ML20352A243
| ML20352A243 | |
| 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: ML20352A243 (73) | |
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LACROSSESOLUTIONS LA CROSSE BOILING WATER REACTOR FINAL STATUS SURVEY RELEASE RECORD STORM DRAIN 5 SURVEY UNIT S3-012-102 B REVISION 1
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS PREPARED BY / DATE:
lktc?-~- Robert F. Yetter III Oct 25 2020 I :57 PM R. F. Yetter III, FSS Specialist cosign REVIEWED BY / DATE:
~u, Mitchell Uz Oct 27 2020 8:04 AM cosign M. D. Uz, FSS Specialist Robert F. Yetter
~ 5. 'lJdwt Oct 27 2020 11 :10 AM REVIEWED BY / DATE: cosign R. Yetter, Director, Radiological Site Closure Sarah Roberts REVIEWED BY / DATE:
Saut4~~ Oct 27 2020 I :00 PM co~an S. Roberts, VP Radiological Programs
---~-- ~fi,/t._
~-~?-c.dft;:; ..
Scott G. Zoller Oct 29 2020 9:41 AM APPROVED BY / DATE: - ~-:--- _ _ (-! cosign S. Zoller, FSS Manager 1
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS TABLE OF CONTENTS
- 1. EXECUTIVE
SUMMARY
................................................................................................................................. 5
- 2. SURVEY UNIT DESCRIPTION ....................................................................................................................... 5
- 3. CLASSIFICATION BASIS ................................................................................................................................. 5
- 4. DATA QUALITY OBJECTIVES ...................................................................................................................... 6
- 5. SURVEY DESIGN ............................................................................................................................................... 9
- 6. SURVEY IMPLEMENTATION ...................................................................................................................... 12
- 7. SURVEY RESULTS .......................................................................................................................................... 13
- 8. QUALITY CONTROL ...................................................................................................................................... 15
- 9. INVESTIGATIONS AND RESULTS .............................................................................................................. 15
- 10. REMEDIATION AND RESULTS ................................................................................................................... 16
- 11. CHANGES FROM THE FINAL STATUS SURVEY PLAN ........................................................................ 16
- 12. DATA QUALITY ASSESSMENT ................................................................................................................... 16
- 13. ANOMALIES ..................................................................................................................................................... 17
- 14. CONCLUSION .................................................................................................................................................. 17
- 15. REFERENCES................................................................................................................................................... 17
- 16. ATTACHMENTS .............................................................................................................................................. 18 ATTACHMENT 1 FIGURES AND MAPS ............................................................................................................. 19 ATTACHMENT 2 MEASUREMENT DATA .......................................................................................................... 21 ATTACHMENT 3 SIGN TEST ............................................................................................................................... 24 ATTACHMENT 4 QUALITY CONTROL ASSESSMENT ...................................................................................... 26 ATTACHMENT 5 GRAPHICAL PRESENTATIONS ............................................................................................. 28 ATTACHMENT 6 SAMPLE ANALYTICAL REPORTS ......................................................................................... 32 ATTACHMENT 7 GEL LABORATORIES ANALYTICAL REPORTS ................................................................... 39 2
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS LIST OF TABLES Table 4 Dose Significant Radionuclides and Mixture for Buried Pipe ............................................................... 7 Table 4 Base Case DCGLs for Buried Pipe Group .............................................................................................. 8 Table 4 Operational DCGLs for Buried Pipe Group ........................................................................................... 9 Table 5-1 Soil/Buried Pipe Surrogate Ratio ............................................................................................................ 9 Table 5-2 Investigation Levels ................................................................................................................................ 11 Table 5-3 Synopsis of Survey Design...................................................................................................................... 12 Table 7 Summary of Systematic, Judgmental, and QC Measurements ........................................................... 14 Table 7 Basic Statistical Properties of the Systematic Measurement Population ............................................ 15 Table 16-1 Survey Unit S3-012-102 B Static Measurements Data Assessment .................................................. 22 Table 16-2 Survey Unit S3-012-102 B Sign Test ................................................................................................... 25 Table 16-3 Survey Unit S3-012-102 B QC Assessment ......................................................................................... 27 LIST OF FIGURES Figure 16-1 Survey Unit S3-012-102 B Drawing ................................................................................................... 20 Figure 16 Quantile Plot for Gross Gamma Activity .......................................................................................... 29 Figure 16 Histogram for Gross Gamma Activity ............................................................................................... 30 Figure 16 Retrospective Power Curve for Survey Unit S3-012-102 B .............................................................. 31 3
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable CWD Circulating Water Discharge CWI Circulating Water Intake DQO Data Quality Objective DCGL Derived Concentration Guideline Level DCGLBP Buried Pipe Base Case Derived Concentration Guideline Level FSS Final Status Survey HSA Historical Site Assessment IC Insignificant Contributors ID Internal Diameter LACBWR La Crosse Boiling Water Reactor LTP License Termination Plan MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MCNP Monte Carlo Neutral Particle MDC Minimum Detectable Concentration NaI Sodium Iodide NORM Naturally Occurring Radioactive Material OpDCGLBP Buried Pipe Operational Derived Concentration Guideline Level PVC PolyVinyl Chloride QAPP Quality Assurance Project Plan QC Quality Control ROC Radionuclides of Concern SOF Sum of Fractions TEDE Total Effective Dose Equivalent TSD Technical Support Document UCL Upper Confidence Limit 4
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS
- 1. EXECUTIVE
SUMMARY
This Final Status Survey (FSS) Release Record for survey unit S3-012-102 B, Storm Drain 5, 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 procedures LC-FS-PR-002, Final Status Survey Package Development (Reference 3) and LC-FS-PR-018, Radiation Surveys of Pipe Interiors Using Sodium/Cesium Iodide Detectors (Reference 4), the LACBWR LTP, and with guidance from NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) (Reference 5).
Survey unit S3-012-102 B has a MARSSIM classification of 3. A survey plan was designed based upon use of the Sign Test as the nonparametric statistical test for compliance. Both the Type I (a) and Type II ( ) decision error rates were set at 0.05. As a systematic measurement population, forty (40) static gamma measurements were acquired from the survey unit. The data assessment results for survey unit S3-012-102 B 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 0.3557 when applying the respective Operational Derived Concentration Guideline Levels (OpDCGLBP) for buried pipe. The mean SOF when applying the respective Base Case DCGLs (DCGLBP) is 0.0645. This SOF equates to a dose for the survey unit of 1.6121 mrem/yr.
- 2. SURVEY UNIT DESCRIPTION S3-012-102 B is an impacted Class 3 buried pipe survey unit. The survey unit consists of the interior surface of the Storm Drain 5 pipe, which is a 30 " Internal Diameter (ID) vitrified clay buried pipe that runs east-west underneath the northern portion of the Switchyard. The total length of pipe is approximately 400 feet (121.92 m). The total interior surface area of the pipe is 291.86 m2 (2,918,635 cm2). Refer to Attachment 1 of this report for a figure depicting survey unit S3-012-102 B.
- 3. CLASSIFICATION BASIS Based on the La Crosse Boiling Water Reactor Historical Site Assessment (HSA)
(Reference 6), the Storm Drain 5 pipe was identified as a Class 3 system.
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS Based upon review of the historical information and completion of a final Survey Unit Classification Worksheet from LC-FS-PR-006, Survey Unit Classification (Reference 7),
the correct final classification of survey unit S3-012-102 B was determined to be Class 3.
- 4. DATA QUALITY OBJECTIVES FSS planning and design relies on a properly executed Data Quality Objective (DQO) process to ensure, through compliance with explicitly defined inputs and boundaries, that the primary objective of the survey is satisfied. The DQO process is described in the LACBWR LTP in accordance with MARSSIM. The appropriate design for a given survey was developed using the DQO process as outlined in Appendix D of MARSSIM.
The DQO process incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis. Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition. The baseline condition is technically known as the null hypothesis. Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection. In designing the survey plan, the underlying assumption, or null hypothesis was that residual activity in the survey unit exceeded the release criteria. Rejection of the null hypothesis would indicate that residual activity within the survey unit does not exceed the 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 S3-012-102 B 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 Technical Support Document (TSD) RS-TD-313196-001, Radionuclides of Concern during LACBWR Decommissioning (Reference 8) established the basis for an initial suite of potential ROC for decommissioning. Insignificant contributors (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 9). 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 are eliminated from further detailed evaluation. Therefore, the final ROCs for LACBWR soil, basement concrete, and buried piping are Cs-137, Co-60, Sr-90, Eu-152 and Eu-154.
LTP, 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 6
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS ROC for the decommissioning of buried pipe at LACBWR and the normalized mixture fractions based on the radionuclide mixture.
Table 4 Dose Significant Radionuclides and Mixture for Buried Pipe 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 (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 (i.e., calculation of surrogate DCGLs and 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 10).
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 DCGL W.
The DCGLW can be multiplied by Area Factors to obtain a Base Case DCGL that represents the same dose to an individual for residual radioactivity over a smaller area within a survey unit.
At LACBWR, compliance is demonstrated through the summation of dose from five (5) distinct source terms for the end state (basements, soils, buried pipe, above-ground structures, and groundwater). When applied to buried pipe, the DCGLs are expressed in units of activity per surface area (dpm/100 cm 2).
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS Buried piping is defined as below ground pipe located outside of structures and basements.
The dose assessment methods and resulting DCGLs for buried piping are described in detail in LTP, Section 6.20. The buried piping was separated into two categories. The first category included the summation and grouping of all impacted buried pipe other than the Circulating Water Discharge (CWD) Pipe and is designated as the "Buried Pipe Group ."
The second category consisted of the CWD Pipe only. The separation of the CWD pipe was necessary because the geometry was significantly different than the other pipes, and the pipes are located in distinctly different parts of the site.
EnergySolutions TSD RS-TD-313196-004, LACBWR Soil DCGL, Basement Concrete DCGL, and Buried Pipe DCGL (Reference 11) and LTP, Section 6.20, provide the exposure scenarios and modeling parameters that were used to calculate the site-specific buried pipe DCGLs. The final DCGLs used during FSS account for the fact that the dose from the In Situ and Excavation scenarios must be summed in the conceptual model for buried pipe dose assessment (i.e., the In Situ and Excavation scenarios occur in parallel). The summed Buried Pipe Base Case DCGLs are reproduced in Table 4-2 below. The IC dose percentages for each of the buried pipe scenarios were used to adjust each buried pipe Base Case DCGL to account for the dose from the eliminated IC radionuclides. The Operational DCGLs for the Storm Drain 5 pipe are provided in Table 4-3.
