ML21067A211
ML21067A211 | |
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Site: | Zion File:ZionSolutions icon.png |
Issue date: | 02/10/2021 |
From: | Yetter R ZionSolutions |
To: | Office of Nuclear Material Safety and Safeguards |
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ML21067A225 | List:
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References | |
ZS-2021-0001 | |
Download: ML21067A211 (244) | |
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= ZIONSOLUTIONSLLC-An EnergySolutions Company ZION STATION RESTORATION PROJECT FINAL STATUS SURVEY RELEASE RECORD Revision 2 CRIB HOUSE/FOREBAY BASEMENT SURVEY UNIT 08100
FSS RELEASE RECORD REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-An energy~Company SURVEY UNIT 08100 v1 / ~ , Robert F. Yetter III
~ ~ Nov 11 2020 I 1:04 AM PREPARED BY / DATE: Robert Yetter III cosi3n Final Status Survey Specialist Robert F. Yetter 9w/,.,eJd :J. 'lJ,efte,t Nov I I 2020 12:29 PM REVIEWED BY / DATE: Robert Yetter cosi3n Director, Radiological Site Closure Sarah Roberts Sarah Roberts Nov 1120201:10PM cosign APPROVED BY / DATE: Sarah Roberts Vice President, Radiological Programs
[2]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc- 1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 TABLE OF CONTENTS
- 1. EXECUTIVE
SUMMARY
................................................................................................................................. 7
- 2. SURVEY UNIT DESCRIPTION ....................................................................................................................... 8
- 3. CLASSIFICATION BASIS ............................................................................................................................... 11
- 4. DATA QUALITY OBJECTIVES (DQO) ........................................................................................................ 13
- 5. SURVEY DESIGN ............................................................................................................................................. 17
- 6. SURVEY IMPLEMENTATION ...................................................................................................................... 26
- 7. SURVEY RESULTS .......................................................................................................................................... 28
- 8. QUALITY CONTROL ...................................................................................................................................... 36
- 9. INVESTIGATIONS AND RESULTS .............................................................................................................. 37
- 10. REMEDIATION AND RESULTS ............................................................................................................... 37
- 11. CHANGES FROM THE FINAL STATUS SURVEY PLAN .................................................................... 37
- 12. DATA QUALITY ASSESSMENT (DQA) .................................................................................................. 37
- 13. ANOMALIES ................................................................................................................................................ 38
- 14. COMPLIANCE EQUATION ....................................................................................................................... 38
- 15. CONCLUSION .............................................................................................................................................. 40
- 16. REFERENCES .............................................................................................................................................. 41
- 17. ATTACHMENTS .......................................................................................................................................... 42 ATTACHMENT 1 ................................................................................................................................................... 43 ATTACHMENT 2 ................................................................................................................................................... 61 ATTACHMENT 3 ................................................................................................................................................... 68 ATTACHMENT 4 ................................................................................................................................................... 70 ATTACHMENT 5 ................................................................................................................................................... 72 ATTACHMENT 6 ................................................................................................................................................... 76 ATTACHMENT 7 ................................................................................................................................................... 82 ATTACHMENT 8 ................................................................................................................................................. 217
[3]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc- 1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 LIST OF TABLES Table 1 - Statistical Quantities for Cs-137 and Co-60 from the 2012 Characterization Survey ...................12 Table 2 - Dose Significant Radionuclides and Mixture ................................................................................15 Table 3 - Base Case DCGLs for Crib House/Forebay Structural Surfaces (BcDCGLB) from LTP Chapter 5, Table 5-3 .......................................................................................................................................................16 Table 4 - Operational DCGLs for Crib House/Forebay Structural Surfaces (OpDCGLB) from LTP Chapter 5, Table 5-4 ...................................................................................................................................................17 Table 5 - Surrogate Ratios ............................................................................................................................18 Table 6 - Action Levels for Survey Unit 08100............................................................................................19 Table 7 - Adjusted Minimum Number of ISOCS Measurements .................................................................20 Table 8 - Random ISOCS Measurement Locations ......................................................................................21 Table 9 - Circulating Water Intake Pipe Judgmental Measurement Locations.............................................22 Table 10 - Forebay Judgmental Measurement Locations .............................................................................23 Table 11 - Investigation Levels .....................................................................................................................24 Table 12 - Synopsis of Survey Design ..........................................................................................................25 Table 13 - Summary of Gamma Spectroscopy Results for ISOCS Measurements Comprising the Statistical Sample Population ........................................................................................................................................29 Table 14 - Basic Statistical Properties of Random ISOCS Measurements ...................................................29 Table 15 - Summary of ISOCS Replicate Measurement for QC ..................................................................30 Table 16 - Summary of Full Suite Concrete Core Analysis by Eberline ......................................................31 Table 17 - Summary of Gamma Spectroscopy Results for Judgmental ISOCS Measurements Taken in Circulating Water Intake Pipes .....................................................................................................................32 Table 18 - Summary of ISOCS Replicate Measurement for QC ..................................................................32 Table 19 - Summary of Results for Judgmental Measurements Taken in the Forebay ................................33 Table 20 - Summary of Replicate Measurement Taken in Forebay for QC .................................................33 Table 21 - Sum of Fractions for Random ISOCS Measurements .................................................................34 Table 22 - Sum of Fractions for Judgmental ISOCS Measurements Taken in the Circulating Water Intake Pipe ...............................................................................................................................................................35 Table 23 - Sum of Fractions for Judgmental Gamma Measurements Taken in the Forebay ........................35 Table 24 - Calculation of Mean BcSOF for Judgmental Measurements Taken in the Circulating Water Intake Pipes Using BcDCGLs ......................................................................................................................36 Table 25 - Calculation Mean BcSOF for Judgmental Measurements Taken in the Forebay Using BcDCGLs
......................................................................................................................................................................36
[4]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable AMCG Average Member of the Critical Group BFM Basement Fill Model DQA Data Quality Assessment DQO Data Quality Objective DCGL Derived Concentration Guideline Level EMC Elevated Measurement Comparison FOV Field of View FSS Final Status Survey GPS Global Positioning System HTD Hard-to-Detect IC Insignificant Contributor ISOCS In Situ Object Counting System LTP License Termination Plan LBGR Lower Bound of the Gray Region MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration MDCR Minimum Detectable Count Rate NAD North American Datum NaI Sodium Iodide OpDCGL Operational Derived Concentration Guideline Level QAPP Quality Assurance Project Plan QC Quality Control RE Radiological Engineer ROC Radionuclides of Concern SOF Sum of Fractions TEDE Total Effective Dose Equivalent [5]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 UBGR Upper Bound of the Gray Region UCL Upper Confidence Level USNRC United States Nuclear Regulatory Commission VSP Visual Sample Plan ZNPS Zion Nuclear Power Station ZSRP Zion Station Restoration Project [6]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100
- 1. EXECUTIVE
SUMMARY
This Final Status Survey (FSS) Release Record for survey unit 08100, Crib House/Forebay basement survey unit, has been generated for the Zion Station Restoration Project (ZSRP) in accordance with ZionSolutions procedure ZS-LT-300-001-005, Final Status Survey Data Reporting (Reference 1) and satisfies the requirements of Section 5.11 of the Zion Station Restoration Project License Termination Plan (LTP) (Reference 2). The FSS package for basement survey unit 08100, Crib House/Forebay, includes FSS design and results for the following: B3-08101A Crib House/Forebay Structural Surfaces B3-08102A Unit 1 Circulating Water Intake Pipe B3-08102B Unit 2 Circulating Water Intake Pipe B3-08401A Forebay Submerged Surfaces FSS sample plans for each of these survey units were developed in accordance with ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development (Reference 3), the ZSRP LTP, and with guidance from NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) (Reference 4). In accordance with ZSRP LTP, Section 5.5.2.1.2 and Table 5-19, the Crib House/Forebay basement survey unit 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 () and Type II () decision error rates were set at 0.05. The Canberra In Situ Object Counting System (ISOCS) was selected as the primary instrument used to perform FSS of the Crib House/Forebay basement survey unit. As a random sample population, fourteen (14) randomly located static ISOCS measurement locations were designated on accessible structural surfaces within the survey unit. The surface area of the Forebay was deemed as not accessible at the time of the initial FSS of the Crib House as it was flooded and hydraulically connected to Lake Michigan. Based on a measurement Field of View (FOV) of 28 m2 for each random ISOCS measurement, the areal scan surface coverage for the measurements equated to 392 m2, or approximately 3% of the total surface area of the Crib House/Forebay basement survey unit (18,254 m2). In addition, two (2) judgmental ISOCS measurements were taken inside each of the Unit 1 and Unit 2 Circulating Water Intake Pipes, each with a FOV of 78 m2 per measurement, or an additional 312 m2 of areal scan surface coverage. The Forebay surface area that was, and continues to be, submerged equated to a surface area of 5,407 m2, or 30% of the total surface area of the Crib House/Forebay basement survey unit. ZionSolutions TSD 17-006, Underwater Survey Methodology for Zion Nuclear [7]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Station Crib House/Forebay Basement Final Status Survey Unit (Reference 5) was developed for the use of scintillation detectors in dry tubes to acquire radiological data for FSS of the submerged wall surfaces. Fourteen (14) judgmental measurements were taken at biased locations within the Forebay using this survey approach. The results for all ISOCS and gross gamma measurements (random and judgmental) taken in the Crib House/Forebay basement survey unit indicate that the Sum of Fractions (SOF) for each measurement, considering the concentration of all applicable Radionuclides of Concern (ROC), either by direct measurement or by inference, is less than 0.1 when applying the respective Operational Derived Concentration Guideline Levels (OpDCGL) for the Crib House/Forebay from ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey (Reference 6). Therefore, the null hypothesis is rejected and the Crib House/Forebay basement survey unit is acceptable for unrestricted release.
- 2. SURVEY UNIT DESCRIPTION The Crib House/Forebay basement survey unit is a Class 3 basement FSS unit. A basement FSS unit is comprised of the combined internal wall and floor surfaces of each remaining building basement below the 588-foot elevation following demolition. The Crib House/Forebay basement structure is located within Class 1 open land survey units 12204A, 12204B and 12204C.
PICTURE 1 CRIB HOUSE 559 FT ELEVATION [8]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 The 552 foot and 559 foot elevations of the Crib House contained the upper pump housings of the six (6) circulatory pumps, three (3) for Unit 1 and three (3) for Unit 2 that provided cooling water from Lake Michigan to various heat exchangers and condensers in the Turbine Building and Auxiliary Building. In addition, the intake/outtake plenum under the Crib House contained the cooling water outlet from these systems back into the lake. The 552 foot elevation also contained the Crib House sumps and sump system components which served as the collection point for the Crib House drain piping. Prior to demolition, the Crib House was comprised of two main elevations, the 594-foot elevation, which was constructed using cinderblock walls and the 559-foot elevation, which was constructed of concrete walls and floors. The basement 559-foot elevation consisted of a room measuring 171 feet long by 37.5 feet wide, resulting in a floor surface area of 6,412.5 ft2 or 595.74 m2. The basement was accessed by two stairways, one to the north and one to the south from the Crib House 594-foot elevation. The room could also be accessed by a hoist-well from the 594-foot elevation that was located between Circulation Pumps 1A and 2A. The west portion of the basement was sunken to a depth of 552-foot elevation, which housed the sumps and sump pump system valves. The remainder of the 559 foot elevation was mostly unencumbered with the exception of the pump housings from each of the circulation pumps protruding from the floor. PICTURE 2 CRIB HOUSE ENGINEERING PRINT The engineering drawings of the 559-foot and 552-foot elevations indicated that the concrete walls were 4 feet thick and the floor was 2 feet and 6 inches think. The concrete floor was covered with a grey paint. Standing water, to a depth of approximately 1/4 inch, [9]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 surrounded several of the sumps on the 552-foot elevation. In addition, the floor paint at several locations was discolored, indicating frequent contact with water. The 559-foot elevation was dry and relatively free of discoloration. Several catwalks and system piping were suspended from the ceiling of the room. All utilities, including electrical and drain systems were external from the concrete structure and were not embedded. The Forebay structure was built to house and protect offshore water intakes providing cooling water from Lake Michigan to the Circulating Water Pumps, which in turn supplied various heat exchangers and condensers in the Turbine Building. It consisted of poured concrete walls, plate steel reinforcements and steel flow restriction gates along with associated conduits, piping and mechanical actuators. These walls and components began at approximately 596-foot elevation and extended to approximately 537-foot elevation with a mean Lake Michigan level of 577-foot elevation. PICTURE 3 FOREBAY The Circulating Water Pumps took suction on the Forebay and pumped cooling water into the Circulating Water Intake Pipes. The Circulating Water Intake Pipes entered the east side of the Turbine Building beneath the Condenser Water Boxes. The interior surface area of the Circulating Water Intake piping was 4,412 m2, but the only portions that were accessible were the two vertical lengths of 9 feet diameter piping (in each unit) from the 588-foot elevation to the 558-foot elevation (approximate surface area of 158 m2). The Circulating Water Intake Pipes are also located within Class 1 open land Survey Units 12205A, 12205B, 12205C, 12205D and 12205E. The boundaries of the Crib House [10]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 basement footprint were defined using a Global Positioning System (GPS) based on the Illinois State Plane System North American Datum (NAD) 1983 East.
- 3. CLASSIFICATION BASIS The Crib House/Forebay survey unit 08100 was initially classified in the Zion Station Historical Site Assessment (HSA) (Reference 7). The interior 552-foot and 559-foot elevation concrete surfaces in the basement structure survey unit were originally designated as non-impacted. The Crib House/Forebay survey unit was not located in a radiologically controlled area. In addition, no radiological postings or labeled radioactive material were identified in or around the Crib House/Forebay structure, and a Radiation Work Permit (RWP) was not required for entry. The HSA classified the exterior of the building as well as the grounds surrounding the building as MARSSIM Class 2. The HSA classified the Circulating Water Intake Pipe interior surfaces as Class 3.
Fixed residual radioactive material was discovered on the 594-foot elevation of the Crib House in 1985. In addition, the Circulatory Water system was the normal effluent release pathway for the facility during operation. Based upon use, location and previous findings, the MARSSIM classification for the interior of the Crib House was changed from its original classification of non-impacted to a MARSSIM impacted Class 2 classification in accordance with ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification (Reference 8). As part of Site Characterization, ZionSolutions acquired and analyzed twenty (20) concrete core samples taken from the 559-foot elevation of the Crib House in March and April of 2012. Sixteen (16) 6-inch concrete core samples were taken from the floors, and four (4) 6-inch concrete core samples were taken from the lower walls. Sample locations were selected at random. Prior to acquiring the core samples, the area was scanned to ensure the absence of surface radioactive contamination at each sample location. Scans were performed with a Ludlum 43-93 100 cm2 alpha-beta scintillation detector. Gross beta background ranged from 150 cpm to 300 cpm. No activity greater than background was observed by scan. All concrete core samples were analyzed by the on-site gamma spectroscopy system for gamma-emitting radionuclides. Only natural activity expected in background was detected during the analysis. No licensed materials were identified in the samples. A summary of the analyses results for the concrete core samples taken during site characterization are presented in Table 1. [11]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Table 1 - Statistical Quantities for Cs-137 and Co-60 from the 2012 Characterization Survey Cs-137 Co-60 Statistical Quantities (pCi/g) (pCi/g) Maximum Value : 9.24E-02 1.44E-01 Mean : 7.00E-02 1.20E-01 Standard Deviation : 1.07E-02 1.84E-02 On November 17 and 18, 2014, six (6) samples were taken of sediment from the Forebay and Crib House basement while divers were used to install cofferdams and plugs. Analysis of the samples indicated the presence of Cs-137 at concentrations ranging from less than Minimum Detectable Concentration (MDC) to 1.09E-01 pCi/g. No other plant-derived radionuclides were detected. The Crib House above the 588-foot elevation was surveyed for unconditional release in January and February of 2015. Once it was demonstrated that the Crib House internal surfaces were suitable for unconditional release, a demolition contractor salvaged clean equipment out of the Crib House. Unrestricted release surveys were performed in March of 2015 on equipment removed prior to and during the demolition of the upper levels of the Crib House, including the Circulating Water pumps 1A and 1B, Butterfly Disk 1C, Turning Vanes, Rotating Assembly and the interior of the Circulating Water Intake Pipes from the 552 foot elevation of the Crib House. All smear and direct readings were less than MDC. The Crib House structural concrete and cinder block above the 588-foot elevation was also surveyed to demonstrate that the material was free of plant-derived radionuclides at concentrations greater than background. The concrete and cinderblock Crib House structure above the 588 foot elevation was demolished and stockpiled to be used as clean hard fill. Consistent with Section 5.5.2.1 of the LTP, the classification for this survey unit was changed from its original classification to Class 3. The survey units and classifications designated for structures below 588-foot elevation from the HSA that were presented in LTP, Table 2-2 were based on screening values and source term assumptions that are significantly different from the Basement Fill Model (BFM) and were therefore not applicable. At the time of LTP submittal, the Forebay and the Circulating Water Intake Piping were completely underwater and not accessible. Process knowledge and the results of environmental monitoring of radiological conditions at effluent outfalls in the past indicate that the probability of residual radioactivity in these FSS units exceeding 50% of the OpDCGLB for the Crib House/Forebay was very low. The FSS unit for the basement of the Crib House/Forebay and the Circulating Water Intake Pipe were designated as Class 3 as defined in MARSSIM, Section 2.2 in that the FSS unit was not expected to contain any residual radioactivity, or expected to contain levels of [12]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 residual radioactivity at a small fraction of the DCGLs, based on site operating history and previous radiation surveys. The Crib House/Forebay basement FSS unit would be subjected to an areal coverage commensurate with the guidance pertaining to Class 3 scan coverage as presented in MARSSIM, Table 5.9, which states that the scan coverage guidance is judgmental. In this context, judgmental areal coverage was defined as sufficient ISOCS measurements to ensure that at least 1% of the surface area in each survey unit was subjected to FSS. A Radiological Engineer (RE) performed a visual inspection and walk-down of the survey unit on June 25, 2016, prior to performing FSS. The purpose of the walk-down was to assess the physical condition of the survey unit, evaluate access points and travel paths and identify potentially hazardous conditions. A final classification assessment was performed in accordance with procedure ZS-LT-300-001-002, Survey Unit Classification as part of the survey design for FSS. Based upon completion of Survey Unit Classification Basis for final classification, which included a review of the historical information, the results of the Characterization Survey data and completion of a final Survey Unit Classification Worksheet, it was concluded that there was a low probability for the presence of residual radioactivity at concentrations greater than 50% of the OpDCGLs, justifying a final survey unit classification of Class 3. At the time of FSS, the Forebay was still submerged. Following completion of FSS and once compliance with the unrestricted release criteria was successfully demonstrated, the Forebay walls were demolished to the 588-foot elevation and the Forebay was backfilled with clean fill. The Circulating Water Intake piping has also been filled with grout.
- 4. DATA QUALITY OBJECTIVES (DQO)
FSS planning and design hinges on coherence with the Data Quality Objective (DQO) process to ensure, through compliance with explicitly defined inputs and boundaries, that the primary objective of the survey is satisfied. The DQO process, utilized in accordance with MARSSIM is described in the ZSRP LTP. 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 [13]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 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 08100 did not exceed the release criteria specified in the LTP and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA). ZionSolutions TSD 11-001, Technical Support Document for Potential Radionuclides of Concern During the Decommissioning of the Zion Station (Reference 9) established the basis for an initial suite of potential ROC for the decommissioning of the Zion Nuclear Power Station (ZNPS). LTP Chapter 2 provides detailed characterization data that described contamination levels in the basements. The survey data for basements is based on core samples obtained at biased locations with elevated contact dose rates and/or evidence of leaks/spills and analyzed for the presence of plant-derived radionuclides. ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms (Reference 10) evaluates the results of the concrete core analysis data from the Containments and Auxiliary Building and refines the initial suite of potential ROC by evaluating the dose significance of each radionuclide. LTP, Section 6.5.2 discusses the process used to derive the ROC for the decommissioning of ZNPS, including the elimination of insignificant dose contributors (IC) from the initial suite. Based upon the analysis of the mixture, it was determined that Co-60, Ni-63, Sr-90, Cs-134 and Cs-137 accounted for 99.5% of all dose in the non-activated contaminated concrete mixes. Table 2 presents the ROC for the decommissioning of Crib House/Forebay structural surfaces and the normalized mixture fractions based on the radionuclide mixture. [14]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Table 2 - Dose Significant Radionuclides and Mixture
% of Total Activity Radionuclide (normalized)(1)(2)
Co-60 0.92% Cs-134 0.01% Cs-137 75.32% Ni-63 23.71% Sr-90 0.05% (1) Based on maximum percent of total activity from Table 20 of TSD 14-019, normalized to one for the dose significant radionuclides. (2) Does not include dose significant radionuclides for activated concrete (H-3, Eu-152, Eu-154). A fundamental precursor to survey design is to establish a relationship between the release criteria and some measurable quantity. This is done through the development of DCGLs. The DCGLs represent average levels of radioactivity above background levels and are presented in terms of surface or mass activity concentrations. Chapter 6 of the LTP describes in detail the modeling used to develop the DCGLs for structures. The end state basements will be comprised of steel and/or concrete structures which will be covered by at least three feet of clean soil and physically altered to a condition which would not realistically allow the remaining structures, if excavated, to be occupied. The exposure pathways in the BFM are associated with residual radioactivity in floors and walls that is released through leaching into water contained in the interstitial spaces of the fill material. The BFM assumes that the inventory of residual radioactivity in a given building is released either instantly or over time by diffusion, depending on whether the activity is surficial or volumetric, respectively. The activity released into the fill water will adsorb onto the clean fill, as a function of the radionuclide-specific distribution coefficients, resulting in equilibrium concentrations between the fill and the water. Consequently, the only potential exposure pathways after backfilling, assuming the as-left geometry, are associated with the residual radioactivity in the water contained in the fill. The final outputs of the BFM are the Basement Derived Concentration Guideline Levels (DCGL), in units of pCi/m2, which are calculated using the BFM Groundwater (GW) and BFM Drilling Spoils Dose Factors. DCGLs are calculated separately for the GW and Drilling Spoils scenarios and for the summation of both scenarios. The summation DCGL is designated as the Base Case DCGL (BcDCGL) and is used during FSS to demonstrate compliance (analogous to the DCGLW as defined in MARSSIM). The BcDCGLs are radionuclide-specific concentrations that represent the 10 CFR 20.1402 dose criterion of 25 mrem/year and are calculated for each ROC and each backfilled basement. [15]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 When applied to structures, the DCGLs are expressed in units of activity per unit of area (pCi/m2). The unity rule is applied when there is more than one ROC. The measurement results for each singular ROC present in the mixture are compared against their respective DCGL to derive a dose fraction. The BcDCGLs for the unrestricted release of the Crib House/Forebay basement survey unit are provided in Table 3. The IC dose percentage of 5% was used to adjust the Crib House/Forebay Basement BcDCGLs to account for the dose from the eliminated IC radionuclides. Table 3 - Base Case DCGLs for Crib House/Forebay Structural Surfaces (BcDCGLB) from LTP Chapter 5, Table 5-3 Base Case DCGL Radionuclide (pCi/m2) Co-60 5.52E+07 Cs-134 2.13E+07 Cs-137 2.96E+07 Ni-63 3.25E+09 Sr-90 1.16E+06 Each radionuclide-specific BcDCGL 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/year to an Average Member of the Critical Group (AMCG). To ensure that the summation of dose from each source term is 25 mrem/year or less after all FSS is completed, the BcDCGLs are reduced based on an expected, or a priori, fraction of the 25 mrem/year dose limit from each source term. The reduced DCGLs, or Operational DCGLs (OpDCGL), can be related to the BcDCGLs as an expected fraction of dose based on an a priori assessment of what the expected dose should be based on the results of site characterization, process knowledge and the extent of planned remediation. The OpDCGL is then used as the DCGL for the FSS design of the survey unit (calculation of surrogate DCGLs, investigations levels, etc.). Details of the OpDCGLs derived for each dose component and the basis for the applied a priori dose fractions are provided in TSD 17-004. The OpDCGLs for the unrestricted release of the Crib House/Forebay basement survey unit are provided in Table 4. [16]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Table 4 - Operational DCGLs for Crib House/Forebay Structural Surfaces (OpDCGLB) from LTP Chapter 5, Table 5-4 Operational DCGL Radionuclide (pCi/m2) Co-60 2.13E+07 Cs-134 8.20E+06 Cs-137 1.14E+07 Ni-63 1.25E+09 Sr-90 4.47E+05 Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the OpDCGL. The Canberra ISOCS was selected as the primary instrument used to perform FSS of basement surfaces. Survey instrument response checks were required prior to issuance and after the instrument had been used. Control and accountability of survey instruments was required to assure the quality and prevent the loss of data. As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. The actual recorded value was used as the recorded FSS result for measurement and/or sample values that are less than MDC. Negative values were recorded as zero. For radionuclides less than MDC, the value representing the highest abundance was selected. Results were not reported as less than MDC. Sample report summaries included unique sample identification, analytical method, radionuclide, result, uncertainty, laboratory data qualifiers, units, and the observed MDC. In accordance with the LTP, for laboratory analysis, MDCs less than 10% of the OpDCGL were preferable while MDCs up to 50% of the OpDCGL were acceptable. The maximum acceptable MDC for measurements obtained using field instruments was 50% of the applicable OpDCGL.
- 5. SURVEY DESIGN The level of effort associated with planning a survey is based on the complexity of the survey and nature of the hazards. Guidance for preparing FSS plans was provided in procedure ZS-LT-300-001-001 Final Status Survey Package Development.
The DQO process determined that Co-60, Ni-63, Sr-90, Cs-134 and Cs-137 would be the ROC in survey unit 08100. During FSS, concentrations for Hard-to-Detect (HTD) ROC Ni-63 and Sr-90 are inferred using a surrogate approach. Cs-137 is the principle surrogate radionuclide for Sr-90, and Co-60 is the principle surrogate radionuclide for Ni-63. The [17]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 mean, maximum and 95% Upper Confidence Level (UCL) of the surrogate ratios for concrete core samples taken in the Auxiliary Building basement were calculated in TSD 14-019 and are presented in Table 5. The maximum ratios will be used in the surrogate calculations during FSS unless area specific ratios are determined by continuing characterization. Table 5 - Surrogate Ratios Auxiliary Building Ratios Mean Max 95%UCL Ni-63/Co-60 44.143 180.450 154.632 Sr-90/Cs-137 0.001 0.002 0.002 For the FSS of survey unit 08100, the surrogate OpDCGLs for Co-60 and Cs-137 were computed based on the maximum ratios from Table 5. The equation for calculating a surrogate DCGL is as follows: Equation 1 1
=
1 2 3 [( ) + ( ) + ( ) + ( )] 2 3 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide Using the Operational DCGLs presented in Table 4 and the maximum ratios from Table 5, the following surrogate calculations were performed: Equation 2 1 (137) = = 1.08 + 07 /2 1 0.002 [(1.14 + 07 )+( )] (137) 4.47 + 05(90) The surrogate OpDCGL that was used for Cs-137 in this survey unit for direct comparison of measurement results to demonstrate compliance is 1.08E+07 pCi/m2. [18]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Equation 3 1 (60) = = 5.23 + 06 /2 1 180.45 [(2.13 + 07 )+( )] (60) 1.25 + 09(63) The surrogate OpDCGL that was used for Co-60 in this survey unit for direct comparison of measurement results to demonstrate compliance is 5.23E+06 pCi/m2. The action level for investigation in a Class 3 basement structure survey unit is 50% of the OpDCGL. The action levels for survey unit 08100 are presented in Table 6. Table 6 - Action Levels for Survey Unit 08100 ROC DCGL (pCi/m2) Co-60 (1) 2.61E+06 Cs-134 (2) 4.10E+06 Cs-137 (3) 5.40E+06 (1) Based on 50% of surrogate adjusted DCGL of 5.23E+06 pCi/m2 for Co-60 while inferring Ni-63 (2) Based on 50% of Operational DCGL (3) Based on 50% of surrogate adjusted DCGL of 1.08E+07 pCi/m2 for Cs-137 while inferring Sr-90 The Sign Test was selected as the non-parametric statistical test. The use of the Sign Test did not require the selection or use of a background reference area, which simplified survey design and implementation. This approach was conservative since it included background Cs-137 as part of the sample set. The Elevated Measurement Comparison (EMC) did not apply to this survey unit. At the ZSRP, EMC only applies to soils as all other media (structural surfaces, embedded pipe, buried pipe and penetrations) will be remediated to their applicable BcDCGL. In addition, survey unit 08100 is a Class 3 basement survey unit and discrete, elevated areas of contamination were not expected. Sample size determination for FSS of basement surfaces is addressed in LTP, Section 5.5.2.2. To ensure that the number of ISOCS measurements based on the necessary areal coverage in a basement surface FSS unit was sufficient to satisfy a statistically based sample design, a calculation was performed to determine sample size. If the sample size based on the statistical design required more ISOCS measurements than the number of ISOCS measurement required by the areal coverage, then the number of ISOCS measurements was adjusted to meet the larger sample size. [19]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Following the guidance in MARSSIM, the Type I decision error that was used for this calculation was set at 0.05 and the Type II decision error was set at 0.05. The Upper Bound of the Gray Region (UBGR) was set at the OpDCGLB. The Lower Bound of the Gray Region (LBGR) was set at the expected fraction of the OpDCGLB. The expected fraction of the OpDCGLB in a Class 3 FSS basement unit was set at 1%. The standard deviation of the concrete core samples taken in the Crib House was used for sigma () for the Crib House/Forebay. The relative shift (/) was calculated as discussed in LTP, Section 5.6.4.1.6. The / for the survey unit data set is defined as shift (), which is the UBGR, or the OpDCGLB (SOF of 1), minus the LBGR (SOF of 0.01), divided by sigma (), which is the standard deviation of the data set used for survey design. The optimal value for / should range between 1 and 3. The largest value the / can have is 3. If the / exceeds 3, then the value of 3 will be used for /. The / was greater than three (3). Consequently, a value of three was used as the adjusted
/. From Table 5-5 of MARSSIM, the required number of measurements (N) for use with the Sign Test, using a value of 0.05 for the Type I and Type II decision errors, is fourteen (14) measurements for a / value of three. Consequently, the number of ISOCS measurements in Crib House/Forebay basement surface FSS unit was adjusted to meet the larger sample size. Table 7 presents the Crib House/Forebay basement surface FSS unit from LTP, Table 5-19 and the adjusted number of ISOCS measurements required.
Table 7 - Adjusted Minimum Number of ISOCS Measurements Required Adjusted # of Adjusted Adjusted Areal ISOCS Areal Areal FSS Unit Classification Coverage Measurements Coverage Coverage (m2) (FOV-28 m2) (m2) (% of Area) Crib House/Forebay Class 3 138 14 392 3% A Prospective Power Curve was generated using MARSSIM 2000, a software package developed for the implementation of MARSSIM in support of the decommissioning license termination rule (10CFR20, Subpart E). The result of the MARSSIM 2000 computer run showed adequate power for the survey design. The survey design specified fourteen (14) ISOCS measurements for non-parametric statistical testing. As the survey unit was classified as Class 3, sample locations were selected at random. The random locations were selected using Visual Sample Plan (VSP), in accordance with ZS-LT-300-001-001. Input parameters included use of a grid layout and the random sampling tool set with a predetermined number (14) of sample points. Measurement locations for the [20]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 ISOCS measurements taken for random design are listed with the grid coordinates in Table 8. Revision 2 of ZSRP LTP, Section 5.1 states that concrete core samples will be collected during FSS to confirm the HTD to surrogate radionuclide ratios. The FSS of the Crib House/Forebay basement walls and floors were completed prior to issuance of Revision 2 of the LTP when this commitment was made. The upper levels of the Crib House were demolished and removed, and the basement below the 588-foot elevation was backfilled and is no longer accessible. Therefore, no concrete core samples were acquired during FSS of the Crib House/Forebay. However, as previously stated, ZionSolutions acquired and analyzed twenty (20) concrete core samples taken from the 559-foot elevation of the Crib House in March and April of 2012 during site characterization. No plant-derived radioactivity was positively identified at detectable concentrations in any of these samples. Table 8 - Random ISOCS Measurement Locations MEASUREMENT ID GRID NO. B3-08101A-FRWC-001-GM 666 B3-08101A-FRWC-002-GM 70 B3-08101A-FRWC-003-GM 1046 B3-08101A-FRFC-004-GM 208 B3-08101A-FRWC-005-GM 150 B3-08101A-FRWC-006-GM 742 B3-08101A-FRWC-007-GM 32 B3-08101A-FRWC-008-GM 251 B3-08101A-FRFC-009-GM 172 B3-08101A-FRWC-010-GM 1149 B3-08101A-FRWC-011-GM 286 B3-08101A-FRFC-012-GM 830 B3-08101A-FRWC-013-GM 429 B3-08101A-FRWC-014-GM 13 B3-08101A-FQWC-014-GM 13 Fourteen (14) ISOCS measurements were required for the non-parametric statistical test (sample size N = 14). The activity in the Unit 1 and Unit 2 Circulating Water Intake Pipes are included with the Crib House/Forebay basement survey unit through the DCGL [21]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 calculation. The Circulating Water Intake Pipes are located on the south end of the Turbine Building, beneath the Condenser Water Boxes, on the 583-foot elevation. Access to the Circulating Water Intake Pipes was limited; therefore, these areas were surveyed as biased areas using judgmental measurements. The area-weighted mean activity of the judgmental sample population in the Unit 1 and Unit 2 Circulating Water Intake Pipes was added to the random mean activity of the Crib House/Forebay FSS unit results (see Section 14). Sample plans B3-08102A-S and B3-08102B-S were generated for the acquisition of the judgmental ISOCS measurements in these pipes. The survey units for the Circulating Water Intake Pipes consisted of the east and west sections of both Unit 1 and Unit 2 Intake Pipes. The interior of each pipe had a surface area of 440 m2, but the only accessible portions of the survey unit were the two vertical lengths of 9-foot diameter piping from the 588-foot elevation to the 558-foot elevation (approximate surface area of 158 m2). In order to allow access for the ISOCS, a hole was cut into each of the two pipes at the 588-foot elevation. The ISOCS was secured at 90 degrees looking down the 30-foot length of pipe, resulting in a FOV of 78 m2. Locations for the ISOCS measurements taken in the Circulating Water Intake Pipes are listed in Table 9. Table 9 - Circulating Water Intake Pipe Judgmental Measurement Locations MEASUREMENT ID GRID NO. B3-08102AS-FJSM-001-GD 01 B3-08102AS-FJSM-002-GD 02 B3-08102AS-FQSM-002-GD 02 B3-08102BS-FJSM-001-GD 01 B3-08102BS-FJSM-002-GD 02 A map of the judgmental ISOCS measurement locations for the Circulating Water Intake Pipes is provided in Attachment 1. The Forebay surface area that was submerged equated to a surface area of 5,407 m2, or 30% of the total surface area of the Crib House/Forebay basement survey unit. While the surfaces of the Forebay were not accessible for random measurements, due to the large surface area involved, additional judgmental measurements were acquired of the submerged wall surfaces using scintillation detectors in dry tubes for FSS. Sample plan B3-08401A-F was generated for the acquisition of 14 judgmental measurements at biased locations within the Forebay using this survey approach. The mechanics of the survey approach are further described in TSD 17-006. Judgmental locations for the measurements taken with scintillation detectors inside the Forebay are listed with a description of the location in Table 10. [22]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 The implementation of quality control measures as referenced by LTP, Section 5.9 and ZionSolutions ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS) (QAPP) (Reference 11) includes the collection of a replicate measurement at 5% of the measurements taken in a survey unit with the locations selected at random. One ISOCS measurement, B3-08101A-FQWC-014-GM was selected randomly for the replicate measurement. An additional replicate ISOCS measurement, B3-08102AS-FQSM-002-GD was selected for the judgmental measurements taken in the Circulating Water Intake Pipe. As part of the Forebay survey, an additional replicate measurement was also acquired at location B3-08401A-FJQC-014-GD. Table 10 - Forebay Judgmental Measurement Locations MEASUREMENT ID DESCRIPTION B3-08401A-FJWC-001-GD Pier 1, South Side, 2 feet below water line B3-08401A-FJWC-002-GD Pier 2, North Side, 2 feet below water line B3-08401A-FJWC-003-GD Pier 2, South Side, 2 feet below water line B3-08401A-FJWC-004-GD Pier 3, North Side, 2 feet below water line B3-08401A-FJWC-005-GD Pier 3, South Side, 2 feet below water line B3-08401A-FJWC-006-GD Pier 4, North Side, 2 feet below water line B3-08401A-FJWC-007-GD Pier 4, South Side, 2 feet below water line B3-08401A-FJWC-008-GD Pier 5, North Side, 2 feet below water line B3-08401A-FJWC-009-GD 5th Screen Box, NW, 2 ft. below water line B3-08401A-FJWC-010-GD Southeast Wall corner, 2 ft. below water line B3-08401A-FJWC-011-GD East Wall Platform, 2 ft. below water line B3-08401A-FJWC-012-GD East Wall Platform, 2 ft. below water line B3-08401A-FJWC-013-GD East Wall Platform, 2 ft. below water line B3-08401A-FJWC-014-GD Northeast Wall corner, 2 ft. below water line B3-08401A-FJQC-014-GD Northeast Wall corner, 2 ft. below water line The areal coverage requirements for FSS of structures as specified in the LTP is commensurate with the probability that a small area of elevated activity could exist within a FSS unit in a concentration exceeding the BcDCGL and the likelihood that such an area would not be detected by the FSS ISOCS measurements. It is highly unlikely that the ISOCS, with a nominal FOV of approximately 28 m2, would not detect and account for elevated areas. The primary basis used to determine reasonable areal coverage for the ISOCS measurements is the potential for the OpDCGL to be exceeded. The criterion for [23]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 selecting reasonable and risk-informed areal coverage is based on a graded approach similar to the guidance for scan surveys during FSS provided in MARSSIM, where the coverage is based on the expected fraction of the DCGL (in this case, OpDCGL). As a Class 3 survey unit, LTP, Table 5-19, reproduced as Table 7, specifies that a minimum of 392 m2 or 3% of the accessible surface area in this structural basement survey unit will be subjected to scan coverage. The surface area covered by a single ISOCS measurement is large (a nominal range of 10-30 m2), and the FOV of the measurement becomes a substitute for scanning that is typically performed by moving a hand-held detector over the surface in question. Fourteen (14) random ISOCS measurements were taken of Crib House basement surfaces at a stand-off distance of 3 meters. This resulted in a FOV for each measurement of 28 m2. The total areal coverage represented by the 14 ISOCS measurements was 392 m2. In addition, 4 judgmental measurements were taken with the ISOCS secured at 90 degrees looking down the 30-foot length of Circulating Water Intake Pipe, resulting in a FOV for each measurement of 78 m2. These measurements added an additional surface area of 312 m2 to the surface area in this survey unit that was subjected to areal scan coverage. The 704 m2 area actually scanned (by ISOCS FOV) represents approximately 4% of the total surface area (18,254 m2) of the survey unit. A map of the surface area scanned by the ISOCS FOV is provided in Attachment 1. For this Class 3 basement structure survey unit, the Investigation Levels for ISOCS measurement results are those levels specified in LTP, Table 5-25, and are reproduced below in Table 11. Table 11 - Investigation Levels Classification Direct Measurement Class 3 >0.5 OpDCGL Table 12 provides a synopsis of the survey design for survey unit 08100. [24]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Table 12 - Synopsis of Survey Design FEATURE DESIGN CRITERIA BASIS Survey Unit Surface 18,254 m2 LTP, Table 5-23 Area
= 3.66E-09 UBGR = SOF of 1 LBGR = SOF of 0.01 Number of 14 (random) Type I error = 0.05 Measurements (N)
Type II error = 0.05
/ = 3 (adjusted)
MARSSIM Table 5.5 Grid Spacing Random LTP, section 5.6.4.5.2 Co 2.13E+07 pCi/m2 Cs-134 - 8.20E+06 pCi/m2 Operational DCGLs for Crib DCGLs Cs-137 - 1.14E+07 pCi/m2 House/Forebay, Ni 1.25E+09 pCi/m2 LTP, Table 5-4 Sr 4.47E+05 pCi/m2 Investigation Level >0.5 Operational DCGL LTP, Table 5-25 Judgmental areal coverage, Scan Areal Coverage 704 m2 or ~4% areal coverage LTP, Table 5-19 3 measurements selected randomly for QC LTP, Section 5.9 replicate measurement analysis [25]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100
- 6. SURVEY IMPLEMENTATION For survey unit 08100, compliance with the unrestricted release criteria was demonstrated through a combination of direct measurements using the ISOCS and direct measurements using scintillation detectors in dry tubes. LTP, Section 5.1 states that if the concentration of residual gamma radioactivity in an individual measurement exceeds a SOF of 0.1, then a sample will be acquired of the elevated media and analyzed for HTD ROC. This threshold was not encountered during the FSS of survey unit 08100. Consequently, no additional samples were acquired for assessment of HTD ROC.
CRIB HOUSE BASEMENT STRUCTURE FSS field activities commenced in the Crib House basement under FSS Sample Plan B3-08101A-F, which included DQOs, survey design, detailed FSS instructions, job safety analysis, and related procedures for reference. A Field Log (ZS-LT-300-001-001, Attachment 14) was used to document field activities and other information pertaining to the performance of the FSS. FSS field activities were projected to take four (4) working days to complete. Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job. The survey required field activities were performed during normal working hours starting on June 24, 2015, and concluding on June 27, 2015. ZionSolutions TSD 14-022, Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures (Reference 12) provides the initial justification for the selection of reasonably conservative geometries for efficiency calibrations for the ISOCS based on the physical conditions of the remediated surface and the anticipated depth and distribution of activity. Prior to implementing the sample plan for the FSS of the Crib House basement structure, the physical condition of the concrete surfaces to be surveyed were assessed to ensure that the geometry was not significantly changed from that assumed in TSD 14-022. All ISOCS measurements were acquired using the geometry labeled as CRIBHOUSE_3M, which assumed a circular plane source with a contaminant depth of 1/2 inch. With the 90-degree collimation shield installed and a stand-off distance of 3 meters, this orientation corresponded to a nominal FOV of 28 m2. A stand-off guide attached to the detector was used to establish a consistent source to detector distance and center the detector over the selected measurement location. No additional adjustments to ISOCS geometry were deemed necessary. The fourteen (14) random ISOCS measurement locations were marked based on grid coordinates provided by VSP. A replicate measurement was also acquired in the Crib House basement at location B3-08101A-FQWC-014-GM at grid #13. The ISOCS detector was oriented perpendicular to the surface of interest represented by the grid coordinate. [26]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 UNIT 1 AND UNIT 2 CIRCULATING WATER INTAKE PIPES Subsequent FSS field activities were conducted starting on September 16, 2015, under FSS Sample Plans B3-08102A-S and B3-08102B-S, which included the requisite DQOs, survey design, detailed FSS instructions, job safety analysis, and related procedures for obtaining ISOCS measurements within the Unit 1 and Unit 2 Circulating Water Intake Pipes for FSS. A Field Log (ZS-LT-300-001-001 Attachment 14) was used to document field activities and other information pertaining to the performance of the FSS. FSS field activities were projected to take four (4) working days to complete. Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job. The survey required field activities were performed during normal working hours starting on September 16, 2015, and concluding on September 17, 2015. The Circulating Water Intake Pipes are located on the south end of the Turbine Building, beneath the Condenser Water Boxes, on the 583-foot elevation. During facility operation, the Unit 1 and Unit 2 Circulating Water Intake Pipes provided cooling water from Lake Michigan to various heat exchangers and condensers in the Turbine Building. The area to be surveyed consisted of the east and west portions of both Intake Pipes. The only access to the interior of the pipe were the two vertical lengths of 9-foot diameter pipe that ran from 588 foot elevation to the 558 foot elevation (approximate surface area of 158 m2). In order to allow access for insertion of the ISOCS, a hole was cut into each of these two pipes at the 588 foot elevation. The ISOCS was then secured at 90 degrees looking down the 30 foot length of pipe. Prior to implementing this sample plan, the physical geometry of the ISOCS measurements in the Circulating Water Intake Pipe were assessed to determine if the geometry were significantly different from that assumed in TSD 14-022. In accordance with the general approach and methods described in TSD 14-022, the efficiency calibrations for the ISOCS measurements in the Intake Pipe were modified to meet the unique geometry encountered in the pipes. The geometry assumed that the detector was positioned perpendicular inside of a cylinder with the exposed face of the detector positioned at a distance of 9.1 meters from the bottom of the pipe surface. The depth of contamination was assumed at 1/2 inch. All measurements were taken using Efficiency ID 3M_TURBINE, which assumed a FOV of 78 m2. Two (2) judgmental ISOCS measurement locations were selected within the Unit 1 Circulating Water Intake Pipe, and two (2) judgmental ISOCS measurement locations were selected within the Unit 2 Circulating Water Intake Pipe. A replicate measurement was also acquired in the Unit 1 Circulating Water Intake Pipe at location B3-08102AS-FQSM-002-GD. [27]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 FOREBAY STRUCTURE FSS field activities were conducted in the Forebay under FSS Sample Plan B3-08401A-F, which included DQOs, survey design, detailed FSS instructions, job safety analysis, and related procedures for reference. The Forebay is considered part of the Crib House basement structure. During the FSS of the Crib House basement, the surface area of the Forebay was deemed as not accessible as it was flooded and directly hydraulically connected to Lake Michigan. Consequently, the selection of a Forebay surface for the acquisition of a random measurement was not possible. The 14 judgmental measurements taken under sample plan B3-08401A-F in the Forebay were intended to supplement the FSS that was performed in the Crib House basement in June of 2015. The radiological survey data that was acquired by the implementation of sample plan B3-08401A-F was the result of specialized measurement methodology using scintillation detectors deployed in dry tubes. TSD 17-006 describes the basis for this methodology. Prior to implementing this sample plan, the physical condition of the surfaces to be surveyed in the Forebay were assessed to determine if the geometry was significantly different from that assumed in TSD 17-006. The assessment confirmed that the geometry used for the efficiency calibrations was valid. The scintillation detector was deployed vertically in a dry tube positioned adjacent to the surface of each designated measurement location. The FOV was equivalent to the surface area of the conformal source utilized during the detectors efficiency determination. Each survey measurement location was made reproducible by utilizing permanent markings on the Forebay walls above the waterline. Measurements were acquired using this approach at fourteen (14) biased locations selected within the Forebay. A replicate measurement was also acquired at location B3-08401A-FJQC-014-GD.
- 7. SURVEY RESULTS Direct measurements were acquired at each random location in the Crib House basement and at the four judgmental locations in the Circulating Water Intake Pipe using the ISOCS.
A summary of the results of the fourteen (14) ISOCS measurements taken for non-parametric statistical testing results is provided in Table 13. The concentrations for Ni-63 and Sr-90 were inferred based on the maximum ratios as specified in Table 5. The complete ISOCS gamma spectroscopy reports are presented in Attachment 7. The basic statistics for the random measurements are summarized in Table 14. [28]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Table 13 - Summary of Gamma Spectroscopy Results for ISOCS Measurements Comprising the Statistical Sample Population Co-60 Cs-134 Cs-137 Ni-63 Sr-90 MEASUREMENT ID (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B3-08101A-FRWC-001-GM 0.00E+00 1.74E+02 2.78E+02 0.00E+00 5.56E-01 B3-08101A-FRWC-002-GM 0.00E+00 4.99E+01 1.73E+01 0.00E+00 3.46E-01 B3-08101A-FRWC-003-GM 1.02E+02 1.07E+01 5.54E+01 1.84E+04 1.11E-01 B3-08101A-FRFC-004-GM 1.84E+02 3.88E+01 1.00E+02 3.33E+04 2.01E-01 B3-08101A-FRWC-005-GM 0.00E+00 1.23E+02 0.00E+00 0.00E+00 0.00E+00 B3-08101A-FRWC-006-GM 1.52E+02 0.00E+00 1.75E+02 2.74E+04 3.49E-01 B3-08101A-FRWC-007-GM 0.00E+00 9.15E+01 9.17E+01 0.00E+00 1.83E-01 B3-08101A-FRWC-008-GM 3.44E+01 2.69E+02 0.00E+00 6.20E+03 0.00E+00 B3-08101A-FRFC-009-GM 1.44E+02 0.00E+00 0.00E+00 2.59E+04 0.00E+00 B3-08101A-FRWC-010-GM 9.72E+01 2.13E+01 0.00E+00 1.75E+04 0.00E+00 B3-08101A-FRWC-011-GM 5.30E+01 2.22E+01 6.57E+01 9.57E+03 1.31E-01 B3-08101A-FRFC-012-GM 5.53E+01 9.56E+00 3.24E+01 9.97E+03 6.48E-02 B3-08101A-FRWC-013-GM 2.86E+01 1.68E+02 0.00E+00 5.16E+03 0.00E+00 B3-08101A-FRWC-014-GM 7.28E+00 0.00E+00 0.00E+00 1.31E+03 0.00E+00 Table 14 - Basic Statistical Properties of Random ISOCS Measurements Mean Median Max Min Std. Dev. BcDCGL Avg. SOF Avg. Dose ROC (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) per ROC Per ROC Co-60 6.12E+01 4.37E+01 1.84E+02 0.00E+00 6.38E+01 5.52E+07 1.11E-06 2.77E-05 Cs-134 6.98E+01 3.05E+01 2.69E+02 0.00E+00 8.37E+01 2.13E+07 3.28E-06 8.19E-05 Cs-137 5.82E+01 2.49E+01 2.78E+02 0.00E+00 8.20E+01 2.96E+07 1.97E-06 4.92E-05 Ni-63 1.10E+04 7.88E+03 3.33E+04 0.00E+00 1.15E+04 3.25E+09 3.40E-06 8.50E-05 Sr-90 1.16E-01 4.97E-02 5.56E-01 0.00E+00 1.64E-01 1.16E+06 1.00E-07 2.51E-06 The mean SOF compared against the BcDCGLs (BcSOF) from random measurements taken on basement structural surfaces in survey unit 08100 is 9.85E-06. This equates to a dose of 2.46E-04 mrem/year. This is derived by summing the average BcSOF per ROC resulting from the average concentration in Table 14. There were no identified elevated areas. The implementation of required QC measures included the collection of one additional ISOCS measurement at location #14 (B3-08101A-FQWC-014-GM) for replicate measurement analysis. The replicate ISOCS measurement results are provided in Table 15. [29]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 The concentration for Ni-63 and Sr-90 were inferred based on the maximum ratios as specified in Table 5. Table 15 - Summary of ISOCS Replicate Measurement for QC Co-60 Cs-134 Cs-137 Ni-63 Sr-90 MEASUREMENT ID (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B3-08101A-FQWC-014-GM 7.95E+01 7.98E+01 4.89E+01 1.44E+04 9.78E+05 Acknowledging that no concrete cores were taken during the FSS of the Crib House, two of the twenty concrete core samples taken during characterization (concrete cores B2-08101A-BJFC-007-CV and B2-08201-CJWC-A018-CV) were retrieved from the archives and analyzed for the full suite of radionuclides to ensure compliance with the FSS material sampling requirements of the approved LTP Revision 2. The results are provided in Table
- 16. The Eberline reports for the sample analysis are also provided in Attachment 8. Residual concentrations of Eu-155 were positively detected but at concentrations with derived dose substantially less than the IC dose adjustments of 5% made to the DCGLs. All other potential plant-derived radionuclides were less than MDC.
For the samples submitted for full isotopic analysis, Tc-99 was initially identified as positively detected at concentrations greater than MDC. Upon consultation with the laboratory, false positives for Tc-99 can be caused by noise equivalent for the analytical technique and an absolute value that is less than the MDC is not appropriate for a beta liquid scintillation method when the MDC is +/- 200% of the value. With concurrence of the laboratory, the positively identified Tc-99 initially identified during the full isotopic analysis of samples from this survey unit was changed to a false positive. [30]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONSZu= SURVEY UNIT 08100 All Energy~Company Table 16 - Summary of Full Suite Concrete Core Analysis by Eberline B2-08101A-BJFC-007-CV (0.5-1.0 in) B2-08101A-BJFC-007-CV (0.0-0.5 in) B2-08201A-CJWC-018-CV (0.0-0.5 in) B2-08201A-CJWC-018-CV (0.5-1.0 in) Nuclides Result Uncert. MDC Result Uncert. MDC Result Uncert. MDC Result Uncert. MDC (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) (pCi/g) H-3 6.35E+00 5.68E+00 9.48E+00 4.97E+00 3.43E+00 5.67E+00 4.02E+00 3.34E+00 5.56E+00 6.41E+00 3.46E+00 5.64E+00 C-14 0.00E+00 4.03E-01 6.91E-01 0.00E+00 3.63E-01 6.28E-01 0.00E+00 3.91E-01 6.81E-01 0.00E+00 3.69E-01 6.41E-01 Mn-54 0.00E+00 1.23E+02 1.52E+02 0.00E+00 1.31E+02 1.78E+02 0.00E+00 2.03E+02 3.28E+02 0.00E+00 1.56E+02 1.90E+02 Fe-55 0.00E+00 2.08E+00 3.04E+00 7.56E-01 2.76E+00 4.46E+00 0.00E+00 3.22E+00 5.12E+00 1.34E+00 2.55E+00 4.30E+00 Ni-59 7.38E-02 1.97E-01 3.17E-01 1.10E-02 2.98E-01 4.67E-01 1.08E-01 3.31E-01 5.28E-01 3.79E-02 2.76E-01 4.38E-01 Co-60 1.19E-01 4.80E-01 7.55E-01 0.00E+00 5.59E-01 7.34E-01 0.00E+00 1.52E+00 1.60E+00 6.65E-02 1.81E-01 8.74E-01 Ni-63 7.46E-01 1.42E+00 2.41E+00 4.56E-01 1.39E+00 2.36E+00 0.00E+00 1.41E+00 2.44E+00 5.54E-01 1.41E+00 2.38E+00 Sr-90 0.00E+00 3.25E-02 6.96E-02 2.48E-02 3.32E-02 6.82E-02 0.00E+00 2.69E-02 6.12E-02 3.48E-03 2.83E-02 6.04E-02 Nb-94 1.51E-01 1.20E-01 2.46E-01 1.74E-02 1.98E-01 2.70E-01 2.62E-01 3.39E-01 5.03E-01 0.00E+00 2.12E-01 2.82E-01 Tc-99 1.29E+00 7.36E-01 1.21E+00 2.07E+00 6.99E-01 1.13E+00 9.57E-01 5.63E-01 9.30E-01 1.71E+00 6.65E-01 1.08E+00 Ag-108m 0.00E+00 1.41E-01 2.06E-01 0.00E+00 2.77E-01 2.37E-01 0.00E+00 3.91E-01 4.55E-01 1.31E-01 1.19E-01 2.29E-01 Sb-125 1.05E+00 2.55E+00 4.60E+00 0.00E+00 3.40E+00 4.75E+00 0.00E+00 6.44E+00 9.17E+00 0.00E+00 3.21E+00 4.56E+00 Cs-134 0.00E+00 1.27E+00 3.23E+00 4.82E-01 1.88E+00 3.99E+00 0.00E+00 6.77E+00 7.60E+00 0.00E+00 1.33E+00 4.46E+00 Cs-137 0.00E+00 2.28E-01 3.10E-01 1.15E-01 2.37E-01 3.78E-01 8.97E-02 4.50E-01 6.93E-01 2.52E-01 2.28E-01 4.02E-01 Eu-152 0.00E+00 8.27E-01 9.63E-01 2.89E-01 8.81E-01 9.93E-01 0.00E+00 2.31E+00 1.19E+00 8.30E-02 6.27E-01 1.02E+00 Eu-154 0.00E+00 8.76E-01 6.04E-01 4.41E-01 9.70E-01 6.53E-01 0.00E+00 1.86E+00 8.00E-01 4.39E-01 8.07E-01 6.61E-01 Eu-155 1.69E+00 1.08E+00 1.65E+00 6.54E-02 1.28E+00 1.85E+00 4.58E-01 1.26E+00 1.94E+00 0.00E+00 1.16E+00 1.69E+00 Np-237 4.84E-02 6.93E-02 1.14E-01 7.53E-02 7.65E-02 1.03E-01 4.18E-02 5.04E-02 6.17E-02 4.72E-02 7.22E-02 1.23E-01 Pu-238 0.00E+00 4.37E-02 1.25E-01 0.00E+00 4.81E-02 1.14E-01 0.00E+00 5.91E-02 1.75E-01 0.00E+00 6.72E-02 1.83E-01 Pu-239/240 0.00E+00 3.89E-02 8.16E-02 0.00E+00 6.21E-02 1.34E-01 1.72E-02 5.27E-02 1.25E-01 4.02E-02 8.70E-02 1.72E-01 Pu-241 2.44E+00 7.59E+00 1.29E+01 0.00E+00 7.51E+00 1.29E+01 7.81E+00 9.44E+00 1.59E+01 0.00E+00 1.01E+01 1.76E+01 Am-241 2.06E-02 5.15E-02 1.07E-01 4.23E-02 5.13E-02 6.24E-02 0.00E+00 4.50E-02 1.27E-01 1.73E-02 5.61E-02 1.16E-01 Am-243 5.82E-02 7.03E-02 8.58E-02 2.02E-01 3.46E-01 6.07E-01 1.14E-01 1.16E-01 1.56E-01 6.77E-02 7.96E-02 1.17E-01 Cm-243/244 8.35E-02 7.99E-02 8.57E-02 1.24E-02 2.98E-02 6.24E-02 4.05E-02 6.63E-02 1.16E-01 6.71E-02 7.25E-02 1.05E-01 [31]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Two (2) judgmental ISOCS measurements were taken within the Unit 1 Circulating Water Intake Pipe, and 2 judgmental ISOCS measurements were taken within the Unit 2 Circulating Water Intake Pipe. A summary of the results of the 4 judgmental ISOCS measurements taken within the Circulating Water Intake Pipes are provided in Table 17. The concentration for Ni-63 and Sr-90 were inferred based on the maximum ratios as specified in Table 5. The complete ISOCS gamma spectroscopy reports are presented in Attachment 7. Table 17 - Summary of Gamma Spectroscopy Results for Judgmental ISOCS Measurements Taken in Circulating Water Intake Pipes Co-60 Cs-134 Cs-137 Ni-63 Sr-90 MEASUREMENT ID (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B3-08102AS-FJSM-001-GD 1.20E+02 1.38E+03 1.90E+02 2.16E+04 3.80E-01 B3-08102AS-FJSM-002-GD 0.00E+00 4.59E+02 2.64E+02 0.00E+00 5.28E-01 B3-08102BS-FJSM-001-GD 4.20E+03 2.30E+02 6.16E+02 7.58E+05 1.23E+00 B3-08102BS-FJSM-002-GD 3.16E+04 2.78E+02 2.08E+03 5.71E+06 4.15E+00 A replicate ISOCS measurement was also acquired in Unit 1 Circulating Water Intake Pipe at location B3-08102AS-FQSM-002-GD. A summary of the results for the QC replicate measurement is provided in Table 18. The concentration for Ni-63 and Sr-90 were inferred based on the maximum ratios as specified in Table 5. Table 18 - Summary of ISOCS Replicate Measurement for QC Co-60 Cs-134 Cs-137 Ni-63 Sr-90 MEASUREMENT ID (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B3-08102AS-FQSM-002-GD 3.61E+01 0.00E+00 0.00E+00 6.52E+04 0.00E+00 Fourteen (14) judgmental measurements were taken within the Forebay using scintillation detectors deployed in dry tubes. A summary of the results of the 14 judgmental measurements taken within the Forebay are provided in Table 19. Each measurement represents the net gamma result at that location in units of pCi/m2. Using the normalized gamma mixture from Table 2, a concentration for each of the gamma-emitting ROC was calculated. The concentrations for Ni-63 and Sr-90 were then inferred based on the maximum ratios as specified in Table 5. [32]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Table 19 - Summary of Results for Judgmental Measurements Taken in the Forebay Co-60 Cs-134 Cs-137 Ni-63 Sr-90 MEASUREMENT ID (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B3-08401A-FJWC-001-GD 6.48E+03 7.08E+01 5.33E+05 1.17E+06 1.07E+03 B3-08401A-FJWC-002-GD 6.65E+03 7.27E+01 5.48E+05 1.20E+06 1.10E+03 B3-08401A-FJWC-003-GD 6.46E+03 7.06E+01 5.32E+05 1.17E+06 1.06E+03 B3-08401A-FJWC-004-GD 6.74E+03 7.37E+01 5.55E+05 1.22E+06 1.11E+03 B3-08401A-FJWC-005-GD 5.78E+03 6.32E+01 4.76E+05 1.04E+06 9.52E+02 B3-08401A-FJWC-006-GD 6.15E+03 6.73E+01 5.07E+05 1.11E+06 1.01E+03 B3-08401A-FJWC-007-GD 6.65E+03 7.27E+01 5.48E+05 1.20E+06 1.10E+03 B3-08401A-FJWC-008-GD 5.96E+03 6.51E+01 4.90E+05 1.08E+06 9.81E+02 B3-08401A-FJWC-009-GD 7.11E+03 7.77E+01 5.85E+05 1.28E+06 1.17E+03 B3-08401A-FJWC-010-GD 7.11E+03 7.77E+01 5.85E+05 1.28E+06 1.17E+03 B3-08401A-FJWC-011-GD 6.96E+03 7.61E+01 5.73E+05 1.26E+06 1.15E+03 B3-08401A-FJWC-012-GD 7.15E+03 7.82E+01 5.89E+05 1.29E+06 1.18E+03 B3-08401A-FJWC-013-GD 6.52E+03 7.13E+01 5.37E+05 1.18E+06 1.07E+03 B3-08401A-FJWC-014-GD 8.22E+03 8.98E+01 6.77E+05 1.48E+06 1.35E+03 A replicate measurement was acquired in the Forebay at location B3-08401A-FJQC-014-GD. A summary of the results for the QC replicate measurement is provided in Table 20. Table 20 - Summary of Replicate Measurement Taken in Forebay for QC Co-60 Cs-134 Cs-137 Ni-63 Sr-90 MEASUREMENT ID (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) B3-08401A-FJQC-014-GD 8.61E+03 9.41E+01 7.09E+05 1.55E+06 1.42E+03 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. [33]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 The equation for the unity rule is: Equation 4 C1 C2 Cn
.......... .. 1 DCGL1 DCGL 2 DCGL n Where: Cn = concentration of radionuclide n DCGLn = DCGL of radionuclide n.
The results of the unity rule calculation (OpSOF) for the ROC for the random ISOCS measurements for survey unit 08100 using OpDCGLs are provided in Table 21. Table 21 - Sum of Fractions for Random ISOCS Measurements FRACTION OF OpDCGL MEASUREMENT ID OpSOF Co-60 Cs-134 Cs-137 Ni-63 Sr-90 B3-08101A-FRWC-001-GM 0.00E+00 2.12E-05 2.44E-05 0.00E+00 1.24E-06 4.68E-05 B3-08101A-FRWC-002-GM 0.00E+00 6.08E-06 1.52E-06 0.00E+00 7.74E-08 7.68E-06 B3-08101A-FRWC-003-GM 4.78E-06 1.30E-06 4.86E-06 1.47E-05 2.48E-07 2.59E-05 B3-08101A-FRFC-004-GM 8.65E-06 4.73E-06 8.81E-06 2.66E-05 4.49E-07 4.92E-05 B3-08101A-FRWC-005-GM 0.00E+00 1.50E-05 0.00E+00 0.00E+00 0.00E+00 1.50E-05 B3-08101A-FRWC-006-GM 7.12E-06 0.00E+00 1.53E-05 2.19E-05 7.81E-07 4.51E-05 B3-08101A-FRWC-007-GM 0.00E+00 1.12E-05 8.04E-06 0.00E+00 4.10E-07 1.96E-05 B3-08101A-FRWC-008-GM 1.61E-06 3.28E-05 0.00E+00 4.96E-06 0.00E+00 3.94E-05 B3-08101A-FRFC-009-GM 6.75E-06 0.00E+00 0.00E+00 2.07E-05 0.00E+00 2.75E-05 B3-08101A-FRWC-010-GM 4.56E-06 2.59E-06 0.00E+00 1.40E-05 0.00E+00 2.12E-05 B3-08101A-FRWC-011-GM 2.49E-06 2.70E-06 5.77E-06 7.66E-06 2.94E-07 1.89E-05 B3-08101A-FRFC-012-GM 2.60E-06 1.17E-06 2.84E-06 7.89E-06 1.45E-07 1.47E-05 B3-08101A-FRWC-013-GM 1.34E-06 2.05E-05 0.00E+00 4.13E-06 0.00E+00 2.59E-05 B3-08101A-FRWC-014-GM 3.42E-07 0.00E+00 0.00E+00 1.05E-06 0.00E+00 1.39E-06 B3-08101A-FQWC-014-GM 3.73E-06 9.73E-06 4.29E-06 1.15E-05 2.19E-07 2.94E-05 Number of Random Measurements = 14 # of Random Measurements with OpSOF > 1 = 0 Max Individual Random Measurement OpSOF = 4.92E-05 Mean Random Measurement OpSOF = 2.56E-05 The results of the unity rule calculation (OpSOF) for the judgmental ISOCS measurements taken in the Circulating Water Intake Pipe using OpDCGLs are provided in Table 22. [34]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Table 22 - Sum of Fractions for Judgmental ISOCS Measurements Taken in the Circulating Water Intake Pipe FRACTION OF OpDCGL MEASUREMENT ID OpSOF Co-60 Cs-134 Cs-137 Ni-63 Sr-90 B3-08102AS-FJSM-001-GD 5.26E-06 1.68E-04 1.67E-05 1.73E-05 8.50E-07 2.08E-04 B3-08102AS-FJSM-002-GD 0.00E+00 5.60E-05 2.31E-05 0.00E+00 1.18E-06 8.03E-05 B3-08102AS-FQSM-002-GD 1.70E-05 0.00E+00 0.00E+00 5.21E-05 0.00E+00 6.91E-05 B3-08102BS-FJSM-001-GD 1.97E-04 2.80E-05 5.40E-05 6.07E-04 2.75E-06 8.89E-04 B3-08102BS-FJSM-002-GD 1.49E-03 3.39E-05 1.82E-04 4.57E-03 9.28E-06 6.28E-03 Number of Judgmental Measurements = 4 # of Judgmental Measurements with OpSOF > 1 = 0 Max Judgmental Measurement OpSOF = 6.28E-03 Mean Judgmental Measurement OpSOF = 1.86E-03 The results of the unity rule calculation (OpSOF) for the judgmental measurements taken in the Forebay using the OpDCGLs are provided in Table 23. Table 23 - Sum of Fractions for Judgmental Gamma Measurements Taken in the Forebay FRACTION OF OpDCGL MEASUREMENT ID OpSOF Co-60 Cs-134 Cs-137 Ni-63 Sr-90 B3-08401A-FJWC-001-GD 3.04E-04 8.64E-06 4.68E-02 9.35E-04 2.39E-03 5.04E-02 B3-08401A-FJWC-002-GD 3.12E-04 8.87E-06 4.80E-02 9.60E-04 2.45E-03 5.18E-02 B3-08401A-FJWC-003-GD 3.03E-04 8.61E-06 4.66E-02 9.32E-04 2.38E-03 5.03E-02 B3-08401A-FJWC-004-GD 3.16E-04 8.98E-06 4.87E-02 9.73E-04 2.48E-03 5.25E-02 B3-08401A-FJWC-005-GD 2.72E-04 7.71E-06 4.18E-02 8.35E-04 2.13E-03 4.50E-02 B3-08401A-FJWC-006-GD 2.89E-04 8.20E-06 4.44E-02 8.88E-04 2.27E-03 4.79E-02 B3-08401A-FJWC-007-GD 3.12E-04 8.87E-06 4.80E-02 9.60E-04 2.45E-03 5.18E-02 B3-08401A-FJWC-008-GD 2.80E-04 7.94E-06 4.30E-02 8.60E-04 2.19E-03 4.64E-02 B3-08401A-FJWC-009-GD 3.34E-04 9.48E-06 5.13E-02 1.03E-03 2.62E-03 5.53E-02 B3-08401A-FJWC-010-GD 3.34E-04 9.48E-06 5.13E-02 1.03E-03 2.62E-03 5.53E-02 B3-08401A-FJWC-011-GD 3.27E-04 9.27E-06 5.02E-02 1.00E-03 2.56E-03 5.42E-02 B3-08401A-FJWC-012-GD 3.36E-04 9.54E-06 5.17E-02 1.03E-03 2.64E-03 5.57E-02 B3-08401A-FJWC-013-GD 3.06E-04 8.69E-06 4.71E-02 9.42E-04 2.40E-03 5.08E-02 B3-08401A-FJWC-014-GD 3.86E-04 1.10E-05 5.94E-02 1.19E-03 3.03E-03 6.40E-02 B3-08401A-FJQC-014-GD 4.04E-04 1.15E-05 6.22E-02 1.24E-03 3.17E-03 6.70E-02 Number of Judgmental Measurements = 14 # of Judgmental Measurements with OpSOF > 1 = 0 Max Judgmental Measurement OpSOF = 6.40E-02 Mean Judgmental Measurement OpSOF = 5.32E-02 [35]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 In order to assess the dose contribution from the Circulating Water Intake Pipe and the Forebay, the concentration of each ROC in each judgmental measurement was also compared against the respective BcDCGLs. This was accomplished using the same method that was used to calculate the mean BcSOF for the random measurements. The calculation of the mean BcSOF for the Circulating Water Intake Pipes is presented in Table 24 and the calculation of the mean BcSOF for the Forebay is presented in Table 25. Table 24 - Calculation of Mean BcSOF for Judgmental Measurements Taken in the Circulating Water Intake Pipes Using BcDCGLs Mean BcDCGL Avg SOF ROC (pCi/m2) (pCi/m2) per ROC Co-60 8.99E+03 5.52E+07 1.63E-04 Cs-134 5.86E+02 2.13E+07 2.75E-05 Cs-137 7.86E+02 2.96E+07 2.66E-05 Ni-63 1.62E+06 3.25E+09 4.99E-04 Sr-90 1.57E+00 1.16E+06 1.36E-06 7.17E-04 Mean BcSOF Table 25 - Calculation Mean BcSOF for Judgmental Measurements Taken in the Forebay Using BcDCGLs Mean BcDCGL Avg SOF ROC (pCi/m2) (pCi/m2) per ROC Co-60 6.71E+03 5.52E+07 1.22E-04 Cs-134 7.34E+01 2.13E+07 3.44E-06 Cs-137 5.52E+05 2.96E+07 1.87E-02 Ni-63 1.21E+06 3.25E+09 3.73E-04 Sr-90 1.10E+03 1.16E+06 9.53E-04 2.01E-02 Mean BcSOF
- 8. QUALITY CONTROL Three (3) replicate measurements were taken during the FSS of this basement structure.
Measurement B3-08101A-FQWC-014-GM was taken with the random measurement population acquired in the Crib House basement, measurement B3-08102AS-FQSM-002-GD was taken with the judgmental measurements taken in the Circulating Water Intake Pipes and measurement B3-08401A-FJQC-014-GD was taken with the judgmental gamma measurements taken in the Forebay. The measurement results were evaluated using USNRC acceptance criteria specified in Inspection Procedure No. 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring (Reference 13). There was [36]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 acceptable agreement between replicate measurement results taken in the Crib House basement and in the Forebay. Comparison of the replicate ISOCS measurements collected from measurement location #2 inside the Unit 1 Circulating Water Intake Pipe was inconclusive. The Cs-137 concentration for both measurements was less than instrument MDC. The reported result for the comparison measurement was a negative value (- 1.76E+02 pCi/m2, thus resulting in a reported concentration of 0.00E+00 pCi/m2). K-40 could not be substituted as the comparison measurement was also negative. As two additional QC samples were taken in this survey unit with acceptable comparison, no further action was deemed necessary. Refer to Attachment 5 for data and quality control analysis results.
- 9. INVESTIGATIONS AND RESULTS No measurements were taken for an investigation during the performance of FSS in this survey unit.
- 10. REMEDIATION AND RESULTS Historically, no radiological remedial action as described by MARSSIM Section 5.4 was performed in this survey unit prior to or as a result of the FSS. Chapter 4 of the ZSRP LTP determined that remediation beyond that required to meet the release criteria is unnecessary and that the remaining residual radioactivity in basement concrete was ALARA.
- 11. CHANGES FROM THE FINAL STATUS SURVEY PLAN There were no addendums to the FSS plan.
- 12. DATA QUALITY ASSESSMENT (DQA)
The DQO sample design and data were reviewed in accordance with ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment (Reference 14) for completeness and consistency. Documentation was complete and legible. Surveys and the collection of measurements were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 3. The analytical results of all samples were less than a OpSOF of one. Additionally, the maximum activity for each ROC did not exceed 10% of their respective OpDCGL for the Crib House/Forebay. Although MARSSIM states that the Sign Test need not be performed in the instance that no measurements surpass the DCGL, the test was conducted to demonstrate coherence to the [37]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 statistical principles of the DQO process. The Sign Test (Attachment 3) was performed on the data and compared to the original assumptions of the DQOs. The evaluation of the Sign Test results clearly demonstrates that the survey unit passes the unrestricted release criteria, thus, the null hypothesis is rejected. The preliminary data review consisted of calculating basic statistical quantities (e.g., mean, median, standard deviation). All data was considered valid including negative values, zeros, values reported below the MDC, and values with uncertainties greater than two standard deviations. The mean and median values for each ROC were well below the respective OpDCGLs. Also, the retrospective power curve showed that a sufficient number of samples were collected to achieve the desired power. Therefore, the survey unit meets the unrestricted release criteria with adequate power as required by the DQOs. The data for Co-60 and Cs-137 is represented graphically through a frequency plot and a quantile plot. All graphical representations are provided in Attachment 6.
- 13. ANOMALIES No anomalies were observed during the performance or analyses of the survey.
- 14. COMPLIANCE EQUATION There are four distinct source terms for the end-state at Zion: backfilled basements, soil, buried piping and groundwater. Demonstrating compliance with the dose criterion requires the summation of dose from the four source terms (see Equation 6-11 from LTP, Section 6-17).
The final compliance dose will be calculated using LTP Equation 6-11 after FSS has been completed in all survey units. The results of the FSS performed for each FSS unit will be reviewed to determine the maximum dose from each of the four source terms (e.g., basement, soil, buried pipe and existing groundwater if applicable) using the mean BcSOF of FSS systematic and random results plus the dose from any identified elevated areas. The compliance dose must be less than 25 mrem/year. The dose contribution from each ROC is accounted for using the BcSOF to ensure that the total dose from all ROC does not exceed the dose criterion. The term for each basement includes the dose contributions from wall and floor surfaces within the basement, the dose contribution from embedded pipe within the basement, the dose contribution from penetrations within the basement and the dose contribution from concrete fill in the basement when clean concrete debris was used as fill. Each (structural surfaces, embedded pipe, and penetrations) are surveyed separately during FSS. The dose from clean concrete fill is predetermined in accordance with LTP, Table 5-16, which is [38]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 conservatively based on a maximum allowable MDC of 5,000 dpm/100cm2. The dose from fill assigned to the Crib House/Forebay is 1.57 mrem/year, which equates to a SOF of 0.063. Basement surface area adjustments (i.e., increases) were applied to the structure surface DCGL calculation for certain basements to ensure that the DCGLs accounted for the contribution of residual radioactivity from basements/structures that cannot, on their own, support a water supply well but were hydraulically connected to a basement that could support a well. One of these structures is the Circulating Water Intake Pipes. The surface area adjustments resulted in lowering the DCGL concentrations (pCi/m2) in the Crib House/Forebay by requiring the allowable total activity to be uniformly distributed over the larger, combined surface areas. The activity in the Circulating Water Intake Pipes is included in both the Crib House/Forebay and the Turbine Building basement. The Intake Pipe was grouted which essentially eliminated the hydraulic connections, however, in calculating the BcDCGLs, the hydraulic connections to the Intake Pipe were assumed to be fully regained in the future after degradation of the isolation barriers and grout. The BcDCGL for the Crib House/Forebay accounts for the activity in the Circulating Water Intake Pipes by summing the surface areas. In accordance with LTP, Table 6-23, the combined summed surface area of the Crib House/Forebay and Circulating Water Intake Pipe is 18,254 m2. The total area is broken down as follows: the Crib House has a surface area of 8,435 m2, the Circulating Water Intake Pipe has a surface area of 4,412 m2 and the Forebay has a surface area of 5,407 m2. Equation 5-9 from LTP Chapter 5 was used to sum the residual activity in the Crib House structure, Forebay structure and Circulating Water Intake Pipes on an area-weighted basis. The result is provided in Equation 5. Equation 5 8,435 4,412 5,407 {( ) (9.85 06 )} + {( ) (7.17 04 )} + {( ) (2.01 02 )} = 0.006 18,254 18,254 18,254 The adjusted BcSOF for the Crib House/Forebay basement structure is 0.006. This equates to a dose of 0.153 mrem/year. The adjusted BcSOF for the Crib House/Forebay is then used in the following equation to calculate BcSOFBASEMENT for the Crib House/Forebay. [39]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 Equation 6
= + + +
where: BcSOFBASEMENT = BcSOF (mean of FSS systematic results plus the dose from any identified elevated areas) for backfilled basements BcSOFB = BcSOF for structural survey unit(s) within the basement (mean of FSS systematic results plus the dose from any identified elevated areas) BcSOFEP = BcSOF for embedded pipe survey unit(s) within the basement (mean of FSS systematic results plus the dose from any identified elevated areas) BcSOFPN = BcSOF for penetration survey unit(s) within the basement (mean of FSS systematic results plus the dose from any identified elevated areas) BcSOFCF = BcSOF for clean concrete fill (if applicable) based on maximum MDC during Unrestricted Release Survey (URS) There are no penetrations or embedded pipe associated with the Crib House/Forebay basement. Consequently, the dose contribution from both (variables BcSOFEP and BcSOFPN) are zero. The BcSOFBASEMENT value for the Crib House/Forebay is then derived as follows: Equation 7
= 0.006 + 0.000 + 0.000 + 0.063 = 0.069 The BcSOFBASEMENT for the Crib House/Forebay basement is 0.069. This SOF equates to a dose of 1.723 mrem/year TEDE to an AMCG from residual radioactivity in the Crib House/Forebay basement.
