ML19261A332

Boiling Water Reactor Final Status Survey Release Record Reactor Building Basement Survey Unit B1-010-001

ML19261A332
Person / Time
Site:	La Crosse  File:Dairyland Power Cooperative icon.png
Issue date:	08/15/2019
From:	Uz M LaCrosseSolutions
To:	Office of Nuclear Material Safety and Safeguards
References
LC-2019-0040
Download: ML19261A332 (402)

Text

LA CROSSE BOILING WATER REACTOR FINAL STATUS SURVEY RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 PREPARED BY / DATE: 8/15/19 M. Uz, Survey Design Specialist REVIEWED BY / DATE: 8/15/19 R. Yetter, Director, Radiolo Radiological Site Closure REVIEWED BY / DATE:

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

8/28/19 S.

S Zoller, Zoller FSS Manager 1

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

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

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

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

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

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

6. SURVEY IMPLEMENTATION ...................................................................................................................... 19

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

8. QUALITY CONTROL...................................................................................................................................... 24

9. INVESTIGATIONS AND RESULTS .............................................................................................................. 24

10. REMEDIATION AND RESULTS ................................................................................................................... 24

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

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

13. ANOMALIES..................................................................................................................................................... 25

14. CONCLUSION .................................................................................................................................................. 26

15. REFERENCES................................................................................................................................................... 26

16. ATTACHMENTS .............................................................................................................................................. 27 ATTACHMENT 1 - FIGURES AND MAPS ......................................................................................................... 28 ATTACHMENT 2 - ISOCS GEOMETRIES.......................................................................................................... 32 ATTACHMENT 3 - SIGN TEST............................................................................................................................ 39 ATTACHMENT 4 - QUALITY CONTROL ASSESSMENT................................................................................ 41 ATTACHMENT 5 - GRAPHICAL PRESENTATIONS........................................................................................ 43 ATTACHMENT 6 - MEASUREMENT ANALYTICAL REPORTS .................................................................... 47 2

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 LIST OF TABLES Table 3 Reactor Building Basement Continuing Characterization Concrete Core Analysis Summary - On-site.......................................................................................................................................................................... 6 Table 3 Reactor Building Basement Continuing Characterization Concrete Core Analysis Summary - Off-site.......................................................................................................................................................................... 8 Table 4 Reactor Building Basement Dose Significant Radionuclides and Mixture........................................ 11 Table 4 Reactor Building Basement Base Case DCGLs ................................................................................... 12 Table 4 Reactor Building Basement Operational DCGLs ................................................................................ 12 Table 5 Reactor Building Basement Surrogate Ratio ....................................................................................... 13 Table 5 Action Levels for Survey Unit B1-010-001 ........................................................................................... 14 Table 5 Number of ISOCS Measurements based on Areal Coverage ............................................................. 15 Table 5 Adjusted Minimum Number of ISOCS Measurements ...................................................................... 16 Table 5 Investigation Levels................................................................................................................................. 17 Table 5 Synopsis of Survey Design ...................................................................................................................... 18 Table 7 Summary of Systematic, Judgmental, and QC Measurements .......................................................... 22 Table 7 Summary of ISOCS Systematic Measurement Statistical Quantities ................................................ 22 Table 7 Summary of ISOCS Judgmental Measurements ................................................................................. 23 Table 7 Summary of Replicate ISOCS Measurements for QC ........................................................................ 24 Table 16 B1-010-001 Sign Test ............................................................................................................................ 40 Table 16 Reactor Building Basement QC Assessment ...................................................................................... 42 LIST OF FIGURES Figure 6 ISOCS Measurement ............................................................................................................................. 20 Figure 16 Reactor Building Basement ISOCS Measurement Locations (1) .................................................... 29 Figure 16 Reactor Building Basement ISOCS Measurement Locations (2) .................................................... 30 Figure 16 Reactor Building Basement ISOCS Measurement Locations (3) .................................................... 31 Figure 16 Quantile Plot for Cs-137 Concentration ............................................................................................ 44 Figure 16 Histogram for Cs-137 Concentration................................................................................................. 45 Figure 16 Retrospective Power Curve for B1-010-001 ...................................................................................... 46 3

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable BFM Basement Fill Model DQO Data Quality Objective DCGL Derived Concentration Guideline Level DCGLB Basement Derived Concentration Guideline Level EMC Elevated Measurement Comparison FOV Field-of-View FSS Final Status Survey IC Insignificant Contributors ISOCS In-Situ Object Counting System 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 OpDCGLB Basement Operational Derived Concentration Guideline Level QAPP Quality Assurance Project Plan QC Quality Control RA Radiological Assessment ROC Radionuclides of Concern SOF Sum-of-Fraction UBGR Upper Bound of the Gray Region WGTV Waste Gas Tank Vault WTB Waste Treatment Building 4

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001

1. EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey unit B1-010-001, Reactor Building Basement, has been generated in accordance with LaCrosseSolutions procedure LC-FS-PR-009, Final Status Survey Data Reporting (Reference 1) and satisfies the requirements of Section 5.11 of the La Crosse Boiling Water Reactor License Termination Plan (LACBWR LTP) (Reference 2).

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

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\VWHPDWLFmeasurement population, forty-five (45) measurements using the Canberra In-Situ Object Counting System (ISOCS) were acquired from the survey unit.

The analytical results for all systematic measurements taken in survey unit B1-010-001 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 0.0232, when applying the respective Operational Derived Concentration Guideline Levels (OpDCGLB). Therefore, the null hypothesis is rejected, and survey unit B1-010-001 is acceptable for unrestricted release.

The mean SOF for systematic measurements when applying the respective Base Case DCGLs (DCGLB) is 0.0004. The maximum SOF for the judgmental measurements, when compared to the DCGLB is 0.0753. The total SOF, when factoring in the area-weighted SOF of the elevated judgmental measurements is 0.0006, which equates to a dose of 0.015 mrem/yr.

2. SURVEY UNIT DESCRIPTION B1-010-001 is an impacted Class 1 basement survey unit. This survey unit housed the nuclear reactor and primary reactor systems. All internal systems, concrete, and the steel liner were removed during demolition. At end-state, the survey unit consisted of the concrete floor and concrete walls up to 3 feet below grade (636 foot elevation). The total surface area of the survey unit is 512 m2.

5

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001

3. CLASSIFICATION BASIS Based on the Historical Site Assessment (Reference 5), the Reactor Building Basement was identified as a Class 1 area.

The initial site characterization surveys performed by EnergySolutions were conducted between October 9, 2014, and August 6, 2015. Because of limited accessibility, the Reactor Building Basement interior structural surfaces characterization was deferred.

A Radiological Assessment (RA) (considered a form of continuing characterization) was performed in the survey unit between March 15, 2019, and March 21, 2019. The RA survey was performed to ensure that any individual ISOCS measurement would not exceed the OpDCGLB during FSS. The RA consisted of a beta-gamma and gamma only scan over 100% of all accessible surfaces and the collection of 30 loose surface contamination samples. Six (6) concrete core samples were obtained at evenly distributed locations, and an additional five (5) cores were obtained at areas of elevated activity identified during the scan survey.

Eleven (11) concrete core samples were collected from the floor and walls in the survey unit. The cores were 3 in diameter and 6 deep. Table 3-1 below summarizes the results from the concrete core analyses using the on-site gamma spectroscopy system. Only the top half-inch of the puck from each core was analyzed with the exception of B1-010-001-CJFC-009-CV 0.5-1 and B1-010-001-CJFC-011-CV 0.5-1.

Table 3 Reactor Building Basement Continuing Characterization Concrete Core Analysis Summary - On-site Cs-137 Puck Activity Sample ID Surface (pCi/g)

B1-010-001-CJFC-C01-CV 0-0.5" Top 4.21E-02 B1-010-001-CJFC-C01-CV 0-0.5" Bottom 0.00E+00 B1-010-001-CJFC-C02-CV 0-0.5" Top 1.86E-01 B1-010-001-CJFC-C02-CV 0-0.5" Bottom 9.93E-02 B1-010-001-CJFC-C03-CV 0-0.5" Top 5.02E-02 B1-010-001-CJFC-C03-CV 0-0.5" Bottom 3.50E-01 B1-010-001-CJFC-C04-CV 0-0.5" Top 1.71E-01 B1-010-001-CJFC-C04-CV 0-0.5" Bottom 5.27E-01 B1-010-001-CJFC-C05-CV 0-0.5" Top 1.72E-01 B1-010-001-CJFC-C05-CV 0-0.5" Bottom 3.32E-01 6

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Cs-137 Puck Activity Sample ID Surface (pCi/g)

B1-010-001-CJFC-C06-CV 0-0.5" Top 3.40E-01 B1-010-001-CJFC-C06-CV 0-0.5" Bottom 3.15E-01 B1-010-001-CJFC-C07-CV 0-0.5" Top 2.80E-01 B1-010-001-CJFC-C07-CV 0-0.5" Bottom 0.00E+00 B1-010-001-CJFC-C08-CV 0-0.5" Top 2.79E-01 B1-010-001-CJFC-C08-CV 0-0.5" Bottom 4.86E-01 B1-010-001-CJFC-C09-CV 0-0.5" Top 4.77E+01 B1-010-001-CJFC-C09-CV 0-0.5" Bottom 2.03E+01 B1-010-001-CJFC-C09-CV 0.5-1 Top 3.50E-01 B1-010-001-CJFC-C09-CV 0.5-1 Bottom 6.98E-03 B1-010-001-CJFC-C10-CV 0-0.5" Top 4.40E-01 B1-010-001-CJFC-C10-CV 0-0.5" Bottom 3.39E-01 B1-010-001-CJFC-C11-CV 0-0.5" Top 9.47E+00 B1-010-001-CJFC-C11-CV 0-0.5 Bottom 4.02E+00 B1-010-001-CJFC-C11-CV 0.5-1 Top 3.37E-01 B1-010-001-CJFC-C11-CV 0.5-1 Bottom 1.02E-01 Note: Bold values indicate activity above MDC Cs-137 was detected in concentrations above MDC in two (2) of the eleven (11) pucks analyzed. No other ROC were identified in the continuing characterization concrete cores.

The top half-inch pucks from concrete core samples B1-010-001-CJFC-C04-CV, B1-010-001-CJFC-C09-CV, and B1-010-001-CJFC-C11-CV were sent off-site to Gel Laboratories for gamma spectroscopy and HTD analysis of the full suite of ROC. Table 3-2 summarizes the results of the off-site analyses.

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FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Table 3 Reactor Building Basement Continuing Characterization Concrete Core Analysis Summary - Off-site B1-010-001-CSFC-C04-CV B1-010-001-CSFC-C09-CV B1-010-001-CSFC-C11-CV Radionuclide (pCi/g) (pCi/g) (pCi/g)

Am-241 2.37E-03 3.12E-04 -1.67E-03 Am-243 -7.80E-03 -5.57E-03 9.25E-03 Cm-243/244 -6.02E-03 -3.69E-03 -1.38E-02 Np-237 0.00E+00 -5.17E-04 3.27E-03 Pu-238 1.25E-02 4.76E-03 -2.14E-02 Pu-239/240 1.21E-02 -1.10E-02 -3.73E-03 Pu-241 1.71E+00 2.52E-01 9.58E-01 Ni-59 1.88E-01 6.84E-01 6.84E-01 Cs-137 3.56E-02 4.82E+01 1.10E+01 Co-60 4.03E-02 6.72E-02 3.21E-03 Eu-152 1.68E-01 -2.96E-01 4.55E-02 Eu-154 -6.38E-03 -9.13E-02 7.01E-03 Eu-155 1.68E-01 1.95E-01 1.73E-01 Nb-94 -7.60E-02 6.47E-02 4.12E-02 Sr-90 8.01E-03 -2.56E-02 2.30E-01 H-3 -3.65E+00 -2.41E+00 -1.22E+00 C-14 -1.10E+00 -2.96E-01 -3.03E+00 Tc-99 6.91E-01 -1.48E-02 -1.65E-02 Fe-55 -4.52E-01 1.66E+00 3.42E+00 Ni-63 -1.45E+00 -2.94E-01 -1.31E-02 Note: Bold values indicate activity above MDC 8

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Cs-137 was positively identified in two (2) of the three (3) core samples. No other ROC were identified in the core samples sent off-site.

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

An assessment of the results of continuing characterization confirmed that the IC dose is unchanged (dose fraction less than 10%).

Based upon review of the historical information, the results of the characterization survey data, and completion of a final Survey Unit Classification Worksheet, the correct final classification of survey unit B1-010-001 was determined to be Class 1.

4. DATA QUALITY OBJECTIVES FSS planning and design relies on a properly executed Data Quality Objective (DQO) process to ensure, through compliance with explicitly defined inputs and boundaries, that the primary objective of the survey is satisfied. The DQO process 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.

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 9

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 that residual activity in the survey unit exceeded the release criteria. Rejection of the null hypothesis would indicate that residual activity within the survey unit does not exceed the release criteria. Therefore, the survey unit would satisfy the primary objective of the FSS sample plan.

The primary objective of the FSS sample plan is to demonstrate that the level of residual radioactivity in survey unit B1-010-001 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 current contamination levels in the basements and soils from the characterization campaign conducted from September 2014 through August 2015. The initial survey data for basements was based on core samples obtained from the walls and floors of the Reactor Building, Waste Treatment Building (WTB), and the balance of the basement structures (primarily the Piping Tunnels) at biased locations with elevated contact dose rates, contamination levels, and/or evidence of leaks/spills. During subsequent characterizations, additional cores were obtained from the Reactor Building and the Waste Gas Tank Vault (WGTV). TSD RS-TD-313196-001 evaluates the results of the concrete core analysis data from the Reactor Building, WTB, Piping Tunnels and WGTV and refines the initial suite of potential ROC by evaluating the dose significance of each radionuclide.

Insignificant dose contributors were determined consistent with the guidance contained in Section 3.3 of NUREG-1757, Volume 2, Revision 1, Consolidated Decommissioning Guidance - Characterization, Survey, and Determination of Radiological Criteria, Final Report (Reference 8). In all soil and concrete scenarios, Cs-137, Co-60, Sr-90, Eu-152 and Eu-154 contribute nearly 100% of the total dose. The remaining radionuclides were designated as insignificant dose contributors and are eliminated from further detailed evaluation. Therefore, the final ROCs for LACBWR soil, basement concrete and buried piping are Cs-137, Co-60, Sr-90, Eu-152 and Eu-154.

LTP Chapter 6, Section 6.14.1 discusses the process used to derive the ROC for the decommissioning of LACBWR, including the elimination of insignificant dose contributors (IC) from the initial suite. Table 4-1 presents the ROC for the decommissioning of basements at LACBWR and the normalized mixture fractions for the Reactor Building Basement based on the radionuclide mixture.

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FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Table 4 Reactor Building Basement Dose Significant Radionuclides and Mixture Fraction of Total Activity Radionuclide (normalized)(1)

Co-60 0.074 Sr-90 0.123 Cs-137 0.796 Eu-152 0.003 Eu-154 0.004 (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 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.

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 backfilled basements below the 636 foot elevation, the DCGLs are expressed in units of activity per unit of area (pCi/m2).

The Basement Fill Model (BFM) applies to the steel-reinforced concrete walls and floors of the backfilled Reactor Building and WGTV below the 636 foot elevation. BFM DCGLs (DCGLB) apply to basement concrete and are calculated in LTP Chapter 6, Section 6.13.

The insignificant dose contributor percentages for the most limiting basement scenario was 11

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 used to adjust the DCGLB to account for the dose from the eliminated insignificant contributor radionuclides. The DCGLB values for the Reactor Building Basement from LTP Chapter 5, Section 5.2.1 are reproduced below in Table 4-2.

Table 4 Reactor Building Basement Base Case DCGLs Reactor Building Radionuclide Basement DCGLB (pCi/m2)

Co-60 5.16E+06 Sr-90 1.45E+07 Cs-137 2.17E+07 Eu-152 1.19E+07 Eu-154 1.10E+07 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 BFM OpDCGLB for the unrestricted release of the Reactor Building Basement survey unit from LTP Chapter 5, Section 5.2.2 are provided in Table 4-3.

Table 4 Reactor Building Basement Operational DCGLs Reactor Building Radionuclide Basement OpDCGLB (pCi/m2)

Co-60 3.61E+05 Sr-90 1.02E+06 Cs-137 1.52E+06 Eu-152 8.33E+05 Eu-154 7.71E+05 Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the Operational DCGL. The Canberra ISOCS was selected as the primary instrument used to perform FSS of basement surfaces. Response checks were required prior to issuance and after use. Control and accountability of ISOCS units was required to assure data quality.

As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. The actual recorded value was used as the recorded FSS result for 12

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 measurement and/or sample values that are less than MDC. Negative values were recorded as zero. Results were not reported as less than MDC (< MDC). Sample report summaries included unique sample identification, analytical method, radionuclide, result, uncertainty, laboratory data qualifiers, units, and the observed MDC.

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

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

5. SURVEY DESIGN The level of effort associated with planning a survey is based on the complexity of the survey unit 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 determined that Co-60, Sr-90, Cs-137, Eu-152, and Eu-154 would be the ROC in survey unit B1-010-001. During FSS, concentrations for the HTD ROC Sr-90 are inferred using a surrogate approach. Cs-137 is the principle surrogate radionuclide for Sr-

90. Both Sr-90 and Cs-137 was positively detected in all thirty (30) concrete core samples assessed in the Reactor Building, Piping Tunnels, and WTB. For the Reactor Building Basement, Sr-90 was not detected in any of the eleven (11) core samples assessed during continuing characterization. The 95% Upper Confidence Limit (UCL) of the Cs-137 fractions was chosen to represent the overall nuclide mix for soils/buried pipe, the Reactor Building, and the Reactor Building Basement. The surrogate ratio for the Reactor Building Basement is given in Table 5-1.

Table 5 Reactor Building Basement Surrogate Ratio Radionuclides Ratio Sr-90/Cs-137 0.5 The equation for calculating a surrogate DCGL is as follows:

Equation 1 1

=

1

+ + +

Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate 13

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 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

() = = 8.71 + 05 /

1 0.5 1.52 + 06 + 1.02 + 06

() ()

The surrogate Operational DCGL that was used for Cs-137 in this survey unit for direct comparison of measurement results to demonstrate compliance was 8.71E+05 pCi/m2.

The action levels for survey unit B1-010-001 are based on the Operational DCGL and are presented in Table 5-2.

Table 5 Action Levels for Survey Unit B1-010-001 OpDCGLB ROC (pCi/m2)

Co-60 3.61E+05 Cs-137 8.71E+05(1)

Eu-152 8.33E+05 Eu-154 7.71E+05 (1) 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.

The Elevated Measurement Comparison (EMC) does not apply to this survey unit. At LACBWR, EMC only applies to Class 1 open land areas.

Sample size determination for FSS basement structures is addressed in LTP Chapter 5, Section 5.5.2.2. To ensure that the number of ISOCS measurements, based on the necessary areal coverage in a basement surface FSS unit, was sufficient to satisfy a statistically based sample design, a calculation was performed to determine sample size. If the sample size based on the statistical design required more ISOCS measurements than the number of 14

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 ISOCS measurements required by the areal coverage, then the number of ISOCS measurements was adjusted to meet the larger sample size.

The number of measurements for FSS was determined in accordance with procedure LC-FS-PR-002. 7KHUHODWLYHVKLIW  IRUWKHVXUYH\XQLWGDWDVHWLVGHILQHGDVVKLIW ZKLFK

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

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

standard deviation of the data sHWXVHGIRUVXUYH\GHVLJQ7KHRSWLPDOYDOXHIRUVKRXOG

UDQJHEHWZHHQRQH  DQGWKUHH  7KHODUJHVWYDOXHWKHFDQKDYHLVWKUHH  ,IWKH

H[FHHGVWKUHH  WKHQWKHYDOXHRIWKUHH  ZLOOEHXVHGIRUIn the absence of prior survey data, the survey design used the MARSSIM recommended standard deviation value of 0.3. 7KHIRUVXUYH\XQLW%-010-001 was calculated as follows:

Equation 3

 = 0.5/0.3 = 1.67 Both the Type ,HUURURU value, and the Type ,,HUURURU value, were set at 0.05. The sample size for use with the Sign Test from Table 5.5 of MARSSIM that equates to the Type I and Type II error of 0.05 and a relative shift of 1.67 is an N value of seventeen (17).

The required areal scan coverage for a Class 1 basement survey unit is 100%. The LTP requires that sufficient measurements be taken in a Class 1 FSS unit to ensure that 100% of the surface area was surveyed. The number of ISOCS measurements required in each FSS unit can be calculated as the quotient of the ISOCS Field-of-View (FOV) divided into the surface area required for areal coverage. Table 5-3 presents the minimum number of ISOCS measurements that were required for survey unit B1-010-001 based on a measurement FOV of 28 m2.

Table 5 Number of ISOCS Measurements based on Areal Coverage Minimum

1. of ISOCS Area Areal Measurements Survey Unit Classification Coverage (based on 28 m2 (m2) (% of Area)

FOV)

Reactor Building Basement Class 1 512 100% 18 The ISOCS FOV was overlapped to ensure that there were no un-surveyed corners and gaps.

The adjusted minimum number of ISOCS measurements in the Reactor Building Basement to account for overlap is provided in Table 5-4.

15

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Table 5 Adjusted Minimum Number of ISOCS Measurements Required Adjusted # of Adjusted Adjusted Areal ISOCS Areal Areal Survey Unit Classification Coverage Measurements Coverage Coverage (based on 16 m2 (% of (m2) (m2)

FOV) Area)

Reactor Building Class 1 512 43 512 100%

Basement The areal scan coverage requirements for FSS of structures as specified in the LTP are commensurate with the probability that a small area of elevated activity could exist within an FSS unit in a concentration exceeding the Base Case DCGL and the likelihood that such an area would not be detected by the FSS ISOCS measurements. It is highly unlikely that the ISOCS, with a nominal FOV of approximately 28 m2 would not detect and account for elevated areas. The primary basis used to determine reasonable areal coverage for the ISOCS measurements is the potential for the Operational DCGL to be exceeded. The criterion for selecting reasonable and risk-informed areal coverage is based on a graded approach similar to the guidance for scan surveys during FSS provided in MARSSIM, where the coverage is based on the expected fraction of the DCGL (in this case the Operational DCGL). All ISOCS measurement locations collected for survey unit B1-010-001 are provided on the map in Attachment 1 of this document.

The coordinates for all of the ISOCS measurement locations were conspicuously marked to designate where to position the survey rig to the center-point of the instrument FOV. The ISOCS detector was then positioned either vertically or horizontally and adjacent to the surface at the center-point of each designated floor or wall measurement location. Each survey measurement location would then be reproducible utilizing permanent markings on the survey unit floor and walls and annotated on the survey map and Attachment 14 of the sample plan, FSS Samples/Measurements Identification and Coordinates.

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 replicate measurement at 5% of the measurements taken in a survey unit with the locations selected at random. Three (3)

ISOCS measurements were selected randomly for the replicate measurements for this survey unit.

In accordance with Section 5.1 of the LTP, concrete core samples are required to be collected at 10% of the ISOCS measurement locations during FSS for HTD analysis. The 16

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 eleven (11) continuing characterization concrete cores were used to satisfy the requirement in the LTP, as they were representative of the survey units end state condition. See Section 3 of this report for the data concerning the concrete cores.

As a Class 1 survey unit, Table 5-4 specifies that a minimum of 512 m2, or 100% of the accessible surface area, in this structural basement survey unit will be subjected to scan coverage. The minimum number of ISOCS measurements required to fully cover the 512 m2 surface area is forty-three (43). Two (2) systematic measurements were added during survey design to fully ensure coverage of gaps. The surface area covered by a single ISOCS measurement is large, and the FOV of the measurement becomes a substitute for scanning that is typically performed by moving a hand-held detector over the surface in question. The majority of systematic ISOCS measurements that were taken during the FSS of the Reactor Building Basement were obtained at a stand-off distance of 3 meters, which resulted in a FOV for each measurement of 28 m2. Seven (7) systematic measurements were taken at a stand-off distance of 2 meters, which resulted in a FOV of 12.56 m2. The six (6) judgmental ISOCS measurements were collected at a stand-off distance of 0.5 meters, which correlates to a ISOCS FOV of 0.79 m2.

To achieve 100% areal coverage for the 512 m2 of floor and wall surfaces that constitute this survey unit, along with the minimum of 5% replicate measurements, 54 ISOCS measurements were taken (45 systematic, 6 judgmental, 3 replicate).

All of the ISOCS measurements were collected using the circular plane geometry, although varied geometries were necessary due to the structural anomalies encountered within the survey unit (use of different stand-off distances). ISOCS geometries specifically employed within this survey unit are provided in Attachment 2 of this report. Maps of the surface area scanned by the ISOCS FOV are provided in Attachment 1.

For this Class 1 basement structure survey unit, the Investigation Levels for ISOCS measurement results are those levels specified in LTP Chapter 5, Table 5-16, and are reproduced below in Table 5-5.

Table 5 Investigation Levels Direct Investigation Classification Scan Investigation Levels Levels

>Operational DCGL or >MDCscan if Class 1 MDCscan is greater than Operational >Operational DCGL DCGL Table 5-6 provides a synopsis of the survey design for survey unit B1-010-001.

17

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Table 5 Synopsis of Survey Design Feature Design Criteria Basis Survey Unit Surface LTP Ch. 5, Table 5-13 and 512 m2 Area Table 5-14 x UBGR = SOF of 1 x LBGR = SOF of 0.5 Number of x Type I error = 0.05 Systematic 17 x Type II error = 0.05 Measurements (N) x  1.67 x MARSSIM Table 5.5 Adjusted Number of Based on 100% scan 43 Systematic coverage accounting for 45 (actual number obtained)

Measurements overlap Co-60: 3.61E+05 Sr-90: 1.02E+06 Operational DCGLs for DCGLs Cs-137: 1.52E+06 Reactor Building Basement, Eu-152: 8.33E+05 (LTP Chapter 5, Table 5-4)

Eu-154: 7.71E+05 Investigation Level >Operational DCGL (LTP Chapter 5, Table 5-16)

Scan Areal Coverage 512 m2 or 100% areal coverage (LTP Chapter 5, Table 5-15)

Number of Minimum of 1 ISOCS Judgmental 6 Measurement per Sample Measurements Plan 3 measurements selected randomly for QC (LTP Chapter 5, Section 5.9) replicate measurement analysis 10% of ISOCS Measurements, HTD (LTP Chapter 5, Section 5.1)

Minimum of 2 18

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001

6. SURVEY IMPLEMENTATION For survey unit B1-010-001, compliance with the unrestricted release criteria was demonstrated through the use of ISOCS for direct measurements.

A walkdown and turnover survey was satisfactorily performed in the Reactor Building Basement in accordance with the Isolation and Control requirements of procedure LC-FS-PR-010, Isolation and Control for Final Status Survey (Reference 11). The Reactor Building Basement was deemed acceptable for turnover and FSS commenced on March 27, 2019 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 were projected to take four (4) working days to complete. Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job. The survey required field activities were performed during normal working hours and concluded on March 29, 2019.

Prior to implementing the sample plan for the FSS of the Reactor Building Basement structure, the physical condition of the concrete surfaces to be surveyed were assessed to ensure that the geometry was not significantly changed from that assumed in LC-FS-TSD-001, Use of ISOCS for FSS of End State Sub Structures at LACBWR (Reference 12). ISOCS measurements were acquired using the circular plane geometry, which assumed a circular plane source with a contaminant depth of 0.5 inches. With the 90-degree collimation shield installed and a source to detector distance of 3 meters, this orientation corresponded to a nominal FOV of 28 m2. A guide attached to the detector assembly, in the form of a plumb-bob or wooden stud, was used to establish a consistent source to detector distance and center the detector over the selected measurement location.

The ISOCS measurement locations specified in FSS sample plan for survey unit B1-010-001 were marked based on the grid coordinates provided in the maps. See Attachment 2 of this report for the ISOCS Geometry Composer Reports.

A total of forty-five (45) systematic ISOCS measurements were collected in the survey unit.

Six (6) judgmental measurements were collected, and three (3) replicate measurements were also acquired in the Reactor Building Basement survey locations #5, #16 and #18. The ISOCS detector face was oriented perpendicular to the surface of interest represented by the grid coordinate. See Picture 1 below for an example of an ISOCS measurement being conducted.

19

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 6 ISOCS Measurement

7. SURVEY RESULTS The SOF or unity rule is applied to the data used for the survey planning, and data evaluation and statistical tests for basement surfaces, since multiple radionuclide-specific measurements will be performed or the concentrations inferred based on known relationships. 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.

20

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 The equation for the unity rule is:

Equation 4 C1 C2 Cn

 ............ d1 DCGL1 DCGL 2 DCGL n Where: Cn = concentration of radionuclide n DCGLn = DCGL of radionuclide n.

The application of the unity rule serves to normalize the data to allow for an accurate comparison of the various data measurements to the release criteria. When the unity rule is applied, the DCGLW (used for the nonparametric statistical test) becomes 1. The DCGLB are directly analogous to the DCGLW as defined in MARSSIM. The use and application of the unity rule was performed in accordance with Section 4.3.3 of MARSSIM.

As described in LTP Chapter 5, Section 5.10.3.2, the Sign Test was used to evaluate the measured residual radioactivity against the dose criterion. The SOF for each measurement was used as the sum value for the Sign Test. The Sign Test then demonstrated that the mean activity for each ROC was less than the OpDCGLB at a Type 1 decision error of 0.05.

For building surfaces, areas of elevated activity were defined as any area identified by measurement/sample (systematic or judgmental) that exceeded the OpDCGLB but was less than the DCGLB. Any area that exceeded the DCGLB would have required remediation. The SOF (based on the OpDCGLB) for a systematic or judgmental measurement/sample(s) can exceed 1 without remediation as long as the survey unit passes the Sign Test, and the mean SOF (based on the OpDCGLB) for the survey unit does not exceed one. Once the survey data set passes the Sign Test (using Operational DCGLs), then the mean radionuclide activity (pCi/m2) for each ROC from systematic measurements along with any identified elevated areas from systematic and judgmental measurement/samples can be used with the Base Case DCGLs to perform a mean SOFB calculation. The dose from residual radioactivity assigned to the FSS unit is the mean SOFB multiplied by 25 mrem/yr.

Direct measurement locations were denoted on the concrete walls and floor of the Reactor Building Basement using the dimensions on the survey map as guidance. See Figure 16-1 on Attachment 1 for a depiction of all measurement locations.

The systematic measurement population consisted of 45 direct measurements that were acquired using the ISOCS. In total, 54 ISOCS measurements were collected, including the systematic, judgmental, and QC measurements. A breakdown of the total ISOCS measurements and SOF for systematic measurements compared to the OpDCGLB is provided in Table 7-1. A summary of the results of the 45 ISOCS measurements taken for non-parametric statistical testing when compared to the DCGLB is provided in Table 7-2.

21

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 The complete ISOCS measurement and gamma spectroscopy reports are presented in Attachment 6.

Table 7 Summary of Systematic, Judgmental, and QC Measurements Total Number of Systematic Measurements 45 Number of Quality Control Measurements 3 Number of Judgmental/Investigational Measurements 6 Total Number of Measurements 54 Mean Systematic Gamma Measurement SOF (1) 0.0061 Max Individual Systematic Gamma Measurement SOF (1) 0.0232 Number of Systematic Gamma Measurements with SOF > 1 (1) 0 (1) Based on the OpDCGLB Table 7 Summary of ISOCS Systematic Measurement Statistical Quantities Mean Median Max Min Std. Dev. BcDCGL Avg SOF Avg Dose ROC 2 (pCi/m ) 2 (pCi/m ) (pCi/m )2 2 (pCi/m ) 2 (pCi/m ) 2 (pCi/m ) per ROC per ROC Co-60 3.90E+02 2.88E+02 1.22E+03 0.000E+00 3.59E+02 5.16E+06 7.57E-05 1.89E-03 Sr-90 4.39E+02 2.18E+02 3.51E+03 0.000E+00 6.62E+02 1.45E+07 3.03E-05 7.57E-04 Cs-137 8.78E+02 4.37E+02 7.03E+03 0.000E+00 1.32E+03 2.17E+07 4.05E-05 1.01E-03 Eu-152 1.34E+03 8.82E+02 6.08E+03 0.000E+00 1.47E+03 1.19E+07 1.13E-04 2.81E-03 Eu-154 1.82E+03 1.51E+03 9.17E+03 0.000E+00 1.59E+03 1.10E+07 1.65E-04 4.13E-03 The total mean SOF for the Reactor Building Basement, based on the mean concentration for each ROC as measured by the systematic measurement population when compared against the DCGLB, is 0.0004. This SOF equates to a dose of 0.0106 mrem/yr.

Six (6) judgmental ISOCS measurement were collected within the survey unit. The judgmental ISOCS measurement results are presented in Table 7-3.

22

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Table 7 Summary of ISOCS Judgmental Measurements Cs-137 Co-60 Eu-152 Eu-154 Sr-90 Measurement ID (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-010-001-FJFC-D44-GM 8.58E+05 2.58E+03 0.00E+00 4.77E+04 4.29E+05 B1-010-001-FJFC-D45-GM 8.04E+05 1.88E+04 5.58E+04 2.48E+04 4.02E+05 B1-010-001-FJFC-D46-GM 2.07E+05 1.65E+04 7.00E+04 5.37E+04 1.04E+05 B1-010-001-FJFC-D47-GM 1.64E+05 2.68E+03 0.00E+00 6.83E+04 8.18E+04 B1-010-001-FJFC-D48-GM 4.38E+04 1.21E+04 0.00E+00 2.48E+04 2.19E+04 B1-010-001-FJFC-D49-GM 1.02E+05 1.01E+04 0.00E+00 9.37E+04 5.12E+04 Note: Bold values indicate activity greater than MDC.

Two (2) judgmental measurements, B1-010-001-FJFC-D44-GM and B1-010-001-FJFC-D45-GM, exceeded the OpDCGLB, at a maximum SOF of 1.0737. The mean SOF of judgmental measurements when compared to the OpDCGLB is 0.5388 and the mean SOF when compared to the DCGLB is 0.03779. Because judgmental measurements are outside of the systematic measurement population, an area-weighted SOF for the two (2) elevated measurements is calculated and added to the average systematic measurement SOF, which is then used to calculate the overall dose assigned to the basement survey unit. The equation for calculating the area-weighted SOF (Equation 5-5 in the LTP) is provided below.

Equation 5

= +

x

where:

SOFB = SOF for structural surface survey unit within a Basement using Base Case DCGLs Mean ConcB ROCi = Mean concentration for the systematic measurements taken during the FSS of structural surface in survey unit for each ROCi Base Case DCGLB ROCi = Base Case DCGL for structural surfaces (DCGLB) for each ROCi Elev ConcB ROCi = Concentration for ROCi in any identified elevated area (systematic or judgmental)

SAElev = surface area of the elevated area SASU = adjusted surface area of FSS unit for DCGL calculation 23

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 The total SOF for the Reactor Building Basement was calculated as follows:

Equation 6

= 0.0004 + 0.0002 = 0.0006 The total SOF assigned to the Reactor Building Basement survey unit is 0.0006, which equates to a dose of 0.015 mrem/yr.

The implementation of required QC measures included the collection of three (3) additional ISOCS measurements at locations throughout the Reactor Building Basement for replicate measurement analysis. The replicate ISOCS measurement results are provided in Table 7-

4. The concentration for Sr-90 is inferred based on the ratio given in Table 5-1.

Table 7 Summary of Replicate ISOCS Measurements for QC Cs-137 Co-60 Eu-152 Eu-154 Sr-90 Measurement ID (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-010-001-QSFC-D05-GM 5.31E+02 5.76E+02 0.00E+00 1.52E+03 2.66E+02 B1-010-001-QSFC-D16-GM 5.09E+02 9.36E+02 0.00E+00 2.66E+03 2.55E+02 B1-010-001-QSFC-D18-GM 3.15E+02 4.23E+02 2.13E+02 2.21E+03 1.58E+02 Note: Bold values indicate activity greater than MDC.

The complete ISOCS gamma spectroscopy reports are presented in Attachment 6.

8. QUALITY CONTROL Three (3) replicate measurements were taken during the FSS of this basement structure. The measurement results were evaluated using USNRC acceptance criteria specified in Inspection Procedure No. 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring (Reference 13). In the case of all three (3) pairs of standard and comparison measurements, there was acceptable QC agreement. 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 No radiological remedial action as described by MARSSIM Section 5.4 was performed in this survey unit as a result of the FSS. Chapter 4 of the LTP determined that remediation 24

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 beyond that required to meet the release criteria is unnecessary and that the remaining residual radioactivity in the structure was ALARA.

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

12. DATA QUALITY ASSESSMENT The DQO sample design and data were reviewed in accordance with LC-FS-PR-008, Final Status Survey Data Assessment (Reference 14) for completeness and consistency.

Documentation was complete and legible. Surveys and the collection of measurements were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 1. The survey design had adequate power as indicated by the Retrospective Power Curve (see Attachment 5).

The analytical results indicated that all systematic measurements were less than a SOF of one (1) when compared to the OpDCGLB. Two (2) judgmental measurements were identified with a SOF greater than one (1) when compared to the OpDCGLB, but less than a SOF of one (1) when compared to the DCGLB.

The Sign Test (Attachment 3) 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 preliminary data review consisted of calculating basic statistical quantities (e.g., mean, median, standard deviation). All data was considered valid including negative values, zeros, values reported below the MDC, and values with uncertainties that exceeded two standard deviations. The mean and median values for each ROC were well below the respective Operational DCGLs. Also, the retrospective power curve shows that a sufficient number of measurements were collected to achieve the desired power. Therefore, the survey unit meets the unrestricted release criteria with adequate power as required by the DQOs.

All graphical presentations are provided in Attachment 5.

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

25

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001

14. CONCLUSION Survey unit B1-010-001 has met the DQOs of the FSS plan. The ALARA criteria as specified in Chapter 4 of the LTP were achieved. The EMC is not applicable to structural surfaces and remediation was 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 OpDCGLB. Additionally, the two (2) elevated judgmental locations were evaluated and the dose was included in the total dose for the survey unit.

The total SOF assigned to the Reactor Building Basement survey unit is 0.0006, which equates to a dose of 0.015 mrem/yr.

The measurement 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. Therefore, in accordance with the LTP Section 5.10, the survey unit meets the release criteria. Survey unit B1-010-001 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-010, Isolation and Control for Final Status Survey

12. LC-FS-TSD-001, Use of ISOCS for FSS of End State Sub Structures at LACBWR

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

14. LC-FS-PR-008, Final Status Survey Data Assessment 26

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001

16. ATTACHMENTS Attachment 1 - Figures and Maps Attachment 2 - ISOCS Geometries Attachment 3 - Sign Test Attachment 4 - Quality Control Assessment Attachment 5 - Graphical Presentations Attachment 6 - Measurement Analytical Reports 27

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 ATTACHMENT 1 FIGURES AND MAPS 28

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 16 Reactor Building Basement ISOCS Measurement Locations (1) 29

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 16 Reactor Building Basement ISOCS Measurement Locations (2) 30

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 16 Reactor Building Basement ISOCS Measurement Locations (3) 31

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 ATTACHMENT 2 ISOCS GEOMETRIES 32

Geometry Composer Report Date: Tuesday, March 26, 2019 - 13:13:12

==

Description:==

Rx Bowl Concrete 0.5M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 0.5M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default)

Detector: 3844f Collimator: 50mm-90d new (newISOCS 50mm side 90deg collimation [large hole collimator])

Environment: Temperature = 22 °C, Pressure = 760 mm Hg, Relative Humidity = 30%

Integration: Convergence = 1.00%, MDRPN = 24 (16), CRPN = 24 (16)

Dimensions (cm)

No. Description d.1 d.2 d.3 d.4 d.5 d.6 Material Density Rel. Conc.

