cs-137

of Samples 25

>MDC 0

0 Mean (pCi/g) 0.046 0.049 Median (pCi/g) 0.046 0.049 Max (pCi/g) 0.055 0.054 Min (pCi/g) 0.025 0.042 Standard Deviation (pCi/g) 0.005 0.003

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 7

Four (4) subsurface soil samples, three (3) surface soil samples, and one (1) sediment soil sample, from characterization were sent to Test America Laboratories for off-site analysis.

The subsurface soil samples and sediment samples were analyzed for the full suite of initial ROC, while the surface soil samples were analyzed for Co-60, Nb-94, Cs-137, Eu-152, Eu-154, Eu-155, and Am-241. For subsurface samples, H-3 was identified in three (3) samples at a maximum concentration of 3.260 pCi/g. Cs-137 was identified in one (1) surface soil sample at a maximum concentration of 0.091 pCi/g. For the sediment sample, C-14, Co-60, and Cs-137 were identified at maximum concentrations of 0.453 pCi/g, 0.136 pCi/g, and 0.136 pCi/g; respectively. No other ROC were identified in any other samples.

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

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-LES was determined to be Class 1.

Between January 25, 2018, and January 31, 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 was set at average background plus 3,525 cpm, which is equivalent to the Operational DCGL. Sixteen (16) alarms were produced and verified during the RASS scan survey. Fifteen (15) judgmental soil samples were collected in the excavation at areas where scan alarms occurred. The

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 8

fifteen (15) samples were analyzed using the on-site gamma spectroscopy system. Gamma spectroscopy revealed Cs-137 concentrations ranging between 5.30E-02 pCi/g and 2.93E+01 pCi/g. Co-60 concentrations ranged between 1.23E-01 pCi/g and 8.57E+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.

4.

DATA QUALITY OBJECTIVES 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 was to demonstrate that the level of residual radioactivity in survey unit L1-SUB-LES 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 to be consistent with the guidance contained in Section 3.3 of NUREG-1757, Volume 2, Revision 1, Consolidated

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 9

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.

LTP Chapter 6, Section 6.14.1 discusses the process used to derive the ROC for the decommissioning of LACBWR, including the elimination of IC from the initial suite.

Table 4-1 presents the ROC for the decommissioning of soil at LACBWR and the normalized mixture fractions based on the radionuclide mixture.

Table 4 Dose Significant Radionuclides and Mixture for Soil Radionuclide Fraction of Total Activity (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).

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.

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 10 In Class 1 survey units, the DCGLW can be multiplied by Area Factors to obtain a Base Case DCGL that represents the same dose to an individual for residual radioactivity over a smaller area within a survey unit.

At LACBWR, compliance is demonstrated through the summation of dose from five (5) distinct source terms for the end-state (basements, soils, buried pipe, above-ground 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, Sections 6.4 and 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 Radionuclide DCGLS (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 OpDCGLS for the unrestricted release of soil are provided in Table 4-3.

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 11 Table 4 Operational DCGLs for Soil Radionuclide OpDCGLS (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 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 concentrations, therefore, the actual concentrations are used as the recorded FSS result for measurement and/or sample values even if less than the reported MDC. Negative reported concentrations are 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-LES 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

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 12 mix for soils/buried pipe, the Reactor Building, and the Waste Gas Tank Vault. The surrogate ratio for soil is given in Table 5-1.

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

Equation 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

1 17.39()+

0.502 1970.45()

= 17.31 /

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

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 13 Table 5 Action Levels for Survey Unit L1-SUB-LES ROC Action Level (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 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. 7KHUHODWLYHVKLIWIRUWKHVXUYH\\XQLWGDWDVHW LVGHILQHGDVVKLIWZKLFKLV

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

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standard deviation of the data set used for survey desLJQ7KHRSWLPDOYDOXHIRUVKRXOG

UDQJHEHWZHHQRQHDQGWKUHH7KHODUJHVWYDOXHWKHFDQKDYHLVWKUHH,IWKH

H[FHHGVWKUHHWKHQWKHYDOXHRIWKUHHZLOOEHXVHGIRU7KHIRUVXUYH\\

unit L1-SUB-LES, based on Cs-137 and Co-60 data for subsurface soil samples collected during characterization of L1-010-103, 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 used as WKHDGMXVWHG%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.

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

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 14 samples were selected using Visual Sample Plan (VSP), in accordance with LC-FS-PR-002.

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

Table 5 Systematic Sample Locations Sample ID Northing Easting L1-SUB-LES-FSGS-001-SB 570981.0228 1641982.3207 L1-SUB-LES-FSGS-002-SB 571010.8457 1641930.6659 L1-SUB-LES-FSGS-003-SB 571010.8457 1641965.1024 L1-SUB-LES-FSGS-004-SB 571040.6686 1641913.4476 L1-SUB-LES-FSGS-005-SB 571040.6686 1641947.8842 L1-SUB-LES-FSGS-006-SB 571040.6686 1641982.3207 L1-SUB-LES-FSGS-007-SB 571070.4916 1641930.6659 L1-SUB-LES-FSGS-008-SB 571070.4916 1641965.1024 L1-SUB-LES-FSGS-009-SB 571070.4916 1641999.539 L1-SUB-LES-FSGS-010-SB 571100.3145 1641947.8842 L1-SUB-LES-FSGS-011-SB 571100.3145 1641982.3207 L1-SUB-LES-FSGS-012-SB 571100.3145 1642016.7573 L1-SUB-LES-FSGS-013-SB 571130.1374 1641965.1024 L1-SUB-LES-FSGS-014-SB 571130.1374 1641999.5390 Only one (1) judgmental sample was required for survey design, and one (1) judgmental soil sample was collected. The collection of sample L1-SUB-LES-FJGS-001-SB was triggered by elevated scans in grid E-1 due to its proximity to the Reactor Building. In total, fifteen (15) soil samples were collected for the FSS of survey unit L1-SUB-LES. The coordinates for the judgmental samples are provided in Table 5-4.

Table 5 Judgmental Sample Locations Sample ID Northing Easting L1-SUB-LES-FJGS-001-SB 571112.387 1642026.268

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 15 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 for continuing characterization. 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 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 samples, L1-SUB-LES-FSGS-001-SB and L1-SUB-LES-FSGS-012-SB, met the requirement that a minimum of 10% of the samples collected for the FSS of survey unit L1-SUB-LES be analyzed for HTD ROC. 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-LES-QSGS-008-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-LES, 100% scan coverage equates to 1,336 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-four (44) of the sixty-three (63) 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 Classification Scan Investigation Levels Direct Investigation Levels Class 1

>Operational DCGL or >MDCscan if MDCscan is greater than Operational DCGL

>Operational DCGL

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 16 Table 5-6 provides a synopsis of the survey design for survey unit L1-SUB-LES.

Table 5 Synopsis of Survey Design Feature Design Criteria Basis Survey Unit Surface Area 1,336 m2 GPS Number of Systematic Samples (N) 14 x

1 x

UBGR = SOF of 1 x

LBGR = SOF of 0.5 x

Type I error = 0.05 x

Type II error = 0.05 x

DGMXVWHG

x MARSSIM Table 5.5 DCGLs and Action Levels x

Co-60: 3.83 pCi/g x

Sr-90: 1970.45 pCi/g x

Cs-137: 17.39 pCi/g (Surrogate Cs-137 DCGL: 17.31 pCi/g) x Eu-152: 8.51 pCi/g x

Eu-154: 7.89 pCi/g Operational DCGLs for soil, LTP Chapter 5, Table 5-6 Scan and Direct Investigation Levels

>Operational DCGL LTP Chapter 5, Table 5-16 Scan Areal Coverage 1,336 m2 or 100% areal coverage LTP Chapter 5, Table 5-15 Number of Judgmental Samples 1

1 Per Sample Plan Actual Number Obtained HTD ROC Analysis 2 samples 2

LTP 5.1 & Signed Sample Plan Actual Number Obtained QC 1 split sample selected at random 2

LTP Chapter 5, Section 5.9 Actual Number Obtained 6.

SURVEY IMPLEMENTATION For survey unit L1-SUB-LES, 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.

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 17 An FSS Supervisor performed a visual inspection and walk-down of the survey unit on February 2, 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 2, 2018.

FSS field activities were projected to take ten (10) 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 February 8, 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 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-four (44) scan grids constituting a total scan coverage of 1,336 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-LES, background ranged from 4349 counts per minute (cpm) up to 6913 cpm.

All designated scan areas and sample locations 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 not to exceed 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 of 17.31 pCi/g, which was based on the surrogate adjusted

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 18 DCGL of Cs-137 while inferring Sr-90). Complete scan results are provided in Attachment 2.

One (1) judgmental soil sample was collected during implementation of FSS. The sample was collected as a result of an alarm that was received in grid E-1, near the Reactor Building, on top of a concrete slab that was remaining in grid post demolition.

The survey design specified that a minimum of two (2) samples were required for HTD ROC analysis. In total, two (2) samples (L1-SUB-LES-FSGS-001-SB and L1-SUB-LES-FSGS-012-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 two (2) samples (L1-SUB-LES-QSGS-008-SB and L1-SUB-LES-FSGS-013-SB SPLIT) for split and duplicate sample analysis.

7.

SURVEY RESULTS All areas identified in the FSS plan were scanned. One (1) location, grid E-1, resulted in an alarm. Table 7-1 provides an overview of the scan results for all forty-four (44) scan grids, 14 sample locations (identified as SP001-SP014), 1 QC sample location (identified as QC008), and two rescans of grids as per QC measures (identified as C3QC and F7QC).

Complete scan results are provided in Attachment 2.

Table 7 Synopsis of Scan Results Scan Area Highest Logged Reading (cpm)

Action Level (cpm)

of Scan Alarms Judgmental Samples Investigation Samples A1 4,658 8,436 0

0 0

A2 6,063 8,285 0

0 0

A3 5,461 7,874 0

0 0

A4 5,759 8,389 0

0 0

A5 5,834 7,874 0

0 0

A6 5,767 10,438 0

0 0

A7 4,931 8,338 0

0 0

A8 5,393 8,285 0

0 0

B1 5,140 8,436 0

0 0

B2 5,186 8,285 0

0 0

B3 5,661 7,874 0

0 0

B4 5,432 8,389 0

0 0

B5 5,254 7,874 0

0 0

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 19 Scan Area Highest Logged Reading (cpm)

Action Level (cpm)

of Scan Alarms Judgmental Samples Investigation Samples B6 6,115 10,438 0

0 0

B7 5,225 7,975 0

0 0

B8 5,725 8,353 0

0 0

C1 5,482 8,436 0

0 0

C2 5,635 8,285 0

0 0

C3 5,569 7,874 0

0 0

C4 5,652 8,389 0

0 0

C5 5,061 7,874 0

0 0

C6 6,490 10,438 0

0 0

C7 5,593 7,975 0

0 0

C8 6,367 8,353 0

0 0

D1 6,830 8,297 0

0 0

D2 6,195 8,389 0

0 0

D3 5,548 7,874 0

0 0

D4 7,258 8,389 0

0 0

D5 6,055 7,874 0

0 0

D6 7,654 8,353 0

0 0

D7 6,243 7,975 0

0 0

D8 6,075 9,255 0

0 0

E1 11,850 8,436 1

1 0

E2 6,064 8,389 0

0 0

E3 5,983 7,874 0

0 0

E4 7,145 8,389 0

0 0

E5 7,208 7,874 0

0 0

E6 8,738 10,438 0

0 0

E7 6,930 9,255 0

0 0

E8 5,816 8,338 0

0 0

F7 8,720 9,255 0

0 0

F8 6,456 8,338 0

0 0

G7 9,093 9,255 0

0 0

G8 7,998 8,338 0

0 0

QC008 5,335 8,067 0

0 0

C3QC 5,905 8,436 0

0 0

F7QC 7,477 8,436 0

0 0

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 20 Scan Area Highest Logged Reading (cpm)

Action Level (cpm)

of Scan Alarms Judgmental Samples Investigation Samples SP001 7,854 8,363 0

0 0

SP002 7,070 8,363 0

0 0

SP003 5,870 8,363 0

0 0

SP004 5,216 8,363 0

0 0

SP005 5,748 8,363 0

0 0

SP006 7,872 8,363 0

0 0

SP007 5,210 8,363 0

0 0

SP008 5,983 8,363 0

0 0

SP009 5,587 8,363 0

0 0

SP010 5,264 8,363 0

0 0

SP011 5,419 8,363 0

0 0

SP012 6,227 8,363 0

0 0

SP013 5,274 8,363 0

0 0

SP014 5,252 8,363 0

0 0

The Action Level was determined by taking the average of five (5) 1-minute static measurements plus 3,525 cpm. The value of 3,525 cpm equates to 100% Cs-137 having a 0.2206 R/hr/pCi/g value for a detector to end cap distance of three (3) inches, 17 pCi/g for the OpDCGLS and a

detector response for Cs-137 of 940 cpm/r/hr.

(0.2206*17pCi/g*940cpm/R/hr = 3,525cpm.)

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 gamma spectroscopy results for the fourteen (14) samples collected for non-parametric statistical testing is provided in Table 7-2. Gamma spectroscopy results revealed three (3) samples above MDC for Cs-137 at a maximum concentration of 0.0725 pCi/g. There were 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 gamma spectroscopy reports for these samples are presented in Attachment 7. The basic statistics for the systematic sample population is summarized in Table 7-3.

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 21 Table 7 Summary of Gamma Spectroscopy Results for Soil Samples Comprising the Statistical Sample Population Sample ID Co-60 Cs-137 Eu-152 Eu-154 Sr-90 (pCi/g)

(pCi/g)

L1-SUB-LES-FSGS-001-SB 7.00E-02 1.01E-01 1.57E-02 2.80E-02 5.07E-02 L1-SUB-LES-FSGS-002-SB 7.83E-02 4.49E-02 1.42E-01 1.06E-01 2.25E-02 L1-SUB-LES-FSGS-003-SB 7.81E-02 3.87E-02 1.50E-02 5.45E-03 1.94E-02 L1-SUB-LES-FSGS-004-SB 6.08E-03 1.95E-02 1.16E-01 5.69E-02 9.79E-03 L1-SUB-LES-FSGS-005-SB 3.85E-02 2.70E-02 1.23E-01 8.64E-02 1.36E-02 L1-SUB-LES-FSGS-006-SB 5.77E-02 5.11E-02 2.69E-01 4.17E-02 2.57E-02 L1-SUB-LES-FSGS-007-SB 3.41E-03 4.31E-02 5.29E-02 1.63E-01 2.16E-02 L1-SUB-LES-FSGS-008-SB 3.23E-02 7.74E-02 4.85E-03 1.84E-02 3.89E-02 L1-SUB-LES-FSGS-009-SB 5.24E-02 8.54E-02 7.49E-02 1.05E-02 4.29E-02 L1-SUB-LES-FSGS-010-SB 2.90E-02 3.70E-02 0.00E+00 1.26E-02 1.86E-02 L1-SUB-LES-FSGS-011-SB 5.97E-02 3.04E-02 4.68E-02 1.41E-01 1.53E-02 L1-SUB-LES-FSGS-012-SB 3.07E-02 7.25E-02 0.00E+00 1.36E-02 3.64E-02 L1-SUB-LES-FSGS-013-SB 1.42E-02 8.61E-03 6.41E-02 5.29E-02 4.32E-03 L1-SUB-LES-FSGS-014-SB 0.00E+00 3.84E-02 0.00E+00 2.10E-02 1.93E-02 Note: Bold values indicate concentrations greater than MDC.

Table 7 Basic Statistical Properties of Systematic Sample Population ROC Mean Median Max Min Std. Dev. BcDCGL Avg SOF per ROC Avg Dose per ROC (pCi/g)

(pCi/g)

Co-60 3.93E-02 3.54E-02 7.83E-02 0.00E+00 2.73E-02 1.06E+01 0.0037 9.27E-02 Cs-137 4.82E-02 4.09E-02 1.01E-01 8.61E-03 2.65E-02 4.83E+01 0.0010 2.50E-02 Eu-152 6.60E-02 4.99E-02 2.69E-01 0.00E+00 7.61E-02 2.36E+01 0.0028 6.99E-02 Eu-154 5.41E-02 3.49E-02 1.63E-01 5.45E-03 5.11E-02 2.19E+01 0.0025 6.18E-02 Sr-90 2.42E-02 2.05E-02 5.07E-02 4.32E-03 1.33E-02 5.47E+03 0.0000 1.11E-04 The off-site laboratory, GEL Laboratories, processed the two (2) samples (L1-SUB-LES-FSGS-001-SB and L1-SUB-LES-FSGS-012-SB) selected for HTD analysis. Both samples were analyzed for Sr-90. Both analyses met the required MDC.

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 22 Laboratory results revealed that Sr-90 was not detected in either of the samples. The results are provided in Table 7-4.

Table 7 Off-Site Analysis Results Sample ID Sr-90 (pCi/g)

Uncertainty (pCi/g)

MDC (pCi/g)

L1-SUB-LES-FSGS-001-SB 3.64E-02 9.27E-02 1.59E-01 L1-SUB-LES-FSGS-012-SB 1.15E-01 1.10E-01 1.82E-01 Note: Bold values indicate concentrations greater than MDC.

The on-site laboratory analyzed the one (1) judgmental soil sample using the on-site gamma spectroscopy system. A summary of the analytical results for the judgmental soil sample is provided in Table 7-5. The gamma spectroscopy result for Cs-137 was above the MDC at 0.0286 pCi/g. No other ROC was identified above the MDC for the judgmental sample. The concentration for Sr-90 was inferred based on the ratio specified in Table 5-1. The gamma spectroscopy report for this sample is presented in Attachment 7.

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

(pCi/g)

L1-SUB-LES-FJGS-001-SB 8.83E-03 2.86E-02 2.73E-02 1.25E-02 1.44E-02 Note: Bold values indicate concentrations greater than MDC.

The implementation of survey specific QC measures included the collection of two (2) samples (L1-SUB-LES-QSGS-008-SB and L1-SUB-LES-FSGS-013-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 one (1) samples above MDC for Cs-137, with a maximum concentration 0.064 pCi/g, 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.

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 23 Table 7 Summary of Gamma Spectroscopy Results for QC Soil Samples Sample ID Co-60 Cs-137 Eu-152 Eu-154 Sr-90 (pCi/g)

(pCi/g)

L1-SUB-LES-QSGS-008-SB 4.78E-02 0.00E+00 6.42E-03 5.54E-03 0.00E+00 L1-SUB-LES-FSGS-013-SB SPLIT 4.51E-02 6.40E-02 9.19E-02 0.00E+00 3.21E-02 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 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-LES are provided in Table 7-7.

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

Sample ID Fraction of Operational DCGL SOF Co-60 Cs-137 Eu-152 Eu-154 Sr-90 L1-SUB-LES-FSGS-001-SB 0.0183 0.0058 0.0018 0.0035 0.0000 0.0295 L1-SUB-LES-FSGS-002-SB 0.0204 0.0026 0.0167 0.0134 0.0000 0.0532 L1-SUB-LES-FSGS-003-SB 0.0204 0.0022 0.0018 0.0007 0.0000 0.0251 L1-SUB-LES-FSGS-004-SB 0.0016 0.0011 0.0136 0.0072 0.0000 0.0236 L1-SUB-LES-FSGS-005-SB 0.0101 0.0016 0.0145 0.0110 0.0000 0.0370 L1-SUB-LES-FSGS-006-SB 0.0151 0.0029 0.0316 0.0053 0.0000 0.0549 L1-SUB-LES-FSGS-007-SB 0.0009 0.0025 0.0062 0.0207 0.0000 0.0303 L1-SUB-LES-FSGS-008-SB 0.0084 0.0045 0.0006 0.0023 0.0000 0.0158 L1-SUB-LES-FSGS-009-SB 0.0137 0.0049 0.0088 0.0013 0.0000 0.0287 1

2 2

1 1

d

DCGL C

n n

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 24 Sample ID Fraction of Operational DCGL SOF Co-60 Cs-137 Eu-152 Eu-154 Sr-90 L1-SUB-LES-FSGS-010-SB 0.0076 0.0021 0.0000 0.0016 0.0000 0.0113 L1-SUB-LES-FSGS-011-SB 0.0156 0.0017 0.0055 0.0179 0.0000 0.0407 L1-SUB-LES-FSGS-012-SB 0.0080 0.0042 0.0000 0.0017 0.0000 0.0139 L1-SUB-LES-FSGS-013-SB 0.0037 0.0005 0.0075 0.0067 0.0000 0.0184 L1-SUB-LES-FSGS-014-SB 0.0000 0.0022 0.0000 0.0027 0.0000 0.0049 L1-SUB-LES-QSGS-008-SB 0.0125 0.0000 0.0008 0.0007 0.0000 0.0139 L1-SUB-LES-FSGS-013-SB SPLIT 0.0118 0.0037 0.0108 0.0000 0.0000 0.0263 Systematic Measurements Number of Systematic Measurements =

14

of Systematic Measurements with SOF > 1 =

0

of Systematic Measurements with SOF > 0.1 (HTD Assessment) =

0 Max Individual Systematic Measurement SOF =

0.0549 Mean Systematic Measurement SOF =

0.0277 The results of the unity rule calculation for the ROC in the judgmental sample population for survey unit L1-SUB-LES are provided in Table 7-8.

Table 7 Sum-of-Fractions for Individual Soil Samples (Judgmental)

Sample ID Fraction of Operational DCGL SOF Co-60 Cs-137 Eu-152 Eu-154 Sr-90 L1-SUB-LES-FJGS-001-SB 0.0023 0.0016 0.0032 0.0016 0.0000 0.0087

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 25 Judgmental Measurements Number of Judgmental Measurements =

1

of Judgmental Measurements with SOF > 1 =

0

of Judgmental Measurements with SOF > 0.1 (HTD Assessment) =

0 Max Individual Judgmental Measurement SOF =

0.0087 Mean Judgmental Measurement SOF =

0.0087 8.

QUALITY CONTROL The on-site laboratory processed two (2) split and duplicate samples (L1-SUB-LES-QSGS-008-SB and L1-SUB-LES-FSGS-013-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 survey unit L1-010-103 was to remove the LSA Building, Septic Tank, Eat Shack Foundation, Oily Water Tank, Circulating Water Intake

& Discharge piping, Main Transformer Substation as well as associated system lines. The purpose of the excavation was not to support removal of contaminated subsurface soil.

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).

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 26 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 Sign Test results are provided in Attachment 3.

The data assessment and 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 is less than the Consultation Triggers for Residential Soil Concentration depicted in Table H.1 of NUREG 1757, Vol.1, Rev. 2 (MOU Table 1).

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

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

13.

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

14.

CONCLUSION Survey unit L1-SUB-LES 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.

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 27 The dose contribution from soil in survey unit L1-SUB-LES is 0.2495 mrem/yr TEDE, based on the average concentration of the ROC in samples used for non-parametric statistical sampling.

Survey unit L1-SUB-LES 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

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 - Figures and Maps - Scan Data - Sign Test - Quality Control Assessment - Consultation Triggers for Residential Soil Concentrations

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 28

- Graphical Presentations - Sample Analytical Reports - GEL Laboratories Analytical Reports

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 29 ATTACHMENT 1 FIGURES AND MAPS

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 30 Figure 16 L1-SUB-LES Sample Locations Map

31 FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES ATTACHMENT 2 SCAN DATA

32 FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES Table 16 L1-SUB-LES Complete Scan Data Detector Type Detector ID M2350-1 ID Location Scan Logged Result (cpm)

Avg

Background

(cpm)

Action Level (cpm)

Scan Alarms 44-10 318218 120636 A1 4,658 4,911 8,436 0

44-10 357776 325246 A2 6,063 4,760 8,285 0

44-10 318218 120636 A3 5,461 4,349 7,874 0

44-10 357776 3325246 A4 5,759 4,864 8,389 0

44-10 318218 120636 A5 5,834 4,349 7,874 0

44-10 162398 126195 A6 5,767 6,913 10,438 0

44-10 318218 120636 A7 4,931 4,813 8,338 0

44-10 357776 325246 A8 5,393 4,760 8,285 0

44-10 318218 120636 B1 5,140 4,911 8,436 0

44-18 357776 325246 B2 5,186 4,760 8,285 0

44-10 318218 120636 B3 5,661 4,349 7,874 0

44-10 357776 3325246 B4 5,432 4,864 8,389 0

44-10 318218 120636 B5 5,254 4,349 7,874 0

44-10 162398 126195 B6 6,115 6,913 10,438 0

44-10 318218 120636 B7 5,225 4,450 7,975 0

44-10 357776 325246 B8 5,725 4,828 8,353 0

44-10 318218 120636 C1 5,482 4,911 8,436 0

44-10 357776 325246 C2 5,635 4,760 8,285 0

44-10 318218 120636 C3 5,569 4,349 7,874 0

44-10 318218 120636 C3QC 5,905 4,911 8,436 0

44-10 357776 3325246 C4 5,652 4,864 8,389 0

44-10 318218 120636 C5 5,061 4,349 7,874 0

44-18 162398 126195 C6 6,490 6,913 10,438 0

44-10 318218 120636 C7 5,593 4,450 7,975 0

44-10 357776 325246 C8 6,367 4,828 8,353 0

44-10 357783 325261 D1 6,830 4,772 8,297 0

44-10 357776 3325246 D2 6,195 4,864 8,389 0

44-10 318218 120636 D3 5,548 4,349 7,874 0

44-10 357776 3325246 D4 7,258 4,864 8,389 0

44-10 318218 120636 D5 6,055 4,349 7,874 0

44-10 357776 325246 D6 7,654 4,828 8,353 0

44-10 318218 120636 D7 6,243 4,450 7,975 0

33 FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES Detector Type Detector ID M2350-1 ID Location Scan Logged Result (cpm)

Avg

Background

(cpm)

Action Level (cpm)

Scan Alarms 44-10 357776 325246 D8 6,075 5,730 9,255 0

44-10 357783 325246 E1 11,850 4,911 8,436 1

44-10 318218 120636 E1 6,055 4,772 8,297 0

44-10 357783 325261 E1 6,992 4,772 8,297 0

44-10 357776 3325246 E2 6,064 4,864 8,389 0

44-10 318218 120636 E3 5,983 4,349 7,874 0

44-18 357776 3325246 E4 7,145 4,864 8,389 0

44-10 318218 120636 E5 7,208 4,349 7,874 0

44-10 162398 126195 E6 8,738 6,913 10,438 0

44-10 357776 325246 E7 6,930 5,730 9,255 0

44-10 318218 120636 E8 5,816 4,813 8,338 0

44-10 357776 325246 F7 8,720 5,730 9,255 0

44-10 318218 120636 F7QC 7,477 4,911 8,436 0

44-10 318218 120636 F8 6,456 4,813 8,338 0

44-10 357776 325246 G7 9,093 5,730 9,255 0

44-10 318218 120636 G8 7,998 4,813 8,338 0

44-10 318218 120636 QC008 5,335 4,542 8,067 0

44-10 357776 325246 SP001 7,854 4,838 8,363 0

44-10 357776 325246 SP001 6,453 4,838 8,363 0

44-10 318218 120636 SP001 5,326 4,911 8,436 0

44-10 357776 325246 SP002 7,070 4,838 8,363 0

44-10 357776 325246 SP002 5,648 4,838 8,363 0

44-10 357776 325246 SP003 5,870 4,838 8,363 0

44-18 357776 325246 SP003 5,797 4,838 8,363 0

44-10 357776 325246 SP004 5,216 4,838 8,363 0

44-10 357776 325246 SP004 5,033 4,838 8,363 0

44-10 357776 325246 SP005 5,748 4,838 8,363 0

44-10 357776 325246 SP005 5,509 4,838 8,363 0

44-10 357776 325246 SP006 7,872 4,838 8,363 0

44-10 357776 325246 SP006 6,910 4,838 8,363 0

44-10 357776 325246 SP007 5,210 4,838 8,363 0

44-10 357776 325246 SP007 5,039 4,838 8,363 0

44-10 357776 325246 SP008 5,983 4,838 8,363 0

34 FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES Detector Type Detector ID M2350-1 ID Location Scan Logged Result (cpm)

Avg

Background

(cpm)

Action Level (cpm)

Scan Alarms 44-10 357776 325246 SP008 5,377 4,838 8,363 0

44-10 357776 325246 SP009 5,587 4,838 8,363 0

44-10 357776 325246 SP009 5,344 4,838 8,363 0

44-10 357776 325246 SP010 5,264 4,838 8,363 0

44-10 357776 325246 SP010 4,877 4,838 8,363 0

44-10 357776 325246 SP011 5,419 4,838 8,363 0

44-10 357776 325246 SP011 4,980 4,838 8,363 0

44-10 357776 325246 SP012 6,227 4,838 8,363 0

44-10 357776 325246 SP012 5,855 4,838 8,363 0

44-10 357776 325246 SP013 5,274 4,838 8,363 0

44-10 357776 325246 SP013 4,983 4,838 8,363 0

44-10 357776 325246 SP014 5,252 4,838 8,363 0

44-10 357776 325246 SP014 4,993 4,838 8,363 0

Average Background established by taking the average of 5 1-minute static readings in each location.