- 15. CONCLUSION Survey unit 08100 has met the DQOs of the FSS plan. The ALARA criteria as specified in Chapter 4 of the LTP were achieved. The EMC is not applicable to structural surfaces and remediation was not required.
All identified ROC were used for statistical testing to determine the adequacy of the survey unit for FSS. Evaluation of the data shows that none of the ROC concentration values [40]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100 exceeds the Operational DCGL or any investigational levels; therefore, in accordance with the LTP Section 5.10, the survey unit meets the release criterion. 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 was properly classified as Class 3. The dose contribution from structural surfaces in Survey Unit 08100, Crib House/Forebay Basement, is 0.153 mrem/year TEDE, based on the average concentration of the ROC in measurements used for non-parametric statistical sampling as well as judgmental measurements taken in the Forebay and the Circulating Water Intake Pipes on an area-weighted basis (mean BcSOF = 0.006). The dose from embedded pipe and penetrations in the Crib House/Forebay is zero and the dose from clean fill is 1.57 mrem/yr. The total dose attributed to the Crib House/Forebay as a summation of all dose components is 1.723 mrem/year. Survey Unit 08100, Crib House/Forebay Basement, is acceptable for unrestricted release.
- 16. REFERENCES
- 1. ZionSolutions procedure ZS-LT-300-001-005, Final Status Survey Data Reporting
- 2. Zion Station Restoration Project License Termination Plan
- 3. ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development
- 4. NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual
- 5. ZionSolutions TSD 17-006, Underwater Survey Methodology for Zion Nuclear Station Crib House/Forebay Basement Final Status Survey Unit
- 6. ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey
- 7. Zion Station Historical Site Assessment
- 8. ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification
- 9. ZionSolutions TSD 11-001, Technical Support Document for Potential Radionuclides of Concern During the Decommissioning of the Zion Station
- 10. ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms
- 11. ZionSolutions ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS)
[41]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTJONSllc-1v1enervyso,t,A;Q,gCompany SURVEY UNIT 08100
- 12. ZionSolutions TSD 14-022, Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures
- 13. U.S. NRC Inspection Procedure No. 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring
- 14. ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment
- 17. ATTACHMENTS Attachment 1 - Figures and Maps Attachment 2 - ISOCS Geometry Attachment 3 - Sign Test Attachment 4 - Forebay Judgmental Measurements Attachment 5 - QC Measurement Assessments Attachment 6 - Graphical Presentations Attachment 7 - ISOCS Reports Attachment 8 - Eberline Analytical Reports
[42]
ATTACHMENT 1 FIGURES AND MAPS [43]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100
~
ZIONSOl.lnJONS
~
Legend 8 3mx3mGrid I" South wall 12m North wall r 588' Original Grid 14 15 16 17 I 1 2 3 4 9m 18 19 20 21 11m 5 6 7 8 Alternate Grid 558' L I 22 23 Sm 24 25 26 9 13 10 11 12 558' Crib House North & South Wall
}:~ 3m 552' I\_ RWC-014-GM QWC-014--GM Circ. Water Pump Room 552' Crib house north & south wall circ. water pump room 552' FSS Crib House 83-08101AF
[44]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS;;;= An Ene,vySOll,(ions Company SURVEY UNIT 08100
~
ZIONSOWTIONS
~
Legend /r-j RWC-007-GM )
/ 52m *wr 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 G 3m x3m Grid em 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 -L 35 36 37 38 42 45 39 40 41 43 44 46 47 48 49 50 51 Selected Grid ~RWC-003-GMI 52m L ~I l 1*)--1' ~
I I\<,I a I z l':1, I s
~
l'rr ll I lZ r** u/1 l~ I t I
~~
- 1§ lZ 11 Circ. Water PumJ> Room East Walls 552 & 558' FFS Crib House *.
,, __ , Circ. water ,/ Penetration Pipe 83-08101AF
[45]
------ 43-l - -
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100
~
ZION 8aJJTIONS Legend 0 3mx3mGrid S2m Original Grid 1 2 3 4 5 6 7 8
,,.. 9 , r.
10 11 12 13 14 15 16 17 D 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 Alternate Grid 35 36
, ...- 37 38 ,./-39 , 40 41 v 42--. 43 i
44
.,~ 45 46 47 . ,,---, 48 49 v ....5R 51 I I ~--- II I ) I I 52 l!L-:, 54 55 ,;e 57 58 60 ' - -M,-/ _ff( ' --.59' 62 63 65 66 68 ~RWC-005-GMl Crib House Pumr Room West Wal 552' FSS Crib House ' Service water B3-08101AF ) penitration pipe / --...... Service water .__ .., i penetration pipe
[46] fLl41
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS;;;= An Ene,vySOll,(ions Company SURVEY UNIT 08100
~
ZION~<--*~-,v Legend 0 3mx3mGrid 52m I rRFC-009-GM D Original Grid 1 4m 1 2 3 4 5 6 7 8 9 11\ 11 12 13 14 15 16 17 D Alternate Grid t 8m 18 35 1C 19 36 20 37 21 38 s 22
~
23 40 2A
~
41
~-<
42 26 43 27 44 14 2& 45 29 46 J(j 47 21 31 48 32 49 33 50 2C 34 51 L 52 53 54 55 56 57 58 59 60 61 I 62 63 64 65 66 87 66
~RFC-004-GM Crib House Circ. Water Pump Room Floors 552' & 558' FSS Crib House B3-08101AF
[47]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100
~ Intake tunnel ZION Sa.lJTKJNS I
11 12 ,. ,. 15 18 10 Legend Intake dividing column
/ ~~WC-OOB-GMI .--r----,r----,---1~ -, ,---,--.....----..-----.
17 10 19 20 21 32 33 35 38 0 3mx3mGrids 22 '3 24 25 28 37 38 39 O 41 Alternate Grid Top View
- Intake tunnel = 90m
- 7 O
- North & south wall
&a . 70 - Intake dividing column= 214m * - North & south walls = 284m
- 50 51 f 72 73 Intake floor= 122m
- Vertical west wall = 52m
- Sloping west wall = 80m *
~WC-011-G~ S$ 54 .. ' /1 75 76 Overfleed of intake tunnel = 30m
- _ 56 57 71 76 79 80 1 92 113 B
. 50 61 92 113 Circ. Water Floor Vertical wut wall Overhead of Intake Structure ~~
91 Intake tunnel [":[:~I} I 90 1A I 92 93 9 i19 12 FSS Crib House Side View f . Y'
. Sloping west wall 1 1 12' B3-08101AF 99 1 \
113 h4 f 123 124 110 I \ 101 ~12 1, 116 117 110 104 115 1 p [48] 107 1 6 11 f461
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS -;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100 Intake tunnel
~
ZIONSouJnoNs ~ .. - - :.: - Top
- 1 *
-~ 1 3 6 ~
- 11 12 15
! ' '--- ~
10 " "
,~-
Legend l r *
~ "f Intake dividing column 18m ! i 51' I ,I 17 18 10 20 21 32 33 34 ** ..1
[!J 3mx3mGrid I -- *- Top
*1 ; Top I 22 23 24 2,5 28 37 38 39 40 Alternate Grid I
I ! ,, .. ... - ~ ,. ,. I
- _._ . ~~
r- ,.- - Intake tunnel "' 9Dm ' Intake dividing column"' 214m' Top View Top 47 . ** North & south walls iJ 68 70
,.,+----<RWC-013-GMI - North & south walls "' 284m ' so 51 \ If 72 ./ - Intake floor"' 122m ' - - Vertical west wall
- 52m '
,
- El Sloping west wall "' 80m *
.., 34 .. ' I. ,. 76 Overhead of Intake tunnel = 30m ' . 51 .\ \
1// 18 10 80 1 82 83 84 80 81 62
"' i -: J[]
BOiiom ., .. Floor Circ. Water ~ Vertical west wall 91 Intake Structure 90 18
.. "'I ,2 93 . I :1 13I 1 111 2 L[I I~ I FSS Crib House 83-08101AF Side View f
101 104 96
,412 115 \*1 1p 1(
1 ~ Sloping west wall 113 11& 114' 111 115 118 m 1 24 10 [49] 107 118 f471
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=.An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100
;;:::::=-
ZIONs<<urioNs .. .~- - ,..._...,,, Top 1 3 4 I
- I , I. 8
- 10
~
14 15 18 Legend 51' I 17 18 19 2ll 21 32 33 34 35 se l 0 3m x 3m Grids 22 23 ,. .
~ -- . 37 39 40 41' j
ap Original Grid Top Top View 47 59 Alternate Grid 72 73 150 Intake tunnel = 90m ' Intake dividing column = 214m
- North & south walls = 284m
- RWC-OOH3M 53 75 76 58 7il 150
- Intake floor= 122m
- Vertical west wall = 52m '
~ Sloping west wall = 80m '
overhead of intake tunnel = 30m ' l50 a,. 82 B3 94 j eanam Circ. Water i L_~ , T :* 91 Intake Structure ' 1111 2A 92 93 94 L~_'==_= _= _=_=_= _= _== f 911
\"
9 121
. 11 12:
FSS Crib House Side View 99 ,123
'" 124 B3-08101AF .~.
113 114 115
\
101 ~)2 10 11, 117 104 16 107 10 [50]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100
~ Intake 11.nnel ZIONSoumoNs Top RWC-006-GM GrNn -11118.ke t\n'lel"' 90m
- 1 *'<l Red - Intake dividing 00UM
- 214m '
Legend :.-,~m::00..~:~~1:~* 11 ..:6 J,*~ Oottedbrown - Vertioalwaatwall*52m ' 1t"-1tt Helmed brUWfl
- Sk:,ph,g west wall
- 80m ' 1,.::.11*,
Pi.rpla:-Owrhead of lntllm Ull'llf: 30m ' 111Ht..C Tall!II aurrace araa
- 945m' 11 32 33 34 . .,
0 3m x 3m Grids 22 37 . 39 40
"( ' op j
Original Grid North & south wall >: * ** -
*-- *i ., l.. ~:J ~
Altemate Grid
** t'.:, &a ro Top View "" 51 \ /} 72 73 Intake tunnel = 90m '
intake dividing column= 214m' 53 . 56' Vt ,
/ / 14 75 76 - North & south walls = 284m ' - Intake floor= 122m
- IRFC-012-GM~
/1 78 79 56 - - Vertical west wal = 52m '
Sloping west wall = 80m ' _ Overhead of intake tunnel = 30m ' 60 ., 62 ~1 11 82 84 Floor Circ. Water Vertical west wall Intake Structure Overhead of
} 90 91 intake tunnel I
2B ,J 93 94 FSS Crib House 1/ 5 96
\"' RWC-010-GM B3-08101AF r . 1 p Sloping west wall , it~ 114 o, 'f15 Side V iew /01 ~ l2 10
[51] 11>!
' . '~
10 Original Grid #19 Service Water Pump Space 2B 107 *Is
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS -;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100 Top
~
ZIONSoulnoNs 10 11 14 Legend r-----*---- .... ------------** 0 3m x 3m Grids 17 22 18 23 19 24 20 25 21 28 80,., 32 37 33 38 34 39 35 40 3fl 41 ,I Alternate Grid Top View RWC-002-GM 6t,J 69 70
- Intake tunnel = 90m '
Intake dividing column= 214m ' North & south walls = 284m ' Intake floor= 122m '
'f ?r/1 1
72 75 73 70
- - Vertlcal west wall = 52m ' =* Sloping west wall
- 80m '
_ Overhead of intake tunnel = 30m ' Alternate Grid #12 - Clrc. Water common Sump
,- /1 78 79 80 1 82 .l ~*-- --
I-- ** ' 11.*: *- ~ - Circ. Water Intake Structure -~ ID 80 91 2C 92 93 94 h9 12 FSS Crib House
)s . l\ *1 12 B3-08101AF Side View . 99 11) 113 114 115 11 1/123 124 \ \
101 ,4 )2 1C 1-----118 1-..111---- 118 104 1~ 1 B [52] 107 118 10
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100
~
ZION8oumoNs Legend Alternate Grid #54 Clrc. Water Intake Structure 2C
- *** ~
19 2 lin Sump RWC-002-GM 0 3m x 3m Grids
*,-EH] ';' 7 Eulwoll 8 11 12 Wfltw.11
[Il] 6,11 WJ 6:-n Original Grid 9 1 13 114 I t==:::::::::1- ! I e **- " -r.-,*- **: -- 5.n ******.J
- Overhead= 17.3557m ' - Floor= 17.3557m ' - North wall = 29.4062m ' Top South wall = 29.4062m ' ~ iG ~ - East wall = 29.4062m
- 28
- West wall= 29.4062m' Total= 152.3362m
- i,.. '.. . -- -- ~--~
Circ. Water
.J n
Common Sump FSS Crib House _J B3-08101AF North to South View [53] East to West View
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100 West Wall
~
ZION Soun>>NS 1 2 3 4 legend 5 6 D 3mx3mGrid South Wall North Wall Original Grid East Wall
- West Well = 74.88m
- I
* - - Sloping East wall = 62.4m ' 16 17 I - East wall= 17.94m' r RWFC-010-GMI North well =
South well = 22.22.442m2m'* I 18 19 I Total:::; 62.78m' I Sloping East Wall Alternate Grid #114 Service Water Clrc. Water Intake PumJ> Space Top Structure 2B 2B r* FSS Crib House B3-08101AF I ._____I1_c .___1B__,___ 1 A____JII'--2A__,__,~H== I 2s= lfL----- I 2c___J [54] 52
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100 Forebay - Figure 1 001 003 007 South side South side South side 2 feet 2 feet 2 feet below below below water line water line
-t 005 South sid 2 feet below
[55]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100 Forebay - Figure 2 r [56]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100 Forebay - Figure 4 [57]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100 Forebay - Figure 5 [58]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100 Forebay - Figure 6 [59] [57]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS-;;;=. An EnefllYSoi\Jrtlns Compeny SURVEY UNIT 08100 Forebay - Figure 7 [60]
ATTACHMENT 2 ISOCS GEOMETRY [61]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS,,c-""EnergySoMionseo,,,p.,,y SURVEY UNIT 08100 A Geometry Composer Report CANBERRA Date: Thursday, October 26, 2017 - 09:47:16
Description:
CRIBHOUSE 3M Comment: CR!BHOUSE 3M File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\ORCULAR_PLANE\CRIBHOUSE 3M .geo Software: !SOCS Template: ORCULAR_PLANE, Version: (default) Detector: 5456 Collimator: 50mm-90d new (newISOCS 50mm side 90deg collimation [large hole collimator]) Environment: Temperature= 22 °C, Pressure= 760 mm Hg, Relative Humidity= 30% Integration: Convergence = 1.00%, MDRPN = 24 (16), CRPN = 24 (16) Dimensions (m) No. Description d.1 d.2 d.3 d..4 d.5 d.6 Matenal Density Rel. Cone:. 1 Side Walls 0 6 none 2 Laver 1 0.0127 concrete 2.3 1.00 3 Layer 2 0 I <none> 4 Layer 3 0 I <none> 5 Layer 4 0 <none> 6 Layer 5 0 I I <none> 7 Layer 6 0 <none> 8 Layer 7 0 I <none> 9 Layer 8 0 I <none> 10 11 Layer 9 Layer 10 0 0 I II I
<none> <none>
12 Absorber! I I 13 Absorber2 I 14 Source-Detector 3 0 0 0 0 List of energies for efficiency curve generation 59.5 63.3 88.0 122.1 143.8 165.9 185.7 238.6 351.9 391.7 583.2 661.7 898.0 911.6 1001.0 1173.2 1332.S 1460.7 1764.5 1836.1 [60] [62]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS;;;=. AnEnergySoiudon&Compaf!Y SURVEY UNIT 08100 Interpolated Efficiency Calibration Curve j 11; Measured - - CalcLMated j 3.Se-00 5 I 3e-OO 5 11/ \
~-- I'-...__ I 2.Se-00 5 I i~ ___ ¢'-
2e-005 I
--+--.i.
1.Se-005
--------- 1e-005 Se-006 0 --
1..- I 0 500 1000 1500 2000 2500 Energy (keV) Datasource: C:\GENIE2K\CAMFILES\CERNIPF .CNF [62] [63]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS;;;=. AnEnergySoiudon&Compaf!Y SURVEY UNIT 08100 A Geometry Composer Report CANBERRA Date: Thursday, October 26, 2017 - 09:47: 16
Description:
CRIBH0USE 3M Comment: CRIBH0USE 3M File Name: C:\GENIE2K\isocs\data\GE0METRY\In-Situ\ORCULAR_PLANE\CRIBH0USE 3M.geo Software: IS0CS Template: ORCULAR_PLANE, Version: (default) [61] Paqe , ofJ. [64]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS,,c- ""EnergySoMionseo,,,p.,,y SURVEY UNIT 08100 A Geometry Composer Report CANBERRA Date: Wednesday, October 18, 2017 - 10:03:19
Description:
3M TURBINE Comment: 3M TURBINE File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\ORCULAR_PLANE\3M TURBINE.gee Software: !SOCS Template: CIRCULAR_PLANE, Version: (default) Detector: 5456 Collimator: 50mm-90d old (oldISOCS 50mm side 90deg collimation [large hole collimator]) Environment: Temperature = 22 °C, Pressure = 760 mm Hg, Relative Humidity = 30% Integration: Convergence = 1.00%, MDRPN = 24 (16), CRPN = 24 (16) Dimensions (m) No. Description d.1 d,2 d.3 dA d,5 d.6 Material Density Rel. Cone. 1 Side Walls 0.016002 2.7432 csteel 7.9 2 Layer 1 9.144 I dryair 0.0013 0.90 3 Layer 2 0.016002 I csteel 7.9 0.10 4 Laver 3 0 <none> 5 Layer 4 0 <none> 6 Layer 5 0 ! <none> 7 Layer 6 0 <none> 8 Layer 7 0 I <none> 9 L.ayerB 0 <none> 10 L.ayer9 0 <none> 11 Layer 10 0 <none> 12 Absorber! I 13 Absorber2 14 Source-Detector 0.3048 0 0 0 0 List of energies for efficiency curve generation 59.5 63.3 88.0 122.1 143.8 165.9 185.7 238.6 351.9 391.7 583.2 661.7 898.0 911.6 1001.0 1173.2 1332.5 1460.7 1764.5 1836.1 A [63] Paqe 1 of 2 [65]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS;;;=. AnEnergySoiudon&Compaf!Y SURVEY UNIT 08100 A Geometry Composer Report CANBERRA Date: Wednesday, October 18, 2017 - 10:03:19
Description:
3M TURBINE Comment: 3M TURBINE File Name: C:\GENIE2K\isocs\data\GEOMETRY\In-Situ\CIRCUlAR_PLANE\3M lURBINE.geo Software: ISOCS Template: CIRCULAR_PLANE, Version: (default) [64] Paqe 2 of 2 [66]
FSS RELEASE RECORD - REV. 2 ~ CRIB HOUSE / FOREBAY BASEMENT = ZIONSOLUTIONS;;;= Anf"91g)'Solutioml~ SURVEY UNIT 08100 Interpolated Efficiency Calibration Curve I CT Measured - - Calculated I 3.5e-00 5
,,)~ \
3e-00 5
/I "'I '--{~ --~
i,1 2.5e-005 t I I ....._ 2e-005 I -------+
*----.1.
l I 1.5e-005 1e-005 ., 5e-006 I..., 0 f.I<- 0 500 1000 1500 2000 2500 Energy (keV) Datasource: C:\GENIE2K\CAMFILES\CERNIPF.CNF [67]
ATTACHMENT 3 SIGN TEST [68]
FSS RELEASE RECORD - REV. 2 CRIB HOUSE / FOREBAY BASEMENT
~ = ZIONSOLUTIONS;.-zc=
SURVEY UNIT 08100 AnEnergySoiulion&Compar,y Sign Test - Crib House/Forebay Survey Area 08000 Survey Area Crib House/Forebay Survey Unit 08101 Survey Unit Structural Surfaces Classification 3 Type I Error 0.05 Number of Measurements 14 SOF
# 1-Ws Sign (Ws) 1 0.00005 1.00 +1 2 0.00001 1.00 +1 3 0.00003 1.00 +1 4 0.00005 1.00 +1 5 0.00002 1.00 +1 6 0.00005 1.00 +1 7 0.00002 1.00 +1 8 0.00004 1.00 +1 9 0.00003 1.00 +1 10 0.00002 1.00 +1 11 0.00002 1.00 +1 12 0.00001 1.00 +1 13 0.00003 1.00 +1 14 0.00000 1.00 +1 Number of positive differences (S+) 14 Critical Value 10 The Survey Unit MEETS the Acceptance Criteria
[69]
ATTACHMENT 4 FOREBAY JUDGMENTAL MEASUREMENTS [70]
FSS RELEASE RECORD - REV. 2 CRIB HOUSE / FOREBAY BASEMENT
~ = ZIONSOLUTIONS;;;=.
SURVEY UNIT 08100 An EnefllYSoi\itions Company Forebay Judgmental Measurements Measurement Location MDC Bkgd Measurement Co-60 (1) Cs-134 (1) Cs-137 (1) (dpm/cm ) 2 (pCi/m ) 2 (cpm) Gross cpm Net cpm Eff. Net dpm dpm/cm2 (pCi/m ) 2 (pCi/m ) 2 (pCi/m ) 2 (pCi/m2) B3-08401A-FJWC-001-GD 58 260935 72 370 298 0.003 116270 120 5.40E+05 6.48E+03 7.08E+01 5.33E+05 B3-08401A-FJWC-002-GD 58 260935 72 378 306 0.003 119391 123 5.54E+05 6.65E+03 7.27E+01 5.48E+05 B3-08401A-FJWC-003-GD 58 260935 72 369 297 0.003 115880 119 5.38E+05 6.46E+03 7.06E+01 5.32E+05 B3-08401A-FJWC-004-GD 58 260935 72 382 310 0.003 120952 125 5.62E+05 6.74E+03 7.37E+01 5.55E+05 B3-08401A-FJWC-005-GD 58 260935 72 338 266 0.003 103785 107 4.82E+05 5.78E+03 6.32E+01 4.76E+05 B3-08401A-FJWC-006-GD 52 235568 65 348 283 0.003 110417 114 5.13E+05 6.15E+03 6.73E+01 5.07E+05 B3-08401A-FJWC-007-GD 52 235568 65 371 306 0.003 119391 123 5.54E+05 6.65E+03 7.27E+01 5.48E+05 B3-08401A-FJWC-008-GD 52 235568 65 339 274 0.003 106906 110 4.97E+05 5.96E+03 6.51E+01 4.90E+05 B3-08401A-FJWC-009-GD 52 235568 65 392 327 0.003 127585 132 5.93E+05 7.11E+03 7.77E+01 5.85E+05 B3-08401A-FJWC-010-GD 58 260935 72 399 327 0.003 127585 132 5.93E+05 7.11E+03 7.77E+01 5.85E+05 B3-08401A-FJWC-011-GD 52 235568 65 385 320 0.003 124854 129 5.80E+05 6.96E+03 7.61E+01 5.73E+05 B3-08401A-FJWC-012-GD 52 235568 65 394 329 0.003 128365 132 5.96E+05 7.15E+03 7.82E+01 5.89E+05 B3-08401A-FJWC-013-GD 52 235568 65 365 300 0.003 117050 121 5.44E+05 6.52E+03 7.13E+01 5.37E+05 B3-08401A-FJWC-014-GD 58 260935 72 450 378 0.003 147483 152 6.85E+05 8.22E+03 8.98E+01 6.77E+05 B3-08401A-FJQC-014-GD 52 235568 65 461 396 0.003 154506 159 7.18E+05 8.61E+03 9.41E+01 7.09E+05 (1) Inferred using normalized gamma mixture [71]
ATTACHMENT 5 QC MEASUREMENT ASSESSMENTS [72]
FSS RELEASE RECORD - REV. 2 CRIB HOUSE / FOREBAY BASEMENT
~ = ZIONSOLUTIONS;.-zc=
SURVEY UNIT 08100 AnEnergySoiulion&Compar,y Replicate Measurement Assessment Survey Unit # 08000 Survey Unit Name Crib House/Forebay Basement Sample Plan # B308101A Sample
Description:
Comparison of duplicate ISOCS measurements collected from measurement location #10. The standard measurement was B3-08101AF-RWC-014-GM, the comparison sample was B3-08101AF-QWC-014-GM. STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (Y/N) Cs-137 0.00E+00 2.38E+02 0.00 0.5 - 2.0 7.83E+01 1.76E+02 0 N K-40 4.12E+04 6.36E+03 6.47 0.5 - 2.0 3.71E+04 5.63E+03 0.9 Y Comments/Corrective Actions: The Cs-137 Table is provided to show acceptance criteria concentration for both measurements was less used to assess split samples. than instrument MDC. The reported result for the standard measurement was a negative value Resolution Agreement Range (-1.035E+02 pCi/m2, thus resulting in a reported 4-7 0.5 - 2.0 concentration of 0.00E+00 pCi/m2). Consequently, as insufficient data was reported 8 - 15 0.6 - 1. 66 for Cs-137, K-40 was substituted for the 16 - 50 0.75 - 1.33 comparison. There was acceptable agreement 51 - 200 0.80 - 1.25 when using K-40. No further action is necessary. >200 0.85 - 1.18 [73]
FSS RELEASE RECORD - REV. 2 CRIB HOUSE / FOREBAY BASEMENT
~ = ZIONSOLUTIONS;.-zc=
SURVEY UNIT 08100 AnEnergySoiulion&Compar,y Replicate Measurement Assessment Survey Unit # 08000 Survey Unit Name Circ Water Intake Pipe Sample Plan # B308102S Sample
Description:
Comparison of duplicate ISOCS measurements collected from measurement location #2 inside the Unit 1 Circ Water Intake Pipe. The standard measurement was B3-08102AS-FJSM-002-GD, the comparison sample was B3-08102AS-FQSM-002-GD. STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (Y/N) Cs-137 2.64E+02 2.54E+03 0.10 0.5 - 2.0 0.00E+00 2.27E+03 0 N Comments/Corrective Actions: The Cs-137 Table is provided to show acceptance criteria concentration for both measurements was less used to assess split samples. than instrument MDC. The reported result for the comparison measurement was a negative value Resolution Agreement Range (-1.759E+02 pCi/m2, thus resulting in a reported 4-7 0.5 - 2.0 concentration of 0.00E+00 pCi/m2). Consequently, as insufficient data was reported
- 8. 15 0.6 - 1. 66 for Cs-137, K-40 could not be substituted as the 16 - 50 0.75 - 1.33 comparison measurement was also negative. As 51 - 200 0.80 - 1.25 two additional QC samples were taken in this >200 0.85 - 1.18 survey unit with acceptable comparison, no further action was deemed necessary
[74]
FSS RELEASE RECORD - REV. 2 CRIB HOUSE / FOREBAY BASEMENT
~ = ZIONSOLUTIONS;.-zc=
SURVEY UNIT 08100 AnEnergySoiulion&Compar,y Replicate Measurement Assessment Survey Unit # 08000 Survey Unit Name Forebay Sample Plan # B308401AF Sample
Description:
Comparison of duplicate NaI measurements collected from measurement location #14 in the Forebay. The standard measurement was B3-08401A-FJWC-014-GD, the comparison sample was B3-08401A-FJQC-014-GD. STANDARD COMPARISON ROC Activity Standard Resolutio Agreement Activity Standard Comparison Acceptable Value Error n Range Value Error Ratio (Y/N) Gross 6.85E+05 N/A N/A +20% 7.18E+05 N/A N/A Y Comments/Corrective Actions: The Cs-137 Table is provided to show acceptance criteria concentration for both measurements was inferred used to assess split samples. from gross gamma results using the non-activated mixture from LTP Table 5-2. As the standard Resolution Agreement Range agreement method was not applicable to gross 4-7 0.5 - 2.0 gamma results, the samples were in agreement if the gross gamma values were with + 20%. The
- 8. 15 0.6 - 1. 66 gross gamma values were within 6%. 16 - 50 0.75 - 1.33 Consequently, the agreement between the two 51 - 200 0.80 - 1.25 measurements were deemed acceptable. >200 0.85 - 1.18
[75]
ATTACHMENT 6 GRAPHICAL PRESENTATIONS [76]
FSS RELEASE RECORD - REV. 2 CRIB HOUSE / FOREBAY BASEMENT
~ = ZIONSOLUTIONS;.-zc=
SURVEY UNIT 08100 AnEnergySoiulion&Compar,y Quantile Plot for Co-60 Survey Unit: 08101
Description:
CRIB HOUSE/FOREBAY STRUCTURAL Mean: 6.12E+01 pCi/m2 2.00E+02 1.80E+02 1.60E+02 Concentration (pCi/m2) 1.40E+02
- 1.20E+02 1.00E+02 ~~
8.00E+01 6.00E+01 4.00E+01 2.00E+01
- 0.00E+00 ..,,
~ ~ ,~
0% 20% 40% 60% 80% 100% Percentage [77]
FSS RELEASE RECORD - REV. 2 CRIB HOUSE / FOREBAY BASEMENT
~ = ZIONSOLUTIONS ;.-zc=
SURVEY UNIT 08100 AnEnergySoiulion&Compar,y Quantile Plot for Cs-137 Survey Unit: 08101
Description:
CRIB HOUSE/FOREBAY STRUCTURAL Mean: 5.82E+01 pCi/m2 3.00E+02 2.50E+02 Concentration (pCi/m2) 2.00E+02 1.50E+02 1.00E+02 ......., 5.00E+01
,~
0.00E+00 ...,
~ ~ ~
0% 20% 40% 60% 80% 100% Percentage [78]
FSS RELEASE RECORD - REV. 2 CRIB HOUSE / FOREBAY BASEMENT
~ = ZIONSOLUTIONS;.-zc=
SURVEY UNIT 08100 AnEnergySoiulion&Compar,y Histogram for Co-60 Survey Unit: 08101
Description:
CRIB HOUSE/FOREBAY STRUCTURAL Mean: 6.12E+01 pCi/m2 Median: 4.37E+01 pCi/m2 ST Dev.: 63.762445 Skew: 0.743206 10 9 8 7 Frequency 6 5 4 3 2 1 0 3.07E+01 6.14E+01 9.22E+01 1.23E+02 1.54E+02 1.84E+02 Upper End Value (pCi/m2) Upper Value Observation Observation Frequency % 3.07E+01 6 43% 6.14E+01 3 21% 9.22E+01 0 0% 1.23E+02 2 14% 1.54E+02 2 14% 1.84E+02 1 7% TOTAL 14 [79]
FSS RELEASE RECORD - REV. 2 CRIB HOUSE / FOREBAY BASEMENT
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SURVEY UNIT 08100 AnEnergySoiulion&Compar,y Histogram for Cs-137 Survey Unit: 08101
Description:
CRIB HOUSE/FOREBAY STRUCTURAL Mean: 5.82E+01 pCi/m2 Median: 2.49E+01 pCi/m2 ST Dev.: 82.014195 Skew: 1.791894 10 9 8 7 Frequency 6 5 4 3 2 1 0 4.63E+01 9.26E+01 1.39E+02 1.85E+02 2.32E+02 2.78E+02 Upper End Value (pCi/m2) Upper Value Observation Observation Frequency % 4.63E+01 8 57% 9.26E+01 3 21% 1.39E+02 1 7% 1.85E+02 1 7% 2.32E+02 0 0% 2.78E+02 1 7% TOTAL 14 [80]
FSS RELEASE RECORD - REV. 2 CRIB HOUSE / FOREBAY BASEMENT
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SURVEY UNIT 08100 An EnergySoiulion&Compar,y Retrospective Power Curve for Survey Unit Iu ecision Errors Required Sample Sizel Ir Survey Survey unit ID: Alpha: B. eta: l;nit: 14 Radionuclide: junity Rule Stati?tical Test 7 I0.05 ..:.J I0.05 ..:.J I
- r. Stgn Test ,----------------------,
DCGL jl.785 r WRS Test 0 1.785 Critical *alue: S.igma J-0221 ..!.J 10 L_BGR jo_ 8925 cr = 40-385
...:J Probability that the Survey Unit Passes Click 1.0 anywhere on the graph to 0.8 update the power curve using nei,vly 0.6 entered param eter 0.4 alttes 0.2 0.0 ,-
1 )% 3)% 5)% 7)% 9)% 1)0%110% True Survey Unit Concentration (percent of DCGL) 1l0% 0% E~Program I [81]
ATTACHMENT 7 ISOCS REPORTS [82]
Page 2 of 7 GA MM A ~ P E C T R U M "" N A L Y S I S
. o*, ' Di:@ - ~
Filename: C:\GENIE2K\CAMFILES\RWC001.CNF Report Generated On 6/30/2015 1 0:56:16 AM Sample Title RWC00l Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels): 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance : 1.000 keV Sample Size 2.827E+001 MA2 Sample Taken On 1/28/2013 12:00:00 PM Acquisition Started 6/29/2015 1:24:59 PM Live Time 600.0 seconds Real Time 600.6 seconds Dead Time 0.10 % Energy Calibration Used Done On 1/27/2015 Efficiency Calibration Used Done On 6/30/2015 Efficiency ID CRIB HOUSE 3M AR [67]
Page 3 of 7 Report Date : 6/30/2015 10:56:17 AM Sample
Title:
RWC00l Peak: Analysis Performed on: 6/30/2015 10:56:16 AM Peal{ Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak ROI ROI Peak Energy FWHM :::::ontinuum No. start end centroid ( keV) (keV) ::::ounts 1 1401 1414 1408.91 352.10 0.96 1.913E+001 2 2431 2444 2438.09 609.43 0.72 1. 370E+001 3 5836 5858 5848.09 1461.33 1. 73 1.150E+001 Dark Orange = First peak in a multiplet region Lite Orange = Other peak in muJ + ~ i:* reod.or-Green= Fitted singlet Errors quoted at 2.000 sigma UCll ID Ttf CA ION RE HT Sample
Title:
RWC001 Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Report Generated: 6/30/2015 10:56:17 AM
...... IDENTIFIED NUCLIDES . .. . . . . . .
Nuclide Id Energy Yield Activity Acti*1i t y Name Confidence (J:eV) ( -. ) (pCi/W-2 ) Uncertaint:,* K-40 0.959 1460.82* 10.66 5.94640E+004 1.21905E+004 Bi-214 0.999 609.32* 45.49 2.22087E+003 l.01222E+003 768.36 4.89 806. 18 1.26 934.06 3.11 1120.29 14.92 1155.21 1. 63 1238.12 5.83 1280.98 1. 43 13 7 7.6 7 3.99 1385. 31 0.79 1401.52 1. 33 140 7 .99 Z.39 1509.21 2.13 1661.27 1.05 1729.59 2.88 1 7 64.49 15. 3 0 1847.43 2 .03 2118. 51 1.16 Pb- 2 14 0.997 241.99 7.25 295.2 2 18.42 351 . 93* 35.60 2.36524E+003 l.07547E+003 785.96 1.06
* = Energy line found in the spectrum.
[68]
Interference Corrected A-~ivities Report Page 4 of~
! = Nuclide was corrected for parent/daughter Energy Tolerance: 1.000 keV Nuclide confidence index threshold~ 0 .30 Errors quoted at 2.000 sigma I TERFERE C COIRECTE REP RT Nuclide. Nuclide Wt mean Wt mean Name Id Confidence Activity (pCi/M2 ) Activity Uncertaint y K-40 0.959 5.946404E+004 , 1. 2 190 48 E+004 Bi-214 I 0.999 I
2.220870E+003 1 1 . 0122 i 3E+003 I Pb-214 I I I 0.997 I 2. 365241E+003 1 .075474E+003
? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis @ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma UNI NTIFIED PE s Peak Locate Perfor111ed on : 6/30/2015 10: 56 : 1 6 AM Peak Locate From Channel : 50 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts er Second % Uncertaint Detect o r Na111e: 5456 Sample Geometry: Cribhouse 3m Sample
Title:
RWC00l Nuclide Library Used: C: \GENIE21<::\CAMFILES \Zion Lib-BNL . NLB Report Generated on : 6/30/2015 10:56:17 AM Nuclide Energ:* Yield Line !IDA Nuclide tlDA Acti*city Dec. Level Name (ke V) ( 0 ) (pCi/M"2 ) (pCi /M"2 ) (pCi/M"2 ) (pCi/M *2 )
+ K-40 14 60. 82 *', 10. 66 9 . 768E+003 9. 77E+00 3 5.946E+004 4.350E+003 Cr-51 320.oa 9.91 1.189E+013 1.19E+013 - 3 .11 3E+012 5.057E+012 Mn-54 834.85 99 .98 1. 567 E+003 1.57E+0 03 -5.324E+002 4.954E+002 Co-58 810.76 99.45 l .'785E+006 1.78E+006 4.421E+005 6.681E+005 Co-60 1173.23 99. 85 7 .601E+00 2 6.55E+002 5 . 966E+001 3 .11 6E+CJ02 1332. 49 99 .98 6 . 552E+00 2 9.204E+001 2 . 538E+002 Nb-94 702.65 99.81 4.090E+002 4.()4E+002 7.4 90E+001 1. 676E+002
[69]
Nuc1ide MDA Report Page 5 of 7 Nuclide Energy Yield Line llDA Nuclide 1101-1. Activity Dec. Level Name (ke'T) (..,) (pCi/U"2 ) (pCi/tl"2 ) (pCi_lM"2 \ (pCi/H"'L ) 871.09 99.tl9 4.037E+002 -~.853E+001 1.6u2E+002 Sn-113 255 .13 2 .11 3.374E+006 1.09E+005 -7.193E+005 1. 493E+006 391.70 64. 97 1.085E+005 -3.795E+004 4.618E+004 Cs-134 475.36 1. 48 5. 472E+004 8.63E+00 2 l.487E+004 2.L92E+004 563.25 8.24 1.170E+004 2.462E+003 4.976E+003 569.33 15.37 6.133E+003 1. 144E+002 2.590E+003 604. 72 97.(,2 8.626E+002 .-6.360E+001 3. 536E+0 02 795.8/i 85.46 1. 219E+003 4.035E+00L 5.057E+002 801.95 8.69 8.173E+003 -4.555E+003 3.059E+003 1038. 61 0.99 1. 233E+005 5.175E+004 5 .115E+004 1167. 97 1. 79 5.538E+004 5.763E+003 2. 145E+004 1365.19 3.02 2.791E+004 -l.315E+004 9.889E+003 Cs-137 661. 66 85.10 6.356E+002 6.36E+002 3.018E+002 2.737E+002 Eu-152 121.78 28.67 1.976E+003 1.63E+003 l.149E+003 S .2 47E+002 244.70 7.61 5.729E+003 2.855E+002 2. 571E+0 03 295.94 0.45 l.241E+005 3.609E+004 5.649E+004 344.28 26.60 1.650E+003 2.073E+002 7.229E+OO~ 367.79 0.86 4.033E+004 7.194E+003 l.689E+004 411.12 2.24 1.200E+004 r-9.987E+003 4.647E+003 443.96 2.83 l.167E+004 .-5.653E+003 4 .714E+ 003 488.68 0. 42 l .112E+005 1. 773E+004 4 .762E+004 563.99 0.49 1. OOOE+005 3.434E+004 4.255E+004 586.26 0.46 8. 4 97E+004 r-3 .264 E+004 3.433E+004 678.62 0.47 8.375E+004 -7.985E+003 3.323E+004 688.67 0.86 6.166E+004 6.903E+003 2.604E+004 719. 35 0.28 1.57f;E+005 3.632E+004 6.368E+004 778. 90 12. 96 3.025E+003 ~ 1. tl89E+003 1.172E+003 810.45 0.32 2.815E+004 D.OOOE+OOD O.OOOE+OOO 867.37 4.26 1. 293E+ 004 .-1.655E+003 5.362E+003 919.33 0. 43 1.334E+005 2.102E+004 5.533E+004 964.08 14.65 4. 213E+003 4.916E+002 1.764E+003 1085.87 10. 2 4 3.606E+003 9.707E+001 1. 278E+003 1089. 74 1. 73 3. 24.8E+O 04 2 .111 E+0 03 l.31 2E+00 4 1112. 07 13.69 3.539E+003 O.OOOE+OOO l.371E+003 1212.95 1. 43 3.577E+004 7.446E+002 1.386E+004 Eu-152 1249.94 0.19 2.463E+005 l.63E+003 ~1.106E+005 9.219E+004 1299.14 1. 63 3.271E+004 2.042E+003 1. 267E+004 1408.01 21.07 1.625E+003 r-1. 104E+003 5 .13 9E+002 1457.64 0.50 1.334E+005 3.500E+004 5.391E+004 1528.10 0.28 1.281E+005 l.741E+004 4.050E+004 Eu-154 123.07 40. 40 l.404E+003 1.40E+003 4.461E+001 6.538E+002 247.93 6.89 6.844E+003 9.014E+002 3.072E+003 591.76 4.95 7.9 23E+003 -1. 269E+003 3.144E+003 692.42 1. 78 3.342E+004 9.759E+003 1. 422E+004 723.30 20.06 l.802E+003 -1. EOE+003 6.745E+002 756.80 4.52 1. 145E+004 l.688E+003 4.693E+003 873.18 12.08 3.720E+003 .- 1 .31 6E+ 002 1. 44 1E+003 996.29 10. 48 5 .811E+003 1.935E+002 2 .38 2E+003 1004.76 18.01 3.192E+003 r-3. 112E+002 1.290E+003 1274.4 3 34 .80 l.62 1E+003 l.012E+OO~ 6.279E+002 159F.4B 1. 80 8.171E+003 O.OOOE+OOO O.OOOE+OOO Eu-155 45.30 1. 31 6 .2 6 1E+004 2.87E+003 1.493E+0 04 2 .893E+004 60 .01 1. 22 7 . 956E+004 5. 968E+003 3.725E+004 86 .55 30.70 2 . 868E+003 r-6. 650E+002 l.354E+003 [70]
Nuclide MDA Report Page 6 or 7 Nuclide Energ~* Yield Line tlDA Nuclide tlDA hctinity Dec. LeTrel Name (ke") ('.,) (pCi/Il"'2 ) (pCi_/W'2 ) (pCi/t12 ) (pCi/Il"L ) 105.31 21.10 3.356E+003 >--4.964E+002 1.567E+003 Tl-208 583.19 85.00 8.455E+002 8.46E+002 4.955E+002 3.839E+o02 Bi-211 351.07 13.02 4.761E+003 4.76E+003 3.037E+003 2.195E+003 Pb-211 404.85 3.78 7.770E+003 6.26E+003 1.294E+002 3.185E+003 427.09 1. 76 2.082E+004 2.609E+001 8.858E+003 832.01 3.52 6.262E+003 8.510E+002 1. 980E+003 Bi-212 39.86 1.06 3.513E+004 9.77E+003 ,-1.128E+004 1.550E+004 727. 33 6.67 ~.775E+003 5.254E+003 4.325E+003 785.37 1.10 4.950E+004 1.107E+004 2. 119E+004 1620.50 1. 47 3.303E+004 9.206E+003 1. :::36E+O(J4 Pb-212 115 .18 0.60 8.324E+004 l.30E+003 1. 773E+004 3.890E+004
;::33. 63 43.60 1.297E+003 8.027E+002 6.037E+002 300.09 3.30 1.193E+004 1.489E+003 5. 291E+003 Pb212-XR 74.82 10.26 8.987E+003 3.99E+003 l.025E+004 4. 311E+003 77 .11 17 .10 3.985E+003 >--8,920E+002 1.885E+003 87.35 3.97 1.603E+004 1. 727E+003 7.584E+003 89.78 1. 46 3.843E+004 -1.099E+004 1.805E+004 f- Bi-214 609.32* 45 49 l.269E+003 1.27E+003 2.221E+003 5. 601E+002 768.36 4.89 1.314E+004 4.8 04E+003 5.7 77E+003 806.18 1. 26 3.286E+004 . . . 1. 553E+003 1.328E+00 4 934.06 3.11 1.802E+004 4.6 5 6E+003 7. 611E+003 1120.29 14.92 6.456E+003 5.426E+003 2.903E+ 003 1155. 21 1. 63 3.152E+004 1. 862E+003 1. 273E+004 1238.12 5.83 1. 086E+004 1. 413E+003 4 .55 0E+003 1280.98 1. 43 3.548E+004 3.519E+003 1. 408E+004 1377.67 3.99 l .335E+004 5.090E+001 5. 296E+003 1385.31 0. 79 6 .171E+004 2.055E+004 2.390E+004 1401.52 1. 33 3.32 2E+004 3.858E+003 1.244E+004 1407.99 2.39 1. 265E+004 -9.02&E+003 4.0 01E+003 1509. 21 2.13 3.523E+004 2.022E+004 1.488E+004 1661. 27 1.05 4. 072E+004 8.769E+003 1.443E+004 1729.59 2.88 2.599E+004 1. 311E+004 1. 078E+00 4 + Bi-214 1764.49 15.30 5.664E+003 1. 27E+003 2.442E+003 2.410E+003 184 7 .43 2.03 2.905E+004
- 9. 67 4E+003 l.125E+004 I> 2118. 51 1.16 O.OOOE+OOO O.OOOE+OOO 0.000E+OOO
+ Pb-214 241.99 7.25 5.552E+003 1. 34E+003 6. 896E+001 2 . 505E+003 295.22 18.42 2.734E+003 l .443E+003 l.248E+003 351. 93* 35.60 1 .341E+003 2 .365E+003 6. 021E+00 2 785.96 1. 06 4.769E+004 5.133E+003 2.014E+004 Pb214-XR 74.82 5.80 l.595E+004 7.03E+003 1.819E+004 7.649E+003 77 .11 9. 70 7.033E+003 -1.574E+003 3.326E+003 87.35 2.24 2.845E+004 3.065E+003 1.34 6E+004 89.78 0.82 6.850E+004 - 1.959E+00 4 3.217E+004 Ra-226 186.21 3.64 1.168E+004 1.17E+004 2.879E+003 5.3 65E+00 3 Ac-228 129.07 2.42 l.862E+004 3.13E+003 l.837E+003 8.643E+003 20~.25 3.89 1.050E+004 4.28 6E+003 4. 779E+0 03 270.24 3. 4 6 1 .001E+004 .-3. 2G4E+oo: 4.401E+003 328.00 2.95 1. 404E+004 4.381E+003 6.228E+003 238.32 11.27 4.184E+003 2.205E+003 1. 881E+003 409.46 1. 92 2.063E+004 4.98 2E+003 8.929E+003 463.00 4. 40 9 .0 79E+003 1. 115E+003 3.887E+003 794.95 4.25 l.031E+004 2.109E+003 4. 226E+00 3 olll.20 25.80 3 .127E+003 1.630E+003 1.397E+003 964. 77 4.99 1.190E+004 6 .532E+003 5 .0 63E+003
[71]
Nuclide MDA Report Page 7 o:F 7 Nuclide Energ:,* Yield Line tlDA Nuclide t1DA ActiYit:: Dec. Le ..el Name (keV) ( C. ) (pCi/M2 ) (pCi /t*l " 2 ) (pCi/M' 2 ) (pCi/tJ"2 ) 968. 97 15.80 4.306E+003 l.776E+003 l.872E+003 1588.20 3.22 1. 660E+004 1.382E+003 6.432E+003 Pa-231 27.36 10.30 4.565E+003 4.56E+003 fi.745E+002 2.070E+003 283.69 1. 70 2.042E+004 -l.002E+003 8.950E+003 300.07 2.47 l.593E+004 1. 989E+oo::: 7.069E+003 302.65 2.20 1. 458E+004 ~3.654E+003 6.275E+003 330.06 1. 40 2.325E+OO.J 9.265E+002 9.955E+003 Th-234 92. 38 2.13 3.070E+015 3.07E+015 l.350E+0 15 l.452E+ 015 92.80 2.10 3.111E+015 1. 44 7E+015 1.472E+015 112. 81 0.21 2.l47E+016 ,-5.447E+Ol5 9.925E+Ol.5 U-235 143.76 10.96 4.209E+003 7.09E+002 l.126E+003 1. 956E+003 163.33 5.08 7.499E+003 8.'.)34E+001 3.422E+003 185.71 57.20 7.092E+002 1.238E+002 3.244E+002 202 .11 1.08 3.079E+004 -9.844E+003 1. 373E+004 205.31 5.0 1 6.814E+003 -3.613E+003 3.046E+003 Am-241 59.54 35.90 1. 372E+003 1.87E+ 003 1. 986E+002 8.748E+002
+ = Nuclide identified during the nuclide identification ,., = Energ:'.: L.ine found in the spectrum > = t1DA nalue not calculated @ = Half-life too short to be able to perform the decay correction
[72]
Page 2 of 7 GA MM A P E C T R U M d N A L y s I s
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Filename: C:\GENIE2K\CAMFILES\RWC002.CNF Report Generated On 6/30/2015 10 :57:38 AM Sample Title RWC002 Spectrum Desc r i ption Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels): 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance : 1.000 keV Sample Size 2.827E+001 M"2 Sample Taken On 1 / 28/2013 12:00:00 PM Acquisition Started 6/29/2015 2:41:55 PM Live Time 6 00.0 seconds Real Time 600.7 sec onds Dead Time 0 .12 % Ener gy Calibration Used Done On 1 /2 7 /2 015 Effi c i e ncy Calibration Used Done On 6 /30/2015 Efficiency ID CRIB HOUSE 3M AR [73]
Page 3 of 7 Report Date : 6/30/2015 10:57:38 AM Sample
Title:
RWC002 Peak: Analysis Performed on: 6/30/2015 10:57:37 AM Peal{ Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak ROI ~or Peak !Energy IFWHM ~ontinuum INo. start ~nd ,centroid (keV) (keV) ::ounts 1 299 307 301. 07 75.00 0.78 1.718E+002 2 1400 1416 1407.72 351. 81 1.13 3.591E+001 3 2430 2446 2437.35 609.24 1. 70 1.700E+001 4 5835 5856 5844.98 1460.56 1. 27 5.500E+OOO Dark Orange = First peak in a multiplet region Oran~e = Other ak in multinlF ' r:-e9-io, Green = Fitted singlet Errors quoted at 2.000 sigma NU DOE ID Nil Clil'ION REPORT Sample
Title:
RWC002 Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Report Generated: 6/30/2015 10:57:38 AM
.. . . . . IDENTIFIED NUCLIDES .........
Nuclide Id Energy Yield Actiuity Acti*Tit~* Name Confidence (ke\T) (':, ) (pCi/ti"2 ) Uncertaint :{ K-40 0.989 1460.82* 10.66 5.49356E+004 1.10517E+004 Bi-211 0.917 351.07* 13.02 8.23241E+003 3.83729E+003 Bi-214 1.000 609.32* 45.49 4.73054E+003 1.41824E+003 768.36 4.89 806.18 1.26 934.06 3 .11 1120.29 14.92 1155. 21 1. 63 1238.12 5.63 1280.98 1. 43 1377. 67 3.99 1385. 31 0.:9 1401.52 1. 33 1407.99 2.39 1509.21 2.13 1661. 27 1.05 1729.59 2.88 1764.49 15.30 184 7 .43 2.03 2118.51 1.16 Pb-214 0.513 241.99 7 .25 295 .22 18.42 351. 93* 35 . 60 3.01399E+003 1 40383E+003 [74]
Interference Corrected ~-tivities Report Page 4 or, Nuclide Id Energy Yield A.ctivity ~ctivity Name Confidence ( keV) (t) (pCi/MA2 ) Pncertaintv
* = Energy line found in the spectrum. @=Energy lin& not used for Weighted !~an Acti~ity = Nuclide was corrected for rarent/daughter Energy Tolerance: 1.000 keu Nuclide confidence index threshold = O.~O Errors quoted at 2.000 sigma IN R R CE treORHECTE Nuclide Nuclide Wt mean Wt mean Name Id Confidence Activity (pCi/MA2 ) Activity Uncertaint y K-40 0.989 5.493562E+004 1.105171E+004 - I ? Bi-211___ i___
0.917 f 8.232408E+003 3.837286E+003 Bi-214 1.000 4 .730540E+003 ---t 1 .418244E+003 L------
? Pb-214 0.513 r3. 013994E+003 - - - _ 1. 403832E+003 ? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis @=nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma UNIDEN IFIID PEAKS Peak Locate Performed on: 6/30/2015 10: 57 : 37 AM Peak Locate From Channel : 50 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. ( keV) Counts per Second % Uncertaintv 1 75.00 1.4202E-001 50.52 M = First peak in a multiplet region m Other peak in a multiplet region F Fitted singlet Errors quoted at 2.000 sigma NWJ Cl M E MDA R~ PO T Detector !.'Jame: 5456 Sample Geometry: Cribhouse 3m Sample
Title:
RWC002 Nuclide Library Used: C:\GENIE2K\CAMFILES\ Zi on Lib-BNL . NLB Report Gene rated on: 6/30/2015 10:57 : 39 AM [75]
Nuclide MDA Report Page 5 of 7 Nuclide Energ:,* Yield Line MDA Nuclide rmA ttCtivit:.' Dec. Le"el Name (keV) hl (pCi/ll"2 ) (pCi/M"2 ) (pCi/11"2 ) (pCi/W'2 )
+ K-40 j *, ,,!,_.,. 8L.
- 10 . 66 6.962E+003 6 96E+003 !! ,i ~!~l l:.*~0 0 4 2 .948E+003 Cr-51 320.08 s. 91 1. 426E+013 1.43E+013 -4.444E+012 6.247E+012 t1n-54 834.85 99. 98 3.3~4E+003 3.39E+003 r-l.852E+003 1.408E+Q03 Co-58 810.76 99.45 2.184E+006 2.18E+006 6.663E+005 8.665E+005 Co-60 1173.23 99.85 6.627E+002 4.01E+u02 .-2.528E+002 2.630E+002 1332. 4 9 99.98 4.009E+002 r-l.9 07E+002 1. 267E+002 Nb-94 702.65 99.81 5.137E+002 3.72E+002 2.524E+002 2.199E+002 871.09 99.89 3.716E+002 r-3.848E+002 1. 439E+002 Sn-113 255 .13 2 .11 4.205E+006 1.16E+005 -2.576E+005 1 .909E+006 391. 70 64.97 1.159E+005 -'.!.733E+004 4.988E+004 Cs-134 475.36 1. 48 6.153E+004 9.99E+002 -6.877E+003 2.634E+004 563.25 8.34 1. 020E+004 1.125E+003 4.230E+003 569.33 15.37 4.215E+003 r-2.193E+003 1.633E+003 604.72 97.62 9.98 7E+002 1. 433E+OOO 4.2 18E+002 7 95. 8 6 85.46 1. 011E+003 1. 736E+002 4.013E+002 801. 95 8.69 9.157E+003 r-1. 906E+003 3.547E+003 103&.61 0.99 1.0 19E+005 -3.887E+003 4.044E+004 1167. 97 1. 79 7.306E+004 5.32 4E+003 3.030E+004 1365.19 3.0~ 3.604E+004 6.188Et003 1.396E+004 Cs-137 661.66 85.10 4.279E+002 4.2 8E+002 2.77 4E+001 l.698E+002 Eu-152 121. 78 28. 67 1.765E+003 l.30E+003 9.535E+U02 8. 196E+002 244.70 7.61 5.514E+003 r-3.144E+003 2.464E+003 295.94 0.45 1.409E+005 1.017E+005 6.492E+004 344.28 26. 60 1.305E+0 03 .-6. 780E+002 5.511E+002 367.79 0.86 5.128E+004 1. 458E+004 2.239E+004 411. 12 2.24 2.228E+004 2.398E+003 9.796E+003 443.96 2.83 9.882E+003 r-4.936E+003 3.828E+003 488.68 0.42 1.254E+OOS 3.309E+004 5.4 74E+004 563.99 0.49 7.751E+004 r-l.168E+004 3.132E+01)4 586.26 0. 46 1.090E+005 1.584E+004 4.635E+004 678.62 0.47 1.114E+005 2.878E+004 4.705E+004 688.67 0.86 5.625E+004 7.976E+003 2.333E+004 719.35 0.28 1.682E+005 2.720E+004 6.895E+004 778.90 12.96 3.313E+003 r-1. 403 E+003 1.315E+003 810.45 0.3~ 1.124E+005 -7.83 4E+003 4.209E+004 867.37 4.26 1.073E+004 r-5.281E+003 4.259E+003 919.33 0.43 9.075E+004 r-5.901E+00 4 3.397E+004 964. 08 14.65 4.219E+003 1 .582E+003 1. 7 67E+003 1085.87 10.24 4.661E+003 -2.037E+003 1.806E+003 1089 .7 4 1. 73 4.009E+004 2.020E+004 1.693E+00 4 1112.07 13.69 4. 905E+0 03 2.256E+003 2.054E+003 1212 .95 1. 43 4. 194E+004 1.784E+004 1.695E+004 Eu-152 1249.94 0.19 2.744E+005 1. 30E+003 r- 3 .9 97E+004 1. 063Et005 1299.14 1. 63 3 .835E+004 1.631E+00 4 1.549E+004 1408. 01 21. 07 3.107E+003 .- 2 .020E+002 l.256E+003 1457.64 0.50 1. 711E+005 ,-2.830E+004 7.278E+004 1528.10 0.28 1.610E+005 8.671E+003 5 . 706E+004 Eu-154 123.07 40.40 l.460E+003 9 . 91E+002 r-l.63 0E+002 6 .8 21E+00 2 247.93 6. 89 6.2 02E+003 r-3.196E+003 2.752E+003 591. 76 4.95 8.500E+003 -1.808E+003 3.435E+003 692.42 1. 78 1.714E+004 -1.384E+003 6 . 072E+003
[76]
Nuclide MDA Report Page 6 oF 7 Nuclide Energ:; Yield Line MDA Nuclide trnA Acti,rity Dec. Level Name (ke~!) ( i;) (pCi/11"2 ) (pCi/M"2 ) (pCir't1"2 ) (pCi/M"2 ) 723. 30 20.06 2.520E+003 l.001E+003 l. 033E+003 756.80 4.52 1.079E+004 ,-8.287E+002 4.359E+003 873.18 12.08 4.673E+003 3.33-lE+OOl 1.915E+003 996.29 10.48 5.076E+003 -:.744E+001 2. 014E+003 1004.76 18.01 2.437E+OOJ -9.057E+002 9.124E+002 1274.43 34.80 9.915E+002 1.347E+002 3.134E+002 1596.48 1. 80 3.237E+004 3.007E+003 l.212E+004 Eu-155 45.30 1. 31 6.483E+004 3.06E+003 ,-6.913E+004 2.910E+004 60.01 1.22 9.287E+004 -3.291E+004 4.389E+004 86.55 30.70 3.057E+003 9.148E+002 1.450E+003 105.31 21.10 3.546E+003 1. 14 6E+00'.") 1.664E+003 Tl-208 583.19 85.00 8.429E+002 8.43E+002 5.449E+002 3.827E+002
.. Bi-211 <il. 07* 13.02 !:,.
- 154E+003 5.15E+003 H.232E+003 2.392E+003 Pb-211 404.85 3.78 1.034E+004 1.03E+004 6.702E+002 4.475E+ 003 427.09 1. 76 2.296E+004 ,-3.28 1E+003 9.934E+003 832.01 3.52 1. 205E+004 ,-1.923E+003 4.870E+003 Bi-212 39.86 1.06 6.299E+004 8.12E+003 -2.695E+004 2.846E+004 727. 33 6.67 8 . 119E+003 2.941E+003 3.496E+ 003 785.37 1. 10 3.963E+004 >-1.885E+002 1.625E+004 1620. 50 1. 4 7 2.838E+004 6.113E+003 1.006E+004 Pb-212 115 .18 0.60 7.753E+004 1.4 7E+00 3 -.:::.194E+00 4 3.608E+004 238.63 43.60 1. 468E+003 1.531E+003 6.895E+002 300.09 3.30 1. 408E+004 5.292E+003 6.376E+003 Pb212-;~R 74.82 10.28 9.803E+003 4. 01E+003 .-2.678E+003 4 .723E+003 77 .11 17.10 4.012E+003 4.957E+002 1.900E+003 87 .35 3.97 1. 649E+004 7.063E+003 7.819E+003 89.78 1. 46 4.383E+004 3.078E+004 2.076E+004
+ Bi-214 609.32* 45.49 1. 4 72E+003 l.47E+003 4 . 7:HEr Q (j ::J u.617E+002 768.36 4.89 1.181E+004 2.633E+003 5. 113E+003 806.18 1. 26 4.075E+004 5.380E+003 1.721E+004 934.06 3.11 1. 557E+004 3.592E+003 6.381E+003 1120.29 14. 92 6.003E+003 3.500E+003 2.677E+003 1155.21 1. 63 3.888E+004 - 2 .232E+003 1.642E+004 1238 .12 5.83 1.387E+004 3.946E+003 6.057E+003 1280.98 1. 43 4.288E+004 ~6. 756E+003 1. 778E+004 1377.67 3 . 99 1.433E+004 6.095E+003 5.789E+003 1385. 31 0. 79 6.158E+004 ~1.666E+004 2.385E+004 1401. 52 1. 33 2.859E+004 6.157E+003 1. 013E+004 1407. 99 2.39 2.576E+004 2.634E+003 1.056E+004 1509.21 2.13 3.197E+004 1.228E+0 04 1.326E+004 1661. 27 1.05 4.057E+004 8.738E+003 1. 437E+ 004 1729.59 2.88 2 .143E+004 8.173E+003 8.503E+003 + Bi-214 1764.49 15.30 5 .8 71E+003 1.47E+003 2.671E+003 2 .513E+003 1847.43 2.03 2.263E+004 - 1 .21 8E+003 8.017E+003
> 2118. 51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO
+ Pb-214 241. 99 7.25 6 . 771E+003 1.89E+003 5.104E+003 3. 115E+003 295 .22 1&. 42 2.997E+003 1.462E+003 1. 380E+003 351. 93 ': 35.60 1. 887E+003 :J . Ol 4F:+O(U 8.756E+002 78.'5. 96 1. 06 3.876E+004 >-2. 061E+003 1.566E+004 Pb214-XR 74.82 5.80 1.739E+004 7 .08E+003 i-4. 752E+003 8.380E+003 77 .11 9. 70 7,079E+003 8 .74 8E+002 3.354E+003 87.35 2.24 2 .92 6E+00 4 l .25 3E+004 1.387E+004 89.78 0.82 7.812E+004 .5.486E+004 3.701E+004 Ra-226 186.21 3. 64 1. 226E+004 1. 23E+00 4 4. 726E+003 5.652E+003
[77]
Nuclide MDA Report Page 7 o~ 7 Nuclide Energr Yield Line t1DA Nuclide tlDA ActiYity Dec. Lavel Name (ke") ( ",) (pCi/tI *2 ) (pCi/M2 ) (pCi/M '2 ) (pCi/U"~ ) Ac-228 129.07 2. 42 1. 837F',+004 3.30E+003 >-7.590E+003 6.524E+003 209.25 3.89 9.932E+003 r-2.324E+002 4. 496E+003 270.24 3. 46 1.170E+004 1. 086E+003 5.253E+003 328.00 2.95 1.364E+004 --,i. 929E+002 6.034E+003 338.32 11. 27 5.0 2 5E+003 2.029E+003 2.303E+003 409 . .J6 1. 92 2.288E+004 5.604E+002 1. 006E+Ou4 463.00 4.40 9.033E+003 .-5.599E+002 3.867E+003 794.95 4.25 9.036E+003 3.446E+001 3.5S6E+003 911. 20 25.80 3.305E+003 2.690E+003 1.486E+003 964.77 4.99 1. 042E+004 1.643E+003 4.323E+003 968. 97 15.80 4.053E+003 7.2 0 1E+002 1. 745E+ 0 03 1588.20 3.22 l.482E+004 1.836E+003 5.547E+003 Pa-231 27.36 10.30 1.651E+004 l.65E+004 2.899E+003 7.462E+003 283.69 1. 70 2.529E+004 -2.298E+003 1.139E+004 300.07 2.47 1. 882E+004 7.070E+003 8.518E+003 302.65 2.20 1.961E+004 3.24CE+ 003 8.80 2E+003 330.06 1. 40 3.242E+004 l.237E+004 1.455E+004 Th-234 92. 38 2.13 3.222E+015 3.18E+015 2.79 1 E+015 1.530E+0 15 92.80 2.10 3.185E+015 1.728E+015 1.510E+015 112. 81 0.21 2.669E+016 6.848E+015 1.255E+ 0 16 U-235 143. 7 6 10. 96 3.790E+003 8.16E+00 2 .-1.102E +003 1. 747E+003 163.::i3 5.08 7.157E+003 -Z.544E+003 3.250E+003 185.71 57.20 8.160E+ 002 5.192E+002 3. 775E+002 202. 11 1.08 3.525E+004 5.594E+003 1. 596E+004 205.31 5.01 6.943E+003 r-2.206E+003 3 . 110E+003 Am-241 59.54 35.90 2.234E+003 2.23E+003 >-7.833E+002 1. 056E+0 03
+ = Nuclide identified during the n uclide identification Energy 1 , 0 found in the spectrum > tlDA value not calculated @ Half-life too short to be able t o perfo rm the deca:' correction
[78]
Page 2 of 7 GA M M A ....' P E C T R U M J__ N A L Y S I S Filename: C:\GENIE2K\CAMFILES\RWC003.CNF Report Generated On 7/9/2015 7:27:49 AM Sample Title RWC003 Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels): 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance : 10.000 keV Sample Size : 2.827E+001 M"2 Sample Taken On 1/28/2013 12:00:00 PM Acquisition Started 6/25/2015 2:43:07 PM Live Time 1000.0 seconds Real Time 1001.8 seconds Dead Time 0.18 % Energy Calibration Used Done On 1/27/2015 Efficiency Calibration Used Done On 7/8/2015 Efficiency ID CRIB HOUSE 3M [79]
Page 3 of 7 Report Date : 7/9/2015 7:27:49 AM Sample
Title:
RWC003 Peak: Analysis Performed on: 7/9/2015 7:27:48 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak ROI !ROI Peak !Energy FWHM ~ontinuum [No. start ~nd ~entroid (keV} (keV} :::ounts 1 80 87 83.44 20.55 0.92 3.129E+002 2 297 312 301.46 75.10 0.94 3.846E+002 3 952 962 955.72 238.76 0.52 8.282E+001 4 1401 1414 1408.04 351. 8 9 0.74 4.521E+001 5 2431 2446 2438.67 609.58 0.99 2.218E+001 6 3640 3652 3645.51 911. 20 0.64 1. 325E+001 7 4479 4490 4484.42 1120.78 0. 7 9 1 . 485E+001 8 5836 5858 5846.91 1461.04 1. 48 8.766E+OOO Oa..rk Orange = Fi.t': s t: p.ea.k :bi a mul't.il).1.e 't~ r e g.L ~,.n Gr.ee.n = Fitt ad ~~ng1et Errors quoted at 2.000 sigma NUCIIDE DE 1TIFIC TIIN RE ORT Sarnple TL.le. RVVCu03 Ntichde Lib(a,:*y Used: ( :\GENiE:2K\C:AMFILES\Zion Lib-BNL.NLB Report Generated: 7f9.120*15 7:?.7:49 AM I Nuclide Id IDENTIFIED NUCLIDES Ene rgy Yield Activi ty Activit y Name Con fi dence ( ke'l) ( ,) (pCi /M"2 ) Uncertaint:* 1.... 11 0 i .000 '.iA\ SC. 8?. "" 1.0.Sii :J. tJticm.:..,.cc~; 6. OO'i J '1F-:*.*O C3 l.3J.*-.':! VJ 1
- OOJ sos. J;",** (,l:i. 4 S 2 . :~s: '75L ,* 0OS G.2 l S70ra co~
768.36 4.89 806 .18 1.26 934 . 06 3 .11
- u 2c. 29.- :.,J. ~?. .'i. . ,l S3 tJ '~Y+0:3 :.. 3(0,i. 4. t +o o:;
1155.21 1. 63 1238.12 5.83 1~8 0.98 1. 4 3 1377.67 3.99 1385 .31 0. 79 14 0 1.52 1. 33 1407.99 2. 3 9 1509.21 2 .1 3 1661.27 1.05 1729. 59 2 . 88 1764.4 9 15 . 30 1 847.43 2 .0 3 2 11 8 .51 1. 16 [80]
Interfer ence Correcte d ~-~ivit ies Report Page 4 of~ !Nuc l i de Id !Energy !Yi el d Ac t:i, vity Pl.ctivi ty !Name :::onfi d e nce (k eV) ( %) (pCi /M"2 ) Uncerta intv 2 95.2 2 18 .42 35J. . ~3* 35.6D 1 .. 64489E+ OO 6 . 55'.,5:-3.E+CO 7 85 . 96 1. 0 6 Ac - 2 2 8 1.000 1 29 . 0 7 2 .42 209.2 5 3 . 89 270. 24 3. 4 6 3 28.0 0 2.95 338.32 11.27 409 .4 6 1. 92 4 63.0 0 4 . 40 794 . 95 4.25 9Jl 20""' 15 . 80 l. . 54207E-,.OO '1-89958E+OO 9 6 4 .77 4.99 9 68.97 15.80 1588.20 3.22 rh--2.3 1 0 . 935 2.5 . b4 *.t :: 4 . 10 8 . 23784.F.+OO 3 . 3406:2E+O C 84 .. 21** (; .. 0 1.1.013-0E +OO 6 , .:f198&---0 0
.. 89.95 1.00 @ = Energy line not used for Weighted Mean Acti vity = Nuclide 11as correct ed for parent /daughter En e r gy Tol e r ance : 1 0 . 000 keV Nucl ide conf idence index threshold
- 0. 30 Errors quoted at 2. 000 s i gma I TERFE EC CORRECTED P RT Nucl i de Nuclide Wt mean Wt mean Name I d Confi dence Activi ty (pCi /M"2 ) Activi ty Uncerta inty K- 40 1.000 3.838879 E+004 6 . 00 1 366E+003
~; 8 .i. ;;'..l .- ' :* !t :it ~- '\:> ... f '.'7'i'5 - . .,,1) ,.:
Bi- 214 1 .000 2 . 028145E+ 003 5 . 639693E+ 002 Pb-214 0.515 1 . 729289E+ 003 6 . 465386E+ 002 Ac-228 1. 000 l . 542066E+ 003 7.899576 E + 002 X ! '* -2::_, D. :; t : : Th-231 0.935 8 . 834993E+ 003 2 . 959459E+ 003
? *- nuc l.idi: :;.::-; :;,a :r.'i: o f a n ~u ,d~te1~\i neci sol 1."<*t.i on . j
- _.,~ -.~ .i ..:**-: t t . ,! , nr _i:a.r er -Y 1...,
r::u c l.id.e con t.;,1.i.1~ii 8 n e rgy l inc,a no t u s ed i .n We i g ht~d M'la n Act.i 1Ti ty E rro .raS quo t o d a t 2 . 0 00 s.ignm [81]
Interference Corrected p*~ivities Report Page 5 of .. u N IF I Peak Loca~e Performed on
- 7/9/2 015 7
- 27 : 48 AM Peak Locate From Channel 50 Peak Locate To Channel ; 8192 Peak Energy Peak Size in Peak CPS No. (keV} Counts er Second % Uncertaint All peaks were identified.