Table 4 Base Case DCGLs for Buried Pipe Group DCGLBP Radionuclide (dpm/100 cm2)
Co-60 7.50E+04 Sr-90 5.16E+05 Cs-137 3.18E+05 Eu-152 1.64E+05 Eu-154 1.52E+05 8
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS Table 4 Operational DCGLs for Buried Pipe Group OpDCGLBP Radionuclide (dpm/100 cm2)
Co-60 1.57E+04 Sr-90 1.08E+05 Cs-137 6.68E+04 Eu-152 3.44E+04 Eu-154 3.20E+04 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.
In accordance with the LTP, the minimum acceptable MDC for measurements obtained using field instruments was 50% of the applicable Operational DCGL.
- 5. SURVEY DESIGN The level of effort associated with planning a survey is based on the complexity of the survey unit and nature of the hazards. Guidance for preparing FSS plans is provided in procedure LC-FS-PR-002, Final Status Survey Package Development.
The DQO process validated that Co-60, Sr-90, Cs-137, Eu-152, and Eu-154 would be the ROC in survey unit S3-012-102 B 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/buried pipe is given in Table 5-1.
Table 5-1 Soil/Buried Pipe Surrogate Ratio Radionuclides Ratio Sr-90/Cs-137 0.502 The equation for calculating a surrogate DCGL is as follows:
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS Equation 1 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3 ... n = DCGL for radionuclides to be represented by the surrogate Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide "n" to surrogate radionuclide Using the Operational DCGLs presented in Table 4-3 and the ratio from Table 5-1, the following surrogate calculation was performed:
Equation 2 1
Surrogatevcci (cs-137) = [( 1 ) ( o 502 )]
6.68£ + 04(cs-l37) + 1.08£ + 0S(sr-90)
= 5.l0E + 04 dpm/100 cm 2 The surrogate Operational DCGL for Cs-137 is then used in the calculation of the gross gamma Operational DCGL, as calculated in Equation 3.
Equation 3 SurrogatevcGL (gamma) 1
[( 0.071 ) +( 0.919 ) +( 0.006 ) +( 0.003 )]
1.57£ + 04(co-60) 5.10£ + 04cs-137 3.44£ + 04(Eu-152) 3.20£ + 04(Eu-154)
= 4.37E + 04 dpm/100 cm 2 The action level for survey unit S3-012-102 B was equivalent to the calculated gross gamma Operational DCGL of 4.37E+04 dpm/100 cm 2.
For the survey of interior pipe surfaces, areal coverage is achieved by the "area of detection" for each static measurement collected. Scanning, in the traditional context, is not applicable to the survey of pipe internal surfaces. For the survey of Storm Drain 5, the detector was erroneously calibrated for a specific geometry of a 3,050 cm2 (1 ft x 1 m) area of contamination on the bottom of the pipe, resulting in inaccurate detector efficiencies and inaccurate calculations for activity per area. TSD LC-FS-TSD-005, MCNP Modeling of Water Discharge Pipes for the LaCrosse Boiling Water Reactor (Reference 12) was written 10
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS to address the discrepancy in efficiency and area of detection. The TSD details the Monte Carlo Neutral Particle (MCNP) radiation transport code that modeled the response of a NaI detector to a calibration source for several different pipe sizes. The MCNP models resulted in efficiency correction factors. The calculated efficiency from original source calibration can be multiplied by the correction factors to obtain an efficiency that more realistically portrays the specific contamination geometry of the pipe. For a 30 " ID pipe, each measurement has a true Field-of-View (FOV) of 7,297 cm 2.
The Storm Drain 5 pipe contains 400 feet of 30"ID vitrified clay piping, which equates to a surface area of 291.86 m2 (2,918,635 cm2). For survey unit S3-012-102 B, 10% survey coverage was selected. Therefore, a total of at least forty (40) distinct measurements over the entire accessible pathway of the piping system were required.
Each static measurement represents the gamma activity in gross counts per minute (cpm) for each specific measurement location. Background is subtracted, then the value is converted to dpm using an efficiency factor based on the calibration source and the efficiency correction factors detailed in TSD LC-FS-TSD-005, MCNP Modeling of Water Discharge Pipes for the LaCrosse Boiling Water Reactor. The total activity in dpm is then adjusted for the assumed effective surface area commensurate with the pipe diameter, resulting in units of dpm/100 cm2. The total gamma surface activity for each measurement was converted to an activity concentration for each gamma-emitting ROC, based on the normalized gamma mixture from Table 4-1. Concentrations for the HTD ROC Sr-90 were inferred using the surrogate approach in accordance with LTP Chapter 5.
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 13) includes the collection of replicate static measurements on 5% of the systematic measurements collected in the survey unit, with the locations selected at random. Three (3) replicate static measurements were selected for Quality Control (QC) analysis for the FSS of this survey unit.
For this Class 3 buried pipe survey unit, the "Investigation Levels" for measurement results are those levels specified in LTP Chapter 5, Table 5-16, and are reproduced below in Table 5-2.
Table 5-2 Investigation Levels Direct Investigation Classification Scan Investigation Levels Levels
>Operational DCGL or >MDC scan if Class 3 MDCscan is greater than Operational >0.5 Operational DCGL DCGL Table 5-3 provides a synopsis of the survey design for survey unit S3-012-102 B.
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS Table 5-3 Synopsis of Survey Design Feature Design Criteria Basis Survey Unit Surface 400 feet of 30"ID vitrified 291.86 m2 (2,918,635 cm2)
Area clay pipe Number of Systematic 40 10% coverage Measurements (N)
- Co-60: 1.57E+04
- Sr-90: 1.08E+05 Operational DCGLs for Operational DCGLs buried pipe,
- Cs-137: 6.68E+04 (dpm/100 cm2) LTP, Table 5-8, Release
- Eu-152: 3.44E+04 Record, Table 4-3
- Eu-154: 3.20E+04 4.37E+04 dpm/100 cm2 Gross Gamma Operational Action Level DCGL, Equation 3 Investigation Level >0.5 Operational DCGL LTP, Table 5-16 Scan Areal Coverage N/A LTP, Section 5.7.1.8 QC 3 replicate measurements LTP, Section 5.9 Judgmental 1 Per sample plan Measurements Non-parametric Sign Test LTP, Section 5.6.4.2 Statistical Test
- 6. SURVEY IMPLEMENTATION 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. The survey unit was inspected and controlled in accordance with LC-FS-PR-010, Isolation and Control for Final Status Survey (Reference 14). 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 24, 2019.
FSS field activities were projected to take four (4) working days to complete. Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job. The survey-required field activities were performed during normal working hours and concluded on September 25, 2019.
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS Daily, prior to and following use, each detector was subjected to an Operational Response Check in accordance with procedure LC-FS-PR-018, Radiation Surveys of Pipe Interiors Using Sodium/Cesium Iodide Detectors. The Daily Operational Response Check compared the background response and the response to check source ranges established for normal background and detector source response to ensure that the detector was working properly.
The forty (40) systematic 1-minute static measurements were collected using a Ludlum Model 2350-1 paired with a Model 44-10 NaI detector operated in the rate-meter mode and using audio response. The detector was fitted into a wheeled rig, which maintained a fixed detector geometry, an area of detection of 7,297 cm2. The static MDC was sufficient to detect residual radioactivity at the action level (adjusted gross gamma Operational DCGL of 4.37E+04 dpm/100 cm2). Complete measurement results are provided in Attachment 2.
One (1) judgmental static measurement was collected during implementation of FSS, in accordance with the sample plan.
The implementation of survey specific QC measures included the collection of three (3) replicate static measurements for QC analysis.
- 7. SURVEY RESULTS 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 Ci + C2 +. ........... Cn ::;; l DCGLi DCGL2 DCGLn Where: Cn = concentration of radionuclide n DCGLn = DCGL of radionuclide n.
The application of the unity rule serves to normalize the data to allow for an accurate comparison of the various data measurements to the release criteria. When the unity rule is applied, the DCGLW (used for the nonparametric statistical test) becomes one (1). The DCGLBP are directly analogous to the DCGLW as defined in MARSSIM. The use and application of the unity rule was performed in accordance with section 4.3.3 of MARSSIM.
As described in LTP, Section 5.10.3.2, the Sign Test was used to evaluate the measured residual radioactivity against the dose criterion. The SOF for each measurement was used as the sum value for the Sign Test. The Sign Test then demonstrated that the mean activity 13
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS for each ROC was less than the OpDCGLBP at a Type I decision error of 0.05. The results of the Sign Test are presented in Attachment 3.
For buried pipe, areas of elevated activity were defined as any area identified by measurement (systematic or judgmental) that exceeded the OpDCGLBP but was less than the DCGLBP. The SOF (based on the OpDCGLB) for a systematic or judgmental measurement can exceed one (1) without remediation as long as the survey unit passes the Sign Test, and the mean SOF (based on the OpDCGLBP) for the survey unit does not exceed one (1). Once the survey data set passes the Sign Test (using Operational DCGLs), then the mean radionuclide activity for each ROC from systematic measurements along with any identified elevated areas from systematic and judgmental samples can be used with the Base Case DCGLs to perform a mean SOFBP calculation. The dose from residual radioactivity assigned to the FSS unit is the mean SOFBP multiplied by 25 mrem/yr.
The systematic measurement population consisted of forty (40) static measurements that were acquired using the Ludlum Model 2350-1 paired to a Model 44-10 detector. In total, forty-four (44) static measurements were collected, including the systematic, judgmental, and QC measurements. A breakdown of the total static measurements and SOF for systematic measurements compared to the OpDCGLBP is provided in Table 7-1. A summary of the results of the systematic measurements taken for non-parametric statistical testing when compared to the DCGLBP is provided in Table 7-2. The complete results of the data assessment for survey unit S3-012-102 B are provided in Attachment 2.