35 FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES ATTACHMENT 3 SIGN TEST

36 FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES Table 16 L1-SUB-LES Sign Test SOF 1-WS Sign (WS) 1 0.0295 0.97

+1 2

0.0532 0.95

+1 3

0.0251 0.97

+1 4

0.0236 0.98

+1 5

0.0370 0.96

+1 6

0.0549 0.95

+1 7

0.0303 0.97

+1 8

0.0158 0.98

+1 9

0.0287 0.97

+1 10 0.0113 0.99

+1 11 0.0407 0.96

+1 12 0.0139 0.99

+1 13 0.0184 0.98

+1 14 0.0049 1.00

+1 Number of positive differences (S+)

14 Critical Value 10 Survey Unit Meets the Acceptance Criteria

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 37 ATTACHMENT 4 QUALITY CONTROL ASSESSMENT

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 38 Table 16 L1-SUB-LES QC Assessment L1-SUB-LES-FSGS-008-SB K-40 6.27E+00 7.32E-01 9

0.6 1.66 L1-SUB-LES-QSGS-008-SB 5.79E+00 6.82E-01 0.92 Y

L1-SUB-LES-FSGS-013-SB K-40 5.48E+00 6.61E-01 8

0.6 1.66 L1-SUB-LES-FSGS-013-SB SPLIT 5.15E+00 6.18E-01 0.94 Y

STANDARD COMPARISON Agreement Range (Low to High)

Standard Error Comparison Ratio Acceptable (Y/N)

Table is provided to show acceptance criteria used to assess split samples.

Comments/Corrective Actions: K-40 was substituted for the assessment of location #8, because Cs-137 was not identified in either the standard or comparison sample. For location #13, K-40 was substituted, because Cs-137 was identified at a low level in only the comparison sample.

Sample ID Sample ID Radionuclide Activity Value Standard Error Resolution Activity Value

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 39 ATTACHMENT 5 CONSULTATION TRIGGERS FOR RESIDENTIAL SOIL CONCENTRATION

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 40

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 41 ATTACHMENT 6 GRAPHICAL PRESENTATIONS

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 42 Figure 16 Quantile Plot for Cs-137 Concentration 0.00E+00 2.00E-02 4.00E-02 6.00E-02 8.00E-02 1.00E-01 1.20E-01 0%

10%

20%

30%

40%

50%

60%

70%

80%

90%

100%

CS-137 CONCENTRATION (PCI/G)

PERCENTAGE

43 FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES Figure 16 Histogram for Cs-137 Concentration 0

1 2

3 4

5 6

2.54E-02 4.23E-02 5.91E-02 7.59E-02 9.28E-02 1.10E-01 FREQUENCY UPPER END VALUE (PCI/G)

44 FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES Figure 16 Retrospective Power Curve for L1-SUB-LES

FSS RELEASE RECORD L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 45 ATTACHMENT 7 SAMPLE ANALYTICAL REPORTS

~ Apex-Gamma 1/31/2019 7:56:26AM Analysis Report for L 1-SUB-LES-FSGS-001-SB SYSTEMATICS FOR l 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-001-SB

SYSTEMATICS FOR l 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 7.984E+02 grams

Dairyland_NPP

2/2/2018 1 :45:00PM

2/5/2018 10:10:34AM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3609.0 seconds

0.25 %

3.00

100 - 4096

100-4096

1.000 keV

7/8/2014

5796 PEAK ANALYSIS REPORT 1/31/2019 7:56:16AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of7

F F

F 1/31/2019 7:56:26AM Page 2 of 7 Analysis Report for L 1-SUB-LES-FSGS-001-SB F

F F

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

169.02 335 -

2 208.61 414 -

3 238.4 1 470 -

4 351.69 697 -

5 582. 87 115 9 -

6 608.86 1212 -

7 726.49 14 4 6 -

8 910.65 1 815 -

9 1459.87 2911 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI Peak Net Peak end Centroid Area 342 338. 55 3. 79E+Ol 42 1 417. 71 6.02E+Ol 484 477.29 3.40E+02 710 703.82 l. 65E+02 1174 1166. 09 9.20E+Ol 1225 1218. 05 l. 11E+02 1 45 9 1 453. 26 4. 24E+Ol 1826 1821. 53

4. 76E+Ol 2929 2919. 86 5. 47E+02 Net Area Continuum Uncertainty Counts 13.93 4.51E+02 30.37 4.05E+02 49. 34 6.37E+02 34.63

3. 00E+02 24.03

1. 55E+02 26.39 l. 28E+02 1 6.51 6. 68E+Ol 19.04 9.26E+Ol 47.52 2. 85E+Ol BACKGROUND SUBTRACT REPORT

1/31/2019 7:56:16AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 169. 02 3.79E+O l 13.93 2

208. 61 6.02E+O l 30.37 3

238.41 3.40E+02 49.3 4 4

351.69 1.65E+02 34. 63 8. 36E+Ol 3.72E+Ol 5

582. 87 9. 20E+Ol 24. 03 6

60 8. 86 l.11E+02 26. 39 4. 12E+Ol 2. 42E+Ol 7

726.4 9 4. 24E+Ol 16.51 8

91 0. 65 4.76E+Ol 1 9. 04 9

1 459. 87 5.47E+02 47.52 5.63E+Ol l. 71E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 3. 79E+Ol

6. 02E+Ol

3. 40E+02 8.12E+Ol 9.20E+Ol 7.0lE+Ol 4.24E+O l 4.76E+Ol 4.90E+02 FWHM (keV) 0.48

1. 29 2.27 2. 25

1. 94 2. 27

1. 87

1. 93 2.87 Subtracted Uncert.

l. 39E+Ol 3.0 4E+Ol 4.93E+Ol 5.08E+O l 2.40E+O l 3. 58E+Ol

1. 65E+Ol l. 90E+Ol 5.05E+Ol

1/31/2019 7:56:26AM Page 3 of7 Analysis Report for l 1-SUB-LES-FSGS-001-SB SYSTEMATICS FOR l 1-SUB-LES WITHIN Survey Unit L 1-010-103 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\library\\HOTLAB.NLB IDENTIFIED NUCLIDES Nucllde Id Energy Name Confidence (keV)

K-40 0.88 1460.75 BI-212 0.55 727.17 785.42 1620.56 PB-212 0.55 77.11 238.63 BI-214 0.33 609.31 1120.29 1238.11 1377. 67 1407.98 1509.19 1764.49

= 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 Yield(%)

10.67

11. 80 2.00 2.75 17.50 44.60 46.30 15.10 5.94 4.11 2.48 2.19 15.80 Activity (pCi/grams) 6.69E+OO 2.82E-01 2.19E-01

1. OlE-01 Activity Uncertainty 7.83E-Ol

1. llE-01 3.38E-02 5.19E-02 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence (pCilgrams)

Uncertainty K-40 0.884 6.69E+OO 7.83E-01 BI-212 0.553 2.82E-01

1. llE-01 PB-212 0.555 2.19E-01 3.38E-02

1/31/2019 7:56:26AM Page 4 of?

Analysis Report for L1-SUB-LES-FSGS-001-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name BI-214 Nuclide Id Confidence 0.333

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCi/grams) 1.0lE-01

= nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Comments Activity Uncertainty 5.19E-02

1/31/2019 7:56:26AM Analysis Report for L 1-SUB-LES-FSGS-001-SB F

F F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 1 169.02 2

208.61 4

351.69 5

582.87 8

910.65 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 7:56:16AM

100

4096 Peak Size (CPS) l.05308E-02 l.67340E-02 2.25627E-02 2.55609E-02 l.32334E-02 Peak CPS(%)

Uncertainty 18.38 25.21

31. 29 13.06 19.98 Peak Type Tol.

Tol.

NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity NuclldeMDA LineMDA Name (keV)

(pCi/grams)

(pCilgrams)

(pCi/grams)

K-40 1460.75 10.67 6.69E+OO 6.36E-01 6.36E-01 AR-41 1293.64 99.16

-2.84E+08 l.29E+l0 l.29E+l0 C0-60 1173.22 100.00

1. 26E-03 6.18E-02 6.74E-02 1332.49 100.00 7.00E-02 6.lSE-02 KR-85 513.99 0.43

1. 23E+Ol l.06E+Ol l.06E+Ol Y-88 898.04 93.70 4.48E-02 3.96E-02 5.59E-02 1836.06 99.20

-l.29E-02 3.96E-02 NB-94 702.63 100.00 2.31E-02 4.21E-02 4.21E-02 871.10 100.00

-l.90E-02 4.59E-02 I-131 284.30 6.06

-4.81E-Ol 5.31E-02 7.02E-01 Page 5 of7 Tolerance Nuclide AC-228 PB-214 AC-228 PA-228

1/31/2019 7:56:26AM Page 6 of7 Analysis Report for L 1-SUB-LES-FSGS-001-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity Nuc/ldeMDA LineMDA Name (keV)

(pCilgrams)

(pCi/grams)

I-131 364.4 8

81. 20

- 2. 30E-02 5.31E- 02 5.31E-02 636. 97 7. 27

- 1.49E-01 6. 68E- 01

+

CS-134 604. 70 97. 60

- 1.1 4E-02 5.26E- 02 5.30E-02 795. 84 85. 40 1. 00E-02 5.26E- 02

+

CS-137 661.65 85. 12 1.0lE-01 6. 16E-02 6. 16E- 02

+

CE-144 80. 12

1. 36 3.64E+OO 2. 74E-Ol 3.56E+OO 133.51

11. 09

-8.62E- 02 2.74E-Ol

+

EU-152 121. 78 28.40 l.57E- 02

1. l OE-01 l.l OE-01 344.28 26. 60

1. 09E- 01 l.45E-0 1 1 408.00 20.7 4

4. 71E-02 2.21E-Ol

+

EU-1 54 123.07 40.40 2. 80E- 02 7.7 5E-02 7.75E- 02 723. 30 19. 70 l.77E-Ol 2. 3 1E-01 1274.51 35.50

1. 28E-02

1. 80E- 01

+

EU-155 86.54 32. 80

- 9.27E-02 1.2 4E-Ol l.24E- 01 105.31

21. 80

- 2. 19E-02 1. 50E-Ol

+

BI - 214 609. 31 4 6. 30 1. 0lE- 01

9. 43E-02

9. 43E-02 1120. 29 15. 10 5. 85E-02 4. 27E-01 1238.11 5.94 2.35E- 01 l.2 4E+OO 1377.67 4.11 9. 33E- 02

1. 04 E+OO 1407.98 2. 48 3.94E- 01 1. 85E+OO 150 9.1 9 2.19

1. 52E+OO 2.12 E+OO 1764.49 15.80 3. 45E-0 1 3. 55E-01

+

PB-21 4 77. 11 10.70 6.57E-Ol 1.lOE-01 4. 81E-Ol 295.2 1 1 9. 20 2. 89E-01 2.0 l E- 01 351. 92 37. 20 l. 67E-Ol l.l OE-01

+

PA-228 89. 95 22. 00 2.27E+OO 9. 39E- 01

1. 58E+ OO 93. 35 35. 00 5. 85E-O l 9. 39E- 01 1 05.00 16. 30 2.99E-01 1.77E+OO 129. 22 2. 97

6. 42E+OO 9.21E+ OO 338. 32 5. 30 3. 17E+OO 6. 07E+OO 463.00 13. 80 l.81E+OO 2. 48E+OO 911.23 16. 70 3. 39E+OO 3. 22E+OO

+

AM-2 41 59. 54 36.30

1. 46E-02 2. 25E-Ol 2.25E- 01

+

CM-243 103.76 23.00 l.59E- 01

1. 4 6E- 01 l.46E- 01 228. 18 10.60

- 3. 79E-02 2.86E-01 277. 60 14. 00 l.48E-02 2. 39E-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

1/31/2019 7:56:26AM Page 7 of7 Analysis Report for L 1-SUB-LES-FSGS-001-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

,..Apex-Gamma 1/31/2019 8:01:57AM Analysis Report for L 1-SUB-LES-FSGS-002-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live nme RealTime DeadTime Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-002-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 9.216E+02 grams

Dairyland_NPP

2/2/2018 1 :53:00PM

2/5/2018 11:12:30AM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3609.6 seconds

0.27%

3.00

100 - 4096

100-4096

1.000 keV

7/8/2014

5798 PEAK ANALYSIS REPORT 1/31/2019 8:01:48AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of6

F F

F 1/31/2019 8:01:57AM Page 2 of6 Analysis Report for L 1-SUB-LES-FSGS-002-SB F

F F

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

185.79 368 -

2 238.46 470 -

3 294.87 582 -

4 351.76 696 -

5 583.10 1160 -

6 608.88 1211 -

7 910.69 1813 -

8 1460.12 2911 -

9 1762.97 3521 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI Peak Net Peak end Centroid Area 375 372.09 6.33E+Ol 484 477.39 4.32E+02 598 590.19 8.24E+Ol 709 703.94 1.83E+02 1175 1166.54

1. 27E+02 1226 1218.10 1.32E+02 1829 1821.62 8.44E+Ol 2929 2920.35 6.55E+02 3531 3526.01 2.36E+Ol Net Area Continuum Uncertainty Counts 35.19 4.92E+02 54.53 6.82E+02 29.98 5.28E+02 34.89 3.16E+02 27.97 1.52E+02 28.85

1. 59E+02 22.85 8.93E+Ol 52.00 3.75E+Ol 10.95 8.SOE+OO BACKGROUND SUBTRACT REPORT

1/31/2019 8:01:48AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 185.79 6.33E+Ol 35.19 2

238.46 4.32E+02 54.53 3

294.87 8.24E+Ol 29.98 4

351.76

1. 83E+02 34.89 8. 36E+Ol 3.72E+Ol 5

583.10 1.27E+02 27.97 6

608.88 1.32E+02 28.85 4.12E+Ol 2.42E+Ol 7

910.69 8.44E+Ol 22.85 8

1460.12 6.55E+02 52.00 5.63E+Ol 1.71E+Ol 9

1762.97 2.36E+Ol 10.95 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 6.33E+Ol 4.32E+02 8.24E+Ol 9.92E+Ol

1. 27E+02 9.08E+Ol 8.44E+Ol 5.98E+02 2.36E+Ol FWHM (keV)

1. 53 2.37

1. 72 1.~

2.46 2.60 3.03 2.89 2.34 Subtracted Uncert.

3.52E+Ol 5.45E+Ol 3.00E+Ol 5.lOE+Ol 2.80E+Ol 3.77E+Ol 2.29E+Ol 5.48E+Ol 1.09E+Ol

1/31/2019 8:01:57AM Page 3 of6 Analysis Report for L 1-SUB-LES-FSGS-002-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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 0.93 1460.75 10.67 7.07E+OO 7.57E-01 PB-212 0.55 77.11 17.50 238.63 44.60 2.41E-01 3.30E-02 BI-214 0.33 609.31 46.30 1.13E-Ol 4.75E-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-Ol 4.69E-02 351.92 37.20 9.30E-02 4.80E-02 RA-226 0.97 186.21 3.28 4.05E-01 2.26E-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 0.938 7.07E+OO 7.57E-01 PB-212 0.557 2.41E-01 3.30E-02

1/31/2019 8:01 :57AM Analysis Report for L 1-SUB-LES-FSGS-002-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name BI-214 PB-214 RA-226 Nuclide Id Confidence 0.335 0.714 0.973

?

= nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis Wt mean Activity (pCilgrams) 1.13E-01

1. llE-01 4.0SE-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Activity Uncertainty 4.75E-02 3.36E-02 2.26E-01 Page4 of6 Comments

1/31/2019 8:01:57AM Analysis Report for L 1-SUB-LES-FSGS-002-SB F

F F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 5 583.10 7

910.69 9

1762.97 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:01:48AM

100

4096 Peak Size (CPS) 3.51754E-02 2.34515E-02 6.55813E-03 Peak CPS(%)

Uncertainty

11. 04 13.53 23.18 Peak Type Tol.

NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LlneMDA Name (keV)

(pCVgrams)

(pCilgrams)

K-40 1460.75 10.67 7.07E+OO 5.72E-Ol 5.72E-01 AR-41 1293.64 99.16

-2.55E+09

1. 53E+l0 l.53E+l0 C0-60 1173.22 100.00 7.83E-02 5.47E-02 6.21E-02 1332.49 100.00 3.94E-02 5.47E-02 KR-85 513.99 0.43 9.47E+OO 9.62E+OO 9.62E+OO Y-88 898.04 93.70 4.47E-03 3.60E-02 4.61E-02 1836.06 99.20 6.56E-03 3.60E-02 NB-94 702.63 100.00 9.08E-03 3.78E-02 3.78E-02 871.10 100.00

-5.77E-02 4.14E-02 I-131 284.30 6.06 l.55E-Ol 4.81E-02 6.46E-01 364.48

81. 20

-2.89E-02 4.81E-02 636.97 7.27 l. 76E-Ol 6.65E-01 CS-134 604.70 97.60 l.16E-02 4.79E-02 4.79E-02 Page 5 of6 Tolerance Nuclide AC-228 PA-228

1/31/2019 8:01 :57AM Page 6 of6 Analysis Report for L 1-SUB-LES-FSGS-002-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity Nucl/deMDA LineMDA Name (keV)

(pCi/grams)

CS-134 795.84 85.40 2.60E-02 4.79E-02 4.92E-02

+

CS-137 661.65 85.12 4.49E-02 5.19E-02

5. 1 9E-02

+

CE-14 4 80.12

1. 36 3.35E+OO 2.61E-Ol 3.23E+OO 133.51 11. 09 2.22E-01 2. 61E-0 1

+

EU-152 121.78 28.4 0

-4.82E-02 1.00E-01

1. 00E- 01 344. 28 26. 60

1. 42E-01

1. 33E-Ol 1408.00 20. 74

- 6. 45E-02 1.85E-01

+

EU-154 123.07 40.40

-2.27E-02 7. 07E-02 7.07E- 02 723.3 0 19.7 0 1.06E-01

2. llE-01 1274.51 35.50

-5.35E-02 l.51E-Ol

+

EU-155 86.54 32.80

- 6.66E-02 1.13E-O l l.13E-Ol 105.31

21. 80 1.64E-02 l.37E-01

+

BI-214 609.31 46.30 1.13E-01 8.90E-02 8.90E-02 1120.29 15.10

- 2. 73E- 02 3.30E-Ol 1238.11 5.94 4.38E-01 1.09E+OO 1377. 67 4.11 4.26E-01

1. 07E+OO 1407. 98 2.48

-5.39E-01

1. 55E+OO 1509.19 2.19

- 4.56E-01 1.48E+OO 1764.49 15.80 1.73E-01 2.97E-Ol

+

PB-21 4 77.11 10.70 4.55E-01 9.33E-02 4.34E-Ol 295.21 19.20 l.28E-01 1.51E-01 351.92 37. 20 9.30E- 02 9.33E-02

+

PA-228 89.95 22.00 l.87E+OO 8. 84E-01

1. 49E+OO 93.35 35.00 8.61E- 01 8. 84E-0 1 105.00 16. 30

- 2.55E-Ol 1.65E+OO 129. 22 2.97 2.46E+OO 8.63E+OO 338. 32 5.30 6. 32E+OO 5.90E+OO 463.00 13.80

-1.98E+OO 2.19E+OO 911.23 16.70 4.lOE+OO 2.97E+OO

+

AM-241 59.54 36.30

-7.47E-02 2.00E-01 2.00E-01

+

CM-243 103. 76 23.00 4.40E-02 l. 32E-01 l. 32E- 01 228.18 10.60 4.61E- 02 2.65E-01 277. 60 14.00 3.35E-03

2. 18E-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

~~~~pex-Gamma 1/31/2019 8:02:51AM Analysis Report for L 1-SUB-LES-FSGS-003-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-003-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 9.282E+02 grams

Dairyland_NPP

2/2/2018 2:01 :OOPM

2/5/2018 12:14:05PM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3609.9 seconds

0.27%

3.00

100-4096

1.000 keV

7/8/2014

5800 PEAK ANALYSIS REPORT 1/31/2019 8:02:42AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of6

F F

1/31/2019 8:02:51AM Page 2 of6 Analysis Report for L 1-SUB-LES-FSGS-003-SB F

F F

F SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

76.39 146 -

2 238.46 469 -

3 338.22 671 -

4 351.69 696 -

5 582.87 1159 -

6 609.08 1210 -

7 910.74 1816 -

8 968. 23 1932 -

9 1331.55 2656 -

10 1460.13 2912 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI Peak Net Peak end Centroid Area 1 60 153.33 2.71E+02 485 477.39 3.21E+02 684 676.87 6.90E+Ol 710 703.82 l.61E+02 11 71 1166.07 9.0lE+Ol 1226 1218.50 l.08E+02 1828 1821. 73 5.53E+Ol 1942 1936. 68 2.63E+Ol 2668 2663.24 3.65E+Ol 2929 2920. 37 5.4 2E+02 Net Area Continuum Uncertainty Counts 59. 98

1. 34E+03 4 9.10 7.32E+02 26.84 2. 88E+02 34.13 3. 19E+02 25.47 l.72E+02 25.37 l. 37E+02 20. 10 8.84E+Ol 16.25 9.95E+Ol 16. 73 5.79E+Ol 48.11 4.92E+Ol BACKGROUND SUBTRACT REPORT

1/31/2019 8:02:42AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 76.39 2.71E+02 59.98 2

238. 46 3. 21E+02 49.10 3

338.22 6.90E+Ol

26. 84 4

351.69 l. 61E+02 34.13 8.36E+Ol 3.72E+Ol 5

582.87 9.0lE+Ol 25.47 6

609.08

1. 08E+02 25.37 4.12E+Ol 2.42E+Ol 7

910.74 5. 53E+Ol 20.10 8

968.23 2.63E+Ol 16.25 9

1331. 55 3. 65E+Ol

16. 73 10 14 60.13 5.42E+02 48. 11 5.63E+Ol 1.71E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 2.71E+02 3. 21E+02 6. 90E+Ol 7.76E+Ol 9.0lE+Ol 6.66E+Ol 5.53E+Ol 2.63E+Ol 3.65E+Ol 4. 86E+0 2 FWHM (keV) 2.71 2.36 2.02 2.20 2. 00 2. 33 2.39

1. 64 2. 34 2.78 Subtracted Uncert.

6.00E+Ol 4. 91E+Ol 2. 68E+Ol 5.05E+Ol 2.55E+Ol 3.51E+Ol 2.0lE+Ol 1.62E+Ol l.67E+Ol

5. llE+Ol

1/31/2019 8:02:51AM Page 3 of6 Analysis Report for L 1-SUB-LES-FSGS-003-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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 0.94 1460.75 10.67 5.70E+OO 6.78E-01 PB-212 0.97 77.11 17.50 4.18E-Ol 9.63E-02 238.63 44.60 1.79E-Ol 2.88E-02 BI-214 0.34 609.31 46.30 8.26E-02 4.38E-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 0.50 77.11 10.70 6.83E-01

1. 57E-Ol 295.21 19.20 351. 92 37.20 7.22E-02 4.71E-02 AC-228 0.56 209.28 4.40 338.32

11. 40 2.02E-01 7.93E-02 794.70 4.60 911. 60 27.70 l.65E-01 6.04E-02 964. 60 5.20 969.11 16.60 1.38E-Ol 8.57E-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

1/31/2019 8:02:51AM Analysis Report for L 1-SUB-LES-FSGS-003-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name K-40 PB-212 BI-214 PB-214 AC-228 Nuclide Id Confidence 0.940 0.974 0.345 0.509 0.560

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCl/grams) 5.70E+OO 1.93E-01 8.26E-02 9.64E-02

1. 69E-Ol

= nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Activity Uncertainty 6.78E-01 2.77E-02 4.38E-02 4.53E-02 4.19E-02 Page 4 of6 Comments

1/31/2019 8:02:51AM Analysis Report for L 1-SUB-LES-FSGS-003-SB F

F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

5 9

Energy (keV) 582.87 1331. 55 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:02:42AM

100

4096 Peak CPS(%)

Peak Size (CPS)

Uncertainty 2.50222E-02 1.01294E-02 14.14 22.93 Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Oairyland_NPP\\Library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi/grams)

(pCVgrams)

K-40 1460.75 10.67 5.70E+OO 5.91E-01 5.91E-01 AR-41 1293.64 99.16 5.14E+08 2.18E+10 2.18E+10 C0-60 1173.22 100.00 2.56E-02 6.24E-02 6.53E-02 1332.49 100.00 7.81E-02 6.24E-02 KR-85 513.99 0.43 7.57E+OO 8.88E+OO 8.88E+OO Y-88 898.04 93.70

-8.74E-03 4.39E-02 4.62E-02 1836.06 99.20 1.48E-02 4.39E-02 NB-94 702.63 100.00 1.37E-02 3.57E-02 3.57E-02 871.10 100.00

4. llE-03 3.93E-02 I-131 284.30 6.06

-4.52E-01 4.51E-02 6.0lE-01 3 64. 4 8

81. 20

-1.42E-02 4.51E-02 636.97 7.27 2.95E-01 6.45E-01 CS-134 604.70

97. 60

-1.17E-03 4.50E-02 4.50E-02 795.84 85.40 2.00E-03 4.78E-02 CS-137 661.65 85.12 3.87E-02 4.99E-02 4.99E-02 CE-144 80.12

1. 36

-9.69E-01 2.49E-01

3. llE+OO Page 5 of6 Tolerance Nuclide

1/31/2019 8:02:51AM Page 6 of6 Analysis Report for L 1-SUB-LES-FSGS-003-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity NuclldeMDA L/neMDA Name (keV)

(pCilgrams)

(pCi/grams)

CE-144 133.51

11. 0 9 l.19E-01 2.49E-Ol

2. 49E-Ol

+

EU-152 121. 78 28.40

-7.05E-02 9.55E-02 9.55E- 02 344.28 26. 60 l.50E-02 l.23E-01 1408. 00 20. 74

-l.03E- 01 l.86E-0 1

+

EU-154 123.07 40.40 5.45E-03 6. 77E-02 6.77E-02 723.30 19. 70 l.75E-01 2.00E-01 127 4.51 35. 50 2.12E-02 l.46E-01

+

EU-155 86.54 32.80

-3.93E- 02 l.07E-01

1. 07E-01 105.31 21.80 3.23E- 02

1. 32E-01

+

BI-2 1 4 609.31 46.30 8.26E- 02 8.52E-02 8. 52E- 02 1120. 29 15.10 8.24E-02 3. 84E-Ol 1238.11 5.94 6.99E-01 l. 09E+OO 1377.67 4.11

- l.96E-Ol 9. 52E-Ol 1407.98 2. 48

-8.60E- 01 l. 55E+OO 1509.19 2.19 2.20E- 01

1. 58E+OO 1764.49 15. 80 2.37E-01 3. 18E-01

+

PB-214 77.11 10.70 6.83E-01 9. 37E- 02 3.71E-Ol 295.21 19.20 2. 56E-01 l.68E-01 351.92 37.20 7.22E-02 9.37E-02

+

PA-228 89.95 22.00

1. 65E+OO 8.64E-Ol

1. 45E+OO 93. 35 35. 00 6.37E- 01 8.64E-01 105. 00 16.30

1. 07E+OO l.65E+OO 129.22 2.97

-3. 06E+OO 8. 49E+OO 338. 32 5.30 8.50E-Ol 5.34E+OO 463.00

13. 80 2. 45E+OO 2.35E+OO 911.23 16.70 3. 04E+OO 2. 88E+OO

+

AM-24 1 59.54 36.30

- l. 83E- 01 1. 96E-Ol 1. 96E-Ol

+

CM-243 103.76 23.00 2. 87E-02 l.2 7E-01 l. 2 7E- 01 228. 18 10.60

- 2.17E-01 2.56E-01 277.60 1 4.00

-3. 56E-02 2. 08E- 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

~~~~pex-Gamma 1/31/2019 8:03:34AM Analysis Report for L 1-SUB-LES-FSGS-004-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-004-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 9.932E+02 grams

Dairyland_NPP

2/2/2018 2:04:00PM

2/5/2018 1:15:20PM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3609.8 seconds

0.27%

3.00

100 - 4096

1.000 keV

7/8/2014

5802 PEAK ANALYSIS REPORT 1/31/2019 8:03:25AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of7

1/31/2019 8:03:34AM Page 2 of7 Analysis Report for L 1-SUB-LES-FSGS-004-SB F

F F

F SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peal<

Energy ROI No.