1 Side Walls 0 100 none 2 Layer 1 1.27 concrete 2.3 1.00 3 Layer 2 0 <none>

4 Layer 3 0 <none>

5 Layer 4 0 <none>

6 Layer 5 0 <none>

7 Layer 6 0 <none>

8 Layer 7 0 <none>

9 Layer 8 0 <none>

10 Layer 9 0 <none>

11 Layer 10 0 <none>

12 Absorber1 13 Absorber2 14 Source-Detector 50 0 0 0 0 List of energies for efficiency curve generation 59.5 88.0 122.1 200.0 400.0 661.7 900.0 1000.0 1173.2 1332.5 1836.0 Page 1 of 2

Geometry Composer Report Date: Tuesday, March 26, 2019 - 13:13:12

==

Description:==

Rx Bowl Concrete 0.5M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 0.5M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default)

Page 2 of 2

Geometry Composer Report Date: Tuesday, March 26, 2019 - 13:14:36

==

Description:==

Rx Bowl Concrete 2M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 2M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default)

Detector: 3844f Collimator: 50mm-90d new (newISOCS 50mm side 90deg collimation [large hole collimator])

Environment: Temperature = 22 °C, Pressure = 760 mm Hg, Relative Humidity = 30%

Integration: Convergence = 1.00%, MDRPN = 24 (16), CRPN = 24 (16)

Dimensions (cm)

No. Description d.1 d.2 d.3 d.4 d.5 d.6 Material Density Rel. Conc.

1 Side Walls 0 400 none 2 Layer 1 1.27 concrete 2.3 1.00 3 Layer 2 0 <none>

4 Layer 3 0 <none>

5 Layer 4 0 <none>

6 Layer 5 0 <none>

7 Layer 6 0 <none>

8 Layer 7 0 <none>

9 Layer 8 0 <none>

10 Layer 9 0 <none>

11 Layer 10 0 <none>

12 Absorber1 13 Absorber2 14 Source-Detector 200 0 0 0 0 List of energies for efficiency curve generation 59.5 88.0 122.1 200.0 400.0 661.7 900.0 1000.0 1173.2 1332.5 1836.0 Page 1 of 2

Geometry Composer Report Date: Tuesday, March 26, 2019 - 13:14:36

==

Description:==

Rx Bowl Concrete 2M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 2M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default)

Page 2 of 2

Geometry Composer Report Date: Tuesday, March 26, 2019 - 13:15:10

==

Description:==

Rx Bowl Concrete 3M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 3M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default)

Detector: 3844f Collimator: 50mm-90d new (newISOCS 50mm side 90deg collimation [large hole collimator])

Environment: Temperature = 22 °C, Pressure = 760 mm Hg, Relative Humidity = 30%

Integration: Convergence = 1.00%, MDRPN = 24 (16), CRPN = 24 (16)

Dimensions (cm)

No. Description d.1 d.2 d.3 d.4 d.5 d.6 Material Density Rel. Conc.

1 Side Walls 0 600 none 2 Layer 1 1.27 concrete 2.3 1.00 3 Layer 2 0 <none>

4 Layer 3 0 <none>

5 Layer 4 0 <none>

6 Layer 5 0 <none>

7 Layer 6 0 <none>

8 Layer 7 0 <none>

9 Layer 8 0 <none>

10 Layer 9 0 <none>

11 Layer 10 0 <none>

12 Absorber1 13 Absorber2 14 Source-Detector 300 0 0 0 0 List of energies for efficiency curve generation 59.5 88.0 122.1 200.0 400.0 661.7 900.0 1000.0 1173.2 1332.5 1836.0 Page 1 of 2

Geometry Composer Report Date: Tuesday, March 26, 2019 - 13:15:10

==

Description:==

Rx Bowl Concrete 3M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 3M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default)

Page 2 of 2

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 ATTACHMENT 3 SIGN TEST 39

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Table 16 B1-010-001 Sign Test SOF

1. 1-Ws Sign (Ws) 1 0.00781 0.99 +1 2 0.00614 0.99 +1 3 0.00454 1.00 +1 4 0.00409 1.00 +1 5 0.00614 0.99 +1 6 0.00249 1.00 +1 7 0.00175 1.00 +1 8 0.00195 1.00 +1 9 0.00416 1.00 +1 10 0.00479 1.00 +1 11 0.00804 0.99 +1 12 0.00522 0.99 +1 13 0.00448 0.99 +1 14 0.00496 1.00 +1 15 0.00411 1.00 +1 16 0.00472 1.00 +1 17 0.00347 1.00 +1 18 0.00934 1.00 +1 19 0.00362 0.99 +1 20 0.01588 1.00 +1 21 0.00206 0.98 +1 22 0.00759 1.00 +1 23 0.00683 0.99 +1 24 0.00419 0.99 +1 25 0.00855 1.00 +1 26 0.01002 0.99 +1 27 0.02319 0.99 +1 28 0.01990 0.98 +1 29 0.00095 0.98 +1 30 0.00228 1.00 +1 31 0.00483 1.00 +1 32 0.00176 1.00 +1 33 0.00054 1.00 +1 34 0.00474 1.00 +1 35 0.00187 1.00 +1 36 0.00567 1.00 +1 37 0.00313 0.99 +1 38 0.00287 1.00 +1 39 0.00910 1.00 +1 40 0.00516 0.99 +1 41 0.00589 0.99 +1 42 0.00716 0.99 +1 43 0.00693 0.99 +1 50 0.01143 0.99 +1 51 0.00803 0.99 +1 Number of positive differences (S+) 45 Critical Value 28 Survey Unit Meets the Acceptance Criteria 40

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 ATTACHMENT 4 QUALITY CONTROL ASSESSMENT 41

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Table 16 Reactor Building Basement QC Assessment STANDARD COMPARISON Activity Standard Agreement Range Activity Standard Comparison Acceptable Measurement ID Radionuclide Resolution Measurement ID Value Error (Low to High) Value Error Ratio (Y/N)

B1-010-001-FSFC-D05-GM K-40* 8.83E+04 1.37E+04 6 0.5 2 B1-010-001-QSFC-D05-GM 7.83E+04 1.29E+04 0.89 Y B1-010-001-FSFC-D16-GM K-40* 8.71E+04 1.33E+04 7 0.5 2 B1-010-001-QSFC-D16-GM 8.64E+04 1.35E+04 0.99 Y B1-010-001-FSFC-D18-GM K-40* 8.12E+04 1.37E+04 6 0.5 2 B1-010-001-QSFC-D18-GM 8.21E+04 1.31E+04 1.01 Y Comments/Corrective Actions: K-40 was substituted for the assessment of locations #5 and #18 because Cs- Table is provided to show acceptance criteria used to assess replicate ISOCS 137 was not identified in either the standard or comparison measurement. K-40 was substitued for the assessment measurements.

of location #16 because of low Cs-137 activity identified in the replicate measurement and no ROC identified in the standard measurement.

42

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 ATTACHMENT 5 GRAPHICAL PRESENTATIONS 43

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 16 Quantile Plot for Cs-137 Concentration 8.00E+03 7.00E+03 Concentration (pCi/m2) 6.00E+03 5.00E+03 4.00E+03 3.00E+03 2.00E+03 1.00E+03 0.00E+00 0% 20% 40% 60% 80% 100%

Percentage 44

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 16 Histogram for Cs-137 Concentration 40 35 30 Frequency 25 20 15 10 5

0 1.17E+03 2.34E+03 3.51E+03 4.69E+03 5.86E+03 7.03E+03 Upper End Value (pCi/m2) 45

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 16 Retrospective Power Curve for B1-010-001 46

FSS RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 ATTACHMENT 6 MEASUREMENT ANALYTICAL REPORTS 47

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

Filename: C:\LACBWR\B1-010-001-FJFC-D44-GM.CNF Report Generated On  : 3/29/2019 9:59:57 AM Sample Title  : B1-010-001-FJFC-D44-GM Sample Description  : Rx Bowl concrete 0.5 M Sample Identification  : D44 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 7.900E-001 M^2 Sample Taken On  : 3/29/2019 7:28:00 AM Acquisition Started  : 3/29/2019 7:29:04 AM Live Time  : 600.0 seconds Real Time  : 600.3 seconds Dead Time  : 0.05 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_0.5M

Peak Analysis Report 3/29/2019 9:59:57 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FJFC-D44-GM Peak Analysis Performed on: 3/29/2019 9:59:57 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 962 955.05 238.83 0.58 5.90E+001 41.00 1.20E+002 2 1525- 1536 1530.60 382.81 0.61 1.91E+001 20.20 3.29E+001 3 2327- 2339 2332.32 583.33 0.81 4.51E+001 16.55 8.90E+000 4 2431- 2442 2436.82 609.46 1.35 3.10E+001 15.64 1.20E+001 5 2635- 2658 2646.78 661.96 1.65 8.45E+002 64.41 4.80E+001 6 3639- 3652 3645.44 911.64 0.59 1.54E+001 14.42 1.26E+001 7 3868- 3881 3874.49 968.89 0.46 1.25E+001 12.87 1.05E+001 8 5834- 5858 5846.32 1461.59 1.66 2.53E+002 34.03 9.03E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 9:59:57 AM Page 3

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Sample

Title:

B1-010-001-FJFC-D44-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.989 1460.81* 10.67 3.25663E+006 5.14122E+005 CS-137 0.998 661.65* 85.12 8.58067E+005 1.22072E+005 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 6.37116E+004 4.54297E+004 300.09 3.41 BI-214 1.000 609.31* 46.30 5.50964E+004 2.86783E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 5.77509E+004 5.44968E+004 964.60 5.20 969.11* 16.60 8.07937E+004 8.35033E+004 1587.90 3.71

Interference Corrected Activity Report 3/29/2019 9:59:57 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 9:59:57 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.989 3.256629E+006 5.141220E+005 CS-137 0.998 8.580667E+005 1.220722E+005 PB-212 1.000 6.371158E+004 4.542965E+004 BI-214 1.000 5.509645E+004 2.867825E+004 AC-228 1.000 6.463381E+004 4.563755E+004

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

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

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

Peak Locate Performed on: 3/29/2019 9:59:57 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 382.81 3.1859E-002 105.67 3 583.33 7.5170E-002 36.70 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/29/2019 9:59:57 AM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FJFC-D44-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 2.910E+005 2.91E+005 3.257E+006 1.281E+005 CO-60 1173.22 100.00 3.824E+004 2.96E+004 2.581E+003 1.751E+004 1332.49 100.00 2.958E+004 -6.722E+003 1.305E+004 CS-134 475.35 1.46 3.010E+006 3.72E+004 -1.034E+006 1.439E+006 563.23 8.38 4.343E+005 2.952E+004 2.045E+005 569.32 15.43 2.283E+005 2.305E+004 1.072E+005 604.70 97.60 3.719E+004 3.700E+004 1.746E+004 795.84 85.40 4.044E+004 1.171E+004 1.870E+004 801.93 8.73 3.973E+005 1.758E+005 1.837E+005 1038.57 1.00 3.279E+006 -2.405E+005 1.489E+006 1167.94 1.80 2.095E+006 1.517E+006 9.583E+005 1365.15 3.04 8.662E+005 2.791E+005 3.748E+005

+ CS-137 661.65* 85.12 4.905E+004 4.91E+004 8.581E+005 2.315E+004 EU-152 121.78 28.40 1.577E+005 1.51E+005 -1.415E+004 7.688E+004 344.27 26.50 1.506E+005 -4.877E+004 7.227E+004 1407.95 20.70 1.617E+005 -4.496E+003 7.211E+004 EU-154 123.07 40.40 1.106E+005 9.79E+004 -1.686E+004 5.388E+004 722.30 20.00 1.719E+005 -5.340E+004 7.982E+004 1274.51 34.40 9.786E+004 4.773E+004 4.400E+004

+ BI-214 609.31* 46.30 3.692E+004 3.69E+004 5.510E+004 1.606E+004 768.36 5.04 6.954E+005 -1.172E+005 3.224E+005 806.17 1.23 2.829E+006 2.192E+005 1.308E+006 934.06 3.21 1.145E+006 8.558E+005 5.283E+005 1120.29 15.10 2.762E+005 2.229E+005 1.277E+005 1155.19 1.69 2.056E+006 1.381E+006 9.333E+005 1238.11 5.94 7.641E+005 8.974E+004 3.540E+005 1280.96 1.47 2.445E+006 5.968E+005 1.107E+006 1377.67 4.11 6.833E+005 -4.648E+005 2.983E+005 1385.31 0.78 3.898E+006 6.359E+005 1.720E+006 1401.50 1.39 2.205E+006 -1.666E+005 9.728E+005 1407.98 2.48 1.350E+006 -3.753E+004 6.019E+005 1509.19 2.19 1.250E+006 -1.764E+005 5.381E+005 1661.28 1.15 2.074E+006 -6.945E+004 8.602E+005 1729.60 3.05 7.152E+005 3.043E+005 2.890E+005 1764.49 15.80 2.386E+005 2.085E+005 1.058E+005 1847.44 2.12 1.531E+006 -1.631E+005 6.624E+005

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 1.426E+006 1.18E+005 9.142E+005 6.956E+005 77.11 10.70 7.876E+005 4.521E+005 3.842E+005 87.20 3.70 1.593E+006 -9.106E+005 7.768E+005 89.80 1.03 5.636E+006 9.328E+005 2.750E+006 241.98 7.49 6.050E+005 7.335E+005 2.937E+005

Nuclide MDA Report 3/29/2019 9:59:57 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 2.101E+005 1.18E+005 6.068E+004 1.012E+005 351.92 37.20 1.180E+005 8.906E+004 5.684E+004 785.91 1.10 2.723E+006 -7.869E+005 1.244E+006

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FJFC-D45-GM.CNF Report Generated On  : 3/29/2019 10:03:01 AM Sample Title  : B1-010-001-FJFC-D45-GM Sample Description  : Rx Bowl concrete 0.5 M Sample Identification  : D45 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 7.900E-001 M^2 Sample Taken On  : 3/29/2019 8:06:00 AM Acquisition Started  : 3/29/2019 8:06:18 AM Live Time  : 600.0 seconds Real Time  : 600.3 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_0.5M

Peak Analysis Report 3/29/2019 10:03:01 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FJFC-D45-GM Peak Analysis Performed on: 3/29/2019 10:03:00 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 962 954.71 238.75 0.49 5.67E+001 38.46 1.08E+002 2 1174- 1186 1179.67 295.03 0.43 3.35E+001 24.76 4.45E+001 3 2430- 2443 2436.75 609.44 0.37 3.33E+001 19.62 2.27E+001 4 2635- 2657 2646.42 661.87 1.44 7.91E+002 61.24 3.75E+001 5 5833- 5857 5845.50 1461.38 2.24 2.21E+002 32.20 9.35E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:03:01 AM Page 3

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

Sample

Title:

B1-010-001-FJFC-D45-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.994 1460.81* 10.67 2.84021E+006 4.76279E+005 CS-137 0.999 661.65* 85.12 8.03636E+005 1.14827E+005 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 6.11633E+004 4.26640E+004 300.09 3.41 BI-214 1.000 609.31* 46.30 5.91420E+004 3.56895E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 9.43086E+004 7.14224E+004 351.92 37.20 785.91 1.10

Interference Corrected Activity Report 3/29/2019 10:03:01 AM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:03:01 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.994 2.840212E+006 4.762794E+005 CS-137 0.999 8.036357E+005 1.148271E+005 PB-212 1.000 6.116332E+004 4.266403E+004 BI-214 1.000 5.914200E+004 3.568947E+004 PB-214 1.000 9.430862E+004 7.142243E+004

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

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

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

Peak Locate Performed on: 3/29/2019 10:03:00 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/29/2019 10:03:01 AM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FJFC-D45-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 2.978E+005 2.98E+005 2.840E+006 1.315E+005 CO-60 1173.22 100.00 3.405E+004 2.89E+004 1.875E+004 1.542E+004 1332.49 100.00 2.889E+004 -1.594E+004 1.270E+004 CS-134 475.35 1.46 2.740E+006 3.89E+004 -3.052E+005 1.304E+006 563.23 8.38 4.249E+005 7.027E+004 1.998E+005 569.32 15.43 2.296E+005 5.933E+004 1.079E+005 604.70 97.60 4.322E+004 -2.797E+003 2.048E+004 795.84 85.40 3.894E+004 -5.986E+002 1.795E+004 801.93 8.73 3.471E+005 -1.035E+005 1.586E+005 1038.57 1.00 2.944E+006 -1.789E+006 1.321E+006 1167.94 1.80 1.968E+006 1.099E+006 8.948E+005 1365.15 3.04 1.056E+006 9.473E+005 4.699E+005

+ CS-137 661.65* 85.12 4.312E+004 4.31E+004 8.036E+005 2.019E+004 EU-152 121.78 28.40 1.528E+005 1.13E+005 -4.096E+004 7.442E+004 344.27 26.50 1.509E+005 5.579E+004 7.245E+004 1407.95 20.70 1.126E+005 -6.883E+004 4.755E+004 EU-154 123.07 40.40 1.077E+005 1.04E+005 -3.863E+004 5.248E+004 722.30 20.00 1.719E+005 3.271E+004 7.982E+004 1274.51 34.40 1.042E+005 2.478E+004 4.715E+004

+ BI-214 609.31* 46.30 5.122E+004 5.12E+004 5.914E+004 2.321E+004 768.36 5.04 6.529E+005 1.331E+005 3.012E+005 806.17 1.23 2.349E+006 -1.653E+006 1.068E+006 934.06 3.21 1.077E+006 -7.961E+005 4.942E+005 1120.29 15.10 2.354E+005 4.228E+004 1.073E+005 1155.19 1.69 2.218E+006 4.320E+005 1.015E+006 1238.11 5.94 7.096E+005 9.527E+005 3.268E+005 1280.96 1.47 2.445E+006 1.346E+006 1.107E+006 1377.67 4.11 8.020E+005 -6.530E+005 3.576E+005 1385.31 0.78 4.324E+006 2.899E+006 1.933E+006 1401.50 1.39 2.353E+006 2.111E+006 1.047E+006 1407.98 2.48 9.397E+005 -5.745E+005 3.969E+005 1509.19 2.19 1.118E+006 1.877E+005 4.720E+005 1661.28 1.15 2.179E+006 1.380E+005 9.124E+005 1729.60 3.05 3.732E+005 5.071E+004 1.180E+005 1764.49 15.80 1.801E+005 1.092E+005 7.660E+004 1847.44 2.12 1.207E+006 6.088E+005 5.007E+005

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 1.366E+006 1.08E+005 9.721E+005 6.653E+005 77.11 10.70 7.566E+005 2.407E+005 3.687E+005 87.20 3.70 1.661E+006 1.180E+006 8.108E+005 89.80 1.03 5.685E+006 1.850E+006 2.775E+006 241.98 7.49 5.797E+005 6.894E+005 2.811E+005

Nuclide MDA Report 3/29/2019 10:03:01 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21* 19.20 1.092E+005 1.08E+005 9.431E+004 5.077E+004 351.92 37.20 1.080E+005 -1.127E+004 5.184E+004 785.91 1.10 3.173E+006 -8.723E+005 1.469E+006

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FJFC-D46-GM.CNF Report Generated On  : 3/29/2019 10:06:01 AM Sample Title  : B1-010-001-FJFC-D46-GM Sample Description  : Rx Bowl concrete 0.5 M Sample Identification  : D46 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 7.900E-001 M^2 Sample Taken On  : 3/29/2019 7:41:00 AM Acquisition Started  : 3/29/2019 7:41:26 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_0.5M

Peak Analysis Report 3/29/2019 10:06:01 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FJFC-D46-GM Peak Analysis Performed on: 3/29/2019 10:06:01 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 961 954.45 238.68 0.78 5.57E+001 36.21 9.73E+001 2 1175- 1186 1180.08 295.13 0.43 1.87E+001 22.43 4.23E+001 3 2431- 2446 2437.31 609.58 1.48 3.42E+001 18.42 1.68E+001 4 2638- 2656 2646.89 661.99 0.85 2.04E+002 31.23 1.18E+001 5 3638- 3652 3645.20 911.58 1.65 3.23E+001 14.89 7.72E+000 6 5835- 5858 5846.70 1461.68 2.37 2.40E+002 32.41 5.74E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:06:01 AM Page 3

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

Sample

Title:

B1-010-001-FJFC-D46-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.986 1460.81* 10.67 3.09315E+006 4.89292E+005 CS-137 0.998 661.65* 85.12 2.07401E+005 4.03258E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 6.00999E+004 4.02546E+004 300.09 3.41 BI-214 0.999 609.31* 46.30 6.07493E+004 3.36464E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 5.26974E+004 6.38181E+004 351.92 37.20 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20

Interference Corrected Activity Report 3/29/2019 10:06:01 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 1.000 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 1.21015E+005 5.75362E+004 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:06:01 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.986 3.093151E+006 4.892917E+005 CS-137 0.998 2.074005E+005 4.032576E+004 PB-212 1.000 6.009990E+004 4.025458E+004 BI-214 0.999 6.074929E+004 3.364636E+004 PB-214 1.000 5.269739E+004 6.381806E+004 AC-228 1.000 1.210149E+005 5.753622E+004

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

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

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

Peak Locate Performed on: 3/29/2019 10:06:01 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/29/2019 10:06:01 AM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FJFC-D46-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 2.351E+005 2.35E+005 3.093E+006 1.001E+005 CO-60 1173.22 100.00 3.355E+004 3.09E+004 -4.124E+004 1.517E+004 1332.49 100.00 3.092E+004 1.653E+004 1.372E+004 CS-134 475.35 1.46 2.557E+006 3.89E+004 1.536E+006 1.213E+006 563.23 8.38 4.249E+005 1.897E+005 1.998E+005 569.32 15.43 2.146E+005 -9.575E+004 1.004E+005 604.70 97.60 4.092E+004 -2.868E+004 1.933E+004 795.84 85.40 3.894E+004 1.132E+004 1.795E+004 801.93 8.73 4.044E+005 -1.741E+005 1.873E+005 1038.57 1.00 3.323E+006 3.125E+006 1.511E+006 1167.94 1.80 2.045E+006 4.287E+005 9.334E+005 1365.15 3.04 1.035E+006 9.043E+005 4.591E+005

+ CS-137 661.65* 85.12 2.375E+004 2.38E+004 2.074E+005 1.050E+004 EU-152 121.78 28.40 1.449E+005 1.38E+005 7.002E+004 7.049E+004 344.27 26.50 1.410E+005 7.993E+004 6.748E+004 1407.95 20.70 1.378E+005 -3.959E+004 6.014E+004 EU-154 123.07 40.40 1.011E+005 1.01E+005 -5.248E+004 4.915E+004 722.30 20.00 1.774E+005 -4.101E+004 8.257E+004 1274.51 34.40 1.026E+005 5.369E+004 4.638E+004

+ BI-214 609.31* 46.30 4.642E+004 4.64E+004 6.075E+004 2.080E+004 768.36 5.04 6.653E+005 -7.675E+005 3.074E+005 806.17 1.23 2.777E+006 -2.177E+006 1.282E+006 934.06 3.21 1.145E+006 -6.658E+003 5.283E+005 1120.29 15.10 2.978E+005 1.667E+005 1.385E+005 1155.19 1.69 2.084E+006 -1.886E+006 9.473E+005 1238.11 5.94 6.879E+005 4.223E+005 3.159E+005 1280.96 1.47 2.372E+006 1.175E+006 1.071E+006 1377.67 4.11 6.448E+005 -2.215E+005 2.790E+005 1385.31 0.78 3.615E+006 1.410E+006 1.578E+006 1401.50 1.39 2.045E+006 7.195E+004 8.927E+005 1407.98 2.48 1.150E+006 -3.304E+005 5.020E+005 1509.19 2.19 1.208E+006 -2.406E+005 5.170E+005 1661.28 1.15 1.844E+006 3.922E+005 7.450E+005 1729.60 3.05 8.834E+005 5.071E+005 3.731E+005 1764.49 15.80 2.282E+005 1.172E+005 1.007E+005 1847.44 2.12 1.207E+006 -6.658E+005 5.007E+005

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 1.351E+006 1.04E+005 1.208E+006 6.577E+005 77.11 10.70 7.418E+005 7.107E+005 3.613E+005 87.20 3.70 1.563E+006 2.373E+005 7.619E+005 89.80 1.03 5.484E+006 4.342E+006 2.674E+006 241.98 7.49 5.616E+005 4.453E+005 2.721E+005

Nuclide MDA Report 3/29/2019 10:06:01 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21* 19.20 1.037E+005 1.04E+005 5.270E+004 4.801E+004 351.92 37.20 1.050E+005 5.314E+004 5.034E+004 785.91 1.10 3.001E+006 -5.453E+005 1.383E+006

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FJFC-D47-GM.CNF Report Generated On  : 3/29/2019 10:08:32 AM Sample Title  : B1-010-001-FJFC-D47-GM Sample Description  : Rx Bowl concrete 0.5 M Sample Identification  : D47 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 7.900E-001 M^2 Sample Taken On  : 3/29/2019 7:53:00 AM Acquisition Started  : 3/29/2019 7:53:55 AM Live Time  : 600.0 seconds Real Time  : 600.3 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_0.5M

Peak Analysis Report 3/29/2019 10:08:32 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FJFC-D47-GM Peak Analysis Performed on: 3/29/2019 10:08:32 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 305 300.80 75.13 0.69 3.55E+001 35.71 1.25E+002 2 948- 962 955.07 238.84 0.68 4.66E+001 34.76 8.84E+001 3 1399- 1415 1407.51 352.02 0.77 6.23E+001 24.93 2.97E+001 4 2326- 2340 2332.97 583.49 1.00 4.07E+001 17.16 1.13E+001 5 2431- 2444 2436.92 609.48 0.80 2.94E+001 17.97 1.86E+001 6 2638- 2655 2646.79 661.97 1.39 1.61E+002 31.17 2.49E+001 7 3869- 3883 3876.00 969.27 0.35 2.63E+001 14.24 7.68E+000 8 5833- 5858 5845.99 1461.51 2.07 2.67E+002 34.25 6.34E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:08:32 AM Page 3

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Sample

Title:

B1-010-001-FJFC-D47-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.991 1460.81* 10.67 3.43271E+006 5.24218E+005 CS-137 0.998 661.65* 85.12 1.63552E+005 3.72523E+004 PB-212 0.999 74.81* 9.60 3.01073E+005 3.08416E+005 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 5.03538E+004 3.83897E+004 300.09 3.41 BI-214 1.000 609.31* 46.30 5.22374E+004 3.26373E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.627 74.81* 6.33 4.56603E+005 4.67740E+005 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 9.98871E+004 4.30729E+004 785.91 1.10 AC-228 0.593 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20

Interference Corrected Activity Report 3/29/2019 10:08:32 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.593 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60 27.70 964.60 5.20 969.11* 16.60 1.70177E+005 9.33865E+004 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:08:32 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.991 3.432712E+006 5.242179E+005 CS-137 0.998 1.635516E+005 3.725234E+004 PB-212 0.999 5.315089E+004 3.809820E+004 BI-214 1.000 5.223742E+004 3.263728E+004 PB-214 0.627 1.022088E+005 4.289422E+004 AC-228 0.593 1.701774E+005 9.338652E+004

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

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

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

Peak Locate Performed on: 3/29/2019 10:08:32 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 4 583.49 6.7837E-002 42.15 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/29/2019 10:08:32 AM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FJFC-D47-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 2.532E+005 2.53E+005 3.433E+006 1.092E+005 CO-60 1173.22 100.00 3.995E+004 3.34E+004 -1.122E+004 1.837E+004 1332.49 100.00 3.342E+004 2.677E+003 1.497E+004 CS-134 475.35 1.46 2.313E+006 3.85E+004 -1.313E+006 1.091E+006 563.23 8.38 4.128E+005 2.826E+004 1.937E+005 569.32 15.43 2.146E+005 3.713E+004 1.004E+005 604.70 97.60 3.848E+004 -1.926E+004 1.810E+004 795.84 85.40 3.856E+004 -2.446E+003 1.776E+004 801.93 8.73 3.863E+005 -6.473E+004 1.782E+005 1038.57 1.00 3.367E+006 -2.542E+006 1.533E+006 1167.94 1.80 2.214E+006 -2.211E+005 1.018E+006 1365.15 3.04 9.898E+005 4.113E+005 4.367E+005

+ CS-137 661.65* 85.12 3.297E+004 3.30E+004 1.636E+005 1.511E+004 EU-152 121.78 28.40 1.533E+005 1.31E+005 -9.235E+004 7.466E+004 344.27 26.50 1.307E+005 -3.661E+004 6.232E+004 1407.95 20.70 1.486E+005 -3.197E+004 6.554E+004 EU-154 123.07 40.40 1.082E+005 9.95E+004 -1.844E+004 5.270E+004 722.30 20.00 1.747E+005 1.818E+004 8.120E+004 1274.51 34.40 9.947E+004 6.829E+004 4.481E+004

+ BI-214 609.31* 46.30 4.672E+004 4.67E+004 5.224E+004 2.096E+004 768.36 5.04 6.273E+005 -5.499E+005 2.884E+005 806.17 1.23 2.724E+006 3.685E+005 1.255E+006 934.06 3.21 1.041E+006 -1.057E+006 4.762E+005 1120.29 15.10 2.884E+005 -3.843E+004 1.338E+005 1155.19 1.69 1.969E+006 -1.100E+006 8.899E+005 1238.11 5.94 7.374E+005 2.329E+005 3.407E+005 1280.96 1.47 1.870E+006 -1.154E+006 8.196E+005 1377.67 4.11 5.814E+005 -3.461E+005 2.473E+005 1385.31 0.78 3.615E+006 1.468E+006 1.578E+006 1401.50 1.39 1.988E+006 -7.723E+005 8.644E+005 1407.98 2.48 1.240E+006 -2.669E+005 5.470E+005 1509.19 2.19 1.208E+006 2.352E+005 5.170E+005 1661.28 1.15 1.714E+006 6.537E+005 6.801E+005 1729.60 3.05 7.152E+005 -6.128E+004 2.890E+005 1764.49 15.80 2.282E+005 2.234E+004 1.007E+005 1847.44 2.12 1.143E+006 -1.006E+005 4.684E+005

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81* 6.33 7.461E+005 5.53E+004 4.566E+005 3.557E+005 77.11 10.70 7.610E+005 4.821E+005 3.709E+005 87.20 3.70 1.611E+006 1.150E+006 7.856E+005 89.80 1.03 5.611E+006 2.360E+006 2.737E+006 241.98 7.49 5.515E+005 2.910E+005 2.670E+005

Nuclide MDA Report 3/29/2019 10:08:32 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 1.923E+005 5.53E+004 1.275E+004 9.232E+004 351.92* 37.20 5.528E+004 9.989E+004 2.547E+004 785.91 1.10 3.173E+006 1.628E+006 1.469E+006

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FJFC-D48-GM.CNF Report Generated On  : 3/29/2019 10:12:57 AM Sample Title  : B1-010-001-FJFC-D48-GM Sample Description  : Rx Bowl concrete 0.5 M Sample Identification  : D48 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 7.900E-001 M^2 Sample Taken On  : 3/29/2019 8:19:00 AM Acquisition Started  : 3/29/2019 8:20:46 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_0.5M

Peak Analysis Report 3/29/2019 10:12:57 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FJFC-D48-GM Peak Analysis Performed on: 3/29/2019 10:12:57 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 295- 306 300.24 74.99 0.64 5.21E+001 39.32 1.33E+002 2 946- 961 954.32 238.65 0.71 5.10E+001 33.78 7.80E+001 3 2326- 2338 2332.78 583.44 1.12 2.70E+001 17.32 1.80E+001 4 2433- 2444 2438.19 609.80 0.53 3.90E+001 17.54 1.50E+001 5 2640- 2654 2646.42 661.87 1.11 4.32E+001 20.39 2.08E+001 6 3639- 3652 3645.07 911.54 0.41 2.14E+001 17.07 1.86E+001 7 5834- 5859 5846.12 1461.54 2.17 2.66E+002 33.36 3.02E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:12:57 AM Page 3

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Sample

Title:

B1-010-001-FJFC-D48-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.991 1460.81* 10.67 3.42392E+006 5.14214E+005 CS-137 0.999 661.65* 85.12 4.38400E+004 2.13622E+004 PB-212 0.711 74.81* 9.60 4.43820E+005 3.46341E+005 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 5.50681E+004 3.75100E+004 300.09 3.41 BI-214 0.998 609.31* 46.30 6.93381E+004 3.24219E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 8.04016E+004 6.46697E+004 964.60 5.20 969.11 16.60 1587.90 3.71

Interference Corrected Activity Report 3/29/2019 10:12:57 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:12:57 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.991 3.423920E+006 5.142145E+005 CS-137 0.999 4.384004E+004 2.136225E+004 PB-212 0.711 5.957522E+004 3.729191E+004 BI-214 0.998 6.933811E+004 3.242188E+004 AC-228 1.000 8.040162E+004 6.466971E+004

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

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

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

Peak Locate Performed on: 3/29/2019 10:12:57 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 583.44 4.4926E-002 64.25 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/29/2019 10:12:57 AM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FJFC-D48-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 1.829E+005 1.83E+005 3.424E+006 7.402E+004 CO-60 1173.22 100.00 3.355E+004 3.28E+004 8.946E+003 1.517E+004 1332.49 100.00 3.281E+004 1.214E+004 1.467E+004 CS-134 475.35 1.46 2.180E+006 4.32E+004 1.576E+006 1.024E+006 563.23 8.38 3.875E+005 1.644E+005 1.811E+005 569.32 15.43 2.118E+005 1.839E+005 9.896E+004 604.70 97.60 4.322E+004 -1.116E+004 2.048E+004 795.84 85.40 4.460E+004 -1.080E+004 2.078E+004 801.93 8.73 3.937E+005 -5.528E+004 1.819E+005 1038.57 1.00 3.367E+006 -6.484E+005 1.533E+006 1167.94 1.80 2.191E+006 1.989E+006 1.006E+006 1365.15 3.04 1.035E+006 2.476E+005 4.591E+005

+ CS-137 661.65* 85.12 2.879E+004 2.88E+004 4.384E+004 1.302E+004 EU-152 121.78 28.40 1.484E+005 1.26E+005 -2.899E+004 7.220E+004 344.27 26.50 1.263E+005 -4.377E+004 6.013E+004 1407.95 20.70 1.340E+005 -6.668E+004 5.823E+004 EU-154 123.07 40.40 1.044E+005 1.03E+005 2.481E+004 5.081E+004 722.30 20.00 1.801E+005 9.884E+004 8.391E+004 1274.51 34.40 1.026E+005 5.369E+004 4.638E+004

+ BI-214 609.31* 46.30 4.083E+004 4.08E+004 6.934E+004 1.801E+004 768.36 5.04 6.835E+005 4.935E+005 3.165E+005 806.17 1.23 2.750E+006 -1.025E+004 1.269E+006 934.06 3.21 1.112E+006 5.317E+005 5.115E+005 1120.29 15.10 2.932E+005 -2.306E+004 1.362E+005 1155.19 1.69 2.295E+006 -2.619E+005 1.053E+006 1238.11 5.94 6.655E+005 1.967E+005 3.047E+005 1280.96 1.47 2.219E+006 -1.773E+006 9.939E+005 1377.67 4.11 8.020E+005 4.878E+005 3.576E+005 1385.31 0.78 3.806E+006 -9.797E+005 1.674E+006 1401.50 1.39 2.100E+006 -1.295E+006 9.202E+005 1407.98 2.48 1.118E+006 -5.565E+005 4.861E+005 1509.19 2.19 9.633E+005 -2.062E+004 3.949E+005 1661.28 1.15 1.570E+006 5.229E+005 6.083E+005 1729.60 3.05 7.152E+005 -9.805E+005 2.890E+005 1764.49 15.80 2.229E+005 8.274E+004 9.799E+004 1847.44 2.12 9.976E+005 3.805E+005 3.959E+005

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 1.315E+006 9.76E+004 1.166E+006 6.401E+005 77.11 10.70 7.220E+005 4.333E+004 3.514E+005 87.20 3.70 1.519E+006 2.212E+005 7.397E+005 89.80 1.03 5.259E+006 6.666E+005 2.562E+006 241.98 7.49 5.298E+005 7.692E+005 2.561E+005

Nuclide MDA Report 3/29/2019 10:12:57 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 1.802E+005 9.76E+004 1.241E+005 8.629E+004 351.92 37.20 9.756E+004 9.891E+004 4.661E+004 785.91 1.10 3.200E+006 2.963E+006 1.483E+006

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FJFC-D49-GM.CNF Report Generated On  : 3/29/2019 10:15:47 AM Sample Title  : B1-010-001-FJFC-D49-GM Sample Description  : Rx Bowl concrete 0.5 M Sample Identification  : D49 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 7.900E-001 M^2 Sample Taken On  : 3/29/2019 8:33:00 AM Acquisition Started  : 3/29/2019 8:34:56 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_0.5M

Peak Analysis Report 3/29/2019 10:15:47 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FJFC-D49-GM Peak Analysis Performed on: 3/29/2019 10:15:47 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 963 954.47 238.69 1.35 5.00E+001 38.24 1.02E+002 2 2432- 2444 2437.93 609.74 0.63 2.65E+001 19.39 2.55E+001 3 2639- 2654 2646.62 661.92 1.05 1.01E+002 25.63 2.12E+001 4 5834- 5857 5846.85 1461.72 1.78 2.64E+002 33.25 3.06E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:15:47 AM Page 3

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Sample

Title:

B1-010-001-FJFC-D49-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.985 1460.81* 10.67 3.39800E+006 5.11914E+005 CS-137 0.999 661.65* 85.12 1.02334E+005 2.87817E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 5.39604E+004 4.21739E+004 300.09 3.41 BI-214 0.999 609.31* 46.30 4.70430E+004 3.49993E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:15:47 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.985 3.398002E+006 5.119138E+005 CS-137 0.999 1.023335E+005 2.878174E+004 PB-212 1.000 5.396043E+004 4.217389E+004 BI-214 0.999 4.704304E+004 3.499931E+004

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

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

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

Peak Locate Performed on: 3/29/2019 10:15:47 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/29/2019 10:15:47 AM Page 5

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FJFC-D49-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 1.844E+005 1.84E+005 3.398E+006 7.477E+004 CO-60 1173.22 100.00 3.780E+004 3.09E+004 1.012E+004 1.729E+004 1332.49 100.00 3.092E+004 6.955E+003 1.372E+004 CS-134 475.35 1.46 2.515E+006 4.17E+004 4.360E+005 1.192E+006 563.23 8.38 4.177E+005 -7.877E+004 1.962E+005 569.32 15.43 2.386E+005 6.401E+004 1.124E+005 604.70 97.60 4.171E+004 -1.635E+004 1.972E+004 795.84 85.40 4.493E+004 1.728E+004 2.094E+004 801.93 8.73 4.149E+005 2.828E+005 1.925E+005 1038.57 1.00 3.739E+006 3.314E+006 1.719E+006 1167.94 1.80 2.020E+006 8.515E+005 9.207E+005 1365.15 3.04 9.898E+005 1.615E+005 4.367E+005

+ CS-137 661.65* 85.12 2.936E+004 2.94E+004 1.023E+005 1.330E+004 EU-152 121.78 28.40 1.414E+005 1.29E+005 -5.703E+003 6.873E+004 344.27 26.50 1.289E+005 -1.273E+005 6.145E+004 1407.95 20.70 1.340E+005 -1.218E+005 5.823E+004 EU-154 123.07 40.40 9.991E+004 9.99E+004 -4.538E+004 4.856E+004 722.30 20.00 1.677E+005 -1.488E+005 7.769E+004 1274.51 34.40 1.183E+005 9.374E+004 5.422E+004

+ BI-214 609.31* 46.30 5.289E+004 5.29E+004 4.704E+004 2.404E+004 768.36 5.04 6.207E+005 -2.752E+005 2.851E+005 806.17 1.23 2.697E+006 -1.114E+006 1.242E+006 934.06 3.21 9.514E+005 1.183E+005 4.314E+005 1120.29 15.10 2.634E+005 -6.651E+004 1.213E+005 1155.19 1.69 2.111E+006 -1.871E+006 9.611E+005 1238.11 5.94 6.805E+005 5.276E+005 3.122E+005 1280.96 1.47 2.682E+006 -5.015E+005 1.225E+006 1377.67 4.11 7.369E+005 -3.311E+005 3.251E+005 1385.31 0.78 4.074E+006 7.106E+005 1.808E+006 1401.50 1.39 2.045E+006 -8.994E+004 8.927E+005 1407.98 2.48 1.118E+006 -1.017E+006 4.861E+005 1509.19 2.19 1.118E+006 5.293E+004 4.720E+005 1661.28 1.15 2.074E+006 1.046E+006 8.602E+005 1729.60 3.05 6.091E+005 2.029E+005 2.360E+005 1764.49 15.80 2.058E+005 6.685E+004 8.946E+004 1847.44 2.12 9.976E+005 3.805E+005 3.959E+005