Table 7 Summary of Systematic, Judgmental, and QC Measurements Number of Systematic Measurements 40 Number of Judgmental Measurements 1 Number of Quality Control Measurements 3 Total Number of Measurements 44 Mean Systematic Measurement SOF (1) 0.3059 Max Individual Systematic Measurement SOF (1) 0.3557 Number of Systematic Measurements with SOF > 1 (1) 0 Number of Judgmental Measurements with SOF > 1 (1) 0 (1) Based on the OpDCGL BP 14
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS Table 7 Basic Statistical Properties of the Systematic Measurement Population Mean Median Max. Min. St. Dev. BcDCGL Avg. Dose Avg. SOF ROC (dpm/100 (dpm/100 (dpm/100 (dpm/100 (dpm/100 (dpm/100 per ROC per ROC cm2) cm2) cm2) cm2) cm2) cm2) (mrem/yr)
Co-60 9.60E+02 9.55E+02 1.11E+03 8.12E+02 7.77E+01 7.50E+04 0.0128 0.3201 Cs-137 1.24E+04 1.23E+04 1.43E+04 1.04E+04 1.00E+03 3.18E+05 0.0389 0.9719 Eu-152 8.19E+01 8.14E+01 9.47E+01 6.92E+01 6.62E+00 1.64E+05 0.0005 0.0125 Eu-154 4.19E+01 4.17E+01 4.85E+01 3.54E+01 3.39E+00 1.52E+05 0.0003 0.0069 Sr-90 6.21E+03 6.17E+03 7.18E+03 5.25E+03 5.02E+02 5.16E+05 0.0120 0.3007 SUM 0.0645 1.6121 The mean SOF for the Storm Drain 5 pipe, based on the mean concentration for each ROC as measured by the systematic measurement population when compared against the DCGLBP, is 0.0645. This SOF equates to a dose rate of 1.6121 mrem/yr.
- 8. QUALITY CONTROL The implementation of survey specific QC measures included the collection of three (3) replicate static measurements for QC analysis. The acceptance criteria for replicate static measurements is that the same conclusion is reached for each measurement. This is defined as the replicate measurement being within 20% of the standard measurement. In cases where the replicate measurement is not within 20% of the standard measurement, but both measurements are below the Operational DCGL, there is an acceptable agreement. All three (3) QC replicate measurement fell within the 20% criteria, and there is an acceptable agreement between standard and replicate results. Refer to Attachment 4 for QC analysis results.
- 9. INVESTIGATIONS AND RESULTS No investigations were performed during the performance or analyses of the survey.
However, the readings from this particular pipe made of vitrified clay, as compared to other buried pipe of different material, were much higher. To verify the higher readings, which were postulated to be caused by Naturally Occurring Radioactive Material (NORM), pieces of the pipe were collected and analyzed by the on-site gamma spectroscopy system. No plant-related radionuclides were identified above their MDCs; however, concentrations of K-40, Bi-214, Pb-214, and Pa-228 were identified greater than their respective MDCs. The report for the on-site analysis of the vitrified clay sample is provided in Attachment 6. A sample of the vitrified clay pieces was also sent off-site to GEL Laboratories for the analysis of the full suite of radionuclides. No radionuclides were positively identified in the off-site analysis of the vitrified clay pipe sample. The IC dose calculated for the sample is 0.0810 15
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS mrem/yr; therefore, no DCGL adjustment is warranted. The GEL Laboratories report for the full-suite radionuclide analysis of the vitrified clay sample is provided in Attachment 7.
- 10. REMEDIATION AND RESULTS No radiological remedial action as described by MARSSIM Section 5.4 was performed in this survey unit. 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 buried pipe was ALARA.
- 11. CHANGES FROM THE FINAL STATUS SURVEY PLAN TSD LC-FS-TSD-005, MCNP Modeling of Water Discharge Pipes for the LaCrosse Boiling Water Reactor, was developed in response to the inaccurate efficiency calibration geometry originally assumed in the sample plan and during survey implementation.
The material of Storm Drain 5 was originally thought to be concrete. During FSS, though, it was found that the actual material of the pipe was vitrified clay. The different material than that stated in the sample plan did not affect any survey measurement.
The accessible portion of the storm drain was approximately 100 feet due to the level of the Mississippi River. The original plan was to take a measurement every 10 feet of the 400 foot pipe. The measurement distance was reduced to every 2.5 feet of the accessible 100 feet of piping to retain the 40 measurements designated in the plan. The 100 feet that was accessible was the portion of the pipe leading from the storm drain entrance. This section of the pipe is the most likely portion to be contaminated as there is no other drain entrance for the pipe.
- 12. DATA QUALITY ASSESSMENT The DQO survey design and data were reviewed in accordance with LC-FS-PR-008, Final Status Survey Data Assessment (Reference 15) for completeness and consistency.
Documentation was complete and legible. Surveys were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 3. The survey design had adequate power as indicated by the Retrospective Power Curve (see Attachment 5).
All measurements were less than a SOF of one (1) when compared to the OpDCGLBP.
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.
16
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS The preliminary data review consisted of calculating basic statistical quantities (e.g., mean, median, standard deviation). All data was considered valid including negative values, zeros, values reported below the MDC, and values with uncertainties that exceeded two standard deviations. The mean and median values for each ROC were well below the respective Operational DCGLs. Also, the retrospective power curve shows that a sufficient number of measurements were collected to achieve the desired power. Therefore, the survey unit meets the unrestricted release criteria with adequate power as required by the DQOs.
- 13. ANOMALIES No anomalies were observed during the performance or analyses of the survey.
- 14. CONCLUSION Survey unit S3-012-102 B has met the DQOs of the FSS plan. The ALARA criteria as specified in Chapter 4 of the LTP were achieved.
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 3. Therefore, in accordance with LTP Section 5.11, the survey unit meets the release criteria.
The dose contribution from survey unit S3-012-102 B is 1.6121 mrem/yr TEDE, based on the average concentration of the ROC in measurements used for non-parametric statistical testing (mean SOF).
Survey unit S3-012-102 B 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. LC-FS-PR-018, Radiation Surveys of Pipe Interiors Using Sodium/Cesium Iodide Detectors
- 5. NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual
- 6. La Crosse Boiling Water Reactor Historical Site Assessment
- 7. LC-FS-PR-006, Survey Unit Classification
- 8. RS-TD-313196-001, Radionuclides of Concern during LACBWR Decommissioning
- 9. NUREG-1757, Volume 2, Revision 1, Consolidated Decommissioning Guidance Characterization, Survey, and Determination of Radiological Criteria, Final Report 17
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS
- 10. LC-FS-TSD-002, Operational Derived Concentration Guideline Levels for Final Status Survey DCGL
- 11. RS-TD-313196-004, LACBWR Soil DCGL, Basement Concrete DCGL, and Buried Pipe
- 12. LC-FS-TSD-005, MCNP Modeling of Water Discharge Pipes for the LaCrosse Boiling Water Reactor
- 13. LC-QA-PN-001, Final Status Survey Quality Assurance Project Plan
- 14. LC-FS-PR-010, Isolation and Control for Final Status Survey
- 15. LC-FS-PR-008, Final Status Survey Data Assessment
- 16. ATTACHMENTS Attachment 1 Figures and Maps Attachment 2 Measurement Data Attachment 3 Sign Test Attachment 4 Quality Control Assessment Attachment 5 Graphical Presentations Attachment 6 Sample Analytical Reports Attachment 7 GEL Laboratories Analytical Reports 18
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS ATTACHMENT 1 FIGURES AND MAPS 19
