ML20352A262
| ML20352A262 | |
| 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: ML20352A262 (458) | |
Text
{{#Wiki_filter:~ LACROSSESOLUTIONS LA CROSSE BOILING WATER REACTOR FINAL STATUS SURVEY RELEASE RECORD SURVEY UNIT L2-011-101 AREA NORTH OF LSE FENCE REVISION 1
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FSS RELEASE RECORD REVISION 1 SURVEY UNIT L2-011-101 AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Robert F. Yetter III Oct 25 2020 1:55 PM PREPARED BY / DATE: cosign R. F. Yetter III, FSS Specialist Mitchell Uz REVIEWED BY / DATE:
?ltitddt'U, Oct 27 2020 8:00 AM cosi n M. D. Uz, FSS Specialist Robert F. Yetter 9lJ,.e,d :J. 'lJ,elwt, Oct 27 2020 11 :05 AM REVIEWED BY / DATE: cosign R. Yetter, Director, Radiological Site Closure Sarah Roberts Oct 27 2020 12:54 PM REVIEWED BY / DATE: cosign S. Roberts, VP Radiological Programs Scott G. Zoller Oct 29 2020 9:36 AM APPROVED BY / DATE:
S. Zoller, FSS Manager 1
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS 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 ...................................................................................................................... 19
- 7. SURVEY RESULTS .......................................................................................................................................... 20
- 8. QUALITY CONTROL ...................................................................................................................................... 28
- 9. INVESTIGATIONS AND RESULTS .............................................................................................................. 28
- 10. REMEDIATION AND RESULTS ................................................................................................................... 28
- 11. CHANGES FROM THE FINAL STATUS SURVEY PLAN ........................................................................ 28
- 12. DATA QUALITY ASSESSMENT (DQA) ....................................................................................................... 28
- 13. ANOMALIES ..................................................................................................................................................... 29
- 14. CONCLUSION .................................................................................................................................................. 29
- 15. REFERENCES................................................................................................................................................... 30
- 16. ATTACHMENTS .............................................................................................................................................. 30 ATTACHMENT 1 - FIGURE ................................................................................................................................... 32 ATTACHMENT 2 - SCAN DATA ............................................................................................................................. 34 ATTACHMENT 3 - SIGN TEST ............................................................................................................................... 39 ATTACHMENT 4 - QUALITY CONTROL ASSESSMENT ...................................................................................... 41 ATTACHMENT 5 - CONSULTATION TRIGGERS FOR RESIDENTIAL SOIL CONCENTRATIONS ................... 43 ATTACHMENT 6 - GRAPHICAL PRESENTATIONS ............................................................................................. 45 ATTACHMENT 7 - SAMPLE ANALYTICAL REPORTS ......................................................................................... 49 ATTACHMENT 8 - GEL LABORATORIES ANALYTICAL REPORTS ................................................................. 322 2
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS LIST OF TABLES Table 3 Statistical Quantities for Cs-137 and Co-60 from the Characterization Survey .................................. 7 Table 3 Off-site Analysis for Characterization Samples ..................................................................................... 8 Table 3 Off-site Analysis for RA Samples ............................................................................................................ 9 Table 4 Dose Significant Radionuclides and Mixture for Soil .......................................................................... 11 Table 4 Base Case DCGLs for Soil ...................................................................................................................... 13 Table 4 Operational DCGLs for Soil ................................................................................................................... 13 Table 5 Soil Surrogate Ratio ............................................................................................................................... 14 Table 5 Action Levels for Survey Unit L2-011-101 ........................................................................................... 15 Table 5 Systematic Sample Locations ................................................................................................................. 16 Table 5 Judgmental Sample Locations ............................................................................................................... 17 Table 5 Investigation Levels ................................................................................................................................ 18 Table 5 Synopsis of Survey Design...................................................................................................................... 18 Table 7 Synopsis of Scan Results ........................................................................................................................ 20 Table 7 Summary of Gamma Spectroscopy Results for Samples Comprising the Statistical Sample Population ........................................................................................................................................................... 24 Table 7 Basic Statistical Properties of Systematic Sample Population ............................................................. 25 Table 7 Off-Site Analysis Results......................................................................................................................... 25 Table 7 Summary of Gamma Spectroscopy Results for Judgmental Samples ................................................ 25 Table 7 Summary of Gamma Spectroscopy Results for QC Samples .............................................................. 26 Table 7 Sum-of-Fractions for Systematic and QC Samples .............................................................................. 26 Table 7 Sum-of-Fractions for Judgmental Samples .......................................................................................... 27 Table 16 Survey Unit L2-011-101 Complete Scan Data .................................................................................... 35 Table 16 Survey Unit L2-011-101 Sign Test ....................................................................................................... 40 Table 16 Survey Unit L2-011-101 QC Assessment ............................................................................................ 42 LIST OF FIGURES Figure 16 Survey Unit L2-011-101 Systematic and Judgmental Sample Locations Map ............................... 33 Figure 16 Quantile Plot for Cs-137 Concentration ............................................................................................ 46 Figure 16 Histogram for Cs-137 Concentration ................................................................................................. 47 Figure 16 Retrospective Power Curve for Survey Unit L2-011-101 ................................................................. 48 3
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable DQA Data Quality Assessment DQO Data Quality Objective DCGL Derived Concentration Guideline Level DCGLS Soil Derived Concentration Guideline Level FSS Final Status Survey GPS Global Positioning System HSA Historical Site Assessment HTD Hard-to-Detect IC Insignificant Contributors LACBWR La Crosse Boiling Water Reactor LBGR Lower Bound of the Gray Region LSE LACBWR Site Enclosure LTP License Termination Plan MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration NaI Sodium Iodide OpDCGLS Soil Operational Derived Concentration Guideline Level QAPP Quality Assurance Project Plan QC Quality Control RA Radiological Assessment ROC Radionuclides of Concern SOF Sum-of-Fractions TEDE Total Effective Dose Equivalent UBGR Upper Bound of the Gray Region UCL Upper Confidence Limit 4
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS
- 1. EXECUTIVE
SUMMARY
This Final Status Survey (FSS) Release Record for survey unit L2-011-101, Area North of LACBWR Site Enclosure (LSE) Fence, 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). Survey unit L2-011-101, an open land survey unit, has a MARSSIM classification of 2. A survey plan was designed based upon use of the Sign Test as the nonparametric statistical test for compliance. Both the Type I () and Type II () decision error rates were set at 0.05. As a systematic sample population, fourteen (14) soil samples were acquired from the survey unit. In addition, soil scanning was performed on 25% of the total surface area in the survey unit. The analytical results for all soil samples taken in survey unit L2-011-101 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 0.0681 when applying the respective Operational Derived Concentration Guideline Levels (OpDCGLS) for soil. Therefore, the null hypothesis is rejected and survey unit L2-011-101 is acceptable for unrestricted release. The mean SOF when applying the respective Base Case DCGLs (DCGLS) for soil is 0.0124. This SOF equates to a dose for the survey unit of 0.3103 mrem/yr.
- 2. SURVEY UNIT DESCRIPTION Survey unit L2-011-101 is an impacted Class 2 open land survey unit. The surface area of the survey unit is 5,728 m2.
The boundary of the survey unit and the location of the soil samples were defined using a Global Positioning System (GPS). Refer to Attachment 1 of this report for a figure depicting survey unit L2-011-101. 5
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS
- 3. CLASSIFICATION BASIS Survey unit L2-011-101 was identified in the Historical Site Assessment (HSA)
(Reference 5) as a Class 2 survey unit. The following summarizes the results of the characterization survey for survey unit L2-011-101. The initial site characterization surveys performed by EnergySolutions were conducted between October 9, 2014, and August 6, 2015. In total, thirteen (13) surface soil samples, sixteen (16) subsurface soil samples, and six (6) asphalt samples were collected in survey unit L2-011-101. All samples were analyzed by the on-site gamma spectroscopy system. For surface soil samples, Cs-137 was detected at concentrations above Minimum Detectable Concentration (MDC) in eight (8) of the samples, at a maximum concentration of 1.39E-01 pCi/g. Co-60 was not detected at concentrations above MDC in any of the surface soil samples. For subsurface soil samples, Cs-137 was detected at concentrations above MDC in two (2) of the samples, at a maximum concentration of 8.80E-02 pCi/g. Co-60 was detected at concentrations above MDC in one (1) of the subsurface soil samples, at a maximum concentration of 1.12E-01 pCi/g. For asphalt samples, no ROC were detected at concentrations above MDC. A summary of the analyses for the surface soil, subsurface soil, and asphalt samples taken during site characterization are presented in Table 3-1. Two (2) surface soil, three (3) subsurface soil, two (2) sediment, and two (2) asphalt samples from characterization were sent to Test America Laboratories for off-site analysis. A summary of the off-site analyses is presented in Table 3-2. 6
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Table 3 Statistical Quantities for Cs-137 and Co-60 from the Characterization Survey Surface Soil Co-60 Cs-137
# of Samples 13
# >MDC 0 8 Mean (pCi/g) 7.30E-02 9.00E-02 Median (pCi/g) 7.70E-02 1.00E-01 Max (pCi/g) 1.06E-01 1.39E-01 Min (pCi/g) 5.30E-02 4.10E-02 Standard Deviation (pCi/g) 1.60E-02 3.00E-02 Subsurface Soil Co-60 Cs-137
# of Samples 16
# >MDC 1 2 Mean (pCi/g) 5.20E-02 4.90E-02 Median (pCi/g) 4.60E-02 4.80E-02 Max (pCi/g) 1.12E-01 8.80E-02 Min (pCi/g) 4.00E-02 3.40E-02 Standard Deviation (pCi/g) 1.80E-02 1.20E-02 Asphalt Co-60 Cs-137
# of Samples 6
# >MDC 0 0 Mean (pCi/g) 5.10E-02 5.10E-02 Median (pCi/g) 5.10E-02 5.10E-02 Max (pCi/g) 5.40E-02 5.40E-02 Min (pCi/g) 4.70E-02 4.70E-02 Standard Deviation (pCi/g) 2.00E-03 3.00E-03 7
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Table 3 Off-site Analysis for Characterization Samples Fe- Ni- Co- Ni- Sr- Nb- Tc- Cs- Pm- Eu- Eu- Eu- Np- Pu- Pu- Pu- Am- Am- Cm-Radionuclide H-3 C-14 55 59 60 63 90 94 99 137 147 152 154 155 237 238 239/240 241 241 243 243/244 L2011101-CJ- 0.096 0.011 0.137 0.041 0.098 0.033 0.031 GS-001-SM L2011101-CR- 0.023 0.016 0.017 0.039 0.131 0.039 0.038 PA-003-AV L2011101-QJ- 0.518 0.727 2.290 2.660 0.016 4.030 0.273 0.014 0.643 0.015 0.705 0.033 0.108 0.040 0.022 0.028 0.025 2.470 0.015 0.022 0.019 GS-001-SB L2011101-QJ- 2.040 0.707 2.240 2.950 0.049 4.140 0.523 0.018 0.585 0.107 0.615 0.048 0.178 0.049 0.026 0.045 0.021 3.100 0.037 0.036 0.034 GS-001-SM L2011101-QJ- 0.012 0.020 0.080 0.060 0.188 0.091 0.042 GS-001-SS L2011101-QQ- 0.017 0.012 0.013 0.040 0.127 0.037 0.031 GS-001-SB L2011101-QQ- 11.810 0.726 2.590 2.600 0.035 3.720 0.255 0.035 0.532 0.103 0.779 0.097 0.205 0.102 0.023 0.037 0.024 2.800 0.019 0.015 0.015 GS-001-SS L2011101-QQ- 2.500 0.731 1.940 2.680 0.017 3.870 0.314 0.014 0.616 0.016 0.697 0.037 0.119 0.041 0.019 0.039 0.016 2.920 0.020 0.028 0.016 GS-002-SB L2011101-QQ- 0.022 0.015 0.015 0.046 0.135 0.042 0.040 PA-001-AV Note: Bold values indicate concentration greater than MDC. Unbolded values indicate the MDC value. All values in pCi/g. Blank cells indicate that a particular radionuclide was not included in the analysis. 8
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS 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 Table 4 of TSD RS-TD-313196-004, LACBWR Soil DCGL, Basement Concrete DCGL, and Buried Pipe DCGL (Reference 6) for soil. If the IC dose calculated is less than the IC dose assigned for DCGL adjustment, then no further action will be taken. If the actual IC dose calculated from the sample result is greater than the IC dose assigned for DCGL adjustment, then a minimum of five (5) additional investigation samples will be taken around the original sample location. Each investigation sample will be analyzed by the on-site gamma spectroscopy system and sent for 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. A Radiological Assessment (RA) in survey unit L2-011-101 was performed in June of 2019 to assess the soil beneath LACBWR Warehouses 1, 2, and 3. Thirty-nine (39) soil samples were collected and analyzed by the on-site gamma spectroscopy system. The average SOF of the sample set was 0.023, with a standard deviation 0.008. The RA data was used to design the FSS. Two samples from the RA were sent off-site for full suite radionuclide analysis. An assessment of the results of continuing characterization confirmed that the IC dose is unchanged. The maximum calculated IC dose was 0.0804 mrem/yr, which is below the 2.5 mrem/yr limit provided in the LTP for DCGL adjustment. A summary of the off-site analytical results for continuing characterization (RA) samples is provided in Table 3-3 below. Only Cs-137 was detected at concentrations greater than MDC in the off-site RA samples. Table 3 Off-site Analysis for RA Samples L2-SUB- L2-SUB-WRS- WRS-Radionuclide ASGS- AJGS-10A-SB 15A-SB H-3 2.56E+00 5.69E-02 C-14 -3.08E-01 -1.75E+00 Fe-55 -3.58E+00 -7.22E+00 Ni-59 7.07E-03 -1.86E-02 Co-60 3.21E-02 -8.37E-03 Ni-63 -4.78E-01 5.70E-01 9
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS L2-SUB- L2-SUB-WRS- WRS-Radionuclide ASGS- AJGS-10A-SB 15A-SB Sr-90 -8.72E-03 -6.96E-02 Nb-94 5.36E-02 -4.00E-03 Tc-99 4.25E-02 -3.04E-01 Cs-137 3.41E-02 1.87E-01 Eu-152 3.90E-02 1.15E-02 Eu-154 -3.00E-02 -1.29E-01 Eu-155 4.28E-02 4.86E-02 Np-237 -5.46E-02 -4.56E-02 Pu-238 9.43E-02 -3.11E-02 Pu-239/240 -7.88E-04 -3.93E-02 Pu-241 -8.38E-01 -1.68E+00 Am-241 4.62E-02 1.79E-02 Am-243 2.89E-02 -5.38E-04 Cm-243/244 0.00E+00 -6.03E-03 Note: Bold values indicate positively identified radionuclide activities. Based upon review of the historical information, the results of the characterization survey data and RA data, and completion of a final Survey Unit Classification Worksheet, the correct final classification of survey unit L2-011-101 was determined to be Class 2.
- 4. DATA QUALITY OBJECTIVES (DQO)
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, utilized in accordance with MARSSIM, is described in the LACBWR LTP. The appropriate design for a given survey was developed using the DQO process as outlined in Appendix D of MARSSIM. A summary of seven steps of the DQO process are outlined as follows. The DQO process incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis. Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition. The baseline condition is technically known as the null hypothesis. Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection. In designing the survey plan, the underlying assumption, or null hypothesis was that residual activity in the survey unit exceeded the release criteria. Rejection of the null 10
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS hypothesis would indicate that residual activity within the survey unit does not exceed the release criteria. Therefore, the survey unit would satisfy the primary objective of the FSS sample plan. The primary objective of the FSS sample plan is to demonstrate that the level of residual radioactivity in survey unit L2-011-101 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). EnergySolutions TSD RS-TD-313196-001, Radionuclides of Concern during LACBWR Decommissioning (Reference 7) established the basis for an initial suite of potential ROC for decommissioning. LTP Chapter 2 provides detailed characterization data that describes the results of surveys taken of soil. Surface and subsurface soil samples were taken in each impacted open land survey units and analyzed for the presence of plant-derived radionuclides. The results of surface and subsurface soil characterization in the impacted area surrounding LACBWR indicate that there is minimal residual radioactivity in soil. IC 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 IC and were 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. The LTP, Section 6.14.1, discusses the process used to derive the ROC for the decommissioning of LACBWR, including the elimination of IC from the initial suite. Table 4-1 presents the ROC for the decommissioning of soil at LACBWR and the normalized mixture fractions based on the radionuclide mixture. Table 4 Dose Significant Radionuclides and Mixture for Soil Fraction of Total Activity Radionuclide (normalized)(1) Co-60 0.064 Sr-90 0.098 Cs-137 0.829 Eu-152 0.005 Eu-154 0.003 11
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS (1) Based on maximum percent of total activity from Table 22 of RS-TD-313196-001, normalized to one for the dose significant radionuclides. The LTP, Section 5.2 states that each radionuclide-specific Base Case DCGL is equivalent to the level of residual radioactivity (above background levels) that could, when considered independently, result in a Total Effective Dose Equivalent (TEDE) of 25 mrem/yr to an Average Member of the Critical Group. To ensure that the summation of dose from each source term is 25 mrem/yr or less after all FSS is completed, the Base Case DCGLs are reduced based on an expected, or a priori, fraction of the 25 mrem/yr dose limit from each source term. The reduced DCGLs, or Operational DCGLs can be related to the Base Case DCGLs as an expected fraction of dose based on an a priori assessment of what the expected dose should be based on the results of site characterization, process knowledge, and the extent of planned remediation. The Operational DCGL is then used as the DCGL for the FSS design of the survey unit (e.g., calculation of surrogate DCGLs, investigation levels). Details of the Operational DCGLs derived for each dose component and the basis for the applied a priori dose fractions are provided in LC-FS-TSD-002, Operational Derived Concentration Guideline Levels for Final Status Survey (Reference 9). Multiple ROCs are known to be present at LACBWR. The dose contribution from each ROC is accounted for using the SOF to ensure that the total dose from all ROC does not exceed the dose criterion. A Base Case DCGL that is established for the average residual radioactivity in a survey unit is equivalent to a DCGLW. In Class 1 land survey units, the DCGLW can be multiplied by Area Factors to obtain a Base Case DCGL that represents the same dose to an individual for residual radioactivity over a smaller area within a survey unit. At LACBWR, compliance is demonstrated through the summation of dose from five (5) distinct source terms (i.e., basements, soils, buried pipe, above-ground structures, and groundwater) for the end-state. When applied to soil, the DCGLs are expressed in units of activity per unit of mass (pCi/g). For LACBWR, soil is defined as a layer of soil beginning at the surface but extending to a depth of 1 m to allow for flexibility in compliance demonstration if contamination deeper than 0.15 m is encountered. Based on characterization data and historical information, there are no expectations of encountering a source term geometry that is comprised of a clean surface layer of soil over a contaminated subsurface soil layer. EnergySolutions TSD RS-TD-313196-004 and the LTP, Section 6.8, provide the exposure scenarios and modeling parameters that were used to calculate the site-specific soil DCGLs. The adjusted soil DCGLs for the unrestricted release of open land survey units as provided in the LTP, Section 6.16.1, are reproduced in Table 4-2. The IC percentages for the most limiting 12
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS basement scenario was used to adjust the DCGLs for soil to account for the dose from the eliminated insignificant contributor radionuclides. Table 4 Base Case DCGLs for Soil DCGLS Radionuclide (pCi/g) Co-60 10.6 Sr-90 5470 Cs-137 48.3 Eu-152 23.6 Eu-154 21.9 The Operational DCGLs are then used as the DCGL for the FSS design of the survey unit (e.g., calculation of surrogate DCGLs, investigation levels). The OpDCGLS for the unrestricted release of soil are provided in Table 4-3. Table 4 Operational DCGLs for Soil OpDCGLS Radionuclide (pCi/g) Co-60 3.83 Sr-90 1970.45 Cs-137 17.39 Eu-152 8.51 Eu-154 7.89 Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the Operational DCGL. Survey instrument response checks were required prior to issuance and after the instrument had been used. Control and accountability of survey instruments was required to assure the quality and prevent the loss of data. As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. The actual reported value was used as the recorded FSS result for measurement and/or sample values that are less than MDC. Negative values were recorded as zero. Results were not reported as less than MDC (< MDC). Sample report 13
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS summaries included unique sample identification, analytical method, radionuclide, result, uncertainty, laboratory data qualifiers, units, and the observed MDC. In accordance with the LTP, for laboratory analysis, MDCs less than 10% of the Operational DCGL were preferable while MDCs up to 50% of the Operational DCGL were acceptable. The minimum acceptable MDC for measurements obtained using field instruments was 50% of the applicable Operational DCGL.
- 5. SURVEY DESIGN The level of effort associated with planning a survey is based on the complexity of the survey and nature of the hazards. Guidance for preparing FSS plans is provided in procedure LC-FS-PR-002, Final Status Survey Package Development.
The DQO process validated that Co-60, Sr-90, Cs-137, Eu-152, and Eu-154 would be the ROC in survey unit L2-011-101 as presented in LTP Section 5.1. During the data analysis of the FSS results, concentrations for the HTD ROC Sr-90 are inferred using a surrogate approach. Cs-137 is the principle surrogate radionuclide for Sr-90. During characterization, both Sr-90 and Cs-137 was positively detected in all thirty (30) concrete core samples assessed in the Reactor Building, Tunnel, and Waste Treatment Building. The 95% Upper Confidence Limit (UCL) of the Cs-137 fractions was chosen to represent the overall nuclide mix for soils/buried pipe, the Reactor Building, and the Waste Gas Tank Vault. The surrogate ratio for soil is given in Table 5-1. Table 5 Soil Surrogate Ratio Radionuclides Ratio Sr-90/Cs-137 0.502 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 Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide 14
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS 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) = = 17.31 / 1 0.502 [(17.39 )+( )] (137) 1970.45(90) The surrogate Operational DCGL that was used for Cs-137 in this survey unit for direct comparison of sample results to demonstrate compliance was 17.31 pCi/g. The action levels for survey unit L2-011-101 are based on the Operational DCGL and are presented in Table 5-2. Table 5 Action Levels for Survey Unit L2-011-101 Action Level ROC (pCi/g) Co-60 3.83(1) Cs-137 17.31(2) Eu-152 8.51(1) Eu-154 7.89(1) (1) Based on the Operational DCGL. (2) Based on the surrogate adjusted DCGL of Cs-137 while inferring Sr-90. The Sign Test was selected as the non-parametric statistical test. The use of the Sign Test did not require the selection or use of a background reference area, which simplified survey design and implementation. This approach was conservative since it included background Cs-137 as part of the sample set. The number of soil samples for FSS was determined in accordance with procedure LC-FS-PR-002. 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), 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 calculated value of / exceeds three (3), an adjusted value of three (3) will be used for /. The / for survey unit L2-011-101, based on the data for surface soil samples collected during the RA of survey unit L2-011-101, was calculated as follows: 15
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Equation 3
/ = (1 - 0.023) / 0.008 = 122.13 As the calculated relative shift was greater than three (3), a value of three (3) was used as the adjusted /. Both the Type I error (i.e., value) and the Type II error (i.e., value) was set at 0.05. The sample size from Table 5.5 of MARSSIM that equates to the Type I and Type II error of 0.05 for use with the Sign Test is an N value of fourteen (14).
A Prospective Power Curve was generated using COMPASS, a software package developed under the sponsorship of the United States Nuclear Regulatory Commission (USNRC) for implementation of the MARSSIM in support of the decommissioning license termination rule (10CFR20, Subpart E). The result of the COMPASS computer run showed adequate power for the survey design. As the survey unit was classified as Class 2 sample locations were selected based on a systematic triangular grid with a random starting point. The systematic locations of the soil samples were selected using Visual Sample Plan (VSP), in accordance with LC-FS-PR-002. Input parameters included use of aerial photographs and the systematic sampling tool set with a predetermined number (14) of samples. The systematic coordinates generated with VSP were integrated with a GPS to identify sample locations in the field. Table 5-3 lists the systematic samples collected for FSS and the corresponding GPS coordinates, based on the Wisconsin State Plane North American Datum 1983 coordinate system. Table 5 Systematic Sample Locations Sample ID Northing Easting L2-011-101-FSGS-001-SS 570848.2236 1642163.1863 L2-011-101-FSPA-002-AV 570848.2236 1642234.4967 L2-011-101-FSPA-003-AV 570971.7368 1642305.8071 L2-011-101-FSGS-004-SS 571095.2500 1642305.8071 L2-011-101-FSGS-005-SS 571218.7632 1642091.8759 L2-011-101-FSGS-006-SS 571218.7632 1642234.4967 L2-011-101-FSGS-007-SS 571280.5198 1642127.5311 L2-011-101-FSGS-008-SS 571280.5198 1642198.8415 L2-011-101-FSGS-009-SS 571280.5198 1642270.1519 L2-011-101-FSGS-010-SS 571342.2764 1642091.8759 L2-011-101-FSGS-011-SS 571342.2764 1642163.1863 L2-011-101-FSGS-012-SS 571342.2764 1642234.4967 16
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Sample ID Northing Easting L2-011-101-FSGS-013-SS 571404.0330 1642198.8415 L2-011-101-FSGS-014-SS 571404.0330 1642234.4967 In accordance with the sample plan, at least one (1) judgmental sample is required from the survey unit. The number of judgmental samples actually obtained was three (3), which brings the total number of samples collected for the FSS of survey unit L2-011-101 to seventeen (17). Table 5-4 lists the judgmental samples collected for FSS and the corresponding GPS coordinates. Table 5 Judgmental Sample Locations Sample ID Northing Easting L2-011-101-FJGS-015-SS 570824.9730 1642226.3320 L2-011-101-FSGS-002-SS 570848.2236 1642234.4967 L2-011-101-FSGS-003-SS 570971.7368 1642305.8071 The LACBWR LTP, Section 5.1 states that soil samples will be collected during FSS to confirm the HTD to surrogate radionuclide ratio. Ten percent (10%) of the FSS samples collected from open land survey units will be analyzed for HTD ROC. Only the HTD radionuclide included as ROC (Sr-90) will be analyzed in the FSS confirmatory samples. In addition, if any sample has a SOF of 10% of the Operational DCGL or more, it must be sent for HTD ROC analysis. For samples with positive results for both the HTD ROC and the corresponding surrogate radionuclide (Cs-137), the HTD surrogate ratio will be derived and compared against the 95% UCL ratio (see Table 5-1). If the derived ratio from the confirmatory samples exceeds the 95% UCL ratio, then the area-specific ratio as determined by actual survey data will be used. The selection of two (2) soil samples (L2-011-101-FSGS-005-SS and L2-011-101-FSGS-013-SS) met the requirement that a minimum of 10% of the samples collected for the FSS of survey unit L2-011-101 be analyzed for HTD ROC. The implementation of quality control measures as referenced by LTP, Section 5.9 and LaCrosseSolutions LC-QA-PN-001, Final Status Survey Quality Assurance Project Plan (QAPP) (Reference 10) includes the collection of a soil sample for split sample analysis on 5% of the soil samples taken in a survey unit with the locations selected at random. One (1) soil sample, L2-011-101-FQGS-009-SS, was designated for split sample QC analysis for the FSS of this survey unit. 17
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS The LTP, Section 5.6.4.4 and Table 5-15, specifies that for Class 2 open land survey units, surface scans will be performed on 5% to 50% of the surface area in the survey unit. For survey unit L2-011-101, 25% scan coverage was selected; the selected coverage equals 1,432 m2. Following selection, fifty-five (55) lanes within four (4) separate scan areas were established, constituting a total area of 1,509 m2 (more than the required minimum). For this Class 2 open land survey unit, the Investigation Levels for area scanning and soil sample measurement results are those levels specified in the LTP, 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 2 MDCscan is greater than Operational >Operational DCGL DCGL Table 5-6 provides a synopsis of the survey design for survey unit L2-011-101.
Table 5 Synopsis of Survey Design Feature Design Criteria Basis Survey Unit Surface Area 5,728 m2 GPS
= 0.008 UBGR = SOF of 1 Number of Systematic Samples 14 LBGR = SOF of 0.023 (N) Type I & II error = 0.05
/ = 3 (adjusted)
MARSSIM Table 5.5 Co-60: 3.83 pCi/g Sr-90: 1970.45 pCi/g Cs-137: 17.39 pCi/g Operational DCGLs for soil, DCGLS and Action Levels (Surrogate Cs-137 LTP, Table 5-6, Release Record, Table 5-2 DCGL: 17.31 pCi/g) Eu-152: 8.51 pCi/g Eu-154: 7.89 pCi/g Scan and Direct Investigation
>Operational DCGL LTP, Table 5-16 Levels 18
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Feature Design Criteria Basis Scan Areal Coverage 1,509, >25% areal coverage LTP, Table 5-15 1 Per Survey Design Judgmental Samples 3 Actual Number Obtained 1 LTP, Section 5.1 HTD ROC Analysis 2 Actual Number Obtained 1 split sample selected at random LTP, Section 5.9 QC 2 Actual Number Obtained
- 6. SURVEY IMPLEMENTATION For survey unit L2-011-101, compliance with the unrestricted release criteria was demonstrated through a combination of soil scanning with a Ludlum Model 44-10 gamma detector and the sampling of soil for isotopic analysis.
An FSS Supervisor performed a visual inspection and walk-down of the survey unit on September 17, 2019, prior to performing FSS. The purpose of the walk-down was to assess the physical condition of the survey unit, evaluate access points and travel paths, and identify potentially hazardous conditions. At the time of survey, the soil in the survey unit was dry and free of any considerable constraint for the collection of samples and scan measurements. FSS field activities were conducted under the FSS Sample Plan, which included DQOs, survey design, detailed FSS instructions, job safety analysis, and related procedures for reference. 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. A Field Log was used to document field activities and other information pertaining to the performance of the FSS. FSS field activities commenced on September 18, 2019, and were concluded on September 20, 2019. A total of one fifty-five (55) different scan lanes, constituting an areal coverage of 1,509 m2, were scanned using a Ludlum 2350-1 paired with a Ludlum Model 44-10 (2 x 2) sodium iodide (NaI) detector. The background was established as the average of five (5) 1-minute static measurements, while maintaining the detector 6 from the soil. In survey unit L2-011-101, background ranged from 3,930 cpm up to 6,002 cpm. All designated scan areas were scanned using a Ludlum 2350-1 paired with a Model 44-10 2x 2 NaI detector operated in the rate-meter mode and using audio response. The probe was positioned no more than 3 from the ground and was moved at a scan speed of approximately 0.5 meters per second. In accordance with RS-TD-313196-006, Ludlum 19
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Model 44-10 Detector Sensitivity (Reference 11), scan MDC was sufficient to detect residual radioactivity at the action level (adjusted surrogate DCGL of 17.31 pCi/g, which was based on the surrogate adjusted DCGL of Cs-137 while inferring Sr-90). Complete scan results are provided in Attachment 2. The fourteen (14) systematic sample locations were marked with flags based on GPS coordinates provided. Each soil sample consisted of approximately one (1) liter of soil. The soil sample media was sifted to remove stones and other media larger than one (1) centimeter in diameter. All soil samples were collected, controlled, transported, stored, and transferred to the on-site laboratory using the Chain-of-Custody process from LC-FS-PR-012, Chain of Custody Protocol (Reference 12), and in accordance with LC-FS-PR-004, Sample Media Collection for Site Characterization and Final Status Survey (Reference 13), LC-FS-PR-005, Sample Media Preparation for Site Characterization and Final Status Survey (Reference 14), and LC-FS-PR-001, Sample Storage (Reference 15). The survey design specified that a minimum of one (1) sample was required for HTD ROC analysis. In total, two (2) samples (L2-011-101-FSGS-005-SS and L2-011-101-FSGS-013-SS) were selected for HTD radionuclide analysis. The implementation of survey specific QC measures included the collection of two (2) samples (L2-011-101-FQGS-009-SS and L2-011-101-FQGS-009-SS SPLIT) for split and duplicate sample analysis.
- 7. SURVEY RESULTS All areas identified in the FSS sample plan were scanned for elevated activity levels. No alarms occurred during the performance of the scan survey. Table 7-1 provides an overview of the scan results for all scan lanes (identified as A 01 through D 28), the 1 m2 scan areas around each sample location before and after sample collection (identified with SP), and QC locations (identified with a QC). Complete scan results are provided in Attachment 2.
Table 7 Synopsis of Scan Results Highest Action # of Logged Investigation Scan Area Level(1) Scan Reading Samples Alarms (cpm) (cpm) 01 SP 5,572 7,381 0 0 02 SP 5,409 7,381 0 0 03 SP 5,205 7,381 0 0 04 SP 4,837 7,381 0 0 20
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Highest Action # of Logged Investigation Scan Area Level(1) Scan Reading Samples Alarms (cpm) (cpm) 05 SP 5,452 7,381 0 0 06 SP 5,020 7,381 0 0 07 SP 5,150 7,381 0 0 08 SP 4,683 7,381 0 0 09 SP 6,041 7,381 0 0 09 SP QC 5,835 7,400 0 0 10 SP 5,678 7,381 0 0 11 SP 4,903 7,381 0 0 12 SP 5,663 7,381 0 0 13 SP 5,377 7,381 0 0 14 SP 4,499 7,381 0 0 15 SP 5,315 7,381 0 0 A 01 5,363 5,937 0 0 A 02 5,468 5,937 0 0 A 03 4,963 5,937 0 0 A 04 4,883 5,937 0 0 A 05 5,059 5,937 0 0 A 06 5,022 5,937 0 0 A 07 4,652 5,937 0 0 A 08 5,256 5,937 0 0 A 09 4,671 5,937 0 0 A 10 5,601 5,937 0 0 A 11 4,700 5,937 0 0 A 12 4,705 5,937 0 0 A 13 4,880 5,937 0 0 A 14 4,657 5,937 0 0 A 15 4,772 5,937 0 0 A 16 4,660 5,937 0 0 A 17 4,726 5,937 0 0 A 18 4,406 5,937 0 0 A 19 4,339 5,937 0 0 A 20 4,733 5,937 0 0 21
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Highest Action # of Logged Investigation Scan Area Level(1) Scan Reading Samples Alarms (cpm) (cpm) B 01 4,748 7,764 0 0 B 02 4,976 7,764 0 0 B 03 4,527 7,764 0 0 B 04 4,469 7,764 0 0 B 05 4,914 7,764 0 0 B 06 4,408 7,764 0 0 B 07 4,332 7,764 0 0 B 08 4,864 7,764 0 0 B 09 4,609 7,764 0 0 B 10 5,144 7,764 0 0 B 11 4,568 7,764 0 0 B 12 4,841 7,764 0 0 B 13 4,714 7,764 0 0 B 14 5,361 7,764 0 0 C 01 5,095 7,764 0 0 C 02 5,780 7,764 0 0 C 03 5,189 7,764 0 0 C 04 6,067 7,764 0 0 C 05 5,833 7,764 0 0 C 06 6,343 7,764 0 0 C 07 5,842 7,764 0 0 C 08 5,795 7,764 0 0 C 09 6,327 7,764 0 0 C 10 6,749 7,764 0 0 C 11 5,978 7,764 0 0 C 12 6,016 7,764 0 0 C 13 6,533 7,764 0 0 C 14 5,942 7,764 0 0 C 15 6,850 7,764 0 0 C 16 6,484 7,764 0 0 C 17 7,190 7,764 0 0 C 18 6,608 7,764 0 0 22
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Highest Action # of Logged Investigation Scan Area Level(1) Scan Reading Samples Alarms (cpm) (cpm) C 19 6,906 7,764 0 0 C 20 6,489 7,764 0 0 D 01 5,457 7,123 0 0 D 01 QC 5,295 5,692 0 0 D 02 5,755 7,123 0 0 D 02 QC 4,811 5,692 0 0 D 03 5,136 7,123 0 0 D 03 QC 4,863 5,692 0 0 D 04 5,361 7,123 0 0 D 04 QC 4,500 5,692 0 0 D 05 5,243 7,123 0 0 D 06 5,059 7,123 0 0 D 07 5,154 7,123 0 0 D 08 5,030 7,123 0 0 D 09 5,346 7,123 0 0 D 10 4,906 7,123 0 0 D 11 5,214 7,123 0 0 D 12 5,400 7,123 0 0 D 13 5,111 7,123 0 0 D 14 5,508 7,123 0 0 D 15 5,202 7,123 0 0 D 16 5,013 7,123 0 0 D 17 4,639 7,123 0 0 D 18 4,880 7,123 0 0 D 19 5,346 7,123 0 0 D 20 4,886 7,123 0 0 D 21 5,063 7,123 0 0 D 22 4,943 7,123 0 0 D 23 4,718 7,123 0 0 D 24 4,859 7,123 0 0 D 25 5,077 7,123 0 0 D 26 5,116 7,123 0 0 23
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Highest Action # of Logged Investigation Scan Area Level(1) Scan Reading Samples Alarms (cpm) (cpm) D 27 5,797 7,123 0 0 D 28 6,858 7,123 0 0 (1) Action Level based on the average background plus 1,762 cpm (50% OpDCGL equivalent). The on-site laboratory analyzed the fourteen (14) soil samples taken for non-parametric statistical testing using the on-site gamma spectroscopy system. A summary of the results for the fourteen (14) samples collected for non-parametric statistical testing is provided in Table 7-2. Gamma spectroscopy results revealed that Cs-137 was positively identified in one (1) systematic samples. No other ROC were positively identified. The concentration for Sr-90 was inferred based on the ratio specified in Table 5-1. The complete gamma spectroscopy reports are presented in Attachment 7. The basic statistics for the systematic sample population are summarized in Table 7-3. Table 7 Summary of Gamma Spectroscopy Results for Samples Comprising the Statistical Sample Population Co-60 Cs-137 Eu-152 Eu-154 Sr-90 Sample ID (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) L2-011-101-FSGS-001-SS 2.73E-02 6.70E-02 1.02E-01 7.15E-02 3.36E-02 L2-011-101-FSPA-002-AV 2.37E-02 1.34E-01 1.18E-01 3.18E-01 6.73E-02 L2-011-101-FSPA-003-AV 1.10E-02 5.11E-02 0.00E+00 3.43E-02 2.57E-02 L2-011-101-FSGS-004-SS 2.57E-02 4.67E-02 1.28E-01 1.49E-01 2.34E-02 L2-011-101-FSGS-005-SS 2.14E-02 8.35E-02 2.77E-02 2.03E-02 4.19E-02 L2-011-101-FSGS-006-SS 4.23E-02 9.38E-02 3.62E-02 6.00E-02 4.71E-02 L2-011-101-FSGS-007-SS 8.98E-02 1.53E-01 1.68E-01 4.56E-02 7.68E-02 L2-011-101-FSGS-008-SS 1.30E-02 7.10E-02 8.47E-02 3.64E-02 3.56E-02 L2-011-101-FSGS-009-SS 6.10E-02 1.16E-02 0.00E+00 2.52E-02 5.82E-03 L2-011-101-FSGS-010-SS 3.87E-02 3.73E-02 9.38E-02 2.67E-02 1.87E-02 L2-011-101-FSGS-011-SS 0.00E+00 4.82E-02 1.49E-01 0.00E+00 2.42E-02 L2-011-101-FSGS-012-SS 7.67E-02 2.54E-02 2.51E-02 1.59E-02 1.28E-02 L2-011-101-FSGS-013-SS 5.62E-02 5.17E-02 1.25E-01 2.08E-01 2.60E-02 L2-011-101-FSGS-014-SS 4.24E-02 2.00E-02 2.05E-01 1.22E-01 1.00E-02 24
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Note: Bold values indicate concentrations greater than MDC. Table 7 Basic Statistical Properties of Systematic Sample Population Mean Median Max Min Std. Dev. BcDCGL Avg. SOF Avg. Dose ROC (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) per ROC Per ROC Co-60 3.78E-02 3.30E-02 8.98E-02 0.00E+00 2.58E-02 1.06E+01 0.0036 0.0892 Cs-137 6.39E-02 5.14E-02 1.53E-01 1.16E-02 4.10E-02 4.83E+01 0.0013 0.0331 Eu-152 9.02E-02 9.79E-02 2.05E-01 0.00E+00 6.42E-02 2.36E+01 0.0038 0.0955 Eu-154 8.09E-02 4.10E-02 3.18E-01 0.00E+00 8.99E-02 2.19E+01 0.0037 0.0924 Sr-90 3.21E-02 2.58E-02 7.68E-02 5.82E-03 2.06E-02 5.47E+03 0.0000 0.0001 The off-site laboratory, GEL Laboratories, processed the two (2) samples selected for HTD ROC analysis. Samples L2-011-101-FSGS-005-SS and L2-011-101-FSGS-013-SS were selected. Only the HTD ROC Sr-90 was included in the analysis. All analyses met the required MDC. Sr-90 was not detected in the off-site analysis of samples L2-011-101-FSGS-005-SS and L2-011-101-FSGS-013-SS. The results are provided in Table 7-4. Table 7 Off-Site Analysis Results Result Uncertainty MDC Sample ID ROC >MDC (pCi/g) (pCi/g) (pCi/g) L2-011-101-FSGS-005-SS Sr-90 -1.35E-02 7.36E-02 1.41E-01 No L2-011-101-FSGS-013-SS Sr-90 7.06E-02 8.50E-02 1.44E-01 No The on-site laboratory analyzed the three (3) judgmental soil samples using the on-site gamma spectroscopy system. A summary of the analytical results for the judgmental and investigational soil samples is provided in Table 7-5. Gamma spectroscopy results revealed that no ROC were positively identified any judgmental sample. The concentrations for Sr-90 were inferred based on the ratio specified in Table 5-1. The complete gamma spectroscopy reports are presented in Attachment 7. Table 7 Summary of Gamma Spectroscopy Results for Judgmental Samples Co-60 Cs-137 Eu-152 Eu-154 Sr-90 Sample ID (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) L2-011-101-FJGS-015-SS 8.65E-02 4.41E-02 4.69E-02 1.05E-02 2.21E-02 L2-011-101-FSGS-002-SS 7.88E-04 5.86E-02 3.13E-02 4.07E-03 2.94E-02 L2-011-101-FSGS-003-SS 6.00E-02 5.13E-02 4.41E-02 6.78E-04 2.58E-02 25
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Note: Bold values indicate concentrations greater than MDC. The implementation of survey specific QC measures included the collection of two (2) samples (L2-011-101-FQGS-009-SS and L2-011-101-FQGS-009-SS SPLIT) for split and duplicate sample analysis. The on-site laboratory analyzed the QC samples using the on-site gamma spectroscopy system. A summary of the analytical results for the QC sample is provided in Table 7-6. Gamma spectroscopy results revealed that no ROC were positively identified in any QC sample. The concentration for Sr-90 was inferred based on the ratio specified in Table 5-1. Table 7 Summary of Gamma Spectroscopy Results for QC Samples Co-60 Cs-137 Eu-152 Eu-154 Sr-90 Sample ID (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) L2-011-101-FQGS-009-SS 5.09E-02 5.60E-02 3.43E-03 2.58E-01 2.81E-02 L2-011-101-FSGS-009-SS SPLIT 2.87E-03 1.21E-01 0.00E+00 5.16E-03 6.07E-02 Note: Bold values indicate concentrations greater than MDC. The SOF or unity rule is the mathematical test used to evaluate compliance with radiological criteria for license termination when more than one radionuclide has been determined to be potentially present. The equation for the unity rule is: Equation 4 C1 C2 Cn
.......... .. 1 DCGL1 DCGL 2 DCGL n Where: Cn = concentration of radionuclide n DCGLn = DCGL of radionuclide n.
The results of the unity rule calculation for the ROC in the systematic sample population for survey unit L2-011-101 are provided in Table 7-7. Table 7 Sum-of-Fractions for Systematic and QC Samples Fraction of Operational DCGL Sample ID SOF Co-60 Cs-137 Eu-152 Eu-154 Sr-90 L2-011-101-FSGS-001-SS 0.0071 0.0039 0.0120 0.0091 0.0000 0.0320 L2-011-101-FSPA-002-AV 0.0062 0.0077 0.0139 0.0403 0.0000 0.0681 L2-011-101-FSPA-003-AV 0.0029 0.0029 0.0000 0.0043 0.0000 0.0102 L2-011-101-FSGS-004-SS 0.0067 0.0027 0.0150 0.0189 0.0000 0.0433 L2-011-101-FSGS-005-SS 0.0056 0.0048 0.0033 0.0026 0.0000 0.0162 L2-011-101-FSGS-006-SS 0.0110 0.0054 0.0043 0.0076 0.0000 0.0283 26
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Fraction of Operational DCGL Sample ID SOF Co-60 Cs-137 Eu-152 Eu-154 Sr-90 L2-011-101-FSGS-007-SS 0.0234 0.0088 0.0197 0.0058 0.0000 0.0578 L2-011-101-FSGS-008-SS 0.0034 0.0041 0.0100 0.0046 0.0000 0.0221 L2-011-101-FSGS-009-SS 0.0159 0.0007 0.0000 0.0032 0.0000 0.0198 L2-011-101-FSGS-010-SS 0.0101 0.0021 0.0110 0.0034 0.0000 0.0267 L2-011-101-FSGS-011-SS 0.0000 0.0028 0.0175 0.0000 0.0000 0.0203 L2-011-101-FSGS-012-SS 0.0200 0.0015 0.0029 0.0020 0.0000 0.0265 L2-011-101-FSGS-013-SS 0.0147 0.0030 0.0147 0.0264 0.0000 0.0587 L2-011-101-FSGS-014-SS 0.0111 0.0012 0.0241 0.0155 0.0000 0.0518 L2-011-101-FQGS-009-SS 0.0133 0.0032 0.0004 0.0327 0.0000 0.0496 L2-011-101-FSGS-009-SS SPLIT 0.0007 0.0070 0.0000 0.0007 0.0000 0.0084 Systematic Samples Number of Systematic Samples = 14
# of Systematic Samples with SOF > 1 = 0
# of Systematic Samples with SOF > 0.1 (HTD Assessment) = 0 Max Individual Systematic Sample SOF = 0.0681 Mean Systematic Sample SOF = 0.0344 The results of the unity rule calculation for the ROC in the judgmental sample populations for survey unit L2-011-101 are provided in Table 7-8.
Table 7 Sum-of-Fractions for Judgmental Samples Fraction of Operational DCGL Sample ID SOF Co-60 Cs-137 Eu-152 Eu-154 Sr-90 L2-011-101-FJGS-015-SS 0.0226 0.0025 0.0055 0.0013 0.0000 0.0320 L2-011-101-FSGS-002-SS 0.0002 0.0034 0.0037 0.0005 0.0000 0.0078 L2-011-101-FSGS-003-SS 0.0157 0.0029 0.0052 0.0001 0.0000 0.0239 Judgmental Samples Number of Judgmental Samples = 3
# of Judgmental Samples with SOF > 1 = 0
# of Judgmental Samples with SOF > 0.1 (HTD Assessment) = 0 Max Individual Judgmental Sample SOF = 0.0320 27
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS
- 8. QUALITY CONTROL The on-site laboratory processed two (2) split and duplicate samples (L2-011-101-FQGS-009-SS and L2-011-101-FQGS-009-SS SPLIT) using gamma spectroscopy analysis. The data was evaluated using USNRC acceptance criteria specified in Inspection Procedure No.
84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring (Reference 16). K-40 was substituted for the assessment because Cs-137 was not identified in either the standard or comparison sample. There was acceptable agreement between field split and duplicate results. Refer to Attachment 4 for data and quality control analysis results.
- 9. INVESTIGATIONS AND RESULTS No investigations were performed during the FSS of survey unit L2-011-101.
- 10. REMEDIATION AND RESULTS No radiological remedial action as described by MARSSIM Section 5.4 was performed in this survey unit prior to or as a result of the FSS. Chapter 4 of the LTP determined that remediation beyond that required to meet the release criteria is unnecessary and that the remaining residual radioactivity in soil was ALARA.
- 11. CHANGES FROM THE FINAL STATUS SURVEY PLAN There were no addendums to the FSS plan.
- 12. DATA QUALITY ASSESSMENT (DQA)
The DQO sample design and data were reviewed in accordance with LC-FS-PR-008, Final Status Survey Data Assessment (Reference 17) for completeness and consistency. Documentation was complete and legible. Surveys and the collection of samples were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 2. The survey design had adequate power as indicated by the Retrospective Power Curve (see Attachment 6). The measurement results indicated that all samples were less than a SOF of one (1) when compared to the OpDCGLS. Although MARSSIM states that the Sign Test need not be performed in the instance that no measurements surpass the Operational DCGL, the test was conducted to demonstrate 28
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS coherence to the statistical principles of the DQO process. The Sign Test was performed on the data and compared to the original assumptions of the DQOs. The evaluation of the Sign Test results clearly demonstrates that the survey unit passes the unrestricted release criteria, thus, the null hypothesis is rejected. The results of the Sign Test are presented in Attachment 3. The preliminary data review consisted of calculating basic statistical quantities (e.g., mean, median, standard deviation). All data was considered valid including negative values, zeros, values reported below the MDC, and values with uncertainties that exceeded two standard deviations. The mean and median values for each ROC were well below the respective Operational DCGLs. Also, the retrospective power curve shows that a sufficient number of samples were collected to achieve the desired power. Therefore, the survey unit meets the unrestricted release criteria with adequate power as required by the DQOs. The mean of all identified isotopes are less than the Consultation Triggers for Residential Soil Concentration depicted in Table H.1 of NUREG 1757, Vol.1, Rev. 2 (MOU Table 1). The full table is included in Attachment 5 of this release record. The data for Cs-137 is presented graphically through a frequency plot and quantile plot. All graphical presentations are provided in Attachment 6.
- 13. ANOMALIES No anomalies were observed during the performance or analyses of the survey.
- 14. CONCLUSION Survey unit L2-011-101 has met the DQOs of the FSS plan. The ALARA criteria as specified in Chapter 4 of the LTP were achieved. The Elevated Measurement Comparison for soils was not applicable and remediation was not required.
All identified ROC were used for statistical testing to determine the adequacy of the survey unit for FSS. Evaluation of the data shows that none of the systematic ROC concentration values exceeds the OpDCGLS; therefore, in accordance with LTP Section 5.11, the survey unit meets the release criteria. The sample data passed the Sign Test. The null hypothesis was rejected. The Retrospective Power Curve showed that adequate power was achieved. The survey unit is properly classified as Class 2. The dose contribution from soil in survey unit L2-011-101 is 0.3103 mrem/yr TEDE, based on the average concentration of the ROC in samples used for non-parametric 29
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS statistical sampling. Survey unit L2-011-101 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
- 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
- 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
- 11. RS-TD-313196-006, Ludlum Model 44-10 Detector Sensitivity
- 12. LC-FS-PR-012, Chain of Custody Protocol
- 13. LC-FS-PR-004, Sample Media Collection for Site Characterization and Final Status Survey
- 14. LC-FS-PR-005, Sample Media Preparation for Site Characterization and Final Status Survey
- 15. LC-FS-PR-001, Sample Storage
- 16. USNRC Inspection Procedure No. 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring
- 17. LC-FS-PR-008, Final Status Survey Data Assessment
- 16. ATTACHMENTS Attachment 1 - Figure Attachment 2 - Scan Data Attachment 3 - Sign Test Attachment 4 - Quality Control Assessment Attachment 5 - Consultation Triggers for Residential Soil Concentrations 30
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Attachment 6 - Graphical Presentations Attachment 7 - Sample Analytical Reports Attachment 8 - GEL Laboratories Analytical Reports 31
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS ATTACHMENT 1 FIGURE 32
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Figure 16 Survey Unit L2-011-101 Systematic and Judgmental Sample Locations Map 1 (easting) north ing) - (easting) north ing) - Legend L2-011-101 (5,728 m 2)
, I I 3)
\ 1 1
5,'.)M,ele,f'S I I I N o 25 5.'.> 75 t:>O 125 150 f7.5 F'ffl 0 Systematic Sa mples l2--011-101 Samples
- LACBWR Site Genoa, W I 0 Biased Sa mples ,-:::::== Date 09/26/2019 L.\CROSSESOU:Tm,:s Drawing 19080601 .b 33
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS ATTACHMENT 2 SCAN DATA 34
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Table 16 Survey Unit L2-011-101 Complete Scan Data Scan Avg Action Detector Detector M2350-1 Logged Scan Location Background Level Type ID ID Result Alarms (cpm) (cpm) (cpm) 44-10 215123 216185 01 SP 5,236 5,619 7,381 0 44-10 215123 216185 01 SP 5,572 5,619 7,381 0 44-10 215123 216185 02 SP 5,409 5,619 7,381 0 44-10 215123 216185 02 SP 4,590 5,619 7,381 0 44-10 215123 216185 02 SP 4,702 5,619 7,381 0 44-10 215123 216185 03 SP 4,609 5,619 7,381 0 44-10 215123 216185 03 SP 5,205 5,619 7,381 0 44-10 215123 216185 03 SP 5,009 5,619 7,381 0 44-10 215123 216185 04 SP 4,252 5,619 7,381 0 44-10 215123 216185 04 SP 4,837 5,619 7,381 0 44-10 215123 216185 05 SP 5,452 5,619 7,381 0 44-10 215123 216185 05 SP 5,291 5,619 7,381 0 44-10 215123 216185 06 SP 5,020 5,619 7,381 0 44-10 215123 216185 06 SP 4,843 5,619 7,381 0 44-10 215123 216185 07 SP 4,751 5,619 7,381 0 44-10 215123 216185 07 SP 5,150 5,619 7,381 0 44-10 215123 216185 08 SP 4,683 5,619 7,381 0 44-10 215123 216185 08 SP 4,258 5,619 7,381 0 44-10 215123 216185 09 SP 6,041 5,619 7,381 0 44-10 215123 216185 09 SP 5,723 5,619 7,381 0 44-10 226940 117014 09 SP QC 5,835 5,638 7,400 0 44-10 226940 117014 09 SP QC 5,636 5,638 7,400 0 44-10 215123 216185 10 SP 5,678 5,619 7,381 0 44-10 215123 216185 10 SP 4,057 5,619 7,381 0 44-10 215123 216185 11 SP 4,680 5,619 7,381 0 44-10 215123 216185 11 SP 4,903 5,619 7,381 0 44-10 215123 216185 12 SP 5,663 5,619 7,381 0 44-10 215123 216185 12 SP 5,615 5,619 7,381 0 44-10 215123 216185 13 SP 5,377 5,619 7,381 0 44-10 215123 216185 13 SP 5,059 5,619 7,381 0 44-10 215123 216185 14 SP 4,155 5,619 7,381 0 35
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Scan Avg Action Detector Detector M2350-1 Logged Scan Location Background Level Type ID ID Result Alarms (cpm) (cpm) (cpm) 44-10 215123 216185 14 SP 4,499 5,619 7,381 0 44-10 215123 216185 15 SP 5,315 5,619 7,381 0 44-10 215123 216185 15 SP 5,179 5,619 7,381 0 44-10 226940 117014 A 01 5,363 4,175 5,937 0 44-10 226940 117014 A 02 5,468 4,175 5,937 0 44-10 226940 117014 A 03 4,963 4,175 5,937 0 44-10 226940 117014 A 04 4,883 4,175 5,937 0 44-10 226940 117014 A 05 5,059 4,175 5,937 0 44-10 226940 117014 A 06 5,022 4,175 5,937 0 44-10 226940 117014 A 07 4,652 4,175 5,937 0 44-10 226940 117014 A 08 5,256 4,175 5,937 0 44-10 226940 117014 A 09 4,671 4,175 5,937 0 44-10 226940 117014 A 10 5,601 4,175 5,937 0 44-10 226940 117014 A 11 4,700 4,175 5,937 0 44-10 226940 117014 A 12 4,705 4,175 5,937 0 44-10 226940 117014 A 13 4,880 4,175 5,937 0 44-10 226940 117014 A 14 4,657 4,175 5,937 0 44-10 226940 117014 A 15 4,772 4,175 5,937 0 44-10 226940 117014 A 16 4,660 4,175 5,937 0 44-10 226940 117014 A 17 4,726 4,175 5,937 0 44-10 226940 117014 A 18 4,406 4,175 5,937 0 44-10 226940 117014 A 19 4,339 4,175 5,937 0 44-10 226940 117014 A 20 4,733 4,175 5,937 0 44-10 215123 216185 B 01 4,748 6,002 7,764 0 44-10 215123 216185 B 02 4,976 6,002 7,764 0 44-10 215123 216185 B 03 4,527 6,002 7,764 0 44-10 215123 216185 B 04 4,469 6,002 7,764 0 44-10 215123 216185 B 05 4,914 6,002 7,764 0 44-10 215123 216185 B 06 4,408 6,002 7,764 0 44-10 215123 216185 B 07 4,332 6,002 7,764 0 44-10 215123 216185 B 08 4,864 6,002 7,764 0 44-10 215123 216185 B 09 4,609 6,002 7,764 0 36
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Scan Avg Action Detector Detector M2350-1 Logged Scan Location Background Level Type ID ID Result Alarms (cpm) (cpm) (cpm) 44-10 215123 216185 B 10 5,144 6,002 7,764 0 44-10 215123 216185 B 11 4,568 6,002 7,764 0 44-10 215123 216185 B 12 4,841 6,002 7,764 0 44-10 215123 216185 B 13 4,714 6,002 7,764 0 44-10 215123 216185 B 14 5,361 6,002 7,764 0 44-10 215123 216185 C 01 5,095 6,002 7,764 0 44-10 215123 216185 C 02 5,780 6,002 7,764 0 44-10 215123 216185 C 03 5,189 6,002 7,764 0 44-10 215123 216185 C 04 6,067 6,002 7,764 0 44-10 215123 216185 C 05 5,833 6,002 7,764 0 44-10 215123 216185 C 06 6,343 6,002 7,764 0 44-10 215123 216185 C 07 5,842 6,002 7,764 0 44-10 215123 216185 C 08 5,795 6,002 7,764 0 44-10 215123 216185 C 09 6,327 6,002 7,764 0 44-10 215123 216185 C 10 6,749 6,002 7,764 0 44-10 215123 216185 C 11 5,978 6,002 7,764 0 44-10 215123 216185 C 12 6,016 6,002 7,764 0 44-10 215123 216185 C 13 6,533 6,002 7,764 0 44-10 215123 216185 C 14 5,942 6,002 7,764 0 44-10 215123 216185 C 15 6,850 6,002 7,764 0 44-10 215123 216185 C 16 6,484 6,002 7,764 0 44-10 215123 216185 C 17 7,190 6,002 7,764 0 44-10 215123 216185 C 18 6,608 6,002 7,764 0 44-10 215123 216185 C 19 6,906 6,002 7,764 0 44-10 215123 216185 C 20 6,489 6,002 7,764 0 44-10 226940 117014 D 01 5,457 5,361 7,123 0 44-10 226940 117014 D 01 QC 5,295 3,930 5,692 0 44-10 226940 117014 D 02 5,755 5,361 7,123 0 44-10 226940 117014 D 02 QC 4,811 3,930 5,692 0 44-10 226940 117014 D 03 5,136 5,361 7,123 0 44-10 226940 117014 D 03 QC 4,863 3,930 5,692 0 44-10 226940 117014 D 04 5,361 5,361 7,123 0 37
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Scan Avg Action Detector Detector M2350-1 Logged Scan Location Background Level Type ID ID Result Alarms (cpm) (cpm) (cpm) 44-10 226940 117014 D 04 QC 4,500 3,930 5,692 0 44-10 226940 117014 D 05 5,243 5,361 7,123 0 44-10 226940 117014 D 06 5,059 5,361 7,123 0 44-10 226940 117014 D 07 5,154 5,361 7,123 0 44-10 226940 117014 D 08 5,030 5,361 7,123 0 44-10 226940 117014 D 09 5,346 5,361 7,123 0 44-10 226940 117014 D 10 4,906 5,361 7,123 0 44-10 226940 117014 D 11 5,214 5,361 7,123 0 44-10 226940 117014 D 12 5,400 5,361 7,123 0 44-10 226940 117014 D 13 5,111 5,361 7,123 0 44-10 226940 117014 D 14 5,508 5,361 7,123 0 44-10 226940 117014 D 15 5,202 5,361 7,123 0 44-10 226940 117014 D 16 5,013 5,361 7,123 0 44-10 226940 117014 D 17 4,639 5,361 7,123 0 44-10 226940 117014 D 18 4,880 5,361 7,123 0 44-10 226940 117014 D 19 5,346 5,361 7,123 0 44-10 226940 117014 D 20 4,886 5,361 7,123 0 44-10 226940 117014 D 21 5,063 5,361 7,123 0 44-10 226940 117014 D 22 4,943 5,361 7,123 0 44-10 226940 117014 D 23 4,718 5,361 7,123 0 44-10 226940 117014 D 24 4,859 5,361 7,123 0 44-10 226940 117014 D 25 5,077 5,361 7,123 0 44-10 226940 117014 D 26 5,116 5,361 7,123 0 44-10 226940 117014 D 27 5,797 5,361 7,123 0 44-10 226940 117014 D 28 6,858 5,361 7,123 0 38
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS ATTACHMENT 3 SIGN TEST 39
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Table 16 Survey Unit L2-011-101 Sign Test SOF
# 1-Ws Sign (Ws) 1 0.0320 0.97 +1 2 0.0681 0.93 +1 3 0.0102 0.99 +1 4 0.0433 0.96 +1 5 0.0162 0.98 +1 6 0.0283 0.97 +1 7 0.0578 0.94 +1 8 0.0221 0.98 +1 9 0.0198 0.98 +1 10 0.0267 0.97 +1 11 0.0203 0.98 +1 12 0.0265 0.97 +1 13 0.0587 0.94 +1 14 0.0518 0.95 +1 Number of positive differences (S+) 14 Critical Value 10 Survey Unit Meets the Acceptance Criteria 40
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS ATTACHMENT 4 QUALITY CONTROL ASSESSMENT 41
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Table 16 Survey Unit L2-011-101 QC Assessment STANDARD COMPARISON Radionuclid Activity Standard Agreement Range Activity Comparison Acceptable Sample ID Resolution Sample ID e Value Error (Low to High) Value Ratio (Y/N) L2-011-101-FQGS-009-SS 7.44E+00 0.96 Y L2-011-101-FSGS-009-SS K-40 7.74E+00 1.15E+00 7 0.5 2 I L2-011-101-FSGS-009-SS SPLIT 8.40E+00 1.09 Y Comments/Corrective Actions: K-40 was substituted for the assessment because Cs-137 was not Table is provided to show acceptance criteria used to assess split samples. identified in either the standard or comparison sample. Reso lution Acceptable R atio
<4 0 .4-2 .5 4- 7 0 .5-2 .0 8-1 5 0 .6- 1.66 16- 50 0 .75 - 1.33 51 -200 0 .80- 1.2 5
> 200 0.8 5- 1.1 8 42
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS ATTACHMENT 5 CONSULTATION TRIGGERS FOR RESIDENTIAL SOIL CONCENTRATION 43
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Table H.1 Consultation Triggers for Residential and Commercial/Industrial Soil Contamination (MOU Table 1) Except for radium-226, thorium-232, or total uranium, concentrations should be aggregated using a sum of the fraction approach to determine site-specific consultation trigger concentrations. This table is based on single contaminant concentrations for residential and cornrnerciaJ/industrial land use when using generally accepted exposure parameters. Table users should select the appropriate column based on the site's reasonably anticipated land use. Radionuclide Residential Soil Concentration Industrial/Commercial Soil Concentration H-3 228 pCi/g 423 pCi/g C-14 46 oCi/g 123 000 oCi/g Na-22 9 oCi/g 14 pCi/g S-35 19,600 pCi/g 32 200,000 pCi/g Cl-36 6 nCi/g 10,700 oCi/g Ca-45 13,500 pCi/g 3 740 000 oCi/g Sc-46 105 pCi/2 169 pCiig Mn-54 69 oCi/g 112 oCi/g Fe-55 269,000 pCi/g 2,210,000 oCi/g Co-57 873 pCi/g 1.420 oCi/e: Co-60 4pCi/g 6 oCi/g Ni-59 20 800 pCi/g 1,230 000 oCi/g Ni-63 9,480 oCi/g 555.000 oCi/g Sr-90+0 23 pCi/g 1,070 oCi/g Nb-94 2 pCi/g 3 pCi/g Tc-99 25 oCi/g 89,400 oCi/g I-129 60 pCi/g 1,080 oCi/g Cs-134 16 pCi/g 26 pCi/g Cs-137+0 6 oCi/g 11 pCi/g Eu-152 4 oCi/g 7 oCi/g Eu-154 5 pCi/g 8 pCi/g lr-192 336 pCi/g 544 pCi/g Pb-210+0 15 oCi/g 123 oCi/g Ra-226 5 pCi/g 5 pCi/g Ac-227+0 10 pCi/g 21 oCi/g Th-228+0 15 pCi/g 25 nCi/g Th-232 5 pCi/g 5 pCi/g U-234 401 pCi/g 3,310 pCi/g U-235+0 20 oCi/g 39 oCi/g U-238+0 74 pCi/g 179 pCi/g total uranium 47 m21'1cg 1230 mg/kg Pu-238 297 oCi/g 1.640 oCi/g Pu-239 259 pCi/g 1,430 oCi/g Pu-241 40,600 pCi/g 172.000 pCi/g Am-241 187oCi/~ 568 pCi/g Cm-242 32.200 pCi/g 344,000 pCi/g Cm-243 35 pCi/g 67 pCi/g 44
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS ATTACHMENT 6 GRAPHICAL PRESENTATIONS 45
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Figure 16 Quantile Plot for Cs-137 Concentration l.SOE-01 l.60E -01 e l.40E-01 e G'
---e:.u UOE 01 z
0 j:: 1.00E-01
<t a:
zw u e 8.00E-02 z 0 e u
.... e "'... 6.00E 02 J, e e u
4.00E-02 e
- e e
2.00E 02 e e O.OOE +IXl OS**0 10% 20"/o 30% 40% 50"/o 60"/o 70"/o 80"1, 90% 1000, PERCENTAGE 46
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Figure 16 Histogram for Cs-137 Concentration 6 5 4 FREQUENCY 3 2 1 0 3.71E-02 6.26E-02 8.81E-02 1.14E-01 1.39E-01 1.65E-01 UPPER END VALUE (PCI/G) 47
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS Figure 16 Retrospective Power Curve for Survey Unit L2-011-101 Probability that th un""ey Cnit Pa se 1.0 ,._ i 0.8 0.6 0.4 0.2 0.0 "- 1)% 3)% 5)% - % 9)% l JO%110% l 0% 150% True urve
- 1 nit once t
- tion (percent .of D
- L) 48
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS ATTACHMENT 7 SAMPLE ANALYTICAL REPORTS 49
9/23/2019 3:32:06PM Page 1 of? ---="Apex-Gamma Analysis Report for L2-011-101-FSGS-001-SS L2-011-101 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-011-101-FSGS-001-SS Sample Delcrtptlon : L2-011-101 Sample Type : 500 ml Marinelli Unit 851mplaM!t Sample Size : 7.824E+D2 grams Facll\y : Dalrylancl_NPP Sample Taken On : 9120/2019 12:25:00PM Aoqulaltlon Started : 8r.i!312D1i 3:01:47PM Procedure : 500ml MarineNi Operator : AdmlnlSb'llar Defector Name :Hon.AB GeomMy : S<nnl Msinelll Live Time : 1800.0 seconds Realllme : 1805.9 seconds Daadllme : 0.32% Peak Locate Threshold : 3.00 Peak Locate Range (In chennala) : 100-4098" PeakAnle Range (l'li:hannels) : 100-4098 ldentiffcatlon Ertergy Tolerance : 1.O00keV En91UY Catballon Used Done On : 7/8/2014 Effldancy Callbratlon U9ed Done On : 718/2()14 Effldency Calb'8tlon Deaaip11on Sanple Number ; 7477 PEAK ANALYSIS REPORT Peak Analy&ie Perfonned on : 9'l3l2018 3:31:67'PM Peak Anatyala From Channel : 100 f>eak. Analysis To Cha'W'lel : 4098
9/231'2019 3:32:06PM Page 2 of7 Analysis Report ror L2-011-101-FSGS-001-SS L2-011-101 Pealr. Enlt'fl'Y ROI ROI Peak NetPffk NetArH Continuum FWHM No. (keV) slart end C.nttold .Ante Uncertalrrty Counts (keV) M 1 238.54 471- 487 477.55 1.30E+02 28.08 1. 75E+02 1.46 m 2 241.38 471- 487 483.23 5.53E+Ol 19.86 1.54E+02 1.47 F 3 294.78 583 - 594 590.01 5.92E+Ol 23.01 1.57E+02 1.88 F 4 352.04 696 - 711 704.50 9.82E+01 24.01 1.52E+02 1. 75 F 5 582.98 11 62 - 1171 1166.30 4.l9E+Ol 1 6.12 5.12E+Ol 1.53 F 6 609.01 1210 - 1225 1218.34 6.94E+Ol 19.58 8.41E+Ol 1. 78 F 7 911.17 1817 - 1827 1822.58 2.86E+Ol 12.69 3.53E+01 1.21 F 8 968.47 1931 - 1942 1937.16 2.77E+Ol 12.34 2.0BE+Ol 2.06 F 9 1460.43 2913- 2928 2920.98 2.89E+02 34.34 l.l9E+Ol 2.26 M = Find peek In a mutl!J)let region m = Olhw peak In a mlJtls,let Nlillon F "" Fitted ainglet Em:ira quolad at 2.000sigma BACKGROUND SUBTRACT REPORT PeakAnelyals Perfomied on : 912312019 3:31:67PM Env. Background Fie : C:\Canbemt\Apex\Root'Dairyfancl.NPP\Oata\0000001384.CNF PNlc E'""flY Original Orig. Area Ambient Bllckgr. Subll'Kted Subttectea No. trr*VJ Atea Uncertainty Baclrtlround Uncert. Aru Un,;e,t. M 1 238. 5 4 l. 30E+02 28.08 l.30E+02 2.81E+Ol m 2 241. 38 5.53E+Ol 19.86 S.53E+Ol l.99E+Ol F 3 294.78 5. 92E+Ol 23.01 5.92E+Ol
- 2.30E+Ol F 4 352.04 9.82E+Ol 24.01 4.18E+Ol 1.86E+Ol 5.64E+Ol 3.04E+Ol F 5 582.98 4.19E+Ol 16.12 4.19E+Ol 1.61E+01 F 6 609.01 6 . 94E+Ol 19.58 2.06E+Ol 1.21E+Ol 4,88E+Ol 2 .30E+Ol F 7 911. 17 2.86E+Ol 12. 69 2.86E+Ol l .2'7*E+Ol F 8 968.47 2.77E+Ol 12.34 2.7'7E+Ol 1.23E+Ol F 9 1460.43 2.89E+02 34.34 2.82E+Ol 8.57E+OO 2.61E+02 3.54E+Ol M = Fil'81 peek In 8 multiplet region m = Otha' peak In a mUltlplet region F
- Fllled singlet Emn quoted at 2.00.0slgma
9/23/2019 3:32:06PM Pagc3 of7 Analysis Report for L2-011-101-FSGS-001-SS L2-011-101 NUCLIDE IDENTIFICATION REPORT Nuclde Library Used : C:\Canbana\Apex\RootlDalryland_NPP\Lbary\HOTLAS.NLB IDENTIFIED NUCLIDES Nuclide Energy Yleldf") Activity Name "' Confidence (keVJ Activity (pCVgnuna) Unanalmy K-40 0.98 1460.75
- 10.67 7.28E+OO l.07E+OO PB-212 0. 55 77 .11 17.50 238.63
- 44. 60 1.72E-Ol 3.81E-02 BI-214 0.34 609.31
- 46.30 1.44E-Ol 6.82E-02 1120.29 15.10 1238.11 5.94 1317.67 4 .11 1407.98 2.48 1509,19 2 .19 1764.49 15.80 PB-214 0.71 77.11 10.70 295.21
- 19.20 2.16E-Ol 8,47E-02 351.92
- 37.20 l.25E-Ol 6.74E-02
* = energy line found In the spedrum.
-
- M!Wlally added nudlde.
? is Manually edled nuclde.
@ = f:1111f1jy line not used fer Weighted Maan ActMty Energy Tolerance: 1.000 bV Nuclide corrftdence Index threshold = 0.30 Etrors quoted at 2.000&igms INTERFERENCE CORRECTED REPORT Hue/Ide Nucllm WtmHn Wtmean Comments Name Id ActlV;ty Activity Confidence Uncertainty (pCV1ram*)
K-40 0.984 7.28&+00 1.07E+00 PB-212 0.559 1.72E-01 3.81E-02 BI-214 0.342 l.44E-01 6.82E-02
9/23/2019 3:32:06PM Pagc4of7 Analysis Report for L2-011-101-FSGS-001-SS L2-011-101 Nuclide Nuclide Wfmean Wtmean Comments Name Id Activity Activity Confidence Uncettalnty (pCVgrams) PB-214 0.,12 1.60E-01 5.21E-02
? = nucllde is part of an undetennlned solution X = nuclide "9,leoted by Ile Interference analysis G = nuclide GOl"llain* energy nnas not used In Weighted Mean Activity ErronJ quoted at 2.000slgma
9/23/2019 3:32:0SPM Page S of1 Analysis Report for L2-011-101-FSGS-001-SS L2-011-101 UNIDENTIFIED PEAKS Peak Locate Performed on . : 9/2312019 3:31 :57PM Peak Lecato From Channel : 100 Peak Loaite To Channel : 4'098 PakCPS(") P.-Jc Tolerance PNkNo. EMIVY (k*V) Peale Sin (CPS} Uncertainty Typa Nuclide m 2 241.38 3.07358E-02 17.95 F 5 582.98 2.32686E-02 19 .24 F 7 911.17 1.58120E-02 22.21 Tel. AC-228 PA-228 F 8 968.47 l . 53931E-02 22.26 Tel. AC-228 M = First peak In a multiplet region m = Other peek in a mult!plet region F = Fitted ainglet Errors quoted at 2.000llgma NUCLIDE MDA RE.PORT
- Nuclide Library Used :* C:\Cenberra\Apax\Root'Dalryland_NPF"Llbrary\HOllAB.Nl.8 Nudlde Energy thv.9
't'leld{3/4) Aallvtty Nucllde IIDA (pCV..,.,.) (pCl/p9IMJ ~
LlnelfDA + K-40 1460.75
- 10.67 7.28E+OO 8.lOE-01 8.lOE-01
+ AR-41 1293.64 99.16 4.02E+09 1.
- 89E+ll l.89E+ll
+ C0- 60 1173.22 100 .*oo -7.02E-02 7,98E-02 9.46E-02 1332.49 100.00 2.,3E-02 7.98E-02 + KR-85 513.99 0.43 6.66E+OO 1. 54E+Ol 1.54E+Ol + Y-88 898.04 93. 70 3.57E-02 5.87E-02 8.lBE-02 1836.06 99.20 1.SOE-03 5.87E-02 + NB-94 702.63 100 . 00 2.59E-02 6.46E-02 6.46)::-02 B71.10 100.0 3.12E-03 i.69E-02 + I-131 284.30 6.06 1.83E-03 7.04E-02 9.43E-Ol
9/23/2019 3:32:06PM Page 6 of7 AnaiyelB Report for L2-D1M01-FSGS-001-SS L2-011-101 Nuclide Enerw Yield(%) AcUvny HuclldeMDA t.lneMDA Name (pCVgra,,,.J (pCl/gnlms) (pCVs,,ams} (k*V) I-131 364 . 48 81.20 -1.24E-02 7.04E-02 7.04E-02 636.97 7.27 1. 70E-01 l.03E+OO + CS-134 604.70 97.60 -2.liE-02 7.40E-02 8.33E-02 195.84 85.40 -1,02E-01 7.40E-02 + CS-137 661.65 85.12 6.70E-02 8.22E-02 8,22E-02 + CE-144 80.12 1.36 4.30E-01 4.03E-01 5.24E+OO 133.51 11.09 -9.llE-02 4.03E-Ol + EU-152 121. 78 28.40 - 1 .0?E--01 1. 56E-01 l,56E-01 344.28 26.t>O 1.02E-01 1.96E-Ol 1408.00 20.14 1.13E-01 3.92E-01 + EU-154 123.07 40.40 -5.83E--02 l.lOE-01 1.lOE-01 723.30 19.70 -4.86E-02 3.14E-01 1274.51 35.50 7.lSE-02 2.53E-01 + EU-155 86.54 32.80 -5.12E-02 1. BlE-01 1. 81E-01 105.31 21.80 -1. 76E-01 2.17E-01 + BI-214 609.31
- 46.30 1, HE-01 1.39E-Ol l. 39E-01 1120.29 15.10 2,28E-01 6.SOE-01 1238 .11 5.94 9.28E-Ol l.67E+00 1377.67 4 .11 -3.31E-01 1.58E+OO 1407.98 2.48 9.43E-01 3,27E+OO 1509.19 2.19 2.39E-02 3.21E+OO 1164.49 15.80 3.03E-01 5.SlE-01
+ PB-214 77.11 10. 70 5.86E-01 1. 43E- 1 7.19E-01 295.21
- 19.20 2.16E-01 1.79E-01 351.92
- 37.20 1.25E-01 1,43E-01
+ PA-228 89.95 22.00 1. 74E+OO 1. 64E+00 2.75E+OO 93.35 35.00 5.09E-02 l.64E+OO 105.00 16.30 -1.SOE+OO 3.09E+OO 129.22 2. 97 -5.14E+OO 1.58E+O l 338.32
- 5.30 -B.69E-01 1.02E+Ol 463.00 13.B0 2.29E+OO 4.57E+OO 911.23 16 . 70 2.49E+OO 5.83E+OO
+ AM-241 59.54 36.30 1. 09E-01 3.41E-Ol 3.41E-01
+ CM-243 103.76 23.00 2.56E-02 2.12E-01 2.12E-01 228.18 10.60 -1. 75E-02 4.30E-01 27'7. 60 14.00 -7.04E-02 3.35E-01
+ = Nuclide idenlifled during lhe nuclide lelentlftcation
* = Energy line found In 1he spectrum
> = MDA value not calculated
@ = Half-life too short ID be able to perfonn the deCay mnectian
? = CAUTION: MDA value is inconaistent wlttl CUnle MDA Ill 95% confidence level
9/231.2019 3:32:0EIPM Pa.!!e7 ot7 Analysis Report for LZ-011-101-FSGS-0O1-SS 1.2-011-101
9/23/2019 4:34:53PM Page 1 of6 Analysis Report for l2-011-101-FSPA-002-AV L2-011-101 GAMMA SPECTRUM ANALYSIS Sample ldantificetion ; l2-011-101-FSPA-002-AV Sample Ceac:rfptlon : L2-011-1O1 Sample T)118 : 500 ml MameHi Unit BamplePoiit Sampestze : 6.797E+02 grams Facllty :~PP Sample Taken On : 9'20/2019 12:46:DOPM Acquleltton Started : 9123/'l019 4:04:30PM Procedure : 500ml MarlneUI Opemor : Administrator Detector Name :HOTLAB Geometry : 500ml Mainalll UwTime : 1800.0 eeccnde Realllme : 1805.8 seconds Dead Time : 0.32 % Peak l.ocele Threshold : 3.00 Peak Locate Range (In cnannela) : 100-4098 PeakArea Ralge (In chamels) : 100-4096 Identification Energy Tolerance : 1.000 keV En"ll)' Calbrallon I.bed Done On : 7IBl2014 Efficiency Calbtation Used Done On : 7/Bl2014 efficiency c.tbnltlon Deec;ription Sample Number : 7479 PEAK ANALYSIS REPORT Peak Analyais Perlormed on : 9'2312019 4:34:44PM PeakAnalyala From ctiannel : 100 PeakAnalyais To Channel : 4096
9/23/2019 4:34:53PM Page 2 of6 Analysis Report for L2-011-101-FSPA-002-AV L2-011-101 Peale Energy ROI ROI Pnk NetPealr NelArN Continuum FWHM No. (bVJ start end Centroid A,u Uncertmnty Counts (k*VJ F 1 238.38 470 - 48 1 477.24 6.64E+Ol 24.41 3.02E+02 1.13 F 2 295.08 583 - 597 590.62 5.28E+Ol 20. 64 2.03E+02 1. 45 F 3 351.76 700 - 708 703.94 9.28E+Ol 22.94 9.65E+Ol 1.28 F -4 609.21 1211 - 1225 1218.76 6.94E+Ol 18.75 5.99E+Ol 1. 64 F 5 910.98 1818 - 1827 1822.20 l.62E+Ol 9.20 1.21E+Ol 1.31 F 6 1460.40 2915 - 2928 2920. 91 l.SBE+02 25.82 1,40E+Ol 2.22 M = Rrst peak In a multiplet region m = other peak In e multiplet region F =FIiied singlet Errors quomd at 2.0001lgma BACKGROUND SUBTRACT REPORT Peak Analysis Pefformed on : 9!.!3/2019 4:34:4-CPM Env. Background FIie : C:\Canberra\Apex\RocN)al,yland_NPP\Da1a\0000001364.CNF Peale Energy Original Orig.Alff Ambient Beclrgr. SubtnH;tad SubtnH:tad No. (lceV) A,- Uncertainty Background Uncert. ARNI unceri. F 1 238.38 6.64E+Ol 24 . 41 6. 64E+Ol 2-. 44E+0l F 2 295.08 5.28E+Ol 20.64 5. 28E+Ol 2.06E+Ol F 3 351. 76 9 . 28E+Ol 22.94 4 . 18E+Ol l.86E+0 l 5 .lOE+Ol 2.95E+01 F 4 609 . 21 6,94E+Ol 18.75 2.06E+Ol l.21E+Ol 4.89E+Ol ~.23E+Ol F 5 910 . 98 1. 62E+Ol 9.20 1 . *62E+Ol 9.20E+OO F 6 1460.40 l . 58E+02 25.82 2.82E+Ol 8.5'7E+OO 1.30E+02 2 . 72E+Ol M "' Finit pNk in a multiplet region m
- Od'ter peak in a multiplet region F .. Fitted slnglat Errors quoted at 2.000sigma
9/23/2019 4:34:53PM Page 3 of6 Analysis Report for L2-011-101-fSPA-002-AV L2-011-101 NUCLIDE IDENTIFICATION REPORT Nuclldlt Library U.ed : C:\Canberta\Apu\RooNlllryland_NPP\Llbrary\HOTl.AB.NLS IDENTIFIED NUCLIDES Nrn:llde Id Energy Yield(%) Actlfllty Activity Neme Canlfdsnce (bVJ (pCV,,,.,,,.) Uncertainty K-40 0.98 1460.75
- 10.67 4.lSE+OO 9.02E-Ol PB-212 0.55 7'7 .11 17.50 238.63
- 44.60 1. 0lE-01 3.74E-02 BI-214 0.34 609 . 31
- 46.30 1.66E-Ol 7.62E-02 1120. 29 15.10 123B.ll 5. 94 1377. 67 4.11 1407.98 2.48 1509.19 2 .19 1764.49 15.80 PB-214 0.71 7'7.11 10.70 295.21
- 19.20 2.22E-Ol 8.75E-02 351.92
- 37.20 1.30E-0l 7.53E-02
- a: Era'gy line found In 1he spectrum.