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 1.337E+006 9.73E+004 1.202E+005 6.507E+005 77.11 10.70 7.395E+005 5.118E+004 3.602E+005 87.20 3.70 1.574E+006 6.275E+005 7.671E+005 89.80 1.03 5.464E+006 6.927E+006 2.664E+006 241.98 7.49 5.600E+005 5.407E+005 2.712E+005

Nuclide MDA Report 3/29/2019 10:15:47 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 1.812E+005 9.73E+004 1.836E+004 8.679E+004 351.92 37.20 9.726E+004 5.067E+004 4.646E+004 785.91 1.10 3.173E+006 -1.970E+006 1.469E+006

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D01-GM.CNF Report Generated On  : 3/27/2019 8:25:05 PM Sample Title  : B1-010-001-FSFC-D01-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D01 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 3:51:00 PM Acquisition Started  : 3/27/2019 3:51:48 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:25:05 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D01-GM Peak Analysis Performed on: 3/27/2019 8:25:04 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 961 953.90 238.54 0.95 5.93E+001 32.56 7.47E+001 2 1402- 1414 1407.87 352.11 1.15 2.37E+001 21.16 3.33E+001 3 2327- 2338 2332.97 583.49 1.15 2.26E+001 16.81 1.84E+001 4 2430- 2442 2436.84 609.47 0.64 3.90E+001 17.11 1.30E+001 5 3639- 3652 3645.09 911.55 0.58 2.48E+001 15.96 1.32E+001 6 5833- 5856 5845.30 1461.33 1.85 2.31E+002 31.94 6.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:25:05 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D01-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.995 1460.81* 10.67 8.32198E+004 1.34037E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.84511E+003 1.05501E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.96342E+003 8.97170E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.09224E+003 9.88826E+002 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40

Interference Corrected Activity Report 3/27/2019 8:25:05 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 1.000 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.62904E+003 1.71953E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:25:05 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.995 8.321976E+004 1.340373E+004 PB-212 1.000 1.845110E+003 1.055009E+003 BI-214 1.000 1.963417E+003 8.971696E+002 PB-214 1.000 1.092242E+003 9.888258E+002 AC-228 1.000 2.629041E+003 1.719529E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:25:04 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 583.49 3.7602E-002 74.50 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:25:05 PM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D01-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 6.784E+003 6.78E+003 8.322E+004 2.904E+003 CO-60 1173.22 100.00 1.175E+003 8.46E+002 5.886E+002 5.421E+002 1332.49 100.00 8.463E+002 -1.008E+002 3.744E+002 CS-134 475.35 1.46 6.212E+004 1.15E+003 -1.788E+004 2.919E+004 563.23 8.38 1.092E+004 1.122E+003 5.101E+003 569.32 15.43 6.009E+003 5.133E+002 2.808E+003 604.70 97.60 1.209E+003 1.163E+003 5.721E+002 795.84 85.40 1.154E+003 -3.105E+002 5.338E+002 801.93 8.73 1.123E+004 -5.680E+003 5.194E+003 1038.57 1.00 8.890E+004 -1.648E+004 4.018E+004 1167.94 1.80 6.126E+004 9.454E+003 2.811E+004 1365.15 3.04 2.347E+004 -1.040E+004 1.010E+004 CS-137 661.65 85.12 1.095E+003 1.09E+003 -1.769E+001 5.084E+002 EU-152 121.78 28.40 3.847E+003 3.70E+003 -2.337E+003 1.866E+003 344.27 26.50 3.698E+003 6.507E+002 1.763E+003 1407.95 20.70 3.958E+003 -1.181E+003 1.735E+003 EU-154 123.07 40.40 2.759E+003 2.76E+003 -9.739E+002 1.339E+003 722.30 20.00 4.658E+003 4.164E+003 2.155E+003 1274.51 34.40 2.880E+003 -2.399E+003 1.302E+003

+ BI-214 609.31* 46.30 1.104E+003 1.10E+003 1.963E+003 4.841E+002 768.36 5.04 1.864E+004 1.238E+004 8.604E+003 806.17 1.23 8.070E+004 9.802E+003 3.734E+004 934.06 3.21 2.980E+004 -1.014E+004 1.365E+004 1120.29 15.10 7.065E+003 -2.740E+003 3.238E+003 1155.19 1.69 6.964E+004 5.244E+004 3.215E+004 1238.11 5.94 1.956E+004 4.973E+003 8.992E+003 1280.96 1.47 6.445E+004 1.871E+004 2.898E+004 1377.67 4.11 2.155E+004 5.156E+003 9.560E+003 1385.31 0.78 1.275E+005 -5.069E+004 5.734E+004 1401.50 1.39 6.845E+004 -1.118E+004 3.059E+004 1407.98 2.48 3.304E+004 -9.855E+003 1.448E+004 1509.19 2.19 2.697E+004 1.257E+004 1.105E+004 1661.28 1.15 6.895E+004 4.395E+004 2.952E+004 1729.60 3.05 1.530E+004 -1.883E+004 5.727E+003 1764.49 15.80 4.638E+003 -1.701E+002 1.942E+003 1847.44 2.12 3.386E+004 1.707E+004 1.404E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.811E+004 1.55E+003 4.061E+004 1.854E+004 77.11 10.70 2.125E+004 1.807E+004 1.035E+004 87.20 3.70 4.282E+004 -1.426E+004 2.083E+004 89.80 1.03 1.492E+005 7.265E+004 7.260E+004 241.98 7.49 1.509E+004 7.951E+003 7.293E+003

Nuclide MDA Report 3/27/2019 8:25:05 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 4.839E+003 1.55E+003 -1.038E+003 2.310E+003 351.92* 37.20 1.546E+003 1.092E+003 7.105E+002 785.91 1.10 8.233E+004 -9.476E+004 3.785E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D02-GM.CNF Report Generated On  : 3/27/2019 8:27:43 PM Sample Title  : B1-010-001-FSFC-D02-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D02 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 4:04:00 PM Acquisition Started  : 3/27/2019 4:04:41 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:27:43 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D02-GM Peak Analysis Performed on: 3/27/2019 8:27:42 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 961 954.14 238.61 0.50 5.28E+001 31.78 6.62E+001 2 2241- 2252 2246.67 561.91 0.68 1.19E+001 9.07 3.10E+000 3 2324- 2340 2331.76 583.19 0.32 3.46E+001 19.20 1.84E+001 4 2432- 2443 2437.42 609.61 0.64 2.26E+001 16.33 1.74E+001 5 3637- 3650 3643.80 911.23 0.98 2.88E+001 15.79 1.22E+001 6 5832- 5856 5843.91 1460.99 1.68 2.33E+002 32.89 9.22E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:27:43 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D02-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.999 1460.81* 10.67 8.38465E+004 1.37237E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.64427E+003 1.02309E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 1.14045E+003 8.34906E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.999 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.05559E+003 1.71101E+003 964.60 5.20 969.11 16.60 1587.90 3.71

Interference Corrected Activity Report 3/27/2019 8:27:43 PM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:27:43 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.999 8.384646E+004 1.372369E+004 PB-212 1.000 1.644273E+003 1.023093E+003 BI-214 0.999 1.140447E+003 8.349064E+002 AC-228 0.999 3.055591E+003 1.711008E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:27:42 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 561.91 1.9833E-002 76.19 Tol. CS-134 3 583.19 5.7649E-002 55.51 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:27:43 PM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D02-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 8.249E+003 8.25E+003 8.385E+004 3.637E+003 CO-60 1173.22 100.00 1.293E+003 7.46E+002 1.219E+003 6.011E+002 1332.49 100.00 7.459E+002 -5.758E+001 3.243E+002 CS-134 475.35 1.46 6.757E+004 9.49E+002 2.923E+003 3.191E+004 563.23 8.38 9.811E+003 -1.556E+003 4.546E+003 569.32 15.43 5.586E+003 4.155E+003 2.596E+003 604.70 97.60 1.176E+003 1.092E+002 5.559E+002 795.84 85.40 9.494E+002 -1.261E+003 4.316E+002 801.93 8.73 1.005E+004 1.054E+004 4.600E+003 1038.57 1.00 9.899E+004 5.550E+004 4.523E+004 1167.94 1.80 6.995E+004 2.132E+004 3.245E+004 1365.15 3.04 2.568E+004 -1.972E+004 1.121E+004 CS-137 661.65 85.12 9.931E+002 9.93E+002 -5.392E+002 4.577E+002 EU-152 121.78 28.40 4.185E+003 3.60E+003 9.314E+002 2.035E+003 344.27 26.50 3.596E+003 -1.774E+003 1.712E+003 1407.95 20.70 4.157E+003 8.661E+002 1.834E+003 EU-154 123.07 40.40 2.914E+003 2.61E+003 1.266E+003 1.417E+003 722.30 20.00 4.313E+003 -6.652E+003 1.983E+003 1274.51 34.40 2.606E+003 9.856E+002 1.165E+003

+ BI-214 609.31* 46.30 1.235E+003 1.23E+003 1.140E+003 5.493E+002 768.36 5.04 1.999E+004 1.896E+004 9.280E+003 806.17 1.23 6.816E+004 -2.802E+004 3.107E+004 934.06 3.21 2.804E+004 -7.188E+003 1.277E+004 1120.29 15.10 8.291E+003 1.062E+003 3.851E+003 1155.19 1.69 6.764E+004 3.806E+004 3.115E+004 1238.11 5.94 2.131E+004 3.188E+003 9.869E+003 1280.96 1.47 5.637E+004 -2.805E+004 2.494E+004 1377.67 4.11 2.061E+004 -1.115E+004 9.093E+003 1385.31 0.78 9.832E+004 -7.124E+004 4.274E+004 1401.50 1.39 5.722E+004 2.013E+003 2.498E+004 1407.98 2.48 3.470E+004 7.229E+003 1.531E+004 1509.19 2.19 2.697E+004 -3.656E+003 1.105E+004 1661.28 1.15 4.400E+004 1.465E+004 1.704E+004 1729.60 3.05 1.863E+004 -4.548E+003 7.394E+003 1764.49 15.80 6.398E+003 5.288E+003 2.822E+003 1847.44 2.12 2.797E+004 -1.654E+004 1.110E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.618E+004 2.69E+003 -3.583E+003 1.757E+004 77.11 10.70 2.009E+004 7.272E+003 9.763E+003 87.20 3.70 4.362E+004 2.523E+004 2.123E+004 89.80 1.03 1.513E+005 1.313E+005 7.365E+004 241.98 7.49 1.448E+004 1.501E+004 6.989E+003

Nuclide MDA Report 3/27/2019 8:27:43 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 5.363E+003 2.69E+003 2.250E+003 2.572E+003 351.92 37.20 2.692E+003 2.556E+003 1.284E+003 785.91 1.10 8.569E+004 1.213E+003 3.953E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D03-GM.CNF Report Generated On  : 3/27/2019 8:29:08 PM Sample Title  : B1-010-001-FSFC-D03-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D03 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 1:56:00 PM Acquisition Started  : 3/27/2019 1:56:59 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:29:08 PM Page 2

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Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D03-GM Peak Analysis Performed on: 3/27/2019 8:29:08 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 962 954.22 238.63 0.58 2.91E+001 36.81 1.03E+002 2 1402- 1415 1407.80 352.10 0.37 4.24E+001 22.10 2.86E+001 3 2327- 2338 2332.79 583.45 0.39 1.73E+001 12.59 7.70E+000 4 3869- 3882 3875.10 969.04 0.69 1.95E+001 12.25 6.54E+000 5 5831- 5854 5843.54 1460.90 2.19 2.45E+002 32.80 6.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:29:08 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D03-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 1.000 1460.81* 10.67 8.82445E+004 1.38831E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 9.04822E+002 1.15458E+003 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.94922E+003 1.06366E+003 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60 27.70 964.60 5.20 969.11* 16.60 3.56193E+003 2.26641E+003 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:29:08 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 1.000 8.824450E+004 1.388314E+004 PB-212 1.000 9.048221E+002 1.154582E+003 PB-214 1.000 1.949217E+003 1.063659E+003 AC-228 1.000 3.561925E+003 2.266410E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:29:08 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 583.45 2.8833E-002 72.76 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:29:08 PM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D03-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 6.781E+003 6.78E+003 8.824E+004 2.903E+003 CO-60 1173.22 100.00 1.017E+003 8.65E+002 -5.651E+002 4.629E+002 1332.49 100.00 8.647E+002 2.069E+002 3.837E+002 CS-134 475.35 1.46 6.318E+004 1.13E+003 4.663E+004 2.972E+004 563.23 8.38 9.978E+003 8.110E+003 4.629E+003 569.32 15.43 5.028E+003 -5.573E+002 2.317E+003 604.70 97.60 1.203E+003 1.342E+003 5.695E+002 795.84 85.40 1.133E+003 1.395E+003 5.234E+002 801.93 8.73 1.154E+004 -8.540E+002 5.345E+003 1038.57 1.00 1.143E+005 4.764E+004 5.291E+004 1167.94 1.80 5.411E+004 3.123E+004 2.453E+004 1365.15 3.04 2.637E+004 2.090E+003 1.155E+004 CS-137 661.65 85.12 1.022E+003 1.02E+003 6.595E+002 4.721E+002 EU-152 121.78 28.40 4.027E+003 3.60E+003 4.033E+002 1.956E+003 344.27 26.50 3.596E+003 -7.235E+002 1.712E+003 1407.95 20.70 4.345E+003 -6.415E+002 1.928E+003 EU-154 123.07 40.40 2.862E+003 2.51E+003 2.098E+003 1.391E+003 722.30 20.00 5.167E+003 3.582E+003 2.410E+003 1274.51 34.40 2.506E+003 -1.159E+003 1.115E+003 BI-214 609.31 46.30 2.525E+003 2.52E+003 1.900E+003 1.194E+003 768.36 5.04 1.638E+004 9.050E+003 7.476E+003 806.17 1.23 7.702E+004 1.264E+004 3.550E+004 934.06 3.21 2.876E+004 2.929E+004 1.313E+004 1120.29 15.10 7.448E+003 5.435E+001 3.430E+003 1155.19 1.69 5.480E+004 -1.630E+004 2.473E+004 1238.11 5.94 2.055E+004 6.656E+003 9.489E+003 1280.96 1.47 6.551E+004 1.070E+003 2.951E+004 1377.67 4.11 2.200E+004 6.542E+003 9.785E+003 1385.31 0.78 1.065E+005 -1.316E+005 4.682E+004 1401.50 1.39 6.311E+004 -1.446E+004 2.793E+004 1407.98 2.48 3.627E+004 -5.355E+003 1.609E+004 1509.19 2.19 2.993E+004 -3.393E+003 1.253E+004 1661.28 1.15 5.166E+004 -6.593E+004 2.087E+004 1729.60 3.05 1.707E+004 5.685E+003 6.613E+003 1764.49 15.80 6.398E+003 5.288E+003 2.822E+003 1847.44 2.12 3.556E+004 1.920E+004 1.489E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.729E+004 1.48E+003 2.556E+004 1.813E+004 77.11 10.70 2.014E+004 6.279E+003 9.787E+003 87.20 3.70 4.404E+004 1.698E+004 2.144E+004 89.80 1.03 1.558E+005 3.870E+003 7.593E+004 241.98 7.49 1.438E+004 8.728E+003 6.935E+003

Nuclide MDA Report 3/27/2019 8:29:08 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.180E+003 1.48E+003 2.090E+003 2.480E+003 351.92* 37.20 1.476E+003 1.949E+003 6.760E+002 785.91 1.10 7.510E+004 -4.966E+004 3.423E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D04-GM.CNF Report Generated On  : 3/27/2019 8:30:18 PM Sample Title  : B1-010-001-FSFC-D04-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D04 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 2:10:00 PM Acquisition Started  : 3/27/2019 2:11:16 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:30:18 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D04-GM Peak Analysis Performed on: 3/27/2019 8:30:18 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 961 954.26 238.64 0.73 3.84E+001 31.88 7.36E+001 2 1401- 1414 1407.11 351.92 0.40 3.07E+001 20.67 2.73E+001 3 2324- 2336 2330.83 582.96 0.69 3.00E+001 19.82 2.60E+001 4 2433- 2444 2438.65 609.92 0.70 3.77E+001 13.92 4.33E+000 5 2639- 2650 2644.74 661.45 0.47 1.24E+001 15.91 1.86E+001 6 5831- 5855 5843.29 1460.83 1.46 2.38E+002 33.29 9.48E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:30:18 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D04-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 1.000 1460.81* 10.67 8.55485E+004 1.39173E+004 CS-137 0.999 661.65* 85.12 3.56348E+002 4.58498E+002 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.19401E+003 1.01036E+003 300.09 3.41 BI-214 0.997 609.31* 46.30 1.89710E+003 7.41675E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.41071E+003 9.77008E+002 785.91 1.10

Interference Corrected Activity Report 3/27/2019 8:30:18 PM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:30:18 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 1.000 8.554853E+004 1.391730E+004 CS-137 0.999 3.563483E+002 4.584976E+002 PB-212 1.000 1.194014E+003 1.010357E+003 BI-214 0.997 1.897095E+003 7.416747E+002 PB-214 1.000 1.410711E+003 9.770084E+002

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

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

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

Peak Locate Performed on: 3/27/2019 8:30:18 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 582.96 5.0000E-002 66.08 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:30:18 PM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D04-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 8.421E+003 8.42E+003 8.555E+004 3.723E+003 CO-60 1173.22 100.00 1.068E+003 9.99E+002 -9.824E+002 4.887E+002 1332.49 100.00 9.991E+002 2.730E+001 4.509E+002 CS-134 475.35 1.46 6.558E+004 1.11E+003 1.230E+004 3.092E+004 563.23 8.38 1.158E+004 5.376E+003 5.428E+003 569.32 15.43 6.552E+003 2.730E+003 3.080E+003 604.70 97.60 1.125E+003 -6.921E+002 5.305E+002 795.84 85.40 1.112E+003 -2.227E+002 5.129E+002 801.93 8.73 1.038E+004 -5.033E+003 4.769E+003 1038.57 1.00 9.023E+004 -1.478E+005 4.085E+004 1167.94 1.80 5.851E+004 -1.715E+004 2.673E+004 1365.15 3.04 2.098E+004 -1.771E+004 8.861E+003

+ CS-137 661.65* 85.12 7.509E+002 7.51E+002 3.563E+002 3.366E+002 EU-152 121.78 28.40 3.868E+003 3.77E+003 -2.247E+003 1.876E+003 344.27 26.50 3.772E+003 1.133E+003 1.800E+003 1407.95 20.70 4.157E+003 5.877E+002 1.834E+003 EU-154 123.07 40.40 2.705E+003 2.70E+003 -2.103E+003 1.312E+003 722.30 20.00 5.313E+003 4.430E+003 2.483E+003 1274.51 34.40 3.049E+003 1.728E+003 1.386E+003

+ BI-214 609.31* 46.30 6.794E+002 6.79E+002 1.897E+003 2.716E+002 768.36 5.04 1.983E+004 -1.132E+002 9.198E+003 806.17 1.23 7.925E+004 6.308E+004 3.661E+004 934.06 3.21 3.480E+004 1.229E+004 1.615E+004 1120.29 15.10 7.952E+003 -1.046E+002 3.682E+003 1155.19 1.69 5.394E+004 9.659E+003 2.430E+004 1238.11 5.94 1.894E+004 -2.368E+004 8.680E+003 1280.96 1.47 6.860E+004 -1.972E+004 3.105E+004 1377.67 4.11 1.804E+004 1.255E+004 7.806E+003 1385.31 0.78 8.930E+004 2.510E+004 3.823E+004 1401.50 1.39 5.876E+004 -2.795E+004 2.575E+004 1407.98 2.48 3.470E+004 4.906E+003 1.531E+004 1509.19 2.19 3.129E+004 5.253E+003 1.321E+004 1661.28 1.15 6.895E+004 -1.160E+004 2.952E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49 15.80 6.398E+003 2.963E+003 2.822E+003 1847.44 2.12 3.386E+004 -5.201E+003 1.404E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.837E+004 1.44E+003 3.122E+004 1.867E+004 77.11 10.70 2.082E+004 -8.133E+002 1.013E+004 87.20 3.70 4.362E+004 1.458E+004 2.123E+004 89.80 1.03 1.506E+005 7.113E+004 7.333E+004 241.98 7.49 1.413E+004 8.121E+003 6.812E+003

Nuclide MDA Report 3/27/2019 8:30:18 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 4.885E+003 1.44E+003 1.899E+003 2.333E+003 351.92* 37.20 1.445E+003 1.411E+003 6.601E+002 785.91 1.10 9.279E+004 2.222E+004 4.308E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D05-GM.CNF Report Generated On  : 3/27/2019 8:34:05 PM Sample Title  : B1-010-001-FSFC-D05-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D05 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 2:24:00 PM Acquisition Started  : 3/27/2019 2:24:27 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:34:05 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D05-GM Peak Analysis Performed on: 3/27/2019 8:34:04 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 960 954.12 238.60 0.41 3.18E+001 31.18 7.82E+001 2 1401- 1412 1406.49 351.77 0.73 3.03E+001 22.38 3.77E+001 3 2038- 2050 2043.69 511.14 1.30 3.42E+001 21.00 2.88E+001 4 2325- 2338 2331.28 583.07 0.49 3.11E+001 18.52 1.89E+001 5 2430- 2442 2436.78 609.45 0.35 2.61E+001 17.16 1.79E+001 6 5832- 5856 5843.82 1460.96 1.69 2.45E+002 32.05 2.96E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:34:05 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D05-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 1.000 1460.81* 10.67 8.82601E+004 1.36548E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 9.88705E+002 9.82869E+002 300.09 3.41 BI-214 1.000 609.31* 46.30 1.31608E+003 8.80127E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.39433E+003 1.05307E+003 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:34:05 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 1.000 8.826012E+004 1.365481E+004 PB-212 1.000 9.887050E+002 9.828690E+002 BI-214 1.000 1.316075E+003 8.801266E+002 PB-214 1.000 1.394333E+003 1.053071E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:34:04 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 511.14 5.6997E-002 61.40 4 583.07 5.1833E-002 59.55 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:34:05 PM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D05-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 5.046E+003 5.05E+003 8.826E+004 2.035E+003 CO-60 1173.22 100.00 1.152E+003 7.46E+002 1.034E+003 5.307E+002 1332.49 100.00 7.459E+002 -5.578E+002 3.243E+002 CS-134 475.35 1.46 6.177E+004 1.06E+003 -1.146E+004 2.901E+004 563.23 8.38 1.054E+004 -1.653E+004 4.910E+003 569.32 15.43 5.927E+003 -1.423E+003 2.767E+003 604.70 97.60 1.060E+003 2.338E+002 4.978E+002 795.84 85.40 1.164E+003 -1.037E+002 5.389E+002 801.93 8.73 1.134E+004 -4.599E+002 5.245E+003 1038.57 1.00 9.779E+004 2.344E+002 4.463E+004 1167.94 1.80 5.851E+004 3.088E+004 2.673E+004 1365.15 3.04 2.568E+004 9.034E+002 1.121E+004 CS-137 661.65 85.12 1.012E+003 1.01E+003 2.220E+002 4.673E+002 EU-152 121.78 28.40 4.261E+003 3.15E+003 1.552E+003 2.073E+003 344.27 26.50 3.505E+003 1.952E+002 1.666E+003 1407.95 20.70 3.150E+003 1.808E+003 1.330E+003 EU-154 123.07 40.40 2.965E+003 2.84E+003 8.934E+002 1.442E+003 722.30 20.00 5.016E+003 -2.762E+003 2.334E+003 1274.51 34.40 2.837E+003 -1.533E+002 1.280E+003

+ BI-214 609.31* 46.30 1.277E+003 1.28E+003 1.316E+003 5.706E+002 768.36 5.04 1.898E+004 1.572E+003 8.778E+003 806.17 1.23 8.070E+004 -6.677E+003 3.734E+004 934.06 3.21 2.692E+004 2.298E+004 1.221E+004 1120.29 15.10 7.882E+003 8.758E+002 3.647E+003 1155.19 1.69 5.565E+004 2.678E+004 2.515E+004 1238.11 5.94 1.915E+004 6.840E+003 8.785E+003 1280.96 1.47 6.114E+004 1.698E+003 2.732E+004 1377.67 4.11 2.061E+004 -1.031E+004 9.093E+003 1385.31 0.78 1.065E+005 -2.655E+004 4.682E+004 1401.50 1.39 5.563E+004 -8.947E+001 2.418E+004 1407.98 2.48 2.629E+004 1.509E+004 1.110E+004 1509.19 2.19 3.613E+004 -2.906E+004 1.563E+004 1661.28 1.15 3.943E+004 1.099E+004 1.476E+004 1729.60 3.05 2.255E+004 1.137E+004 9.353E+003 1764.49 15.80 6.687E+003 1.183E+003 2.967E+003 1847.44 2.12 3.204E+004 -2.081E+004 1.313E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.672E+004 1.60E+003 8.716E+003 1.784E+004 77.11 10.70 2.059E+004 2.072E+003 1.001E+004 87.20 3.70 4.385E+004 1.715E+004 2.135E+004 89.80 1.03 1.500E+005 -2.557E+004 7.300E+004 241.98 7.49 1.440E+004 6.679E+003 6.949E+003

Nuclide MDA Report 3/27/2019 8:34:05 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 4.915E+003 1.60E+003 -1.809E+003 2.348E+003 351.92* 37.20 1.598E+003 1.394E+003 7.369E+002 785.91 1.10 8.813E+004 6.877E+003 4.075E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D06-GM.CNF Report Generated On  : 3/27/2019 8:35:33 PM Sample Title  : B1-010-001-FSFC-D06-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D06 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 2:48:00 PM Acquisition Started  : 3/27/2019 2:49:06 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:35:33 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D06-GM Peak Analysis Performed on: 3/27/2019 8:35:33 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 367- 378 371.93 92.93 1.09 3.53E+001 35.84 1.14E+002 2 946- 961 955.12 238.85 1.03 5.48E+001 35.47 8.62E+001 3 1402- 1413 1407.47 352.01 0.38 3.17E+001 19.37 2.43E+001 4 1730- 1741 1735.75 434.13 0.78 1.42E+001 10.79 5.82E+000 5 2326- 2338 2331.95 583.23 0.59 2.08E+001 16.90 1.93E+001 6 5833- 5856 5844.08 1461.03 2.10 2.10E+002 31.05 8.22E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:35:33 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D06-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.999 1460.81* 10.67 7.55654E+004 1.28076E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.70753E+003 1.13741E+003 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.45801E+003 9.21153E+002 785.91 1.10 PA-234 0.994 94.67* 15.50 3.37392E+003 3.48891E+003 98.44 25.10 111.00 8.55 131.28 20.00 152.70 7.20 226.87 6.50 569.26 10.40 733.00 8.50 883.24 12.00 946.00 20.00 949.00 7.80

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:35:33 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.999 7.556540E+004 1.280759E+004 PB-212 1.000 1.707528E+003 1.137406E+003 PB-214 1.000 1.458007E+003 9.211533E+002 PA-234 0.994 3.373922E+003 3.488915E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:35:33 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 4 434.13 2.3625E-002 76.10 5 583.23 3.4583E-002 81.45 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:35:33 PM Page 5

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D06-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 7.593E+003 7.59E+003 7.557E+004 3.309E+003 CO-60 1173.22 100.00 1.043E+003 8.08E+002 4.832E+002 4.760E+002 1332.49 100.00 8.078E+002 6.478E+002 3.552E+002 CS-134 475.35 1.46 6.212E+004 1.16E+003 -3.792E+004 2.919E+004 563.23 8.38 1.129E+004 -6.146E+003 5.285E+003 569.32 15.43 6.209E+003 -1.530E+003 2.908E+003 604.70 97.60 1.187E+003 1.504E+003 5.613E+002 795.84 85.40 1.164E+003 -3.084E+002 5.389E+002 801.93 8.73 1.071E+004 -5.276E+003 4.933E+003 1038.57 1.00 8.335E+004 -6.034E+004 3.741E+004 1167.94 1.80 5.636E+004 -2.004E+004 2.566E+004 1365.15 3.04 2.496E+004 9.475E+003 1.085E+004 CS-137 661.65 85.12 1.068E+003 1.07E+003 4.367E+002 4.951E+002 EU-152 121.78 28.40 4.131E+003 3.57E+003 1.597E+002 2.008E+003 344.27 26.50 3.570E+003 2.058E+003 1.699E+003 1407.95 20.70 3.958E+003 2.260E+002 1.735E+003 EU-154 123.07 40.40 2.876E+003 2.65E+003 -4.856E+002 1.398E+003 722.30 20.00 5.313E+003 -5.684E+003 2.483E+003 1274.51 34.40 2.654E+003 -3.229E+003 1.189E+003 BI-214 609.31 46.30 2.283E+003 2.28E+003 1.573E+003 1.073E+003 768.36 5.04 1.810E+004 -3.388E+003 8.336E+003 806.17 1.23 7.152E+004 1.920E+004 3.275E+004 934.06 3.21 3.048E+004 3.896E+004 1.398E+004 1120.29 15.10 8.291E+003 6.300E+003 3.851E+003 1155.19 1.69 5.890E+004 6.909E+003 2.678E+004 1238.11 5.94 2.187E+004 9.432E+003 1.014E+004 1280.96 1.47 6.337E+004 5.648E+003 2.844E+004 1377.67 4.11 2.287E+004 -1.183E+004 1.022E+004 1385.31 0.78 1.038E+005 -1.466E+005 4.550E+004 1401.50 1.39 5.876E+004 2.822E+004 2.575E+004 1407.98 2.48 3.304E+004 1.887E+003 1.448E+004 1509.19 2.19 2.850E+004 3.143E+003 1.182E+004 1661.28 1.15 5.500E+004 2.564E+004 2.254E+004 1729.60 3.05 2.255E+004 -7.551E+002 9.353E+003 1764.49 15.80 5.768E+003 4.175E+003 2.508E+003 1847.44 2.12 3.870E+004 -1.145E+004 1.646E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.879E+004 1.32E+003 6.038E+004 1.888E+004 77.11 10.70 2.070E+004 -8.324E+002 1.007E+004 87.20 3.70 4.205E+004 8.748E+003 2.045E+004 89.80 1.03 1.490E+005 2.494E+004 7.252E+004 241.98 7.49 1.475E+004 1.486E+004 7.123E+003

Nuclide MDA Report 3/27/2019 8:35:33 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.093E+003 1.32E+003 3.541E+003 2.437E+003 351.92* 37.20 1.317E+003 1.458E+003 5.964E+002 785.91 1.10 9.429E+004 -6.578E+003 4.382E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D07-GM.CNF Report Generated On  : 3/27/2019 8:38:30 PM Sample Title  : B1-010-001-FSFC-D07-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D07 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 3:00:00 PM Acquisition Started  : 3/27/2019 3:01:05 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:38:30 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D07-GM Peak Analysis Performed on: 3/27/2019 8:38:30 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 949- 960 954.18 238.61 0.79 5.41E+001 27.90 5.49E+001 2 1108- 1120 1113.16 278.39 0.51 2.95E+001 18.61 2.15E+001 3 2034- 2052 2040.92 510.45 0.63 5.69E+001 26.22 3.41E+001 4 2325- 2339 2331.77 583.19 0.34 3.52E+001 18.27 1.68E+001 5 2430- 2443 2436.51 609.38 0.83 3.69E+001 16.75 1.21E+001 6 3637- 3650 3643.26 911.09 0.57 3.74E+001 15.62 8.60E+000 7 5832- 5855 5844.24 1461.07 1.68 2.33E+002 34.15 1.46E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:38:30 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D07-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.999 1460.81* 10.67 8.40820E+004 1.41266E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.68304E+003 9.08872E+002 300.09 3.41 BI-214 1.000 609.31* 46.30 1.85745E+003 8.76162E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.999 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.96558E+003 1.71820E+003 964.60 5.20 969.11 16.60 1587.90 3.71

Interference Corrected Activity Report 3/27/2019 8:38:30 PM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:38:30 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.999 8.408196E+004 1.412660E+004 PB-212 1.000 1.683045E+003 9.088725E+002 BI-214 1.000 1.857446E+003 8.761620E+002 AC-228 0.999 3.965578E+003 1.718204E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:38:30 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 278.39 4.9126E-002 63.15 3 510.45 9.4821E-002 46.10 4 583.19 5.8694E-002 51.88 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:38:30 PM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D07-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 1.001E+004 1.00E+004 8.408E+004 4.517E+003 CO-60 1173.22 100.00 1.152E+003 8.27E+002 -4.991E+002 5.307E+002 1332.49 100.00 8.273E+002 -4.139E+002 3.650E+002 CS-134 475.35 1.46 5.410E+004 1.13E+003 -3.810E+003 2.517E+004 563.23 8.38 1.129E+004 5.118E+003 5.285E+003 569.32 15.43 6.913E+003 6.173E+003 3.260E+003 604.70 97.60 1.125E+003 -5.464E+002 5.305E+002 795.84 85.40 1.184E+003 -2.183E+002 5.490E+002 801.93 8.73 1.202E+004 1.541E+003 5.587E+003 1038.57 1.00 9.154E+004 7.998E+004 4.150E+004 1167.94 1.80 5.781E+004 -1.631E+004 2.638E+004 1365.15 3.04 2.098E+004 -4.198E+004 8.861E+003 CS-137 661.65 85.12 1.068E+003 1.07E+003 -7.019E+002 4.951E+002 EU-152 121.78 28.40 3.920E+003 3.45E+003 -3.538E+003 1.902E+003 344.27 26.50 3.452E+003 1.804E+002 1.639E+003 1407.95 20.70 4.436E+003 3.978E+003 1.973E+003 EU-154 123.07 40.40 2.810E+003 2.81E+003 1.180E+003 1.364E+003 722.30 20.00 5.593E+003 3.627E+003 2.623E+003 1274.51 34.40 2.837E+003 -5.902E+001 1.280E+003

+ BI-214 609.31* 46.30 1.091E+003 1.09E+003 1.857E+003 4.776E+002 768.36 5.04 2.079E+004 3.698E+003 9.678E+003 806.17 1.23 7.626E+004 -1.935E+002 3.512E+004 934.06 3.21 2.946E+004 -1.231E+004 1.348E+004 1120.29 15.10 7.740E+003 2.943E+003 3.576E+003 1155.19 1.69 6.415E+004 -1.212E+004 2.941E+004 1238.11 5.94 1.807E+004 -5.449E+003 8.246E+003 1280.96 1.47 5.999E+004 -1.798E+004 2.675E+004 1377.67 4.11 2.244E+004 4.835E+003 1.000E+004 1385.31 0.78 1.090E+005 -1.548E+004 4.810E+004 1401.50 1.39 5.563E+004 2.657E+004 2.418E+004 1407.98 2.48 3.702E+004 3.321E+004 1.647E+004 1509.19 2.19 3.258E+004 6.123E+003 1.386E+004 1661.28 1.15 5.166E+004 2.198E+004 2.087E+004 1729.60 3.05 2.005E+004 -4.205E+003 8.100E+003 1764.49 15.80 6.544E+003 5.566E+003 2.896E+003 1847.44 2.12 3.386E+004 -8.869E+003 1.404E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.772E+004 2.59E+003 3.704E+004 1.834E+004 77.11 10.70 2.030E+004 -6.488E+003 9.870E+003 87.20 3.70 4.367E+004 1.065E+004 2.125E+004 89.80 1.03 1.490E+005 -2.542E+004 7.252E+004 241.98 7.49 1.454E+004 1.842E+004 7.016E+003

Nuclide MDA Report 3/27/2019 8:38:30 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 4.792E+003 2.59E+003 -1.324E+003 2.286E+003 351.92 37.20 2.592E+003 3.942E+001 1.234E+003 785.91 1.10 8.651E+004 -1.644E+004 3.994E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D08-GM.CNF Report Generated On  : 3/27/2019 8:40:19 PM Sample Title  : B1-010-001-FSFC-D08-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D08 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 3:12:00 PM Acquisition Started  : 3/27/2019 3:13:36 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:40:19 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D08-GM Peak Analysis Performed on: 3/27/2019 8:40:19 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 964 953.76 238.51 0.68 6.32E+001 35.46 7.68E+001 2 1402- 1415 1408.72 352.33 0.81 3.97E+001 21.82 2.83E+001 3 2327- 2338 2332.56 583.39 1.47 2.28E+001 19.45 2.72E+001 4 2431- 2443 2436.48 609.38 0.42 3.09E+001 19.66 2.41E+001 5 3637- 3650 3643.59 911.17 0.73 2.28E+001 17.39 1.92E+001 6 5833- 5855 5844.50 1461.13 1.30 2.10E+002 30.50 5.75E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:40:19 PM Page 3

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

Sample

Title:

B1-010-001-FSFC-D08-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.998 1460.81* 10.67 7.57370E+004 1.26436E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.96598E+003 1.14715E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.55413E+003 1.00934E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.82731E+003 1.04579E+003 785.91 1.10 AC-228 0.999 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40

Interference Corrected Activity Report 3/27/2019 8:40:19 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.999 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.41977E+003 1.86471E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:40:19 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.998 7.573698E+004 1.264356E+004 PB-212 1.000 1.965977E+003 1.147153E+003 BI-214 1.000 1.554125E+003 1.009343E+003 PB-214 0.999 1.827312E+003 1.045788E+003 AC-228 0.999 2.419773E+003 1.864711E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:40:19 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 583.39 3.8000E-002 85.31 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:40:20 PM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D08-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 6.573E+003 6.57E+003 7.574E+004 2.799E+003 CO-60 1173.22 100.00 1.175E+003 9.51E+002 -1.843E+002 5.421E+002 1332.49 100.00 9.512E+002 -6.776E+002 4.269E+002 CS-134 475.35 1.46 5.958E+004 1.10E+003 -3.321E+003 2.791E+004 563.23 8.38 1.158E+004 2.037E+003 5.428E+003 569.32 15.43 6.440E+003 3.428E+003 3.023E+003 604.70 97.60 1.182E+003 -1.096E+003 5.586E+002 795.84 85.40 1.101E+003 6.205E+002 5.075E+002 801.93 8.73 1.016E+004 3.153E+003 4.657E+003 1038.57 1.00 8.618E+004 -4.246E+004 3.882E+004 1167.94 1.80 6.058E+004 6.548E+003 2.777E+004 1365.15 3.04 2.832E+004 5.721E+003 1.253E+004 CS-137 661.65 85.12 1.129E+003 1.13E+003 -3.257E+002 5.257E+002 EU-152 121.78 28.40 4.057E+003 3.65E+003 8.439E+002 1.971E+003 344.27 26.50 3.647E+003 1.678E+003 1.737E+003 1407.95 20.70 3.958E+003 2.260E+002 1.735E+003 EU-154 123.07 40.40 2.838E+003 2.84E+003 7.195E+002 1.378E+003 722.30 20.00 4.740E+003 5.946E+003 2.196E+003 1274.51 34.40 2.966E+003 2.396E+003 1.345E+003

+ BI-214 609.31* 46.30 1.479E+003 1.48E+003 1.554E+003 6.714E+002 768.36 5.04 2.200E+004 8.340E+003 1.028E+004 806.17 1.23 6.902E+004 -1.185E+004 3.150E+004 934.06 3.21 3.178E+004 1.593E+004 1.463E+004 1120.29 15.10 7.811E+003 6.187E+003 3.612E+003 1155.19 1.69 6.270E+004 1.708E+003 2.868E+004 1238.11 5.94 1.956E+004 7.866E+003 8.992E+003 1280.96 1.47 7.248E+004 4.735E+004 3.300E+004 1377.67 4.11 2.287E+004 -5.829E+003 1.022E+004 1385.31 0.78 1.187E+005 1.091E+005 5.293E+004 1401.50 1.39 5.563E+004 4.026E+004 2.418E+004 1407.98 2.48 3.304E+004 1.887E+003 1.448E+004 1509.19 2.19 3.499E+004 -3.661E+003 1.507E+004 1661.28 1.15 3.401E+004 7.326E+003 1.205E+004 1729.60 3.05 2.255E+004 1.137E+004 9.353E+003 1764.49 15.80 7.097E+003 4.201E+003 3.172E+003 1847.44 2.12 4.017E+004 2.561E+004 1.720E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.772E+004 1.47E+003 5.659E+004 1.834E+004 77.11 10.70 2.077E+004 2.223E+004 1.010E+004 87.20 3.70 4.431E+004 1.686E+003 2.158E+004 89.80 1.03 1.530E+005 -3.363E+004 7.452E+004 241.98 7.49 1.446E+004 1.941E+004 6.976E+003