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SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS Figure 16-1 Survey Unit S3-012-102 B Drawing Legend D Buildings Storm Drain Pipes Other Piping 20
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS ATTACHMENT 2 MEASUREMENT DATA 21
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSE SOLUTIONS Table 16-1 Survey Unit S3-012-102 B Static Measurements Data Assessment Gamma Result Activity1 (dpm/100 cm2) Fraction of OpDCGL Measurement Measurement Measurement ID Population 2 OpSOF dpm/100 cm Co-60 Cs-137 Eu-152 Eu-154 Sr-90 Co-60 Cs-137 Eu-152 Eu-154 Sr-90 S 1 11188 7.99E+02 1.03E+04 6.81E+01 3.49E+01 5.16E+03 0.0509 0.1540 0.0020 0.0011 0.0478 0.2557 S 2 13002 9.29E+02 1.20E+04 7.92E+01 4.05E+01 6.00E+03 0.0591 0.1790 0.0023 0.0013 0.0556 0.2972 S 3 12479 8.91E+02 1.15E+04 7.60E+01 3.89E+01 5.76E+03 0.0568 0.1717 0.0022 0.0012 0.0533 0.2853 S 4 14297 1.02E+03 1.31E+04 8.70E+01 4.46E+01 6.60E+03 0.0650 0.1968 0.0025 0.0014 0.0611 0.3268 S 5 14468 1.03E+03 1.33E+04 8.81E+01 4.51E+01 6.68E+03 0.0658 0.1991 0.0026 0.0014 0.0618 0.3307 S 6 13312 9.51E+02 1.22E+04 8.11E+01 4.15E+01 6.14E+03 0.0606 0.1832 0.0024 0.0013 0.0569 0.3043 S 7 13791 9.85E+02 1.27E+04 8.40E+01 4.30E+01 6.36E+03 0.0627 0.1898 0.0024 0.0013 0.0589 0.3153 S 8 14119 1.01E+03 1.30E+04 8.60E+01 4.40E+01 6.52E+03 0.0642 0.1943 0.0025 0.0014 0.0603 0.3228 S 9 15561 1.11E+03 1.43E+04 9.47E+01 4.85E+01 7.18E+03 0.0708 0.2142 0.0028 0.0015 0.0665 0.3557 S 10 15416 1.10E+03 1.42E+04 9.39E+01 4.80E+01 7.12E+03 0.0701 0.2122 0.0027 0.0015 0.0659 0.3524 S 11 14625 1.04E+03 1.34E+04 8.90E+01 4.56E+01 6.75E+03 0.0665 0.2013 0.0026 0.0014 0.0625 0.3343 S 12 13385 9.56E+02 1.23E+04 8.15E+01 4.17E+01 6.18E+03 0.0609 0.1842 0.0024 0.0013 0.0572 0.3060 S 13 13821 9.87E+02 1.27E+04 8.42E+01 4.31E+01 6.38E+03 0.0629 0.1902 0.0024 0.0013 0.0591 0.3160 S 14 14528 1.04E+03 1.34E+04 8.85E+01 4.53E+01 6.71E+03 0.0661 0.2000 0.0026 0.0014 0.0621 0.3321 S 15 13138 9.38E+02 1.21E+04 8.00E+01 4.09E+01 6.06E+03 0.0598 0.1808 0.0023 0.0013 0.0561 0.3003 S 16 13917 9.94E+02 1.28E+04 8.47E+01 4.34E+01 6.42E+03 0.0633 0.1915 0.0025 0.0014 0.0595 0.3182 S 17 12930 9.23E+02 1.19E+04 7.87E+01 4.03E+01 5.97E+03 0.0588 0.1780 0.0023 0.0013 0.0553 0.2956 S 18 12915 9.22E+02 1.19E+04 7.86E+01 4.02E+01 5.96E+03 0.0588 0.1778 0.0023 0.0013 0.0552 0.2952 S 19 13219 9.44E+02 1.22E+04 8.05E+01 4.12E+01 6.10E+03 0.0601 0.1819 0.0023 0.0013 0.0565 0.3022 S 20 14516 1.04E+03 1.33E+04 8.84E+01 4.52E+01 6.70E+03 0.0660 0.1998 0.0026 0.0014 0.0620 0.3318 S 21 14986 1.07E+03 1.38E+04 9.12E+01 4.67E+01 6.92E+03 0.0682 0.2063 0.0027 0.0015 0.0640 0.3426 S 22 13367 9.55E+02 1.23E+04 8.14E+01 4.17E+01 6.17E+03 0.0608 0.1840 0.0024 0.0013 0.0571 0.3056 S 23 14992 1.07E+03 1.38E+04 9.13E+01 4.67E+01 6.92E+03 0.0682 0.2063 0.0027 0.0015 0.0641 0.3427 S 24 13346 9.53E+02 1.23E+04 8.13E+01 4.16E+01 6.16E+03 0.0607 0.1837 0.0024 0.0013 0.0570 0.3051 22
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SURVEY UNIT S3-012-102 B LACROSSE SOLUTIONS Gamma Result Activity1 (dpm/100 cm2) Fraction of OpDCGL Measurement Measurement Measurement ID Population OpSOF dpm/100 cm2 Co-60 Cs-137 Eu-152 Eu-154 Sr-90 Co-60 Cs-137 Eu-152 Eu-154 Sr-90 S 25 11654 8.32E+02 1.07E+04 7.10E+01 3.63E+01 5.38E+03 0.0530 0.1604 0.0021 0.0011 0.0498 0.2664 S 26 13105 9.36E+02 1.20E+04 7.98E+01 4.08E+01 6.05E+03 0.0596 0.1804 0.0023 0.0013 0.0560 0.2996 S 27 14194 1.01E+03 1.30E+04 8.64E+01 4.42E+01 6.55E+03 0.0646 0.1954 0.0025 0.0014 0.0607 0.3245 S 28 13415 9.58E+02 1.23E+04 8.17E+01 4.18E+01 6.19E+03 0.0610 0.1846 0.0024 0.0013 0.0573 0.3067 S 29 13875 9.91E+02 1.28E+04 8.45E+01 4.32E+01 6.40E+03 0.0631 0.1910 0.0025 0.0014 0.0593 0.3172 S 30 12482 8.91E+02 1.15E+04 7.60E+01 3.89E+01 5.76E+03 0.0568 0.1718 0.0022 0.0012 0.0533 0.2853 S 31 12512 8.94E+02 1.15E+04 7.62E+01 3.90E+01 5.77E+03 0.0569 0.1722 0.0022 0.0012 0.0535 0.2860 S 32 12566 8.97E+02 1.16E+04 7.65E+01 3.92E+01 5.80E+03 0.0572 0.1729 0.0022 0.0012 0.0537 0.2873 S 33 13659 9.76E+02 1.26E+04 8.32E+01 4.26E+01 6.30E+03 0.0621 0.1880 0.0024 0.0013 0.0584 0.3122 S 34 14685 1.05E+03 1.35E+04 8.94E+01 4.58E+01 6.78E+03 0.0668 0.2021 0.0026 0.0014 0.0628 0.3357 S 35 12262 8.76E+02 1.13E+04 7.47E+01 3.82E+01 5.66E+03 0.0558 0.1688 0.0022 0.0012 0.0524 0.2803 S 36 11871 8.48E+02 1.09E+04 7.23E+01 3.70E+01 5.48E+03 0.0540 0.1634 0.0021 0.0012 0.0507 0.2714 S 37 12106 8.65E+02 1.11E+04 7.37E+01 3.77E+01 5.59E+03 0.0551 0.1666 0.0021 0.0012 0.0517 0.2767 S 38 11365 8.12E+02 1.04E+04 6.92E+01 3.54E+01 5.25E+03 0.0517 0.1564 0.0020 0.0011 0.0486 0.2598 S 39 12530 8.95E+02 1.15E+04 7.63E+01 3.90E+01 5.78E+03 0.0570 0.1725 0.0022 0.0012 0.0535 0.2864 S 40 11582 8.27E+02 1.06E+04 7.05E+01 3.61E+01 5.35E+03 0.0527 0.1594 0.0020 0.0011 0.0495 0.2648 J 41 J 13337 9.53E+02 1.23E+04 8.12E+01 4.16E+01 6.16E+03 0.0607 0.1836 0.0024 0.0013 0.0570 0.3049 Q 13 QC 15360 1.10E+03 1.41E+04 9.35E+01 4.79E+01 7.09E+03 0.0699 0.2114 0.0027 0.0015 0.0656 0.3511 Q 24 QC 13606 9.72E+02 1.25E+04 8.28E+01 4.24E+01 6.28E+03 0.0619 0.1873 0.0024 0.0013 0.0581 0.3110 Q 7 QC 14553 1.04E+03 1.34E+04 8.86E+01 4.54E+01 6.72E+03 0.0662 0.2003 0.0026 0.0014 0.0622 0.3327 (1) Sr-90 activity inferred from Cs-137.
23
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS ATTACHMENT 3 SIGN TEST 24
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SURVEY UNIT S3-012-102 B LACROSSE SOLUTIONS Table 16-2 Survey Unit S3-012-102 B Sign Test SOF
- 1-Ws Sign (Ws) 1 0.2557 0.74 +1 2 0.2972 0.70 +1 3 0.2853 0.71 +1 4 0.3268 0.67 +1 5 0.3307 0.67 +1 6 0.3043 0.70 +1 7 0.3153 0.68 +1 8 0.3228 0.68 +1 9 0.3557 0.64 +1 10 0.3524 0.65 +1 11 0.3343 0.67 +1 12 0.3060 0.69 +1 13 0.3160 0.68 +1 14 0.3321 0.67 +1 15 0.3003 0.70 +1 16 0.3182 0.68 +1 17 0.2956 0.70 +1 18 0.2952 0.70 +1 19 0.3022 0.70 +1 20 0.3318 0.67 +1 21 0.3426 0.66 +1 22 0.3056 0.69 +1 23 0.3427 0.66 +1 24 0.3051 0.69 +1 25 0.2664 0.73 +1 26 0.2996 0.70 +1 27 0.3245 0.68 +1 28 0.3067 0.69 +1 29 0.3172 0.68 +1 30 0.2853 0.71 +1 31 0.2860 0.71 +1 32 0.2873 0.71 +1 33 0.3122 0.69 +1 34 0.3357 0.66 +1 35 0.2803 0.72 +1 36 0.2714 0.73 +1 37 0.2767 0.72 +1 38 0.2598 0.74 +1 39 0.2864 0.71 +1 40 0.2648 0.74 +1 Number of positive differences (S+) 33 Critical Value 21 Survey Unit Meets the Acceptance Criteria 25
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS ATTACHMENT 4 QUALITY CONTROL ASSESSMENT 26
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 SURVEY UNIT S3-012-102 B Table 16-3 Survey Unit S3-012-102 B QC Assessment Activity Activity Acceptable
+20% -20%
ID Value ID Value (YIN) 7 13791 16549 11033 7Q 14553 y 13 13821 16585 11057 13Q 15360 y 24 13346 16015 10676 24Q 13606 y Comments/Corrective Actions: The replicate measurement results are in acceptable The acceptance criteria for replicate static measurements and is that the agreement same conclusion is reached for each measurement. This is defined as the replicate measurement being within 20% of the standard measurement. In cases where the replicate measurement is not within 20% of the standard measurement, but both measurements are below the Operational DCGL, there is an acceptable agreement.
27
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS ATTACHMENT 5 GRAPHICAL PRESENTATIONS 28
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS Figure 16 Quantile Plot for Gross Gamma Activity 1.80E+04 1.60E+04 1.40E+04 1.20E+04 1.00E+04 8.00E+03 6.00E+03 4.00E+03 2.00E+03 0.00E+00 0.00% 10.00% 20.00% 30.00% 40.00% 50.00% 60.00% 70.00% 80.00% 90.00% 100.00%
PERCENTAGE 29
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS Figure 16 Histogram for Gross Gamma Activity 30 25 20 15 10 5
0 2.59E+03 5.19E+03 7.78E+03 1.04E+04 1.30E+04 1.56E+04 UPPER END VALUE (DPM/100CM2) 30
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS Figure 16 Retrospective Power Curve for Survey Unit S3-012-102 B Prob bility th t th 1.0 I
0.8 0.6 0.4 0.2 I 0.0 I 10% 3D% 5)% "'0% 9)% 1)0% 110% 130% l510%
Tru u nit on ent
- tion (p I cent of D *, :I.)
