ML19295G841

Revised Final Status Survey (FSS) Report - Phase 2, Release Record - Unit 1 Tendon Buttress Pits Survey Unit 06107

ML19295G841
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	09/01/2019
From:	Giza P ZionSolutions
To:	Office of Nuclear Material Safety and Safeguards
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References
ZS-2019-0090
Download: ML19295G841 (72)

Text

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= ZIONSOLUTIONSLLC-An EnergySolutions Company ZION STATION RESTORATION PROJECT FINAL STATUS SURVEY RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107

FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 PREPARED BY / DATE: Patricia Giza 2019-09-01 Radiological Engineer REVIEWED BY / DATE: Jeffrey Graham 2019-09-01 Radiological Engineer APPROVED BY / DATE: D. Wojtkowiak 2019-09-01 C/LT Manager

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

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

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

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

4. DATA QUALITY OBJECTIVES (DQO) ............................................................................. 6

5. SURVEY DESIGN ................................................................................................................ 10

6. SURVEY IMPLEMENTATION ......................................................................................... 13

7. SURVEY RESULTS ............................................................................................................. 14

8. QUALITY CONTROL ......................................................................................................... 15

9. INVESTIGATIONS AND RESULTS ................................................................................. 16

10. REMEDIATION AND RESULTS....................................................................................... 16

11. CHANGES FROM THE SURVEY PLAN ......................................................................... 16

12. DATA QUALITY ASSESSMENT (DQA) .......................................................................... 16

13. ANOMALIES ........................................................................................................................ 16

14. CONCLUSION ...................................................................................................................... 16

15. REFERENCES ...................................................................................................................... 17

16. ATTACHMENTS .................................................................................................................. 18 ATTACHMENT 1 - FIGURES AND MAPS ....................................................................... 19 ATTACHMENT 2 - QC DATA ............................................................................................ 22 ATTACHMENT 3 - ISOCS ANALYTICAL REPORTS................................................... 24 LIST OF TABLES Table 1 - Dose Significant Radionuclides and Mixture.................................................................... 8 Table 2 - Base Case and Operational DCGLs .................................................................................. 9 Table 3 - Surrogate Ratios .............................................................................................................. 11 Table 4 - Investigation Levels ........................................................................................................ 12 Table 5 - Synopsis of Survey Design ............................................................................................. 13 Table 6 - Unit 1 Tendon Buttress Pits - Measured Concentrations of ROC for FSS ..................... 15 Table 7 - Unit 1 Buttress Pits- Statistical Quantities ...................................................................... 15

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable BcDCGL Base Case Derived Concentration Guideline Level DQA Data Quality Assessment DQO Data Quality Objective DCGL Derived Concentration Guideline Level FSS Final Status Survey HTD Hard-to-Detect IC Insignificant Contributor LTP License Termination Plan MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual OpDCGL Operational Derived Concentration Guideline Level OpSOF Operational Sum of Fractions QAPP Quality Assurance Project Plan QC Quality Control ROC Radionuclides of Concern SOF Sum of Fractions UCL Upper Confidence Level ZNPS Zion Nuclear Power Station ZSRP Zion Station Restoration Project

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107

1. EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey unit 06107, Unit 1 Tendon Buttress Pits has been generated for the Zion Station Restoration Project (ZSRP) in accordance with ZionSolutions procedure ZS-LT-300-001-005, Final Status Survey Data Reporting (Reference 1) and satisfies the requirements of Section 5.11 of the Zion Station Restoration Project License Termination Plan (LTP) (Reference 2).

The FSS Sample Plan B3-06107AF was developed in accordance with ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development (Reference 3) the ZSRP LTP, and guidance from NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) (Reference 4).

In April of 2016, an FSS was conducted on the Turbine Building basement structure. The sample plan design for the FSS of the Turbine Building did not include the surface area of the Unit 1 and Unit 2 Tendon Buttress Pits. A separate sample plan was written to include seven (7) additional judgmental measurements to represent the surface area of each of the Tendon Buttress Pits. The result of each ISOCS measurement will be added as per the LTP Chapter 5, section 5.5.6.1.

Final Status Survey was performed in the Unit 1 Tendon Buttress Pits to demonstrate that the concentrations of residual radioactivity were equal to or below site-specific Derived Concentration Guideline Levels (DCGL) corresponding to the dose criterion in 10 CFR 20.1402. The Unit 1 Tendon Buttress Pits have a MARSSIM Classification of 3.

Both the Type I () and Type II () decision rates were set at 0.05. The Canberra In situ Object Counting System (ISOCS) was selected as the primary instrument used to perform FSS. The Tendon Buttress Pits were surveyed as biased areas using judgmental locations.

The result of the judgmental measurements was added to the systematic mean of the Turbine Building basement survey. Seven (7) judgmental ISOCS measurements with a Field-of-View (FOV) of 28 m2 were originally designed for each Buttress Pit floor with the possibility of 1 additional measurement taken on the wall if accessible. After the engineer walk down and visual inspection, it was decided to revise the original Circular Plane geometry to the Room geometry, which decreased the FOV from 28 m2 to 18.7 m2. See ZionSolutions TSD 14-022 Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures (Reference 5). Based on the new FOV of 18.70 m2 for each judgmental ISOCS measurement, the total surface area coverage for the measurements equated to 130 m2 or approximately 9% of the total surface area of the Unit 1 Tendon Buttress Pits.

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 The results from each judgmental ISOCS measurement taken in the Unit 1 Tendon Buttress Pits indicate a Sum of Fractions (SOF), considering the concentration of all applicable Radionuclides of Concern (ROC), either by direct measurement or by inference, that is less than 0.1 when applying the respective Operational DCGLs (OpDCGL) for the Turbine Building Basement from ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey (Reference 6). Therefore, the null hypothesis is rejected, and the Unit 1 Tendon Buttress Pit survey unit is acceptable for unrestricted release.

2. SURVEY UNIT DESCRIPTION The Tendon Buttress Pits are bound by the interior surface of the structure from 591 foot elevation down to the 565 foot elevation. The survey unit consists of the Containment concrete exterior and buttress, tendon steel end caps protruding from the buttress faces, perimeter walls and the wall dividing the Tendon Buttress Pits into chambers. The Tendon Buttress Pits are 26 feet deep and 4 feet wide with angled side walls which limits access. There are six entrances (see Attachment 1). In the end-state condition, the portions of the structures above the 588 foot elevation will be removed and disposed of as waste. The remaining void below the 588 foot elevation will be backfilled with a combination of clean demolition debris and clean fill.

3. CLASSIFICATION BASIS The Turbine Building basement survey unit 06100 was classified in accordance with ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification (Reference 7). The Tendon Buttress Pits were not included in the original sample plan, #B3-06100AS, but are part of the Turbine Building survey unit.

Based on information from the Zion Station Historical Site Assessment (HSA)

(Reference 8), the initial classification for Turbine Building basement 06100 survey unit was Class 3. Although the Unit 1 Tendon Buttress Pits were inaccessible during site characterization in 2013, the results of environmental monitoring of radiological effluents indicate that the residual radioactivity in the Tendon Buttress Pits was minimal, supporting the classification.

4. DATA QUALITY OBJECTIVES (DQO)

Final Status Survey planning and design hinges on coherence with the 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 ZSRP LTP. The appropriate design for a given survey will be developed using the DQO process as outlined in Appendix D of MARSSIM.

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 The DQO process incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis. Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition. The baseline condition is technically known as the null hypothesis. Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection. In designing the survey plan, the underlying assumption, or null hypothesis was that residual activity in the survey unit exceeded the release criteria. Rejection of the null hypothesis would indicate that residual activity within the survey unit does not exceed the release criteria. Therefore, the survey unit would satisfy the primary objective of the FSS sample plan.

The primary objective of the FSS sample plan is to demonstrate that the level of residual radioactivity in survey unit 06107 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).

ZionSolutions TSD 11-001, Technical Support Document for Potential Radionuclides of Concern During the Decommissioning of the Zion Station (Reference 9) established the basis for an initial suite of potential ROC for the decommissioning of the Zion Nuclear Power Station (ZNPS). LTP Chapter 2 provides detailed characterization data that described contamination levels in the basements. The survey data for this basement is based on core samples obtained at biased locations with elevated contact dose rates and/or evidence of leaks/spills and analyzed for the presence of plant-derived radionuclides.

ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms (Reference 10) evaluates the results of the concrete core analysis data from the Containments and Auxiliary Building and refines the initial suite of potential ROC by evaluating the dose significance of each radionuclide.

License Termination Plan Chapter 6, section 6.5.2 discusses the process used to derive the ROC for the decommissioning of ZNPS, including the elimination of insignificant dose contributors (IC) from the initial suite. LTP section 6.5.2 also states that the Auxiliary Building basement ROC and the IC percentage of 5% for adjusting ROC DCGLs will also be applied to all other basements with the exception of the Containments. This includes the Turbine Building basement survey unit. Table 1 presents the ROC from the Auxiliary Building basement structural surfaces and the normalized fractions based on the radionuclide mixture.

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 Table 1 - Dose Significant Radionuclides and Mixture

% of Total Activity Radionuclide (normalized)(1)

Co-60 0.92%

Cs-134 0.01%

Cs-137 75.32%

Ni-63 23.71%

Sr-90 0.05%

(1) Based on maximum percent of total activity from Table 20 of TSD 14-019, normalized to one for the dose significant radionuclides.

A fundamental precursor to survey design is to establish a relationship between the release criteria and some measurable quantity. This is done through the development of DCGLs.

The DCGLs represent average levels of radioactivity above background levels and are presented in terms of surface or mass activity concentrations. Chapter 6 of the LTP describes in detail the modeling used to develop the DCGLs for structures.

The End State basements will be comprised of steel and/or concrete structures which will be covered by at least three feet of clean soil and physically altered to a condition which would not realistically allow the remaining structures, if excavated, to be occupied. The exposure pathways in the BFM are associated with residual radioactivity in floors and walls that is released through leaching into water contained in the interstitial spaces of the fill material. The BFM assumes that the inventory of residual radioactivity in a given building is released either instantly or over time by diffusion, depending on whether the activity is surficial or volumetric, respectively. The activity released into the fill water will adsorb onto the clean fill, as a function of the radionuclide-specific distribution coefficients, resulting in equilibrium concentrations between the fill and the water.

Consequently, the only potential exposure pathways after backfill, assuming the as-left geometry, are associated with the residual radioactivity in the water contained in the fill.

The final outputs of the BFM are the basement DCGLs, which are calculated using the BFM Groundwater (GW) and BFM Drilling Spoils Dose Factors (LTP Chapter 6, Tables 6-24 and 6-25). The DCGLs for basement structure surfaces are calculated separately for the GW and Drilling Spoils scenarios and for the summation of both scenarios. The summation DCGL is designated as the Base Case DCGL (BcDCGL) and is used during FSS to demonstrate compliance (analogous to the DCGLW as defined in MARSSIM). The BcDCGLs are radionuclide-specific concentrations that represent the 10 CFR 20.1402 dose criterion of 25 mrem/yr and are calculated for each ROC and each backfilled basement.

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 When applied to structures, the DCGLs are expressed in units of activity per unit of area (pCi/m2). The unity rule is applied when there is more than one ROC. The measurement results for each singular ROC present in the mixture are compared against their respective DCGL to derive a dose fraction.

The BcDCGLs for the unrestricted release of the Turbine Building survey unit (including the Tendon Buttress Pits) are provided in Table 2. The IC dose percentage of 5% was used to adjust the Turbine Building BcDCGLs to account for the dose from the eliminated IC radionuclides.

Each radionuclide-specific BcDCGL is equivalent to the level of residual radioactivity (above background levels) that could, when considered independently, result in a TEDE of 25 mrem/yr to an AMCG. To ensure that the summation of dose from each source term is 25 mrem/yr or less after all FSS is completed, the BcDCGL is reduced based on an expected, or a priori, fraction of the 25 mrem/yr dose limit from each source term. The reduced DCGLB or Operational DCGL can be related to the BcDCGL 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 OpDCGL is then used as the DCGL for the FSS design of the survey unit (calculation of surrogate DCGLs, investigations levels, etc.). Details of the OpDCGLs derived for each dose component and the basis for the applied a priori dose fractions are provided in TSD 17-004. The OpDCGLB for FSS in the Unit 1 Tendon Buttress Pits are also provided in Table 2.