-
- Manually added nudlde.
? = Manually ecitad nuclde.
@ = Energy line not used fur Weighted Mem1 AciM1y Ehellb' Tolerance : 1.000 'aV Nudfde mnftclence index ttveahold = 0.30 Errors Quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nudlde Nut:llde INrmNn wrmeen Comments Name Id Acflvlty Activity Contidenee Unt:erfalnty (pCVgrama)
K-40 0.980 4.15E+00 9.02E-Ol PB-212 0.553 l.OlE-01 3.74E-02 BI-214 0.349 l.66E-01 7.62E-02
9/23/2019 4:34:53PM Page4of6 Analysis Report for L2-011-101-FSPA-002-AV L2-011-101 Nuclide Nuclide Wtmun Wtmean Comments Name Id Act/Vlty Activity Confidence (pCVgrama) Uncertainty PB-214 0.718 l.69E-01 5.71E-02 1 = nudlde Is part of an undelllnninad aolutloo X = nudlde rejected by the Interference analysis
@ = nucllde contains energy lines nut UIHld in Weighted Mean ActMty En0rs ql.lOl8d at 2.000&igma
9/23/2019 4:34:53PM Page S of6 Analysis Report for L2-011-101-FSPA-002-AV L2-011-101 UNIDENTIFIED PEAKS Peak Locate Performed on : 8.12ar.i!019 4:34:44PM Peak Locate From Channel : 100 Peak Locate To Channel : 4098 Pnlc CPS (3/4) Ta/91111nce PealrNa. Energy (keV) PNk Sin (CPS} Unce,talnty Nuclide F 5 910.98 8.98105E-03 28.47 Tol. AC-228 PA-228 M = Fll"llt peak In a muldl)let region m = other peak in a muHlplet regton F ;; Fitl8d silglet Ertol'I qualld at 2.000slgma NUCLIDE MDA REPORT
~Ide Lhary Uaed : C:\Canbemi\Apex\Root\Dairyland_NPP\Lix'aly\HOTLAB.N~
Nucllde Energy Waldt"J AclMty NudldeMDA LlneMDA Name (PC..,,.) (pCVgnlm*) (p~J (hV) + K-40 1460.75
- 10.67 4.lSE+OO 9.44E-01 9.44E-Ol
+ AR-41 1293.64 99.16 -2.0 l E+ll 1. 87E+ll 1.87E+ll + C0-60 1173 . 22 1332.49 100 ._DO 100.dO
-2.40E-02 2.37E-02 8.SlE-02 8 . 99E-02 8.SlE-02
+ KR-85 513. 99 0.43 1.64E+Ol l.65E+Ol 1.6SE+Ol + Y-88 898.04 93.70 5.53E-02 7.lOE-02 8.57E-02 1836.06 99.2 0 -2.25E-02 7.lOE-02 + NB-94 702.63 100.00 3.56E.-02 6.48E-02 6.48E-02 871.10 100.00 -4.998-03 7 .13E-02 + I-131 284.30 6.06 -2.63E-Ol 8.37E-D2 l.06E+OO 364.48 81.20 -1. 70E-02 8.37E-02 636.97 7.27 -6.SBE-02 1.12E+00 + CS-134 604.70 97.60 -2.67E-02 8 . 52E-02 9.02E-02 795.84 85.40 4.18E-02 8 . 52E-02 + CS-137 661. 65 85.12 l,34E-Ol 9.60E-02 9.60E-02
9/23/2019 4:34:53PM Page 6 of6 Analysis Report for L2-011-101-FSPA-002-AV L2-011-101 Nuclide Enelf1Y Yleldl%J Activity NuclldeMDA LJneMDA tum* (pellgn,ms) (pCVgn,msJ (pCVg,ame) (lreVJ + CE-144 80 .12 1.36 3.31E+OO 4.39E-Ol 5.6?E+OO 133.51 11.09 2 , SOE-01 4.3 9E-01 + EU-152 121. 78 28.40 -1.09E-02 l.63E-01 1.63E-01 344.28 26.60 -4.29E-Ol 2.13E-01 1408.00 20.'74 l.lBE-01 4.00E-01 + EU-154 123.07 40.40 -4 .31E-02 l.16E-01 l.16E-01
'723.30 19.70 3. lBE-01 3 . 47E-Ol 1274.51 35.50 -4 .52E-02 2.34E-01
+ EU-155 B6.54 32.80 -1, 10E-01 1.91E-01 l. 91E-01 105.31 21.80 -l. D7E-01 2,25E-01 + BI-214 609.31
- 46.30 1 . 66E-01 1 .43E-01 1. 43E-Ol 1120.29 15.10 1. 99E-01 7.28E-01 1238.11 5.94 7 . 95E-01 1.93E+00 1377.67 4 .11 1 . 12E+OO 2.16E+OO 1407.98 2.48 9.82E-Ol 3.34E+00 1509.19 2.19 3.81E-01 3.02E+OO 1764.49 15.80 5.83E-01 6.35E-Ol
+ PB-214 77 .ll 10.70 7.25E-01 1. 34E-Ol 7 .66E-Ol 295.21 19.20 2.22E-01 2.48E-Ol 351.92 ..* 37.20 1.30E-01 1.34E-Ol + PA-228 89.95 22.00 7.22E-Ol l.78E+OO 3.00E+OO 93.35 35.00 1.28E+00 1. 78E+OO 105.00 16.30 -1. 0BE+00 3.28E+OO 129.22 2.97 2.llE+OO 1. 73E+01 338.32 5.30 2.06E+OO 1.14E+Ol 463.00 13.80 8,BlE-01 4 . 56E+OO 911.23 16.70 l.60E+00 5.21E+OO + AM-241 59.54 36.30 l.SSE-01 3.61E-Ol 3 . 61E-01 + CM-243 103.76 23.00 9.25E-02 2. 1 9E-Ol 2.19E-01 228 . 18 10.60 -B.20E-02 4.55E-01 277.60 14.00 -2 .20E-01 3.47E-01
+ '"' Nuclide identified during the nucllde Identification
* = Energy line found in the apeclrum
> = MDA value not calculated 0 = Half.life too llhort. to be able to perform ltte decay carrecdon 7 = CAUTION: MDA value ia lnconelatent with Cun1e MDA al 85% confidence level
9124/2019 7:18:51AM Page 1 of6 Analysis Report for L2-01M01-FSPA-003-AV L2-011-101 GAMMA SPECTRUM ANALYSIS Sample Identification : l2-011-101-FSPA-003-AV Sample Delcflptlon : l2-011-101 Sample Type : 500 ml Marinelli Unit SamplePMtl SampJoSlze : 7.209E-+-02 grams Feclllty : Dairyland.J4PP Sample Taken On : 8120/2019 3:20:00PM AcquleltJon St8r1ed : 812412019 8~:33AM ProcadU'11 : 50IJrl'j Marinelli Oparator : Administrator Detector Name : HOTLAB Geomelry : SOOmlt.Analli Lfvellme : 1800.0 aecand& Realllme : 1805.7 seconds Oelldllme : 0.31 % Peak Locate Th1'811hokf : 3.00 Peak Lacate Range On channeta) *: 100*4D98 Pellk Atee Range (In channels) : 100-4098 ldantifieatlon Energy Tolerance : 1.000keV Energy Call>rallon USed Done On : 7/Bl2014 Effid1mcy Calibration Uaed Oona On : 718f2014 Efficiency Cllllbratlon Deec;nptlon Sa-nple Number : 7482 PEAK ANALYSIS REPORT PeakAnalyaia Paformad on : 912A/2019 7:18:42AM F1eak Analyale From Channel : 100 Peak Analyela To ChaMel : 4096
9/2412019 7:18:51AM Page 2 of6 Analysis Report for L2-011-101 -FSPA-()()3-AV L2-011-101 Peaff Enerr,y ROI ROI Peak NfltPNlr NetAru Continuum FWHM No. (keV) mrt and Centroid AIN Uncertainty Counts (lreVJ F 1 185.84 364 - 377 3 72. 18 4.30E+Ol 22.27 3.32E+02 1. 30 F 2 2 3 8.63 4 73 - 4 85 477 . 7 3 1. 20E+02 26.96 l. 90E+02 1.51 F 3 2 95.21 586 - 595 590.88 5.17E+Ol 19.04 l.23E+02 1. 1 4 F 4 351.87 700 - 709 704 . 18 7.38E+Ol 21.33 9.21E+01 1. 53 F s 609.06 1212 - 1225 1218.46 4 . 93E+Ol 16.19 S.-86E+Ol 1.37 F 6 911 .28 1817 - 1827 1822 . 79 1 . 94E+Ol 10.33 2 ~20E+Ol 1.22 F 7 1460.58 291 3 - 2929 2921. 27 2.24E+02 30~37 l.29E+Ol 2 . 34 M "' First peak In a m.illlpklt region m "' other peak In a multiplet region F ,. Fitted singlet Emn quoted at 2.000slgma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/24/2019 7:18:42AM Env. Background Fie : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Orlgfn*I Orlg.AtH Ambient Badrr,r. Subtncted Subtracted No. (kallJ Aree Uncertainty Background Uncen. AIN Um:ert. F 1 185.84 4.30E+01 22 .27 4.30E+01 2. 2 3E+Ol F 2 238*. 63 l.20E+02 26.96 l.20E+02 2. 70E+Ol F 3 295.21 S. 17E+Ol 19 . 04 5.17E+Ol 1 .90E+Ol F 4 351.87 7.38E+Ol 21.33 4.18E+Ol 1. 86E+0l 3.20E+Ol 2.83E+01 F 5 609.06 4.93E+Ol 16.19 2.06E+Ol 1. 21E+Ol 2.87E+Ol
- 2.02E+Ol F 6 911.28 l. 94E+Ol 10.33 1. 94E+.0 1 *l.03E+Ol F 7 1460.58 2.24E+02 30 . 37 2.82E+01 8 , 57E+OO 1 . 96E+02 3.16E+Ol M "' First peak In a mulllplet regioo m
- Other peak In a majtlplet n,gion F
- Fitted singlet
&tors quoted at 2.000ligma
9/24/2019 7:18:51AM Page 3 of6 Analysis Report for L2-011-101-FSPA--003-AV L2--011-101 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Rcot\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy 'lle/d(%) AcfMly Activity Name Contldent:e (keV) (pevg,.,na) Um:erllllnty K-40 0. 99 1460 . 75
- 10.67 5.93E+OO 1.0lE+OO PB-212 0. 56 77.11 17.50 238.63
- 44.60 1 . 71E-Ol 3.96E-02 BI-214 0.34 609.31
- 46.30 9.17E-02 6.48E-02 1120.29 15.10 1238 .11 5.94 1377. 67 4 .11 1407.98 2 . 48 1509. 1 9 2.19 1764.49 15.80 PB-214 0.72 77.11 10.70 295.21
- 1 9.20 2.0SE-01 7.62E-02 351.92
- 37.20 7.68E-02 6.79E-02 RA-226 0.97 186.21
- 3.28 7.03E-Ol 3.66E-Ol
* =Energy Una found In 1he epec;tnJm.
* =Manually added nudide.
? =Manually edil9d nuclide.
@ =Energy line not used for Weighted Mean ActMty Energy Tolerance : 1.000 keV Nuclde confidence Index tnreshold = 0.30 Errol'I quoted at 2.000ligma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmean Wtmaan comments Name Id ActMty Acttwty Conlfdance Uncertainty (pCVgrams)
K-40 0.995 S.93E+OO 1.0lE+OO PB-212 0.5 60 1. 71E-Ol 3.96E-02
9/24/2019 7:18:51AM Page 4 of6 Analysis Report for L2-011-101-FSPA-003-AV L2-011-101 Nuclide Nuclide wtmNn wtmNn Comment. Name Id Af:tlvity Activity eontfdem:* (pCVgrams) Uncertainty BI-214 0.345 9.17E-02 6.48E-02 PB-214 0.721 . L34E-01 5.07E-02 RA-226 0.978 7.03E-Ol 3.66E-01
? = nuc:llde Is part ~ an undetermined solution X = nucllde rejected by the Interference armlysls G = nuclde contains energy lines not used in Weighted Mean AcllvllY Errors quoted at 2.000aigma
9124/2019 7:18:51AM Page S of6 Analysis Report for L2-011-101-FSPA-003-AV L2-011-101 UNIDENTIFIED PEAKS Peek Locata Performed on : 9/2-412019 7:18:42AM Peak Loada From a,annel : 100 Peak Locate To Channel : 4096 PeakCPS ('1/4) Peak Tolerance l'NkNo. Peele Sb (CPS) Uncertainty 'f)P9 Nucllde F 6 911.28 1.07757E-02 26.62 AC-228 PA-2 28 M ., Flllt peak In a mu~et region m = Olller peak In a multiplet region F = Fitted singlet Enora quoted at 2.000elgma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP'll.ibrary\HOTLAB.NLB Nuclide Energy Vleldt"') Actlvtty NuclldellDA un,MDA Heme (hV) (pCl/gtam*J (pCVg,ama) (pCf/glama) + K-40 1460.'75
- 10.67 S.93E+OO 8.94E-Dl 8.94E-01
+ AR-41 1293.64 99.16 1. 06E+13 2. 58E+l 3 2.58E+13 + C0-60 1173.22 100.00 1.l0E-02 8.54E-02 l.OSE-01 1332 .49 100.00 -4.53E-02 8.54E-02 + KR-85 513.99 0 .43 5.96E+OO 1. 54E+Ol 1.54E+Ol + Y-88 898.04 93.70 4.52E-02 5.68E-02 B.26E-02 1836. 06 99.20 2 . lBE-03 5 . 68E-0 2 + NB-94 702 .63 100.00 - 3. 67E- 03 6.73E-02 fi.73E-02 871.10 100.00 -8 .0SE-02 7.74E-02 + I -131 284.30 6.06 1. 66E-Ol 8 . 57E-02 l. lSE+OO 364.48 81.20 -1 ,J5E-02 8.57E-02 636 . 97 7.27 -4 .0BE-Ol l.09E+OO + CS- 134 604.70 97.60 5.34E-04 B.1 4E-02 8.14E-02 795.84 85.40 -l.99E-02 8.39E-02 + CS- 137 661.65 85.12 5. llE-02 8.74E- 02 8.74E-02
9/24/2019 7:18:51AM Page6 of6 Analysis Report for L2-011-101-FSPA-003-AV L2*D11-101 Nuclide Ene,vy YJefdf"J Activity NualdeMDA Llne&fDA Name (pCVgra,m) (pCV,,.,,,SJ (pCVgntn5) (lc*VJ + CE-144 80.12 1. 36 2.85E+OO 4.06E-01 5.33E+OO 133.51 11. 09 -3.20E-01 4.06E-01 + EU-152 121. 78 28,40 -3.61E-03 l.61E-01 l.61E--01 344.28 26.60 -l.62E-01 2.llE-01 140B.OO 20.'74 -1.42E-Ol 3.03E-01 + EU-154 123.07 40.40 3.43E-02 1.14E-Ol l.14E-01 723. 30 19.70 8.34E-02 3.38£-01 1214.51 35.50 -6.52E-02 2.48E-01 + EU-155 86.54 32.80 -6. 39E-02 1. BlE-01 l. BlE-01 105.31 21.80 -9.48E-02 2.15E-01 + BI-214 609.31
- 46.30 9.17E-02 1.32E-Ol 1. 32E...:01 1120.29 15.10 1. 89E-Ol 6.62E-01 1238.11 5. 9-4 l.14E+OO 2.00E+OO 1377.67 4.11 -1.48E+OO l.90E+OO 1407.98 2.48 -l.19E+OO 2.53E+OO 1509.19 2.19 2.59E-01 2.85E+OO 1764.49 15.80 1.85E-01 5.37E-Ol
+ PB-214 77.11 10.70 7.61E-01 1.27E-Ol 7.36E-01 295.21 19.20 2 , 0SE~Ol 1. 64E-01
- l. 27E-Ol 351. 92
- 37.20 7.68E-02
+ PA-228 89.95 22.00 -l.12E+OO 2.44E+00 4.03E+OO 93.35 35.00 4.86E-01 2.44E+OO 105.00 16.30 -3.39E+OO 4.55E+OO 129.22 2.97 3.29E+OO 2.40E+Ol 338.32 . 5.30 -1.95E+OO 1.57E+01 463. 00 13.80 1.88E+OO 7.03E+OO 911.23 16.70 5.94:e:+oo 7.84E+OO + AM-241 59.54 36.30 9. 96'E_:02 3.34E-01 3 .34E...:.01
+ CM-243 103.76 23.00 -1. 68E-0l 2.04E-O1 2.04E-01 228.18 10.60 -4.69E-02 4.29E-Ol 277.60 14.00 -7.48E-02 3.59E-Ol
+
- Nuc~de ideotified during the nucllde Identification
= Energy lne round in ti,e spectrum
> = MDA valua not calcul91ed
@ = Half-life too short to be eble to perform the decay COffllction
? = CAUTION: MDA value is incanslstenl with Cunte MDA at 95% confidence level
9/24/2019 7:50:02AM Page 1 of6 JApex-Gamma Analysis Report for L2-011-101-FSGS-004-SS L2-O11-101 GAMMA SPECTRUM ANALYSIS Sample ldentfflcatlon : L2-01M 01-FSGS-004-SS SsnJ)le D11crlr,tion : 1.2-011-101 Sample Type : 500 mf Marinelli Unit Sample Paint Sample Size : 9.312E+02 grams Fadllty : Dlll~and__NPP Sarr1Jle Taken On : 9/20J2019 1:52:DOeM Acqulailion Started : Bf.W2019 1:1D~ Procedure : 500ml Marinelli Operator : Admlnlstnmir Delac10r Name :HOTLAB
- Geometry : 500ml Marinell Llvallma : 1800.0 seconds Realllrne : 1805.6 seconds Daed11me : 0.31 %
Peek l..ocal9 Threshold : J.00 Peak Loaste Range {In ct.nnall) : 100-4098 PB hea Range (In dlal"l'lela) : 100-4098 ldenllftcatlon Energy Tolerance : 1.000keV Energy Callntlon Used Done On : 71112014 Effleiency callbrallon Used Done On : 7J8/2014 Efficiency Cell,rallcn Deecrlptlon Sample Number : 7-183 PEAK ANALYSIS REPORT Peak Analyaie Performed on : 9/24/2019 7:49:54-AM Peak Analyala From Channel : 100 Peak Analysis To Cl'lannel : 4096
9/24/2019 7:50:02AM Page2of6 Analysis Report for L2-011-101-FSGS-004-SS L2-011-101 Peele Energy ROI ROI Pealr NetPfflc NetAIH Continuum FWHM (hVJ start end Centroid Area Uncertainty Counts (lreVJ No. F 1 238.30 474 - 481 477 . 07 3.83E+Ol 20.00 2.20E+02 1.39 F 2 295.12 584 - 595 590.69 6,27E+Ol 22. 7 8 2.02E+02 1.42 F 3 352.01 700 - 711 704.45 l.33E+02 25.45 8.52E+Ol 1.34 F 4 477.43 950 - 960 955.25 3.29E+Ol 14.93 7.66E+Ol 1.15 F 5 609.22 1213 - 1224 1218. 7 7 6.lOE+Ol 18.66 6,00E+Ol 1. 74 F 6 1460.81 2915 - 2928 2921. 73 1. 14E+02 22.76 2. 71E+Ol 2.43 M
- Flnt peak In a mulllplet region m
- Other peak In a muldplet region F = Fillsd singlet Emn quoted at 2.DOOslgma BACKGROUND SUBTRACT REPORT Peak Analysis P9rformed on : 9/24/2019 7:49:54AM Env. Badcground FIie : C:\canberra\Apex\Root\Dalryland_NF'PIData\0000001364.CNF Peak Enerr,y Original Orig. Area Ambient BM:kgr. Subtracted Subtracted No. {keV) AtN Uncertainty Background Um:ert Ante Unc81t.
F 1 238.30 3.83E+Ol 20 . 00 3 . 83E+Ol 2 .00E+Ol F 2 295.12 6.27E+Ol 22.78 6 . 27E+Ol 2.28E+Ol F 3 352 .01 l.33E+02 25.45 4.l8E+Ol 1. B6E+0l 9.15E+Ol 3,15E+Ol F 4 4 77. 43 3.29E+Ol 14.93 3 . 29E+Ol 1,49E+Ol F 5 609.22 6.lOE+Ol 18.66 2.06E+Ol 1.21E+Ol *4.05E+Ol 2.22E+Ol F 6 1460. 81 1.14E+02 22.76 2.82E+Ol 8.57E+OO 8.55E+Ol 2.43E+Ol M "' First peak in a multiplet region m = Other peek In a mutiplet region F = Rited singlet Errors quoted at 2.000aigma
9/24/2019 7:50:02AM Page 3 of6 Analysis Report for L2-011-101-FSGS-o04-SS L2-011-101 NUCLIDE IDENTIFICATION REPORT Nucllde Library Uled : C:\Cenberra\ApeX\Rool\Dalryland_NPP\Lltnry\HOn>.B.NLB IDENTIFIED NUCLIDES Nucllde Id Energy Yield(3/4) Advlty ActJmy Name Confidence {lr*VJ (pCVgra1n11} Unowtalmy l{-40 0. 9*9 1460.75
- 10.67 2.00E+OO 5.80E-01 PB-212 0. 54 77 .11 17.50 238.63
- 44. 60 4.23E-02 2.22E-02 BI-214 0. 34 609.31
- 46.30 1.00E-01 5,53E-02 1120. 29 15. 10 1238 .11 5.94 1377.67 4.11 1407 . 98 2 . 48 1509.19 2.19 1764.49 15.80 PB-214 0 .72 77.11 10 . 70 295.21
- 19.20 1 . 93E-Ol 7.06E-02 351.92
- 37.20 l.70E-Ol 5 .91E-02
* "' Energy line lbu'ld ln the speclrum.
- = MarAJally added nuclide.
? = Mcn.iaRy DCilDd nuclde.
@ = Energy line not used for W ~ Mean Actl\lltV Enerw Tolerance : 1.000 IO&V Nuclide canfldence Index lhre8hold "' 0.30 Errors quoted at 2.000eigmt INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmeen Wtmean Commants Name Id Actlvlty At:tfvlty Conlldetrc;e (pCVg,amsJ UncMalnty K-4 0 0.999 2.00E+OO 5 .80E-Ol PB-212 0.548 4.23E-02 2.22E-02 BI-21 4 0.3 49 l.OOE- 01 5. 53E-02
9/24/2019 7:50:02AM Page4 of6 Analysis Report for L2-011-101-FSGS-004-SS L2-011-101 Nuclide Nuclide Wtmean WtmNn Comments Name Id Activity Activity Con'fldence (pCVgrams) Uncertainty PB-214 0.720 1. 79E-01 4.53E-02
? = nudide is part of an \Jndetermlned solullon X = nuellde rajectad by the interference analysis
@ = nuclide contains energy lina not ueed In Weighted Mean Activity Errors quoted at 2.00()eigma
9124/2019 7:50:02AM Page 5 of6 Analysis Report for l.2-011-101-FSGS-004-SS l.2-011-101 UNIDENTIFIED PEAKS Peak Locate Performed on : 9/2-4/2019 7:49:5.fAM Peak Locate Frcxn Channel : 100 Peak Locate To Channel : 4098 PukCPS"') Pas/r Tolerance Peak No. Enwgy(b\1 PNlc Size (CPS} Unoerlalntv 1}'pe Nucllde F 4 477.43 1. 82708E-02 22.70 Sum M =- Rrsl peak In a muHIJllel region m = Olher peak In a multiplet region F = Fitted alnglet Errors quoted at 2.000alg ma NUCLIDE MDA REPORT Nualda Ubrary Used : C:\Canbena\Apex\RooflDalr)'tano_NPP\UbraryV-IOTI.AB.NLB Nuclide Ene,gy Vlehl!"J Activity Nuclide JIDA LlnaMDA Name (pCl/gramsJ (pCl/gre,q} (pCVgrama) th\l) + K-40 1460,7 5
- 10.67 2.00E+OO 7.67E-01 7 . 67E-Ol
+ AR-41 1293. 64 99.16 1.231Hl3 3.98E+13 3.98E+l3 + C0-60 1173.22 100.00 2.57E-02 6.51E-02 7.0lE-02 1332.49 100.00 1.27E-03 6.SlE-02 + KR-85 513.99 a. 43 1.18E+Ol 1.16E+Ol l .16E+Ol + Y-88 898.04 93. 10 -1.SlE-02 3.36E-02 S. 7 2E-02 1836.06 99.20 -4 .26E-02 3. 3 6E-02 + NB-94 702.63 100.00 4.3'7E-03 4.38E-02 4.38E-02 871.10 100.00 1. 28E- 02 5.95E-02 + I-131 284 .30 6 . 06 7.61E-03 6 . 90E-02 9.0BE-01 364.48 81.20 7.82E-03 6.90E-02 636.97 7.27 -4.02E-01 8.71E-01 + CS-134 604.70 97.60 -1 . 04E-03 6 . llE-02 6.35E-02 795.84 85. 40 -2.90E-03 6.ll E-02 + CS- 137 661. 65 85.12 4.67E-02 1.llE-02 7 .ll E-02 + CE-144 80.12 1.36 7.29E-01 3 , 43E-01 4.06E+OO 133.51 11.09 -1.46E-01 3 ,43E-01
9/24/2019 7:50:02AM Page6of6 Anatysls Report for L2-011-101-FSGS-004-SS L2-011-101 Nuclide Energy Yield(%) Activity Nuclide MDA L.ltfflllDA Name (pCUgrarm,) {pCVgramsJ (pCVgratu) (k*V) + EU-152 121.78 28.40 l.28E-Ol l.43E-01 1.43E-Ol 344.28 26.60 -l.46E-Ol l.64E-Ol 1408.00 20.74 -2.32E-02 2.92E-Ol + EU-154 123.07 40.40 1.49E-Ol 1.0lE-01 1. OlE-01
- 723.30 19.70 -9.02E-02 2.66E-Ol 1274.51 35.50 -1.89E-02 l.6SE-01
+ EU-155 86.54 32.80 9.29E-03 1.45E-01 l.45E-Ol 105.31 21.80 4.17E-02 1. 86E-Ol + BI-214 609.31
- 46,30 1.00E-01 l.OOE-01 1.00E-01 1120.29 15 .10 -5.54E-02 5.09E-01 1238.11 5.94 -6.36E-01 1.36E+OO 13'77.67 4.11 . 1.12E+OO 1.50E+OO 1407. 98 2.48 -1.94E-Ol 2.44E+OO 1509.19 2.19 -1.47E-01 l.95E+OO 1764.49 15.80 2.36E-Ol 4.16E-01
+ PB-214 17 .11 10. 70 -6.lOE-04 9 . B?E-02 5.42E-01 295.21
- 19.20 l.93E-Ol 1.69E-Ol 351.92
- 37.20 1.70E-Ol 9.87E-02
+ PA-228 89.95 22.00 1.82E+OO 2.09E+OO 3.55E+OO 93.35 35.00 -1.67E+OO 2.09E+OO 105.00 16.30 1.24E+OO 4.19E+OO 129.22 2. 97 -3.06E+Ol 2.18E+Ol 338.32 5.30 . 6.25E+OO 1. 35E+Ol 463.00 13.80 3.17E+OO 5.60E+OO 911.23 16.70 3.SOE+OO 6.0SE+OO + AM-241 59.54 36.30 -S.25E-02 2.71E-Ol 2.71E-Ol + CM-243 103.76 23.00 8.17E-02 1. 78E-01 l. 78E-01 228~18 10 . 60 9.46E-04 3.64E-01 277. 60 14 .00 -2.lOE-01 2. 71E-01
+ = Nuclide hfenlllled durinsi the nuclide Identification * =Energy tine found In the 9Pactrum > = MDAvalue net calculated 0 = Half-111'8 loo short lo be able to perform the decay oorrecllon ? = CAUTION: MCAvak.Je b! lnconslatent with Cunt& MCA at 95% confidence le\'el
9/24/2019 8:35:22AM Page 1 of 6 ~Apex-Gamma Analysis Report for L2-011-101-FSGS-005-SS l2-011-101 GAMMA SPECTRUM ANALYSIS Sample ldmttflcatlan : L2-011-1D1-F=SGS-OOS-SS Semple D11Cf1ptfon : L2-011-101 SM!plelype : 500 ml Marineli Unit Smnpie~ Sample Sim : 9.003E+02 grams Fecllty : Datrytand_NPP Sample Taken On : 9120/2019 2:01:00PM Acquisition Startsd : &rl4/2019 8:05:03AM Procedure : 500rnl Marinell Opera1Dr : Admlnletndor Oelact0r Name : HOltAB Gaomelry : 500rnl Marlnell LIYelime : 1800.0 seconds ReelT11ne : 1805.3 seconds Oeadllme : 0.30% Peak Locale Threshold : 3.00 PNkl.ocala Range (In chant"lela) : 100-4098 Peak Area Renge (in diamels} : 100-4098 Identification Energy Tolerance : 1.000 keV Energy Cellbratlon UHd Done On : 7/Bl2014 Effitiency calibration Used Done On : 7/812014 Eflldency Clft>rallcn Deaalpllon Sample Number : 7484 PEAK ANALYSIS REPORT Peek Analysis Perf'Drmed on : 9124/2019 8:35:13AM Peak Analyaia From aiannel : 100 Peak.Anatysia To Clwinel : 4096
9124/2019 8:35:22AM Pagc2of6 Analysis Report for L2-O11-1O1-FSGS-005-SS L2-011-1O1 Peale En8l'fly ROI ROI Pair NtltPesk Net.Atea Continuum FWHM No. (k*VJ start end centroid AIN Uncertalnt.y Counts (keV) F 1 185.47 368 - 378 371.44 3.311H01 20.72 2. 99E+02 1.03 2 238.48 474 - 481 477.43 3.41E+Ol 33.59 2.38E+02 0.92 F 3 295.07 584 - 595 590.58 5.97E+01 18.94 1.38E+02 0.85 F 4 351.86 697 - 710 704.15 l.32E+02 26.73 1.29E+02 1.70 F 5 609.15 1212 - 1226 1218.63 9.68E+Ol 21.91 6.0SE+Ol 2.00 F 6 910.83 1011 - *1e21 1821.90 l.83E+Ol 10.20 l.88E+01 1.47 F 7 1460.43 2914 - 2929 2920. 97. l.44E+02 24.69 l.70E+01 2.42 F 8 1764.49 3524 - 3534 3529.06 1. 95E+01 9.05 O~OOE+OO 2.01 M = First peak In a multiplet n:lglon m = Otner peak In a multiplet region F = Fitted Singlet EITOIS quoted at Z.OOOsigma BACKGROUND SUBTRACT REPORT Peale Analy9is Pertonned on : 9J2A/2019 8:35:13AM Env. Background FIie : C:\Ca,berra\Apex\Root\Delrylend_NPP\Oata\0000001364.CNF PHI< Ene,gy Original Orfg. Arff Ambient Baclcgr. Subtracted Subtracted (keV) Area Uncertainty Background Uncert. Area Uncert No. F 1 185.47 3.31E+Ol 20.72 3.31E+Ol 2.07E+Ol 2 238.48 3.41E+Ol 33.59 3.41E+Ol 3.36E+Ol F 3 295.07 5.97E+Ol 18.94 5.97E+Ol 1.89E+Ol F 4 351.86 l.32E+02 26.73 4.18E+01 1.86E+Ol 9.06E+Ol 3.26E+Ol F 5 609.15 9.68E+Ol 21.91 2.06E+01 1.21E+Ol 7.62E+Ol 2.50E+Ol F 6 910.83 1.83E+01 10.20 l.83E+01 1.02E+Ol F 7 1460.43 1.44E+02 24.69 2.82E+Ol 8.57E+OO 1.16E+02 2.61E+Ol 1764.49 1.95E+Ol 9.05 7.59E+OO 4.90E+OO 1.19E+Ol 1.03E.+01 F 8 M =First peak In a multlplet region m =Other peak in a multiplet region F = Flied sln~et Errors quoted at 2.000slgma
9/24/2019 8:35:22AM Page 3 of6 Analysis Report for L2-011-101-FSGS-005-SS L2-011-1D1 NUCLIDE IDENTIFICATION REPORT NucRda Library Used : C:\Canbeml\Apex\RoDf\Delryland_NPP\Ubrlry\HOTI.AB.NLB IDENTIFIED NUCLIDES Nucllde Id Enel'{IY Yield(%) ACCMty Activity Name ConlldfHJt:e (keV) (pCVgrama) Uncett.alnty K-40 0.98 1460.75
- 10.67 2.BOE+OO 6.SlE-01 PB-212 0.55 77.11 .1 7 .so 238.63
- 44.60 3.91E-02 3.85E-02 BI-214 0.55 609.31
- 46.30 1. 95E-Ol 6.49E-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 2.27E-01 1. 98E-Ol PB-214 0 .72 77 .11 10.70 295 .21
- 19.20 1.90E-Ol 6.09E-02 351.92
- 37.20 1.74E-01 6.31E-02 RA-226 0 .91 186.21
- 3 * .28 4.32E-01 2.72E-Ol
* = Erwgy nne found in the apec:trum.
- =Manually added nucid&.
? a Manually edited nudida.
@ = Erwgy Nne not uaed for Weighted Mean Activity Energy Tolef8nee : 1.000 keV Nuclide confidence Index threshcld = 0.30 Errol'B quoted at 2.000algma INTERFERENCE CORRECTED REPORT Nuclide Nuclide wrmean Mmean Comments Name Id Activity Activity ConRdenoa Uncertainty (pCl/grams}
I<:-40 0.984 2.BOE+OO 6.SlE-01 PB-212 0 .558 3.91E-02 3.85E-02
9/24/2019 8:35:22AM Page 4 of6 Analysis Report for L2-011-101-FSG~05-SS L2-011-101
- Nuclide Nuclide mmean mmean Comments Name Id Activity Activity Calffldence (pCl/grams) Uncertainty BI-214 0.550 1.98E-01 6.17E-02 PB-214 0.720 l. 82E-01 4.38E- 02 RA-226 0.916 4 . 32E~Ol 2.72E-01 1 = nudid* is pert of en undetermined solution X = mdde reiactlld by the interference analysls
@ = nuclida contains energy lin85 not-used In Weighted Mean ActMty Enors quoted at 2.0DOslgma
9/24/2019 8:35:22AM Page S of6 Analysis Report for L2-011-101-FSGS-005-SS L2-011-101 UNIDENTIFtED PEAKS Peak Locate Performed on : 912412()19 8:35:13AM Peek Locate From Channel : 100 Peak Locate To Channel : 4096 PeakCPS"'J Tolerance PealcNo. Energy(hV) Pwlr Ske {CPS) Uncerteltdy Nuclide F 6 910 -83 l.0l 789E-02 27.85 Tol. AC-228 PA-228 M ,. Fhl peek In a mulllplet region m = other peak In a multlplet region F = Fitted singlet Enc11 QuotGd at 2.000slslma NUCLIDE MDA REPORT Nucllde LAnry Used : C:\Canberra\Apex~ot\Daiyland_NPPilibrary\HOTLAB.NLB Nur;llde EnwvY Yfald{M) Activity Nuclide IIDA Une.llDA Name (pCV,,,,,,,.) (pCVgn,ma) (pCl/glams) (IN'l'J + K-4*0 1460.75
- 10. 67 2.BOE+OO 7.47E-01 7.4'?E-01
+ AR- 41 1293_ 64 99. 1 6 2.81E+l3 5.10E+l3 5.10E+13 + CO-60 1173.22 100.00 2.14E-02 6,32E-02 7.40E-02 1332.49 100.00 -3 . 62E-02 6.32E-02 + KR-85 513.99
- 0. 43 1. 578+01 1.23E+0l 1.23E+Ol
+ Y-88 898.04 93.70 1. 98E-02 5 . 12E-02 5 , 64E-02 1836.06 99.20 2_58E-02 5.12E-02 + NB-94 702.63 100.00 2 . 33E-02 5.35E-02 5,35E-02 871.10 100.00 -5.27E-03 6.25E-02 + I-131 284.30 6.06 -3.92E-01 6. 77E-02 8 . 42E-0l 364.48 81.20 -1.19E-02 6.77E-02 636.97 7.27 9.49E-02 8.12E- Ol + CS-134 604 . 70 97.60 -2 .23E-02 6.26E- 02 7 .SlE-02 795.84 85. 40 -5 .48E-02 6.26E-02 + CS- 137 661. 65 85.12 B.35E-02 7. 00E-02 7.00E-02
9/2412019 8:35:22AM Page6of6 Analysis Repart for L2-011-101-FSGs.-005-SS l.2-011-101 Nuclide EINIIIY w.td{%}- Advlty NuclldeMDA UneMDA Name (pCVgrams} (pCl/gnuns) (pCl/gralna) (ke\lJ + CE-144 80.12 1.36 1.llE-Ol 3.32E-Ol 4.l6E+OO 133.51 11.09 -8.SSE-02 3.32E-Ol + EU-152 121. 78 28.40 -1.25E-02 1.35E-01 1.35E-Ol 344.28 26.60 2.77E-02 1. 65E-01 1408.00 20.74 2.78£-01 3.02E-Ol + EU-154 123.07 40.40 2.03£-02 9.48E-02 9.48E-02 723.30 19.70 3.70£-02 2. 57E-01 1274.51 35.50 4 .19E-.02 1.96E-Ol + EU-155 86.54 32.80 -7.63E-02 1. 47E-01 l.47E-01 105.31 21.80 8.85E-02 1.81E-01 + BI-21.4 609.31
- 46.30 1 .95E-01 1.08E-01 1.08E-Ol 1120 .29 15.10 3.lOE-01 5.0SE-01 1238.11 5 .94 8.79E-Ol 1.24E+00 1377.67 4.11 6.24E-01 1.41E+OO 1407.98 2.48 2.32E+OO 2.52E+OO 1509.19 2.19 4.21E-01 2.79E+OO 1764 .49
- 15.80 2.27E-01 2.84E-Ol
+ PB-214 77.11 10.70 6.43E-01 1.16E-01 5.61E-Ol 295.21
- 19.20 l.90E-01 1.46E-Ol 351.92
- 37.20 1.74E-Ol 1.16E-01
+ PA-228 89.95 22.00 1.06E+0O 2.09E+00 3.59E+OO 93.35 35.00 -9.44E-01 2.09E+OO 105.00 16.30 1. 71E+0O 4.14E+OO 129.22 2.97 -1.16E+01 2.14E+Ol 338.32 5 .30 -5.65E+OO 1.32E+Ol 463.00 13.80 -5.76E-O~ 5.34E+OO 911.23 16.70 2.29E+OO 6.43E+OO + AM-241 59.54 36.30 3.46E-03 2 . 68E-Ol 2.68E-01 + CM-243 103.76 23.00 -3.60E-02 1.?0E-01 1.70E-Ol 228.18 10.60 -1.27E-O1 3.58E-01 277. 60 14.00 7,65E-02 2.89E-Ol
* = Nuclide ldentlfled during the nuclide identification
* = Energy line found In the spectnJm
> :: MDA value not calcUlated
@ = Half-llfe too short to be able lo perfonn 1he decay eorTe<<mon
? = CAUTION: MDA value Is lncongfstent with CUnie MDA et 95% confidence level
iflt'. 9/24/2019 9:05:59AM Page 1 of6 .~ Apex-Gamma Analysis Report for l2-011-101-FSGS-006-SS l2-011-101 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-011-101-FSGS-006-SS Sample DNCI IJJtion : l2-011-101 SempleTYJJB : 500 ml Mamenl Unit Sample Point SmnpleSlze : 8.720E+D2 gram& Facllty : Oaiiyland_NPP Sample TakBl"I On : 9120/2019 2:14:DDPM Acquietiion Started : 9/24/2019 8:35:~ Procadun, : 500ml Marlnelll Opera1cr : Admlnlatralnr
~rNane :HOTLAB Geometry : 500ml Mameli Llvallme : 1B00.0 aaconde Realllme : 1805.6 &eamda Dead lime : 0.31 %
Peak Locate Threshold : 3.00 PefJk uicate Range (In channela) : 100-4098 Peak Area Range (In chamals) : 100-4096 ldentfflcatlon Energy Tola,.nc:e : 1.00DkeV Energy Call>ratlon Used Done On : 7l9J2014 Efficiency Calbralion Used Dene On : 7IB/2014 Efficiency Callbr8Hotl Description Sample Number : 7485 PEAK ANALYSIS REPORT Peak Analy&is Perfonned Ol'I : 912A/2019 9:05:49AM PeakAnalyais From <llannel : 100 Paak.Analyaia To Channel : 4096
9/24/2019 9:05:59AM Page 2 of6 Analysis Report for L2-011-101-FSGS-006-SS L2-011-101 Peale EnertlY ROI ROI Peak NetPNk Net Area continuum FWHM No. (hV) start end Centroid A,u Uncertainty counas (keVJ F 1 186,12 369 - 380 372.74 4.61E+Ol 22.68 2,70E+02 1.37 F 2 238.56 469 - 482 477.60 5.02E+Ol 23.18 3.01E+02 1.35 F 3 2 95 .14 586 - 594 590.74 B.44E+Ol 23.18 1.07E+02 1.56 F 4 351.68 69B - 710 703.79 9.76E+Ol 23.78 1.20E+02 1. 62 F 5 609.16 1212 - 1225 1218.65 1. 07E+02 22.71 5.60E+Ol l . 79 F 6 1460. 61 2914 - 2928 2921.33 1. 29E+02 23.55 l.50E+Ol 2.39 M"' Arel: peak in a rnulllplet region m
- Other peek in II mulllplet region F"' Fitted elnglat Emm, quollld at 2.000elgma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/24/2019 9:05:-49AM Env. Background Ale : C:\Cenberra\Apex\Root\Daiyland_NPPIDllla\0000001364.CNF Peak Enqy Original Orig. AnNI Amblwtt Backgr. Subtracted Subtracted No. (keVJ ARNI Uncertainty Background Uncfllf. Area Um:att.
F 1 186.12 4.61E+01 22.68 4.61E+Ol 2.27E+Ol F 2 238.56 5.02E+Ol 23.18 5.02E+Ol 2.32E+Ol F 3 295.14 8.44E+Ol 23 .18 8.44E+01 2.32E+Ol F 4 351.68 9. 76E+0l 23.78 4,lBE+Ol l. 86E+Ol 5.59E+Ol 3 . 02E+Ol F s 609.16 l.07E+02 22.71 2.06E+Ol 1. 21E+Ol 8.60E+Ol 2.57E+Ol F 6 1460.61 1.29E+02 23.55 2.82E+01 8.57E+OO 1.01E+02 2.SlE+Ol M = First peak In a roolllplet region m == Other peak In a multiplet region F "" Fitted singlet Emn quoted et 2.0DOsigma
9/24/2019 9:05:59AM Page 3 of6 Analysis Report for L2-011-101-FSGS-006-SS L2-011-101 NUCLIDE IDENTIFICATION REPORT NucUdt Library UuCl : C:\Canbena\Apex\Rcat\Dalryland_NPP\UbraryV-IOTLAB.NLB IDENTIFIED NUCLIDES Nucllde Id EnfRJW Yield(%) Activity Acflvltr Name contldtnc* (k*VJ (pCVgramt1) Uncattalnly K-40 0.99 1460.75
- 10.67 2.52E+OO 6.42E-Ol PB-212 0.56 77 .ll 17.50 238.63
- 44,60 5.93E-02 2.76E-02 BI-214 0.34 609 .31
- 46.30 2.27E-Ol 6.91E-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 7'7.11 10.70 295.21
- 19.20 2.77E-01 7.72E-02 351.92
- 37,20 l. llE-01 6.001::-02 RA-226 0.99 186.21
- 3.28 6.24E-01 3.09E-Ol
* = Energy Ina found In the 1pectrum.
* .. Manually added nuclide.
? .. Manually ded nllCid&.
O
- Energy ltn* not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence Index threshold ,. 0.30
- Errors quoted at 2.000llgma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wlmean Wtmean Comments Name Id ActJvlly ActMty Confidence (pCl/g11msJ Uncertainty K-40 0.997 2.52E+00 6.42E-01 PB-212 0.560 5 . 93E-02 2.76E-02
9/24/2019 9:05:59AM Page 4 of6 Analysis Report for L2-011-101-FSGS-006-SS L2-011-101 Nuclide Nuclide WI mean MfflNII Comments Name Id ActJvlty Activity Confidence (pCVgrams) Uncertainty BI-214 0.34 8 2.27E-01 6.91E-02 PB-214 0.716 1.73E-Ol 4.74E-02 RA-226 0.999 6.24E-01 3.09E- 01 7 = nuclide Is part of an undetermined SGlutlon X = nuclide rejected by lhe Interference analysts
@ ,. nuclide contains enefQY Rnes not used In Weighted Mean Activity Emin, quoted at 2.000sigma
9/24/2019 9:05:59AM Page 5 of6 Analysis Report for L2-011-101-FSGS-006-SS L2-011-101 UNIDENTIFIED PEAKS Peak Loc;a1& Pemmned on : 9124/.2019 8:05:49AM PNk l..oGat9 Fn:im Ctl11nnal : 100 Peak Locaa Tc Channel : 4096 PeakNo. Enerr,y(hV) Put Sin (CPS) Pffk CPS" Unc<<talnty Pffk Type To,.,_noe Nuclld#J Al peaks were 1""'1tlfled. M
- Flrat peak In a multiplet region m = OlhEr peak In e mu111 plet region F - Fitted singlet EfJ0l'8 quoted at 2.000ligma NUCLIDE MDA REPORT
,._.aide Ll>,ary Used : C:\Canbefra\Apex\Root\Dalryland_NPP\LibraryViOTLAB.NLB Nuclide Energy Yfflld(%) Acfwlty NudidfllfDA UneMDA Name (pCV,,,.ms) (pcv,,,a,ns) (pCVgrams)
(RV) + K-40 1460.75
- 10.67 2.52E+00 7 ,46E-01 7,46E-Ol
+ AR-4 1 1293 . 64 99.16 2.BSE+13 5,25E+13 5.25E+13 + C0-60 1173.22 100.00 1.49E-02 6.0SE-02 8 . 0SE-02 1332.49 100. 00 4.23E- 2 6.0SE-02 + KR-85 513.99 0.43 1.44E+0l 1.19E+Ol 1.19E+Ol + Y-88 898.04 93.70 3.36E-02 S.3EiE-02 5.36E-02 1836.06 99.20 -1.40E-02 6 . 04E-02 + NB-94 702.63 100.00 2.32E-03 5.23E-02 5.23E-02 871.10 100.00 -1. 71E-02 5.56E-02 + I-131 284.30 6.06 -1.0BE-02 6.83E-02 9.lOE-01 364 .48 81.20 -4.91E-04 6.83E-02 636.97 7.27 -1. 63E-01 9.O3E-01 + CS-134 604.70 97. 60 -1. 91E-02 5.'7SE-02 7.SOE-02 795.84 85.40 -7.22E- 2 5.75E-02 + CS-137 661. 65 85.12 9.38E-02 6.'75E-02 6. 75E-02 + CE-144 80.12 1.36 -3.37E-Ol 3.34E-01 4.41E+OO 133.51 11.09 -9.19E-02 3.34E-01 + EU-152 121. 78 28.40 -3.BOE-0.2 1.36E-Ol 1.36E-01
9/24/2019 9:05:59AM Page 6 of6 Analyaia Report for L2-011-101-FSGS-006-SS L2.011-101 Nuclide Enerm, Yield(%) AarMty NuclldeMDA UneMDA Name (keV) (pC(ig,ams) (pCVgnms) (pCUgrama) EU-152 344.28 26.60 3.62E-02 l.36E-01 l.7SE-01 1408.00 20.74 1.76E-Ol 2. 8'7E-'01 + EU-154 123.07 40.40 -6.63E-03 9,59E-02 9.59E-02 723.30 19.70 -8.SSE-03 2.61E-01 1274.51 35.50 6.00E-02 2.07E-01 + EU-155 86.54 32.80 -7.SOE-02 l.SlE-01 1.SlE-01 105.31 21.80 -1.00E-03 1.74E-01 + BI-214 609.31"
- 46.30 2.27E-01 1. 08!;-01 1.08E-01 1120 .29 15.10 4.17E-01 5.30E-Ol 1238.11 5.94 6.46E-01 l. llE+OO 1371.6'7 4 .11 2.52E-01 1. 42E+OO 1407.98 2.48 1.47E+OO 2. 39E+0O 1509.19 2.19 l.23E+OO 3,0lE+OO 1764.49 15,80 5.14E-01 5.23E-01
+ PB-214 71,11 10.70 6 , 41E-01 1.16E-01 6.0SE-01 295.21
- 19.20 2.77E--01 1. 24E-01 351. 92
- 37.20 1.llE-01 l.16E-01
+ PA-228 89 . 95 22.00 4,34E+OO 2.21E+OO 3.83E+OO 93.35 35.00 7.65E-O l 2.21E+OO 105.00 16. 30 -2,00E-01 4.04E+OO 129.22 2.97 -1. 73E+Ol 2.17E+Cl 338.32 *S.30 5.38E+OO 1. 44E+Ol 463.00 13~80 3.61E-01 S. 66E+OO 911.23 16.70 3.44E+OO 6.22E+OO + AM-241 59.54 36.30 - 3 .02E-02 2.75E-01 2.75E-Ol + CM-243 103.76 23.00 3.72E-02 1.68E-01 1.68E-01 228.18 10,60 -l. lOE.-01 3.68E-Ol 277.60 14.00 -1.23E-Ol 2.82E-01
+ = Nuclide ldentlfled during Iha nuclide Identification * = Energy IN fou'ld In 1he spectrum > = MDA value not calculated @ = Half-life too short to be able to perform the decay" correction ? = CAUTION: MDA value la Inconsistent with Currie MDA at 95% confidence !eve.I
9/24/2019 9:51:D7AM Page 1 of7
l'Apex-Gamma Analysis Report for L2-011-101-FSGS-007-SS L2-011-101 GAMMA SPECTRUM ANALYSIS Sample fdentfflcatton : L2-011-101-FSGS--007-SS SampleDeacrlption : L2-011-101 SampleT)1>8 : 500.ml Marinellf Unit Sample Point Sample Size : 7.213E+02 grams Fadllly : Dalryland_NPP Sample Taken On : 912012019 2:21 :OOPM Acqulaltlon Started : 9'2412018 9:20:44AM Procedure : 500ml Martnell OJ)lrator : AdmlnlBlndDr .
Detector Name : HOTLAB Geometry : ~ I Martnell Live Time : 1BOO.D seccnda Realllme : 1805.8 seconds Dead Time : D.32% Peak LDC4118 Threshold : 3.00 Peak Locate Range (ti diannela) ! 100 -4088
?eak Anta Range (In channels) : 100-4098 Identification Energy Tolerance : 1.DDOkeV Energy Calblatlon Used Done On : 71812014 Efficiency C&a>ration Used Done On : 7tar.l01-4 Efficiency calbratsan Daecrtptlon Sample Number : 7486 PEAK ANALYSIS REPORT Paak Analy&ia Perbmed on : 9124/2019 9:50:57AM PeakAnaly&is From Ctlannel : 100 Peak Analyafs To Channel : 4096
9/2-41.2019 9:51:07AM Page 2of7 Analysis Report for L2-011-101-FSGS-007-SS L2-011-101 Peale Energy ROI ROI Pettie NetPealr NetA,ea ConUnuum FWHM No. (keV} st.art end Centroid Alea Uncemtfnty Counts (lce\lJ F 1 76.52 147 - 159 153.58 1.95E+02 48.59 7.09E+02 3.02 F 2 238.64 471 -- 485 477.76 2.38E+02 37.51 3.90E+02 1.57 F 3 295.02 585 - 598 590.49 8.20E+Ol 24.14 2.17E+02 1.50 F 4 338.31 671 - 681 677.05 5.75E+Ol 21.95 l. 32E+02 1.88 F 5 351.61 696 - 709 703.64 1.27E+02 26. 72 1. 79E+02 1.43 F 6 582.84 1161 - 1171 1166.02 6.23E+01 19.65 6.85E+01 1.95 F 1 609.06 1212 - 1225 1218.46 .8. 27E+Ol 21.30 1.85E+01 1.77 F 8 910.81 1814 - 1829 1821.85 4.00E+Ol 14.28 4.33E-+01 1.47 F 9 1119.69 2234 - 2244 2239.5.6 2.llE+Ol 11.55 2.47E+Ol 1.87 F 10 1460.59 2914 -- 2929 2921. 30 2.60E+02 32.55 7.27E+OO 2.43 M = First peak In a multiplet region m = Other peak In a multiplet region F = Fitted singlet EITOfS quoted at 2.000slgma BACKGROUND SUBTRACT REPORT Peak Analysis Perfonned on : 9124/2019 9:50:57AM Env. Background Fie : C:\Canbena\,Apex\Roat\Dalryland_NPP\Data\0000001384.CNF Peek Energy Original Orig. Area Ambient Backgr. SubtnH;ted Submlcted (lreV) Area UncMtalnty Backg10und Uncett. Area . Uncert. No. F 1 76.52 1.95E+02 48.59 l.95E+02 4.86E+Ol F 2 238.64 2.38E+02 31.51 2.38E+02 3.75E+Ol F 3 295.02 8.20E+Ol 24.14 8.20E+Ol 2.41E+Ol F 4 338.31 5.75E+Ol 21.95 S.'75E+01 2.20E+Ol F 5 351.61 1.27E+02 26.72 4.18E+01 1. 86E+0l 8.55E+01 3.26E+Ol F 6 582.84 6.23E+Ol 19.65 6.23E+01 1.96E+Ol F 7 609.06 8.27E+Ol 21.30 2 .06E+Ol 1. 21E+Ol 6.21E+01 2.45E+Ol F 8 910.81 4.00E+Ol 14.28 4.00E+Ol 1.43E+Ol F 9 1119.69 2.llE+Ol 11.55 2.11E+Ol 1.16E+Ol F 10 1460.S9 2.60E+02 32.55 2.82E+Ol 8.57E+OO 2.32E+02 3.37E+01 M = Firat peak in a multiplet region m =Ottter peak in a multiplet svglon F
- AIied singlet Ena-s quoted at 2.000eigma
9'..!4/2019 9:51 :07AM Page 3 of7 Analysis Report for L2-011-101-FSGS-007...SS L2-011-101 NUCLIDE IDENTIFICATION REPORT Nuclide Ubrery Ueed : C:\Cariberra\Apex\RooN)alryleind_NPP'.l.Jbrary'IHOTl.AB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Actlvity A.ctlvl~ - Name Conlldflnce (ke\l) (pCVgnmaJ Uncertalmy K-40 0.99 1460,75
- 10.67 7.02E+OO 1.09E+OO PB-212 0.98 ,7 . 11
- 17.50 7.69E-Ol 1.98E-01 238 . 63
- 44.60 3.40E-Ol 5.65E-02 BI-214 0.57 609 . 31
- 46. 30 1.98E-Ol 7,90E-02 1120 . 29
- 15 .10 3.57E-Ol 1. 96E-01 1238.11 5,94 1377.67 4 .11 1407 .98 2 . 48 1509.19 2 . 19 1?64.49 15.80 PB-214 0 . 98 77.11
- 10.70 1 . 26E+00 3.25E-Ol 295.21
- 19 .20 3.25E-01 9.70E-02 351. 92
- 37.20 2 . 0SE-01 7.86E-02
* = Energy llne found In the 5Pactrum.
- =Manually added nuclide.
? = Manu110y ecited nuclde.
@ = Enit,gy line h0t used for Weighted Mean Activity Energy Tolerance : 1,000 keV Nudide conftdence Index threshold = 0.30 Errors quoted at 2.DIJOslgma INTERFERENCE CORRECTED REPORT Nuclide Nuclide wtmean Wtmean Comments Name Id Activity Actlttlty Confidence Uncertainty (pCV,,amsJ K-40 0.996 7.02E+OO 1.09E+OO PB-212 0.984 3.60E-Ol 5.44E-02 BI-214 0.571 2.20E-Ol 7.33E-02
9/24/2019 9:51:07AM Page4 of? Analysis Report for L2-011-101-FSGS-007-SS L2-011-101 Nuclide" Nuclide wtmean wrmeen Comments Name Id Actlvlly Acflvlty ConffdMce (pCl/grams) Uncertainty PB-214 0.981 2.67E-01 6.0lE- 02
? = nudlde Is part of an undBlllnnined eclution X = nudlde re]ected by 1he Interference analyals
@ = nuclide contains energy lines not used in Weighted Mean Acttvlly Erron5 quoted at 2.000sigma
9/24/2019 9:51 :07AM Page 5 of7 Analysis Report for l2.011-101-FSGS-007-SS L2-011-101 UNIDENTIFIED PEAKS Peak L ~ Perfonned on : 9/2412019 9:50:57AM Peak Locate From Channel : 100 Peak Locste To Channel : -4096 PukCl'S"') Peak Tolennr:e PukNo. Energy (lr*VJ Peak Sin (CPS) Uncel'falnty 1)-pe Nuclide F 4 338.31 3.19584E-02 19.08 Tol. AC-228 PA-228 F 6 582.84 3.46072E-02 15.77 F 8 910.81 2.22049E-02 17.87 Tol. AC-228 PA-228 M "' First peak In a rNJltlplet region m = Other peak In a mulllplat raglon F = Fitted singlet Errors quotsd at 2.000sii,na NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Daiyland_NPP\LibraryV-IOTLAS;NLB NudldlJ EMIW Vfeld("A) AdMty NuclldeMDA LlnellDA Name (pCV.,.,,,_} (pCU,,,..,,..J (pCVflJalU) tb\lJ + K-40 1460.75
- 10. 67 7.02E+OO 8.31E-Ol B.31E-01
+ AA-41 1293. 64 99.16 -3. 64E+13 1. .0 9E+l4 1.09E+l4 + C0-60 1173.22 100.00 8.98&... 02 9.91E-02 1.lSE-01 1332.49 100 . 00 3.89E-02
- 9.91E-02
+ KR-85 513.99 0.43 1 . SlE+Ol 1.77E+Ol 1.7'7E+Ol + Y-88 898.04 93.70 2 . 33E-03 7.31E-02 9.31E-02 1836.06 99.20 -2. 63E-02 7 . 31E-02 + NB-94 702.63 100.00 1. 36E-02 7.20E-02 7.20E-02 871.10 100,00 -4,28E-03 7.80E-02 + I-131 284.30 6.06 -4.liE-02 9.54E-02 1.30E+OO 364.48 81.20 -5 .19E-0 2 9.54E-02
9/24/2019 9:51:07AM Page6of7 Analysis Report for L2-011-101-FSGS-007-SS L2-011-101 Nuclide Energy Yield(%} ActJvtty NucNdeMDA UneMDA Name (pCl/grams} (pCVgramsJ (pCVgramtt) (keV) I-131 636.97 7.27 3.29E-01 9.54E-02 1.33E+OO + CS-134 604.70 97.60 l.OOE-02 8.72E-02 l.OOE-01 795.84 85 .40 -8.87E-02 8. 72E-02 + CS-137 661.65 85.12 1.53E-01 1 .14E-Ol 1.UE-01 + CE-144 80.12 1.36 -3.12E+OO 4.82E-Ol 6.55E+OO 133.51 11.09 3.03E-01 4.82E-01 + EU-152 121.78 28.40 --1. 76E-01 l.82E-01 1.82E-Ol 344.28 26.60 -6.lOE-02 2.48E-01 1408.00 20.74 l.68E-Ol 3.98E-Ol + EU-154 123.07 40.40 -8.60E-02 l. 28E-01 1.28E-01 723.30 19. 70 2.93E-01 4.12E-01 1274.51 35.50 4.56E-02 2.88E-01 + EU--15S 86.54 32.80 2.12E-02 2.20E-01 2.20E-01 105.31 21.80 l.28E-01 2.58E-Ol + BI-214 609.31
- 46.30 1.98E-01 l.44E-01 1.44E-Ol 1120.29
- 15.10 3.57E-01 3.64E-Ol 1238.11 S.94 3.65E-01 2.04E+OO 1377.67 4.11 3.36E-01 1.90E+OO 1407.98 2.48 1.40E+OO 3.33E+OO 1509.19 2.19 1.63E+00 3.23E+OO 1764.49 15.80 3.27E-01 5 .49E-Ol
+ PB-214 77.11
- 10.70 l.26E+OO 1.59E--01 6.68E-Ol 295 .. 21
- 19.20 3.25E-01 2.36E-Ol 351. 92
- 37.20 2.0SE-01 1 .59E-01
+ PA-228 89.95 22.00 2.60E+OO 3.19E+OO 5 .48E+OO 93.35 3S.00 5.83E-01 3.19E+OO 105.00 16.30 3.42E+OO 6.14E+OO 129.22 2.97 4.00E+OO 3.16E+01 338.32 5.30 2.20E+OO 2.03E+01 463.00 13.80 2.76E+OO 8.36E+OO 911.23 16.70 1.03E+01 1.l3E+Ol + AM-241 59.54 36.30 1.73E-01 3.96E-Ol 3.96E-Ol + CM-243 103.76 23.00 1.27E-01 2.49E-01 2.49E-01 228.18 10.60 9.36E~02 4.98E-01 277.60 14.00. 1.56E-Ol 4.28E-O'l
.. == Nuclde
+ Identified during the nudide Identification Energy line found In the llf)&clrum
> = MOAvatue not calculated
@ = Half-me too lhort to be able to perfonn the decay corredlon
? = CAUTION: MDA wlue is inconsislent with Currie MDA at 95% confidence level
9/2412019 9:51 :07AM Page7of7 Analysis Report for L2-011-101-FSGS-007-SS L.2-011-101
9124/2019 10:21:54AM Page 1 of6 ~Apex-Gamma Analysis Report for l2-011-101-FSGS-008-SS l2-011-1D1 GAMMA SPECTRUM ANALYSIS Sample ldenlfflcalion : L2-011-101-FSGS-008-SS Sample DBICl'1pllon : L2-011-101 Sample Type : 600 ml Marinelli Unit Samplef'cmt Sample Size : 8.955E+D2 grsma Facllty : Dalryland_NPP Sample Taken On : 9120/2019 9:37:00AM Acquisition Startad : 912412019 9:51:35AM Procedure : 500ml Marinel6 Operator : Adminlatnm>r Detector Name :HOTLAB Geom&tty : 500ml Mamelll Liva Time : 1800.0 sec:ands Real Time : 11106.7 seconds
- D.32%
Peale: Locate Threahold : 3.00 Peak Locate Renge (in chai'lnels) :100-4098 Peak Area Range lin diannels) : 100-4098 ldantffication Energy Talerance : 1.000 keV Energy Calibration Used Done On : 7/812014 Efflclancy Calbratlon Used Dane On : 7/Bl2014 Eflk:iency Calbratlon Deacrlptlon SM1pfeNumber : 7487 PEAK ANALYSIS REPORT Peak Analylis Perfurmed on : 9/24/2019 10:21:45,\M Peek Analysis From Olennel : 100 Peak Analy&ls To Channel : 4096
9/24/2019 10:21:54AM Page2of6 Analysis Report for L2-011-101-FSGS-008-SS L2-011-101 Peale Energy ROI ROI Peale NetPeak NetArea Continuum FWHM No. (lreVJ start end Cen'llold Araa Uncertainty counfs (k*VJ F 1 238.46 472 - 481 477.40 6.90E+Ol 24.35 2.93E+02 0.97 F 2 295.14 585 - 594 590.74 6.4BE+Ol 21.40 l.20E+02 1.50 F 3 351. 73 698 - 709 703.89 l.42E+02 27.22 9.90E+Ol 1.75 F 4 582.38 1159 - 1171 1165 .10 3.65E+Ol 14.73 3.95E+Ol 2.02 F 5 609.27 1211 - 1226 1218.88 8.19E+Ol 19.52 3.75E+Ol 2.07 F 6 910.64 1816 - 1826 1821.52 2,78E+Ol 12 .-43 1.66E+Ol 1.88 F 7 1119. 97 2235 - *2246 2240.12 2. 791H01 12.46 1,87E+Ol 2.50 F B 1460.56 2914 - 2928 2921.23 1.65E+02 26 .59 1. 86E+Ol 2.39 F 9 1764.49 3524 - 3535 3529.04 1. 87E+Ol 8.81 O.OOE+OO 1.20 M
- First peek In a roo1Up1et regton m = Other peak in a multlplet region F = Frttecl ainglet Em,~ quoted at 2.000algma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9/24/2019 10:21 :45AM Env. Background File : C;\Canbe1TB\Apex\R0ot\Dalrytand_NPP\Oata\0000001364.CNF Peel< Energy Original Orlg.A,ea Ambient *sat:lcgr. Subtracted Subtracted No. (lreV) Area Uncertainty Background Unce,t ArH Uncert.
F 1 238.46 6.90E+Ol 24.35 6.90E+Ol 2.44E+Ol F 2 295.14 6.48E+Ol 21.40 6.48;E+Ol 2.14E+01 F 3 351. 73 1.42E+02 27.22 4.18E+01 1. 86E+Ol l.OOE+02 3,30E+Ol F 4 582.38 3.65E+Ol 14.73 3.65E+Ol l.4 7E+Ol F 5 609.27 8.19E+Ol 19.52 2.06E+Ol 1. 21E+Ol 6.13E+Ol 2.30E+Ol F 6 910.64 2.78E+Ol 12 .43 2.78E+Ol 1.24E+Ol F 7 1119. 97 2.79E+Ol 12 . 46 2 .79E+01 l.25E+Ol F 8 1460.56 1.65E+02 26.59 2.82E+Ol 8.57E+OO 1.37E+02 2.79E+Ol F 9 1764.49 l.87E+01 B.81 7.59E+OO 4.90E+OO 1.llE+Ol l.OlE+Ol M = F"lnll peak In a multlplet region m ~ Other peak in a mdtlplet region F = Fitted singlet Em,n, quoted at 2.000lillgme
9/24/2019 10:21 :54AM Page 3 of6 Analysis Report for L2-011-101-FSGS-008-SS L2-011-101 NUCLIDE IDENTIFICATION,REPORT Nuclide Library UNCI : ~nberra~ot\Ollr)tancl_NPP\UlllwylliOTtAB.NLB IDENTIFIED NUCLIDES Nudlde Id Energy Vleld(3/4) .Activity Actlvlty N.,,,. Conffdence {keVJ (pCV11ratu) UnCflftalmy K-40 0.99 1460.75 10.67 3.34E+OO 7.0SE-01 PB-212 0. 55 '77.11 17.50 238.63
- 44.60 7.94E-02 2.83E-02 BI-214 0.78 609.31
- 46.30 1. SBE-01 5.97E-02 1120.29
- 15.10 3.81E-01 1. 71E-01 1238.11 s. 94 1377.67 4.11 1407.98 2.48 1509.19 2.19 1764.49
- 15. 80 2.14E-01 1.95E-01 PB-214 0.71 77.11 10. 70 295.21
- 19.20 2.07E-01 6 . 91E-02 351.92
- 37.20 l.93E-01 6.43E-02
* = EnatlJY nna foood In the spectrum.
- = Manually added nucllde.
? "' Manually edled nuclde.
@ = Energy line not U88d ror We~ Meen ActMty Energy Tole111na1 : 1.000 keV Nuellda conflde1'108 Index tttrnhold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nucllde wrmnn Wtmeen comments Name Id Acflvtty Activity Conlldence Uncerllllnty (pCVglam*J K-40 0. 994 3.34E+OO 7 , 0SE-01 .
PB-212 0.557 7.94E-02 2.83E-02 BI-214 0.785 1.84E-01 5.42E-02
9/24/2019 10:21:54AM Page4of6 Analysis Report for L2-011-101-FSGS-008-SS L2-011-101 Nuclide Nuc/lde Wlmean wr mean Comments Name Id Activity Acflvlty Confidence Uncertainty (pCilgrams) PB-214 0.718 2.00E-01 4.71E-02
? = ruclide is part of an undetennined aolutlon X = nuellde rejeded by 1ha interfef8nce analysis G! = nuclide contains energy lines nat used in Weighted Mean Actlvity Errors quoted at 2.000sigma
9/24/2019 10:21:54AM Page S of6 Analysis Report for 1.2-011-101-FSGS-008-SS 1.2-011-101 UNIDENTIFIED PEAKS Peak Loc:ate Performed on : 9124/2019 10:21:45AM Peak LoGllte FIQTI Chlnnel : 100 Peak Locate To Channel : 4096 Pule CPS("} Peak Tolerance PeakNo. Peak Sin (CPS) Uncertainty 'fype Nuclide F 4 582.38 2.02973E-02 20.16 F 6 910.64 1.54481E-02 22.36 AC-228 PA-228 M :: Flnlt peak In a nMJl!lplet region m - Other peak ln II multiplet region F = F'llted singlet Erront quoted et 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canbarra'IApex\Roo&Jai'yland_NPP'.Library\1-lOTLAB.NLS Nuclla EnarvY Yraldt") AdMty NuclldeMDA LJn*MDA Name (pCl/gn,ms) (pCl/gnlms) (pClfs1rams) tle\?
+ K-40 1460.75
- 10.67 3.34E+OO 7. 50E-Ol 7.SOE-01
+ AR-41 1293.64 99.16 -1. 49E+14 4.93E+14 4.93E+14 + C0-60 1173.22 100.00 1. 30E-02 5.89E-02 7.80E-02 1332.49 100.00 -5.52E-03 5.89E-02 + KR-85 513.99 0.43 7.98E+OO 1.22E+Ol 1.22E+Ol + Y-88 898.04 93.70 4.17E-03 5.16E-02 6.48E-02 1836.06 99.20 -2. 65E-02 5.16E-02 + NB-94 702,63 100.00 -4.47E-02 4.79E-02 4.79E-02 871.10 100.00 -4.79E-03 5.35E-02 + I-131 284.30 6.06 -4.69E-01 6.87E-02 9.19:£-01 364.48 81.20 l.63E-02 6.87E-02 636.97 7.27 6.52E-01 9.49E-01 + CS-134 604.70 97, 60 -9.19E-03 6.12E-02 7,19E-02 795.84 85.40 -4.02E-02 6.1'2.E-02
9/24/2019 10:21:54AM Page 6of6 Analyala Report for L2-011-101-FSGS-008-SS L.2-n11-101 Nuclide Enetr,y 'lleld('1/4,) Arztlrify NuclldeMOA LlneMDA Name (pevg,.,,,.) (pCVr,,amsJ {pCl/grems) (b"' + CS-137 661.65 85.12 7.lOE-02 7.00E-02 7.00E-02 + CE-144 80.12 1.36 -2. 46E+OO 3.39E-Ol 4.34E+oo* 133.51 11.09 -9.92E-02 3.39E-Ol + EU-152 121.78 28.40 -3.59E-02 1.38E-Ol 1.38E-01 344.28 26.60 8.47E-02 1.64E-Ol 1408.00 20.74 2.44E-01 3.04E-01 + EU-154 123.07 40.40 3.64E-02 9.84E-02 9.84E-02 723.30 19.70 2.29E-01 3.lOE-01 1274.51 35.50 2.34E-03 l.69E-Ol + EU-155 86.54 32.80 3.00E-02 1. 59E-01 1.59E-01 105.31 21. BO 4,03E-02 1. 92E~Ol + BI-214 609.31
- 46.30 l.58E-01 9.70E-02 9.70E-02 1120.29
- 15.10 3.81E-01 2.59E-01 1238.11 5.94 5.93E-Ol l.51E+OO 1377.67 4.11 5.93E-01 1.69E+OO 1407.98 2.48 2.04E+OO 2.54E+OO 1509.19 2.19 9.14E-02 2,21E+OO 1764.49
- 15.80 2.14:E-Ol 2.86E-Ol
+ PB-214 77 .11 10.70 3.75E-01 1. 06E-Ol 5.86E-01 295.21
- 19.20 2.07E-01 1. 31E-01 351. 92
- 37.20 l.93E-01 l.06E-Ol
+ PA-228 89.95 22.00 5.66E+OO 2.81E+OO 4.84E+OO 93.35 35.00 -1.30E+OO 2.81E+OO 105.00 16 .30 2,99E+OO 5.43E+OO
.129.22 2.97 -1.lOE+Ol 2.67E+Ol 338.32 5.30 8.77E+OO l.64E+0l 463.00 13.80 -3.75E+OO 7.02E+OO 911.23 16.70 7.35E+OO 9.12E:+00
+ AM-241 59.54 36.30 3.81E-02 2.73E-Ol 2.73E-01 + CM-243 103.76 23.00 1.83E--01 1. 88E-Ol l.88E-Ol 228.18 10.60 *2. 78E-02 3.63E-01 277.60 14.00 1.llE-01 3.0BE-01
... = Nudlde identified dl.l'lng the nuelide ldentfflcation
* = Energy ine found in the spectrum
- > = MDA value not calculated
@ = Half-fife too ehort to be able to pelfonn the decay CCIT'8Cticn ? = CMJTION: MOA value Is Inconsistent wfth Currie MDA al 95% confidence level
9/24/2019 10:52:41AM Page 1 of6 Analysis Report for L2-011-101-FSGS-009-SS l2-011-101 GAMMA SPECTRUM ANALYSIS Sample Identification : 12..011-101-FSGS-009-SS Sample Oeacriptlon : L2..(l11-101 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 7.222E..O:Z grams Fdl" : Dalryland_NPP Sample Taken On : 9120/2019 9:45:00AM Acqulaltion Started : 912412()111 10:22:22AM Procedure : 500ml Mamel Operator : Administrator Detector Mane : HOltAB GemneCTy : 500ml MMnelH Llvellme : 1800.o seconds Realllme : 1805.5 98C0f'lds C>aadllrne : D.30 % Peak Locate Threshold : 3.00 Paek Locate Range (fn channels) : 100-4096 Paak Area Range (ti dlannel&) : 100-4096 ldenttllcatlon Energy Tolerance : 1.000 keV Energy Cebatlon Used Done On : 7/812014 Effictency C&lbratlan Used Done On : 71812014 Efflclency Calbratlnn Ceecrtp&n Sarrpe Number : 7488 PEAK ANALYSIS REPORT PeakAnelysie Perfonnafon : 9/2412019 10:52:32AM Peak Analylila Fram Ql8nttel : 100 Paek.Analyals To Chamlll : 4096
9/24/2019 10:52:41AM Pagc2of6 Analy&la Report for LZ-011-101-FSGS-009-SS L2-011-101 Peek Energy ROI ROI PNk NetPeak NetArN Continuum FWHM No. (lceVJ start end Centroid Area Uncertainty Count, (k*VJ F 1 76.56 147 - 161 153.67 l.44E+02 45.95 7.73E+02 2.86 F 2 238.45 470 - 481 477.38 1.74E+02 33.19 3.44E+02 1.17 F 3 295.27 584 - 595 590.99 7.29E+Ol 24.86 1. 79E+02 1.93 F 4 338.05 670 - 682 676.53 5.68E+Ol 21.57 l.63E+02 1.69 F 5 351.80 697 - 709 704.02 1.0lE+02 25.66 1.63E+02 1.77 F 6 583.09 1162 - 1173 1166.53 7.49E+01 20.28 6.48E+Ol 1.81 F 7 609.16 1211 - 1224 1218.65 8.64E+01 21.99 8.73E+Ol 1. 81 F 8
- 910. 91 1817 - 1829 1822.07 5.31E+Ol 16.52 3.25E+Ol 2.04 M 9 964.33 1924 - 1943 1928.89 l.07E+Ol 9.35 3.79E+Ol 1.39 m 10 968.98 1924 - 1943 1938.18 1.72E+Ol 10.83 2.95E+Ol 1.39 F 11 1119.63 2234 - 2244 2239.43 2.81E+Ol 12.35 1. 66E+Ol 2.32 F 12 1460.66 2914 - 2929 2921.43 2.85E+02 34.25 l.53E+Ol 2.41 M = First peak In a multiplet raglan m = Other peak in e multiplet region F = Fitted ainglet Errors quoted at 2.llOOsigma BACKGROUND SUBTRACT REPORT PeakAnaJysl& Performed on : 9124/2019 10:52:32AM Env. Background File : C:\Csnberra\Apex\Rcat\Dalrytand_NPP'\Data\0000001364.CNF Peale Energy Onglnal Orlfl. An,a Ambient Backgr. Subtract.Gd Subtncted No. {keV) Area Uncertalnly Background Uncert. Area Uncert F 1 76.56 1.44E+02 45.95 l_.44E+02 4.S9E+Ol F 2 238.45 1.74E+02 33.19 1.74E+02 3.32E+01 F 3 295.27 7.29E+Ol 24.86 7.29E+Ol 2.49E+Ol F 4 338.05 5.68E+Ol 21.5'7 5.68E+Ol 2.16E+Ol F 5 351.80 1.01E+02 25.66 4.18E+Ol l,86E+Ol 5.95E+Ol 3.17E+01 F 6 583.09 7.49E+Ol 2.0 .28 7.49E+Ol 2.03E+01 F 7 609.16 8.64E+Ol 21.99 2.06E+01 1,21E+Ol 6.58E+Ol 2.51E+Ol F 8 910.91 5.31E+Ol 16.52 5.31E+Ol l.65E+Ol M 9 964.33 1.07E+Ol 9.35 1.07E+Ol 9.35E+OO m 10 968.98 1.72E+Ol 10.83 1.72E+Ol l.08E+Ol F 11 1119.63 2.81E+01 12.35 2.81E+Ol l.24E+0l F 12 1460.66 2.85E+02 34.25 2.82E+Ol 8.57E+OO 2.57E+02 3.53E+Ol
9/24/2019 10:52:41AM Page 3 of6 An~la Report for LZ-011-101-FSGS-<109-SS L2-011-1O1 M - First peak In a rooltfplet raglan rn = Other peak In a multiplet region F = Filt9CI 8inglet E1T0111 quoted at 2.000sJoma NUCLIDE IDENTIFICATION REPORT Nuclide Library U.ed : C:\CanbarTa\Apa\Roo(\Dairyland_Npp\Ulnry\HOTl.AB.NLS IDENTIFIED NUCLIDES Nuclide Id EnflllW Yleldt'(,J ActMty Actlt,lly Name Contfdence (keV) (pCl/fnlmsJ UltCflfftllnty K-40 0.99 1460.75
- 10.67 7.74E+00 1.15E+OO PB-212 0.98 77 . 11
- 17.50 5.68E-Ol 1 . 85E-Ol 238.63
- 44.60 2.49E-Ol 4.91E-02 BI-214 0 .57 609.31
- 46.30 2.lOE-01 8.O9E-02 1120.29
- 15.10 4.76E-Ol 2.lOE-01 1238.11 5.94 1377. 67 4.11 1407.98 2.48 1509.19 2. 1 9 1764. 49 15.80 PB-214 0 . 99 77 .11
- 10. 70 9.29E-01 3.03E-Ol 295.21
- 19.20 2.89E-Ol 9.95E-02 351.92
- 37.20 1.42E-01 7.61E-02 AC-228 0.70 209.28 4.40 338.32
- 11.-40 4.27E-Ol 1. 6-4E-01 794.70 4.60 911.60
- 27.70 4,0BE-01 1.28E-Ol 964. 60
- 5.20 4.60E-Ol 4 . 03E-01 969.11
- 16.60 2.33E-01 l.47E-01
* =ensgy llne found In 1h8 apettrum.