(keV) start 1

238. 49 472 -

2 294.93 584 -

3 337.6 8 670 -

4 582.72 1159 -

5 60 8. 95 121 0 -

6 910.92 181 7 -

7 1460. 1 6 2910 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI end 485 604 683 1174 1226 1831 2930 Peal<

NetPeak Net Area Continuum Centroid Area Uncertainty Counts 477. 46 3.37E+02 50. 26 7. 13E+02 590.30 l. 11E+02 34.02 6. 05E+02 675. 79 7.59E+Ol

27. 49 3. 29E+02 1165.77 1.10E+02 27. 35 1.70E+02 1218.23 l.19E+02 26.87 1.62E+02 1822.08 5. 69E+Ol 18. 72

l. 05E+02 2920.44 5.47E+02 47. 88 5.76E+Ol BACKGROUND SUBTRACT REPORT

1/31/2019 8:03:25AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peal<

Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 238.49 3.37E+02 50.26 2

29 4. 93 1.11E+02 34.02 3

337.68 7.59E+Ol 27.49 4

582.72 l.10E+02 27.35 5

608.95 l.19E+02 26. 87 4.12E+Ol 2.42E+Ol 6

910. 92 5.69E+Ol 18.72 7

1460. 16 5.47E+02 47.88 5.63E+Ol 1.71E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 3. 37E+02 1.11E+02 7.59E+Ol 1.10E+02 7.80E+Ol 5.69E+Ol 4.91E+02 FWHM (keV) 2. 09 2.43

1. 77 2.55 2.24

1. 65 3.00 Subtracted Uncert.

5.03E+Ol 3. 40E+O l 2. 75E+Ol 2.73E+Ol 3.62E+Ol

1. 87E+Ol 5.0 9E+Ol

1/31/2019 8:03:34AM Page 3 of7 Analysis Report for L 1-SUB-LES-FSGS-004-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 0.94 1460.75 PB-212 0.55 77.11 238.63 BI-214 0.33 609.31 1120.29 1238.11 1377.67 1407.98 1509.19 1764.49

= 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 Yield(%)

10.67 17.50 44.60

46. 30 15.10 5.94 4.11 2.48 2.19 15.80 Activity (pCilgrams) 5.39E+OO

1. 75E-01 9.03E-02 Activity Uncertainty 6.33E-Ol 2.76E-02 4.22E-02 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence (pCilgrams)

Uncertainty K-40 0.946 5.39E+OO 6.33E-Ol PB-212 0.558 1.75E-01 2.76E-02 BI-214 0.339 9.03E-02 4.22E-02

1/31/2019 8:03:34AM Analysis Report for L 1-SUB-LES-FSGS-004-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

?

= 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 Page 4 of7

1/31/2019 8:03:34AM Analysis Report for L 1-SUB-LES-FSGS-004-SB F

F F

F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 2 294.93 3

337.68 4

582.72 6

910.92 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:03:25AM

100

4096 Peak Size (CPS) 3.09140£-02 2.10755£-02 3.06538£-02 1.58055E-02 Peak CPS(%)

Uncertainty 15.28 18.12 12.39 16.45 Peak Type Tol.

Tol.

NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nucllde Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCl/grams)

(pCi/grams)

K-40 1460.75 10.67 5.39E+OO 5.81E-01 5.81E-01 AR-41 1293.64 99.16 2.40E+09 2.70E+l0 2.70E+l0 C0-60 1173.22 100.00 6.08E-03 4.16E-02 5.52E-02 1332.49 100.00

-l.OOE-02 4.16E-02 KR-85 513. 99 0.43 6.55E+OO 8.25E+OO 8.25E+OO Y-88 898.04 93.70 9.18E-03 3.19E-02 3.97E-02 1836.06 99.20 l.29E-02 3.19E-02 NB-94 702.63 100.00 4.25E-02 3.67E-02 3.67E-02 871.10 100.00

-6.19E-03 3.67E-02 I-131 284.30 6.06

-5.74E-01

4. llE-02 5.58E-Ol Page 5 of7 Tolerance Nuclide PB-214 AC-228 PA-228 AC-228 PA-228

1/31/2019 8:03:34AM Page 6 of7 Analysis Report for l 1-SUB-LES-FSGS-004-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity NuclldeMDA LineMDA Name (keV)

(pCi!grams)

(pCi/grams)

I-131 364. 48

81. 20

- 3.64E- 02

4. llE- 02 4. llE-02 636.97 7.27

-1.12E-01 5.69E-0 1

+

CS-134 604.70 97. 60 4.54E- 03 4.27E- 02

4. 27E-02 795.84 85.40

-2.74E-02 4.45E-02

+

CS-137 661.65 85.12 1. 95E- 02 4.59E-02 4.59E-02

+

CE-144 80.12

1. 36

- 3. 97E- 01 2.34E-01 2. 97E+OO 133. 51

11. 09

-1. 81E-02 2.3 4E-01

+

EU-152 121.78 28.40

- 5. 19E-02 9. lOE- 02 9. lOE-02 344.28 26.60

- 2.16E- 01 l.23E-Ol 1408.00 20. 74 1.1 6E- 01 1. 89E- 01

+

EU-154 123.07 40.40

-1.lOE-0 2 6. 41E-02 6. 41E-02 723.30 19.70 5.69E-02 1.77E- 01 1274.51 35.50

-5. 52E-03 1.31E- 01

+

EU-155 86. 54 32.80 1.30E-02 1.06E- 01 1. 06E-Ol 105. 31

21. 80 4.52E-02

1. 23E-01

+

BI-214 609.31 46.30 9.03E-02 8. 33E-02 8.33E-02 1120.29 15. 10 3.64E-01 3.58E-01 1238.11 5.94 2. lOE-01 9.5 6E-O l 1377. 67 4.11 3.04E- 02 9.19E-0 1 1407. 98 2.48 9.68E-0 1 1.58E+OO 1509.19 2.19 1.17E-01 1.48E+OO 17 64.49 15.80 2.92E-01 2.76E-01

+

PB-2 14 77.11 10.70 4.74E-01 9.18E-02 4.07E-01 295.2 1 19. 20

- 2.06E-02 1. 58E-01 351. 92 37. 20 1.70E-01 9.18E-02

+

PA-228 89.95 22.00 2.13E+OO 8.47E-01 1.45E+OO 93. 35 35.00 2. 77E-01 8.47E-01 105.00 16.30 1.0 lE+OO 1.59E+OO 129. 22 2.97 2. 19E+OO 8. 51E+OO 338. 32 5.30

-5.55E-01 5.41E+OO 463.00 13.80 1.34E+OO

2. 1 7E+OO 911.23 16.70 4.44E+OO 2.74E+OO

+

AM-241 59.54 36.30

-l.26E-01 1.82E-01 1. 82E-01

+

CM-243 103.76

23. 00 1.22E-01 1.19E-Ol 1.19E-01 228.18 10.60

-3.23E-02 2.4 3E-01 277.60 14.00 1.39E-Ol 1. 97E-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

1/31/2019 8:03:34AM Page 7 of7 Analysis Report for L 1-SUB-LES-FSGS-004-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

~~~~pex-Gamma 1/31/2019 8:05:01AM Analysis Report for L 1-SUB-LES-FSGS-005-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-005-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 9.730E+02 grams

Dairyland_NPP

2/2/2018 2:08:00PM

2/5/2018 2: 16:06PM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3610.3 seconds

0.29%

3.00

100 - 4096

1.000 keV

7/8/2014

5804 PEAK ANALYSIS REPORT 1/31/2019 8:04:52AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of6

1/31/2019 8:05:01AM Page 2 of6 Analysis Report for L 1-SUB-LES-FSGS-005-SB F

F F

F SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

185.97 369 -

2 238.53 469 -

3 295.03 586 -

4 351.7 9 695 -

5 582. 85 1157 -

6 608.89 1214 -

7 91 0. 98 1815 -

8 1460. 11 2909 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI end 377 485 596 712 11 74 1227 1828 2 930 Peak NetPeak Net Area Continuum Centroid Area Uncertainty Counts 372. 45 9.21E+ Ol 36.60 5.40E+02 477.53 3.99E+02 52.83 7. 1 4E+02 590.52 7.31E+Ol 30. 48 3. 53E+02 704.00 1.98E+02 35.24 2.97E+02 11 66. 05 1. 19E+02 27. 77

1. 63E+02 1218.11

1. 44E+02 27. 90

1. 36E+02 1822. 20 7. 02E+ Ol

21. 41 9. llE+Ol 2920.33 5.98E+02 49. 77

4. 34E+Ol BACKGROUND SUBTRACT REPORT

1/31/2019 8:04:52AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 185. 97 9. 21E+Ol 36.60 2

238.53 3.99E+02 52.83 3

295.03 7.31E+Ol 30.48 4

351.79 l.98E+02 35.24 8.36E+Ol 3. 72E+Ol 5

582.85 1.19E+02 27.77 6

608.89 l.44E+02 27. 90 4. 12E+Ol 2. 42E+Ol 7

910.98 7.02E+Ol

21. 41 8

1 460. 11 5.98E+02 49. 77 5. 63E+Ol

l. 71E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 9.21E+Ol 3. 99E+02 7.31E+O l 1.15E+02 1.19E+02

1. 02E+02 7. 02E+O l 5. 42E+02 FWHM (keV)

1. 65 2. 49

1. 91 2.4 5 2.83 2.09 2. 34 2. 87 Subtracted Uncert.

3.66E+Ol 5.28E+Ol 3. 05E+Ol 5. 13E+Ol 2. 78E+Ol 3.69E+Ol

2. 14E+Ol 5.26E+Ol

1/31/2019 8:05:01AM Page 3 of6 Analysis Report for L 1-SUB-LES-FSGS-005-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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 0.93 1460.75 10.67 6.07E+OO 6.79E-01 PB-212 0.55 77.11 17.50 238.63 44.60 2.12E-01 3.0lE-02 BI-214 0.33 609.31 46.30 l.21E-01 4.42E-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

1. 07E-Ol 4.51E-02 351.92 37.20 l.02E-Ol 4.58E-02 RA-226 0.99 186.21 3.28 5.58E-Ol 2.24E-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 (pCilgrams)

Uncertainty K-40 0.936 6.07E+OO 6.79E-01 PB-212 0.559 2.12E-Ol 3.0lE-02

1/31/2019 8:05:01AM Analysis Report for L 1-SUB-LES-FSGS-005-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name BI-214 PB-214 RA-226 Nuclide Id Confidence 0.335 0.718 0.991

?

= nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis Wt mean Activity (pCilgrams) l.21E-01

1. OSE-01 5.58E-Ol

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Activity Uncertainty 4.42E-02 3.21E-02 2.24E-Ol Page 4 of6 Comments

1/31/2019 8:05:01AM Analysis Report for L 1-SUB-LES-FSGS-005-SB F

F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 5 582.85 7

910.98 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:04:52AM

100

4096 Peak Size (CPS) 3.30575E-02 l.94986E-02 Peak CPS(%)

Uncertainty

11. 67 15.25 Peak Type Tol.

NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCVgrams)

(pCilgrams)

(pCi/grams)

K-40 1460.75 10.67 6.07E+OO 5.65E-01 5.65E-01 AR-41 1293.64 99.16 5.47E+09 4.52E+l0 4.52E+l0 C0-60 1173.22 100.00 3. 85E-02 4.04E-02 5.51E-02 1332.49 100.00

-4.40E-02 4.04E-02 KR-85 513.99 0.43

6. 72E+OO 8.55E+OO 8.55E+OO Y-88 898.04 93.70 6.05E-02 3.08E-02 4.62E-02 1836.06 99.20 l.49E-02 3.08E-02 NB-94 702.63 100.00

-l.07E-02 3.40E-02 3.40E-02 871.10 100.00

-6.76E-02 3.42E-02 I-131 284.30 6.06 3.53E-01 4.48E-02 6.08E-01 364.48 81.20 3.27E-02 4.48E-02 636.97 7.27

-9.68E-02 5.87E-01 CS-134 604.70 97.60

-7.47E-02 4.12E-02 4.73E-02 795.84 85. 40

-l.lOE-02 4.12E-02 Page 5 of6 Tolerance Nuclide AC-228 PA-228

1/31/2019 8:05:01AM Page 6 of6 Analysis Report for L 1-SUB-LES-FSGS-005-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

+

CS-137 661. 65 85. 12 2.70£ -02 4.46£-02 4.46£-02

+

CE-144 80.12

1. 36

-7. 91£- 01 2.40£- 01 3.03E+OO 133. 51

11. 09 1.47£-01 2.40E-Ol

+

EU-152 121.78 28.40

-4.82£-02 9.08£-02 9.08E-02 344. 28 26.60 1.23E-01 1.19E-01 1408.00 20.74

- 3.81E-02 1.73E- 01

+

EU-1 54 123. 07 40.40

-2.91E-02 6.40E-02 6.4 0E-02 723.30 19.70 8.64£ -02 2.04£-0 1 1274.51 35.50 2.55E-03 1.35E-01

+

EU-155 86.54 32.80

-1. 90E-02 1.06E-01 1.06E-01 105.31 21. 80 8.7 7E-02 1.32E-Ol

+

BI-214 609.31 46.30 1.21£-01 7.92£- 02 7.92£- 02 1120.29 15.10 1. 94£-01 3.41E-Ol 1238.11

5. 94

-4.05£-01 9.93E-01 1377. 67 4. 11

-4.19E-01 8. 78E-01 1407. 98 2.48

-3.18E-Ol 1.45E+OO 1509. 1 9

2. 1 9

- 8. 91E- 01

1. 35E+OO 1764.49 1 5. 80 3.08E-01 3.15E-01

+

PB-214 77. 11 10.70 4.97E-Ol 9. 06E-02 4.13£- 01 295. 21 19. 20 1.07E-01

1. 03E-01 351. 92 37. 20

1. 02E- 01 9. 06E-02

+

PA-228 89. 95 22.00 2.43E+OO 8. 88E-01 1.53E+OO 93. 35 35.00

-2.80E-01 8.88E-01 1 05. 00 16.30 1.74E+OO

1. 7 5E+OO 129.22 2.97 8.65E+OO 8.79E+OO 338. 32 5. 30 8.42E+OO 5.78E+OO 463.00 13.80 5.69E-O l 2. 17E+OO 911.23 16.70

1. 96E+OO 3.05E+OO

+

AM-241 59.54 36.30

-3.52E-03 1.91E-Ol 1.91E-01

+

CM-243 103.76 23.00 8.68E-02 1.26E-0 1 1.26E- 01 228.18 10.60

- 1.92E-Ol 2.38E-01 277.6 0 14.00

-6. 02E-0 2

1. 98E-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

~~~~pex-Gamma 1/31/2019 8:06:19AM Analysis Report for L 1-SUB-LES-FSGS-006-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-006-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 9.351 E+02 grams

Dairyland_NPP

2/2/2018 2:15:00PM

2/5/2018 3:17:26PM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3609. 7 seconds

0.27 %

3.00

100

4096

100

4096

1.000 keV

7/8/2014

5806 PEAK ANALYSIS REPORT 1/31/2019 8:06:10AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of6

1/31/2019 8:06:19AM Page 2 of6 Analysis Report for L 1-SUB-LES-FSGS-006-SB F

F F

F SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

76.48 146 -

2 238.61 469 -

3 294.81 581 -

4 338.22 671 -

5 351. 61 695 -

6 582.94 1158 -

7 608.92 1211 -

8 910.62 1814 -

9 948.81 1892 -

10 968.47 1932 -

11 1460.12 2911 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI end 158 485 595 681 711 1174 1224 1829 1902 1942 2928 Peak Net Peak Net Area Continuum Centroid Area Uncertainty Counts 153.50 1.64E+02

49. 96 1.28E+03 477.69 3. 69E+02 50.89 7.22E+02 590.07 9.84E+Ol 32.70

4. 50E+02 676.88 6.21E+Ol 24.95 2.51E+02 703.65 1.61E+02 33.36 3.67E+02 1166.22 1.05E+02 26.19

1. 49E+02 1218.17 1.19E+02 27.14 1.38E+02 1821.48 8.84E+Ol 22.53 6.86E+Ol 1897.86 1.41E+Ol 9.71 4.51E+Ol 1937.17 2.66E+Ol 15.97 9.23E+Ol 292 0.36 5.88E+02 49.09 2.66E+Ol BACKGROUND SUBTRACT REPORT

1/31/2019 8:06:10AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 76.48 l.64E+02 49.96 2

238.61 3.69E+02 50.89 3

294.81 9.84E+Ol 32.70 4

338.22 6. 21E+Ol 24.95 5

351.61 l.61E+02 33.36 8.36E+Ol 3.72E+Ol 6

582.94 l.05E+02 26.19 7

608.92 l.19E+02 27.14 4.12E+Ol 2.42E+Ol 8

910.62 8.84E+O l 22.53 9

948.81 1.41E+Ol 9.71 10 968. 4 7 2.66E+Ol 15.97 11 1460.12 5.88E+02 49.09 5. 63E+Ol 1.71E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area l.64E+02 3.69E+02 9.84E+Ol 6.21E+Ol 7.76E+Ol l.05E+02 7.74E+Ol 8.84E+Ol 1.41E+Ol 2.66E+Ol 5.32E+02 FWHM (keV)

1. 78 2.39 2.03

1. 53

1. 93 2.72 2.18 3.22 0.82

1. 64 2.78 Subtracted Uncert.

5.00E+Ol 5.09E+Ol 3. 27E+Ol 2.50E+Ol 5.00E+Ol 2. 62E+Ol 3. 64E+Ol 2. 25E+Ol 9.71E+OO 1.60E+Ol 5.20E+Ol

1/31/2019 8:06:19AM Page 3 of6 Analysis Report for L 1-SUB-LES-FSGS-006-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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 0.93 1460.75 10.67 6.20E+OO

6. 96E-01 PB-212 0. 98 77.11 17.50 2.SOE-01 7.80E-02 238.63 44.60 2.04E-01 3.00E-02 BI-214 0.33 609.31 46.30 9.53E-02 4.51E-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 0.97 77.11 10.70 4.08E-01

1. 27E-01 295.21 19.20

1. 50E-01 5.05E-02 351.92 37.20 7.17E-02 4.63E-02 AC-228 0.55 209.28 4.40 338.32

11. 40 l.81E-01 7.31E-02 794.70 4.60 911. 60 27.70 2.62E-01 6.77E-02 964.60 5.20 969.11 16.60 1.39E-Ol 8. 37E-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

1/31/2019 8:06:19AM Analysis Report for L 1-SUB-LES-FSGS-006-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

?

=

X =

Nuclide Name K-40 PB-212 BI-214 PB-214 AC-228 Nuclide Id Confidence 0.939 0.982 0.337 0.974 0.559 nuclide is part of an undetermined solution nuclide rejected by the interference analysis Wt mean Activity (pCl/grams) 6.20E+OO 2.0lE-01 9.53E-02 1.06E-01 2.02E-01

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

6. 96E-01 2.BlE-02 4.51E-02 3.31E-02 4.27E-02 Page 4 of6 Comments

1/31/2019 8:06:19AM Analysis Report for L 1-SUB-LES-FSGS-006-SB F

F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

6 9

Energy (keV) 582.94 948.81 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:06:10AM

100

4096 Peak CPS(%)

Peak Size (CPS)

Uncertainty 2.90908E-02 3.90365E-03 12.50 34.56 Peak Type S-Esc NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi/grams)

(pCVgrams)

(pCl/grams)

K-40 1460.75 10.67 6.20E+OO 5.35E-01 5.35E-Ol AR-41 1293.64 99.16

-2.17E+l0 6.04E+l0 6.04E+l0 C0-60 1173.22 100.00

-6.15E-03 4.79£-02 6.00E-02 1332.49 100.00 5.77E-02 4.79E-02 KR-85 513.99 0.43 2.08E+Ol 9.66E+OO 9.66E+OO Y-88 898.04 93.70

1. 96E-03 3.39E-02 4.49E-02 1836.06 99.20

-2.27E-03 3.39E-02 NB-94 702.63 100.00 8.40E-03 3.50E-02 3.50E-02 871.10 100.00

-4.16E-02 3.64E-02 I-131 284.30 6.06

-3.46£-01 4.73E-02 6.19E-01 364.48

81. 20 5.28E-03 4.73E-02 636.97 7.27

-5.14£-02 5.87E-01 CS-134 604.70 97.60 4.13E-03 4.45E-02 4.45E-02 795.84 85.40

-1.96E-02 4.66E-02 CS-137 661.65 85.12

5. llE-02 4.97E-02 4.97E-02 Page 5 of6 Tolerance Nuclide

1/31/2019 8:06:19AM Page 6 of6 Analysis Report for L 1-SUB-LES-FSGS-006-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity NuclldeMDA LlneMDA Name (keV)

(pCi!grams)

(pCilgrams)

+

CE-144 80.12

1. 36

- l.63E+OO 2. 48E-01 3. 07E+OO 133.51 11. 09 7.91E-02 2. 48E-01

+

EU-152 121. 78 28.40

- 3.91E- 02 9.53E-02 9.53E-02 344.28 26.60

- 3.47E- 02 l.20E-01 1408. 00 20. 74 2.69E-01 2. 32E-01

+

EU-154 123.07 40.40

-3. 82E-02 6. 70E-02 6. 70E-02 723. 30 19.70 4.17E-02 2. 02E-01 1274. 51 35.50 4.38E-02 l. 36E- 01

+

EU-155 86. 54 32.80

1. 36E-02 l.09E- 01 l.09E- 01 105.31 21.80 l.74E-02 l. 30E- 01

+

BI-214 609.31 46.30 9. 53E-02 8.22E- 02 8. 22E- 02 1120.29 15.10 l.36E-Ol 3. 62E-01 1238.11

5. 94

-l.34E-01 9.89E-Ol 1377. 67 4.11 2.79E- 01 9. 66E- 01 1407.98 2.48 2.24E+OO l. 94E+OO 1509.19 2.19 3.79E-01

1. 57E+OO 1764. 49 15. 80 2.12E-01 3. 25E- 01

+

PB-214 77.11 10.70 4. 08E-01 9. 89E-02 3. 44E-01 295.21 19.20 1.SOE-01 1.32E- 01 351. 92 37. 20 7. 17E-02 9. 89E-02

+

PA-228 89. 95 22.00 2. 18E+OO 9.4 0E-01 l. 60E+OO 93. 35 35.00 4.57E-01 9. 40E- 01 105. 00 16.30 6. 99E-Ol

l. 78E+OO 129. 22 2.97

-2. 33E+OO 9. 32E+OO 338. 32 5.30 7.94E+OO 5.99E+ OO 4 63.00 13. 80 2. 38E+OO 2.42E+OO 911.23 16.70 3. 15E+OO 3. 25E+OO

+

AM-241 59. 5 4 36.30

-5. 61E-02 1.96E-01 l. 96E-01

+

CM-243 103. 76 23.00

-4. 36E-02

1. 24E-Ol 1.24E-01 228. 18 10. 60

-2. 04E-02 2. 54E-01 277.60 14.00

-1. 41E-01 2.05E-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

..ft Apex-Gamma 1/31/2019 8:10:05AM Analysis Report for L 1-SUB-LES-FSGS-007-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-007-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 9.022E+02 grams

Oairyland_NPP

2/2/2018 2:20:00PM

2/5/2018 4:18:58PM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3609.8 seconds

0.27%

3.00

100-4096

1.000 keV

7/8/2014

5808 PEAK ANALYSIS REPORT 1/31/2019 8:09:57AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page 1 of7

F F

F 1/31/2019 8:10:0SAM Page 2 of?

