ML20352A236
| ML20352A236 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 11/02/2020 |
| From: | La CrosseSolutions |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML20356A041 | List:
|
| References | |
| LC-2020-0023 | |
| Download: ML20352A236 (781) | |
Text
{{#Wiki_filter:~ LACROSSESOLUTIONS LA CROSSE BOILING WATER REACTOR FINAL STATUS SURVEY RELEASE RECORD REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 REVISION 1
FSS RELEASE RECORD REVISION 1 REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Robert F. Yetter III PREPARED BY / DATE: Oct 26 2020 11:11 AM cosign R. F. Yetter III, FSS Specialist Mitchell Uz REVIEWED BY / DATE: ~~ Oct 27 2020 7:48 AM cosign M. D. Uz, FSS Specialist Robert F. Yetter a)_ /l _ . . .6. (i; *( )Jnl-lnu REVIEWED BY / DATE: .~ .a . ~ Oct 27 2020 10:56 AM cosign R. Yetter, Director, Radiological Site Closure Sarah Roberts REVIEWED BY / DATE: Oct 27 2020 12:24 PM cosign S. Roberts, VP Radiological Programs Scott G. Zoller APPROVED BY / DATE: Oct 29 2020 9:10 AM cosign S. Zoller, FSS Manager 1
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 TABLE OF CONTENTS
- 1. EXECUTIVE
SUMMARY
............................................................................................................................ 5
- 2. SURVEY UNIT DESCRIPTION ................................................................................................................... 5
- 3. CLASSIFICATION BASIS ........................................................................................................................... 6
- 4. DATA QUALITY OBJECTIVES ................................................................................................................ 10
- 5. SURVEY DESIGN ....................................................................................................................................... 14
- 6. SURVEY IMPLEMENTATION ................................................................................................................. 20
- 7. SURVEY RESULTS .................................................................................................................................... 21
- 8. QUALITY CONTROL ................................................................................................................................ 25
- 9. INVESTIGATIONS AND RESULTS ......................................................................................................... 25
- 10. REMEDIATION AND RESULTS ............................................................................................................... 25
- 11. CHANGES FROM THE FINAL STATUS SURVEY PLAN...................................................................... 26
- 12. DATA QUALITY ASSESSMENT............................................................................................................... 26
- 13. ANOMALIES............................................................................................................................................... 26
- 14. CONCLUSION ............................................................................................................................................ 27
- 15. REFERENCES ............................................................................................................................................ 27
- 16. ATTACHMENTS ........................................................................................................................................ 28 ATTACHMENT 1 - FIGURES AND MAPS ............................................................................................................. 29 ATTACHMENT 2 - ISOCS GEOMETRIES ............................................................................................................. 33 ATTACHMENT 3 - SIGN TEST ............................................................................................................................... 40 ATTACHMENT 4 - QUALITY CONTROL ASSESSMENT ...................................................................................... 42 ATTACHMENT 5 - GRAPHICAL PRESENTATIONS ............................................................................................. 44 ATTACHMENT 6 - MEASUREMENT ANALYTICAL REPORTS ........................................................................... 48 ATTACHMENT 7 - SAMPLE ANALYTICAL REPORTS ....................................................................................... 403 ATTACHMENT 8 - GEL LABORATORIES ANALYTICAL REPORTS ................................................................. 718 2
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 LIST OF TABLES Table 3 Reactor Building Basement Continuing Characterization Concrete Core Analysis Summary - On-site.......................................................................................................................................................................... 6 Table 3 Reactor Building Basement Continuing Characterization Concrete Core Analysis Summary - Off-site.......................................................................................................................................................................... 8 Table 3 Continuing Characterization Soil Borings Analysis Summary - Off-site ............................................ 9 Table 4 Reactor Building Basement Dose Significant Radionuclides and Mixture ........................................ 12 Table 4 Reactor Building Basement Base Case DCGLs ................................................................................... 13 Table 4 Reactor Building Basement Operational DCGLs ................................................................................ 13 Table 5 Reactor Building Basement Surrogate Ratio ....................................................................................... 14 Table 5 Action Levels for Survey Unit B1-010-001 ........................................................................................... 15 Table 5 Number of ISOCS Measurements based on Areal Coverage ............................................................. 16 Table 5 Adjusted Minimum Number of ISOCS Measurements ...................................................................... 17 Table 5 Investigation Levels ................................................................................................................................. 18 Table 5 Synopsis of Survey Design ...................................................................................................................... 19 Table 7 Summary of Systematic, Judgmental, and QC Measurements .......................................................... 23 Table 7 Summary of ISOCS Systematic Measurement Statistical Quantities ................................................ 23 Table 7 Summary of ISOCS Judgmental Measurements ................................................................................. 24 Table 7 Summary of Replicate ISOCS Measurements for QC ........................................................................ 25 Table 16 B1-010-001 Sign Test ............................................................................................................................ 41 Table 16 Reactor Building Basement QC Assessment ...................................................................................... 43 LIST OF FIGURES Figure 6 ISOCS Measurement ............................................................................................................................. 21 Figure 16 Reactor Building Basement ISOCS Measurement Locations (1) .................................................... 30 Figure 16 Reactor Building Basement ISOCS Measurement Locations (2) .................................................... 31 Figure 16 Reactor Building Basement ISOCS Measurement Locations (3) .................................................... 32 Figure 16 Quantile Plot for Cs-137 Concentration ............................................................................................ 45 Figure 16 Histogram for Cs-137 Concentration ................................................................................................. 46 Figure 16 Retrospective Power Curve for B1-010-001 ...................................................................................... 47 3
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable BFM Basement Fill Model DQO Data Quality Objective DCGL Derived Concentration Guideline Level DCGLB Basement Derived Concentration Guideline Level EMC Elevated Measurement Comparison FOV Field-of-View FSS Final Status Survey IC Insignificant Contributors ISOCS In-Situ Object Counting System LACBWR La Crosse Boiling Water Reactor LBGR Lower Bound of the Gray Region LTP License Termination Plan MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration OpDCGLB Basement Operational Derived Concentration Guideline Level QAPP Quality Assurance Project Plan QC Quality Control RA Radiological Assessment ROC Radionuclides of Concern SOF Sum of Fractions UBGR Upper Bound of the Gray Region WGTV Waste Gas Tank Vault WTB Waste Treatment Building 4
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001
- 1. EXECUTIVE
SUMMARY
This Final Status Survey (FSS) Release Record for survey unit B1-010-001, Reactor Building Basement, has been generated in accordance with LaCrosseSolutions procedure LC-FS-PR-009, Final Status Survey Data Reporting (Reference 1) and satisfies the requirements of Section 5.11 of the La Crosse Boiling Water Reactor License Termination Plan (LACBWR LTP) (Reference 2). An FSS sample plan for this survey unit was developed in accordance with LaCrosseSolutions procedure LC-FS-PR-002, Final Status Survey Package Development (Reference 3), the LACBWR LTP, and with guidance from NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) (Reference 4). This survey unit has a MARSSIM classification of 1. A survey plan was designed based upon use of the Sign Test as the nonparametric statistical test for compliance. Both the Type I () and Type II () decision error rates were set at 0.05. As a systematic measurement population, forty-five (45) measurements using the Canberra In-Situ Object Counting System (ISOCS) were acquired from the survey unit. The analytical results for all systematic measurements taken in survey unit B1-010-001 indicate that the maximum Sum of Fractions (SOF), considering the concentration of all applicable Radionuclides of Concern (ROC), either by direct measurement or by inference, is equal to 0.0232, when applying the respective Operational Derived Concentration Guideline Levels (OpDCGLB). Therefore, the null hypothesis is rejected, and survey unit B1-010-001 is acceptable for unrestricted release. The mean SOF for systematic measurements when applying the respective Base Case DCGLs (DCGLB) is 0.0004. The maximum SOF for the judgmental measurements, when compared to the DCGLB is 0.0753. The total SOF, when factoring in the area-weighted SOF of the elevated judgmental measurements is 0.0006, which equates to a dose of 0.015 mrem/yr.
- 2. SURVEY UNIT DESCRIPTION B1-010-001 is an impacted Class 1 basement survey unit. This survey unit housed the nuclear reactor and primary reactor systems. All internal systems, concrete, and the steel liner were removed during demolition. At end-state, the survey unit consisted of the concrete floor and concrete walls up to 3 feet below grade (636 foot elevation). The total surface area of the survey unit is 512 m2.
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001
- 3. CLASSIFICATION BASIS Based on the Historical Site Assessment (Reference 5), the Reactor Building Basement was identified as a Class 1 area.
The initial site characterization surveys performed by EnergySolutions were conducted between October 9, 2014, and August 6, 2015. Because of limited accessibility, the Reactor Building Basement interior structural surfaces characterization was deferred. A Radiological Assessment (RA) (considered a form of continuing characterization) was performed in the survey unit between March 15, 2019, and March 21, 2019. The RA survey was performed to ensure that any individual ISOCS measurement would not exceed the OpDCGLB during FSS. The RA consisted of a beta-gamma and gamma only scan over 100% of all accessible surfaces and the collection of 30 loose surface contamination samples. Six (6) concrete core samples were obtained at evenly distributed locations, and an additional five (5) cores were obtained at areas of elevated activity identified during the scan survey. Eleven (11) concrete core samples were collected from the floor and walls in the survey unit. The cores were 3 in diameter and 6 deep. Table 3-1 below summarizes the results from the concrete core analyses using the on-site gamma spectroscopy system. Only the top half-inch of the puck from each core was analyzed with the exception of B1-010-001-CJFC-009-CV 0.5-1 and B1-010-001-CJFC-011-CV 0.5-1. Table 3 Reactor Building Basement Continuing Characterization Concrete Core Analysis Summary - On-site Cs-137 Puck Activity Sample ID Surface (pCi/g) B1-010-001-CJFC-C01-CV 0-0.5" Top 4.21E-02 B1-010-001-CJFC-C01-CV 0-0.5" Bottom 0.00E+00 B1-010-001-CJFC-C02-CV 0-0.5" Top 1.86E-01 B1-010-001-CJFC-C02-CV 0-0.5" Bottom 9.93E-02 B1-010-001-CJFC-C03-CV 0-0.5" Top 5.02E-02 B1-010-001-CJFC-C03-CV 0-0.5" Bottom 3.50E-01 B1-010-001-CJFC-C04-CV 0-0.5" Top 1.71E-01 B1-010-001-CJFC-C04-CV 0-0.5" Bottom 5.27E-01 B1-010-001-CJFC-C05-CV 0-0.5" Top 1.72E-01 B1-010-001-CJFC-C05-CV 0-0.5" Bottom 3.32E-01 6
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 Cs-137 Puck Activity Sample ID Surface (pCi/g) B1-010-001-CJFC-C06-CV 0-0.5" Top 3.40E-01 B1-010-001-CJFC-C06-CV 0-0.5" Bottom 3.15E-01 B1-010-001-CJFC-C07-CV 0-0.5" Top 2.80E-01 B1-010-001-CJFC-C07-CV 0-0.5" Bottom 0.00E+00 B1-010-001-CJFC-C08-CV 0-0.5" Top 2.79E-01 B1-010-001-CJFC-C08-CV 0-0.5" Bottom 4.86E-01 B1-010-001-CJFC-C09-CV 0-0.5" Top 4.77E+01 B1-010-001-CJFC-C09-CV 0-0.5" Bottom 2.03E+01 B1-010-001-CJFC-C09-CV 0.5-1 Top 3.50E-01 B1-010-001-CJFC-C09-CV 0.5-1 Bottom 6.98E-03 B1-010-001-CJFC-C10-CV 0-0.5" Top 4.40E-01 B1-010-001-CJFC-C10-CV 0-0.5" Bottom 3.39E-01 B1-010-001-CJFC-C11-CV 0-0.5" Top 9.47E+00 B1-010-001-CJFC-C11-CV 0-0.5 Bottom 4.02E+00 B1-010-001-CJFC-C11-CV 0.5-1 Top 3.37E-01 B1-010-001-CJFC-C11-CV 0.5-1 Bottom 1.02E-01 Note: Bold values indicate activity above MDC Cs-137 was detected in concentrations above MDC in two (2) of the eleven (11) pucks analyzed. No other ROC were identified in the continuing characterization concrete cores. The on-site gamma spectroscopy reports are provided in Attachment 7. The top half-inch pucks from concrete core samples B1-010-001-CJFC-C04-CV, B1-010-001-CJFC-C09-CV, and B1-010-001-CJFC-C11-CV were sent off-site to GEL Laboratories for gamma spectroscopy and HTD analysis of the full suite of ROC. Table 3-2 summarizes the results of the off-site analyses. 7
FSS RELEASE RECORD - REVISION 1 REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Table 3 Reactor Building Basement Continuing Characterization Concrete Core Analysis Summary - Off-site B1-010-001-CSFC-C04-CV B1-010-001-CSFC-C09-CV B1-010-001-CSFC-C11-CV Radionuclide (pCi/g) (pCi/g) (pCi/g) Am-241 2.37E-03 3.12E-04 -1.67E-03 Am-243 -7.80E-03 -5.57E-03 9.25E-03 Cm-243/244 -6.02E-03 -3.69E-03 -1.38E-02 Np-237 0.00E+00 -5.17E-04 3.27E-03 Pu-238 1.25E-02 4.76E-03 -2.14E-02 Pu-239/240 1.21E-02 -1.10E-02 -3.73E-03 Pu-241 1.71E+00 2.52E-01 9.58E-01 Ni-59 1.88E-01 6.84E-01 6.84E-01 Cs-137 3.56E-02 4.82E+01 1.10E+01 Co-60 4.03E-02 6.72E-02 3.21E-03 Eu-152 1.68E-01 -2.96E-01 4.55E-02 Eu-154 -6.38E-03 -9.13E-02 7.01E-03 Eu-155 1.68E-01 1.95E-01 1.73E-01 Nb-94 -7.60E-02 6.47E-02 4.12E-02 Sr-90 8.01E-03 -2.56E-02 2.30E-01 H-3 -3.65E+00 -2.41E+00 -1.22E+00 C-14 -1.10E+00 -2.96E-01 -3.03E+00 Tc-99 6.91E-01 -1.48E-02 -1.65E-02 Fe-55 -4.52E-01 1.66E+00 3.42E+00 Ni-63 -1.45E+00 -2.94E-01 -1.31E-02 Note: Bold values indicate activity above MDC 8
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REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 R ' *OLUIWNS Cs-137 was positively identified in two (2) of the three (3) core samples. No other ROC were identified in the core samples sent off-site. An additional RA was conducted to evaluate the soil adjacent to and beneath the Reactor Building. Vertical soil borings were performed at eight locations around the perimeter of the Reactor Building, and diagonal soil borings were performed at four locations. At each location, two soil samples were collected. In total, 26 soils samples were collected (two at each location plus two QC samples). Cs-137 was detected at concentrations above MDC in four of the samples, with a maximum concentration of 3.40E-01 pCi/g. No other ROC were positively identified. Four of the soil boring samples were sent off-site to GEL Laboratories for analysis of the full suite of radionuclides. Only Cs-137 was positively identified in the analyses of the vertical borings. Cs-137 was not detected in the diagonal borings performed to collect sample below the Reactor Building. The GEL Laboratories analytical reports are provided in Attachment 8. Table 3 Continuing Characterization Soil Borings Analysis Summary - Off-site B1-010-001- B1-010-001- B1-010-001- B1-010-001-Radionuclide CIGS-BG02- CIGS-BH02- CIGS-BJ02- CIGS-BK01-SB (pCi/g) SB (pCi/g) SB (pCi/g) SB (pCi/g) H-3 -9.50E-01 3.87E-01 7.13E-01 -2.39E-01 C-14 -2.11E-01 -3.37E+00 1.82E+00 -6.86E-01 Fe-55 2.10E+00 1.36E+00 2.29E+00 7.44E-01 Ni-59 -9.26E-01 2.05E-01 6.79E-01 1.95E+00 Co-60 1.42E-03 -1.65E-02 -5.00E-04 -1.00E-02 Ni-63 -9.05E-01 -1.76E+00 -1.66E+00 -8.80E-01 Sr-90 -8.69E-03 -1.07E-02 4.55E-02 5.75E-02 Nb-94 6.13E-03 -3.42E-03 -1.13E-02 -2.79E-03 Tc-99 1.01E-01 -2.42E-01 3.43E-01 -4.95E-01 Cs-137 5.35E-01 1.33E-01 4.64E-03 -5.04E-03 Eu-152 5.51E-03 -1.01E-02 8.60E-03 -1.21E-02 Eu-154 -2.52E-02 -4.41E-02 1.34E-02 -1.49E-02 Eu-155 5.29E-03 -2.97E-02 6.07E-02 6.89E-03 Np-237 -7.71E-04 -1.06E-03 8.98E-04 6.32E-04 Pu-238 -6.16E-03 5.82E-03 -1.08E-02 -4.78E-03 Pu-239/240 -8.02E-03 4.15E-04 -9.27E-03 1.09E-02 Pu-241 3.05E-01 7.48E-01 9.11E-01 -1.63E-01 Am-241 1.51E-02 2.93E-02 9.43E-03 4.67E-03 Am-243 4.42E-02 -5.30E-03 -2.59E-03 1.61E-02 Cm-243/244 -7.32E-03 3.19E-04 1.78E-02 1.26E-02 Note: Bold values indicate positively identified radionuclide activities. Section 5.1 of the LTP states that the actual Insignificant Contributor (IC) dose will be calculated for each individual sample result using the DCGLs from TSD RS-TD-313196-004, LACBWR Soil DCGL, Basement Concrete DCGL, and Buried Pipe DCGL, Table 35 (Reference 6) for basement structures. If the IC dose calculated is less than the IC dose 9
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 assigned for DCGL adjustment, then no further action will be taken. If the actual IC dose calculated from the sample result is greater than the IC dose assigned for DCGL adjustment, then a minimum of five (5) additional investigation samples will be taken around the original sample location. Each investigation sample will be analyzed by the on-site gamma spectroscopy system and sent for HTD analysis (full suite of radionuclides from LTP Table 5-1). As with the original sample, the actual IC dose will be calculated for each investigation sample. In this case, the actual calculated maximum IC dose from an individual sample observed in the survey unit will be used to readjust the DCGLs in that survey unit. If the maximum IC dose exceeds 10%, then the additional radionuclides that were the cause of the IC dose exceeding 10% will be added as additional ROC for that survey unit. The survey unit-specific DCGLs used for compliance, the ROC for that survey unit, and the survey data serving as the basis for the IC dose adjustment will be documented in the release record for the survey unit. An assessment of the results of continuing characterization confirmed that the IC dose is unchanged. The maximum calculated IC dose was 0.0374 mrem/yr for the concrete core samples and 0.0573 mrem/yr for the soil samples, which is below the 2.5 mrem/yr limit provided in the LTP for DCGL adjustment. Based upon review of the historical information, the results of the characterization survey data, and completion of a final Survey Unit Classification Worksheet, the correct final classification of survey unit B1-010-001 was determined to be Class 1.
- 4. DATA QUALITY OBJECTIVES FSS planning and design relies on a properly executed Data Quality Objective (DQO) process to ensure, through compliance with explicitly defined inputs and boundaries, that the primary objective of the survey is satisfied. The DQO process is described in the LACBWR LTP in accordance with MARSSIM. The appropriate design for a given survey was developed using the DQO process as outlined in Appendix D of MARSSIM.
The DQO process incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis. Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition. The baseline condition is technically known as the null hypothesis. Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection. In designing the survey plan, the underlying assumption, or null hypothesis was 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 10
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 release criteria. Therefore, the survey unit would satisfy the primary objective of the FSS sample plan. The primary objective of the FSS sample plan is to demonstrate that the level of residual radioactivity in survey unit B1-010-001 did not exceed the release criteria specified in the LTP and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA). LaCrosseSolutions TSD RS-TD-313196-001, Radionuclides of Concern during LACBWR Decommissioning (Reference 7) established the basis for an initial suite of potential ROC for decommissioning. LTP Chapter 2 provides detailed characterization data that describes current contamination levels in the basements and soils from the characterization campaign conducted from September 2014 through August 2015. The initial survey data for basements was based on core samples obtained from the walls and floors of the Reactor Building, Waste Treatment Building (WTB), and the balance of the basement structures (primarily the Piping Tunnels) at biased locations with elevated contact dose rates, contamination levels, and/or evidence of leaks/spills. During subsequent characterizations, additional cores were obtained from the Reactor Building and the Waste Gas Tank Vault (WGTV). TSD RS-TD-313196-001 evaluates the results of the concrete core analysis data from the Reactor Building, WTB, Piping Tunnels and WGTV and refines the initial suite of potential ROC by evaluating the dose significance of each radionuclide. Insignificant dose contributors were determined consistent with the guidance contained in Section 3.3 of NUREG-1757, Volume 2, Revision 1, Consolidated Decommissioning Guidance - Characterization, Survey, and Determination of Radiological Criteria, Final Report (Reference 8). In all soil and concrete scenarios, Cs-137, Co-60, Sr-90, Eu-152 and Eu-154 contribute nearly 100% of the total dose. The remaining radionuclides were designated as insignificant dose contributors and are eliminated from further detailed evaluation. Therefore, the final ROCs for LACBWR soil, basement concrete and buried piping are Cs-137, Co-60, Sr-90, Eu-152 and Eu-154. LTP Chapter 6, Section 6.14.1 discusses the process used to derive the ROC for the decommissioning of LACBWR, including the elimination of insignificant dose contributors (IC) from the initial suite. Table 4-1 presents the ROC for the decommissioning of basements at LACBWR and the normalized mixture fractions for the Reactor Building Basement based on the radionuclide mixture. 11
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 Table 4 Reactor Building Basement Dose Significant Radionuclides and Mixture Fraction of Total Activity Radionuclide (normalized)(1) Co-60 0.074 Sr-90 0.123 Cs-137 0.796 Eu-152 0.003 Eu-154 0.004 (1) Based on maximum percent of total activity from Table 22 of RS-TD-313196-001, normalized to one for the dose significant radionuclides. LTP, Section 5.2 states that each radionuclide-specific Base Case DCGL is equivalent to the level of residual radioactivity (above background levels) that could, when considered independently, result in a Total Effective Dose Equivalent of 25 mrem/yr to an Average Member of the Critical Group. To ensure that the summation of dose from each source term is 25 mrem/yr or less after all FSS is completed, the Base Case DCGLs are reduced based on an expected, or a priori, fraction of the 25 mrem/yr dose limit from each source term. The reduced DCGLs, or Operational DCGLs can be related to the Base Case DCGLs as an expected fraction of dose based on an a priori assessment of what the expected dose should be based on the results of site characterization, process knowledge and the extent of planned remediation. The Operational DCGL is then used as the DCGL for the FSS design of the survey unit (calculation of surrogate DCGLs, investigations levels, etc.). Details of the Operational DCGLs derived for each dose component and the basis for the applied a priori dose fractions are provided in LC-FS-TSD-002, Operational Derived Concentration Guideline Levels for Final Status Survey (Reference 9). The dose contribution from each ROC is accounted for using the SOF to ensure that the total dose from all ROC does not exceed the dose criterion. A Base Case DCGL that is established for the average residual radioactivity in a survey unit is equivalent to a DCGLW. At LACBWR, compliance is demonstrated through the summation of dose from five (5) distinct source terms for the end-state (basements, soils, buried pipe, above ground structures, and groundwater). When applied to backfilled basements below the 636 foot elevation, the DCGLs are expressed in units of activity per unit of area (pCi/m2). The Basement Fill Model (BFM) applies to the steel-reinforced concrete walls and floors of the backfilled Reactor Building and WGTV below the 636 foot elevation. BFM DCGLs (DCGLB) apply to basement concrete and are calculated in LTP Chapter 6, Section 6.13. The insignificant dose contributor percentages for the most limiting basement scenario was 12
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 used to adjust the DCGLB to account for the dose from the eliminated insignificant contributor radionuclides. The DCGLB values for the Reactor Building Basement from LTP Chapter 5, Section 5.2.1 are reproduced below in Table 4-2. Table 4 Reactor Building Basement Base Case DCGLs Reactor Building Radionuclide Basement DCGLB (pCi/m2) Co-60 5.16E+06 Sr-90 1.45E+07 Cs-137 2.17E+07 Eu-152 1.19E+07 Eu-154 1.10E+07 The Operational DCGLs are then used as the DCGL for the FSS design of the survey unit (calculation of surrogate DCGLs, investigation levels, etc.). The BFM OpDCGLB for the unrestricted release of the Reactor Building Basement survey unit from LTP Chapter 5, Section 5.2.2 are provided in Table 4-3. Table 4 Reactor Building Basement Operational DCGLs Reactor Building Radionuclide Basement OpDCGLB (pCi/m2) Co-60 3.61E+05 Sr-90 1.02E+06 Cs-137 1.52E+06 Eu-152 8.33E+05 Eu-154 7.71E+05 Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the Operational DCGL. The Canberra ISOCS was selected as the primary instrument used to perform FSS of basement surfaces. Response checks were required prior to issuance and after use. Control and accountability of ISOCS units was required to assure data quality. As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. The actual recorded value was used as the recorded FSS result for 13
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 measurement and/or sample values that are less than MDC. Negative values were recorded as zero. Results were not reported as less than MDC (< MDC). Sample report summaries included unique sample identification, analytical method, radionuclide, result, uncertainty, laboratory data qualifiers, units, and the observed MDC. In accordance with the LTP, for laboratory analysis, MDCs less than 10% of the Operational DCGL were preferable while MDCs up to 50% of the Operational DCGL were acceptable. The minimum acceptable MDC for measurements obtained using field instruments was 50% of the applicable Operational DCGL.
- 5. SURVEY DESIGN The level of effort associated with planning a survey is based on the complexity of the survey unit and nature of the hazards. Guidance for preparing FSS plans is provided in procedure LC-FS-PR-002, Final Status Survey Package Development.
The DQO process determined that Co-60, Sr-90, Cs-137, Eu-152, and Eu-154 would be the ROC in survey unit B1-010-001. During FSS, concentrations for the HTD ROC Sr-90 are inferred using a surrogate approach. Cs-137 is the principle surrogate radionuclide for Sr-
- 90. Both Sr-90 and Cs-137 was positively detected in all thirty (30) concrete core samples assessed in the Reactor Building, Piping Tunnels, and WTB. For the Reactor Building Basement, Sr-90 was not detected in any of the eleven (11) core samples assessed during continuing characterization. The 95% Upper Confidence Limit (UCL) of the Cs-137 fractions was chosen to represent the overall nuclide mix for soils/buried pipe, the Reactor Building, and the Reactor Building Basement. The surrogate ratio for the Reactor Building Basement is given in Table 5-1.
Table 5 Reactor Building Basement Surrogate Ratio Radionuclides Ratio Sr-90/Cs-137 0.5 The equation for calculating a surrogate DCGL is as follows: Equation 1 1
=
1 2 3 [( ) + ( ) + ( ) + ( )] 2 3 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate 14
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide Using the Operational DCGLs presented in Table 4-3 and the ratio from Table 5-1, the following surrogate calculation was performed: Equation 2 1 (137) = = 8.71 + 05 /2 1 0.5 [(1.52 + 06 ) + (1.02 + 06 )] (137) (90) The surrogate Operational DCGL that was used for Cs-137 in this survey unit for direct comparison of measurement results to demonstrate compliance was 8.71E+05 pCi/m2. The action levels for survey unit B1-010-001 are based on the Operational DCGL and are presented in Table 5-2. Table 5 Action Levels for Survey Unit B1-010-001 OpDCGLB ROC (pCi/m2) Co-60 3.61E+05 Cs-137 8.71E+05(1) Eu-152 8.33E+05 Eu-154 7.71E+05 (1) Based on the surrogate adjusted DCGL of Cs-137 while inferring Sr-90. The Sign Test was selected as the non-parametric statistical test. The use of the Sign Test did not require the selection or use of a background reference area, which simplified survey design and implementation. The Elevated Measurement Comparison (EMC) does not apply to this survey unit. At LACBWR, EMC only applies to Class 1 open land areas. Sample size determination for FSS basement structures is addressed in LTP Chapter 5, Section 5.5.2.2. To ensure that the number of ISOCS measurements, based on the necessary areal coverage in a basement surface FSS unit, was sufficient to satisfy a statistically based sample design, a calculation was performed to determine sample size. If the sample size based on the statistical design required more ISOCS measurements than the number of 15
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 ISOCS measurements required by the areal coverage, then the number of ISOCS measurements was adjusted to meet the larger sample size. The number of measurements for FSS was determined in accordance with procedure LC-FS-PR-002. The relative shift (/) for the survey unit data set is defined as shift (), which is the Upper Boundary of the Gray Region (UBGR), or the DCGL (SOF of 1), minus the Lower Bound of the Gray Region (LBGR) (SOF of 0.5), divided by sigma (), which is the standard deviation of the data set used for survey design. The optimal value for / should range between one (1) and three (3). The largest value the / can have is three (3). If the
/ exceeds three (3), then the value of three (3) will be used for /. In the absence of prior survey data, the survey design used the MARSSIM recommended standard deviation value of 0.3. The / for survey unit B1-010-001 was calculated as follows:
Equation 3
/ = 0.5/0.3 = 1.67 Both the Type I error, or value, and the Type II error, or value, were set at 0.05. The sample size for use with the Sign Test from Table 5.5 of MARSSIM that equates to the Type I and Type II error of 0.05 and a relative shift of 1.67 is an N value of seventeen (17).
The required areal scan coverage for a Class 1 basement survey unit is 100%. The LTP requires that sufficient measurements be taken in a Class 1 FSS unit to ensure that 100% of the surface area was surveyed. The number of ISOCS measurements required in each FSS unit can be calculated as the quotient of the ISOCS Field-of-View (FOV) divided into the surface area required for areal coverage. Table 5-3 presents the minimum number of ISOCS measurements that were required for survey unit B1-010-001 based on a measurement FOV of 28 m2. Table 5 Number of ISOCS Measurements based on Areal Coverage Minimum
# of ISOCS Area Areal Measurements Survey Unit Classification Coverage (based on 28 m2 (m2) (% of Area)
FOV) Reactor Building Basement Class 1 512 100% 18 The ISOCS FOV was overlapped to ensure that there were no un-surveyed corners and gaps. The adjusted minimum number of ISOCS measurements in the Reactor Building Basement to account for overlap is provided in Table 5-4. 16
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 Table 5 Adjusted Minimum Number of ISOCS Measurements Required Adjusted # of Adjusted Adjusted Areal ISOCS Areal Areal Survey Unit Classification Coverage Measurements Coverage Coverage (based on 16 m2 (% of (m2) (m2) FOV) Area) Reactor Building Class 1 512 43 512 100% Basement The areal scan coverage requirements for FSS of structures as specified in the LTP are commensurate with the probability that a small area of elevated activity could exist within an FSS unit in a concentration exceeding the Base Case DCGL and the likelihood that such an area would not be detected by the FSS ISOCS measurements. It is highly unlikely that the ISOCS, with a nominal FOV of approximately 28 m2 would not detect and account for elevated areas. The primary basis used to determine reasonable areal coverage for the ISOCS measurements is the potential for the Operational DCGL to be exceeded. The criterion for selecting reasonable and risk-informed areal coverage is based on a graded approach similar to the guidance for scan surveys during FSS provided in MARSSIM, where the coverage is based on the expected fraction of the DCGL (in this case the Operational DCGL). All ISOCS measurement locations collected for survey unit B1-010-001 are provided on the map in Attachment 1 of this document. The coordinates for all of the ISOCS measurement locations were conspicuously marked to designate where to position the survey rig to the center-point of the instrument FOV. The ISOCS detector was then positioned either vertically or horizontally and adjacent to the surface at the center-point of each designated floor or wall measurement location. Each survey measurement location would then be reproducible utilizing permanent markings on the survey unit floor and walls and annotated on the survey map and Attachment 14 of the sample plan, FSS Samples/Measurements Identification and Coordinates. The implementation of quality control measures as referenced by LTP Chapter 5, Section 5.9 and LaCrosseSolutions LC-QA-PN-001, Final Status Survey Quality Assurance Project Plan (QAPP) (Reference 10) includes the collection of a replicate measurement at 5% of the measurements taken in a survey unit with the locations selected at random. Three (3) ISOCS measurements were selected randomly for the replicate measurements for this survey unit. In accordance with Section 5.1 of the LTP, concrete core samples are required to be collected at 10% of the ISOCS measurement locations during FSS for HTD analysis. The 17
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 eleven (11) continuing characterization concrete cores were used to satisfy the requirement in the LTP, as they were representative of the survey units end state condition. See Section 3 of this report for the data concerning the concrete cores. As a Class 1 survey unit, Table 5-4 specifies that a minimum of 512 m2, or 100% of the accessible surface area, in this structural basement survey unit will be subjected to scan coverage. The minimum number of ISOCS measurements required to fully cover the 512 m2 surface area is forty-three (43). Two (2) systematic measurements were added during survey design to fully ensure coverage of gaps. The surface area covered by a single ISOCS measurement is large, and the FOV of the measurement becomes a substitute for scanning that is typically performed by moving a hand-held detector over the surface in question. The majority of systematic ISOCS measurements that were taken during the FSS of the Reactor Building Basement were obtained at a stand-off distance of 3 meters, which resulted in a FOV for each measurement of 28 m2. Seven (7) systematic measurements were taken at a stand-off distance of 2 meters, which resulted in a FOV of 12.56 m2. The six (6) judgmental ISOCS measurements were collected at a stand-off distance of 0.5 meters, which correlates to a ISOCS FOV of 0.79 m2. To achieve 100% areal coverage for the 512 m2 of floor and wall surfaces that constitute this survey unit, along with the minimum of 5% replicate measurements, 54 ISOCS measurements were taken (45 systematic, 6 judgmental, 3 replicate). All of the ISOCS measurements were collected using the circular plane geometry, although varied geometries were necessary due to the structural anomalies encountered within the survey unit (use of different stand-off distances). ISOCS geometries specifically employed within this survey unit are provided in Attachment 2 of this report. Maps of the surface area scanned by the ISOCS FOV are provided in Attachment 1. For this Class 1 basement structure survey unit, the Investigation Levels for ISOCS measurement results are those levels specified in LTP Chapter 5, Table 5-16, and are reproduced below in Table 5-5. Table 5 Investigation Levels Direct Investigation Classification Scan Investigation Levels Levels
>Operational DCGL or >MDCscan if Class 1 MDCscan is greater than Operational >Operational DCGL DCGL Table 5-6 provides a synopsis of the survey design for survey unit B1-010-001.
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 Table 5 Synopsis of Survey Design Feature Design Criteria Basis Survey Unit Surface LTP Ch. 5, Table 5-13 and 512 m2 Area Table 5-14 UBGR = SOF of 1 LBGR = SOF of 0.5 Number of Type I error = 0.05 Systematic 17 Type II error = 0.05 Measurements (N)
/ = 1.67 MARSSIM Table 5.5 Adjusted Number of Based on 100% scan 43 Systematic coverage accounting for 45 (actual number obtained)
Measurements overlap Co-60: 3.61E+05 Sr-90: 1.02E+06 Operational DCGLs for DCGLs Cs-137: 1.52E+06 Reactor Building Basement, Eu-152 : 8.33E+05 (LTP Chapter 5, Table 5-4) Eu-154: 7.71E+05 Investigation Level >Operational DCGL (LTP Chapter 5, Table 5-16) Scan Areal Coverage 512 m2 or 100% areal coverage (LTP Chapter 5, Table 5-15) Number of Minimum of 1 ISOCS Judgmental 6 Measurement per Sample Measurements Plan 3 measurements selected randomly for QC (LTP Chapter 5, Section 5.9) replicate measurement analysis 10% of ISOCS Measurements, HTD (LTP Chapter 5, Section 5.1) Minimum of 2 19
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001
- 6. SURVEY IMPLEMENTATION For survey unit B1-010-001, compliance with the unrestricted release criteria was demonstrated through the use of ISOCS for direct measurements.
A walkdown and turnover survey was satisfactorily performed in the Reactor Building Basement in accordance with the Isolation and Control requirements of procedure LC-FS-PR-010, Isolation and Control for Final Status Survey (Reference 11). The Reactor Building Basement was deemed acceptable for turnover and FSS commenced on March 27, 2019 under the FSS sample plan, which included DQOs, survey design, detailed FSS instructions, job safety analysis, and related procedures for reference. A Field Log was used to document field activities and other information pertaining to the performance of the FSS. FSS field activities were projected to take four (4) working days to complete. Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job. The survey required field activities were performed during normal working hours and concluded on March 29, 2019. Prior to implementing the sample plan for the FSS of the Reactor Building Basement structure, the physical condition of the concrete surfaces to be surveyed were assessed to ensure that the geometry was not significantly changed from that assumed in LC-FS-TSD-001, Use of ISOCS for FSS of End State Sub Structures at LACBWR (Reference 12). ISOCS measurements were acquired using the circular plane geometry, which assumed a circular plane source with a contaminant depth of 0.5 inches. With the 90-degree collimation shield installed and a source to detector distance of 3 meters, this orientation corresponded to a nominal FOV of 28 m2. A guide attached to the detector assembly, in the form of a plumb-bob or wooden stud, was used to establish a consistent source to detector distance and center the detector over the selected measurement location. The ISOCS measurement locations specified in FSS sample plan for survey unit B1-010-001 were marked based on the grid coordinates provided in the maps. See Attachment 2 of this report for the ISOCS Geometry Composer Reports. A total of forty-five (45) systematic ISOCS measurements were collected in the survey unit. Six (6) judgmental measurements were collected, and three (3) replicate measurements were also acquired in the Reactor Building Basement survey locations #5, #16 and #18. The ISOCS detector face was oriented perpendicular to the surface of interest represented by the grid coordinate. See Picture 1 below for an example of an ISOCS measurement being conducted. 20
FSS RELEASE RECORD - REVISION 1 REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 6 ISOCS Measurement
- 7. SURVEY RESULTS The SOF or unity rule is applied to the data used for the survey planning, and data evaluation and statistical tests for basement surfaces, since multiple radionuclide-specific measurements will be performed or the concentrations inferred based on known relationships. The SOF or unity rule is the mathematical test used to evaluate compliance with radiological criteria for license termination when more than one radionuclide has been determined to be potentially present.
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 The equation for the unity rule is: Equation 4 C1 C2 Cn
.......... .. 1 DCGL1 DCGL 2 DCGL n Where: Cn = concentration of radionuclide n DCGLn = DCGL of radionuclide n.
The application of the unity rule serves to normalize the data to allow for an accurate comparison of the various data measurements to the release criteria. When the unity rule is applied, the DCGLW (used for the nonparametric statistical test) becomes 1. The DCGLB are directly analogous to the DCGLW as defined in MARSSIM. The use and application of the unity rule was performed in accordance with Section 4.3.3 of MARSSIM. As described in LTP Chapter 5, Section 5.10.3.2, the Sign Test was used to evaluate the measured residual radioactivity against the dose criterion. The SOF for each measurement was used as the sum value for the Sign Test. The Sign Test then demonstrated that the mean activity for each ROC was less than the OpDCGLB at a Type 1 decision error of 0.05. For building surfaces, areas of elevated activity were defined as any area identified by measurement/sample (systematic or judgmental) that exceeded the OpDCGLB but was less than the DCGLB. Any area that exceeded the DCGLB would have required remediation. The SOF (based on the OpDCGLB) for a systematic or judgmental measurement/sample(s) can exceed 1 without remediation as long as the survey unit passes the Sign Test, and the mean SOF (based on the OpDCGLB) for the survey unit does not exceed one. Once the survey data set passes the Sign Test (using Operational DCGLs), then the mean radionuclide activity (pCi/m2) for each ROC from systematic measurements along with any identified elevated areas from systematic and judgmental measurement/samples can be used with the Base Case DCGLs to perform a mean SOFB calculation. The dose from residual radioactivity assigned to the FSS unit is the mean SOFB multiplied by 25 mrem/yr. Direct measurement locations were denoted on the concrete walls and floor of the Reactor Building Basement using the dimensions on the survey map as guidance. See Figure 16-1 on Attachment 1 for a depiction of all measurement locations. The systematic measurement population consisted of 45 direct measurements that were acquired using the ISOCS. In total, 54 ISOCS measurements were collected, including the systematic, judgmental, and QC measurements. A breakdown of the total ISOCS measurements and SOF for systematic measurements compared to the OpDCGLB is provided in Table 7-1. A summary of the results of the 45 ISOCS measurements taken for non-parametric statistical testing when compared to the DCGLB is provided in Table 7-2. 22
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 The complete ISOCS measurement and gamma spectroscopy reports are presented in Attachment 6. Table 7 Summary of Systematic, Judgmental, and QC Measurements Total Number of Systematic Measurements 45 Number of Quality Control Measurements 3 Number of Judgmental/Investigational Measurements 6 Total Number of Measurements 54 Mean Systematic Gamma Measurement SOF (1) 0.0061 Max Individual Systematic Gamma Measurement SOF (1) 0.0232 Number of Systematic Gamma Measurements with SOF > 1 (1) 0 (1) Based on the OpDCGLB Table 7 Summary of ISOCS Systematic Measurement Statistical Quantities Mean Median Max Min Std. Dev. BcDCGL Avg SOF Avg Dose ROC (pCi/m ) 2 (pCi/m ) 2 (pCi/m )2 (pCi/m ) 2 (pCi/m ) 2 (pCi/m ) 2 per ROC per ROC Co-60 3.90E+02 2.88E+02 1.22E+03 0.000E+00 3.59E+02 5.16E+06 7.57E-05 1.89E-03 Sr-90 4.39E+02 2.18E+02 3.51E+03 0.000E+00 6.62E+02 1.45E+07 3.03E-05 7.57E-04 Cs-137 8.78E+02 4.37E+02 7.03E+03 0.000E+00 1.32E+03 2.17E+07 4.05E-05 1.01E-03 Eu-152 1.34E+03 8.82E+02 6.08E+03 0.000E+00 1.47E+03 1.19E+07 1.13E-04 2.81E-03 Eu-154 1.82E+03 1.51E+03 9.17E+03 0.000E+00 1.59E+03 1.10E+07 1.65E-04 4.13E-03 The total mean SOF for the Reactor Building Basement, based on the mean concentration for each ROC as measured by the systematic measurement population when compared against the DCGLB, is 0.0004. This SOF equates to a dose of 0.0106 mrem/yr. Six (6) judgmental ISOCS measurement were collected within the survey unit. The judgmental ISOCS measurement results are presented in Table 7-3. 23
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 Table 7 Summary of ISOCS Judgmental Measurements Cs-137 Co-60 Eu-152 Eu-154 Sr-90 Measurement ID (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B1-010-001-FJFC-D44-GM 8.58E+05 2.58E+03 0.00E+00 4.77E+04 4.29E+05 B1-010-001-FJFC-D45-GM 8.04E+05 1.88E+04 5.58E+04 2.48E+04 4.02E+05 B1-010-001-FJFC-D46-GM 2.07E+05 1.65E+04 7.00E+04 5.37E+04 1.04E+05 B1-010-001-FJFC-D47-GM 1.64E+05 2.68E+03 0.00E+00 6.83E+04 8.18E+04 B1-010-001-FJFC-D48-GM 4.38E+04 1.21E+04 0.00E+00 2.48E+04 2.19E+04 B1-010-001-FJFC-D49-GM 1.02E+05 1.01E+04 0.00E+00 9.37E+04 5.12E+04 Note: Bold values indicate activity greater than MDC. Two (2) judgmental measurements, B1-010-001-FJFC-D44-GM and B1-010-001-FJFC-D45-GM, exceeded the OpDCGLB, at a maximum SOF of 1.0737. The mean SOF of judgmental measurements when compared to the OpDCGLB is 0.5388 and the mean SOF when compared to the DCGLB is 0.03779. Because judgmental measurements are outside of the systematic measurement population, an area-weighted SOF for the two (2) elevated measurements is calculated and added to the average systematic measurement SOF, which is then used to calculate the overall dose assigned to the basement survey unit. The equation for calculating the area-weighted SOF (Equation 5-5 in the LTP) is provided below. Equation 5 ( )
= +
=1 [ x ( )]
where: SOFB = SOF for structural surface survey unit within a Basement using Base Case DCGLs Mean ConcB ROCi = Mean concentration for the systematic measurements taken during the FSS of structural surface in survey unit for each ROCi Base Case DCGLB ROCi = Base Case DCGL for structural surfaces (DCGLB) for each ROCi Elev ConcB ROCi = Concentration for ROCi in any identified elevated area (systematic or judgmental) SAElev = surface area of the elevated area SASU = adjusted surface area of FSS unit for DCGL calculation 24
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 The total SOF for the Reactor Building Basement was calculated as follows: Equation 6
= 0.0004 + 0.0002 = 0.0006 The total SOF assigned to the Reactor Building Basement survey unit is 0.0006, which equates to a dose of 0.015 mrem/yr.
The implementation of required QC measures included the collection of three (3) additional ISOCS measurements at locations throughout the Reactor Building Basement for replicate measurement analysis. The replicate ISOCS measurement results are provided in Table 7-
- 4. The concentration for Sr-90 is inferred based on the ratio given in Table 5-1.
Table 7 Summary of Replicate ISOCS Measurements for QC Cs-137 Co-60 Eu-152 Eu-154 Sr-90 Measurement ID (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B1-010-001-QSFC-D05-GM 5.31E+02 5.76E+02 0.00E+00 1.52E+03 2.66E+02 B1-010-001-QSFC-D16-GM 5.09E+02 9.36E+02 0.00E+00 2.66E+03 2.55E+02 B1-010-001-QSFC-D18-GM 3.15E+02 4.23E+02 2.13E+02 2.21E+03 1.58E+02 Note: Bold values indicate activity greater than MDC. The complete ISOCS gamma spectroscopy reports are presented in Attachment 6.
- 8. QUALITY CONTROL Three (3) replicate measurements were taken during the FSS of this basement structure. The measurement results were evaluated using USNRC acceptance criteria specified in Inspection Procedure No. 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring (Reference 13). In the case of all three (3) pairs of standard and comparison measurements, there was acceptable QC agreement. Refer to Attachment 4 for data and quality control analysis results.
- 9. INVESTIGATIONS AND RESULTS No investigations were performed during the performance or analyses of the survey.
- 10. REMEDIATION AND RESULTS No radiological remedial action as described by MARSSIM Section 5.4 was performed in this survey unit as a result of the FSS. Chapter 4 of the LTP determined that remediation 25
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 beyond that required to meet the release criteria is unnecessary and that the remaining residual radioactivity in the structure was ALARA.
- 11. CHANGES FROM THE FINAL STATUS SURVEY PLAN There were no addendums to the FSS plan.
- 12. DATA QUALITY ASSESSMENT The DQO sample design and data were reviewed in accordance with LC-FS-PR-008, Final Status Survey Data Assessment (Reference 14) for completeness and consistency.
Documentation was complete and legible. Surveys and the collection of measurements were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 1. The survey design had adequate power as indicated by the Retrospective Power Curve (see Attachment 5). The analytical results indicated that all systematic measurements were less than a SOF of one (1) when compared to the OpDCGLB. Two (2) judgmental measurements were identified with a SOF greater than one (1) when compared to the OpDCGLB, but less than a SOF of one (1) when compared to the DCGLB. The Sign Test (Attachment 3) was performed on the data and compared to the original assumptions of the DQOs. The evaluation of the Sign Test results clearly demonstrates that the survey unit passes the unrestricted release criteria, thus, the null hypothesis is rejected. The preliminary data review consisted of calculating basic statistical quantities (e.g., mean, median, standard deviation). All data was considered valid including negative values, zeros, values reported below the MDC, and values with uncertainties that exceeded two standard deviations. The mean and median values for each ROC were well below the respective Operational DCGLs. Also, the retrospective power curve shows that a sufficient number of measurements were collected to achieve the desired power. Therefore, the survey unit meets the unrestricted release criteria with adequate power as required by the DQOs. All graphical presentations are provided in Attachment 5.
- 13. ANOMALIES No anomalies were observed during the performance or analyses of the survey.
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001
- 14. CONCLUSION Survey unit B1-010-001 has met the DQOs of the FSS plan. The ALARA criteria as specified in Chapter 4 of the LTP were achieved. The EMC is not applicable to structural surfaces and remediation was not required.
All identified ROC were used for statistical testing to determine the adequacy of the survey unit for FSS. Evaluation of the data shows that none of the systematic ROC concentration values exceeds the OpDCGLB. Additionally, the two (2) elevated judgmental locations were evaluated and the dose was included in the total dose for the survey unit. The total SOF assigned to the Reactor Building Basement survey unit is 0.0006, which equates to a dose of 0.015 mrem/yr. The measurement data passed the Sign Test. The null hypothesis was rejected. The Retrospective Power Curve showed that adequate power was achieved. The survey unit is properly classified as Class 1. Therefore, in accordance with the LTP Section 5.10, the survey unit meets the release criteria. Survey unit B1-010-001 is acceptable for unrestricted release.
- 15. REFERENCES
- 1. LC-FS-PR-009, Final Status Survey Data Reporting
- 2. La Crosse Boiling Water Reactor License Termination Plan (LTP)
- 3. LC-FS-PR-002, Final Status Survey Package Development
- 4. NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)
- 5. La Crosse Boiling Water Reactor Historical Site Assessment (HSA)
- 6. RS-TD-313196-004, LACBWR Soil DCGL, Basement Concrete DCGL, and Buried Pipe DCGL
- 7. RS-TD-313196-001, Radionuclides of Concern during LACBWR Decommissioning
- 8. NUREG-1757, Volume 2, Revision 1, Consolidated Decommissioning Guidance -
Characterization, Survey, and Determination of Radiological Criteria, Final Report
- 9. LC-FS-TSD-002, Operational Derived Concentration Guideline Levels for Final Status Survey
- 10. LC-QA-PN-001, Final Status Survey Quality Assurance Project Plan (QAPP)
- 11. LC-FS-PR-010, Isolation and Control for Final Status Survey
- 12. LC-FS-TSD-001, Use of ISOCS for FSS of End State Sub Structures at LACBWR
- 13. USNRC Inspection Procedure No. 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring
- 14. LC-FS-PR-008, Final Status Survey Data Assessment 27
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- 16. ATTACHMENTS Attachment 1 - Figures and Maps Attachment 2 - ISOCS Geometries Attachment 3 - Sign Test Attachment 4 - Quality Control Assessment Attachment 5 - Graphical Presentations Attachment 6 - Measurement Analytical Reports Attachment 7 - Sample Analytical Reports Attachment 8 - GEL Laboratories Analytical Reports 28
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 ATTACHMENT 1 FIGURES AND MAPS 29
FSS RELEASE RECORD - REVISION 1 REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 16 Reactor Building Basement ISOCS Measurement Locations (1) C n NOR . ... SOUlli ,. WEST 1 D I l 16 23 "3/ ;j\j OE.SCRIPTJON REACTOR BUILDING ISOCS SAWLE LOCATIONS - WALLS DETAIL DATE 1().()5.16 DRAWING 15090101 - ISOCS L10 30
FSS RELEASE RECORD - REVISION 1 REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 16 Reactor Building Basement ISOCS Measurement Locations (2) DESCRIPTION REACTOR BUILDING ISOCS SAMPLE 1--- - - - - ~ LOCATIONS - NORTHERN HALF DATE 04/17/2019 DRAWING 15090101c - Bowl Samples - North 31
FSS RELEASE RECORD - REVISION 1 REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 16 Reactor Building Basement ISOCS Measurement Locations (3) DESCRIPTION REACTOR BUILDING !SOCS SAMPLE LOCATIONS - SOUTHERN HALF DATE 04/ 16/ 2019 DRAWING 15090101 - Bowl Samples - South 32
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 ATTACHMENT 2 ISOCS GEOMETRIES 33
A Geometry Composer Report CANBERRA Date: Tuesday, March 26, 2019 - 13:13:12
== Description:== Rx Bowl Concrete 0.5M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 0.5M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default) Detector: 3844f Collimator: 50mm-90d new (newISOCS 50mm side 90deg collimation [large hole collimator]) Environment: Temperature = 22 °C, Pressure = 760 mm Hg, Relative Humidity = 30% Integration: Convergence = 1.00%, MDRPN = 24 (16), CRPN = 24 (16) Dimensions (cm) No. Description d.1 d.2 d.3 d.4 d.5 d.6 Material Density Rel. Conc. 1 Side Walls 0 100 none 2 Layer 1 1.27 concrete 2.3 1.00 3 Layer 2 0 <none> 4 Layer 3 0 <none> 5 Layer 4 0 <none> 6 Layer 5 0 <none> 7 Layer 6 0 <none> 8 Layer 7 0 <none> 9 Layer 8 0 <none> 10 Layer 9 0 <none> 11 Layer 10 0 <none> 12 Absorber1 13 Absorber2 14 Source-Detector 50 0 0 0 0 List of energies for efficiency curve generation 59.5 88.0 122.1 200.0 400.0 661.7 900.0 1000.0 1173.2 1332.5 1836.0 CIRCULAR PLANE 0 14.3 0 0 Oir~tion Convention A Page 1 of 2
A Geometry Composer Report CANBERRA Date: Tuesday, March 26, 2019 - 13:13:12
== Description:== Rx Bowl Concrete 0.5M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 0.5M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default) Page 2 of 2
A Geometry Composer Report CANBERRA Date: Tuesday, March 26, 2019 - 13:14:36
== Description:== Rx Bowl Concrete 2M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 2M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default) Detector: 3844f Collimator: 50mm-90d new (newISOCS 50mm side 90deg collimation [large hole collimator]) Environment: Temperature = 22 °C, Pressure = 760 mm Hg, Relative Humidity = 30% Integration: Convergence = 1.00%, MDRPN = 24 (16), CRPN = 24 (16) Dimensions (cm) No. Description d.1 d.2 d.3 d.4 d.5 d.6 Material Density Rel. Conc. 1 Side Walls 0 400 none 2 Layer 1 1.27 concrete 2.3 1.00 3 Layer 2 0 <none> 4 Layer 3 0 <none> 5 Layer 4 0 <none> 6 Layer 5 0 <none> 7 Layer 6 0 <none> 8 Layer 7 0 <none> 9 Layer 8 0 <none> 10 Layer 9 0 <none> 11 Layer 10 0 <none> 12 Absorber1 13 Absorber2 14 Source-Detector 200 0 0 0 0 List of energies for efficiency curve generation 59.5 88.0 122.1 200.0 400.0 661.7 900.0 1000.0 1173.2 1332.5 1836.0 CIRCULAR PLANE 0 14.3 0 0 Oir~tion Convention A Page 1 of 2
A Geometry Composer Report CANBERRA Date: Tuesday, March 26, 2019 - 13:14:36
== Description:== Rx Bowl Concrete 2M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 2M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default) Page 2 of 2
A Geometry Composer Report CANBERRA Date: Tuesday, March 26, 2019 - 13:15:10
== Description:== Rx Bowl Concrete 3M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 3M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default) Detector: 3844f Collimator: 50mm-90d new (newISOCS 50mm side 90deg collimation [large hole collimator]) Environment: Temperature = 22 °C, Pressure = 760 mm Hg, Relative Humidity = 30% Integration: Convergence = 1.00%, MDRPN = 24 (16), CRPN = 24 (16) Dimensions (cm) No. Description d.1 d.2 d.3 d.4 d.5 d.6 Material Density Rel. Conc. 1 Side Walls 0 600 none 2 Layer 1 1.27 concrete 2.3 1.00 3 Layer 2 0 <none> 4 Layer 3 0 <none> 5 Layer 4 0 <none> 6 Layer 5 0 <none> 7 Layer 6 0 <none> 8 Layer 7 0 <none> 9 Layer 8 0 <none> 10 Layer 9 0 <none> 11 Layer 10 0 <none> 12 Absorber1 13 Absorber2 14 Source-Detector 300 0 0 0 0 List of energies for efficiency curve generation 59.5 88.0 122.1 200.0 400.0 661.7 900.0 1000.0 1173.2 1332.5 1836.0 CIRCULAR PLANE 0 14.3 0 0 Oir~tion Convention A Page 1 of 2
A Geometry Composer Report CANBERRA Date: Tuesday, March 26, 2019 - 13:15:10
== Description:== Rx Bowl Concrete 3M Comment: shielding with 90 deg collimator File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCULAR_PLANE\RxBowl Con 3M.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default) Page 2 of 2
FSS RELEASE RECORD - REVISION 1
~
REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 ATTACHMENT 3 SIGN TEST 40
FSS RELEASE RECORD - REVISION 1 REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Table 16 B1-010-001 Sign Test SOF
# 1-Ws Sign (Ws) 1 0.00781 0.99 +1 2 0.00614 0.99 +1 3 0.00454 1.00 +1 4 0.00409 1.00 +1 5 0.00614 0.99 +1 6 0.00249 1.00 +1 7 0.00175 1.00 +1 8 0.00195 1.00 +1 9 0.00416 1.00 +1 10 0.00479 1.00 +1 11 0.00804 0.99 +1 12 0.00522 0.99 +1 13 0.00448 0.99 +1 14 0.00496 1.00 +1 15 0.00411 1.00 +1 16 0.00472 1.00 +1 17 0.00347 1.00 +1 18 0.00934 1.00 +1 19 0.00362 0.99 +1 20 0.01588 1.00 +1 21 0.00206 0.98 +1 22 0.00759 1.00 +1 23 0.00683 0.99 +1 24 0.00419 0.99 +1 25 0.00855 1.00 +1 26 0.01002 0.99 +1 27 0.02319 0.99 +1 28 0.01990 0.98 +1 29 0.00095 0.98 +1 30 0.00228 1.00 +1 31 0.00483 1.00 +1 32 0.00176 1.00 +1 33 0.00054 1.00 +1 34 0.00474 1.00 +1 35 0.00187 1.00 +1 36 0.00567 1.00 +1 37 0.00313 0.99 +1 38 0.00287 1.00 +1 39 0.00910 1.00 +1 40 0.00516 0.99 +1 41 0.00589 0.99 +1 42 0.00716 0.99 +1 43 0.00693 0.99 +1 50 0.01143 0.99 +1 51 0.00803 0.99 +1 Number of positive differences (S+) 45 Critical Value 28 Survey Unit Meets the Acceptance Criteria 41
FSS RELEASE RECORD - REVISION 1
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 ATTACHMENT 4 QUALITY CONTROL ASSESSMENT 42
FSS RELEASE RECORD - REVISION 1 REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Table 16 Reactor Building Basement QC Assessment STANDARD COMPARISON Activity Standard Agreement Range Activity Standard Comparison Acceptable Measurement ID Radionuclide Resolution Measurement ID Value Error (Low to High) Value Error Ratio (Y/N) B1-010-001-FSFC-D05-GM K-40* 8.83E+04 1.37E+04 6 0.5 I 2 B1-010-001-QSFC-D05-GM 7.83E+04 1.29E+04 0.89 Y B1-010-001-FSFC-D16-GM K-40* 8.71E+04 1.33E+04 7 0.5 I 2 B1-010-001-QSFC-D16-GM 8.64E+04 1.35E+04 0.99 Y B1-010-001-FSFC-D18-GM K-40* 8.12E+04 1.37E+04 6 0.5 I 2 B1-010-001-QSFC-D18-GM 8.21E+04 1.31E+04 1.01 Y Comments/Corrective Actions: K-40 was substituted for the assessment of locations #5 and #18 because Cs- Table is provided to show acceptance criteria used to assess replicate ISOCS 137 was not identified in either the standard or comparison measurement. K-40 was substitued for the assessment measurements. of location #16 because of low Cs-137 activity identified in the replicate measurement and no ROC identified in Reso lution Acceptable Ratio the standard measurement.
<4 0.4-2.5 4 -7 0 .5-2.0 8- 15 0 .6- 1. 66 16-50 0 .7 5- 1.33 51-200 0 .80- 1.2 5
> 200 0 .8 5- 1.1 8 43
FSS RELEASE RECORD - REVISION 1
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 ATTACHMENT 5 GRAPHICAL PRESENTATIONS 44
FSS RELEASE RECORD - REVISION 1 REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 16 Quantile Plot for Cs-137 Concentration 8.00E+03 7.00E+03 ......., Concentration (pCi/m2) 6.00E+03 5.00E+03 4.00E+03 3.00E+03 2.00E+03 .., 1.00E+03 ..... .... ..., ..., -* rr ...,
'~
........ ' *~
T T
......., & i.. ....
0.00E+00 TT 1....... I" T 0% 20% 40% 60% 80% 100% Percentage 45
FSS RELEASE RECORD - REVISION 1
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 Figure 16 Histogram for Cs-137 Concentration 40 35 30 Frequency 25 20 15 10 5 0 1.17E+03 2.34E+03 3.51E+03 4.69E+03 5.86E+03 7.03E+03 Upper End Value (pCi/m2) 46
FSS RELEASE RECORD - REVISION 1 REACTOR BUILDING BASEMENT SURVEY UNIT B1-010-001 Figure 16 Retrospective Power Curve for B1-010-001 Probabil!ity that the Survey Unit Passes 1.0 I 0.8 0.6 0.4
- 0. 2 0.0 101/4 3]1/4 501/4 -oz 901/4 1 JO1/4 11 O1/4 1301/4 15O1/4 True Sul!'Vey Unit Concentration (percent of D CGL),
47
FSS RELEASE RECORD - REVISION 1
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REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 ATTACHMENT 6 MEASUREMENT ANALYTICAL REPORTS 48
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FJFC-D44-GM.CNF Report Generated On : 3/29/2019 9:59:57 AM Sample Title : B1-010-001-FJFC-D44-GM Sample Description : Rx Bowl concrete 0.5 M Sample Identification : D44 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 7.900E-001 M^2 Sample Taken On : 3/29/2019 7:28:00 AM Acquisition Started : 3/29/2019 7:29:04 AM Live Time : 600.0 seconds Real Time : 600.3 seconds Dead Time : 0.05 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_0.5M
Peak Analysis Report 3/29/2019 9:59:57 AM Page 2
- P E A K A N A L Y S I S R E P O R T *****
Detector Name: 3844 Sample
Title:
B1-010-001-FJFC-D44-GM Peak Analysis Performed on: 3/29/2019 9:59:57 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 962 955.05 238.83 0.58 5.90E+001 41.00 1.20E+002 2 1525- 1536 1530.60 382.81 0.61 1.91E+001 20.20 3.29E+001 3 2327- 2339 2332.32 583.33 0.81 4.51E+001 16.55 8.90E+000 4 2431- 2442 2436.82 609.46 1.35 3.10E+001 15.64 1.20E+001 5 2635- 2658 2646.78 661.96 1.65 8.45E+002 64.41 4.80E+001 6 3639- 3652 3645.44 911.64 0.59 1.54E+001 14.42 1.26E+001 7 3868- 3881 3874.49 968.89 0.46 1.25E+001 12.87 1.05E+001 8 5834- 5858 5846.32 1461.59 1.66 2.53E+002 34.03 9.03E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 9:59:57 AM Page 3
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Sample
Title:
B1-010-001-FJFC-D44-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.989 1460.81* 10.67 3.25663E+006 5.14122E+005 CS-137 0.998 661.65* 85.12 8.58067E+005 1.22072E+005 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 6.37116E+004 4.54297E+004 300.09 3.41 BI-214 1.000 609.31* 46.30 5.50964E+004 2.86783E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 5.77509E+004 5.44968E+004 964.60 5.20 969.11* 16.60 8.07937E+004 8.35033E+004 1587.90 3.71
Interference Corrected Activity Report 3/29/2019 9:59:57 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 9:59:57 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.989 3.256629E+006 5.141220E+005 CS-137 0.998 8.580667E+005 1.220722E+005 PB-212 1.000 6.371158E+004 4.542965E+004 BI-214 1.000 5.509645E+004 2.867825E+004 AC-228 1.000 6.463381E+004 4.563755E+004
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 9:59:57 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 382.81 3.1859E-002 105.67 3 583.33 7.5170E-002 36.70 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/29/2019 9:59:57 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FJFC-D44-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 2.910E+005 2.91E+005 3.257E+006 1.281E+005 CO-60 1173.22 100.00 3.824E+004 2.96E+004 2.581E+003 1.751E+004 1332.49 100.00 2.958E+004 -6.722E+003 1.305E+004 CS-134 475.35 1.46 3.010E+006 3.72E+004 -1.034E+006 1.439E+006 563.23 8.38 4.343E+005 2.952E+004 2.045E+005 569.32 15.43 2.283E+005 2.305E+004 1.072E+005 604.70 97.60 3.719E+004 3.700E+004 1.746E+004 795.84 85.40 4.044E+004 1.171E+004 1.870E+004 801.93 8.73 3.973E+005 1.758E+005 1.837E+005 1038.57 1.00 3.279E+006 -2.405E+005 1.489E+006 1167.94 1.80 2.095E+006 1.517E+006 9.583E+005 1365.15 3.04 8.662E+005 2.791E+005 3.748E+005 + CS-137 661.65* 85.12 4.905E+004 4.91E+004 8.581E+005 2.315E+004 EU-152 121.78 28.40 1.577E+005 1.51E+005 -1.415E+004 7.688E+004 344.27 26.50 1.506E+005 -4.877E+004 7.227E+004 1407.95 20.70 1.617E+005 -4.496E+003 7.211E+004 EU-154 123.07 40.40 1.106E+005 9.79E+004 -1.686E+004 5.388E+004 722.30 20.00 1.719E+005 -5.340E+004 7.982E+004 1274.51 34.40 9.786E+004 4.773E+004 4.400E+004 + BI-214 609.31* 46.30 3.692E+004 3.69E+004 5.510E+004 1.606E+004 768.36 5.04 6.954E+005 -1.172E+005 3.224E+005 806.17 1.23 2.829E+006 2.192E+005 1.308E+006 934.06 3.21 1.145E+006 8.558E+005 5.283E+005 1120.29 15.10 2.762E+005 2.229E+005 1.277E+005 1155.19 1.69 2.056E+006 1.381E+006 9.333E+005 1238.11 5.94 7.641E+005 8.974E+004 3.540E+005 1280.96 1.47 2.445E+006 5.968E+005 1.107E+006 1377.67 4.11 6.833E+005 -4.648E+005 2.983E+005 1385.31 0.78 3.898E+006 6.359E+005 1.720E+006 1401.50 1.39 2.205E+006 -1.666E+005 9.728E+005 1407.98 2.48 1.350E+006 -3.753E+004 6.019E+005 1509.19 2.19 1.250E+006 -1.764E+005 5.381E+005 1661.28 1.15 2.074E+006 -6.945E+004 8.602E+005 1729.60 3.05 7.152E+005 3.043E+005 2.890E+005 1764.49 15.80 2.386E+005 2.085E+005 1.058E+005 1847.44 2.12 1.531E+006 -1.631E+005 6.624E+005 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 1.426E+006 1.18E+005 9.142E+005 6.956E+005 77.11 10.70 7.876E+005 4.521E+005 3.842E+005 87.20 3.70 1.593E+006 -9.106E+005 7.768E+005 89.80 1.03 5.636E+006 9.328E+005 2.750E+006 241.98 7.49 6.050E+005 7.335E+005 2.937E+005
Nuclide MDA Report 3/29/2019 9:59:57 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 2.101E+005 1.18E+005 6.068E+004 1.012E+005 351.92 37.20 1.180E+005 8.906E+004 5.684E+004 785.91 1.10 2.723E+006 -7.869E+005 1.244E+006
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FJFC-D45-GM.CNF Report Generated On : 3/29/2019 10:03:01 AM Sample Title : B1-010-001-FJFC-D45-GM Sample Description : Rx Bowl concrete 0.5 M Sample Identification : D45 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 7.900E-001 M^2 Sample Taken On : 3/29/2019 8:06:00 AM Acquisition Started : 3/29/2019 8:06:18 AM Live Time : 600.0 seconds Real Time : 600.3 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_0.5M
Peak Analysis Report 3/29/2019 10:03:01 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FJFC-D45-GM Peak Analysis Performed on: 3/29/2019 10:03:00 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 962 954.71 238.75 0.49 5.67E+001 38.46 1.08E+002 2 1174- 1186 1179.67 295.03 0.43 3.35E+001 24.76 4.45E+001 3 2430- 2443 2436.75 609.44 0.37 3.33E+001 19.62 2.27E+001 4 2635- 2657 2646.42 661.87 1.44 7.91E+002 61.24 3.75E+001 5 5833- 5857 5845.50 1461.38 2.24 2.21E+002 32.20 9.35E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:03:01 AM Page 3
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Sample
Title:
B1-010-001-FJFC-D45-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.994 1460.81* 10.67 2.84021E+006 4.76279E+005 CS-137 0.999 661.65* 85.12 8.03636E+005 1.14827E+005 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 6.11633E+004 4.26640E+004 300.09 3.41 BI-214 1.000 609.31* 46.30 5.91420E+004 3.56895E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 9.43086E+004 7.14224E+004 351.92 37.20 785.91 1.10
Interference Corrected Activity Report 3/29/2019 10:03:01 AM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:03:01 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.994 2.840212E+006 4.762794E+005 CS-137 0.999 8.036357E+005 1.148271E+005 PB-212 1.000 6.116332E+004 4.266403E+004 BI-214 1.000 5.914200E+004 3.568947E+004 PB-214 1.000 9.430862E+004 7.142243E+004
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 10:03:00 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/29/2019 10:03:01 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FJFC-D45-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 2.978E+005 2.98E+005 2.840E+006 1.315E+005 CO-60 1173.22 100.00 3.405E+004 2.89E+004 1.875E+004 1.542E+004 1332.49 100.00 2.889E+004 -1.594E+004 1.270E+004 CS-134 475.35 1.46 2.740E+006 3.89E+004 -3.052E+005 1.304E+006 563.23 8.38 4.249E+005 7.027E+004 1.998E+005 569.32 15.43 2.296E+005 5.933E+004 1.079E+005 604.70 97.60 4.322E+004 -2.797E+003 2.048E+004 795.84 85.40 3.894E+004 -5.986E+002 1.795E+004 801.93 8.73 3.471E+005 -1.035E+005 1.586E+005 1038.57 1.00 2.944E+006 -1.789E+006 1.321E+006 1167.94 1.80 1.968E+006 1.099E+006 8.948E+005 1365.15 3.04 1.056E+006 9.473E+005 4.699E+005 + CS-137 661.65* 85.12 4.312E+004 4.31E+004 8.036E+005 2.019E+004 EU-152 121.78 28.40 1.528E+005 1.13E+005 -4.096E+004 7.442E+004 344.27 26.50 1.509E+005 5.579E+004 7.245E+004 1407.95 20.70 1.126E+005 -6.883E+004 4.755E+004 EU-154 123.07 40.40 1.077E+005 1.04E+005 -3.863E+004 5.248E+004 722.30 20.00 1.719E+005 3.271E+004 7.982E+004 1274.51 34.40 1.042E+005 2.478E+004 4.715E+004 + BI-214 609.31* 46.30 5.122E+004 5.12E+004 5.914E+004 2.321E+004 768.36 5.04 6.529E+005 1.331E+005 3.012E+005 806.17 1.23 2.349E+006 -1.653E+006 1.068E+006 934.06 3.21 1.077E+006 -7.961E+005 4.942E+005 1120.29 15.10 2.354E+005 4.228E+004 1.073E+005 1155.19 1.69 2.218E+006 4.320E+005 1.015E+006 1238.11 5.94 7.096E+005 9.527E+005 3.268E+005 1280.96 1.47 2.445E+006 1.346E+006 1.107E+006 1377.67 4.11 8.020E+005 -6.530E+005 3.576E+005 1385.31 0.78 4.324E+006 2.899E+006 1.933E+006 1401.50 1.39 2.353E+006 2.111E+006 1.047E+006 1407.98 2.48 9.397E+005 -5.745E+005 3.969E+005 1509.19 2.19 1.118E+006 1.877E+005 4.720E+005 1661.28 1.15 2.179E+006 1.380E+005 9.124E+005 1729.60 3.05 3.732E+005 5.071E+004 1.180E+005 1764.49 15.80 1.801E+005 1.092E+005 7.660E+004 1847.44 2.12 1.207E+006 6.088E+005 5.007E+005 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 1.366E+006 1.08E+005 9.721E+005 6.653E+005 77.11 10.70 7.566E+005 2.407E+005 3.687E+005 87.20 3.70 1.661E+006 1.180E+006 8.108E+005 89.80 1.03 5.685E+006 1.850E+006 2.775E+006 241.98 7.49 5.797E+005 6.894E+005 2.811E+005
Nuclide MDA Report 3/29/2019 10:03:01 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21* 19.20 1.092E+005 1.08E+005 9.431E+004 5.077E+004 351.92 37.20 1.080E+005 -1.127E+004 5.184E+004 785.91 1.10 3.173E+006 -8.723E+005 1.469E+006
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FJFC-D46-GM.CNF Report Generated On : 3/29/2019 10:06:01 AM Sample Title : B1-010-001-FJFC-D46-GM Sample Description : Rx Bowl concrete 0.5 M Sample Identification : D46 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 7.900E-001 M^2 Sample Taken On : 3/29/2019 7:41:00 AM Acquisition Started : 3/29/2019 7:41:26 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_0.5M
Peak Analysis Report 3/29/2019 10:06:01 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FJFC-D46-GM Peak Analysis Performed on: 3/29/2019 10:06:01 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 961 954.45 238.68 0.78 5.57E+001 36.21 9.73E+001 2 1175- 1186 1180.08 295.13 0.43 1.87E+001 22.43 4.23E+001 3 2431- 2446 2437.31 609.58 1.48 3.42E+001 18.42 1.68E+001 4 2638- 2656 2646.89 661.99 0.85 2.04E+002 31.23 1.18E+001 5 3638- 3652 3645.20 911.58 1.65 3.23E+001 14.89 7.72E+000 6 5835- 5858 5846.70 1461.68 2.37 2.40E+002 32.41 5.74E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:06:01 AM Page 3
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Sample
Title:
B1-010-001-FJFC-D46-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.986 1460.81* 10.67 3.09315E+006 4.89292E+005 CS-137 0.998 661.65* 85.12 2.07401E+005 4.03258E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 6.00999E+004 4.02546E+004 300.09 3.41 BI-214 0.999 609.31* 46.30 6.07493E+004 3.36464E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 5.26974E+004 6.38181E+004 351.92 37.20 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20
Interference Corrected Activity Report 3/29/2019 10:06:01 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 1.000 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 1.21015E+005 5.75362E+004 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:06:01 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.986 3.093151E+006 4.892917E+005 CS-137 0.998 2.074005E+005 4.032576E+004 PB-212 1.000 6.009990E+004 4.025458E+004 BI-214 0.999 6.074929E+004 3.364636E+004 PB-214 1.000 5.269739E+004 6.381806E+004 AC-228 1.000 1.210149E+005 5.753622E+004
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 10:06:01 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/29/2019 10:06:01 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FJFC-D46-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 2.351E+005 2.35E+005 3.093E+006 1.001E+005 CO-60 1173.22 100.00 3.355E+004 3.09E+004 -4.124E+004 1.517E+004 1332.49 100.00 3.092E+004 1.653E+004 1.372E+004 CS-134 475.35 1.46 2.557E+006 3.89E+004 1.536E+006 1.213E+006 563.23 8.38 4.249E+005 1.897E+005 1.998E+005 569.32 15.43 2.146E+005 -9.575E+004 1.004E+005 604.70 97.60 4.092E+004 -2.868E+004 1.933E+004 795.84 85.40 3.894E+004 1.132E+004 1.795E+004 801.93 8.73 4.044E+005 -1.741E+005 1.873E+005 1038.57 1.00 3.323E+006 3.125E+006 1.511E+006 1167.94 1.80 2.045E+006 4.287E+005 9.334E+005 1365.15 3.04 1.035E+006 9.043E+005 4.591E+005 + CS-137 661.65* 85.12 2.375E+004 2.38E+004 2.074E+005 1.050E+004 EU-152 121.78 28.40 1.449E+005 1.38E+005 7.002E+004 7.049E+004 344.27 26.50 1.410E+005 7.993E+004 6.748E+004 1407.95 20.70 1.378E+005 -3.959E+004 6.014E+004 EU-154 123.07 40.40 1.011E+005 1.01E+005 -5.248E+004 4.915E+004 722.30 20.00 1.774E+005 -4.101E+004 8.257E+004 1274.51 34.40 1.026E+005 5.369E+004 4.638E+004 + BI-214 609.31* 46.30 4.642E+004 4.64E+004 6.075E+004 2.080E+004 768.36 5.04 6.653E+005 -7.675E+005 3.074E+005 806.17 1.23 2.777E+006 -2.177E+006 1.282E+006 934.06 3.21 1.145E+006 -6.658E+003 5.283E+005 1120.29 15.10 2.978E+005 1.667E+005 1.385E+005 1155.19 1.69 2.084E+006 -1.886E+006 9.473E+005 1238.11 5.94 6.879E+005 4.223E+005 3.159E+005 1280.96 1.47 2.372E+006 1.175E+006 1.071E+006 1377.67 4.11 6.448E+005 -2.215E+005 2.790E+005 1385.31 0.78 3.615E+006 1.410E+006 1.578E+006 1401.50 1.39 2.045E+006 7.195E+004 8.927E+005 1407.98 2.48 1.150E+006 -3.304E+005 5.020E+005 1509.19 2.19 1.208E+006 -2.406E+005 5.170E+005 1661.28 1.15 1.844E+006 3.922E+005 7.450E+005 1729.60 3.05 8.834E+005 5.071E+005 3.731E+005 1764.49 15.80 2.282E+005 1.172E+005 1.007E+005 1847.44 2.12 1.207E+006 -6.658E+005 5.007E+005 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 1.351E+006 1.04E+005 1.208E+006 6.577E+005 77.11 10.70 7.418E+005 7.107E+005 3.613E+005 87.20 3.70 1.563E+006 2.373E+005 7.619E+005 89.80 1.03 5.484E+006 4.342E+006 2.674E+006 241.98 7.49 5.616E+005 4.453E+005 2.721E+005
Nuclide MDA Report 3/29/2019 10:06:01 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21* 19.20 1.037E+005 1.04E+005 5.270E+004 4.801E+004 351.92 37.20 1.050E+005 5.314E+004 5.034E+004 785.91 1.10 3.001E+006 -5.453E+005 1.383E+006
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FJFC-D47-GM.CNF Report Generated On : 3/29/2019 10:08:32 AM Sample Title : B1-010-001-FJFC-D47-GM Sample Description : Rx Bowl concrete 0.5 M Sample Identification : D47 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 7.900E-001 M^2 Sample Taken On : 3/29/2019 7:53:00 AM Acquisition Started : 3/29/2019 7:53:55 AM Live Time : 600.0 seconds Real Time : 600.3 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_0.5M
Peak Analysis Report 3/29/2019 10:08:32 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FJFC-D47-GM Peak Analysis Performed on: 3/29/2019 10:08:32 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 305 300.80 75.13 0.69 3.55E+001 35.71 1.25E+002 2 948- 962 955.07 238.84 0.68 4.66E+001 34.76 8.84E+001 3 1399- 1415 1407.51 352.02 0.77 6.23E+001 24.93 2.97E+001 4 2326- 2340 2332.97 583.49 1.00 4.07E+001 17.16 1.13E+001 5 2431- 2444 2436.92 609.48 0.80 2.94E+001 17.97 1.86E+001 6 2638- 2655 2646.79 661.97 1.39 1.61E+002 31.17 2.49E+001 7 3869- 3883 3876.00 969.27 0.35 2.63E+001 14.24 7.68E+000 8 5833- 5858 5845.99 1461.51 2.07 2.67E+002 34.25 6.34E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:08:32 AM Page 3
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Sample
Title:
B1-010-001-FJFC-D47-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.991 1460.81* 10.67 3.43271E+006 5.24218E+005 CS-137 0.998 661.65* 85.12 1.63552E+005 3.72523E+004 PB-212 0.999 74.81* 9.60 3.01073E+005 3.08416E+005 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 5.03538E+004 3.83897E+004 300.09 3.41 BI-214 1.000 609.31* 46.30 5.22374E+004 3.26373E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.627 74.81* 6.33 4.56603E+005 4.67740E+005 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 9.98871E+004 4.30729E+004 785.91 1.10 AC-228 0.593 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20
Interference Corrected Activity Report 3/29/2019 10:08:32 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.593 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60 27.70 964.60 5.20 969.11* 16.60 1.70177E+005 9.33865E+004 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:08:32 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.991 3.432712E+006 5.242179E+005 CS-137 0.998 1.635516E+005 3.725234E+004 PB-212 0.999 5.315089E+004 3.809820E+004 BI-214 1.000 5.223742E+004 3.263728E+004 PB-214 0.627 1.022088E+005 4.289422E+004 AC-228 0.593 1.701774E+005 9.338652E+004
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 10:08:32 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 4 583.49 6.7837E-002 42.15 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/29/2019 10:08:32 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FJFC-D47-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 2.532E+005 2.53E+005 3.433E+006 1.092E+005 CO-60 1173.22 100.00 3.995E+004 3.34E+004 -1.122E+004 1.837E+004 1332.49 100.00 3.342E+004 2.677E+003 1.497E+004 CS-134 475.35 1.46 2.313E+006 3.85E+004 -1.313E+006 1.091E+006 563.23 8.38 4.128E+005 2.826E+004 1.937E+005 569.32 15.43 2.146E+005 3.713E+004 1.004E+005 604.70 97.60 3.848E+004 -1.926E+004 1.810E+004 795.84 85.40 3.856E+004 -2.446E+003 1.776E+004 801.93 8.73 3.863E+005 -6.473E+004 1.782E+005 1038.57 1.00 3.367E+006 -2.542E+006 1.533E+006 1167.94 1.80 2.214E+006 -2.211E+005 1.018E+006 1365.15 3.04 9.898E+005 4.113E+005 4.367E+005 + CS-137 661.65* 85.12 3.297E+004 3.30E+004 1.636E+005 1.511E+004 EU-152 121.78 28.40 1.533E+005 1.31E+005 -9.235E+004 7.466E+004 344.27 26.50 1.307E+005 -3.661E+004 6.232E+004 1407.95 20.70 1.486E+005 -3.197E+004 6.554E+004 EU-154 123.07 40.40 1.082E+005 9.95E+004 -1.844E+004 5.270E+004 722.30 20.00 1.747E+005 1.818E+004 8.120E+004 1274.51 34.40 9.947E+004 6.829E+004 4.481E+004 + BI-214 609.31* 46.30 4.672E+004 4.67E+004 5.224E+004 2.096E+004 768.36 5.04 6.273E+005 -5.499E+005 2.884E+005 806.17 1.23 2.724E+006 3.685E+005 1.255E+006 934.06 3.21 1.041E+006 -1.057E+006 4.762E+005 1120.29 15.10 2.884E+005 -3.843E+004 1.338E+005 1155.19 1.69 1.969E+006 -1.100E+006 8.899E+005 1238.11 5.94 7.374E+005 2.329E+005 3.407E+005 1280.96 1.47 1.870E+006 -1.154E+006 8.196E+005 1377.67 4.11 5.814E+005 -3.461E+005 2.473E+005 1385.31 0.78 3.615E+006 1.468E+006 1.578E+006 1401.50 1.39 1.988E+006 -7.723E+005 8.644E+005 1407.98 2.48 1.240E+006 -2.669E+005 5.470E+005 1509.19 2.19 1.208E+006 2.352E+005 5.170E+005 1661.28 1.15 1.714E+006 6.537E+005 6.801E+005 1729.60 3.05 7.152E+005 -6.128E+004 2.890E+005 1764.49 15.80 2.282E+005 2.234E+004 1.007E+005 1847.44 2.12 1.143E+006 -1.006E+005 4.684E+005 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81* 6.33 7.461E+005 5.53E+004 4.566E+005 3.557E+005 77.11 10.70 7.610E+005 4.821E+005 3.709E+005 87.20 3.70 1.611E+006 1.150E+006 7.856E+005 89.80 1.03 5.611E+006 2.360E+006 2.737E+006 241.98 7.49 5.515E+005 2.910E+005 2.670E+005
Nuclide MDA Report 3/29/2019 10:08:32 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 1.923E+005 5.53E+004 1.275E+004 9.232E+004 351.92* 37.20 5.528E+004 9.989E+004 2.547E+004 785.91 1.10 3.173E+006 1.628E+006 1.469E+006
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FJFC-D48-GM.CNF Report Generated On : 3/29/2019 10:12:57 AM Sample Title : B1-010-001-FJFC-D48-GM Sample Description : Rx Bowl concrete 0.5 M Sample Identification : D48 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 7.900E-001 M^2 Sample Taken On : 3/29/2019 8:19:00 AM Acquisition Started : 3/29/2019 8:20:46 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_0.5M
Peak Analysis Report 3/29/2019 10:12:57 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FJFC-D48-GM Peak Analysis Performed on: 3/29/2019 10:12:57 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 295- 306 300.24 74.99 0.64 5.21E+001 39.32 1.33E+002 2 946- 961 954.32 238.65 0.71 5.10E+001 33.78 7.80E+001 3 2326- 2338 2332.78 583.44 1.12 2.70E+001 17.32 1.80E+001 4 2433- 2444 2438.19 609.80 0.53 3.90E+001 17.54 1.50E+001 5 2640- 2654 2646.42 661.87 1.11 4.32E+001 20.39 2.08E+001 6 3639- 3652 3645.07 911.54 0.41 2.14E+001 17.07 1.86E+001 7 5834- 5859 5846.12 1461.54 2.17 2.66E+002 33.36 3.02E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:12:57 AM Page 3
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Sample
Title:
B1-010-001-FJFC-D48-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.991 1460.81* 10.67 3.42392E+006 5.14214E+005 CS-137 0.999 661.65* 85.12 4.38400E+004 2.13622E+004 PB-212 0.711 74.81* 9.60 4.43820E+005 3.46341E+005 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 5.50681E+004 3.75100E+004 300.09 3.41 BI-214 0.998 609.31* 46.30 6.93381E+004 3.24219E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 8.04016E+004 6.46697E+004 964.60 5.20 969.11 16.60 1587.90 3.71
Interference Corrected Activity Report 3/29/2019 10:12:57 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:12:57 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.991 3.423920E+006 5.142145E+005 CS-137 0.999 4.384004E+004 2.136225E+004 PB-212 0.711 5.957522E+004 3.729191E+004 BI-214 0.998 6.933811E+004 3.242188E+004 AC-228 1.000 8.040162E+004 6.466971E+004
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 10:12:57 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 583.44 4.4926E-002 64.25 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/29/2019 10:12:57 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FJFC-D48-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 1.829E+005 1.83E+005 3.424E+006 7.402E+004 CO-60 1173.22 100.00 3.355E+004 3.28E+004 8.946E+003 1.517E+004 1332.49 100.00 3.281E+004 1.214E+004 1.467E+004 CS-134 475.35 1.46 2.180E+006 4.32E+004 1.576E+006 1.024E+006 563.23 8.38 3.875E+005 1.644E+005 1.811E+005 569.32 15.43 2.118E+005 1.839E+005 9.896E+004 604.70 97.60 4.322E+004 -1.116E+004 2.048E+004 795.84 85.40 4.460E+004 -1.080E+004 2.078E+004 801.93 8.73 3.937E+005 -5.528E+004 1.819E+005 1038.57 1.00 3.367E+006 -6.484E+005 1.533E+006 1167.94 1.80 2.191E+006 1.989E+006 1.006E+006 1365.15 3.04 1.035E+006 2.476E+005 4.591E+005 + CS-137 661.65* 85.12 2.879E+004 2.88E+004 4.384E+004 1.302E+004 EU-152 121.78 28.40 1.484E+005 1.26E+005 -2.899E+004 7.220E+004 344.27 26.50 1.263E+005 -4.377E+004 6.013E+004 1407.95 20.70 1.340E+005 -6.668E+004 5.823E+004 EU-154 123.07 40.40 1.044E+005 1.03E+005 2.481E+004 5.081E+004 722.30 20.00 1.801E+005 9.884E+004 8.391E+004 1274.51 34.40 1.026E+005 5.369E+004 4.638E+004 + BI-214 609.31* 46.30 4.083E+004 4.08E+004 6.934E+004 1.801E+004 768.36 5.04 6.835E+005 4.935E+005 3.165E+005 806.17 1.23 2.750E+006 -1.025E+004 1.269E+006 934.06 3.21 1.112E+006 5.317E+005 5.115E+005 1120.29 15.10 2.932E+005 -2.306E+004 1.362E+005 1155.19 1.69 2.295E+006 -2.619E+005 1.053E+006 1238.11 5.94 6.655E+005 1.967E+005 3.047E+005 1280.96 1.47 2.219E+006 -1.773E+006 9.939E+005 1377.67 4.11 8.020E+005 4.878E+005 3.576E+005 1385.31 0.78 3.806E+006 -9.797E+005 1.674E+006 1401.50 1.39 2.100E+006 -1.295E+006 9.202E+005 1407.98 2.48 1.118E+006 -5.565E+005 4.861E+005 1509.19 2.19 9.633E+005 -2.062E+004 3.949E+005 1661.28 1.15 1.570E+006 5.229E+005 6.083E+005 1729.60 3.05 7.152E+005 -9.805E+005 2.890E+005 1764.49 15.80 2.229E+005 8.274E+004 9.799E+004 1847.44 2.12 9.976E+005 3.805E+005 3.959E+005 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 1.315E+006 9.76E+004 1.166E+006 6.401E+005 77.11 10.70 7.220E+005 4.333E+004 3.514E+005 87.20 3.70 1.519E+006 2.212E+005 7.397E+005 89.80 1.03 5.259E+006 6.666E+005 2.562E+006 241.98 7.49 5.298E+005 7.692E+005 2.561E+005
Nuclide MDA Report 3/29/2019 10:12:57 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 1.802E+005 9.76E+004 1.241E+005 8.629E+004 351.92 37.20 9.756E+004 9.891E+004 4.661E+004 785.91 1.10 3.200E+006 2.963E+006 1.483E+006
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FJFC-D49-GM.CNF Report Generated On : 3/29/2019 10:15:47 AM Sample Title : B1-010-001-FJFC-D49-GM Sample Description : Rx Bowl concrete 0.5 M Sample Identification : D49 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 7.900E-001 M^2 Sample Taken On : 3/29/2019 8:33:00 AM Acquisition Started : 3/29/2019 8:34:56 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_0.5M
Peak Analysis Report 3/29/2019 10:15:47 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FJFC-D49-GM Peak Analysis Performed on: 3/29/2019 10:15:47 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 963 954.47 238.69 1.35 5.00E+001 38.24 1.02E+002 2 2432- 2444 2437.93 609.74 0.63 2.65E+001 19.39 2.55E+001 3 2639- 2654 2646.62 661.92 1.05 1.01E+002 25.63 2.12E+001 4 5834- 5857 5846.85 1461.72 1.78 2.64E+002 33.25 3.06E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:15:47 AM Page 3
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Sample
Title:
B1-010-001-FJFC-D49-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.985 1460.81* 10.67 3.39800E+006 5.11914E+005 CS-137 0.999 661.65* 85.12 1.02334E+005 2.87817E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 5.39604E+004 4.21739E+004 300.09 3.41 BI-214 0.999 609.31* 46.30 4.70430E+004 3.49993E+004 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:15:47 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.985 3.398002E+006 5.119138E+005 CS-137 0.999 1.023335E+005 2.878174E+004 PB-212 1.000 5.396043E+004 4.217389E+004 BI-214 0.999 4.704304E+004 3.499931E+004
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 10:15:47 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/29/2019 10:15:47 AM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FJFC-D49-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 1.844E+005 1.84E+005 3.398E+006 7.477E+004 CO-60 1173.22 100.00 3.780E+004 3.09E+004 1.012E+004 1.729E+004 1332.49 100.00 3.092E+004 6.955E+003 1.372E+004 CS-134 475.35 1.46 2.515E+006 4.17E+004 4.360E+005 1.192E+006 563.23 8.38 4.177E+005 -7.877E+004 1.962E+005 569.32 15.43 2.386E+005 6.401E+004 1.124E+005 604.70 97.60 4.171E+004 -1.635E+004 1.972E+004 795.84 85.40 4.493E+004 1.728E+004 2.094E+004 801.93 8.73 4.149E+005 2.828E+005 1.925E+005 1038.57 1.00 3.739E+006 3.314E+006 1.719E+006 1167.94 1.80 2.020E+006 8.515E+005 9.207E+005 1365.15 3.04 9.898E+005 1.615E+005 4.367E+005 + CS-137 661.65* 85.12 2.936E+004 2.94E+004 1.023E+005 1.330E+004 EU-152 121.78 28.40 1.414E+005 1.29E+005 -5.703E+003 6.873E+004 344.27 26.50 1.289E+005 -1.273E+005 6.145E+004 1407.95 20.70 1.340E+005 -1.218E+005 5.823E+004 EU-154 123.07 40.40 9.991E+004 9.99E+004 -4.538E+004 4.856E+004 722.30 20.00 1.677E+005 -1.488E+005 7.769E+004 1274.51 34.40 1.183E+005 9.374E+004 5.422E+004 + BI-214 609.31* 46.30 5.289E+004 5.29E+004 4.704E+004 2.404E+004 768.36 5.04 6.207E+005 -2.752E+005 2.851E+005 806.17 1.23 2.697E+006 -1.114E+006 1.242E+006 934.06 3.21 9.514E+005 1.183E+005 4.314E+005 1120.29 15.10 2.634E+005 -6.651E+004 1.213E+005 1155.19 1.69 2.111E+006 -1.871E+006 9.611E+005 1238.11 5.94 6.805E+005 5.276E+005 3.122E+005 1280.96 1.47 2.682E+006 -5.015E+005 1.225E+006 1377.67 4.11 7.369E+005 -3.311E+005 3.251E+005 1385.31 0.78 4.074E+006 7.106E+005 1.808E+006 1401.50 1.39 2.045E+006 -8.994E+004 8.927E+005 1407.98 2.48 1.118E+006 -1.017E+006 4.861E+005 1509.19 2.19 1.118E+006 5.293E+004 4.720E+005 1661.28 1.15 2.074E+006 1.046E+006 8.602E+005 1729.60 3.05 6.091E+005 2.029E+005 2.360E+005 1764.49 15.80 2.058E+005 6.685E+004 8.946E+004 1847.44 2.12 9.976E+005 3.805E+005 3.959E+005 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 1.337E+006 9.73E+004 1.202E+005 6.507E+005 77.11 10.70 7.395E+005 5.118E+004 3.602E+005 87.20 3.70 1.574E+006 6.275E+005 7.671E+005 89.80 1.03 5.464E+006 6.927E+006 2.664E+006 241.98 7.49 5.600E+005 5.407E+005 2.712E+005
Nuclide MDA Report 3/29/2019 10:15:47 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 1.812E+005 9.73E+004 1.836E+004 8.679E+004 351.92 37.20 9.726E+004 5.067E+004 4.646E+004 785.91 1.10 3.173E+006 -1.970E+006 1.469E+006
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D01-GM.CNF Report Generated On : 3/27/2019 8:25:05 PM Sample Title : B1-010-001-FSFC-D01-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D01 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 3:51:00 PM Acquisition Started : 3/27/2019 3:51:48 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:25:05 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D01-GM Peak Analysis Performed on: 3/27/2019 8:25:04 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 961 953.90 238.54 0.95 5.93E+001 32.56 7.47E+001 2 1402- 1414 1407.87 352.11 1.15 2.37E+001 21.16 3.33E+001 3 2327- 2338 2332.97 583.49 1.15 2.26E+001 16.81 1.84E+001 4 2430- 2442 2436.84 609.47 0.64 3.90E+001 17.11 1.30E+001 5 3639- 3652 3645.09 911.55 0.58 2.48E+001 15.96 1.32E+001 6 5833- 5856 5845.30 1461.33 1.85 2.31E+002 31.94 6.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:25:05 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D01-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.995 1460.81* 10.67 8.32198E+004 1.34037E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.84511E+003 1.05501E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.96342E+003 8.97170E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.09224E+003 9.88826E+002 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40
Interference Corrected Activity Report 3/27/2019 8:25:05 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 1.000 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.62904E+003 1.71953E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:25:05 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.995 8.321976E+004 1.340373E+004 PB-212 1.000 1.845110E+003 1.055009E+003 BI-214 1.000 1.963417E+003 8.971696E+002 PB-214 1.000 1.092242E+003 9.888258E+002 AC-228 1.000 2.629041E+003 1.719529E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:25:04 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 583.49 3.7602E-002 74.50 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:25:05 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D01-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 6.784E+003 6.78E+003 8.322E+004 2.904E+003 CO-60 1173.22 100.00 1.175E+003 8.46E+002 5.886E+002 5.421E+002 1332.49 100.00 8.463E+002 -1.008E+002 3.744E+002 CS-134 475.35 1.46 6.212E+004 1.15E+003 -1.788E+004 2.919E+004 563.23 8.38 1.092E+004 1.122E+003 5.101E+003 569.32 15.43 6.009E+003 5.133E+002 2.808E+003 604.70 97.60 1.209E+003 1.163E+003 5.721E+002 795.84 85.40 1.154E+003 -3.105E+002 5.338E+002 801.93 8.73 1.123E+004 -5.680E+003 5.194E+003 1038.57 1.00 8.890E+004 -1.648E+004 4.018E+004 1167.94 1.80 6.126E+004 9.454E+003 2.811E+004 1365.15 3.04 2.347E+004 -1.040E+004 1.010E+004 CS-137 661.65 85.12 1.095E+003 1.09E+003 -1.769E+001 5.084E+002 EU-152 121.78 28.40 3.847E+003 3.70E+003 -2.337E+003 1.866E+003 344.27 26.50 3.698E+003 6.507E+002 1.763E+003 1407.95 20.70 3.958E+003 -1.181E+003 1.735E+003 EU-154 123.07 40.40 2.759E+003 2.76E+003 -9.739E+002 1.339E+003 722.30 20.00 4.658E+003 4.164E+003 2.155E+003 1274.51 34.40 2.880E+003 -2.399E+003 1.302E+003 + BI-214 609.31* 46.30 1.104E+003 1.10E+003 1.963E+003 4.841E+002 768.36 5.04 1.864E+004 1.238E+004 8.604E+003 806.17 1.23 8.070E+004 9.802E+003 3.734E+004 934.06 3.21 2.980E+004 -1.014E+004 1.365E+004 1120.29 15.10 7.065E+003 -2.740E+003 3.238E+003 1155.19 1.69 6.964E+004 5.244E+004 3.215E+004 1238.11 5.94 1.956E+004 4.973E+003 8.992E+003 1280.96 1.47 6.445E+004 1.871E+004 2.898E+004 1377.67 4.11 2.155E+004 5.156E+003 9.560E+003 1385.31 0.78 1.275E+005 -5.069E+004 5.734E+004 1401.50 1.39 6.845E+004 -1.118E+004 3.059E+004 1407.98 2.48 3.304E+004 -9.855E+003 1.448E+004 1509.19 2.19 2.697E+004 1.257E+004 1.105E+004 1661.28 1.15 6.895E+004 4.395E+004 2.952E+004 1729.60 3.05 1.530E+004 -1.883E+004 5.727E+003 1764.49 15.80 4.638E+003 -1.701E+002 1.942E+003 1847.44 2.12 3.386E+004 1.707E+004 1.404E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.811E+004 1.55E+003 4.061E+004 1.854E+004 77.11 10.70 2.125E+004 1.807E+004 1.035E+004 87.20 3.70 4.282E+004 -1.426E+004 2.083E+004 89.80 1.03 1.492E+005 7.265E+004 7.260E+004 241.98 7.49 1.509E+004 7.951E+003 7.293E+003
Nuclide MDA Report 3/27/2019 8:25:05 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 4.839E+003 1.55E+003 -1.038E+003 2.310E+003 351.92* 37.20 1.546E+003 1.092E+003 7.105E+002 785.91 1.10 8.233E+004 -9.476E+004 3.785E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D02-GM.CNF Report Generated On : 3/27/2019 8:27:43 PM Sample Title : B1-010-001-FSFC-D02-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D02 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 4:04:00 PM Acquisition Started : 3/27/2019 4:04:41 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:27:43 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D02-GM Peak Analysis Performed on: 3/27/2019 8:27:42 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 961 954.14 238.61 0.50 5.28E+001 31.78 6.62E+001 2 2241- 2252 2246.67 561.91 0.68 1.19E+001 9.07 3.10E+000 3 2324- 2340 2331.76 583.19 0.32 3.46E+001 19.20 1.84E+001 4 2432- 2443 2437.42 609.61 0.64 2.26E+001 16.33 1.74E+001 5 3637- 3650 3643.80 911.23 0.98 2.88E+001 15.79 1.22E+001 6 5832- 5856 5843.91 1460.99 1.68 2.33E+002 32.89 9.22E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:27:43 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D02-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.999 1460.81* 10.67 8.38465E+004 1.37237E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.64427E+003 1.02309E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 1.14045E+003 8.34906E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.999 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.05559E+003 1.71101E+003 964.60 5.20 969.11 16.60 1587.90 3.71