* =Manually added nuclide.
? == Ma:,ually adtted nudlde.
Q
- Energy llne not uaed fbr ~ d Mean .Activity Energy Tolerance : 1.000 klN Nuclide confidence index thf88hold = 0.30 El'1'0nl quoted 111 2.000elgma
9124/2019 10:52:41AM Page4 of6 Analysis Report for L2-011-101-FSGS-009-SS L2-011-101 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmean Mmean eommen,s Name Id Actlllity Activity Confidence (pCVgram.s) ~ncertalnty K-40 0.999 7 . 74E+OO 1.15E+OO PB-212 0.983 2.61E-01 4.75E-02 BI-214 o*.s12 2.44E-01 7.SSE-02 PB-214 0.991 2.0BE-01 5.94E-02 AC-228 0.701 3.61E-01 8. l SE-02
? = nuclide Is part of an undetermined solution X = oocllde rejected by the Interference analyale
@ = nuclide cont&lns energy lines not used In We~ed Mean Activity Errors quoted al 2.000slgma
9/24/2019 10:52:41AM Page S of6 Analysis Report for L2-011-101-FSGS-009-SS L.2-011-101 UNIDENTIFIED PEAKS Peak Locate Performed on : !l/2412019 10:52:32AM Peale Locate Fmm Chamel : 100 Paelc Locate To Channel : 4096 Peak CPS "') Paak Tohtrance l'NltNo. EnetfJY(h~ Peak SIie (CPS) Unwfalnly Type Nucllde F 6 583,09 4.15884E--02 13.55 M Flrst peal< In a rnultlplet region m .. other peak in a multiplet region F
- Fitted alngtet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Ubrary Used : C:\Canberra'\Apex\Root.\Dtliryland_NPP\Ubrary\HOTLAB.NLB Nuclide
- EnetrlY (lr*\I)
'lield{%} Acflvlty (pCV,ra,ns)
Nllt:llda M'DA (pCVg,amsJ LlnaMDA (pc.v,,,.m.J + K-40 1460. 75
- 10.67 7.74E+OO 9 . 06E-01 9 . 06E-01
+ AR-41 1293.64 99.16 1. 74E+l4 9.52E+l4 9.52E+l4 + C0-60 1173.22 100. 00 6.lOE-02 9.57E-02 1.0SE-01 1332.49 100.00 2.93E- 02 9.57E- 02 + KR-85
- 513.99 0.43 8.07E+OO 1.61E+0l 1,61E+Ol
+ Y-88 898.04 93.70 1.SlE-02 6.72E-02 8 . llE-02 183 6.06 99.20 4.03E- 03 6 , 72E-02 + NB-94 702.63 100.00 -3.36E-0 2 6.91E- 02 6. 91E-02 871.10 100.00 -6.53E-02 7.67E-02 + I -13 1 284 ~30 6.06 5.22E-01 9.93E-02 1.23E+OO 364.48 81.20 2.82E-02 9.93E-02 636.9'i 7.27 2.91E-01 1.43E+OO + CS-134 604.70 97.60 4.40E-03 8.97E- 02 9,34E-02 795.84 85.40 -4.76E-02 8,97E-02 + CS-137 661.65 85.12 1.16E-02 9.60E-02 9.60E-02 + CE-144 80.12 1.36 -2 . 25E-02 4.65E-Ol 6.06E+OO 133.51 11.09 2.04E-01 4.65E-Ol
9/24/2019 10:52:41AM Page 6 of6 Analysis Report for L2-011-101-FSGS-009-SS L2-011-101 NucJlde Name ,. Energy
~
Yield(%) Acrlvlly (pCVgramsJ NuclldeMDA (pCi/r,ram*) UnalfDA (pCV,,,.maJ + EU-152 121.78 28.40 -9.1-4E-02 1. 77E-01 1. 77E-01 344.28 26.60 -S.09E-03 2.56E-0l 1408.00 20.74 -1 .42E-01 3.54E-01 + EU-154 123.07 40.40 2.52E-02 1.27E-01 1. 27E-Ol 723.30 19.70 2.49E-01 3.55E-01 1274.51 35.50 1.59E-02 2 . 95E-01 + EU-155 86.54 32.80 1.02E-Ol 2.lOE-01 2 . lOE-01 105.31 21. 80 -4.49E-02 2.48E-01 + BI-214 609.31
- 46.30 2.iOE-01 1.48E-01 1. 48E-01 1120.29
- 15.10 4,76E-Ol 2.95E-Ol 1238.11 5.94 -1. 41E+OO 1.92E+OO 1377.67 4.11 4,lOE-01 1 , 93E+OO 1407.98 2.48 -1,19E+OO 2.96E+OO 1509.19 2.19 7.09E-03 3.22E+OO 1 764. 49 15.80 1.37E-01 5,09E-01
+ PB-214 77.11
- 10.70 9 .29E-01 1.52E-Ol 7.28E-01 295.21
- 19.20 2,89E-Ol 2 . 06E-Ol 351.92
- 37.20 1.42E-01 1.52E-Ol
+ PA-228 89.95 22.00 1.02E+Ol 3.73E+OO 6.45E+OO 93.35 35.00 ...;5.84E-01 3.73E+OO 105.00 16.30 -1.87E+OO 6.99E+OO 129.22 2. 97 1.49E+Ol 3.71E+Ol 338.32 5.30 1. BSE+OO 2.SlE+Ol 463.00 13,80 1.14E+OO 9.24E+OO 911.23 16.70 1.17E+Ol 1.30E+Ol + AM-241 59.54 36.30 5.12E-O2 3.78E-O1 3.78E-01 + CM-243 103.76 23.00 1.26E-Ol 2.37E-Ol 2.37E-01 228.18 10.60 l.28E-Ol 4.88E-Ol 277.60 14.00 -3.26E-01 3.89E-Ol
+ = Nucllde Identified during the nuclide ldentlllcatlon * = Energy llne found In the spectrum > = MDA value not calculated C = ~lfa 100 short to be able to perfonn the decay correction ? = CAUTION: MDA value Is Inconsistent with Cunie MDA at 95% confidence level
9124/2019 12:35:18PM Page 1 of6 Analysis Report for L2-011-101-FSGS-010-SS L2-(l11-101 GAMMA SPECTRUM ANALYSIS Sample ldenllflcatlon : L2-011-1O1-FSGS-010-SS Sample Deacrii,tlan : U-011-101 Sample Type : 500 ml MartneMI Unit SanplePomt Sample Size : 8.441E+02 grams Faclllly : Dairyland_NPP Sample Taken On : 9120J2019 10:03:00AM AcqulslHon started : 9/24/2019 12:06:00PM PrDCeCI ure : 500ml Mmlnelll Operatiir : Admlnlatrator Detector Name : HOTLAB Geometry : 500ml Mrinelr. Llva11me : 1800.0 MCOnde Real Time : 1805.5 seconds Deadllme : 0.31 % Peak Locale Threshold : 3.00 Peak Locata Range (In chennela) : 100-4096 Peak Area Range (In dlamels) : 100-4096 ldenllflcation Energy Toleran1;9 : 1.000keV Energy Caibretion UsBd Done On : 7~14 Efficiency Call:iralion Used Done On : 7/8J2014 Efficiency Calibration Oeecrlptlan Sample Number : 7490 PEAK ANALYSIS REPORT P8filk Analysis Perfcrmed on : 9124/2019 12:35:09PN Peak.Analyaia From Channel : 100 Peale Analy&ls To Channel : 4098
9/24/2019 12:35:18PM Page2of6 Analysis Report for L2-011-101-FSGS-010-SS L2-011-101 Peak Enel'flY ROI ROI Peale NetPeak Net.Area continuum FWHM No. (k*VJ start end CentlDid Area Uncertainty Counis (keVJ F 1 238.48 473 - 481 477 . 44 4. 30E+Ol 22.61 2.41E+ 02 1.15 F 2 295.09 584 - 596 590.64 7.66E+Ol 22.41 1. 40E+ 02 1.60 F 3 351.81 699 - 710 704.05 1.14E+02 25.70 1.25E+02 1. 73 F
- 4 583.43 1163 - 1172 1167.21 2.53E+Ol 13. 78 5.21E+01 1.52 F 5 609.2 4 1212 - 1227 1218.81 8.34E+Ol 20.79 5.SOE+Ol 2.43 F 6 1460.47 2913 - 2929 2921 ~ 04 1.14E+02 22 . 22 1.64E+Ol 2.51 M = Flnst peak in a r n J ~ region m
- Other peak in a muhiplet region F .,. Fitted singlet Errons quoted at 2.000sigma BACKGROUND SUBTRACT REPORT PeakAnalyels Performed on : 9/24/2019 '\2:35:09PM Env. Background Fie : c:\Canberra\ApeX\Root\Oairyland_NPP\Dtna\0000001364.CNF PNlc Energy Original Orig. Area Ambient Backgr. Subtracted subtracted No. (keV) Al'N Uncertainty Background Um;ert. Alu UnC8lt F 1 238.48 4.30E+Ol 22.61 4,30E+Ol 2.26E+Ol F 2 295.09 7.66E+Ol 22.41 7.66E+Ol 2.24E+01 F 3 351.81 1.14E+02 25.70 4.18E+Ol l.86E+Ol 7.25E+Ol 3.17E+Ol F 4 583 . 43 2,53E+Ol 13.78 2.53E+Ol 1.38E+Ol F 5 609 . 24 8.34E+Ol 20.79 2.06E+Ol 1 , 21E+Ol 6.28E+Ol 2.41E+01 F 6 1460.47 1.14E+02 22.22 2.82E+Ol B,57E+OO 8,62E+Ol 2 . 38E+Ol M= Finst peak si a multiplet region m = Othar peek in a multiplet raglan F
- Fitted alnglet Errors quoted at 2.000aigma
9/24/2019 12:35:18PM Page3 of6 Analysis Report for L2-011-101-FSGS-010-SS L2-011-101
. NUCLIDE -,DENTIFICATION REPORT Nuclide Library Ulld : C:\Canbarra\Apn\RaoN>al~and_NPP\Utn,y\HOllAB.NLB IDENTIFIED NUCLIDES Nudlde Id Energy Yield(%) Actlvfly At:tlvl,Y Name Contld9nce (lreVJ (pCl/gnms) Unffttalnty K-40 0 .98 1460.75
- 10.67 2.23E+OO 6.27E-01 PB-212 0 .55 77 .11 17.50 238.63
- 44 *. 60 5.25E-02 2. 77E-02 BI-214 0.34 609.31
- 46.30 1. 71E-Ol 6.63E-02 1120.29 15.10 1238.11 5.94 1377 . 67 4 .11 1407.98 2.48 1509.19 2. 19 1764.49 15.80 PB-214 0 . 72 TJ .11 10.70 295.21
- 19 .20 2 . 60E-01 7.70E-02 351.92 ir 37.20 l.48E-01 6.SJE-02
* = Energy line foU"ld In 1he spectrun.
- 111 Mal"lJally added nuellde.
? ,. Manuany edited nuclide.
@ = Energy llne not used tor Weighted Mean .Activity Energy Tolerance : 1.D00 keV NUCiide contldence Index ttnshold = 0.30 Emrs quoted at 2.000Bigma INTERFERENCE CORRECTED REPORT Nucllde Nut:lkla WtfflNn Mmeen comments M,rm, Id Activity Actlvffy l:ontldence Um:emllnty (pCVg,.,,,s)
K-40 0.987 2.23E+OO 6.27E-Ol PB-212 0.558 5.25E-02 2.77E-02 BI-214 0 .349 1. 71E-01 6.63E-02
9/24/2019 12:35:18PM Page 4 of6 Analysis Report for L2-01 M 01-FSGS-010--SS L2-011-101 Nuclide Nuclide Wtmean Wf mNff Comments Nam* Id Activity Ar:tMty
- Contfdence Uncertainty (pCl/grams)
PB-214 0.720 1. 95E--:-01 4.98E-02
? = nudtcle Is part of an oodetermlned aolution X = nudide rejectBd by the intel'ferenc.e analysle
@ = nudlde contains energy linea not u11ed in Weighmd M8811 Activity Em>rS quoted at 2.0DOslgma
9/24/2019 12:35:18PM Page 5 of6 Analysis Report for L2-011-101-FSG~10-SS L2-011-101 UNIDENTIFIED PEAKS Peak Locate Performed on : 912412019 12:35:09PM Peek Locate From Channel : 100 Peak Locate To Channel : 4098 PNk"cPSf") Peak Talerancs PNlrNo. Energy {Ire\? Peale Size (CPS) Uncertainty fype iiuciitie F 4 583.43 1. 40631E-02 27.22 M ., Am peak In a m.illlplet raglon rn "' Other peak in a multiplet region F
- Fitted ainglet Errors quoted at 2.000&igna NUCLIDE MDA REPORT Nucllde Lbary U&ed : C:\Canberra\Apex\Root\Dalfyland_NPP\Ubrary\HOTlAB.NLB Nudlde EnwvY Y181dl") Activity Nucfldf,MDA LlnaMDA Nein* {pCVflams) (pCVgramsJ (p~nrms) fk*V)
+ K-40 1460.75
- 10.67 2 .23E+OO 7 . 89E-01 7 . 89E-01
+ AR-41 1293.64 99.16 -2.94E+14 1.0lE+l S 1.01E+l5 + CO-60 11 '73.22 100 .00 -B.75E-02 7.07E-02 7.01E-02 1332.49 100 .00 3.87E- 02 7 .19E-02 . + KR-85 513.99 0.43 1.20E+Ol l,32E+01 l .32E+Ol + Y-88 898.04 93. 70 -7.91E-03 5,47E-02 6 .54E-02 1836.06 99.20 -5.09E- 02 5.47E-02 + NB-94 '702.63 100.00 -6.04E-02 5.49E-02 5. 49E-02 871.10 100.00 1. 75E-03 5.87E-02 + I -131 284.30 6 .06 4.58E-01 7.43E-02 9. 76E-01 364.48 81.20 -'7,73E-02 7,43E-02 636.97 7 . 27 -5.38E-01 8 . 74E-01 + CS-134 604.70 97.60 -1.37E-02 6,68E- 02 7,65E-02 795.84 85 .40 -1.22E-02 6.6BE-0 2 + CS-137 661. 65 85.12 3.73E-02 6.84E-02 6 . 84E-02 + CE-14-4 80.12 1. 36 -5. 02E-02 3.63E-01 4.SOE+OO 133.51 11.09 -1. 09E-01 3 . 63E-Ol
9/24/2019 12:35:18PM Pa@.e 6 of 6 Analygis RePOlt for L2-011*101-FSGS-010-SS L2-011-101 Nuclide EnfH'9y Yield(%} Ac#vlty Nuc<<de MDA LfnellDA Nam* (lee\? (pCU(ll'IUM) (pCi/grams) (pCilgrams) + EU-152 121.78 28.40 9.38E-02 l .42E-Ol l.42E-Ol 344.28 26.60 -l.lOE-01 1.68E-Ol 1408.00 20.74 9.59E-02 2.96E-Ol + EU-154 123.07 40.40 -3.03E-02 9. 83E-02 9.83E-02 723.30 19.70 2.46E-01 2.89E-Ol 1214.51 35.50 2.67E-02 1.69E-01 + EU-155 86.54 32.80 -2.48E-02 1.58E-01 l.SSE-01 105.31 21.80 -5.38E-02 1.91E-Ol + BI-214 609.31
- 46.30 1.71E-01 1.14E-01 l.14E-01 1120.29 15.10 3.04E-Ol 5.52E-01 1238 .11 5.94 2.20E-Ol 1.38E+OO 1377.67 4.11 -4.89E-01 1,66E+OO 1407.98 2.48 8.02E-Ol 2.47E+OO 1509.19 2.19 -2.22E+OO 3.11E+OO 1764.49 15.80 4. 49E-Ol 5.0lE-01
+ PB-214 77.ll 10.70 4.59E-01 1.20E-01 6.lSE-01 295.21
- 19.20 2.60E-Ol 1.60E-Ol 351.92
- 37.20 l.48E-Ol 1.20E-Ol
+ PA-228 89.95 22.00 2.62E+OO 3.0lE+OO 5.04E+OO 93.35 35.00 2.03E-Ol 3.0lE+OO 105.00 16.30 -2.0SE+OO 5.64E+OO 129.22 2.97 -l.29E+Ol 2.92E+Ol 338.32 S.30 6.72E+OO 1.77E+Ol 463.00 13.80 l.43E+OO 7.59E+OO 911.23 16.70 4.25E+OO 9.12E+OO + AM-241 59.54 36.30 7.62E-02 2.76E-01 2.76E-01 + CM-243 103.76 23.00 -2.41E-02 l.84E-Ol l.84E-Ol 228.18 10.60 2.83E-02 3.53E-Ol 277.60 l*LOO -. 2. 63E-02* 2.96E-Ol
+ ::;
Nuclide identified during Iha nuclide Identification
* =- Energy me found in the gpedJ\tm
- MDA value not calculated
- Half.fir-. too ehort to be able to perform lhe decay conectlon
? = CAUTION: MDA value is inc:oll9istent with Cunfe MDA at 95% confidence level
9/24/2019 1:05:52PM Page 1 of7 JApex-Gamma Analysis Report for L2-011-101-FSGS-011-SS L2-011-101 GAMMA SPECTRUM ANALYSIS Smnple ldentlflcation : l.2-011-101-FSGS-011-SS Sample ONCtlpticn : l.2-011-1O1 SampleType : 500 ml IWarineWi Unit Sampla Pclnt SampleSiz.e ; 8.479E+02 9"BmB Faclity ~ Dalryland_NPP Sample Taken On : ~0/2019 10:23:00MI Aoqulaitlon Started : 81'2412019 12:35:32PM Pnx:edure : 600ml Marfnelll Operator : Admlnlstnm,r Oeled.orNama :HOTLAB Geometry : 600ml Marinelli Lhle1'Tme : 1800.0 9800hda Reel rime : 1805.5 a:econde Dead Tlme : 0.30% Peak Locale Threshcld : 3.00 Peak Locate Range (In d'lannals) : 100-4098 Peak Area Range (In channels) : 100 - 4096 ldeintfflcatlan Energy Tolaran011 : 1.000 keV Energy ca11>ra11on Used Dene On : 711112014 Efficiency Calbratlon Used Done On : 71Br.Z014 Efficiency Caftbratlon Description Sample Nirnbar : 7491 PEAK ANALYSIS REPORT Peak.Analyais Perfunned on : 9.12412019 1:05:43PM PeakAnelyeis From Channel : 100 Peak Analysis To Cllarmel : 4096
912412019 1:05:52PM Page 2 of7 Analysis Report for L2-011-101-FSGS-011-SS L2.011-101 Peak Energy ROI ROI Peak NetPealr NetArea Continuum FWHM No. (hV) start end Centroid Are.a Uncertainty Counts (k*VJ F 1 77.41 151 - 162 155.37 7.53E+Ol 31.91 5.56E+02 1. 43 M 2 87.32 170 - 189 175.17 3.59E+Ol 20.91 2.47E+02 0. 85 m 3 92.92 170 - 189 186.38 4.18E+Ol 21.21 2.26E+02 0. 86 F 4 238.44 474 - 482 477.35 1.05E+02 29.23 2.53E+02 1.64 F 5 295.07 587- 595 590. 60 5 .82E+Ol 20.74 l.43E+02 1.16 F 6 338.40 671- 683 677.24 3.93E+Ol 18.34 1.41E+02 1.53 F 7 351.81 695. - 709 704.05 Ll9E+02 26.11 1.49E+02 1.60 F 8 582.58 1158 - 1172 1165 .51** 5.12E+Ol 18.35* 5.23E+01 3.09 F 9 608.92 1212 - 1223 1218.18 6.31E+Ol 18.35 5.71E+Ol 1.45 F 10 1460.53 2914 - 2929 2921.18 2.53E+02 32.57 2.40E+Ol 2.50 M = Fim peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2.000&lgma BACKGROUND SUBTRACT REPORT PeakAnalyals Perfonned on ; 9/24/2019 1:05:43PM Env. Background FIie : C:\Canben'a"\ApelM00t\Dairyland_NPP'Data\OD00001364.CNF Peak EIHH"9Y Original Orig.Ate* Ambient Backgr. Subfnlcl.ed Subtracted No. (keV) Area Uncenalnty Background Unc<<t. AIU Uncert. F 1 77.41 7.53E+Ol 31.91 7.S3E+Ol 3 .l9E+Ol M 2 87.32 3.59E+Ol 20.91 3.59E+Ol
- 2.O-9E+0l m 3 92.92 4.18E+Ol 21.21 4.l8E+Ol 2.12E+0l F 4 238.44 1.05E+02 29.23 l.05E+02 2.92E+Ol F 5 295.07 5.82E+Ol 20.74 S.82E+Ol 2.07E+Ol F 6 338.40 3.93E+Ol 18.34 3.93E+01 1 .S3E+01 F 7 351.81 1.19E+02 26.11 4.18E+Ol l.86E+Ol 7.7lE+Ol 3.2.lE+Ol F 8 582.58 5.12E+Ol 18.35 5.12E+Ol l.84E+Ol F 9 608.92 6.31E+Ol 18.35 2,06E+Ol 1.21E+Ol 4.25E+Ol 2.20E+Ol F 10 1460.53 2.53E+02 32.57 2.82E+01 8.57E+OO 2.24E+02 3.37E+Ol M a First peak In a multiplet region m =Other peak ln_a multiplet region F = Fitted singlet Emn quoted at 2.000Slgma
9124/2019 1:05:52PM Page 3 of7 Analysis Report for l2-011-101-FSG~11-SS L2-011-101
.NUCLIDE IDENTIFICATION REPORT Nl.iellele Library Uaeel : C:\CarmnalApex\Rool\Dl~d_NPP\Llbrmy\HOTt.AB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy V1eld(%) Activity Activity Name Conffdence (keVJ (pCVgrams) Uncettalnty K-40 0.99 1460.75
- 10,67 5.77E+OO 9.23E-Ol PB-212 0.99 77.11
- 17.50 2.48E-Ol 1.07E-01 238.63
- 44.60 1.27E-Ol 3,61E-02 BI-214 0.33 609,31
- 46.30 l.lSE-01 6.00E-02 1120.29 15.10 1238 . 11 5,S4 1377.67 4.11 1407.98 2.48 1509.19 2 .19 1764.49 15.80 PB-214 0 .99 77.11
- 10.70 4.06E-Ol 1.14E-Ol 295.21
- 19.20 1.96E-01 7.06E-02 351.92
- 37.20 l.57E-Ol 6.58E-02
" = Energy Hne fol.Wld In tile spectrum.
- =Manually added nuclde.
? - ~ually edted nuclide.
@ = Energy line net used for Weighted M8alAc1:Mty Enarvv Tolerance : 1.000 'aV Nuclide confidence index 1hreshold = 0.30 Erras quoted at2000.igma INTERFERENCE CORRECTED REPORT Nuclide Nudlde wtmean Wlmean Commenm Name Id Ar:tlvlty Acllvlty Contldence (pCl/glwmaJ unceri.,nty K-40 0.993 S.77E+OO 9,23E-Ol PB-212 0.992 1.29E-Ol 3,44E-02 BI-214 0.337 1. lSE-01 6.00E-02
9/24/2019 1:05:52PM Page 4 of7 Analysis Report for L2-011-101-FSGS-011-SS L2-011-101 Nuclide Nucllde Mmeen Wtmean Comments Name Id Activity Activity confidence Uncertainty (pCVg,-,nsJ PB-214 0.996 l.77E-01 4.66E-02 7 = nuc:lda is part of an unda1Blmined aolutlon X = nuclide rejected by the irurference analysls
@ = nudide conteilis eri*rgy line. not U8ed in Weighted Mean Activity En'Ons quoted at 2.000slgma
9/2412019 1 :05:52PM Page S of7 Analysis Report for l2-011-101-FSGS-011-SS l2-011-101 UNIDENTIFIED PEAKS Peak Locale Perfonned on : 9124/2019 1:OS:43PM Peak l..ocabt From Channel : 100 Peak Locale To Channel : .-096 Peak CPS "') Peale Tolennoe PNlrNo. Energy(hV) PN1c Size (CPS} Um>>ttalnty 7wJ* Nuc:J/de M 2 87.32 1.99228E-02 29.15 Tel. EU-155 m 3 92. 92 2.32154E-02 25,38 PA-228 F 6 338.40 2.18501E-02 23.32 AC-228 PA-228 F 8 582.58 2.84685E-02 17.91 M = Arst peak In a ll'l.lftlplet region m = Olher peak In
- multlplet region F = Fitted singlet Em:>n1 quoted at 2.DOOalgma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dalryland_NPP\Llbrary\HOTLAB.NLB Nuclide E""'flY ~) Acflvlty NuclldeMDA UnelfOA Name (lreV)
(pCV,rama) (.oCV,nimaJ (pevgr.,a.) + K-40 1460 .75
- 10 .67 5.77E+00 8.38E-01 8.38E-01
+ AR-41 1293.64 99.16 -9.23E+l4 l.21E+l5 l.21E+15 + C0-60 1173.22 100.00 ,;_4.48E-02 7.57E-02 8.73E-02 1332.49 100.00 -2.0SE-02 7.57E-02 + KR-85 513.99 0.43 l.30E+Ol l.43E+Ol l.43E+Ol + Y-88 898.04 93.70 -3.45E-02 5.16E-02 7.23E-02 1836.06 99.20 -l. 35E-02 5.16E-02 + NB-94 702.63 100.00 3.38E-02 5.59E-02 5.59E-02 871.10 100.00 2.73E-03 6.14E-02
9/2412019 1:05:52PM Page 6of7 Analysis Report for L.2-011-101-FSGS--011-SS L.2-011-101 Nut:Jlde Enetr,y Yield(%} Activity Nuclide AIDA LlneMDA Name (keV) (pCVgram.s) (pcuv,.m.J (pCVgraruJ + I-131 284.30 6.06 1.66E-01 7,46E-02 1.02E+OO 364.48 81.20 -6.76E-02 7.46E-02 636.97 7.27 -9.O3E-0l 1.07E+OO + CS-134 604.70 97.60 1.04E-Ol 7.14E-02 7 .14E-02 795.84 85.40 7.00E-02 7.90E-02 + CS-137 661.65 85.12 4.82E-02 8.62E-02 8.62E-02 + CE-144 80.12 1.36 1.BOE+OO 3.77E-Ol 4.79E+OO 133.51 11.09 S.30E-02 3. 77E~0l + EU-152 121.78 28.40 -2.32E-02 1. 46E-01 1.46E-0l 344.:28 26.60 -4,19E-02 1. 91E-Ol 1408.00 20.74 1. 49E-01 3.39E-01 + EU-154 123.07 40.40 -5.78E-02 1.0lE-01 1.0lE-01 723.30 19.70 -1.22E-01 3.03E-01 1274.51 35,50 -4,13E-02 2.0SE-01 + EU-155 86.54 32.80 -3.lSE-02 l.64E-01 1. 64E-01 105.31 + BI-214 609.31 .. 21.80 46.30
-6. 44E-02 l.15E-01 1. 09E-01 l.93E-01 1.09E-Ol 1120.29 15.10 7.61E-01 6.24E-01 1238.11 5.94 4.llE-01 l.66E+OO 1377.67 4.11 -3.02E-Ol 1.59E+OO 1407.98 2.48 1.25E+OO 2.83E+OO 1509.19 2.19 2.79E-01 2.89E+OO 1764.49 15.80 1. 89E-02 4.99E-01
+ PB-214 '17.11
- 10.70 4,06E-01 1. 30E-Ol 4.86E-01 295.21
- 19.20 1.96E-01 1,47E-01 351. 92
- 37.20 1.57E-01 1.30E-01
+ PA-228 89.95 22.00 5.28E+OO 3.09E+00 5.38E+00 93.35 35.00 -1.23E+OO 3.09E+OO 105.00 16.30 -4,43E+OO 5. 71E+OO 129.22 2.97 -6.32E+OO 3.06E+Ol 338.32 5.30 l.93E+Ol 2.07E+Ol 463.00 13.80 2.23E+OO 8. 41E+00 911. 23 16.70 5.05E+OO 9 . 98E+00 + AM-241 59.54 36.30 -2.41E-02 3.00E-01 3.00E-01 + CM-243 103 . 76 23.00 1. 70E-02 l.84E-Ol 1.84E- 01 228.18 10.60 7.SOE-02 4.03E-01 277. 60 14.00 -6.63E-02 3.16E-01
+ = Nuclide identified during 1he nuclide Identification * = Energy Nne foutld In the spectrum > = MDA \/Blue not calculated @ = Half-life too short to be able to perfonn the decay cutection ? = CAUTION: MDAwlue Is inconaietent with OJnfe MOAal 95% c:onfidenc:e level
9/24/2019 1 :05:52PM Page 7 of7 Analysis Report for L2--011-101-FSGS-011-SS L2--011-101
9/24/2019 1:45:54PM Pagel of6 . l'Apex-Gamma Analysis Report for L2-01M01-FSGS-012-SS L2-011-101 GAMMA SPECTRUM ANALYSIS Sample ldentlflcallon : L2-011-101-FSGS-012-SS Sample OAcrlptlon : L2-011-101 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size : 8.006E+02 grams Fldily : Dalryland_NPP Sample Taken On : 9/20/2019 10:30:00AM Acquisition Slartad : 912412019 1:15:35PM ProceciJre : 500ml Marinslli Operetcr : Admlriltnmlr O..ctcrN8me : HOTLAB Geometry : 500ml MartnelU LiwTrme : 1800.0 aeconds Real Time : 1805.7 seconds Oead11me : 0.31 % Peak Locate Threshold : 3.00 Peek Locate Renge On channel&) : 100 - -4098 Peale Area Range (In channels) : 10D-4098 ldemfication Energy Tolerance : 1.000 keV Et1819Y Calbtatlon Used Done On : 7/8/2014 Efficiency Calbatlon Used Done On : 7/&'2014 Efficiency Callntlon Descitptlcm Ssnple NllTlber : 7492 PEAK ANALYSIS REPORT PeakAnalysia Perfunned on : ~ 1 9 1:45;45PM PeakAnalyala From Channel : 100 F>eak Analysis To Chamel : 4096
9/24/2019 1:45:54PM Page 2 of6 Analysis Report for L2-011-101-FSGS-012-SS L2-011-101 Peat Energy ROI ROI l'Nlc NetPHlc NetAru continuum FWHIII No. (lre\lJ 5lart and Centroid Al'N Uncertainty counts (lreVJ F 1 238.47 474 - 482 477.42 1.36E+02 30.84 2.SOE:+ 02 1.42 F 2 294.98 585 - 595 590. 41 4.74E+Ol 19.53 l.74E+02 1.14 F 3 351. 78 699 - 708 703.99 8.40E+Ol 23.07 l.28E+02 l.35 F 4 583.25 1162 - 1172 1166.84 4,60E+0l 17.11 5.54E+0l 1.89 F 5 609.31 1214 - 1226 1218.95 6.12E+0l 18.88 7.81E+Ol 1. 61 F 6 911.09 1816 - 1827 1822.42 3.38~+01 13. 70 2 . 93E+0l 2.05 F 7 1460 .50 2912 - 2931 2921. '12*- 2.4.6£+02 31. 49 4.56E+00 2.44 M = First peek in a multiplet region m == Other peek In a R'llltlplet region F = Fitted alnglet l=non, quoted Ill 2.O00sigme BACKGROUND SUBTRACT REPORT Peak Analysis Perfonned on : 9/24/2019 1:45:45PM Env. Background FIie : C:\Canberra\Apex\Rool\Dalryland__.NPP\Data\0000001364.CNF Peale Energy Original Orig. Area Ambient Badrgr. Subtrar:ted Subtracted No. (keV) Area Uncertainty Background Uncert. A,u Uncert. F 1 238.47 1. 36E+02 30.84 1.36E+02 3.08E+Ol F 2 294.98 4.74E+Ol 19. 53 4.74E+Ol 1. 95E+Ol F 3 351. 78 8.40E+Ol 23.07 4.18E+Ol l.86E+Ol 4.23E+Ol 2.96E+Ol F 4 5B3.25 4.60E+Ol 17.11 4.60E+ Ol l. 71E+Ol F 5 609.31 6,12E+Ol 18.88 2,06E+Ol -1.21E+0l 4.06E+0l 2.24E+Ol F 6 911.09 3.38E+Ol 13.70 3.38E+Ol 1.37E+Ol F 7 1460.50 2.46E+02 31.49 2.82E+Ol 8.57E+OO 2.18E+02 3.26E+0l M = First peak in a mu~ region m = Other peek In a rrutlplet region F = Fitted alnglet Error& quoted at 2.000sigrn8
9/2412019 1:45:54PM Page3 of6 Analysis Report for L2-011-101-FSGS-012-SS L2-011-101 NUCLIDE ./DENTIFICATION REPORT Nucide Library UNd : C:\Canbenll\A~ol\Duyland~PP\Lbary\HOTLAB.NLB IDENTIFIED NUCLIDES Nucllde Id Energy Yleldl") Activffy Activity Nam* Conlldance (k*VJ (pCVgreN) Uncwtalnty K-40 0.99 1460.75
- 10. 67 5.92E+OO 9.47E-01 PB-212 0 .55 77.11 17.50 238.63
- 44. 60 1.76E-01 4.07E-02 BI-214 0.35 609.31
- 46.30 1.l'JE-01 6.49E-02 1120.29 15.10 1238.11 5.94 1377.67 4 .11 1407 .98 2.48 1509.19 2.19 1764.49 15.80 PB-214 0.71 77, 11 10.70 295.21
- 19.20 l.69E-01 7.02E-02 351.92
- 37.20 9.12E-02 6.41E-02
" = E=nargy l~a found in the speclrUm.
-
- MmtueDy added nuclide.
? = ManuaHy edited nudlde.
@ ,., Energy 6ne n01 uaed for Weighted Mean Activity Energy Tclerance : 1.000 kaV Nuctldt confidence index threahold = C.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtm*n WtmNn Commanfa Name Id Activity Acflvlty Conlfdence Uncertainty (pCVg,anq)
K-40 0.990 5.92E+OO 9,47E-01 PB-212 0.557 1. 76E-01 4.07E-02 BI-214 0.350 1.17E-01 6.49E-02
9/24/2019 1:45:54PM Page 4 of6 Analysis Report for L2-011-101-FSGS-012-SS L2-011-101 Nuclide Nucllde Mmean Wtmean Comments Name Id . Activity Activity Confidence Uncettatn~ (pCVgrams) PB-214 0.717 1 .27E-01 4. 73E-02
? = rucllde Is part of an undetermined IOlutlon X = nuclide rejected by the interfenma, analy&is
@ = nucllde contains energy linea not used In Weighted Mean Activity Errors quoted at 2.000slgma
9/2412019 1:45:54PM Pages of6 Analysis Report for L.2-011-101-FSGS-012-SS L.2-011-101 UNIDENTIFIED PEAKS Peak Locate Pslforrned on : 9124/2019 1:.46:45PM Peak Locate From Ch8Mel : 100 Peek Locate To Channel : 4096 Peak CPS "') Tolerance PealrNo. Energy(hVJ Puk Size (CPS) Uncertainty Nucllde F 4 583.25 2.55499E-02 18.60 F 6 911. 09 1.87866E-02 20.25 Tol. AC-228 PA-228 M "' Finll peak In a mulllplet region m "' Other peak in a multiplet region F = Fittad elnglet . Enors quolBd at 2.DOOslgl'rlil NUCLIDE MDA REPORT Nuclide Linty Used : C::\Canberre~\ROOtlDeir)'land_NPP\Llbrary"l-t()lt.AB.NLB Nuclide EIMllfW Vleld{%J Advffy NualldeMDA UnelfOA Name (pCl!g,ams) (pCl/fpams) (pCVgr.wn*) (hV) 1460.75 10.67 5.92E+OO 7.32E-Ol 7.32E-Ol
+ K-40 * + AR-41 1293.64 99.16 1. 30E+15 1.70E+l5 1. 70E+15 + C0-60 1173.22 100.00 -2. 73E-02 8.83E-02 9.02E-02 1332.49 100.00 7 . 67E-02 8.83E-02 + KR-85 513.99 0.43 7.31E+0O 1.50E+0l 1. S0E+0l + Y-88 898.04 93.70 5.72E- 03 5.77E-02 7.46E-02 1836.06 99.20 -9.lOE-03 S.77E-02 + NB-94 702.63 100.00 3.llE-03 6.40E-02 6.40E-02 871.10 100.00 1.24E-02 6 . 68E-02 + I-131 284.30 6.06 -3.49E-01 8,SOE-02 l,12E+OO 364.48 81.20 -2.19E-02 8.SOE-02 636.97 7 . 27 -l. 56E+00 1. 0lE+00 + CS-134 604.70 97. 60 -4.26E-02 7,78E-02 7.78E-02 795.84 85.40 2.49E-02 8.03E-02
9/2412019 1:45:54PM Page 6 of6 Analysis Report for L2-D11-101-FSGS~12-SS U-011-101 M,g/de Elttqy Weldt") Activity NuclldeMDA LlneMDA Name (keV) (pCVg,a,ns) {pCVgntm,J (pCl/gratM)
+ CS-137 661.65 85,12 2,54E-02 B.35E-02 8.35E-02 + CE-144 80.12 1.36 -3.09E+OO 4.02E-Ol 5. 09E+OO 133.51 11.09 -5.02E-02 4.02E-Ol + EU-152 121. 78 28.40 2.SlE-02 1. 58E-Ol 1.58E-01 344.28 26.60 7.94E-03 2.0SE-01 1408. 00 20.74 2.36E-Ol 3.40E-Ol + EU-154 123.07 40.40 1.59E-02 1.llE-01 1. llE-01 723. 30 19.70 3.30E-Ol 3.57E-Ol 1274.51 35.50 1.73E-Ol 2.69E-Ol
+ EU-155 B6,54 32.80 B.77E-02 l.84E-Ol 1.84E-Ol 105.31 21.80 -4.13E-02 2.0BE-01 + BI-214 609.31
- 46.30 1. l 7E-Ol 1. 28E-Ol 1.28E-01 1120.29 15.10 -5.49E-02 5.49E-Ol 1238.11 5.94 -8.75E-02 l.67E+OO 1377.67 4.11 3.lSE-01 1,54E+OO 1407.98 2.48 l. 97E+00 2.84E+00 1509.19 2.19 4.0SE-01 2.91E+OO 1764.49 15.80 3.48E-Ol S.17E-Ol
+ PB-214 77 .11 10,70 l. llE-01 1.23E-Ol 6.86E-01 295.21
- 19.20 l.69E-01 1.79E-Ol 351.92
- 37.20 9.12E-02 1.23E-01
+ PA-228 89.95 22.00 3.68E+OO 3,4'1E+OO 5.97E+00 93.35 35.00 -2.06E+OO 3.47E+OO 105.00 16.30 6.68E-01 6.36&+00 129. 22 2.97 -l.37E+Ol 3.36E+Ol 338.32 5.30 2.18E+Ol 2.27E+Ol 463 . 00 13.80 1.33E+OO 8.73E+OO 911. 23 16.70 l.45E+Ol 1,17E+01 + AM-241 59,54 36.30 -2,24E-01 3.17E-Ol 3.17E-01 + CM-243 103.76 23.00 -5.69E-02 1.99E-01 1.99E-01 228.18 10.60 3.29E-Ol 4.35E-Ol 277.60 14.00 l.83E'"701 3.59E-Ol
+ = Nuclide identified during the nuclide Identification * = Energy line found in the spectrum > = MDA value not calculat2d @ = Half.life too short to be able to perform lhe decay 001TBction ? = CAUTION: MDA value IS Inconsistent wtth Cania MDA at 95% oonfldanoe level
9/24/2019 2:18:43PM Page 1 of7 .....tApex-Gamma Analysis Report for L2-011-101-FSGS-013-SS L2-011-101 GAMMA SPECTRUM ANALYSIS SNnple Identification : L2-011-101-FSGS-013-SS Semple Oeec:ription : L2-011-101 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size . 8.230E+D2 grama Faaillly : Dairyland_NPP 5-nploTakenOn : 9J20J2019 10;43:00AM Acquisition Started : 91U'2019 1:48:24PM Proc.edure : 500ml Martnelll Operator : Admlnlstramr Detector Name :Hon.AB GeomelJy : 500ml Mari'leMI Llvel1me : 1800.o seconds RealTlme : 1806.7 seconds Dffdllme : 0.32 % Pll8k Loc.a1B Thruehold : 3.00 Peak locale Range (In channels) ! 100-4098 Peak Area Range (In channels) : 100-4096 ldenllflcallcn Energy Tolerance : 1.000keV Energy Cslbratlon Used Done On : 7/8/2014 E1llclancy Calbratloh \Jaad Done On : 7/8'2(114 Effk.leuc., Calb1"911on Description Sample Number : 7493 PEAK ANALYSIS REPORT PeakAnaly&is Pariormed on : 9124/201 a 2:18:34PM PeakAnelyeis From Channel : 100 Peak Analyeia To Channel : 4096
9/24/2019 2:18:43PM Pagc2 of7 Analysis Report for L2-011-101-FSGS-013-SS L2-011-101 Peak En81f1Y ROI ROI Peak NetPeak NetArea Continuum FWHII No. (lreVJ start end Centroid Alu Uncwtalnty Counts (keV) F 1 77 . 22 148 - 160 154.98 6.24E+Ol 26.38 6.92E+02 0.84 F 2 185.70 364 - 379 371. 90 6.90E+Ol 29.09 4.66E+02 1.87 M 3 238.70 469 - 489 477. 87 1.49E+02 30.27 2.15E+02 1. 36 m 4 241.67 469 - 489 483.82 5.20E+01 20.99 2.01E+02 1. 36 F 5 295. 06 583 - 595 590.58 6.98E+01 24.27 2.09E+02 1. 61 F 6 351.79 695 - 710 704.01 1 .32E+02 28.55 2.10E+02 1. 79 F 7 583.18 1163 - 1173 . 1166. 70 4.83E+Ol 16.97 5.83E+Ol 1.49 F 8 609 . 04 1211- 1225 1218 . *4 2 l.04E+02 23.34 9.03E+Ol 1.85 F 9 661. 41 1318 - 1328 1323.14 6.45E+Ol 18.95 5 .25E+Ol 1. 74 F 10 910.84 1817 - 1828 1821.92 2.78E+01 12.90 2.92E+Ol 2 .09 F 11 1460.63 2913 - 2929 2921.38 2.08E+02 29.49 1. 68E+Ol 2.70 M .. First peak In a rrultiplet region m =Other peak In a mulllplet n,gion F = Fltlec:I Singlet Errors quoted at 2.000sigrna BACKGROUND SUBTRACT REPORT Peak Analysis Perfum,ed on : 9124/2019 2:18:34PM Env. Baclcground Fne : C:\Canl>erra\Apax\Rool\Oalrylllnd_NPP\Data'°DOOOD1384.CNF Peak Energy Original Orig.Alea Ambient Sackgr. Subhcted Subtracted No. (ke\l) A,u Uncertainty Background UnC411t. Al'N Uncert. F 1 77.22 6.24E+Ol 26.38 6.24E+Ol 2.64E+Ol F 2 185.70 6.90E+Ol 29. 09 6.90E+Ol 2.91E+Ol M 3 238.70 1. 49E+02 30.27 1.49E+02 3.03E+01 m 4 241. 67 5.20E+01 20.99 5.20E+Ol 2.lOE+Ol F 5 295.06 6.98E+Ol 24.27 6.98E+Ol 2.43E+01 F 6 351. 79 l.32E+02 28.55 4 . lSE+Ol 1 *.86E+0l 9.0lE+Ol 3.41E+Ol F 7 583.1B 4.83E+Ol 16.97 4 ,'83E+Ol 1. 70E+Ol F 8 609.04 l.04E+02 23*. 34 2.06E+Ol l.21E+Ol 8.30E+Ol 2.63E+Ol F 9 661.4i 6.45E+Ol 18.95 3.31E+Ol 1.27E+Ol 3.15E+Ol 2.2BE+Ol F 10 910.84 2.78E+01 12.90 2.78E+Ol 1. 29E+Ol F 11 1460.63 2.08E+02 29.49 2.82E+Ol 8.57E+OO 1.80E+02 3.07E+01
=
M Arst peak In a mu111pllll region
=
m other peak In a multiplet n,gion F =Ftlted singlet Errors quoted at 2.000Slgma
9/24/2019 2:18:43PM Pagc3 of7 Analysis Report for l2-011-101-FSGS-013-SS L2-011-101 NUCLIDE IDENTIFICATION REPORT Nuclide Libl'81'Y Used : C;\Canberra\Apex\Root\Dalryland_NPP\Ubrary\HOTI.AB.NLB IDENTIFIED NUCLIDES Nucfltle Id Ene,gy Yleldl"J ActMty Ar.tlviiy Name conndence (bVJ (pCVg,a,m) Uncertainty K-40 0. 99 1460. 75
- 10.67 4.76E+OO 8.55E-01 CS-137 0.99 661.65
- 85.12 5.17E-02 3,76E-02 PB-212 0 .99 77.11
- 17 . 50 2.13E-01 9.llE-02 238.63
- 44,60 1.87E-01 3.92E-02 BI-214 0.34 609.31
- 46.30 2.32E-01 7.47E-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 .,, .11
- 10.70 3.48E-Ol 1 .49E-01 295.21
- 19.20 2.42E-Ol 8.52E-02 351. 92
- 37.20 1.89E-Ol 7.21E-02 RA-226 0.96 186.21
- 3.28 9.87E-01 4.20E-01
* - Energy line foood in 1he spectrum.
- = Manually added nuclide.
?
- Manually ediled nuclide.
@ = Energy line not used for Weighted Mean Activity Eneiw Tolerance : 1.000 keV Nucllcle conftdence Index thre9hold = 0.3D Emn quoted at 2.000slgma INTERFERENCE CORRECTED REPORT
9/24/2019 2:18:43PM Page 4 of7 Analysis Report for L2-011-101-FSGS-013-SS L2-011-101 Nuclide Nuclide WfmHn WtmHn Comments Name Id Activity Activity Confidence Uncetfalnty (pCVgrama) K-40 0.998 4. 76E+0O 8.55E-01 CS-137 0.991 5.17E-02 3.76E--02 PB-212 0.999 1. 72E-01 3. 63E-02 BI-21 4 0.344 2.32E-01 7.47E-02 PB-214 0.997 1. 94E-Ol 5.21E-02 RA-226 0.960 9.87E-Ol 4.20E-01
? = nuclde I* part of an u n d ~ solution X = nuclide rejected b'J the interferance analysis
@ = nuclide contains energy lines not used In Weighted Mean ActMty Enors Quoted at 2.000SIQma
9/24/2019 2:18:43PM Page S of7 Analysis Report for l2-011-101-FSGS-013-SS L2-011-101 UNIDENTIFIED PEAKS Peak Locale Perfomled on : 8/24'.l019 2:18:34PM Peak L.ocabl Fram Channel : 100 Pede Locata To Channel : 4096 l'ealtCPSl"J Peak Tolerance PNkNo. l'Nk S~* (CPS) Um;ertalnty Type Nucllde m 4 241.67 2.88978E-02 20.18 F 7 583.18 2.68229E-0 2 17.57 F 10 910.84 1.54173E-02 23.24 Tol. AC-228 PA-228 M
- Ffrst peak In e multiplet n,glon m
- Other peak kl a multiplet region F = Fitted singlet Errors quoted at 2.000slgrra NUCLIDE MDA REPORT Nuclide Library Used ; C:\Canbena\Apex\Rool\Dairytand_NPP\Llbrary'liOTLAB.NLB Nuclide E""'9y Vleld(%) Actwity NuclldellDA LinellDA Name (pCVgntmsJ {pCl/gramaJ (pCVg,an,a)
'°"'
+ K-40 1460.15
- 10. 67 4.76E+OO 8.14E-Ol 8.14E-Ol
+ AR-41 1293.64 99.16 4. 97E+14 2.0lE+lS 2 . 01E+15 + C0-60 1173.22 100 .* 00 - 2.12E- 02 8.02E- C2 8.C2E-02 1332.49 100.00 5.62E-02 8.50E-02 + KR-85 513.99 0.43 l.14E+Ol 1. 47E+ 0l 1.47E+Ol + Y-88 898.04 93.70 l.62E-02 4,99E-02 8.12E-02 1836.06 99.20 -4.31E-02 4,99E-02 + NB-94 702. 63 100.00 -9.23E-03 6.0GE-02 6.06E-02 871.10 100.00 -7.17E-02 6.32E-02 + I-131 284.30 6.06 4 .29E-01 8 . SOE-02 l . lOE+OO 364.48 81.20 - 2.68E- 02 8.SOE-02
9/24/2019 2:18:43PM Pqc6of7 AnalySII Report fnr L.2-011-101-FSGS-013-SS L2-011-101 Nuclide Enargy Yield(%) At:llvtty Nuclide.VD.A UneMDA Heme (pCVgrams) (pt:llgrams) (pCVgrams) (bV) I-131 636.97 7.27 4.48E-Ol 8.SOE-02 1.18E+OO + CS-134 604.70 97.60 -1,28E-02 8 .19E,;_02 8.BOE-02 795.84 85.40 8.79E-03 8.19E-02 + CS-137 661. 65
- 85.12 5.l?E-02 6.75E-02 6.75E-02
+ CE-144 80.12 1.36 -4.56E-Ol 3.97E-01 5.26E+OO 133.51 11.09 -l.54E-Ol 3.97E-01 + EU-152 121.78 28.40 -8.84E-03 1. SSE-01 1.55E-01 344.28. 26.60 1.25E-Ol 1.98E-Ol 1408.00 20.74 1.14E-01 3.30E-01 + EU-154 123.07 40.40 -1. 45E-03 l.09E-01 l.09E-Ol 723.30 19.70 2.0SE-01 3.07E-Ol 1274.51 35.50 -2.61E-Ol 2.40E-01 + EU-155 86.54 32.80 -1.02£-01 1. 74E-01 1. 74E-01 105.31 21.80 -9.35E-02 2.06E-01 + BI-214 609.31
- 46 .30 2.32E-01 l.34E-01 1.34E-01 1120.29 15.10 -1.00E-01 5.67E-01 1238 .11 5.94 -7,29E-Ol 1. 66E+OO 1377.67 4.11 9.74E-01 1.67E+OO 1407.98 2.48 9.56E-01 2.76E+OO 1509.19 2.19 9.67E-Ol 2.58E+OO 1764.49 15.80 5.44E-Ol 5.99E-Ol
+ PB-214 77.11
- 10.70 3.48E-01 l.SlE-01 5.74E-01 295.21
- 19.20 2.42E-Ol 2.00E-01 351.92
- 37.20 1.89E-01 1. 51E-O1
+ PA-228 89.95 22.00 6.25E+OO 3.33E+OO 5.78E+OO 93.35 35.00 -4.16E-Ol 3.33E+OO 105.00 16.30 -1.62E+OO 6.33E+OO 129.22 2.97 -3.SlE+OO 3 . 33E+Ol 338.32 5.30 l.05E+Ol 2.24E+Ol 463.00 13.80 -3.20E+OO 8.84E+OO 911. 23 16 . 10 -5.93E+OO 1 . llE+0l + AM-241 59.54 36.30 2.56E-02 3.31E-01 3.311!-0l + CM-243 103.76 23.00 3. 49E-02 1.97E-Ol 1. 97E-01 228.18 10.60 1. 7.2.E-01 4.33E-O.l 277.60 14.00 3.58E-02 3.40E-01
+ = Nuclide identified during the nuc:llde ldenuncatlon * = Energy line found in the &peG!rum > = MDA velue nc,t calculawd @ = Half-life loo ehort to be alJle to perfonn the decay correction 7 = CAUTION: MCA value 18 Inconsistent with Cunte MDA at 95% confidence level
9"24/2019 2:18:43PM Page? of7 Analysis Report for L.2-011-101-FSGS-013-SS L.2-011-101
9/24/2019 2:51:55PM Page 1 of6 JApex-Gamma Analysis Report for L2-011-101-FSGS-014-SS L2-011-101 GAMMA SPECTRUM ANALYSIS Sample ldantificetioe') : L2-011-101-FSGS-014-SS Sample Deacrlpt!Ol'I : L.2-011-101 Semple Type : 500 ml Marinelli Unit Semple Point 5an1>'a Sfze : 8.827E-t02 r,ame Facility : Dalryland_NPP Sample Talran On : 9120/2019 2:35:00PM Aoqulaition Started : 9/24/2019 2:21 :38PM
- Prvcedure : 500ml Mllrinell Operator : Administrator Dewctor Name : HOTLAB t3eomeCry : 500ml Mll1nelll Llvellme : 1800.0 seconds Real Time : 1805.3 seconds D'e adTlme : 0.29%
Peak Locat. Threahold : 3.00 Peak locale Range On channels) : 100-4098 Peak Ania Range (In dlannels) : 100-4096 ldenlffloatlon Energy Tolerance ; 1.000 keV Energy Cellbratlon Used Don8 On : 7181201-4 Efflalency calbratlon Used Done On : 7JBl201-4 Efflc:fency Cslbratlan ~ Swnple Numller : 7494 PEAK ANALYSIS REPORT PeakAnalyaia Perfottn&d on : 9/2412019 2:51:*SPM Peak Analyaia From Channel : 100 Peak Analytda To Ch-,nel : 4096
9/24/2019 2:51:55PM Page 2 of6 Analysis Report for L2-011-101-FSGS-014-SS L2-011-101 Peak EnetrlY ROI ROI Peak. NetPaak NetArea Continuum FWHM No. (keVJ start end Cenlrold Al'INI Uncerulnty counts (k*VJ F l 77 .11 148 - 158 154.76 7.15E+Ol 32.95 4.95E+02 l. 74 F 2 295.05 582 - 594 590.55 7.85E+Ol 23.06 1. 57E+02 1.46 F 3 351.91 701 - 712 704.25 l.59E+02 27.22 7.77E+Ol 1. 60 F 4 609.26 1212 - 1224 1218.85 1.09E+02 23.39 7.SSE+Ol 1. 65 F 5 1332.39 2659- 2670 2664.91 1. 79E+Ol 9.69 9.02E+00 2.05 F 6 1460.70 2915 - 2928 2921. 52 9.06E+Ol 20.03 2:3SE+Ol 1.82 M
- Rrst peak in a multiplet regl0n m
- Olher peak in a mutiplet region F "' Fitted singlet Errors quoted at 2.000aigma BACKGROUND SUBTRACT REPORT PaakAnalysie Performed on : 9/2412019 2:51 :-tePM Env. Background FIie : C:\C8nbeml\Apex\Rool\Dairyland_NPP\Da1a\0000001364.CNF Pealr Energy Orlfllnaf Orlf/. AIM Ambient Bllclrgr. Subtracted Subtntcted No. {k*\7 Area Uncertainty Baclcground Uncert. ArH U1Jcelt.
F 1 77 .11 7.15E+Ol 32.95 7.15E+Ol 3.29E+Ol F 2 295.05 7.85E+Ol 23.06 7.85E+Ol 2.31E+Ol F 3 351.91 1.59E+02 2 7 .22 4.18E+Ol l.86E+Ol 1.17E+02 3.30E+Ol F 4 60 9. 26 1.09E+02 23.39 2.06E+Ol l. 21E+Ol 8.85E+Ol 2.63E+Ol F 5 1332.39 1. 79E+Ol 9.69 1. 79E+Ol 9.69E+00 F 6 1460.70 9.06E+Ol 20.03 2.82E+01 8.57E+OO -6.24E+Ol 2.18E+Ol M = Fim peak in a rntAliplet region m "' Other peak in a multiplet region F -= Fitted singlet Errors quoted at 2.000aigma
9/24/2019 2:51:55PM Page 3 of6 Analysis Report for L2-011-101-FSGS-014--SS L.2-011-101 NUCLIDE IDENTIFICATION*REPORT
- Nuclcle Library Used : C:'\Canberra\Apax'IRoal'IDalT)'land_NPP\Ubrary\Hon.AB.NLB IDENTIFIED NUCLIDES Nucllde Id EnetfW Y,eld('1/4J ActMty Activity NMHI Conlld8nce {lre\lJ (pCVgramsJ Unca,m/nty K-40 1. 00 1460,"/5
- 10. 67 l.54E+OO 5.44E-Ol BI-214 0 .34 609 .31
- 46 . 30 2.31E-01 6.99E-02 1120.29 15.10 1238.11 5. 94 1377.67 4 .11 1407.98 2.48 1 509.19 2.19 1764 .49 15.80 PB-214 0 .99 77.11 1r 10,10 3.73E-Ol 1. 74E-Ol 295.21
- 19.20 2.SSE-01 7 .S?E-02 351.92
- 37.20 2.29E-01 6.SSE-02
*
- En.-gy line fouid In lhe spectrum.
- = Manualy added nuclde.
? =ManuaNy edited nuclide.
@ =Energy llne not uaad for Weighted Mean Aedvlty Energy Tolerance : 1.000 keV Nuclide confldanca Index threwdd = 0.30 Errera qUObld at 2.000eiE,na INTERFERENCE CORRECTED REPORT Nuclide Nuclide Mn-.-n M:r.a.:ir. Commanta Name Id Acflvlty AcffVUy Conffdence (pcv,,.,,,.J Unce,tr,lnry K-40 1. 000 l.54E+OO 5.44E-Ol BI-2 14 0.349 2 . 31E-01 6.99E-02 PB-214 0.999 2.SOE-01 4.76E-02
912412019 2:51:55PM Page4of6 Analyals Report 1ot L2.011-101-FSGS-014-SS l2..011*1D1
? = ru:ide is pat of an undetsnnfned aolutlon X = n.teide rejected by the interference analyaie
@ = nucide contains ene,gy ~nes not UB8d in Weighted Mean Activity Enors quoted at 2.000Blgme
9fl4/2019 2:51 :55PM Page 5 of6 Analysis Report for L2-011-101-FSGS-014-SS L2-011-1D1 UNIDENTIFIED PEAKS Peak Locete Performed on : 9/24/2019 2:51:46PM Peek Locate From Channel : 100 Peek Localle To Channel : 4096 Peak CPS(%) Peak Tolelanc:e PNlrNo. Ener,y(hV) ~ Sin (CPS) . Unce,1alnfy 1)'pe Nuclide F 5 1332.39 9.92519E-03 27.12 C0-60 M
- First peak in a multlplat region m = Oth8'1' pesk In a multiplet region F '"' FlttBd singlet Enors quoCiad at 2.000aigma NUCLIDE MDA REPORT Nuclide Llnry Used : C:'X:1~ot'1Du)1ancl_NPP\Llbrar)'\t-10Tl.AB.NLB Nuclide Energy (hV)
Weld(%) Activity NuclldeMDA (pCVgramsJ (pCVgntma} LinellDA (pCVpaml) + K-40 1460.75
- 10.67 1.54E+00 7.86E-01 1,86E-01
+ AR-41 1293.64 99.16 2.24E+14 3. B9E+14 3.89E+14 + C0-60 1173 .22 100.00 4.24E-02 7.83E-02 8.lSE-02 1332.49 100.00 1. 07E-02 7.83E-02 + KR-85 513.99 0.43 l.62E+Ol 1 ,32E+Ol 1,32E+Ol + Y-88 898.04 93.70 1.60E-02 5.23E-02 6.88E-02 1B36_06 99.20 -4.04E-02 5.23E-02 + NB-94 702.63 100.00 -1. 43E-02 4,99E-02 4.99E-02 871.10 100.00 2.06E-03 5_67E-02 + I-131 284.30 6.06 3.lJE-01 1.0SE-02 9.54E-Ol 364.48 81.20 2.4!1E-03 7.0SE-02 636 . 97 7.27 -1.07E-01 9.25E-01 + CS-134 604.70 97.60 -4.99E-03 6.45E-02 8,lSE-02 795.84 85.40 4 . 26E-03 6. 45E-02 + CS-137 661. 65 85.12 2.00E-02 6.42E-02 6 .42E-02 + CE-144 80.12 1.36 -3.54E+00 3.51E-Ol 4.53E+OO 133.51 11.09 -1. 62E-02 3.SlE-01
9/24i2019 2:51:SSPM Pase 6of6 Analysis Report for L2-011-101-FSGS-014-SS L2~1M01 Nucllde Energy Yield(%} Activity Nuclide MOA LlnellDA Name (pCl/gtam$) (pCV(lrBmaJ (pCVsnimsJ (lreV) + EU-152 121.78 28.40 -9.B?E-02 1.30E-01 1.30E-Ol 344.28 26. 60 -8.B3E-01 1.66E-Ol 1408.00 20.74 2.0SE-01 2.96E-01 + EU-154 123.07 40.40 --4.12E-02 9.14E-02 9.14E-02 723.30 19.70 l.22E-Ol 2.65E-Ol 1274.51 35.50 -1.49E-02 1,77E-01 + EU-155 86.54 32. 80 8.82E-02 1.58E-01 1. 58E-Ol 105,31 21. 80 1.98E-02 1.87E-Ol + BI-214 609.31
- 46.30 2.31E-Ol i.lSE-01 1,15E-01 1120. 29 15.10 2.67E-Ol 5. 41E-01 1238.11 5. 94 -5. 48E-01 l. 34E+00 1377.67 4. 11 5.72E-01 l.74E+OO 1407.98 2.48 1. 71E+00 2.47E+OO 1509 .19 2.19 -2,56E+OO 2.24E+OO 1764. 49 15.80 4.22E-Ol 5.25E-01
+ PB-214 77.11
- 10.70 3.73E-01 l.03E-Ol 4.31E-01 295.21
- 19.20 2.SSE-01 l.62E-01 351.92
- 37.20 2.29E-01 1.03E-Ol
+ PA-22B 89.95 22.00 2. 66E+OO 2.65E+OO 4.56E+OO 93.35 35.00 -1.40E+OO 2.65E+OO 105.00 16.30 -l.56E-02 5.16E+OO 129.22 2.97 -7.60E+OO 2.59E+Ol 338.32 5.;30 .-3.34E+OO 1. 70E+Ol 463.00 13.80 ~2.63E+OO 6.52E+OO 911. 23 16.70 l.80E+OO B.06E+00 + .AM-241 59.54 36.30 -3.31E-02 2.71E- 1 2. 71E-Ol + CM-243 103.76 23.00 6.94E-02 1. BlE-01 l . BlE-01 228.18 *10.60 -5.04E-02 3,68E-01 277.60 14.00 '.""1. 74E-01 2.88E- Ol
+ = Nudlde Identified during 1he nuclide identification * = Energy Qne found In the spectrum >
- MCA value not calculated
@ .. Halr-Jlfe too short to be able to pe,folm the decay COff9Ctlon ? = CAUTION: MDA value Is Inconsistent wittl Currie MDA al 95% confidence level
9/24/2019 3:22:56PM Page 1 of7
tApex-Gamma Analysis Report for L2-011-101-FJGS-015-SS L2-011-101 GAMMA SPECTRUM ANALYSIS Sample Identification : l.2-01M01-FJGS-01S-SS Sample Deacripllon : L2-011-101 Sample Type ; 500 ml MaineDI Unit S.mpl1Pomt Sample Size : 6,2481:f-02 grams Facility : Dalryland_NPP SampleTebnOn : 9120/2019 3:01:00PM Acquisition Started '. 9/2412019 2:52:38PM Procedure : 500ml Maitneal 0perator : Admlnlstrallor Ddeclor Name : HOTLAB Geometry ; 500ml MarlneHI LIYe Time : 1800,0 *eccJtld*
Real Time : 1805.6 aecand1 Daadllme : 0.31 % Peak locate Thre&hcld : 3.00 Pllllk Lccale Range (In channels) : 100-4096 PB An,a Range (In cflannels) : 100-4096 ldentiflcallon Energy Tolerance ; 1.000 kaV Energy Cabatlon Used Done On : 7/B/2014 Effliclenq, Cdbratlon Usect Done On : 7/812014 Efficiency Celbration Oeec~ Saq)le Number : 7495 PEAK ANALYSIS REPORT Peak AnaJysis Pelfonned on : 912412019 3:22:47PM PNkAnalysla From Channel : 100 Peek Analyals To Channel : -4096
9/24/2019 3:22:56PM Page2of7 Analysi& Report for L2-011-101-FJGS-015-SS L2*0't1-101 Peal< Energy ROI ROI Peek. Nettaealr NetAru Continuum FWHII No. (lre\l) start end Centroid AIH Une41,talnty Counts (keV} M 1 74.83 146- 159 150.20 6.67E+Ol 26.51 3.90E+02 0.99 m 2 77.09 146- 159 15-4.72 7.78E+Ol 28,11 3.87E+02 0.99 F 3 136.23 270 - 277 272.97 2.90E+Ol 19.85 2.93E+02 0.66 M 4 238.56 474 - 488 47'7.60 2.17E+02 34.90 2.04E+02 1.63 m 5 241.75 474 - 488 483.97 7.0SE+Ol 23.27 2.05E+02 1. 63 F 6 295.20 587 - 596 590.85 '7.17E+01 23.81 1.81E+02 1.44 F 7 351.96 699 - 711 704.35 1.35E+02 28.53 1.69E+02 1.79 F 8 510.01 1011 - 1028 1020.38 4.97E+Ol 18.89 9.48E+Ol 2.66 F 9 583.07 1160 - 1173 1166.49 7.13E+Ol 20.36 6.96E+Ol 2.15 F 10 609.23 1213 .. 1224 1218 ._80 9.87E+Ol 23.45 8.68E+Ol 1.84 F 11 911.06 1816 - 1827 1822.35 S.36E+Ol 17.48 4 .19E+01 2.09 F 12 1120.20 2236- 2245 2240.58 1.94E+Ol 10.95 2.24E+01 1.63 F 13 1460.61 2913 - 2930 2921.33 3.4SE+02 37.55 1.24E+Ol 2.40 M = First peak in a rrKJltfJilet mglon m =Other peak In a multiplet region F = Fttted $inglet Enors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT PeakAnatylis Performed on : 9124/2018 3:22:47PM Env. Background FIie : C:\canberra\Apex\Root\Delryland_NPP\Data\0000001364.CNF Peak Energy Original orig.A,- Ambient Badrgr. Subtracted Subtnct,d (keV) Al'H UnctUtalnty Background Uncert. Area Uncett. No. M 1 74.83 6.61E+Ol 26.51 6.67E+Ol 2.65E+Ol m 2 77.09 7.78E+Ol 28.11 7.78E+Ol 2.81E+Ol F 3 136.23 2.90E+Ol 19.85 2.90E+01 1.99E+Ol M 4 238.56 2.17E+02 34.90 2.17E+02 3.49E+Ol m 5 241. 75 i.05E+01 23.27 7.0SE+Ol 2.33E+Ol F 6 295.20 '1.17E+Ol 23.81 7.17E+01 2.38°E+Ol F 7 351~96 1.35E+02 28.53 4.l8E+Ol 1 ~86E+Cll 9.34E+01 3.41E+Ol F 8 510.01 4.97E+Ol 18.89 4.97E+Ol l.89E+Ol F 9 583.07 7.l3E+Ol 20.36 7.13E+Ol 2.04E+Ol F 10 609.23 9.87E+Ol 23.45 2.06E+Ol 1.21E+Ol 7.81E+Ol 2.64E+Ol F 11 911.06 5.36E+Ol 17.48 5.36E+Ol 1.75E+Ol F 12 1120.20 1. 94E+Ol 10.95 1.94l!:+01 1.lOE+Ol F 13 1-460. 61 3.45E+02 37.55 2.82E+Ol 8.57E+OO 3.l7E+02 3.85E+Ol
9/24/2019 3:22:58PM Page3 of7 Analysis Report for l2-011-101-FJG$-01S-SS l.2-011-101 M = Arst peak In a mu~ region m = Other peak in a m~plal region F = Flttad alnglet . . E;nnra quoted at 2.000elgma NUCLIDE IDENTIFICATION REPORT Nuc:llda Ubra,y Used : C:\Canbell8\Apex\Root\Dalrand_NPP\Librmy\HOTI..AB.Nl.,.S IDENTIFIED NUCLIDES Nuclide Id Enerr,y Yfeldl%J Actrvity Actlvtty Name Confidence (keV) (pCl/r,ranu) Uncemlnty K-40 0.99 1460.75
- 10.67 l, llE+Ol l.48E+00 PB-212 1.00 77 .11
- 17.50 3.SlE-01 1.29E-Ol 238.63
- 44.60 3.59E-Ol 6.0SE-02 BI-214 0.58 609.31
- 46.30 2.88E- Ol 9.86E-02 1120. 29
- 15.10 3.80E-01 2.lSE-01 1238. l.l 5 . 94 1377.67 4 .11 1407.98 2.48 1509.19 2.19 1764.49 15. 80 PB-214 1. 00 77 . 11
- 10.70 5.74E-Ol 2. llE-01 295.21
- 19.20 3.29E-Ol 1. lOE-01 351.92
- 37.20 2.58E-Ol 9.SOE-02
.,
- Enargy flfl* found in th1 spectrum.
- = Manually added nudide.
? "' Manually edited nuclide.
@ = Energy line not uaed for Weighted Meen ActMty Energy Tolerance : 1.000 keV Nuclfde conlldence Jndexthreshold = 0.30 Errcll quotad at 2.DOOalgma INTERFERENCE CORRECTED REPORT
9/24/2019 3:22:56PM Pagc4of7 Analysls Report for L2-011-101-FJGS-015-SS L2-011-101 Nuclide Nuclide wtmean Wtmean* Comments Name Id Activity Activity Confidence Um;ertalnty (pCVgrsma) K-40 0.997 1. llE+Ol l.48E+OO PB-212 1 .000 3.28E-01 S.SJE-02 BI -214 0.584 3.04E-01 8.96E-02 PB-214 1 .-000 2.62E-01 6.88E-02
? "' nudlda Is part of an undetermined solull0n X "' nudlde rejected by the lnterfetence analysis
@ "' nudtde contains energy lfnes not used In Weighted Mean Acllvlty Errore quo1ed et 2.ooo.iglTII
9/24/2019 3:22:56PM Page S of7 Analysis Report for L2-011-101-FJGS-015-SS L2-011-101 UNIDENTIFIED PEAKS Peak Locate Performed.on : 9/24J2019 3:22:47PM Peak Locata From Chelinel : 100
.Peak Locata To Channel : 4098 l'NlrNo. EnetJIY (hV) 'Peek Sin (CPS)
PNlr CPS Um:.nalmy
"'J Tolerance Nut:llde M 1 74.83 3.70636E-02 19.87 F 3 136.23 1.61058E-02 34.24 rn 5 241.75 3.91850E-02 16.49 F 8 510.01 2.76028E-02 19 . 00 F 9 583.07 3.95883E-02 14. 29 F 11 911.06 2.97893E-02 16.30 Tol. AC-228 PA-228 M
- First peak In a irofllplet raglon m "' Other peak in a mul!iplel region F ,. Fitted alnglet Emn quoted at 2.000.lgm NUCLIDE MDA REPORT Nucllde Ubrary Umd : C:\Canbena\Apex\Root\Dalryland_NPP\Llbrary'I-IOTLAB.NLB Nuclide Energy (Ire\?
Yield(%j Al;iivity (pCV(lnln9) lluclideillDA (pCVgnuns} LJn*ilDA (pCVgtMla)
+ K-40 1460.75
- 10.67 1 . llE+Ol 1.03E+OO 1.03E+OO
+ AR-41 1293. 64 99.16 -6.80E+14 7 .43E+14 7.43E+l4 + C0-60 1173.22 100.00 2.78E-03 l. 21E-01 l.28E-01 1332.49 100.00 8,65E-02 1. 21E-Ol
9124/2019 3:22:56PM Pase6of7 Analysis Report for L2-011-101-FJGS-015-SS L2-011-101 Nucllde Energy YJeldf"J Activity Nuclide AIDA LtneM'DA Name (pCVgrama) (pCVgnimsJ (pCl!grams) (k*V)
+ KR-85 513.99 0.43 1.23E+OO l,97E+Ol l.97E+Ol + Y-88 898.04 93.70 1. 09E-01 6, 99E-02 l.lSE-01 1836.06 99.20 -3.0BE-02 6.99E-02 + NB-94 702.63 100.00 -2.88E-02 8.46E-02 8.46E-02 871.10 100.00 -S. 47E-02 9. 7?E-02 + I-131 284.30 6.06 7. 42E-01 1.21E-0l 1. 51E+00 364.48 81.20 l * .04E-01 1.21E-01 636 . 97 7.27 -5.52E-01 1. 54E+OO + CS-134 604.70 97.60 -2.52E-02 l. llE-01 l.lBE-01 795.84 85.40 1.33E-02 1.llE-01 + CS-137 661.65 85.12 4.41E-02 l.12E-Ol 1 .12E-Ol + CE-144 80.12 1.36 -1.57E+OO 5.SlE-01 7.17E+OO 133.51 11.09 1. 95E-01 5.SlE-01
+ EU-152 121.78 28.40 4.69E-02 2. 16E-01 2.16E-Ol 344.28 26.60 7.65E-02 2.88E-Ol 1408.00 20.74 3.lOE-01 4.98E-Ol + EU-154 123.07 40.40 1.05E-02 1.53E-Ol l.53E-Ol 723. 30 19.70 3.12E-01 5.02E-01 1274.51 35.50 1.02E-02 3.13E-01 + EU-155 86.54 32.80 -1. 42E-Ol 2.39E-Ol 2.39E-01 105.31 21. 80 -1. 76E-O l 2.95E-Ol + BI-214 609.31
- 46.30 2.BBE-01 1.66E-01 1.66E-01 1120.29
- 15.10 3.80E-Ol 3.76E-01 1238.11 5.94 6.62E-01 2.38E+OO 1377.67 4.11 5.93E-Ol 2.53E+OO 1407.98 2.48 2.59E+00 4,16E+OO 1509.19 2.19 1.45E+OO 3.92E+OO 1764. 49 15 .80 5.94E-Ol 7.42E-01
+ PB-214 77. 11
- 10.70 5.74E-Ol 1. 78E-01 4.98E-01 295.21
- 19.20 3.29E-Ol 2.29E-01 351.92
- 37.20 2.SBE-01 1.78E-01
+ PA-228 89.95 22.00 4.82E+OO 4.28E+OO 7.17E+OO 93.35 35.00 2,36E+OO 4.28E+OO 105.00 16.30 -3.77E+OO 8.lSE+OO 129.22 2.97 -4.87E+OO 4.19E+Ol 338.32 . 5.30 7.BOE+OO 2.90E+Ol 463 .00 13.80 7 .* BSE+00 1 .21E+Ol 911.23 16.70 2.38E+ l l.65E+Ol + AM-241 59.54 36.30 -6.04E-02 4 . 46E-Ol 4.46E-01 + CM-243 103.76 23.00 1. 96E-Ol 2.BBE-01 2,88E-01 228.18 10.60 -6.38E-02 S,56E-01 2'77. 60 14.00 2.09E-02 4.54E-01
= Nuclide ldentltled during the nuclde identification * ,., Energy line found in the spectrum > = MOA value net calculated @ = Half-life too short to be able to perform the decay correctlcn 7 " CAUTION: MDA value is inconsistent with Qme MDA al 95% confidence level
9/24/2019 3:22:56PM Page 7 of7 Analysis Report for L2-011-101-FJGS.015-SS L2-011-101
9/23/2019 4:03:44PM Page 1 of6 _...tApex-Gamma Analysis Report for L2-011-101-FSGS-002-SS L2-011-101 GAMMA SPECTRUM ANALYSIS Sample ldentitlcatlon ~ L.2-011-101-FSOS-002-SS Sample Deecrfl)IIOn : l2-011-101 SamPleType : 500 ml Malinelll Unit Sanpte Point SemplaSim : 8.773Eof-02 gnama Facility : Dalryland_NPP Sampte Taken On : 9/20/2019 1:0O:00PM Acquisition started : 9/23/2019 3:33:26PM Pfocedure : 500ml Marinelll Operatat - Admlni.tni1or OelectorName :HOTLAB Geometry : 500ml Matneln l..Ne'Ttme : 18D0.0 9eCCf'lds Real Tlrne : 1805.6 seconds Dead Time : 0.31 % P88k l.Qcate Toreshold ; 3.00 Peak l.Qcate Range (In chennela) : 100-4096 Peak Area Range On channels) : 100-4096 Identification Energy Tolenmce : 1.000 ksV Energy Cellbration Ueed Done On . : 7/812014 Efficiency Calbra11on U&ed Done On : 71812014 Efficiency Calbration D98Criptlon Sample Number : 747B PEAK ANALYSIS REPORT Peak Anlltylis Performed on : W23/2019 4:03:35PM Paet.Anelysla From Channel : 100 Peak.Analysis To Channel : 4098
9/23/2019 4:03:44-PM Page 2 of6 Analysis Report for L2-011-101-FSGS-002-SS L2-011-101 Peale Energy ROI ROI Pealr NetPeak NetArea Continuum FWHM No. (ke\l) start end CentrDid ArN Uncertainty Counts {lr*VJ F 1 238.41 469 - 481 477 . 29 5.28E+Ol 21. 78 2.57E+02 1.12 F 2 295.17 587 - 595 590.79 5.13E+Ol 18.75 1.09E+02 1.12 F 3 338 .00 672 - 6B1 67 6. 43 2.35E+Ol 13.66 9.62E+Ol 0.81 F 4 351.85 697 - 708 704 . 12 8.0lE+Ol 21.41 9.62E+Ol 1.52 F 5 609.01 1215 - 1223 1218.35 S.68E+Ol 16.53 2.43E+Ol 1.39 F 6 1460.36 29°14- 2929 2920.84 l.88E+02 27.91 1.02E+Ol 2.51 M = First peak In a roolltplet region m
- Other peak In a multiplet region F = Fdtsd singlet Eno,- quatf.td at 2.DOOelgma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 9123/2019 4:03:35PM Env. Background FIie : C:\C11nbefta\Apex\Root\Delryland_NPPIDati1\0000001364.CNF Peak .Enerw Original Ol1g.AIN Ambient Baclcgr. Subltacted Sublracfed No. {leeV) AIU Uncertainty Ba~r,round Unr:ert Area Um:wt.