Table 2 - Base Case and Operational DCGLs Base Case Turbine Operational Turbine Radionuclide Building DCGLs Building DCGLs 2

pCi/m pCi/m2 Co-60 7.03E+07 5.98E+06 Ni-63 2.18E+09 1.85E+08 Sr-90 7.74E+05 6.58E+04 Cs-134 1.59E+07 1.35E+06 Cs-137 2.11E+07 1.79E+06 Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the OpDCGL. The Canberra ISOCS was selected as the primary instrument used to perform FSS of basement surfaces. Survey instrument response checks were required prior to issuance and after the instrument had been used.

Control and accountability of survey instruments was required to assure the quality and prevent the loss of data.

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. The actual recorded value was used as the recorded FSS result for measurement and/or sample values that are less than MDC. Negative values were recorded as zero. For radionuclides less than MDC, the value representing the highest abundance was selected. Results were not reported as less than 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 OpDCGL were preferable while MDCs up to 50% of the OpDCGL were acceptable. The maximum acceptable MDC for measurements obtained using field instruments was 50% of the applicable OpDCGL.

5. SURVEY DESIGN The level of effort associated with planning a survey is based on the complexity of the survey and nature of the hazards. Guidance for preparing FSS plans is provided in procedure ZS-LT-300-001-001. The procedure states that the FSS of a Class 3 survey unit shall have between 1% and 10% areal scan coverage. Due to safety concerns identified by a walkdown of the Tendon Buttress Pits, an areal coverage of 5% was selected. The ISOCS Room geometry was selected in accordance with TSD 14-022 and the original FOV of 28 m2 was adjusted to a box FOV of 18.70 m2 for total surface scan area of approximately 130 m2.

Sample size determination for the FSS of the Turbine Building basement is addressed in LTP Chapter 5, section 5.5.2.2. The surface areas of the Tendon Buttress Pits were not included in the surface area that was surveyed as the Turbine Building basement.

Consequently, the source term from biased judgmental FSS results from the surfaces of the Tendon Buttress Pits will be added to the Turbine Building basement. This is addressed in LTP Chapter 5, Table 5-22. The FSS data taken in the Turbine Building basement passed the Sign Test. The mean dose contribution for the Turbine Building basement is then calculated using the mean concentrations from the FSS of the Turbine Building basement walls and floors plus the mean of the judgmental samples taken in other portions of the Turbine Building basement survey unit (e.g., the Circulating Water Intake Pipe, the Circulating Water Discharge Pipe and the Buttress Pits/Tendon Tunnels) on an area-weighted basis. The total basement area used in the weighted average calculation is the adjusted surface area used to calculate the DCGLs in LTP Chapter 6, section 6.6.8. The adjusted area for the Turbine Building basement from LTP Chapter 5, Table 5-23 is 27,135 m2. In accordance with TSD 14-014, End State Surface Areas, Volumes, and Source Terms of Ancillary Buildings (Reference 11), the total surface area of one Tendon

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 Buttress Pit is 2,863 ft2 or 266 m2. The total surface area of all six Unit 1 Tendon Buttress Pits is 1,596 m2.

The area-weighted SOF is calculated in accordance with LTP Chapter 5, Equation 5-8, which is reproduced as follows. The SOFBi,B variable in the equation is based on the mean of the judgmental samples.

Equation 1

, = ,

=1 where:

SOFB,B = total surface SOF including all surface survey units in basement (B)

SASUi,B = surface area of survey unit (i) in basement (B)

SAAdjust,B = adjusted surface area for DCGL calculation (Table 5-23) for basement (B)

SOFBi,B = SOFB for survey unit (i) in basement (B)

This sample plan for the Unit 1 Tendon Buttress pits consisted of 7 judgmental locations, one on the floor of each Buttress Pit and one on the wall. Attachment 1, Figures and Maps, illustrates the locations of the ISOCS measurements taken.

The DQO process determined that Co-60, Ni-63, Sr-90, Cs-134, Cs-137 would be the ROC in survey unit 06107. During FSS, concentrations for Hard-to-Detect (HTD) ROC Ni-63 and Sr-90 are inferred using a surrogate approach specified in LTP section 5.2.11.

Cs-137 is the principle surrogate radionuclide for Sr-90 and Co-60 is the principle surrogate radionuclide for Ni-63. The mean, maximum and 95% Upper Confidence Level (UCL) of the surrogate ratios for concrete core samples taken in the Auxiliary Building basement were calculated in TSD 14-019 and are presented in LTP Chapter 5, Table 5-15, which is reproduced in Table 3 below.

Table 3 - Surrogate Ratios Auxiliary Building Ratios Mean Max 95%UCL Ni-63/Co-60 44.143 180.450 154.632 Sr-90/Cs-137 0.001 0.002 0.002 For the FSS of survey unit 06107, the surrogate OpDCGLs for Co-60 and Cs-137 are based on the maximum ratios from Table 3. The equation for calculating a surrogate DCGL is as follows:

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 Equation 2 1

=

1 2 3

+ + +

2 3 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide Using the OpDCGLs for the Turbine Building basement presented in Table 2 and the maximum ratios from Table 3, the following surrogate calculations were performed for FSS unit 06107; Equation 3 1

(137) = = 1.70 + 06 /2 1 0.002

+

1.79 + 06(137) 6.58 + 04(90)

The surrogate OpDCGL that was used for Cs-137 in FSS unit 06107 for direct comparison of measurement results to demonstrate compliance is 1.70E+06 pCi/m2.

Equation 4 1

(60) = = 8.75 + 05 /2 1 180.45

+

5.98 + 06(60) 1.85 + 08(63)

The surrogate OpDCGL that was used for Co-60 in FSS unit 06107 for direct comparison of measurement results to demonstrate compliance is 8.75E+05 pCi/m2.

For this Class 3 basement structure survey units the Investigation Levels for ISOCS measurement results are those levels specified in LTP Chapter 5, Table 5-25 and are reproduced below in Table 4.

Table 4 - Investigation Levels Direct Investigation Classification Levels Class 3 >0.5 Operational DCGL In compliance with ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS) (QAPP) (Reference 12), replicate measurements were performed on 5% of the static measurement locations.

Table 5 provides a synopsis of the survey design for survey unit 06107.

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 Table 5 - Synopsis of Survey Design Feature Design Criteria Basis Survey Unit Surface 1,596 m2 TSD 14-014, Table 63 Area Number of Static 7 judgmental measurements w/ FOV of ZS-LT-300-001-001, Measurements 18.70 m2 for 8% areal coverage Attachment 4 Measurement 1 measurement on the floor of each ZS-LT-300-001-001, Spacing buttress pit Attachment 4

• Co 5.98E+06 pCi/m2

• Cs-134 - 1.35E+06 pCi/m2 Operational DCGLs for Turbine DCGLs

• Cs-137 - 1.79E+06 pCi/m2 Building

• Ni 1.85E+08 pCi/m2 (LTP Chapter 5, Table 5-4)

• Sr 6.58E+04 pCi/m2 Measurement

>0.5 Operational DCGL (LTP Chapter 5, Table 5-25)

Investigation Level Survey Area ZS-LT-300-001-001, 130 m2 for ~8% surface coverage Coverage Attachment 4 Quality Control 5% Duplicate ISOCS Measurements (LTP Chapter 5, section 5.9)

6. SURVEY IMPLEMENTATION A walk down was performed by FSS personnel on May 22, 2018. Access into the Tendon Buttress Pits was via a set of ladders. The surfaces were very slippery due to the presence of water and tendon grease. Due to safety concerns pertaining to safe personnel access, no turnover surveys were performed prior to accepting the Unit 1 Tendon Buttress Pits for FSS.

Field Logs (ZS-LT-300-001-001 Attachment 14) were used to document field activities and other information pertaining to the performance of the FSS. Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job.

ZionSolutions TSD 14-022 provides the initial justification for the selection of reasonably conservative geometries for efficiency calibrations for the ISOCS based on the physical conditions and distribution of activity. All ISOCS measurements were acquired using approved geometries.

The ISOCS detector was positioned vertical to the floor surface at the center-point of each selected measurement location. The Room geometry utilizes a 180 degree FOV

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 (collimator removed) and the measurement location is at the top center of the room.

This orientation corresponded to a nominal FOV of 18.70 m2.

The measured activity for each gamma-emitting ROC (and any other gamma-emitting radionuclide that was positively detected by ISOCS) was recorded (in units of pCi/m2).

Background was not subtracted from any measurement. A SOF calculation was performed for each measurement by dividing the reported concentration of each ROC by the OpDCGL for each ROC to derive an individual ROC fraction. The individual Operational SOF (OpSOF) were then summed to provide a total OpSOF value for the measurement.

For the 7 judgmental measurements taken in survey unit 06107, compliance with the unrestricted release criteria was demonstrated by direct comparison of the ISOCS measurement results to their respective OpDCGL.

One (1) duplicate measurement was taken with the ISOCS in the fifth Tendon Buttress Pit (designated as Grid #5). This location was randomly selected using the Microsoft Excel RANDBETWEEN function. The number of replicate measurements satisfies the requirement that a minimum of 5% percent of the number of measurements that will be used for non-parametric statistical testing be selected for additional Quality Control (QC) evaluation.

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

The application of the unity rule served to normalize the data to allow for an accurate comparison of the results from the 7 judgmental measurements to the release criteria.

When the unity rule was applied, the DCGLW (used for the nonparametric statistical test) becomes one. The BcDCGLB 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 previously stated, as the extent of this survey was the acquisition of judgmental measurements at biased locations, compliance was demonstrated by direct comparison of each measurement result to the release criterion. For building surfaces, areas of elevated activity were defined as any area identified by measurement (systematic or judgmental) that exceeded the OpDCGL but was less than the BcDCGL. Any area that exceeded the BcDCGL would have required remediation. This was not the case for the FSS of the Unit 1 Tendon Buttress Pits, as all measurements taken, when compared against the OpDCGL, was less than an OpSOF of one. The ISOCS measured concentration results from the Unit

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 1 Tendon Buttress Pits are listed in Table 6. Table 7 presents the mean concentration of the judgmental measurements and BcSOF when compared against BcDCGL.

Table 6 - Unit 1 Tendon Buttress Pits - Measured Concentrations of ROC for FSS Co-60 Ni-63(1) Sr-90(1) Cs-134 Cs-137 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B3-06107A-FJFC-001-GD 1.66E+03 3.00E+05 8.44E+00 1.42E+03 4.22E+03 0.005 B3-06107A-FJFC-002-GD 4.24E+03 7.65E+05 1.60E+01 1.93E+03 8.02E+03 0.011 B3-06107A-FJFC-003-GD 1.09E+04 1.97E+06 5.84E+01 5.29E+03 2.92E+04 0.034 B3-06107A-FJFC-004-GD 2.80E+03 5.05E+05 6.76E+00 1.34E+03 3.38E+03 0.006 B3-06107A-FJFC-005-GD 7.88E+03 1.42E+06 6.06E+00 0.00E+00 3.03E+03 0.011 B3-06107A-FJFC-006-GD 1.18E+03 2.13E+05 0.00E+00 0.00E+00 0.00E+00 0.001 B3-06107A-FJWC-007-GD 5.96E+03 1.08E+06 1.65E+00 1.29E+02 8.24E+02 0.007 (1) Inferred concentration Table 7 - Unit 1 Tendon Buttress Pits - Judgmental Measurement Population INDIVIDUAL MEASUREMENT METRICS Total Number of Judgmental Measurements = 7 Number of Quality Control Measurements = 1 Total Number of Measurements = 8 Mean Judgmental OpSOF = 0.011 Max Individual Judgmental Measurement OpSOF = 0.034 Number of Judgmental Measurements with OpSOF >1 = 0 STATISTICAL QUANTITIES Standard Avg.