Interference Corrected Activity Report 3/27/2019 8:27:43 PM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:27:43 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.999 8.384646E+004 1.372369E+004 PB-212 1.000 1.644273E+003 1.023093E+003 BI-214 0.999 1.140447E+003 8.349064E+002 AC-228 0.999 3.055591E+003 1.711008E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:27:42 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 561.91 1.9833E-002 76.19 Tol. CS-134 3 583.19 5.7649E-002 55.51 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:27:43 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D02-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 8.249E+003 8.25E+003 8.385E+004 3.637E+003 CO-60 1173.22 100.00 1.293E+003 7.46E+002 1.219E+003 6.011E+002 1332.49 100.00 7.459E+002 -5.758E+001 3.243E+002 CS-134 475.35 1.46 6.757E+004 9.49E+002 2.923E+003 3.191E+004 563.23 8.38 9.811E+003 -1.556E+003 4.546E+003 569.32 15.43 5.586E+003 4.155E+003 2.596E+003 604.70 97.60 1.176E+003 1.092E+002 5.559E+002 795.84 85.40 9.494E+002 -1.261E+003 4.316E+002 801.93 8.73 1.005E+004 1.054E+004 4.600E+003 1038.57 1.00 9.899E+004 5.550E+004 4.523E+004 1167.94 1.80 6.995E+004 2.132E+004 3.245E+004 1365.15 3.04 2.568E+004 -1.972E+004 1.121E+004 CS-137 661.65 85.12 9.931E+002 9.93E+002 -5.392E+002 4.577E+002 EU-152 121.78 28.40 4.185E+003 3.60E+003 9.314E+002 2.035E+003 344.27 26.50 3.596E+003 -1.774E+003 1.712E+003 1407.95 20.70 4.157E+003 8.661E+002 1.834E+003 EU-154 123.07 40.40 2.914E+003 2.61E+003 1.266E+003 1.417E+003 722.30 20.00 4.313E+003 -6.652E+003 1.983E+003 1274.51 34.40 2.606E+003 9.856E+002 1.165E+003 + BI-214 609.31* 46.30 1.235E+003 1.23E+003 1.140E+003 5.493E+002 768.36 5.04 1.999E+004 1.896E+004 9.280E+003 806.17 1.23 6.816E+004 -2.802E+004 3.107E+004 934.06 3.21 2.804E+004 -7.188E+003 1.277E+004 1120.29 15.10 8.291E+003 1.062E+003 3.851E+003 1155.19 1.69 6.764E+004 3.806E+004 3.115E+004 1238.11 5.94 2.131E+004 3.188E+003 9.869E+003 1280.96 1.47 5.637E+004 -2.805E+004 2.494E+004 1377.67 4.11 2.061E+004 -1.115E+004 9.093E+003 1385.31 0.78 9.832E+004 -7.124E+004 4.274E+004 1401.50 1.39 5.722E+004 2.013E+003 2.498E+004 1407.98 2.48 3.470E+004 7.229E+003 1.531E+004 1509.19 2.19 2.697E+004 -3.656E+003 1.105E+004 1661.28 1.15 4.400E+004 1.465E+004 1.704E+004 1729.60 3.05 1.863E+004 -4.548E+003 7.394E+003 1764.49 15.80 6.398E+003 5.288E+003 2.822E+003 1847.44 2.12 2.797E+004 -1.654E+004 1.110E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.618E+004 2.69E+003 -3.583E+003 1.757E+004 77.11 10.70 2.009E+004 7.272E+003 9.763E+003 87.20 3.70 4.362E+004 2.523E+004 2.123E+004 89.80 1.03 1.513E+005 1.313E+005 7.365E+004 241.98 7.49 1.448E+004 1.501E+004 6.989E+003
Nuclide MDA Report 3/27/2019 8:27:43 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 5.363E+003 2.69E+003 2.250E+003 2.572E+003 351.92 37.20 2.692E+003 2.556E+003 1.284E+003 785.91 1.10 8.569E+004 1.213E+003 3.953E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D03-GM.CNF Report Generated On : 3/27/2019 8:29:08 PM Sample Title : B1-010-001-FSFC-D03-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D03 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 1:56:00 PM Acquisition Started : 3/27/2019 1:56:59 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:29:08 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D03-GM Peak Analysis Performed on: 3/27/2019 8:29:08 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 962 954.22 238.63 0.58 2.91E+001 36.81 1.03E+002 2 1402- 1415 1407.80 352.10 0.37 4.24E+001 22.10 2.86E+001 3 2327- 2338 2332.79 583.45 0.39 1.73E+001 12.59 7.70E+000 4 3869- 3882 3875.10 969.04 0.69 1.95E+001 12.25 6.54E+000 5 5831- 5854 5843.54 1460.90 2.19 2.45E+002 32.80 6.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:29:08 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D03-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 1.000 1460.81* 10.67 8.82445E+004 1.38831E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 9.04822E+002 1.15458E+003 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.94922E+003 1.06366E+003 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60 27.70 964.60 5.20 969.11* 16.60 3.56193E+003 2.26641E+003 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:29:08 PM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 1.000 8.824450E+004 1.388314E+004 PB-212 1.000 9.048221E+002 1.154582E+003 PB-214 1.000 1.949217E+003 1.063659E+003 AC-228 1.000 3.561925E+003 2.266410E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:29:08 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 583.45 2.8833E-002 72.76 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:29:08 PM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D03-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 6.781E+003 6.78E+003 8.824E+004 2.903E+003 CO-60 1173.22 100.00 1.017E+003 8.65E+002 -5.651E+002 4.629E+002 1332.49 100.00 8.647E+002 2.069E+002 3.837E+002 CS-134 475.35 1.46 6.318E+004 1.13E+003 4.663E+004 2.972E+004 563.23 8.38 9.978E+003 8.110E+003 4.629E+003 569.32 15.43 5.028E+003 -5.573E+002 2.317E+003 604.70 97.60 1.203E+003 1.342E+003 5.695E+002 795.84 85.40 1.133E+003 1.395E+003 5.234E+002 801.93 8.73 1.154E+004 -8.540E+002 5.345E+003 1038.57 1.00 1.143E+005 4.764E+004 5.291E+004 1167.94 1.80 5.411E+004 3.123E+004 2.453E+004 1365.15 3.04 2.637E+004 2.090E+003 1.155E+004 CS-137 661.65 85.12 1.022E+003 1.02E+003 6.595E+002 4.721E+002 EU-152 121.78 28.40 4.027E+003 3.60E+003 4.033E+002 1.956E+003 344.27 26.50 3.596E+003 -7.235E+002 1.712E+003 1407.95 20.70 4.345E+003 -6.415E+002 1.928E+003 EU-154 123.07 40.40 2.862E+003 2.51E+003 2.098E+003 1.391E+003 722.30 20.00 5.167E+003 3.582E+003 2.410E+003 1274.51 34.40 2.506E+003 -1.159E+003 1.115E+003 BI-214 609.31 46.30 2.525E+003 2.52E+003 1.900E+003 1.194E+003 768.36 5.04 1.638E+004 9.050E+003 7.476E+003 806.17 1.23 7.702E+004 1.264E+004 3.550E+004 934.06 3.21 2.876E+004 2.929E+004 1.313E+004 1120.29 15.10 7.448E+003 5.435E+001 3.430E+003 1155.19 1.69 5.480E+004 -1.630E+004 2.473E+004 1238.11 5.94 2.055E+004 6.656E+003 9.489E+003 1280.96 1.47 6.551E+004 1.070E+003 2.951E+004 1377.67 4.11 2.200E+004 6.542E+003 9.785E+003 1385.31 0.78 1.065E+005 -1.316E+005 4.682E+004 1401.50 1.39 6.311E+004 -1.446E+004 2.793E+004 1407.98 2.48 3.627E+004 -5.355E+003 1.609E+004 1509.19 2.19 2.993E+004 -3.393E+003 1.253E+004 1661.28 1.15 5.166E+004 -6.593E+004 2.087E+004 1729.60 3.05 1.707E+004 5.685E+003 6.613E+003 1764.49 15.80 6.398E+003 5.288E+003 2.822E+003 1847.44 2.12 3.556E+004 1.920E+004 1.489E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.729E+004 1.48E+003 2.556E+004 1.813E+004 77.11 10.70 2.014E+004 6.279E+003 9.787E+003 87.20 3.70 4.404E+004 1.698E+004 2.144E+004 89.80 1.03 1.558E+005 3.870E+003 7.593E+004 241.98 7.49 1.438E+004 8.728E+003 6.935E+003
Nuclide MDA Report 3/27/2019 8:29:08 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.180E+003 1.48E+003 2.090E+003 2.480E+003 351.92* 37.20 1.476E+003 1.949E+003 6.760E+002 785.91 1.10 7.510E+004 -4.966E+004 3.423E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D04-GM.CNF Report Generated On : 3/27/2019 8:30:18 PM Sample Title : B1-010-001-FSFC-D04-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D04 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 2:10:00 PM Acquisition Started : 3/27/2019 2:11:16 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:30:18 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D04-GM Peak Analysis Performed on: 3/27/2019 8:30:18 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 961 954.26 238.64 0.73 3.84E+001 31.88 7.36E+001 2 1401- 1414 1407.11 351.92 0.40 3.07E+001 20.67 2.73E+001 3 2324- 2336 2330.83 582.96 0.69 3.00E+001 19.82 2.60E+001 4 2433- 2444 2438.65 609.92 0.70 3.77E+001 13.92 4.33E+000 5 2639- 2650 2644.74 661.45 0.47 1.24E+001 15.91 1.86E+001 6 5831- 5855 5843.29 1460.83 1.46 2.38E+002 33.29 9.48E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:30:18 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D04-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 1.000 1460.81* 10.67 8.55485E+004 1.39173E+004 CS-137 0.999 661.65* 85.12 3.56348E+002 4.58498E+002 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.19401E+003 1.01036E+003 300.09 3.41 BI-214 0.997 609.31* 46.30 1.89710E+003 7.41675E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.41071E+003 9.77008E+002 785.91 1.10
Interference Corrected Activity Report 3/27/2019 8:30:18 PM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:30:18 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 1.000 8.554853E+004 1.391730E+004 CS-137 0.999 3.563483E+002 4.584976E+002 PB-212 1.000 1.194014E+003 1.010357E+003 BI-214 0.997 1.897095E+003 7.416747E+002 PB-214 1.000 1.410711E+003 9.770084E+002
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:30:18 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 582.96 5.0000E-002 66.08 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:30:18 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D04-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 8.421E+003 8.42E+003 8.555E+004 3.723E+003 CO-60 1173.22 100.00 1.068E+003 9.99E+002 -9.824E+002 4.887E+002 1332.49 100.00 9.991E+002 2.730E+001 4.509E+002 CS-134 475.35 1.46 6.558E+004 1.11E+003 1.230E+004 3.092E+004 563.23 8.38 1.158E+004 5.376E+003 5.428E+003 569.32 15.43 6.552E+003 2.730E+003 3.080E+003 604.70 97.60 1.125E+003 -6.921E+002 5.305E+002 795.84 85.40 1.112E+003 -2.227E+002 5.129E+002 801.93 8.73 1.038E+004 -5.033E+003 4.769E+003 1038.57 1.00 9.023E+004 -1.478E+005 4.085E+004 1167.94 1.80 5.851E+004 -1.715E+004 2.673E+004 1365.15 3.04 2.098E+004 -1.771E+004 8.861E+003 + CS-137 661.65* 85.12 7.509E+002 7.51E+002 3.563E+002 3.366E+002 EU-152 121.78 28.40 3.868E+003 3.77E+003 -2.247E+003 1.876E+003 344.27 26.50 3.772E+003 1.133E+003 1.800E+003 1407.95 20.70 4.157E+003 5.877E+002 1.834E+003 EU-154 123.07 40.40 2.705E+003 2.70E+003 -2.103E+003 1.312E+003 722.30 20.00 5.313E+003 4.430E+003 2.483E+003 1274.51 34.40 3.049E+003 1.728E+003 1.386E+003 + BI-214 609.31* 46.30 6.794E+002 6.79E+002 1.897E+003 2.716E+002 768.36 5.04 1.983E+004 -1.132E+002 9.198E+003 806.17 1.23 7.925E+004 6.308E+004 3.661E+004 934.06 3.21 3.480E+004 1.229E+004 1.615E+004 1120.29 15.10 7.952E+003 -1.046E+002 3.682E+003 1155.19 1.69 5.394E+004 9.659E+003 2.430E+004 1238.11 5.94 1.894E+004 -2.368E+004 8.680E+003 1280.96 1.47 6.860E+004 -1.972E+004 3.105E+004 1377.67 4.11 1.804E+004 1.255E+004 7.806E+003 1385.31 0.78 8.930E+004 2.510E+004 3.823E+004 1401.50 1.39 5.876E+004 -2.795E+004 2.575E+004 1407.98 2.48 3.470E+004 4.906E+003 1.531E+004 1509.19 2.19 3.129E+004 5.253E+003 1.321E+004 1661.28 1.15 6.895E+004 -1.160E+004 2.952E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49 15.80 6.398E+003 2.963E+003 2.822E+003 1847.44 2.12 3.386E+004 -5.201E+003 1.404E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.837E+004 1.44E+003 3.122E+004 1.867E+004 77.11 10.70 2.082E+004 -8.133E+002 1.013E+004 87.20 3.70 4.362E+004 1.458E+004 2.123E+004 89.80 1.03 1.506E+005 7.113E+004 7.333E+004 241.98 7.49 1.413E+004 8.121E+003 6.812E+003
Nuclide MDA Report 3/27/2019 8:30:18 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 4.885E+003 1.44E+003 1.899E+003 2.333E+003 351.92* 37.20 1.445E+003 1.411E+003 6.601E+002 785.91 1.10 9.279E+004 2.222E+004 4.308E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FSFC-D05-GM.CNF Report Generated On : 3/27/2019 8:34:05 PM Sample Title : B1-010-001-FSFC-D05-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D05 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 2:24:00 PM Acquisition Started : 3/27/2019 2:24:27 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:34:05 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D05-GM Peak Analysis Performed on: 3/27/2019 8:34:04 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 960 954.12 238.60 0.41 3.18E+001 31.18 7.82E+001 2 1401- 1412 1406.49 351.77 0.73 3.03E+001 22.38 3.77E+001 3 2038- 2050 2043.69 511.14 1.30 3.42E+001 21.00 2.88E+001 4 2325- 2338 2331.28 583.07 0.49 3.11E+001 18.52 1.89E+001 5 2430- 2442 2436.78 609.45 0.35 2.61E+001 17.16 1.79E+001 6 5832- 5856 5843.82 1460.96 1.69 2.45E+002 32.05 2.96E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:34:05 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D05-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 1.000 1460.81* 10.67 8.82601E+004 1.36548E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 9.88705E+002 9.82869E+002 300.09 3.41 BI-214 1.000 609.31* 46.30 1.31608E+003 8.80127E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.39433E+003 1.05307E+003 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:34:05 PM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 1.000 8.826012E+004 1.365481E+004 PB-212 1.000 9.887050E+002 9.828690E+002 BI-214 1.000 1.316075E+003 8.801266E+002 PB-214 1.000 1.394333E+003 1.053071E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:34:04 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 511.14 5.6997E-002 61.40 4 583.07 5.1833E-002 59.55 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:34:05 PM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D05-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 5.046E+003 5.05E+003 8.826E+004 2.035E+003 CO-60 1173.22 100.00 1.152E+003 7.46E+002 1.034E+003 5.307E+002 1332.49 100.00 7.459E+002 -5.578E+002 3.243E+002 CS-134 475.35 1.46 6.177E+004 1.06E+003 -1.146E+004 2.901E+004 563.23 8.38 1.054E+004 -1.653E+004 4.910E+003 569.32 15.43 5.927E+003 -1.423E+003 2.767E+003 604.70 97.60 1.060E+003 2.338E+002 4.978E+002 795.84 85.40 1.164E+003 -1.037E+002 5.389E+002 801.93 8.73 1.134E+004 -4.599E+002 5.245E+003 1038.57 1.00 9.779E+004 2.344E+002 4.463E+004 1167.94 1.80 5.851E+004 3.088E+004 2.673E+004 1365.15 3.04 2.568E+004 9.034E+002 1.121E+004 CS-137 661.65 85.12 1.012E+003 1.01E+003 2.220E+002 4.673E+002 EU-152 121.78 28.40 4.261E+003 3.15E+003 1.552E+003 2.073E+003 344.27 26.50 3.505E+003 1.952E+002 1.666E+003 1407.95 20.70 3.150E+003 1.808E+003 1.330E+003 EU-154 123.07 40.40 2.965E+003 2.84E+003 8.934E+002 1.442E+003 722.30 20.00 5.016E+003 -2.762E+003 2.334E+003 1274.51 34.40 2.837E+003 -1.533E+002 1.280E+003 + BI-214 609.31* 46.30 1.277E+003 1.28E+003 1.316E+003 5.706E+002 768.36 5.04 1.898E+004 1.572E+003 8.778E+003 806.17 1.23 8.070E+004 -6.677E+003 3.734E+004 934.06 3.21 2.692E+004 2.298E+004 1.221E+004 1120.29 15.10 7.882E+003 8.758E+002 3.647E+003 1155.19 1.69 5.565E+004 2.678E+004 2.515E+004 1238.11 5.94 1.915E+004 6.840E+003 8.785E+003 1280.96 1.47 6.114E+004 1.698E+003 2.732E+004 1377.67 4.11 2.061E+004 -1.031E+004 9.093E+003 1385.31 0.78 1.065E+005 -2.655E+004 4.682E+004 1401.50 1.39 5.563E+004 -8.947E+001 2.418E+004 1407.98 2.48 2.629E+004 1.509E+004 1.110E+004 1509.19 2.19 3.613E+004 -2.906E+004 1.563E+004 1661.28 1.15 3.943E+004 1.099E+004 1.476E+004 1729.60 3.05 2.255E+004 1.137E+004 9.353E+003 1764.49 15.80 6.687E+003 1.183E+003 2.967E+003 1847.44 2.12 3.204E+004 -2.081E+004 1.313E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.672E+004 1.60E+003 8.716E+003 1.784E+004 77.11 10.70 2.059E+004 2.072E+003 1.001E+004 87.20 3.70 4.385E+004 1.715E+004 2.135E+004 89.80 1.03 1.500E+005 -2.557E+004 7.300E+004 241.98 7.49 1.440E+004 6.679E+003 6.949E+003
Nuclide MDA Report 3/27/2019 8:34:05 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 4.915E+003 1.60E+003 -1.809E+003 2.348E+003 351.92* 37.20 1.598E+003 1.394E+003 7.369E+002 785.91 1.10 8.813E+004 6.877E+003 4.075E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D06-GM.CNF Report Generated On : 3/27/2019 8:35:33 PM Sample Title : B1-010-001-FSFC-D06-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D06 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 2:48:00 PM Acquisition Started : 3/27/2019 2:49:06 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:35:33 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D06-GM Peak Analysis Performed on: 3/27/2019 8:35:33 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 367- 378 371.93 92.93 1.09 3.53E+001 35.84 1.14E+002 2 946- 961 955.12 238.85 1.03 5.48E+001 35.47 8.62E+001 3 1402- 1413 1407.47 352.01 0.38 3.17E+001 19.37 2.43E+001 4 1730- 1741 1735.75 434.13 0.78 1.42E+001 10.79 5.82E+000 5 2326- 2338 2331.95 583.23 0.59 2.08E+001 16.90 1.93E+001 6 5833- 5856 5844.08 1461.03 2.10 2.10E+002 31.05 8.22E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:35:33 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D06-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.999 1460.81* 10.67 7.55654E+004 1.28076E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.70753E+003 1.13741E+003 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.45801E+003 9.21153E+002 785.91 1.10 PA-234 0.994 94.67* 15.50 3.37392E+003 3.48891E+003 98.44 25.10 111.00 8.55 131.28 20.00 152.70 7.20 226.87 6.50 569.26 10.40 733.00 8.50 883.24 12.00 946.00 20.00 949.00 7.80
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:35:33 PM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.999 7.556540E+004 1.280759E+004 PB-212 1.000 1.707528E+003 1.137406E+003 PB-214 1.000 1.458007E+003 9.211533E+002 PA-234 0.994 3.373922E+003 3.488915E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:35:33 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 4 434.13 2.3625E-002 76.10 5 583.23 3.4583E-002 81.45 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:35:33 PM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D06-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 7.593E+003 7.59E+003 7.557E+004 3.309E+003 CO-60 1173.22 100.00 1.043E+003 8.08E+002 4.832E+002 4.760E+002 1332.49 100.00 8.078E+002 6.478E+002 3.552E+002 CS-134 475.35 1.46 6.212E+004 1.16E+003 -3.792E+004 2.919E+004 563.23 8.38 1.129E+004 -6.146E+003 5.285E+003 569.32 15.43 6.209E+003 -1.530E+003 2.908E+003 604.70 97.60 1.187E+003 1.504E+003 5.613E+002 795.84 85.40 1.164E+003 -3.084E+002 5.389E+002 801.93 8.73 1.071E+004 -5.276E+003 4.933E+003 1038.57 1.00 8.335E+004 -6.034E+004 3.741E+004 1167.94 1.80 5.636E+004 -2.004E+004 2.566E+004 1365.15 3.04 2.496E+004 9.475E+003 1.085E+004 CS-137 661.65 85.12 1.068E+003 1.07E+003 4.367E+002 4.951E+002 EU-152 121.78 28.40 4.131E+003 3.57E+003 1.597E+002 2.008E+003 344.27 26.50 3.570E+003 2.058E+003 1.699E+003 1407.95 20.70 3.958E+003 2.260E+002 1.735E+003 EU-154 123.07 40.40 2.876E+003 2.65E+003 -4.856E+002 1.398E+003 722.30 20.00 5.313E+003 -5.684E+003 2.483E+003 1274.51 34.40 2.654E+003 -3.229E+003 1.189E+003 BI-214 609.31 46.30 2.283E+003 2.28E+003 1.573E+003 1.073E+003 768.36 5.04 1.810E+004 -3.388E+003 8.336E+003 806.17 1.23 7.152E+004 1.920E+004 3.275E+004 934.06 3.21 3.048E+004 3.896E+004 1.398E+004 1120.29 15.10 8.291E+003 6.300E+003 3.851E+003 1155.19 1.69 5.890E+004 6.909E+003 2.678E+004 1238.11 5.94 2.187E+004 9.432E+003 1.014E+004 1280.96 1.47 6.337E+004 5.648E+003 2.844E+004 1377.67 4.11 2.287E+004 -1.183E+004 1.022E+004 1385.31 0.78 1.038E+005 -1.466E+005 4.550E+004 1401.50 1.39 5.876E+004 2.822E+004 2.575E+004 1407.98 2.48 3.304E+004 1.887E+003 1.448E+004 1509.19 2.19 2.850E+004 3.143E+003 1.182E+004 1661.28 1.15 5.500E+004 2.564E+004 2.254E+004 1729.60 3.05 2.255E+004 -7.551E+002 9.353E+003 1764.49 15.80 5.768E+003 4.175E+003 2.508E+003 1847.44 2.12 3.870E+004 -1.145E+004 1.646E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.879E+004 1.32E+003 6.038E+004 1.888E+004 77.11 10.70 2.070E+004 -8.324E+002 1.007E+004 87.20 3.70 4.205E+004 8.748E+003 2.045E+004 89.80 1.03 1.490E+005 2.494E+004 7.252E+004 241.98 7.49 1.475E+004 1.486E+004 7.123E+003
Nuclide MDA Report 3/27/2019 8:35:33 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.093E+003 1.32E+003 3.541E+003 2.437E+003 351.92* 37.20 1.317E+003 1.458E+003 5.964E+002 785.91 1.10 9.429E+004 -6.578E+003 4.382E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FSFC-D07-GM.CNF Report Generated On : 3/27/2019 8:38:30 PM Sample Title : B1-010-001-FSFC-D07-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D07 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 3:00:00 PM Acquisition Started : 3/27/2019 3:01:05 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:38:30 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D07-GM Peak Analysis Performed on: 3/27/2019 8:38:30 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 949- 960 954.18 238.61 0.79 5.41E+001 27.90 5.49E+001 2 1108- 1120 1113.16 278.39 0.51 2.95E+001 18.61 2.15E+001 3 2034- 2052 2040.92 510.45 0.63 5.69E+001 26.22 3.41E+001 4 2325- 2339 2331.77 583.19 0.34 3.52E+001 18.27 1.68E+001 5 2430- 2443 2436.51 609.38 0.83 3.69E+001 16.75 1.21E+001 6 3637- 3650 3643.26 911.09 0.57 3.74E+001 15.62 8.60E+000 7 5832- 5855 5844.24 1461.07 1.68 2.33E+002 34.15 1.46E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:38:30 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D07-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.999 1460.81* 10.67 8.40820E+004 1.41266E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.68304E+003 9.08872E+002 300.09 3.41 BI-214 1.000 609.31* 46.30 1.85745E+003 8.76162E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.999 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.96558E+003 1.71820E+003 964.60 5.20 969.11 16.60 1587.90 3.71
Interference Corrected Activity Report 3/27/2019 8:38:30 PM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:38:30 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.999 8.408196E+004 1.412660E+004 PB-212 1.000 1.683045E+003 9.088725E+002 BI-214 1.000 1.857446E+003 8.761620E+002 AC-228 0.999 3.965578E+003 1.718204E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:38:30 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 278.39 4.9126E-002 63.15 3 510.45 9.4821E-002 46.10 4 583.19 5.8694E-002 51.88 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:38:30 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D07-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 1.001E+004 1.00E+004 8.408E+004 4.517E+003 CO-60 1173.22 100.00 1.152E+003 8.27E+002 -4.991E+002 5.307E+002 1332.49 100.00 8.273E+002 -4.139E+002 3.650E+002 CS-134 475.35 1.46 5.410E+004 1.13E+003 -3.810E+003 2.517E+004 563.23 8.38 1.129E+004 5.118E+003 5.285E+003 569.32 15.43 6.913E+003 6.173E+003 3.260E+003 604.70 97.60 1.125E+003 -5.464E+002 5.305E+002 795.84 85.40 1.184E+003 -2.183E+002 5.490E+002 801.93 8.73 1.202E+004 1.541E+003 5.587E+003 1038.57 1.00 9.154E+004 7.998E+004 4.150E+004 1167.94 1.80 5.781E+004 -1.631E+004 2.638E+004 1365.15 3.04 2.098E+004 -4.198E+004 8.861E+003 CS-137 661.65 85.12 1.068E+003 1.07E+003 -7.019E+002 4.951E+002 EU-152 121.78 28.40 3.920E+003 3.45E+003 -3.538E+003 1.902E+003 344.27 26.50 3.452E+003 1.804E+002 1.639E+003 1407.95 20.70 4.436E+003 3.978E+003 1.973E+003 EU-154 123.07 40.40 2.810E+003 2.81E+003 1.180E+003 1.364E+003 722.30 20.00 5.593E+003 3.627E+003 2.623E+003 1274.51 34.40 2.837E+003 -5.902E+001 1.280E+003 + BI-214 609.31* 46.30 1.091E+003 1.09E+003 1.857E+003 4.776E+002 768.36 5.04 2.079E+004 3.698E+003 9.678E+003 806.17 1.23 7.626E+004 -1.935E+002 3.512E+004 934.06 3.21 2.946E+004 -1.231E+004 1.348E+004 1120.29 15.10 7.740E+003 2.943E+003 3.576E+003 1155.19 1.69 6.415E+004 -1.212E+004 2.941E+004 1238.11 5.94 1.807E+004 -5.449E+003 8.246E+003 1280.96 1.47 5.999E+004 -1.798E+004 2.675E+004 1377.67 4.11 2.244E+004 4.835E+003 1.000E+004 1385.31 0.78 1.090E+005 -1.548E+004 4.810E+004 1401.50 1.39 5.563E+004 2.657E+004 2.418E+004 1407.98 2.48 3.702E+004 3.321E+004 1.647E+004 1509.19 2.19 3.258E+004 6.123E+003 1.386E+004 1661.28 1.15 5.166E+004 2.198E+004 2.087E+004 1729.60 3.05 2.005E+004 -4.205E+003 8.100E+003 1764.49 15.80 6.544E+003 5.566E+003 2.896E+003 1847.44 2.12 3.386E+004 -8.869E+003 1.404E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.772E+004 2.59E+003 3.704E+004 1.834E+004 77.11 10.70 2.030E+004 -6.488E+003 9.870E+003 87.20 3.70 4.367E+004 1.065E+004 2.125E+004 89.80 1.03 1.490E+005 -2.542E+004 7.252E+004 241.98 7.49 1.454E+004 1.842E+004 7.016E+003
Nuclide MDA Report 3/27/2019 8:38:30 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 4.792E+003 2.59E+003 -1.324E+003 2.286E+003 351.92 37.20 2.592E+003 3.942E+001 1.234E+003 785.91 1.10 8.651E+004 -1.644E+004 3.994E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D08-GM.CNF Report Generated On : 3/27/2019 8:40:19 PM Sample Title : B1-010-001-FSFC-D08-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D08 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 3:12:00 PM Acquisition Started : 3/27/2019 3:13:36 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:40:19 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D08-GM Peak Analysis Performed on: 3/27/2019 8:40:19 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 964 953.76 238.51 0.68 6.32E+001 35.46 7.68E+001 2 1402- 1415 1408.72 352.33 0.81 3.97E+001 21.82 2.83E+001 3 2327- 2338 2332.56 583.39 1.47 2.28E+001 19.45 2.72E+001 4 2431- 2443 2436.48 609.38 0.42 3.09E+001 19.66 2.41E+001 5 3637- 3650 3643.59 911.17 0.73 2.28E+001 17.39 1.92E+001 6 5833- 5855 5844.50 1461.13 1.30 2.10E+002 30.50 5.75E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:40:19 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D08-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.998 1460.81* 10.67 7.57370E+004 1.26436E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.96598E+003 1.14715E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.55413E+003 1.00934E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.82731E+003 1.04579E+003 785.91 1.10 AC-228 0.999 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40
Interference Corrected Activity Report 3/27/2019 8:40:19 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.999 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.41977E+003 1.86471E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:40:19 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.998 7.573698E+004 1.264356E+004 PB-212 1.000 1.965977E+003 1.147153E+003 BI-214 1.000 1.554125E+003 1.009343E+003 PB-214 0.999 1.827312E+003 1.045788E+003 AC-228 0.999 2.419773E+003 1.864711E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:40:19 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 583.39 3.8000E-002 85.31 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:40:20 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D08-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 6.573E+003 6.57E+003 7.574E+004 2.799E+003 CO-60 1173.22 100.00 1.175E+003 9.51E+002 -1.843E+002 5.421E+002 1332.49 100.00 9.512E+002 -6.776E+002 4.269E+002 CS-134 475.35 1.46 5.958E+004 1.10E+003 -3.321E+003 2.791E+004 563.23 8.38 1.158E+004 2.037E+003 5.428E+003 569.32 15.43 6.440E+003 3.428E+003 3.023E+003 604.70 97.60 1.182E+003 -1.096E+003 5.586E+002 795.84 85.40 1.101E+003 6.205E+002 5.075E+002 801.93 8.73 1.016E+004 3.153E+003 4.657E+003 1038.57 1.00 8.618E+004 -4.246E+004 3.882E+004 1167.94 1.80 6.058E+004 6.548E+003 2.777E+004 1365.15 3.04 2.832E+004 5.721E+003 1.253E+004 CS-137 661.65 85.12 1.129E+003 1.13E+003 -3.257E+002 5.257E+002 EU-152 121.78 28.40 4.057E+003 3.65E+003 8.439E+002 1.971E+003 344.27 26.50 3.647E+003 1.678E+003 1.737E+003 1407.95 20.70 3.958E+003 2.260E+002 1.735E+003 EU-154 123.07 40.40 2.838E+003 2.84E+003 7.195E+002 1.378E+003 722.30 20.00 4.740E+003 5.946E+003 2.196E+003 1274.51 34.40 2.966E+003 2.396E+003 1.345E+003 + BI-214 609.31* 46.30 1.479E+003 1.48E+003 1.554E+003 6.714E+002 768.36 5.04 2.200E+004 8.340E+003 1.028E+004 806.17 1.23 6.902E+004 -1.185E+004 3.150E+004 934.06 3.21 3.178E+004 1.593E+004 1.463E+004 1120.29 15.10 7.811E+003 6.187E+003 3.612E+003 1155.19 1.69 6.270E+004 1.708E+003 2.868E+004 1238.11 5.94 1.956E+004 7.866E+003 8.992E+003 1280.96 1.47 7.248E+004 4.735E+004 3.300E+004 1377.67 4.11 2.287E+004 -5.829E+003 1.022E+004 1385.31 0.78 1.187E+005 1.091E+005 5.293E+004 1401.50 1.39 5.563E+004 4.026E+004 2.418E+004 1407.98 2.48 3.304E+004 1.887E+003 1.448E+004 1509.19 2.19 3.499E+004 -3.661E+003 1.507E+004 1661.28 1.15 3.401E+004 7.326E+003 1.205E+004 1729.60 3.05 2.255E+004 1.137E+004 9.353E+003 1764.49 15.80 7.097E+003 4.201E+003 3.172E+003 1847.44 2.12 4.017E+004 2.561E+004 1.720E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.772E+004 1.47E+003 5.659E+004 1.834E+004 77.11 10.70 2.077E+004 2.223E+004 1.010E+004 87.20 3.70 4.431E+004 1.686E+003 2.158E+004 89.80 1.03 1.530E+005 -3.363E+004 7.452E+004 241.98 7.49 1.446E+004 1.941E+004 6.976E+003
Nuclide MDA Report 3/27/2019 8:40:20 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.020E+003 1.47E+003 1.541E+003 2.400E+003 351.92* 37.20 1.473E+003 1.827E+003 6.742E+002 785.91 1.10 7.790E+004 -2.585E+004 3.563E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D09-GM.CNF Report Generated On : 3/27/2019 8:42:37 PM Sample Title : B1-010-001-FSFC-D09-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D09 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 3:24:00 PM Acquisition Started : 3/27/2019 3:26:28 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:42:38 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D09-GM Peak Analysis Performed on: 3/27/2019 8:42:37 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 1402- 1413 1407.61 352.05 0.82 2.80E+001 19.55 2.70E+001 2 2037- 2049 2043.60 511.12 0.90 2.40E+001 22.55 3.90E+001 3 2326- 2337 2331.49 583.12 0.39 1.76E+001 16.27 1.94E+001 4 2431- 2442 2436.10 609.28 0.53 2.25E+001 18.09 2.35E+001 5 5834- 5856 5844.61 1461.16 1.18 2.24E+002 31.61 6.26E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:42:38 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D09-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.998 1460.81* 10.67 8.05979E+004 1.31902E+004 BI-214 1.000 609.31* 46.30 1.13364E+003 9.22163E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.28805E+003 9.22427E+002 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:42:38 PM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.998 8.059794E+004 1.319019E+004 BI-214 1.000 1.133636E+003 9.221627E+002 PB-214 1.000 1.288046E+003 9.224265E+002
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:42:37 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 511.12 3.9987E-002 94.01 3 583.12 2.9291E-002 92.58 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:42:38 PM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D09-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 7.021E+003 7.02E+003 8.060E+004 3.023E+003 CO-60 1173.22 100.00 1.081E+003 9.35E+002 1.066E+002 4.949E+002 1332.49 100.00 9.346E+002 -1.979E+002 4.186E+002 CS-134 475.35 1.46 6.032E+004 1.07E+003 -3.103E+004 2.828E+004 563.23 8.38 1.046E+004 2.425E+003 4.871E+003 569.32 15.43 5.802E+003 2.041E+003 2.704E+003 604.70 97.60 1.209E+003 6.538E+002 5.721E+002 795.84 85.40 1.068E+003 8.316E+001 4.910E+002 801.93 8.73 1.060E+004 -5.523E+002 4.879E+003 1038.57 1.00 1.164E+005 5.344E+004 5.391E+004 1167.94 1.80 5.334E+004 -1.380E+004 2.415E+004 1365.15 3.04 2.704E+004 -6.625E+003 1.189E+004 CS-137 661.65 85.12 1.112E+003 1.11E+003 7.554E+002 5.171E+002 EU-152 121.78 28.40 3.956E+003 3.48E+003 -6.780E+002 1.920E+003 344.27 26.50 3.478E+003 -2.214E+003 1.653E+003 1407.95 20.70 4.157E+003 1.142E+002 1.834E+003 EU-154 123.07 40.40 2.799E+003 2.80E+003 2.203E+003 1.359E+003 722.30 20.00 4.268E+003 -4.202E+003 1.960E+003 1274.51 34.40 2.837E+003 2.963E+003 1.280E+003 + BI-214 609.31* 46.30 1.412E+003 1.41E+003 1.134E+003 6.377E+002 768.36 5.04 2.110E+004 1.202E+004 9.833E+003 806.17 1.23 6.816E+004 -1.199E+004 3.107E+004 934.06 3.21 2.730E+004 -2.902E+003 1.240E+004 1120.29 15.10 7.596E+003 7.443E+003 3.504E+003 1155.19 1.69 6.627E+004 -4.711E+002 3.046E+004 1238.11 5.94 1.894E+004 1.121E+004 8.680E+003 1280.96 1.47 5.881E+004 2.398E+004 2.616E+004 1377.67 4.11 2.061E+004 -4.260E+003 9.093E+003 1385.31 0.78 9.832E+004 -1.278E+005 4.274E+004 1401.50 1.39 5.876E+004 -3.624E+004 2.575E+004 1407.98 2.48 3.470E+004 9.533E+002 1.531E+004 1509.19 2.19 3.258E+004 -2.208E+004 1.386E+004 1661.28 1.15 5.500E+004 2.564E+004 2.254E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49 15.80 5.422E+003 1.194E+003 2.334E+003 1847.44 2.12 2.297E+004 6.402E+003 8.598E+003 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.879E+004 1.37E+003 -1.217E+004 1.888E+004 77.11 10.70 2.181E+004 2.265E+004 1.062E+004 87.20 3.70 4.196E+004 -3.801E+004 2.040E+004 89.80 1.03 1.477E+005 -4.014E+004 7.187E+004 241.98 7.49 1.435E+004 -4.015E+003 6.921E+003
Nuclide MDA Report 3/27/2019 8:42:38 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.049E+003 1.37E+003 5.674E+003 2.415E+003 351.92* 37.20 1.368E+003 1.288E+003 6.217E+002 785.91 1.10 7.510E+004 -2.863E+004 3.423E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D10-GM.CNF Report Generated On : 3/27/2019 8:44:50 PM Sample Title : B1-010-001-FSFC-D10-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D10 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 3:38:00 PM Acquisition Started : 3/27/2019 3:39:27 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:44:50 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D10-GM Peak Analysis Performed on: 3/27/2019 8:44:50 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 294- 304 299.78 74.88 0.42 3.75E+001 35.23 1.14E+002 2 1228- 1239 1233.23 308.43 0.26 1.35E+001 16.71 2.25E+001 3 1403- 1414 1408.20 352.20 0.92 2.82E+001 20.28 2.98E+001 4 2325- 2338 2331.55 583.14 1.69 3.50E+001 17.25 1.30E+001 5 2429- 2443 2436.08 609.27 0.75 4.80E+001 19.12 1.50E+001 6 3639- 3652 3645.34 911.61 0.85 2.12E+001 13.38 7.76E+000 7 5833- 5857 5844.75 1461.20 1.49 2.50E+002 34.97 1.42E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:44:50 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D10-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.997 1460.81* 10.67 8.99765E+004 1.46260E+004 BI-214 1.000 609.31* 46.30 2.41608E+003 1.01102E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.625 74.81* 6.33 1.43004E+004 1.37424E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.29785E+003 9.55855E+002 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.25283E+003 1.44228E+003 964.60 5.20 969.11 16.60 1587.90 3.71
Interference Corrected Activity Report 3/27/2019 8:44:50 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:44:50 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.997 8.997647E+004 1.462597E+004 BI-214 1.000 2.416080E+003 1.011022E+003 PB-214 0.625 1.360457E+003 9.535513E+002 AC-228 1.000 2.252832E+003 1.442279E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:44:50 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 308.43 2.2512E-002 123.71 4 583.14 5.8325E-002 49.29 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:44:50 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D10-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 9.835E+003 9.84E+003 8.998E+004 4.430E+003 CO-60 1173.22 100.00 1.105E+003 8.46E+002 1.113E+002 5.071E+002 1332.49 100.00 8.463E+002 1.431E+002 3.744E+002 CS-134 475.35 1.46 5.883E+004 1.08E+003 -1.502E+004 2.754E+004 563.23 8.38 1.014E+004 -8.718E+003 4.711E+003 569.32 15.43 5.497E+003 1.876E+003 2.552E+003 604.70 97.60 1.219E+003 -1.152E+003 5.775E+002 795.84 85.40 1.079E+003 -3.500E+001 4.966E+002 801.93 8.73 9.574E+003 -7.134E+003 4.364E+003 1038.57 1.00 9.534E+004 -5.722E+003 4.340E+004 1167.94 1.80 6.126E+004 4.987E+004 2.811E+004 1365.15 3.04 3.014E+004 1.822E+004 1.344E+004 CS-137 661.65 85.12 1.077E+003 1.08E+003 4.215E+002 4.996E+002 EU-152 121.78 28.40 3.951E+003 3.50E+003 2.617E+003 1.918E+003 344.27 26.50 3.505E+003 -1.455E+003 1.666E+003 1407.95 20.70 4.059E+003 -1.007E+003 1.785E+003 EU-154 123.07 40.40 2.759E+003 2.76E+003 5.932E+002 1.339E+003 722.30 20.00 4.781E+003 1.792E+003 2.217E+003 1274.51 34.40 2.966E+003 1.076E+003 1.345E+003 + BI-214 609.31* 46.30 1.227E+003 1.23E+003 2.416E+003 5.456E+002 768.36 5.04 1.864E+004 -8.006E+002 8.604E+003 806.17 1.23 6.641E+004 -2.321E+004 3.019E+004 934.06 3.21 3.241E+004 4.870E+003 1.495E+004 1120.29 15.10 7.882E+003 4.502E+003 3.647E+003 1155.19 1.69 6.557E+004 4.889E+003 3.012E+004 1238.11 5.94 2.016E+004 1.899E+004 9.293E+003 1280.96 1.47 6.226E+004 4.963E+003 2.789E+004 1377.67 4.11 2.155E+004 5.156E+003 9.560E+003 1385.31 0.78 1.140E+005 5.676E+004 5.057E+004 1401.50 1.39 5.876E+004 -3.193E+004 2.575E+004 1407.98 2.48 3.388E+004 -8.406E+003 1.490E+004 1509.19 2.19 3.129E+004 -1.033E+004 1.321E+004 1661.28 1.15 5.500E+004 -3.388E+004 2.254E+004 1729.60 3.05 2.859E+004 -3.198E+003 1.237E+004 1764.49 15.80 7.097E+003 6.680E+003 3.172E+003 1847.44 2.12 3.556E+004 2.075E+003 1.489E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81* 6.33 2.177E+004 1.43E+003 1.430E+004 1.037E+004 77.11 10.70 2.150E+004 2.043E+004 1.047E+004 87.20 3.70 4.181E+004 -3.015E+004 2.033E+004 89.80 1.03 1.439E+005 -7.482E+004 6.996E+004 241.98 7.49 1.470E+004 8.014E+003 7.096E+003
Nuclide MDA Report 3/27/2019 8:44:50 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 4.990E+003 1.43E+003 -8.589E+002 2.385E+003 351.92* 37.20 1.432E+003 1.298E+003 6.537E+002 785.91 1.10 8.651E+004 2.615E+003 3.994E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D11-GM.CNF Report Generated On : 3/27/2019 8:46:25 PM Sample Title : B1-010-001-FSFC-D11-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D11 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 10:53:00 AM Acquisition Started : 3/27/2019 10:53:21 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:46:25 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D11-GM Peak Analysis Performed on: 3/27/2019 8:46:25 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 963 955.67 238.99 0.41 7.35E+001 33.29 6.65E+001 2 1404- 1415 1409.58 352.54 0.41 2.97E+001 20.80 3.13E+001 3 2327- 2343 2335.28 584.07 0.99 3.90E+001 20.45 2.10E+001 4 2435- 2447 2440.89 610.48 0.52 3.34E+001 16.06 1.16E+001 5 5840- 5865 5853.02 1463.26 1.19 2.62E+002 33.15 3.11E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:46:25 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D11-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.899 1460.81* 10.67 9.44382E+004 1.42740E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.28791E+003 1.09929E+003 300.09 3.41 BI-214 0.990 609.31* 46.30 1.68420E+003 8.37649E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.610 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98* 7.49 1.36236E+004 6.54586E+003 295.21 19.20 351.92* 37.20 1.36769E+003 9.82184E+002 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:46:25 PM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.899 9.443817E+004 1.427399E+004 PB-212 0.999 2.058228E+003 1.111599E+003 BI-214 0.990 1.684204E+003 8.376486E+002 PB-214 0.610 1.367695E+003 9.821836E+002
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:46:25 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 584.07 6.5028E-002 52.42 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:46:25 PM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D11-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 5.221E+003 5.22E+003 9.444E+004 2.123E+003 CO-60 1173.22 100.00 1.164E+003 7.67E+002 8.270E+002 5.365E+002 1332.49 100.00 7.672E+002 -9.863E+002 3.349E+002 CS-134 475.35 1.46 5.572E+004 1.03E+003 1.631E+003 2.599E+004 563.23 8.38 1.100E+004 1.396E+003 5.139E+003 569.32 15.43 6.287E+003 5.493E+003 2.947E+003 604.70 97.60 1.108E+003 -9.969E+002 5.218E+002 795.84 85.40 1.034E+003 -1.081E+003 4.740E+002 801.93 8.73 1.134E+004 1.554E+003 5.245E+003 1038.57 1.00 1.048E+005 1.760E+003 4.811E+004 1167.94 1.80 5.851E+004 -6.679E+004 2.673E+004 1365.15 3.04 2.185E+004 1.643E+003 9.294E+003 CS-137 661.65 85.12 1.129E+003 1.13E+003 -7.576E+002 5.257E+002 EU-152 121.78 28.40 3.930E+003 3.38E+003 -1.293E+003 1.908E+003 344.27 26.50 3.384E+003 -2.593E+003 1.606E+003 1407.95 20.70 4.059E+003 1.831E+003 1.785E+003 EU-154 123.07 40.40 2.749E+003 2.70E+003 -5.296E+002 1.334E+003 722.30 20.00 5.349E+003 2.737E+003 2.501E+003 1274.51 34.40 2.701E+003 -4.598E+002 1.212E+003 + BI-214 609.31* 46.30 1.061E+003 1.06E+003 1.684E+003 4.622E+002 768.36 5.04 2.110E+004 1.568E+004 9.833E+003 806.17 1.23 7.314E+004 3.227E+004 3.356E+004 934.06 3.21 3.146E+004 -1.074E+004 1.447E+004 1120.29 15.10 7.882E+003 6.293E+003 3.647E+003 1155.19 1.69 6.270E+004 -1.564E+004 2.868E+004 1238.11 5.94 2.016E+004 2.320E+004 9.293E+003 1280.96 1.47 5.637E+004 -2.517E+004 2.494E+004 1377.67 4.11 2.200E+004 1.239E+004 9.785E+003 1385.31 0.78 1.011E+005 -1.927E+004 4.414E+004 1401.50 1.39 5.229E+004 -2.824E+004 2.251E+004 1407.98 2.48 3.388E+004 1.528E+004 1.490E+004 1509.19 2.19 3.258E+004 1.225E+002 1.386E+004 1661.28 1.15 6.104E+004 6.105E+003 2.556E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49 15.80 6.687E+003 5.845E+003 2.967E+003 1847.44 2.12 3.556E+004 1.920E+004 1.489E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.605E+004 1.47E+003 1.271E+004 1.751E+004 77.11 10.70 1.977E+004 -4.661E+003 9.606E+003 87.20 3.70 4.385E+004 1.394E+004 2.135E+004 89.80 1.03 1.503E+005 1.781E+004 7.316E+004 241.98* 7.49 9.205E+003 1.362E+004 4.352E+003
Nuclide MDA Report 3/27/2019 8:46:25 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.223E+003 1.47E+003 1.341E+003 2.502E+003 351.92* 37.20 1.466E+003 1.368E+003 6.707E+002 785.91 1.10 7.970E+004 -1.576E+004 3.653E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D12-GM.CNF Report Generated On : 3/27/2019 8:47:58 PM Sample Title : B1-010-001-FSFC-D12-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D12 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 11:07:00 AM Acquisition Started : 3/27/2019 11:07:30 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:47:58 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D12-GM Peak Analysis Performed on: 3/27/2019 8:47:58 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 306 300.16 74.97 0.71 2.84E+001 34.22 1.10E+002 2 1402- 1413 1407.78 352.09 0.34 2.32E+001 21.25 3.58E+001 3 2430- 2445 2437.14 609.54 0.79 4.84E+001 18.21 1.16E+001 4 3639- 3652 3645.16 911.57 0.70 1.37E+001 16.77 2.03E+001 5 5832- 5858 5845.10 1461.28 2.00 2.65E+002 33.47 3.46E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:47:58 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D12-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.996 1460.81* 10.67 9.52989E+004 1.44002E+004 BI-214 1.000 609.31* 46.30 2.43850E+003 9.68542E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.626 74.81* 6.33 1.07960E+004 1.31881E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.06590E+003 9.92235E+002 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 1.44891E+003 1.78652E+003 964.60 5.20 969.11 16.60 1587.90 3.71
Interference Corrected Activity Report 3/27/2019 8:47:58 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:47:58 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.996 9.529887E+004 1.440018E+004 BI-214 1.000 2.438496E+003 9.685424E+002 PB-214 0.626 1.120671E+003 9.894385E+002 AC-228 1.000 1.448909E+003 1.786520E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:47:58 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/27/2019 8:47:58 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D12-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 5.643E+003 5.64E+003 9.530E+004 2.334E+003 CO-60 1173.22 100.00 9.624E+002 9.00E+002 -4.891E+002 4.357E+002 1332.49 100.00 9.005E+002 5.289E+002 4.015E+002 CS-134 475.35 1.46 5.845E+004 1.20E+003 -1.841E+004 2.735E+004 563.23 8.38 1.179E+004 4.522E+003 5.533E+003 569.32 15.43 5.802E+003 -3.669E+003 2.704E+003 604.70 97.60 1.203E+003 -4.577E+002 5.695E+002 795.84 85.40 1.223E+003 5.295E+002 5.686E+002 801.93 8.73 1.173E+004 -9.834E+003 5.443E+003 1038.57 1.00 9.657E+004 2.365E+004 4.402E+004 1167.94 1.80 5.851E+004 5.740E+003 2.673E+004 1365.15 3.04 3.128E+004 2.461E+004 1.401E+004 CS-137 661.65 85.12 1.249E+003 1.25E+003 8.819E+002 5.858E+002 EU-152 121.78 28.40 3.997E+003 3.52E+003 -9.131E+002 1.941E+003 344.27 26.50 3.557E+003 -2.021E+003 1.692E+003 1407.95 20.70 3.523E+003 1.231E+003 1.517E+003 EU-154 123.07 40.40 2.785E+003 2.35E+003 -2.590E+001 1.352E+003 722.30 20.00 5.277E+003 9.754E+002 2.465E+003 1274.51 34.40 2.349E+003 -2.037E+003 1.036E+003 + BI-214 609.31* 46.30 1.109E+003 1.11E+003 2.438E+003 4.863E+002 768.36 5.04 2.063E+004 6.624E+003 9.600E+003 806.17 1.23 8.282E+004 1.558E+004 3.840E+004 934.06 3.21 3.114E+004 6.345E+003 1.431E+004 1120.29 15.10 7.740E+003 2.868E+003 3.576E+003 1155.19 1.69 6.121E+004 1.339E+004 2.794E+004 1238.11 5.94 2.075E+004 1.623E+004 9.585E+003 1280.96 1.47 6.114E+004 6.518E+003 2.732E+004 1377.67 4.11 1.804E+004 8.967E+002 7.806E+003 1385.31 0.78 1.065E+005 -1.127E+005 4.682E+004 1401.50 1.39 6.311E+004 -6.234E+004 2.793E+004 1407.98 2.48 2.941E+004 1.028E+004 1.266E+004 1509.19 2.19 2.533E+004 -3.600E+004 1.023E+004 1661.28 1.15 5.500E+004 -3.388E+004 2.254E+004 1729.60 3.05 1.707E+004 5.685E+003 6.613E+003 1764.49 15.80 6.963E+003 6.401E+003 3.105E+003 1847.44 2.12 3.204E+004 1.494E+004 1.313E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81* 6.33 2.137E+004 1.56E+003 1.080E+004 1.017E+004 77.11 10.70 2.042E+004 2.574E+004 9.929E+003 87.20 3.70 4.381E+004 2.390E+004 2.132E+004 89.80 1.03 1.571E+005 8.274E+004 7.654E+004 241.98 7.49 1.470E+004 9.073E+003 7.096E+003
Nuclide MDA Report 3/27/2019 8:47:58 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 4.930E+003 1.56E+003 4.131E+002 2.355E+003 351.92* 37.20 1.558E+003 1.066E+003 7.167E+002 785.91 1.10 8.487E+004 -3.627E+004 3.911E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FSFC-D13-GM.CNF Report Generated On : 3/27/2019 8:50:07 PM Sample Title : B1-010-001-FSFC-D13-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D13 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 11:22:00 AM Acquisition Started : 3/27/2019 11:22:50 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:50:07 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D13-GM Peak Analysis Performed on: 3/27/2019 8:50:06 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 960 953.88 238.54 1.59 4.10E+001 30.96 6.90E+001 2 1401- 1413 1406.86 351.86 0.72 3.14E+001 21.77 3.26E+001 3 2325- 2339 2332.88 583.47 0.56 4.16E+001 16.58 9.40E+000 4 5833- 5857 5845.25 1461.32 2.08 2.46E+002 31.37 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:50:07 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D13-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.995 1460.81* 10.67 8.86232E+004 1.34653E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.27485E+003 9.84512E+002 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.44307E+003 1.02743E+003 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:50:07 PM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.995 8.862317E+004 1.346526E+004 PB-212 1.000 1.274851E+003 9.845124E+002 PB-214 1.000 1.443067E+003 1.027428E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:50:06 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 583.47 6.9338E-002 39.86 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:50:07 PM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D13-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 9.749E+002 9.75E+002 8.862E+004 0.000E+000 CO-60 1173.22 100.00 1.017E+003 9.18E+002 -9.228E+002 4.629E+002 1332.49 100.00 9.177E+002 2.879E+002 4.102E+002 CS-134 475.35 1.46 6.388E+004 1.07E+003 4.993E+003 3.006E+004 563.23 8.38 1.143E+004 -2.174E+003 5.357E+003 569.32 15.43 6.050E+003 6.435E+002 2.828E+003 604.70 97.60 1.198E+003 9.592E+002 5.668E+002 795.84 85.40 1.068E+003 -1.625E+003 4.910E+002 801.93 8.73 1.113E+004 -8.255E+003 5.143E+003 1038.57 1.00 9.657E+004 -2.129E+004 4.402E+004 1167.94 1.80 5.636E+004 -3.184E+004 2.566E+004 1365.15 3.04 2.267E+004 -6.273E+003 9.707E+003 CS-137 661.65 85.12 1.103E+003 1.10E+003 5.524E+002 5.128E+002 EU-152 121.78 28.40 3.858E+003 3.52E+003 -7.548E+002 1.871E+003 344.27 26.50 3.916E+003 -3.242E+003 1.872E+003 1407.95 20.70 3.523E+003 -2.267E+003 1.517E+003 EU-154 123.07 40.40 2.741E+003 2.74E+003 2.351E+003 1.330E+003 722.30 20.00 4.700E+003 1.612E+003 2.176E+003 1274.51 34.40 2.792E+003 -1.038E+003 1.258E+003 BI-214 609.31 46.30 2.478E+003 2.48E+003 3.064E+003 1.171E+003 768.36 5.04 1.916E+004 2.021E+004 8.863E+003 806.17 1.23 8.352E+004 3.337E+004 3.875E+004 934.06 3.21 2.911E+004 8.812E+003 1.330E+004 1120.29 15.10 7.740E+003 7.554E+003 3.576E+003 1155.19 1.69 7.029E+004 2.303E+004 3.247E+004 1238.11 5.94 2.075E+004 8.056E+003 9.585E+003 1280.96 1.47 6.445E+004 8.214E+003 2.898E+004 1377.67 4.11 2.200E+004 6.522E+002 9.785E+003 1385.31 0.78 1.317E+005 6.523E+004 5.943E+004 1401.50 1.39 4.868E+004 -2.904E+004 2.071E+004 1407.98 2.48 2.941E+004 -1.893E+004 1.266E+004 1509.19 2.19 3.129E+004 1.796E+004 1.321E+004 1661.28 1.15 7.368E+004 5.128E+004 3.188E+004 1729.60 3.05 2.476E+004 3.411E+003 1.046E+004 1764.49 15.80 6.687E+003 -1.087E+003 2.967E+003 1847.44 2.12 2.297E+004 6.402E+003 8.598E+003 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.832E+004 1.54E+003 3.164E+004 1.864E+004 77.11 10.70 2.103E+004 1.721E+004 1.023E+004 87.20 3.70 4.329E+004 -1.850E+004 2.107E+004 89.80 1.03 1.498E+005 8.726E+002 7.292E+004 241.98 7.49 1.462E+004 1.689E+004 7.056E+003
Nuclide MDA Report 3/27/2019 8:50:07 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.079E+003 1.54E+003 -2.595E+003 2.430E+003 351.92* 37.20 1.537E+003 1.443E+003 7.060E+002 785.91 1.10 7.605E+004 -2.530E+004 3.470E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D14-GM.CNF Report Generated On : 3/27/2019 8:58:13 PM Sample Title : B1-010-001-FSFC-D14-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D14 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 11:37:00 AM Acquisition Started : 3/27/2019 11:37:22 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:58:13 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D14-GM Peak Analysis Performed on: 3/27/2019 8:58:13 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 950- 961 955.06 238.84 1.08 2.82E+001 29.26 7.28E+001 2 2280- 2291 2285.98 571.74 1.36 1.58E+001 10.45 4.24E+000 3 2328- 2340 2333.09 583.52 0.59 3.50E+001 18.45 1.90E+001 4 2432- 2443 2437.42 609.61 0.80 3.39E+001 18.09 1.91E+001 5 3870- 3883 3876.15 969.30 0.82 1.35E+001 13.80 1.05E+001 6 5833- 5856 5845.02 1461.27 2.37 2.22E+002 29.80 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:58:13 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D14-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.996 1460.81* 10.67 7.99747E+004 1.26054E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 8.77193E+002 9.21583E+002 300.09 3.41 BI-214 0.999 609.31* 46.30 1.70670E+003 9.36650E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60 27.70 964.60 5.20 969.11* 16.60 2.47119E+003 2.53677E+003 1587.90 3.71 PA-234 0.992 94.67 15.50
Interference Corrected Activity Report 3/27/2019 8:58:13 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty PA-234 0.992 98.44 25.10 111.00 8.55 131.28 20.00 152.70 7.20 226.87 6.50 569.26* 10.40 3.40635E+003 2.30370E+003 733.00 8.50 883.24 12.00 946.00 20.00 949.00 7.80
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:58:13 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.996 7.997474E+004 1.260538E+004 PB-212 1.000 8.771935E+002 9.215829E+002 BI-214 0.999 1.706704E+003 9.366502E+002 AC-228 1.000 2.471188E+003 2.536772E+003 PA-234 0.992 3.406354E+003 2.303695E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:58:13 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 583.52 5.8364E-002 52.69 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:58:13 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D14-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 9.748E+002 9.75E+002 7.997E+004 0.000E+000 CO-60 1173.22 100.00 1.209E+003 9.51E+002 5.031E+002 5.588E+002 1332.49 100.00 9.512E+002 4.741E+002 4.269E+002 CS-134 475.35 1.46 6.212E+004 1.09E+003 -1.070E+004 2.919E+004 563.23 8.38 1.100E+004 -4.779E+002 5.139E+003 569.32 15.43 5.844E+003 -2.662E+003 2.725E+003 604.70 97.60 1.251E+003 -2.502E+002 5.931E+002 795.84 85.40 1.090E+003 1.920E+002 5.021E+002 801.93 8.73 1.050E+004 -7.738E+003 4.824E+003 1038.57 1.00 9.899E+004 -6.017E+004 4.523E+004 1167.94 1.80 6.699E+004 7.919E+004 3.097E+004 1365.15 3.04 3.071E+004 1.871E+004 1.373E+004 CS-137 661.65 85.12 1.121E+003 1.12E+003 9.782E+002 5.214E+002 EU-152 121.78 28.40 4.007E+003 3.65E+003 4.701E+002 1.946E+003 344.27 26.50 3.647E+003 -2.352E+003 1.737E+003 1407.95 20.70 3.958E+003 -4.103E+003 1.735E+003 EU-154 123.07 40.40 2.803E+003 2.80E+003 1.447E+003 1.361E+003 722.30 20.00 4.268E+003 1.713E+003 1.960E+003 1274.51 34.40 3.008E+003 -5.666E+002 1.366E+003 + BI-214 609.31* 46.30 1.283E+003 1.28E+003 1.707E+003 5.733E+002 768.36 5.04 1.983E+004 3.842E+003 9.198E+003 806.17 1.23 7.702E+004 1.280E+004 3.550E+004 934.06 3.21 3.014E+004 1.217E+004 1.382E+004 1120.29 15.10 7.373E+003 1.441E+003 3.393E+003 1155.19 1.69 6.627E+004 4.128E+004 3.046E+004 1238.11 5.94 1.976E+004 1.375E+004 9.094E+003 1280.96 1.47 7.057E+004 -1.355E+004 3.204E+004 1377.67 4.11 2.061E+004 1.704E+004 9.093E+003 1385.31 0.78 1.090E+005 -5.936E+004 4.810E+004 1401.50 1.39 6.025E+004 -1.379E+004 2.649E+004 1407.98 2.48 3.304E+004 -3.425E+004 1.448E+004 1509.19 2.19 3.499E+004 2.335E+004 1.507E+004 1661.28 1.15 6.380E+004 3.663E+004 2.695E+004 1729.60 3.05 2.369E+004 -1.579E+002 9.920E+003 1764.49 15.80 5.048E+003 3.061E+003 2.147E+003 1847.44 2.12 2.797E+004 -2.507E+004 1.110E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.729E+004 2.70E+003 6.247E+004 1.813E+004 77.11 10.70 2.002E+004 2.393E+003 9.727E+003 87.20 3.70 4.394E+004 2.446E+004 2.139E+004 89.80 1.03 1.524E+005 -2.504E+002 7.420E+004 241.98 7.49 1.486E+004 2.334E+004 7.176E+003
Nuclide MDA Report 3/27/2019 8:58:13 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 5.005E+003 2.70E+003 -3.188E+002 2.393E+003 351.92 37.20 2.701E+003 2.114E+003 1.288E+003 785.91 1.10 9.279E+004 3.410E+003 4.308E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FSFC-D15-GM.CNF Report Generated On : 3/27/2019 8:59:18 PM Sample Title : B1-010-001-FSFC-D15-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D15 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 11:50:00 AM Acquisition Started : 3/27/2019 11:50:19 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 8:59:18 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D15-GM Peak Analysis Performed on: 3/27/2019 8:59:17 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 962 954.77 238.76 0.50 4.82E+001 32.00 7.18E+001 2 1402- 1414 1407.70 352.07 1.05 3.01E+001 23.47 3.99E+001 3 2327- 2339 2332.63 583.41 0.83 3.15E+001 18.25 1.95E+001 4 2431- 2444 2437.32 609.59 0.37 2.84E+001 20.45 2.76E+001 5 4475- 4488 4481.88 1120.69 0.78 2.33E+001 10.59 1.70E+000 6 5833- 5857 5845.51 1461.39 1.59 2.30E+002 32.67 9.07E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:59:18 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D15-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.994 1460.81* 10.67 8.28356E+004 1.36153E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.49919E+003 1.02434E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 1.42957E+003 1.04576E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29* 15.10 5.06608E+003 2.33738E+003 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.38388E+003 1.10221E+003 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 8:59:18 PM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.994 8.283561E+004 1.361532E+004 PB-212 1.000 1.499188E+003 1.024341E+003 BI-214 0.999 2.036093E+003 9.545754E+002 PB-214 1.000 1.383875E+003 1.102214E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 8:59:17 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 583.41 5.2500E-002 57.93 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 8:59:18 PM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D15-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 8.178E+003 8.18E+003 8.284E+004 3.601E+003 CO-60 1173.22 100.00 1.030E+003 8.83E+002 1.313E+002 4.695E+002 1332.49 100.00 8.828E+002 -4.548E+002 3.927E+002 CS-134 475.35 1.46 6.068E+004 1.09E+003 -3.291E+004 2.847E+004 563.23 8.38 1.030E+004 -5.784E+002 4.792E+003 569.32 15.43 5.968E+003 1.305E+003 2.788E+003 604.70 97.60 1.171E+003 -7.619E+002 5.531E+002 795.84 85.40 1.090E+003 7.263E+002 5.021E+002 801.93 8.73 9.694E+003 4.499E+002 4.424E+003 1038.57 1.00 9.657E+004 -3.226E+004 4.402E+004 1167.94 1.80 5.781E+004 9.926E+003 2.638E+004 1365.15 3.04 2.832E+004 2.409E+004 1.253E+004 CS-137 661.65 85.12 1.137E+003 1.14E+003 4.185E+002 5.299E+002 EU-152 121.78 28.40 4.199E+003 3.54E+003 1.585E+002 2.042E+003 344.27 26.50 3.544E+003 -3.067E+001 1.686E+003 1407.95 20.70 4.345E+003 9.257E+002 1.928E+003 EU-154 123.07 40.40 2.935E+003 2.93E+003 -4.053E+002 1.427E+003 722.30 20.00 5.016E+003 2.375E+003 2.334E+003 1274.51 34.40 3.008E+003 -1.200E+003 1.366E+003 + BI-214 609.31* 46.30 1.582E+003 1.58E+003 1.430E+003 7.228E+002 768.36 5.04 1.916E+004 1.829E+003 8.863E+003 806.17 1.23 6.902E+004 3.841E+004 3.150E+004 934.06 3.21 2.980E+004 5.467E+003 1.365E+004 1120.29* 15.10 2.143E+003 5.066E+003 7.773E+002 1155.19 1.69 5.811E+004 -1.346E+005 2.638E+004 1238.11 5.94 2.055E+004 1.653E+003 9.489E+003 1280.96 1.47 6.445E+004 1.334E+004 2.898E+004 1377.67 4.11 2.109E+004 1.122E+004 9.330E+003 1385.31 0.78 1.090E+005 -1.036E+005 4.810E+004 1401.50 1.39 5.722E+004 -9.604E+004 2.498E+004 1407.98 2.48 3.627E+004 7.727E+003 1.609E+004 1509.19 2.19 3.829E+004 2.874E+004 1.671E+004 1661.28 1.15 5.166E+004 2.198E+004 2.087E+004 1729.60 3.05 2.578E+004 1.564E+004 1.097E+004 1764.49 15.80 7.097E+003 6.680E+003 3.172E+003 1847.44 2.12 3.386E+004 -1.867E+003 1.404E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.720E+004 1.69E+003 4.196E+004 1.808E+004 77.11 10.70 2.026E+004 6.396E+003 9.846E+003 87.20 3.70 4.191E+004 -5.330E+003 2.038E+004 89.80 1.03 1.442E+005 -6.886E+004 7.013E+004 241.98 7.49 1.451E+004 7.106E+003 7.003E+003
Nuclide MDA Report 3/27/2019 8:59:18 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.166E+003 1.69E+003 2.024E+003 2.473E+003 351.92* 37.20 1.695E+003 1.384E+003 7.851E+002 785.91 1.10 9.503E+004 -3.939E+004 4.419E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: 3844 Report Generated On : 3/28/2019 10:16:42 AM Sample Title : B1-010-001-FSFC-D16-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D16 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 10:06:00 AM Acquisition Started : 3/28/2019 10:06:41 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 10:16:42 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D16-GM Peak Analysis Performed on: 3/28/2019 10:16:42 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 959 952.73 238.25 0.45 3.62E+001 29.85 7.08E+001 2 2322- 2334 2328.08 582.27 0.79 3.28E+001 15.77 1.12E+001 3 2427- 2440 2434.09 608.78 1.18 2.21E+001 17.85 1.99E+001 4 4469- 4482 4475.88 1119.19 0.73 1.87E+001 11.55 5.26E+000 5 5826- 5849 5837.03 1459.27 1.31 2.42E+002 31.11 0.00E+000 6 7044- 7059 7051.58 1762.59 0.56 1.54E+001 10.34 3.63E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 10:16:42 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D16-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.959 1460.81* 10.67 8.70947E+004 1.33098E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.12393E+003 9.45253E+002 300.09 3.41 BI-214 0.986 609.31* 46.30 1.10955E+003 9.09295E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29* 15.10 4.07163E+003 2.53124E+003 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49* 15.80 4.27399E+003 2.89501E+003 1847.44 2.12 2118.54 1.21
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 10:16:42 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.959 8.709466E+004 1.330983E+004 PB-212 0.999 1.123931E+003 9.452532E+002 BI-214 0.986 1.675182E+003 8.206520E+002
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 10:16:42 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 582.27 5.4688E-002 48.07 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/28/2019 10:16:43 AM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D16-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 9.739E+002 9.74E+002 8.709E+004 0.000E+000 CO-60 1173.22 100.00 1.017E+003 9.99E+002 -3.580E+002 4.629E+002 1332.49 100.00 9.991E+002 4.654E+000 4.509E+002 CS-134 475.35 1.46 6.524E+004 1.09E+003 4.217E+003 3.075E+004 563.23 8.38 1.022E+004 -4.998E+003 4.752E+003 569.32 15.43 5.886E+003 1.160E+003 2.746E+003 604.70 97.60 1.165E+003 1.375E+003 5.503E+002 795.84 85.40 1.090E+003 -1.920E+001 5.021E+002 801.93 8.73 9.694E+003 -1.329E+003 4.424E+003 1038.57 1.00 8.890E+004 4.967E+004 4.018E+004 1167.94 1.80 5.709E+004 -1.227E+004 2.602E+004 1365.15 3.04 2.423E+004 1.686E+004 1.048E+004 CS-137 661.65 85.12 1.137E+003 1.14E+003 2.873E+002 5.299E+002 EU-152 121.78 28.40 3.894E+003 3.34E+003 -2.676E+003 1.889E+003 344.27 26.50 3.342E+003 -2.337E+003 1.585E+003 1407.95 20.70 3.958E+003 -2.151E+003 1.735E+003 EU-154 123.07 40.40 2.745E+003 2.46E+003 -9.175E+001 1.332E+003 722.30 20.00 5.490E+003 3.376E+003 2.571E+003 1274.51 34.40 2.455E+003 -1.529E+003 1.089E+003 + BI-214 609.31* 46.30 1.393E+003 1.39E+003 1.110E+003 6.282E+002 768.36 5.04 1.864E+004 1.432E+004 8.604E+003 806.17 1.23 6.986E+004 -2.565E+004 3.192E+004 934.06 3.21 2.767E+004 -2.041E+004 1.258E+004 1120.29* 15.10 3.322E+003 4.072E+003 1.367E+003 1155.19 1.69 6.557E+004 -5.211E+003 3.012E+004 1238.11 5.94 1.915E+004 1.094E+004 8.785E+003 1280.96 1.47 6.226E+004 2.445E+004 2.789E+004 1377.67 4.11 2.200E+004 1.973E+004 9.785E+003 1385.31 0.78 9.832E+004 -7.353E+004 4.274E+004 1401.50 1.39 5.399E+004 -4.429E+004 2.336E+004 1407.98 2.48 3.304E+004 -1.796E+004 1.448E+004 1509.19 2.19 2.993E+004 -1.212E+004 1.253E+004 1661.28 1.15 5.811E+004 2.930E+004 2.410E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49* 15.80 3.834E+003 4.274E+003 1.541E+003 1847.44 2.12 3.556E+004 1.920E+004 1.489E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.712E+004 2.50E+003 2.815E+004 1.804E+004 77.11 10.70 2.042E+004 5.935E+003 9.929E+003 87.20 3.70 4.357E+004 2.754E+004 2.121E+004 89.80 1.03 1.469E+005 -6.720E+004 7.146E+004 241.98 7.49 1.416E+004 8.590E+003 6.825E+003
Nuclide MDA Report 3/28/2019 10:16:43 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 4.869E+003 2.50E+003 2.212E+003 2.325E+003 351.92 37.20 2.498E+003 1.485E+003 1.187E+003 785.91 1.10 8.487E+004 -8.734E+004 3.911E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: 3844 Report Generated On : 3/28/2019 10:57:26 AM Sample Title : B1-010-001-FSFC-D17-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D17 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 10:47:00 AM Acquisition Started : 3/28/2019 10:47:25 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 10:57:26 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D17-GM Peak Analysis Performed on: 3/28/2019 10:57:26 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 945- 960 953.83 238.53 0.74 5.09E+001 37.20 9.81E+001 2 1102- 1113 1107.58 276.99 0.43 1.56E+001 20.17 3.44E+001 3 1400- 1412 1405.92 351.63 0.92 3.39E+001 21.59 3.11E+001 4 2322- 2334 2328.25 582.31 0.40 3.11E+001 17.07 1.59E+001 5 2428- 2440 2433.61 608.66 0.55 3.12E+001 17.96 1.78E+001 6 5825- 5848 5837.71 1459.44 1.60 2.24E+002 30.76 3.09E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 10:57:26 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D17-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.967 1460.81* 10.67 8.05907E+004 1.29200E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.58215E+003 1.18460E+003 300.09 3.41 BI-214 0.997 609.31* 46.30 1.57129E+003 9.25678E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.55721E+003 1.02343E+003 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 10:57:26 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.967 8.059070E+004 1.291997E+004 PB-212 1.000 1.582155E+003 1.184598E+003 BI-214 0.997 1.571289E+003 9.256777E+002 PB-214 0.999 1.557208E+003 1.023432E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 10:57:26 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 276.99 2.5942E-002 129.59 4 582.31 5.1879E-002 54.84 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D17-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 5.191E+003 5.19E+003 8.059E+004 2.108E+003 CO-60 1173.22 100.00 9.901E+002 9.51E+002 -4.289E+002 4.495E+002 1332.49 100.00 9.512E+002 3.640E+002 4.269E+002 CS-134 475.35 1.46 6.177E+004 1.03E+003 -1.855E+004 2.901E+004 563.23 8.38 9.811E+003 -6.133E+003 4.546E+003 569.32 15.43 5.452E+003 -2.030E+003 2.530E+003 604.70 97.60 1.125E+003 6.863E+002 5.305E+002 795.84 85.40 1.034E+003 -1.069E+002 4.740E+002 801.93 8.73 9.813E+003 5.050E+003 4.484E+003 1038.57 1.00 8.190E+004 1.602E+004 3.668E+004 1167.94 1.80 5.255E+004 1.157E+004 2.375E+004 1365.15 3.04 2.832E+004 -3.598E+003 1.253E+004 CS-137 661.65 85.12 1.129E+003 1.13E+003 2.317E+002 5.257E+002 EU-152 121.78 28.40 4.052E+003 3.28E+003 -1.237E+002 1.968E+003 344.27 26.50 3.370E+003 -3.771E+003 1.599E+003 1407.95 20.70 3.280E+003 8.466E+002 1.395E+003 EU-154 123.07 40.40 2.838E+003 2.46E+003 9.119E+002 1.378E+003 722.30 20.00 4.740E+003 -2.744E+003 2.196E+003 1274.51 34.40 2.455E+003 -1.767E+003 1.089E+003 + BI-214 609.31* 46.30 1.300E+003 1.30E+003 1.571E+003 5.817E+002 768.36 5.04 1.864E+004 -5.690E+003 8.604E+003 806.17 1.23 7.152E+004 1.725E+003 3.275E+004 934.06 3.21 2.876E+004 4.362E+003 1.313E+004 1120.29 15.10 6.985E+003 1.932E+003 3.198E+003 1155.19 1.69 5.648E+004 -6.148E+004 2.557E+004 1238.11 5.94 1.739E+004 -2.198E+003 7.904E+003 1280.96 1.47 5.637E+004 -4.337E+004 2.494E+004 1377.67 4.11 2.528E+004 1.323E+004 1.143E+004 1385.31 0.78 1.140E+005 3.727E+003 5.057E+004 1401.50 1.39 5.399E+004 -3.374E+004 2.336E+004 1407.98 2.48 2.738E+004 7.067E+003 1.165E+004 1509.19 2.19 2.993E+004 -1.796E+003 1.253E+004 1661.28 1.15 5.166E+004 2.198E+004 2.087E+004 1729.60 3.05 1.707E+004 -3.376E+003 6.613E+003 1764.49 15.80 6.092E+003 4.731E+003 2.670E+003 1847.44 2.12 3.386E+004 -3.334E+002 1.404E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.746E+004 1.50E+003 -1.057E+004 1.821E+004 77.11 10.70 2.082E+004 1.649E+004 1.013E+004 87.20 3.70 4.329E+004 1.151E+003 2.107E+004 89.80 1.03 1.490E+005 -6.481E+004 7.252E+004 241.98 7.49 1.509E+004 -1.341E+003 7.293E+003
Nuclide MDA Report 3/28/2019 10:57:26 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.122E+003 1.50E+003 3.658E+003 2.452E+003 351.92* 37.20 1.500E+003 1.557E+003 6.877E+002 785.91 1.10 8.813E+004 -5.749E+004 4.075E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: 3844 Report Generated On : 3/28/2019 11:10:52 AM Sample Title : B1-010-001-FSFC-D18-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D18 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 11:00:00 AM Acquisition Started : 3/28/2019 11:00:50 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 11:10:52 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D18-GM Peak Analysis Performed on: 3/28/2019 11:10:51 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 964 953.84 238.53 0.72 5.26E+001 33.84 7.44E+001 2 2324- 2336 2330.05 582.76 0.96 2.74E+001 18.95 2.36E+001 3 2428- 2441 2434.75 608.94 0.45 3.25E+001 15.67 1.05E+001 4 5826- 5851 5838.03 1459.52 1.87 2.26E+002 33.30 1.24E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
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Sample
Title:
B1-010-001-FSFC-D18-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.971 1460.81* 10.67 8.11844E+004 1.37344E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.63541E+003 1.08484E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 1.63538E+003 8.15788E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.971 8.118440E+004 1.373445E+004 PB-212 1.000 1.635411E+003 1.084842E+003 BI-214 0.999 1.635380E+003 8.157883E+002
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 11:10:51 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 582.76 4.5711E-002 69.10 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D18-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 9.484E+003 9.48E+003 8.118E+004 4.255E+003 CO-60 1173.22 100.00 1.187E+003 6.53E+002 4.146E+002 5.478E+002 1332.49 100.00 6.528E+002 1.194E+002 2.777E+002 CS-134 475.35 1.46 5.368E+004 1.11E+003 -4.891E+004 2.497E+004 563.23 8.38 1.038E+004 2.659E+003 4.832E+003 569.32 15.43 5.497E+003 -9.808E+002 2.552E+003 604.70 97.60 1.108E+003 6.530E+002 5.218E+002 795.84 85.40 1.133E+003 -3.989E+002 5.234E+002 801.93 8.73 1.071E+004 1.485E+003 4.933E+003 1038.57 1.00 1.091E+005 -7.626E+004 5.030E+004 1167.94 1.80 5.781E+004 -1.292E+004 2.638E+004 1365.15 3.04 2.185E+004 3.723E+003 9.294E+003 CS-137 661.65 85.12 1.095E+003 1.09E+003 9.354E+002 5.084E+002 EU-152 121.78 28.40 3.992E+003 3.36E+003 -1.194E+003 1.938E+003 344.27 26.50 3.356E+003 -5.175E+003 1.592E+003 1407.95 20.70 4.059E+003 1.778E+003 1.785E+003 EU-154 123.07 40.40 2.799E+003 2.75E+003 -8.609E+002 1.359E+003 722.30 20.00 5.167E+003 3.842E+003 2.410E+003 1274.51 34.40 2.747E+003 -9.499E+002 1.235E+003 + BI-214 609.31* 46.30 1.026E+003 1.03E+003 1.635E+003 4.448E+002 768.36 5.04 1.678E+004 -1.189E+003 7.676E+003 806.17 1.23 7.549E+004 2.076E+004 3.473E+004 934.06 3.21 3.014E+004 5.260E+003 1.382E+004 1120.29 15.10 7.297E+003 -4.125E+002 3.355E+003 1155.19 1.69 6.415E+004 -2.607E+004 2.941E+004 1238.11 5.94 2.016E+004 9.546E+002 9.293E+003 1280.96 1.47 7.057E+004 -4.866E+004 3.204E+004 1377.67 4.11 2.109E+004 -1.894E+003 9.330E+003 1385.31 0.78 1.187E+005 7.461E+004 5.293E+004 1401.50 1.39 5.722E+004 -2.059E+004 2.498E+004 1407.98 2.48 3.388E+004 1.484E+004 1.490E+004 1509.19 2.19 2.850E+004 -1.201E+004 1.182E+004 1661.28 1.15 5.811E+004 -1.351E+004 2.410E+004 1729.60 3.05 2.005E+004 8.528E+003 8.100E+003 1764.49 15.80 5.933E+003 4.453E+003 2.590E+003 1847.44 2.12 3.556E+004 7.291E+003 1.489E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.790E+004 2.60E+003 2.910E+004 1.843E+004 77.11 10.70 2.080E+004 8.879E+003 1.012E+004 87.20 3.70 4.253E+004 8.470E+003 2.069E+004 89.80 1.03 1.495E+005 1.344E+004 7.276E+004 241.98 7.49 1.407E+004 9.189E+002 6.784E+003
Nuclide MDA Report 3/28/2019 11:10:52 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 5.251E+003 2.60E+003 2.047E+003 2.516E+003 351.92 37.20 2.602E+003 1.196E+003 1.239E+003 785.91 1.10 8.651E+004 -1.413E+004 3.994E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: 3844 Report Generated On : 3/28/2019 11:37:22 AM Sample Title : B1-010-001-FSFC-D19-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D19 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 11:25:00 AM Acquisition Started : 3/28/2019 11:27:21 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 11:37:22 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D19-GM Peak Analysis Performed on: 3/28/2019 11:37:21 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 958 952.94 238.30 0.40 4.55E+001 28.25 6.05E+001 2 1174- 1185 1179.52 294.99 0.33 1.82E+001 22.21 4.18E+001 3 2324- 2336 2330.41 582.85 0.59 3.35E+001 16.00 1.15E+001 4 2428- 2439 2433.80 608.71 0.44 3.10E+001 17.44 1.80E+001 5 3633- 3646 3639.80 910.23 0.50 2.83E+001 16.90 1.57E+001 6 3865- 3878 3871.06 968.03 0.46 1.11E+001 11.99 8.86E+000 7 5826- 5850 5838.35 1459.60 1.36 2.52E+002 32.56 3.17E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 11:37:22 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D19-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.974 1460.81* 10.67 9.06462E+004 1.39096E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.41326E+003 9.07086E+002 300.09 3.41 BI-214 0.997 609.31* 46.30 1.55955E+003 8.99702E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 1.47200E+003 1.81471E+003 351.92 37.20 785.91 1.10 AC-228 0.987 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40
Interference Corrected Activity Report 3/28/2019 11:37:22 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.987 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.00208E+003 1.82469E+003 964.60 5.20 969.11* 16.60 2.03726E+003 2.20213E+003 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 11:37:22 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.974 9.064618E+004 1.390958E+004 PB-212 0.999 1.413259E+003 9.070864E+002 BI-214 0.997 1.559553E+003 8.997018E+002 PB-214 1.000 1.472004E+003 1.814713E+003 AC-228 0.987 2.609317E+003 1.405030E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 11:37:21 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 582.85 5.5861E-002 47.74 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/28/2019 11:37:22 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D19-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 5.290E+003 5.29E+003 9.065E+004 2.158E+003 CO-60 1173.22 100.00 1.209E+003 8.65E+002 1.766E+002 5.588E+002 1332.49 100.00 8.647E+002 -7.584E+001 3.837E+002 CS-134 475.35 1.46 6.212E+004 1.16E+003 -2.847E+003 2.919E+004 563.23 8.38 1.054E+004 -8.603E+003 4.910E+003 569.32 15.43 5.886E+003 3.051E+003 2.746E+003 604.70 97.60 1.225E+003 7.745E+002 5.801E+002 795.84 85.40 1.164E+003 -3.012E+002 5.389E+002 801.93 8.73 1.123E+004 -1.614E+003 5.194E+003 1038.57 1.00 9.657E+004 9.551E+004 4.402E+004 1167.94 1.80 6.878E+004 4.350E+004 3.187E+004 1365.15 3.04 2.637E+004 -1.585E+004 1.155E+004 CS-137 661.65 85.12 1.162E+003 1.16E+003 7.533E+002 5.424E+002 EU-152 121.78 28.40 4.072E+003 3.52E+003 1.017E+003 1.978E+003 344.27 26.50 3.518E+003 -3.097E+003 1.673E+003 1407.95 20.70 3.748E+003 -1.356E+002 1.629E+003 EU-154 123.07 40.40 2.817E+003 2.79E+003 8.083E+002 1.368E+003 722.30 20.00 4.781E+003 4.528E+003 2.217E+003 1274.51 34.40 2.792E+003 -1.173E+003 1.258E+003 + BI-214 609.31* 46.30 1.247E+003 1.25E+003 1.560E+003 5.552E+002 768.36 5.04 2.155E+004 2.549E+003 1.006E+004 806.17 1.23 7.626E+004 -4.831E+004 3.512E+004 934.06 3.21 3.014E+004 -3.495E+004 1.382E+004 1120.29 15.10 7.952E+003 1.001E+004 3.682E+003 1155.19 1.69 6.121E+004 1.311E+004 2.794E+004 1238.11 5.94 1.996E+004 1.387E+004 9.194E+003 1280.96 1.47 6.226E+004 -1.045E+004 2.789E+004 1377.67 4.11 2.881E+004 1.499E+004 1.319E+004 1385.31 0.78 1.296E+005 -3.003E+004 5.840E+004 1401.50 1.39 6.170E+004 3.217E+004 2.722E+004 1407.98 2.48 3.128E+004 -1.132E+003 1.360E+004 1509.19 2.19 3.932E+004 1.878E+004 1.723E+004 1661.28 1.15 5.811E+004 3.663E+003 2.410E+004 1729.60 3.05 2.255E+004 1.137E+004 9.353E+003 1764.49 15.80 6.398E+003 2.563E+003 2.822E+003 1847.44 2.12 2.297E+004 6.402E+003 8.598E+003 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.772E+004 2.62E+003 5.490E+004 1.834E+004 77.11 10.70 2.061E+004 2.749E+003 1.002E+004 87.20 3.70 4.320E+004 -5.153E+003 2.102E+004 89.80 1.03 1.490E+005 -8.096E+004 7.252E+004 241.98 7.49 1.451E+004 1.229E+004 7.003E+003
Nuclide MDA Report 3/28/2019 11:37:22 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21* 19.20 2.952E+003 2.62E+003 1.472E+003 1.367E+003 351.92 37.20 2.620E+003 2.406E+002 1.248E+003 785.91 1.10 8.318E+004 -4.280E+004 3.827E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FSFC-D20-GM.CNF Report Generated On : 3/29/2019 10:37:42 AM Sample Title : B1-010-001-FSFC-D20-GM Sample Description : Rx Bowl 2M Concrete Sample Identification : D20 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 1.256E+001 M^2 Sample Taken On : 3/28/2019 3:28:00 PM Acquisition Started : 3/28/2019 3:43:14 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_2M
Peak Analysis Report 3/29/2019 10:37:42 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D20-GM Peak Analysis Performed on: 3/29/2019 10:37:41 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 959 953.38 238.41 0.93 4.18E+001 25.53 4.82E+001 2 2429- 2441 2434.93 608.99 0.30 2.58E+001 16.57 1.63E+001 3 2638- 2653 2645.51 661.64 1.06 5.66E+001 19.08 1.14E+001 4 5828- 5851 5840.51 1460.14 1.27 1.84E+002 28.85 6.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:37:42 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D20-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.992 1460.81* 10.67 1.48191E+005 2.62614E+004 CS-137 1.000 661.65* 85.12 3.63185E+003 1.29981E+003 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.88500E+003 1.82086E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 2.89634E+003 1.90015E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:37:42 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.992 1.481906E+005 2.626136E+004 CS-137 1.000 3.631851E+003 1.299811E+003 PB-212 1.000 2.885003E+003 1.820860E+003 BI-214 0.999 2.896339E+003 1.900146E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 10:37:41 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/29/2019 10:37:42 AM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D20-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 1.517E+004 1.52E+004 1.482E+005 6.496E+003 CO-60 1173.22 100.00 2.182E+003 1.71E+003 1.128E+002 9.894E+002 1332.49 100.00 1.715E+003 6.034E+001 7.486E+002 CS-134 475.35 1.46 1.216E+005 2.10E+003 7.647E+004 5.664E+004 563.23 8.38 2.076E+004 -2.503E+004 9.575E+003 569.32 15.43 1.228E+004 1.338E+002 5.702E+003 604.70 97.60 2.410E+003 1.024E+003 1.133E+003 795.84 85.40 2.095E+003 -5.689E+002 9.512E+002 801.93 8.73 1.972E+004 -1.731E+004 8.911E+003 1038.57 1.00 2.186E+005 -4.054E+004 9.978E+004 1167.94 1.80 1.192E+005 3.626E+004 5.397E+004 1365.15 3.04 5.417E+004 -2.217E+004 2.344E+004 + CS-137 661.65* 85.12 1.412E+003 1.41E+003 3.632E+003 6.192E+002 EU-152 121.78 28.40 8.522E+003 6.42E+003 5.592E+003 4.134E+003 344.27 26.50 7.025E+003 -1.102E+004 3.321E+003 1407.95 20.70 6.416E+003 3.235E+003 2.661E+003 EU-154 123.07 40.40 5.951E+003 5.95E+003 3.612E+003 2.886E+003 722.30 20.00 8.910E+003 -7.009E+003 4.066E+003 1274.51 34.40 6.341E+003 -2.441E+002 2.861E+003 + BI-214 609.31* 46.30 2.728E+003 2.73E+003 2.896E+003 1.212E+003 768.36 5.04 4.169E+004 -2.334E+004 1.925E+004 806.17 1.23 1.465E+005 -1.095E+005 6.654E+004 934.06 3.21 5.936E+004 1.563E+004 2.687E+004 1120.29 15.10 1.579E+004 1.650E+003 7.239E+003 1155.19 1.69 1.317E+005 -4.607E+004 5.986E+004 1238.11 5.94 4.185E+004 2.210E+004 1.916E+004 1280.96 1.47 1.367E+005 8.379E+004 6.108E+004 1377.67 4.11 4.033E+004 -1.898E+004 1.745E+004 1385.31 0.78 1.997E+005 4.420E+004 8.548E+004 1401.50 1.39 1.169E+005 -1.351E+004 5.035E+004 1407.98 2.48 5.355E+004 2.700E+004 2.221E+004 1509.19 2.19 6.697E+004 -4.465E+003 2.805E+004 1661.28 1.15 1.075E+005 4.101E+004 4.266E+004 1729.60 3.05 5.051E+004 2.189E+003 2.095E+004 1764.49 15.80 1.292E+004 9.352E+003 5.617E+003 1847.44 2.12 5.147E+004 1.434E+004 1.927E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 7.843E+004 5.58E+003 1.165E+004 3.808E+004 77.11 10.70 4.380E+004 4.333E+004 2.128E+004 87.20 3.70 9.168E+004 -2.544E+004 4.456E+004 89.80 1.03 3.291E+005 4.825E+005 1.601E+005 241.98 7.49 2.905E+004 3.387E+004 1.396E+004
Nuclide MDA Report 3/29/2019 10:37:42 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 1.023E+004 5.58E+003 -1.971E+003 4.870E+003 351.92 37.20 5.583E+003 7.244E+003 2.653E+003 785.91 1.10 1.570E+005 -9.295E+004 7.106E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: 3844 Report Generated On : 3/28/2019 4:10:57 PM Sample Title : B1-010-001-FSFC-D21-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D21 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 4:00:00 PM Acquisition Started : 3/28/2019 4:00:56 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 4:10:57 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D21-GM Peak Analysis Performed on: 3/28/2019 4:10:57 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 960 953.62 238.47 1.02 5.51E+001 32.33 6.99E+001 2 1401- 1413 1407.21 351.95 0.77 2.65E+001 18.58 2.25E+001 3 2429- 2442 2435.68 609.18 0.78 3.47E+001 14.17 5.31E+000 4 5829- 5854 5840.15 1460.05 1.69 2.09E+002 28.91 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 4:10:57 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D21-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.990 1460.81* 10.67 7.52468E+004 1.21247E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.71276E+003 1.04234E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.74615E+003 7.47341E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.21909E+003 8.76371E+002 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 4:10:57 PM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.990 7.524677E+004 1.212475E+004 PB-212 1.000 1.712757E+003 1.042342E+003 BI-214 1.000 1.746148E+003 7.473414E+002 PB-214 1.000 1.219090E+003 8.763708E+002
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 4:10:57 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/28/2019 4:10:58 PM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D21-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 9.743E+002 9.74E+002 7.525E+004 0.000E+000 CO-60 1173.22 100.00 9.482E+002 8.08E+002 -7.938E+002 4.286E+002 1332.49 100.00 8.078E+002 9.897E+001 3.552E+002 CS-134 475.35 1.46 5.451E+004 9.24E+002 1.182E+004 2.538E+004 563.23 8.38 9.727E+003 5.318E+002 4.504E+003 569.32 15.43 5.315E+003 3.006E+003 2.461E+003 604.70 97.60 9.424E+002 5.528E+002 4.390E+002 795.84 85.40 9.236E+002 2.217E+002 4.187E+002 801.93 8.73 8.679E+003 -3.579E+003 3.917E+003 1038.57 1.00 8.618E+004 4.100E+004 3.882E+004 1167.94 1.80 5.094E+004 -3.236E+004 2.295E+004 1365.15 3.04 2.496E+004 8.692E+003 1.085E+004 CS-137 661.65 85.12 1.171E+003 1.17E+003 5.760E+002 5.465E+002 EU-152 121.78 28.40 3.745E+003 3.20E+003 9.333E+002 1.815E+003 344.27 26.50 3.200E+003 -3.146E+003 1.514E+003 1407.95 20.70 3.523E+003 2.351E+003 1.517E+003 EU-154 123.07 40.40 2.564E+003 2.46E+003 -1.900E+003 1.242E+003 722.30 20.00 4.575E+003 -1.452E+002 2.113E+003 1274.51 34.40 2.455E+003 -1.551E+003 1.089E+003 + BI-214 609.31* 46.30 7.880E+002 7.88E+002 1.746E+003 3.259E+002 768.36 5.04 1.678E+004 6.076E+003 7.676E+003 806.17 1.23 5.676E+004 -4.785E+004 2.537E+004 934.06 3.21 2.804E+004 5.135E+003 1.277E+004 1120.29 15.10 7.882E+003 4.916E+003 3.647E+003 1155.19 1.69 5.890E+004 -7.374E+003 2.678E+004 1238.11 5.94 1.643E+004 -4.074E+003 7.425E+003 1280.96 1.47 6.759E+004 4.979E+004 3.055E+004 1377.67 4.11 1.804E+004 4.788E+003 7.806E+003 1385.31 0.78 1.011E+005 3.558E+003 4.414E+004 1401.50 1.39 4.473E+004 -1.678E+004 1.873E+004 1407.98 2.48 2.941E+004 1.962E+004 1.266E+004 1509.19 2.19 2.697E+004 -1.572E+004 1.105E+004 1661.28 1.15 5.500E+004 1.308E+002 2.254E+004 1729.60 3.05 1.707E+004 -2.665E+003 6.613E+003 1764.49 15.80 4.848E+003 2.783E+003 2.047E+003 1847.44 2.12 3.204E+004 1.494E+004 1.313E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.645E+004 1.29E+003 3.974E+004 1.771E+004 77.11 10.70 1.965E+004 3.385E+003 9.544E+003 87.20 3.70 4.007E+004 2.072E+004 1.946E+004 89.80 1.03 1.398E+005 -1.659E+004 6.791E+004 241.98 7.49 1.454E+004 2.037E+004 7.016E+003
Nuclide MDA Report 3/28/2019 4:10:58 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 4.585E+003 1.29E+003 2.940E+003 2.183E+003 351.92* 37.20 1.294E+003 1.219E+003 5.849E+002 785.91 1.10 8.146E+004 5.599E+004 3.741E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D22-GM.CNF Report Generated On : 3/29/2019 10:40:20 AM Sample Title : B1-010-001-FSFC-D22-GM Sample Description : Rx Bowl 2M Concrete Sample Identification : D22 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 1.256E+001 M^2 Sample Taken On : 3/28/2019 3:28:00 PM Acquisition Started : 3/28/2019 3:29:55 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_2M
Peak Analysis Report 3/29/2019 10:40:20 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D22-GM Peak Analysis Performed on: 3/29/2019 10:40:19 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 962 954.41 238.67 0.92 3.90E+001 28.72 5.80E+001 2 1402- 1413 1407.42 352.00 0.34 1.73E+001 17.35 2.27E+001 3 2325- 2337 2330.62 582.90 0.87 2.55E+001 14.61 1.05E+001 4 3635- 3648 3641.50 910.65 0.29 1.58E+001 13.21 9.23E+000 5 5829- 5852 5840.80 1460.21 1.75 1.94E+002 30.29 8.89E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:40:20 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D22-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.994 1460.81* 10.67 1.56341E+005 2.76059E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.69423E+003 2.02883E+003 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.76726E+003 1.79894E+003 785.91 1.10 AC-228 0.995 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.73954E+003 3.16152E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:40:20 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.994 1.563413E+005 2.760595E+004 PB-212 1.000 2.694230E+003 2.028829E+003 PB-214 1.000 1.767257E+003 1.798938E+003 AC-228 0.995 3.739537E+003 3.161521E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 10:40:19 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 582.90 4.2431E-002 57.38 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/29/2019 10:40:20 AM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D22-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 1.792E+004 1.79E+004 1.563E+005 7.871E+003 CO-60 1173.22 100.00 2.331E+003 1.76E+003 -6.350E+001 1.064E+003 1332.49 100.00 1.761E+003 -5.833E+002 7.717E+002 CS-134 475.35 1.46 1.121E+005 2.29E+003 -8.583E+004 5.187E+004 563.23 8.38 2.355E+004 1.172E+004 1.097E+004 569.32 15.43 1.218E+004 3.315E+003 5.652E+003 604.70 97.60 2.369E+003 3.528E+002 1.113E+003 795.84 85.40 2.287E+003 -8.897E+001 1.047E+003 801.93 8.73 1.972E+004 -1.866E+004 8.911E+003 1038.57 1.00 2.017E+005 1.763E+004 9.133E+004 1167.94 1.80 1.209E+005 -6.348E+004 5.484E+004 1365.15 3.04 2.899E+004 -3.299E+004 1.085E+004 CS-137 661.65 85.12 2.742E+003 2.74E+003 2.569E+003 1.284E+003 EU-152 121.78 28.40 8.299E+003 7.44E+003 8.032E+002 4.022E+003 344.27 26.50 7.440E+003 3.283E+002 3.528E+003 1407.95 20.70 7.612E+003 1.761E+003 3.259E+003 EU-154 123.07 40.40 5.666E+003 5.67E+003 -5.387E+003 2.744E+003 722.30 20.00 1.122E+004 5.675E+003 5.221E+003 1274.51 34.40 6.241E+003 2.835E+003 2.812E+003 BI-214 609.31 46.30 4.957E+003 4.96E+003 3.605E+003 2.326E+003 768.36 5.04 4.008E+004 4.432E+003 1.844E+004 806.17 1.23 1.465E+005 9.584E+004 6.654E+004 934.06 3.21 6.272E+004 2.454E+004 2.855E+004 1120.29 15.10 1.631E+004 6.030E+003 7.499E+003 1155.19 1.69 1.434E+005 1.809E+005 6.573E+004 1238.11 5.94 4.088E+004 9.768E+003 1.868E+004 1280.96 1.47 1.441E+005 2.560E+004 6.478E+004 1377.67 4.11 4.274E+004 -1.397E+004 1.866E+004 1385.31 0.78 2.322E+005 -5.475E+004 1.017E+005 1401.50 1.39 1.046E+005 -6.933E+004 4.416E+004 1407.98 2.48 6.354E+004 1.470E+004 2.720E+004 1509.19 2.19 6.376E+004 2.888E+003 2.644E+004 1661.28 1.15 1.075E+005 4.101E+004 4.266E+004 1729.60 3.05 5.993E+004 3.820E+004 2.566E+004 1764.49 15.80 1.215E+004 3.309E+003 5.229E+003 1847.44 2.12 4.440E+004 9.563E+003 1.573E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 7.853E+004 2.84E+003 8.643E+003 3.813E+004 77.11 10.70 4.427E+004 3.841E+004 2.152E+004 87.20 3.70 9.485E+004 2.694E+004 4.615E+004 89.80 1.03 3.262E+005 1.190E+005 1.587E+005 241.98 7.49 2.957E+004 3.826E+004 1.423E+004
Nuclide MDA Report 3/29/2019 10:40:20 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 1.044E+004 2.84E+003 9.433E+003 4.977E+003 351.92* 37.20 2.843E+003 1.767E+003 1.283E+003 785.91 1.10 1.935E+005 -1.912E+005 8.934E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: 3844 Report Generated On : 3/28/2019 11:49:34 AM Sample Title : B1-010-001-FSFC-D23-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D23 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 11:39:00 AM Acquisition Started : 3/28/2019 11:39:32 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 11:49:34 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D23-GM Peak Analysis Performed on: 3/28/2019 11:49:33 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 949- 960 954.31 238.65 0.89 2.63E+001 27.52 6.47E+001 2 1400- 1414 1406.90 351.87 0.31 3.60E+001 26.24 4.70E+001 3 5828- 5851 5839.17 1459.80 1.97 2.25E+002 31.44 5.64E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 11:49:34 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D23-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.982 1460.81* 10.67 8.11277E+004 1.31530E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 8.19556E+002 8.66462E+002 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.65436E+003 1.23531E+003 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 11:49:34 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.982 8.112769E+004 1.315304E+004 PB-212 1.000 8.195564E+002 8.664624E+002 PB-214 1.000 1.654361E+003 1.235309E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 11:49:33 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/28/2019 11:49:34 AM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D23-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 6.494E+003 6.49E+003 8.113E+004 2.760E+003 CO-60 1173.22 100.00 1.017E+003 9.00E+002 -1.197E+002 4.629E+002 1332.49 100.00 9.005E+002 8.278E+002 4.015E+002 CS-134 475.35 1.46 6.558E+004 1.07E+003 4.560E+004 3.092E+004 563.23 8.38 1.085E+004 3.372E+003 5.064E+003 569.32 15.43 5.673E+003 5.218E+003 2.640E+003 604.70 97.60 1.066E+003 1.005E+003 5.009E+002 795.84 85.40 1.252E+003 1.097E+003 5.829E+002 801.93 8.73 1.134E+004 -2.081E+004 5.245E+003 1038.57 1.00 8.755E+004 -3.877E+004 3.951E+004 1167.94 1.80 5.990E+004 4.614E+004 2.743E+004 1365.15 3.04 2.423E+004 -1.396E+004 1.048E+004 CS-137 661.65 85.12 1.171E+003 1.17E+003 1.172E+003 5.465E+002 EU-152 121.78 28.40 4.007E+003 3.57E+003 2.659E+003 1.946E+003 344.27 26.50 3.570E+003 -1.925E+003 1.699E+003 1407.95 20.70 4.059E+003 -9.921E+002 1.785E+003 EU-154 123.07 40.40 2.734E+003 2.73E+003 -2.634E+003 1.327E+003 722.30 20.00 4.446E+003 -5.464E+003 2.049E+003 1274.51 34.40 2.880E+003 -1.006E+003 1.302E+003 BI-214 609.31 46.30 2.270E+003 2.27E+003 5.563E+002 1.067E+003 768.36 5.04 1.864E+004 -3.170E+003 8.604E+003 806.17 1.23 7.925E+004 6.688E+004 3.661E+004 934.06 3.21 3.303E+004 6.725E+003 1.526E+004 1120.29 15.10 7.065E+003 3.433E+002 3.238E+003 1155.19 1.69 6.415E+004 2.073E+004 2.941E+004 1238.11 5.94 1.976E+004 -9.323E+003 9.094E+003 1280.96 1.47 7.342E+004 -6.127E+003 3.347E+004 1377.67 4.11 2.287E+004 1.501E+004 1.022E+004 1385.31 0.78 1.115E+005 9.488E+004 4.935E+004 1401.50 1.39 5.876E+004 1.105E+004 2.575E+004 1407.98 2.48 3.388E+004 -8.281E+003 1.490E+004 1509.19 2.19 2.355E+004 8.980E+003 9.343E+003 1661.28 1.15 6.104E+004 -3.358E+003 2.556E+004 1729.60 3.05 2.005E+004 8.528E+003 8.100E+003 1764.49 15.80 7.228E+003 4.372E+003 3.237E+003 1847.44 2.12 3.204E+004 1.494E+004 1.313E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.772E+004 1.89E+003 3.315E+004 1.834E+004 77.11 10.70 2.033E+004 8.092E+003 9.882E+003 87.20 3.70 4.472E+004 2.502E+004 2.178E+004 89.80 1.03 1.551E+005 1.204E+005 7.554E+004 241.98 7.49 1.373E+004 3.161E+003 6.615E+003
Nuclide MDA Report 3/28/2019 11:49:34 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.122E+003 1.89E+003 -1.551E+003 2.452E+003 351.92* 37.20 1.890E+003 1.654E+003 8.826E+002 785.91 1.10 8.569E+004 4.946E+004 3.953E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: 3844 Report Generated On : 3/28/2019 12:02:52 PM Sample Title : B1-010-001-FSFC-D24-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D24 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 11:51:00 AM Acquisition Started : 3/28/2019 11:52:52 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 12:02:52 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D24-GM Peak Analysis Performed on: 3/28/2019 12:02:52 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 294- 306 299.51 74.81 0.85 5.34E+001 38.99 1.24E+002 2 948- 962 954.13 238.60 1.02 5.76E+001 32.86 7.34E+001 3 2428- 2439 2433.33 608.59 0.47 2.20E+001 17.27 2.00E+001 4 3634- 3647 3640.53 910.41 0.80 1.99E+001 16.41 1.61E+001 5 5828- 5850 5839.78 1459.96 1.59 2.18E+002 31.00 5.68E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 12:02:53 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D24-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.987 1460.81* 10.67 7.85984E+004 1.29130E+004 PB-212 0.713 74.81* 9.60 1.34566E+004 1.01952E+004 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.79207E+003 1.06172E+003 300.09 3.41 BI-214 0.996 609.31* 46.30 1.10785E+003 8.80160E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.993 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.11301E+003 1.75586E+003 964.60 5.20 969.11 16.60 1587.90 3.71
Interference Corrected Activity Report 3/28/2019 12:02:53 PM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 12:02:53 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.987 7.859841E+004 1.291303E+004 PB-212 0.713 1.917216E+003 1.056010E+003 BI-214 0.996 1.107855E+003 8.801605E+002 AC-228 0.993 2.113009E+003 1.755856E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 12:02:52 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/28/2019 12:02:53 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D24-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 6.527E+003 6.53E+003 7.860E+004 2.777E+003 CO-60 1173.22 100.00 1.105E+003 7.46E+002 4.445E+002 5.071E+002 1332.49 100.00 7.459E+002 -4.985E+002 3.243E+002 CS-134 475.35 1.46 6.691E+004 1.10E+003 -6.131E+004 3.158E+004 563.23 8.38 1.077E+004 -3.263E+002 5.026E+003 569.32 15.43 5.968E+003 -4.134E+003 2.788E+003 604.70 97.60 1.225E+003 1.040E+003 5.801E+002 795.84 85.40 1.101E+003 8.173E+002 5.075E+002 801.93 8.73 1.016E+004 2.009E+003 4.657E+003 1038.57 1.00 9.657E+004 2.194E+004 4.402E+004 1167.94 1.80 6.258E+004 -5.364E+004 2.877E+004 1365.15 3.04 2.568E+004 7.829E+003 1.121E+004 CS-137 661.65 85.12 1.171E+003 1.17E+003 2.288E+002 5.465E+002 EU-152 121.78 28.40 4.052E+003 3.69E+003 8.815E+002 1.968E+003 344.27 26.50 3.685E+003 -2.658E+003 1.756E+003 1407.95 20.70 3.748E+003 1.061E+003 1.629E+003 EU-154 123.07 40.40 2.817E+003 2.82E+003 -3.530E+003 1.368E+003 722.30 20.00 5.627E+003 6.918E+002 2.640E+003 1274.51 34.40 3.049E+003 1.260E+003 1.386E+003 + BI-214 609.31* 46.30 1.336E+003 1.34E+003 1.108E+003 5.997E+002 768.36 5.04 1.999E+004 9.014E+002 9.280E+003 806.17 1.23 7.393E+004 -1.132E+004 3.395E+004 934.06 3.21 2.946E+004 -2.991E+004 1.348E+004 1120.29 15.10 7.811E+003 3.197E+001 3.612E+003 1155.19 1.69 6.627E+004 4.127E+004 3.046E+004 1238.11 5.94 1.915E+004 1.807E+003 8.785E+003 1280.96 1.47 6.226E+004 -3.054E+004 2.789E+004 1377.67 4.11 2.244E+004 5.946E+003 1.000E+004 1385.31 0.78 1.115E+005 -1.469E+005 4.935E+004 1401.50 1.39 6.025E+004 -3.355E+004 2.649E+004 1407.98 2.48 3.128E+004 8.855E+003 1.360E+004 1509.19 2.19 2.697E+004 -1.668E+004 1.105E+004 1661.28 1.15 5.166E+004 2.198E+004 2.087E+004 1729.60 3.05 2.369E+004 1.145E+003 9.920E+003 1764.49 15.80 5.598E+003 1.600E+003 2.423E+003 1847.44 2.12 3.556E+004 1.897E+003 1.489E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.858E+004 2.76E+003 6.146E+004 1.877E+004 77.11 10.70 2.042E+004 5.627E+003 9.929E+003 87.20 3.70 4.584E+004 3.571E+004 2.234E+004 89.80 1.03 1.592E+005 6.631E+004 7.761E+004 241.98 7.49 1.451E+004 -5.202E+003 7.003E+003
Nuclide MDA Report 3/28/2019 12:02:53 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 5.377E+003 2.76E+003 6.586E+003 2.579E+003 351.92 37.20 2.763E+003 2.704E+003 1.319E+003 785.91 1.10 9.354E+004 2.444E+004 4.345E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: 3844 Report Generated On : 3/28/2019 12:17:06 PM Sample Title : B1-010-001-FSFC-D25-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D25 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 12:05:00 AM Acquisition Started : 3/28/2019 12:07:04 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 12:17:06 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D25-GM Peak Analysis Performed on: 3/28/2019 12:17:05 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 960 953.46 238.43 0.45 4.78E+001 32.12 7.62E+001 2 2428- 2443 2435.25 609.07 0.73 2.80E+001 18.77 2.00E+001 3 3633- 3647 3640.28 910.34 0.38 3.30E+001 17.46 1.50E+001 4 5828- 5850 5839.23 1459.82 1.03 2.66E+002 32.62 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 12:17:06 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D25-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.983 1460.81* 10.67 9.57578E+004 1.41588E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.48775E+003 1.02683E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.40911E+003 9.61511E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.992 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.49726E+003 1.89375E+003 964.60 5.20 969.11 16.60 1587.90 3.71
Interference Corrected Activity Report 3/28/2019 12:17:06 PM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 12:17:06 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.983 9.575782E+004 1.415880E+004 PB-212 1.000 1.487755E+003 1.026833E+003 BI-214 1.000 1.409106E+003 9.615115E+002 AC-228 0.992 3.497263E+003 1.893754E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 12:17:05 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/28/2019 12:17:06 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D25-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 9.741E+002 9.74E+002 9.576E+004 0.000E+000 CO-60 1173.22 100.00 1.030E+003 8.83E+002 4.602E+002 4.696E+002 1332.49 100.00 8.830E+002 2.847E+002 3.928E+002 CS-134 475.35 1.46 6.459E+004 1.11E+003 -1.047E+004 3.042E+004 563.23 8.38 1.062E+004 -1.929E+003 4.951E+003 569.32 15.43 6.133E+003 -3.421E+003 2.870E+003 604.70 97.60 1.108E+003 -1.271E+002 5.220E+002 795.84 85.40 1.123E+003 4.093E+001 5.184E+002 801.93 8.73 1.061E+004 -5.201E+003 4.881E+003 1038.57 1.00 9.662E+004 4.520E+004 4.404E+004 1167.94 1.80 5.924E+004 -2.697E+004 2.710E+004 1365.15 3.04 2.424E+004 7.618E+003 1.049E+004 CS-137 661.65 85.12 1.179E+003 1.18E+003 7.795E+002 5.506E+002 EU-152 121.78 28.40 4.022E+003 3.34E+003 2.641E+003 1.953E+003 344.27 26.50 3.343E+003 -4.599E+003 1.585E+003 1407.95 20.70 4.436E+003 1.180E+003 1.973E+003 EU-154 123.07 40.40 2.817E+003 2.82E+003 -1.093E+001 1.368E+003 722.30 20.00 4.700E+003 2.472E+003 2.176E+003 1274.51 34.40 2.837E+003 -2.278E+003 1.280E+003 + BI-214 609.31* 46.30 1.419E+003 1.42E+003 1.409E+003 6.415E+002 768.36 5.04 1.916E+004 1.041E+003 8.863E+003 806.17 1.23 7.472E+004 2.173E+004 3.435E+004 934.06 3.21 3.241E+004 1.783E+004 1.495E+004 1120.29 15.10 7.221E+003 4.483E+003 3.316E+003 1155.19 1.69 5.811E+004 2.044E+004 2.638E+004 1238.11 5.94 2.131E+004 8.603E+003 9.869E+003 1280.96 1.47 5.761E+004 7.535E+003 2.556E+004 1377.67 4.11 1.859E+004 -2.242E+002 8.080E+003 1385.31 0.78 1.038E+005 0.000E+000 4.550E+004 1401.50 1.39 6.449E+004 1.425E+004 2.862E+004 1407.98 2.48 3.702E+004 9.845E+003 1.647E+004 1509.19 2.19 3.129E+004 1.796E+004 1.321E+004 1661.28 1.15 5.811E+004 2.930E+004 2.410E+004 1729.60 3.05 1.530E+004 4.264E+003 5.727E+003 1764.49 15.80 6.544E+003 3.611E+003 2.896E+003 1847.44 2.12 2.297E+004 6.402E+003 8.598E+003 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.716E+004 2.61E+003 2.242E+004 1.806E+004 77.11 10.70 2.077E+004 1.644E+004 1.010E+004 87.20 3.70 4.263E+004 -2.617E+004 2.074E+004 89.80 1.03 1.519E+005 7.177E+004 7.396E+004 241.98 7.49 1.462E+004 1.955E+004 7.056E+003