F l 238.41 5.28E+Ol 21. 78 5.28E+Ol 2.18E+01 F 2 295.17 S.13E+Ol 18.75 5.13E+Ol 1. 87!;:+01 F 3 338.00 2.35E+Ol 13.66 2.35E+Ol 1. 37E+Ol F 4 351. 85 8.0lE+Ol 21.41 4,18E+Ol L 86E+Ol 3.83E+Ol 2.84E+Ol F 5 609.01 5.68E+Ol 16 . 53 2.06E+Ol l.21E+Ol 3. 62E+Ol 2. 05E+Ol F 6 1460.36 1.88E+02 27.91 2.82E+Ol 8.57E+OO - 1.60E+02 2.92E+Ol M = First peak k'I a mulllplet region m = other peak In a multiplet region F = Fitted singlet Errors quo1ed at 2.000slgma
9/23/2019 4:03:44PM Page 3 of6 Analysis Report for L2-011-101-FSGS-002-SS L2-011-101 NUCLIDE IDENTIFICATION REPORT Nucllda Library Used : C:\Canberra~d_NPPU.lbrary\HOTLAB.NL8 IDENTIFIED NUCLIDES Nuclide Id Enerrw Yreldl%) ActiVfty Activity Name Conlldence (Ire~ (pCVQtalU) Unc,,,qlnty R-40 0 . 97 1460.75
- 10.67 3.98E+OO 7.58E-Ol PB-212 0 .55 77.11 17.50 238.63
- 44.60 6.21E-02 2.SSE-02 BI-214 0 .34 609.31
- 46.30 9.50E-02 5.40E-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 PB-214 0 .72 77 .11 10. '70 295 ,21
- 19.20 1.67E-Ol 6.17E-02 351.92
- 37.20 7.54E-02 5.GOE-02
* = Energy ~ne found in the spectrum.
- ... Maiually added nuclde.
7 =Manually edited nLdde.
@ = Energy llne not ualtd fur Weightsd Mean Activity Energy Talerance : 1.000 kBV Nuclde confidence Index lhresllo!d "' 0.30 Errera quoted at 2.0DDslgma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmean Wtmun comments Name Id Activity Activity Confidence Unc.rflllnty (pCV.-ms)
K-40 0. 977 :3.98E+00 7 . 58E-01 PB-212 0 .555 6.21E-02 2.58E-02 BI-214 0.342 9.SOE-02 5.40E-02
9/23/2019 4:03:44PM Page4of6 Analysis Report for L2-011-101-FSGS-002-SS L2-011-101 Nuclide Nuclide Wl'meen Wt.mean Comments Name Id Ar:twlty Activity Confidence Uncertainty (pCilgrams) PB-214 0.721 1. 1 7E-Ol 4 .15E- 02
? = nuclide is part ar an undelermlned &Clfutlon X = nuclide rejadBd by the Interference analysts
@ = nuclide contain& energy llnes not used In Weighted Mean Activity Errors quoted at 2.000aigma
9/2312019 4:03:44PM Page S of6 Analysis Report for L2-011-101-FSGS-002-SS L2-011-101 UNIDENTIFIED PEAKS Peele Locate Performed on : 9/23/2019 4:03:35PM Peak Locate From Channel : 100 Peek Locete To Channel : 4096 Peale CPS (%) Peak Tolerance PNkNo. Peak 61- (CPS) Unr:e,talnty Type Nur:llda F 3 338.00 1.30350E-02 29.12 Tol. AC-228 PA-228 M = Flnt peak In a n.ill4llet region m z Other peak in a m~plel n1gion F = Fnted singlet Em>ra qUOllld at 2.0UDllllgme NUCLIDE MDA REPORT Nuclide Lln.ry Used : C:\CanbemMpex\Root\Dairyland_NPP\library\HOTLAB.NLB Nudlda Energy Yreld("J ActMty NuclldeMDA l.lnetlDA Name (pCVgn,ma} (pCI/QIUt*J (pCllglama} timVJ + K-40 1460.75
- 10. 67 3.98E+O0 '7,03E-01 7.03E-Ol
+ AR-41 1293. 64 99.16 -1.lOE+ll l.27E+ll l.27E+11 + C0-60 1173.22 100.00 -5.31E-02 6 , 70E-02 7.81E-02 1332.49 100.00 7.BBE-04 6.'iOE-02 + KR-85 513.99 0.43 1.30E+Ol 1. 26E+0l l.26E+Ol + Y-88 898.0-4 93,70 9,62E-03 4.32E-02 6.45E-02 1836.06 99.20 -4.96E-02 4.32E-02 + NB-94 702.63 100 . 00 -4.B6E-02 4.98E-02 4.98E-02 871.10 100 . 00 -5.94E-02 5.34E-02 + I-131 284.30 6. 06 -2.36E-01 6.87E-02 8.27E-01 364.48 81.20 1. 99E-02 6,87E-02 636.97 7.27 3.94E-01 8.48E-01 + CS-134 604.70 97.60 5.76E-02 6.25E-02 6.25E-02 795.84 85.40 -1. B9E-02 6.48E-02 + CS- 13'7 661. 65 85.12 5.B6E-02 1.14E-02 7.14E-02
9/2312019 4:03:44PM Puge6of6 Analyels Report for L2-011-101-FSGS-002-SS L2-01M01 Nuclide Energy YIMl"'J AGtlvlty NucHdeMDA UneMDA Name {ke\l) (pCVgrams) (pCi/gn,ms) (pCI/Ql'alna) + CE-144 80.12 1.36 1.24E-0l 3.41E-01 4.14E+OO 133.51 11.09 1.57E-02 3.41£-01 + EU-1S2 121. 78 28.40 3.13E-02 1.31E-Ol l.31E-Ol 344.28 26.60 -4. 87E-02 1.62E-01 1408.00 20.74 2.40E-02 3.16E-01 + EU-154 123.07 40.40 4.07E-03 9.lOE-02 9.lOE-02 723.30 19.70 -9.14E-02 2.47E-01 1274.51 35.50 2.09E-01 2.39E-01 + EU-155 86.54 32.80 -8.37E-02 1.46E-Ol 1.46E-01 105.31 21.80 -2.07E-03 1.SlE-01 + BI-214 609.31
- 46.30 9.SOE-02 8.60E-02 8.60E'."'02 1120.29 15.10 2.36E-Ol 4.92E-01 1238.11 5.94 6.06E-01 1.31E+00 1377.67 4.11 -l.99E-01 l.SOE+OO 1407.98 2.48 2.0lE-01 2.64E+OO 1509.19 2.19 -1.27E-Ol 2.S0E+00 1764.49 15.80 2.95E-Ol 4.07E-01
+ PB-214 77.11 10.70 2.88E-Ol 1. 0BE-01 5.58E-01 295.21
- 19.20 l.67E-Ol 1.25E-Ol 351. 92
- 37.20 7.54E-02 1.0SE-01
+ PA-228 89.95 22.00 1.89E+OO l.33E+OO 2.30E+OO 93.35 35.00 -7.57E-Ol l.33E+OO 105.00 16.30 -1.46&+00 2.53E+OO 129.22 2.97 -2.lOE+OO 1.30E+Ol 338.32 5.30 -2.14E-01 8.57E+OO 463.00 13.80 3.lOE+OO 3.70E+OO 911.23 16.70 2.84E+OO 4.19E+OO + AM-241 59.54 36.30 3.-62E-02 2.73E-Ol 2.73E-Ol + CM-243 103.76 23.00 --4.27E-03 l.72E-Ol l.72E-Ol 228.18 10.60 -5.45E-02 3.41E-01 277.60 14. 00. 5.47E-02 2.94E-01
+ !!!< Nuclide Identified during the nuclide identification .. = Energy line found In the spec1rum > = MDA value not calculated @ = Half~ife too short to be able to perform the decay comu:tion ? = CAUTION: MDA value Is inconsistent YJiih Currie MDA at 95% confidence level
9/24/2019 6:47:57AM Page 1 of7 Analysis Report for L2-011-101-FSGS-003-SS L2-011-101 GAMMA SPECTRUM ANALYSIS Sample ldenlfflcallon : L2-011-101-FSGS-003-SS Smnple DNCl'lptlon : L2-011-1D1 Sami:,te Type : 500 ml Marinelli Unit Sample Point Saq>leSu.e : 8.123E+o2 gnims Faclllty : Dall)1and_NPP Sample Taken On : 9/20J2019 1:26:DOPM Acquisition started : 9/2412019 6:17::MAM Procedure : 600ml Malinell ()l)eraklr : A.dmlnistralDr Dalactor Name : HOilAB Geometry : 500ml Marinelli LIYeTlmt : 1 eoo.o seconds Real lime : 1805.78~8 Dead Time : 0.31 % Peak Lclcala Threshold : a.oo Peak Lccala Range (In channels) : 100-4096 Peak Area Range Qn channels) : 100-4096 ldanlfflcaflon EFMUY Tolenmce : 1.000 keV Energy Calibration Used Done On : 71812014 Efficiency Callbndlon UMd Done On : 7f&/2014 Efflaeney Callbrali0fl Deecrtptlon Sample Number : 7481 PEAK ANALYSIS REPORT Palk Analyli8 Perfunned on : 9/2412019 8:47:"8AM Peak.Analysis From Channel : 100 PeakAnaly&is To Chamel : 4096
9/24/2019 6:47:57AM Page2 of7 Analysis Report for L2-011-101-FSGS-003-SS L2-011-101 Peall. Energy ROI ROI Peale Net Peale NetAtM ConUnuum FWHM No. (hV} start end Centroid Area Uncertainty Counts {Ire\.? M 1 238.55 473 - 490 477.58 1.04E+02 26 . 88 2.10E+02 1.56 m 2 241.77 473 - 490 484.00 5. 51E+Ol 21 . 02 1. 80E+02 1.57 F 3 295.13 584 - 595 590.72 5. 87E+Ol 20 .79 l,53E+ 2 1.38 F 4 338.46 669 - 682 677.36 3.45E+Ol 17.42 l . 47E+02 1.36 F 5 351.91 698 - 711 704 . 25 1. 09E+02 24.74 1.11E+02 1. 96 F 6 583.59 1163 - 1172 1167.52 2.77E+Ol 12.54 5.29E+Ol 1. 60 F 1 609. 23 1214 - 1225 1218.79 7.20E+Ol 19.55 5. 71E+Ol 1.56 F 8 1119.81 2234 - 2244 2239.81 l .49E+Ol 6.86 4.16E+Ol 1.50 F 9 1460.51 2911 - 2928 2921.13 2.55&+02 32 . 67 2 . 30E+Ol 2.34 M = First peek In a multlplet region m =Other peak in a mulllplet region F = Fitted alnglet Errol'8 quoted at 2.000algma BACKGROUND SUBTRACT REPORT Peak Analysis Peffonned on : 9/2412019 6:47:48AM Env. Backgroond File : C:\Cari>effll\Apel(IR()ot\Dakyiand_NPP\Oeta\0000001364.CNF Peak EIHIIJIY Original Orig. Aru Ambient Baekgr. Subtncfed Subtracted No. (keV) Area Uncertainty Background Uncert. AIM .Uru:81f. M 1 238.55 l.04E+02 26.88 1.04E+02 2.69E+01 rn 2 241.77 5 . 51E+Ol 21.02 5.51E+Ol 2.lDE+Ol F 3 295.13 5.87E+Ol 20.79 5.87E+Ol 2.0BE+Ol F 4 338.46 3.45E+Ol 17.42 3.45E+Ol 1.74E+Ol F 5 351. 91 l.09E+02 24.74 4. 18E+Ol 1 , 86E+Ol 6. 75E+Ol 3 .lOE+Ol F 6 583.59 2.77E+Ol 12.54 2.17E+Ol l.25E+Ol F 1 609. 2 3 7. 20E+Ol 1 9.55 2.06E+Ol l..21E+Ol 5 .14E+0l 2.30E+Ol F 8 1119.81 1.49E+Ol 6.86 1.49E+Ol 6.86E+OO F 9 1460. 51 2.55 E+02 32.67 2.82E+Ol 8.57E+OO 2. 27E+02 3.38E+Ol M = First peak il a tooltilllet n=glon m =other peak In a mulllplet region F = Fitted singlet Errors quoted at 2.000&lgma
9/24/2019 6:47:57AM Page3 of7 Analysis Report for L2-011-101-FSGS-003-SS L2-011-101 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dalryland_NPP\Llbrary\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yleldf") Activity Activity Name Confidence (keVJ (pCV,,.ma) Uncertainty K-40 0 .99 1460.75
- 10.67 6-09E+OO 9.67E-01 PB-212 0 .56 '77.11 11.50 238.63
- 44.60 l.32E-Ol 3.48E-02 BI-214 0 .57 609.31
- 46.30 1. 46E-Ol 6.S?E-02 1120.29
- 15 .10 2.24E-01 1.O4E-0l 1238.11 5. 94 1377.67 4. 11 1407.99 2,48 1509.19 2. 19 1764.49 15.80 PB-214 O.i2 77.11 10.70 295.21
- 19 .20 2~07E-01 7 .39E-02 351.92
- 37.20 l.44E-01 6.62E-02
* = Energy line found in 1M apec;trum.
-
- M.waly added nuclld&.
? "' Manualy edibld nudide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV NUcl!de confidence lnd&X ttnsho!O .. o.ao Errors quoted at 2.000slgrna INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmeen Wfmean comments Name Id Activity Actlvtly Confidence Um:Mialniy (pCVgramaJ K-40 0 .991 6.09E+OO 9.67E-01 PB-212 0 .560 1.32E-01 3.4BE-02 BI-214 0.579 1. 68E-Ol 5.55E-02
9/2412019 6:47:57AM Page4of7 Analysis Report for L2-011-101-FSGS-003-SS L2-D11-101 Nuclide Nuclide Wt mean Wtmean comment. Name Id ActNlty Activity Confidence (pCVgram$} Uncertainty PB-214 0.721 1. 72E-Ol 4.93E-02 7 = nudfde Is part of an undetennined solution X = nucllde rejected by 1he fnterference analysle
@ = nuclide contains energy llnes not used in Weighted Mean Activity Enors quoted at 2.000eigma
9/24/2019 6:47:57AM Pagc5 of7 Analysis Report for L2-011-101-FSGS-003-SS L2-011-101 UNIDENTIFIED PEAKS Peele Locate Performed on : 9/24r.i!019 6!47:48AM Peale Locate From Channel : 1DO Peele Locate To Channet : 4096 PNkCPS(") Peak Tolersnce PHkNo. l'uk Sia (CPS) UIN>>l'talnfy J}tpe Nuclide m 2 241,77 3.06166E-02 19.07 F 4 338.46 l. 91747E-02 25.23 AC-228 PA-228 F 6 583.59 1. 53958E-02 22. 63 M
- First J1118k in fl multiplet region m = Other peak In a multiplet region F = F1ttad singlet Errors quoted at 2.00Daigma NUCLIDE MDA REPORT Nuclide Library U--1 : C:\Canbena\Apex\Root,Dairyl11nd_NPP\Library\HOTLAB.NLB Nuclide EnetrJY Yield(%) ActMty Nuclide IIDA UneMDA Name (pCVgrams) (pCVgn,ms) (pCVgra.ms)
(h~ + K-40 1460.75
- 10.67 6.09E+OO 8.8SE-Ol 8.85E-Ol
+ AR-41 1293.64 99.16 -8.84E+l2 3.78E+13 3.78E+13 + co-60 1173.22 1 00.0 0 6.00E-02 8.SlE-02 8.74E-02 1332.49 100.00 l. 60E-02 8.SlE-02 + KR-85 513.99 0.43 l.33E+Ol 1.SOE+Ol l.50E+Ol + Y-88 898.04 93.70 1 . 68E-02 5.04E-02 7.40E-02 1836.06 99.20 -3.99E-02 5.04E-02 + NB-94 702.63 100.00 -7.41E-03 6.23E-02 6.23E-02 871.10 100.00 -8.SOE-03 6.35E-02 + I-131 284.30 6.06 4.16E-Ol 7.53E-02 1.06E+00 364.48 81.20 3.43E-02 7.53E-02
9/24/2019 6:47:57AM Page 6 of7 Analysis Report for L2-011-101-FSGS-003-SS L2-011-101 Nuclfde Energy Yleld"'J Actltllty NucJldeMDA UnellDA Name (pCl/gtams) (pCVg,ams) (pCUgrams) (ke~ I-131 636.97 7.27 l.llE-01 7.53E-02 l.14E+OO + CS-134 604.70 97.60 -4.49E-02 7.56E-02 7.92E-02 795.84 85.40 -7.49E-02 7.56E-02 + CS-137 661.65 85.12 S.13E-02 7.54E-02 7.54E-02 + CE-144 80. 12 1.36 -5.46E-01 3.87E-01 4.89E+OO 133.51 11.09 2.71E-01 3.87E-01 + EU-152 121. 78 28 *.40 -1. llE-01 1.52E-01 1.52E-01 344.28 26.60 4.41E-02 1.99E-01 1408.00 20,74 -1.97E-01 2.85E-01 + EU-154 123.07 40.40 6.78E-04 1. OBE-01 1,0BE-01 723.30 19.70 -8.40E-02 3.llE-01 1274.51 35.50 8.85E-02 2,22E-01 + EU-155 86.54 32.80 -8.63E-03 1. ?SE-01 l.75E-Ol 105. 31 21.80 1.34E-01 2.12E-01 + BI-214 609.31
- 46.30 l.46E-01 1.14E-Ol l.14E-01 1120.29
- 15.10 2.24E-01 3.92E-01 1238 . 11 5.94 5.15E-Ol 1.81E+OO 1377.67 4 .11 8.73E-Ol 1.49E+OO 1407.98 2.48 -1.65E+OO 2.38E+OO 1509.19 2.19 8 . 09E-Ol 2.44E+0O 1764.49 15.80 7.96E-02 4.27E-Ol
+ PB-214 77 .11 10.70 4.98E-01 1. 23E-01 6.68E-01 295 .21
- 19.20 2.07E-01 1.70E-01 351.92
- 37.20 1.44E-01 1. 23E-01
+ PA-228 89.95 22.00 2.83E+OO 2.44E+OO 4.l3E+OO 93.35 35.00 -2.24E-01 2.44E+0O 105.00 16.30 3.53E+OO 4.75E+OO 129.22 2.97 5.18E+OO 2,33E+Ol 338.32 5.30 2.87E+OO 1.58E+Ol 463.00 13.80 -3.56E-01 5.BSE+OO 911. 23 16.70 7.29E+OO 8,17E+OO + AM-241 59.54 36.30 l. 75E-02 3.15E-01 3.lS;E-01 + CM-243 103.76 23.00 6.29E-02 2.03E-Ol 2,03E-01 228.18 10.60 -3.06E-01 3.91~-0l 277.60 14.00 -2.13E-02 3,28E-01
+ = Nuc;lide identified during the nucride Identification * = Energy line found in tha apeclrum > = MDA value not calcula1ed @ = Half-life too ehort to be able to perform the decay c;om,cUon ? = CAUTION: MDA value is inoonsist.il with Cunie MOA at 95% confidence IIMII
9/2412019 6:47:57AM Page 7 of7 Analysis Report for L.2-011-101-FSGS-003-SS L.2-011-101
9124/2019 11:24:41AM 'Page 1 of6 Analysis Report for l2-011-1O1-FQGS-009-SS l2-011-1O1 GAMMA SPECTRUM ANALYSIS Sanple Identification : 1.2-011-101-FQGS-009-SS
&mple OMCtlptlon : L2-011*101 sample Type : 500 ml Marfneljl Untt Sample Point Sample SiZ8 : 7.209E+o2 grams Facilty : Dalryland_NPP Sample Taken On : 9120/2018 9:62:00AM Acqulsfflon Started ~ 9124/2019 10:54:23AM Procedure : {i()(Jml MarinaHI Operator : Admlnl8tlmor Detactor Na-ne : HOTLAB Geometry : 500ml Marinel~
LNeTime : 1800.0 seconds Real Time : 1805.5 eeconds DeadTime : 0.31 % Peak l.ccate Thre&hold :3.00 Peak Loca1e Ran119 (fn channels) : 100--4096 Peek Area Range Qn c::hl!lllnels) : 100-4096 ldaltification Energy Tolerance : 1.000 keV Energy Calhatlon Used Done On : 7/812014 Effic:iancy Calbration Used Done On : 71812014 Efficiency CeHbrrion Descrfptlon Sanl)le Number : 7489 PEAK ANALYSIS REPORT PeekAnaly9is Performed on : 11124/2018 11:24:32AM Peak Analysis From Otannef : 100 Peak Analysis To Chamel : 4096
9/24/2019 11:24:41AM Page 2 of6 Analysis Report for L2-011-101-FQGS-009-SS L2-011-101 Peale Energy ROI ROI Peak N9tPeak NelArea Continuum FWHM No. (keVJ start end Qmtrold Area Unt:ertalnty Counts (k*VJ F 1 76.38 14:7- 160 153.30 1. 66E+02 45.71 7.30E+02 2.67 F 2 238.58 472- 485 477.63 2.07E+02 35.27 2.86E+02 1.77 F 3 295.31 587- 595 591.07 5.SOE+Ol 21.19 l.56E+02 1.23 F 4 338.61 669 - 685 677.65 4.68E+Ol 20.20 l.74E+02 1.99 F 5 351.86 698 - 711 704.15 1.29E+02 27.21 1.82E+02 1.49 F 6 5B3.05 1160 - 1170 1166.45 7.69E+Ol 19.81 4.40E+Ol 1. 78 F 7 609.17 1214 - 1224 1218.67 7.52E+Ol 19.52 4. 71E+01 1. 56 F 8 911.33 1817 - 1829 1822.90 5.12E+Ol 17.36 4.25E+Ol 2.82 F 9 1460.52 2912 - 2930 2921.16 2.74E+02 34.16 3.BOE+Ol 2. 62 M "' First peak in a mu~et re1110n m "" Other peak in a m!Mlplet f'811ion F "' Frtted singlet Erran, qucl9d at 2.000sigma BACKGROUND SUBTRACT REPORT Peel< Analysls Performed on : 9124/2019 11:24:32AM Env. Background FIie : C:\Canberra\Ape>t\Rod\Dalryland_NPP\Data\0000001364.CNF Pok Enfll0' Original Orig. Atea Ambient Saclcgr. Subtnlcted Subtrar:ted No. (keV) AIU Uncertainty Background Uncert. Ania Uncert. F 1 76.38 1 . 66E+02 45.71 1. 66E+02 4.57E+Ol F 2 238.58 2.07E+02 35.27 2.0'7E+02 3 . 53E+Ol F 3 295.31 5.SOE+Ol 21.19 5.SOE+Ol 2.12E+Ol F 4 338.61 4.68E+Ol 20.20 4.68E+Ol 2.02E+Ol F 5 351. 86 1.29E+02 27.21 4.18E+Ol 1. 86E+0l B.77E+01 3.30E+01 F 6 583.05 7.69E+Ol 19.81 7.69E+01 1.98E+01 F 7 609.17 7.52E+Ol 19.52 2 . 06E+Ol 1. 21E+Ol 5.46E+Ol 2.30E+Ol F 8 911.33 5.12E+01 17.36 5.12E+Ol 1. 74:E+Ol F 9 1460.52 2.74E+02 34.16 2.82E+Ol 8.57E+OO 2.46E+02 3.52E+Ol M = Fil"9l peak in a multiplet region m "' other peak in a multiplet region F
- Fitted ainglet Enon, quolBd 111 2.000algma
9/24/2019 11 :24:41AM Page 3 of6 Analysls Report for L2-011-101-FQGS-009-SS L2-01M01 NUCLIDE IDENTIFICATION REPORT Nucllde Llbra,y Uled : C:\Canberra\Apex\RooNlalryiand_JtPP\Llbrwy\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Ener,w Yield(3/4) Activlly Actlvfty Name ' Conlldence fk*VJ (pCVgrama) Ur,certalnty K-40 0.99 1460.75
- 10. 67 7 . 44E+OO 1.14E+OO PB-212 0.97 77 .11
- 17.50 6.58E-01 1.86E-Ol 238.63
- 44. 60 2.96E-01 5.27E-02 BI-214 0.34 609.31
- 46.30 l.74E-01 7.40E-02 1120.29 15.10 1238 .11 5.94
*1377 . 67 4. 11 1407.98 2.48 1509 . 19 2. 1 9 1764.49 15.80 PB-214 0.98 77 .11
- 1 0.70 1.0BE+00 3.OSE-O1 295.21
- 19.20 2.lBE-01 8.48E-02 351. 92
- 37.20 2.lOE-01 7.97E-02 AC-228 0.30 209.28 4 .40 338 . 32
- 11.40 3.54E-01 l.54E-01 794. 70 4 .60 911. 60
- 27 .70 3.94E-01 1.35E-01 96 4 .60 5.20 969 .11 16. 60
* = Energy llne found In lhe spe<:trum.
- = Manually added nudlde.
? = Manualy eclted nuclde.
@ = Energy ltne not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide canfldence Index threshold= 0.30 Errors quoted at 2.000sigme INTERFERENCE CORRECTED REPORT
9/24/2019 11:24:41AM Page 4 of6 Analysis Report for L2-011-101-FQGS-009-SS L2-011-101 Nucl#M Nuclide Wlmeen WtmNn Comments Name Id Actl11lty A'11Jt,ity Confidem:e . (pCVgrems} Unc81'tltinty K-40 0.992 7.44E+OO 1.14E+OO PB-212 0.976 . 3.13E-Ol 5.OBE-O2 BI-214 0.348 1.74E-01 7.40E-02 PB-214 0.986 2.26E-01 5.71E-02 AC-228 0.304 3.76E-Ol l.OlE-01
? = nuclide is pert of en undeterrniied solution X = nuclide rejected by the lnterferanca anelyllis
@ = nuclide cootaina energy lines not used in Weighted Mean Activfty Emlra quo.d at 2.000&igma
9/24/2019 11:24:41AM Page S of6 Analysis Report for L2-011-101-FQGS-009-SS L2-011-101 UNIDENTIFIED PEAKS Peak LocalB P1rfonned on : 9124/2019 11::24:32AM Peak Locam From Cta1nel : 100 Peek Locete To Channel : 4098 PeakCPS("J Peak Tolennc:e PNlcNo.* Enerr,y~\I) Pule Sin (CPS) Uncertainty Type Nuclide F 6 583.05 4.27453E-02 12.87 M = Flrat peak In a mut~ n,glon m :::. other peak In a mlAtlplet r&gion F :::: Fitted s'nglel Errors qUClled at 2.000sigmll NUCLIDE MDA REPORT Nucl!de LbaTY Uaad :, C:\Can~nmi\Apex\Root\Daiyland_NPPILlbra'Y""tOTLAB.NLB Mlcllde EnetflY Y,aldf"J Ac#Vlty NuclldaMDA UneUDA Name (pCll;rams} (pCVgtamaJ (pCVgnt,,..) (lteV) + K-40 1460.?5
- 10. 67 7.44E+OO 1.13E+00 1.13E+OO
+ AR-41 1293.64 99.16 2.47E+14 1. 02E+l5 1.02E+15 + co-60 11'73.22 100.00 5.09E-02 9.14E-02 l,O?E-01 1332.49 100.00 2.34E-02 9.14E-02
+ KR-85 513.99 0.43 9.83E+OO 1. 73E+0l 1. 73E+Ol + Y-88 898.04 93.70 -2.04E-02 5,70E-02 8.43E-02 1836.06 99.20 -3.79E-02 5.70E-02 + ~-94 702.63 100.00 l.45E-02 7.02E-02 7.02E-02 871.10 100. 00 6.14E-02 8.23E- 02 + 1-131 284.30 6.06 -1.91E-01 1.00E-01 1.27E+00 364.48 81.20 3.95E-02 1. 00E-01 636.97 7.27 4.28E-01 1. 27E+00 + CS- 134 604.70 97.60 -7,94E-02 8.8'JE-02 8.87E-02 795.84 85.40 8.26E-02 9 . 89E-02 + CS-137 661. 65 85.12 5.60E-02 9,57E-02 9.57E-02 + CE-144 80.12 1.36 -2,44E+00 4.73E-01 6.21E+OO 133.51 11.09 2,6SE-01 4.73E-01
9/24/2019 11:24:41AM Page 6 of6 Analysl a Report for L2-011-101-FQGS-009-SS LZ-011-101 Nuclide Enetgy Yleld{%) AcrMty NucltdeMDA LIM.IIIDA Name (pCllgrem.) (pCVgrams) (pCl/gralns} (lreV)
+ EU-152 121.78 28.40 -8.97E-02 l.79E-Ol 1. 79E-01 344.28 26.60 3.43E-03 2.39E-01 1408.00 20.74 -3.lBE-02 3.77E-Ol + EU-154 123.07 40.40 -3.6BE-02 1.26E-Ol 1.26E-Ol 723.30 19.70 2.SBE-01 4.0SE-01 1274.51 35.50 -l.49E-Ol 2.63E- 1
+ EU-155 86.54 32.80 -6.64E-02 2~14E-01 2.14E-Ol 105.31 21.80 -1. 92E-Ol 2. 47E-Ol. + BI-214 609.31
- 46.30 1. 74E-Ol 1.21E-Ol l.21E-Ol 1120.29 15.10 3.16E-Ol 7.25E-Ol 1238 .11 5.94 -1.0SE-Ol l.97E+OO 1377.67 4.11 6.27E-01 l.90E+OO 1407.98 2.48 -2.66E-Ol 3.15E+OO 1509.19 2.19 2.65E-Ol 2.85E+OO 1764 .49 15.80 3.78E-Ol 5. 75E-Ol *.
+ PB-214 71.11
- 10.70 l.OSE+OO 1. 60E-01 6.96E-Ol 295.21
- 19.20 2.lBE-01 1. 79E-0l 351. 92
- 37.20 2.lOE-01 l.60E-01
+ PA-228 89.95 22.00 5.85E+OO 4.0SE+O0 6.74E+OO 93.35 35.00 2.16E+OO 4.05E+OO 105 .00 16.30 -5,96E-Ol 7.18E+00 12 9. 22 2.97 1.38E+Ol 3.69E+Ol 338.32 5.30 1.218+01 2.3'7E+Ol 463.00 13.80 -8.54E+OO 9.15E+OC 9il.23 16.70 l.97E+01 1. 47E+0l + AM-241 59.54 36.30 6.51E-02 3.67E-01 3.67E-:01 + CM-243 103.76 23.00 -l.13E-02 2.41E-Ol 2.41E-01 228 .18 10, 60. *5.22E-02 -4.96E..;.01 277.60 14.00 -9,86E-02 3. 95E-01
+ = Nudide identffled during the nuclide identification * = Energy llne found In lhe spectrum > = MDA value not calculated @
- Halt-life too short 10 be able to perfonn the decay correction
? = CAUTION: MDA value Is fnconsisler,t with Cunte MDA at 95% confidence lewl
9124/2019 4:04:29PM Page 1 of6 __.fApex-Gamma Analysis Report for L2-011-101-FSGS-009-SS (SPLIT) L2-011-101 GAMMA SPECTRUM ANALYSIS Sample lderiific:atian : L2-011-101-FSG~9-SS (SPLIT) Sample Deecrlptlon : l..2..()11-101 Sample Type : 500 ml Marinelli Unit
&wnplePolrt Sample Slza : 7.318E+02 grams Faclllty : Dalrytend_NPP Sampl& Taken Ori ; 9m>r.2019 9;45:00AM Acquiaiticn Started : 9/24/2019 3:34:10PM Procedure : 500ml Mamell Operatcr : Mnlnlatrator Detector Name : HOTLAB Geometry : 500ml MaltnelH L!Yellme : 1800.0 seconds Raia! l1me : 18D5.1 secomls Dead Tima : 0.29%
Peak Lccrlle Threehclld : 3.00 Peak Locate Range {In channels) : 100-4098 Peak.Area Range (In channels) ; 100-4098 ldantlflcatian Ef"Kll'gy Toleraruie : 1.000 k~V Energy Gallbratlon Used Done On . : 71812014 Efficiency Calbratlon Ueed DQne On : 71812014 E1llclancy Calibration Deecription Sanple Ni.mbar : 7496 PEAK ANALYSIS REPORT Paek Analysis P&rfurmed on : 9/2412019 4;04:19PM Peek Analy8ia From Chmnel : 100 Peak Analysis To Channel : .4Q96
9124/2019 4:04:2aPM Pagel of6 Analysl8 Report for L2-011*101.fSGS-009-SS (SPLIT) 1.2-011*101 f'eal( Enerfly ROI ROI Pale Net Peek NetAtea Continuum FWHM No. {keV) start end Centroid A,u Uncertainty eounes (keV) M 1 14.12 145 - 162 149.98 6.39E+Ol 27.01 4.57E+02 1.06 m 2 17.16 145 - 162 154.87 9.18E+Ol 29.17 4.04E+02 1.07 F 3 238.37 471 - 485 477.23 2.69E+02 39.13 3.18E+02 1.93 F 4 295.31 585 - 596 591.07 5.16E+01 18.45 1.75E+02 0.80 F 5 338.16 671 - 682 676. 76 5.S0E+0l 22.32 1.65E+02 1.83 F 6 351. 97 699 - 712 704. 3.6 1.36E+02 27~50 1.43E+02 1.98 F 7 510.29 1014 - 1028 1020. 95 4.49E+Ol 10;10 1.13E+02 2.00 F 8 583.00 1161- 1175 1166.35 7.52E+Ol 20.91 7.85E+Ol 2.20 F 9 608.96 1212 - 1223 1218.25 6.SOE+Ol 21.04 9.00E+Ol 2.07 F 10 910.71 1815 - 1829 1821.67 4.77E+Ol 15.80 3.00E+Ol 2.18 F 11 968.50 1932 - 1942 1937.22 2.22E+Ol 12.63 3.85E+01 1. 71 F 12 1460.54 2913 - 2930 2921.20 3.10E+02 35.71 1. 88E+Ol 2.81 M= First peak In a multiplet region m = other peak In e muhlplet region F ;;: Fitted singlet Errol's quoted at 2.000slgma BACKGROUND SUBTRACT REPORT PeakAnalytsis Performed on : 912"'2019 4:04:19PM Env. Background Flle : C:\Canberra\Apex\Root\Dai~nd_NPP\Deta\0000001364.CNF Peale Energy Orlglnal Otlg. Al'l!\8 Ambient Baclcgr. Subtracted SubfntCNd No. (ke\l) AnNI Uncertainty Baclcground Uncert Area Un~ M 1 74.72 6.39E+Ol 27.01 *6. 39E+0l 2.70E+01 m 2 77.16 9.18E+Ol 29.17 9.18E+Ol 2.92E+Ol F 3 238.37 2.69E+02 39.13 2.69E+02 3.91E+01 F 4 295.31 5.16E+Ol 18.45 5.16E+01 1.84E+Ol F 5 338.16 5.* SOE+Ol 22.32 5.SOE+Ol 2.23E+Ol F 6 351.97 1.36E+02 27.50 4.18E+Ol 1.86E+Ol 9.40E+Ol 3.32E+Ol F 7 510.29 4.49E+Ol 18.70 4.49E+Ol 1.87E+Ol F 8 583.00 7.52:E+Ol 20.91 7.52E+Ol 2.09E+Ol F 9 608.96 6.SOE+Ol 21.04 2.06E+Ol 1.21E+01 4.44E+Ol 2.43E+0l F 10 910.71 4.77E+Ol 15.80 4.77E+Ol l.58E+Ol F 11 968.50 2.22E+Ol 12.63 2.22E+Ol 1.26E+Ol F 12 1460.54 3.10E+02 35.71 2.82E+01 8.57E+OO 2.82E+02 3.67E+Ol
9124/2019 4:04:29PM Anatyeis Report for L2-011-101-FSGS-O0~S (SPLIT) L2-011-101 M = Firat peet in a multlplet rvgion m = Other peak in a multipll!lt region F = Fitted efnglet Em:n quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Uud : C:\Canberra\Ape'll\Rool\Dfiryland_NPP\Llbrary\HOTLAB.NLB IDENTIFfED NUCLIDE$ Nuclide Id Energy Yleld(3/4) Actmt.y Activity Name Confidence (keV) (pCVgrams) Uneetf.linty K-40 0.99 1460.75
- 10. 67 8.40E+OO l.19E+00 PB-212 0 .99 77 .11
- 17.50 3.53E-01 l. 14E-0l 238.63
- 44.60 3.79E-0l 5.8SE-02 BI-214 0.34 609.31
- 46.30 l.40E-Ol 7. 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 PB-214 0.99 77.11
- 10 .70 5.77E-Ol 1.87E-Ol 295 .21
- 19.20 2.02E-Ol 7.28E-02
~51.92
- 37.20 2.22E-01 7.92E-02 AC-228 0.57 209.28 4.40 338.32
- ll .4O 4.09E-01 l.67E-0l 794.70 4.60 911.60
- 27.70 3.61E-Ol l.21E-Ol 964.60 5.20 969.11
- 16.60 2.96E-Ol 1. 69E-01
* =Energy line b.l'ld In 1:he epednlm.
* ,. ManuaHy added nudide.
? = Mariually edited nudlde.
G
- Energy line not used Jot Wefghted Mean Activity Energy Tolerance : 1.000 keV Nucllde confidence Index 1tnshokl = 0.30 Errors quoted at 2.000slgma
9/24/2019 4:04:29PM Page4of6 Analysis Report for L2-D11-101-FSG~09-SS (SPLIT) L2-011-101 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wtmean Wtmean Comments Name
- Id Activtty Actlvtty Confidence Uncertlllnt:y (pCUgramsJ K-40 0 .993 8.40E+OO 1.19E+OO PB-212 0 .993 3.49E-01 5.25E-02 BI-214 0 .340 1.40E-01 7.68E-02 PB-214 0 .999 l.96E-01 5.19E-02 AC-228 0 .570 3 . 57E-01 8.47E-02
? = nualde Is part of an undetennlned solution X = nudlde rejected by the lntetfemnce analysis CD = nucllde c;:cntalns energy ~s not used In Weighted Mean Acltvtly Erron quoted et 2.000aigma
9/2412019 4:04:29PM Page S of6 Analysis Report for L2-011-1D1-FSGS-009-SS (SPLIT) L2-011-101 UNIDENTIFIED PEAKS Peak locate Performed on : 9/2412019 4:04:19PM Peak Lccale Fmm Cllannal : 100 Peek Lccete To ct,annel : 4096 PNlcCPSf") Peak '1blel9nce l'NkNo. Energy(nV) Peak Size (CPS} Uncertainty 1>>>* Nuclide M 1 74.72 3.55008E-02 21.14 F 7 510.29 2.49481E-02 20.82 F 8 583.00 4.17731E-02 13.90 M
- Fnt peak In e multiplet region m "" Other peak in a multiplaC region F
- Fitted alnf;llet Errans quolBd at 2.000sigrns NUCLIDE MDA REPORT Nuclide Ubraty Used : C:\Carbena\Apex\Rilot\Oo)'land_NPPtl..lbra~OllAB.NLB Nuclide EIN/fflY VJald"'J At:tlvlty Nuallde IIDA LlneMDA N*me (pCVgnuns) (pCVg,amsJ (pCVgrams)
(lmV) + K-40 1460.75
- 10. 67 8.40E+00 9.46E-01 9.46E-01
+ AR-41 1293.64 99.16 1.47E+15 5.87E+15 5 .87E+l *5 + CO-60 1173.22 100.00 2.87E-03 7.77E-02 1.O6E-01 1332. 49 100.00 -4.41E-03 7 .77E-02 + KR-85 513,99 0.43 B.41E+OO 1. 75E+Ol l.75E+Ol + Y-88 898.04 93. 70 l.30E-02 7.50E-02 9.0lE-02 1836.06 99.20 -4,73E-03 7.SOE-02 + NB-94 702.63 100. 00 3.17E- 02 7.37E-02 7.40E-02 871.10 100. 00 -6.74E-03 7 .37E-02 + I-131 284.30 6.06 -3.96E-02 9.59E-02 1.32E+OO 364.48 81.20 -7.99E-02 9.59E-02 636.97 7 . 27 l.3'7E+00 1 .42E+OO + CS-134 604.70 97.60 7,30E-02 7.71E-02 8.74E-02 795.84 85.40 -1.04E-Ol 7.71E-02
912412019 4:04:29PM Page 6 of6 Analysis Report for L2-01M 01-FSGS-000-SS (SPLIT) l2*011-101 Nuclide Energy 'lfeld(%) Acflvlty Nuclld.eMDA IJneMOA Milne (pCVgrams) (pCl/gnlms) (pCl/grem8J (*VJ + CS-137 661.65 85.12 1.21£-01 1,00E-01 1.00E-01 + CE-144 80 .12 1.36 -2.04E+OO 4.81E-Ol 6.lOE+OO 133.51 11.09 3.38E-Ol 4.SlE-01 + EU-152 121.78 28.40 -6.80E-02 l.76E-Ol 1.76E-Ol 344.28 26.60 -1.62E-01 2.43E-Ol 1408.00 20.74 -6.68E-02 3.08E-Ol + EU-154 123.07... 40.40 5,16E-03 l.25E-01 1.25E-Ol 723.30 19.70 3.70E-Ol 4.18E-Ol 1274.51 35.50 5.98E-02 2.59E-Ol + EU-155 86.54 32.80 -1.89E-01 2.04E-Ol 2.04E-Ol 105.31 21.80 -1.09E-02 2.38E-Ol + BI-214 609.31
- 46.30 1.40E-01 l,44E-Ol l.44E-01 1120.29 15.10 3.07E-Ol 7.09E-01 1238.11 5.94 2.03E-02 1.92E+OO 1377,67 4.11 -4 .59E-Ol 1.84E+00 1407.98 2.48 -5 .-59£-01 2.57E+OO 1509.19 2.19 5,30E-01 3,51E+OO 1764.49 15.80 3.69E-01 5.54E-Ol
+ PB-214 77.11
- 10.70 5.77E-01 1. 48E-Ol 4.33E-Ol 295.21
- 19.20 2.02E-Ol 2,0SE-01 351.92
- 37.20 2.22E-01 1. 48E-01
+ PA-228 89.95 22.00 7.70E+OO 4.40E+OO 7.53E+OO 93.35 35.00 l.66E+OO 4.40E+OO 105.00 16.30 -3.0SE+OO 7.89E+OO 129.22 2.97 -5.43E-01 4,31E+Ol 338.32 ,5.30 1.90E+Ol 2.95E+Ol 463.00 13.80 l.20E+Ol 1.11E+Ol 911.23 16.70 6.60E+OO 1.SOE+Ol + AM_;.241 59.54 36.30 l.SOE-01 3.82E-01 3.82E-01 + CM-243 103.76 23.00 -9.27E-02 2.27E-Ol 2.27E-01 228.18 10.60 3.l.7E-Ol 4.90E-01 277.60 14.00 -7 .66E-02 4.08E-01
= Nudfda Identified during the nuclide identlflcaUon 1:
=Energy liie found in 1he spectrum
> ;;: MDA vak.te net calculated
@ = Half-life too short to be able to perform the decay ccnedlon
? = CAUTION: MDA value is inconsistent YAth Qime MDA at 95% confidence level
12/8/2017 11 :04:57AM Page 1 of6 Jlt'Apex-Gamma Analysis Report for L2-SUB-WRS-ASGS-01A-SB 12/4/17 GAMMA SPECTRUM ANALYS/S
/
Sample Identification : L2-SUB-WRS-ASGS-01A-SB Sample Description : 12/4/17 Sample Type : 500 ml Marinelli Unit Sample Point
. /
Sample Size : 6.858E+02 grams Facility : Dairyland_NPP Sample Taken On : 12/4/2017 1:07:00PM ./ Acquisition Started : 12/8/2017 10:04:34AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli / Live Time : 3600.0 seconds Real Time : 3611.7 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 : 3673 PEAK ANALYSIS REPORT Peak Analysis Performed on : 12/8/2017 11:04:48AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/8/2017 11:04:57AM Page 2 of6 Analysis Report for L2-SUB-WRS-ASGS-01 A-SB 12/4/17 Peak Energy ROI ROI Peal< Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 76 . 83 147 - 160 154.21 2.48E+02 53.43 l. 7 3E+ 03 1.35 F 2 18 6 . 06 369 - 377 372.61 7.lOE+Ol 37.61 6.56E+02 1.53 F 3 238 .44 469 - 481 477.35 4 .20E+02 52.88 8.09Et02 1.17 F 4 294 .98 586 - 596 590 . 41 l .38E +02 31 . 92 3.81E +02 1.24 F 5 338 . 09 668 - 680 676.60 l.22E+02 30.81 3.32E+ 02 1. 67 F 6 351. 66 695 - 7 12 703.7 5 3.00E+02 40.10 3.87£+ 02 1. 66 F 7 510.26 1013 - 1026 1 020.89 9.lOE+O l 28.46 2.28E+ 02 2.58 F 8 582.89 1158 - 1171 1166. 12 1.34E+02 28 . 01 1.68E+ 02 1. 7 5 F 9 609.00 12 09 - 1223 1218 . 33 1 .98E+02 32 . 64 2.02E+ 02 1. 65 F 10 661.46 1 318 - 1329 1323.24 1 .76E+02 30.20 l.22E+ 02 1. 7 8 F 11 726.82 1 450 - 1457 1453.93 3.03E+O l 16. 00 8.96E+ Ol 1.12 F 12 910 . 93 1817 - 1827 1822 . 10 l .1 4E+02 24. 64 8.16E+Ol 1. 74 F 13 968.63 1932 - 1945 1937 .49 5.95E+01 19.65 l.03E+02 1. 7 1 F 14 1119. 78 2234 - 2248 2239 . 75 2.59E+Ol 16.03 1. 35E+ 02 1. 56 F 15 1331.98 2659 - 2669 2664.10 2 .0lE+O l 11. 47 3 . 36E+ Ol 1. 48 F 16 1460 . 31 2913 - 2928 2920.73 6 . 53E+02 53.04 5 . 50E+Ol 2 . 29 F 17 1763. 89 3 5 21- 3535 3527.86 4.24E+01 14.08 7 . SOE+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 PeakAnalysis Performed on : 12/8/2017 11:04:48AM 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 76.83 2 . 48E+02 53.43 2.48E+02 5.34E+Ol F 2 186.06 7.lOE+ Ol 37.61 7 . lOE+ Ol 3.76E+ Ol F 3 238.44 4.20E+0 2 52.88 4.20E+ 02 5.29E+Ol F 4 294.98 1. 38E+ 02 31. 92 l .38E+ 02 3 .1 9E+O l F 5 338.09 1.22E+02 30 .8 1 1 .22E+02 3 . 08E+Ol F 6 351 . 66 3.00E +02 40. 1 0 8.36E+Ol 3.72E+O l 2.16E+02 5.47E+Ol F 7 510.26 9.lOE+Ol 28.46 9 .lOE+O l 2.85E+ Ol F 8 582.89 1. 34E+02 28.01 1 . 34E+02 2.80E+O l F 9 609.00 l.98E +02 32. 64 4 . 1 2E+O l 2.42E +Ol 1 .5 7E+02 4.06E+Ol F 10 661. 4 6 l.76E+02 30.20 6.61 E+Ol 2 . 54E +Ol l . 09E+02 3.95E+Ol F 11 726 . 82 3 .03E+Ol 16.00 3.03E+Ol 1 .60E+O l F 12 91 0 . 93 1. 14E+02 24 . 64 1. 14E+02 2 . 46E+O l
12/8/2017 11:04:57AM Page 3 of6 Analysis Report for L2-SUB-WRS-ASGS-01 A-SB 12/4/17 Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 13 968 . 63 5 . 95E+Ol 19 . 65 5.95 E+Ol 1 . 97E+Ol F 14 111 9.78 2 . 59E +Ol 16. 03 2.59E+O l 1 . 60E+O l F 15 1331.98 2 .0l E+Ol 11. 47 2 . 0lE+Ol 1. 15E +Ol F 16 14 60.31 6 . 53E+02 53.04 5.63E+O l 1. 71E+Ol 5.96E+02 5 . 57E+O l F 17 1763 . 89 4 . 24E+Ol 1 4 . 08 1 .52E+O l 9 . 80E+OO 2 .72E+Ol l . 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\Dairyland_ NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(3/4) Activity Activity Name Confidence (keV) ,(pCilgrams) Uncertainty K- 40 0.96 1460.75
- 10.67 9 . 4 7E+OO 1. 03E+OO CS-13 7 0 . 99 661 . 65
- 85 . 12 1. 08E- 0 1 3 . 93E- 02 BI-2 1 2 0.59 7 27 .17
- 11. 80 2 . 35E-0 1 l.24E-O l 785 . 42 2.00 1620 . 56 2 . 75 PB - 212 0 . 99 77 .11
- 17 . 50 S . 1 3E- 01 1.15E- 01 238.63
- 4 4 .60 3. 1 6E-Ol 4.30E-02 BI - 214 0.76 609 . 31
- 4 6 . 30 2 . 64 E- 0 1 6 . 98E-02 1120. 29
- 15 . 10 2 . 31 E-01 1.43E- 01 1238.11 5 . 94 1377.67 4 . 11 1 407.98 2.48 1 509 .1 9 2.19 1764 . 49
- 15.80 3.42E-01 2 . 1 7E-01 PB-2 14 0 . 99 77 . 11
- 10.70 8.39E- 01 1 . 88E- 01 295 . 2 1
- 19.20 2.87E-Ol 6.80E-02 351 . 92
- 37.20 2. 72E- 01 7.0lE-02 RA- 226 0.99 186.21
- 3.28 6 . llE- 01 3 . 25E - 01 AC-228 0 . 59 209 .2 8 4.40 338 . 32
- 11 . 4 0 4 . 83E-01 1. 24£- 01 794. 7 0 4. 60 911.60
- 27.70 4.60E- 01 1.02E-01 964.60 5.20 969 . 11
- 16.60 4.24E - 01 1.4 1E-01
12/8/2017 11 :04:57AM Page4 of6 Analysis Report for L2-SUB-WRS-ASGS-01A-SB 12/4/17
* = 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 . 969 9.47E+OO 1.03E+OO
/ CS - 137 0 . 994 1.0BE-0 1 3 .93E-02
. BI-2 1 2 0 . 591 2 . 3SE-01 1.24E-01 PB- 212 0 .993 3 . 1 9E-01 4.04E-02 BI-214 0.764 2.64E-01 6.03E-02 PB-2 14 0 .990 2 . 82E-0 1 4.74E-02 RA-226 0 .996 6 . llE- 01 3.25E-01 AC - 228 0 . 595 4.59E-01 6.87E-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
12/8/2017 11 :04:57AM Page 5 of6 Analysis Report for l2-SUB-WRS-ASGS-01A-SB 12/4/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/8/2017 11 :04:48AM 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 7 510.26 2.52735E-02 1 5.64 F 8 582.89 3 . 73133E- 02 10.43 F 15 1331.98 S.57803E-03 28 . 56 Tol. M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairyland_NPP\library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCllgrams) (pCilgrams) (keV) + K- 40 1 460 . 75
- 10 . 67 9.47E+00 8 .03E-01 8 . 03E-01
+ AR-41 12 93.64 99 . 16 1.07E+14 1 .7 2E+l 4 1.72E+14 + CO-60 1173.22 100 . 00 8.33E-03 7 . 27E -0 2 8 .38E-02 1332. 49 100 . 00 6 .1 6E-02 7.27£-02 + KR-85 513.99 0.43 -6 . l0E+00 1.33E+0l 1. 33E+ 0 l + Y-88 898 .0 4 93 . 70 -3.5 1E-02 4.39E-02 6.60E-02 1836.06 99 .2 0 1.15E-02 4 . 398-02 + NB-94 702.63 100 . 00 2 . 80E-02 5 . 17£-02 5.17E - 02 871.10 100.00 7 .98E-03 6. 3 4E -02 + I-131 284.30 6.06 6 . 27E-02 7 . 09E-02 9.64E - 01 364.4 8 81. 20 - 3.13E - 03 7.09E- 02 636 .97 7.27 5.03E-01 1.12E+00 + CS-134 604.70 97 . 60 l.41E-01 6 . 84E-02 7.46E-02 795. 84 85.40 8.54E- 03 6 . 84E- 02 + CS - 137 661. 65
- 85. 1 2 1. 0BE-01 6.59E-02 6.59E-0 2
12/8/2017 11:04:57AM Page 6 of6 Analysis Report for L2-SUB-WRS-ASGS-01 A-SB 12/4/17 Nuclide Energy Yield(%) Activity Nuclide MDA LlneMDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV) + CE-144 80.12 1. 36 -1. 72E+OO 3 . 62E-Ol 4.90E+OO 133 . 51 11.09 9 . 81E-02 3.62E-01 t EU-152 121.78 28.40 -4 . 40E-02 l .37E-O l 1. 37E- 01 244.69 7 .49 - 1.80E+OO 6.95E-01 964.00 14.44 -7 .6 5E-02 5 . 79E- Ol 1408.00 20.74 8 . 75E-02 3.16E-Ol + EU - 154 123 . 07 40.4 0 4.64E-03 9.69E-02 9.69E-02 247.94 6.60 -3 . Sl E+ OO 6 . 55E - 01 723.30 1 9 .70 1 . 65E-01 3.0SE- 01 873.20 11.50 l.99E - 01 5.36£-0 1 1004.76 17.90 l.75E-01 3.78E-01 1274.51 35.50 l . 31E-03 1.98£-01 + EU-155 86.54 32.80 -1.27E-01 l.63E-0 1 1.63E-01 1 05 .31 21. 80 -9 . 38E-0 2 1.85E- Ol + BI - 214 609.31
- 46.30 2.64E-01 1 . 25E-01 1.25E-Ol 1120. 29
- 1 5 .10 2.31E-0 1 4.34E - 01 1 238 .11 5.94 4.9 5E-0 1 l . 58E +OO 1 377.67 4.11 - l.07E-0 1 l.41E+OO 14 07.98 2 .48 7 . 3 1 E-01 2.64E+OO 1509 .19 2 .19 2.81 E+OO 2.56E+O O 1764.49 *-A* 15.80 3.42E - 01 3.26E-01
+ PB-214 77.11 10.70 8.39E-01 1 . 38E-01 5 . 53E- 01 295.21
- 19.20 2.8 7E-01 1. 53E- 01 351.92
- 37.20 2.72£-01 1. 38E-01
+ PA-228 89.95 22.00 5.96E+ OO 2 . 63E+ OO 4 . 45E+O O 93.35 35.00 1.97E+ OO 2.63E+OO 105.00 16.30 -1.25E+OO 4.72E+OO 129.22 2 .97 -8.33E+OO 2. 52E+Ol 338.32 5.30 2.26E+Ol l.76E+ Ol 463.00 13. 80 2.44E +OO 6.97E+OO 911 .23 16 .70 1. 54E +Ol 9.66E+OO + AM-2 41 59.54 36.30 7.62E-03 2 . 89E -0 1 2.89E-01 + CM-243 1 03.76 23.00 3 . 58E-03 1.79E-01 1. 79E -01 228.18 10.60 3. 71E-02 3.71E-O l 277.60 14.00 1 . 61£-01 3.16E-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
12/8/2017 12:08:26PM Page I of 7 ~JtApex-Gamma Analysis Report for l2-SUB-WRS-ASGS-02A-SB 12/4/17 GAMMA SPECTRUM ANALYSIS Sample Identification : l2-SUB-WRS-ASGS-02A-SB / Sample Description : 12/4/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size Facility 8.773E+02 grams
- Dairyland_NPP I
Sample Taken On : 12/4/2017 2:50:00PM Acquisition Started : 12/8/2017 11 :08:03AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB / Geometry : 500ml Marinelli live Time
- 3600.0 sec~~:;;
Real Time : 3611.2 sec/ 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 : 3674 PEAK ANALYSIS REPORT Peak Analysis Performed on 12/8/2017 12:08:17PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/8/2017 12:08:26PM Page 2 of7 Analysis Report for L2-SUB-WRS-ASGS-02A-SB 12/4/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 76.75 147 - 1 58 154 . 04 1.14E+02 45 .87 l.OSE+03 1. 82 M 2 238 . 5 4 473 - 489 477.56 2.07E+02 37.09 3.33E+02 1. 43 m 3 241.81 473 - 489 484.08 6.26E+Ol 25.67 3 . 70E+02 1. 43 F 4 295.15 587 - 595 590 .7 5 B.19E+Ol 25.47 2 . 44E+ 02 1.10 M 5 327.86 653 - 685 656 . 15 2 . 41 E+Ol 16.55 1.45E+02 1.06 m 6 338.14 653 - 685 676 . 71 3 . 96E+Ol 23 .29 1.32E+ 02 1. 07 F 7 35 1 .8 4 697 - 709 70 4 . 11 2 . 20E+ 02 34 .01 1. 88E+02 1. 7 5 F 8 583.30 11 62 - 1173 1166.94 4 . 88E+Ol 18.94 l .16E+02 1. 51 F 9 608.8 7 1 214 - 1224 1218.08 1 . 16E+02 25.79 1. 29E+02 1.54 F 10 910.68 1816 - 1827 1821 .61 3.48E+Ol 16 . 29 7.27E+Ol 1.85 F 11 1460.17 2914 - 2929 2920 . 46 4 .29E+02 42 . 1 2 2.73E+Ol 2.43 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 : 12/8/2017 12:08:17PM 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 76.75 1. 14E +02 45 . 87 1.14E+02 4.59E +01 M 2 238.54 2.07E+02 37 . 09 2.07E+02 3.71E+ 01 m 3 241.81 6.26E+Ol 25 .6 7 6.26E+Ol 2 . 57 E+Ol F 4 295.15 8.19E+Ol 25.47 8 . 19E+Ol 2.55E+Ol M 5 327.86 2 . 41E+Ol 16.55 2.41E+Ol 1.66E+O l m 6 338.14 3.96E+Ol 23.29 3.96E+Ol 2 . 33E+Ol F 7 351. 84 2.20E+02 34 . 01 8.36E+Ol 3.72E+ Ol l. 37E+02 5. 04E+Ol F 8 583 . 30 4.88E+Ol 18.94 4.88E+Ol 1. 89E+Ol F 9 608.87 1 . 16E+02 25.79 4. 12E+Ol 2.42E+Ol 7.52E+Ol 3.54E+Ol F 10 910.68 3.48E+Ol 16. 29 3.48E+Ol 1. 63E+Ol F 11 1460.17 4 .29E+02 42.12 5.63E+01 1 . 71E+Ol 3.73E+02 4 . 55E+Ol M = First peak in a multiplet region m == Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma
12/8/2017 12:08:26PM Page 3 of7 Analysis Report for L2-SUB-WRS-ASGS-02A-SB 12/4/17 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) (pCilgrams) Uncertainty K- 40 0 . 94 14 60.75
- 1 0.67 4.63E+ OO 6.20E-01 PB-2 1 2 0.99 77 .11
- 17.50 l.85E-0 1 7 . 52E-02 238 . 63
- 44.60 1. 22E-01 2.27E-02 BI - 2 14 0.33 609. 3 1
- 46.30 9.86E-02 4.67E-02 1120. 29 15.1 0 1238.11 5 . 94 1377 . 67 4 . 11 1407.98 2.48 1509 . 19 2. 1 9 1764.49 15.80 PB-214 0 . 99 77 .11
- 1 0. 70 3 .02E-Ol 1. 23E-01 295.21
- 19.20 1. 33E-0 1 4 .20E-02 351. 92
- 37.20 1. 35E - 0 1 5.0lE-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 0.94 8 4.63E+OO 6 . 20E-01
12/8/2017 12:08:26PM Page4 of7 Analysis Report for L2-SUB-WRS-ASGS-02A-SB 12/4/17 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) PB-2 1 2 0.993 l.20E-01 2. 1 8E-02 BI - 214 0.334 9 . 86E-02 4.67E-02 PB- 21 4 0.996 1 . 32E-01 3. 1 2E-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
12/8/2017 12:08:26PM Page 5 of7 Analysis Report for L2-SUB-WRS-ASGS-02A-SB 12/4/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/8/2017 12:08:17PM 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 3 241 . 8 1 1.73803£- 02 2 0. 51 ~\tfl
'~~
M 5 327.86 6.69866E-03 34.32 ~ m 6 338 . 14 1.09988£-02 29 .41 Tol. AC-228 PA- 228 F 8 583.30 1.35596E-02 19 . 40 _s* 'L0b F 10 910.68 9.68033E-03 23 .37 Tol. AC-,228 / PA-228 M = First peak in a multiplet region
'}~7 }~ \~~
m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA Line MDA Name (pCl/grams) (pCilgrams) (pCilgrams) (keV) + K- 40 1460.75
- 10 . 67 4.63E+OO 5 . 63E-01 5.63E-01
+ AR- 41 1293.64 99 . 16 -4. 90E+l3 8.91E+l 3 8 . 9 1E+ l 3 + ./co-60 1173.22 1 00 . 00 7.75E- 02 5 . 17E-02 6 . 42E-02 1332.49 100.00 4 . 0SE-02 5. 1 7E-02 + KR-85 513. 99 0. 43 4.42E+OO 8.48E +OO 8.48E+OO
12/8/2017 12:08:26PM Page 6 of? Analysts Report for L2-SUB-WRS-ASGS-02A-SB 12/4/17 Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCilgrams) (keV) + Y-88 898 . 0 4 93 .7 0 2. 69E - 02 3 . 53E- 02 4 . 61E-02 1836. 06 99 . 20 - 8 .1 8E-03 3 . 53E- 02 + NB- 94 702.63 1 00.00 7 . 57 E- 03 3.63E- 02 3 . 63E-02 8 71.1 0 100 . 00 -5 . 09E -0 2 3 . 83E - 02 + I-131 284.30 6 . 06 -5 .lOE -02 4 . 92E-02 6.70E - Ol 364 .4 8 81. 20 2 . 56E-02 4 . 92E - 02 636.97 7.27 4.SOE-01 6 . 60E - Ol + CS-1 34 604.70 97 . 60 - 5 . 87E-02 4 . 80E-02 4 . 80E - 02 795.8 4 85.40 -1 .42E -02 4.81E - 02 + / CS-137 661.65 85 .12 6 . 92E-02 5 . 19E-02 5 .19E- 02 + CE -144 80 . 12 1. 36 - 1 . 14E+OO 2. 53 E-01 3.12E+OO 133 . 51 11.09 2 . 53E - 02 2 . 53E-01 + / EU-152 121.78 28 . 40 - 5 . 45E-02 9.29E-02 9 . 29E-02 244.69 7. 49 8. 4 7E-02 4 . 41E-O l 964.00 14 . 44 3.97E-0 1 3. 46E- 01 1408. 00 20 . 7 4 6 . 67E-02 l. 92E- 01 + /EU-15 4 123. 07 40.40 5 . 33E- 03 6.6 3E-0 2 6 . 63E-02 247 . 94 6.60 8 .98E- 02 4.66E- 01 723.3 0 19.70 -2. 79E-02 l.97E-01 873.2 0 11. 50 - 5 . 63E- 03 3.36E-01 1 00 4 . 76 17.90 2 . 0lE- 01 2.62E-01 127 4. 5 1 35.50 - 3 . 63E- 02 1. 35E-01 + EU- 1 55 86.54 32.80 l . 92E-02 l. l OE- 0 1 1.lOE-0 1 1 05.3 1 21. 80 3.82E-02 1. 33 E-01 + BI-214 609 . 31
- 4 6.30 9.86E- 02 8.42E-02 8 .42E - 02 112 0 . 29 1 5 . 10 1. 21E-0 1 3.74E-01 1238.11 5 . 94 1.28E+OO l. ll E+O O 1377 . 67 4 . 11 3 . 32E-0 1 9 .8 5E-01 1407.98 2 .4 8 5 . 58E-O l l . 61E+OO 1 509 . 19 2 . 19 6.62E-0 1 1.5 6E+O O 1 764.49 15 . 80 3 . lOE -01 3 . 05E-01
+ PB-214 77 .11
- 1 0 . 70 3 .0 2E -0 1 8.71E-02 3 .24 E-0 1 295 .2 1
- 1 9 . 20 1 .33E-01 9 .1 2E-02 351. 92
- 37 . 20 1 . 35E - 01 8. 7 1 E-02
+ PA- 228 89.95 22 . 00 2 . 77E+OO 1 .72E+OO 2.95E+OO 93 . 35 35 . 00 7 . 32E-01 1 . 72E+OO 105 . 00 16 . 30 2 .79E-01 3 . 31E+OO 129.22 2 . 97 - 9 . 53E +OO l . 69E+O l 338 . 32 5 . 30 - 8 . 44E - 01 1 . llE+Ol 46 3 .00 13 . 80 2 . 31E+OO 4.31E+O O 911. 23 16.70 4 . 20E +OO 5 . 79E+O O + /AM- 241 59.54 36 . 30 3 . 80E-02 2 . 0 lE- 01 2 .0 l E- 01 + CM- 243 103 . 76 2 3 .00 3 . 83E-02 1. 27E-01 1.27E-01 228 . 18 1 0. 60 l . 07E- 01 2.63E-01 277 . 60 14 .00 1. 2BE-01 2 . 14E-0 1
12/8/2017 12:08:26PM Page 7 of7 Analysis Report for L2-SUB-WRS-ASGS-02A-SB 12/4/17
+ = 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
12/8/2017 2:38:07PM Page 1 of7
~pex-Gamma Analysis Report for L2-SUB-WRS-ASGS-03A-SB 12/4/17 GAMMA SPECTRUM ANALYSJS Sample Identification : L2-SUB-WRS-ASGS-03A-SB Sample Description : 12/4/17 Sample Type : 500 ml Marinelli . /
Unit Sample Point Sample Size 8.361 E+02 grams Facility : Dairyland_NPP Sample Taken On : 12/4/2017 1:15:37PM Acquisition Started : 12/8/2017 1:37:44PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 3600.0 seconds Real Time : 3611.2 seconds Dead Time : 0.31 % Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 3676 PEAK ANALYSIS REPORT Peak Analysis Performed on : 12/8/2017 2:37:58PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/8/2017 2:38:07PM Page 2 of7 Analysis Report for L2-SUB-WRS-ASGS-03A-SB 12/4/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 77 . 15 151 - 1 61 154.85 8.00E+ Ol 35 . 7 8 1.05E+ 03 0.98 F 2 238 . 46 47 4 - 482 477.39 2.13E+ 02 38 . 93 4 .14E+02 1. 38 F 3 294.88 583 - 596 590.20 1 . 13E+ 02 31. 76 3. 4 7E+02 2 . 05 F 4 351.73 699 - 709 703.90 l .62E+ 02 31.02 1 . 98E+02 1. 54 F 5 510.21 1011 - 1028 1020.78 5.96E+O l 21.14 1 . 69E+02 2.00 F 6 570 . 90 1137 - 1146 1142. 1 5 2.65E+O l 13 . 71 5 . 38E+Ol 1. 41 F 7 582 . 72 11 58 - 1173 1165.79 7.19E+ Ol 21. 50 1 . 35E+ 02 1. 85 F 8 608.8 5 12 1 3 - 1227 1218.02 1 .25E+ 02 25.09 l . 0 5E+0 2 1. 63 F 9 910.61 1817 - 1827 182 1. 47 3.04E+ Ol 13.19 8 . 13E+ Ol 1. 26 F 10 968.44 1933 - 1942 1937 . 1 0 2.32E+Ol 12.84 5 . 23E+Ol 1.21 F 11 1119 . 40 2234 - 2244 2238 . 98 2 . 49E+Ol 13 .32 6 . 33E+Ol 1.25 F 12 1459 . 89 29 11 - 2929 2919.9 0 4 . 33E+02 42.28 2 . 96E+Ol 2 . 40 F 13 1763.19 3522 - 3531 3526 .44 l .88E+Ol 9.64 7.62E+OO 1.69 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 : 12/8/2017 2:37:58PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 77. 1 5 8 .0 0E+Ol 35.78 8.00E+Ol 3 . 58E+ 01 F 2 238 . 46 2 . 1 3E+02 38.93 2.13E+0 2 3.89E +Ol F 3 294.88 1. 1 3E+02 31.76 1. 13E+02 3.18E+Ol F 4 351.73 1.62E+02 31.02 8 . 36E+Ol 3.72E+Ol 7 . 82 E+O l 4.84E+Ol F 5 5 1 0 . 21 5 . 96E+Ol 21.14 5.96E+O l 2. llE+Ol F 6 570.90 2.65E+Ol 13.71 2.65E+O l 1 . 37E+Ol F 7 582 . 72 7.19E+ Ol 21. 50 7.19E+O l 2 . 15E+Ol F 8 608.85 1 . 25E+02 25 . 09 4. 1 2E+Ol 2 . 42E+Ol 8.35E+01 3 . 49E+Ol F 9 910.61 3.04E+Ol 13.19 3.04E+Ol 1.32E+Ol F 10 968.44 2.32E+O l 12.84 2.32E+Ol l.28E+Ol F 11 1119.40 2.49E+ 01 13.32 2. 49E+Ol 1. 33E+ Ol F 12 1459.89 4 .33E+02 42.28 5 . 63E+Ol l. 7 1 E+Ol 3.77E+02 4 . 56E+ 01 F 13 1763.19 1. 88E+01 9.64 l .8 8E+ Ol 9.64E+ OO
12/8/2017 2:38:07PM Page3 of7 Analysis Report for L2-SUB-WRS-ASGS-03A-SB 12/4/17 M = First peak in a multiplet region m = Other peak ln a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K-40 0 .8 8 14 60. 75
- 10.6 7 4 . 91E+ 00 6.5 4E-01 PB- 2 1 2 0 . 99 7 7 . 11
- 1 7 . 50 1. 3 5E-0 1 6.0 8E-0 2 238 . 63
- 44 . 60 l.3 1 E-0 1 2. 4 9£-0 2 BI - 2 1 4 0.5 4 609. 3 1
- 46 . 3 0 l.15 E-01 4.84 £ - 0 2 11 2 0. 2 9
- 15 .10 l. 8 2E- 0 1 9 . 77£- 02 1238 . 11 5.94 1377 . 67 4. 11 1407 . 98 2 .4 8 1509.1 9 2 .19 1 7 64. 4 9 1 5. 8 0 PB- 21 4 0 .9 9 7 7 .11
- 10 . 70 2 . 2 0£- 01 9 .95E-02 295.21
- 1 9 . 20 1. 93£ -01 5.Sl E-02 3 51 . 92
- 3 7. 20 8. 0 7E-0 2 5 .0 2£-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
12/8/2017 2:38:0?PM Page4 of7 Analysis Report for L2-SUB-WRS-ASGS-03A-SB 12/4/17 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) K-4 0 0 . 8 89 4. 91E+OO 6 . 5 4 E- 01 PB-212 0.997 1 .21E- 0 1 2 . 3 3E-02 BI-2 1 4 0 . 547 1. 2 8E- 01 4 . 34E- 02 PB - 214 0 . 992 1 . 1 8 E- 01 3 . 5 1E- 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
12/8/2017 2:38:07PM Page 5 of7 Analysis Report for L2-SUB-WRS-ASGS-03A-SB 12/4/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/8/2017 2:37:58PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 5 510 . 21 l. 65581E- 02 1 7.73 \\>~1....~ F 6 57 0. 90 7 . 37310E -0 3 25.82 pl~ F 7 582. 72 1.99724E- 02 14.95 F 9 9 1 0.61 8 . 45778£-03 21 . 66 Tol.