Mean Median Max Min BcDCGL Avg. Dose ROC Deviation BcSOF per ROC per ROC (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

Co-60 4.95E+03 4.24E+03 1.09E+04 1.18E+03 3.54E+03 7.03E+07 0.000 0.002 Ni-63 8.92E+05 7.65E+05 1.97E+06 2.13E+05 6.39E+05 2.18E+09 0.000 0.010 Sr-90 1.39E+01 6.76E+00 5.84E+01 0.00E+00 2.03E+01 7.74E+05 0.000 0.000 Cs-134 1.44E+03 1.34E+03 5.29E+03 0.00E+00 1.87E+03 1.59E+07 0.000 0.002 Cs-137 6.95E+03 3.38E+03 2.92E+04 0.00E+00 1.01E+04 2.11E+07 0.000 0.008 Mean BcSOF for Survey Unit = 0.001 Dose (based on Mean BcSOF) = 0.023 mrem/yr

8. QUALITY CONTROL The implementation of required QC measures included the collection of 1 additional ISOCS measurements in survey unit 06107 for replicate measurement analysis. The ISOCS gamma spectroscopy reports for the replicate measurements are presented in

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FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 Attachment 3. The replicate ISOCS measurement met the required acceptance criteria.

The completed Replicate Sample Assessment Form is included in Attachment 2 of this Release Record.

9. INVESTIGATIONS AND RESULTS No measurements were taken for an investigation during the performance of FSS in this survey unit.

10. REMEDIATION AND RESULTS No remediation was performed in this survey unit.

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

12. DATA QUALITY ASSESSMENT (DQA)

In accordance with procedure ZS-LT-300-001-004, the DQOs, sample design, and data were reviewed for completeness, accuracy, and consistency. Documentation was complete and legible. The FSS unit was properly classified as Class 3. All measurement results were individually reviewed and validated. The FOV for the number of measurements taken was sufficient to meet the requirement of 5% areal coverage of surfaces for a Class 3 survey unit. The instrumentation used to perform the FSS were in calibration, capable of detecting the activity with an adequate MDC and successfully response checked prior to and following use. An adequate number of replicate measurements were taken and the results meet the acceptance criteria as specified in the QAPP.

The analytical results of the 7 judgmental measurements were less than an OpSOF of one.

The preliminary data review consisted of calculating basic statistical quantities (e.g.,

mean, median, standard deviation). All data was considered valid and the values reported below the MDC, and values with uncertainties that exceeded two standard deviations.

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

14. CONCLUSION Seven (7) judgmental measurements were taken, one in each of the Unit 1 Tendon Buttress Pits. The FOV of each measurement included the floor and three walls. The total surface area of all of the Unit 1 Tendon Buttress Pits is 1,596 m2. The FOV for the box Room geometry used for the ISOCS measurement was 18.70 m2, which equated to an areal

[16]

FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 coverage of 130 m2 or 7% of the surface area of the Buttress Pits. The requirements for a Class 3 survey unit have been met.

All of the measurements were below an OpSOF of 0.5. The average BcSOF for the survey unit was 0.001. The calculated dose from the mean ROC concentrations detected by these judgmental measurements is 0.023 mrem/yr.

The conclusion of this Release Record is that when the seven judgmental measurement results from the Unit 1 Tendon Buttress Pits are added to the mean of the Turbine Building basement FSS results, the Turbine Building basement survey unit will pass FSS.

15. REFERENCES

1. ZionSolutions Procedure ZS-LT-300-001-005, Final Status Survey Data Reporting

2. Zion Station Restoration Project License Termination Plan

3. ZionSolutions Procedure ZS-LT-300-001-001, Final Status Survey Package Development

4. NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual

5. ZionSolutions TSD 14-022 Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures

6. ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey

7. ZionSolutions Procedure ZS-LT-300-001-002, Survey Unit Classification

8. Zion Station Historical Site Assessment

9. ZionSolutions TSD 11-001, Technical Support Document for Potential Radionuclides of Concern During the Decommissioning of the Zion Station

10. ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms

11. ZionSolutions TSD 14-014, End State Surface Areas, Volumes, and Source Terms of Ancillary Buildings

12. ZionSolutions ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS)

[17]

FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107

16. ATTACHMENTS Attachment 1 - Figure and Maps Attachment 2 - QC Data Attachment 3 - ISOCS Analytical Reports

[18]

ATTACHMENT 1 - FIGURES AND MAPS

[19]

FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107

[20]

FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107

[21]

ATTACHMENT 2 - QC DATA

[22]

FSS RELEASE RECORD UNIT 1 TENDON BUTTRESS PITS SURVEY UNIT 06107 UNIT 1 Tendon Buttress Pits- QC Agreement Replicate Measurement Assessment Survey Unit # 06000 Survey Unit Name Unit 1 Buttress Pits Sample Plan # B3-06107A-F Sample

Description:

Comparison of systematic and QC ISOCS measurements of concrete floor at GRID #5. The standard measurement is ID as B3-06107A-FJFC-005-GD. The comparison measurement is ID as B3-06107A-FQFC-005-GD STANDARD COMPARISON Radionuclide Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (Y/N)

(pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

K-40 7.03E+05 9.68E+04 7 0.5-2.0 7.09E+05 9.63E+04 1.0 Y Comments/Corrective Actions: There was acceptable The acceptance criterion for replicate static agreement between the standard measurement and the measurements is as per the following Table.

replicate measurement. Based on the professional judgment of the Radiological Engineer, the same conclusion was reached for each measurement. No further action is necessary.

[23]

ATTACHMENT 3 - ISOCS ANALYTICAL REPORTS

[24]

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

Filename: C:\Users\kevin\Desktop\Buttress\00005016. CNF Report Generated On 6/12/2018 1:10 : 24 PM Sample Title B306107AFJFC001GD Sample Description U-1 2B BUTTRESS PIT (NORTH)

Sample Identification 001 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 8!:i - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.870E+001 M"'2 Sample Taken On 6/8/2018 3:14: 00 PM Acquisition started 6/8/2018 3:14:43 PM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0.08 %

Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 6/12/2018 Efficiency ID BUTTRESS PIT A

[25]

Peak Analysis Report 6/12/2018 1:10:24 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B306107AFJFC001GD Peak Analysis Performed on: 6/12/2018 1:10:24 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 285- 305 300.45 75 .11 0.78 3.51E+002 113.26 7.87E+002 2 947- 959 954.75 238.69 0.73 1.18E+002 44.80 1. 46E+002 3 1174 - 1190 1181.20 295.30 0.84 1.12E+002 41.95 1.0SE+002 4 1398 - 1414 1407.30 351.82 0.65 l.29E+002 38.33 7.63E+001 5 2324 - 2336 2330.55 582.64 1. 06 4.88E+001 22.45 2.92E+001 6 2424 - 2443 2434.85 608.71 1. 08 1.70E+002 34.29 3.52E+001 7 2639- 2652 2644.27 661.07 0.32 3.05E+001 17 .71 1.SSE+OOl 8 3065- 3076 3070.37 767.59 0.89 1.90E+001 17.25 2.20E+001 9 3635- 3649 3641.54 910.39 0.61 5.45E+001 21.84 2.25E+001 10 3867- 3880 3873.65 968. 41 0.69 2.18E+001 16.63 1. 72E+001 11 4471- 4486 4477.95 1119.49 0 .55 4.87E+001 19.30 1 .43E+001 12 5322- 5335 5328.03 1332.01 0 .31 1.85E+001 13.88 1 .0SE+OOl 13 5828- 5852 5840.01 1460.00 1. 52 4.05E+002 41.50 6.25E+OOO 14 7047- 7064 7055.76 1763.94 1. 49 5.97E+001 16.44 2.33E+OOO M First peak in a mult iplet region m = Other peak in a mult iplet region F = Fitted singlet Errors quoted at 2.000 sigma

[26]

Interference Corrected Activity Report 6/12/2018 1 : 10 : 24 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:

B306107AFJFC001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

• * *

• t

• t I I ******** f, I

• IDENTIFIED NUCLIDES *

• A -f!

• a *

• a a

• a e t, * *

• e

• I Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0 .999 1 460.82* 10.66 7.36146E+005 9.89106E+004 Cs-137 0 .999 661.66* 85.10 4 .22983E+003 2.50441E+003 Tl-208 1 . 000 583. 19* 85.00 6.23238E+003 2.96315E+003 Pb-212 1. 000 238.63* 43.60 1 .64002E+004 6.77122E+003 Bi-214 0 .999 609.32* 45.49 4.16839E+004 9.79719E+003 1120.29* 14.92 5.3378SE+004 2.15971E+004 1764.49* 15.30 8.61491E+004 2.47164E+004 Pb-214 1 . 000 295.22* 18.42 4 .19121E+004 l .70493E+004 351.93* 35.60 2.79817E+004 9.32647E+003 Ac-228 0 .561 338.32 11. 27 911.20* 25.80 3.03999E+004 1. 25346E+004 968.97* 15.80 2.06650E+004 1.58580E+004

• - Energy line found in the spectrum.

@ ~ Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold - 0.30 Errors quoted at 2.000 sigma

[27]

Interference Corrected Activity Report 6/12/2018 1:10 : 24 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.999 7.361459E+OOS 9.891058E+004 Cs-137 0 .999 4.229828E+003 2.50441SE+003 Tl-208 1 .000 6.232382E+003 2.963152E+003 Pb-212 1 .000 1.640019E+004 6.771218E+003 Bi-214 0 .999 4.857576E+004 8.392064E+003 Pb-214 1 .000 3.119012E+004 8.182251E+003 Ac-228 0 .561 2.665652E+004 9.833623E+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

[28]

Interference Corrected Activity Report 6/12/2018 1 :10 :24 PM Page s

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

Peak Locate Performed on: 6/12/2018 1: 10 :24 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.11 5.8450E-001 32.29 8 767.59 3.1596E-002 91. 01 12 1332.01 3.0833E-002 75.03 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F "' Fitted singlet Errors quoted at 2.000 sigma

[29]

Nuclide MDA Report 6/12/2018 1: 10 :25 PM Page 6

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

Det e ctor Name: 5456-A Sample Geometry:

Sample

Title:

B306107AFJFC001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/M"2 ) (pCi/MA2 ) (pCi/M"2 )

+ K-40 1460 .82* 10.66 3.532E+004 3.53E+004 7.361E+005 1. 520 E+004 Co-60 1173 .23 99.85 7.164E+003 6.72E+003 5.975E+002 3.354E+003 1332.49 99.98 6.725E+003 1.669E+003 3.116E+003 Nb-94 702.65 99. 81 5.535E+003 5.54E+003 6.270E+003 2.601E+003 871. 09 99. 89 6.065E+003 2.822E+003 2.843E+003 Ag-108m 433.90 90.50 5.811E+003 5.81E+003 -1.834E+003 2.772E+003 614.30 89.80 9.413E+003 -3.685E+003 4.537E+003 722.90 90.80 7.254E+003 3.991E+003 3.441E+003 Cs - 134 604.72 97.62 8.921E+003 7.26E+003 1.424E+003 4.306E+003 795.86 85.46 7.256E+003 1.162E+003 3.419E+003

+ cs-137 661.66* 85. 10 3.527E+003 3.53E+003 4.230E+003 1 .576E+003 Eu-152 121. 78 28.67 2.459E+004 2.20E+004 -5.749E+003 l .208E+004 344.28 26.60 2.204E+004 -2.267E+003 1.063E+004 1408 .01 21. 07 2.817E+004 1. 016E+004 1.287E+004 Eu-154 123.07 40.40 1.761E+004 1.76E+004 l.428E+004 8.648E+003 723.30 20.06 3.257E+004 l.726E+004 1. 545E+004 1274.43 34.80 1.78DE+004 - 7.218E+003 8.212E+003 Eu-155 86.55 30.70 2.549E+004 2.55E+004 - l. 946E+003 1.254E+004 105. 31 21.10 3.521E+004 2.868E+004 1.731E+004

+ Tl-208 583.19* 85.00 4. 037E+003 4.04E+003 6.232E+003 1.846E+003 Bi-212 727.33 6.67 9.912E+004 9.91E+004 5.293E+004 4.702E+004