31
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS ATTACHMENT 6 SAMPLE ANALYTICAL REPORTS 32
9/11/2019 2:10:07PM Page 1 of6
~ Apex-Gamma Analysis Report for SD 5 30" CLAY PIPE (PIECES)
SD 5 30" CLAY PIPE GAMMA SPECTRUM ANALYSIS Sample Identification : SD 5 30" CLAY PIPE (PIECES)
Sample Description : SD 5 30" CLAY PIPE Sample Type : 500 ml Marinelli Unit Sample Point Sample Size 6.067E+02 grams Facility : Dairyland_NPP Sample Taken On : 9/11/2019 1:15:00PM Acquisition Started : 9/11/2019 1:54:52PM Procedure : 500ml Marinelli Operator : Administrator Detector Name : HOTLAB Geometry : 500ml Marinelli Live Time : 900.0 seconds Real Time : 903.0 seconds Dead Time : 0.33%
Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 100-4096 Peak Area Range (in channels) : 100 - 4096 Identification Energy Tolerance : 1.000 keV Energy Calibration Used Done On : 7/8/2014 Efficiency Calibration Used Done On : 7/8/2014 Efficiency Calibration Description Sample Number : 7437 PEAK ANALYSIS REPORT Peak Analysis Performed on : 9/11/2019 2:09:58PM Peak Analysis From Channel : 100 Peak Analysis To Channel : 4096
9/11/2019 2:10:07PM Page 2 of6 Analysis Report for SD 5 30" CLAY PIPE (PIECES)
SD 5 30" CLAY PIPE Peak Energy ROI ROI Peak Net Peak Net Area Continuum FWHM No. (keV) start end Centroid Area Uncertainty Counts (keV)
F 1 76.22 147 - 159 152.99 3.38E+02 56.19 7.56E+02 3.12 F 2 129.17 254 - 265 258.86 7.86E+0l 32.37 4.19E+02 2.01 F 3 185.94 366 - 376 372. 37 1.16E+02 32. 13 3.30E+02 1. 78 F 4 238.58 471- 485 477.64 3.77E+02 45.61 4 . 55E+02 1.33 F 5 295 .11 582 - 595 590.67 1.81E+02 32.45 2.31E+02 1. 58 F 6 338.23 670 - 684 67 6. 8 9 9.72E+0l 25.33 1.66E+02 2.08 F 7 351.85 700 - 711 704.14 2.69E+02 36. 91 1.93E+02 1. 31 F 8 510.51 1016 - 1026 1021.39 5.41E+0l 17.99 7.19E+0l 1. 43 F 9 583.13 1159 - 1173 1166.60 1. 29E+02 24.92 8.31E+0l 1.55 F 10 609.19 1212 - 1225 1218.71 2.02E+02 30.87 9.32E+0l 1. 76 F 11 727. 07 1451 - 1459 1454.44 3.04E+0l 13. 75 4.40E+0l 1.27 F 12 911.12 1816 - 1828 1822.48 7.81E+0l 19.28 3.90E+0l 1. 60 F 13 969 . 06 1934 - 1945 1938.34 3 .7 0E+0l 16.02 6.52E+0l 1. 68 F 14 1120. 35 2236 - 22 47 2240.88 4.97E+0l 16.57 3.36E+0l 2 . 20 F 15 1460.52 2913 - 2928 2921.14 2.18E+02 30 .18 2.00E+0l 2.27 F 16 1764.25 3522 - 3533 3528 .5 7 2.13E+0l 10.31 5.46E+00 2.01 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 : 9/11/2019 2:09:SBPM 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 76.22 3 .38E+02 56.19 3 . 38E+02 5 . 62E+0l F 2 129.17 7.86E+0l 32.37 7.86E+0l 3 .24E+0l F 3 185 .9 4 1.16E+02 32.13 l.16E+02 3.21E+0l F 4 238.58 3.77E+02 45.61 3.77E+02 4.56E+0l F 5 295 .11 1.81E+02 32.45 1.81E+02 3.24E+0l F 6 338.23 9.72E+0l 25.33 9.72E+0l 2.53E+0l F 7 351.85 2.69E+02 36.91 2.09E+0l 9.30E+00 2.48E+02 3.8 1E+0l F 8 510.51 5.41E+0l 17.99 1 .82E+0l 7.13E+00 3 . 59E+0l 1.94E+0l F 9 583 .13 1. 29E+02 24.92 1.29E+02 2.49E+0l F 10 609.19 2.02E+02 30.87 1.03E+0l 6.0SE+00 1.92E+02 3.15E+0l F 11 727 . 07 3.0 4E+0l 13 . 75 3.04E+ 0l 1. 38E+0l F 12 911.12 7.81E+0l 19.28 7.81E+0l 1.93E+01 F 13 969 . 06 3.70E+0l 1 6 .0 2 3.70E+0l 1.60E+0l
9/11/2019 2:10:07PM Page 3 of6 Analysis Report for SD 5 30" CLAY PIPE (PIECES)
SD 5 30" CLAY PIPE Peak Energy Original Orig. Area Ambient Backgr. Subtracted Subtracted No. (keV) Area Uncertainty Background Uncert. Area Uncert.
F 14 1120.35 4.97E+Ol 16.57 4.97E+Ol 1.66E+Ol F 15 1460 . 52 2.18E+02 30.18 1.41E+01 4.28E+00 2.04E+02 3.05E+01 F 16 1764.25 2 . 13E+01 10.31 3.79E+OO 2.45E+OO 1.75E+Ol 1.06E+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) (pCVgrams) Uncertainty K-40 0.99 1460.75
- 10.67 1.46E+01 2 .34E+OO BI- 212 0 . 60 727 .1 7
- 11.80 1.06E+OO 4.85E-01 785.42 2.00 1620.56 2.75 PB-212 0.96 77 .11
- 17.50 3.19E+OO 5.70E-01 238.63
- 44.60 1.28E+OO 1. 69E-01 BI-214 0 . 78 609.31
- 46.30 1. 4 6E+OO 2.52E-01 1120.29
- 15.10 2.00E+OO 6.74E-01 1238 .11 5.94 1377. 67 4 .11 140 7 .98 2.48 1509.19 2.19 1 76 4.49
- 1 5.80 9.93E-01 6.05E-01 PB-214 0.97 77 .11
- 10.70 5.23E+OO 9.33E-01 295.21
- 19. 20 1.70E+OO 3.17E-01 351. 92
- 37 .20 1. 41E+OO 2 .28E-01 RA-226 0 .98 186.21
- 3.28 4.51E+OO 1. 27E+OO AC-228 0.61 209.28 4.40 338 . 32
- 11. 40 l.74E+OO 4.62E-01 79 4. 70 4.60 911. 60
- 27.70 1. 43E+OO 3 . 58E-01 96 4.60 5.20 969 . 11
- 16.60 1.19E+00 5.19E-01
9/11/2019 2:10:07PM Page 4 of6 Analysis Report for SD 5 30" CLAY PIPE (PIECES)
SD 5 30" CLAY PIPE
- = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000sigma INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence Uncertainty (pCl/grams)
K-40 0.991 l.46E+0l 2.34E+00 BI-212 0.604 1.06E+00 4.85E-01 PB-212 0.965 1. 36E+00 l.62E-01 BI-214 0.785 1. 45E+00 2.20E-01 PB-214 0.979 1. 57E+00 l.82E-01 RA-226 0.988 4.51E+00 1. 27E+00 AC-228 0.618 l.47E+00 2.48E-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
9/11/2019 2:10:07PM Page 5 of6 Analysis Report for SD 5 30" CLAY PIPE (PIECES)
SD 5 30" CLAY PIPE UNIDENTIFIED PEAKS Peak Locate Perfonned on : 9/11/2019 2:09:58PM 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 2 129.17 8.72968E-02 20.60 Tol. PA-228 F 8 510.51 3.98762E-02 26.96 F 9 583.13 1.43601E-01 9.64 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) (pCUgrams) (pCUgrams)
(keV)
+ K-40 1460.75
- 10.67 l.46E+0l 1.84E+0O 1.84E+00
+ AR-41 1293 . 64 99.16 -5.84E-02 3 . 25E-01 3.25E-01
+ CO-60 1173.22 100.00 3.64E-02 2. llE-01 2 . 30E-01 1332.49 1 00.00 l.06E-01 2. llE-01
+ KR-85 513.99 0.43 4.33E+0l 4.39E+0l 4.39E+Ol
+ Y-88 898.04 93.70 -4.47E-02 l .63E-0l 2.02E-01 1836.06 99.20 3.04E-02 l.63E-01
+ NB-94 702.63 100.00 9.98E-02 1. 80E-01 1.80E-0l 871.10 100.00 -l.00E-01 1. 84E-0l
+ I-131 284.30 6.06 -1 . 14E+0O l.68E-0l 2.14E+00 364.48 81.20 9. 96E-02 l.68E-01 636.97 7.27 -6.62E-01 2.26E+00
+ CS-134 604.70 97.60 -l.20E-02 2.43E-01 2.97E-01 795.84 85.40 - l .37E-01 2.43E-01
+ CS-1 37 661.65 85.12 l.37E-01 2.12E-01 2 .12E-01
9/11/2019 2:10:07PM Page 6 of6 Analysis Report for SO 5 30" CLAY PIPE (PIECES)
SD 5 30" CLAY PIPE Nuclide Energy Yield(%) Activity NuclideMDA LlneMDA Name (pCi/grams) (pCilgrams) (pCi/grams)
(keV)
+ CE-144 80.12 1. 36 -1.26E+Ol 1.15E+OO 1. 72E+Ol 133.51 11.09 -5.78E-01 1.15E+OO
+ EU-152 121. 78 28.40 -1. 97E-01 4.30E-01 4.30E-01 344.28 26 .60 -l.15E+OO 6.46E-01 1408.00 20 . 74 9.85E-02 9.13E-01
+ EU-154 123.07 40.40 -3.60E-02 3. llE-01 3. llE-01 723. 30 19.70 8.55E-01 1.lOE+OO 1274.51 35.50 1. 02E-01 7.02E-01
+ EU-155 86.54 32.80 -2.23E-01 5.60E-01 5.60E-01 105.31 21. 80 2. 78E-01 6.19E-01
+ BI-214 609.31
- 4 6. 30 1.46E+OO 3.24E-01 3.24E-01 1120.29
- 15.10 2.00E+OO 9.70E-01 1238.11 5.94 2.79E+OO 4.63E+OO 1377.67 4 .11 3.14E+OO 5.15E+OO 1407.98 2.48 8.24E-01 7.64E+00 1509.19 2.19 3.48E+OO 9.35E+OO 1764.49
- 15.80 9.93E-01 8.04E-01
+ PB-214 77 .11
- 10.70 5.23E+OO 3.35E-01 1.65E+OO 295.21
- 19.20 1.70E+OO 5.78E-01 351. 92
- 37.20 1.41E+00 3.35E-01
+ PA-228 89.95 22.00 1. 43E+OO 4.76E-01 8.44E-01 93.35 35.00 -5.25E-02 4.76E-01 105.00 16.30 -4.92E-02 8.41E-01 12 9. 22 2.97 -1.14E+OO 4 . 26E+OO 338.32 5.30 3.34E+00 3.lOE+OO 463.00 13 . 80 5.61E-01 1.15E+00 911. 23 16.70 3.39E+OO 1.74E+OO
+ AM-241 59.54 36.30 -4.84E-01 9.16E-01 9.16E-01
+ CM-243 103 . 76 23.00 3.52E-01 5.90E-01 5.90E-01 228.18 10.60 -2.37E-01 1. 24E+OO 277.60 14.00 -4.67E-01 1.03E+OO
+ = Nuclide identified during the nuclide identification
- = Energy line found in the spectrum
> = MDA value not calculated
@ = Half-life too short to be able to perform the decay correction
? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level
FSS RELEASE RECORD REVISION 1 STORM DRAIN 5 ~
SURVEY UNIT S3-012-102 B LACROSSESOLUTIONS ATTACHMENT 7 GEL LABORATORIES ANALYTICAL REPORTS 39
[i]ij* I Laboratories LLc PO Bex 30712 Charleston SC 29417 a member of The GEL Group INC 2040 Sa*1a,;ie Road Charleston. SC 29407 P 843 556.8171 F 84:;_766.117B gel. com October 14, 2020 Mr. Jason Q. Spaide LaCrosseSolutions S4601 State Hwy 35 Genoa, Wisconsin 54632 Re: LACBWR Site Restoration Project, Level 5 Package Work Order: 523444
Dear Mr. Spaide:
GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for the sample(s) we received on October 07, 2020. This revised data report has been prepared and reviewed in accordance with GEL's standard operating procedures. The data package has been revised to report a Level 5 package.