Nuclide MDA Report 3/28/2019 12:17:06 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 4.930E+003 2.61E+003 -5.908E+002 2.355E+003 351.92 37.20 2.611E+003 8.049E+002 1.243E+003 785.91 1.10 8.233E+004 -7.799E+004 3.785E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: 3844 Report Generated On : 3/28/2019 8:21:21 AM Sample Title : B1-010-001-FSFC-D26-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D26 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 7:54:00 AM Acquisition Started : 3/28/2019 8:11:21 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 8:21:21 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D26-GM Peak Analysis Performed on: 3/28/2019 8:21:21 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 961 954.01 238.57 0.80 5.27E+001 32.90 7.53E+001 2 1400- 1414 1406.03 351.65 0.41 5.08E+001 22.57 2.63E+001 3 3636- 3649 3642.43 910.88 0.35 2.99E+001 15.90 1.21E+001 4 5827- 5852 5840.35 1460.10 1.96 2.60E+002 33.90 6.49E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 8:21:21 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D26-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.991 1460.81* 10.67 9.34334E+004 1.44404E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.64017E+003 1.05670E+003 300.09 3.41 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 2.33317E+003 1.10273E+003 785.91 1.10 AC-228 0.997 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.16711E+003 1.72495E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 8:21:21 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.991 9.343339E+004 1.444039E+004 PB-212 1.000 1.640174E+003 1.056703E+003 PB-214 0.999 2.333166E+003 1.102726E+003 AC-228 0.997 3.167115E+003 1.724951E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 8:21:21 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/28/2019 8:21:22 AM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D26-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 7.213E+003 7.21E+003 9.343E+004 3.119E+003 CO-60 1173.22 100.00 1.004E+003 9.51E+002 -1.454E+002 4.563E+002 1332.49 100.00 9.512E+002 6.423E+002 4.269E+002 CS-134 475.35 1.46 5.958E+004 1.14E+003 -1.755E+003 2.791E+004 563.23 8.38 1.179E+004 7.712E+003 5.533E+003 569.32 15.43 5.886E+003 3.295E+003 2.746E+003 604.70 97.60 1.137E+003 1.727E+003 5.363E+002 795.84 85.40 1.194E+003 1.115E+003 5.540E+002 801.93 8.73 1.027E+004 -7.157E+003 4.714E+003 1038.57 1.00 8.618E+004 -6.271E+004 3.882E+004 1167.94 1.80 5.334E+004 1.598E+004 2.415E+004 1365.15 3.04 2.098E+004 -2.252E+004 8.861E+003 CS-137 661.65 85.12 1.031E+003 1.03E+003 1.175E+002 4.768E+002 EU-152 121.78 28.40 4.117E+003 3.37E+003 4.706E+003 2.001E+003 344.27 26.50 3.370E+003 -3.497E+003 1.599E+003 1407.95 20.70 4.059E+003 -4.069E+003 1.785E+003 EU-154 123.07 40.40 2.806E+003 2.75E+003 -1.316E+003 1.363E+003 722.30 20.00 4.700E+003 3.060E+003 2.176E+003 1274.51 34.40 2.747E+003 1.893E+003 1.235E+003 BI-214 609.31 46.30 2.431E+003 2.43E+003 2.144E+003 1.147E+003 768.36 5.04 2.185E+004 1.819E+004 1.021E+004 806.17 1.23 7.393E+004 -1.311E+004 3.395E+004 934.06 3.21 2.911E+004 2.185E+003 1.330E+004 1120.29 15.10 8.552E+003 2.254E+003 3.982E+003 1155.19 1.69 5.480E+004 2.714E+004 2.473E+004 1238.11 5.94 1.996E+004 1.792E+004 9.194E+003 1280.96 1.47 6.656E+004 5.130E+004 3.004E+004 1377.67 4.11 2.061E+004 1.058E+004 9.093E+003 1385.31 0.78 1.065E+005 2.122E+004 4.682E+004 1401.50 1.39 6.716E+004 4.105E+004 2.995E+004 1407.98 2.48 3.388E+004 -3.396E+004 1.490E+004 1509.19 2.19 3.499E+004 2.335E+004 1.507E+004 1661.28 1.15 4.802E+004 -9.890E+003 1.905E+004 1729.60 3.05 2.255E+004 1.137E+004 9.353E+003 1764.49 15.80 7.356E+003 7.236E+003 3.301E+003 1847.44 2.12 3.717E+004 2.134E+004 1.570E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.949E+004 1.45E+003 3.959E+004 1.923E+004 77.11 10.70 2.188E+004 2.483E+004 1.066E+004 87.20 3.70 4.343E+004 -7.361E+003 2.114E+004 89.80 1.03 1.494E+005 -2.071E+004 7.268E+004 241.98 7.49 1.507E+004 1.045E+004 7.280E+003
Nuclide MDA Report 3/28/2019 8:21:22 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.418E+003 1.45E+003 3.949E+003 2.599E+003 351.92* 37.20 1.448E+003 2.333E+003 6.619E+002 785.91 1.10 8.318E+004 -3.184E+004 3.827E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D27-GM.CNF Report Generated On : 3/29/2019 10:43:38 AM Sample Title : B1-010-001-FSFC-D27-GM Sample Description : Rx Bowl 2M Concrete Sample Identification : D27 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 1.256E+001 M^2 Sample Taken On : 3/28/2019 3:15:00 PM Acquisition Started : 3/28/2019 3:15:57 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_2M
Peak Analysis Report 3/29/2019 10:43:38 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D27-GM Peak Analysis Performed on: 3/29/2019 10:43:38 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 960 954.04 238.58 1.01 5.30E+001 31.72 6.80E+001 2 2636- 2652 2644.51 661.39 1.01 7.12E+001 21.68 1.48E+001 3 3635- 3648 3641.05 910.54 0.61 3.40E+001 11.66 0.00E+000 4 5828- 5851 5839.09 1459.78 1.95 2.05E+002 29.38 2.77E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:43:38 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D27-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.981 1460.81* 10.67 1.65258E+005 2.73123E+004 CS-137 0.999 661.65* 85.12 4.56625E+003 1.49551E+003 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 3.66110E+003 2.26658E+003 300.09 3.41 AC-228 0.994 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 8.06186E+003 2.91850E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:43:38 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.981 1.652578E+005 2.731226E+004 CS-137 0.999 4.566251E+003 1.495509E+003 PB-212 1.000 3.661098E+003 2.266575E+003 AC-228 0.994 8.061860E+003 2.918497E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 10:43:38 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/29/2019 10:43:38 AM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D27-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 1.077E+004 1.08E+004 1.653E+005 4.295E+003 CO-60 1173.22 100.00 2.524E+003 1.76E+003 1.015E+003 1.160E+003 1332.49 100.00 1.761E+003 -3.738E+002 7.717E+002 CS-134 475.35 1.46 1.226E+005 2.27E+003 -2.319E+003 5.709E+004 563.23 8.38 2.248E+004 7.460E+003 1.043E+004 569.32 15.43 1.248E+004 2.597E+003 5.801E+003 604.70 97.60 2.271E+003 7.795E+002 1.063E+003 795.84 85.40 2.287E+003 -3.009E+003 1.047E+003 801.93 8.73 2.348E+004 -1.903E+004 1.079E+004 1038.57 1.00 1.957E+005 4.632E+004 8.833E+004 1167.94 1.80 1.384E+005 6.054E+004 6.357E+004 1365.15 3.04 4.273E+004 2.154E+004 1.772E+004 + CS-137 661.65* 85.12 1.611E+003 1.61E+003 4.566E+003 7.187E+002 EU-152 121.78 28.40 8.580E+003 7.59E+003 2.707E+003 4.163E+003 344.27 26.50 7.593E+003 -1.087E+004 3.604E+003 1407.95 20.70 8.381E+003 2.864E+003 3.644E+003 EU-154 123.07 40.40 5.992E+003 5.37E+003 -3.202E+003 2.907E+003 722.30 20.00 1.051E+004 9.168E+003 4.867E+003 1274.51 34.40 5.370E+003 -2.398E+003 2.376E+003 BI-214 609.31 46.30 5.326E+003 5.33E+003 5.101E+003 2.511E+003 768.36 5.04 4.049E+004 -3.508E+004 1.865E+004 806.17 1.23 1.706E+005 -5.239E+004 7.856E+004 934.06 3.21 5.936E+004 5.187E+003 2.687E+004 1120.29 15.10 1.579E+004 8.451E+003 7.239E+003 1155.19 1.69 1.299E+005 4.158E+004 5.897E+004 1238.11 5.94 4.185E+004 5.128E+003 1.916E+004 1280.96 1.47 1.260E+005 2.546E+004 5.576E+004 1377.67 4.11 4.033E+004 8.665E+003 1.745E+004 1385.31 0.78 2.438E+005 2.015E+005 1.076E+005 1401.50 1.39 1.207E+005 8.403E+004 5.225E+004 1407.98 2.48 6.996E+004 2.391E+004 3.041E+004 1509.19 2.19 7.000E+004 4.019E+004 2.956E+004 1661.28 1.15 7.616E+004 -4.921E+004 2.698E+004 1729.60 3.05 4.780E+004 2.274E+003 1.959E+004 1764.49 15.80 1.215E+004 3.825E+003 5.229E+003 1847.44 2.12 7.586E+004 3.825E+004 3.146E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 7.943E+004 5.63E+003 8.808E+004 3.858E+004 77.11 10.70 4.390E+004 2.825E+004 2.133E+004 87.20 3.70 8.794E+004 -1.147E+005 4.270E+004 89.80 1.03 3.133E+005 4.489E+003 1.523E+005 241.98 7.49 3.085E+004 1.656E+004 1.486E+004
Nuclide MDA Report 3/29/2019 10:43:38 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 1.034E+004 5.63E+003 2.822E+003 4.924E+003 351.92 37.20 5.625E+003 7.913E+003 2.674E+003 785.91 1.10 1.701E+005 -1.736E+005 7.763E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D28-GM.CNF Report Generated On : 3/29/2019 10:46:21 AM Sample Title : B1-010-001-FSFC-D28-GM Sample Description : Rx Bowl 2M Concrete Sample Identification : D28 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 1.256E+001 M^2 Sample Taken On : 3/28/2019 3:02:00 PM Acquisition Started : 3/28/2019 3:02:25 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_2M
Peak Analysis Report 3/29/2019 10:46:21 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D28-GM Peak Analysis Performed on: 3/29/2019 10:46:21 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 945- 961 954.48 238.69 1.53 6.77E+001 33.81 6.83E+001 2 1402- 1415 1407.09 351.92 0.58 1.86E+001 20.84 3.24E+001 3 2036- 2048 2042.38 510.82 0.39 3.43E+001 18.85 2.07E+001 4 2427- 2439 2433.77 608.70 0.79 2.69E+001 16.64 1.61E+001 5 2634- 2653 2643.87 661.23 1.07 1.10E+002 27.43 2.24E+001 6 3345- 3358 3351.71 838.21 0.46 1.30E+001 11.49 7.03E+000 7 5828- 5852 5840.16 1460.05 2.10 2.31E+002 32.62 8.76E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:46:21 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D28-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.990 1460.81* 10.67 1.86227E+005 3.04451E+004 CS-137 0.997 661.65* 85.12 7.02899E+003 1.95187E+003 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 4.67158E+003 2.45079E+003 300.09 3.41 BI-214 0.997 609.31* 46.30 3.02434E+003 1.91115E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.90192E+003 2.15533E+003 785.91 1.10
Interference Corrected Activity Report 3/29/2019 10:46:21 AM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:46:21 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.990 1.862271E+005 3.044507E+004 CS-137 0.997 7.028987E+003 1.951866E+003 PB-212 1.000 4.671576E+003 2.450787E+003 BI-214 0.997 3.024340E+003 1.911154E+003 PB-214 1.000 1.901919E+003 2.155330E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 10:46:21 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 510.82 5.7129E-002 54.99 6 838.21 2.1625E-002 88.59 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/29/2019 10:46:21 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D28-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 1.781E+004 1.78E+004 1.862E+005 7.816E+003 CO-60 1173.22 100.00 2.151E+003 1.89E+003 -4.717E+002 9.738E+002 1332.49 100.00 1.892E+003 1.121E+003 8.370E+002 CS-134 475.35 1.46 1.338E+005 2.31E+003 -5.107E+004 6.271E+004 563.23 8.38 2.284E+004 -1.786E+004 1.062E+004 569.32 15.43 1.277E+004 5.471E+003 5.947E+003 604.70 97.60 2.515E+003 2.073E+003 1.186E+003 795.84 85.40 2.313E+003 -5.160E+002 1.060E+003 801.93 8.73 2.195E+004 -7.454E+002 1.003E+004 1038.57 1.00 2.266E+005 8.109E+004 1.037E+005 1167.94 1.80 1.276E+005 5.269E+004 5.816E+004 1365.15 3.04 6.045E+004 -1.863E+004 2.658E+004 + CS-137 661.65* 85.12 2.044E+003 2.04E+003 7.029E+003 9.350E+002 EU-152 121.78 28.40 8.907E+003 7.50E+003 3.978E+003 4.326E+003 344.27 26.50 7.501E+003 -3.260E+003 3.559E+003 1407.95 20.70 8.620E+003 -3.911E+003 3.763E+003 EU-154 123.07 40.40 6.246E+003 6.24E+003 3.045E+003 3.034E+003 722.30 20.00 1.014E+004 1.034E+004 4.680E+003 1274.51 34.40 6.241E+003 -5.995E+002 2.812E+003 + BI-214 609.31* 46.30 2.712E+003 2.71E+003 3.024E+003 1.204E+003 768.36 5.04 4.129E+004 1.665E+004 1.905E+004 806.17 1.23 1.465E+005 4.639E+004 6.654E+004 934.06 3.21 6.272E+004 2.879E+004 2.855E+004 1120.29 15.10 1.597E+004 1.300E+004 7.326E+003 1155.19 1.69 1.418E+005 3.552E+004 6.492E+004 1238.11 5.94 4.372E+004 -3.094E+004 2.010E+004 1280.96 1.47 1.577E+005 5.578E+004 7.162E+004 1377.67 4.11 4.389E+004 -1.038E+004 1.923E+004 1385.31 0.78 2.381E+005 1.214E+005 1.047E+005 1401.50 1.39 1.244E+005 9.003E+004 5.408E+004 1407.98 2.48 7.195E+004 -3.265E+004 3.141E+004 1509.19 2.19 6.376E+004 3.014E+003 2.644E+004 1661.28 1.15 7.616E+004 -2.870E+004 2.698E+004 1729.60 3.05 4.174E+004 -5.730E+003 1.656E+004 1764.49 15.80 1.399E+004 1.122E+004 6.153E+003 1847.44 2.12 7.180E+004 3.347E+004 2.943E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 8.052E+004 3.47E+003 9.259E+003 3.912E+004 77.11 10.70 4.390E+004 5.266E+003 2.133E+004 87.20 3.70 9.650E+004 7.934E+004 4.698E+004 89.80 1.03 3.354E+005 -5.045E+004 1.633E+005 241.98 7.49 3.249E+004 -5.635E+003 1.569E+004
Nuclide MDA Report 3/29/2019 10:46:21 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 1.106E+004 3.47E+003 -1.976E+003 5.286E+003 351.92* 37.20 3.473E+003 1.902E+003 1.598E+003 785.91 1.10 1.803E+005 -7.132E+004 8.271E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FSFC-D29-GM.CNF Report Generated On : 3/27/2019 9:00:26 PM Sample Title : B1-010-001-FSFC-D29-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D29 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 8:24:00 AM Acquisition Started : 3/27/2019 8:24:53 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 9:00:26 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D29-GM Peak Analysis Performed on: 3/27/2019 9:00:26 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 960 954.64 238.73 0.92 7.99E+001 28.14 4.11E+001 2 1345- 1358 1351.47 338.00 1.14 2.42E+001 19.55 2.48E+001 3 2323- 2336 2330.37 582.84 1.04 2.49E+001 18.25 2.11E+001 4 2426- 2439 2432.82 608.46 0.32 3.43E+001 17.66 1.57E+001 5 3634- 3647 3640.51 910.40 0.76 1.44E+001 12.23 7.57E+000 6 5825- 5847 5836.64 1459.17 1.23 2.12E+002 33.40 1.73E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:00:26 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D29-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.953 1460.81* 10.67 7.61936E+004 1.35690E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.48737E+003 9.62059E+002 300.09 3.41 BI-214 0.995 609.31* 46.30 1.72568E+003 9.15519E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.992 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32* 11.40 3.55745E+003 2.92712E+003 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 1.52951E+003 1.30843E+003 964.60 5.20 969.11 16.60 1587.90 3.71
Interference Corrected Activity Report 3/27/2019 9:00:26 PM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:00:26 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.953 7.619356E+004 1.356903E+004 PB-212 1.000 2.487372E+003 9.620595E+002 BI-214 0.995 1.725677E+003 9.155186E+002 AC-228 0.992 1.867229E+003 1.194521E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 9:00:26 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 582.84 4.1558E-002 73.20 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 9:00:26 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D29-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 1.068E+004 1.07E+004 7.619E+004 4.853E+003 CO-60 1173.22 100.00 1.017E+003 7.67E+002 -3.616E+002 4.629E+002 1332.49 100.00 7.672E+002 -9.059E+002 3.349E+002 CS-134 475.35 1.46 5.807E+004 8.97E+002 1.924E+004 2.716E+004 563.23 8.38 1.022E+004 -1.165E+003 4.752E+003 569.32 15.43 5.407E+003 2.545E+003 2.507E+003 604.70 97.60 1.114E+003 1.316E+003 5.247E+002 795.84 85.40 8.970E+002 3.071E+002 4.054E+002 801.93 8.73 7.972E+003 -1.027E+004 3.563E+003 1038.57 1.00 9.534E+004 -2.406E+004 4.340E+004 1167.94 1.80 5.487E+004 -8.982E+003 2.491E+004 1365.15 3.04 2.704E+004 -5.119E+003 1.189E+004 CS-137 661.65 85.12 9.221E+002 9.22E+002 -2.798E+001 4.222E+002 EU-152 121.78 28.40 3.831E+003 3.17E+003 7.891E+002 1.858E+003 344.27 26.50 3.171E+003 -2.601E+003 1.499E+003 1407.95 20.70 4.252E+003 -5.990E+002 1.881E+003 EU-154 123.07 40.40 2.679E+003 2.68E+003 -9.689E+002 1.299E+003 722.30 20.00 4.532E+003 -3.078E+003 2.092E+003 1274.51 34.40 2.880E+003 -3.406E+001 1.302E+003 + BI-214 609.31* 46.30 1.230E+003 1.23E+003 1.726E+003 5.469E+002 768.36 5.04 1.846E+004 1.483E+004 8.516E+003 806.17 1.23 6.551E+004 4.684E+004 2.974E+004 934.06 3.21 2.181E+004 -1.762E+003 9.650E+003 1120.29 15.10 6.823E+003 1.321E+003 3.117E+003 1155.19 1.69 5.968E+004 -5.274E+003 2.717E+004 1238.11 5.94 1.807E+004 9.150E+003 8.246E+003 1280.96 1.47 5.761E+004 -1.379E+004 2.556E+004 1377.67 4.11 2.244E+004 1.392E+004 1.000E+004 1385.31 0.78 9.832E+004 -5.028E+004 4.274E+004 1401.50 1.39 5.722E+004 2.810E+004 2.498E+004 1407.98 2.48 3.549E+004 -5.000E+003 1.570E+004 1509.19 2.19 3.129E+004 -1.033E+004 1.321E+004 1661.28 1.15 5.500E+004 2.564E+004 2.254E+004 1729.60 3.05 1.863E+004 7.107E+003 7.394E+003 1764.49 15.80 5.239E+003 -1.322E+003 2.243E+003 1847.44 2.12 3.386E+004 1.707E+004 1.404E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.605E+004 2.60E+003 3.993E+004 1.751E+004 77.11 10.70 1.940E+004 1.394E+004 9.421E+003 87.20 3.70 4.263E+004 5.442E+004 2.074E+004 89.80 1.03 1.477E+005 6.933E+004 7.187E+004 241.98 7.49 1.385E+004 9.702E+003 6.672E+003
Nuclide MDA Report 3/27/2019 9:00:26 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 4.823E+003 2.60E+003 2.460E+003 2.302E+003 351.92 37.20 2.602E+003 3.461E+003 1.239E+003 785.91 1.10 7.881E+004 3.786E+004 3.608E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: 3844 Report Generated On : 3/28/2019 8:33:23 AM Sample Title : B1-010-001-FSFC-D30-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D30 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 8:23:00 AM Acquisition Started : 3/28/2019 8:23:22 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 8:33:23 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D30-GM Peak Analysis Performed on: 3/28/2019 8:33:23 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 960 953.61 238.47 1.13 5.53E+001 33.02 7.47E+001 2 1399- 1413 1406.01 351.65 0.63 4.73E+001 23.04 2.97E+001 3 2326- 2337 2331.50 583.12 0.76 2.63E+001 12.75 5.72E+000 4 2429- 2443 2436.34 609.34 0.55 3.63E+001 19.06 1.88E+001 5 5830- 5852 5841.42 1460.36 1.39 2.25E+002 32.07 8.48E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 8:33:23 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D30-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.996 1460.81* 10.67 8.08452E+004 1.33398E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.71973E+003 1.06325E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.82475E+003 9.87560E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 2.17613E+003 1.11490E+003 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 8:33:23 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.996 8.084517E+004 1.333982E+004 PB-212 1.000 1.719732E+003 1.063248E+003 BI-214 1.000 1.824754E+003 9.875603E+002 PB-214 0.999 2.176126E+003 1.114895E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 8:33:23 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 583.12 4.3802E-002 48.50 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/28/2019 8:33:23 AM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D30-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 7.736E+003 7.74E+003 8.085E+004 3.381E+003 CO-60 1173.22 100.00 1.117E+003 8.83E+002 -6.168E+002 5.131E+002 1332.49 100.00 8.828E+002 -9.815E+000 3.927E+002 CS-134 475.35 1.46 6.524E+004 1.08E+003 -3.559E+004 3.075E+004 563.23 8.38 1.100E+004 -2.257E+003 5.139E+003 569.32 15.43 5.886E+003 3.062E+003 2.746E+003 604.70 97.60 1.176E+003 -1.165E+003 5.559E+002 795.84 85.40 1.079E+003 -9.811E+001 4.966E+002 801.93 8.73 1.103E+004 2.456E+003 5.091E+003 1038.57 1.00 9.657E+004 -1.112E+005 4.402E+004 1167.94 1.80 6.126E+004 -7.697E+004 2.811E+004 1365.15 3.04 2.704E+004 1.076E+004 1.189E+004 CS-137 661.65 85.12 1.086E+003 1.09E+003 2.871E+002 5.040E+002 EU-152 121.78 28.40 4.077E+003 3.15E+003 -2.254E+003 1.981E+003 344.27 26.50 3.531E+003 -6.515E+003 1.679E+003 1407.95 20.70 3.150E+003 -3.020E+003 1.330E+003 EU-154 123.07 40.40 2.831E+003 2.83E+003 -1.462E+002 1.375E+003 722.30 20.00 4.861E+003 2.175E+003 2.257E+003 1274.51 34.40 2.880E+003 1.507E+003 1.302E+003 + BI-214 609.31* 46.30 1.360E+003 1.36E+003 1.825E+003 6.118E+002 768.36 5.04 1.949E+004 1.173E+004 9.032E+003 806.17 1.23 7.851E+004 -4.036E+004 3.625E+004 934.06 3.21 2.840E+004 -1.130E+004 1.295E+004 1120.29 15.10 7.952E+003 6.287E+003 3.682E+003 1155.19 1.69 5.811E+004 -1.153E+004 2.638E+004 1238.11 5.94 2.055E+004 1.055E+004 9.489E+003 1280.96 1.47 6.337E+004 -4.643E+004 2.844E+004 1377.67 4.11 1.804E+004 1.255E+004 7.806E+003 1385.31 0.78 9.832E+004 -3.953E+004 4.274E+004 1401.50 1.39 5.399E+004 -2.986E+004 2.336E+004 1407.98 2.48 2.629E+004 -2.521E+004 1.110E+004 1509.19 2.19 3.381E+004 -3.667E+003 1.447E+004 1661.28 1.15 5.811E+004 2.930E+004 2.410E+004 1729.60 3.05 1.863E+004 -5.330E+003 7.394E+003 1764.49 15.80 6.398E+003 3.190E+003 2.822E+003 1847.44 2.12 2.563E+004 8.536E+003 9.928E+003 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.941E+004 1.52E+003 4.484E+004 1.919E+004 77.11 10.70 2.190E+004 2.148E+004 1.067E+004 87.20 3.70 4.531E+004 -4.897E+003 2.208E+004 89.80 1.03 1.540E+005 -4.237E+004 7.499E+004 241.98 7.49 1.527E+004 2.390E+004 7.383E+003
Nuclide MDA Report 3/28/2019 8:33:23 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 4.975E+003 1.52E+003 -3.303E+003 2.378E+003 351.92* 37.20 1.522E+003 2.176E+003 6.987E+002 785.91 1.10 8.813E+004 -9.810E+003 4.075E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: 3844 Report Generated On : 3/28/2019 8:55:50 AM Sample Title : B1-010-001-FSFC-D31-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D31 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 8:43:00 AM Acquisition Started : 3/28/2019 8:45:49 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 8:55:50 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D31-GM Peak Analysis Performed on: 3/28/2019 8:55:50 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 959 953.42 238.42 0.93 4.05E+001 33.97 8.85E+001 2 2324- 2339 2330.78 582.94 0.63 3.80E+001 18.57 1.60E+001 3 2429- 2442 2436.35 609.34 1.47 3.48E+001 18.76 1.92E+001 4 3636- 3649 3642.85 910.99 0.95 2.32E+001 15.66 1.38E+001 5 5829- 5852 5841.66 1460.43 1.55 2.49E+002 33.05 6.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 8:55:51 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D31-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.997 1460.81* 10.67 8.96646E+004 1.40173E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.25888E+003 1.07557E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 1.75345E+003 9.70577E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.998 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.45849E+003 1.68465E+003 964.60 5.20 969.11 16.60 1587.90 3.71
Interference Corrected Activity Report 3/28/2019 8:55:51 AM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 8:55:51 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.997 8.966464E+004 1.401732E+004 PB-212 1.000 1.258878E+003 1.075569E+003 BI-214 1.000 1.753446E+003 9.705772E+002 AC-228 0.998 2.458490E+003 1.684649E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 8:55:50 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 582.94 6.3333E-002 48.87 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/28/2019 8:55:51 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D31-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 6.781E+003 6.78E+003 8.966E+004 2.903E+003 CO-60 1173.22 100.00 9.624E+002 7.67E+002 -3.746E+002 4.357E+002 1332.49 100.00 7.672E+002 2.699E+001 3.349E+002 CS-134 475.35 1.46 5.883E+004 1.09E+003 -7.474E+004 2.754E+004 563.23 8.38 1.030E+004 5.252E+003 4.792E+003 569.32 15.43 6.009E+003 -1.242E+003 2.808E+003 604.70 97.60 1.148E+003 2.929E+002 5.419E+002 795.84 85.40 1.090E+003 6.433E+002 5.021E+002 801.93 8.73 1.092E+004 -4.284E+003 5.039E+003 1038.57 1.00 9.779E+004 2.664E+003 4.463E+004 1167.94 1.80 5.921E+004 -2.542E+004 2.708E+004 1365.15 3.04 2.098E+004 3.071E+003 8.861E+003 CS-137 661.65 85.12 1.154E+003 1.15E+003 9.073E+002 5.383E+002 EU-152 121.78 28.40 4.087E+003 3.44E+003 1.116E+003 1.986E+003 344.27 26.50 3.438E+003 -5.375E+003 1.633E+003 1407.95 20.70 3.855E+003 -3.956E+001 1.683E+003 EU-154 123.07 40.40 2.887E+003 2.89E+003 1.832E+003 1.403E+003 722.30 20.00 5.349E+003 4.197E+003 2.501E+003 1274.51 34.40 3.129E+003 3.024E+003 1.426E+003 + BI-214 609.31* 46.30 1.343E+003 1.34E+003 1.753E+003 6.036E+002 768.36 5.04 1.881E+004 -6.065E+003 8.691E+003 806.17 1.23 8.141E+004 8.580E+004 3.770E+004 934.06 3.21 3.210E+004 2.340E+004 1.479E+004 1120.29 15.10 7.952E+003 5.128E+003 3.682E+003 1155.19 1.69 6.764E+004 -2.961E+004 3.115E+004 1238.11 5.94 1.976E+004 7.964E+003 9.094E+003 1280.96 1.47 5.999E+004 -7.216E+004 2.675E+004 1377.67 4.11 2.370E+004 1.648E+004 1.064E+004 1385.31 0.78 1.065E+005 -2.172E+005 4.682E+004 1401.50 1.39 5.563E+004 -8.871E+004 2.418E+004 1407.98 2.48 3.218E+004 -3.302E+002 1.405E+004 1509.19 2.19 3.129E+004 1.796E+004 1.321E+004 1661.28 1.15 4.802E+004 1.831E+004 1.905E+004 1729.60 3.05 1.707E+004 -8.972E+003 6.613E+003 1764.49 15.80 6.963E+003 3.794E+003 3.105E+003 1847.44 2.12 3.556E+004 -1.624E+004 1.489E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.858E+004 2.68E+003 2.515E+004 1.877E+004 77.11 10.70 2.114E+004 1.917E+004 1.029E+004 87.20 3.70 4.282E+004 2.374E+004 2.083E+004 89.80 1.03 1.497E+005 5.541E+004 7.284E+004 241.98 7.49 1.527E+004 2.033E+004 7.383E+003
Nuclide MDA Report 3/28/2019 8:55:51 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 5.251E+003 2.68E+003 2.953E+002 2.516E+003 351.92 37.20 2.683E+003 2.166E+003 1.279E+003 785.91 1.10 8.059E+004 3.556E+004 3.698E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: 3844 Report Generated On : 3/28/2019 9:08:53 AM Sample Title : B1-010-001-FSFC-D32-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D32 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 8:58:00 AM Acquisition Started : 3/28/2019 8:58:52 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 9:08:53 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D32-GM Peak Analysis Performed on: 3/28/2019 9:08:53 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 1401- 1413 1406.51 351.77 0.34 3.07E+001 20.09 2.63E+001 2 2324- 2336 2329.50 582.62 0.89 2.26E+001 15.37 1.34E+001 3 2428- 2442 2434.61 608.91 1.20 4.53E+001 17.22 9.66E+000 4 5827- 5851 5840.39 1460.11 1.65 2.42E+002 31.91 3.08E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 9:08:53 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D32-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.991 1460.81* 10.67 8.71025E+004 1.35555E+004 BI-214 0.999 609.31* 46.30 2.28145E+003 9.14461E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.41154E+003 9.50770E+002 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 9:08:53 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.991 8.710249E+004 1.355552E+004 BI-214 0.999 2.281452E+003 9.144613E+002 PB-214 1.000 1.411535E+003 9.507704E+002
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 9:08:53 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 582.62 3.7708E-002 67.92 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/28/2019 9:08:53 AM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D32-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 5.177E+003 5.18E+003 8.710E+004 2.102E+003 CO-60 1173.22 100.00 1.068E+003 9.99E+002 -6.598E+002 4.887E+002 1332.49 100.00 9.991E+002 1.787E+002 4.509E+002 CS-134 475.35 1.46 6.248E+004 9.99E+002 -3.849E+004 2.936E+004 563.23 8.38 1.136E+004 9.963E+002 5.322E+003 569.32 15.43 6.050E+003 9.082E+002 2.828E+003 604.70 97.60 1.171E+003 9.244E+002 5.531E+002 795.84 85.40 9.987E+002 -1.428E+002 4.563E+002 801.93 8.73 9.574E+003 -5.923E+003 4.364E+003 1038.57 1.00 9.409E+004 1.952E+004 4.278E+004 1167.94 1.80 6.258E+004 1.575E+004 2.877E+004 1365.15 3.04 1.911E+004 -1.716E+004 7.926E+003 CS-137 661.65 85.12 1.103E+003 1.10E+003 7.485E+002 5.128E+002 EU-152 121.78 28.40 4.097E+003 3.37E+003 -2.920E+003 1.991E+003 344.27 26.50 3.370E+003 -5.418E+002 1.599E+003 1407.95 20.70 4.252E+003 -5.909E+003 1.881E+003 EU-154 123.07 40.40 2.873E+003 2.87E+003 3.136E+002 1.396E+003 722.30 20.00 4.740E+003 -2.683E+003 2.196E+003 1274.51 34.40 3.129E+003 2.099E+003 1.426E+003 + BI-214 609.31* 46.30 1.025E+003 1.02E+003 2.281E+003 4.442E+002 768.36 5.04 2.079E+004 1.099E+004 9.678E+003 806.17 1.23 6.986E+004 -3.962E+004 3.192E+004 934.06 3.21 3.048E+004 6.211E+003 1.398E+004 1120.29 15.10 8.157E+003 7.062E+003 3.784E+003 1155.19 1.69 6.898E+004 3.455E+004 3.182E+004 1238.11 5.94 1.976E+004 2.117E+003 9.094E+003 1280.96 1.47 7.434E+004 6.561E+004 3.393E+004 1377.67 4.11 1.963E+004 8.506E+003 8.601E+003 1385.31 0.78 1.065E+005 -2.036E+004 4.682E+004 1401.50 1.39 6.584E+004 5.905E+004 2.929E+004 1407.98 2.48 3.549E+004 -4.932E+004 1.570E+004 1509.19 2.19 2.533E+004 -5.328E+004 1.023E+004 1661.28 1.15 4.802E+004 -7.326E+003 1.905E+004 1729.60 3.05 2.134E+004 -1.015E+003 8.749E+003 1764.49 15.80 6.827E+003 6.123E+003 3.037E+003 1847.44 2.12 3.386E+004 1.707E+004 1.404E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.904E+004 1.39E+003 1.173E+004 1.900E+004 77.11 10.70 2.155E+004 1.417E+004 1.049E+004 87.20 3.70 4.277E+004 -1.657E+004 2.081E+004 89.80 1.03 1.513E+005 6.134E+004 7.365E+004 241.98 7.49 1.486E+004 1.305E+004 7.176E+003
Nuclide MDA Report 3/28/2019 9:08:53 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.064E+003 1.39E+003 -5.822E+002 2.422E+003 351.92* 37.20 1.392E+003 1.412E+003 6.336E+002 785.91 1.10 8.569E+004 6.663E+004 3.953E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: 3844 Report Generated On : 3/28/2019 9:21:42 AM Sample Title : B1-010-001-FSFC-D33-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D33 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 9:11:00 AM Acquisition Started : 3/28/2019 9:11:41 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 9:21:42 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D33-GM Peak Analysis Performed on: 3/28/2019 9:21:41 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 943- 960 953.28 238.39 0.95 7.63E+001 35.24 7.07E+001 2 3636- 3649 3642.44 910.89 0.65 2.90E+001 18.66 2.10E+001 3 5830- 5854 5841.30 1460.34 1.78 2.31E+002 32.46 8.46E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 9:21:42 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D33-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.996 1460.81* 10.67 8.30123E+004 1.35505E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.37165E+003 1.15985E+003 300.09 3.41 AC-228 0.997 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.07436E+003 2.01020E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 9:21:42 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.996 8.301231E+004 1.355052E+004 PB-212 0.999 2.371654E+003 1.159853E+003 AC-228 0.997 3.074358E+003 2.010197E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 9:21:41 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/28/2019 9:21:42 AM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D33-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 7.761E+003 7.76E+003 8.301E+004 3.393E+003 CO-60 1173.22 100.00 1.141E+003 8.08E+002 -4.008E+002 5.249E+002 1332.49 100.00 8.078E+002 -7.283E+002 3.552E+002 CS-134 475.35 1.46 6.177E+004 9.37E+002 1.415E+004 2.901E+004 563.23 8.38 1.054E+004 8.463E+003 4.910E+003 569.32 15.43 5.452E+003 -1.527E+003 2.530E+003 604.70 97.60 1.072E+003 -1.180E+002 5.039E+002 795.84 85.40 9.366E+002 1.020E+002 4.252E+002 801.93 8.73 1.016E+004 4.112E+003 4.657E+003 1038.57 1.00 8.335E+004 -3.202E+004 3.741E+004 1167.94 1.80 5.990E+004 -5.491E+004 2.743E+004 1365.15 3.04 2.704E+004 9.887E+003 1.189E+004 CS-137 661.65 85.12 1.077E+003 1.08E+003 2.784E+002 4.996E+002 EU-152 121.78 28.40 3.956E+003 3.63E+003 -3.481E+003 1.920E+003 344.27 26.50 3.635E+003 -1.569E+003 1.731E+003 1407.95 20.70 4.345E+003 -8.439E+002 1.928E+003 EU-154 123.07 40.40 2.795E+003 2.80E+003 1.718E+002 1.357E+003 722.30 20.00 4.575E+003 4.657E+003 2.113E+003 1274.51 34.40 2.923E+003 2.294E+003 1.323E+003 BI-214 609.31 46.30 2.370E+003 2.37E+003 2.563E+003 1.117E+003 768.36 5.04 2.200E+004 7.887E+003 1.028E+004 806.17 1.23 7.393E+004 4.840E+003 3.395E+004 934.06 3.21 2.980E+004 -9.061E+003 1.365E+004 1120.29 15.10 7.297E+003 4.774E+003 3.355E+003 1155.19 1.69 5.307E+004 -1.058E+004 2.386E+004 1238.11 5.94 2.075E+004 6.512E+003 9.585E+003 1280.96 1.47 6.656E+004 2.782E+004 3.004E+004 1377.67 4.11 1.747E+004 6.415E+003 7.522E+003 1385.31 0.78 1.011E+005 7.590E+004 4.414E+004 1401.50 1.39 5.563E+004 3.221E+003 2.418E+004 1407.98 2.48 3.627E+004 -7.044E+003 1.609E+004 1509.19 2.19 2.697E+004 1.257E+004 1.105E+004 1661.28 1.15 6.104E+004 8.343E+003 2.556E+004 1729.60 3.05 2.005E+004 8.528E+003 8.100E+003 1764.49 15.80 5.933E+003 -2.087E+002 2.590E+003 1847.44 2.12 2.797E+004 1.067E+004 1.110E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.751E+004 2.68E+003 3.154E+004 1.824E+004 77.11 10.70 2.098E+004 2.051E+004 1.021E+004 87.20 3.70 4.390E+004 1.479E+004 2.137E+004 89.80 1.03 1.476E+005 -6.614E+004 7.178E+004 241.98 7.49 1.496E+004 2.900E+002 7.228E+003
Nuclide MDA Report 3/28/2019 9:21:42 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 5.335E+003 2.68E+003 1.070E+003 2.558E+003 351.92 37.20 2.683E+003 1.641E+003 1.279E+003 785.91 1.10 8.651E+004 6.080E+004 3.994E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FSFC-D34-GM.CNF Report Generated On : 3/27/2019 9:01:56 PM Sample Title : B1-010-001-FSFC-D34-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D34 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 8:42:00 AM Acquisition Started : 3/27/2019 8:43:24 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 9:01:56 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D34-GM Peak Analysis Performed on: 3/27/2019 9:01:56 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 949- 961 955.01 238.82 0.41 2.33E+001 26.29 5.67E+001 2 2328- 2340 2333.04 583.51 0.73 2.13E+001 15.19 1.37E+001 3 2429- 2445 2436.70 609.43 0.53 5.29E+001 19.02 1.21E+001 4 5831- 5854 5843.88 1460.98 1.53 2.15E+002 29.33 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:01:56 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D34-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.999 1460.81* 10.67 7.74422E+004 1.23495E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 7.24535E+002 8.26503E+002 300.09 3.41 BI-214 1.000 609.31* 46.30 2.66118E+003 1.01637E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:01:56 PM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.999 7.744224E+004 1.234949E+004 PB-212 1.000 7.245353E+002 8.265030E+002 BI-214 1.000 2.661175E+003 1.016369E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 9:01:56 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 583.51 3.5476E-002 71.38 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 9:01:56 PM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D34-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 9.747E+002 9.75E+002 7.744E+004 0.000E+000 CO-60 1173.22 100.00 1.030E+003 8.46E+002 9.818E+002 4.695E+002 1332.49 100.00 8.463E+002 -5.353E+001 3.744E+002 CS-134 475.35 1.46 6.318E+004 1.07E+003 -5.031E+004 2.972E+004 563.23 8.38 1.022E+004 -1.701E+003 4.752E+003 569.32 15.43 5.407E+003 -3.124E+003 2.507E+003 604.70 97.60 1.165E+003 -1.085E+003 5.503E+002 795.84 85.40 1.068E+003 5.250E+002 4.910E+002 801.93 8.73 9.694E+003 3.361E+003 4.424E+003 1038.57 1.00 9.657E+004 4.470E+004 4.402E+004 1167.94 1.80 5.012E+004 2.190E+004 2.254E+004 1365.15 3.04 2.955E+004 -1.048E+004 1.314E+004 CS-137 661.65 85.12 1.068E+003 1.07E+003 2.510E+002 4.951E+002 EU-152 121.78 28.40 3.762E+003 3.42E+003 1.822E+001 1.823E+003 344.27 26.50 3.425E+003 -4.291E+003 1.626E+003 1407.95 20.70 4.059E+003 1.499E+003 1.785E+003 EU-154 123.07 40.40 2.649E+003 2.51E+003 1.315E+003 1.284E+003 722.30 20.00 4.740E+003 2.500E+003 2.196E+003 1274.51 34.40 2.506E+003 6.897E+002 1.115E+003 + BI-214 609.31* 46.30 1.152E+003 1.15E+003 2.661E+003 5.078E+002 768.36 5.04 1.898E+004 1.179E+004 8.778E+003 806.17 1.23 6.816E+004 4.247E+004 3.107E+004 934.06 3.21 2.730E+004 5.572E+003 1.240E+004 1120.29 15.10 5.940E+003 -6.685E+003 2.676E+003 1155.19 1.69 5.218E+004 -5.803E+004 2.342E+004 1238.11 5.94 1.762E+004 7.421E+003 8.020E+003 1280.96 1.47 5.999E+004 -7.099E+004 2.675E+004 1377.67 4.11 1.804E+004 -1.121E+003 7.806E+003 1385.31 0.78 1.164E+005 -5.121E+004 5.176E+004 1401.50 1.39 5.722E+004 2.013E+003 2.498E+004 1407.98 2.48 3.388E+004 1.252E+004 1.490E+004 1509.19 2.19 3.258E+004 1.976E+004 1.386E+004 1661.28 1.15 4.802E+004 -8.974E+003 1.905E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49 15.80 5.048E+003 3.061E+003 2.147E+003 1847.44 2.12 3.556E+004 -1.067E+003 1.489E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.685E+004 2.67E+003 1.510E+004 1.791E+004 77.11 10.70 2.028E+004 1.521E+004 9.858E+003 87.20 3.70 4.093E+004 2.735E+003 1.989E+004 89.80 1.03 1.436E+005 1.466E+004 6.979E+004 241.98 7.49 1.327E+004 6.299E+003 6.383E+003
Nuclide MDA Report 3/27/2019 9:01:56 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 4.419E+003 2.67E+003 1.957E+003 2.100E+003 351.92 37.20 2.665E+003 1.361E+003 1.271E+003 785.91 1.10 8.813E+004 -3.084E+004 4.075E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FSFC-D35-GM.CNF Report Generated On : 3/27/2019 9:03:02 PM Sample Title : B1-010-001-FSFC-D35-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D35 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 9:04:00 AM Acquisition Started : 3/27/2019 9:05:12 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 9:03:02 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D35-GM Peak Analysis Performed on: 3/27/2019 9:03:02 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 958 952.68 238.24 0.67 2.79E+001 27.41 6.21E+001 2 1400- 1413 1405.57 351.54 0.82 4.30E+001 24.71 3.90E+001 3 2426- 2440 2432.97 608.50 1.13 2.45E+001 18.94 2.25E+001 4 5824- 5847 5835.50 1458.89 0.89 1.69E+002 27.01 3.21E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:03:02 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D35-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.936 1460.81* 10.67 6.07351E+004 1.09375E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 8.67969E+002 8.63469E+002 300.09 3.41 BI-214 0.995 609.31* 46.30 1.23231E+003 9.65838E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.97681E+003 1.17909E+003 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:03:02 PM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.936 6.073511E+004 1.093748E+004 PB-212 0.999 8.679694E+002 8.634687E+002 BI-214 0.995 1.232310E+003 9.658382E+002 PB-214 0.999 1.976806E+003 1.179094E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 9:03:02 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/27/2019 9:03:02 PM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D35-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 5.337E+003 5.34E+003 6.074E+004 2.182E+003 CO-60 1173.22 100.00 9.482E+002 7.24E+002 2.430E+002 4.286E+002 1332.49 100.00 7.239E+002 -8.483E+001 3.133E+002 CS-134 475.35 1.46 5.920E+004 9.49E+002 -2.113E+004 2.773E+004 563.23 8.38 9.895E+003 -7.229E+003 4.588E+003 569.32 15.43 5.126E+003 -3.996E+003 2.366E+003 604.70 97.60 1.137E+003 7.201E+002 5.363E+002 795.84 85.40 9.494E+002 -4.750E+002 4.316E+002 801.93 8.73 1.038E+004 7.325E+003 4.769E+003 1038.57 1.00 7.736E+004 -4.232E+004 3.441E+004 1167.94 1.80 5.094E+004 -2.230E+003 2.295E+004 1365.15 3.04 2.568E+004 1.927E+004 1.121E+004 CS-137 661.65 85.12 1.012E+003 1.01E+003 7.907E+001 4.673E+002 EU-152 121.78 28.40 3.951E+003 3.40E+003 -7.203E+002 1.918E+003 344.27 26.50 3.397E+003 -4.052E+003 1.612E+003 1407.95 20.70 4.436E+003 -1.849E+002 1.973E+003 EU-154 123.07 40.40 2.730E+003 2.56E+003 8.503E+002 1.325E+003 722.30 20.00 3.833E+003 -1.477E+003 1.743E+003 1274.51 34.40 2.556E+003 -4.887E+001 1.140E+003 + BI-214 609.31* 46.30 1.472E+003 1.47E+003 1.232E+003 6.682E+002 768.36 5.04 1.736E+004 1.099E+004 7.966E+003 806.17 1.23 7.777E+004 4.563E+004 3.587E+004 934.06 3.21 2.876E+004 -4.976E+003 1.313E+004 1120.29 15.10 7.297E+003 4.707E+003 3.355E+003 1155.19 1.69 6.045E+004 1.086E+004 2.756E+004 1238.11 5.94 1.691E+004 5.950E+003 7.668E+003 1280.96 1.47 5.999E+004 4.154E+004 2.675E+004 1377.67 4.11 1.963E+004 -2.275E+004 8.601E+003 1385.31 0.78 9.242E+004 2.846E+004 3.979E+004 1401.50 1.39 6.170E+004 5.100E+004 2.722E+004 1407.98 2.48 3.702E+004 -1.544E+003 1.647E+004 1509.19 2.19 2.993E+004 1.616E+004 1.253E+004 1661.28 1.15 4.400E+004 -9.615E+003 1.704E+004 1729.60 3.05 2.134E+004 -1.523E+003 8.749E+003 1764.49 15.80 5.239E+003 9.103E+002 2.243E+003 1847.44 2.12 3.204E+004 1.494E+004 1.313E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.794E+004 1.71E+003 3.323E+004 1.845E+004 77.11 10.70 2.066E+004 1.376E+004 1.005E+004 87.20 3.70 4.093E+004 4.087E+002 1.989E+004 89.80 1.03 1.419E+005 -9.166E+004 6.894E+004 241.98 7.49 1.368E+004 1.443E+004 6.586E+003
Nuclide MDA Report 3/27/2019 9:03:02 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 4.602E+003 1.71E+003 6.107E+002 2.191E+003 351.92* 37.20 1.708E+003 1.977E+003 7.918E+002 785.91 1.10 7.119E+004 -2.705E+004 3.227E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FSFC-D36-GM.CNF Report Generated On : 3/27/2019 9:04:08 PM Sample Title : B1-010-001-FSFC-D36-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D36 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 9:23:00 AM Acquisition Started : 3/27/2019 9:23:00 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 9:04:08 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D36-GM Peak Analysis Performed on: 3/27/2019 9:04:08 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 945- 959 952.41 238.17 0.85 8.88E+001 32.02 5.82E+001 2 1400- 1413 1406.32 351.73 0.82 2.17E+001 20.77 3.13E+001 3 2323- 2336 2329.65 582.66 0.94 3.14E+001 17.24 1.56E+001 4 2427- 2439 2432.72 608.43 0.68 4.61E+001 16.35 7.94E+000 5 3632- 3645 3638.20 909.83 0.45 2.55E+001 15.59 1.25E+001 6 5826- 5847 5836.15 1459.05 0.87 2.01E+002 30.24 7.60E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:04:08 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D36-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.946 1460.81* 10.67 7.24762E+004 1.24213E+004 PB-212 0.998 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.76063E+003 1.08899E+003 300.09 3.41 BI-214 0.994 609.31* 46.30 2.31685E+003 8.74311E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 9.98956E+002 9.68318E+002 785.91 1.10 AC-228 0.984 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40
Interference Corrected Activity Report 3/27/2019 9:04:08 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.984 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.70368E+003 1.68081E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:04:08 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.946 7.247621E+004 1.242127E+004 PB-212 0.998 2.760628E+003 1.088987E+003 BI-214 0.994 2.316849E+003 8.743107E+002 PB-214 1.000 9.989564E+002 9.683176E+002 AC-228 0.984 2.703676E+003 1.680806E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
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Peak Locate Performed on: 3/27/2019 9:04:08 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 582.66 5.2349E-002 54.89 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 9:04:08 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D36-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 7.154E+003 7.15E+003 7.248E+004 3.090E+003 CO-60 1173.22 100.00 9.338E+002 7.01E+002 -1.584E+003 4.214E+002 1332.49 100.00 7.011E+002 4.679E+002 3.019E+002 CS-134 475.35 1.46 6.283E+004 1.10E+003 -7.348E+003 2.954E+004 563.23 8.38 9.555E+003 4.420E+003 4.418E+003 569.32 15.43 5.174E+003 -2.046E+003 2.390E+003 604.70 97.60 1.096E+003 1.360E+003 5.159E+002 795.84 85.40 1.194E+003 9.069E+002 5.539E+002 801.93 8.73 1.134E+004 9.650E+003 5.245E+003 1038.57 1.00 9.409E+004 -3.075E+004 4.278E+004 1167.94 1.80 5.851E+004 -2.869E+004 2.673E+004 1365.15 3.04 2.347E+004 -1.297E+004 1.010E+004 CS-137 661.65 85.12 1.146E+003 1.15E+003 8.840E+002 5.341E+002 EU-152 121.78 28.40 3.956E+003 3.33E+003 1.859E+003 1.920E+003 344.27 26.50 3.328E+003 -2.059E+003 1.578E+003 1407.95 20.70 4.345E+003 3.797E+003 1.928E+003 EU-154 123.07 40.40 2.767E+003 2.77E+003 8.675E+002 1.343E+003 722.30 20.00 4.489E+003 -3.138E+003 2.071E+003 1274.51 34.40 3.008E+003 1.091E+003 1.366E+003 + BI-214 609.31* 46.30 8.902E+002 8.90E+002 2.317E+003 3.771E+002 768.36 5.04 1.846E+004 -1.096E+004 8.516E+003 806.17 1.23 7.702E+004 2.343E+004 3.550E+004 934.06 3.21 3.081E+004 6.471E+003 1.415E+004 1120.29 15.10 6.905E+003 -1.703E+003 3.158E+003 1155.19 1.69 6.045E+004 4.184E+004 2.756E+004 1238.11 5.94 2.075E+004 7.193E+003 9.585E+003 1280.96 1.47 6.226E+004 -4.191E+004 2.789E+004 1377.67 4.11 1.626E+004 9.864E+003 6.919E+003 1385.31 0.78 1.038E+005 8.065E+004 4.550E+004 1401.50 1.39 5.722E+004 4.295E+004 2.498E+004 1407.98 2.48 3.627E+004 3.170E+004 1.609E+004 1509.19 2.19 2.533E+004 1.946E+003 1.023E+004 1661.28 1.15 5.500E+004 2.564E+004 2.254E+004 1729.60 3.05 2.578E+004 1.131E+003 1.097E+004 1764.49 15.80 5.933E+003 4.453E+003 2.590E+003 1847.44 2.12 3.386E+004 1.707E+004 1.404E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.849E+004 1.53E+003 4.617E+004 1.873E+004 77.11 10.70 2.109E+004 1.124E+004 1.027E+004 87.20 3.70 4.268E+004 1.342E+004 2.076E+004 89.80 1.03 1.477E+005 8.410E+004 7.187E+004 241.98 7.49 1.491E+004 -9.707E+003 7.202E+003
Nuclide MDA Report 3/27/2019 9:04:08 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 4.745E+003 1.53E+003 2.035E+003 2.263E+003 351.92* 37.20 1.528E+003 9.990E+002 7.020E+002 785.91 1.10 8.318E+004 -4.195E+004 3.827E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: 3844 Report Generated On : 3/28/2019 9:33:16 AM Sample Title : B1-010-001-FSFC-D37-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D37 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 9:22:00 AM Acquisition Started : 3/28/2019 9:23:15 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 9:33:16 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D37-GM Peak Analysis Performed on: 3/28/2019 9:33:16 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 295- 304 299.86 74.90 0.41 2.95E+001 33.44 1.11E+002 2 949- 960 954.67 238.74 1.15 4.20E+001 28.76 6.50E+001 3 1401- 1413 1407.57 352.04 0.94 3.23E+001 19.19 2.28E+001 4 2324- 2338 2331.35 583.09 0.33 3.10E+001 17.22 1.50E+001 5 2429- 2443 2436.56 609.39 0.58 4.60E+001 16.96 8.97E+000 6 3636- 3650 3642.61 910.93 0.52 4.33E+001 14.71 3.75E+000 7 5829- 5853 5841.78 1460.46 1.62 2.44E+002 32.03 3.07E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 9:33:16 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D37-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.998 1460.81* 10.67 8.78399E+004 1.36270E+004 PB-212 1.000 74.81* 9.60 7.40938E+003 8.53574E+003 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.30747E+003 9.19139E+002 300.09 3.41 BI-214 1.000 609.31* 46.30 2.31704E+003 9.03774E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.626 74.81* 6.33 1.12370E+004 1.29452E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.48353E+003 9.14292E+002 785.91 1.10 AC-228 0.998 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40
Interference Corrected Activity Report 3/28/2019 9:33:16 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.998 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 4.58515E+003 1.64746E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 9:33:16 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.998 8.783988E+004 1.362699E+004 PB-212 1.000 1.365914E+003 9.138820E+002 BI-214 1.000 2.317044E+003 9.037736E+002 PB-214 0.626 1.521660E+003 9.120459E+002 AC-228 0.998 4.585147E+003 1.647459E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 9:33:16 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 4 583.09 5.1667E-002 55.55 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/28/2019 9:33:17 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D37-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 5.171E+003 5.17E+003 8.784E+004 2.098E+003 CO-60 1173.22 100.00 8.890E+002 8.65E+002 6.417E+002 3.990E+002 1332.49 100.00 8.647E+002 4.824E+002 3.837E+002 CS-134 475.35 1.46 5.572E+004 1.11E+003 2.848E+004 2.599E+004 563.23 8.38 1.069E+004 -2.668E+003 4.987E+003 569.32 15.43 5.221E+003 1.853E+003 2.414E+003 604.70 97.60 1.143E+003 -2.935E+002 5.391E+002 795.84 85.40 1.112E+003 8.721E+002 5.129E+002 801.93 8.73 1.082E+004 -6.782E+003 4.986E+003 1038.57 1.00 1.013E+005 2.357E+004 4.640E+004 1167.94 1.80 4.384E+004 -2.493E+004 1.940E+004 1365.15 3.04 2.423E+004 -2.607E+004 1.048E+004 CS-137 661.65 85.12 1.146E+003 1.15E+003 -6.421E+002 5.341E+002 EU-152 121.78 28.40 4.194E+003 3.45E+003 -2.248E+003 2.040E+003 344.27 26.50 3.452E+003 -1.174E+003 1.639E+003 1407.95 20.70 4.436E+003 1.130E+003 1.973E+003 EU-154 123.07 40.40 2.914E+003 2.91E+003 -1.688E+003 1.417E+003 722.30 20.00 5.055E+003 -3.543E+002 2.353E+003 1274.51 34.40 3.049E+003 -2.074E+002 1.386E+003 + BI-214 609.31* 46.30 9.787E+002 9.79E+002 2.317E+003 4.212E+002 768.36 5.04 1.846E+004 -3.638E+003 8.516E+003 806.17 1.23 7.998E+004 8.222E+004 3.698E+004 934.06 3.21 3.422E+004 2.233E+004 1.586E+004 1120.29 15.10 8.157E+003 5.221E+003 3.784E+003 1155.19 1.69 6.415E+004 2.937E+004 2.941E+004 1238.11 5.94 1.936E+004 -2.073E+003 8.889E+003 1280.96 1.47 7.342E+004 1.142E+004 3.347E+004 1377.67 4.11 2.155E+004 -1.516E+003 9.560E+003 1385.31 0.78 1.065E+005 -1.212E+004 4.682E+004 1401.50 1.39 5.399E+004 -1.122E+004 2.336E+004 1407.98 2.48 3.702E+004 9.434E+003 1.647E+004 1509.19 2.19 3.129E+004 6.511E+003 1.321E+004 1661.28 1.15 6.643E+004 4.029E+004 2.826E+004 1729.60 3.05 2.134E+004 9.950E+003 8.749E+003 1764.49 15.80 4.179E+003 -9.045E+002 1.713E+003 1847.44 2.12 3.556E+004 1.920E+004 1.489E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81* 6.33 2.087E+004 1.30E+003 1.124E+004 9.918E+003 77.11 10.70 2.075E+004 1.207E+004 1.009E+004 87.20 3.70 4.517E+004 2.484E+002 2.201E+004 89.80 1.03 1.557E+005 7.284E+004 7.585E+004 241.98 7.49 1.421E+004 1.483E+004 6.853E+003
Nuclide MDA Report 3/28/2019 9:33:17 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.166E+003 1.30E+003 3.552E+003 2.473E+003 351.92* 37.20 1.295E+003 1.484E+003 5.854E+002 785.91 1.10 8.233E+004 -1.200E+005 3.785E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: 3844 Report Generated On : 3/28/2019 9:48:55 AM Sample Title : B1-010-001-FSFC-D38-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D38 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 9:36:00 AM Acquisition Started : 3/28/2019 9:38:54 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 9:48:55 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D38-GM Peak Analysis Performed on: 3/28/2019 9:48:54 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 947- 961 953.95 238.56 0.62 4.43E+001 32.94 7.88E+001 2 1400- 1414 1407.68 352.07 0.32 4.03E+001 22.55 2.97E+001 3 2325- 2338 2331.42 583.10 0.32 4.49E+001 16.86 9.07E+000 4 3638- 3651 3644.76 911.47 0.80 2.71E+001 15.43 1.09E+001 5 5830- 5855 5841.69 1460.43 1.88 2.60E+002 33.70 5.96E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 9:48:55 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D38-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.997 1460.81* 10.67 9.36396E+004 1.43923E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.37664E+003 1.04813E+003 300.09 3.41 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.85391E+003 1.07889E+003 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 2.87171E+003 1.67009E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 9:48:55 AM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.997 9.363961E+004 1.439235E+004 PB-212 1.000 1.376644E+003 1.048130E+003 PB-214 1.000 1.853913E+003 1.078888E+003 AC-228 1.000 2.871706E+003 1.670089E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 9:48:54 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 583.10 7.4884E-002 37.52 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/28/2019 9:48:55 AM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D38-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 6.771E+003 6.77E+003 9.364E+004 2.898E+003 CO-60 1173.22 100.00 1.043E+003 8.46E+002 -3.357E+002 4.760E+002 1332.49 100.00 8.463E+002 -1.228E+002 3.744E+002 CS-134 475.35 1.46 5.768E+004 1.03E+003 -3.644E+004 2.697E+004 563.23 8.38 9.380E+003 -2.034E+003 4.330E+003 569.32 15.43 5.497E+003 -3.202E+003 2.552E+003 604.70 97.60 1.125E+003 1.310E+003 5.305E+002 795.84 85.40 1.034E+003 5.904E+002 4.740E+002 801.93 8.73 1.005E+004 -4.690E+003 4.600E+003 1038.57 1.00 9.409E+004 6.229E+004 4.278E+004 1167.94 1.80 5.411E+004 2.796E+003 2.453E+004 1365.15 3.04 2.185E+004 -1.013E+004 9.294E+003 CS-137 661.65 85.12 1.068E+003 1.07E+003 -1.337E+002 4.951E+002 EU-152 121.78 28.40 4.052E+003 3.33E+003 -1.119E+003 1.968E+003 344.27 26.50 3.328E+003 -1.921E+003 1.578E+003 1407.95 20.70 4.345E+003 -4.607E+002 1.928E+003 EU-154 123.07 40.40 2.873E+003 2.87E+003 2.215E+003 1.396E+003 722.30 20.00 4.446E+003 1.648E+003 2.049E+003 1274.51 34.40 3.129E+003 1.362E+002 1.426E+003 BI-214 609.31 46.30 2.455E+003 2.45E+003 3.280E+003 1.159E+003 768.36 5.04 2.110E+004 -2.053E+004 9.833E+003 806.17 1.23 7.393E+004 1.975E+004 3.395E+004 934.06 3.21 2.946E+004 2.296E+004 1.348E+004 1120.29 15.10 7.373E+003 -2.181E+003 3.393E+003 1155.19 1.69 6.557E+004 4.227E+004 3.012E+004 1238.11 5.94 1.872E+004 7.866E+002 8.573E+003 1280.96 1.47 6.226E+004 -7.046E+004 2.789E+004 1377.67 4.11 2.109E+004 1.062E+004 9.330E+003 1385.31 0.78 1.065E+005 5.534E+004 4.682E+004 1401.50 1.39 5.563E+004 4.921E+003 2.418E+004 1407.98 2.48 3.627E+004 -3.845E+003 1.609E+004 1509.19 2.19 2.697E+004 -1.116E+004 1.105E+004 1661.28 1.15 6.104E+004 3.297E+004 2.556E+004 1729.60 3.05 2.134E+004 -9.543E+003 8.749E+003 1764.49 15.80 6.398E+003 3.208E+003 2.822E+003 1847.44 2.12 3.009E+004 -3.201E+004 1.216E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.703E+004 1.53E+003 4.660E+004 1.800E+004 77.11 10.70 2.028E+004 1.015E+004 9.858E+003 87.20 3.70 4.249E+004 2.019E+003 2.067E+004 89.80 1.03 1.452E+005 2.493E+004 7.063E+004 241.98 7.49 1.432E+004 8.330E+003 6.908E+003
Nuclide MDA Report 3/28/2019 9:48:55 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.418E+003 1.53E+003 8.042E+001 2.599E+003 351.92* 37.20 1.535E+003 1.854E+003 7.051E+002 785.91 1.10 7.970E+004 4.217E+003 3.653E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: 3844 Report Generated On : 3/28/2019 10:44:33 AM Sample Title : B1-010-001-FSFC-D39-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D39 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 10:33:00 AM Acquisition Started : 3/28/2019 10:34:32 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 10:44:33 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D39-GM Peak Analysis Performed on: 3/28/2019 10:44:33 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 962 953.78 238.51 0.94 5.95E+001 32.51 6.55E+001 2 1400- 1411 1405.91 351.62 0.53 2.21E+001 20.44 3.29E+001 3 2427- 2440 2434.44 608.87 0.62 4.73E+001 19.06 1.57E+001 4 3634- 3647 3640.06 910.29 1.36 2.98E+001 14.49 8.18E+000 5 5826- 5849 5837.53 1459.39 1.95 2.24E+002 29.93 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 10:44:33 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D39-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.965 1460.81* 10.67 8.06214E+004 1.26661E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.85128E+003 1.05386E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 2.38041E+003 1.00644E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.01681E+003 9.53546E+002 785.91 1.10 AC-228 0.991 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40
Interference Corrected Activity Report 3/28/2019 10:44:33 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.991 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.16040E+003 1.57875E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 10:44:33 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.965 8.062144E+004 1.266611E+004 PB-212 1.000 1.851279E+003 1.053863E+003 BI-214 0.999 2.380414E+003 1.006444E+003 PB-214 0.999 1.016808E+003 9.535456E+002 AC-228 0.991 3.160405E+003 1.578755E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 10:44:33 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/28/2019 10:44:33 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D39-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 9.739E+002 9.74E+002 8.062E+004 0.000E+000 CO-60 1173.22 100.00 1.129E+003 7.46E+002 1.707E+002 5.191E+002 1332.49 100.00 7.459E+002 -8.997E+000 3.243E+002 CS-134 475.35 1.46 5.768E+004 1.10E+003 -9.006E+003 2.697E+004 563.23 8.38 1.022E+004 7.820E+002 4.752E+003 569.32 15.43 5.630E+003 -1.246E+003 2.618E+003 604.70 97.60 1.198E+003 6.902E+002 5.668E+002 795.84 85.40 1.101E+003 -1.000E+002 5.075E+002 801.93 8.73 1.038E+004 -1.161E+004 4.769E+003 1038.57 1.00 9.283E+004 3.519E+004 4.215E+004 1167.94 1.80 6.058E+004 -8.855E+003 2.777E+004 1365.15 3.04 2.568E+004 8.582E+003 1.121E+004 CS-137 661.65 85.12 1.226E+003 1.23E+003 1.185E+003 5.743E+002 EU-152 121.78 28.40 3.982E+003 3.54E+003 -2.623E+002 1.933E+003 344.27 26.50 3.544E+003 -2.904E+003 1.686E+003 1407.95 20.70 4.524E+003 2.962E+003 2.018E+003 EU-154 123.07 40.40 2.824E+003 2.79E+003 2.860E+003 1.371E+003 722.30 20.00 4.978E+003 3.262E+003 2.315E+003 1274.51 34.40 2.792E+003 4.717E+002 1.258E+003 + BI-214 609.31* 46.30 1.228E+003 1.23E+003 2.380E+003 5.461E+002 768.36 5.04 1.698E+004 -8.308E+003 7.774E+003 806.17 1.23 7.233E+004 1.593E+004 3.315E+004 934.06 3.21 3.333E+004 1.447E+004 1.541E+004 1120.29 15.10 7.882E+003 -1.956E+003 3.647E+003 1155.19 1.69 6.045E+004 1.017E+004 2.756E+004 1238.11 5.94 1.762E+004 -1.777E+003 8.020E+003 1280.96 1.47 6.551E+004 -5.994E+003 2.951E+004 1377.67 4.11 2.013E+004 -4.284E+003 8.851E+003 1385.31 0.78 1.090E+005 -7.640E+004 4.810E+004 1401.50 1.39 6.449E+004 1.432E+004 2.862E+004 1407.98 2.48 3.776E+004 2.472E+004 1.684E+004 1509.19 2.19 3.613E+004 2.514E+004 1.563E+004 1661.28 1.15 3.943E+004 1.099E+004 1.476E+004 1729.60 3.05 2.676E+004 5.449E+003 1.145E+004 1764.49 15.80 6.092E+003 2.034E+003 2.670E+003 1847.44 2.12 2.563E+004 -1.040E+004 9.928E+003 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.658E+004 1.50E+003 3.016E+004 1.777E+004 77.11 10.70 1.982E+004 -6.735E+003 9.630E+003 87.20 3.70 4.348E+004 4.664E+004 2.116E+004 89.80 1.03 1.464E+005 -2.130E+004 7.121E+004 241.98 7.49 1.418E+004 1.087E+004 6.839E+003
Nuclide MDA Report 3/28/2019 10:44:33 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.194E+003 1.50E+003 -7.489E+002 2.488E+003 351.92* 37.20 1.497E+003 1.017E+003 6.861E+002 785.91 1.10 8.403E+004 -7.299E+004 3.870E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: 3844 Report Generated On : 3/28/2019 10:04:21 AM Sample Title : B1-010-001-FSFC-D40-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D40 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 9:52:00 AM Acquisition Started : 3/28/2019 9:54:20 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 10:04:21 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D40-GM Peak Analysis Performed on: 3/28/2019 10:04:21 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 961 953.36 238.41 0.59 3.47E+001 31.20 7.53E+001 2 2325- 2337 2330.29 582.82 0.33 2.69E+001 18.30 2.11E+001 3 2430- 2442 2435.17 609.05 0.36 2.93E+001 17.18 1.67E+001 4 3634- 3647 3640.25 910.34 0.32 3.20E+001 14.32 7.00E+000 5 5825- 5850 5837.93 1459.49 1.94 2.43E+002 31.18 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 10:04:21 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D40-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.970 1460.81* 10.67 8.74641E+004 1.33468E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.07946E+003 9.85474E+002 300.09 3.41 BI-214 1.000 609.31* 46.30 1.47281E+003 8.85054E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 AC-228 0.992 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.39127E+003 1.56809E+003 964.60 5.20 969.11 16.60 1587.90 3.71
Interference Corrected Activity Report 3/28/2019 10:04:21 AM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 10:04:21 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.970 8.746415E+004 1.334682E+004 PB-212 1.000 1.079464E+003 9.854740E+002 BI-214 1.000 1.472808E+003 8.850540E+002 AC-228 0.992 3.391272E+003 1.568094E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 10:04:21 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 2 582.82 4.4792E-002 68.11 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/28/2019 10:04:21 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D40-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 9.740E+002 9.74E+002 8.746E+004 0.000E+000 CO-60 1173.22 100.00 1.117E+003 8.08E+002 6.903E+002 5.131E+002 1332.49 100.00 8.078E+002 7.498E+000 3.552E+002 CS-134 475.35 1.46 6.212E+004 9.10E+002 -5.300E+004 2.919E+004 563.23 8.38 1.006E+004 3.159E+003 4.670E+003 569.32 15.43 5.315E+003 -6.765E+002 2.461E+003 604.70 97.60 1.154E+003 8.529E+002 5.448E+002 795.84 85.40 9.104E+002 1.239E+002 4.121E+002 801.93 8.73 9.813E+003 -3.295E+003 4.484E+003 1038.57 1.00 8.755E+004 -6.710E+004 3.951E+004 1167.94 1.80 6.387E+004 2.890E+004 2.941E+004 1365.15 3.04 2.568E+004 1.927E+004 1.121E+004 CS-137 661.65 85.12 1.203E+003 1.20E+003 1.466E+003 5.625E+002 EU-152 121.78 28.40 3.868E+003 3.01E+003 2.628E+002 1.876E+003 344.27 26.50 3.609E+003 -3.666E+003 1.718E+003 1407.95 20.70 3.013E+003 -4.069E+003 1.262E+003 EU-154 123.07 40.40 2.705E+003 2.61E+003 -6.605E+002 1.312E+003 722.30 20.00 4.781E+003 9.607E+002 2.217E+003 1274.51 34.40 2.606E+003 -5.300E+002 1.165E+003 + BI-214 609.31* 46.30 1.241E+003 1.24E+003 1.473E+003 5.525E+002 768.36 5.04 1.792E+004 -4.403E+002 8.245E+003 806.17 1.23 7.314E+004 2.101E+004 3.356E+004 934.06 3.21 2.654E+004 8.909E+003 1.201E+004 1120.29 15.10 7.522E+003 4.875E+003 3.467E+003 1155.19 1.69 6.415E+004 3.537E+004 2.941E+004 1238.11 5.94 1.936E+004 -3.049E+003 8.889E+003 1280.96 1.47 5.881E+004 3.550E+004 2.616E+004 1377.67 4.11 1.912E+004 8.113E+003 8.345E+003 1385.31 0.78 1.011E+005 -2.350E+004 4.414E+004 1401.50 1.39 6.025E+004 2.990E+004 2.649E+004 1407.98 2.48 2.515E+004 -3.396E+004 1.053E+004 1509.19 2.19 3.129E+004 -1.302E+004 1.321E+004 1661.28 1.15 5.500E+004 6.541E+002 2.254E+004 1729.60 3.05 2.578E+004 5.298E+003 1.097E+004 1764.49 15.80 6.247E+003 5.010E+003 2.747E+003 1847.44 2.12 3.870E+004 8.439E+003 1.646E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 PB-214 74.81 6.33 3.720E+004 2.75E+003 2.314E+004 1.808E+004 77.11 10.70 2.096E+004 2.924E+004 1.020E+004 87.20 3.70 4.362E+004 1.515E+004 2.123E+004 89.80 1.03 1.508E+005 -4.281E+004 7.341E+004 241.98 7.49 1.435E+004 1.121E+004 6.921E+003
Nuclide MDA Report 3/28/2019 10:04:21 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) PB-214 295.21 19.20 5.194E+003 2.75E+003 3.501E+002 2.488E+003 351.92 37.20 2.754E+003 2.074E+003 1.315E+003 785.91 1.10 7.605E+004 -4.237E+004 3.470E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D41-GM.CNF Report Generated On : 3/27/2019 9:05:23 PM Sample Title : B1-010-001-FSFC-D41-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D41 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 9:39:00 AM Acquisition Started : 3/27/2019 9:39:23 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 9:05:23 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D41-GM Peak Analysis Performed on: 3/27/2019 9:05:22 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 945- 959 952.80 238.27 0.99 3.17E+001 33.17 8.33E+001 2 1174- 1185 1179.08 294.88 1.15 1.95E+001 20.30 3.25E+001 3 1400- 1413 1405.84 351.60 0.82 3.35E+001 19.65 2.25E+001 4 2424- 2440 2431.93 608.24 0.39 4.72E+001 19.32 1.48E+001 5 3631- 3645 3637.17 909.57 0.93 3.57E+001 15.41 8.34E+000 6 5821- 5847 5834.02 1458.52 1.96 2.16E+002 30.29 3.20E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:05:23 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D41-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.911 1460.81* 10.67 7.76353E+004 1.26437E+004 PB-212 0.999 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 9.85095E+002 1.04309E+003 300.09 3.41 BI-214 0.992 609.31* 46.30 2.37501E+003 1.01817E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 1.57855E+003 1.66412E+003 351.92* 37.20 1.54165E+003 9.36268E+002 785.91 1.10 AC-228 0.979 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40
Interference Corrected Activity Report 3/27/2019 9:05:23 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.979 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.77789E+003 1.69080E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:05:23 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.911 7.763525E+004 1.264374E+004 PB-212 0.999 9.850953E+002 1.043094E+003 BI-214 0.992 2.375007E+003 1.018173E+003 PB-214 0.999 1.550522E+003 8.159862E+002 AC-228 0.979 3.777894E+003 1.690796E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 9:05:22 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/27/2019 9:05:23 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D41-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 5.328E+003 5.33E+003 7.764E+004 2.177E+003 CO-60 1173.22 100.00 1.141E+003 8.83E+002 -1.437E+002 5.249E+002 1332.49 100.00 8.828E+002 4.679E+002 3.927E+002 CS-134 475.35 1.46 5.995E+004 1.12E+003 1.717E+004 2.810E+004 563.23 8.38 9.811E+003 1.187E+003 4.546E+003 569.32 15.43 4.928E+003 -4.577E+003 2.268E+003 604.70 97.60 1.159E+003 1.191E+003 5.476E+002 795.84 85.40 1.122E+003 4.788E+002 5.182E+002 801.93 8.73 1.038E+004 3.893E+003 4.769E+003 1038.57 1.00 8.890E+004 -3.784E+003 4.018E+004 1167.94 1.80 5.990E+004 1.771E+004 2.743E+004 1365.15 3.04 2.098E+004 -1.460E+004 8.861E+003 CS-137 661.65 85.12 1.077E+003 1.08E+003 2.820E+002 4.996E+002 EU-152 121.78 28.40 3.868E+003 3.27E+003 1.774E+002 1.876E+003 344.27 26.50 3.272E+003 -6.733E+003 1.550E+003 1407.95 20.70 3.748E+003 -2.984E+003 1.629E+003 EU-154 123.07 40.40 2.664E+003 2.61E+003 -1.639E+003 1.291E+003 722.30 20.00 4.358E+003 2.229E+003 2.005E+003 1274.51 34.40 2.606E+003 1.654E+003 1.165E+003 + BI-214 609.31* 46.30 1.259E+003 1.26E+003 2.375E+003 5.616E+002 768.36 5.04 1.898E+004 -5.962E+003 8.778E+003 806.17 1.23 6.274E+004 -5.564E+004 2.836E+004 934.06 3.21 2.767E+004 -1.350E+004 1.258E+004 1120.29 15.10 7.952E+003 3.070E+003 3.682E+003 1155.19 1.69 6.343E+004 3.355E+004 2.905E+004 1238.11 5.94 1.715E+004 1.457E+003 7.787E+003 1280.96 1.47 5.881E+004 3.081E+004 2.616E+004 1377.67 4.11 1.859E+004 5.889E+003 8.080E+003 1385.31 0.78 9.832E+004 3.898E+004 4.274E+004 1401.50 1.39 4.868E+004 -4.886E+004 2.071E+004 1407.98 2.48 3.128E+004 -2.490E+004 1.360E+004 1509.19 2.19 2.697E+004 8.339E+002 1.105E+004 1661.28 1.15 5.166E+004 2.198E+004 2.087E+004 1729.60 3.05 2.005E+004 8.528E+003 8.100E+003 1764.49 15.80 5.598E+003 3.896E+003 2.423E+003 1847.44 2.12 3.556E+004 1.920E+004 1.489E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.685E+004 1.32E+003 5.738E+004 1.791E+004 77.11 10.70 2.054E+004 3.511E+004 9.988E+003 87.20 3.70 4.220E+004 2.266E+003 2.052E+004 89.80 1.03 1.456E+005 -3.333E+004 7.079E+004 241.98 7.49 1.427E+004 2.476E+003 6.880E+003
Nuclide MDA Report 3/27/2019 9:05:23 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21* 19.20 2.656E+003 1.32E+003 1.579E+003 1.218E+003 351.92* 37.20 1.325E+003 1.542E+003 6.001E+002 785.91 1.10 8.318E+004 -4.320E+004 3.827E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FSFC-D42-GM.CNF Report Generated On : 3/27/2019 9:07:11 PM Sample Title : B1-010-001-FSFC-D42-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D42 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 9:55:00 AM Acquisition Started : 3/27/2019 9:55:26 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 9:07:11 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D42-GM Peak Analysis Performed on: 3/27/2019 9:07:11 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 295- 305 299.44 74.79 0.90 4.17E+001 33.07 9.63E+001 2 947- 958 952.49 238.19 1.11 3.10E+001 25.41 5.20E+001 3 1399- 1411 1404.53 351.28 0.39 2.60E+001 20.85 3.10E+001 4 2425- 2438 2430.76 607.94 0.79 3.69E+001 17.44 1.41E+001 5 5822- 5845 5832.95 1458.25 1.55 1.97E+002 31.00 1.13E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:07:11 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D42-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.890 1460.81* 10.67 7.07733E+004 1.25923E+004 PB-212 0.998 74.81* 9.60 1.05151E+004 8.60772E+003 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 9.64011E+002 8.04929E+002 300.09 3.41 BI-214 0.987 609.31* 46.30 1.85712E+003 9.08664E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.469 74.81* 6.33 1.59470E+004 1.30544E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.19644E+003 9.76846E+002 785.91 1.10
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:07:11 PM Page 4
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.890 7.077327E+004 1.259228E+004 PB-212 0.998 1.039549E+003 8.014524E+002 BI-214 0.987 1.857118E+003 9.086643E+002 PB-214 0.469 1.269798E+003 9.741458E+002
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/27/2019 9:07:11 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/27/2019 9:07:11 PM Page 5
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D42-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 8.784E+003 8.78E+003 7.077E+004 3.905E+003 CO-60 1173.22 100.00 9.901E+002 8.83E+002 5.970E+002 4.495E+002 1332.49 100.00 8.828E+002 2.577E+002 3.927E+002 CS-134 475.35 1.46 5.532E+004 1.08E+003 1.818E+003 2.579E+004 563.23 8.38 1.014E+004 -2.847E+003 4.711E+003 569.32 15.43 5.315E+003 -4.733E+003 2.461E+003 604.70 97.60 1.084E+003 -7.552E+000 5.099E+002 795.84 85.40 1.154E+003 -3.243E+002 5.338E+002 801.93 8.73 1.173E+004 1.118E+004 5.443E+003 1038.57 1.00 9.534E+004 2.050E+004 4.340E+004 1167.94 1.80 5.487E+004 4.957E+003 2.491E+004 1365.15 3.04 2.267E+004 3.588E+003 9.707E+003 CS-137 661.65 85.12 1.234E+003 1.23E+003 7.291E+002 5.782E+002 EU-152 121.78 28.40 3.821E+003 3.36E+003 6.772E+002 1.853E+003 344.27 26.50 3.356E+003 -5.399E+003 1.592E+003 1407.95 20.70 3.855E+003 1.563E+003 1.683E+003 EU-154 123.07 40.40 2.679E+003 2.68E+003 -1.242E+003 1.299E+003 722.30 20.00 4.268E+003 2.970E+003 1.960E+003 1274.51 34.40 2.880E+003 -8.413E+002 1.302E+003 + BI-214 609.31* 46.30 1.171E+003 1.17E+003 1.857E+003 5.173E+002 768.36 5.04 1.810E+004 9.774E+003 8.336E+003 806.17 1.23 7.549E+004 4.178E+004 3.473E+004 934.06 3.21 2.535E+004 -4.638E+002 1.142E+004 1120.29 15.10 8.089E+003 3.777E+003 3.751E+003 1155.19 1.69 5.968E+004 6.077E+003 2.717E+004 1238.11 5.94 1.667E+004 9.718E+003 7.548E+003 1280.96 1.47 6.656E+004 -3.596E+003 3.004E+004 1377.67 4.11 1.912E+004 6.585E+003 8.345E+003 1385.31 0.78 1.038E+005 1.953E+003 4.550E+004 1401.50 1.39 5.563E+004 -4.160E+004 2.418E+004 1407.98 2.48 3.218E+004 1.304E+004 1.405E+004 1509.19 2.19 3.613E+004 -6.286E+003 1.563E+004 1661.28 1.15 4.400E+004 1.465E+004 1.704E+004 1729.60 3.05 2.005E+004 -1.267E+004 8.100E+003 1764.49 15.80 7.727E+003 8.071E+003 3.487E+003 1847.44 2.12 1.570E+004 -8.536E+003 4.964E+003 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81* 6.33 2.021E+004 1.50E+003 1.595E+004 9.586E+003 77.11 10.70 1.994E+004 1.479E+004 9.691E+003 87.20 3.70 4.152E+004 -1.258E+004 2.018E+004 89.80 1.03 1.417E+005 8.371E+003 6.886E+004 241.98 7.49 1.324E+004 8.454E+003 6.368E+003
Nuclide MDA Report 3/27/2019 9:07:11 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 4.777E+003 1.50E+003 -1.385E+003 2.279E+003 351.92* 37.20 1.498E+003 1.196E+003 6.870E+002 785.91 1.10 7.881E+004 1.470E+004 3.608E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D43-GM.CNF Report Generated On : 3/29/2019 10:49:21 AM Sample Title : B1-010-001-FSFC-D43-GM Sample Description : Rx Bowl concrete 2M Sample Identification : D43 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 1.256E+001 M^2 Sample Taken On : 3/29/2019 8:51:00 AM Acquisition Started : 3/29/2019 8:52:53 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_2M
Peak Analysis Report 3/29/2019 10:49:21 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D43-GM Peak Analysis Performed on: 3/29/2019 10:49:21 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 949- 961 954.17 238.61 0.76 2.98E+001 25.39 4.92E+001 2 1402- 1414 1407.87 352.11 1.08 1.86E+001 20.37 3.24E+001 3 2327- 2338 2332.88 583.47 1.15 1.34E+001 14.85 1.66E+001 4 2431- 2445 2437.03 609.51 1.17 3.99E+001 16.26 9.13E+000 5 2641- 2653 2646.74 661.95 0.38 2.98E+001 16.17 1.33E+001 6 5836- 5857 5847.15 1461.80 1.47 1.74E+002 30.58 1.61E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:49:21 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D43-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.983 1460.81* 10.67 1.40201E+005 2.72350E+004 CS-137 0.998 661.65* 85.12 1.90988E+003 1.06328E+003 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.05933E+003 1.78292E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 4.48706E+003 1.91731E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.90751E+003 2.10882E+003 785.91 1.10
Interference Corrected Activity Report 3/29/2019 10:49:21 AM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:49:21 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.983 1.402007E+005 2.723495E+004 CS-137 0.998 1.909876E+003 1.063284E+003 PB-212 1.000 2.059332E+003 1.782924E+003 BI-214 1.000 4.487058E+003 1.917314E+003 PB-214 1.000 1.907512E+003 2.108819E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 10:49:21 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 583.47 2.2389E-002 110.51 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/29/2019 10:49:21 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D43-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 2.270E+004 2.27E+004 1.402E+005 1.026E+004 CO-60 1173.22 100.00 2.497E+003 2.01E+003 9.398E+002 1.147E+003 1332.49 100.00 2.013E+003 8.115E+002 8.976E+002 CS-134 475.35 1.46 1.252E+005 2.12E+003 -1.374E+004 5.844E+004 563.23 8.38 2.076E+004 -1.033E+004 9.575E+003 569.32 15.43 1.134E+004 3.274E+003 5.233E+003 604.70 97.60 2.502E+003 -1.475E+003 1.179E+003 795.84 85.40 2.124E+003 -8.060E+001 9.655E+002 801.93 8.73 2.420E+004 1.273E+004 1.115E+004 1038.57 1.00 2.186E+005 5.993E+004 9.978E+004 1167.94 1.80 1.323E+005 -1.208E+005 6.054E+004 1365.15 3.04 5.417E+004 1.803E+004 2.344E+004 + CS-137 661.65* 85.12 1.435E+003 1.43E+003 1.910E+003 6.304E+002 EU-152 121.78 28.40 8.705E+003 7.77E+003 -2.332E+003 4.225E+003 344.27 26.50 7.772E+003 8.493E+002 3.694E+003 1407.95 20.70 8.381E+003 2.635E+003 3.644E+003 EU-154 123.07 40.40 5.992E+003 5.25E+003 -4.437E+003 2.907E+003 722.30 20.00 1.051E+004 7.389E+003 4.867E+003 1274.51 34.40 5.250E+003 8.565E+002 2.316E+003 + BI-214 609.31* 46.30 2.199E+003 2.20E+003 4.487E+003 9.473E+002 768.36 5.04 3.883E+004 -2.315E+004 1.782E+004 806.17 1.23 1.689E+005 1.519E+005 7.770E+004 934.06 3.21 5.760E+004 6.017E+004 2.599E+004 1120.29 15.10 1.410E+004 8.139E+003 6.395E+003 1155.19 1.69 1.385E+005 1.358E+005 6.328E+004 1238.11 5.94 4.638E+004 2.344E+004 2.143E+004 1280.96 1.47 1.203E+005 -6.699E+004 5.289E+004 1377.67 4.11 4.500E+004 5.514E+003 1.979E+004 1385.31 0.78 2.198E+005 -2.652E+003 9.557E+004 1401.50 1.39 1.089E+005 -1.226E+005 4.631E+004 1407.98 2.48 6.996E+004 2.200E+004 3.041E+004 1509.19 2.19 6.376E+004 3.265E+003 2.644E+004 1661.28 1.15 9.851E+004 -4.665E+004 3.816E+004 1729.60 3.05 3.824E+004 1.273E+004 1.481E+004 1764.49 15.80 1.131E+004 6.858E+003 4.810E+003 1847.44 2.12 9.001E+004 1.395E+004 3.853E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 7.823E+004 3.39E+003 4.849E+004 3.798E+004 77.11 10.70 4.347E+004 3.446E+004 2.112E+004 87.20 3.70 8.883E+004 -5.577E+004 4.314E+004 89.80 1.03 3.156E+005 3.089E+005 1.534E+005 241.98 7.49 2.768E+004 2.256E+004 1.328E+004
Nuclide MDA Report 3/29/2019 10:49:21 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 1.048E+004 3.39E+003 4.322E+003 4.995E+003 351.92* 37.20 3.386E+003 1.908E+003 1.555E+003 785.91 1.10 1.742E+005 3.154E+004 7.970E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: C:\LACBWR\B1-010-001-FSFC-D50-GM.CNF Report Generated On : 3/29/2019 10:52:10 AM Sample Title : B1-010-001-FSFC-D50-GM Sample Description : Rx Bowl 2M Concrete Sample Identification : D50 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 1.256E+001 M^2 Sample Taken On : 3/28/2019 2:50:00 AM Acquisition Started : 3/28/2019 2:49:47 PM Live Time : 600.0 seconds Real Time : 600.3 seconds Dead Time : 0.05 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_2M
Peak Analysis Report 3/29/2019 10:52:10 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D50-GM Peak Analysis Performed on: 3/29/2019 10:52:09 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 305 300.37 75.03 0.98 2.67E+001 32.27 1.02E+002 2 1400- 1412 1406.35 351.73 0.92 1.83E+001 22.39 4.07E+001 3 2032- 2046 2040.27 510.29 0.36 2.40E+001 20.99 2.80E+001 4 2326- 2338 2331.15 583.04 0.33 2.69E+001 17.93 2.01E+001 5 2429- 2440 2434.90 608.98 0.41 2.10E+001 17.21 2.10E+001 6 3866- 3879 3872.95 968.50 0.30 9.27E+000 12.63 1.07E+001 7 5828- 5852 5840.72 1460.19 1.72 2.15E+002 30.97 6.09E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:52:10 AM Page 3
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Sample
Title:
B1-010-001-FSFC-D50-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.993 1460.81* 10.67 1.73091E+005 2.87493E+004 BI-214 0.999 609.31* 46.30 2.36205E+003 1.95960E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.626 74.81* 6.33 2.22868E+004 2.73161E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.87519E+003 2.31171E+003 785.91 1.10 AC-228 0.999 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60 27.70 964.60 5.20 969.11* 16.60 3.79520E+003 5.17849E+003 1587.90 3.71
Interference Corrected Activity Report 3/29/2019 10:52:10 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 10:52:10 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.993 1.730911E+005 2.874934E+004 BI-214 0.999 2.362048E+003 1.959599E+003 PB-214 0.626 2.020336E+003 2.303475E+003 AC-228 0.999 3.795202E+003 5.178494E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 10:52:09 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 510.29 4.0080E-002 87.30 4 583.04 4.4867E-002 66.60 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/29/2019 10:52:10 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D50-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 1.538E+004 1.54E+004 1.731E+005 6.601E+003 CO-60 1173.22 100.00 2.550E+003 2.13E+003 -1.345E+002 1.173E+003 1332.49 100.00 2.127E+003 1.284E+002 9.545E+002 CS-134 475.35 1.46 1.411E+005 2.24E+003 2.481E+004 6.635E+004 563.23 8.38 2.556E+004 2.625E+004 1.197E+004 569.32 15.43 1.229E+004 -4.148E+003 5.705E+003 604.70 97.60 2.491E+003 2.245E+003 1.173E+003 795.84 85.40 2.235E+003 -2.642E+002 1.021E+003 801.93 8.73 2.059E+004 -4.208E+004 9.351E+003 1038.57 1.00 2.292E+005 4.009E+004 1.051E+005 1167.94 1.80 1.355E+005 -8.338E+004 6.210E+004 1365.15 3.04 6.047E+004 -3.368E+004 2.659E+004 CS-137 661.65 85.12 2.506E+003 2.51E+003 -3.567E+002 1.166E+003 EU-152 121.78 28.40 9.201E+003 7.34E+003 6.078E+003 4.473E+003 344.27 26.50 7.919E+003 -5.340E+003 3.767E+003 1407.95 20.70 7.335E+003 1.682E+003 3.120E+003 EU-154 123.07 40.40 6.461E+003 6.46E+003 2.911E+003 3.141E+003 722.30 20.00 1.096E+004 6.760E+003 5.092E+003 1274.51 34.40 6.535E+003 3.559E+003 2.959E+003 + BI-214 609.31* 46.30 3.000E+003 3.00E+003 2.362E+003 1.348E+003 768.36 5.04 4.285E+004 1.380E+004 1.983E+004 806.17 1.23 1.600E+005 2.054E+004 7.326E+004 934.06 3.21 6.667E+004 -7.132E+003 3.053E+004 1120.29 15.10 1.262E+004 -1.728E+004 5.652E+003 1155.19 1.69 1.512E+005 3.278E+004 6.962E+004 1238.11 5.94 4.185E+004 2.304E+004 1.916E+004 1280.96 1.47 1.464E+005 -1.322E+005 6.597E+004 1377.67 4.11 5.113E+004 2.339E+004 2.285E+004 1385.31 0.78 2.322E+005 6.271E+004 1.017E+005 1401.50 1.39 1.130E+005 2.538E+004 4.837E+004 1407.98 2.48 6.122E+004 1.404E+004 2.604E+004 1509.19 2.19 6.034E+004 -2.440E+004 2.473E+004 1661.28 1.15 9.851E+004 -1.281E+005 3.816E+004 1729.60 3.05 4.780E+004 2.228E+004 1.959E+004 1764.49 15.80 1.292E+004 -3.138E+003 5.617E+003 1847.44 2.12 7.180E+004 3.347E+004 2.943E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81* 6.33 4.426E+004 3.76E+003 2.229E+004 2.100E+004 77.11 10.70 4.593E+004 -1.828E+004 2.234E+004 87.20 3.70 9.640E+004 7.923E+004 4.692E+004 89.80 1.03 3.330E+005 3.035E+005 1.621E+005 241.98 7.49 3.290E+004 2.097E+004 1.589E+004
Nuclide MDA Report 3/29/2019 10:52:10 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 1.109E+004 3.76E+003 9.792E+003 5.302E+003 351.92* 37.20 3.761E+003 1.875E+003 1.742E+003 785.91 1.10 1.842E+005 -1.512E+004 8.466E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-FSFC-D51-GM.CNF Report Generated On : 3/29/2019 12:34:03 PM Sample Title : B1-010-001-FSFC-D51-GM Sample Description : Rx Bowl concrete 2M Sample Identification : D51 Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 1.256E+001 M^2 Sample Taken On : 3/29/2019 9:05:00 AM Acquisition Started : 3/29/2019 9:05:38 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_2M
Peak Analysis Report 3/29/2019 12:34:03 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-FSFC-D51-GM Peak Analysis Performed on: 3/29/2019 12:34:03 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 305 300.83 75.14 0.65 2.75E+001 29.27 8.25E+001 2 948- 962 955.09 238.84 0.59 2.58E+001 29.62 6.72E+001 3 1175- 1188 1180.89 295.33 1.45 2.93E+001 20.02 2.57E+001 4 1403- 1415 1408.84 352.36 1.28 3.01E+001 18.47 2.09E+001 5 2431- 2443 2436.03 609.26 0.59 2.31E+001 16.75 1.59E+001 6 2641- 2653 2646.45 661.88 0.39 3.06E+001 14.62 7.42E+000 7 5834- 5858 5847.13 1461.79 2.24 1.77E+002 26.61 0.00E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 12:34:03 PM Page 3
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Sample
Title:
B1-010-001-FSFC-D51-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.983 1460.81* 10.67 1.42669E+005 2.44727E+004 CS-137 0.999 661.65* 85.12 1.96297E+003 9.67476E+002 PB-212 0.999 74.81* 9.60 1.50802E+004 1.63293E+004 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 1.78441E+003 2.06518E+003 300.09 3.41 BI-214 1.000 609.31* 46.30 2.59635E+003 1.91399E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.998 74.81* 6.33 2.28704E+004 2.47649E+004 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 5.27716E+003 3.70607E+003 351.92* 37.20 3.08412E+003 1.95631E+003 785.91 1.10
Interference Corrected Activity Report 3/29/2019 12:34:03 PM Page 4
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/29/2019 12:34:03 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.983 1.426694E+005 2.447269E+004 CS-137 0.999 1.962968E+003 9.674756E+002 PB-212 0.999 1.955925E+003 2.048942E+003 BI-214 1.000 2.596353E+003 1.913991E+003 PB-214 0.998 3.641397E+003 1.725930E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/29/2019 12:34:03 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
Nuclide MDA Report 3/29/2019 12:34:03 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-FSFC-D51-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 2.181E+003 2.18E+003 1.427E+005 0.000E+000 CO-60 1173.22 100.00 2.360E+003 2.05E+003 -1.124E+003 1.078E+003 1332.49 100.00 2.051E+003 1.031E+002 9.169E+002 CS-134 475.35 1.46 1.330E+005 2.15E+003 7.442E+004 6.229E+004 563.23 8.38 2.096E+004 -1.515E+002 9.674E+003 569.32 15.43 1.248E+004 -1.875E+003 5.801E+003 604.70 97.60 2.153E+003 -3.963E+003 1.004E+003 795.84 85.40 2.287E+003 -4.942E+002 1.047E+003 801.93 8.73 2.087E+004 -1.703E+004 9.487E+003 1038.57 1.00 2.213E+005 5.808E+004 1.011E+005 1167.94 1.80 1.292E+005 -3.176E+004 5.896E+004 1365.15 3.04 6.738E+004 -2.693E+004 3.005E+004 + CS-137 661.65* 85.12 1.183E+003 1.18E+003 1.963E+003 5.046E+002 EU-152 121.78 28.40 8.751E+003 7.09E+003 1.931E+003 4.248E+003 344.27 26.50 7.091E+003 1.982E+003 3.353E+003 1407.95 20.70 8.620E+003 -5.055E+002 3.763E+003 EU-154 123.07 40.40 6.088E+003 6.09E+003 -6.308E+002 2.955E+003 722.30 20.00 9.545E+003 2.448E+003 4.384E+003 1274.51 34.40 6.140E+003 -2.314E+003 2.761E+003 + BI-214 609.31* 46.30 2.845E+003 2.84E+003 2.596E+003 1.270E+003 768.36 5.04 4.008E+004 2.068E+004 1.844E+004 806.17 1.23 1.361E+005 -1.638E+005 6.129E+004 934.06 3.21 6.353E+004 5.403E+003 2.896E+004 1120.29 15.10 1.762E+004 1.786E+004 8.152E+003 1155.19 1.69 1.385E+005 3.309E+004 6.328E+004 1238.11 5.94 4.326E+004 2.546E+004 1.987E+004 1280.96 1.47 1.392E+005 -1.112E+005 6.234E+004 1377.67 4.11 5.017E+004 1.273E+004 2.237E+004 1385.31 0.78 2.198E+005 -1.653E+005 9.557E+004 1401.50 1.39 1.130E+005 -5.552E+004 4.837E+004 1407.98 2.48 7.195E+004 -4.219E+003 3.141E+004 1509.19 2.19 7.289E+004 4.420E+004 3.101E+004 1661.28 1.15 1.367E+005 7.381E+004 5.724E+004 1729.60 3.05 4.174E+004 1.592E+004 1.656E+004 1764.49 15.80 1.466E+004 1.247E+004 6.486E+003 1847.44 2.12 7.586E+004 -4.184E+004 3.146E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81* 6.33 3.963E+004 2.78E+003 2.287E+004 1.869E+004 77.11 10.70 4.272E+004 3.877E+004 2.074E+004 87.20 3.70 9.038E+004 3.702E+004 4.391E+004 89.80 1.03 3.061E+005 -2.162E+005 1.487E+005 241.98 7.49 2.858E+004 1.952E+004 1.373E+004
Nuclide MDA Report 3/29/2019 12:34:03 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21* 19.20 5.482E+003 2.78E+003 5.277E+003 2.497E+003 351.92* 37.20 2.783E+003 3.084E+003 1.253E+003 785.91 1.10 1.861E+005 1.365E+005 8.561E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
- G A M M A S P E C T R U M A N A L Y S I S *****
Filename: C:\LACBWR\B1-010-001-QSFC-D05-GM.CNF Report Generated On : 3/27/2019 9:09:02 PM Sample Title : B1-010-001-QSFC-D05-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D05 QC Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/27/2019 2:35:00 PM Acquisition Started : 3/27/2019 2:35:49 PM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/27/2019 9:09:02 PM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-QSFC-D05-GM Peak Analysis Performed on: 3/27/2019 9:09:01 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 948- 962 953.54 238.45 1.05 7.30E+001 31.20 5.90E+001 2 1401- 1413 1407.35 351.98 1.36 3.38E+001 21.02 2.92E+001 3 2326- 2338 2332.62 583.40 0.71 2.87E+001 19.24 2.43E+001 4 2429- 2442 2435.08 609.02 0.93 3.98E+001 19.24 1.92E+001 5 3636- 3651 3644.24 911.33 1.53 3.40E+001 17.54 1.40E+001 6 5832- 5854 5843.78 1460.95 1.15 2.17E+002 30.95 5.75E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:09:02 PM Page 3
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Sample
Title:
B1-010-001-QSFC-D05-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 1.000 1460.81* 10.67 7.82517E+004 1.28880E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.27008E+003 1.03617E+003 300.09 3.41 BI-214 0.999 609.31* 46.30 2.00440E+003 1.00165E+003 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 1.55587E+003 9.98546E+002 785.91 1.10 AC-228 1.000 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40
Interference Corrected Activity Report 3/27/2019 9:09:02 PM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 1.000 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.60374E+003 1.90591E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/27/2019 9:09:02 PM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 1.000 7.825170E+004 1.288804E+004 PB-212 1.000 2.270080E+003 1.036165E+003 BI-214 0.999 2.004399E+003 1.001647E+003 PB-214 1.000 1.555866E+003 9.985456E+002 AC-228 1.000 3.603738E+003 1.905910E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
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Peak Locate Performed on: 3/27/2019 9:09:01 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 583.40 4.7767E-002 67.14 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/27/2019 9:09:02 PM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-QSFC-D05-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 6.569E+003 6.57E+003 7.825E+004 2.797E+003 CO-60 1173.22 100.00 1.175E+003 7.67E+002 -2.554E+002 5.421E+002 1332.49 100.00 7.672E+002 5.758E+002 3.349E+002 CS-134 475.35 1.46 6.422E+004 1.11E+003 -9.557E+003 3.024E+004 563.23 8.38 1.062E+004 -3.370E+003 4.949E+003 569.32 15.43 5.717E+003 -1.559E+002 2.662E+003 604.70 97.60 1.225E+003 8.390E+002 5.801E+002 795.84 85.40 1.112E+003 5.303E+000 5.129E+002 801.93 8.73 1.123E+004 -1.251E+003 5.194E+003 1038.57 1.00 1.036E+005 -1.845E+004 4.755E+004 1167.94 1.80 6.514E+004 3.262E+004 3.005E+004 1365.15 3.04 2.267E+004 -2.359E+003 9.707E+003 CS-137 661.65 85.12 1.211E+003 1.21E+003 5.305E+002 5.665E+002 EU-152 121.78 28.40 3.976E+003 3.33E+003 -3.315E+003 1.931E+003 344.27 26.50 3.328E+003 -1.866E+003 1.578E+003 1407.95 20.70 3.523E+003 -1.878E+003 1.517E+003 EU-154 123.07 40.40 2.827E+003 2.83E+003 1.519E+003 1.373E+003 722.30 20.00 4.861E+003 2.024E+003 2.257E+003 1274.51 34.40 2.966E+003 -1.405E+003 1.345E+003 + BI-214 609.31* 46.30 1.338E+003 1.34E+003 2.004E+003 6.010E+002 768.36 5.04 2.031E+004 9.378E+003 9.441E+003 806.17 1.23 8.141E+004 5.676E+004 3.770E+004 934.06 3.21 3.081E+004 2.006E+004 1.415E+004 1120.29 15.10 7.221E+003 5.945E+003 3.316E+003 1155.19 1.69 6.121E+004 -3.859E+004 2.794E+004 1238.11 5.94 2.240E+004 2.669E+003 1.041E+004 1280.96 1.47 6.551E+004 -2.783E+003 2.951E+004 1377.67 4.11 1.912E+004 7.818E+003 8.345E+003 1385.31 0.78 1.011E+005 -1.022E+005 4.414E+004 1401.50 1.39 5.563E+004 -3.937E+003 2.418E+004 1407.98 2.48 2.941E+004 -1.567E+004 1.266E+004 1509.19 2.19 3.258E+004 6.939E+002 1.386E+004 1661.28 1.15 5.166E+004 3.052E+003 2.087E+004 1729.60 3.05 2.005E+004 -2.428E+003 8.100E+003 1764.49 15.80 5.768E+003 4.175E+003 2.508E+003 1847.44 2.12 3.870E+004 2.347E+004 1.646E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.820E+004 1.45E+003 4.252E+004 1.858E+004 77.11 10.70 2.075E+004 1.008E+004 1.009E+004 87.20 3.70 4.325E+004 -4.759E+003 2.104E+004 89.80 1.03 1.497E+005 -2.951E+004 7.284E+004 241.98 7.49 1.470E+004 1.780E+004 7.096E+003
Nuclide MDA Report 3/27/2019 9:09:02 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 5.293E+003 1.45E+003 2.322E+003 2.537E+003 351.92* 37.20 1.450E+003 1.556E+003 6.625E+002 785.91 1.10 8.403E+004 6.127E+004 3.870E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: 3844 Report Generated On : 3/28/2019 10:29:15 AM Sample Title : B1-010-001-QSFC-D16-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D16 QC Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 10:18:00 AM Acquisition Started : 3/28/2019 10:19:14 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.03 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 10:29:15 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-QSFC-D16-GM Peak Analysis Performed on: 3/28/2019 10:29:15 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 962 953.50 238.45 0.85 7.85E+001 36.37 8.05E+001 2 1399- 1413 1406.11 351.67 0.86 5.03E+001 19.83 1.67E+001 3 2036- 2048 2042.22 510.78 0.50 2.19E+001 18.29 2.31E+001 4 2427- 2440 2433.85 608.72 1.38 4.77E+001 15.81 5.31E+000 5 2639- 2650 2644.11 661.29 0.80 1.77E+001 14.30 1.33E+001 6 3634- 3649 3640.98 910.52 0.39 3.92E+001 16.55 9.78E+000 7 5825- 5849 5837.80 1459.46 2.00 2.40E+002 31.78 3.08E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 10:29:15 AM Page 3
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Sample
Title:
B1-010-001-QSFC-D16-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.968 1460.81* 10.67 8.63537E+004 1.34818E+004 CS-137 0.998 661.65* 85.12 5.08538E+002 4.14857E+002 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.44215E+003 1.19668E+003 300.09 3.41 BI-214 0.997 609.31* 46.30 2.39916E+003 8.52609E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29 15.10 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 1.000 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21 19.20 351.92* 37.20 2.31231E+003 9.84011E+002 785.91 1.10 AC-228 0.994 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20
Interference Corrected Activity Report 3/28/2019 10:29:15 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.994 338.32 11.40 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 4.15736E+003 1.81886E+003 964.60 5.20 969.11 16.60 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.968 8.635370E+004 1.348176E+004 CS-137 0.998 5.085379E+002 4.148573E+002 PB-212 1.000 2.442154E+003 1.196680E+003 BI-214 0.997 2.399160E+003 8.526093E+002 PB-214 1.000 2.312315E+003 9.840105E+002 AC-228 0.994 4.157360E+003 1.818857E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 10:29:15 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 3 510.78 3.6574E-002 83.34 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/28/2019 10:29:15 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-QSFC-D16-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 5.180E+003 5.18E+003 8.635E+004 2.103E+003 CO-60 1173.22 100.00 1.068E+003 9.51E+002 5.177E+002 4.887E+002 1332.49 100.00 9.512E+002 9.357E+002 4.269E+002 CS-134 475.35 1.46 5.652E+004 1.14E+003 2.009E+004 2.638E+004 563.23 8.38 1.114E+004 8.224E+003 5.213E+003 569.32 15.43 5.630E+003 -1.603E+003 2.618E+003 604.70 97.60 1.137E+003 8.294E+002 5.363E+002 795.84 85.40 1.174E+003 -7.137E+002 5.440E+002 801.93 8.73 1.123E+004 -1.225E+004 5.194E+003 1038.57 1.00 9.154E+004 1.035E+004 4.150E+004 1167.94 1.80 6.192E+004 -3.238E+004 2.844E+004 1365.15 3.04 2.568E+004 1.109E+004 1.121E+004 + CS-137 661.65* 85.12 6.233E+002 6.23E+002 5.085E+002 2.728E+002 EU-152 121.78 28.40 4.032E+003 3.14E+003 -3.481E+003 1.958E+003 344.27 26.50 3.141E+003 -3.097E+003 1.484E+003 1407.95 20.70 3.855E+003 -1.407E+003 1.683E+003 EU-154 123.07 40.40 2.866E+003 2.87E+003 -3.153E+002 1.392E+003 722.30 20.00 4.781E+003 0.000E+000 2.217E+003 1274.51 34.40 3.049E+003 2.662E+003 1.386E+003 + BI-214 609.31* 46.30 7.726E+002 7.73E+002 2.399E+003 3.182E+002 768.36 5.04 1.810E+004 -1.901E+004 8.336E+003 806.17 1.23 8.070E+004 2.536E+004 3.734E+004 934.06 3.21 3.048E+004 -1.391E+004 1.398E+004 1120.29 15.10 8.021E+003 5.109E+003 3.716E+003 1155.19 1.69 6.270E+004 9.415E+003 2.868E+004 1238.11 5.94 1.762E+004 -1.061E+004 8.020E+003 1280.96 1.47 6.656E+004 3.297E+004 3.004E+004 1377.67 4.11 2.061E+004 -3.799E+003 9.093E+003 1385.31 0.78 9.242E+004 2.819E+004 3.979E+004 1401.50 1.39 5.399E+004 -9.586E+002 2.336E+004 1407.98 2.48 3.218E+004 -1.174E+004 1.405E+004 1509.19 2.19 2.993E+004 -1.212E+004 1.253E+004 1661.28 1.15 4.802E+004 1.831E+004 1.905E+004 1729.60 3.05 1.863E+004 7.107E+003 7.394E+003 1764.49 15.80 5.422E+003 1.638E+003 2.334E+003 1847.44 2.12 4.423E+004 -2.450E+004 1.923E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.658E+004 1.17E+003 3.023E+004 1.777E+004 77.11 10.70 2.011E+004 3.848E+003 9.775E+003 87.20 3.70 4.348E+004 8.908E+003 2.116E+004 89.80 1.03 1.516E+005 -5.670E+003 7.381E+004 241.98 7.49 1.504E+004 1.816E+004 7.267E+003
Nuclide MDA Report 3/28/2019 10:29:15 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21 19.20 4.885E+003 1.17E+003 3.268E+003 2.333E+003 351.92* 37.20 1.173E+003 2.312E+003 5.242E+002 785.91 1.10 8.732E+004 2.146E+004 4.034E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
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Filename: 3844 Report Generated On : 3/28/2019 11:22:47 AM Sample Title : B1-010-001-QSFC-D18-GM Sample Description : Rx Bowl 3M Concrete Sample Identification : D18 QC Sample Type : Gamma Direct Sample Geometry : Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 85 - 8000 Peak Area Range (in channels) : 85 - 8000 Identification Energy Tolerance : 3.000 keV Sample Size : 2.827E+001 M^2 Sample Taken On : 3/28/2019 11:12:00 AM Acquisition Started : 3/28/2019 11:12:47 AM Live Time : 600.0 seconds Real Time : 600.2 seconds Dead Time : 0.04 % Energy Calibration Used Done On : 10/24/2017 Efficiency Calibration Used Done On : 3/26/2019 Efficiency ID : RxBOWL_CON_3M
Peak Analysis Report 3/28/2019 11:22:47 AM Page 2
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Detector Name: 3844 Sample
Title:
B1-010-001-QSFC-D18-GM Peak Analysis Performed on: 3/28/2019 11:22:47 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8000 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 946- 962 954.03 238.58 1.17 8.91E+001 36.40 7.69E+001 M 2 1174- 1207 1179.08 294.88 0.67 1.64E+001 11.88 2.75E+001 m 3 1174- 1207 1201.25 300.42 0.67 1.79E+001 10.87 1.50E+001 4 1399- 1411 1405.77 351.59 0.84 3.25E+001 19.77 2.45E+001 5 2323- 2336 2329.15 582.53 0.80 2.80E+001 18.64 2.10E+001 6 2425- 2439 2433.23 608.56 1.53 5.06E+001 17.64 9.41E+000 7 3635- 3648 3641.58 910.67 0.99 3.10E+001 14.19 7.00E+000 8 3866- 3879 3872.52 968.40 0.34 1.89E+001 11.45 5.05E+000 9 4468- 4481 4474.03 1118.73 0.67 1.90E+001 8.72 0.00E+000 10 5826- 5849 5838.16 1459.55 1.48 2.28E+002 30.98 2.99E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 11:22:48 AM Page 3
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Sample
Title:
B1-010-001-QSFC-D18-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB
.................... IDENTIFIED NUCLIDES ....................
Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty K-40 0.972 1460.81* 10.67 8.20698E+004 1.30518E+004 PB-212 1.000 74.81 9.60 77.11 17.50 87.20 6.30 89.80 1.75 115.19 0.60 238.63* 44.60 2.77141E+003 1.21627E+003 300.09* 3.41 8.23659E+003 5.17734E+003 BI-214 0.990 609.31* 46.30 2.54462E+003 9.45328E+002 768.36 5.04 806.17 1.23 934.06 3.21 1120.29* 15.10 4.12731E+003 1.92231E+003 1155.19 1.69 1238.11 5.94 1280.96 1.47 1377.67 4.11 1385.31 0.78 1401.50 1.39 1407.98 2.48 1509.19 2.19 1661.28 1.15 1729.60 3.05 1764.49 15.80 1847.44 2.12 2118.54 1.21 PB-214 0.999 74.81 6.33 77.11 10.70 87.20 3.70 89.80 1.03 241.98 7.49 295.21* 19.20 1.33119E+003 9.85785E+002 351.92* 37.20 1.49219E+003 9.39593E+002 785.91 1.10 AC-228 0.994 89.95 2.10 93.35 3.50 129.08 2.80 209.28 4.40 270.23 3.60 327.64 3.20 338.32 11.40
Interference Corrected Activity Report 3/28/2019 11:22:48 AM Page 4 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M^2 ) Uncertainty AC-228 0.994 409.51 2.13 463.00 4.40 794.70 4.60 911.60* 27.70 3.28595E+003 1.55137E+003 964.60 5.20 969.11* 16.60 3.46665E+003 2.11981E+003 1587.90 3.71
* = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 3.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma
Interference Corrected Activity Report 3/28/2019 11:22:48 AM Page 5
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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M^2 ) Uncertainty K-40 0.972 8.206984E+004 1.305183E+004 PB-212 1.000 3.057254E+003 1.184041E+003 BI-214 0.990 2.852834E+003 8.483022E+002 PB-214 0.999 1.415549E+003 6.801367E+002 AC-228 0.994 3.348978E+003 1.251922E+003
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis
@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma
********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 3/28/2019 11:22:47 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8000 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 5 582.53 4.6667E-002 66.56 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma
Nuclide MDA Report 3/28/2019 11:22:48 AM Page 6
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Detector Name: 3844 Sample Geometry: Sample
Title:
B1-010-001-QSFC-D18-GM Nuclide Library Used: C:\GENIE2K\CAMFILES\LACBWR.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ K-40 1460.81* 10.67 5.076E+003 5.08E+003 8.207E+004 2.051E+003 CO-60 1173.22 100.00 1.175E+003 9.67E+002 -1.199E+003 5.421E+002 1332.49 100.00 9.675E+002 4.229E+002 4.351E+002 CS-134 475.35 1.46 6.032E+004 1.12E+003 7.508E+003 2.828E+004 563.23 8.38 9.641E+003 -7.604E+003 4.461E+003 569.32 15.43 5.497E+003 -1.154E+002 2.552E+003 604.70 97.60 1.182E+003 1.112E+003 5.586E+002 795.84 85.40 1.122E+003 6.965E+001 5.182E+002 801.93 8.73 9.452E+003 -2.673E+003 4.303E+003 1038.57 1.00 8.190E+004 -1.026E+005 3.668E+004 1167.94 1.80 6.576E+004 4.906E+004 3.036E+004 1365.15 3.04 2.894E+004 -1.180E+004 1.284E+004 CS-137 661.65 85.12 1.154E+003 1.15E+003 3.151E+002 5.383E+002 EU-152 121.78 28.40 3.997E+003 3.07E+003 2.133E+002 1.941E+003 344.27 26.50 3.066E+003 -5.048E+003 1.447E+003 1407.95 20.70 3.958E+003 -4.553E+003 1.735E+003 EU-154 123.07 40.40 2.803E+003 2.80E+003 -6.766E+002 1.361E+003 722.30 20.00 4.617E+003 2.214E+003 2.134E+003 1274.51 34.40 3.089E+003 -2.996E+003 1.406E+003 + BI-214 609.31* 46.30 9.993E+002 5.88E+002 2.545E+003 4.316E+002 768.36 5.04 2.047E+004 -1.323E+003 9.521E+003 806.17 1.23 7.393E+004 3.450E+004 3.395E+004 934.06 3.21 2.840E+004 -1.690E+004 1.295E+004 1120.29* 15.10 5.878E+002 4.127E+003 0.000E+000 1155.19 1.69 5.890E+004 -9.319E+003 2.678E+004 1238.11 5.94 1.894E+004 6.118E+003 8.680E+003 1280.96 1.47 7.704E+004 2.278E+004 3.528E+004 1377.67 4.11 2.200E+004 -6.155E+003 9.785E+003 1385.31 0.78 1.187E+005 6.812E+004 5.293E+004 1401.50 1.39 5.876E+004 -1.370E+004 2.575E+004 1407.98 2.48 3.304E+004 -3.800E+004 1.448E+004 1509.19 2.19 2.697E+004 1.257E+004 1.105E+004 1661.28 1.15 5.166E+004 -1.648E+004 2.087E+004 1729.60 3.05 2.134E+004 -4.619E+003 8.749E+003 1764.49 15.80 5.933E+003 1.874E+003 2.590E+003 1847.44 2.12 3.204E+004 1.494E+004 1.313E+004 > 2118.54 1.21 0.000E+000 0.000E+000 0.000E+000 + PB-214 74.81 6.33 3.798E+004 1.35E+003 3.788E+004 1.847E+004 77.11 10.70 2.105E+004 2.457E+004 1.024E+004 87.20 3.70 4.301E+004 -2.303E+004 2.093E+004 89.80 1.03 1.527E+005 7.462E+003 7.436E+004 241.98 7.49 1.507E+004 1.383E+004 7.280E+003
Nuclide MDA Report 3/28/2019 11:22:48 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 ) (pCi/M^2 )
+ PB-214 295.21* 19.20 2.198E+003 1.35E+003 1.331E+003 9.892E+002 351.92* 37.20 1.346E+003 1.492E+003 6.108E+002 785.91 1.10 8.971E+004 3.453E+004 4.154E+004
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated
@ = Half-life too short to be able to perform the decay correction
FSS RELEASE RECORD - REVISION 1
~
REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 ATTACHMENT 7 SAMPLE ANALYTICAL REPORTS 403
5/20/2019 2:43:21PM Page I of6 Analysis Report for B1-010-001-CIGS-Bl01-SB 81-010-001 (45 GEO-PROBE) GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-Bl01-SB Sample Description : 81-010-001 (45 GEO-PROBE) Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 9.479E+02 grams Facility : Dairyland_NPP Sample Taken On : 5/16/2019 3:25:00PM Acquisition Started : 5/20/2019 2:13:02PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.4 seconds Dead Time : 0.30% Peak locate Threshold : 3.00 Peak locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6339 PEAK ANALYSIS REPORT Peak Analysis Performed on : 5/20/2019 2:43:12PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
5/20/2019 2:43:21PM Page 2 of6 Analysis Report for B1-010-001-CIGS-BL01 -SB 81-010-001 (45 GEO-PROBE) Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 72 473 - 485 477.92 l .69E+02 34 . 54 3.00E+02 2.12 F 2 295.34 586 - 595 591.13 4.84E+Ol 22.31 l .64E+02 1. 71 F 3 583.41 115 9 - 1172 1167 . 16 5.28E+Ol 17 . 33 4.93E+Ol 2 . 10 F 4 609.58 1214 - 1223 1219.48 6.0lE+Ol 18 . 46 5.05E+Ol 1. 84 F 5 911.47 1817 - 1829 1823.17 2 . 98E+Ol 14 . 11 3.89E+Ol 2.13 F 6 1461. 09 2914 - 2931 2922 . 28 2 . 84E+02 33.81 O.OOE+OO 3 . 02 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 5/20/2019 2:43:12PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238.72 l.69E+02 34 . 54 l .69E+02 3.45E+Ol F 2 295 . 34 4.84E+Ol 22 . 31 4.84E+Ol 2.23E+Ol F 3 583 . 41 5.28E+Ol 17.33 5.28E+Ol 1.73E+Ol F 4 609.58 6.0lE+Ol 18.46 2.06E+Ol 1.21E+Ol 3 . 95E+Ol 2.21E+Ol F 5 911.47 2.98E+Ol 14 .11 2.98E+Ol l . 41E+Ol F 6 14 61. 09 2.84E+02 33.81 2.82E+Ol 8 . 57E+OO 2 . 56E+02 3.49E+Ol
=
M First peak in a multiplet region m = Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
5/20/2019 2:43:21PM Page 3 of 6 Analysis Report for 81-010-001 -CIGS-BL01-SB 81-010-001 (45 GEO-PROBE) NUCLIDE IDENTIFICATION REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K-40 0 . 98 1460 . 75
- 10 . 67 5 . 88E+00 8 . 66E- 01 PB-212 0 . 55 77 . 11 17 . 50 238 . 63
- 44 . 60 1 . 83E- 01 3 . 88E-02 BI-214 0 . 34 609 . 31
- 46 . 30 9 . 60E- 02 5 . 39E-02 1120. 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1 4 07.98 2 . 48 1509 . 19 2.19 1764 . 49 15 . 80
* = Energy line found In the spectrum.
- = Manually added nuclide.
? = ManuaUy edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams)
K- 40 0 . 982 5 . 88E+00 8 . 66E- 01 PB- 212 0 . 559 l . 83E - 01 3 . 88E-02 BI - 214 0 . 344 9 . 60E- 02 5 . 39E - 02
5/20/2019 2:43:21 PM Pagc4 of6 Analysis Report for B1-010-001-CIGS-BL01-SB B1-010-001 (45 GEO-PROBE)
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
5/20/2019 2:43:21 PM Page 5 of6 Analysis Report for B1-010-001-CIGS-BL01-SB 81 -010-001 (45 GEO-PROBE) UNIDENTIFIED PEAKS Peak Locate Perfonned on : 5/20/2019 2:43:12PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS('1/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 295 . 34 2 . 6900 4E-02 23 . 04 Tol. PB- 214 F 3 583 . 41 2 . 93505E- 02 16 . 40 F 5 911. 47 l . 65290E - 02 23 . 71 Tol. AC-228 PA-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCVgrams) (pCUgrams) (pCilgrams) (keV) + K-40 1 4 60.75
- 10 . 67 5 . 88£+00 5 . 78 E-01 5 . 78E - 0 1
+ AR- 4 1 1293 . 64 99 . 16 6.88£+13 3 . 16£+14 3 . 16E+1 4 + CO- 60 1173.22 100 . 00 7 . 78E-02 6 . 40£- 02 9 . 00 E-02 1332. 4 9 100 . 00 1 . 22£-02 6. 4 0E- 02 + KR-85 513 . 99 0 . 43 l . 06E+0l 1. 24E+0l 1. 24£+01 + Y- 88 898 . 04 93 . 70 l . 97E- 02 5 . 3SE- 02 6 . 52E - 02 1836 . 06 99 . 20 - 6 . 14E- 03 5 . 35E-02 + NB- 94 702 . 63 100 . 00 -4 . 48E-02 4 . 65£-02 4. 65E- 02 871 .1 0 100 . 00 -5 . 64E- 02 5 . 64E-02 + I - 131 28 4. 30 6 . 06 4 . 8 1E- 02 7 . 29E-02 9 . 80£-0 1 364 . 48 81. 20 8 . 90E- 03 7.29E- 02 636 . 97 7 . 27 - 3 . 06E - 0l 8.79E- 01 + CS - 134 604 . 70 97 . 60 1. 0 4E-01 6 . 59E-02 6.59E- 02
5/20/2019 2:43:21PM Page 6 of 6 Analysis Report for B1-010-001-CIGS-BL01-SB B1-010-001 (45 GEO-PROBE) Nuclide Energy Yield(3/4) Activity NuclldeMDA LineMDA Name (pCilgrams) (pCl/grams) (pCUgrams) (keV) CS -1 34 795 . 84 85 . 40 2 . 31E- 02 6 . 59E- 02 7.25E-02 + CS-137 661 . 65 85 . 12 4 . 70E - 02 6 . 71E-02 6.71E - 02 + CE-1 44 80 . 12 l. 36 - 6 . 71E - 01 3 . 52E - 01 4 . 26E+OO 133. 51 11. 09 1. llE - 01 3 . 52E-01 + EU-152 121 . 78 28 . 40 -l. 7 1 E- 02 1 . 33E - 01 1 . 33E - 01 344 . 28 26 . 60 -3 . 96E-01 l . 76E-01 1408 . 00 20 . 7 4 1 . 14E- 01 2.92E-Ol + EU- 154 123 . 07 40 . 40 -4.31E- 02 9 . 35E- 02 9.35E- 02 723 . 30 19 . 70 3 . 86E- 02 2 . 89E- 01 1274 . 51 35 . 50 - 2 . 77E- 01 1. 93E-Ol + EU- 155 86 . 54 32 . 80 1 . 83E- 02 1 . 51E- Ol 1. SlE- 01 105 . 31 2 1. 80 3 . 30E- 02 l . 78E- 01 + BI- 214 609 . 31
- 46 . 30 9.60E- 02 9 . 24E - 02 9 . 24E-02 1120 . 29 15 . 10 -5 . 42E- 02 4 . 8 4E- 01 1238 .11 5 . 94 3 .llE- 01 1. 51E+OO 1377 . 67 4 . 11 -1.1 8E-0 1 l . 27E+OO 1407 . 98 2 . 48 9 . 49E - 01 2 . 44 E+OO 1509 . 19 2 . 19 1. 4 1E+ OO 2 . 59E+OO 1764 . 49 1 5 .8 0 2.36E- Ol 3 . 54E- Ol
+ PB- 214 77 . 11 1 0 . 70 4 . 92E- 01 1.33E-01 5 . 92E-01 295 . 21 19 . 20 3 . 66E- 01 2 . S l E-0 1 351 . 92 37 . 20 2 . 26E- 01 l . 33E-01 + PA-228 89 . 95 22 . 00 2 . 18E+OO 2 . 65E+OO 4 . 39E+ OO 93 . 35 35 . 00 2 . 87E+OO 2 . 65E+OO 105 . 00 16 . 30 - 2 . 56E+OO 4 . 7 4E+OO 129 . 22 2 . 97 8 . 73E- 01 2 . 56E+O l 338 . 32 5 . 30 1 . 29E+ Ol l . 7 4E+Ol 463 . 00 1 3 . 80 3 . 13E+OO 6 . 5 1 E+OO 911 . 23 1 6 . 70 1. 09E+Ol 9 . 13E+OO + AM-241 59 . 54 36 . 30 1. 07E - Ol 2 . 76E - 01 2 . 76E - Ol + CM- 243 103 . 76 23 . 00 - 5 . 93E- 02 l . 70E - 01 l . 70E- 01 228 . 18 1 0 . 60 1. 2 4E- 01 3 . 79E- 01 277 . 60 1 4. 00 - 1 . 17E-01 2 . 85E-01
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
5/20/2019 3:17:28PM Page 1 of7 __.Apex-Gamma Analysis Report for B1-010-001-CIGS-BL02-SB B1-010-001 (45 GEO PROBE) GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BL02-SB Sample Description : B1-010-001 (45 GEO PROBE) Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 9.358E+02 grams Facility : Dairyland_NPP Sample Taken On : 5/17/2019 8:50:00AM Acquisition Started : 5/20/2019 2:47:09PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.6 seconds Dead Time : 0.31 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6340 PEAK ANALYSIS REPORT Peak Analysis Performed on : 5/20/2019 3:17:18PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
5/20/2019 3:17:28PM Page 2 of7 Analysis Report for 81-010-001-CIGS-BL02-SB 8 1-010-001 (45 GEO PROBE) Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 202 . 75 401 - 409 405 . 99 3 . 26E+Ol 20 . 25 l . 98E+02 1.20 F 2 238 . 79 456 - 485 478 . 07 l. 75E +02 37 . 19 7 . 72E+02 2 . 46 F 3 351 . 98 696 - 71 1 704 . 40 l. 12E+02 27 . 60 1. 56E+02 2 . 83 F 4 582 . 67 1160 - 1173 1165 . 69 6 . 84E+Ol 19 . 47 5 . 60E+Ol 2 . 36 F 5 609 . 43 1212 - 1228 1219 . 20 8 . 51E+Ol 20 . 72 4 . 70E+Ol 2 . 49 F 6 911. 40 1818 - 1829 1823 . 04 3.03E+Ol 14 . 50 4 . 25E+Ol 2 . 16 F 7 969 . 35 1934 - 1945 1938 . 93 2 . lOE+Ol 11. 65 3 . 98E+Ol 1.35 F 8 14 61. 05 2912 - 2932 2922 . 21 2 . 94E+02 34 . 51 5 . 07E+OO 3 . 14 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 5/20/2019 3:17:18PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 202 . 75 3 . 26E+Ol 20 . 25 3 . 26E+Ol 2 . 03E +Ol F 2 238.79 1. 75E+02 37. 19 l . 75E+02 3 . 72E+Ol F 3 351. 98 l . 12E+02 27 . 60 4 . 18E+O l 1. 86E+Ol 6 . 97E+Ol 3 . 33 E+Ol F 4 582 . 67 6 . 84E+Ol 19 . 47 6 . 84E+Ol l . 95E+Ol F 5 609 .4 3 8 . Sl E+O l 20 . 72 2 . 06E+O l l.21E+Ol 6 . 45E+Ol 2 . 40E+Ol F 6 911 . 40 3 . 03E+Ol 1 4. 50 3. 03E+Ol 1. 45E+Ol F 7 969 . 35 2 . lOE+O l 11. 65 2 . lOE+Ol l. 17E+Ol F 8 1461.05 2.94E+02 34 . 51 2 . 82E+Ol 8 . 57E+OO 2 . 66E+02 3 . 56E+Ol
=
M First peak in a multiplet region
=
m Other peak In a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
5/20/2019 3:17:28PM Page 3 of7 Analysis Report for B1-010-001-CIGS-BL02-SB 81-010-001 (45 GEO PROBE) NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nucllde Id Energy Yield(3/4) Activity Activity Name Confidence {keV) (pCVgrams) Uncertainty K-40 0 . 98 1460.75
- 10.67 6.20E+00 8.97E-01 PB- 212 0 . 55 77 .11 17.50 238.63
- 44.60 1.93E-01 4.22E-02 BI-214 0 . 34 609.31
- 46.30 1 . 59E-01 5.97E-02 1120.29 15.10 1238 .11 5.94 1377. 67 4 . 11 1407.98 2 . 48 1509.19 2.19 1 7 64 . 49 15.80
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence Index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams)
K-40 0.986 6 . 20E+00 8.97E-01 PB-212 0.557 1. 93E-01 4.22E-02 BI-214 0.348 1. 59E- 0 1 5 . 97E-02
5/20/2019 3:17:28PM Page 4 of7 Analysis Report for B1-010-001 -CIGS-BL02-SB B1-010-001 (45 GEO PROBE)
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
5/20/2019 3:17:28PM Page 5 of7 Analysis Report for B1-010-001-CIGS-BL02-SB B1-010-001 (45 GEO PROBE) UNIDENTIFIED PEAKS Peak Locate Performed on : 5/20/2019 3:17:18PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 202 . 75 1 . 81195£-02 31. 05 F 3 351 . 98 3.87362£-02 23 . 87 Tol. PB- 214 F 4 582 . 67 3.80042£- 02 14.23 F 6 911.40 1.68362E- 02 23.93 Tol. AC- 228 PA- 228 F 7 969 . 35 1 .1 6638E - 02 27 . 75 Tol. AC - 228 M = First peak in a multiplet reg ion m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nucl/deMDA LineMDA Name (pCilgrams) (pCl/grams) (pCUgrams) (keV) + K- 40 1460.75
- 10 . 67 6 . 20E+ 00 6 . 34E-01 6 . 34E-0 1
+ AR-41 1293 . 64 99 . 16 - 1. 0SE+l0 5 . 4 3E+ll 5 . 43E+ ll + CO-60 1173 . 22 100 . 00 3 . 41E-02 7 . 88E- 02 8.21E- 02 1332 . 49 100 . 00 8 . 33E -0 2 7 . 8 8E- 02 + KR- 85 513 . 99 0 . 43 9 . 8 4E+00 1 . 27E+0l 1. 27E+ 0 l + Y- 88 898 . 04 93.70 1 . 44E- 02 5 . 39E-02 6.79E-02 1836 . 06 99.20 -3.25E- 02 5.39E- 02 + NB- 94 702 . 63 100.00 - 4. 03E- 02 5 . 26E-02 5.26E- 02 871.10 100.00 - 1 . 55E -0 2 6.0lE- 02 + I - 131 284 . 30 6.06 - 5 . 39E- 01 6 . 84E-02 8 . 73E-01
5/20/2019 3:17:28PM Page6 of 7 Analysis Report for B1-010-001-CIGS-BL02-SB B1-010-001 (45 GEO PROBE) Nuclide Energy Yield(3/4) Activity Nucllde MDA L/neMDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV) I-131 364 . 48 81.20 1. 71E- 02 6 . 84E-02 6 . 84E-02 636 . 97 7.27 3 . 4 9E- 01 9 . 47E-01 + CS-134 604 . 70 97 . 60 - 1 . 05E-02 6 . 82E-02 6 . 96E- 02 795 . 84 85 . 40 5 . 04E-02 6 . 82E-02 + CS- 137 661. 65 85 . 12 3 . 29E-02 7 . 0lE - 02 7 . 0lE-02 + CE- 144 80 . 12 1. 36 1 . lOE+OO 3.47E-01 4 . 46E+OO 133 . 51 1 1. 09 2 . 68E - 01 3.47E-01 + EU - 152 121 . 78 28 . 40 - 9 . 14E- 02 1 . 38E- 01 l .38E- 01 344.28 26 . 60 3 . 83E- 02 1.80E- 01 1408 . 00 20 . 74 3 . 16E-02 2.61E-Ol + EU- 154 123 . 07 40 . 40 -1 . 30E-02 9. 78E- 02 9 . 78E-02 723 . 30 19 . 70 7.94E- 02 2 . 95E-01 1274 . 51 35 . 50 3.58E- 02 2 . 00E-01 + EU- 155 86 . 5 4 32.80 2 . 70E-02 1 . 58E- Ol 1 . 58E- 01 105 . 31 21. 80 1 . 60E- 03 l . 84E- 01 + BI - 2 1 4 609 . 3 1
- 46 . 30 1 . 59E-0 1 9 . 90E - 02 9 . 90E-02 1120 . 29 15 . 10 3 . 44E - 01 5 . 29E-01 1238 . 11 5 . 94 3 . 60E- 01 1 . 60E+OO 1377.67 4 . 11 1. 1 5E+OO 1. 35E+OO 1407 . 98 2 . 48 2 . 64E- 01 2 . 18E+OO 1509 . 19 2 . 19 1 . 32E+OO 2.49E+OO 1764 . 49 15 . 80 2 . 58E-01 3 . 71E-01
+ PB- 214 77 . 11 10 . 70 6 . SOE- 01 l . 45E- 01 5 . 95E-01 295 . 21 1 9 . 20 3 . 54E- Ol 2 . 47E-01 351 . 92 37 . 20 2 . 74E-Ol l . 45E- 01 + PA-228 89 . 95 22.00 2.52E+OO 1. 59E+ OO 2 . 71E+OO 93 . 35 35 . 00 1. 03E+OO 1. 59E+00 105 . 00 16.30 5 . 93E - 01 2 . 90E+OO 129 . 22 2.97 - 3 . 82E - Ol 1 . 55E+Ol 338 . 32 5.30 1. 25E+Ol 1. 06E+Ol 463 . 00 13 . 80 - l . 05E+OO 3 . 88E+OO 911 . 23 16 . 70 3 . 02E+OO 5.47E+OO + AM- 241 59 . 54 36 . 30 2 . 94E-03 2 . 76E-O l 2 . 76E-0 1 + CM- 243 103 . 76 23 . 00 - 8 . 85E- 02 1.75E- Ol 1 . 75E- 01 228 . 18 10 . 60 4 . 26E- 02 3 . 84E-Ol 277 . 60 1 4 . 00 - 5 .3 0E- 02 3 . 06E-01
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
5/20/2019 3:17:28PM Page 7 of7 Analysis Report for B1-010-001*CIGS-Bl02-SB B1-010-001 (45 GEO PROBE)
6/10/2019 10:49:41 AM Page I of6 ~~~~pex-Gamma Analysis Report for 81-010-001-CIGS-BA01-SB 81-010-001 8 GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001-CIGS-BA01-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 7.613E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/5/2019 1:08:00PM Acquisition Started : 6/10/2019 9:52:54AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1806. 1 seconds Dead Time : 0.34 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6765 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/10/2019 10:49:32AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/10/2019 10:49:4 1AM Page 2 of6 Analysis Report for B1-01~001-CIGS-BA01-SB 81-010-001 B Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238.68 474 - 485 477 . 83 1 . 88E+02 32 . 96 l . 94E+02 2 . 07 F 2 269 . 89 537 - 545 540 . 23 2.72E+Ol 17 . 61 l . 37E+02 1.27 F 3 295 . 22 587 - 596 590 . 90 5.79E+Ol 22 . 12 l . 47E+02 1. 71 F 4 351 . 88 701 - 710 70 4.18 8.89E+Ol 22 .4 2 8 . 80E+Ol 1. 61 F 5 58 3 . 07 1161 - 117 4 1166. 48 5.89E+Ol 18 . 65 6 . 09E+Ol 2 . 25 F 6 609 . 00 1213 - 1225 1218 .34 7 . 30E+Ol 19 . 97 7.42E+Ol 1. 64 F 7 1460.67 2914 - 2928 292 1.46 2.50E+02 31 . 99 7 .50E+OO 2 .4 1 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/10/2019 10:49:32AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 68 1.88E+02 32 .9 6 1. 88E+02 3.30E+Ol F 2 269.89 2 . 72E+Ol 17.61 2 . 72E+Ol l . 76E+Ol F 3 295 . 22 5 . 79E+Ol 22 . 12 5.79E+Ol 2 . 21E+Ol F 4 351 . 88 8 . 89E+Ol 22 .42 4.18E+Ol 1. 86E+O l 4.71E+Ol 2 . 91E+Ol F 5 583 . 07 5 . 89E+Ol 18.65 5 . 89E+Ol l.87E+Ol F 6 609.00 7.30E+Ol 19.97 2 . 06E+Ol 1.21E+O l 5.24E+Ol 2.34E+Ol F 7 1460 . 67 2 . 50E+02 31. 99 2.82E+Ol 8 . 57E+OO 2 . 22E+02 3.31E+Ol M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 2.000sigma
6/10/2019 10:49:41AM Page3 of 6 Analysis Report for B1-010-001-CIGS-BA01-SB B1-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty K- 40 0 . 99 1460 .75
- 10 . 67 6 . 35E+OO 1. OlE+OO PB- 212 0 . 56 77 .11 17 . 50 238 . 63
- 44 . 60 2. 55E-Ol 4 . 66E-02 BI - 214 0 . 34 609 . 31
- 46 . 30 1 . 58E-01 7 . 12E- 02 1120. 29 15 . 10 1238 . 11 5.94 1377 . 67 4 . 11 1407 . 98 2 . 48 1509 . 19 2 . 19 1764 . 49 15 . 80 PB- 214 0 . 72 77 . 11 10 . 70 295 . 21
- 19 . 20 2 . 18E- 01 8 . 38E-02 351 . 92
- 37 . 20 l. 07E- 01 6 . 63E-02
* "' Energy line found in the spectrum.
- :;: Manually added nuclide.
? "' Manually edited nuclide.
@ "' Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold "' 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)
K- 40 0 . 999 6 . 35E+OO 1 . 0lE+OO PB- 212 0 . 560 2 . 55E- 01 4 . 66E - 02 BI-214 0 . 342 1 . 58 E-0 1 7. 12E- 02
6/10/2019 10:49:41AM Page4 of6 Analysis Report for B1-010-001-CIGS-BA01-SB B1-010-001 B Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) PB- 214 0 . 721 1. SOE- 01 5 . 20 E-02
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/10/2019 10:49:41 AM Page 5 of6 Analysis Report for B1 -010-001-CIGS-BA01-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/10/2019 10:49:32AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS{%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide F 2 269 . 89 l . 50915E-02 32 .4 1 F 5 583 . 07 3 . 26956E-02 15 . 85 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nudide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Llbrary\HOTLAB.NLB Nucllde Energy Yield(3/4) Activity Nuc/ldeMDA LlneMDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV)
+ K-40 1460 . 75
- 10.67 6 . 35E+00 7 . 90E-01 7 . 90E- 01
+ AR- 41 1293 . 64 99 . 16 5 . 51E+17 l.48E+l8 l . 48E+18 + CO - 60 1173 . 22 100 . 00 6 . 58E -0 2 7 .34 E- 02 l . 00E-01 1332 . 49 100.00 4.31E- 02 7 . 34E- 02 + KR- 85 513 . 99 0 . 43 l.27E+0l 1 . 50E+0l 1. S0E+0l + Y-88 898 . 04 93 . 70 -5.65E-02 5 . 0 4E-02 8 . 02E-02 1836 . 06 99 . 20 - 2 . 02E-02 5 . 04E-02 + NB-94 702.63 100 . 00 - 7 . 06E - 03 6 . 42E-02 6 . 42E-02 871 . 10 100 . 00 - 5 .9 3E - 02 7 . 03E-02 + I-131 28 4. 30 6.06 8.27E-02 9 . llE - 02 l . 22E+00 364.48 81.20 5 . 15E-02 9 . llE- 02 636 . 97 7 . 27 - 5 . 45E-01 1. 33E+00 + CS-134 604 . 70 97 . 60 -l. 48E- 02 8.65£-02 8 . 65E-02 795.84 85 . 40 - 2.57E- 02 8 . BlE-02 + CS-137 661 . 65 85.12 3 . 44£- 02 9 . l0E - 02 9 . l0E-02 + CE- 144 80 . 12 1.36 5 . 74E-01 4 . 35E - 01 5 . 48E+00
6/10/2019 10:49:4 1AM Page 6 of6 Analysis Report for 81-010-001-CIGS-BA01-SB 81-010-001 B Nuclide Energy Yield(3/4) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV) CE-144 133 . 51 11.09 3 . 35E- Ol 4 . 35E - Ol 4 . 35E- Ol + EU- 152 1 21 . 78 28 . 40 - 1. 05E- 01 1. 65E - 01 1 . 65E-01 344 . 28 26 . 60 -4. 89E-Ol 2 . 23E-Ol 1408.00 20 . 74 1 . 98E - 01 3 . 21E- 01 + EU-154 123 . 07 40 . 40 2 . 86E-02 1 . 17E-01 1 .1 7E-Ol 723 . 30 1 9 . 70 -l. 12E- 02 3 . 47E- 0 1 1274 . 51 35 . 50 -1. 36E- 01 2 . 34E- 0 1 + EU-1 55 86 . 54 32 . 80 - 1. 53E- 02 1. 85E-01 l . 85E-01 105.31 2 1. 80 3 . 21E-02 2 . 31E-01 + BI - 214 609 . 31
- 46 . 30 1. 58E- 01 l . 3 4E-01 1 . 34E- 01 1120 . 29 15 . 10 5 . 46E- 01 6 . 73£-01 1238 . 11 5 . 94 1. 28E+OO l . 95E+OO 1377 . 67 4 . 11 -2 . 49E - Ol l . 90E+OO 1407.98 2 . 48 1. 65E+OO 2 . 68E+OO 1509 . 19 2 . 19 -4. 02E+OO 2 . 79E+OO 1764 . 49 15 . 80 1. 22E- 01 4 . 83E- Ol
+ PB- 214 77 . 11 1 0 . 70 6 . 87E- Ol 1.19E- Ol 7.56E- 0 1 295 . 21
- 19 . 20 2 .18E - 01 l . 70E- 01 351. 92
- 37 . 20 l . 07E- 01 l .1 9E-01
+ PA- 228 89 . 95 22 . 00 7 . 85E+OO 6 . 30E+OO 1 . 06E+Ol 93 . 35 3 5. 00 5. llE- 01 6 . 30E+OO 105.00 16 . 30 2.35E- Ol l . 23E+Ol 1 2 9 . 22 2 . 97 - 7 . 44E+Ol 6 . 15E+Ol 338 . 32 5 . 30 3 . 38E+Ol 4 . 38E+Ol 463 . 00 1 3 . 80 5 . 68E+OO 1 . 54E+Ol 911.23 16 . 70 1 . 77E+Ol 2 . 31E+Ol + AM- 241 59 . 5 4 36 . 30 -8 . 72E-02 3 . 69E - 01 3 . 69E- 01 + CM- 243 103 . 76 23 . 00 1. 32E- 01 2 . 23E - 01 2 . 23E - 01 228 . 18 1 0 . 60 - 5 . 25£- 02 4 . 5 1 E- 01 277 . 60 14 . 00 - 6 .8 7E- 02 3 . SlE - 01
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> :: MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? :: CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/10/2019 11 :26:46AM Page I of6
..f(Apex-Gamma Analysis Report for 8 1-010-001-CIGS-8A02-S8 81-010-001 8 GAMMA SPECTRUM ANALYS/S Sample Identification : 81-010-001-CIGS-BA02-SB Sample Description : 81-010-001 8 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 6.619E+02 grams Facility : Dalryland_NPP Sample Taken On : 6/5/2019 1:13:00PM Acquisition Started : 6/10/2019 10:56:27AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.4 seconds Deadl1me : 0.30%
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6766 PEAK ANALYSIS REPORT Peak Analysis Perfomied on : 6/10/2019 11 :26:37AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/10/2019 11 :26:46AM Page 2 of6 Analysis Report for B1-010-001-CIGS-BA02-SB B1-010-001 B Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 51 469 - 485 477 . 49 1 . 57E+02 32 . 24 2 . 65E+02 2 . 35 F 2 351 . 91 697 - 711 704 . 26 8 . 37E+Ol 21. 87 1 . 11E+02 1. 73 F 3 582 . 52 1161 - 1170 1165 . 39 2 . 55E+Ol 12 .4 9 5 . 77E+Ol 0 . 77 F 4 609 . 0 4 1212 - 1 223 1218 . 41 6 . 34E+Ol 19 . 21 6 . 60E+Ol 1. 82 F 5 910 . 66 1817 - 1827 1821.57 2 . 26E+Ol 12 . 16 2 . 99E+Ol 1. 78 F 6 1460 . 17 2911 - 2928 292 0 . 46 2 . 10E+02 29 . 66 l . 83E+Ol 2 . 62 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/ 10/2019 11 :26:37AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001 364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238.51 1 . 57E+02 32 . 24 l.57E+02 3 . 22E+Ol F 2 351 . 91 8 . 37E+Ol 21. 87 4.18E+Ol l . 86E+Ol 4 . 19E+Ol 2 . 87E+Ol F 3 582.52 2 . 55E+O l 12 . 49 2 . 55E+Ol 1. 25E+Ol F 4 609 . 04 6 . 34E+Ol 19 . 21 2 . 06E+Ol l.21E+Ol 4 . 28E+Ol 2 . 27E+Ol F 5 910 . 66 2 . 26E+Ol 12 . 16 2 . 26E+Ol 1 . 22E+Ol F 6 1460 . 17 2 . 10E+02 29 . 66 2 . 82E+O l 8 . 57E+OO l. 82E+02 3 . 09E+Ol
=
M First peak in a multiplet region
=
m Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/10/2019 11 :26:46AM Page3 of 6 Analysis Report for 81-010-001-CIGS-BA02-SB 81-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty K- 40 0 . 94 1460 . 75
- 10 . 67 6 . 00E+OO l . 07E+OO PB- 212 0 . 55 77 . 11 17.50 238 . 63
- 44 . 60 2.45E-01 5. l BE-02 BI - 214 0 . 34 609.31
- 46 . 30 1.49E-01 7 . 94E-02 1120. 29 15 .1 0 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2.48 1509.19 2 . 19 1764 . 4 9 15 . 80
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams)
K- 40 0 . 948 6 . 00E+OO l . 07 E+OO PB-2 12 0.559 2 . 45E- 01 5.18E-02 BI-214 0.344 1. 4 9E - 01 7.94E- 02
6/10/2019 11 :26:46AM Page4 of6 Analysis Report for 81-010-001-CIGS-BA02-SB B1-010-001 B
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/ 10/2019 11 :26:46AM Page 5 of6 Analysis Report for B1 -010-001-CIGS-BA02-SB 81 -010-001 B UNIDENTIFIED PEAKS Peak Locate Perfonned on : 6/ 10/2019 11 :26:37AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS('1/4) Peak Tolerance Peak No. Energy (keV} Peak Size (CPS) Uncertainty Type Nuclide F 2 351.91 2 . 32722E-02 34 . 27 Tol. PB-2 1 4 F 3 582.52 1. 41850E - 02 24 . 46 F 5 910 . 66 l . 25527E-02 26 . 91 Tol. AC-228 PA-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyfand_NPP\Library\HOTLAB.NLB Nuclide Energy Yield{3/4) Activity Nuc/ldeMDA LlneMDA Name (pCVgrams) (pCVgrams) (pCVgrams) (keV) + K-40 1460 . 75
- 10 . 67 6 . 00E+0O l . 04E+00 1 . 04E+00
+ AR- 41 1293 . 64 99 . 16 -4 . 78E+17 2 . 50E+18 2 . 50E+l8 + CO- 60 1173. 22 100.00 4 . 68E-02 l . 03E-0l l . llE-01 1332 . 49 100 . 00 3 . 37E- 02 1. 03E-Ol + KR- 85 513 . 99 0 . 43 l.93E+0l 1 . 78E+Ol l . 78E+Ol + Y- 88 898.04 93 . 70 1.61E-03 5 . 80E- 02 8 . llE- 02 1836 . 06 99 . 20 7 . 74E-03 5.80E-02 + NB- 94 702 . 63 100 . 00 2 . 63E-02 6 . 89E- 02 6 . 89E- 02 871.10 100.00 - 7.35E- 02 7 . 56E- 02 + I-131 284 . 30 6.06 -6 . 00E-0 1 9 . 63E-02 l.37E+OO 364.48 81.20 2 . 62E-03 9 . 63E-02 636 . 97 7 . 27 1. 47E-01 l . 30E+OO
6/10/201 9 11 :26:46AM Page6 of6 Analysis Report for B1-010-001-CIGS-BA02-SB B1-010-001 B Nuclide Energy Yield{%) Activity Nuclide MDA LlneMDA Name (pCi/grams) (pCl/grams) (pCi/grams) (keV) + CS - 134 604 . 70 97 . 60 9 . 36E- 02 9 . 22E-02 9 . 28E-02 795 . 84 85 . 40 -5 . 02E- 02 9 . 22E-02 + CS-137 661 . 65 85.12 7 . 02E- 02 9 . 86E- 02 9 . 86E-02 + CE- 144 80 . 12 1. 36 - l . 84E+OO 4 . 51E-0 1 5 . 68E+OO 133 . 51 11.09 -4 . 31E- 03 4 . 51E - Ol + EU- 152 121 . 78 28 . 40 - l.28E- 01 l . 70E-01 l . 70E-Ol 34 4. 28 26 . 60 l . 52E-01 2 . 35E - 01 1 408 . 00 20 . 74 -5 . 12E- 02 4 . 27E-01 + EU-154 123 . 07 40 . 40 - l . 52E- 03 l . 21E-01 1. 21E-01 723 . 30 19 . 70 2 . 47E- 01 3 . 80E - 01 1274 . 51 35 . 50 - 8 . 17E- 02 2 . 07E- 01 + EU- 155 86 . 54 32 . 80 - 3 . 1 3E- 02 l . 97E-01 1. 97E- 0 1 105 . 31 21. 80 -2 . 2 4E- 02 2 . 4 3E - 01 + BI - 214 609 . 31
- 46.30 1 . 49E- Ol l .4 5E- Ol 1. 45E - Ol 1120 . 29 15 . 10 6 . 27E - 03 6 . 93E - 01 1 238 .11 5 . 94 1. 07E+OO 2 . 09E+OO 1377 . 67 4 . 11 7 . 34E- 01 1. 87E+OO 1407 . 98 2 . 48 - 4 . 28E-01 3 . 56E+OO 1 509 . 19 2 . 19 -l. 57E+OO 2 . 99E+OO 1 764 . 49 15 . 80 2 . 5 4E - Ol 5 . 4 0E - Ol
+ PB- 214 77 . 11 1 0 . 70 7 . 02E- 01 1 . 77 E- 01 7 . 82E-01 295 . 21 1 9 . 20 l .4 0E-02 3 . 25E-01 351 . 92 37 . 20 2 . 0 4E - 01 l . 77E- 01 + PA- 228 89 . 95 22 . 00 - l . 97E+OO 7 . lOE+OO 1. l 7E+Ol 93 . 35 3 5 . 00 5 . Sl E- 0 1 7 .lOE+OO 105 . 00 1 6 . 30 - 6 . 35E+OO 1 . 34E+Ol 129 . 22 2 . 97 1 . 58E+Ol 6 . 83E+Ol 338 . 32 5 . 30 2 . 42E+Ol 4 . 62E+Ol 463 . 00 1 3 . 80 1 . 70E+Ol l . 76E+Ol 911 . 23 1 6 . 70 5 . 58E+OO 2 . 33E+Ol + AM- 241 59 . 54 36 . 30 l . 26E- 02 3 . 56E - Ol 3 . 56E- 01 + CM- 243 103 . 76 23 . 0 0 -1. 89E- 01 2 . 32E-01 2 . 32E-01 228 . 18 10 . 60 5 . 63E - 02 4 . 4 3E-01 277 . 60 14. 00 l .47E-02 4 . 14E- 01
+ = Nuclide identified during the nuclide identification
=Energy line found in the spectrum
> = MDA value not calculated
@ = Haff-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/12/2019 1 :05:01 PM Page l of6 __.Apex-Gamma Analysis Report for B1-010-001-CIGS-8B01-SB B1-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-B801-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 9.036E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/6/2019 1:46:00PM Acquisition Started : 6/12/2019 12:34:42PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.6 seconds Dead llme : 0.31 % Peak locate Threshold : 3.00 Peak locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6814 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/12/2019 1:04:52PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/ 12/2019 1:05:01PM Page 2of 6 Analysis Report for B1-010-001-CIGS-B801-SB B1-010-001 B Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 71 473 - 485 477 . 89 2 . 00E+02 37 . 19 3 . 32E+02 2 . 13 F 2 295 . 22 585 - 595 590 . 90 8 . 83E+Ol 25 . 26 1 . 62E+02 1. 74 F 3 351 . 79 697 - 708 704 . 01 1 . 09E +02 25 . 79 1 . 44E+02 1. 56 F 4 583 . 05 1159 - 117 1 1166 . 45 5 . 05E+Ol 17 . 19 6 . 18E+Ol 1. 77 F 5 609 . 32 1214 - 1225 1218 . 98 9 . 42E+Ol 21. 91 6 .4 0E+Ol 1. 63 F 6 911 . 18 1817 - 1828 1822 . 59 3 . 93E+Ol 14 . 88 3 . 87E+Ol 1. 72 F 7 1120 . 67 2236 - 2247 22 41.51 2 . 28E+Ol 12 . 33 3 . 38E+Ol 1. 75 F 8 1460 . 92 2913 - 2931 2921. 95 2 .4 5E+02 31. 49 5 . 0 l E+OO 2 . 99 F 9 1764 . 24 3523 - 3534 3528 . 55 2 . 22E+Ol 9 . 76 O. OOE+OO 2 . 73 M :: First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/12/2019 1:04:52PM Env. Background File : C:\Canberra\Apex\Rool\Dairyland_NPP\ Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 7 1 2 . 00E+02 37 .1 9 2 . 00E+02 3 . 72E+Ol F 2 295 . 22 8 . 83E+Ol 25 . 26 8 . 83E+Ol 2 . 53E+Ol F 3 351 . 79 1 . 09E+02 25 . 79 4. 18E+Ol l. 86E+Ol 6 . 72E+Ol 3 . 18E+Ol F 4 583 . 05 5 . 0SE+Ol 17 . 19 5 . 05E+Ol l . 72E+Ol F 5 609 . 32 9 . 42E+Ol 21. 91 2 . 06E+Ol 1 . 21E+Ol 7 . 37E+Ol 2 . 50E+Ol F 6 911 . 18 3 . 93E+Ol 14 . 88 3 . 93E+Ol l .4 9E+Ol F 7 1120 . 67 2 . 28E+Ol 12 . 33 2 . 28E+Ol 1 . 23E+Ol F 8 1460 . 92 2 . 45E+02 31. 49 2 . 82E+O l 8 . 57E+OO 2.17E+02 3 . 26E+Ol F 9 176 4. 2 4 2 . 22E +Ol 9 . 76 7 . 59E+OO 4 . 90E+OO 1.46E+Ol l . 09E+Ol M =First peak in a multiplet region m =Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/ 12/2019 1:05:01 PM Page 3 of6 Analysis Report for B1-010-001-CIGS-8B01-SB B1-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty K-40 0 . 99 1460 . 75
- 10 . 67 5 . 23E+OO 8 . 39E-01 PB-212 0 . 55 77 . 11 17 . 50 238 . 63
- 44 . 60 2.28E - 01 4 . 41E- 02 BI - 214 0 . 78 609 . 31
- 46 . 30 l . SSE-01 6.47E- 02 1120 . 29
- 15.10 3 . 09E- 01 1.67E- Ol 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2 . 48 1509 . 19 2 . 19 1764 . 49
- 15 . 80 2 . 78E - 01 2.09E- 01 PB- 214 0 . 72 77 . 11 10 . 70 295 . 21
- 19 . 20 2 . 80E-01 8 . llE- 02 351 . 92
- 37 . 20 1. 28E- 01 6 . llE- 02
* =Energy line found in the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV
=
Nuclide confidence index threshold 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCVgrams) K- 40 0 . 996 5 . 23E+OO 8 . 39E- 01 PB- 212 0 . 559 2 . 28E-01 4.41E - 02 BI - 214 0 . 782 2.09E-01 5 . 80E - 02
6/12/2019 1:05:01PM Page 4 of6 Analysis Report for 81-010-001-CIGS-8801-SB 81-010-001 B Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pC//grams) PB-214 0 . 720 1 . 83E- 0 1 4 . 88 E-02
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/12/2019 1 :05:01 PM Page 5 of6 Analysis Report for B 1-010-001-CIGS-BBO 1-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/12/2019 1:04:52PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 4 583 . 05 2 . 80298£- 02 17.04 F 6 911.18 2.18281£-02 18 . 93 Tol. AC-228 PA-228 M = First peak In a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dalryland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclldeMDA LineMDA Name (pCVgrams) (pCi/grams) (pCilgrams) (keV) + K-40 1460.75
- 10.67 5.23E+00 6.55E- 0l 6.55E-01
+ @ AR-41 1 293.64 99.16 1.00E+26 1. 00E+26 l.00E+26 + CO-60 1173.22 100.00 -4.26£-02 7.57£-02 8 . 64E-02 1332 . 49 100.00 2.32£-02 7.57E-02 + KR-85 513.99 0 . 43 1.90E+0l 1. 41E+ 0l l.41E+0l + Y-88 898.04 93 . 70 4 . 07E-03 5 . 92E - 02 6 . 87E-02 1836.06 99.20 -l.09E-02 5 . 92E- 02 + NB-94 702 . 63 100.00 2.91E-02 5.48E-02 5.48E- 02 871 . 10 100.00 -l . 14E-02 5.81E- 02 + I-131 284.30 6.06 - 1 . 79E-01 9 . 14E-02 1. l0E+00 364.48 81.20 2.53E- 02 9.14E-02 636.97 7.27 -2.83E-02 1.14E+00 + CS-134 604.70 97. 60 -4.79E-02 6.97E-02 7 . 72E-02 795.84 85.40 -6 . 94E-03 6.97E-02
6/12/2019 1:05:01PM Page6 of6 Analysis Report for B1-010-001-CIGS-8801-SB B1-010-001 B Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCi/grams) (pCUgrams) (pCUgrams) (keV) + CS-137 661. 65 85.12 6.00E-02 7 . 93E-02 7.93E-02 + CE-144 80 . 12 1.36 -6 . 17E-01 3 . 81E-01 4 . 66E+00 133.51 11.09 3.16E-01 3.81E-01 + EU-152 121. 78 28.40 -1 . 19E-01 1. 42E-0l 1. 42E-01 344 . 28 26.60 2 . 19E-01 1.92E-01 1408.00 20.74 -8.72E-02 2.95E-01 + EU-154 123.07 40 . 40 -5.53E-02 1 .0 lE-01 1.0lE-01 723. 30 19 . 70 9.61E-02 3.18E-0l 1274.51 35.50 1. 04E-01 2 . l0E-01 + EU-155 86 . 54 32 . 80 9.30E-03 1 . 62E-01 1 . 62E-01 105 . 31 21. 80 -l.08E-01 1.95E-01 + BI-214 609 . 31
- 46.30 1.88E-01 1.05E-0l 1.05E-01 1120.29
- 15.10 3.09E-01 3 . 31E-01 1238 .11 5.94 1 .43E+00 1.63E+00 1377.67 4 . 11 5.09E-02 1. 37E+00 1407.98 2.48 -7.29E-01 2.47E+00 1509 . 19 2.19 -2.52E+00 2.35E+00 1764 . 49
- 15.80 2.78E-0l 2.83E-0l
+ PB-214 77 . 11 10.70 3.03E-0l l.16E-01 6.29E-01 295 . 21
- 19 . 20 2.80E-01 1. 53E-01 351.92
- 37.20 1. 28E-01 1.16E-01
+ PA-228 89.95 22 . 00 1.83E+00 1. 25E+0l 2 . 09E+0l 93.35 35 . 00 - 1 . 57E+00 1 . 25E+0l 105 . 00 16.30 -l.45E+0l 2.38E+0l 129 . 22 2 . 97 1.01E+ 02 1.27E+02 338.32 5.30 1. 09E+02 8 . 64E+0l 463.00 13.80 1.29E+0l 3 . 20E+0l 911 . 23 16.70 1. 48E+0l 4.46E+0l + AM-241 59 . 54 36.30 1.48E-02 2 . 88E-01 2.88E-01 + CM-243 103.76 23 . 00 -2.06E-02 1 .90E-01 1.90E-01 228 .1 8 10.60 -1. 03E-01 3.85E-01 277 . 60 14.00 -3.43E-02 2 . 94E-01
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/12/2019 1:40:16PM Page 1 of6
.....t'Apex-Gamma Analysis Report for B1-010-001-CIGS-B802-SB B1-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BB02-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 8.280E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/6/2019 1:55:00PM Acquisition Started : 6/12/2019 1 :09:57PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.6 seconds Dead Time : 0.31 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100
- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6815 PEAK ANALYSIS REPORT Peak Analysis Perfonned on : 6/12/2019 1:40:07PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/12/2019 1:40:16PM Page 2 of6 Analysis Report for B1-010-001-CIGS-BB02-SB 81-010-001 8 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238.50 470 - 485 477.48 l.43E+02 31.05 3.56E+02 1.60 F 2 295 . 27 588 - 598 590 .9 9 3 . 0lE+Ol 15.85 1. 87E+02 0.77 F 3 351.80 697 - 708 704.04 8 . 95E+Ol 24.13 1.28E+02 1. 76 F 4 583.15 1163 - 1171 1166.63 4.92E+Ol 16.01 3.13E+Ol 1. 63 F 5 609 . 33 1213 - 1224 1219.00 5 . 90E+Ol 16.91 3.0lE+Ol 1. 59 F 6 1461. 03 2914 - 2932 2922 . 18 2 . 50E+02 32.13 1. 22E+Ol 2.75 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/12/2019 1:40:07PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 50 1. 43E+02 31.05 1. 43E+02 3 . lOE+Ol F 2 295 . 27 3.0lE+Ol 15.85 3 . 0lE+Ol l.59E+Ol F 3 351. 80 8.95E+Ol 24.13 4. 1 8E+Ol 1. 86E+Ol 4.77E+Ol 3 . 05E+Ol F 4 583.15 4.92E+Ol 16.01 4.92E+Ol l . 60E+Ol F 5 609.33 5.90E+Ol 16.91 2.06E+Ol 1. 21E+Ol 3.84E+Ol 2 . 08E+Ol F 6 1461.03 2.50E+02 32 . 13 2 . 82E+Ol 8 . 57E+OO 2 . 22E+02 3 . 33E+Ol M = First peak in a multiplet region
=
m Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/12/2019 1:40:16PM Page 3 of6 Analysis Report for 81-010-001-CIGS-8802-SB 81-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (keV) (pCl/grams) Uncertainty K-40 0 . 98 1460 . 75
- 10 .. 67 5 . 84E+00 9 . 33E- 0 1 PB-2 12 0.55 77 . 11 17. 50 238.63
- 44.60 1 . 78E-01 3.97E- 02 BI-214 0.35 609 . 31
- 46.30 1.07E-01 5 . 82E-02 1120. 29 15.10 1238 .11 5.94 1377.67 4 .11 1407 . 98 2.48 1509 . 19 2.19 1764 . 49 15 . 80 PB-214 0 . 72 77 .11 10.70 295 . 21
- 19.20 1 . 04E-01 5 . 50E - 02 351. 92
- 37 . 20 9 . 95E-02 6 . 38E-02
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams)
K-40 0.987 5.84E+00 9 . 33E- 01 PB- 212 0.558 1. 78E-01 3 . 97E - 02 BI - 214 0 . 350 1. 07E-01 5 . 82E - 02
6/12/2019 1:40:16PM Page4 of6 Analysis Report for B 1-010-001-CIGS-8B02-SB B1-010-001 B Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) PB-214 0 . 720 1.02E-01 4 . 17E-02
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000slgma
6/12/2019 1:40:16PM Page 5 of 6 Analysis Report for 81-010-001-CIGS-8 802-SB 81-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/12/2019 1:40:0?PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 4 583 . 15 2 . 73569E- 02 1 6 . 26 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity NuclldeMDA LlneMDA Name (pCl/grams) (pCVgrams) (pCUgrams) (keV) + K- 40 1460 . 75
- 10 . 67 5 . 84E+00 7 . 71E-01 7 . 71E-01
+ @ AR-41 1293 . 64 99 . 16 1. 00E+ 2 6 1.00E+26 1. 00E+26 + CO- 60 1173 . 22 100 . 00 2 . 44E - 02 7 . 55E - 02 9 . 43E - 02 1332 . 49 100 . 00 4 . 93E - 02 7 . 55E - 02 + KR- 85 513 . 99 0 . 43 l . 36E+0l l . 53E+0l 1. 53E+0l + Y- 88 898 . 0 4 93 . 70 - 5 .5 9E-0 2 5 . 93E- 02 7 . 03E-02 1836 . 06 99.20 -2 . 08E- 02 5.93E-02 + NB- 94 702 . 63 100 . 00 - l. 98E-02 5 . 98E - 02 6 . 07E-02 871 . 10 100 . 00 1 . 02E - 02 5 . 98E - 02 + I - 131 284 . 30 6 . 06 - 9 . 29E - 01 9 .4 5E-02 l . 22E+00 36 4 . 4 8 81.20 4. 26E - 02 9 . 45E - 02 636 . 97 7 . 27 - 5 . 08E-0 1 l . 42E+00 + CS - 134 604 . 70 97.60 - 6 . 84E - 03 6 . 67E - 02 6 . 67E- 02 795.84 85.40 2.13E - 02 8 . 42E-02 + CS - 137 661. 65 85 . 12 1. 09E - 01 8 . 62E - 02 8 . 62E- 02 + CE - 144 80 . 12 1. 36 2 . 06E+00 3 . 98E - 01 4 . 91E+00 133 . 51 11.09 1. 51E-01 3 . 98E-01
6/12/2019 1:40:1 6PM Page 6 of6 Analysis Report for 81-010-001-CIGS-8B02-SB 81-010-001 B Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCl/grams) (pCJ/grams) (pCVgrams) (keV) + EU-152 121 . 78 28 . 40 - 8 . 39E - 02 l . 51E- 01 1. 51E- 01 344 . 28 26 . 60 8 . 84E-02 l . 94E-01 1408 . 00 20 . 74 4 . l0E-02 2 . 95E- 01 + EU- 154 123 . 07 40 . 40 - 1. 24E - 01 l.04E- 0l 1 . 04E- 01 723 . 30 19 . 70 -l.95E-02 3 . 08E-01 1274 . 51 35.50 -1.35E-01 2 . 07E-01 + EU-155 86.54 32 . 80 -9.67E-02 1.69E- 01 1. 69E- 01 105 . 31 21. 80 7 . 64E-02 2 . 00E-01 + BI-214 609 . 31
- 46.30 1 . 07E-01 9.69E- 02 9 . 69E- 02 1120 . 29 15 . 10 3.26E-01 5 . 26E-01 1238 . 11 5 . 94 7 . 82E-01 l . 73E+00 1377 . 67 4 .11 6 . 72E-01 1 . 49E+00 1407 . 98 2 . 48 3 . 43E-01 2 . 46E+00 1509 . 19 2 . 19 l.34E+00 2.81E+00 1764 . 49 15.80 3 . 51E-01 5 . llE- 01
+ PB-214 77 . 11 10 . 70 9.27E - 01 1.22E-01 6 . 6 4E- 01 295 . 21
- 19.20 l . 04E-01 1 . 80E-01 351 . 92
- 37 . 20 9 . 95E-02 l . 22E- 01
+ PA-228 89 . 95 22 . 00 2 . 89E+0l 1 . 35E+0l 2 . 29E+0l 93 . 35 35 . 00 8 . 25E+00 1 . 35E+0l 105 . 00 16 . 30 1.59E+01 2 . 45E+0l 129 . 22 2. 97 - 2 . 28E+00 l . 31E+02 338 . 32 5 . 30 4 . 05E+0l 8 . 62E+0l 463.00 13 . 80 - 2 . 33E+00 3 . 36E+0l 911 . 23 16 . 70 3 . 04E + 0l 4 . 81E+0l + AM-241 59 . 54 36 . 30 -6 . 49E-02 3.04E-01 3 . 04E-01 + CM-243 103 . 76 23 . 00 6 . 21E-02 l . 90E-0l 1. 90E-01 228 . 18 10 . 60 1 . 33E-01 4 . 02E-01 277 . 60 14 . 00 3 . 30E - 02 3 . 38E-01
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/12/2019 3:23:23PM Pagel of5 __.,Apex-Gamma Analysis Report for B1-010-001-CIGS-BC01 -SB 81-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BC01-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 7.672E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/6/2019 1:06:00PM Acquisition Started : 6/12/2019 2:53:05PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.5 seconds Dead Time : 0.31 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6817 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/12/2019 3:23:14PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/12/2019 3:23:23PM Page2 of5 Analysis Report for B1-01 0-001-CIGS-BC01-SB B1-010-001 B Peak Energy ROI ROI Peale Net Peale Net Area Continuum FWHM No. (leeV) start end Centroid Area Uncertainty Counts (leeV) F 1 238 . 78 471 - 485 478 . 04 1 . 26E+02 30 . 80 3 . 33E+02 1 . 82 F 2 351. 99 699 - 711 704 . 40 7 . 97E+Ol 23 . 95 l . 35E+02 2 . 11 F 3 583 . 50 1162 - 117 4 1167 . 35 3 . 69E+ Ol 16 . 77 7 . 62E+Ol 1. 97 F 4 609 . 66 1210 - 1225 1 219 . 65 4 . 74E+Ol 15 . 95 6 . 86E+Ol 1. 56 F 5 1460 . 95 2915 - 2931 2922 . 01 2 . 05E+02 29.55 2 . 13E+Ol 2.18 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/12/2019 3:23:14PM Env. Background File : C:\Canberra\Apex\Root\Oairyland_NPP\Oata\0000001364.CNF Peale Energy Original Orig. Area Ambient Baclegr. Subtracted Subtracted No. {keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 78 1 . 26E+02 30 . 80 1. 26E+02 3 . 08E+Ol F 2 351. 99 7 . 97E+Ol 23 . 95 4 . 18E+Ol 1.86E+Ol 3 . 79E+Ol 3 . 03E+Ol F 3 583 . 50 3 . 69E+Ol 16 . 77 3 . 69E+Ol 1.68E+Ol F 4 609.66 4 . 74E+Ol 15 . 95 2.06E+Ol 1. 21E+Ol 2 . 68E+Ol 2.00E+Ol F 5 1460.95 2 . 05E+02 29 . 55 2.82E+Ol 8.57E+OO 1.77E+02 3 . 08E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairytand_N PP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES
6/12/2019 3:23:23PM Page 3 of 5 Analysis Report for B1-010-001-CIGS-BC01 -SB B1-010-001 B Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty K-40 0 . 99 1460 . 75
- 10 . 67 5 . 03E+OO 9 . 18E- 01 PB- 212 0 . 55 77 . 11 17 . 50 238 . 63
- 44 . 60 1 . 69E- 01 4 . 24E-02 BI-214 0 . 34 609 . 31
- 46 . 30 8 . 05E- 02 6 . 03E- 02 1120 . 29 1 5 . 10 1 238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2 . 48 1509 . 19 2 . 19 1764.49 15 . 80
* = Energy line found in the spectrum.
* = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)
K- 40 0.994 5 . 03E+OO 9 . 18E-01 PB- 212 0 . 557 1. 69E- 01 4.24E-02 BI - 214 0 . 340 8 . 05E- 02 6 . 03E-02
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/12/2019 3:23:23PM Page4 of 5 Analysis Report for B1-010-001-CIGS-BC01-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/12/2019 3:23:14PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 351 . 99 2 . 10728E- 02 3 9.98 Tol. PB-214 F 3 583 . 50 2 . 0 474 1E- 02 22 . 75 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ N PP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclldeMDA LineMDA Name (pCl/grams) (pCUgrams) (pCVgrams) (keV) + K- 40 1 4 60 . 75
- 10 . 67 5 . 03E+00 8 . 98E- 01 8 . 98E- 01
+ @ AR- 41 1293 . 64 99 . 16 1. 00E+26 1.00E+26 1. 00E+26 + CO- 60 1173 . 22 100 . 00 4 . 40E- 03 8 . 37E - 02 9 . 19E- 02 1332 . 49 100 . 00 5 .4 0E- 02 8 . 37E- 02 + KR-85 513 . 99 0 . 43 1.1 6E+0l 1 . 54E+0l 1 . 5 4E+0l + Y-88 898 . 0 4 93 . 70 1. 53E- 02 6 .4 1E-02 7 . 8 1E- 02 1836 . 06 99 . 20 9 . 40E- 03 6 . 41E- 02 + NB - 94 702 . 63 100 . 00 2 . 73E- 02 6.37E- 02 6 . 37E- 02 871 .1 0 100 . 00 8 . 82E-03 7 . 03E-02 + I-131 284 . 30 6 . 06 4 . 73E-01 9.59E-02 l . 32E+00 36 4 . 4 8 81.20 5 . 1 4E-02 9 . 59E-02 636 . 97 7 . 27 6 . llE- 01 l . 48E+00 + CS- 134 604 . 70 97 . 60 1 . 94E- 02 7.S0E- 02 7 . 9 0E- 02 795.8 4 85 . 40 - 6 . 64E - 02 7 . 50E- 02 + CS-137 66 1. 65 85 . 12 7 . llE-02 8.76E-02 8 . 76E-02
6/12/2019 3:23:23PM Page 5 of5 Analysis Report for B1-010-001-CIGS-BC01-SB B1-010-001 B Nucllde Energy Yield(%) Activity Nuc/ldeMDA LlneMDA Name (pCVgrams) (pCVgrams) (pCVgrams) (keV) + CE-144 80 . 12 1. 36 3 . 00E+OO 3 . 87E- 01 5 . 18E+OO 133 . 51 11. 09 -2 . 18E-03 3 . 87E- Ol + EU- 152 1 21. 78 28 . 40 2 . 98E-02 l . 53E- Ol 1. 53E- 01 344 . 28 26 . 60 -l . 80E - 01 2 . 00E- 0 1 1408 . 00 20 . 74 1. 27E-01 3 . 55E-01 + EU- 154 1 23 . 07 40 . 40 - 2 . lOE - 02 l . 06E- 01 1. 06E- 0 1 723 . 30 19 . 70 1. 83E -0 1 3 . 30E- 01 1274 . 51 35 . 50 1 . 20E-01 2 . 58E- 01 + EU- 155 86 . 54 32 . 80 2 . 83E- 02 1. 7 9E - Ol 1 . 79E- 01 105 . 31 21. 80 - 5 . 31E- 02 2 . lSE-01 + BI -2 1 4 609 . 31
- 46 . 30 8 . 05E-02 1. 34E- 01 1. 34E- 01 1120 . 29 15 . 10 3 . 80E- 01 5 . 98E- 0 1 1238 . 11 5 . 94 - 1. 85E-01 1 . 55E+OO 1377 . 67 4 .11 7 . 89E- 01 1 . 68E+OO 1407 . 98 2 . 48 1.06E+OO 2 . 96E+OO 1 509 . 19 2 . 19 -2 . 12E+OO 2 . 37E+OO 1764 . 49 15 . 80 1. 59E-Ol 4 . 38E- 01
+ PB- 214 77 . 11 10 . 70 2 . 54E- 01 l . 61E - Ol 6 . 87E- Ol 295 . 21 19 . 20 2 . 61E- 0 1 2 . 71E- 01 351. 92 37 . 20 1 . 76E-Ol 1. 61E-01 + PA- 228 89 . 95 22.00 2 . 70E+OO 1. SO E+Ol 2 . 53E+Ol 93 . 35 35 . 00 - 2 . 16E+OO 1 . 50E+Ol 105 . 00 16. 30 - 1 . 90E+O l 2 . 85E+Ol 129 . 22 2 . 97 1 . 99E+Ol 1. 43E+02 338 . 32 5 . 30 5 .83E+Ol 9 . 63E+Ol 46 3 . 00 13 . 80 4 . 09E+OO 3 . 94E+Ol 911 . 23 16 . 70 4 . 13E+Ol 5. 2 6E+Ol + AM- 241 59 . 54 36 . 30 - 7 . 45E- 02 3 . 20E- 01 3 . 20E - Ol + CM- 243 1 03 . 76 23 . 00 1. 3S E- 02 2 . 06E- 01 2 . 06E - Ol 22 8 . 18 10 . 60 1 . 93E- 01 4 . 31E- 01 277 . 60 14 . 00 - 6 . 47E- 02 3 . 32E- 01
+ = Nuclide identified during the nuclide Identification * = Energy line found in the spectrum > = MDA value not calculated @ = Half-life too short to be able to perfonn the decay correction ? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/12/2019 3:54:13PM Page I of7 __.,,Apex-Gamma Analysis Report for B1-010-001-CIGS-BC02-SB B1-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BC02-SB Sample Description : 81-010-001 B Sample TyPe : 500 ml Marinelli Unit Sample Point Sample Size 7.466E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/612019 1:14:00PM Acquisition Started : 6/12/2019 3:23:55PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real lime : 1805.7 seconds Dead Time : 0.31 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100- 4096 Peak Area Range (in channels) : 100- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/812014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6818 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/ 1212019 3:54:04PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/12/2019 3:54:13PM Page 2 of7 Analysis Report for B 1-010-001-CIGS-BC02..SB B1-010-001 B Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (lceV) F 1 238 . 53 469 - 485 477 . 53 l.07E+02 27 . 90 3 . 74E+02 1. 47 F 2 351 . 93 698 - 710 704 . 28 8 . 06E+Ol 23 . 33 l. 21E+02 2 . 04 F 3 609 . 53 12 12 - 1226 1219 . 38 6 . 24E+Ol 17 . 44 3 . 39E+Ol 2 . 05 F 4 91 1. 05 1816 - 1828 1822 . 33 2 . 87E+Ol 12 . 22 2 . 25E+Ol 1. 74 F 5 968 . 99 1934 - 1943 1938 . 21 l . 52E+Ol 11. 35 5 . 27E+Ol 1.19 F 6 1460 . 85 2912 - 2929 2921 . 81 2 . 37E+02 31. 53 l . 22E+01 2 . 76 M = First peak in a multiplet region rn = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/ 12/2019 3:54:04PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 53 l . 07 E+02 27 . 90 l . 07E+02 2 . 79E+Ol F 2 351. 93 8 . 06E+Ol 23 . 33 4 . 18E+O l l.86E+O l 3 . 88E+Ol 2 . 98E+Ol F 3 609 . 53 6 . 24E+Ol 17 . 44 2 . 06E+Ol l . 21E+Ol 4 .18E+Ol 2 .1 2E+Ol F 4 911.05 2 . 87E+Ol 12 . 22 2 . 87E+Ol 1. 22E+Ol F 5 968 . 99 1. 52E+Ol 11. 35 l.52E+Ol l . 14E+Ol F 6 1 460 . 85 2 . 37E+02 31. 53 2 . 82 E+Ol 8 . 57E+OO 2.09E+02 3 . 27E+Ol M = First peak in a multiplet region
=
m Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/12/2019 3:54:13PM Page 3 of7 Analysis Report for B1-010-001-CIGS-BC02-SB B1-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{%) Activity Activity Name Confidence (keV) (pCl/grams) Uncertainty K-40 0 . 99 1460.75
- 10 . 67 6 . 09E+OO 1 . 0lE+OO PB-212 0.55 77 . 11 17 . 50 238 . 63
- 44.60 1. 48E-01 3 . 93E- 02 BI - 214 0 . 34 609 . 31
- 46 . 30 1 . 29E - 01 6 . 59E- 02 1120 . 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2 . 48 1509 . 19 2 . 19 1764 . 49 15 . 80
* = Energy line found In the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence Index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pC/lgrams)
K- 40 0 . 998 6 . 09E+OO 1 . 0lE+OO PB- 212 0 . 559 1 . 48E - 01 3 . 93E-02 BI-214 0 . 346 1. 29E-01 6 . 59E-02
6/12/2019 3:54:13PM Page 4 of7 Analysis Report for 81-010-001-CIGS-BC02-SB B1-010-001 B
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/12/2019 3:54:13PM Page 5 of7 Analysis Report for B1-010-001-CIGS-BC02-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Perfonned on : 6/12/2019 3:54:04PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide F 2 35 1. 93 2 . 15454E-02 38 . 47 Tol. PB- 214 F 4 911 . 05 l . 59563E- 02 21. 27 Tol. AC-228 PA-228 F 5 968 . 99 8 . 43173E- 03 37 . 40 Tol. AC - 228 M = First peak In a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield{3/4) Activity NuclideMDA LineMDA Name (pCl/grams) (pCl/grams) (pCl/grams) (keV) + K- 40 1460 . 75
- 10 . 67 6 . 09E+00 8 . 54E-01 8 . 54E-01
+ @ AR-41 1293 . 64 99 . 16 1. 00E+26 1 . 00E+26 1 . 00E+26 + CO- 60 1173 . 22 100 . 00 8 . 53E-02 7 . 88E- 02 l. llE-01 1332 . 49 100.00 1 . 0SE-02 7 . 88E-02 + KR-85 513 . 99 0 . 43 l . 04E+0l l . 55E+0l 1. 55E+0l + Y- 88 898 . 04 93 . 70 - l . 70E- 02 6 . 27E- 02 7 . 65E - 02 1836 . 06 99 . 20 1 . 48E- 02 6 . 27E-02 + NB- 94 702.63 100.00 1 . 32E- 02 6 . 59E-02 6 . 59E-02 871 . 10 100 . 00 -5.25E- 02 7.17E-02 + I - 13 1 284 . 30 6.06 -1. 09E+00 1. 0lE- 01 1 . 25E+00 364 . 48 81. 20 - 6 . 59E- 03 1 . 0lE- 01
6/12/2019 3:54:13PM Page6 of7 Analysis Report for B 1-010-001-CIGS-BC02-SB B1-010-001 B Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCVgrams) (pCVgrams) (pCVgrams) (keV) I-131 636 . 97 7 .27 -4.48£-01 1. 0lE-01 l.38E+00 + CS-134 604 . 70 97 . 60 -3 . 22£-05 7.69£- 02 7 . 69E-02 795 . 84 85 . 40 -7.22£-03 7.91E-02 + CS-137 661. 65 85.12 4.58E-02 9.08E- 02 9.08£-02 + CE- 144 80 . 12 1.36 -1.14£-01 3.99E-01 5.37£+00 133 . 51 11.09 1.18E-01 3.99E-01 + EU-152 121. 78 28.40 -7.17£-02 1 .SSE-01 l .55E-01 344 . 28 26 . 60 9.30E- 02 2 . 12£-01 1408.00 20.74 2.02£-01 3.35£-01 + EU-154 123 . 07 40.40 - 3.00E- 02 1. 09£-01 1.09£-01 723 . 30 19 . 70 -1 . 83£-01 3 . 32E-01 1274 . 51 35 . 50 3.67E- 02 2 . 59£-01 + EU-155 86 . 54 32 . 80 6.98£- 02 1. 84£- 01 1 . 84£-01 105 . 31 21. 80 -4 . 54E-02 2.24£-01 + BI-214 609 . 31
- 4 6. 30 1.29£-01 l.13E-01 l.13E-01 1120.29 15 . 10 3 . 05E-0l 6 . 63E-01 1238 . 11 5 . 94 6 . 02E-0l l . 77E+00 1377 . 67 4 .11 1.60E+00 2 . 09£+00 1407 . 98 2.48 l.68E+00 2 . 80E+00 1509.19 2 . 19 6.69E- 0l 2 . 55E+00 1764 .4 9 15 . 80 2 . 30£- 01 4.79E-0l
+ PB-214 77 . 11 10 . 70 6 . 61£-01 1 . 65£-01 7 . 27E-01 295 . 21 19. 20 4 . 19£-01 2 . 86E - 01 351 . 92 37 . 20 1 . 73£-01 1.65E-01 + PA-228 89 . 95 22.00 2 . 05E+0l l . 50E+0l 2.61E+0l 93 . 35 35 . 00 -l.16E+0l l . 50E+0l 105 . 00 16 . 30 5 . 19£+00 3 . 03E+0l 129 . 22 2 . 97 1. 03E+02 1 . 52£+02 338 . 32 5.30 7 . 74E+00 l . 02E+02 463 . 00 13 . 80 - 1 . 00E+00 4 . 24E+0l 911.23 16 . 70 5 . 25£+01 5 . 27E+0l + AM-241 59.54 36.30 - 3.62£-02 3 . 21£- 01 3 . 21E-0l + CM- 243 103 . 76 23 . 00 1 . 39£- 01 2 .16£-01 2 . 16£-01 228.18 10 . 60 4.90£-03 4 . 39£-01 277 . 60 14 . 00 -2.91£-02 3.S0E-01
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Cunrie MDA at 95% confidence level
6/12/2019 3:54:13PM Page 7 of7 Analysis Report for B1-010-001-CIGS-BC02-SB B1-010-001 B
6/12/2019 4:28:38PM Page I of 6 __....t'Apex-Gamma Analysis Report for B1-010-001-CIGS-BD01-SB B1-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BD01-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 7.872E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/6/2019 10:39:00AM Acquisition Started : 6/12/2019 3:58:18PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Tlme : 1800.0 seconds RealTlme : 1805.5 seconds Dead Tlme : 0.30% Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100
- 4096 Peak Area Range (in channels) : 100
- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6819 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/12/2019 4:28:28PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/12/2019 4:28:38PM Page 2 of6 Analysis Report for 8 1-010-001-CIGS-8D01-SB 81-010-001 B Peale Energy ROI ROI Peale NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 76 . 70 147 - 159 153 . 95 1 . 31E+02 38 . 83 5 . 56E+02 2 . 23 F 2 238 . 60 473 - 485 477 . 67 l . 53E+02 31. 80 2 . 87E+02 1. 68 F 3 338 . 53 671 - 681 677 . 49 3 . 05E+Ol 3 . 74 l .1 2E+02 0 . 52 F 4 352 . 06 698 - 709 704 . 56 7 . 09E+Ol 22 . 94 l.32E+02 1.85 F 5 583 . 29 1161 - 1172 1166 . 92 4 . 06E+Ol 17 . 86 8 .1 2E+Ol 2 . 02 F 6 609 . 54 1214 - 1225 12 1 9 . 42 4 . 63E+Ol 15.79 5 . 08E+Ol 1.29 F 7 910 . 91 1818 - 1827 1822 . 05 1. 38E+Ol 10 . 54 4 . 89E+Ol 1.11 F 8 968 . 95 1933 - 1944 1938.12 2.47E+Ol 11. 57 2 . 46E+Ol 1. 48 1 F 9 1461. 03 2914 - 2930 2922 .17 2 . 63E+02 33 . 07 1 . 70E+Ol 2.64 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/ 12/2019 4:28:28PM Env. Background File : C:\Canberra\Apex\Root\Dalryland_NPP\Data\0000001364.CNF Peale Energy Original Orig. Area Ambient Baclegr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 76.70 1.31E+02 38.83 l . 31E+02 3 . 88E+Ol F 2 238 . 60 l . 53E+02 31. 80 l . 53E+02 3 .1 8E+Ol F 3 338 . 53 3 . 05E+Ol 3 . 74 3 . 05E+Ol 3 . 74E+OO F 4 352.06 7.09E+Ol 22 . 94 4 . 18E+O l 1 . 86E+Ol 2 . 91E+Ol 2 . 95E+Ol F 5 583 . 29 4 . 06E+Ol 17.86 4 . 06E+Ol 1 . 79E+Ol F 6 609.54 4.63E+Ol 15.79 2.06E+Ol l . 21E+Ol 2 . 57E+Ol l . 99E+Ol F 7 910.91 1. 38E+Ol 10.54 1 . 38E+Ol l . OSE+Ol F 8 968 . 95 2.47E+Ol 11. 57 2 . 47E+Ol l . 16E+Ol F 9 1461.03 2 . 63E+02 33 . 07 2 . 82E+Ol 8 . 57E+OO 2 . 35E+02 3 . 42E+Ol M =First peak in a multiplet region m = Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/12/2019 4:28:38PM Page 3 of 6 Analysis Report for B1-010-001-CIGS-8D01-SB B1-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield('1/4) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty K- 40 0 . 98 1 460 . 75
- 10 . 67 6 . 5 1E+00 l . 0lE+00 PB- 212 0 . 99 77 . 11
- 17 . 50 4 . 73£- 01 1. 43£- 01 238 . 63
- 44 . 60 2 . 00E- 01 4 . 29£- 02 BI-214 0.34 609 . 31
- 46 . 30 7 . 53E-02 5 . 84E- 02 1120 . 29 15 . 10 1 238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2 . 48 1509 . 19 2 . 19 1764. 49 15 . 80 PB-21 4 0 . 52 77 . 11
- 10 . 70 7 . 74£ - 01 2 . 3SE- 01 295 . 21 19 . 20 351. 92
- 37 . 20 6 . 39E - 02 6 . 49E - 02 AC- 228 0 . 60 209 . 28 4 . 40 338 . 32
- 1 1.4 0 2 . llE-01 2 . 78E- 02 794 . 70 4 . 60 911 . 60
- 27.70 9 . 70E-02 7 . 44E- 02 964.60 5 .2 0 969 . 11
- 1 6 . 60 3 . 07 E-01 l . 44E - 0 1
* =Energy line found in the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT
6/ 12/2019 4:28:38PM Page 4 of6 Analysis Report for B1-010-001 -CIGS-BD01-SB B1-010-001 B Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) K- 40 0 . 988 6 . 51E+OO l . OlE+OO PB- 212 0 . 992 2 . lBE- 01 4 . 13E- 02 BI - 214 0 . 345 7.53E- 02 5 . 84E- 02 PB- 214 0 . 520 8 . 90E-02 6 . 28E- 02 AC- 228 0 . 601 2.0lE- 01 2.56E- 02
? = nudide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/12/2019 4:28:38PM Page 5 of6 Analysis Report for B1-010-001-CIGS-8D01-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/12/2019 4:28:28PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy {keV) Peak Size (CPS) Uncertainty Type Nuclide F 5 583 . 29 2.25436E-02 22.01 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA LineMDA Name (pCl/grams) (pCl/grams) (pCilgrams) {keV) + K-40 1460 . 75
- 10 . 67 6.51E+00 8 . 54E-01 8 . 54E-01
+ @ AR-41 1293.64 99.16 1.00E+26 1.00E+26 1.00E+26 + CO-60 1173.22 100 . 00 -1.15E- 02 8 . 69E-02 9 . 84E-02 1332.49 100.00 1.31E-02 8.69E-02 + KR-85 513.99 0.43 1. l0E+0l 1. 57E+0l l . 57E+0 l + Y-88 898 . 04 93.70 2 . 20E-02 5 . 95E-02 8.03E-02 1836.06 99 . 20 -2.38E-02 5.95E-02 + NB- 94 702.63 100 . 00 -6.07E-02 6.07E-02 6.07E-02 871 . 10 100 . 00 -8.64E-03 7.03E-02 + I-131 284 . 30 6 . 06 5.86E-01 1. 08E-01 l.31E+00 364.48 81.20 -4.20E-02 1. 08E-01 636.97 7.27 1. 43E-02 1 . 36E+00
+ CS-134 604.70 97.60 1 . 94E-02 7 .8 4E-02 7 . 84E-02 795.84 85.40 1.60E-02 8.24E-02 + CS-137 661. 65 85.12 8.80E-02 8.17E- 02 8.17E-02 + CE-144 80 . 12 1.36 -2.03E+00 4 . 17E-01 5.31E+00 133 . 51 11.09 1. 21E- 01 4.17E-01
6/12/2019 4:28:38PM Page 6 of6 Analysis Report for B1-010-001-CIGS-BO01-SB B1-010-001 B Nucllde Energy Yield(%) Activity Nucllde MDA LlneMDA Name (keV) (pCl/grams) (pCi/grams) (pCl/grams) + EU-152 121.78 28 . 40 -6.58£-02 1.57£-01 1. 57E- Ol 344.28 26 . 60 -2.41E-02 1. 96E-01 1408.00 20.74 1.72E-Ol 3.46E-01 + EU-154 123 . 07 40 . 40 - 7.69E- 03 1. lOE - 01 1. lOE-01 723 . 30 19 . 70 -5 . 92E-02 3 . lOE-01 1274 . 51 35 . 50 - 1 . 26E- 01 1 . 82E- 01 + EU-1 55 86 . 54 32 . 80 - 5.lOE- 02 1 . 79E - 01 1 . 79E-Ol 105.31 21. 80 1.04E-01 2.17£-01 + BI-214 609.31
- 46 . 30 7.53£- 02 l.14E - 01 1.14£- 01 1120 . 29 15 .10 -1.41E-Ol 5 . 58E-01 1238 . 11 5 . 94 3 . 51E-01 1 . 81E+OO 1377 . 67 4 . 11 -3.59E-01 1 . 74E+OO 1407 . 98 2 . 48 1.44E+OO 2 .8 9E+OO 1509 . 19 2 . 19 -9.71E-02 2 . 87E+OO 1764.49 15 . 80 2 . 85E - 01 4.27E- 01
+ PB-214 77 . 11
- 10.70 7 . 74E-01 l.30E-01 5 .4 2E- 01 295.21 19 . 20 2 . 66E-01 2 . 78E-01 351. 92
- 37 . 20 6 . 39E- 02 1 . 30E-01
+ PA-228 89 . 95 22 . 00 2 . 31E+Ol 1 . 68E+Ol 2 . 91E+Ol 93 . 35 35 . 00 -2.36E+OO l . 68E+Ol 105 . 00 16 . 30 -3 . 16E+OO 3.19E+Ol 129 . 22 2 . 97 l.26E+02 1 . 72E+02 338.32 5 . 30 4 .44 E+Ol 1.06E+02 463.00 13 . 80 -2 . 86E+OO 4.29E+Ol 911. 23 16.70 3 . 88E+Ol 5 . 70E+Ol + AM-241 59 . 54 36 . 30 l. llE -0 1 3 . 31E- 01 3 . 31E-01 + CM-243 103.76 23 . 00 - 8 . 84E - 02 2 . 03E - Ol 2 . 03E - Ol 228.18 10 . 60 l. 89E-02 4 . 45E-01 277.60 14 . 00 - 7 . 35E-02 3 . 26E-01
+ =
=
Nuclide identified during the nuclide identification Energy line found in the spectrum
> = MDA value not calculated @ = Haff.fife too short to be able to perform the decay correction ? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/13/2019 5:51:23AM Page I of6
~ Apex-Gamma Analysis Report for B1-010-001-CIGS-BD02-SB B1-010-001 8 GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001-CIGS-BD02-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 7.965E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/6/2019 10:59:00AM Acquisition Started : 6/13/2019 5:21 :04AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.8 seconds Dead Time : 0.32%
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100 - 4096 ldenUflcation Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6822 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/13/2019 5:51 :14AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/13/2019 5:51 :23AM Page 2 of6 Analysis Report for 81-010-001-CIGS-8D02-SB B1-010-001 B Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 55 469 - 485 477 . 5 7 l . 63E+02 3 1. 85 3 . 20E+02 1. 76 F 2 295 . 07 582 - 595 590 . 58 3 . 44E+Ol 19 . 97 2 . 02E+02 1. 59 F 3 338 . 16 673 - 682 676 . 75 2 . 95E+Ol 16 . 81 l . 05E+02 1. 50 F 4 583 . 10 1161 - 1172 1166 . 54 3 . 34E+Ol 14 . 75 7 . 83E+Ol 1.18 F 5 608 . 97 1213 - 1 224 1218 . 28 6 . 15E+Ol 17 . 23 3 . 49E+Ol 1.51 F 6 1460 . 94 2912 - 2930 2921.99 2 . 25E+02 30 . 48 1 . 4 4E+Ol 2 . 59 M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/ 13/2019 5:51 :14AM Env. Background File : C:\Canberra\Apex\Root\Dalryland_NPP\Data\0000001 364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238.55 1 . 63E+02 31. 85 1.63E+02 3 . 19E+Ol F 2 295 . 07 3 . 44 E+Ol 19 . 97 3 . 44E+Ol 2 . 00E+Ol F 3 338 . 16 2 . 95 E+Ol 16 . 81 2 . 95E+O l 1 . 68E+Ol F 4 583 . 10 3 . 34E+Ol 1 4 . 75 3 . 34E+Ol l . 48E+Ol F 5 608.97 6 . 15E+Ol 17 . 23 2 . 06E+Ol l . 21E+Ol 4.09E+Ol 2 . llE+Ol F 6 1460 . 94 2 . 25E+02 30 . 48 2 . 82E+Ol 8 . 57E+OO 1 . 97E+02 3 . 17E+Ol
=
M First peak in a multiplet region m = Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/13/2019 5:51 :23AM Page 3 of6 Analysis Report for B1-010-001-CIGS-BO02-SB B1-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty K-40 0 . 99 1460 . 75
- 10.67 5 .38 E+OO 9.16E-01 PB-212 0 . 55 77 .11 17 .so 238 . 63
- 44 . 60 2. llE-01 4 . 27E-02 BI-214 0 . 34 609.31
- 46 .3 0 l.18E-0 1 6.12E-02 1120.29 15.10 1238 . 11 5.94 1377.67 4 . 11 1407.98 2.48 1509.19 2 . 19 1764 . 49 15.80
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)
K-40 0 . 994 S . 38E+OO 9 . 16E- 01 PB-212 0.559 2 . llE- 01 4.27E-02 BI-214 0 . 341 l .1 8E-01 6 . 12E-02
6/13/2019 5:51 :23AM Page4 of6 Analysis Report for B1-010-001-CIGS-BD02-SB B1-010-001 B
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/13/2019 5:51:23AM Page 5 of6 Analysis Report for 8 1-010-001-CIGS-BO02-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/13/2019 5:51:14AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide F 2 295 . 07 1 . 91251E - 02 29 . 00 Tol. PB- 214 F 3 338 . 16 1 . 636 40E - 02 28 . 54 Tol. AC- 228 PA-228 F 4 583 . 10 1 . 85751E-02 22 . 06 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity Nucl/deMDA LlneMDA Name (pCVgrams) (pCVgrams) (pCVgrams) (ke V) + K- 40 1460 . 75
- 10 . 67 5 . 3 8E+0O 8 . 33E - 0l 8 . 33E- 01
+ @ AR- 4 1 1293 . 64 99 . 16 1 . 00E+26 l . 00E+26 1. 00E+26 + CO- 60 1173 . 22 1 0 0 . 00 4 . 37 E- 02 7 . 51E-02 9 . 80E - 02 1332 . 49 100 . 00 1. 96E- 03 7 . Sl E- 02 + KR- 85 513 . 9 9 0 . 43 8 . 64E+0O 1. 41E+0l l . 41E+Ol + Y- 88 898 . 04 93 . 70 6 . 09E- 03 5 . 59E - 02 6 . 66E-0 2 1836 . 06 99 . 20 2 . 60E- 02 5 . 59E- 02 + NB- 94 702 . 63 100 . 00 - 5 . 59E - 02 5 . 82E- 02 5 . 82E - 02 871 . 10 100 . 00 -2 . 87E- 02 6 . 47E- 02 + I - 131 28 4. 30 6 . 06 - 1 . 96E-0 1 1. 07E- 01 l . 37 E+0O 3 6 4 . 48 81.20 9 . 87E- 02 1 . 07 E- 01 636 . 97 7 . 27 1 . 27E+OO 1. 51E+00 + CS -1 34 60 4. 70 97 . 60 - 3 . 47E- 02 7 . 21E- 02 7 . 21E- 02
6/13/2019 5:51 :23AM Page6 of 6 Analysis Report for 81 -010-001-CIGS-8D02-SB 81-010-001 B Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCi/grams) (pCi/grams) (pCilgrams) (keV} CS-134 795 . 84 85 . 40 -8 . 48E - 02 7 . 21E-02 7 . 73E-02 + CS - 137 661 . 65 85 . 12 6 . 09E - 02 8 . 28E - 02 8 . 28E - 02 + CE-1 44 80 . 12 1. 36 - 2 . 57E+OO 3 . 89E-01 4 . 95E+OO 133 . 51 11.09 -1. 77E-01 3 . 89E - 01 + EU- 152 121 . 78 28 . 40 2 . 17E-02 1 . 53E-Ol 1. 53E - Ol 344 . 2 8 26 . 60 - 4 . 18E-O l 1. 88E - 01 1408 . 00 20 . 74 3 . 64E - 02 3 . 61E- Ol + EU- 154 123 . 07 40 . 40 1. 33E- 02 1. 08E - 01 1 . 08E- 01 723 . 30 19 . 70 - 9 . 21E- 02 2 . 86E - 01 1 27 4.51 35 . 50 1 . 03E - 02 2 . 27E-01 + EU- 155 86 . 54 32 . 80 5 . 91E -02 1 . 77E- 01 1 . 77E- 01 1 05 . 3 1 21. 80 - 3 . 23E - 02 2 . 07E- 01 + BI-214 609 . 31
- 46 . 30 1.lBE- 01 1 . 05E- 01 1 . 0SE- 01 1 120 . 29 15.10 - 2 . 26E- 01 5 . 7 1 E-O l 1238 . 11 5 . 94 5 . 12E- 01 1. 54E+OO 1377 . 67 4 . 11 2 . lOE- 01 1 . 48E+OO 1407 . 98 2.48 3 . 04E- 01 3 . 0lE+OO 1509 . 19 2 . 19 5 . 94E- Ol 2.58E+OO 1764 . 49 15 . 80 1 . 91E- 01 4 . 35E- Ol
+ PB- 214 77 .11 10 . 70 4 . SO E- 01 1 .4 6E- 0 1 6.62E-01 295.21 1 9 . 20 5 . 70E- 03 2.73E-01 351. 92 37 . 20 1. 0 4E-01 1. 46E-01 + PA-228 89 . 95 22 . 00 4 . 29E+Ol 2 . 43E+Ol 4.27E+Ol 93 . 35 35 . 00 - 1 . 72E+Ol 2 . 43E+Ol 105 . 00 1 6 . 30 9 . 89E+OO 4. 67E+Ol 129.22 2 . 97 - 3 . 56E+Ol 2 . 43E+02 338 . 32 5 . 30 6 . 30E+Ol 1. 58E+02 463 . 00 1 3 . 80 - 2 . 25E+Ol 6 . 25E+Ol 911 .2 3 1 6 . 70 l . 77E+OO 7 . 63E+Ol + AM- 241 59 . 54 36 . 30 7 . 15E- 02 3 . 21E- Ol 3 . 21E - 01 + CM- 243 103 . 76 23 . 00 l. 4 5E- 01 2 . 0lE-01 2 . 0lE-01 228 . 18 10 . 60 - 4 . 39E -0 2 4 . 15E-01 277 . 60 1 4 . 00 -3 . 7 4E - 02 3 . 38E - 01
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/13/2019 6:22:14AM Page 1 of5 _.Apex-Gamma Analysis Report for B1-010-001-CIGS-BE01-SB B1-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BE01-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 8.367E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/6/2019 9:17:00AM Acquisition Started : 6/13/2019 5:51:56AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live lime : 1800.0 seconds Real lime : 1805.2 seconds Dead lime : 0.29% Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6823 PEAK ANALYSIS REPORT Peak Analysis Perfonned on : 6/ 13/2019 6:22:05AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/13/2019 6:22:14AM Page 2 ofS Analysis Report for B1-010-001-CIGS-BE01-SB B1-010-001 B Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 58 472 - 485 477 . 64 1 . 74E+02 33 . 47 2 . 68E+ 02 2 . 02 F 2 295 . 15 587 - 595 590 . 7 5 4. 93E+Ol 20 . 24 1. 40E+02 1. 2 6 F 3 582 . 97 1159 - 1172 1166 . 28 4. 73E+Ol 16 . 39 6 . 64E+O l 1. 48 F 4 609 . 62 1213 - 1 226 1219 . 58 4. 82E+Ol 17 . 75 6 . 30E+Ol 2 . 33 F 5 1460 . 87 2914 - 2929 2921 . 8 4 2 . 28E+02 30 . 67 1 . 58E+Ol 2 . 60 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/13/2019 6:22:0SAM Env. Background File : C:\Canberra\Apex\ Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 58 l . 74E+02 33 .4 7 l . 74E+02 3 . 35E+Ol F 2 295 . 15 4 . 93E+Ol 20 . 24 4 . 93E+Ol 2 . 02E+Ol F 3 582 . 97 4 . 73E+Ol 16 . 39 4 . 73E+Ol 1. 64E+Ol F 4 609 . 62 4 . 82E+Ol 17 . 75 2 . 06E+ Ol 1. 2 1E+Ol 2 . 76E+Ol 2 . 15E+Ol F 5 1460.87 2 . 28E+02 30 . 67 2 . 82E+Ol 8 . 57E+OO 2 . 00E+02 3 . 18E+Ol M = First peak in a multiplet reg ion m = Other peak in a multiplet region F = Fitted singlet Errors quoted al 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C :\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES
6/13/2019 6:22:14AM Page3 ofS Analysis Report tor B1-010-001-CIG~BE01 -SB B1-010-001 B Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K-40 0 . 99 1460 . 75
- 10 . 67 5 . 20E+00 8.78E- 01 PB- 212 0 . 56 77 . 11 17 . 50 238 . 63
- 4 4. 60 2 . 14E-0 l 4 . 27E-02 BI- 214 0 . 34 609 . 31
- 46 . 30 7 . 61E-02 5 . 93E - 02 1120 . 29 15 . 10 1238 . 11 5 . 94 1 377 . 67 4 . 11 1407 . 98 2 . 48 1509 . 19 2 . 19 176 4.4 9 15 . 80
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000slgma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)
K- 40 0 . 998 5 . 20E+00 8 . 78E- 01 PB- 212 0 . 560 2 . 14E- 01 4 . 27E- 02 BI-214 0 . 34 2 7 . 61E-02 S.93E-02
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used In Weighted Mean Activity Errors quoted at 2.000sigma
6/13/2019 6:22:14AM Page 4of5 Analysis Report for B1-010-001-CIGS-BE01-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/13/2019 6:22:0SAM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide F 2 295 . 15 2 . 736 22£- 02 2 0. 55 Tol. PB-214 F 3 582 . 97 2 . 62882 £- 02 17 . 32 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield{3/4) Activity NuclldeMDA L/neMDA Name {pCVgrams) (pCi/grams) (pCVgrams) (keV) + K- 40 1460 . 75
- 10 . 67 5 . 20E+00 7.88E- 01 7 . 88E-01
+ @ AR- 41 1293 . 64 99 . 16 1 . 00E+26 1 . 00E+26 1 . 00 E+26 + CO-6 0 1173 . 22 1 0 0 .0 0 2 . 2 6E- 02 7. 58E- 02 8 . 99E- 02 1332 . 49 100 . 00 - 2 . 12£- 0 2 7 . 58£- 02 + KR- 85 513 .9 9 0 . 43 - 2 . 21E - 01 1 . 36E+0l 1. 36E+0l + Y-88 8 98 . 0 4 93 . 70 2 . 88E - 0 2 5 . 62E- 02 7 . 71E- 02 1836 . 06 99 . 20 -7 . 97E - 03 5 . 62E- 02 + NB- 94 7 02 . 63 100 . 00 2 . 97E - 03 6 . 28E- 02 6 . 32£- 02 8 71 . 1 0 1 00. 00 - 2 .1 9£ - 02 6 . 2 8£ - 02 + I - 131 28 4. 30 6 . 06 - 2 . 9 4£ - 01 1. 0 4E- 01 l .3 4E+00 36 4. 48 81 . 20 8 . 59E -03 1. 04E- 01 636 . 97 7 .27 -2 . 86E -0 1 1. 33E+00 + CS- 134 60 4 . 70 97 . 6 0 5 . 67 E- 03 7 . 20£- 0 2 7 . 20 E- 0 2 795 . 84 85 .4 0 2 . 27£ - 02 7 . 31E- 02 + CS- 137 661. 65 8 5 . 12 7 . 47 E- 02 8 . l0E-02 8. l0 E- 02 + CE-144 80 .1 2 1. 36 3 . 42 E+00 3 . 87E- 01 4 . 92£+00
6/13/2019 6:22:14AM Page 5 of5 Analysis Report for B1-010-001-CIGS-BE01-SB B1-010-001 B Nuclide Energy Yield(%) Activity NuclideMDA LlneMDA Name (pCUgrams) (pCilgrams) (pCilgrams) (keV) CE-144 133.51 11.09 1 . 44E-01 3.87E- 01 3.87E-01 + EU-152 121.78 28.40 -6.75E-02 1.S0E- 01 l .S0E-01 344.28 26.60 -5.96E-0l l .84E-01 1408.00 20.74 -2 . 02E-01 2 . 61E-01 + EU- 154 123.07 40.40 l.86E-02 1 . 0SE-01 l.05E-0 l 723.30 19.70 -6.09E-02 3.07E- 01 1274.51 35.50 4.18E-02 2.36E-01 + EU-155 86 . 54 32 . 80 -9.86E-02 1. 63E-01 l.63E-0 1 105 . 31 21. 80 -7.07E-02 2.08E-01 + BI-214 609.31
- 46 . 30 7 . 61E-02 1.16E-0 1 l.16E - 01 1120 . 29 15 . 10 9 . 57E-02 5.34E-01 1238 .11 5.94 -1 . 77E+00 1.50E+00 1377.67 4 . 11 6 . 72E-01 1.67E+00 1407.98 2 . 48 -1 . 69E+00 2.18E+00 1509 . 19 2.19 6 . 20E- 01 2 . 70E+00 1764.49 15.80 2 . 88E -0 1 4.14E-01
+ PB-214 77 .11 10.70 7.69E-01 l . 40E-01 6 . 64E-0 1 295.21 19 .20 2.30E-01 2 . 69E-01 351. 92 37.20 1 .07E-0l 1. 40E-0l + PA-228 89.95 22 . 00 3 . 28E+0l 2 . SSE+0l 4.28E+0l 93.35 35 . 00 -3.00E-01 2 . 55E+O l 105.00 16.30 6.02E+00 5 . 04E+0l 129.22 2.97 -1.51E+02 2.52E+02 338.32 5 . 30 2.08E+02 l . 63E+02 463.00 13 . 80 3.70E+0l 6.65E+0l 911 . 23 16.70 7 . 44E+0l 8.08E+0l + AM-241 59.54 36 . 30 - l . 02E-01 3 . l0E-01 3.l0E-01 + CM-243 103.76 23 . 00 6.91E-02 2.0lE-01 2.0lE-01 228.18 10 . 60 l . 91E-01 3 . 98E-01 277.60 14 . 00 -3 . 26E - 01 3.20E-01