~'
AC-228
./
PA-228 F 10 968 . 44 6.44148£- 03 27. 68 Tol. AC-228/ F 13 1763 . 19 5 . 23141E - 03 25 .5 9 ()~~\~ M = First peak in a multiplet region r'n = 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\HOT LAB.NLB Nuclide Energy Yield{3/4) Activity Nuc/ideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV) + K-40 14 60.75
- 10.67 4.91E+00 6.12E- 0l 6 . 12E-01
+ AR-41 1293 . 64 99.16 - 1.73E+l3 4.48E+14 4.48E+l4 + CO-60 1173.22 100.00 -3.00E-02 5.36E-02 6.0 lE-02 1332 . 49 100 . 00 7 . 86E-02 5.36E- 02 + KR-85 513.99 0 . 43 -2.75E-0 1 9.24E+00 9 . 24E+00 + Y-88 898 . 04 93 . 70 -2.20E- 02 3 . 71E-02 4 . 77E - 02 183 6.06 99.20 -1 . 32 E- 02 3.71E-02 + NB- 94 702 . 63 100 . 00 -6. 45E-03 3.61E - 02 3 . 61E - 02 871.10 1 00.00 -4. 2 1E-0 2 4 . llE-02
12/8/2017 2:38:07PM Page 6 of7 Analysis Report for L2-SUB-WRS-ASGS-03A-SB 12/4/17 Nuclide Energy Yield(3/4) Activity NuclldeMDA LineMDA Name (pCilgrams) (pCi/grams) (pCilgrams) (keV) + I-131 284.30 6.06 5.56E-02 5. 06E-02 6.92E - 01 364 . 48 81.20 -1. 58E- 02 5.06E-02 636.9 7 7.27 4.60E- 01 6.86E-01 + CS-1 34 604 . 70 97.60 - 4.15E- 02 4.16E-02 4.84E-02 795 . 84 85 .4 0 - 3 . 86E- 02 4 . 16E-02 + CS - 137 6 61.65 85 . 12 8.SBE-02 5 .5 5E-02 5 . SSE-02 + CE-144 80 . 12 1.36 -7.60E- 0 1 2.60E -01 3.23 E+OO 133.51 11. 09 -1.17E- 01 2.60E-01 + EU-152 121. 78 28.40 8.15E-02 1.02E-01 1 .02E-01 244.69 7 . 49 -1.17E-01 4. 55E -0 1 964.00 1 4 . 44 2.27E-01 3 . 55E -0 1 1408.00 20 . 74 -2.67E-02 2 . 02E-01 + EU-154 123.07 40.4 0 -2 . 08E-02 7.04E-02 7 .04E-02 247 . 94 6 . 60 -6.43E-01 4 . 66E-Ol 723.30 19. 70 4 .63E-02 1 . 96E-01 873 . 20 11.50 -2 .0SE-0 1 3 . 60E-01 1004.76 1 7.90 7.29E-02 2. 7 6E-01 1274.51 35.50 3.97E-02 1. 54E-0 1 + EU- 155 86 . 54 32.80 -8 . 81E-02 l . 12E-01 1.12E-0 1 105.31 2 1. 80 -6.14 E-02 1. 38E-0 1 + BI-214 609 . 31
- 46 . 30 1.lSE -01 8. 79E-02 8.7 9E- 02 112 0.29
- 15.10 1 .82E -0 1 2 . 28E-01 123 8 . 11 5 .94 3 . 72E-01 1. llE+OO 1377 .6 7 4 .11 4.46E-01 1 . 1 2E+ OO 1 40 7 .98 2.48 -2.23E-01 1. 68E+ OO 1509 . 19 2.19 7.96E-0 1 1 . 76E+ OO 1764 . 49 15 .80 2.2 1E-01 3.20E - 01
+ PB-2 14 77 . 11
- 1 0.70 2 . 20E -01 9. OSE-02 3.31E-01 2 95.2 1
- 19 .20 1.93E- 0 1 1. 27E-01 351 . 92
- 37 . 20 8 . 07E- 02 9.0SE-02
+ PA-228 89.95 22 .00 l.19E+OO 2 . 09E+ OO 3.46E+OO 93 . 35 3 5 . 00 6.17E-01 2 . 09E+OO 1 05.00 1 6.30 -2.66E+OO 3 . 92E+OO 129 .2 2 2 . 97 l.02E+Ol 2.04 E+Ol 338.32 5 .30 l.95E +OO l . 2 6E+O l 463 . 00 13 .80 - 2 . 42 E+O O 5. 47E+O O 911 . 23 16 . 70 7.76E+OO 6 . 65E+OO + AM-241 59 . 54 36. 30 2.68E - 0 2 2.14E-01 2.14E- 01 + CM-243 1 03.76 23.00 -1.02E-0 1 1 .32E-01 l .3 2E-0 1 228 .18 1 0 .60 -1.15E-0 1 2.60E-01 27 7 .60 1 4 .00 - 5 .22E-03 2 . 2 0E-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
12/8/2017 2:38:0?PM Page 7 of7 Analysis Report for L2-SUB-WRS-ASGS-03A-SB 12/4/17
12/8/2017 3:43:33PM Page 1 of7
..!(Apex-Gamma Analysis Report for L2-SUB-WRS-ASGS-04A-SB 12/4/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-ASGS-04A-SB Sample Description 4 Sample Type ; ;~~ ;~Mari~ /
Unit Sample Point Sample Size 8.905E+02 grams . / Facility : Dairyland_NPP Sample Taken On : 12/4/2017 2:20:00PM Acquisition Started : 12/8/2017 2:43:09PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB / Geometry : 500ml Marinelli Live Time : 3600.0 seconds Real Time : 3611.5 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 : 3677 PEAK ANALYSIS REPORT Peak Analysis Performed on 12/8/2017 3:43:24PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/8/2017 3:43:33PM Page 2of7 Analysis Report for L2-SUB-WRS-ASGS-04A-SB 12/4/17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 76 . 1 5 147 - 161 152 .84 2.97E+02 66.63 1.49E+03 3 .8 9 F 2 186.19 365 - 37 7 372 .8 7 6.20E+O l 34 .41 8 .74 E+02 1. 30 F 3 238.40 459 - 485 477 . 27 4.15E+02 50.85 l.25E +03 1. 61 F 4 294.98 587 - 595 590.41 1.23E+02 30.88 3 .02E +02 1.28 F 5 338.16 671 - 685 676.75 8.91E+Ol 27 . 73 3.65E+ 02 1.55 F 6 351. 7 5 699 - 712 703.93 l .81E+02 33.60 3 . 5 4E +02 1.45 F 7 583.00 1161 - 1173 1166.33 1.25E+02 26.21 1.23E+02 1. 71 F 8 608.93 1210 - 1227 1218 . 19 1 . 72E+02 29. 47 1.64E+02 1. 73 F 9 859 . 9 1 1717 - 1 726 1720.08 2.16E+O l 8.31 6.63E +Ol 1. 31 F 10 910.40 1815 - 1829 1821.04 7. 45E+Ol 22.72 1.19E+02 2 .3 7 F 11 968.46 1930 - 1942 1937.14 5.93E+ Ol 19.81 9.62E+Ol 1. 86 F 12 1119.85 2235 - 2246 2239.89 2.95E+Ol 14 . 95 8.54£+01 1. 34 F 13 1460. 0 8 2911 - 2929 2920.27 7.70E+02 56.71 3.68E+ 01 2.45 F 14 1763.16 3521 - 3532 3526 . 38 2.58E+Ol 11. 49 1. 23E+ Ol 2.23 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 : 12/8/2017 3:43:24PM 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 76.15 2 .97E+0 2 66.63 2 . 97E+0 2 6 . 66E+O l F 2 186.19 6.20E+Ol 34.41 6.20E+Ol 3.44E+Ol F 3 238.40 4 . 15E+02 50.85 4.1 5E+02 5 . 08E +Ol F 4 294.98 l .23E+02 30.88 l .23E+02 3 . 09E +Ol F 5 338 . 16 8. 91E+Ol 27 .7 3 8.91E+Ol 2.77E+Ol F 6 351. 75 l.81E+02 33.60 8 . 36E+Ol 3 .7 2E +Ol 9.73E+Ol 5.0lE+Ol F 7 583.00 1.25E+02 26.21 l . 25E+02 2 .6 2E+Ol F 8 608 .9 3 l .72E+02 29. 47 4.1 2E+Ol 2.42E+O l 1 .30E+02 3.BlE+Ol F 9 859 . 91 2.16E+Ol 8.31 2.16E+Ol 8. 3 1E+OO F 10 9 10 .40 7.45E+Ol 22.72 7.45E+Ol 2.27E+Ol F 11 968.46 5.93E+Ol 19.81 5.93E+Ol 1.98E+Ol F 12 1119.85 2.95E+Ol 14.95 2.95E+Ol 1.SOE+O l F 13 1460.08 7.70E+02 56.71 5.63E+Ol 1.71E+ Ol 7.14E+02 5.92E+Ol F 14 1763.16 2.58E+Ol 11. 49 2.58E+Ol l.15E+Ol
12/8/2017 3:43:33PM Page 3 of7 Analysis Report for L2-SUB-WRS-ASGS-04A-SB 12/4/17 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K-40 0 . 93 1460.75
- 10.67 8.73E+OO 8. 72E-01 PB-212 0.95 77 .11
- 17.50 4 . 80E-01 1. 12E- 01 238 .63
- 44.60 2.40E-01 3. 1 9E - 02 BI-214 0.56 609.31
- 46.30 1. 68E- Ol 5.02E-02 1120.29
- 15 . 10 2.02E - 01 1.03E-01 1238. 11 5 . 94 1377 . 67 4.1 1 1407 . 98 2.48 1509.19 2. 1 9 17 64.49 15.80 PB-21 4 0.97 77.11
- 10.70 7 . 85E-01 l.83E-01 295.21
- 19.20 l. 97E-01 5.05E-02 351 . 92
- 37.20 9 .44 E-0 2 4.88E-02 RA-226 1. 00 186 .21
- 3 .28 4. llE-0 1 2 . 29E-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
12/8/2017 3:43:33PM Page 4 of7 Analysis Report for L2-SUB-WRS-ASGS-04A-SB 12/4/17 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K- 40 0.930 8.73E+OO 8 . 72£-01 PB - 212 0. 954 2 . 5 1E- 01 3 .0 BE -02 BI -214 0.568 1.75E-01 4 . 51E-02 PB-21 4 0.972 1 . 52E - 01 3.45 E-02 RA- 226 1 . 000 4.llE -01 2 . 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
12/8/2017 3:43:33PM Page 5 of7 Analysis Report for L2-SUB-WRS-ASGS-04A-SB 12/4/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/8/2017 3:43:24PM 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 5 338 .16 2.47543E-02 15.56 F 7 583.00 3.46015E-02 10.52 F 9 859 . 91 5 .990 74E-03 19 . 27 F 10 910.40 2.06897E-02 15 . 25 F 11 968 . 46 1 . 64852E - 02 16 . 69 F 14 1763 . 16 7.17496E-03 22 . 25 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCflgrams) (pCi/grams) (pCUgrams) (keV) + K- 40 1460.75
- 10.67 8.73E+00 5.89E-01 5 . 89E-01
+ AR-41 1293.64 99.16 3.55E+14 5 . 00E+l4 5.00E+14 + CO-60 1173.22 100.00 5.81£-02 5.32E-02 6.93£-02 1332.49 100.00 1.89E- 02 5 .32E- 02 + KR-85 513.99 0.43 6.82E+00 9 . 94E+00 9 . 94E+00 + Y-88 898.04 93.70 8.S l E- 04 4. 17E- 02 5 . 24£-02 1836 . 06 99.20 1. 43£-02 4.17E-02 + NB-94 702 . 63 100.00 - 4.86E-03 4.0SE-02 4 . 05£-02 871. 1 0 100.00 -7.47E-03 4.69E-02
12/8/2017 3:43:33PM Page6 of7 Analysis Report for L2-SUB-WRS-ASGS-04A-SB 12/4/17 Nuclide Energy Yield(%) Activity Nuc/ldeMDA LlneMDA Name (pCilgrams) (pCi/grams) (pCilgrams) (keV) + I-131 284 . 30 6 .0 6 - 5 .53E- 01 5.47E- 02 7 . 46E-01 364-48 81.20 - 2 . 33E- 02 5 .4 7E-02 636.97 7.27 - 1.38E- Ol 7 . 14E- 01 + CS-1 34 604.7 0 97. 60 -7. 54E - 03 5.43E-02 5 . 43E- 02 795 . 84 85.40 - 4 . 22E- 03 5.57 E- 02 + CS-137 661. 65 85.12 5 . 7 1 E- 02 5 . 39E- 02 5 . 39E-02 + CE- 144 80 .12 1.36 -l . 63E+OO 2 .7 3E-01 3.44E+ OO 1 33.5 1 11.09 l .21E-0 1 2. 7 3E-01 + EU-152 121.78 28.40 -7.14 E- 02 1. 03E-01 1. OJE-0 1 244.69 7 . 49 - 4 . 24E - 01 4 . 97E-0 1 964 . 00 14.44 6 .17 E- 01 4 . 17E-0 1 1408 . 00 20.74 8.61E-02 2 . 19E-O l + EU- 154 123 . 07 40 . 40 2.62E-0 2 7 .35E-0 2 7 .3 5E-02 247.94 6.60 -5 .99E-0 1 4 . 98E-0 1 723 . 30 19 . 70 -8.14E-02 2 . 16E- 0 1 873 .2 0 11.50 -6 .66E-02 4 . 1 6E-01 1004.76 17.90 -6 .75E-02 2.79E-01 1274 . 51 35 .50 -l.19E- 0 1 1. 69£- 01 + EU- 155 86.54 32 . 80 - 7.8 4E- 02 l. 18E-01 l . 18E-01 105 . 31 2 1. 80 -6 . 74E-02 l.40E-01 + BI - 214 609.31
- 46.30 l. 68E-0 1 9 . 4 2E-02 9.42 E-0 2 1120 . 29
- 15.10 2.02E-01 2 .5 4E-01 12 38. 11 5.94 1.47E+OO 1 . 21E+OO 1377 . 67 4 . 11 -2 .95E-01 1 .1 2E+OO 1407.98 2 .48 7 . 20E-01 l.83E+OO 1509.19 2.19 8 . 28E-01 1 . 83E+OO 17 64.49 15. 80 3 . 03E- 0 1 3 . 38E-01
+ PB-214 77 . 11 *k 10 . 70 7 . 85E - Ol 9.95E-02 4 . llE-01 295.21
- 19.20 1. 97E-01 9.95E-02 351.92
- 37 . 20 9 .44 E-02 9.98E-02
+ PA- 228 89. 95 22.00 4.79E+OO 2.18E+ OO 3.67E+OO 93.35 35.00 7 . 31E-01 2. 1 8E+OO 105.00 16 .3 0 -l . 67E+OO 3. 99E+ OO 129.22 2 .97 4 . 0 3E+ OO 2.14E+ Ol 338.32 5 .3 0 l.1 5E +Ol l . 40 E+ Ol 463.00 13.80 5 .64 E+OO 5.71E+OO 911 . 23 16 . 70 8 . 06E+OO 7 . 56E+OO + AM-241 59 . 54 36 . 30 6 . 04E- 02 2.21E- Ol 2 .21E-0 1 + CM-243 1 03.7 6 23 .00 -5.00E-02 1. 35E-01 l .35E-0 1 228.18 10.60 2.64E-02 2 .85 E-0 1 277.60 14 .00 -5 .58E-04 2.3 4E-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
12/8/2017 3:43:33PM Page 7 of7 Analysis Report for L2-SUB-WRS-ASGS-04A-SB 12/4/17
12/8/2017 4:45:58PM Page J of7 _.Apex-Gamma Analysis Report for L2-SUB-WRS-ASGS-05A-SB 12/4/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-ASGS-05A-SB J Sample Description : 12/4/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 9.585E+02 grams Facility : Dairyland_NPP Sample Taken On : 12/4/2017 1:24:00PM Acquisition Started : 12/8/2017 3:45:35PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB / Geometry : 500ml Marinell( / Live Time : 3600.0 seconds Real Time : 3611.3 seconds Dead lime : 0.31 o;/ Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100 - 4096 Peak Area Range (ln 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 : 3678 PEAK ANALYSIS REPORT Peak Analysis Performed on 12/8/2017 4:45:49PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/8/2017 4:45:58PM Page2 of? Analysis Report for L2..SUB-WRS-ASGS-05A-SB 12/4/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) M 1 74 . 73 146 - 161 150 .0 1 1. 23E+02 39.83 8. 1 6E+ 02 1. 49 m 2 76.99 146 - 161 154 .52 l.27E+02 39.61 8.67E+02 1. 49 F 3 185.80 364 - 376 372.11 9.34E+ Ol 38.02 7.13E+02 1. 87 F 4 238.57 472 - 485 477.62 2.77E+ 02 43.60 5.42E+02 1. 68 M 5 295.19 582 - 604 590 .84 7.94E+Ol 25.15 2.27E+02 1.17 m 6 300.27 582 - 604 601. 00 2.88E+Ol 18 . 65 2.06E+02 1.17 F 7 338 . 37 670 - 68 1 677 . 17 4 .95E+Ol 21. 89 2.72E+02 1. 20 F 8 351.71 698 - 709 703 . 85 1. 29E+02 29. 79 2.64E+02 1.50 F 9 582 . 65 1159 - 1172 1165 . 63 8 . 72E+Ol 22.32 1.44E+02 1. 28 F 10 609. 14 1212 - 1224 1218 . 62 1 . 10E+02 25.09 1. 20E+02 1. 84 F 11 91 1.12 1817 - 1 828 1822.48 5 . 30E+O l 18 . 13 8.48E+Ol 1. 49 F 12 968.44 1931 - 1942 1937.10 2.99E+Ol 15.75 8.90E+Ol 1. 60 F 13 1331.61 2659 - 2668 2 663.36 l . 92E+01 12.17 3.46E+Ol 1. 88 F 14 1460.12 2912 - 2928 2920.36 5 .51E+02 48.23 3 .80E+01 2.50 F 15 1762 . 42 3521- 3530 3524.90 1 . 79E+Ol 9.94 1.61E+Ol 1. 36 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 : 12/8/2017 4:45:49PM 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. M 1 74.73 1.23E+02 39.83 1. 23E+02 3.98E+Ol m 2 76 . 99 1. 27E+ 02 39.61 1. 27E+02 3 . 96E+Ol F 3 185.80 9 . 34E +Ol 38.02 9.34E+Ol 3 . 80E+Ol F 4 238.57 2 .77E+ 02 43.60 2.77E+02 4 . 36E+Ol M 5 295 . 19 7 .94E+ Ol 25 . 15 7.94E+Ol 2 . 51E+ Ol m 6 300.27 2.88£+01 18.65 2.88E+0 1 1. 86E+ Ol F 7 338 . 37 4 .95E +Ol 21. 89 4. 95E+Ol 2.19E+Ol F 8 351 . 71 l . 29E+02 29 . 79 8.36E+Ol 3 . 72E+Ol 4.57E+Ol 4 . 77 E+Ol F 9 582 . 65 8.72E+Ol 22.32 8.72E+Ol 2 . 23E+01 F 10 609 . 14 1 . 10E+02 25.09 4 . 12E+Ol 2.42E+Ol 6 . 91E+Ol 3 . 49E+01 F 11 911.12 5 . 30E+Ol 18.13 5 .30E+Ol l .8 1E+Ol F 12 968.44 2.99E+Ol 15.75 2.99E+Ol 1 . 58E+Ol F 13 1331.61 l . 92E+Ol 12.17 1.92E+Ol l . 22E+Ol F 14 1460.12 5.51E+02 48.23 5 . 63E+Ol 1.71E+ 0 1 4 . 95E+02 5. 12E+0 1
12/8/2017 4:45:58PM Page 3 of 7 Analysis Report for L2-SUB-WRS-ASGS-05A-SB 12/4/17 Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 15 1 7 62.42 1. 79E+O l 9.94 l.79E+Ol 9.94E+OO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K-4 0 0.93 1 460.75
- 10.67 5.62E+OO 6.60E-01 PB-21 2 0 . 99 77 . 1 1
- 1 7 .50 1. 87E-0 1 5 . 96E -02 238.63
- 44 . 60 l.4 9E -0 1 2 . 47E-02 BI - 2 1 4 0 . 34 609 . 31
- 46.30 8.31£-02 4 . 2 1 E- 02 1120.29 15.10 1 2 3 8 . 11 5.94 1377 . 67 4.11 1407 . 98 2 . 48 1509 . 19 2. 1 9 1764.49 1 5 .80 PB- 214 0 . 99 77 .11
- 10. 70 3.06E-01 9 . 74£ - 02 295 . 21
- 1 9.20 l . 19E- Ol 3.80E-02 351 . 92
- 37 . 20 4. 1 2E- 02 4 . 30E-02 RA-226 0 . 97 186 .2 1
- 3.28 5 . 7 4E- 0 1 2 . 36E- 01 AC- 228 0 . 60 209.28 4.40 338.32
- 11. 40 1.41E-01 6 .25E-02 79 4. 70 4.60 91 1. 6 0
- 27 . 70 l .53E-01 5. 2 9E-02 964.60 5 . 20 969 .11
- 1 6.60 1. 52E -0 1 8 . 06E-0 2
12/8/2017 4:45:SSPM Page4 of7 Analysis Report for L2-SUB-WRS-ASGS-05A-SB 12/4/17
* = 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 0.939 5.62E+OO 6.6 0E-01 PB-212 0.999 l.47E -01 2.29E-02 BI -214 0.347 8.31E-02 4.21E-02 PB- 214 0 . 996 8.30E-02 2.75E-02 RA-226 0 .974 5 . 7 4E-0 1 2.3 6E-01 AC-228 0 . 602 1 . 49E -0 1 3.61E-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
12/8/2017 4:45:SSPM Page5 of? Analysis Report for L2~UB-WRS-ASGS-05A-SB 12/4/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/8/2017 4:45:49PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclid~ IY,l M 1 74.73 3 .4 2373E -02 16 . 16 m 6 300 . 27 7.99005E-03 32.41 F 9 582.65 2.42110E- 02 1 2 . 80 F 13 1331 .61 5.33515E-03 3 1 . 69 F 15 1762.42 4 . 97882E-03 27 . 73 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV) + K-40 1460.75
- 10.67 5 . 62E+00 5.45E-01 5.45E-01
+ AR-41 1293.64 99.16 5.55E+l4 9.44E+ 14 9.44E+ l4 + CO-60 1173 . 22 100 .00 4.90E-03 5 . 03E-02 5.70E-02 1332. 49 100.00 3.25E-02 5.03E-02 + KR-85 513.99 0.43 1 .46E+ 0 l 8.71E+00 8. 71E+ 00 + Y-88 898.04 93 . 70 - l . 89E-02 2. 86E-02 4.25E-02 1836.06 99 . 20 4 . 94E-03 2.86E-02 + NB-94 702.63 100.00 l.67E-02 3 . 58E-02 3.58E-02 871.10 100.00 - 1 .53E-02 3.77£-02 + I-131 284.30 6 . 06 - 2 . 02E-0l 4 . 95E-02 6.28E-01
12/8/2017 4:45:58PM Page6of7 Analysis Report for L2-SUB-WRS-ASGS-05A-SB 12/4/17 Nuclide Energy Yield(%) Activity NuclldeMDA LineMDA Name (pCilgrams) (pCi/grams) (pCilgrams) (keV) I-131 364.48 81. 20 2 .67E- 03 4.95E- 02 4.95E- 02 636.97 7.27 2 . 70E- 02 6.34E=01 + CS-134 604.70 97. 60 3.99E-03 4 . 40E-02 4.42E-02 795.84 85 .4 0 5.50E-03 4.40E-02 + CS-137 661. 65 85.12 4 . 42E-02 4 . BlE-02 4.81£-02 + CE-144 80.12 1. 36 -1 . 33E+OO 2 . 39E-01 3 .03E+OO 133.51 11. 09 -1. 34E- 03 2.39£ -0 1 + EU-15 2 121. 7 8 28.40 -1. 23E-01 9 . 1 9E-02 9.19E-02 244.69 7.49 - 3.70E- 01 4.24E-0 1 964 . 00 14 . 44 3.81E- 01 3.55E-01 1408 . 00 20.74 -5.14E-02 l.78E-Ol + EU-154 123.07 40.4 0 -2.66£-02 6 . SOE-02 6.50£-02 247 . 94 6.60 - 5.69E- 01 4.41E-Ol 723.30 19.70 1. 84E- 01 2.09E-01 873.20 11. 50 - 1 .92£-0 1 3.27£-01 1004 . 76 1 7 .9 0 1.92£-01 2.45E - 01 1274.51 35 . 50 -8.26E-02 l.31E-01 + EU-155 86.54 32.80 -1.27E-01 l. 04E-01 1.04£-01 105.31 21.80 -2.65E-02 l .2 6E-0 1 + BI-21 4 609.31
- 46 . 30 8.31E-02 7.67E - 02 7 .6 7E-02 1120. 29 15.10 3.87E - 01 3.73E-01 1238 .11 5.94 3 . 88E-Ol l . OlE+OO 1377 .6 7 4 .11 3 . 79E- 01 9.22E-01 1407 .98 2 .4 8 -4.30E-0 1 l . 49E+OO 1509.19 2.19 9 . 65E-01 1 .6 5E+OO 1764.49 15 .80 l.43E- 0 1 2.68£- 01
+ PB-214 77.11
- 1 0.70 3 . 06E-01 7.79E - 02 2 . 40E-01 295 .21
- 19 . 20 l.19E-01 7 .79 E-02 35 1. 92
- 37 . 20 4.12E-02 8 . 42E-02
+ PA-228 89.95 22.00 3.29E+OO 1.99E+OO 3 .41E+OO 93 . 35 35 . 00 1. 37E-01 1.99E+OO 105.00 16.30 1.22E+OO 3.81E+OO 129 . 22 2 . 97 l . 54E+O l 2.00E+O l 338.32 5.30 1 . 21E+Ol l.29E+O l 463.00 13 . 80 3 .18E+OO 5.00E+OO 911.23 16 .7 0 9 . 5 8E +OO 6.57E+OO + AM-2 41 59.54 36.30 1.07E-0 1 l . 94E-01 1.94E- 01 + CM-243 103.76 23 . 00 4.85E-02 l . 20E-0 1 l . 20E-01 228 . 18 10 . 60 1. 69E - Ol 2 . 44E-0 1 277.60 14 .00 -4 . 26E-02 1 . 99E-01
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
12/8/2017 4:45:58PM Page 7 of7 Analysis Report for L2-SUB-WRS-ASGS-05A-SB 12/4/17
12/8/201 "'f 6:01 :58PM Page 1 of7 ~ ....l'Apex-Gamma Analysis Report for L2-SUB-WRS-ASGS-06A-SB 12/4/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-ASGS-06A-SB / Sample Description : 12/4/17 Sample Type : 500 ml Marinelli / Unit Sample Point Sample Size : 8.789E+02 grams Facility : Dairyland_NPP Sample Taken On : 12/4/2017 2:13:00PM Acquisition Started : 12/8/2017 5:01:35PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB / Geometry : 500ml Marinelli Live Time : 3600.0 seconds / ' Real Time : 3611.5 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 : 3679 PEAK ANALYSIS REPORT Peak Analysis Performed on : 12/8/2017 6:01 :49PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/8/2017 6:01:58PM Page2of7 Analysis Report for L2-SUB-WRS-ASGS-06A-SB 12/4/17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start e.n d Centroid Area Uncertainty Counts (keV) F 1 77.25 152 - 157 155.05 l.04E+ 02 39 . 63 6 .8 9E+0 2 1. 02 F 2 238 . 51 469 - 481 477 . 49 3.22E+02 47 . 99 7. 65E+ 02 1. 28 F 3 295.04 587 - 596 590 . 52 1. OOE+02 29.90 3.72E+ 02 1. 26 F 4 337.93 671- 680 676 . 29 7.00E+Ol 26 . 23 2.52E+0 2 1. 49 F 5 351.76 698 - 708 7 0 3 .9 4 l . 93E+ 02 34.75 2.81E+ 0 2 1. 53 F 6 58 2 .99 1 159 - 1173 11 66.32 l . 20E+ 02 26 . 34 1.63E+02 1. 70 F 7 609.07 12 12 - 1 227 1 21 8.47 l . 46E+02 27 . 82 l.3 0E+02 1. 94 F 8 661.42 1319 - 1 329 1 323. 1 5 1 .03E+02 2 5 . 73 1.53E+02 1. 62 F 9 910.49 1814 - 1 827 1 82 1 . 23 8 . 1 9E+ 0 1 23 . 28 l .1 2E+0 2 2.24 F 10 968.71 1933 - 1942 1937.65 4 .77 E+01 17 . 41 6.81E+Ol 1. 47 F 11 14 60 . 22 2911 - 2929 292 0 .55 7.48E+02 55. 91 l.90E+Ol 2 .54 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 : 12/8/2017 6:01:49PM 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 77.25 1.04E+02 39 . 63 l.0 4E+ 02 3.96E+Ol F 2 238.51 3.22E+02 47 . 99 3 .22E+02 4 .80E+Ol F 3 295 .04 1 . 00E+02 29. 90 1. OOE+02 2 . 99E+Ol F 4 337.93 7.0 0E+Ol 26 .2 3 7.00E+Ol 2 .62E+O l F 5 351.76 1 .93E+ 0 2 34 . 7 5 8 . 36E+Ol 3 . 72E+Ol 1. 09E+02 5 .09E+O l F 6 582.99 1. 20 E+ 02 2 6. 34 1. 20E+02 2 . 63E+ Ol F 7 609 . 07 1.46E+ 02 27.82 4.12E+Ol 2.42E+01 l .0 5E+0 2 3 . 69E+O l F 8 661. 42 1 . 03E+ 02 25.73 6. 6 1E+O l 2.54E+Ol 3.69E+Ol 3.61E+Ol F 9 910.49 8 . 1 9E+ Ol 23 . 28 8. 1 9E +Ol 2.33E+O l F 10 968.71 4 . 77E+Ol 17 . 41 4 . 77E+ Ol 1.74E+ Ol F 11 1460.22 7.48E+02 55 .91 5 .6 3E+ Ol 1 .71E+Ol 6. 91 E+ 02 5.85E+Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma
12/8/2017 6:01 :58PM Page 3 of7 Analysis Report for L2-SUB-WRS-ASGS-06A-SB 12/4/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairy1and_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) {pCilgrams) Uncertainty K-40 0.95 1460 .75
- 10 . 67 8.57E+OO 8.67E-O l CS-137 0.99 661. 65
- 85.12 2.83E -0 2 2 . 78E-02 PB- 212 0.99 77.11
- 17 . 50 1. 66E-01 6.42E-02 238 . 63
- 44.60 l .8 9E-01 2 . 98E-02 BI - 214 0.34 609 . 31
- 4 6. 30 1. 37E-01 4.89E-02 1120. 29 15 . 10 1238 . 11 5 . 94 1 377 . 67 4 . 11 1407. 98 2.48 1509.19 2.19 1764 .49 15.80 PB-214 0.99 77 .11
- 10 . 70 2.71E- 01 1. OSE -01 295 . 21
- 19.20 l . 63E-01 4 . 93E -02 351. 92
- 37 .20 1. 07E-Ol 5.03E-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)
12/8/2017 6:01:58PM Page 4 of7 Analysis Report for L2-SUB-WRS-ASGS-06A-SB 12/4/17 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) JK-40 0 .95 6 8 .57E+OO 8 . 67E-01 CS-137 0.992 2 . 83E-02 2 . 78 E-02 PB-212 0 . 998 1 .7 2E-01 2.7 3E-02 BI -2 1 4 0 . 345 1. 37 E- 01 4.8 9E- 02 PB- 21 4 0.996 1.21E- 01 3 . 37E-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
12/8/2017 6:01 :58PM Pagc5 of7 Analysis Report for L2-SUB-WRS-ASGS-06A-SB 12/4/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/8/2017 6:01 :49PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 4 337 .93 l.94553E- 02 18.73 Tol. AC- 228/ PA-228 F 6 582 . 99 3.33730E-02 1 0 . 96
- 1) 1,,\)./.
F 9 910.49 2 . 27637E-02 14.20 Tol.
~~28 F 10 968 . 71 1 . 32475E-02 18 . 25 Tol. J:l:C-228 . /
M = First peak in a multlplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuclide MDA LineMDA Name (pCi/grams) (pCilgrams) (pCilgrams) (keV) + K-40 14 60.75
- 10 .67 8.57E +OO 5.52E- 01 S.52E - 01
+ AR-41 1293. 64 99.16 -3.84E+14 1.19E+15 1.19E+l5 + C0- 60 1173 .22 100 .00 -9.49E- 03 6. 14E-02 6.98E-02 1332.49 1 00 . 00 7.36E-02 6.14E-02 + KR- 85 5 1 3.99 0. 43 8.37E+OO 9.54E+OO 9.54E+OO + Y- 88 898.04 93.70 7.39E-03 3.0 lE - 02 5. 14E-02 1836.06 99.20 -1.22E- 02 3 . 0lE - 02 + NB-94 702.63 1 00 . 00 2.18E-02 3 . 90E - 02 3 . 90E-02 871.10 100.00 -2.72£-02 4 . 65E-02 + I-131 284.30 6.06 -3 .1 3E-02 5.76£- 02 7 . 48E-01 364.48 81. 20 - l .96E-02 5. 76E-02
12/8/2017 6:01:SBPM Page6 of? Analysis Report for L2-SUB-WRS-ASGS-06A-SB 12/4/17 Nuclide Energy Yield(%) Activity Nuc/ideMDA Line MDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV) I-131 636 . 97 7 . 27 -6.21E-01 5.76E-0 2 7.53E-01 + CS-134 604 . 70 97 . 60 ~3.0SE-03 4.86E-0 2 5 . 20E-02 795.84 85.4 0 -2.58E-02 4 . 86E - 02 + CS-13 7 661. 65
- 85.12 2 . 83E-0 2 5.35E-02 5.35E-02
+ CE-144 80.12 1. 36 -1.91E+OO 2 . 82E-01 3.39E+OO 133.51 11. 09 1 .31E- 01 2.82E-01 + EU- 1 52 121. 7 8 28.40 4 .0 7E- 02 1. 08 E-01 l.08E - 01 2 44 .69 7.49 - 1.35E+OO 5.16E-0 1 964.00 14.44 4 . 4 0E-01 4.02E-01 14 08.00 20.74 1. 23£-01 2.0 l E- 01 + EU-154 123.07 40 . 40 -1. 4 6E-02 7.56E-02 7 . 56E- 02 247.94 6.60 -2 .42E +00 5 . 17E-0 1 723 . 30 19 .70 1.63E-0 1 2.43E-01 873 . 20 11. 50 - 2.45E-01 3.98E-01 1004 . 76 17.90 - 2.67E-01 2.78E - 01 1274 . 5 1 35 . 50 5.08E-02 1.62E - Ol + EU-155 86.54 32.80 -2.33E-02 1. 19'E-01 1.19E-01 10 5.3 1 21. 80 -7 .2 9E- 03 1.44E-01 + BI- 2 14 609 . 31
- 46 . 30 1 . 37E-01 8.78E-02 8 .78E- 02 112 0. 29 15.10 -9 . ll E-02 4.12E-01 1238 .11 5.94 6.llE-0 1 l .2 3E+OO 1 377.67 4.11 1 . 08E+OO 1 . 19E+OO 1 40 7 . 98 2.48 1. 02E+OO 1 . 68E+OO 1509 .19 2 . 19 7 . 76E-01 1 . 90E+OO 1 764 .4 9 15 .80 8.05E-02 2 . 93E-01
+ PB-214 77 . 11
- 10.70 2.71E-0 1 9.20E-02 2 . 23E-01 295 . 21
- 19 . 20 1. 63E-01 1.lSE- 0 1 351.92
- 37 . 20 l.07E-0 1 9 . 20E-02
+ PA-228 89 . 95 22.00 1 . 94E+OO 2.29E+OO 3.90E+OO 93.35 35 . 00 - l .66E+ OO 2.29E+OO 1 05.00 16.30 4 . 19E- 01 4.40E+OO 12 9. 22 2.97 7.98E+OO 2 .4 1E+Ol 338.32 5.30 1. 37E+01 1 . 51E+Ol 46 3 . 00 13 . 8 0 8 . 62E-01 6 . 09E+ OO 911. 2 3 16 . 70 1.57E+Ol 8 . 5 4E+OO + AM-241 59 . 54 36.30 l.57E-02 2 . 1 7 E-0 1 2.1 7E - 0 1 + CM- 243 1 03.76 23 . 00 4 .03E-04 l.38E-01 1. 38E- 01 228 .1 8 10.60 6 . 13E- 02 2.91E- 0 1 2 77.60 14.00 - l . 20E-0 1 2.30E- 0 1
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
12/8/2017 6:01 :58PM Page 7 of7 Analysis Report for L2-SUB-WRS-ASGS-06A-SB 12/4/17
12/7/201 '1 8:41:02PM Page I of7 ~.Ji/S~~pex-Gamma Analysis Report for L2-SUB-WRS-QSGS-06A-SB L2-011-101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-QSGS-06A-SB / Sample Description : L2-011-101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 8.611E+02 grams ./ Facility : Dairyland_NPP Sample Taken On : 12/4/2017 3: 12:00PM Acquisition Started : 12n/2017 7:40:39PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB / Geometry : 500ml Marinelli Live Time : 3600.0 seconds Real Time : 3611.5 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 : 3667 PEAK ANALYSIS REPORT Peak Analysis Perfonned on 12/7/2017 8:40:53PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/7/2017 8:41:02PM Page 2 of 7 Analysis Report for L2-SUB-WRS-QSGS-06A-SB L2-011 -101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 54 . 15 106 - 111 108 .85 3 . 54E+Ol 29 . 91 4 . 16E+02 1.05 M 2 74.76 145 - 1 75 1 50 .0 7 8 .4 5E+O l 35 . 35 8.65E+02 1 . 04 m 3 77.0 1 145 - 175 1 5 4. 56 1 . 3 5E+0 2 39 . 53 7 . 44E+02 1. 0 4 F 4 93 . 08 182 - 193 1 86 . 70 7 . 2 5E+Ol 38 . 77 l . 07E+03 1. 30 F 5 185 . 90 369 - 376 372.30 8 . 83E+Ol 34 . 41 5 . 25E+ 02 1. 21 F 6 238 . 52 4 73 - 485 477.51 4 .1 3E+ 02 49. 79 5 . 90E+02 1. 32 F 7 294 . 89 585 - 597 590.23 7 . 68E+Ol 24.77 3 . 86E+ 02 0 . 98 F 8 338 . 34 671 - 68 1 677 . 11 8 . 80E+Ol 2 6 . 52 2 . 6 1E+02 1. 38 F 9 351 . 84 700 - 709 70 4.11 1. 4 7E+02 30 . 52 2 .5 8E+02 1 . 21 F 10 583 . 08 1159 - 117 1 1166 . 51 l . 2 4 E+0 2 26 .0 2 1 . 11E+02 1. 81 F 11 609 . 1 7 12 12 - 1225 1 2 1 8 . 67 1 . 35E+02 2 7 . 13 1 .5 0E+02 1. 6 0 F 12 *910 . 8 5 1812 - 1829 1 82 1. 95 8 . 4 1 E+ Ol 2 1. 57 l.1 3E+0 2 1. 8 5 13 968 .4 7 1933 - 1943 1937.1 7 l. 91 E+ Ol 24 . 52 l. 08E+ 02 1. 4 8 F 14 1 460 .4 2 2913 - 2929 2920 . 94 7 . 62E+02 56 . 85 3 . 28E+ Ol 2 . 28 F 15 1 508 . 20 30 1 2 - 30 21 3016.50 1. 06E+O l 7 . 92 1. 00E+ Ol l. 58 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted a t 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 12/7/2017 8:40:53PM 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 54 . 15 3 . 54E+ Ol 29 . 91 3 . 5 4E+Ol 2 . 99E+Ol M 2 74 . 76 8 . 45E+O l 3 5. 35 8. 45E+O l 3 . 53E+Ol m 3 77 . 01 1. 35E+02 39 . 53 l . 3 5E+02 3.95E+Ol F 4 93 . 08 7 . 25E+ Ol 38 . 77 7 . 25E+ Ol 3 . 88E+O l F 5 185 .90 8 . 83E+ Ol 34 .4 1 8 . 83E + Ol 3 . 44E+O l F 6 238 . 52 4 . 13E+02 49 . 7 9 4 .1 3E+02 4 . 98E+O l F 7 294.89 7.6 8E+O l 2 4.77 7 . 68E+Ol 2 . 48E + Ol F 8 338 . 34 8 . 80E+ Ol 2 6. 52 8 . 80E+Ol 2. 65E+ Ol F 9 351. 84 1. 4 7E+ 02 30 . 52 8 . 36E+Ol 3 . 72E+Ol 6.32E+ Ol 4 . 81 E+Ol F 10 58 3 . 0 8 1 . 24E+0 2 26 .02 1. 24E+ 02 2.60E+ Ol F 11 609 .1 7 l .35E+ 02 27 . 1 3 4.1 2E+Ol 2 . 42E+Ol 9 . 36E+O l 3 . 64E+O l F 12 9 10. 85 8 . 41E+ Ol 2 1. 57 8 .4 1E+Ol 2 . 16E+Ol 13 968 . 47 1. 91E+ Ol 24 . 52 l . 91 E+Ol 2 . 45E+Ol F 14 1460 . 42 7 . 62E+ 02 56 . 85 5 . 63E+Ol l . 71E+O l 7 . 0SE +02 5 . 94E+Ol
12/7/2017 8:41:02PM Page 3 of7 Analysis Report for L2-SUB-WRS-QSGS-06A-SB L2-011 -101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 15 1508.20 1 .0 6E+ Ol 7. 92 1 .06E+Ol 7.92E+OO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K- 40 0.98 1460 . 75
- 1 0 .6 7 8.92E+OO 9.00E-01 PB-212 0.99 77 .11
- 17 . 5 0 2 .22E- Ol 6 . 64E-02 238 . 63
- 44 .60 2.48E - 01 3 . 2 4£-02 BI - 21 4 0.3 7 609 .3 1
- 4 6.30 1 . 25E- 0 1 4.91 E-02 1120 . 29 15. 1 0 1238 .11 5. 94 1377.67 4 . 11 1 407.98 2.48 1509.19
- 2.19 6 .7 4E- 01 5 .03E- 01 1764.49 15 . 80 PB- 214 0.99 77 . 11
- 10 . 70 3 .63E - 01 1.09E- 01 295.2 1
- 19 . 20 1.27E-Ol 4. 16E-02 351 .9 2
- 37. 20 6 . 34E- 02 4. 8 4E-0 2 RA- 226 0.98 186 .21
- 3 .2 8 6 . 0SE- 0 1 2 . 3 8E -O l AC-228 0 . 58 209 .2 8 4.40 338 .3 2
- 1 1. 40 2 .78E-01 8.49E-02 794 .70 4. 60 911 .60
- 27.70 2 . 71E- Ol 7.04E-02 964 . 60 5.20 969.11
- 16.60 1.08E-01 1.3 9E- Ol
12/7/2017 8:41:02PM Page 4 of7 Analysis Report for l2-SUB-WRS-QSGS-06A-SB L2-011-101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)
K- 40 0.982 8 .92E+ OO 9. 00 E-0 1 PB- 212 0.998 2.32E-Ol 2 .9 4E - 02 BI - 214 0 . 374 1 . 30E- 01 4.89E - 02 PB-214 0 .9 9 4 9 . 12E- 02 3 . 0SE - 02 RA-226 0 .985 6.05 E-0 1 2 .38E- Ol AC- 228 0 . 583 2 . 52 E- Ol 5 . 0SE - 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
12ll/2017 8:41:02PM Page 5 of7 Analysis Report for L2-SUB-WRS-QSGS-06A-SB L2-011 -101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/7/2017 8:40:53PM 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 F M 1 2 54 .1 5 74 . 76 9.83092E - 03 2 . 34742E - 02 42.26 20.91 t))
~~ ~'I>-~
F 4 93 . 08 2 . 01335E-02 26 . 75 Tol.
~~~ ?-(..,
~-J F 10 583 . 08 3 . 45166E-02 1 0 . 47 <P'"v
=
M First peak in a multiplet region
=
m Other peak in a multiplet region F = Fitted singlet
~ ,,,'\
Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield{%) Activity NuclideMDA Line MDA Name (pC/lgrams) (pCilgrams) (pCilgrams) (keV) + K- 4 0 1460.75
- 10.67 8.92E+OO 5 . 93E-Ol 5 . 93E- 01
+ AR-41 1293.64 99.16 2.14E+ll 2 . 76E+ll 2.76E+ll + /co-60 1173.22 100.00 - 6.40E-02 5. 13 E-02 6 . 39E-02 1332 .49 1 00.00 -4.0SE - 02 5 . 13E-0 2 + KR-85 513 . 99 0 . 43 8.77E+OO l . OlE+ Ol 1.0lE+Ol + Y-88 898 . 0 4 93 . 70 -1.21£- 02 3.77E-02 4.63E-02 1836 . 06 99.20 -1. 08E-02 3 . 77 E- 02 + NB- 94 702 . 63 100.00 7 .0 2E-03 4 . 16E- 02 4 . 16E-02 871 .1 0 1 00 .00 -1.82£- 02 4.45E-02 + I - 13 1 284.30 6.06 - 2.77E - 02 5.38E-02 6 .77E- 01 364 . 48 81. 20 2 . 85E-02 5 . 38E-02
12/7/2017 8:41:02PM Page 6 of7 Analysis Report for L2-SUB-WRS-QSGS-06A-SB L2-011-101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 Nuclide Energy Yield(%) Activity N uc/ide MDA LfneMDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV) j,r-131 636.97 7.27 8 .91E- 03 5.38E-02 7.09E-01 + CS - 134 604.70 97.60 -3 . 33E-03 5.25E =02 5.25E-02 795.84 85.40 9.97E-03 5.39E-02
- / CS-137 CE-144 661 . 65 80 .1 2 133. 51 85.12 1.36 11.09 9.85E- 02 3.58E+OO 3 . 02E-01 6.21E-02 2.82E-01 6.21E-02 3.52E+OO 2.82E- 01
+ EU- 1 52 121.78 28 .40 -6.80E- 02 1.06E-01 1. 06E-Ol 244.69 7 .49 -5. 00E-0 1 5.35E-01 964 .00 14.44 4.23E-01 4 . 13E-Ol 1408.00 20.74 - 3.69E- 02 2.12E-01 + EU-15 4 123.07 40 . 40 -4.81E-02 7.42E-02 7.42E-02 247 . 94 6 . 60 -1. 0 lE+OO 5 .04E-01 72 3.30 1 9.70 4 .43E-02 2 . 24E-01 87 3 . 20 11. 50 1. 45E-01 4.0lE-01 1004. 76 17 .90 - 3.54E-02 2.87E-01 1274 . 51 35.50 -6.73E- 02 l.51E-Ol + EU-155 86 . 54 32 . 80 - 1.41E-0 2 1 . 20E-01 1. 20E-01 1 05 . 31 21. 80 9.66E-02 1 . 47E-01 + BI-214 609.31
- 4 6 . 30 1.25E- 01 9. 09E-02 9.09E-02 1120 . 29 15 .1 0 2.67£-01 4 . 33E-01 1238.11 5 . 94 2 .2 7E -01 l .15E+OO 1377 . 67 4.11 - 5 . 56E - 01 l.20 E+OO 140 7 .98 2.48 - 3 .08E- 01 1.77E+OO 1509 .19
- 2 .19 6.74E - 0 1 8.73E-01 1 76 4 .49 15.80 3 . SOE-01 3.03E-01
+ PB-214 77 . 11
- 10 .70 3 . 63E - 01 9.14E - 02 2.48E-0 1 295 . 21
- 19.20 l.27E- 01 1.28E-01 351 . 92
- 37.20 6.34E-02 9.14E-02
+ PA-228 89.95 22 .00 -2 .2 7E-01 l . 14E+OO 1. 96E+OO 93 . 35 35.00 -l.70E-0 2 1.14E+OO 105.00 1 6 . 30 2.04E+OO 2 . 22E+OO 129.22 2 . 97 - 3.65E+OO 1. 16E+O l 338.32 5 . 30 1. llE+OO 7.63E+OO 463.00 13 . 80 -3.07E-0 1 2 . 91E+OO 911.23 16 .7 0 6.54E+OO 4.14E+OO + / ~M-241 59.54 36.30 -3.80E-02 2.16E-0 1 2. 16E-0 1 + CM-243 103.76 23 . 00 9. llE-02 1 .40E-01 1.40E-01 228.18 10.60 8.36E -02 2.89E- 01 277.60 14 . 00 -6.0SE-02 2.28E-01
.. == Energy
+ Nuclide identified during the nuclide identification 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
12/7/2017 8:41:02PM Page 7 of 7 Analysis Report for L2-SUB-WRS-QSGS-06A-SB L2-011 -101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17
12/8/201' 7:03:52PM Page J of7 pex-Gamma Analysis Report for L2-SUB-WRS-ASGS-07 A-SB 12/4/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-ASGS-07A-SB / Sample Description : 12/4/17 Sample Type : 500 ml Marinelli / Unit Sample Point Sample Size 6.652E+02 grams Facility : Dairyland_NPP Sample Taken On : 12/4/2017 2:31:00PM / Acquisition Started : 12/8/2017 6:03:29PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry Live Time
- 500ml Marinelli /
- 3600.0 seconds Real Time : 3611.3 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 : 3680 PEAK ANALYS/S REPORT Peak Analysis Performed on 12/8/2017 7:03:43PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/8/2017 7:03:52PM Page 2 of7 Analysis Report for L2-SUB-WRS-ASGS-07 A-SB 12/4/ 17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) M 1 74 . 60 143 - 192 149 . 75 l . 61E+02 4 3.88 l .03E+03 1.53 m 2 76 . 92 1 43 - 192 154 .39 2 . 53E+02 49 .93 1. 02E+03 1. 54 m 3 87.1 4 143 - 192 174 . 82 l .17E+0 2 39.86 9 . 86E+02 1. 55 m 4 92.63 143 - 192 185.79 1 .31E+02 41. 44 9 . 65E+0 2 1. 57 F 5 185 . 87 367 - 378 372 . 2 4 1.06E+02 41. 46 8.20E+ 02 1.81 F 6 20 9. 12 415 - 422 41 8.73 4 . 33E+Ol 28.96 4 . 86E+ 02 1. 06 F 7 23 8. 39 470 - 481 477 . 2 5 4 . 65E+02 55 . 87 8 . 58E+0 2 1. 32 F 8 29 5.07 583 - 596 59 0.6 0 1. 58E+02 3 5.1 8 5 . 20E+02 1. 44 F 9 338.10 673 - 681 676 .6 3 1. 1 6E+02 28 .80 2 . 2 9E+02 1. 32 F 10 351. 71 695 - 71 2 70 3 . 86 2 . 55E+ 02 37.37 4.04E+02 1. 4 9 F 11 462.27 919 - 933 924.92 5 .lOE+Ol 2 0. 93 2 . 31E+02 1.38 F 12 510.5 4 1012 - 1 030 1 021.45 l . 29E+02 29 .05 2.66E+02 2.17 F 13 582.99 1160 - 1171 1166 . 33 l .22E +02 27.76 l . 74 E+02 1. 67 F 14 609.16 1 2 11 - 1226 1 2 18.66 l .77E+02 30 . 13 l.70E+02 1. 58 F 15 661. 27 1 31 8 - 1328 1322.85 1.41E+02 28.4 5 1. 44 E+02 1. 62 F 16 72 6.89 144 7 - 1458 14 5 4 .07 3. 72E+O l 1 8.39 1.14E+02 1. 71 F 17 9 1 0. 63 1 816 - 1827 182 1 .5 1 l. 1 5E+02 24 . 89 1. OOE+ 02 1. 66 F 18 968.44 1933 - 1945 1937 . 11 6.41E+Ol 21.10 1.34E+02 1. 53 F 19 1119.88 2233 - 2245 2239.95 4.70E+0 1 17 .39 8 .8 3E+Ol 1. 6 1 F 20 1332.0 5 2658 - 2 66 9 2664.24 3 . 50E+0 1 13.92 2 .06E+ Ol 2 .71 F 21 1460. 12 2913 - 2930 292 0. 36 7 . 60E+02 56. 26 2 .54E+ Ol 2 . 37 F 22 1763 .1 5 3522 - 3531 3526.37 2 . 02E+Ol 1 0.34 l.70E+ Ol 1. 35 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 : 12/8/2017 7:03:43PM 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. M 1 74.60 l . 61E+02 43 . 88 l.61 E+0 2 4 . 39E +Ol m 2 7 6 . 92. 2 . 53E+02 4 9.93 2 . 53E+ 02 4.99E +01 m 3 87. 14 1 .1 7E+0 2 39.86 1 .17 E+02 3.99E +Ol m 4 92.63 1.31E+02 41.44 l.31E+02 4.14E+Ol F 5 185.87 1. 06E+ 02 4 1. 46 1 . 06E+02 4 . lSE+ Ol F 6 209 . 12 4.33E+Ol 28 .9 6 4. 33E+Ol 2 . 90E+Ol F 7 238 .39 4 . 65 E+02 55.87 4.65E+ 02 5 . 59E+Ol
12/8/2017 7:03:52PM Page3 of7 Analys is Report for L2-SUB-WRS-ASGS-07A-SB 12/4/1 7 Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 8 295 . 0 7 l. 58E+ 02 35 . 1 8 1. 58E+02 3.52E+ Ol F 9 338 . 1 0 1.16E+02 28 . 80 l . 16E+ 02 2.88E+Ol F 10 351.71 2 . 55E+02 37 . 37 8 . 36E+0 1 3 . 72E+O l 1. 71E+02 5 . 27Et01 F 11 462 . 27 5 . l OE+Ol 20.93 5 .l OE+Ol 2 . 09E+01 F 12 5 1 0 . 54 l . 29E+02 2 9. 05 7 .2 8E+O l 2 . 85E+ Ol 5 . 58E+ Ol 4 . 07E+O l F 13 582.99 l . 22E+ 02 27 . 76 1 . 22E+02 2 . 78E+ Ol F 14 609 . 16 l . 77E+ 02 30 . 1 3 4 . 12E+O l 2 . 42E+Ol 1.36E+02 3 . 8 7E+O l F 15 661 . 27 1. 41E+ 02 28 .4 5 6 . 61E+O l 2 . 54E+O l 7 .S OE+Ol 3 . 81 E+Ol F 16 7 2 6 . 89 3 . 72E+ Ol 1 8 . 39 3 .7 2E+ Ol 1 . 84 E+Ol F 17 9 1 0 . 63 1 . 1 5 E+0 2 2 4 . 89 1.15E+02 2 . 4 9E+Ol F 18 968 . 44 6 . 41E+O l 21. 10 6 . 41E+Ol 2. ll E+O l F 19 1119 . 88 4 . 70E+ Ol 17.39 4 . 70E+Ol l. 7 4E+Ol F 20 1 332.05 3 .S OE+ Ol 13 . 92 3 . 50E+Ol l . 39E+Ol F 21 14 60.1 2 7 . 60E +02 56 . 26 5 . 63E+ Ol 1. 71E+O l 7 . 04E +0 2 5.88E+Ol F 22 1 763 . 1 5 2 .02E +Ol 1 0. 34 2. 02E+ Ol l.03E+Ol
=
M First peak in a multiplet region
=
m Other peak in a multiplet region
=
F Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) {pCi/grams) Uncertainty K-40 0 .9 3 1 46 0.75
- 10 . 67 l .1 5E+Ol 1.16E+OO CS - 1 3 7 0 .9 7 66 1. 65
- 85 . 12 7 . 61E - 02 3 .8 9E-02 BI - 212 0 . 59 7 27 . 17
- 11. 80 2 . 97E -0 1 1. 4 8E- 01 7 8 5 . 42 2 . 00 1620 . 56 2 . 75 PB-2 1 2 0.99 77 . 11
- 17 . 5 0 5 . 38E- 01 1 .1 2E-0 1 23 8 .63
- 44.60 3 . 60E - 0 1 4 . 71 E- 02 BI - 214 0 . 57 609.31
- 4 6. 30 2 . 35E - 0 1 6 . 82E-02 112 0. 29
- 1 5 . 10 4. 32E - 0 1 1 . 61E- 01 1238 . 11 5.94 1 377 . 67 4 . 11 1 407 . 98 2 . 48 1509 . 19 2.19 1764.49 15.80
12/8/2017 7:03:52PM Page4of7 Analysis Report for L2-SUB-WRS-ASGS-07 A-SB 12/4/17 Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty PB-214 0.99 77 . 11
- 10.70 8.79E-0 1 l . 83E-01 295 . 21
- 19.20 3.4 0E-0 1 7.74E-02 351.92
- 37.20 2 .23E-0 1 6.93E-0 2 RA-226 0.98 186.21
- 3.28 9.37E-0 1 3.71E-01 AC-228 0. 72 209.28
- 4.40 3.09E-Ol 2.07E-01 338 .32
- 11. 40 4.76E-O l l . 20E-01 794 .7 0 4.60 911 . 60
- 27.70 4.78E-01 l.06E-01 964 . 60 5.20 969.11
- 1 6 .60 4 . 71E-01 l.56E-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 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams)
K-40 0.939 1.15E+Ol 1. l 6E +OO
/ CS-137 0 . 977 7 . 61E-02 3.89E-02 BI-2 1 2 0 . 596 2 . 97E- 01 1. 48E-0 1 PB-2 1 2 0.992 3 . 61E-0 1 4.3 7E -02 BI-2 1 4 0 . 579 2 .65E-0 1 6.28E - 02 PB-2 1 4 0.994 2 . 76E-0 1 5.00E-02 RA-226 0.982 9 . 37E-01 3.7 1E-01 AC-228 0.727 4.58E-0 1 6.69E- 02
? = nuclide Is part of an undetermined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
12/8/2017 7:03:52PM Page 5 of? Analysis Report for L2-SUB-WRS-ASGS-07A-SB 12/4/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/8/2017 7:03:43PM 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
~\
.~1>
M 1 7 4.6 0 4.46016E-02 13.67 m
~
3 87.14 3 .2 3940E -0 2 1 7.09 Tol. m 4 92.63 3.63088E -02 15.85 Tol.
~
~""1,,i>'\
F 11 4 62. 27 l.4 1579E-02 20 . 53 To l.
~~
F 12 510 . 54 1 . 55077E-0 2 36 . 4 5 "\fl.-dzt6 F 13 582.99 3 . 39852E-0 2 11. 35 1'1tD F 20 1332.05 9.73186E-03 1 9 . 86 f ,Ji, F 22 1763 . 15 5 . 6219 7E-03 25.55 Pi ),t( M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma er~:~ NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ NP P\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCifgrams) (pCilgrams) (keV) + K-4 0 14 60.75
- 10 . 67 l. lSE+0l 7.47£-01 7 .4 7E-01
+ AR-4 1 1 293. 64 99.16 2.13E +15 2 . 38E+15 2.38E+l5 + CO- 60 1173 . 22 100 . 00 3 . 66E-02 7.66E-02 8.58E- 02
12/8/2017 7:03:52PM Page6 of7 Analysis Report for L2-SUB-WRS-ASGS-07 A-SB 12/4/ 17 Nuclide Energy Yield{%) Activity Nuc/ideMDA Line MDA Name (pCilgrams) (pCilgrams) (pCilgrams) (keV) C0-60 1332.49 100.00 6. llE-02 7 . 66.E- 02 7.66E-02 + KR-85 513 . 99 0.43 2.40E- 02 1. 40E+Ol 1. 40E+Ol + Y- 88 898.04 93.70 - 4. llE-02 5 . 15E- 02 6 . 35E-02 1836 . 06 99 . 20 - 3.48£- 02 5 . lSE- 02 + NB-9 4 702.63 100.00 -4 . 31E- 02 5 . 31E-02 5.31E-02 871.10 100.00 - 3 . 99E-02 5.88E - 02 + I - 131 284.30 6 . 06 - 1 . 7 1 E-01 7 . 70E-02 l.OSE+OO 364.48 81 . 20 1 .62E-02 7.70E-02 636 . 97 7.27 1 . 30E-01 1. 05E +OO + CS - 134 604 . 70 97.60 -2 . 63E - 02 7.24E-02 7.30E-02 795.84 85 . 40 -l . 03E-02 7.24E-02 + CS-137 661 . 65
- 85.12 7 . 61E-02 6.96E - 02 6.96E-02
+ CE-144 80 . 12 1. 36 2 . 20E+OO 3 . 80E-01 4 . 84E +OO 133 . 51 1 1.09 2.lOE-02 3.80E-01 + EU-152 121.78 28 . 40 - l.19E- 01 1.47E-01 l . 47E-01 244 . 69 7. 4 9 - l . 87E+OO 7.38E-01 964 . 00 14.44 - 3.lBE- 01 6.0lE-01 1408.00 20.74 - 1.18E-01 2 . 88E- 0 1 + EU- 154 123.07 40 . 40 - 3 . 57£- 02 1.04£-01 1 . 04E-01 247.94 6 . 60 - 3 . 59E+OO 7 . 00E- 0 1 723.30 19.70 3.31E - Ol 3.30E-01 873 . 20 11.50 -6.70E - 01 5 . 07E-01 1 004 . 76 17.90 l. 18E-01 3.80E-01 1274.51 35.50 7.40E-02 2.34E- 01 + EU-155 86.54 32.80 -1.07E-01 1.68E-01 1. 68E-0 1 105 . 31 21. 80 -2 . 60E- 02 l . 91E- 01 + BI -214 609.31
- 46 . 30 2.35E- 01 1 . 25E-01 1. 25£ - 01 1120 . 29
- 15 . 10 4.32E-01 3 . 52E- 01 1238.11 5 . 94 2.00E+OO 1 .62E+00 1377.67 4 . 11 7.25E- Ol 1. 69E+OO 1407 .98 2 . 48 - 9 . 88E-01 2 . 41E+OO 1509 . 19 2 . 19 1. llE+OO 2 . 75E+OO 1764 . 49 15.80 4 . 20E-01 4 . 53E-01
+ PB-214 77 .11
- 10 . 70 8 . 79E-01 1. 44E-01 3.75£-0 1 295.21
- 1 9.20 3 . 40E-01 1. 96E-01 351.92
- 37.20 2.23E-Ol l .44E-01
+ PA-228 89.95 22.00 8.27E+OO 3 . 38E+OO 5 . 76E+OO 93 . 35 35 . 00 8.20E- 02 3 . 38E+OO 105.00 16.30 1. 1 3E-01 6 . 0lE+ OO 129 . 22 2.97 8 . 13E+OO 3 . 29E+ Ol 338.32 5.30 1. 82E+O l 2 . 18E+01 463.00 13 . 80 9 . lOE+OO 9 . 07E+OO 911.23 16 . 70 1. 38E+Ol 1. 23E+Ol + AM-241 59.54 36 . 30 - 4 . 28E-02 3.02E-01 3.02E-01 + CM-243 1 03.76 23 . 00 -1 . 06E-02 l .84E-0 1 1.84E-01 228.18 10 . 60 - l . 91E - 01 4.00E- 01 277.60 14 . 00 -6.22E - 02 3 . 32E-01
12/8/2017 7:03:52PM Page 7 of7 Analysis Report for L2-SUB-WRS-ASGS-07 A-SB 12/4/17
+ = 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% conftde:nce level
12/8/2017 8:22:02PM Page I of7 ~ ~ ~pex-Gamma Analysis Report for L2-SUB-WRS-ASGS-08A-SB 12/4/17 GAMMA SPECTRUM ANALYSJS Sample Identification : L2-SUB-WRS-ASGS-08A-SB. / Sample Description : 12/4/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 1.018E+03 grams / ' Facility : Dairyland_ NPP Sample Taken On : 12/4/2017 1:28:00PM_/ Acquisition Started : 12/8/2017 7:21:39PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli/ Live Time : 3600.0 second§ Real Time : 3611.4 seconds Dead Time : 0.32 °1 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 : 3681 PEAK ANALYSIS REPORT Peak Analysis Performed on : 12/8/2017 8:21 :53PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/8/2017 8:22:02PM Page2of7 Analysis Report for L2-SUB-WRS-ASGS-08A-SB 12/4/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 76.04 147 - 157 152 . 62 2.46E+02 58.32 9.94E+02 3.88 F 2 185 . 61 364 - 377 371.72 7 .0lE+ Ol 32 .19 8.31E+02 1.17 M 3 238.50 474 - 489 477 .47 3 . 20E+02 44 . 62 3 .67E+02 1. 31 m 4 241.68 474 - 489 483.84 6.91E+Ol 26. 50 3.93E+ 02 1.31 F 5 294.96 584 - 605 590.37 l .13E+02 30.84 6.10E+ 02 1. 67 M 6 327.69 652 - 684 655.82 2.49E+Ol 16. 96 1.68E+ 0 2 1. 17 m 7 338.06 652 - 684 676.55 6.56E+Ol 21. 95 1. 65E+02 1. 18 F 8 351.67 695 - 708 703.77 2.09E+02 33.79 2.59E +02 1. 39 F 9 510 . 26 1014 - 1028 1020 . 88 8.32E+Ol 26 .18 l.90E +02 2 . 56 F 10 583 . 03 1162 - 1173 1166 . 40 1 .03E+02 24 .8 3 1.2 1 E+02 1. 80 F 11 609.00 1213 - 1225 1218 . 34 1 .51E+0 2 27.50 1. 16E+0 2 1. 43 F 12 767.96 1 531 - 1 541 1536.21 2.28E+Ol 14.95 7 . 59E+Ol 1. 73 F 13 910.84 1817 - 1826 1821. 92 6.88E+ Ol 19.42 5 . 00E +Ol 1. 67 F 14 968.76 1933 - 1946 1937.74 4 . 46E+O l 17.18 6.30E+O l 2.26 F 15 1460 .1 2 2912 - 2928 2920 . 35 5.31E+02 46 . 70 2 .91E+Ol 2. 45 F 16 1728. 50 34 53 - 3462 3457.06 1. 3 1 E+Ol 2.81 2 . 62E+OO 0.74 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 : 12/8/2017 8:21:53PM 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 76.04 2 . 46E+02 58 . 32 2.46E+02 5.83E+Ol F 2 185 . 6 1 7 .0 lE+O l 32 .19 7.0lE+Ol 3.22E+Ol M 3 238 . 50 3 . 20E+02 44.62 3.20E+02 4.46E+O l m 4 241. 68 6 . 91E+Ol 26 . 50 6.91E+ Ol 2.65E+Ol F 5 294.96 1.13E+02 30.84 1 . 1 3E+02 3 . 08E+O l M 6 32 7.6 9 2 . 49E+Ol 16 . 96 2 . 49E+Ol 1 . 70E+Ol m 7 338.06 6.56E+ Ol 21. 95 6.56E+Ol 2 . 19E+Ol F 8 351. 67 2.09E+02 33.79 8.36E+Ol 3 .72E+Ol 1.26E+02 5.03E+Ol F 9 510.26 8.32E+Ol 26 . 1 8 8.32E+Ol 2.62E +Ol F 10 583 . 03 1 . 03E+02 24 . 83 1.03E+02 2.48E+Ol F 11 609.00 1.51E+02 27.50 4. 1 2E+Ol 2.42E+Ol 1.10E+02 3.66E+01 F 12 767.96 2.28E+Ol 14.95 2.28E+Ol 1.50E+01 F 13 910 . 84 6.88E+Ol 19.42 6 . 88E+Ol 1.94E+O l
12/8/2017 8:22:02PM Page 3 of7 Analysis Report for L2-SUB-WRS-ASGS-08A-SB 12/4/17 Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 14 968.76 4 . 46E+01 17.18 4 .46E+Ol 1. 72E+Ol F 15 1460.12 5.31E+02 46.70 5.63E+Ol 1 . 71E+ Ol 4.74E+02 4.9 7E +Ol F 1 6 1728 . 50 l . 31E+Ol 2.81 1 .31E+01 2.81E+OO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) ,(pCilgrams) Uncertainty K-40 0.93 1 46 0.75
- 10.67 5 . 08E+OO 6.02E-01 PB- 2 1 2 0.55 77 .11 17 .50 238 . 63
- 44.60 1 .62E-Ol 2.41E- 02 BI -214 0 . 34 609 . 31
- 46 . 30 1. 25E-01 4 . 20E- 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 . 7 0 295.21
- 19.20 l.59E- Ol 4.40E-02 351.92
- 37.20 1.06E-O l 4.30E -02 RA-226 0 .94 1 86.21
- 3.28 4.0SE -01 1. 88E-01 AC-228 0 . 59 209.28 4.40 338 . 32
- 11.40 1.75E-01 5 .92E-02 794 .7 0 4.60 911. 60
- 27.70 1 .87 E-01 5.35E-02 964 . 60 5 . 20 969 . 11
- 16 .60 2 . 1 4E-01 8.30E-02
12/8/2017 8:22:02PM Page 4 of7 Analysis Report for L2-SUB-WRS-ASGS-08A-SB 12/4/17
* ;:: 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. 93 8 5. 08E+O O 6 . 0 2E -0 1 PB- 212 0 .55 8 l .6 2E-01 2 . 41E- 0 2 BI - 21 4 0.3 42 1. 2 5 E-0 1 4. 20E- 0 2 PB-2 1 4 0 . 71 3 1 . 32E- 01 3 . 0 7E- 0 2 RA- 22 6 0 .9 44 4 .05E -01 l.88E-0 1 AC- 22 8 0 . 5 91 1. 88E - 01 3 . 5 8E- 0 2
? = 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
12/8/2017 8:22:02PM Page 5 of7 Analysis Report for l2-SUB-WRS-ASGS-08A-SB 12/4/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/8/2017 8:21 :53PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 1 76.04 6.82218E-02 11.87 ~if( m 4 241. 68 l.92015E-02 19.17 ~~it\ 1..,-t~ M 6 327 .6 9 6.91299E-03 34.07 ~ F 9 510 . 26 2.31219E-02 15 .73 --r\~ F 10 583.03 2 . 85758E-02 12.07 ---n F 12 767 .9 6 6.34215E-03 32.7S 6~~ F 16 1 728.50 3 .63 359E-03 10.73 ~~ is'1
~0'~~
M = First peak in a multiplet region m = Other peak in a multiplet region I~) {?* 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 (pCilgrams) (pCilgrams) (pCi/grams) (keV) + K- 40 1460.75
- 10.67 5.08E+00 4.94E-01 4.94E-01
+ AR-41 1293 . 64 99 .16 1. 86E+15 3.26E+15 3.26E+15 + CO-60 1173.22 100.00 l.07E - 02 4. 5 7E-02 4.98E-02 1 33 2.49 100.00 -7 . 52E- 03 4.57 E- 02 + KR-85 513. 99 0 . 43 l.34E+0l 8.54E+00 8 . 54E+00 + Y-88 898 . 04 93.70 2.12E - 02 3 . 0SE- 02 4.08E-02 1836 . 06 99.20 -1.59£-02 3.0SE-02 + NB-94 702 .63 100 .00 -l.03E-03 3.28E-02 3.28E-02 871.10 100 . 00 -1. 26E-02 3.SSE-02
12/8/2017 8:22:02PM Page 6 of7 Analysis Report for L2-SUB-WRS-ASGS-08A-SB 12/4/17 Nuclide Energy Yield{%} Activity NuclideMDA Line MDA Name (pCilgrams} (pCilgrams) (pCilgrams) (keV} + I-131 284 .30 6.06 - 3 . 61E- 0 1 4.89'E-02 6 .2 6E-01 364. 48 81. 20 1.B lE-02 4.89E-02 636 . 97 7.27 4.lBE-0 1 6 . 24E - 0 1 + CS - 134 604 . 70 97.60 -2 . 02 E-02 4.28E- 02 4 .38E-02 795.84 85.40 2 .5 7E- 02 4.28E-02 + CS-137 661. 65 85.12 6.54E-02 4 . 6 1 E- 02 4.61E-02 + CE - 144 80.12 1. 36 -4.28 E+ OO 2.31 E- 01 2.92E+OO 133. 51 11.09 1.42E-0 1 2.31E-0 1 + EU-152 121. 7 8 28.40 -4 . 90E-0 2 8 . 63E-02 8 . 63E-02 244 . 69 7.49 -7.1 7 E-03 4 .21E- 0 1 964 .00 14 .44 -1.39E- 0 1 3 . 48E - 0 1 1408.00 20.74 5.95E-02 1. 81E - 0 1 + EU- 1 54 12 3 .0 7 40.40 1. 58E-02 6. 1 4E-02 6 . 14E-02 247.94 6.6 0 2.27£ -01 4 . 27E - 01 72 3.30 1 9.70 -3. 96E- 02 1 . 78E - 01 873.20 11. 50 -2 . 55E- 0 1 3.0SE-01 1 004 . 7 6 17.90 -1. 5 5E- 02 2 .lOE-01 1274 . 51 35 . 50 4.80 E-02 l.31E-01 + EU- 1 55 86.54 32.80 -2 .1 2E-02 1.0lE- 01 1. OlE-01 1 05 . 31 21. 80 6.19E-03 l . 2 5E-01 + BI-2 14 609 . 3 1
- 46.30 1 . 25E-01 7.1 8 E-02 7 . lBE-02 1120. 29 1 5.1 0 2 . 8 1 E-02 3 . 29E - Ol 1238 . 11 5.94 8. 1 9E-O l 9 . 46E-01 1377 . 67 4 .11 6.87E-0 1 9.83E-01 1407 . 98 2.48 4 .98E-0 1 1. S l E+OO 1 509 . 1 9 2 .19 - 2. 82£-01 1. 29E+OO 1764.49 15. 80 5 . 84E-02 2.31E-01
+ PB-214 77 . 11 10. 70 4 . 91E-01 8 . 06E-02 3.84E- 01 295 . 21
- 19.20 1. 59E-Ol 1 . 6 1£-01 35 1. 92
- 37 . 20 1. 06E- 01 8 . 06E-02
+ PA- 2 2 8 89 .95 22.00 5 . 31 E+OO 2 .16E+OO 3 . 70 E+OO 93 . 35 3 5.00 - 6.llE-01 2. 1 6E+OO 105.00 16.30 - 6.63E-01 4. 20E+OO 1 29 . 22 2.97 -6 . 47E-0 1 2.09E+O l 338 . 32 5.30 -1.41E+ OO 1.35E+Ol 463.0 0 13.80 1 .69E+ OO 5.46E+ OO 911. 23 16.70 8.52E+ OO 6 . 96E+ OO + AM-241 59 . 54 36 . 3 0 -1.31 E-02 l .8 1 E-01 l. Bl E-0 1 + CM- 243 103.76 23.00 1.28E-02 1.19E-Ol 1. 1 9E- 0 1 228.18 10 .60 - 2 . lBE-0 1 2 . 26E -0 1 277.60 1 4.00 - 2.61E-02 1. 89E-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 wi1h Currie MDA at 95% confidence level
1218/2017 8:22:02PM Page 7 of7 Analysis Report for L2-SUB-WRS-ASGS-08A-SB 12/4/17
12/8/2017 8A9:52AM Page J of7 ~~~~pex-Gamma Analysis Report for L2-SUB-WRS-ASGS-09A-SB 12/4/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-ASGS-09A-SB Sample Description Sample Type
- 1214111 I
- 500 ml Marinelli Unit Sample Point Sample Size 8.239E+02 grams Facility : Dairyland_NPP Sample Taken On : 12/4/2017 2:04:00PM /
Acquisition Started : 12/8/2017 7:49:29AM Procedure : 500ml Marinelli/ Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 3600.0 seconds / Real Time : 3611.4 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 : 3671 PEAK ANALYSIS REPORT Peak Analysis Performed on 12/8/2017 8:49:43AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/8/2017 8:49:52AM Page2 of? Analysis Report for L2-SUB-WRS-ASGS-09A-SB 12/4/1 7 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM (keV) start end Centroid Area Uncertainty Counts (keV) No. F 1 76 . 98 147 - 161 154.50 l .93E+02 46.99 1. 54 E+03 1. 26 F 2 185 . 51 3 63 - 3 76 371 . 52 9 .27E +Ol 39 . 11 9 . 21E+02 1. 65 M 3 238 . 53 474 - 489 477 . 54 3 .74E+02 47 .67 3,88E+02 1. 35 m 4 24 1. 8 4 474 - 489 484.1 5 1.14E+02 29 .4 6 3 . 56E+02 1. 35 F 5 2 95.01 585 - 594 590 . 47 1.36E+0 2 31. 36 3 . 0 2E+02 1. 34 M 6 328. 23 653 - 685 656 . 90 3 . 24E+O l 21. 56 2 . 39E+ 02 1. 63 m 7 338.18 653 - 685 676 . 79 l.03E+02 28.53 2 . 48E+ 02 1. 6 4 F 8 351 . 78 695 - 710 703.98 2 . 18E+02 35.11 3 . 20E+02 1. 64 F 9 462.97 921 - 9 30 926 . 33 3 . 05E+ Ol 19 . 17 l . 62E+02 1. 42 E' 10 583 . 12 11 62 - 1171 1166 . 5 8 1. 28E+02 27 . 19 1.14E+02 1. 75 F 11 609 . 07 1213 - 1225 1218.48 1. 70E+02 29 . 78 1. 56E+ 02 1. 48 F 12 661 . 32 1317 - 1 327 1322. 95 l . 54E+02 2 8 . 80 l.43E+02 1. 4 6 F 13 910 . 46 1817 - 1828 1821.16 8.03E+ Ol 21.16 7 .8 0E+ Ol 1. 8 5 F 14 968.47 1932 - 1942 1937 . 17 3 . 40E+01 15.86 9 .87E+Ol 1. 22 F 15 11 20. 07 2236 - 2246 22 40 . 32 2.89E+Ol 15 . 43 1. 03E+02 1.17 F 16 1460.24 2912 - 2929 2920.58 6 . 89E+02 53.57 2 . 66E+Ol 2 . 23 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 : 12/8/2017 8:49:43AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted (keV) Area Uncertainty Background Uncert. Area Uncert. No. F 1 76 . 98 1. 93E+02 46.99 1.93E+02 4. 70E+ Ol F 2 185 . 51 9.27E+Ol 39 . 11 9 . 27E+ Ol 3.91E+ Ol M 3 238 . 53 3.74E+02 47.67 3.74E +02 4.77E+O l m 4 24 1. 8 4 1 . 14E+02 29 . 46 l . 14E+02 2 . 95E+O l F 5 295.0 1 1. 36E+02 31 . 36 l . 36E+02 3.1 4E+Ol M 6 328 . 23 3 .24 E+ Ol 21. 56 3 . 24E+Ol 2.16E+ Ol m 7 338 . 18 l.03E+02 28 . 53 l. 03E+02 2.85E+O l F 8 351. 78 2 .1 8E+02 35.11 8 . 36E+Ol 3 . 72E +Ol 1. 35E+02 5.12E+O l F 9 462.97 3.0SE+Ol 19.17 3. 0SE+ Ol 1.92E+ Ol F 10 58 3.12 1 .28E+02 27.19 1. 28E+02 2.72E +01 F 11 609 .0 7 1.70E+02 29 . 78 4.12E+ Ol 2.42E+O l 1 .2 9E+02 3 .84 E+Ol F 12 661. 32 1.54E+ 02 28 . 80 6 . 61E+Ol 2 .5 4E +Ol 8 . 76E+O l 3 .84 E+Ol F 13 910 .4 6 8.03E+Ol 21. 16 8 . 03E+Ol 2. 12E+Ol
12/8/2017 8:49:52AM Page 3 of7 Analysis Report for L2-SUB-WRS-ASGS-09A-SB 12/4/17 Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 14 968.4 7 3 . 40E+ Ol 15.86 3 . 40E+Ol 1. 59E+Ol F 15 1120 . 07 2 . 89E+Ol 15.4 3 2 . 89E+Ol l .54E+ Ol F 16 14 60.24 6.89E +02 53.57 5. 63E+Ol l.71E+Ol 6.32£+ 02 5.62E +Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K- 40 0 . 95 1 460. 75
- 1 0.67 8.36E+ OO 8 . 76E- 01 CS-137 0 . 98 661 . 65
- 85 . 12 7 .18E- 02 3 . 17E-02 PB-212 0 . 99 77 . 11
- 17.50 3 . 31E - Ol 8 . 3 4E - 02 238 . 63
- 4 4 .60 2 . 34E- 01 3 .2 2E-02 BI - 214 0 . 57 609 . 31
- 46. 30 1.80E- 0 1 5 .4 6E - 02 1 1 20 . 29
- 15.10 2 . 14E- 01 l.15E-01 1238 . 11 5 . 94 1 377 . 67 4.11 1 40 7 .98 2 .4 8 1509.19 2.19 1764 . 49 1 5 . 80 PB -214 0.99 77 . 11
- 10 .7 0 5.42£-0 1 1. 36E-01 29 5 . 21
- 1 9 . 20 2. 35E-01 5 . 56E-0 2 351 . 92
- 37.20 l.41E- 01 5 . 41E- 02 RA-22 6 0 . 92 186.21
- 3.28 6 . 63E-01 2 . 82 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
12/8/2017 8:49:52AM Page4 of7 Analysis Report for L2-SUB-WRS-ASGS-09A-SB 12/4/17 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) rc- 40 0 . 959 8.36E+OO 8 . 76E-01 S-137 0 . 982 7. 1 8E- 02 3 . 17E-02 PB-2 1 2 0 . 998 2.32E- 01 3 .02E-0 2 BI-214 0 . 5 79 1. 8 6E-01 4 . 93E-02 PB-214 0 . 996 1. 85E- 0 1 3 .7 5E-02 RA-226 0 . 924 6 . 63£- 01 2.82E-01
? = nuclide is part of an undetermined solution X = nuclide rej ected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
12/8/2017 8:49:52AM Page 5 of7 Analysis Report for L2-SUB-WRS-ASGS-09A-SB 12/4/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/8/2017 8:49:43AM 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 4 241 . 84 3 . 16855E- 02 12.91 ~~it{ M 6 328.23 8 . 99155E -03 33.30
~'1.,'91 m 7 338 . 18 2.85991£- 02 13 .86 Tol. AC-228 PA-228
/J~l.x
\ ~