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 GEL' s 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, Edith Kent Project Manager Purchase Order: 672583 Enclosures
Table of Contents Case Narrative....................................................................................3 Chain of Custody and Supporting Documentation.........................5 Laboratory Certifications..................................................................8 Radiological Analysis.......................................................................10 Case Narrative..........................................................................11 Sample Data Summary............................................................22 Quality Control Summary.......................................................26
Case Narrative Page 1 of 31 SDG: 523444 Rev1
The data package has been revised to report a Level 5 package.
Case Narrative for LaCrosseSolutions, LLC (672583)
SDG: 523444 October 14, 2020 Laboratory Identification:
GEL Laboratories LLC 2040 Savage Road Charleston, South Carolina 29407 (843) 556-8171 Summary Sample Receipt The sample arrived at GEL Laboratories LLC, Charleston, South Carolina on October 07, 2020 for analysis. The sample was delivered with proper chain of custody documentation and signatures. All sample containers arrived without any visible signs of tampering or breakage. There are no additional comments concerning sample receipt.
Sample Identification The laboratory received the following sample:
Laboratory ID Client ID 523444001 Clay Pipe Sample Case Narrative Sample analyses were conducted using methodology as outlined in GEL Laboratories, LLC (GEL)
Standard Operating Procedures. Any technical or administrative problems during analysis, data review, and reduction are contained in the analytical case narratives in the enclosed data package.
Data Package The enclosed data package contains the following sections: General Narrative, Chain of Custody and Supporting Documentation, and data from the following fractions: Radiochemistry.
Edith Kent Project Manager GEL Page Laboratories 2 of 31 SDG: LLC 523444 Rev1Char1eston, SC 29417 PO Box 30712 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com
Chain of Custody and Supporting Documentation Page 3 of 31 SDG: 523444 Rev1
Page 4 of 31 5l3LJYL /
h~ _ _ _ l _ _ _ ~ _ _ _ l
=t! I~~£?~~!e~Il~~io~~sy GEL Laboratories, LLC Project # LACBWR Site 2040 Savage Road SDG: 523444 Rev1 GEL Quote#: - - - - - - - - - - - - < I SpecialfyAnalyucs COC Number 11 >:
PO Number: 672583 Client Name: La Crosse Solutions Project/Site Name: LACBWR-Genoa WI Address: 5460 I State Road 35
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Time I. Kevin L Murra 10/06/2020 0930 2
Use Only: Custody Seal Intact? [ ] Yes [ ] No Cooler Temp: '1,..t..,,C
> For.sample sltij,ping 4iJ~:~e/i~~ij;4it~lJ.I.;:fefk~'g'ijlf/1c)R~f* ~a rlJilW iI,t~i~tfp/.Jimf) Mo~ri#'@ f' [ IQ.tli£r: r I.) Chain of Custody Number= Client Determined 2.) QC Codes: N Nomuil Sample. TB .,. Trip Blank. FD = Fidd Duplicate, EB = Equipment Blank. MS = ~*fatrix Spike Sample. MSD =Matrix Spike Duplicate Sample,
-* ---* ****----*** 0,:
,, ___ ,. _____ ----- ___ ____ ..,__.__ __ ____ __ G =Grab, C =Composite J.) Field Filtered: For liquid matrices, indicatewi1h a* Y
- for yes lhe sample was fidd filtered or
- N - for sample was not field filtered.
4.) Matrb: Codes: DW=Oririking Water, GW=-Groundwater, SW=Surfacc Water. WW""Waste Water, W"'"Wata , ML=Misc Liquid. SO'-'-Soil, SO,,,Sediment, SL,,,.Sludge, SS,,,,Solid Waste, O=Oil. F=Fi ltcr. P=Wi_pe. U=Urine. F=Fccal. N""Nasal 5.) Sample Analysis Requested: Analytical method requested (i.e. 8260B .* 6010B/7470A) and number of containers provided for each (i.e. 81608
- 3, 60J0B,'7.J70A * .I).
6.) Preservative Type: HA = Hydrochloric Acid. NI = Nitric Acid, SH = Sodium Hydroxide. SA = Sulforic Acid, AA= Ascorbic Acid. HX "-' Hexane.ST ,.,, Sodium Thiosulfate. If no preservative is added= leave field blank
B /LarJoratories LLC SAMPLE RECEIPT & REVIEW FORM Client:
SDG/AR /COC/W ork Order: $'2..3 L/ i...t Receive d By: ZKW l O *1, 1..--9 Date Receive d:
Li?._. r_*:~~ l
~
Circle Applicablc:
FedEx Ground UPS Field S,ervices Courier Other Carrier and Trackin g Numbe r 1
I
<l~ \~ l'2o nS* 2,-: sq Sll.~pcctcd Hazard lnf'onnation
- ,,.gi zo
- 1r Net Counts> 10(/cpm on samples not marked "radioacti ve", contact the Radia !ion Safety Group for funher investigat l 1I ionj Hazard Class Shipped:
A)Shi ipcd ,Ls a DOT Hazardous?
UN#: i
[f UN29 IO, Is the Radioactive Shipment Survey Complian t'/ Yes_-\- No_
B) Did the client designate the samples arc to be received ,t,; rndioactivc?
C) Did the RSO ci ,Lssify the samples as radionctivc?
D) Did the client dcsic.natc samples arc hazardous?
El Did the RSO idcntif ssiblc hazards? Foreign Soil RCRA Asbestos i
Beryllium Other:
Sample Recei pt Criteria Commcn ls/Qualif icrs (Require d for Non-Cop forming Items)
Shipping containe rs received intact and Circle Applicable: Seals broken Damaged container Lc:1king contn inc r Oth'.cr (de scribe) sealed?
Chain of custody doc uments included Circle Applicable : Client contacrcd :md prO\,idcd COC 2 COC created upo1, rcc'}!ip1 with shipmen t?
Presc,vation Method: Wet Ice Ice Packs DI)' ice /!"Olm'\
3 Samples requiring cold preserva tion Other:
- all 1cmpcnuurcs arc recorded in Celsius \.__,./
within (0 $ 6 de *. C)?*
Daily check performe d and passed on IR Temperature Device Serial#: IR3-18 4
temperat ure gun? Secondary Temperature Device Se,ial # (If Applicable):
Circle Applicable : Seals hrokcn 0.imagcd cunlaincr 5 Sample containe rs intact and sea led? Lcnking container Oth~r (dcscribcJ Samples requiring chemica l preserva tion -* Sample ID's :ind Containe rs Affected:
6 at proper pH?
If Preservation added. Lot#:
If Yes. arc Encores or Soil Kits present for solids? Yes_ No
__ NA_( lf fes, lake to VOA Freezer)
Do any samp les require Vol atile Do liquid VOA vials contain acid preservation Yes_ No_
7 NA_(l f rnjknown. select No)
Analysis'? Krc liquid VOA vials free of hcadspace ? Yes_ No __ NA_ _
Sample JD's and i:0111~1incrs affected:
ID's and 1es1s affected:
8 Samples received within holding time?
Sample !D's on COC match !D's on !D's and containers affee1cd:
9 bo1tles?
Circle Applicable: No dates on containers No times on containers COC mis~ing info Other (describe)
Number of containe rs received match Circle Applicab le: No container count on COC 01hcr (describe 11 )
number indicated on COC?
Are sample containe rs identifia ble as 12 GEL irovided b use of GEL labels?
COC form is properly signed in 13 Not relinquished Other (describe) relinquis hed/rece ived sections?
Commcnls {Use Continual ion Fonn if needed):
GL-CHL-SR-001 Rev 7 i Page 5 of 31 SDG: 523444 Rev1
Laboratory Certifications Page 6 of 31 SDG: 523444 Rev1
List of current GEL Certifications as of 14 October 2020 State Certification Alabama 42200 Alaska 17-018 Alaska Drinking Water SC00012 Arkansas 88-0651 CLIA 42D0904046 California 2940 Colorado SC00012 Connecticut PH-0169 DoD ELAP/ ISOl 7025 A2LA 2567.01 Florida NELAP E87156 Foreign Soils Permit P330-15-00283,P330-15-00253 Georgia SC00012 Georgia SDWA 967 Hawaii SC00012 Idaho SC00012 Illinois NELAP 200029 Indiana C-SC-01 Kansas NELAP E-10332 Kentucky SDWA 90129 Kentucky Wastewater 90129 Louisiana Drinking Water LA024 Louisiana NELAP 03046 (AI33904)
Maine 2019020 Maryland 270 Massachusetts M-SC012 Massachusetts PFAS Approv Letter Michigan 9976 Mississippi SC00012 Nebraska NE-OS-26-13 Nevada SC000122020-1 New Hampshire NELAP 2054 New Jersey NELAP SC002 New Mexico SC00012 New York NELAP 11501 North Carolina 233 North Carolina SDWA 45709 North Dakota R-158 Oklahoma 2019-165 Pennsylvania NELAP 68-00485 Puerto Rico SC00012 S. Carolina Radiochem 10120002 Sanitation Districts of L 9255651 South Carolina Chemistry 10120001 Tennessee TN 02934 TexasNELAP T104704235-20-17 UtahNELAP SC000122020-32 Vermont VT87156 Virginia NELAP 460202 Washington C780 Page 7 of 31 SDG: 523444 Rev1
Radiological Analysis Page 8 of 31 SDG: 523444 Rev1
Case Narrative Page 9 of 31 SDG: 523444 Rev1
Radiochemistry Technical Case Narrative LaCrosseSolutions, LLC SDG #: 523444 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# 28 Analytical Batch: 2048817 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 24 Preparation Batch: 2048799 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662074 Method Blank (MB) 1204662075 523444001(Clay Pipe Sample) Sample Duplicate (DUP) 1204662076 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-069 REV# 0 Analytical Batch: 2048818 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 24 Preparation Batch: 2048799 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 Page 10 of 31 SDG: 523444 Rev1
The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662077 Method Blank (MB) 1204662078 523444001(Clay Pipe Sample) Sample Duplicate (DUP) 1204662079 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# 28 Analytical Batch: 2048821 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 24 Preparation Batch: 2048799 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662080 Method Blank (MB) 1204662081 523444001(Clay Pipe Sample) Sample Duplicate (DUP) 1204662082 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 Page 11 of 31 SDG: 523444 Rev1
Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 24 Preparation Batch: 2048799 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 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: 2049079 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 24 Preparation Batch: 2048799 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662634 Method Blank (MB) 1204662635 523444001(Clay Pipe Sample) Sample Duplicate (DUP) 1204662636 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 12 of 31 SDG: 523444 Rev1
Product: Gamma Ni59, Solid Analytical Method: DOE RESL Ni-I Analytical Procedure: GL-RAD-A-022 REV# 19 Analytical Batch: 2049118 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 24 Preparation Batch: 2048799 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662711 Method Blank (MB) 1204662712 523444001(Clay Pipe Sample) Sample Duplicate (DUP) 1204662713 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: 2049031 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 24 Preparation Batch: 2048799 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662481 Method Blank (MB)
Page 13 of 31 SDG: 523444 Rev1
1204662482 523444001(Clay Pipe Sample) Sample Duplicate (DUP) 1204662483 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.