+ = Nuclide identified during the nuclide identification * = Energy line found in the spectrum > = MDA value not calculated @ = Half-life too short to be able to perform the decay correction ? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/13/2019 6:59:14AM Page 1 of7 _.Apex-Gamma Analysis Report for B1-010-001-CIGS-BE02-SB B1-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BE02-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 8.556E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/6/2019 9:28:00AM Acquisition Started : 6/13/2019 6:28:56AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.4 seconds Dead Time : 0.30% Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6824 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/13/2019 6:59:0SAM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/13/2019 6:59:1 4AM Page 2 of7 Analysis Report for B 1-010-001-CIGS-BE02-SB B1-010-001 B Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 62 469 - 485 477 . 72 1 . 55E+02 31. 56 3 . 16E+02 1. 84 F 2 35 1 . 96 697 - 712 704 . 35 l . 04E+02 25 . 20 l . 39E+02 2 . 23 F 3 582 . 84 1159 - 1174 11 66 . 03 4 . 24E+Ol 1 7 . 12 6 . 05E+Ol 2 . 79 F 4 609 . 21 12 1 5 - 1225 1218 . 75 5.19E+Ol 17 . 22 6 . 12E+Ol 1. 35 F 5 910.78 1816 - 1827 182 1. 80 3 . 20E+Ol 14 . 36 4. 30E+Ol 1. 83 F 6 968 . 68 1933 - 1942 1937 . 57 l . 55E+Ol 10 . 96 3 . 80E+Ol 1. 37 F 7 14 60 . 83 29 1 3 - 2930 292 1. 7 6 2 .4 4E+02 31. 93 l . 76E+Ol 2 . 77 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/13/2019 6:59:0SAM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 62 1 . 55E +02 31. 56 1 . 55E+02 3 .1 6E+Ol F 2 351 . 96 1. 04E+02 25 . 20 4 . 18E+Ol 1. 86E+Ol 6 . 22E+Ol 3 . 13E+Ol F 3 582 . 84 4 . 24E+Ol 17 . 12 4 . 24E+Ol l . 71E+Ol F 4 609 . 21 5 . 19E+Ol 17 . 22 2 . 06E+Ol l . 21E+Ol 3 . 13E+Ol 2 . lOE+Ol F 5 910 . 78 3 . 20E+Ol 14 . 36 3 . 20E+Ol 1. 44E+Ol F 6 968 . 68 l . 55E+Ol 10 . 96 1. 55E+Ol 1. lOE+Ol F 7 1460 . 83 2 . 44E+02 31. 93 2 . 82E+Ol 8 . 57E+OO 2 . 16E+02 3 . 31E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/13/2019 6:59:14AM Page 3 of7 Analysis Report for B1-010-001-CIGS-BE02-SB B1-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairyland_NPP\library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (keV) (pCl/grams) Uncertainty K- 40 0 . 99 1460 . 75
- 10 . 67 5 .4 9E+OO 8 . 96E-01 PB-212 0 . 56 77 . 11 1 7 . 50 238 . 63
- 44 . 60 1. 86E - Ol 3 . 93E-02 BI - 21 4 0 . 34 609 . 31
- 46 . 30 8 . 43E - 02 5 . 68E- 02 1120 . 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2 . 48 1509 . 19 2 . 19 1764 . 49 15 . 80
* = Energy line found In the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams)
K- 40 0 . 999 5 . 49E+OO 8.96E- 01 PB- 212 0 . 560 1 . 86E-01 3 . 93E- 02 BI-214 0.349 8 . 43E- 02 5 . 68E- 02
6/13/2019 6:59:14AM Page4of7 Analysis Report for B1-010-001-CIGS-BE02-SB B1-010-001 B
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/ 13/2019 6:59:14AM Page5 of7 Analysis Report for 8 1-010-001 -CIGS-BE02-SB 81-010-001 B UNIDENTIFIED PEAKS Peak Locate Perfomied on : 6/13/2019 6:59:0SAM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS (%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nucllde F 2 351 . 96 3 . 45769E- 02 25 . 17 Tol. PB-214 F 3 582 . 84 2 . 35425E-02 20 . 20 F 5 910 . 78 1 . 77914E-02 22 . 42 Tol. AC- 228 PA- 228 F 6 968 . 68 8 . 63669£-03 35 . 26 Tol. AC- 228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\iibrary\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCUgrams) (pCilgrams) (pCUgrams) (keV) + K- 40 1460 . 75
- 10 . 67 5 . 49£+00 7 . 93£-01 7 . 93£-01
+ @ AR- 41 1293 . 64 99 . 16 1 . 00E+26 1 . 00E+26 l . 00E+26 + CO- 60 11 73 . 22 1 00 . 00 -1. 84£- 02 6 . 88E-02 8.09E-02 1332 . 49 100.00 2 . 14£- 02 6 . 88£-02 + KR-85 513 . 99 0 . 43 1. 08£+01 1 . 44E+ 0l 1. 44E+Ol + Y- 88 898 . 04 93 . 70 - 2 . 54E - 02 5.20E - 02 6 . 98E - 02 1836.06 99 . 20 - 2 . 75£- 02 5 . 20E-02 + NB-94 702.63 100 . 00 4 . 61E-03 5 . 28E-02 5 . 54E-02 87 1 . 1 0 1 00.00 - 2 . 96£-02 5 . 28E - 02 + I - 131 284.30 6 . 06 2 . 52E-01 9 . 92£- 02 1 . 33E+0O
6/13/2019 6:59:14AM Page6 of7 Analysis Report for B 1-010-001-CIGS-BE02-SB 81-010-001 B Nuclide Energy Yield(%) Activity Nucl/deMDA LineMDA Name (pCi/grams) (pCi/grams) (pCi/grams) (keV) I-131 364 . 48 81. 20 2.67E-02 9 . 92E-02 9.92E-02 636 . 97 7.27 -1.31E-01 l . 32E+OO + CS-134 604.70 97. 60 -6 . 49E-02 7. 1 9E-02 7 . 19E-02 795.84 85.40 -2.67E-03 7.48E-02 + CS-137 661 . 65 85.12 2 . 59E-02 7.28E-02 7 . 28E-02 + CE-144 80.12 1.36 - l . 13E+OO 3.70E-01 4 . 86E+OO 133. 51 11. 09 -9.09E-02 3 . 70E-Ol + EU-152 121.78 28.40 -3.79E-02 1. 43E-01 1 . 43E -0 1 344 . 28 26. 60 8.52E-02 l . 94E-01 1408.00 20.74 2 . 20E-01 3.05E-01 + EU-154 123.07 40.40 3 . 49E-02 1. Ol E-01 1. OlE-01 723 . 30 19 . 70 3 . 02E-02 3 . 00E-01 1274.51 35 . 50 4 . 05E-02 2 . 26E-Ol + EU-155 86.54 32.80 -1 . 65E-0 1 1. 67E - 01 l.67E-01 105.31 21. 80 1 . 68E-01 1 . 98E-01 + BI-214 609 . 31
- 46 . 30 8 .4 3E-02 1. 09E-01 1. 09E-01 1120 . 29 15 . 10 3 . 03E-01 5 . 66E-01 1238 . 11 5.94 4.85E-01 l.49E+OO 1377.67 4 .11 5 . 25E-01 l . 60E+OO 1407 . 98 2.48 1. 84E+OO 2.SSE+OO 1509.19 2 . 19 l.53E+OO 2 . 40E+OO 1764 .49 15.80 2.66E- 01 4 . 52E - 01
+ PB-214 77 . 11 10 . 70 6 . 23E-01 l . 52E- 01 6 . 60E - 01 295 . 21 19.20 2.19E-01 2 . 46E-01 351 . 92 37.20 2 . 46E-01 l . 52E-01 + PA-228 89 . 95 22.00 6.69E+Ol 2.51E+Ol 4 . 42E+Ol 93.35 35.00 -8.72E+OO 2.51E+Ol 105.00 16. 30 2.42E+Ol 4.81E+Ol 129 . 22 2.97 -1 . 56E+02 2 . 48E+02 338.32 5.30 1 . 07E+02 l.69E+02 463 . 00 13 . 80 3 . 29E+Ol 6 . 62E+Ol 911. 23 16 . 70 1 . 01E+02 9.00E+Ol + AM-241 59 . 54 36.30 2.33E-Ol 3.02E-01 3.02E-01 + CM-243 103.76 23 . 00 8 . 92E-02 1 . 88E-01 1.88E-01 228.18 10.60 1 . 44E-Ol 3 . 88E-01 277 . 60 14 . 00 2 . 70E-01 3 . 43E-Ol
+ =
=
Nuclide identified during the nuclide identification Energy line found in the spectrum
> = MDA value not calculated @ = Half-life too short to be able to perform the decay correction ? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/13/2019 6:59:14AM Page 7 of7 Analysis Report for B1-010-001-CIGS-BE02-SB B1-010-001 B
6/10/2019 12:38:04PM Page J of 7 __.Apex-Gamma Analysis Report for B1-010-001-CIGS-BF01-SB 81-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BF01-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 8.422E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/6/2019 8:40:00AM Acquisition Started : 6/10/2019 12:07:41PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.6 seconds Dead Time : 0.31 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6767 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/ 10/2019 12:37:SSPM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/ 10/2019 12:38:04PM Page2 of7 Analysis Report for 81-01 0-001 -CIGS-8F01-S8 81-010-001 B Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 59 471 - 485 477 . 65 1 . 96E+02 35 . 84 3 . 49E+02 1. 96 F 2 295 . 37 586 - 595 591. 18 4 . 70E+O l 18 . 24 1. 54E+ 02 0 . 81 F 3 338 . 01 669 - 681 67 6 . 4 5 3 .0 9E+Ol 19 . 54 l . 89E+02 1. 58 F 4 35 1. 92 699 - 711 704 . 27 9.64E+Ol 23 . 87 9 . 76E+O l 2 . 07 F 5 583 . 15 11 63 - 1173 1166 . 64 4 . 28E+Ol 1 6 . 87 5 . 92E+Ol 2 . 03 F 6 608 . 86 1 214 - 1224 1218.06 6 .3 6E+Ol 18 . 83 5 . 72E+Ol 1. 63 F 7 726 . 68 1450 - 1457 1453 . 65 1 . 29E+Ol 4 . 45 3 . 54E+Ol 0 . 60 F 8 910 . 97 1817 - 1827 1822 . 18 3 . 52E+Ol 13 . 71 2 . 20E+Ol 1. 90 F 9 1460. 40 2914 - 2929 2920. 92 2 . 75E+02 33.83 1 . 83E+Ol 2 . 46 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/10/2019 12:37:55PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 59 1 . 96E+02 35 . 8 4 1 . 96E+02 3 . 58 E+Ol F 2 295 . 37 4 . 70E +Ol 18 . 24 4 . 7 0E+Ol 1. 82E+Ol F 3 338.01 3 . 09E+Ol 1 9 . 54 3 . 09E+Ol 1. 95E+O l F 4 35 1. 92 9 . 64E+Ol 23 . 87 4.1 8E+Ol l . 86E+Ol 5 . 46E+O l 3 . 03 E+Ol F 5 583 . 15 4 . 28E +Ol 16 . 87 4.28E+Ol 1.69E+Ol F 6 608 . 86 6 . 36E+O l 18.83 2 . 0 6E+Ol 1 . 2 1E+Ol 4 . 3 0E+Ol 2 . 24E+Ol F 7 726 . 68 1. 29E+Ol 4 . 45 1. 29E+Ol 4 . 45E+OO F 8 910.97 3 . 52E+Ol 13 . 71 3 . 52E+Ol 1 . 37E+Ol F 9 1460 . 40 2 . 75E+02 33 . 83 2 . 82E+Ol 8.57E+OO 2 . 47E+02 3 . 49E+Ol
=
M First peak in a multiplet region
=
m Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/ 10/2019 12:38:04PM Page 3 of? Analysis Report for B1-0 10-001 -CIGS-BF01-SB B1 -010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K-40 0 . 98 1460 . 75
- 10 . 67 6.40E+OO 9.70E - 01 BI-212 0 . 57 727 .1 7
- 11. 80 1.63E-01 5 . 67E - 02 785.42 2 . 00 1620 . 56 2 . 75 PB-212 0 . 56 77 . 11 17 . 50 238 . 63
- 44.60 2 . 40E-0 1 4 . 56E-02 BI-214 0 . 33 609 . 31
- 46 . 30 1. 18E- 01 6 . 15E- 02 1120 . 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2 .4 8 1509 . 19 2 . 19 1764 . 49 15 . 80 PB- 214 0 . 72 77 . 11 10 . 7 0 295 . 21
- 1 9 . 20 1 . 60E-01 6 . 25E- 02 351. 92
- 37 . 20 1.12E- 01 6 . 23E-02
* =Energy line found in the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence (pCi/grams) Uncertainty
6/ 10/2019 12:38:04PM Page4of7 Analysis Report for B1 -010-001-CIGS-BF01-SB 81-010-001 B Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) K- 40 0 . 981 6.40E+00 9 . 70E- 01 BI -212 0 . 578 1 . 63E - 01 5.67E-02 PB- 212 0 . 560 2 . 40E-0l 4.56E-02 BI - 214 0 . 334 1 . 18E-01 6 . 15E- 02 PB- 214 0 . 720 1.36E- 01 4.41E- 02
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
611012019 12:38:04PM Page 5 of7 Analysis Report for 81-010-001-CIGS-BF01-SB 81-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 611012019 12:37:55PM Peak Locate From Channel : 100 Peak locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide F 3 338 . 01 l . 71573E - 02 31. 63 Tol. AC- 228 PA-228 F 5 583 . 15 2 . 37796E- 02 19 . 71 F 8 910 . 97 1 . 95518E- 02 1 9 . 48 Tol. AC- 228 PA-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Ubrary\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity Nuc/ideMDA LineMDA Name (pCl/grams) (pCIJgrams) (pCVgrams) (keV)
+ K- 40 1460.75
- 10 . 67 6 . 40E+00 7 . 97E- 01 7 . 97E-01
+ AR-41 1293 . 64 99 . 16 - 3 . 67E+l4 2 . 03E+l5 2 . 03E+l5 + CO- 60 1173 . 22 100 . 00 - 4 . 71£- 02 7 . 62E- 02 8 . 72E-02 1332 . 49 100 . 00 3 . 57E- 02 7 . 62E - 02 + KR- 85 513 . 99 0 . 43 1. 59E+0 l 1 . 35E+0l 1. 35E+0l + Y-88 898 . 04 93 . 70 3 . 95E- 02 5 . 49E-02 7 . 35E-02 1836 . 06 99 . 20 1 . 0lE - 02 5 . 49E- 02 + NB- 94 702 . 63 100 . 00 3 . 07E - 02 6 . 30E- 02 6 . 50E- 02 871 . 10 1 00 . 00 - 2 . 04E- 03 6.30E- 02 + I - 131 28 4 . 30 6 . 06 3 . 41E- 01 7 . 99E - 02 l . 07E+00 364 .4 8 81.20 1. 73E-02 7 . 99E - 02
6/10/2019 12:38:04PM Page 6 of7 Analysis Report for B 1-010-001-CIGS-BF01-SB B1-010-001 B Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCilgrams) (pCi/grams) (pCl/grams) (keV) I-131 636 . 97 7.27 - 2 . 60E- 0 1 7 . 99E- 02 1 . 04E+OO + CS-134 604 . 70 97 . 60 -7 . 49E-0 2 7 . 52E- 02 7 . 52E-02 795 . 84 85 . 40 9 . 33E- 03 8 . llE - 02 + CS-1 37 661 . 65 85 . 12 8 . 00E-02 7 . 71E-02 7 . 7 1E-02 + CE- 144 80 . 12 1.36 1 . 40E+OO 3 . 98E- 01 4 . 86E+OO 133 . 51 1 1. 09 1. 17E- 0 1 3 . 98E - 01 + EU- 152 121. 7 8 28.40 - 6 . 02E- 03 l . 55E - Ol l . 55E- Ol 3 4 4 . 28 2 6 . 60 - 7 . 52E- 02 1 . 99E - Ol 1408 . 00 20 . 74 4 . 62E- 02 2 . 97E- Ol + EU - 154 123 . 07 4 0 . 40 - 4 . 66E-02 1 . 0BE - 01 1 . 08E- 01 723 . 30 19 . 70 2 . 27E-01 3 . 4 9E-01 1274 . 51 35 . 50 1 . 35E-0 1 2 . 27E- 0 1 + EU- 155 86 . 54 32 . 80 3 . 06E - 02 1 . 71E - Ol 1 . 7 1E- Ol 1 05 . 31 21. 80 l. 34E-01 l. 98E-01 + BI - 2 1 4 609 . 31
- 4 6 . 30 l.1 8E-01 1. 0 9E-01 1. 09E- 0 1 1120 . 29 15 . 10 5 . 49E - Ol 5 . 67E- 01 1238 . 11 5 . 94 - 5 . 93E-0 4 1 . 65E+OO 1377 . 67 4 . 11 - 5 . 27E- 01 l . 53E+OO 1 4 07 . 98 2 .4 8 3 . 86E - 0 1 2 .4 8E+OO 1 509 .1 9 2 . 19 l . 07E+OO 2 . 6 1E+OO 1764. 49 15 . 80 - 2 . 96E - 02 4. 59E- 01
+ PB- 2 1 4 77 . 11 10 . 70 4 . 68E-01 1 . 1 4E- 01 6 . 62E-01 295 . 21
- 19 . 20 1 . 60E - Ol 1. 58E- 01 351. 92
- 37 . 20 1 . 12E- 01 1 . 14E- 01
+ PA- 228 89 . 95 22 . 00 6 . 63E+OO 3 . 38E+OO 5 . 77E+OO 93 . 35 35 . 00 1 . 39E+OO 3 . 38E+OO 105 . 00 16 . 30 4 . 99E+OO 6 . 19E+OO 129 . 22 2 . 97 - 1 . 0lE+Ol 3 . 3 9E+ Ol 338 . 32 5 . 30 2 . 0 4E+Ol 2 . 32E+Ol 463 . 00 13 . 80 5 . 41E+OO 8 . 91E+OO 911 . 23 16 . 70 8 . 13E+OO 1 . 13E+Ol + AM- 241 59 . 54 36 . 30 - 5 . 52E-02 3.13E- 01 3 . 13E-01 + CM-2 43 103 . 76 23 . 00 8 . 22E - 02 1. 91E-01 l . 91E-01 228 . 18 1 0 . 60 -2 . 84E -0 2 3 . 96E- 0 1 277 . 60 1 4 . 00 7 . 97E-02 3 . 29 E- 0 1
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perfonn the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/10/2019 12:38:04PM Page 7 of7 Analysis Report for B1-010-001-CIGS-BF01-SB B1-010-001 B
6/10/2019 1:17:41PM Page 1 of6 _...Apex-Gamma Analysis Report for B1-010-001-CIGS-BF02-SB B1-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BF02-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 7.159E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/6/2019 8:46:00AM Acquisition Started : 6/10/2019 12:47:23PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.5 seconds Dead Time : 0.30 % Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100 - 4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6768 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/10/2019 1:17:32PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/10/2019 1:17:41PM Page2 of 6 Analysis Report for 81-010-001-CIGS-BF02-SB 81-010-001 8 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 42 469 - 481 477 . 31 1 . 22E+02 30 . 26 2 . 88E+02 1. 67 F 2 29 4 . 97 587 - 596 590 . 39 3 . 47E+0l 18 . 70 1. 56E+02 1. 31 F 3 3 38 . 27 673 - 682 676 . 97 1 . 98E+0l 12 . 96 l . 10E+02 0 .8 1 F 4 351 . 7 4 700 - 709 703 . 91 8 . 97E+0l 22 . 50 9. 90E+ Ol 1. 31 F 5 609 . 3 2 1213 - 1225 1 218 . 97 5 . 09E+0l 17 . 05 5. 08E+Ol 1. 90 F 6 91 0 .96 18 1 5 - 1 828 182 2.1 6 3. 7 4E+0l 14 . 21 2 . 8 2E+Ol 2 . 17 F 7 14 60 . 7 2 2 91 4 - 2 93 0 2 92 1. 55 2 . 16E+02 29 . 55 3 . 76E+OO 2 . 68 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/10/2019 1:17:32PM Env. Background File : C:\Canberra\Apex\Root\Dalryland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 42 1 . 22E+02 30 . 26 l . 22E +02 3 . 03E+Ol F 2 29 4. 97 3 . 47 E+0l 1 8 . 70 3 .4 7E+0l 1. 87E+0l F 3 338 . 27 1 . 98E+0l 12 . 96 1 . 98E+0l 1 . 30E+0l F 4 351 . 74 8 . 97E+0l 22 . 50 4 . 18E+0 l 1. 86E+0 l 4 . 7 9E+0l 2 . 92E+0l F 5 609 . 32 5 . 09E+0l 1 7 . 05 2 . 06E+0 l 1. 21E+0 l 3 . 03E+0l 2 . 09E+0l F 6 9 1 0 . 96 3 . 74E+0l 1 4. 21 3 . 7 4E+Ol 1.4 2E+Ol F 7 1460 . 72 2 . 16E+0 2 29 . 55 2. 82E+0l 8 . 57E+00 1. 88E+02 3 . 08E+0l M =First peak in a multiplet region
=
m Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/10/2019 1:17:41PM Page 3 of6 Analysis Report for B1-010-001-CIGS-BF02-SB B1-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nucllde Id Energy Vleld(%) Activity Activity Name Confidence (keV) (pC//grams) Uncertainty K-40 1.00 1460 . 75
- 10 . 67 5 . 72E+OO 9.89E-01 PB-212 0 . 55 77 . 11 17 . 50 238 . 63
- 44.60 1.76£-01 4.45E-02 BI-2 1 4 0 . 35 609 . 31
- 46.30 9 . 76E- 02 6.75E-02 1120. 29 15 . 10 1238 .11 5.94 1377.67 4.11 1407.98 2.48 1509 . 19 2 . 19 1764 . 49 15 .80 PB-214 0 . 71 77 . 11 10 . 70 295 . 21
- 19 .2 0 1. 38E- 01 7.SOE-02 351. 92
- 37 . 20 1.16£- 01 7 . 07E- 02
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
=
@ Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV
=
Nuclide confidence index threshold 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams) K-40 1 . 000 5 . 72E+OO 9 . 89E-01 PB- 212 0 . 555 l.76E- Ol 4.45£- 02 BI-214 0.350 9 . 76E-02 6 . 75E- 02
6/10/2019 1:17:41PM Page4 of6 Analysis Report for 81-010-001-CIGS-BF02-SB B1-010-001 B Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCVgrams) PB-214 0.716 1.26£-01 5.14£-02
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/10/2019 1:17:41PM Page 5 of6 Analysis Report for B1-010-001-CIGS-BF02-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/10/2019 1:17:32PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 3 338.27 l . 10112E-02 32 . 70 Tol. AC-228 PA- 228 F 6 910.96 2.07972E- 02 18.98 Tol. AC-228 PA-228 M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCVgrams) (pCUgrams) (pCl/grams) (keV) + K-40 1460 . 75
- 10 . 67 5 . 72E+00 8 . 04E-01 8 . 04E-01
+ AR-41 1293.64 99 . 16 -2.83E+l5 2 . 92E+l5 2 . 92E+15 + CO- 60 1173 . 22 100 . 00 -6.19E-02 7 . 81E-02 9 . 49E-02 1332.49 100.00 -l.38E-02 7 . 81E-02 + KR-85 513.99 0.43 9.SlE+00 1 . 49E+0l l.49E+0l + Y-88 898 . 04 93 . 70 -6.56E-02 5 . 34E-02 7 . 02E-02 1836.06 99.20 - 5.60E-02 5.34E-02 + NB-94 702.63 100.00 -6.81E-03 6.99E-02 7.06E-02 871.10 100.00 2.16E-02 6 . 99E-02 + I-131 284.30 6.06 -3 . llE-01 8 . 82E-02 l.20E+00 364.48 81.20 - 2 . 86E-02 8.82E-02 636.97 7 . 27 9 . 41E-02 l.23E+00
6/ 10/2019 1:17:41PM Page 6 of6 Analysis Report for B1-01 0-001-CIGS-BF02-SB B1-010-001 B Nuclide Energy Yield(%) Activity Nucl/deMDA Line MDA Name (pCi/grams) (pCl/grams) (pCl/grams) (keV) + CS- 134 604 . 70 97 . 60 - 9 . 2 4E - 03 7 . 73E- 02 7.87E- 02 795 . 84 85 . 40 -3 . 93E-02 7. 7 3E- 02 + CS-137 661 . 65 85 . 12 5 . 84E-02 8 . 32E-02 8.32E- 02 + CE- 1 44 80 . 12 1.36 -9 . 5 1E-01 4 . 30E-01 5. 15E+OO 133 . 51 11.09 -2.4 4E-02 4 .30E-01 + EU- 152 12 1. 78 28 . 40 1 . 60E- 02 1 . 70E- Ol 1 . 70E- Ol 344 . 28 26.60 - 1 . 84E- Ol 2 . 18E- Ol 1408 . 00 20 . 7 4 5 . 09E- 02 3.57E- 01 + EU-154 123 . 07 40 . 40 6 . 23E -02 1 . 21E-01 l.21E-01 723 . 30 19 . 70 1.75E- 01 3 . 48E-01 1274 . 51 35 . 50 3 . 23E- 02 2 . 43E- Ol + EU- 155 86 . 54 32 . 80 -3 . 15E -02 1. 88E- 01 1. 88E-01 105 . 31 21.80 1 . 2 4E-02 2 . 31E-01 + BI-214 609 . 31
- 46.30 9 . 7 6E- 02 1 . 27E-01 1 . 27E-01 1120 . 29 15 . 10 4 . 92E- 01 6 . 67E - 01 1238 . 11 5 . 94 l . 4 9E+OO 1 . 92E+OO 1377 . 67 4 . 11 2 . 21E- 01 1. 69E+OO 1407 . 98 2 . 48 4 . 25E- 01 2 . 98E+OO 1509 . 19 2 . 19 1 . 49E+OO 3 . 59E+OO 176 4. 49 15 . 80 1 . 63E-O l 5 . 27E-01
+ PB-214 77 .11 10.70 4 . 42E-0 1 1.30E-01 6 . 97£-01 295 . 21
- 19 . 20 1. 38E - 01 l.86E - 01 351 . 92
- 37 . 20 1.1 6E- Ol l . 30E- Ol
+ PA- 228 89.95 22 . 00 6 . 77E+OO 3 . 90E+OO 6 . 62E+OO 93.35 35 . 00 - 1 . 04 E- Ol 3 . 90E+OO 105 . 00 16 . 30 9 . 12E- 01 7 . 34E+OO 129 . 22 2 . 97 1. 80E +Ol 3 . 80E+Ol 338 . 32 5 . 30 -1 . 71E +OO 2 . 41E+Ol 463 . 00 13 . 80 4 . 51E+OO 1 . 03E+Ol 911.23 16 . 70 1. 96E +Ol l . 33E+Ol + AM-241 59.54 36 . 30 1 . 60E - 01 3 . 58E-01 3 . 58E- 01 + CM- 243 103.76 23 . 00 4 . 51 E-0 2 2 . 22E - 01 2 . 22E - 01 2 2 8 . 18 10 . 60 -5 . 5 4E -02 4 . 51E- 01 277 . 60 1 4 . 00 - 1 . 77 E- 01 3 . 75E- 01
+
. = Nuclide identified during the nuclide identification
=Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/10/2019 8:13:56AM Pagel of6 ___,Apex-Gamma Analysis Report for B1-010-001-CIGS-BG01-SB B1-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BG01-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Siz.e 8.193E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/5/2019 1:39:00PM Acquisition Started : 6/10/2019 7:43:37AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.8 seconds Dead Time : 0.32 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6761 PEAK ANALYSIS REPORT Peak Analysts Performed on : 6/10/2019 8:13:47AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/10/2019 8:13:56AM Page 2 of6 Analysis Report for B1-010-001-CIGS-BG01-SB B1-010-001 B Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 61 469 - 485 477 . 70 1. 69E+02 32 . 00 3 . 19E+02 1. 69 F 2 295 . 10 587 - 597 590 . 66 5 . 67E+Ol 21. 04 1. 4 8E+02 1. 46 F 3 351.78 698 - 7 12 703 . 99 9 . 98E+Ol 24 . 34 1 . 19E+02 2 . 01 F 4 583 . 00 1159 - 1172 1166 . 34 5 . 85E+Ol 18 . 76 6 . 65E+Ol 1. 93 F 5 609 . 24 1212 - 1 224 1218 . 82 6 . 95E+Ol 19 . 66 4 . 87E+Ol 2 . 35 F 6 1460 . 97 2914 - 2932 2922 . 06 2 . 46E+02 31. 86 9 . 50E+OO 2 . 70 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/10/2019 8:13:47AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 61 l . 69E+02 32 . 00 l . 69E+02 3.20E+Ol F 2 295 . 10 5.67E+Ol 21. 04 5 . 67E +Ol 2 .lOE+Ol F 3 351 . 78 9 . 98E+Ol 24 . 34 4 . 18E+Ol 1. 86E+Ol 5 . 80E+Ol 3 . 06E+Ol F 4 583 . 00 5.85E+Ol 18 . 76 5 . 85E+ Ol l . 88E+Ol F 5 609 . 24 6 . 95E+Ol 19 . 66 2 . 06E+Ol 1. 21E+Ol 4 . 89E+Ol 2 . 3 1E+Ol F 6 1460 . 97 2 . 46E+02 31. 86 2 . 82E+Ol 8 . 57E+OO 2 . 18E+02 3.30E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma
6/ 10/2019 8:13:56AM Page 3 of6 Analysis Report for B1-010-001-CIGS-BG01-SB B1-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K- 40 0 . 99 1460 . 75
- 10 . 67 5 . 81E+OO 9 . 35E-01 PB- 212 0 . 56 77 . 11 17 . 50 238 . 63
- 44 . 60 2 . 12E- 01 4 . 18E- 02 BI-21 4 0 . 34 609 . 31
- 46 . 30 1. 37E- 01 6 . 54E- 02 1120 . 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2 .4 8 1509 . 19 2 .1 9 1764 . 49 15 . 80 PB-21 4 0 . 71 77 . 11 10 . 70 295 . 21
- 1 9 . 20 1. 98E- 01 7 . 41E - 02 351 . 92
- 37 . 20 1. 22E- 01 6 .4 9E - 02
* =Energy line found in the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)
K-4 0 0 . 992 5 . 81E+OO 9 . 35E- 01 PB- 212 0 . 560 2 . 12E- 01 4 . 18E- 02 BI - 21 4 0 . 349 1. 37E- 01 6 . 54 E- 02
6/10/2019 8:13:56AM Page4 of6 Analysis Report for B1-010-001-CIGS-BG01-SB B1-010-001 B Nuclide Nuclide wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams) PB-214 0.719 l . SSE - 01 4.88E-02
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/10/2019 8:13:56AM Page 5 of6 Analysis Report for B1-010-001-CIGS-BG01-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/10/2019 8:13:47AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 4 583 . 00 3 . 25014£- 02 16 . 03 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairytand_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA LlneMDA Name (pCUgrams) (pCUgrams) (pCUgrams) (keV} + K- 40 14 60.75
- 10 . 67 5 . 81E+0 0 7 . 65E- 01 7 . 65E-01
+ AR-41 1 293 . 64 99 . 16 - 2 . 08E+l7 5 .4 9E+17 5 . 49E+1 7 + CO-60 1173 . 22 100 . 00 5 . 39E- 02 7 . 52E - 02 9 . 66E - 02 1332 . 49 100 . 00 4 . 60E -0 3 7 . 52E - 02 + KR- 85 5 1 3 . 99 0 . 43 1 . 0SE+ 0 l l . 44 E+ 0l 1 . 44E+0l + Y- 88 898 . 04 93 . 70 l . 26E- 02 5 . 36E- 02 7 . 7 7E - 02 1836 . 06 99 . 20 - 2 . 68E- 02 5 . 36E-02 + NB- 94 702 . 63 100.00 -6 . 17E- 02 5 . 56E- 02 5 . 56E - 02 871 . 10 100 . 00 - 5 . 63E-0 2 6 . 76E - 02 + I - 131 284 . 30 6 . 06 1. 45E- 01 9 . 34E - 02 l . 21E+00 364 . 48 81.20 9 . 22E- 02 9 . 3 4E-02 636 . 97 7 . 27 - 3 . 89E- 02 1 . 19E+00 + CS - 134 60 4. 70 97 . 60 - 5 . 48E- 03 7 . 33E-02 7 . 58E - 02 795 . 84 85.40 - 1 . 02E- 02 7 . 33E - 02 + CS- 137 661. 65 85 . 12 4 . 3 7E- 02 8 . 2 7E-02 8 . 27E-02 + CE-1 44 80 . 12 1. 36 4 . 24E+ 00 3 . 92E-01 5 . llE+00 133 . 51 11.09 - 6 . 44E- 02 3 . 92E - 01
6/10/2019 8:13:56AM Page6 of6 Analysis Report for B1-010-001 -CIGS-BG01-SB 81-010-001 B Nuclide Energy Yield(%) Activity NuclideMDA LlneMDA Name (pCilgrams) (pCi/grams) (pCilgrams) (keV) + EU- 152 121.78 28 .4 0 -6.60E-02 l . 54E-Ol 1. 54E-Ol 344.28 26 . 60 8.97E-02 2.02E-Ol 1408. 00 20.74 5 . 48E-02 3.32E-01 + EU-154 123.07 40.40 -4.32E-02 1 . 08E-Ol 1 . 08E-01 723 . 30 19.70 -1 . 95E-01 3 . 04E-01 1274.51 35 . 50 5 . 41E-02 2 . 31E- 01 + EU-155 86.54 32.80 -2.38E-02 1. 72E-01 1.72E-Ol 105.31 21. 80 3 . 14E-02 2 . 09E-01 + BI-214 609.31
- 46.30 1.37E-01 l . 09E-01 1.09E-01 1120. 29 15.10 l . 50E-01 5 . 83E-Ol 1238 .11 5.94 1 . llE+OO 1 . 74E+OO 1377. 67 4.11 -1 . lOE+OO 1 . 32E+OO 1407 . 98 2.48 4 . 58E - 01 2 . 77E+OO 1509 . 19 2 . 19 1. 44E-01 2.51E+OO 1764.49 15.80 3 . 91E-Ol 5 . 37E-01
+ PB-214 77.11 10 . 70 3 . 61E-01 l.26E-01 6 . 75E-01 295.21
- 19.20 1. 98E-01 1. 63E-01 351 . 92
- 37 . 20 l . 22E - 01 1.26E-01
+ PA- 228 89.95 22 . 00 4 . 65E+OO 5 . 34E+OO 9.07E+OO 93.35 35.00 6.85E-01 5.34E+OO 105 . 00 16.30 3 . 59E+OO 1. 03E+Ol 129.22 2.97 5.13E+Ol 5.41E+Ol 338 . 32 5.30 1.84E+Ol 3.49E+Ol 463.00 13.80 8 . 73E+OO 1. 39E+Ol 911.23 16.70 8 . 43E+OO 1. 85E+Ol + AM-241 59 . 54 36.30 9 . SOE- 02 3 . 27E-01 3.27E-01 + CM-243 103.76 23.00 9.19E-02 2.0lE-01 2.0lE-01 228.18 10.60 9.45E-02 4.30E-01 277 . 60 14.00 -8.58E-02 3.45E-01
+ = Nuclide identified during the nuclide identification
= Energy line found In the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perfom, the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/10/2019 8:44:39AM Page I of6 _...,Apex-Gamma Analysis Report for 81-010-001-CIGS-8G02-S8 81-010-001 8 GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001-CIGS-8G02-S8 Sample Description : 81-010-001 8 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 7 .367E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/5/2019 1:58:00PM Acquisition Started : 6/10/2019 8:14:20AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.6 seconds Dead Time : 0.31 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6762 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/ 10/2019 8:44:30AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/10/2019 8:44:39AM Page 2of6 Analysis Report for B1-010-001-CIGS-BG02-SB B1-010-001 B Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 54 471 - 481 477 . 55 l . 28E+02 33.32 3.16E+02 1. 78 F 2 295.45 586 - 597 591. 34 3 . 38E+0l 18 . 82 2 . 11E+02 1.18 F 3 351.59 696 - 710 703 . 61 8 . 91E+0l 24 . 71 l.58E+02 2 . 14 F 4 583.10 1160 - 1172 1166 . 54 4.33E+0l 16 . 44 4.90E+0l 2 . 03 F 5 609.52 1214 - 1225 1219 . 36 6 . 00E+0l 17 . 91 5.61E+0l 1. 49 F 6 661 . 72 1317 - 1331 1323.75 2 . 18E+02 31. 42 7 . 22E+0 l 1. 92 F 7 1460.83 2914 - 2931 2921 . 78 2.41E+02 31 . 70 2.31E+0l 2 . 62 M = First peak In a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/10/2019 8:44:30AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 54 1.28E+02 33.32 1 . 28E+02 3 . 33E+Ol F 2 295 . 45 3 . 38E+0l 18 . 82 3 . 38E+0l 1. 88E+0l F 3 351.59 8.91E+0l 24 . 71 4.18E+0l 1 . 86E+0l 4.73E+0l 3.09E+0l F 4 583.10 4 . 33E+0l 16.44 4 . 33E+0l l.64E+0l F 5 609 . 52 6 . 00E+0l 17.91 2 . 06E+0l 1. 21E+0l 3.95E+0 l 2.16E+0l F 6 661 . 72 2 . 18E+02 31. 42 3 . 31E+0l 1.27E+0l 1. 85E+02 3 . 39E+0l F 7 1460 . 83 2 . 41E+02 31 . 70 2 . 82E+0l 8.57E+00 2 . 12E+02 3 . 28E+0l
=
M First peak in a multiplet region
=
m Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/10/2019 8:44:39AM Page 3 of6 Analysis Report for B1-010-001 -CIGS-BG02-SB 81-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nucllde Id Energy Yield(3/4) Activity Activity Name Confidence (keV) (pCl/grams) Uncertainty K-4 0 0 . 99 1460.75
- 10 . 67 6 . 28E+OO l . 03E+OO CS -1 37 0 . 99 661. 65
- 85 . 12 3 . 40E - 01 6 . 48E- 02 PB- 212 0 . 55 77 .11 17.50 238 .63
- 44 . 60 1. BOE-01 4.76E-02 BI-214 0 . 34 609.31
- 46.30 1 . 23E-0 1 6 . 80E- 02 1120 . 29 15 .1 0 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2 .48 1509 .1 9 2 .1 9 1764.49 15.80 PB-214 0 . 70 77 . 11 10 . 70 295 . 21
- 19.20 1. 31E- Ol 7 . 34E-02 35 1. 92
- 37 . 20 1. llE-01 7 . 27E-02
* =Energy line found In the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nucllde Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)
K-40 0 . 999 6 .2 8E+OO 1. 03E+OO CS-137 0 . 999 3 .4 0E-01 6 . 48E-02
6/10/2019 8:44:39AM Page4of6 Analysis Report for 81-010-001-CIGS-8G02-S8 81-010-001 8 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) PB-212 0 . 559 l. 80E - 01 4 . 76E- 02 BI-214 0.346 l.23E-0l 6.80E-02 PB- 214 0.709 1.21E- 01 5.17E-02
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/10/2019 8:44:39AM Page 5 of6 Analysis Report for B1-010-001-CIGS-BG02-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/10/2019 8:44:30AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 4 583.10 2.40342E-02 19 . 00 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000slgma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Ubrary\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCUgrams) (pCUgrams) (pCVgrams) (keV) + K-40 1460.75
- 10 . 67 6.28E+OO 9. 78E-01 9 . 78E - 01
+ AR-41 1293.64 99 . 16 9.90E+J!.6 6.57E+l7 6 . 57E+17 + C0-60 1173.22 100 . 00 1.05E-03 9 . 60E- 02 9 . 89E-02 1332 . 49 100.00 -2.22E-02 9 . 60E-02 + KR-85 513.99 0 . 43 1.16E+Ol 1 .69E+Ol 1 . 69E+Ol + Y-88 898.04 93.70 5 . 88E- 03 5.96E-02 7 . 44E- 02 1836 . 06 99 . 20 -9.59E-02 5 . 96E- 02 + NB-94 702.63 100.00 1 . 85E-02 6 . 24E- 02 6 . 24E-02 871.10 100 . 00 - 5 . 05E-03 6.86E- 02 + I-131 284 . 30 6 . 06 3.0lE- 01 1.04E- 01 1.31E+OO 364 . 48 81. 20 2 . 59E-02 l . 04E-01 636 . 97 7 . 27 -7 .1 5E-01 l.27E+OO + CS-134 604 . 70 97 . 60 -1.87E-02 8 . 34E- 02 8.34E-02 795 . 84 85 . 40 - 7.85E- 02 8 . 86E-02 + CS-137 661. 65
- 85 .1 2 3 .4 0E - 01 8 . 56E- 02 8.56E-02
+ CE-144 80 . 12 1. 36 -3.68£-01 4 . 31E-01 5.52E+OO 133.51 11. 09 - 8.35E - 02 4.31E-01
6/ 10/2019 8:44:39AM Page6 of6 Analysis Report for B1-01Q..001-CIGS-BG02-SB B1-010-001 B Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (keV) (pCUgrams) (pCilgrams) (pCUgrams) + EU-1 5 2 121 . 78 28 .4 0 - l. 68E - 01 1. 66E- 01 1. 66E- Ol 3 4 4 .2 8 26 . 60 l . 14E- Ol 2 . 39E- 0 1 14 08 . 00 20 . 74 8 . 57E - 02 3 . 55E- Ol + EU- 154 123 . 07 40 .4 0 - 1 . 95E - 02 1.18E- 01 1 . 18E- 01 723 . 30 19 . 70 1. 69E - 01 3 . 53E- 01 127 4 . 51 35 . 50 -3 . 27E - 02 2 . 54E- 01 + EU-1 55 86 . 5 4 32 . 80 - 4 . 53E-0 2 1 . 90E- 0 1 1. 90E- Ol 1 05 . 3 1 21. 80 7 . 89E - 02 2 . 34E- 01 + BI - 214 609 . 31
- 46 . 30 1 . 23E - 01 1 . 25E- 01 1 . 25E- 01 1120 . 29 1 5 . 10 4 . 69E - 01 6 . 91E- 01 1238 . 11 5 . 94 6 . 46E- 01 1 . 80E+OO 1377 . 67 4 . 11 7 . 55E - 02 2 . 06E+OO 1 4 07 . 98 2 .4 8 7 .1 6E - Ol 2 . 96E+OO 1509 . 19 2 . 19 - 3 . 33E - 01 3 . 16E+OO 176 4 . 49 15 . 80 4. lOE - 02 4. 40E- 0 1
+ PB- 2 14 77 . 11 1 0 . 70 9. 7 2 E- 01 l . 52E- 0 1 7 . 57E- 0 1 295 . 21
- 19 . 20 1 . 3 1E - 01 2 . 19E- 01 351 .9 2
- 37 . 20 l . llE - 01 1 . 52E-01
+ PA- 228 89 . 95 22 . 00 l . 27E+Ol 6 . 03E+OO 1 . 03 E+Ol 93 . 35 35 . 00 - 2 . 91E +OO 6 . 03E+OO 1 05 . 00 16 . 30 6 . 03.E- 0 1 1 . 15E+Ol 1 29 . 22 2 . 97 l . 48E+Ol 5 . 91E+Ol 338 . 3 2 5 . 30 3 . 50E+ Ol 4.1 9E+ Ol 463 . 00 13 . 80 - 3 . 23E+OO 1 . 70E+Ol 911 . 23 16 . 70 1 . 03E+Ol 1. 92E+Ol + AM- 2 41 59 . 54 36 . 30 - 1 .88E - Ol 3 . 49E- Ol 3. 49E- 01 + CM- 2 4 3 1 03 . 76 23 . 00 l . 06E- 02 2 . 22E- 01 2 . 22E- Ol 228 .1 8 1 0 . 60 2 . 77E- Ol 4 . 70E-0 1 2 7 7 . 60 1 4 . 00 2 . 63 E- 0 2 3 . 90E- Ol
+ =
=
Nuclide identified during the nuclide Identification Energy line found in the spectrum
> = MDA value not calculated @ = Half-life too short to be able to perform the decay correction ? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/10/2019 9:17:48AM Page I of6 ~~~~pex-Gamma Analysis Report for B1-010-001-CIGS-BH01-SB B1-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BH01-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 8.658E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/5/2019 2:26:00PM Acquisition Started : 6/10/2019 8:47:29AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.7 seconds Dead Time : 0.32 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100- 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6763 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/10/2019 9:17:39AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/10/2019 9:17:48AM Page 2 of6 Analysis Report for 81-010-001-CIGS-BH01-SB B1-010-001 B Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238.53 469 - 4 82 477 . 53 1 . 71E+02 35 . 41 3 . 91E+02 1. 60 F 2 294 . 94 584 - 595 590.32 7.94E+O l 25 . 21 2.16E+02 1. 57 F 3 338 . 20 673 - 683 676.84 2.29E+O l 15.02 l . 57E+02 0 . 91 F 4 351. 82 698 - 711 704 . 07 1.76E+02 29 . 85 1 .3 8E+02 1. 62 F 5 583 . 13 1159 - 1172 1166.60 5.85E+Ol 18. 91 l.02E+02 1. 54 F 6 609.40 1213 - 1224 1219 . 13 1 . 32E+02 24 . 59 3.90E+Ol 1. 87 F 7 661.69 1319 - 1331 1323 . 69 5 . 57E+Ol 16.55 3.66E+Ol 1. 44 F 8 911. 25 1818 - 1827 1822 . 73 l . 52E+Ol 1.28 4 . 00E+Ol 0 . 63 F 9 1460.81 2914 - 2929 2921. 73 2.29E+02 30 . 83 1.60E+Ol 2 . 41 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/10/2019 9:17:39AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 53 1 . 7 1E+02 35 . 41 1. 71E+02 3.54E+Ol F 2 294 . 94 7 . 94E+Ol 25.21 7.94E+Ol 2.52E+Ol F 3 338.20 2.29E+Ol 15.02 2 . 29E +Ol 1. SOE+Ol F 4 351.82 1.76E+02 29.85 4 . 18E+Ol 1 . 86E+Ol 1.34E+02 3.52E+Ol F 5 583.13 5.85E+Ol 18.91 5.85E+Ol 1. 89E+Ol F 6 609.40 l . 32E+02 24 . 59 2 . 06E+Ol 1. 21E+Ol 1.11£+02 2.74E+Ol F 7 661 . 69 5 . 57E+01 16 . 55 3 . 31E+Ol l . 27E+Ol 2 . 26E+Ol 2.09E+Ol F 8 911 . 25 1. 52E+Ol 1.28 l. 52E+Ol l . 28E+OO F 9 1460.81 2 . 29E+02 30 . 83 2.82E+O l 8.57E+OO 2 . 01E+02 3 . 20E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma
6/10/2019 9:17:48AM Page3 of6 Analysis Report for B1 -010-001-CIGS-BH01-SB 81-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K- 40 0 . 99 1460 . 75
- 10 . 67 5.05E+00 8 . 53E-01 CS-137 1.00 661 . 65
- 85 . 12 3 . 53E- 02 3 . 26E-02 PB- 212 0 . 55 77 . 11 17 . 50 238 . 63
- 44 . 60 2 . 04E-01 4 . 35E-02 BI-214 0.34 609 . 31
- 46 . 30 2 . 95E-01 7 .4 8E- 02 1120 . 29 15.10 1238 . 11 5 . 94 1377 . 67 4 . 11 1407.98 2 . 48 1509.19 2 . 19 1764 . 49 15 . 80 PB- 21 4 0 . 71 77 .11 10 . 70 295 . 21
- 19 . 20 2 . 62E-01 8 . 42E- 02 35 1. 92
- 37 . 20 2 . 68E-0l 7 . 14E- 02 AC- 228 0 . 30 209 . 28 4 .4 0 338 . 32
- 11 . 40 1. 44E-01 9 . 46E-02 794.70 4.60 911 . 60
- 27 . 70 9 . 71E- 02 9 . 21E- 03 964 . 60 5 . 20 969 . 11 16 . 60
* =Energy line found in the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT
6/ 10/2019 9:17:48AM Page 4 of6 Analysis Report for B1-010-001-CIGS-BH01-SB B1-010-001 B Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K- 40 0 . 999 5 . 0SE+OO 8 . 53E- Ol CS- 137 1.000 3.53E- 02 3 . 26E - 02 PB- 212 0 . 559 2.04E- Ol 4 . 35E - 02 BI - 214 0 . 349 2 . 95E- 01 7 . 48E - 02 PB- 214 0 . 717 2 . 66E - 0 1 5 . 45E- 02 AC- 228 0 . 302 9 . 76E- 02 9 . 16E- 03
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/10/2019 9:17:48AM Page5 of6 Analysis Report for B1-010-001 -CIGS-BH01-SB 81-010-001 B UNIDENTIFIED PEAKS Peak Locate Perfonned on : 6/ 10/2019 9:17:39AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide F 5 583 . 13 3 . 25254E- 02 16 . 15 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA Line MDA Name (pCilgrams) (pCi/grams) (pCi/grams) (keV) + K- 40 1460 . 75
- 10 . 67 5 . 0SE+00 7 . 64E-01 7 . 64E-01
+ AR-41 1 293 . 64 99 . 16 - 1 . 01E+l7 5.71E+17 5.71E+17 + CO - 60 1173 . 22 100 . 00 2 . 44E- 02 8 . 69E- 02 8.69E- 02 1332 . 49 100 . 00 2 . 66E - 02 8 . 77E-02 + KR- 85 513 . 99 0 . 43 7 . 33E+00 1 . 44E+0l 1. 44E+0l + Y-88 898 . 04 93 . 70 6 . 17E- 03 5 . 07E- 02 7 . 17E- 02 1836 . 06 99 . 20 - l . 91E-02 5 . 07E-02 + NB- 94 702 . 63 100 . 00 1 . 65E- 02 5 . B0E- 02 5 . 80E-02 871 . 10 100 . 00 -2 . 25E - 02 5 . 90E- 02 + I - 131 284.30 6 . 06 -2 . 57E - 01 7 . 74E-02 l.13E+00 364 . 48 81.20 - 3 . 16E- 02 7 . 74E-02 636 . 97 7 . 27 3 . 70E-01 1.lSE+00 + CS- 134 604 . 70 97 . 60 - 3 . 02E - 02 7 . 16E- 02 8 . 20E-02 795 . 84 85 . 40 - 5 . 76E - 02 7.16E- 02 + CS-137 661.65
- 85 . 12 3 . 53E - 02 6 . 08E-02 6 . 08E-02
+ CE-144 80 . 12 1. 36 9 . 43E-01 3 . 73E-01 4 . 94E+00 133 . 51 11.09 -1 . 98E - 0l 3 . 73E-01
6/10/2019 9:17:48AM Page 6 of 6 Analysis Report for B1-010-001-CIGS-BH01-SB 81-010-001 B Nuclide Energy Yield{%) Activity NuclldeMDA LlneMDA Name (pCilgrams) (pCi/grams) (pCilgrams) (keV) + EU-152 121 . 78 28 . 40 -8 . 70E-02 l . 48E-01 1. 48E-01 344.28 26 . 60 - 5 . 78E- 02 1. 89E- 0 l 1408 . 00 20 . 74 - l . 72E- 0l 3 . 38E- 01 + EU- 154 123 . 07 40 . 40 -2.03E-02 l.04E- 01 l.04E- 01 723 . 30 19 . 70 2 . 07E-01 3.26E-01 1274 . 51 35 . 50 2 . 98£-02 2 . 24E- 01 + EU- 155 86.54 32 . 80 -l . 23E- 01 l . 70E- 01 l . 70E-01 105 . 31 21. 80 -2 . 33E- 02 2 . 13E- 01 + BI - 214 609 . 31
- 46 . 30 2 . 95E-01 9 . 74E-02 9 . 74E-02 1120.29 15.10 3 . 77£- 01 6 . 22£-01 1238.11 5 . 94 4.28E-01 l . 58E+00 1377 . 67 4 . 11 1. 37E+00 l . 64E+00 1407 . 98 2 . 48 - l . 44E+00 2 . 82E+00 1509 . 19 2 . 19 l . 48E +00 3 . 09E+00 1764 . 49 15.80 1. 59E-01 4 . 58E-01
+ PB-2 1 4 77 . 11 10.70 6 . 14E-01 1. 23£-01 6 . 80E - 01 295.21
- 19 . 20 2.62E-0 1 l . 88E-01 351 . 92
- 37 . 20 2 . 68E - 0l 1 . 23£- 0 1
+ PA- 228 89 . 95 22 . 00 3 . 28E+00 5 . 55E+00 9 . llE+ 00 93.35 35 . 00 2 . 53£+00 5 . 55E+00 105 . 00 16.30 - 4 . 07£+00 1. 05E+0l 129 . 22 2 . 97 -1. 33£+00 5 . 17E+0l 338 . 32 5 . 30 2 . 02E+0l 3 . 37E+0 l 463.00 13 . 80 9 . 14E+00 1.44E+0l 911. 23 16 . 70 - 3 . 58E-01 1.76E+0l + AM-241 59.54 36 . 30 -6 . 83E-02 3 . 07E-01 3 . 07E- 01 + CM- 243 103.76 23 . 00 - 7 . 29E-02 2 . 03E - 01 2 . 03E-01 228 . 18 10 . 60 - 3 . 37E- 01 3 . 8 1 E- 0 1 277.60 1 4. 00 - 2 . 03E- 0l 3 . 29E- 0l
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/10/2019 9:49:11AM Page I of6 _....-Apex-Gamma Analysis Report for B1 -010-001 -CIGS-BH02-SB 81-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B 1-010-001-CIGS-BH02-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 7.551E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/5/2019 2:32:00PM Acquisition Started : 6/10/2019 9:18:53AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.4 seconds Dead Time : 0.30 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6764 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/10/2019 9:49:02AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/10/2019 9:49:11AM Page2 of6 Analysis Report for B1-010-001-CIGS-BH02-SB B1-010-001 B Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 77 . 13 147 - 158 154.81 7 . 25E+Ol 29 . 77 5.81E+02 1.10 F 2 186 . 48 365 - 378 373 . 47 5 . 00E+Ol 22 . 72 3 . 89E+02 1. 04 F 3 238 . 52 474 - 485 477 . 51 1 . 62E+02 32.72 3 . 06E+02 1. 76 F 4 295 . 09 586 - 596 590.63 6 . 90E+Ol 23 . 65 1. 81E+02 1. 58 F 5 351. 82 697 - 710 704 . 08 1 . 74E+02 29 . 81 1 .1 9E+02 1. 93 F 6 583 . 02 1160 - 1173 1166 . 39 5 . 37E+01 19 . 36 9 . 96E+Ol 1. 90 F 7 609 . 38 1213 - 1225 1219.09 9 . 38E+Ol 22.24 6 . 33E+Ol 2 . 11 F 8 661.63 1316 - 1328 1323 . 57 8 . 52E+Ol 21.25 5 . 5 4E+Ol 1. 91 F 9 910 . 90 1815 - 1829 1822 . 04 3 . 97E+Ol 14 . 52 3 . 0SE+Ol 2 . 24 F 10 1460 . 86 2913 - 2931 2921.84 2 . 74E+02 33 . 43 8 . 81E+OO 2 . 79 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/10/2019 9:49:02AM Env. Background File : C:\Canberra\Apex\Root\Dairyl.and_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 77 . 13 7 . 25E+Ol 29 . 77 7 . 25E+Ol 2 . 98E+Ol F 2 186 . 48 5 . 00E+Ol 22 . 72 5 . 00E+Ol 2 . 27E+Ol F 3 238 . 52 1 . 62E+02 32 . 72 1 . 62E+02 3 . 27E+O l F 4 295 . 09 6 . 90E+Ol 23 . 65 6 . 90E+Ol 2 . 36E+Ol F 5 351 . 82 1 . 74E+02 29 . 81 4 . 18E+Ol 1. 86E+Ol 1 . 32E+02 3 . 51E+Ol F 6 583 . 02 5 . 37E+Ol 19 . 36 5 . 37E+Ol 1 . 94E+Ol F 7 609 . 38 9 . 38E+Ol 22 . 2 4 2 . 06E+Ol 1 . 21E+Ol 7 . 32E+Ol 2.53E+01 F 8 661 . 63 8 . 52E+Ol 21.25 3 . 31E+Ol 1 . 27E+Ol 5 . 22E+Ol 2 . 47E+Ol F 9 910 . 90 3 . 97E+Ol 14 . 52 3 . 97E+Ol 1. 45E+Ol F 10 1 460 . 86 2 . 74E+02 33 . 43 2 . 82E+O l 8 . 57E+OO 2 .4 6E+02 3 . 45E+Ol M = First peak in a multiplet region
=
m Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/10/2019 9:49:11AM Page 3 of6 Analysis Report for B1-010-001-CIGS-BH02-SB B1-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{3/4) Activity Activity Name Confidence (keV) (pCUgrams) Uncertainty K- 40 0 . 99 1460 . 75
- 10.67 7 . lOE+OO 1. 07E+OO CS - 137 1.00 661 . 65
- 85 .1 2 9 . 34E - 02 4 .4 6E-02 PB-212 0.99 77 . 11
- 17 .5 0 2 .7 0E-01 1 . 12E- 01 238 .63
- 44.60 2 . 22E-01 4.61E-02 BI-214 0.34 609 . 31
- 46.30 2 .2 3E-01 7.83E-02 1120.29 15.10 1238 .11 5 .94 1377.67 4 .11 1407 . 98 2.48 1509.19 2 .1 9 1764 . 49 15 .8 0 PB-214 0 .99 77 . 11
- 10 . 70 4.42E-Ol 1 . 84E- 01 295.21
- 19.20 2 . 61E - 01 9.0SE-02 351 . 92
- 37 . 20 3 . 03E-01 8.18E-02 RA-226 0.98 186 . 21
- 3 .2 8 7 . 82E-01 3 .58 E-01
* =Energy line found in the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)
K-40 0 . 998 7.lOE+OO 1. 07E+OO
6/10/2019 9:49:11AM Page 4 of6 Analysis Report for B1-010-001-CIGS-BH02-SB 81-010-001 8 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) CS - 137 1 . 000 9.34E-02 4 . 46E-02 PB- 212 0 . 999 2.0SE-01 4 . 30E- 02 BI-214 0 . 349 2 . 23E - 01 7.83E- 02 PB- 2 1 4 0.998 2 . 67E- 01 5 . 80E-02 RA- 226 0 . 988 7 . 82 E-01 3 . 58E-01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/ 10/2019 9:49:11AM Page 5 of6 Analysis Report for 81-010-001-CIGS-BH02-SB 81 -010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/ 10/2019 9:49:02AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide F 6 583 . 02 2 . 98074E-02 18 . 04 F 9 910 . 90 2 . 20490E-02 18 . 29 AC-228 PA-228 M = First peak In a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA LineMDA Name (pCl/grams) (pCflgrams) (pCVgrams) (keV) + K- 40 1460 . 75
- 10 . 67 7 . l0E+00 8 . 18E-0l 8.18E- 01
+ AR-41 1293 . 64 99 . 16 2 . 43E+l7 7.07E+17 7 . 07E+17 + CO-60 1173 . 22 100.00 -1 . 02E-02 9 . 37E-02 9 . 49E-02 1332 . 49 100 . 00 2 . 56E- 02 9 . 37E- 02 + KR- 85 513 . 99 0 . 43 6 . 45E-01 1. 51E+0l 1.51E+0l + Y- 88 898 . 04 93 . 70 1. 86E- 03 7 . 03E- 02 7.80E-02 1836 . 06 99 . 20 - 3 . 48E- 02 7 . 03E-02 + NB-94 702 . 63 100 . 00 8 . 49E-03 6 . 56E-02 6 . 56E- 02 871 . 10 100 . 00 - 7 . 72E - 02 7 . 08E- 02 + I - 131 284 . 30 6 . 06 1. 20E- 01 9 . 77E- 02 l.32E+00 364 . 48 81 . 20 - 6 . 51E-03 9 . 77E-02 636 . 97 7 . 27 - 1.13E-0l 1 . 24E+00 + CS-134 604 . 70 97 . 60 -4 . 87E-02 8 . 14E-02 9 . 22E-02 795 . 84 85 . 40 3 . 62E- 02 8 . 14E- 02
6/10/2019 9:49:11AM Page6 of6 Analysis Report for B1-010-001-CIGS-BH02-SB B1-010-001 8 Nuclide Energy Y1eld(%) Activity Nuc/ldeMDA LlneMDA Name (pCUgrams) (pCUgrams) (pCilgrams) (keV) + CS-137 661. 65
- 85 . 12 9 . 34E- 02 7 . 59E - 02 7 . 59E- 02
+ CE - 144 80 . 12 1. 36 - 3 . 63E+OO 4 . 41E - 01 5 . 74E+OO 133 . 51 11.09 4 . 22E - 02 4 . 41E- 01 + EU- 152 121 . 78 28 . 4 0 - 3 . 67E- 02 l. 66E - Ol 1. 66E-01 344.28 26 . 60 l . 40E - 01 2 . 27E- 01 1408 . 00 20 . 74 2 . 49E - Ol 4 . 18E-01 + EU- 154 123 . 07 40 . 40 - 9 . 4 4E- 03 1 . 17E- 01 1.17E- 01 723 . 30 19 . 70 2 . 08E-01 3 . 40E- 0 1 1274 . 51 35 . 50 - 1 . 86E - 01 2 . 36E-Ol + EU-155 86 . 54 32 . 80 - 6 . 0lE-02 1. 99E-01 1. 99E- 01 105 . 31 2 1. 80 - 6 . 71E- 02 2 . 29E- 01 + BI - 214 609 . 31
- 46 . 30 2 . 23E- 01 l . 27E - 01 1 . 27E- 0 1 1120 . 29 15 . 10 3 . 67E - Ol 7 . 09E - 01 1 238 . 11 5 . 94 1 . 58E- 01 l . 85E+OO 1377 . 67 4 . 11 8 . 4 4E-01 1 . 95E+OO 1 407 . 98 2. 48 2 . 08E+OO 3 . 49E+OO 1 509 .1 9 2 . 19 1. 85E- 01 3 . 16E+OO 1764 . 49 15 . 80 5 . 14E- 0 1 6 . 2 4E- 01
+ PB-214 77 . 11
- 10 . 70 4 . 42 E- 0 1 1. 35E- 01 5 . 60E - Ol 295 . 21
- 19 . 20 2 . 61E - Ol 1. 94E-Ol 35 1 . 92
- 37 . 20 3 . 03E- Ol l . 35E - 01
+ PA-228 89 . 95 22 . 00 2 . 49E+OO 6 . 25E+OO 1. 06E+Ol 93 . 35 35 . 00 8 . 64E- 01 6 . 25E+OO 105 . 00 16 . 30 - 7 . 82E+OO 1.15E+Ol 1 29 . 22 2 . 97 2 . SlE+Ol 6 . 06E+Ol 338 . 32 5 . 30 4 . 09E+Ol 4 . 09E+Ol 463 . 00 13 . 80 - 2 . 48E+OO 1 . 65E+Ol 911 . 23 16 . 70 1 . 96E+Ol 2 . ll E+Ol + AM- 2 4 1 59 . 54 36 . 30 5 . 79E- 02 3 . 49E- 01 3 . 49E-01 + CM- 2 4 3 103 . 76 23 . 00 1 . 70E- 02 2 . 20E- 01 2 . 20E- 01 228 . 18 1 0 . 60 - 4 . 0SE- 01 4 . 36E- 0 1 277 . 60 14 . 00 9 . 9 4E- 02 3 . 82E- 0 1
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perfom, the decay correction
? = CAUTION: MDA value is Inconsistent with Currie MDA at 95% confidence level
6/13/2019 7:29:48AM Page 1 of5
...t'Apex-Gamma Analysis Report for 81-010-001-CIGS-8101-SB 81-010-001 B GAMMA SPECTRUM ANALYS/S Sample Identification : 81-010-001-CIGS-8I01-SB Sample Description : 81-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 9. 768E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/8/2019 11:09:00AM Acquisition Started : 6/13/2019 6:59:29AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.2 seconds Dead Time : 0.29 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100
- 4096 Peak Area Range (in channels) : 100
- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6825 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/13/2019 7:29:39AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/13/2019 7:29:48AM Page 2 of 5 Analysis Report for 81-010-001-CIGS-8101-S8 81-010-001 8 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 53 472 - 485 477 . 53 l . SSE+02 31 . 99 2 . 68E+02 1. 86 F 2 583 . 18 1161 - 1171 1166 . 70 5 . 16E+Ol 17 . 55 6 . 08E+Ol 1. 64 F 3 609 . 35 1214 - 1223 1219 . 04 3 . 94E+Ol 16 . 24 5 . 93E+Ol 1. 58 F 4 911 . 12 1817 - 1830 1822 . 49 4 . 52E+Ol 15 . 65 2 . 83E+Ol 2 . 46 F 5 1460 . 89 2914 - 2930 2921. 90 2 . 54E+02 32 . 43 1 . 63E+Ol 2 . 76 M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/ 13/2019 7:29:39AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_ NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 53 1 . 55E+02 31. 99 1 . SSE+02 3 . 20E+Ol F 2 583 . 18 5 . 16E+Ol 17 . 55 5 . 16E+Ol 1 . 75E+Ol F 3 609 . 35 3 . 94E+Ol 16 . 24 2 . 06E+Ol 1. 21E+Ol 1.89E+Ol 2.03E+Ol F 4 911 .1 2 4 . 52E+Ol 15 . 65 4.52E+Ol 1.57E+Ol F 5 1460 . 89 2 . 54E+02 32 . 43 2 . 82E+Ol 8 . 57E+OO 2 . 26E+02 3 . 35E+Ol M = First peak in a multiplet region
=
m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES
6/13/2019 7:29:48AM Page 3 of5 Analysis Report for B1-010-001-CIGS-BI01-SB B1-010-001 B Nuclide Id Energy Yield(%) Activity Activity Name Confldence (keV) (pCilgrams) Uncertainty K- 40 0 . 99 1460 . 75
- 10 . 67 5.0 4E+ OO 7 . 99E- 01 PB-2 12 0 . 55 77 . 11 17 .so 238 . 63
- 44 . 60 1 . 64E - 01 3 . 48E- 02 BI - 2 1 4 0 . 35 609 . 31
- 46 . 30 4. 45E- 02 4 . 78E - 02 1120 . 29 1 5 . 10 1238 .11 5 .94 1377 . 67 4 . 11 1407 . 98 2 . 48 1509 . 19 2 . 19 1764 . 49 15 . 80
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCUgrams)
K- 40 0 . 997 5 . 0 4E+OO 7 . 99E- 0 1 PB-212 0 . 559 l . 6 4E- 0 1 3 . 48E- 0 2 BI -21 4 0 . 350 4 . 45E- 02 4 . 78 E- 02
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/13/2019 7:29:48AM Page4 ofS Analysis Report for B1-010-001-CIGS-8101-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/13/2019 7:29:39AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS (%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide F 2 583 . 18 2 . 864 4 3E - 02 1 7 . 01 F 4 911. 1 2 2 . 51277E- 02 1 7 . 30 Tol. AC-2 28 PA- 228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity Nuc/ideMDA LineMDA Name (pCUgrams) (pCUgrams) (pCUgrams) (keV) + K- 40 1460 . 75
- 10 . 67 5.04E+00 6.BlE- 01 6 . BlE- 01
+ AR-4 1 1 293 . 64 9 9.1 6 - 1. 36E+l 7 9 . 21E+l7 9 . 21E+l7 + CO- 60 1173 . 22 100 . 00 6 . 2 1E- 03 6 . 92E- 02 8 . l0E-02 1332 . 49 100 . 00 l . 02E- 02 6 . 92E-02 + KR- 85 513 . 99 0 . 43 l . 57E+0l l . 27E+0l 1. 27E+0l + Y- 88 898 . 0 4 93 . 70 - l . 05E- 02 4 . 50E- 0 2 6 . 25E- 02 1836 . 06 99 . 20 - 4 . 04E- 0 2 4 . S0E- 02 + NB- 94 702 . 63 1 00 . 00 2 . 55E- 0 2 4 . 74 E- 02 5 . l BE - 02 871 . 10 100 . 00 - 2 . l0E- 02 4 . 74E-02 + I- 131 28 4. 30 6 . 06 - 1. 52E- 01 7 . 43E- 02 9 . 56E- 0 l 36 4.4 8 81. 20 - 3 . 8 1E-0 3 7 . 43E- 02 636 . 97 7 . 27 - 4 . lSE- 01 9 . 55E-01 + CS -1 34 604.70 97 . 60 7 . 52E - 02 6 .1 5E- 02 6 .1 5E- 02 795 . 84 85 . 40 -4. 55E- 02 6 . 39E-02
6/13/2019 7:29:48AM Page 5 ofS Analysis Report for B1-010-001-CIGS-BI01 -SB B1-010-001 B Nuclide Energy Yield(3/4) Activity NuclldeMDA LineMDA Name (pCVgrams) (pCVgrams) (pCVgrams) (lceV) + CS-137 661.65 85.12 7 . 92E-02 7.28E-02 7.28E- 02 + CE-144 80.12 1.36 l.04E+OO 3 . 25E-01 4.13E+OO 133 . 51 11.09 9 . 80E-02 3 . 25E - 01 + EU-152 121.78 28.40 -1.74E-02 1. 31E-01 1. 31E-01 344.28 26. 60 -3.20E-Ol 1. 69E-01 1408 . 00 20.74 -2.42E-01 2 . 56E-Ol + EU-154 123 . 07 40.40 -4.56E-03 9 . 20E-02 9 . 20E - 02 723.30 19.70 7 . 94E-02 2.53E-01 1274 . 51 35 . 50 -5 . 52E-02 1 . 90E-01 + EU-155 86 . 54 32.80 - 8.09E-02 1 . 41E-01 1.41E-Ol 105 . 31 21. 80 -1.19E-02 1.79E-01 + BI-214 609 . 31
- 46.30 4.45E-02 9.29E-02 9.29E-02 1120 . 29 15.10 -4.58E-02 4 . 73E-01 1238 . 11 5 . 94 -2 . 56E-01 l . 42E+OO 1377 . 67 4 . 11 6 . llE - 01 1.30E+OO 1407.98 2.48 -2.03E+OO 2 . 14E+OO 1509 . 19 2.19 1.68E+OO 2.32E+OO 1764.49 15.80 1.64E-01 3.55E-01
+ PB-214 77 . 11 10.70 7 . 75E-Ol l . 24E-01 5 . 64E-01 295.21 19.20 l.19E-Ol 2 . 20E-01 351. 92 37.20 1.68E- 01 l . 24E-01 + PA-228 89.95 22.00 9.18E+OO 4 . 69E+00 8 . lOE+OO 93 . 35 35.00 l.87E+OO 4 . 69E+OO 105.00 16.30 -2 . 29E+OO 9 . 23E+OO 129 . 22 2 . 97 1.52E+Ol 4 . 71E+Ol 338.32 5.30 1. 59E+Ol 3.15E+Ol 463.00 13.80 5.0lE+OO 1 . 32E+Ol 911. 23 16. 70 1.64E+Ol l.74E+Ol + AM-241 59.54 36 . 30 1 . 96E-02 2 . 53E-01 2.53E-01 + CM- 243 103 . 76 23 . 00 7 . 32E - 03 l . 68E-01 1 . 68E- 01 228.18 10.60 l.87E - 02 3.36E-01 277.60 14.00 l.19E-01 2 . 74E-01
+ = Nuclide identified during the nudide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/8/2019 3:51 :42PM Page 1 of6
~ Apex-Gamma Analysis Report for B1-010-001-CQGS-BH01-SB B1-010-001 (45* GEO-PROBE)
GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CQGS-BH01-SB Sample Description : B1-010-001 (45* GEO-PROBE) Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 7.670E+02 grems Facility : Dairyland_NPP Sample Taken On : 6/5/2019 3:38:00PM Acquisition Started : 6/8/2019 3:21 :22PM Procedure : 500ml Marinelli Operator : Administrator Detector Name :HOTlAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.8 seconds Dead Time : 0.32 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6756 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/8/2019 3:51:33PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/8/2019 3:51 :42PM Page 2 of6 Analysis Report for 81 -010-001-CQGS-BH01-SB 81-010-001 (45* GEO-PROBE) Peale Energy ROI ROI Peale Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) M 1 74 . 67 144 - 160 149 . 88 7 . 58E+O l 27 . 27 3 . 69E+02 1.16 m 2 77.09 144 - 160 154 . 72 8.08E+Ol 28 . 04 3 . 75E+02 1.17 F 3 238 . 68 474 - 481 477 . 84 1 . 03E+02 29 . 31 2 . 67E+02 1.19 F 4 295 . 35 584 - 598 591 . 15 8.00E+Ol 23 . 23 2 . 03E+02 1. 45 F 5 351 . 8 1 697 - 709 70 4. 05 1. 59E+02 29 . 4 9 1 . 53E+02 1. 7 1 F 6 583 . 42 1161- 1174 1167 . 17 5 . 0lE+Ol 16 . 78 5 . 28E+Ol 1. 83 F 7 609 . 28 12 13 - 1225 1218 . 89 8 . 91E+Ol 21. 64 6 . 90E+Ol 1. 74 M 8 650 . 68 1298 - 1330 1301 . 68 9 . 37E+OO 6 . 75 1.64E+Ol 1. 53 F 9 727 . 69 1452 - 1460 1 455 . 67 l . 30E+Ol 10 . 24 3.34E+Ol 1. 31 F 10 1332.99 2662 - 2671 2666 . 11 l . 24E+Ol 7 . 99 1. OOE+Ol 1. 03 F 11 1461.08 2914 - 2930 2922 . 27 2 . 23E+02 30 . 63 2 .1 6E+Ol 2 . 60 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/8/2019 3:51 :33PM Env. Background File : C:\Canberra\Apex\Root\Dairytand_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. M 1 74 . 67 7 . 58E+Ol 27 . 27 7 . 58E+Ol 2 . 73E+Ol m 2 77 . 09 8 . 08E+Ol 28 . 04 8 . 08E+Ol 2 . 80E+Ol F 3 238 . 68 l . 03E+02 29 . 31 l . 03E +02 2 . 93E+Ol F 4 295 . 35 8 . 00E+Ol 23.23 8 . 00E+Ol 2 . 32E+Ol F 5 351. 81 1. 59E+02 29 . 49 4.18E+Ol 1 . 86E+Ol 1 . 18E+02 3 . 49E+Ol F 6 583 . 42 5 . 0lE+Ol 16 . 78 5 . 0lE+Ol 1 . 68E+Ol F 7 609 . 28 8 . 91E+Ol 21. 64 2.06E+Ol 1. 21E+Ol 6 . 86E+Ol 2 . 48E+Ol M 8 650 . 68 9 . 37E+OO 6 . 75 9 . 37E+OO 6 . 75E+OO F 9 727 . 69 1 . 30E+Ol 10 . 24 1. 30E+Ol 1. 02E+Ol F 10 1332 . 99 1 . 24E+Ol 7 . 99 1. 24E+Ol 7 . 99E+OO F 11 1 4 61. 08 2 . 23E+02 30 . 63 2.82E+Ol 8 . 57E+OO l . 94E+02 3 . 18E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma
6/8/2019 3:51 :42PM Page 3 of6 Analysis Report for B1-010-001-CQGS-BH01-SB B1 -010-001 (45* GEO-PROBE) NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K-40 0.98 1460 . 75
- 10 . 67 5.52E+OO 9 . 54E-01 BI-212 0 . 57 727 . 17
- 11. 80 l.81E-Ol 1. 42E-Ol 785 . 42 2 . 00 1620 . 56 2 . 75 PB- 212 1. 00 77 . 11
- 17 . 50 2 . 97E- 01 1. 05E - 01 238 . 63
- 44 . 60 l . 39E- Ol 4 . 0lE - 02 BI-214 0 . 35 609 . 31
- 4 6 . 30 2 . 06E-01 7.53E-02 1120. 29 15 . 10 1238 . 11 5 . 94 1377.67 4 .11 1407 . 98 2 . 48 1509 . 19 2 . 19 1764.49 15.80 PB-21 4 0 . 99 77.11
- 10 . 70 4.85E - 01 1. 71E-01 295.21
- 19 . 20 2 . 99E- Ol 8.79E- 02 351 . 92
- 37 . 20 2 . 65E- Ol 7 . 96E-02
* =Energy line found in the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT
6/8/2019 3:51 :42PM Page4 of6 Analysis Report for B1 -010-001-CQGS-BH01-SB B1-010- 001 (45* GEO-PROBE) Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams) K- 40 0 . 983 5.52E+00 9 . 54E- 01 BI - 212 0 . 575 1. 81E-01 1 . 42E- 01 PB- 212 1 . 000 l . 37E-01 3 . 77E-02 BI - 214 0 . 350 2 . 06E- 0l 7 . 53E- 02 PB- 214 0 . 998 2 . 78E - 01 5 . 62E- 02
? = nuciide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/8/2019 3:51 :42PM Page 5 of6 Analysis Report for B1-010-001-CQGS-BH01-SB B1-010-001 (45* GEO-PROBE) UNIDENTIFIED PEAKS Peak Locate Performed on : 6/8/2019 3:51:33PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide M 1 74 . 67 4 . 21127E-02 17 . 99 F 6 583 . 42 2 . 78142E-02 16 . 76 M 8 650.68 5 . 20487E-03 36 . 01 F 10 1332 . 99 6 . 89939E- 03 32 . 15 M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Hue/Ide Energy Yield{%) Activity NuclldeMDA LlneMDA Name (pCilgrams) (pCl/grams) (pCVgrams) (keV) + K- 40 1460 . 75
- 10 . 67 S . 52E+OO 9 . 17E- 01 9.17E-0 1
+ AR-41 1 293 . 64 99 . 16 -3.88E+09 5 . 77Etl0 5 . 77Etl 0 + C0-60 1173 . 22 100 . 00 4 . 72E-02 8 . 59E- 02 9 . 34E- 02 1332 . 49 100 . 00 3 . 17E- 02 8 . 59E- 02 + KR- 85 513 . 99 0 . 43 - 1. 46E+ OO 1 . 44E+O l 1.44E+O l + Y-88 898 . 04 93 . 70 1.18E-02 4 . 94E-02 7.66E-02 1836 . 06 99 . 20 - 4 . 28E- 02 4 . 94E- 02 + NB-94 702 . 63 100 . 00 -1.47E-02 5 . 74E- 02 5 . 74E- 02 871. 1 0 100 . 00 - 2 . 99E- 02 6 . 59E-02 + I - 131 284.30 6 . 06 6 . 73E- 01 7 . 32E- 02 1.09E+OO 364 . 48 81. 20 -5 . 75E-02 7 . 32E-02 636 . 97 7 . 27 3 . 30E-01 l . 04E+OO + CS-134 604 . 70 97 . 60 - 7 . 70E-03 8 . 43E- 02 8 . 81E- 02
6/8/2019 3:51 :42PM Page 6 of6 Analysis Report for B1-010-001 -CQGS-BH01-SB B1-010-001 (45* GEO-P ROBE) Nuclide Energy Yield(3/4) Activity NuclldeMDA LlneMDA Name (keV) (pCUgrams) (pCilgrams) (pCUgrams) CS - 134 795 . 84 85 . 40 -7 . 09E- 02 8 . 43E-02 8 . 43E - 02 + CS-1 37 661 . 65 85 . 12 5 . 0lE- 03 9 . 75E- 02 9 . 75E- 02 + CE-1 44 80 .1 2 1. 36 -2 . 41E+00 4. 21 E-0 1 5 . 54E+00 133 . 51 11.09 -1 . 27E- 01 4 . 21E-01 + EU- 152 1 21 . 78 28 . 40 -1 . l0E- 01 1. 63E-0 1 1 . 63E - 01 344 . 28 26 . 60 - 1 . 07E- 02 2 . 14E- 0l 1408 . 00 20 . 74 3 . 46E- 01 3 . 93E-0 l + EU- 154 123 . 07 40 . 40 -9 . 88E-02 1. 1 4E-01 1.14E-01 7 23 . 30 19 . 70 - 3 . 76E- 02 3 . 3 5E-01 1 27 4. 51 35 . 50 - 2 . 72E- 02 2 . 14E-01 + EU- 155 86 . 54 32 . 80 -2 . 87E- 02 1. 89E- 01 1. 89E-0l 105 . 31 21.80 - 1 . 84E- 02 2 . 17E- 0l + BI -2 14 609 . 31
- 46 . 30 2 .0 6E- 0 1 1. 29E-01 l.29E - 01 11 20 . 29 15 . 10 2 . 78 E- 01 6 . 36E - 01 1 238 .11 5 . 94 - 6 . 64E- 02 1 . 67E+00 1377 . 67 4 . 11 1. 87E- 01 1 . 72E+00 14 07 . 98 2 .4 8 2 . 90E+00 3 . 29E+00 1 509 .1 9 2 .1 9 7 . 63E- 02 2 . 86E+00 1 764 . 49 15 . 80 4 . 93E- 02 5 . 04E- 01
+ PB-214 77 . 11
- 1 0. 7 0 4 . 85E-01 1. 41E- 0 1 3 . 99E-01 295 . 21
- 19 . 20 2 . 99E- 01 2 . 2 1 E- 01 351. 92
- 37 . 20 2 . 65E- 01 1. 4 1E- 01
+ PA-228 89 . 95 22 . 00 2 . 23E+00 l . 54E+00 2 . 65E+ 00 93 . 35 35 . 0 0 - 7 . 20£- 01 1 . 54E+00 105 . 00 1 6 . 30 1. 28E+00 2 . 82E+00 129 . 22 2 . 97 6 . 22E+00 1 . 52E+0l 33 8 . 32 5 . 30 - 8 . 36E- 01 9 . 75E+00 463 . 00 13 . 80 - 3 . 23E+00 3 . 87E+00 911 . 23 16 . 70 5 . 79E -01 4. 98E+00 + AM- 241 59 . 54 36 . 30 - l. llE- 01 3 . 34E-01 3 . 34E- 01 + CM- 243 103 . 76 23 . 00 - 5 . 19E- 03 2 . 08E - 01 2 . 08E- 01 228 . 1 8 10 . 60 - 3 . 82E- 01 4 . 31E- 01 277 . 60 1 4. 00 9 . 89E-02 3 . 74E-01
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
61812019 4:26:43PM Page I of7 _...Apex-Gamma Analysis Report for B1-010-001-CQGS-BH02-SB B1-010-001 (45* GEO-PROBE) GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 -CQGS-BH02-SB Sample Description : B1-010-001 (45* GEO-PROBE) Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 6.025E+02 grams Facility : Dairyland_NPP Sample Taken On : 61512019 3:42:00PM Acquisition Started : 61812019 3:56:24PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.9 seconds Dead lime : 0.33 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 71812014 Efficiency Calibration Used Done On : 71812014 Efficiency Calibration Description Sample Number : 6757 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/812019 4:26:34PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/8/2019 4:26:43PM Page2 of7 Analysis Report for B 1-010-001-CQGS-BH02-SB B1-010-001 (45* GEO-PROBE) Peak Energy ROI ROI Peal< NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 92 473 - 485 478 . 31 l . 73E+02 35 . 46 2 . 90E+02 2 . 35 F 2 295 . 12 587 - 597 590 . 69 4 . 24E+Ol 19 . 36 1. 76E+02 1. 20 F 3 338 .4 8 673 - 685 677 . 40 4 . 44E+Ol 19 . 03 l . 28E+02 1. 65 F 4 351 . 93 698 - 709 704 . 30 9 .4 1E+Ol 24 . 46 1. 70E+02 1.41 F 5 582 . 89 1162 - 1172 1166 . 11 3 . 70E+Ol 15 . 24 4 . 81E+Ol 1. 78 F 6 609 . 5 8 1213 - 1226 1219 . 49 6 . 71E+Ol 19.85 8 . 03E+Ol 1. 93 F 7 661. 93 1317 - 1330 1324 . 18 7 . 98E+Ol 20 . 64 5 . 60E+Ol 2 . 22 F 8 910 . 87 1815 - 1827 1821. 98 3 . 65E+Ol 14 . 69 2 . 60E+Ol 2 . 91 F 9 1461 . 24 291 5 - 2930 2922 . 60 l . 87E+02 28 . 52 3 . ll E+Ol 2 . 33 M = First peak in a multiplet region m = Other peak in a multiplet region F = Frtted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/8/2019 4:26:34PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 92 1 . 73E+02 35 . 4 6 1 . 73E+02 3 . 55E+Ol F 2 295 . 12 4 . 24E+Ol 19 . 36 4 . 24E+Ol l . 94E+Ol F 3 338 .4 8 4 . 44E+Ol 1 9 . 03 4 . 44E+Ol l . 90E+Ol F 4 351 . 93 9.41E+O l 24 . 46 4 . 18E+Ol 1. 86E+Ol 5 . 23E+Ol 3 . 07E+Ol F 5 582 . 89 3 . 70E+ Ol 15 . 24 3 . 70E+Ol 1. 52E+Ol F 6 6 0 9 . 58 6 . 71E+ Ol 19 . 85 2 . 06E+Ol l . 21E+Ol 4 .6 5E+Ol 2 . 33E+Ol F 7 661 .93 7 . 98E+O l 20 . 64 3 . 31E+Ol 1. 27E+ Ol 4 . 67E+Ol 2 . 42E+Ol F 8 910 . 87 3.65E+Ol 1 4 . 69 3 . 65E+Ol 1 . 47E+O l F 9 1461.24 l . 87E+02 28 . 52 2 . 82E+Ol 8 . 57E+OO l . 59E+02 2 . 98E+Ol
=
M First peak in a multiplet region
=
m Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/8/2019 4:26:43PM Page 3 of7 Analysis Report for s1-010.001-CQGS-BH02-SB B1-010-001 (45* GEO-PROBE) NUCLIDE IDENTIFICATION REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{3/4) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K-4 0 0.96 1460.75
- 1 0 . 67 5.76E+OO 1.12E+OO CS - 137 0 . 98 661. 65
- 85 . 12 1. 05E- 01 5.47E-02 PB-212 0.55 77 .11 17 . 50 238 . 63
- 44 . 60 2 . 97E- 01 6 . 27E-02 BI-214 0.34 609.31
- 46.30 1 . 78E-01 8 .95E- 02 1120 . 29 15.10 1238 . 11 5 . 94 1377 . 67 4.11 1407 . 98 2.48 1509 . 19 2 . 19 1764 .4 9 15 .80 PB-214 0.72 77 . 11 10.70 295.21
- 19.20 2 . 0lE-01 9 .24E-02 351. 92
- 37 . 20 l .S OE-01 8.84E-02
* =Energy line found in the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams)
K-40 0 . 962 5 . 76E+OO 1.12E+OO CS-137 0 . 987 1. OSE-01 5 . 47E-02
6/8/2019 4:26:43PM Page4 of? Analysis Report for B1-010-001-CQGS-BH02-SB B1-010-001 (45* GEO-PROBE) Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) PB-212 0.551 2.97E-01 6.27E-02 BI-214 0.344 1 . 78E-01 8.95E-02 PB-214 0. 7 21 l. 75E-01 6.39E-02
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/8/2019 4:26:43PM Page5 of7 Analysis Report for B1-010-001-CQGS-BH02-SB B1-010-001 (45* GEO-PROBE) UNIDENTIFIED PEAKS Peak Locate Performed on : 6/8/2019 4:26:34PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke VJ Peak Size (CPS) Uncertainty Type Nuclide F 3 338 . 48 2 . 46456E - 02 21. 45 Tol. AC-228 PA-228 F 5 582 . 89 2 . 05410E-02 20 . 61 F 8 910 . 87 2 . 02702E - 02 20 . 13 Tol. AC- 228 PA- 228 M = First peak In a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nucllde Energy Yield(%) Activity NuclideMDA LineMDA Name (pCl/grams) (pCUgrams) (pCUgrams) (keV) + K- 40 1460 . 75
- 10 . 67 5 . 76E+00 1 . 24E+00 1. 24E+00
+ AR- 41 1293 . 64 99 . 16 - 4 . 38E+10 9 . 77E+l0 9 . 77E+ 1 0 + CO- 60 1173 . 22 100 . 00 7 . 03E-02 1. 09E- 0 1 1. 23E- 0l 1332 . 49 100 . 00 9 . lSE - 02 1. 09E- 0l + KR- 85 513 . 99 0 . 43 2 . 28E+0l 2 . 03E+0l 2 . 03E+0l + Y- 88 898 . 04 93 . 70 2 . 08E -0 3 5 . 77E- 02 9 . 93E- 02 1836 . 06 99 . 20 - 8 . l 0E - 02 5 . 77 E- 02 + NB- 94 702 . 63 100 . 00 4 .l SE - 03 7 . 38E- 02 7 . 38E- 02 871 . 10 100 . 00 - 5 . 81E - 02 8 . 47E- 02 + I -1 31 284.30 6 . 06 3 . 8 4E- 01 1.07E- 0l 1 . 41 E+00 364 . 48 81.20 - 1 . 65E- 03 l . 07E- 01
6/8/2019 4:26:43PM Page 6 of7 Analysis Report for B1-010-001-CQGS-BH02-SB B1-010-001 (45* GEO-PROBE) Nuclide Energy Yield{%) Activity Nuclide MDA LlneMDA Name (pCVgrams) (pCVgrams) (pCVgrams) (keV) I - 131 636 . 97 7 . 27 2 . 36£ - 01 1. 07E-01 1 . 32E+00 + CS - 134 604 . 70 97 . 60 1 . 70£ - 02 1.06E-01 1. 06£-01 795 . 84 85 . 40 -4 . 64E-02 1 . 07£-01 + CS-137 661. 65
- 85 . 12 1. 05£ - 0 1 9 . 67E- 02 9 . 67E-02
+ CE-144 80 . 12 1. 36 2 . 77E+00 5 . 1 4£-0 1 6 . 79E+00 133 . 51 11.09 - 9 . llE-02 5 . 14E-01 + EU- 152 121 . 78 28 . 40 -1 . l0E-01 1 . 95£-01 1 . 95£- 01 3 4 4 . 28 26 . 60 - 8 . 52£ - 03 2 . 85£-01 1408 . 00 20 . 74 2 . 39£-0 1 4 . SlE-01 + EU - 154 123 . 07 4 0 . 40 - 7 . 72£ - 02 l . 37E-01 l . 37E-01 723 . 30 1 9 . 70 l . 25E - 0l 4 . llE- 01 1274 . 51 35.50 1. 63E - 01 3 . 14E- 01 + EU - 155 86 . 54 32 . 80 5 . 43E-02 2 . 32E-01 2 . 32E-01 105 . 31 21. 80 6 . 09E-02 2 . 75E-01 + BI-214 609 . 31
- 46 . 30 1 . 78E - 01 1 . 73E-01 1. 73E-01 1120 . 29 15.10 3 . 23£ - 01 8 . 28£ - 01 1238 . 11 5 . 94 4 . 92£- 01 2 . 06E+00 1377 . 67 4 . 11 6 . 94£ - 01 2.59E+00 1 4 07 . 98 2 . 48 2 . 00E+00 3 . 77E+00 1509 . 19 2 . 19 l . 17E+00 3 . 41E+00 1764 . 49 15 . 80 5 . 14E- 01 7.16£-01
+ PB- 214 77 . 11 10 . 70 1.20E+00 l . 82E- 0 1 9 . 18E-01 295 . 21
- 19 . 20 2 . 0lE-01 2.41E-01 351 . 92
- 37 . 20 1. S0E- 01 1. 82E-01
+ PA- 228 89 . 95 22 . 00 4 . 9 4E+00 1.89E+00 3.31E+00 93 . 35 35.00 - 7. 4 6E*- 01 l . 89E+00 105 . 00 16.30 1 . 96E+00 3 . 62E+00 129 . 22 2 . 97 7 . 74E+00 1. 86E+0l 338 . 32 5 . 30 1. 8 4E+00 1 . 34E+0l 463 . 00 13 . 80 3 . 24E - 01 4 . 72E+00 911.23 16 . 70 4 .1 3E+00 6 ._95E+00 + AM- 241 59 . 54 36 . 30 2 . 25E - 01 4.lSE- 01 4.lSE- 01 + CM-243 103 . 76 23 . 00 l . 63E - 0l 2 . 64E-01 2 . 64E-01 228 . 18 10 . 60 - 2 . 35£ - 01 5 . 43E- 01 277 . 60 14 . 00 1 . 18E- 01 4 . 53E- 01
+ = Nuclide identified during the nuclide identification * = Energy line fou nd in the spectrum > = MOA value not calculated @ = Half-life too short to be able to perfonn the decay correction ? = CAUTION: MOA value is inconsistent with Currie MOA at 95% confidence level
6/8/2019 4:26:43PM Page 7 of7 Analysis Report for B1-010-001-CQGS-BH02-SB B1-010-001 (45* GEO-PROBE)
6/13/2019 8:31 :32AM Page J of7 __.-Apex-Gamma Analysis Report for 81-010-001-CIGS-BJ01-SB 81-010-001 8 GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001-CIGS-BJ01-SB Sample Description : 81-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 6.945E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/7/2019 2:09:00PM Acquisition Started : 6/13/2019 8:01 :14AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.6 seconds Dead Time : 0.31 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6827 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/13/2019 8:31:23AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/13/2019 8:31 :32AM Page 2 of7 Analysis Report for 81-010-001-CIGS-BJ01-SB 8 1-010-001 8 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 76.46 147 - 160 1 53 . 46 l . 67E+02 47.07 7 . 21E+02 3 . 02 F 2 92.78 180 - 191 186 . 10 4 . 97E +Ol 28 . 65 5 . 67E+02 1.27 F 3 186 . 55 368 - 379 373 . 59 4 . 61E+Ol 6 . 52 3 . 90E+02 0 . 48 F 4 238 . 65 471 - 485 4 77 . 77 2 . 00E +02 35 . 02 3 . 41E+02 1. 67 F 5 295 . 20 582 - 596 590 . 85 6 . 31E+Ol 2 4. 59 2 . 5 1E+ 02 1. 80 F 6 351. 79 698 - 709 704 . 01 1 . 06E+02 26 . 81 l . 53E+02 1. 94 F 7 463.1 8 922 - 930 926 . 75 1. 69E+Ol 11 . 71 7 . 65E+Ol 0 . 81 F 8 511.15 1015 - 1030 1022 . 68 6 . 63E+Ol 20 . 61 8 . 00E+Ol 2 . 92 F 9 583 . 31 1159 - 1 172 1166 . 97 5 . 71E+Ol 19 . 74 9 .4 5E+Ol 2.05 F 10 609 . 32 1212 - 1225 1218 . 98 8 . 15E+Ol 20 . 92 6 . 30E+Ol 2 . 07 F 11 911.22 1818 - 1829 1822 . 67 3 . 39E+Ol 15 . 56 5 . 90E+Ol 1. 9 4 F 12 9 6 9 . 20 1 934 - 1 944 1938 . 62 2 . 54E+Ol 13.16 4 . 8 4E+O l 1. 46 F 13 1460 . 75 2914 - 2930 2921. 61 3 . 26E+02 36 . 78 2 . 17E+Ol 2 . 58 M = First peak in a multiplet reg ion m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/13/2019 8:31 :23AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 76 . 46 l . 67E+02 47 . 07 l. 67E+02 4 . 71E+Ol F 2 92 . 78 4 . 97E+Ol 28 . 65 4 . 97E+Ol 2 . 86E+Ol F 3 186 . 55 4. 61E+Ol 6 . 52 4 . 61E+Ol 6 . 52E+OO F 4 238 . 65 2 . 00E+02 35 . 02 2 . 00E+02 3 . 50E+Ol F 5 295 . 20 6 . 31E+Ol 2 4. 59 6 . 31E+Ol 2 . 46E+Ol F 6 35 1. 79 1. 06E+02 26 . 81 4 .18E+Ol 1. 86E+Ol 6. 41E+Ol 3 . 26E+Ol F 7 4 63 . 18 l. 69E+Ol 11 . 71 l. 69E+Ol l .1 7E+Ol F 8 511 . 15 6 . 63E+Ol 20 . 61 3.64E+O l l. 4 3E+O l 3 . 00E+Ol 2 . 51E+O l F 9 583 . 3 1 5 . 7 1E+Ol 19 . 7 4 5 . 71E+ Ol 1. 97E+ Ol F 10 609 . 32 8 . 15E+Ol 20 . 92 2.06E+Ol 1. 21E+O l 6 . 09E+Ol 2 .4 2E+Ol F 11 911.22 3 . 39E+Ol 15 . 56 3 . 39E+Ol l . 56E+Ol F 12 969 . 20 2 . 5 4E+O l 13 . 16 2 . 5 4E+Ol l. 32E+Ol F 13 1460 . 75 3 . 2 6E+02 36 . 78 2 . 82E+Ol 8 . 57E+OO 2. 98E+02 3 . 78E+Ol
6/13/2019 8:31 :32AM Page3 of7 Analysis Report for B1-010-001-CIGS-BJ01-SB 81-010-001 B M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCVgrams) Uncertainty K-40 1.00 1460 . 75
- 10 . 67 9 . 34E+OO 1 . 29E+OO PB- 212 0 . 98 77 .11
- 17 . 50 6.85E- Ol 1. 99E-01 238 . 63
- 44 . 60 2.97E- 01 5 . 42E-02 BI-214 0 . 35 609.31
- 46 . 30 2.02E-01 8 . 09E-02 1120.29 15 . 10 1 238 . 11 5 . 94 1377 . 67 4 . 11 1407.98 2 . 48 1509. 19 2.19 1764.49 15 . 80 PB-214 0.98 77 . 11
- 10.70 l.12E+OO 3 . 25E-01 295 . 21
- 19 . 20 2 . 60E - 01 1 . 02E- 01 351 . 92
- 37 . 20 l . 59E- 01 8 .l SE- 02 RA- 226 0 . 98 186 .2 1
- 3 .28 7 . 85E- 01 1 . 19E-01
" =Energy line found In the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT
6/13/2019 8:31 :32AM Page4 of7 Analysis Report for B1-010-001-CIGS-BJ01-SB B1-010-001 B Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams) K- 40 1.000 9.34E+00 1. 29E+00 PB-212 0 . 981 3 . lSE-01 5.2 4E-02 BI-214 0 . 350 2 . 02E-01 8 . 09E- 02 PB - 214 0 . 988 2 . 14E- 01 6 . 26E- 02 RA- 226 0 . 982 7.85E- 01 1.19E- 01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/13/2019 8:31 :32AM Page 5 of7 Analysis Report for B1-010-001-CIGS-BJ01-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/13/2019 8:31 :23AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide F 2 92 . 78 2 . 76166£-02 28 . 82 Tol. PA- 228 F 7 463 . 18 9 . 38310E - 03 34 . 68 Tol. PA-228 F 8 511.15 1 . 66403£ - 02 41. 83 F 9 583 . 31 3 . 17015E- 02 17 . 29 F 11 911 . 22 1. 88209£-02 22.96 Tol. AC- 228 PA-228 F 12 969 . 20 1 . 40978E-02 25 . 93 Tol. AC-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity Nucllde MDA LlneMDA Name (pCl/grams) (pCVgrams) (pCVgrams) (keV) + K- 40 1 4 60 . 75
- 10 . 67 9 . 34E+00 1 . 0lE+00 1 . 0lE+00
+ @ AR-41 1293 . 64 99 . 16 l . 00E+26 1. 00E+26 1. 00E+26 + CO-60 1173 . 22 100 . 00 2 . 49£- 03 1 . 0SE- 01 1.14£-01 1332 . 49 100 . 00 1 . 23£- 0 2 1 . 0SE- 01 + KR- 85 513 . 99 0 . 43 1 . 72£+01 1 . 84£+0 1 1. 84£+01
6/13/2019 8:31:32AM Page 6 of7 Analysis Report for B 1-010-001-CIGS-BJO 1-SB 81-010-001 B Nuclide Energy Yield(%) Activity NuclideMDA L/neMDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV) + Y-88 898.04 93.70 -3.59E-02 6.73E-02 9.66E-02 1836.06 99 . 20 3 . 39E-02 6.73E-02 + NB-94 702.63 100 . 00 -2.57E-02 7.23E-02 7.23E-02 871.10 100 . 00 -2 . 45E-03 8.84E-02 + I-131 284.30 6 . 06 -4 . 33E-01 1 . 18E-01 l . 45E+OO 364.48 81. 20 - 5.31E - 02 l.18E-01 636 . 97 7 .27 3.14E-01 1. 59E+OO + CS-134 604.70 97 . 60 5.lSE-03 9.58E-02 9.58E-02 795 . 84 85 . 40 O.OOE+OO 9.60E-02 + CS-137 661.65 85.12 8 . 90E-02 1. 04E-01 1.04E-01 + CE-144 80.12 1. 36 4 . 34E-Ol 4.80E-01 6.54E+OO 133 .51 11. 09 1.16E-Ol 4 . 80E-01 + EU-152 121 .78 28.40 -l.73E-01 1. 85E-Ol 1.85E-01 344.28 26.60 8.36E-03 2.39E-01 1408 . 00 20.74 2.70E-01 4.07E-Ol + EU-154 123.07 40.40 -6.68E-02 1.31E-01 1.31E-01 723 . 30 19.70 2.87E-01 4.43E-01 1274 . 51 35 . 50 1.05E-01 2 . 88£-01 + EU-155 86.54 32 . 80 1. 85E-02 2.18E-Ol 2.18£-01 105 . 31 21.80 -1.56E-Ol 2.56E-01 + BI-214 609.31
- 46.30 2.02E-Ol 1.40E-01 l.40E-01 1120. 29 15.10 1. 06E-Ol 8.20£-01 1238 .11 5.94 1 . 46E+OO 2 . 17E+OO 1377 . 67 4 .11 -3.55E-02 1.98E+OO 1407.98 2.48 2.26E+OO 3.40E+OO 1509.19 2.19 7.72E-01 3.70E+OO 1764.49 15.80 4.08E-01 6.09E-01
+ PB-214 77 .11
- 10.70 1.12E+OO l.53E-01 7.18E-01 295 . 21
- 19.20 2.60E- Ol 2.70£-01 351 . 92
- 37 . 20 1. 59E- 01 1 .53E-01
+ PA-2 28 89. 95 22 . 00 -6 . 23E+OO 1.45E+Ol 2 . 44E+Ol 93.35 35.00 7.05E+OO 1 .45E+O l 105 . 00 16 . 30 -1. 22E+Ol 2.66E+Ol 129.22 2 . 97 -7.30E+O l 1.34E+02 338.32 5 . 30 2 . 17E+Ol 8.87E+Ol 463.00 13 . 80 9 . 52E+OO 3. 72E+Ol 911.23 16.70 4.46E+Ol 5.27E+Ol + AM-241 59.54 36.30 2 . 57E-01 3.93E-01 3.93E-01 + CM-243 103.76 23 . 00 -5 . 50E-02 2.45E-01 2.45E-01 228.18 10.60 l . 30E-01 5.25E-01 277.60 14.00 -7.lOE-02 4.16E-01
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value Is inconsistent with Currie MDA at 95% confidence level
6/13/2019 8:31 :32AM Page 7 of7 Analysis Report for B1-010-001-CIGS-BJ01-SB B1-010-001 B
6/13/2019 9:13:36AM Page 1 of7 _...Apex-Gamma Analysis Report for B1-010-001-CIGS-8J02-S8 81-010-001 8 GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001-CIGS-8J02-S8 Sample Description : 81-010-001 8 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 7.731E+02 grams Facility : Dairyland_NPP Sample Taken On : 6/7/2019 4:09:00PM Acquisition Started : 6/13/2019 8:43:18AM Procedure : 500ml Marinelli Operator : Adm inistrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.4 seconds Dead Time : 0.30 % Peak Locale Threshold : 3.00 Peak Locate Range (in channels) : 100
- 4096 Peak Area Range (in channels) : 100- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6828 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/13/2019 9:13:27AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/ 13/2019 9:13:36AM Page 2 of7 Analysis Report for B1-010-001 -CIGS-BJ02-SB B1-010-001 B Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 77 .1 9 148 - 159 154 . 92 9 . 15E+0l 34 . 22 6 . 32E+02 1. 45 M 2 238 . 58 471 - 488 477 . 64 2.05E+02 34 . 34 2 . 35E+02 1. 61 m 3 241 . 69 471 - 488 483 . 85 5.63E+01 21. 64 1. 85E +02 1. 62 F 4 295 . 00 583 - 59 4 590 . 46 4 . 70E+0l 20 . 1 1 l . 46E+02 1. 56 F 5 338 . 30 671 - 681 677 . 0 4 4 . 14E+01 18 . 77 l . 37E+02 1. 36 F 6 351 . 97 701 - 711 704.37 8 . 41E+01 23 . 27 1. 40E+02 1.58 F 7 583.26 1161 - 1172 1166.87 4.93E+0l 17 . 36 5 . 41E+0 l 2 . 03 F 8 609 . 10 12 11 - 1223 1218 . 5 4 6 . 27E+0l 18 . 99 6 . 1 6E+0 l 1. 96 F 9 1461. 00 2913 - 2930 2922 .1 1 3 . 14E+02 36 . 11 2 . 25E +0l 2 . 61 M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/13/2019 9 :13:27AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001 364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 77 . 19 9 . 15E+0l 34 . 22 9 .15E+0l 3 . 42E+01 M 2 238 . 58 2 . 05E+02 34.34 2 . 05E+02 3 . 43E+0l m 3 24 1 . 69 5 . 63E+0l 21. 64 5 . 63E+0l 2 . 16E+0l F 4 295 . 00 4 . 70E+0l 20 . 11 4 . 70E+0 l 2 . 0lE+0l F 5 338 . 30 4 . 14E+0l 18 . 77 4 . 14E+0l 1. 88E+0l F 6 351. 97 8 . 41E+0l 23 . 27 4. 18E+0l 1. 86E+0 l 4 . 24E+0l 2 . 98E+0l F 7 583 . 26 4 . 93E+0l 17 . 36 4 . 93E+0l 1 . 74E+0l F 8 609 . 10 6 . 27E+0l 18 . 99 2 . 06E+0l 1. 21E+0l 4 . 21E+0l 2 . 25E+0l F 9 1461.00 3 . 14E+02 36 . 11 2 . 82E+0l 8 . 57E+00 2 . 86E+02 3 . 71E+0l M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma
6/ 13/2019 9:13:36AM Page 3 of7 Analysis Report for B1-010-001-CIGS-BJ02-SB B1-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K-40 0 . 99 1460 . 75
- 10 . 67 8 . 06E+OO l.14E+OO PB- 212 1.00 77 . 11
- 17 . 50 3 . 33E- 01 l . 26E- Ol 238.63
- 44 . 60 2 . 73E- 01 4 . 79E - 02 BI-214 0 . 34 609 . 31
- 46 . 30 1. 26E-01 6 . 75E- 02 1120 . 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2.48 1509 . 19 2.19 1764.49 15.80 PB-214 0 . 99 77 . 11
- 10 . 70 5 . 44E- 01 2 . 07E-01 295 . 21
- 19 . 20 1. 74E- Ol 7 . 49E - 02 351 . 92
- 37 . 20 9 . 47E-02 6 . 68E - 02
* =Energy line found in the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCVgrams)
K-40 0.990 8 . 06E+OO l.14E+OO PB-212 1 . 000 2 . 71E- 01 4.SOE - 02 BI - 214 0 . 346 1. 26E-01 6 . 75E-02
6/13/2019 9:13:36AM Page4of7 Analysis Report for B1-010-001-CIGS-BJ02-SB B1-010-001 B Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pC/lgrams) PB-214 0.998 1. 28£-01 4.86£-02
? = nuclide Is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/ 13/2019 9:13:36AM Page 5 of7 Analysis Report for B 1-010-001-CIGS-BJ02-SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/13/2019 9:13:27AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide m 3 241 . 69 3 . 12748E-02 19 . 22 F 5 338 . 30 2 . 29785E- 02 22 . 69 Tol. AC-228 PA- 228 F 7 583 . 26 2 . 74117E-02 17.59 M = First peak In a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuclide MDA LineMDA Name (pCl/grams) (pCVgrams) (pCl/grams) (keV)
+ K-40 1460 . 75
- 10 . 67 8 . 06E+00 9 . 22E-01 9.22E- 01
+ @ AR-41 1293 . 64 99 . 16 1. 00E+26 l.00E+26 1.00E+26 + CO - 60 1173 . 22 100 . 00 4 . 94E-02 8.74E- 02 1. l0E-01 1332 . 49 100 . 00 3 . 90E- 02 8 . 74E- 02 + KR-85 513 . 99 0 . 43 2.04E+0l 1 . 65E+0l l . 65E+0 l + Y- 88 898 . 04 93.70 1. 21E-02 6 . 04E- 02 8 . 0lE-02 1836 . 06 99 . 20 - 7 . 85E-03 6 . 04E-02 + NB-94 702 . 63 100.00 3 . 0lE - 02 6 . 50E-02 6 . 50E- 02 871 . 10 100 . 00 -3 . 87E - 03 7.22E-02 + I-131 284 . 30 6 . 06 - 2.98E-01 l . 03E-01 1. 26E+00 364 . 48 81. 20 3 . 62E- 03 l. 03E- 01
6/13/2019 9:13:36AM Page6 of? Analysis Report for B1-010-001-CIGS-BJ02-SB B1-010-001 B Nuclide Energy Yield{3/4) Activity NuclldeMDA LineMDA Name (pCUgrams) (pCUgrams) (pCUgrams) (keV} I-131 636.97 7.27 3. llE-01 1. 03E-01 1. 41E+OO + CS-134 604.70 97 . 60 7.29E-02 8.09E-02 8 . 09E- 02 795 . 84 85 . 40 4 . 37E-05 8.68E-02 + CS-137 661 . 65 85 . 12 1.03E-Ol 8.93E-02 8.93E-02 + CE-144 80 . 12 1. 36 -l.70E+OO 4.lBE-01 5.68E+OO 133.51 11.09 -2.03E-01 4 . 18E-01 + EU-152 121.78 28.40 -1.lOE-01 1.63E-Ol 1.63E-01 344.28 26.60 -4.46E-01 2 .llE- 01 1408.00 20.74 1 . 58E-01 3 . 38E-01 + EU-154 123 . 07 40 .4 0 -2 . 75E-02 1.16E-01 1.16E-01 723.30 19.70 -7.61E-03 3.72E-01 1274 . 51 35.50 -1.22E-02 2 . 48E-01 + EU-155 86.54 32.80 3.24E-03 1. 95E-Ol 1.95E-01 105 . 31 21. 80 3.03E- 02 2.22E-01 + BI - 214 609 . 31
- 46.30 1. 26E-01 1. 23E-01 1. 23E-01 1120.29 15.10 2.56E-01 6.88E-01 1238.11 5.94 -l.20E+OO 1. 86E+OO 1377 . 67 4 .11 6.78E-01 1.77E+OO 1407.98 2 . 48 1.32E+OO 2.82E+OO 1509.19 2.19 -4 . 00E- 01 2 . 35E+OO 1764 .49 15 . 80 2.27E-01 5 . 36E-01
+ PB-214 77 .11
- 10.70 5 . 44E-01 1.33E-01 5.68E-01 295.21
- 19.20 1.74E-01 1. 7 5E-01 351.92
- 37.20 9.47E-02 1. 33E-01
+ PA-228 89 . 95 22.00 1.82E+Ol 1 . 24E+Ol 2. llE+Ol 93 . 35 35.00 6.74E+OO 1. 24E+Ol 105.00 16.30 3.54E-02 2.22E+Ol 129.22 2.97 -1.57E+OO l.17E+02 338 . 32 5 . 30 5.30E+Ol 7.82E+Ol 463.00 13 .8 0 1. 87E+OO 2 . 95E+Ol 911.23 16 . 70 1 . 08E+OO 4 .13E+Ol + AM-241 59 . 54 36 . 30 1. 06E-Ol 3 . 48E-01 3.48E-01 + CM-243 103.76 23.00 7.40E-02 2 . 16E-01 2.16E-01 228.18 10.60 7.96E-02 4.45E-01 277.60 14.00 -1.53E-01 3.45E-01
+ = Nuclide Identified during the nuclide identification * = Energy line found in the spectrum > = MDA value not calculated @ = Half-life too short to be able to perform the decay correction ? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/13/2019 9:13:36AM Page? of? Analysis Report for B1-010-001-CIGS-BJ02-SB 81-010-001 B
6/13/2019 10:08:12AM Page I of7
.J'Apex-Gamma Analysis Report for B1-010-001-CIGS-BK01-SB B1-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BK01-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 8. 192E+02 grams Facility : Dairytand_NPP Sample Taken On : 6/7/2019 9:37:00AM Acquisition Started : 6/13/2019 9:37:53AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 1800.0 seconds Real Time : 1805.4 seconds Dead Time : 0.30%
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6829 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/13/2019 10:08:03AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/ 13/2019 10:08:12AM Page2 of7 Analysis Report for B1 -010..001 -CIGS-BK01 -SB B1-010-0 01 B Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 48 473 - 485 477 . 43 1 . 73E+02 33 . 54 2 . 82E+02 1. 87 F 2 338 . 17 671 - 683 676 . 78 3 . 85E+0l 1 8 . 90 1 . 53E+02 1. 60 F 3 352 . 05 700 - 710 704 . 52 8.29E+0 l 23 . 72 l . 41E+02 1. 61 F 4 5 1 0 . 92 1017 - 1030 1022 . 21 5 . 97E+0l 18 . 88 6 . 30E+0l 2 . 31 F 5 583 .1 6 1159 - 1172 1166 . 67 4.08E+0l 16 . 19 7 . 61E+0l 1. 67 F 6 609.27 1210 - 1227 1218 . 87 7.25E+0l 19 . 08 4 . 03E+0l 2 . 72 F 7 9 1 0 . 82 1816 - 1828 1821 . 8 8 4. 00E+0 l 15 . 66 5 . 56E+0l 1. 76 F 8 1460 . 37 2913 - 29 3 0 2920 . 86 2 . 73E+02 33 . 32 7 . 84E+ 00 2 . 83 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/ 13/2019 10:08:03AM Env. Background File : C:\Canberra\Apex\Root\Dairytand_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 48 1 . 73E+02 33 . 54 1.73E+02 3 . 35E+0l F 2 338 . 17 3 . 85E+01 18 . 90 3.85E+0l 1 . 89E+0l F 3 352 . 05 8 . 29E+0l 23 . 72 4 . 18E+0l 1. 86E+0l 4 . llE+0l 3 . 0lE+0l F 4 510 . 92 5 . 97 E+0l 18 . 88 3 . 64E+ 0 l l . 43E+0l 2 . 33E+0l 2 . 37E+0l F 5 583 . 16 4 . 08E+0l 16 . 19 4. 08E+0l 1 . 62E+0l F 6 609 . 27 7 . 25E+0l 19 . 08 2 . 06E+0 l l . 21E+0l 5.19E+0l 2.26E+0l F 7 910 . 82 4 . 00E+0l 15 . 66 4 . 00E+0l 1. 57E+0l F 8 1460 . 37 2 . 73E+02 33 . 32 2 . 82E+0 l 8 . 57E+00 2 . 4 4E+02 3 .4 4E+0l
=
M First peak in a multiplet region
=
m Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma
6/13/2019 10:08:12AM Page 3 of 7 Analysis Report for 81-010-001-CIGS-BK01-SB B1-010-001 B NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield('1/4) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K- 40 0.97 1460 . 75
- 10. 67 6 . 50E+OO 9 . 84E-01 PB- 212 0 . 55 77 . 11 17 . 50 238 . 63
- 44 . 60 2 . 18E- 01 4 . 37E- 02 BI - 214 0 . 34 609 . 31
- 46 . 30 l.46E- Ol 6 . 40E- 02 1120 . 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4.11 1407 . 98 2 . 48 1509 . 19 2.19 1764 . 49 15 . 80
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams)
K-40 0 . 977 6 . 50E+OO 9.84E-0 1 PB- 212 0.558 2 . 18E-01 4 . 37E- 02 BI - 214 0.349 1. 4 6E- 01 6 . 40E-02
6/13/2019 10:08:12AM Page4 of7 Analysis Report for B1-010-001-CIGS-BK01-SB B1-010-001 B
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/13/2019 10:08:12AM Page 5 of7 Analysis Report for B1-010-001-CIGS-BK01 -SB B1-010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/13/2019 10:08:03AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 338 . 17 2 . 13954E- 02 24 . 54 Tol. AC- 228 PA-228 F 3 352 . 05 2.28252E-02 36.69 Tol. PB- 214 F 4 510 . 92 l . 29455E-02 50 . 75 F 5 583 . 16 2 . 26811E-02 19 . 83 F 7 9 1 0 . 82 2 . 22179E-02 19 . 58 Tol. AC-228 PA-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield{%) Activity Nucl/deMDA LlneMDA Name (pCUgrams) (pC/l grams) (pCUgrams) (keV) + K- 40 1460 . 75
- 10 . 67 6 . 50E+00 7.40E - 01 7 . 40E- 01
+ @ AR-41 1293 . 64 99 . 16 1.00E+26 1 . 00E+26 1 . 00E+26 + CO-60 1173 . 22 100 . 00 6 . 00E-02 7.52E- 02 9 . 59E-02 1332 . 49 100 . 00 -5 . 81E-03 7 . 52E-02 + KR-85 513 . 99 0 . 43 2 . 07E+0l 1. 51E+0l l . 51E+0l + Y- 88 898 . 04 93 . 70 -8 . 02E-03 6 . 00E-02 7 . 18E-02 1836 . 06 99 . 20 3 . 24E- 02 6 . 00E-02
6/13/2019 10:08:12AM Page 6 of7 Analysis Report for B 1--010-001-CIGS-BK01-SB 81--010-001 B Nuclide Energy Yleld("/4) Activity NuclldeMDA LlneMDA Name (pCl/grams) (pCl/grams) (pCVgrams) (keV) + NB-94 702.63 100.00 4 .18E-02 6. llE-02 6.46E-02 871.10 100.00 2.03E-02 6. llE-02 + I-131 284.30 6 . 06 -2.42E+OO 9.64E-02 1.21E+OO 364.48 81.20 - 3.13E-02 9 . 64E-02 636. 97 7 . 27 7 . 05E - 02 l . 21E+OO + CS-134 604.70 97 . 60 O. OOE+OO 7.61E-02 7 . 61E- 02 795.84 85 . 40 2.05E-02 7.75E-02 + CS-137 661. 65 85 . 12 l . 21E-Ol 8.53E-02 8.53E-02 + CE-144 80.12 1. 36 1 . 76E-Ol 3.79E-01 5 . 04E+OO 133 . 51 11. 09 - 4 . 09E- Ol 3 . 79E-01 + EU- 152 121.78 28 . 40 5.46E-03 1. 56E-01 1. 56E-01 344 . 28 26 . 60 -1.23E-01 2.06E-01 1408 . 00 20.74 7.71E- 02 3 . 19E-01 + EU-154 123 . 07 40 . 40 5 . 18E-04 1.09E- Ol 1. 09E-Ol 723 . 30 19 . 70 2 . 18E- 01 3 . 39E-Ol 1274 . 51 35 . 50 2 . 78E- 02 2 . 31E-01 + EU-155 86 . 54 32 . 80 2 . 76E-02 1.76E-01 1.76E-0 1 105 . 31 21. 80 1. OlE-02 2 . 06E- 01 + BI-214 609 . 31
- 46.30 1.46E-01 1. lOE-01 1.lOE-01 1120 , 29 15.lO 6.SOE- Ol 6.61E-Ol 1238 . 11 5.94 9.26E - Ol l.57E+OO 1377 . 67 4 .11 3.58E-01 1.54E+OO 1407 . 98 2 . 48 6 .44E-01 2 . 66E+OO 1509 . 19 2 . 19 2.42E+OO 3 . 40E+OO 1764.49 15 . 80 2.06E-01 5 . 06E-01
+ PB-214 77 . 11 10.70 4.25E-01 1.61E-Ol 6.72E- 01 295.21 19.20 3 . 47E-01 2 . 74E-01 351 . 92 37 . 20 1. 45E-01 1.61E-01 + PA-228 89 . 95 22 . 00 2 . 14E+Ol 1 . 37E+Ol 2 . 39E+01 93 . 35 35 . 00 2 . 22E+OO 1. 37E+01 105 . 00 16 . 30 4 . 71E+OO 2 . 61E+Ol 12 9 . 22 2 . 97 1 . 04E+02 1 . 37E+02 338 . 32 5.30 8.66E+Ol 9 . 44E+01 463 . 00 13.80 1. 83E+Ol 3 . 46E+Ol 911.23 16 . 70 8 . 38E+Ol 5 . 35E+Ol + AM-241 59.54 36.30 1. 98£-01 3 . lSE-01 3 . lSE-01 + CM-243 1 03 . 76 23.00 - 8 . 07E- 02 l.95E-01 1. 95E - 01 228.18 10.60 -3 . 49E-01 3 . 96£-01 277.60 14 . 00 6.74£- 02 3.39E-01
+ = Nuclide identified during the nuclide identification * = Energy line found in the spectrum > = MDA value not calculated @ = Half-life too short to be able to perform the decay correction ? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/13/2019 10:08:12AM Page 7 of7 Analysis Report for 81-010-001-CIGS-BK01-SB 81-010-001 B
6/13/2019 10:39:19AM Page J of6 _J'Apex-Gamma Analysis Report for B1-010-001-CIGS-BK02-SB B1 -010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BK02-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 8.137E+02 grams Facility : Dairyland_NPP Sample Taken On : 61712019 11:16:00AM Acquisition Started : 6/13/2019 10:09:01AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live lime : 1800.0 seconds Real lime : 1805.4 seconds Dead Time : 0.30% Peak locate Threshold : 3.00 Peak locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6830 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/13/2019 10:39:1 0AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/13/2019 10:39:19AM Page2 of6 Analysis Report for B1-010-001-CIGS-BK02-SB B1-010-001 B Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 76 . 86 147 - 158 154 . 26 6 . 99E+01 32 . 09 5.27E+02 1. 65 F 2 238 .4 6 47 1 - 483 477 . 40 1 . 15E+02 31. 06 3 . 08E+02 1. 9 1 F 3 337 . 91 671 - 684 676 . 25 3 . 15E+Ol 17 . 23 1. 38E+02 1. 57 F 4 351 . 69 696 - 711 703 . 81 7 . 52E+Ol 23 . 22 l . 40E+02 2 . 43 F 5 583 . 08 1161 - 1174 1 1 66 . 50 3 . 3 4E+Ol 1 5 . 87 8 . 50E+Ol 1. 75 F 6 608 .9 8 1212 - 1223 1218 . 29 4 . 31E+01 16 . 91 5 . 37E+Ol 2 . 11 F 7 910 . 58 1817 - 1826 1 82 1. 40 2 . 22E+Ol 11 . 73 3 . 16E+Ol 1. 34 F 8 1460 . 55 2913 - 2930 292 1. 22 2 . 32E+02 30 . 77 9 . 00E+OO 2 . 88 M = First peak in a multiplet region m = Other peak in a mulUplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/13/2019 10:39:10AM Env. Background File : C:\Canberra\Apex\Root\Dairy1and_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 76 . 86 6 . 99E+Ol 32 . 09 6 . 99E+Ol 3 . 21E+Ol F 2 238 . 46 l .1 5E+02 31.06 l . 15E+02 3 . llE+Ol F 3 337 . 91 3 . 15E+Ol 17 . 23 3 . 15E+Ol l . 72E+Ol F 4 351 . 69 7 . 52E+Ol 23 . 22 4 . 18E+Ol l . 86E+Ol 3 . 34E+Ol 2 . 98E+Ol F 5 583 . 08 3 . 3 4E+Ol 15 . 87 3 . 3 4E+Ol 1. 59E+Ol F 6 608 . 98 4 . 31E+Ol 16 . 91 2 . 06E+01 1. 2 1 E+01 2 . 25E+Ol 2 . 08E+Ol F 7 910 . 58 2 . 22E+Ol 11 . 73 2 . 22E+Ol 1.17£+01 F 8 1460 . 55 2 . 32E+02 30 . 77 2 . 82E+Ol 8 . 57E+OO 2 . 03E+02 3 . 19E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma
6/ 13/2019 10:39: 19AM Page3 of6 Analysis Report for B1-010-001-CIGS-BK02-SB 81-010-001 8 NUCLIDE IDENTIFICATION REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K- 40 0 . 99 1460 . 75
- 10 . 67 5 . 45E+00 9 . 07E-01 PB-212 0 . 99 77 . 11
- 17 . 50 2 . 43E-01 1.13E-01 238 . 63
- 44 . 60 1.45E-01 4 . 0l E-02 BI-21 4 0 . 34 609 . 31
- 46 . 30 6.37E-02 5 . 89E-02 1120 . 29 15 . 10 1238 . 1 1 5 . 94 1377 . 67 4 . 11 1407 . 98 2 . 48 1509.19 2 . 19 176 4.4 9 15 . 80 PB-21 4 0 . 52 77 .1 1
- 1 0 . 70 3 . 98E- 0l 1. 84E-0l 295 . 21 19 . 20 351 . 92
- 37 . 20 7 . 08E- 02 6 . 32E- 02
* =Energy line found in the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)
K-40 0 . 994 5 . 45E+00 9 . 07E- 01 PB- 212 0 . 994 l . 51E - 01 3 . 80E- 02 BI - 214 0 . 341 6 . 37E- 02 5 . 89E- 02
6/13/2019 10:39:19AM Pagc4 of6 Analysis Report for 81-010-001-CIGS-8K02-SB 81-010-001 8 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) PB-2 14 0 . 520 7 . 93E - 02 6 . 02E- 02
? = nuclide Is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/13/2019 10:39:19AM Page 5 of6 Analysis Report for B1--010-001-CIGS-BK02-SB B1--010-001 B UNIDENTIFIED PEAKS Peak Locate Performed on : 6/13/2019 10:39:10AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 3 337 . 91 l. 7485 4E-02 27 . 37 Tol. AC- 228 PA- 228 F 5 583 . 08 1 . 85777E - 02 23 . 72 F 7 910 . 58 l . 23 130E - 02 26 . 47 Tol. PA- 228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield{%) Activity Nucl/deMDA LlneMDA Name (pCilgrams) (pCilgrams) (pCl/grams) (keV) + K- 4 0 14 60 . 75
- 1 0 . 67 5 . 45E+00 7 . 62E- 0 1 7 . 62E-0 1
+ @ AR- 41 1 293 . 64 99 . 16 l . 00E+26 l . 00E+26 1 . 00E+26 + CO-60 1173 . 22 100 . 00 -3. 49E- 02 8 . 31E-02 8 . 43E-02 1332 .4 9 100 . 00 3 . 20E- 02 8 . 31E-02 + KR-85 5 1 3 . 99 0 . 43 6 . 20E+00 1. 37E+ 0 l l. 37E+0l + Y- 88 898 . 0 4 93 . 70 1. 4 l E- 02 5 . 44 E- 02 7 . 63E-02 1836 . 06 99 . 20 - 2 . 43E- 02 5 . 44E - 02 + NB- 94 702 . 63 100 . 00 l . 12E-02 5 . 65E-02 5.65E-02 87 1. 10 100 . 00 -l . 02E- 02 6 . 02E - 02 + I - 131 284 .3 0 6 . 06 -3.37E- 0l 9 . 33E-02 l.30 E+00 36 4 . 4 8 81. 20 6 . 46E- 02 9 . 33E- 02 636 . 97 7 . 27 6 . 24 E- 0 1 1. 33E+00 + CS-134 604.70 97.60 7 . 69E-02 7 . 20E-02 7 . 20E-02
6/13/2019 10:39:19AM Page 6of6 Analysis Report for B 1-010-001-CIGS-BK02-SB 81-010-001 B Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCUgrams) (pCUgrams) (pCi/grams) (keV) CS-134 795 . 84 85 . 40 -1.70E-03 7 . 2 0E-02 7.32E-02 + CS-137 661.65 85.12 -1. 53E-02 7 . 41 E-02 7 . 41E-02 + CE-144 80.12 1. 36 -2 . 16E+OO 3 . 98E-01 4.92E+OO 133.51 11.09 3 . 65E-01 3 . 98E-01 + EU-152 121.78 28 . 40 -1. 03E-01 l.47E-01 1.47E-Ol 344.28 26 . 60 -2 . 33E-02 l . 94E-Ol 1408. 00 20 . 74 2 . 00E-02 3 . 21E-Ol + EU-154 123.07 40.40 -9 . 49E-02 1. 03E-Ol 1 . 03E-01 723.30 19 . 70 2 . 32E-01 3 . 35E-01 1274.51 35.50 -l.43E-01 2 . 33E-01 + EU - 1 55 86.54 32.80 8 . 00E-02 1 . 72E-01 1 . 72E-Ol 105.31 21. 80 -1. 35E-01 2 . 06E-01 + BI-214 609.31
- 46.30 6 . 37E-02 l.12E-01 l.12E-Ol 1120.29 15.10 - 1 .06E-01 5.50E-01 1238 .11 5.94 4.69E-01 1.62E+ OO 1377 . 67 4 .11 5.76E-01 1. 72E+OO 1407 . 98 2.48 1. 67E-Ol 2.68E+OO 1509.19 2 . 19 5 . 03E-01 2.70E+OO 1764.49 15 . 80 1. 29E-01 4.64E-Ol
+ PB-214 77.11
- 10.70 3.98E-01 1 .34E-01 4.96E-01 295.21 19 . 20 2.97E- 01 2.76E-01 351.92
- 37 . 20 7 . 08E-02 1. 34E-01
+ PA-228 89.95 22 . 00 7.00E+OO 1. 31E+Ol 2.21E+Ol 93 . 35 35.00 2 . 02E+OO l . 31E+Ol 105.00 16.30 -2.87E+Ol 2.48E+Ol 129 . 22 2 . 97 5 . 89E+Ol l . 31E+02 338.32 5 . 30 1 . 97E+Ol 8 . 40E+Ol 463.00 13.80 -6 . 18E+OO 3.41E+Ol 911.23 16 . 70 3 . 45E+OO 4 . 31E+Ol + AM-241 59 . 54 36 . 30 - 5 . 61 E- 02 3.0 l E-01 3 . 0lE-01 + CM-243 103 . 7 6 23.00 -7.28E-02 1. 97E-0 1 l.97E-0 1 228.18 10.60 3.SlE-01 4 . 1 7E-01 277 . 60 14 . 00 1. 79E- 01 3.34E-Ol
+ = Nuclide identified during the nuclide identification * = Energy line found in the spectrum > = MDA value not calculated @ = Half-life too short to be able to perfom, the decay correction ? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
6/13/2019 8:00:40AM Page I of5 Analysis Report for B1-010-001-CIGS-BI02-SB B1-010-001 B GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001-CIGS-BI02-SB Sample Description : B1-010-001 B Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 7.731E+02 grams Facility : Dairytand_ NPP Sample Taken On : 6/8/2019 1:18:00PM Acquisition Started : 6/13/2019 7:30:22AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli live Time : 1800.0 seconds Real Time : 1805.3 seconds Dead Time : 0.29 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 6826 PEAK ANALYSIS REPORT Peak Analysis Performed on : 6/13/2019 8:00:31AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
6/13/2019 8:00:40AM Page 2 ofS Analysis Report for B1-010-001-CIGS-BI02-SB B1-010-001 B Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 62 472 - 485 477 . 71 1 . 12E+02 27 . 64 2 . 39E+02 1. 64 F 2 295 . 01 585 - 595 590 . 48 3 . 77E+Ol 18 . 96 1. 52E+02 1.39 F 3 582.95 1162 - 1173 1166 . 23 3 .9 5E+Ol 15 . 05 4 . 63E+Ol 1.43 F 4 1460.9 1 2914 - 2930 2 921.94 2 .2 9E+02 3 0. 90 1. 64E+Ol 2.77 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 6/13/2019 8:00:31AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 62 l . 12E +02 27.64 l.1 2E+02 2 . 76E+O l F 2 295 . 01 3 . 77E+Ol 18 . 96 3 .7 7E+Ol l . 90E+Ol F 3 582 . 95 3 . 95E +Ol 15.05 3 . 95E+Ol 1 . SOE+O l F 4 1460 . 91 2 . 29E +02 3 0 .90 2 . 82E+O l 8 . 57E+OO 2 . 01E+02 3.21E+O l
=
M First peak in a multiplet region
=
m Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES
6/13/2019 8:00:40AM Page 3 of5 Analysis Report for 81-010-001-CIGS-8 I02-SB 81-010-001 B Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K- 40 0 . 99 14 60 . 75
- 1 0. 67 5 . 65E+00 9 . 57£-01 PB-212 0 . 56 77 . 11 17 . 50 238 .6 3
- 44 .6 0 1. 4 9E - 0l 3 . 77£- 02
* = Energy line found in the spectrum.
* = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pC/Jgrams)
K- 40 0 . 996 5 . 65E+00 9 . 57E-0 1 PB- 212 0 . 560 l .4 9E- 0 1 3 .7 7E-02
? = nuclide is part of an undetermined solution X = nuclide rejected by the Interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
6/13/2019 8:00:40AM Page4 of5 Analysis Report for B1-010-001-CIGS-BI02-SB 81-010-001 B UNIDENTIFIED PEAKS Peak Locate Perfonned on : 6/13/2019 8:00:31AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide F 2 295 . 01 2 . 09670E-02 25 . 12 Tol. PB-214 F 3 582 . 95 2 . 19673E-02 19 . 03 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(3/4) Activity Nucl/deMDA LlneMDA Name (pCl/grams) (pCVgrams) (pCilgrams) (keV) + K-40 1460.75
- 10.67 5 . 65E+00 8.61E-01 8 . 61E - 01
+ AR-41 1 293 . 64 99.16 -1.15E+17 4.53E+17 4.53E+17 + CO-60 11 73 . 22 100.00 -3.45E-02 7 . l0E-02 9.65E- 02 1 332.49 100.00 -1. 45E- 04 7 . l0E- 02 + KR-85 513.99 0.43 1. 65E+0l 1. 56E+0l 1. 56E+0l + Y-88 898.04 93.70 3.49E-02 5 . 68E-02 8 . 03E-02 1836.06 99.20 4.59E-03 5 . 68E-02 + NB-94 702 . 63 100.00 2.00E-02 5 . 80E-02 5.80E-02 871 . 10 100.00 -3 . 0lE-03 6.60E-02 + I-131 284.30 6.06 3.98E-02 8 . 66E-02 1.15E+00 364.48 81. 20 -5 . 96E-03 8.66E-02 636.97 7.27 4.98E-01 1.17E+00 + CS-134 604.70 97.60 3 . 70E-02 6 . 87E-02 7.26E - 02 795.84 85 .4 0 4 . 98E-03 6.87E-02 + CS-137 661. 65 85.12 7 . 03E-02 8 . 69E-02 8.69E - 02 + CE-144 80.12 1. 36 -9.05E-01 4 . 1 2E-01 4.91E+00
6/13/2019 8:00:40AM Page 5 of5 Analysis Report for 81-010-001-CIGS-8I02-SB 81-010-001 B Nuclide Energy Yield{%) Activity Nucl/deMDA LineMDA Name (pCl/grams) (pCi/grams) (pCl/grams) (keV) CE-144 133.51 11. 09 -1. 86E-02 4.12E- 01 4 . 12E-01 + EU- 152 121.78 28.40 -6 . SOE-02 1. 56E-01 1.56E-01 344 . 28 26.60 -4.44E-01 l .90E-01 1408 . 00 20.74 1.02E-01 3 . 08E-01 + EU-154 123.07 40.40 1. 23E-02 1. llE-0 1 1. llE-01 723 . 30 1 9.70 2 . 94E-02 3 . 30E-01 1274 . 51 35.50 -1. 49E-01 2 . 03E-01 + EU-155 86 . 54 32.80 -l.20E-Ol 1. 67E-01 1.67E-01 105.31 21. 80 1. 36E-02 2.16E-01 + BI-214 609 . 31 46.30 l.98E-01 1.55E- 01 1. 55E-01 1120 . 29 15.10 -5. 75E -01 5.73E-01 1238 . 11 5.94 -1 . 0lE-01 1.69E+OO 1377.67 4.1 1 1. 59E-01 1.52E+OO 1407.98 2.48 8 .5 2E-01 2 . 57E+OO 1509.19 2 . 19 -9.71E-01 2.24E+OO 1764 . 49 15.80 2 . 59E-01 4.75E-Ol + PB-214 77 . 11 10.70 5.09E-01 1.46E- 01 6 . 78E-01 295.21 19.20 1.13E-01 2 . 71E-01 351 . 92 37.20 1 . 72E-Ol 1.46E-01 + PA-228 89 . 95 22.00 1. 51E+OO 5 . 20E+OO 8.81E+OO 93 . 35 35.00 =3.03E+00 5 . 20E+00 105.00 16 . 30 - 2.75E+OO 1. OSE+Ol 129 .22 2.97 7 . 31E+OO 5.62E+Ol 338.32 5.30 1 . 68E+Ol 3.47E+Ol 463.00 13.80 7 . 13E +OO 1. 52E+Ol 911. 23 16 .7 0 l . 57E+OO 1. 81E+Ol + AM-241 59 . 54 36.30 -2.63E-01 3.03E-01 3 . 03E-01 + CM-243 103.76 23 . 00 - 4.96E- 02 2 . 02E-Ol 2 . 02E-01 228 . 18 10.60 1. 63E-01 4.28E-01 277.60 14 . 00 l. 78 E-02 3.38E-01
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 , __,4:34PM Page I of6
~pex-Gamma Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C01-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 (O" - 0.5") TOP Sample Description : B1-010-001-CSFC-C01-CV Sample Type : Planchet Unit Sample Point Sample Size 1.711E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 9:25:00AM Acquisition Started : 3/21/2019 11 :54 :18AM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 1200.0 seconds Real nme : 1203.7 seconds Dead nme : 0.31 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100- 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 5929 PEAK ANALYSIS REPORT Peak Analysis Perfonned on : 3/21/2019 12:14:25PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 1
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 12:14:34PM Page 2 of 6 Analysis Report for 81-010-001 (O"
- 0.5") TOP 81-010-001-CSFC-C01-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)
F 1 238 . 42 4 72 - 4 81 477 . 31 5 . 40E +0l 20 . 94 1 . 50E+02 1. 34 F 2 295 . 41 588 - 595 591 . 27 3 . 68 E+ 0l 1 6 . 82 6 . 95E+0l 1. 4 6 F 3 351 . 94 700 - 710 704 . 31 5 . 44 E+0l 18.6 4 8 .9 0E+0l 1. 4 5 F 4 583 . 36 116 1 - 1173 11 67 . 07 2 . 78 E+0l 12 . 33 2 . 00E+0l 2 . 00 F 5 609 . 14 1213 - 1224 1218 . 62 3 . 81£+01 14. 81 4. 24E+0l 1. 57 F 6 1460 . 90 2914 - 2929 2921 . 92 9 . 54E +0l 2 0.0 8 3 . 99E+0 0 2 . 58 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I 8KG. SUBTRACT Peak Analysis Performed on : 3/21/2019 12:14:25PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio
- Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 238 . 42 5 . 40E+ 0 l 20 . 94 5 . 40£+01 2 . 09E +0l F 2 29 5. 41 3 .68 E+ 0 l 1 6. 82 1 . 73E+0l 9 . 5 9E+00 1 . 94E+0l 1 . 94E+0l F 3 351 . 9 4 5 .44 E+0l 18 . 64 2 . SS E+0 l l . 03E+0l 2 . 89E+0l 2 . 13E+0l F 4 583 . 3 6 2 . 78Et01 12 . 33 2 . 78E+0l l . 23E +0l F 5 609 .14 3 . 81E+01 14.8 1 l . 29E+0l 7 . 69E+0 0 2. 5 2E+0l l. 67E+0l F 6 1460 . 90 9 . 5 4E+01 20 . 08 l . 90E+0l 5 . 03E+00 7 . 64E+0l 2. 07E+0l M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 10/26/2020 Page 2
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1£. ,-+:34PM Page 3 of 6 Analysis Report for B1-010-001 (O" - 0.5") TOP B 1-010-001-CSFC-C01-CV NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCilgrams) Uncertainty K-40 0 . 996 1460 . 75
- 10 . 67 1 . 25E+0l 3 . 47E+00 PB-212 0 . 522 77 . 11 17 . 50 238 . 63
- 44 . 60 3 . 48E-01 1 . 36E - 01 BI - 214 0 . 362 609 .3 1
- 46 . 30 4 . 02E - 01 2 . 68E- 01 1120 . 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1 4 07 . 98 2.48 1509.19 2 . 19 1764 . 49 15 . 80 PB - 21 4 0 . 691 77 . 11 10 . 70 295 . 21
- 19 . 20 3 . 56E - 01 3 . 55E-0 1 351.92
- 37 . 20 3 . 26E - 01 2 . 41E-01
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak locate Performed on : 3/21/2019 12:14:25PM Peak locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide F 4 583 . 36 2 . 31690E - 02 22 . 17 10/26/2020 Page 3
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 12:14:34PM Page4 of6 Analysis Report for B1-0 10-001 (O"
- 0.5") TOP B1-010-001-CSFC-C01-CV M = First peak in a multiplet reg ion m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)
K-40 0 . 996 l . 25E+Ol 3 . 47E+OO PB-212 0 . 522 3 . 48E - 01 1. 36E - 01 BI-214 0 . 362 4 . 02E - 01 2 . 68E - 01 PB - 214 0.691 3 . 35E - 01 l . 99E - 01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 4
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 12:14:34PM Page 5 of6 Analysis Report for B1 -01 0-001 (O" - 0.5") TOP B1-010-001-CSFC-C01-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21/2019 12:14:25PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 4 583.36 2.31690E-02 22 . 17 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyfand_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield{%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCi/grams) (keV)
+ K- 40 1460.75
- 10.67 l . 25E+0l 3 .4 7E+00 3 . 47E+00
+ AR- 41 1293 . 64 99 . 16 6.04E-01 9.90E - 01 9 . 90£ - 01
+ CO-60 1173 . 22 100 . 00 1 . 88E-01 4 . 17E-0l v 4 . 62E-01 1332 .49 100 . 00 l . 78E-01 4 . 17E- 01
+ KR -8 5 513 . 99 0 . 43 4 . 72E+0l 6 . 55E+0l 6 . 55E+0l
+ Y- 88 898 . 04 93 . 70 -2 . 50E-0l 2 . 92E-01 2 . 92E-01 1836.06 99.20 2 .18E-01 3 .80 E-01
+ I-131 284 . 30 6 . 06 -2 . 15E+00 2.28E-0l 3 . 12E+00 364 . 48 81.20 -9 . 94E-02 2.28E-01 636.97 7 . 27 l . 08E+0O 3 .4 2E+O0
+ CS-134 604 . 70 97 . 60 1 . 34E-02 3.39E-01 3 . 54E-01 795 . 84 85.40 - 1 . llE- 01 3.39E-01
+ CS - 137 661. 65 85 . 12 4.21E - 02 3 . 75E - Ol v°' 3 . 75E - 01
+ CE - 144 80 . 12 1. 36 l . 02E+0l 1 .4 8E+00 1. 58E+Ol 133 . 51 11. 09 5 . 84E-0l l . 48E+O0
+ EU - 152 121 . 78 28 . 43 -2 . 41E-01 5 . 13E-01 5 . 13E-01 344 . 28 26 . 60 -6.98E-01 8 . 07E-0 1 10/26/2020 Page 5
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 12:14:34PM Page6 of6 Analysis Report for B1-010-001 (0" - 0.5") TOP B1 -010-001-CSFC-C01-CV Nuclide Energy Yield(%) Activity Nuclide MDA LlneMDA Name (pCilgrams) (pCUgrams) (pCUgrams) (keV} EU-152 1408 . 08 20 . 75 l . 22E+OO 5 . 13E - 01 // l . 69E+OO
+ EU-154 123 . 07 40 . 40 -2.17E-01 3 . 68E-01 3 . 68E-Ol 723 . 30 19 . 70 4 . 92E-01 l . 50E+OO 1274 . 51 34 . 40 8 . 22E-01 l . 14E+OO
+ EU-155 86 . 54 32.80 6 . l0E-02 5 . 68E - 01 5 . 68E-01 105 . 31 21. 80 -1 . 57£-01 6 . 80E-01
+ BI - 214 609 . 31
- 4 6 . 30 4 . 02E-01 5.21E-01 5 . 21£-01 1120.29 15 . 10 1 . 17E+OO 2 . 76E+OO 1238 . 11 5.94 5 . 17E+OO 8 . lOE+OO 1377. 67 4 .11 4 . 94E 00 9 . 89E+OO 1407.98 2 . 48 1 . 02E+Ol 1 . 41E+Ol 1509 .1 9 2 . 19 -l . 24E+OO 9 . 91E+OO 1764 . 49 15 . 80 - 5 . 65E-01 2.20E+OO
+ PB-214 77 . 11 10.70 1.88E+OO 5 . 00E-01 2 . 14E+OO 295.21
- 19 . 20 3 . 56£ - 01 6 . 84E-01 351. 92
- 37 . 20 3.26£-01 5.00E- 01
+ PA-228 89 . 95 22 . 00 7 . 09E-01 5 . 29E-01 8 . 90E- 01 93 . 35 35 . 00 9 . 32E-02 5.29£- 01 105 . 00 16 . 30 4 . 02£-01 9 . 93E - 01 129 . 22 2 . 97 l . 72E+OO 5 . 80E+OO 338.32 5 . 30 - 9 . 67E-02 4 . 33E+OO 463 . 00 13 . 80 4 . 13£-01 1 . 85E+OO 911. 23 16.70 1 . 44E+OO 2 . 27E+OO
+ AM-241 59 . 54 36 . 30 2.09E-01 8 .7 9E-Ol 8.79E - 01
+ CM-243 103.76 23 . 00 3 . 29£ - 01 6 . 52£-01 6 . 52E-01 228 . 18 10.60 -l . 43E+OO l . 46E+OO 277 . 60 14 . 00 6 . 06£ - 01 1 . 42E+OO
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 6
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1L.J1 :57PM Page I of6
~pex-Gamma Analysis Report for 81-010-001 (0" - 0.5") BOTTOM 81-010-001-CSFC-C01-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 (0" - 0.5") BOTTOM Sample Description : 81-010-001-CSFC-C01-CV Sample Type : Planchet Unit Sample Point Sample Size 1.711E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 9:25:00AM Acquisition Started : 3/21/2019 12:16:40PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live nme : 900.0 seconds Real nme : 902.9 seconds Dead nme : 0.32 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number Peak Analysis Performed on : 3/21/2019 12:31 :48PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 7
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 12:31 :57PM Page 2 of6 Analysis Report for B1-010-001 (o* - 0.5") BOTTOM B 1-010-001-CSFC-C01-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 62 469 - 485 477.71 7 . 77E+Ol 23 . 44 l . 62E+02 2 . 28 F 2 352 . 00 698 - 710 704 . 42 4 . 93E+Ol 16 . 91 5 . 55E+Ol 1. 69 F 3 583 . 15 1163 - 1171 1166 . 64 2 . 00E+Ol 9 . 83 l . 54E+Ol 0 . 86 F 4 609 . 63 1215 - 1226 1219 . 58 3 . 62E+Ol 14 . 17 3 . 60E+Ol 1. 61 F 5 1461 . 21 2916 - 2930 2922 . 54 8 . 19E+Ol 18 . 60 6 . 58E+OO 2 . 42 M = First peak in a multiplet region m = Other peak in a mult!plet reg ion F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCEPEAK/BKG.SUBTRACT Peak Analysis Performed on : 3/21/2019 12:31 :48PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is : Original
- Peak Ratio
- Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 238 . 62 7 . 77E+Ol 23 . 44 7 . 77E+Ol 2 . 34E+Ol F 2 352 . 00 4 . 93E+Ol 16 . 91 l . 91E+Ol 7 . 75E+OO 3 . 02E+Ol 1. 86E+Ol F 3 583 . 15 2 . 00E+Ol 9 . 83 2 . 00E+Ol 9 . 83E+OO F 4 609 . 63 3 . 62E+Ol 1 4. 17 9 . 69E+OO 5 . 77E+OO 2 . 65E+Ol 1 . 53E+Ol F 5 14 61. 21 8 . 19E+Ol 18 . 60 1 . 43E+Ol 3 . 77E+OO 6 . 76E+Ol l . 90E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 8
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 12:31 :57PM Page 3 of 6 Analysis Report for 81-010-001 (O" - 0.5") BOTTOM B1 -010-001-CSFC-C01-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCi/grams) Uncertainty K-40 0 . 966 1460 . 75
- 10 . 67 1 . 48E+0l 4 . 24E+00 PB-212 0 . 527 77 . 11 1 7 . 50 238 . 63
- 44 . 60 6 . 67E- 01 2 . 04E-01 BI-214 0 . 357 609 . 31
- 46 . 30 5 . 66E-01 3 . 28E-01 1120 . 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2 . 48 1509 . 19 2 . 19 1764 . 49 15 . 80
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted al 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21 /2019 12:31 :48PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS} Peak No. Energy (keV) Uncertainty Type Nuclide F 2 352 . 00 3 . 35430E-02 30 . 80 Tol. PB-21 4 F 3 583 . 15 2 . 22086E- 02 24 . 59 M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma 10/26/2020 Page 9
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 12:31 :57PM Page 4 of6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B 1-010-001 -CSFC-C01-CV INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0 . 966 1 . 48E+01 4 . 24E+OO PB-212 0 . 527 6 . 67E-01 2 . 04E - 01 BI-214 0 . 357 5 . 66E-01 3 . 28E-01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 10
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 12:31 :57PM Page 5 of6 Analysis Report for B1-010-001 (0" - 0.5") BOTTOM B1-010-001-CSFC-C01-CV UNIDENTIFIED PEAKS Peak Locate Perfomied on : 3/21/2019 12:31 :48PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke V} Peak Size (CPS) Uncertainty Type Nuclide F 2 352 . 00 3 . 35 4 30E - 02 30 . 80 Tol. PB- 214 F 3 583 . 15 2 . 22086E-02 24 . 59 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nudide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield{%) Activity NuclideMDA LineMDA Name (pCl/grams) (pCl/grams) (pCl/grams) (keV)
+ K-40 1460 . 75
- 10 . 67 1 .48 E+01 4 . 32E+00 4 . 32E+00
+ AR- 41 1293 . 64 99 . 16 - 1 . 28E- 0l 1. 39E+00 / 1. 39E+00
+ CO- 60 1173 . 22 100 . 00 5 . 81E- 02 4 . 65E- 01 4 . 65E- 01 1332 . 49 100 . 00 2 . 91 E- 01 4 . 81E - 01
+ KR- 85 513 . 99 0 . 43 6 . 94 E+ 0l 8 . 07 E+0l 8 . 07E+0l
+ Y- 88 898 . 04 93 . 70 6 . 39E-02 2 . 70E-01 3 . 41E-01 1836 . 06 99 . 20 - S. 39E - 01 2 . 70E-01
+ I - 131 284 . 30 6 . 06 - 2 . 07E+00 3 . 08E - 01 3 .4 3E+00 364 . 48 81 . 20 3 . 81E- 02 3 . 08E-0 1 636 . 97 7 . 27 1 . 71E+00 4. 61E+00
+ CS - 134 604 . 70 97.60 - 1 . 71E- 0 1 4 . 23E -0 1 4 . 23E - 01 795 . 8 4 85 . 40 1 . 25E- 01 5 . 03E - 01
+ CS - 137 661. 65 85 . 12 - 8 . 09E- 03 3 . 91E-01 3 . 91E-01
+ CE - 144 80 . 12 1.36 - 1 . 49E+00 1 . 80E+ 0 0 l . 84E+0l 133 . 51 11 . 09 1. S0E+00 l . 80E+00 10/26/2020 Page 11
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 12:31 :57PM Page6 of6 Analysis Report for B1 -010-001 (O"
- 0.5") BOTTOM 81 -010-001 -CSFC-C01 *CV Nuclide Energy Yield(%) Activity NuclideMDA LlneMDA Name (pCi/grams) (pCilgrams) (pCUgrams)
(keV)
+ EU - 152 121 . 78 28 . 43 -3 . 48E - 01 6 . 27E - 01 / 6 . 27E-01 344 . 28 26 . 60 1.44E- 01 9 . 52E- 01 1408 . 08 20 . 75 7.41E-01 2 . 05E+00
+ EU-154 123 . 07 40 . 40 -5 . 83E-02 4 . 48E- 01 / 4 . 48E-0l 723 . 30 19 . 70 -2 . llE- 01 1 . 76E+00 1274 . 51 34 . 40 8 . 21E-01 1 . 37E+00
+ EU-155 86 . 54 32 . 80 4 . 88E-02 6 . 48E-01 6 . 48E-01 105 . 31 21. 80 1 . 50E- 01 8 . 52E-01
+ BI - 214 609 . 31
- 46 . 30 5 . 66E- 01 6 . 19E- 01 6 . 19E-01 1120 . 29 15 . 10 -9 . 00E- 01 3 . 06E+00 1238 . 11 5 . 94 -4 . 20E- 01 9 . 18E+00 1377 . 67 4 . 11 6 . 45E+00 1. 0lE+0l 1407 . 98 2 . 48 6 . 20E+00 1 . 71E+0l 1509 . 19 2 . 19 7 . 15E- 01 l . 44E+0l 1764 . 49 15 . 80 1. 41E+00 2 . 79E+00
+ PB- 214 77 . 11 10 . 70 l . 19E+00 8 . lOE - 01 2 . 54E+00 295 . 21 19 . 20 7 . 62E-01 1 . 26E +00 351 . 92 37 . 20 7 . 42E-01 8 . l0E - 01
+ PA- 228 89 . 95 22 . 00 -6 . 07E-02 6 . 31E- 01 1 . 03E+00 93 . 35 35 . 00 -2 . 20E - 02 6 . 31E- 01 105 . 00 16 . 30 9 . 06E- 01 l . 27E+00 129 . 22 2 . 97 - l . 26E+00 6 . 96E+00 338 . 32 5 . 30 4 . 00E - 01 5 . 0SE+00 463 . 00 13 . 80 -4 . 66E - 01 1 . 90E+00 911. 23 16 . 70 1 . 50£+00 2 . 98E+00
+ AM- 241 59 . 54 36 . 30 3 . 36E - 02 9 . 98E-01 9 . 98E - 01
+ CM- 243 103 . 76 23 . 00 - l . 72E- 01 8 . 12E-01 8 . 12E- 0l 228 .1 8 10 . 60 -5 . 65£ - 01 1 . 95E +00 277 . 60 14 . 00 - 1. 82E - 01 1. 57E+00
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 12
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 ,), L1 :57PM Page I of S
~pex-Gamma Analysis Report for 81-010-001 (O" - 0.5") TOP 81-010-001-CSFC-C02-CV GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001 co* -0.5") TOP Sample Description : 81-010-001-CSFC-C02-CV Sample Type : Planchet Unit Sample Point Sample Size 1.319E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 1:54:00PM Acquisition Started : 3/21/2019 3:06:41PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live lime : 900.0 seconds Real lime : 902.8 seconds Dead lime : 0.31 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number Peak Analysis Performed on : 3/21/2019 3:21 :48PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 13
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:21 :57PM Page 2 of 5 Analysis Report for 81-010-001 (O" - 0.5") TOP B 1-010-001-CSFC-C02-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. {keV) start end Centroid Area Uncertainty Counts (keV) F 1 1461.29 2916 - 2929 2922 . 69 6 . 69E+Ol 16 . 75 3 . 33E+OO 2 . 50 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I BKG. SUBTRACT Peak Analysis Performed on : 3/21 /2019 3:21 :48PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairytand_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 1461. 2 9 6 . 69E+Ol 16 . 75 l . 43E+Ol 3. 77E+ OO 5 . 27E+Ol 1 . 72E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairytand_ NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCi/grams) Uncertainty K-40 0 . 955 1460 . 75
- 10 . 67 1 . 50E +Ol 4 . 95E+OO 10/26/2020 Page 14
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:21 :57PM Page 3 of 5 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C02-CV
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21/2019 3:21 :48PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide All peaks were identified . M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) K- 40 0 . 955 l . 50E+Ol 4 . 95E+OO
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 15
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:21 :57PM Pagc4 of5 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C02-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21 /2019 3:21 :48PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Rool\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA LineMDA Name (pCl/grams) (pCl/grams) (pCilgrams) (keV)
+ K-40 1460 . 75
- 10 . 67 1. SOE+Ol 5 . 18E+OO 5 . 18E+OO
+ AR- 41 1293 . 64 99 . 16 4 . 97E - 01 8 . 20E - 01 8 . 20E - 01
+ C0- 60 1173 . 22 100 . 00 - 1 . 69E-01 4 . 41E-Ol ..,- 4 . 63E-01 1332 . 49 100 . 00 3 . 30E-02 4 . 41E - 01
+ KR- 85 513 . 99 0 . 43 5 . 19E+Ol 9 . 21E+Ol 9 . 21E+Ol
+ Y- 88 898 . 04 93 . 70 2 . 97E - 04 4 . 42E-01 4 . 42E - 01 1836 . 06 99 . 20 - 3 . 59 E-02 4 . 95E - 01
+ I-131 284 . 30 6 . 06 -1 . 95E- 01 3 . 46E - 01 4 . SOE+OO 364 . 48 81.20 1. 21E - 01 3 . 46E - 01 636 . 97 7 . 27 6 . ll E- 01 4 . 72E+OO
+ CS- 134 604 . 70 97 . 60 4 . 95E-01 4 . 82E - 01 5 . 16E- 01 795 . 8 4 85 . 40 4 . 91E- 03 4. 82E - 01
+ CS - 137 661. 65 85 . 12 1.86E- 01 5 . 43E- 01 ,r 5 . 43E - 01
+ CE - 144 80 . 12 1.36 - 6 . 64E+OO 2 . 00E+OO 2 . 14E+Ol 133 . 51 11. 09 l . 65E+OO 2 . 00E+OO
+ EU-1 52 121 . 78 28 . 43 - 1 . 20E - 01 7 .4 6E- 01 t""' 7 . 46E- 01 34 4. 28 26 . 60 - 2 . 27E+OO l . 04E+OO 1408 . 08 20 . 75 l . 69E+OO 2 . 65E+OO 10/26/2020 Page 16
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:21 :57PM Page 5 of 5 Analysis Report for 81-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C02-CV Nuclide Energy Yield(%) Activity NuclideMDA Line MDA Name (pCi/grams) (pCi/grams) (pCilgrams) (keV)
+ EU-154 123 . 07 40 . 40 1. OSE - 01 5 . 27E-01 .,/ 5 . 27E-01 723 . 30 19 . 70 l . 47E - 01 2 . 08E+OO 1274 . 51 34 . 40 1 . 03E+OO 1 . 94E+OO
+ EU - 155 86 . 54 32 . 80 2 .4 1E- 01 8 . 05E-01 8 . 0SE - 01 105 . 31 21. 80 - 2 . 38E - 01 9 . 63E-01
+ BI - 214 609 . 31 4 6. 30 4.17E - 01 l . 05E+OO l . 05E+OO 1120 . 29 15 . 10 1 . 71E +OO 4 . 04E + OO 1238 . 11 5 . 94 3 .4 7E+OO l . 09E+Ol 1377 . 67 4 . 11 3 . 63E+OO l.21E+Ol 1407 . 98 2 . 48 l . 42E+Ol 2 . 22E+Ol 1509 . 19 2 . 19 -4 . 46E+OO 1. 32E+Ol 1764.49 15 . 80 9 . 14E-01 2 . 74E+OO
+ PB-214 77 . 11 10 . 70 1.09E+OO 8 . 22E - 01 2.90E+OO 295 . 21 19.20 2 . 06E - 01 l . 54E+OO 351. 92 37 . 20 6.25E - 01 8.22E-01
+ PA-228 89 . 95 22.00 3 . 35E-Ol 7 . 06E-Ol 1 . 22E+OO 93 . 35 35 . 00 -2 . 29E-01 7 . 06E-01 105 . 00 16.30 -l.43E-01 l . 34E+OO 129 . 22 2 . 97 2 . 67E+OO 7 . 98E+OO 338.32 5.30 2 . 51E+OO 5 . 47E+OO 463 . 00 13 . 80 -5 . 92E- 01 2 . 28E+OO 911 . 23 16. 70 2 .5 2E+OO 3 . 17E+OO
+ AM-241 59 . 54 36 . 30 -6 . 0BE-01 l . 27E+OO 1. 27E+OO
+ CM-243 1 03 . 76 23 .0 0 - 5 . 91E - 01 8 . 9 1E- 01 8 . 91E - 01 228.18 10.60 -1.31£-02 2 . 33E+OO 277 . 60 14 . 00 7 . 78E-01 1.89E+OO
+ = Nuclide identified during the nuclide identification
= Energy line found In the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION : MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 17
LAC LTP - Final Status Survey Package - 3/26/2019 3/2112019 3:37:46PM Page I of6
~pex-Gamma Analysis Report for B1-010-001 (0" - 0.5") BOTTOM B1-010-001-CSFC-C02-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 (0" - 0.5") BOTTOM Sample Descliptlon : B1-010-001-CSFC-C02-CV Sample Type : Planchet Unit Sample Point Sample Size 1.319E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 1:54:00PM Acquisition Started : 3/21/2019 3:22:30PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds Real Time : 903.0 seconds Dead Time : 0.33 %
Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100 - 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 5939 PEAK ANALYSIS R#oid Peak Analysis Performed on : 3/21/2019 3:37:37PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 18
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 3:37:46PM Page 2 of 6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B1-010-001-CSFC-C02-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 57 474 - 484 477 . 61 4 . 89E+0l 18 . 73 9 . 67E+0l 1. 77 F 2 352 . 11 700 - 710 704 . 65 3 . 99E+0l 16 . 06 4 . 80E+0l 1. 8 7 F 3 14 61.15 2917 - 2930 2922 . 41 4 . 95E+0l 14 . 66 5 . 61E+00 2 . 14 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I 8KG. SUBTRACT Peak Analysis Performed on : 3/21/2019 3:37:37PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 238 . 57 4 . 89E+0l 18 . 73 4. 89E+0l 1 . 87E+0l F 2 352 . 11 3 . 99E+0l 16 . 06 1 . 91E+0l 7. 75E+ 0 0 2 . 08E+0l 1 . 78E+0l F 3 1461.15 4 . 95E+0l 14 .6 6 1 . 43E+0l 3 . 77E+00 3 . 52E+0l 1 . 51E+0l M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Ubrary\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 19
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:37:46PM Page 3 of 6 Analysis Report for 81-010-001 (O" - 0.5") BOTTOM B1-010-001-CSFC-C02-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCilgrams) Uncertainty K-4 0 0 . 975 14 60 . 75
- 10.67 l . 00E+0l 4 . 34E+00 PB- 212 0 . 527 77 . 11 17 . 50 238 . 63
- 44 . 60 5 . 44E - 01 2 . llE - 01
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Perforrned on : 3/21/2019 3:37:37PM Peak locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (ke V) Uncertainty Type Nuclide F 2 352 . 11 2 . 30917E - 02 42 . 90 Tol. PB - 214 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams) K- 40 0 . 975 l . 00E+0l 4 . 34E+00 10/26/2020 Page 20
LAC LTP - Final Status Survey Package - 3/26/2019 3121/2019 3:37:46PM Page4of 6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B 1-010-001-CSFC-C02-CV Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) PB- 212 0 . 52 7 5 . 4 4E- 01 2. llE - 01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 21
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:37:46PM Page S of6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B 1-010-001-CSFC-C02-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21 /2019 3:37:37PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 352 . 11 2 . 30917E- 02 42 . 90 PB - 214 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield{%) Activity NuclideMDA LlneMDA Name (pCI/grams) (pCllgrams) (pCI/grams) (keV)
+ K- 40 1460 . 75
- 10 . 67 l . 00E+0l 5 .4 3E+00 5 .4 3E+0 0
+ AR - 41 1293 . 64 99 . 16 2 . 12E- 01 l . 00E+00 l.00E+00
+ CO - 60 1173.22 100 . 00 2 . 22E- 02 5 . 92E - 01 6 . 15E-01 1332 . 49 100 . 00 1. 04E - 02 5 . 92£ - 01
+ KR- 85 513 . 99 0 .4 3 2 . 16E+0l 9 . 05E+0l 9 . 05E+0l
+ Y- 88 898 . 04 93 . 70 8 . 81E-02 4. 54E-01 4 . 54£ - 01 1836 . 06 99 . 20 - 1 . 32E - 0 2 4 . 95E-01
+ I - 131 284 . 30 6 . 06 3 . 60E - 01 3 . 5 2E-0l 4 . 31E+00 364 . 48 8 1. 20 - l . 33E- 01 3.52E - 01 636 . 97 7 . 27 - 6 . 16E-0 1 4 . 90E+00
+ CS- 134 60 4. 70 97 . 60 6 . 02E- 01 4. 80E- 01 4 . 80E - 01 795 . 84 85 . 40 2 . 29E-0 2 5 . 0lE - 01
+ CS - 137 661. 65 85 . 12 9 . 93E- 02 5 . 43E - 01 5 . 43E - 01
+ CE- 144 80 . 12 1. 36 3 . 16E+00 1 . 98E+00 2 . 28E+0l 133 . 51 11. 09 - 8 . 23E-01 1 . 98E+00
+ EU- 15 2 121. 78 2 8 .4 3 l . 5 1E- 0l 8 . 0 2E- 01 / 8 . 02E - 01 344 . 28 2 6. 60 - 4 . 17E- 01 1. 27E+00 10/26/2020 Page 22
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:37:46PM Page 6 of6 Analysis Report for 81-010-001 (O" - 0.5") BOTTOM B1-010-001-CSFC-C02-CV Nuclide Energy Yield(3/4) Activity Nuclide MDA LlneMDA Name (pCVgrams) (pCilgrams) (pCVgrams) (keV) EU-152 1408 . 08 20 . 75 - 2 . 02E+OO 8 . 02E-01 2 . 56E+OO
+ EU - 154 123 . 07 40 . 40 2 . 0lE- 01 5 . 66E-01/ 5 . 66E- 01 723 . 30 19 . 70 6 . 76E- 01 2.31E+OO 1274 . 51 34 . 40 - 4 . 09E- 01 l . 56E+OO
+ EU - 155 86 . 54 32 . 80 2 . 77E - 02 7 . 96E - 01 7 . 96E-01 105 . 31 21. 80 - 4 . 67E-02 9 . 89E-01
+ BI - 214 609 . 31 46 . 30 - l . 38E - 02 9 . 47E - 01 9 . 47E - 01 1120 . 29 15 . 10 2 . 45E+OO 4 . 04E+OO 1238 . 11 5 . 94 -2 . 18E+OO l . OOE+Ol 1377 . 67 4 . 11 -6 . 73E+OO 9 . 14E+OO 1407 . 98 2 . 48 -l . 69E+Ol 2 . 14E+Ol 1509 . 19 2 . 19 - 2 . 85E - 01 l . 87E+Ol 1764.49 15 . 80 7 . 85E - 01 3 . 63E+OO
+ PB- 214 77 . 11 10 . 70 1. 55E+OO 9 . 8 6E- 01 3 . 07E+OO 295 . 21 19 . 20 7 . 75E - 01 1 . 53E+OO 351 . 92 37 . 20 5 . 19E- 01 9 . 86E- 01
+ PA- 228 89 . 95 22 . 00 7 . 70E - 01 6 . 91E-01 1 . 22E+OO 93 . 35 35 . 00 - 3 . 19E- 01 6 . 91E - 01 105 . 00 16 . 30 -1. 22£- 01 1 . 40E +OO 129 . 22 2 . 97 5 . 20E+OO 8 . 0lE+OO 338 . 32 5 . 30 2 . 69E+OO 6 . 5 4 E+OO 463.00 13 . 80 2 . 20E - 01 2 . 39E+OO 911 . 23 16 . 70 2 . 07E+ OO 3 . 20E+OO
+ AM- 241 59 . 54 36 . 30 - 2 . 97E -0 1 1. 27E+00 1. 27E+OO
+ CM- 243 103 . 76 23 . 00 -4 . 52E -0 1 9 . 25E- 01 9 . 25E - 01 228 . 18 10 . 60 - 7 . 51E - Ol 2 . 21E+OO 277 . 60 14 . 00 5 . 33E - Ol 1 . 93E+OO
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction 7 = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 23
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 ::S:53:19PM Page 1 of6
~pex-Gamma Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C03-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 (O" - 0.5") TOP Sample Description : B1-010-001-CSFC-C03-CV Sample Type : Planchet Unit Sample Point Sample Size 1.320E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 1:30:00PM Acquisition Started : 3/21/2019 3:38:03PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds Real Time : 902.9 seconds Dead Time : 0.32 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100- 4096 Peak Area Range (in channels) : 100- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 5940 PEAK ANALYSIS REPORT Peak Analysis Performed on : 3/21/2019 3:53:10PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 24
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:53:19PM Page 2 of 6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C03-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 66 4 74 - 485 477 . 79 3 . 83E+Ol 18 . 15 l . 09E+02 1. 87 F 2 911 . 16 1817 - 1827 1822 . 57 1 . 61E+Ol 8 . 77 5 . SOE+OO 1. 86 F 3 14 61. 68 2918 - 2930 2923 . 47 4 . 95E+Ol 15 . 13 1. 20E+Ol 2 . 22 M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I 8KG. SUBTRACT Peak Analysis Performed on : 3/21/2019 3:53:10PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 238 . 66 3 . 83E+Ol 18 . 15 3 . 83E+Ol 1 . 82E+Ol F 2 911 . 16 l . 61E+Ol 8 . 77 l . 61E+Ol 8 . 77E+OO F 3 14 61. 68 4 . 95E+Ol 15 . 13 4 . 9SE+Ol l . SlE+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Oairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 25
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:53:19PM Page 3 of 6 Analysis Report for B1-010-001 (O"
- 0.5") TOP B1-010-001-CSFC-C03-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCi/grams) Uncertainty K- 40 0 . 871 1460 . 75
- 10 . 67 1 . 41E+0l 4 . 36E+00 PB - 212 0 . 527 77 . 11 17 . 50 238 . 63
- 44 . 60 4. 26£ - 01 2 . 03E- 01
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21/2019 3:53:10PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak Size (CPS) Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Uncertainty Type Nuclide F 2 911.16 1 . 792 4 3£-02 27 . 17 Tol. AC - 228 PA- 228 M = First peak In a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT 10/26/2020 Page 26
LAC LTP - Final Status Survey Package - 3/26/2019 312112019 3:53:19PM Page 4 of6 Analysis Report for B1-010-001 (O" - 0.5") TOP 81-010-001-CSFC-C03-CV Nuclide Nuclide Wt mean Wtmean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K- 40 0 . 871 1.41E+Ol 4. 36E+OO PB - 212 0 . 527 4 . 26E -0 1 2 . 03E- 01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 27
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 3:53:19PM Page 5 of 6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C03-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21 /2019 3:53:10PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 911.16 1. 79243E-02 27 . 17 AC- 228 PA- 228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA LineMDA Name (pCl/grams) (pCl/grams) (pCl/grams) (keV}
+ K- 40 1460 . 75
- 10 . 67 1. 4 lE+0l 4 .44 E+0O 4 . 44E+O0
+ AR- 41 1293 . 64 99 . 16 l . 05E - 01 9 . 62E - 01 9 . 62E - 01
+ CO - 60 1173 . 22 100 . 00 - 2 . 16£- 01 5 . 09E - 01 / 5 . 09E- 01 1332 . 49 100 . 00 - 9 . 42£ - 02 5 . 22£- 01
+ KR- 85 513 . 99 0 . 43 7 . 66E+0l 9 . 05E+0l 9 . 05E+0l
+ Y- 88 898 . 04 93 . 70 5 . 76E - 02 2 . 78E - 01 4 . 75E-0l 1836 . 06 99 . 20 - 1 . 0 4E- 01 2 . 78E - 01
+ I-131 284 . 30 6 . 06 -3 . 80E - 01 3 . 75E - 01 4 . 56E+00 364.48 81. 20 -3 . 71E-02 3 . 75E-01 636 . 97 7 . 27 -1 . 0lE+00 5 . 07E+00
+ CS-134 604 . 70 97 . 60 2 . SlE - 01 4 . 19E- Ol 4 . 27E-01 795 . 84 85 . 40 -2 . 95E-02 4 . 19E-01
+ CS-137 661 . 65 85 . 12 5 . 02£ - 02 4 . 7 4£ - 01 4 . 74£ - 01
+ CE - 144 80 . 12 1. 36 l . 0lE+Ol l . 92E+00 2 . 30E+Ol 133 . 51 11.09 -4 . 34£-01 l . 92E+00 10/26/2020 Page 28
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 3:53:19PM Page 6 of6 Analysis Report for B1-010-001 co* -0.5") TOP B 1-010-001-CSFC-C03-CV Nuclide Energy Yield(%) Activity NuclldeMDA Line MDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV)
+ EU-152 121 . 78 28 . 43 l . 86E - 01 7 . 05E- 01 / 7 . 05E-01 344 . 28 26 . 60 - 3 . 85E- 01 1. 20E+00 1408 . 08 20 . 75 3 . 52E - 02 2 . 45E+00
+ EU- 154 123 . 07 40 . 40 - 7 . 05E - 02 4 . 98E- 01 / 4 . 98E-01 723 . 30 19 . 70 2.09E - 01 1 . 93E+00 1 27 4. 51 34 . 40 1. 93E - 02 l . 35E+00
+ EU - 155 86 . 54 32 . 80 l.48E - 01 8 . 25E- 01 8 . 25E - 01 105 . 31 21. 8 0 - l.59E-01 1 . 00E+O0
+ BI - 214 609 . 31 4 6 . 30 5 . 4 9E- 01 8 . 77E- 01 8 . 77E-0l 1120 . 29 15 . 10 l . SlE+00 3 . 32E+00 1238 . 11 5 . 94 - 3 . 59E+00 l . 05E+0l 1377 . 67 4 . 11 4 . 88E+00 l . 05E+0l 1407 . 98 2 . 48 2 . 95E - 01 2 . 0SE+0l 1509 . 19 2 . 19 -2 . 14E+0l 1 . 53E+0l 1764 . 49 15 . 80 l . 14E+00 2 . 99E+00
+ PB - 214 77 . 11 10 . 70 7 . 14E- 01 8 .4 8E- 01 3 . 00E+00 295 . 21 19 . 20 -2 . 31E-01 1 . 52E+00 351. 92 37 . 20 2 . 07E- 01 8 . 48E- 01
+ PA- 228 89 . 95 22 . 00 5 . 09E- 01 7 . 40E- 01 1 . 26E+ 00 93 . 35 35 . 00 2 . 15E- 01 7 . 40E- 01 105 . 00 16 . 30 - 2 . 41E - 01 1 . 44E+00 129 . 22 2 . 97 4 . 50E+00 7 . 69E+00 338 . 32 5 . 30 3 . 95E+00 6 . 57E+00 463 . 00 13 . 80 7 . 68E- 01 2 . 64E+00 911.23 16 . 70 2 . 37E+00 3 . 37E+00
+ AM- 241 59 .5 4 36 . 30 - 1 . 94E- 02 1. 27E+00 l . 27E+00
+ CM- 243 103 . 76 23 . 00 5 . 32E- 01 9 . 83E - 01 9 .8 3E- 01 228 . 18 10 . 60 -1 . 88E+00 2 . 17E +00 277 . 60 14 . 00 9 . 08E- 01 2 . 03E +00
+ = Nuclide identified during the nuclide Identification
* = Energy line found In the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 29
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 4:08:52PM Page I of 6 pex-Gamma Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B1-010-001-CSF~C03-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 (O" - 0.5") BOTTOM Sample Description : B1-010-001-CSF~C03-CV Sample Type : Planchet Unit Sample Point Sample Size 1.320E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21 /2019 1:30:00PM Acquisition Started : 3/21 /2019 3:53:35PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds Real Time : 902.8 seconds Dead lime : 0.31 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100
- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number
- 014 ~7:J:;/
PEAK ANALYSIS R7f/i!;ff:== Peak Analysis Performed on : 3/21/2019 4:08:43PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 30
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 4:08:52PM Page 2 of6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B 1-010-001-CSFC-C03-CV Peak Energy ROI ROI Peak. Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 59 473 - 485 477 . 66 4 . 58E+0l 17. 59 9 . 46E+0l 1. 58 F 2 1461 . 29 2916 - 2930 2922 . 70 4.24E+0l 13 . 69 3.31E+00 2 . 93 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCEPEAKIBKG.SUBTRACT Peak Analysis Performed on : 3/21/2019 4 :08:43PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak. Energy Original Orig. Area Ambient Back.gr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 238 . 59 4 . 58E+01 17 . 59 4 . 58E+0l 1 . 76E+0l F 2 1461.29 4 . 24E+0l 13 . 69 l . 43E+0l 3 . 77E+00 2 . 81E+0l 1 . 42E+0l M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES Nuclide Name Id Confidence Energy (k.eV) Yield(%) Activity Activity (pCi/grams) Uncertainty 10/26/2020 Page 31
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 4:08:52PM Page 3 of6 Analysis Report for 81-010-001 (O" - 0.5") BOTTOM B 1-010-001-CSFC-C03-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCVgrams) Uncertainty K- 40 0 . 954 1460 . 75
- 10 . 67 7 . 98E+OO 4 . 06E+OO PB - 212 0 . 527 77 . 11 17 . 50 238 . 63
- 44 . 60 5 . lOE - 01 1 . 97E- 01
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21/2019 4:08:43PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0 . 954 7 . 98E+OO 4 . 06E+OO PB-212 0 . 527 5 . lOE-01 1 . 97E - 01 10/26/2020 Page 32
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/<<v 19 4:08:52PM Page4 of 6 Analysis Report for 81-010-001 (O" - 0.5") BOTTOM B1-010-001-CSFC-C03-CV
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 33
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 4:08:52PM Page 5 of6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B1-010-001-CSFC-C03-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21 /2019 4:08:43PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Llbrary\HOTLABAIR.NLB Nuclide Energy Yield(%) Activity Nucl/de MDA LlneMDA Name (pCl/grams} (pCl/grams) (pCl/grams) {keV)
+ K- 40 1460 . 75
- 10 . 67 7 . 98E+ 00 5 . lBE+00 5 . 18E+00
+ AR- 41 1293 . 64 99 . 16 2 . 30E - 01 1 . 38E+00 1. 38E+00
+ CO- 60 1173 . 22 100 . 00 6 . 14E- 02 5 . 75E- 01 / 5 . 90E - 01 1332 .4 9 100 . 00 4. 16E- 01 5 . 75E- 01
+ KR- 85 513 . 99 0 .4 3 7 . 13E+0l 9 . 52E+0l 9 . 52E+0l
+ Y- 88 898 . 04 93 . 70 - 1 . 43E - 01 4 . 75E - 01 4 . 75E - 01 1836 . 06 99 . 20 -4. 42E- 01 4. 95E- 01
+ I - 131 284 . 30 6 . 06 - 7 . 69E - 01 3 . 29E - 01 4 . 19E+00 364 . 48 81. 20 1. 19E- 0l 3 . 29E- 01 636 . 97 7 . 27 - 9 . 94 E- 01 4 . 37E +00
+ CS- 1 3 4 6 0 4. 70 97 . 60 2 . 03 E- 01 4 . 59E- 01 4. 59E- 01 795 . 8 4 85 .4 0 -2. 54 E- 02 4 . 82E- 01
+ CS - 13 7 661 . 65 85 . 12 3 . S0E - 01 5 . 19E- 01 r 5 . 19E- 0l
+ CE - 144 80 . 12 1. 36 - l . 65E+00 l . 8 4E+00 2 . 17E+0l 133 . 51 11 . 09 - 5 . 61E - 01 1 . 84E +00
+ EU - 152 121 . 78 28 .4 3 2 . 62 E- 01 7 . 66E - 01 7 . 66E- 01 344 . 28 26 . 60 - 5 . 39E - 01 1 . 09E+00 1408 . 0 8 20 . 75 - 3 . 52E - 0 2 1 . 69 E+ 00 10/26/2020 Page 34
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 4:08:52PM Page 6 of6 Analysis Report for 81-010-001 (O" - 0.5") BOTTOM 81-010-001-CSF~C03-CV Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCi/grams) (pCi/grams) (pCi/grams) (keV)
+ EU-154 123.07 40 . 40 6 . 27E-02 5.37E-01 / 5 . 37E-Ol 723 . 30 19 . 70 5 . 02E-Ol l . 93E+OO 1274.51 34 . 40 -1. 85E-01 l . 56E+OO
+ EU-155 86 . 54 32.80 -l . 37E - 01 7.75E-01 7 . 75E - 01 105 . 31 21. 80 2 . 07E-01 l . 02E+OO
+ BI - 214 609 . 31 46 . 30 3 . 74E-01 9 . 74E-01 9 . 74E-01 1120 . 29 15 . 10 -l . 67E+OO 3 . 03E+OO 1238 . 11 5 . 94 - 4 . 57E+OO 7 . 26E+OO 1377 . 67 4 . 11 -7 . 78E+OO 7 . 50E+OO 1407 . 98 2 . 48 -2 . 95E- 01 l . 42E+01 1509 . 19 2 . 19 3 . 56E - 01 2 . 0lE+Ol 1764.49 15 . 80 - 2 . 18E+OO 2 . 99E+OO
+ PB-214 77 . 11 10 . 70 1.29E+OO 8 . 73E-01 2 . 91E+00 295 . 21 19 . 20 -2 . 93E- 01 l . 32E+OO 351. 92 37 . 20 6 . 67E- 01 8 . 73E-Ol
+ PA- 228 89 . 95 22 . 00 9 . 48E- 01 7 . 15E- 01 1 . 24E+OO 93 . 35 35 . 00 - 1 . 50E-01 7 . 15E-01 105 . 00 16 . 30 4 . 4 6E - 01 l . 48E+OO 129 . 22 2 . 97 4 . 47E+OO 8.00E+OO 338 . 32 5 . 30 1.73E- 01 5 . 72E+OO 463 . 00 13 . 80 3 . llE- 02 2 . 25E+OO 911.23 16 . 70 8 . 91E- 01 3 . 71E+OO
+ AM-241 59 . 54 36 . 30 5 . 52E- 01 1 . 27E+OO 1. 27E+OO
+ CM-243 103 . 76 23 . 00 3.lOE- 01 9 . 70E - 01 9 . 70E- 01 228 . 18 10 . 60 - 7 . 59E - 01 2 . 08E+OO 277 . 60 14 . 00 9 . 04E- 01 1 . 89E+OO
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 35
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 b.41 :48AM Page 1 of6
~pex-Gamma Analysis Report for B1-010-001 (0" - 0.5") TOP B 1-010-001-CSFC-C04-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 (O"
- 0.5") TOP Sample Description : B1-010-001-CSFC-C04-CV Sample Type : Planchel Unit Sample Point Sample Size 1.400E+02 grams Facility : Oairyland_NPP Sample Taken On : 3/21/2019 3:10:00PM Acquisition Started : 3/22/2019 6:26:31AM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on OET Live nme : 900.0 seconds Real Time : 903.4 seconds Dead Time : 0.38 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100- 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 5948 PEAK ANAL vSISRPORT Peak Analysis Performed on : 3/22/2019 6:41 :39AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 36
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 6:41 :48AM Page 2 of 6 Analysis Report for B1-010-001 (O" - 0.5") TOP B 1-010-001-CSFC-C04-CV Peale Energy ROI ROI Peale Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 23 8. 6 9 471 - 482 4 77 .8 6 3 . 96 E+Ol 1 7 . 89 l . 32E+02 1. 28 F 2 14 61. 12 2915 - 2928 2922 . 35 6 . 38E+Ol 16 . 08 O. OOE+OO 2 . 26 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I BKG. SUBTRACT Peak Analysis Performed on : 3/22/2019 6:41 :39AM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peale Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 23 8. 69 3. 9 6E+Ol 17 .8 9 3 . 9 6E+Ol 1 . 79E+Ol F 2 14 61.12 6. 3 8E+Ol 16 . 08 1 . 43E+Ol 3 .77 E+ OO 4 . 96E+Ol 1 . 65E+Ol M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCVgrams) Uncertainty 10/26/2020 Page 37
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 6:41 :48AM Page 3 of 6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C04-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCl/grams) Uncertainty K-4 0 0 . 978 14 60 . 75
- 10 .6 7 1. 33E+0l 4.4 8E+ 00 PB- 2 1 2 0 . 526 77 . 11 17 . 50 238 . 63
- 44 . 60 4. 15E- 01 1. 89E-01
* = Energy line found In the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 6:41 :39AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (ke VJ Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) K- 40 0 . 978 1. 33E+0l 4 . 48E+00 PB-2 1 2 0 . 526 4 . lSE - 01 1. 89E- 01 10/26/2020 Page 38
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 6:41 :48AM Page 4 of6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C04-CV
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used In Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 39
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 6:41 :48AM Page S of 6 Analysis Report for 81-010-001 (0" - 0.5") TOP 81-010-001-CSFC-C04-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3122/2019 6:41 :39AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M= First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nucllde Energy Yield(%) Activity Nucl/deMDA LlneMDA Name (pCl/grams) (pCl/grams) (pCUgrams) (keV)
+ K- 40 1460 . 75
- 10 . 67 l . 33E+0l 4 . 44E+00 4.4 4E+OO
+ AR-41 1293 . 64 99 . 16 1. 33E 02 l . 83E+02 1 . 83E+02
+ CO- 60 1173 . 22 100 . 00 2 . 67 E- 01 4 . 15E- 01 J 5 . 57E-Ol 1332 . 49 100 . 00 - 2 . 02E - 01 4 . 15E- 01
+ KR- 85 513 . 99 0 . 43 8 . 86E+0l 8 . 83E+0l 8 . 83E+Ol
+ Y-88 898 . 04 93 . 7 0 - l . 09E - 02 3 . 32E- 01 4 . 69E-01 1836 . 06 99 . 20 - 4 . 28E-0l 3 .3 2E - 01
+ I - 131 284 . 30 6 . 06 - 3 . 85E - 01 3 . 34E- 01 4 . 36E+O0 364 . 48 81.20 1. 86E-03 3 . 34E-Ol 636 . 97 7 . 27 1.48E-01 4 . 50E+00
+ CS - 134 604 . 7 0 97 . 60 2 . l0E- 01 3 . 99E- 01 3 . 99E-01 795 . 84 85 . 40 -3 . 69E- 01 4 . 36E- 01
+ CS - 137 661 . 65 85 . 12 l . 71E- 01 4 . 47E- 01 ./ 4 . 47E- 01
+ CE - 144 80 . 12 1.36 - 1 . 52E+0l l . 83E+OO 1. 86E+0l 133 . 51 11.09 -5 . 98E - 0l 1. 83E+00
+ EU- 152 121 . 78 28 . 43 - 1 . 5 2E- 0l 7 . 21 E- Ol ,/ 7 . 21E - 01 344 . 28 26 . 60 - 2 . 09E+00 l . 06E+O0 1 408 . 08 20 . 75 2 . 72E-0 l l . 74E+ 00 10/26/2020 Page 40
LAC LTP - Final Status Survey Package - 3/26/2019 3122/2019 6:4 1:48AM Page 6 of6 Analysis Report for B1-010-001 (O" - 0.5") TOP B 1-01 0-001-CSFC-C04-CV Nucllde Energy Yield{%) Activity NuclldeMDA LlneMDA Name (pCi/grams} {pCilgrams} (pCilgrams} (keV}
+ EU-154 123 . 07 40 . 40 -8 . 25E-02 5 . 08E-01 ( 5 . 08E- 01 723. 30 19 . 70 l . 19E+OO 2.26E+OO 1274 . 51 34 . 40 -4 . 95E-Ol 1 . 09E+OO
+ EU-155 86 . 54 32 . 80 3 . 82E-01 7 . 41E- 01 7 . 41E-01 105 . 31 21. 80 -5 . 67E-01 8.85E- 01
+ BI-214 609 . 31 46 . 30 3 . 85E- 01 8.56E-01 8.56E-01 1120 . 29 15 . 10 2 . 55E+OO 3 . 60E+OO 1238 . 11 5 . 94 -6 . 35E+OO 8 . 26E+OO 1377 . 67 4 . 11 2 . 57E+OO 1 . 04E+Ol 1407 . 98 2 . 48 2 . 28E+OO l.46E+Ol 1509 . 19 2 . 19 9 . 41E+OO 2 . 02E+Ol 1764 . 49 15 . 80 1. 29E+OO 3.04E+OO
+ PB-214 77 . 11 10 . 70 1 . 32E+OO 8 . 87E-01 2 . 59E+OO 295 . 21 19 . 20 7 . 00E- 01 l . 44E+OO 351. 92 37 . 20 4 . 34E- 01 8 . 87E-01
+ PA-228 89 . 95 22 . 00 4 . 91E - 01 1 . 06E+OO l . 75E+OO 93.35 35 . 00 3 . 70E - Ol 1 . 06E+OO 105 . 00 16 . 30 - l . 60E+OO 1 . 93E+OO 129 . 22 2 . 97 5 . 64E+OO 1 . 16E+Ol 338 . 32 5 . 30 2 . 09E+OO 8 . 70E+OO 463 . 00 13 . 80 -3 . 20E- 01 3 . 0lE+OO 911 . 23 16 . 70 1 . llE+OO 4 . 49E+OO
+ AM-241 59 . 54 36 . 30 2 . 60E - 01 l . 20E+OO l . 20E+OO
+ CM- 243 103 . 76 23 . 00 -9 . 12E- 02 8 . 64E- Ol 8 . 64E - 01 228 . 18 10 . 60 -3 . 19E- 01 l . 91E+OO 277 . 60 14 . 00 4 . 40E- 02 1 . 78£ +00
+
. = Nuclide identified during the nuclide Identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perfonn the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 41
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 o:05:41PM Page I of6
~pex-Gamma Analysis Report for 81-010-001 (0" - 0.5") TOP 81-010-001-CSFC-C0S-CV GAMMA SPECTRUM ANALYSIS Sample Identification : 81 -010-001 (0" - 0.5") TOP Sample Description : 81-010-001-CSFC-C0S-CV Sample Type : Planchet Unit Sample Point Sample Size 1.188E +02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 1:20:00PM Acquisition Started : 3/21/2019 4:45:22PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live T1me : 1200.0 seconds Real T1me : 1203.8 seconds Dead T1me : 0.32 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 1,a,2014 77 _ / Efficiency Calibration Description : /C-::JJ:lvµ,t,,.J lll Sample Number o~Jz.h PE: ANALYSfii/i!!fi= Peak Analysis Perfonned on : 3/21 /2019 5:05:32PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 1
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/:!u19 5:05:41PM Page 2 of6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C05-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. {keV) start end Centroid Area Uncertainty Counts (keV) F 1 77 . 36 152 - 158 155 . 26 2 . 60E+01 18 . 48 l . 53E+02 1.06 F 2 238 . 72 474 - 481 477 . 91 5 . 85E+01 19 . 51 8.46E+Ol 1. 21 F 3 14 61. 08 2916 - 2929 2922 . 28 7 . llE+Ol 17 . 82 l . 40E+01 2 . 41 M = First peak in a multiplet reg ion m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I 8KG. SUBTRACT Peak Analysis Performed on : 3/21/2019 5:05:32PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 77 . 36 2 . 60E+Ol 18 . 48 2 . 60E+Ol 1 . 85E+Ol F 2 238 . 72 5 . 85E+Ol 19 . 51 5 . 85E+Ol 1 . 95E+Ol F 3 1461.08 7 . llE+Ol 17 . 82 1 . 90E+Ol 5 . 03E+OO 5 . 21E+Ol l . 85E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 2
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 5:05:41 PM Page 3 of 6 Analysis Report for B1-010-001 (0" - 0.5") TOP B1-010-001-CSFC-C0S-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCi/grams) Uncertainty K-40 0 . 982 14 60 . 7 5
- 10.67 1.23E+Ol 4 . 43E+OO PB-212 0 . 996 77 . 11
- 17 . 50 5.35E-01 3 . 82E- 01 238 . 63
- 44.60 5 . 43E-01 1 . 83E- Ol
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/2112019 5:05:32PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (ke VJ Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0 . 982 1. 23E+Ol 4 .4 3E+OO PB-212 0 . 996 5 .41E-01 1 .65£-0 1 10/26/2020 Page 3
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/:.w19 5:05:41PM Page 4 of6 Analysis Report for B1-010-001 (0"
- 0.5") TOP 81-010-001-CSFC-C0S-CV
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 4
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 5:05:41PM Page 5 of6 Analysis Report for B1 -010-001 (0" - 0.5") TOP B1-010-001-CSFC-C0S-CV UNIDENTIFIED PEAKS Peak Locate Perfonned on : 3/21/2019 5:05:32PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak In a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield(%) Activity Nuc/ideMDA LineMDA Name (pCUgrams) (pCllgrams) (pCllgrams) (keV)
+ K- 40 1460.75
- 10 . 67 1. 23E+0l 5 . 84E+00 5 . 84E+00
+ AR-41 1293 . 64 99 . 16 7 . 21E- 0l 1 . 89E+00 1 . 89E+00
+ CO-60 1173 . 22 100 . 00 8 . 22E-02 4 . 03E-01 / 5 . 86E - 01 1332 . 49 100 . 00 1 . 27E-01 4 . 03E-01
+ KR-85 513 . 99 0.43 1 . 02E+0l 8 . 66E+0l 8 . 66E+0l
+ Y-8 8 898 . 04 93 . 70 8 . 00E-02 8 . SlE-02 4.82E-01 1836 . 06 99 . 20 0 . 00E+00 8 . 51E - 02
+ I - 131 284 . 30 6.06 - 8.70E- 01 3 . 29E - 01 3 . 90E+00 364 . 48 81. 20 -6.0SE-02 3 . 29E-01 636. 97 7.27 3 . 20E+00 4.57E+00
+ CS-134 604 . 70 97 . 60 2 . 19E-01 3 . 85E-01 4 . 07E-0l 795 . 84 85 .4 0 4 . 09E-02 3.85E-0l
+ CS-137 661. 65 85 . 12 1. 72E-01 4 . 48E-01/" 4.48E- 01
+ CE-144 80 . 12 1. 36 -1.33E+00 l . 85E+00 l . 96E+0l 133 . 51 11 . 09 - 1 . 30E- 01 1.85E+00
+ EU-152 121 . 78 28 .4 3 l .57E-0l 6 . 33E-01 / 6.33E-01 344 . 28 26 . 60 - 2 . 41E+00 l . l0E+00 1408.08 20 . 75 -4.57E-01 2 . 21E+00 10/26/2020 Page 5
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 5:05:41PM Page 6 of6 Analysis Report for B1 -010-001 (0" - 0.5") TOP B1 -010-001-CSFC-C0S-CV Nuclide Energy Yleld{3/4) Activity Nuc/ideMDA LlneMDA Name (pCl/grams) (pCl/grams) (pCilgrams) (keV)
+ EU - 154 123.07 40 . 40 - l . 72E-01 4. 39£- 01 / 4 . 39£ - 01 723 . 30 19 . 70 l . 29E+00 l.95E+00 1274 . 51 34 . 40 2 . 68£- 01 1 . 26£+00
+ EU -1 55 86 . 54 32 . 80 - 8 . 26E- 02 7 . 09E- 01 7 . 09E-01 105.31 21. 80 - 3.91E-02 8 . 81E- 01
+ BI-214 609 . 31 46 . 30 1. 35£-01 8 . 34E- 01 8 . 34E-01 1120 . 29 15 . 10 6 . 03E-01 3 . 37E+00 1238 . 11 5 . 94 6 . 41£+00 9 . 59E+00 1377 . 67 4 . 11 - 4 . 07E+00 9 . 21E+00 1407 . 98 2 . 48 - 3 . 83E+00 1. 85E+0l 1509 . 19 2 . 19 - 8 . 91E+00 1 . 68E+0l 1764 . 49 15 . 80 - 4 . 28E- 01 3 . 02E+00
+ PB- 214 77 . 11 10 . 70 l . 58E+00 8 . 57E- 01 2 . 66E+00 295 . 21 19 . 20 1 . 72E+00 1 . 40E+00 351 . 92 37 . 20 9 . 48E- 01 8.57E - 01
+ PA- 228 89 . 95 22 . 00 -1. 83E - 01 7 . 29E- 01 1 . 17E+00 93 . 35 35.00 3 . llE - 01 7 . 29E- 01 105 . 00 16 . 30 - 6 . 08E- 01 l . 33E+00 129 . 22 2 . 97 -9 . 59E+00 7 . 03E+00 338 . 32 5 . 30 3 . 56E+00 6 . 00E+00 463 . 00 13 . 80 -6 . 77E - 01 2 . 42E+00 911.23 16 . 70 1 . 98E+00 2 . 98E+00
+ AM- 241 59 . 54 36 . 30 - 1. 4 7E-02 1 . 19E+00 1 . 19E+00
+ CM- 243 103 . 76 23 . 00 - 4 . 59E- 01 8 . 53£- 01 8 . 53E - 01 228 . 18 10 . 60 - 1 . 31£ - 01 2 . 02E+00 277 . 60 14 . 00 -7 . 39£ - 01 1 . 73 E+00
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 6
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 4:45:05PM Page I of 6 pex-Gamma Analysis Report for B1-010-001 (0" - 0.5") BOTTOM B1-010-001-CSFC-C05-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 (0" - 0.5") BOTTOM Sample Description : B1-010-001-CSFC-C05-CV Sample Type : Planchet Unit Sample Point Sample Size 1.188E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 1 :20:32PM Acquisition Started : 3/21/2019 4:24:47PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live nme : 1200.0 seconds Real Time : 1203.6 seconds Dead nme : 0.30% Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Callbratlon Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 5943 PEAK ANALYSJS REPORT Peak Analysis Performed on : 3/21/2019 4:44:56PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 7
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/W19 4:45:0SPM Page 2 of6 Analysis Report for B1-010-001 (0" - 0.5") BOTTOM B1-010-001-CSFC-C0S-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 54 472 - 48 1 477 . 56 4 . 21E+Ol 19 . 26 l . 10E+02 1. 57 F 2 609 . 14 1214 - 1223 1218 . 62 2 . 65E +Ol 12 . 13 2 . 13E+Ol 1. 62 F 3 14 61.28 2915 - 29 2 9 2922 . 67 6 .4 5E+Ol 16 . 97 3 . 66E+OO 2 . 74 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I BKG. SUBTRACT Peak Analysis Performed on : 3/21/2019 4:44:56PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 23 8. 5 4 4. 21E+Ol 19 . 2 6 4 . 21E+Ol 1 . 93E+Ol F 2 60 9. 1 4 2 . 65E+Ol 1 2 . 13 1. 29E+Ol 7. 6 9E+OO l . 3 6E+Ol 1 .4 4E+Ol F 3 1461.2 8 6 .4 5E+Ol 16 . 97 l .9 0E+Ol 5 . 03E+OO 4. 55E+Ol 1. 77E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 8
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 4:45:05PM Page 3 of6 Analysis Report for 81-010-001 (0" - 0.5") BOTTOM B1-010-001-CSFC-COS-CV Nuclide Name Id Confidence Energy (keV) Yield(3/4) Activity Activity (pCilgrams) Uncertainty K- 40 0 . 957 1460 . 75
- 10 . 67 l . 08E+Ol 4 . 23E+OO PB - 212 0 . 526 77 . 11 17 . 50 238 . 63
- 44 . 60 3 . 90E-Ol 1. 80E- 01 BI - 214 0 . 362 609 . 31
- 46 . 30 3 . 13E- Ol 3 . 31E-01 1120 . 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2. 48 1509 . 19 2 . 19 1764 . 49 15 . 80
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21 /2019 4:44:56PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet reg ion m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT 10/26/2020 Page 9
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 4:45:0SPM Page 4 of6 Analysis Report for B1-010-001 co* -0.5") BOTTOM 81-010-001-CSFC-COS-CV Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0 . 957 1 . 08E+Ol 4 . 23E+OO PB- 212 0 . 526 3 . 90E - 01 l . 80E-01 BI-214 0 . 362 3 . 13E-01 3 . 31E - 01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 10
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 4:qo:0SPM Page 5 of 6 Analysis Report for B1-010-001 (0"
- 0.5") BOTTOM B 1-010-001-CSFC-COS-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21/2019 4:44:56PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified.