F 9 4 62 . 97 8.47322E-03 31. 41 Tol. SB -1 {/'> f\o1Y 28 10 ~--i,cl 'l,1-'i
~h-~'
f 583.12 3.56609E-02 10.59 f 13 910 .4 6 2.23168E-02 13 . 17 Tol. P 28 F 14 968.47 9.45489E-03 23.30 Tel. 11.J/\ AC-228,./
=
M First peak in a multiplet region
=
m Other peak in a multiplet region C)=o-~~ F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCi/grams) (keV) + K-40 1460 . 75
- 10 .67 8.36E+OO 6.07£- 01 6.07£- 01
+ AR-41 1293.64 99 . 16 2 . 27E+l3 4 . 32E+13 4.32E+ l 3
12/8/2017 8:49:52AM Page 6 of7 Analysis Report for L2-SUB-WRS-ASGS-09A-SB 12/4/17 Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCi/grams) (pCilgrams) (keV) + CO-60 1173 . 22 100.00 1.1 7E - 02 6.2 1E-0 2 7.06E-02 1332 . 49 100 . 00 3.23E- 02 6.21E-02 + KR-85 513 . 99 0 . 43 1.19E+0l 1. l l E+0l 1. llE+0 l + Y- 88 898 . 04 93 . 70 7.08£-02 3 .86E -02 5 . 73E-02 1836.06 99 . 20 5 . 2 4E-03 3.86E-02 + NB- 94 702 .6 3 100. 00 3 . 55E- 02 4. 58E-02 4. 58E-02 87 1 . 1 0 100.00 -4.14E - 02 5 . 19E-02 + I - 131 284 . 30 6. 06 -4.80E - 01 5 . 84E -02 7.64E-0 1 36 4 . 48 81 . 20 3 . 12E-02 5.8 4E -02 636 .9 7 7.27 -4 . 03E-01 7 . 58E-01 + CS- 134 604 . 70 97.60 5 . 31E-03 5.43E-02 5 . 9 4E-0 2 795.84 85 . 40 - 4 . 16E- 03 5 .4 3E -0 2 + CS-137 661 . 65
- 85.12 7 . 18E-02 S . 60E-02 5 . 60E - 02
+ CE-144 80.12 1. 36 - 6.31E-01 2 . 95E-0 1 3 . 71E+00 133. 5 1 11.09 4.64E-02 2 . 95E- 01 + EU- 152 1 21.78 28 . 4 0 - 1 . llE - 01 l.1 2E- 01 l . 12E- 01 24 4.6 9 7 . 49 - 8 . 47E-03 5.62E- 0 1 964.00 14. 44 2 . 92E-01 4.24E - 01 1408.00 20.74 - 1.52E-01 2 . 02E - 0 l + EU - 154 123 .0 7 40 . 40 - 9.81E-03 7 .95E-02 7 . 95E-02 247 . 94 6 . 60 - 4.20E- 02 5 . SlE- 01 72 3 . 30 19 . 70 1. 21E -0 1 2.36E-01 873 . 20 11. 50 2 . 22E-01 4.6 0E - 01 1 004 . 76 1 7 . 90 -1. 06E- 01 2.85E-01 1 274.5 1 35 . 5 0 -8 .58 E- 02 l.67E-0 1
+ EU- 155 86 . 54 32.80 7 . 36E-02 1.28E-01 1. 28E-01 105.31 21. 80 -5 .0lE- 02 1.S 0E -01 + BI - 214 609 . 31
- 4 6 . 30 l . 80E- 0 1 9. S lE - 02 9 . SlE-02 1120 . 29
- 15. 1 0 2 .14E-01 2 . 93E- 01 1238 . 11 5.94 7 . 20E-0 1 1 . 32E+0 0 137 7.6 7 4 . 11 4.73E-01 1 . 19E+00 1407 . 98 2 . 48 - 1 .2 7E+0 0 l . 69E+00 1509 . 1 9 2 . 19 1. 93E+00 2 . 25E+ 00 1 764 . 49 15 . 80 2 . 31E - 0 1 3.24 E-01
+ PB- 214 77.11
- 10.70 5 . 42E- 0 1 1 . 07E-01 4 .44 E- 01 295.2 1
- 19.20 2.35E- 0 1 1. l 0E-01 351 . 92
- 37.20 1.41E- 0 1 1. 07E- 01
+ PA- 228 89 . 95 22 .00 9 . 55E- 0 1 1. 85E+ 00 3.lSE+0 0 93.3 5 35 . 00 - 7.51E -01 1. 85E+00 105. 00 16 . 30 -3 .4 6E-0 1 3.47E+00 129. 22 2.97 2 . 99E+0 0 1.87E+0l 338 .3 2 5.30 l . 71E+0 0 1 . 2 6E+0l 463 . 00 13. 80 1. 72E+00 5.00E+00 911.23 16 . 70 3.21E+00 6 . 71E+ 0 0 + AM-241 59.54 36.30 -2 . 12E-01 2 . 33E-01 2 .33E-01 + CM- 243 103. 76 23 . 00 2 . 28E-03 1. 45E- 01 1.45E- 0 1 228. 18 10.60 -1.55E - 0 1 3 .14E-01 277.60 14 . 00 l .34E- 01 2 .5 4E- 0 1
12/8/2017 8:49:52AM Page 7 of7 Analysis Report for L2-SUB-WRS-ASGS-09A-SB 12/4/17
+ = 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
12/8/2017 9:52:31AM Page l of7 pex-Gamma Analysis Report for L2-SUB-WRS-ASGS-1 0A-SB 12/4/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-ASG,- 0A-SB Sample Description : 12/4/17 Sample Type : 500 ml Marinelli . Unit Sample Point Sample Size 6.TT6E+02 grams Facility : Dairyland_NPP Sample Taken On : 12/4/2017 2:37:00PM Acquisition Started : 12/8/2017 8:52:08AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB / Geometry : 500ml Marinelli / Live Time : 3600.0 seconds Real Time : 3611.8 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 : 3672 PEAK ANALYSIS REPORT Peak Analysis Performed on : 12/8/2017 9:52:22AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/8/201 7 9:52:31AM Page2 of7 Analysis Report for L2-SUB-WRS-ASGS-1 0A-SB 12/4/17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM (keV) start end Centroid Area Uncertainty Counts (keV) No. F 1 76.90 147 - 157 154.35 2.17E+02 49. 7 4 1. 27E+03 1. 21 F 2 186.04 369 - 376 372.58 8.06E+Ol 31. 98 5.13E+02 1.03 M 3 238.45 4 70 - 491 477.38 5.00E+02 52 .29 3 . 92E+02 1. 36 m 4 241.47 470 - 491 483 .41 l.31E+02 30.59 3.63E+02 1. 37 M 5 295.03 587 - 606 590.51 l.19E+02 27 . 80 2 . 46E+02 0.87 m 6 299.90 587 - 606 600.26 2.99E+ Ol 17 . 59 l.85E+02 0.87 F 7 338.20 672 - 685 676.83 8.02E+ Ol 26.73 4 .31 E+02 1.19 F 8 351.72 698 - 708 703.86 2.69E+ 02 38.81 2.84E+02 1. 32 F 9 582.91 11 59 - 1171 1166.17 1 .23E+02 25.52 1 . 39E+02 1. 33 F 10 609.12 12 1 3 - 1225 1218.57 1. 86E+02 30.89 l.66E+ 02 1. 44 F 11 661. 36 1 318 - 1328 1 323 .04 l. 79E+02 30. 1 2 1.14E+ 02 1. 57 F 12 726 . 51 1448 - 1457 145 3 . 32 2.90E+Ol 1 6.40 9.24E+Ol 1. 44 F 13 910.78 1816 - 1828 1821.80 9. 1 6E+Ol 23.75 1. 28E+02 1. 76 F 14 968.78 1 933 - 1943 1937.78 4.57E+Ol 19.76 1. 20E+02 1. 71 F 15 1119.77 2234 - 2247 2239.72 4 .79E+Ol 18.50 7 . 74 E+Ol 2 . 56 F 16 14 60.29 2912 - 293 1 2920.69 6.93E+02 53.89 3.73E+Ol 2.33 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 : 12/8/2017 9:52:22AM 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 76.90 2.17E+ 02 49.74 2.17E+02 4. 97E+Ol F 2 186.04 8.06E+ Ol 3 1 .98 8 . 06E+Ol 3.20E+01 M 3 238.45 5 . 00E+02 52.29 5 .00E+02 5.23 E+ Ol m 4 241.47 l . 31E+02 30 . 59 1. 3 1 E+ 02 3 . 06E+O l M 5 295. 03 1. 19E+02 27.80 1 .19E+ 02 2 .78E +Ol m 6 299.90 2 . 99E+Ol 17 . 59 2 . 99E+ Ol 1.76E+ Ol F 7 338.20 8.02E+Ol 26.73 8.02E+Ol 2.67E+Ol F 8 35 1. 72 2.69E+02 38.81 8.36E+ Ol 3 . 72E+Ol 1.85E+02 5.38E+Ol F 9 582 .91 1.23E+02 25 . 52 1 . 23E+02 2.55E+Ol F 10 609.12 l .8 6E+02 30 . 89 4 .12E+ Ol 2.42E+Ol 1 .4 5E +02 3 . 92E+O l F 11 661. 36 1 .79E+02 30 . 12 6.61E+Ol 2.54E+ Ol 1 . 13E+02 3.94E+Ol F 12 726.51 2 . 90E+Ol 16.40 2.90E+Ol l .64E+O l F 13 910 .78 9.16E+Ol 23.75 9.16E+Ol 2.37E+Ol
12/8/2017 9:52:31 AM Page 3 of7 Analysis Report for L2-SUB-WRS-ASGS-1 0A-SB 12/4/17 Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 14 968 . 78 4 . 57 E+Ol 19 . 76 4 .5 7E+O l 1. 98E+O l F 15 111 9 . 77 4. 79E+Ol 18 . 50 4 . 79E+ Ol 1.85E+Ol F 16 14 60.29 6 . 93E+02 53 . 8 9 5.63 E+Ol 1 . 71E+ Ol 6 . 37E+02 5 . 65E+ Ol M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairyland_NPP\library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K-40 0.96 1460. 7 5
- 10 . 67 l. 0 2E+Ol l . 07E+OO CS- 137 0 . 98 661 . 65
- 8 5 . 12 1 . 12E-Ol 3. 97E - 02 BI - 212 0 . 55 727 .1 7
- 1 1. 80 2 . 2 7E- 0 1 1. 29E - 01 78 5. 42 2 . 00 162 0. 56 2 . 75 PB-21 2 0 .9 9 77 .11
- 1 7. 50 4. 53E- 0 1 1 . 08E- 01 238 . 63
- 44 . 60 3.80E- 0 1 4. 44E- 02 BI - 2 1 4 0 . 57 60 9. 31
- 46 . 30 2 .4 6E-Ol 6 . 81E- 02 112 0. 29
- 15 . 1 0 4 . 32E- 01 1. 68E- 0 1 1 238 . 11 5 . 94 1377 . 67 4 .11 1407 . 98 2.48 1509.1 9 2.19 17 64. 4 9 15 . 80 PB- 214 0 . 99 7 7. 11
- 10 . 70 7 .41E - 0 1 1. 76E- 01 29 5. 21
- 19 . 20 2. SlE-01 5 . 99E-02 351. 92
- 37 . 2 0 2. 36E - 01 6 . 95E-02 RA-226 0 . 99 186 . 21
- 3 . 28 7. 02E- 0 1 2 . 81E - 01 AC-228 0 . 58 2 0 9.28 4 . 40 338 . 32
- 11. 40 3 . 22E- 0 1 1 .0 8E-0 1 794 . 70 4. 60 911. 60
- 27.70 3.75 E-01 9 . 85E-0 2 964.60 5 .2 0 969 . 11
- 1 6.6 0 3 . 30E -0 1 1 . 4 3E- 0 1
12/8/2017 9:52:31AM Page4 of7 Analysis Report for L2-SUB-WRS-ASGS-10A-SB 12/4/17
* = 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 0.967 l. 02E+0 l l.07E+00 CS-137 0 .98 7 1. 12 E-01 3.97E-02 BI-212 0. 557 2 . 27E- 01 l.29E-01 PB-2 1 2 0.9 95 3.70E-01 4 . 1 2E-02 BI-2 14 0.575 2 . 7 2E-01 6.31E-02 PB- 214 0.994 2 . 38E-0 1 4.4 1E-02 RA-226 0.995 7.0 2E-01 2.81E - 01 AC- 228 0.587 3.4 6E-01 6.S0E-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
12/8/2017 9:52:31 AM Page 5 of7 Analysis Report for L2-SUB-WRS-ASGS-1 0A-SB 12/4/ 17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/8/2017 9:52:22AM 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 4 2 41. 4 7 3 . 64 608£- 02 11. 65 m 6 29 9 .90 8.3 138 9E-03 29 . 38 F 9 5 82 .91 3 . 40770E-02 10. 4 0 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) (pCilgrams) (pCi/grams) (keV) + K-40 1460 . 75
- 1 0 . 67 1. 02E+0l 7 .78E -0 1 7 . 78E -01
+ AR-41 1 2 93. 64 99 .1 6 - 2 . 02E +1 3 5 .98E+13 5 . 98 E+1 3 + CO-60 1173. 22 1 00 . 00 -l . 45E - 02 7.74 E- 02 8 . 59E-0 2 1332 . 49 1 0 0.00 7.66E-02 7 . 74E -0 2 + KR- 85 5 1 3 . 99 0 . 43 1 . 93E+0 l 1. 3 2E+0 l l.32E+0 l + Y- 88 898 . 04 93 . 70 4 .8 9E-02 3 .57E - 02 6.97E - 02 1 836 . 06 99 . 20 - 2 . 68E- 0 3 3. 57E - 02 + NB- 94 70 2 . 63 1 00 . 00 6 . ll E- 0 3 5 . 37E-0 2 5 . 3 7E - 02 87 1 . 1 0 1 00 . 00 -1. 52E - 02 5.9 4E-02 + I - 131 284 . 3 0 6 . 06 8 . 56E-02 7 . 32E-0 2 9 . 7 9E-0 1 36 4. 48 8 1. 20 - 2. 05E - 02 7 . 32E - 02 636 . 97 7 .27 5 . 93E-01 9 . 90E - 0 1
12/8/2017 9:52:31AM Page6 of7 Analysis Report for L2-SUB-WRS-ASGS-1 OA-SB 12/4/17 Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCi/grams) (pCilgrams) (keV) + CS- 134 604 . 70 97.60 -2 . 97E-02 7 .06E-02 7 . 36E- 02 795.84 85.40 -7.65E-0 3 7.06E- 02 + CS- 137 661.65
- 85 .1 2 1.12E-0 1 6 . 53E-02 6.53E-02
+ CE-144 80.12 1. 36 -8 . 50E+OO 3 . 59E-Ol 4 . 76E+O O 133 . 51 11 . 09 8.62E-0 2 3.59E-01 + EU- 152 121 . 78 28 . 40 -4 .83E-0 2 1 . 38E- 0 1 l. 38E-01 2 44.69 7.49 8 . 99E -0 2 7. 12E-01 964.00 14. 44 5.29E-01 5. 71E -01 1 408 .00 20.74 -4. 26E-03 2.80E- 01 + EU- 154 123 .07 4 0. 40 -8.3 1E-02 9.67E - 02 9.67E-02 247.94 6 . 60 -l. 14E- 01 6.7 5E - 01 723 . 30 19 . 70 5.88E- 02 3.04E- 0 1 873.20 11. 50 -1.83E- 01 5. 18E-01 1004 . 76 17 . 90 -9.72E- 02 3.48E-01 1274.51 35.50 -3 . 78E-02 2.19E- 01 + EU- 155 86 .54 32 . 80 - l.54 E-0 1 1. 60E - 0 1 1. 6 0E-01 105.31 2 1. 80 4.30E-02 1. 93E - 0 1 + BI-214 609.31
- 4 6 . 30 2.46E-0 1 1 .18E- 0 1 l . 1 8E-0 1 1120.29
- 15.10 4 . 32E- 01 3 . 32E-01 1238 . 11 5 . 94 1.40E- 01 1. 54E+OO 1377 . 67 4 . 11 2.92E- 01 1.66E+OO 1407.98 2 . 48 - 3 . 56E- 02 2.34E+OO 1509 . 19 2 . 19 2.16E+OO 2. 47E+OO 1764.49 15 . 80 4 . 17E- 01 3 . 99E-0 1
+ PB-214 77 . 11
- 10 .7 0 7 . 41E-01 l.15E-01 4 . 46E- 01 295 .2 1
- 19 .20 2 . 51E- 0 1 1 . lSE - 0 1 351.92
- 37 .20 2.36E- 0 1 1. 20E - 01
+ PA- 228 89 . 95 22 .00 8 . 90E +OO 2 . 40E+ OO 4 .l OE +OO 93.35 35.00 8 .44 E- 0 1 2.4 0E+OO 105 . 00 16.30 6 . 08E-01 4.49E+OO 129 . 22 2.97 9.85E+OO 2.32E+01 338 . 32 5 . 30 l .55E+O l 1 .59E+Ol 463 . 00 13.80 1 .48E+OO 6 . 25E+OO 911 . 23 16 . 70 1.88E+Ol 8 . 75E+OO + AM- 241 59.54 36 . 30 1. 60E -O l 2 . 94E - 01 2.94E-0 1 + CM-243 103. 7 6 23 .00 1 .2 0E-01 l . 85E- 01 1 . BSE-01 228.1 8 1 0 .6 0 l.58E-02 3.81E-01 277.60 1 4 .00 9 .34E -02 3.18E-0 1
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
12/8/2017 9:52:31AM Page 7 of7 Analysis Report for l2-SUB-WRS-ASGS-10A-SB 12/4/17
121712017 6:34:29PM Page I of7 ~ ~~~pex-Gamma Analysis Report for L2-SUB-WRS-ASGS-11A-SB L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 GAMMA SPECTRUM ANALYS/S Sample Identification : L2-SUB-WRS-ASG&-11A-SB Sample Description : L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 1.021 E+03 grams/ Facility : Dairyland_NPP Sample Taken On : 12/4/2017 1:36:00PM Acquisition Started : 121712017 5:34:05PM Procedure : 500ml Marinelli/ Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli / Live Time : 3600.0 seconds Real Time : 3611.5 seconds Dead Time : 0.32 % 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 : 3665 PEAK ANALYS/S REPORT Peak Analysis Performed on 12n/2017 6:34:20PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/7/2017 6:34:29PM Page2 of7 Analysis Report for L2-SUB-WRS-ASGS-11 A-SB L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM (keV) start end Centroid Area Uncertainty Counts (keV) No. F 1 76.83 147 - 1 59 1 54.21 l . 7 1 E+02 4 3 .87 l.14 E+03 1. 31 F 2 238 . 53 474 - 48 1 477 . 53 2 . 79E+ 02 44.48 4.69E+02 1. 18 F 3 270. 53 5 37 - 5 45 541. 52 3 . 94E+ Ol 23.22 2 . 69E+02 1.23
- F 4 295 .04 586 - 59 5 59 0. 54 1.17E+02 30 . 38 3 .1 3E +02 1.33 F 5 338.37 674 - 685 677 .1 8 5 . 39E+O l 21. 65 2.38E+02 1.11 F 6 35 1. 73 699 - 709 703 .8 9 l . 79E+02 31. 94 l. 92E+02 1.51 F 7 583.00 1162 - 1172 1166.33 9 . 02E +Ol 23.02 9.90E+01 1. 66 F 8 608.94 1 213 - 1223 1218 . 22 1 . 10E+02 25 .20 1.13E+0 2 1. 61 F 9 911 . 07 1 816 - 1829 1 822.37 7.0 lE+O l 20 . 17 9.31E+Ol 1. 68 F 10 1119 . 82 2235 - 2244 2239 . 82 2.87E+Ol 14 . 54 S.22E+Ol 1.59 F 11 1460. 36 29 1 2 - 2929 2920 .84 4.67E+02 43 . 46 1. 34E+Ol 2 . 44 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 : 12/7/2017 6:34:20PM 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 76.83 l . 71E+02 43.87 1.71E+02 4 . 39E+Ol F 2 238 .53 2 . 79E +02 44 .4 8 2 . 79E+ 02 4 . 45E+Ol F 3 270.53 3 .94 E+Ol 23.22 3 . 94E +Ol 2.32E+Ol F 4 295.04 l.17E+02 30 . 38 1.17E+02 3.04E+Ol F 5 338 .37 5.39E+O l 21.65 5.39E+Ol 2 .1 6E+Ol F 6 351 .7 3 1.79E+02 31. 9 4 8.36E+ Ol 3 .7 2E +Ol 9 . 58E+ Ol 4.90E+Ol F 7 583 . 00 9.02E+ Ol 23 .0 2 9.02E+ Ol 2.30E+Ol F' 8 608 . 94 1.1 0E+02 25 .2 0 4. 12E+Ol 2.42E+Ol 6.87E+O l 3 . SOE+Ol F 9 911.07 7.0lE+Ol 20. 1 7 7.0 lE+ Ol 2.02E+Ol F 10 1119.82 2 . 87E +Ol 14. 5 4 2 . 87E +Ol 1. 45E+Ol F 11 1460. 36 4 . 67E+02 43 . 4 6 5.63E+O l 1. 7 1E +Ol 4 . 1 0E+ 02 4.67 E+O l M =First peak in a multiplet region m =Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma
1217/2017 6:34:29PM Page 3 of7 Analysis Report for L2-SUB-WRS-ASGS-11A-SB L2-011-101/ PACKAGE# L2--SUB-WRS (A) RA 12/07/17 NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K- 40 0.97 1460.75
- 1 0.67 4.38E +OO 5.55E-O l PB-212 0.99 77 . 11
- 17.50 2.38E-01 6.28E-02 238 . 63
- 44.60 1. 41 E-0 1 2.36E-02 BI-214 0 .56 609.31
- 46.30 7.75E-02 3 . 97E- 02 1120. 29
- 15.10 1. 72E - 01 8.74E-02 123 8 .11 5.94 1377 . 67 4 .11 1407 . 98 2 . 48 1509.19 2.19 1764.49 15 . 80 PB-214 0 . 99 77 . 11
- 10.70 3 . 89E- 01 1. 03E-01 295.21
- 19.20 1. 64E-0 1 4 .33E- 02 351.92
- 37.20 8. ll E-02 4.17E-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-40 0.976 4.38E+O O 5.SSE-01
12/7/2017 6:34:29PM Page4 of? Analysis Report for L2-SUB-WRS-ASGS-11A-SB L2-011 -101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) PB-212 0 .995 1. 44E-0 1 2.22E-02 BI -2 14 0 .5 69 9 . 36E- 02 3.61E- 02 PB- 214 0.994 1.24E-01 2.9 0E-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
12/7/2017 6:34:29PM Page 5 of7 Analysis Report for L2-SUB-WRS-ASGS-11 A-SB L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/7/2017 6:34:20PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peale CPS (%) Peak Tolerance Peak No. Energy (ke V) Peak Size (CPS) Uncertainty Type Nuclide F 3 2 7 0.53 1.09407£-02 29 .48 ~(.;.,_ F 5 338 . 37 l.4965 7E-02 20.09 Tol. AC-228 . / PA-228 F 7 583.00 2 . 506 44E- 02 12 . 76 ;f}t;Q~/ F 9 911. 07 l.94664E-02 14. 39 Tol. AC-228 PA-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCl/grams) (pCi/grams) (pCilgrams) (keV) + K- 40 1 460 . 75
- 10 . 67 4.38E+00 4 . 61E-01 4.6 1E-01
+ AR-41 1293. 64 99 . 16 1 . 43E+ 1 0 1 .61E+ ll 1.61E+ll + CO-60 1173.22 100.00 1. 40E-02 4.70E-02 5.35E-02 1332.49 100 . 00 3.72E-02 4 . 70E-02 + KR-85 5 13.99 0 . 43 l. llE+0 l 8 . 12E+ 00 8 . 12E+00 + Y- 88 898.04 93.70 -2.00E-02 2 . 85E-02 3.97E-02 1836 . 06 99.20 -3.09E-03 2 . 85E-02 + NB- 94 702.63 1 00.00 7.58£- 03 3.14E-02 3 .1 4E-02 87 1 . 1 0 1 00 . 00 l . 40E - 02 3 . 71E-02
12rl/2017 6:34:29PM Page6 of7 Analysis Report for l2-SUB-WRS-ASGS-11 A-SB L2-011 -101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCi/grams) (pCilgrams) (keV) + I-131 284 . 30 6.06 8.74E - 02 4 . 27E-02 5.71E- 01 364 . 48 81.20 2.04 E-0 3 4.27E - 02 636.97 7 .2 7 5.20E - 01 5.69E- 01 + CS-134 604.70 97.60 5.62E-02 4.00E-02 4 .0 7E- 02 795.84 85 .4 0 1.41E- 02 4 . 00E-02 + CS-137 661. 65 85.12 5.98E-02 4.74E-02 4.74E - 0 2 + CE- 144 80.12 1.36 -1.19E+OO 2.29E-01 2 . 78E+ OO 133 .51 11.09 5.00E- 02 2.29E-01 + EU- 152 121.78 28 . 40 - 5 .61E-0 2 8. 92E- 02 8.92E-02 244.69 7 .49 -9.65E- 01 4.21E - 01 964.00 14 . 44 7 . 96E- 03 2.85E-01 1408 . 00 20 .74 7 . 28E-02 1. 59E-0 1 + EU-15 4 123 .07 40.40 -2.33 E-02 6.31E-02 6.31E- 02 247.94 6 . 60 -1.84E+OO 4.14 E-01 723.30 19 .70 - 7.52E-02 1.68E-0 1 873.20 11. 50 7.54E-02 3.16E-0 1 1004.76 17.90 3.19E-02 2.15E - 01 1274.51 35.50 9 . 31E-02 l.31E-0 1 + EU-155 86.54 32.80 -5 . 12E-02 9.69E-02 9.69E - 02 105 . 31 21. 80 - 4.33E-02 1. 17E- 01 + B1-214 609.31
- 46. 30 7 . 75E-02 6 . 97E-02 6.97 E-02 1120.29
- 15.10 1 .72E-Ol 1. 71E- 01 1238.11 5.94 5.36E-01 8 . 92E-01 1377.67 4 .11 -2.41E- 01 8 . 47E-01 1407.98 2.48 6.0BE-01 l.33 E+OO 1509.19 2.19 2 . 41E-Ol 1.3 9E+OO 1764.49 15.80 1 . 92E-01 2.49E-01
+ PB-214 77 . 11
- 10.70 3 .8 9E-01 7.39E- 02 2 . 95E-01 295.2 1
- 19 . 20 1.64E- Ol 9 . 07E - 02 351. 92
- 37 . 20 8 . llE- 02 7.39E-02
+ PA-228 89.95 22 . 00 1.63E+OO 9 . 31E-01 l.58E+OO 93.35 35 . 00 1. 84E-01 9.3 1E-0 1 105.00 16 . 30 - 6.66E-01 1 . 73E+OO 129 . 22 2.97 1.21E+OO 9.40E+OO 338.32 5 . 30 4.67 E+OO 5 . 89E+OO 463 . 00 13.80 2.04E+OO 2 . 39E+OO 911.23 16 . 70 5.43E+OO 3.2 4E+ OO + AM-241 59.5 4 36 . 30 -l.25E-03 1 .80E-0 1 1 . 80E-01 + CM- 243 103.76 23 . 00 - 6.28E - 02 1 . llE-01 1 . llE -0 1 228.18 10 . 60 - 2.12E-01 2 . 33E-01 277.60 1 4 . 00 - 3.18E-02 1. 90E-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
12/7/2017 6:34:29PM Page 7 of7 Analysis Report for L2-SUB-WRS-ASGS-11A-SB L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17
12/7/201 7 7:37:15PM Page J of6 ~~§~pex-Gamma Analysis Report for L2-SUB-WRS-ASGS-12A-SB L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-ASGS-12A-SB Sample Description : L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 Sample Type : 500 ml Marine~ Unit Sample Point Sample Size 7 .558E+02 grams / Facility : Dairyland_NPP Sample Taken On : 12/4/2017 1: 58:00PM Acquisition Started : 12/7/2017 6:36:51PM Procedure : 500ml Marinelli
/
Operator : Administrator Detector Name : HOTLAB Geom etry : 500ml Marinelli J Live Time : 3600.0 seconds Real Time : 3611. 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 : 7/8/201 4 Efficiency Calibration Description Sample Number : 3666 PEAK ANALYSIS REPORT Peak Analysis Performed on : 12/7/2017 7:37:06PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12f7/2017 7:37:15PM Page 2 of6 Analysis Report for L2-SUB-WRS-ASGS-12A-SB L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 76 . 10 147 - 160 152. 7 4 l.61E+02 53 . 89 1. 09E+03 3.19 F 2 185.86 368 - 376 372.22 5.92E+O l 28.39 4.55E+02 1.07 F 3 238 . 50 47 1 - 482 477.47 1.28E+02 33.45 5 .4 4E+02 1.18 F 4 295 . 03 586 - 596 590.52 1 . 04E+02 28.53 2.90E+ 02 1. 37 F 5 351.71 7 00 - 711 7 03.85 1 . 8 1E+02 31. 87 2 . 01E+02 1. 51 F 6 582.88 1158 - 1173 11 66. 09 5 .6 9E+Ol 17 .96 9 . 20E+ Ol 1. 37 F 7 609. 1 1 12 14 - 1 222 1 218 . 55 1. 0 4E+02 23.39 7 . 42E+Ol 1. 37 F 8 911 . 1 4 18 1 7 - 1828 1 822.53 2 . 74E+Ol 1 3 . 17 4.66E+Ol 1. 43 M 9 964.4 8 1924 - 1943 1 929 .18 2 .5 6E+Ol 12 .37 3.56E+ Ol 1. 63 m 10 969 . 04 192 4 - 1943 1938 . 30 2.48E+ Ol 13 .0 1 5. 15E+ Ol 1. 63 F 11 1460 . 42 291 4 - 2929 2920 . 96 3.31E+02 36.95 2.20E+ Ol 2 . 20 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 : 12/7/2017 7:37:06PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 76.10 1 .61E+02 5 3.89 1. 61E+02 5 .3 9E+01 F 2 185.86 5.92E+Ol 28.39 5 . 92E+Ol 2.84E+O l F 3 238 .50 1. 28E+02 33.45 1. 28E+02 3.35E+0 1 F 4 295.03 1.04E+02 28.53 1 .0 4E+0 2 2.85E+O l F 5 351. 71 1. 81E+02 31. 87 8.36E+O l 3.72E+Ol 9.74E+Ol 4 .90E+Ol F 6 582.88 5 .69E+O l 17.96 5 . 69E+O l 1 .8 0E+Ol F 7 609 .11 1. 04E+02 23 . 39 4.1 2E +O l 2.42E+O l 6 . 23E+Ol 3.37E+O l F 8 911.14 2.74E+Ol 13 . 17 2.74E+Ol 1.32E +O l M 9 964.48 2.56E+O l 12.37 2. 56E+Ol l.24 E+O l m 10 969.04 2.48E+Ol 13.01 2.48E+Ol 1.30E+Ol F 11 1460.42 3.31E+02 36.95 5 . 63E+Ol 1.71E+O l 2 .7 5E+02 4.07E+Ol M "' First peak in a multiplet region rn = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigrna
12/7/2017 7:37:15PM Pagc3of6 Analysis Report for L2-SUB-WRS-ASGS-12A-SB L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 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 1 460.75
- 10.67 3 . 96E+OO 6 . 27E-01 PB - 212 0 . 55 77 . 1 1 17.50 238 . 63
- 4 4 .60 8 . 75E-02 2 . 33£-02 BI-214 0 . 34 609 . 31
- 46.30 9.SOE-02 5.16£-02 1120 . 29 15 . 10 1238.1 1 5. 94 1377. 67 4 .11 1407.98 2. 48 1 509.19 2.19 1764.49 1 5.80 PB- 214 0. 71 77.11 10.70 295 . 21
- 19 . 20 1 .9 7£- 01 5 . 48E-02 351. 92
- 37.20 1. llE-0 1 5.62E-02 RA-226 0 . 98 186.21
- 3.28 4.62E - 0 1 2 . 23E-0 1 AC-228 0.36 209 . 28 4.40 338 . 32 11. 40 794.70 4.60 91 1. 60
- 27.70 1. Ol E-01 4.85E-02 964 . 60
- 5 .2 0 5 . 26E-01 2.SSE-01 969 . 11
- 16.60 1.61E-01 8 . 45E-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
12/7/2017 7:37:15PM Page 4 of6 Analysis Report for L2-SUB-WRS-ASGS-12A-SB L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCi/grams) K- 40 0 . 983 3 . 96E+ OO 6.27E - 0 1 PB- 212 0 . 558 8 .7 5E-02 2.33£-02 BI - 21 4 0. 346 9 . SOE-02 5 . 1 6E - 02 PB - 214 0 . 716 1. 55E - 01 3 . 93E-02 RA-226 0 . 981 4 . 62E-0 1 2 . 23E - Ol AC-228 0 . 3p3 1 . 26£-0 1 4 . lSE - 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
12/7/2017 7:37:15PM Page 5 of6 Analysis Report for L2-SUB-WRS-ASGS-12A-SB L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/7/2017 7:37:06PM 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
-111 F 1 76.10 4. 4 8310E-02 1 6.70 F 6 582 . 88 l.58036E-02 15.79 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 (pCilgrams) (pCilgrams) (pCilgrams)
(keV) + K-40 14 60.75
- 10. 67 3 . 96E+00 6 . 41E - 01 6.41E-01
+ AR-41 1293 . 64 99.16 1 . 06E+ll 2 .52E+ll 2. 52E+ll + CO-60 1173 . 22 100.00 3 . 66E-0 2 6 . 00E-02 6 . 21E-02 1332.49 100.00 5 . 03£- 02 6.00E- 02 + KR- 85 513. 99 0.43 9.93E+00 l .0lE+0l 1.0lE+0l + Y-88 898.04 93.70 - 2 . 28E -0 2 3 .61E-02 4.96E- 02 1836.06 99.20 -8 . 53E-02 3.61E-0 2 + NB-94 702 . 63 100.00 2.43E-02 4 . 12E- 02 4.12E-02 871.1 0 100.00 -5.90E-02 4.20E- 02 + I-131 284.30 6.06 -1.94E-01 5.39E-02 7.09£- 01 364.48 81. 20 3.28E-02 5 .39E- 02 636.97 7 . 27 -3.21E-01 7.27E- 01 + CS-134 604.70 97 . 60 9.42E-02 5 . 00E- 02 5.24E - 02 795.84 85.40 2 . llE-02 5.00E - 02 + CS - 137 661. 65 85.12 l.13E-01 6 . 43E - 02 6.43E-0 2 + CE-144 80 . 12 1.36 -2.25E-01 2.72E-01 3.48E+00
12/7/2017 7 :37:15PM Page6 of6 Analysis Report for L2-SUB-WRS-ASGS-12A-SB L2-011-101/ PACKAGE# L2-SUB-WRS (A) RA 12/07/17 Nuclide Energy Yield(%) Activity Nuclide MDA LineMDA Name (pCilgrams) (pCi/grams) (pCilgrams) (keV) CE - 144 133.51 11 . 09 - 1. 55E-O l 2 . 72E-01 2.72E- 0 1 t EU-1 52 121.78 28.40 l . 23E-02 1. 09E -01 1. 09E - 0 1 244.69 7 .4 9 -2.13E-01 4.79E-01 964 . 00 14.44 1. 61E-01 3.94E-0 1 1408.00 20.74 1.29E-01 2.23E-01 + EU-154 123 . 07 40 .40 6.02E-02 7 . 69E-02 7.69E-02 247.94 6.60 -5 . 56E-01 4 . 97E- 01 723. 30 19.70 -7 . 57E-02 2 . 23E-01 873.20 11. 50 3 . 90E-01 3 . 90E-01 100 4 . 76 17.90 l. 79E-01 2 . 80E-01 1274.51 35.50 - 2 .2 2E - 02 l . 35E- 01 + EU- 155 86 . 5 4 32.80 -8.30E-02 1. 20E-01 l . 20E-01 105.31 21.80 9 .1 3E-03 l.4 6E-01 + BI-214 609 . 3 1
- 4 6 . 30 9 . SOE-02 8.60E- 02 8 . 60E-0 2 1120. 29 15 . 10 2 . 0SE-01 3 . 96E-01 1 238 .11 5 . 94 8 . 15E-01 1 .1 2E+OO 1377 . 67 4 . 11 2 . 37E-01 l . 09E+OO 1407 . 98 2 .48 1. 08E+OO l. 86E+OO 1509 .19 2 . 19 3.61E-02 l. 74E+OO 1764 . 49 1 5 . 80 4 .18E-0 1 3.71 E- 01
+ PB-214 77 . 11 1 0 . 70 1 . 78E-Ol 1.02E- 01 4.66E-01 29 5.2 1
- 19 . 20 l . 97 E-01 l . 21E-01 351. 92
- 37.20 l . llE - 01 1. 02E-01
+ PA-228 89.95 22 . 00 8 . 96E-01 1 .1 8E+OO l . 98E+ OO 93 .35 35.00 4.88E-01 l . 18E+ OO 1 05.00 16.30 4 . 21E-01 2 . 22E+OO 129.22 2 . 97 3 . 54E+OO 1 .1 6E+Ol 338 . 32 5.30 5 . 87E+ OO 7.45E+ OO 463.00 13 . 80 2 . 03E-0 1 3 . 13E+ OO 911.23 16 .7 0 3.24E+OO 3.44E+OO + AM-241 59 . 54 36 . 30 -5.67E-02 2.2 1E-01 2 . 21E-01 + CM-243 1 03 . 76 23 . 00 2 .0 4E- 02 1.40E-01 1. 40E- 01 228 . 18 10.60 - 7.68E- 02 2 . 84E-01 277.60 14 . 00 -2 .56E-02 2.40E-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
12/7/2017 9:42:00PM Page l of 7 pex-Gamma Analysis Report for L2-SUB-WRS-ASGS-13A-SB L2-011-101/PACKAGE#: L2-SUB-WRS (A} RA 12/07/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-ASGS-13A-SB Sample Description : l2-011-101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 9.046E+02 grams / Facility : Dairyland_NPP Sample Taken On : 12/4/2017 1:43:00PM Acquisition Started : 12/7/2017 8:41:37PM Procedure : 500ml Marinelli . / Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli / Live Time : 3600.0 second! Real Time : 3611.5 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 : 3668 PEAK ANALYSIS REPORT Peak Analysis Performed on : 12/7/2017 9:41 :51PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/7/2017 9:42:00PM Page 2 of7 Analysis Report for L2-SUB-WRS-ASGS-13A-SB L2-011 -101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) M 1 74 . 65 146 - 161 149.8 5 l .0 7E+0 2 36.13 7 . 28E+02 1. 22 m 2 77 . 02 146 - 161 154.58 1 . 37E+02 38 . 38 7.87E+ 02 1. 23 F 3 186 . 09 368 - 376 372.67 6 . 82E+01 34.18 5 . 42E+02 1. 40 M 4 238 . 54 474 - 490 4 77 .55 2.51E +02 40.48 3 . 60E+02 1. 30 m 5 241 .44 474 - 490 483.3 5 1 . 09E+02 29.06 3.67E+02 1. 30 F 6 295 . 26 587 - 595 590.97 1 .0SE +02 29 . 41 2.85E+02 1. 30 F 7 338 . 10 671- 680 676.63 4.21E +Ol 23 .60 2 . 45E+02 1. 44 F 8 351 . 78 698 - 710 703 .98 l .7 1 E+02 31.64 2 .7 7E+02 1. 34 F 9 582 . 96 11 60 - 1172 1166 . 26 8 . 76E+Ol 23 . 54 l . 25E+ 02 1. 91 F 10 609 . 03 1 210 - 1223 1218.39 1. 47E+02 28 . 11 1.26E+02 1. 83 F 11 66 1 . 33 1 317 - 1 327 1322.97 1. 65E+02 28 . 87 l . 04E +02 1.55 F 12 910 . 47 1 815 - 1828 182 1.18 5 .56E+Ol 17.64 7.70E+Ol 1. 40 F 13 1119.98 2236 - 2245 2240.14 2. l SE+Ol 12 .8 3 5 . 41E+Ol 1. 32 F 14 1332. 16 2659 - 26 71 2664 .4 6 4. 2 6E+01 15 . 07 2 . 78E+Ol 2.40 F 15 1460 . 34 2912 - 2930 2920 . 80 4.87E+02 45.46 3 . 73E+Ol 2 .36 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 : 12/7/2017 9:41:51PM 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. M 1 74.65 1. 07E+02 36. 13 1.07E+02 3.61 E+01 m 2 77.02 l . 37E+02 38.38 l.37E+02 3 .84 E+O l F 3 186 .09 6 .8 2E+O l 34 .1 8 6.82E+Ol 3 .4 2E+01 M 4 238.54 2 . 51E+02 40.48 2 . 5 1E+02 4 . 05E+Ol m 5 241. 44 l . 09E+02 29.06 1.09E+02 2 . 91E+Ol F 6 295.26 1. 05E+02 29.41 1. 05E+02 2.94E+Ol F 7 338 . 10 4 . 21E+Ol 23 . 60 4.21E+Ol 2.36E+Ol F 8 351 .78 1. 7 1E+02 31. 64 8.36E+Ol 3.72E+O l 8.74E+Ol 4.88E+Ol F 9 582.96 8.76E+Ol 23 . 54 8 . 76E+O l 2.35E+ 01 F 10 609.03 l.4 7E+02 28. 11 4 . 12E+ Ol 2.42E+Ol l.0 6E+02 3.7 1 E+Ol F 11 661.33 1.65E+02 28.87 6 . 61E+Ol 2.54E+Ol 9.84E+01 3.84E+ Ol F 12 910 . 47 5.56E+01 17.64 5 . 56E+Ol l . 76E+Ol F 13 1119 . 98 2.15E+Ol 12.83 2 . 15E+Ol 1 . 28E+O l F 14 1332 . 16 4 . 26E+Ol 1 5 . 07 4 . 26E+ Ol 1. 51E+Ol
12/7/2017 9:42:00PM Page 3 of7 Analysis Report for l2-SUB-WRS-ASGS-13A-SB l2-011-101/PACKAGE#: l2-SUB-WRS (A) RA 12/07/17 Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 15 1 460.34 4.87E +02 45.46 5.63E+Ol l. 7 1 E+Ol 4 . 30E+02 4 .86E+0 1 M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K- 40 0.97 1460.75
- 10.67 5.18E+OO 6.52E- 01 CS-137 0 . 98 661. 65
- 85.12 7 .3 5E-02 2.90E-02 PB - 2 12 0.99 77.11
- 17.50 2 . 14E-01 6 . 14E- 02 238 . 63
- 44.60 l .4 3E-01 2.42E-02 BI - 214 0 .57 609.31
- 46 . 30 1.35E-Ol 4.78E-02 1120.29
- 15. 1 0 l. 45E -01 8.69E- 02 1238 .11 5 .94 1377. 67 4.11 1407.98 2.48 1509.19 2. 19 1764.49 15.80 PB-214 0.99 77 .11 ... 10 .70 3.SOE-01 1. OOE-01 295 . 21
- 1 9. 20 1. 66E- 01 4 . 72E-02 351. 92
- 37.20 8.34E- 02 4.68 E-02 RA-226 0.99 186.2 1
- 3 . 28 4 . 45E-01 2.24E - 01
* = Energy line found in the spectrum.
- : Manually added nuclide.
? "' Manually edited nuclide.
=
@ Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma
12/7/2017 9:42:00PM Page4 of? Analysis Report for L2-SUB-WRS-ASGS-13A-SB L2-011-101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty
/(pCilgrams)
K- 40 0.97 4 5 . 18E+OO 6.52E-01 CS-137 0.984 7.3 5 E-02 2 . 90E- 02
- 1. 42E-01 2.27E-02 PB-2 12 0.999 BI- 214 0 .5 76 1. 37E-01 4 . 1 9E-02 PB - 2 14 0 . 998 l . 24E-Ol 3 . 1 8E-02 RA- 226 0 . 998 4 .45E-01 2 . 24E-01
? = nuclide is part of an undetemiined solution X = nuclide rejected by the interference analysis
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000sigma
1217/2017 9:42:00PM Page 5 of7 Analysls Report for L2-SUB-WRS-ASGS-13A-SB L2-011 -101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/7/2017 9:41 :51 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 M 1 7 4.65 2 . 97949£-02 16.84 //hi., m 5 241.44 3.02995E-02 13. 32 f).>1,,\~ F 7 338.10 l.16832E-02 28 . 06 Tol. AC-228 PA-2 28 F F 9 12 582.96 910. 4 7 2.43352£-02
- 1. 54 359E- 02 13 . 43 15 . 87 Tol. P - 228
~
~i))J'1 (})-'\))~:-.\
F 14 1 332.16 1 .1 8356E-02 17. 69 Tol. &C -60 ~1~r~.;~ ~ ti . @
=
=
M Flrst peak in a multiplet region
=
m Other peak in a multiplet region F Fitted singlet
>~~
Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity Nuclide MDA LineMDA Name (pCi/grams) (pCilgrams) (pCilgrams) (keV) + K-40 1 460 . 75
- 1 0.67 5.18E+00 5.82E-01 5.82E-01
+ AR-41 12 93.64 99.16 2. 93E+ll 6 . 1 8E+ll 6 . 18E+ll + / CO-6 0 1173.22 100 . 00 3 . 88E-02 5.82E - 02 5.82E-02 1332 . 49 100 . 00 1. 39E-02 5.85E-02 + KR-85 513. 99 0.43 4.57E+00 8.89E+00 8.89E+00 + Y-88 898 . 04 93.70 1 . 44 E- 02 2.26E-02 4.75E-02 1836.06 99.20 - 1 . 52E-02 2 . 26E-02
12/7/2017 9:42:00PM Page 6 of7 Analysis Report for L2-SUB-WRS-ASGS-13A-SB L2-011-101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 Nuclide Energy Yield(%) Activity Nuclide MDA LineMDA Name (pCi/grams) (pCilgrams) (pCi/grams) (keV} + NB-94 702.63 100 . 00 -7.89E-03 3.35E-02 3 . 35E-02 87 1. 1 0 100.00 - 2.64E - 02 4 . 15E- 02 + I-131 28 4. 30 6. 06 - 2. 55E- 0 1 4 . 75E-02 6 . 25E - 01 36 4.4 8 81.20 - 3 . 91E-03 4 . 75E- 02 636 . 97 7 . 27 - 5.73E-0 1 5 . 89E-01 + / c s - 134 60 4. 70 97 . 60 7.36E-02 4 .4 7E-02 4 . 91E- 02 795 . 84 85 .4 0 -8 . 27E-03 4 . 47E-02 + CS-137 661.65
- 85.12 7 . 35E- 02 4 . 80E-02 4 . 80E-0 2
+ CE-1 4 4 80 . 12 1. 36 - 7.69E- 01 2 . 56E- 0 1 3 . 21E+OO 133 . 5 1 11.0 9 2 . 22E-0 1 2 . 56E- 01 + / EU- 152 121. 78 28 .40 - 1 . 76E-03 9 . 7 3E-0 2 9 . 73E- 02 24 4. 69 7.49 3 . 09E-02 4.68E-01 964.00 14.4 4 1. 86E-01 3.63E- 01 14 0 8.00 20.74 -1 . 31£- 0 1 1.62E- 01 + ~ U- 154 123 . 07 40.40 1 . 63E-02 6.89E-02 6.89E- 02 247 . 94 6.60 2 . 34E-01 4.84E-01 723.30 19 . 70 1 .7 2E-01 1 .9 3E- 01 873 . 20 11. 50 3 . 58E - 02 3 . 68E - 01 1 004. 76 17. 90 -2 . 39E- 02 2 . 50E - 01 1 274. 5 1 35.50 2 . 0 4E-02 1 . 4 5E-01 + EU- 155 86.54 32 . 80 - 2 . 40E- 02 l. 12E-0 1 l . 12E- 0 1 105 .3 1 21. 80 1.98E-02 1 . 38E -01 + BI-214 6 09. 31
- 46.30 1.35E-0 1 8.30E-02 8 . 30E - 02 11 20.29
- 15 . 10 1. 45E- Ol 1.93E-01 1 238 . 11 5 . 94 6 . 07E-01 l.OlE +OO 1 377.67 4 . 11 - 2 . 48E-03 l . 04E +OO 14 07.98 2.48 - 1.09E+OO l . 35E+OO 1 509. 1 9 2 . 19 - 1.24E+OO 1.48E+OO 1764 . 49 1 5.80 1.98E-01 2 . 52 E- 01
+ PB-214 77.11
- 1 0.70 3.SOE-01 9 . llE-0 2 2.42E -01 295.21
- 19 . 20 l.66E-0 1 9.SOE - 02 35 1. 92
- 37 .2 0 8 . 34E-02 9. llE-02
+ PA-228 89 . 95 22.00 1. 23E+OO 1. l 7E+OO 1. 97E+OO 93 .3 5 35 . 00 1.4 8E- 01 l . 1 7E+O O 1 0 5 . 00 16.30 7 . 4 5E- 01 2 . 25E+OO 129.22 2 . 97 7 . 60E-Ol 1.14E+Ol 338.32 5 . 30 2 . 08E+OO 7.41E +OO 463 .00 13 . 80 6 . 1 7E- 01 2 . 89E+OO 911 . 23 16 . 70 5 . 22E+OO 3 . 79E+O O + / AM-2 4 1 59.54 36.30 l . 18E-03 1 .95E- 01 1. 95E-01 + CM-2 43 103 . 76 23 . 00 3 . 0lE- 02 1.32E- 0 1 1. 32E-01 228 .1 8 10.60 2.29E-02 2 . 61E-01 277.60 14 . 00 - 9 . 25E- 03 2 . 08E-01
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
12f7/2017 9:42:00PM Page 7 of7 Analysis Report for L2-SUB-WRS-ASGS-13A-SB L2-011-101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17
1217/2017 10:43:1 SPM Page J of 7 pex-Gamma Analysis Report for L2-SUB-WRS-ASGS-14A-SB L2-011 -101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-ASGS-14A-SB Sample Description : L2-011-101/PACKA.:JE#: L2-SUB-WRS (A) RA 12/07/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 1.004E+03 grams / Facility : Dairyland_NPP Sample Taken On : 12/4/2017 1:40:00PM Acquisition Started : 1217/2017 9:42:52PM Procedure : 500ml Marinelli
/
Opera tor : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 3600.0 seconds Real Time : 3611.6 seconds Dead Time : 0 .32% I 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 : 3669 PEAK ANALYSIS REPORT Peak Analysis Performed on : 1217/2017 10:43:06PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/7/2017 10:43:15PM Page 2 of7 Analysis Report for L2-SUB-WRS-ASGS-14A-SB L2-011-101 /PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 76.86 148 - 1 60 15 4.27 8.57E+O l 32 .1 3 1 . 15E+03 0.74 F 2 92 .6 5 183 - 193 18 5 .84 5. 4 7E+Ol 34.48 8.50E +02 1. 22 F 3 185.80 366 - 379 372.09 6.69E +Ol 29 . 85 7.88E+02 1. 07 M 4 238 . 53 471- 491 477.53 1. 52E+02 32 . 87 3 . 36E+02 1.35 m 5 2 41. 62 471 - 491 483.71 7 . 84E+O l 25 . 88 3 . 05E+ 02 1. 35 F 6 295 . 1 8 58 7 - 596 590.80 1 . 0 1 E+ 0 2 26 . 96 2 .66E+ 02 1.12 F 7 351 . 7 4 69 7 - 708 703 . 9 0 2.0 2E+ 02 33 . 80 2.51 E+02 1. 38 F 8 58 2 . 7 9 11 63 - 117 0 11 65 . 91 3 . 76E+O l 15 . 95 6 . 99E+ Ol 1.11 F 9 609.14 1215 - 1 223 12 1 8.62 1.44E+02 26.18 5.67E+ Ol 1. 60 F 10 910.49 18 1 6 - 1826 1821.22 2.48E+ 0 1 13.67 6 . 1 2E+ 01 1. 41 F 11 1120 . 1 3 2236 - 224 5 2240.44 2 . 9 1E+0 1 14.24 4 . 85 E+Ol 1.55 F 12 1332 . 1 4 2 660 - 2669 2664.42 1 . 67E +O l 1 0.69 2 . 68E+Ol 1.51 F 13 1460.23 2 912 - 2928 2920 . 58 3 . 76E+0 2 39. 34 2.12E+01 2 .4 3 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 : 12n/2017 10:43:06PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 76.86 8.57E+Ol 32.13 8 . 57E+Ol 3.21E+ Ol F 2 92 . 65 5 . 4 7E+Ol 34.48 5.47E+O l 3.45E +Ol F 3 1 85.80 6.69E+Ol 29.85 6 . 69E+ Ol 2 . 99E+ Ol M 4 238.53 1.52E+ 0 2 32.8 7 l . 5 2E+02 3.29E+Ol m 5 241.62 7 . 84E +Ol 25.88 7 . 84E+O l 2.59E+Ol F 6 295 . 18 l.0 1E +0 2 2 6 .96 1 . 01E+02 2 . 70E+Ol F 7 351 .74 2.02E+02 33 . 80 8 . 36E+Ol 3.72 E+ Ol 1 .18E+02 5 . 03E+Ol F 8 582.79 3.76E+Ol 15 . 95 3 . 76E+ Ol 1 .59E+ Ol F 9 609.14 1 . 44E+02 26 . 18 4 . 12E+Ol 2.42E +0 1 1 .03E+ 02 3 . 5 7E +Ol F 10 910.49 2 . 48E+Ol 1 3.6 7 2 .4 8E+ Ol 1.37 E+Ol F 11 1120 .13 2.91E+O l 1 4 . 24 2 . 91E+O l l . 42E+Ol F 12 1332 . 14 l . 67E+ Ol 1 0 . 69 1 . 67E+Ol 1. 07E+0 1 F 13 1460.23 3 . 76£+ 02 39 . 34 5 .63E+Ol l . 71E+ Ol 3 . 19E+02 4 . 29E+Ol
12/7/2017 10:43:15PM Page 3 of7 Analysis Report for L2-SUB-WRS-ASGS-14A-SB L2-011-101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 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\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCl/grams) Uncertainty K- 4 0 0. 95 1 46 0.7 5
- 1 0 . 67 3 . 4 6E+O O 5 .04E- 0 1 PB-2 12 0.99 77 .11
- 17 . 50 l. 21E- Ol 4 .6 0E- 0 2 238 .6 3
- 44 .60 7 .8 0E- 02 1 .7 4E-0 2 BI - 214 0.58 60 9 . 3 1
- 46 . 30 l.18E - 01 4 . 1 4E- 0 2 112 0 . 2 9
- 1 5. 1 0 l. 77E-Ol 8. 70£ - 0 2 123 8 .11 5.94 1377 . 67 4 .11 1407. 98 2 . 48 15 0 9 .19 2. 1 9 17 6 4 . 49 1 5. 80 PB- 214 0. 99 77 . 11
- 10 . 70 1 . 98£ -0 1 7 . 52£- 02 295.21
- 19.2 0 l.44E-01 3 . 90E- 02 351 .9 2
- 3 7. 20 1. 02E- 01 4 . 35E- 02 RA- 226 0.9 7 186 . 21
- 3 . 28 3.92E- 0 1 1 . 7 7E-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
12/7/2017 10:43:15PM Page4 of7 Analysis Report for L2-SUB-WRS-ASGS-14A-SB L2-011-101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0.958 3 . 46E+OO 5 .0 4E-0 1 PB-212 0.996 7 .4 2E-02 1. 64E-02 BI-2 14 0.582 1 . 29E-01 3 .7 4E-02 PB- 21 4 0.995 1.19E-01 2 .7 3E - 02 RA-226 0. 973 3.92E-01 1.77E- 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
12rT/2017 10:43:15PM Page 5 of7 Analysis Report for L2-SUB-WRS-ASGS-14A-SB L2-011 -1 01/PACKAGE#: L2-SUB-WRS (A) RA 12/07/1 7 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/7/2017 10:43:06PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance ~t(v} Peak No. Energy (keV) Peak Size (CPS)
~*-fl..
Uncertainty Type F 2 92.65 1 .51811E-0 2 31. 55 Tol. P 28 ,_-,q m 5 24 1. 62 2 .1 7668E-02 16.52 fy l>v\ F F 10 8 582 .79 910.49 l . 04570E-02 6.88243£ -03 21.18 27.59 Tol. o
~ -228 1~ ~*7..,1.;/,
F 12 1332.14 4 . 6371 5E- 03 32.02 , r 'l!.~u>6 M = First peak in a multiplet region m = Other peak in a multiplet region
~r- , t.-\r F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCi/grams) (pCilgrams)
(keV) + K-4 0 1460.75
- 1 0.67 3 .4 6E+00 4.85E-01 4 . 85E-01
+ AR-41 1 293 .64 99 . 1 6 2 . 00E+ ll 7.51E+l l 7.51E +ll + CO-6 0 1173 . 22 100 . 00 3.44E-02 4 . lSE-02 5.04E-02 1332 .49 100.00 2.90E -0 2 4 .lSE-02 + KR-85 513.99 0. 43 6.33E+00 7 . 39E+00 7 . 39E+00 + Y-88 898.04 93 . 70 -2.00E-02 2.62E-02 3.36E-02 1 836 . 06 99.20 - l .61E-02 2 .62E-02 + NB- 94 702 . 63 100.00 -2. 52E-02 3 . l0E-0 2 3 .l0E-02 87 1 . 1 0 100.00 -9.27E- 03 3.40E-02 + I-131 284.30 6.06 -2 .88E- 01 4. 26E-02 5.24E-01
12/7/2017 10:43:15PM Page 6 of7 Analysis Report for L2-SUB-WRS-ASGS-14A-SB L2-011-101/PACKAGE#: L2-SUB-WRS (A) RA 12/07/17 Nuclide Energy Yield(%) Activity Nuclide MDA LineMDA Name (pCi/grams) (pC;Jgrams) (pCVgrams) (keV} I -131 364.48 81. 20 l.37E-02 4 . 26E-02 4.26E-02 636 . 97 7 .2 7 2.42E-01 5 . 19E-0 1 + CS - 1 3 4 604.70 97.60 8.20E-02 3 . 88E- 02 4 . 15E-0 2 795 . 84 85.40 -4.34E-02 3.88E - 02 + CS - 137 661. 65 85. 1 2 4 . 74E-02 4.54E- 02 4 . 54E - 02 + CE- 144 80 . 12 1. 36 l.02 E- 01 2.09E-01 2 . 70E+OO 133. 51 11. 09 -6.61E-02 2 . 09E-01 + EU-152 121 .78 28.40 4 . 22E-02 8 . 41E- 02 8.4 1 E-02 244 . 69 7 . 49 - 2. 0 4E-02 3 . 72E-01 964.00 14 .4 4 1. 36E-01 2 . 92E-01 1408.00 20.74 4.06E-03 1 . 53E-01 + EU-154 123.07 40.40 7 . 66E-03 5 . 87E - 02 5.87E-02 247 . 94 6 . 60 1.29E-01 4.0SE-01 723.30 19 . 70 -2 . 87E-02 1. 4 9E-01 873 . 20 1 1.50 8 . 14E-02 3.03E-01 1004 . 76 1 7.90 -3 . 94E-03 1 . 86E-01 1 274.51 35.50 1.92E-02 l . 12 E-0 1 + EU-155 86 . 54 32 .8 0 - 4 .64£-02 9 . 45E- 02 9.45E-02 105 . 31 21. 80 -4.79E-03 l . l 6E-01 + BI-214 609.31
- 46 . 30 l.18E-01 6.27E- 02 6 .2 7E-02 1120 . 29
- 1 5 .1 0 l.77E - 01 1. 65E- 01 1238 .11 5 . 94 7 .83E- 02 8.SSE-01 1377.67 4 .11 8.70E-02 8.41E -01 1407.98 2.48 3 . 39E-02 l . 28E+ OO 1509.19 2.19 8.75E-01 l . 56E+ OO 1764 . 49 15.80 2. llE-01 2 . 42E-01
+ PB- 214 77 . 11
- 10.70 1.98E-0 1 7 . 95E- 02 3 . 02E-01 295 . 2 1
- 19 . 20 1. 44E-01 8.56E-02 351 . 92
- 37 . 20 1.02E-01 7.95E-02
+ PA-228 89 . 95 22.00 -6.59E-01 1.02E+OO 1. 71E+ OO 93.35 35.00 1.59E- 01 1. 02E+ OO 1 05 . 00 16 . 30 6 . 45E - 01 l.97E+OO 1 29.22 2 .97 - 2 . 30E+OO 9.85E+OO 338 . 32 5 .30 2 . 0BE-01 6 . 38E+OO 463 . 00 13.80 1. 42E+OO 2.54E+00 911.23 16 .7 0 2 . 88E+OO 2.89E+OO + AM- 241 59.5 4 36.30 -1 . 12E-0 1 l .72E-01 l.72E- 01 + CM-243 103 .7 6 23 . 00 8.69E-02 1 . 12E-01 l.12E-01 228.18 10.60 1. OSE-02 2.27E-01 2 77.60 14.00 - l . 56E- 01 1 . 79E - 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
12/7/2017 10:43:15PM Page 7 of7 Analysis Report for L2-SUB-WRS-ASGS-14A-SB L2-011-101/PACKAGE#; L2-SUB-WRS (A) RA 12/07/17
~~ ~* ~pex-Gamma 12/7/2017 11:14:35AM Pagel of7 Analysis Report for L2-SUB-WRS-AJGS-15A-SB 12/5/17 GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description
- L2-SUB-WRS-AJGS-15A-SB
- 12/5/17 I
Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 5.615E+02 grams/ Facility : Dairyland_NPP Sample Taken On : 12/5/2017 2:31:00PM / Acquisition Started : 12/7/2017 10:14:12AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry Live Time :
- 500ml Marinelli 3600.0 seconds
/
Real Time : 3611 .6 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 : 3660 PEAK ANALYSJS REPORT Peak Analysis Performed on : 12f7/2017 11 :14:26AM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/7/2017 11:14:35AM Page 2 of7 Analysis Report for L2-SUB-WRS-AJGS-15A-SB 12/5/17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM (keV) start end Centroid Area Uncertainty Counts (keV) No. M 1 74.75 142 - 192 150 . 05 1 .6 6E+02 48 . 32 8.86E+02 1.14 m 2 76 . 95 142 - 192 1 54 . 44 3 . 42E+02 67 . 62 7.60E+02 1.14 m 3 92.57 142 - 192 185.68 l . 04E +02 34.73 7.98E+02 1.17 F 4 186.02 369 - 377 372 . 53 8 . 28E+O l 35.08 6.80E+02 1. 1 4 M 5 238 .54 471 - 491 477 .5 5 6 . 02E+0 2 56.8 3 4.5 1 E+ 02 1. 38 m 6 241.59 471 - 491 483.66 1 . 3 4E+0 2 31. 45 4.02E+ 02 1.38 F 7 270 . 01 534 - 545 540.47 4.45E+01 24.36 4.69E +02 0 . 98 F 8 294 .97 587 - 594 590.39 l .79E+02 35. 15 2.85E+02 1.37 F 9 338. 1 4 673 - 685 676. 72 1. 28E+02 29.31 3 .17 E+02 1.22 F 10 351.78 698 - 708 703.99 3.00E+02 41.14 2.80E+ 02 1. 49 F 11 462.4 1 917 - 930 925 .21 3.83E+Ol 2 0 .10 2 . 17E+ 02 1. 42 F 12 510.4 8 1013 - 1030 1021. 32 l.34E+ 02 30.32 2.53E +02 2 . 50 F 13 582 .96 1160 - 117 0 1 166. 25 1 .8 1E+02 30 . 73 1 . 59E+02 1. 30 F 14 609.10 12 10 - 1227 1218 . 53 2.13E+02 32 . 77 l.98E+02 1. 7 6 F 15 661. 32 1317 - 1328 1322. 96 2 . 21E+02 33.12 1.17 E+ 02 1. 80 F 16 727 . 19 1 449 - 1458 1454.67 2.98E+Ol 17.69 9.23E+ Ol 1. 92 F 17 859.88 1 715 - 1725 1720.01 2 . 59E+Ol 16.56 9.90E+ Ol 1. 75 F 18 910 . 96 1 816 - 1828 1822.16 l . 25E+02 25 . 02 7.08E+Ol 1. 94 F 19 968 . 54 1933 - 1943 1937.29 6.88E+O l 22 . 24 1. 26E+02 1. 71 F 20 1331 . 76 2659 - 2668 2663.66 1. 56E+ Ol 9.76 2 . 95E +Ol 1. 03 F 21 14 60.30 2914 - 2930 2920 . 70 7.08E +02 54 . 41 2 . 87E+Ol 2 . 36 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 : 12/7/2017 11 :14:26AM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted (keV) Area Uncertainty Background Uncert. Area Uncert. No . M 1 74 . 75 l.66 E+02 48.32 l.66E+02 4.83E+O l m 2 76.95 3 . 42E+ 02 67.62 3.42E+02 6 . 76E+Ol m 3 92.57 1. 04E+02 34 . 73 1 .04E +02 3.47E+Ol F 4 186.02 8 . 28E+Ol 35.08 8.28E+ Ol 3.51E+Ol M 5 238 .54 6 . 02E +02 56 . 83 6.02E+02 5.68E+Ol m 6 241 . 59 l.34E+02 31. 45 1 . 34E+02 3 .l SE+Ol F 7 270 .0 1 4 . 45E+Ol 24.36 4.45E+Ol 2 .44E+ Ol F 8 294 . 97 1 . 79E+02 35 .1 5 1. 79E+02 3 . 5 2 E+Ol
12/7/2017 11 :14:35AM Page3 of7 Analysis Report for L2-SUB-WRS-AJGS-15A-SB 12/5/17 Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 9 338 . 14 1. 28E +02 29 . 31 1. 2 8E+02 2 . 93E+Ol F 10 351 . 78 3 . 00E+02 41.14 8.36E+ 0 1 3 . 72 E+Ol 2 .16E+0 2 5.55E+Ol F 11 462.4 1 3.83E+Ol 20 .1 0 3 . 83E +Ol 2.0 lE+Ol F 12 510 .4 8 l . 34E+02 3 0.32 7 . 28E+01 2 .85E+Ol 6 . 14E+O l 4 . 16E+01 F 13 582.96 l.81E+02 30.73 1 . 81E+02 3.07E+O l F 14 609 . 10 2.13E +02 32.77 4.12E+O l 2 .4 2E+O l 1.72E+02 4.0 7 E+ Ol F 15 661. 32 2.21E+02 33. 1 2 6.61E +Ol 2 .54 E+01 1. 55E+02 4 . 1 7E+Ol F 16 727.19 2 . 98E+Ol 17 . 69 2 .98E+Ol 1 . 77E+Ol F 17 859 . 88 2 . 59E+O l 16.56 2 . 59E+Ol 1. 66E+Ol F 18 910.96 l . 25E+02 25.02 1. 25E+0 2 2 . 50E+Ol F 19 968.54 6 . 88E+Ol 22.24 6.88E+Ol 2 . 22E+ Ol F 20 1 331. 76 1. 5 6E+ Ol 9 . 76 l . 56E+Ol 9 .7 68+00 F 21 1460. 30 7 . 08E+02 54 .4 1 5 . 63 E+Ol 1.71E+Ol 6 . 52E+ 02 5.70E+01 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K- 40 0 . 96 1460.75
- 10.67 1. 26E+Ol 1. 31E+ OO CS - 1 37 0. 98 661. 6$
- 85 . 12 1. 86E-01 5 . 12E-02 BI- 2 1 2 0 . 60 727 . 1 7
- 11. 80 2.82E-0 1 1.68E-Ol 785 . 42 2.00 1620 . 56 2.75 PB - 212 0 . 99 77 .11
- 17 . 50 8 . 62E-Ol 1. 79E-0 1 238 . 63
- 44.60 5 . 53E- 01 5. 95E- 02 BI - 214 0.34 609 . 31
- 4 6 . 30 3 . 53E-0 1 8.58E- 02 1120 . 29 15 . 10 1238 . 11 5. 94 1377 . 67 4 .11 1407.98 2 . 48 150 9.19 2 . 19 1764.49 15 . 80 PB- 214 0.99 77 .11
- 10 . 70 1 .41E+O O 2 . 93E-Ol 295.21
- 19.20 4 . 55£- 0 1 9.22E- 02
12/7/201 7 11 :14:35AM Page 4 of7 Analysis Report for L2-SUB-WRS-AJGS-15A-SB 12/5/17 Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty PB-214 0 .9 9 351 . 92
- 37 . 20 3 . 33E-0 1 8.69E-0 2 RA- 226 0 .99 186.2 1
- 3 . 28 8 . 70 E-01 3 .7 2E- 0 1 AC- 228 0 . 59 209 . 28 4 . 40 338 . 3 2
- 11. 40 6 . 22E-0 1 1. 45E-01 794 . 7 0 4 . 60 911 . 60
- 27 . 70 6. 18E-01 1. 2 6E-01 9 64 . 60 5 . 20 969 .11
- 1 6 . 60 5.9 9E- 0 1 l . 95E - 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 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams)
K-40 0 .967 1. 26E+0l 1. 31E+00 CS-137 0 . 983 l. 86E- 01 5. 12E-02 BI-21 2 0 . 605 2 . 82 E-0 1 1 .68E-0 1 PB- 212 0 . 998 5 . 59E -0 1 5.66£-02 BI-214 0.3 46 3 . 5 3E-01 8 . 58E -0 2 PB-214 0 . 99 5 3 .9 5E - 01 6.20E -02 RA- 22 6 0 . 994 8 .7 0E-0 1 3.72E-0 1 AC- 228 0 . 594 6 . 1 6E-0 1 8.5 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
12f7/2017 11:14:35AM Page 5 of7 Analysis Report for L2-SUB-WRS-AJGS-15A-SB 12/5/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/7/2017 11:14:26AM 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 1 74.75 4.59973E- 02 14.59 f~*t-1'~~~ m 3 92.57 2 .88 331£-02 16.73 Tol. 7~F'5'1 m 6 24 1 .59 3 . 70839E -0 2 11 . 78 f'b~'M 2-'2% F 7 270.01 l . 23675E-02 27.36 µ 0 _ li.:;M
~~
F 11 4 62. 41 l .06 347E-02 26.26 Tol. F 12 5 1 0.48 1.70475E-02 33.91 ---,)Wi
~ ~
~ ,2--\t'l'<t.. ,-JD F 13 582.96 5 . 02657E-02 8.49 F 17 859 . 88 7.20048£-03 31.95
~
F 20 1331. 76 4.32056E- 03 31. 36 Tol. ,l)--:s: f<~L 1t>>'vJ<$.(5\- )& J P,.'C:- JI El ,G u.~ '{J~U:!h 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\Dairy!and_NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV) + K-40 1 460. 75
- 1 0.67 1.26E+Ol 8.86E-01 8 .8 6E - 0 1
+ AR-41 1 2 93.64 99.16 - l . 18E+05 1.80E+ 06 1. 80E+06
12/7/2017 11:14:35AM Page 6 of7 Analysis Report for L2-SUB-WRS-AJGS-15A-SB 12/5/17 Nuclide Energy Yield{%) Activity NuclideMDA LineMDA Name (pCilgrams) (pCi/grams) (pCilgrams) (keV) + / CO-60 1173.22 1332 . 49 1 00 . 00 1 00 . 00 6.93E-02
- 5 . 71E-02 8.13 E- 02 1 . l0E- 0 1 8 . 13E-02
+ KR- 85 513 . 99 0 . 43 3 . 76E-0 1 1 . 72E+ 0 l l . 72E+0l + Y- 88 8 98 . 04 93 . 70 2 . 75E-02 6 . 1 4E- 02 8 . 62E- 02 1836 . 06 99 . 20 - 1 . 51E- 02 6 . 1 4E-0 2 + NB- 94 702 . 63 1 00 . 00 3 . 58E-03 6 . 70E- 02 6 . 70E- 02 87 1.1 0 1 00 . 00 - 4.65E-02 7 . 5 9E-02 + I-131 2 84 . 30 6 . 06 - 1 . 96E - 01 7. 3 4E- 0 2 1 . 03E+ 00 364 . 48 81.20 - 3 . l0E- 02 7 . 34E-02 636 . 97 7 . 27 - 4 . 03E- 0 1 1 . 04E+ 00 + / CS- 1 34 60 4 .7 0 97 . 60 - 7 . 99E- 03 8 . 43E- 0 2 9 . 21 E- 02 7 95 . 84 85 . 4 0 -8 . 2 1 E- 02 8 . 43E -02 + / CS - 1 37 66 1. 65
- 85.12 1. 86E-0 1 7 . 98E-02 7 . 98E-02
+ CE- 144 80 . 12 1.36 3. 5 9E +0 0 4 . 36E- 0 1 5 . 86E +00 133.5 1 11.09 - 3 . 99E - 01 4 . 36E-0 1 + /EU-1 52 1 21.78 2 8 . 40 -9 . 63E - 02 l . 7 0E-0 1 1. 7 0E-0 1 2 44.69 7 . 49 3 .l 0E-02 9 . ll E-0 1 9 64. 00 14 . 4 4 1. 1 4E+0 0 7.4 7E-01 1408.00 20 . 74 2 .4 2£- 03 3.41E- 0 1 + EU- 154 123.07 40 . 40 - 2 . 20E- 02 l . 20E- 01 1 . 20£-01 247 . 9 4 6 . 60 - 9 . 62E-02 8 . 36E-01 723 . 30 19 . 70 1.4 7E- 01 3 . 60E-0 1 8 7 3 . 20 11. 50 5 . 02E-02 6. S0E-01 1004. 76 1 7 . 90 2 . 71 E-02 4 . 4 2E- 0 1 1 27 4 . 5 1 35 .50 - 3 . 34 E-02 2 . 74E- 0 1 + EU - 155 86 . 54 32 . 80 - 2 . 1 3E-0 1 1 . 98E- 01 l . 98E-01 1 05 . 31 21. 80 2 . 4 0E-02 2. 30E-01 + BI - 214 60 9 . 31
- 4 6 . 30 3 . 53E - 01 1 . 58E - 01 1. 58 E-01 1 12 0. 29 15 . 10 1 . 23E- 01 6 . 60 E-01 12 38 . 11 5 . 94 6 . 54E- 01 1. 82E+ 00 1 3 77. 67 4 . 11 6 . 54E- 02 l . 84 E+00 1 4 07.98 2 . 48 2 . 02E -02 2 . 8 5E+00 1 509 . 1 9 2.19 1 . 59E+00 2. 7 8E+00 1 764 .4 9 1 5 . 80 6. 0 3E-0 1 6 . 17E-0 1
+ PB - 214 77.11
- 1 0. 70 1 . 4 1E+00 l. 4 4E-0 l 3 .85E- 0 1 295 . 21
- 1 9 . 20 4 . 55E-0 1 1 . 49E-01 3 51. 92
- 3 7. 20 3. 33E-0 1 1. 44E- 01
+ PA- 228 89 . 95 2 2 . 00 2 . 09E+00 6 . 9 1 E-01 1.1 8E+00 93 . 35 35 . 00 - l . 38E- 03 6 . 9 1E- 01 1 0 5 .0 0 16 . 30 2 . 07E- 03 1 .2 4E+00 12 9 . 22 2 . 97 3 .9 9E+00 6 . 67E+00 338 . 32 5. 30 6 .1 8E+00 4 . 60E+00 463 . 00 13. 80 - 1 .06E+00 l. 73E +00 9 11 . 23 16 . 7 0 3 . 52 E+00 2.4 2E+00 + /AM- 24 1 59 . 5 4 36.30 3 . 26E-0 1 3 . 63E - 0 1 3 . 63E-0 1 + CM- 24 3 1 03 . 76 23.00 2 . 3 1 E- 02 2. 2 0E-0 1 2 .2 0E- 01 228 . 18 10 . 60 9.63E - 02 4 . 66E- 01 277 . 6 0 1 4 . 00 7.65E- 02 3 .8 3E-01
1217/2017 11 :14:35AM Page 7 of7 Analysis Report for L2-SUB-WRS-AJGS-15A-SB 12/5/17
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
~ :Apex-Gamma Analysis Report for L2-SUB-WRS-AJGS-16A-SB 12f7/201 r 12:56:34PM Page J of6 12/5/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-AJGS-16A-SB Sample Description : 12/5/17 Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 7.955E+02 grams Facility : Dairyland_NPP Sample Taken On : 12/5/2017 2:39:00PM /
Acquisition Started : 12/7/2017 11:56:11AM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 3600.0 seconds Real Time : 3611.7 sec/ 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 : 3661 PEAK ANALYSIS REPORT Peak Analysis Performed on : 12/712017 12:56:25PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12ll/2017 12:56:34PM Page 2 of6 Analysis Report for L2-SUB-WRS-AJGS-1 6A-SB 12/5/17 Peak Energy ROI ROI Peak NetPeak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 77 . 06 1 47 - 158 154.67 l.23E+ 02 43 . 21 l . 24E+03 1.24 F 2 185 .5 5 366 - 376 371.60 8.26E+ Ol 33 .6 0 6.07E+ 02 1.36 F 3 209 . 15 415 - 4 22 418 . 79 4.25E+Ol 2 4 .8 8 3 . 83E+ 02 1. 29 F 4 238.55 469 - 4 85 477.58 3.30E +02 45 . 20 7 .4 0E+ 02 1.26 F 5 270.08 537 - 545 5 40.61 4.89E+Ol 26 . 13 2 .7 8E+ 02 1.55 F 6 295 . 02 582 - 595 590.48 7 .68E+Ol 25.94 3.62E+ 02 1.28 F 7 338. 15 673 - 680 676.74 4.66E+Ol 22.29 2 .0 2E+02 1.18 F 8 351 . 79 698 - 708 704.01 l . 45E+02 30.41 2 . 62E+ 02 1. 32 F 9 583 .0 3 1159 - 1175 1166.40 9 . 38E+Ol 22.65 l . 40E+02 1.50 F 10 609 . 1 6 1213 - 1227 1218 . 66 l . 08E+02 23.94 9 . 7 5E+ Ol 1. 90 F 11 910 . 87 18 17 - 18 27 182 1 .98 6 . 91E+Ol 20.96 8.04 E+ Ol 2 . 00 F 12 1332 . 15 2659 - 2669 2664. 44 2 . lSE+Ol 11. 90 3 . 09E+ Ol 1. 61 F 13 1460 . 30 2912 - 2930 2920. 72 5 . 96E+02 49.80 3.56E+ Ol 2 . 57 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma BACKGROUND SUBTRACT REPORT Peak Analysis Performed on : 12/7/2017 12:56:25PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 77. 06 l . 2 3E+02 43 .21 l.23E+02 4 .3 2E+ Ol F 2 1 85 . 55 8 . 26E+Ol 33 . 60 8.26E+O l 3 . 36E+O l F 3 209 . 15 4.25E +Ol 24.88 4 .2 5E+Ol 2.49E+ Ol F 4 238.55 3 . 30E+02 45.2 0 3.30E+02 4 . 52E +Ol F 5 270 . 08 4.89E+O l 26 .1 3 4 . 89E +Ol 2 . 61E+O l F 6 295 . 02 7 .6 8E+Ol 2 5.94 7 . 68E+Ol 2.59E+O l F 7 338.15 4 . 66E+Ol 22 .2 9 4.66E+01 2.23E+Ol F 8 35 1 . 79 1. 4 5E+02 30. 41 8 . 36E+ Ol 3 .7 2E+O l 6 . lSE+Ol 4.81E+Ol F 9 583.03 9 . 38E+Ol 22.65 9 . 38E+Ol 2.26E+ Ol F 10 609 . 16 l. 08E +02 23.94 4 . 1 2E+Ol 2.42E+ Ol 6 . 71E+Ol 3 . 41E+Ol F 11 910 .87 6 . 91E+Ol 20.96 6 . 91 E+O l 2.lOE+Ol F 12 1332 . 15 2 .l SE+Ol 11 . 90 2.15E+ Ol l . 19E+Ol F 13 1 460.30 5 . 96E+02 4 9 . 80 5 . 63E+O l 1. 71E+ Ol 5 . 40E+02 5 . 27E+ Ol
12nt2017 12:56:34PM Page 3 of6 Analysis Report for L2-SUB-WRS-AJGS-16A-SB 12/5/17 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(3/4) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K-40 0.96 1460.75
- 1 0. 67 7 . 39E+OO 8 . 30E-Ol PB- 212 0.99 77 . 11
- 17.50 2 . 19E~Ol 7.79E-02 238 .63
- 44 .6 0 2 .14 E- 01 3.13E- 02 BI - 214 0.34 609.3 1
- 46 . 30 9. 71E-02 4.96E- 02 1120 . 29 15.10 1238. 11 5 .94 1377.67 4 . 11 1407 . 98 2.48 1509 . 19 2.19 1764 .49 15 . 80 PB- 214 0.99 77 . 11
- 10. 70 3 . 57E -0 1 1 . 27E-01 295 . 21
- 19.20 1. 38E-01 4. 71E-02 351 . 92
- 37 .2 0 6.68E-02 5.23E-02 RA-226 0 . 93 186 .2 1
- 3.28 6 . llE-0 1 2 . 51E-01 AC-228 0 . 44 209 .28
- 4.40 2 . 53E -0 1 1. 4 9E-01 338 . 32
- 11 . 40 1. 59E-Ol 7 . 66E-02 794 . 70 4 . 60 911. 60
- 27.70 2.41E-Ol 7.38E - 02 964.60 5 .20 969 . 11 16.60
* = Energy line found in the spectrum,
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma
12rr/2017 12:56:34PM Page4 of6 Analysis Report for L2-SUB-WRS-AJGS-16A-SB 12/5/17 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0.969 7 . 39E+OO 8 . 30E- 01 PB-212 0.999 2 . 06E-0 1 2.92E-02 BI-214 0.348 9 . 71E-02 4.96E-02 PB-214 0.997 1. OOE-01 3.39E-02 RA-226 0.932 6 . llE-01 2.S l E-0 1 AC-228 0.445 2.07E-01 5.00E-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