Preparation Information Aliquot Reduced Aliquots were reduced due to limited sample volume Technical Information Recounts Sample 1204662483 (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: 2048822 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 24 Preparation Batch: 2048799 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662083 Method Blank (MB) 1204662084 52344400l(Clay Pipe Sample) Sample Duplicate (DUP) 1204662085 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 14 of 31 SDG: 523444 Rev1
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: 2048871 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662161 Method Blank (MB) 1204662162 523444001(Clay Pipe Sample) Sample Duplicate (DUP) 1204662163 Laboratory Control Sample (LCS)
The samples in this SDG were analyzed on an "as received" basis.
Data Summary:
There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable.
Product: Liquid Scint Fe55, Solid Analytical Method: DOE RESL Fe-1, Modified Analytical Procedure: GL-RAD-A-040 REV# 13 Analytical Batch: 2049102 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 24 Preparation Batch: 2048799 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662669 Method Blank (MB) 1204662670 523444001(Clay Pipe Sample) Sample Duplicate (DUP) 1204662671 Laboratory Control Sample (LCS)
The samples in this SDG were analyzed on a "dry weight" basis.
Page 15 of 31 SDG: 523444 Rev1
Data Summary:
There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable.
Product: Liquid Scint Ni63, Solid Analytical Method: DOE RESL Ni-1, Modified Analytical Procedure: GL-RAD-A-022 REV# 19 Analytical Batch: 2049103 Preparation Method: Dry Soil Prep Preparation Procedure: GL-RAD-A-021 REV# 24 Preparation Batch: 2048799 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662672 Method Blank (MB) 1204662673 523444001(Clay Pipe Sample) Sample Duplicate (DUP) 1204662674 Laboratory Control Sample (LCS)
The samples in this SDG were analyzed on a "dry weight" basis.
Data Summary:
All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.
Miscellaneous Information Additional Comments Wet sample was used for analysis due to short TAT and limited dry volume.
Product: LSC, Tritium Distillation, Solid Analytical Method: EPA 906.0 Modified Analytical Procedure: GL-RAD-A-002 REV# 23 Analytical Batch: 2049115 Composite Preparation Method: GEL Prep Method Page 16 of 31 SDG: 523444 Rev1
Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662700 Method Blank (MB) 1204662701 523444001(Clay Pipe Sample) Sample Duplicate (DUP) 1204662702 523444001(Clay Pipe Sample) Matrix Spike (MS) 1204662703 Laboratory Control Sample (LCS)
The samples in this SDG were analyzed on an "as received" basis.
Data Summary:
All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.
Technical Information Recounts Samples 1204662700 (MB), 1204662701 (Clay Pipe SampleDUP) and 523444001 (Clay Pipe Sample) were recounted due to high MDCs. The recounts are reported.
Product: Liquid Scint C14, Solid Analytical Method: EPA EERF C-01 Modified Analytical Procedure: GL-RAD-A-003 REV# 16 Analytical Batch: 2049116 Composite Preparation Method: GEL Prep Method Composite Preparation Procedure: GL-RAD-A-026 REV# 18 Composite Preparation Batch: 2048877 The following samples were analyzed using the above methods and analytical procedure(s).
GEL Sample ID# Client Sample Identification 523444001 Clay Pipe Sample 1204662704 Method Blank (MB) 1204662705 523444001(Clay Pipe Sample) Sample Duplicate (DUP) 1204662706 523444001(Clay Pipe Sample) Matrix Spike (MS) 1204662707 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 17 of 31 SDG: 523444 Rev1
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 18 of 31 SDG: 523444 Rev1
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Qualifier Definition Report for ENRG070 LaCrosseSolutions, LLC (672583)
Client SDG: 523444 GEL Work Order: 523444 The Qualifiers in this report are defined as follows:
- A quality control analyte recovery is outside of specified acceptance criteria
Review/Validation GEL requires all analytical data to be verified by a qualified data reviewer. In addition, all CLP-like deliverables receive a third level review of the fractional data package.
The following data validator verified the information presented in this data report:
Signature: Name: Kate Gellatly Date: 13 OCT 2020
Title:
Analyst I Page 19 of 31 SDG: 523444 Rev1
Sample Data Summary Page 20 of 31 SDG: 523444 Rev1
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 13, 2020 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project, Level 5 Package Client Sample ID: Clay Pipe Sample Project: ENRG07002 Sample ID: 523444001 Client ID: ENRG070 Matrix: Misc Solid Collect Date: 21-SEP-20 10:00 Receive Date: 07-OCT-20 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 0.00327 +/-0.00919 0.00981 0.400 pCi/g HAKB 10/09/20 0954 2048817 1 Americium-243 U 0.0183 +/-0.0183 0.0212 0.400 pCi/g Curium-243/244 U -0.00207 +/-0.0122 0.0289 0.400 pCi/g Alphaspec Np, Solid "Dry Weight Corrected" Neptunium-237 U -0.000525 +/-0.00347 0.00812 0.0100 pCi/g HAKB 10/11/20 1732 2048818 2 Alphaspec Pu238, 239/240, Solid "Dry Weight Corrected" Plutonium-238 U 0.00370 +/-0.0126 0.0234 0.400 pCi/g HAKB 10/09/20 0954 2048821 3 Plutonium-239/240 U -0.0136 +/-0.00980 0.0362 0.400 pCi/g Liquid Scint Pu241, Solid "Dry Weight Corrected" Plutonium-241 U 0.926 +/-2.37 4.04 5.00 pCi/g HAKB 10/10/20 2225 2048822 4 Rad Gamma Spec Analysis Gamma Ni59, Solid "Dry Weight Corrected" Nickel-59 U -0.294 +/-1.71 3.21 5.00 pCi/g RP1 10/09/20 0915 2049118 5 Gamma, Cs137, Co60, Nb94, Eu152, Eu154, Eu155 "Dry Weight Corrected" Cesium-137 U -0.00378 +/-0.0492 0.0897 1.00 pCi/g MXR1 10/08/20 0931 2049079 6 Cobalt-60 U -0.0406 +/-0.0563 0.0921 pCi/g Europium-152 U -0.0209 +/-0.110 0.211 pCi/g Europium-154 U 0.129 +/-0.134 0.304 pCi/g Europium-155 U 0.0616 +/-0.112 0.225 pCi/g Niobium-94 U 0.0617 +/-0.0424 0.0917 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, Solid "Dry Weight Corrected" Strontium-90 U 0.128 +/-0.226 0.391 0.400 pCi/g JXC9 10/09/20 1139 2049031 7 Rad Liquid Scintillation Analysis LSC, Tritium Distillation, Solid "As Received" Tritium U -1.41 +/-4.80 8.57 10.0 pCi/g EW3 10/12/20 0212 2049115 8 Liquid Scint C14, Solid "As Received" Carbon-14 U -0.755 +/-2.27 3.96 5.00 pCi/g EW3 10/10/20 1833 2049116 9 Liquid Scint Tc99, Solid "As Received" Technetium-99 U -0.179 +/-0.963 1.66 2.00 pCi/g JJ3 10/13/20 0454 2048871 10 Liquid Scint Fe55, Solid "Dry Weight Corrected" Iron-55 U -4.00 +/-6.13 9.83 10.0 pCi/g RP1 10/12/20 0751 2049102 11 Liquid Scint Ni63, Solid "Dry Weight Corrected" Page 21 of 31 SDG: 523444 Rev1
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 13, 2020 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project, Level 5 Package Client Sample ID: Clay Pipe Sample Project: ENRG07002 Sample ID: 523444001 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 0.996 +/-1.81 3.09 5.00 pCi/g RP1 10/12/20 0427 2049103 12 The following Prep Methods were performed:
Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 CXC1 10/07/20 1410 2048799 GEL Prep Method Laboratory Composite 2048877 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, 91.2 (15%-125%)
Solid "Dry Weight Corrected" Curium-243/244 Tracer Alphaspec Isotopic Am241 Am243, Cm243/244, 79.7 (15%-125%)
Solid "Dry Weight Corrected" Americium-243 Tracer Alphaspec Np, Solid "Dry Weight Corrected" 69.7 (15%-125%)
Plutonium-242 Tracer Alphaspec Pu238, 239/240, Solid "Dry Weight 83.2 (15%-125%)
Corrected" Plutonium-242 Tracer Liquid Scint Pu241, Solid "Dry Weight Corrected" 83.2 (15%-125%)
Nickel Carrier Gamma Ni59, Solid "Dry Weight Corrected" 97.7 (25%-125%)