Nuclide MDA Report 3/27/2019 8:40:20 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.020E+003 1.47E+003 1.541E+003 2.400E+003 351.92* 37.20 1.473E+003 1.827E+003 6.742E+002 785.91 1.10 7.790E+004 -2.585E+004 3.563E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D09-GM.CNF Report Generated On  : 3/27/2019 8:42:37 PM Sample Title  : B1-010-001-FSFC-D09-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D09 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 3:24:00 PM Acquisition Started  : 3/27/2019 3:26:28 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:42:38 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D09-GM Peak Analysis Performed on: 3/27/2019 8:42:37 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 1402- 1413 1407.61 352.05 0.82 2.80E+001 19.55 2.70E+001 2 2037- 2049 2043.60 511.12 0.90 2.40E+001 22.55 3.90E+001 3 2326- 2337 2331.49 583.12 0.39 1.76E+001 16.27 1.94E+001 4 2431- 2442 2436.10 609.28 0.53 2.25E+001 18.09 2.35E+001 5 5834- 5856 5844.61 1461.16 1.18 2.24E+002 31.61 6.26E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:42:38 PM Page 3

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

Sample

Title:

B1-010-001-FSFC-D09-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.998 1460.81* 10.67 8.05979E+004 1.31902E+004 BI-214 1.000 609.31* 46.30 1.13364E+003 9.22163E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.28805E+003 9.22427E+002 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:42:38 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.998 8.059794E+004 1.319019E+004 BI-214 1.000 1.133636E+003 9.221627E+002 PB-214 1.000 1.288046E+003 9.224265E+002

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

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

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

Peak Locate Performed on: 3/27/2019 8:42:37 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 511.12 3.9987E-002 94.01 3 583.12 2.9291E-002 92.58 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:42:38 PM Page 5

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D09-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 7.021E+003 7.02E+003 8.060E+004 3.023E+003 CO-60 1173.22 100.00 1.081E+003 9.35E+002 1.066E+002 4.949E+002 1332.49 100.00 9.346E+002 -1.979E+002 4.186E+002 CS-134 475.35 1.46 6.032E+004 1.07E+003 -3.103E+004 2.828E+004 563.23 8.38 1.046E+004 2.425E+003 4.871E+003 569.32 15.43 5.802E+003 2.041E+003 2.704E+003 604.70 97.60 1.209E+003 6.538E+002 5.721E+002 795.84 85.40 1.068E+003 8.316E+001 4.910E+002 801.93 8.73 1.060E+004 -5.523E+002 4.879E+003 1038.57 1.00 1.164E+005 5.344E+004 5.391E+004 1167.94 1.80 5.334E+004 -1.380E+004 2.415E+004 1365.15 3.04 2.704E+004 -6.625E+003 1.189E+004 CS-137 661.65 85.12 1.112E+003 1.11E+003 7.554E+002 5.171E+002 EU-152 121.78 28.40 3.956E+003 3.48E+003 -6.780E+002 1.920E+003 344.27 26.50 3.478E+003 -2.214E+003 1.653E+003 1407.95 20.70 4.157E+003 1.142E+002 1.834E+003 EU-154 123.07 40.40 2.799E+003 2.80E+003 2.203E+003 1.359E+003 722.30 20.00 4.268E+003 -4.202E+003 1.960E+003 1274.51 34.40 2.837E+003 2.963E+003 1.280E+003

+ BI-214 609.31* 46.30 1.412E+003 1.41E+003 1.134E+003 6.377E+002 768.36 5.04 2.110E+004 1.202E+004 9.833E+003 806.17 1.23 6.816E+004 -1.199E+004 3.107E+004 934.06 3.21 2.730E+004 -2.902E+003 1.240E+004 1120.29 15.10 7.596E+003 7.443E+003 3.504E+003 1155.19 1.69 6.627E+004 -4.711E+002 3.046E+004 1238.11 5.94 1.894E+004 1.121E+004 8.680E+003 1280.96 1.47 5.881E+004 2.398E+004 2.616E+004 1377.67 4.11 2.061E+004 -4.260E+003 9.093E+003 1385.31 0.78 9.832E+004 -1.278E+005 4.274E+004 1401.50 1.39 5.876E+004 -3.624E+004 2.575E+004 1407.98 2.48 3.470E+004 9.533E+002 1.531E+004 1509.19 2.19 3.258E+004 -2.208E+004 1.386E+004 1661.28 1.15 5.500E+004 2.564E+004 2.254E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49 15.80 5.422E+003 1.194E+003 2.334E+003 1847.44 2.12 2.297E+004 6.402E+003 8.598E+003

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.879E+004 1.37E+003 -1.217E+004 1.888E+004 77.11 10.70 2.181E+004 2.265E+004 1.062E+004 87.20 3.70 4.196E+004 -3.801E+004 2.040E+004 89.80 1.03 1.477E+005 -4.014E+004 7.187E+004 241.98 7.49 1.435E+004 -4.015E+003 6.921E+003

Nuclide MDA Report 3/27/2019 8:42:38 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.049E+003 1.37E+003 5.674E+003 2.415E+003 351.92* 37.20 1.368E+003 1.288E+003 6.217E+002 785.91 1.10 7.510E+004 -2.863E+004 3.423E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D10-GM.CNF Report Generated On  : 3/27/2019 8:44:50 PM Sample Title  : B1-010-001-FSFC-D10-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D10 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 3:38:00 PM Acquisition Started  : 3/27/2019 3:39:27 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:44:50 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D10-GM Peak Analysis Performed on: 3/27/2019 8:44:50 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 294- 304 299.78 74.88 0.42 3.75E+001 35.23 1.14E+002 2 1228- 1239 1233.23 308.43 0.26 1.35E+001 16.71 2.25E+001 3 1403- 1414 1408.20 352.20 0.92 2.82E+001 20.28 2.98E+001 4 2325- 2338 2331.55 583.14 1.69 3.50E+001 17.25 1.30E+001 5 2429- 2443 2436.08 609.27 0.75 4.80E+001 19.12 1.50E+001 6 3639- 3652 3645.34 911.61 0.85 2.12E+001 13.38 7.76E+000 7 5833- 5857 5844.75 1461.20 1.49 2.50E+002 34.97 1.42E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:44:50 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D10-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.997 1460.81* 10.67 8.99765E+004 1.46260E+004 BI-214 1.000 609.31* 46.30 2.41608E+003 1.01102E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.625 74.81* 6.33 1.43004E+004 1.37424E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.29785E+003 9.55855E+002 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.25283E+003 1.44228E+003 964.60 5.20 969.11 16.60 1587.90 3.71

Interference Corrected Activity Report 3/27/2019 8:44:50 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:44:50 PM Page 5

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.997 8.997647E+004 1.462597E+004 BI-214 1.000 2.416080E+003 1.011022E+003 PB-214 0.625 1.360457E+003 9.535513E+002 AC-228 1.000 2.252832E+003 1.442279E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:44:50 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 308.43 2.2512E-002 123.71 4 583.14 5.8325E-002 49.29 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:44:50 PM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D10-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 9.835E+003 9.84E+003 8.998E+004 4.430E+003 CO-60 1173.22 100.00 1.105E+003 8.46E+002 1.113E+002 5.071E+002 1332.49 100.00 8.463E+002 1.431E+002 3.744E+002 CS-134 475.35 1.46 5.883E+004 1.08E+003 -1.502E+004 2.754E+004 563.23 8.38 1.014E+004 -8.718E+003 4.711E+003 569.32 15.43 5.497E+003 1.876E+003 2.552E+003 604.70 97.60 1.219E+003 -1.152E+003 5.775E+002 795.84 85.40 1.079E+003 -3.500E+001 4.966E+002 801.93 8.73 9.574E+003 -7.134E+003 4.364E+003 1038.57 1.00 9.534E+004 -5.722E+003 4.340E+004 1167.94 1.80 6.126E+004 4.987E+004 2.811E+004 1365.15 3.04 3.014E+004 1.822E+004 1.344E+004 CS-137 661.65 85.12 1.077E+003 1.08E+003 4.215E+002 4.996E+002 EU-152 121.78 28.40 3.951E+003 3.50E+003 2.617E+003 1.918E+003 344.27 26.50 3.505E+003 -1.455E+003 1.666E+003 1407.95 20.70 4.059E+003 -1.007E+003 1.785E+003 EU-154 123.07 40.40 2.759E+003 2.76E+003 5.932E+002 1.339E+003 722.30 20.00 4.781E+003 1.792E+003 2.217E+003 1274.51 34.40 2.966E+003 1.076E+003 1.345E+003

+ BI-214 609.31* 46.30 1.227E+003 1.23E+003 2.416E+003 5.456E+002 768.36 5.04 1.864E+004 -8.006E+002 8.604E+003 806.17 1.23 6.641E+004 -2.321E+004 3.019E+004 934.06 3.21 3.241E+004 4.870E+003 1.495E+004 1120.29 15.10 7.882E+003 4.502E+003 3.647E+003 1155.19 1.69 6.557E+004 4.889E+003 3.012E+004 1238.11 5.94 2.016E+004 1.899E+004 9.293E+003 1280.96 1.47 6.226E+004 4.963E+003 2.789E+004 1377.67 4.11 2.155E+004 5.156E+003 9.560E+003 1385.31 0.78 1.140E+005 5.676E+004 5.057E+004 1401.50 1.39 5.876E+004 -3.193E+004 2.575E+004 1407.98 2.48 3.388E+004 -8.406E+003 1.490E+004 1509.19 2.19 3.129E+004 -1.033E+004 1.321E+004 1661.28 1.15 5.500E+004 -3.388E+004 2.254E+004 1729.60 3.05 2.859E+004 -3.198E+003 1.237E+004 1764.49 15.80 7.097E+003 6.680E+003 3.172E+003 1847.44 2.12 3.556E+004 2.075E+003 1.489E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81* 6.33 2.177E+004 1.43E+003 1.430E+004 1.037E+004 77.11 10.70 2.150E+004 2.043E+004 1.047E+004 87.20 3.70 4.181E+004 -3.015E+004 2.033E+004 89.80 1.03 1.439E+005 -7.482E+004 6.996E+004 241.98 7.49 1.470E+004 8.014E+003 7.096E+003

Nuclide MDA Report 3/27/2019 8:44:50 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 4.990E+003 1.43E+003 -8.589E+002 2.385E+003 351.92* 37.20 1.432E+003 1.298E+003 6.537E+002 785.91 1.10 8.651E+004 2.615E+003 3.994E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D11-GM.CNF Report Generated On  : 3/27/2019 8:46:25 PM Sample Title  : B1-010-001-FSFC-D11-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D11 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 10:53:00 AM Acquisition Started  : 3/27/2019 10:53:21 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:46:25 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D11-GM Peak Analysis Performed on: 3/27/2019 8:46:25 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 963 955.67 238.99 0.41 7.35E+001 33.29 6.65E+001 2 1404- 1415 1409.58 352.54 0.41 2.97E+001 20.80 3.13E+001 3 2327- 2343 2335.28 584.07 0.99 3.90E+001 20.45 2.10E+001 4 2435- 2447 2440.89 610.48 0.52 3.34E+001 16.06 1.16E+001 5 5840- 5865 5853.02 1463.26 1.19 2.62E+002 33.15 3.11E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:46:25 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D11-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.899 1460.81* 10.67 9.44382E+004 1.42740E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.28791E+003 1.09929E+003 300.09 3.41 BI-214 0.990 609.31* 46.30 1.68420E+003 8.37649E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.610 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98* 7.49 1.36236E+004 6.54586E+003 295.21 19.20 351.92* 37.20 1.36769E+003 9.82184E+002 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:46:25 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.899 9.443817E+004 1.427399E+004 PB-212 0.999 2.058228E+003 1.111599E+003 BI-214 0.990 1.684204E+003 8.376486E+002 PB-214 0.610 1.367695E+003 9.821836E+002

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

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

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

Peak Locate Performed on: 3/27/2019 8:46:25 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 584.07 6.5028E-002 52.42 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:46:25 PM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D11-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 5.221E+003 5.22E+003 9.444E+004 2.123E+003 CO-60 1173.22 100.00 1.164E+003 7.67E+002 8.270E+002 5.365E+002 1332.49 100.00 7.672E+002 -9.863E+002 3.349E+002 CS-134 475.35 1.46 5.572E+004 1.03E+003 1.631E+003 2.599E+004 563.23 8.38 1.100E+004 1.396E+003 5.139E+003 569.32 15.43 6.287E+003 5.493E+003 2.947E+003 604.70 97.60 1.108E+003 -9.969E+002 5.218E+002 795.84 85.40 1.034E+003 -1.081E+003 4.740E+002 801.93 8.73 1.134E+004 1.554E+003 5.245E+003 1038.57 1.00 1.048E+005 1.760E+003 4.811E+004 1167.94 1.80 5.851E+004 -6.679E+004 2.673E+004 1365.15 3.04 2.185E+004 1.643E+003 9.294E+003 CS-137 661.65 85.12 1.129E+003 1.13E+003 -7.576E+002 5.257E+002 EU-152 121.78 28.40 3.930E+003 3.38E+003 -1.293E+003 1.908E+003 344.27 26.50 3.384E+003 -2.593E+003 1.606E+003 1407.95 20.70 4.059E+003 1.831E+003 1.785E+003 EU-154 123.07 40.40 2.749E+003 2.70E+003 -5.296E+002 1.334E+003 722.30 20.00 5.349E+003 2.737E+003 2.501E+003 1274.51 34.40 2.701E+003 -4.598E+002 1.212E+003

+ BI-214 609.31* 46.30 1.061E+003 1.06E+003 1.684E+003 4.622E+002 768.36 5.04 2.110E+004 1.568E+004 9.833E+003 806.17 1.23 7.314E+004 3.227E+004 3.356E+004 934.06 3.21 3.146E+004 -1.074E+004 1.447E+004 1120.29 15.10 7.882E+003 6.293E+003 3.647E+003 1155.19 1.69 6.270E+004 -1.564E+004 2.868E+004 1238.11 5.94 2.016E+004 2.320E+004 9.293E+003 1280.96 1.47 5.637E+004 -2.517E+004 2.494E+004 1377.67 4.11 2.200E+004 1.239E+004 9.785E+003 1385.31 0.78 1.011E+005 -1.927E+004 4.414E+004 1401.50 1.39 5.229E+004 -2.824E+004 2.251E+004 1407.98 2.48 3.388E+004 1.528E+004 1.490E+004 1509.19 2.19 3.258E+004 1.225E+002 1.386E+004 1661.28 1.15 6.104E+004 6.105E+003 2.556E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49 15.80 6.687E+003 5.845E+003 2.967E+003 1847.44 2.12 3.556E+004 1.920E+004 1.489E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.605E+004 1.47E+003 1.271E+004 1.751E+004 77.11 10.70 1.977E+004 -4.661E+003 9.606E+003 87.20 3.70 4.385E+004 1.394E+004 2.135E+004 89.80 1.03 1.503E+005 1.781E+004 7.316E+004 241.98* 7.49 9.205E+003 1.362E+004 4.352E+003

Nuclide MDA Report 3/27/2019 8:46:25 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.223E+003 1.47E+003 1.341E+003 2.502E+003 351.92* 37.20 1.466E+003 1.368E+003 6.707E+002 785.91 1.10 7.970E+004 -1.576E+004 3.653E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D12-GM.CNF Report Generated On  : 3/27/2019 8:47:58 PM Sample Title  : B1-010-001-FSFC-D12-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D12 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 11:07:00 AM Acquisition Started  : 3/27/2019 11:07:30 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:47:58 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D12-GM Peak Analysis Performed on: 3/27/2019 8:47:58 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 306 300.16 74.97 0.71 2.84E+001 34.22 1.10E+002 2 1402- 1413 1407.78 352.09 0.34 2.32E+001 21.25 3.58E+001 3 2430- 2445 2437.14 609.54 0.79 4.84E+001 18.21 1.16E+001 4 3639- 3652 3645.16 911.57 0.70 1.37E+001 16.77 2.03E+001 5 5832- 5858 5845.10 1461.28 2.00 2.65E+002 33.47 3.46E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:47:58 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D12-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.996 1460.81* 10.67 9.52989E+004 1.44002E+004 BI-214 1.000 609.31* 46.30 2.43850E+003 9.68542E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.626 74.81* 6.33 1.07960E+004 1.31881E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.06590E+003 9.92235E+002 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 1.44891E+003 1.78652E+003 964.60 5.20 969.11 16.60 1587.90 3.71

Interference Corrected Activity Report 3/27/2019 8:47:58 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:47:58 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.996 9.529887E+004 1.440018E+004 BI-214 1.000 2.438496E+003 9.685424E+002 PB-214 0.626 1.120671E+003 9.894385E+002 AC-228 1.000 1.448909E+003 1.786520E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:47:58 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/27/2019 8:47:58 PM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D12-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 5.643E+003 5.64E+003 9.530E+004 2.334E+003 CO-60 1173.22 100.00 9.624E+002 9.00E+002 -4.891E+002 4.357E+002 1332.49 100.00 9.005E+002 5.289E+002 4.015E+002 CS-134 475.35 1.46 5.845E+004 1.20E+003 -1.841E+004 2.735E+004 563.23 8.38 1.179E+004 4.522E+003 5.533E+003 569.32 15.43 5.802E+003 -3.669E+003 2.704E+003 604.70 97.60 1.203E+003 -4.577E+002 5.695E+002 795.84 85.40 1.223E+003 5.295E+002 5.686E+002 801.93 8.73 1.173E+004 -9.834E+003 5.443E+003 1038.57 1.00 9.657E+004 2.365E+004 4.402E+004 1167.94 1.80 5.851E+004 5.740E+003 2.673E+004 1365.15 3.04 3.128E+004 2.461E+004 1.401E+004 CS-137 661.65 85.12 1.249E+003 1.25E+003 8.819E+002 5.858E+002 EU-152 121.78 28.40 3.997E+003 3.52E+003 -9.131E+002 1.941E+003 344.27 26.50 3.557E+003 -2.021E+003 1.692E+003 1407.95 20.70 3.523E+003 1.231E+003 1.517E+003 EU-154 123.07 40.40 2.785E+003 2.35E+003 -2.590E+001 1.352E+003 722.30 20.00 5.277E+003 9.754E+002 2.465E+003 1274.51 34.40 2.349E+003 -2.037E+003 1.036E+003

+ BI-214 609.31* 46.30 1.109E+003 1.11E+003 2.438E+003 4.863E+002 768.36 5.04 2.063E+004 6.624E+003 9.600E+003 806.17 1.23 8.282E+004 1.558E+004 3.840E+004 934.06 3.21 3.114E+004 6.345E+003 1.431E+004 1120.29 15.10 7.740E+003 2.868E+003 3.576E+003 1155.19 1.69 6.121E+004 1.339E+004 2.794E+004 1238.11 5.94 2.075E+004 1.623E+004 9.585E+003 1280.96 1.47 6.114E+004 6.518E+003 2.732E+004 1377.67 4.11 1.804E+004 8.967E+002 7.806E+003 1385.31 0.78 1.065E+005 -1.127E+005 4.682E+004 1401.50 1.39 6.311E+004 -6.234E+004 2.793E+004 1407.98 2.48 2.941E+004 1.028E+004 1.266E+004 1509.19 2.19 2.533E+004 -3.600E+004 1.023E+004 1661.28 1.15 5.500E+004 -3.388E+004 2.254E+004 1729.60 3.05 1.707E+004 5.685E+003 6.613E+003 1764.49 15.80 6.963E+003 6.401E+003 3.105E+003 1847.44 2.12 3.204E+004 1.494E+004 1.313E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81* 6.33 2.137E+004 1.56E+003 1.080E+004 1.017E+004 77.11 10.70 2.042E+004 2.574E+004 9.929E+003 87.20 3.70 4.381E+004 2.390E+004 2.132E+004 89.80 1.03 1.571E+005 8.274E+004 7.654E+004 241.98 7.49 1.470E+004 9.073E+003 7.096E+003

Nuclide MDA Report 3/27/2019 8:47:58 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 4.930E+003 1.56E+003 4.131E+002 2.355E+003 351.92* 37.20 1.558E+003 1.066E+003 7.167E+002 785.91 1.10 8.487E+004 -3.627E+004 3.911E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D13-GM.CNF Report Generated On  : 3/27/2019 8:50:07 PM Sample Title  : B1-010-001-FSFC-D13-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D13 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 11:22:00 AM Acquisition Started  : 3/27/2019 11:22:50 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:50:07 PM Page 2

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Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D13-GM Peak Analysis Performed on: 3/27/2019 8:50:06 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 960 953.88 238.54 1.59 4.10E+001 30.96 6.90E+001 2 1401- 1413 1406.86 351.86 0.72 3.14E+001 21.77 3.26E+001 3 2325- 2339 2332.88 583.47 0.56 4.16E+001 16.58 9.40E+000 4 5833- 5857 5845.25 1461.32 2.08 2.46E+002 31.37 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:50:07 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D13-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.995 1460.81* 10.67 8.86232E+004 1.34653E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.27485E+003 9.84512E+002 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.44307E+003 1.02743E+003 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:50:07 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.995 8.862317E+004 1.346526E+004 PB-212 1.000 1.274851E+003 9.845124E+002 PB-214 1.000 1.443067E+003 1.027428E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:50:06 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 583.47 6.9338E-002 39.86 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:50:07 PM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D13-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 9.749E+002 9.75E+002 8.862E+004 0.000E+000 CO-60 1173.22 100.00 1.017E+003 9.18E+002 -9.228E+002 4.629E+002 1332.49 100.00 9.177E+002 2.879E+002 4.102E+002 CS-134 475.35 1.46 6.388E+004 1.07E+003 4.993E+003 3.006E+004 563.23 8.38 1.143E+004 -2.174E+003 5.357E+003 569.32 15.43 6.050E+003 6.435E+002 2.828E+003 604.70 97.60 1.198E+003 9.592E+002 5.668E+002 795.84 85.40 1.068E+003 -1.625E+003 4.910E+002 801.93 8.73 1.113E+004 -8.255E+003 5.143E+003 1038.57 1.00 9.657E+004 -2.129E+004 4.402E+004 1167.94 1.80 5.636E+004 -3.184E+004 2.566E+004 1365.15 3.04 2.267E+004 -6.273E+003 9.707E+003 CS-137 661.65 85.12 1.103E+003 1.10E+003 5.524E+002 5.128E+002 EU-152 121.78 28.40 3.858E+003 3.52E+003 -7.548E+002 1.871E+003 344.27 26.50 3.916E+003 -3.242E+003 1.872E+003 1407.95 20.70 3.523E+003 -2.267E+003 1.517E+003 EU-154 123.07 40.40 2.741E+003 2.74E+003 2.351E+003 1.330E+003 722.30 20.00 4.700E+003 1.612E+003 2.176E+003 1274.51 34.40 2.792E+003 -1.038E+003 1.258E+003 BI-214 609.31 46.30 2.478E+003 2.48E+003 3.064E+003 1.171E+003 768.36 5.04 1.916E+004 2.021E+004 8.863E+003 806.17 1.23 8.352E+004 3.337E+004 3.875E+004 934.06 3.21 2.911E+004 8.812E+003 1.330E+004 1120.29 15.10 7.740E+003 7.554E+003 3.576E+003 1155.19 1.69 7.029E+004 2.303E+004 3.247E+004 1238.11 5.94 2.075E+004 8.056E+003 9.585E+003 1280.96 1.47 6.445E+004 8.214E+003 2.898E+004 1377.67 4.11 2.200E+004 6.522E+002 9.785E+003 1385.31 0.78 1.317E+005 6.523E+004 5.943E+004 1401.50 1.39 4.868E+004 -2.904E+004 2.071E+004 1407.98 2.48 2.941E+004 -1.893E+004 1.266E+004 1509.19 2.19 3.129E+004 1.796E+004 1.321E+004 1661.28 1.15 7.368E+004 5.128E+004 3.188E+004 1729.60 3.05 2.476E+004 3.411E+003 1.046E+004 1764.49 15.80 6.687E+003 -1.087E+003 2.967E+003 1847.44 2.12 2.297E+004 6.402E+003 8.598E+003

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.832E+004 1.54E+003 3.164E+004 1.864E+004 77.11 10.70 2.103E+004 1.721E+004 1.023E+004 87.20 3.70 4.329E+004 -1.850E+004 2.107E+004 89.80 1.03 1.498E+005 8.726E+002 7.292E+004 241.98 7.49 1.462E+004 1.689E+004 7.056E+003

Nuclide MDA Report 3/27/2019 8:50:07 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.079E+003 1.54E+003 -2.595E+003 2.430E+003 351.92* 37.20 1.537E+003 1.443E+003 7.060E+002 785.91 1.10 7.605E+004 -2.530E+004 3.470E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D14-GM.CNF Report Generated On  : 3/27/2019 8:58:13 PM Sample Title  : B1-010-001-FSFC-D14-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D14 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 11:37:00 AM Acquisition Started  : 3/27/2019 11:37:22 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:58:13 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D14-GM Peak Analysis Performed on: 3/27/2019 8:58:13 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 950- 961 955.06 238.84 1.08 2.82E+001 29.26 7.28E+001 2 2280- 2291 2285.98 571.74 1.36 1.58E+001 10.45 4.24E+000 3 2328- 2340 2333.09 583.52 0.59 3.50E+001 18.45 1.90E+001 4 2432- 2443 2437.42 609.61 0.80 3.39E+001 18.09 1.91E+001 5 3870- 3883 3876.15 969.30 0.82 1.35E+001 13.80 1.05E+001 6 5833- 5856 5845.02 1461.27 2.37 2.22E+002 29.80 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:58:13 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D14-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.996 1460.81* 10.67 7.99747E+004 1.26054E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 8.77193E+002 9.21583E+002 300.09 3.41 BI-214 0.999 609.31* 46.30 1.70670E+003 9.36650E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60 27.70 964.60 5.20 969.11* 16.60 2.47119E+003 2.53677E+003 1587.90 3.71 PA-234 0.992 94.67 15.50

Interference Corrected Activity Report 3/27/2019 8:58:13 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty PA-234 0.992 98.44 25.10 111.00 8.55 131.28 20.00 152.70 7.20 226.87 6.50 569.26* 10.40 3.40635E+003 2.30370E+003 733.00 8.50 883.24 12.00 946.00 20.00 949.00 7.80

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:58:13 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.996 7.997474E+004 1.260538E+004 PB-212 1.000 8.771935E+002 9.215829E+002 BI-214 0.999 1.706704E+003 9.366502E+002 AC-228 1.000 2.471188E+003 2.536772E+003 PA-234 0.992 3.406354E+003 2.303695E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:58:13 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 583.52 5.8364E-002 52.69 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:58:13 PM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D14-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 9.748E+002 9.75E+002 7.997E+004 0.000E+000 CO-60 1173.22 100.00 1.209E+003 9.51E+002 5.031E+002 5.588E+002 1332.49 100.00 9.512E+002 4.741E+002 4.269E+002 CS-134 475.35 1.46 6.212E+004 1.09E+003 -1.070E+004 2.919E+004 563.23 8.38 1.100E+004 -4.779E+002 5.139E+003 569.32 15.43 5.844E+003 -2.662E+003 2.725E+003 604.70 97.60 1.251E+003 -2.502E+002 5.931E+002 795.84 85.40 1.090E+003 1.920E+002 5.021E+002 801.93 8.73 1.050E+004 -7.738E+003 4.824E+003 1038.57 1.00 9.899E+004 -6.017E+004 4.523E+004 1167.94 1.80 6.699E+004 7.919E+004 3.097E+004 1365.15 3.04 3.071E+004 1.871E+004 1.373E+004 CS-137 661.65 85.12 1.121E+003 1.12E+003 9.782E+002 5.214E+002 EU-152 121.78 28.40 4.007E+003 3.65E+003 4.701E+002 1.946E+003 344.27 26.50 3.647E+003 -2.352E+003 1.737E+003 1407.95 20.70 3.958E+003 -4.103E+003 1.735E+003 EU-154 123.07 40.40 2.803E+003 2.80E+003 1.447E+003 1.361E+003 722.30 20.00 4.268E+003 1.713E+003 1.960E+003 1274.51 34.40 3.008E+003 -5.666E+002 1.366E+003

+ BI-214 609.31* 46.30 1.283E+003 1.28E+003 1.707E+003 5.733E+002 768.36 5.04 1.983E+004 3.842E+003 9.198E+003 806.17 1.23 7.702E+004 1.280E+004 3.550E+004 934.06 3.21 3.014E+004 1.217E+004 1.382E+004 1120.29 15.10 7.373E+003 1.441E+003 3.393E+003 1155.19 1.69 6.627E+004 4.128E+004 3.046E+004 1238.11 5.94 1.976E+004 1.375E+004 9.094E+003 1280.96 1.47 7.057E+004 -1.355E+004 3.204E+004 1377.67 4.11 2.061E+004 1.704E+004 9.093E+003 1385.31 0.78 1.090E+005 -5.936E+004 4.810E+004 1401.50 1.39 6.025E+004 -1.379E+004 2.649E+004 1407.98 2.48 3.304E+004 -3.425E+004 1.448E+004 1509.19 2.19 3.499E+004 2.335E+004 1.507E+004 1661.28 1.15 6.380E+004 3.663E+004 2.695E+004 1729.60 3.05 2.369E+004 -1.579E+002 9.920E+003 1764.49 15.80 5.048E+003 3.061E+003 2.147E+003 1847.44 2.12 2.797E+004 -2.507E+004 1.110E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.729E+004 2.70E+003 6.247E+004 1.813E+004 77.11 10.70 2.002E+004 2.393E+003 9.727E+003 87.20 3.70 4.394E+004 2.446E+004 2.139E+004 89.80 1.03 1.524E+005 -2.504E+002 7.420E+004 241.98 7.49 1.486E+004 2.334E+004 7.176E+003

Nuclide MDA Report 3/27/2019 8:58:13 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 5.005E+003 2.70E+003 -3.188E+002 2.393E+003 351.92 37.20 2.701E+003 2.114E+003 1.288E+003 785.91 1.10 9.279E+004 3.410E+003 4.308E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D15-GM.CNF Report Generated On  : 3/27/2019 8:59:18 PM Sample Title  : B1-010-001-FSFC-D15-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D15 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 11:50:00 AM Acquisition Started  : 3/27/2019 11:50:19 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 8:59:18 PM Page 2

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Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D15-GM Peak Analysis Performed on: 3/27/2019 8:59:17 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 962 954.77 238.76 0.50 4.82E+001 32.00 7.18E+001 2 1402- 1414 1407.70 352.07 1.05 3.01E+001 23.47 3.99E+001 3 2327- 2339 2332.63 583.41 0.83 3.15E+001 18.25 1.95E+001 4 2431- 2444 2437.32 609.59 0.37 2.84E+001 20.45 2.76E+001 5 4475- 4488 4481.88 1120.69 0.78 2.33E+001 10.59 1.70E+000 6 5833- 5857 5845.51 1461.39 1.59 2.30E+002 32.67 9.07E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:59:18 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D15-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.994 1460.81* 10.67 8.28356E+004 1.36153E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.49919E+003 1.02434E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 1.42957E+003 1.04576E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29* 15.10 5.06608E+003 2.33738E+003 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.38388E+003 1.10221E+003 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 8:59:18 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.994 8.283561E+004 1.361532E+004 PB-212 1.000 1.499188E+003 1.024341E+003 BI-214 0.999 2.036093E+003 9.545754E+002 PB-214 1.000 1.383875E+003 1.102214E+003

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

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

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

Peak Locate Performed on: 3/27/2019 8:59:17 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 583.41 5.2500E-002 57.93 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 8:59:18 PM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D15-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 8.178E+003 8.18E+003 8.284E+004 3.601E+003 CO-60 1173.22 100.00 1.030E+003 8.83E+002 1.313E+002 4.695E+002 1332.49 100.00 8.828E+002 -4.548E+002 3.927E+002 CS-134 475.35 1.46 6.068E+004 1.09E+003 -3.291E+004 2.847E+004 563.23 8.38 1.030E+004 -5.784E+002 4.792E+003 569.32 15.43 5.968E+003 1.305E+003 2.788E+003 604.70 97.60 1.171E+003 -7.619E+002 5.531E+002 795.84 85.40 1.090E+003 7.263E+002 5.021E+002 801.93 8.73 9.694E+003 4.499E+002 4.424E+003 1038.57 1.00 9.657E+004 -3.226E+004 4.402E+004 1167.94 1.80 5.781E+004 9.926E+003 2.638E+004 1365.15 3.04 2.832E+004 2.409E+004 1.253E+004 CS-137 661.65 85.12 1.137E+003 1.14E+003 4.185E+002 5.299E+002 EU-152 121.78 28.40 4.199E+003 3.54E+003 1.585E+002 2.042E+003 344.27 26.50 3.544E+003 -3.067E+001 1.686E+003 1407.95 20.70 4.345E+003 9.257E+002 1.928E+003 EU-154 123.07 40.40 2.935E+003 2.93E+003 -4.053E+002 1.427E+003 722.30 20.00 5.016E+003 2.375E+003 2.334E+003 1274.51 34.40 3.008E+003 -1.200E+003 1.366E+003

+ BI-214 609.31* 46.30 1.582E+003 1.58E+003 1.430E+003 7.228E+002 768.36 5.04 1.916E+004 1.829E+003 8.863E+003 806.17 1.23 6.902E+004 3.841E+004 3.150E+004 934.06 3.21 2.980E+004 5.467E+003 1.365E+004 1120.29* 15.10 2.143E+003 5.066E+003 7.773E+002 1155.19 1.69 5.811E+004 -1.346E+005 2.638E+004 1238.11 5.94 2.055E+004 1.653E+003 9.489E+003 1280.96 1.47 6.445E+004 1.334E+004 2.898E+004 1377.67 4.11 2.109E+004 1.122E+004 9.330E+003 1385.31 0.78 1.090E+005 -1.036E+005 4.810E+004 1401.50 1.39 5.722E+004 -9.604E+004 2.498E+004 1407.98 2.48 3.627E+004 7.727E+003 1.609E+004 1509.19 2.19 3.829E+004 2.874E+004 1.671E+004 1661.28 1.15 5.166E+004 2.198E+004 2.087E+004 1729.60 3.05 2.578E+004 1.564E+004 1.097E+004 1764.49 15.80 7.097E+003 6.680E+003 3.172E+003 1847.44 2.12 3.386E+004 -1.867E+003 1.404E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.720E+004 1.69E+003 4.196E+004 1.808E+004 77.11 10.70 2.026E+004 6.396E+003 9.846E+003 87.20 3.70 4.191E+004 -5.330E+003 2.038E+004 89.80 1.03 1.442E+005 -6.886E+004 7.013E+004 241.98 7.49 1.451E+004 7.106E+003 7.003E+003

Nuclide MDA Report 3/27/2019 8:59:18 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.166E+003 1.69E+003 2.024E+003 2.473E+003 351.92* 37.20 1.695E+003 1.384E+003 7.851E+002 785.91 1.10 9.503E+004 -3.939E+004 4.419E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 10:16:42 AM Sample Title  : B1-010-001-FSFC-D16-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D16 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 10:06:00 AM Acquisition Started  : 3/28/2019 10:06:41 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 10:16:42 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D16-GM Peak Analysis Performed on: 3/28/2019 10:16:42 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 959 952.73 238.25 0.45 3.62E+001 29.85 7.08E+001 2 2322- 2334 2328.08 582.27 0.79 3.28E+001 15.77 1.12E+001 3 2427- 2440 2434.09 608.78 1.18 2.21E+001 17.85 1.99E+001 4 4469- 4482 4475.88 1119.19 0.73 1.87E+001 11.55 5.26E+000 5 5826- 5849 5837.03 1459.27 1.31 2.42E+002 31.11 0.00E+000 6 7044- 7059 7051.58 1762.59 0.56 1.54E+001 10.34 3.63E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 10:16:42 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D16-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.959 1460.81* 10.67 8.70947E+004 1.33098E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.12393E+003 9.45253E+002 300.09 3.41 BI-214 0.986 609.31* 46.30 1.10955E+003 9.09295E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29* 15.10 4.07163E+003 2.53124E+003 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49* 15.80 4.27399E+003 2.89501E+003 1847.44 2.12 2118.54 1.21

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 10:16:42 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.959 8.709466E+004 1.330983E+004 PB-212 0.999 1.123931E+003 9.452532E+002 BI-214 0.986 1.675182E+003 8.206520E+002

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

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

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

Peak Locate Performed on: 3/28/2019 10:16:42 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 582.27 5.4688E-002 48.07 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 10:16:43 AM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D16-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 9.739E+002 9.74E+002 8.709E+004 0.000E+000 CO-60 1173.22 100.00 1.017E+003 9.99E+002 -3.580E+002 4.629E+002 1332.49 100.00 9.991E+002 4.654E+000 4.509E+002 CS-134 475.35 1.46 6.524E+004 1.09E+003 4.217E+003 3.075E+004 563.23 8.38 1.022E+004 -4.998E+003 4.752E+003 569.32 15.43 5.886E+003 1.160E+003 2.746E+003 604.70 97.60 1.165E+003 1.375E+003 5.503E+002 795.84 85.40 1.090E+003 -1.920E+001 5.021E+002 801.93 8.73 9.694E+003 -1.329E+003 4.424E+003 1038.57 1.00 8.890E+004 4.967E+004 4.018E+004 1167.94 1.80 5.709E+004 -1.227E+004 2.602E+004 1365.15 3.04 2.423E+004 1.686E+004 1.048E+004 CS-137 661.65 85.12 1.137E+003 1.14E+003 2.873E+002 5.299E+002 EU-152 121.78 28.40 3.894E+003 3.34E+003 -2.676E+003 1.889E+003 344.27 26.50 3.342E+003 -2.337E+003 1.585E+003 1407.95 20.70 3.958E+003 -2.151E+003 1.735E+003 EU-154 123.07 40.40 2.745E+003 2.46E+003 -9.175E+001 1.332E+003 722.30 20.00 5.490E+003 3.376E+003 2.571E+003 1274.51 34.40 2.455E+003 -1.529E+003 1.089E+003

+ BI-214 609.31* 46.30 1.393E+003 1.39E+003 1.110E+003 6.282E+002 768.36 5.04 1.864E+004 1.432E+004 8.604E+003 806.17 1.23 6.986E+004 -2.565E+004 3.192E+004 934.06 3.21 2.767E+004 -2.041E+004 1.258E+004 1120.29* 15.10 3.322E+003 4.072E+003 1.367E+003 1155.19 1.69 6.557E+004 -5.211E+003 3.012E+004 1238.11 5.94 1.915E+004 1.094E+004 8.785E+003 1280.96 1.47 6.226E+004 2.445E+004 2.789E+004 1377.67 4.11 2.200E+004 1.973E+004 9.785E+003 1385.31 0.78 9.832E+004 -7.353E+004 4.274E+004 1401.50 1.39 5.399E+004 -4.429E+004 2.336E+004 1407.98 2.48 3.304E+004 -1.796E+004 1.448E+004 1509.19 2.19 2.993E+004 -1.212E+004 1.253E+004 1661.28 1.15 5.811E+004 2.930E+004 2.410E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49* 15.80 3.834E+003 4.274E+003 1.541E+003 1847.44 2.12 3.556E+004 1.920E+004 1.489E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.712E+004 2.50E+003 2.815E+004 1.804E+004 77.11 10.70 2.042E+004 5.935E+003 9.929E+003 87.20 3.70 4.357E+004 2.754E+004 2.121E+004 89.80 1.03 1.469E+005 -6.720E+004 7.146E+004 241.98 7.49 1.416E+004 8.590E+003 6.825E+003

Nuclide MDA Report 3/28/2019 10:16:43 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 4.869E+003 2.50E+003 2.212E+003 2.325E+003 351.92 37.20 2.498E+003 1.485E+003 1.187E+003 785.91 1.10 8.487E+004 -8.734E+004 3.911E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 10:57:26 AM Sample Title  : B1-010-001-FSFC-D17-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D17 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 10:47:00 AM Acquisition Started  : 3/28/2019 10:47:25 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 10:57:26 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D17-GM Peak Analysis Performed on: 3/28/2019 10:57:26 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 945- 960 953.83 238.53 0.74 5.09E+001 37.20 9.81E+001 2 1102- 1113 1107.58 276.99 0.43 1.56E+001 20.17 3.44E+001 3 1400- 1412 1405.92 351.63 0.92 3.39E+001 21.59 3.11E+001 4 2322- 2334 2328.25 582.31 0.40 3.11E+001 17.07 1.59E+001 5 2428- 2440 2433.61 608.66 0.55 3.12E+001 17.96 1.78E+001 6 5825- 5848 5837.71 1459.44 1.60 2.24E+002 30.76 3.09E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 10:57:26 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D17-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.967 1460.81* 10.67 8.05907E+004 1.29200E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.58215E+003 1.18460E+003 300.09 3.41 BI-214 0.997 609.31* 46.30 1.57129E+003 9.25678E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.55721E+003 1.02343E+003 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 10:57:26 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.967 8.059070E+004 1.291997E+004 PB-212 1.000 1.582155E+003 1.184598E+003 BI-214 0.997 1.571289E+003 9.256777E+002 PB-214 0.999 1.557208E+003 1.023432E+003