.NI l DEM EPORT Detector Name" 54.56 Sample Geometry
- Cribhouse 3m Sample Title : RWC003 Nuclide Library Used : C:\GENIE2K\CAMFII..ES \Zion Lib-- BNL . NLB Report Generated on : 7/9/2015 7 : 27 : 50 AM Nuclide Energy Yield Line MDA Nuclide t-1DA Acti.,ity Dec. Le**el Name (keV) (:) (pCi/l-1'*2 ) (pCi/W-2 ) (pCi/M"2 ) (pCi/W-2 )
+ K-40 1460.82* 10.66 3.164E+003 3. 1 6E+003 3.339E+004 1.387E+003 Cr-51 32 0 .08 9.91 7.984E+Ol2 7.98E+012 '-1. 489E+011 3.648E+012 Mn-54 834.85 99.98 1. 362E+003 1.36E+003 ~4.996E+001 5.706E+002 Co-58 810.76 99.45 1.166E+006 l.17E+006 2.375E+005 4.993E+0 05 Co-60 1173.23 99.85 3.280E+002 3.00E+002 1.365E+002 l.3 85E+002 1332.49 99.98 2.997E+002 l.397E+002 1.228E+002 Nb-94 702.65 99.81 2.34 7E+002 2.07E+002 2.980E+001 l .02 9E+002 871.09 99.89 2 .069E+002 2.078E+001 8.737E+001 Sn-113 .255.13 2 .11 2.035E+006 6.14E+004 1.286E+005 9.347E+005 391 . 70 64.97 6.136E+004 3 .839E+003 2.736E+004 Cs-134 475 .36 1.48 2.862E+004 4.87E+002 2.979E+003 l.249E+004 563.25 8.34 4.867E+003 '-1. 056E+003 2.083E+003 569.33 15 .37 1. 988E+003 '-6. 28 5E+00 2 8.033E+002 604.72 97.62 4.873E+002 '- 2 .8 57E+001 2.127E+002 79 5 .86 85.46 6.848E+002 2 . 391E+001 3.021E+002 801.95 8.69 3.533E+003 9.007E+002 l.3 6fiE+0 03 1038.61 0.99 4.646E+004 - 1. 647 E+003 1.927E+004 1167 . 97 1. 79 2.571E+004 7 .276E+0 03 1.054E+00 4 1365.19 3.02 1. 179E+004 5.476E+002 4 .41 3E+003 Cs-137 661.66 85 .10 :::: .598E+002 2.60E+002 5.858E+001 1.124E+002 Eu-152 121. 78 28 .67 1. 001E+003 7.54E+002 -9.932E+OOO 4.735E+002 244. 70 7.61 3.41 7E+003 -l.118E+0 03 1.580E+003 2 95 . 94 0.45 7 .844E+00 4 6 .0 50E+004 3.682E+004 3 44. 28 26.60 7.537E+002 '-4.167E+001 3.335E+002 367.79 o. 86 2 . 350E+004 ~5.878 E+00 3 1.037E+004 411.12 2 . 24 9. 118E+003 ~ l . 611E+0 03 3 .99 6E+003 443.96 2 . 83 7.088E+003 '- 6 . 098E+002 3.081E+003 4 88 . 68 0 . 42 4.547E+0 04 ~l. 469E+004 1 .9 47E+ 004 51'i3. 99 (J.49 4 . 72 6E+004 7.933E+00 3 2. 063E+0 04 58 6 . 2 6 0.46 4. 699E+004 -8 .11 7E+003 2 .023E+004 678.62 0. 4 7 4 . 57 4E+ 004 O. OOOE+OOO 1 . 946E+004 688.67 0 . 86 2 . 531E+004 '-1. 411E+004 1.077E+00 4 719 . 35 0 . 28 8 . 259E+004 '-1. 44 4E+004 3 .53 6E+00 4
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Nuclide :MDA Report Page 6 of 7 "Nuclide Energy Yield Line MDA Nuclide t-lDA Acti-1:it:, Dec. Le,rel Name (keV) ( ".; ) (pCi/M"2 ) (pCi/t1"2 ) (pCi/t1 '2 ) (pCi/t-12 ) 778.90 12.96 1. 709E+003 -3.680E+002 7.218E+002 810.45 0.32 6.063E+004 -3.317E+004 2.485E+o04 867.37 4.26 4.986E+003 -5.598E+002 2.068E+003 919.33 0. 43 5.616E+004 4.030E+002 2. 372E+004 964.08 14. 65 1. S39E+003 .-1.033E+001 8.389E+002 1085.87 10.24 2.315E+003 2.098E+002 9.602E+002 1089. 7 4 1. 73 1. 220E+004 5.191E+003 4.930E+003 1112.07 13.69 1.658E+003 -3.193E+002 6.794E+002 1212.95 1. 43 1.557E+004 -l.794E+003 6.291E+003 Eu-152 1249.94 0.19 1.191E+005 7.54E+002 -3.590E+o04 4.814E+004 1299.14 1. 63 l.312E+004 -2.651E+003 5.205E+003 1408. 01 21.07 1. 460E+003 3.825E+002 6. 213E+002 1457.64 0.50 5.456E+004 -1.805E+D04 2.263E+D04 1528.10 0.28 6.788E+004 1.892E+004 2.541E+004 Eu-154 123.07 40.40 7.494E+D02 5.35E+002 -1. 980E+001 3.54 2E+oo::: 247.93 6.89 3.473E+003 -l.998E+003 1. 583E+003 591.76 4.95 4.861E+003 1. 208E+002 2.103E+003 692.42 1. 78 l.414E+004 -2.750E+003 6.089E+003 723.30 20.06 1.094E+003 -1.514E+002 4.583E+o02 756.80 4.52 4. 963E+003 -4.302E+003 2.078E+003 873.18 12.08 2.079E+003 1-3.103E+002 8.779E+002 996.29 10. 48 2.206E+003 3.095E+ 002 9.042E+002 1004.76 18.01 1.430E+003 .-1.550E+002 5.990E+002 1274.43 34.80 5.349E+002 1-3.354E+002 2.002E+002 1596.48 1. 80 8.020E+003 >-7.356E+003 2.535E+003 Eu-155 45.30 1. 31 2.608E+004 1. 38E+003 -a.281E+003 l.21 6E+004 60.01 1. 22 3.455E+ D04 1.531E+004 l.634E+004 86.55 30.70 1.378E+003 -5.451E+002 6 . 578E+002 1()5.31 21.10 1. 738E+003 3.007E+001 8.235E+002 Tl-208 583.19 85.00 4.391E+002 4.39E+00 2 4.572E+002 2.040E+002 Bi-211 351.07* 13.02 2.325E+003 2.32E+003 4.493E+003 1.083E+003 Pb-211 404.85 3.78 4.735E+003 4.74E+003 >-l.148E+003 2.075E+003 427. 09 1. 76 1.096E+004 1-1.4 75E+0D3 4.837E+003 832.01 3.52 6.206E+003 l.209E+003 2.657E+003 Bi-212 39.86 1.06 3.959E+0D4 3.92E+003 l.187E+004 l.903E+004 727.33 6.67 3. 920E+003 1.4 39E+003 1. 739E +003 785.37 1.10 2.184E+004 5.122E+0D3 9.532E+003 1620 .50 1. 47 1.330E+004 -l.107E+00 3 5.152E+003 Pb-212 115 .18 0.60 4.400E+004 7.16E+002 6.151E+003 2.086E+004 238.63* 43.60 7.164E+002 5 .248E+002 3.386E+002 300.09 3.30 6.294E+003 3.107E+003 2.858E+003 Pb212-XR 74 .82 10.28 4.379E+003 l.95E+003 6.570E+003 2 .119E+003 77 .11 17.10 1.947E+D 03 -5. 734E+002 9.320E+002 87.35 3.97 7.502E+003 2.941E+003 3.581E+003 89.78 1.46 2.009E+004 7.055E+003 9 .58 1E+003
+ Bi- 214 609.32"' 45.49 6.532E+002 6.53E+002 2.152E+003 2 . 968E+002 768 . 36 4.89 5.826E+003 2 .606E+D03 2.604E+D03 806.18 1. ,::6 1. 577E+D04 1. 132E+003 6.660E+003 934.06 3 . 11 7 .457E+003 1.486E+003 3.192E+003 1120.29* 1 4.92 2.090E+003 l.4 53E+003 9.233E+002 1155.21 1. 63 l. 728E+004 5.629E+003 7. 514E+003 1238.12 5 .8 3 6.034E+003 2 . 95 4E+D03 2.691E+003 1280.98 1. 43 2.066E+004 1. 004E+004 8.982E+003 1377 . 67 3.99 6 . 747E+003 2 .B a3E+003 2 .870E+ 003
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Nuc1ide MDA Report Page 7 or~ - Nuclide Energy Yield Line MDA Nuclide HDA Acti vity Dec. Le **el Name (keV) ( ;) (pCi/U"2 ) (pCi/t-1"2 ) (pCi /!1"2 ) (pCi / tl"2 ) 1385.31 0.79 2.020E+004 4.2 2 2E+ 0 03 7.561E+0 0 3 1401. 52 1. 33 1. 787E+004 7 .0 3 BE+003 7 .410 E+ 0 03 1407.99 2.39 1.045E+OC14 '-4.70 4 E+00 2 4 .3 7B E+0 0 3 1509.2 1 2. 1 2 1.164E+004 3.530E+003 4. 827E+ 0 03 1661.27 1.05 2.227E+004 6. 711E+003 8.99 9E+ 0 03 1729.59 2.8B 8.297E+003 2. 5 74E+003 3.352E+003
+ Bi-214 1764.49 15.30 3. 4 72E+003 6.53E+002 3.458E+00 3 1.53 4E+0 03 1847.43 2.03 8.033E+003 6.488 E+0 0 2 2.B46E+ 0 03
> 2118. 51 1.16 O.OOOE+OOO O.OOO E+OOO O.O OOE+OOO
+ Pb-214 241.~9* 7.25 4.312E+003 8.51E+002 3.15 9E+003 2.03 8E+003 295.~2 18.42 1. 735E+003 1.734E+ 0 0 3 8. 161E+002 351.93* 35.60 8. 5 11E+00 2 1.645E+003 3. 965E+00 2 7a5.96 1.06 2.334E+004 1. 095E+004 1.023E+ 0 04 Pb214-XR 74.82 5.80 7. 7 69E+003 3.44E+003 l.166E+00 4 3. 7 6 0E+ 0 0 3 77 .11 9.70 3.437E+003 '-1.0 12E+ OO: 1.645E+00 3 87.35 2. 2 4 l.331E+004 5.218E+ 003 6.353E+003 89.78 0.82 3.580E+004 1. 25 7E+004 1. 708E+00 4 Ra-226 186.21 3.64 6.683E+003 6.6BE+003 4.239E+003 3.133E+0 03 + Ac-228 129.07 2.42 1. 068E+004 l .05E+003 4.905E+003 5 .0 5 7E+0 0 3 2 09.25 3.89 5.282E+003 3.751E+ 0 02 2.4 3 4E+0 0 3 270.24 3.46 6. 5 11E+003 2.557E+002 2 .9 9 3E+ 003 328.00 2.95 7.742E+0 0 3 3.504E+003 3.533E+0 03 338.32 11.27 2.0C15E+003 3.3 8 8E+002 9 .1 2 9E+0 02 40 9 .4 6 1. 92 1 . 072E+0 0 4 1. 2 10E+002 4.778 E+0 0 3 463.00 4.40 4.770E+00 3 l. 158E+003 2.11 6E+0 0 3 7 94.95 4.25 6. 2 82 E+003 2.37 BE+003 2.77 9E+0 0 3 911. 20* 25.80 1.052E+003 1. 542E+0 0 3 4.623E+0 0 2 9 64. 7 7 4.9 9 5.478E+0 03 1.185E+003 2.4 0 1E+00 3 968.97 15.80 2.486E+003 2 . 114E+003 l .13 6E+003 1588.20 3.22 7.501E+003 l.677E+003 3. 07 5E+003 Pa-231 2 7.36* 10. 3 0 5 .646E+ 003 5.65E+003 1. 12 BE+00 4 2 .7 44 E+003 283.6 9 1. 70 1.189E+ 004 '-l. 9 10E+003 5 .4 00 E+ 00 3 300.07 2 .47 8.409E+00 3 4.1 51E+003 3. B18 E+003 302. 65 2 .20 8.801E+003 '-2 .249E+003 3. 9 65 E+00 3 3 3 0.06 1.40 1. 2 9 4E+004 '-4.5 3 3 E+003 5. 7 5 BE+00 3 Th- 2 34 9 2 . 38 2 .13 1. 2 98E+0 15 1 .3 0E+015 5.705E+014 6.195E+ Ol 4 92.80 2.10 1.312 E+01 5 7 . 557 E+ 014 6. 263E+0 14 11 2 . 8 1 0 . 21 1. 1 8 5 E+0 16 4.697 E+01 5 5. 622E+Ol5 U-235 143.76 10.96 1.956E+0 03 4 . 45E+0 0 2 '-3. 0 7 6E+0 02 9 .139E+002 1 63 . 3 3 5 .08 4. 614E+003 '-7. 763E+0 02 2 . 163E+ 0 0 3 18 5. 71 57.20 4.44 7 E+ 0 0 2 3. 9 17E+0 02 2 .091E+ 0 02 202 .11 1.08 1. 75 7 E+ 00 4 '-l .114E+004 8 .05 5E+00 3 205.31 5 . 01 4.1 82 E+ 003 9.1 02E+002 1. 9 32E+0 03 Am-24 1 5 9 .54 3 5.90 7 .58 3E+0 02 7. 58E+ 0 02 '- 2 . 2 68 E+ 0 02 3.5 6 5E+0 02 + = Nuc lide ident ified during the n u c l i de identification * = Energy line found in the spectrum > = MDA *ra lue n o t calc ulated @ = Ha lf-life t oo sho rt to be able t o per f orm the d eca::,* correct ion
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Page 2 of 6 GAMM A u P E C T R U M d N A L y s I s
'r.,"'ilrrn-Mi~ ._..-,"\:UJ UUIJU~
Filename: C:\GENIE2K\CAMFILES\RFC004.CNF Report Generated On 7/9/2015 7:24:48 AM Sample Title RFC004 Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance : 10.000 keV Sample Size
- 2.827E+001 MA2 Sample Taken On 1 / 2 8/ 2 01 3 1 2 :0 0 :00 PM Acquisition Started 6/29/2015 10:4 4 :35 AM Live Time 600. 0 seconds Real Time 600. 4 seconds De ad Time 0 .07 %
Energy Calibration Used Done On 1/27/2015 Efficiency Calibration Used Do ne On 7/8/2015 Effici e ncy ID CRIB HOUSE 3M [85]
Page 3 of 6 Report Date: 7/9/2015 7:24:48 AM Sample
Title:
RFC004 Peak: Analysis Performed on: 7/9/2015 7:24:47 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak ROI ROI Peak !Energy FWHM Continuum No. start end centroid (keV) (keV) ~ounts 1 5832 5851 5844.81 1460.51 1. 60 8.317E+OOO D.t.rk Ouln~a ::c First peak i n a multi.plet :a:egi.,n n. Green= Fitted s~nglet Errors quoted at 2. 000 sigma NUCll E IDENTIFIC TIO REPORT Sample
Title:
RFC004 Nuclide Library Used: C:\GENIE2K\CAMFILES\ZJon Ub-BNL NLB Report Generated: 7/9/2015 7:24:48 AM
...... IDENTIFIED NUCLIDES . . . . ... . .
Nuclide Id Energ:: Yield Activit y Activit:* Name Confidence ( keV) { ) (pCi / M"2 ) Unc e rtain ty
*r.:*.. ,,:c 1. .000 1. ~;50. 22 "' :t :>. 55 1 .~IS37SF.- uo,.. s . o::ne1~~<>C3 @=Energy line not used for Weig hted Me an Act ivity = Nuclide was corre c ted for parent/daughter Energ:* Tolerance : 10. 000 keV Nuclide confidence inde x thr eshold 0.30 Err ors q u oted at 2.000 sigma I TE FE ENCE CORRECTED Rf PORT Nuclide Nuclide Wt mean Wt mean Name I d Confidence Act ivity (pCi / M" 2 } Activity Uncertai nty K-40 1.000 1.763755E+004 5.031873E+003 ? = nucl..i.ae i s pa:i-:t o :f. an -~,.nd~ b .;u:min e d sol u tion = n* ,* .... . ~ - '.'i. :~ .. ,= E enc;: na 1 ,;: * .*, .., , @ - 11u cl.i r.fo con ::a .i .~s e r..19:t:~ y li.ne3 n c *t u o sc :i.n Wt.111:i.ghted Mea n Act.ivi.t y
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Interference Corrected ~tivities Report Page 4 oT ~ DNID NTIFIED ------- KS Peak Locate Performed on : 7 /9/2015 7 : 24 . 47 AM Peak Locate From Channel ~ 50 Peak Locate To Channel : 8192 Peak Energy Peak Size in Peak CPS No. {keV) Counts er Second % Uncertaint All peaks were identified. NU DA Rf PO T Detector Name
- 5456 Sample Geometry ** Cribhouse 3m Sample Title ~ RFC004 Nuclide Library Used : C ; \GENIE2K\CAMF:i:LES\Zion Li!:> *BNL . 1'1 LB Report Generated on : 7/9/2015 7 : 24 : ~9 AM Nuclide Energy Yie ld Line ~rnA Nuclide MDA Activity Dec . Le"el Name (ke") ( ':. ) (pCi/1-1"2 ) (pCi/t1"2 ) (pCi/!1"2 ) (pCi/M"2 )
+ K-40 1460.82* 10.66 4.706E+003 4.71E+003 1 .764E+004 2 .029E+003 Cr-51 320.08 9.91 1. 04 7E+013 1. 05E+013 4.200E-+:012 4.606E+012 Mn-54 834.85 99.98 1. 802E+003 1. 80E+003 6. 871E+001 7.149E+002 Co-58 810.76 99.45 1.154E+006 1.15E+006 -5.628 E+005 4.320E+005 Co-60 1173.23 99.85 6.122E+002 5.80E+002 l.934E+002 2 .636E+002 1332.49 99.98 5.803E+002 2.532E+002 2 .451E+0 02 Nb-94 702.65 99.81 2.684E+002 1. 46E+002 5.617E+001 l . 100E+002 871. 09 99.89 1. 457E+002 o-l. 880E+002 4.605E+001 Sn-113 255.13 2 .11 2.615E+006 6.97E+004 1.067E+006 1.166E+006 391.70 64.97 6. 971E+004 - 1 . 325E+0 04 2.91 9E+004 Cs-134 475.36 1. 48 4.517E+004 6.07E+002 1. 628 E+004 l. 955E+ 004 563.25 8.34 4 .655E+003 >-1. 04 5E+003 1. 742E+003 569.33 15.37 2.538E+003 1. 768E+002 9.500E+002 604. 72 97.62 6.066E+002 1.314E+001 2.516E+002 795.86 85.46 8.679E+002 8. 719E+001 3.665E+0 02 801. 95 8.69 7.386E+003 1 .616E+0 03 3.028E+003 1038 .61 0.99 5. 272E+004 -2 . 041E+003 1.97 4E+004 1167. 97 1. 79 3.754E+004 6.443E+003 1. 490E+004 1365. 19 3.02 1.701E+00 4 3.664E+003 6.027E+ 003 Cs-137 661. 66 85.10 3.233E+002 3.23E+002 1. 061 E+00 2 1. 325E+002 Eu-152 121. 78 28 .67 8.904E+002 8.90E+002 - 2 .938 E+002 4.004E+002 244.70 7 . 61 3.810E+003 l . 907E+ 002 1. 690E+003 2 95 .94 0.45 7.525E+004 3.354E+004 3 .363E+004 344.28 26 . 60 1. 04 1E+0 03 1. 552E+002 4 . 483E+002 367. 79 0.86 3.209E+004 6. 3 93E+003 1. 374E+004 411. 12 2.24 1.353E+004 7.58 8E+003 5.8 27E+003 44 3 . 96 2.83 1. 111E+004 4.32 1E+003 4 . 783E+003 488.68 0. 42 6 .049E+004 ... 3 . 309E+003 2 .4 79E+004 563.99 0.49 4.441E+00 4 2 . 773E+003 1. 720E+00 4 586.2 6 0. 4 6 3 .7 3 5E+004 ... 1.307E+004 1.323E+0 04 678 .62 0.47 5 . 514E +004 3.995E+003 2 . 188E+00 4 688 . 67 0. 86 2.795E+004 2.036E+0 03 1. 083E+004 719.35 0.28 7.8 7 6E+004 o- 4 .0 24E+004 2 . 9 48E+00 4
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Nuclide MDA Report Page 5 ~ ~ 6 Nuclide Energy Yield Line MDA Nuclide tlDA Acti*rity Dec. Le*.rel Name (keV) ( ) (pCi/tI"2 ) (pCi/H"2 ) (pCi/M"2 ) (pCi_lW2 ) 778.90 12.96 l.965E+003 -5 .113E*l-001 7. 613E+002 810.45 0.32 9.495E+004 2.637E+00 4 3.837E+004 867.37 4.26 3.857E+003 4.979E+003 1. 219E+003 919.33 0.43 6.458E+004 '-l. l 76E+004 2.502E+004 964. 08 14.65 2.267E+003 3.549E+002 9.159E+002 1085.87 10.24 2.923E+003 9.733E+002 l.132E+003 1089.74 1. 73 1. 733E+004 3.246E+003 6. 713E+003 1112. 07 13. 69 2.413E+003 9.204E+001 9.575E+002 1212.95 1. 43 1.355E+004 1.841E+003 4.283E+00 3 Eu-152 1249.94 0.19 l.308E+005 8.90E+002 '-1. 233E+005 4.635E+004 1299.14 1. 63 4.515E+003 O.OOOE+OOO O.OO OE+OOO 1408.01 21.07 l.894E+003 1. 231E+002 7.652E+002 1457.64 0.50 1.117E+005 O.OOOE+OOO 4.810E+004 1528.10 0 .2 8 2.846E+004 O.OOOE+ OOO O.O OOE+OOO Eu-154 123.07 40.40 '7.540E+002 7.54E+002 ~7. 396E+001 3.428E+002 247.93 6.89 5.001E+003 l.081E+003 2.244E+003 591.76 4.95 6.052E+003 l.00 8E+002 2. 481E+003 692.42 1. 78 2.018E+004 2.4 22E+003 8.451E+003 723.30 20.06 l.825E+003 3.834E+002 7.644E+002 756.80 4.52 4.613E+003 ""2.608E+003 l.634E+003 873.18 12.08 2 .391E+003 4.105E+002 9.261E +002 996.29 10.48 3.213E+003 5.514E+002 1. 275E+003 1004.76 18.01 1.541E+003 3.579E+001 5,769E+002 1274.43 34.80 9.956E+002 6.216E+001 3.856E+002 1596.48 1. 80 4.919E+003 O.OOOE+OOO O.OOOE+OOO Eu-155 45.30 1. 31 2.488E+004 l.34E+r:J03 ~2 .365E+003 l.098E+004 60.01 1. 22 3.053E+004 -l.167E+D04 1. 370E+004
- 86. 55 30.70 1.342E+003 -4.849E+002 6.187E+002 105.31 21.10 l.658E+003 -4.238E+002 7.529E+002 Tl-208 583.19 85.00 4. 511E+002 4.51E+002 2 .880E+002 1 .996E+002 Bi-211 351.07 13.02 2.437E+003 2.44E+003 2.223E+001 1. 087E+003 Pb-211 404.85 3. 78 7.024E+003 7.02E+003 3.675E+002 3.024E+003 427.09 1. 76 1. 325 E+004 4. 284 E+003 5.548E+003 832.01 3.5 2 8.250E+003 1-2. 74 7E+002 3.382E+003 Bi-212 39.86 1.06 2.399E+004 4.08E+003 6.174E+003 l.072E+ 004 727. 33 6.67 4.083E+003 1. 068E+0 02 l. 673E+00 3 785.37 1.10 2.709E+004 6.295E+003 1.123E+004 1620. 50 1. 47 l.358E+004 -4.152E+003 4.293E+003 Pb-212 115.18 0.60 4.517E+004 8.28E+002 -6.757E+00 3 2.069E+004 238.63 43.60 8. 279E+002 3.794E+D02 3. 813E+002 300.09 3 .30 8.381E+003 1. 087E +003 3.708E+0D3 Pb212-:~R 74.82 10.28 3 .945E+003 1.67E+0D3 l.104E+003 1. 855E+003 77 .11 17.10 l.6 69E+0 03 1-5.979E+002 7 .651E+002 87.35 3.97 7.413E+003 1.930E+001 3 .42 2E+ 003 89.78 1. 4 6 1. 832E+004 '-5. 686E+003 8 .38 7E+00 3 Bi-214 609.32 45.49 l.150E+003 1. 15E+003 9.410E+002 5.25 7E+002 768.36 4.89 5 . 371E+003 '-8.56 8E+002 2.170E+ 003 806.18 l. ~6 1.624E+004 '-l.257E+003 6.079E+003 934.06 3.11 7.107E+003 1-1. 926E+0 03 2.660E+003 1120. 29 14.92 3.016E+003 1. 22 1E+003 1.305E+003 1155.21 1. 63 2.087E+004 l.688E+00 3 8 .555E+003 1238 .12 5 .83 8.085E+003 2 .390 E+003 3 . 499E+00 3 1280.98 1. 43 2 .178E+004 8.307E+003 8.643E+rJ03 1 377 .67 3.99 9.310E+003 3.65 4E+ 003 3.81 6E+ 003
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Nuc1ida MCA Report Page 6 er 15 Nuclide Energ.1 Yield Line MDA Nuclide tfDA Acti *:i ty Dec. Le*Tel Name (keq ( ) (pCi/W'2 ) (pCi/I1"2 ) (pCi/M"2 ) (pCi/MA2 ) 1385. 31 0.,9 4.100E+004 '-4.691E+003 1.627E+004 14 01. 52 1. 33 2.254E+004 4.340E+003 8.733E+003 1407.99 2.39 l.570E+004 5.227E+0 02 6.435E+003 1509.21 2.13 l.316E+004 ---1. 223E+003 4. 926E+003 1661. 27 1.05 1.937E+004 ---3.948E+003 6.123E+003 1729.59 2.88 1. 285E+004 4.902E+003 5. 100E+003 Bi-214 17 64. 4 9 15.30 4.189E+003 l.15E+003 ~.478E+003 1. 842E+003 1847.43 2.03 l.339E+004 7.209E+002 4.744E+003 I> 2118. 51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OO O Pb-214 241. 99 7.25 4.065E+003 9.91E+002 1. B4E+003 l.835E+003 295.22 18. 42 1. 617E+003 9.130E+ 002 7.228E+002 351. 93 35.60 9.912E+002 2.21 6E+002 4.473E+002 785.96 1.06 2. 962E+004 6.221E+ 003 1. 240E+004 Pb214-XR 74.82 5.80 6.999E+003 2.95E+003 l.959E+003 3.2 92 E+003 77 .11 9.70 2.946E+003
- l .055E+003 1.350E+003 87.35 2.24 l.315E+004 3.424E+001 6.072E+003 89.78 0.82 3.265E+004 ~1. 013E+004 l.495E+ 004 Ra-226 186.21 3.64 7.578E+003 7.58E+003 3.023E+002 3.441E+003 Ac-228 129.07 2.42 9.723E+003 l.48E+003 4.619E+002 4.388E+003 209.25 3.89 7.172E+003 2.065E+ 003 3.242E+003 270.24 3. 46 7.076E+003 *3.280E+002 2 . 101E+003 328.00 2.95 9.109E+003 1.640E+003 3.991E+003 338.32 1 1.27 2.357E+003 *3.973E+002 1. 029E+003 409.46 1. 92 1.007E+004 ---5.889E+003 4.067E+003 463.00 4.40 5.250E+003 ---2.202E+003 2.177E+00 3 794.95 4.25 8.381E+003 4 .119E+003 3.588E+003 911. 20 25.80 l.477E+003 3.139E+002 6.324E+002 964.77 4. 99 5.468E+003 6.257E+ 001 2.170E+003 968. 97 15.80 2.095E+003 7.426E+001 8. 686E+002 1588.20 3.22 1.174E+004 4.995E+003 4.744E+003 Pa-231 27.36 10 .30 2.603E+003 2.60E+003 --- 5 . 701E+002 l.170E+0 03 283.69 1. 70 l.618E+004 5.820E+003 7 .1 79E+003 300.07 2.4 7 1.120E+004 l.452E+ 003 4 . 954E+0 03 302.65 2.20 l.1 44E+004 ~6.509E+003 4.995E+003 330.06 1. 40 1.595E+004 ---8.435E+003 6.786E+003 Th-234 92 .38 2.13 1.432E+015 1. 43E +015 4. 29 8E+014 6. 611E+014 92 . 80 2.10 1.439E+015 5 .0 32E+014 6 . 637E+014 112 . 81 0.21 1. 252E+016 2 . 839E+Ol4 5. 698E+015 U-2 35 14 3 .76 10. 96 2.288E+003 4.88E+ 002 6.066E+002 l .037E+003 163.33 5.08 5.27 0E+0 03 1.660E+003 2.396E+003 185. 71 57.20 4. 8 77E+0 02 1. 326E+002 2.217E+002 202. 11 1.08 2 . 119E+004 --- 8 . 7 65E+003 9 .377E+003 205.31 5 . 01 4.9 92 E+00 3 ~2 . 8 75E+00 2 2 . 231E+003 Am-241 59 . 54 35.90 8 . 204E+002 8 .20E+002 l. 653 E+002 3 .725E+O O~
+ ~ Nuclide identified during t he nuclide identification .,, =- Energy line found in the spectrum > "' tmA ,*alue not calculated @ Half-life too shor t to be able t o perform the deca:- correction
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Page 2 of 7 GAMM A u P E C T R U M . i N ALYSIS Filename: C:\GENIE2K\CAMFILES\RWC005.CNF Report Generated On 7/9/2015 7:29:31 AM Sample Title RWC005 Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance : 10.000 keV Sample Size
- 2.827E+001 M"2 Sample Taken On 1 /28/2013 12: 00:00 PM Acquisition Started 6/29/2015 9:32:20 AM Live Time 600.0 seconds Real Time 600 .6 seconds Dead Time 0.10 %
Energy Calibration Used Done On 1/27/2015 Efficiency Calibration Use d Done On 7/8/2015 Efficiency ID CRIB HOUSE 3M [90]
Page 3 of 7 Report Date : 7/9/2015 7:29:32 AM Sample
Title:
RWC005 Peak: Analysis Performed on: 7/9/2015 7:29:31 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak ~OI ~or Peak Energy FWHM ~ontinuum INo. start iend cent r oid (keV) (keV} C:ounts 1 2431 2444 2438.15 609.44 1.50 1.367E+001 2 5834 5855 5844.48 1460.43 1.32 2.934E+OOO 3 7056 7067 7061.98 1764.34 0.36 0.000E+OOO
- r.hu:.k O:r.a:ng e = :Fi r:st. paak :*.n a mu l.t.ip1et. :regi .on L
Green ;, Fitte d sing .let Errors quoted at 2.000 sigma UCIIDE IDENTIFICATll'N RE O T Sample
Title:
RWC005 Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Ub~BNL.NLB Report Generated: 7i9/2015 7:29 32 AM
. ..... IDENTIFIED NUCLIDES .........
Nuclide Id Energy Yield Activ i t y Activit:* Name Confide nce ( keV) ( *.) (pCi 'M"2 ) Uncertaint:*
- --.: --,~o .000 Vl 6C. El 2 * :LO .S5 Z . ::56G0S1,; :-00i, 6 . C/ .31* *::~
~***C:O~ ,:°l)_*- 2 ':i../, 'i . ~00 SC!?.:;2 ~ 4:S. u ; 1 . /31. 9 1ji!*I* 003 , o 575gw;.;.o'J~
768.3 6 4 . 89 806.18 1.26 93 4 . 0 6 3 .11 1120. 29 14. 92 1155.21 1. 63 12 38 .1 2 5.83 1 280 . 98 1.43 1377. 6 7 3. 9 9 138 5. 3 1 0.7 9 140 1 . 52 1. 33 1407.99 2.3 9 1 5 0 9 .21 2.13 1661. 2 7 1.05 1729 . 59 2 . 88 l i S-1 . 1, 9 6 15 .30 J. 1 -1, 35:t.--~o:3 *1. . J:3 /}S 5.K . OC3 18 47. 43 ' 2 . 03 211 8 .51 1.16
,,._, E.:.,~ Y:g ~r J. ;1 1, ;-:- .f:o '!.1.C*d .'1.~l 1:~):::. ,j**,;,~c ~,.:.,;:n: . ~ = Ene r g~* l ine n o t u sed for Weighted Hean Ac ti ni t y = Nu c lide was corrected for p a r e nt /dau g h t e r Ene rgy To l e ranc e : 10.000 keV Nuclide con fid e n ce inJex threshold 0 . 30
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Interference Corrected - ~tivities Report Page 4 OT~ INTERFERE CE C RRECTED R PO Nuclide Nuclide Wt mean Wt mean Name Id Confidence Activity (pCi/M"2 } Activity Uncertaint y K-40 1.000 3.568092E+004 6.813408E+003
,;-: :.~.1.:1. *. .,. 3SO Bi-214 1.000 1.979829E+003 6.437546E+002 ? ~ Dtl Cl.i.de .is .PIii rt: o.f a u u n.cl~ t;e:r.n1i.ned. s ,o:l11ti.('n X. - ....l.' ~i. r E:>iecte ' l:-y tJ .e ::i. arf-:renc Ana.iy.s1.s @ = nuc.1..ide con tain :-1 energy lines riot u s e d .in W~ i g ht:.c.=::d Mea n Ac t .i.v i t .
E:1:zor tJ ~1u oted at 2. 000 s igma UNID TlflED PE s Peak Locate Performed on~ 7/9/2015 7 : 29 : 3 1 AM Peak Locate From Channel : 50 Peak Locate To Channel : 8192 Peak Energy Peak Size in Peak CPS No. (keV} Counts er Second % Uncertaint All peaks were identified.
~NU=-=-=~~=-=---~~RT Detector Name : 5456 Sample Geometry / Cribhouse 3m SampJ.e Title : RWC005 Nuclide Library Used ; C : \GENIE2K\CA_Tl.1FILES\Zion Lib*- BNL NLB Reporc Generated o n : 7/9/2015 7 :* 29 i 32 AM Nucl ide Energy Yield Line rrnA Nuclide MDA Actiuity Dec. Le*.*el Name (keV) (. } (pCi/M"2 ) (pCi/tl'2 ) (pCi 1 W'2 ) (pCi / t-1"2 ) + K-40 U60.82* 10.66 3.330E+003 3.33E+003 3.568E+004 1.341E+003 Cr-51 320.08 9.91 1.046E+013 1. 05E+013 1. 418E+012 4.600E+012 !ln-54 834.85 99.98 1.479E+003 1. 48E+003 r-5.840E+002 5.537E+002 Co-58 810.76 99 .4 5 1. 786E+006 1. 79E+006 r-7.143E+004 7.478E+005 Co-60 11-:'3.23 99.85 4.431E+ 002 3.09E+002 r-l. 440E+00 1 1.791E+002 1332.49 99.98 3.093E+002 r-5.413E+001 1.096E+002 Nb-94 702.65 99.81 3 .113E+002 2 .79E+002 2.681E+000 1. 315E+002 871.09 99.89 2.791E+002 -8.00 0E+ 00l 1.128E+002 Sn-113 255.13 2 . 11 2 . 761E+006 9.39E+ 004 1. 081E+006 1 .239E+006 391.70 64.97 9.387E+004 - 2 .718E+004 4 .1 28E+00 4 Cs-134 475.36 1. 48 3.167E+004 7. 48 E+002 -7.298E+003 1. 280E+004
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Nuclide MDA Report Page 5 ,---f: 7 ' Nuclide Energy Yield Line UDA Nuclide rmA Acti *.*it:* Dec. Level Name ( ke) ( ~) (pCi/M"2 ) (pCi/11-2 ) (pCi/M"2 ) (pCi /IJ"2 ) 563.25 8.34 7.206E+003 5.285E+002 3.018E+003 569.33 15.37 2.832E+003 2.358E+002 l.09 7E+003 604.72* 97.62 8.771E+002 l.816E+003 3.866E+002 795.86 85.46 7.481E+002 -1.655E+002 3.067E+002 801.95 8.69 8.197E+003 3.074E+003 3.433E+003 1038.61 0.99 5.272E+004 4.898E+003 1.973E+004 1167.97 1. 79 2.659E+ 00 4 5.011E+003 9.420E+003 1365.19 3.02 l.701E+004 -1.374E+0 03 6.026E+003 Cs-137 661.66 85.10 2.823E+002 2.82E+002 -9.581E+001 1.12 0E+002 Eu-152 121. 78 28.6; 1.123E+003 1.08E+003 5.695E+002 5.16 9E+002 244.70 7.61 3.890E+003 1. 94 6E+002 1.730E+003 295.94 0.45 7.525E+004 1.967E+00 4 3.363E+004 34-L28 26.60 1. 075E+003 2.673E+001 4.653E+0 02 367.79 0. 86 2,404E+004 r-8, 097E+003 9.714E+003 411. 12 2.24 1.308E+004 5.210E+002 5.598E+003 443.96 2.83 8.042E+003 r-2.89 9E+003 3.24 9E+003 488.6B 0.42 6.391E+004 .- l , 951E+0 0 4 2.650E+004 563.99 0. 4 9 5.866E+004 r-1. 54 8E+004 2.433E+ 004 586.26 0.46 4.831E+004 r-1. 911E+004 1.871E+004 678.62 0. 47 6.315E+004 .-7.961E+003 2.589E+004 688. 67 0.86 2 .795E+004 -6.5 45E+003 l.0 83E+004 719.35 0.28 1.032E+005 r-4.451E+004 4.169E+004 778.90 12. 96 2.308E+003 2.454E+002 9.324E+002 610.<JS 0.32 1.068E+005 r-2 .104E+0 03 4 . 430E+ 004 867.37 4.26 7.391E+003 r-2. 118E+003 2 . 987E+003 919.33 0. 43 7.582E+004 8.961E+003 3.064E+004 964. 08 14.65 2 .6 78E+003 2 .90 2E+002 1.122E+003 1085 .8 7 10.24 2.923E+003 1. 369E+002 l.132E+003 1089.74 1. 73 1. 891E+004 3.246E+003 7.505E+003 1112. 07 13.69 3.206E+003 1. 086E+003 1.354E+003 1212.95 1. 43 2 .921E+004 5.17 8E+003 1. 211E+004 Eu-152 1249.94 0.19 1.987E+005 1.08E+003 7.044E+003 8.028E+004 1299.14 1. 63 2.187E+004 2.920E+003 8.679E+003 1408.01 21. 07 1.445E+003 -2.23 8E+001 5.410E+00 2 1457.64 0.50 1.188E+005 O.OOOE+OOO 5 .167E+004 1528.10 0.28 7.738E+004 1.052E+004 2.446E+004 Eu-154 123.07 40.40 7.739E+002 7 . 74 E+002 -2.766E+0 02 3.527E+002 247.93 6.89 5 . 72 0E+00 3 3.375E+003 2 . 604E+0 03 591. 76 4.95 5.284E+003 -7.054E+002 2.097E+003 692.42 1. 78 1.7ll8E+00 4 2 .57 3E+003 6 .9 00E+ 003 723. 30 20 .06 1.179E+003 - 8 .58 0E+ 002 4.413E+002 756. 8 0 4.52 7 . 459E+003 -1.2 60E+003 3.057E+003 873.18 12 .08 2.98 9E+003 2.986E+002 1.2 25E+003 996 .29 10.48 3. 680E+003 5 .2 51E+00 1 1. 508E+003 1004.7 6 18.01 1. 720E+003 r- 6.26 4E+00 1 6.661E+002 1274.43 34.80 8.92L!E+002 8.288E+001 3.340E+002 1596.48 1.BO l.3 38E+004 r- 4 .5 45E+003 4. 229E+0 03 Eu-155 45.3 0 1. 31 3.142E+004 1 . 50E+003 r-7. 848E+00 3 1.425E+ 004 60 . 0 1 1. 22 5 .120E+004 6 .0 28E+003 2.4 04E+004 86 . 55 30 .70 l. 503E+0 03 r-1. 38 9E+003 6 . 991E+002 105 .3 1 21.10 2 . 149E+003 l.8 24E+002 9.981E+0 02 Tl-2 08 583 . 19 85 . 00 5 . 327E+002 5 . 33E+0 02 3 .59 3E+002 2 . 404E+002 Bi-211 351.07 1 3 . 02 3 . 270E+003 3,2--,,E+003 2 .6 37E+003 1. 503E+ 003 Pb-211 404 . 85 3 . 78 6 . 00BE+003 6 .0lE+OO~ 4. 206E+002 2 .51 6E +003 [93]
Nuclide MDA Report Page 6 rr 7 Nuclide Energy Yield Line ~JOA Nuclide MDA Activit:,* Dec. LeTTel Name ( ke") (. ) (pCi/t1"2 ) (pCi/1-12 ) (pCi IM"2 ) (pCi/M"2 ) 427.09 1. 76 1.496E+004 4.372E+0 03 fi.407E+003 832.01 3.52 8.717E+003 -2.060E+002 3.615E+003 Bi-212 39. 86 1.06 3.091E+004 5.64E+003 1.142E+.0 04 1.418E+004 727.33 6.67 5.635E+003 l.604E+003 2.450E+003 785.37 1.10 3.096E+004 8.575E+003 1.317E+004 1620.50 1. 4 7 1. 987E+004 5.536E+003 7.436E+003 Pb-212 115 .18 0.60 5.052E+004 9.44E+002 1.573E+004 2.336E+004 238.63 43. 60 9.435E+002 7.993E+002 4.391E+002 300.09 3.30 8.000E+003 >-1.604E+003 3.518E+003 Pb212-XR 74.82 10.28 5.030E+003 2.34E+003 4.285E+003 2. 395E+003 77 .11 17.10 2.342E+003 -8.600E+002 1.102E+00 3 87 .35 3.97 8.512E+003 1-l. 5 7 9E+003 3. 972E+003 8~.78 1. 4 6 2.309E+004 1-5.575E+003 l.077E+004
+ Bi-214 609.32* 4 5. 4 9 8.379E+002 5. 05E+002 1. 735E+003 3.693E+002 768.36 4.89 6.907E+003 1. 748E+003 2.938E+003 806.18 1. 26 1. 812E+004 2.923E+003 7 .020E+003 934.06 3.11 9.914E+003 2.594E+002 4.064E+003 1120.29 14.92 3.108E+003 1.837E+003 1.351E+003 1155. 21 1. 63 1. 960E+004 2.954E+ 003 7.920E+003 1238.12 5.83 6.698E+003 2. 311E+003 2.80SE+003 1280.98 1. 43 2 .178E+004 4.901E+003 8.643E+003 1377. 67 3.99 1.033E+004 5.580E+003 4.327E+003 13d5.31 0.79 3.367E+004 4 .170E+003 1. 260E+004 1401. 52 1.33 2. 461E+004 3.191E+003 9.764E+003 1407.99 2.39 1.125E+004 3.485E+002 4.212E+003 1509.21 2.13 1. 603E+004 3.790E+003 6.360E+003 1661. 27 1.05 2.444E+004 5.264E+003 8.659E+003 1729.59 2.88 1.178E+004 2.574E+003 4.5 62 E+003 + Bi-214 1764.49* 15.30 5.050E+Oo;:: 5.05E+002 3 .172E+003 O.OOOE+OOO 1847.43 2 .03 1.061E+004 1.442E+003 3.354E+003 I> 2118. 51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO Pb-214 241. 99 7.25 4.128E+003 1.25E+003 2 .563E+002 1.866E+003 295.22 18.42 1.788E+003 9.904E+002 8.081E+002 351.93 35.60 1.248E+003 1. 115E+003 5.755E+002 785.96 1.06 3. 224E+004 6.463E+003 1.371E+004 Pb214-XR 74.82 5.80 8.925E+003 4.13E+003 7 .6 03E+0 03 4.255E+003 77.11 9.70 4 .133E+003 1-1.518E+003 l.944E+003 87.35 2.24 1.510E+004 -2.8 02E+003 7 .047E+003 89.78 0.82 4.115E+004 >-9.936E+003 1.920E+004 Ra-226 186.21 3.64 7.147E+003 7.15E+003 4.838E+002 3.225E+003 Ac-2L8 12 9.07 2.42 1.176E+00 4 1.92E+003 - 2 .867E+003 5.404E+003 209 .2 5 3.89 6.365E+003 6.277E+002 2 .838E+003 270.24 3. cJ 6 6.700E+003 -3.8 57E+003 2 . 913E+003 328.00 2.95 9.998E+003 4.627E+003 4.4 36E+ 003 338.32 11. 27 2.481E+003 >-2 ,9 17E+002 1. 091E+003 409.46 1. 92 1. 189E+004 -1. 090E+003 4.982E+003 463.00 4.40 7.243E+003 1.552E+003 3.174E+003 794.95 4.25 6.686E+003 3.180E+rJ01 2. 7 41E+003 911. 20 25.80 l.92 5E+003 1.518E+003 8.563E+002 964. *77 4.99 6.951E+003 4.403E+002 2 . 911E+003 968.9 7 1 5 .80 2.655E+003 1. 268E+0 03 1.14 9E+003 1588.20 3 . 22 1. 321E+004 5.8 28E+ 003 5 .4 7 8E+003 Pa-231 27.36 10.30 2.064E+00 3 2 .06E+0 03 -2.390E+002 9 .00 9E+002 283 .69 1. 70 l.652E+004 4.347E+0 03 7 .3 48E+003
[94]
Nuclide MDA Report PagQ 7 - 7 Nuclide Energy Yield Line t-1D1-i. Nuclide IIDA Acti*rity Dec. Level Name (ke) ( ) (pCi/[1"2 ) (pCi/U"2 ) (pCi/N"2 ) (pCilti"2 ) 300.07 2. 4 7 1. 06~E+004 2.l43E+003 4.700E+003 302.65 2.20 1. 113E+004 -l.244E+003 4.837E+003 330.06 1. 40 1.595E+004 -7.295E+003 6.786E+003 Th-234 92.38 2 .13 1.765E+015 l.76E+015 3.231E+014 8.275E+014 92.80 2.10 1.801E+015 3.812E+Ol4 8. 449E+014 112. 81 0.21 1. 233E+016 -3.265E+015 5.608E+015 U-235 143.76 10. 96 2.352E+003 4. 81E+002 ,--; . 442E+002 1.069E+003 163.33 5.08 5.409E+003 1.222E+003 2.465E+ 003 185. 71 57.20 4. 811E+002 7.937E+001 2. 1 84E+002 202 .11 1.08 2.166E+004 -8.305E+003 9.60 8E+003 205.31 5.01 6.290E+003 3.702E+003 2.880E+003 Am-241 59.54 35.9CJ 1. 228E+003 1. 23E+003 2.858E+002 5.763E+002
+ = Nuclide identified during the nuclide identification
- Energ~* line found in the spectrum
> t1DA ~,alue not calculated @ Half-life too short to be able to perform the deca~* correction
[95]
Page 2 of 7
'GA MM A - P E C T R U M -~ N A L Y S I S 9 -
Zm SUL i
- lfJ. , **.;
1t i'!.:'~'."7.!~ 1\-t':1: - (*;~:, . Filename: C:\GENIE2K\CAMFILES\RWC006.CNF Report Generated On 7/9/2015 7:30:28 AM Sample Title RWC006 Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels): 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance : 10.000 keV Sample Size
- 2.827E+001 MA2 Sample Taken On 1 / 28/2013 1 2 :0 0 : 00 PM Ac quisiti on Started 6/29 / 2015 2 :02:22 PM Live Time 600 . 0 s econds Real Time 600 .7 seconds Dead Time 0 .11 ~
Energy Calibration Use d Do n e On 1 /2 7 /2 015 Efficiency Calibrat i on Used Done On 7 / 8 /2 015 Efficiency ID CRIB HOUSE 3M [96]
Page 3 of 7 Report Date : 7/9/2015 7:30:28 AM Sample
Title:
RWC006 Peali Analysis Performed on: 7/9/2015 7:30:27 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak IROI ROI Peak Energy FWHM Continuum No. start end centroid (keV) (keV) ~ounts 1 1174 1187 1180.57 2 95.00 0.85 3.150E+ 0 01 2 1402 1415 1408.31 351.95 0.87 2 .771E+001 3 2325 2339 2333.11 583.19 0.85 3.750E+OOO 4 2429 2444 2437.50 609.28 0.43 2 . 800E+001 5 3872 3881 3876.95 969.02 0.74 2.525E+OOO 6 4477 4488 4482.09 1120.20 0.79 1.030E+001 7 5837 5858 5845.86 1460.78 2.11 2.334E+OOO D ar.k. Orange :.:: F'i:r.s *t peak .i.:l;'l :. DTl.l.l.t i p.lcilt .r.t!Ag.ion. Gr~en : , Fit.t:.~d ei.ngie *.: Errors quoted at 2. 000 sigma N l D IDE TIFIC TIIN REPORT Sarnple Tille.: RVVC006 Nuclide Lib1ant Used : C:\GENIE2K\CAMFILES\Zion Ub-BNL.NLB Repo,t Generated: 7/9/2015 7:30:28 AM Nuclide Name Id Confidence IDENTIFIED NUCLIDES Energ y (keV } Yie ld (-; } Ac ti,,i t ~* (pCi /M A2 } Activi t y I Unce rt a inty K--~~O -~. 000 l/J G0. C.?. ~ 1 0.56 3. ss.sr.,r :-~+ 001~ S. '0 21 5 rJ** OJ3
'i'.l *-.?.0 i'; :.. . 000 5e 3 . 1 s *.* G:::i .JO ~ . 1,; 727:l!+OC2 3 . .l. ~C c ?.K ~OO?.
r,:i -'.n,~ .:. . OJO sos. 3 ~ *** 11!:i.~9 2 . ~O(Sl.lk ***CO.:J D. ?.:~ t,;; .;r-:; .*OC?. 7 66. 3 6 4.89 80 6 .18 1.26 93 4.06 3 . 11
,1,J. 20. ~9
- F . fl'..1 3 . 6 9 Gi 9i:'.+ OC:! 2 . :vu:n:u::-f-~c,:,
1155. 2 1 1. 63 1 238 .1 2 5.83 128 0.98 1. 43 1377 . 67 3.99 1385 . 3 1 0 . 79 1 40 1. 52 1. 33 14 07 . 99 2.3 9 15 0 9. 21 2 :1 3 16 61. 27 1.05 1729 . 59 2 .88 176 4.4 9 15.30 1847 . 43 2 . 03 2 118 .51 1.16 [97]
Interference Corrected *ctivities Report Page 4 o~ 7 Nuclide Id Energy Yield A.ctivity A.ctivity Name ~onfidence (keV) ( %) (oCi/M"2 ) Uncertaintv 295 . J
- 1 8 42. ;2 . 6 -~ J.l.'lE**HW ]. . ,49691'E+OO 35.l 9 3 * ;35 . 60 2 . Ci8138E-~00 Ii! . 92 '727E+!'r0 785.96 1. 06
.. .,. ... ... ** .. _, .. - ~~ ... . ' @ Energ~ line not used for Weighted Hean Activit~
Nuclide 1ras corrected for parent/daughter Energ:* Tolerance : 10. 000 keV Nuclide confi dence index threshold = 0 .30 Errors quoted a t 2.000 sigma INTERF R NC CO RECTED EPOR Nuclide Nuclide Wt mean Wt mean Name Id Confidence Activity (pCi/M2 ) Activity Uncertainty K-40 1.000 3.585936E+004 6.772464E+003
.*~--e* '
- B - :LU C . u. e:
*A* r=-..-*JJ (; . :3 S.** J..
Tl-208 1.000 9.472712E+002 3.190822E+002 X ~ i --~:. .l I'.) '.j .G9 Bi-214 1.000 2.436637E+003 8.465972E+002 Pb-214 1.000 2.238944E+003 7.670049E+ 002
'? - nucl ide :Ls p a:r t o :t7 ll.:n u i.ideter.nti.:1sid sol .u t.ion 'r = u_llat.1 . ;.,*** ~ct...-.3 ~o**: th"' ti*, 1 :-",:... 1.: 41!*:!:-~-;,::. "-11<1: ~n . 1*:_- i @ = nu c l:Lde ooc:..:.i.;..ins e ii1,e r ~'J!" l :i.nas no-t 'i.-r.s ed i n Weigb t!Eld Mean Ac ti:t":i.*i;y Error~ q 1i o ted a.t 2 . 000 :o.i .graa ENTIFIE Peak Locate Performed on : 7/9/2015 7
- 30
- 27 ATl.1 Peak Locat e From Channel : 50 Peak Locate To Channel ~ 8192 Peak Ene rgy Peak Size in Peak CPS No. (keV) Counts per Second % Uncertaintv 5 969.02 2.9125E-002 55.56 M First peak in a multiplet region m ~ Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma
[98]
111:lldl 11111011 arr,a 5 DI J NUCLIDE MDI REPORT Detector Name: 5456 Sample Geometry: Cribhouse 3m Sample
Title:
RWC006 Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Report Generated on: 7/9/2015 7:30:29 AM Nuclide Energ~* Yield Line UDA Nuclide HOA Acti*rit:* Dec. Level Name ( ke*r) ( . ) (pCi/M"2 ) (pCi/Il"2 ) (pCi/H"2 ) (pCi / I1" 2 )
+ K-40 14 60. 82* 10.66 2.857E+003 2.86E+003 3.586E+004 l.104E+ 003 Cr-51 320.08 9.91 1.213E+013 l.21E+013 3.942E+012 5.433E+01 2 Mn-54 834.85 99. 98 2.184E+003 2.1BE+003 6. 711E+002 9.0 57E+002 Co-58 810.76 99.45 1.516E+006 1. 5 2E+006 -3.62 9E+005 6. 126E+005 Co-60 1173.23 99.85 5.469E+002 5.30E+002 1.986E+002 2.310E+002 1332. 49 99.98 5.304E+002 2.0 89E+ 002 2. 200E+00 2 Nb-94 702.65 99.81 2.985E+002 2.98E+002 1. 2 94E+002 1.250E+002 871.09 99.89 2. 97 5E+002 7.783E+OOO 1. 219E+00 2 Sn-113 255.13 2 .11 3.061E+006 1. 07E+005 -5.106E+005 1.390E+0 06 391.70 64.97 1. 067E+005 5.198E+004 4. 7 71E+0 0 4 Cs-134 475.36 1. 48 3.571E+004 7. 50E+oo.::: -4.221E+002 l.481E+004 563.25 8.34 5.684E+003 t-l,995E+003 2 . 2 56E+003 569.33 15.37 4 . 118E+003 2.955E+ 002 1. 739E+003 604. 72* 97.62 1. 265E+003 2.309E+003 5. 803E+0 02 795.86 85. 4 6 7.4 95E+002 -1.070E+ 001 3. 072E+002 801. 95 8.69 7.818E+003 t-3.3 88E+ 002 3. 242E+003 1038.61 0.9 9 6.406E+004 1.222E+004 2.5 42E+0 0 4 1167. 97 1. 79 3.436E+004 1.144E+004 l . 331E+004 1365.19 3.02 1.977E+00 4 1. 837E+003 7 .401E+003 Cs-137 661.66 85.10 4.342E+002 4.34E+002 1. 85 0E+00 2 1. 879E+002 Eu-1 52 121.78 28.67 1.415E+003 1. 41E+003 B.547E+0 01 6. 63 2E+00 2 244.70 7.61 4. 57 BE+003 1. 232E+002 2.0 75E+003 295.94 0. 45 1. 046E+005 5 .BOBE+0 0 4 4.8 35E+004 34 4 .28 26.60 1. 412E+003 8.3 32E+00 2 6. 337E+002 367.79 0.86 3 . 9 19E+004 1. 29 0E+004 1. 72 9E+00 4 411.12 2 .24 9.802E+003 .... 9.383E+003 3. %1 E+003 443. 96 2.83 9. 51 8E+o0 3 -2. 7 92E+003 3 . 986E+003 48 8 .68 0 .4 2 9.495E+004 4.2 2 0E+00 4 4 . 2 01E+00 4 563.99 0. 4 9 4.860E+004 - 2 . 3 17E+004 1.928E+004 586.26 0 . 46 4.843E+004 -4.083E+004 1. 87 6E+004 678.62 0.47 7.34 5E+00 4 1.191E+00 4 3 .102E+0 04 688 .67 0. 86 4. Z32E+004 1. 5 43E+004 1 . 800E+ 00 4 71 9 . 35 0 .28 1. 034E+ 005 - 9 .167E+003 4 . 179E+004 778.90 12 .96 2. 601E+ 003 8 . 606E+00 2 l. 079E+003 810.45 0 . 32 9 . 510E+004 - 2 . 697E+0 0 4 3.843E+00 4 86 7. 37 4. 2 6 6. 87 8E+003 - 8 .13 2E+002 2 . 729E+003 919 . 33 0. 43 7.036E+004 5.63 5 E+0 03 2 . 792E+004 964. 08 14. 65 2 . 90 8E+o 03 6. 8 19E+0 02 1. 237E+0 03 1085.87 10 . 24 2 . 917E+003 fi . 526E+00 2 1.130E+003 1089 . 74 1. 7 3 1. 33 7E+004 -3. 239E+0 03 4 . 73 7E+ 003 1112 .07 13. 69 2 . 409E+ 003 4 .1 34 E+0 02 9 .558E+ 002 1 212. 95 1. 4 3 2 . 596E+ 004 2. 301E+0 03 1. 04 9E+0 04 Eu-152 1249. 94 0 .19 2.2 37E+00 5 1.41E+OU3 2 . 071E +004 9 . 278E+0 04
[99]
Nuclide MDA Report Page 6 of 7 Nuclide Energ:, Yiel d Line MD.?\ Nuclide MDA Activity Dec. Le*rel Name (keV) ( :) (pCi/H'*2 ) (pCi/tY'2 ) (pCi/tI* ' 2 ) (pCi/W2 ) 1299.14 1. 63 2.192E+004 6.021E+003 8.700E+003 1408. 01 21.07 2.343E+003 1.086E+003 9.895E+002 1457.64 0.50 8.094E+004 -1.5':'8E+004 3. 271E+004 1528.10 0.28 9.756E+004 2. 101E+004 3.456E+0 04 Eu-154 123.07 40. 40 1.133E+003 1.13E+003 5.750E+002 5.323E+002 247.93 6.89 5.539E+003 4.961E+002 2.515E+003 591. "76 4.95 6.068E+003 ... 3.175E+002 2. 487E+003 692.42 1. 78 2 .115E+004 1.882E+003 8.930E+003 723. 30 20.06 1.548E+003 -4.300E+002 6.256E+002 756.80 4.52 7.89dE+003 -3.lllE+OOl 3.275E+003 873.18 12.08 3.882E+003 1.774E+003 1.671E+003 996.29 10.48 3.878E+003 1.955E+003 l .608E+003 1004.76 18.01 1. 872E+003 -<i.855E+002 7. 429E+002 1274.43 34.80 1.247E+003 3.113E+002 5 .110E+002 1596.48 1. 80 4.909E+003 O.OOOE+OOO O.OOOE+OO O Eu-155 45.30 1.31 4.315E+o04 2.12E+003 --8.023E+003 1. 964E+004 60.01 1. 22 6,141E+004 1. 051E+002 2.915E+004
- 86. 55 30.70 2.124E+003 --3.568E+002 1. 010E+003 105.31 21.10 2.504E+003 5.701E+002 1.177E+003
+ Tl-208 583.19* 85.00 2.599E+002 2.60E+002 9.473E+002 1.039E+002 Bi-211 351.07* 13.02 3.065E+003 3.07E+G03 5.685E+003 1. 401E+003 Pb-211 404.85 3.78 6.283E+003 6.28E+003 >-1.226E+003 2.653E+003 427.09 1. 76 1.498E+004 '-l.194E+003 6. 414E+003 832.01 3.52 7.213E+003 2.751E+002 2.862E+003 Bi-212 39.86 1. 06 4.014E+004 5.65E+003 --1.287E+004 1.805E+004 727.33 6.67 5.648E+003 1.839E+003 2.455E+003 785.37 1.10 2.568E+004 2.565E+003 1.053E+004 1620.50 1. 47 1.355E+004 --9.206E+002 4.283E+003 Pb-212 115 .18 0.60 5,824E+004 1.09E+o03 --4.453E+003 2.724E+004 238.63 43.60 l.090E+003 l.097E+003 5.12 6E+002 300.09 3.30 1. 016E+00 4 2 .462E+002 4.599E+003 Pb212-XR 74.82 10.28 5.869E+003 2. 71E+003 4.438E+003 2. 81 9E+003 77 .11 17.10 2.714E+003 '-l.696E+003 l.289E+003 87.35 3. ~:J7 l. 131E+004 6.598E+002 5.370E+003 89.78 1. 46 2 .808E+004 '-2.542E+003 1.327E+004 + Bi-214 609.32
- 45.49 l.208E+003 1.21E+003 2.205E+003 5. 5 43E+002 768.36 4.89 8. 972E+003 4.927E+003 3.970E+003 806.18 1. 2 6 2.518E+004 5.583E+003 1.055E+004 934.06 3.11 1.442E+004 5.397E+003 6.320E+003 1120.29* 14.92 2.907E+003 3.697E+003 1.251E+003 1155.21 1. 63 2.202E+ 004 '-6. 507E+003 9.134 E+003 1238.12 5.8 3 7 .005E+003 2 .835E+003 2.958E+003 1280.98 1. 43 3. 24 3E+004 1. 082E+004 1. 3 96E+004 1377.67 3.99 1.036E+004 2.624E+003 4.337E+003 1385. 31 0.79 2 .910E+004 --1. 567E+003 1.031E+004 1401. 52 1.33 5.088E+003 O. OOOE+OOO LJ.OO OE+OOO 1407.99 2 .39 1.824E+004 Fl.71 7E+003 7.703E+0 03 1509.21 2.13 1 .835E+004 2. 7 93E+003 7.521E+003 1661.27 1.05 1.932E+004 6. 5 63E+0 02 6 .108E+003 1729.59 2.8 8 1. 283E+004 2.544E+003 5.089E+003
+ Bi-214 1764.49 15 .30 5.171E+003 1.21E+003 4. 7 96E+003 2.334E+003 1 84 : .4 3 2.03 2.175E+00 4 7. 8 10E+00 3 8.91 4E+003
> 2118. 51 1.16 O.OOOE+OOO 0. 000E+OOO O.OO OE+OOO
+ Pb-214 241.9 9 7.25 5 .374E+003 1.12E+003 2. 581E+0 03 2 .490E+003
[100]
Nuclide MDA Report Page 7 of 7 Nuclide Energy Yiel d Line tJDA Nuclide tJDA Ac tivity Dec. Level Name (ke") ( '.' ) (pCi/M"2 ) (pCi/M"2 ) {pCi.111"2 ) (pCi/11" 2 ) 295.22* 18.42 ?..l07E+003 2.683E+003 9. 679E+ 0 02 351. 93*.*: 35.60 1.122E+003 2.081E+00 3 5 . 128 E+ 002 785.96 1. 06 2.674E+00 4 ~5 . 0 8 7 E+002 l . 0 96E+ 0 04 Pb214-}~R 74.82 5.80 1. 041E+004 4.79E+003 "' . 875E+00 3 5.002 E+003 77 .11 9.70 4 .790E+003 '-2.9 9 3E+00 3 2 .2 7 4E+0 03 87.35 2.24 2 . 007E+004 l.1 71E+00 3 9.52 7E+ 003 89.78 0.82 5.004E+004 1-4. 5 31E+00 3 2.365 E+ 0 0 4 r.a-226 1 3 6.21 3.64 1.003E+004 1. 00E+00 4 6.08 2E+003 4 .66 3E+003 Ac-228 129.07 2. 42 1.458E+004 2.14E+003 7 .585E+0 02 6.821E+003 209.25 3.89 7.474E+003 - 2 .020E+0 0 2 3.393E+0 03 270.24 3. 46 9.593E+003 2.151E+003 4 .361E+ 003 328.00 2.95 9.767E+003 -1.973E+003 4.32 1E+003 338.32 11.27 2.763E+003 ~7. 0 46E+ 002 1.232 E+003 409.46 1.92 1.480E+004 1.071E+003 6. 4 35E+0 0 3 463.00 4.40 6.459E+003 1. 071E+00 3 2.781E+ 0 03 794.95 4.25 7 .432E+003 l.12 7E+003 3 . 113E+003 911. 20 25.80 2. 141E+003 1.332E+ 003 9 .6 4 4E+ 00 2 964.77 4. 9 9 6.935E+003 l.491E+003 2.9 0 4E+00 3 968.97 15.80 3.097E+003 1 . 63 8E+ 0 03 1 ..37 0E +003 1588.20 3.22 1.172E+004 3.150E+0 03 4. 7 35E+00 3 Pa-231 27.36 10.30 9.291E+0 0 3 9 .29E+003 1-1.56 0E+0 03 4.1 8 5E+0 0 3 283.69 1. 70 1. 771E+ 004 4 .163E+003 7.9 5 0E+0 0 3 300.07 2.47 1. 35 7 E+004 3 . 2 9 0E+002 6 . 144E+ 003 302.65 2. 2 0 1. 364E+004 1-1.293 E+003 6 . 0 96E+00 3 330.06 1. 40 2.197E+004 -5.00 1E+ 003 9. 7 95E+0 0 3 Th-234 92.38 2 .13 2. 072E+0 15 2.07 E+01 5 '- 1 .4 7 1E+014 9. 8 12E+014 92.80 2.10 2 .173E+015 5 .9 6 6E+014 1.031E+Ol5 112.81 0.21 1. 808E+016 1. 417E+ 0 1 5 8.4 85E+01 5 U-235 143.76 10.96 2.830 E+003 5.85E+0 0 2 - 8 .9 3 3E+002 1 .3 08E+0 0 3 163.33 5.08 6.401E+0 () 3 2 .691E +003 2.962E+ 0 0 3 185. 71 57.20 5.851E+002 4.371E+00 1 2.703E+ 0 02 202. 11 1.08 2.298E+004 -6.138E+00 3 l . 0 2 7E+ 0 04 205. 3 1 5.01 6.063E+003 1. 21 5E+ 0 0 3 2 .7 67E+00 3 Am-241 59.54 35.90 l.421E+003 1.42E+0 03 ~1.520E+002 6.728E+002
+
- Nuclide identifi ed d u ring the nuclide identification
- Energ y line f ound in the spe ct rum
> = ?IDA value not calcula ted @= Half-life to o short to be able to pe r f o rm the d ecay c o r r ection
[101]
Page 2 of 7 GA MM A ,., P E C T R U M .A N A L Y S I S
§::::U!Uf~ * ~
Filename: C:\GENIE2K\CAMFILES\rwc007.CNF Report Generated On 7/9/2015 7:31:16 AM Sample Title RWC007 Spectrum Description Sample Identification Sample Type Sample Geometry Cribhous e 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance : 10.000 keV Sample Size
- 2.827E+001 MA2 Sample Taken On 1/2 8/2 0 13 12 : 00 :00 PM Acquisit ion St arted 6/ 25/2015 2:03: 11 PM Live Time 1000 . 0 seconds Real Time 1001.6 seconds Dead Time 0 .16 %
Energy Calibration Used Done On 1 /2 7/2 015 Efficiency Calibration Used Do ne On 7 /8/ 20 15 Efficiency ID CRIB HOU SE 3M [102]
Page 3 of 7 Report Date: 7/9/2015 7:31:16 AM Sample
Title:
RWC007 Peak: Analysis Performed on: 7/9/2015 7:31:15 AM Peak. Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak ROI ROI Peak Energy FWHM ~ontinuurn No. start e:1d ~entroid ( keV) (keV) ~ounts 1 297 308 301. 4 7 75.10 0.64 2.652E+002 2 1399 1416 1408.91 352.10 1. 47 3.112E+001 3 2037 2049 2044.51 511.03 1.23 2.745E+001 4 2429 2445 2437.92 609.39 0.65 1.689E+001 5 3641 3651 3645.87 911.29 0.49 1.410E+001 6 5837 5860 5847.45 1461.17 1. 76 1.394E+001 7 7058 7071 7065.07 1765.11 1.01 1.716E+000 .Da.:r. k O~ ange -~ F:i.ra"t.". pe.,k. :...n a mul t :1.plet .r:eg:i.ou. Grean =: F.:i.t.t .~d s .i .ng1.e,t . Errors quoted at 2.000 sigma llDE I E TIFIC TION EPOHT
...... I DENTIFIED NUCLIDES . . ... . . . .
Nuclide Id Energy Yield Acti*-ity Ac ti,.-ity Name Confidence (keV) (. ) (pCi/M"2 ) Uncertainty Z* Gl 'i . 000 *:.1. so . e.2~ l.0 . 56 J. 1?.J.*11:c,;-.-co~ i.on 1s;-~. oo:i S*:~-~3 0. 1 91 5V . * . 0 1. *~ Ni.0C -~ .?. Yr8?. t -;*00 ~ ~. :53 3 ~ Sll'.-i-006
.-e!-. *2 U . ~. S9S 3!:iL U'l ~ :! 3.0?. :;; . 96?.)? [ -*003 .: . SVi,3 '-lE:.;:-.~03 3L--?.:t I,; *: .000 $0!;.32 1i'L t. g :, . er i s:J.r:,.,.ocJ .3. 63,42 ..~ 00'2.
768 .36 4.89 806.18 1. 26 934.06 3.11 1120 . 29 14 .92 1155.21 1. 63 1238.12 5.83 1280 . % 1.4 3 1377. 67 3.99 1385 . 31 0.79 1401. 52 1. 33 1407.99 2.39 1509.21 2 .13 1 661. 2 7 1. 05 172 9 . 59 2 . 88
- ! / 51l . ~
,; s* l .?.3:l 3. 9/> l j'.U; -!- CC3 'a . 1., ',?~ '::1::+r c:::;
18 4: .4 3 2.03 [103]
Interference Corrected ~~tivities Report Page 4 or 7 Nuclide Id Energy !Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Oncertaint v Pb-214 0.517 241. 99 7.25 295.22 18.42
- 3:51. 9 .3* 35 .[ 0 2 -. i8302E+Oi) 1 . 0341.';,E+OO 785.96 1. 06 Ac-228 1.000 129.07 2.42 209.25 3.89 270.24 3.46 328.00 2.95 338.32 11. 27 409.46 1. 92 463.00 4.40 7 94. 95 4.25 911 . 20
- 2 .5 "B() :l.. 2.6~81.E+OD ? . 4621 4E+OO 964.77 4.99 968.97 15.80
.. 1588.20 ..
3.22 w: -.- ~~-~:"' ~;*.79:f ,.1. * :~ ~ *o::. :~n o ..: -.":. t;::',~1 r.,~_c~c ~~Ltir::. ~
@ Energy line not used for Weighted Mean Activity Nuclide ttas corrected for parent/daughter Energ:; Tolerance : 10. 000 ke "
Nuclide confidence index threshold 0.30 Errors quoted at 2. 000 sigma INTERFERENCE CORREC ED REPORT Nuclide Nuclide Wt mean Wt mean Name Id Confidence Activity (pCi/MA2 ) Activity Uncertainty K-40 1. 000 3.721708E+004 6.021164E+003 Sr-85 0 . 394 4.279017E+006 2.533477E+006 j{ (":,;-*'. 3-~ J . ,"l,~j
? 1\:i.*,.2J.:!. 0 . 9 98 5. 9 o27 1 7E+00 3 l . g2,; 3oaE+cJCl3 Bi-214 1. 000 2.143898E+003 5 . 252765E+002 ? Ph -21 4 0. 5:!.7 2 .1 8:~01.9E+ 0C3 p! . 03 4 1 33E*+*C02 Ac-228 1.000 1. 266807E+003 7.462138E+002 . !.:i d1e* .i& pa:r.t o:f c1:n: ,.n1del:'-"lrm.i:ced so.l u tion ? *- a *1...,c. ~n:,: l..*. **..., : q r, <l -Y i 'Le=f:;,.;..; ..:.1..,~ . , .. ( :t ~*;.,*1 @ *- nu c .1.::.:le c o !t:ta:i.ns e 11e.r.gy :!..in es n o t~ *ua t!:d i.n We i gh t ed Mea.n Ac tiv i t y Erro r s -:ru.ot.ed r.,. t 2 . rrno s igma f IED s Peak Locat e Perrormed on 7/9/20 15 7 : 31 ~15 AM
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Interference Corrected ~~tivities Report Page 5 or 7 Peak Locate From Channel: 50 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second 9.; Uncertainty 1 75.10 1.3779E-001 41. 29 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma NU RT Detector Name ~ 5456 Sample Geometry:: Cribhouse 3m SamGle Title : RWC007 Nuclide Li~rary Used : c~\GENIE2K\CAMFILES\Zion Lib- BNL . NLB Report Generated on ~ 7/9/2015 7 ~31 ~17 AM Nuclide Energ:,* Yi eld Line MDA Nuclide MDA Acti~'it:,* Dec. Level Name (keV) ( C ) (pCi/t1"2 0
) (pCi /M"2 ) (pCi/W'2 ) (pCi/W2 ) + K-40 1460.d2* 10.66 3.849E+003 3.85E+003 3.722E+004 1. 730E+003 Cr-51 320.08 9*. 91 6.719E+Ol2 6. 72E+012 -7. 381E+Oll 3.015E+012 Mn-54 834.85 99.98 1 .539E+003 1. 54E+003 2.691E+002 6.588E+002 Co-58 810.76 99. 45 1. 284E+006 1. 28E+006 3.324E+005 5.581E+005 Co-60 1173.23 99.85 2.655E+002 2.40E+002 -4.236E+001 1.073E+002 1332. 49 99.98 2.397E+002 -4.990E+001 9.286E+001 Nb-94 702.65 99.81 2.347E+002 2.07E+002 1.955E+001 1.029E+002 871.09 99.89 2.069E+002 7.244E+001 8.73 7E+001 Sn-113 255 .13 2 .11 1. 991E+006 5.89E+004 2.268E+005 9.126E+005 391.70 64.97 5.892E+004 -1. 077E+004 2. 614E+004 Cs-134 475.36 1. 48 3.226E+004 6. 11E+002 1. 4 61E+004 1.431E+004 563.25 8.34 5.943E+003 2.687E+002 2.622E+003 569 .33 15.37 2. 2 37E+003 -1.410E+002 9.275E+002 604.72* 97.62 6. 105E+002 1. 953E+003 2.742E+002 795.86 85.46 6.848E+002 2.050E+002 3.021E+002 801. 95 3.69 6.760E+003 1.381E+003 2.982E+003 1038.61 0.99 4.130E+004 .... 1.135E+004 1.669E+004 1167. ~7 1. 79 3.105E+004 3. 113E+003 l,321E+004 1365.19 3.02 1.738E+004 4.347E+003 7. 2 06E+003 Cs-137 661.66 85. 10 2 . 753E+002 2. 75E+002 9.687E+001 1. 202E+002 Eu-152 121. 78 28.67 9 . 733E+002 7 . 86E+002 3.586E+001 4.598E+002 244.70 7.61 3.713E+003 7 .081E+002 1. 728E+003 29 5 . 94 0.45 7 .704E+004 7 .1 25E+004 3. 613E+004 344.28 26.60 7. 862E+002 -4.735E+OOO 3.498E+002 367.79 0.86 2.508E+004 1.371E+003 1. 115E+004 41 1. 12 2 . 24 1. 082E+004 1. 558E+003 4.845E+003 443.96 2 . 83 7 .485E+003 1. 478E+003 3.280E+003 488 . 68 0.4 2 6 . 160E+004 1. 228E+004 2 .753E+004 563 .99 0.49 4 . 726E+ 00 4 - 9 .423E+003 2 .063E+004 586.26 0. 46 3.622E+004 -4, 221E+004 1.485E+00 4 678.62 0.47 5.073E+004 -6.305E+003 2 .195E+004
[105]
Nuc1ide MDA Report Page 6 ,. .., 7 Nuclide Energy Yield Line MDA Nuclide lIDA Acti'!ity Dec. Lff1,el Name (keV) ( ': ) (pCi/M"2 ) (pCid1"2 ) (pCi/U"2 ) (pCi/M"2 ) 688.67 O.C6 2.893E+004 5.582E+003 1.257E+004 719. 35 0.28 1.054E+005 3.176E+004 4.677E+004 778.90 12.96 1.847E+003 2.330E+002 7.907E+002 810.45 0.32 7.600E+004 r-6.140E+003 3.254Et 004 867.37 4.26 4.432E+003 -2.750E+002 1. 791E+003 919.33 0. 43 5.848E+004 1.488E+ 004 2.488E+004
%4.08 14.65 2. 411E+003 1. 363E+003 1.075E+003 1 085.87 10.24 2.432E+003 1.131E+003 1.018E+ 003 1089.74 1. 73 1.373E+004 4.434E+003 5.693E+003 1112. 07 13. 69 2.150E+003 6.94 2 E+002 9.259E+002 1212.95 1. 43 2.221E+004 8.280E+003 9.610E+003 Eu-152 1249.94 0.19 1.340E+005 7.86E+002 7.920E+002 5.559E+004 1299.14 1. 63 l.502E+004 2.430E+OlJ3 6. 1 58E+003 1408.01 21.07 1. 460E+003 6.2 40E+002 6. 213E+002 1457.64 0.50 5.164E+0()4 5.846E+003 2 .117E+004 1528.10 0.28 4.64 1E+004 r-1. 419E+004 1.467E+00 4 Eu-154 123.07 40.40 7.09 7E+002 7.10E+002 r-5.109E+001 3.344E+002 247.93 6.89 3.925E+003 r4,682E+002 1.809E+003 591.76 4.95 4.209E+003 l.148E+002 1.778E+003 692.42 1. 78 1.317E+004 1.188E+003 5.601E+003 723. 30 20 .0 6 l.191E+003 r-2.731E+ 002 5.066E+002 75 6.80 4.52 5.606E+003 9.244E+002 2.400E+003 873.18 12.08 1. 285E+003 r-l.283E+003 4.808E+002 996.29 10. 48 2.331E+003 7.712E+002 9.666E+002 1 004.76 18.01 1.289E+003 3.372E+ 0 0 1 5.283E+002 1274.43 34.80 7.461E+002 1. 242E+001 3.058E+002 1596.48 1. 80 8.020E+003 5.449E+002 2 .5 35E+ 003 Eu-155 45.30 1. 31 2.108E+004 1.35E+003 ~4.856E+003 9.661E+003 60.01 1. 22 2. 919E+004 ~2.636E+003 1.366E+004 86.55 30.70 1. 34 7E+003 r-8.583E+002 6.420E+002 105.31 21.10 1. 700E+003 4.801E+002 8.045E+002 Tl-208 583.19 85.00 4.284E+00 2 4.28E+002 4.062 E+002 1 .9 86E+0 02 + Bi-211 351. 07* 13.02 2.094E+003 2.09E+003 5.963E+003 9.679E+002 Pb-211 404.85 3.78 4. 611E+003 4.61E+003 d.1 02E+003 2.013E+003 427.09 1. 76 1. 017E+004 i-2.027E+003 4.439E+003 832.01 3.52 5 . 230E+0 03 r-l. 236E+002 2. 169E+003 Bi-212 39.86 1.06 2.083E+004 2.96E+003 1.369E+004 9.650E+003 727. 33 6.67 2.959E+003 -1. 609E+003 1. 259E+003 785.37 1.10 1 . 784E+004 1.02 4E+002 7.536E+00 3 1620 .50 1. 47 1. 192E+004 9.227E+002 4.462E+003 Pb-212 115.18 0.60 3.910E+004 7.27E+002 r-8.77 6E+0 03 1. 841E+004 238 .63 4 3.60 7. 272E+OOZ 7 .271E+002 3.440E+002 300.(19 3.30 7.327E+003 4.380E+003 3.374E+003 Pb212-XR 74.82 10.28 4.123E+003 l.79E+003 4.587E+003 l.991E+003 77 .11 17 .10 1. 786E+003 r3.4 8 1E+O(J2 8. 513E+0 02 87.35 3.97 7 . 332E+003 4.5 24E+002 3.495E+003 89.78 1. 4 6 1. 989E+004 6 .322E+003 9 .4 81E+003 + Bi-214 609.32* 45.49 5.853E+002 5.65 E+002 1. 872E+002 2.629E+002 7 68 . 36 4.89 5 .490E+003 6.283E+002 2.436E+003 806.18 1.26 1.577E+004 l .40 3 E+003 6.660E+003 934.06 3 .11 9.106E+003 5 . 640E+003 4.01 7E+003 1120.29 14 . 92 2 . 611E+003 1. 265E+003 1 .1 8 4E+00 3 1155.21 1. 63 1.323E+004 1.016E+003 5.487E+003 1238 . 12 5 . 83 6 . 034 E+003 3 .625E+003 2 .6 91E+003
[106]
Nuclide MDA Report Page 7 0~ 7 Nuclide Energy Yield Line t-1DA Nuclide MDA Acti,,it:,* Dec. Level Name (keV) ( *.*, ) (pCi/t1"':L ) (pCi/H"2 ) (pCi/t12 ) (pCi/M"2 ) 1280.98 1. 43 l.~82E+004 2.492E+002 6.559E+003 1377.67 3.99 7.002E+003 3.425E +003 2.998E+003 1385.31 0.79 2.977E+004 6.1S7E+003 1.235E+004 1401. 52 1. 33 1. 588E+004 -1. 267E+003 6.417E+003 1407.99 2.39 1.093E+004 3. 2 62E+003 4.614E+003 1509.21 2.13 l.102E+004 4.401E+003 4.515E+ 00 3 1661 .27 1.05 2.506E+004 l.263E+004 1.039E+0 04 1729.59 2.88 9.334E+003 1.691E+003 3. 871E+003
+ Bi-214 1764.49* 15.30 l.107E+003 5.85E+002 3.952E+0 03 4.019E+002 1847.43 2.03 1. 220E+004 5.19 1E+003 4 .930E+003
> 2118. 51 1.16 O.OOOE+OOO O. OOOE+OOO O.OOOE+OOO
+ Pb-214 241.99 7.25 3.682E+003 7.67E+002 1.870E+003 1. 722E+003 295.22 18.42 l.646E+003 1.438E+003 7.717E+002 351. 93* 35.60 7.667E+002 2.183E+003 3.543E+002 785. 96 1.06 2.145E+004 7.712E+003 9.283E+003 Pb214-XR 74.82 5.80 7.316E+003 3.15E+003 8 .139E+003 3.533E+003 77 .11 9.70 3.152E+003 r-6.143E+002 1.5 02E+003 87.35 2.24 1.301E+004 8.027E+002 6.202E+003 89.78 0.82 3.545E+004 1.127E+00 4 1.690E+004 Ra-22 6 1 86.21 3.64 6.806E+003 6.81E+003 3.130E+003 3.194E+003 + Ac-228 129.07 2.42 9.792E+003 1.04E+003 4 .017E+003 4.612E+003 209.25 3.89 5.583E+003 4.226E+002 2.585E+003 270.24 3.46 6.906E+003 2.558E+0 03 3.191E+003 328.00 2.95 6.599E+003 ,-7. 490E+002 2.962E+003 338.32 11. 27 2.180E+003 8.513E+00~ 1.000E+003 409.46 1. 92 l.007E+004 1-3.517E+003 4. 456E+003 463.00 4.40 4. 770E+003 l.411E+003 2 . 11 6E+ 003 794.95 4.25 6. 141E+003 2.893E+003 2.709E+003 911. 20* 25. 80 1.038E+003 1. 267E+003 4.552E+002 964. 77 4.99 6.262E+003 2.544E+003 2.792E+003 968.97 15.80 2.129E+003 1. 14 9E+003 9.5 75E+002 1 588 .20 3.22 7.501E+003 9.455E+002 3.075E+003 Pa-231 27.36 10.30 2.216E+003 2.22E+003 1-4,875E+002 l.029E+003 283.69 1.70 1.253E+004 4.041E+002 .'i.718E+003 300.07 2. 4 7 9.789E+003 5.852E+0 03 4.508E+003 302.65 2.20 9.349E+003 9.5 12E+002 4. 239E+003 330.06 1. 40 1. 370E+004 r-2.04 2E+003 6 .138E+003 Th-2 34 92. 38 2.13 1.197E+015 1.20E+015 2.199E+01 4 5.692E+014 92.80 2.10 1.210E+015 1.112E+014 5.751E+014 112. 81 0.21 1.160E+016 2.271E+015 5.497E+015 U-235 143.76 10. 96 l.902E+003 4.30E+002 -3.11 6E+ 002 8 .8 7 0E+002 163.33 5.08 4.283E+003 9.692E+002 2.048E +003 185. 71 57.20 4.295E+002 1. 48CE+002 2 .015E+002 202. 11 1.08 l. 85 3E +004 -3 .8 71E+003 8 .532E+003 205.31 5.01 4.480E+003 1. 270E+003 2 .081E+0 03 Am-241 59 .54 35.90 6.868E+002 6.87E+002 - 2 . 524E+002 3.208E+002 + = Nuc l ide identified during the nuclide identification * = Energ~* line found in the spectrum > = MDA value not c alculated @=Half-life too short to be able to perform the decay correct ion
[107]
Page 2 of 7 GA MM A J P E C T R U M A N A L Y S I S e;~itmi.tll:T.t:fil I ~,*; m-:t!E..f~(ilJ"
;L :i~ '!°l Filename: C:\GENIE2K\CAMFILES\RWC008.CNF Report Generated On 7/9/2015 7:31:55 AM Sample Title RWC008 Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance : 10.000 keV Sample Size
- 2.827E+001 M"2 Sample Taken On 1/28/2013 1 2 :00:00 PM Acquisition Started 6/29/2015 12:51:56 PM Live Time 600 . 0 seconds Real Time 600 .9 seconds Dead Time 0 .15 %
Energy Calibration Used Done On 1/27 /20 15 Efficiency Calibration Used Done On 7/8/2015 Efficiency ID CRIB HOUSE 3M [108]
Page 3 of 7 Report Date: 7/9/2015 7:31:55 AM Sample
Title:
RWC008 Peak:Analysis Performed on: 7/9/2015 7:31:54 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak ROI ROI Peak !Energy FWHM ;:::ontinuum No. start ~nd centroid (keV) (keV) ;:::ounts 1 299 305 301.99 75.23 0.73 1. 525E+002 2 2326 2338 2332.59 583.06 0.97 1.625E+001 3 2431 2444 2437.55 609.29 0.87 1. 206E+001 4 5836 5857 5845.99 1460.81 0.71 7.951E+00O Dark (;x-ar..ge :;:, F i.r- 1:1, t peak. .i n a mu.l tipl.e t. reg.i.c.n Graen = Fi.tted s :i.n.g.1. t, Errors quoted at 2.000 sigma UCllDE ID NII IC Tl N EPORT Sample Title. RWC00B Nuclide Library Usicd: C*\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Report Generated: 7/9/2015 7*31 :55 A.M
. . . . .. I DENTIFIED NUCLIDES . . .. . . . . .