12/7/2017 12:56:34PM Page 5 of6 Analysis Report for L2-SUB-WRS-AJGS-16A-SB 12/5/1 7 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/7/2017 12:56:25PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type N~e F 5 270.08 l . 35707E-02 26 . 74 F 9 583 .0 3 2 . 60685E-02 12 . 07 F 12 1332 .15 5.96813E- 03 2 7. 69 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_ NPP\Library\HOTLAB.NLB Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCilgrams) (keV) + K-40 14 60 . 75
- 1 0.67 7 . 39E+0 0 6.54E-01 6 .5 4E-0 l
+ AR- 41 1 293 . 6 4 99.16 4 . 84E+05 2 . 16E+06 2 .1 6E+06 + CO-6 0 11 73.22 100.0 0 1.32E-02 6 . 06E- 02 6 . 89E-02 1332.49 1 00.0 0 3.82E- 02 6 . 06E-02 + KR-85 5 13 .99 0 . 43 1 . 1 4E+0l 1 . 0 lE+0l l.0lE+0 l + Y-88 898 .0 4 93.70 -l.73E-0 2 3. 63E- 02 5.21E-02 1836.06 99.20 -2 .95E- 02 3 . 63E-02 + NB-9 4 702.63 100.00 - 3.60E- 02 3 . 83E-02 3 . 83E-02 871.10 100.00 -4.08E- 02 4 . 94E-0 2 + I-131 28 4. 30 6 . 06 4.1 7E-01 4 . 76E-0 2 6.34E- 01 364.48 81. 2 0 - 1.87E-02 4 . 76E -0 2 636 . 97 7 . 27 3 .00E-0 1 6 . 58E-01 + CS-1 3 4 604 . 70 97 . 60 - 3.57E-03 5 . 1 2E - 02 5 . 12E- 02 795 . 8 4 85.4 0 - 2 .69E- 0 2 5 . 57E- 02 + CS-137 661. 65 85.12 5 . 43E - 02 5.87E -0 2 5 . 87E-02
12/7/201 7 12:56:34PM Page 6 of6 Analysis Report for L2-SUB-WRS-AJGS-16A-SB 12/5/17 Nuclide Energy Yield(%) Activity NuclideMDA Line MDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV} + CE-144 80 .1 2 1. 36 - 2.46E+OO 2.BOE-01 3 . 64E+OO 133.51 11. 09 - 2 .9 6E-01 2 . BOE-01 + EU-1 52 121 . 78 28.40 -5 . 26E- 02 1 . llE-01 1. llE-0 1 244 . 69 7 .4 9 -3 .S SE- 01 5 . 36E-01 964 . 00 14.44 2.49E-01 4.38E-01 1408 . 00 20 . 74 l . 84E-01 2 . 32E-01 + EU-154 123 . 07 40.40 - 5 . 44E- 02 7.82E-02 7 . 82E-02 2 47.94 6 . 60 -5. 91E-0 1 5 . 28E- Ol 723.30 19.70 1. 41E- 0 1 2 . 31E- Ol 873 . 20 1 1.50 1.lOE- 01 4 . 46E-01 1004. 76 17.90 1. 68E-01 2 . 87E- 01 1274. 5 1 35 . 50 -1. 41E- 0 1 1. 69E-01 + EU- 155 86 . 54 32.80 2.35E-02 1 . 27E- 01 1. 27E-01 105. 31 21. 8Q - 3.66E-02 l.48E- 01 + BI - 2 1 4 609.31
- 46.30 9 . 7 1E-02 9.05E - 02 9 . 05E- 02 1120.29 15 .10 - 2 . 19£-01 4.41E- 01 1238 . 11 5.94 8 . 06£-01 1. 24E+OO 1377.67 4 . 11 2 . 20E - 01 l . 1 5E+OO 1407 . 98 2.48 1 . 54E+OO 1 . 94E+OO 1 509.19 2 . 19 - 4 . 23E-01 1 . 72E+OO 1 764 . 49 15 . 80 1 . 36£- 01 3 . 19E-01
+ PB-214 77 . 11
- 10 . 70 3 . 57E- 01 1 . 00E-01 3 . 84E-01 295.21
- 19 . 20 1.38E-01 1. 37E-01 351. 92
- 37.20 6 . 68E-02 1. OOE- 01
+ PA-2 28 89 . 95 22 .0 0 1. OOE+OO 4.51 E-0 1 7 . 70E - 01 93.35 35.00 1. 99E-01 4. 51E- 01 105 .00 16.30 5.66E-02 8.39E-01 129.22 2 . 97 3.80 E+OO 4 . 52E+OO 338 . 32 5.30 1.53£+00 2.92E+ OO 463.00 13.80 -8.39E- 0 1 l. 1 6E+OO 911. 23 16.70 1. 50E+OO 1.64E+OO + AM-241 59 . 54 36.30 - l.52E-02 2 .28E-01 2 . 28E - 0 1 + CM-243 103 .76 23 . 00 1.83E-02 1. 41E-01 1. 4 1E- 0 1 228.18 10.60 -2.52E-01 2 . 9 1E-0 1 277. 60 14 . 00 - l . 33E-01 2 . 4 1E-0 1
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
12/7/2017 1:59:10PM Page I of7 ~~~~pex-Gamma Analysis Report for L2-SUB-WRS-AJGS-17A-SB 12/5/17 GAMMA SPECTRUM ANALYSJS Sample Identification : L2-SUB-WRS.AJGS-17A-SB Sample Description : 12/5/1 7 Sample Type : 500 ml Marinelli Unit Sample Point /l L,::7v{ {?v£-9 Sample Size Facility 8.673E+02 grams / ~a~
- Dairyland_NPP Sample Taken On i0/3lt~
- 12/5/2017 2:43:00PM Acquisition Started : 12/7/2017 12:58:46PM /
Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli / Live Time : 3600.0 seconds Real Time : 3611.7 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 : 3662 PEAK ANALYSIS REPORT Peak Analysis Performed on 12/7/2017 1 :59:01 PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12m2011 1:59:10PM Page 2 of7 Analysis Report for L2-SUB-WRS-AJGS-17A-SB 12/5/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) M 1 7 4.4 5 142 - 159 149. 45 9. 2 4E+Ol 33 . 46 6 . 72E+ 02 0. 96 m 2 7 6 .8 4 142 - 159 154 . 22 l . 24 E+02 37 . 70 6 . 93E+02 0.96 F 3 92 . 95 182 - 1 93 1 86 . 45 8 . 25E+ Ol 3 8 . 53 l . 03E+03 1.25 F 4 1 85.7 5 365 - 379 3 7 2 . 00 8 .4 3E+Ol 31. 81 8 . 10E+ 02 1.20 F 5 2 3 8.47 4 73 - 4 82 47 7 .41 3 .1 7E+0 2 45 . 81 5 . 69E+02 1. 11 F 6 29 5 . 01 587 - 595 5 90.48 6 . 85E+0 1 26 .0 4 2 . 90E+02 1.20 F 7 338 . 14 672 - 682 676 . 7 1 8 . 84E+O l 27 . 4 0 2.44£+ 02 1. 66 F 8 3 5 1 .8 1 699 - 709 704.05 1 .62£+02 31. 57 2 .4 0E+02 1. 4 3 F 9 5 8 2. 99 11 61 - 1171 1166 . 32 l . 08E+02 2 5 . 21 1 . 10E+02 1. 75 F 10 60 9 . 09 1 212 - 1 225 1 218 . 52 9 . 93E+Ol 24 . 72 1. 30E+02 2 . 02 F 11 72 7 . 29 1451 - 1 46 0 14 5 4. 87 3 . 29E+Ol 1 6 . 85 7. 67 E+0 1 1. 88 F 12 911 . 10 1 81 4 - 1830 18 22.4 3 9 . 59E +Ol 22 . 69 7 . 21E+Ol 2.65 F 13 9 68 . 55 1933 - 194 2 1937 . 32 5 .1 7E +Ol 18 .2 7 6 . 62E+ Ol 1. 65 F 14 14 60 . 28 2912 - 2928 2920 . 68 6 . 89E+ 02 54 . 45 6.40E+ 0 1 2.32 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 : 12/7/2017 1:59:00PM 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. M 1 7 4 . 45 9.2 4E+O l 33 . 46 9 .2 4E+O l 3 . 35E +Ol rn 2 76 . 8 4 1 . 24E+ 02 37 . 70 l. 24E+02 3 . 77E+O l F 3 92 .9 5 8 . 25E+ Ol 38 . 53 8 . 25E+ Ol 3.8 5E+Ol F 4 185 . 75 8 .43E+O l 31. 8 1 8 .4 3E+ Ol 3.1 8E+Ol F 5 238 .4 7 3 .17E+02 45.81 3 .1 7E+02 4 . 58E+ Ol F 6 295.0 1 6 .8 5E+O l 26 . 04 6.85E+O l 2. 60E +0 1 F 7 338 .1 4 8 . 84E+Ol 2 7 .40 8.8 4E+ Ol 2 .7 4E+ Ol F 8 351 . 81 l . 62 E+0 2 3 1.57 8 . 36E+O l 3 . 72E+Ol 7.82E+ 0 1 4. 88E+O l F 9 582 . 99 1. 08E +02 2 5. 21 l . 08E+ 02 2 . 52E+O l F 10 609.0 9 9 . 93E+O l 2 4. 72 4. 1 2E+Ol 2 . 42E+Ol 5 . 82 E+ Ol 3 .4 6E+Ol F 11 727.29 3.29E+Ol 1 6 .8 5 3 . 29E+ Ol 1. 6 9E+Ol F 12 911 . 10 9 . 59E+Ol 2 2 .69 9 . 59E+O l 2 . 2 7 E+ Ol F 13 968 . 55 5 .1 7E+Ol 1 8 . 27 5 . 17E+Ol l .83 E+ Ol F 14 1460 . 28 6 . 89E+02 5 4. 45 5. 63E+ Ol l. 7 1E+ Ol 6 . 33E +02 5 . 71E+Ol
12/7/2017 1:59:10PM Page 3 of7 Analysis Report for L2-SUB-WRS-AJGS-17A-SB 12/5/17 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCilgrams) Uncertainty K- 40 0 . 96 1460 . 75
- 1 0 . 67 7 .95E+ OO 8 . 42E- Ol BI-212 0.60 727.17
- 11 . 80 2.02E-01 l . 04E- 01 7 85.42 2 .00 1620 . 56 2.75 PB-2 12 0 .99 77 . 11
- 1 7.50 2.03E- 01 6.2 9E -0 2 23 8.6 3
- 4 4 .60 l.88E-O l 2.89E-02 BI- 2 14 0.34 609.31
- 46.30 7 . 72 E-0 2 4 .61E- 02 112 0. 29 15 . 10 1238 . 11 5 . 94 1377 . 67 4 . 11 1407.98 2.48 1 509.19 2.19 17 64. 4 9 15 . 80 PB- 2 1 4 0 . 99 77 . 11
- 1 0 . 70 3 . 32E-0 1 l. 03E-01 295 . 21
- 19 . 20 1.13E-O l 4 . 33E-02 35 1. 92
- 37 .20 7.79E- 02 4 . 87E - 02 RA- 226 0. 96 186.21
- 3.28 5.73E-01 2 .18E-Ol AC-22 8 0.60 209.28 4.40 338.32
- 11.40 2. 77E-01 8.69E- 02 794 .7 0 4 .60 911 . 60
- 27.7 0 3 . 07E-Ol 7.38E-0 2 964.60 5.2 0 969 . 11
- 16 .60 2 . 91E- 01 l .04 E-Ol
* = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma
12/7/2017 1:59:10PM Page 4 of7 Analysis Report for L2-SUB-WRS-AJGS-17 A-SB 12/5/17 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K- 4 0 0. 966 7 . 95E+ OO 8. 4 2E- 01 BI-212 0. 604 2 .02E- 0 1 1. 0 4E- 0 1 PB- 2 12 0. 994 l. 8 1E- 0 1 2. 6 5E - 02 BI - 214 0 . 3 46 7 . 72E - 02 4 . 61E-02 PB- 214 0 . 9 95 9 . 19E- 02 3 . llE -02 RA- 226 0.966 5 .7 3E - 0 1 2 . 18E-0 1 AC- 228 0 . 604 2 . 94E- 0 1 4 . 94E - 0 2
? = 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
12/7/2017 1:59:10PM Page 5 of7 Analysis Report for L2-SUB-WRS-AJGS-17A-SB 12/5/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/7/2017 1:59:00PM 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 7 4 . 45 2 .56 634E-02 18 .11 F 3 92 . 95 2 . 2 90 98£- 02 23 . 36 To l. F 9 5 82 . 99 3 . 00515 E-02 1 1. 65 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted al 2.000sigma NUCLIDE MDA REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB Nuclide Energy Yield{%) Activity NuclideMDA Line MDA Name (pCi/grams) (pCilgrams) (pCilgrams) (keV) + K-4 0 1 46 0 . 75
- 10.67 7.95E+ 00 6 . 61E- 0 1 6.6 1E-01
+ / AR-4 1 1 293 . 64 99 . 16 2 . 2 8E+06 2. 92E+ 06 2 . 92E +0 6 + . CO-6 0 1173 . 22 1 00.00 7.33E-0 2 6 . 02E- 02 7 . 09E-0 2 1 332.4 9 100 .0 0 3 . 56E-02 6 . 02E-0 2 + KR-8 5 513. 99 0 . 43 4 . 97E+00 9 . 4 9E+00 9 .49E+00 + Y-88 89 8.04 93 . 70 2 .1 3 E- 02 3 . 43E-02 5.23E - 02 183 6. 06 99 . 20 9 . 33E - 0 3 3 .4 3E- 02 + NB-94 702 . 63 1 00 . 00 8.58E-0 3 3 . 99E-0 2 3 . 99E- 02 8 71. 10 1 00 . 00 -6 . l 9E - 02 4 . 29E- 02 + I- 13 1 284 . 3 0 6 .0 6 - 6 . 17E- 02 4 . 44E- 02 5 . 97E - 0 1 364 . 4 8 81 . 20 - 1. 53E-02 4. 44E-0 2 636 .97 7.27 2 . 90E-0l 6 . 26E - 0 1 + /CS-134 604. 70 97.60 -3 . 66E -03 4 . 67E-02 4.67E- 02
12/7/2017 1:59:10PM Page 6 of7 Analysis Report for L2-SUB-WRS-AJGS-17A-SB 12/5/17 Nuclide Energy Yield(%) Activity Nuclide MDA LlneMDA Name (pCi/grams) (pCilgrams) (pCilgrams) (keV) 795 .84 85.40 - 3.41E-02 4.67E-02 5.37E-02 CS-1 3 4 + CS -1 37 661 . 65 85.12 8.04E-02 5.64E-0 2 5 . 64E-02 + CE - 144 80.12 1. 36 -3.40E-01 2.64E-01 3 . 36E+OO 133. 5 1 11.09 S.16E-02 2 .6 4E- 01 + EU-152 121.78 28.40 -1 . lSE-01 1. 02E-01 l . 02E - 01 I 244 .6 9 964. 00 7.49 14.44
- 2 .98E-O l 6.36E-01 5.12E- 01 4.23E-01 1 408.00 20.74 1.47E-01 2. 1 9E-01 7.23E-0 2
+ I EU- 154 123 . 07 247 .94 40 . 40 6 . 60
- 3 .19E-02
-6.81E-01 7.23E-02 5.03E-01 723 . 30 19 .70 2 . 78E-Ol 2.32E- 01 873.20 11. so 4.45E- 02 3.84 E- 01 1004.76 17 . 90 4.92E-03 2.89E-01 1274.51 35.50 -9.19E-02 1.58E-01
+ EU-1 55 86.54 32 . 80 -4 . 29E-03 l. l SE-01 1. 15E- 01 105.31 21. 80 - 4.98E-02 1.43E-01 + BI - 214 609.31
- 46 . 30 7.72E-02 8 .73E-02 8.73E-02 1120.29 15.10 - 2.19E-01 3 . 94E-01 1238. 11 5.94 - l.9 8E-01 l.20E+O O 1377 . 67 4.11 5 . 55E-0 1 1 . 17E+OO 1407 . 98 2.48 l.23E+OO 1. 83E +OO 1509.19 2.19 6 . 74E-0 3 1 . 51E+OO 1764. 49 15 . 80 2 . 76E-01 3 .1 2E - 01
+ PB-214 77.11
- 10 .70 3 . 32E-01 9.04E-02 2.39E-01 295 . 21
- 19.20 1.13E-01 1 . 0lE-01 35 1 .9 2
- 37.20 7.79E-0 2 9 .0 4E-02
+ PA-228 89.95 22.00 -2.lSE - 03 4.34E-01 7 . 35E-01 93 . 35 35.00 5.91E-02 4.34E-01 105 . 00 16.30 3.96E-01 8 . 42E- 0 1 1 29.22 2.97 3 .24E-01 4.29E+OO 338.32 5 . 30 2.98E+OO 2.92E+OO 463.00 13 . 80 6.80E-02 l .16E+OO + + I AM-24 1 CM-243 911 . 23 59.54 103. 7 6 16 . 70 36.30 23.00 2.37E+OO 9 . 93E-03
- 6 . 69E-03 2 . 1 5E-01 1 . 37E-01 1 .57E+OO 2.lS E-0 1 l.37E-01 228.18 10.60 l.64E-01 2 . 85E- Ol 277 .6 0 14.00 7.98E-02 2 . 25E-0 1
+ = Nuclide identified during the nuclide identification
* = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
12f7/2017 1:59:10PM Page 7 of? Analysis Report for L2-SUB-WRS-AJGS-17A-SB 12/5/17
12/7/2017 4:17:43PM Pagel of 7 pex-Gamma Analysis Report for L2-SUB-WRS-AJGS-18A-SB 12/5/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-AJGS-18A-SB Sample Description : 12/5/17 Sample Type : 500 ml Marinelli
~;_1;v Unit Sample Point Sample Size : 9.751E+02 gram Facility : Dairyland_NPP Sample Taken On : 12/5/2017 2:46:00PM I u/yi.4 Acquisition Started : 12/7/2017 3:17:20PM Procedure : 500ml Marinelli /
Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 3600.0 seconds Real Time : 3611.3 se conds Dead Time : 0.31 % 7 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 : 3663 PEAK ANALYSIS REPORT Peak Analysis Performed on : 12/7/2017 4:17:34PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/7/2017 4 :17:43PM Page2 of7 Analysis Report for L2-SUB-WRS-AJGS-18A-SB 12/5/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 77 . 03 14 7 - 1 59 154.61 l . 04E +02 38.22 l . 35E+03 0. 94 M 2 122. 60 243 - 262 2 4 5 .7 2 4 . 58E +Ol 28.00 4 . 1 6E+02 1. 06 m 3 128 . 95 243 - 262 258 .4 3 6 . 39E +Ol 30.87 4 . 81E+02 1. 07 F 4 185 . 77 365 - 379 372 . 03 6.48E +Ol 30.22 8 . 7 1 E+02 1.10 M 5 238 . 55 473 - 488 477 . 58 3 . 74E+02 45.71 3 . 22E+02 1.27 m 6 241.46 473 - 488 48 3 . 39 7 . 59E+Ol 25.13 3 . 14E+02 1. 28 F 7 295 . 07 583 - 595 590.60 9 . 69E+Ol 27 . 88 3.71E+ 02 1. 26 F 8 338 . 24 672 - 685 676.91 5 . 54E+O l 23 . 32 3 . 35E+02 1.21 F 9 351 . 76 698 - 710 703.96 1 . 33E+02 28.88 2.99E+02 1.20 F 10 583 . 0 1 11 59 - 1172 1166 . 36 1.22E+02 25.24 l.05E+02 1. 66 F 11 609 . 18 1212 - 1226 1218.70 8.91E+Ol 22 . 85 1. 35E+02 1. 61 F 12 910 . 79 18 16 - 1827 1 82 1. 81 6 .81E+O l 20 . 01 7 . 70E+Ol 1. 78 F 13 968 . 85 1 933 - 1943 1937 .9 1 2 . 1 4E+Ol 18.72 8.25E+01 2.40 F 14 1460. 27 2912 - 2928 2920.65 5 .0 3E+02 4 6.0 4 2.99E+01 2.32 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 : 12/7/2017 4:17:34PM 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 77 . 03 1 . 04E+02 38 . 22 1 .04E+0 2 3.82E+Ol M 2 122 . 60 4.58E+O l 28 . 00 4 . 58E+Ol 2.80 E+Ol m 3 1 28 . 95 6 . 39E+Ol 30 . 87 6 . 39E+Ol 3 .0 9E +Ol F 4 1 85.77 6 . 48E+Ol 30.22 6.48E+Ol 3 . 02 E+Ol M 5 238.55 3 . 74E+02 4 5 . 71 3 . 74E+02 4 . 5 7E+O l m 6 241.46 7 . 59E+Ol 25 . 13 7 .59E+ Ol 2 . 5 1 E+Ol F 7 295.07 9 . 69E+Ol 27.88 9 . 69E+Ol 2 . 79E+Ol F 8 338.24 5 .5 4E+Ol 23 . 3 2 5 . 54E+ Ol 2 . 33E+Ol F 9 35 1. 76 l . 3 3E+02 28 . 88 8.36E+O l 3.72E+O l 4 . 90E+O l 4 . 71E+Ol F 10 583 . 01 1 .2 2E+02 25.24 l .2 2E+ 02 2.52E+ Ol F 11 609. 1 8 8 . 91E+Ol 22.85 4.12E +Ol 2.42E+Ol 4.80E+O l 3.33E+Ol F 12 910.79 6.81E+Ol 20 . 01 6.BlE+O l 2.00E+Ol F 13 968 . 85 2 . 14E+Ol 18 .7 2 2 .1 4E+Ol l.87E+Ol F 14 1460 .27 5 . 03E+02 46 . 0 4 5 . 63E+Ol l.71E+01 4 . 47 E+02 4. 91E+Ol
12!7/2017 4:17:43PM Page 3 of7 Analysis Report for L2-SUB-WRS-AJGS-18A-SB 12/5/17 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used : C:\Canberra\Apex\Root\Dairyland_NPP\Library\HOTLAB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%) Activity Activity Name Confidence (keV) (pCi/grams) Uncertainty K-40 0.96 1460.75
- 10 . 67 4 . 99E+OO 6 . lSE- 01 PB-212 0.99 77 . 11
- 17. 50 1.Sl E- 01 5.61E- 02 238 . 63
- 44 .6 0 1. 98E-01 2.63E-02 BI -214 0 . 34 609 . 31
- 46 . 30 5 . 66E-02 3.94E- 02 1120. 2 9 15 . 10 1238 .11 5.94 1377. 67 4 . 11 1407.98 2 .48 1 509 .1 9 2.19 1764 . 49 15.80 PB- 2 1 4 0.99 77 .11
- 10 . 70 2 .4 6E-Ol 9.18E-02 295.21
- 19 . 20 1. 42E-01 4.lSE-02 351.92
- 37.20 4.34E-02 4.18E-02 RA-226 0 . 96 186.21
- 3.28 3.92E- 0 1 1.84E-01 AC - 228 0.58 209 . 28 4.40 338 . 32
- 11. 40 1.55E- Ol 6 . 55E-02 7 94 . 70 4 . 60 911. 60
- 27 . 70 l . 94E-01 5.7SE-02 96 4.60 5.20 969 .11
- 16.60 1. 07E - 01 9.39E- 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
1217/2017 4:17:43PM Page4 of7 Analysis Report for L2-SUB-WRS-AJGS-18A-SB 12/5/17 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K-40 0.964 4.99E+OO 6 . 15E- 01 PB-212 0.999 1. 81E-O l 2.40E-02 BI -214 0.348 5.66E-02 3.94E-02 PB-21 4 0.997 7.99E-02 2.83E-02 RA- 226 0.969 3.92E-01 l .84E- 01 AC - 228 0.589 1. 64E - 0 1 3.93E-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
12/7/2017 4:17:43PM Page5 of7 Analysis Report for L2-SUB-WRS-AJGS-18A-SB 12/5/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/7/2017 4:17:34PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type M 2 122 . 60 1. 27116E-02 30.59 Tol. m 3 128.95 1 . 77575E- 02 24.14 Tol. m 6 241.46 2 . 1072 1E- 02 16 . 56 F 10 583 .01 3.39461E-02 10.32 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 Nuclide MDA LineMDA Name (pCilgrams) (pCi/grams) (pCilgrams) (keV) + K- 40 1460.75
- 10.67 4.99E+00 5 . 19E-01 5 .19E-0l
+ AR-41 1293 .6 4 99.16 2.02E+06 5.43E+06 5.43E+06 + I CO-60 1173.22 1332. 4 9 100.00 100.00 3.07E- 02
-7 . 21£-04 4.43E-02 5 . 54E-02 4.43E-02
+ KR-85 513 . 99 0.43 l. 09E+0l 8.73E+00 8.73E+00 + Y-88 898.04 93 . 70 -2 .1 3E-02 3.31£-02 3 . 81E - 02 1 836.06 99 . 20 -2.65E-02 3.31E-02 + NB-94 702 . 63 100.00 1.48E-02 3.SlE- 02 3.SlE- 02 871.10 100.00 -1.5 1E-02 3.69E-02 + I-131 284.30 6 . 06 -8. 45E-02 3.95E-02 5.13E-01 364.48 81. 2 0 -2. 4 4E-02 3.95E-02
12/7/2017 4:17:43PM Page6 of7 Analysis Report for L2-SUB-WRS-AJGS-18A-SB 12/5/17 Nuclide Energy Yield(%) Activity NuclideMDA LineMDA Name (pCi/grams) (pCilgrams) (pCi/grams) (keV)
/ I-131 636.97 7.27 -3 . lB E- 01 3.95E-02 5 . 45E-0 1
+ CS-134 604 . 70 97.60 -8.61 E-03 4.14E- 02 4. 1 4E-02 795.84 85 . 40 - 7.35E-03 4.44E-02 + /cs-137 661 .65 85.12 4.87E-02 5.00E -0 2 5 .0 0E-02 + CE- 1 44 80. 1 2 1. 36 - 1 . 77E+OO 2.3 5E-01 2 . 94E+OO 1 33.51 11. 09 - 7.30E-02 2 . 35E-01 + / EU-15 2 1 21.78 28.40 - 2 . 24E- 02 9 . 13E- 02 9. J.3E - 02 244.69 7 . 49 -3 . 27E-02 4.39E-01 964.00 14.44 9.44E-02 3.25E-01 + / EU-154 1408.00 123.07 247.94 20 .74 40 . 40 6.60 2.89E-02
-2.03E-02
-5. 7 3E-02 6.47E - 02
- 1. 75E-01 6.4 7E-02 4.26E-0 1 723.30 19.70 3. 4 8E - 02 1. 89E - 01 873 . 2 0 11.50 1. 21E-01 3 . 20E-01 1004.76 1 7 .9 0 - 9.07E-02 2 . 17E-01 127 4 .5 1 35.50 -5 . 32E-0 2 1. 39E-01
+ EU- 1 55 86.54 32.80 - 7 . SlE-02 1 . 02E - 01 1 . 02 E-01 105.31 21. 80 3 . 63E-0 2 1. 2 7E- 01 + BI- 214 609 . 3 1
- 46.30 5 . 66E-02 7.92E- 02 7 . 92E-02 1120.29 15.10 2.lOE- 01 3.62E- 01 1 23 8. 1 1 5. 94 1. 53E- 0 1 l.OlE+OO 13 77 . 6 7 4 . 11 8.43E - 03 9.36E-0 1 1 4 07.98 2.48 2.41E -Ol 1 . 4 6E +OO 1509 . 19 2. 19 - 4.29E-01 1 . 4 3E+ OO 1764.49 15 . 8 0 l. 4 9E - 01 2. 60E-01
+ PB-214 77 . 11
- 10 .70 2 . 46E-01 8.61E -02 3.34E-01 295 . 21
- 19 . 20 l . 42E - 0 1 1.lOE-0 1 351 . 92
- 37 . 20 4 . 3 4E - 0 2 8 . 61E-02
+ PA- 228 89. 95 22 . 0 0 l . 18E+OO 4.00E-01 6 . 95E-01 93 .3 5 35 . 00 - 2.51E-01 4 . 00E -01 1 05.00 16 .30 4 . 74 E- 01 8 . 04E-0 1 12 9. 22 2.97 -1.29E+OO 4 .1 2E+OO 338 . 32 5 . 30 3 . 58E- 01 2.68E+00 +
/ AM-24 1 463 . 00 911 .2 3 59 . 5 4 13 . 80 16 . 70 36 . 30 1.87E - 01 1 . 28E+OO
-2.13E - 03 1. 88E-01 1.0BE+OO
- 1. 42E+OO l.88E-01
+ CM-243 1 03.76 23.00 9.63E - 02 1. 22E-01 1. 22E-01 228 . 18 1 0 . 60 l.74E-01 2 . 56E-01 277 . 60 14 .00 -l.23E-02 1. 958 -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
1217/2017 4:17:43PM Page 7 of7 Analysis Report for L2-SUB-WRS-AJGS-18A-S8 12/5/17
~ Apex-Ga.mma Analysis Report for L2-SUB-WRS-AJGS-19A-SB 12/7/2017 5:20:36PM Page 1 of6 12/5/17 GAMMA SPECTRUM ANALYSIS Sample Identification : L2-SUB-WRS-AJGS-19A-SB Sample Description : 12/5/17 Sample Type : 500 ml Marinelli /
Unit Sample Point Sample Size 9.447E+02 grams
/
Facility : Dairyland_NPP Sample Taken On : 12/5/2017 2:50:00PM / Acquisition Started : 12/7/2017 4:20:13PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli/ Live Time : 3600.0 seconds Real Time : 3611.3 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 : 3664 PEAK ANALYSIS REPORT Peak Analysis Performed on 12nt2017 5:20:27PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
12/7/2017 5:20:36PM Page 2 of6 Analysis Report for L2-SUB-WRS-AJGS-19A-SB 12/5/17 Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV) F 1 209.35 416 - 424 419.19 3.SSE+Ol 26 . 34 4 . 23E+02 1. 09 F 2 238.40 473 - 481 477.28 2 . 18E+02 41. 0 4 5.41E+02 1. 07 F 3 295.14 582 - 594 590 . 74 8 . 96E+Ol 27.51 3.56E+0 2 1. 2 4 F 4 3 51.66 697 - 709 703.75 1. 52E +02 30.47 2.70E+02 1. 36 F 5 583.00 1157 - 1173 1166.34 9 . 07E+Ol 22.47 l . 17E+02 1. 67 F 6 609.21 1212 - 1227 1218. 75 l . 05E+02 23.93 l . 30E+02 1. 66 F 7 910.72 1816 - 1829 182 1 .67 5 . 98E+Ol 19.5 1 9 . 25E+Ol 1. 87 F 8 968. 96 1933 - 1944 1938.13 3.47E +Ol 16.85 7.71E+Ol 1. 99 F 9 1119.93 2235 - 2246 2240.05 3 . 84E+01 15 . 84 6 . 60E+Ol 1. 57 F 10 1460 . 28 2911 - 2928 2920.67 5.2 4E+02 47. 0 1 2.75E+Ol 2 . 38 F 11 1729 . 08 3453 - 3463 3458 . 24 1 .67 E+Ol 8.79 2 .50E+OO 2 . 10 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 : 12/7/2017 5:20:27PM Env. Background File : C:\Canberra\Apex\Root\Dairyland_NPP\Data\0000001364.CNF Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert. F 1 209.35 3.SSE+Ol 26 .34 3 . SSE+Ol 2.63E+Ol F 2 238.40 2 . 18E+02 41. 04 2.18E+02 4. l OE+Ol F 3 295.14 8.96E+Ol 27.51 8.96E+Ol 2.75E+Ol F 4 351.66 1 . 52E+02 30.47 8 . 36E+Ol 3.72E+ 0 1 6.82E+Ol 4.81E+Ol F 5 583.00 9.07E+Ol 22.47 9.07E+Ol 2.25E+ Ol F 6 609.21 1.05E+0 2 23.93 4 . 12E+Ol 2.42E +Ol 6.37E+Ol 3.40E+Ol F 7 910.72 5 . 98E+Ol 19.51 5 . 98E+O l 1 . 95E+Ol F 8 968 .96 3 .4 7E+Ol 16.85 3.47E+Ol 1. 69E+Ol F 9 1119. 93 3 . 84E+Ol 15 .8 4 3.84E+Ol 1. 58E+01 F 10 1460.28 5 . 24E+02 47.01 5 . 63E+Ol 1.7 1E+Ol 4.68E+02 5.00E+Ol F 11 1729. 08 1. 67E+Ol 8.79 1 . 67E+Ol 8.79E+OO
=
M First peak in a multiplet region
=
m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000sigma
12/7/2017 5:20:36PM Page 3 of6 Analysis Report for L2-SUB-WRS-AJGS-19A-S8 12/5/17 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 .9 6 1460.75
- 10 . 67 5.39E +OO 6.SOE-01 PB- 212 0 . 55 77.1 1 17 .50 238 . 63
- 44.60 1.19E-Ol 2 . 32E- 02 BI -2 1 4 0.58 609.3 1
- 46 .30 7 . 76E-02 4.17E-02 1120.29
- 15. 1 0 2.48E- 01 1. 03E-01 12 38 . 11 5. 94 1377 . 67 4 . 11 1407.98 2 . 48 1509 .19 2 . 19 1764 . 49 1 5 . 80 PB- 214 0 .71 77 .1 1 1 0.70 295 . 21
- 19.20 1. 36E-01 4.22E -0 2 351.92
- 37.20 6 . 23E-02 4. 41E-02 AC- 228 0 . 39 209 . 28
- 4 . 40 1 . 78E-01 l . 33E-01 338 . 32 11.40 794.70 4. 60 911. 60
- 27.70 l.76E-01 5 . 78E - 02 964.60 5.20 969 . 11
- 1 6 . 60 1. 80E-01 8.76E-02
" = Energy line found in the spectrum.
- =Manually added nuclide.
? =Manually edited nuclide.
@ =Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT
1217/2017 5:20:36PM Page4 of6 Analysis Report for L2-SUB-WRS-AJGS-19A-SB 12/5/17 Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCilgrams) K- 4 0 0 .965 5 . 3 9E+OO 6. SOE- 01 PB- 212 0.555 1.1 9E- 01 2.32E-0 2 BI- 214 0.581 1. 02E-01 3 . 87 E-02 PB- 2 14 0. 71 5 l. OlE-01 3. 0 SE- 02 AC-22 8 0 . 3 94 1. 77E-01 4.53E-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
12(1/2017 5:20:36PM Page 5 of 6 Analysis Report tor L2-SUB-WRS-AJGS-19A-SB 12/5/17 UNIDENTIFIED PEAKS Peak Locate Performed on : 12/7/2017 5:20:27PM Peak Locate From Channel : 100 Peak Locate To Channel : 4096 Peak CPS(%) Peak Tolerance Peak No. Energy (keV) Peak Size (CPS) Uncertainty Type Nuclide F 5 58 3 .00 2 .5 1831E-02 12 . 3 9 F 11 172 9. 0 8 4. 637 97E- 0 3 2 6 .3 3 Sum 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 Yreld{3/4) Activity NuclideMDA Line MDA Name (pCilgrams) (pCilgrams) (pCi/grams) (keV) + K-4 0 1 460 . 7 5
- 10 . 67 5 . 39E+0 0 5. 3 3E-0 1 5 .33E-0 1
+ AR-41 1 2 93. 64 99 .16 6 .90 E+ 05 7. 86E+ 06 7 . 86E+ 0 6 + CO- 60 1173. 22 1 0 0 .0 0 - 1. 44 E- 02 4. 95E - 02 5 . 7 6E-0 2 1332 . 49 1 00. 00 2 . llE- 02 4.9 5E-0 2
+ KR- 8 5 513 . 9 9 0. 43 l .lSE+0l 8. 84E+00 8 . 8 4E +00 + Y-8 8 89 8.04 93. 70 - 9 . 0 SE- 0 3 3 .24E-02 4. 45 E- 0 2 183 6 . 06 99 . 20 - 6 . 85£-0 3 3 . 24E- 02 + NB- 94 702 . 63 10 0 .0 0 -1. 0 lE-02 3.78E-02 3 . 78£-02 871 . 1 0 1 0 0 . 00 8.94E-03 3.93 £ - 02 + I-131 284 .30 6. 06 2 . 54£ - 0 2 4. 03E-0 2 5 . 3 7 E-01 364 . 4 8 8 1. 2 0 - 2 . 0SE-02 4 . 03E-0 2 63 6. 97 7 . 27 - l.73E-03 5 . 59E- 0 1 + CS-1 34 60 4. 70 97. 60 -3 . 73 E-04 4 . 24 E- 02 4. 2 4E- 02 795 . 8 4 85 . 40 - 2 . 33E-02 4 . 3 1 E-02 + CS- 137 661.65 8 5 .1 2 5 .2 1 E-02 5.0SE-0 2 5 . 0SE- 02 + CE-144 80 . 12 1. 36 - 3 . 03E- 01 2 .4 3E- 0 l 2 . 96E+ 0 0
12/7/2017 5:20:36PM Page6of6 Analysis Report for L2-SUB-WRS-AJGS-19A-SB 12/5/17 Nuclide Energy Yield(%) Activity NuclideMDA Line MDA Name (pCUgrams) (pCilgrams) (pCi/grams) (keV} CE-144 133.51 11.09 2.41E-01 2.43E-01 2 .4 3E-01 + EU - 152 12 1 .78 28 . 4 0 -6.14E- 02 9.39E-02 9 . 39E-02 244.69 7 . 49 -6.40E-01 4.42E - 0 1 964.00 1 4.44 2.48E-01 3.46E-01 1408 . 00 20 . 74 1.08E-01 1. 83E-01 + EU- 154 123.07 40.40 - 1.31E-02 6.63E-02 6 . 63E-02 247.94 6.60 - 1.26E+OO 4.46E-01 723.30 19.70 -1 . 80E - 02 l . 88E-01 873.20 11.50 -2.93E-03 3 . 32E -0 1 1004.76 17 . 90 1. 85E-01 2 . 54E-01 1274 . 51 35.50 -1 .lSE-02 1. 24E-0 1 + EU-155 86.5 4 32 . 80 -1. 30E-01 1. 04E-01 l.04E-01 1 05.31 21. 80 9 .75E-0 3 1.28E-0 1 + BI-214 609.31
- 46 .30 7 . 76E-02 8.21E-02 8.21E-02 1120 . 29
- 15.10 2 .4 8E-01 2.13E-0 1 1238. 11 5.9 4 6 . 19E-01 1. 05E+ OO 1377.67 4 . 11 8.96E-01 9 . 76E-01 14 07 . 98 2.48 9 .0 2E-01 1 . 53E+00 1509.19 2 . 19 -1 . llE+ OO l.42E+OO 1764.49 15.80 l . 4 2E -01 2.83E-0 1
+ PB-21 4 77 .11 10.70 1 . 26E-01 8.68E- 02 4.03E-01 295.21
- 19 . 20 1. 36E-01 l.12E-01 351 .92
- 37.20 6.23E-02 8.68E-02
+ PA-228 89.95 22.00 9.25E-01 4.39E-Ol 7 . 47E-0 1 93.35 35.00 8.56E-02 4.39E-01 105.00 16 . 30 2 . 06E-01 8.28E-01 129 .22 2.97 l.0 7E+OO 4.38E+OO 338.32 5 .30 2.03E+OO 2 . 85E+OO 463.00 13.80 - 3.65E-02 1. 08E +OO 911. 23 1 6.70 1 . llE+OO 1. 52E+OO + AM-241 59.54 36 . 30 5.29E- 02 l.90E- 0 1 l. 90E-01 + CM-243 103. 76 23.00 4 . 85E-02 1.22E-01 l . 22E - 01 228 . 18 1 0.60 5.76E-02 2.SOE-01 277.60 14 . 00 -7.96E-02 2.08E- 01
+ = Nuclide identified during the nuclide identification
= Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
FSS RELEASE RECORD - REVISION 1 SURVEY UNIT L2-011-101 ~ AREA NORTH OF LSE FENCE LACROSSESOLUTIONS ATTACHMENT 8 GEL LABORATORIES ANALYTICAL REPORTS 322
lij =I* ILaboratories LLc PO Box:10712 Charteston SC29417 a member of The GEL Group INC 2040 Savage Road Charteston SC 29407 P 843 556.8171 F 84,766.1178 gel. com October 15, 2019 Mr. Jason Q. Spaide LaCrosseSolutions S4601 State Hwy 35 Genoa, Wisconsin 54632 Re: LACBWR Site Restoration Project Work Order: 490846
Dear Mr. Spaide:
GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for the sample(s) we received on September 20, 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 37 SDG: 490846
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: 490846 GEL Work Order: 490846 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 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-SUB-TDS-FJGS-A24-SB Project: ENRG07001 Sample ID: 490846001 Client ID: ENRG070 Matrix: Soil Collect Date: 03-JUL-19 12:56 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0174 +/-0.0686 0.134 0.400 pCi/g JXC9 10/07/19 1511 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 88.4 (25%-125%) Notes: 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 3 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-SUB-TDS-FJGS-A25-SB Project: ENRG07001 Sample ID: 490846002 Client ID: ENRG070 Matrix: Soil Collect Date: 03-JUL-19 13:01 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0855 +/-0.0784 0.128 0.400 pCi/g JXC9 10/07/19 1511 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 88.4 (25%-125%) Notes: 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 4 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-SUB-TDS-FJGS-A12A-SB Project: ENRG07001 Sample ID: 490846003 Client ID: ENRG070 Matrix: Soil Collect Date: 12-JUL-19 13:02 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0271 +/-0.0476 0.104 0.400 pCi/g JXC9 10/07/19 1511 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 84 (25%-125%) Notes: 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 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-107-FJGS-005-SS Project: ENRG07001 Sample ID: 490846004 Client ID: ENRG070 Matrix: Soil Collect Date: 08-AUG-19 15:29 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.033 +/-0.0803 0.145 0.400 pCi/g JXC9 10/07/19 1511 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 70.7 (25%-125%) Notes: 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 6 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-107-FJGS-016-SS Project: ENRG07001 Sample ID: 490846005 Client ID: ENRG070 Matrix: Soil Collect Date: 09-AUG-19 14:00 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0505 +/-0.0835 0.167 0.400 pCi/g JXC9 10/07/19 1511 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 81.8 (25%-125%) Notes: 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 7 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-101-FJGS-003-SS Project: ENRG07001 Sample ID: 490846006 Client ID: ENRG070 Matrix: Soil Collect Date: 08-AUG-19 14:21 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.00619 +/-0.0654 0.121 0.400 pCi/g JXC9 10/08/19 0817 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 81.8 (25%-125%) Notes: 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 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-102-FJGS-010-SS Project: ENRG07001 Sample ID: 490846007 Client ID: ENRG070 Matrix: Soil Collect Date: 15-AUG-19 08:48 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0125 +/-0.0576 0.106 0.400 pCi/g JXC9 10/08/19 1106 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 79.6 (25%-125%) Notes: 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 9 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-103-FJGS-008-SS Project: ENRG07001 Sample ID: 490846008 Client ID: ENRG070 Matrix: Soil Collect Date: 14-AUG-19 10:25 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0247 +/-0.0832 0.149 0.400 pCi/g JXC9 10/07/19 1510 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 90.6 (25%-125%) Notes: 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 10 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-104-FJGS-006-SS Project: ENRG07001 Sample ID: 490846009 Client ID: ENRG070 Matrix: Soil Collect Date: 23-AUG-19 08:44 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0047 +/-0.0675 0.130 0.400 pCi/g JXC9 10/07/19 1510 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 81.8 (25%-125%) Notes: 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 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-105-FJGS-008-SS Project: ENRG07001 Sample ID: 490846010 Client ID: ENRG070 Matrix: Soil Collect Date: 23-AUG-19 13:39 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0453 +/-0.0588 0.125 0.400 pCi/g JXC9 10/08/19 0817 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 77.3 (25%-125%) Notes: 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 12 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-106-FJGS-004-SS Project: ENRG07001 Sample ID: 490846011 Client ID: ENRG070 Matrix: Soil Collect Date: 28-AUG-19 10:39 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.024 +/-0.0648 0.117 0.400 pCi/g JXC9 10/07/19 1510 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 92.8 (25%-125%) Notes: 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 13 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-106-FJGS-017-SS Project: ENRG07001 Sample ID: 490846012 Client ID: ENRG070 Matrix: Soil Collect Date: 28-AUG-19 14:31 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.023 +/-0.0397 0.0872 0.400 pCi/g JXC9 10/08/19 0817 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 84 (25%-125%) Notes: 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 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-106-FJGS-018-SS Project: ENRG07001 Sample ID: 490846013 Client ID: ENRG070 Matrix: Soil Collect Date: 28-AUG-19 14:51 Receive Date: 20-SEP-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0371 +/-0.0984 0.174 0.400 pCi/g JXC9 10/07/19 1510 1921875 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 86.2 (25%-125%) Notes: 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 15 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-SUB-TDS-CJGS-A01-SB Project: ENRG07001 Sample ID: 490846014 Client ID: ENRG070 Matrix: Soil Collect Date: 27-JUN-19 10:51 Receive Date: 20-SEP-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 0.0233 +/-0.0336 0.0405 0.400 pCi/g MXS2 10/14/19 0853 1919949 1 Americium-243 U -0.0154 +/-0.0278 0.0708 0.400 pCi/g Curium-243/244 U -0.00404 +/-0.0179 0.0466 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U -0.00044 +/-0.00286 0.0059 0.010 pCi/g MXS2 10/13/19 1023 1919950 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U 0.0035 +/-0.0399 0.0848 0.400 pCi/g MXS2 10/14/19 0738 1919951 3 Plutonium-239/240 U -0.00481 +/-0.0332 0.0808 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U 3.99 +/-3.10 5.16 5.00 pCi/g MXS2 10/14/19 2041 1919952 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U -0.464 +/-1.15 1.82 5.00 pCi/g TXJ1 10/11/19 0816 1921366 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 0.312 +/-0.0643 0.0341 1.00 pCi/g MXR1 10/05/19 1250 1919313 6 Cobalt-60 U 0.00967 +/-0.0204 0.0438 pCi/g Europium-152 U 0.031 +/-0.0481 0.0992 pCi/g Europium-154 U 0.0292 +/-0.0612 0.129 pCi/g Europium-155 U 0.00749 +/-0.0528 0.102 pCi/g Niobium-94 U 0.00999 +/-0.0155 0.0334 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0873 +/-0.113 0.192 0.400 pCi/g JXC9 10/07/19 1510 1921875 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U 4.06 +/-4.58 7.69 10.0 pCi/g EW3 10/04/19 0308 1921574 8 Liquid Scint C14, Solid "As Received" Carbon-14 U -2.58 +/-2.02 3.60 5.00 pCi/g TXP3 10/09/19 1559 1921585 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U -0.45 +/-0.886 1.55 2.00 pCi/g JJ3 10/06/19 0743 1921541 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U -1.7 +/-5.55 7.59 10.0 pCi/g TXJ1 10/11/19 1543 1921313 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 16 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-SUB-TDS-CJGS-A01-SB Project: ENRG07001 Sample ID: 490846014 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 1.70 +/-2.13 3.60 5.00 pCi/g TXJ1 10/11/19 1554 1921355 12 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 RYH1 09/25/19 1209 1919153 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, 71.8 (15%-125%) Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 84.8 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 97.2 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 55.2 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 55.2 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 108 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 86.2 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 104 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 64.4 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 81.5 (25%-125%) Notes: Page 17 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 15, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-SUB-TDS-CJGS-A01-SB Project: ENRG07001 Sample ID: 490846014 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 18 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Report Date: October 15, 2019 LaCrosseSolutions Page 1 of 7 S4601 State Hwy 35 Genoa, Wisconsin
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Mr. Jason Q. Spaide Workorder: 490846 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 1919949 QC1204388648 490846014 DUP Americium-241 U 0.0233 U 0.0153 pCi/g N/A N/A MXS2 10/14/19 08:53 Uncertainty +/-0.0336 +/-0.0404 Americium-243 U -0.0154 U -0.00504 pCi/g N/A N/A Uncertainty +/-0.0278 +/-0.0171 Curium-243/244 U -0.00404 U -0.0184 pCi/g N/A N/A Uncertainty +/-0.0179 +/-0.0318 QC1204388649 LCS Americium-241 1.92 1.77 pCi/g 92.4 (75%-125%) 10/14/19 08:53 Uncertainty +/-0.186 Americium-243 U -0.0226 pCi/g (75%-125%) Uncertainty +/-0.0444 Curium-243/244 2.26 1.89 pCi/g 83.8 (75%-125%) Uncertainty +/-0.191 QC1204388647 MB Americium-241 U -0.00254 pCi/g 10/14/19 08:53 Uncertainty +/-0.0237 Americium-243 U 0.000499 pCi/g Uncertainty +/-0.0229 Curium-243/244 U -0.00426 pCi/g Uncertainty +/-0.0193 Batch 1919950 QC1204388651 490846014 DUP Neptunium-237 U -0.00044 U -0.00249 pCi/g N/A N/A MXS2 10/13/19 10:23 Uncertainty +/-0.00286 +/-0.00293 QC1204388652 LCS Neptunium-237 1.44 1.55 pCi/g 108 (75%-125%) 10/13/19 10:23 Uncertainty +/-0.056 QC1204388650 MB Neptunium-237 U -0.00178 pCi/g 10/13/19 10:23 Uncertainty +/-0.00276 Page 19 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 490846 Page 2 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 1919951 QC1204388654 490846014 DUP Plutonium-238 U 0.0035 U 0.0176 pCi/g N/A N/A MXS2 10/14/19 07:38 Uncertainty +/-0.0399 +/-0.0379 Plutonium-239/240 U -0.00481 U -0.0268 pCi/g N/A N/A Uncertainty +/-0.0332 +/-0.0203 QC1204388655 LCS Plutonium-238 U 0.00911 pCi/g 10/14/19 07:38 Uncertainty +/-0.0382 Plutonium-239/240 1.96 1.86 pCi/g 95.3 (75%-125%) Uncertainty +/-0.244 QC1204388653 MB Plutonium-238 U -0.00287 pCi/g 10/14/19 07:38 Uncertainty +/-0.0268 Plutonium-239/240 U 0.00918 pCi/g Uncertainty +/-0.0253 Batch 1919952 QC1204388657 490846014 DUP Plutonium-241 U 3.99 U 3.44 pCi/g N/A N/A MXS2 10/15/19 02:00 Uncertainty +/-3.10 +/-2.41 QC1204388658 LCS Plutonium-241 162 184 pCi/g 113 (75%-125%) 10/15/19 04:04 Uncertainty +/-4.54 QC1204388656 MB Plutonium-241 U 1.84 pCi/g 10/14/19 22:45 Uncertainty +/-2.15 Rad Gamma Spec Batch 1919313 QC1204386990 490846014 DUP Cesium-137 0.312 0.350 pCi/g 11.5 (0%-20%) MXR1 10/05/19 15:03 Uncertainty +/-0.0643 +/-0.0553 Cobalt-60 U 0.00967 U 0.0062 pCi/g N/A N/A Uncertainty +/-0.0204 +/-0.0199 Europium-152 U 0.031 U -0.00481 pCi/g N/A N/A Uncertainty +/-0.0481 +/-0.0438 Page 20 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 490846 Page 3 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 1919313 Europium-154 U 0.0292 U 0.00422 pCi/g N/A N/A MXR1 10/05/19 15:03 Uncertainty +/-0.0612 +/-0.0613 Europium-155 U 0.00749 U -0.0257 pCi/g N/A N/A Uncertainty +/-0.0528 +/-0.0382 Niobium-94 U 0.00999 U 0.0181 pCi/g N/A N/A Uncertainty +/-0.0155 +/-0.0137 QC1204386991 LCS Americium-241 487 510 pCi/g 105 (75%-125%) 10/05/19 12:52 Uncertainty +/-5.36 Cesium-137 167 164 pCi/g 98.3 (75%-125%) Uncertainty +/-3.96 Cobalt-60 108 107 pCi/g 98.5 (75%-125%) Uncertainty +/-3.72 Europium-152 U -0.591 pCi/g Uncertainty +/-1.40 Europium-154 U -0.258 pCi/g Uncertainty +/-0.900 Europium-155 U 0.655 pCi/g Uncertainty +/-1.02 Niobium-94 U 0.231 pCi/g Uncertainty +/-0.450 QC1204386989 MB Cesium-137 U -0.00479 pCi/g 10/05/19 12:51 Uncertainty +/-0.0152 Cobalt-60 U -0.00517 pCi/g Uncertainty +/-0.0145 Europium-152 U -0.000709 pCi/g Uncertainty +/-0.0424 Europium-154 U -0.0286 pCi/g Uncertainty +/-0.038 Europium-155 U 0.0641 pCi/g Uncertainty +/-0.0928 Page 21 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 490846 Page 4 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 1919313 Niobium-94 U 0.00784 pCi/g MXR1 10/05/19 12:51 Uncertainty +/-0.0142 Batch 1921366 QC1204391968 490846014 DUP Nickel-59 U -0.464 U -0.171 pCi/g N/A N/A TXJ1 10/11/19 08:17 Uncertainty +/-1.15 +/-0.691 QC1204391969 LCS Nickel-59 92.8 100 pCi/g 108 (75%-125%) 10/11/19 09:30 Uncertainty +/-6.10 QC1204391967 MB Nickel-59 U 1.07 pCi/g 10/11/19 08:17 Uncertainty +/-1.85 Rad Gas Flow Batch 1921875 QC1204393106 490846005 DUP Strontium-90 U -0.0505 U 0.0293 pCi/g N/A N/A JXC9 10/07/19 15:10 Uncertainty +/-0.0835 +/-0.0985 QC1204393107 LCS Strontium-90 5.36 5.83 pCi/g 109 (75%-125%) 10/07/19 15:10 Uncertainty +/-0.340 QC1204393105 MB Strontium-90 U 0.015 pCi/g 10/07/19 15:10 Uncertainty +/-0.0671 Rad Liquid Scintillation Batch 1921313 QC1204391802 490846014 DUP Iron-55 U -1.7 U -0.904 pCi/g N/A N/A TXJ1 10/11/19 18:19 Uncertainty +/-5.55 +/-5.29 QC1204391803 LCS Iron-55 76.4 71.5 pCi/g 93.5 (75%-125%) 10/11/19 19:37 Uncertainty +/-5.37 QC1204391801 MB Iron-55 U 1.03 pCi/g 10/11/19 17:01 Uncertainty +/-4.39 Page 22 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 490846 Page 5 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 1921355 QC1204391926 490846014 DUP Nickel-63 U 1.70 U -0.61 pCi/g N/A N/A TXJ1 10/11/19 16:28 Uncertainty +/-2.13 +/-2.12 QC1204391927 LCS Nickel-63 96.5 101 pCi/g 104 (75%-125%) 10/11/19 16:44 Uncertainty +/-5.11 QC1204391925 MB Nickel-63 U -0.418 pCi/g 10/11/19 16:11 Uncertainty +/-2.23 Batch 1921541 QC1204392284 490846014 DUP Technetium-99 U -0.45 U -0.161 pCi/g N/A N/A JJ3 10/06/19 08:48 Uncertainty +/-0.886 +/-0.901 QC1204392285 LCS Technetium-99 41.1 36.7 pCi/g 89.3 (75%-125%) 10/06/19 09:20 Uncertainty +/-1.70 QC1204392283 MB Technetium-99 U -0.684 pCi/g 10/06/19 08:15 Uncertainty +/-0.898 Batch 1921574 QC1204392383 490846014 DUP Tritium U 4.06 U 4.45 pCi/g N/A N/A EW3 10/04/19 05:53 Uncertainty +/-4.58 +/-4.62 QC1204392385 LCS Tritium 146 129 pCi/g 88.1 (75%-125%) 10/04/19 07:27 Uncertainty +/-8.79 QC1204392382 MB Tritium U 3.98 pCi/g 10/04/19 03:55 Uncertainty +/-4.49 QC1204392384 490846014 MS Tritium 149 U 4.06 124 pCi/g 83.3 (75%-125%) 10/04/19 06:40 Uncertainty +/-4.58 +/-8.95 Page 23 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 490846 Page 6 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 1921585 QC1204392425 490846014 DUP Carbon-14 U -2.58 U -1.82 pCi/g N/A N/A TXP3 10/09/19 17:34 Uncertainty +/-2.02 +/-2.01 QC1204392427 LCS Carbon-14 142 133 pCi/g 93.5 (75%-125%) 10/09/19 19:10 Uncertainty +/-4.36 QC1204392424 MB Carbon-14 U 0.0484 pCi/g 10/09/19 16:46 Uncertainty +/-2.08 QC1204392426 490846014 MS Carbon-14 146 U -2.58 132 pCi/g 90.2 (75%-125%) 10/09/19 18:23 Uncertainty +/-2.02 +/-4.40 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 See case narrative for an explanation 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 24 of 37 SDG: 490846
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 490846 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 25 of 37 SDG: 490846
Radiochemistry Technical Case Narrative LaCrosseSolutions, LLC SDG #: 490846 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: 1919949 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1919153 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846014 L1-SUB-TDS-CJGS-A01-SB 1204388647 Method Blank (MB) 1204388648 490846014(L1-SUB-TDS-CJGS-A01-SB) Sample Duplicate (DUP) 1204388649 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 The Cm-244 portion of sample 1204388647 (MB) was recounted due to results more negative than the three sigma TPU. The recount is reported. Product: Alphaspec Np, Solid Analytical Method: ASTM C 1475-00 Modified Analytical Procedure: GL-RAD-A-032 REV# 22 Analytical Batch: 1919950 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1919153 Page Laboratories GEL 26 of 37 SDG:u.c 490846 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846014 L1-SUB-TDS-CJGS-A01-SB 1204388650 Method Blank (MB) 1204388651 490846014(L1-SUB-TDS-CJGS-A01-SB) Sample Duplicate (DUP) 1204388652 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: 1919951 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1919153 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846014 L1-SUB-TDS-CJGS-A01-SB 1204388653 Method Blank (MB) 1204388654 490846014(L1-SUB-TDS-CJGS-A01-SB) Sample Duplicate (DUP) 1204388655 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Dry Weight Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1919153 Page Laboratories GEL 27 of 37 SDG:u.c 490846 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846001 L1-SUB-TDS-FJGS-A24-SB 490846002 L1-SUB-TDS-FJGS-A25-SB 490846003 L1-SUB-TDS-FJGS-A12A-SB 490846004 L1-010-107-FJGS-005-SS 490846005 L1-010-107-FJGS-016-SS 490846006 L1-010-101-FJGS-003-SS 490846007 L1-010-102-FJGS-010-SS 490846008 L1-010-103-FJGS-008-SS 490846009 L1-010-104-FJGS-006-SS 490846010 L1-010-105-FJGS-008-SS 490846011 L1-010-106-FJGS-004-SS 490846012 L1-010-106-FJGS-017-SS 490846013 L1-010-106-FJGS-018-SS 490846014 L1-SUB-TDS-CJGS-A01-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: 1919313 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1919153 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846014 L1-SUB-TDS-CJGS-A01-SB 1204386989 Method Blank (MB) 1204386990 490846014(L1-SUB-TDS-CJGS-A01-SB) Sample Duplicate (DUP) 1204386991 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 37 SDG:u.c 490846 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Product: Gamma Ni59, Solid Analytical Method: DOE RESL Ni-1 Analytical Procedure: GL-RAD-A-022 REV# 19 Analytical Batch: 1921366 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1919153 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846014 L1-SUB-TDS-CJGS-A01-SB 1204391967 Method Blank (MB) 1204391968 490846014(L1-SUB-TDS-CJGS-A01-SB) Sample Duplicate (DUP) 1204391969 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: 1921875 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1919153 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846001 L1-SUB-TDS-FJGS-A24-SB 490846002 L1-SUB-TDS-FJGS-A25-SB 490846003 L1-SUB-TDS-FJGS-A12A-SB 490846004 L1-010-107-FJGS-005-SS 490846005 L1-010-107-FJGS-016-SS 490846006 L1-010-101-FJGS-003-SS 490846007 L1-010-102-FJGS-010-SS 490846008 L1-010-103-FJGS-008-SS 490846009 L1-010-104-FJGS-006-SS Page Laboratories GEL 29 of 37 SDG:u.c 490846 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
490846010 L1-010-105-FJGS-008-SS 490846011 L1-010-106-FJGS-004-SS 490846012 L1-010-106-FJGS-017-SS 490846013 L1-010-106-FJGS-018-SS 490846014 L1-SUB-TDS-CJGS-A01-SB 1204393105 Method Blank (MB) 1204393106 490846005(L1-010-107-FJGS-016-SS) Sample Duplicate (DUP) 1204393107 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 Samples 490846006 (L1-010-101-FJGS-003-SS), 490846007 (L1-010-102-FJGS-010-SS), 490846010 (L1-010-105-FJGS-008-SS) and 490846012 (L1-010-106-FJGS-017-SS) were recounted due to results more negative than the three sigma TPU. The second counts are 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: 1919952 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1919153 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846014 L1-SUB-TDS-CJGS-A01-SB 1204388656 Method Blank (MB) 1204388657 490846014(L1-SUB-TDS-CJGS-A01-SB) Sample Duplicate (DUP) 1204388658 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 30 of 37 SDG:u.c 490846 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Product: Liquid Scint Fe55, Solid Analytical Method: DOE RESL Fe-1, Modified Analytical Procedure: GL-RAD-A-040 REV# 13 Analytical Batch: 1921313 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1919153 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846014 L1-SUB-TDS-CJGS-A01-SB 1204391801 Method Blank (MB) 1204391802 490846014(L1-SUB-TDS-CJGS-A01-SB) Sample Duplicate (DUP) 1204391803 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 Samples were recounted due to high MDCs. The recounts are reported. Product: Liquid Scint Ni63, Solid Analytical Method: DOE RESL Ni-1, Modified Analytical Procedure: GL-RAD-A-022 REV# 19 Analytical Batch: 1921355 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1919153 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846014 L1-SUB-TDS-CJGS-A01-SB 1204391925 Method Blank (MB) 1204391926 490846014(L1-SUB-TDS-CJGS-A01-SB) Sample Duplicate (DUP) 1204391927 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Page Laboratories GEL 31 of 37 SDG:u.c 490846 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Liquid Scint Tc99, Solid Analytical Method: DOE EML HASL-300, Tc-02-RC Modified Analytical Procedure: GL-RAD-A-059 REV# 5 Analytical Batch: 1921541 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846014 L1-SUB-TDS-CJGS-A01-SB 1204392283 Method Blank (MB) 1204392284 490846014(L1-SUB-TDS-CJGS-A01-SB) Sample Duplicate (DUP) 1204392285 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# 23 Analytical Batch: 1921574 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846014 L1-SUB-TDS-CJGS-A01-SB 1204392382 Method Blank (MB) 1204392383 490846014(L1-SUB-TDS-CJGS-A01-SB) Sample Duplicate (DUP) 1204392384 490846014(L1-SUB-TDS-CJGS-A01-SB) Matrix Spike (MS) 1204392385 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 32 of 37 SDG:u.c 490846 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Product: Liquid Scint C14, Solid Analytical Method: EPA EERF C-01 Modified Analytical Procedure: GL-RAD-A-003 REV# 16 Analytical Batch: 1921585 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 490846014 L1-SUB-TDS-CJGS-A01-SB 1204392424 Method Blank (MB) 1204392425 490846014(L1-SUB-TDS-CJGS-A01-SB) Sample Duplicate (DUP) 1204392426 490846014(L1-SUB-TDS-CJGS-A01-SB) Matrix Spike (MS) 1204392427 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on an "as received" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Certification Statement Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless otherwise noted in the analytical case narrative. Page Laboratories GEL 33 of 37 SDG:u.c 490846 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Page 34 of 37 SDG: 490846 Pa8C: ,, ,_ Y 9oli'L/ \a Project~ LACIJwr, GEL Quote~; C'OC Numl>or'lJ PO NtrrriOOr 672583 Sile GEL Work Order Nt1mber.- m9., I ~£~~£l~ ~yl5Pec ~l~M~~ ~ Chain of Custodv and AnaMical Reouest GEL L1bors1orie,. LLC 20~0 Sav,1gc Rood Charleston, SC 29407 Phone: (8H) 556-RI 71 GEL Projec/ M11nuger: fID<: (843) 766-1178 Client Name: LaCro,sc Solut,ons Phone# 600-689-4259 Sample Analysis Req11e.sted (S) (Fill in the number of containers for each test) Project/Sile Nome: LACIJWR-Genoa WI Fax# Shguld thi,
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Page 35 of 37 SDG: 490846 i---1 9 o 2-y lo
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Cij =I"°"- GEL Labomto,ie>, LLC Paf,!C:. Project# L\CflWR '- Sile !I I Laboratories LLC 2040 Savage Roid GEL QtJDle ~: f,heme;lry I ll!11llocl100lt,;I')' I 'l;,ilio\,""1$llay IS,,oclalh' /lrnlr/t<<:s Charlcsion. S( 29407 COC Number'", Chain of Custodv and Analvtical Reauest Phone: (843) 556-8171 PO Number: 67258., GEi, Work Order Number: GEL Project Manager: Fax 1843) 766-ll 78 Client Name. L, Cro&se Solulions Phone~ 608.(,89-4259 Sample Anal~is Rcquestc<I <*J (Fil! in the number of containers for each test) ProJCCIISitc Name: LACBWR-Gcnoa WI Fax11 Shou!.d this <- Prc>ervalivc Type (61
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°C l l Ch~n ofCo;t<<l) >',mbe,- Clka, D<ccm"n<<I l) QC Codes. N- Kon,,,1 Soo,pk. TJI - fop Nonie fO - F"ld Dual"""- ED
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FL g Flarnmabte/11,,njtable LW=Listed Waste ' OT= Other _I Unknown J,em../"'Kan1j,i1_Jum(/fJ'!g<J.*,;,voj RCRA Metals CO= Corrosiee (F.K,I' t>nd U~ll.1*1ed n~mes.) (i.e.. Hi)llr*/m,* pH. a.,be.,ws, heryl/;um, immms, Mher dlspmiti-<flnCl/ms. (,,"e,: Orlgln,ef As~ Arscmc 111:= Mercury RE-' Reaciive w.mo ,1,det~J: mis~. heal//, /rmards, e1i:.) sOnlplf_M, 1ypc ,,J.<ifle collecfod/mJ1J, odd Ba= Barium S,,,. Selenium Dosoriplwn: rnat~ice.i. ~Id .. Cd'-Cadmmm Ag=sn,..,, Cr=C-h,ominm MR~ Misc. RCRA mc!als ITSCA Re~ted PCB = Po lormatei:I I rb n Lend bipheoyls
SAMPLE RECEIPT & REVIEW FORNI SDGl,\JVCOC!W<*rl< On!or. Carrie r anil Tl'ncking Numb er - FcdE~ hprc11;
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g Samples received wi1Jilnholding 1ime? I ~: w Do !iqoid VO/\ 1*i:ilsco,Uai,i~cid p,,:.!C~'alio<tl y..,__ ArchqoidVOA1*in!sfrecofhc:idspa,:,1Ycs_ No_ Son,p~ ID~ and ,on.,"1,<> oJJ\ue<I*
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Co,nmonts (Use ConJin,,alion f Oml ir needed l' p~_j__or....L Gl*CHL*SR,001 Rev6 Page 36 of 37 SDG: 490846
List of current GEL Certifications as of 15 October 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 Massachusetts PFAS Approv Letter 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 2019165 Pennsylvania NELAP 6800485 Puerto Rico SC00012 S. Carolina Radiochem 10120002 Sanitation Districts of L 9255651 South Carolina Chemistry 10120001 Tennessee TN 02934 Texas NELAP T1047042351915 Utah NELAP SC00012201928 Vermont VT87156 Virginia NELAP 460202 Washington C780 Page 37 of 37 SDG: 490846
tcl=l* ILaboratories LLc O = ** PO Box ~07 12 Charteston SC 29417 8 member of The GEL Group INC 2040 Savage Road Charfesron SC 29407 P 843_556.8171 F 843.766.1178 gel co m November 14, 2019 Mr. Jason Q. Spaide LaCrosseSolutions S4601 State Hwy 35 Genoa, Wisconsin 54632 Re: LACBWR Site Restoration Project Work Order: 493624
Dear Mr. Spaide:
GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for the sample(s) we received on October 21, 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 72 SDG: 493624
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: 493624 GEL Work Order: 493624 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 H Analytical holding time was exceeded U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.