+ Pb-212 238.63* 43.60 9.341E+003 9.34E+003 l.640E+004 4.482E+003

+ Bi-214 609.32* 45.49 9.665E+003 9.67E+003 4.168E+004 4.501E+003 1120.29* 14. 92 2.703E+004 5.338E+004 1. 203E+004 1764 .49* 15.30 1. 724E+004 8.615E+004 6.669E+003

+ Pb-214 295.22* 18.42 2.327E+004 1 .16E+004 4.191E+004 1 .113E+004 351.93* 35.60 1. 164E+004 2.798E+004 5.524E+003 Ra-226 186.21 3.64 1. 752E+005 l .75E+005 5.533E+004 8.564E+004

+ Ac-228 338.32 11. 27 5.266E+004 1 .63E+004 -5.963E+003 2.542E+004 911. 2 O* 25.80 1. 628E+004 3.040E+004 7.384E+003 968.97* 15. 80 2.398E+004 2.066E+004 1 .071E+004 Am-241 59 .5 4 35.90 1. 842E+004 1 . 84E+004 -2 . 718E+003 9.028E+003

+ = 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

[30]

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

Filename: C:\Users\kevin\Desktop\Buttress\00004851 .CNF Report Generated on 6/12/2018 1:08:13 .PM Sample Title B306107AFJFC002GD Sample Description Ul BUTTRESS PI T 3B Sample Identification 002 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peal: Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.870E+001 MA2 Sample Taken On 5/24/2018 8:33: 00 AM Acquisition Started 5/24/2018 8:39: 11 AM Live Time 600.0 seconds Real Time 600.9 seconds Dead Time 0.15 %

Energy Calibration used Done On 3/15/2018 Efficiency Calibration Used Done On 6/12/2018 Efficiency ID BUTTRESS PIT A

[31]

Peak Analysis Report 6/12/2018 1:08:13 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B306107AFJFC002GD Peak Analysis Performed on: 6/12/2018 1:08:13 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) {keV) Area Uncert. Counts 1 126- 135 130.81 32.70 0. 88 1.01E+002 39.48 1.06E+002 2 281- 315 300.63 75.16 0. 81 4.19E+002 182.49 l.47E+003 3 945- 975 954.92 238.73 1. 26 2.86E+002 90.49 3.60E+002 4 1172- 1188 1180.13 295.03 0.84 1.01E+002 47.90 1.51E+002 5 1346- 1360 1353.06 338.27 0.64 6.08E+001 33.38 7.52E+001 6 1400- 1417 1407.57 351.89 1. 27 2.16E+002 44.91 8.86E+001 7 2035- 2046 2040.29 510.07 0.57 3.69E+001 25.63 5.0lE+OOl 8 2323- 2340 2331.83 582.96 1. 12 1 .04E+002 33.77 5.56E+001 9 2425- 2445 2436.23 609.06 1. 23 2.46E+002 41.26 4.96E+001 10 2638- 2653 2645.54 661.39 0.86 5.79E+001 24.46 3.0lE+OOl 11 3066- 3078 30 71 .83 767.96 0.60 1.13E+001 21. 66 3.77E+001 12 3633- 3653 3642.97 910.74 1. 92 7.72E+001 24.69 2.08E+001 13 3838- 3881 3874.53 968.63 0 .99 5.44E+001 44.39 6.96E+001 14 4472- 4490 4480.70 1120.18 1. 92 7.09E+001 26.20 2.91E+001 15 4686- 4699 4692.17 1173.04 0.34 2.60E+001 16.08 1.40E+001 16 4945- 4958 4951.04 1237.76 0.37 3.18E+001 18.75 2.03E+001 17 5323- 5336 5329.44 1332.36 0.56 2.25E+001 15.20 1. 25E+001 18 5831- 5854 5842.55 1460 .64 1. 61 4.66E+002 45.26 1. 16E+001 19 6911- 6926 6918.43 1729.61 0.69 1 . 7 0E+ 001 10.79 4.00E+OQO 20 7049- 7066 7058.01 1764.50 0.46 6.90E+001 16.61 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[32]

Interference Corrected Activity Report 6/12/2 018 1 : 08:13 PM Page 3

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

Sample

Title:

B306107AFJFC002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB I * * * * * *

• I'.,* * * * *""*"""

• IDENTIFIED NUCLIDES

• Ii . .. ........ .... . .. - ...

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1. 000 1460 .82* 10 .66 8.48504E+005 1.10491E+005 Co-60 1. 000 1173.23* 99.85 4.38676E+003 2.73614E+003 1332.49* 99.98 4.10460E+003 2.78890E+003 Cs-137 1. 000 661.66* 85.10 8.02677E+003 3.52229E+003 Tl-208 1. 000 583.19* 85.00 1. 333 54E+O 04 4.60238E+003 Pb-212 1. 000 238.63* 43.60 3.97626E+004 1 .41312E+004 Bi-214 1. 000 609.32* 45.49 6.05322E+004 1.24764E+004 11 20 .29* 14.92 7.78381E+004 2.94149E+004 1764.49* 15. 30 9.96491E+004 2.52854E+004 Pb-214 1 . 000 295.22* 18.42 3.77259E+004 1.88781E+004 351.93* 35.60 4 .70488E+004 1.20402E+004 Ac-228 1 . 000 338.32* 11. 27 4 .06455E+004 2.32076E+004 911.20* 25.80 4 .30803E+004 1.43962E+004 968.97* 15.80 5.15336E+004 4 .22890E+004

• =Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold ~ 0 .3 0 Errors quoted at 2. 000 sigma

[33]

Interference Corrected Activity Report 6/12/2018 1:08: 13 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 8.485039E+OOS 1 .104914E+OOS Co-60 1.000 4.248371E+003 1 .953131E+003 Cs-137 1. 000 8.026769E+003 3.522288E+003 Tl-208 1. 000 1.333543E+004 4.602382E+003 Pb-212 1. 000 3.976260E+004 1.413125E+004 Bi-214 1.000 6.941047E+004 1.045755E+004 Pb-214 1. 000 4.435305E+004 1.015132E+004 Ac-228 1. 000 4.310881E+004 1.175176E+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

[34]

Interference Corrected Activity Report 6/12/2018 1:08:13 PM Page 5

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

Peak Locate Performed on: 6/12/2018 1:08:13 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.70 1.6877E-001 38.99 2 75.16 6.9801E-001 43.57 7 510.07 6.1566E-002 69.38 11 767.96 1. 8 776E-0 02 192.29 16 1237.76 5.2917E-002 59.04 Sum 19 1729.61 2.8333E-002 63.49 Sum M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[35]

Nuclide MDA Report 6/12/2018 1:08: 13 PM Page 6

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

Detector Name: 5456-A Sample Geometry:

Sample

Title:

B306107AFJFC002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 4.538E+004 4 .54E+004 8.485E+005 2.023E+004

+ Co-60 1173.23* 99.85 3.908E+003 3.91E+003 4.387E+003 l .726E+003 1332.49* 99.98 4.051E+003 4.105E+003 1.779E+003 Nb-94 702.65 99.81 6.072E+003 5.99E+003 4.802E+003 2.870E+003 871. 09 99.89 5.990E+003 -1. 640E+003 2.805E+003 Ag-108m 433.90 90.50 6.788E+003 6.79E+003 8.166E+002 3.261E+003 614.30 89.80 1.132E+004 2.711E+003 5.492E+003 722.90 90.80 7.283E+003 3.330E+003 3.456E+003 Cs-134 604.72 97.62 1. 056E+004 7.52E+003 l.937E+003 5.125E+003 795.86 85.46 7.517E+003 4 .605E+003 3.549E+003

+ Cs-137 661. 66* 85.10 4.736E+003 4.74E+003 8.027E+003 2.181E+003 Eu-152 121. 78 28.67 2.830E+004 2.43E+004 -2.516E+004 1. 393E+004 344.28 26.60 2.430E+004 -3.804E+003 1. 176E+004 1408.01 21 .07 3.166E+004 -1 .724E+004 1. 461E+O 04 Eu-154 123.07 40.40 2.020E+004 l. 99E+004 -5.194E+003 9.942E+003 723.30 20.06 3.324E+004 2.955E+004 l. 578E+004 1274.43 34.80 l.989E+004 9.212E+003 9.257E+003 Eu-155 86.55 30.70 2.904E+004 2.90E+004 3.678E+004 1. 432E+O 04 105.31 21 .10 3.975E+004 3.422E+004 l.958E+004

+ Tl-208 583.19* 85.00 S.996E+003 6.00E+003 1.334E+004 2.825E+003 Bi-212 727.33 6.67 9.666E+004 9.67E+004 9.247E+003 4.579E+004

+ Pb-212 238.63* 43.60 1.958E+004 1.96E+004 3.976E+004 9.601E+003

+ Bi-214 609.32* 45.49 l.148E+004 3.91E+003 6.053E+004 5.409E+003 1120. 29* 14.92 3.919E+004 7.784E+004 1.811E+004 1764.49* 15.30 3.908E+003 9.965E+004 O.OOOE+OOO

+ Pb-214 295.22* 18.42 2.772E+004 l.27E+004 3.773E+004 1.335E+004 351.93* 35.60 1.273E+004 4.705E+004 6.069E+003 Ra-226 186.21 3.64 2.139E+005 2.14E+005 2.945E+OOS 1.0SOE+OOS

+ Ac-228 338.32* 11. 27 3.428E+004 l.74E+004 4.065E+004 1.624E+004 911. 2 O* 25.80 l.743E+004 4.308E+004 7.959E+003 968.97* 15.80 6.775E+004 5.153E+004 3.260E+004 Am-241 5 9. 54 35.90 2.219E+004 2.22E+004 5.370E+002 1.091E+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

[36]

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

Filename: C:\Users\kevin\Desktop\Buttress\00004847.CNF Report Generated On 6/16/2018 1:54:47 PM Sample Title B306107AFJFC003GD Sample Description Ul BUTTRESS PI T 4A Sample Identification 003 Sample Type GAMMA DIRECT Sample Geometry Buttress Pit Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 5/23/2018 1:52 :00 PM Acquisition Started 5/23/2018 1:58:25 PM Live Time 600.0 seconds Real Time 600.6 seconds Dead Time 0 . 10 %

Energy Calibration Used Done On 3/15/2018 Efficiency Calibration used Done On 6/12/2018 Efficiency ID BUTTRESS PIT A

[37]

Peak Analysis Report 6/16/2018 1:54:47 PM Page 2

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

Detector Name: 5 4 56-A Sample

Title:

B306107AFJFC003GD Peak Analysis Performed on: 6/16/2018 1: 54 :46 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 138 131.85 32.96 0.99 1.11E+002 42.25 1.11E+002 2 285- 306 301 .18 75. 30 0.97 2.86E+002 123.06 9.33E+002 3 346- 355 350.56 87. 64 0.32 1.36E+001 62.20 4.21E+002 4 950- 966 956.49 239.12 0.64 1.02E+002 63.94 2.88E+002 5 1172- 1190 1182.31 295.58 0.91 1.06E+002 46.81 1.31E+002 6 1348- 1361 1354.24 338.56 0.33 2.81E+001 31.53 7.99E+001 7 1401- 1419 1409.45 352.36 0.81 1.85E+002 46.95 1.08E+002 8 2327- 2341 2335.48 583.87 1.12 6.71E+001 25.74 3.39E+001 9 2432- 2448 2439.78 609.95 1. 60 l.68E+002 34.93 4.40E+001 10 2638- 2659 26 49 .25 662.31 0.74 2.11E+002 34.24 2.19E+001 11 3072- 3084 3077.65 769.41 0.30 2.59E+001 16.26 1 .51E+001 12 3641- 3655 36 4 7 .94 911 .99 1. 59 6.67E+001 23.90 2.63E+001 13 3874- 3887 3880.75 970.19 0.82 3.15E+001 19.37 2.25E+001 14 4478- 4493 4485.78 1121 .45 0.63 4.90E+001 20.30 1.80E+001 15 4688- 4705 4697.12 1174 .28 1. 35 5.76E+001 23.49 2.44E+001 16 5327- 5344 5335.85 1333.96 0.40 6.52E+001 18.70 6.79E+OOO 17 5631- 5644 5637.65 1409.41 0.51 1.18E+001 10.22 5.16E+OOO 18 5839- 5863 5851.15 1462.79 1.19 4.13E+002 41. 31 3.25E+OOO 19 7060- 7075 7067.96 1766.99 1. 02 5.00E+OOl 17.23 7.98E+OOO M = First peak in a mul tiplet region m = Other peak in a mul tiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

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Interference Corrected Activity Report 6/16/2 018 1:54:47 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:

B306107AFJFC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

• * * * * * *

• t, I * * * * * * * .. *

• IDENTIFIED NUCLIDES * * * * * * * * * * * * *

• r

• III

• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 0.994 1460 .82* 10 .66 7.51678E+OOS 9.96002E+004 Co-60 0.997 11 73.23* 99.85 9.71704E+003 4.04186E+003 1332.49* 99.98 1 .18939E+004 3.54181E+003 Cs-137 0.999 661.66* 85. 10 2.92693E+004 5.90720E+003 Eu-155 0.347 86.55* 30.70 2.02055E+003 9.23840E+003 1 05.31 21. 10 Tl-208 0.999 583.19* 85. 00 8.57559E+003 3.44951E+003 Pb-212 1. 000 238.63* 43.60 1.41860E+004 9.19270E+003 Bi-214 0.997 609.32* 45.49 4.13087E+004 9.92062E+003 1120.29* 14.92 5.38108E+004 2.27042E+004 1764.49* 15.30 7.23047E+004 2.55754E+004 Pb-214 1.000 295.22* 18.42 3.97459E+004 1. 861 76E+O 04 351.93* 35.60 4.02250E+004 1.18588E+004 Ac-228 0 .999 338.32* 11. 27 1. 88102E+004 2.12999E+004 911. 20* 25.80 3.72180E+004 1.38241E+004 968.97* 15.80 2.98483E+004 1.85626E+004

• ~ Energy line found in the spectrum.