Nuclide Id Energy Yield Activity Act i v ity Name Confidence (keV) (; ) (pCi/M"'2 ) Uncertai nty Jl;*lj j :~. coo :v.. so. i 2 -- 10 .. ZO 3. ;)5l ?.5*:*r001 "/ . 5 -~ 539.~-:~003 Cs-134 0.391 475.36 1.48 563.25 8.34 569.33 15.37 SC 4 . '/'). "' S,7 . 52 ?. . *1.?.22?.";:""oo:; a. ( ii'i.~9_-,;-0,00.2 795.86 85.46 801. 95 8.69 1038 . 61 0.99 1167.97 1. 79 1365.19 3. 0 2
~ ~~. - ?O!: 1 .001 j~3. ,l 9
- 35 .JO :S . IC i.3 7' -' + 0C~ 3 . = ~J2 C.6.(~:-:-:c?.
- 3. '.- ?. 'U, .".. 0 0 0 i>0~. 3 2 * .~ b . ~~S ?.sco,or:~002 ~. '.i. O5!::i.?.;'"- 00?
76 8 . 3 6 4.89 806.18 1. 2 6 93 4.0 6 3 .11 11 2 0. 2 9 1 4 . 92 1155. 21 1. 63 1 2 38.1 2 5.83 1280.98 1. 43 1377 . 67 3 . 9 St 13 85.31 0.'79 140 1. 52 1. 33 140'7. 99 2 .3 9 [109]
Interference Corrected '\ctivities Report Page 4 or 7 Nuclide Id !Energy Yield !Activity ~ctivity Name t:onfidence (keV) ( %) (oCi/M"2 ) Oncertaintv 1661.27 1.05 1729.59 2.88 1764.49 15.30 1847.43 2.03 2118.51 1.16
- a:.: ~7*-~)C,:_-':. Jjf .1..J.:.".'.~! :*~.O.A.'J d . ~; r~. ~tlts i:;;~p-~ G t:) ,.~~,.:\.,
@ Energy line not used fo r Weighted !~an Activity Nuclide 11as corrected for parent/daughter Energy Tolerance: 10.000 keV Nuclide confidence index thres h old
- 0.30 Errors quoted at 2.000 s i gma INTERFEREN E CORREC E EPO T Nuclide Nuclide Wt mean Wt mean Name Id Confidence Activity (pCi/M"2 ) Activity Uncertainty K-40 1. 000 3.951253E+004 7.505393E+00 3
- Cs-:1.3 4 0.391 2. '122 32 3£ +0 03 9. 4 0 4287E+OU2 Tl-208 1. 000 5.707371E+002 3.342 061E+002
? :Si-21, 4 1 .00 0 2. 60Cl.9'iF.+003 8. 105S21tE+002 ? = m,1 ol i de i s pe.:r.t of ,m i;r.cle te:e.:minad so1 *"1 t:i.,:,n
- a.cl.i ,:. e -~ ....ject~d. b tl1 .: __. t,-e;.rtu::: ~;;i,c-..:. * :t43_-- ,. ;s;..:....,
@ - nuc l i cla cor. t:.:d:ns an1i.xgy lines n ot used .in Wai.gh~:.ed. Mean Ac-tiv:H:y Erro r:s quotecl at 2.000 s i gma I
Peak Locate Performed on ~ 7/9/ 2 015 7 ! 3 1 : 54 AM Peak Locate From Channel; 50 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts per Second % Uncertaintv 1 75.23 8.7518E-002 70.58 M = First peak in a multiplet region m = Other peak in a multiplet regi on F = Fitted singlet Errors quoted at 2.000 sigma 11 MDA REPORT Detector Name : 5~56 [110]
Nuc1ide MDA Report ~age 5 of 7 'Sample Geometry: Cribhouse 3m Sample
Title:
RWCOOB Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB Report Generated on: 7/9/2015 7:31:56 AM Nuclide Energy Yield Line t1DA Nuclide NDA Acti,.it~* Dec. Level Name ( ke**) ( .. ) (pCi/M"2 } (p(;i/n"2 ) (pCi/M"2 ) (pCi/H"2 )
+ K-40 1460.82* 10.66 4.913E+003 4.91E+003 3.951E+004 2.132E+003 Cr-51 320.08 9.91 1. 075E+013 1.08E+013 1. 015E+012 4.742E+012 Mn-54 834.85 99.98 l.939E+003 1. 94E+003 1-l. 718E+001 7.833E+002 Co-58 810.76 99.45 1.702E+006 1.70E+006 7.377E+004 7.060E+005 Co-60 11"73.23 99.85 3.775E+002 3.59E+002 >-1.178E+001 1. 462E+002 1332.49 99.98 3.586E+002 4.719E+001 1.342E+002 Nb-94 702.65 99.81 3.364E+002 2.79E+002 6.479E+001 1. 440E+002 871.09 99.89 2.791E+002 t-1. 270E+002 1.128E+002 Sn-113 255.13 2.11 3.242E+006 8.15E+004 7.758E+005 1.480E+006 391. 70 64.97 8.154E+004 - 1 .594E+004 3.511E+004 + Cs-134 475.36 1. 48 3. 372E+004 8.31E+002 >-1.123E+004 1.382E+004 563.25 8.34 8.963E+003 2.595E+003 3. 8 96E+003 569.33 15.37 3.325E+003 t-4.126E+002 1. 344E+003 604.72* 97.62 8.306E+002 2. 722E+003 3.634E+002 795.86 85. 46 9.707E+002 6.046E+ 00 2 4.180E+002 801. 95 8.69 7.387E+003 7 .379E+002 3.0 28E+003 1038.61 0.99 6.908E+004 2.082E+004 2.791E+004 1167. 97 1. 79 4.300E+004 1.043E+004 1.763E+004 1365. 19 3.02 2.201E+004 4 .923E+003 8.524E+003 Cs-137 661. 66 85.10 2.823E+002 2.82E+002 ... 9.258E+001 1.120E+002 Eu-152 121.78 28.67 1.560E+003 1.17E+003 3.734E+002 7.351E+002 244.70 7.61 4.667E+003 1-3,219E+002 2. 119E+003 295.94 0.45 1.001E+005 1.997E+004 4.60 6E+004 344.28 26. 60 1.170E+003 ... 4.44 9E+002 5.127E+002 367.79 0.86 2.970E+004 -9.547E+003 1.254E+004 411.12 2.24 1.440E+004 1-3.05 6E+003 6.259E+003 443.96 2.83 1. 216E+004 5.079E+002 5.306E+003 488.68 0.42 7.306E+004 -1.190E+003 3.108E+004 563.99 0.49 7.882E+004 2.7 96E+004 3.441E+0 04 586.26 0.46 6.040E+004 -- 1 .709E+ 004 2.476E+004 678. 62 0.47 6.316E+004 6.008E+002 2.589E+004 688. 67 0.86 4. 381E+004 1.522E+004 1. 876E+0 04 719. 35 0.28 8.788E+004 - 2 .652E+004 3.404E+0 0 4 778.90 12.96 ~. 968E+003 -1. 562E+002 1. 2 62E+003 810.45 0.32 1.22 1E+005 6.029E+004 5 .195E+004 86".37 4. 26 7.391E+003 -l.1:9E+003 2.98 7E+003 919.33 0 . 43 6.458E+004 1-l. 445E+004 2.502E+004 964. 08 14.65 2.800E+003 >-4.018E+001 l.182E+003 1085.87 10.24 3.432E+003 7,908E+002 1.387E+003 1089 .74 1. 73 1. 733E+004 1.803E+003 6.713E+003 1112.07 13. 69 l.98 2E+003 1-l.473E+003 7.417E+002 1212.95 1. 43 3.068E+004 4.09 1E+002 1. 2 85E+004 Eu-152 1249.94 0.19 1. 987E+005 1.17E+003 3.874E+004 8 . 028E+004 1299 . 1 4 1. 63 2.505E+004 t- 4,588E+003 1.027E+004 1408.01 21.07 1. 760E+003 .... 8.057E+001 6.985E+002 1457.64 0 . 50 9.556E+004 t-2 .115E+004 4.002E+004
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Nuclide MDA Report Page 6 ~f 7 Nuclide Energ~* Yield Li ne !1DA Nuclide l-lDA Acti"ity Dec. Leel Name ( ke';) ( ..: ) (pCi/H"2 ) (pCi/W2 ) (pCi/M"2 ) (pCi/W2 ) 1528.10 0.28 l.132E+0 0 5 3.155E+004 4. 237E+004 Eu-154 123.07 40.40 l.100E+003 1.10E+ 0 0 3 -9.690E+001 5.159E+ oo: 247.93 6 . 89 5.492E+003 8.8.69E+OO O 2.490E+ 003 591.76 4.95 6.053E+003 -7.198E+on 2 2.481E+003 692.42 1. 78 2 .196E+004 9.990E+00 3 9.343E+003 723.30 20.06 1.825E+003 >-5.781E+001 7.644E+002 756.80 4.52 6.513E+003 2.235E+002 2.5d4E+003 873.18 12.08 2.989E+003 1-2.488E+0 0 2 1. 2 2 5E+003 996.29 10. 48 3.456E+ 003 l.123E+003 1. 3 96E+003 1004.76 18.01 1 .330E+ 0 03 -3.937E+002 4.710E+00 2 1274.43 34.80 1. 245E+003 1. 8 35E+002 5.102E+0 02 1596.48 1. 80 2.184E+004 5.795E+003 8.458 E+ 0 03 Eu-155 45.30 1.31 3.994E+ 004 1.93E+003 3.919E+ 00 3 1. 8 51E+ 0 04 60.01 1.22 4.998E+004 1. 915E+003 2.343E+0 0 4 86.55 30.70 1, 928E+003 -9.533E+002 9.115E+002 105.31 21. 10 2.680E+003 4.899E+002 1. 2 64 E+0 03
+ Tl-208 583.19* 85.00 4.654E+002 4.65E+002 5.707E+002 2.06 3E+ OO ~
Bi-211 351.07 13.02 3.774E+003 3.77E+00 3 1. 658E+003 1. 755E+0 03 Pb-211 404.85 3. "7 B 7.892E+003 7 ,75E+003 -1. 713E+003 3.45 8 E+0 03 427.09 1. 76 1.385E+004 -5.565E+002 5.848 E+ 003 832.01 3.5 2 7 .749E+ 003 2.747E+ 002 3.131E+ 003 Bi-212 39.86 1.06 5.669E+004 5.3 0E+ 0 03 3.845E+0 0 4 2.707E+0 04 727.33 6.67 5.297E+ 0 03 2 . 0 39E+003 2. 281E+ 0 03 785.37 1.10 2 .408E+004 -6.402E+003 9.72 8 E+ 0 03 1620.50 1. 47 1.714E+004 1-2.307E+003 6 . 071E+ 0 03 Pb-212 115 .18 0.60 6.045E+004 1.11E+003 l.222 E+00 4 2.B32 E+ 0 04 238.63 43.60 l.114E+003 8.0BBE+0 02 5. 2 4 3E+002 300.09 3.30 9.420E+003 i-1. 91 9 E+ 0 0 3 4 . 228E+0 03 Pb212-~~R 74.82 10. 2 8 6.204E+003 2 .81E+003 i-1.0 23E+00 3 2.98 5 E+ 003 77 .11 17.10 2. 811E+003 >- l . 9 7 7 E+0 0 2 1.336E+0 03 87.35 3.97 1.114E+00 4 4.510E+0 0 3 5.2B 8E+OIJ3
- 89. 7 8 1. 46 2.9 2 3 E+004 1. 3 13E+ 0 0 4 1. 3 84E+0 04
+ Bi-214 609. 32* 4 5 . 49 7 .934E+00 2 7.93E+002 2. 6 0 0E+0 0 3 3. 4 71E+ 002 768.36 4.89 7.419E+003 1. 71 4 E+ 0 03 3. 1 94E+0 03 806 . 18 1. 26 2.514E+004 5. 9 09E+ 003 1. 05 3E+00 4 934.06 3. 11 l. 2 4 3E+004 3.90 6 E+ 0 03 5. 32 1E+0 03 1120.29 14.?2 4.2 2 7E+00 3 2.889 E+ 0 0 3 1. 91 0E+ 0 03 1155.21 1. 6 3 2 . 796E+004 1. 417E+ 0 0 4 1. 2 1 0E+004 1238.12 5. B3 7.8 3 0E+003 2. 6 13E+ 0 0 3 3.37 1E+0 03 12B0.98 1. 4 3 2 .495E+0 0 4 -8.90 1E+ 0 0 2 1.02 3E+004 1377.67 3. 99 8 .744E+003 2.816E+ 003 3.53 3E+003 138 5. 31 0.79 4.6 9 6E+004 1.173E+ 0 0 4 1. 925E+ 004 14 01. 52 1. 3 3 1. 7 4 3E+ 0 0 4 >-5 . 63 1 E+ 00 3 6 . 175E+ 0 0 3 1407.99 2.39 1. 371E+004 t-3. 6 59E+ 0 02 5.43 8E+0 0 3 1 5 09. 21 2.13 1. 8 3 6E+004 4.19 2 E+ 0 0 3 7. 525E+0 03 1661. 27 1. 0 5 1. 93 7E+00 4 -1.18 4 E+ 0 0 4 6. 123E+ 003 17 2 9.59 2. 8 8 1. 2 85E+004 2.941E+ 0 0 3 5. 1 0 0E+0 03 + Bi-214 1 764.4 9 15.30 5. 0 17E+0 03 7. 9 3E+ 002 3 . 9 05E+003 2 . 2 5 6E+ 003 18 47.43 2. 0 3 2 .165E+00 4 8. 0 85 E+0 0 3 8. 875E+ 0 03 I> 2118. 51 1.1 6 O. OOOE+ OOO O. OOO E+ OOO O. OOOE+OOO Pb -214 241.99 "7 . 2 5 5 .403E+0 03 1. 48E+ 003 4.0 6 &E+002 2 .503E+ 00 3 295 . 2 2 1 8 .42 2 . 3 4 0E+ 003 2 .01 9 E+ 003 l. 08 4E+0 03 3 5 1. 9 3 3 5 . 60 1.4 77E+00 3 1. 22 8E+ 00 3 6 .90 0E+002 785 . 9 6 1. 0 6 2 . 3 3 0 E+0 04 - 7 . 643E+ 00 3 9 .2 46E+003
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Nuc1ide MDA Report Page 7 ~~ 7 Nuclide Energ~* Yield Line MDA Nuclide HDA Acti*dt~* Dec. LeTTel Name (keV) ('7,) (pCi/W'2 ) (pCi/M"2 ) (pCi /t1"2 ) (pCi/W2 ) Pb214-XR 74.82 5.80 1. 101E+004 4.96E+003 ,-1. 814E+003 5.296E+003 77 .11 9.70 4. 960E+003 ~3.49 0E+002 2.35 8E+003 87.35 2.24 1.977E+004 8.002E+003 9.382E+003 89.78 0.82 5.210E+004 2.341E+ 004 2.46 8E+ 004 Ra-226 lBG.21 3.64 9.660E+003 ~.66E+003 4.350E+003 4.4 8 2E+003 Ac-228 129.07 2.42 1.314E+004 2.25E+003 ~S.719E+003 6.097E+003 209.25 3.89 8.360E+003 3.032E+003 3.83 6E+00 3 270.24 3. 4 6 l.002E+004 t-7,251E+002 4.574E+003 328.00 2.95 l .119E+004 6.118E+003 5.030E+ 003 338.32 11. 27 3.254E+003 1. -:'11E+003 l.4 77E+003 409.46 1. 92 l.715E+004 3.747E+003 7 .609E+003 463.00 4.40 7.427E+003 3. U9E+003 3.266E+003 794.95 4.25 8.381E+003 1. 484E+003 3.588E+003 911. 20 25. 80 2.245E+003 l.78 5E+003 l.016E+003 964.77 4.99 8.126E+003 3. 128E+003 3.499E+003 968. 97 15. 80 3.238E+003 2.541E+003 1. 440E+0 03 1588.20 3.22 l.091E+004 1. 457E+003 4.331E+0 03 Pa-231 27.36 10.30 2.688E+003 2.69E+003 9.056E+00 2 l . 213E+0 03 283.69 1. 70 1.810E+004 ~1. 515E+003 8 .141E+003 300.07 2.47 1. 259E+004 -2.564E+003 5 . 648E+003 302.65 2.20 1.369E+004 .-6. 710E+002 6. 118E+003 330.06 1. 40 2.324E+004 4. 2 96E+003 l .043E+004 Th-234 92. 38 2.13 ::!.078E+015 2.0BE+015 3.7 99E+Ol4 9. 8 40E+014 92.80 2.10 .Z.163E+Ol5 8.795E+ 014 l.0 2 6E+015 112. 81 0.21 l.861E+016 6 .9 03E+015 8. 7 44E+015 U-235 143.76 10. 96 3.006E+003 6.33E+ 002 8.1 5 4E+001 l.3 97E+0 03 163.33 5.08 5.804E+003 5 .446E+002 2 .663E+003 185. 71 57.20 6.333E+002 4 . 944E+002 2. 9 45E+002 202 . 11 1. 08 3.057E+004 .- 7 .561E+002 1.4 07E+004 205.31 5.01 6.432E +003 1. 84 3E+00 3 2.951E+0 03 Arn- 241 59.54 3 5 .90 l.243E+003 1. 2 4E+0 03 5 .375E+00 2 5. 835E+0 02
+ = Nuclide identified during the nuclide identification * - Energy line f ound in the spectrum > = MDA Tralue not calculated @ Half-li f e too short to be able to perform t h e deca ~ c orrection
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Page 2 o f 6 GA MM A ..., P E C T R U M .. i N A L Y S I S
., IO '5tl ttJffll \ .\ ~. * *- ; I .J~ l .,.,._~ . .!.:-* .c_;p.: { ;~::.;~_.
Filename: C:\GENIE2K\CAMFILES\RWC009.CNF Report Generated On 7/9/2015 7:32:35 AM Sample Title RFC009 Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels): 50 - 8192 Peak Area Range (in channels} : 50 - 8192 Identification Energy Tolerance : 10.000 keV Sample Size
- 2.827E+001 M"'2 Sample Taken On 1/28/2013 12:00:00 PM Acquisition Started 6/29/2 015 10:07: 2 7 AM Live Time 600.0 seconds Rea l Time 600.4 seconds Dead Time 0.06 !ii Energy Calibration Used Done On 1/27 / 2015 Efficiency Calibration Used Done On 7/8/2015 Efficiency ID CRIB HOUSE 3M
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Page 3 of 6 Report Date: 7/9/2015 7:32:35 AM Sample
Title:
RFC009 Peak:Analysis Performed on: 7/9/2015 7:32:35 AM Peak. Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak IROI IROI Peak Energy FWHM Continuum No. start ~nd K::entroid (keV} (keV) Counts 1 5834 5855 5845.78 1460.76 1. 83 2.724E+O0O Da.r:-k. Oi:" nge. -= .F .L r:s t- peak i .:o a muli;:ipl.e t r:eg.:i.on Green =- Fitted singJ.ert Errors quoted at 2.000 sigma NUCLIDE IDE T FIC Tl N RIPO T Sample T_itle: R FC.009 . .. _. . ... _. Nuclide Library Used: C;\GENIE2,K.\CAf.,1FlLES\Zmn L1b-BNL..NLE Report Generated: 7/9':/2(d5 7::~2:36 AM
...... IDENTIFIED NUCLIDES . . . .. . . . .
Nuclide Id Energy Yield Activit~* Acti*,ity Name Confidence (keV) () ) (pCi/H"2 ) Uncertaint:* X - 4. C :'.. i.)00 ;~,.Go.e-:2 .. :1.0.SG 3. r,,532S;.; ,: CO ~; 6. 6G39:.:.*~ *!*0C3
@ = Energ~, line not used for Weighted t1ean Activity = Nuclide ,ras corrected for parent /daughter Ene r gy To lerance : 10.000 keV Nuclide confidence index threshold 0. 30 Errors quoted at 2. 000 sigma I TER E E CE C RRECTED R PORT Nuclide Nuclide Wt mean Wt mean Name Id Confidence Acti v ity (pCi/M"2 } Activity Uncertainty K-40 1. 000 3.453864E+004 6.663913E+003 ? *-* n:11cl :i.cle ::.1:1 pc, .1-:*t o :E a.n u.nc.ia ter nli.!l *.!c.i s o l.\11:.i.o :n A -= !)u - l. J. :::ta *-'-'1:,i e.=i:.aa. _.* *t.. ~ :l:~,t:'=II:ic:r(:.:;~-: . .:;, .._1,:1l_;t~1:;. @ *-* !1UC.l.i d.~ co:\ t;ains s:ne i:t~Y 1. i ne s 11o t u s ed :h ~ WGigh -t~ d Mean .Ac tiv*:i.t.y Erro r s quo t e ci ti. 't: 2. 0 00 ~;.i 9111a
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Interference Corrected -~tivities Report Page 4 oF ~ Peak Locate Performed on : 7/9/2015 7 : 32 : 35 AM Peak Locate From Channel : 50 Peak Locate To Channel ~ 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts er Second 9s Uncertaint
- All peaks were identified.
NU IDE MDA REPORT Detector Name ; 5456 Sample Geometry : Cribhouse 3m Sample Title ; RFC009 Nuclide Library Used : C : \GENIE2K\CAMFILES\ Zion Lib*3NL . NLB Report Generated on : 7/9/2015 7:32 '. 36 AM Nuclide Energy Yield Line MDA Nuclide MDA Acti vit:' Dec. LeT e l 7 Name (keV) ( ': ) (pCi/M"2 ) (pCi/I1"2 ) (pCi/M"2 ) (pCi/M"2 )
+ K-40 1460.82* 10.66 3.164E+003 3.16E+003 3.454E+004 1. 258E+003 Cr-51 320.08 9.91 1. 021E+013 1.02E+013 i-l. 097E+Oll 4 .473E+012 Mn-54 834.85 99.98 2.180E+003 2.18E+003 7.301E+002 9.042E+002 Co-58 810.76 99.45 9.952E+005 9.95E+005 t-3,751E+005 3.526E+005 Co-60 1173.23 99.85 5.474E+002 5.00E+002 l.846E+002 2.312E+002 1332. 49 99.98 5.002E+002 1.975E+002 2.050E+002 Nb-94 702.65 99.81 3.364E+00 2 2.97E+002 1. 381E+002 l.44 0E+002 871. 09 99.89 2. 972E+002 8.412E+001 1. 218E+002 Sn-112 255 .13 2 .11 2.402E+006 9.61E+004 ~6.187E+005 l.06 0E+006 391.70 64.97 9.614E+004 ,- 2 . 587 E+00 3 4.241E+004 Cs-134 475.36 1. 48 4.375E+004 5.98E+002 1. 740E+004 1.884E+004 563.25 8.34 6.860 E+003 1""5, 675E+002 2 . 845E+00 3 569.33 15.37 2. B32E+003 r-1. 4 74E+003 1.097E+003 604 . 72 97.62 6.066E+002 t-4. 062E+0 01 2.516E+002 795 .86 85.46 5.985E+002 1""3.425E+0 02 2.318E+002 801. 95 8 .69 8. 568E+003 9.469E+0 02 3.619E+003 1 038.61 0.99 7. 771E+004 2.5 71E+0 0 4 3.223E+004 1167.97 1. 79 4.038E+004 l.432E+00 3 l. 632E+004 1365.19 3 .02 1.7 01E+00 4 4.579E+002 6.027E+003 Cs -137 661. 66 85.10 3.036E+002 3.04E+002 -1. 050E+002 1 . 227E+002 Eu-152 121. 78 28 .67 1.233E+003 1.14E+003 - 2 . 063E+0 02 5.715E+002 244. 7 0 7 .61 3.890E+003 - 5 . 334E+002 1. 730E+ 003 295.94 0. 45 9.907E+004 3.991E+004 4.554E+004 344.28 26 .60 l.139E+003 ,-2.305E+0 02 4.974E+002 367.79 0.86 3.533E+004 1.70 5E+002 1. 536E+004 411. 12 2.24 1.353E+004 ,-1. 22 9E+003 5.827E+003 443 .96 2 .83 9.503E+003 e-3. 311E+00 3 3 . 980E+003 488.68 0.42 5.681E+004 r-7.0 49E+0 03 2.295E+004 563.99 0. 4 9 6.706E+004 2 .84 0E+0 04 2 .85 3E+004 586 .2 6 0 . 46 6.382E+004 c- 4 .09 8E+004 2 . 647E+004 678.62 0. 4 7 7. 009E+004 8.178E+OOJ 2 . 935E+00 4 688 .67 0.86 3.282E+004 ,-7.17 6E+003 1.326E+004 719. 35 0.28 9.592E+004 1. 646E+004 3.806E+004
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Nucl.ide MDA Report Page 5 " 6
- Nuclide Energ:.: Yield Line tiDA Nuclide MDA Activity Dec. Le~,el Name (keV) (~ ) (pCi/MA2 ) (pCi/M"2 ) (pCi/W2 ) (pCi/W2 )
778. 90 12.96 2.457E+003 4.266E+002 l.007E+003 810.45 0.32 7.248E+004 1. 066E+004 2. 713E+004 867.37 4.26 ,.391E+003 1. 0~2E+003 2.987E+003 919.33 0. 43 8.073E+004 2.266E+004 3.309E+004 964.08 14.65 2.800E+003 7.232E+002 l.182E+003 1085.87 10.24 3.19()E+003 -3.650E+001 1.266E+003 1089.74 1. 73 2.L:89E+004 4.779E+003 9.493E+003 1112. 07 13. 69 2. 211E+003 2.301E+002 8.565E+002 1212.95 1. 43 2.414E+004 6.443E+002 9.577E+003 Eu-152 1249.94 0.19 2.115E+005 1. 14E+003 -2.01 2E+003 6.671E+004 1299.14 1. 63 1.549E+004 ... 2.085E+003 5.489E+003 1408.01 21.07 1. 894E+003 8.952E+001 7.652E+002 l-!57.64 0.50 1.153E+005 1-l.29 0E+004 4.991E+004 1528.10 0.28 9.765E+004 5.258E+003 3.460E+004 Eu-154 123.07 40. 40 1. 024E+003 8. 92E+002 ... 1.045E+002 4.776E+002 247.93 6.89 4.825E+003 1. 937E+003 2.156E+003 591. 76 4.95 5.684E+003 6.718E+001 2.297E+003 692.42 1. 78 1.708E+004 -1. 816E+003 6.900E+003 723.30 20.06 1.908E+003 6.462E+002 8.058E+002 756.80 4.52 5.347E+003 -2.153E+003 2.002E+003 873.18 12.08 2.391E+003 2.364E+002 9.261E+002 996.29 10.48 2.638E+003 --1.286E+003 9.874E+002 1004.76 18.01 l. 541E+003 1-5.488E+002 5. 769E+002 12,4. 43 34.80 8.922E+002 ... 1. 312E+002 3.340E+002 1596.48 1. 80 l.688E+004 >-2.27 2E+003 5.981E+003 Eu-155 45.30 1.31 3.005E+004 1. 80E+003 3.033E+003 1.356E+004 60.01 1. 22 3.669E+004 -9. 4 63E+003 l.678E+004 86.55 30.70 1.798E+003 ... 5.837E+002 8. 466E+002 105.31 21.10 2.024E+003 ... 8.047E+002 9.359E+002 Tl-208 583.19 85.00 4.800E+002 4.80E+002 -7.9 25E+OOO 2.141E+002 Bi-211 351. 07 13.02 3.685E+003 3.69E+003 2.267E+003 1. 711E+003 Pb-211 404.85 3.78 8 .663E+003 4.04E+003 3.983E+003 3.844E+003 427.09 1. 76 1.695E+004 l.342E+003 7.398E+003 832.01 3.52 4.043E+003 -2.885E+003 1.278E+003 Bi-212 39. 86 1. 06 2.571E+004 4.99E+003 3.091E+003 1 .158E+004 727. 33 6.67 5.951E+003 3.542E+003 2.608E+003 785.37 1.10 2.408E+004 2.988E+003 9.728E+003 1620.50 1. 4 7 4.99 4E+003 O.OOOE+OOO O.OOOE+OOO Pb-212 115 .18 0.60 4.620E+004 8.76E+002 ... 2. 813E+004 2.120E+004 238 .63 43.60 8.761E+002 3.549E+002 4 . 054E+002 300.09 3.30 8.000E+003 >-2.025E+00 3 3.518E+003 Pb212-XR 74.82 10.28 5 . 081E+003 2 .22E+003 2 .966E+003 2 .423E+0 03 77 .11 17.10 2.222E+003 --1.605E+003 1. 04 2E+003 87.35 3.97 9.530E+003 ,-3,603E+003 4.481E+003 89.78 1. 46 2.309E+004 '""l.828E+004 1.077E+004 Bi-214 609.32 45. 49 l.615E+003 1.62E+003 2.223E+003 7.579E+002 768.36 4.8 9 7.893E+003 3.294E+003 3 .431E+003 806.18 1.~6 1.812E+004 '""3. 678E+003 7 .020E+003 934.06 3.11 1. 368E+004 8. 088E+003 5.949E+003 1120.29 14. 92 3.526E+CJO::! 2.174E+003 1.560E+003 1155 .21 1. 63 2 .421E+OO<J 5.386E+003 1.023E+004 1238.12 5 . 83 7 .830E+ 003 3 . 262E+003 3.371E+0 03 1280 .98 1. 43 1. 783E+004 '""4.154E+002 6 . 695E+003 1377. 6; 3 . 99 9 .31 0E+003 3 .2 33E+0 03 3. 816E+003 [117]
Nuc1ide MDA Report Page 6 . c 6 Nuclide Energ:* Yield Line MDA Nuclide MD.A Acti *., it~* Dec. Level Name (keV) ( .. ) (pCi 1 1-1A2 ) (pCi/M"2 ) (pCi/r1"2 ) (pCi *M"2 ) 13J5.31 0.79 4.100E+004 >-9,5J9E+OOJ 1.627E+004 1401.52 1. 33 3.533E+004 1.642E+0 04 1.513E+004 1407.99 2.39 1.570E+004 3.062E+003 6.435E+003 1509.21 ~.13 l.836E+004 6.506E+ 003 7.525E+003 1661.27 1.05 3.161E+004 1.974E+ 003 l.225F.:+004 1729.59 2.88 1. 055E+004 8.988E+002 3.951E+003 Bi-214 1764.49 15.30 4.388E+003 1.62E+003 2. 725E+003 l.942E+003 1847.43 2.03 l,732E+004 >-1. 442E+003 6.709E+003 > 2118. 51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO Pb-214 241.99 7.25 4.596E+003 l.35E+003 1. 370E+003 2.100E+003 295.22 18.42 2.299E+003 1.520E+003 1.064E+003 351.93 35.60 l.351E+003 6.812E+002 6. 271E+002 785.96 1. 06 2.330E+004 -2.666E+002 9 . 246E+003 Pb214-XR 74.82 5.80 9.015E+003 3.92E+003 5.263E+003 4.300E+003 77 .11 9.70 3.922E+003 -2.833E+003 1 .838E+003 87.35 2.24 l.691E+004 -6.392E+003 7 .9 5 0E+003 89.78 0.82 4 .115E+004 -3.258E+004 l.920E+004 Ra-2.26 186.21 3.64 9.167E+003 9. 17E+003 2.847E+003 4.235E+00 3 Ac-228 129.07 2.42 l.378E+004 l.96E+003 2.714E+003 6.415E+003 209.25 3.89 7.063E+003 -1. 013E+003 3.187E+003 270.24 3.46 8.544E+003 -l. 1 25E+003 3.835E+003 328.00 2.95 1. 119E+ 004 6.511E+003 5 .030E+003 338.32 11. 27 2.871E+003 i-2 .112E+002 1. 286E+003 409.46 1. 92 1.562E+004 2.855E+003 6.846E+003 463.00 4.40 6.001E+003 >-4,888E+002 2.553E+003 794.95 4.25 7.420E+003 2.783E+003 3.107E+003 911,20 25.80 1.~63E+ 003 9.545E+002 8.756E+002 964.77 4.99 6.951E+003 4.635E+002 2. 911E+003 968.97 15.80 3.104E+003 1.578E+003 1. 373E+003 1588.20 3.22 l.321E+004 6.660E+003 5.478E+003 Pa-231 27.36 10.30 l.947E+003 1.95E+003 >-1.694E+002 8 . 4 2 7 E+ 00 2 283.69 1. 70 1 .927E+004 >-3,530 E+002 8 .723E +003 300.07 2.47 1 .069E+004 -2. 70 5E+003 4. 7 00E+0 0 3 302.65 2.20 1 .419E+004 l.621E+003 6.368E+003 330.06 1.40 1. 769E+004 --6 . 1 0 9E+003 7.655E+003 Th-234 92.38 2 .13 1.8 1 9E+015 1.82E+015 --4.4 52E+Ol2 8.546E+ 014 92.80 2.10 l.897E+015 4. 692E+014 8.9 2 9E+014 112.81 0.21 l.552E+016 -- 1 .130E+01 5 7 . 2 02E+01 5 U-235 143.76 1 0.96 2.933E+003 5.82E+0 0 2 - 4.07 7 E+002 1. 3 60E+ 0 0 3 163.33 5.08 5.477E+003 9.237E+002 2. 4 99E+003 185. 71 5 7 .20 5.8 2 0E+002 1.525E+002 2.689E+002 202 .11 1.08 2 . 463E+0 0 4 -1 . 628E+0 04 l.1 0 9E+004 205.31 5 .01 5 .3 49E+003 '--1. 46 8E+002 2 . 410E+00 3 Am-241 59.54 35.90 9.644E+002 9.64E+002 1. 230E+002 4.445E+0 0 2
+ = Nuclide identified during the nuclide identification
- Energ~ line found in the spe ctrum
>
- MDA value not cal culat e d
@
- Ha lf-li f e too s hort to be a ble to p e rform the de cay corre c t i on
[118]
Page 2 of 7 GA MM A S P E C T R U M t-~ N A L Y S I S
~ * /I 1. s o1.,_ 'KhS.
A't C.-;f',"'::.tS:."-..tt ; 'l1t f;1~ : ~r!
..., ~(!!Drf~Tt@ ~m1 Filename: C:\GENIE2K\CAMFILES\RWC010.CNF Report Generated On 7/9/2015 7:33:14 AM Sample Title RWC0l0 Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels): 50 - 8192 Peak Area Range (in channels} : 50 - 8192 Identification Energy Tolerance: 10.000 keV Sample Size
- 2.827E+001 MA2 Sample Taken On 1/28/2013 12: 00 : 00 PM Acquisition Started 6/29 / 2015 2:16:34 PM Live Time 600. 0 s e conds Real Time 600.6 seconds Dead Time 0 .10 %
Ener gy Calib rat i on Used Done On 1 /27/20 15 Efficiency Ca libration Used Done On 7 / 8/2 015 Efficienc y ID CRIB HOUSE 3 M [119]
Page 3 of 7 Report Date : 7/9/2015 7:33:14 AM Sample
Title:
RWC0l0 Peal{ Analysis Performed on: 7/9/2015 7:33:13 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak ROI ROI Peak Energy FWHM ~ontinuum INo. start end centroid (keV) ( keV) ~aunts 1 1177 1187 1181.08 295.13 0.47 2 .7 50E+001 2 1403 1416 1407.97 351. 87 1.25 3.l00E +00l 3 2430 2444 2436.74 609.09 1. 40 1.521E+001 4 4477 4489 4483.48 1120.55 0.40 1.125E+001 5 5833 5855 5846.26 1460.88 1. 51 5.310E+000 Dark Orange .; Fi .:rgt p e:ii:kk i .n .3. mu.l.t..i.ple t , :.r: eg.i on Green = Fitted. r'. ingl.et Errors quoted at 2.000 sigma U LID IDE TIFICATIO R ORT Sample
Title:
R\!VC010 Mw:; l1de Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Report Generated: 7/9/2015 7 33:14 AM
. . . ... IDENTIFIED NUCLIDES . ., . . * . . . .
Nuclide Id Energy Yield Activity Acti vi t :* Name Confidence (keV} ( *, ) (pCi/M"2 } Uncertaint '.I (-'..-./; 0 L COC 11. s0. ':! -* 1 0.S:'i S. Fl.5:18;. ->-001. 7 . ~,5tJ77t *:-003 i) j_ . ?. :J ; :t .000 sos 3 2 :. -'fo . I' 9 ?. * ?.2760):;.;.QQ:J c. co1 ;-,. a1;+002 768.36 4.89 806.18 1.26 934.06 3 .11 i :i.'.? O. _*:g: ** i _t,, . 9? ?.
- 96 ) ;;i 0::+00~ ~. -'. :,.s.olm+ooJ 1155.21 1. 63 1238 .12 5.83 1280.98 1.43 1377. 67 3.99 1385.31 0.79 140 1. 52 1.33 1407.99 2 . 39 1509.21 2.13 1661. 2 7 1.05 1729.59 2 .88 1764.49 15.30 1847.4 3 2.03 2118 . 51 1. 16 Pb- 21 4 1. 000 241.S9 7.25
?~:.. ~_?. * " ti. 1l2. l .(i SC "l.4J.::t- '.;C3 ,_. 2 ? S!,:J s*,,.*CC3
- s1. z3*,** J ;:i .60 l . g :_
3 5.~ Q~*~*+OCJ 8 . ij ~OS'.,E+ CC? [120]
- Interference Corrected Ar-'"ivities Report Page 4 of ..
Nuclide Id Energy Yield ~cti vity A.ctivity Name Confidence (keV) ( %) (pCi/M" 2 ) Oncertaintv
@ = Energ~, line not used for Weighted Mean Activity = Nuclide 11as correc ted for parent / dau ghter Energy T~lerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted a t 2 . 000 sigma N RFE E CE CORRECTED REPORT Nuclide Nuclide Wt mean Wt* mean Name Id Confidence Activity (pCi/M"2 ) Activity Unc ertainty K-40 1.000 3.775183E+004 7.168768E+003
- { E-a L .3 t . ~1:'
':{ C~-*l:;;i~. 31}2 X B ..i. '::l l f..~9fi Bi-214 1. 000 2.319350E+003 7. 4 85435E+002 Pb-214 1. 000 1.730565E+003 7. 2 02 3 0 8E+002 ? - nu c l .::..de i s )?ctX t o :t: an u .ndete ~-mine d ~ol .uti o n I = "'IUC.Li e ":*1=J11-.:.tcrl. Dy * .;( ,r.:. in*c :r:J:: el:-1° 11c'"" . c, .. lyo.l-~ @ = n uc.':.. i .cle con*l;a:i.u s ,;u:.e:r:g y .l..i.nes r.o'i:. used i n We :l.gh t od M.ean J>.-1::tiv:i.ty TIFIE PEAKS Peak Locate Pe r fo r med on : 7 / 9 / 2 0 15 7 : 33 : 13 AM Peak Lo cate From Channel~ 50 Peak Locate To Channel : 81 92 Peak Energy Peak Size in Peak CPS No. (keV) Counts er Se con d % Unc ertaint All peaks were identified.
ORT De t e ctor Name* 5456 Samp l e Geometry
- Cr i;)hOUS e 3in Sample Titl e *. RWCOlO Nuclide Library Us ed
- C ; \GENIE2K\CAM FILES\Zi o n Lib~BNL . NLB Reper~ Generated on : 7/9/2015 7 : 33 :; 1 5 AM
[121]
Nuo1ide MDA Report Page 5 of 7 , Nuclide Energ~* Yield Line MDA Nuclide l-IDA Acti"it'..' Dec. Le*re l Name (keV) ( ') (pCi/tlA2 ) (pCi /11" 2 ) (pCi/W2 ) (pCi/[1A2 )
+ K-40 1460.32* 10.66 4.135E+003 4.13E+ 003 3.775E+004 1.743E+003 Cr-51 320.08 9.91 1.172E+013 1.17E+013 .... 3.981E+0 1 2 5.225E+012 tln-54 834.35 99.98 1.802E+003 1. 80E+003 '"4.124E+002 7.15 1 E+002 Co-58 810.76 99.45 1. 703E+006 1.70E+006 2.684E+005 7 .064E+005 Co-60 1173.23 S/9.85 4.432E+002 4 .37E+002 1. 336E+002 1. 791E+002 1332.49 99.98 4.367E+002 ,-3.331E+001 1.733E+002 Nb-94 702.65 99.81 3.595E+002 3.59E+002 2.808E+001 1.556E+002 871. 09 99.89 3. 726E+002 9.897E+001 1. 595E+002 Sn-113 255.13 2. 11 2.765E+006 8.16E+ 004 -9.384E+005 1.241E+006 391. 70 64.97 8.157E+004 -1. 659E+004 3. 512E+004 Cs-134 475.36 1. 48 3.912E+004 9.38E+002 5.952E+003 l. 652E+004 563.25 8.34 4.016E+003 ~4.3 7 9E+003 l.423E+003 569.33 15.37 3.930E+003 ~1.369E+003 1.646E+003 604. 72* 97.62 9.510E+002 2.333E+003 4.236E+002 795.86 85.46 9.380E+002 ,--1, 381E+002 4.016E+002 801.95 8.69 5.909E+003 '"2.09 1E+003 2.289E+003 1038.61 0.99 6.908E+ 004 ,-8.164E+003 2.791E+004 1167. 97 1. 79 3.083E+0 04 ,-4,773E+002 1.154E+004 1365.19 3.02 1.348E+004 1. 832E+003 4.262E+003 Cs-137 661. 66 85.10 3.416E+002 3.42E+002 '"9.083E+001 1.417E+002 Eu-152 121. 78 28.67 1.568E+003 1.36E+003 8.456E+002 7.391E+002 244.70 7.61 4.731E+003 .... 1, 34 6E+003 2.151E+003 295.94 0. 45 9.803E+004 5. 0 51E+004 4.502E+004 344.28 26.60 1.363E+003 2.561E+002 6.092E+002 367.79 0. 86 3. 7 32E+004 ,-1, 705E+ 003 l.635E+0 04 411.12 2.24 1.397E+004 ,-z.853E+003 6.047E+003 443.96 2.83 9.933E+003 r-4.077E+0 03 4.195E+003 488.68 0.42 5.281E+004 ,-1.813E+00 4 2.095E+004 563.99 0. 4 9 5.552E+004 1.122E+00 4 2.2 7 6E+004 586 .26 0. 4 6 7.295E+004 .-3.227E+00 4 3.103E+004 678.62 0.47 7.628E+004 ,....z. 906E+004 3.245E+004 688.67 0.86 3.495E+004 7.481E+002 1.432E+004 719.35 0.28 9.592E+004 ,-7. 573E+004 3.80 6E+004 778.90 12.96 2.596E+003 ,-2. 65 9E+002 1.077E+003 810.45 0.32 9.495E+004 ,-z, 693E+004 3.837E+004 867.37 4.26 6. 871E+003 ~1.022E+003 2.726E+OO?
919.33 0.43 8.960E+004 1 .314E+004 3 .752E+004 964.08 14.65 3.518E+003 9.643E+002 1.54 2E+003 1085.87 10.24 2 .619E+003 7.300E+002 9.805E+002 1089.74 1. 73 2 . 166E+ 004 4.431E+003 8.880E+003 1112. 07 13.69 1.709E+003 d.150E+003 6.05 6E+ 002 1 2 12.95 1. 43 2. 7 65E+004 8.548E+003 1. 133E+004 Eu-152 1249.94 0.19 1.692E+005 1.36E+003 3.610E+004 6.555E+00 4 1299.14 1. 63 2 .505E+004 6.257E+003 1.027E+004 1408. 01 21. 07 2. 0 16E+003 6.522E+002 8.265E+002 1457.64 0.50 1.117 E+005 O.OOOE+OOO 4.810E+004 1 528 .10 0. 28 7.739E+004 1.052E+004 2 .44 6E+004 Eu-154 12 3.07 40.40 1.087E+003 1.09E+003 -2.070E+002 5.092E+002 247.93 6.89 5 .414E+003 ~3.34 2E+002 2.451E+003 591.76 4 .95 6.395E+003 1.02 0E+003 2.65 2E+003 692 .42 1. 78 1. 7 08E+004 ~ 2 .321E+003 6 . 900E +003 72 3 . 30 20.06 1.545E +003 ..... 5.477E+oo::: 6.24 2E+ 002
- 56.80 4 .5 2 8.278E+003 1.214E+003 3.46 7E+003
[122]
Nuclide MDA Report Page 6 of ..,
*Nuclide Energ:; Yield Line UDA Nuclide MDA Activit:' Dec. Le"el Name (keV} (',} (pCi/M"2 } (pCi/H"2 } (pCi / H"2 ) (pCi/tl"2 )
873.18 12.08 2.989E+003 ... 9.811E+002 1. 225E+003 996. 29 10.48 2.943E+003 -2.144E+002 1.140E+003 1004.76 18.01 2.150E+003 4.295E+002 8.812E+002 1274.43 34.80 1.245E+003 4.470E+002 5.102E+002 1596.48 1.80 4.919E+003 O.OOOE+OOO O.OOOE+OOO Eu-155 45.30 1. 31 3.634E+004 2.00E+003 l.492E+004 1. 671E+004 60.01 1. 22 6.558E+004 l.269E+004 3.123E+004 86.55 30.70 1.998E+003 ""9,717E+002 9.466E+002 105.31 21.10 2.707E+003 1.088E+003 1.277E+003 Tl-208 583. 1 9 85.00 5.327E+002 5.33E+002 1.376E+002 2.404E+002 Bi-211 351. or 13.02 3.234E+003 3.23E+003 5.071E+003 1.485E+003 Pb-211 404.85 3.76 6.008E+003 6.01E+003 4. 306E+002 2.516E+003 427.09 1. 76 1.695E+004 1. 019E+003 7.398E+003
!i32.0l 3.52 7.203E+003 -2.472E+002 2.858E+003 Bi-212 39.86 1.06 2.529E+004 5.64E+003 2.483E+003 l.137E+004 727.33 6. 6'"' 5.635E+003 3.399E+002 2.450E+003 785.37 1.10 2.845E+004 3.841E+003 1.191E+004 1620.50 1.47 l,714E+004 3.691E+003 6.071E+003 Pb-212 115 .18 . 0. 60 6.120E+004 1 . 15E+003 -1.789E+004 2.870E+004 238.63 43.60 l.150E+003 1. 251E+003 5.421E+002 300.09 3.30 8.193E+ 003 -7.504E+002 3.614E+003 Pb212-~~R 74.82 10.28 6.404E+003 2.63E+003 9.492E+003 3.085E+003 77 .11 17.10 2.634E+003 -l.122E+003 1.247E+003 87.35 3.97 l.146E+004 5.432E+003 5.444E+003 89.78 1. 4 6 2.670E+004 ... 9.144E+003 l.258E+004 + Bi-214 609.32* 45.49 9.083E+002 9.08E+002 2.228E+003 4.045E+002 768.36 4.89 6.907E+003 O.OOOE+OOO 2.938E+003 806.18 1.26 2.394E+004 ... 3.772E+002 9.~28E+003 934.06 3.11 1.100E+004 5.942E+003 4.608E+003 1120. 29* 14.92 3.088E+003 2.962E+003 1.341E+003 1155.21 1. 63 2.881E+004 1. 320E+004 1. 252E+004 1238.12 5.83 8.568E+003 3.655E+003 3.740E+003 1280.98 1. 43 1.543E+004 -5.400E+003 5.466E+003 1377.67 3.99 1. 080E+004 5.394E+003 4.561E+003 1385.31 0.79 3.367E+004 ... 1.095E+004 1. 260E+004 1401. 52 1. 33 1. 743E+004 - 7 . 27 3E+003 6 .1 75E+003 1407.99 2.39 1. 570E+004 5.339E+003 6.435E+003 1509.21 2.13 1.603E+004 3.484E+003 6.360E+003 1661. 27 1.05 3.712E+004 1.579E+004 1. 500E+004 1729.59 2.88 1. 556E+004 4.657E+003 6.452E+ 003 + Bi-214 1764.49 15.30 3.754E+003 9.08E+002 2.376E+003 1.62 4E+00 3 1847.43 2 .03 1.552E+004 2.163E+003 5 .810E+003 I> 2118.51 1. 16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO + Pb-214 241.99 7.25 5. 674E+00 3 1.18E+003 2.788E+003 2.639E+003 295.2 2
- 18.4 2 1. 877E+003 1.490E+003 8 .525E+0 02 351. 93* 35.60 1.184E+003 1.856E+003 5.437 E+0 02 785.96 1.06 3.346E+004 1.155E+004 l.432E+004 Pb214-XR 7 4. 82 5.80 1.136E+004 4.65E+0 03 1.684E+0 04 5.4 7 4E+00 3 77 .11 9.70 4.648E+003 - l . 979E+003 2 . 201E+00 3 87.35 2.24 2.033E+004 9.637E+003 9.659E+003 8 9. 78 0.82 4."759E+004 --l.630E+004 2.242E+004 Ra-226 186. 2 1 3.6~ 9.167E+003 9.17E+003 2.327E+003 4 .2 35E+003 Ac-228 129.07 2 .4 2 l .5 06E+0 04 2.43E+003 4.056E+003 7 .0 56E+0 03 209.25 3.89 8.889E+003 4.027E+003 4.1 00E+00 3
[123]
Nuclide MDA Report Page 7 of~
- . Nuclide Energ:* Yield Li ne t-1DA Nuclide I1DA rtCtiTTit~* Dec. LeTTel Name (ke'7) { ~-) {pCi 1t--1"2 ) (pCi I W-2 ) (pCi/11" 2 ) (pCi/W'2 )
270.24 3.46 8.544E+003 i-2.368E+003 3.835E+003 328.00 2.95 8.624E+003 1. 144E+003 3.749E+003 338.:'2 11.27 3.021E+003 l.603E+003 1.361E+003 409.46 1. 92 1.715E+004 5.277E+003 7.609E+003 463.00 4.40 7.053E+003 8.685E+002 3.079E+003 794.95 4.25 9.491E+003 .J.675E+003 4 . 14 3E+003 911. 20 25. 80 2.433E+003 t!.139E+003 1. ll1E+003 964. 77 4.99 8.892E+003 3.324E+003 3.882E+00 3 968.97 15.80 3.303E+003 l.075E+003 1.473E+003 1588.20 3.22 1.000E+004 6.244E+002 3.874E+003 Pa-231 27.36 10.30 2 .514E+003 2.51E+003 3.873E+OOO 1.1 2 6E+ 003 283.69 1. 70 1.898E+004 4. 894E+003 8.5 8 1E+003 300.07 2.47 1.095E+004 -1. 00 2E+003 4.829E+00 3 302.65 2.20 1.175E+004 - 4 .847E+003 5 .149E+003 330.06 1. 40 2 .02 2E+004 4 .675E+003 8.918E+003 Th-234 92.38 2.13 1.969E+015 1. 97E+015 1.189E+0 14 9.293E+014 92.80 2.10 2.130E+015 1. 407E+ 0 15 1. 009E+015 112.81 0.21 1. 672E+016 -3. 721E+015 7.798E+01 5 U-235 143. 7 6 10.96 2.982E+003 6.18E+002 1.393E+002 1.384E+00 3 163.33 5.08 6.052E+003 1.334E+003 2.7 8 7E+00 3 185.71 57.20 6.18 4E+002 3.567E+002 2.8 71E+ 00 2 202 .11 1.08 2.725E+004 ~3.155E+003 1. 240E+ 004 205.31 5.01 4. 8 98E+003 .... 4.766E+002 2.184E+ 003 Am-241 59.54 35.90 1.508E+003 l.51E+ 003 .... J. 57 4E+002 7 .162E+0 02
+ Nuclide identified during the nuclide identification * ~ Energy line found in the spectrum > = t1DA *ralue not calculated @ Half-life too short to be able to perform the decay corre cti on
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Page 2 of 7 GA MM A ._; P E C T R U M -J. N A L Y S I S Filename: C:\GENIE2K\CAMFILES\RWC011.CNF Report Generated On 7/9/2015 7:34:13 AM Sample Title RWC0ll Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels): 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance: 10.000 keV Sample Size
- 2.827E+001 MA2 Sample Taken On 1/28/2013 12:00:00 PM Acquisition Started 6/29/2015 1:07:07 PM Live Time 600.0 seconds Real Time 600.8 seconds Dead Time 0.13 %
Energy Calibration Used Done On 1 /27/2015 Efficiency Calibration Used Done On 7/8/2015 Efficiency ID CRIB HOUSE 3M [125]
Page 3 o f 7 Report Date : 7/9/2015 7:34:14 AM Sample
Title:
RWC0l 1 Peak Analysis Performed on: 7/9/2015 7:34:13 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak ROI ROI Peak !Energy FWHM ~ontinuum No. start end centroid (keV) (keV) ~ounts 1 948 961 955.86 238.80 1.08 4.719E+001 2 1402 1417 1408.83 352.08 1. 03 2.358E+001 3 2432 2444 2438.65 609.57 0.94 1. 953E+001 4 5836 5857 5846.48 1460.93 1. 92 O.OOOE+OOO 5 7058 7069 7063.29 1764.66 1.15 2.750E+OOO Oa.:ir:k O:canga ~~ F :i..r.:s t . p e ak i.n a nul 1. t.i.p :Le t :r.egi.on Green = Fitted ::,Ji.n.,p,:l.et: Errors quoted at 2.000 sigma N CLIDE IDENTIFICATION REPORT Sample
Title:
RWC011 Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Ub~BNL.NLB Report Generated. 7/9/2015 7 34:14 AM
... ... I DENTIFIED NUCLIDES ..... ....
Nuc lide Id Energ:, Yield Acti.,it:* Ac t i vit y Name Confidence (keV) { ,) (pCi / W2 ) Uncertainty K -*:10 : .coo JA SO.C.? *~ :1-0 . ~ *~ 3. 71 0CSE+*OOIJ 6. 7*15.t;; Sfch 0 03 Pb-212 1. 000 115 .18 0.60
?.:'.JO. GJ*.fl! B .60 1 . -,,01-:c, .1,:+ cc3 S. 'iS!:i*I.JE < lO,,
300.09 3.30
~J.-? l ". :. . 000 G:l 9 . 3 2 ** r, ;;,. l!S :I. . :53C?Sri, *OCJ '/ . ~.557~:1-,*CO?.
768. 3 6 4 . 89 8 06.18 1. 2 6 934. 06 3 . 11 1120. 2 9 14 . 92 1155 . 21 1. 63 1238.1 2 5.83 128 0.98 1. 43 1377. 6 7 3 . 99 1385 . 3 1 0 . 79 1401. 52 1. 33 1407 . 99 2 . 39 15 09 . 21 2.13 1661. 27 1.05 172 9.5 9 2 . 88
- u s,*. 4S ~ 13 .30 i4 . 7:l.?:n :~,+ 0 03 ? . ** J .*. ss.:: . 0::1 1 847 . 43 2 . 03 211 8 . 51 1.16
[126]
Interference Corrected ~~tivities Report Page 4 o~ 7 Nuclide Id !Energy [Yield ~ctivity Activity Name Confidence (keV} ( %) (pCi/M/\2 ) Oncertaintv 295.22 18.42 351 . 9:3* :1 5 . tiO ~ .. Ol509E*+*tl-O 6 . 1;; 7 ~~7E+t'JC
. ! )\.~.':lC . 785. 96 1.06 lt ... 1.:.-~ C!' *, :c;*e . *.:..'J1t"?* ;1:,:-. ~:".',*'"' :s~:-. .-, r. t:.. ,....l:ffl * @ = Energ~ line not used for Wei ghted Mean Act ivity ! = Nuclide Has corrected for parent/daughter Energy Tolerance: 10.000 k~*
Nuclide confidence inde:~ threshol d O. 30 Errors quoted at 2.000 sigma I TERF E C C RRECTED PORT Nuclide Nuclide Wt mean Wt mean Name Id Confidence Activity {pCi/M/\2 ) Activity Uncertainty K-40 1. 000 3.710862E+004 6.776458E+003 1-;. B . *-:!~3 i. :'." .* '3 1: C~ *-l.:J.4 \j . -~;. t\
!: n
- _ ,*.11 [ . 99f*
Pb-212 1.000 8.692995E+002 6.911422E+00 2 Bi-214 1.000 l.96148 2 E+003 7.054214E+002 Pb-214 0.515 2.015090E+003 8.674308E+002
}i: :r:J."l. -:t 2 *)' 0 . 7:24. ? *- nuclide :i.s pa r t o ,: an 'i.,ndete.~ti1:i.r1.aci so].ut i o n ..* = .r*il'°'.l~..-!. 1~.l t..;,;.:J t-:l *,'.);,,_. ' :ut *.*::i~-- ..:r,c. . 4n *.1~~"'* .,*: @ *- 11-ucl :kle con t;ain s e nergy l.i.nes n :>t ..1sed in t<io:L\Tilt~d !il 'a ,m JlCt~ivit~/
0
- Peak Locate Performed on ~ 7/9/2015 7 :: 34 : 13 AM Peak Locai:e From Channe.:i. ~ 50 Peak Locate To Channel : 8192 Peak Energy Peak Size in Peak CPS No. (keV) Counts er Second % Uncertaint All peaks were identified .
DA RE Detector Name : 5456 Sam?le Geometry : Cribhouse 3m Sample Title : RWC0ll [127]
Nuc1ide MDA Report ~age 5 of 7 Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Report Generated on: 7/9/2015 7:34:14 AM Nuclide Enerq:* Yield Line llCA Nuclide t-lDA Acti~*ity Dec. Le7el Name (ke") ( ) (pCi/!f"2 ) (pCi/t-1' 2 ) (pCi/M"2 ) (pCi/tl"2 )
+ K-40 1460.82* 10.66 6.47:,E+002 6.48E+002 3.711E+004 0.000E+000 Cr-51 320.08 9.91 9.695E+012 9.70E+0 12 7. 017E+0ll 4.215E+012 Mn-54 834.85 99.98 2.849E+003 2.85E+003 l.145E+003 l.239E+003 Co-58 810.76 9). 45 l.946E+006 1.95E+006 7.389E+005 8.279E+005 Co-60 1173.23 99.85 3.383E+002 3.38E+002 1. 571E+001 1.266E+0lJ2 1332. 49 99.98 4.001E+002 7.287E+001 1.550E+002 Nb-94 702.65 99.81 3.242E+002 2.59E+002 3.737E+001 1. 379E+002 871.09 99.89 2.595E+002 ... 6.829E+001 1.030E+002 Sn-113 255.13 2 .11 2.764E+006 7.88E+004 r-3.037E+005 1. 240E+006 391. 70 64.97 7.879E+004 6.976E+002 3.373E+004 Cs-134 475.36 1.48 3.563E+004 7.03E+002 ,-..4.141E+003 1. 478E+004 563.25 8.34 5.669E+003 r-9,514E+002 2 . 250E+003 569.33 15.37 3.325E+003 r-1. 7 68E+002 1.344E+003 604.72* 97.62 1.015E+003 1.707E+003 4.557E+002 795.86 85.46 7.027E+002 4.983E+001 2.839E+002 801. 95 8.69 5.909E+003 ... 1. 968E+003 2.289E+003 1038.61 0.99 6.908E+004 i--2.327E+004 2.791E+004 1167. 97 1. 79 3.440E+004 l.146E+004 l.332E+004 1365.19 3.02 1. 348E+004 ... 1.237E+004 4.262E+003 Cs-137 661.66 85.10 3.905E+002 3.91E+002 6.949E+001 1.661E+002 Eu-152 121.78 28.67 1. 233E+003 1.08E+003 .-3.621E+002 5. 715E+002 244.70 7.61 4.118E+003 ... 2 .111E+003 1. 844E+003 295.94 0.45 9.907E+004 4.613E+004 4.554E+004 344.28 26.60 1. 075E+003 ,-..7.827E+001 4.653E+002 367.79 0. 8 6 3.092E+004 2.480E+003 1.315E+004 411.12 2.24 1. 397E+004 1.030E+003 6.047E+003 443. 96 2.83 9.503E+003 4.910E+002 3.980E+003 488.68 0.42 7.017E+004 r-5.035E+003 2. 9 63E+004 563.99 0.49 4.847E+004 1. 849E+003 1.923E+004 586.26 0.46 6.382E+004 1.068E+004 2.647E+004 678.62 0.4 7 7.009E+004 9.697E+003 2.935E+004 688.67 0.86 3.282E+004 3.976E+003 1.326E+004 719. 35 0.28 1. 099E+005 -5.383E+004 4.503E+004 778.90 12.96 1. 965E+003 -2.250E+002 7.613E+0 0L 810.45 0.32 1.173E+005 2 .171E+004 4 .953E+00 4 867.37 4. 2 6 5.642E+003 r- 7 .993E+003 2 .112E+003 919.33 0.43 7.049E+004 1.936E+004 2 . 797E+0 0 4 964.08 14. 65 2.800E+003 9. 724E+002 1. 182E+003 1085.87 10.24 2.619E+003 r-6.083E+002 9.805E+002 1089.74 1. 73 2.035E+004 4.569E+003 8.221E+003 111 2 .07 13 . 69 2. 413E+003 2.025E+00 2 9. 57 6E+002 1212.95 1. 43 2.596E+004 5 .063E+003 1. 049E+004 Eu-152 1249.94 0.19 2 .115E+005 1 .08E+003 ,-..6.088E+004 8. 671E+004 1299.14 1. 63 2.004E+004 1. 2 5 1E+003 7.763E+003 1408.01 21.07 2.016E+003 7 .002E+002 8. 2 65E+002 1457.64 0.50 5.32 5E+00 4 ,-..4.301E+003 1.887E+004 1528.10 0. 28 7 . ~39E+004 7.887E+003 2.446E+004 Eu- 154 123.07 40. 40 1.016E+003 7. 70E+ 002 3.693E+002 4.740E+002
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Nuclide M>A Report Page 6 .c 7 Nuclide Energ:* Yield Line MDA Nucl ide tlDA rl.Ctivi t :* Dec. Lev el Name (keV) ( -) (pCi/M"2 ) (pCi /11"2 ) (pCi/Il"2 } (pCi/M'-2 ) 247.93 6 .8 9 4.734E+003 - l. 448E+003 2 .111E+003 591.76 4.95 6.39SE+003 '-1. 751E+003 2.652E+003 692.42 1. 78 2.018E+004 '...345E+003 8.451E+003 723. 30 20.06 l.545E+003 '--6.435E+002 6.242E+002 756.80 4.52 --:.882E+003 :.304E+003 3.269E+003 873.18 12.08 2.391E+003 '-'...642E+003 9.261E+002 996. 2 9 10.48 4.084E+003 :.532E+003 1. 710E+003 1004.76 18.01 2.150E+003 1 .534E+001 8.8 12E+002 1274.43 34.80 7.697E+002 '-3.730E+002 2.727E+002 1596.48 1. 80 1.338E+004 '-2. 272E+003 4.229E+003 Eu-155 45.30 1. 31 3.187E+004 1. 82E+003 1. 033E+003 1. 447E+004 60.01 1. 22 4.476E+004 '-9.578E+003 2.082E+004 86.55 30.70 1. 817E+003 '-8.196E+002 8.562E+002 105.31 21.10 2.266E+003 2.702E+002 l.057E+003 Tl-208 583.19 85.00 4.983E+002 4.98E+002 3.502E+002 2.232E+002 Bi-211 351. 07* 13.02 2.962E+003 2.96E+003 5.504E+003 1.349E+003 Pb-211 404.85 3.78 7.024E+003 7.02E+003 '-8.320E+001 3.024E+003 427.09 1. 76 l.442E+004 '-6,324E+002 6.134E+003 832.01 3.52 7.203E+003 2. 4 72E+002 2.858E+003 Bi-212 39.86 1.06 3.588E+004 5.47E+003 7.692E+003 l.667E+004 727. 33 6.67 5.469E+003 2.772E+003 2.367E+003 785.37 1.10 2.564E+004 3.171E+003 l.051E+004 1620.50 1. 4 7 l.987E+004 2. 614E+003 7.436E+00 3
+ Pb-212 115.18 0.60 5.275E+004 9.71E+002 ~1.364E+004 2.448E+004 238.63* 43.60 9.715E+002 l.204E+003 4.530E+002 300.09 3.30 7.802E+003 l.562E+003 3.419E+003 Pb212-XR 74.82 10.28 5.694E+003 2.82E+003 4.652E+003 2.730E+003 77 .11 17 .10 2.821E+003 -2.996E+001 l.341E+003 87.35 3.97 l.005E+004 3.143E+003 4.740E+003 89.78 1.46 2.656E+004 4.185E+003 1. 251E+004 + Bi-214 609.32* 45.49 9.697E+002 9.70E+002 1.630E+003 4.353E+002 768.36 4.89 5.713E+003 9.520E+001 2 .344E+003 806.18 1. 26 2.394E+004 6.271E+003 9.928E+003 934.06 3.11 1.150E+004 -6.602E+002 4.857E+00 3 1120.29 14 .92 3.823E+003 2.564E+003 1. 709E+003 1155.21 1. 63 1.669E+004 -7.036E+003 6.467E+003 1238.12 5.83 8.798E+003 4. 155E+003 3.8 55E+003 1280.98 1. 43 3.237E+004 1. 860E+004 l.394E+004 137'.67 3.99 1 .125E+004 4.932E+003 4. 784E+003 1385.31 0.79 3.367E+004 '-7.037E+003 1. 260E+004 1401. 52 1. 33 1. 743E+00 4 3.754E+003 6.175E+003 1407.99 2 . 39 l . 5 70E+0 04 5 .190E+003 6 .4 35E+00 3 1509. 21 2 .13 1. 469 E+004 '-2.904E+003 5.689E+003 1661. 27 1. 05 2 .444E+004 5.264E+003 8,659E+003 1729.59 2.88 9.105E+003 l .961E+00 3 3 .226E+003 + Bi-214 1 764.49* 15.30 2.126E+003 9 . 70 E+002 4. 712E+003 8. 103E+002 1847.4 3 2.03 1. 890E+OO,J 4.614E+003 7 .500E+003
> 2118.51 1.1 6 O.OOOE+OOO O.OOOE+ OOO 0.000E+OOO
+ Pb- 214 2 41. 99* 7.25 5 . 848E+003 1.08E+003 7. 248E+00 3 2 . 727E+003 295.22 18. 42 2.084E+003 1 .171E+ 003 9.562E+002 35 1. 93* 35 .60 1.084E+003 2 .015E+ 003 4.939E+002 785 . 96 1.06 2.962E+004 1 . 3f- 2E+0 0 4 1. 240E+004 Pb214-XR 74. 82 5 .80 1 . 010E+004 4. 98 E+003 8.254E+003 4.843E+003 77 .11 9 .7 0 4. 979E+003 '- S .287E+001 2 . 367E+003
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Nuclide MDA Raport Page 7 c 7 Nuclide Energ:* Yield Line MDA Nuclide tmA ;\.ctivit~, Dec. Level Name ( ke) ('~) (pCi/M"2 ) (pCi 'M"2 ) (pCi ;tl"2 ) (pCi/~1"2 ) 87.35 2.24 l.783E+004 5.577E+003 8.410E+003 89.78 0.82 4.734E+004 7.460E+003 2.230E+004 Ra-226 186.21 3.64 8.821E+003 8.82E+003 4.018E+003 4. 062E+003 Ac-228 129.07 2.42 1 .357E+004 2.07E+003 5. l 73E+003 6. 311E+003 209.25 3.89 7.791E+003 l.145E+003 3.551E+003 270.24 3.46 6.891E+003 -2.35~E+003 3.008E+003 328.00 2.95 l.081E+004 4.448E+003 4.840E+ 003 338.32 11. 27 2.541E+003 l.343E+003 l.12 1E+003 409.46 1. 92 1.344E+004 -7.971E+003 5.752E+003 463.00 4.40 6.446E+003 8.717E+002 2.775E+003 794.95 4.25 6.686E+003 -1.431E+003 2.741E+003 911.20 25.80 2.074E+003 8.406E+002 9.309E+002 964.77 4.99 7.565E+ 003 3.441E+003 3.218E+003 968. 97 15.80 2.485E+003 1.210E+002 l.064E+003 158B.20 3.22 1. 091E+004 4.163E+003 4.33 1E+003 Pa-231 27.36 10.30 2.326E+003 2.33E+003 -6.939E+002 1.032 E+003 2B3.69 1. 70 1. 58 4E+004 6.4 48E+003 7.006E+003 300.07 2.47 l.042E+004 2.0B7E+o03 4.567E+003 302.65 2.20 l.234E+004 l.695E+003 5.444E+003 330.06 1. 40 1. 925E+004 -7.760E+001 8.436E+003 Th-234 92.38 2.13 l.772E+Ol5 1. 77E+015 5.552E+013 8. 311E+014 92.BO 2.10 l.830E+015 4.407E+014 8.593E+014 112. 81 0.21 l.694E+Ol6 3.114E+015 7.906E+015 U-235 143.76 10.96 2.B32E+003 5.66E+002 1.843E+002 1.310E+003 163.33 5.08 5.477E+003 6.755E+002 2.499E+003 185.71 57.20 5.656E+002 l.408E+002 2.607E+002 202 .11 1.08 2.579E+004 3.56 2E+003 1.167E+004 205.31 5.01 5.601E+003 5.383E+002 2.535E+003 Am-241 59.54 35.90 1.02BE+003 1.03E+003 -4.959E+002 4.765E+002
+ = Nuclide identified during the nuclide identification
- Energy line found in the spectrum
> MDA '.ralue not calculated @ Half-life too short to be able to perform the decay correction
[130]
Pa g e 2 of 7 GA M M A ....J P E C T R U M .. .>. N ALYS I S Filename: C:\GENIE2K\CAMFILES\RWC012.CNF Report Generated On 7/9/2015 7:35:37 AM Sample Title RFC012 Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance: 10.000 keV Sample Size
- 2.827E+001 MA2 Sample Taken On 1/28/2013 12:00:00 PM Acquisition Started 6/29/2015 1:47:52 PM Live Time 600.0 seconds Real Time 600.6 seconds Dead Time 0.10 %
Energy Calibrati on Used Done On 1/27/2015 Efficiency Calibration Used Done On 7/8/2015 Efficiency ID CRIB HOUSE 3M [131]
Page 3 of 7 Report Date: 7/9/2015 7:35:38 AM Sample
Title:
RFC012 Peal< Analysis Performed on: 7/9/2015 7:35:37 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak !ROI ROI Peak !Energy FWHM ~ontinuum No. start end centroid (keV) (keV} Counts 1 1402 1416 1407.43 351.73 0.98 2.280E+001 2 2430 2446 2438.40 609.51 1. 45 8.463E+OOO 3 5837 5857 5846.73 1460.99 1.10 8.116E+OOO Dar k Ur:ange ~ F.'i..rst peak. .i .n .s rnul t .i.p l .~ t-. :1:*egi.0.1*, G-z:-e en ~, Fi t te d. llling.l.e t Errors quoted at 2.000 sigma I Tl ICATION EPIRT Sample T,itle: RFC012 _. . .. Nuclide Library Used. C:\GENIE2K\CAMFiLES\Z1on L1b8NL..NLB Report Generated: ?/9/2015 7:35 38 AM [ IDENTIFIED NUCLIDES . . . . . . . ., ., Nuclide Id Energ:* Yield Act i ,Ji t ::r Activity Name Confi dence (keV) ( ) (pCi / !1"2 ) Uncertaint :,
-~---~,o .000 :VJi :SC. 8?