M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Oairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield(3/4) Activity Nuclide MDA LineMDA Name (pCUgrams) (pCUgrams) (pCUgrams) (keV)
+ K- 40 1 4 60 . 75
- 10 . 67 1. 08E+ 0l 4. 9 4E+ 00 4. 9 4E+00
+ AR- 41 12 93 . 64 99 . 16 9 . 33E- 0 1 1 . 7 4E+00 1. 74E+00 CO - 60 1173 . 22 100 . 00 - 1. l0E-0 1 4. 59E - 01 .,,/ 4 . 59E- 0 1 1332 .4 9 1 00. 0 0 -6.41 E- 02 5 . 67E- 0 l
+ KR-85 513 . 99 0.4 3 - 5 . 8 5E+ 00 8. 06 E+0l 8.0 6E+0 l
+ Y-8 8 8 98 . 0 4 93 . 70 3 . lSE-0 1 3.39E - 01 4. 21 E-0 1 1836 . 06 99 . 20 - 1 .4 7E-01 3 .3 9E -0 1
+ I - 131 284 . 30 6 . 06 2. 82E+00 3 . 00E-01 4. 21E +00 364 . 48 81.20 - 2 . 18E- 0l 3 . 00E - 01 636 . 97 7 . 27 1 . 64E+ 0 0 4 . 44E+00
+ CS - 134 604 . 70 97 . 60 l . 87E - 01 4.2 9E - 01 4. 29E - 01 795 . 84 85 . 40 - 5 . 41E- 02 4 . 40E - 0l
+ CS - 137 661 . 65 85 . 12 3 . 32E - 0l 5 . 44 E- 01 ~ S .44 E- 01
+ CE - 144 80 . 12 1.36 - 9 . 48E+00 l . 71E+00 l . 8 4E+Ol 133 . 51 11.09 - 6 . 68E - 0l 1. 71 E+00
+ EU - 152 121 . 78 28 . 43 - 9.68E- 02 6 . 64E- 0l / 6 . 64E- 01 344 . 28 26 . 60 - 2 . 81 E+00 l. 03E +00 14 0 8 . 08 20 . 75 l . 76E+00 2 .4 3E+00 10/26/2020 Page 11
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /~u19 4:45:0SPM Page 6 of6 Analysis Report for B1 -010-0 01 (0" - 0.5") BOTTOM B 1-010-001-CSFC-COS-CV Nucl/de Energy Yield(%) Activity NuclldeMDA LineMDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV)
+ EU-154 123 . 07 40 . 40 - 9 . 27E-02 4 . 69E-0l / 4 . 69E-01 723 . 30 19 . 70 1 . 53E+00 2 . 0SE+00 1274 . 51 34 . 40 5 . 28E-01 1.26E+00
+ EU-155 86 . 54 32 . 80 -5 . 93E-02 7 . 21E-01 7 . 21E - 01 105 . 31 21. 80 1 . 54E-01 8 . 42E - 01
+ BI-214 609 . 31
- 4 6 . 30 3 . 13E-01 6 . llE-01 6 . llE-01 1120. 29 15 . 10 8 . 80E-0l 3 . 48E+00 1238 . 11 5 . 94 6 . 24E+00 9 . 76E+00 1377 . 67 4 . 11 3 . 63E+00 l . 24E+0l 1407 . 98 2 . 48 1 . 47E+0l 2 . 04E+0l 1509 . 19 2 . 19 4 . 79E+00 l . 88E+0l 1764 . 49 15 . 80 9 . 51E-01 2 . 49E+00
+ PB-214 77 . 11 10 . 70 8.66E-02 8.06E - 01 2 . 50E+00 295.21 19.20 1 . 19E+00 l . 46E+00 351 . 92 37 . 20 2 . 48E-01 8 . 06E-0l
+ PA-228 89 . 95 22 . 00 1 . 22E+00 6 . 98E-0l 1 . 20E+00 93 . 35 35 . 00 2 . 51E-01 6 . 98E-01 105 . 00 16 . 30 l . 65E-0l 1. 25E+00 129 . 22 2 . 97 1 . 74E+00 7 . llE+00 338 . 32 5 . 30 2 . 21E+00 5 . 91E+O0 463 . 00 13 . 80 -1. 09E+00 2 . 33E+00 911. 23 16 . 70 2 . 54E+00 2 . 70E+00
+ AM-241 59 . 54 36.30 6 . 46E - 01 1.29E+00 1.29E+00
+ CM-243 103.76 23 . 00 1. 3 4E-02 8 . 00E-01 8 . 00E - 01 228.18 10 . 60 4 . 54E - 01 2 . 14E+00 277 . 60 14.00 - 1 . 21E+00 1 . 71E+O0
+ = Nuclide Identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 12
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2::.!:.!:49PM Page I of6 J\pex-Gamma Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C06-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1 -010-001 (O" - 0.5") TOP Sample Description : B1-010-001-CSFC-C06-CV Sample Type : Planchet Unit Sample Point Sample Size 1.286E+02 grams Facility : Da!ryland_NPP Sample Taken On : 3/21/2019 1:07:00PM Acquisition Started : 3/21/2019 2:07:34PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live nme : 900.0 seconds Real nme : 902.9 seconds Dead nme : 0.32 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100
- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number PEAK ANALYSIS RPORT Peak Analysis Performed on : 3/21/2019 2:22:40PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 1
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/£019 2:22:49PM Page2 of6 Analysis Report for 81-010-001 (O" - 0.5") TOP 81-010-001-CSFC-C06-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 295 . 20 587 - 597 590 . 86 5.42E+Ol 17 . 45 7 . 42E+Ol 1.18 F 2 352 . 03 699 - 711 704 . 48 8 . 04E+Ol 19.92 4 . 72E+Ol 1. 62 F 3 609 . 54 1214 - 1224 1219.41 5 . 37E+Ol 16.17 2 . SOE+Ol 1. 64 F 4 1460 . 87 2915 - 2928 2921 . 85 4 . 03E+Ol 13.12 3.45E+OO 1. 94 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCEPEAKIBKG.SUBTRACT Peak Analysis Performed on : 3/21 /2019 2:22:40PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Co"ected Co"ected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 295 . 20 5 . 42E+Ol 17 . 45 1 . 30E+Ol 7.19E+OO 4.12E+Ol 1 . 89E+Ol F 2 352 . 03 8 . 04E+Ol 19 .92 1 . 91E+Ol 7.75E+OO 6.13E+Ol 2 . 14E+Ol F 3 609 . 54 S . 37E+Ol 16 . 17 9.69E+OO 5 . 77E+OO 4.40E+Ol 1 . 72E+Ol F 4 1460 . 87 4.03E+Ol 13 . 12 1. 43E+Ol 3 . 77E+OO 2 . 60E+Ol 1 . 37E+O l M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000slgma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 2
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:2:.!:49PM Page 3 of 6 Analysis Report for B1-010-001 (O"
- 0.5") TOP B1-010-001-CSFC-C06-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCl/grams) Uncertainty K-40 0 . 998 1460 . 75
- 10 . 67 7 . 58E+O O 4 . 00E+OO BI - 214 0.360 609 . 31
- 46 . 30 1. 25E+OO 4 . 92E- Ol 1120 . 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2 . 48 1509 . 19 2 . 19 1764 .4 9 15 . 80 PB - 214 0 . 692 77 . 11 10 . 70 295.21
- 19 . 20 1 . 34E+OO 6 . 16E- 01 351 . 92
- 37 . 20 l . 22E+O O 4 . 31E - 01
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21/2019 2:22:40PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide All peaks were identified . M = First peak in a multiplet reg ion m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT 10/26/2020 Page 3
LAC LTP - Final Status Survey Package - 3/26/2019 3/211:.!019 2:22:49PM Page4 of6 Analysis Report for 81-010-001 (0" - 0.5") TOP B1-010-001-CSFC-C06-CV Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0 . 998 7 . SBE+OO 4.0 0E+OO BI - 214 0 . 360 1. 25E +OO 4 . 92E-01 PB- 214 0 . 692 1. 26E +OO 3 . 53E-01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 4
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:2.:::49PM Page S of6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C06-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21 /2019 2:22:40PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nudide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA L.ineMDA Name (pCVgrams) (pCVgrams) (pCVgrams) (keV)
+ K- 40 1 4 60 . 75
- 10 . 67 7 . 5 8E+00 5 . 3 4E+00 5 . 3 4E+00
+ AR- 41 1293 . 64 99 .1 6 - 3 . 93 E- 01 8 . 64E-01 8 . 64E - 01
+ CO- 60 1173 . 22 100 . 00 - 1. 41E- 01 4 . 96E-01 5 . 66E- 01 1332 . 49 100 . 00 -1. 32E - 01 4 . 96E - 01
+ KR- 85 513 . 99 0 . 43 4 . 51E+0l 8 . 60E+0l 8 . 60E +0l
+ Y- 88 898 . 04 93 . 70 2 . 95E - 0l 3 . 60E - 01 5 . 19E-0l 1836 . 06 9 9 . 20 - 3 . 8 7E- 02 3 . 60E - 01
+ I - 131 284.30 6 . 06 3 . 6 9E- 01 3 . 75E - 01 4 . 59E+00 364 . 48 81. 2 0 7 . 50E - 02 3 . 75E-01 636 . 97 7 . 27 4 . 52E+00 5 . 18E +00
+ CS - 134 604 . 70 97 . 60 -2. 84E- 01 4 . 74E - 01 5 . 88E-01 795 . 8 4 85 . 40 - 2 . 02E- 01 4 . 74E- 01
+ CS - 137 66 1. 65 85 .1 2 2 . 65E- 01 6 . 55E - 01 6 . 55E- 0 1
+ CE- 144 80 . 12 1. 36 - 2 . 58E+00 2 . 02E+00 2 . 37E+0l 133 . 51 11.09 1. 4 4E- 01 2 . 02E+00
+ EU - 152 121.78 28 .4 3 6 . 27E - 0 1 8 . 2 6E- 01 J 8. 2 6E- 01 344 . 28 26 . 60 3 . 64E- 02 l . 27E +00 1 4 08 . 0 8 20 . 75 3 . 25E- 0l 2 . 72E +00 10/26/2020 Page 5
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:22:49PM Page 6 of6 Analysis Report for B1-010-001 (O" - 0.5") TOP B 1-010-001-CSFC-C06-CV Nucllde Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCl/grams} (pCl/grams} (pCl/grams) (keV)
+ EU - 154 123 . 07 40.40 1 . 47E-0l 5 . 78E-0l / 5 . 78E- 01 723 . 30 19 . 70 1. 37E+00 2 . 34E+00 1274 . 51 34 . 40 - 3 . 51E- 01 1 . 32E+00
+ EU - 155 86 . 54 32 . 80 4 . 54E-01 8 . 20£- 01 8 . 20£-01 105 . 3 1 21. 80 - 3 . 79E- 01 l . 03E+00
+ BI-214 609 . 31
- 46 . 30 1. 25E+00 7 . 24 £ -01 7 . 24E- 0l 1120 . 29 15 . 10 3 . 04E+00 4. 00E+00 1238 . 11 5 . 94 2 . 73E+00 l . 28E+0l 1377 . 67 4 . 11 8 . 58E+00 1. 35E+0l 1407 . 98 2 . 48 2 . 72E+00 2 . 28E+0l 1509 . 19 2 . 19 4 . 43E+00 2 . 32E+0l 1764 . 49 15 . 80 7 . 94E - 01 3 . 91E+00
+ PB - 21 4 77 . 11 10 . 70 l.41E+00 6 . 99E - 01 3 . 18E+00 295 . 21
- 19 . 20 1 . 34E+ 00 l . 26E+00 351. 92
- 37 . 20 1 . 22E+00 6 . 99£- 01
+ PA - 228 89 . 95 22 . 00 5 . 69E - 02 7 . 1 4£ - 01 l . 21E+00 93 . 35 35 . 00 -2 . 39£-01 7 .1 4£ - 01 105 . 00 16 . 30 3 . 37E - 01 l . 45E +00 129 . 22 2 . 97 - 2 . 45E +00 7 . 88E+00 338 . 32 5 . 30 5 . 30E+00 6 . 37E+00 4 63 . 00 13 . 80 l . 52E+00 2 . 74E+00 911 . 23 16 . 70 l . 06E+00 3 . 17E+00
+ AM- 241 59 . 54 36 . 30 -5 . 77£- 02 1 . 3 4E+00 l . 3 4E+00
+ CM- 243 103 . 76 23 . 00 1 . 63E- 01 1. 0lE+00 l . 0lE +00 228 . 18 10 . 60 - 1 . 64£+00 2 . 23E+00 277 . 60 14 . 00 - 4 . 0SE - 01 l . 87E+00
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able lo perfonn the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 6
LAC LTP - Final Status Survey Package - 3/26/2019 3/2112019 3:u:i:58PM Page I of6 pex-Gamma Analysis Report for 81-010-001 (Ow - 0.5") TOP 81-010-001-CSFC-C0B-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 (Ow - 0.5") TOP Sample Description : 81-010-001-CSFC-C06-CV Sample Type : Planchet Unit Sample Point Sample Size 1.242E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 1:07:00PM Acquisition Started : 3/21/2019 2:45:41PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchel on OET Live Time : 1200.0 seconds Real Time : 1203.9 seconds Dead Time : 0.32 % Peak Locate Threshold : 3.00 Peak Locale Range (In channels) : 100 - 4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Callbratfon Used Done On : 7/8/2014 Efficiency Callbralion Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 5937 PEAK ANALYSIS REPORT Peak Analysis Performed on : 3/21/2019 3:05:49PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 7
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:05:58PM Page 2 of 6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CSFC-C06-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 352 . 14 698 - 712 704 . 72 7 . 13E+ 0 l 19 . 61 7 . 09E+0l 1. 84 F 2 609 . 33 1214 - 1225 1219 . 00 4 . 48E+0l 15 . 02 2 . 40E+0l 1. 86 F 3 677 . 24 1351 - 1358 1354 . 80 8 . 93E+00 8 . 01 1. 20E+0l 1. 48 F 4 14 61. 32 2915 - 2930 2922 . 76 6 . 86E+0 l 17 . 35 7 . 64E+00 2 . 75 M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I BKG. SUBTRACT Peak Analysis Performed on : 3/21/2019 3:05:49PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Oairyland_NPP\Oata\0000001363.CNF Corrected Area is: Original
- Peak Ratio
- Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F l 352 . 14 7 . 13E+0l 19 . 61 2 . 55E+0l 1 . 03E+0l 4 . 58E+0l 2 . 22E+0l F 2 609 . 33 4 . 48E+0l 15 . 02 l . 29E+0l 7 . 69E+00 3 . 19E+0l 1. 69E+0l F 3 677 . 24 8 . 93E+00 8 . 01 8 . 93E+00 8 . 0lE+00 F 4 1 4 61 . 32 6 . 86£+01 17 . 35 l . 90E+0l 5 . 03E+00 4 . 96E+0l 1 . 81E+0l M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairytand_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 8
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:0o:58PM Page 3 of6 Analysis Report for 81-010-001 (0" - 0.5") TOP B1-010-001-CSFC-C06-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCVgrams) Uncertainty K-4 0 0 . 949 1460 . 75
- 10 . 67 1 . 12E+Ol 4 . 13E+OO BI - 214 0 . 364 609.31
- 4 6. 30 7 . 0lE - 01 3.74E-01 1120 . 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1407 .98 2 . 48 1509 . 19 2 . 19 1764 . 49 15 .8 0
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locale Performed on : 3/21/2019 3:05:49PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide F 1 352 . 14 3 .8 1972£- 02 24.18 Tol. PB - 214 F 3 677 . 24 7.44137£-03 44 . 87 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT 10/26/2020 Page 9
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:05:58PM Page 4 of6 Analysis Report tor B1-010-001 (0" - 0.S-) TOP B 1-010-001-CSFC-C06-CV Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) K-40 0 . 949 l . 12E+Ol 4 . 13E+OO BI - 214 0 . 364 7 . 0lE - 01 3 . 74E- Ol
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used In Weighted Mean Activity Errors quoted at 2.0D0sigma 10/26/2020 Page 10
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 3:0!>:58PM Page 5 of6 Analysis Report for 81-010-001 (O" - 0.5") TOP B1 -010-001-CSFC-C06-CV UNIDENTIFIED PEAKS Peak Locate Performed on ; 3/21/2019 3:05:49PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nucl/de F 1 352 . 14 3 . 81972E- 02 24 . 18 Tol. PB- 214 F 3 677 . 24 7 . 44137E - 03 44 . 87 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Oairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA LlneMDA Name (pCilgrams) (pCl/grams) (pCl/grams) (keV)
+ K- 40 1460 . 75
- 10 . 67 l . 12E+0l 5 . 12E+0O 5 . 12E+00
+ AR-41 1 293 . 64 99 . 16 - 3 .4 8£ - 01 8 . 40E- 01 8 . 40E- 01
+ CO- 60 11 73 . 22 100 . 00 7 . 88E- 02 4 . 31E- 01 / 4 . B0E- 0 1 1332 . 49 100 . 00 1 . 77E - 01 4 . 31E-01
+ KR - 85 513 . 99 0 . 43 5 . 27E+0l 8 . 4 4E+0l 8 . 44E+0l
+ Y-88 898 . 04 93 . 70 3 . 44E- 02 3 . 2 4E- 01 4 . 80E-01 1836 . 06 99 . 20 9 . 02E-02 3 . 2 4E-01
+ I - 131 284 . 30 6 . 06 - 4 . 26E+00 3 . 09E- 01 3 . 67E+00 364 . 48 81. 20 l . 02E - 01 3 . 09E - 01 636 . 97 7 . 27 5 . 22E - 0l 4 . 04E+00
+ CS-134 604 . 70 97 . 60 -2 . 16E-01 4 . 06E-01 4 . 59E-01 795 . 84 85 . 40 -3 . 55E-01 4 . 06E - 01
+ CS-137 661 . 65 85 . 12 3 .4 0E - 01 5 . 16E- 01 5 . 16E- 01
+ CE-144 80 . 12 1. 36 - 5 . 94E- 01 l . 79E+00 l . 95E+0l 133 . 51 11 . 09 5 .4 2E-01 l . 79E+00 10/26/2020 Page 11
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 3:05:SBPM Page 6 of6 Analysis Report for 81-010-001 co* -O.S-) TOP B1-010-001-CSFC-C06-CV Nucllde Energy Yield(%) Activity NuclldeMDA LfneMDA Name (pCUgrams) (pCilgrams) (pCflgrams) (keV)
+ EU - 152 12 1. 78 28 . 43 2 . 38E- 03 6 . BOE-0 1 / 6 . SOE-01 34 4. 28 26 . 60 3 . 90E- 01 1. OOE+OO 1408 . 08 20 . 75 - 1 . 18E+OO l . 96E+OO
+ EU - 154 123 . 07 40 . 40 6 . 77E- 02 4 . 83E- 0 1 / 4 . 83E- Ol 723 . 30 19 . 70 3 . 71E- 01 1 . 98E+OO 1274 . 51 34 . 40 9 . 40E - 01 l . 60E+OO
+ EU- 155 86 . 54 32 . 80 - 1 . 98E-02 6 . 97E - 01 6 . 97E - 01 105 . 31 21. 8 0 3 . 03E- 02 8 . 98E- 01
+ BI - 214 609 . 31
- 46 . 30 7 . 0lE - 01 6 . 12E- 01 6 . 12E-01 1120 . 29 15 . 10 - 9 . 30E-02 3 . 33E+OO 1238 . 11 5 . 94 1 . 15E+Ol 1 . 02E+Ol 1377 . 67 4 . 11 2 . 52E+OO 1 . 0lE+Ol 1 4 07 . 98 2 . 48 - 9 . 84E+OO 1. 64E+Ol 1509 . 19 2 . 19 - 2 . 84E+OO 1 . 60E+Ol 1764 . 49 15 . 80 1 . 38E+OO 3 . 55E+OO
+ PB - 214 77 . 11 10 . 70 1. 88E+OO 9 . 06E - 01 2 . 71E+OO 295 . 21 19 . 20 l . 29E+OO l . 39E+OO 351. 92 37 . 20 1. 26E+ OO 9 . 06E-0 1
+ PA- 228 89 . 95 22 . 00 3 . 93E- 01 6 . 24E- 01 1 . 05E+OO 93 . 35 35 . 00 l. 31E - 01 6 . 24E- 01 105 . 00 16 . 30 2 . SOE- 01 l . 27E+OO 129 . 22 2 . 97 - l .2 9E+OO 6 . 93E+OO 338 . 32 5 . 30 1 . 78E+OO 5 . 00E+OO 463 . 00 13 . 80 - l . 35E+OO 2 . 24E+OO 911. 23 16 . 70 3 .13E+O O 3 . lSE+OO
+ AM- 241 59 . 54 36 . 30 6 . 26E - 01 l . 15E+OO 1 . 15E+OO CM- 243 103 . 76 23 . 00 5 . lOE - 01 8 . GOE-01 8 . GOE-01 228 . 18 10 . 60 2 . 74E - 01 2 . 00E +OO 277 . 60 14 . 00 1 . 32E+OO 1 . 79E +OO
+
. = Nuclide Identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 12
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:44:38PM Pagel of 6
~pex-Gamma Analysis Report for B1-010-001 (0" - 0.5") BOTTOM B 1-010-001-CSFC-COS-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 (0"
- 0.5") BOTTOM Sample Description : B1-010-001-CSFC-C06-CV Sample Type : Planchet Unit Sample Point Sample Size 1.286E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 1 :07:00PM Acquisition Started : 3/21/2019 2:24:19PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 1200.0 seconds Real Time : 1203.9 seconds Dead Time : 0.33 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100- 4096 Peak Area Range (in channels) : 100- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 5936 PEAK ANALYSIS REPORT Peak Analysis Performed on : 3/21 /2019 2:44:29PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 13
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:44:38PM Page 2 of 6 Analysis Report for B1-010-001 (0" - 0.S-) BOTTOM B1-010-001-CSFC-C06-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 74 475 - 482 477 . 96 2 . 59£+01 17 . 10 1. 39E+02 1.09 F 2 295 . 26 588 - 597 590 . 96 4 . 44E+0l 17 . 22 8 . 18E+0l 1.43 F 3 3 5 1 . 86 697 - 710 704 . 15 6 . 14 E+0l 18 . 43 7 . 72E+0l 1. 45 F 4 609 . 27 1213 - 1225 1 2 1 8 . 86 8 . 30E+0l 19 . 57 2 . 60E+0l 2 . 10 F 5 1461.11 2915 - 2929 2922 . 34 4 . 60 E+0l 14 . 75 1. 06£+01 3 . 01 F 6 1765 . 21 3526 - 3535 3530 . 49 1. 07E+0l 6 . 97 2 . 23E+00 1.26 M = First peak In a multiplet region m = Other peak in a multiplet region F : Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCEPEAK/BKG.SUBTRACT Peak Analysis Performed on : 3/21/2019 2:44:29PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Co"ected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F l 238 . 74 2 . 59E+0l 17 . 10 2 . 59E+0l l . 71E+0l F 2 295 . 26 4 . 44E+0l 17 . 22 1 . 73E+0l 9 . 59E+00 2 . 71E+0l l . 97E+0l F 3 351 . 86 6 . 14E+0l 18 . 43 2 . 55E+0 l l . 03E+0l 3 . 59E+0l 2 . llE+0l F 4 609 . 27 8 . 30E+0l 19 . 57 l . 29E+0l 7 . 69E+00 7 . 0lE+0l 2 . l0E+0l F 5 1461.11 4 . 60E+0l 1 4. 75 l . 90E+0l 5 . 03E+00 2 . 70E+0l 1 . 56E+0l F 6 1765 . 21 l . 07E+0l 6 . 97 1. 07E+0l 6 . 97E+00 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 10/26/2020 Page 14
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:44:38PM Page 3 of6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B1-010-001-CSFC-C06-CV NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCVgrams) Uncertainty K- 40 0 . 979 1460 . 75
- 10 . 67 5 . 89E+OO 3 . 42E+OO PB- 212 0 . 525 77 . 11 1 7. 50 238 . 63
- 44 . 60 2 . 22E - 01 1 . 47E- 01 BI - 21 4 0 . 546 60 9. 31
- 46 . 30 l . 49E+OO 4. 55E- 01 1120 . 29 15 . 10 123 8 . 11 5 . 94 1377 . 67 4 . 11 1407 . 98 2 . 48 1509 . 19 2 . 19 1764 . 4 9
- 15 . 80 l . 89E+OO 1 . 23E+OO PB -2 1 4 0 . 692 77 .11 10 . 70 295 . 2 1
- 19 . 20 6 . 58E- 01 4. 81 E- 01 351 . 92
- 37 . 20 5 . 39E - 01 3 . l BE- 01
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted al 2.000sigma UNIDENTIFIED PEAKS Peak Locale Performed on : 3/21/2019 2:44:29PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak Size (CPS) Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Uncertainty Type Nuclide 10/26/2020 Page 15
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:44:38PM Pagc 4 of 6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B1-010-001-CSFC-C06-CV All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K- 4 0 0 . 979 5 . 89E+OO 3 . 42E+OO PB- 212 0 . 525 2 . 22E-Ol l . 47E - 01 BI-214 0 . 546 l . 54E+OO 4 . 27E - 01 PB- 214 0 . 692 5 . 75E-0 1 2 . 65E - 01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 16
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 2:44:38PM Page 5 of6 Analysis Report for 81--010-001 (O" - 0.5") BOTTOM B 1-010-001-CSFC-C06-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21/2019 2:44:29PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA LineMDA Name (pCVgrams) (pCl/grams) {pCl/grams) (keV)
+ K- 40 1460 . 75
- 10 . 67 5 . 89E+ OO 5.18E+OO 5 . 18E+OO
+ AR-41 1293 . 64 99 . 16 1 . 82E-01 4 . 77E-01 4 . 77E- 01
+ C0- 60 1173 . 22 100 . 00 1 . 74 E- 01 4. 55E-01 v' 4 . 73E-01 1332 . 4 9 100 . 00 2 . 30E- 01 4. 55E- 01
+ KR- 85 513 . 99 0 . 43 6 . llE +Ol 8 . 26E+Ol 8 . 26E +Ol
+ Y- 88 898 . 04 93 . 70 5 . llE- 02 4 . 04E- 01 4. 04E- 01 1836.06 99.20 6 . 66 E-02 4 . lOE-01
+ I - 131 284 . 30 6 . 06 - 5 . 39E- 02 3 . 02E - 01 3 . 81E+OO 364 . 48 81.20 - 8 . 94 E- 02 3 . 02E-01 636 . 97 7 . 27 -2 . 93E+OO 3 _42E+OO
+ CS- 134 60 4. 70 97 . 60 - 7 . 40 E- 02 4 . 00E- 01 5 . 56E-Ol 795 . 84 85 .4 0 - 3 . 78E- 03 4 . 00E-01
+ CS - 137 661 . 65 85 . 12 3 . 15E- 01 4 . 48E-Ql ,V 4 . 48E-01
+ CE-144 80 . 12 1. 36 2 . 61E+OO l . 79E+OO 1. 95E+Ol 133 . 51 11 . 09 - 2 . 62E- 01 l . 79E+OO
+ EU - 152 121 . 78 28 . 43 -2 . 39E- Ol 6 . 81E - OU/ 6 . 81E-Ol 34 4. 28 26 . 60 -1. 80E-01 9 . 458-01 1408 . 08 20 . 75 - 2 . 53E- 01 2 . 04E+OO 10/26/2020 Page 17
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:44:38PM Page6 of6 Analysis Report for B1-010-001 co* -0.5") BOTTOM B1-010-001-CSFC-C06-CV Nuclide Energy Vie.Id(%) Activity NuclldeMDA LlneMDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV)
+ EU-154 123 . 07 40.40 1. 99E-01 4 . 88E - 01 / 4 . 88E-01 723 . 30 19.70 3 . 04E-01 1.68E+OO 1274 . 51 34.40 6 . 07E-01 1 . 23E+OO
+ EU-155 86.54 32 . 80 -3 . lOE-01 6 . 58E - 01 6 . 58E-01 105.31 21. 80 2 . 77E-01 9 . 0lE-01
+ BI-214 609 . 31
- 46.30 l . 49E+OO 6 . 09E-01 6 . 09E-01 1120 . 29 15.10 3 . 77E+OO 3.67E+OO 1238 .11 5 . 94 6 . 45E+OO 9 . 31E+OO 1377. 67 4 . 11 5 . 39E+OO l . 20E+Ol 1407 . 98 2 . 48 -2.12E+OO l . 71E+Ol 1509.19 2 . 19 -2.45E+Ol l.91E+Ol 1764.49
- 15.80 1 . 89E+OO 1 . 40E+OO
+ PB-214 77 . 11 10 . 70 1 . 94E+OO 6 . 64E- 01 2 . 69E+OO 295 . 21
- 19 . 20 6 . 58E-Ol 1 . 00E+OO 351. 92
- 37 . 20 5 . 39E- 01 6 . 64E - 01
+ PA-228 89.95 22.00 5.51E- 02 6.08E - 01 l.02E+OO 93 . 35 35.00 -l.28E-Ol 6 . 08E-01 105.00 16 . 30 - 7 . 99E-02 1 . 25E+OO 129 . 22 2 . 97 1 . 94E+OO 6 . 81E+OO 338 . 32 5 . 30 2 . 37E+OO 5 . 21E+OO 463 . 00 13.80 - 7 . 27E - 01 2 . 19E+00 911 . 23 16 . 70 -9.95E - 02 2 . 61E+OO
+ AM-241 59 . 54 36 . 30 -l.04E-01 l . 18E+OO l . 18E+OO
+ CM-243 103.76 23 . 00 -3 . 63E - Ol 8 .4 3E-01 8 . 43E-01 228.18 10 . 60 5 . 94E-01 l . 93E+OO 277 . 60 14 . 00 -1.55E+OO 1 . 54E+OO
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is Inconsistent w ith Currie MDA at 95% confidence level 10/26/2020 Page 18
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1:17:51PM Page I of5 pex-Gamma Analysis Report for 81-010-001 (O" - 0.5") TOP 81-010-001-CJFC-C07-CV GAMMA SPECTRUM ANAL YS/S Sample Identification : 81-010-001 (O" - 0.5") TOP Sample Description : 81-010-001-CJFC-C07-CV Sample Type : Planchet Unit Sample Point Sample Size 1.266E+02 grams Facility : Dairy1and_NPP Sample Taken On : 3/21/2019 10:53:00AM Acquisition Started : 3/21/2019 1:02:35PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLA8 Geometry : Planchet on DET Live Time : 900.0 seconds Real lime : 902.8 seconds Dead Time : 0.31 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100- 4096 Peak Area Range (in channels) : 100- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 5931 PEAK ANAL YS/S REPORT Peak Analysis Performed on : 3/21/2019 1:17:42PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 1
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/:.!019 1:17:51PM Page 2 of5 Analysis Report for 81-010--001 (O" - 0.5") TOP B1-010-001-CJFC-C07-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 1 4 61.21 2916 - 2928 2922 . 54 4 . 46E+0l 14 . 56 1. 30E+0l 2 . 14 M ::: First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I BKG. SUBTRACT Peak Analysis Performed on : 3/21 /2019 1:17:42PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Co"ected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 1 4 61.21 4 . 46E+0l 14 . 56 1 .4 3E +0l 3 . 77E+00 3 . 03E+0l l . 50E+0l M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Llbrary\HOTLABAIR.NLB IDENTIFIED NUCLIDES Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCilgrams) Uncertainty K- 40 0 . 966 1460 . 75
- 10 . 67 8 . 97E+00 4 . 48E+00 10/26/2020 Page 2
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1:11:51PM Page 3 of5 Analysis Report for B1*010-001 (0" - OS) TOP B 1-010-001-CJFC-C07-CV
* = Energy line found in the spectrum.
- = Manually added nuclide.
? ::: Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Perfonned on : 3/21/2019 1:17:42PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak Size (CPS) Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0 . 966 8.97E+ OO 4.48E +OO
? = nuclide is part of an undetennined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 3
LAC LTP - Final Status Survey Package - 3/26/2019 1:17:51PM Page 4 of 5 Analysis Report for B1-010-001 (O" - 0.5") TOP B1 -010-001-CJFC.C07-CV UNIDENTIFIED PEAKS Peak Locate Perfonned on : 3/21 /2019 1:17:42PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield{3/4) Activity Nuclide MDA LineMDA Name (pCl/grams) (pCilgrams) (pCl/grams) (keV}
+ K- 40 1460 . 75
- 1 0 . 67 8 . 97E+00 6 . SSE+00 6 . 55E+00
+ AR- 41 1293 . 64 99 . 16 - 3 . 60E- 0l l . 12E+00 l . 12E+00
+ CO- 60 1173 .2 2 100 . 00 2 . 96E-01 4. 59E-01 { 6 . 65E-01 1332 .4 9 100 . 00 - l . 23E-01 4 . 59E - 01
+ KR-85 513 . 99 0 . 43 4 . 21E+0l 9 . 92E+0l 9 . 92E+0l
+ Y- 88 898 . 04 93 . 70 - 6 . 58E- 02 4 . 24E - 01 4 . 49E - 01 1836 . 06 99 . 20 l . 18E-01 4 . 24E - 01
+ I-131 284 . 30 6 . 06 - l . 94E+00 3 .4 6E- 01 3 . 84E+00 364 . 48 81. 20 1 . 31E - 02 3 . 46E - 0l 636 . 97 7 . 27 2 . 75E+00 5 . llE+00
+ CS - 134 604 . 70 97 . 60 3 . 16E- 0 1 4 . lSE-01 4 . lSE-01 795 . 84 85 . 40 5 . 12E- 02 4. 81E-01
+ CS-137 661 . 65 85 . 12 2 . S0E-01 4. 73£-01 ) 4 . 73E-01
+ CE-144 80 . 12 1.36 1.49E+0l l . 94E+00 2 . 17E+0l 133 . 51 11.09 -1 . 03E+00 l . 94E+00
+ EU - 152 121 . 78 28 . 43 - 2 . 72 £- 01 7 . 33£ - 01 ) 7 . 33E - 01 344 . 28 26 . 60 -l . 13E+00 l . 12E+00 1408 . 08 20 . 75 -6 . 98E - 01 1 . 93E+00 10/26/2020 Page 4
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1:1 r :51PM Pages of5 Analysis Report for B1-010-001 (O" - 0.5") TOP B 1-010-001-CJFC-C07-CV Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV)
+ EU - 154 123 . 07 40 .4 0 - 2 . 25E - 01 5.04E - 01 5 . 04E-01 723. 30 19 . 70 -1. 34E-Ol 1. 85E+OO 1274.51 34 . 40 5 . 84E - 01 l . 76E +OO
+ EU-155 86 . 54 32 . 80 2 . 12E- 01 7 . 66E - 01 7 . 66E - 01 105 . 31 21. 80 -2 . 88E-01 1 . 02E+OO
+ BI-214 609 . 31 46 . 30 6 . 44E-01 8.59E-01 8 . 59E-01 1120 . 29 15 . 10 -1 . 52E+OO 2 . 83E+OO 1238 .11 5 . 94 8 . 17E+OO l . 02E+Ol 1377.67 4 .11 3 . 39E+OO 1 . 02E+Ol 1407 . 98 2 . 48 -5.84E+OO 1.61E+Ol 1509.19 2 . 19 -9.85E+OO 1 . 38E+Ol 1764.49 15 . 80 1 . 43E+OO 3 . 36E+OO
+ PB-214 77 . 11 10 . 70 1 . 36E-01 8.17E-01 2 . 86E+OO 295 . 21 19 . 20 7 . 72E- 01 1.56E+OO 351. 92 37 . 20 -2 . llE-01 8 . 17E-Ol
+ PA-228 89 . 95 22 . 00 2 . 04E-01 6.93E-01 1 . 15£+00 93 . 35 35 . 00 - 1 . 91E - 01 6 . 93E-01 105.00 16 . 30 -5.27E-Ol l . 46E+OO 129 . 22 2.97 -2.54E-01 7 . 59E+OO 338.32 5 . 30 -7.28E-01 5 . 87E+OO 463 . 00 13 . 80 4 . 92E-01 2 . 60E+OO 911.23 16 . 70 1. 84E+OO 2 . 96E+OO
+ AM-241 59.54 36 . 30 -2 . 45E-Ol l.33E+OO l.33E+OO
+ CM-243 103 . 76 23 . 00 -4 . 58E-02 9.58E-01 9 . 58E-01 228 . 18 10 . 60 4 . 49E-02 2 . 36E+OO 277 . 60 14 . 00 1 . lOE+OO l . 91E+OO
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION : MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 5
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 l . .> ..1:41PM Page 1 of6 pex-Gamma Analysis Report for B1-010.001 (O" - 0.5") BOTTOM B1--010-001-CJFC-C07-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010.001 (O" - 0.5") BOTTOM Sample Description : B1-010-001-CJFC-C07-CV Sample Type : Planchet Unit Sample Point Sample Size 1.266E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 10:53:00AM Acquisition Started : 3/21/2019 1:18:25PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Ptanchet on DET Live Time : 900.0 seconds Real Time : 902.6 seconds Dead Time : 0.29 % Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100 - 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number PEAK ANALYSI~ Peak Analysis Performed on : 3/21/2019 1:33:33PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 6
LAC LTP - Final Status Survey Package - 3/26/2019 3/21uu19 1:33:41PM Page 2 of 6 Analysis Report for 81-010-001 (0" - 0.5") BOTTOM 81-010-001-CJFC-C0?-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 239 . 02 473 - 485 478 . 51 4 . 60E+Ol 18 . 08 8 . 93E+Ol 1.82 F 2 1 46 1.37 2916 - 2 930 2922 . 85 4 . SlE+Ol 13 . 63 0 . 00E+OO 2 . 46 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I BKG. SUBTRACT Peak Analysis Performed on : 3/21/2019 1:33:33PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert F 1 239 . 02 4. 60E+Ol 18 . 08 4 .6 0E+Ol 1 . 8 1E +Ol F 2 1461.37 4 . SlE+Ol 13 . 63 1 . 43E+Ol 3 . 77E+OO 3 . 08E+Ol 1 . 41E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCilgrams) Uncertainty 10/26/2020 Page 7
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1:33:41PM Page 3 of6 Analysis Report for 81-010-001 (O" - 0.5") BOTTOM B1-010-001-CJFC-C07-CV Nuclide Name Id Confidence Energy {keV) Yield{%) Activity Activity (pCl/grams) Uncertainty K- 40 0 . 941 1460 . 75
- 10 . 67 9 . 12E+OO 4 . 22E+OO PB-2 1 2 0 . 509 77 . 11 17 . 50 238 . 63
- 44 . 60 5 . 35E - 01 2 . 12E- 01
* = Energy line found In the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keY Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21/2019 1:33:33PM Peak Locale From Channel ; 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy {keV) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams) K-40 0 . 941 9 . 12E+OO 4 . 22E+OO PB- 2 1 2 0 . 509 5 . 35E- 0 1 2 . 12E- 01 10/26/2020 Page 8
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1:33:41PM Pagc4 of6 Analysis Report for 81-010-001 (O" - 0.5") BOTTOM 81-010-001-CJ FC-C07-CV
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 9
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1:33:41PM Page 5 of6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM 81-010-001-CJFC-CO?-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21 /2019 1:33:33PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Oairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield(%) Activity Nuc/ldeMDA LlneMDA Name (pCl/grams) (pCl/grams) (pCl/grams) (keV)
+ K-40 1460 . 75
- 10.67 9 . 12E+00 4 . 91E+00 4.91E+0O
+ AR - 41 1293 . 64 99 . 16 1. 86E- 02 1.30E+00 1. 30E+00
+ CO-60 1173 . 22 100 . 00 7 . 95E-02 5. 82E-01 r 6 . 77E-01 1332 . 49 100 . 00 -1 . 60 E- 02 5 . 82E-0l
+ KR-85 513 . 99 0 . 43 2 . 24E+0l 9 . 09E+0l 9 . 09E+0l
+ Y-88 898.04 93 . 70 2.95 E-01 2 . 90E-01 4 . 24E-0l 1836 . 06 99 . 20 3 . 93£-02 2.90£ - 01
+ I-131 284 . 30 6.06 -5 . 75E-0l 2 . 98£-01 4 . 26£+00 364 . 48 81.20 -2 . 16£ -01 2 . 98£-01 636 . 97 7 . 27 3.38E+00 5 . 46E+00
+ CS - 134 604 . 70 97 . 60 3 . 08E-0 1 4 . l0E-01 4 . lOE-01 795 . 84 85 . 40 1. 25E-01 4.81£-01
+ CS-137 661 . 65 85 . 12 -l . llE - 01 4. 95£ - 01 4 . 95£ - 01
+ CE - 144 80 . 12 1. 36 l . 07E+0l l.92E+00 2 . 21E +0l 133 . 51 11.09 - 8 . 64£ - 01 1.92E+00
+ EU-152 121. 78 28 . 43 -6 . 98E-01 7. 25£ - 01 / 7 . 25£-01 344 . 28 26 . 60 - 2 . 66E+00 1. 07E+00 1408 . 08 20 . 75 5 . 73E - 01 2 . 56E+00 10/26/2020 Page 10
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 1:33:41PM Page 6 of6 Analysis Report for 81 -010-001 (0" - 0.5") BOTTOM B 1-010-001-CJFC-CO?-CV Nuclide Energy Yield(3/4) Activity NuclideMDA LlneMDA Name (pCilgrams) (pCilgrams) (pCilgrams) {keV)
+ EU-154 123.07 40.40 -2.33E -0 1 5 . 18E-01 / 5. l BE-01 723.30 1 9 . 70 -1 . 69E-0 1 l.90E+OO 1 274 . 5 1 34.40 3 .4 3E- 01 l . 62E+OO
+ EU - 155 86.54 32.80 6 . 48E-01 8 . 04E-01 8 . 04E-01 105 . 31 21. 80 1.48E- 01 9.94E - 01
+ BI-21 4 609 . 31 46.30 2 .23E-01 8 . 24E-01 8 . 24E-01 112 0.29 1 5. 1 0 -3.48E- 01 3.0SE+OO 12 38 .11 5.94 -2 . 53E+OO 8.24E+OO 1377 . 67 4 .11 7.99E+OO 1. 32E +O1 1 4 07 . 98 2 . 48 4.79E +OO 2 . 14E+O l 1509 . 19 2.19 -5.57E-01 1. 78E +O l 1764.49 15.80 - l. 64E-01 2.86E+OO
+ PB- 214 77. 11 10 .7 0 - 3.80E - 01 9 .1 6E-0 1 2.BBE +OO 295 . 21 19 . 20 6.SlE - 01 l .59E+OO 351 . 92 37.20 1. 26E +OO 9 . 1 6E- 01
+ PA-228 89 . 95 22 . 00 1. 98E - 01 7 . 23E-01 1 . 22E + OO 93 . 35 35.00 l . 3 1E- 01 7 . 23E-Ol 105 .00 16 .3 0 2 .0 SE-01 1.46E+OO 1 29.22 2.97 2.18E +OO 7.63E+OO 338 . 32 5 . 30 - 6.70E - 01 5.47E +OO 463.00 1 3.80 3 . 46E-01 2 .38E+ OO 911 . 23 16.70 2. 72E+OO 3.37E +OO
+ AM- 241 59.54 36.30 l.48E - 01 l. 29E+OO 1. 29E +OO
+ CM- 243 10 3.76 23. 0 0 4.B lE-01 9.70E-01 9.70E-01 228 . 1 8 1 0 . 60 -1. 70E +OO 2.15 E+OO 277.6 0 1 4.0 0 -7.lSE-01 1 . 76E+OO
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life loo short to be able to perform the decay correction
? = CAUTION : MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 11
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1 :49:29PM Page I of6
~pex-Gamma Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CJFC-COB-CV GAMMA SPECTRUM ANAL YS/S Sample Identification : B1-010-001 (O"
- 0.5") TOP Sample Description : B1-010-001-CJFC-C0S-CV Sample Type : Planchet Unit Sample Point Sample Size 1.275E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 12:35:00PM Acquisition Started : 3/21 /2019 1:34 :14PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds Real nme : 902.9 seconds Dead lime : 0.32 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100
- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 5933 PEAK ANALYSIS 9/EPORT Peak Analysis Performed on : 3/21 /2019 1 :49:20PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 12
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1:49:29PM Pagel of6 Analysis Report for 81-010-001 (0" - 0.5") TOP 81-010-001-CJFC-C0B-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 76 .98 149 - 159 154 . 51 4.17E+Ol 21.49 1 .8 6E+02 1. 61 F 2 351. 62 698 - 710 703.66 4 .62E+Ol 15 .68 3.76E+Ol 1. 77 F 3 1460 . 87 2915 - 2927 2921.85 3.25E+01 12 . 49 9.45E+OO 2.51 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCEPEAK/BKG.SUBTRACT Peak Analysis Performed on : 3/21/2019 1:49:20PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 76.98 4 . 17E+Ol 21. 49 4.17E+O l 2.lSE+O l F 2 351 . 62 4.62E+Ol 15.68 l . 91E+01 7.75E+OO 2 . 71E+Ol 1. 75E+Ol F 3 1 460 . 87 3 . 25E+Ol 12 . 49 l . 43E+Ol 3 . 77E+OO 1 . 82E+Ol 1 . 30E+Ol M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nudide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 13
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1:49:29PM Pago3 of6 Analysis Report for B1 -0 10-001 (O"
- 0.5") TOP B1-010-001-CJFC-C08-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCVgrams) Uncertainty K-40 0 . 998 1460 .75
- 10.67 5.35E+00 3.84E+00 PB-214 0 . 525 77 . 11
- 10 .7 0 l . 75E+00 9 . llE-01 295 . 21 19 . 20 351. 92
- 37.20 5 .4 5E- 01 3 . 53E-01
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Perfonned on : 3/21/2019 1:49:20PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigrna INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams) K-40 0.998 5.35E+00 3.84E+00 10/26/2020 Page 14
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1:49:29PM Page4 of6 Analysis Report for B1-010-001 {0" - 0.5") TOP B1-010-001-CJFC-C0S-CV Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pC/lgrams) PB- 214 0 . 525 7 . 03E -Ol 3 . 29E- 01
? = nuclide is part of an undetermined solution X = nuclide rejected by the Interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 15
LAC LTP - Final Status Survey Package - 3/26/2019 3/2112019 1:49:29PM Page 5 of6 Analysfs Report for 81-010-001 (0" - 0.5") TOP B1-010-001-CJ FC-C0B-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21/2019 1:49:20PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peale No. Energy {keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used ; C;\Canberra'Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yleld(3/4) Activity NuclideMDA LineMDA Name (pCl/grams) {pCilgrams) (pCl/grams) (lceV)
+ K- 4 0 1 4 60 . 75
- 1 0. 67 5 . 35E+O O 6 . lO E+ OO 6 .lOE+OO
+ AR-41 1 29 3 .64 99 . 16 l .8 4E- 02 8 . 64E- 01 8 . 64£-0 1
+ C0- 60 1173.22 10 0. 00 2 . 48 E- 01 4 .7 9E - 01 .,/ 5 . 85E- 01 1332 .4 9 1 00 . 00 - 2 . lSE - 02 4 . 79E-01
+ KR- 85 513 . 99 0 . 43 7 . 43 E+Ol 9 . llE+Ol 9 . llE +Ol t Y-8 8 898 . 0 4 93 .70 8.78 E-0 2 4.69E-01 5. 02E-01 1836 . 06 99 . 20 - 5 . 52 E- 01 4 . 6 9E-01 t I -131 284 . 30 6 . 06 1. 1 8E-Ol 3 . 61 £ - 01 4 . 63 E+O O 364 . 48 81. 20 2.25E-0 1 3 . 61E- 01 63 6. 97 7 .2 7 -3 . 40 E+ OO 5 .1 4E + OO
+ CS- 134 604 . 7 0 97 . 6 0 3 . 02E -02 3 . 69E - Ol 4. 97E-O l 795 . 84 8 5 . 40 -1 .7 9E - 01 3 . 69E- 01
+ CS - 137 661 . 65 8 5 . 12 2 .7 9E - 01 5 . 62E - 01 5. 62E-01
+ CE-144 80 . 12 1. 36 - 1 . 22E+ Ol 2 . 0lE + OO 2 . 26E+ Ol 133 . 51 1 1. 09 -4 . 20E - Ol 2 . 0lE+OO
+ EU- 152 1 21 . 78 2 8 . 43 9 . 72 E- 0 2 7. 71 E-0 1 ,/ 7 . 71 E-O l 344 . 28 26. 6 0 -1 . 00 E+ OO 1. 16E+OO 1 4 0 8. 08 20. 75 - 9 . 85 E- Ol 1. 57E+ OO 10/26/2020 Page 16
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1:49:29PM Page 6 of6 Analysis Report for BH)10-001 (0" - 0.5") TOP B 1-010-001-CJFC-C0B-CV Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (keV) (pCilgrams) (pCilgrams) (pCVgrams)
+ EU-154 123.0 7 40.40 1. BSE-01 5 . 49E-01 / 5 . 49E-Ol 723 . 30 19.70 l.82E +00 2 . 29E+OO 1274.51 34.40 - 4.28E - 01 l . 39E+OO
+ EU-155 86.54 32 .8 0 - 3 . 18E- 02 7 . BOE -0 1 7.BOE- 01 105.31 21. 80 -l.25E-01 l.02E+OO
+ BI -21 4 609 . 31 46.30 1. 05E +OO 1.07E+OO 1. 07E+OO 1120. 29 15.10 -1. 09E+OO 3.87E+OO 1238 .11 5 . 94 8.68E+OO 1. 25E+Ol 1377 . 67 4. 11 - l.26E+OO 1 . 14E+Ol 1407.98 2 . 48 -8.24E 00 l.31E+01 1509 .1 9 2 . 19 -9.47E+OO 2 . 46E+Ol 1764.49 15 .8 0 1 .6 5E+OO 3.55E+OO
+ PB-214 77 .11
- 10. 70 l . 75E+OO 6 .60E-01 2.18E+OO 295 . 21 19 . 20 - 7.SOE - 01 l . 60E+OO 351.92
- 37.20 5.45E - 01 6.60E- 01
+ PA-2 28 89.95 22.00 l.47E+OO 6 .7 6E -01 1.20E+OO 93.35 35 . 00 -2.54E-01 6.76£-01 105.00 16.30 5.84E-01 1 . 43E+OO 129.22 2.97 -4. 45E + OO 7 . 61E+OO 338 . 32 5 . 30 4.82E+OO 6.35E+OO 463.00 13 .. 80 l.35E+OO 2 . 61E+00 911.23 1 6 . 70 - l . 27E+OO 3 . 08E+OO
+ AM-241 59 . 54 36.30 7 .2 9E-01 l .26E+O O 1 . 26E+OO
+ CM-243 103.76 23.00 7.07E-Ol 9.BOE-01 9.BOE-01 228 . 18 10.60 2.54E-01 2 .38 E+OO 277.60 14.00 -9.21E-01 l .82E+OO
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 17
LAC LTP - Final Status Survey Package - 3/26/2019 3/2112019 2:U5:54PM Page I of 6
~pex-Gamma Analysis Report for B1-010--001 (0" - 0.5") BOTTOM B 1-010-001-CJFC-COB-CV GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001 (O" - OS) BOTTOM Sample Description : 81-010-001-CJFC-C0S-CV Sample Type : Planchet Unit Sample Point Sample Size 1.275E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 12:35:00PM Acquisition Started : 3/21/2019 1:50:37PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds RealTime : 903.4 seconds Dead lime : 0.37 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in ci1annels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number Peak Analysis Performed on : 3/21/2019 2:05:45PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 18
LAC LTP - Final Status Survey Package - 3/26/2019 3/21 /2019 2:05:54PM Page 2 of 6 Analys is Report for B1-010-001 (O" - 0.5") BOTTOM B1-010-001-CJFC-C08-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (lceV) start end Centroid Area Uncertafnty Counts (keV) F 1 23 8. 87 472 - 484 478 . 21 3.58E+Ol 16 . 92 9 . 73E+Ol 1. 72 F 2 1 461. 18 29 1 7 - 2929 2922 . 46 4 . 67E+Ol 14 . 16 2 . 73E+OO 2 . 32 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCEPEAKIBKG.SUBTRACT Peak Analysis Performed on : 3/2112019 2:05:45PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is : Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Un cert. Area Uncert.
F 1 23 8. 87 3 . 58E+Ol 1 6 . 92 3 . SB E+Ol l. 69E+O l F 2 1461.1 8 4 . 67 E+Ol 14 .1 6 l.43E+Ol 3 . 77E +OO 3 . 24E+Ol l. 47E+O l M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Ape><\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCilgrams) Uncertainty 10/26/2020 Page 19
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:05:54PM Page 3 of6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B1-010-001-CJFC-COS-CV Nuclide Name Id Confidence Energy (keV) Yield{%) Activity Activity (pCVgrams) Uncertainty K- 40 0 .9 71 1460 . 75
- 10 . 67 9 . 53E +0O 4.34 E+00 PB-212 0 . 520 77 . 11 17 . 50 238 .63
- 44 .6 0 4 . 13E- 01 l.9 6E - 0l
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nudide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21/2019 2:05:45PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV} Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K- 40 0 . 971 9 . 53E+OO 4 _34E+OO PB- 212 0 . 520 4 . 13E- 01 l . 96E- 01 10/26/2020 Page 20
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:05:54PM Page 4 of6 Analysis Report for 81-010-001 (0" - 0.5") BOTTOM B 1-010-001-CJFC-COB-CV
? :a 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 al .2.000sigma 10/26/2020 Page 21
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:05:54PM Page 5 of6 Analysis Report for 81-010-001 (0" - 0.5") BOTTOM 8 1-010-001-CJFC-C0S-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21 /2019 2:05:45PM Peak Locale From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M : First peak in a multiplet reg ion m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Ape>C\Root\Dairyland_ NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield(3/4) Activity NuclldeMDA UneMDA Name (pCl/grams) (pCl/grams) (pCl/grams) (keV)
+ K-40 1460.75
- 10 . 67 9 . 53E+00 5.24E+00 5 . 24E+0O
+ AR-41 1 293.64 99 . 16 -8.69E-01 8 . 64E-01 8 . 64E- 01
+ CO-60 1173 . 22 100 . 00 2.75 E-01 5. 21E-01 ,..-, 5.42E-01 1332 . 49 100 . 00 l . 76E - 01 5 . 21E-01
+ KR-85 513.99 0.43 8 . 73E+0l 9.53E+0l 9 . 53E+0l
+ Y-88 898 . 04 93 . 70 -9 . llE - 02 2.87£-0 1 5.02E-0 1 1836 . 06 99 . 20 3 . 91E - 02 2.87E-01
+ I-131 284 . 30 6 . 06 2 . 09E +00 3 . 46E- 01 4.55E+0O 364 . 48 81. 20 4 . 71E-02 3 . 46E-0l 636.97 7 . 27 -2.07E +00 5 .1 5 E+0O
+ CS-134 604 . 7 0 97 . 60 2 . 8 4E -0l 4 . 33 E-0l 4 . 66E-0l 795 .8 4 85 . 40 -3 . 95 E-01 4 . 33E-01
+ CS-137 661. 65 85.12 4 . 86£-01 5 . 25E - 01 .,... 5 . 2 5 E-01
+ CE-144 80 . 12 1.36 - 4 . 83E+00 1 . 99E+0O 2.32E+01 133. 51 11 . 09 3 . 38 E-01 1. 99E+00
+ EU-152 121. 78 28 . 43 -5 . 28E-01 7. 39E-0 Y 7.39E-01 344.28 26 . 60 -3 . lSE+00 1.09E+00 1408 . 08 20 . 75 l. 60 E-01 2 . 54 E+00 10/26/2020 Page 22
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 2:05:54PM Page 6 of6 Analysis Report for 81-010-001 (0" - 0.5") BOTTOM 81 -010-001-CJFC-C0S-CV Nuclide Energy Yield(%) Activity Nuclide MDA Line MDA Name (pCi/grams) (pCUgrams) (pCi/grams) (keV)
+ EU - 154 123 . 07 4 0.40 -9 . 68E - 02 5. 26E-01 / 5 .. 26E-0 1 723 . 30 19 . 70 -5 . 99E-01 2 . 04Et00 1274 . 51 34 . 40 8 . 92E-01 1.7 5E+OO
+ EU - 155 86 . 54 32.80 9 . 75E - 02 8 . 2 9E- 01 8 . 29E - 01 105 . 31 21. BO 3 . 16E-01 1 .03E+OO
+ BI - 21 4 609 . 31 46 . 30 3 .1 9E-Ol 9.B OE-01 9.80E - 0 1 1120 . 29 15 . 10 1 . 65E +OO 3 . 34E+OO 1238 . 11 5 . 94 4 . 31E+O O 1.0lE+O l 1377. 67 4.11 -5. BOE+OO l.08E+Ol 140 7. 98 2 . 48 l . 34E+00 2 .13E+Ol 1509 .1 9 2 . 19 - 7 . 75E+ OO l . 93E+Ol 1764 .4 9 15.80 1.89E+OO 3 . 75E+OO
+ PB- 214 77 . 11 1 0 . 70 1 . 43E+OO 9 . 2 4E- 01 3 . 28E+OO 295 . 21 19.20 l . 08E+ OO 1.60Et00 351 . 92 37 . 20 l.15E+OO 9 . 24E- 01 t PA-228 89 . 95 22 . 00 1 . 0 BE- 02 7.1 4E- 01 l. 2 1E+OO 93 . 35 3 5 . 00 7. 3 0E-02 7 . 1 4E - 0 1 105 . 00 16.30 6.44E-01 1. 44E+OO 129.22 2 . 97 2 . 77E+OO 7 . 79E+OO 338.32 5 . 30 8.BOE-01 S .54 E+OO 463 . 00 13 . 80 2.31E+00 2 . 69E+OO 911 . 23 1 6 . 70 - 1.17E+OO 2 . 72E+OO
+ AM- 24 1 59 . 54 36 . 30 - 2 . 02E - 01 1 . 53£+00 1. 53E+ OO
+ CM-243 103 . 76 23.00 3 . 89E-02 9. 71E - 01 9 . 71E - 01 228 .1 8 10 . 60 5 . 29E -0 1 2 . 25Et 0 0 277 . 60 14 . 00 1. 3 4E+OO l. 98E+OO
+ = Nuclide identified during the nuclide identification
. = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 23
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1 2:15AM Page I of6 JtApex-Gamma Ana'l ysis Report tor 81-010-001 (O" - 0.5") TOP B1-010-001-CJFC-COS-CV GAMMA SPECTRUM ANALYSJS Sample Identification : 81-010-001 (O" - 0.5") TOP Sample Description : 81-010-001-CJFC-COB-CV Sample Type : Planchet Unit Sample Point Sample Size 1.345E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 5:06:04PM Acquisition Started : 3/22/2019 10:16:59AM Procedure : Planchet on DET Operator : Administrator Detector Name :HOTLA8 Geometry : Planchet on DET Live Time : 900.0 seconds Real Time : 903.2 seconds Dead Time : 0.35% Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (In channels) : 100- 4096 ldenttfication Energy Toleranoe : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Descfiptlon Sample Number Peak Analysis Performed on : 3/22/2019 10:32:06AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 24
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 10:32:15AM Page 2 of6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CJFC-C09-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 23 8. 47 47 3 - 4 85 4 7 7. 42 7. 06E +O l 29 . 77 4 . 57E+02 1. 67 F 2 351. 67 6 99 - 708 703 . 77 6 . 4 8E+Ol 24 . 29 2 . 30E+0 2 1. 32 F 3 609 . 1 7 1213 - 122 4 1218 . 68 2 . 9 8E+Ol 1 4 . 32 6 . 0 0E+O l 1. 56 F 4 661 .53 1317 - 1332 1323 . 37 2 . 99 E+0 3 111. 6 4 5 .5 6E+O l 1. 93 F 5 1460 . 66 2913 - 2 92 7 2 92 1.43 7 . 71E+ Ol 18 . 71 1 . 69E+O l 2 . 02 M = Flrst peak in a multiplet region m = Other peak In a multiplet region F :a Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I BKG. SUBTRACT Peak Analysis Performed on : 3/22/2019 10:32:06AM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Oairyland_NPP\Oata\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 238 .4 7 7 .0 6E+O l 29 .77 7. 06E +O l 2 . 9 8E+O l F 2 35 1. 67 6 . 4 8E+Ol 2 4. 29 1 .91 E+Ol 7.75E+ 0 0 4 . 5 7 E+0 1 2 . 5 5E+0 1 F 3 609 . 17 2 . 9 8E+O l 14 . 32 9 . 69E +O O 5 . 7 7£+0 0 2 . 0lE+ Ol l . 5 4E+ Ol F 4 661. 5 3 2 . 99E+03 11 1. 6 4 1 . 72E+Ol 7. 2 7E+OO 2 . 98E+03 l. 12 E+ 0 2 F 5 1 460 _6 6 7 . 71E+Ol 18 . 71 l .4 3E+Ol 3 . 77 E+OO 6 . 29E+Ol 1 . 91 E+Ol M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 25
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 10:32:1SAM Page 3 of6 Analysis Report for 81-010-001 (O" - 0.5") TOP B 1-010-001-CJFC-C09-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCilgrams) Uncertainty K-4 0 0 .99 9 1460. 7 5
- 10. 67 1. 7 5E+Ol 5 .4 0E+OO CS- 13 7 0 .998 66 1. 65
- B5. 12 4. 77E+Ol 3 . 15E+OO PB- 212 0 . 524 77 .11 17 . 50 2 3 8. 63
- 4 4 . 60 7 . 71E - 01 3 . 27 E- 0 1 BI - 21 4 0 . 363 60 9. 31
- 4 6 . 30 5.4 5E - 01 4. 1 9E- 0 1 1120.29 15 .1 0 12 38 . 11 5 . 94 137 7. 6 7 4 . 11 1 4 0 7.98 2 .4 8 150 9.19 2 . 19 1 76 4 . 4 9 15 . 80
- = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTlflED PEAKS Peak Locate Performed on : 3/22/2019 10:32:06AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide F 2 351 . 67 5 . 081 11 E-0 2 2 7. 8 8 To l. PB- 2 14 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Erroffi quoted at 2.000sigma 10/26/2020 Page 26
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 10:32:15AM Page 4of 6 Analysis Report for B 1-010-001 (0" - 0.5") TOP B1-010-001-CJFC-C09-CV INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Conffdence Uncenainty (pCilgrams) K- 40 0 . 99 9 1. 75 E+Ol / 5 . 40 E+OO CS - 137 0 .9 98 4 . 77 E+Ol 3 . 15E+OO PB- 212 0 .52 4 7 . 71 E-01 3.27E - 01 BI- 2 14 0 . 363 5 .4 5E- 01 4. 19E-01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 27
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 10:32:15AM Page 5 of6 Analysis Report for B1-010-001 (Q* - 0.5") TOP B1-010-001-CJFC-C09-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 10:32:06AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 351. 67 5 . 08111£-02 27.88 Tol. PB-214 M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dalryland_NPP\Llbrary\HOTLABAIR.NLB Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCi/gramsJ (pCi/gramsJ (pCi/grams) (keV}
+ K- 40 1460.75
- 10.67 l . 75 E+Ol 6 . 65E+OO 6.65E+OO
+ AR-41 1293 . 64 99 .1 6 -1 . 35E+02 3 . 82E+02 3.82E+02
+ C0- 60 1173 . 22 100 .00 5 . 04E-02 5.31E-01 / 6 . 26E- Ol 1332.49 100 . 00 -1. 85E-01 5 . 31£-01 t- KR-85 513 . 99 0 . 43 -4.69E+OO l . 73E+02 1 . 73£+02
+ Y-88 898 . 04 93 . 70 -1 .99E- 01 4.00E-01 4 . 68E-01 1836 . 06 99 . 20 1 . 12E-01 4.00E - 01
+ 1 - 131 284.30 6 . 06 6 . 37E-01 8 . 35E-01 9 . 13E+OO 364.48 81 . 20 2.49E-Ol 8 . 35E - 01 636.97 7 . 27 1. 46E+OO 7.51E+OO
+ CS- 134 604.70 97 . 60 -5.0SE-02 5 .4 4E-01 6 . 60£- 01 795.84 85 . 40 2 . 41E-Ol 5 . 44E-01
+ CS-137 661 . 65
- 85.12 4 . 77E+Ol 5 . 84E-01 5 . 84£-01
+ CE-144 80.12 1.36 1.08E+Ol 3.00E+OO 3 . 19E+Ol 133. 51 11 .0 9 - 1 . 71E+00 3 . 00E +OO
+ EU-1 52 121 . 78 28.43 2 . 32£-01 1 . 21E+oo 1.21E+OO 10/26/2020 Page 28
LAC LTP - Final Status Survey Package - 3/26/2019 3122/2019 10:32:15AM Page6of6 Analysis Report for 01-010-001 co* - o.5") TOP B1-010-001-CJFC-C09-CV Nuclfde Energy Yield(3/4) Activity NuclideMDA LineMDA Name (pCl/grams) (pCUgrams) (pCi/grams) (keV) EU-15 2 344.28 26. 60 -1 .47E +OO 1 .21E+OO 2 . 33E+OO 1408.08 2 0.75 4.15E- 01 l .49E+OO
+ EU-154 123 . 07 40.40 - 2 .69E- 01 8 . 40E-Ol/ 8.40E-01 723. 30 19.70 3 . 04E-01 2.35E+OO 1274 .51 34.40 - 2 . 96E -0 1 l . 48E+OO
+ EU- 155 86.54 32 . 80 4.22E -02 1. 16E+OO l . 16E+OO 105.31 21. 80 -2.76E-Ol l.5 7E+OO
+ BI-214 609.31
- 46.30 5.45E-O l 9.33E -Ol 9.33E-01 1120.29 1 5.10 2 . 25E+OO 3.89E+OO 1238.11 5.94 2 .87E +O O 1 . llE+Ol 1377 . 67 4 . 11 -1.20E +OO l. 19E+Ol 1407.98 2 . 48 3 . 47E+OO l.25E +O l 1509 . 19 2 . 19 9.79E+00 2.lOE+Ol 1764 . 49 15.80 l.34E+OO 3 . 16E+OO
+ PB-214 77 .11 10 . 70 2 . 08E+OO 1,82E+OO 4.32E+OO 295 .21 19.20 1. 67E+OO 2.94E+OO 351. 92 37.20 l. 79E+OO 1.82E+OO
+ PA-228 89.95 22 . 00 3 . 26E- Ol l .76E+OO 2.89E +00 93 . 35 35 . 00 1. 83E-01 1 . 76E+O O 105.00 16.30 - 1.27E+OO 3 . 60E+OO 129 . 22 2 . 97 - 4 . 94E+OO 1. 94E+Ol 338 . 32 5.30 l.03E+Ol 2.00E+Ol 463.00 13 . 80 7.69E +O O l .1 9E+Ol 911 . 23 16.70 3.00E+OO 6.03E +O O
+ AM-241 59.54 36.30 1 .30E+O O 2.02E+OO 2.02E +O O t CM - 243 103.76 23.00 -7 .60E-01 l .4 8E+OO 1.48E+OO 228.18 10 . 60 - 1 . 12 E+OO 4.33E+OO 277. 60 1 4.00 6.53E-01 3.77E+OO
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> ;:: MDA value not calculated Half-life too short to be able to perform the decay correction
? ;;;
CAUTION: MDA value Is Inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 29
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1u:48:S0AM Page I of6
~pex-Gamma Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B1-010-001-CJFC-C09-CV GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001 (O"
- 0.5") BOTTOM Sample Description : B1-010-001-CJFC-C09-CV Sample Type : Planchet Unit Sample Point Sample Size 1.345E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 5:06:00PM Acquisition Started : 3/22/2019 10:33:34AM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds Real Tlme : 902.7 seconds Dead lime : 0.30%
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak.Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 ~ Efficiency Calibration Description : /4 ,,ll,,()J.t I {)~ :z,z_./tf Sample Number PE::ANALY~ Peak Analysis Performed on : 3/22/2019 10:48:41AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 30
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 10:48:S0AM Page 2 of6 Analysis Report for B1-010-001 (0" - 0.5") BOTTOM B 1-010-001-CJFC-C09-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 71 473 - 485 477. 89 6 . 66E+Ol 27 . 39 2.87E+02 2 . 09 F 2 351 . 97 697 - 711 7 04. 37 7 .0 2E+01 24 . 32 2 . 43E+02 1. 75 F 3 609 .1 1 12 1 4 - 1223 1 218 . 56 3 . 04E+01 14 . 10 3 . 8 1E+Ol 1. 72 F 4 661 . 60 1 31 7 - 1330 1 323 . 52 l . 28E+03 73 .4 9 5 . 78E+O l 1. 89 F 5 146 0.49 2 91 4 - 2929 2921.10 8 . 70E+Ol 18 . 7 1 O.OOE+OO 2 . 55 M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT
.R EFERENCE PEAK I 8KG. SUBTRACT Peak Analysis Performed on : 3/22/2019 10:48:41 AM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_ NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 238 . 71 6 . 66E+ Ol 27 . 39 6 . 66E+Ol 2 .7 4E +O l F 2 3 51 .97 7. 02E+Ol 24 . 32 l . 91E +01 7.7 5E +OO 5 . llE+Ol 2 . 5 5 E+ Ol F 3 60 9 . 11 3 . 0 4E+O 1 4. 10 9 . 69E+OO 5 . 77E+OO 2 . 07E +Ol 1 . 52E+ Ol F 4 661 . 60 l . 28E+03 73 . 4 9 1 . 72E+Ol 7 . 27E+OO l . 26E+03 7 . 39E+Ol F 5 1460 . 49 8 . 70E+Ol 18. 71 l .4 3E+Ol 3 . 77E+OO 7 . 27E+Ol l . 91E+O l M :: First peak in a multiplet region m == Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 31
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 10:48:S0AM Page J of 6 Analysis Report for 81-010-001 (O" - OS) BOTTOM 81-010-001-CJFC-C0S-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCl/grams) Uncertainty K-40 0 . 989 1 460 . 75
- 10 . 67 2 . 02 E+ Ol 5 . 43 E+ OO CS - 137 1 . 000 6 61. 65
- 85 . 12 2 . 03E+Ol 1 . 62E+O O PB - 2 1 2 0 . 526 77 . 11 1 7. 50 2 38 .63
- 44.60 7 . 2 8E-O l 3 . 0 2E- 01 BI- 214 0 . 361 609 . 31
- 4 6.30 5 . 61E-O l 4 .14 E- Ol 1120 . 29 15 . 10 12 38 .11 5 . 94 13 77 . 67 4 .11 1 4 07.98 2.48 1 509 . 1 9 2 . 19 176 4.49 15 . 80
* = Energy line found In the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nudide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 10:48:41AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide F 2 351 . 97 5. 67 41 2£- 0 2 24. 9 9 To l. PB- 2 14 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 10/26/2020 Page 32
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 10:48:SOAM Page4 of6 Analysis Report for 81-010-001 (0" - 0.5") BOTTOM B 1-010-001 -CJ FC-C09-CV INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams} K-40 0.989 2 . 02E+Ol / 5.43E+OO CS-137 1.000 2.03E+Ol 1.62E+OO PB-212 0 .526 7.28E-01 3.02E-Ol BI-214 0 . 361 5 . 61E-01 4.14E-Ol
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used In Weighted Mean Activity Errors quoted at 2.000slgma 10/26/2020 Page 33
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 10:48:S0AM Page 5 of6 Analysis Report for 81-010-001 (0" - 0.5") BOTTOM B1-010-001-CJFC-C09-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 10:48:41AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS} Uncertainty Type Nuclide F 2 351.97 5 . 67412E - 02 24 . 99 Tol. PB-214 M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairylan d_NPP\Llbrary\HOTLABAIR.NLB Nuclide Energy Yield(%) Activity NuclideMDA Line MDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV)
+ K-40 1460.75
- 10.67 2 . 02 E+0l 4.62E+O0 4.62E+O0
+ AR-41 1293.64 99.16 -2.01E+02 3.82E+02 3.82E+02
+ CO-60 1173.22 10 0.00 2.49E-02 4 . 74E-01 vi 6.lSE-01 1332.49 100.00 l.24E - 01 4.74E - 01
+ KR-85 513 . 99 0.43 9 . 85E+0l l . 46E+02 1 . 46E+02
+ Y- 88 898.04 93.70 2 . 75E-02 4.58E-01 4.SBE-01 1836.06 99.20 l.86E-Ol 4.88E-0l
+ I -131 284.30 6.06 -2.48E-01 6 . 95E-01 7 . 53E+00 364.48 81.20 7 . 62E-02 6.95E-0l 636 . 97 7.27 4 . 87 E+00 8.22E+00
+ CS-134 604.70 97.60 5.64E-02 5.66E-Ol 5.66E-0l 795 . 84 85 . 40 4.43E - 0l 6.0SE - 01
+ CS-137 661. 65
- 85.12 2.03£+01 5. 94E-01 5.94E - 01
+ CE-144 80 . 12 1. 36 l.85E - 01 2.86E+OO 2 . 86E+Ol 133 . 51 11.09 l . SSE+0O 2.86E+O0
+ EU-152 121 .78 28.43 -l.97E-01 1. 04E+OO / 1. 04E+O0 10/26/2020 Page 34
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 10:48:S0AM Page 6 of6 Analysis Report for 8 1-010-001 (O" - OS) BOTTOM 8 1-010-001-CJFC-C09-CV Nuclide Energy Yleld{%) Activity NuclldeMDA LineMDA Name (pCIJgrams) (pCilgrams) (pCUgrams) (keV) EU - 152 344 . 28 26 . 60 3 . 07E - 01 1.04E+OO 1. 85E+OO EU-154 1 4 08 . 08 123 . 07 20 . 75 9.59E- 01
- 4.0 l E-01 7 . 24E-01 1 2. 60E+OO 7.24E-01
+ 40 . 40 723 . 30 19 . 70 7 . BlE-02 2 . 26E+OO 1274 . 51 3 4. 40 l. 44E+OO l . 74E+OO
+ EU - 155 86 . 54 32 . 80 3 . 96E-01 1. 02E+00 l . 02E+OO 105 . 31 21. 80 7 . 70E-01 l . 42E+00
+ BI-214 609 . 31 -11 4 6 . 30 5 . 61E-Ol 7 . 74E- 01 7.74E-01 1120 . 29 15 . 10 7 . 81E -01 3 . 51E+ OO 1238 . 11 5 . 94 4 . 49E+OO 1. 20E+Ol 1377 . 67 4 .11 -7 . 39E+OO 1 . 29E+Ol 1 407 . 98 2.48 8 . 03E+OO 2.18E+Ol 1509 . 19 2 .1 9 l . 12E+Ol 2 . 22E+Ol 1764 . 49 15 . 80 2 . 24E +OO 3 . 90E+OO
+ PB - 214 77 . 11 10 . 70 2 . 29 E-0 1 1.57E+OO 3.79E+OO 295 . 21 19 . 20 -9 . 96E-Ol 2 . 36E+OO 351 . 92 37 . 20 1 . llE+OO l . 57E+OO
+ PA-228 89 . 95 22 . 00 l . 66E+OO l.52E+OO 2 . 59E+OO 93 . 35 35 . 00 -l . 14E+OO l . 52E+OO 105 . 00 16 . 30 2 . 66E+OO 3 . 33E+OO 129 . 22 2 . 97 - 8 . 53E+OO l . 78E +Ol 338 . 32 5 . 30 - 1. 50E+OO 1 . 62E+Ol 463.00 13 . 80 - 1 . 59E+OO 8 . 80E+00 911 . 23 16 . 70 2 . 13E+OO 5 . 61E+00
+ AM-24 1 59 . 54 36 . 30 - 6 . 37E - 01 1 . 61E+OO 1 . 61E+OO
+ CM- 243 103 . 76 23 . 00 7 . 30E - 01 1 . 36E+OO 1 . 36E+OO 228 . 18 10 . 60 -3 . 77 E+OO 3 . 20E+OO 277 . 60 14 . 00 l. 58 E+ OO 3 . lOE+OO
+ = Nuclide identified during the nudide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA val ue is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 35
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1n)4:25AM Page I of6
~pex-Gamma Analysis Report for B1-010-001 (0.5" - 1.0") TOP B1-010-001-CJFC-C0S-CV GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001 (0.5"- 1.0") TOP Sample Description : 81-010-001-CJFC-C0S-CV Sample Type : Planchet Unit Sample Point Sample Size 1.464E+02 grams Facility : Dairyland_ NPP Sample Taken On : 3/21/2019 5:06:00PM Acquisition Started : 3/22/2019 10:49:0SAM Procedure : Planchet on DET Operator : Adm inistrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds Real Time : 902.7 seconds Dead Time : 0.30 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number Peak Analysis Performed on : 3/22/2019 11:04:15AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 36
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 11 :04:25AM Page 2 of6 Analysis Report for B1-010-001 (0.5" - 1.0") TOP B1-010-001-CJFC-C09-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) starl end Centroid Area Uncertainty Counts (keV) F 1 238 . 02 473 - 481 476 . 52 3 . 58E+Ol 17 . 09 8 . 06E+Ol 1. 65 F 2 352 . 16 698 - 708 704 . 75 3.68E+Ol 14.37 3 . 48E+Ol 1. 43 F 3 1460 . 69 2916 - 2927 2921 . 50 4 . 03E+Ol 13 . 08 2 .7 1E+OO 2 .4 2 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCEPEAK/BKG.SUBTRACT Peak Analysis Performed on : 3/22/2019 11 :04:1 5AM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio
- Background Peak Energy Original Orig. Area Ambient Backgr. Co"ected Corrected No_ (keV) Area Uncertainty Background Uncerl. Area Uncert.
F 1 238 .02 3.SBE+O l 17 .0 9 3 . 58E+Ol 1 . 71E +O l F 2 352.16 3.68E+Ol 14 . 37 l . 91E+Ol 7 . 75E+OO l . 77E+Ol l . 63E+Ol F 3 1460 . 69 4 . 03E+Ol 13 . 08 1. 43E+Ol 3 . 77E+OO 2 .6 0E+Ol 1.36E+Ol M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 37
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 11 :04:25AM Page 3 of6 Analysis Report for B1-010-001 (0.5" - 1.0") TOP B1-010-001-CJFC-C09-CV Nuclide Name Id Confidence Energy (keV) Yield(3/4) Activity Activity (pCVgrams) Uncertainty K- 40 0 . 999 1 460 . 75
- 10 . 67 6 . 65E + OO 3.SOE+OO PB- 212 0 . 486 77 . 11 17 . 50 238 . 63
- 44 . 60 3 . 58E - 01 1 . 72E- Ol
* = Energy line found in the spectrum.
~ = Manually added nuclide.
? = Manually edited nudide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak locate Performed on : 3/22/2019 11 :04:15AM Peak l ocate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide F 2 352 . 16 l.96549E - 02 46.13 To l. PB- 214 M = First peak in a multlplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) K- 40 0 . 999 6.65E+0O 3 . S0E+O0 10/26/2020 Page 38
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 11 :04:25AM Page 4 of6 Analysis Report for 81-010-001 (0.5" - 1.0") TOP 81 -010-001-CJFC-C09-CV Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence (pCi/grams) Uncertainty PB-212 0 . 486 3 . 58E -0 1 l. 72E- 01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used In Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 39
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 11 :ll4:25AM Page 5 of6 Analysis Report for B1-010-001 (0.5" -1 .0") TOP B1-010-001 ~CJFC-C09-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 11:04:15AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 352 . 16 l . 965 4 9E - 02 46 . 13 Tol. PB - 214 M = First peak In a multiplet reg ion m = Other peak in a multiplet region F "' Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dalryland_ NPP\Llbrary\HOTLABAIRNLB Nuclide Energy Yield(%) Activity NuclldeMDA LlneMDA Name (pCl/grams) (pCl/grams) (pCl/grams) {keV)
+ K-40 1460.75
- 10 . 67 6 . 65E+00 4.56E+00 4 . 56E+00
+ AR-41 1293 . 64 99 .1 6 - l . 95E+02 3 . 56E+02 3 . 56E+02
+ CO-60 1173.22 100 . 00 4.76E- 0l 5. 03E- 01 5 . 86E - 01 1332 . 49 100 . 00 l . 14E- 01 5 . 03E - 01
+ KR- 85 513 . 99 0 . 43 6 . 24E+0l 8 . 0BE+0l 8 . 08E+0l
+ Y- 88 898 . 04 93.70 -1 . 25£- 01 4 . l0E-0 1 4 . l0E - 01 1836 . 06 99 . 20 -2 . 14E-01 4 . l0E - 01
+ I - 131 284 . 30 6 . 06 2 . 61E+O0 2.98E-01 3.94E+00 364 . 48 Bl. 20 6 . 89E- 02 2 . 98E-01 636 . 97 7 . 27 2 . 03E- 01 4 . 34E+00
+ CS - 134 604 . 70 97 . 60 2 . 93E- 01 3.78E-01 3 . 98E-01 795 . 84 85 . 40 3 . 93E-02 3 . 78E - 0l
+ CS-137 661. 65 85 . 12 3 . S0E-01 4 . SlE-01 ii" 4 . SlE-01
+ CE- 1 4 4 80.12 1. 36 9 . 08E +00 1.70E+00 1.93E+0 l 133.51 11.09 - 4.53E - 01 l . 70E+00
+ EU- 152 121 . 78 28 . 43 - 5 . 30E - 02 7 . 06E-01 7 . 06E-01 344 . 28 26 . 60 3 . 8 4 E-0l 9.86E-0 1 10/26/2020 Page 40
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 11 :04:25AM Page 6 of6 Analysis Report for 81-010-001 (0.5"-1 .0") TOP B1-01Q.001-GJFC-C09-CV Nuclide Energy Ylefd(3/4) Activity NuclldeMDA UneMDA Name (pCVgrams) (pCilgrams) (pCilgrams) (keV) EU-152 1408 . 08
+ EU - 154 123 . 07 20 . 75 40 . 40 5 . 45E-02 6.0 0E - 02
- 7. 0 6E-01
- 4. 92E - 01 1 1. 91E+OO 4 . 92E-01 723 . 30 1 9 . 70 - 7 . 87E - 01 l . 56E + OO 1274 . 51 34 . 40 2 . 27E-01 l.36E+OO
+ EU-1 55 86 . 54 32 . 80 3 . 04E - 01 6 . 81E - 01 6 . 8 1 E-0 1 105 . 31 21. 80 7 . 38 E- 01 8 . 99E-01
+ BI - 21 4 609 . 31 46 . 30 4 . 08 E- 01 8 . 18E-01 8 . 18E - 01 1120 . 29 1 5 . 10 1. 29E+OO 3 . 22E + OO 1238 . 11 5 . 94 3 . 99E+OO 8 . 14E+OO 1377 . 67 4 . 11 2 . 71E+OO 9 . 97E+OO 1407 . 98 2 .4 8 4. 56E-01 l . 60 E+Ol 1 5 09 .1 9 2 . 19 2 . 5 7E +OO l . 19E+Ol 1764 .4 9 15 . 80 -l. 65 E+OO 2 . 70E+OO
+ PB-214 77 .11 1 0 . 70 -l. 66 E- 02 8 . 0lE - 01 2 . 62 E+OO 295.21 19 . 20 - l . 76E - Ol 1 . 21E+OO 351. 92 37 . 20 5 . 35E - Ol 8 . 0lE - 01
+ PA - 228 89 . 95 22 . 00 - 2 . 12 E- 01 9 . 75£- 0 1 l . 64 E+OO 93 . 35 35 . 00 - 6 . 19E-01 9 . 75E - Ol 105 . 00 16 . 30 9 . 88E- 01 2 . 09E+OO 129.22 2 . 97 5 . 72E + OO l .1 6E+Ol 338 . 32 5 . 30 7 . 52E+ OO 8 . 82E + OO 463 . 00 13 . 80 l . 38E + OO 3 . 70E+OO 911 . 23 16 . 70 2 . 12E + OO 4 . 72E+OO
+ AM-2 41 59 . 54 36 . 30 l . 20E - 01 l. 09E+ OO 1. 09E+OO
+ CM- 2 4 3 103 . 76 23 . 00 3 . 5 3E- 01 8 . SlE- 0 1 8 . SlE - 01 22 8. 1 8 1 0. 60 9.65 E- 01 2 . 03E +OO 277 . 60 14 . 00 - l . 94E - 01 1 . 71E +OO
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction 7 = CAUTION : MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 41
LAC LTP - Final Status Survey Package - 3/26/2019 3122/2019 11 :20:00AM Page J of6 pex-Gamma Analysis Report for B1-010-001 (0.5"
- 1.0") BOTTOM B1-010-001-CJ FC-C09-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-01,0-001 (0.5" - 1.0") BOTTOM Sample Description : B1-010-001-CJFC-C09- CV Sample Type : Planchet Unit Sample Point Sample Size 1.464E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 5:06:00PM Acquisition Started : 3/22/2019 11:0442AM Procedure : Ptanchet on OET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds Real Time : 902. 7 seconds Dead Time : 0.30 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 1D0 - 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibratlon Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/812014 Efficiency Calibration Description Sample Number : 5953 PEAK ANALYSIS REPORT Peak Analysis Performed on : 3/22/2019 11 :19:51AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 42
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 11:20:00AM Page 2of6 Analysis Report for 81-010-001 (0.5"-1.0") BOTTOM 81 -010-001-CJ FC-C09-CV Peak Energy ROI ROI Peak Net Peale Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 .3 0 472 - 481 477 . 08 2 . 65E+O l 15 . 64 8 . 37E+Ol 1. 43 F 2 352 . 04 699 - 710 704 .5 1 3 . 61E+Ol 14.46 4 . 54E+Ol 1. 47 F 3 582 .8 5 1162 - 1171 1166 . 03 1.83E+Ol 9.98 1 . 63E+Ol 1. 36 F 4 1461 . 03 2916 - 2928 2922 . 17 4 . SlE+Ol 14.44 l . 31E+Ol 2.15 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I BKG. SUBTRACT Peak Analysis Performed on : 3/22/2019 11:19:51 AM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original .. Peak Ratio - Background Peak Energy or;g;nal Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 23 8. 30 2 . 65E +Ol 15 .64 2 . 65E+Ol 1.56E+Ol F 2 352 . 04 3 . 61E+Ol 14 .46 1 . 91E+Ol 7 . 75E+OO 1 .70E+Ol 1 .64 E+Ol F 3 582.85 1.83E+Ol 9 . 98 1 . 83E+Ol 9.98E+OO F 4 1461.03 4.SlE+Ol 14.44 1.4 3E+Ol 3 .77 E+OO 3 .08 E+O l 1 .49E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Oalryland_NPP\Library\HOTLABAIR.NL8 IDENTIFIED NUCLIDES 10/26/2020 Page 43
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 11 :l0:00AM Page 3 of 6 Analysis Report for B1-010-001 (0.5" - 1.0") BOTTOM B 1-010-001 -CJ FC-C09-CV Nuclide Name Id Confidence Energy (keV) Yield(3/4) Activity Activity (pCVgrams) Uncertainty K-4 0 0 . 988 14 6 0 . 75
- 10.67 7 . 89E+O0 3 . 84E+00 PB-21 2 0 . 515 77 . 11 17. 50 238 . 63
- 44. 60 2 . 66E- 01 1 . 57E -01
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 11 :19:51AM Peak Locate From Channel : 100 Peak Locale To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (kaV) Uncertainty Type Nuclide F 2 352.04 1 .8 8627£ - 02 48 . 31 Tol. PB- 21 4 F 3 582 . 85 2 . 03098E- 02 27 . 31 ...-:--: I ( .... ZLJt M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT 10/26/2020 Page 44
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 11:20:00AM Page4 of6 Analysis Report for B1-010-001 (0.5' -1 .0") BOTTOM B1-010-001-CJFC-C09-CV Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCUgrams) K-40 0 .9 88 7 . 89E+00 3 . 84E+OO PB-212 0.515 2 . 66E - 01 l . 57E-01
? = nuclide is part of an undetermined solution X = nuclide tejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 45
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 11 ::l0:00AM Page 5 of6 Analysis Report for 81-010-001 (0.5" - 1.0") BOTTOM B1-010-001-CJFC-C09-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 11:19:51AM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 352 . 04 l . 88627E -0 2 48 . 31 Tol. PB-214 F 3 582.85 2.03098E -0 2 27.31 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield(%) Activity Nuc/ideMDA LlneMDA Name (pCUgrams) (pCUgrams} (pCl/grams) (keV)
+ K-40 1460 . 75 "It
- 10. 67 7.89E+00 5.69E+00 5.69E+00
+ AR-41 1293.64 99.16 -1. 36E+02 2 . 83E+02 2.83E+02
+ CO-60 1173.22 100.00 3.SSE-01 5. 21E-0l 5. 21E-01 1332.49 100.00 4.22E-01 6.14E-01
+ KR-85 513 . 99 0 .43 4.06E+0l 8 . 30E+0l 8 . 30E+0l
+ Y-88 898.04 93.70 2.12E-0l 3.79E- 01 3.79E-0l 1836.06 99.20 l.37E-01 4.l0E-01
+ I-131 284.30 6.06 0.00E+00 2 . 83E-0l 3.99E+00 364 .4 8 81.20 -2 . 00E-01 2.83£-01 636.97 7 .27 2.39E+00 4.99E+00
+ CS-134 604 . 70 97 . 60 2.69E-01 3.90E-01 3.90E-01 795.84 85 . 40 -5. 14E-02 3 . 98E - 01 CS-137 661. 65 85.12 6.98E- 03 4. 63E - 01 ,/ 4.63£-01 CE - 144 80.12 1. 36 -8.78E-0 l l .79E+00 l . 92E+0l 133 . 51 11 . 09 -4. llE-02 1.79E+00 10/26/2020 Page 46
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 11:20 :00AM Page 6 of6 Analysis Report for B1 -010-001 (0.5" - 1.0") BOTTOM B1 -010-001-CJFC-C09*CV Nuclide Energy Yield(%) Activity NuclldeMDA LineMDA Name (pCilgrams) (pCi/grams) (pCi/grams) (keV)
+ EU-152 121.78 28 . 43 -2 .5 7E - 01 6 . 87E-01 / 6 . 87E-01 344 . 28 26 . 60 3 . 92 E- 0 1 9.45E-01 1408 . 08 20 . 75 2 . 75E-Ol / 1. 79E+OO
+ EU-154 123 . 07 40 . 40 -3 . 70E- 01 4 . BOE- 01 4. 80E-01 723 . 30 19 . 70 - l . 57E-0 1 l.7 1E+OO 1274 . 51 34 . 40 1. SSE-01 l.26E+OO
+ EU - 155 86 . 54 32 . 80 - 3 . 23E- 0 1 6 . 59E - 0 1 6 .5 9E-01 105 . 31 21. 80 - 6 . lOE - 02 9 . 19E-01
+ BI-214 609 . 31 4 6 . 30 1. 78E-0 1 8.18E-01 8 . lBE-01 1120 . 29 15 . 10 1.09E+OO 3 . 07E+OO 1238 .11 5 . 94 5 . 60E+OO l . OOE+Ol 1 377 . 67 4 . 11 6 . 28E+OO l.09 E+Ol 1 407 . 98 2 . 48 2 . 30E+OO 1.SOE+Ol 1509.19 2.19 1 . 29E+Ol 2 . 24E+Ol 1764 . 49 15.80 l . 22E+OO 3 . 73E +OO
+ PB- 2 1 4 77 . 11 10 . 70 2 . 89E+OO 8.56E-Ol 2 . 66E+OO 295 . 21 19 . 20 1 . 71 E-01 l.36E+OO 351.92 37 . 20 9.66E-01 8 . 56E-01
+ PA-228 89 . 95 22 . 00 1.13E+OO 1 . 0 3E+OO 1. 73E+OO 93 . 35 35.00 -3 . 72E -01 1 .03E +OO 105.00 16 . 30 6 . 43E-0 1 2.19E+OO 129 . 22 2 . 97 l.68 E+OO l.19E+Ol 338 . 32 5 . 30 - 2 . 84E+OO 8.48E+OO 463 . 00 13. 80 - 4. 58E-Ol 3 . 77E+OO 911 . 23 16.70 1. 51E+O O 4 .0lE+OO
+ AM-241 59 . 54 36 . 30 - 2 . 0SE - 01 1 . llE+OO 1. llE+OO
+ CM-243 103 . 76 23.00 l . 06E - 01 8 . 75E - 01 8 . 75E-01 228 . 18 10 . 60 -6 . 69E-01 l.89E+OO 277 . 60 14.00 3 . 77E - 02 l . 69E+OO
+ Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 47
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 1 1:15PM Page I of6
~pex-Gamma Analysis Report for B1-010-001 (0" - 0.5"} TOP 81-010-001-CJFC-C10-CV GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001 (O" - 0.5") TOP Sample Description : 81 -010-001-CJFC-C10-CV Sample Type : Ptanchet Unit Sample Point Sample Slz.e 1.374E+02 grams Facility : Dalryland_NPP Sample Taken On : 3/21/2019 2:50:00PM Acquisition Started : 3/21/2019 5:05:59PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLA8 Geometry : Planchet on DET Live Time : 900.0 seconds Real Time : 902.8 seconds Dead Time : 0.31 %
Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100 -4096 Peak Area Range (in channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number Peak Analysis Performed on : 3/21/2019 5:21 :06PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 48
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 5:21:15PM Page2 of6 Analysis Report for B1-010-001 (O"
- 0.5") TOP B1-010-001-CJFC-C10-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV} start end Centroid Area Uncertainty Counts (keV)
F 1 238.58 474 - 481 477 . 64 2 . 30E+Ol 16 . 67 9 . 52E+Ol 1.15 F 2 352 . 21 699 - 710 704 . 84 3 . 78E+Ol 15 . 03 5 . 31E+Ol 1. 54 F 3 609 . 05 1213 - 1224 1218.43 2.BBE+Ol 12 . 05 1. 52£+0 1 1. 78 F 4 1461 .36 2918 - 2929 2922.84 5 . 61E+Ol 15 . 22 2 . 44E+OO 1.85 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I 8KG. SUBTRACT Peak Analysis Performed on : 3/21/2019 5:21 :06PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Rool\Dairyland_NPP\Data\0000001363. CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV} Area Uncertainty Background Uncerl. Area Uncert.
F 1 238 . 58 2 . 30E+Ol 16.67 2 .30E+O l l .67E+O l F 2 352 . 21 3 . 78E+Ol 15 . 03 l.91E+Ol 7.75E+OO 1 .87E+01 1 . 69E+01 F 3 609.05 2.88E+Ol 12 . 05 9 . 69E+OO 5.77£+00 1 .9 1E+Ol 1.34E+Ol F 4 1461.36 5.61E+Ol 15 . 22 1.43E+Ol 3 . 77E+OO 4.19E+Ol l.57E+Ol M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nudide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 49
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 5:Z1:15PM Page 3 of6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CJFC-C10-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCilgrams) Uncertainty K-40 0 . 942 146 0. 75
- 10 . 67 1 . 14E+Ol 4 . 32E +OO PB-2 12 0 .52 7 77 . 11 1 7. 50 238 . 63
- 44. 60 2 . 46E-01 1.7 9E -0 1 BI - 214 0 . 359 609 . 31
- 4 6 . 30 5 . 07E-Ol 3 . 55E - 01 112 0. 29 15 . 10 1238 . 11 5 . 94 1 377. 67 4 . 11 14 07. 98 2 . 48 1509 . 19 2 . 19 176 4. 49 15 . 80
* = Energy Hne found In the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Perfonned on : 3/21/2019 5:21 :06PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak Size (CPS) Peak CPS(3/4) Peak Tolerance Peak No. Energy {keV) Uncertainty Type Nuclide F 2 352 . 2 1 2 . 07224£-02 45 . 32 Tol. PB-21 4 M = First peak in a multiplet region m = Other peak in a multiplet region F "' Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT 10/26/2020 Page 50
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 5:21 :1 5PM Page4of6 Analysis Report for 81-010-001 (0" - 0.5") TOP B1-010-001-CJFC-C10-CV Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-4 0 0.942 l . 1 4E+0l 4 . 32E+00 PB- 212 0 .52 7 2.46E-01 l . 79E-01 BI - 214 0 . 35 9 5.07E - 01 3.SSE- 01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.O00sigma 10/26/2020 Page 51
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 5:21 :15PM Page5 of6 Analysis Report for B1-010-001 (0" - 0.5") TOP B1-010-001 -CJFC-C10-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21/2019 5:21 :06PM Peak Locate From Channel : 100 Peek Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 352.21 2. 07224E-02 45 . 32 ToL PB-214 M = First peak in a multiplet region m =Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield(3/4) Activity NuclideMDA LineMDA Name (pCi/grams) (pCflgrams) (pCilgrams) (keV)
+ K-40 1460 . 75
- 10.67 l . 14E+0l 4 . 81E+00 4.81E+00
+ AR-41 1293.64 99.16 6.97E-0l 1. 38E+00 l . 38E+00
+ CO-60 1173 . 22 100.00 8.BSE-02 5. 30E-0l / 5 . 30E-01 1332.49 100.00 -3.04E-01 5.98E - 01
+ KR- 85 513. 99 0. 43 l. 73E+0l 8.77E+0l 8.77E+0l
+ Y-88 898.04 93 . 70 -5.34E-02 3 . 90E-01 4.46E-01 1836 . 06 99 . 20 l.09E-01 3.90E-01
+ I-131 284 . 30 6 . 06 - 4.llE+00 3 . 13E-01 3 . 71E+00 364 . 48 81. 20 -5.91E-0 2 3 .13E - 0l 636.97 7 . 27 4.81E+00 5.53E+00
+ CS-134 604 . 70 97.60 - 5 . 28E-02 4.32E-01 4.32E - 0l 795.84 85.40 l . 62E-01 5 . lSE-01
+ CS-137 661. 65 85.12 4.40E-0l 5. 27E-01'"./ 5.27E-0l
+ CE-144 80.12 1. 36 5.lSE+00 1. 88E+00 2.03E+0l 133 . 51 11 . 09 3.40E-01 1 .88E+ 00
+ EU-152 121. 78 28.43 l.41E-01 7 . 03£-01 7 .03E-01 344 . 28 26 . 60 -2.97E-O l l.08E+00 10/26/2020 Page 52
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 5:21:1 5PM Page 6 of 6 Analysis Report for B1 -010-001 (0" - 0.5") TOP B1-010-001-CJFC-C10-CV Nuclide Energy Yield(%) Activity NuclideMDA LlneMDA Name (pCl/grams) (pCilgrams) (pCUgrams) (keV) EU- 152 1 408 . 08 20. 7 5 4 . 06E- Ol 7 . 03E-01 1. 4 6E +OO
+ EU- 1 54 123 . 07 40.40 1. 38E-0 1 5 . 03E- 01 / 5 . 03£- 0 1 7 23 . 30 19 . 70 -5 . 0lE- 01 l . 67E+OO 1274 . 51 34.40 - 6.93E - 01 l . 40 E+OO
+ EU-155 86 . 54 32.80 -2.00E - 01 7 . 39E-01 7 . 39£- 0 1 105 . 31 21. 80 7.27£-02 9 . 82E-01
+ BI - 214 609 . 31
- 46 . 30 5.07E- 01 6 . 0SE-01 6 . 0SE - 01 1120 . 29 1 5 .10 1 . 75E+OO 4 . 21E+OO 1238_11 5 . 94 l.13 E+OO 9 . 16E+OO 1377 . 67 4 .11 -7.39E+OO l.OlE+Ol 1 407-98 2 . 48 3.40E+OO 1.22E+O l 1 509 . 19 2 .1 9 6.85E+OO l . 80E+O l 1764 . 49 1 5.80 l.75E+O O 3 . 48 E+OO
+ PB- 214 77 .11 10.70 2 . 68E +OO 8 . 95E-0 1 2.78E+OO 295.21 1 9.20 4.42E-01 1 . 48 E+OO 351 . 92 37.20 4 .66E-01 8 . 95E-01
+ PA - 228 89.95 22.00 3.06E- 01 7. lOE - 01 l. l 7E+OO 93 . 35 35 . 00 7 . 28 E- 02 7.lOE - 01 10 5.0 0 16 . 30 1. 99 E- 01 1 . 42E+OO 129 . 22 2 . 97 3.03E+OO 7 . 70E+OO 338 . 32 5 . 30 -4 . 84 E-0 1 5.85E+OO 463 . 00 13 . 80 9 . 33E-02 2 . 52E+O O 911 . 23 16 . 70 l . BBE+0.0 3 . 30E +OO
+ AM- 24 1 59 . 54 36 . 30 - 1. 0 lE:+OO 1.19E+OO l.1 9E+OO
+ CM-243 103.76 23 . 00 -9.0BE -0 2 9.27E-01 9 . 27E - 0 1 228 .1 8 10 . 60 -8 . 22E - 01 2 . 22 E+ OO 277 . 60 14 . 00 - 8 . 95E- 0 1 l . 65E +OO
+ " Nuclide ldentified during the nudide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 53
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 :> ..,7:02PM Page I of6
~pex-Gamma Analysis Report for B1-010-001 (0" -0.5") BOTTOM 81---010-001-CJFC-C10-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 (O"
- 0.5") BOTTOM Sample Description : B1-010-001-CJFC-C10-CV Sample Type : Planchet Unit Sample Point Sample Size 1.37 4E:+02 grams Facility : Dairyland_NPP Sample Taken On : 3/21/2019 2:50:00PM Acquisition Started : 3/21/2019 5:21 :46PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live nme : 900.0 seconds Real lime : 902.9 seconds Dead Time : 0.32 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description
- /0-dtpJJ tJ:.!r/c;,~~'I' Sample Number
, s.. , ~L PEAK ANAL ySJSRPO Peak Analysis Performed on : 3/21/2019 5:36:53PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 54
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 5:37:02PM Page 2 of6 Analysis Report for 81-010-001 (O" - 0.5") BOTTOM 81-010-001-CJFC-C10-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 352 .4 2 699 - 708 705 . 26 3 . 71 E+0l 14 . 58 4 . 94 E+0l 0 . 91 F 2 14 61. 38 2917 - 2 930 2 922 .8 7 6 . 31 E+0l 1 6. 14 2 . 94E+00 2 . 35 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I 8KG. SUBTRACT Peak Analysis Performed on : 3121/2019 5:36:53PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CN F Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 352 . 42 3 . 71E+0l 14 . 5 8 l . 91E+0l 7 . 75E+00 1 . 80E+ 0l l . 65E+0l F 2 1 4 61. 3 8 6 . 31E+0l 16 .14 l . 43E+0l 3 . 77E+00 4 . 88E+ 0l 1 . 66E+0l M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Llbrary\HOTLABAIR.NLB IDENTIFIED NUCLIDES Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCi/grams) Uncertainty 10/26/2020 Page 1
LAC LTP - Final Status Survey Package - 3/26/2019 312112019 s:ar:02PM Page 3 of6 Analysis Report for B1-010-001 (O"
- 0.5") BOTTOM B1-010-001-CJFC-C10-CV Nuclide Name Id Confidence Energy (keV) Yield(3/4) Activity Activity (pCVgrams) Uncertainty K- 40 0 . 939 14 60 . 75
- 10 . 67 1 . 33E+Ol 4 . 58 E+ OO
* = Energy line found in the spectrum.