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

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

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

Peak Locate Performed on: 3/28/2019 10:57:26 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 276.99 2.5942E-002 129.59 4 582.31 5.1879E-002 54.84 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 10:57:26 AM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D17-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 5.191E+003 5.19E+003 8.059E+004 2.108E+003 CO-60 1173.22 100.00 9.901E+002 9.51E+002 -4.289E+002 4.495E+002 1332.49 100.00 9.512E+002 3.640E+002 4.269E+002 CS-134 475.35 1.46 6.177E+004 1.03E+003 -1.855E+004 2.901E+004 563.23 8.38 9.811E+003 -6.133E+003 4.546E+003 569.32 15.43 5.452E+003 -2.030E+003 2.530E+003 604.70 97.60 1.125E+003 6.863E+002 5.305E+002 795.84 85.40 1.034E+003 -1.069E+002 4.740E+002 801.93 8.73 9.813E+003 5.050E+003 4.484E+003 1038.57 1.00 8.190E+004 1.602E+004 3.668E+004 1167.94 1.80 5.255E+004 1.157E+004 2.375E+004 1365.15 3.04 2.832E+004 -3.598E+003 1.253E+004 CS-137 661.65 85.12 1.129E+003 1.13E+003 2.317E+002 5.257E+002 EU-152 121.78 28.40 4.052E+003 3.28E+003 -1.237E+002 1.968E+003 344.27 26.50 3.370E+003 -3.771E+003 1.599E+003 1407.95 20.70 3.280E+003 8.466E+002 1.395E+003 EU-154 123.07 40.40 2.838E+003 2.46E+003 9.119E+002 1.378E+003 722.30 20.00 4.740E+003 -2.744E+003 2.196E+003 1274.51 34.40 2.455E+003 -1.767E+003 1.089E+003

+ BI-214 609.31* 46.30 1.300E+003 1.30E+003 1.571E+003 5.817E+002 768.36 5.04 1.864E+004 -5.690E+003 8.604E+003 806.17 1.23 7.152E+004 1.725E+003 3.275E+004 934.06 3.21 2.876E+004 4.362E+003 1.313E+004 1120.29 15.10 6.985E+003 1.932E+003 3.198E+003 1155.19 1.69 5.648E+004 -6.148E+004 2.557E+004 1238.11 5.94 1.739E+004 -2.198E+003 7.904E+003 1280.96 1.47 5.637E+004 -4.337E+004 2.494E+004 1377.67 4.11 2.528E+004 1.323E+004 1.143E+004 1385.31 0.78 1.140E+005 3.727E+003 5.057E+004 1401.50 1.39 5.399E+004 -3.374E+004 2.336E+004 1407.98 2.48 2.738E+004 7.067E+003 1.165E+004 1509.19 2.19 2.993E+004 -1.796E+003 1.253E+004 1661.28 1.15 5.166E+004 2.198E+004 2.087E+004 1729.60 3.05 1.707E+004 -3.376E+003 6.613E+003 1764.49 15.80 6.092E+003 4.731E+003 2.670E+003 1847.44 2.12 3.386E+004 -3.334E+002 1.404E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.746E+004 1.50E+003 -1.057E+004 1.821E+004 77.11 10.70 2.082E+004 1.649E+004 1.013E+004 87.20 3.70 4.329E+004 1.151E+003 2.107E+004 89.80 1.03 1.490E+005 -6.481E+004 7.252E+004 241.98 7.49 1.509E+004 -1.341E+003 7.293E+003

Nuclide MDA Report 3/28/2019 10:57:26 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.122E+003 1.50E+003 3.658E+003 2.452E+003 351.92* 37.20 1.500E+003 1.557E+003 6.877E+002 785.91 1.10 8.813E+004 -5.749E+004 4.075E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 11:10:52 AM Sample Title  : B1-010-001-FSFC-D18-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D18 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 11:00:00 AM Acquisition Started  : 3/28/2019 11:00:50 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 11:10:52 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D18-GM Peak Analysis Performed on: 3/28/2019 11:10:51 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 964 953.84 238.53 0.72 5.26E+001 33.84 7.44E+001 2 2324- 2336 2330.05 582.76 0.96 2.74E+001 18.95 2.36E+001 3 2428- 2441 2434.75 608.94 0.45 3.25E+001 15.67 1.05E+001 4 5826- 5851 5838.03 1459.52 1.87 2.26E+002 33.30 1.24E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 11:10:52 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D18-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.971 1460.81* 10.67 8.11844E+004 1.37344E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.63541E+003 1.08484E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 1.63538E+003 8.15788E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 11:10:52 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.971 8.118440E+004 1.373445E+004 PB-212 1.000 1.635411E+003 1.084842E+003 BI-214 0.999 1.635380E+003 8.157883E+002

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

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

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

Peak Locate Performed on: 3/28/2019 11:10:51 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 582.76 4.5711E-002 69.10 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 11:10:52 AM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D18-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 9.484E+003 9.48E+003 8.118E+004 4.255E+003 CO-60 1173.22 100.00 1.187E+003 6.53E+002 4.146E+002 5.478E+002 1332.49 100.00 6.528E+002 1.194E+002 2.777E+002 CS-134 475.35 1.46 5.368E+004 1.11E+003 -4.891E+004 2.497E+004 563.23 8.38 1.038E+004 2.659E+003 4.832E+003 569.32 15.43 5.497E+003 -9.808E+002 2.552E+003 604.70 97.60 1.108E+003 6.530E+002 5.218E+002 795.84 85.40 1.133E+003 -3.989E+002 5.234E+002 801.93 8.73 1.071E+004 1.485E+003 4.933E+003 1038.57 1.00 1.091E+005 -7.626E+004 5.030E+004 1167.94 1.80 5.781E+004 -1.292E+004 2.638E+004 1365.15 3.04 2.185E+004 3.723E+003 9.294E+003 CS-137 661.65 85.12 1.095E+003 1.09E+003 9.354E+002 5.084E+002 EU-152 121.78 28.40 3.992E+003 3.36E+003 -1.194E+003 1.938E+003 344.27 26.50 3.356E+003 -5.175E+003 1.592E+003 1407.95 20.70 4.059E+003 1.778E+003 1.785E+003 EU-154 123.07 40.40 2.799E+003 2.75E+003 -8.609E+002 1.359E+003 722.30 20.00 5.167E+003 3.842E+003 2.410E+003 1274.51 34.40 2.747E+003 -9.499E+002 1.235E+003

+ BI-214 609.31* 46.30 1.026E+003 1.03E+003 1.635E+003 4.448E+002 768.36 5.04 1.678E+004 -1.189E+003 7.676E+003 806.17 1.23 7.549E+004 2.076E+004 3.473E+004 934.06 3.21 3.014E+004 5.260E+003 1.382E+004 1120.29 15.10 7.297E+003 -4.125E+002 3.355E+003 1155.19 1.69 6.415E+004 -2.607E+004 2.941E+004 1238.11 5.94 2.016E+004 9.546E+002 9.293E+003 1280.96 1.47 7.057E+004 -4.866E+004 3.204E+004 1377.67 4.11 2.109E+004 -1.894E+003 9.330E+003 1385.31 0.78 1.187E+005 7.461E+004 5.293E+004 1401.50 1.39 5.722E+004 -2.059E+004 2.498E+004 1407.98 2.48 3.388E+004 1.484E+004 1.490E+004 1509.19 2.19 2.850E+004 -1.201E+004 1.182E+004 1661.28 1.15 5.811E+004 -1.351E+004 2.410E+004 1729.60 3.05 2.005E+004 8.528E+003 8.100E+003 1764.49 15.80 5.933E+003 4.453E+003 2.590E+003 1847.44 2.12 3.556E+004 7.291E+003 1.489E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.790E+004 2.60E+003 2.910E+004 1.843E+004 77.11 10.70 2.080E+004 8.879E+003 1.012E+004 87.20 3.70 4.253E+004 8.470E+003 2.069E+004 89.80 1.03 1.495E+005 1.344E+004 7.276E+004 241.98 7.49 1.407E+004 9.189E+002 6.784E+003

Nuclide MDA Report 3/28/2019 11:10:52 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 5.251E+003 2.60E+003 2.047E+003 2.516E+003 351.92 37.20 2.602E+003 1.196E+003 1.239E+003 785.91 1.10 8.651E+004 -1.413E+004 3.994E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 11:37:22 AM Sample Title  : B1-010-001-FSFC-D19-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D19 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 11:25:00 AM Acquisition Started  : 3/28/2019 11:27:21 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 11:37:22 AM Page 2

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Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D19-GM Peak Analysis Performed on: 3/28/2019 11:37:21 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 958 952.94 238.30 0.40 4.55E+001 28.25 6.05E+001 2 1174- 1185 1179.52 294.99 0.33 1.82E+001 22.21 4.18E+001 3 2324- 2336 2330.41 582.85 0.59 3.35E+001 16.00 1.15E+001 4 2428- 2439 2433.80 608.71 0.44 3.10E+001 17.44 1.80E+001 5 3633- 3646 3639.80 910.23 0.50 2.83E+001 16.90 1.57E+001 6 3865- 3878 3871.06 968.03 0.46 1.11E+001 11.99 8.86E+000 7 5826- 5850 5838.35 1459.60 1.36 2.52E+002 32.56 3.17E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 11:37:22 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D19-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.974 1460.81* 10.67 9.06462E+004 1.39096E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.41326E+003 9.07086E+002 300.09 3.41 BI-214 0.997 609.31* 46.30 1.55955E+003 8.99702E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 1.47200E+003 1.81471E+003 351.92 37.20 785.91 1.10 AC-228 0.987 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40

Interference Corrected Activity Report 3/28/2019 11:37:22 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.987 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.00208E+003 1.82469E+003 964.60 5.20 969.11* 16.60 2.03726E+003 2.20213E+003 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 11:37:22 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.974 9.064618E+004 1.390958E+004 PB-212 0.999 1.413259E+003 9.070864E+002 BI-214 0.997 1.559553E+003 8.997018E+002 PB-214 1.000 1.472004E+003 1.814713E+003 AC-228 0.987 2.609317E+003 1.405030E+003

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

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

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

Peak Locate Performed on: 3/28/2019 11:37:21 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 582.85 5.5861E-002 47.74 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 11:37:22 AM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D19-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 5.290E+003 5.29E+003 9.065E+004 2.158E+003 CO-60 1173.22 100.00 1.209E+003 8.65E+002 1.766E+002 5.588E+002 1332.49 100.00 8.647E+002 -7.584E+001 3.837E+002 CS-134 475.35 1.46 6.212E+004 1.16E+003 -2.847E+003 2.919E+004 563.23 8.38 1.054E+004 -8.603E+003 4.910E+003 569.32 15.43 5.886E+003 3.051E+003 2.746E+003 604.70 97.60 1.225E+003 7.745E+002 5.801E+002 795.84 85.40 1.164E+003 -3.012E+002 5.389E+002 801.93 8.73 1.123E+004 -1.614E+003 5.194E+003 1038.57 1.00 9.657E+004 9.551E+004 4.402E+004 1167.94 1.80 6.878E+004 4.350E+004 3.187E+004 1365.15 3.04 2.637E+004 -1.585E+004 1.155E+004 CS-137 661.65 85.12 1.162E+003 1.16E+003 7.533E+002 5.424E+002 EU-152 121.78 28.40 4.072E+003 3.52E+003 1.017E+003 1.978E+003 344.27 26.50 3.518E+003 -3.097E+003 1.673E+003 1407.95 20.70 3.748E+003 -1.356E+002 1.629E+003 EU-154 123.07 40.40 2.817E+003 2.79E+003 8.083E+002 1.368E+003 722.30 20.00 4.781E+003 4.528E+003 2.217E+003 1274.51 34.40 2.792E+003 -1.173E+003 1.258E+003

+ BI-214 609.31* 46.30 1.247E+003 1.25E+003 1.560E+003 5.552E+002 768.36 5.04 2.155E+004 2.549E+003 1.006E+004 806.17 1.23 7.626E+004 -4.831E+004 3.512E+004 934.06 3.21 3.014E+004 -3.495E+004 1.382E+004 1120.29 15.10 7.952E+003 1.001E+004 3.682E+003 1155.19 1.69 6.121E+004 1.311E+004 2.794E+004 1238.11 5.94 1.996E+004 1.387E+004 9.194E+003 1280.96 1.47 6.226E+004 -1.045E+004 2.789E+004 1377.67 4.11 2.881E+004 1.499E+004 1.319E+004 1385.31 0.78 1.296E+005 -3.003E+004 5.840E+004 1401.50 1.39 6.170E+004 3.217E+004 2.722E+004 1407.98 2.48 3.128E+004 -1.132E+003 1.360E+004 1509.19 2.19 3.932E+004 1.878E+004 1.723E+004 1661.28 1.15 5.811E+004 3.663E+003 2.410E+004 1729.60 3.05 2.255E+004 1.137E+004 9.353E+003 1764.49 15.80 6.398E+003 2.563E+003 2.822E+003 1847.44 2.12 2.297E+004 6.402E+003 8.598E+003

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.772E+004 2.62E+003 5.490E+004 1.834E+004 77.11 10.70 2.061E+004 2.749E+003 1.002E+004 87.20 3.70 4.320E+004 -5.153E+003 2.102E+004 89.80 1.03 1.490E+005 -8.096E+004 7.252E+004 241.98 7.49 1.451E+004 1.229E+004 7.003E+003

Nuclide MDA Report 3/28/2019 11:37:22 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21* 19.20 2.952E+003 2.62E+003 1.472E+003 1.367E+003 351.92 37.20 2.620E+003 2.406E+002 1.248E+003 785.91 1.10 8.318E+004 -4.280E+004 3.827E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D20-GM.CNF Report Generated On  : 3/29/2019 10:37:42 AM Sample Title  : B1-010-001-FSFC-D20-GM Sample Description  : Rx Bowl 2M Concrete Sample Identification  : D20 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 1.256E+001 M^2 Sample Taken On  : 3/28/2019 3:28:00 PM Acquisition Started  : 3/28/2019 3:43:14 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_2M

Peak Analysis Report 3/29/2019 10:37:42 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D20-GM Peak Analysis Performed on: 3/29/2019 10:37:41 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 959 953.38 238.41 0.93 4.18E+001 25.53 4.82E+001 2 2429- 2441 2434.93 608.99 0.30 2.58E+001 16.57 1.63E+001 3 2638- 2653 2645.51 661.64 1.06 5.66E+001 19.08 1.14E+001 4 5828- 5851 5840.51 1460.14 1.27 1.84E+002 28.85 6.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:37:42 AM Page 3

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

Sample

Title:

B1-010-001-FSFC-D20-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.992 1460.81* 10.67 1.48191E+005 2.62614E+004 CS-137 1.000 661.65* 85.12 3.63185E+003 1.29981E+003 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.88500E+003 1.82086E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 2.89634E+003 1.90015E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:37:42 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.992 1.481906E+005 2.626136E+004 CS-137 1.000 3.631851E+003 1.299811E+003 PB-212 1.000 2.885003E+003 1.820860E+003 BI-214 0.999 2.896339E+003 1.900146E+003

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

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

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

Peak Locate Performed on: 3/29/2019 10:37:41 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/29/2019 10:37:42 AM Page 5

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D20-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 1.517E+004 1.52E+004 1.482E+005 6.496E+003 CO-60 1173.22 100.00 2.182E+003 1.71E+003 1.128E+002 9.894E+002 1332.49 100.00 1.715E+003 6.034E+001 7.486E+002 CS-134 475.35 1.46 1.216E+005 2.10E+003 7.647E+004 5.664E+004 563.23 8.38 2.076E+004 -2.503E+004 9.575E+003 569.32 15.43 1.228E+004 1.338E+002 5.702E+003 604.70 97.60 2.410E+003 1.024E+003 1.133E+003 795.84 85.40 2.095E+003 -5.689E+002 9.512E+002 801.93 8.73 1.972E+004 -1.731E+004 8.911E+003 1038.57 1.00 2.186E+005 -4.054E+004 9.978E+004 1167.94 1.80 1.192E+005 3.626E+004 5.397E+004 1365.15 3.04 5.417E+004 -2.217E+004 2.344E+004

+ CS-137 661.65* 85.12 1.412E+003 1.41E+003 3.632E+003 6.192E+002 EU-152 121.78 28.40 8.522E+003 6.42E+003 5.592E+003 4.134E+003 344.27 26.50 7.025E+003 -1.102E+004 3.321E+003 1407.95 20.70 6.416E+003 3.235E+003 2.661E+003 EU-154 123.07 40.40 5.951E+003 5.95E+003 3.612E+003 2.886E+003 722.30 20.00 8.910E+003 -7.009E+003 4.066E+003 1274.51 34.40 6.341E+003 -2.441E+002 2.861E+003

+ BI-214 609.31* 46.30 2.728E+003 2.73E+003 2.896E+003 1.212E+003 768.36 5.04 4.169E+004 -2.334E+004 1.925E+004 806.17 1.23 1.465E+005 -1.095E+005 6.654E+004 934.06 3.21 5.936E+004 1.563E+004 2.687E+004 1120.29 15.10 1.579E+004 1.650E+003 7.239E+003 1155.19 1.69 1.317E+005 -4.607E+004 5.986E+004 1238.11 5.94 4.185E+004 2.210E+004 1.916E+004 1280.96 1.47 1.367E+005 8.379E+004 6.108E+004 1377.67 4.11 4.033E+004 -1.898E+004 1.745E+004 1385.31 0.78 1.997E+005 4.420E+004 8.548E+004 1401.50 1.39 1.169E+005 -1.351E+004 5.035E+004 1407.98 2.48 5.355E+004 2.700E+004 2.221E+004 1509.19 2.19 6.697E+004 -4.465E+003 2.805E+004 1661.28 1.15 1.075E+005 4.101E+004 4.266E+004 1729.60 3.05 5.051E+004 2.189E+003 2.095E+004 1764.49 15.80 1.292E+004 9.352E+003 5.617E+003 1847.44 2.12 5.147E+004 1.434E+004 1.927E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 7.843E+004 5.58E+003 1.165E+004 3.808E+004 77.11 10.70 4.380E+004 4.333E+004 2.128E+004 87.20 3.70 9.168E+004 -2.544E+004 4.456E+004 89.80 1.03 3.291E+005 4.825E+005 1.601E+005 241.98 7.49 2.905E+004 3.387E+004 1.396E+004

Nuclide MDA Report 3/29/2019 10:37:42 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 1.023E+004 5.58E+003 -1.971E+003 4.870E+003 351.92 37.20 5.583E+003 7.244E+003 2.653E+003 785.91 1.10 1.570E+005 -9.295E+004 7.106E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 4:10:57 PM Sample Title  : B1-010-001-FSFC-D21-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D21 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 4:00:00 PM Acquisition Started  : 3/28/2019 4:00:56 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 4:10:57 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D21-GM Peak Analysis Performed on: 3/28/2019 4:10:57 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 960 953.62 238.47 1.02 5.51E+001 32.33 6.99E+001 2 1401- 1413 1407.21 351.95 0.77 2.65E+001 18.58 2.25E+001 3 2429- 2442 2435.68 609.18 0.78 3.47E+001 14.17 5.31E+000 4 5829- 5854 5840.15 1460.05 1.69 2.09E+002 28.91 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 4:10:57 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D21-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.990 1460.81* 10.67 7.52468E+004 1.21247E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.71276E+003 1.04234E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.74615E+003 7.47341E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.21909E+003 8.76371E+002 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 4:10:57 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.990 7.524677E+004 1.212475E+004 PB-212 1.000 1.712757E+003 1.042342E+003 BI-214 1.000 1.746148E+003 7.473414E+002 PB-214 1.000 1.219090E+003 8.763708E+002

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

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

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

Peak Locate Performed on: 3/28/2019 4:10:57 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/28/2019 4:10:58 PM Page 5

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D21-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 9.743E+002 9.74E+002 7.525E+004 0.000E+000 CO-60 1173.22 100.00 9.482E+002 8.08E+002 -7.938E+002 4.286E+002 1332.49 100.00 8.078E+002 9.897E+001 3.552E+002 CS-134 475.35 1.46 5.451E+004 9.24E+002 1.182E+004 2.538E+004 563.23 8.38 9.727E+003 5.318E+002 4.504E+003 569.32 15.43 5.315E+003 3.006E+003 2.461E+003 604.70 97.60 9.424E+002 5.528E+002 4.390E+002 795.84 85.40 9.236E+002 2.217E+002 4.187E+002 801.93 8.73 8.679E+003 -3.579E+003 3.917E+003 1038.57 1.00 8.618E+004 4.100E+004 3.882E+004 1167.94 1.80 5.094E+004 -3.236E+004 2.295E+004 1365.15 3.04 2.496E+004 8.692E+003 1.085E+004 CS-137 661.65 85.12 1.171E+003 1.17E+003 5.760E+002 5.465E+002 EU-152 121.78 28.40 3.745E+003 3.20E+003 9.333E+002 1.815E+003 344.27 26.50 3.200E+003 -3.146E+003 1.514E+003 1407.95 20.70 3.523E+003 2.351E+003 1.517E+003 EU-154 123.07 40.40 2.564E+003 2.46E+003 -1.900E+003 1.242E+003 722.30 20.00 4.575E+003 -1.452E+002 2.113E+003 1274.51 34.40 2.455E+003 -1.551E+003 1.089E+003

+ BI-214 609.31* 46.30 7.880E+002 7.88E+002 1.746E+003 3.259E+002 768.36 5.04 1.678E+004 6.076E+003 7.676E+003 806.17 1.23 5.676E+004 -4.785E+004 2.537E+004 934.06 3.21 2.804E+004 5.135E+003 1.277E+004 1120.29 15.10 7.882E+003 4.916E+003 3.647E+003 1155.19 1.69 5.890E+004 -7.374E+003 2.678E+004 1238.11 5.94 1.643E+004 -4.074E+003 7.425E+003 1280.96 1.47 6.759E+004 4.979E+004 3.055E+004 1377.67 4.11 1.804E+004 4.788E+003 7.806E+003 1385.31 0.78 1.011E+005 3.558E+003 4.414E+004 1401.50 1.39 4.473E+004 -1.678E+004 1.873E+004 1407.98 2.48 2.941E+004 1.962E+004 1.266E+004 1509.19 2.19 2.697E+004 -1.572E+004 1.105E+004 1661.28 1.15 5.500E+004 1.308E+002 2.254E+004 1729.60 3.05 1.707E+004 -2.665E+003 6.613E+003 1764.49 15.80 4.848E+003 2.783E+003 2.047E+003 1847.44 2.12 3.204E+004 1.494E+004 1.313E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.645E+004 1.29E+003 3.974E+004 1.771E+004 77.11 10.70 1.965E+004 3.385E+003 9.544E+003 87.20 3.70 4.007E+004 2.072E+004 1.946E+004 89.80 1.03 1.398E+005 -1.659E+004 6.791E+004 241.98 7.49 1.454E+004 2.037E+004 7.016E+003

Nuclide MDA Report 3/28/2019 4:10:58 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 4.585E+003 1.29E+003 2.940E+003 2.183E+003 351.92* 37.20 1.294E+003 1.219E+003 5.849E+002 785.91 1.10 8.146E+004 5.599E+004 3.741E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D22-GM.CNF Report Generated On  : 3/29/2019 10:40:20 AM Sample Title  : B1-010-001-FSFC-D22-GM Sample Description  : Rx Bowl 2M Concrete Sample Identification  : D22 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 1.256E+001 M^2 Sample Taken On  : 3/28/2019 3:28:00 PM Acquisition Started  : 3/28/2019 3:29:55 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_2M

Peak Analysis Report 3/29/2019 10:40:20 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D22-GM Peak Analysis Performed on: 3/29/2019 10:40:19 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 962 954.41 238.67 0.92 3.90E+001 28.72 5.80E+001 2 1402- 1413 1407.42 352.00 0.34 1.73E+001 17.35 2.27E+001 3 2325- 2337 2330.62 582.90 0.87 2.55E+001 14.61 1.05E+001 4 3635- 3648 3641.50 910.65 0.29 1.58E+001 13.21 9.23E+000 5 5829- 5852 5840.80 1460.21 1.75 1.94E+002 30.29 8.89E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:40:20 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D22-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.994 1460.81* 10.67 1.56341E+005 2.76059E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.69423E+003 2.02883E+003 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.76726E+003 1.79894E+003 785.91 1.10 AC-228 0.995 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.73954E+003 3.16152E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:40:20 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.994 1.563413E+005 2.760595E+004 PB-212 1.000 2.694230E+003 2.028829E+003 PB-214 1.000 1.767257E+003 1.798938E+003 AC-228 0.995 3.739537E+003 3.161521E+003

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

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

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

Peak Locate Performed on: 3/29/2019 10:40:19 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 582.90 4.2431E-002 57.38 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/29/2019 10:40:20 AM Page 5

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D22-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 1.792E+004 1.79E+004 1.563E+005 7.871E+003 CO-60 1173.22 100.00 2.331E+003 1.76E+003 -6.350E+001 1.064E+003 1332.49 100.00 1.761E+003 -5.833E+002 7.717E+002 CS-134 475.35 1.46 1.121E+005 2.29E+003 -8.583E+004 5.187E+004 563.23 8.38 2.355E+004 1.172E+004 1.097E+004 569.32 15.43 1.218E+004 3.315E+003 5.652E+003 604.70 97.60 2.369E+003 3.528E+002 1.113E+003 795.84 85.40 2.287E+003 -8.897E+001 1.047E+003 801.93 8.73 1.972E+004 -1.866E+004 8.911E+003 1038.57 1.00 2.017E+005 1.763E+004 9.133E+004 1167.94 1.80 1.209E+005 -6.348E+004 5.484E+004 1365.15 3.04 2.899E+004 -3.299E+004 1.085E+004 CS-137 661.65 85.12 2.742E+003 2.74E+003 2.569E+003 1.284E+003 EU-152 121.78 28.40 8.299E+003 7.44E+003 8.032E+002 4.022E+003 344.27 26.50 7.440E+003 3.283E+002 3.528E+003 1407.95 20.70 7.612E+003 1.761E+003 3.259E+003 EU-154 123.07 40.40 5.666E+003 5.67E+003 -5.387E+003 2.744E+003 722.30 20.00 1.122E+004 5.675E+003 5.221E+003 1274.51 34.40 6.241E+003 2.835E+003 2.812E+003 BI-214 609.31 46.30 4.957E+003 4.96E+003 3.605E+003 2.326E+003 768.36 5.04 4.008E+004 4.432E+003 1.844E+004 806.17 1.23 1.465E+005 9.584E+004 6.654E+004 934.06 3.21 6.272E+004 2.454E+004 2.855E+004 1120.29 15.10 1.631E+004 6.030E+003 7.499E+003 1155.19 1.69 1.434E+005 1.809E+005 6.573E+004 1238.11 5.94 4.088E+004 9.768E+003 1.868E+004 1280.96 1.47 1.441E+005 2.560E+004 6.478E+004 1377.67 4.11 4.274E+004 -1.397E+004 1.866E+004 1385.31 0.78 2.322E+005 -5.475E+004 1.017E+005 1401.50 1.39 1.046E+005 -6.933E+004 4.416E+004 1407.98 2.48 6.354E+004 1.470E+004 2.720E+004 1509.19 2.19 6.376E+004 2.888E+003 2.644E+004 1661.28 1.15 1.075E+005 4.101E+004 4.266E+004 1729.60 3.05 5.993E+004 3.820E+004 2.566E+004 1764.49 15.80 1.215E+004 3.309E+003 5.229E+003 1847.44 2.12 4.440E+004 9.563E+003 1.573E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 7.853E+004 2.84E+003 8.643E+003 3.813E+004 77.11 10.70 4.427E+004 3.841E+004 2.152E+004 87.20 3.70 9.485E+004 2.694E+004 4.615E+004 89.80 1.03 3.262E+005 1.190E+005 1.587E+005 241.98 7.49 2.957E+004 3.826E+004 1.423E+004

Nuclide MDA Report 3/29/2019 10:40:20 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 1.044E+004 2.84E+003 9.433E+003 4.977E+003 351.92* 37.20 2.843E+003 1.767E+003 1.283E+003 785.91 1.10 1.935E+005 -1.912E+005 8.934E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 11:49:34 AM Sample Title  : B1-010-001-FSFC-D23-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D23 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 11:39:00 AM Acquisition Started  : 3/28/2019 11:39:32 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 11:49:34 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D23-GM Peak Analysis Performed on: 3/28/2019 11:49:33 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 949- 960 954.31 238.65 0.89 2.63E+001 27.52 6.47E+001 2 1400- 1414 1406.90 351.87 0.31 3.60E+001 26.24 4.70E+001 3 5828- 5851 5839.17 1459.80 1.97 2.25E+002 31.44 5.64E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 11:49:34 AM Page 3

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

Sample

Title:

B1-010-001-FSFC-D23-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.982 1460.81* 10.67 8.11277E+004 1.31530E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 8.19556E+002 8.66462E+002 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.65436E+003 1.23531E+003 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 11:49:34 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.982 8.112769E+004 1.315304E+004 PB-212 1.000 8.195564E+002 8.664624E+002 PB-214 1.000 1.654361E+003 1.235309E+003

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

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

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

Peak Locate Performed on: 3/28/2019 11:49:33 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/28/2019 11:49:34 AM Page 5

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D23-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 6.494E+003 6.49E+003 8.113E+004 2.760E+003 CO-60 1173.22 100.00 1.017E+003 9.00E+002 -1.197E+002 4.629E+002 1332.49 100.00 9.005E+002 8.278E+002 4.015E+002 CS-134 475.35 1.46 6.558E+004 1.07E+003 4.560E+004 3.092E+004 563.23 8.38 1.085E+004 3.372E+003 5.064E+003 569.32 15.43 5.673E+003 5.218E+003 2.640E+003 604.70 97.60 1.066E+003 1.005E+003 5.009E+002 795.84 85.40 1.252E+003 1.097E+003 5.829E+002 801.93 8.73 1.134E+004 -2.081E+004 5.245E+003 1038.57 1.00 8.755E+004 -3.877E+004 3.951E+004 1167.94 1.80 5.990E+004 4.614E+004 2.743E+004 1365.15 3.04 2.423E+004 -1.396E+004 1.048E+004 CS-137 661.65 85.12 1.171E+003 1.17E+003 1.172E+003 5.465E+002 EU-152 121.78 28.40 4.007E+003 3.57E+003 2.659E+003 1.946E+003 344.27 26.50 3.570E+003 -1.925E+003 1.699E+003 1407.95 20.70 4.059E+003 -9.921E+002 1.785E+003 EU-154 123.07 40.40 2.734E+003 2.73E+003 -2.634E+003 1.327E+003 722.30 20.00 4.446E+003 -5.464E+003 2.049E+003 1274.51 34.40 2.880E+003 -1.006E+003 1.302E+003 BI-214 609.31 46.30 2.270E+003 2.27E+003 5.563E+002 1.067E+003 768.36 5.04 1.864E+004 -3.170E+003 8.604E+003 806.17 1.23 7.925E+004 6.688E+004 3.661E+004 934.06 3.21 3.303E+004 6.725E+003 1.526E+004 1120.29 15.10 7.065E+003 3.433E+002 3.238E+003 1155.19 1.69 6.415E+004 2.073E+004 2.941E+004 1238.11 5.94 1.976E+004 -9.323E+003 9.094E+003 1280.96 1.47 7.342E+004 -6.127E+003 3.347E+004 1377.67 4.11 2.287E+004 1.501E+004 1.022E+004 1385.31 0.78 1.115E+005 9.488E+004 4.935E+004 1401.50 1.39 5.876E+004 1.105E+004 2.575E+004 1407.98 2.48 3.388E+004 -8.281E+003 1.490E+004 1509.19 2.19 2.355E+004 8.980E+003 9.343E+003 1661.28 1.15 6.104E+004 -3.358E+003 2.556E+004 1729.60 3.05 2.005E+004 8.528E+003 8.100E+003 1764.49 15.80 7.228E+003 4.372E+003 3.237E+003 1847.44 2.12 3.204E+004 1.494E+004 1.313E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.772E+004 1.89E+003 3.315E+004 1.834E+004 77.11 10.70 2.033E+004 8.092E+003 9.882E+003 87.20 3.70 4.472E+004 2.502E+004 2.178E+004 89.80 1.03 1.551E+005 1.204E+005 7.554E+004 241.98 7.49 1.373E+004 3.161E+003 6.615E+003

Nuclide MDA Report 3/28/2019 11:49:34 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.122E+003 1.89E+003 -1.551E+003 2.452E+003 351.92* 37.20 1.890E+003 1.654E+003 8.826E+002 785.91 1.10 8.569E+004 4.946E+004 3.953E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 12:02:52 PM Sample Title  : B1-010-001-FSFC-D24-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D24 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 11:51:00 AM Acquisition Started  : 3/28/2019 11:52:52 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 12:02:52 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D24-GM Peak Analysis Performed on: 3/28/2019 12:02:52 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 294- 306 299.51 74.81 0.85 5.34E+001 38.99 1.24E+002 2 948- 962 954.13 238.60 1.02 5.76E+001 32.86 7.34E+001 3 2428- 2439 2433.33 608.59 0.47 2.20E+001 17.27 2.00E+001 4 3634- 3647 3640.53 910.41 0.80 1.99E+001 16.41 1.61E+001 5 5828- 5850 5839.78 1459.96 1.59 2.18E+002 31.00 5.68E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 12:02:53 PM Page 3

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

Sample

Title:

B1-010-001-FSFC-D24-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.987 1460.81* 10.67 7.85984E+004 1.29130E+004 PB-212 0.713 74.81* 9.60 1.34566E+004 1.01952E+004 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.79207E+003 1.06172E+003 300.09 3.41 BI-214 0.996 609.31* 46.30 1.10785E+003 8.80160E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.993 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.11301E+003 1.75586E+003 964.60 5.20 969.11 16.60 1587.90 3.71

Interference Corrected Activity Report 3/28/2019 12:02:53 PM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 12:02:53 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.987 7.859841E+004 1.291303E+004 PB-212 0.713 1.917216E+003 1.056010E+003 BI-214 0.996 1.107855E+003 8.801605E+002 AC-228 0.993 2.113009E+003 1.755856E+003

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

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

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

Peak Locate Performed on: 3/28/2019 12:02:52 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/28/2019 12:02:53 PM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D24-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 6.527E+003 6.53E+003 7.860E+004 2.777E+003 CO-60 1173.22 100.00 1.105E+003 7.46E+002 4.445E+002 5.071E+002 1332.49 100.00 7.459E+002 -4.985E+002 3.243E+002 CS-134 475.35 1.46 6.691E+004 1.10E+003 -6.131E+004 3.158E+004 563.23 8.38 1.077E+004 -3.263E+002 5.026E+003 569.32 15.43 5.968E+003 -4.134E+003 2.788E+003 604.70 97.60 1.225E+003 1.040E+003 5.801E+002 795.84 85.40 1.101E+003 8.173E+002 5.075E+002 801.93 8.73 1.016E+004 2.009E+003 4.657E+003 1038.57 1.00 9.657E+004 2.194E+004 4.402E+004 1167.94 1.80 6.258E+004 -5.364E+004 2.877E+004 1365.15 3.04 2.568E+004 7.829E+003 1.121E+004 CS-137 661.65 85.12 1.171E+003 1.17E+003 2.288E+002 5.465E+002 EU-152 121.78 28.40 4.052E+003 3.69E+003 8.815E+002 1.968E+003 344.27 26.50 3.685E+003 -2.658E+003 1.756E+003 1407.95 20.70 3.748E+003 1.061E+003 1.629E+003 EU-154 123.07 40.40 2.817E+003 2.82E+003 -3.530E+003 1.368E+003 722.30 20.00 5.627E+003 6.918E+002 2.640E+003 1274.51 34.40 3.049E+003 1.260E+003 1.386E+003

+ BI-214 609.31* 46.30 1.336E+003 1.34E+003 1.108E+003 5.997E+002 768.36 5.04 1.999E+004 9.014E+002 9.280E+003 806.17 1.23 7.393E+004 -1.132E+004 3.395E+004 934.06 3.21 2.946E+004 -2.991E+004 1.348E+004 1120.29 15.10 7.811E+003 3.197E+001 3.612E+003 1155.19 1.69 6.627E+004 4.127E+004 3.046E+004 1238.11 5.94 1.915E+004 1.807E+003 8.785E+003 1280.96 1.47 6.226E+004 -3.054E+004 2.789E+004 1377.67 4.11 2.244E+004 5.946E+003 1.000E+004 1385.31 0.78 1.115E+005 -1.469E+005 4.935E+004 1401.50 1.39 6.025E+004 -3.355E+004 2.649E+004 1407.98 2.48 3.128E+004 8.855E+003 1.360E+004 1509.19 2.19 2.697E+004 -1.668E+004 1.105E+004 1661.28 1.15 5.166E+004 2.198E+004 2.087E+004 1729.60 3.05 2.369E+004 1.145E+003 9.920E+003 1764.49 15.80 5.598E+003 1.600E+003 2.423E+003 1847.44 2.12 3.556E+004 1.897E+003 1.489E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.858E+004 2.76E+003 6.146E+004 1.877E+004 77.11 10.70 2.042E+004 5.627E+003 9.929E+003 87.20 3.70 4.584E+004 3.571E+004 2.234E+004 89.80 1.03 1.592E+005 6.631E+004 7.761E+004 241.98 7.49 1.451E+004 -5.202E+003 7.003E+003

Nuclide MDA Report 3/28/2019 12:02:53 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 5.377E+003 2.76E+003 6.586E+003 2.579E+003 351.92 37.20 2.763E+003 2.704E+003 1.319E+003 785.91 1.10 9.354E+004 2.444E+004 4.345E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 12:17:06 PM Sample Title  : B1-010-001-FSFC-D25-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D25 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 12:05:00 AM Acquisition Started  : 3/28/2019 12:07:04 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 12:17:06 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D25-GM Peak Analysis Performed on: 3/28/2019 12:17:05 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 960 953.46 238.43 0.45 4.78E+001 32.12 7.62E+001 2 2428- 2443 2435.25 609.07 0.73 2.80E+001 18.77 2.00E+001 3 3633- 3647 3640.28 910.34 0.38 3.30E+001 17.46 1.50E+001 4 5828- 5850 5839.23 1459.82 1.03 2.66E+002 32.62 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 12:17:06 PM Page 3

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

Sample

Title:

B1-010-001-FSFC-D25-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.983 1460.81* 10.67 9.57578E+004 1.41588E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.48775E+003 1.02683E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.40911E+003 9.61511E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.992 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.49726E+003 1.89375E+003 964.60 5.20 969.11 16.60 1587.90 3.71

Interference Corrected Activity Report 3/28/2019 12:17:06 PM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 12:17:06 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.983 9.575782E+004 1.415880E+004 PB-212 1.000 1.487755E+003 1.026833E+003 BI-214 1.000 1.409106E+003 9.615115E+002 AC-228 0.992 3.497263E+003 1.893754E+003

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

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

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

Peak Locate Performed on: 3/28/2019 12:17:05 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/28/2019 12:17:06 PM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D25-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 9.741E+002 9.74E+002 9.576E+004 0.000E+000 CO-60 1173.22 100.00 1.030E+003 8.83E+002 4.602E+002 4.696E+002 1332.49 100.00 8.830E+002 2.847E+002 3.928E+002 CS-134 475.35 1.46 6.459E+004 1.11E+003 -1.047E+004 3.042E+004 563.23 8.38 1.062E+004 -1.929E+003 4.951E+003 569.32 15.43 6.133E+003 -3.421E+003 2.870E+003 604.70 97.60 1.108E+003 -1.271E+002 5.220E+002 795.84 85.40 1.123E+003 4.093E+001 5.184E+002 801.93 8.73 1.061E+004 -5.201E+003 4.881E+003 1038.57 1.00 9.662E+004 4.520E+004 4.404E+004 1167.94 1.80 5.924E+004 -2.697E+004 2.710E+004 1365.15 3.04 2.424E+004 7.618E+003 1.049E+004 CS-137 661.65 85.12 1.179E+003 1.18E+003 7.795E+002 5.506E+002 EU-152 121.78 28.40 4.022E+003 3.34E+003 2.641E+003 1.953E+003 344.27 26.50 3.343E+003 -4.599E+003 1.585E+003 1407.95 20.70 4.436E+003 1.180E+003 1.973E+003 EU-154 123.07 40.40 2.817E+003 2.82E+003 -1.093E+001 1.368E+003 722.30 20.00 4.700E+003 2.472E+003 2.176E+003 1274.51 34.40 2.837E+003 -2.278E+003 1.280E+003