Analysis Report for L 1-SUB-LES-FSGS-007-SB F

F F

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

185.41 367 -

2 238.56 471 -

3 295. 29 583 -

4 338. 35 672 -

5 351.64 695 -

6 582.74 1159 -

7 609.01 1210 -

8 968.91 1932 -

9 111 9. 05 2232 -

10 1460.11 2911 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI Peak NetPeak end Centroid Area 376 371. 32 5.70E+Ol 485 477.60 3.10E+02 597 591.03 4.52E+Ol 684 677.13 8.05E+Ol 710 703.71 l.85E+02 1172 1165.82 9.43E+Ol 1227 1218. 35 l.21E+02 1943 1938.04

2. 72E+Ol 2243 2238.28 3.24E+Ol 2930 2920.32 5.21E+02 Net Area Continuum Uncertainty Counts 34.12 5.89E+02 48.81

7. 1 7E+02 54.98 4.88E+02 28.81 2.64E+02 34.66 2. 84E+02 23.95 l.06E+02 25.8 4 9.87E+Ol 16.77 9.42E+Ol 14.40 5.40E+Ol 46.20 3.00E+Ol BACKGROUND SUBTRACT REPORT

1/31/2019 8:09:57AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland _ NPP\\Data\\0000001364. CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 185.41 5. 70E+O l 34.12 2

238.56 3.1 0E+02 48.8 1 3

295.29 4.52E+Ol 54.98 4

338. 35 8.0SE+Ol 28.81 5

351.64 1.85E+02 34. 66 8. 36E+Ol 3. 72E+Ol 6

582.74 9.43E+Ol 23.95 7

60 9.01 1.21E+02 25. 84 4.12E+Ol

2. 42E+Ol 8

968. 91 2. 72E+Ol 16. 77 9

1119.05 3.24E+Ol 14.40 10 1460. 11 5.21E+02 46. 20 5. 63E+Ol

1. 71E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 5.70E+Ol 3.10E+02 4.52E+Ol 8. 0SE+Ol 1.01E+02 9.43E+Ol 8.03E+Ol 2.72E+Ol 3.24E+Ol 4.65E+02 FWHM (keV)

1. 53 2.18

1. 57 2.41 2.31 2.20 2.82

1. 98

1. 47 2.90 Subtracted Uncert.

3.41E+Ol 4.88E+Ol 5.SOE+Ol 2.88E+Ol 5.08E+Ol 2.39E+Ol 3.54E+O l l.68E+Ol 1.44E+Ol

4. 93E+Ol

1/31/2019 8:10:0SAM Page 3 of7 Analysis Report for L 1-SUB-LES-FSGS-007-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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 0.93 1460.75 10.67 5.61E+OO 6.72E-Ol PB-212 0.56 77.11 17.50 238.63 44.60 l.77E-01 2.94E-02 BI-214 0.34 609.31 46.30 l.02E-Ol 4.55E-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 7.17E-02 8.73E-02 351.92 37.20 9.71E-02 4.89E-02 RA-226 0.90 186.21 3.28

3. 72E-Ol 2.24E-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 0.936 5.61E+OO 6.72E-01 PB-212 0.560 l.77E-01 2.94E-02

1/31/2019 8:10:0SAM Analysis Report for L 1-SUB-LES-FSGS-007-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name BI-214 PB-214 RA-226 Nuclide Id Confidence 0.342 0.714 0.902

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCilgrams)

1. 02E-01 9.11E-02 3.72E-Ol

= nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Activity Uncertainty 4.SSE-02 4. 27E-02 2.24E-01 Page 4 of7 Comments

1/31/2019 8:10:05AM Analysis Report for L 1-SUB-LES-FSGS-007-SB F

F F

F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 4 338.35 6

582.74 8

968.91 9

1119.05 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:09:57AM

100

4096 Peak Size (CPS) 2.23716E-02 2.61938E-02 7.56121E-03 9.00500E-03 Peak CPS(%)

Uncertainty 17.89 12.70 30.80 22.21 Peak Type Tol.

Tol.

NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCl/grams)

(pCUgrams)

(pCi/grams)

K-40 1460.75 10.67 5.61E+OO 5.69E-01 5.69E-01 AR-41 1293.64 99.16 2.94E+l0 9.19E+l0 9.19E+l0 C0-60 1173.22 100.00 3.41E-03 4.58E-02 5.49E-02 1332.49 100.00 8.74E-04 4.58E-02 KR-85 513.99 0.43 5.28E+OO 9.26E+OO 9.26E+OO Y-88 898.04 93.70 9.28E-03 3.51E-02 4.46E-02 1836.06 99.20 l.08E-02 3.SlE-02 NB-94 702.63 100.00 8.82E-03 3.38E-02 3.38E-02 871.10 100.00

-5.41E-03 3.99E-02 I-131 284.30 6.06

-2.95E-01 4.69E-02 6.49E-01 364.48 81.20

-4.77E-03 4.69E-02 Page 5 of7 Tolerance Nuclide AC-228 PA-228 AC-228

1/31/2019 8:10:0SAM Page 6 of7 Analysis Report for L 1-SUB-LES-FSGS-007-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCi!grams)

I-131 636.97 7. 27 2.52E- 01 4.69E-02 6. 39E- 01

+

CS-134 604.70 97.60 3.79E-03 4.47E-02 4.47E- 02 795.84 85. 40 8.46E-04 4.73E- 02

+

CS-137 661.65 85.12 4.31E-02

4. 75E- 02 4. 75E-02

+

CE-144 80.12

1. 36 2.77E+OO 2. 55E- 01 3.17E+OO 133.51

11. 09

- 2.13E-02 2.55E-0 1

+

EU-152 121.78 2 8. 40

-1.86E-02 9.93E- 02 9. 93E- 02 344.28 26.60

-4. 20E-02 1.30E- 01 1408.00 20. 74 5.29E- 02 2. 02E- 01

+

EU-154 123.07 40.40

- 1.49E-0 2 6. 98E-02 6. 98E- 02 723. 30

19. 70 1.63E-01 2. 08E-Ol 1274.51 35. 50 6.15E-03 1.47E- 01

+

EU-155 86.54 32.80 1.12E-02 1.09E- 01

1. 09E- 01 105.31

21. 80 1.06E-01

1. 37E- 01

+

BI-214 609.31 46. 30 1.02E-01 8.18E- 02 8.1 8E- 02 1120. 29 15. 10 1.42E-01 3. 61E- 01 1238.11 5. 94 1.31E-01 1. 00E+OO 1377. 67 4. 11 1.27E-01 9. 90E-01 1407. 98 2.4 8 4.42E-01 1. 69E+OO 1509.19 2.19

1. 56E+OO 1. 71E+OO 1764.49 15.80 2.56E-01 2. 96E- 01

+

PB-214 77.11 10.70 7. 41E-01 9.4 7E-02 4. 33E-01 295. 21 19. 20 7. 17E-02 1.43E- 01 351. 92 37.20 9.71E-02 9.47E- 02

+

PA-228 89.95 22.00

1. 34E+OO 9. 81E-Ol 1. 64E+OO 93.35 35. 00 5. 08E-01 9. 81E-01 105.00 16. 30 1.19E+OO 1. 91E+OO 129.22 2.97 8. 84E+O O

1. OlE+Ol 338.32 5.30 6. 75E+OO 6.47E+OO 463.00 13.80

- 6. 64E-01 2.38E+OO 911. 23 16.70 3. 47E+OO 3.38E+OO

+

AM-241 59.54 36.30

-7.64E-02

1. 95E- 01 1.95E-01

+

CM-243 103.76 23.00

-3. 57E-03 1.29E-01 1.29E-01 228. 18 1 0. 60 8. 53E-02 2. 71E-Ol 277.60 14.00 -1. 52E-01 2.18E-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

1/31/2019 8:10:0SAM Page 7 of?

Analysis Report for L 1-SUB-LES-FSGS-007-SB SYSTEMATICS FOR L1-SUB-LES WITHIN Survey Unit U-010-103

_.Apex-Gamma 1/31/2019 8:12:26AM Analysis Report for L 1-SUB-LES-FSGS-008-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live nme Real Time Dead lime Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-008-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 8.529E+02 grams

Dairyland_NPP

2/2/2018 1:31:00PM

2/5/2018 6:22:11PM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3610.1 seconds

0.28%

3.00

100 - 4096

1.000 keV

7/8/2014

5810 PEAK ANALYSIS REPORT 1/31/2019 8:12:17AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of6

1/31/2019 8:12:26AM Page 2 of 6 Analysis Report for L 1-SUB-LES-FSGS-008-SB F

F F

F SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

238.48 47 1 -

2 29 4.84 587 -

3 338.56 673 -

4 351.63 698 -

5 583. 1 0 1161 -

6 608. 85 1212 -

7 726. 97 1450 -

8 910. 40 181 5 -

9 1 460. 12 2912 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI end 484 596 683 709 1173 1224 1459 1828 2930 Peak Net Peak Net Area Continuum Centroid Area Uncertainty Counts 477. 44 2. 98E+02 47.54 5. 99E+02 590.14 1. 07E+02 30. 21 2. 89E+02 677.56 6.55E+Ol 25. 06 2. 60E+02 703.68 1. 60E+02 34.02 2.75E+02 1166.53 9. 15E+Ol 24. 59 1.20E+02 1218. 03 1. 19E+02 27. 62 1.54E+02 1454.2 4

1. 80E+Ol

20. 96 8.00E+Ol 1821. 04 6. 39E+Ol 20.56

1. 03E+02 2920. 35 5.47E+02 47.4 1 2. 85E+Ol BACKGROUND SUBTRACT REPORT

1/31/2019 8:12:17AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 238.4 8 2. 98E+02 47.54 2

2 94. 84

1. 07E+02 30.21 3

338. 56 6.55E+Ol 25.06 4

351.63 1.60E+02 34.02 8.36E+Ol 3. 72E+Ol 5

583. 10 9. 15E+Ol 24. 59 6

608. 85 1.19E+02 27.62 4.12E+Ol 2. 42E+Ol 7

726.97

1. 80E+Ol 20.96 8

910.40 6.39E+Ol 2 0.56 9

1460. 12 5.47E+02

47. 41 5.63E+Ol 1. 71E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 2. 98E+02 1.07E+02 6.55E+Ol 7.68E+Ol 9.1 5E+Ol 7.83E+Ol 1. 80E+Ol 6. 39E+Ol 4.91E+02 FWHM (keV) 2.31 2.11

1. 44

1. 99 2.39 2.15 1.11 2.05 2.89 Subtracted Uncert.

4. 75E+Ol 3.02E+O l 2. 51E+Ol 5. 04 E+Ol 2. 46E+Ol 3.67E+Ol

2. l OE+O l 2.06E+O l 5. 04E+Ol

1/31 /2019 8:12:26AM Page 3 of6 Analysis Report for L 1-SUB-LES-FSGS-008-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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)

(pCVgrams)

Uncertainty K-40 0. 93 1 460. 75 1 0. 67 6. 27E+OO 7. 32E- 01 BI-212 0. 60 727. 17

11. 80

1. 12E- 01 1.31E-Ol 785.42 2. 00 1620. 56 2.75 PB-212 0. 55 77.11 1 7. 50 238.63

44. 60 l. 80E- 01 3. 02E- 02 BI - 21 4 0.33 609.31 46.30

1. 06E-Ol 4.99E- 02 1120.29 15. 10 1238. 11 5. 94 1377. 67 4. 11 1407. 98 2. 48 1509.1 9 2. 19 176 4. 4 9 15. 80 PB-21 4 0.70 77.11 10. 70 295. 21

19. 20

1. 79E- 01 5. 14E-02 351. 92 37. 20 7. 77E- 02 5. 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 INTERFERENCE CORRECTED REPORT Nuclide Name Nuclide Id Confidence Wt mean Activity (pCilgrams)

Wt mean Comments Activity Uncertainty

1/31/2019 8:12:26AM Analysis Report for L 1-SUB-LES-FSGS-008-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name K-40 BI-212 PB-212 BI-214 PB-214 Nuclide Id Confidence 0. 938 0.601 0.558 0.332 0.708

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCi/grams) 6.27E+OO l.12E-Ol 1.80E-01 1.06E-01

1. 28E-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Activity Uncertainty 7.32E-01 1.31E-01 3.02E-02 4.99E-02 3.63E-02 Page 4 of6 Comments

1/31/2019 8:12:26AM Analysis Report for L 1-SUB-LES-FSGS-008-SB F

F F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 3 338.56 5

583.10 8

910.40 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:12:17AM

100

4096 Peak Size (CPS) l.82001E-02 2.54246E-02 1.77438E-02 Peak CPS(%)

Uncertainty 19.13

13. 43 16.09 Peak Type Tol.

Tol.

NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi/grams)

(pCi!grams)

(pCilgrams)

K-40 1460.75 10.67

6. 27E+OO

5. 96E-01 5.96E-01 AR-41 1293.64 99.16 5.14E+10 2. 77E+ll

2. 77E+ll C0-60 1173.22 100.00 6.60E-03 5.49E-02 6.31E-02 1332.49 100.00 3.23E-02 5.49E-02 KR-85 513.99 0.43 l.26E+Ol 9.59E+OO 9.59E+00 Y-88 898.04 93.70 2.99E-03 3.72E-02 4.65E-02 1836.06 99.20

-1.98E-02

3. 72E-02 NB-94 702.63 100.00 1.70E-02 4.16E-02 4.38E-02 871.10 100.00

-3.52E-02 4.16E-02 I-131 284.30 6.06

-3.74E-01 4.93E-02 6.53E-01 364.48

81. 20

-3.54E-02 4.93E-02 636.97 7.27

-1.51E-01 7.30E-01 CS-134 604.70 97.60

-1.31E-02 5.lOE-02 5.lOE-02 Page 5 of6 Tolerance Nuclide AC-228 PA-228 PA-228

1/31/2019 8:12:26AM Page 6 of6 Analysis Report for L 1-SUB-LES-FSGS-008-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity Nuclide MDA LineMDA Name (keV)

(pCi/grams)

(pCilgrams)

(pCi/grams)

CS-134 795.84 85.40

-4.33E-02 5. lOE-02 5.28E-02

+

CS-137 661.65 85.12 7.74E-02 5.49E-02 5.49E-02

+

CE-144 80.12

1. 36

-1.28E+OO 2.77E-O l 3.37E+OO 133. 51

11. 09 4.57E-02 2.77E-01

+

EU-152 121. 7 8 28. 40 4.85E-03 1. 04E-01 1.04E-01 344.28 26.60

-3.06E-02 1.41E-01 1408.00 20.74

-8.51E-03 2.07E-01

+

EU-154 123. 07 40.40

-1. 28E-02 7.30E-02 7. 30E-02 723.30 19.70

1. 84E-02 2. 22E-Ol 1274. 51 35.50

-5.68E-02

1. 57E-01

+

EU-155 86.54 32.80 2.31E-02 1.19E-01

1. 19E-01 105.31

21. 80

-4.07E-02 1.36E-01

+

BI-214 609.31 46.30 1.06E-01 9.16E-02 9.16E-02 1120.29 15.10 3.03E-01 4.13E-01 1238.11 5.94 4.20E-01 1.12E+OO 1377.67 4.11

-4.35E-01 9. 66E-01 1407.98 2.48

-7. llE-02 1.73E+OO 1509.19 2.19 6.59E-02

1. 88E+OO 1764.49 15.80 3.54E-Ol 3.06E- 01

+

PB-214 77.11 10.70 6.46E-01 9.54E-02 4.59E-0 1 295.21 19.20 1.79E-01 1.06E-01 351.92 37.20 7.77E-02 9.54E-02

+

PA-228 89.95 22.00 1.98E+OO 1.12E+OO 1.94E+OO 93.35 35.00

- 6.02E-Ol 1.12E+OO 105.00 16.30

-1.03E+OO 2.0 9E+OO 129.22 2.97

2. llE+OO 1.15E+Ol 338.32 5.30 3.44E+OO 7.78E+OO 463.00 13.80

1. 35E+OO 2. 84E+OO 911. 23 16.70 3. 56E+OO 3. 98E+OO

+

AM-241 59.54 36.30

-1.15E-01 2.lOE-0 1 2.lOE-01

+

CM-243 103.76 23. 00

- 7.70E-02

1. 30E-Ol 1. 30E-01 228.18 10.60

5. 96E-02 2. 76E- 01 277.60 14.00

-l.55E-Ol 2.26E-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 perfonn the decay correction

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

Jt'Apex-Gamma 1/31/2019 8:15:11AM Analysis Report for L 1-SUB-LES-FSGS-009-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-009-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 8.862E+02 grams

Dairyland_NPP

2/2/2018 2:32:00PM

2/5/2018 7:31:34PM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3609.8 seconds

0.27%

3.00

100

4096

100-4096

1.000 keV

7/8/2014

5812 PEAK ANALYSIS REPORT 1/31/2019 8:15:03AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of7

F F

F 1/31/2019 8:15:11AM Page 2 of 7 Analysis Report for L 1-SUB-LES-FSGS-009-SB F

F F

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

238.50 469 -

2 294.50 585 -

3 351.64 695 -

4 582. 76 1157 -

5 608. 98 121 2 -

6 910.77 1817 -

7 968.73 1 933 -

8 1331.90 2659 -

9 1460. 02 2911 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI Peak NetPeak end Centroid Area 485 477.47 4.11E+02 596 589.46 6.06E+O l 711 703.7 1 l. 93E+02 1173 1165.86

1. 33E+02 1225 1218.29 l. 44E+02 1831 1821.78 5.92E+ Ol 1943 1937.69 3. 59E+Ol 2670 2663.94 1.84E+O l 2929 2920. 1 5 4. 86E+02 Net Area Continuum Uncertainty Counts 53. 15 6. 84E+02 26.13 4.08E+02 36.87 3. 19E+02 28. 35

1. 40E+02 28.20 l.02E+02 20.09 8.80E+Ol 16.63 6. 99E+Ol 9.66 2.74E+Ol 44. 97 3. 31E+Ol BACKGROUND SUBTRACT REPORT

1/31/2019 8:15:03AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 238.50 4.11E+02 53.15 2

294. 50 6. 06E+Ol 26. 13 3

351.6 4 l. 93E+02 36.87 8.36E+Ol 3.72E+Ol 4

582.76 l. 33E+02 28.35 5

608.98 1.44E+02 28.20 4.12E+Ol 2.42E+Ol 6

910. 77 5.92E+Ol 20.09 7

968. 73 3. 59E+Ol 16.63 8

1331. 90 1. 84E+Ol 9. 66 9

1460.02 4.86E+02 44.97 5. 63E+Ol

1. 71E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 4. 11E+02 6. 06E+Ol 1.10E+02

1. 33E+02 l.03E+02

5. 92E+Ol 3. 59E+Ol

1. 84E+Ol 4. 30E+02 FWHM (keV) 2. 55

1. 23 2.74 2. 81 2.61 2. 80

1. 85 0.82 2.77 Subtracted Uncert.

5.32E+Ol 2. 61 E+Ol 5.24E+Ol 2.84E+Ol

3. 72E+Ol 2.0lE+Ol l. 66E+Ol 9. 66E+OO 4. 81E+Ol

1/31/2019 8:15:11AM Page 3 of7 Analysis Report for L 1-SUB-LES-FSGS-009-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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 0.91 1460.75 10.67 5.28E+OO 6.60E-01 PB-212 0.55 77.11 17.50 238.63 44.60 2.39E-01 3.33E-02 BI-214 0.34 609.31 46.30

1. 33E-01 4.89E-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 0.69 77.11 10.70 295.21 19.20

9. 77E-02 4.24E-02 351.92 37.20 1.07E-01 5.13E-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 K-40 0.917 5.28E+OO 6.60E-01 PB-212 0.558 2.39E-01 3.33E-02 BI-214 0.341 l.33E-01 4.89E-02

1/31/2019 8:15:11AM Analysis Report for L 1-SUB-LES-FSGS-009-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name PB-214 Nuclide Id Confidence 0.692

?

= nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis Wt mean Activity (pCi/grams) 1.0lE-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Activity Uncertainty 3.27E-02 Page 4 of7 Comments

1/31/2019 8:15:11AM Analysis Report for L 1-SUB-LES-FSGS-009-SB F

F F

F

+

SYSTEMATICS FOR l 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 4 582.76 6

910. 77 7

968. 7 3 8

1331.90 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:15:03AM

100

4096 Peak Size (CPS) 3. 70203E-02 1.64378E- 02 9.96790E- 03 5.10840£- 03 Peak CPS(%)

Uncertainty 10. 64 16.98

23. 18 26. 27 Peak Type Tol.

Tol.

NUCLIDE MDA REPORT Nudide library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity Nuc/ideMDA LineMDA Name (keV)

(pCVgrams)

(pCl/grams)

K-40 1460. 75 10.67 5.28E+OO 5. 84E- 01 5. 84E-Ol AR-41 1293.64 99. 16 1.16E+ll 3. 17E+ll 3.17E+ll C0-60 1173. 22 100. 00 5.24E-02 5.0SE-02 6. 40E- 02 1332.49 100. 00 4. 31E-02 5. 0SE- 02 KR-85 513. 99 0. 43 1. 39E+Ol 9. 49E+OO 9.49E+OO Y-88 898. 04 93.70

- 1.65E- 03 3.48E-02 4.46E-02 1836. 06 99.20 2. 02E-02 3.48E-02 NB-94 702.63 100.00

-2. 71E-02 3.SlE-02 3. SlE-02 871.10 100.00

-2.99E-02 4. 08E- 02 I-131 284. 30 6. 06

-3.74E-02 4.89E-02 6.56E-01 364. 48

81. 20 3. 12E-02 4.89E- 02 Page 5 of7 Tolerance Nuclide AC-228 PA-228 AC-228 C0- 60

1/31/2019 8:15:11AM Page 6 of7 Analysis Report for L 1-SUB-LES-FSGS-009-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity NuclideMDA Line MDA Name (keV)

(pCi/grams)

(pCilgrams)

I-131 636. 97 7. 27 6.43£-02 4.89£-02 6.23£-01

+

CS-134 604.70 97.60

- 1.02E-02 4.76E-02 4.95E-02 795. 84 85.40

-3.15E-02 4.76E-02

+

CS-137 661.65

85. 1 2 8.54E-02 5.67E-02 5. 67E-02

+

CE-144 80.12

1. 36

-6. llE-01 2.60E-01 3. 22E+OO 133.51

11. 09 1.90E-02 2.60E-01

+

EU-152 121.78 28.40

-2.40E-02 1. 0lE-01 1. 0lE- 01 344.28 26.60 7.49£-02 1.26£-01 1408.00 20.74

-3.41£-02 2. 04E-01

+

EU-154 123.07 40.40

-6.93E-03 7.lOE-02 7.lOE-02 723.30 19.70

1. 05E-02 2.13E-01 1274.51 35.50

-8.64E-02 1.38E-01

+

EU-155 86.54 32.80

-2.60£- 02 1. 12£- 01 1.12E-01 105. 31 21.80 l.OOE-01 1.38E-01

+

BI-214 609.31 46.30 l.33E-01 8. 12E-02 8.12E-02 1120.29 15.10 2.27E-01 3.97E-01 1238. 11 5.94 8.67E-01

1. 07E+OO 1377. 67 4. 11

-2.50E-01 9. 30E- 01 1407.98 2.48

-2.85E-01 1.70E+OO 1509. 19 2. 19 1.75E-01 1.71E+OO 1764.49 15.80 1.00E-01 3.13E-01

+

PB-214 77.11 1 0. 70 7.00E-01 l. OOE-01 4.35E-01 295.21 19.20 9. 77E-02

1. 25E-01 351.92 37.20 1.07E-01 1.00E-01

+

PA-228 89. 95 22.00 3.16E+OO l.09E+OO

1. 88E+OO 93.35 35. 00

-3.05£-01 1.09E+OO 105.00 16.30

1. 02E+OO

2. llE+OO 129.22 2. 97 8.62E+OO l. llE+Ol 338.32 5.30 2.59E+OO 6.85E+OO 463.00 13.80

-2.73E-01 2.81E+OO 911. 23 16.70 3.03E+OO 3.73E+OO

+

AM-241 59.54 36.30

-1.47E-01 2.04E-01 2.04E-01

+

CM-243 103.76 23.00 9.19E-03 1. 30E- 01 1.30E-01 228.18 10.60

- 2.65E-01 2.60E-01 277. 60 14.00

-1. 08E-01 2.15E-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

1/31/2019 8:15:11AM Page 7 of7 Analysis Report for L 1-SUB-LES-FSGS-009-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

,Jt'Apex-Gamma 1/31/2019 8:27:30AM Analysis Report for L 1-SUB-LES-FSGF-010-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGF-010-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 9.107E+02 grams

Dairyland_NPP

2/2/2018 2:24:00PM

2/5/2018 8:52:00PM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3610.0 seconds

0.28%

3.00

100 -4096

1.000 keV

7/8/2014

5817 PEAK ANALYSIS REPORT 1/31/2019 8:27:21AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of7

1/31/2019 8:27:30AM Page 2 of7 Analysis Report for L 1-SUB-LES-FSGF-010-SB F

F F

F SYSTEMATICS FOR L1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

238.66 469 -

2 295.29 587 -

3 338.51 670 -

4 351.60 696 -

5 582.88 1159 -

6 608.90 1210 -

7 661. 4 7 1317 -

8 911.18 1817 -

9 1460.20 2910 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI end 485 597 681 711 1174 1223 1328 1829 2930 Peak NetPeak NetArea Continuum Centroid Area Uncertainty Counts 477.80 3.47E+02 50.69 7.14E+02 591.03 5.92E+Ol

26. 75 3.34E+02 677.46 3.56E+Ol 19.61 2.61E+02 703.63 l.69E+02 33.50 3.02E+02 1166.11 l.12E+02 27.73 l.73E+02 1218.14 1.12E+02 26.90 l.51E+02 1323.26 l.16E+02 26.88 l.26E+02 1822.60 4.68E+Ol 19.96 l.05E+02 2920.51 5.31E+02 46.54 2.62E+Ol BACKGROUND SUBTRACT REPORT

1/31/2019 8:27:21AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 238.66 3.47E+02 50.69 2

295.29 5.92E+Ol 26.75 3

338.51 3.56E+Ol 19.61 4

351.60 l.69E+02 33.50 8.36E+Ol

3. 72E+Ol 5

582.88 l.12E+02 27.73 6

608.90 l.12E+02 26.90 4.12E+Ol 2.42E+Ol 7

661.47 l.16E+02 26.88 6.61E+Ol 2.54E+Ol 8

911.18 4.68E+Ol

19. 96 9

1460.20 5.31E+02 46.54 5.63E+Ol

1. 71E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 3.47E+02 5.92E+Ol 3.56E+Ol 8.53E+Ol l.12E+02 7.09E+Ol 4.98E+Ol 4.68E+Ol 4.74E+02 FWHM (keV) 2.49

1. 48

1. 01 2.14 2.66 2.12 2.04 2.44 2.84 Subtracted Uncert.

5.07E+Ol 2.67E+Ol

1. 96E+Ol 5.0lE+Ol 2.77E+Ol 3.62E+Ol 3.70E+Ol 2.00E+Ol 4.96E+Ol

1/31/2019 8:27:30AM Page 3 of?