- = Manually added nudide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/21 /2019 5:36:53PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak Size (CPS) Peak No. Energy {keV) Uncertainty Type Nuclide F l 352 . 42 l . 99810E-02 45 . 90 Tol. PB- 214 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams) K- 40 0 . 939 1 . 33E+Ol 4. 58Et00 10/26/2020 Page 2
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 5:37:02PM Page 4 of6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B1-010-001-CJFC-C10-CV
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 3
LAC LTP - Final Status Survey Package - 3/26/2019 I 3/21/2019 5:37:02PM Page 5 of6 Analysis Report for 81-010-001 (O" - 0.5") BOTTOM 81-010-001-CJFC-C10-CV UNIDENTIFIED PEAKS Peak locate Perfonned on : 3121 /2019 5:36:53PM Peak locate From Channel : 100 Peak locate To Channel : 4096 Peak CPS(3/4) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 352 .4 2 l.99810E-02 45.90 Tol. PB-214 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\L.ibrary\HOTLA8AIR.Nl8 Nuclide Energy Yield(%) Activity NuclldeMDA Line MDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV)
+ K-40 1460. 75
- 10 .6 7 1 . 33E+0l 4 . 90E+00 4 .9 0E+00
+ AR-41 1293 . 64 99 . 16 6 . 47E-0 1 l.68E+00 l . 68E+00
+ CO-60 1173.22 100 . 00 3 . 22E-0 1 4. 00E-01 S . SSE-01 1332 .49 100 . 00 -7.33E-02 4 . 00E-01
+ KR-85 513 . 99 0 . 43 6 . 89E+0l 8 . 69E+0l 8 . 69E+0l
+ Y-88 898 . 04 93 . 70 -l.95E-0l 3 . 90E-01 4 . 66E- 01 1836 . 06 99 . 20 1.09E-0 1 3 . 90E-01
+ I-131 284 . 30 6 . 06 -2.07E+00 3 . 31E-01 3 . 79E+00 364 . 48 81 . 20 -1.0lE-01 3 . 31E-01 636 . 97 7 . 27 3 . 57E-01 4 . 88E+00
+ CS-134 604 . 70 97 . 60 3 . 29E-01 4 . 53E-01 4.53E-01 795 . 84 85 . 40 1. l0E-0 1 4.63E-01
+ CS - 137 661. 65 85 . 12 3.39E-01 5 . 1 6E - 01 / 5 . 16E-01
+ CE-144 80 . 12 1.36 2 . 88E-0l 1 . 86E+00 2 . 17E+0l 133 . 51 11.09 1 . 07E-01 l . 86E+00
+ EU-152 121 . 78 28 . 43 -2.50E-01 6 . 97E-01 6 . 97E- 01 344.28 26 . 60 -S. 04E- 01 l.07E+00 10/26/2020 Page 4
LAC LTP - Final Status Survey Package - 3/26/2019 3/21/2019 5:37:02PM Page 6 of6 Analysis Report for 81-010-001 (O" - 0.5") BOTTOM B1-010-001-CJFC-C10-CV Nuclide Energy Yield(3/4) Activity NuclldeMDA LlneMDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV) EU-152 1408 . 08 20 . 75 l.40E-01 6.97E-01 2 . 03E+00
+ EU-154 123 . 07 40 . 40 -4.18E-01 4 . 86E- Ol l 4 . 86E-01 723 . 30 19.70 -3.76E-01 1 . 89E+OO 1274 . 51 34 . 40 - 5 . 37E-01 1 . 58E+OO
+ EU - 155 86 . 54 32 .8 0 -l.2 8E- 01 7.84E-01 7 . 84E - 01 105 . 31 21. 80 2 . 96E - 01 1 . 0lE+OO
+ BI -2 14 609 . 31 46.30 3.00E-01 9 .4 5E-0 1 9 .4 5E-01 1120 . 29 15 . 10 1. 86E+OO 4 . 08E+OO 1238 . 11 5 . 94 5 . 54E+OO 1 . 0SE+Ol 1377 . 67 4 . 11 2 . 82E+OO 1 . 35E+Ol 1407 . 98 2 .4 8 1 .17 E+OO l . 70E+Ol 1509 . 19 2 . 19 -1. 83E+OO l.47E+Ol 1764 . 49 15.80 2 .19E+OO 3 . 82E+OO
+ PB-214 77 . 11 10 . 70 3 .62E +OO 9 . 55E-01 2.99E+OO 295 . 21 19 . 20 7.17E- 01 1. 59E+OO 351 . 92 37 . 20 8.63E-01 9 . SSE-01
+ PA-228 89 . 95 22 . 00 l.20E+OO 7 . 18E-01 l . 2SE+OO 93 . 35 35 . 00 -9.21E - 02 7.18E-01 105 .00 16 . 30 4.08E-01 1 . 46E+OO 129 . 22 2 . 97 1 . 24E+OO 7 . 57E+OO 338 . 32 5 . 30 4.0SE - 01 5 . 79E+OO 463 . 00 13 . 80 l .30E +OO 2 . 57E+OO 911 . 23 16.70 6.90E-01 3 .48 E+OO
+ AM-241 59 . 54 36 . 30 1.05E+00 1. 28E+OO l . 28E+OO
+ CM-243 103 . 76 23.00 1 .42E- 01 9.45E-01 9.45E-01 228 . 18 10 . 60 -3.70E-01 2 .1 4E+OO 277 . 60 14 . 00 -2.16£-01 1 . 60E+OO
+ = Nuclide identified during the nuclide identification
* =Energy line found in the spectrum
> = MOA value not calculated
@ = Half-life too short to be able to perfomn the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 5
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1 *"1 :35PM Page I of6
~~~~pex-Gamma Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CJFC-C11-CV GAMMA SPECTRUM ANALYSIS Sample Identification : B1-010-001 (O" - 0.5") TOP Sample Description : 81-010-001-CJFC-C11-CV Sample Type : Planchet Unit Sample Point Sample Size 1.541E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/22/2019 12:40:00PM Acquisition Started : 3/22/2019 1:06:19PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds Real Time : 902.7 seconds Dead Time : 0.30 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100- 4096 Peak Area Range (in channels) : 100- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number PEAK ANALYSIS POR Peak Analysis Performed on : 3/22/2019 1:21 :26PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 6
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:21 :35PM Page 2 of6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1--010-001-CJFC-C11-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 6 61. 74 1318 - 13 31 13 2 3 . 79 6 .9 4E+02 5 4.4 8 3 . 00E+Ol 1. 8 8 F 2 14 61. 13 2915 - 2929 2922 . 38 6 . 78 E+Ol 17 . 28 7 . 50E+OO 3 .0 1 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I BKG. SUBTRACT Peak Analysis Performed on : 3/22/2019 1:21 :26PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 661 . 74 6.94E+02 5 4. 48 1 . 72E+Ol 7. 27E+ OO 6.76 E+02 5. 50E+O l F 2 1461 . 13 6.78E+Ol 17 . 28 l . 43E+Ol 3 . 7 7E+ OO 5 . 35E+Ol l . 77E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\library\HOTLABAIR.NLB IDENTIFIED NUCLIDES Nuclide Name Id Confidence Energy {keV} Yield(%) Activity Activity (pCilgrams) Uncertainty 10/26/2020 Page 7
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:21 :35PM Page 3 of6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001-CJFC-C11-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCVgrams) Uncertainty K- 40 0 . 977 1460 . 75
- 10 . 67 1 . 30E +Ol 4. 36E+OO CS - 137 0 . 999 661. 65
- 85 . 12 9 . 47E +OO 9 . 26E - 01
* = Energy llne found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 1:21 :26PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000slgma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCVgrams) K- 40 0 . 977 1 . 30E+Ol 4 . 36E+OO CS - 137 0 . 999 9 . 47 E+OO "' 9 . 26E - Ol 10/26/2020 Page 8
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:21 :35PM Page4 of6 Analysis Report for 81-010-001 (O" - 0.5") TOP B1-010-001-CJFC-C11-CV
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 9
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:21 :35PM Page 5 of 6 Analysis Report for B1-010-001 (O" - 0.5") TOP B1-010-001 -CJFC-C11-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 1:21 :26PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Llbrary\HOTLABAIR.NLB Nuclide Energy Yield(3/4) Activity Nucllde MDA LlneMDA Name (pCl/grams) (pCl/grams) (pCilgrams) (keV)
+ K- 40 1 4 60 . 75
- 10 . 67 l . 30E+0l 4 . 93E+ 00 4 . 93E+00
+ AR- 41 1293 . 64 99 . 16 2 . 56E - 01 6 . 32E-01 6 . 32E-01
+ CO- 60 1173 . 22 100 . 00 - 2 . 76E-01 3 . 57E - 01 4 . 49E-0l 1332 . 49 100 . 00 - l . 75E - 01 3 . 57E-01
+ KR-85 513 . 99 0 . 43 1. 25E+0l 1 . 00E+02 l . 00E+02
+ Y- 88 898 . 04 93 . 70 l . 46E- 01 3 . 79E-01 3 . 79E - 01 1 836 . 06 99 . 20 -3 . 72E - 02 4. 2 4E- 01
+ I - 131 284 . 30 6 . 06 - 1 . 0 4E+00 4 . 3 4E- 01 4 . 72 E+00 364 . 48 81 . 20 l.36E-01 4 . 34E - 0l 636 . 97 7 . 27 l . 93E+00 5 . 13E+00
+ CS - 134 604 . 70 97 . 60 9 . 68 E- 03 3 . 82E - 0l 3 . 82E- 01 795 . 8 4 85 .4 0 1. llE - 02 3.87E- 01
+ CS - 137 661.65
- 85 . 12 9 . 47E+00 4 . 20E - 0 1'1 4 . 20E- 0l
+ CE-144 80 . 12 1. 36 1 . 39E+0l 1 . 96E+0 0 2 . llE+0l 133 . 5 1 11.09 7 . l 0E-01 1. 96E +00
+ EU - 152 121 . 78 28 . 43 - 4 . 31E - 0l 7 . 8 5E- 01 7 . 85E- 01 3 44. 28 26 . 60 - l . 43E+00 l.29 E+00 1408 . 08 20 . 75 - 4 . 09 E- 0l 2 . 35E+00 10/26/2020 Page 10
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1;21:35PM Page 6 of6 Analysis Report for B1-010-001 (O" - 0.5"} TOP B1.010-001-CJFC-C11-CV Nuclide Energy Yield('1/4) Activity NuclldeMDA Line MDA Name (pCi/grams) (pCilgrams) (pCilgrams) (keV)
+ EU-154 123 . 07 40 . 40 -3.02E-01 5. 54E - 01 / 5 . 54E-01 723 . 30 19.70 - 2.BlE-01 l . 59E+OO 1274.51 34 . 40 -1 .2 6E+OO l . 45E+OO
+ EU - 155 86.54 32 . 80 1 . 55E-Ol 7.56E-01 7 . 56E-01 105. 31 21. 80 2 . 91E- 01 9.84E-01
+ BI-214 609 . 31 46 . 30 6 .4 9E-01 8.58E - 01 8.58E-Ol 1120.29 15 . 10 - 6 . 79E - Ol 3 . 06E+OO 1238 . 11 5 . 94 - 3 . 13E+OO 6 . 77E+OO 1377 .67 4 . 11 5.37E+OO 9.95E+OO 1 407.98 2 . 48 - 3 .4 2E+OO l . 97E+Ol 1509 .1 9 2 . 19 -2 . 03E-01 1. 72E+O l 1 764.49 15.80 7 . 82E-Ol 2.35E+OO
+ PB-214 77 .11 10 . 70 1.SOE - 01 9 . 83E -0 1 2 . 80E+OO 295 . 21 19 . 20 1 .1 2E+OO 1. 69E+OO 351. 92 37 . 20 6 . 84E-01 9 .8 3E-01
+ PA- 228 89.95 22 . 00 2 . 06E-01 6.69E - 01 l. lOE+OO 93.35 35 . 00 -l.02E-Ol 6.69E-01 105 . 00 16 . 30 2 . 72E - 01 l.34E+00 129 . 22 2 . 97 4 . 53E+ OO 7 . 59E +OO 338.32 5.30 4 . 65E+OO 6.70E+OO 463.00 13. 80 1.93E+OO 3 . 37E+OO 911. 23 16.70 1. SOE+OO 2 . 74£+00
+ AM-241 59 . 54 36 . 30 6 . 79E-02 1 . 22E+OO 1. 22E+OO
+ CM-243 103 . 76 23.00 - 1. 81E-01 9.36E -0 1 9 . 36E-01 228 .1 8 10.60 -2.23E+00 2.33E+OO 277 . 60 14.00 5 .59E -01 2.16E+OO
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Cunie MDA at 95% confidence level 10/26/2020 Page 11
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:a8:11PM Pagel of6
~pex-Gamma Analysis Report for 81-010-001 (0"
- 0.5") BOTTOM 81-010-001-CJFC-C11-CV GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001 (O"
- 0.5") BOTTOM Sample Description : B1-010-001-CJFC-C11-CV Sample Type : Planchet Unit Sample Point Sample Size 1.541E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/22/2019 12:40 :00PM Acqu isition Started : 3/22/2019 1:22:56PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds Real Time : 902.6 seconds Dead Time : 0.29 %
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100
- 4096 Peak Area Range (In channels) : 100
- 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number Peak Analysis Performed on : 3/22/2019 1 :38:02PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 12
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:38:11PM Page: 2 of6 Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B1-010-001 -CJFC-C11-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238.49 472 - 485 477.46 7 . 0SE+Ol 21. 88 1. 39E+02 1. 68 F 2 661.82 1318 - 1331 1323 . 96 3 . 04E+02 36 .0 8 4.60E+Ol 1. 83 F 3 1461.30 2915 - 2929 2922. 71 7.lOE+Ol 17 . 35 7. 44E+OO 2.37 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCEPEAKIBKG.SUBTR ACT Peak Analysis Performed on : 3/22/2019 1:38:02PM Ref. Peak Energy : 0.00 Reference Date Peak Ratlo : 0.00 Uncertainty : 0.00 Background FIie : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original* Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 238 . 49 7.0SE+Ol 21. 88 7 . 0SE+Ol 2.19E+Ol F 2 661.82 3.04E+02 36 . 08 1. 72E+Ol 7 . 27E+OO 2.87E+02 3.68E+O l F 3 1461.30 7.lOE+Ol 17 . 35 1.43E+Ol 3. 77E+OO 5.68E+Ol 1.78E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Ubrary\HOTLABAIR.NLB IDENTIFIED NUCLIDE$ 10/26/2020 Page 13
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:38:11 PM Page 3 ofo Analysis Report for B1-010-001 (O" - 0.5") BOTTOM B1-010-001-CJFC-C11-CV Nuclide Name Id Confidence Energy (keV) Yield{3/4) Activity Activity (pC#/grams) Uncertainty K- 40 0.953 1460.75
- 10 . 67 l.38E+0l 4 . 38E +00 CS-137 0.995 661.65
- 85 . 1 2 4.02E+O0 5.60E-01 PB-212 0.525 77 . 11 17 . 50 238 . 63
- 44 . 60 6. 72E- 01 2 . llE - 01
* = Energy line found in the spectrum .
- = Manually added nuclide.
? = Manually edited nuclide .
Energy Tolerance : 1.000 keV Nuclide confidence inde.x threshold = 0.. 30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Perlormed on : 3/2212019 1:38:02PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak Size (CPS) Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Uncertainty Type Nuclide All peaks were identified. M = First peak in a multiplet region m = Other peak in a multiplet reg ion F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide NucHde Wt mean Wtmean Comments Name Id Activity Activity Confidence Uncertainty (pCUgrams) K-40 0 .9 53 1. 38E+ 01 4 . 38E+OO 10/26/2020 Page 14
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:38:11PM Page4 of6 Analysis Report for B1-010-001 (O"
- 0.5") BOTTOM B1-010-001-CJFC-C11 *CV Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)
CS- 137 0.9 9 5 4.0 2E+O O 5. 60E-0 1 PB-2 1 2 0 . 52 5 6 .7 2E -0 1 2. llE -01
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 15
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:38:11PM Page 5 of 6 Analysis Report for 8 1-010-001 (0" - 0.S-) BOTTOM B1-010-001-CJFC-C11-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 1:38:02PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide All peaks were identified. M = First peak In a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP'1.ibrary\HOTLABAIR.NLB Nuclide Energy Yield{3/4) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCUgrams) (keV)
+ K-40 1460 . 75
- 10.67 1 . 38E+01 4.94E+OO 4 . 94E+OO
+ AR-41 1293 . 64 99.16 8.0lE-03 5.58E-01 5.SBE-01
+ C0-60 1173.22 100 . 00 2 . 26E-Ol 4. 93E-01 .I 4.95E-01 1332.49 100.00 -1.07E-01 4.93E-01
+ KR-85 513.99 0.43 7.0lE+Ol 9.13E+Ol 9 .13E+Ol
+ Y-88 898 . 04 93 . 70 2.0BE- 01 2.38E-01 4.49E-01 1836 . 06 99 . 20 -1.21E-Ol 2.38E-O l
+ I-131 284.30 6.06 9.33E-01 3.66E-01 4.52E+OO 364.48 8 1. 20 2.53E-02 3.66E-Ol 636.97 7.27 -8.71E-01 4 . 90E+OO
+ CS-134 604 . 70 97.60 -6.96E-02 3.68E-01 3.89E-0 1 795.84 85.40 6.93E-02 3.68£-01
+ CS-137 661.65
- 85.12 4.02E+OO 4. 87E-01 4.87E-01
+ CE-144 80 . 12 1. 36 1. OSE+Ol l.86E+OO l.99E+O l 133.51 11 . 09 1. 20E+OO l.86E+OO
+ EU-152 121.78 28 . 43 - 2.06E-01 7. 4 4E - 01 7. 44E - 01 344.28 26.60 -2.29E+OO 1.14E+OO 1408 . 08 20 . 75 3 . 62E-Ol 1 . 30 E+OO 10/26/2020 Page 16
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:38:11 PM Page 6 of6 Analysis Report for 8 1-01D-0D1 (0" - 0.5") BOTTOM B1-0 10-0D1-CJFC-C11-CV Nuclide Energy Yield(%) Activity Nuclide MDA LlneMDA Name (keV} (pCVgrams) (pCVgrams) (pCVgrams)
+ EU-154 123 . 07 40 .4 0 1. 52E-02 5 . 28E-Ol J 5.28E-01 723 . 30 19.70 l.17E+OO l.87E+OO 1274 . 51 34 . 40 4 . 14E- 0 1 l . 41E+OO
+ EU-1 55 86 . 54 32 . 80 l.91E-01 7 . 29E-01 7 . 29E-01 105 . 31 2 1. 80 - 3.40E- 02 9 . 23E - Ol
+ BI - 214 609 . 31 4 6 . 30 1.02E-01 8 . 50E-01 8 . SOE-01 11 20 . 29 15 . 10 -9 . 99E- 0 1 3 . 33E+OO 1238 . 11 5.94 3 . 82E+OO 8.77E + OO 1377 . 67 4 . 11 6 . 99E+OO 1. 27E+Ol 1407 . 98 2.48 3 . 03E+OO l . 09E+Ol 1509 . 19 2 . 19 1 . 30E+OO l. 47E +Ol 1764 . 49 15 . 80 4 . 77E- 01 3 . lOE+OO
+ PB - 214 77 . 11 10 . 70 - 1 . 0 4E+OO 9 . 13E-01 2 . 54E+OO 295 . 2 1 19 . 20 -4 . 04E-01 l.57E+OO 351 . 92 37 . 20 7.55E- 0 1 9 .13E- Ol
+ PA- 228 89 . 95 22 . 00 4 . 82E-02 6 . 48E-01 1.07E+OO 93 . 35 35.00 2 .. 48E-01 6 . 48E-Ol 105 . 00 16 . 30 2 . 98E - 01 1 . 28E+OO 129 . 22 2 . 97 3 . 8 4E+OO 7 . 46E+OO 338 . 32 5.30 - 3.42E+OO 5.82E+OO 463 . 00 13 . 80 2 . 99E+OO 2 . 89E+ OO 911.23 16 . 70 l. 7 9E+OO 2 . 8 5E+OO
+ AM- 241 59 . 54 36 . 30 7 . 18E- 02 l . 1 9E+00 l . 19E+OO
+ CM- 243 103 . 76 23 . 00 - 9 . 268-02 8 . 838-01 8 . 83E-01 228 . 18 10 . 60 2 . 7 0E-0 1 2.21 E+OO 277 . 60 14 . 00 - l.22E+OO 1 .88E+OO
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 17
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1 ::53:45PM Page I of6
~pex-Gamma Analysfs Report for 81*010-001 (0.5"
- 1.0") TOP B1-010-001-CJFC-C11-CV GAMMA SPECTRUM ANAL YS/S Sample Identification : 81-010-001 (0.5" - 1.0") TOP Sample Description : B1-010-001-CJFC-C11-CV Sample Type : Planchet Unit Sample Point Sample Size 1.686E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/22/2019 12:40:00PM Acqu isition Started : 3/22/2019 1:38:29PM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds Real Time : 902.7 seconds Dead Time : 0.30%
Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100 - 4096 Peak Area Range (in channels ) : 100- 4096 Identification Energy Tolerance : 1.000 keV
- 7/8/2014
~~
Energy Calibration Used Done On Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description 43/~z:./~
~~
Sample Number 5956 PEAK ANALvs!SWRT Peak Analysis Performed on : 3/22/2019 1:53:36PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 18
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:53:45PM Page 2 of6 Analysis Report for 81-010-001 (0.5"-1.0") TOP 81 -010-001-CJFC-C11-CV Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 . 71 473 - 485 477 . 90 3 . 93E+01 15.83 9 . 69E+Ol 1.11 F 2 351. 94 699 - 708 704 .3 1 3 . 67 E+Ol 15 . 20 5 .9 6E+Ol 1. 31 F 3 583 . 31 1160 - 1172 1166 . 97 2 . 56E+Ol 11 . 57 1 . 93E+Ol 1. 96 F 4 609.47 1213 - 1224 1219 . 28 2 . BOE+Ol 12 . 45 2 .l OE+Ol 2 . 00 F 5 727 . 07 1451 - 1458 1454 .4 3 l.llE+Ol 7 . 61 4.73E+OO 1.50 F 6 1 4 61. 1 4 29 1 5 - 2929 2922.39 6 . 69E+Ol 17 .10 7.2 1E+OO 2 . 70 M = First peak in a multiplet region m = Other peak In a multiplet region F "' Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCE PEAK I BKG. SUBTRACT Peak Analysis Performed on : 3/22/2019 1:53:36PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio* Background Peale Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 238.7 1 3 . 93E+O l 1 5.83 3.93E +Ol l.58E+O l F 2 351.94 3 . 67E+O l 15 . 20 1 . 91E+Ol 7.75E+ OO l.76E +Ol l.71E +Ol F 3 583 . 31 2 . 56E+Ol 11 . 57 2.56E+Ol l. 16E+Ol F 4 609 . 47 2 . BOE+Ol 12.45 9 . 69E+OO 5 . 77E+OO l.83E+Ol l.37E+Ol F 5 727 . 07 1 . llE+Ol 7.61 1 . llE+Ol 7 . 61E+00 F 6 146 1. 14 6 . 69E+Ol 17 . 10 l.43E+Ol 3 . 77E+OO 5.27E+Ol l. 75E+Ol M = First peak In a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma 10/26/2020 Page 19
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:53:45PM Page 3 of 6 Analysis Report for B 1-010-001 (0.5" - 1.0") TOP B1-010-001-CJFC-C11-CV NUCLIDE IDENTIFICATION REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pC/lgrams) Uncertainty K- 40 0 . 976 1 460 . 75
- 10 . 67 l . 17E+O l 3.94 E+OO BI-212 0 .610 727 . 17
- 11 . 8 0 l .1 3E+00 7 . 75E - 01 785 .4 2 2.00 1620 . 56 2 . 75 PB- 212 0 . 526 77 . 11 17 . 50 2 3 8 .63
- 4 4.60 3.43E-01 1.3 9E- 01 BI- 2 1 4 0 . 362 60 9 . 3 1
- 46 . 30 3 . 97E- 0 1 2 . 98 E- Ol 1120 . 29 15 . 10 1 238 . 11 5 . 94 1377 . 67 4 .11 14 0 7 . 98 2 . 48 1 5 0 9 .1 9 2 . 19 1764 .4 9 15 . 80
* = Energy line found in the spectrum.
* = Manually added nuclide.
? = Manually edited nuclide.
Energy Tolerance : 1.000 keV Nuclide confidence Index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Perfonned on : 3/22/2019 1:53:36PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuc.lide F 2 351.94 1 . 95700E - 02 48 . 42 PB-214 F 3 583 . 31 2 . 84293E - 02 22 . 61 10/26/2020 Page 20
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:53:4SPM Page4 of6 Analysis Report for 81-010-001 (0.5" - 1.0*1 TOP 81-010-001-CJFC-C11-CV M = First peak in a multiplet region m =Other peak in a multiplet region F = Fltted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nucllde Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) K-40 0.976 l. l 7E+Ol 3 . 94E+OO BI-212 0.610 l .13E +OO 7.75E-01 PB - 212 0.526 3 . 43E-Ol l.39E-01 BI-214 0.362 3.97E-01 2.98E-01
? = nuclide Is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 21
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:53:45PM Page 5 of6 Analysis Report for B1-010-001 (0.5 - 1.0") TOP 81-010-001-CJFC-C11-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 1:53:36PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 351 . 94 l.95700E-02 48.42 Tol. PB-214 F 3 583.31 2.84293E - 02 22.61 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB Nuclide Energy Yield{°/o) Activity NuclideMDA LineMDA Name (pCUgrams) (pCUgrams) (pCUgrams) (keV)
+ K-40 1460.75
- 10.67 l.17E+0l 4.48E+00 4.48E+00
+ AR-41 1293.64 99.16 1.39E-01 6.0BE-01 6 .0 BE-01
+ CO-60 1173.22 100.00 3.78E-02 3. 94E-0l 4.62E-0l 1332 .4 9 100.00 -4.09E-01 3.94E-01
+ KR- 85 513.99 0 . 43 1. 02E+02 8.50E+0l 8.50E+0l
+ Y- 88 898 . 04 93 . 70 9 . B0E-02 2 .74E-01 3 . 72E-01 18 36 .0 6 99.20 -l.44E-01 2.74E-01
+ I-131 284.30 6.06 6 . 29E- 01 2.64E-01 3.68E+00 364.48 81 . 20 - 4 . 4 8E-02 2.64E-01 636. 97 7 .27 1.19E+0O 4.49E+0O
+ CS-134 604.70 97 .6 0 - 3.61E- 02 3.45E-01 3.79E - 01 795.84 85.40 -2.65E-01 3.45£-01
+ CS-137 661.65 85.12 3.37E-01 4.43E-01/ 4.43E-01
+ CE-144 80. 12 1. 36 -4.30 E+00 1 .54 E+00 1 .70 E+0l 1 33.51 11 . 09 1.62E-01 1 . 54E+0O 10/26/2020 Page 22
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 1:53:45PM Page 6of6 Analysis Report for B1-010-001 (0.5" - 1.0") TOP B1-010-001-CJFC-C11 -CV Nuclide Energy Yield(3/4) Activity Nucflde MDA LlneMDA Name (pCi/grams) (pCilgrams) (pCVgrams) (keV)
+ EU- 15 2 121 . 78 2 8 .4 3 - 1 . 36E- 0 1 5 . 75£- 0 1 ./ 5. 7 5 E-01 344 . 28 26 . 60 2 . 62E -O l 9 . 45E-01 1408 . 08 20 . 75 -8 . 27E-02 l . 84E+OO
+ EU - 154 123 . 07 40 . 40 - 1 . 44E - 01 4. 04E- 01 / 4 . 04£- 01 723 . 30 19 . 70 -5 . 27£-0 1 l.68E+OO 127 4. 51 34 . 40 4 . 39E - 01 1. 33E+OO
+ EU-15 5 86 . 54 32 .8 0 1 . 70£ -0 1 6 . 24E- 01 6 . 24E-01 105 . 31 21. 80 - 1 . 45£-01 8 . 09£-0 1
+ BI - 21 4 609 . 31
- 46 . 30 3 . 97£- 01 5.32E- 01 5 . 32E-01 1120 . 29 1 5. 10 6 . 33£-01 3 . 33E+OO 1238.11 5 . 94 -3.07E - 01 7 . 07E + OO 1377 . 67 4 . 11 3 . 60E+OO 9 . 90E + OO 1407 . 98 2 . 48 -6 . 92E-Ol l . 54E+Ol 1509 . 19 2 . 19 -9 . 76E+OO 1 . 57E+O l 1764 . 4 9 1 5 . 80 2 . SOE+OO 3 . 6 0E+ OO
+ PB-2 1 4 77 . 11 10 . 70 1 . 81E+OO 7 . 75£-01 2 . 33E+OO 295 . 21 19 . 20 1. llE- 0 1 l . 25E+OO 35 1. 92 37 . 20 8. 03E- 0 1 7 . 7 5 E- 01
+ PA-228 8 9 .95 22 . 00 8. 0lE - 0 1 5 . 9 4£ - 0 1 9. 84E- 01 93 . 35 35 . 00 -2. 60E- 0 1 5 . 94£-01 105 . 00 16 . 30 - 2 . 97E- Dl l . 12E+OO 129 . 22 2 . 97 - 3 . 03£+00 5 . 77E+OO 338 . 32 5 . 30 -2 . 59£- 02 4.63£+00 463 . 00 13. 80 - 2 . 92E- 0 2 l . 9 6E+OO 911 . 23 16 . 70 1.28£+00 2.82£+00
+ AM- 241 59 . 54 3 6. 30 1 . 51E-01 1 .0 3£+ 00 1 . 03E+OO
+ CM- 243 103 .7 6 23 . 00 - 3 . 82E - 02 7 . 78E - 0 1 7 . 78£-01 228 . 18 10 . 60 - 4 . 56E- 01 1. 76E+OO 277 . 60 14.00 6 . 15 E- 0 1 l. 57E+OO
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is Inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 23
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 L.u9:24PM Pagel of6 pex-Gamma Analysis Report for B1-010-001 (0.5" - 1.0") BOTTOM 81-010-001-CJFC-C11-CV GAMMA SPECTRUM ANALYSIS Sample Identification : 81-010-001 (0.5 - 1.0") BOTTOM Sample Description : B1-010-001-CJFC-C11-CV Sample Type : Planchet Unit Sample Point Sample Size 1.686E+02 grams Facility : Dairyland_NPP Sample Taken On : 3/22/2019 12:40:00PM Acquisition Started : 3/22/2019 1:54:0SPM Procedure : Planchet on DET Operator : Administrator Detector Name : HOTLAB Geometry : Planchet on DET Live Time : 900.0 seconds Real Time : 902.6 seconds Dead Time : 0.29% Peak Locate Threshold : 3.00 Peak Locate Range (In channels) : 100-4096 Peak Area Range On channels) : 100-4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number Peak Analysis Performed on : 3/22/2019 2:09:15PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096 10/26/2020 Page 24
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 2:09:24PM Page2 of6 Analysis Report for B1-010-001 (0.5" - 1.0") BOTTOM B1-010-001-CJFC-C11-CV Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No_ (keV) start end Centroid Area Uncertainty Counts (keV) F 1 238 .81 474 - 482 478.10 S.99E+01 21.04 1.20E+02 1.36 F 2 352 . 39 701 - 712 705 - 21 4 . 35E+Ol 15.93 5.24E+Ol 1. 73 F 3 609 . 77 121 5 - 1224 1 219 . 87 2 .8 3E+01 12 . 11 2 .2 5E+01 1.29 F 4 1461.09 2917 - 2929 2922 .3 0 7 . 99E+Ol 18 . 61 1 .0 3E+Ol 2.34 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma AREA CORRECTION REPORT REFERENCEPEAKIBKG.SUBTRACT Peak Analysis Performed on : 3/22/2019 2:09:1 5PM Ref. Peak Energy : 0.00 Reference Date Peak Ratio : 0.00 Uncertainty : 0.00 Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001363.CNF Corrected Area is: Original
- Peak Ratio - Background Peak Energy Original Orig. Area Ambient Backgr. Corrected Corrected No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 1 238 . 81 5 .9 9E+01 21.04 5 . 99E+Ol 2 . l OE +Ol F 2 352 . 39 4.35E+Ol 1 5 .93 1 . 91E+01 7.75E+OO 2 . 44E+O l 1 .77E+Ol F 3 609 . 77 2 . 83E+Ol 12 .11 9 .6 9E+OO 5.77E+OO 1 .8 6E+Ol 1 . 34E+Ol F 4 1461.09 7 . 99E +O l 18.61 1 .4 3E+Ol 3.77E+OO 6 . 57E+Ol l . 90E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nudide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLABAIR.NLB IDENTIFIED NUCLIDES 10/26/2020 Page 25
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/201 9 2:09:24PM Page 3 of6 Analysis Report for B1-010-001 (0.5" - 1.0") BOTTOM B1-010-001-CJFC-C11-CV Nuclide Name Id Confidence Energy (keV) Yield(%) Activity Activity (pCilgrams) Uncertainty K- 40 0.981 1460 . 75
- 10 . 67 l . 46E+Ol 4 . 30E+OO PB - 212 0.523 77 .11 17 . 50 238.63
- 44.60 5.23E-01 1.85E-0 1 BI-214 0.348 609.31
- 46.30 4.02E-01 2.91E-01 1120.29 15 . 10 1238 . 11 5.94 1377.67 4 . 11 1407.98 2. 48 1509 . 19 2.19 1764.49 15 . 80
* = Energy line found In the spectrum.
- = Manually added nudide.
? :: Manually edited nuclide.
Energy Tolerance : 1.000 keV Nudide confidence index threshold = 0.30 Errors quoted at 2.000sigma UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 2:09:15PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak Size (CPS) Peak No. Energy (keV) Uncertainty Type Nuclide F 2 352 . 39 2.70794E-02 36.35 Tol. PB-214 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT 10/26/2020 Page 26
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 2:09:24PM Page4of6 Analysis Report for B1-010-001 (0.5" - 1.0) BOTTOM B1--010-001-CJFC-C11-CV Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncerlalnty (pCilgrams) K-40 0.981 1. 4 6E+Ol 4.30E+OO PB-212 0 . 523 5 .2 3E- 01 1 . 85£-01 BI-214 0 . 348 4.02E-01 2.91E-01
? :a nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma 10/26/2020 Page 27
LAC LTP - Final Status Survey Package - 3/26/2019 3/2212019 2:U9:24PM Page 5 of6 Analysis Report for B1-010-001 (0.5" - 1.0"} BOTTOM B1-010-001 -CJFC-C1 1-CV UNIDENTIFIED PEAKS Peak Locate Performed on : 3/22/2019 2:09:1 5PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 2 352.39 2 . 70794£- 02 36.35 Tol. PB - 214 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000slgma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTL.ABAIR.NLB Nuclide Energy Yield(%) Activity NuctideMDA LineMDA Name (keV) (pCVgrams) (pCUgrams) (pCVgrams)
+ K-40 1 460.75
- 10 . 67 1. 4 6E+Ol 4.74E+00 4 . 74E+OO t AR- 41 1293 .6 4 99 . 16 2.73E -01 8.75E - Ol 8.75E - Ol
+ C0-60 1173 .2 2 100.00 2.74£-01 4 . 99£-01/ 5.34E-Ol 1332. 4 9 100.00 4 . 13E-01 4.99E-01
+ KR - 85 513 . 99 0 . 43 7 . 34E+Ol 8 . SOE+Ol 8.SOE+Ol
+ Y-88 898.04 93.70 -2.95E-02 3.46£-01 3.46E-01 1836 . 06 99.20 -1.SSE-01 3.B?E - 01
+ I-131 284.30 6 . 06 -1. 4 9E+OO 2.86E - 01 3 . 52E+OO 364.48 81.20 -9. 72E-02 2.86£-01 636.97 7.27 -1.98E+OO 3.62E+OO
+ CS-134 604 . 70 97 .6 0 -5 . 70E-02 3.09E-Ol 3 . 79E-01 795 . 84 85.40 -1 . 27£-01 3.09E-01
+ CS-137 661 . 65 85.12 1.02E-0 1 4 . 16E - 01 4 . 16E- 01
+ CE -1 44 80 . 12 1.36 2 . 79E - 01 1. 59E+OO 1. 71E+Ol 133 . 51 11.09 -7.34E-01 1.59E+OO
+ EU-152 121 . 78 28 . 43 -7 . 82E-02 6 . llE-01 6 . llE-0 1 344 . 28 26 .60 -6.83E-01 9 . 24E-01 10/26/2020 Page 28
LAC LTP - Final Status Survey Package - 3/26/2019 3/22/2019 2:09:24PM Page 6 of6 Analysis Report for B1-010-001 (0.5" - 1.0") BOTTOM B1-010-00 1-CJFC-C11-CV Nuclide Energy Yield(%) Activity Nuc/ldeMDA Line MDA Name (pCl/grams) (pCilgrams) (pCilgrams) (keV) EU-152 1408 . 08 20 .75 -5.24E-Ol 6. llE-01 / 1. 45E+OO
+ EU-154 123.07 40.40 5 . 37E-02 4.36E - 01 4.36E-01 723 . 30 19 . 70 8.26E-02 1.60E+OO 1274 . 51 34 . 40 -1. SlE-02 l . 25E+OO
+ EU-155 86 . 54 32 . 80 -l. 85E - 02 6.0lE-01 6.0lE-01 105 . 31 21. 80 l . 65E-01 7.96E-01
+ BI-214 609.31
- 46 . 30 4.02E-01 5.27E-01 5.27E-01 1120.29 15 . 10 1. 38E+OO 3 . 16E+OO 1238 .11 5 . 94 2 . 56E+OO 9 . 17E+OO 1377 . 67 4 . 11 l . 42E+00 8.19E+OO 1407 .98 2 . 48 -4 . 38E+OO 1. 21E+Ol 1509 . 19 2 . 19 3 . 35E+OO 1. 20E+Ol 1764 . 49 15 . 80 9.34E-01 3.24E+OO
+ PB-214 77 .11 10 . 70 3.57E - 01 7.82E-01 2 . 31E+OO 295.21 19.20 6.52E-01 l.25E+OO 351. 92 37 . 20 5.03E-01 7.82E-Ol
+ PA-228 89.95 22.00 9.31E-01 5 . 70E-01 9 . 66E-01 93.35 35.00 3.77E-Ol 5.70E -0 1 105 . 00 16 . 30 l.47E - 01 l . 12E+OO 129 . 22 2 . 97 - 1 . lBE+OO 6.20£+00 338.32 5 . 30 7.85E- 01 4.76E+OO 463.00 13 . 80 l .48 E+OO 2.16E+OO 911. 23 16 . 70 1. 20E+OO 2 . 48E+OO
+ AM-241 59 .54 36 . 30 1.06£-01 l.07E+OO 1. 07E+OO
+ CM-243 103.76 23 . 00 5 . 24E-01 7.BOE-01 7.80E-01 228.18 10.60 -1.39£+00 1 . 78E+OO 277.60 14.00 6 . 70E - 01 1 . 60E+OO
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level 10/26/2020 Page 29
FSS RELEASE RECORD - REVISION 1
~
REACTOR BUILDING BASEMENT R ' *OLUIWNS SURVEY UNIT B1-010-001 ATTACHMENT 8 GEL LABORATORIES ANALYTICAL REPORTS 718
lij =I I [Laboratories LLc $ = ** PO Box ~07 12 Charteston SC 294 7 amember of The GEL Group INC 2040 S3'/a(leRoad Charteston. SC29407 P 843.556.8171 F 843.766. 117g ge l.c om April 08, 2019 Mr. Jason Q. Spaide LaCrosseSolutions S4601 State Hwy 35 Genoa, Wisconsin 54632 Re: LACBWR Site Restoration Project Work Order: 474479
Dear Mr. Spaide:
GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for the sample(s) we received on March 26, 2019. This original data report has been prepared and reviewed in accordance with GELs standard operating procedures. Test results for NELAP or ISO 17025 accredited tests are verified to meet the requirements of those standards, with any exceptions noted. The results reported relate only to the items tested and to the sample as received by the laboratory. These results may not be reproduced except as full reports without approval by the laboratory. Copies of GELs accreditations and certifications can be found on our website at www.gel.com. Our policy is to provide high quality, personalized analytical services to enable you to meet your analytical needs on time every time. We trust that you will find everything in order and to your satisfaction. If you have any questions, please do not hesitate to call me at (843) 556-8171, ext. 4453. Sincerely, PM_SIGN_HERE Edith Kent Project Manager Purchase Order: 672583 Enclosures Page 1 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 (843) 5568171 www.gel.com Certificate of Analysis Report for ENRG070 LaCrosseSolutions, LLC (672583) Client SDG: 474479 GEL Work Order: 474479 The Qualifiers in this report are defined as follows:
- A quality control analyte recovery is outside of specified acceptance criteria
** Analyte is a Tracer compound
** Analyte is a surrogate compound U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.
Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the Certificate of Analysis. The designation ND, if present, appears in the result column when the analyte concentration is not detected above the limit as defined in the U qualifier above. This data report has been prepared and reviewed in accordance with GEL Laboratories LLC standard operating procedures. Please direct any questions to your Project Manager, Edith Kent. Reviewed by USER_SIGN_HERE Page 2 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 8, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CSFC-C04-CV Project: ENRG07001 Sample ID: 474479001 Client ID: ENRG070 Matrix: Misc Solid Collect Date: 21-MAR-19 15:10 Receive Date: 26-MAR-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 U 0.00237 +/-0.0248 0.0518 0.400 pCi/g JXR5 03/29/19 0840 1861503 1 Americium-243 U -0.00784 +/-0.0461 0.110 0.400 pCi/g Curium-243/244 U -0.00602 +/-0.0182 0.0511 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U 0.00 +/-0.00281 0.00559 0.010 pCi/g BXA4 04/04/19 1306 1863211 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U 0.0125 +/-0.0429 0.0822 0.400 pCi/g JXR5 03/29/19 0841 1861504 3 Plutonium-239/240 U 0.0121 +/-0.038 0.0711 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U 1.71 +/-2.68 4.53 5.00 pCi/g JXR5 04/02/19 1025 1861505 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U 0.188 +/-0.654 1.83 5.00 pCi/g TXJ1 04/05/19 0633 1862862 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 U 0.0356 +/-0.0965 0.204 1.00 pCi/g MXR1 03/27/19 1015 1861561 6 Cobalt-60 U 0.0403 +/-0.0822 0.223 pCi/g Europium-152 U 0.168 +/-0.242 0.515 pCi/g Europium-154 U -0.00638 +/-0.277 0.609 pCi/g Europium-155 U 0.168 +/-0.231 0.461 pCi/g Niobium-94 U -0.076 +/-0.099 0.157 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.00801 +/-0.0918 0.175 0.400 pCi/g JXK3 03/28/19 1400 1861382 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U -3.65 +/-2.97 5.40 10.0 pCi/g BXM4 04/05/19 1339 1862842 8 Liquid Scint C14, Solid "As Received" Carbon-14 U -1.1 +/-2.02 3.51 5.00 pCi/g TXP3 04/05/19 0931 1862851 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U 0.691 +/-0.988 1.67 2.00 pCi/g CXS7 04/08/19 0751 1862829 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U -0.452 +/-4.58 6.63 10.0 pCi/g TXJ1 04/04/19 1850 1862811 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 3 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 8, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CSFC-C04-CV Project: ENRG07001 Sample ID: 474479001 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 U -1.45 +/-1.21 2.29 5.00 pCi/g TXJ1 04/04/19 2324 1862816 12 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 03/26/19 1519 1861369 The following Analytical Methods were performed: Method Description Analyst Comments 1 DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-1 6 DOE HASL 300, 4.5.2.3/Ga-01-R 7 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified 8 EPA 906.0 Modified 9 EPA EERF C-01 Modified 10 DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-1, Modified 12 DOE RESL Ni-1, Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 42.1 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 70.3 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 100 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 68.1 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 68.1 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 109 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 73.5 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 90.8 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 56.2 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 98.8 (25%-125%) Notes: Page 4 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 8, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CSFC-C04-CV Project: ENRG07001 Sample ID: 474479001 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma). Column headers are defined as follows: DF: Dilution Factor Lc/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 5 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 8, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CJFC-C09-CV Project: ENRG07001 Sample ID: 474479002 Client ID: ENRG070 Matrix: Misc Solid Collect Date: 21-MAR-19 17:06 Receive Date: 26-MAR-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 U 0.000312 +/-0.0231 0.0514 0.400 pCi/g JXR5 03/29/19 0840 1861503 1 Americium-243 U -0.00557 +/-0.0188 0.0489 0.400 pCi/g Curium-243/244 U -0.00369 +/-0.0163 0.0426 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U -0.000517 +/-0.00506 0.00988 0.010 pCi/g BXA4 04/04/19 1306 1863211 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U 0.00476 +/-0.0265 0.0507 0.400 pCi/g JXR5 03/31/19 1916 1861504 3 Plutonium-239/240 U -0.011 +/-0.0208 0.0642 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U 0.252 +/-3.07 5.22 5.00 pCi/g JXR5 04/02/19 1227 1861505 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U 0.684 +/-1.46 3.00 5.00 pCi/g TXJ1 04/05/19 0711 1862862 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 48.2 +/-1.37 0.205 1.00 pCi/g MXR1 03/27/19 1016 1861561 6 Cobalt-60 U 0.0672 +/-0.0964 0.242 pCi/g Europium-152 U -0.296 +/-0.470 0.800 pCi/g Europium-154 U -0.0913 +/-0.301 0.579 pCi/g Europium-155 U 0.195 +/-0.376 0.656 pCi/g Niobium-94 U 0.0647 +/-0.0795 0.182 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0256 +/-0.068 0.140 0.400 pCi/g JXK3 03/28/19 1525 1861382 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U -2.41 +/-3.17 5.67 10.0 pCi/g BXM4 04/05/19 1512 1862842 8 Liquid Scint C14, Solid "As Received" Carbon-14 U -0.296 +/-2.08 3.59 5.00 pCi/g TXP3 04/05/19 1024 1862851 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U -0.0148 +/-0.853 1.47 2.00 pCi/g CXS7 04/08/19 0824 1862829 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U 1.66 +/-4.34 6.11 10.0 pCi/g TXJ1 04/04/19 1921 1862811 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 6 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 8, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CJFC-C09-CV Project: ENRG07001 Sample ID: 474479002 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 U -0.294 +/-1.52 2.70 5.00 pCi/g TXJ1 04/04/19 2340 1862816 12 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 03/26/19 1519 1861369 The following Analytical Methods were performed: Method Description Analyst Comments 1 DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-1 6 DOE HASL 300, 4.5.2.3/Ga-01-R 7 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified 8 EPA 906.0 Modified 9 EPA EERF C-01 Modified 10 DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-1, Modified 12 DOE RESL Ni-1, Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 79.9 (15%-125%) Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 87.5 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 82.3 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 55.9 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 55.9 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 98.8 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 84.3 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 90.5 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 62.4 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 84.1 (25%-125%) Notes: Page 7 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 8, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CJFC-C09-CV Project: ENRG07001 Sample ID: 474479002 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma). Column headers are defined as follows: DF: Dilution Factor Lc/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 8 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 8, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CJFC-C11-CV Project: ENRG07001 Sample ID: 474479003 Client ID: ENRG070 Matrix: Misc Solid Collect Date: 22-MAR-19 12:40 Receive Date: 26-MAR-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 U -0.00167 +/-0.0251 0.0586 0.400 pCi/g JXR5 03/29/19 0840 1861503 1 Americium-243 U 0.00925 +/-0.0414 0.0811 0.400 pCi/g Curium-243/244 U -0.0138 +/-0.0195 0.0639 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U 0.00327 +/-0.00419 0.00672 0.010 pCi/g BXA4 04/04/19 1306 1863211 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U -0.0214 +/-0.0319 0.0807 0.400 pCi/g JXR5 03/29/19 0841 1861504 3 Plutonium-239/240 U -0.00373 +/-0.027 0.0618 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U 0.958 +/-2.12 3.58 5.00 pCi/g JXR5 04/02/19 1429 1861505 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U 0.684 +/-2.76 5.13 5.00 pCi/g TXJ1 04/05/19 0712 1862862 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 11.0 +/-0.647 0.156 1.00 pCi/g MXR1 03/27/19 1016 1861561 6 Cobalt-60 U 0.00321 +/-0.0829 0.195 pCi/g Europium-152 U 0.0455 +/-0.260 0.478 pCi/g Europium-154 U 0.00701 +/-0.225 0.512 pCi/g Europium-155 U 0.173 +/-0.241 0.446 pCi/g Niobium-94 U 0.0412 +/-0.090 0.184 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.230 +/-0.149 0.233 0.400 pCi/g JXK3 03/28/19 1402 1861382 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U -1.22 +/-3.26 5.74 10.0 pCi/g BXM4 04/05/19 1645 1862842 8 Liquid Scint C14, Solid "As Received" Carbon-14 U -3.03 +/-2.02 3.60 5.00 pCi/g TXP3 04/04/19 1846 1862851 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U -0.0165 +/-0.921 1.59 2.00 pCi/g CXS7 04/08/19 0856 1862829 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U 3.42 +/-4.86 6.80 10.0 pCi/g TXJ1 04/04/19 1953 1862811 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 9 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 8, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CJFC-C11-CV Project: ENRG07001 Sample ID: 474479003 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 U -0.0131 +/-1.38 2.43 5.00 pCi/g TXJ1 04/04/19 2356 1862816 12 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 03/26/19 1519 1861369 The following Analytical Methods were performed: Method Description Analyst Comments 1 DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-1 6 DOE HASL 300, 4.5.2.3/Ga-01-R 7 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified 8 EPA 906.0 Modified 9 EPA EERF C-01 Modified 10 DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-1, Modified 12 DOE RESL Ni-1, Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 43.5 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 62.8 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 103 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 82.1 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 82.1 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 103 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 88.6 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 90 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 58 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 92.1 (25%-125%) Notes: Page 10 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: April 8, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CJFC-C11-CV Project: ENRG07001 Sample ID: 474479003 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma). Column headers are defined as follows: DF: Dilution Factor Lc/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 11 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Report Date: April 8, 2019 LaCrosseSolutions Page 1 of 7 S4601 State Hwy 35 Genoa, Wisconsin
Contact:
Mr. Jason Q. Spaide Workorder: 474479 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 1861503 QC1204246812 474479001 DUP Americium-241 U 0.00237 U -0.00632 pCi/g N/A N/A JXR5 03/29/19 08:40 Uncertainty +/-0.0248 +/-0.0545 Americium-243 U -0.00784 U -0.0221 pCi/g N/A N/A Uncertainty +/-0.0461 +/-0.0366 Curium-243/244 U -0.00602 U -0.0249 pCi/g N/A N/A Uncertainty +/-0.0182 +/-0.0578 QC1204246813 LCS Americium-241 1.81 1.73 pCi/g 95.7 (75%-125%) 03/29/19 08:40 Uncertainty +/-0.205 Americium-243 U -0.0411 pCi/g (75%-125%) Uncertainty +/-0.0267 Curium-243/244 2.17 1.87 pCi/g 86 (75%-125%) Uncertainty +/-0.212 QC1204246811 MB Americium-241 U 0.00 pCi/g 03/29/19 08:40 Uncertainty +/-0.0186 Americium-243 U -0.0127 pCi/g Uncertainty +/-0.0316 Curium-243/244 U -0.00182 pCi/g Uncertainty +/-0.0273 Batch 1861504 QC1204246815 474479001 DUP Plutonium-238 U 0.0125 U 0.020 pCi/g N/A N/A JXR5 03/29/19 08:41 Uncertainty +/-0.0429 +/-0.0389 Plutonium-239/240 U 0.0121 U -0.00154 pCi/g N/A N/A Uncertainty +/-0.038 +/-0.0231 QC1204246816 LCS Plutonium-238 U 0.012 pCi/g 03/29/19 08:41 Uncertainty +/-0.0316 Page 12 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 474479 Page 2 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 1861504 Plutonium-239/240 1.84 1.96 pCi/g 106 (75%-125%) JXR5 03/29/19 08:41 Uncertainty +/-0.242 QC1204246814 MB Plutonium-238 U -0.0192 pCi/g 03/29/19 08:41 Uncertainty +/-0.0276 Plutonium-239/240 U -0.00137 pCi/g Uncertainty +/-0.0206 Batch 1861505 QC1204246818 474479001 DUP Plutonium-241 U 1.71 U 0.358 pCi/g N/A N/A JXR5 04/02/19 18:33 Uncertainty +/-2.68 +/-2.55 QC1204246819 LCS Plutonium-241 124 128 pCi/g 103 (75%-125%) 04/02/19 20:35 Uncertainty +/-4.21 QC1204246817 MB Plutonium-241 U 1.90 pCi/g 04/02/19 16:31 Uncertainty +/-2.01 Batch 1863211 QC1204250785 474479001 DUP Neptunium-237 U 0.00 U -0.00346 pCi/g N/A N/A BXA4 04/04/19 13:09 Uncertainty +/-0.00281 +/-0.0045 QC1204250786 LCS Neptunium-237 1.37 1.35 pCi/g 98.4 (75%-125%) 04/04/19 13:06 Uncertainty +/-0.0546 QC1204250784 MB Neptunium-237 U -0.00157 pCi/g 04/04/19 13:06 Uncertainty +/-0.00341 Rad Gamma Spec Batch 1861561 QC1204247021 474479001 DUP Cesium-137 U 0.0356 U 0.0192 pCi/g N/A N/A MXR1 03/27/19 11:22 Uncertainty +/-0.0965 +/-0.0877 Cobalt-60 U 0.0403 U 0.0108 pCi/g N/A N/A Uncertainty +/-0.0822 +/-0.108 Page 13 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 474479 Page 3 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 1861561 Europium-152 U 0.168 U -0.119 pCi/g N/A N/A MXR1 03/27/19 11:22 Uncertainty +/-0.242 +/-0.226 Europium-154 U -0.00638 U 0.0367 pCi/g N/A N/A Uncertainty +/-0.277 +/-0.326 Europium-155 U 0.168 U -0.0667 pCi/g N/A N/A Uncertainty +/-0.231 +/-0.208 Niobium-94 U -0.076 U -0.0113 pCi/g N/A N/A Uncertainty +/-0.099 +/-0.089 QC1204247022 LCS Americium-241 1300 1250 pCi/g 96.1 (75%-125%) 03/27/19 18:36 Uncertainty +/-40.5 Cesium-137 496 537 pCi/g 108 (75%-125%) Uncertainty +/-10.6 Cobalt-60 399 410 pCi/g 103 (75%-125%) Uncertainty +/-11.3 Europium-152 U -1.23 pCi/g Uncertainty +/-4.17 Europium-154 U -0.0891 pCi/g Uncertainty +/-3.13 Europium-155 U 1.42 pCi/g Uncertainty +/-4.08 Niobium-94 U 1.04 pCi/g Uncertainty +/-1.23 QC1204247020 MB Cesium-137 U -0.041 pCi/g 03/27/19 11:32 Uncertainty +/-0.0842 Cobalt-60 U 0.0933 pCi/g Uncertainty +/-0.0812 Europium-152 U 0.0366 pCi/g Uncertainty +/-0.218 Europium-154 U -0.00868 pCi/g Uncertainty +/-0.241 Page 14 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 474479 Page 4 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 1861561 Europium-155 U -0.0251 pCi/g MXR1 03/27/19 11:32 Uncertainty +/-0.223 Niobium-94 U 0.0195 pCi/g Uncertainty +/-0.0936 Batch 1862862 QC1204249964 474479001 DUP Nickel-59 U 0.188 U -0.208 pCi/g N/A N/A TXJ1 04/05/19 07:14 Uncertainty +/-0.654 +/-0.407 QC1204249965 LCS Nickel-59 91.8 103 pCi/g 112 (75%-125%) 04/05/19 07:46 Uncertainty +/-8.87 QC1204249963 MB Nickel-59 U -1.61 pCi/g 04/05/19 07:13 Uncertainty +/-2.11 Rad Gas Flow Batch 1861382 QC1204246548 474479002 DUP Strontium-90 U -0.0256 U 0.0736 pCi/g N/A N/A JXK3 03/28/19 14:02 Uncertainty +/-0.068 +/-0.0868 QC1204246549 LCS Strontium-90 6.77 7.34 pCi/g 108 (75%-125%) 03/28/19 14:02 Uncertainty +/-0.437 QC1204246547 MB Strontium-90 U -0.0771 pCi/g 03/28/19 14:02 Uncertainty +/-0.0545 Rad Liquid Scintillation Batch 1862811 QC1204249789 474479001 DUP Iron-55 U -0.452 U 0.657 pCi/g N/A N/A TXJ1 04/04/19 20:57 Uncertainty +/-4.58 +/-4.74 QC1204249790 LCS Iron-55 76.6 66.9 pCi/g 87.3 (75%-125%) 04/04/19 21:28 Uncertainty +/-5.92 Page 15 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 474479 Page 5 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 1862811 QC1204249788 MB Iron-55 U -0.429 pCi/g TXJ1 04/04/19 20:25 Uncertainty +/-3.94 Batch 1862816 QC1204249804 474479001 DUP Nickel-63 U -1.45 U -1.24 pCi/g N/A N/A TXJ1 04/05/19 00:29 Uncertainty +/-1.21 +/-1.28 QC1204249805 LCS Nickel-63 80.5 86.4 pCi/g 107 (75%-125%) 04/05/19 00:45 Uncertainty +/-4.18 QC1204249803 MB Nickel-63 U 1.12 pCi/g 04/05/19 00:12 Uncertainty +/-1.66 Batch 1862829 QC1204249846 474479001 DUP Technetium-99 U 0.691 U 0.189 pCi/g N/A N/A CXS7 04/08/19 10:00 Uncertainty +/-0.988 +/-0.960 QC1204249847 LCS Technetium-99 35.8 32.4 pCi/g 90.4 (75%-125%) 04/08/19 10:32 Uncertainty +/-1.66 QC1204249845 MB Technetium-99 U 0.0787 pCi/g 04/08/19 09:28 Uncertainty +/-0.905 Batch 1862842 QC1204249893 474479001 DUP Tritium U -3.65 U -1.32 pCi/g N/A N/A BXM4 04/06/19 09:25 Uncertainty +/-2.97 +/-3.30 QC1204249895 LCS Tritium 14.1 11.0 pCi/g 78 (75%-125%) 04/06/19 12:31 Uncertainty +/-1.13 QC1204249892 MB Tritium U -0.593 pCi/g 04/06/19 07:53 Uncertainty +/-0.728 Page 16 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 474479 Page 6 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 1862842 QC1204249894 474479001 MS Tritium 153 U -3.65 119 pCi/g 77.9 (75%-125%) BXM4 04/08/19 09:17 Uncertainty +/-2.97 +/-39.5 Batch 1862851 QC1204249923 474479001 DUP Carbon-14 U -1.1 U -2.4 pCi/g N/A N/A TXP3 04/04/19 20:32 Uncertainty +/-2.02 +/-2.00 QC1204249925 LCS Carbon-14 144 141 pCi/g 97.5 (75%-125%) 04/04/19 22:18 Uncertainty +/-4.27 QC1204249922 MB Carbon-14 U -2.63 pCi/g 04/04/19 19:39 Uncertainty +/-1.99 QC1204249924 474479001 MS Carbon-14 153 U -1.1 150 pCi/g 98.1 (75%-125%) 04/04/19 21:25 Uncertainty +/-2.02 +/-4.52 Notes: Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma). The Qualifiers in this report are defined as follows:
** Analyte is a Tracer compound < Result is less than value reported > Result is greater than value reported BD Results are either below the MDC or tracer recovery is low FA Failed analysis.
H Analytical holding time was exceeded J Value is estimated K Analyte present. Reported value may be biased high. Actual value is expected to be lower. L Analyte present. Reported value may be biased low. Actual value is expected to be higher. M M if above MDC and less than LLD M REMP Result > MDC/CL and < RDL N/A RPD or %Recovery limits do not apply. N1 See case narrative ND Analyte concentration is not detected above the detection limit NJ Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Q One or more quality control criteria have not been met. Refer to the applicable narrative or DER. Page 17 of 29 SDG: 474479
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 474479 Page 7 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD. UI Gamma Spectroscopy--Uncertain identification UJ Gamma Spectroscopy--Uncertain identification UL Not considered detected. The associated number is the reported concentration, which may be inaccurate due to a low bias. X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y Other specific qualifiers were required to properly define the results. Consult case narrative.
^ RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL. Qualifier Not Applicable for Radiochemistry.
h Preparation or preservation holding time was exceeded N/A indicates that spike recovery limits do not apply when sample concentration exceeds spike conc. by a factor of 4 or more or %RPD not applicable.
^ The Relative Percent Difference (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptance criteria when the sample is greater than five times (5X) the contract required detection limit (RL). In cases where either the sample or duplicate value is less than 5X the RL, a control limit of +/- the RL is used to evaluate the DUP result.
- Indicates that a Quality Control parameter was not within specifications.
For PS, PSD, and SDILT results, the values listed are the measured amounts, not final concentrations. Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the QC Summary. Page 18 of 29 SDG: 474479
Radiochemistry Technical Case Narrative LaCrosseSolutions, LLC (ENRG) SDG #: 474479 Product: Alphaspec Isotopic Am241 Am243, Cm243/244, Solid Analytical Method: DOE EML HASL-300, Am-05-RC Modified Analytical Procedure: GL-RAD-A-011 REV# 27 Analytical Batch: 1861503 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1861369 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV 1204246811 Method Blank (MB) 1204246812 474479001(B1-010-001-CSFC-C04-CV) Sample Duplicate (DUP) 1204246813 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Alphaspec Pu238, 239/240, Solid Analytical Method: DOE EML HASL-300, Pu-11-RC Modified Analytical Procedure: GL-RAD-A-011 REV# 27 Analytical Batch: 1861504 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1861369 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV Page Laboratories GEL 19 of 29 SDG:llC 474479 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
1204246814 Method Blank (MB) 1204246815 474479001(B1-010-001-CSFC-C04-CV) Sample Duplicate (DUP) 1204246816 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Technical Information Recounts Sample 474479002 (B1-010-001-CJFC-C09-CV) was recounted due to results more negative than the three sigma TPU. The second count is reported. Product: Alphaspec Np, Solid Analytical Method: ASTM C 1475-00 Modified Analytical Procedure: GL-RAD-A-032 REV# 22 Analytical Batch: 1863211 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1861369 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV 1204250784 Method Blank (MB) 1204250785 474479001(B1-010-001-CSFC-C04-CV) Sample Duplicate (DUP) 1204250786 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Technical Information Sample Re-prep/Re-analysis The batch was reprepped with larger aliquots in order to achieve the requested detection limits. The re-analysis is reported. Page Laboratories GEL 20 of 29 SDG:llC 474479 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
Product: Dry Weight Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1861369 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV The samples in this SDG were analyzed on an "as received" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 Analytical Method: DOE HASL 300, 4.5.2.3/Ga-01-R Analytical Procedure: GL-RAD-A-013 REV# 27 Analytical Batch: 1861561 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1861369 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV 1204247020 Method Blank (MB) 1204247021 474479001(B1-010-001-CSFC-C04-CV) Sample Duplicate (DUP) 1204247022 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Page Laboratories GEL 21 of 29 SDG:llC 474479 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
Product: Gamma Ni59, Solid Analytical Method: DOE RESL Ni-1 Analytical Procedure: GL-RAD-A-022 REV# 18 Analytical Batch: 1862862 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1861369 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV 1204249963 Method Blank (MB) 1204249964 474479001(B1-010-001-CSFC-C04-CV) Sample Duplicate (DUP) 1204249965 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: GFPC, Sr90, Solid Analytical Method: EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Analytical Procedure: GL-RAD-A-004 REV# 21 Analytical Batch: 1861382 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1861369 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV 1204246547 Method Blank (MB) 1204246548 474479002(B1-010-001-CJFC-C09-CV) Sample Duplicate (DUP) 1204246549 Laboratory Control Sample (LCS) Page Laboratories GEL 22 of 29 SDG:llC 474479 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Preparation Information Homogenous Matrix Samples were non-homogenous matrix. Samples were pieces of rocks/bricks Technical Information Recounts Sample 474479002 (B1-010-001-CJFC-C09-CV) was recounted due to results more negative than the three sigma TPU. The second count is reported. Product: Liquid Scint Pu241, Solid Analytical Method: DOE EML HASL-300, Pu-11-RC Modified Analytical Procedure: GL-RAD-A-035 REV# 21 Analytical Batch: 1861505 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1861369 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV 1204246817 Method Blank (MB) 1204246818 474479001(B1-010-001-CSFC-C04-CV) Sample Duplicate (DUP) 1204246819 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Page Laboratories GEL 23 of 29 SDG:llC 474479 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
Product: Liquid Scint Fe55, Solid Analytical Method: DOE RESL Fe-1, Modified Analytical Procedure: GL-RAD-A-040 REV# 13 Analytical Batch: 1862811 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1861369 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV 1204249788 Method Blank (MB) 1204249789 474479001(B1-010-001-CSFC-C04-CV) Sample Duplicate (DUP) 1204249790 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Liquid Scint Ni63, Solid Analytical Method: DOE RESL Ni-1, Modified Analytical Procedure: GL-RAD-A-022 REV# 18 Analytical Batch: 1862816 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1861369 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV 1204249803 Method Blank (MB) 1204249804 474479001(B1-010-001-CSFC-C04-CV) Sample Duplicate (DUP) 1204249805 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this Page Laboratories GEL 24 of 29 SDG:llC 474479 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Liquid Scint Tc99, Solid Analytical Method: DOE EML HASL-300, Tc-02-RC Modified Analytical Procedure: GL-RAD-A-059 REV# 5 Analytical Batch: 1862829 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV 1204249845 Method Blank (MB) 1204249846 474479001(B1-010-001-CSFC-C04-CV) Sample Duplicate (DUP) 1204249847 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on an "as received" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: LSC, Tritium Distillation, Solid Analytical Method: EPA 906.0 Modified Analytical Procedure: GL-RAD-A-002 REV# 22 Analytical Batch: 1862842 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV 1204249892 Method Blank (MB) 1204249893 474479001(B1-010-001-CSFC-C04-CV) Sample Duplicate (DUP) 1204249894 474479001(B1-010-001-CSFC-C04-CV) Matrix Spike (MS) 1204249895 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on an "as received" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where Page Laboratories GEL 25 of 29 SDG:llC 474479 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
applicable, with the following exceptions. Technical Information Recounts Sample 1204249894 (B1-010-001-CSFC-C04-CVMS) was recounted due to low recovery. The recount is reported. Product: Liquid Scint C14, Solid Analytical Method: EPA EERF C-01 Modified Analytical Procedure: GL-RAD-A-003 REV# 16 Analytical Batch: 1862851 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 474479001 B1-010-001-CSFC-C04-CV 474479002 B1-010-001-CJFC-C09-CV 474479003 B1-010-001-CJFC-C11-CV 1204249922 Method Blank (MB) 1204249923 474479001(B1-010-001-CSFC-C04-CV) Sample Duplicate (DUP) 1204249924 474479001(B1-010-001-CSFC-C04-CV) Matrix Spike (MS) 1204249925 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on an "as received" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Technical Information Recounts Samples 474479001 (B1-010-001-CSFC-C04-CV) and 474479002 (B1-010-001-CJFC-C09-CV) were recounted due to results more negative than the three sigma TPU. The second counts are reported. Certification Statement Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless otherwise noted in the analytical case narrative. Page Laboratories GEL 26 of 29 SDG: llC 474479 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
Page 27 of 29 SDG: 474479 Pai,..-* 1 of ProjeclU---1,:',£!);\VR __ ~-- _ _ __J 2 W=t! LaboratoneSLLC I , GEL Laboratories, LLC IReceil'ing Dopt 2040SavageRoad GEL Quote#, - - - - - - - - - - - - ~ ,1: ..,"""' cr.,,nkslJ) I lladS!Cooe,isl!y I - y ISpe,::lailyMa1y11::s Charleston, SC 29407 coc Nuniber" 1: lf ?Y. 11.7-1 Chain of Custodv and An~Mical Rerluest Phone: (843) 556-8111 PO Number: 672583 GEL Work Order Number: GEL Project Manager: Fax: (843) 766-J !78 Client Name. La Crosse Solution, Phone# 608-689.-4259 Sample Analysis Requestrd {~) (Fill in the number of containers for each test) Projce11Sitc Name: L\CBWR-Gcnoa WI Fax# Should this <- Preservative Type(6) _ .. m~teM ~ .,. Address. 54601 State Road 35 <on,jdened* ,; ..- "'
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Are sample contaiucrs idcntifi;iblc ;,s 12 GEL i ro,*ided? COCfonn is properly sigr.ed iu Citcle Appl1cahJe- Nol rehnq11isbcd Otl,er(descnbcl 13 n:li!l:jui,Jied/receivetl se<..1ions? Commerns (Use Cornim,ation Fo,m if ncalcJJ* _(L:.2___ Dae _ _,5 .I 7 I ,q PM (orPMA1 n:v,cw: humtls Page _LO! _I_ GL-CHL-SR-001 Rev6 Page 28 of 29 SDG: 474479
List of current GEL Certifications as of 08 April 2019 State Certification Alaska 17018 Arkansas 880651 CLIA 42D0904046 California 2940 Colorado SC00012 Connecticut PH0169 DoD ELAP/ ISO17025 A2LA 2567.01 Florida NELAP E87156 Foreign Soils Permit P3301500283, P3301500253 Georgia SC00012 Georgia SDWA 967 Hawaii SC00012 Idaho SC00012 Illinois NELAP 200029 Indiana CSC01 Kansas NELAP E10332 Kentucky SDWA 90129 Kentucky Wastewater 90129 Louisiana NELAP 03046 (AI33904) Louisiana SDWA LA024 Maryland 270 Massachusetts MSC012 Michigan 9976 Mississippi SC00012 Nebraska NEOS2613 Nevada SC0001220192 New Hampshire NELAP 2054 New Jersey NELAP SC002 New Mexico SC00012 New York NELAP 11501 North Carolina 233 North Carolina SDWA 45709 North Dakota R158 Oklahoma 9904 Pennsylvania NELAP 6800485 Puerto Rico SC00012 S. Carolina Radiochem 10120002 South Carolina Chemistry 10120001 Tennessee TN 02934 Texas NELAP T1047042351914 Utah NELAP SC00012201827 Vermont VT87156 Virginia NELAP 460202 Washington C780 Page 29 of 29 SDG: 474479
11=1* ILaboratories LLC O = POBox:')0712 Chadeston SC294'7 cl member of The GEL Group INC 2040 Sa*,*age Road Chadeston. SC 29407 P 843.556.8171 F 843.766.1178 gel.c om August 23, 2019 Mr. Jason Q. Spaide LaCrosseSolutions S4601 State Hwy 35 Genoa, Wisconsin 54632 Re: LACBWR Site Restoration Project Work Order: 486045
Dear Mr. Spaide:
GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for the sample(s) we received on July 30, 2019. This original data report has been prepared and reviewed in accordance with GELs standard operating procedures. Test results for NELAP or ISO 17025 accredited tests are verified to meet the requirements of those standards, with any exceptions noted. The results reported relate only to the items tested and to the sample as received by the laboratory. These results may not be reproduced except as full reports without approval by the laboratory. Copies of GELs accreditations and certifications can be found on our website at www.gel.com. Our policy is to provide high quality, personalized analytical services to enable you to meet your analytical needs on time every time. We trust that you will find everything in order and to your satisfaction. If you have any questions, please do not hesitate to call me at (843) 556-8171, ext. 4453. Sincerely, PM_SIGN_HERE Edith Kent Project Manager Purchase Order: 672583 Enclosures Page 1 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 (843) 5568171 www.gel.com Certificate of Analysis Report for ENRG070 LaCrosseSolutions, LLC (672583) Client SDG: 486045 GEL Work Order: 486045 The Qualifiers in this report are defined as follows:
- A quality control analyte recovery is outside of specified acceptance criteria
** Analyte is a Tracer compound
** Analyte is a surrogate compound U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.
Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the Certificate of Analysis. The designation ND, if present, appears in the result column when the analyte concentration is not detected above the limit as defined in the U qualifier above. This data report has been prepared and reviewed in accordance with GEL Laboratories LLC standard operating procedures. Please direct any questions to your Project Manager, Edith Kent. Reviewed by USER_SIGN_HERE Page 2 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BG02-SB Project: ENRG07001 Sample ID: 486045001 Client ID: ENRG070 Matrix: Soil Collect Date: 05-JUN-19 13:38 Receive Date: 30-JUL-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 U 0.0151 +/-0.0458 0.0862 0.400 pCi/g BXA4 08/12/19 1314 1902013 1 Americium-243 U 0.0442 +/-0.0524 0.0766 0.400 pCi/g Curium-243/244 U -0.00732 +/-0.017 0.0502 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U -0.000771 +/-0.00341 0.0089 0.010 pCi/g BXA4 08/18/19 1156 1902014 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U -0.00616 +/-0.0208 0.0541 0.400 pCi/g BXA4 08/12/19 1149 1902016 3 Plutonium-239/240 U -0.00802 +/-0.0152 0.0469 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U 0.305 +/-1.86 3.17 5.00 pCi/g HAKB 08/21/19 1544 1908504 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U -0.926 +/-1.84 3.18 5.00 pCi/g TXJ1 08/17/19 0624 1905901 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 0.535 +/-0.0734 0.0457 1.00 pCi/g MXR1 08/01/19 1927 1901923 6 Cobalt-60 U 0.00142 +/-0.0227 0.0485 pCi/g Europium-152 U 0.00551 +/-0.0546 0.111 pCi/g Europium-154 U -0.0252 +/-0.0676 0.129 pCi/g Europium-155 U 0.00529 +/-0.0476 0.0945 pCi/g Niobium-94 U 0.00613 +/-0.0215 0.0435 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.00869 +/-0.0603 0.116 0.400 pCi/g JXC9 08/22/19 1528 1909237 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U -0.95 +/-3.59 7.29 10.0 pCi/g EW3 08/06/19 2052 1903364 8 Liquid Scint C14, Solid "As Received" Carbon-14 U -0.211 +/-2.29 3.94 5.00 pCi/g TXP3 08/20/19 1637 1905892 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U 0.101 +/-0.515 0.917 2.00 pCi/g JJ3 08/20/19 0944 1907292 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U 2.10 +/-7.19 9.86 10.0 pCi/g TXJ1 08/17/19 1951 1905861 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 3 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BG02-SB Project: ENRG07001 Sample ID: 486045001 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 U -0.905 +/-2.07 3.66 5.00 pCi/g TXJ1 08/17/19 0340 1905868 12 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXC1 07/31/19 1016 1901819 The following Analytical Methods were performed: Method Description Analyst Comments 1 DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-1 6 DOE HASL 300, 4.5.2.3/Ga-01-R 7 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified 8 EPA 906.0 Modified 9 EPA EERF C-01 Modified 10 DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-1, Modified 12 DOE RESL Ni-1, Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 62.3 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 73.2 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 99.2 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 77.8 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 85.4 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 92.5 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 98.2 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 95.6 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 57.2 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 60.2 (25%-125%) Notes: Page 4 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BG02-SB Project: ENRG07001 Sample ID: 486045001 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma). Column headers are defined as follows: DF: Dilution Factor Lc/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 5 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BH02-SB Project: ENRG07001 Sample ID: 486045002 Client ID: ENRG070 Matrix: Soil Collect Date: 05-JUN-19 14:32 Receive Date: 30-JUL-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 U 0.0293 +/-0.047 0.0782 0.400 pCi/g BXA4 08/12/19 1314 1902013 1 Americium-243 U -0.0053 +/-0.0312 0.0741 0.400 pCi/g Curium-243/244 U 0.000319 +/-0.0237 0.0526 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U -0.00106 +/-0.00469 0.010 0.010 pCi/g BXA4 08/22/19 1416 1902014 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U 0.00582 +/-0.0376 0.0768 0.400 pCi/g BXA4 08/12/19 1149 1902016 3 Plutonium-239/240 U 0.000415 +/-0.0308 0.0684 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U 0.748 +/-2.09 3.55 5.00 pCi/g HAKB 08/21/19 1747 1908504 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U 0.205 +/-0.650 1.51 5.00 pCi/g TXJ1 08/17/19 0625 1905901 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 0.133 +/-0.0778 0.0833 1.00 pCi/g MXR1 08/01/19 1928 1901923 6 Cobalt-60 U -0.0165 +/-0.0389 0.075 pCi/g Europium-152 U -0.0101 +/-0.0981 0.197 pCi/g Europium-154 U -0.0441 +/-0.107 0.174 pCi/g Europium-155 U -0.0297 +/-0.0776 0.147 pCi/g Niobium-94 U -0.00342 +/-0.0327 0.0647 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0107 +/-0.0523 0.104 0.400 pCi/g JXC9 08/22/19 1528 1909237 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U 0.387 +/-3.78 7.22 10.0 pCi/g EW3 08/06/19 2120 1903364 8 Liquid Scint C14, Solid "As Received" Carbon-14 U -3.37 +/-2.31 4.09 5.00 pCi/g TXP3 08/20/19 1727 1905892 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U -0.242 +/-0.604 1.08 2.00 pCi/g JJ3 08/20/19 1006 1907292 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U 1.36 +/-6.22 8.61 10.0 pCi/g TXJ1 08/18/19 1038 1905861 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 6 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BH02-SB Project: ENRG07001 Sample ID: 486045002 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 U -1.76 +/-1.90 3.43 5.00 pCi/g TXJ1 08/17/19 0402 1905868 12 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXC1 07/31/19 1016 1901819 The following Analytical Methods were performed: Method Description Analyst Comments 1 DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-1 6 DOE HASL 300, 4.5.2.3/Ga-01-R 7 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified 8 EPA 906.0 Modified 9 EPA EERF C-01 Modified 10 DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-1, Modified 12 DOE RESL Ni-1, Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 73.7 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 67.4 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 70.3 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 49.8 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 79.5 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 102 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 95.9 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 75.7 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 50.4 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 64.7 (25%-125%) Notes: Page 7 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BH02-SB Project: ENRG07001 Sample ID: 486045002 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma). Column headers are defined as follows: DF: Dilution Factor Lc/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 8 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BJ02-SB Project: ENRG07001 Sample ID: 486045003 Client ID: ENRG070 Matrix: Soil Collect Date: 07-JUN-19 16:09 Receive Date: 30-JUL-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 U 0.00943 +/-0.0441 0.0866 0.400 pCi/g BXA4 08/12/19 1255 1902013 1 Americium-243 U -0.00259 +/-0.0242 0.0562 0.400 pCi/g Curium-243/244 U 0.0178 +/-0.0314 0.0476 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U 0.000898 +/-0.00723 0.0144 0.010 pCi/g BXA4 08/19/19 0839 1902014 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U -0.0108 +/-0.0153 0.0499 0.400 pCi/g BXA4 08/12/19 1149 1902016 3 Plutonium-239/240 U -0.00927 +/-0.0149 0.0476 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U 0.911 +/-2.60 4.42 5.00 pCi/g HAKB 08/21/19 1951 1908504 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U 0.679 +/-2.01 2.23 5.00 pCi/g TXJ1 08/17/19 0711 1905901 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 U 0.00464 +/-0.0259 0.0478 1.00 pCi/g MXR1 08/02/19 0548 1901923 6 Cobalt-60 U -0.0005 +/-0.0223 0.048 pCi/g Europium-152 U 0.0086 +/-0.058 0.110 pCi/g Europium-154 U 0.0134 +/-0.0836 0.167 pCi/g Europium-155 U 0.0607 +/-0.0585 0.126 pCi/g Niobium-94 U -0.0113 +/-0.0158 0.0276 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0455 +/-0.0608 0.104 0.400 pCi/g JXC9 08/22/19 1528 1909237 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U 0.713 +/-3.85 7.24 10.0 pCi/g EW3 08/06/19 2147 1903364 8 Liquid Scint C14, Solid "As Received" Carbon-14 U 1.82 +/-2.23 3.74 5.00 pCi/g TXP3 08/20/19 1816 1905892 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U 0.343 +/-0.569 0.978 2.00 pCi/g JJ3 08/20/19 1049 1907292 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U 2.29 +/-6.96 9.54 10.0 pCi/g TXJ1 08/17/19 2055 1905861 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 9 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BJ02-SB Project: ENRG07001 Sample ID: 486045003 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 U -1.66 +/-1.69 3.05 5.00 pCi/g TXJ1 08/17/19 0423 1905868 12 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXC1 07/31/19 1016 1901819 The following Analytical Methods were performed: Method Description Analyst Comments 1 DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-1 6 DOE HASL 300, 4.5.2.3/Ga-01-R 7 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified 8 EPA 906.0 Modified 9 EPA EERF C-01 Modified 10 DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-1, Modified 12 DOE RESL Ni-1, Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 84.8 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 82.5 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 96.6 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 89 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 64.8 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 87.5 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 84.2 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 98.6 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 56.9 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 73.5 (25%-125%) Notes: Page 10 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BJ02-SB Project: ENRG07001 Sample ID: 486045003 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma). Column headers are defined as follows: DF: Dilution Factor Lc/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 11 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BK01-SB Project: ENRG07001 Sample ID: 486045004 Client ID: ENRG070 Matrix: Soil Collect Date: 07-JUN-19 09:37 Receive Date: 30-JUL-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Alpha Spec Analysis Alphaspec Isotopic Am241 Am243, Cm243/244, Solid "Dry Weight Corrected" Americium-241 U 0.00467 +/-0.0301 0.0616 0.400 pCi/g BXA4 08/12/19 1255 1902013 1 Americium-243 U 0.0161 +/-0.0312 0.0536 0.400 pCi/g Curium-243/244 U 0.0126 +/-0.0288 0.0458 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U 0.000632 +/-0.00408 0.00834 0.010 pCi/g BXA4 08/19/19 0839 1902014 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U -0.00478 +/-0.0216 0.0545 0.400 pCi/g BXA4 08/12/19 1149 1902016 3 Plutonium-239/240 U 0.0109 +/-0.0289 0.0519 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U -0.163 +/-1.68 2.88 5.00 pCi/g HAKB 08/21/19 2155 1908504 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U 1.95 +/-2.01 3.92 5.00 pCi/g TXJ1 08/17/19 0711 1905901 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 U -0.00504 +/-0.0198 0.0386 1.00 pCi/g MXR1 08/02/19 0548 1901923 6 Cobalt-60 U -0.01 +/-0.0216 0.0417 pCi/g Europium-152 U -0.0121 +/-0.0496 0.100 pCi/g Europium-154 U -0.0149 +/-0.0738 0.149 pCi/g Europium-155 U 0.00689 +/-0.0489 0.0997 pCi/g Niobium-94 U -0.00279 +/-0.0175 0.0339 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0575 +/-0.0682 0.115 0.400 pCi/g JXC9 08/22/19 1528 1909237 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U -0.239 +/-3.66 7.18 10.0 pCi/g EW3 08/06/19 2215 1903364 8 Liquid Scint C14, Solid "As Received" Carbon-14 U -0.686 +/-2.30 3.98 5.00 pCi/g TXP3 08/20/19 1904 1905892 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U -0.495 +/-0.498 0.977 2.00 pCi/g JJ3 08/20/19 1111 1907292 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U 0.744 +/-7.05 9.73 10.0 pCi/g TXJ1 08/17/19 2126 1905861 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 12 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BK01-SB Project: ENRG07001 Sample ID: 486045004 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Liquid Scintillation Analysis Liquid Scint Ni63, Solid "Dry Weight Corrected" Nickel-63 U -0.88 +/-1.67 2.96 5.00 pCi/g TXJ1 08/17/19 0445 1905868 12 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXC1 07/31/19 1016 1901819 The following Analytical Methods were performed: Method Description Analyst Comments 1 DOE EML HASL-300, Am-05-RC Modified 2 ASTM C 1475-00 Modified 3 DOE EML HASL-300, Pu-11-RC Modified 4 DOE EML HASL-300, Pu-11-RC Modified 5 DOE RESL Ni-1 6 DOE HASL 300, 4.5.2.3/Ga-01-R 7 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified 8 EPA 906.0 Modified 9 EPA EERF C-01 Modified 10 DOE EML HASL-300, Tc-02-RC Modified 11 DOE RESL Fe-1, Modified 12 DOE RESL Ni-1, Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 85.3 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 86.2 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 96.4 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 76.8 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 91.7 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 95.5 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 88.9 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 98.3 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 57 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 75.3 (25%-125%) Notes: Page 13 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: August 23, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: B1-010-001-CIGS-BK01-SB Project: ENRG07001 Sample ID: 486045004 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma). Column headers are defined as follows: DF: Dilution Factor Lc/LC: Critical Level DL: Detection Limit PF: Prep Factor MDA: Minimum Detectable Activity RL: Reporting Limit MDC: Minimum Detectable Concentration SQL: Sample Quantitation Limit Page 14 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Report Date: August 23, 2019 LaCrosseSolutions Page 1 of 7 S4601 State Hwy 35 Genoa, Wisconsin
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Mr. Jason Q. Spaide Workorder: 486045 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 1902013 QC1204345141 486045001 DUP Americium-241 U 0.0151 U 0.0173 pCi/g N/A N/A BXA4 08/12/19 12:55 Uncertainty +/-0.0458 +/-0.0345 Americium-243 U 0.0442 U -0.0103 pCi/g N/A N/A Uncertainty +/-0.0524 +/-0.0233 Curium-243/244 U -0.00732 U -0.0121 pCi/g N/A N/A Uncertainty +/-0.017 +/-0.0196 QC1204345142 LCS Americium-241 1.92 1.90 pCi/g 99.2 (75%-125%) 08/12/19 12:55 Uncertainty +/-0.208 Americium-243 U 0.00324 pCi/g (75%-125%) Uncertainty +/-0.0339 Curium-243/244 2.28 1.98 pCi/g 86.9 (75%-125%) Uncertainty +/-0.211 QC1204345140 MB Americium-241 U -0.00702 pCi/g 08/12/19 12:55 Uncertainty +/-0.0413 Americium-243 U 0.004 pCi/g Uncertainty +/-0.0258 Curium-243/244 U 0.00303 pCi/g Uncertainty +/-0.0317 Batch 1902014 QC1204345144 486045001 DUP Neptunium-237 U -0.000771 U 0.00053 pCi/g N/A N/A BXA4 08/19/19 08:39 Uncertainty +/-0.00341 +/-0.00603 QC1204345145 LCS Neptunium-237 0.866 0.901 pCi/g 104 (75%-125%) 08/19/19 08:39 Uncertainty +/-0.0706 QC1204345143 MB Neptunium-237 U -0.000509 pCi/g 08/19/19 08:39 Uncertainty +/-0.00351 Page 15 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 486045 Page 2 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 1902016 QC1204345150 486045001 DUP Plutonium-238 U -0.00616 U 0.000528 pCi/g N/A N/A BXA4 08/12/19 13:15 Uncertainty +/-0.0208 +/-0.0243 Plutonium-239/240 U -0.00802 U 0.0219 pCi/g N/A N/A Uncertainty +/-0.0152 +/-0.0328 QC1204345151 LCS Plutonium-238 U 0.00421 pCi/g 08/12/19 13:15 Uncertainty +/-0.0158 Plutonium-239/240 1.96 1.81 pCi/g 92.3 (75%-125%) Uncertainty +/-0.197 QC1204345149 MB Plutonium-238 U 0.0148 pCi/g 08/12/19 13:15 Uncertainty +/-0.0356 Plutonium-239/240 U 0.0106 pCi/g Uncertainty +/-0.0244 Batch 1908504 QC1204360627 486045001 DUP Plutonium-241 U 0.305 U 1.23 pCi/g N/A N/A HAKB 08/22/19 03:15 Uncertainty +/-1.86 +/-1.98 QC1204360628 LCS Plutonium-241 60.8 57.4 pCi/g 94.3 (75%-125%) 08/22/19 05:16 Uncertainty +/-6.89 QC1204360626 MB Plutonium-241 U 0.427 pCi/g 08/21/19 23:59 Uncertainty +/-1.74 Rad Gamma Spec Batch 1901923 QC1204344917 486045001 DUP Cesium-137 0.535 0.527 pCi/g 1.47 (0%-20%) MXR1 08/02/19 05:49 Uncertainty +/-0.0734 +/-0.0914 Cobalt-60 U 0.00142 U 0.00278 pCi/g N/A N/A Uncertainty +/-0.0227 +/-0.0323 Europium-152 U 0.00551 U 0.0551 pCi/g N/A N/A Uncertainty +/-0.0546 +/-0.0999 Page 16 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 486045 Page 3 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 1901923 Europium-154 U -0.0252 U -0.0105 pCi/g N/A N/A MXR1 08/02/19 05:49 Uncertainty +/-0.0676 +/-0.102 Europium-155 U 0.00529 U -0.0185 pCi/g N/A N/A Uncertainty +/-0.0476 +/-0.0862 Niobium-94 U 0.00613 U -0.0301 pCi/g N/A N/A Uncertainty +/-0.0215 +/-0.029 QC1204344918 LCS Americium-241 487 528 pCi/g 108 (75%-125%) 08/02/19 05:52 Uncertainty +/-7.63 Cesium-137 168 169 pCi/g 101 (75%-125%) Uncertainty +/-2.87 Cobalt-60 111 107 pCi/g 97 (75%-125%) Uncertainty +/-2.71 Europium-152 U -0.249 pCi/g Uncertainty +/-1.10 Europium-154 U 0.220 pCi/g Uncertainty +/-0.835 Europium-155 U 0.198 pCi/g Uncertainty +/-0.968 Niobium-94 U -0.0402 pCi/g Uncertainty +/-0.359 QC1204344916 MB Cesium-137 U 0.000719 pCi/g 08/02/19 05:49 Uncertainty +/-0.0202 Cobalt-60 U -0.0169 pCi/g Uncertainty +/-0.0167 Europium-152 U 0.000411 pCi/g Uncertainty +/-0.0467 Europium-154 U 0.0164 pCi/g Uncertainty +/-0.0547 Europium-155 U -0.00898 pCi/g Uncertainty +/-0.0463 Page 17 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 486045 Page 4 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 1901923 Niobium-94 U 0.0118 pCi/g MXR1 08/02/19 05:49 Uncertainty +/-0.0162 Batch 1905901 QC1204354110 486045001 DUP Nickel-59 U -0.926 U 0.110 pCi/g N/A N/A TXJ1 08/17/19 07:31 Uncertainty +/-1.84 +/-0.583 QC1204354111 LCS Nickel-59 90.3 94.8 pCi/g 105 (75%-125%) 08/17/19 08:20 Uncertainty +/-6.04 QC1204354109 MB Nickel-59 U 1.37 pCi/g 08/17/19 07:30 Uncertainty +/-1.66 Rad Gas Flow Batch 1909237 QC1204362415 486045001 DUP Strontium-90 U -0.00869 U 0.0624 pCi/g N/A N/A JXC9 08/22/19 15:28 Uncertainty +/-0.0603 +/-0.0591 QC1204362416 LCS Strontium-90 5.57 5.08 pCi/g 91.2 (75%-125%) 08/22/19 15:28 Uncertainty +/-0.306 QC1204362414 MB Strontium-90 U 0.0313 pCi/g 08/22/19 15:28 Uncertainty +/-0.0725 Rad Liquid Scintillation Batch 1903364 QC1204348116 486045001 DUP Tritium U -0.95 U 0.0122 pCi/g N/A N/A EW3 08/06/19 23:10 Uncertainty +/-3.59 +/-3.43 QC1204348118 LCS Tritium 148 148 pCi/g 99.8 (75%-125%) 08/06/19 23:55 Uncertainty +/-18.0 QC1204348115 MB Tritium U -0.122 pCi/g 08/06/19 22:42 Uncertainty +/-3.51 Page 18 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 486045 Page 5 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 1903364 QC1204348117 486045001 MS Tritium 150 U -0.95 153 pCi/g 102 (75%-125%) EW3 08/06/19 23:37 Uncertainty +/-3.59 +/-18.6 Batch 1905861 QC1204354010 486045001 DUP Iron-55 U 2.10 U -0.955 pCi/g N/A N/A TXJ1 08/17/19 22:30 Uncertainty +/-7.19 +/-7.15 QC1204354011 LCS Iron-55 77.8 71.6 pCi/g 92 (75%-125%) 08/17/19 23:02 Uncertainty +/-8.57 QC1204354009 MB Iron-55 U 7.34 pCi/g 08/17/19 21:58 Uncertainty +/-6.70 Batch 1905868 QC1204354034 486045004 DUP Nickel-63 U -0.88 U -0.589 pCi/g N/A N/A TXJ1 08/17/19 05:28 Uncertainty +/-1.67 +/-2.28 QC1204354035 LCS Nickel-63 95.3 84.5 pCi/g 88.7 (75%-125%) 08/17/19 05:49 Uncertainty +/-3.75 QC1204354033 MB Nickel-63 U -0.0787 pCi/g 08/17/19 05:06 Uncertainty +/-2.05 Batch 1905892 QC1204354086 486045001 DUP Carbon-14 U -0.211 U -0.402 pCi/g N/A N/A TXP3 08/20/19 20:41 Uncertainty +/-2.29 +/-2.09 QC1204354088 LCS Carbon-14 130 123 pCi/g 94.8 (75%-125%) 08/20/19 22:18 Uncertainty +/-4.02 QC1204354085 MB Carbon-14 U 0.302 pCi/g 08/20/19 19:53 Uncertainty +/-2.12 Page 19 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 486045 Page 6 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 1905892 QC1204354087 486045001 MS Carbon-14 137 U -0.211 134 pCi/g 97.9 (75%-125%) TXP3 08/20/19 21:30 Uncertainty +/-2.29 +/-4.30 Batch 1907292 QC1204357424 486045001 DUP Technetium-99 U 0.101 U -0.111 pCi/g N/A N/A JJ3 08/20/19 13:24 Uncertainty +/-0.515 +/-0.498 QC1204357425 LCS Technetium-99 40.6 36.6 pCi/g 90.2 (75%-125%) 08/20/19 13:46 Uncertainty +/-1.77 QC1204357423 MB Technetium-99 U -0.304 pCi/g 08/20/19 12:41 Uncertainty +/-0.392 Notes: Counting Uncertainty is calculated at the 95% confidence level (1.96-sigma). The Qualifiers in this report are defined as follows:
** Analyte is a Tracer compound < Result is less than value reported > Result is greater than value reported BD Results are either below the MDC or tracer recovery is low FA Failed analysis.
H Analytical holding time was exceeded J Value is estimated K Analyte present. Reported value may be biased high. Actual value is expected to be lower. L Analyte present. Reported value may be biased low. Actual value is expected to be higher. M M if above MDC and less than LLD M REMP Result > MDC/CL and < RDL N/A RPD or %Recovery limits do not apply. N1 See case narrative ND Analyte concentration is not detected above the detection limit NJ Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Q One or more quality control criteria have not been met. Refer to the applicable narrative or DER. R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD. UI Gamma Spectroscopy--Uncertain identification Page 20 of 33 SDG: 486045
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 486045 Page 7 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time UJ Gamma Spectroscopy--Uncertain identification UL Not considered detected. The associated number is the reported concentration, which may be inaccurate due to a low bias. X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y Other specific qualifiers were required to properly define the results. Consult case narrative.
^ RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL. Qualifier Not Applicable for Radiochemistry.
h Preparation or preservation holding time was exceeded N/A indicates that spike recovery limits do not apply when sample concentration exceeds spike conc. by a factor of 4 or more or %RPD not applicable.
^ The Relative Percent Difference (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptance criteria when the sample is greater than five times (5X) the contract required detection limit (RL). In cases where either the sample or duplicate value is less than 5X the RL, a control limit of +/- the RL is used to evaluate the DUP result.
- Indicates that a Quality Control parameter was not within specifications.
For PS, PSD, and SDILT results, the values listed are the measured amounts, not final concentrations. Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the QC Summary. Page 21 of 33 SDG: 486045
Radiochemistry Technical Case Narrative LaCrosseSolutions, LLC SDG #: 486045 Product: Alphaspec Isotopic Am241 Am243, Cm243/244, Solid Analytical Method: DOE EML HASL-300, Am-05-RC Modified Analytical Procedure: GL-RAD-A-011 REV# 27 Analytical Batch: 1902013 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1901819 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204345140 Method Blank (MB) 1204345141 486045001(B1-010-001-CIGS-BG02-SB) Sample Duplicate (DUP) 1204345142 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Miscellaneous Information Manual Integration Manual integration of alpha spectroscopy spectra 1204345141 (B1-010-001-CIGS-BG02-SBDUP) was performed to fully separate counts in Regions of Interest which would have been biased. Product: Alphaspec Np, Solid Analytical Method: ASTM C 1475-00 Modified Analytical Procedure: GL-RAD-A-032 REV# 22 Analytical Batch: 1902014 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1901819 Page Laboratories GEL 22 of 33 SDG:llC 486045 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204345143 Method Blank (MB) 1204345144 486045001(B1-010-001-CIGS-BG02-SB) Sample Duplicate (DUP) 1204345145 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Technical Information Recounts Sample 486045002 (B1-010-001-CIGS-BH02-SB) was recounted due to high MDC. The recount is reported. Product: Alphaspec Pu238, 239/240, Solid Analytical Method: DOE EML HASL-300, Pu-11-RC Modified Analytical Procedure: GL-RAD-A-011 REV# 27 Analytical Batch: 1902016 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1901819 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204345149 Method Blank (MB) 1204345150 486045001(B1-010-001-CIGS-BG02-SB) Sample Duplicate (DUP) 1204345151 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Page Laboratories GEL 23 of 33 SDG:llC 486045 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
Miscellaneous Information Additional Comments Sample 486045004 (B1-010-001-CIGS-BK01-SB) did not meet the resolution requirement of having a full width half maximum of 100 keV or less for the tracer; however, the tracer yield requirement was met and the tracer peak is within the tracer region of interest. Product: Dry Weight Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1901819 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB The samples in this SDG were analyzed on an "as received" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 Analytical Method: DOE HASL 300, 4.5.2.3/Ga-01-R Analytical Procedure: GL-RAD-A-013 REV# 27 Analytical Batch: 1901923 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1901819 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204344916 Method Blank (MB) 1204344917 486045001(B1-010-001-CIGS-BG02-SB) Sample Duplicate (DUP) Page Laboratories GEL 24 of 33 SDG:llC 486045 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
1204344918 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Gamma Ni59, Solid Analytical Method: DOE RESL Ni-1 Analytical Procedure: GL-RAD-A-022 REV# 19 Analytical Batch: 1905901 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1901819 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204354109 Method Blank (MB) 1204354110 486045001(B1-010-001-CIGS-BG02-SB) Sample Duplicate (DUP) 1204354111 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: GFPC, Sr90, Solid Analytical Method: EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Analytical Procedure: GL-RAD-A-004 REV# 21 Analytical Batch: 1909237 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1901819 Page Laboratories GEL 25 of 33 SDG:llC 486045 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204362414 Method Blank (MB) 1204362415 486045001(B1-010-001-CIGS-BG02-SB) Sample Duplicate (DUP) 1204362416 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Liquid Scint Pu241, Solid Analytical Method: DOE EML HASL-300, Pu-11-RC Modified Analytical Procedure: GL-RAD-A-035 REV# 21 Analytical Batch: 1908504 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1901819 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204360626 Method Blank (MB) 1204360627 486045001(B1-010-001-CIGS-BG02-SB) Sample Duplicate (DUP) 1204360628 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Technical Information Sample Re-prep/Re-analysis Samples were reprepped to verify the results. The re-analysis is being reported. Page Laboratories GEL 26 of 33 SDG:llC 486045 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
Miscellaneous Information Additional Comments Samples 1204360626 (MB) and 486045001 (B1-010-001-CIGS-BG02-SB) did not meet the resolution requirement of having a full width half maximum of 100 keV or less for the tracer; however, the tracer yield requirement was met and the tracer peaks are within the tracer region of interest. Product: LSC, Tritium Distillation, Solid Analytical Method: EPA 906.0 Modified Analytical Procedure: GL-RAD-A-002 REV# 22 Analytical Batch: 1903364 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204348115 Method Blank (MB) 1204348116 486045001(B1-010-001-CIGS-BG02-SB) Sample Duplicate (DUP) 1204348117 486045001(B1-010-001-CIGS-BG02-SB) Matrix Spike (MS) 1204348118 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on an "as received" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Liquid Scint Fe55, Solid Analytical Method: DOE RESL Fe-1, Modified Analytical Procedure: GL-RAD-A-040 REV# 13 Analytical Batch: 1905861 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1901819 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB Page Laboratories GEL 27 of 33 SDG:llC 486045 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204354009 Method Blank (MB) 1204354010 486045001(B1-010-001-CIGS-BG02-SB) Sample Duplicate (DUP) 1204354011 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Technical Information Recounts Sample 486045002 (B1-010-001-CIGS-BH02-SB) was recounted due to high MDC. The recount is reported. Product: Liquid Scint Ni63, Solid Analytical Method: DOE RESL Ni-1, Modified Analytical Procedure: GL-RAD-A-022 REV# 19 Analytical Batch: 1905868 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1901819 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204354033 Method Blank (MB) 1204354034 486045004(B1-010-001-CIGS-BK01-SB) Sample Duplicate (DUP) 1204354035 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Page Laboratories GEL 28 of 33 SDG:llC 486045 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
Product: Liquid Scint C14, Solid Analytical Method: EPA EERF C-01 Modified Analytical Procedure: GL-RAD-A-003 REV# 16 Analytical Batch: 1905892 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204354085 Method Blank (MB) 1204354086 486045001(B1-010-001-CIGS-BG02-SB) Sample Duplicate (DUP) 1204354087 486045001(B1-010-001-CIGS-BG02-SB) Matrix Spike (MS) 1204354088 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on an "as received" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Liquid Scint Tc99, Solid Analytical Method: DOE EML HASL-300, Tc-02-RC Modified Analytical Procedure: GL-RAD-A-059 REV# 5 Analytical Batch: 1907292 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 486045001 B1-010-001-CIGS-BG02-SB 486045002 B1-010-001-CIGS-BH02-SB 486045003 B1-010-001-CIGS-BJ02-SB 486045004 B1-010-001-CIGS-BK01-SB 1204357423 Method Blank (MB) 1204357424 486045001(B1-010-001-CIGS-BG02-SB) Sample Duplicate (DUP) 1204357425 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on an "as received" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Page Laboratories GEL 29 of 33 SDG:llC 486045 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
Certification Statement Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless otherwise noted in the analytical case narrative. Page Laboratories GEL 30 of 33 SDG:llC 486045 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
Page 31 of 33 SDG: 486045 Pase* Pmj~cl ~ 1 LAC'RWR of
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PO Number: 672583 GEL W{Jrk Order Number: GEL Project Manager: Fax: (8~:l\ 766-1178 lJ!.AJ/OL/ I::, Clienl Na111e. LIi Crosse Soltuions Phone# 608"689-4259 Sample Annlysi~ Requested 1~1 (Fill in the number of containers for each lest) Projce1ISi1c Name* LACBWR-Ocnoa WI Fax~ ShnnM ch;. c ~-- P,-,,,;crvat,ve Type(6)
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R<linqui,h<<l 8)'(S;sncd) Date Tm,o R<<ci,*od ~y (signed) , Dale Ti"'< Fa, Resulls: r 1 Yes Xl '<o 1.KevinLMwrav/ 7/ZJ,i/"f /000 1"" -,, ~ "I*, Scloc1Delivcrabk' 1 CofA f 1 ncsummar.* r llesel I fXlLcv<:12 J 1Levcl3 r 1Lc,e14 2 U 2 \. ! ;/ddilimwlllcmark.,* None 3 3 For Lab ReceMng V.,;e Only: C,r.,wdySeo/ /Iliac(' [ ) Ye-' [ ) No Cuoler Temp: "C
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4J ~1,.,,, COO<,* DW"Driru,,~ w,,.,._ GW* o,..,,,,,_, sw s..,roe, ,1*~,'t. W\\'-Wa,tc w..cr, w-w ..,~. '1L*),1i,, t,q,.i. SO *S,,,I_ SO-ScJ,oo.,nl. St.*Sl"Og,. SS=Sol,tl w,,,,. O*Oil. fafoltcr. r=w,I". U*llm><. F=Fi:c,I. N"~=I 0 j,) s,.,,,1o An,1,.,, R<4~s<od. Aoal,-i,cnl a,olh,O "'"'"""' (,o_ s,oou, .OIUBJ7<7<1A) '"" """"-'t of"°'""" "'°"dcdfoc,..,h 1, ,, ;-;;am
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- N;t"< A<iJ, SIi - So<irum H,Oro,iJ,.SA - Sulrun, Add, M - A=I*< Aoi<l. HX - lh,nc, ST- So<in,m Tl>'°""fal<.lf ""P"""'""'., a.J.l,;,j - k"e field bl.u,l 7.J , , ~4- 1, haradcrlsllc Ha,uds 1Lis1elel!gnirnblc LW~ Lis(od Wn.ste OT - Ottier / Unknown /JdlJ.w rogllnt/l)g /nmJ/llng andl~r RCRA Mcul< CO"' Corrosive (l*:K,l'ond U-Mredu-o-<lc.<.) (I.e.: Hip_h-'/mrpfl. asheslo.,, beryllium, ,rritoill.<, <1/J,.., dispm<(Jfcr,ncut11< (,,e.: Ongi,ref 1,., = Ars:",c Hg.a Merc~ry RE" Reactive Wa,teCtJde(.<): mi.,c :,e~//1, lr=ard,. Nc.j _,;n;ple($), iypeof.,i1e c,,//c,;;/edfrom, odd Ba= Bantnn SO"' Scleon,m ~~~~~~"---, Dcscriptwn: ""1lrtc,:,,. ~k:.)
Cd =C'admnnn Ag=Silvcr jTSCA RtIDolaled j Cr - Chromium MR"' Misc. RCR,, metals PCB"' Po\;*ehlonnated l'b n Lead b,phen;-ls
SAMPLE REC ElPT & REV[EW FORM Clicn t: /- 11. l/.- t~ SOG/ARICOC/Work Order: '_!H..\ ._ m
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'lf Net Counts > lOOcp,n 011 .a111ples nOI marked "radjoactive". contact lhe Radia1ion Safuty Group for furtt1er in=1igat1on.
-<a.ard Class Ship!}ed:
UN~: A)Sl,iooed ai a DOT Hazardous? \J lfUN29lO. Is 1be Radioactive Shipu1et11 Sun-ey Co,np!iant? Yes~ No_ BJ Did the clhon< desiguate Che sa111ples are lo received as rndjoactive 1 CJ Did the RSO d,1<sify1he s.1mp!os as radioactive? be 111 Coe notation or radioacnve Sliekers 011 eon1ai Ma~unum Net Couam Obsen,ed* (Obsorved Count ners oqunl cliem dosignnti~n.
, .. Area Background Counts): 1/J Cl'M C!f,s.siliecl os: Rad l Rad 2 RadJ I mRIHr DJ Did the client desiynat< sarnpl~* arc '
ha.ardous? ~ COJ notation or liaza,rd label~ c., oonmiuers eq""I c~ient dosignnti~n. tt Dor Eis yes, se!Ol:t Ha,.,rds lxlow. EJ Did the RSO idcntifyoossible!1azards? \I PCB's flommabl~ Foreign Soil RCR,\ ,\sbestos S<<ylliurn 0~1er. Shipp S:unplc Receipt Cri1eriu t z< z* Commcnb/Q"alifl*rs (R~quirCII for Non-Conform ing hems) I sealeding containers received intact n11d Cirdo App!icablo: Seals b<ok,n D,mose<t oont,io o, teak;.,~ <ontairm Othor{de<<:rol>oJ
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Chain of custody documents indude<l Circlo Applioabl,: Clionl oontocted ,nd pro,'tdo 2 d COC with Shi mcm? COC creotod "P'"' <ecoipl 3 Samples requ1ri11g cold presen,ation witl1in (0 !: 6 deg C)?* Daily chc"'k pcrfonned and pass~d on IR Pr=n- ation Method: Wei kc le,: Paoks
'al! tempemmru.s arc r,:cotded in Tcn1per~1tm: Oc,*itc Soriol N*
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I'~, "'"" dd< .o1M ff Ycs, are Encores or Soil Kits pre.s(:ul For solids?
\'es No NA (lfyes. take to VOA FrCozor)
Do any sainples require Volatile o liquid VOA vi~I, co111ain acid preserva1ion? 7 Yes No NA (Jf unknoWll. sell!C! No) Analysis"' .'\re liquid VOA ,*ials free ofhcadspace? Yes~ No_ NA
$;,nr,le ID", *"d ""'"'" "" ,IToorod, -
8 Samples rcce;\"c>J withi11 holding lime? ID'sand 1est, affec1ed: Sample !D"s on COC nint<.ll ID"s on m*s and containers affec1ed:
' bottles?
Date & time on COC match date & time iO Circle Applicable: No dales on C<J111,tincrs No times on containers COC missing ;nro on bmtks ? O!hcr(describe) Number or contai<>ers received matcl1 Circle Applicable: No coma;ner coum on Coe
" number indieated on COC"?
Are sample comainers identifiable as Other(describe)
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.Ill Circle App!icablo:
13 No1 rclinquisl,ed Other (des,;ribe) relinq~ished/r.:ceived sections: Co,mncnts (Use Continuation Fonn ifae.:ded): PM('" PM.-\) ,oview: [niti,,ls Dmc 7 f 311 1-"1 !>age ...L ... of I GL-CHL-SR-001 Rev 6 Page 32 of 33 SDG: 486045
List of current GEL Certifications as of 23 August 2019 State Certification Alaska 17018 Arkansas 880651 CLIA 42D0904046 California 2940 Colorado SC00012 Connecticut PH0169 DoD ELAP/ ISO17025 A2LA 2567.01 Florida NELAP E87156 Foreign Soils Permit P3301500283, P3301500253 Georgia SC00012 Georgia SDWA 967 Hawaii SC00012 Idaho SC00012 Illinois NELAP 200029 Indiana CSC01 Kansas NELAP E10332 Kentucky SDWA 90129 Kentucky Wastewater 90129 Louisiana Drinking Water LA024 Louisiana NELAP 03046 (AI33904) Maine 2019020 Maryland 270 Massachusetts MSC012 Michigan 9976 Mississippi SC00012 Nebraska NEOS2613 Nevada SC0001220201 New Hampshire NELAP 2054 New Jersey NELAP SC002 New Mexico SC00012 New York NELAP 11501 North Carolina 233 North Carolina SDWA 45709 North Dakota R158 Oklahoma 9904 Pennsylvania NELAP 6800485 Puerto Rico SC00012 S. Carolina Radiochem 10120002 South Carolina Chemistry 10120001 Tennessee TN 02934 Texas NELAP T1047042351915 Utah NELAP SC00012201928 Vermont VT87156 Virginia NELAP 460202 Washington C780 Page 33 of 33 SDG: 486045}}