+ BI-214 609.31* 46.30 1.419E+003 1.42E+003 1.409E+003 6.415E+002 768.36 5.04 1.916E+004 1.041E+003 8.863E+003 806.17 1.23 7.472E+004 2.173E+004 3.435E+004 934.06 3.21 3.241E+004 1.783E+004 1.495E+004 1120.29 15.10 7.221E+003 4.483E+003 3.316E+003 1155.19 1.69 5.811E+004 2.044E+004 2.638E+004 1238.11 5.94 2.131E+004 8.603E+003 9.869E+003 1280.96 1.47 5.761E+004 7.535E+003 2.556E+004 1377.67 4.11 1.859E+004 -2.242E+002 8.080E+003 1385.31 0.78 1.038E+005 0.000E+000 4.550E+004 1401.50 1.39 6.449E+004 1.425E+004 2.862E+004 1407.98 2.48 3.702E+004 9.845E+003 1.647E+004 1509.19 2.19 3.129E+004 1.796E+004 1.321E+004 1661.28 1.15 5.811E+004 2.930E+004 2.410E+004 1729.60 3.05 1.530E+004 4.264E+003 5.727E+003 1764.49 15.80 6.544E+003 3.611E+003 2.896E+003 1847.44 2.12 2.297E+004 6.402E+003 8.598E+003

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.716E+004 2.61E+003 2.242E+004 1.806E+004 77.11 10.70 2.077E+004 1.644E+004 1.010E+004 87.20 3.70 4.263E+004 -2.617E+004 2.074E+004 89.80 1.03 1.519E+005 7.177E+004 7.396E+004 241.98 7.49 1.462E+004 1.955E+004 7.056E+003

Nuclide MDA Report 3/28/2019 12:17:06 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 4.930E+003 2.61E+003 -5.908E+002 2.355E+003 351.92 37.20 2.611E+003 8.049E+002 1.243E+003 785.91 1.10 8.233E+004 -7.799E+004 3.785E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 8:21:21 AM Sample Title  : B1-010-001-FSFC-D26-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D26 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 7:54:00 AM Acquisition Started  : 3/28/2019 8:11:21 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 8:21:21 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D26-GM Peak Analysis Performed on: 3/28/2019 8:21:21 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 961 954.01 238.57 0.80 5.27E+001 32.90 7.53E+001 2 1400- 1414 1406.03 351.65 0.41 5.08E+001 22.57 2.63E+001 3 3636- 3649 3642.43 910.88 0.35 2.99E+001 15.90 1.21E+001 4 5827- 5852 5840.35 1460.10 1.96 2.60E+002 33.90 6.49E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 8:21:21 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D26-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.991 1460.81* 10.67 9.34334E+004 1.44404E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.64017E+003 1.05670E+003 300.09 3.41 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 2.33317E+003 1.10273E+003 785.91 1.10 AC-228 0.997 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.16711E+003 1.72495E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 8:21:21 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.991 9.343339E+004 1.444039E+004 PB-212 1.000 1.640174E+003 1.056703E+003 PB-214 0.999 2.333166E+003 1.102726E+003 AC-228 0.997 3.167115E+003 1.724951E+003

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

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

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

Peak Locate Performed on: 3/28/2019 8:21:21 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/28/2019 8:21:22 AM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D26-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 7.213E+003 7.21E+003 9.343E+004 3.119E+003 CO-60 1173.22 100.00 1.004E+003 9.51E+002 -1.454E+002 4.563E+002 1332.49 100.00 9.512E+002 6.423E+002 4.269E+002 CS-134 475.35 1.46 5.958E+004 1.14E+003 -1.755E+003 2.791E+004 563.23 8.38 1.179E+004 7.712E+003 5.533E+003 569.32 15.43 5.886E+003 3.295E+003 2.746E+003 604.70 97.60 1.137E+003 1.727E+003 5.363E+002 795.84 85.40 1.194E+003 1.115E+003 5.540E+002 801.93 8.73 1.027E+004 -7.157E+003 4.714E+003 1038.57 1.00 8.618E+004 -6.271E+004 3.882E+004 1167.94 1.80 5.334E+004 1.598E+004 2.415E+004 1365.15 3.04 2.098E+004 -2.252E+004 8.861E+003 CS-137 661.65 85.12 1.031E+003 1.03E+003 1.175E+002 4.768E+002 EU-152 121.78 28.40 4.117E+003 3.37E+003 4.706E+003 2.001E+003 344.27 26.50 3.370E+003 -3.497E+003 1.599E+003 1407.95 20.70 4.059E+003 -4.069E+003 1.785E+003 EU-154 123.07 40.40 2.806E+003 2.75E+003 -1.316E+003 1.363E+003 722.30 20.00 4.700E+003 3.060E+003 2.176E+003 1274.51 34.40 2.747E+003 1.893E+003 1.235E+003 BI-214 609.31 46.30 2.431E+003 2.43E+003 2.144E+003 1.147E+003 768.36 5.04 2.185E+004 1.819E+004 1.021E+004 806.17 1.23 7.393E+004 -1.311E+004 3.395E+004 934.06 3.21 2.911E+004 2.185E+003 1.330E+004 1120.29 15.10 8.552E+003 2.254E+003 3.982E+003 1155.19 1.69 5.480E+004 2.714E+004 2.473E+004 1238.11 5.94 1.996E+004 1.792E+004 9.194E+003 1280.96 1.47 6.656E+004 5.130E+004 3.004E+004 1377.67 4.11 2.061E+004 1.058E+004 9.093E+003 1385.31 0.78 1.065E+005 2.122E+004 4.682E+004 1401.50 1.39 6.716E+004 4.105E+004 2.995E+004 1407.98 2.48 3.388E+004 -3.396E+004 1.490E+004 1509.19 2.19 3.499E+004 2.335E+004 1.507E+004 1661.28 1.15 4.802E+004 -9.890E+003 1.905E+004 1729.60 3.05 2.255E+004 1.137E+004 9.353E+003 1764.49 15.80 7.356E+003 7.236E+003 3.301E+003 1847.44 2.12 3.717E+004 2.134E+004 1.570E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.949E+004 1.45E+003 3.959E+004 1.923E+004 77.11 10.70 2.188E+004 2.483E+004 1.066E+004 87.20 3.70 4.343E+004 -7.361E+003 2.114E+004 89.80 1.03 1.494E+005 -2.071E+004 7.268E+004 241.98 7.49 1.507E+004 1.045E+004 7.280E+003

Nuclide MDA Report 3/28/2019 8:21:22 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.418E+003 1.45E+003 3.949E+003 2.599E+003 351.92* 37.20 1.448E+003 2.333E+003 6.619E+002 785.91 1.10 8.318E+004 -3.184E+004 3.827E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D27-GM.CNF Report Generated On  : 3/29/2019 10:43:38 AM Sample Title  : B1-010-001-FSFC-D27-GM Sample Description  : Rx Bowl 2M Concrete Sample Identification  : D27 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 1.256E+001 M^2 Sample Taken On  : 3/28/2019 3:15:00 PM Acquisition Started  : 3/28/2019 3:15:57 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_2M

Peak Analysis Report 3/29/2019 10:43:38 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D27-GM Peak Analysis Performed on: 3/29/2019 10:43:38 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 960 954.04 238.58 1.01 5.30E+001 31.72 6.80E+001 2 2636- 2652 2644.51 661.39 1.01 7.12E+001 21.68 1.48E+001 3 3635- 3648 3641.05 910.54 0.61 3.40E+001 11.66 0.00E+000 4 5828- 5851 5839.09 1459.78 1.95 2.05E+002 29.38 2.77E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:43:38 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D27-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.981 1460.81* 10.67 1.65258E+005 2.73123E+004 CS-137 0.999 661.65* 85.12 4.56625E+003 1.49551E+003 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 3.66110E+003 2.26658E+003 300.09 3.41 AC-228 0.994 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 8.06186E+003 2.91850E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:43:38 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.981 1.652578E+005 2.731226E+004 CS-137 0.999 4.566251E+003 1.495509E+003 PB-212 1.000 3.661098E+003 2.266575E+003 AC-228 0.994 8.061860E+003 2.918497E+003

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

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

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

Peak Locate Performed on: 3/29/2019 10:43:38 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/29/2019 10:43:38 AM Page 5

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D27-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 1.077E+004 1.08E+004 1.653E+005 4.295E+003 CO-60 1173.22 100.00 2.524E+003 1.76E+003 1.015E+003 1.160E+003 1332.49 100.00 1.761E+003 -3.738E+002 7.717E+002 CS-134 475.35 1.46 1.226E+005 2.27E+003 -2.319E+003 5.709E+004 563.23 8.38 2.248E+004 7.460E+003 1.043E+004 569.32 15.43 1.248E+004 2.597E+003 5.801E+003 604.70 97.60 2.271E+003 7.795E+002 1.063E+003 795.84 85.40 2.287E+003 -3.009E+003 1.047E+003 801.93 8.73 2.348E+004 -1.903E+004 1.079E+004 1038.57 1.00 1.957E+005 4.632E+004 8.833E+004 1167.94 1.80 1.384E+005 6.054E+004 6.357E+004 1365.15 3.04 4.273E+004 2.154E+004 1.772E+004

+ CS-137 661.65* 85.12 1.611E+003 1.61E+003 4.566E+003 7.187E+002 EU-152 121.78 28.40 8.580E+003 7.59E+003 2.707E+003 4.163E+003 344.27 26.50 7.593E+003 -1.087E+004 3.604E+003 1407.95 20.70 8.381E+003 2.864E+003 3.644E+003 EU-154 123.07 40.40 5.992E+003 5.37E+003 -3.202E+003 2.907E+003 722.30 20.00 1.051E+004 9.168E+003 4.867E+003 1274.51 34.40 5.370E+003 -2.398E+003 2.376E+003 BI-214 609.31 46.30 5.326E+003 5.33E+003 5.101E+003 2.511E+003 768.36 5.04 4.049E+004 -3.508E+004 1.865E+004 806.17 1.23 1.706E+005 -5.239E+004 7.856E+004 934.06 3.21 5.936E+004 5.187E+003 2.687E+004 1120.29 15.10 1.579E+004 8.451E+003 7.239E+003 1155.19 1.69 1.299E+005 4.158E+004 5.897E+004 1238.11 5.94 4.185E+004 5.128E+003 1.916E+004 1280.96 1.47 1.260E+005 2.546E+004 5.576E+004 1377.67 4.11 4.033E+004 8.665E+003 1.745E+004 1385.31 0.78 2.438E+005 2.015E+005 1.076E+005 1401.50 1.39 1.207E+005 8.403E+004 5.225E+004 1407.98 2.48 6.996E+004 2.391E+004 3.041E+004 1509.19 2.19 7.000E+004 4.019E+004 2.956E+004 1661.28 1.15 7.616E+004 -4.921E+004 2.698E+004 1729.60 3.05 4.780E+004 2.274E+003 1.959E+004 1764.49 15.80 1.215E+004 3.825E+003 5.229E+003 1847.44 2.12 7.586E+004 3.825E+004 3.146E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 7.943E+004 5.63E+003 8.808E+004 3.858E+004 77.11 10.70 4.390E+004 2.825E+004 2.133E+004 87.20 3.70 8.794E+004 -1.147E+005 4.270E+004 89.80 1.03 3.133E+005 4.489E+003 1.523E+005 241.98 7.49 3.085E+004 1.656E+004 1.486E+004

Nuclide MDA Report 3/29/2019 10:43:38 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 1.034E+004 5.63E+003 2.822E+003 4.924E+003 351.92 37.20 5.625E+003 7.913E+003 2.674E+003 785.91 1.10 1.701E+005 -1.736E+005 7.763E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D28-GM.CNF Report Generated On  : 3/29/2019 10:46:21 AM Sample Title  : B1-010-001-FSFC-D28-GM Sample Description  : Rx Bowl 2M Concrete Sample Identification  : D28 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 1.256E+001 M^2 Sample Taken On  : 3/28/2019 3:02:00 PM Acquisition Started  : 3/28/2019 3:02:25 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_2M

Peak Analysis Report 3/29/2019 10:46:21 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D28-GM Peak Analysis Performed on: 3/29/2019 10:46:21 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 945- 961 954.48 238.69 1.53 6.77E+001 33.81 6.83E+001 2 1402- 1415 1407.09 351.92 0.58 1.86E+001 20.84 3.24E+001 3 2036- 2048 2042.38 510.82 0.39 3.43E+001 18.85 2.07E+001 4 2427- 2439 2433.77 608.70 0.79 2.69E+001 16.64 1.61E+001 5 2634- 2653 2643.87 661.23 1.07 1.10E+002 27.43 2.24E+001 6 3345- 3358 3351.71 838.21 0.46 1.30E+001 11.49 7.03E+000 7 5828- 5852 5840.16 1460.05 2.10 2.31E+002 32.62 8.76E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:46:21 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D28-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.990 1460.81* 10.67 1.86227E+005 3.04451E+004 CS-137 0.997 661.65* 85.12 7.02899E+003 1.95187E+003 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 4.67158E+003 2.45079E+003 300.09 3.41 BI-214 0.997 609.31* 46.30 3.02434E+003 1.91115E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.90192E+003 2.15533E+003 785.91 1.10

Interference Corrected Activity Report 3/29/2019 10:46:21 AM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:46:21 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.990 1.862271E+005 3.044507E+004 CS-137 0.997 7.028987E+003 1.951866E+003 PB-212 1.000 4.671576E+003 2.450787E+003 BI-214 0.997 3.024340E+003 1.911154E+003 PB-214 1.000 1.901919E+003 2.155330E+003

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

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

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

Peak Locate Performed on: 3/29/2019 10:46:21 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 510.82 5.7129E-002 54.99 6 838.21 2.1625E-002 88.59 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/29/2019 10:46:21 AM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D28-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 1.781E+004 1.78E+004 1.862E+005 7.816E+003 CO-60 1173.22 100.00 2.151E+003 1.89E+003 -4.717E+002 9.738E+002 1332.49 100.00 1.892E+003 1.121E+003 8.370E+002 CS-134 475.35 1.46 1.338E+005 2.31E+003 -5.107E+004 6.271E+004 563.23 8.38 2.284E+004 -1.786E+004 1.062E+004 569.32 15.43 1.277E+004 5.471E+003 5.947E+003 604.70 97.60 2.515E+003 2.073E+003 1.186E+003 795.84 85.40 2.313E+003 -5.160E+002 1.060E+003 801.93 8.73 2.195E+004 -7.454E+002 1.003E+004 1038.57 1.00 2.266E+005 8.109E+004 1.037E+005 1167.94 1.80 1.276E+005 5.269E+004 5.816E+004 1365.15 3.04 6.045E+004 -1.863E+004 2.658E+004

+ CS-137 661.65* 85.12 2.044E+003 2.04E+003 7.029E+003 9.350E+002 EU-152 121.78 28.40 8.907E+003 7.50E+003 3.978E+003 4.326E+003 344.27 26.50 7.501E+003 -3.260E+003 3.559E+003 1407.95 20.70 8.620E+003 -3.911E+003 3.763E+003 EU-154 123.07 40.40 6.246E+003 6.24E+003 3.045E+003 3.034E+003 722.30 20.00 1.014E+004 1.034E+004 4.680E+003 1274.51 34.40 6.241E+003 -5.995E+002 2.812E+003

+ BI-214 609.31* 46.30 2.712E+003 2.71E+003 3.024E+003 1.204E+003 768.36 5.04 4.129E+004 1.665E+004 1.905E+004 806.17 1.23 1.465E+005 4.639E+004 6.654E+004 934.06 3.21 6.272E+004 2.879E+004 2.855E+004 1120.29 15.10 1.597E+004 1.300E+004 7.326E+003 1155.19 1.69 1.418E+005 3.552E+004 6.492E+004 1238.11 5.94 4.372E+004 -3.094E+004 2.010E+004 1280.96 1.47 1.577E+005 5.578E+004 7.162E+004 1377.67 4.11 4.389E+004 -1.038E+004 1.923E+004 1385.31 0.78 2.381E+005 1.214E+005 1.047E+005 1401.50 1.39 1.244E+005 9.003E+004 5.408E+004 1407.98 2.48 7.195E+004 -3.265E+004 3.141E+004 1509.19 2.19 6.376E+004 3.014E+003 2.644E+004 1661.28 1.15 7.616E+004 -2.870E+004 2.698E+004 1729.60 3.05 4.174E+004 -5.730E+003 1.656E+004 1764.49 15.80 1.399E+004 1.122E+004 6.153E+003 1847.44 2.12 7.180E+004 3.347E+004 2.943E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 8.052E+004 3.47E+003 9.259E+003 3.912E+004 77.11 10.70 4.390E+004 5.266E+003 2.133E+004 87.20 3.70 9.650E+004 7.934E+004 4.698E+004 89.80 1.03 3.354E+005 -5.045E+004 1.633E+005 241.98 7.49 3.249E+004 -5.635E+003 1.569E+004

Nuclide MDA Report 3/29/2019 10:46:21 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 1.106E+004 3.47E+003 -1.976E+003 5.286E+003 351.92* 37.20 3.473E+003 1.902E+003 1.598E+003 785.91 1.10 1.803E+005 -7.132E+004 8.271E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D29-GM.CNF Report Generated On  : 3/27/2019 9:00:26 PM Sample Title  : B1-010-001-FSFC-D29-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D29 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 8:24:00 AM Acquisition Started  : 3/27/2019 8:24:53 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 9:00:26 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D29-GM Peak Analysis Performed on: 3/27/2019 9:00:26 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 960 954.64 238.73 0.92 7.99E+001 28.14 4.11E+001 2 1345- 1358 1351.47 338.00 1.14 2.42E+001 19.55 2.48E+001 3 2323- 2336 2330.37 582.84 1.04 2.49E+001 18.25 2.11E+001 4 2426- 2439 2432.82 608.46 0.32 3.43E+001 17.66 1.57E+001 5 3634- 3647 3640.51 910.40 0.76 1.44E+001 12.23 7.57E+000 6 5825- 5847 5836.64 1459.17 1.23 2.12E+002 33.40 1.73E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:00:26 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D29-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.953 1460.81* 10.67 7.61936E+004 1.35690E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.48737E+003 9.62059E+002 300.09 3.41 BI-214 0.995 609.31* 46.30 1.72568E+003 9.15519E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.992 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32* 11.40 3.55745E+003 2.92712E+003 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 1.52951E+003 1.30843E+003 964.60 5.20 969.11 16.60 1587.90 3.71

Interference Corrected Activity Report 3/27/2019 9:00:26 PM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:00:26 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.953 7.619356E+004 1.356903E+004 PB-212 1.000 2.487372E+003 9.620595E+002 BI-214 0.995 1.725677E+003 9.155186E+002 AC-228 0.992 1.867229E+003 1.194521E+003

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

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

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

Peak Locate Performed on: 3/27/2019 9:00:26 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 582.84 4.1558E-002 73.20 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 9:00:26 PM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D29-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 1.068E+004 1.07E+004 7.619E+004 4.853E+003 CO-60 1173.22 100.00 1.017E+003 7.67E+002 -3.616E+002 4.629E+002 1332.49 100.00 7.672E+002 -9.059E+002 3.349E+002 CS-134 475.35 1.46 5.807E+004 8.97E+002 1.924E+004 2.716E+004 563.23 8.38 1.022E+004 -1.165E+003 4.752E+003 569.32 15.43 5.407E+003 2.545E+003 2.507E+003 604.70 97.60 1.114E+003 1.316E+003 5.247E+002 795.84 85.40 8.970E+002 3.071E+002 4.054E+002 801.93 8.73 7.972E+003 -1.027E+004 3.563E+003 1038.57 1.00 9.534E+004 -2.406E+004 4.340E+004 1167.94 1.80 5.487E+004 -8.982E+003 2.491E+004 1365.15 3.04 2.704E+004 -5.119E+003 1.189E+004 CS-137 661.65 85.12 9.221E+002 9.22E+002 -2.798E+001 4.222E+002 EU-152 121.78 28.40 3.831E+003 3.17E+003 7.891E+002 1.858E+003 344.27 26.50 3.171E+003 -2.601E+003 1.499E+003 1407.95 20.70 4.252E+003 -5.990E+002 1.881E+003 EU-154 123.07 40.40 2.679E+003 2.68E+003 -9.689E+002 1.299E+003 722.30 20.00 4.532E+003 -3.078E+003 2.092E+003 1274.51 34.40 2.880E+003 -3.406E+001 1.302E+003

+ BI-214 609.31* 46.30 1.230E+003 1.23E+003 1.726E+003 5.469E+002 768.36 5.04 1.846E+004 1.483E+004 8.516E+003 806.17 1.23 6.551E+004 4.684E+004 2.974E+004 934.06 3.21 2.181E+004 -1.762E+003 9.650E+003 1120.29 15.10 6.823E+003 1.321E+003 3.117E+003 1155.19 1.69 5.968E+004 -5.274E+003 2.717E+004 1238.11 5.94 1.807E+004 9.150E+003 8.246E+003 1280.96 1.47 5.761E+004 -1.379E+004 2.556E+004 1377.67 4.11 2.244E+004 1.392E+004 1.000E+004 1385.31 0.78 9.832E+004 -5.028E+004 4.274E+004 1401.50 1.39 5.722E+004 2.810E+004 2.498E+004 1407.98 2.48 3.549E+004 -5.000E+003 1.570E+004 1509.19 2.19 3.129E+004 -1.033E+004 1.321E+004 1661.28 1.15 5.500E+004 2.564E+004 2.254E+004 1729.60 3.05 1.863E+004 7.107E+003 7.394E+003 1764.49 15.80 5.239E+003 -1.322E+003 2.243E+003 1847.44 2.12 3.386E+004 1.707E+004 1.404E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.605E+004 2.60E+003 3.993E+004 1.751E+004 77.11 10.70 1.940E+004 1.394E+004 9.421E+003 87.20 3.70 4.263E+004 5.442E+004 2.074E+004 89.80 1.03 1.477E+005 6.933E+004 7.187E+004 241.98 7.49 1.385E+004 9.702E+003 6.672E+003

Nuclide MDA Report 3/27/2019 9:00:26 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 4.823E+003 2.60E+003 2.460E+003 2.302E+003 351.92 37.20 2.602E+003 3.461E+003 1.239E+003 785.91 1.10 7.881E+004 3.786E+004 3.608E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 8:33:23 AM Sample Title  : B1-010-001-FSFC-D30-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D30 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 8:23:00 AM Acquisition Started  : 3/28/2019 8:23:22 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 8:33:23 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D30-GM Peak Analysis Performed on: 3/28/2019 8:33:23 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 960 953.61 238.47 1.13 5.53E+001 33.02 7.47E+001 2 1399- 1413 1406.01 351.65 0.63 4.73E+001 23.04 2.97E+001 3 2326- 2337 2331.50 583.12 0.76 2.63E+001 12.75 5.72E+000 4 2429- 2443 2436.34 609.34 0.55 3.63E+001 19.06 1.88E+001 5 5830- 5852 5841.42 1460.36 1.39 2.25E+002 32.07 8.48E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 8:33:23 AM Page 3

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

Sample

Title:

B1-010-001-FSFC-D30-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.996 1460.81* 10.67 8.08452E+004 1.33398E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.71973E+003 1.06325E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.82475E+003 9.87560E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 2.17613E+003 1.11490E+003 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 8:33:23 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.996 8.084517E+004 1.333982E+004 PB-212 1.000 1.719732E+003 1.063248E+003 BI-214 1.000 1.824754E+003 9.875603E+002 PB-214 0.999 2.176126E+003 1.114895E+003

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

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

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

Peak Locate Performed on: 3/28/2019 8:33:23 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 583.12 4.3802E-002 48.50 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 8:33:23 AM Page 5

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D30-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 7.736E+003 7.74E+003 8.085E+004 3.381E+003 CO-60 1173.22 100.00 1.117E+003 8.83E+002 -6.168E+002 5.131E+002 1332.49 100.00 8.828E+002 -9.815E+000 3.927E+002 CS-134 475.35 1.46 6.524E+004 1.08E+003 -3.559E+004 3.075E+004 563.23 8.38 1.100E+004 -2.257E+003 5.139E+003 569.32 15.43 5.886E+003 3.062E+003 2.746E+003 604.70 97.60 1.176E+003 -1.165E+003 5.559E+002 795.84 85.40 1.079E+003 -9.811E+001 4.966E+002 801.93 8.73 1.103E+004 2.456E+003 5.091E+003 1038.57 1.00 9.657E+004 -1.112E+005 4.402E+004 1167.94 1.80 6.126E+004 -7.697E+004 2.811E+004 1365.15 3.04 2.704E+004 1.076E+004 1.189E+004 CS-137 661.65 85.12 1.086E+003 1.09E+003 2.871E+002 5.040E+002 EU-152 121.78 28.40 4.077E+003 3.15E+003 -2.254E+003 1.981E+003 344.27 26.50 3.531E+003 -6.515E+003 1.679E+003 1407.95 20.70 3.150E+003 -3.020E+003 1.330E+003 EU-154 123.07 40.40 2.831E+003 2.83E+003 -1.462E+002 1.375E+003 722.30 20.00 4.861E+003 2.175E+003 2.257E+003 1274.51 34.40 2.880E+003 1.507E+003 1.302E+003

+ BI-214 609.31* 46.30 1.360E+003 1.36E+003 1.825E+003 6.118E+002 768.36 5.04 1.949E+004 1.173E+004 9.032E+003 806.17 1.23 7.851E+004 -4.036E+004 3.625E+004 934.06 3.21 2.840E+004 -1.130E+004 1.295E+004 1120.29 15.10 7.952E+003 6.287E+003 3.682E+003 1155.19 1.69 5.811E+004 -1.153E+004 2.638E+004 1238.11 5.94 2.055E+004 1.055E+004 9.489E+003 1280.96 1.47 6.337E+004 -4.643E+004 2.844E+004 1377.67 4.11 1.804E+004 1.255E+004 7.806E+003 1385.31 0.78 9.832E+004 -3.953E+004 4.274E+004 1401.50 1.39 5.399E+004 -2.986E+004 2.336E+004 1407.98 2.48 2.629E+004 -2.521E+004 1.110E+004 1509.19 2.19 3.381E+004 -3.667E+003 1.447E+004 1661.28 1.15 5.811E+004 2.930E+004 2.410E+004 1729.60 3.05 1.863E+004 -5.330E+003 7.394E+003 1764.49 15.80 6.398E+003 3.190E+003 2.822E+003 1847.44 2.12 2.563E+004 8.536E+003 9.928E+003

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.941E+004 1.52E+003 4.484E+004 1.919E+004 77.11 10.70 2.190E+004 2.148E+004 1.067E+004 87.20 3.70 4.531E+004 -4.897E+003 2.208E+004 89.80 1.03 1.540E+005 -4.237E+004 7.499E+004 241.98 7.49 1.527E+004 2.390E+004 7.383E+003

Nuclide MDA Report 3/28/2019 8:33:23 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 4.975E+003 1.52E+003 -3.303E+003 2.378E+003 351.92* 37.20 1.522E+003 2.176E+003 6.987E+002 785.91 1.10 8.813E+004 -9.810E+003 4.075E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 8:55:50 AM Sample Title  : B1-010-001-FSFC-D31-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D31 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 8:43:00 AM Acquisition Started  : 3/28/2019 8:45:49 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 8:55:50 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D31-GM Peak Analysis Performed on: 3/28/2019 8:55:50 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 959 953.42 238.42 0.93 4.05E+001 33.97 8.85E+001 2 2324- 2339 2330.78 582.94 0.63 3.80E+001 18.57 1.60E+001 3 2429- 2442 2436.35 609.34 1.47 3.48E+001 18.76 1.92E+001 4 3636- 3649 3642.85 910.99 0.95 2.32E+001 15.66 1.38E+001 5 5829- 5852 5841.66 1460.43 1.55 2.49E+002 33.05 6.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 8:55:51 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D31-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.997 1460.81* 10.67 8.96646E+004 1.40173E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.25888E+003 1.07557E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.75345E+003 9.70577E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.998 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.45849E+003 1.68465E+003 964.60 5.20 969.11 16.60 1587.90 3.71

Interference Corrected Activity Report 3/28/2019 8:55:51 AM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 8:55:51 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.997 8.966464E+004 1.401732E+004 PB-212 1.000 1.258878E+003 1.075569E+003 BI-214 1.000 1.753446E+003 9.705772E+002 AC-228 0.998 2.458490E+003 1.684649E+003

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

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

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

Peak Locate Performed on: 3/28/2019 8:55:50 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 582.94 6.3333E-002 48.87 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 8:55:51 AM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D31-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 6.781E+003 6.78E+003 8.966E+004 2.903E+003 CO-60 1173.22 100.00 9.624E+002 7.67E+002 -3.746E+002 4.357E+002 1332.49 100.00 7.672E+002 2.699E+001 3.349E+002 CS-134 475.35 1.46 5.883E+004 1.09E+003 -7.474E+004 2.754E+004 563.23 8.38 1.030E+004 5.252E+003 4.792E+003 569.32 15.43 6.009E+003 -1.242E+003 2.808E+003 604.70 97.60 1.148E+003 2.929E+002 5.419E+002 795.84 85.40 1.090E+003 6.433E+002 5.021E+002 801.93 8.73 1.092E+004 -4.284E+003 5.039E+003 1038.57 1.00 9.779E+004 2.664E+003 4.463E+004 1167.94 1.80 5.921E+004 -2.542E+004 2.708E+004 1365.15 3.04 2.098E+004 3.071E+003 8.861E+003 CS-137 661.65 85.12 1.154E+003 1.15E+003 9.073E+002 5.383E+002 EU-152 121.78 28.40 4.087E+003 3.44E+003 1.116E+003 1.986E+003 344.27 26.50 3.438E+003 -5.375E+003 1.633E+003 1407.95 20.70 3.855E+003 -3.956E+001 1.683E+003 EU-154 123.07 40.40 2.887E+003 2.89E+003 1.832E+003 1.403E+003 722.30 20.00 5.349E+003 4.197E+003 2.501E+003 1274.51 34.40 3.129E+003 3.024E+003 1.426E+003

+ BI-214 609.31* 46.30 1.343E+003 1.34E+003 1.753E+003 6.036E+002 768.36 5.04 1.881E+004 -6.065E+003 8.691E+003 806.17 1.23 8.141E+004 8.580E+004 3.770E+004 934.06 3.21 3.210E+004 2.340E+004 1.479E+004 1120.29 15.10 7.952E+003 5.128E+003 3.682E+003 1155.19 1.69 6.764E+004 -2.961E+004 3.115E+004 1238.11 5.94 1.976E+004 7.964E+003 9.094E+003 1280.96 1.47 5.999E+004 -7.216E+004 2.675E+004 1377.67 4.11 2.370E+004 1.648E+004 1.064E+004 1385.31 0.78 1.065E+005 -2.172E+005 4.682E+004 1401.50 1.39 5.563E+004 -8.871E+004 2.418E+004 1407.98 2.48 3.218E+004 -3.302E+002 1.405E+004 1509.19 2.19 3.129E+004 1.796E+004 1.321E+004 1661.28 1.15 4.802E+004 1.831E+004 1.905E+004 1729.60 3.05 1.707E+004 -8.972E+003 6.613E+003 1764.49 15.80 6.963E+003 3.794E+003 3.105E+003 1847.44 2.12 3.556E+004 -1.624E+004 1.489E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.858E+004 2.68E+003 2.515E+004 1.877E+004 77.11 10.70 2.114E+004 1.917E+004 1.029E+004 87.20 3.70 4.282E+004 2.374E+004 2.083E+004 89.80 1.03 1.497E+005 5.541E+004 7.284E+004 241.98 7.49 1.527E+004 2.033E+004 7.383E+003

Nuclide MDA Report 3/28/2019 8:55:51 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 5.251E+003 2.68E+003 2.953E+002 2.516E+003 351.92 37.20 2.683E+003 2.166E+003 1.279E+003 785.91 1.10 8.059E+004 3.556E+004 3.698E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 9:08:53 AM Sample Title  : B1-010-001-FSFC-D32-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D32 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 8:58:00 AM Acquisition Started  : 3/28/2019 8:58:52 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 9:08:53 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D32-GM Peak Analysis Performed on: 3/28/2019 9:08:53 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 1401- 1413 1406.51 351.77 0.34 3.07E+001 20.09 2.63E+001 2 2324- 2336 2329.50 582.62 0.89 2.26E+001 15.37 1.34E+001 3 2428- 2442 2434.61 608.91 1.20 4.53E+001 17.22 9.66E+000 4 5827- 5851 5840.39 1460.11 1.65 2.42E+002 31.91 3.08E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 9:08:53 AM Page 3

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

Sample

Title:

B1-010-001-FSFC-D32-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.991 1460.81* 10.67 8.71025E+004 1.35555E+004 BI-214 0.999 609.31* 46.30 2.28145E+003 9.14461E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.41154E+003 9.50770E+002 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 9:08:53 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.991 8.710249E+004 1.355552E+004 BI-214 0.999 2.281452E+003 9.144613E+002 PB-214 1.000 1.411535E+003 9.507704E+002

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

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

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

Peak Locate Performed on: 3/28/2019 9:08:53 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 582.62 3.7708E-002 67.92 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 9:08:53 AM Page 5

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D32-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 5.177E+003 5.18E+003 8.710E+004 2.102E+003 CO-60 1173.22 100.00 1.068E+003 9.99E+002 -6.598E+002 4.887E+002 1332.49 100.00 9.991E+002 1.787E+002 4.509E+002 CS-134 475.35 1.46 6.248E+004 9.99E+002 -3.849E+004 2.936E+004 563.23 8.38 1.136E+004 9.963E+002 5.322E+003 569.32 15.43 6.050E+003 9.082E+002 2.828E+003 604.70 97.60 1.171E+003 9.244E+002 5.531E+002 795.84 85.40 9.987E+002 -1.428E+002 4.563E+002 801.93 8.73 9.574E+003 -5.923E+003 4.364E+003 1038.57 1.00 9.409E+004 1.952E+004 4.278E+004 1167.94 1.80 6.258E+004 1.575E+004 2.877E+004 1365.15 3.04 1.911E+004 -1.716E+004 7.926E+003 CS-137 661.65 85.12 1.103E+003 1.10E+003 7.485E+002 5.128E+002 EU-152 121.78 28.40 4.097E+003 3.37E+003 -2.920E+003 1.991E+003 344.27 26.50 3.370E+003 -5.418E+002 1.599E+003 1407.95 20.70 4.252E+003 -5.909E+003 1.881E+003 EU-154 123.07 40.40 2.873E+003 2.87E+003 3.136E+002 1.396E+003 722.30 20.00 4.740E+003 -2.683E+003 2.196E+003 1274.51 34.40 3.129E+003 2.099E+003 1.426E+003

+ BI-214 609.31* 46.30 1.025E+003 1.02E+003 2.281E+003 4.442E+002 768.36 5.04 2.079E+004 1.099E+004 9.678E+003 806.17 1.23 6.986E+004 -3.962E+004 3.192E+004 934.06 3.21 3.048E+004 6.211E+003 1.398E+004 1120.29 15.10 8.157E+003 7.062E+003 3.784E+003 1155.19 1.69 6.898E+004 3.455E+004 3.182E+004 1238.11 5.94 1.976E+004 2.117E+003 9.094E+003 1280.96 1.47 7.434E+004 6.561E+004 3.393E+004 1377.67 4.11 1.963E+004 8.506E+003 8.601E+003 1385.31 0.78 1.065E+005 -2.036E+004 4.682E+004 1401.50 1.39 6.584E+004 5.905E+004 2.929E+004 1407.98 2.48 3.549E+004 -4.932E+004 1.570E+004 1509.19 2.19 2.533E+004 -5.328E+004 1.023E+004 1661.28 1.15 4.802E+004 -7.326E+003 1.905E+004 1729.60 3.05 2.134E+004 -1.015E+003 8.749E+003 1764.49 15.80 6.827E+003 6.123E+003 3.037E+003 1847.44 2.12 3.386E+004 1.707E+004 1.404E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.904E+004 1.39E+003 1.173E+004 1.900E+004 77.11 10.70 2.155E+004 1.417E+004 1.049E+004 87.20 3.70 4.277E+004 -1.657E+004 2.081E+004 89.80 1.03 1.513E+005 6.134E+004 7.365E+004 241.98 7.49 1.486E+004 1.305E+004 7.176E+003

Nuclide MDA Report 3/28/2019 9:08:53 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.064E+003 1.39E+003 -5.822E+002 2.422E+003 351.92* 37.20 1.392E+003 1.412E+003 6.336E+002 785.91 1.10 8.569E+004 6.663E+004 3.953E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 9:21:42 AM Sample Title  : B1-010-001-FSFC-D33-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D33 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 9:11:00 AM Acquisition Started  : 3/28/2019 9:11:41 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 9:21:42 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D33-GM Peak Analysis Performed on: 3/28/2019 9:21:41 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 943- 960 953.28 238.39 0.95 7.63E+001 35.24 7.07E+001 2 3636- 3649 3642.44 910.89 0.65 2.90E+001 18.66 2.10E+001 3 5830- 5854 5841.30 1460.34 1.78 2.31E+002 32.46 8.46E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 9:21:42 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D33-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.996 1460.81* 10.67 8.30123E+004 1.35505E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.37165E+003 1.15985E+003 300.09 3.41 AC-228 0.997 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.07436E+003 2.01020E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 9:21:42 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.996 8.301231E+004 1.355052E+004 PB-212 0.999 2.371654E+003 1.159853E+003 AC-228 0.997 3.074358E+003 2.010197E+003

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

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

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

Peak Locate Performed on: 3/28/2019 9:21:41 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/28/2019 9:21:42 AM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D33-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 7.761E+003 7.76E+003 8.301E+004 3.393E+003 CO-60 1173.22 100.00 1.141E+003 8.08E+002 -4.008E+002 5.249E+002 1332.49 100.00 8.078E+002 -7.283E+002 3.552E+002 CS-134 475.35 1.46 6.177E+004 9.37E+002 1.415E+004 2.901E+004 563.23 8.38 1.054E+004 8.463E+003 4.910E+003 569.32 15.43 5.452E+003 -1.527E+003 2.530E+003 604.70 97.60 1.072E+003 -1.180E+002 5.039E+002 795.84 85.40 9.366E+002 1.020E+002 4.252E+002 801.93 8.73 1.016E+004 4.112E+003 4.657E+003 1038.57 1.00 8.335E+004 -3.202E+004 3.741E+004 1167.94 1.80 5.990E+004 -5.491E+004 2.743E+004 1365.15 3.04 2.704E+004 9.887E+003 1.189E+004 CS-137 661.65 85.12 1.077E+003 1.08E+003 2.784E+002 4.996E+002 EU-152 121.78 28.40 3.956E+003 3.63E+003 -3.481E+003 1.920E+003 344.27 26.50 3.635E+003 -1.569E+003 1.731E+003 1407.95 20.70 4.345E+003 -8.439E+002 1.928E+003 EU-154 123.07 40.40 2.795E+003 2.80E+003 1.718E+002 1.357E+003 722.30 20.00 4.575E+003 4.657E+003 2.113E+003 1274.51 34.40 2.923E+003 2.294E+003 1.323E+003 BI-214 609.31 46.30 2.370E+003 2.37E+003 2.563E+003 1.117E+003 768.36 5.04 2.200E+004 7.887E+003 1.028E+004 806.17 1.23 7.393E+004 4.840E+003 3.395E+004 934.06 3.21 2.980E+004 -9.061E+003 1.365E+004 1120.29 15.10 7.297E+003 4.774E+003 3.355E+003 1155.19 1.69 5.307E+004 -1.058E+004 2.386E+004 1238.11 5.94 2.075E+004 6.512E+003 9.585E+003 1280.96 1.47 6.656E+004 2.782E+004 3.004E+004 1377.67 4.11 1.747E+004 6.415E+003 7.522E+003 1385.31 0.78 1.011E+005 7.590E+004 4.414E+004 1401.50 1.39 5.563E+004 3.221E+003 2.418E+004 1407.98 2.48 3.627E+004 -7.044E+003 1.609E+004 1509.19 2.19 2.697E+004 1.257E+004 1.105E+004 1661.28 1.15 6.104E+004 8.343E+003 2.556E+004 1729.60 3.05 2.005E+004 8.528E+003 8.100E+003 1764.49 15.80 5.933E+003 -2.087E+002 2.590E+003 1847.44 2.12 2.797E+004 1.067E+004 1.110E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.751E+004 2.68E+003 3.154E+004 1.824E+004 77.11 10.70 2.098E+004 2.051E+004 1.021E+004 87.20 3.70 4.390E+004 1.479E+004 2.137E+004 89.80 1.03 1.476E+005 -6.614E+004 7.178E+004 241.98 7.49 1.496E+004 2.900E+002 7.228E+003