@ ~ Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold ~ 0 .30 Errors quoted at 2. 000 sigma

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Interference Corrected Activity Report 6/16/2018 1:54:47 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.994 7.516776E+005 9.960015E+004 Co-60 0.997 1. 094839E+004 2.663791E+003 Cs-137 0.999 2.926929E+004 5.907202E+003 Eu-155 0.347 2.020546E+003 9.238400E+003 Tl-208 0.999 8.575587E+003 3.449507E+003 Pb-212 1.000 1.418600E+004 9.192697E+003 Bi-214 0.997 4.656500E+004 8.565672E+003 Pb-214 1.000 4.008672E+004 1. 000206E+004 Ac-228 0.999 3.122496E+004 9.834675E+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

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

Peak Locate Performed on: 6/16/2018 1:54:46 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.96 1.8452E-001 38. 17 2 75.30 4.7700E-001 43. 00 11 769.41 4.3181E-002 62.76 17 1409.41 l.9730E-002 86.36 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F "' Fitted singlet Errors quoted at 2.000 sigma

[41]

Nuclide MDA Report 6/16/2018 1 :54 :47 PM Page 6

• • • • • N U C L I D E MD A REPORT ****

• Detector Name: 5456-A Sample Geometry: Buttress Pit Sample

Title:

B306107AFJFC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 2.724E+004 2. 7 2E+004 7.517E+005 l .116E+D04

+ Co-60 1173.23* 99.85 5.438E+003 3.32E+003 9.717E+003 2.491E+003 1332.49* 99.98 3.324E+OD3 l .189E+004 1.415E+D03 Nb- 94 702.65 99. 81 5.780E+003 S.78E+003 2.592E+003 2.724E+D03 871.09 99.89 6.102E+003 3.336E+003 2.861E+003 Ag- 108m 433.90 90.50 6.608E+D03 6.61E+003 2.067E+003 3.171E+003 614.30 89.80 9.992E+003 -3.816E+OD3 4.827E+003 722.90 90.80 6.729E+003 -5.629E+OD2 3.179E+003 Cs-134 604.72 97.62 9.443E+D03 7.48E+D03 -1.195E+003 4.567E+003 795.86 85.46 7.481E+003 5.298E+003 3.531E+003

+ Cs-137 661.66* 85. 10 4.506E+003 4 .51E+003 2.927E+OD4 2.066E+003 Eu-152 121.78 28.67 2.692E+D04 2.33E+004 1 .185E+004 1.324E+004 344.28 26.60 2.330E+004 -8.29SE+003 1.126E+004 1408.01 21.07 3.075E+004 -1.414E+003 1.416E+004 Eu-154 123.07 40.40 1. 898E+OD4 l .73E+004 3.756E+003 9.331E+D03 723.30 20.06 3.133E+OD4 3. 1*23E+004 1.482E+004 1274 . 43 34.80 1. 728E+004 l.461E+004 7.951E+003

+ Eu-155 86.55* 30.70 1.548E+OD4 1 .55E+D04 2.021E+003 7.538E+OD3 105. 31 21.10 3.718E+OD4 -2.215E+D04 1. 830E+004

+ Tl-208 583.19* 85.00 4.524E+003 4.52E+003 8.576E+003 2.089E+003 Bi-212 727.33 6.67 9.283E+004 9.28E+D04 -2.132E+004 4.38BE+004

+ Pb-212 238.63* 43.60 1 .427E+004 1.43E+004 1 .419E+D04 6.947E+D03

+ Bi-214 609.32* 45.49 1 .013E+004 1. 01E+004 4.131E+004 4.73SE+003 112 0 . 29* 14.92 2.952E+004 5.381E+D04 l. 328E+OD4 1764.49* 15.30 2.732E+004 7.230E+004 1. 170E+004

+ Pb-214 295.22* 18.42 2.68SE+004 1.43E+004 3.975E+OD4 1. 292E+D04 351.93* 35.60 1 .429E+004 4.D22E+004 6.852E+D03 Ra-226 186.21 3.64 1 .977E+OOS 1. 98E+005 1.126E+OOS 9.688E+004

+ Ac-228 338.32* 11. 27 3.449E+004 1. 75E+004 1. 881E+004 1.634E+004 911. 20* 25.80 1 .754E+004 3.722E+004 8.016E+D03 968.97* 15.80 2.718E+004 2.985E+004 1. 231E+004 Am-241 59.54 35.90 2.019E+004 2.02E+004 -1. 224E+004 9.916E+D03

+=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

[42]

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

Filename: C:\Users\kevin\Desktop\Buttress\00004858.CNF Report Generated On 6/16/2018 1:55:39 PM Sample Title B306107AFJFC004GD Sample Description Ul BUTTRESS PIT SA Sample Identification 004 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 5/28/2018 9:56:00 AM Acquisition Started 5/29/2018 9:59:06 AM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0 . 08 %

Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 6/12/2018 Efficiency ID BUTTRESS PIT A

[43]

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Detector Name: 5456-A Sample

Title:

B306107AFJFC004GD Peak Analysis Performed on: 6/16/2018 1 :55:38 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 138 129.63 32.41 0 .88 7.94E+001 36. 64 8.36E+001 2 296- 306 301.09 75.27 1. 02 7.62E+001 74.94 5.57E+002 3 334- 345 3 40 .34 85.09 0.86 8. llE+ OOl 69. 02 4.41E+002 4 463- 473 467.60 116.90 0.69 7.22E+001 55.79 2.95E+002 5 950- 979 955.56 238.89 0.83 1.93E+002 81.23 3.0SE+002 6 1037- 1047 1042.99 260.75 0.70 2.69E+001 28.99 7.61E+001 7 1174- 1189 1181.36 295.34 1. 11 1.15E+002 41. 36 1.04E+002 8 1399- 1416 1407.90 351.98 1.27 1.60E+002 42.53 8.98E+001 9 2036- 2051 2042. 51 510 .63 0.42 6.75E+001 27.03 3.45E+001 10 2327- 2341 2333.39 583.35 1.44 7.llE+OOl 26.97 3.79E+001 11 2427- 2445 2436.28 609. 07 1.33 2.20E+002 36.44 3.33E+001 12 2641- 2653 2646.75 661.69 0 .30 2.45E+001 17.74 2.05E+001 13 3636- 3652 3644.44 911.11 0 .89 6.19E+001 20. 61 1.31E+001 14 3729- 3742 3735.82 933.95 0 .83 1.53E+001 14.58 1.37E+001 15 3869- 3883 3875.29 968.82 0 .96 4.38E+001 17.47 1.13E+001 16 4474- 4487 4480.06 1120.01 0 .77 2.83E+001 16.92 1.47E+001 17 5832- 5857 5843.73 1460.93 1. 56 4.31E+002 42.82 6.SOE+OOO 18 7052- 7069 7060.72 1765.18 0 .70 6.69E+001 17 .16 2.12E+OOO M ~ First peak in a multiplet region m ~ Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

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Interference Corrected Activity Report 6/16/2018 1:55:39 PM Page 3

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Sample

Title:

B306107AFJFC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

• I * * * * * * "' * * * * * * * * * *

• IDENTIFIED NUCLIDES ., * ., * * * * * * * * * * * ~ ., * ., ~ r Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1. 000 1460.82* 10.66 7.83323E+OOS 1.03423E+005 Cs-137 1. 000 661.66* 85.10 3.38822E+003 2.49198E+003 Eu-152 0.674 121.78* 28.67 1. 16964E+O 04 9.3340SE+003 344.28* 26.60 4.66360E+004 1 .43185E+004 1408.01 21.07 Eu-155 0.346 86.55* 30.70 1. 20570E+004 1 .05407E+004 1 05.31 21.10 Tl-208 1. 000 583.19* 85.00 9.08658E+003 3.61589E+003 Pb-212 1.000 238.63* 43.60 2.67950E+004 1.21034E+004 Bi-214 1.000 609.32* 45.49 5.39753E+004 1.10550E+004 1120.29* 14.92 3.11027E+004 1.87248E+004 1764.49* 15.30 9.66085E+004 2.59657E+004 Pb-214 1.000 295.22* 18.42 4.29962E+004 1.69150E+004 351.93* 35.60 3.48412E+004 1.06175E+004 Ac-228 0. 562 338.32 11.27 911.20* 25.80 3.45447E+004 l.19774E+004 968.97* 15.80 4.14197E+004 l.69800E+004

• = Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold ~ 0 .30 Errors quoted at 2.000 sigma

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Interference Corrected Activity Report 6/16/2018 1:55:39 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 7.8 33233E+OOS 1 .034231E+OD5 Cs-137 1.000 3.388219E+003 2.491979E+D03 Eu-152 0.674 9.239221E+003 8 .811 557E+003 Eu-155 0 .346 1.205696E+004 1.054066E+004 Tl-208 1 .000 9.086584E+003 3.615893E+003 Pb-212 1 .000 2.679500E+004 1.210345E+004 Bi-214 1 .000 5.381539E+004 8.937926E+003 Pb-214 1 .000 3.219444E+004 1.015667E+D04 Ac-228 0.562 3.682891E+004 9.787419E+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

[46]

Interference Correcte d Activity Report 6/16/2018 1: 55: 39 PM Page 5

• • • • • • • • • • U N I D E N T I F I E D P E AK S **********

Peak Locate Performed on: 6/16/201 8 1 :55:38 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.41 1. 3237E-001 46. 14 2 75.27 1. 2696E-001 98.38 6 260.75 4.4862E-002 107.71 9 510.63 1.1246E-001 40.06 14 933.95 2.5546E-002 95.12 Sum M ~ First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[47]

Nuclide MDA Report 6/16/2018 1 :55:39 PM Page 6

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

Detector Name: 5456-A Sample Geometry:

Sample

Title:

B306107AFJFC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10. 66 3.649E+004 3.65E+004 7.833E+005 1.578E+004 Co-60 1173.23 99.85 7.304E+D03 5.99E+D03 2.801E+003 3.423E+003 1332.49 99.98 5.991E+D03 -5.099E+003 2.749E+003 Nb-94 702.65 99.81 5.440E+003 5. 4 4E+OD3 -1.13SE+003 2.554E+003 871.09 99.89 6.213E+003 -5.164E+003 2.917E+003 Ag-108m 433.90 90.50 6.071E+003 6.07E+003 -l.217E+D03 2.902E+003 61 4 .30 89.80 1.044E+004 -1.152E+003 5.05DE+003 722.90 90.80 7.254E+003 2.646E+OD3 3.441E+003 Cs-134 60 4 .72 97.62 9.799E+003 7.22E+003 l.340E+D03 4.745E+003 795.86 85.46 7.22SE+003 2.823E+003 3.403E+003