- 1 0.55 3. 42 0 S C? +00t, S. 9552 ::i:f ~-003 Ba-133 0.986 79.61 2.65
- 81. 00 32.90 276.40 7.16 302.85 18.34
- 5s.c1:, 52.05 :--. . '2733~1:~*003 !l . s: : 10£ ,-00::!
383.85 8.94 Cs-134 0 . 389 475.36 1.48 563.25 8.34 569.33 15.37 50 -1. . '/? -* s-*, . '5:..;. .?.
- 82?. >Sc; ~C03 ,'l. 3 9 5:~::r,,;~*0C?.
795 . 86 85 .46 80 1. 95 8. 69 1038.61 0.99 11 67. 97 1. 79 1365.19 3.02 P..1 -*.'.?. 1 ;, 'J.9S*9 3 5 ,_. c*; ,, :,J. C?. :j. ~ a*12s..;. oo:; 2. ~ 9 *1 ~) ~*e *:<J 03 H i - ? '.l r* 1 .0J0 5CS. :l.'.?*-* J1,J . ~ !;'! :: . s~s~3:r5~...-c.oz r . c2 :"'IO't':*oo:> 768.36 4.89 8 06.1 8 1. 2 6 93 4.06 3 .11 112 0. 2 9 14. 92 1155. 21 1. 63 1238 .1 2 5 . 83 [132]
Interference Corrected ~~tivities Report Page 4 of~ Nuclide Id Energy !Yield ~ctivity A.ctivity !Name Confidence (keV) ( %) (pCi/M"2 ) Oncertaint v 1377.67 3.99 1385.31 0.79 1401.52 1.33 1407.99 2.39 1509.21 2.13 1661. 27 1.05 1729.59 2.88 1764.49 15.30 1847.43 2.03 2118.51 1.16 Pb-214 1.000 241.99 7.25 295.22 18.42 351 . !(3* 35 . 60 1 . 89912E+ OO B. 38.,i32E+OO
.* 785.96 1. 06 ,. -:-~. ~.....1.,*~-,:-£~ ...:; .~1?.o i-.oL *,t_cl .1. / ,. *:-~.~--:~ ,sp , c:t, .:;~t:~i. .. @=Energy line not used for Weighted Mean Acti ~ity = Nuclide was corrected for parent/daughter Energy Tolerance : 10.000 keV Nuclide confidence index threshold 0.30 Errors quoted at 2.000 sigma I TEH ERE C C RREC ED REPORT Nuclide Nuclide Wt mean Wt mean Name Id Confidence Activity (pCi/M"2 ) Activity Uncertaint y K-40 1.000 3.420879E+004 6.966253E+003 ? Ba-1 33 0.986 l . 275588E*t*003 5. 631.29712:+ 002 ? Cs-1 3,.1 0.389 2.822550:1!:+003 8.396:t. 3 '.i.E+002 ? Bi - .21.:l. 0.999 5 . H l7~51E+003 2 . 29'1.S9,~E+003 ? :g,i.-2:lA 1.000 .2 . ;695832E*00 3 S . 021196i~+002 ? Ph ..*21. 4 1.000 l . 899l 2 1iHC03 8. 38 4 3 22E+00:! '? - nu.C!Li..de i.s l)a::;t o .f c.4.!l u n d !!!'texrtt iii ad so.J:u'i:.i.on Y' = l i
- J-e, .1. . y . 'l. i.~d:e--:.i:'
- r **:. -c ~ *..J ,. 17. '.
@ = n u c l ide co1lta i n ~ enr::1zg-..{ L i.n e ts .n o t used i n We :i.gh.ted .f..P.a:n .lD-.*crtiv it:y Exr o ;r.s quoted , t 2 . 000 s igma Pe 2 k ~ocace Performed on : 7/9/2015 7
- 35 ;* 37 AM Peak Locate rrom Channel : 50 Peak Locate ~o Channel : BJ_ 92
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Interference Corrected -~tivities Report Page 5 of~ Peak Energy Peak Size in Peak CPS No. (keV} Counts er Second % Uncertaint All peaks were identified. NOC DA REPO BT__ Detector Name*: 5456 Sample Geometry : Cribhouse 3m Sample Title ~ RFC012 Nuclide Li~~ary Used : C: \GENIZ2K\CAMFILES\Zion Lib- *BNL 1\JLB Report Genera~ed on~ 7/9/2015 7 : 35 : 38 AM Nuclide Energy Yield Line MDA Nuclide tlDA Acti.,i ty Dec . Level Name ( ke'T) ( ) (pCi/M" 2 ) (pCi/l-1"'2 ) (pCi/tl-"2 ) (pCi/ M"2 }
+ K- 40 1460.82* 10.66 4.983E+003 4.98E+003 3.4 21E+00 4 2.1 67 E+003 Cr-51 320.08 9.91 1.10 1E+013 1.10E+013 6.056E+012 4 . 8 70E+01 2 ~ln-54 834.85 99.98 2.18 1E+003 2 .18E+003 3.437E+002 9. 0 45 E+00 2 Co-58 810.76 99.45 1.703E+0 06 1.70E+00 6 8.05 0E+004 7. 063E+005 Co-60 1173. 23 9 9.85 4.432E+002 3.09E+002 7.594E+001 1. 791E+002 1332.49 99.98 3.093E+002 4.16 4E+001 1. 0 96E+00 2 Nb-94 702.65 99.81 3. 113E+002 2.38E+002 ..-2.860E+001 1.315E+002 871. 09 99. 89 2 .377E+0 02 1. 2 37E+00 1 9.209E+001 Sn-113 255.13 2.11 2.038E+006 6.98E+004 .-1. 22 9E+00fi 8. 7 73E+005 391. 70 64.97 6.976E+004 ..-3.965E+004 2.922E+00 4 + Cs-134 475.36 1.48 3.372 E+004 7.55E+002 1. 5 2 4E+003 1. 3 82E+0 0 4 563.25 8.34 7.207E+003 l.514E+003 3.018E+0 03 56 9 .33 15.37 2 . 8 32E+003 ..-3. 979E+003 1. 09 7E+0 03 604. 72* 97.62 7 .553E+002 2.823E+003 3. 2 57E+002 795.86 85.46 8.30 4E+002 .-5.398E+001 3.478E+00 2 801.95 8 .6 9 5.909E+003 ..-2.091E+003 2.28 9E+003 1038.61 0.99 7.355E+004 ..-7.69 7E+0 03 3.015E+004 11 67 .97 1. 79 3 .083E+004 7.1 60E+0 02 1 .154 E+004 1365 .19 3.02 1. 7 01E+004 6. 8 70E+0 02 6.0 27E+003 Cs-137 661.66 85.10 3. 905E+002 3 . 91E+002 3 . 425E+0 01 1. 661E+002 Eu-1 52 121.78 2 8.67 1. 283E+003 1. 11E+003 r-l. 72 5E+001 5.969 E+002 244.70 7 .61 4.667E+003 r-1. 802E+00 2 2 .119E+003 295.94 0. 45 9 . 907E+00 4 6 . 436E+00 4 4. 554E+0 0 4 344.28 26.60 1.108E+003 1. 2 47E+001 4. 81 6E+002 367 . 79 0. 8 6 3 . 919E+004 1.99 6E+003 l. 729E+0 04 411. 1 2 2 . 24 1 .3 97E+00 4 - 6 . 339E+003 6 . 047E+0 03 443. 96 2.8 3 1 .111E+00 4 3 . 290E+001 4 . 783E+00 3 488 . 68 0 .4 2 5 . 2 81E+004 2. 014E+003 2.0 95E+00 4 563.99 0.4 9 5.552E+ 004 -l.1 0 9E+004 2 . 276E+0 04 586 .26 0. 4 6 6. 703E+004 - 5 .3 63E+0 03 2 .807 E+004 678. 62 0 .4 7 5.05 2E+ 004 -3 . 365E+00 4 l. 957E+00 4 688 .67 0 .86 4 . 05 4E+00 4 1. 047E+ 004 1.712E+00 4 71 9 . 35 0 . 28 9 . 592E+00 4 l.0 97E+00 4 3.806E+0 04 778.90 12 . 96 2. 45 7E+003 - 2 . 5 13E+002 1. 007E+00 3 810 .4 5 0 . 32 9.4 95E+ 004 - 3 .3 66E+004 3 . 837 E+ 00 4 867. 37 4. 2 6 6 . 871E+003 2 .358E+002 2 .726E+ 003 n 9 . 33 0. 43 9 . 366E+004 4 . 785E+00 4 3 . 955E+00 4 964 . 08 14 . 65 2 . 678 E+ 003 >- 3 .7 06E+ 002 1.12 2E+003 1085.8: 10 . 24 2.260E+0 03 r-4.86 7E+ 002 8 . 006E+002 1089 . 74 1. 7 3 1.733E+004 3 . 24 6E+00 3 6 . 713 E+ 00 3
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Nuclide MCA Report Page 6 -~ 7 Nuclide Energy Yield Line UDrl Nucl i de MD.1. Acti*rity Dec. Le*.;,el Name ( ke'.') ( ) (pCi/U2 ) (pCi/W'2 ) (pCi/M"2 ) (pCi/1-1'2 ) 1112. 07 13.69 2.211E+003 i-3.221E+002 8 .565E+002 1212.95 1. 43 3.u68E+004 8.336E+003 l.285E+004 Eu-152 1249.94 0.19 l.847E+005 l.11E+003 5.142E+004 7.328E+004 1299.14 1.63 2.004E+004 5.005E+003 7.763E+003 1408. 01 21.07 l.613E+003 -1. 846E+002 6.248E+002 1457.64 0.50 9.556E+004 -5.543E+004 4.002E+004 1528.10 0.28 1. 263E+005 4.206E+004 4.893E+004 Eu-154 123. 0-:' 40. 40 9.943E+002 5.39E+002 -5.299E+OOO 4.629E+002 247.93 6.89 4.641E+003 -l.823E+003 2.065E+003 591.76 4.95 4.842E+003 6.046E+002 l.875E+0 03 692.42 1. 78 l.124E+004 -7.266E+003 3.984E+003 723.30 20.06 l.645E+003 6.533E+002 6.742E+002 756.80 4.52 8.653E+003 2.235E+003 3.655E+o03 873.18 12.08 5.386E+002 O.OOOE+OOO O.OOOE+OOO 996.29 10.48 3.680E+003 --6.389E+002 l.508E+003 1004.76 18.01 2.019E+003 4.653E+002 8.159E+002 1274.43 34.80 8. 923E+002 i-?.253E+002 3.340E+002 1596.48 1. 80 l.688E+004 3.636E+003 5.981E+003 Eu-155 45.30 1. 31 2.958E+004 l.86E+003 9.473E+002 1.333E+004 60.01 1.22 5.633E+004 6.065E+003 2.660E+004 86.55 30.70 1.864E+003 i- 7 .996E+002 8.797E +002 105.31 21.10 2.468E+003 2.264E+002 l.158E+0 03 Tl-208 583.19 85.00 5.409E+002 5.4 1E+002 3.597E+002 2.445E+002
+ Bi-211 351.07* 13.02 2.882E+003 2.88E+003 5.18 7E+003 l .309E+003 Pb-211 404.85 3.78 8.093E+003 7.20E+003 l.66 2E+003 3 .559 E+003 427.09 1. 76 1. 442E+004 5. 962E+002 6. 134E+003 832.01 3.52 7.203E+003 -1. 786E+003 2.858E+003 Bi-212 3~.86 1.06 2.163E+Q04 4. 31E+003 '""2.352E+002 9.540E+003 727. 33 6.67 4.314E+003 l.071E+003 1.789E+003 785.37 1.10 2.564E+004 -2.744E+003 l.051E+004 1620.50 1.47 2,603E+004 1.107E+004 1. 052E+004 Pb-212 115 .18 0.60 5.572E+004 l.08E+003 - 3 .116E+004 2.596 E+004 238.63 43.60 1. 083E+003 l.296E+003 5.091E+002 300.09 3.30 9.256E+003 2.270E+003 4.146E+003 Pb212-XR 74.8 2 10.28 5.898E+00 3 2.82E+003 8.103E+003 2 .832E+003 7 7 .11 17.10 2.821E+003 2 . 119E+002 1. 341E+0 03 87.35 3.97 1. 010E+004 3.538E+003 4.765E+003 89.78 1. 4 6 2.541E+004 -l.611E+003 l .1 93E+0 04 + Bi-214 609.32* 45.49 7.214E+002 7.21E+002 2 .6 96E+003 3. 111E+002 768.36 4 .89 6.346E+003 l.936E+003 2.658E+003 806.18 1. 26 1.978E+004 2 .565E+003 7.848E+002 934.06 3 .11 l.243E+004 4.126E+003 5.32 1E+003 1120 . 29 14.92 3.823E+003 1. 974E+003 1. 709E+003 1155. 21 1. 63 2.087E+004 1. 142E+003 8.555E+003 1238.12 5.83 7.566E+003 3 .517E+003 3.239E+003 128 0 .98 1. 43 1. 789E+004 -4.154E+002 6.695E+003 1377 .67 3.99 9.837E+003 4.960E+003 4.080E+0 03 1385.31 0.79 4.100E+004 5. 473E+003 1.627E+0 0 4 1401. 52 1. 32 1. 743E+004 -2 . 346E+003 6 .17 5E+003 1407.99 2.39 1.256E+004 ,-1.960E+003 4.864E+003 1509.21 2.13 1. 469E+004 4.890E+003 5.689E+0 03 1661.2 7 1.05 2.833E+004 :!..9 74E+00 3 1. 0 61E+004 1729.59 2.88 1.285E+004 4.902E+003 5.100E+003 + Bi-214 17 64 .49 15.30 4.290E+003 7.21E+002 2 .9 39E+00 3 1. 89 2E+f')03
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Nuc1ide MDA Report Page 7 -~ 7 Nuclide Energ~* Yield Line MDA Nuclide l1DA Acti,rit~* Dec. Le,:el Name (keV) ( :; ) (pCi/M"2 ) (pCi.'H2 ) (pCi/H"2 ) (pCi/11"2 ) 1847.43 2.03 l.552E+004 -3.605E+002 S.810E+003 > 2118. 51 1. 16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO
+ Pb-214 241. 99 7.25 4.705E+003 l.05E+003 8.200E+002 2.155E+003 295.22 18.42 2.173E+003 1. 571E+003 l.001E+003 351.93* 35.60 l.055E+003 l.899E+003 4.792E+002 785.96 1.06 2.962E+004 2.518E+003 1. 240E+004 Pb214-::R 74. 82 5.ao 1.046E+004 4.98E+003 1. 438E+00 4 5.024E+003 77 .11 9.70 4.979E+003 3.739E+002 2.367E+003 87.35 2.24 l.792E+004 6.278E+003 3.454E+003 89.78 0.82 4.529E+004 ..-2.872E+003 2.127E+004 Ra-226 186.21 3.64 9.081E+003 9.08E+003 5.207E+003 4.192E+003 Ac-228 129.07 2. 42 l.497E+004 1. 80E+003 3.138E+003 7.009E+003 209.25 3.89 7.063E+003 ..-J.948E+00 1 3.187E+003 270.24 3.46 8.690E+003 O.OOOE+OOO 3.908E+003 328.00 2.95 8.370E+003 -1.650E+00 3 3.622E+003 338.32 11.27 3.163E+003 7.124E+ 0 02 l.432E+003 409.46 1. 92 1. 295E+004 l.217E+ 0 03 5.507E+003 463.00 4.40 7.053E+003 6.101E+002 3.079E+003 794.95 4.25 7.756E+003 2.582E+003 3.276E+003 911. 20 25.80 1.804E+003 9.469E+002 7.958E+002 964. 77 4.99 6.951E+003 1. 159E+002 2 . 911E+003 968. 97 15.80 3.104E+003 l.782E+003 l.373E+003 1588.20 3.22 l.OOOE+004 l.041E+003 3.874E+003 Pa-231 27.36 10.30 2.646E+003 2.65E+003 9.232E+002 l .192E+003 283.69 1. 70 l.618E+004 -9.861E+ 002 7.179E+003 300.07 2. 47 1. 237E+004 3.033E+003 5.539E+003 302.65 2.20 1. 419E+004 4.940E+003 6.368E+003 330.06 1. 40 l.713E+004 -5.209E+003 7.377E+003 Th-234 92.38 2.13 1.997 E+015 2 .00E+015 4.283E+014 9.431E+014 92.30 2.10 2.045E+015 5.385E+014 9.663E+014 112. 81 0. 2 1 1. 776E+016 -5.222E+Ol 4 8 .316E+015 U-235 143.76 10 . 96 2.673E+003 6.18E+002 - 5 .767E+002 l.230E+00 3 163.33 5.08 5.740E+003 1.817E+003 2.631E+003 185. 71 57.20 6.184E+002 4.794E+002 2.871E+002 202 .11 1.08 2.211E+004 -1. 313E+004 9.835 E+0 03 205.31 5.01 5.434E+003 -l.174E+003 2.452E+003 Am-241 59.54 35.90 l.264E+003 1. 26E+003 -4.081E+002 5.943E+002 + = Nuclide identified during the nuclide identification * =' Energy line found in t he spectrum > MD.A '!alue not calculated @ Half-life too short to be able to perform the decay correction
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Page 2 of 7 GAMM A .., P E C T R U M ~ .. N A L Y S I S Filename: C:\GENIE2K\CAMFILES\RWC013.CNF Report Generated On 7/9/2015 7:36:35 AM Sample Title RWC013 Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels): 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance: 10.000 keV Sample Size
- 2.827E+001 M"2 Sample Taken On 1 /28/2013 12:00:00 PM Acquisition Started 6/29/2015 12:31:20 PM Live Time 600.0 seconds Real Time 600 .7 seconds Dead Time 0 .12 %
Energy Calibration Used Done On 1 /27/ 201 5 Efficiency Calibration Used Done On 7 /8/201 5 Efficie ncy ID CRIB HOUSE 3M [137]
Page 3 of 7 Report Date: 7/9/2015 7:36:35 AM Sample
Title:
RWC013 Peali Analysis Performed on: 7/9/2015 7:36:34 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak !ROI ROI Peak E,nergy FWHM Continuum No. start end !Centroid {keV) {keV) Counts 1 80 87 83.49 20.56 0.83 2.809E+001 2 296 307 300.31 74.81 0.62 2.304E+00 2 3 2431 2445 2439.80 609.86 0.61 1 . 313E+001 4 5838 5857 5847.44 1461.17 0.98 1. 266E+001 Da.r..!t *Orange = F.i rs t peak. .i.ifl. a 1Rt.1.l ti.p1t.1 \'. .1:eg.i cn Green ; F;.i t:t.ed s .i.og.l.et Errors quoted at 2.000 sigma u I EI ENTIFIC TION EPIRT Sarnple
Title:
RWCC 12; Nuclide Library Used. C:1;GEN~E2K\CAMFILES\Zton Lib-BNL.NLB Report Generated: 7f9/2015 7:36:35 AM Nuclide Id IDENTIFIED NUCLI DES Energy Yield
* * * * *
- II Activ ity Ac t i vit:,
]
Name Con fidence (keV) ( ) (pCi/MA2 ) Uncertainty
-~ * *4 0 ~-. 000 :..t.50. 5 ? * 'l O . 56 3. 3S.1 ? *:.:(c1 00~ '/. l. £ t.& /~ *1*0 0J Cs-1 34 0.3 8 7 475.36 1. 48 563.25 8.34 56 9.33 15.37 6C 1 . *n,i S'i. 52 2. ::::37:i. 0:i~'-003 e. l263.?.F:*i*0 02 795.86 85 .46 801. 95 8 .69 1038.61 0.99 11 67.97 1. 79 13 65.19 3.02 B:' **T : 4. l 000 SOS.3?. t -'~>>. IJS ?.
- 2 3 2.1 :B+0 C::l 7 . '7 5.3?. 9F; -~0 0 2 768. 36 4.8 9 8 0 6 .18 1. 2 6 93 4 . 06 3 .11 1120. 2 9 14 . 92 11 55. 2 1 1. 63 1238 . 12 5. 83 12 80. 98 1.43 1377. 67 3 .9 9 1385 . 31 0. 79 14 01.52 1. 33 1407 . 99 2 . 39 1 509 . 21 2 .1 3
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Interference Corrected - tivities Report Page 4 of~
- Nuclide Id Energy rYield ~ctivity ~ctivity Name Confidence (keV) ( %) (pCi/M"'2 ) Uncertaintv 1729.59 2.88 1764.49 15.30 1847.43 2.03 2118.51 1.16 T':h **:231 0 . 933 .:./5 . 64 14 10 4 . 2.'H;8;3£,+00 1 .. 861!f0E~ !lt:l 84 . 21* Iii, 6(} 6 . 4143:3E+OO 6 . 95024E+OD 89.95 1.00
- .-: ~ I.;r .~ ....r;,~y .l:.:..i..:1 ~
.-..0. L~c.1. ~ i \ ..:~~ -~*~~c-:...'!~.;.:l :,, * @ = Energy line not used for Weighted ~lean ActiTrit:, = Nuclide was corrected for parent/daughter Energy Tolerance: 10.000 ke" Nuclide confidence index threshold - 0.30 Errors quoted at 2.000 sigma T RFERENCE C EC ED REPO Nuclide Nuclide Wt mean Wt mean Name Id Confidence Activity (pCi/M"'2 ) Activity Uncertainty K-40 1. 000 3.384212E+004 7.164973E+003 ? Cs-13 4 0.387 2. 3 379981iH*003 0 .126320IH*0 02 ? Di -214 1.000 2.232283E+ C03 7. 76329,1E+ 002 - .. :F: . 2 .31 C f,J,~'."
Th-231 0.933 4.385568E+003 1.816486E+003
? = nucJ.ic.i.e i.s pt<lrt. o:i: an u n d..etei~i,~i .ned sol ution ;r,;_ ci.i .de, .*f-i} t .:t .d. .b:_T * .ht:! .;.,., * .r.ferunce _n* .L}':>l.. @ -- :u.::.c.1.i.de con*cc i n R ene 1:gy 1.ines no t used i.n Wa i ght.ed Mean l i.cti v ity IED P -A- -
Peak Loca ce Performed on
- 7/9/2 015 7 . 36 : 34 AM Peak Locate From Channel : 50 Peak Locate To Channel ; 8192 Peak Energy Peak Size in Peak CPS No. keV Counts er Second % Uncertaint All peaks were identified.
ORT De t ector Name:. 5-156 Sample Geometry : Cribf'ouse 3m Sample Title : RWC013 [139]
Nuclide MDA Report ,ge 5 of 7 'Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Report Generated o n: 7/9/2015 7:36:36 AM Nuclide Energy Yield Line MDA Nuclide MDi-i _i:.cti vi t:* Dec. Lev el Name (keV) ( ) (pCi/M"2 ) (pCitM' 2 ) ,pCi/H"2 ) (pCi/tl"2 )
+ K-40 1460.82* 10.66 5.925E+003 5.92E+003 3.384E+004 2.638E+003 Cr-51 320.08 9.91 9.404E+012 9.40E+012 c-l,444E+012 4.069E+012 t-1n-5.J 834.85 99.98 1.938E+003 1.94E+003 -1. 031E+002 7.833E+002 Co-58 810.76 99.45 l.513E+006 1. 51E+006 -4.425E+005 6 .113E+005 Co-60 1173.23 99.85 3.774E+002 3.09E+002 3.928E+001 1.462E+002 1332.49 99.98 3.093E+002 -B.744E+001 1.096E+002 Nb-94 702.65 99.81 1.315E+002 1.32E+002 r-l.340E+002 4.158E+001 871.09 99.89 2.377E+002 2.474E+001 9.209E+001 Sn-113 255 .13 2 .11 2.666E+006 9.84E+004 r-3,921E+004 1.192E+006 391.70 64.97 9.841E+004 3.662E+004 4.354E+004 + Cs-134 475.36 1. 48 3.742E+004 7.48E+002 -1. 460E+004 1.567E+004 563.25 8.34 7.843E+003 4.324E+002 3.337E+003 569.33 15.37 4.107E+003 -5.718E+002 1.735E+003 604.72* 97.62 8.803E+002 2.337E+003 3.882E+002 795.86 85. 46 7.482E+002 r-l.424E+002 3.067E+002 801. 95 8.69 6.449E+003 r-2.460E+002 2.559E+003 1038.61 0.99 4.548E+004 -2.939E+004 1. 611E+004 1167.97 1. 79 3.754E+004 r-l.561E+004 1. 490E+OO<!
1365.19 3.02 2.200E+004 1.374E+003 8.524E+003 Cs-137 661. 66 85.10 3.233E+002 3.23E+002 r-7,843E+001 1.325E+002 Eu-152 121. 78 28.67 1.360E+003 1.23E+003 1.296E+002 6.354E+002 244.70 7.61 4.731E+003 r-8.406E+002 2.151E+003 295.94 0.45 9.4B3E+004 3.215E+004 4.342E+004 344.28 26.60 1. 229E+003 3.235E+001 5.420E+002 367.79 0. 86 2.970E+004 r-7.032E+003 1. 254E+004 411.12 2.24 1.353E+004 3.179E+003 5.827E+003 443.96 2.83 1.182E+004 2.138E+003 5.138E+00 3
'3/488.68 0.42 7_017E+004 r-l.007E+002 2 . 963E+004 563.99 0.49 7.437E+004 2.086E+004 3.218E+004 586.26 0.46 6.382E+004 -2.2 2 5E+004 2.647E+004 678.62 0.47 6.673E+004 -1. 945E+004 2.767E+004 688.67 0.86 3.878E+004 3.879E+002 1.624E+004 719. 35 0.28 1.327E+005 -2.012E+004 5.645E+004 778.90 12.96 2.145E+003 -3.191E+002 8.512E+002 810.45 0.32 1.068E+005 4.671E+004 4.430E+004 867.37 4 .26 9.129E+003 1.B7 4E+003 3.856E +003 91 9 .33 0.43 7.0 49E+004 6.183E+003 2.797E+004 964.08 14. 65 2.267E+003 r-l.8 08E+002 9.159E+002 1085.87 10.24 2.923E+003 r-2. 433E+002 1.132E+003 1089.74 1. 73 1.733E+004 r- 2 .164E+003 6.713E+01)3 1112. 07 13.6~ 2.413E+003 r-6. 443E+001 9. 57 6E+002 1212.95 1.43 2.414E+004 r-8, 285E+002 9.577E+003 Eu-152 1249.94 0.19 1.987E+005 1. 23E+003 2 .113E+004 8.028E+0 0 4 1299.14 1. 63 1. 796E+004 r- 2 .781E+002 6. 72 3E+ 003 1408.rJl 21.07 2.016E+003 6.954E+002 8.2 65E+002 1457 .64 0.50 7 . 5 18E+004 -3.907E+004 2.983E+004 1528.10 0.28 9.765E+004 1.446E+004 3.460E+004 Eu-154 123.0., 40. 40 l.00 9E+003 6.10E+002 l.932E+00 2 4.703E+0 02
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Nuclide MDA Report Page 6 ~- 7 Nuclide Energ:,* Yield Line tlDA Nuclide t-1DA Acti,.'ity Dec. Le,,el Name (ke") ('~) (pCi/t-1"2 ) (pCi/L1"2 ) (pCi/U"2 ) (pCi/H"2 )
'L.47.93 6.89 5 .170E+003 - 1. 007E+003 2.329E+003 591. 76 4.95 6.053E+003 - 1 .583E+0 03 2.481E+003 692.42 1. 78 l.708E+004 2.472E+003 6.900E+003 723. 30 20.06 1. 545E+OOJ -3.01 ?.F'.+00?. 6.242E+002
- 56.80 4.52 7.459E+003 -l. 881E+o03 3.058E+003 873.18 12.08 2.143E+003 -7.464E+002 8.021E+002 996.29 10.46 2.638E+003 4.288E+002 9.874E+002 1004.76 18.01 2.150E+003 5. 420E+002 8.812E+002 1274,43 34.80 6.099E+002 .-1. 243E+002
- 1.928E+002 1596.48 1. 80 1.957E+004 5. 454E+003 7.325E+003 Eu-155 45.30 1. 31 3.230E+004 l.91E+003 .-9.552E+003 1. 469E+004 60.01 1. 22 4.406E+004 .-9.530E+ 00 3 2.047E+004 86.55 30.70 l.910E+003 ,-,J,574E+0 02 9.025E+002 105.31 21.10 2.233E+003 -1. 142E+003 1.040E+003 Tl-208 583.1(,j 85.00 5.875E+002 5.88E+002 5.741E+002 2.678E+002 Bi-211 351.07 13.02 3.166E+003 3.17E+003 l.360E+003 1. 451E+003 Pb-211 40<1.85 3.78 7.686E+003 7.69E+003 ,-1, 2 9 6E+O 03 3.355E+003 427 .. 09 1. 76 1. 496E+004 -6.525E+003 6.407E+003 832.01 3.52 9.156E+003 1. 709E+003 3.835E+003
. Bi-212 39.86 1. 06 2.260E+004 4.31E+003 -1. 073E+004 l.003E+004 727. 33 6.67 4.314E+003 3.568E+002 1. 789E+003 785.37 1.10 2.238E+004 -6.829E+002 8.881E+003 1620.50 1.47 l.987E+004 2.922E+003 7.436E+003 Pb-212 115 .18 0.60 5.814E+004 1. 05E+003 4. 722E+003 2. 717E+004 238.63 43.60 l.046E+003 7.052E+002 4.901E+002 300.09 3.30 9.420E+003 3.184E+003 4.2 28E+003 Pb212-XR 74.82 10.28 5.782E+003 2 .53E+003 4.664E+003 2 .774 E+003 77 .11 17.10 2.529E+003 ,-4.031E+002 1.195E+003 87.35 3.97 1. 049E+004 .-1.764E+003 4.962E+003 89.78 1. 46 2.859E+004 6.139E+003 l.352E+004 + Bi-214 609.32* 45.49 8.409E+002 8.4 1E+002 2.232E+003 3.708E+002 768.36 4.89 7.893E+0 03 3 .687E+003 3.431E+003 806.18 1. 26 1. 812E+004 ,-l.886E+003 7.020E+003 934.06 3.11 l.150E+004 3.103E+003 4.857E+003 1120.29 14.92 3,526E+003 1. 799E+003 l.560E+003 1155. 21 1. 63 1.960E+004 6.081E+003 7.920E+003 1 238 .12 5.83 6.698E+003 '-1.574E+003 2.805E+003 1280.98 1.43 2.343E+004 4.569E+003 9 .4 68E+003 1377.67 3.99 9.310E+003 3.100E+002 3.816E+003 1385.31 0.79 3.757E+004 6.842E+003 l.455E+004 1 401.52 1. 33 2.254E+004 7.508E+003 8.733E+003 1407.99 2.39 1. 570E+004 3.920E+003 6.435E+003 1 509.21 2 .13 1. 316E+004 -3.057E+002 4.926E +003 1661. 27 1.05 7.122E+003 O.OOOE+OOO O.OOOE+OOO 1729.59 2.88 1. 1 78E+004 3 .922E+003 4 .5 62 E+003 + Bi-214 1764.49 15.30 4.846E+003 8.41E+002 3.736E+003 2 .1 71E+003 1847.43 2.03 l .061E+004 -5.407E+003 3.354E+003
- .> 2118. 51 1.16 O.OOOE+OOO O.OOOE+OOO O.O OOE+OOO Pb-214 241.99 7.25 4. 916E+003 l.35E+003 4.02 7E+002 2.260E+003 295 . 22 18 .4 2 2.320E+003 2 .043E+003 l.074E+003 351. 93 35.60 1. 351E+003 1.592E+003 6 . 271E+002 78 5. 96 1.06 2 . 330E+004 -5.3 32E+003 9.246E+003 Pb214-XR 74.82 5.80 l.026E+004 4.46E+003 8. 276E+003 4 .9 22 E+003 77 .11 9.70 4.463E+003 - 7 .113E+002 2 .10 9E+003
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Nuclide MDA Report Page 7 ' - 7 Nuclide Energy Yield Line HOA Nuclide rmA Activity Dec. Le*:el Name (ke~_') ( ) (pCi/IviA2 ) (pCi/W2 ) (pCi,'W'2 ) (pCi/rI"2 ) 87.35 2 . ;;> ~ 1..861E+004 >-3.130E+003 B.803E+003
- 89. 75 0.82 5.095E+004 1. 094E+004 2.410E+004 Ra-226 186.21 3.64 1. 02oE+004 1. 03E+004 7.333E+003 4. 7 31E+ 003 Ac-228 129.07 2.42 1. 224E+004 2.00E+003 >-2 . 043E+003 5.645E+003 209.25 3.89 8.974E+003 5.514E+003 4 .143E+003 270.24 3.46 9.773E+003 l. 54 7E+003 4.44SIE+003 328.00 2.95 1.021E+004 1. 291E+003 4.540E+003 338.32 11.27 2.656E+003 8.291E+002 1. 179E+003 409.46 1. 92 1.479E+ 004 2.736E+003 6.431E+003 463.00 4.40 7.243E+003 2.345E+003 3.174E+ 003 794.95 4.25 ?.756E+003 1.670E+003 3.276E+ 003 911. 20 25. 80 2.001E+003 7.750E+002 8.944E+ 0 02 964.77 4.99 6.951E+003 l.993E+003 2. 911E+003 968.97 15. 80 3.035E+003 2.321E+003 1.339E+003 1588.20 3.22 1.000E+004 2.185E+003 3.874E+003 Pa-231 27. 36* 10.30 2.861E+003 2.86E+003 5.800E+003 1.300E+003 283.69 1. 70 1.982E+004 4. 2 40E+003 9.000E+003 300.07 2.47 1.259E+004 4.253E+003 5.648E+003 302.65 2.20 1.010E+004 5.402E+003 4.326E+0 03 330.06 1. 40 2.022E+004 -l.504E+003 8.91 8E+0 03 Th-234 92.38 2.13 1.974E+Ol5 1.97E+Ol5 6. 72 8E+014 9.321E+014
- 92. 80 2.10 2.013E+015 9. 110E+014 9.504E+0 1 4 112. 81 0.21 1. 762E+016 6.309E+015 8.247E+015 U-235 143.76 10.96 2.780E+003 6.48E+002 >-3. 076E+00 2 l.284E+003 163.33 5.08 5.991E+003 2 . 014E+O(J3 2.756E+0 03 185. 71 57.20 6.479E+002 3.203E+002 3.018E+002 202. 11 1.08 2.423E+004 1.427E+003 1. 089E+004 205.31 5.01 6. 144E+ 003 2.434E+003 2.807E+003 Am-241 59.54 35.90 l.12 1E+003 l.12E+003 9.433E+ 0D1 5.227E+002
+ = Nuclide identified during the nuclide identification * = Energr line found in the spectrum > = rmA **alue not calculated @ = Half-life t oo s h ort to be able t o perform the decay correction
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Page 2 of 7 GAMM A :.., P E C T R U M I. L N A L y s I s
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Im .~m.U tt)Y , Filename: C:\GENIE2K\CAMFILES\RWC014. CNF Report Generated On 7/9/2015 7:47:24 AM Sample Title B3-08101AF-RWC-014-GM Spectrum Description Sample Identification Sample Type Sample Geometry Cribhouse 3m Peak Locate Threshold : 3.00 Peak Locate Range (in channels) : 50 - 8192 Peak Area Range (in channels) : 50 - 8192 Identification Energy Tolerance: 10.000 keV Sample Size
- 2.827E+001 MA2 Sample Taken On 1/28/2 013 1 2:00: 00 PM Acquisition Started 6/25/2015 12:48:39 PM Live Time 1000. 0 seconds Real Time 1000.9 seconds Dead Time 0 .09 %
Energy Calibration Used Done On 1 /27/2 01 5 Efficiency Calibration Used Done On 7 / 8 /2 015 Efficie ncy ID CRIB HOUSE 3M [143]
Page 3 o f 7 Report Date: 7/9/2015 7:47:24 AM Sample
Title:
B3-08101AF-RWC-014-GM Peak: Analysis Performed on: 7/9/2015 7:47:23 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 P E A K A N A L Y S I S R E P O R T Peak ROI ROI Peak !Energy FWHM Continuum No. start end c entroid (keV) (keV ) rounts 1 297 306 301.51 75.11 1.0 4 3.027E+002 2 948 960 955.45 238.69 0.77 1.068E+ 0 02 3 1176 1186 1180.79 295.05 0.69 4.96 7 E+001 4 1402 1415 1408.02 351. 88 0.88 3.757E+001 5 2430 2446 2438.18 609.45 1.29 2.351E+001 6 5836 5857 5846.60 1460.96 1. 30 1. 32 7 E+001 7 7058 7069 7063.73 1764.77 0.47 4 . 558E+000 Dark O:.t:*11.mga = F.i.7.*!l t. pe~k :u1 a. Jlt ill. t::i.pl.et :r.egi.tm Green= Fitted si-nglet Errors quoted at 2. 000 sigma UCI D ID T FIG TIIN PORT IDENTIFIED NUCLIDES . . . . . .. .. Nuclide Id Energy Yield Ac ti"it:* Act i *Ji ty Name Confidence {keV) (' ) (pCi /t-1" 2 ) Uncertaint:* X***IJ.C 'l. . 000 11160. G?.-' 1 0. G6 IJ . "i. } 99 S:O,-;- OCI~ S. J530C.I!:-, 0 0.3 Bet *-:1.Z>>3 0.3~2 '?S. 5:1. :-: ?. . :iJ *;.. cg~2::,;e+oo~1. l . $SO)*_ s::- ~-~C {I
- 81. DO 32 .90 276 .4 0 7.1 6 3C?. 9:i ** l .:: . 3 4: r . ?,GSlAl -+ J03 i.
- l 01J J,:;.;*OJ3 3 ."i5.0 ~. !t- G2.0 j : . . H ,?.J :j'Z1 CO:J ~i . 2. SSS~::::+ CC2 383. 85 8.94 Pb- 2 12 0 . 997 115.18 0. 60
.2 J g . 53 ~ 1, 3. SC I . !1S56/H:+:)02 5. i~30!)i:i1\*,' 00-"
- Jcr.. cs,,, 3.J0 G.C08iO&.; OQ3 s . ?.33t:Vi:r:*.oo:::
- L> *?H :; . OOJ f>OS . 3 ~ ~ /JJ. 1,. 9 ?.
- 1 ,~11?'n ;* "ooJ s :r:1os;;,-oc2 768.3 6 4 .89 8 06 .1 8 1. 26 934. 0 6 3. 11 1120 . 29 14. 92 1155 . 2 1 1. 63 1238.12 5. 83 1280 . 98 1. 43 1377.6'7 3 . 99 1385. 31 0 . 79
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- Interference Corrected P -*-tivi ties Report Page 4 of ...
NucJ,ide Id !Energy !Yield ~ctivity A.ctivity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty 1407.99 2.39 1509.21 2.13 1661. 27 1.05 1729.59 2.88 1 "l't,4 . 49* l :":. 30 2. -4011~.E-H,O :1 . .l0l65E-Hm 1847.43 2.03
..,, . . .. 2118.51 1.16 '* .. - ~- . ' @ Energr line not used for Weighted Mean Activity NucliJe was corrected for parent/daughter Energy Tolerance : 10.000 keV Nuclide confidence index threshold 0.30 Errors quoted at 2.000 sigma IN ER E E CE C EC ED R PO T Nuclide Nuclide Wt mean Wt mean Name Id Confidence Activity (pCi/Ml\2 ) Activity Uncertainty K-40 1.000 4.118892E+004 6.363078E+003 Ba-133 0.332 1.152883E+003 4.004 629E+002 'I{ C..:J -1 :l*.*, I ;3')0 "": (i, ~ _;~
{ I\i.-..:11 *- ~- ,*. ;;,:, *- Pb-212 0.997 7.542204E+002 5.402988 E+002 Bi-214 1.000 2.193155E+003 5.678780E+002
; >, ">h--~~4 .. .9 .; ~ ? = n u c l :i.d ,3 i.1:, p ,u 7i.: of a n nn det.e:..,uinac. sol ution
- c-_i.de- rsje---*ti0.:i b t'h.:, * .u **-:,:;i.fe?: nee a.11 1 .J.1..l
@ -- ~ -~c.i.:i.de conta.i .no e n e rgy line F- 11o t ,rn,,d i::! WaightGd Mean A.e tivity s
Pea!~ Locate l?erformed on : 7/9/2 015 7 : 47 : 23 AM Pea k Loca*te Froill Channel : 50 Peak Loca te To Channel : 8192 Peak Energy Peak Size in Peak CPS No. (keV) Coun ts er Second % Uncertaint All peaks were identified. DE MD REPO De;:ec;:or Name . 5456 [145]
Nuc1ide MDA Report r ge 5 of 7 Sample Geometry: Cribhouse 3m Sample
Title:
B3-08101AF-RWC-014-GM Nuclide Library Used: C: \GENIE2K\CAMFILES \Zion Lib-BNL ..NLB Report Generated on: 7/9/2015 7:47:24 AM Nuclide Energr Yield Line NOA Nuclide ~rnA ;;.cti "it:* Dec. Le"el Name (keV) C~) (pCi/M"2 ) (pCi/W2 ) (pCi/M"2 ) (pCi/t-1"2 )
+ K-40 1460.62*}; 10.66 3.691E+003 3.69E+003 ~ .119E+004 l.651E+003 Cr-51 320.08 9.91 7.872E+012 7 .87E+012 :.489E+012 3.592E+012 Mn-54 834.85 99.98 1.694E+003 1.69E+003 5.749E+002 7.36 5E+002 Co-58 810.76 99. 45 9 . 296E+005 9.30E+005 ~3.22 8E+005 3.810E+005 Co-60 1173.23 99.85 2.987E+0 02 2.40E+002 '- l .200E+002 1.239E+002 1332.49 99.98 2 .397E+002 9.979E+OOO 9.286E+001 Nb-94 702.65 99.81 2.465E+002 2,24E+002 2.681E+001 1.087E+002 8-1.09 99.89 2.235E+002 2.895E+001 9.571E+001 Sn-113 255.13 2 .11 2.279E+006 6.13E+004 -7.088E+005 1.057E+006 391. 70 64.97 6.133E+004 ~8.314 E+003 2.735E+004 Cs-134 475.36 1.48 2.862E+004 4.47E+002 ~2.098E+00 1 1.249E+004 563.25 8.34 5.511E+003 1.81 0E+003 2.4 06E+003 569.33 15.37 2.653E+003 '-1. 175E+003 l.136E+003 604.72* 97.62 7 .114E+002 2.237E+003 3.247E+002 795.86 85.46 4.473E+002 '-2.649E+002 1. 833E+002 801. 95 8.69 5.536E+003 '-2.02 2E+003 2.370E+003 1038.61 0.99 4.646E+004 '-5.399E+003 1. 927E+004 1167. 97 1. 79 3.222E+004 l.2 52E+ 004 1. 380E+004 1365.19 3.02 l,644E+004 2.973E+ 003 6.7 41E+003 Cs-137 661.66 85.10 2. 516E+002 2.52E+002 -6.83 0 E+0 01 1.083E+002 Eu-152 121. 78 28.67 1 .001E+003 6.64E+002 l.187E+002 4.735E+002 244,70 7.61 3 .386E+003 - 2 .94 8E+001 1.564E+003 295 .94 0.45 7.562E+004 8.168E+003 3 .542E+004 344.28 26. 60 6.643E+002 -1.60 3E+0 01 2 .88 8E+002 367.79 0.86 2.793E+004 5.184E+003 1. 258E+004 411.12 2.24 1. 00 1E+00 4 -6. 992E+002 4.441E+003 443.96 2.83 7.676E+003 -1.43 9E+003 3.375E+003 488.68 0.42 5.553E+004 4. 35 4E+003 2.449E+004 563.99 0.49 4.319E+004 1. 705E+003 1.860E+004 586 .2 6 0.46 5 .142E+004 O.OOOE+OO O 2.244E+004 678.62 0.47 5.227E+004 4 .119£+003 2 . 272E+004 688.67 0.86 2 .627E+00 4 3.315E+003 l.12 5E+004 719.35 0.28 9.6()4E+004 2.833E+004 4.208E+004 778 .90 12 . 96 2 .0 34E+003 1. 7 33E+002 8 . 84 1E+ 00L 810.45 0.32 6 . 063E+004 '- 5 .047E+003 2.485E+004 567. 37 4.26 4 .71 9E+003 4.378 E+002 1 . 934E+ 003 919 . 33 0 .4 3 5 . 373E+004 ~1. 53 1E+004 2.250E+00 4 964. 08 14.65 2.055E+003 3.644E+ 002 8 .969E+ 002 1085.87 1 0.2 4 2 .647E+003 4.013E+002 1.126E+00 3 1089.74 1. 73 1. 299E+004 8.343E+002 5 . 325E+ 003 111 2 . 07 13. 69 1.839E+003 2 .116E+0 02 7 . 7 04E+002 1212.95 1. 43 1. 752E +004 -6. 900E+0 02 7,264E+003 Eu-152 1249 .9 4 0 . 19 1.472E+005 6.64E+002 2 .703 E+004 6.215E+004 1 299 . 1 4 1. 63 1. 667 E+00 4 2 .9 18E+003 6.98 3E+003 1408.01 21.07 1.056E+003 7.650E+001 4.189E+002 1457 . 64 0. 5 0 7 .12 7 E+00 4 ~ :. .:54E+004 3 . 098E+004
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Nuc1ide MDA Report Page 6 o~ 7 Nuc.lide Energ:,* Yield Line tlDA Nuclide MDA Acti**it:* Dec. Le'.*el Name (ke'l) (,) (pCi,IW'2 ) {pCi / tJ"2 ) (pCi / l-1" 2 ) (pCi/M"2 ) 1528.10 0.28 6.788E+004 - l .577E+ 003 2. 541E+004 Eu-154 123.07 40.40 7.936E+002 7.46E+002 1.462E+O OO 3.76 3 E+ 002 247.93 6.89 3.603E+003 -1. 0 03E+0 0 3 1.648E+003 591.76 4.95 4.70,E+003 -3.392E+002 2.027E+0 03 692.42 1. 78 1. 816E+004 5.815E+00 3 B. 0 99E+ 003 723. 30 20.06 1.361E+003 6.161E+00 2 5.916E+ 0 02 756.80 4.52 7.155E+003 5. 0 62E+00 3 3.175E+ 0 03 873.18 12.08 2.246E+003 -B.651E+00 2 9. 616E+0 02 996.29 10.46 2.331E+0 03 3.673E+00 2 9.666E+ 0 02 1004.76 18.01 l.616E+003 5.579E+00 2 6.917E+ 0 02 1274.43 34.80 7.461E+ 002 -2.200 E+00 2 3.058E+00 2 1596.48 1. 80 l.012E+004 -6.811E+00 2 3.585E+0 03 Eu-155 45.30 1. 31 2.393E+004 1.34E+0 03 -9.584E+003 l.10 9E+004 60.01 1. 22 3.471E+ 0 0 4 9 .7 94E+00 3 1.642E+0 04 86.55 30.:0 l.338E+003 -1. 375E+00 3 6.37 4E+0 02 105.31 21.10 1. Bl9E+003 1. 968E+00 2 8.636E+ 002 Tl-208 583.19 '35.00 4.174E+002 4.17E+002 3.148E+002 1. 931E+ 0 02 Bi-211 351. 07* 13.02 2 .117E+003 2 .12E+ 0 03 4.648E+003 9 .791E+00 2 Pb-211 404.85 3.78 4. 611E+003 4.61E+003 ,-9.329E+002 2.0 13E+00 3 427.09 1. 76 1.193E+004 1. 151E+00 3 5 . 32 2 E+ 0 03 832 . 01 3.52 5.494E+003 9. 6 15E+002 2.301E+ 0 03 Bi - 212 39.86 1.06 1.972E+004 3 .75E+003 1. 476E+003 9.09 8E+003 727.33 6.67 3.750E+ 003 l.030E+003 l.654E+003 785.37 1.10 2.184E+004 5.12 2E+003 9.532E+003 1620.50 1. 4 7 1.330E+004 4.429E+003 5.15 2 E+003
+ Pb-212 115 .18 0.60 4.033E+004 8.3 9E+002 - 2 .12 9E+004 1. 903E+ 0 04 238.63* 43.60 8.386E+002 7. 5 66E+0 02 3.9 97 E+ 0 0 2 300.09* 3.30 8.174E+003 6.009E+003 3. 8 00E+0 03 Pb2 12-XR 74.82 10 .2 8 4. 35 8E+00 3 l.91E+003 4.797 E+0 03 2.1 09E+ 0 03 77 .11 17.10 l.914E+003 >-3.530E+00 2 9.15 3E+00 2 87.35 3.97 8.168E+003 6.653E+003 3. 914E+ 0 0 3 89.78 1. 4 6 1.995E+004 5.4 2 9E+00 2 9. 514E+ 0 03 + Bi-214 609. 32
- 4 5. 4 9 6 .820E+00 2 6.82E+002 2.1 4 4E+003 3. 113E+002 768.36 4. 8 9 5 .373E+003 >-6. 42 6E+002 2 .377E+0 03 806.18 1. 26 1.930E+004 3.876E+003 8.424E+0 0 3 93 4. 06 3.11 1. 02 9E+004 5.546E+0 03 4.60 8E+0 0 3 1120. 29 14. 92 3 . 0 51E+003 3.306E+003 l.404E+003 1155. 2 1 1. 63 1.872E+ 004 8 .131E+0 03 8 . 2 31E+ 0 0 3 1 238 .12 5.83 6. 2 63E+003 4.461E+003 2.80 5 E+ 0 0 3 1 280 .98 1. 4 3 2. 0 66E+004 8 .191E+00 3 8.98 2 E+003 1377.67 3 .9 9 7 . 710E+ 0 0 3 8. 2 4 6E+002 3.35 2 E+ no3 138 5 .31 0.79 2. 2 54E+004 -l.52 5E+00 3 8 .7 3 1E+003 1401. 52 1. 33 2 . 265 E+0 04 1.450E+0 0 4 9. R0 3E+ 003 1407.99 2.39 9.419E+ 00 3 3. 6 7 4 E+00 3 3. B61E+ 0 03 1509.21 2.13 1.03 5E+004 2.0 78 E+0 0 3 4.180E+ 0 0 3 1 661. 27 1.05 2.070E+004 4 . 2 6 4 E+00 3 8 . 2 15E+ 0 03 1 729 . 59 2. 8 8 5 .4 63E+0 03 5 . 14 BE+0 0 2 1. 93 5E+0 02
+ Bi-21 4 1764 .4 9* 15 . 30 1. 558E+00 3 6.82E+00 2 2.401E+0 0 3 6 . 2 7 4E+002 1 847 . 43 2.03 1.373E+004 1.16 2E+ 0 03 5. 6 92 E+ 003 I> 2 118. 51 1.1 6 O.OOOE+ OOO O .OOO E+ OOO O.OOOE+ OOO Pb-2 1 4 2 41.9 9
- 7.25 5 . 0 48E+003 7 . 75E+002 4. 554E+003 2 .40 6E+003 29 5. 22 **, 18.42 1.tJ 66E+003 1.078 E+ 003 6 . 81 5E+0 02 35 1. 93* 3 5 .60 7 . 749E+0 02 : . 7 0 2E+ 003 3 . 585E+ 002 785. 96 1.06 2.2 7 3E+0 04 9 . 6 6 4E+003 9 . 923E+ 0 03
[147]
Nuc1ida MDA Report Paga 7 of 7 Nu'?lide Energ:* Yield Line IJDA Nuclide t-IDA Acti *rit~* Dec. Level Name (keV) ( ) (pCi/il"2 ) (pC:i/M"2 ) (pCi,'M2 ) (pCihI"2 ) Ph214-XR 7 4. 8?. 5. 80 7.732E+003 3.38E+003 8. 511E+003 3.741E+003 77 .11 9.70 3.378E+003 r--l'i.229E+0 02 l.615E+ 00 3 87.35 2.24 1. 449E+004 l.180E+00 4 6.94 3E+003 89.78 0.82 3.557E+004 9.676E+002 1.696E+004 Ra-226 186.21 3.64 6.886E+003 6.891::+003 2.62 0J::+003 3.234E+ 0 03 Ac-228 129.07 2. 4 2 1.063E+004 1.60E+003 3.153E+0 03 5.033E+003 209.25 3.89 6.139E+003 3.252 E+003 2.B63E+003 270.24 3.46 6.373E+003 -5.461E+002 2.924E+003 328.00 2.95 8.204E+003 1 .332E+003 3.764E+003 338.32 11.27 2.1 0 7E+003 9.019E+002 9.637E+002 409.46 1. 92 9.129E+003 ~3.366E+ 0 03 3.985E+00 3 463.00 4.40 5.062E+003 7.321E+002 2.263E+003 794.95 4.25 5.374E+003 1. 837E+ 003 2.325E+003 911. 20 25. 80 l.597E+003 1.726E+003 7.348E+002 964. 77 4.99 5.753E+003 2.690E+003 2.538E+003 968. 97 15.80 2.199E+003 1.674E+ 003 9.923E+002 1588.20 3.22 5.377E+003 1. 499E+003 2.013E+003 Pa-231 27.36 10.30 2.106E+003 2.11E+003 3.569E+002 9.745E+002 283.69 1. 70 l.268E+004 2.961E+003 5.7 95E+003 300.07 2.47 9.388E+003 2.512E+003 4.307E+003 302.65 2.20 9.480E+003 4.831E+002 4.304E+003 330.06 1. 40 l.574E+004 9.700E+001 7.158E+003 Th-234 92.38 2 .13 l .307E+015 1. 31E+015 1. 469E+014 6 . 242E+014 92.80 2.10 l.343E+015 3.271E+014 6.415E+014 112. 81 0.21 1.128E+016 -2.275E+015 5.34 1E+015 U-235 143.76 10.96 2.317E+003 4.55E+002 1. 301E+002 l.095E+003 163.33 5.08 4.697E+003 8. 478E+ 0 02 2.205E+003 185. 71 57.20 4.546E+002 2.333E+002 2.140E+002 202. 11 1.08 l.925E+004 r-2.16 3E+002 8.896E+003 205.31 5.01 4.890E+003 9.505E+002 2.286E+003 Am-241 59 . 54 35 .90 8.233E+002 8.23E+002 2.848E+OO:::: 3.890E+002
+ Nuclide identified during the nuclide identification
- Energy line f ound in the spectrum NDA "alue not calculated Half-life too short t o be able to parform the decay correction
[148]
- GAMM A S P E C T R lJ M A NA L Y S I S *****
Filename: C:\GENIE2K\B308102\lJ1SE.CNF Report Generated On 9/26/2017 2: 4 6: 14 PM Sample Title B308102ASFJSM001GD Sample Description lJlSE Rl Sample Identification Sample Type Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 50 - 8192 Peak Area Range (in channels) 50 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 9/17/2015 2:09:13 PM Acquisition Started 9/17/2015 2:09:13 PM Live Time 600.0 seconds Real Time 601.2 seconds Dead Time 0 .20 % Energy Calibration Used Done On 1/27/2015 Efficiency Calibration Used Done On 9/26/2 0 17 Efficiency ID 3M TURBINE [149]
Peak Analysis Report 9/26/2017 2:46: 14 PM Page 2
- P E A K A N A L Y S I S R E P O R T *****
Detector Name: 5456 Sample
Title:
B308102ASFJSM001GD Peak Analysis Performed on: 9/26/2017 2:46:13 PM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Ne t Peak Net Ar ea Continuum No. start end centroid (keV) ( keV). Area Uncert. Counts 1 80- 86 83.23 20.50 0 .73 5.58E+001 39. 7 9 1 .26E+002 2 951- 959 955.86 238.80 0 .44 1. 56E+ 0 01 13.30 1 .34E+001 M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 000 sigma [150]
Interference Corrected ActiTTity Report 9/26/2017 2~46:14 PM Page 3
- N U C L I D E I D E N T I F I C A T I O N R E P O R T *** **
Sample
Title:
B308102ASFJSM001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncer tainty Pb-212 1.000 238.63* 43.60 3.05117E+005 2.64520E+005
*=Energy line found in the spectrum. @=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold 0.30 Errors quoted at 2. 000 sigma
[151]
Interference Corrected *...;ti vi ty Report 9/26/201 . 2: 46: 14 PM Page 4
- I N T E R F E R E N C E C O R R E C T E D R E P O R T *****
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2) Uncertainty Pb-212 1.000 3.051165E+005 2.645203E+005
? = Nuclide is part of an undetermined solution X Nuclide rejected by the interference analysis @ ~ Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2. 000 sigma ********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 9/26/2017 2:46:13 PM Peak Locate From Channel: 50 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 1 20.50 9.304SE-002 71. 27 M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma [152]
Nuclide MDA Report 2:46:14 PM Page 5
- N U C L I D E MD A REPORT *****
Detector Name: 5456 Sample Geometry: Sample
Title:
B308102ASFJSM001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV} ( %) (pCi/M"2 ) (pCi/M"2 } (pCi/M"2 } (pCi/M"2 ) K-40 1460.82 10 .66 3.962E+006 3.96E+006 1. 765E+006 1. 714E+006 Co-60 1173.23 99.85 1. 373E+005 1. 37E+005 9.332E+003 4.342E+ 00 4 1332.49 99.98 2.140E+005 -6.959E+004 8.012E+004 Nb-94 702.65 99.81 1 .342E+005 l.18E+005 2.167E+004 4.754E+004 871.09 99.89 1.178E+005 -8.002E+003 3.723E+004 Ag-108m 433.90 90.50 1.776E+005 l.62E+005 l.102E+004 7.175E+004 614.30 89.80 1. 620E+005 -2.007E+004 6.064E+0 0 4 722.90 90.80 2.271E+005 7.849E+004 9.175E+0 04 Cs-134 604.72 97.62 l.011E+005 1. 01E+005 3.433E+003 3.195E+004 7 95. 8 6 85.46 2.526E+005 1.075E+005 1. 021E+ 005 Cs-137 661.66 85. 10 2.159E+005 2.16E+005 1. 482E+ 004 8.565E+004 Eu-152 121.78 28.67 6.314E+005 5.74E+005 1. 835E+005 2.839E+005 344.28 26.60 5.740E+005 4.232E+004 2.353E+005 1408.01 21.07 7.174E+005 -1. 462E+0 05 2.268E+005 Eu-154 123.07 40.40 4.014E+005 4.01E+005 9.526E+0 0 4 l .781E+005 723.30 20.06 8.756E+005 -3.554E+005 3.392E+005 1274.43 34.80 5.186E+005 1. 11 7E+OOS 1. 838E+005 Eu-155 86.55 30.70 5.397E+005 5. 4 0E+005 -3. 053E+0OS 2.417E+005 105.31 21. 10 8.088E+005 1. 7 63E+005 3.623E+005 Tl-208 583.19 85.00 2.328E+005 2.33E+005 1.661E+004 9.541E+004 Bi-212 727.33 6.67 2.882E+006 2.88E+006 -6.375E+005 1.144E+006
-t Pb-212 238.63* 43.60 3.967E+005 3.97E+005 3.051E+005 1.719E+005 Bi-214 609.32 45.49 5.154E+005 5. 15E+005 l .701E+005 2.177E+005 1120.29 14.92 l.600E+006 -2.319E+ 005 6.349E+005 1764.49 15.30 l.435E+006 2.511E+005 5.083E+005 Pb-214 295.22 18.42 8.541E+005 5.98E+005 -1. 523E+005 3.577E+005 351. 93 35.60 5.983E+005 1. 732E+005 2.601E+005 Ra-226 186.21 3.64 4 .784E+006 4.78E+006 1.509E+006 2.110E+006 Ac-228 338.32 11. 27 1 .173E+006 6.84E+00S -l.253E+005 4.654E+005 911. 20 25.80 6.835E+005 -2.646E+005 2.558E+O0S 968.97 15.80 l.510E+006 1.338E+005 6.101E+005 Am-241 59.54 35.90 7.006E+005 7. 01E+005 -7.798E+004 3.258E+005 + = Nuclide identified during the nuclide i dentification * = Ene rgy line found in the spectrum > = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated @ = Half-life too short to be able to perform the decay correction
[153]
- ***********~******~******* * ****** ****************
GAMM A S P E C T R U M A N A L Y S I S **** *
- ~**********~******************* **********************************
Filename: C:\GENIE2K\B308102\U1SW.CNF Report Generated On 9/26/2017 2:50: 04 PM Sample Title B308 1 02ASFJSM00 2GD Sample Description OlSW Rl Sample Identification Sample Type Sample Geometry Peak Locate Threshold 3 . 00 Peak Locate Range (in channels) 50 8192 Peak Area Range (in channels) 50 - 8192 Identification Energy Tolerance 10.000 keV Sample Size l.OOOE+OOO M"2 Sample Taken On 9/17/2015 2:49:06 PM Acquisition Started 9/17 / 2015 2:49:06 PM Live Time 600. 0 seconds Real Time 601.1 seconds Dead Time 0.19 ~ Energy Calibration Used Done On 1/27 / 2 0 15 Efficiency Calibration Used Done On 9/26 / 2 0 17 Efficiency ID 3M TURBI NE [154]
Peak Analysis Report 9/26/~017 2:50:(J = Cal c ulated MDA is zero due to zero coun ts i n the regi o n, or the r e gion is outside the spect rum, o r MDA has n o t been cal c ula ted
@ = Half-life too short to b e abl e to p e rform the decay correction
[158]
- + ************************* ' ***************
GAMM A S I' i C T R U M A N A L Y S s ***** .lename: C:\GENIE2K\CAMFILES\U2NE.CNF ~ort Generated On 9/21/2015 10 :30: 01 AM tmple Title B308102BSFJSM001GD tmple Description U2NE tmple Identification tmple Type tmple Geometr~, !ak Locate Threshold 3 . 00 iak Locate Range (in channels ) 50 - 8192 iak Area Range (in channels) 50 - 8192 lentification Energy Tolerance 1. 000 FWHM tmple Size 1 . 000E+000 METERS tmple Taken On 1/28/2013 12: 00 : 00 PM
- quisition Started 9/17/2015 10 :36: 00 AM
.ve Time 600 . 0 seconds ial Time 6 00 . 4 seconds iad Time 0 . 06 % Energy Calibrat ion Used Done On 1 / 2 7/20 15 Efficiency Calibration Used Done On 7 / 24 / 2 0 1 4 Efficiency ID 3M TURBINE a r e a [159]
!ak Analysis Report 9/21/2015 10:30: 01 AM Page 2 P E A K A N A L Y S I S R E P O R T ***** Detector Name: 5456 Sample
Title:
B308102BSFJSM001GD Peak Analysis Performed on: 9/21/2015 10 : 30 : 01 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 Peak ROI ROI Pea k Energy FWHM Net Peak Net Ar~a Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 297- 306 301.19 75.03 0.59 1.95E+001 22.58 4.65E+001
= First peak in a multiplet region = Other peak in a multiplet region = Fitted singlet
- rors quoted at 2 . 000 sigma
[160]
1terference Corrected Acti ~y Report 9/21/2015 lC 0 : 01 AM Page 3 N U C L I D E I D E N T I F I C A T I O N R E P O R T ***** Sample
Title:
B308102BSFJSM001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion LiB. NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence {keV) ( s) (pCi/METE ) Uncertainty
* = Energy line found in the spectrum. @ ~ Energy line not used for Weighted Mean Activit7 Energy Tolerance : 1.000 FWHM Nuclide confidence index threshold = 0.30 Errors quoted at 2 .000 sigma
[161]
1terference Corrected Acti* :y Report 9/21/2015 10 J: 01 AM Page 4 I N T E R F E R E N C E C O R R E C T E D R E P O R T ***** Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/METE ) Uncertainty
? nuclide is part of an undetermined solution X nuclide rejected by the interference analysis @ = nuclide contains energy lines not used in Weighted Mean Activit 1*
Errors quoted at 2. 000 sigma
********** U N I DE N T I F I E D P E A K S **********
Peak Locate Performed on: 9/21/2015 10:30:01 AM Peak Locate From Channel: 50 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75.03 3.2431E-002 116.06 Tol . PB-212 PB-214 M First peak in a multiplet region m ~ Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma [162]
1clide MDA Report 9/21/2015 10:3 Jl AM Page 5 N U C L I D E M DA R E P O R T ***** Detector Name: 5456 Sample Geometri': Sample
Title:
B308102BSFJSM001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion LiB.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/METE) (pCi/METE) (pCi/METE) (pCi/METE) K-40 1460.81 10 .67 2.525E+005 2.53E+005 2.2 1 8E+005 1.145E+005 MN-54 834.83 99.97 8.400E+004 8.40E+004 -6.087E+003 3.333E+004 C0-60 1173.22 100.00 2.637E+004 2.64E+004 l.357E+004 1 .156E+004 1332.49 100.00 3.101E+004 2.084E+004 1 .379E+004 NB-94 702.63 100.00 6.671E+003 2.08E+003 2.694E+002 2.363E+003 871.10 100.00 2.084E+003 O.OOOE+OOO O.OOOE+OOO SN-113 255.12 1. 93 1.497E+008 3.57E+006 -3.007E+007 6.321E+007 391.69 64. 90 3.571E+006 -5.202E+005 1.383E+006 CS-134 475.35 1. 46 l.371E+006 4.60E+003 4.236E +005 5.441E+005 563.23 8.38 1. 793E+005 -3.380E+004 6.354E+004 569.32 15.43 l.581E+005 4.737E+004 6.479E+004 604.70 97.60 4.595E+003 O.OOOE+OOO O.OOOE+OOO 795.84 85.40 1.562E+004 2.122E+003 4.938E+003 801.93 8.73 1 .532E+005 2.081E+004 4.842E+004 1038.57 1.00 1 .837E+006 3.958E+005 6.510E+005 1167.94 1.80 3.100E+005 O.OOOE+OOO O.OOOE+OOO 1365.15 3.04 8.645E+005 2.879E+005 3.349E+OOS CS-137 661.65 85.12 l.240E+004 1. 24E+004 2.564E+003 5.009E+003 EU-152 121.78 28.40 3.950E+004 1.95E+004 1 .062E +004 1.731E+004 244.69 7.49 1.484E+005 1. 333E+004 6.388E+004 295.94 0.45 2.160E+006 2.042E+005 8.956E+005 344.27 26.50 3.418E+004 4.443E+003 1. 381E+004 367.79 0.86 8.223E+005 -6.493E+005 3.078E+005 411. 11 2.21 4.914E+005 1.142E+005 2.038E+005 443.98 3.11 3.769E+005 1 .018E+005 1. 579E+005 488.68 0.42 2.085E+006 4.992E+OOS 8.078E+005 563.99 0.49 1.682E+006 l.172E +005 6.295E+005 586.26 0.46 1. 566E+006 -1.897E+005 5.548E+005 678.62 0.47 1. 269E+006 -6.036E+005 4.012E+005 688.67 0 .86 8.843E+005 -7.142E +00 4 3.133E+005 719.35 0 .28 3.205E+006 -2.978E+005 1.200E+006 778.89 12.74 1 .058E+005 3.500E+004 4.387E+004 810.45 0 .32 2.894E +006 -3.360E+005 1.083E+006 867.32 4.16 1.556E+005 -4.757E+004 4.9 1 8E+004 919.33 0.43 5.680E+ 005 O.OOOE+OOO O.OOOE+OOO 964.0 1 14.40 9.495E+004 2.710E+004 3.892E+004 1085.78 10.00 8.804E+004 1.185E+003 3.119E+004 1089.74 1. 73 5.104E+005 -1.237E +005 1.808E+005 1112.02 13.30 1 .945E+004 O.OOOE +OOO O.OOOE+OOO 1212.95 1. 42 5.105E+005 6.937E+004 1.614E+005 1249.94 0.19 3.90 5E+006 5.306E+005 1. 234E+006 1299.14 1. 62 7.493E+005 1. 715E+005 2.902E+005 [163]
1clide MDA Report 9/21/2015 10 :3 ')1 AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/METE) (pCi/METE) (pCi/METE) (pCi/METE) EU-152 1407.95 20.70 3.717E+004 1.95E+004 -1.010E+004 1.175E+004 1457.64 0.50 1.962E+006 -2.641E+005 6.952E+005 1528.10 0.28 1.043E+006 O.OOOE+OOO O.OOOE+OOO EU-154 123.10 40.46 2.383E+004 1. 50E+004 -6.635E+003 l.006E+004 247.93 6.95 1.553E+005 7.576E+003 6.557E+004 591.76 4.99 1 .562E+005 -4.206E+003 5.535E+004 692.42 1.80 5.893E+005 -2.146E+004 2.283E+005 723.30 20.22 4.118E+004 2.217E+003 l.459E+004 756.76 4.57 1.849E+005 4.978E+003 6.550E+004 873.19 12.27 9.330E+004 2.573E+004 3.614E+004 996.26 10.64 l.124E+005 2.514E+004 4.353E+004 1004.72 18.01 1.500E+004 O.OOOE+OOO O.OOOE+OOO 1274.44 35.19 3.709E+004 1.235E+004 l.437E+004 1596.49 1.80 4.887E+005 6.642E+004 l.545E+005 EU-155 45.30 1. 33 2.346E+006 6 . 02E+004 -7.311E+005 9.823E+005 60.01 1.13 l.352E+006 -4.315E+005 5.464E+005 86.54 30.70 7.022E+004 3.058E+004 3.184E+004 105.31 21.20 6.021E+004 -2.666E+003 2.578E+004
@ Tl-208 583.19 84.50 1. OOOE+026 1. OOE+026 1.000E+026 1.000E+020 BI-211 72.87 1.20 1.557E+006 9.61E+004 2.665E+005 7.128E+005 351.10 12.20 9.607E+004 1. 2 98E+O 04 4.176E+004 404.80 4.10 2.733E+005 1. 234E+005 1.170E+005 426.90 1. 90 4.185E+005 -3.193E+004 l.661E+005 831.80 3.30 3.014E+005 -3.448E+003 1.196E+005 PB-211 404.80 3.00 3.735E+005 3 . 55E+005 1 .686E+005 l .599E+005 427.10 1. 40 5.205E+005 -1.110E+005 2.016E+005 831. 80 2.80 3.552E+005 -4.064E+003 1 .409E+005 BI-212 39.86 1.10 2.443E+006 5.72E+004 5.695E+005 1.001E+006 727.17 11.80 5.716E+004 -l.847E+004 2.025E+004 785.42 2.00 3.457E+005 -1.489E+005 1.225E+005 1620.56 2.75 3.283E+005 6.188E+004 l.163E+005 PB-212 74.81 9.60 2.234E+005 2.55E+004 1.489E+005 1.037E+005 77.11 17.50 7.575E+004 1.419E+004 3.361E+004 87.20 6.30 2.288E+005 1.684E+005 l.036E+005 89.80 1. 75 5.691E+005 1.223E+005 2.463E+005 115.19 0 .60 1. 515E+006 6.350E+005 6.557E+005 238.63 44.60 2.550E+004 5.912E+003 1.125E+004 300.09 3. 41 2.613E+005 8.579E+004 l.094E+005 BI-214 609.31 46.30 2.688E+004 2 . 69E+004 l.223E+004 1.144E+004 768.36 5.04 2.330E+005 3.305E+004 9.664E+004 806.17 1. 23 8.013E+005 3.362E+004 3.179E+005 934.06 3.21 2.282E+005 - 6.143E+004 8.084E +004 1120.29 15.10 8.344E+004 1.330E+004 3.420E+004 1155.19 1. 69 3.694E+005 -8.784E+004 1.168E+005 1238.11 5.94 l.577E+005 -3.662E+003 5.903E+004 1280.96 1. 47 1.623E+005 O.OOOE+OOO O.OOOE+OOO 1377.67 4.11 2.376E+005 2.575E+004 8.893E+004 1385.31 0.78 8.577E+005 l.166E+005 2.712E+005 1401.50 1.39 1 .778E+005 O.OOOE+OOO O.O OOE+OOO 1407.98 2.48 2.716E+005 -7.381E+004 8.585E+004 1509.19 2.19 3.167E+005 - 1.076E+004 1 .0 0 1E+005
[164]
iclide MDA Report 9/21/2015 10 : :? 01 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/METE) (pCi/METE) (pCi/METE) (pCi/METE) BI-214 1661.28 1.15 2.318E+005 2.69E+004 O.OOOE+OOO O.OOOE+OOO 1729.60 3.05 3.546E+005 9.881E+004 1.327E+005 1764.49 15.80 9.057E+004 1.766E+004 3.660E+004 1847.44 2.12 5.278E+005 1. 471E+005 1.976E+005
> 2118.54 1. 21 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO PB-214 74.81 6.33 3.392E+005 3.25E+004 2.262E+005 1. 57 5E+005 77.11 10.70 1.240E+005 2.323E+004 5.503E+004 87.20 3.70 3.900E+005 2.870E+005 1. 766E+005 89.80 1.03 9.681E+005 2.080E+005 4.189E+005 241.98 7.49 1.107E+005 -2.546E+004 4.636E+004 295.21 19.20 4.828E+004 1. 178E+004 2.039E+004 351.92 37.20 3.247E+004 1.928E+003 1.417E+004 785.91 1.10 7.297E+005 -3.389E+004 2.731E+005 RA-226 186.21 3.28 3.390E+005 3 . 39E+005 1.077E+005 1. 504E+005 AC-228 89.95 2.10 4.738E+005 4.24E+004 1 .169E+005 2.050E+005 93.35 3.50 3.599E+005 1 .179E+005 1.612E+005 129.08 2.80 2.526E+005 -1.234E+005 1.048E+005 209.28 4.40 2.428E+005 1.448E+005 1 .068E+005 270.23 3.60 2.150E+005 4.091E+003 8.813E+004 327.64 3.20 2.071E+005 -5.818E+004 8.020E+004 338.32 11. 40 8.157E+004 -9.654E+003 3.416E+004 409.51 2.13 3.021E+005 4.677E+004 1.131E+005 463.00 4.40 1 .527E+005 -3.310E+004 5.716E+004 794.70 4.60 1.196E+005 1.625E+004 3.780E+004 911.60 27.70 4.237E+004 -3.023E+003 1 .737E+004 964. 60 5.20 2.160E+005 1. 787E+004 8.726E+004 969.11 16.60 6.299E+004 1 .081E+004 2.499E+004 1587.90 3.71 7.026E+004 O.OOOE+OOO O.OOOE+OOO PA-234M 766.36 0.29 3.018E+006 7 . 09E+005 -3.141E+005 1.169E+006 1001. 03 0.84 7.088E+005 9.633E+004 2.241E+005 TH-234 92.38 2.81 4.753E+017 4.75E+017 2.179E+017 2.133E+017 92.80 2.77 4.810E+017 2.238E+017 2.159E+017 112.81 0.28 2.550E+018 -1. 486E+018 1.045E+018 U-235 89.96 1. 50 6.633E+005 2.22E+004 1 .637E+005 2.870E+005 93.35 2.50 5.039E+005 1. 651E+005 2.257E+005 105.00 1.00 9.587E+005 1.180E+005 4.168E+005 109.1 4 1. 50 6.135E+005 -7.734E+004 2.655E+005 143.76 10.50 8.536E+004 -1.364E+003 3.694E+004 163.35 4.70 1 .931E+005 -1.046E+004 8.355E+004 185.71 54.00 2.222E+004 1. 240E + 00 4 9.951E+003 202.12 1.00 6.649E+005 -2.652E+ 005 2.687E+005 205.31 4.70 1.827E+005 -4.350E+003 7.7 72 E+004 AM-241 59.54 36.30 3.104E+004 3 . 10E+004 -1.093E+004 1. 272E+004 + = 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
[165]
- " ~************************* ****************
GAMM A S I-- E C T R U M A N A L Y S .1. S ***** .lename: C:\GENIE2K\CAMFILES\U2NW.CNF iport Generated On 9/21/2015 10:36:54 AM 1mple Title B308102BSFJSM002GD 1mple Description U2NW 1mple Identification 1mple Type tmple Geometry iak Locate Threshold 3.00 iak Locate Range (in channels ) 50 - 8192 !ak Area Range (in channels) 50 - 8192 lentification Energy Tolerance 1. 000 FWHM 1mple Size 1 , 000E+000 METERS 1mple Taken On 1/28/2013 12:00: 00 PM
- quisition Started 9/17/2015 11 :30:59 AM
.ve Time 600 . 0 seconds ial Time 600 .4 seconds iad Time 0 . 07 % Energy Calibration Used Done On 1/27/2015 Efficiency Calibration Used Done On 7/24/2014 Efficiency ID 3M TURBINE area [166]
~ak Analysis Report 9/21/2015 10:36:54 AM Page 2 P E A K A N A L Y S I S R E P O R T ***** Detector Name: 5456 Sample
Title:
B308102BSFJSM002GD Peak Anal:,sis Performed on: 9/21/2015 10 :36:53 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 286- 306 292.38 72.83 0.74 3.53E+001 14.42 2.45E+001 2 286- 306 300. 14 74.77 0.74 4.59E+001 16.73 3.35E+001 3 4 685- 4703 4693.72 1173.06 1.18 1. 08E+002 21. 40 2.l0E+000 4 5322- 5339 5330.62 1332.13 1. 74 8.60E+001 18.55 0.00E+000 5 5837- 5848 5842.98 1460.06 0.52 1.70E+001 9.97 2.95E+000
= First peak in a mult iplet region Other peak in a mult iplet region = Fitted singlet
- rors quoted at 2 . 000 sigma
[167]
1terference Corrected Acti* .y Report 9/21/2015 10 5:54 AM Page 3 NUCLIDE I D E N T I F I C A T I O N R E P O R T ***** Sample
Title:
B308102BSFJSM002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion LiB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/METE) Uncertainty K-40 0 .963 1460.81* 10.67 1.48314E+005 8.76051E+004 CO-60 0 .994 1173.22* 100.00 1.29989E+005 2.78011E+004 1332.49* 100.00 1.08707E+005 2.50054E+004
* = Energy line found in the spectrum. @ = Energy line not used for Weighted Mean'Activity Energy Tolerance : 1.000 FWHM Nuclide confidence index threshold= 0 .30 Errors quoted at 2. 000 sigma
[168]
1terference Corrected Acti * :y Report 9/21/2015 10 5:54 AM Page 4 I N T E R F E R E N C E C O R R E C T E D R E P O R T ***** Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence {pCi/METE) Uncertainty K-40 0.963 1.483140E+005 8.760513E+004 CO-60 0.994 1.182243E+005 1.859155E+004
? ~ nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis @ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2. 000 sigma ********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 9/21/2015 10 :36:53 AM Peak Locate From Channel: 50 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty T 1,pe Nuclide M 1 72.83 5.8879E-002 40.82 Tol. BI-211 m 2 7 4.77 7.6574E-002 36.42 Tol. PB-212 PB-214 M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma [169]
1clide MDA Report 9/21/2015 10:3 S4 AM Page 5 N U C L I D E M D A R E P O R T ***** Detector Name: 5456 Sample Geometry: Sample
Title:
B308102BSFJSM002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion LiB.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/METE) (pCi/METE) (pCi/METE) (pCi/METE)
+ K-40 1460.81* 10.67 1.035E+005 l .04E+005 l.483E+005 3.999E+004 MN-54 834.83 99.97 6.898E+004 6.90E+004 -1.869E+004 2.582E+004 + CO-60 1173.22* 100.00 1 .345E+004 3.42E+003 1.300E+005 5.093E+003 1332.49* 100.00 3.421E+003 1.087E+005 0.000E+000 NB-94 702.63 100.00 1.079E+004 1. 01E+004 2.027E+003 4.421E+003 871.10 100.00 1.010E+004 3.851E+003 4.006E+003 SN-113 255.12 1. 93 1. 781E+008 4.72E+006 -1.361E+007 7.743E+007 391.69 64.90 4.717E+006 l.003E+006 1.956E+006 CS-134 475.35 1. 46 1.571E+006 2.23E+004 2.876E+005 6.438E+005 563.23 8.38 2.724E+005 -2.495E+004 1.101E+005 569.32 15.43 l .485E+005 -7.895E+003 5.999E+004 604.70 97.60 2.226E+004 1. 698E+003 8.834E+003 795.84 85.40 3.368E+004 1 .128E+004 1.397E+004 801. 93 8.73 2.729E+005 -4.371E+004 1 .083E+005 1038.57 1.00 2.377E+006 7.915E+005 9.207E+005 1167.9 4 1. 80 1.233E+006 -1. 241E+005 4.616E+005 1365.15 3.04 7.748E+005 7.798E+004 2.900E+005 CS-137 661.65 85.12 1.655E+004 1 . 65E+004 7.436E+003 7.084E+003 EU-152 121.78 28.40 3.847E+004 3.72E+004 -7.049E+003 1.679E+004 244.69 7.49 1 .074E+005 -5.236E+004 4.340E+004 295.94 0 .45 2.738E+006 1.249E+006 1.185E+006 344.27 26.50 4.395E+004 7.986E+003 1.870E+004 367.79 0.86 1 .438E+006 8.434E+005 6.156E+005 411. 11 2.21 4.368E+005 -6.194E+004 l.765E+005 443.98 3.11 3.769E+005 1.087E+005 1.5 7 9E+005 488.68 0.42 l.869E+006 -8.536E+005 6.996E+005 563.99 0.49 2.048E+006 -2.968E+005 8.127 E+005 586.26 0.46 2.211E+006 -2.951E+005 8.772E+005 678.62 0.47 1.856E+006 -2.069E+006 6.948E+005 688. 67 0.86 1. 343E+006 4.087E+005 5. 42 6E+005 719.35 0.28 2.765E+006 7.444E+004 9.796E+005 778.89 12.74 l .058E+005 2.458E+004 4.387E+004 810.4 5 0.32 1 .978E+006 -1.21 0E +006 6.254E+005 867.32 4.16 3.354E+005 1. 4 67E+005 1 .391E+005 919.33 0.43 2. 752 E+006 l.994E+005 1 .092E+006 964.01 14.40 7.595E+004 7.9 0 4E+003 2.942E+004 1085.78 10.00 1. 243E+005 -4.740E+003 4.932E+004 1089.74 1. 73 5.104E+005 -3.161E + 005 1 .8 08 E+0 05 1112.02 13.30 9.424E+004 3.594E+004 3.739E+004 1212.95 1. 42 6.442E+005 -2.255E+005 2.282E+005 1249.94 0 .19 3.905E+006 -6.633E + 005 1 .234E+006 1299. 14 1. 62 6.715E+005 7.278E+004 2 .514E+005
[170]
1clide MDA Report 9/21/2015 10:3 c, 4 AM Page 6 Nuclide Enerqy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) Uo) (pCi/METE) (pCi/METE) (pCi/METE) (pCi/METE) EU-152 1407.95 20.70 3.717E+004 3.72E+004 O.OOOE+OOO 1.175E+004 1457.64 0.50 1.555E+006 O.OOOE+OOO 4.916E+005 1528.10 0.28 1.043E+006 O.OOOE+OOO O.OOOE+OOO EU-154 123.10 40.46 2.995E+004 8.36E+003 8.651E+002 1. 312E+004 247.93 6.95 1.900E+005 5.626E+004 8.294E+004 591. 7 6 4.99 2.669E+005 5.888E+004 1.107E+005 692.42 1. 80 5.893E+005 1. 4 72E+005 2.283E+005 723.30 20.22 6.254E+004 1 .441E+004 2.527E+004 756.76 4.57 2.392E+005 -2.115E+004 9.264E+004 873.19 12.27 1.018E+005 3.107E+004 4.041E+004 996.26 10.64 8.68BE+004 -3.275E+004 3.07BE+004 1004.72 18.01 4.079E+004 -2.079E+004 1.290E+004 1274.44 35.19 8.357E+003 O.OOOE+OOO 0.000E+OOO 1596.49 1. 80 4.888E+005 6.642E+004 1.545E+005 EU-155 45.30 1. 33 2.553E+006 5 . 56E+004 -2.140E+006 1 .086E+006 60.01 1.13 2.044E+006 -4.974E+005 8.923E+005 86.54 30.70 5.561E+004 -1.738E+004 2.453E+004 105.3 1 21. 20 7.522E+004 7.197E+003 3.328E+004
@ Tl-208 583.19 84.50 1 .000E+026 1 .00E+026 1. OOOE+026 1.000E+020 BI-211 72.87 1. 20 1. 818E+006 5.57E+004 2.751E+005 8.435E+005 351. 10 12.20 5.568E+004 -4.114E+004 2.157E+004 404.80 4.10 1.744E+005 -5.716E+004 6.754E+004 426.90 1. 90 5.065E+005 8.181E+004 2.101E+005 831.80 3.30 2.135E+005 -8.046E+004 7.563E+004 PB-211 404.80 3.00 2.383E+005 2.38E+005 -7.812E+004 9.231E+004 427. 10 1. 40 6.875E+005 5.417E+003 2.851E+005 831.80 2.80 2.516E+005 -9.482E+004 8.913E+004 BI-212 39.86 1.1 0 4.517E+006 7.39E+004 l .701E+006 2.038E+006 727.17 11. 80 7.393E+004 7.694E+003 2.864E+004 785.42 2.00 4.008E+005 -2.885E+005 1 .500E+005 1620.56 2.75 2.602E+005 3.536E+004 B.226E+004 PB-212 74.81 9.60 2.475E+005 2.93E+004 l.963E+005 1 .158E+005 77.11 17.50 8.332E+004 6.6 0 8E+ 0 03 3.740E+004 87.20 6 .30 1.880E+005 1 .859E+ 0 04 8.320E+004 89.80 1. 75 6.504E+005 -6.217E+ 0 04 2.869E+005 115.19 0.60 1 .366E+006 -6.215E+ 005 5.813E+005 2 38.63 44.60 2 .932E +004 1 .387E+ 00 4 1 .316E+0 0 4 300.09 3.41 2.487E+005 -3.870E+ 00 4 1 .032E+005 BI - 214 609.31 46.30 3.072E+004 3 . 07E+004 2.055E+004 1. 335E+00 4 768.36 5.04 2.205E+005 6.819E+004 9.040E+004 806.17 1. 23 8.013E+005 -l.192E+005 3.179E+ 005 934.06 3.21 2.952E+005 9.829E+004 1.143E+005 1120.29 15.10 7.285E+004 l.334E+0 04 2.891E+004 1 155.19 1. 69 l.358E+005 O.OOOE+OOO O.OOOE+OOO 1238.11 5.94 1 .078E+00 5 O.OOOE + OOO 3.408E+004 1280.96 1. 4 7 6.455E+OOS 5.497E+004 2.416E+005 1377.67 4.11 1.624E+ 005 -5.518E +00 3 5.134E+004 1385.31 0 .78 3.154E+005 O.OOOE+OOO O.OOOE+OOO 1401. 50 1. 39 1.778E+005 O.OOOE+OOO O.OOOE+OOO 1407 .98 2.48 2.716E+005 O.OOOE+OOO 8.585E+004 1509.19 2.19 l.165E+005 O.OOOE+OOO O.OOOE+OOO
[171]
1clide MDA Report 9/21/2015 10 :2 ,5 4 AM Page 7 Nuclide Energy Yield Line MCA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/METE) (p~i/METE) (pCi/METE) (pCi/METE) BI-214 1661.28 1.15 2.318E+005 3. 07E+004 O.OOOE+OOO O.OOOE+OOO 1729.60 3.05 3.546E+005 9.8RlE+004 l.327 E+005 1764.49 15.80 9.057E+004 1 .873E+004 3. 6t50E+004 1847.44 2.12 4.553E+005 9.806E+004 l . 613E+005
> 2118.54 1. 21 O.OOOE+OOO O.OOOE+OQO O.OOOE+OOO PB-214 74.81 6.33 3.758E+005 2 . 54E+004 2.980E+005 1.7~8E+005 77.11 10.70 1. 364E+005 1.082E+004 6.123E+OO.J 87.20 3.70 3.205E+005 3.169E+004 1 .418E+005 89.80 1. 03 1.106E+006 -1.057E+005 4.880E+005 241. 98 7.49 1. 377E+005 4.882E+004 5.985E+004 295.21 19.20 5.399E+004 5.543E+003 2.325E+004 351.92 37.20 2.538E+004 5.966E+003 1. 063E+004 785.91 1. 10 7.297E+005 -4.067E+005 2.731E+005 RA-226 186.2 1 3.28 3.390E+005 3.39E+005 8.247E+004 l.504E+005 AC-228 89.95 2.10 5.415E+005 4.24E+004 -5.300E+004 2.389E+005 93.35 3.50 3.534E+005 -5.630E+003 1.579E+005 129.08 2.80 3.203E+005 -5.374E+004 1.386E+005 209.28 4.40 2.176E+005 -6.490E+004 9.415E+004 270.23 3.60 2.695E+005 -4.206E+004 l .154E+005 327.64 3.20 3.127E+005 8 .854E+004 1 .330E+005 338.32 11. 40 8.878E+004 -5 .006E+003 3.777E+004 409.5 1 2.13 3.370E+005 5 .261E+004 1.306E+005 463.00 4.40 2.251E+005 2 .305E+004 9.335E+004 794.70 4.60 2.292E+005 2 .844E+004 9.260E+004 911.60 27. 70 4.237E+004 1. 209E+003 1.737E+004 964.60 5.20 1.839E+005 -6.700E+003 7.125E+004 969.11 16.60 4.462E+004 -7.207E+003 1.581E+004 1587.90 3.71 1.911E+005 -6.491E+003 6.040E+004 PA-234M 766.36 0.29 3.294E+006 1.16E+006 1. 256E+006 1.307E+006 1001 .03 0 .84 1 .157E+006 6.020E+004 4. 4 82E+005 TH-234 92.38 2.8 1 5.225E+017 5.14E+017 2.925E+D17 2.369E+017 92.80 2.77 5.136E+017 1. 7 19E+017 2.322E+017 112.81 0.28 3.908E+018 6.912E+017 l .724E+018 U-235 89.96 1. 50 7.580E+005 2.06E+004 -7.420E+004 3.344E+005 93.35 2.50 4.947E+005 -7.882E+003 2. 2 11E+005 105.00 1. 00 1.111E+006 6.113E+004 4.931E+005 109.14 1. 50 5.741E+005 -2.122E+005 2.458E+005 143.76 10.50 9.525E+004 1.957E+004 4.189E+004 163.35 4.70 2.101E+005 7.397E+004 9.207E+004 185. 7 1 5 4.00 2 .056E+004 3.055E+002 9.120E+003 202.12 1.00 7.481E+005 -2.122E+005 3.102E+005 205.31 4.70 2.147E+005 2.424E+004 9.374E+004 AM-241 59.5 4 36.30 4.640E+004 4 . 64E+004 -6.316E+002 2 . 040E+ 00 4 + = 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
[172]
GAMM A SP.r.;CTRUM ANALYS.LS .lename: C:\GENIE2K\CAMFILES\U2NBKG.CNF iport Generated On 9/21/201 5 10 :2£ : 11 AM tmple Title U2 BKG ~ple Description U2NBKG tmple Identification tmple Tj1 pe tmple Geometry iak Locate Threshold 3. 00 iak Locate Range (in channels ) 50 - 8192 iak Area Range (in channels) 50 - 8192 lentification Energy Tolerance 1. 000 FWHM tmple Size l. OOOE+OOO Meter tmple Taken On 1/28/2013 12: 00 : 00 PM
- quisition Started 9/17/2015 1 :25: 04 PM
.ve Time 600 . 0 seconds ial Time 600 .9 seconds !ad Time 0 . 15 % Energy Calibration Used Done On 1 /27/2 0 15 Efficiency Calibration Used Done On 7/24/20 14 EfficienC:'_' I D 3M TURBI NE area c.., \+c.l..{c. 6 \(_J2-u 0 /,;. " ' e...,_~.;>,:(_ Q ~\'.._\ ~ ~ \ . \ ~ [173]
iak Arialysis Report 9/21/2015 10:26:11 AM Page 2 P E A K A N A L Y S I S REPORT ***** Detector Name: 5456 Sample
Title:
U2 BKG Peak Analysis Performed on: 9/ 21/2015 10 :26: 10 AM Peak Analysis From Channel: 50 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV} (keV} Area Uncert. Counts 1 80- 89 83.48 20.56 1.00 1.86E+002 40 .89 9.00E+00l 2 297- 308 301.42 75.09 0.71 6.49E+001 39.55 1 .27E+002 3 333- 344 340.51 84.87 0.57 4.86E+001 33.79 9.34E+001 4 949- 960 955.48 238.70 0.73 2.70E+001 23.24 4.30E+001 5 1404- 1414 1408 .87 352.09 0.80 1.45E+001 15.40 1.85E+001 6 2328- 2338 2333.12 583.19 0.57 2.45E+001 13.47 8.47E+000 7 5835- 5856 5844.63 1460.47 2.13 1.46E+002 2 6. 34 7 .53E+000
= First peak in a multiplet region Other peak in a multiplet region = Fitted singlet
- rors quoted at 2 . 000 sigma
[174]
iterference Corrected Acti, y Report 9/21/2015 10 ): 11 AM Page 3 N U C L I D E I D E N T I F I C A T I O N R E P O R T **** .-
- ~** ~** * ******
Sample
Title:
U2 BKG Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion LiB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/Mete) Uncertainty K-40 0.992 1460.81* 10.67 1 .27427E+006 2.52207E+005 BI-211 0.965 72.87 1. 20 35 1 .10* 12.20 6.71048E+004 7.22717E+004 404.80 4. 10 426.90 1. 90 831. 80 3.30 PB-212 0 . 4 90 74.81* 9.60 3.82125E+005 2.44994E+005 77.11 17.50 87.20 6.30 89.80 1. 75 115.19 0.60 238.63* 44.60 2 . 99963E+004 2 . 62239E + 004 300.09 3.41 TH-231 0 . 992 26. 64 18.70 84.21* 8.00 3.11717E+005 2.25324E+005 89.95 1.25
*=En ergy l in e found in the spectrum. @ = Ene rgy line not used for Weighted Mean Activity Energy Tolerance : 1.000 FWHM Nuclide confidence index threshold 0 .30 Errors quoted at 2. 000 sigma
[175]
iterference Corrected Acti* .y Report 9/21/2015 10 5: 11 AM Page 4 I N T E R F E R E N C E C O R R E C T E D R E P O R T ***** Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/Mete) Uncertainty K-40 0.992 1.274268E+006 2.522069E+005 BI-211 0.965 6.710481E+004 7.227171E+004 PB-212 0. 4 90 3.398503E+004 2.607499E+004 TH-231 0.992 3.117174E+005 2.253237E+005
? = nuclide is part of an undetermined solution X ~ nuclide rejected by the interference analysis @ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2. 000 sigma ********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 9/21/2015 10 :26: 10 AM Peak Locate From Channel: 50 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second 9* Uncertainty Type Nuclide 1 20.56 3.1004E-001 21. 98 6 583.19 4.0884E-002 54.89 Tol. Tl-208 M = First peak in a multiplet region m = Other peak in a multiplet region F - Fitted singlet Err o rs quoted a t 2 . 000 sigma [176]
lClide MDA Report 9/21/2015 10:2 11 AM Pa ge 5
- N U C L I D E M DA R E P O R T *****
Detector Name: 5456 Sample Geometry: Sample
Title:
U2 BKG Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion- LiB.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (~ ) (pCi/Mete) {pCi/Mete) (pCi/Mete) (pCi/Mete)
+ K-40 1460.81* 10.67 1.723E+005 1.72E+005 1 .274E+006 7.439E+004 MN-54 834.83 99.97 6.899E+004 6.90E+004 1 .923E+004 2.582E+004 CO-60 1173.22 100.00 1 .809E+004 1. 1 7E+004 1 .807E+003 7.416E+003 1332.49 100.00 l.174E+004 -8.849E+003 4.159E+003 NB-94 702.63 100.00 1.197E+004 1.01E+004 1.357E+003 5.013E+003 871.10 100.00 1.010E+004 2.233E+003 4.006E+003 SN-113 255.12 1. 93 1. 976E+008 4.96E+006 -2.444E+007 8.719E+007 391. 69 64.90 4.957E+006 -6.6 1 0E+004 2.076E+006 CS-134 475.35 1. 46 1 .660E+006 2.55E +004 -4.445E+005 6.883E+005 563.23 8.38 3.219E+005 6. 1 16E+004 1. 348E+005 569.32 15.43 1. 754E+005 -2.398E+004 7.348E+004 604.70 97.60 2.550E+004 4.246E+002 1 .045E+004 795.84 85.40 2.550E+004 -9.817E+003 9.876E+003 801. 93 8.73 2.936E+005 -l.821E+004 1 .186E+005 1038.57 1. 00 l .456E+006 -8.905E+005 4.604E+005 1167.94 1. 80 1 .233E+006 -2.864E+004 4.6 1 6E+005 1365.15 3.04 5.297E+005 -3.599E+005 1.675E+005 CS - 13 7 661.65 85.12 1 .594E+004 1.59E+004 5.994E+003 6.783E+003 EU-1 52 121.78 28.40 !:?.930E+004 5.02E+004 -3.094E+003 2.72 1E+004 244.69 7.49 1.791E+005 -3.617E+003 7.923E+004 295.9 4 0.45 3.837E+006 1.960E+006 1. 7 34E+006 344.27 26.50 5.023E+004 7.028E+003 2.183E+004 367.79 0.86 1. 583E+D06 2.368E+005 6.882E+005 411. 1 1 2.2 1 5.395E+005 -8.51 7E+003 2 . 27 9E+00 5 443.98 3.1 1 3.397E+005 1. 293E+004 l.392E+005 488.68 0.42 2.276E+006 -3.038E+005 9.032E+005 5 63.99 0.49 2.834E+006 6.107E+005 1. 2 05 E+006 586.26 0.46 2.810E+006 8.197E+005 1.177E+006 67 8. 62 0.47 2.874E+006 1 .245E+006 1. 20 4E+006 68 8. 67 0.86 1.587E+006 7.14 2E+00 4 6.6 4 6E+005 719.35 0.28 5.401E+006 2 .457E+006 2.297E+ 0 06 778.89 12.74 8. 7 40E+004 -2.667E+003 3.468E+ 0 04 810.45 0.32 2.496E+006 -1 .344E+005 8.845E+ 00 5 867.32 4.16 2.771E+005 3. 2 77E+004 1.100E+0 0 5 919.33 0.43 2. 2 60E +006 -5.773E+005 8.458E+D05 964. 01 14.40 l .003E+005 3.991E+004 4.161E+0 0 4 1085.78 10.00 1.021E +005 2.844E+004 3.820E+004 1089.74 1. 73 8.254E +005 2.159E +005 3.383E +005 1112.02 13.30 1.014E+005 l .078E+004 4.096E+0 0 4 1212 .95 1. 4 2 1 . 2 08 E+006 1 .4 22E+00 5 5. 1 04 E+005 1249.94 0.19 6.374E+006 3.980E +005 2.469E+0 0 6 1299.14 1. 62 8.178E+005 1 .060E+005 3.245E+0 05
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1clide MDA Report 9/21 / 2015 10 : 2 ll AM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/Mete) (pCi/Mete) (pCi/Mete) (pCi/Mete) EU-152 1407.95 20.70 6.067E+004 5.02E+004 2. 010E+004 2.350E+004 1457.64 0 .50 3.978E+006 -l.057E+005 1. 703E+006 1528.10 0.28 l .043E+006 O.OOOE+OOO O.OOOE+OOO EU-154 123.10 40.46 4.446E+004 3.32E+004 2. 636E+003 2. 038E-:*004 247.93 6.95 2.096E+005 5.125E+004 9.273E+004 591.76 4. 99 2.526E+005 -4.507E+004 1. 036E+005 692.42 1. 80 8.899E+005 2.910E+005 3.786E+005 723.30 20.22 6.254E+004 7.761E+003 2.527E+004 756.76 4.57 2.808E+005 -l .543E+005 1.135E+005 873.19 12.27 1 .018E+005 l .165E+003 4.041E+004 996.26 10.64 1. 124E+005 -3.275E+004 4.353E+004 1004 .72 18.01 5.968E+004 -2.079E+004 2.234E+004 1274.44 35.19 3.324E+004 -4.890E+003 l.244E+004 1596.49 1. 80 4.888E+005 -l.328E+005 l.545E+005 EU-155 45.30 1. 33 4.310E+006 9.94E+004 -8.484E+005 1. 965E+006 60.01 1.13 2.973E+006 -1.319E+006 1. 357E+006 86.54 30.70 9.938E+004 -5.803E+003 4.64 1 E+004 105.31 21. 20 1 .128E+005 2.453E+004 5.209E+004
@ Tl-208 583.19 84.50 l .OOOE+026 1. OOE +026 1.000E+026 1.000E+020
+ BI-211 72.87 1. 20 2.430E+006 l.15E+005 1.147E+006 1 .149E+00 6 351.10* 12.20 1.148E+005 6.710E+004 5.112E+004 404.80 4 . 10 2.303E+005 -4.899E+004 9.552E+004 426.90 1. 90 6.220E+005 9.946E+004 2.678E+005 831. 80 3.30 3.452E+005 6.978E+004 l .415E+005 PB-211 404.80 3.00 3.148E+005 3 . 15E+005 -6.696E+004 l .305E+005 427. 10 1. 40 9.486E+005 5.041E+005 4.157E+005 831. 8 0 2.80 4.068E+005 8.224E+004 1. 668E+005 BI-212 39.86 1. 10 5.228E+006 1.03E+005 7.119E+003 2.394E+006 727.17 11. 80 1. 026E+ 005 3.847E +004 4.296E+004 785.42 2.00 5.591E+005 1.090E+005 2.292E+005 1 620.56 2.75 3.283E+005 4.862E+004 l. 163E+005 + PB - 212 74.81* 9.60 3.656E+005 4. 0 9E+004 3.821E+005 1. 748E+005
- 77. 1 1 17 .50 1. 212E+005 5.891E+003 5.633E+004 87.20 6.30 3.503E+005 1.849E+005 1. 643E+005 89.8 0 1. 75 1.053E+006 8.591E+004 4.881E+0 05 115.19 0 .60 2.155E+006 -1. 34 9E+005 9.758E+ 005 238.63* 44.60 4 .093E+004 3.000E+004 1 .896E+ 00 4 300.09 3. 41 3.43 2E+005 -2.329E+004 l.504E+ 005 BI-214 609.31 46.30 5.562E+004 5 . 56E+004 6.503E+004 2.580E+ 0 04 76 8.36 5.04 2.447E+00 5 - 2 .40 7E+00 4 1 . 02 5E+ 005 806.17 1. 23 8.013E+005 5.501E+004 3.179E+00 5 934.06 3.21 4.095E+005 7.850E+004 l .715E+005 11 2 0.29 15 .10 l. 2 16E+005 7. 028E +004 5.330E+004 1155.19 1. 69 3.694E+005 -2.259E+005 1 .168E+005 1238.11 5.94 2.200E+005 -9. 418E+003 9.017E+004 12 80.96 1. 4 7 6.4 55E+005 -l.499E+004 2.416E+005 1377.67 4. 11 3.113E+005 1.076E+005 1. 258E+005 1385.31 0.78 l.255E+006 1.7 4 8E+005 4.697E+ 005 1401. 50 1.3 9 7 .075E+005 -1.369E+00 5 2 . 6 4 8E+005 1407.98 2.48 4 .433E+005 l.476E+005 1.717 E+0 05 1509.19 2.19 5.170E+005 1.722E +005 2. 00 3E+005
[178]
iclide MDA Report 9/21/2 015 10 :2 l l AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/Mete} (pCi/Mete) (pCi/Mete) (pCi/Mete) BI-214 1661.28 1.15 2.318E+005 5.56E+004 O.OOOE+OOO O.OOOE+OOO 1729.60 3.05 3.956E+005 1. 318E+005 1. 533E+005 1764.49 15.80 1.019E+005 4.616E+004 4.226E+004 1847.44 2.12 4.553E+005 9.806E+004 1.613E+005
> 2118.54 1.21 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO PB-214 74.81 6.33 5.266E+005 4 .. 42E+004 5.366E+005 2.512E+005 77.11 10.70 1 .984E+005 9.646E+003 9.224E+004 87.20 3.70 5.971E+005 3.151E+005 2.801E+005 89.80 1.03 1.791E+006 1 .461E+005 8.303E+005 241.98 7.49 1.844E+005 3.699E+004 8.322E+004 295.2 1 19.20 7.694E+004 8.195E+003 3.472E+004 351.92 37.20 4.421E+004 2.286E+004 2.004E+004 785.91 1.10 1.018E+006 1. 235E+005 4.172E+005 RA-226 186.21 3.28 4.736E+005 4 . 74E+005 3.126E+005 2.177E+005 AC-228 89.95 2.10 8.839E+005 6.49E+004 1.743E+005 4.101E+005 93.35 3.50 5.731E+005 2.343E+005 2.678E+005 129.08 2.80 6.169E+005 2.425E+005 2.869E+005 209.28 4.40 2.543E+005 -5.746E+004 1 .125E+005 270.23 3.60 3.367E+005 -3.580E+003 1. 4 90E+O 05 327.6 4 3.20 4.053E+005 -9.912E+003 1.793E+005 338.32 11. 40 1.380E+005 8.611E+004 6.237E+004 409.51 2.13 4.888E+005 -5.612E+003 2.064E+005 463.00 4. 4 0 2.764E+005 7.803E+004 l.190E+005 794.70 4.60 2.130E+005 5.037E+004 8.453E+004 911.60 27.70 6.486E+004 2.506E+004 2.861E+004 964.60 5.20 2.300E+005 8.587E+004 9.426E+004 969.1 1 16.60 8.714E+004 3.964E+004 3.7 07E+004 1587.90 3.71 2.411E+005 -3.245E+004 8.542E+004 PA-234M 766.36 0.29 4.557E+006 1 . 61E+006 1. 382E+006 1.939E+006 1001.03 0.84 1 .605E+006 6.02 0E+005 6.723E+005 TH-234 92.38 2.81 7.152E+017 7.15E+017 1. 396E+Ol 7 3.332E+017 92.80 2.77 7.501E+017 3.443E+ 017 3.503E+017 112.81 0.28 5.838E+018 1 .2 02E+ 018 2.688E+018 U-235 89.96 1.50 1.237E+006 2. 78 E+004 2.441E+005 5.741E+005 93.35 2.50 8.024E+005 3.281E+ 0 05 3.749E+005 105.00 1. 00 1.632E+006 2.438E+ 005 7.533E+005 109.14 1. 50 1.096E+006 -5. 980E+ 00 4 5 .0 67E+00 5 143.76 10.50 1. 24 9E+005 -2.636E+ 00 3 5.671E+004 163.35 4.70 2.665E+005 -5.528E+ 00 4 1.2 0 3E+005 185.71 54.00 2.780E+004 1 .41 2E +00 4 1.2 74E+004 202.12 1.00 l .109E+006 1 .821E+0 05 4.905E+005 205.31 4.70 2.616E + 005 4.009E +00 4 1 .172E+005 AM-241 59.54 36.30 6.167E+004 6.17E+004 -3.347E+004 2.804E+004 + = 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
[179]
GAMM A S P E C T R U M A N A L Y S I S ***** .lename: E:\4-27-17 \U2NBKG. CNF !port Generated On 5/1/2017 11 :24:59 AM tmple Title U2 BKG tmple Description U2NBKG Rl tmple Identification 1mple Type unple Geometry !ak Locate Threshold 3 ,. 00 !ak Locate Range (in channels) 85 - 8192 !ak Area Range (in channels) 85 - 8192 lentification Energy Tolerance 10.000 keV 1mple Size 7.800E+001 Sq Meter 1mple Taken On 1/28/2013 12:00:00 PM
- quisi tion Started 9/17/2015 1:25:04 PM
.ve Time 600.0 seconds ial Time 600.9 seconds !ad Time 0 . 15 % Energy Calibration Used Done On 1/27/2015 Efficiency Calibration Used Done On 4/27/2017 Efficiency ID 3M TURBINE [180]
iak Analysis Report 5/1/2017 11 :25: 00 'l- Page 2 P E A K A N A L Y S I S REPORT ***** Detector Name: 5456 Sample
Title:
U2 BKG Peak Analysis Performed on: 5/1/2017 11:24:59 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Pea k Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 297- 308 301. 42 75.09 0.71 6.49E+001 39.55 1 .27E+002 2 333- 344 340. 51 84.87 0.57 4.86E+001 33.79 9.34E+001 3 949- 960 ~55.48 238.70 0.73 2.70E+001 23.24 4.30E+001 4 1404- 1414 1408.87 352.09 0.80 1.45E+001 15. 40 1 .85E+001 5 2328- 2338 2333.12 583.19 0.57 2.45E+001 13.47 8.47E+OOO 6 5835- 5856 5844.63 1 460.47 2.13 1.46E+002 26.34 7.53E+OOO First peak in a mult iplet region Other peak in a multiplet region Fitted singlet
- rors quoted at 2 . 000 sigma
[181]
1terference Corrected Act. _ty Report 5/1/2017 1 25:00 AM Page 3 NUCLIDE I D E N T I F I C A T I O N R E P O R T ***** Sample
Title:
U2 BKG Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/Sq M) Uncertainty K-40 1 . 000 1460 . 82* 10 .66 6.35157E+004 1.26855E+004 Ba-133 0 .58 4 79.61* 2.65 4 .05835E+004 2.60645E+004 81.00* 32.90 2.43516E+003 1.76081E+003 276.40 7.16 302.85 18.34 356.01* 62.05 6.19441E+002 6.67136£+002 383.85 8.94 Eu-155 0 . 306 45.30 1. 31
- 60. 01 1.22 86.55* 30.70 3.22300E+003 2.32974E+003 105.31 21.10 Tl-208 1.000 583.19* 85.00 8.31 2 47E+002 4.67125E+002 Pb-212 0 .872 115.18 0.60 238.63* 43.60 1 .14573E+003 1.00199E+003 300.09 3.30
*=Energy line found in the spectrum. @ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide c onfidence i ndex threshold - 0.30 Errors quoted at 2.000 s i gma
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1terference Corrected Act Lty Report 5/1/2017 J 25:0 0 AM Page 4 I N T E R F E R E N C E C O R R E C T E D R E P O R T ***** Nuclide Wt mean Wt me an Nuclide Id Activity Activity Name Confidence (pCi/Sq M) Uncertaint~; K-40 1.000 6.351569E+004 1. 2 6854 8E+004 X Cd-109 0.963 Ba-133 0.584 6.456958E+002 6.669169E+002 Eu-155 0.306 2.368401E+003 2.491345E+003 Tl-208 1. 000 8.312470E+002 4.671251E+002 X Bi-211 0 .998 Pb-212 0 .872 1 .145726E+003 1.001985E+003 X Pb-214 0 .493
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis @ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma ********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 5/1/2017 11:24:59 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified. [183]
1clide MDA Report 5/1/201-: 11 :25:00 AM Page 5 "*** N U C L I D E MD A R E P O R T ***** Detector Name: 5456 Sample Geometry: Sample
Title:
U2 BKG Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/Sq M) (pCi/Sg M) (pCi/Sq M) (pCi/Sg M) + K-40 1460.82* 10.66 8.590E+003 8.59E+003 6.352E+004 3.708E+003 Cr-51 320.08 9.91 2.303E+014 2.30E+014 6.758E+013 1.069E+014 Mn-54 834.85 99.98 6.988E+003 6.99E+003 3.127E+003 3.101E+003 Co-58 810.76 99.45 9.100E+006 9. 10E+006 4.726E+006 3.987E+006 Co-60 1173.23 99.85 1.421E+D03 1.08E+003 2.297E+002 6.321E+002 1332.49 99.98 1.077E+003 6.185E+002 4.550E+002 Nb-94 702.65 99.81 9.182E+002 7.48E+002 5.548E+002 4.163E+002 871.09 99.89 7.475E+002 -5.172E+002 3.263E+002 Sn-113 255.13 2.11 1.142E+007 3.46E+005 -4.862E+006 5.309E+006 391.70 64. 97 3.460E+005 -3.539E+004 1 .569E+005 Cs-134 475.36 1. 48 1 .254E+005 2.28E+003 -8.491E+004 5.693E+004 563.25 8.34 2.281E+004 -1.254E+004 1.029E+004 569.33 15.37 1.282E+004 -6.396E+003 5.804E+003 604.72 97. 62 2.729E+003 -1 .929E+003 1 .266E+003 795.86 85.46 2.282E+003 5.427E+002 1.013E+003 801. 95 8.69 2.346E+004 1.196E+004 1.046E+004 1038.61 0.99 2.057E+005 -l.064E+004 9.015E+004 1167.97 1. 79 1.177E+005 -1. 7 53E+005 5.137E+004 1365.19 3.02 5.934E+004 3.205E+004 2.485E+004 Cs-137 661.66 85.10 l.046E+003 1.05E+003 9.368E+001 4.714E+002 Eu-152 121.78 28.67 3.419E+003 3.19E+003 9.348E+002 1.631E+003 244.7 0 7.61 1.194E+004 8.428E+002 5.590E+003 295.9 4 0.45 2.269E+005 9.805E+004 1. 064E+005 344.28 26.60 3.193E+003 -1.568E+003 l.468E+003 367.79 0.86 9.406E+004 -4.001E+004 4.293E+004 411.12 2.24 3.880E+004 -9.337E+ 003 1.773E+004 443.96 2.83 3.030E+004 -4.824E+003 1. 378E+004 488.68 0.42 2.114E+005 l.378E+005 9.597E+004 563.99 0.49 1 .889E+005 -5.872E+004 8.551E+004 586.26 0.46 2.628E+005 2.479E+005 1.217E+005 678.62 0.47 1.990E+005 1. 744E+004 8.929 E+004 688.67 0.86 l.138E+005 5.862E+0 0 4 5.128E+004 719.35 0.28 3.147E+005 -1. 081E+0 05 1. 396E+005 778.90 12.96 8.135E+003 1. 061E+0 03 3 .671E+003 810.45 0.32 2.640E+005 1. 401E+0 05 1.157E+005 867.37 4.26 2.055E+004 6.048E+003 9.007E+003 919.33 0.43 l .879E+005 -1.428 E+00 4 8.090E+004 964.08 14.65 7.228E+003 2.518E+003 3.223E+003 1085.87 10.24 9.108E+003 4.541E+00 3 3.959E+003 1089. 7 4 1. 73 6.127E+004 5.212E+004 2.711E+004 1112.07 13.69 7.649E+003 1.007E+003 3.374E+003 1212.95 1. 43 8.677E+004 6.228E+004 3.886E+004 [184]
1clide MDA Report 5/1/2017 11 :25: 00 AM Page 6 Nuclide Energy Yield Line MDA Nucl ide MDA Activity Dec. Level Name (keV) ( %) (pCi/Sq M) (pCi/Sq M) (pCi/Sq M) (pCi/Sq M) Eu-152 1249.94 0 .19 5.308E+005 3.19E+003 7.170E+004 2.307E+005 1299.1 4 1. 63 6.114E+004 -6.111E+004 2. 6 46E+004 1408.01 21.07 4.454E+003 -3.561E+003 1 .895E+003 1457.64 0.50 6.409E+005 1.612E+006 3.062E+005 1528.10 0 .28 1. 793E+005 -9.172E+004 6.353E+004 Eu-154 123.07 40.40 2.627E+003 2 . 63E+003 7.095E+001 1. 253E+003 247.93 6.89 1.299E+004 1.680E+003 6.036E+003 591.76 4.95 2.012E+004 -1.218E+004 9.079E+003 692.42 1. 78 6.241E+004 1.610E+004 2.826E+004 723.30 20.06 5.305E+003 2.471E+003 2.386E+003 756.80 4.52 2.366E+004 9.021E+003 1. 062E+004 873.18 12.08 7.651E+003 -4.784E+003 3.340E+003 996.29 10.48 1.044E+004 -3.174E+003 4.618E+003 1004.76 18.01 6.364E+003 1.507E+003 2.831E+003 1274.43 34.80 3.323E+003 1. 770E+003 1.456E+003 1596.48 1. 80 4.749E+004 -1.599E+004 1.919E+004 + Eu-155 45.30 1. 31 7.642E+004 3.53E+003 -1.356E+004 3.607E+004 60.01 1.22 9.397E+004 -4.824E+004 4.469E+004 8 6. 55* 30. 70 3.534E+003 3.223E+003 1.677E+003 105.31 21. 10 6.046E+003 5.407E+ 002 2.889E+003 + Tl-208 583.19* 85. 00 6.002E+002 6.00E+002 8.312E+002 2.542E+002 Bi-211 351.07* 13.02 4.247E+003 4.25E+003 2.483E+003 1 .891E+003 Pb-211 404.85 3.78 1.815E+004 1 .82E+004 -9.363E+003 8.217E+003 427.09 1. 76 4.446E+004 3.948E+002 2.033E+004 832. 01 3.52 2.130E+004 -7.299E+003 9.335E+003 Bi-212 39.86 1.06 6.919E+004 1. 2 0E+004 1.32 5E+004 3. 2 79E+004 727.33 6.67 1. 204E+004 -7.324E+002 5.370E+003 785.37 1. 10 7.709E+004 3.722E+004 3.446E+004 162 0. 5 0 1. 47 5.332E+004 -2.311E+003 2.211E+004 + Pb-212 115.18 0.60 1. 357E+005 1. 56E+003 -7.223E+003 6.456E+004 238.63* 43.60 1. 563E+003 1 .146E+003 7.243E+002 300.09 3.30 2.389E+004 3.332E+003 1.110E+004 Pb212-XR 74.82 10.28 1.177E+004 6.50E+003 2.094E+004 5.702E+003 77 .11 1 7 . 10 6.498E+003 -8.384E+002 3.139E+003 87.35 3.97 2.638E+004 3.293E+003 1. 272E+004 89.78 1. 46 6.542E+004 -2.257E+004 3.143E+004 Bi-2 14 609. 32 45.49 2.855E+0 03 2 .85E+003 3.02 5E+003 l.3 40E+003 768.36 4.89 1 .813E+004 4.496E+002 8.152E+003 806.18 1. 26 5. 850E +004 2.130E+004 2.563E+004 934.06 3. 11 3. 1 51E+004 3.164E+004 1. 41 7E+004 1120.29 14.92 6.96 2E+003 7.051£+002 3.118E+003 1155.21 1. 63 6.226E+004 -2.975E+004 2.776E+004 1238.12 5.83 1 .941E+004 1. 879E+003 8.730E+003 1280.98 1. 43 6.875E+004 3.758E+004 3.033E+004 137 7.67 3.99 2.1 8 3E+004 -1. 680E+003 9.3 97E+003 1385.3 1 0.79 8.969E+004 -4.381E+004 3.7 2 0E+004 1401.52 1. 33 5 .656E+004 - 2 .932E+004 2.369E+0 0 4 1407.99 2.39 3.430E+ 004 -2.742E+004 1 .459E+004 1509.21 2.13 2.909E+004 1. 109E+00 4 1 .154E+00 4 1661. 2 7 1. 0 5 3 .5 32E+0 0 4 4. 8 00E+00 3 1 .117E+004 [185]
1clide MDA Report 5/1/2017 11 :25: 00 AM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/Sq M) (pCi/Sq M) (pCi/Sq M) (pCi/Sq M) Bi-214 1729.59 2.88 2.690E+004 2.85E+003 1.254E+004 1.103E+004 1764.49 15.30 5.946E+003 9.728E+002 2.511E+003 1847.43 2.03 3.174E+004 1.057E+004 1. 229E+004
> 2118. 51 1.16 O.OOOE+D00 O.OOOE+ OOO O.OOOE+OOO Pb-214 241.99* 7.25 9.411E+003 1.56E+003 6.897E+D03 4.360E+003 295.22 18.42 4.881E+003 2.977E+003 2.290E+003 351.93* 35.60 1.555E+003 9.091E+002 6.925E+002 785.96 1. 06 7.721E+004 -3.806E+004 3.435E+004 Pb214-XR 74.82 5.80 2.089E+004 1 .15E+004 3.716E+004 1. 012E+004
- 77. 11 9.70 1. 14 7E+004 -1.480E+003 5.540E+003 87.35 2.24 4.680E+004 5.843E+003 2.256E+004 89.78 0.82 1.166E+005 -4.023E+004 5.602E+004 Ra-226 186.21 3.64 2.200E+004 2.20E+004 -6.314E+003 1.039E+004 Ac-228 129.07 2.42 3.735E+004 3.86E+003 l.488E+004 1.785E+004 209.25 3. 89 2.100E+004 -2.231E+003 9.897E+003 270.24 3. 46 2.299E+004 -3.317E+003 1. 073E+004 328.00 2.95 2.922E+004 -1.555E+004 1.362E+004 338.32 11. 27 7.478E+003 -1.399E+003 3.476E+003 409.46 1. 92 3.895E+004 -1 .087E+004 1.778E+004 463.00 4.40 1.957E+004 1. 246E+004 8.997E+003 794.95 4.25 1.854E+004 4.081E+003 8.204E+003 911. 20 25.80 3.863E+003 -2.903E+002 1. 743E+003 964.77 4.99 1. 925E+004 1.019E+004 8.623E+003 968.97 15.80 6.094E+003 1.833E+D03 2.730E+003 1588.20 3.22 2.524E+D04 4.165E+003 1.057E+004 Pa-231 27.36 10.30 1.067E+004 1.07E+004 2.563E+D03 5.152E+003 283.69 1. 70 4.475E+004 2.293E+004 2.078E+004 300.07 2.47 3.192E+004 4.451E+003 l .483E+004 302.65 2.20 3.390E+004 -1.006£+004 1. 567E+004 330.06 1. 40 6.354E+004 6.756E+003 2.968E+004 Th-234 92.38 2.13 4.468E+016 4 . 44E+016 1.148E+016 2.142E+016 92.80 2.10 4.439£+016 2.639E+015 2.126E+016 112.81 0.21 4.119E+017 9.684E+016 1.963E+017 U-235 143.76 10.96 7.291E+003 1 .44E+003 -1.677E+003 3.459E+003 163.33 5.08 1 .625E+004 8.824E+003 7.707E+D03 185.71 57.20 1 .443E+003 3.572£+002 6.828E+002 202.11 1. 08 6.750E+004 -5.234E+004 3.161E+0 0 4 205.31 5. 01 1 .573E+004 9.525E+002 7.402E+003 Am-241 59.54 3 5 .90 2.194E+003 2 . 19E+003 3.024E+002 1 .043E+ 00 3
+ : Nuclide identified during the nuclide identification * = Energy line found in the spectrum > :: Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated @ = Half-life too short to be able to perform the decay correction
[186]
"************************ ~************************i .k**************** GAMM A S ~ E C T R U M A N A L Y !::> I S ***** .lename: E:\4-27-17\U2NE . CNF iport Generated On 4/27/2017 5: 11 :57 PM Lmple Title B308102BSFJSM001GD Lmple Description U2NE Rl" Lmple Identification Lmple Type Lmple Geometry !ak Locate Threshold 3 . 00 ~ak Locate Range (in channels) 85 - 8192 !ak Area Range (in channels) 85 - 8192 lentification Energy Tolerance 10.000 keV tmple Size 7.800E+001 SQ MET Lmple Taken On 1/28/2013 12:00:00 PM
- quisition Started 9/17/2015 10:36:00 AM
.ve Time 600.0 seconds ial Time 600.4 seconds !ad Time 0 . 06 % Energy Calibration Used Done On 1/27/2015 Efficiency Calibration Used Done On 4/27/2017 Efficiency ID 3M TURBINE [187]
iak Analysis Report 4/27/2017 5: 11 :57 P Page 2 P E A K A N A L Y S I S R E P O R T ***** Detector Name: 5456 Sample
Title:
B308102BSFJSM001GD Peak Analysis Performed on: 4/27/2017 5: 11 :57 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 297- 306 301.19 75.03 0 .59 1 .95E+001 22.58 4.65E+001
= First peak in a multiplet region Other peak in a multiplet region = Fitted singlet
- rors quoted at 2 . 000 sigma
[188]
1terference Corrected Act_ Lty Report 4/27/2017 11 :57 PM Page 3 N U C L I D E I D E N T I F I C A T I O N R E P O R T ***** Sample 'I'itle: B308102BSFJSM001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Li b-BNL.NLB
* "' * * * * * * * * * *
- ti* * .. ' .. * .. IDENTIFIED NUCLIDES
- o; *
- I I t, I* I Nuclide Id Energy Yield Activity Activity Name Confidence (keV} ( %) (pCi/SQ M) Uncertainty
* = Energy line found in the spectrum. @=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0 .30 Errors quoted at 2. 000 sigma
[189]
1terference Corrected Act. ~ ty Report 4 /27/2017 11 :57 PM Page 4 I N T E R F E R E N C E C O R R E C T E D R E P O R T ***** Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/SQ M) Uncertainty
? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis @ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2. 000 sigma ********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 4/27/2017 5: 11 :57 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75.03 3.2431E-002 116.0 6 Tol. Pb214-XR Ba-133 Pb212-XR Pb212-XR Pb214-XR M = First peak in a mult iplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 000 sigma [190]
1clide MDA Report 4/27/201 5:11:57 PM Page 5
- N U C L I D E M DA R E P O R T *****
Detector Name: 5456 Sample Geometry: Sample
Title:
B308102BSFJSM001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/SQ M) (pCi/SQ M) (pCi/SQ M) (pCi/SQ M) K-40 1460.82 10.66 1.394E+004 1.39E+004 1.735E+004 6.381E+003 Cr-51 320.08 9.91 1.519E+014 l.52E+014 l.893E+013 6.772E+013 Mn-54 834.85 99.98 6.027E+003 6.03E+003 O.OOOE+OOO 2.620E+003 Co-58 810.76 99.45 7.816E+006 7.82E+006 -3.010E+006 3.346E+006 Co-60 1173.23 99.85 1. 4 77E+003 1. 48E+003 4.170E+002 6.602E+002 1332.49 99.98 1 .717E+003 1.350E+003 7.748E+002 Nb-94 702.65 99.81 7.272E+002 5.56E+002 1.494E+002 3.208E+002 871.09 99.89 5.564E+002 6.465E+001 2.307E+002 Sn-113 255.13 2. 11 8.494E+006 2.54E+005 -3.711E+006 3.845E+006 391. 70 64.97 2.539E+005 4.132E+004 1 .109E+005 Cs-134 475.36 1. 48 8.829E+004 1.09E+003 2.662E+004 3.838E+004 563.25 8.34 1 .601E+004 7.664E+003 6.892E+003 569.33 15.37 9.287E+003 2.576E+003 4.037E+003 604.72 97. 62 1. 092E+003 - 1 .966E+003 4.476E+002 795.86 85.46 1.245E+003 3.371E+002 4.940E+002 8 01. 95 8.69 1.229E+004 -5.438E+003 4.877E+003 1038.61 0.99 1. 232E+005 9.397E+002 4.888E+004 1167.97 1. 79 1.144E+005 - 1 .012E+005 4.973E+004 1365.19 3.02 4.668E+004 -5.181E+004 1.852E+004 Cs-137 661.66 85. 10 7.460E+002 7.46E+002 -3.851E+002 3.212E+002 Eu-152 121.78 28.67 2.014E+003 2.01E+003 -9.279E+002 9.283E+002 244.70 7.61 8.278E+003 -1.1 1 2E+003 3.759E+003 295.94 0.45 1.233E+005 -8.299E+ 004 5.456E+004 344.28 26.60 2.380E+003 -3.433E+002 l. 061E+003 367.79 0.86 8.679E+004 3.420E+004 3.929E+004 411 .12 2.24 2.408E+004 1 .070E+003 1. 037E+004 443.96 2.83 2.388E+004 3.225E+003 1.057E+004 488.68 0.42 1.612E+005 5.7 25E+004 7.088E+004 563.99 0.49 1.243E+005 -1.095E+005 5.32 0E+004 586.26 0.46 1 .613E+ 00 5 4 .490E+004 7.091E+004 678.62 0.47 1 .062E+005 4.516E+004 4, 2 89E+004 688. 67 0.86 7.256E+004 6.873E+003 3.0 6 4E+004 719.35 0 .28 2.376E+005 8.067E+ 004 1 .0llE+OOS 778.9 0 12.96 6.414E+003 -2.456E+00 2 2 .811E+003 810.45 0 .32 2.349E+005 -7. 2 59E+004 1.011E+005 867.37 4.26 1.231E+004 -9.765E+003 4.884E +003 919.33 0 .43 1.940E+005 4.443E+004 8.3 95E+004 964.08 14 . 65 6.484E+003 1.685E+002 2.851E+003 1085.87 10 .24 7.970E+003 - 8.948E+003 3.3 91E+003 1089.7 4 1. 73 4 .905E+004 5.646E+003 2.1 0 0E+0 04 1 112 .0 7 13.69 4.69 2E+00 3 -5. 2 68E+002 1. 8 96E+0 03 1212.95 1. 43 4.71 2E+004 2. 00 5E+ 004 1 . 90 4E+004 [191]
1clide MDA Report 4/27/201 5: 11 :57 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/SQ M) (pCi/SQ M) (pCi/SQ M) (pCi/SQ M) Eu-152 1249.94 0.19 2.757E+005 2.01E+003 -7.042E+004 1 .032E+005 1299.14 1. 63 5.294£+004 3.039E+004 2.236E+004 1408.01 21.07 2.644E+003 7.368E+002 9.896E+002 1457.64 0.50 3.414E+005 4.307E+005 1.565E+005 1528.10 0.28 5.225E+004 O.OOOE+OOO O.OOOE+OOO Eu-154 123.07 40.40 1.607E+003 1 . 61E+003 -5.324E+002 7.431E+002 247.93 6.89 9.805E+003 2.507E+002 4.445E+003 591.76 4.95 1.314E+004 3.657E+003 5.592E+003 6 92. 4 2 1. 78 4.521E+004 6.871E+003 1.965E+004 723.30 20.06 3.289E+003 -1. 480E+002 l.377E+003 756.80 4.52 1. 263E+004 -1. 425E+004 5.101E+003 873.18 12.08 5.695E+003 -3.690E+003 2.362E+003 996.29 10.48 7.397E+003 3.995E+003 3.098E+003 1004.76 18.01 2.793E+003 7.783E+002 1.045E+003 1274.43 34.80 2.141E+003 9.108E+002 8.651E+002 1596.48 1. 80 3.624E+004 -2.020E+004 1.357E+004 Eu-155 45.30 1. 31 4.593E+004 2 . 72E+003 9.049E+003 2.082E+004 60.0 1 1. 22 4.248E+004 -5.149E+003 1.894E+004 86.55 30.70 2.719E+003 1.290E+003 1.270E+003 105.31 21.10 3.035E+003 -1.561E+003 l.383E+003 Tl-208 583.19 85. 00 7.789E+002 7.79E+002 -6.688E+OOO 3.436E+002 Bi-211 351.07 13.02 5.695E+003 5.69E+003 6.687E+003 2.615E+003 Pb-211 404.85 3.78 1.492E+004 l.49E+004 8.073E+003 6.600E+003 427.09 1. 76 3.217E+004 7.643E+003 1.419E+004 832.01 3.52 2.075E+004 9.915E+003 9.056E+003 Bi-212 39. 8 6 1. 06 2.761E+004 8.02E+003 -3.685E+004 1 . 2 00E+004 727.33 6.67 8.021E+003 -1.604E+003 3.359E+003 785.37 1.10 5.483E+004 2.267E+003 2.333E+004 1620.50 1. 47 4 .037E+004 -8.402E+003 1 .564E+004 Pb-212 115.18 0. 60 7.791E+004 1.41E+003 -1.812E+004 3.567E+004 238.63 43.60 1.407E+003 6.008E+002 6.464E+002 300.09 3.30 1.536E+004 -1.049E+004 6.835E+003 Pb212-XR 74.82 10.28 7.639E+003 3.85E+003 1.335E+004 3.636E+003 77.1 1 17.10 3 . 851E+003 -9.547E+002 1 .816E+003 87.35 3.97 1. 402E+004 5.291E+003 6.537E+003 89.78 1. 46 3.596E +004 -2.470E+004 1 .669E+004 Bi-214 609.32 45.49 1.381E+003 1. 38E+003 -3.351E+002 6.029E+002 768.36 4.89 1.514E+004 -1.611E+003 6.656E+003 806.18 1.26 5.206E+004 2.282E+004 2.242E+004 934.06 3.11 2.126E+004 -4.661E+003 9.043E+003 1120.29 14.92 5.393E+003 7.373E+002 2.334E+003 1155.2 1 1. 63 2.989E+004 -l.400E+003 1.158E+004 1238.12 5.83 1.018E+004 5.416E+002 4.115E+003 1280.98 1. 43 3.593E+004 1.196E+004 l.392E+004 1377.67 3 .99 l.580E+004 6 .7 22 E+003 6.384E+003 1385.31 0.79 4.160E+004 -l.385E+005 1. 315E+004 1401. 52 1. 33 3 .654E+004 l.018E+004 1. 368E+004 1407 .99 2.39 2.036E+004 5.673E+003 7.619E+003 1509.21 2.13 2.060E +004 4.438E+003 7.300E+003 1661. 27 1.05 4.457E+004 9.599E+003 1. 579E+004 [192]
1clide MDA Report 4/27/201 5:11:57 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/SQ M) (pCi/SQ M) (pCi/SQ M) (pCi/SQ M) Bi-214 1729.59 2.88 2.152E+004 1. 38E+003 7.166E+003 8.336E+003 1764.49 15.30 6.191E+003 3.755E+003 2.634E+003 1847.43 2.03 2.844E+004 7.927E+003 1.065E+004
> 2118.5 1 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO Pb-214 241.99 7.25 8.531E+003 1. 95E+003 2.546E+003 3.918E+003 295.22 18.42 2.562E+003 -2.315E+003 1.130E+003 351.93 35.60 1 .949E+003 4.510E+002 8.894E+002 785.96 1. 06 5.246E+004 -6.313E+004 2.197E+004 Pb214-XR 74.82 5.80 1 .356E+004 6.80E+003 2.369E+004 6.452E+003 77.1 1 9.70 6.797E+003 -1.685E+003 3.204E+003 87.35 2.24 2.487E+004 9.387E+003 1. 160E+004 89.78 0.82 6.410E+004 -4.403E+004 2.976E+004 Ra-226 186.21 3.64 1 .606E+004 1.61E+004 4.013E+003 7.422E+003 Ac-228 129.07 2.42 2.213E+004 3.41E+003 8.237E+003 1.024E+004 209.25 3.89 1. 4 97E+004 -1 .595E+004 6.882E+003 270.24 3.46 1. 242E+004 -1 .312E+004 5.443E+003 328.00 2.95 1 .721E+004 -1 .672E+004 7.615E+003 338.32 11. 27 5.565E+003 1.762E+003 2.519E+003 409.46 1. 92 2.750E+004 -4.415E+003 1.205E+004 463.00 4.40 1.371E+004 -4.066E+003 6.066E+003 794.95 4.25 1.034E+004 4.731E+002 4.102E+003 911. 20 25.80 3.413E+003 1.635E+003 1 .518E+003 964.77 4.99 1.664E+004 3.295E+002 7.317E+003 968.97 15.80 5.003E+003 -9.167E+002 2.184E+003 1588.20 3.22 1.819E+004 6.059E+003 7.047E+003 Pa-231 27.36 10.30 5.057E+003 5 . 06E+003 7.298E+002 2.343E+003 283.69 1. 70 2.901E+004 3.938E+003 l.291E+004 300.07 2.47 2.053E+004 -1.402E+004 9.131E+003 302.65 2 .20 2.699E+004 1.131E+004 1. 222E+004 330.06 1. 40 3.945E+004 -6.252E+003 1. 763E+004 Th-234 92.38 2.13 2.649E+016 2 . 63E+016 2. 781E+016 1. 233E+016 92.80 2.10 2.626E+016 2.026E+016 1.220E+016 112.8 1 0 .21 2.361E+017 1. 288E+017 1.084E+017 U-235 143.76 10 .96 4.730E+003 1.02E+003 -9.678E+002 2.178E+003 163.33 5.08 1 .004E+004 3.182E+003 4.602E+003 185.71 57.20 1 .020E+003 3.597E+002 4.712E+002 202. 11 1.08 5.413E+004 9.281E+003 2.493E+004 205.31 5.01 1.115E+004 -8.090E+003 5.111E+003 Am-241 59.54 35.90 9.489E+002 9.49E+002 1 .114E+002 4.210E+002 + = Nuclide identified during the nuclide identification * = Ene rgy line found in the spectrum > Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated @ = Half-life too short to be able to perform the decay correctio n
[193]
G A MMA S P E C T R U M A N A L Y S I S ***** .lename: E:\4-27-17\U2NW .CNF iport Generated On 4/27/2017 5:21: 07 PM 1mple Title B308102BSFJSM002GD 1mple Description U2NW Rl 1mple Identification 1mple Type 1mple Geometry iak Locate Threshold 3 . 00 iak Locate Range (in channels ) 85 - 8192 iak Area Range (in channels) 85 - 8192 lentification Energy Tolerance 10.000 keV 1mple Size 1.000E+000 SQM 1mple Taken On 1/28/2013 12:00:00 PM
- quisition Started 9/17/2015 11:45:37 AM
.ve Time 600. 0 seconds ial Time 600.5 seconds iad Time 0 . 08 % Energy Calibration Used Done On 1/27/2015 Efficiency Calibration Used Done On 4/27/2017 Efficiency ID 3M TURBINE [194]
!ak Analysis Report 4/27/20 17 5:21: 07 F Page 2 P E A K A N A L Y S I S R E P O R T ***** Detector Name: 5456 Sample
Title:
B308102BSFJSM002GD Peak Analysis Performed on: 4/27/2017 5:21: 07 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 4685- 4702 4693.76 1173.07 1. 14 9.90E+001 19.90 0 .00E+000 2 5322- 5340 5330.69 1332.14 1. 83 8.30E+001 18.22 0 .00E+000 3 5839- 5850 5844.24 1460.37 0.38 2.39E+001 11. 38 3.15E+000
= First peak in a multiplet region Other peak in a multiplet region - Fitted singlet
- rors quoted at 2 .000 sigma
[195]
1terference Corrected Act. Lty Report 4/27/2017 21:08 PM Page 3 N U C L I D E I D E N T I F I C A T I O N R E P O R T *****
- i************************************************************ * ***
Sample
Title:
B308102BSFJSM002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/SQM ) Uncertainty K-40 1 . 000 1460.82* 10.66 8.06759E+005 3.91 2 65E+005 Co-60 0.999 1173.23* 99.85 4.47300E+005 9.67703E+004 1332.49* 99.98 4.00353E+005 9.35430E+004
* ~ Energy line found in the spectrum. @: Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2 .000 sigma
[196]
1terference Corrected Act. Lty Report 4/27/2017 21: 08 PM Page 4 I N T E R F E R E N C E C OR R E C T E D R E P O R T ***** Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/SQM) Uncertainty K-40 1. 000 8.067592E+005 3.912650E+005 Co-60 0.999 4.230307E+005 6.725688E+004
? ~ Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysis @ = Nuclide contains energy lines not used i n Weighted Mean Activity Errors quoted at 2. 000 sigma ********** U N I D E N T I F I E D P E A K S **********
Peak Locate Performed on: 4/27/2017 5 :21: 07 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol. No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified. [197]
1clide MDA Report 4/27/201 5:21:08 PM Page 5 '*** N U C L I D E MD A R E P O R T ***** Detector Name: 5456 Sample Geometr~': Sample
Title:
B308102BSFJSM002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/SQM) (pCi/SQM ) (pCi/SQM ) (pCi/SQM )
+ K-40 1460.82* 10.66 4.165E+005 4.17E+005 8.068E+005 1 .625E+005 Cr-51 320.08 9.91 1.186E+016 1 .19E+016 -7.945E+015 5.289E+015 Mn-54 834.85 99.98 4.114E+005 4.11E+005 -1.882E+005 1. 750E+005 Co-58 810.76 99.45 7.093E+008 7.09E+008 -1.187E+008 3.108E+008 + Co-60 1173.23* 99.85 1.223E+004 1 .22E+004 4.473E+005 0.000E+000 1332.49* 99.98 1 .305E+004 4.004E+005 0.000E+000 Nb-94 702.65 99.81 4.963E+004 4.96E+ 004 -1.745E+004 2.148E+004 871.09 99. 89 6.139E+004 2.120E+004 2.700E+004 Sn-113 255.13 2. 11 7.528E+008 2.58E+007 -4.059E+008 3.450E+008 391.70 64.97 2.580E+007 8.670E+006 1 .164E+007 Cs-134 475.36 1. 48 7.638E+006 1 . 42E+005 -4.154E+006 3.369E+006 563.25 8.34 1.473E+006 9.614E+004 6.499E+005 569.33 1 5 .37 7.030E+005 -5.767E+005 3.042E+005 604.72 97. 62 1.419E+005 -5.167E+004 6.328E+004 795.86 85.46 l .535E+005 2.543E+004 6.674E+004 8 01.95 8.69 1.425E+006 -7.468E+005 6.135E+005 1038.61 0.99 1.724E+007 -3.353E+ 006 7.626E+006 1167.97 1. 79 2.110E+007 -1.307E+006 9.965E+006 1365.19 3.02 4 .628E+006 2.500E+006 1 .938E+006 Cs-137 661.66 85. 10 7.177E+004 7 . 18E+004 3.179E+004 3.184E+004 Eu-152 121.78 2 8.67 1 .852E+005 1.85E+005 9.238E +004 8.646E+004 244. 70 7.61 7.516E+005 1.948E+005 3.461E+005 295.94 0.45 1 .329E+007 -2.56 1 E+006 6.093E+006 344.28 26.60 1 .961E+005 -1.521E+005 8.801E+004 367.79 0 .86 6.770E+006 -3.673E+006 3.065E+006 411.12 2.24 2.549E+006 1.324E+006 1.144E+006 443.96 2.83 1 .689E+006 -1.406E+006 7.372E+005 488.68 0.42 1 .317E+007 -5.041E+005 5.828E+006 563.99 0.49 1 .156E+007 -1.960E+006 5.082E+006 586.2 6 0.46 1 .161E+007 - 2 . 2 42E+ 005 5 .049E+006 678.62 0.47 1 .350E+007 7.872E+006 5.954E+006 688. 67 0.86 6.926E +006 3.569E+ 00 6 3.02 3E+00 6 71 9 .35 0.28 2.402E+007 5.108E+005 1. 0 63E+00 7 778 . 9 0 12.96 5.254E+005 3.242E+005 2 .318E+005 81 0.45 0.32 2.1 11E+007 1.199E+007 9. 2 84E+006 867.37 4.26 1 .722E+006 -3.992 E+005 7. 62 0E+00 5 91 9. 33 0.43 1 .769E+007 7.203E+006 7.826E+006 964.08 14. 65 5.179E+005 -8.301E+004 2. 285E+005 1085.87 10.24 6.217E+005 4.3 62E+004 2.645E+005 1089.7 4 1. 73 4. 2 1 3E+006 2 .104E+00 6 1.831E+006 1112 .07 13.69 5.532E+005 -2.733 E+ 005 2.41 5E+005 1212 .95 1. 43 5.704E+006 3. 2 34E+00 6 2.500E+006
[198]
iclide MDA Report 4/27/201 5:21:08 PM Page 6 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/SQM ) (pCi/SQM) (pCi/SQM ) (pCi/SQM ) Eu-152 1249.94 0.19 2.999E+007 1.85E+005 1.398E+007 1.229E+007 1299.14 1. 63 4.769E+006 1.439E+006 2.064E+006 1408.01 21.07 2.876E+005 2.394E+004 1.179E+005 1457.64 0.50 2.310E+007 1. 709E+007 1. 044E+007 1528.10 0.28 1.975E+007 7.531E+006 7.835E+006 Eu-154 123.07 40.40 1. 393E+005 1. 39E+005 2.272E+004 6.493E+004 247.93 6.89 9.46BE+005 5.797E+005 4.378E+005 591. 76 4.95 1. 205E+006 1.590E+005 5.260E+005 692.42 1. 78 3.086E+006 -3.171E+005 l.313E+006 723.30 20.06 3.851E+005 -2.091E+004 1.717E+005 756.80 4.52 l.314E+006 -5.935E+005 5.627E+005 873.18 12.08 6.128E+005 l.589E+005 2.685E+005 996.29 10.48 7.381E+005 1.645E+005 3.222E+005 1004.76 18. 01 4.758E+005 3.048E+005 2. 1 05E+005 1274.43 34.80 1.670E+005 7.105E+004 6.748E+004 1596.48 1. 80 2.827E+006 7.879E+005 1.058E+006 Eu-155 45.30 1.31 5.566E+006 2 . 39E+005 1. 420E+006 2.616E+006 60.01 1.22 5.587E+006 -3.720E+006 2.614E+006 86.55 30.70 2.393E+005 4.457E+004 1.127E+005 105.31 21.10 2.877E+005 2.713E+004 1.334E+005 Tl-208 583.19 85.00 5.478E+004 5.48E+004 2.850E+004 2.381E+004 Bi-211 351.07 13.02 4.489E+005 4.49E+005 1 .286E+005 2.064E+005 Pb-211 404.85 3.78 1. 285E+006 1. 29E+006 -2.187E+005 5.756E+005 427.09 1. 76 2.835E+006 -1.390E+006 l.270E+006 832.0 1 3.52 1.527E+006 -3.036E+005 6.608E+005 Bi-212 39. 8 6 1. 06 4.087E+006 9.57E+005 -3.263E+005 1. 903E+006 727.33 6.67 9.573E+005 -5.905E+004 4.279E+005 785.37 1.10 5.421E+006 4.480E+006 2.391E+006 1620.50 1. 47 2.434E+006 5.243E+005 8.624E+005 Pb-212 115.18 0.60 6.918E+006 1. 27E+005 -3.279E+006 3.203E+006 238.63 43.60 1.271E+005 8.501E+004 5.906E+004 300.09 3.30 1. 552E+OO 6 -1.013E+006 7.098E+005 Pb212-XR 74.82 10 .28 6.189E+005 3.47E+005 9.273E+005 2.951E+005 77.11 17.10 3.473E+005 2.454E+005 1. 651E+005 87.35 3.97 1.240E+006 2.252E+005 5.830E+005 89.78 1. 46 3.127E+006 -6.940E+005 1. 463E+006 Bi-214 609.32 45.49 1.312E+005 1. 31E+005 -4.007E+004 5.878E+004 768.36 4 .89 1. 264E+006 2.818E+005 5.608E+005 806.18 1. 26 4.061E+006 -2.493E +006 1. 748E +006 934.06 3. 11 1 .895E+006 -1.440E+006 8.236E+005 1120.29 14.92 5.025E+005 4.391E+005 2.229E+005 1155.21 1. 63 3. 234E +006. 5.553E+005 1. 355E+006 1238.12 5.83 1.097E+006 7.041E+004 4.725E+005 1280.98 1. 43 2.166E+006 -2.275E+006 7.675E+005 1377.67 3.99 1.232E+006 5.243E+005 4.979E+005 1385.31 0.79 5.780E+006 2.205E+006 2.294E+006 1401. 52 1. 33 3.180E+006 -1.026E+006 1.232E+ 006 1407.99 2.39 2.215E+006 1 .844E+005 9.078E+005 1509.21 2.13 1.607E+006 3.461E+005 5.694E +0 05 1661.2 7 1.05 4 .497 E+006 1. 49 7E+006 1. 7 42E +00 6 [199]
1clide MDA Report 4/27/201 5:21:08 PM Page 7 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/SQM) (pCi/SQM ) (pCi/SQM ) (pCi/SQM) Bi-214 1729.59 2.88 1. 298E+006 1. 31E+005 2.795E+005 4.598E+005 1764.49 15.30 3.198E+005 1.065E+005 1. 239E+005 1847.43 2.03 2.219E+006 6.183E+005 8.304E+005
> 2118.51 1. 16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO Pb-214 241.99 7.25 7.579E+005 1.70E+005 3.257E+005 3.518E+005 295.22 18.42 2.918E+005 1.948E+005 1 .341E+005 351.93 35.60 1 .696E+005 1 .891E+004 7.819E+004 785.96 1. 06 5.234E+006 -2.839E+005 2.285E+006 Pb214-XR 74.82 5.80 1.098E+006 6.13E+005 1.645E+006 5.237E+005
- 77. 11 9.70 6.130E+005 4.330E+005 2.913E+005 87.35 2.24 2.200E+006 3.996E+005 1.035E+006 89.78 0 .82 5.575E+006 -1.237E+006 2.609E+006 Ra-226 186.21 3.64 1. 265E+006 1.26E+006 -9.488E+003 5.847E+005 Ac-228 129.07 2.42 1.942E+006 2.38E+005 9.653E+005 9.065E+005 209.25 3.89 1. 2 61E+00 6 -5.443E+005 5.835E+005 270.24 3.46 1.229E+006 -3.621E+005 5.546E+005 328.00 2.95 1.703E+006 1.016E+006 7.744E+005 338.32 11.27 4.341E+005 1.208E+005 1.965E+005 409.46 1. 92 2.544E+006 -1.157E+006 1. 140E+006 463.00 4.40 1.243E+006 -1.851E+005 5.598E+005 794.95 4.25 1. 275E+006 -1 .143E+006 5.542E+005 911. 20 25.80 2.376E+005 -9.305E+004 1. 041E+005 964.77 4.99 1.360E+006 -4.200E+005 6.016E+005 968.97 15.80 4.208E+005 2.408E+005 1.856E+005 1588.20 3.22 1. 874E+006 9.451E+005 7.774E+005 Pa-231 27.36 10.30 4.300E+005 4 . 30E+005 -3.747E+005 2.005E+005 283.69 1. 70 3.097E+006 1.561E+006 1 .424E+006 300.07 2.47 2.073E+006 -1.353E+006 9.483E+005 302.65 2.20 2.254E+006 -1.748E+005 1.027E+006 330.06 1. 40 3.134E+006 1 .303E+005 1.404E+006 Th-234 92.38 2.13 2.221E+018 2 . 18E+018 1 .462E+018 1.039E+018 92.80 2.10 2.178E+018 1. 239E+Ol 7 1.016E+018 112.81 0.21 2.233E+019 8.309E+018 1. 041E+019 U-235 143.76 10.96 3.614E+005 8.03E+004 -1.319E+0 0 5 1. 66 2E+005 163.33 5.08 7.743E+005 -2.373E+0 05 3.545E+005 185.71 57.20 8.028E+004 4.479E+0 0 3 3.712E+004 202.11 1. 08 4 .347E+006 7.865E+D 0 5 2 .00 7E+006 205.31 5. 01 9.789E+005 -4.784E+0 0 4 4.533E+005 Am-24 1 59.5 4 35.90 1. 333E+005 1. 33E+005 -6.839E+0 0 3 6.247E+004
+ = Nuclide identified during the nuclide identification
- Energy line found in the spectrum
> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated @ :::: Half - life too short to b e able to perform the d e cay correction
[200]
ATTACHMENT 8 EBERLINE ANALYTICAL REPORTS [217]
EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD
- - EBER LINE OAK RIDGE, TENNESSEE 37830 PHONE (865) 481--0683
.~ ANALYTICAL FAX (865) 483-1+621 EBS-OR-47182 May 8, 2020 Gerald Wood Zion Solutions, LLC 2701 Deborah Avenue Zion, IL 60099 CASE NARRATIVE Work Order # 20-04072-OR SAMPLE RECEIPT This work order contains nine solid samples received 04/25/2020. Samples were analyzed for Isotopic Plutonium, Plutonium-241, Neptunium-237, Americium~241/243, Curium-243/244, Total Strontium, Technetium-99, Tritium, Carbon-14, Promethium-147, Nickel-59/63, Iron-55 and by Gamma Spectroscopy.