Nuclide MDA Report 3/28/2019 9:21:42 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 5.335E+003 2.68E+003 1.070E+003 2.558E+003 351.92 37.20 2.683E+003 1.641E+003 1.279E+003 785.91 1.10 8.651E+004 6.080E+004 3.994E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D34-GM.CNF Report Generated On  : 3/27/2019 9:01:56 PM Sample Title  : B1-010-001-FSFC-D34-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D34 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 8:42:00 AM Acquisition Started  : 3/27/2019 8:43:24 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 9:01:56 PM Page 2

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Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D34-GM Peak Analysis Performed on: 3/27/2019 9:01:56 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 949- 961 955.01 238.82 0.41 2.33E+001 26.29 5.67E+001 2 2328- 2340 2333.04 583.51 0.73 2.13E+001 15.19 1.37E+001 3 2429- 2445 2436.70 609.43 0.53 5.29E+001 19.02 1.21E+001 4 5831- 5854 5843.88 1460.98 1.53 2.15E+002 29.33 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:01:56 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D34-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.999 1460.81* 10.67 7.74422E+004 1.23495E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 7.24535E+002 8.26503E+002 300.09 3.41 BI-214 1.000 609.31* 46.30 2.66118E+003 1.01637E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:01:56 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.999 7.744224E+004 1.234949E+004 PB-212 1.000 7.245353E+002 8.265030E+002 BI-214 1.000 2.661175E+003 1.016369E+003

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

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

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

Peak Locate Performed on: 3/27/2019 9:01:56 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 583.51 3.5476E-002 71.38 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 9:01:56 PM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D34-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 9.747E+002 9.75E+002 7.744E+004 0.000E+000 CO-60 1173.22 100.00 1.030E+003 8.46E+002 9.818E+002 4.695E+002 1332.49 100.00 8.463E+002 -5.353E+001 3.744E+002 CS-134 475.35 1.46 6.318E+004 1.07E+003 -5.031E+004 2.972E+004 563.23 8.38 1.022E+004 -1.701E+003 4.752E+003 569.32 15.43 5.407E+003 -3.124E+003 2.507E+003 604.70 97.60 1.165E+003 -1.085E+003 5.503E+002 795.84 85.40 1.068E+003 5.250E+002 4.910E+002 801.93 8.73 9.694E+003 3.361E+003 4.424E+003 1038.57 1.00 9.657E+004 4.470E+004 4.402E+004 1167.94 1.80 5.012E+004 2.190E+004 2.254E+004 1365.15 3.04 2.955E+004 -1.048E+004 1.314E+004 CS-137 661.65 85.12 1.068E+003 1.07E+003 2.510E+002 4.951E+002 EU-152 121.78 28.40 3.762E+003 3.42E+003 1.822E+001 1.823E+003 344.27 26.50 3.425E+003 -4.291E+003 1.626E+003 1407.95 20.70 4.059E+003 1.499E+003 1.785E+003 EU-154 123.07 40.40 2.649E+003 2.51E+003 1.315E+003 1.284E+003 722.30 20.00 4.740E+003 2.500E+003 2.196E+003 1274.51 34.40 2.506E+003 6.897E+002 1.115E+003

+ BI-214 609.31* 46.30 1.152E+003 1.15E+003 2.661E+003 5.078E+002 768.36 5.04 1.898E+004 1.179E+004 8.778E+003 806.17 1.23 6.816E+004 4.247E+004 3.107E+004 934.06 3.21 2.730E+004 5.572E+003 1.240E+004 1120.29 15.10 5.940E+003 -6.685E+003 2.676E+003 1155.19 1.69 5.218E+004 -5.803E+004 2.342E+004 1238.11 5.94 1.762E+004 7.421E+003 8.020E+003 1280.96 1.47 5.999E+004 -7.099E+004 2.675E+004 1377.67 4.11 1.804E+004 -1.121E+003 7.806E+003 1385.31 0.78 1.164E+005 -5.121E+004 5.176E+004 1401.50 1.39 5.722E+004 2.013E+003 2.498E+004 1407.98 2.48 3.388E+004 1.252E+004 1.490E+004 1509.19 2.19 3.258E+004 1.976E+004 1.386E+004 1661.28 1.15 4.802E+004 -8.974E+003 1.905E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49 15.80 5.048E+003 3.061E+003 2.147E+003 1847.44 2.12 3.556E+004 -1.067E+003 1.489E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.685E+004 2.67E+003 1.510E+004 1.791E+004 77.11 10.70 2.028E+004 1.521E+004 9.858E+003 87.20 3.70 4.093E+004 2.735E+003 1.989E+004 89.80 1.03 1.436E+005 1.466E+004 6.979E+004 241.98 7.49 1.327E+004 6.299E+003 6.383E+003

Nuclide MDA Report 3/27/2019 9:01:56 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 4.419E+003 2.67E+003 1.957E+003 2.100E+003 351.92 37.20 2.665E+003 1.361E+003 1.271E+003 785.91 1.10 8.813E+004 -3.084E+004 4.075E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D35-GM.CNF Report Generated On  : 3/27/2019 9:03:02 PM Sample Title  : B1-010-001-FSFC-D35-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D35 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 9:04:00 AM Acquisition Started  : 3/27/2019 9:05:12 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 9:03:02 PM Page 2

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Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D35-GM Peak Analysis Performed on: 3/27/2019 9:03:02 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 958 952.68 238.24 0.67 2.79E+001 27.41 6.21E+001 2 1400- 1413 1405.57 351.54 0.82 4.30E+001 24.71 3.90E+001 3 2426- 2440 2432.97 608.50 1.13 2.45E+001 18.94 2.25E+001 4 5824- 5847 5835.50 1458.89 0.89 1.69E+002 27.01 3.21E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:03:02 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D35-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.936 1460.81* 10.67 6.07351E+004 1.09375E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 8.67969E+002 8.63469E+002 300.09 3.41 BI-214 0.995 609.31* 46.30 1.23231E+003 9.65838E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.97681E+003 1.17909E+003 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:03:02 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.936 6.073511E+004 1.093748E+004 PB-212 0.999 8.679694E+002 8.634687E+002 BI-214 0.995 1.232310E+003 9.658382E+002 PB-214 0.999 1.976806E+003 1.179094E+003

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

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

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

Peak Locate Performed on: 3/27/2019 9:03:02 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/27/2019 9:03:02 PM Page 5

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D35-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 5.337E+003 5.34E+003 6.074E+004 2.182E+003 CO-60 1173.22 100.00 9.482E+002 7.24E+002 2.430E+002 4.286E+002 1332.49 100.00 7.239E+002 -8.483E+001 3.133E+002 CS-134 475.35 1.46 5.920E+004 9.49E+002 -2.113E+004 2.773E+004 563.23 8.38 9.895E+003 -7.229E+003 4.588E+003 569.32 15.43 5.126E+003 -3.996E+003 2.366E+003 604.70 97.60 1.137E+003 7.201E+002 5.363E+002 795.84 85.40 9.494E+002 -4.750E+002 4.316E+002 801.93 8.73 1.038E+004 7.325E+003 4.769E+003 1038.57 1.00 7.736E+004 -4.232E+004 3.441E+004 1167.94 1.80 5.094E+004 -2.230E+003 2.295E+004 1365.15 3.04 2.568E+004 1.927E+004 1.121E+004 CS-137 661.65 85.12 1.012E+003 1.01E+003 7.907E+001 4.673E+002 EU-152 121.78 28.40 3.951E+003 3.40E+003 -7.203E+002 1.918E+003 344.27 26.50 3.397E+003 -4.052E+003 1.612E+003 1407.95 20.70 4.436E+003 -1.849E+002 1.973E+003 EU-154 123.07 40.40 2.730E+003 2.56E+003 8.503E+002 1.325E+003 722.30 20.00 3.833E+003 -1.477E+003 1.743E+003 1274.51 34.40 2.556E+003 -4.887E+001 1.140E+003

+ BI-214 609.31* 46.30 1.472E+003 1.47E+003 1.232E+003 6.682E+002 768.36 5.04 1.736E+004 1.099E+004 7.966E+003 806.17 1.23 7.777E+004 4.563E+004 3.587E+004 934.06 3.21 2.876E+004 -4.976E+003 1.313E+004 1120.29 15.10 7.297E+003 4.707E+003 3.355E+003 1155.19 1.69 6.045E+004 1.086E+004 2.756E+004 1238.11 5.94 1.691E+004 5.950E+003 7.668E+003 1280.96 1.47 5.999E+004 4.154E+004 2.675E+004 1377.67 4.11 1.963E+004 -2.275E+004 8.601E+003 1385.31 0.78 9.242E+004 2.846E+004 3.979E+004 1401.50 1.39 6.170E+004 5.100E+004 2.722E+004 1407.98 2.48 3.702E+004 -1.544E+003 1.647E+004 1509.19 2.19 2.993E+004 1.616E+004 1.253E+004 1661.28 1.15 4.400E+004 -9.615E+003 1.704E+004 1729.60 3.05 2.134E+004 -1.523E+003 8.749E+003 1764.49 15.80 5.239E+003 9.103E+002 2.243E+003 1847.44 2.12 3.204E+004 1.494E+004 1.313E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.794E+004 1.71E+003 3.323E+004 1.845E+004 77.11 10.70 2.066E+004 1.376E+004 1.005E+004 87.20 3.70 4.093E+004 4.087E+002 1.989E+004 89.80 1.03 1.419E+005 -9.166E+004 6.894E+004 241.98 7.49 1.368E+004 1.443E+004 6.586E+003

Nuclide MDA Report 3/27/2019 9:03:02 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 4.602E+003 1.71E+003 6.107E+002 2.191E+003 351.92* 37.20 1.708E+003 1.977E+003 7.918E+002 785.91 1.10 7.119E+004 -2.705E+004 3.227E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D36-GM.CNF Report Generated On  : 3/27/2019 9:04:08 PM Sample Title  : B1-010-001-FSFC-D36-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D36 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 9:23:00 AM Acquisition Started  : 3/27/2019 9:23:00 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 9:04:08 PM Page 2

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Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D36-GM Peak Analysis Performed on: 3/27/2019 9:04:08 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 945- 959 952.41 238.17 0.85 8.88E+001 32.02 5.82E+001 2 1400- 1413 1406.32 351.73 0.82 2.17E+001 20.77 3.13E+001 3 2323- 2336 2329.65 582.66 0.94 3.14E+001 17.24 1.56E+001 4 2427- 2439 2432.72 608.43 0.68 4.61E+001 16.35 7.94E+000 5 3632- 3645 3638.20 909.83 0.45 2.55E+001 15.59 1.25E+001 6 5826- 5847 5836.15 1459.05 0.87 2.01E+002 30.24 7.60E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:04:08 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D36-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.946 1460.81* 10.67 7.24762E+004 1.24213E+004 PB-212 0.998 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.76063E+003 1.08899E+003 300.09 3.41 BI-214 0.994 609.31* 46.30 2.31685E+003 8.74311E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 9.98956E+002 9.68318E+002 785.91 1.10 AC-228 0.984 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40

Interference Corrected Activity Report 3/27/2019 9:04:08 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.984 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.70368E+003 1.68081E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:04:08 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.946 7.247621E+004 1.242127E+004 PB-212 0.998 2.760628E+003 1.088987E+003 BI-214 0.994 2.316849E+003 8.743107E+002 PB-214 1.000 9.989564E+002 9.683176E+002 AC-228 0.984 2.703676E+003 1.680806E+003

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

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

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

Peak Locate Performed on: 3/27/2019 9:04:08 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 582.66 5.2349E-002 54.89 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 9:04:08 PM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D36-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 7.154E+003 7.15E+003 7.248E+004 3.090E+003 CO-60 1173.22 100.00 9.338E+002 7.01E+002 -1.584E+003 4.214E+002 1332.49 100.00 7.011E+002 4.679E+002 3.019E+002 CS-134 475.35 1.46 6.283E+004 1.10E+003 -7.348E+003 2.954E+004 563.23 8.38 9.555E+003 4.420E+003 4.418E+003 569.32 15.43 5.174E+003 -2.046E+003 2.390E+003 604.70 97.60 1.096E+003 1.360E+003 5.159E+002 795.84 85.40 1.194E+003 9.069E+002 5.539E+002 801.93 8.73 1.134E+004 9.650E+003 5.245E+003 1038.57 1.00 9.409E+004 -3.075E+004 4.278E+004 1167.94 1.80 5.851E+004 -2.869E+004 2.673E+004 1365.15 3.04 2.347E+004 -1.297E+004 1.010E+004 CS-137 661.65 85.12 1.146E+003 1.15E+003 8.840E+002 5.341E+002 EU-152 121.78 28.40 3.956E+003 3.33E+003 1.859E+003 1.920E+003 344.27 26.50 3.328E+003 -2.059E+003 1.578E+003 1407.95 20.70 4.345E+003 3.797E+003 1.928E+003 EU-154 123.07 40.40 2.767E+003 2.77E+003 8.675E+002 1.343E+003 722.30 20.00 4.489E+003 -3.138E+003 2.071E+003 1274.51 34.40 3.008E+003 1.091E+003 1.366E+003

+ BI-214 609.31* 46.30 8.902E+002 8.90E+002 2.317E+003 3.771E+002 768.36 5.04 1.846E+004 -1.096E+004 8.516E+003 806.17 1.23 7.702E+004 2.343E+004 3.550E+004 934.06 3.21 3.081E+004 6.471E+003 1.415E+004 1120.29 15.10 6.905E+003 -1.703E+003 3.158E+003 1155.19 1.69 6.045E+004 4.184E+004 2.756E+004 1238.11 5.94 2.075E+004 7.193E+003 9.585E+003 1280.96 1.47 6.226E+004 -4.191E+004 2.789E+004 1377.67 4.11 1.626E+004 9.864E+003 6.919E+003 1385.31 0.78 1.038E+005 8.065E+004 4.550E+004 1401.50 1.39 5.722E+004 4.295E+004 2.498E+004 1407.98 2.48 3.627E+004 3.170E+004 1.609E+004 1509.19 2.19 2.533E+004 1.946E+003 1.023E+004 1661.28 1.15 5.500E+004 2.564E+004 2.254E+004 1729.60 3.05 2.578E+004 1.131E+003 1.097E+004 1764.49 15.80 5.933E+003 4.453E+003 2.590E+003 1847.44 2.12 3.386E+004 1.707E+004 1.404E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.849E+004 1.53E+003 4.617E+004 1.873E+004 77.11 10.70 2.109E+004 1.124E+004 1.027E+004 87.20 3.70 4.268E+004 1.342E+004 2.076E+004 89.80 1.03 1.477E+005 8.410E+004 7.187E+004 241.98 7.49 1.491E+004 -9.707E+003 7.202E+003

Nuclide MDA Report 3/27/2019 9:04:08 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 4.745E+003 1.53E+003 2.035E+003 2.263E+003 351.92* 37.20 1.528E+003 9.990E+002 7.020E+002 785.91 1.10 8.318E+004 -4.195E+004 3.827E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 9:33:16 AM Sample Title  : B1-010-001-FSFC-D37-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D37 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 9:22:00 AM Acquisition Started  : 3/28/2019 9:23:15 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 9:33:16 AM Page 2

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Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D37-GM Peak Analysis Performed on: 3/28/2019 9:33:16 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 295- 304 299.86 74.90 0.41 2.95E+001 33.44 1.11E+002 2 949- 960 954.67 238.74 1.15 4.20E+001 28.76 6.50E+001 3 1401- 1413 1407.57 352.04 0.94 3.23E+001 19.19 2.28E+001 4 2324- 2338 2331.35 583.09 0.33 3.10E+001 17.22 1.50E+001 5 2429- 2443 2436.56 609.39 0.58 4.60E+001 16.96 8.97E+000 6 3636- 3650 3642.61 910.93 0.52 4.33E+001 14.71 3.75E+000 7 5829- 5853 5841.78 1460.46 1.62 2.44E+002 32.03 3.07E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 9:33:16 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D37-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.998 1460.81* 10.67 8.78399E+004 1.36270E+004 PB-212 1.000 74.81* 9.60 7.40938E+003 8.53574E+003 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.30747E+003 9.19139E+002 300.09 3.41 BI-214 1.000 609.31* 46.30 2.31704E+003 9.03774E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.626 74.81* 6.33 1.12370E+004 1.29452E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.48353E+003 9.14292E+002 785.91 1.10 AC-228 0.998 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40

Interference Corrected Activity Report 3/28/2019 9:33:16 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.998 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 4.58515E+003 1.64746E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 9:33:16 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.998 8.783988E+004 1.362699E+004 PB-212 1.000 1.365914E+003 9.138820E+002 BI-214 1.000 2.317044E+003 9.037736E+002 PB-214 0.626 1.521660E+003 9.120459E+002 AC-228 0.998 4.585147E+003 1.647459E+003

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

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

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

Peak Locate Performed on: 3/28/2019 9:33:16 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 4 583.09 5.1667E-002 55.55 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 9:33:17 AM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D37-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 5.171E+003 5.17E+003 8.784E+004 2.098E+003 CO-60 1173.22 100.00 8.890E+002 8.65E+002 6.417E+002 3.990E+002 1332.49 100.00 8.647E+002 4.824E+002 3.837E+002 CS-134 475.35 1.46 5.572E+004 1.11E+003 2.848E+004 2.599E+004 563.23 8.38 1.069E+004 -2.668E+003 4.987E+003 569.32 15.43 5.221E+003 1.853E+003 2.414E+003 604.70 97.60 1.143E+003 -2.935E+002 5.391E+002 795.84 85.40 1.112E+003 8.721E+002 5.129E+002 801.93 8.73 1.082E+004 -6.782E+003 4.986E+003 1038.57 1.00 1.013E+005 2.357E+004 4.640E+004 1167.94 1.80 4.384E+004 -2.493E+004 1.940E+004 1365.15 3.04 2.423E+004 -2.607E+004 1.048E+004 CS-137 661.65 85.12 1.146E+003 1.15E+003 -6.421E+002 5.341E+002 EU-152 121.78 28.40 4.194E+003 3.45E+003 -2.248E+003 2.040E+003 344.27 26.50 3.452E+003 -1.174E+003 1.639E+003 1407.95 20.70 4.436E+003 1.130E+003 1.973E+003 EU-154 123.07 40.40 2.914E+003 2.91E+003 -1.688E+003 1.417E+003 722.30 20.00 5.055E+003 -3.543E+002 2.353E+003 1274.51 34.40 3.049E+003 -2.074E+002 1.386E+003

+ BI-214 609.31* 46.30 9.787E+002 9.79E+002 2.317E+003 4.212E+002 768.36 5.04 1.846E+004 -3.638E+003 8.516E+003 806.17 1.23 7.998E+004 8.222E+004 3.698E+004 934.06 3.21 3.422E+004 2.233E+004 1.586E+004 1120.29 15.10 8.157E+003 5.221E+003 3.784E+003 1155.19 1.69 6.415E+004 2.937E+004 2.941E+004 1238.11 5.94 1.936E+004 -2.073E+003 8.889E+003 1280.96 1.47 7.342E+004 1.142E+004 3.347E+004 1377.67 4.11 2.155E+004 -1.516E+003 9.560E+003 1385.31 0.78 1.065E+005 -1.212E+004 4.682E+004 1401.50 1.39 5.399E+004 -1.122E+004 2.336E+004 1407.98 2.48 3.702E+004 9.434E+003 1.647E+004 1509.19 2.19 3.129E+004 6.511E+003 1.321E+004 1661.28 1.15 6.643E+004 4.029E+004 2.826E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49 15.80 4.179E+003 -9.045E+002 1.713E+003 1847.44 2.12 3.556E+004 1.920E+004 1.489E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81* 6.33 2.087E+004 1.30E+003 1.124E+004 9.918E+003 77.11 10.70 2.075E+004 1.207E+004 1.009E+004 87.20 3.70 4.517E+004 2.484E+002 2.201E+004 89.80 1.03 1.557E+005 7.284E+004 7.585E+004 241.98 7.49 1.421E+004 1.483E+004 6.853E+003

Nuclide MDA Report 3/28/2019 9:33:17 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.166E+003 1.30E+003 3.552E+003 2.473E+003 351.92* 37.20 1.295E+003 1.484E+003 5.854E+002 785.91 1.10 8.233E+004 -1.200E+005 3.785E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 9:48:55 AM Sample Title  : B1-010-001-FSFC-D38-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D38 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 9:36:00 AM Acquisition Started  : 3/28/2019 9:38:54 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 9:48:55 AM Page 2

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Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D38-GM Peak Analysis Performed on: 3/28/2019 9:48:54 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 961 953.95 238.56 0.62 4.43E+001 32.94 7.88E+001 2 1400- 1414 1407.68 352.07 0.32 4.03E+001 22.55 2.97E+001 3 2325- 2338 2331.42 583.10 0.32 4.49E+001 16.86 9.07E+000 4 3638- 3651 3644.76 911.47 0.80 2.71E+001 15.43 1.09E+001 5 5830- 5855 5841.69 1460.43 1.88 2.60E+002 33.70 5.96E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 9:48:55 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D38-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.997 1460.81* 10.67 9.36396E+004 1.43923E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.37664E+003 1.04813E+003 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.85391E+003 1.07889E+003 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.87171E+003 1.67009E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 9:48:55 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.997 9.363961E+004 1.439235E+004 PB-212 1.000 1.376644E+003 1.048130E+003 PB-214 1.000 1.853913E+003 1.078888E+003 AC-228 1.000 2.871706E+003 1.670089E+003

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

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

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

Peak Locate Performed on: 3/28/2019 9:48:54 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 583.10 7.4884E-002 37.52 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 9:48:55 AM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D38-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 6.771E+003 6.77E+003 9.364E+004 2.898E+003 CO-60 1173.22 100.00 1.043E+003 8.46E+002 -3.357E+002 4.760E+002 1332.49 100.00 8.463E+002 -1.228E+002 3.744E+002 CS-134 475.35 1.46 5.768E+004 1.03E+003 -3.644E+004 2.697E+004 563.23 8.38 9.380E+003 -2.034E+003 4.330E+003 569.32 15.43 5.497E+003 -3.202E+003 2.552E+003 604.70 97.60 1.125E+003 1.310E+003 5.305E+002 795.84 85.40 1.034E+003 5.904E+002 4.740E+002 801.93 8.73 1.005E+004 -4.690E+003 4.600E+003 1038.57 1.00 9.409E+004 6.229E+004 4.278E+004 1167.94 1.80 5.411E+004 2.796E+003 2.453E+004 1365.15 3.04 2.185E+004 -1.013E+004 9.294E+003 CS-137 661.65 85.12 1.068E+003 1.07E+003 -1.337E+002 4.951E+002 EU-152 121.78 28.40 4.052E+003 3.33E+003 -1.119E+003 1.968E+003 344.27 26.50 3.328E+003 -1.921E+003 1.578E+003 1407.95 20.70 4.345E+003 -4.607E+002 1.928E+003 EU-154 123.07 40.40 2.873E+003 2.87E+003 2.215E+003 1.396E+003 722.30 20.00 4.446E+003 1.648E+003 2.049E+003 1274.51 34.40 3.129E+003 1.362E+002 1.426E+003 BI-214 609.31 46.30 2.455E+003 2.45E+003 3.280E+003 1.159E+003 768.36 5.04 2.110E+004 -2.053E+004 9.833E+003 806.17 1.23 7.393E+004 1.975E+004 3.395E+004 934.06 3.21 2.946E+004 2.296E+004 1.348E+004 1120.29 15.10 7.373E+003 -2.181E+003 3.393E+003 1155.19 1.69 6.557E+004 4.227E+004 3.012E+004 1238.11 5.94 1.872E+004 7.866E+002 8.573E+003 1280.96 1.47 6.226E+004 -7.046E+004 2.789E+004 1377.67 4.11 2.109E+004 1.062E+004 9.330E+003 1385.31 0.78 1.065E+005 5.534E+004 4.682E+004 1401.50 1.39 5.563E+004 4.921E+003 2.418E+004 1407.98 2.48 3.627E+004 -3.845E+003 1.609E+004 1509.19 2.19 2.697E+004 -1.116E+004 1.105E+004 1661.28 1.15 6.104E+004 3.297E+004 2.556E+004 1729.60 3.05 2.134E+004 -9.543E+003 8.749E+003 1764.49 15.80 6.398E+003 3.208E+003 2.822E+003 1847.44 2.12 3.009E+004 -3.201E+004 1.216E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.703E+004 1.53E+003 4.660E+004 1.800E+004 77.11 10.70 2.028E+004 1.015E+004 9.858E+003 87.20 3.70 4.249E+004 2.019E+003 2.067E+004 89.80 1.03 1.452E+005 2.493E+004 7.063E+004 241.98 7.49 1.432E+004 8.330E+003 6.908E+003

Nuclide MDA Report 3/28/2019 9:48:55 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.418E+003 1.53E+003 8.042E+001 2.599E+003 351.92* 37.20 1.535E+003 1.854E+003 7.051E+002 785.91 1.10 7.970E+004 4.217E+003 3.653E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 10:44:33 AM Sample Title  : B1-010-001-FSFC-D39-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D39 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 10:33:00 AM Acquisition Started  : 3/28/2019 10:34:32 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 10:44:33 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D39-GM Peak Analysis Performed on: 3/28/2019 10:44:33 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 962 953.78 238.51 0.94 5.95E+001 32.51 6.55E+001 2 1400- 1411 1405.91 351.62 0.53 2.21E+001 20.44 3.29E+001 3 2427- 2440 2434.44 608.87 0.62 4.73E+001 19.06 1.57E+001 4 3634- 3647 3640.06 910.29 1.36 2.98E+001 14.49 8.18E+000 5 5826- 5849 5837.53 1459.39 1.95 2.24E+002 29.93 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 10:44:33 AM Page 3

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

Sample

Title:

B1-010-001-FSFC-D39-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.965 1460.81* 10.67 8.06214E+004 1.26661E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.85128E+003 1.05386E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 2.38041E+003 1.00644E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.01681E+003 9.53546E+002 785.91 1.10 AC-228 0.991 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40

Interference Corrected Activity Report 3/28/2019 10:44:33 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.991 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.16040E+003 1.57875E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 10:44:33 AM Page 5

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.965 8.062144E+004 1.266611E+004 PB-212 1.000 1.851279E+003 1.053863E+003 BI-214 0.999 2.380414E+003 1.006444E+003 PB-214 0.999 1.016808E+003 9.535456E+002 AC-228 0.991 3.160405E+003 1.578755E+003

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

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

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

Peak Locate Performed on: 3/28/2019 10:44:33 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/28/2019 10:44:33 AM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D39-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 9.739E+002 9.74E+002 8.062E+004 0.000E+000 CO-60 1173.22 100.00 1.129E+003 7.46E+002 1.707E+002 5.191E+002 1332.49 100.00 7.459E+002 -8.997E+000 3.243E+002 CS-134 475.35 1.46 5.768E+004 1.10E+003 -9.006E+003 2.697E+004 563.23 8.38 1.022E+004 7.820E+002 4.752E+003 569.32 15.43 5.630E+003 -1.246E+003 2.618E+003 604.70 97.60 1.198E+003 6.902E+002 5.668E+002 795.84 85.40 1.101E+003 -1.000E+002 5.075E+002 801.93 8.73 1.038E+004 -1.161E+004 4.769E+003 1038.57 1.00 9.283E+004 3.519E+004 4.215E+004 1167.94 1.80 6.058E+004 -8.855E+003 2.777E+004 1365.15 3.04 2.568E+004 8.582E+003 1.121E+004 CS-137 661.65 85.12 1.226E+003 1.23E+003 1.185E+003 5.743E+002 EU-152 121.78 28.40 3.982E+003 3.54E+003 -2.623E+002 1.933E+003 344.27 26.50 3.544E+003 -2.904E+003 1.686E+003 1407.95 20.70 4.524E+003 2.962E+003 2.018E+003 EU-154 123.07 40.40 2.824E+003 2.79E+003 2.860E+003 1.371E+003 722.30 20.00 4.978E+003 3.262E+003 2.315E+003 1274.51 34.40 2.792E+003 4.717E+002 1.258E+003

+ BI-214 609.31* 46.30 1.228E+003 1.23E+003 2.380E+003 5.461E+002 768.36 5.04 1.698E+004 -8.308E+003 7.774E+003 806.17 1.23 7.233E+004 1.593E+004 3.315E+004 934.06 3.21 3.333E+004 1.447E+004 1.541E+004 1120.29 15.10 7.882E+003 -1.956E+003 3.647E+003 1155.19 1.69 6.045E+004 1.017E+004 2.756E+004 1238.11 5.94 1.762E+004 -1.777E+003 8.020E+003 1280.96 1.47 6.551E+004 -5.994E+003 2.951E+004 1377.67 4.11 2.013E+004 -4.284E+003 8.851E+003 1385.31 0.78 1.090E+005 -7.640E+004 4.810E+004 1401.50 1.39 6.449E+004 1.432E+004 2.862E+004 1407.98 2.48 3.776E+004 2.472E+004 1.684E+004 1509.19 2.19 3.613E+004 2.514E+004 1.563E+004 1661.28 1.15 3.943E+004 1.099E+004 1.476E+004 1729.60 3.05 2.676E+004 5.449E+003 1.145E+004 1764.49 15.80 6.092E+003 2.034E+003 2.670E+003 1847.44 2.12 2.563E+004 -1.040E+004 9.928E+003

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.658E+004 1.50E+003 3.016E+004 1.777E+004 77.11 10.70 1.982E+004 -6.735E+003 9.630E+003 87.20 3.70 4.348E+004 4.664E+004 2.116E+004 89.80 1.03 1.464E+005 -2.130E+004 7.121E+004 241.98 7.49 1.418E+004 1.087E+004 6.839E+003

Nuclide MDA Report 3/28/2019 10:44:33 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.194E+003 1.50E+003 -7.489E+002 2.488E+003 351.92* 37.20 1.497E+003 1.017E+003 6.861E+002 785.91 1.10 8.403E+004 -7.299E+004 3.870E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 10:04:21 AM Sample Title  : B1-010-001-FSFC-D40-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D40 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 9:52:00 AM Acquisition Started  : 3/28/2019 9:54:20 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 10:04:21 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D40-GM Peak Analysis Performed on: 3/28/2019 10:04:21 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 961 953.36 238.41 0.59 3.47E+001 31.20 7.53E+001 2 2325- 2337 2330.29 582.82 0.33 2.69E+001 18.30 2.11E+001 3 2430- 2442 2435.17 609.05 0.36 2.93E+001 17.18 1.67E+001 4 3634- 3647 3640.25 910.34 0.32 3.20E+001 14.32 7.00E+000 5 5825- 5850 5837.93 1459.49 1.94 2.43E+002 31.18 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 10:04:21 AM Page 3

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

Sample

Title:

B1-010-001-FSFC-D40-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.970 1460.81* 10.67 8.74641E+004 1.33468E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.07946E+003 9.85474E+002 300.09 3.41 BI-214 1.000 609.31* 46.30 1.47281E+003 8.85054E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.992 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.39127E+003 1.56809E+003 964.60 5.20 969.11 16.60 1587.90 3.71

Interference Corrected Activity Report 3/28/2019 10:04:21 AM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 10:04:21 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.970 8.746415E+004 1.334682E+004 PB-212 1.000 1.079464E+003 9.854740E+002 BI-214 1.000 1.472808E+003 8.850540E+002 AC-228 0.992 3.391272E+003 1.568094E+003

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

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

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

Peak Locate Performed on: 3/28/2019 10:04:21 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 2 582.82 4.4792E-002 68.11 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 10:04:21 AM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D40-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 9.740E+002 9.74E+002 8.746E+004 0.000E+000 CO-60 1173.22 100.00 1.117E+003 8.08E+002 6.903E+002 5.131E+002 1332.49 100.00 8.078E+002 7.498E+000 3.552E+002 CS-134 475.35 1.46 6.212E+004 9.10E+002 -5.300E+004 2.919E+004 563.23 8.38 1.006E+004 3.159E+003 4.670E+003 569.32 15.43 5.315E+003 -6.765E+002 2.461E+003 604.70 97.60 1.154E+003 8.529E+002 5.448E+002 795.84 85.40 9.104E+002 1.239E+002 4.121E+002 801.93 8.73 9.813E+003 -3.295E+003 4.484E+003 1038.57 1.00 8.755E+004 -6.710E+004 3.951E+004 1167.94 1.80 6.387E+004 2.890E+004 2.941E+004 1365.15 3.04 2.568E+004 1.927E+004 1.121E+004 CS-137 661.65 85.12 1.203E+003 1.20E+003 1.466E+003 5.625E+002 EU-152 121.78 28.40 3.868E+003 3.01E+003 2.628E+002 1.876E+003 344.27 26.50 3.609E+003 -3.666E+003 1.718E+003 1407.95 20.70 3.013E+003 -4.069E+003 1.262E+003 EU-154 123.07 40.40 2.705E+003 2.61E+003 -6.605E+002 1.312E+003 722.30 20.00 4.781E+003 9.607E+002 2.217E+003 1274.51 34.40 2.606E+003 -5.300E+002 1.165E+003

+ BI-214 609.31* 46.30 1.241E+003 1.24E+003 1.473E+003 5.525E+002 768.36 5.04 1.792E+004 -4.403E+002 8.245E+003 806.17 1.23 7.314E+004 2.101E+004 3.356E+004 934.06 3.21 2.654E+004 8.909E+003 1.201E+004 1120.29 15.10 7.522E+003 4.875E+003 3.467E+003 1155.19 1.69 6.415E+004 3.537E+004 2.941E+004 1238.11 5.94 1.936E+004 -3.049E+003 8.889E+003 1280.96 1.47 5.881E+004 3.550E+004 2.616E+004 1377.67 4.11 1.912E+004 8.113E+003 8.345E+003 1385.31 0.78 1.011E+005 -2.350E+004 4.414E+004 1401.50 1.39 6.025E+004 2.990E+004 2.649E+004 1407.98 2.48 2.515E+004 -3.396E+004 1.053E+004 1509.19 2.19 3.129E+004 -1.302E+004 1.321E+004 1661.28 1.15 5.500E+004 6.541E+002 2.254E+004 1729.60 3.05 2.578E+004 5.298E+003 1.097E+004 1764.49 15.80 6.247E+003 5.010E+003 2.747E+003 1847.44 2.12 3.870E+004 8.439E+003 1.646E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.720E+004 2.75E+003 2.314E+004 1.808E+004 77.11 10.70 2.096E+004 2.924E+004 1.020E+004 87.20 3.70 4.362E+004 1.515E+004 2.123E+004 89.80 1.03 1.508E+005 -4.281E+004 7.341E+004 241.98 7.49 1.435E+004 1.121E+004 6.921E+003

Nuclide MDA Report 3/28/2019 10:04:21 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

PB-214 295.21 19.20 5.194E+003 2.75E+003 3.501E+002 2.488E+003 351.92 37.20 2.754E+003 2.074E+003 1.315E+003 785.91 1.10 7.605E+004 -4.237E+004 3.470E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D41-GM.CNF Report Generated On  : 3/27/2019 9:05:23 PM Sample Title  : B1-010-001-FSFC-D41-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D41 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 9:39:00 AM Acquisition Started  : 3/27/2019 9:39:23 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 9:05:23 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D41-GM Peak Analysis Performed on: 3/27/2019 9:05:22 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 945- 959 952.80 238.27 0.99 3.17E+001 33.17 8.33E+001 2 1174- 1185 1179.08 294.88 1.15 1.95E+001 20.30 3.25E+001 3 1400- 1413 1405.84 351.60 0.82 3.35E+001 19.65 2.25E+001 4 2424- 2440 2431.93 608.24 0.39 4.72E+001 19.32 1.48E+001 5 3631- 3645 3637.17 909.57 0.93 3.57E+001 15.41 8.34E+000 6 5821- 5847 5834.02 1458.52 1.96 2.16E+002 30.29 3.20E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:05:23 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D41-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.911 1460.81* 10.67 7.76353E+004 1.26437E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 9.85095E+002 1.04309E+003 300.09 3.41 BI-214 0.992 609.31* 46.30 2.37501E+003 1.01817E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 1.57855E+003 1.66412E+003 351.92* 37.20 1.54165E+003 9.36268E+002 785.91 1.10 AC-228 0.979 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40

Interference Corrected Activity Report 3/27/2019 9:05:23 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.979 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.77789E+003 1.69080E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:05:23 PM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.911 7.763525E+004 1.264374E+004 PB-212 0.999 9.850953E+002 1.043094E+003 BI-214 0.992 2.375007E+003 1.018173E+003 PB-214 0.999 1.550522E+003 8.159862E+002 AC-228 0.979 3.777894E+003 1.690796E+003

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

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

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

Peak Locate Performed on: 3/27/2019 9:05:22 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/27/2019 9:05:23 PM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D41-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 5.328E+003 5.33E+003 7.764E+004 2.177E+003 CO-60 1173.22 100.00 1.141E+003 8.83E+002 -1.437E+002 5.249E+002 1332.49 100.00 8.828E+002 4.679E+002 3.927E+002 CS-134 475.35 1.46 5.995E+004 1.12E+003 1.717E+004 2.810E+004 563.23 8.38 9.811E+003 1.187E+003 4.546E+003 569.32 15.43 4.928E+003 -4.577E+003 2.268E+003 604.70 97.60 1.159E+003 1.191E+003 5.476E+002 795.84 85.40 1.122E+003 4.788E+002 5.182E+002 801.93 8.73 1.038E+004 3.893E+003 4.769E+003 1038.57 1.00 8.890E+004 -3.784E+003 4.018E+004 1167.94 1.80 5.990E+004 1.771E+004 2.743E+004 1365.15 3.04 2.098E+004 -1.460E+004 8.861E+003 CS-137 661.65 85.12 1.077E+003 1.08E+003 2.820E+002 4.996E+002 EU-152 121.78 28.40 3.868E+003 3.27E+003 1.774E+002 1.876E+003 344.27 26.50 3.272E+003 -6.733E+003 1.550E+003 1407.95 20.70 3.748E+003 -2.984E+003 1.629E+003 EU-154 123.07 40.40 2.664E+003 2.61E+003 -1.639E+003 1.291E+003 722.30 20.00 4.358E+003 2.229E+003 2.005E+003 1274.51 34.40 2.606E+003 1.654E+003 1.165E+003

+ BI-214 609.31* 46.30 1.259E+003 1.26E+003 2.375E+003 5.616E+002 768.36 5.04 1.898E+004 -5.962E+003 8.778E+003 806.17 1.23 6.274E+004 -5.564E+004 2.836E+004 934.06 3.21 2.767E+004 -1.350E+004 1.258E+004 1120.29 15.10 7.952E+003 3.070E+003 3.682E+003 1155.19 1.69 6.343E+004 3.355E+004 2.905E+004 1238.11 5.94 1.715E+004 1.457E+003 7.787E+003 1280.96 1.47 5.881E+004 3.081E+004 2.616E+004 1377.67 4.11 1.859E+004 5.889E+003 8.080E+003 1385.31 0.78 9.832E+004 3.898E+004 4.274E+004 1401.50 1.39 4.868E+004 -4.886E+004 2.071E+004 1407.98 2.48 3.128E+004 -2.490E+004 1.360E+004 1509.19 2.19 2.697E+004 8.339E+002 1.105E+004 1661.28 1.15 5.166E+004 2.198E+004 2.087E+004 1729.60 3.05 2.005E+004 8.528E+003 8.100E+003 1764.49 15.80 5.598E+003 3.896E+003 2.423E+003 1847.44 2.12 3.556E+004 1.920E+004 1.489E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.685E+004 1.32E+003 5.738E+004 1.791E+004 77.11 10.70 2.054E+004 3.511E+004 9.988E+003 87.20 3.70 4.220E+004 2.266E+003 2.052E+004 89.80 1.03 1.456E+005 -3.333E+004 7.079E+004 241.98 7.49 1.427E+004 2.476E+003 6.880E+003