Strontium Carrier GFPC, Sr90, Solid "Dry Weight Corrected" 82.6 (25%-125%)
Technetium-99m Tracer Liquid Scint Tc99, Solid "As Received" 88.3 (15%-125%)
Iron-59 Tracer Liquid Scint Fe55, Solid "Dry Weight Corrected" 38.1 (15%-125%)
Nickel Carrier Liquid Scint Ni63, Solid "Dry Weight Corrected" 78.2 (25%-125%)
Page 22 of 31 SDG: 523444 Rev1
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report Date: October 13, 2020 Company : LaCrosseSolutions Address : S4601 State Hwy 35 Genoa, Wisconsin 54632
Contact:
Mr. Jason Q. Spaide Project: LACBWR Site Restoration Project, Level 5 Package Client Sample ID: Clay Pipe Sample Project: ENRG07002 Sample ID: 523444001 Client ID: ENRG070 Parameter Qualifier Result Uncertainty MDC RL Units PF DF Analyst Date Time Batch Method 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 31 SDG: 523444 Rev1
Quality Control Summary Page 24 of 31 SDG: 523444 Rev1
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Report Date: October 13, 2020 LaCrosseSolutions Page 1 of 7 S4601 State Hwy 35 Genoa, Wisconsin
Contact:
Mr. Jason Q. Spaide Workorder: 523444 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 2048817 QC1204662075 523444001 DUP Americium-241 U 0.00327 U 0.00526 pCi/g N/A N/A HAKB 10/09/20 09:06 Uncertainty +/-0.00919 +/-0.0165 Americium-243 U 0.0183 U -0.00175 pCi/g N/A N/A Uncertainty +/-0.0183 +/-0.0121 Curium-243/244 U -0.00207 U 0.00786 pCi/g N/A N/A Uncertainty +/-0.0122 +/-0.0135 QC1204662076 LCS Americium-241 0.977 0.862 pCi/g 88.2 (75%-125%) 10/09/20 09:06 Uncertainty +/-0.106 Americium-243 U 0.00342 pCi/g (75%-125%)
Uncertainty +/-0.00942 Curium-243/244 1.10 0.929 pCi/g 84.2 (75%-125%)
Uncertainty +/-0.109 QC1204662074 MB Americium-241 U -0.00357 pCi/g 10/09/20 09:06 Uncertainty +/-0.00827 Americium-243 U 0.00147 pCi/g Uncertainty +/-0.00819 Curium-243/244 U -0.00792 pCi/g Uncertainty +/-0.00902 Batch 2048818 QC1204662078 523444001 DUP Neptunium-237 U -0.000525 U -2.05E-05 pCi/g N/A N/A HAKB 10/11/20 17:32 Uncertainty +/-0.00347 +/-0.00416 QC1204662079 LCS Neptunium-237 0.869 1.06 pCi/g 122 (75%-125%) 10/11/20 18:39 Uncertainty +/-0.0626 QC1204662077 MB Neptunium-237 U -0.00109 pCi/g 10/11/20 18:39 Uncertainty +/-0.00201 Page 25 of 31 SDG: 523444 Rev1
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 523444 Page 2 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 2048821 QC1204662081 523444001 DUP Plutonium-238 U 0.00370 U -0.00153 pCi/g N/A N/A HAKB 10/09/20 09:54 Uncertainty +/-0.0126 +/-0.00678 Plutonium-239/240 U -0.0136 U 0.0129 pCi/g N/A N/A Uncertainty +/-0.00980 +/-0.0157 QC1204662082 LCS Plutonium-238 U 0.00861 pCi/g 10/09/20 09:54 Uncertainty +/-0.0171 Plutonium-239/240 0.992 1.07 pCi/g 108 (75%-125%)
Uncertainty +/-0.133 QC1204662080 MB Plutonium-238 U 0.00620 pCi/g 10/09/20 09:54 Uncertainty +/-0.0122 Plutonium-239/240 U 0.00282 pCi/g Uncertainty +/-0.0126 Batch 2048822 QC1204662084 523444001 DUP Plutonium-241 U 0.926 U 0.678 pCi/g N/A N/A HAKB 10/10/20 23:28 Uncertainty +/-2.37 +/-2.29 QC1204662085 LCS Plutonium-241 39.1 39.0 pCi/g 99.7 (75%-125%) 10/11/20 00:00 Uncertainty +/-3.44 QC1204662083 MB Plutonium-241 U 0.673 pCi/g 10/10/20 22:56 Uncertainty +/-2.06 Rad Gamma Spec Batch 2049079 QC1204662635 523444001 DUP Cesium-137 U -0.00378 U 0.00786 pCi/g N/A N/A MXR1 10/08/20 10:39 Uncertainty +/-0.0492 +/-0.0505 Cobalt-60 U -0.0406 U 0.0191 pCi/g N/A N/A Uncertainty +/-0.0563 +/-0.0539 Europium-152 U -0.0209 U -0.0449 pCi/g N/A N/A Uncertainty +/-0.110 +/-0.111 Page 26 of 31 SDG: 523444 Rev1
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 523444 Page 3 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 2049079 Europium-154 U 0.129 U -0.0678 pCi/g N/A N/A MXR1 10/08/20 10:39 Uncertainty +/-0.134 +/-0.167 Europium-155 U 0.0616 U 0.0958 pCi/g N/A N/A Uncertainty +/-0.112 +/-0.133 Niobium-94 U 0.0617 U 0.0300 pCi/g N/A N/A Uncertainty +/-0.0424 +/-0.0440 QC1204662636 LCS Americium-241 486 549 pCi/g 113 (75%-125%) 10/08/20 10:42 Uncertainty +/-12.0 Cesium-137 163 161 pCi/g 98.4 (75%-125%)
Uncertainty +/-3.21 Cobalt-60 94.6 92.5 pCi/g 97.7 (75%-125%)
Uncertainty +/-2.98 Europium-152 U -0.215 pCi/g Uncertainty +/-1.30 Europium-154 U 0.0978 pCi/g Uncertainty +/-0.971 Europium-155 U -0.166 pCi/g Uncertainty +/-0.976 Niobium-94 U -0.259 pCi/g Uncertainty +/-0.438 QC1204662634 MB Cesium-137 U -0.00661 pCi/g 10/08/20 09:31 Uncertainty +/-0.0231 Cobalt-60 U 0.00485 pCi/g Uncertainty +/-0.0235 Europium-152 U -0.0189 pCi/g Uncertainty +/-0.0533 Europium-154 U 0.0427 pCi/g Uncertainty +/-0.0755 Europium-155 U 0.0261 pCi/g Uncertainty +/-0.0580 Page 27 of 31 SDG: 523444 Rev1
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 523444 Page 4 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 2049079 Niobium-94 U 0.00583 pCi/g MXR1 10/08/20 09:31 Uncertainty +/-0.0189 Batch 2049118 QC1204662712 523444001 DUP Nickel-59 U -0.294 U 0.815 pCi/g N/A N/A RP1 10/09/20 09:16 Uncertainty +/-1.71 +/-1.14 QC1204662713 LCS Nickel-59 106 83.5 pCi/g 78.5 (75%-125%) 10/09/20 09:50 Uncertainty +/-7.74 QC1204662711 MB Nickel-59 U -0.127 pCi/g 10/09/20 09:16 Uncertainty +/-0.560 Rad Gas Flow Batch 2049031 QC1204662482 523444001 DUP Strontium-90 U 0.128 U -0.152 pCi/g N/A N/A JXC9 10/09/20 11:38 Uncertainty +/-0.226 +/-0.191 QC1204662483 LCS Strontium-90 26.3 31.0 pCi/g 118 (75%-125%) 10/12/20 12:26 Uncertainty +/-1.44 QC1204662481 MB Strontium-90 U -0.0553 pCi/g 10/09/20 11:38 Uncertainty +/-0.212 Rad Liquid Scintillation Batch 2048871 QC1204662162 523444001 DUP Technetium-99 U -0.179 U -0.249 pCi/g N/A N/A JJ3 10/13/20 06:08 Uncertainty +/-0.963 +/-0.869 QC1204662163 LCS Technetium-99 33.6 31.1 pCi/g 92.4 (75%-125%) 10/13/20 06:46 Uncertainty +/-1.41 QC1204662161 MB Technetium-99 U -0.621 pCi/g 10/13/20 05:31 Uncertainty +/-0.812 Page 28 of 31 SDG: 523444 Rev1
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 523444 Page 5 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 2049102 QC1204662670 523444001 DUP Iron-55 U -4.00 U -3.41 pCi/g N/A N/A RP1 10/12/20 10:36 Uncertainty +/-6.13 +/-6.00 QC1204662671 LCS Iron-55 184 175 pCi/g 95.3 (75%-125%) 10/12/20 11:59 Uncertainty +/-6.90 QC1204662669 MB Iron-55 U 1.10 pCi/g 10/12/20 09:14 Uncertainty +/-4.71 Batch 2049103 QC1204662673 523444001 DUP Nickel-63 U 0.996 U 0.980 pCi/g N/A N/A RP1 10/12/20 04:59 Uncertainty +/-1.81 +/-1.56 QC1204662674 LCS Nickel-63 71.3 66.9 pCi/g 93.8 (75%-125%) 10/12/20 05:15 Uncertainty +/-3.33 QC1204662672 MB Nickel-63 U 0.534 pCi/g 10/12/20 04:43 Uncertainty +/-1.54 Batch 2049115 QC1204662701 523444001 DUP Tritium U -1.41 U 0.584 pCi/g N/A N/A EW3 10/12/20 06:07 Uncertainty +/-4.80 +/-4.91 QC1204662703 LCS Tritium 127 113 pCi/g 89 (75%-125%) 10/11/20 02:16 Uncertainty +/-10.9 QC1204662700 MB Tritium U -3.14 pCi/g 10/12/20 04:46 Uncertainty +/-4.44 QC1204662702 523444001 MS Tritium 127 U -1.41 123 pCi/g 96.6 (75%-125%) 10/11/20 01:25 Uncertainty +/-4.80 +/-11.6 Page 29 of 31 SDG: 523444 Rev1
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 523444 Page 6 of 7 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Liquid Scintillation Batch 2049116 QC1204662705 523444001 DUP Carbon-14 U -0.755 U -0.345 pCi/g N/A N/A EW3 10/10/20 19:55 Uncertainty +/-2.27 +/-2.28 QC1204662707 LCS Carbon-14 148 140 pCi/g 94.5 (75%-125%) 10/10/20 21:18 Uncertainty +/-4.89 QC1204662704 MB Carbon-14 U 0.218 pCi/g 10/10/20 19:14 Uncertainty +/-2.26 QC1204662706 523444001 MS Carbon-14 148 U -0.755 150 pCi/g 101 (75%-125%) 10/10/20 20:37 Uncertainty +/-2.27 +/-5.00 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 30 of 31 SDG: 523444 Rev1
GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 523444 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 31 of 31 SDG: 523444 Rev1