CLIENT ID LABID CLIENT ID LAB ID B 1-06202A-FSWC-040-CV 20-04072-04 B2-08201-CJWC-A0 18-CV 0 5-1 0 20-04072-09 B l-06214A-FSFC-00 1-CV 20-04072-05 L2- l 02 l 4C-RJGS-00 1-SM-A 20-04072-10 B2-08101A-BJFC-007-CV 0 0-0 5 20-04072-06 Ll-12109L-CJGS-0 01-SB-A 20-04072-11 B2-08101A-BJFC-007-CV 0 5-1 0 20-04072-07 Ll-12106L-CJGS-0 0 1-SB-A 20-04072-12 B2-08201-CJWC-A018-CV 0 0-0 5 20-04072-08 ANALYTICAL METHODS Isotopic Plutonium and Plutonium-241 were analyzed using Method EML Pu-02 Modified. Neptunium-237 was analyzed using EIChroM Method ACW08 Modified. Americium and Curium were analyzed using Method EML Am-01 Modified. Total Strontium was analyzed using EIChroM Method SRW0l Modified. Technetium-99 was analyzed using EIChroM Method TCS0l Modified. Tritium was performed using Method LANL ER-210 Modified. Carbon-14 was perfonned using EPA Method 520.0 Modified. Promethium-147 was performed using Method EML Pm-01 Modified. Nickel-59/63 was performed using Method ASTM 3500-Ni Modified. Iron-55 was performed using EML Method Fe-01-01 Modified. Gamma Spectroscopy was performed using EPA Method 901.1 Modified. Laboratory qualifiers are as follows: U - Result is less than the MDA. ANALYTICAL RESULTS Combined Standard Uncertainty is reported at 1-sigma value. Page 1 of 6
ANALYTICAL RESULTS CONTINUED Minimum Detectable Activity (MDA) values for data represented in this report are sample-specific. MDA measurements are determined based on factors and conditions including instrument settings, aliquot size and matrix type. ISOTOPIC PLUTONIUM Samples were prepared by removing representative aliquots followed by mixed acid digestions as appropriate. Plutonium was selectively extracted by ion exchange. Plutonium was eluted, micro-precipitated and mounted on micro-porous filter media. Sample activities were determined by alpha spectroscopy using energy specific regions of interest for Plutonium-238 and Plutonium-239. Chemical recovery was determined using a Plutonium-242 tracer. Activity of the Plutonium-242 tracer was determined by alpha spectroscopy using an energy specific region of interest. Samples demonstrated acceptable results for all Plutonium analyses Chemical recovery was acceptable for all samples. The Plutonium-238 and Plutonium-239/240 method blank demonstrated acceptable results. Results for the Plutonium-238 and Plutonium-239/240 duplicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Plutonium-238 and Plutonium-239 laboratory control sample demonstrated an acceptable percent recovery. PLUTONIUM-241 Following sample analysis for Isotopic Plutonium, filter media used was dissolved. Dissolved samples were placed into scintillation vials, scintillation cocktail was added and Plutonium-241 was detennined by liquid scintillation counting. Analytical tracer recovery was determined by yields from the Isotopic Plutonium tracer. Samples demonstrated acceptable results for all Plutonium-241 analyses. All sample results demonstrated slightly high method detection limits. Chemical recovery was acceptable for all samples. The Plutonium-241 method blank demonstrated an acceptable result. Results for the Plutonium-241 duplicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Plutonium-241 laboratory control sample demonstrated an acceptable percent recovery. NEPTUNIUM-23 7 Samples were prepared by removing representative aliquots followed by mixed acid digestions as appropriate. Sample residues were dissolved in dilute acid and Neptunium was selectively separated using EIChroM stabilized selective resins. Neptunium was eluted, micro-precipitated and mounted on micro-porous filter media. Sample activities were determined by alpha spectroscopy using an energy specific region of interest for Neptunium-237 activity. A Neptunium-239 tracer was used for chemical yields, which was determined by beta proportional counting. Samples demonstrated acceptable results for all Neptunium-237 analyses. Chemical recovery was acceptable for all samples. The Neptunium-237 method blank demonstrated an acceptable result. Results for the Neptunium-237 duplicate demonstrated a high relative percent difference; however, nonnalized difference is within acceptable limits for the analytical technique. Results for the Neptunium-237 laboratory control sample demonstrated an acceptable percent recovery. Page 2 of 6
ANALYTICAL RESULTS CONTINUED AMERICIUM-241 Samples were prepared by removing representative aliquots followed by mixed acid digestions as appropriate. Samples were co-precipitated with Calcium Phosphate. Precipitates were nitrate converted using Nitric acid and Aluminum Nitrate. The Americium fractions were separated from other elements using the EIChroM, TRU and UTEVA resins. The separated Americium fractions were mounted on a membrane filter by micro-precipitation and counted on the alpha spectroscopy system. Analytical tracer recovery was determined using an Americium-243 standard and subsequent activity determination by alpha spectroscopy. Samples demonstrated acceptable results for all Americium-241 analyses. Chemical recovery was acceptable for all samples. The Americium-241 method blank demonstrated an acceptable result. Results for the Americium-241 duplicate demonstrated an acceptable relative percent difference and normalized difference. Results for the Americium-241 laboratory control sample demonstrated an acceptable percent recovery. AMERICIUM-243 Samples were prepared by removing representative aliquots followed by mixed acid digestions as appropriate. Samples were co-precipitated with Calcium Phosphate. Precipitates were nitrate converted using Nitric acid and Aluminum Nitrate. The Americium fractions were separated from other elements using the EIChroM, TRU and UTEV A resins. The separated Americium fractions were mounted on a membrane filter by micro-precipitation and counted on the alpha spectroscopy system. Analytical tracer recovery was determined using a Curium-244 standard and subsequent activity determination by alpha spectroscopy. Samples demonstrated acceptable results for all Americium-243 analyses. Chemical recovery was low for laboratory fraction -06 (Client ID: B2-08101A-BJFC-007-CV O 0-0 5). Chemical recovery was acceptable for all other samples. The Americium-243 method blank demonstrated an acceptable result. Results for the Americium-243 duplicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Americium-243 laboratory control sample demonstrated an acceptable percent recovery. CURIUM-243/244 Samples were prepared by removing representative aliquots followed by mixed acid digestions as appropriate. Samples were co-precipitated with Calcium Phosphate. Precipitates were nitrate converted using Nitric acid and Aluminum Nitrate. The Curium fractions were separated from other elements using the EIChroM, TRU and UTEV A resins. The separated Curium fractions were mounted on a membrane filter by micro-precipitation and counted on the alpha spectroscopy system. Analytical tracer recovery was determined using an Americium-243 standard and subsequent activity determination by alpha spectroscopy. Samples demonstrated acceptable results for all Curium-243/244 analyses. Chemical recovery was acceptable for all samples. The Curium-243/244 method blank demonstrated an acceptable result. Results for the Curium-243/244 duplicate demonstrated an acceptable relative percent difference and normalized difference. Results for the Curium-244 laboratory control sample demonstrated an acceptable percent recovery. Page 3 of 6
ANALYTICAL RESULTS CONTINUED TOTAL STRONTIUM Samples were prepared by acid digestion as appropriate for the matrix. Digested samples were acidified and selectively extracted and precipitated. Precipitates were then mounted on 47mm filters. Filters were reweighed to detennine aliquot size. Sample activities were determined by gas flow proportional counting. Samples demonstrated acceptable results for all Total Strontium analyses. Strontium-90 is reported from Total Strontium assuming secular equilibrium. Chemical recovery was acceptable for all samples. The Total Strontium method blank demonstrated an acceptable result. Results for the Total Strontium duplicate demonstrated a high relative percent difference; however, nonnalized difference is within acceptable limits for the analytical technique. Results for the Total Strontium laboratory control sample demonstrated an acceptable percent recovery. TECHNETIUM-99 A representative aliquot was removed from each sample followed by leaching in acids. Samples were prepared by oxidative reactions with Nitric acid and Hydrogen Peroxide. After complete oxidization, Technetium was selectively extracted using EIChroM stabilized resins. Special cleanup chemistry was conducted for complete removal of interferences associated with Uranium. Processed resins were transferred to liquid scintillation vials, scintillation cocktail was added, and samples were counted by beta liquid scintillation. Samples demonstrated acceptable results for all Technetium-99 analyses. The Technetium-99 method blank demonstrated an acceptable result. Results for the Technetium-99 duplicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Technetium-99 laboratory control sample demonstrated an acceptable percent recovery. TRITIUM A representative aliquot of each sample was equilibrated with Tritium free water. Equilibrates were transferred into round-bottomed distillation flasks and attached to single stage stills. A portion of each middle distillation fraction was transferred to a liquid scintillation vial and cocktail was added. Samples were counted by beta liquid scintillation. Samples demonstrated acceptable results for all Tritium analyses. The Tritium method blank demonstrated an acceptable result. Results for the Tritium duplicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Tritium laboratory control sample demonstrated an acceptable percent recovery. CARBON-14 A representative aliquot of each sample was placed into a I-liter reaction vessel. A carbonate solution was added. Samples were oxidized using Potassium Permanganate. Carbon Dioxide was evolved and Carbon-14 was captured into Harvey brand, Carb-Sorb cocktail. Carbon-14 beta emissions were then determined by beta liquid scintillation using an energy selective region. Page 4 of 6
ANALYTICAL RESULTS CONTINUED CARBON-14 CONTINUED Samples demonstrated acceptable results for all Carbon-14 analyses. The Carbon-14 method blank demonstrated an acceptable result. Results for the Carbon-14 duplicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Carbon-14 laboratory control sample demonstrated an acceptable percent recovery. PROMETHIUM-147 Samples were prepared by leaching in HNO3. Aliquots were taken to near dryness. Sample residues were dissolved in deionized water. The pH of each sample was adjusted with HNO3. Samples were extracted with scintillation extractant. Organic phase of each sample was transferred to scintillation vials. Promethium-14 7 was determined by liquid scintillation counting. Samples demonstrated acceptable results for all Promethium-147 analyses. The Promethium-147 method blank demonstrated an acceptable result. Results for the Promethium-14 7 duplicate demonstrated an acceptable relative percent difference and normalized difference. Results for the Promethium-147 laboratory control sample demonstrated an acceptable percent recovery. NICKEL-63 A representative aliquot of each sample was prepared by leaching in acids. Aliquots were placed into appropriately sized beakers. Stable elemental Nickel carrier was added to each sample prior to digestion. Samples were digested in concentrated Nitric acid. After digestion, each sample pH was adjusted and Nickel-63 was precipitated selectively with Dimethylglyoxime. Precipitates were selectively separated, redissolved, and residual acid was effectively neutralized. Sample residuals were placed into scintillation vials, scintillation cocktail was added, and Nickel-63 activity was determined by beta liquid scintillation. Samples demonstrated acceptable results for all Nickel-63 analyses. The Nickel-63 method blank demonstrated an acceptable result. Results for the Nickel-63 duplicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Nickel-63 laboratory control sample demonstrated an acceptable percent recovery. NICKEL-59 Representative aliquots were removed from samples and placed into Petri geometry containers. Samples were counted by low-energy photon spectroscopy. Samples demonstrated acceptable results for all Nickel-59 analyses. The Nickel-59 method blank demonstrated an acceptable result. Results for the Nickel-59 replicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the lron-55 laborato1y control sample demonstrated a statistically acceptable percent recovery. Page 5 of 6
ANALYTICAL RESULTS CONTINUED IRON-55 Representative aliquots were removed from samples and placed into Petri geometry containers. Samples were counted by low-energy photon spectroscopy. Samples demonstrated acceptable results for all Iron-55 analyses. The Iron-55 method blank demonstrated an acceptable result. Results for the Iron-55 replicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Iron-55 laboratory control sample demonstrated an acceptable percent recovery. GAMMA SPECTROSCOPY Samples for Gamma Spectroscopy analysis were prepared by transferring a known mass of each homogenized sample to a standard geometry container. Samples were counted on High Purity Germanium (HPGe) gamma ray detectors. Samples demonstrated acceptable results for all gamma-emitting radionuclides as reported. Cobalt-60 results for laboratory fraction -08 (Client ID: B2-08201-CJWC-A0 18-CV 0 0-0 5) demonstrated a slightly high method detection limit. The method blank demonstrated acceptable results for all radionuclides as reported. Results for the Bismuth-214 and Potassium-40 replicate demonstrated an acceptable relative percent difference and normalized difference. Results for the Thorium-234 replicate demonstrated a high relative percent; however, normalized difference is within acceptable limits for the analytical technique. Results for the Cobalt-60 and Cesium-137 laboratory control sample demonstrated an acceptable percent recovery. CERTIFICATION OF ACCURACY I certify that this data report is in compliance with the terms and conditions of the Purchase Order, both technically and for completeness, for other than the conditions detailed above. Release of the data contained in this hard copy data package has been authorized by the cognizant project manager or his/her ( _ ** ~ac te as verified by the following signature. M.R. McDougall Laboratory Manager Date: 11/13/2019 Eberline Analytical wants and encourages your feedback regarding our performance providing radioanalytical services. Please visit http://eberlineanalytical.com/ to provide us with feedback on our services. Page 6 of 6
Printed: 5/7/2020 9:24 PM Page 1 of 19 ReE_orf To: Work Order Details: Gerald Wood SOG* 20-04072 Eberline Analytica l I Zion Solutions-~-"-~ Purchase Order: 677116 -- ------1 Final Report of Analysis
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2701 Deborah Ave _-_---_--------------1-,_A_n_;,,L,Y~i.'i_c;t~g;ry;*-****EN~~~ONMENTAL Zion, IL 60099 Sample Matrix: SO Lab ID Sample Type Client ID I Sample Date Receipt Date Analysis Date Batch ID Analyte Method Result CU CSU MDA Qualifier Report Units 04/25/20 00:00 4/25/2020 4/30/2020 20-04072 Americium-241 EML Am-01 Modified 5.55E+OO 1.66E-01 , pCi/g 20-04072-01 , LCS KNOWN 04/25/2000:00 4/25/2020 4/30/2020 20-04072 Americium-241 EMLAm-01 Modified 5.47E+OO _ 1.01E+OO ---1.10E+OO - 1.40E-01 pCi/g 20-04072-01 ' LCS : SPIKE 20-04072-02 MBL BLANK 04/25/20 00:00 4/25/2020 4/30/2020 20-04072 Americium-241--
- EML Am-01 Modified** - - --6.96E~02 **
- 7.57E-02 : 7.59E-02 i 9.09E-02 u*-- - -- pCj/g. *
*--s,:06202A-FSWC-040-CV 06/18/1810:30 '4/25/2020 4/30/2020 20-04072 ;;;;;;;cium-241 EMLAm-01 Modified __ 7.52E-02***-*a:00E~2 _____ 8.02E-02 1.11E ___ u pCi/g ----1 ~:03 - - __D_lJ~ -
06/18/1810:30 4/25/2020 4/30/2020 20-04072 : Americium-241 EMLAm-01 Modified 6.44E-02 8.10E-02 8.12E-02 1.29E-01 U pCi/g 072-04 DO B1-06202A-FSWC-040-CV -*--**-*-~,.** --**-**"-' *-- ~ 4.60E-02 1.37E-01 U pCi/g TRG 81-06214A-FSFC-001-CV 05/05/18 15:15 4/25/2020 4/30/2020 20-04072 Americium-241 EML Am-01 Modified -4.34E-04 4.60E-02 20-04072-05 . 20-0407i:o6* TRG ' 82-08101A:SJFC-007-CVOO:o5*--- 05/09/12 14:22 : 4/25/2020 4/30/2020 20-04072 ' Americium-241 EML Am-01 Modified 4.23E-02 5'.'-iiic:02 5.14E-02 ---6.24E-02 u ' pCi/g 05/09/12 14:22 4/25/2020 4/30/2020 20-04072 Americium-241 EML Am-01 Modified 2.06E-02 : 5.15E-02 5.16E-02 1.07E-01 U pCi/g
*20:04072-07 TRG B2-08101A-BJFC-007-CV O 5-1 0 1.27E-01 U pCi/g 2~04072=08 7
TRG-, 82-08201-CJWC-A018-CV00- 05 05/10/1212:56 , 4/25/2020 4/30/2020. 2():04072. -A~ericium-241 ** iML,,;,;:;;~01M;;-dtfi;d -1.29E-02-: 4.50E-02 4.50E-02 I '- 1.73E-02 i 5.61E-02 5.61E-02 1.16E-01 U pCi/g 20-04072-09 TRG 82-08201-CJWC-A018-CVO 5-1 0 05/10/1212:56 4/25/2020 4/30/2020 20-04072 Americium-241 EMLAm-01 Modified 20-04072-10 TRG L2-10214C-RJGS-001-SM-A___ 05/07/19 07:45 4/25/2020 4/30/202Ci" 20-04072 ,,;,;:;;;;,;~;~;;;:241 EML Am-01 Modified I 3.36E-02 , 5.17E-02**+-*;;;:;-~:02 8.85E-02 i U pCi/g r**u ' ' pCi/g 20-04072-1*;-*'*
, 20-04072-12 -TRG L1-12109L-CJGS-001-SB-A TRG---- *-L1-12106L-CJGS-001-SB-A 08/21/19 10:25 4/25/2020 ' 4/30/2020 08/14/1913:30-, 4/25/2020' 4/30/2020 20-04072 Americium-241 20-04072**;;:;;;;;;;cium-241 EML l\;;;=01 Modified EMLAm-01 Modified 6.61 E-02. . 6:iiii:02 . " *-;,-:79E:02 4.47E-02""6-:-86E:o:1*~~- 6.87E-02 9.05E-oi"
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04/25/20 00:00 : 4/25/2020 4/30/2020 20-04072 Americium-243 EML Am-01 Modified 6.05E+OO , 1.82E-01 : pCi/g 20-04072-01 i LCS KNOWN 04/25/20 00:00 4/25/2020 4/30/2020 20-04072 Americium-243 EML*;;;;:a,*M~dified 5.41E+OO : 7.46E-01 1.10E+OO 9.62E-02 pCi/g 20-04072-01 LCS -----SPIKE 20-04072-02 : ,,, -MBL BLANK 04/25/20 00:00 : 4/25/2020 4/30/2020 ' 20-04072 : Americium-243 EML Am-01 Modified 5.60E-02 6~78E=ai'""" 6.83E-02 8.26E-02 u pCi/g 20-04072-03 DUP _ 81-06202A-FSWC-040-CV 06/18/1810:30 f 4/25/2020 4/30/2020 20-04072
- Americium-243 EML Am-01 Modified 7.10E-02 i 7.33E-02 7.40E-02 7.74E-02 U pCi/g 06/18/1810:30
- 4/25/2020 4/30/2020 20-04072 Americium-243 EML Am-01 Modified 2.85E-02 ' 6.17E-02 6.18E-02 1.22E-01 U pCi/g 20-04072-04 DCl~06202A-FSWC-04 0-CV 4/25/2020 4/30/2020 20-04072 : *:;;;;;ericium-243 EMLAm-01 Modified 4.43E-02 5.81E-02 5.84E-02 8.86E-02 U pCi/g ---
~04072-05 TRG
- 81-06214A-FSFC-001-CV 05/05/1815:15 05/09/1214:22 4/25/2020 4/30/2020 20-04072 . Americium-243 EML Am-01 Modified 2.02E-01 3.46E-01 3.47E-01 6.07E-01 U pCi/g 20-04072-06 TRG B2-08101A-BJFC-007-CVO 0-0 5 05/09/1214:22 4/25/2020 i 4/30/2020 20-04072 Americium-243 EMLAm-01 Modified 5.82E-02 7.03E-02 7.09E-02 8.58E-02 U ' pCi/g 20-04072-07 TRG B2-08101A-BJFC-007-CV05-1 0 20-04072-08 7 - TRG___ 82-08201-CJWC-A018-CV00- 05 05/10/1212:56 4/25/2020, 4/30/2020 20-04072 ' __ Americium-243- -~ EMLAm-01 Modified 1.14E~ 1.16E-01 1.17E-01 : 1.56E-01 U pCi/g 4/25/2020 4/30/2020 20-04072 . Americium-243 EMLAm-01 Modified 6.77E-02 ! 7.96E-02 8.03E-02 1.17E-01 U pC_i~ig_ _,
, 20-04072-09 TRG B2-08201-CJWC-A018-CV05- 10 05/10/1212:56 05/07/19 07:45 _ 4/25/2020 4/30/2020- 20-~?_2~*---'--- Americium-243 EMLAm-01 Modified 1.41E-02 3.38E-02 3.39E-02--~,- 7.10E-02 U pCi/~-- 20-04072-10 TRG_____ L2-10214C-RJGS-001-SM-A 08/21/1910:25 4/25/2020, 4/30/2020 20-04072: Americium-243 EMLAm-01 Modified -1.41E-02 3.49E-02 3.50E-02 9.95E-02 U pCi/g 20-04072-11 TRG ; L1-12109L-CJGS-001-SB-A 08/14/1913:30 4/25/2020 4/30/2020 20-04072 i Americium-243 EMLAm-01 Modified -2.63E-02 4.75E-02 4.77E-02 1.46E-01 U pCi/g 20:04072-12 TRG ,,___ L1=12106L-CJGS-001-SB-A Sample;DO=Duplicate Original;U=Non-detect CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal ( ~ EBERL INE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 5/7/2020 9:23 PM Page 2 of 19 Rep_ort To: Work Order Details: SDG.* 20-04072
*l-Gerald Wood Eberline Analytica l Final Report of Analysis Lab Sample Client I -~~~.
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- Report Units ID Type ID Date Date Date ID 04/25/20 00:00 4/25/2020 4/30/2020 20-04072 Curium-243/244 EML Am-01 Modified 5.99E+00 1.08E-01 pCilg 20-04072*01 ! LCS KNOWN 04/25/20 00:00 4/25/2020 4/30/2020
- 20-::-04072 Curium-243/244 EML Am-01 Modified .* 5.83E+00 : 1.07E+00 1.28E+00 1.07E-01 pCilg l-~0_:?~?.72-01 i LCS ' SPIKE 4/30/2020 20-04072 , Curium-243/244 EMLAm-01 Modified 1.14E-01
- 9.99E-02 1.01E-01 1.14E-01 pCi/g f 20-04072-02 . MBL : BLANK 0412512000:00 , 4125/2020
- 4.96E-02 : 9.78E-02 i U pCi/g --
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- 20-04072 Curium-243/244 EML Am-01 Modified 2.12E-02 4.60E-02 : 4.60E-02 9.08E-02 ' U pCi/g 20-04072-04 ' DO B1-06202A-FSWC-040-CV -**
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05/05/1815:15 i 4/25/2020 4/30/2020 20-04072 Curium-243/244 EMLAm-01 Modified 3.47E-02 6.62E-02 6.63E-02 1.22E-01 U pCi/g 20-04072-05 TRG B1-06214A-FSFC-001-CV
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I 05/09112_:_4;~~' 4/25/2020 4/30/2020 20-04072 Curium-243/244 EML Am-01 Modified 1.24E-02 2.98E-02 *-* 2.98E-02 6.24E-02 / U po~04072-06 TRG
- B2-08101A-BJFC-007-C_':I_ 0 0-0 5
~0-04072-07 TRG B2-08101A-BJFC-007-CV05:.! 0 05/0~/1_~~4:22 4/25/202~*-**'.'1:30/2020 ..._20-04072 Curium:~~3/~~. ,. EMLAm-01 Modified_ .. 1 8.35E-02 7.99E-02 8.06E-02 8.57E-02 U pCi/g 05/10/1212:56 : 4/25/2020 4/30/2020 20-04072 Curium-243/244 EMLAm-01 Modified ; 4.05E-02 6.63E-02 6.64E-02 i 1.16E-01 U pCi/g 20-04072-08 TRG B2-08201-CJWC-A018-CV00-05 20-04072-09 : TRG **-B2-08201-CJWC-A018-CV 05-10 0511011212:56 ' 4/2512020 4130/2020 20-04072 Curium-243/244 EMLAm-01 Modified ~:02.. ***:;::-25E-02-***-*7~30E-02 1.05E-01 U pCi/g*-
20-04072-10 TRG L2-10214C-RJGS-001=SM-A .... ?5!?7119 07:45 .4/25/2020 4/30/2020 ' 20-04072 Curium-243/244 EML A;;;-:O1.Modi~ld~--' ~-1~3I:aI* *-4~ijf021... ;;:;*iiE=o2 8.65E-02 u pCi/g 08/2111910:25 : 4/25/2020 4130/2020 20-04072 . Curium-2431244 EMLAm-01 Modified 2.31E-02 4.97E-02 4.98E-02 9.66E-02 U pCilg 20-04072-11 TRG : L1-12109L-CJGS-001-SB-A ,,,~---~---~ __ ,_,,_*.,,~ ' """ f-----------* *-*---- TRG L1-12106L-CJGS-001-SB-A 0811411913:_3?*...
- 412512020 4/30/2020 20-04072 Curium-243/~.~-* EMLArn:?:.!'1odified .....*. ___ '.::_5_.9_1=,~02 7.04E:?,.~ ..*.*. 7.06.§:02 1.05E-01 i U pCi/g 20-04072-12 I . .~.. . KNOWN 04/25/20 00:00 4125/2020 4127/2020 20-04072 Carbon-14 EPA520.0 Modified 1.32E+03 3.70E+01
.1 pCilg 20-04072-01 LCS l 20-04072-01 LCS SPIKE **- 04125120 00:00 4125/2020.. 4/27/2020 . 20-04072 c_~,:t:?n-14
- EPA 520.0 Modified EPA 520.0 Modified
.*...1.:.3_~E+03 -3.73E-01 9.67E+00 4.65E-01 1.81 E+02 4.68E-01 I 4.08E+00 7.99E-01 U pCi/g pCi/g 20-04072-02 MBL BLANK 04/25/20 00:00 4/25/2020 4/27/2020 20-04072 Carbon-14 U pCi/g 20-04072-03 ,
20-04072-04 . DUP B1-06202A-FSWC-040-CV DO **:****;:;J~~202A-FSWC-040-C V 06/18/1810:30 06/18/1810:30 4/25/2020 4/25/2020 4/27/2020 4/27/2020 20-04072 ' 20-04072 ' Carbon-14 Carbon-14 EPA520.0 Modified EPA~~?:.~_1".lodified
. -5.57E-01 -4.31E-01 . 3.64E-01 3.70§:01 3.72E-01 3.75E-01 6.32E-01 6.39E-01 --:** ***u*-* pCi/g I 20-04072-05 TRG
- B1-06214A-FSFC-001-CV 05/05/1815:15 4/25/2020 4/28/2020 20-04072 Carbon-14 EPA520.0 Modified -6.32E-01 3.49E-01 3.60E-01 6.09E-01 i U pCi/g 20-04072-06 TRG B2-08101A-BJFC-007-CV00-05 05/09/1214:22 4/25/2020' 4/28/2020. 20-04072 : Carbon-14 EPA520.0 Modified -456E=o1***:* 3.63E-01 3.69E-01--~* 6.28E-01 i U pCi/g 1---*- .... . ..
05/09/12 14:22 4/25/2020 4/28/2020 20-04072 Carbon-14 EPA 520.0 Modified -2.87E-01 4.0~§:_01 4.04E-01 6.91 E-01 U pCilg 20-04072-07 TRG '. B2-08101A-BJFC-00~:_<:_V 0 5-1 0 05/10/12 12:56 4/25/2020 4/28/2020 20-04072 Carbon-14 EPA 520.0 Modified -6.71 E-01 3.91 E-01 4.02E-01 , 6.81 E-01 U pCi/g 20-04072-08 TRG , B2-08201-CJWC-A018-CV 0 0-0 5 pCi/g I 20-04072-09 TRG ! B2-08201-CJWC-A018-CV05-10 05/10/1212:56 4/25/2020 4/28/2020 20-04072 Carbon-14 ***-EPA520.0Modified -5.32E-O~9E:01 3.77E-01 6.41E-01 U ! 20-04072-10
- TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 4/28/2020 : 20-04072 : Carbon-14 EPA520.0 Modified -4.72E-01 3.76E-01 3.81E-01 6.50E-01 i U i pCVg 08/21/1910:25 4/25/2020 4/28/2020 20-04072
- Carbon-14 *- . EPA520.0 Modifi;d -4.92E~o1**-* 3.91E-01 3.97E-01 6.77E-01 U : pCi/g 20-04072-11 j TRG , l1-12109L-CJGS-001-SB-A 20-04072-12 i TRG ' L1-12106L-CJGS-001-SB-A 08/14/1913:30 4/25/2020 4/28/2020 20-04072j Carbon-14 . ~520.0 Modified -3.28E-01 3.68E-01 3.71E-01 i 6.33E-01 j U pCi/g Sample;DO=Duplicate Original;U=Non-detect CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal
( ~ EBERL INE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 5/7/2020 9:23 PM Page 3 of 19 ReE_ort To: Work Order Details: Gerald Wood SOG: 20-04072 Eberline Analytical 1,,,______ Zion ,,,,,, Solutions _ _ _ ,,,,,,,,,,, Purchase Order 677116 Final Report of Analysis 2701 Deborah Ave Analysis
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Zion, IL 60099 Sample Matrix: SO Lab ID Sample Date Receipt Date Analysis Date Batch ID Analyte I Method Result CU CSU MDA Qualifier Report Units 20-04072-01 : 04/25/20 00:00 4125/202 lron-55 EML Fe-01-01 Modified 4,08E+03 3,50E+02 04/25120 00:00 4/, lron-55 EML Fe-01-01 Modified 3A1E+03 2,32E+02 6,33E+02 2,51E+02 pCi/g ___04125120 00:00
-,,;::_c~=-..:,:,:=__;___:::==_:___;_==-=---=:._c, __:::::,c,,,,,,_,,,, ___;_l_ro,__;_n_-5_5 _ _ ,I- EML Fe-01-01 Modified 5,18E+00 1,92E+01 1,92E+01 3,01E+01 u U pCilg 1 --~-----
DUP 81-06202A-FSWC-040-CV 06/18/1810:30 06/18/18 10:3C ,,_ _ _ _ _ _ _ _ _ _ _,,,, lron-55 EML Fe-01-01 Modified 3,19E-02 U1E-01 U1E-01 2,15E-01 U pCi/g 20-04072-04 DO 81-06202A-FSWC-040-CV 06/18118 10:30 20-04072 lron-55 EML Fe-01-01 Modified -3,00E-02 1A1E-01 1A1E-01 2,23E-01 u 81-06214A-FSFC-001-CV 05105/1815:15 20-04072 lron-55 EML Fe-01-01 Modified 6,56E-02 L89E-01 1,89E-01 3,14E-01 u U 82-08101A-BJFC-007-CV 0 0-0 5 05/09/12 14:22 20-04072 lron-55 EML Fe-01-01 Modified 7,56E-01 2,76E+00 2,76E+00 4A6E+00 u U pCi/g 82-08101A-BJFC-007-CV 0 5-1 0 I 05/09112 14:22 05/0! 4/2912020_,,, 20-04072_ lron-55 EML Fe-01-01 Modified -U6E+00 2,08E+00 2,10E+00 3,04E+00 u U pCilg u ___,_,_~---- 82-08201-CJWC-A018-CV 0 0-0 5 82-08201-CJWC-A018-CV 0 5-1 0 I 05/10/1212:56 05/1( 05110/12 12:56 4125/2020 4/29/2020 20-04072 4129/2020 , 20-04072 lron-55 lron-55 EML Fe-01-01 Modified EML Fe-01-01 Modified
-U9E-01 L34E+00 3,22E+00 2,55E+00 3,22E+00 2,56E+00 5,12E+00 4,30E+0C U
u pCi/g 20-04072-09 TRG 20-04072-10 , TRG L2-10214C-RJGS-001-SM-A 05107/19 07:45 4/2912020 20-04072 lron-55 EML Fe-01-01 Modified 5,91E-02 6,71E-02 6,79E-02 U5E-01 u 20-04072-11 TRG ; L1-12109L-CJGS-001-SB-A 08/21/19 10:25 4/2912020 20-04072 lron-55 EML Fe-01-01 Modified ! -1,82E-02 3,86E-01 3,86E-01 6,15E-01 U pCi/g 20-04072-12 TRG
----L1-12106L-CJGS-001-SB-A 08114119 13:30 4/25/2020 4129/2020 20-04072 lron-55 EML Fe-01-01 Modified ~------ I L85E-01 , 2,37E-01 ,,,,-_,,,_,_,,,,,,,,,_,,,,,,_,____,,~---f-,--,,,~--,,_,_______ , 2,39E-01
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pCi/g 20-04072 Tritium LANL ER-210 Modified ' 3,69E+02 6,96E+00 2,18E+01 3,62E+00 pCi/g
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LCS SPIKE 04125/20 00:00 4/25/2020 4/3012020 =*c* -- 04125/20 00:00 4125/2020
- 4/3012020 20-04072 Tritium LANL ER-210 Modified i-2-,0-5_E_+_OO_ _ _ 2,16E+00 _ _ __
_ ___,_2,16E+00 3.62E+00 u MBL BLANK , ___ ,_,.,,,,_,_." DUP : B1-06202A-FSWC-040-CV I 06/18/1810:30 4125/2020, 4130/2020 20-04072 Tritium ,,,_ LANL ER-210 Modified -i,--,1,85E+OO 2,36E+00 2.37E+00 3,98E+00 u DO
- B1-06202A-FSWC-040-CVI I_ -~18/1810:30 06/18/18 10:30 4/25/2020 4/30/202(
4/30/2020 20-04072 Tritium LANL ER-210 Modified 3,70E+00 2A2E+00 2.42E+00 3,98E+00 u !:.~_ii~-- TRG B1-06214A-FSFC-001-CV I 05/05118 15:15 4/25/2020 511/2020 20-04072 Tritium f LANL ER-210 Modified 3,86E+00 2A0E+00 2A1E+00 3,94E+00 u pCilg T u II B2-08101A-BJFC-007-CV 0 0-0 5 05/09/1214:22 05/09112 14:22 : 4/25/2020 , 5/1/2020 20-04072 Tritium LANL ER-210 Modified_,____4,-9-7E_+_o_o~1-----, 3A3E+00 3A4E+00 5,67E+00 pCilg TRG TRG B2-08101A-BJFC-007-CV 0 5-1 0 05/09/12 14:22 4/2512020 5/1/2020 20-04072 Tritium _LA_N_L_ER_-_2_10_M_o_difi_1e_d__+-j_6_,3_5_E+_0_0--i-------<-- 5.68E+00 5,69E+00 9A8E+00
---~-------'----~----'--'----I u pCi/g TRG B2-08201-CJWC-A018-CV 0 0-0 5 05110/12 12:56 4/25/2020 511/2020 20-04072 Tritium LANL ER-210 Modified i 4,02E+00 3,34E+00 3,35E+00 5-56E+00 u pCi/g I 05/10/12 12:56 : 4125/2020 , 5/11202 Tritium I LANL ER-210 Modified J 6A1E+00 1 3A6E+00 3.47E+00 5.64E+00 pCi/g ----- -- II TRG B2-08201-CJWC-A018-CV 0 5-1 0 5/112020 20-04072 -----*= 05/07/19 07:45 4125/2020 5/1/2020 20-04072- *. Tritium LANL ER-210 Modified 2,74E+00 2-28E+00 2.28E+00 3,79E+00 u pCi/g TRG L2-10214C-RJGS-001-SM-A TRG L1-12109L-CJGS-001-SB-A L1-12109L-CJGS-001-SB-A I 08121/1910:25 4125/2020 511/2020 20-04072 --- Tritium LANL ER-210 Modified 8-51E+00 2,36E+00 2.41E+00 3,67E+00 pCi/g 172-12 TRG L1-12106L-CJGS-001-SB-A L1-12106L-CJGS-001-SB-A I 08/1411913:30 4/2512020 51112020 20-04072 Tritium I LANL ER-210 Modified 1.50E+00 2,16E+00 2,16E+00 3.64E+00 u pCilg CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect
( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 5/7/2020 9:23 PM Page 4 of 19 Report To: Work Order Details: Gerald Wood SDG. 20-04072 Eberline Analytical -sw**-~w~~ Zion Solutions ~,, _ , , ________
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,, ,.,,, KNOWN 04/25/20 00:00 4/25/2020 4/28/2020 20-04072 20-04072
- lron-55 lron-55 ASTM 3500-Ni Modified ASTM 3500-Ni Modified 4.08E+03 3.05E+03 3.50E+02 2.42E+02 3.20E+02 2.94E+02
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pCi/g pCi/g 20-04072-01 LCS SPIKE 04/25/20 00:00 4/25/2020 4128/2020 .... ************-*** .......*..... ) 20-04072-02 MBL BLANK 04/25/20,,,,.,,_,,, ________ 00:00,,,, i 4/25/2020 4/2812020 20-04072 Nickel-59 ASTM 3500-Ni Modified ___-2.65E+00 1.49E+01 1.49E+01 2.28E+01 u pCi/g
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20-04072-03 DUP B1-06202A-FSWC-040-CV 06/18/18 10:30 4/25/2020 4/28/2020 20-04072 Nickel-59 ASTM 3500-Ni Modified -2.89E-02 ,,,,,,, __ 7.41E-02
- 7.41E-02 1.11E-01 u pCi/g
-*-* -~*
20-04072-04 DO B 1-06202A-FSWC-040-CV 06/18/18 10:30 : 4/25/2020 4/2812020 20-04072 Nickel-59 ASTM 3500-Ni Modified 1.46E-02 7.26E-02 7.27E-02 1.15E-01 u ---****- pCi/g
.,,, .,, _,_, ... " --- ~-**-- . ***---- ..., ... -4.18E-03 9.97E-02 9.97E-02 . 1.53E-01 U . pCi/g 20-04072-05 TRG B1-06214A-FSFC-001-CV 05105/18 15:15 ' 4125/2020 4128/2020 20-04072 Nickel-59 ASTM 3500-Ni Modified """----***-------*-*- -------- _,_,,__,_,_,_~,N~-,-m ,_,_,._*-,-~-,-.*~
20-04072-06 TRG B2-08101A-BJFC-007-CV 0 0-0 5 05/09/12 14:22 4/2512020 4/2812020 20-04072 Nickel-59 ASTM 3500-Ni Modified 1.10E-02 2.98E-01 2.98E-01 4.67E-01 u pCi/g B2-08101A-BJFC-007-CV 0 5-1 0 05109/12 14:22
- 4/2512020 4/29/2020 20-04072 j Nickel-59 ASTM 3500-Ni Modified 7.38E-02 1.97E-01 1.97E-01 3.17E-01 u : pCilg 20-04072-07
---**---*--s***** TRG B2-08201-CJWC-A018-CV 0 0-0 5 05/10/12 12:56 4125/2020 4129/2020 20-04072 i Nickel-59 ASTM 3500-Ni Modified 1.08E-01 3.31E-01 3.31E-01 ' 5.28E-01 u pCi/g 20-04072-08 TRG
-- *-- . 2.76E-01 2.76E-01 4.38E-01 u pCilg 20-04072-09 TRG B2-08201-CJWC-A018-CV 0 5-1 0 05/10112 12:56 4/2512020 4/2912020 20-04072 Nickel-59 ASTM 3500-Ni Modified 3.79E-02 -*---- ,._,m *- -------*-**
pCilg 20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05107119 07:45 4/25/2020 4/29/2020 20-04072 Nickel-59 ASTM 3500-Ni Modified -6.28E-03 4.68E-02 4.68E-02
---~*~~*--*--<-*~ ***-'*U 7.12E-02 -*****
- Y****-*m * * ************ *~*~~*
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* --------~-*--*-*---------*------**- 4/2912020 20-04072 Nickel-59 ASTM 3500-Ni Modified -1.36E-01 1.78E-01 1.78E-01 2.52E-01 u pCi/g 20-04072-12
- TRG j L 1-12106L-CJGS-001-SB-A 08/14119 13:30 4125/2020 j
i ... ,._ .. ***- ......... ****-*** 04125/20 00:00 4/25/2020 4130/2020 20-04072 : Nickel-63 ASTM 3500-Ni Modified 1.46E+03 4.39E+01 i pCilg 20-04072-01 LCS KNOWN
. ASTM 3500-Ni Modified 1.48E+03 9.06E+00 8.76E+01 2.19E+00 pCi/g 20-04072-01
- LCS SPIKE 04/25/20 00:00 : 4125/2020 4130/2020 20-04072 Nickel-63 1.28E+00 2.22E+00 u
-pCilg 20-04072-02 MBL BLANK 04/25/20 00:00 i 4/2512020
- 4/30/2020 20-04072 Nickel-63 ASTM 3500-Ni Modified -8.58E-01 1.28E+00
**----**-,n,.,.,.. .,,_,,.,
i 20-04072-03 DUP B1-06202A-FSWC-040-CV 06118118 10:30 i 4/25/20~?~*.~/3012020 20-04072 Nickel-63 ASTM 3500-Ni Modified 9.36E-01 1.30E+00 1.31E+00 2.20E+00 u pCi/g 20-04072-04 DO . B1-06202A-FSWC-040-CV 06/18/18 10:30 4/2512020 4/3012020 20-04072 Nickel-63 ASTM 3500-Ni Modified 1.45E+00 1.32E+00 1.32E+00 2.20E+00 u pCi/g 20-04072-05 TRG B1-06214A-FSFC-001-CV 05/05/18 15:15 4125/2020 4130/2020
- 20-04072 ' Nickel-63 ASTM 3500-Ni Modified 2.70E-01 1.37E+00 1.37E+00 2.33E+00 u pCi/g
* *- - I 20-04072-06
- TRG ! B2-08101A-BJFC-007-CV 0 0-0 5 05109112 14:22 4/25/2020 4130/2020 20-04072 Nickel-63 ASTM 3500-Ni Modified 4.56E-01 1.39E+00 1.39E+00 l 2.36E+00 u pCi/g 20-04072-07
- TRG B2-08101A-BJFC-007-CV0 5-1 0 05/09/12 14:22 I 412512020
- 413012020 20-04072 j Nickel-63 ASTM 3500-Ni Modified 7.46E-01 1.42E+00 i 1.42E+00 2.41E+00 u pCilg 20-04072-08 ; TRG B2-08201-CJWC-A018-CV 0 0-0 5
----*-*-v-********-*---*
05/10/12 12:56 l 412512020 4130/2020 20-04072 j Nickel-63 ASTM 3500-Ni Modified
-6.62E-01 1.41E+00 1.41E+00 2.44E+00 u pCi/g 20-04072-09 TRG B2-08201-CJWC-A018-CV 0 5-1 0 05/10112 12:56 4/2512020 4/3012020 20-04072 i Nickel-63 ASTM 3500-Ni Modified 5.54E-01 1.41E+00 1.41E+00 2.38E+00 u pCilg 20-04072-10 : TRG L2-10214C-RJGS-001-SM-A 05107119 07 :45 4/25/2020 : 4/30/2020 20-04072 ! Nickel-63 ASTM 3500-Ni Modified -1.73E-01 1.30E+00 1.30E+00 2.24E+00 --t---*--*
u pCilg 20-04072-11 TRG L 1-12109L-CJGS-001-SB-A 08121/19 10:25 4/2512020 4130/2020 20-04072 Nickel-63 ASTM 3500-Ni Modified 7.13E-01 1.36E+00 1.36E+00 I 2.30E+00 u pCi/g 20-04072-12 TRG L 1-12106L-CJGS-001-SB-A 08/14/19 13:30 4125/2020 4/3012020 20-04072 Nickel-63 ASTM 3500-Ni Modified I -1.09E+00 1.24E+00 1.24E+00 2.16E+00 ! u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=No rmal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 5/7/2020 9:23 PM Page 5 of 19 ReE_ort To: Work Order Details: Gerald Wood SDG: 20-04072 Eberline Analytical I Zion Solutions Purchase Order:: 677116 i---------"--*--~--~-~- --1--A~~ly~;~_Category* :_____ ENVIRON_MENTAC _____ - -*- -----*-*-**-*- Final Report of Analysis 2701 Deborah Ave Zion, IL 60099 Samp/e Matrix: ' SO Lab ID Sample Type Client ID I Sample Date Receipt Date Analysis Date Batch ID A lyt na e I M hO d et I R I
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-*** 05/09/1214:22 . 4/25/2020 i 4/25/2020 4/29/2020 4/29/2020 20-04072 ; .. Neptunium-2:37 20-04~7_2._ Neptunium-237 EIChroM ACW08 Mod EIChroMACW08Mod 7.53E-02 7.65E-02 7.70E-02 1.03E-01 U pCi/g I 20-04072-07 TRG B2-08101A-BJFC-007-CV O 5-1 0 05/09/12 14:22 ._4__12.~l~02CJ __4!29/2020 20-Cl4__Cl!2_
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20-04072-08 TRG B2-08201-CJWC-A018-CV00-05
""' --------- 05/10/1212:56 . 4/25/2020 4/29/2020
- 20-04072 Neptunium-237
---- EIChroMACW08Mod 4.18E-02 4.72E-02 5.04E-02 7.22E-02 5.07E-02 7.24E-02 6.17E-02
_ 1.23E-01 U U pCi/g pCi/g 20-04072-09 TRG : B2-08201-CJWC-A018-CVO 5-1 0 05/10/1212:56 4/25/2020 4/29/2020 20-04072 . Neptunium-237 EIChroM ACW08 Mod 20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 4/29/2020*---*20:04012** Neptunium-237 EIChroM-ACW08 Mod 7.03E-02 . 6.64E-02 --6.69E=o2*-.----8.17E-02 ' U pCi/g
- 20-04072-11 :
20-04072-12 . TRG TRG L1-12109L-CJGS-001-SB-A L1-12106L-CJGS-001-SB-A 08/21/19 10:25 4/25/2020 08/14/1913:30 ______ 4/25/2020 4/29/2020 4/29/2020 20-04072 20-04072 Neptunium-237
- Neptunium-237
- EIChr~MACW08 Mod EIChroM ACW08 Mod 4.14E-02 1.52E-02 4:99E-02 5.68E-02 5.01 E-02 5.68E-02 6.1 OE-02 1.23E-01 U ***------:~u*
pCi/g pCi/g I 20-04072-01 LCS KNOWN 04/25/20 00:00 4/25/2020 4/29/2020 20-04072 , Promethium-147 EML Pm-01 Modified 5.99E+01 1.62E+OO I ' i pCi/g
*20-04072-01 LCS SPIKE 04/25/20 00:00 4/25/2020 4/29/2020 20-04072 Promethium-147**** -E-ML Pm-01 Modified 5.89E+01 1.77E+OO , 9.02E+OO : 1.51E+OO : pCi/g ~0:_04()72-02 MBL BLANK ____ ..*. 04/25/20 00:00 4/25/2020 4/29/2020 i 20-04072 Promethium-147 EML Pm-01 Modified 5.01E-01 8.91E-01 .....~:~4__1c:01 1.51E+OO U pCi/g 20-04072-03 DUP B1-06202A-FSWC-040-CV 06/18/1810:30 4/25/2020 ' 4/29/2020 20-04072 Promethium-147 EML Pm-01 Modified 1.47E+OO 1.41E+OO : 1.43E+OO I 2.36E+OO U pCi/g 20-04072-04 DO B1-06202A-FSWC-040-CV 06/18/1810:30 4/25/2020: 4/29/2020 20-04072 , Promethium-147 EML Pm-01 Modified 1.63E+OO . 1.46E+OO I 1.48E+OO 2.44E+OO U pCiig**-
t20-04072-05 TRG __ B1-06214A-FSFC-001-CV 05/05/1815:1_5_ 4/25/2()20 4/30/2020 _2CJ:~_Cl!2.. Promethium-147 EML Pm-01 Modified 1.38E+_CJCJ__ . 1.52E+OO .,.. 1.53E+OO 2.55E+OO U pCi/g 20-04072-06 TRG B2-08101A-BJFC-007-CV O_ 0-0 5__ ___()5109/12 14:22 4/25/2020 4/30/2020 20-04072 Prom_ethium-147 EML Pm-01 Modified 1.34E+01 ___ 7.541c+OO 7.80E+OO _J 1.24E+01 pCi/g 20-04072-07 TRG B2-08101A-BJFC-007-CVO 5-1 0 05/09/1214:22 4/25/2020 4/30/2020 20-04072 Promethium-147 EML Pm-01 Modified 1.17E+01 7.08E+OO 7.30E+OO 1.17E+01 U pCi/g
---~CJ::_()_4()?_2_:CJ_~--- TRG B2-08201-CJWC-A018-CV00-05 05/10/1212:56 4/25/2020. 4/30/2020 20-04072 Promethium-147 ... EMLPm-01 Modified 7.99E+OO 7.19E+OO 7.29E+OO ) 1.20E+01 U pCi/g _____ _ ~--04072-09 . TRG B2-08201-CJWC-A018-CV O 5-1 0 05/10/12 12:56 4/25/2020 . 4/30/2020 ' 20-04072 Promethium-147 EML Pm-01 Modified 1.1 OE+01 7 .27E+OO 7.46E+OO 1.20E+01 U pCi/g 20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 4/30/2020 20-04072 Promethium-147 EML Pm-01 Modified 9.09E-01 1.18E+OO , 1.19E+OO 1.99E+OO U pCi/g 20-04072-11 1 TRG L1-12109L-CJGS-001-SB-A 08/21/1910:25 4/25/2020 4/30/2020 20-04072 Promethium-147 EML Pm-01 Modified 1.66E+OO : 1.14E+OO i 1.17E+OO 1.90E+OO U pCi/_g_
20-04072-12 TRG L1-12106L-CJGS-001-SB-A I 08/14/1913:30 i 4/25/2020 4/30/2020 20-04072 Promethium-147 ] EML Pm-01 Modified I 7.42E-02 1.04E+OO ! 1.04E+OO i 1.78E+OO U pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=No nnal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 5/7/2020 9:23 PM Page 6 of 19 Report To: Work Order Details: Eberline Analytical - G_eraldWo_od Zion Solutions Purchase Order: Sl)(;- -~Q~Q4_0_7_2_ __ 677116 Final Re ort of Anal sis -- 2701 Deborah Ave ------------ Analysis Categ;;;;---E-N_V_I_RO_N_M_E_N_T_A_L________.__**-****-----*--*****--- p y ----- - ---- ...-*--***--**-------..-** * *---** *--*-* ..... . * * - - - - - - - - - - -..*- -*** ................... ,........................ Zion, IL 60099 Sample Matrix: SO Lab Sample Client Sample Receipt Analysis Batch Anal te Method Result CU CSU MDA Qualifier . Report ID Type ID Date Date Date ID y : , Units 20-04072-01 j LCS , KNOWN 04/25/20 00:00 : 4/25/2020 4/30/2020 20-04072 Plutonium-238 EML Pu-02 Modified 7.13E+OO 1.50E-01 :
- pCi/g 20-04072-01 LCS
- SPIKE 04/25/20 00:00 : 4/25/2020 4/30/2020 20-04072 Plutonium-238 EML Pu-02 Modified 5.64E+OO 7.02E-01 ' 8.87E-01 : 1.36E-01 pCi/g I 20-0-4-07-2--0-2~, .... MBL-. - BLANK -- ---- ... ---+-0..4.. 0-i..4-/-25***1*2*0**2**0****.. ****4***,*3*****0***1**2****0****2**-o* . ******2**0**_**04*****0*1****2*****-****** Plutonium::,iis
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EML_P.. -1.22E-02 ; 5.21 E-02 5.21 E-02 1.45E-01 U pCi/g 20--04072-03 DUP 81-::06202A-FSWC-040-CV 06/18/1810:30 i 4/25/2020 4/30/2020 20-04072-- Plutonium-238-- EML Pu-02 Modified 7.21E-02 i 9.43E-02 , 9.45E-02 1.52E-01 : U pCi/g 20-04072-04 , DO *- 81-06202A-FSWC-040-CV 06/18/1810:30 . 4/25/2020 4/30/2020 20-04072 Plutonium-238 EML Pu-02 Modified -- 5.50E-02 ! 7.41E-02 7.42E-02 1.16E-01 U i pCi/g 20-04072-05 __,_ TRG ' 06214A-FSFC-001-CV 05/05/1815:15 4/25/2020 4/30/2020 20-04072 Plutonium-238 EML Pu-02 Modified -2.76E-03 i 3.23E-02 3.23E-02 6.77E-02 U ! pCi/g 20-04072-06 TRG 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 ! 4/25/2020 4/30/2020 20-04072 Plutonium-238 EML Pu-02 Modified -8.11E-03 4.81 E-02 4.81 E-02 1.14E-01 U , pCi/g 20-04072-07 TRG ****- B2-08101A-BJFC-007-CV O 5-1 0 05/09/12 14:22 : 4/25/2020 ' 4/30/2020 , 20-04072 ' Plutonium-238 EML Pu-02 Modified -1.77E-02 4.37E-02 4.37E-02 1.25E-01 - ...... U - - pCi/g --- 20-04072-08 TRG B2-08201-CJWC-A01B=cv*oo~o-s
- 05/10/1212:56 ; 4/25/2020 4/30/2020 20-04072 ' Plutonium-238 EML Pu-02 Modified -2.84E-02 j 5.91E-02 5.92E-02 1~75E=01 - - *u. -- pCi/g 20-04072-09 TRG 82-08201-CJWC-A018-CVO 5-1 0 05/10/1212:56 4/25/2020 4/30/2020 20-04072 Plutonium-238 EML Pu-02 M*~dified -2.21E-02 , 6.72E-02 ' 6.72E-02 : 1.83E-01*-* U pCi/g 20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020. 4/30/2020 04072 Pi~t;~;;;;;;-_238 EML Pu-02 Modified 3.03E-02 8.41E-02 8.42E-02 ' 1.82E-01 U . pCi/g 20-04072-11 TRG L1-12109L-CJGS-001-S8-A 08/21/1910:25 ! 4/25/2020. 4/30/2020 20-04072 Plutonium-238 EML Pu-02 Modified 1.84E-02 i 6.63E-02 6.63E-02 . 1.50E~01 . U pCi/g I 20-04072-12 ' TRG i L1-12106L-CJGS-001-SB-A 08/14/1913:30 4/25/2020. 4/30/2020 20-04072 Plutonium-238 EML Pu-02 Modified -2.11E-02 : 3.38E-02 3.38E-02 1.06E-01 :l.J pCi/g I 20-04072-01 LCS KNOWN ------ 04/25/20 00:00 4/25/202:-:::::~-0~:*-*::~04072 Plutonium-239/2:: EML Pu-02 Modified 5.63E+OO : 1.80E-01 i i pCi/g 20-04072-01 : LCS SPIKE 04/25/20 00:00 i 4/25/2020 i 4/30/2020 20-04072 Plutonium-239/240 EML Pu-02 Modified 5.93E+OO , 7.24E-01 9.21E-01 8.31E-02 ! pCi/g 20-04072-02 ' MBL BLANK 04/25/20 00:00 4/25/2020 . 4/30/2020 20-04072 [ Plutonium-239/240 EML Pu-02 Modified -1.47E-02 3.81 E-02 3.82E-02_ ... 1.28E-01 ' U . pCi/g 20-04072-03 DUP B1-06202A-FSWC-040-CV 06/18/18 10:30 4/25/2020 4/30/2020 i 20-04072 : Plutonium-239/240 EML Pu-02 Modified -3.56E-03 i 4.03E-02 4.03E-02 i 1.23E-01 U pCi/g 20-04072-04 i DO 81-06202A-FSWC-040-CV 06/18/1810:30 i 4/25/2020 i 4/30/2020 i 20-04072 ' Plutonium-239/240 EML Pu-02 Modified 3.60E-02 6.36E-02 6.37E-02 1.15E-01 U pCi/g 20-04072-05 TRG 81-06214A-FSFC-001-CV 05/05/18 15:15 ' 4/25/2020 , 4/30/2020 20-04072 Plutonium-239/240 EML Pu-02 Modified O.OOE+OO 4.43E-02 4.43E-02 9.58E-02 ' U pCi/g
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39..12 1.34E-01 u ! pCi/g 20-04072-07 TRG B2-08101A-BJFC-007-CV O 5-1 0 05/09/12 14:22 4/25/2020 . 4/30/2020 : 20-04072 Plutonium-239/240 EML Pu-02 Modified -3.32E-03 3.89E-02 3.89E-02 J 8.16E-02 U pCi/g
.2?_-:_Cl~~n-08 TRG i B2-08201-CJWC-A018-CVO 0-0 5 05/10/1212:56 4/25/2020 : 4/30/2020 20-~_ll,7-~. Plutonium-239~2~~.. EML Pu-02 Modified 1.72E-02 J 5.27E-02 5.27E-02 , 1.25E-01 _ _lJ __ pCi/g 20-04072-09 TRG 82-08201-CJWC-A018-CVO 5-1 0 05/10/1212:56 4/25/2020 . 4/30/2020 . 20-04072 Plutonium-239/240 EML Pu-02 Modified 4.02E-02 8.70E-02 8.71E-02 1.72E-01 U pCi/g 20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 4/30/2020 20-04072 Plutonium-239/240 EML Pu-02 Modified -5.12E-03 5.98E-02 5.98E-02 1.26E-01 U pCi/g 20-04072-11 TRG L1-12109L-CJGS-001-SB-A 08/21/1910:25 4/25/2020 4/30/2020 i 20-04072 Plutonium-239/240 EML Pu-02 Modified 1.88E-02 4.51E-02 4.51E-02 9.45E-02 U pCi/g 20-04072-12 TRG L1-12106L-CJGS-001-SB-A 08/14/1!)13:30 4/25/2020 4/30/2020 20-04072 Plutonium-239/240 EML Pu-02 Modified i 1.02E-02 3.11E-02 .*. 3.11E-02 7.38E-02~ U pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect
( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/ 483-4621
Printed: 517/2020 9:23 PM Page 7 of 19 Report To: Work Order Details: Gerald Wood SDG. 20-04072 Eberline Analytical _______ ,,,,,,,,,,, Zion Solutions ----,,,. ,,,,_ ,, ,,,,,,,,,_, -** --"-* Purchase Order:
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- 5/1/2020 20-04072 Plutonium-241 EML Pu-02 Modified 2.83E+02 1.30E+01 : pCi/g LCS SPIKE 04/25/20 00:00 : 4/25/2020 5/1/2020 20-04072 Plutonium-241 EML Pu-02 Modified 3.08E+02 8.37E+00 2.64E+01 7.08E+00 pCi/Q 20-04072-01
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20-04072-02 MBL BLANK 04/25/20 00:00 : 4/25/2020 5/112020 20-04072 Plutonium-241 EML Pu-02 Modified -1.57E+00 : 4.81E+00 : 4.81E+00
- 8.28E+00 u pCi/g 20-04072-03 DUP B1-06202A-FSWC-040-CV os118t18 10:30 I 412512020 5/1/2020 20-04072 Plutonium-241 EML Pu-02 Modified -1.14E+00 5.83E+00 5.84E+00 1.00E+01 u pCi/g w,,.,,,,,,,,,,,,,,_,,,,, ,,,,..,,,, *--*- ,
20-04072-04 : DO B 1-06202A-FSWC-040-CV 06/18/18 10:30 4/25/2020 5/1/2020 20-04072 Plutonium-241 EML Pu-02 Modified 1.51E+00 5.85E+00 5.85E+00 9.95E+00 : u pCi/g
**--**--*-*--- EML Pu-02 Modified 9.59E-01 3.72E+00
- 3.72E+00 : 6.33E+00 u pCi/g 20-04072-05 TRG 81-06214A-FSFC-001-CV 05/05/18 15:15 : 4/25/2020 5/1/2020 20-04072
- Plutonium-241 :
20-04072-06 : TRG : B2-08101A-BJFC-007-CV 0 0-0 5 05/09/12 14:22 i 4/25/2020 5/1/2020 20-04072 : Plutonium-241 EML Pu-02 Modified -1.47E+00 7.51E+00
- 7.52E+00 1.29E+01 u pCi/g
! EML Pu-02 Modified 2.44E+00 7.59E+00 7.59E+00 1.29E+01 u pCi/g 20-04072-07 20-04072-08 TRG TRG 82-08101A-BJFC-007-CV0 5-1 0 82-08201-CJWC-A018-CV 0 0-0 5 05/09/12 14:22 05110112 12:56 4/25/2020 I 412512020 5/1/2020 5/1/2020 20-04072 20-04072
- Plutonium-241 Plutonium-241 EML Pu-02 Modified 7.81E+00 9.44E+00
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u u pCi/g pCi/g 20-04072-09 TRG 82-08201-CJWC-A018-CV 0 5-1 0 05/10/12 12:56 : 4/25/2020 5/1/2020 20-04072 Plutonium-241 EML Pu-02 Modified -8.68E+O0 1.01E+01 1.38E+01 u pCi/g 20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 5/1/2020 20-04072 Plutonium-241 EML Pu-02 Modified -1.04E+00 8.03E+00 8.03E+00
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20-04072-11 , TRG ! L 1-12109L-CJGS-001-SB-A 08/21/19 10:25 i 4/25/2020 5/1/2020 20-04072 : Plutonium-241 EML Pu-02 Modified -7.34E-01 5.65E+00 5.65E+00 9.68E+00 u pCilg 20-04072-12 TRG L 1-12106L-CJGS-001-SB-A 08/14/19 13:30 ! 4/25/2020 5/1/2020 20-04072 .,,,,_, Plutonium-241 EML Pu-02 Modified -4.80E+00 4.25E+00 4.27E+00 7.44E+00 u
': pCi/g
~---*------** 20-04072-01 '. LCS KNOWN 04/25/20 00:00 ' 4/25/2020 5/1/2020 20-04072
- Technetium-99 EIChroM TCS01 Modified 1.01E+03 : 2.22E+01 . pCi/g 20-04072-01 LCS SPIKE 04/25/20 00:00 I 412512020 5/1/2020 20-04072 T echnetium-99 EIChroM TCS01 Modified 1.04E+03 5.96E+00 1.04E+02 1.42E+00 pCi/g 20-04072-02 MBL : BLANK 04/25/20 00:00 4/25/2020 5/1/2020 20-04072 Technetium-99 EIChroM TCS01 Modified 2.58E-01 8.27E-01 8.28E-01 1.41E+00 u pCi/g
*----*-*--. ~**-~***-***
20-04072-03 DUP 81-06202A-FSWC-040-CV 06/18/18 10:30 4/25/2020 5/1/2020 20-04072 Technetium-99 EIChroM TCS01 Modified 1.00E+00 6.85E-01 6.92E-01
--- : 1.14E+00 u pCi/g 20-04072-04 DO
- 81-06202A-FSWC-040-CV 06/18/18 10:30 4/25/2020 5/1/2020 20-04072 T echnetium-99 EIChroM TCS01 Modified 1.79E+00 7.12E-01 7.34E-01 1.16E+00 pCi/g 20-04072-05 TRG B1-06214A-FSFC-001-CV 05/05/1815:15 4/25/2020 5/1/2020 20-04072 T echnetium-99 EIChroM TCS01 Modified 1.49E+00 6.88E-01 7.04E-01 1.13E+00 : pCi/g
*******-*~*~*****-- ; ; 1.13E+00 pCi/g 20-04072-06 : TRG B2-08101A-BJFC-007-CV 0 0-0 5 05/09/12 14 :22 4/25/2020 5/1/2020 20-04072 Technetium-99 EIChroM TCS01 Modified 2.07E+00 6.99E-01 7.28E-01 20-04072-07 i TRG 82-08101A-BJFC-007-CV 0 5-1 0 05/09/12 14:22 4/25/2020 5/1/2020 20-04072 T echnetium-99 EIChroM TCS01 Modified 1.29E+00 7.36E-01 7.47E-01 : 1.21E+00 : pCi/g 20-04072 T echnetium-99 EIChroM TCS01 Modified 9.57E-01 5.63E-01 5.71E-01 9.30E-01 pCi/g 20-04072-08 : TRG 82-08201-CJWC-A018-CV 0 0-0 5 05/10/12 12:56 4/25/2020 5/1/2020 '
20-04072-09 TRG ! B2-08201-CJWC-A018-CV 0 5-1 0 05110/12 12:56 4/25/2020 : 5/1/2020 20-04072 T echnetium-99 EIChroM TCS01 Modified 1.71E+00 6.65E-01 6.87E-01 1.08E+00 P~..i'.~- 20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 5/1/2020 20-04072 Technetium-99 EIChroM TCS01 Modified 1.46E+00 6.40E-01 6.56E-01 1.04E+00 i pCi/g i
- L 1-12109L-CJGS-001-SB-A 08/21/19 10:25 4/25/2020
- 5/1/2020 20-04072 : Technetium-99 EIChroM TCS01 Modified 1.73E+00 7.60E-01 7.80E-01 1.24E+00 pCi/g 20-04072-11 TRG 20-04072-12 i TRG : L 1-12106L-CJGS-001-SB-A 08/14/1913:30 4/25/2020 5/1/2020 20-04072 : T echnetium-99 EIChroM TCS01 Modified 1.17E+00 5.13E-01 5.26E-01 8.38E-01 ! pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect
( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/ 483-4621
Printed: 517/2020 9:23 PM Page 8 of 19 Report To: Work Order Details: Gerald Wood SDG: 20-04072 Eberline Analytical ___ Zion Solutions Purchase Order: 677116 -------------------1 r** ,. --------*--1*-* "" -----------------***---*-*--------- Final Report of Analysis 2701 Deborah Ave -----1---A_na/ysis Category: ENVIRONMENTAL w,wc-~------------------ 1 Zion, IL 60099 Sample Matrix: so Lab ID Sample Type Client ID I Sample Date Receipt Date Analysis Date Batch ID Analyte I Method Result CU CSU MDA Qualifier Ri:i~rt 2,0,:_!l:'.1_()72,:0,1 LCS _KNOWN 04/25/20 0000_ ---~/2~_20,20,_., -~2~/2_()2,0, __ 2,0,:0,4072 Strontium-90 EIChroM SRW01 Modified 1, 5.02E+01 ...2-~.8.-~E.:0,.~ **-*-----*-********-* ___ pCi/g --< 20-04072-01 LCS SPIKE 04/25/2000:00 4/25/2020 4/29/2020 20-04072 Strontium-90 EIChroM SRW01 Modified! 5.18E+01 1.42E+OO 1_81E+01 6_90E-01 pCi/g 20-04072-02 MBL 1 BLANK
- 04/25/20 00:00 4/25/2020 4/29/2020 20-04072 - Strontium-90 EIChroM SRW01 M~difi~d l 1 _96E-02 . 2.87E-02 2.95E-02 - *s_93E:_:-02 * -- -*u- ... pCi/g -
r-zo=o4012:03--- DUP-~-~- B1-06202A-FSWC-040-CV 06/18/1810:30 i 4/25/2020 4/29/2020 20-04072*--st;~~tium-90 EIChroM SRW01 Modified i -5.2i~~~3*=-3,~58.~~- ~~-~~~~:.:-~=-----7.73E-02 u pCi/g --1 4/29/2020 20-04072 Strontium-90 EIChroM SRW01 Modified I 9_38E-03 3_70E-02 3_72E-02 7_85E-02 U pCi/g 20-04072-04 DO B1-06202A-FSWC-040-CV 06/18/18 10:30 05/05/1815:15
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- 5_70E-02 - u ---- --- pCi/g ---1 I_2,_()-040,?2-05 :- TRG ----" s1:06214A:l'._~_C-001-CV 20-04072-06 TRG B2-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 , 4/25/2020 4/29/2020 20-04072 , Strontium-90 EIChroM SRW01 Modified 2.48E-02 3_32E:_02 3.43E-02 6.82E-02 : U pCi/g 20-04072-07 TRG B2-08101A-BJFC-007-CV O 5-1 0 05/09/12 14:22 4/25/2020 4/29/2020 20-04072 Strontium-90 EIChroM SRW01 Modified -8_90E-04 3_25E-02 3_25E-02 6_96E-02 _ U _ pCi/g 20-04072-08 TRG B2-08201-CJWC-A018-CV O 0-0 5 05/10/12 12:56 i 4/25/2020 4/29/2020 20-04072 Strontium-90 EIChroM SRW01 Modified -2_77E:02 2.69E-02 2.86E-02 ' 6:12E:.:-02* -* *** *u - ~
TRG B2-08201-CJWC-A018-CV O 5--1 0 05/10/12 12:56 4/25/2020 4/29/2020 20-04072 : Strontium-90 EIChroM SRW01 Modified 3.48E-03 2_83E-02 2.83E-02 6_04E-02 U pCi/g 20-04072-09 v wn~ =*-*-*-- 20-04072, 10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 4/29/2020 20-04072 Strontium-90 EIChroM SRW01 Modified -9.40E-03 3.41E-02 3.42E-02 7_39E-02 U pCi/g
--~-11 ___ ---TRG L1-12109L-CJGS-001-SB-A 08/21/1910:25 i 4/25/2020 4/29/2020 20-04072 : Strontium-90 EIChroM SRW01 Modified -2_56E -*-----3_76E + 3.86E-02 8_28E-02 , U pCi/g---t Strontium-90 EIChroM SRW01 Modified 2.42E-02 3.09E-02 3.20E-02 6.34E-02 U pCi/g I
20-04072-12 _ __ TRG L1-12106L-CJGS-001-SB-A 08/14/19 13:30 4/25/2020 4/29/2020 20-04072
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I--- ; __2,?:_!l::1_072,.::£.1...___~~8. KNOWN __ 04/25/2000:00 l 4/25/2020 4/27/2020 20-04072 ___________Cobalt-60 EPA901.1 Modified ~~i,~_2
- 1.02E+01 i --- ___ pCi/g ba.~~.072-01 LCS KNOWN 04/25/20 00:00
- 4/2512,?2,9____ 4/27/2020 20-04072 Cesium-137 EPA901.1 Modified 1.94E+0,2,__ 7.96E+OO _________ pCi/g _
1 1.45E+01 . 1.89E+01 2.39E+00 1 pCi/g 20-04072-01 LCS SPIKE 04/25/20 00:00 4/25/2020 4/27/2020 20-04072 Cobalt-60 EPA 901.1 Modified 2.37E+02 ----t 20-04072-01 LCS SPIKE 04/25/2000:00 : 4/25/2020 4/27/2020 20--04072 Cesium-137 -*--*iPA901_1 Modified 1.56E+02 1_37E+01 *r-1.59E+01 1.57E+OO pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=*Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 517/2020 9:23 PM Page 9 of 19 Report To: Work Order Details: Eberline Analytical I G_eraldW~_?d_ +************************** SDG: _20-04072 ------ 677116 Zion Solutions ........ .................... Purchase Order:* Final Re port of Anal ysis .. 1~,,,,,, 2701 Deborah Ave
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MENTAL_.,._,,,_,,,,_,,_~,M'- __ ,_,, ,,,,, _ __,,,,,,,__,~,,,_--,,,"'"""""---------I Zion, IL 60099 Sample Matrix. , SO Lab Sample ' Client Sample Receipt Analysis Batch Analyte Method Result CU CSU MDA Qualifier ' Report ID Type ID Date Date Date ID . . Units 20*04072*02 MBL BLANK 04/25/2000:00 4/25/2020 4/27/2020 20*04072, Actinium*228 EPA901.1 Modified******* _ _:_1~'.'§.:~2*** 7.02E*02 *. 7.02E*02 1.12E*01 U pC~~ .. _ 20*04072*02 i MBL ' BLANK *---- 04/25/2000:00 : 4/25/2020 4/27/2020 20*04072 Silver*108m EPA901.1 Modified *1.07E*02 3.23E*02 3.23E*02 3.11E*02 U pCi/g , .*20*04072*02 ' MBL BLANK .. 04/25/2000:00 4/25/2020 4/27/2020 20*04072 Barium*133 EPA901.1 Modified *1.49E*02 3.36E*02 3.36E*02 3.93E*02 U pCi/g 20.04072.02 MBL ! s°LANK ***** **. 04/25/200()'.oo 4/25/2020 4/27/2020 20*04072 Bismuth*214 EPA 901.1 Modified *1.14E*02 6.22E*02 6.22E*02 9.39E*02 u pCi/g 20*04072*02 MBL BLANK 04/25/2000:00 4/25/2020 4/27/2020 20*04072 Cobalt*60 EPA901.1 Modified 5.05E*03 2.55E*02 2.55E*02 ! 4.40E*02 U pCi/g 20.04072.02 : MBL BLANK 04/25/2000:00 ! 4/25/2020 4/27/2020 20*04072 ; Cesium*134 EPA901.1 Modified 2:i2E:03* 2.89E:02* 2.89E*02 ' 3.62E*02 U pCi/g *** 20*04072*02 MBL BLANK 04/25/2000:00 i 4/25/2020 4/27/2020 20*04072 i Cesium.137 EPA901.1 Modified 1.42E*02 2.86E*02 2.87E*02 5.01E*02 U ' pCi/g 1 U pCi/g
.**20*04072*02 MBL BLANK 04/25/2000:00 4/25/2020 4/27/2020 20*04072 Europium*152 EPA901.1 Modified 7.98E*02 7.05E*02 7.06E*02 9.37E*02 20*04072*02 MBL BLANK 04/25/2000:00 4/25/2020, 4/27/2020 20*04072 Europium*154 EPA901.1 Modified 1.97E*02 , 6.70E*02 6.70E*02 i 4.51E*02 U pCi/g *-20-0!072:02 MBL *** BLANK *...*.*.***.*. 04/25/2000~0() 4/25/2020 4/27/2020 20*04072 Europium*155 EPA901.1 Modified 9.34E*03 .*... 4.73E*02 4.73E*02 ' 6.30E*02 U I pCi/g 20*04072*02 MBL BLANK 04/25/2000:00 , .4/25/2020 4/27/2020 20*04072 Holmium*166m EPA901.1 Modified ..*.. 3.65E*02 4.29E*02 ' 4.29E*02 ' 3.72E*02 U , pCi/g ***20:()4072*02 MBL : BLANK 04/2512.9 00:00 , 4/25/2020 4/27/2020 2CJ:04072 lodine.129 .* EPA 901.1 Modified *2.51E-03 5.23E*02 i 5.23E*02 7.37E-02 U pCi/g 20*04072-02 ! MBL BLANK 04/25/20 00:00 4/25/2020 4/27/2020 20*04072 Potassium-40 EPA 901.1 Modified 3.19E-01 2.51 E-01 2.52E*01 5.75E*01 : U pCi/g 20-04072*02 : MBL BLANK 04/25/2000:00 4/25/2020 4/27/2020 20-04072 Manganese-54 EPA901.1 Modified 7.72E*03 . 2.13E*02 2.13E*02 3.63E-02 U pCi/g I* 20:04072-02 : MBL ! BLANK 04/25/20 00:00 : 4/25/2020 *. 4/27/2020 : 20*04072 Molybdenum-93 EPA 901.1 Modified . *6.89E-03 . 2.12E*02 2.12E*02 ! 3.08E*02 U , pCi/g 20*04072*02 MBL I BLANK 04/25/20 00:00 , 4/25/2020 4/27/2020 20*04072 1 Niobium*94 EPA 901.1 Modified 1.50E*02 2.37E*02 2.37E*02 ! 3.65E*02 , U pCi/g 20-04072*02 MBL BLANK 04/25/20 00:00 4/25/2020 4/27/2020 20*04072 : Lead*210 EPA901.1 Modified 3.17E*01 4.58E*01 4.58E*01 ! 6.69E*01 U ( pCi/g 20-04072*02 ! MBL , BLANK 04/25/2000:00 i 4/25/2020 4/27/2020, 20*04072 i Lead*212 EPA901.1 Modified ... 2.73E*02 1 4.45E*02 4.45E*02 ! 6.52E*02 U i pCi/g 20-04072*02 ! MBL BLANK 04/25/20 00:00 , 4/25/2020 4/27/2020 20*04072 ' Lead*214 EPA 901.1 Modified 2.00E*02 j 5.02E*02 5.02E*02 i 7.53E*02 U I pCi/g 20*04072*02 MBL BLANK 04/25/2000:00 4/25/2020 4/27/2020 20*04072 Promethium*145 EPA901.1 Modified 3.32E*02 6.87E*02 6.87E*02 9.40E*02 U j pCi/g 20.04072.02 MBL : BLANK 04/25/2000:00 4/25/2020 4/27/2020 20-04072 : Radium*226 EPA901.1 Modified *1.14E*02 6.22E*02 6.22E*02 9.39E*02 U pCi/g t-----~-******---',-------------+--*-------'"'"""""'------- -----*--+--------- ---'------~--------~--- +---'--*~,,,,,_
20*04072*02 ; MBL ! BLANK 04/25/2000:00 4/25/2020 4/27/2020 20*04072 Antimony*125 EPA901.1 Modified j 1.99E*02 4.96E*02 4.96E*02 9.23E*02 U J pCi/g 20*04072*02 ! MBL BLANK 04/25/2000:00 4/25/2020 4/27/2020 20*04072., Thorium*234 EPA901.1 Modified ! 7.38E*01*********4~4E-:_01 4.15E*01 6.72E.01 U pCi/g 20*04072*02 , MBL ! BLANK 04/25/2000:00 ,-4/25/2020 ** 4/27/2020 20*04072 i Thallium*208 EPA901.1 Modified ; 8.23E*02 6.42E*02 6.44E*02 1.28E*01 U : pCi/g 20-04072*02 MBL : BLANK 04/25/2000:00 : 4/25/2020 4/27/2020 20*04072 Uranium*235 EPA901.1 Modified I 8.75E*02 1.50E*01 1.50E*01 2.15E.01 U pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1*sigma);MDA=Minimal Detected Activity;LCS=*Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 517/2020 9:23 PM Page 10 of 19 Report To: Work Order Details: Eberline Analytica l _ G_eraldWo_od _ ************* SOG 20-04072 -- --- ***************** Final Re ort of Anal sis p y
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7 6 Zion, IL 60099 Sample Matrix. SO Lab Sample Client Sample Receipt Analysis Batch A lyt M h d R I CU CSU ! MDA : Q rfi Report Date Date Date ID na e et O esu t : : ua 1 ,er : Units ID Type
- ID 20*04072*03 i DUP B1*06202A*FSWC*040-CV 06/18/18 10:30 4/25/20~()_._ 4/27/2020 20*04072
- Actinium*228 -*** EPA 901.1 Modified .... 3.56E*01 2.24E*01 2.24E-01 : 5.24E*01 i U pCi/g 06/18/1810:30 4/25/2020 4/27/2020 20*04072 Silver*108m EPA 901.1 Modified 1.25E*02 4.64E*02 4.64E*02 : 7.07E-02 U pCi/g 20*04072*03
- DUP B1*06202A*FSWC*040-CV 06/18/1810:30 4/25/2020 4/27/2020 20*04072
- BarilJm.133 EPA901.1 Modified 1.50E*03 2.56E*02 2.57E*02 1.41E*01 U pCi/g 20*04072*03 DUP i B1*06202A-FSWC*040.CV 20-04072*03 i DUP : 81*06202A*FSWC-040.CV ~~ 06/18/1810:30 : 4/25/2020**-~~~.~~()_20 20*04072 Bismu!h*214___ EPA901.1 Modified 3.97E*01-
- 1.88E*01 1.89E*01 i 2.74E*01 pCi/g 06/18/1810:30 4/25/2020 4/27/2020 20*04072 Cobalt.60 EPA 901.1 Modified 3.90E*02 8.20E*02 8.21E*02 1.20E*01 U pCi/g 20*04072-03 DUP B1*06202A-FSWC*040-CV **-**--"~*-*- ...... - - - - - - * * * * * * * - - - - - - - - ' - - - - - - - - - - - - - - - - - - ' - - " - - - I
- ---~-- *-*-- ***/**- *********---***--- -*-** *-**- ***--*--*-*--*
06/18/1810:30 4/25/2020 4/27/2020 20*04072 Cesium*134 EPA901.1 Modified *2.78E*01 1.81E*01 1.82E*01 1.76E*01 U pCi/g 20*04072*03 DUP B1*06202A*FSWC*040-CV
**2.Cl_:()4072-03 DUP B1*06202A*FSWC*040.cv 06/18/1810:30 4/25/2020-- 4/27/2020. 20.04072 Cesium*137 ... EPA901.1 Modified *3.81E*03_ *--523E*02 5.23E*02 8.14E-02 u i pCi/g 06!1.~/1~~~-3? 4/25/2020 4/27/2020 ~Cl_:()_~()_72 Europium*15~-** EPA901.1 Modified *2.06E*01 2.83E*01 2.83E-01 2.37E-01 U pCi/g .2~_()_72*03 DUP B1-06202A*FSWC*040.C\/*-** ......