h Preparation or preservation holding time was exceeded 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 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RAGS-002-SS Project: ENRG07001 Sample ID: 493624001 Client ID: ENRG070 Matrix: Soil Collect Date: 08-SEP-16 11:05 Receive Date: 21-OCT-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 HUh 0.0084 +/-0.0467 0.0895 0.400 pCi/g HAKB 11/06/19 0953 1929693 1 Americium-243 HUh 0.0346 +/-0.0974 0.104 0.400 pCi/g Curium-243/244 HUh -0.00429 +/-0.037 0.0857 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 HUh 0.00125 +/-0.00299 0.00529 0.010 pCi/g HAKB 11/11/19 1231 1929694 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 HUh 0.00487 +/-0.0271 0.0519 0.400 pCi/g HAKB 11/06/19 0922 1929695 3 Plutonium-239/240 HUh -0.00402 +/-0.0278 0.0676 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 HUh -1.25 +/-2.38 4.12 5.00 pCi/g HAKB 11/09/19 0252 1929696 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 HUh -0.18 +/-1.68 3.01 5.00 pCi/g TXJ1 10/30/19 0619 1931847 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 Hh 0.113 +/-0.0594 0.0518 1.00 pCi/g MXR1 10/30/19 0857 1929624 6 Cobalt-60 HUh 0.036 +/-0.0349 0.0881 pCi/g Europium-152 HUh -0.00616 +/-0.0669 0.115 pCi/g Europium-154 HUh -0.0128 +/-0.0717 0.149 pCi/g Europium-155 HUh 0.0587 +/-0.0622 0.134 pCi/g Niobium-94 HUh 0.0376 +/-0.0275 0.0407 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 HUh 0.0238 +/-0.0658 0.120 0.400 pCi/g JXC9 11/06/19 1419 1933651 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium HU 1.65 +/-5.62 9.75 10.0 pCi/g EW3 10/28/19 2327 1929721 8 Liquid Scint C14, Solid "As Received" Carbon-14 HU 1.92 +/-1.76 2.94 5.00 pCi/g TXP3 11/08/19 1739 1934551 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 HU -0.00734 +/-0.483 0.861 2.00 pCi/g JJ3 11/05/19 2229 1929739 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 HUh -1.57 +/-12.1 18.7 10.0 pCi/g RP1 11/01/19 0908 1931683 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 3 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RAGS-002-SS Project: ENRG07001 Sample ID: 493624001 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 HUh -0.424 +/-1.17 2.08 5.00 pCi/g RP1 10/30/19 1251 1931689 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 10/22/19 1024 1929602 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, 35 (15%-125%) Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 18.2 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 91.7 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 79.9 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 79.9 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 98.8 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 92.8 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 92.1 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 20.5 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 97.4 (25%-125%) Notes: Page 4 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RAGS-002-SS Project: ENRG07001 Sample ID: 493624001 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 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RAGS-004-SS Project: ENRG07001 Sample ID: 493624002 Client ID: ENRG070 Matrix: Soil Collect Date: 13-SEP-16 11:00 Receive Date: 21-OCT-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 HUh -0.00947 +/-0.0286 0.0803 0.400 pCi/g HAKB 11/06/19 0953 1929693 1 Americium-243 HUh 0.049 +/-0.0706 0.0851 0.400 pCi/g Curium-243/244 HUh -0.0105 +/-0.0316 0.0888 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 HUh 0.00322 +/-0.00457 0.00708 0.010 pCi/g HAKB 11/11/19 1407 1929694 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 HUh 0.0216 +/-0.043 0.0698 0.400 pCi/g HAKB 11/06/19 0922 1929695 3 Plutonium-239/240 HUh 0.00537 +/-0.0299 0.0572 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 HUh -0.71 +/-2.66 4.58 5.00 pCi/g HAKB 11/09/19 0453 1929696 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 HUh 0.790 +/-1.61 1.85 5.00 pCi/g TXJ1 10/30/19 0732 1931847 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 HUh -0.00991 +/-0.0244 0.0436 1.00 pCi/g MXR1 10/30/19 2007 1929624 6 Cobalt-60 HUh -0.0119 +/-0.0357 0.0682 pCi/g Europium-152 HUh 0.0185 +/-0.085 0.158 pCi/g Europium-154 HUh -0.0397 +/-0.0855 0.151 pCi/g Europium-155 HUh 0.0322 +/-0.121 0.245 pCi/g Niobium-94 HUh 0.00172 +/-0.0225 0.0424 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 HUh -0.0186 +/-0.0688 0.136 0.400 pCi/g JXC9 11/07/19 0654 1933651 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium HU 6.63 +/-5.88 9.76 10.0 pCi/g EW3 10/29/19 0019 1929721 8 Liquid Scint C14, Solid "As Received" Carbon-14 HU 0.791 +/-1.54 2.62 5.00 pCi/g TXP3 11/10/19 1745 1934551 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 HU 0.117 +/-0.461 0.809 2.00 pCi/g JJ3 11/05/19 2312 1929739 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 HUh -8.13 +/-10.8 16.8 10.0 pCi/g RP1 11/01/19 1112 1931683 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 6 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RAGS-004-SS Project: ENRG07001 Sample ID: 493624002 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 HUh -0.325 +/-1.16 2.04 5.00 pCi/g RP1 10/30/19 1308 1931689 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 10/22/19 1024 1929602 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, 45.5 (15%-125%) Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 29.7 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 77.2 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 72.9 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 72.9 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 106 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 75.1 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 95.4 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 23.8 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 101 (25%-125%) Notes: Page 7 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RAGS-004-SS Project: ENRG07001 Sample ID: 493624002 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 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RBGS-004-SS Project: ENRG07001 Sample ID: 493624003 Client ID: ENRG070 Matrix: Soil Collect Date: 14-OCT-16 09:02 Receive Date: 21-OCT-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 HUh 0.00515 +/-0.0286 0.0549 0.400 pCi/g HAKB 11/11/19 2243 1929693 1 Americium-243 HUh 0.0273 +/-0.0467 0.0409 0.400 pCi/g Curium-243/244 HUh 0.0083 +/-0.0311 0.0524 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 HUh 0.00372 +/-0.00542 0.00881 0.010 pCi/g HAKB 11/11/19 1407 1929694 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 HUh 0.00351 +/-0.0367 0.0765 0.400 pCi/g HAKB 11/06/19 0922 1929695 3 Plutonium-239/240 HUh 0.0186 +/-0.0427 0.0677 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 HUh -2.96 +/-3.25 5.69 5.00 pCi/g HAKB 11/09/19 0654 1929696 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 HUh -1.19 +/-1.81 3.10 5.00 pCi/g TXJ1 10/30/19 0732 1931847 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 Hh 0.165 +/-0.0676 0.0583 1.00 pCi/g MXR1 10/30/19 2007 1929624 6 Cobalt-60 HUh 0.00774 +/-0.0495 0.104 pCi/g Europium-152 HUh 0.00852 +/-0.0674 0.143 pCi/g Europium-154 HUh -0.0312 +/-0.128 0.242 pCi/g Europium-155 HUh 0.0809 +/-0.0975 0.216 pCi/g Niobium-94 HUh 0.0112 +/-0.0238 0.0472 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 HUh -0.0302 +/-0.0603 0.125 0.400 pCi/g JXC9 11/06/19 1419 1933651 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium HU 2.06 +/-5.54 9.58 10.0 pCi/g EW3 10/29/19 0111 1929721 8 Liquid Scint C14, Solid "As Received" Carbon-14 HU 1.88 +/-1.91 3.20 5.00 pCi/g TXP3 11/08/19 1914 1934551 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 HU 0.210 +/-0.757 1.32 2.00 pCi/g JJ3 11/05/19 2354 1929739 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 HUh -3.06 +/-10.9 16.7 10.0 pCi/g RP1 11/01/19 1316 1931683 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 9 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RBGS-004-SS Project: ENRG07001 Sample ID: 493624003 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 HUh -0.265 +/-1.50 2.64 5.00 pCi/g RP1 10/30/19 1324 1931689 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 10/22/19 1024 1929602 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, 63.2 (15%-125%) Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 38.5 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 67 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 58.2 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 58.2 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 84.1 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 90.6 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 83.5 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 24.3 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 77.5 (25%-125%) Notes: Page 10 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RBGS-004-SS Project: ENRG07001 Sample ID: 493624003 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 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RBGS-007-SS Project: ENRG07001 Sample ID: 493624004 Client ID: ENRG070 Matrix: Soil Collect Date: 24-OCT-16 09:05 Receive Date: 21-OCT-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 HUh 0.0113 +/-0.0385 0.0714 0.400 pCi/g HAKB 11/06/19 0953 1929693 1 Americium-243 HUh 0.0127 +/-0.0397 0.0744 0.400 pCi/g Curium-243/244 HUh -0.00764 +/-0.0449 0.107 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 HUh 0.00296 +/-0.00441 0.00677 0.010 pCi/g HAKB 11/11/19 1407 1929694 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 HUh 0.0131 +/-0.0504 0.0977 0.400 pCi/g HAKB 11/07/19 0836 1929695 3 Plutonium-239/240 HUh -0.0113 +/-0.0263 0.0779 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 HUh -3.33 +/-2.87 5.04 5.00 pCi/g HAKB 11/09/19 0856 1929696 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 HUh 0.384 +/-1.43 2.69 5.00 pCi/g TXJ1 10/30/19 0901 1931847 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 Hh 0.174 +/-0.128 0.107 1.00 pCi/g MXR1 10/30/19 2008 1929624 6 Cobalt-60 HUh 0.010 +/-0.0701 0.154 pCi/g Europium-152 HUh -0.0434 +/-0.125 0.241 pCi/g Europium-154 HUh 0.0975 +/-0.198 0.446 pCi/g Europium-155 HUh 0.184 +/-0.157 0.316 pCi/g Niobium-94 HUh -0.0248 +/-0.0531 0.0943 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 HUh -0.0921 +/-0.0818 0.172 0.400 pCi/g JXC9 11/06/19 1419 1933651 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium HU -0.242 +/-5.47 9.57 10.0 pCi/g EW3 10/30/19 0546 1929721 8 Liquid Scint C14, Solid "As Received" Carbon-14 HU 1.60 +/-1.86 3.13 5.00 pCi/g TXP3 11/08/19 2000 1934551 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 HU 0.0756 +/-0.755 1.33 2.00 pCi/g JJ3 11/06/19 0037 1929739 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 HUh -2.34 +/-9.51 14.1 10.0 pCi/g RP1 11/01/19 1519 1931683 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 12 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RBGS-007-SS Project: ENRG07001 Sample ID: 493624004 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 HUh -0.239 +/-1.48 2.61 5.00 pCi/g RP1 10/30/19 1340 1931689 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 10/22/19 1024 1929602 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, 57.8 (15%-125%) Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 55.4 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 61.1 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 67.4 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 67.4 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 77.8 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 88.4 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 79.7 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 33.8 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 75.7 (25%-125%) Notes: Page 13 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-RBGS-007-SS Project: ENRG07001 Sample ID: 493624004 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 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L4-OFF-SOL-IJGS-A01-SS NE Project: ENRG07001 Sample ID: 493624005 Client ID: ENRG070 Matrix: Soil Collect Date: 04-MAY-17 08:25 Receive Date: 21-OCT-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 HUh 0.00418 +/-0.0437 0.0913 0.400 pCi/g HAKB 11/06/19 0953 1929693 1 Americium-243 HUh 0.0805 +/-0.113 0.180 0.400 pCi/g Curium-243/244 HUh 0.0123 +/-0.046 0.0774 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 HUh 0.0027 +/-0.0048 0.00826 0.010 pCi/g HAKB 11/11/19 1407 1929694 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 HUh 0.00535 +/-0.0297 0.057 0.400 pCi/g HAKB 11/07/19 0919 1929695 3 Plutonium-239/240 HUh 0.00565 +/-0.0365 0.0746 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 HUh -1.69 +/-2.64 4.58 5.00 pCi/g HAKB 11/09/19 1057 1929696 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 HUh -0.319 +/-1.80 3.04 5.00 pCi/g TXJ1 10/30/19 0902 1931847 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 HUh -0.0202 +/-0.0335 0.062 1.00 pCi/g MXR1 10/31/19 1914 1929624 6 Cobalt-60 HUh -0.000764 +/-0.0486 0.105 pCi/g Europium-152 HUh -0.0349 +/-0.0944 0.189 pCi/g Europium-154 HUh 0.0419 +/-0.107 0.261 pCi/g Europium-155 HUh 0.0633 +/-0.0849 0.189 pCi/g Niobium-94 HUh -0.0074 +/-0.0313 0.0606 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 HUh -0.0141 +/-0.058 0.117 0.400 pCi/g JXC9 11/06/19 1419 1933651 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium HU 3.03 +/-5.68 9.73 10.0 pCi/g EW3 10/29/19 0406 1929721 8 Liquid Scint C14, Solid "As Received" Carbon-14 HU 2.67 +/-1.65 2.70 5.00 pCi/g TXP3 11/08/19 2047 1934551 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 HU 0.468 +/-0.587 0.992 2.00 pCi/g JJ3 11/06/19 0235 1929739 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 HUh -2.65 +/-8.40 12.7 10.0 pCi/g RP1 11/01/19 1723 1931683 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 15 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L4-OFF-SOL-IJGS-A01-SS NE Project: ENRG07001 Sample ID: 493624005 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 HUh 0.190 +/-1.16 2.01 5.00 pCi/g RP1 10/30/19 1357 1931689 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 10/22/19 1024 1929602 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, 40 (15%-125%) Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 32.4 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 89.7 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 71.9 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 71.9 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 98 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 88.4 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 95.2 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 28.8 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 101 (25%-125%) Notes: Page 16 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L4-OFF-SOL-IJGS-A01-SS NE Project: ENRG07001 Sample ID: 493624005 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 17 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L4-OFF-SOL-IJGS-A03-SS SW Project: ENRG07001 Sample ID: 493624006 Client ID: ENRG070 Matrix: Soil Collect Date: 04-MAY-17 09:30 Receive Date: 21-OCT-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 HUh -0.00883 +/-0.0399 0.101 0.400 pCi/g HAKB 11/06/19 0953 1929693 1 Americium-243 HUh 0.00791 +/-0.0933 0.197 0.400 pCi/g Curium-243/244 HUh -0.00337 +/-0.0291 0.0673 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 HUh 0.00226 +/-0.004 0.00662 0.010 pCi/g HAKB 11/11/19 1407 1929694 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 HUh -0.0135 +/-0.0384 0.0935 0.400 pCi/g HAKB 11/06/19 0953 1929695 3 Plutonium-239/240 HUh 0.00711 +/-0.0355 0.071 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 HUh -1.48 +/-2.38 4.14 5.00 pCi/g HAKB 11/09/19 1258 1929696 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 HUh 0.850 +/-0.613 1.77 5.00 pCi/g TXJ1 10/30/19 0902 1931847 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 HUh -0.0164 +/-0.0249 0.0423 1.00 pCi/g MXR1 11/01/19 0622 1929624 6 Cobalt-60 HUh 0.00904 +/-0.0233 0.0583 pCi/g Europium-152 HUh 0.123 +/-0.0925 0.150 pCi/g Europium-154 HUh -0.097 +/-0.081 0.110 pCi/g Europium-155 HUh 0.0555 +/-0.0883 0.181 pCi/g Niobium-94 HUh 0.0103 +/-0.0227 0.049 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 HUh -0.0582 +/-0.055 0.122 0.400 pCi/g JXC9 11/06/19 1419 1933651 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium HU 3.85 +/-5.29 8.96 10.0 pCi/g EW3 10/29/19 0458 1929721 8 Liquid Scint C14, Solid "As Received" Carbon-14 HU 1.65 +/-1.66 2.79 5.00 pCi/g TXP3 11/10/19 1832 1934551 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 HU -0.11 +/-1.09 1.95 2.00 pCi/g JJ3 11/06/19 0317 1929739 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 HUh -1.18 +/-6.18 8.97 10.0 pCi/g RP1 11/01/19 1927 1931683 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 18 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L4-OFF-SOL-IJGS-A03-SS SW Project: ENRG07001 Sample ID: 493624006 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 HUh -0.546 +/-1.17 2.08 5.00 pCi/g RP1 10/30/19 1413 1931689 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 10/22/19 1024 1929602 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, 42.8 (15%-125%) Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 27.2 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 69.5 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 80 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 80 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 98.4 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 95 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 63.8 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 43.4 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 96.5 (25%-125%) Notes: Page 19 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L4-OFF-SOL-IJGS-A03-SS SW Project: ENRG07001 Sample ID: 493624006 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 20 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: S3-012-109B-FJGS-062-SM Project: ENRG07001 Sample ID: 493624007 Client ID: ENRG070 Matrix: Soil Collect Date: 22-AUG-19 10:05 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0139 +/-0.0617 0.113 0.400 pCi/g JXC9 11/06/19 1419 1933651 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 110 (25%-125%) Notes: 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 21 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: S3-012-109B-FJGS-063-SM Project: ENRG07001 Sample ID: 493624008 Client ID: ENRG070 Matrix: Soil Collect Date: 22-AUG-19 10:14 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.00923 +/-0.0636 0.121 0.400 pCi/g JXC9 11/06/19 1419 1933651 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 104 (25%-125%) Notes: 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 22 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: S3-012-109B-FJGS-064-SM Project: ENRG07001 Sample ID: 493624009 Client ID: ENRG070 Matrix: Soil Collect Date: 22-AUG-19 13:12 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0355 +/-0.0445 0.0974 0.400 pCi/g JXC9 11/06/19 1419 1933651 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 104 (25%-125%) Notes: 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 23 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-011-101-FSGS-013-SS Project: ENRG07001 Sample ID: 493624010 Client ID: ENRG070 Matrix: Soil Collect Date: 20-SEP-19 10:43 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0706 +/-0.085 0.144 0.400 pCi/g JXC9 11/06/19 1419 1933651 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 97.2 (25%-125%) Notes: 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 24 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-011-104-FSGS-001-SS Project: ENRG07001 Sample ID: 493624011 Client ID: ENRG070 Matrix: Soil Collect Date: 09-SEP-19 14:08 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0354 +/-0.0446 0.096 0.400 pCi/g JXC9 11/06/19 1419 1933651 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 113 (25%-125%) Notes: 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 25 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-011-104-FSGS-010-SS Project: ENRG07001 Sample ID: 493624012 Client ID: ENRG070 Matrix: Soil Collect Date: 09-SEP-19 14:46 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0194 +/-0.0367 0.0792 0.400 pCi/g JXC9 11/07/19 0654 1933651 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 97.2 (25%-125%) Notes: 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 26 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-FSGS-004-SS Project: ENRG07001 Sample ID: 493624013 Client ID: ENRG070 Matrix: Soil Collect Date: 05-SEP-19 08:58 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.112 +/-0.084 0.133 0.400 pCi/g JXC9 11/06/19 1419 1933651 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 92.8 (25%-125%) Notes: 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 27 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-109-FSGS-005-SS Project: ENRG07001 Sample ID: 493624014 Client ID: ENRG070 Matrix: Soil Collect Date: 24-SEP-19 08:05 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0801 +/-0.0672 0.107 0.400 pCi/g JXC9 11/06/19 1419 1933651 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 88.4 (25%-125%) Notes: 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 28 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-109-FSGS-006-SS Project: ENRG07001 Sample ID: 493624015 Client ID: ENRG070 Matrix: Soil Collect Date: 24-SEP-19 10:36 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0454 +/-0.038 0.0913 0.400 pCi/g JXC9 11/06/19 1419 1933651 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 104 (25%-125%) Notes: 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 29 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-109-FSGS-011-SS Project: ENRG07001 Sample ID: 493624016 Client ID: ENRG070 Matrix: Soil Collect Date: 23-SEP-19 14:09 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0482 +/-0.0493 0.111 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 92.8 (25%-125%) Notes: 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 30 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-107-FSGS-008-SS Project: ENRG07001 Sample ID: 493624017 Client ID: ENRG070 Matrix: Soil Collect Date: 08-AUG-19 15:00 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0295 +/-0.0766 0.151 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 84 (25%-125%) Notes: 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 31 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-101-FSGS-015-SS Project: ENRG07001 Sample ID: 493624018 Client ID: ENRG070 Matrix: Soil Collect Date: 08-AUG-19 15:12 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0436 +/-0.0544 0.118 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 88.4 (25%-125%) Notes: 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 32 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-102-FSGS-007-SS Project: ENRG07001 Sample ID: 493624019 Client ID: ENRG070 Matrix: Soil Collect Date: 14-AUG-19 15:18 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0969 +/-0.0724 0.155 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 88.4 (25%-125%) Notes: 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 33 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-103-FSGS-005-SS Project: ENRG07001 Sample ID: 493624020 Client ID: ENRG070 Matrix: Soil Collect Date: 14-AUG-19 10:13 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0229 +/-0.0522 0.109 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1024 1929602 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 90.6 (25%-125%) Notes: 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 34 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-104-FSGS-016-SS Project: ENRG07001 Sample ID: 493624021 Client ID: ENRG070 Matrix: Soil Collect Date: 23-AUG-19 09:57 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0967 +/-0.087 0.141 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1034 1929603 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 79.6 (25%-125%) Notes: 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 35 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-010-105-FSGS-007-SS Project: ENRG07001 Sample ID: 493624022 Client ID: ENRG070 Matrix: Soil Collect Date: 23-AUG-19 13:29 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0341 +/-0.0859 0.154 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1034 1929603 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 79.6 (25%-125%) Notes: 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 36 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-011-101-FSGS-005-SS Project: ENRG07001 Sample ID: 493624023 Client ID: ENRG070 Matrix: Soil Collect Date: 20-SEP-19 14:01 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0135 +/-0.0736 0.141 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1034 1929603 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 88.4 (25%-125%) Notes: 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 37 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
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Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-011-104-FSGS-011-SS Project: ENRG07001 Sample ID: 493624024 Client ID: ENRG070 Matrix: Soil Collect Date: 09-SEP-19 14:52 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.058 +/-0.0508 0.117 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1034 1929603 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 88.4 (25%-125%) Notes: 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 38 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
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Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-101-FSGS-005-SS Project: ENRG07001 Sample ID: 493624025 Client ID: ENRG070 Matrix: Soil Collect Date: 05-SEP-19 13:00 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0836 +/-0.0864 0.144 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1034 1929603 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 102 (25%-125%) Notes: 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 39 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-109-FSGS-014-SS Project: ENRG07001 Sample ID: 493624026 Client ID: ENRG070 Matrix: Soil Collect Date: 23-SEP-19 14:21 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0202 +/-0.0604 0.110 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1034 1929603 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 97.2 (25%-125%) Notes: 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 40 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
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Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L3-012-109-FSGS-017-SS Project: ENRG07001 Sample ID: 493624027 Client ID: ENRG070 Matrix: Soil Collect Date: 24-SEP-19 13:52 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0116 +/-0.0446 0.0829 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1034 1929603 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 115 (25%-125%) Notes: 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 41 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
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Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-PAD-GR5-AJGS-006-SS Project: ENRG07001 Sample ID: 493624028 Client ID: ENRG070 Matrix: Soil Collect Date: 12-JUL-19 12:22 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0456 +/-0.0691 0.119 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1034 1929603 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 104 (25%-125%) Notes: 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 42 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: November 14, 2019 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L1-PAD-GR10-AJGS-007-SS Project: ENRG07001 Sample ID: 493624029 Client ID: ENRG070 Matrix: Soil Collect Date: 13-JUL-19 13:48 Receive Date: 21-OCT-19 Collector: Client Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.0349 +/-0.0546 0.0954 0.400 pCi/g JXC9 11/06/19 1526 1933654 1 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXB7 10/22/19 1034 1929603 The following Analytical Methods were performed: Method Description Analyst Comments 1 EPA 905.0 Modified/DOE RP501 Rev. 1 Modified Surrogate/Tracer Recovery Test Result Nominal Recovery% Acceptable Limits Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 97.2 (25%-125%) Notes: 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 43 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Report Date: November 14, 2019 LaCrosseSolutions Page 1 of 7 S4601 State Hwy 35 Genoa, Wisconsin
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Mr. Jason Q. Spaide Workorder: 493624 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 1929693 QC1204411092 493624001 DUP Americium-241 HUh 0.0084 HU 0.0166 pCi/g N/A N/A HAKB 11/06/19 09:53 Uncertainty +/-0.0467 +/-0.0457 Americium-243 HUh 0.0346 HU -0.012 pCi/g N/A N/A Uncertainty +/-0.0974 +/-0.0532 Curium-243/244 HUh -0.00429 HU -0.0069 pCi/g N/A N/A Uncertainty +/-0.037 +/-0.0305 QC1204411093 LCS Americium-241 1.92 1.99 pCi/g 104 (75%-125%) 11/07/19 09:18 Uncertainty +/-0.348 Americium-243 U 0.00469 pCi/g (75%-125%) Uncertainty +/-0.0491 Curium-243/244 2.26 2.33 pCi/g 103 (75%-125%) Uncertainty +/-0.373 QC1204411091 MB Americium-241 U 0.014 pCi/g 11/06/19 09:53 Uncertainty +/-0.0279 Americium-243 U 0.0163 pCi/g Uncertainty +/-0.0371 Curium-243/244 U 0.00352 pCi/g Uncertainty +/-0.0196 Batch 1929694 QC1204411095 493624003 DUP Neptunium-237 HUh 0.00372 HU 0.00341 pCi/g N/A N/A HAKB 11/11/19 14:07 Uncertainty +/-0.00542 +/-0.00442 QC1204411096 LCS Neptunium-237 0.869 1.01 pCi/g 116 (75%-125%) 11/11/19 14:07 Uncertainty +/-0.0485 QC1204411094 MB Neptunium-237 U -0.000288 pCi/g 11/11/19 14:07 Uncertainty +/-0.00229 Page 44 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 493624 Page 2 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 1929695 QC1204411098 493624001 DUP Plutonium-238 HUh 0.00487 HU 0.0052 pCi/g N/A N/A HAKB 11/06/19 09:53 Uncertainty +/-0.0271 +/-0.0366 Plutonium-239/240 HUh -0.00402 HU -0.00169 pCi/g N/A N/A Uncertainty +/-0.0278 +/-0.0254 QC1204411099 LCS Plutonium-238 U -0.00294 pCi/g 11/06/19 09:53 Uncertainty +/-0.0203 Plutonium-239/240 1.96 2.06 pCi/g 105 (75%-125%) Uncertainty +/-0.231 QC1204411097 MB Plutonium-238 U 0.00862 pCi/g 11/06/19 09:53 Uncertainty +/-0.0295 Plutonium-239/240 U 0.00663 pCi/g Uncertainty +/-0.0297 Batch 1929696 QC1204411101 493624001 DUP Plutonium-241 HUh -1.25 HU -2.36 pCi/g N/A N/A HAKB 11/09/19 17:00 Uncertainty +/-2.38 +/-2.42 QC1204411102 LCS Plutonium-241 162 155 pCi/g 95.5 (75%-125%) 11/09/19 19:02 Uncertainty +/-4.78 QC1204411100 MB Plutonium-241 U -0.546 pCi/g 11/09/19 14:59 Uncertainty +/-1.98 Rad Gamma Spec Batch 1929624 QC1204410975 493624001 DUP Cesium-137 Hh 0.113 H 0.0865 pCi/g 26.4 (0% - 100%) MXR1 11/01/19 06:24 Uncertainty +/-0.0594 +/-0.0561 Cobalt-60 HUh 0.036 HU 0.0428 pCi/g N/A N/A Uncertainty +/-0.0349 +/-0.0446 Europium-152 HUh -0.00616 HU 0.070 pCi/g N/A N/A Uncertainty +/-0.0669 +/-0.0644 Page 45 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 493624 Page 3 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 1929624 Europium-154 HUh -0.0128 HU -0.0196 pCi/g N/A N/A MXR1 11/01/19 06:24 Uncertainty +/-0.0717 +/-0.109 Europium-155 HUh 0.0587 HU 0.0597 pCi/g N/A N/A Uncertainty +/-0.0622 +/-0.088 Niobium-94 HUh 0.0376 HU -0.0216 pCi/g N/A N/A Uncertainty +/-0.0275 +/-0.0246 QC1204410976 LCS Americium-241 487 512 pCi/g 105 (75%-125%) 11/01/19 06:24 Uncertainty +/-6.27 Cesium-137 167 166 pCi/g 99.4 (75%-125%) Uncertainty +/-3.92 Cobalt-60 107 106 pCi/g 98.5 (75%-125%) Uncertainty +/-3.73 Europium-152 U -1.13 pCi/g Uncertainty +/-1.44 Europium-154 U -0.069 pCi/g Uncertainty +/-1.07 Europium-155 U -1.32 pCi/g Uncertainty +/-1.03 Niobium-94 U -0.276 pCi/g Uncertainty +/-0.508 QC1204410974 MB Cesium-137 U 0.00323 pCi/g 11/01/19 06:23 Uncertainty +/-0.0103 Cobalt-60 U 0.0164 pCi/g Uncertainty +/-0.0236 Europium-152 U 0.0135 pCi/g Uncertainty +/-0.0399 Europium-154 U 0.0106 pCi/g Uncertainty +/-0.0612 Europium-155 U -0.00293 pCi/g Uncertainty +/-0.0231 Page 46 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 493624 Page 4 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 1929624 Niobium-94 U 0.00978 pCi/g MXR1 11/01/19 06:23 Uncertainty +/-0.020 Batch 1931847 QC1204415727 493624001 DUP Nickel-59 HUh -0.18 HU -0.803 pCi/g N/A N/A TXJ1 10/30/19 10:43 Uncertainty +/-1.68 +/-1.60 QC1204415728 LCS Nickel-59 90.3 73.2 pCi/g 81.1 (75%-125%) 10/30/19 10:44 Uncertainty +/-6.52 QC1204415726 MB Nickel-59 U -0.45 pCi/g 10/30/19 10:43 Uncertainty +/-1.04 Rad Gas Flow Batch 1933651 QC1204420255 493624005 DUP Strontium-90 HUh -0.0141 HU -0.134 pCi/g N/A N/A JXC9 11/06/19 14:18 Uncertainty +/-0.058 +/-0.105 QC1204420256 LCS Strontium-90 5.40 4.94 pCi/g 91.4 (75%-125%) 11/06/19 14:20 Uncertainty +/-0.313 QC1204420254 MB Strontium-90 U -0.00246 pCi/g 11/06/19 14:18 Uncertainty +/-0.0478 Batch 1933654 QC1204420263 493624025 DUP Strontium-90 U 0.0836 U 0.0226 pCi/g N/A N/A JXC9 11/06/19 15:26 Uncertainty +/-0.0864 +/-0.0608 QC1204420264 LCS Strontium-90 5.51 6.75 pCi/g 122 (75%-125%) 11/07/19 06:45 Uncertainty +/-0.356 QC1204420262 MB Strontium-90 U -0.02 pCi/g 11/06/19 15:26 Uncertainty +/-0.0423 Page 47 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 493624 Page 5 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 1929721 QC1204411179 493624001 DUP Tritium HU 1.65 HU -3.61 pCi/g N/A N/A EW3 10/30/19 06:58 Uncertainty +/-5.62 +/-5.09 QC1204411181 LCS Tritium 142 152 pCi/g 107 (75%-125%) 10/29/19 07:49 Uncertainty +/-17.1 QC1204411178 MB Tritium U 0.00583 pCi/g 10/29/19 05:50 Uncertainty +/-4.35 QC1204411180 493624001 MS Tritium 171 HU 1.65 H 138 pCi/g 80.3 (75%-125%) 10/29/19 07:33 Uncertainty +/-5.62 +/-17.9 Batch 1929739 QC1204411223 493624001 DUP Technetium-99 HU -0.00734 HU 0.523 pCi/g N/A N/A JJ3 11/06/19 04:42 Uncertainty +/-0.483 +/-0.575 QC1204411224 LCS Technetium-99 38.8 37.5 pCi/g 96.7 (75%-125%) 11/06/19 05:25 Uncertainty +/-2.62 QC1204411222 MB Technetium-99 U 0.488 pCi/g 11/06/19 04:00 Uncertainty +/-0.492 Batch 1931683 QC1204415380 493624001 DUP Iron-55 HUh -1.57 HU -9.54 pCi/g N/A N/A RP1 11/01/19 21:31 Uncertainty +/-12.1 +/-8.16 QC1204415381 LCS Iron-55 75.4 73.8 pCi/g 97.8 (75%-125%) 10/31/19 18:25 Uncertainty +/-4.98 QC1204415379 MB Iron-55 U 2.24 pCi/g 10/31/19 16:19 Uncertainty +/-3.57 Page 48 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 493624 Page 6 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 1931689 QC1204415395 493624001 DUP Nickel-63 HUh -0.424 HU -0.114 pCi/g N/A N/A RP1 10/30/19 14:46 Uncertainty +/-1.17 +/-1.26 QC1204415396 LCS Nickel-63 70.5 60.2 pCi/g 85.4 (75%-125%) 10/30/19 15:03 Uncertainty +/-3.12 QC1204415394 MB Nickel-63 U -0.312 pCi/g 10/30/19 14:30 Uncertainty +/-1.36 Batch 1934551 QC1204422492 493624001 DUP Carbon-14 HU 1.92 HU 1.76 pCi/g N/A N/A TXP3 11/08/19 22:21 Uncertainty +/-1.76 +/-1.72 QC1204422494 LCS Carbon-14 128 125 pCi/g 97.6 (75%-125%) 11/08/19 23:55 Uncertainty +/-3.84 QC1204422491 MB Carbon-14 U 1.00 pCi/g 11/09/19 12:08 Uncertainty +/-1.18 QC1204422493 493624001 MS Carbon-14 150 HU 1.92 H 146 pCi/g 97.3 (75%-125%) 11/08/19 23:08 Uncertainty +/-1.76 +/-4.51 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 See case narrative for an explanation 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. Page 49 of 72 SDG: 493624
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 493624 Page 7 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time 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 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 50 of 72 SDG: 493624
Radiochemistry Technical Case Narrative LaCrosseSolutions, LLC SDG #: 493624 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: 1929693 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1929602 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 1204411091 Method Blank (MB) 1204411092 493624001(L3-012-101-RAGS-002-SS) Sample Duplicate (DUP) 1204411093 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 Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204411092 (L3-012-101-RAGS-002-SSDUP) Received 21-OCT-19, out of holding 07-MAR-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 Page Laboratories GEL 51 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Recounts The Am-243 traced portion of sample 493624003 (L3-012-101-RBGS-004-SS) was recounted due to a suspected false positive. The recount is reported. Product: Alphaspec Np, Solid Analytical Method: ASTM C 1475-00 Modified Analytical Procedure: GL-RAD-A-032 REV# 22 Analytical Batch: 1929694 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1929602 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 1204411094 Method Blank (MB) 1204411095 493624003(L3-012-101-RBGS-004-SS) Sample Duplicate (DUP) 1204411096 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 Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204411095 (L3-012-101-RBGS-004-SSDUP) Received 21-OCT-19, out of holding 12-APR-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 Page Laboratories GEL 52 of 72 SDG: u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 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: 1929695 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1929602 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 1204411097 Method Blank (MB) 1204411098 493624001(L3-012-101-RAGS-002-SS) Sample Duplicate (DUP) 1204411099 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 Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204411098 (L3-012-101-RAGS-002-SSDUP) Received 21-OCT-19, out of holding 07-MAR-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 Page Laboratories GEL 53 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Recounts Samples 493624004 (L3-012-101-RBGS-007-SS) and 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) were recounted due to a peak shift. The recounts are reported. Miscellaneous Information Additional Comments The tracer peak centroid for sample 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) is greater than 50 keV from the expected library energy value 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: 1929602 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 493624007 S3-012-109B-FJGS-062-SM 493624008 S3-012-109B-FJGS-063-SM 493624009 S3-012-109B-FJGS-064-SM 493624010 L2-011-101-FSGS-013-SS 493624011 L2-011-104-FSGS-001-SS 493624012 L2-011-104-FSGS-010-SS 493624013 L3-012-101-FSGS-004-SS 493624014 L3-012-109-FSGS-005-SS 493624015 L3-012-109-FSGS-006-SS 493624016 L3-012-109-FSGS-011-SS 493624017 L1-010-107-FSGS-008-SS 493624018 L1-010-101-FSGS-015-SS 493624019 L1-010-102-FSGS-007-SS 493624020 L1-010-103-FSGS-005-SS 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 54 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Product: Dry Weight Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1929603 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624021 L1-010-104-FSGS-016-SS 493624022 L1-010-105-FSGS-007-SS 493624023 L2-011-101-FSGS-005-SS 493624024 L2-011-104-FSGS-011-SS 493624025 L3-012-101-FSGS-005-SS 493624026 L3-012-109-FSGS-014-SS 493624027 L3-012-109-FSGS-017-SS 493624028 L1-PAD-GR5-AJGS-006-SS 493624029 L1-PAD-GR10-AJGS-007-SS 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: 1929624 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1929602 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 1204410974 Method Blank (MB) 1204410975 493624001(L3-012-101-RAGS-002-SS) Sample Duplicate (DUP) 1204410976 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Page Laboratories GEL 55 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Technical Information Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204410975 (L3-012-101-RAGS-002-SSDUP) Received 21-OCT-19, out of holding 07-MAR-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 Product: Gamma Ni59, Solid Analytical Method: DOE RESL Ni-1 Analytical Procedure: GL-RAD-A-022 REV# 19 Analytical Batch: 1931847 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1929602 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 1204415726 Method Blank (MB) 1204415727 493624001(L3-012-101-RAGS-002-SS) Sample Duplicate (DUP) 1204415728 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Page Laboratories GEL 56 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Technical Information Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204415727 (L3-012-101-RAGS-002-SSDUP) Received 21-OCT-19, out of holding 07-MAR-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 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: 1933651 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1929602 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 493624007 S3-012-109B-FJGS-062-SM 493624008 S3-012-109B-FJGS-063-SM 493624009 S3-012-109B-FJGS-064-SM 493624010 L2-011-101-FSGS-013-SS 493624011 L2-011-104-FSGS-001-SS 493624012 L2-011-104-FSGS-010-SS 493624013 L3-012-101-FSGS-004-SS Page Laboratories GEL 57 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
493624014 L3-012-109-FSGS-005-SS 493624015 L3-012-109-FSGS-006-SS 1204420254 Method Blank (MB) 1204420255 493624005(L4-OFF-SOL-IJGS-A01-SS NE) Sample Duplicate (DUP) 1204420256 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 Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204420255 (L4-OFF-SOL-IJGS-A01-SS NEDUP) Received 21-OCT-19, out of holding 31-OCT-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 Recounts Samples 493624002 (L3-012-101-RAGS-004-SS) and 493624012 (L2-011-104-FSGS-010-SS) were recounted due to results more negative than the three sigma TPU. The second counts are reported. 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: 1933654 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batches: 1929602 and 1929603 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624016 L3-012-109-FSGS-011-SS 493624017 L1-010-107-FSGS-008-SS Page Laboratories GEL 58 of 72 SDG: u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
493624018 L1-010-101-FSGS-015-SS 493624019 L1-010-102-FSGS-007-SS 493624020 L1-010-103-FSGS-005-SS 493624021 L1-010-104-FSGS-016-SS 493624022 L1-010-105-FSGS-007-SS 493624023 L2-011-101-FSGS-005-SS 493624024 L2-011-104-FSGS-011-SS 493624025 L3-012-101-FSGS-005-SS 493624026 L3-012-109-FSGS-014-SS 493624027 L3-012-109-FSGS-017-SS 493624028 L1-PAD-GR5-AJGS-006-SS 493624029 L1-PAD-GR10-AJGS-007-SS 1204420262 Method Blank (MB) 1204420263 493624025(L3-012-101-FSGS-005-SS) Sample Duplicate (DUP) 1204420264 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 1204420264 (LCS) was recounted due to high recovery. The recount 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: 1929696 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1929602 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 1204411100 Method Blank (MB) 1204411101 493624001(L3-012-101-RAGS-002-SS) Sample Duplicate (DUP) 1204411102 Laboratory Control Sample (LCS) Page Laboratories GEL 59 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.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. Quality Control (QC) Information RDL Met Sample (see below) did not meet the detection limit due to a lower sample yield. The client yield requirement was met. The sample was counted the maximum count time in order to achieve the lowest possible MDAs. Sample Analyte Value 493624003 (L3-012-101-RBGS-004-SS) Plutonium-241 Result -2.96 < MDA 5.69 > RDL 5 pCi/g Technical Information Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204411101 (L3-012-101-RAGS-002-SSDUP) Received 21-OCT-19, out of holding 07-MAR-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 Miscellaneous Information Additional Comments The tracer peak centroid for sample 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) is greater than 50 keV from the expected library energy value for the tracer; however, the tracer yield requirement was met and the tracer peak is within the tracer region of interest. Product: LSC, Tritium Distillation, Solid Analytical Method: EPA 906.0 Modified Analytical Procedure: GL-RAD-A-002 REV# 23 Analytical Batch: 1929721 Page Laboratories GEL 60 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 1204411178 Method Blank (MB) 1204411179 493624001(L3-012-101-RAGS-002-SS) Sample Duplicate (DUP) 1204411180 493624001(L3-012-101-RAGS-002-SS) Matrix Spike (MS) 1204411181 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 Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204411179 (L3-012-101-RAGS-002-SSDUP) Received 21-OCT-19, out of holding 07-MAR-17 1204411180 (L3-012-101-RAGS-002-SSMS) Received 21-OCT-19, out of holding 07-MAR-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 Recounts Samples 1204411179 (L3-012-101-RAGS-002-SSDUP) and 493624004 (L3-012-101-RBGS-007-SS) were recounted due to high MDCs. The recounts are reported. Product: Liquid Scint Tc99, Solid Analytical Method: DOE EML HASL-300, Tc-02-RC Modified Analytical Procedure: GL-RAD-A-059 REV# 5 Analytical Batch: 1929739 Page Laboratories GEL 61 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 1204411222 Method Blank (MB) 1204411223 493624001(L3-012-101-RAGS-002-SS) Sample Duplicate (DUP) 1204411224 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 Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204411223 (L3-012-101-RAGS-002-SSDUP) Received 21-OCT-19, out of holding 07-MAR-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 Product: Liquid Scint Fe55, Solid Analytical Method: DOE RESL Fe-1, Modified Analytical Procedure: GL-RAD-A-040 REV# 13 Analytical Batch: 1931683 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1929602 Page Laboratories GEL 62 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 1204415379 Method Blank (MB) 1204415380 493624001(L3-012-101-RAGS-002-SS) Sample Duplicate (DUP) 1204415381 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. Quality Control (QC) Information RDL Met Samples (see below) did not meet the detection limits. Samples were counted the maximum count time in order to achieve the lowest MDAs possible. Sample Analyte Value 1204415380 (L3-012-101-RAGS-002-SSDUP) Iron-55 Result -9.54 < MDA 12.4 > RDL 10 pCi/g 493624001 (L3-012-101-RAGS-002-SS) Iron-55 Result -1.57 < MDA 18.7 > RDL 10 pCi/g 493624002 (L3-012-101-RAGS-004-SS) Iron-55 Result -8.13 < MDA 16.8 > RDL 10 pCi/g 493624003 (L3-012-101-RBGS-004-SS) Iron-55 Result -3.06 < MDA 16.7 > RDL 10 pCi/g 493624004 (L3-012-101-RBGS-007-SS) Iron-55 Result -2.34 < MDA 14.1 > RDL 10 pCi/g 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Iron-55 Result -2.65 < MDA 12.7 > RDL 10 pCi/g Technical Information Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204415380 (L3-012-101-RAGS-002-SSDUP) Received 21-OCT-19, out of holding 07-MAR-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 Page Laboratories GEL 63 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Recounts Samples 1204415380 (L3-012-101-RAGS-002-SSDUP), 493624001 (L3-012-101-RAGS-002-SS), 493624002 (L3-012-101-RAGS-004-SS), 493624003 (L3-012-101-RBGS-004-SS), 493624004 (L3-012-101-RBGS-007-SS), 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) and 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) were recounted due to high MDCs. The recounts are reported. Product: Liquid Scint Ni63, Solid Analytical Method: DOE RESL Ni-1, Modified Analytical Procedure: GL-RAD-A-022 REV# 19 Analytical Batch: 1931689 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 23 Preparation Batch: 1929602 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 1204415394 Method Blank (MB) 1204415395 493624001(L3-012-101-RAGS-002-SS) Sample Duplicate (DUP) 1204415396 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 Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204415395 (L3-012-101-RAGS-002-SSDUP) Received 21-OCT-19, out of holding 07-MAR-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 Page Laboratories GEL 64 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 Product: Liquid Scint C14, Solid Analytical Method: EPA EERF C-01 Modified Analytical Procedure: GL-RAD-A-003 REV# 16 Analytical Batch: 1934551 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 493624001 L3-012-101-RAGS-002-SS 493624002 L3-012-101-RAGS-004-SS 493624003 L3-012-101-RBGS-004-SS 493624004 L3-012-101-RBGS-007-SS 493624005 L4-OFF-SOL-IJGS-A01-SS NE 493624006 L4-OFF-SOL-IJGS-A03-SS SW 1204422491 Method Blank (MB) 1204422492 493624001(L3-012-101-RAGS-002-SS) Sample Duplicate (DUP) 1204422493 493624001(L3-012-101-RAGS-002-SS) Matrix Spike (MS) 1204422494 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 Holding Time Samples (See Below) were received and analyzed outside the hold time. Sample Value 1204422492 (L3-012-101-RAGS-002-SSDUP) Received 21-OCT-19, out of holding 07-MAR-17 1204422493 (L3-012-101-RAGS-002-SSMS) Received 21-OCT-19, out of holding 07-MAR-17 493624001 (L3-012-101-RAGS-002-SS) Received 21-OCT-19, out of holding 07-MAR-17 493624002 (L3-012-101-RAGS-004-SS) Received 21-OCT-19, out of holding 12-MAR-17 493624003 (L3-012-101-RBGS-004-SS) Received 21-OCT-19, out of holding 12-APR-17 493624004 (L3-012-101-RBGS-007-SS) Received 21-OCT-19, out of holding 22-APR-17 493624005 (L4-OFF-SOL-IJGS-A01-SS NE) Received 21-OCT-19, out of holding 31-OCT-17 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) Received 21-OCT-19, out of holding 31-OCT-17 Page Laboratories GEL 65 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Recounts Samples 493624002 (L3-012-101-RAGS-004-SS) and 493624006 (L4-OFF-SOL-IJGS-A03-SS SW) were recounted to verify sample results. Recounts 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 66 of 72 SDG:u.c 493624 PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Page 67 of 72 SDG: 493624 L/9sloZ-Y Page: I nf _ 4 _ _ _-0 I , Projcclll LACBWR Site ***---- GEL Quote f: - - - - - - - - - - - - - - j [SJ=t* Laboratories LLC Chemfsl:r,, ! Rad!OChemlslry I Andlobloassay I Specillftv Anatvt~ GEL Laboratoncs. UC 2040Savah>eRoad Charlestnn, SC 29407 coc Num~r ,;-,_ Chain of Custodv and Ana".+ical Reriuest Phone: (843J 556*817! PO Number: 672583 GEL Work Order Number; GEL Project Manager: Fas: 1343\ 766-1178 Client Name La Crosse Solu1ions Phone~ 608--689-4259 Snmplc Analysis Requested !IJ (Fill in the number of containers for each test) Prnject1S ite Narnc. LACBWR-Gcnoa WJ r*ax ii Sliou!EI this ~ <- Preservative Type (6) Addrtss: 54601 Slate Road 35 '""'Pie l>t .!! .,. con,ldored: i :t~ ,.,
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_hel/lf: te_g,mfli,g'_l,o,u/JUlg amt/or ~ l IAs m Arse~,c Hgm*Mer,;,,ry RE= Rc~c!i*-e ~II.\. (i.C,'.' (Jr/gill of sample(<). 'lyf!f Waste eodt!~<): mi.\c. h?alrh 1,a:m*d,. etc) Ba= Bari,un Sc--Seleniuni Description, oJ ,iie colle<:tedfhWI. <Hid m(lt,i,;;c.,, etc) Cd =Cadmium Ag= Silver /TSCA Rcr,ulaf<"<I Cr= t.1lmmium l\fR,,,Mtsc. RCRA metals PCB = Po ychlnrmafcil I .. pr, .. i_,,;,d - biphenyls
Page 69 of 72 SDG: 493624 W:1111 ILaboratone, s Page: 3 of __4 _ ___ L./C/3/v?_ '--1 GEL Laboratorie.s, LLC Projccli/ 1,ACBWR .0 ite GEL Quote #* ~ - _ _ _ _ _ _ _ _ _ _ _ _ LLC 2040SavagcR ,;,ad
~-"""' ~,my I AM1ocMm1Sll}I IRa<:11obioas,;ar I s.,,,,;;aftv /ln!tiYtfeS coc Number"' _____ 7 Charleston, SC 29~07 Chain of Custody and Analvtical Reauest Phone: (843) 556-S17l PO Number: 672583 GEL WorkOrder Nr,,nber. GEL Projed Manager: Fax: (843) 766-! 178 Client Name* La Crosse Solutions Phone# 608-6l!9-4259 Sample Analysis Requested !1') (Fill i11 the: number of containers for each ce~t)
Projoct/Sitc Name: LACB WR-Genoa WJ Fax ii Should !his c 0-- Prcser.*ative Type (6) 0 Address* 54601 Slate Road 35 "'"'rte be ~ considered: -~ Colle<:led By: Kevin L Murray ,._ E Comments Send Results To.Scott Zoller sg,oller@energysolutinns.com ""i ~ ] ~ 0 Note: extra sample is
,~ ~; ~ "'
"Timo ,! ~ 'g ;: = ~ ,,; required for sample C-0~"'"'" ~ ~ ~
Sample ID 2~""ee
*oa1oroll""""1 ir.i~-.. J or Field s,mpl* -- c. -~ .,il spec1"fi1c QC
*Forro,,,=.,He,-inJ;,,.,,,.sta.,a11dJ"lm>dat~1ime (,non.,r,1-~i lhh~.:?: Coden, 1;'>1<<,"'3°'Ma1ri,"' ~ ! l/, E[ ~
L!-010-W7-FSGS-008-SS 08/08119 !5:00 N N SO N N 1 I Ll-010-101-FJGS-015-SS 08/081!9 15:12 N N so N *'-.,N,, ! 1 1.1-010-102-FSGS-007-SS 08114119 15:18 N N SO N N I I Ll--010-103-fSGS-005-SS 08114/19 W:JJ N N SO N *-~-i,:i, l 1 LI-OIO-I04-FJGS-016-SS 08!.?3.'19 9*57 N N SO N N I I LI-0!0-!05-FSGS-007-SS 081'.!3/\9 13:29 N N SO N ','if> 1 1 l2--011-101-FSGS-005-SS 09120/19 14.0! N N SO N N l ! LZ-011-104-FSGS-Ol l-SS 09109119 14:52 N N SO N "N' ._. I I U-012-!01-FSGS-005-SS 09/05/19 13:00 N N SO N N ! l D-012-109-FSGS-014-SS 09/23119 14:21 N N SO N :'. _i;,;, \' I I Ch3in of Custody Signatures TAT Requested: Norn13f: _X Rush: Specify: (Suhjttl to Sur~harg,,) Relinquished ByfS1gnc<l) D.110 Time Rece"*eJ by(sogned) Date T,m* Fa., R.esul1s: r 1 Yes rXl No
- 1. Kc,*in LMurra, "'11612019 l:J1J l I .I 1 ~ , ,',; ~,rt,rf..~r-~7.J.C.TJ w7i,nrfs",",~",",,_"',,"_,-,L,*M>c:"-fCJC-",*,CACC, -JQC-cS-o_m_m_a_m-Cf-:C 1,,-,-d-l-CDXC-l-,-,-,,-2--f ll-,-_,-,-,--
- J-lle-,-,-,,---j 2 ~ 2 4dd1/ia,a<1/ R~mark,*: Non~
3 3
> fors~mp/esl,/ppit1g 4n,t delfrerrderuil.,, see Sample Receipt & Rl!l1ew form (SRR.)
Ft>r /,11b ReceMng l!u O"IJ"' C,wod,-Si:a/ '""""e [ J Ye, ( ] Nr, Cooler Temp: °C IS~mpleC,,l/atio11 Time Zone: [ I Eastern ! ] Pl'lcific [X] Centm! [ JMountain [ ] Other: l ) Chaia ofC"s<od, ~*""""' - ("hen, ll""""'d Z ) QC Codes: N "Nom"I Sample. *r11 = Trip !ll>ak. FD " I ,<id Dilplic.'lle. EB = Eqvrprnen, Blank. MS " MIOln< Sp,kc Samrl~ MSD =Mahi, Spi\c D,ph,,io Sam11k G = Gc.,b_ (. "Com['<<'it< JI F,old Fil<<:cod r.,. !,quid "'*'"""'~ md,ca,c ,.,,1, a* Y
- ror )~~ *he ,ampfo ~*as lioM !il"red or* N - fo, sample
"~' n,,>t field fillered 4_) Ma,ri, Code,. DW* D,iol-ing Wa,,r. CW -{),mm<iw>ter, SW=Surfoc, Waoor, WW"W>Sle WoEer. w,*w""* ML=M~c l.iqLJ1d. S0°Soil. SO"S.d1"""* ~I .=Sl<odge. SS=Sohd Wa1."e. Oa--Qil, F* F,loc,, P~\\'1pe. ll=l;r,n,,. F*F<<,,t, 1'=7<~"'1 S l Samplo An;,lisis Ro(lii.'>ted An>l)1ul metood r.,qu,>ted O o, *lOOU. 601011/N7UA)
"'1d nu,nl,e, of'°"'°""" f"0'1dod for c"<h (, o ~]WI! . J (./J//JI< 7J,M - 11 6 ) P,-c,on,atL,~ Tyre IU -. fl)drochloric Acid. NI = :-,,,n, Ami. SIi ~ Sod1L1m H.1*d,0'1<f<,
=Sulfono Acid. AA, A.soo,t,i, Acod. IIX ~ IJe,,n;,. ST= Sod,um Th,osulfate, If oo P"""""";,~ " added = I.,,,~
SA (;dd blank 7.1 , * , *- Char.. ctcristic Hazard., I 11,is!ed Wasie 1uthcr f'ktpeprp,ld elmJ! 11iJdi(amatditaµs. FL~ Flannnable/lgnilllb!e LW"' Listed Waste OT~ Other /Unknown RCRA Mttals lu!JJJwl'egard/ng hand/mg aml/pl"dilipOS4/ CO"' Corro_sivc {F.K,l' mkl U-/1>1,:dwasre.i') ('":*' Hif!!,,fow pH. asbe,;1,a,. hery/Uum. irri1an1,. "'""'
*~=Arsenic JJ~ Mercury RE~ Reacttve wncen,.s. (le.: Origm,,f$1llt/p/efs), h"P",
- Waste code(s): nn,,c. heal/I, Jw:ard.,*, ela.J Ba"' Barium &"' Selenium ~~~~-~ _ _ _ of.<ite.crnlcctedJhim. oddmatrfres "etc.)
Cd~ Cadmium* Ag= Silwr /fsCA Rcgu!Hte.l 7 7] ____________ Descrlpl1on:
* **~
er~ Cllmmium MR,,,Misc. RCRA mclals PCB= Pol_vchionnated --------------------- Pb"' Lead biphe11yls
Page 70 of 72 SDG: 493624 Y 9 3 ly 2-'-/
,:~;~c~#- LA~B\\-;;*- ,.,::---
OEL Quote a: ~---- ----- --4 4
----j [il=I""'" I ILaboratorieSLLC ~o~~~a:;c~o~~LLC coc Number"'
""' cnem""",r I And!o<:hemist,y I lladiol>>oassay I S!l<l<illlty AA<llytios Charleston, SC 20407 Chain of Custodv and Analvtical Reauest Phone: (84Jl 556-8171 PO Ntunt>er:_Q_77583 GEL Wort Order N11mber; GEL Project Manager: Fax:<MJJ 766-1178 Client Name: La Crosse Solutions Phone# 608.{)89-4259 I Sample Analysis Requested IS) (Fill in t!i_e_ m1111ber ~_conlai11ers for_each t~)
Project/Site Name* LACBWR-Gcno;i Wl Fax# S~o~fd th;,
<-* P!"l'scn'ative Type {6)
Address: 54601 smtc Road 3S Collected By. Kevin L Murray Send Reoul!s To:Scou Zollc, sgzollcr@cncrgysolutions.com sao,plelu con,id~ned:
- . i: I f I' Comments Sample ID
,,,,,1,,0
-,T<"OC'""'"'" - I "" *
"T ...: * , ;
(~;~;'~-~) i Ftold i s,",,,1
;;;_;[:~ .
i £ Note: extra sample is required for sample specific QC
- fo, cma '""' - ;,1Ji,,,1e .,/art
_!.,j-012-109-FJG_S-Ol 7-SS dare,)inte (rnrn-dd- I {hhmm.>. Coil< "' F1ltoNOm M,i,,, l 09124119 !3:52 N N so N N 1_1-PAD-GRS-AJGS-006-SS _27112/!Q 12,22 N N so N <*]i::-1
------- L1-PAl).QR I0--AJGS.,QQJ-SS 07/13119
~
11;_4_8 N N SQ N N
*-sJ
~--1-----..........
Chain of Custody Signa111res t-Rehnqu,shed By IS,g,,ed) Oak Tune Rocc,ved by ("b"'od) ,., ,-..,,
~'-
TATRe([llCllted: Fax Resul_!!;_: [ ] Yes Norlll/ll:_x. ._Rush: Specify, (Suhject tn Sur<hatgl,) ur.q t,< :,,v,, fXJ No 1'-l(cvin L M~rray '/v,,,d, 10/jfj/2019 /3,tS- LIJ, ( Sclec1 [)elivcrabl~:I JC ~A [ ] ~ Summary_ ~ _ I ___ ~ v e l 2 _l_J_Level 3 f J L.evel_,j_ z V 1 Add11imu,/ Remarkt: None 3 J For La_b Recdvi11g lise On{I Cu.,wdy&c,I 1111<:_u".Jl Ye, U No
> for sample $llippi11g ami delfre,y details, see Sample Reuipl & Review form (SNR.) <.Wier Temp: "C
!Sample Collection Time Zone f JEastern. [ ] Pacific !X] Cen1raJ [ JMountain
[ ] Other: l ) Cham ~fCus,ody Numbo,= (h"1, !kt<crmn,d 2 ) QC Codes N - Nornml Sample, HI -- Tr,p Bl.ml, FO = flo!d Oup!,.,.t<. Efl = Eqo1prn¢ol lll;*nk MS ~ Main< Spike S>~<. MSD O ~1a,nx Sp,k< Dupl,ca" San,,,lc. G = 0.ab, C = Compc,,,o, J ) Pidd f;l,o,e,J f'<X liqoid rnat1 io.,s. "'"""< ";oh a* Y
- fot y,c; oho sam~,c was fio!d filter<< or* N
- for sample""" ,ot fidd filtorod 4 J Moc,i, Cod,,,; rtW-DfiokO,g W""* GW=G"""1<iwotor, ~"\\~Surf""" \\'"or, WW=W><<o Wmor. W *W*k~, ML=MJ<< LCQ",d. S0°Srnl, SD=Sod,m,m. Sl.=Sl,,dg,. SS=Solid WMtc.
O-Oil, F-F,ltec, P~WiP"', l:=IJrioe, f *Fecal, :'<=N>>al 5.) Sample AtllLI)'i, 1\cqoo~cd ,lnaly,ical nh,to;xi '"'1"""'" (* , 826(18_ 6(110JIJ7470,I) "'" nonober of wotai,,rs pr<>11dod for e.1ch (t c .!Wm
- l, 6f//OJNJ70A
- 1)
I~.) P,,~ern,tive T;p<. IU =lly<lro,;hlonc Acid. 1'1 r N"',c Acl<l SIi ~ So,J<orn Hydrosick SA~ Sulfwic Add. ,I.A= A=b" Acid flX _, H*"'"'* S~' r >DO""" ll,iocolfa,o. lfno pr<<cmlEiv; is oddod = lco,e fL<ld blsnl
- ,., KNOWN 01( 1*oss1m,1*; lfAZARllS lcharactcrls tlt llazards I jLlstOO Waste I [ill§: J>kcue_pio,;fdi,Bnyt1_dd/ll,Jlllll 4etiifrs.
FL"' Flammable/lgmtahle LW,.,J.isled Waste -OT~ Other I Unknown
,Rcll.a\_Metah CO~ Corrosive (F.K,P ,md U-/i,ted~Y1$le,J !hduw-r,11:itrdi"Jl t,(litdling a11_tl/ar,Jisp1JS11l IAS =Arsenic (1.e,: fliglr/ow pH. asbe.,ms. heryil,um, 1rri1ums. o1/1er
,rjf-~rcury RE= Reacli\*e Wastecode(s): wr,ceraj. :r1.e.; Origm ,,f:,amp/i(s), rypr .
mi.,c. heu/lh /l(l=ards, etc.; Ba=Barium 8e-- Selenium ofs{/e*e,J11ec1,mfro,ii, odp mmri<'e.<, erd. _, Desc_rlption; - -, -* Ol=Cadmnm 1 ,,gaa Silver
- c,~Chromi um MR"' Mtsc. RCRA metals jTSCA Ref,iiTatcd PCB"' Po Ychlormatcil I Ph= Lead 1:>ivhcnyls
Client : ,_ ,~ r-1( SAMPLE REC Ef PT & REVIEW FORM Rccci1*etl B fsoG/A RJCOC IWork Order ' L
!natc Received:
- J
' 31,; **z_y (ud, \ppl""1> k
( FedEx bprcs >>. l'udE> Ground UPS Field Servic~s Courier Other Carrie r and Trnckini:: Numb er 175'1- 3' 57 5~ f7 ft Suspected 1-!a~urd Jnforn,mion
~ z* *If Net Comm ,. IOOcpm on smnplcs not nrnrkc><i "rndioac!ivc". conr.,ci the Radiniioo Safely G,m,p for further im*,sl;gst;on .
Hazard Clns.< .%ippc-d: [;'.'/#: A)Sh,n,.,*d ,,s a DOT l-la.ardous'! .I If LiN2910, Is the Radioacm*c S!11pu1cnl s.,ncyC 01npl,,,i11 Yes_,_ .'.fo. B) Did ihc clic,u dcsig11,;cc !he samples ,in, JO b.: rc-cd ,cd as rndioact1 vc*> l COC nowt ion or radioactive sticker.; °" co'llaiucrs equal tlicm dc~gnation. C) Did the RSO dassifr lhc samples as M,1'irnun* ,'\ct Coums Obscrvc>J* {Ob>crV<d Co,11,1,
* .-\re, Background C0< ,nl$) ;~CP M I mRJllr rndioacl,vc? J Cln,.<ificd o,: R,1<1 ! R,><I 2 R,ul J D) Pid 11,c clieiu dcsig,,atc ,,mnpie, arc COC nooanon or ho,or<l labcl, ou cnnr,iucrs equal ha,,ardous' client de,;i~..,alion.
fO,u Eis vc.s. >deer Haz.1rd, below El o;J tl,c RSO idcm,r, fl'O>>obk hazarrt,1 .I PC B's Flammable Fordgu Soil RCR,I Asl><slos Bc'l)*lliu,n Other. S,1m1*k Rceeir,t Critcrio Sl1ipping containers rec~ived imuct and sealed '
-' < z*
z C,rcl, ,lrpk,1hl, Commcnr.s/Qu,olificrs (Required (or Non*Cunform s,,,1, broken Damo~o) Ciw111 ur c1~1mdy documcnr.1 included 2 rirck *lrrl"" "I, Clicn, '"'"'*"" " and pco,idecl CO(" with shipm ent COC cre,,ocd upon ,.,,,,po Sam1>lc, rc<]tming cold preservati(ln Pn,sen*atioll .\fcthod: Wet Ice Jc" P,1ck,
' within (0.:;:: 6 deg. C)?* *all ,cmpernlurcs ,,re rccor<lcd "' CclsiHs Dry ,cc ~ 01hcr T£MP : 2.;*
Daily chec~ performed and passed Oil lR lempcmturc gun? l Tcn,pcrnturc Dcvke Serial #: Scco11da,;* l"c111µcrn1urc fJC<*,ce Scri,I -
!! ( If Applicable/.
Sample containers 111rnct and seal<:<!'! Ci,d, Appl"able Soals brnlcn Damaged C<lillarner
' Sam1lks requiring ch~mic,11 prcscrvaiion Leaking ,on1mnor Other (J,,,or,l>e)
S,1mplc Ill's and Cooomnor, .*\ff<<tod
' at proper pH'.'
lfP,*sc "' 11 ,111,i *d L"'" If Ycl, are Encore< or Soil Kits prescnl for solids'? Yes No_ :--'.'\ _(i(}')S. ra~c lo VOA Free7.cr) Do an_v srnnplcs requir~ Volatl k Do liq,ud VO,\ ,*i,11s coi*tain $id prcscr\',1ho11°
' Analys,s
I
*\r~ liq11i<l VOA ,*i,1!, free ofhcadspace' Ycs S"'upl, m*, ,,nd """'""c" ,ff,ct<<l
\'es.
No
'so
- NA --
N,\ (lfunknow"* sctoct No) ilD'.s and tests ,1tfoc1cd; Samples reccjvcd wiih;n ~oldong iionc1 Samµlc ID's on COC match ID's on ll)'s and co,>1aiucrs ,ffcctcd bonks Da!~ &. time on COC match date & mnc C'irdc . \pplic ahk No dates '"' contmncrs
'" 011 bolt/cs? No tin,cs on co,11ainer< COC u1iss;ng ,nfo 011,cc idc><.ribc)
Number of co111nir>er., rc><:eiwd maid, Cirdc .-\ppl*cablc: No crn"aiuc,* Cllll!H 011 COC
" numb~r imlicatcd 011 coc>
.-\re sampl e comamcrs idemifm~lc a~
(Jthcr (dcsc, ihel
" fF 1 COC fonn is properly s,gned in I
Circle \1,plaeabl<,*
" rclm11 uishedlr~ceiwd s~ctioos'.'
Co111mon1s {l'ie Continum10u Fonn if needed)* Not rnlinquishc<l (JU,cr (<ksc*ri11c1 PM (or l'M:\) r.:1,cw. lni1ials
- /1,1 e,_ ----- ""'" L0}2Jcj !.'l Pa~c _ I
"' - I GL-CHL..SR-001 Rev 6 Page 71 of 72 SDG: 493624
List of current GEL Certifications as of 14 November 2019 State Certification Alaska 17018 Alaska Drinking Water SC00012 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 Massachusetts PFAS Approv Letter 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 2019165 Pennsylvania NELAP 6800485 Puerto Rico SC00012 S. Carolina Radiochem 10120002 Sanitation Districts of L 9255651 South Carolina Chemistry 10120001 Tennessee TN 02934 Texas NELAP T1047042351915 Utah NELAP SC00012201929 Vermont VT87156 Virginia NELAP 460202 Washington C780 Page 72 of 72 SDG: 493624
tcl=l* ILaboratories LLc PO Box ~0712 Charteston SC 29417 a member of The GEL Group INC 2040 Savage Road Charfesron SC 29407 P 843_556.8171 F 843.766.1178 gel co m February 01, 2018 Mr. Jason Q. Spaide LaCrosseSolutions S4601 State Hwy 35 Genoa, Wisconsin 54632 Re: LACBWR Site Restoration Project Work Order: 441021
Dear Mr. Spaide:
GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for the sample(s) we received on January 08, 2018. This original data report has been prepared and reviewed in accordance with GELs standard operating procedures. Our policy is to provide high quality, personalized analytical services to enable you to meet your analytical needs on time every time. We trust that you will find everything in order and to your satisfaction. If you have any questions, please do not hesitate to call me at (843) 556-8171, ext. 4453. Sincerely, PM_SIGN_HERE Edith Kent Project Manager Purchase Order: 672583 Enclosures Page 1 of 26
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: 441021 GEL Work Order: 441021 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 26
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: February 1, 2018 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-SUB-WRS-ASGS-10A-SB Project: ENRG07001 Sample ID: 441021001 Client ID: ENRG070 Matrix: Soil Collect Date: 04-DEC-17 14:37 Receive Date: 08-JAN-18 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 0.0462 +/-0.0819 0.135 0.400 pCi/g BXA4 01/13/18 1144 1730044 1 Americium-243 U 0.0289 +/-0.0954 0.179 0.400 pCi/g Curium-243/244 U 0.00 +/-0.0337 0.046 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U -0.0546 +/-0.103 0.319 0.400 pCi/g BXA4 01/16/18 1430 1730045 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U 0.0943 +/-0.0991 0.138 0.400 pCi/g BXA4 01/13/18 1144 1730046 3 Plutonium-239/240 U -0.000788 +/-0.0916 0.190 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U -0.838 +/-2.20 3.79 5.00 pCi/g BXA4 01/16/18 1002 1730047 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U 0.00707 +/-1.35 2.71 5.00 pCi/g TXJ1 01/24/18 0615 1730218 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 U 0.0341 +/-0.0667 0.0753 1.00 pCi/g MXR1 01/11/18 0841 1730111 6 Cobalt-60 U 0.0321 +/-0.0375 0.092 pCi/g Europium-152 U 0.039 +/-0.0881 0.183 pCi/g Europium-154 U -0.03 +/-0.0939 0.183 pCi/g Europium-155 U 0.0428 +/-0.096 0.189 pCi/g Niobium-94 U 0.0536 +/-0.051 0.069 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.00872 +/-0.148 0.288 0.400 pCi/g KSD1 01/11/18 1105 1730073 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U 2.56 +/-4.05 6.91 10.0 pCi/g BXM4 01/15/18 1336 1730202 8 Liquid Scint C14, Solid "As Received" Carbon-14 U -0.308 +/-2.24 3.86 5.00 pCi/g BXM4 01/16/18 1201 1730208 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U 0.0425 +/-1.00 1.73 2.00 pCi/g CXS7 01/28/18 1151 1730190 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U -3.58 +/-5.04 7.41 10.0 pCi/g TXJ1 01/31/18 1523 1734775 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 3 of 26
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: February 1, 2018 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-SUB-WRS-ASGS-10A-SB Project: ENRG07001 Sample ID: 441021001 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 -0.478 +/-1.42 2.53 5.00 pCi/g TXJ1 01/24/18 1947 1730183 12 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JXO1 01/08/18 1414 1730077 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, 88.4 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 98.2 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 75.8 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 89.2 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 73.6 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 96.4 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 110 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 91.9 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 72.4 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 93.7 (25%-125%) Notes: Page 4 of 26
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: February 1, 2018 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-SUB-WRS-ASGS-10A-SB Project: ENRG07001 Sample ID: 441021001 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 26
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: February 1, 2018 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-SUB-WRS-AJGS-15A-SB Project: ENRG07001 Sample ID: 441021002 Client ID: ENRG070 Matrix: Soil Collect Date: 05-DEC-17 14:31 Receive Date: 08-JAN-18 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 0.0179 +/-0.053 0.0962 0.400 pCi/g BXA4 01/13/18 1144 1730044 1 Americium-243 U -0.000538 +/-0.0712 0.149 0.400 pCi/g Curium-243/244 U -0.00603 +/-0.0288 0.0701 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U -0.0456 +/-0.154 0.400 0.400 pCi/g BXA4 01/13/18 1115 1730045 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U -0.0311 +/-0.0455 0.135 0.400 pCi/g BXA4 01/13/18 1144 1730046 3 Plutonium-239/240 U -0.0393 +/-0.0802 0.193 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U -1.68 +/-2.54 4.40 5.00 pCi/g BXA4 01/17/18 1829 1730047 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U -0.0186 +/-1.36 2.57 5.00 pCi/g TXJ1 01/24/18 0727 1730218 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 0.187 +/-0.076 0.0916 1.00 pCi/g MXR1 01/11/18 0842 1730111 6 Cobalt-60 U -0.00837 +/-0.040 0.0862 pCi/g Europium-152 U 0.0115 +/-0.097 0.186 pCi/g Europium-154 U -0.129 +/-0.170 0.288 pCi/g Europium-155 U 0.0486 +/-0.0952 0.194 pCi/g Niobium-94 U -0.004 +/-0.0439 0.0774 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U -0.0696 +/-0.123 0.268 0.400 pCi/g KSD1 01/11/18 1301 1730073 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U 0.0569 +/-3.99 7.02 10.0 pCi/g BXM4 01/15/18 1428 1730202 8 Liquid Scint C14, Solid "As Received" Carbon-14 U -1.75 +/-2.14 3.75 5.00 pCi/g BXM4 01/16/18 1247 1730208 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U -0.304 +/-1.03 1.80 2.00 pCi/g CXS7 01/28/18 1223 1730190 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U -7.22 +/-5.20 7.82 10.0 pCi/g TXJ1 01/31/18 1555 1734775 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 6 of 26
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: February 1, 2018 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-SUB-WRS-AJGS-15A-SB Project: ENRG07001 Sample ID: 441021002 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 0.570 +/-1.39 2.39 5.00 pCi/g TXJ1 01/24/18 2004 1730183 12 The following Prep Methods were performed: Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JXO1 01/08/18 1414 1730077 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, 109 (15%-125%) Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 91.9 (15%-125%) Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 81 (15%-125%) Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 87.4 (15%-125%) Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 50.7 (15%-125%) Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 93.5 (25%-125%) Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 107 (25%-125%) Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 89.5 (15%-125%) Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 70.2 (15%-125%) Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 99.2 (25%-125%) Notes: Page 7 of 26
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: February 1, 2018 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project Client Sample ID: L2-SUB-WRS-AJGS-15A-SB Project: ENRG07001 Sample ID: 441021002 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 26
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Report Date: February 1, 2018 LaCrosseSolutions Page 1 of 7 S4601 State Hwy 35 Genoa, Wisconsin
Contact:
Mr. Jason Q. Spaide Workorder: 441021 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 1730044 QC1203948279 441021001 DUP Americium-241 U 0.0462 U 0.0883 pCi/g N/A N/A BXA4 01/13/18 11:44 Uncertainty +/-0.0819 +/-0.0948 Americium-243 U 0.0289 U -0.000407 pCi/g N/A N/A Uncertainty +/-0.0954 +/-0.064 Curium-243/244 U 0.00 U 0.00 pCi/g N/A N/A Uncertainty +/-0.0337 +/-0.035 QC1203948280 LCS Americium-241 9.33 8.95 pCi/g 95.9 (75%-125%) 01/13/18 11:44 Uncertainty +/-0.707 Americium-243 U 0.0291 pCi/g (75%-125%) Uncertainty +/-0.0962 Curium-243/244 11.7 11.5 pCi/g 97.9 (75%-125%) Uncertainty +/-0.795 QC1203948278 MB Americium-241 U 0.0383 pCi/g 01/13/18 11:44 Uncertainty +/-0.0639 Americium-243 U 0.00647 pCi/g Uncertainty +/-0.0628 Curium-243/244 U -0.000151 pCi/g Uncertainty +/-0.0493 Batch 1730045 QC1203948282 441021001 DUP Neptunium-237 U -0.0546 U 0.0128 pCi/g N/A N/A BXA4 01/13/18 11:15 Uncertainty +/-0.103 +/-0.134 QC1203948283 LCS Neptunium-237 21.1 23.1 pCi/g 110 (75%-125%) 01/13/18 11:15 Uncertainty +/-2.06 QC1203948281 MB Neptunium-237 U -0.00876 pCi/g 01/13/18 11:15 Uncertainty +/-0.131 Page 9 of 26
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 441021 Page 2 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 1730046 QC1203948285 441021001 DUP Plutonium-238 U 0.0943 U -0.029 pCi/g N/A N/A BXA4 01/13/18 11:44 Uncertainty +/-0.0991 +/-0.0701 Plutonium-239/240 U -0.000788 U -0.058 pCi/g N/A N/A Uncertainty +/-0.0916 +/-0.0898 QC1203948286 LCS Plutonium-238 U -0.0959 pCi/g 01/13/18 11:44 Uncertainty +/-0.117 Plutonium-239/240 9.36 10.5 pCi/g 112 (75%-125%) Uncertainty +/-0.934 QC1203948284 MB Plutonium-238 U -0.0242 pCi/g 01/13/18 11:44 Uncertainty +/-0.0445 Plutonium-239/240 U 0.00774 pCi/g Uncertainty +/-0.0627 Batch 1730047 QC1203948288 441021001 DUP Plutonium-241 U -0.838 U -0.931 pCi/g N/A N/A BXA4 01/16/18 16:14 Uncertainty +/-2.20 +/-1.92 QC1203948289 LCS Plutonium-241 70.8 55.9 pCi/g 78.9 (75%-125%) 01/16/18 18:17 Uncertainty +/-2.55 QC1203948287 MB Plutonium-241 U -2.31 pCi/g 01/16/18 14:10 Uncertainty +/-2.90 Rad Gamma Spec Batch 1730111 QC1203948456 441021001 DUP Cesium-137 U 0.0341 0.141 pCi/g 60.8 (0% - 100%) MXR1 01/11/18 09:48 Uncertainty +/-0.0667 +/-0.0631 Cobalt-60 U 0.0321 U -0.00831 pCi/g N/A N/A Uncertainty +/-0.0375 +/-0.0414 Europium-152 U 0.039 U 0.0343 pCi/g N/A N/A Uncertainty +/-0.0881 +/-0.0761 Page 10 of 26
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 441021 Page 3 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 1730111 Europium-154 U -0.03 U -0.0618 pCi/g N/A N/A MXR1 01/11/18 09:48 Uncertainty +/-0.0939 +/-0.112 Europium-155 U 0.0428 U 0.0551 pCi/g N/A N/A Uncertainty +/-0.096 +/-0.0831 Niobium-94 U 0.0536 U -0.0178 pCi/g N/A N/A Uncertainty +/-0.051 +/-0.0369 QC1203948457 LCS Americium-241 488 546 pCi/g 112 (75%-125%) 01/11/18 09:48 Uncertainty +/-13.3 Cesium-137 174 172 pCi/g 98.9 (75%-125%) Uncertainty +/-3.50 Cobalt-60 136 139 pCi/g 103 (75%-125%) Uncertainty +/-3.65 Europium-152 U -0.494 pCi/g Uncertainty +/-1.49 Europium-154 U -0.592 pCi/g Uncertainty +/-0.975 Europium-155 U 0.175 pCi/g Uncertainty +/-1.31 Niobium-94 U 0.115 pCi/g Uncertainty +/-0.472 QC1203948455 MB Cesium-137 U -0.00748 pCi/g 01/11/18 08:42 Uncertainty +/-0.0289 Cobalt-60 U 0.00549 pCi/g Uncertainty +/-0.0211 Europium-152 U -0.00811 pCi/g Uncertainty +/-0.048 Europium-154 U -0.0381 pCi/g Uncertainty +/-0.0836 Europium-155 U 0.0109 pCi/g Uncertainty +/-0.0474 Page 11 of 26
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 441021 Page 4 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 1730111 Niobium-94 U 0.00932 pCi/g MXR1 01/11/18 08:42 Uncertainty +/-0.0184 Batch 1730218 QC1203948719 441021001 DUP Nickel-59 U 0.00707 U -0.435 pCi/g N/A N/A TXJ1 01/24/18 09:26 Uncertainty +/-1.35 +/-1.09 QC1203948720 LCS Nickel-59 94.4 78.7 pCi/g 83.3 (75%-125%) 01/24/18 09:27 Uncertainty +/-6.43 QC1203948718 MB Nickel-59 U 0.395 pCi/g 01/24/18 08:31 Uncertainty +/-1.24 Rad Gas Flow Batch 1730073 QC1203948366 441021001 DUP Strontium-90 U -0.00872 U 0.00106 pCi/g N/A N/A KSD1 01/11/18 11:05 Uncertainty +/-0.148 +/-0.159 QC1203948367 LCS Strontium-90 23.1 21.1 pCi/g 91.2 (75%-125%) 01/11/18 11:05 Uncertainty +/-1.06 QC1203948365 MB Strontium-90 U 0.0341 pCi/g 01/11/18 11:05 Uncertainty +/-0.122 Rad Liquid Scintillation Batch 1730183 QC1203948613 441021001 DUP Nickel-63 U -0.478 U 1.15 pCi/g N/A N/A TXJ1 01/24/18 20:36 Uncertainty +/-1.42 +/-1.45 QC1203948614 LCS Nickel-63 83.6 85.7 pCi/g 103 (75%-125%) 01/24/18 20:53 Uncertainty +/-4.00 QC1203948612 MB Nickel-63 U 0.797 pCi/g 01/24/18 20:20 Uncertainty +/-1.84 Page 12 of 26
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 441021 Page 5 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 1730190 QC1203948630 441021001 DUP Technetium-99 U 0.0425 U -0.714 pCi/g N/A N/A CXS7 01/28/18 13:26 Uncertainty +/-1.00 +/-0.941 QC1203948631 LCS Technetium-99 40.4 34.8 pCi/g 86 (75%-125%) 01/28/18 13:58 Uncertainty +/-1.60 QC1203948629 MB Technetium-99 U 0.142 pCi/g 01/28/18 12:54 Uncertainty +/-0.915 Batch 1730202 QC1203948669 441021001 DUP Tritium U 2.56 U -0.23 pCi/g N/A N/A BXM4 01/15/18 16:12 Uncertainty +/-4.05 +/-3.93 QC1203948671 LCS Tritium 53.0 48.6 pCi/g 91.6 (75%-125%) 01/15/18 17:56 Uncertainty +/-5.97 QC1203948668 MB Tritium U -0.922 pCi/g 01/15/18 15:20 Uncertainty +/-3.78 QC1203948670 441021001 MS Tritium 107 U 2.56 86.0 pCi/g 80 (75%-125%) 01/15/18 17:04 Uncertainty +/-4.05 +/-11.3 Batch 1730208 QC1203948684 441021001 DUP Carbon-14 U -0.308 U -0.771 pCi/g N/A N/A BXM4 01/16/18 14:20 Uncertainty +/-2.24 +/-2.10 QC1203948686 LCS Carbon-14 140 139 pCi/g 99.6 (75%-125%) 01/16/18 15:53 Uncertainty +/-4.38 QC1203948683 MB Carbon-14 U -1.34 pCi/g 01/16/18 13:34 Uncertainty +/-2.09 QC1203948685 441021001 MS Carbon-14 310 U -0.308 301 pCi/g 97.1 (75%-125%) 01/16/18 15:06 Uncertainty +/-2.24 +/-9.63 Page 13 of 26
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 441021 Page 6 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 1734775 QC1203960226 441021001 DUP Iron-55 U -3.58 U -3.86 pCi/g N/A N/A TXJ1 01/31/18 17:00 Uncertainty +/-5.04 +/-5.19 QC1203960227 LCS Iron-55 124 116 pCi/g 93.7 (75%-125%) 01/31/18 17:31 Uncertainty +/-7.87 QC1203960225 MB Iron-55 U -1.82 pCi/g 01/31/18 16:27 Uncertainty +/-4.63 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 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. Page 14 of 26
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 441021 Page 7 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time
^ 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 15 of 26
Radiochemistry Technical Case Narrative LaCrosseSolutions, LLC (ENRG) SDG #: 441021 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# 26 Analytical Batch: 1730044 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1730077 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203948278 Method Blank (MB) 1203948279 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) 1203948280 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 Np, Solid Analytical Method: ASTM C 1475-00 Modified Analytical Procedure: GL-RAD-A-032 REV# 21 Analytical Batch: 1730045 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1730077 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203948281 Method Blank (MB) 1203948282 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) Page GEL16Laboratories of 26 u.c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
1203948283 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 441021001 (L2-SUB-WRS-ASGS-10A-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# 26 Analytical Batch: 1730046 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1730077 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203948284 Method Blank (MB) 1203948285 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) 1203948286 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on a "dry weight" basis. Data Summary: There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable. Product: Dry Weight Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1730077 Page GEL17Laboratories of 26 u.c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-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: 1730111 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1730077 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203948455 Method Blank (MB) 1203948456 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) 1203948457 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# 18 Analytical Batch: 1730218 Preparation Method: Dry Soil Prep Page GEL18Laboratories of 26 u.c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1730077 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203948718 Method Blank (MB) 1203948719 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) 1203948720 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# 19 Analytical Batch: 1730073 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1730077 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203948365 Method Blank (MB) 1203948366 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) 1203948367 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 441021002 (L2-SUB-WRS-AJGS-15A-SB) was recounted due to results more negative than the three sigma TPU. The second count is reported. Page GEL19Laboratories of 26 u.c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Product: Liquid Scint Pu241, Solid Analytical Method: DOE EML HASL-300, Pu-11-RC Modified Analytical Procedure: GL-RAD-A-035 REV# 19 Analytical Batch: 1730047 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1730077 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203948287 Method Blank (MB) 1203948288 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) 1203948289 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 441021002 (L2-SUB-WRS-AJGS-15A-SB) was recounted due to high MDC. The recount is reported. Sample 441021001 (L2-SUB-WRS-ASGS-10A-SB) was recounted for tracer yield only due to a detector error. The recount is reported. Product: Liquid Scint Ni63, Solid Analytical Method: DOE RESL Ni-1, Modified Analytical Procedure: GL-RAD-A-022 REV# 18 Analytical Batch: 1730183 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1730077 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification Page GEL20Laboratories of 26 u.c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203948612 Method Blank (MB) 1203948613 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) 1203948614 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 Tc99, Solid Analytical Method: DOE EML HASL-300, Tc-02-RC Modified Analytical Procedure: GL-RAD-A-059 REV# 5 Analytical Batch: 1730190 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203948629 Method Blank (MB) 1203948630 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) 1203948631 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: 1730202 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203948668 Method Blank (MB) 1203948669 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) Page GEL21Laboratories of 26 u.c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
1203948670 441021001(L2-SUB-WRS-ASGS-10A-SB) Matrix Spike (MS) 1203948671 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on an "as received" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Miscellaneous Information Additional Comments The matrix spike, 1203948670 (L2-SUB-WRS-ASGS-10A-SBMS), aliquot was reduced to conserve sample volume. Product: Liquid Scint C14, Solid Analytical Method: EPA EERF C-01 Modified Analytical Procedure: GL-RAD-A-003 REV# 15 Analytical Batch: 1730208 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203948683 Method Blank (MB) 1203948684 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) 1203948685 441021001(L2-SUB-WRS-ASGS-10A-SB) Matrix Spike (MS) 1203948686 Laboratory Control Sample (LCS) The samples in this SDG were analyzed on an "as received" basis. Data Summary: All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions. Miscellaneous Information Additional Comments The matrix spike, 1203948685 (L2-SUB-WRS-ASGS-10A-SBMS), aliquot was reduced to conserve sample volume. Product: Liquid Scint Fe55, Solid Page GEL22Laboratories of 26 u.c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Analytical Method: DOE RESL Fe-1, Modified Analytical Procedure: GL-RAD-A-040 REV# 13 Analytical Batch: 1734775 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 22 Preparation Batch: 1730077 The following samples were analyzed using the above methods and analytical procedure(s). GEL Sample ID# Client Sample Identification 441021001 L2-SUB-WRS-ASGS-10A-SB 441021002 L2-SUB-WRS-AJGS-15A-SB 1203960225 Method Blank (MB) 1203960226 441021001(L2-SUB-WRS-ASGS-10A-SB) Sample Duplicate (DUP) 1203960227 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 due to high relative percent difference/relative error ratio. The re-analysis is being 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 GEL23Laboratories of 26 u.c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.766.1178 www.gal.com
Page 24 of 26 Page'---'---"'.-~--' GEL Chain of Custody and Analytical Request GEL l...aboratoril'S, LLC Pmj<.,>ct#: 1_ AcU,.,JJt ,S,,te -- 2040 Savage Road GELQuote#:_,--_ _ _ _ _ _ _ _ __J **See www.gel.com for GEL's Sample Acceptance SOP** Charleston. SC 29407 COCNumbcri* SQ f ::lC-R-~GEL Work Order Number: I </C/J {)2,/ Phone: (843) 556-8171 PO Nurnher* Fax: (843) 766-1178 Client Name; i J!, Croi.se ~o iu+,: ~ "15 l'lmoc" {,,CJ'i? i;J'J'c'f_;2_51_ Sample Analysis Requested (5 ' (Fill in the number of comainers for each test) Proj<.,'Ct/SitcName* LftC SWK - Ge,,m u.n:: 5"1../ {oQ( .<J., k RC-0.& , ,;- Fax#:
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Mountain Chain of Custody Si_!naturcs Sample Shippi11g and Delivery Details Rdi11quishcd By iS1gncd) Dale Ti,nc Received by isigned) Dme /_~/:' GEL PM: l,_fl,jj_], 01-0;,.1 /lo O'i10 {~;;::- -d~ 5": Sf!! IDale Shipp~-<l: I 2 3 CL, f !l' 2 3
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*If Net Coun!1 > lCIO<pm"" ..,.,pie, not marked "radioactive", contact l],c Radiatiou Safety Group for further Smpecle<l Hai td ltd'011001lon Shl M* T Hazan!=?
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Damaged O<llUainer LHl:1118 oontolnor 01111,r (do<cribe) 1 sealed? ' Chain ~~tstOdy documents included
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Presermlcn Melhod: W"' ke Ja,Pacb Dry i<<> ~ Olhcr. 3 Samples ~uiring cold preservation witrun co k 6 dcl?. C)?* *o11 * ~ ,... tt!COl'd,d in Cel,!u* TEMP: /(11:C Daily chcl:k performed and passed on IR Temperature Device Serial#: i f.'.:1-- ! 7 4 temperanlre gun? / S,,.o,,d"')' 'l',mPffi""'- Devi<< Sotial #(If A.ppli<oble): Clme Appliool,Je, 5,.1, bn,ken D"""god conlain,r Looking contain,r Otb,r (dt:oc,ibo) I/
' Sample Jmtainers intact and sealed?
Samples iequiring chemical prcservation Somplo lD'* at1d Coouli= Affecu,d:
' at proper Pm If Yes, Are Encores or Soil Kits present? Yes_ No_ (If yes, take to VOA f=m)
Do VOA vials contain acid preservation? Yes . No_ NIA_ (If uoknoWII., select No) Do any sJmples require Volatile 'VQA vials free ofheadspa~? Yes No_N/A 7 Analysis?,' - Sample ID's and containers affected: I I ID', ll!ld 1o,;,s affcct,d; 8 Sample> ieceived within holding time? I Sample JO's on COC 11un,:h !D's on Srznple lD's ond coatainors affoctod: 9 oot11es1 i Sampl<, ID'* affected: Date & tibe on COC match date & time 10 on bonle~? Number Jr <:011tainers received match Samplo JD's affocted: 11 number i~dicated 011 COC? Att sam~le containers identiliable as 12 GEL nrotided? COC forip is properly signed in 13 rc 1l=uislicd/rcccived sections? Comments (U~ Co<ttirn,atioo Form if needed): I I PM (or PMA) ll'View; ! n i t i a l ~ D** 11:</Jf/ Page-1...or ..!.... I GL CHL SR 001 Rev 5 Page 25 of 26
List of current GEL Certifications as of 01 February 2018 State Certification Alaska UST0110 Arkansas 880651 CLIA 42D0904046 California 2940 Colorado SC00012 Connecticut PH0169 Delaware SC00012 DoD ELAP/ ISO17025 A2LA 2567.01 Florida NELAP E87156 Foreign Soils Permit P3301500283, P3301500253 Georgia SC00012 Georgia SDWA 967 Hawaii SC00012 Idaho Chemistry SC00012 Idaho Radiochemistry SC00012 Illinois NELAP 200029 Indiana CSC01 Kansas NELAP E10332 Kentucky SDWA 90129 Kentucky Wastewater 90129 Louisiana NELAP 03046 (AI33904) Louisiana SDWA LA180011 Maryland 270 Massachusetts MSC012 Michigan 9976 Mississippi SC00012 Nebraska NEOS2613 Nevada SC0001220181 New Hampshire NELAP 205415 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 Radchem 10120002 South Carolina Chemistry 10120001 Tennessee TN 02934 Texas NELAP T1047042351712 Utah NELAP SC00012201725 Vermont VT87156 Virginia NELAP 460202 Washington C780 West Virginia 997404 Page 26 of 26}}