Analysis Report for L 1-SUB-LES-FSGF-010-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Oairyland_NPP\\Library\\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%)

Activity Activity Name Confidence

{keV)

(pCi/grams)

Uncertainty K-40 0.95 1460.75 10.67 5.67E+OO 6.71E-01 CS-137 0.99 661.65 85.12 3.70E-02 2.75E-02 PB-212 0.56 77.11 17.50 238.63 44.60

1. 96E-01 3.05E-02 BI-214 0.33 609.31 46.30 8.96E-02 4.60E-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 9.30E-02 4.23E-02 351.92 37.20 8.08E-02 4.76E-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 (pCl/grams)

Uncertainty K-40 0.953 5.67E+OO 6.71E-01 CS-137 0.995 3.70E-02 2.75E-02

1/31/2019 8:27:30AM Analysis Report for L 1-SUB-LES-FSGF-010-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name PB-212 BI-214 PB-214 Nuclide Id Confidence 0.560 0.336 0.712

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCilgrams)

1. 96E-Ol

8. 96E-02 8.77E-02

= nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Activity Uncertainty 3.0SE-02 4.60E-02 3.16E-02 Page4 of7 Comments

1/31/2019 8:27:30AM Analysis Report for L 1-SUB-LES-FSGF-010-SB F

F F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 3 338.51 5

582.88 8

911.18 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:27:21AM

100

4096 Peak Size (CPS) 9.88687E-03 3.112 62E-02 1.29921E-02 Peak CPS(%)

Uncertainty 27.54 12.37

21. 34 Peak Type Tol.

Tol.

NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity NuclldeMDA LineMDA Name (keV)

(pCilgrams)

(pCi/grams)

K-40 1460.75 10.67 5.67E+OO 5.56E-Ol 5.56E-01 AR-41 1293.64 99.16

-2.14E+ll

4. 93E+ll

4. 93E+ll C0-60 1173.22 100.00 2.90E-02 4.58E-02 5.28E-02 1332.49 100.00 2.13E-02 4.58E-02 KR-85 513. 99 0.43 l.84E+Ol 9.67E+OO 9.67E+OO Y-88 898.04 93.70

-l.37E-02 2.65E-02 4.25E-02 1836.06 99.20

-2.29E-02 2.65E-02 NB-94 702. 63 100.00 1.77E-02 3.79E-02 3.79E-02 871.10 100.00 1.25E-03 4.03E-02 I-131 284.30 6.06

-8.56E-02 4.90E-02 6.32E-Ol 364.48

81. 20 l.OSE-02 4.90E-02 Page 5 of7 Tolerance Nuclide AC-228 PA-228 AC-228 PA-228

1/31/2019 8:27:30AM Page 6 of7 Analysis Report for L 1-SUB-LES-FSGF-010-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

I-131 636.97 7.27

1. 54E-Ol 4. 90E- 02 6.48E-Ol

+

CS-134 604.70 97.60 6.91E-02 4.44E- 02 4.70E- 02 795.84 85. 40

-6.80E-03

4. 44E-02

+

CS-137 661.65

85. 1 2 3. 70E-02 4. 99E-02

4. 99E-02

+

CE-144 80.12

1. 36

- 1. 0l E+OO 2. SOE- 01 3. 17E+OO 133. 51 11. 09 6.58E-02 2. 50E-01

+

EU-152 121.78 28.40

- 4. 71E- 02 9.98E-02 9.98E-02 34 4. 28 2 6.60

- 4.05E-02 1. 23E-Ol 1 408.00 20. 74

- 7. 46E-03 1.63E-01

+

EU-154 123. 07 40.40

1. 26E- 02 7.07E-02 7.07E-02 723. 30 1 9. 70

- 9. 28E-02

1. 99E- 01 1274.51 35.50 2.71E-02 1.50E-Ol

+

EU-1 55 86. 54 32. 80

- 7. 39E-02

1. llE-01 1.llE- 01 1 05.31

21. 80

-4. 60E- 02

1. 31E-01

+

BI - 214 60 9. 31 4 6. 30 8.96E-02 8. 61E- 02 8. 61E- 02 1120.29 1 5. 10

- 8.66E- 03 3.38E-Ol 1238. 11 5. 94 4. 53E-01 1.04E+OO 1377.67 4. 11 l.19E- 01 9. 81E-01 1 407. 98

2. 48

-6.23E-02

1. 36E+OO 1509. 1 9 2. 19 1.27E+OO

l. 86E+OO 17 64. 49 15.80 1.59E-0 1 2.5 4E- 01

+

PB-214 77. 11

10. 70 6.08E- 01 9. 54E-02

4. 31E-Ol 295. 21 19. 20 9. 30E-02 l.08E-Ol 351.92 37.20 8.08E- 02 9.54E-02

+

PA-228 89. 95 22.00 2. 86E+OO 1. 15E+OO

1. 96E+OO 93. 35 35.00

-2.22E- 01 1.15E+OO 105. 00 1 6.30 -l. 02E+OO 2. llE+OO 129. 22 2.97

- 8.93E- 01 l. 13E+ Ol 338.32 5.30

- 1.1 8E-01 6.91E+OO 463. 00 13.80

- l.4 4E+O O 2.66E+OO 911. 23 16.70 5. 77E+OO 3.90E+OO

+

AM-241 59.54 36.30 5. 99E-02 1.98E- 01 1.98E- 01

+

CM-243 1 03. 76 23.00

-3.14E-02 1. 27E-01 l.27E- 01 228.18 10.60

-4.86E-02 2.58E- 01 277.60 14.00 3.52E-02 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

1/31/2019 8:27:30AM Page 7 of7 Analysis Report for L 1-SUB-LES-FSGF-010-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

J,Apex-Gamma 1/31/2019 8:30:53AM Analysis Report for L 1-SUB-LES-FSGS-011-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-011-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 8.541E+02 grams

Dairyland_NPP

2/2/2018 2:40:00PM

2/5/2018 11:49:55PM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3609.9 seconds

0.27%

3.00

100 -4096

100-4096

1.000 keV

7/8/2014

5822 PEAK ANALYSIS REPORT 1/31/2019 8:30:44AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of7

F M

m F

F F

M m

F F

1/31/2019 8:30:53AM Page 2 of?

Analysis Report for L 1-SUB-LES-FSGS-011-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

238.44 469 -

2 294. 98 584 -

3 299.71 584 -

4 338.49 671 -

5 351.53 695 -

6 582.89 1160 -

7 609.05 1213 -

8 661. 32 1314 -

9 784.33 1565 -

10 911. 05 1817 -

11 1460. 1 6 2912 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI end 485 606 606 681 71 0 117 3 1227 1331 1574 1829 2930 Peak Net Peak Net Area Continuum Centroid Area Uncertainty Counts 477.35 3. 37E+02 48.84 7.56E+02 590.40 1.29E+02 31. 97 3. 05E+02 599.86 5.76E+Ol 24.91 3.10E+02 677.41 5.24E+Ol 23. 54 2.36E+02 703.48 1.88E+02 35.89 3.08E+02 1166.12 8.97E+Ol 24.47 1.29E+02 1218.44

1. 31E+02

26. 96 l.15E+02 1322. 96 1.05E+02 23.79 1. 13E+02 1568.94 1.40E+Ol 9.21 4.67E+Ol 1822. 33 6.35E+Ol 20.68 9.39E+Ol 2920.44 4.69E+02 43.36 O. OOE+OO BACKGROUND SUBTRACT REPORT

1/31/2019 8:30:44AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 238.4 4 3.37E+02 48.84 2

2 94. 98 1.29E+02 31.97 3

299.71 5.76E+Ol 24.91 4

338.4 9 5.24E+Ol 23.54 5

351. 53 1.88E+02 35.89 8. 36E+Ol 3.72E+Ol 6

582.89 8.97E+Ol 24. 47 7

609.05 1.31E+02 26. 96 4.12E+Ol 2.42E+Ol 8

661. 32 1.0SE+02 23. 79 6.61E+Ol 2.54E+O l 9

784. 33 1.40E+Ol 9.21 10 911. 05 6.35E+Ol 20.68 11 1460. 16 4.69E+02 43.36 5. 63E+Ol

1. 71E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 3.37E+02 1.29E+02 5.76E+Ol 5.24E+Ol

1. 04E+02 8.97E+Ol 9.0l E+Ol 3.85E+Ol

1. 40E+Ol 6. 35E+Ol 4.12E+02 FWHM (keV) 2.0 1 2.1 7 2.18 1.53 2.52 2.33 2.23 2.05 1.10 2.23 2.81 Subtracted Uncert.

4.88E+Ol 3.20E+Ol 2.49E+Ol 2.35E+Ol 5. 17E+Ol 2.45E+Ol 3.62E+Ol 3.48E+Ol 9.21E+OO 2.07E+Ol 4.66E+Ol

1/31/2019 8:30:53AM Page 3 of7 Analysis Report for L 1-SUB-LES-FSGS-011-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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 0.94 1460.75 10.67 5.26E+OO 6.62E-01 CS-137 0.98 661.65 85.12 3.04E-02 2.76E-02 PB-212 0.55 77.11 17.50 238.63 44.60 2.03E-01 3.13E-02 BI-214 0.34 609.31 46.30 l.21E-01 4.93E-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 2.16E-01 5.45E-02 351.92 37.20

1. 05E-Ol 5.25E-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 Name Nuclide Id Confidence Wt mean Activity (pCilgrams)

Wt mean Comments Activity Uncertainty

1/31/2019 8:30:53AM Analysis Report for L 1-SUB-LES-FSGS-011-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name K-40 CS-137 PB-212 BI-214 PB-214 Nuclide Id Confidence 0.946 0.983 0.556 0.344 0.705

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCi/grams) 5.26E+OO 3.04E-02 2.03E-01 1.21E-01 1.58E-01 nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Activity Uncertainty 6.62E-01 2.76E-02 3.13E-02 4.93E-02 3.78E-02 Page 4 of7 Comments

1/31/2019 8:30:53AM Analysis Report for L 1-SUB-LES-FSGS-011-SB m

F F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 3 299.71 4

338.49 6

582.89 9

784.33 10 911. 05 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:30:44AM

100

4096 Peak CPS(%)

Peak Size (CPS)

Uncertainty l.59878E-02 21.64 1.45504E-02 22.47 2.49288E-02 13.63 3.88778E-03 32.90

1. 76461E-02 16.27 Peak Type Tol.

Tol.

NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland _ N PP\\Library\\HOTLAB. NLB Nuclide Energy Yield(%)

Activity NuclldeMDA LlneMDA Name (keV)

(pCVgrams)

(pCi/grams)

K-40 1460.75 10.67 5.26E+OO 5.12E-01 5.12E-01 AR-41 1293.64 99.16

-3.14E+ll l.47E+l2 l.47E+l2 C0-60 1173.22 100.00 5.97E-02 4.92E-02 6.21E-02 1332.49 100.00 3.32E-02 4.92E-02 KR-85 513. 99 0.43 7.48E+OO 9.34E+OO 9.34E+OO Y-88 898.04 93.70

-7.29E-04 2.69E-02 4.61E-02 Page 5 of7 Tolerance Nuclide AC-228 PA-228 AC-228 PA-228

1/31/2019 8:30:53AM Page 6 of7 Analysis Report for L 1-SUB-LES-FSGS-011-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity Nuc/ldeMDA LineMDA Name (keV)

(pCilgrams)

Y-88 1836. 06 99.20

-4.62E-02 2. 69E-02 2.69E-02

+

NB-94 702.63 100.00 3.94E-02 4.19E-02 4.19E-02 871.10 100.00

1. 4 7E- 02 4.25E- 02

+

I-131 284. 30 6.06 4. 39E-02 4. 91E-02 6.56E-01 364.48

81. 20

-4.39E-02 4.91E-02 636.97 7.27 3.61E-Ol 6.93E-01

+

CS-134 604. 70

97. 60

-2.83E-02 4.58E-02 5.17E-02 795. 84 85. 40

- l. 79E-02 4.58E-02

+

CS-137 661.65 85.12 3.04E-02 5.4 9E-02 5.49E-02

+

CE-144 80. 12 1.36

-l.42E+OO 2.55E- 01 3. 38E+OO 133. 51

11. 09 2.89E-02 2.55E-01

+

EU-152 121. 78 28.40

-4. 23E- 02 l.OlE- 01

l. OlE- 01 344.28 26.60

- 8.56E- 02

1. 36E-Ol 1408.00 20.7 4 4. 68E- 02 2. 04E-01

+

EU-1 54 123.07 40.40

-3.lOE-02 7.08E-02 7. 08E-02 723. 30 19.70

1. 41E-Ol 2.15E-Ol 1274.51 35. 50

-l.31E-Ol l.46E-01

+

EU-155 86.54 32.80 7.92E-02 l. 19E-01

l. 19E-Ol 105.31

21. 80 8.75E-02 l.43E-01

+

BI-214 609.31 46.30 l.21E-01 8. 70E-02 8.70E-02 1120. 29 15.10 5. 0lE-01 4.08E-01 1238.11 5.94

1. 32E-O l l.06E+OO 1377. 67 4.11 8. 22E-02

1. 05E+OO 1407.98 2.48 3. 91E-0 1

1. 71E+OO 1509.1 9 2.19 6.87E-01 l.54E+OO 1764. 49 15. 80

1. 4 7E-O l 2.37E-Ol

+

PB-214 77.11 10. 70 4.66E-Ol 1.0 lE- 01 4.63E-01 295.21 19. 20 2.16E-Ol

1. OlE-01 351.92 37.20 1.05E-01 1.02E- 01

+

PA-228 89.95 22.00 2.61E+OO

1. 24E+OO

2. 1 8E+OO 93.35 35.00

-1. 33E+OO 1.24E+OO 105.00 16.30 5.91E-01 2.49E+OO 129.22 2.97

-l.92E+OO 1.24E+Ol 338.32 5.30 3.49E+OO 8.20E+OO 463.00

13. 80 3.42E+OO 3.45E+OO 911.23 16. 70 6.25E+OO 4.55E+OO

+

AM-241 59. 54 36. 30

-1. 25E-03 2. 13E-Ol 2.13E-01

+

CM-243 103.76 23.00 7. 28E-02 l.36E-01 1. 36E-01 228. 18 10.60

-7.56E-02 2.73E-01 277. 60 14.00 5.03E-04 2.lOE- 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

1/31/2019 8:30:53AM Page 7 of7 Analysis Report for U-SUB-LES-FSGS-011-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

.JtApex-Gamma 1/31/2019 8:34:41AM Analysis Report for L 1-SUB-LES-FSGS-012-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-012-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 9.546E+02 grams

Dairyland_NPP

2/2/2018 2:45:00PM

2/6/2018 12:52:37AM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3609. 7 seconds

0.27%

3.00

100-4096

100 - 4096

1.000 keV

7/8/2014

5825 PEAK ANALYSIS REPORT 1/31/2019 8:34:32AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of7

1/31/2019 8:34:41AM Page 2 of7 Analysis Report for L 1-SUB-LES-FSGS-012-SB F

F F

F SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

238.73 472 -

2 295. 11 585 -

3 338. 33 670 -

4 351.53 698 -

5 509.94 1014 -

6 583. 00 1159 -

7 609. 00 1214 -

8 661. 32 1313 -

9 968.69 1933 -

10 1460.25 2912 -

11 1763.28 3522 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI end 485 596 685 708 1026 1174 1226 1331 1945 2928 3531 Peak Net Peak Net Area Continuum Centroid Area Uncertainty Counts 477. 95 3. 89E+02 53.02 6.42E+02 590.67 9.33E+Ol 30.45 3.23E+02 677.0 9 7.32E+Ol 28. 34 3.48E+02 703.4 9 l.67E+ 02 33.94 2.56E+02 1020.25 7.51E+Ol 25.75 1.72E+02 1166.34 1.06E+02 26. 97 1.59E+02 1218.32 1.32E+02 26. 53

1. 02E+02 1322.96 l.69E+02 28.98

1. 00E+02 1937. 61 4.21E+Ol 16.66 6.86E+Ol 2920.61 5.65E+02 48.48 4.26E+Ol 3526.64 1.56E+Ol 1 0. 04 1.49E+Ol BACKGROUND SUBTRACT REPORT

1/31/2019 8:34:32AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 238.73 3. 89E+02 53.02 2

295.11 9.33E+O l 30.45 3

338.33 7.32E+Ol 28.34 4

351.53 l. 67E+02 33.94 8.36E+Ol 3.72E+Ol 5

509.94 7. 51E+Ol 25.75 6

583.00

1. 06E+02 26.97 7

609. 00 1.32E+02 26. 53 4.12E+Ol 2.42E+Ol 8

661. 32 l.69E+02 28.98 6.61E+Ol 2.54E+Ol 9

968.69 4.2 1E+Ol 16.66 10 1460. 25 5.65E+02 48.48 5. 63E+Ol

1. 71E+Ol 11 1763. 28

1. 56E+Ol 1 0. 04 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 3.89E+02 9. 33E+Ol 7.32E+Ol 8.36E+Ol 7.51E+Ol

1. 06E+02 9.07E+Ol l.02E+02 4.21E+Ol 5. 09E+02 l. 56E+Ol FWHM (keV) 2.62

1. 88 2.2 1

1. 85 2. 60 2.71 2.34

2. 44

1. 74 2.56

1. 82 Subtracted Uncert.

5. 30E+Ol 3.04E+Ol 2.83E+Ol 5. 04E+Ol 2. 57E+Ol 2.70E+Ol 3.59E+Ol 3.85E+Ol 1.67E+Ol 5.14E+Ol l.OOE+Ol

1/31/2019 8:34:41AM Page 3 of7 Analysis Report for L 1-SUB-LES-FSGS-012-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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. 96 1460.75 10.67 5.81E+OO 6.69E-01 CS-137 0.98 661.65 85.12 7.25E-02 2.75E-02 PB-212 0.55 77.11 17.50 238.63 44.60 2.lOE-01 3.06E-02 BI-214 0.34 609.31

46. 30 1.09E-01 4.37E-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

1. 40E-01 4.61E-02 351.92 37.20 7.56E-02 4.57E-02

= Energy line found in the spectrum.

a: 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 Name Nuclide Id Confidence Wt mean Activity (pCi/grams)

Wt mean Comments Activity Uncertainty

1/31/2019 8:34:41AM Analysis Report for L 1-SUB-LES-FSGS-012-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name K-40 CS-137 PB-212 BI-214 PB-214 Nuclide Id Confidence 0. 961 0.983 0.559 0. 342 0.708

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCl/grams) 5.81E+OO 7.25E-02 2.lOE-01 l.09E-01

1. 07E-01

= nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Activity Uncertainty 6.69E-Ol 2.75E-02 3.06E-02 4.37E-02 3.25E-02 Page 4 of7 Comments

1/31/2019 8:34:41AM Analysis Report for L 1-SUB-LES-FSGS-012-SB F

F F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit l 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 3 338.33 5

509.94 6

583.00 9

968.69 11 1763.28 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:34:32AM

100

4096 Peak Size (CPS) 2.03259E-02 2.08512E-02 2.93097E-02 1.16973E-02 4.33696E-03 Peak CPS(%)

Uncertainty 19.37 17.15 12.78 19.79 32.14 Peak Type Tol.

Tol.

NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCi/grams)

K-40 1460.75 10.67 5.81E+OO 5.57E-01 5.57E-Ol AR-41 1293.64 99.16 1.01E+l2 1.90E+l2

1. 90E+12 C0-60 1173.22 100.00 3.07E-02 4.0lE-02 5.37E-02 1332.49 100.00

-3.63E-03 4.0lE-02 KR-85 513. 99 0.43 8.22E+OO 8.69E+OO 8.69E+OO Y-88 898.04 93.70

-2.18E-02 3.06E-02 4.31E-02 1836.06 99.20 5.70E-03 3.06E-02 NB-94 702.63 100.00 9.39E-04 3.48E-02 3.48E-02 871.10 100.00

-1. 25E-02

3. 96E-02 I-131 284.30 6.06 4.33E-01 4.78E-02 6.38E-01 Page 5 of7 Tolerance Nuclide AC-228 PA-228 AC-228

1/31/2019 8:34:41AM Page 6 of7 Analysis Report for L 1-SUB-LES-FSGS-012-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-01Q..103 Nucllde Energy Yield(%)

Activity NuclldeMDA LineMDA Name (keV)

(pCilgrams)

(pCi/grams)

I-131 364.4 8

81. 20

-8. 34E-03 4. 78E- 02 4.78E- 02 636.97 7.27

- 2.33E- 01 6.22E-Ol

+

CS-134 604. 70 97.60

- 6.38E-02 4.56E-02 4.56E-02 795.84 85.40 2. 27E- 02 4.91E-02

+

CS - 137 661.65 85.12 7.25E-02 4.83E- 02 4.83E- 02

+

CE-14 4 80.12

1. 36

-1. 31E+OO 2.43E-01 3.03E+OO 133.51

11. 09 l.12E-02 2.43E-01

+

EU-152 121. 78 28.40

-1. 21E-Ol 9.40E-02 9.40E-02 3 44.28 26. 60

-2.15E-02 1.21E-01 1408.00 20.74

-l.59E-02 l.77E-01

+

EU-1 54 123.07 40. 40

- 6.14E-02 6.64E-02 6.64E-02 723.30 19.70

1. 36E-02 1.87E-Ol 1274.51 35. 50

- 1. 42E- 03

1. 41E-01

+

EU-155 86.54 32.80 8.08E-02 l.lOE-01 1.lOE-01 105. 31

21. 80

-4. 39E-03

1. 28E-01

+

BI-214 609. 31 46.30 l.09E-01 7.49E-02 7.4 9E- 02 1120.29 15.10 1.13E-01 3. 79E-01 1238. 11 5.94 9.59E-01

1. 03E+OO 1377.67 4.11

- 2.82E- 02 8.84E-01 1407. 98 2.4 8

-1. 33E-01 1.48E+OO 1509. 19 2. 19 1.16E+OO

1. 51E+OO 1764.49 15.8 0 2.29E-01 2. 73E-01

+

PB-214 77.11 10.70 5.80E-01 8.30E-02 4.1 3E-Ol 295.2 1 19.20 l.40E-01 1.04E-01 351. 92 37.20 7. 56E- 02 8.30E-02

+

PA-228 89.95 22.00 3.56E+OO

1. 26E+OO 2.14E+OO 93. 35 35. 00 2. 69E-01

1. 26E+OO 105.00 16.30

-2.17E-01 2.32E+OO 129.22 2. 97 4.80E+OO

1. 23E+Ol 338.32 5.30 6.89E+OO 7. 96E+OO 463.00 13.80 2.50E+OO 3.21E+OO 911. 23 1 6.70 6.04E+OO 4. 18E+OO

+

AM-241 59.54 36.30 3. 96E-02

1. 96E-0 1

1. 96E-01

+

CM-243 103.76 23.00 3.lOE-02 l.24E-01

1. 2 4E-01 228.18 10.60

-2. 93E-03 2.51E-01 277.60 14.00

-1. 44E-01

2. llE- 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

1/31/2019 8:34:41AM Page 7 of7 Analysis Report for L 1-SUB-LES-FSGS-012-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

~ ~§'~pex-Gamma 1/31/2019 8:36:45AM Analysis Report for L 1-SUB-LES-FSGS-013-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-013-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 9.180E+02 grams

Dairyland_NPP

2/2/2018 2:53:00PM

2/6/2018 1 :55:58AM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3609.9 seconds

0.28%

3.00

100-4096

100 - 4096

1.000 keV

7/8/2014

5827 PEAK ANALYSIS REPORT 1/31/2019 8:36:36AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of6

F F

1/31/2019 8:36:45AM Page 2 of6 Analysis Report for l 1-SUB-LES-FSGS-013-SB SYSTEMATICS FOR l 1-SUB-LES WITHIN Survey Unit l 1-010-103 Peak Energy ROI No.

(keV) start 1

238.62 469 -

2 29 4.92 585 -

3 351.68 697 -

4 582.84 1159 -

5 608.92 1214 -

6 726. 91 1450 -

7 910.91 1816 -

8 1460. 19 2910 -

9 1763.18 3521 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI end 485 596 710 1172 1224 1459 1826 2928 3531 Peak NetPeak Net Area Continuum Centroid Area Uncertainty Counts 477.71 4.14E+02 52.89 6. 20E+02 590. 29 9.45E+Ol 31.67 3. 75E+02 703.79 l.86E+02 35. 18 2. 63E+02 1166.03 8.95E+Ol 24.65 l.4 3E+02 1218. 18 8.61E+Ol 24. 08 l.27E+02 1454.11 l.89E+O l 4. 62 9. 32E+Ol 1822.06 4.42E+Ol 17.06 7.44E+Ol 2920.4 9 5. 18E+02

46. 40 3.98E+Ol 3526. 43 l. 95E+Ol 10.01 l. llE+Ol BACKGROUND SUBTRACT REPORT

1/31/2019 8:36:36AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 238.62 4.14E+02 52.89 2

294.92 9.45E+Ol 31.67 3

351.68

1. 86E+02 35.18 8.36E+Ol

3. 72E+Ol 4

582.84 8.95E+Ol 24.65 5

608.92 8.61E+Ol 24.08 4.12E+Ol 2.42E+Ol 6

726. 91 l.89E+Ol 4.62 7

910. 91 4.42E+Ol 17.06 8

1460.19 5.18E+02 46.40 5. 63E+Ol

1. 71E+Ol 9

1763.18 l.95E+Ol 10.01 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 4.1 4E+02 9.45E+Ol

l. 03E+02 8.95E+Ol 4.49E+Ol l.89E+Ol 4. 42E+Ol 4.62E+02 l.95E+Ol FWHM (keV) 2. 86

1. 85 2.35 2. 11

1. 89 0. 61

1. 44 2.84

1. 77 Subtracted Uncert.

5.29E+Ol 3.17E+Ol 5.12E+Ol 2.46E+Ol 3.42E+Ol 4.62E+OO l. 71E+Ol 4.95E+Ol

1. OOE+Ol

1/31/2019 8:36:45AM Page 3 of6 Analysis Report for L 1-SUB-LES-FSGS-013-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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 0.95 1460.75 10.67 5.48E+OO 6.61E-01 BI-212 0.59 727.17

11. 80

1. 09E-Ol 2.73E-02 785.42 2.00 1620.56 2.75 PB-212 0.56 77.11 17.50 238.63 44.60 2.33E-01 3.21E-02 BI-214 0.33 609.31 46.30 5.63E-02 4.29E-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

1. 4 7E-01 4.98E-02 351.92 37.20 9.64E-02 4.84E-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 Name Nuclide Id Confidence Wt mean Activity (pCl/grams)

Wt mean Comments Activity Uncertainty

1/31/2019 8:36:45AM Analysis Report for l 1-SUB-LES-FSGS-013-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name K-40 BI-212 PB-212 BI-214 PB-214 Nuclide Id Confidence 0.951 0.598 0.560 0.337 0.712

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCilgrams) 5.48E+OO 1.09E-Ol 2.33E-Ol 5.63E-02 l.21E-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Activity Uncertainty 6.61E-Ol 2.73E-02 3.21E-02 4.29E-02 3.47E-02 Page 4 of6 Comments

1/31/2019 8:36:45AM Analysis Report for L 1-SUB-LES-FSGS-013-SB F

F F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 4 582.84 7

910.91 9

1763.18 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:36:36AM

100

4096 Peak Size (CPS)

2. 48713E-02 l.22689E-02 5.40537E-03 Peak CPS(%)

Uncertainty 13.76

19. 31 25.73 Peak Type Tol.

NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity Nuclide MDA LlneMDA Name (keV)

(pCilgrams)

(pCi/grams)

K-40 1460.75 10.67 5.48E+OO 5.83E-01 5.83E-01 AR-41 1293.64 99.16 l.60E+l2 2.78E+l2 2.78E+l2 C0-60 1173.22 100.00 l.42E-02 4.61E-02 5.93E-02 1332.49 100.00 9.70E-03 4.61E-02 KR-85 513. 99 0.43 9.34E+OO 8.64E+OO 8.64E+OO Y-88 898.04 93.70

-2.20E-02 3.18E-02 4.31E-02 1836.06 99.20

-3.13E-03 3.18E-02 NB-94 702.63 100.00

-2.24E-02 3.52E-02 3.52E-02 871.10 100.00 1.81E-02 4.05E-02 I-131 284.30 6.06

-7.73E-02 4.67E-02 6.38E-Ol 364.48 81.20 2.39E-02 4.67E-02 636.97 7.27 3.91E-01 6.53E-Ol CS-134 604.70 97.60

-5.53E-02 4.46E-02 4.46E-02 Page 5 of6 Tolerance Nuclide AC-228 PA-228

1/31/2019 8:36:45AM Page 6 of 6 Analysis Report for L 1-SUB-LES-FSGS-013-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCi!grams)

(pCilgrams)

CS-134 795.84

85. 40

- 2.22E- 02 4.4 6E-02 4.65E-02

+

CS-137 661.65 85.12 8. 61E-03 4. 68E- 02 4.68E- 02

+

CE-1 44 80. 12

1. 36 1.69E+OO 2. 48E-01

3. 1 8E+OO 133. 51

11. 09 8. 90E-02 2.48E- 01

+

EU-152 121. 78

28. 40 6. 41E-02 9.89E-02 9. 89E-02 344. 28 26. 60 1.65E-02 1. 25E-01 1 40 8. 00 20.74 1.51E- 01 2.0lE- 01

+

EU-154 123.07 40.40 5. 29E-02 6. 95E-02 6.95E-02 723. 30 1 9. 70 2. 27E- 01 2.15E-01 1 274. 51 35. 50 2.73E-03 1. 27E-01

+

EU-155 86. 54 32. 80

- 9. 28E- 02 1.08E- 01 1.08E- 01 105.31

21. 80 1.09E-01

1. 33E-01

+

BI-214 609. 31 4 6. 30 5.63E-02 7.97E-02 7.97E- 02 1120. 29 15.10 3.57E-01 3.59E- 01 1 238.11 5.94

1. 55E+OO

1. ll E+OO 1377.67 4.11

- 1. 76E- 01

1. 02E+OO 1407.98 2. 48 1.26E+O O 1.68E+OO 1509.1 9 2.19 1.72E+OO l.65E+OO 1764.49 15.80 2.32E-01 2.98E-Ol

+

PB-2 1 4 77. 11 10.70 7. 48E- 01 8.97E-02 4. 32E- 01 295. 21 19.20 1.47E-01 1.16E-01 351.92 37.20 9.64E-02 8.97E- 02

+

PA-228

89. 95 22.00 2.73E+OO 1.29E+OO 2.20E+OO 93.35 35. 00 9.07E- 03 1. 29E+OO 105.00 1 6.30 2.03E+OO 2.47E+OO 129. 22 2. 97 l.41E+OO

1. 30E+Ol 338.32 5. 30 8.90E+OO 8. 54E+OO 4 63.00 13. 80 4. 19E-01 3. 17E+O O 911.23 1 6.70 5.1 4E+OO

4. 13E+OO

+

AM-24 1 59.54 36.30

-1.59£- 01 1. 91E- 01

1. 91E-01

+

CM-243 103.76 23.00 3. 08E- 02

1. 26E-Ol 1.26E-Ol 228.1 8 10. 60 1. 32E-Ol 2. 59£ -0 1 277. 60 14.00 4.09E- 02 2.06E- 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

_.Apex-Gamma 1/31/2019 8:38:26AM Analysis Report for L 1-SUB-LES-FSGS-014-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-014-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 8.720E+02 grams

Oairyland_NPP

2/2/2018 2:59:00PM

2/6/2018 6:41:37AM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3610.1 seconds

0.28%

3.00

100 - 4096

100 -4096

1.000 keV

7/8/2014

5829 PEAK ANALYSIS REPORT 1/31/2019 8:38:17AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of7

1/31/2019 8:38:26AM Page 2 of7 Analysis Report for L 1-SUB-LES-FSGS-014-SB F

F F

F SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

185. 34 368 -

2 238.47 469 -

3 2 94. 90 584 -

4 338. 05 673 -

5 351.65 695 -

6 451.69 900 -

7 583.06 1159 -

8 609.08 1209 -

9 726. 55 1449 -

10 910.82 181 5 -

11 1119.77 2235 -

12 1460. 22 2909 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI end 376 485 595 681 712 907 1174 1225 1459 1829 2245 2 928 Peak NetPeak Net Area Continuum Centroid Area Uncertainty Counts 371. 19 4.18E+Ol 26. 06 5.07E+02 477.42 3.97E+02 52.04 6. 89E+02 590.26 9.63E+Ol

31. 87 4.02E+02 676. 53

4. 15E+Ol 23.02 2.19E+02 703.74 l.71E+02 32.82 3.46E+02 903.76 l.83E+Ol 5. 98 9.lOE+Ol 1166.46 9.56E+Ol

24. 85 l.35E+02 1218.50

1. 28E+02 26.60 1. 40E+02 1453.39 2.91E+Ol 13. 29 5. 59E+Ol 1821.88 5.38E+Ol 18. 19 6.90E+Ol 2239. 72

2. 26E+O l 13.21

4. 72E+Ol 2920. 55 5.21E+02 46.30 2. 29E+Ol BACKGROUND SUBTRACT REPORT Peak Analysis Performed on Env. Background File Peak Energy No.

(keV) 1 185. 34 2

238.47 3

294.90 4

33 8.05 5

351. 65 6

451. 69 7

583. 06 8

609. 08 9

726. 55 10 910.82

1/31/2019 8:38:17AM

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Original Orig. Area Ambient Backgr.

Area Uncertainty

Background

Uncert.

4.18E+Ol 26.06 3. 97E+02 52.04 9.63E+Ol

31. 87 4.15E+Ol 23.02

1. 71E+02 32.82 8. 36E+Ol 3. 72E+Ol

1. 83E+Ol 5.98 9.56E+Ol 2 4.85 1.28E+02

26. 60 4.12E+Ol 2. 42E+Ol 2.91E+Ol 13.29 5.38E+Ol 18.19 11 111 9. 77 2. 26E+O l 13.21 12 1460. 22 5. 21E+02

46. 30 5.63E+Ol

1. 71E+Ol Subtracted Area 4.18E+Ol 3.97E+02 9. 63E+Ol 4. 15E+Ol 8. 79E+Ol

1. 83E+Ol 9.56E+Ol 8.70E+Ol 2. 91E+Ol 5. 38E+Ol 2. 26E+Ol 4. 65E+02 FWHM (keV) 0.90 2. 52

1. 70

1. 44

1. 85 0.56 2.49 2.05

1. 02 2. 09

1. 65 2. 90 Subtracted Uncert.

2.61E+Ol 5.20E+Ol 3. 19E+Ol 2. 30E+Ol 4. 96E+Ol 5.98E+OO 2. 48E+Ol 3.60E+Ol

1. 33E+Ol 1. 82E+Ol 1. 32E+Ol 4. 94E+Ol

1/31/2019 8:38:26AM Page 3 of7 Analysis Report for L 1-SUB-LES-FSGS-014-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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 0.95 1460.75 10.67 S.81E+OO 6.96E-Ol BI-212 0.56 727.17

11. 80 l.77E-Ol 8.14E-02 785.42 2.00 1620.56 2.75 PB-212 0.55 77.11 17.50 238.63 44.60 2.35E-Ol 3.31E-02 BI-214 0.57 609.31 46.30 1.lSE-01 4.79E-02 1120.29 15.10 1.58E-01 9.28E-02 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.58E-Ol 5.28E-02 351.92 37.20 8.70E-02 4.93E-02 RA-226 0.88 186.21 3.28 2.82E-Ol 1.77E-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

1/31/2019 8:38:26AM Analysis Report for L 1-SUB-LES-FSGS-014-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 INTERFERENCE CORRECTED REPORT Nuclide Name K-40 BI-212 PB-212 BI-214 PB-214 RA-226 Nuclide Id Confidence 0.956 0.562 0.558 0.574

0. 711 0.887

?

= nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis Wt mean Activity (pCilgrams) 5.81E+OO 1.77E-01 2.35E-01 1.24E-Ol

1. 20E-01 2.82E-Ol

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

6. 96E-01 8.14E-02 3.31E-02 4.26E-02 3.60E-02 1.77E-01 Page4 of?

Comments

1/31/2019 8:38:26AM Analysis Report for L 1-SUB-LES-FSGS-014-SB F

F F

F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 4 338.05 6

451.69 7

583.06 10 910.82 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:38:17AM

100

4096 Peak Size (CPS) l.15161E-02 5.08970E-03 2.65519E-02 1.49439E-02 Peak CPS(%)

Uncertainty 27.76 16.32 13.00 16.91 Peak Type Tol.

Tol.

NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nucllde Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCi/grams)

K-40 1460.75 10.67 5.81E+OO 5.66E-01 5.66E-01 AR-41 1293.64 99.16

-9.74E+l2

1. 87E+l3

1. 87E+l3 C0-60 1173.22 100.00

-1.lOE-03 4.39E-02 5.69E-02 1332.49 100.00

-l.05E-02 4.39E-02 KR-85 513.99 0.43 l.52E+Ol 9.56E+OO 9.56E+OO Y-88 898.04 93.70 7.36E-03 2.78E-02 4.77E-02 1836.06 99.20

-6.38E-03 2.78E-02 NB-94 702.63 100.00 4.75E-04 3.86E-02 3.86E-02 871.10 100.00

-2. 27E-02 3.90E-02 I-131 284.30 6.06

-1.74E-01 5.39E-02 6.70E-01 Page 5 of7 Tolerance Nuclide AC-228 PA-228 AC-228 PA-228

1/31/2019 8:38:26AM Page 6 of7 Analysis Report for L 1-SUB-LES-FSGS-014-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi/grams)

(pCi!grams)

I-131 364. 48 81.20 2. 82E-02 5.39E- 02 5.39E-02 636.97 7.27 1.08E-01 7. 06E-01

+

CS-134 604.70 97. 60

-4.72E-03 4.88E-02 4.88E-02 795.84 85.40

-3.49E-02 5.00E-02

+

CS-1 37 661.65 85.12 3.84E-02 5.33E- 02 5.33E-02

+

CE-144 80.12

1. 36 7.09E-01 2.5 6E-01 3.33E+OO 133. 51

11. 09

-2. llE-01 2.56E-01

+

EU-152 121. 78

28. 40

-1.86E-0 2 1.02E-O l 1.02E-01 344. 28 26. 60

-6.25E-02

1. 28E-01 1408. 00 20.74

-4.92E-02 1.93E-01

+

EU-154 123.07 40.40 2.lOE-02 7. 25E-02 7.25E-02 723.30 19.70 9.60E-02 2.18E-01 1274.51 35.50 3.95E-02

1. 48E-01

+

EU-155 86.54 32.80

- 3.61E-02 1.15E-01 l.15E-01 1 05. 31 21. 80 6.59E- 03

1. 38E-01

+

BI-214 609.31 46.30 l.15E-Ol 9.12E-02 9.12E-02 1120. 29 15.10 1.58E-01 1.94E-01 1238.11 5. 94 3.75E-01 1.07E+OO 1377. 67 4.11

- 3.57E-01 9. 68E- 01 1407.98 2.48

-4. llE- 01 1.62E+OO 1509.19

2. 19

-1.48E+OO 1. 57E+OO 17 64. 4 9 15.80

1. 62E-01 2.87E-01

+

PB-214 77.11 10.70 4.82E-01 1.05E- 01 4.52E-01 295. 21 19. 20

1. 58E-Ol 1.26E-01 351. 92 37.20 8. 70E- 02 1.05E-01

+

PA-228 89. 95 22.00 3.17E+OO 1.59E+OO 2.69E+OO 93. 35 35.00 3.70E-01

1. 59E+OO 105.00 16. 30

- 7.74E-Ol 2.98E+OO 129.22 2.97 9.38E-Ol

1. 55E+Ol 338.32 5.30 7.56E+OO 9. 99E+OO 463.00 13. 80 3.42E+OO 4.09E+OO 911. 23 16.7 0 5.05E+OO 4.87E+OO

+

AM-241 59.54 36.30 2.19E-02 2. llE-01

2. llE-01

+

CM-243 103.76 23.00

-1.06E-0 2 1.32E-01 1.32E-01 228. 18 10.60 2. 39E-Ol 2.80E-01 277.60 14.00

-1.33E-02 2.19E-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 perfo,m the decay correction

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

1/31/2019 8:38:26AM Page 7 of7 Analysis Report for L 1-SUB-LES-FSGS-014-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

1/31/2019 8:47:14AM Analysis Report for L 1-SUB-LES-QSGS-008-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010..103 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-QSGS-008-SB

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103

500 ml Marinelli 9.077E+02 grams

Dairyland_NPP

2/2/2018 1:32:00PM

2/6/2018 9:29:56AM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3609.6 seconds

0.27%

3.00

100 - 4096

1.000 keV

7/8/2014

5831 PEAK ANALYSIS REPORT 1/31/2019 8:47:05AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Pagel of6

F F

1/31 /2019 8:47:14AM Page 2 of6 Analysis Report for L 1-SUB-LES-QSGS-008-SB F

F F

F SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Energy ROI No.

(keV) start 1

76. 04 14 7 -

2 238.51 469 -

3 294. 85 583 -

4 351.86 698 -

5 582. 80 1160 -

6 608.93 1212 -

7 910. 78 1815 -

8 1191. 90 2379 -

9 1460. 25 2912 -

10 1764. 27 3522 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI Peak Net Peak end Centroid Area 161 152.63 2. 69E+02 485 477. 49 3. 08E+02 594 590. 16

1. 01E+02 709 704.15 l.73E+02 1173 1165.95 9. 14E+Ol 1223 1218.19 1.05E+02 1829 1821.80 7.33E+Ol 2388 2383. 97 l.81E+Ol 2 930 2 920.62 5.39E+02 3535 3528.61 2. 67E+Ol Net Area Continuum Uncertainty Counts 63.67

1. 35E+03 48. 68 8. 07E+02 29.68

3. 43E+02 33.83 2.41E+02 24. 66

1. 28E+02 26.12 1.26E+02 20.91 7. lOE+Ol 12. 35

4. 24E+Ol 47. 09 3.80E+Ol 10. 54 O. OOE+OO BACKGROUND SUBTRACT REPORT

1/31/2019 8:47:0SAM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 76. 04 2. 69E+02 63. 67 2

238. 51 3. 08E+02 48.68 3

29 4. 85 1. 01E+02 29.68 4

351.86 l. 73E+02 33. 83 8. 36E+Ol 3. 72E+Ol 5

582.80 9. 14E+Ol 24.66 6

608. 93

1. 05E+02 26. 12 4. 12E+Ol 2.42E+Ol 7

910. 78 7. 33E+O l 20.91 8

1191. 90

l. 81E+Ol 12. 35 9

1460. 25 5. 39E+02 47. 09 5. 63E+Ol l. 71E+Ol 10 1764.27 2. 67E+Ol 10.54 1. 52E+Ol 9. 80E+O O M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 2. 69E+02 3. 08E+02

1. 01E+02 8. 93E+Ol 9. 14E+Ol 6.35E+Ol 7.33E+Ol

1. 81E+Ol 4. 82E+02 1.16E+Ol FWHM (keV) 4. 43 2. 11

1. 60 2.11 2. 32 2. 11 2.67

1. 71 2. 72 2. 42 Subtracted Uncert.

6.37E+Ol 4.87E+O l 2. 97E+O l 5. 03E+Ol 2. 47E+Ol 3. 56E+Ol 2.09E+Ol 1.24E+Ol 5. 0lE+Ol 1.44E+Ol

1/31/2019 8:47:14AM Page 3 of6 Analysis Report for L 1-SUB-LES-QSGS-008-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 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. 96 1460.75 10.67 5.79E+OO 6.82E-01 PB-212 0.55 77.11 17.50 238.63 44.60 1.75E-01

2. 91E-02 BI-214 0.53 609.31

46. 30 8.06E-02 4.54E-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 1.lOE-01 l.37E-Ol PB-214 0.71 77.11 10.70 295.21 19.20 1.59E-01 4.74E-02 351. 92 37.20 8.50E-02 4.80E-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 K-40 0.961 5.79E+OO 6.82E-01 PB-212 0.559 1.75E-01 2.91E-02 BI-214 0.539 8.35E-02 4.31E-02

1/31/2019 8:47:14AM Page 4 of6 Analysis Report for L 1-SUB-LES-QSGS-008-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Name PB-214 Nuclide Id Confidence 0. 71 5

?

= nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis Wt mean Activity (pCilgrams)

1. 23E-Ol

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Wt mean Comments Activity Uncertainty 3.37E-02

1/31/2019 8:47:14AM Analysis Report for L 1-SUB-LES-QSGS-008-SB F

F F

F

+

SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 1 76.04 5

582.80 7

910.78 8

1191. 90 M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:47:0SAM

100

4096 Peak Size (CPS)

7. 45965E-02

2. 53966E-02 2.03734E-02 5.04064E-03 Peak CPS(%)

Uncertainty

11. 85

13. 49 14.26 34.04 Peak Type Tol.

NUCLIDE MDA REPORT Nuclide library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity Nuc/ideMDA LineMDA Name (keV)

(pCVgrams)

(pC/lgrams)

(pCUgrams)

K-40 1460.75 10.67 5.79E+OO 5.83E-01 5.83E-01 AR-41 1293.64 99.16

-4.44E+13 8.81E+13 8.81E+13 C0-60 1173.22 100.00 4.65E-02 4.90E-02 5.93E-02 1332.49 100.00 4.78E-02 4.90E-02 KR-85 513. 99 0.43 5.61E+OO 9.12E+OO 9.12E+OO Y-88 898.04 93.70

-1.14E-02 3.41E-02 4.44E-02 1836.06 99.20

-2.48E-02 3.41E-02 NB-94 702.63 100.00 1.17E-02 3.77E-02 3.77E-02 871.10 100.00

-4.60E-02 3.94E-02 I-131 284.30 6.06

-3.04E-01 5.05E-02 6.76E-01 364.48 81.20 4.94E-04 5.05E-02 636.97 7.27 8.09E-02 6.54E-01 Page 5 of6 Tolerance Nuclide AC-228 PA-228

1/31/2019 8:47:14AM Page 6 of6 Analysis Report for L 1-SUB-LES-QSGS-008-SB SYSTEMATICS FOR L 1-SUB-LES WITHIN Survey Unit L 1-010-103 Nuclide Energy Yield(%)

Activity Nuclide MDA LlneMDA Name (keV)

(pCilgrams)

+

CS-134 604.70 97.60 6.98E- 02 4.56E-02

4. 56E-02 795.84 85.40 l.52E-02 4.93E-02

+

CS-137 661.65 85.12

-6.13E-05 4.80E-02 4. 80E-02

+

CE-1 44 80.12

1. 36

-l.13E+OO 2. 55E-01 3.19E+00 133.51

11. 09 4.92E-02 2. 55E-01

+

EU-152 121. 78 28.40

-9.49E-02 9.48E-02 9.48E-02 344.28 26.60 6.42E-03 l. 25E-01 1408.00 20.74

-2.16E-02 2.03E-Ol

+

EU-154 123.07 40.40

-6.14E-02 6.65E- 02 6.65E-02 723.30 19.70 5.54E-03 l.95E-Ol 1274.51 35.50 4.lOE-02 l.50E-01

+

EU-155 86.54 32.80

-l.98E-03 l. 12E-O l l.12E-01 105.31 21.80 6.55E-02

1. 35E-01

+

BI-214 60 9.31 46.30 8.06E-02 8.lOE-02 8.lOE-02 1120.29 15.10 2.81E-01 3.88E-01 1238.11 5. 94 5. 44E-01 l.OlE+OO 1377.67 4.11

1. OlE- 02 l.12E+OO 1407.98 2.48

-l.80E-01 1.70E+OO 1509.19 2.19

7. 96E-01

1. 50E+OO 1764.49 15.80 l.lOE-01 2.21E-01

+

PB-214 77.11 10.70 6.90E-01

8. 72E-02 4.34E-01 295. 21 19.20 1.59E-Ol l. 12E-01 351.92 37.20 8.50E-02 8.72E-02

+

PA-228 89.95

22. 00 l.71E+OO

1. 74E+OO 2.95E+OO 93.35 35. 00 9.00E-01 l.7 4E+OO 105. 00 16.30 2.52E-Ol 3.33E+OO 12 9. 22 2. 97 1.21E+Ol l.74E+Ol 338.32 5. 30

-4.20E+OO

1. 09E+Ol 463.00 13.80

-9. 21E-Ol 4.37E+OO 911. 23 16.70 8.77E+OO 5. 81E+OO

+

AM-241 59.54 36.30

-9.36E-02

1. 94E- 01 l.94E-Ol

+

CM-243 103.76 23. 00 l.97E-02 l.29E-Ol l. 29E-01 228.18 10.60

-1.02E-01 2.64E-01 277.60 14.00 2.94E-02 2.lOE-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

__.Apex-Gamma 1/31/2019 8:48:11AM Analysis Report for l 1-SUB-LES-FJGS-001-SB U-010-103 PACKAGE: L 1-SUB-LES GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FJGS-001-SB

L 1-010-103

500 ml Marinelli 1.045E+03 grams

Dairyland_NPP

2/8/2018 1 :43:00PM

2/9/2018 7:17:47AM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3610.6 seconds

0.29%

3.00

100-4096

1.000 keV

7/8/2014

5833 PACKAGE: L 1-SUB-LES PEAK ANALYSIS REPORT 1/31/2019 8:48:02AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Pagel of6

1/31/2019 8:48:11AM Page 2 of6 Analysis Report for L 1-SUB-LES-FJGS-001-SB F

F F

F L1-010-103 Peak Energy ROI No.

(keV) start 1

238.50 472 -

2 294.99 585 -

3 351.83 696 -

4 582.92 1161-5 608.92 1210 -

6 661.28 1315 -

7 910.62 1817 -

8 1460.1 9 2911-9 1763. 92 3523 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma PACKAGE: L 1-SUB-LES ROI Peak Net Peak Net Area Continuum end Centroid Area Uncertainty Counts 485 477.47 3. 27E+02 49.75 6. 39E+02 596 590.44 8. 49E+O l 31. 71 3.60E+02 710 704.08 2. 01E+02 35.96 2.96E+02 1171 1166. 18 8. 59E+Ol 23.32 1. 24E+02 1224 1218. 1 7 1.16E+02 26. 56

1. 35E+02 1329 1322.88 l. 10E+02 27. 10 1.65E+02 1829 1821. 48 6.34E+Ol 20.12 9.lOE+Ol 2930 2920.50 5. 37E+02 47. 12 4.53E+Ol 3534 3527. 90 2.82E+Ol 11.21 4.88E+OO BACKGROUND SUBTRACT REPORT

1/31/2019 8:48:02AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 238.50 3. 27E+02 49.75 2

294.99 8.49E+Ol 31. 71 3

351.83 2. 01E+02 35. 96 8.36E+Ol

3. 72E+Ol 4

582.92 8. 59E+Ol 23.32 5

608. 92 1.16E+02 26.56 4.12E+Ol 2.42E+Ol 6

661.28 1.10E+02 27.10 6.61E+Ol 2. 54E+Ol 7

910. 62 6.34E+Ol 20.12 8

1460.19 5.37E+02 47.12 5.63E+Ol

1. 71E+Ol 9

1763.92 2.82E+Ol 11.21 1.52E+Ol 9.80E+OO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 3.27E+02 8.49E+Ol 1.17E+02 8.59E+Ol 7.50E+Ol 4.43E+O l 6.34E+Ol 4.81E+02 l.30E+O l FWHM (keV) 2.58 2.11 2.21

1. 56 2. 19 2. 34

2. 07 2.68 3.00 Subtracted Uncert.

4.98E+Ol

3. 17E+Ol

5. 1 7E+Ol 2. 33E+Ol 3.59E+O l 3.71E+Ol 2.0lE+Ol 5.0l E+Ol l.49E+Ol

1/31/2019 8:48:11AM Page 3 of6 Analysis Report for L 1-SUB-LES-FJGS-001-SB L1-010-103 PACKAGE: L 1-SUB-LES 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 0.95 1460.75 10.67 5.0lE+OO 5.92E-Ol CS-137 0.97 661.65 85.12 2.86E-02 2.40E-02 PB-212 0.55 77.11 17.50 238.63 44.60 l.61E-01 2.59E-02 BI-214 0.53 609.31 46.30 8.26E-02 3.98E-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

1. OSE-01 l.23E-Ol PB-214 0.71 77.11 10.70 295.21

19. 20 1.16E-01 4.37E-02 351.92 37.20 9.70E-02 4.30E-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 K-40 0.951 5.0lE+OO 5.92E-Ol CS-137 0.979 2.86E-02 2.40E-02

Analysis Report for L 1-SUB-LES-FJGS-001-SB L 1-010-103 PACKAGE: L 1-SUB-LES Nuclide Nuclide Name Id Confidence PB-212 0.558 BI-214 0.531 PB-214 0.718

?

= nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis 1/31/2019 Wt mean Activity (pCilgrams) 1.61E-01 8.SOE-02 1.06E-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 8:48:11AM Page 4 of6 Wt mean Comments Activity Uncertainty 2.59E-02 3. 79E-02 3.07E-02

1/31/2019 8:48:11AM Analysis Report for L 1-SUB-LES-FJGS-001-SB F

F

+

U-010-103 Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 4 582.92 7

910.62 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma PACKAGE: L 1-SUB-LES UNIDENTIFIED PEAKS

1/31/2019 8:48:02AM

100

4096 Peak Size (CPS) 2.38629E-02 l.76234E-02 Peak CPS(%)

Uncertainty 13.57 15.86 NUCLIDE MDA REPORT Peak Type Tol.

Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nuclide Energy Yield(%)

Activity Nuc/ideMDA LineMDA Name (keV)

(pCVgrams)

(pCilgrams)

(pCi/grams)

K-40 1460.75 10.67 5.0lE+OO 5.24E-01 5.24E-01 AR-41 1293.64 99.16 4.70E-01 3.65E+Ol 3.65E+Ol C0-60 1173.22 100.00

-l.12E-02 4.16E-02 4.80E-02 1332.49 100.00 8.83E-03 4.16E-02 KR-85 513.99 0.43

1. OlE+Ol 8.lOE+OO 8.lOE+OO Y-88 898.04 93.70 5.74E-03 2.98E-02 3.95E-02 1836.06 99.20

-1. 53E-02 2.98E-02 NB-94 702.63 100.00

-2.74E-02 3.38E-02 3.38E-02 871.10 100.00

-5.94E-04 3.54E-02 I-131 284.30 6.06

-6.lOE-03 3.31E-02 4.52E-01 364. 48

81. 20

-1.88E-03 3.31E-02 636.97 7.27

-2.26E-01 4.47E-01 CS-134 604.70 97.60 7.39E-03 4.03E-02 4.03E-02 795.84 85.40 2.13E-02 4.09E-02 Page 5 of6 Tolerance Nuclide AC-228 PA-228

1/31/2019 8:48:11AM Page 6 of6 Analysis Report for L 1-SUB-LES-FJGS-001-SB L 1-010-1 03 PACKAGE: L 1-SUB-LES Nuclide Energy Yield(%)

Activity NuclldeMDA LlneMDA Name

{keV)

(pCilgrams)

+

CS-137 661.65 85.12 2.86E-02 4.76E-02 4.76E-02

+

CE-144

80. 1 2

1. 36

-9.66E-02 2.19E-Ol 2. 78E+OO 133.51

11. 09

-5.32E-02 2.19E-01

+

EU-152 121.78 28.40

-2.66E-02 8.61E-02 8.61E-02 344.28 26. 60 2.73E-02 1.09E-Ol 1408.00 20. 74 7.15E-02

1. 73E-01

+

EU-154 123.07 40.40

1. 25E-02 6. lOE-02 6.lOE-02 723.30 19.70 7.06E-02 1.78E-01 1274.51 35.50 7.64E-02 1.17E-01

+

EU-155 86.54 32.80

-5.87E-03 9.74E-02 9.74E-02 105.31 21.80

-1.17E-02 l.lBE-01

+

BI-214 609.31 46.30 8.26E-02 7.37E-02 7.37E-02 1120.29 15. 10 2.08E- 02 3. 37E-01 1238. 11 5.94

3. llE-01 9. 15E-01 1377. 67 4.11

-4.50E-02 8.91E-01 1407.98 2.48 5.98E-01 1.44E+OO 1509.19 2.19 8.31E-01 1.28E+OO 1764.49 15.80 1.0BE-01 2.04E-01

+

PB-214 77.11 10.70 3.73E-Ol 8.18E-02 3.79E-Ol 295.21 19.20 1.1 6E- 01 9. 93E-02 351.92 37.20 9.7 0E-02 8.18E-02

+

PA-228 89.95 22. 00 2.58E-01 1.46E-01 2.49E-01 93.35 35.00 4.75E-02

1. 46E-01 105. 00 16.30

-4. 79£-02 2. 77E-01 129. 22 2.97 2. 64E- 01

1. 43E+OO 338.32 5.30 5.79£-01 9. 23E-01 463.00

13. 80 1.52E-01 3. 82E- 01 911. 23 16.70 7.63E-01 5.21E-01

+

AM-241 59.54 36.30 8.20E-02 1.75E-01 1.75E-01

+

CM-243 103.76 23. 00

- 2.98E- 03 1. 12E-01 1.12E-01 228.18 10.60

1. 83E-03 2.29E-01 277.60 14.00 1.58E-02 1.86E-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 perfonn the decay correction

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

Analysis Report for L 1-SUB-LES-FSGS-013-SB SPLIT 02/02/18 - 1453 1/31/2019 8:53:51AM GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Peak Analysis Performed on

L 1-SUB-LES-FSGS-013-SB SPLIT

02/02/18 - 1453

500 ml Marinelli 9.779E+02 grams

Dairyland_NPP

2/2/2018 2:53:00PM

10/17/2018 8:29:52AM

500ml Marinelli

Administrator

HOTLAB

500ml Marinelli

3600.0 seconds

3610.1 seconds

0.28%

3.00

100 - 4096

100-4096

1.000 keV

7/8/2014

5835 PEAK ANALYSIS REPORT 1/31/2019 8:53:42AM Peak Analysis From Channel Peak Analysis To Channel

100

4096 Page I of6

F F

F 1/31/2019 8:53:51AM Page 2 of 6 Analysis Report for L 1-SUB-LES-FSGS-013-SB SPLIT F

F F

02/02/18 -1453 Peak Energy ROI No.

(keV) start 1

238. 66 469 -

2 295. 31 583 -

3 338.42 672 -

4 352.08 697 -

5 583. 45 1162 -

6 609.26 1212 -

7 661.81 1315 -

8 716.8 4 1 430 -

9 911. 49 1817 -

10 968.96 1934 -

11 1 461. 12 2912 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma ROI Peak Net Peak Net Area Continuum end Centroid Area Uncertainty Counts 485 477.79 3. 54E+02 49. 86 6. 25E+02 598 591.08 9. 20E+Ol 32.16 4. 28E+02 683 677. 27 6. 53E+O l 27. 50 2. 66E+02 711 704.59 1. 63E+02 33. 33 2. 82E+02 1174 1167. 24 6.28E+O l 22. 15 1. 20E+02 1226 1218. 86

1. 25E+02 27. 82

1. 45E+02 1330 1323.93 1.57E+02 28.71

1. OOE+02 1437 1433.97 2.16E+O l

11. 4 6 4.80E+Ol 1830 1823.21 4.07E+Ol 16.82 8.63E+Ol 1944 1 938. 14 2. 92E+Ol

15. 34 7.37E+Ol 2931 2922.35 5.19E+ 02 46. 04 9. 65E+OO BACKGROUND SUBTRACT REPORT

1/31/2019 8:53:42AM Peak Analysis Performed on Env. Background File

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Data\\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr.

No.

(keV)

Area Uncertainty

Background

Uncert.

1 238.66 3. 54E+02 49.86 2

295.31 9. 20E+Ol 32.1 6 3

338.42 6. 53E+Ol 27. 50 4

352.08 1.63E+02 33.33 8.36E+Ol 3.72E+Ol 5

583. 45 6. 28E+Ol

22. 1 5 6

609.26

1. 25E+02 27.82 4.12E+Ol 2.42E+Ol 7

661.81 1. 57E+02

28. 71 6. 61E+Ol 2.54E+Ol 8

716.84 2. 16E+Ol

11. 46 9

911. 49 4. 07E+Ol 16.82 1 0 968. 96 2. 92E+Ol 15.34 11 1461.12 5.19E+02 46.04 5.63E+Ol

1. 71E+Ol M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma Subtracted Area 3.54E+02 9.20E+Ol 6.53E+Ol 7.93E+Ol 6.28E+Ol 8.39E+Ol 9.llE+Ol 2. 16E+Ol 4. 07E+Ol 2. 92E+Ol 4. 62E+02 FWHM (keV) 2.61 2.28 2.11 2. 2 0 2.30 2. 45 2. 28

1. 29

1. 71

1. 66 3.04 Subtracted Uncert.

4.99E+Ol 3.22E+Ol 2.75E+Ol 5.00E+Ol 2. 22E+Ol 3.69E+Ol 3.83E+Ol

1. 15E+Ol

1. 68E+Ol

1. 53E+Ol 4.91E+Ol

1/31/2019 8:53:51AM Page 3 of6 Analysis Report for L 1-SUB-LES-FSGS-013-SB SPLIT 02/02/18 - 1453 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)

(pCVgrams)

Uncertainty K-40 0.97 1460.75 10.67 5.15E+OO 6.18E-Ol CS-137 0.99 661.65 85.12 6.40E-02 2.71E-02 PB-212 0.56 77.11 17.50 238.63 44.60 1.87E-01 2.80E-02 BI-214 0.34 609.31 46.30 9.89E-02 4.38E-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 1.35E-01 4.75E-02 351.92 37.20 7.0lE-02 4.43E-02 AC-228 0.63 209.28 4.40 338.32

11. 40 1.82E-01 7.70E-02 794.70 4.60 911. 60 27.70

1. l 6E-01 4.80E-02 964. 60 5.20 969.11 16.60 1.46E-01 7.69E-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

Analysis Report for L 1-SUB-LES-FSGS-013-SB SPLIT 02/02/18 - 1453 Nuclide Name K-40 CS-137 PB-212 BI-214 PB-214 AC-228 Nuclide Id Confidence 0.979

0. 996 0.560 0.349

0. 719 0.631

?

= nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis 1/31/2019 8:53:51AM Wt mean Wt mean Activity Activity (pCi/grams)

Uncertainty 5.lSE+OO 6.lSE-01 6.40E-02 2.71E-02 1.87E-01 2.SOE-02 9.89E-02 4.38E-02

1. OOE-01 3.24E-02 1.37E-01 3.60E-02

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma Page 4 of6 Comments

1/31/2019 8:53:51AM Analysis Report for L 1-SUB-LES-FSGS-013-SB SPLIT 02/02/18 - 1453 F

F Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

5 8

Energy (keV) 583.45 716.84 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma UNIDENTIFIED PEAKS

1/31/2019 8:53:42AM

100

4096 Peak CPS(%)

Peak Size (CPS)

Uncertainty l.74434E-02 6.00669E-03 17.64 26.51 Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Dairyland_NPP\\Library\\HOTLAB.NLB Nuc/lde Energy Yield{%)

Activity NuclldeMDA LlneMDA Name (keV)

(pCilgrams)

(pCi/grams)

+

K-40 1460.75 10.67 5.15E+OO 4.74E-01 4.74E-Ol

+

@ AR-41 1293.64 99.16 1.00E+26 1.00E+26 l.OOE+26

+

C0-60 1173.22 100.00 4.51E-02 4.98E-02 6.0lE-02 1332.49 100.00 3.36E-02 4.98E-02

+

KR-85 513.99 0.43 l.29E+Ol 8.95E+OO 8.95E+OO

+

Y-88 898.04 93.70

-3.56E-02

1. 45E-01 2.13E-01 1836.06 99.20 9.23E-02 l.45E-01

+

NB-94 702.63 100.00

-6.83E-03 3.35E-02 3.35E-02 871.10 100.00

-2.99E-04 3.82E-02

+

I-131 284.30 6.06 4.85E+08 l.29E+08 1.79E+09 364.48

81. 20 2.14E+07 1.29E+08 636.97 7.27

-3.83E+08 1.72E+09

+

CS-134 604.70 97.60

-1.44E-02 5.40E-02 5.40E-02 795.84 85.40 4.07E-02 5.54E-02

+

CS-137 661.65 85.12 6.40E-02 4.68E-02 4.68E-02

+

CE-144 80.12

1. 36

-4.79E-01 4.31E-01 5.43E+OO Page 5 of6 Tolerance Nuclide

1/31/2019 8:53:51AM Page 6 of6 Analysis Report for L 1-SUB-LES-FSGS-013-SB SPLIT 02/02/18 - 1453 Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi!grams)

(pCi/grams)

CE-144 133.51

11. 09

-5.71E-03 4.31E-01 4.31E-01

+

EU-152 121. 78 28.40

-8. llE-03 9.09E-02 9.09E-02 344. 28 26. 60

-3.66E-03 1.1 9E-01 1408.00 20. 74 9.19E-02 l.97E-01

+

EU-154 123.07 40.40

-l.98E-02 6.49E- 02 6.49E-02 723.30 19.70

- 2.23E-02 l.94E-Ol 1274. 51 35. 50

-l.29E-Ol 1.38E-Ol

+

EU-155 86. 54 32. 80

-3.91E-02 1.1 3E-01 1.13E-01 105.31

21. 80

-5.07E-02 l.33E-01

+

BI-214 609.31 4 6. 30 9.89E-02 8.08E- 02 8.08E- 02 1120. 29 15.10 6.63E-02 3. 30E-01 1238.11 5.94 5.97E-01 9. 28E-01 1377.67 4.11

6. llE-01 9.52E-01 1407.98 2.48 7.42E-01 1.59E+OO 1509.19 2.19 7.14E-Ol

1. 22E+OO 1764.49 15. 80 4.08E-02 2. 29E-01

+

PB-214 77.11 10.70 5.0 6E-01 8.65E-02 3. 98E-01 295.21 19.20 l.35E-01 l.26E-01 351. 92 37. 20 7.0lE-02 8.65E-02

+

@ PA-228 89. 95 22.00 l.OOE+26 1.00E+26 l.OOE+26 93. 35 35.00 1.00E+26 1.00E+26 105. 00 16.30 1.00E+26 l.OOE+26 129.22 2. 97 1.00E+26 1.00E+26 338.32 5.30 1.00E+26 1.00E+26 463.00

13. 80 l.OOE+26 l.OOE+26 911.23 16.70

1. OOE+26 l.OOE+26

+

AM-241 59.54 36.30 5.89E-02 1. 96E-01

1. 96E-Ol

+

CM-24 3 103.76 23.00

-l. 30E-02 l.18E-01 l.1 8E- 01 228.1 8 10.60

-2.05E-01 2.35E-01 277.60 14.00

- 5.08E-02

1. 99E-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 L1-010-103 EXCAVATION SURVEY UNIT L1-SUB-LES 46 ATTACHMENT 8 GEL LABORATORIES ANALYTICAL REPORTS

ffl::t11 [ Laboratories LLC

... 1* f,,'- * *1, t{

t-ut1t-<1n*, C::f 2*'-1',

a member of The GEL Group INC

, *.J, s. c, Fiod

,,, -. :, *.J,;

p,.j'* *'.,I 81"1 F.J: -,,. I'-:.

April 17, 20 18 Mr. Jason Q. Spaide La Crosse So I utions S4601 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 for the sample(s) we received on March 22, 2018. This original data report has been prepared and reviewed in accordance with GEL *s standard operating procedures.

Our policy is to provide high quality, personalized analytical services to enable you to meet your analytical needs on time every time. We trust that you will find everything in order and to your satisfaction. If you have any questions, please do not hesitate to call me at (843) 556-8 171, ext. 4453.

Purchase Order: 672583 Enclosures Sincerely, Edith Kent Project Manager

.!~111111111 ~111111111111 111111 II gel.com

age 2 of 27 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-81 71 - 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.

U I Gamma Spectroscopy--Uncertain identification Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the Certificate of Analysis.

The designation ND, if present, appears in the result column when the analyte concentration is not detected above the limit as defined in the 'U' qualifier above.

This data report has been prepared and reviewed in accordance with GEL Laboratories LLC standard operating procedures. Please direct any questions to your Project Manager, Edith Kent.

Reviewed by

GEL LABORATORIES LL 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date:

April 17,2018 Company:

Address:

Contact:

LaCrosseSolutions S4601 State Hwy 35 Genoa, Wisconsin 54632 Mr. Jason Q. Spaide Project:

LACBWR Site Restoration Project Client Sample ID:

Sample ID:

L l-SUB-LES-FSGS-00 I-SB 446394001 Matrix:

Collect Date:

Receive Date:

Collector:

Soil 02-FEB-18 13:45 22-MAR-18 Client Parameter Qualifier Result Uncertainty Zad Gas Flow Proportional Counting

iFPC, Sr90, Solid "Dry Weight Corrected"

trontium-90 U

0.0364 rhe following Prep Methods were performed:

v1ethod Description

)ry Soil Prep Dry Soil Prep GL-RAD-A-02 1

+/-0.0927 The following Analytical Methods were perfom1ed:

\\1ethod Description MDC 0.159 EPA 905.0 Modified/DOE RP501 Rev. I Modified

urrogate/Tracer Recovery Test

,trontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected"

~otes:

RL 0.400 Analyst JXOI

ounting Uncertainty is calculated at the 95% confidence level ( 1.96-sigma).

Column headers are defined as follows:

OF: Dilution Factor DL: Detection Limit MDA: Minimum Detectable Activity MDC: Minimum Detectable Concentration age 3 of 27 Le/LC: Critical Level PF: Prep Factor RL: Reporting Limit SQL: Sample Quantitation Limit Project:

Client ID:

ENRG07001 ENRG070 Units PF DF Analyst Date Time Batch Method pCi/g K SD I 04/02/18 1804 1749761 Date Time Prep Batch 03/22/18 1330 1749454 Analyst Comments Result Nominal Recovery%

Acceptable Limits 93 (25%-125%)

GEL LABORATORIES LL--

2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date:

April 17, 2018 Company:

Address:

Contact:

LaCrosseSolutions S460l State Hwy 35 Genoa, Wisconsin 54632 Mr. Jason Q. Spaide Project:

LACBWR Site Restoration Project Parameter Client Sample ID:

Sample ID:

Matrix:

Collect Date:

Receive Date:

Collector:

L 1-SUB-LES-FSGS-O 12-SB 446394002 Soil 02-FEB-I 8 14:45 22-MAR-18 Client Qualifier Result Uncertainty lad Gas Flow Proportional Counting JFPC, Sr90, Solid "Dry Weight Corrected" MDC RL

irontium-90 U

0.1 15

+/-0.1 I 0

0. 183 0.400 fhe following Prep Methods were performed:

Vlethod Description Analyst

)ry Soil Prep Dry Soil Prep GL-RAD-A-021 JXOI The following Analytical Methods were performed:

\\1ethod Description EPA 905.0 Modified/DOE RP501 Rev. I Modified

,urrogate/Tracer Recovery Test itrontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 1/otes:

ounting Uncertainty is calculated at the 95% confidence level ( 1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor DL: Detection Limit MDA: Minimum Detectable Activity MDC: Minimum Detectable Concentration age 4 of 27 Le/LC: Critical Level PF: Prep Factor R.L: Reporting Limit SQL: Sample Quantitation Limit Project:

Client ID:

ENRG07001 ENRG070 Units PF OF Analyst Date Time Batch Method pCi/g KSDI 04/02/18 1804 1749761 Date Time Prep Batch 03/22/18 1330 1749454 Analyst Comments Result Nominal Recovery%

Acceptable Limits 97.7 (25%-125%)

GEL LABORATORIES LL._

2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date:

Aprjl 17, 2018 Company:

Address:

Contact:

LaCrosseSolutions S460l State Hwy 35 Genoa, Wisconsin 54632 Mr. Jason Q. Spaide Project:

LACBWR Site Restoration Project Client Sample ID:

Sample ID:

Ll-SUB-DRS-FSGS-Wl2-SB 446394003 Matrix:

Collect Date:

Receive Date:

Collector:

Soil 27-FEB-l 8 08:48 22-MAR-18 Client Parameter Qualifier Result Uncertainty lad Gas Flow Proportional Counting

iFPC, Sr90, Solid "Dry Weight Corrected"

,trontium-90 U

-0.0222 rhe following Prep Methods were perfonned:

vtethod Description

)ry Soil Prep Dry Soil Prep GL-RAD-A-021

+/-0.0755 The following Analytical Methods were performed:

Vlethod Description MDC 0.134 EPA 905.0 Modified/DOE RP501 Rev. I Modified

,urrogate/Tracer Recovery Test

,trontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" llotes:

RL 0.400 Analyst JXOI

ounting Uncertainty is calculated at the 95% confidence level ( 1.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor DL: Detection Limit MDA: Minimum Detectable Activity MDC: Minimum Detectable Concentration age 5 of 27 Le/LC: Critical Level PF: Prep Factor RL: Reporting Limit SQL: Sample Quantitation Limit Project:

Client ID:

ENRG07001 ENRG070 Units PF OF Analyst Date Time Batch Method pCi/g KSDI 04/02/ 18 1805 1749761 Date Time Prep Batch 03/22/18 1330 1749454 Analyst Comments Result Nominal Recovery%

Acceptable Limits I 02 (25%-125%)

GEL LABORATORIES LL'-'

2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date:

April 17, 2018 Company:

Address:

Contact:

LaCrosseSolutions S460 I State Hwy 35 Genoa, Wisconsin 54632 Mr. Jason Q. Spaide Project:

LACBWR Site Restoration Project Client Sample ID:

Sample ID:

L 1-SUB-DRS-FSGS-W I 4-SB 446394004 Matrix:

Collect Date:

Receive Date:

Collector:

Soil 27-FEB-I 8 08:31 22-MAR-18 Client Parameter Qualifier Result Uncertainty lad Gas Flow Proportional Counting

]FPC, Sr90, Solid "Dry Weight Corrected" itrontium-90 U

0.103 rhe following Prep Methods were performed:

v1ethod Description

)ry Soil Prep Dry Soil Prep GL-RAD-A-021

+/-0.0922 The following Analytical Methods were perforn1ed:

v1ethod Description MDC

0. 153 EPA 905.0 Modified/DOE RP501 Rev. I Modified

urrogate/Tracer Recovery Test

irontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected"

\\Jotes:

RL 0.400 Analyst JXOI

ounting Uncertainty is calculated at the 95% confidence level ( I.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor DL: Detection Limit MDA: Minimum Detectable Activity MDC: Minimum Detectable Concentration age 6 of 27 Le/LC: Critical Level PF: Prep Factor RL: Reporting Limit SQL: Sample Quantitation Limit Project:

Client ID:

ENRG07001 ENRG070 Units PF DF Analyst Date Time Batch Method pCi/g KSDI 04/02/18 1805 1749761 Date Time Prep Batch 03/22/ 18 1330 1749454 Analyst Comments Result Nominal Recovery%

Acceptable Limits 95.3 (25%-125%)

GEL LA BORA TORIES LL" 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Company:

Address:

Contact:

Project:

Client Sample ID:

Sample ID:

Matrix:

Collect Date:

Receive Date:

Collector:

LaCrosseSolutions S460 I State Hwy 35 Genoa, Wisconsin 54632 Mr. Jason Q. Spaide LACBWR Site Restoration Project L2-SUB-I 03-AJGS-002-SB 446394005 Soil 23-FEB-18 14:03 22-MAR-18 Client Parameter Qualifier Result Uncertainty MDC RL lad Alpha Spec Analysis

\\ lphaspec Isotopic Am24 I Am243, Cm243/244, Solid "Dry Weight Corrected"

\\mcricium-241 U

-0.0132

+/-0.0259 0.0722 0.400

\\mcricium-243 U

0.00638

+/-0.0667

0. 139 0.400

urium-243/244 U

0.00

+/-0.0161 0.0239 0.400

\\lphaspec Np, Solid "Dry Weight Corrected"

~cptunium-237 U

-0.000991

+/-0.00238 0.00548 0.010

\\lphaspec Pu238, 239/240, Solid "Ory Weight Corrected"

'lutonium-238 U

0.0149

+/-0.0293 0.0406 0.400

'lutonium-239/240 U

0.0193

+/-0.0341 0.0517 0.400 jquid Scint Pu24 I, Solid "Dry Weight Corrected"

'lutonium-241 U

-0.703

+/-2.45 4.19 5.00 lad Gamma Spec Analysis Jamma Ni59, Solid "Ory Weight Corrected"

~ickel-59 U

-0.244

+/-1.24 2.43 5.00 Jamma, Cs 137, Co60, Nb94, Eu 152, Eu 154, Eul55 "Dry Weight Corrected"

esium-137 UI 0.00

+/-0.0497 0.0593 1.00

obalt-60 U

-0.00529

+/-0.0311 0.067

uropium-152 U

-0.0 117

+/-0.0719 0.125

uropium-154 U

0.0772

+/-0.105 0.263

uropium-1 55 U

-0.0189

+/-0.0641 0.128 fobium-94 U

-0.0208

+/-0.0256 0.0432 lad Gas Flow Proportional Counting JFPC, Sr90, Solid "Dry Weight Corrected" itrontium-90 U

0.00765

+/-0.0638 0.112 0.400 lad Liquid Scintillation Analysis

.SC, Tritium Distillation, Solid "As Received" "ritium U

-0.61

+/-3.32 5.89 10.0 jquid Sc int C 14, Solid "As Received"

arbon-14 U

0.0595

+/-2.30 3.95 5.00

-iquid Scint Tc99, Solid "As Received"

echnetium-99 U

-0.162

+/-0.818 1.42 2.00

-iquid Scint Fe55, Solid "Dry Weight Corrected" ron-55 U

6. 70

+/-4.9 1 7.15 10.0

-iquid Scint Ni63, Solid "Dry Weight Corrected" age 7 of 27 Project:

Client ID:

Units pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g PF Report Date:

April 17, 2018 ENRG07001 ENRG070 OF Analyst Date Time Batch Method HAKB 03/27/18 0906 1749552 HAKB 03/27/18 1346 1749553 2

HAKB 03/27/18 0906 1749554 3

HAKB 03/28/ 18 1012 1749555 4

TXJ I 04/05/18 1346 1751598 5

MXRI 03/27/18 0857 1749466 6

KSDI 04/02/18 1805 1749761 7

MXH8 03/30/18 1228 1750348 BXM4 03/29/18 2124 1750468 CXS7 04/15/18 0915 1753302 TXJ I 04/12/18 0954 1751 579 8

9 10 II

GEL LABORATORIES LL'-'

2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date:

A pri I 17, 20 I 8 Company:

Address:

Contact:

Project:

LaCrosseSolutions S460 l State Hwy 35 Genoa, Wisconsin 54632 Mr. Jason Q. Spaide LACBWR Site Restoration Project Client Sample ID: L2-SUB-I 03-AJGS-002-SB 446394005 Sample ID:

Parameter Qualifier Result Uncertainty MDC lad Liquid Scintillation Analysis jquid Scint Ni63, Solid "Dry Weight Corrected"

~ickel-63 U

-1.38

+/-1.70 3.08 fhe following Prep Methods were performed:

v1ethod Description

)ry Soil Prep Dry Soil Prep GL-RAD-A-021 The following Analytical Methods were perfonned:

\\1ethod Description 0

I 2

DOE EML HASL-300, Am-05-RC Modified ASTM C 1475-00 Modified DOE EML 1-IASL-300, Pu-11-RC Modified DOE EML HASL-300, Pu-I I-RC Modified DOE RESL Ni-I DOE HASL 300, 4.5.2.3/Ga-Ol-R EPA 905.0 Modified/DOE RP501 Rev. I Modified EPA 906.0 Modified EPA EERF C-01 Modified DOE EML HASL-300. Tc-02-RC Modified DOE RESL Fe-I, Modified DOE RESL Ni-I, Modified

urrogate/Tracer Recovery Test

\\mericium-243 Tracer

urium-243/244 Tracer

\\mericium-243 Tracer

'lutonium-242 Tracer

~ickel Carrier

,trontium Carrier "echnetium-99111 Tracer ron-59 Tracer

~ickel Carrier 1/otes:

age 8 of 27 Alphaspec Isotopic Am24 I Am243, Cm243/244, Solid "Dry Weight Corrected" Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Alphaspec Np, Solid "Dry Weight Corrected" Alphaspec Pu238. 239/240, Solid "Dry Weight Corrected" Liquid Scint Pu241, Solid "Dry Weight Corrected" Gamma Ni59, Solid "Dry Weight Corrected" GFPC, Sr90, Solid "Dry Weight Corrected" Liquid Sein\\ Tc99. Solid "As Received" Liquid Scint Fe55, Solid "Dry Weight Corrected" Liquid Scint Ni63, Solid "Dry Weight Corrected" RL 5.00 Analyst JXOI Project:

Client ID:

ENRG07001 ENRG070 Units PF OF Analyst Date Time Batch Method pCi/g TXJI 04/07/18 0535 1751578 12 Date Time Prep Batch 03/22/18 1330 1749454 Analyst Comments Result Nominal Recovery%

Acceptable Limits 65.8 (15%-125%)

23.9 (15%-125%)

99 (15%-125%)

69.2 (15%-125%)

IOI (25%-125%)

102 (25%-125%)

89.7 (15%-125%)

73 (15%-125%)

78.5 (25%-1 25%)

GEL LABORATORIES Llv 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date:

April 17, 2018 Parameter Company:

Address:

Contact:

Project:

Client Sample 10:

Sample ID:

La Crosse Solutions S460 I State Hwy 35 Genoa, Wisconsin 54632 Mr. Jason Q. Spaide LACBWR Site Restoration Project L2-SUB-I 03-AJGS-002-SB 446394005 Qualifier Result Uncertainty MDC R.L

ounting Uncertainty is calculated at the 95% confidence level ( I.96-sigma).