+ Cs-137 66 1 .66* 85. 10 3.733E+003 3.73E+003 3.388E+003 1. 679E+003

+ Eu-152 121.78* 28.67 1.459E+004 l .46E+D04 l. 170E+D04 7.078E+003 34 4 .28* 26.60 1.715E+004 4.664E+004 8.182E+003 1408.01 21. 07 2.605E+004 2.109E+004 1.181E+004 Eu-154 123.07 40.40 1.735E+004 1 .74E+OD4 -1.157E+OD4 8.519E+003 723.30 20.06 3.312E+004 3.703E+D03 1.572E+004 1274.43 34.80 1. 880E+004 4.204E+003 8.712E+003

+ Eu-155 86.55* 30.70 l .670E+004 1.67E+OD4 1.206E+OD4 8.147E+003 105.31 21.10 3.516E+004 l.091E+004 l .729E+004

+ Tl-208 583.19* 85.00 4.771E+OD3 4.77E+003 9.087E+003 2.213E+003 Bi-212 727.33 6.67 9.540E+OD4 9.54E+004 -6.054E+OD4 4.516E+004

+ Pb-212 238.63* 43.60 1. 785E+004 1 .78E+004 2.679E+004 8.736E+003

+ Bi-214 609.32* 45.49 9.226E+OD3 9.23E+D03 5.398E+OD4 4.281E+003 1120.29* 14.92 2.669E+004 3.110E+OD4 1 .186E+004 1764.49* 15. 30 1.623E+004 9.661E+OD4 6.161E+003

+ Pb-214 295.22* 18.42 2.274E+004 1. 28E+D04 4 .30DE+004 l .087E+004 351.93* 35.60 1.281E+004 3.484E+004 6.113E+003 Ra-226 186.21 3.64 1. 877E+005 1.88E+005 6.921E+004 9.190E+004

+ Ac-228 338.32 11 . 27 5.256E+004 1.37E+004 -1.211E+004 2.538E+004 911.20* 25.80 1. 372E+004 3.454E+004 6.107E+OD3 968.97* 15.80 2.034E+004 4 .142E+004 8.891E+003 Am-241 59.54 35.90 1. 935E+004 1.93E+OD4 3.157E+OD3 9.492E+003

+ - 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

[48]

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

Filename: C:\Users\kevin\Desktop\Buttress\00004843.CNF Report Generated On 6/12/2018 1:04:06 PM Sample Title B306107AFQFC005GD Sample Description Ul BUTTRESS PIT 6A QC Sample Identification 005 QC Sample Type GAMMA DIRECT Sample Geometry Buttress Pit Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1.870E+001 M... 2 Sample Taken on 5/22/2018 3:17:00 PM Acquisition Started 5/22/2018 3:18:12 PM Live Time 600.0 seconds Real Time 600.S seconds Dead Time 0.08 %

Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 6/12/2018 Efficiency ID BUTTRESS PIT A

[49]

Peak Analysis Report 6/12/2018 1:04:06 PM Page 2

• • • • • P E A K A N A L Y S I S REPORT *****

Detector Name: 5456-A Sample

Title:

B306107AFQFC005GD Peak Analysis Performed on: 6/12/2018 1: 04 :06 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 306 300.74 75.18 0.60 9.85E+001 72.47 5.08E+002 2 329- 345 340.03 85.01 0.35 9.78E+001 88.21 5.87E+002 3 945- 963 954.60 238.65 1. 11 1 .20E+002 59.57 2.25E+002 4 1076- 1086 108 0 .63 270.16 0.41 2.62E+001 28.18 7.18E+001 5 1173- 1186 1181 .01 295.25 1.19 7.86E+001 36.58 9.24E+001 6 1347- 1358 1353.21 338.30 1. 14 3.21E+001 28 .12 6.39E+001 7 1399- 1416 1407.31 351.83 1. 45 1. 53E+O 02 40.03 7.63E+001 8 2035- 2051 2042.56 510.64 0.56 4.68E+001 29.45 5.42E+001 9 2323- 2338 2331.30 582.82 1. 26 6.67E+001 25.37 3.13E+001 10 2428- 2446 2436.51 609.13 0.41 1. 54E+002 32.33 3.21E+001 11 2903- 2914 2908.50 727.13 0.60 1.84E+001 15.83 1 .76E+001 12 3636- 3651 3643. 01 910.75 1. 59 6.22E+001 22.60 2.18E+001 13 3868- 3883 3875.03 968.76 0.51 3.36E+001 19.65 2.04E+001 14 4471- 4486 4478.77 1119 .69 1.39 5.00E+OOl 20. 44 1.80E+001 15 4945- 4958 4951.54 1237.88 0.49 1. 96E+001 17.12 l.94E+001 16 5831- 5854 5842.37 1460.59 1. 38 3.90E+002 40.70 6.00E+OOO 17 7049- 7066 7057.94 1764.48 1. 07 5.47E+001 15.82 2.33E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[50]

Interference corrected Activity Report 6/12/2018 1 :04:06 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:

B306107AFQFC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

"' IDENTIFIED NUCLIDES . ... ......... . .... ! ....

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 1. 000 1460.82* 10.66 7.09518E+005 9.63221E+004 Eu-155 0.346 86.55* 30.70 l.45389E+004 1.34276E+004 105.31 21. 10 Tl-208 1.000 583.19* 85. 00 8.51856E+003 3.39884E+003 Bi-212 1.000 727.33* 6.67 3.45034E+004 2.99882E+004 Pb-212 1. 000 238.63* 43.60 1.67263E+004 8.71324E+003 Bi-214 1.000 609.32* 45.49 3.78101E+004 9.14939E+003 1120. 29* 14.92 5.48835E+004 2.28495E+004 1764.49* 15.30 7.89549E+004 2.36992E+004 Pb-214 1. 000 295.22* 18.42 2.93579E+004 1 .44515E+004 351.93* 35.60 3.32034E+004 1. 00235E+004 Ac-228 1.000 338.32* 11.27 2.14848E+004 1 .91011E+004 911.20* 25.80 3.47049E+004 1.30516E+004 968.97* 15.80 3.17932E+004 1.88301E+004

• ~ Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0 .30 Errors quoted at 2.000 sigma

[51]

Interference Corrected Activity Report 6/12/2018 1 :04:06 PM 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 1.000 7.095175E+OOS 9.632210E+004 X Ag-108m 0.3 9 1 Eu-155 0.346 1.453890E+004 1.342758E+004 Tl-208 1.000 8.518562E+003 3.398840E+003 Bi-212 1. 000 3.450343E+004 2.998820E+004 Pb-212 1. 000 1. 672630E+004 8.713242E+003 Bi-214 1. 000 4.458421E+004 7.995752E+003 Pb-214 1. 000 3.195435E+004 8.236255E+003 Ac-228 1. 000 3.081692E+004 9.352922E+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

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Interference Corrected Activity Report 6/12/2018 1 : 04: 06 PM Page 5

• • • • • • • • • • U N I D E N T I F I E D P E AK S **********

Peak Locate Performed on: 6/12/2018 1 : 04: 06 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.18 1. 6412E-001 73.60 4 270.16 4.3656E-002 107.57 8 510.64 7.7941E-002 62.96 15 1237.88 3.2735E-002 87.18 M = First peak in a multiplet region m == Other peak in a multiplet region F == Fitted singlet Errors quoted at 2 . 000 sigma

[53]

Nuclide MDA Report 6/12/2018 1 :04 : 06 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Buttress Pit Sample

Title:

B306107AFQFC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 )

+ K-40 1460.82* 10 .66 3.429E+004 3.43E+004 7.095E+005 1 .468E+004 Co-60 1173.23 99.85 6.786E+003 5.99E+003 -3.231E+003 3.165E+003 1332.49 99.98 5.989E+003 -1.671E+003 2.748E+003 Nb-94 702.65 99.81 5.376E+003 4.94E+003 2.958E+002 2.522E+003 8 71. 09 99.89 4.945E+003 -5.610E+003 2.283E+003 Ag-108m 433.90 90.50 5.618E+003 3.39E+003 -2.721E+003 2.675E+003 614.30* 89.80 4.578E+003 1 .915E+004 2. 121E+ 003 722.90* 90.80 3.390E+003 2.535E+003 1. 508E+003 Cs-134 604.72 97.62 8.806E+003 6.87E+003 -3.031E+003 4.249E+003 795.86 85.46 6.865E+003 -3.872E+002 3.223E+003 Cs-137 661. 66 85 .10 7.259E+003 7.26E+003 2.491E+003 3.442E+003 Eu-152 121. 78 28.67 2.505E+004 2.17E+004 -5.643E+003 l.231E+004 344.28 26.60 2.166E+004 9.026E+002 1. 044E+004 1408. 01 21. 07 3.044E+004 2.100E+004 l.401E+004 Eu-154 123.07 40.40 1.774E+004 1.64E+004 4.00BE+002 8.711E+003 723.30 20.06 2.898E+004 1.800E+004 1.365E+004 1274.43 34.80 1.637E+004 -9.470E+003 7.496E+003

+ Eu-155 86.55* 30. 70 2.142E+004 2.14E+004 l.454E+004 1.051E+004 105.31 21. 10 3.385E+004 -9.565E+003 1.663E+004

+ Tl-208 583.19* 85. 00 4.425E+003 4.43E+003 8.519E+003 2.040E+003

+ Bi-212 727.33* 6.67 4.615E+004 4.61E+004 3.450E+004 2.054E+004

+ Pb-212 238.63* 43.60 1. 3 04E+O 04 1.30E+004 1 .673E+004 6.334E+003

+ Bi-214 609.32* 45.49 9.037E+003 9.04E+003 3.781E+004 4.186E+003 1120.29* 14. 92 2.959E+004 5.488E+004 1.331E+004 1764.49* 15.30 l.723E+004 7.895E+004 6.660E+003

+ Pb-214 295.22* 18.42 2.068E+004 1.19E+004 2.936E+004 9.832E+003 351.93* 35.60 1.185E+004 3.320E+004 5.632E+003 Ra-226 186.21 3.64 1.739E+005 1 .74E+005 3.664E+004 8.497E+004

+ Ac-228 338.32* 11. 27 3.012E+004 1 .64E+004 2.148E+004 1. 415E+004 911.20* 25.80 1.637E+004 3.470E+004 7.428E+003 968.97* 15.80 2.727E+004 3.179E+004 1 .235E+004 Arn-241 59.54 35.90 1 .843E+004 1.84E+004 5.700E+003 9.033E+003

+=Nuclide identified during the nuclide i dentification

• =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

[54]

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

Filename: C:\Users\kevin\Desktop\Buttress\00004845. CNF Report Generated On 6/12/2018 1:05:43 PM Sample Title B306107AFJFCOOSGD Sample Description Ul BUTTRESS PI T 6A Sample Identification 005 Sample Type GAMMA DIRECT Sample Geometry Buttress Pit Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 :keV Sample Size 1.870E+001 MA2 Sample Taken On 5/22/2018 3: 01 : 00 PM Acquisition Started 5/22/2018 3: 04 : 31 PM Live Time 600. 0 seconds Real Time 600.5 seconds Dead Time 0.09 %

Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 6/12/2018 Efficiency ID BUTTRESS PIT A

[55]

Peak Analysis Report 6/12/2018 1:05:43 PM Page 2

• • • • • P E A K ANALYS I S R E P O R T *****

Detector Name: 5456-A Sample

Title:

B306107AFJFC005GD Peak Analysis Performed on: 6/12/2018 1:05:43 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 126- 137 130.19 32.55 0.72 1.05E+002 41. 57 1. 09E+002 2 286- 305 300.59 75.15 0.80 2.04E+002 114 .14 8.68E+002 3 345- 355 350.02 87.51 0.72 -2.05E+001 64.91 4.51E+002 4 948- 962 954.82 238.70 1.13 1.09E+002 51.96 1 .96E+002 5 1173- 1188 1180.78 295.19 0.99 7.80E+001 43.63 1.32E+002 6 1399- 1418 1407.93 351.98 0.83 1.76E+002 41.87 7.52E+001 7 2326- 2341 2332.27 583.07 0.96 6.80E+001 25.88 3.30E+001 8 2425- 2445 2436.49 609.12 1. 31 1.90E+002 33.71 2.60E+001 9 2640- 2652 2645.45 661.36 0.35 2.19E+001 17.97 2.21E+001 10 3634- 3651 3642.63 910.66 0.43 5.09E+001 24.74 3.0lE+OOl 11 3867- 3881 3874.66 968.67 0.96 4.25E+001 16.15 7.46E+OOO 12 4472- 4489 44 80 .38 1120.09 0.91 6.59E+001 20.83 1.21E+001 13 4946- 4959 4952.30 1238.08 0.44 2.41E+001 16.84 1. 69E+001 14 5503- 5516 5509.07 1377.27 1. 21 2.34E+001 10.52 1. 59E+OOO 15 5831- 5855 5842.44 1460.61 1.60 3.86E+002 41.31 9.55E+OOO 16 7051- 7067 7059.18 1764.80 0.71 5.57E+001 17 .37 6.33E+OOO M = First peak in a mul t iplet region m = Other peak in a mul t iplet region F "" Fitted singlet Errors quoted at 2 . 000 sigma

[56]

Interference Corrected Activity Report 6/12/2018 1 :05: 43 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:

B306107AFJFC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

• * * * * * * * .. I * * *

• I *

• I II ., IDENTIFIED NUCLIDES 4 ~ * .. * .. .. * .. * * * * * * ~ .. * '

• Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"'2 ) uncertainty K-40 1.000 1460.82* 10.66 7.03057E+005 9.68210E+004 Cs-137 1.000 661.66* 85.10 3.03496E+003 2.51597E+003 Eu-155 0.348 8 6.55* 30.70 -3.04336E+003 9.65152E+003 1 0 5.31 21. 10 Tl-208 1.000 583.19* 85. 00 8.69348E+003 3.46774E+003 Pb-212 1.000 238.63* 43.60 1. 51027E+004 7.62814E+003 Bi-214 1.000 609.32* 45.49 4.66620E+004 1 .00004E+004 1120.29* 14.92 7.22879E+004 2.35732E+004 1764.49* 15.30 8.04122E+004 2.59026E+004 Pb-214 1.000 295.22* 18.42 2.91349E+004 1 .69526E+004 351. 93* 35.60 3.82405E+004 1 .07553E+004 Ac-228 0.562 338.32 11. 27 911. 2 O* 25.80 2.83978E+004 1 .40739E+004 968.97* 15.80 4.02701E+004 l .57335E+004

• ~ Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0. 30 Errors quoted at 2. 000 sigma

[57]

Interference Corrected Activity Report 6/12/2018 1 :05:43 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 7.030569E+005 9.682099E+004 Cs-137 1. 000 3.034965E+003 2.515973E+003 Eu-155 0.348 -3.043357E+003 9.651518E+003 Tl-208 1. 000 8.693475E+003 3.467742E+003 Pb-212 1. 000 l. 510266E+004 7.628141E+003 Bi-214 1. 000 5.391734E+004 8.674647E+003 Pb-214 1. 000 3.562727E+004 9.081784E+003 Ac-228 0.562 3.367496E+004 1. 048959E+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

[58]

'Interference Corrected Activity Report 6/12/2018 1 :05:43 PM Page 5

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

Peak Locate Performed on: 6/12/2018 1:05:42 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % uncertainty Type Nuclide 1 32.55 1. 7571E-001 39. 43 2 75.15 3.3946E-001 56.04 13 1238.08 4.0224E-002 69.77 Sum 14 1377.27 3.9017E-002 44.96 M = First peak in a multiplet region m = Other peak in a multiplet region F : Fitted singlet Errors quoted at 2 . 000 sigma

[59]

Nuclide MDA Report 6/12/2018 1:05:43 PM Page 6

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

Detector Name: 5456-A Sample Geometry: Buttress Pit Sample

Title:

B306107AFJFC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 4.282E+004 4.28E+D04 7.031E+OD5 1.895E+004 Co-60 1173.23 99.85 7.346E+003 5.79E+003 7.880E+003 3.445E+D03 1332.49 99.98 5.789E+003 -1.230E+003 2.648E+003 Nb-94 702.65 99.81 5.659E+003 5.51E+003 3.761E+003 2.663E+003 871.09 99.89 5.515E+003 -1.061E+003 2.568E+003 Ag-108m 433.90 90.50 5.773E+003 5.77E+OD3 -5.387E+003 2.753E+003 614.30 89.80 9.635E+003 -4.034E+003 4.648E+003 722.90 90.80 6.332E+003 1.949E+003 2.980E+003 Cs-134 604.72 97.62 9.272E+003 6.78E+003 -1.326E+003 4.482E+003 795.86 85.46 6.784E+003 -2.827E+003 3.183E+003

+ Cs-137 661.66* 85.10 3.870E+003 3.87E+003 3.035E+003 1 .748E+OD3 Eu-152 121. 78 28.67 2.549E+004 2.24E+004 -6.709E+003 1 .253E+004 344.28 26.60 2.241E+004 -2.386E+004 1.082E+004 1408.01 21.07 2.981E+004 -1. 678E+004 1.369E+OD4 Eu-154 123.07 40.40 1.803E+004 1.75E+004 2.027E+003 8.860E+D03 723 . 30 20.06 2.898E+004 1.004E+004 1.365E+004 1274.43 34.80 1.746E+004 -1.441E+004 8.039E+003

+ Eu-155 86.55* 30.70 1. 640E+004 1.64E+D04 -3.043E+003 7.999E+003 105.31 21.10 3.548E+004 4.930E+003 1 .745E+004

+ Tl-208 583.19* 85.00 4.536E+003 4 .54E+003 8.693E+003 2.095E+003 Bi-212 727.33 6.67 8.605E+004 8.61E+004 -3.638E+004 4.049E+004

+ Pb-212 238.63* 43.60 1.127E+004 1 .13E+004 1.510E+004 5.445E+003

+ Bi-214 609.32* 45.49 8.502E+003 8.50E+003 4.666E+004 3.919E+003 1120.29* 14.92 2.652E+004 7.229E+004 l.177E+004 1764.49* 15. 30 2.503E+004 8.041E+004 1.056E+004

+ Pb-214 295.22* 18.42 2.553E+004 l .22E+004 2.913E+004 1.226E+004 351.93* 35.60 1.218E+004 3.824E+004 5.796E+003 Ra-226 186.21 3.64 1.843E+005 1.84E+OOS -4.781E+004 9.020E+004

+ Ac-228 338.32 11. 27 5.388E+004 l.74E+004 2.541E+004 2.604E+004 911.20* 25.80 2.006E+004 2.840E+004 9.273E+003 968.97* 15.80 1. 739E+004 4.027E+004 7.413E+003 Am-241 59.54 35.90 2.067E+004 2. 07E+OD4 9.390E+OD3 1 .016E+004

+ =Nuclide identified during the nuclide i dentification

• =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

[60]

• • • • • GAMM A S P E C T R U M ANALYSIS *****

Filename: C:\Users\kevin\Desktop\Buttress\00004844.CNF Report Generated On 6/12/2018 1: 04: 48 PM Sample Title B306107AFJFC006GD Sample Description Ul BUTTRESS PIT lB Sample Identification 006 Sample Type GAMMA DIRECT Sample Geometry Buttress Pit Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1. 8 70E+001 M... 2 Sample Taken On 5/22/2018 12:45:00 PM Acquisition Started 5/22/2018 12:48:45 PM Live Time 600.0 seconds Real Time 600.6 seconds Dead Time 0 . 11 %

Energy Calibration used Done On 3/15/2018 Efficiency Calibration Used Done On 6/12/2018 Efficiency ID BUTTRESS PIT A

[61]

Peak Analysis Report 6/12/2018 1:04: 48 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B306107AFJFC006GD Peak Analysis Performed on: 6/12/2018 1:04:48 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area uncert. Counts 1 126- 134 130.55 32.64 0.83 5.53E+001 33.38 8.27E+001 2 289- 317 299.97 74.99 0.96 3.41E+002 144.80 1.06E+003 3 551- 560 555.27 138.82 0.98 5.60E+001 47 .26 2.21E+002 4 720- 729 724.43 181.11 0.91 1.94E+001 39 .21 1. 62E+002 5 945- 960 954.57 238.64 1. 58 8.86E+001 55.11 2.21E+002 6 1170- 1205 118 0.48 295.12 1. 07 9.92E+001 77.96 2.38E+002 7 1347- 1360 1353.02 338.26 0.50 3.19E+001 32.19 8.21E+001 8 1400- 1415 140 7. 00 351.75 1.44 1.40E+002 40. 84 9.07E+001 9 2326- 2340 2331.58 582.89 1. 54 6.44E+001 26.80 3.96E+001 10 2426- 2445 2435.92 608.98 0.94 1.70E+002 34.24 3.51E+001 11 3634- 3650 3643.54 910.89 1. 70 5.79E+001 22.81 2.31E+001 12 3867- 3881 3873.24 968.31 0.86 3.90E+001 18.16 1.40E+001 13 4472- 4488 4479.73 1119 .93 0.44 5.79E+001 20.57 1.51E+001 14 4944- 4957 4950.45 1237.61 0.66 3.29E+001 13.69 5.llE+OOO 15 5504- 5517 5510.02 1377.51 0.35 1.74E+001 1 1. 62 5.55E+OOO 16 5830- 5854 5842.41 1460.60 1. 75 3.82E+002 40 .38 6.25E+OOO 17 7050- 7065 7057.98 1764.49 0.63 4.lOE+OOl 17.56 1.20E+001 M = First peak in a multiplet region m ; Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[62]

Interference Corrected Activity Report 6/12/2018 1:04:48 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:

B306107AFJFC006GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

• fl

• I * * * * * * * * *

• I * * *

• I Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1 .000 1460.82* 10.66 6.94511E+005 9.50403E+004 Tl-208 1 .000 583.19* 85.00 8.22704E+003 3.56403E+003 Pb-212 1. 000 238.63* 43.60 1 .23193E+004 7.91731E+003 Bi-214 1 .000 609.32* 45.49 4.17294E+004 9.79198E+003 1120.29* 14.92 6.35598E+004 2.31312E+004 1764.49* 15.30 5.92116E+004 2.57957E+004 Pb-214 1 .000 295.22* 18.42 3.70409E+004 2.97119E+004 351.93* 35.60 3.04909E+004 9.98334E+003 Ra-226 0.959 186.21* 3.64 2.78920E+004 5.66092E+004 Ac-228 1 .000 338.32* 11.27 2.13596E+004 2.17815E+004 911. 20* 25.80 3.23167E+004 1.31066E+004 968.97* 15.BO 3.69016E+004 1.75199E+004

• = Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0 .30 Errors quoted at 2.000 sigma

[63]

Interference Corrected Activity Report 6/12/2018 1:04:48 PM 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/MA2 ) Uncertainty K-40 1.000 6.945112E+005 9.504034E+004 Tl-208 1. 000 8.227041E+003 3.564030E+003 Pb-212 1. 000 1.231926E+004 7.917310E+003 Bi-214 1. 000 4.658934E+004 8.512202E+003 Pb-214 1. 000 3.115533E+004 9.463420E+003 Ra-226 0.959 2.789195E+004 5.660915E+004 Ac-228 1.000 3.158748E+004 9.454625E+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

[64]

Interference Corrected Activity Report 6/12/2018 1:04:48 PM Page 5

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

Peak Locate Performed on: 6/12/2 018 1 :04:48 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.64 9.2101E-002 60.41 2 74.99 5.6809E- 001 42.48 3 138.82 9.3351E-002 8 4 .38 14 1237.61 5.4814E-002 41 .63 15 1377.51 2.9076E-002 66.59 M = First peak in a multiplet region m other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[65]

Nuclide MDA Report 6/12/2018 1 : 04 :48 PM Page 6

• • • • • N U C L I D E MDA REPORT *****

Detector Name: 5456-A Sample Geometry: Buttress Pit Sample

Title:

B306107AFJFC006GD Nuclide Library used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/MA2 )

+ K-40 1460 . 82* 10.66 3.532E+004 3.53E+004 6.945E+D05 1.520E+004 Co-60 1173.23 99.85 6.487E+003 6.12E+003 -4.003E+003 3.015E+003 1332.49 99.98 6.118E+003 1.189E+OD3 2. 813E+003 Nb-94 702.65 99.81 5.408E+003 5.35E+003 1.097E+003 2.538E+003 871. 09 99.89 5.346E+003 2.032E+003 2.483E+003 Ag-108m 433.90 90.50 5.677E+003 5.68E+003 -3.657E+OD3 2.705E+003 614.30 89.80 9.451E+003 -2.724E+OD3 4.556E+003 722.90 90.80 7.429E+003 1. 021E+O 03 3.529E+003 Cs-134 604.72 97.62 8.872E+003 7. 0 2E+D03 -9.334E+OD2 4. 282E+003 795.86 85.46 7.025E+003 -1. 898E+O 03 3.303E+003 Cs-137 661.66 85.10 6.692E+003 6.69E+003 -6.084E+003 3.158E+003 Eu-152 121.78 28.67 2.533E+004 2.11E+D04 -2.203E+D04 1. 245E+004 344.28 26.60 2. 114E+004 -6.642E+003 1. 018E+004 1408. 01 21. 07 2.884E+004 2.176E+004 1. 320E+004 Eu-154 123.07 40.40 1.798E+004 1.78E+D04 -2.296E+D04 8.831E+003 723.30 20.06 3 .42 9E+004 2.587E+D04 1. 630E+004 1274.43 34.80 1. 780E+004 -9.086E+003 8.212E+003 Eu-155 86.55 30.70 2.565E+004 2.57E+004 1.105E+OD4 1.263E+004 105.31 21.10 3.592E+004 -3.107E+004 1.766E+004

+ Tl-208 583.19* 85.00 4.857E+003 4.86E+003 8.227E+003 2.256E+003 Bi-212 727.33 6.67 l.027E+OOS 1.03E+OOS 4.883E+004 4.881E+004

+ Pb-212 238.63* 43.60 1. 222E+004 1.22E+004 1.232E+004 5.924E+D03

+ Bi-214 609.32* 45.49 9.634E+003 9.63E+003 4 .173E+004 4.484E+003 1120.29* 14.92 2.793E+004 6.356E+004 1 .248E+004 1764.49* 15. 30 3.244E+004 5.921E+D04 1 .427E+004

+ Pb-214 295.22* 18.42 4. 731E+004 1.25E+004 3.704E+004 2.315E+004 351. 93* 35.60 1. 249E+004 3.049E+OD4 S.949E+003

+ Ra-226 186.21* 3.64 9.429E+004 9.43E+004 2.789E+004 4.520E+D04

+ Ac-228 338.32* 11. 27 3.496E+004 1. 71E+004 2.136E+004 1.658E+004 911. 2 O* 25.80 1.710E+004 3.232E+004 7.796E+D03 968.97* 15.80 2.308E+004 3.690E+004 1. 026E+004 Am-241 59.54 35.90 2.024E+004 2.02E+004 1.578E+D04 9.940E+003

+ = 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

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

Filename: C:\Users\kevin\Desktop\Buttress\00004846.CNF Report Generated On 6/12/2018 1: 06: 31 PM Sample Title B306107AFJWC007GD Sample Description Ul BUTTRESS PIT lB WALL SHOT Sample Identification 007 Sample Type GAMMA DIRECT Sample Geometry Buttress Pit Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 1. 8 70E+O 01 Sample Taken On 5/22/2018 1:17:00 PM Acquisition Started 5/22/2018 1:18:25 PM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0 . 09 %

Energy Calibration Used Done On 3/15/20.18 Efficiency Calibration Used Done On 6/12/2018 Efficiency ID BUTTRESS PIT A

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Peak Analysis Report 6/12/2018 1 :06:31 PM Page 2

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

Detector Name: 5456-A Sample

Title:

B306107AFJWC007GD Peak Analysis Performed on: 6/12/2018 1 :06:30 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area uncert. Counts 1 126- 134 130 .48 32.62 0.55 3.42E+001 23.04 3.78E+001 2 285- 305 300.22 75.05 0.97 2.75E+002 118.59 8.92E+002 3 332- 346 339.50 84.87 0.55 7.94E+001 83.00 5.66E+002 4 739- 748 743.81 185.95 1. 36 4.85E+001 41. 37 1.68E+002 5 869- 879 873.53 218.38 0.83 l.95 E+001 38.66 l .42E+002 6 949- 972 954.93 238.73 1.17 1.96E+002 72.31 2.75E+002 7 1176- 1188 1180 .67 295.17 1. 06 6.40E+001 36.15 9.80E+001 8 1348 - 1360 1353.51 338.38 0.72 3.16E+001 27.80 5.94E+001 9 1398- 1415 1407 .28 351.82 0.95 1.88E+002 41.61 7.46E+001 10 2326 - 2339 2331.92 582.98 0.44 5.55E+001 25. 94 4.0SE+OOl 11 2427- 2447 2435.99 609 .00 1. 36 2.08E+002 39.08 4.84E+001 12 2638- 2650 2644.64 661.16 0.50 5.95E+OOO 17.30 2.60E+001 13 3635- 3649 3642.20 910 .55 0.68 3.28E+001 21.39 2.82E+001 14 3868- 3881 387 4 .76 968.69 0.38 3.55E+001 16.08 l .OSE+OOl 15 4471- 4490 4479.98 1120. 00 0.64 7.60E+001 24.18 2.00E+OOl 16 4945- 4958 4951 . 39 1237.85 0 .39 2.8SE+001 14.41 8.54E+OOO 17 5831- 5855 5842.74 1460.68 1. 78 4.17E+002 42.08 6.25E+OOO 18 7050- 7066 7058.02 1764.50 0 .93 6.48E+001 16.98 2.24E+OOO M = First peak in a mul t iplet region m = Other peak in a mult iplet region F ~ Fitted singlet Errors quoted at 2.000 sigma

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Interference Corrected Activity Report 6/12/2018 1 :06:31 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:

B306107AFJWC007GD Nuclide Library used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

• ****** * *** *** i, ****

• IDENTIFIED NUCLIDES * ,, I * * * * * * * * *

• I I I * * ~ -'

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/ ) Uncertainty K-40 1.000 1460.82* 10. 66 7.58216E+005 1. 00972E+005 Cs-137 1.000 661. 66* 85.10 8.24497E+002 2.39741E+003 Eu-155 0.346 86.55* 30.70 1 .18068E+004 l.25596E+004 1 05.31 21.10 Tl-208 1.000 583.19* 85.00 7.09625E+003 3.42165E+003 Pb-212 1.000 238.63* 43.60 2.72248E+004 1.09783E+004 Bi-214 1.000 609.32* 45.49 5.09857E+004 1.13873E+004 1120.29* 14.92 8.33818E+004 2.73556E+004 1764.49* 15.30 9.35276E+004 2.56436E+004 Pb-214 1 .000 295.22* 18.42 2.38893E+004 1.40325E+004 351.93* 35.60 4.09643E+004 l.09289E+004 Ra-226 1 .000 186.21* 3.64 7.05902E+004 6.13895E+004 Ac-228 1 .000 338.32* 11. 27 2.11049E+004 1.88833E+004 911.20* 25.80 1. 82836E+004 1.20612E+004 968.97* 15 .80 3.36063E+004 l.55357E+004

• =Energy line found in the spectrum.

@ ~ Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0.30 Errors quoted at 2.000 sigma

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Interference Corrected Activity Report 6/12/2018 1: 06: 31 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/ ) Uncertainty K-40 1. 000 7.582158E+005 1 .009715E+005 Cs-137 1.000 8.244971E+002 2.397413E+003 Eu-155 0.346 1.180676E+004 1 .255956E+004 Tl-208 1 .000 7.096246E+003 3.42164SE+003 Pb-212 1 .000 2.722485E+004 1.097830E+004 Bi-214 1.000 6.120300E+004 9.727179E+003 Pb-214 1.000 3.451752E+004 8.622348E+003 Ra-226 1. 000 7.059019E+004 6.138952E+004 Ac-228 1. 000 2.344917E+004 8.505849E+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

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Interference Corrected Activity Report 6/12/2018 1 :06:31 PM Page 5

• • • • • • • • • • U N I D E N T I F I E D PE AK S **********

Peak Locate Performed on: 6/12/2018 1:06:30 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.62 5.7037E-002 67.33 2 75.05 4.5836E-001 43.12 5 218.38 3.2505E-002 198.24 16 1237.85 4.7432E-002 50.64 Sum M = First peak in a multiplet region rn = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma

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Nuclide MDA Report 6/12/2018 1 :06: 31 PM Page 6

• • • • • N U C L I D E MD A REP ORT *****

Detector Name: 5456-A Sample Geometry: Buttress Pit Sample

Title:

B306107AFJWC007GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/ ) (pCi/ ) (pCi/ ) (pCi/ )

+ K-40 1460.82* 10.66 3.536E+004 3.54E+004 7.582E+OOS l .522E+004 Co-60 1173.23 99.85 6.737E+003 6.37E+003 1.737E+003 3.140E+003 1332.49 99.98 6.369E+003 5.96SE+003 2.938E+003 Nb-94 702. 6 5 99.81 5.504E+003 5.50E+003 7.30SE+002 2.586E+003 871. 09 99.89 5.797E+003 3.504E+001 2.709E+003 Ag-108m 433.90 90.50 6.125E+003 6.12E+003 1.528E+003 2.929E+003 614.30 89.80 1.057E+004 -3.266E+003 5.117E+003 722.90 90.80 6.793E+003 2.771E+003 3.211E+003 Cs-134 604.72 97.62 9.761E+003 7.37E+003 -1.446E+003 4.726E+003 795.86 85.46 7.369E+003 1 .295E+002 3.475E+003

+ Cs-137 661. 66* 85. 10 4.155E+003 4.16E+003 8.245E+002 1.890E+003 Eu-152 121. 78 28.67 2.615E+004 2.13E+004 -9.460E+002 1 .286E+004 344.28 26.60 2.131E+004 -5.495E+003 1 .027E+004 1408 . 01 21. 07 2.817E+004 1.997E+004 1.287E+004 Eu-154 123 . 07 40.40 1. 837E+004 1.84E+004 -8.156E+003 9.030E+003 723.30 20.06 3.119E+004 4.802E+004 l.475E+004 1274.43 34.80 1. 880E+O 04 1. 2 08E+O 03 8.710E+003

+ Eu-155 86.55* 30.70 2.022E+004 2.02E+004 1.181E+004 9.909E+003 105.31 21.10 3.620E+004 -2.823E+003 l.781E+004

+ Tl-208 583.19* 85.00 4.807E+003 4.81E+003 7.096E+003 2.230E+003 Bi-212 727.33 6.67 9.018E+004 9.02E+004 4.222E+003 4.25SE+004

+ Pb-212 238 . 63* 43.60 1. 563E+004 1 .56E+004 2.722E+004 7.628E+003

+ Bi-214 609.32* 45.49 1. 133E+004 1 .13E+004 5.099E+004 5.332E+003 1120 .29* 14.92 3.320E+004 8.338E+004 1 .512E+004 1764.49* 15.30 1.678E+004 9.353E+004 6.434E+003

+ Pb-214 295.22* 18.42 2.093E+004 1.18E+004 2.389E+004 9.959E+003 351.93* 35.60 1.177E+004 4.096E+004 5.591E+003

+ Ra-226 186.21* 3.64 9.713E+004 9.71E+004 7.059E+004 4.660E+004

+ Ac-228 338.32* 11. 27 2.979E+004 1.81E+004 2.110E+004 1.399E+004 911. 20* 25.80 l.808E+004 1. 828E+004 8.288E+003 968.97* 15.80 1.938E+004 3.361E+004 8.407E+003 Am-241 59.54 35.90 1.927E+004 1.93E+004 2.106E+003 9.456E+003

+ = Nuclide identified during the nuclide i dentification

• =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

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