Nuclide MDA Report 3/27/2019 9:05:23 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21* 19.20 2.656E+003 1.32E+003 1.579E+003 1.218E+003 351.92* 37.20 1.325E+003 1.542E+003 6.001E+002 785.91 1.10 8.318E+004 -4.320E+004 3.827E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D42-GM.CNF Report Generated On  : 3/27/2019 9:07:11 PM Sample Title  : B1-010-001-FSFC-D42-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D42 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 9:55:00 AM Acquisition Started  : 3/27/2019 9:55:26 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 9:07:11 PM Page 2

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Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D42-GM Peak Analysis Performed on: 3/27/2019 9:07:11 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 295- 305 299.44 74.79 0.90 4.17E+001 33.07 9.63E+001 2 947- 958 952.49 238.19 1.11 3.10E+001 25.41 5.20E+001 3 1399- 1411 1404.53 351.28 0.39 2.60E+001 20.85 3.10E+001 4 2425- 2438 2430.76 607.94 0.79 3.69E+001 17.44 1.41E+001 5 5822- 5845 5832.95 1458.25 1.55 1.97E+002 31.00 1.13E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:07:11 PM Page 3

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Sample

Title:

B1-010-001-FSFC-D42-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.890 1460.81* 10.67 7.07733E+004 1.25923E+004 PB-212 0.998 74.81* 9.60 1.05151E+004 8.60772E+003 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 9.64011E+002 8.04929E+002 300.09 3.41 BI-214 0.987 609.31* 46.30 1.85712E+003 9.08664E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.469 74.81* 6.33 1.59470E+004 1.30544E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.19644E+003 9.76846E+002 785.91 1.10

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:07:11 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.890 7.077327E+004 1.259228E+004 PB-212 0.998 1.039549E+003 8.014524E+002 BI-214 0.987 1.857118E+003 9.086643E+002 PB-214 0.469 1.269798E+003 9.741458E+002

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

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

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

Peak Locate Performed on: 3/27/2019 9:07:11 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/27/2019 9:07:11 PM Page 5

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D42-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 8.784E+003 8.78E+003 7.077E+004 3.905E+003 CO-60 1173.22 100.00 9.901E+002 8.83E+002 5.970E+002 4.495E+002 1332.49 100.00 8.828E+002 2.577E+002 3.927E+002 CS-134 475.35 1.46 5.532E+004 1.08E+003 1.818E+003 2.579E+004 563.23 8.38 1.014E+004 -2.847E+003 4.711E+003 569.32 15.43 5.315E+003 -4.733E+003 2.461E+003 604.70 97.60 1.084E+003 -7.552E+000 5.099E+002 795.84 85.40 1.154E+003 -3.243E+002 5.338E+002 801.93 8.73 1.173E+004 1.118E+004 5.443E+003 1038.57 1.00 9.534E+004 2.050E+004 4.340E+004 1167.94 1.80 5.487E+004 4.957E+003 2.491E+004 1365.15 3.04 2.267E+004 3.588E+003 9.707E+003 CS-137 661.65 85.12 1.234E+003 1.23E+003 7.291E+002 5.782E+002 EU-152 121.78 28.40 3.821E+003 3.36E+003 6.772E+002 1.853E+003 344.27 26.50 3.356E+003 -5.399E+003 1.592E+003 1407.95 20.70 3.855E+003 1.563E+003 1.683E+003 EU-154 123.07 40.40 2.679E+003 2.68E+003 -1.242E+003 1.299E+003 722.30 20.00 4.268E+003 2.970E+003 1.960E+003 1274.51 34.40 2.880E+003 -8.413E+002 1.302E+003

+ BI-214 609.31* 46.30 1.171E+003 1.17E+003 1.857E+003 5.173E+002 768.36 5.04 1.810E+004 9.774E+003 8.336E+003 806.17 1.23 7.549E+004 4.178E+004 3.473E+004 934.06 3.21 2.535E+004 -4.638E+002 1.142E+004 1120.29 15.10 8.089E+003 3.777E+003 3.751E+003 1155.19 1.69 5.968E+004 6.077E+003 2.717E+004 1238.11 5.94 1.667E+004 9.718E+003 7.548E+003 1280.96 1.47 6.656E+004 -3.596E+003 3.004E+004 1377.67 4.11 1.912E+004 6.585E+003 8.345E+003 1385.31 0.78 1.038E+005 1.953E+003 4.550E+004 1401.50 1.39 5.563E+004 -4.160E+004 2.418E+004 1407.98 2.48 3.218E+004 1.304E+004 1.405E+004 1509.19 2.19 3.613E+004 -6.286E+003 1.563E+004 1661.28 1.15 4.400E+004 1.465E+004 1.704E+004 1729.60 3.05 2.005E+004 -1.267E+004 8.100E+003 1764.49 15.80 7.727E+003 8.071E+003 3.487E+003 1847.44 2.12 1.570E+004 -8.536E+003 4.964E+003

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81* 6.33 2.021E+004 1.50E+003 1.595E+004 9.586E+003 77.11 10.70 1.994E+004 1.479E+004 9.691E+003 87.20 3.70 4.152E+004 -1.258E+004 2.018E+004 89.80 1.03 1.417E+005 8.371E+003 6.886E+004 241.98 7.49 1.324E+004 8.454E+003 6.368E+003

Nuclide MDA Report 3/27/2019 9:07:11 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 4.777E+003 1.50E+003 -1.385E+003 2.279E+003 351.92* 37.20 1.498E+003 1.196E+003 6.870E+002 785.91 1.10 7.881E+004 1.470E+004 3.608E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D43-GM.CNF Report Generated On  : 3/29/2019 10:49:21 AM Sample Title  : B1-010-001-FSFC-D43-GM Sample Description  : Rx Bowl concrete 2M Sample Identification  : D43 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 1.256E+001 M^2 Sample Taken On  : 3/29/2019 8:51:00 AM Acquisition Started  : 3/29/2019 8:52:53 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_2M

Peak Analysis Report 3/29/2019 10:49:21 AM Page 2

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Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D43-GM Peak Analysis Performed on: 3/29/2019 10:49:21 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 949- 961 954.17 238.61 0.76 2.98E+001 25.39 4.92E+001 2 1402- 1414 1407.87 352.11 1.08 1.86E+001 20.37 3.24E+001 3 2327- 2338 2332.88 583.47 1.15 1.34E+001 14.85 1.66E+001 4 2431- 2445 2437.03 609.51 1.17 3.99E+001 16.26 9.13E+000 5 2641- 2653 2646.74 661.95 0.38 2.98E+001 16.17 1.33E+001 6 5836- 5857 5847.15 1461.80 1.47 1.74E+002 30.58 1.61E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:49:21 AM Page 3

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Sample

Title:

B1-010-001-FSFC-D43-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.983 1460.81* 10.67 1.40201E+005 2.72350E+004 CS-137 0.998 661.65* 85.12 1.90988E+003 1.06328E+003 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.05933E+003 1.78292E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 4.48706E+003 1.91731E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.90751E+003 2.10882E+003 785.91 1.10

Interference Corrected Activity Report 3/29/2019 10:49:21 AM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:49:21 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.983 1.402007E+005 2.723495E+004 CS-137 0.998 1.909876E+003 1.063284E+003 PB-212 1.000 2.059332E+003 1.782924E+003 BI-214 1.000 4.487058E+003 1.917314E+003 PB-214 1.000 1.907512E+003 2.108819E+003

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

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

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

Peak Locate Performed on: 3/29/2019 10:49:21 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 583.47 2.2389E-002 110.51 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/29/2019 10:49:21 AM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D43-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 2.270E+004 2.27E+004 1.402E+005 1.026E+004 CO-60 1173.22 100.00 2.497E+003 2.01E+003 9.398E+002 1.147E+003 1332.49 100.00 2.013E+003 8.115E+002 8.976E+002 CS-134 475.35 1.46 1.252E+005 2.12E+003 -1.374E+004 5.844E+004 563.23 8.38 2.076E+004 -1.033E+004 9.575E+003 569.32 15.43 1.134E+004 3.274E+003 5.233E+003 604.70 97.60 2.502E+003 -1.475E+003 1.179E+003 795.84 85.40 2.124E+003 -8.060E+001 9.655E+002 801.93 8.73 2.420E+004 1.273E+004 1.115E+004 1038.57 1.00 2.186E+005 5.993E+004 9.978E+004 1167.94 1.80 1.323E+005 -1.208E+005 6.054E+004 1365.15 3.04 5.417E+004 1.803E+004 2.344E+004

+ CS-137 661.65* 85.12 1.435E+003 1.43E+003 1.910E+003 6.304E+002 EU-152 121.78 28.40 8.705E+003 7.77E+003 -2.332E+003 4.225E+003 344.27 26.50 7.772E+003 8.493E+002 3.694E+003 1407.95 20.70 8.381E+003 2.635E+003 3.644E+003 EU-154 123.07 40.40 5.992E+003 5.25E+003 -4.437E+003 2.907E+003 722.30 20.00 1.051E+004 7.389E+003 4.867E+003 1274.51 34.40 5.250E+003 8.565E+002 2.316E+003

+ BI-214 609.31* 46.30 2.199E+003 2.20E+003 4.487E+003 9.473E+002 768.36 5.04 3.883E+004 -2.315E+004 1.782E+004 806.17 1.23 1.689E+005 1.519E+005 7.770E+004 934.06 3.21 5.760E+004 6.017E+004 2.599E+004 1120.29 15.10 1.410E+004 8.139E+003 6.395E+003 1155.19 1.69 1.385E+005 1.358E+005 6.328E+004 1238.11 5.94 4.638E+004 2.344E+004 2.143E+004 1280.96 1.47 1.203E+005 -6.699E+004 5.289E+004 1377.67 4.11 4.500E+004 5.514E+003 1.979E+004 1385.31 0.78 2.198E+005 -2.652E+003 9.557E+004 1401.50 1.39 1.089E+005 -1.226E+005 4.631E+004 1407.98 2.48 6.996E+004 2.200E+004 3.041E+004 1509.19 2.19 6.376E+004 3.265E+003 2.644E+004 1661.28 1.15 9.851E+004 -4.665E+004 3.816E+004 1729.60 3.05 3.824E+004 1.273E+004 1.481E+004 1764.49 15.80 1.131E+004 6.858E+003 4.810E+003 1847.44 2.12 9.001E+004 1.395E+004 3.853E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 7.823E+004 3.39E+003 4.849E+004 3.798E+004 77.11 10.70 4.347E+004 3.446E+004 2.112E+004 87.20 3.70 8.883E+004 -5.577E+004 4.314E+004 89.80 1.03 3.156E+005 3.089E+005 1.534E+005 241.98 7.49 2.768E+004 2.256E+004 1.328E+004

Nuclide MDA Report 3/29/2019 10:49:21 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 1.048E+004 3.39E+003 4.322E+003 4.995E+003 351.92* 37.20 3.386E+003 1.908E+003 1.555E+003 785.91 1.10 1.742E+005 3.154E+004 7.970E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D50-GM.CNF Report Generated On  : 3/29/2019 10:52:10 AM Sample Title  : B1-010-001-FSFC-D50-GM Sample Description  : Rx Bowl 2M Concrete Sample Identification  : D50 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 1.256E+001 M^2 Sample Taken On  : 3/28/2019 2:50:00 AM Acquisition Started  : 3/28/2019 2:49:47 PM Live Time  : 600.0 seconds Real Time  : 600.3 seconds Dead Time  : 0.05 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_2M

Peak Analysis Report 3/29/2019 10:52:10 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D50-GM Peak Analysis Performed on: 3/29/2019 10:52:09 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 305 300.37 75.03 0.98 2.67E+001 32.27 1.02E+002 2 1400- 1412 1406.35 351.73 0.92 1.83E+001 22.39 4.07E+001 3 2032- 2046 2040.27 510.29 0.36 2.40E+001 20.99 2.80E+001 4 2326- 2338 2331.15 583.04 0.33 2.69E+001 17.93 2.01E+001 5 2429- 2440 2434.90 608.98 0.41 2.10E+001 17.21 2.10E+001 6 3866- 3879 3872.95 968.50 0.30 9.27E+000 12.63 1.07E+001 7 5828- 5852 5840.72 1460.19 1.72 2.15E+002 30.97 6.09E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:52:10 AM Page 3

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

Sample

Title:

B1-010-001-FSFC-D50-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.993 1460.81* 10.67 1.73091E+005 2.87493E+004 BI-214 0.999 609.31* 46.30 2.36205E+003 1.95960E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.626 74.81* 6.33 2.22868E+004 2.73161E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.87519E+003 2.31171E+003 785.91 1.10 AC-228 0.999 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60 27.70 964.60 5.20 969.11* 16.60 3.79520E+003 5.17849E+003 1587.90 3.71

Interference Corrected Activity Report 3/29/2019 10:52:10 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 10:52:10 AM Page 5

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.993 1.730911E+005 2.874934E+004 BI-214 0.999 2.362048E+003 1.959599E+003 PB-214 0.626 2.020336E+003 2.303475E+003 AC-228 0.999 3.795202E+003 5.178494E+003

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

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

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

Peak Locate Performed on: 3/29/2019 10:52:09 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 510.29 4.0080E-002 87.30 4 583.04 4.4867E-002 66.60 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/29/2019 10:52:10 AM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D50-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 1.538E+004 1.54E+004 1.731E+005 6.601E+003 CO-60 1173.22 100.00 2.550E+003 2.13E+003 -1.345E+002 1.173E+003 1332.49 100.00 2.127E+003 1.284E+002 9.545E+002 CS-134 475.35 1.46 1.411E+005 2.24E+003 2.481E+004 6.635E+004 563.23 8.38 2.556E+004 2.625E+004 1.197E+004 569.32 15.43 1.229E+004 -4.148E+003 5.705E+003 604.70 97.60 2.491E+003 2.245E+003 1.173E+003 795.84 85.40 2.235E+003 -2.642E+002 1.021E+003 801.93 8.73 2.059E+004 -4.208E+004 9.351E+003 1038.57 1.00 2.292E+005 4.009E+004 1.051E+005 1167.94 1.80 1.355E+005 -8.338E+004 6.210E+004 1365.15 3.04 6.047E+004 -3.368E+004 2.659E+004 CS-137 661.65 85.12 2.506E+003 2.51E+003 -3.567E+002 1.166E+003 EU-152 121.78 28.40 9.201E+003 7.34E+003 6.078E+003 4.473E+003 344.27 26.50 7.919E+003 -5.340E+003 3.767E+003 1407.95 20.70 7.335E+003 1.682E+003 3.120E+003 EU-154 123.07 40.40 6.461E+003 6.46E+003 2.911E+003 3.141E+003 722.30 20.00 1.096E+004 6.760E+003 5.092E+003 1274.51 34.40 6.535E+003 3.559E+003 2.959E+003

+ BI-214 609.31* 46.30 3.000E+003 3.00E+003 2.362E+003 1.348E+003 768.36 5.04 4.285E+004 1.380E+004 1.983E+004 806.17 1.23 1.600E+005 2.054E+004 7.326E+004 934.06 3.21 6.667E+004 -7.132E+003 3.053E+004 1120.29 15.10 1.262E+004 -1.728E+004 5.652E+003 1155.19 1.69 1.512E+005 3.278E+004 6.962E+004 1238.11 5.94 4.185E+004 2.304E+004 1.916E+004 1280.96 1.47 1.464E+005 -1.322E+005 6.597E+004 1377.67 4.11 5.113E+004 2.339E+004 2.285E+004 1385.31 0.78 2.322E+005 6.271E+004 1.017E+005 1401.50 1.39 1.130E+005 2.538E+004 4.837E+004 1407.98 2.48 6.122E+004 1.404E+004 2.604E+004 1509.19 2.19 6.034E+004 -2.440E+004 2.473E+004 1661.28 1.15 9.851E+004 -1.281E+005 3.816E+004 1729.60 3.05 4.780E+004 2.228E+004 1.959E+004 1764.49 15.80 1.292E+004 -3.138E+003 5.617E+003 1847.44 2.12 7.180E+004 3.347E+004 2.943E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81* 6.33 4.426E+004 3.76E+003 2.229E+004 2.100E+004 77.11 10.70 4.593E+004 -1.828E+004 2.234E+004 87.20 3.70 9.640E+004 7.923E+004 4.692E+004 89.80 1.03 3.330E+005 3.035E+005 1.621E+005 241.98 7.49 3.290E+004 2.097E+004 1.589E+004

Nuclide MDA Report 3/29/2019 10:52:10 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 1.109E+004 3.76E+003 9.792E+003 5.302E+003 351.92* 37.20 3.761E+003 1.875E+003 1.742E+003 785.91 1.10 1.842E+005 -1.512E+004 8.466E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-FSFC-D51-GM.CNF Report Generated On  : 3/29/2019 12:34:03 PM Sample Title  : B1-010-001-FSFC-D51-GM Sample Description  : Rx Bowl concrete 2M Sample Identification  : D51 Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 1.256E+001 M^2 Sample Taken On  : 3/29/2019 9:05:00 AM Acquisition Started  : 3/29/2019 9:05:38 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_2M

Peak Analysis Report 3/29/2019 12:34:03 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-FSFC-D51-GM Peak Analysis Performed on: 3/29/2019 12:34:03 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 305 300.83 75.14 0.65 2.75E+001 29.27 8.25E+001 2 948- 962 955.09 238.84 0.59 2.58E+001 29.62 6.72E+001 3 1175- 1188 1180.89 295.33 1.45 2.93E+001 20.02 2.57E+001 4 1403- 1415 1408.84 352.36 1.28 3.01E+001 18.47 2.09E+001 5 2431- 2443 2436.03 609.26 0.59 2.31E+001 16.75 1.59E+001 6 2641- 2653 2646.45 661.88 0.39 3.06E+001 14.62 7.42E+000 7 5834- 5858 5847.13 1461.79 2.24 1.77E+002 26.61 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 12:34:03 PM Page 3

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

Sample

Title:

B1-010-001-FSFC-D51-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.983 1460.81* 10.67 1.42669E+005 2.44727E+004 CS-137 0.999 661.65* 85.12 1.96297E+003 9.67476E+002 PB-212 0.999 74.81* 9.60 1.50802E+004 1.63293E+004 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.78441E+003 2.06518E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 2.59635E+003 1.91399E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.998 74.81* 6.33 2.28704E+004 2.47649E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 5.27716E+003 3.70607E+003 351.92* 37.20 3.08412E+003 1.95631E+003 785.91 1.10

Interference Corrected Activity Report 3/29/2019 12:34:03 PM Page 4

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/29/2019 12:34:03 PM Page 5

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.983 1.426694E+005 2.447269E+004 CS-137 0.999 1.962968E+003 9.674756E+002 PB-212 0.999 1.955925E+003 2.048942E+003 BI-214 1.000 2.596353E+003 1.913991E+003 PB-214 0.998 3.641397E+003 1.725930E+003

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

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

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

Peak Locate Performed on: 3/29/2019 12:34:03 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide All peaks were identified.

Nuclide MDA Report 3/29/2019 12:34:03 PM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-FSFC-D51-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 2.181E+003 2.18E+003 1.427E+005 0.000E+000 CO-60 1173.22 100.00 2.360E+003 2.05E+003 -1.124E+003 1.078E+003 1332.49 100.00 2.051E+003 1.031E+002 9.169E+002 CS-134 475.35 1.46 1.330E+005 2.15E+003 7.442E+004 6.229E+004 563.23 8.38 2.096E+004 -1.515E+002 9.674E+003 569.32 15.43 1.248E+004 -1.875E+003 5.801E+003 604.70 97.60 2.153E+003 -3.963E+003 1.004E+003 795.84 85.40 2.287E+003 -4.942E+002 1.047E+003 801.93 8.73 2.087E+004 -1.703E+004 9.487E+003 1038.57 1.00 2.213E+005 5.808E+004 1.011E+005 1167.94 1.80 1.292E+005 -3.176E+004 5.896E+004 1365.15 3.04 6.738E+004 -2.693E+004 3.005E+004

+ CS-137 661.65* 85.12 1.183E+003 1.18E+003 1.963E+003 5.046E+002 EU-152 121.78 28.40 8.751E+003 7.09E+003 1.931E+003 4.248E+003 344.27 26.50 7.091E+003 1.982E+003 3.353E+003 1407.95 20.70 8.620E+003 -5.055E+002 3.763E+003 EU-154 123.07 40.40 6.088E+003 6.09E+003 -6.308E+002 2.955E+003 722.30 20.00 9.545E+003 2.448E+003 4.384E+003 1274.51 34.40 6.140E+003 -2.314E+003 2.761E+003

+ BI-214 609.31* 46.30 2.845E+003 2.84E+003 2.596E+003 1.270E+003 768.36 5.04 4.008E+004 2.068E+004 1.844E+004 806.17 1.23 1.361E+005 -1.638E+005 6.129E+004 934.06 3.21 6.353E+004 5.403E+003 2.896E+004 1120.29 15.10 1.762E+004 1.786E+004 8.152E+003 1155.19 1.69 1.385E+005 3.309E+004 6.328E+004 1238.11 5.94 4.326E+004 2.546E+004 1.987E+004 1280.96 1.47 1.392E+005 -1.112E+005 6.234E+004 1377.67 4.11 5.017E+004 1.273E+004 2.237E+004 1385.31 0.78 2.198E+005 -1.653E+005 9.557E+004 1401.50 1.39 1.130E+005 -5.552E+004 4.837E+004 1407.98 2.48 7.195E+004 -4.219E+003 3.141E+004 1509.19 2.19 7.289E+004 4.420E+004 3.101E+004 1661.28 1.15 1.367E+005 7.381E+004 5.724E+004 1729.60 3.05 4.174E+004 1.592E+004 1.656E+004 1764.49 15.80 1.466E+004 1.247E+004 6.486E+003 1847.44 2.12 7.586E+004 -4.184E+004 3.146E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81* 6.33 3.963E+004 2.78E+003 2.287E+004 1.869E+004 77.11 10.70 4.272E+004 3.877E+004 2.074E+004 87.20 3.70 9.038E+004 3.702E+004 4.391E+004 89.80 1.03 3.061E+005 -2.162E+005 1.487E+005 241.98 7.49 2.858E+004 1.952E+004 1.373E+004

Nuclide MDA Report 3/29/2019 12:34:03 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21* 19.20 5.482E+003 2.78E+003 5.277E+003 2.497E+003 351.92* 37.20 2.783E+003 3.084E+003 1.253E+003 785.91 1.10 1.861E+005 1.365E+005 8.561E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: C:\LACBWR\B1-010-001-QSFC-D05-GM.CNF Report Generated On  : 3/27/2019 9:09:02 PM Sample Title  : B1-010-001-QSFC-D05-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D05 QC Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/27/2019 2:35:00 PM Acquisition Started  : 3/27/2019 2:35:49 PM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/27/2019 9:09:02 PM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-QSFC-D05-GM Peak Analysis Performed on: 3/27/2019 9:09:01 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 962 953.54 238.45 1.05 7.30E+001 31.20 5.90E+001 2 1401- 1413 1407.35 351.98 1.36 3.38E+001 21.02 2.92E+001 3 2326- 2338 2332.62 583.40 0.71 2.87E+001 19.24 2.43E+001 4 2429- 2442 2435.08 609.02 0.93 3.98E+001 19.24 1.92E+001 5 3636- 3651 3644.24 911.33 1.53 3.40E+001 17.54 1.40E+001 6 5832- 5854 5843.78 1460.95 1.15 2.17E+002 30.95 5.75E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/27/2019 9:09:02 PM Page 3

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Sample

Title:

B1-010-001-QSFC-D05-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 1.000 1460.81* 10.67 7.82517E+004 1.28880E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.27008E+003 1.03617E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 2.00440E+003 1.00165E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.55587E+003 9.98546E+002 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40

Interference Corrected Activity Report 3/27/2019 9:09:02 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 1.000 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.60374E+003 1.90591E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 1.000 7.825170E+004 1.288804E+004 PB-212 1.000 2.270080E+003 1.036165E+003 BI-214 0.999 2.004399E+003 1.001647E+003 PB-214 1.000 1.555866E+003 9.985456E+002 AC-228 1.000 3.603738E+003 1.905910E+003

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

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

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

Peak Locate Performed on: 3/27/2019 9:09:01 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 583.40 4.7767E-002 67.14 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/27/2019 9:09:02 PM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-QSFC-D05-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 6.569E+003 6.57E+003 7.825E+004 2.797E+003 CO-60 1173.22 100.00 1.175E+003 7.67E+002 -2.554E+002 5.421E+002 1332.49 100.00 7.672E+002 5.758E+002 3.349E+002 CS-134 475.35 1.46 6.422E+004 1.11E+003 -9.557E+003 3.024E+004 563.23 8.38 1.062E+004 -3.370E+003 4.949E+003 569.32 15.43 5.717E+003 -1.559E+002 2.662E+003 604.70 97.60 1.225E+003 8.390E+002 5.801E+002 795.84 85.40 1.112E+003 5.303E+000 5.129E+002 801.93 8.73 1.123E+004 -1.251E+003 5.194E+003 1038.57 1.00 1.036E+005 -1.845E+004 4.755E+004 1167.94 1.80 6.514E+004 3.262E+004 3.005E+004 1365.15 3.04 2.267E+004 -2.359E+003 9.707E+003 CS-137 661.65 85.12 1.211E+003 1.21E+003 5.305E+002 5.665E+002 EU-152 121.78 28.40 3.976E+003 3.33E+003 -3.315E+003 1.931E+003 344.27 26.50 3.328E+003 -1.866E+003 1.578E+003 1407.95 20.70 3.523E+003 -1.878E+003 1.517E+003 EU-154 123.07 40.40 2.827E+003 2.83E+003 1.519E+003 1.373E+003 722.30 20.00 4.861E+003 2.024E+003 2.257E+003 1274.51 34.40 2.966E+003 -1.405E+003 1.345E+003

+ BI-214 609.31* 46.30 1.338E+003 1.34E+003 2.004E+003 6.010E+002 768.36 5.04 2.031E+004 9.378E+003 9.441E+003 806.17 1.23 8.141E+004 5.676E+004 3.770E+004 934.06 3.21 3.081E+004 2.006E+004 1.415E+004 1120.29 15.10 7.221E+003 5.945E+003 3.316E+003 1155.19 1.69 6.121E+004 -3.859E+004 2.794E+004 1238.11 5.94 2.240E+004 2.669E+003 1.041E+004 1280.96 1.47 6.551E+004 -2.783E+003 2.951E+004 1377.67 4.11 1.912E+004 7.818E+003 8.345E+003 1385.31 0.78 1.011E+005 -1.022E+005 4.414E+004 1401.50 1.39 5.563E+004 -3.937E+003 2.418E+004 1407.98 2.48 2.941E+004 -1.567E+004 1.266E+004 1509.19 2.19 3.258E+004 6.939E+002 1.386E+004 1661.28 1.15 5.166E+004 3.052E+003 2.087E+004 1729.60 3.05 2.005E+004 -2.428E+003 8.100E+003 1764.49 15.80 5.768E+003 4.175E+003 2.508E+003 1847.44 2.12 3.870E+004 2.347E+004 1.646E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.820E+004 1.45E+003 4.252E+004 1.858E+004 77.11 10.70 2.075E+004 1.008E+004 1.009E+004 87.20 3.70 4.325E+004 -4.759E+003 2.104E+004 89.80 1.03 1.497E+005 -2.951E+004 7.284E+004 241.98 7.49 1.470E+004 1.780E+004 7.096E+003

Nuclide MDA Report 3/27/2019 9:09:02 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 5.293E+003 1.45E+003 2.322E+003 2.537E+003 351.92* 37.20 1.450E+003 1.556E+003 6.625E+002 785.91 1.10 8.403E+004 6.127E+004 3.870E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 10:29:15 AM Sample Title  : B1-010-001-QSFC-D16-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D16 QC Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 10:18:00 AM Acquisition Started  : 3/28/2019 10:19:14 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.03 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 10:29:15 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-QSFC-D16-GM Peak Analysis Performed on: 3/28/2019 10:29:15 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 962 953.50 238.45 0.85 7.85E+001 36.37 8.05E+001 2 1399- 1413 1406.11 351.67 0.86 5.03E+001 19.83 1.67E+001 3 2036- 2048 2042.22 510.78 0.50 2.19E+001 18.29 2.31E+001 4 2427- 2440 2433.85 608.72 1.38 4.77E+001 15.81 5.31E+000 5 2639- 2650 2644.11 661.29 0.80 1.77E+001 14.30 1.33E+001 6 3634- 3649 3640.98 910.52 0.39 3.92E+001 16.55 9.78E+000 7 5825- 5849 5837.80 1459.46 2.00 2.40E+002 31.78 3.08E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 10:29:15 AM Page 3

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Sample

Title:

B1-010-001-QSFC-D16-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.968 1460.81* 10.67 8.63537E+004 1.34818E+004 CS-137 0.998 661.65* 85.12 5.08538E+002 4.14857E+002 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.44215E+003 1.19668E+003 300.09 3.41 BI-214 0.997 609.31* 46.30 2.39916E+003 8.52609E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 2.31231E+003 9.84011E+002 785.91 1.10 AC-228 0.994 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20

Interference Corrected Activity Report 3/28/2019 10:29:15 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.994 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 4.15736E+003 1.81886E+003 964.60 5.20 969.11 16.60 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 10:29:15 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.968 8.635370E+004 1.348176E+004 CS-137 0.998 5.085379E+002 4.148573E+002 PB-212 1.000 2.442154E+003 1.196680E+003 BI-214 0.997 2.399160E+003 8.526093E+002 PB-214 1.000 2.312315E+003 9.840105E+002 AC-228 0.994 4.157360E+003 1.818857E+003

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

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

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

Peak Locate Performed on: 3/28/2019 10:29:15 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 3 510.78 3.6574E-002 83.34 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 10:29:15 AM Page 6

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Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-QSFC-D16-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 5.180E+003 5.18E+003 8.635E+004 2.103E+003 CO-60 1173.22 100.00 1.068E+003 9.51E+002 5.177E+002 4.887E+002 1332.49 100.00 9.512E+002 9.357E+002 4.269E+002 CS-134 475.35 1.46 5.652E+004 1.14E+003 2.009E+004 2.638E+004 563.23 8.38 1.114E+004 8.224E+003 5.213E+003 569.32 15.43 5.630E+003 -1.603E+003 2.618E+003 604.70 97.60 1.137E+003 8.294E+002 5.363E+002 795.84 85.40 1.174E+003 -7.137E+002 5.440E+002 801.93 8.73 1.123E+004 -1.225E+004 5.194E+003 1038.57 1.00 9.154E+004 1.035E+004 4.150E+004 1167.94 1.80 6.192E+004 -3.238E+004 2.844E+004 1365.15 3.04 2.568E+004 1.109E+004 1.121E+004

+ CS-137 661.65* 85.12 6.233E+002 6.23E+002 5.085E+002 2.728E+002 EU-152 121.78 28.40 4.032E+003 3.14E+003 -3.481E+003 1.958E+003 344.27 26.50 3.141E+003 -3.097E+003 1.484E+003 1407.95 20.70 3.855E+003 -1.407E+003 1.683E+003 EU-154 123.07 40.40 2.866E+003 2.87E+003 -3.153E+002 1.392E+003 722.30 20.00 4.781E+003 0.000E+000 2.217E+003 1274.51 34.40 3.049E+003 2.662E+003 1.386E+003

+ BI-214 609.31* 46.30 7.726E+002 7.73E+002 2.399E+003 3.182E+002 768.36 5.04 1.810E+004 -1.901E+004 8.336E+003 806.17 1.23 8.070E+004 2.536E+004 3.734E+004 934.06 3.21 3.048E+004 -1.391E+004 1.398E+004 1120.29 15.10 8.021E+003 5.109E+003 3.716E+003 1155.19 1.69 6.270E+004 9.415E+003 2.868E+004 1238.11 5.94 1.762E+004 -1.061E+004 8.020E+003 1280.96 1.47 6.656E+004 3.297E+004 3.004E+004 1377.67 4.11 2.061E+004 -3.799E+003 9.093E+003 1385.31 0.78 9.242E+004 2.819E+004 3.979E+004 1401.50 1.39 5.399E+004 -9.586E+002 2.336E+004 1407.98 2.48 3.218E+004 -1.174E+004 1.405E+004 1509.19 2.19 2.993E+004 -1.212E+004 1.253E+004 1661.28 1.15 4.802E+004 1.831E+004 1.905E+004 1729.60 3.05 1.863E+004 7.107E+003 7.394E+003 1764.49 15.80 5.422E+003 1.638E+003 2.334E+003 1847.44 2.12 4.423E+004 -2.450E+004 1.923E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.658E+004 1.17E+003 3.023E+004 1.777E+004 77.11 10.70 2.011E+004 3.848E+003 9.775E+003 87.20 3.70 4.348E+004 8.908E+003 2.116E+004 89.80 1.03 1.516E+005 -5.670E+003 7.381E+004 241.98 7.49 1.504E+004 1.816E+004 7.267E+003

Nuclide MDA Report 3/28/2019 10:29:15 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21 19.20 4.885E+003 1.17E+003 3.268E+003 2.333E+003 351.92* 37.20 1.173E+003 2.312E+003 5.242E+002 785.91 1.10 8.732E+004 2.146E+004 4.034E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

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

Filename: 3844 Report Generated On  : 3/28/2019 11:22:47 AM Sample Title  : B1-010-001-QSFC-D18-GM Sample Description  : Rx Bowl 3M Concrete Sample Identification  : D18 QC Sample Type  : Gamma Direct Sample Geometry  :

Peak Locate Threshold  : 3.00 Peak Locate Range (in channels)  : 85 - 8000 Peak Area Range (in channels)  : 85 - 8000 Identification Energy Tolerance  : 3.000 keV Sample Size  : 2.827E+001 M^2 Sample Taken On  : 3/28/2019 11:12:00 AM Acquisition Started  : 3/28/2019 11:12:47 AM Live Time  : 600.0 seconds Real Time  : 600.2 seconds Dead Time  : 0.04 %

Energy Calibration Used Done On  : 10/24/2017 Efficiency Calibration Used Done On  : 3/26/2019 Efficiency ID  : RxBOWL_CON_3M

Peak Analysis Report 3/28/2019 11:22:47 AM Page 2

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

Detector Name: 3844 Sample

Title:

B1-010-001-QSFC-D18-GM Peak Analysis Performed on: 3/28/2019 11:22:47 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 962 954.03 238.58 1.17 8.91E+001 36.40 7.69E+001 M 2 1174- 1207 1179.08 294.88 0.67 1.64E+001 11.88 2.75E+001 m 3 1174- 1207 1201.25 300.42 0.67 1.79E+001 10.87 1.50E+001 4 1399- 1411 1405.77 351.59 0.84 3.25E+001 19.77 2.45E+001 5 2323- 2336 2329.15 582.53 0.80 2.80E+001 18.64 2.10E+001 6 2425- 2439 2433.23 608.56 1.53 5.06E+001 17.64 9.41E+000 7 3635- 3648 3641.58 910.67 0.99 3.10E+001 14.19 7.00E+000 8 3866- 3879 3872.52 968.40 0.34 1.89E+001 11.45 5.05E+000 9 4468- 4481 4474.03 1118.73 0.67 1.90E+001 8.72 0.00E+000 10 5826- 5849 5838.16 1459.55 1.48 2.28E+002 30.98 2.99E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 11:22:48 AM Page 3

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Sample

Title:

B1-010-001-QSFC-D18-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.972 1460.81* 10.67 8.20698E+004 1.30518E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.77141E+003 1.21627E+003 300.09* 3.41 8.23659E+003 5.17734E+003 BI-214 0.990 609.31* 46.30 2.54462E+003 9.45328E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29* 15.10 4.12731E+003 1.92231E+003 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 1.33119E+003 9.85785E+002 351.92* 37.20 1.49219E+003 9.39593E+002 785.91 1.10 AC-228 0.994 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40

Interference Corrected Activity Report 3/28/2019 11:22:48 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.994 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.28595E+003 1.55137E+003 964.60 5.20 969.11* 16.60 3.46665E+003 2.11981E+003 1587.90 3.71

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

Interference Corrected Activity Report 3/28/2019 11:22:48 AM Page 5

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.972 8.206984E+004 1.305183E+004 PB-212 1.000 3.057254E+003 1.184041E+003 BI-214 0.990 2.852834E+003 8.483022E+002 PB-214 0.999 1.415549E+003 6.801367E+002 AC-228 0.994 3.348978E+003 1.251922E+003

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

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

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

Peak Locate Performed on: 3/28/2019 11:22:47 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 5 582.53 4.6667E-002 66.56 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

Nuclide MDA Report 3/28/2019 11:22:48 AM Page 6

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

Detector Name: 3844 Sample Geometry:

Sample

Title:

B1-010-001-QSFC-D18-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ K-40 1460.81* 10.67 5.076E+003 5.08E+003 8.207E+004 2.051E+003 CO-60 1173.22 100.00 1.175E+003 9.67E+002 -1.199E+003 5.421E+002 1332.49 100.00 9.675E+002 4.229E+002 4.351E+002 CS-134 475.35 1.46 6.032E+004 1.12E+003 7.508E+003 2.828E+004 563.23 8.38 9.641E+003 -7.604E+003 4.461E+003 569.32 15.43 5.497E+003 -1.154E+002 2.552E+003 604.70 97.60 1.182E+003 1.112E+003 5.586E+002 795.84 85.40 1.122E+003 6.965E+001 5.182E+002 801.93 8.73 9.452E+003 -2.673E+003 4.303E+003 1038.57 1.00 8.190E+004 -1.026E+005 3.668E+004 1167.94 1.80 6.576E+004 4.906E+004 3.036E+004 1365.15 3.04 2.894E+004 -1.180E+004 1.284E+004 CS-137 661.65 85.12 1.154E+003 1.15E+003 3.151E+002 5.383E+002 EU-152 121.78 28.40 3.997E+003 3.07E+003 2.133E+002 1.941E+003 344.27 26.50 3.066E+003 -5.048E+003 1.447E+003 1407.95 20.70 3.958E+003 -4.553E+003 1.735E+003 EU-154 123.07 40.40 2.803E+003 2.80E+003 -6.766E+002 1.361E+003 722.30 20.00 4.617E+003 2.214E+003 2.134E+003 1274.51 34.40 3.089E+003 -2.996E+003 1.406E+003

+ BI-214 609.31* 46.30 9.993E+002 5.88E+002 2.545E+003 4.316E+002 768.36 5.04 2.047E+004 -1.323E+003 9.521E+003 806.17 1.23 7.393E+004 3.450E+004 3.395E+004 934.06 3.21 2.840E+004 -1.690E+004 1.295E+004 1120.29* 15.10 5.878E+002 4.127E+003 0.000E+000 1155.19 1.69 5.890E+004 -9.319E+003 2.678E+004 1238.11 5.94 1.894E+004 6.118E+003 8.680E+003 1280.96 1.47 7.704E+004 2.278E+004 3.528E+004 1377.67 4.11 2.200E+004 -6.155E+003 9.785E+003 1385.31 0.78 1.187E+005 6.812E+004 5.293E+004 1401.50 1.39 5.876E+004 -1.370E+004 2.575E+004 1407.98 2.48 3.304E+004 -3.800E+004 1.448E+004 1509.19 2.19 2.697E+004 1.257E+004 1.105E+004 1661.28 1.15 5.166E+004 -1.648E+004 2.087E+004 1729.60 3.05 2.134E+004 -4.619E+003 8.749E+003 1764.49 15.80 5.933E+003 1.874E+003 2.590E+003 1847.44 2.12 3.204E+004 1.494E+004 1.313E+004

> 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000

+ PB-214 74.81 6.33 3.798E+004 1.35E+003 3.788E+004 1.847E+004 77.11 10.70 2.105E+004 2.457E+004 1.024E+004 87.20 3.70 4.301E+004 -2.303E+004 2.093E+004 89.80 1.03 1.527E+005 7.462E+003 7.436E+004 241.98 7.49 1.507E+004 1.383E+004 7.280E+003

Nuclide MDA Report 3/28/2019 11:22:48 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )

+ PB-214 295.21* 19.20 2.198E+003 1.35E+003 1.331E+003 9.892E+002 351.92* 37.20 1.346E+003 1.492E+003 6.108E+002 785.91 1.10 8.971E+004 3.453E+004 4.154E+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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