Column headers are defined as follows:

DF: Dilution Factor DL: Detection Limit MDA: Minimum Detectable Activity MDC: Minimum Detectable Concentration age 9 of 27 Le/LC: Critical Level PF: Prep Factor RL: Reporting Limit SQL: Sample Quantitation Limit Project:

Client ID:

ENRG07001 ENRG070 Units PF DF Analyst Date Time Batch Method

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Reoort Date: April 17, 2018 LaCrosseSolutions Page 1 of S4601 State Hwy 35 Genoa, Wisconsin

Contact:

Mr. Jason Q. Spaide Workorder:

446394 Parmname NOM Sam~le Qual QC Units RPO%

REC%

Range Anlst Date Time Rad Alpha Spec 3atch 1749552 QC I203994922 446394005 DUP Americium-24 I u

-0.0132 u

-0.0035 1 pCi/g NIA NIAHAKB 03/27118 09:0 Uncertainty

+/-0.0259

+l-0.0242 Americium-243 u

0.00638 u 0.0305 pCilg NIA NIA Uncertainty

+l-0.0667

+/-0.0396 Curium-243/244 u

0.00 u

-0.0104 pCi/g NIA NIA Uncertainty

+/-0.0 I 6 I

+/-0.0348 QC 1203994923 LCS Americium-241 1.93 1.92 pCi/g 99.7 (75%- 125%)

03127118 09:0 Uncertainty

+/-0.210 Americium-243 u

0.0107 pCi/g (75%-125%)

Uncertainty

+l-0.02 I Curium-2431244 2.41 2.18 pCilg 90.6 (75%-125%)

Uncertainty

+l-0.222 QC120399492 J MB Americium-241 u

-0.00837 pCilg 03/27/ 18 09:0 Uncertainty

+/-0.0286 Americium-243 u

-0.00824 pCilg Uncertainty

+/-0.0156 Curium-2431244 u

0.0056 pCi/g Uncertainty

+l-0.021 3atch 1749553 QC 1203994925 446394005 DUP Neptunium-237 u

-0.000991 u

-0.00 I 03 pCi/g NIA N/AHAKB 03/27/18 13:4 Uncertainty

+l-0.00238

+l-0.00201 QC l 203994926 LCS Neptunium-237 1.48 1.67 pCi/g 113 (75%-125%)

03127/ 18 13:4 Uncertainty

+l-0.0554 QC 1203994924 MB Neptunium-237 u

0.00128 pCilg 03127/18 13:4 Uncertainty

+/-0.00307 age 10 of 27

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summarl'.

Workordcr:

446394 Page 2 of Parmnamc NOM Sam~le Qual QC Units RPO%

REC%

Range Anlst Date Time Rad Alpha Spec 3atch 1749554 QC 1203994928 446394005 DUP Plutonium-238 u

0.0 149 u 0.0153 pCilg NIA NIA IIAKB 03127118 09:0 Uncertain!)

+l-0.0293

+l-0.0271 Plutonium-2391240 u

0.0193 u

-0.00484 pCilg NIA NIA Uncertain!)

+l-0.0341

+l-0.0 146 QC1203994929 LCS Plutonium-238 u

0.0177 pCilg 03127118 09:0 Uncertain!)

+l-0.0314 Plutonium-2391240 1.94 1.95 pCi/g 101 (75%-125%)

Uncertain!)

+l-0.242 QC 1203994927 MB Plutonium-238 u

-0.00134 pCilg 03127118 09:0 Uncertainty

+l-0.031 Plutonium-2391240 u

0.000335 pCilg Uncertainty

+l-0.0248 3atch 1749555 QCl203994931 446394005 DUP Plutonium-241 u

-0.703 u 0.6 13 pCi/g NIA NIAHAKB 03128118 14:2 Uncertainty

+l-2.45

+l-2.2 1 QC 1203994932 LCS Plutonium-241 69.5 73.9 pCilg 106 (75%- 125%)

03128/18 16:2 Uncertain!)

+l-3.53 QC 1203994930 MB Plutonium-241 u

0.201 pCi/g 03128/18 12: I Uncertainty

+l-2.47 Rad Gamma Spec 3atch 1749466 QC1203994728 446394005 DUP Cesium-137 UI 0.00 u 0.000751 pCi/g NIA NIAMXR I 03128118 08:5 Uncertainty

+l-0.0497

+l-0.0237 Cobalt-60 u

-0.00529 u 0.000415 pCi/g NIA NIA Uncertainty

+l-0.03 11

+l-0.0206 Europium-152 u

-0.01 17 u

-0.00698 pCilg NIA NIA Uncertain!)

+l-0.0719

+l-0.0584 age 11 of 27

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summar:y Workorder:

446394 Page 3 of Parmname NOM Samele Qual QC Units RPO%

REC%

Range Anlst Date Time Rad Gamma Spec 3atch 1749466 Europium-154 u

0.0772 u 0.0134 pCilg NIA NIAMXRI 03/28/18 08:5 Uncertainty

+l-0. 105

+l-0.0852 Europium-155 u

-0.0189 u 0.0436 pCilg NIA NIA Uncertainty

+l-0.064 1

+l-0.057 Niobium-94 u

-0.0208 u

-0.00613 pCilg NIA NIA Uncertainty

+l-0.0256

+l-0.0242 QC 1203994 729 LCS Americium-24 1 488 570 pCi/g 117 (75%- 125%)

03128/18 09:2 Uncertainty

+l-14.9 Cesium-137 173 169 pCilg 97.4 (75%-1 25%)

Uncertainty

+l-3.33 Cobalt-60 132 130 pCilg 98.2 (75%-125%)

Uncertainty

+l-3.47 Europium-152 u

1.53 pCi/g Uncertainty

+l-1.41 Europium-154 u

-0.542 pCi/g Uncertainly

+l-1.02 Europium-155 u

0.586 pCilg Unce11ainty

+l-l.36 Niobium-94 u

-0.00958 pCilg Uncertainty

+l-0.436 QC1203994727 MB Cesium-137 u

-0.005 12 pCilg 03127/18 08:5 Uncertainty

+l-0.01 17 Cobalt-60 u

-0.00268 pCilg Uncertainty

+l-0.020 Europium-152 u

-0.011 9 pCilg Uncertainty

+l-0.035 Europium-154 u

-0.00315 pCilg Uncertainty

+l-0.0481 Europium-155 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 Workorder:

446394 QC Summarl:

Page 4 of Parm name NOM Sample Qual QC Units RPO%

REC%

Range Anlst Date Time Rad Gamma Sper 3atch 1749466 Niobium-94 u

0.00616 pCi/g MXRI 03127/18 08:5 Uncertainty

+/-0.0189 3atch 1751598 QC 1203999565 446394005 DUP Nickel-59 u

-0.244 u

-0.487 pCi/g NIA NIA TX.JI 04/05118 14:5 Uncertainty

+/-1.24

+l-0.632 QC 1203999566 LCS Nickel-59 94.2 80.5 pCilg 85.5 (75%-125%)

04/05/18 I 4:5 Uncertainty

+/-6.36 QC 1203999564 MB Nickel-59 u

-0.0478 pCi/g 04/05/18 13:4 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/ 18 18:0 Uncertainty

+/-0.0638

+/-0.113 QC 1203995446 LCS Strontium-90 20.6 22.5 pCilg 109 (75%-125%)

04/02/ I 8 I 6:5 Unce11ainty

+l-1.23 QC 1203995444 MB Strontium-90 u

0.0166 pCi/g 04/02/18 18:0 Uncertainty

+/-0.0585 Rad Liquid Scintillation 3atch 1750348 QC 1203996820 446394005 DUP Tritium u

-0.61 u 0.312 pCi/g NIA N/AMXH8 03130/18 I 4: I Uncertainty

+l-3.32

+l-3.67 QC 1203996822 LCS Tritium 58.0 48.4 pCilg 83.5 (75%-125%)

03/31/18 07:5 Uncertainty

+l-9.46 QC 1203996819 MB Tritium u

0.765 pCi/g 03/30118 13:2 Uncertainly

+/-3.14 age 13 of 27

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Workorder:

446394 QC Summar!

Page 5 of Parmname NOM Same le Qual QC Units RPD%

REC%

Range Anlst Date Time Rad Liquid Scintillation 3atch 1750348 QC 120399682 I 446394005 MS Tritium 126 u

-0.61 I09 pCilg 86.4 (75%-125%) MXI-18 03130118 15:0 Uncertainty

+l-3.32

+l-11.3 3atch 1750468 QCJ203997027 446394005 DUP Carbon-14 u

0.0595 u

-0.396 pCilg NIA NIABXM4 03129/18 22:3 Uncertainty

+l-2.30

+l-2.24 QC 1203997029 LCS Carbon-14 135 122 pCilg 90.3 (75%-1 25%)

03129/18 23: 5 Uncertainty

+l-4.52 QC 1203997026 MB Carbon-1 4 u

-0.1 09 pCi/g 03129118 22:0 Uncertainty

+l-2.24 QC 1203997028 446394005 MS Carbon-1 4 272 u

0.0595 257 pCi/g 94.4 (75%-125%)

03129118 23: I Uncertainty

+l-2.30

+l-9. 15 3atch 1751578 QC I 203999522 446394005 DUP Nickel-63 u

-1.38 u

-0.199 pCi/g NIA NIA TXJ I 04107118 06:0 Uncertainty

+l-1.70

+l-1.92 QC I 203999523 LCS Nickel-63 85.3 88.7 pCilg 104 (75%-1 25%)

04107118 06:2 Uncertainty

+l-4.13 QC 1203999521 MB Nickel-63 u

-0. 145 pCilg 04107118 05:5 Uncertainty

+l-1.64 3atch 1751579 QC1203999525 446394005 DUP lron-55 u

6.70 u

-0.19 1 pCi/g NIA NIA TXJ I 04110118 00:2 Uncertainty

+l-4.91

+l-2.21 QC 1203999526 LCS lron-55 116

90. 1 pCi/g 77.9 (75%-125%)

04/10118 0 I :2 Uncertainty

+l-4. 16 age 14 of 27

GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Workorder:

QC Summary 446394 Parmname NOM Sample Qual Rad Liquid Scintillation 3atch 1751579 QC 1203999524 MB lron-55 u

Uncertainty 3atch 1753302 QCl204003340 446394005 DUP Technetium-99 u

-0.162 u Uncertainty

+/-0.818 QC120400334 1 LCS Technetium-99 31.7 Uncertainty QC 1204003339 MB Technetium-99 u

Uncertainty Notes:

Counting Uncertainty is calculated at the 95% confidence level ( 1.96-sigma).

The Qualifiers in this report are defined as follows:

BD FA H

Analyte is a Tracer compound Result is less than value reported Result is greater than value reported Results are either below the MDC or tracer recovery is low Failed analysis.

Analytical holding time was exceeded Value is estimated QC

-0.888

+/-2.03

-0.351

+/-0.766 24.6

+/-1.26

-0.265

+/-0.678 Units pCi/g pCi/g pCi/g pCi/g K

Analyte present. Reported value may be biased high. Actual value is expected to be lower.

L Analyte present. Repo11ed 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.

N l Sec 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 r~jected U

Analyte was analyzed for. but not detected above the MDL. MDA. MDC or LOD.

UI Gamma Spectroscopy--Uncertain identification age 15 of 27 Page 6 of RPO%

REC%

Range Anlst Date Time TXJI 04/09/ 18 23:2 NIA NIA CXS7 04/15/18 10:0 77.7 (75%-125%)

04/15/18 10:3 04/ 15/ 18 09:4

GEL LABO RA TORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Workorder:

446394 QC Summary Parm name NOM Sample Qual QC Vnits RPO%

REC%

Range Anlst UJ UL X

y h

Gamma Spectroscopy--Uncertain identification Not considered detected. The associated number is the reported concentration. which may be inaccurate due to a low bias.

Consult Case Narrative. Data Summary package. or Project Manager concerning this qualifier Other specific qualifiers were required to properly define the results. Consult case narrative.

RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL. Qualifier Not Applicable for Radiochemistry.

Preparation or preservation holding time was exceeded Page 7 of Date Time NIA indicates that spike recovery limits do not apply when sample concentration exceeds spike cone. by a factor of 4 or more or %RPD not applicable.

/\\ The Relative Percent Difference (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptance criteria when the sample is greater than live 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 SOIL T results. the values listed are the measured amounts, not final concentrations.

Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the QC Summary.

age 16 of27

Radiochemistry Technical Case Narrative LaCrosseSolutions, LLC (ENRG)

SOG #: 446394 Product: Alphaspec Isotopic Am241 Am243, Cm243/244, Solid Analvtical Method: DOE EML HASL-300, Am-05-RC Modified Analytical Procedure: GL-RAD-A-011 REV# 26 Analytical Batch: 1749552 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-02 I REV# 22 Preparation Batch: I 749454 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID#

446394005 1203994921 1203994922 1203994923 Client Sam pie Identification L2-SUB-l 03-AJGS-002-SB Method Blank (MB) 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP)

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 1203994923 (LCS) was perfonned to fully separate counts in Regions of Interest which would have been biased.

Product: Alphaspec Np, Solid Analytical Method: ASTM C 1475-00 Modified Analytical Procedure: GL-RAD-A-032 REY# 21 Analytical Batch: I 749553 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-02 I REV# 22 Preparation Batch: 1749454 PO Box 30712 Charleston, SC 29417 2040Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gel.com

The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID#

446394005 1203994924 1203994925 1203994926 Client Sample Identification L2-SUB-J 03-AJGS-002-SB Method Blank (MB) 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP)

Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on a "di)' 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-I I-RC Modified Analytical Procedure: GL-RAD-A-011 REY# 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#

446394005 1203994927 1203994928 1203994929 Client Sample Identification L2-SUB-l 03-AJGS-002-SB Method Blank (MB) 446394005(L2-SUB-l 03-AJGS-002-SB) Sample Duplicate (DUP)

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: 1749454 PO Box 30712 Char1eston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.geJ.com

The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID#

446394001 446394002 446394003 446394004 446394005 Client Sample Identification L I-SUB-LES-FSGS-00 I-SB L 1-SUB-LES-FSGS-O 12-SB LJ-SUB-DRS-FSGS-W I 2-SB L I-SUB-DRS-FSGS-Wl4-SB 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, Eul55 Analytical Method: DOE HASL 300, 4.5.2.3/Ga-O 1-R Analytical Procedure: GL-RAD-A-01 3 REV# 27 Analytical Batch: 1749466 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1749454 The fo llowing samples were analyzed using the above methods and analytical procedure(s).

Client Sam pie Identification L2-SUB-I 03-AJGS-002-SB Method Blank (MB)

GEL Sample ID#

446394005 1203994727 1203994728 1203994729 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP)

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 UI Reason Results are considered a false positive due to no valid peak.

Analyte Sample Client Sample Cesium-1 37 446394005 L2-SUB-I 03-AJGS-002-SB a~f.91.M~ortes u.c PO Box 30712 Charleston, 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 Analytical Procedure: GL-RAD-A-022 REV# 18 Analytical Batch: 1751598 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-02 1 REV# 22 Preparation Batch: 1749454 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID#

446394005 1203999564 1203999565 1203999566 Client Sam pie Jdentification L2-SUB-I 03-AJGS-002-SB Method Blank (MB) 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP)

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 JD#

446394001 446394002 446394003 446394004 446394005 1203995444 1203995445 1203995446 Client Sample Identification L I-SUB-LES-FSGS-001-SB L I-SUB-LES-FSGS-012-SB L 1-SUB-DRS-FSGS-W 12-SB Ll-SUB-DRS-FSGS-W 14-SB L2-SUB-I 03-AJGS-002-SB Method Blank (MB) 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP)

Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on a "dry weight" basis.

a~~ortesuc PO Box 30712 Charleston, SC 29417 2040 Savage Roacl Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.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 EM L 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 Sample ID#

446394005 1203994930 1203994931 1203994932 Client Sample Identification L2-SUB-I 03-AJGS-002-SB Method Blank (MB) 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP)

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 Analvtical Procedure: GL-RAD-A-002 REY# 22 Analytical Batch: 1750348 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID#

446394005 1203996819 1203996820 1203996821 1203996822 Client Sam pie Identification L2-SUB-I 03-AJGS-002-SB Method Blank (MB) 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP) 446394005(L2-SUB-I 03-AJGS-002-SB) Matrix Spike (MS)

Laboratory Control Sample (LCS)

The samples in this SDG were analyzed on an "as received" basis.

a~ ~~rtes u.c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.llfl.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-I 03-AJGS-002-SBMS), aliquot was reduced to conserve sample volume.

Product: Liquid Scint C14, Solid Analytical Method: EPA EERF C-0 I 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 ID#

446394005 1203997026 1203997027 1203997028 1203997029 Client Sample Identification L2-SUB-103-AJGS-002-SB Method Blank (MB) 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP) 446394005(L2-SUB-I 03-AJGS-002-SB) Matrix Spike (MS)

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-I, Modified PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.oe1.com

Analytical Procedure: GL-RAD-A-022 REV# 18 Analytical Batch: 175 1578 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1749454 The fo llowing samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID#

446394005 120399952 1 1203999522 1203999523 Client Sample Identification L2-SUB-I 03-AJGS-002-SB Method Blank (MB) 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP)

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. A II 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 Analvtical Method: DOE RESL Fe-I, Modified Analytical Procedure: GL-RAD-A-040 REV# 13 Analytical Batch: 175 1579 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#

446394005 1203999524 1203999525 1203999526 Client Sample Identification L2-SUB-I 03-AJGS-002-SB Method Blank (MB) 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP)

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 Char1eston, SC 29417 2040 savage Road CharleSIX>n, SC 29407 P 843,556.8171 F 843.766.1178 www.gel.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 the above methods and analytical procedure(s).

GEL Sample ID#

446394005 1204003339 1204003340 120400334 1 Client Sample Identification L2-SUB-I 03-AJGS-002-SB Method Blank (MB) 446394005(L2-SUB-I 03-AJGS-002-SB) Sample Duplicate (DUP)

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 Box 30712 Char1eston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com

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Charleston, SC 29407

@C Number <1l:

Chain of Custody and Analytical Request L/0 3 9 C Phone: (843) 556-8171 r:&Number:

fo, JS-8"3 GEL Work Order Number:

GEL Project Manager:

Fax: (843) 766-1178 C!Thnl Name:

Le., Cro~.<::. p

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Phone # /,...0%

{,-, f-9 '-f;) Sy Sample Analysis Requested <~l (Fill in the number of containers for each test)

Project/Sile Name: L-ftCt?.wR. - Gevtoo

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Chain of Custody Signatures TAT Requested: Normal: _;(i_ Rush:

Specify:

(Subject to Surcharge)

Relinquished By (Signed)

Date Time Received by (signed)

Date Time F:ix Results: f l Y cs

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Addi1io11al Remarks:

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For Lab Receiving Use 011~v: C11s1ody Seal Intact? [ ) Yes

[) No Cnoler Temp:

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> For sample shipping and delivery details, see Sample Receipt & Reviewfonn (SRR.)

Sample Collection Time Zone: [ ] Eastern l J Pacific MCentral [) Mountain

[ ) Other:

I.) Ch,in of Custody Number ~ Client Delennin<d 2.) QC Codes: N ~ Nonn*I Sample, TB

Trip 81,nk. FO = Field Duplicate, f.B ~ Equipment Blank. l\\lS ~ M,tri., Spike Sample. i\\lSD ~ M:11rix Spike Duplicalc Sample. G " Gr.1b. C ~ Compo.,ite

).) Field Filtered: For liquid matrices. indicore with n

Y - for yes the sa,nple was field fihcrcd or* N - for i;amplc was not field fihcred.

4.) Matrix Codes: DW=Drinking \\\\'a1er. CW-Groundwater. SW-Surface Water. WW~WaS1c Waler. \\Vn\\V01cr. ML~Misc liquid. SO* Soil. SD~Scdiincn1, SL-Sludge. ss, s.,1it1 Waste, 0 *011, F~Filtcr. P-Wipc. U~Urinc. F~fecal. i-;s Nasal S.) Sample Analysis Requcsrcd: Anal)1ie:il method requested (1.c. 8260B, 60lOBn470A} and number of containers pro\\'idcd fo, each (i.e. 8]~08 - 3. 60/081i47nA - I).

6.) J>r\\!scJ'\\*ati\\l'C T)*pt-: HA

Hydrochloric Acid. NI = Nitric ;\\ cid, Sff

Sodium Hydroxide, SA ~ Sulfuric Acid. AA = Ascorbic Acitl, IIX

Jlc."tanc, ST =" Sodium Thiosulfo1i::. If no prc;,;crv:uivc i~ added -:w kave field blank 7.) Are there any known or possible hazards I Characteristic Hazards I

!Listed Waste Other Please provitld any additional details associated with 1hese samples?

FL= Flammable/lgmtable L'\\\\= Listed Waste OT~ Other / Unknown below regarding hariJlling,llnd!or iJisposal CO = Corrosive (F.K,P and U-listed wastes.)

(i.e.: High/low pH. asbestos, beryllium, irritants, other concerns. c(i.e,: Origi'n of sttmple(s), type RCRA Metals I

RE = Reactive Waste code(s):

misc. health hazard.~. etc.)

of site collected from. odd matri~, ere./

As= Arsenic Hg= Mercury

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Description:==

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Ba =Barium Si!= Selenium ITSCA Rc2ulated I

Cd=Cadmium Ag= Silwr P(.;B = Polychlonnated

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SAMPLE RECEIPT & REVIEW FORM Client:

Carrier and-Tracking Number Suspected Bamrd [nfonnaUon Shipped as a DOT Hazardous?

COC/Samples m.m:ed or classified as radioactive?

ls package. COC, and/or Samples mazkcd HAZ?

Sample Receipt Criteria 1 Shipping containers received intact and scaled?

2 Chain of custody documents included with shipment?

3 Samples requiring cold preservation within (0.s 6 deg. C)?*

4 Daily check performed and passed on IR temperature gun?

S Sample containers intact and scaled?

6 Samples requiring chemical preservation at proper pH?

7 Do any samples require Volatile Analysis?

8 Samples received within holding time?

9 Sample ID's on COC match ID's on bottles?

10 ~n*::~!~ on COC match date & time 11 Number of containers received match number indicated on COC?

12 Are sample containers identifiable as GEL rovidcd?

13 COC fonn is properly signed in relinquished/received sections?

Comments (Use Continuation Form if needed):

age 26 of 27

.;C,;:irck Appticable:

FedEit Express ~

UPS Field Services Courier Other 77£r:/ 17-'1~ 3cZ~o r;

0

If Net Counts> l OOcpm on samples not m:irked "111dioactivc*, contact the Radiation Safety Group for further Z investigation.

Hazard Class Shipped:

UN#:

Maximum Net Counts Observed* (Observed Counts* Area Background Counts): _..,..,....__CPM / mR/Ur Onssltled ns: Rad 1 Rad 2 Rad 3 If yes, select Hazards below, and contact the GEL Safety Group.

PCB's Flammable Foreign Soil RCRA Asbestos Beryllium Other:

Comments/QuaHIJers (Rcqu.ln!d for Non-Confomdng Items)

Circle Applicable:

Sea.ls bmlcen Damaged contoiner Leoking container Other (describe)

Preservation Method: Wet lee Ice Pocks Dry ice on Other.

o11 tempcr.uurcs arc recorded in Celsius Circle AppliCllble: Seals broken Damoged container Leaking contoiner Other (describe)

Sample !D's and ContainCJS Affected:

If Yes, Are Encores or Soil Kits present? Yes_ No_ (Ifyes, take to VOA Freezer)

Do VOA vials contain acid preservation? Yes

. No_ NIA, (If unknown. select No)

VOA vials free ofheadspace? Yes No_ NIA Sample !D's and containers affected:

!D's and tests affected:

Sample ID'5 and containers affcct.ed:

Sample ID's affected:

Sample !D's affected:

List of current GEL Certifications as of 17 April 2018 State Certification Alaska 17- 018 Arkansas 88- 0651 CLIA 4200904046 California 2940 Colorado SC00012 Connecticut PH- 0169 Delaware SCOOOl2 OoD ELAP/ ISO 17025 A2LA 2567.01 Florida NELAP E87 156 Foreign Soils Permit P330- 15-00283,P330 00253 Georgia SC00012 Georgia SOWA 967 Hawaii SC000 12 Idaho Chemistry SC00012 Idaho Radiochemistry SCOOOl2 Illinois NELAP 200029 Indiana C-SC- 01 Kansas NELAP E-10332 Kentucky SOWA 90129 Kentucky Wastewater 90129 Louisiana NELAP 03046 (AJ33904)

Louisiana SOWA LAl8001 I Maryland 270 Massachusetts M-SC012 Michigan 9976 Mississippi SCOOOl2 Nebraska NE-OS 13 Nevada SC000122018-I New Hampshire NELAP 205415 New Jersey NELAP SC002 New Mexico SC00012 New York NELAP 11501 North Carolina 233 North Carolina SOWA 45709 North Dakota R-158 Oklahoma 9904 Pennsylvania NELAP 68- 00485 Puerto Rico SC00012 S. Carolina Radiochem 10120002 South Carolina Chemistry 10120001 Tennessee TN 02934 Texas NELAP T I04704235 13 Utah NELAP SC000122018-26 Vern10nt VT87156 Virginia NELAP 460202 Washington C780 West Virginia 997404 age 27 of 27

ML19261A338

Contents

Text

SUMMARY

SUMMARY

Background

Background

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Background

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Background

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Background

Background

Background

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Dear Mr. Spaide:

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ML19261A338

Text

SUMMARY

SUMMARY

Background

Background

Background

Background

Background

Background

Background

Background

Background

Background

Background

Background

Background

Background

Background

Background

Background

Background

Background

Background

Dear Mr. Spaide:

Contact:

Contact:

Contact:

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