06/18/1810:30 4/25/2020 4/27/2020. 20*04072 Europium*154 EPA901.1 Modified 1.01E*01 1.56E*01 1.56E-01 1.24E*01 U pCi/g 20*04072*03 DUP B1*06202A*FSWC*040-CV 20-04072*03 DUP : B1*06202A*FSWC*040*CV 06/18/1810:30 : 4/25/2020 ___4/27/2020
- 20*04072 Europium*155 EPA 901.1 Modified ! 1.92E*01 --9~66E=o2* 9.71E-02 2.57E-01 U pCi/g 4/25/2020 4/27/2020 20-04072 Holmium*166m EPA901.1 Modified*- ********-7.09E:o2 4.66E-02*****:-**:;:i;7E-02 9.07E-02 U pCi/g *--
20*04072*03 : DUP : B1*06202A*FSWC*040-CV *--*---**********--** ... 06/18/1810:30
- - - - * ----*--*-*--*---* __________"_____ --+--*- - - - - - *--. __.,_____,_____________ ___________
06/18/1810:30 4/25/2020 4/27/2020 20*04072 lodine*129 EPA901.1 Modified -9.48E-02 1.40E-01 1.40E-01 2.12E-01 U pCi/g 20-04072-03 DUP B1*06202A-FSWC-040-CV J------,-----:-----*-*-***-***-**-------------,.-------'----------+-
**--- *******--**** - -*-*-***------+-- ----'------------ ---:------i------ --'--=---1 pCi/g 06/18/1810:30 4/25/2020 4/27/2020 20-04072 Potassium-40 EPA901.1 Modified 5.33E+OO 1.33E+OO 1.36E+OO 1.17E+OO :
20-04072-03 DUP B1*06202A-FSWC-040*CV ,__, '----'"'°""- ------~-- *~*- --~- - 06/18/1810:30 4/25/2020 4/27/2020 20-04072 Manganese-54 EPA901.1 Modified -1.27E*01 2.81E-01 2.81E*01 4.02E-01 U pCi/g 20*04072*03 DUP 81-06202A-FSWC*040-CV
* ()6/18/1810:30 .. 4/25/2020 4/27/2020 20*04072 Molybdenum-93 ** - EPA901.1 M~difi;d - 4.05E-03 ** _4.95E-02 4.95E-02 8.09E-02 U pCilg -**
20-04072-03 DUP 81-06202A~FSW.C-040-CV * ************ 06/18/1810:30 4/25/2020 4/27/2020
- 20*04072 Niobium*94 EPA 901.1 Modified 3.53E*02 . 3.29E-02 3.30E-02 7.25E-02 U pCi/g 20-04_~_72_-0_3_, __ D_U_P___s_1_-0_6_2_02_A_-_Fs_w_c_-0_4_o_.c_v_.
06/18/1810:30 *-~/25/2020 4/27/2020 20-04072 : Lead-210 EPA901.1 Modified. 7.39E-01 J 1.03E+OO 1.03E+OO 1.73E+OO : U pCi/g .. -~?:?~72.03 ' DUP B1-06202A*FSWC-040-CV 06/18/1810:30 4/25/2020 4/27/2020 20*04072 Lead*212 EPA901.1 Modified 3.69E-01 1.43E-01 1.44E-01 2.13E*01 pCi/g 20-04072-03 DUP B1*06202A-FSWC-040-CV i 06/18/1810:30 4/25/2020
- 4/27/2020 20-04072 Lead-214 EPA901.1 Modified 4.16E-01
- 1.57E*01 1.59E*01 2.60E-01 : pCi/g 20*04072-03 : DUP 81-06202A-FSWC*040*CV 06/18/1810:30 i 4/25/2020 4/27/2020 20-04072 Promethium.145 EPA901.1 Modified 2.20E-02 i 1.30E-01 1.30E*01 2.16E-01 i U pCi/g 20.04072.03 i DUP 81-06202A*FSWC-040-CV 06/18/1810:30 i 4/25/2020
- 4/27/2020 20*04072 Radium-226 EPA901.1 Modified 3.97E-01 1 1.88E-01 1.89E-01 2.74E-01 pCilg 20-04072-03 ' DUP 81-06202A*FSWC-040*CV 20*04072-03 DUP 81-06202A-FSWC*040-CV 06/18/1810:30 I 4/2512020 4127/2020 20-04072 Antimony-125 EPA 901.1 Modified 1.79E-02 7.68E-02 7.68E-02 3.30E-01 U pCi/g 06/18/1810:30 : 4/25/2020 4/27/2020 20-04072 Thorium*234 EPA 901.1 Modified 2.06E+OO 9.35E-01 9.41E-01 1.65E+OO U pCi/g 20.04072.03 DUP 81-06202A*FSWC-040-CV 06/18/1.il10:30 i 4/25/2020: 4/27/2020 20*04072 Thallium*208 ** EPA901.1 Modffi~d 2.57E-01 1.41E-01 1.42E-01 2.77E-01 U pCi/g
- 20:04072.03 DUP B1*06202A-FSWC-040-CV ,~,-m~---+------ i-------'-----~---- --.c.__;c__, ...
1------'----~-- --------------- -+---------1 Uranium-235 EPA 901.1 Modified j 9.50E-02 2.66E-01 2.66E-01 4.10E-01 U pCi/g 20-04072-03 DUP 81-06202A-FSWC-040-CV 06118/1810:30 4/25/2020
- 4/27/2020 20-04072 Sample;DO=Duplicate Original;U=Non-detect CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1*sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal
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Printed: 5/7/2020 9:23 PM Page 11 of 19 Report To: Work Order Details: Eberline Analytical , G_eraldWo~d -- SOG. 20-04072 ************-************ _ -- . . . . .. Final Re ort of Anal sis p y
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..20-04072-04 DO B1-06202A-FSV\l~:040-CV 06118/1810:30 4!~5!?.~20 4/27/2020 20-0~072. Silver-108m .......... EPA901.1 Modified 9.84E-03 3.48E-02 , 3.48E-02 6.21E-02 U ..........
20-04072-04 DO 81-06202A-FSWC-040-CV 06/1811810:30 4/2512020 412712020 20-04072 Barium-133 EPA901.1 Modified -1.08E-01 1.24E-01 1.25E-01 1.25E-01 U pCilg
------ -*** '""'"_,_______ ,,,_~*-~---- ---
20-04072-04 DO 81-06202A-FSWC-040-CV 06/18/1810:30 412512020 412712020 20-04072 Bismuth-214 EPA901.1 Modified 3.95E-01 1.24E-01 1.26E-01 2.81E-01 pCi/g c***-***-----.----'-------. .--...- - - - * - - - - - - ! , *- - - - - - - - - - - . . . . . C - - - - - - - + - - - - - - - - - - - + - -1.48E-o~. --------'------;---------*~-"--'---1
.?~:_G4072-04 DO B1-06202A-FSWC-04~~~- 06/18/1810:3_G__ i 412512020 4/2712020 20-04072 c~~alt:60 ,,,,,,,, EPA901.1 Modified 5.691=_~~2 < .5-:~~E-0_2,., ,,, 1_,08E:01 U pCi/g_
20-04072-04 DO 81-06202A-FSWC-040-CV 06/18/1810:30 I 4125/2020 4/27/2020 20-04072 Cesium-134 EPA901.1 Modified 4.12E-02 6.30E-02 6.31E-02 1.57E-01 U pCi/g t-----~--------*w,_m,~ *-------+-------i----~--- ---*-----~-**--~ ,,_,_,, ,.__,_,,, -----II*****"'" ' --'""" , " - - - - - - - - - - - - - * * * - - - - * : * *--**------ 20-04072*04 DO 81-06202A-FSWC-040-CV 06/18/1810:30 I 4125/2020 412712020 20-04072 Cesium-137 EPA901.1 Modified 1.37E-01 8.16E-02 8.19E-02 1.23E-01 pCi/g 20-04072-04 DO ; B 1-06202A-FSWC-040_:-CV . -*- 06118118 10:30 ! 412512020 4/27/2020 20-04072 E~ropium-152 EPA 901.1 Modified *-*-:;;: 18E-01 2.79E-01 2.80E-01 2.32E-01 *0**-----pCilg*- 20-04072-04 DO : 81-06202A-FSWC-040-CV 0611811810:30 4/2512020 4127/2020 20-04072:,_. Europium-154 _ EPA901.1 M~difi~d -3.08E-02 1.08E-0_~ 1.08E~O1 1.23E-01 U pCilg
~_D4072-04 DO B1-06202A-FSWC-040-C.~ 06/18/1810:30 i 412512020 412712020 20-04072 Europium-155 EPA901.1 Modified 1.47E-01 : 1.48E-01 1.48E-01 2.41E-01 __ U pCilg 20-04072-04 : DO 81-06202A-FSWC-040-CV . ---* 06118/1810:30 412512020 4/2712020 20-04072 Holmium-166m EPA901.1 Modified 2.05E-02 9.15E-02 9.15E-02 8.70E-02 U pCi/g 20-04072-04 DO 81-06202A-FSWC-040-CV 06118/1810:30 412512020 4/27/2020 20-04072 lodine-129 EPA901.1 Modified -1.46E-02 1.39E-01 1.39E-01 , 2.25E-01 U pCi/g 20-04072-04 : DO 81-06202A-FSWC-040-CV ---06/18/1810:30 [ 4125/2020 4/27/2020 ' 20-04072 Potassium-40 EPA901.1 Modified 5.71E+00 1.33E+00 1.36E+00 1.03E+00 pCilg 20-04072-04 DO ' 81-06202A-FSWC-040-CV 06/18118 10:30 1 412512020 ' 412712020 20-04072-** Manganese-54 EPA 901.1 Modified -3.94E-02 2.94E-01 2.94E-01 3.94E-01 U pCilg ---- - .. .... ,' . - + - - - - - - - - . . L . - - ' - - - - - f... ,.. '*---.. *---*--... --.-*<-*
20-04072-04 DO 81-06202A-FSWC-040-CV 06/18/1810:30 412512020
- 412712020 20-04072 , Molybdenum-93 EPA 901.1 Modified 1.65E-02 5.15E-02 5.15E-02 8.71E-02 ! U pCi/g 20-04072-04 DO 81-06202A-FSWC-040-CV 0611811810:30 -4:;25/2020 4/27/2020 --20-04072-, Niobium-94 EPA901.1 Modified -6.70E-03 5.79E-02 5.79E-02 7.05E-02 U pClig--
20-04072-04 DO ' 81-06202A-FSWC-040-CV 06/18/1810:30 412512020 412712020 20-04072 Lead-210 *-* EPA901.1 Modified 1.52E+00 1.36E+00 1.36E+00 2.25E+00 U pCilg 20-04072-04 ' DO I 81-06202A-FSWC-040-CV 06/1811810:30 I 412512020 412712020 20-04072 Lead-212 ... iPA901.1 Modified*-
- 3.09E-01 : 1.09E-01 U0E-01 2.26E-01 pCilg t - - - - - - - - - - - - - - - - - - - - - * - - t - - - - - - - + - - - - - ; - - - - , - - - - ~ - - - - - - - + - - - - - - - - - - - - - - ' - - - - - - +1.26E-01 ------;---------,-~---"-**---
20-04072.04 : DO ! 81-06202A-FSWC-040-CV 06118/1810:30 412512020 4/2712020 20-04072 Lead-214 EPA901.1 Modified 4.22E-01 : 1.28E-01 3.22E-01
- pCilg 20-04072-04 DO : B1-06202A-FSWC-040-CV 06118/1810:30 4/2512020 4127/2020 20-04072 Promethium-145 EPA901.1 Modified 5.31E-02 1.32E-01 1.33E-01 ! 2.22E-01 i U , pCi/g 20-04072-04 DO i 81-06202A-FSWC-040-CV 06/18/1810:30 4125/2020 4127/2020 : 20-04072 i Radium-226 EPA901.1 Modified 3.95E-01 1.24E-01 1.26E-01 i 2.81E-01 . 1 pCilg 20-04072-04 DO B1-06202A-FSWC-040-CV 06/18/1810:30 4125/2020. 412712020 20-04072--, Antimony-125 EPA901.1 Modified 1.54E-01 i 1.81E-01 1.81E-01 3.19E-01 -----U-~- pCi/g 20-04072-04 DO 81-06202A-FSWC-040-CV 06118/1810:30 4125/2020 4/2712020 20-~-~!~.. Thorium-234 EPA 901.1 Modified 1.20E+00 1.43E+00 .._1~4~E+00 2.40E+00 U ' pCilg 20-04072-04 DO B1-06202A-FSWC-040-CV 06118/1810:30 4/25/2020 4/27/2020 20-04072 1 Thallium-208 EPA901.1 Modified 3.67E-01 1.71E-01 1.72E-01 2.42E-01 I pCi/g 20::04072-04 DO B1-06202A-FSWC-040-CV 06/18/1810:30 412512020 412712020 20-04072 ! Uranium-235 -- EPA901.1 Modified J 8.27E-02 : 2.71E-01 2.71E-01 4.15E-01 U , pCj/g-CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect (1§) EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 517/2020 9:23 PM Page 12 of 19 Report To: Work Order Details: Eberline Analytical G_erald wo_od Zion Solutions
' SOG Purchase Order* ?Q~Q-~072 677116 Final Re port of Anal ysis ----- 2701 Deborah Ave . - .... --- ---- --- ,... Analysis Category: _E_N_V-IR_O_N_M-ENTAL __,__,__________
f,-,, _ _,,-,, ***------------"-"-~-~---*-*--- ,,_,_,__,_,_,,, ---+---~----*-- * ,M_, _ _,,_ ___ _,,_,,_ _ _ _ __, Zion, IL 60099 Sample Matrix: SO Lab Sample Client Sample Receipt Analysis Batch A I M h R I CU : CSU MDA
- Q rfi Report ID Type ID Date Date Date ID na yte et od esu t , , ua 1 ,er Units 20-04072--05 TRG B1-06214A-FSFC-001-CV 05/05/1815:15
- 4/25/2020 4/27/2020 20-04072 Actinium-228 EPA901.1 Modified -127E-01 1A9E-01 1A9E-01 8A9E-01 U pCi/g 20-04072-05 TRG 81-06214A-FSFC-001-CV 05/05/1815:15 4/25/2020 4/27/2020 20-04072 Silver-108m EPA90U Modified 3.17E-02 1.22E-01 L22E-01 U9E-01 U pCi/g 20-04072-05 TRG B1-06214A-FSFC-001-CV 05/05/18 15:15 4/25/2020 4/27/2020 20-04072 Barium-133 EPA 901,1 Modified i . 1~07E:02 6.60E-02 6.60E-02 2.75E **u * *. - pCi/g
,.20-04072-05 °TRG-:-131:-06214A-FSFC-001~CV 05/05/18 15:15 i 4/25/2020 4/27/2020 20-04072 I Bismuth-214 ---EPA901 11~1~dified I 7 JJ3E:a;* i 2.65E-01 - 2.67E-01 2.56E-01 : pCi/g 20-04072-05 1 TRG _ ~1~0_6214A-FSFC-001-CV 05,1()_5/18_ 15:15, _ ~/25!~?20 4/27/2020 20-04072 : Cobalt-60 EPA 901.1 Modified i :5:4_1E-02 ' 1.85E-01 1.85E-01 2.88~:0,1_ __ ,, U pCi/g 20-04072-05 TRG : B1-06214A-FSFC-001-CV .,, 05/05/1815:15 4/25/2020 4/_2_7/~~~o,,__ _2-9*04072 Cesium-134 EPA901.1 Modified -4.09E-02 " 9.97E-02 9.97E-02 3.59E-01 U pG_~!l_ __ 20-04072-05 I TRG : B1-06214A-FSFC-001-CV 05/05/1815:15 4/25/2020 4/27/2020 20-04072 Cesium-137 EPA901.1 Modified 2.89E-03 1A8E-01 1A8E-01 2.07E-01 U pCi/g 20-04072-05 TRG I B1-06214A-FSFC-001-CV 05/05/1815:15 4/25/202? ___4l27!~020: 20-04072 J Europium-152___ EPA901.1 Modified ~3.Ei9E:01__ ,_ 5.24E-01 5.25E-01 3.08E::!_1_ _ LJ __ pCi/g 20-04072-05 TRG [ 81-06214A-FSFC-001-CV 05/05/1815:15 4/25/2020 4/27/2020 20-04072 . Europium-154 EPA 901.1 Modified -3*'.:!-E::_0_1___.. __ 4.60E:?.1......*. 4.60E-01 1.72E-01 U f:.~~9-20-04072-05 : TRG ! 81-06214A-FSFC-001-CV 05/05/18 15:15 ! 4/25/2020 4/27/2020 ' 20-04072 Europium-155 EPA 901.1 Modified 2A4E-01 _2.07E-01 ___ 2.08E-01 3.25E-01 U pCi/g 20-04072-05 TRG B1-06214A-FSFC-001-CV 05/05/1815:15 4/25/2020 4/27/2020 20-04072 Holmium-166m EPA901.1 Modified -3A8E-02 1.83E-01 1.83E-01 1.39E--01 U pCi/g
**********-'"'~****-*--- *- ' ***-' ..-. ***-**-*-***-* . -* *-**---~*-~*
20-04072-05 TRG --~1-06214A-FSFC-001-CV 05/05/1815:15 4/25/2020: 4/27/2020 20-04072 lodine-129 EPA901.1 Modified i 2.86E-02 2AOE-01 2AOE-01 3.60E-01 U pCi/g 20-04072-05 TRG : B1-06214A-FSFC-001-CV 05/05/1815:15 ' 4/25/2020
----*---*--- 4/27/2020 20-04072 Potassium-40 EPA901.1 Modified 6A5E+OO 4.62E-01 1.84E+OO 4.28E-01 1.87E+OO 4.28E-01 8.62E-01 8.84E-01 U
__,,__ ____ pCi/g pCi/g
,~-~
20-04072-05 TRG 81-06214A-FSFC-001-CV 05/05/1815:15 i 4/25/2020 4/27/2020 20-04072 Manganese-54 EPA901.1 Modified 20-04072-05 TRG i B1-06214A-FSFC-001-CV 05/05/1815:15 (4/25/2020 4/27/2020 20-04072 Molybdenum-93 EPA901.1 Modified 3.42E-02 i 1.02E-01 ****1:o:i"E-01 1.37E-01 *u . . . pCi/g 20-04072-05 TRG i 81--06214A-FSFC-001-CV 05/05/1815:15 4/25/2020 4/27/2020 20-0407:i°* Niobium-94 EPA901.1 Modified 2.32E-02 1.21E-01 1.21E-01 1.79E-01 U pCi/g 20-04072-05 TRG : B1-06214A-FSFC-001-CV 05/05/1815:15 4/25/2020 4/27/2020 20-04072 i Lead-210 EPA 901.1 Modified 1.38E+OO 1.56E+OO 1.56E+OO 2.45E+OO U j pCi/g 20-04072-05
- TRG ' B1-06214A-FSFC-001-CV 05/05/1815:15 4/25/2020 . . 4/27/2020--20-04072 Lead-212 EPA901.1 Modified 7.02E-01 ***2:39E=01_,,_ 2.42E-01 3.38E-01 ' pCi/g 20-04072-05 j TRG 81-06214A-FSFC-001-CV 05/05/1815:15 4/25/2020 4/27/2020 20-04072 Lead-214 EPA901.1 Modified 5.56E-01 2.39E-01 : 2.41E-01 4.17E-01 i pCi/g 20-04072-05 J TRG i B1-06214A-FSFC-001-CV 05/05/1815:15 i 4/25/2020 4/27/2020 20-04072 i Promethium-145... EPA901.1 Modifi~d...... -2.11E-01 2.3:iii=-01--
- 2.32E-01 3.16E-01 U pCi/g 20-04072-05 TRG B1-06214A-FSFC-001-CV 05/05/1815:15 i 4/25/2020. 4/27/2020. 20-04072 ; Radium-226 EPA901.1 Modified 7~03E=01 2.65E-01 2.67E-01 2.56E-01 pCi/g 20-04072-05 i TRG
- B1-06214A-FSFC-001-CV 05/05/1815:15 i 4/25/2020: 4/27/2020 20-04072 Antimony-125 EPA901.1 Modified 4.16E-01 4.52E-01 4.52E-01 7.29E-01 U pCi/g 20-04072-05 : TRG i 81-06214A-FSFC-001-CV 05/05/1815:15 J 4/25/2020 4/27/2020 20-04072 1 Thorium-234 EPA901.1 Modified i 2.43E+OO 1.33E+OO 1.33E+OO 2.19E+OO U .. '. . pCi/g 20-04072-05 ' TRG : 81-06214A-FSFC-001-CV 05/05/1815:15 j 4/25/2020 4127/2020 i 20-04072 j Thallium-208 EPA901.1 Modified i 4.50E-01 2.41E--01 2.42E-01 4.10E-01 . pCi/g 20-04072-05 TRG 81-06214A-FSFC--001-CV 05/05/18 15:15 i 4/25/2020 4/27/2020 20-04072 : Uranium-235 EPA 901.1 Modified ! 5.84E-01 4.01E-01____ 4.02E-01 6.81E-01 U
- pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect
( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/ 483-4621
Printed: 5/7/2020 9:23 PM Page 13 of 19 Report To: Work Order Details: Eberline Analytical t Gerald Wood
~-_ ........ Zion Solutions__ ..... *--~---* ***-** ____ ... Purchase Order:
SDG. 20-04072 677116
. .... .,,.. -* ""~-*<S~******-***---*~-*- ........ ~*.
Final Report of Analysis 2701 Deborah Ave ~ ~ Analysis Category: ENVIRONMENTAL
-*----*---**-* --*------ -------------~ *-**=*m**~~~--~ **~*
Zion, IL 60099 m-*~**~*~w*~- Sample Matrix: so Client Sample Receipt Analysis Batch Report Lab Sample Analyte Method Result cu CSU MDA Qualifier. Units ID Type . ID Date Date Date ID I 20.04012-06 TRG 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14 :22 ____ 4/25/2020
,,,,,_, 4/27/2020 20-04072 ----.------,,,, ____ .,,,,_,,,,,,,,,Actinium-228 ---
EPA 901.1 Modified 7.82E-01 8.24E-01 : 8.25E-01 i 1.38E+OO u oCi/q 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Silver-108m EPA 901.1 Modified -7.38E-02 2.77E-01 2.77E-01 : 2.37E-01 u l 20-04072-06 TRG i B2-08101 A-BJFC-007-CV O 0-0 5 ...,,,.., Barium-133
.., *..... f********
EPA 901.1 Modified 2.93E-01 5.75E-01
. 5.76E-01 i 7.52E-01 u . pCi/g___
20-04072-06 TRG 82-08101A-BJFC-007-CV O 0-0 5 05/09112 14:22 4/25/2020 4/27/2020 20-04072 ,,,, ,~
---**~*-* I-*- .,. -*-- ~---*----*
B2-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Bismuth-214 EPA 901.1 Modified 1.34E+OO 4.57E-01 4.62E-01 3.37E-01 pCi/g 20-04072-06
- TRG
*--* _,_,_....., *-----------** 7.34E-01 u pCi/g EPA 901.1 Modified -5.83E-01 5.59E-01 5.60E-01 20-04072-06 -**-**-~~-***
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---* ,,. ,,,,*..* *-'**-*~*-
EPA 901.1 Modified 4.82E-01 1.88E+OO 1.88E+OO 3.99E+OO
. u pCi/g 20-04072-06 TRG - -*---*~~~~~* *~-*"- :
20-04072-06 TRG 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14 :22 4/25/2020 4/27/2020 20-04072 Cesium-137 EPA901.1 Modified 1.15E-01 2.37E-01 2.37E-01 3.78E-01 u pCi/g
--------- ------* I 20-04072-06 TRG B2-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 :
Europium-152 EPA 901.1 Modified
. 2.89E-01 8.81E-01 8.81E-01 9.93E-01 I
u pCi/g 20-04072-06 TRG : 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Europium-154 EPA 901.1 Modified 4.41E-01 9.70E-01 9.70E-01 6.53E-01 u pCi/g v~~-------*~-'owo*~-*- 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 . Europium-155 EPA901.1 Modified____ 6.54E-02 1.28E+OO 1.28E+OO 1.85E+OO : u pCi/g 20-04072-06 I t------------ -** TRG ,_,.,.._ .. ____ ,~_, __ ,,
--*---*--*-*-, -------*----~- ~---*~ ,,_,_,,_,.,,,v=-------~--~~~ rn*, -*~~**-=*-------- ---~-----
20-04072-06 TRG 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Holmium-166m EPA901.1 Modified 3.81E-01 2.78E-01 2.79E-01 3.12E-01 l u pCi/g
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20-04072-06 , TRG 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 lodine-129 EPA 901.1 Modified 2.64E-01 6.11E-01 6.11E-01 9.18E-01 u pCi/g
! EPA901.1 Modified I 8.56E+OO 3.05E+OO 3.08E+OO 3.60E+OO : pCi/g 20-04072-06
- TRG B2-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Potassium-40 1 zo-04072-06
- TRG B2-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 : 4/25/2020 4/27/2020 20-04072
- Manganese-54 EPA 901.1 Modified-** _! _-1.66E+01_ : _ 1.31E+02 1.31E+02 1.78E+02 u pCi/g
,.,.,*-.w*"S""""-***** --,*-*********~'"'****' ,.,,.. ,.
20-04072-06 I TRG B2-08101A-BJFC-007-CV O 0-0 5 05/09/12 14 :22 i 4/25/2020 4/27/2020 20-04072 Molybdenum-93 EPA 901.1 Modified i... 6.50E-02 3.10E-01 3.10E-01 4.58E-01 I u pCi/g 20-04072-06 I TRG B2-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Niobium-94 ____ __ EPA 901.1,,,Modified ,,,.,, .. ,. ,.,,,..,,,_. 1.74E-02 1.98E-01 1.98E-01 2.70E-01 u pCi/g
-------~*----
20-04072-06 : TRG B2-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Lead-210 EPA 901.1 ~o_di~E>d .. L 4~33E+OO 4.51E+OO
~********~******"-'-*m*
4.51E+OO 7.13E+OO u pCi/g
-----~*
B2-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Lead-212 EPA 901.1 Modified l 1.07E+OO 4.84E-01 4.88E-01 7.40E-01 pCi/g ~'._D_4.072-06 I TRG ----- TRG 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072
- Lead-214 EPA 901.1 Modified I
1.33E+OO 4.24E-01 4.30E-01 1.24E+OO pCi/g 20-04072-06 I i 20-04072-06 TRG 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Promethium-145 EPA901.1 Modified l 3.88E-01 6.81E-01 6.81E-01 1.06E+OO u pCi/g B2-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 j Radium-226 EPA 901.1 Modified 1.34E+OO 4.57E-01 4.62E-01 3.37E-01 pCi/g 20-04072-06 : TRG I 20-04012-06 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Antimony-125 EPA 901.1 Modified -1.51E+OO 3.40E+OO 3.40E+OO 4.75E+OO u pCi/g ......,....__,_,_ TRG 20-04072-06 TRG 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Thorium-234 EPA 901.1 Modified 7.69E+OO 3.52E+OO 3.54E+OO 5.86E+OO u pCi/g 20-04072-06 TRG 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Thallium-208 EPA 901.1 Modified 3.SOE-01 6.33E-01 6.33E-01 9.84E-01 u pCi/g I 20-04072-06 TRG 82-08101A-BJFC-007-CV O 0-0 5 05/09/12 14:22 4/25/2020 4/27/2020 I 20-04072 Uranium-235 EPA 901.1 Modified 2.58E-01 1.08E+OO 1.08E+OO 1.65E+OO u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=,Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 517/2020 9:23 PM Page 14 of 19 Report To: Work Order Details: Eberline Analytica l G_eraldWo_od Zion Solutions _____
****************** SOG.
Purchase Order: 20-04072 6771_1_6_ _ _ _ __ Final Report of Analysis 2701 Deborah Ave** '""'"""w '" , , , Analysis C~t~g;ry, .....
,0 ENVIRONMENTAL *---* *, _ _ _ _ _ _ _ _ _ _ , , _ , , , , _ _ _ _ , _ _ ~=-*" ,wm",mw,m _ _ _ _ ,_",___ ~ o - * *
- Zion, IL 60099 Sample Matrix: SO Sample Receipt Analysis Batch A R CU CS .. Report Lab Sample Client ID Type ID Date Date Date ID na Iyte Method esu It U MDA Qualifier Units 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Actinium-228 EPA 901.1 Modified 1.48E+00 ' 6.73E-01 6.77E-01 1.21E+00 pCi/g 20-04072-07 -*" TRG B2-08101A-BJFC-007-CV 0 5-1 0 05/09/1214:22 4/25/2020 4/27/2020 20-04072 Silver*108m EPA901.1 Modified *1.03E-01 1.41E-01 1.41E-01 2.06E-01 U pCi/g 20-04072-07 TRG
- B2-08101A-BJFC-007-CV05-10 ........
05/09/12 14:22 . 4/25/2020 4/27/2020 20*04072 _________ Barium-133 ....... ,... EPA_901.1 Modified ____ ..... 8.29E-02 __ 1.69E*01 ... _____ 1.69E-01 4.70E*01 ...... U --*--*--****pCi/g __ 20-04072-07 TRG ! B2-08101A-BJFC-007-CV 0 5-1 0 05/09/1214:22 4/25/2020 4/27/2020 20*04072 Bismuth*214 *. EPA901::. Modified __.1_:2.2.~.;00 6.96E-01 6.98E-01 1.08E+00 . pCi/g 2,0-04072-07 TRG B2-08101A-BJFC-007-CV05-10
' 4/25/2020 4/27/2020 20-04072 Coba\t.60 EPA 901.1 Modified 1.19E-01 . 4.80E-01 4.80E-01 7.55E-01 U pCi/g ___ .,
20*04072*0_~. *i . TRG : B2*08101A*BJFC-007-CV 0 5.1 0 05/09/12 14:22 ,... 20-04072-07 : TRG 82-08101A-BJFC-007-CV 0 5-1 0 05/09/12 14:22 -*-~!~512,_°.2..°. 4/27/2020 20-04072 , Cesium:_1.3-4 EPA 901.1 Modified -*** _ O.OOE+OO
- r 1.27E~??... 1.27E+00 .3.23E+OO _ U ____...,.. pCi/g 20-04072-07 i TRG 82-08101A-BJFC-007*CV05-1 0 05/09/1214:22 4/25/2020 4/27/2020. 20*04072 Cesium*137 EPA901.1 Modified I *1.22E-01 2.28E-01 : 2.28E-01 3.10E-01 U . pCi/g 05/09/1214:22 4/25/2020 4/27/2020 20-04072 Europium-152 EPA901.1 Modified -2.32E*01 8.27E-01 8.27E-01 , 9.63E*01 U pCi/g 20-04072-07 : TRG ! 82-08101A*BJFC-007-CV05-1 0 05/09/1214:22 4/25/2020 4/27/2020 20*04072 Europium*154 EPA901.1 Modified :1.58E-01 8.76E-01 --8.76E-01 .*.. **6.04E*01 U .......*. --pCi/g 20-04072-07 : TRG ! 82-08101A-BJFC*007-CV0 5-1 0 20~04072.07 TRG : B2*08101A-BJFC-007-CV05-1 0 05/09/1214:22*--**--4/25/2020 4/27/2020 20-04072
- Europium-155 EPA901.1 Modified *;--_69E:-oo - *1*:aaE+OO ! 1.0SE+00 1.65E+00 U- , --p~
20-04072-07 TRG 82-08101A*BJFC-007_:--CV*0--5-1 0 05/09/1214:22 4/25/2020 4/27/2020 20-04072 : Holmium-166m EPA901.1 Modified ! 8.14E-02 ' 3.02E-01 3.02E-01 2.88E-01 U T' pCi/g
.,, 20-04072-07 TRG j B2-08101A-BJFC-007-CV 0 5-1 0 05/09/12 14:22 , 4/25/2020 4/27/2020 20-04072 lodine-129 EPA 901.1 Modified 3.45E-01 3.43E-01 _,., ~- 3.43E-01 5.53E-01 IJ .. *s-*M--** *** **-pci;g 05/09/12 14:22 : 4/25/2020 4/27/2020 20-04072 Potassium-40 EPA 901.1 Modified ...~.:,5-~+01 ! 3.01E+00 3.0?.1§:+00 1.92E+00 pCi/g 20-04072-07 TRG : 82-08101A-BJFC-007-CV °._5-:,2__0 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 Manganese-54 EPA 901.1 Modified -1.12E+02 1.23E+02 1.23E+02 1.52E+02 U pCi/g 20-04072-07 TRG 82-08101A-BJFC-007-CV 0 5-1 0 05/09/1214:22 : 4/25/2020 4/27/2020 20-04072 Mo\ybdenum-93 EPA901.1 Modified 3.27E-02 __ ,, 2.06E-01____ 2.06E-01 , 3.48E-01 U pC~- -~0=~~?2-07 TRG ; 82-08101A-BJFC-007-CV0 5-1 0 05/09/1214:22 4/25/2020 4/27/2020 20-04072 Niobium-94 EPA901.1 Modified 1.51E-01 1.20E-01 1.21E-01 2.46E-01 U pCi/g 20-04072-07 TRG 82-08101A-BJFC-007-CV05-1 0 20-04072-07 TRG 82-08101:;;_:-BJFC~007-CV 0 5-1 0 05/09/12 14:22 4/25/2020 4/27/2020 20-04072 i Lead-210 EPA 901.1 Modified 3.ssii:oo ' 4.40E+00 4.40E+00 7.34E+00 j u .. ,,,, pCi/g - ~0-04072-07 TRG 82-08101A-BJFC-007-CV05-1 0 05/09/1214:22 '4/25/2020 412ii2oio 20-0407~ L~~d:212'""' EPA901.1Modified,_ 7.44E-01 -~~5-§-01 2.88E-01 7.47&01*-- u pCi/g 05/09/1214:22 4/25/2020 4/27/2020 20-04072 Lead-214 EPA901.1 Modified 9.94E-01 4.58E-01 4.61E-01 7.75E-01 , pCi/g 20-04072-07 TRG 82-08101A-BJFC-007-CV05-1 0 20-04072-07 TRG 82-08101A-BJFC-007-CV05-1 0 05/09/1214:22 4/25/2020 4/27/2020 20-04072 i Promethium-145 EPA901.1 Modified 2.32E-01 , 5.73E-01 : 5.73E-01 7.98E-01 u *---o~
05/09/1214:22 ' 4/25/2020 4/27/2020 __ 20-04072 _, Radium-226 EPA901.1 Modified 1.22E+00 : 6.96E-0~--- 6.98E-01 j 1.08E+00 pCi/g ---*** 20-04072-07 i TRG B2-08101A-BJFC-007-CV0 5-1 0 05/09/1214:22 ; 4/25/2020 4/27/2020 20-04072 Antimony-125 EPA901.1 Modified 1.05E+00 : 2.55E+00 , 2.55E+00 4.60E+00 U pCi/g 20-04072-07 TRG 82-08101A-BJFC-007-CV05-1 0 05/09/1214:22 i 4/25/2020 4/27/2020 20-04072 Thorium-234 EPA901.1 Modified 3.08E+00 3.34E+00 3.35E+00 4.83E+00 U pCi/g 20-04072-07 TRG 82-08101A-BJFC-007-CV05-1 0 05/09/12 14:22 : 4/25/2020 4/27/2020 20-04072 Thallium-208 EPA 901.1 Modifi~cl ---- 3.96E-01 6.22E-01 6.22E-01 1.04E+00 U .... ,..,., pCi/g 20-04072-07 TRG 82-08101A-BJFC-007-CV 0 5-1 0 20-04072-07 TRG 82-08101A-BJFC-007-CV05-1 0 05/09/1214:22 ; 4/25/2020: 4/27/2020 20-04072 Uranium-235**-* *-*EPA901.1 Modified ... I 1.48E-01 9.48E-01 9.48E-01 1.30E+00 U pCi/g Sample;DO=Duplicate Original;U=Non-detect CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal ( ~ EBERL INE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 5/7/2020 9:23 PM Page 15 of 19 Report To: Work Order Details: Gerald Wood SDG. 20-04072 Eberline Analytical I Zion Solutions Purchase Order.* 677116 Final Report of Analysis 2701 Deborah Ave . + _'-'.!7§.'t.~i.s,.ga!EifL().'Y:..* __ ENVIRONMENTAL _ _ _ ......... *******~=J Zion, IL 60099 Sample Matrix: SO Lab ID Sample Type Client ID I Sample Date Receipt Date Analysis Date Batch ID Analyte I Method I Result CU CSU MDA Qualifier Ri~i~rt 20*04072-08 TRG B2*08201*CJWC-A018*CV00-05 05/10/1212:56 4/25/2020 4/27/2020 20-04072 Actinium-228 EPA901.1 Modified 1.89E+OO 1.33E+OO 1.34E+OO : 2.70E+OO U pCi/g 20-04072*08 TRG ..** B2-08201-CJWC*A018~Cv*o*o:o5 05/10/1212:56 4/25/2020 4/27/2020: 20*04072 Silver*108m EPA901.1 Modified *1.60E-01 : 3.91E-01 3.91E*01 4.55E*01 U pCi/g t~04072*08 TRG B2*08201-C.JWC:Ao1icvoo~o5 05/10/1212:56 : 4/25/2020 4/27/2020 20-04072 Barium*133 EPA901.1 Modified 1.34E*01
- 2.59E*01 : 2.59E*01 : 9.98E-01 u pCi/g j_ici:()4072*0~**-**:.~. s2.6s20*,:cJWC-"2?!!l:CV_(l_?:05 05/10/1212:56 ! 4/25/2020 4/27/2020 20*04072 Bismuth*214_._,_ EPA901.1 Modified 1.31E+OO ; 6.33E*01 : 6.36E*01 9.56E*01 pCi/g 20.04072.os TRG B2-08201*CJWC*A018.CV00*0*5*****05/10/1 212:56 4/25/2020, 4/27/2020 20*04072 Cobalt*60 EPA901.1 Modified ******* *8.17E*01 1.52E+OO .*. 1.52E+OO 1.60E+OO *****************************P.~ii.g 20*04072*08 TRG : B2*08201*CJWC*A018*CVO O*O 5 05/10/1212:56 i 4/25/2020 4/27/2020 20*04072 Cesium*134 EPA901.1 Modified *5.14E+OO 6.77E+OO 6.77E+OO 7.60E+OO . U pCi/g 20~04072*08 TRG .- B2*08201*CJWC*A018*CV O O*O 5 05/10/12 12:56 ' 4/25/2020 4/27/2020 20-04072 Cesium* 137 EPA 901'.1Mod-ifi~d ,* 8.97E*02 4.50E*01 4.50E*01 6.93E*01.. U
** pCiig*-**
20*04072*08 TRG ., ... B2*08201*CJWC*A018*CV00-05 05/10/1212:56 4/25/2020 4/27/2020 20*04072 ,-* Europium*152 EPA901.1 Modified *1.78E+OO ' 2.31E+OO 2.31E+OO 1.19E+OO -**** U pCi/g 20-04072*08 TRG B2*08201*CJWC*A018.CV00-05 05/10/1212:56 4/25/2020 4/27/2020' 20*04072 Europium*154 EPA901.1 Modified *2.01E*01 ' 1.86E+OO 1.86E+OO 8.00E*01 U . pCi/g ~ 20.0407~* TRG 1
- B2*08201*CJWC*-"2_~1.8:E.? O*O 5 05/10/12 .'..~~~ __;__4/25/~020 4/27/2020 20*04072
- E~*;~;;;;;-,;,. 1.55 *
- EPA 901.1 Modified -- ==*4.58E*01 1.26E+OO 1.26E+OO 1.94E+OO U -~=y~ii_g_==~=
20*04072*08 TRG B2*08201-CJWC*A018*CV00-05 05/10/1212:56 4/25/2020 4/27/2020. 20*04072 Holmium*166m EPA901.1 Modified 3.42E-01 , 5.13E-01 5.13E*01 3.33E*01 U 20*04072*08 ' TRG : B2*08201*CJWC-A018.CV O O*O 5 05/10/12_1_2:56 4/25/2020 4/27/2020 20-04072 * . .....l"dine*129 EPA 901:.1 ..Modified *1.99E*02 7.20E*01 7.20E*01 1.0SE+OO *******~*-**** pCi/g 20*04072*08 TRG
- B2*08201*CJWC*A018.CV00-05 05/10/1212:56 4/25/2020 4/27/2020 20*04072 Potassium-40 EPA901.1 Modified 6.63E+OO 4.17E+OO 4.18E+OO 5.44E+OO pCi/g 20.04072.08 TRG ' B2*08201*CJWC*A018*CV00-05 05/10/1212:56 : 4/25/2020: 4/27/2020
- 20*04072' Manganese.54 EPA901.1 Modified ! -2.99E+01 : 2.03E+02 ' 2.03E+02 3.28E+02 U pCl/g
**------ - - ~ * - - -
_., ___,_ -~*.,**----*--*-----*-*-~--*.,*****- *-************--*******. ******~*-* 20.04072.08 TRG B2*08201*CJWC*A018-CV00*05 05/10/1212:56 ; 4/25/2020
- 4/27/2020 20*04072 Molybdenum.93 EPA901.1 Modified -2.37E*01 ! 5.55E*01 5.55E-01 7.95E*01 U pCi/g 1----***** ' . *********-*-******--****- .*** .-**
20*04072*08 TRG B2-08201-CJWC-A018*CV00-05 05/10/1212:56 i 4/25/2020 4/27/2020 20*04072 Niobium-94 EPA901.1 Modified 2.62E*01 3.39E-01 3.39E*01 5.03E-01 U pCi/g 20.04072.08 TRG B2-08201-CJWC*A018-CV O 0-0 5 05/10/12 12:56 4/25/2020 4/27/202C020-04072 T*******c;~d*210~-- -** EPA 901.1 Modified 6.20E+OO 4.99E+OO 5.00E+OO 8.26E+OO . u *-* ****;;cilg**-* L.2-?:?.4072-08 TRG B2-08201*CJWC-A018-CVO 0-0 5 -*05/10/1212:56*-1 4/25/2020 4/27/2020
- 20-0407:i°*t Lead-212 *..... _ EPA901.1_Modified 8.14E-01 . 3.71E-01 3.73E-01 1.02E+OO - lJ - pCi/g 20-04072-08 TRG B2*08201-CJWC-A018-CV O 0-0 5 05/10/12 12:56 i 4/25/2020 4/27/2020 20-04072 L:.1'_~:2-.1.~*-**** EPA 901.1 Modified 1.25E+OO i 7.13E-01 7.16E-01 1.26E+OO -*~---*, pCi/g 20-04072*08 TRG B2-08201-CJWC-A018*CV00-05 05/10/1212:56 ! 4/25/2020. 4/27/2020, 20-04072 Promethium-145 EPA901.1 Modified -2.10E-01 7.80E-01 7.80E*01 1.14E+OO , U pCi/g t-******
20-04072-08 TRG B2*08201*CJWC*A018-CV00-05 05/10/1212:56 ; 4/25/2020. 4/27/2020 20*04072 Radium*226 EPA901.1 Modified 1.31E+OO 6.33E-01 ' 6.36E-01 9.56E-01 ... pCii;;. --** I 20-04072-08 TRG B2-08201-CJWC-A018-CV00-05 **-*05/10/1212:56 i 4/25/2020' 4/27/2020' 20-04072 Antimony*125-**** EPA901.1 Modified -2.89E-01 6.44E+OO 6.44E+OO 9.17E+OO U pCi/g
'L~C!:-~?.?2*08 TRG B2-08201-CJWC*A018-CV O 0-0 5 05/10/12 12:56 I 4/25/2020 4/27/2020
- 20-04072 .721()~.ufTl:~3'.\-***. _ EPA.9~~~1 ~.o~i~E>d. J 7.28E+OO 4.18E+OO ' 4.20E+OO 6.66E+OO pCi/g I
-~*0*04072*08 TRG B2-08201*CJWC*A018-CV00*05 05/10/1212:56 ; 4/25/2020 4/27/2020' 20*04072 Thallium-208 EPA901.1 Modified ! 5.36E*01 9.57E-01 9.58E-01 1.57E+OO U pCi/g 20-04072-08 TRG B2-08201*CJWC-A018-CV00-05 05/10/1212:56 i 4/25/2020 4/27/2020 20*04072 Uranium-235 EPA901.1 Modified i 7.87E-01 1.10E+OO , 1.10E+OO 1.81E+OO U pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1*sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect
( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 5/7/2020 9:23 PM Page 16 of 19 Report To: Work Order Details: Eberline Analytical . G_erald wo_od ...... SOG. ~Q-04072 . . . . . ..... .. . . . .. Final Re port of Anal ysis !~~~ ~:~!~~~Ave--*** ******- * ******-*-*-**-*"* *;};1;;;fj~:{!i1! :* 1 1 1 - - - - - - - - * * * * * * * * * ************-******** .................................................. ... .......... .
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Zion, IL 60099 Sample Matrix. SO Lab Sample Client Sample Receipt Analysis Batch Analyte Method Result CU CSU MDA Qualifier , Rep.art ID Type ID Date Date Date ID Units 20*04072-09 ....... !RG B2-08201-CJWC-A018-CV 0 5-1 0 ---~5,l_~0/12 12:56 4/251202,~--~13!~03_°- .* 20-04072 Actinium-228 EPA 901.1 Modified -2.94E-01 8.38E-01 8.38E-01 1.11 E+00 U pCi/g 20-04072-09_ .. TRG B2-08201-CJWC-A018-CV05-10 05/10/1212:56 . 4/25/2020 4/27/2020 20-04072 Silver-108m EPA901.1 Modified 1.31~:01 1.19E-01 1.19E-01 2.29E-01 U .........* pCi/g ..... 20-04072-09 TRG B2-08201-CJWC-A018-CV05-10 05/10/1212:56 : 4/25/2020 4/27/2020 20-04072 Barium-133 EPA901.1 Modified -5.55E-02 1.21E-01 1.21E-01 6.16E-01 U pCi/g 20-04072-09 TRG , 82-08201-CJWC-A018-CV05-1 0 05/10/1212:56 ! 4/25/2020 4/27/2020 20-04072 Bismuth-214 EPA901.1 Modified 9.88E-01
- 4.95E-01 ' 4.98E-01 8.46E-01 pCi/g 20-04072-09 TRG B2-08201-CJWC-A018-CV 0 5-1 0 05/10/12 12:56 4/25/2020 4/27/2020 20-04072 Cobalt-60 EPA 901.1 Modified 6.65E-02 1.81 E-01 1.81 E-01 : 8.74E-01 U pCi/g 20-04072-09 TRG B2-08201-CJWC-A018-CV 0 5-1 0 05/10/12 12:56 : 4/25/2020
- 4/27/2020 ** 20-04072 Cesium-134 EPA 901.1 Modified 0.00E+00 ... 1.33E+00 **-1.33E+OO **;;:46E.;OO U*
- pCi/g 20-04072-09 ***--;:izG* . B2-08201*CJWC~ci'is:cv*o*5-10 05/10/1212:56 4/25/2020 4/27/2020 20-04072 Cesium-137 EPA901.1 Modified 2.52E-01 2.28E:01 2.28E-01 4.02E-01 u *.... pCi/g 1------~---...;-----------* ***--********* ***--**-------------*-:-****..*******-*---*----------+ ----*------+-----~---- ----------------~--**** *----*- 8.30E-02 6.27E-01 6.27E-01 1.02E+00 U pCi/g 20-04072-09 TRG B2-08201-CJWC-A018-CV05-10 05/10/1212:56 : 4/25/2020 4/27/2020 20-04072
- Europium*152 EPA901.1 Modified 1 4.39E-01 : 8.07E-01 8.07E-01 6.61E-Oi
- U pCi/g 20-04072-09 TRG B2-08201-CJWC:A018-CV05-10 05/10/1212:56 4/25/2020 4/27/2020 20-04072 r* E~;~piu~'.:;54 EPA901.1 Modified
- 20:04072-09 _ ... TRG***** B2-08201-CJWC-A018-CV 0 5.1 0 05/10/12 12:56 4/25/2020 4/27 iio20-20~04072 . Europium-155 EPA 901.1 Modified
-8.71 E-02 1.16E+00 1.16E+00 1.69E+00 .. u* . . . . **~---- ---------****-* t 3.43E-01 2.93E-01 U pCi/g 20-04072-09 TRG B2-08201-CJWC-A018-CV05-10 05/10/1212:56 4/25/2020 4/27/2020 20-04072 Holmium-166m EPA901.1 Modified 2.90E-02 3.43E-01 20-04072-09 ... TRG B2-08201-CJWC-A018-CV05-10 05/10/1212:56 ! 4/25/2020. 4/27/2020 20-04072: lodj~e:129 -* EPA901.1 Modified -3.76E-01 i 5.87E-01 i 5.87E-01 8.14E-01 U . --pCl/g*-*****
20-04072-09 TRG B2-08201-CJWC-A018-CV05-10 05/10/1212:56 : 4/25/2020 4/27/2020 20-04072 Potassium-40 .... EPA901.1 Modified 8.11E+00 3.11E+00 , 3.14E+00 3.93E+00 pCi/g -*20-04072-09 TRG B2-08201-CJWC-A018-CV05-1 0 05/10/1212:56 i 4/25/2020
- 4/27/2020 20-04072 Manga~;;e-54 EPA901.1 Modified -5.06E+01 1.56E+02 : 1.56E+02 1.90E+02 U . pCi/g
*-20:04072-09 TRG B2-08201:CJWC-A018-CV 0 5-1 0 05/10112 12:56 i 4/25/2020 4/27/2020 20-04072
- Molybdenum-93 EPA 901.1 Modified -8.88E-02 3.31 E-01 3.31E-01 4.46E-01 u* . **. -****pCi/g****
20-04072-09-* TRG B2-08201-CJWC-A018-CV05-10 05/10/1212:56 : 4/25/2020 4/27/2020, 20-04072 Niobium-94 EPA901.1 Modified -7.09E-02 2.12E-01 2.12E-01 ; 2.82E-01..... U pCi/g 20-04072-09 TRG , B2-08201-CJWC-A018-CV05-10 05/10/1212:56 i 4/25/2020 4/27/2020 20-04072 , Lead-210 EPA901.1 Modified 4.42E+00 3.86E+00 3.87E+00 6.32E+00 U pCi/g
- 20~04072-09 TRG .. ! B2-08201-CJWC-A018-CV05-10 05/10/1212:56 i 4/25/2020
- 4/27/2020**:**20:04072 Lead-212 EPA901.1 Modified 3.96E-01 3.85E-01 3.86E-01 i 6.35E-01 U pCi/g ...
20-04072-09
- TRG B2-08201-CJWC-A018-CV05-10 05/10/1212:56 4/25/2020 4/27/2020 20-04072
- Lead-214 EPA901.1 Modified 9.67E-01 4.55E-01 4.57E-01 9.06E-01 i pCi/g 20-04072-09 i TRG ; B2-08201-CJWC-A018-CV05-10 05/10/1212:56 4/25/2020 4/27/2020 20-04072 Promethium-145 EPA901.1 Modified 9.01E-02 6.14E-01 6.14E-01 I 9.28E-01 : U , pCi/g 20-04072-09 : TRG : B2-08201-CJWC-A018-CV05-1 0 05/10/1212:56 4/25/2020 4/27/2020 20-04072 . Radium-226 EPA901.1 Modified 9.88E-01 4.95E-01 4.98E-01 8.46E-01 ' i pCi/g 20-04072-09
- TRG : B2-08201-CJWC-A018-CV05-1 0 05/10/1212:56 4/25/2020 4/27/2020 20-04072. Antimony-125 EPA901.1 Modified -1.17E+00 3.21E+00 3.21E+00 4.56E+00 U pCi/g 20-04072-09 TRG j B2-08201-CJWC-A018-CV 0 5-1 0 05/10/12 12:56 4/25/2020 4/27/2020 20-04072 Thorium-234 EPA 901.1 Modified 5.06E+00 3.29E+00 .... 3.30E+00 5.36E+00 _!.. _ _U ...... , ....... pCi/g ..... .
20-04072-09 TRG i 82-08201-CJWC-A018-CV05-1 0 05/10/1212:56 4/25/2020 4/27/2020 20-04072 Thallium-208 EPA901.1 Modified 7.44E-01 5.68E-01 5.69E-01 9.58E-01 U pCi/g 20-04072-09 TRG B2-08201-CJWC-A018-CV0 5-1 0 05/10/1212:56 4/25/2020 4/27/2020 20-04072 Uranium-235 EPA901.1 Modified 1.69E-01 9.78E-01 9.78E-01 1.49E+00 i U pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect ( ~ EBERLINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/ 483-4621
Page 17 of 19 Printed: 5/7/2020 9:23 PM Report To: Work Order Details: Eberline Analytica l G_eraldWo_od Zion Solutions Purchase Order.* SOG. 20-04072 677116 Final Re port of Anal ysis 2701 Deborah Ave -****-* Analysis Categ~;::***- ENVIRONMENTAL -*--*--- *- . *-*
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Zion, IL 60099 Sample Matrix.* SO Lab Sample
- Client Sample Receipt Analysis Batch ID A I na yte M hO d et R I esu 1 CU CSU MDA *. Q rfi
- ua 1 ,er i Report Units ID Type ID Date
- Date Date 05/07/1907:45 : 4/25/2020 4/27/2020 20-04072 Actinium-228 EPA901.1 Modified 2.05E-01 8.86E-02 8.92E-02
- 1.84E-01
- pCi/g 20-04072-10 : TRG L2-10214C-RJGS-001-SM-A 20-04072*10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 4/27/2020 20-04072 Silver-108m EPA 901.1 Modified 2.26E-02 . 1.67E-02 1.67E-02 3.00E-02 U i pCi/g 05/07/1907:45 4/25/2020 4/27/2020 20-04072 Barium-133 ...* EPA901.1 Modified 4.61E-03 3.41E-02 3.41E-02
- 4.72E-02 ' U pCi/g 20-04072-10 TRG L2-10214C-RJGS-001-SM-A
. 05/07/19 07:45 4/25/2020
- 4/27/2020 20-04072 : Bismuth-214 *--***EPA 901.1 Modified 1.82E-01 4.48E-02 4.58E-02 1.49E-01 : ; pCi/g
--20:04072-10 TRG -****L2=1*0214c.RJGS-001-SM-A 05/07/19 07:45 4/25/2020 4/27/2020 20-04072 Cobalt-60 EPA 901.1 Modified 2.65E-01 3.39E-02 3.65E-02 4.51 E-02 : pCi/g 20-04072-10 : TRG L2-10214C-RJGS-001.SM*A 20-04072-10 I TRG ! L2-10214C-RJGS-001-SM-A . -*05/07/1907:45 . 4/25/2020 - 4/27/2020 20:04072.. Cesium-134 EPA901.1 Modified -1.57E-01 4.61E-02 4.68E-02 3.57E-02 U pCi/g 05/07/19 07:45 : 4!25!2020 4/27/2020 20-04072 Cesium-137 EPA 901.1 Modified 2.18E+OO 2.50E-01 2.74E-01 5.19E-02 ;
- pCi/g 20-04072-10 TRG ' L2-10214C-RJGS-001-SM-A 05/07/1907:45 4/25/2020 4/27/2020 20-04072 Europium-152 EPA901.1 Modified 1.33E-02 6.46E-02 6.46E-02 7.87E-02 U pCi/g 20-04072-10 TRG L2-10214C-RJGS-001-SM-A ---,t----------t****
- -**" -------------------t--------i *~*****--*,s ***-**---- '***- -ss-*,s***- *-*--*-----
Europium-154 EPA901.1 Modified 4.61E-02 5.72E-02 5.72E-02 4.12E-02 U ! pCi/g 20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 4/27/2020 20-04072 05/07/19 07:45 : 4/25/2020 4/27/2020_.__2?:°.~0,~~.--_E_;'.':?Eium-155 EPA901.1 Modified -8.47E-03 4.60E-02 : ...~~°.E_~~--* 6.57E-02
- U pCi/g
.2°.:~_()72-10 TRG-* ** L2-10214C-RJGS-001-SM-A 05/07/19 07:45 , 4/25/2020 4/27/2020 20-04072 Holmium-166m EPA 901.1 Modified .. 5.:7_9§~03_ 2.77E-02 2.77E-02 2.78E-02 U pCi/g *-
.2..0:0,4?:2.: 10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 4/27/2020 20-04072 lodine-129 EPA901.1 Modified 9.89E-03 2.49E-02 2.49E-02 7.80E-02 U pCi/g 20-04072-10 TRG , L2-10214C-RJGS-001-SM-A 05/07/1907:45 4/25/2020 4/27/2020' 20-04072 Potassium-40 EPA901.1 Modified 5.09E+OO 6.51E-01
- 7.02E-01 4.74E-01 pCi/g 20-04072-10 TRG L2-10214C-RJGS-001-SM-A
- - - - - - - - ' - - - - - - - + - - - - - - - - - * - - - - - l - - - - - ~ ' - - - - -3.94E-02 -------------~--*-----
05/07/1907:45 4/25/2020 4/27/2020 20-04072 Manganese-54 EPA901.1 Modified 7.01E-03 3.94E-02 5.91E-02 U pCi/g 20-04072-10 TRG L2-10214C-RJGS-001-SM-A -*- . **-****-***-****--**--
,,...,,...-.,.~****
05/07/1907:45 4/25/2020 4/27/2020 20-04072 Molybdenum-93 EPA901.1 Modified -1.32E-02 1.69E-02 1.69E-02 2.01E-02 U pCi/g **- 20-04072-10 TRG .c L2-10214C-RJGS-001-SM-A 05/07/1907:45 4/25/2020 4/27/2020
- 20-04072 Niobium-94 EPA901.1 Modified 2.40E-02 1.67E-02 1.68E-02 2.53E-02 U pCi/g 20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 4/27/2020 : 20-04072 Lead-210 EPA901.1 Modified 4.98E-01 . 4.11E-01 4.12E-01 6.82E-01 U pCi/g 20-04072-10 , TRG : L2-10214C-RJGS-001-SM-A 20-04072-10 i TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 4/27/2020- 20-04072 Lead-212 EPA 901.1 Modified 2.12E-01 i 5:56E-02 5.66E-02 7.94E-02 pCi/g r-** -----t-----,---- ---------+----- -----******------ ---***-******---* ---****"-*----+- ---------+----- ~------
20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05/07/19 07:45 4/25/2020 , 4/27/2020 20-04072 Lead-214 EPA 901.1 Modified 2.10E-01 5.98E-02 6.07E-02 1.09E-01 i pCi/g 05/07/19 07:45 4/25/2020 4/27/2020 20-04072 ! Promethium-145 EPA 901.1 Modified -4.66E-02 4.65E-02 4.66E-02 c--7.14E-02 i U pCi/g 20-04072-10 i TRG L2-10214C-RJGS-001-SM-A 05/07/1907:45 4/25/2020
- 4/27/2020 20-04072 Radium-226 EPA901.1 Modified 1.82E-01 4.48E-02 4.58E-02 1.49E-01 ' pCi/g 20-04072-10 i TRG L2-10214C-RJGS-001-SM-A 20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05/07/1907:45 4/25/2020 4/27/2020
- 20-04072 i Antimony-125 EPA901.1 Modified 3.SOE-02 : 7.98E-02 7.99E-02 i 1.18E-01 U pCi/g 05/07/19 07:45 4/25/2020 4/27/2020 20-04072 Thorium-234 EPA 901.1 Modified 8.17E-01 ; 2.93E-01 2.96E-01 i 4.86E-01 U pCUg 20-04072-10 TRG L2-10214C-RJGS-001-SM-A 05/07/1907:45 4/25/2020. 4/27/2020 20-04072 Thallium-208 EPA901.1 Modified 1.SOE-01 i 5.83E-02 5.91E-02
- 9.63E-02 ' pCi/g 20-04072-10 i TRG L2-10214C-RJGS-001-SM-A 4/25/2020' 4/27/2020 20-04072 Uranium-235 EPA901.1 Modified 1.17E-01 1.05E-01 1.05E-01 1.57E-01 i U pCi/g 20-04072-10 i TRG i L2-10214C-RJGS-001-SM-A 05/07/1907:45 Sample;DO=Duplicate Original;U=Non-detect CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal
( ~ EBERL INE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Printed: 5/7/2020 9:23 PM Page 18 of 19 Rep_ort To: Work Order Details: Gerald Wood SDG: 20-04072 Eberline Analytica l I Zion Solutions __ ,____ ,,,,,,,,,,,,_, .._,,, __ _
. **.f--,* ,,4,,_,,,,,,,, Purchase Order: ,,,,,,,,,,,,,,,,,,,,,,,,_____ 677116 ,,,,,,,,, _ _ _ _ __ ------**m*_,,,, _ _ ,,,WAW Final Report of Analysis 2701 Deborah Ave --------- ,,,-,,,,,,,,_,, __,,,,,,,,, .. ,,,,,,,,1 Analysis Category:. ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, __,,_.,,__ _ENVIRONMENTAL
_ - - - - ------ ,,,,,,,,,,,,,,,,,,,,,,,,, ,,,,,,,,,,,,,,___,, - - - - - - - 1 Zion, IL 60099 Sample Matrix: SO Lab ID Sample Type Client ID I Sample Date Receipt Date Analysis Date Batch ID A na Iyte I M hO d et I R esu It CU CSU MDA Q rfi ua 1 ,er ' Report Units 08/21/1910:25 4/25/2020 4/27/2020 20-04072 Actinium-228 EPA901.1 Modified 1.11E+00 2.50E-01 2.57E-01 4.54E-01 pCi/g 20-04072-11 TRG L1-12109L-CJGS-001-SB-A 20-04072-11 TRG L1-12109L-CJGS-001-SB-A 08/21/191°-~2--5__ 4/25/2020 4/27/2020 20-04072; Silver-108m EPA901.1 Modified 'is1E:03 - 4.71E-02 __4,?1~:o~:~--:T~C.E:°-2____ U pCi/g 08/21/1910:25 : 4/25/2020 4/27/2020 20-04072 Barium-133 EPA901.1 Modified 8.15E-03 2.98E-02 2.98E-02 . 1.50E-01 U pCi/g 20-04072-11 TRG L1-12109L-CJGS-001-SB-A ,,,,,,,,, ,=--**""""'"'"'""'""'w'~*-""""""""-*--~-e*: *--*- ,,, _ _ _ _ _ _ _ ,_'"""' *--~=*---*w ...-,---~"'",,, "*"
*=~~_, _ _,,
08/21/1910:25 4/25/2020 4/27/2020 20-04072 Bismuth-214 EPA901.1 Modified 1.24E+00 1.90E-01 2.00E-01 2.55E-01 pCi/g 20-04072-11 TRG L1-12109L-CJGS-001-SB-A 4/25/2020 4/27/2020 20-04072 ,------C~b;l;:60 EPA901.1 Modified ...... _9.43E-02 7:75E_:P~ ... ; ... -7:7-6~:°-~-*- 1.1i:~=a.1__ _ U - P.~i!9.. -- 20-04072-11 : TRG L1-12109L-CJGS-001-SB-A 08/21/1910:25 08/21/1910:25 4/25/2020 4/27/2020 20-04072 Cesium-134 EPA901.1 Modified 4.83E-02 5.80E-02 5.81E-02 1.47E-01 U pCi/g 20-04072-11 , TRG L1-12109L-CJGS-001-SB-A '"20:0407~:.1.2,____ 1:1'~-- L1-12109L-CJGS-001-SB-A 08/21/1910:25 4/25/2020 __4,1271202-0 20-04072 Cesium-137 EPA901.1 Modified - I -1~47E:o;-***r---8.15E-°-~-- 8.18E-02 1.31E-01 ,,_pCi/g*-~ 08/21/1910:25 4/25/2020 4/27/2020 20-04072 Europium-152 EPA901.1 Modified : -2.05E-03 1.31E-01 1.31E-01 2.52E-01 U pCi/g 20-04072-11
- TRG L1-12109L-CJGS-001-SB-A 4/25/2020 4/27/2020 20-04072 Europium-154 EPA901.1 Modified -1.19E-01 2.01E-01 , __2.01E:,°-1 , 1.31E-01 U pCi/g __
20-04072-11 ! TRG L1-12109L-CJGS-001-SB-A 08/21/1910:25 08/21/1910:25 4/25/2020. 4/27/2020 20-04072 Europium-155 EPA901.1 Modified 1.01E+00 1.84E-01 1.91E-01 2.67E-01 . pCi/g 20-04072-11 TRG L1-12109L-CJGS-001-SB-A "" --~*m*-*-*----,,_, -- ,~~-*, ,,,.-~,~*...-,,~--*~~,, ~ =~~';"=" 08/21/1910:25 : 4/25/2020 4/27/2020 20-04072 Holmium-166m EPA901.1 Modified 2.38E-01 8.51E-02 8.60E-02 1.38E-01 , pCi/g 20-04072-11 TRG . L1-12109L-CJGS-001-SB-A
20-0407i11-
- TRG ___ L1-12109L-CJGS-001-SB-A 08/21/1910:25 4/25/2020 4/27/2020 20-04072 1
lodine-129 EPA901.1 Modified -1.11E-01 __, ___ 216E:01-T 2.17E-01 3.07E-01 U --. ---pCi/g --1, 20-04072-11 TRG , L1-12109L-CJGS-001-SB-A 08121_1.!_~ 10:25 ° 4/25/2020 ----~'-2~/~020 20-04072 :__ Potassium-40 EPA901.1 Modified 2.59E+01 2-:~~~+.00 2.96E+00 1:93E+OO pCi/g I, 20-04072-11 i TRG____ L1:12_109L-CJGS-001-SB-A___ __ 08/21/1910:25 4/25/2020 4/27/2020 20-04072 __ Manganese-54 _____ -~_F'A901.1 Modified _ __1~3E:01 _ , 1.23E-01 1.23E-01 1.76E-01 , _U pCi/g 08/21/1910:25 , 4/25/2020 4/27/2020 20-04072 Molybdenum-93 EPA901.1 Modified 1.49E-02 6.62E-02 6.62E-02 9.11E-02 U pCi/g 20-04072-11 TRG L1-12109L-CJGS-001-SB-A
-* 08/21_/1910:25--;*4i25/2020
- 4/27/2020 20-04072 Niobium-94 EPA901.1 Modified ___ 2.92E-02 6.45E-02 6.45E-02 9.12E-02 : U - pCi/g L~.°-4,072-11 TRG L1-12109L-CJGS-001-SB-A 08/21/1910:25 4/25/2020 4/27/2020 20-04072 Lead-210 EPA901.1 Modified 2.40E+00 1.43E+00 1.43E+00 2.34E+00 pCi/g 20-04072-11 TRG L1-12109L-CJGS-001-SB-A
- 1.89E-01 1.98E-01 2.88E-01 : pCi/g 20-04072-11 *
' 20-04072-11 TRG TRG L1-12109L-CJGS-001-SB-A L1-12109L-CJGS-001-SB-A
,,~--
08/21/1910:25 08/21/1910:25
. 4/25/2020 ~----~-~"-------------~-- , 4/25/2020 4/27/2020_, 20-04072 4/27/2020 20-04072 Lead-212 Lead-214 EPA901.1 Modified EPA901.1 Modified - 1:1ii:oo 1.35E+00 2.32E-01 2.42E-01 3.27E-01 1 pCi/g L1-12109L-CJGS-001-SB-A 08/21/1910:25 i 4/25/2020 4/27/2020 20-04072 Promethium-145 EPA901.1 Modified 4.47E-02____ 1.81E-01 1.81E-01 2.63E-01 j_---* U pCi/g
,20-04072-11 TRG 08/21/19 10:25 4,(~~!~~~..---4'.~/}020 I 20-04072 Radium-226 EPA 901.1 Modified 1.24E+00 i 1.90E-01 2.00E-01 i 2.55E-01 i pCi/g 8 20-04072-11 TRG L1-12109L-CJGS-001-SB-A 08/21/1910:25 , 4/25/2020 4/27/2020 20-04072 Antimony-125 EPA901.1 Modified -1.85E-01 , 1.95E-01 1.96E-01 2.67E-01 . U pCi/g 20-04072-11 TRG L1-12109L-CJGS-001-SB-A 20-04072-11 TRG L1-12109L-CJGS-001-SB-A 08/21/1910:25 i 4/25/2020 4/27/2020 20-04072 Thorium-234 EPA901.1 Modified --6:9:iE:;:;;-a--* 1.33E+00 1.37E+00 ; 1.97E+00 f"------U-- pCi/g
**e* -.s,--~~1 ******~** '
pCi/g 08/21/1910:25 4/25/2020" 4/27/2020 20-04072 Thallium-208 EPA901.1 Modified 9.01E-01 1.88E-01 1.93E-01 3.50E-01 20-04072-11 TRG L1-12109L-CJGS-001-SB-A 20-04072-11 TRG I L1-12109L-CJGS-001-SB-A 08/21/1910:25 1 4/25/2020 4/27/2020 20-04072 Uranium-235 EPA901.1 Modified 5.96E-01 ' 3.59E-01 3.60E-01 , 5.40E-01 U I pCi/g Sample;DO=Duplicate Original;U=Non-detect CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal ( ~ EBERL INE ANALYTICAL EBERUNE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
Page 19 of 19 Printed: 5/7/2020 9:23 PM Ref)_ort To: Work Order Details: Gerald Wood SOG* 20-04072 Eberlin e Analyti cal Zion Solutions _______ _____ ___ f Purchase Order:: 677116 Final Report of Analysis 2701 Deborah Ave ,,J__ ~'!afJS.iS.,C:!3!'!gory-
- Sample Matrix:
- ENVIRgNryi~T::,JII:\~_ _
SO ______ _ -~---- _ Zion, IL 60099 Batch Report Lab Sample Client Sample Receipt Analysis Units Date ID Analyte Method Result CU CSU MDA Qualifier ID Type ID Date Date 20-04072 Actinium-228 EPA90U Modified 5,36E-01 1.52E-01 1.54E-01 i 3_38E-01 pCi/g 20-04072-12 TRG L1-12106L-CJGS-001-SB-A 08/14/1913:30 4/25/2020 4/27/2020 Silver-108m EPA 901 _1 Modified 4.17E-03 2,76E-02 2,76E-02 , 4,45E-02 U pCi/g 20-04072-12 TRG L1-12106L-CJGS-001-SB-A 08/14/19 13:30 4/25/2020 4/27/2020 : 20-04072 20-04072-12 i TRG L1-12106L-CJGS-001-SB-A 08/14/1913:30*-, 4/25/2020 4/27/2020 20-04072 Barium-133 EPA90U Modified -3_19E-01 1.03E-01 1.05E-01 6,63E-02 U *;c;/~ 08/14/19 13:30 ! 4/25/2020 4/27/2020 20-04072 Bismuth-214 EPA 901-1 Modified 6.70E-01 1,24E-01 1,29E-01 i 1,96E-01 : , pCi/Q 20-04072-12 TRG L1-12106L-CJGS-001-SB-A Cobalt-60 EPA90U Modified 2,89E-02 : 5,38E-02 5.38E-02 : 7-28E-02 : U 20-04072-12 TRG L1-12106L-CJGS-001-SB-::A 08/14/1913:30 i 4/25/2020 4/27/2020 20-04072 ,, 20-04072 Cesium-134 EPA90U Modified 1,56E-02 3,25E-02 3_25E-02 7A8E-02 U pCi/g 20-04072-12 : TRG L1-12106L-CJGS-001-SB-A 08/1411913:30 4/25/2020 4/27/2020 20-04072 ,,,,,,C;;i~--- EPA90UModified 1,92E-01 6A3E-02 6,50E-02 9,63E-02 __,,_,,,_ pCi/g_,,,.,, 20-04072-12 i TRG L1-12106L-CJGS-001-SB-A --08/14/1913:30 4/25/2020. 4/27/2020 Europium-152 EPA901.1 Modified 1.34E-01 ______1'.31E-01 1.31E-01 _ 1.51E-01 U pCi/g 20-04072-12 TRG ; L1-12106L-CJGS-001-SB-A 08/14/1913:30 4/25/2020, 4/27/2020---20:04072 - TRG : L1-12106L-CJGS-001-SB-A ___ ?_~/14/1913:30 4/25/2020 4/27/2020 20:04072
- Europi~;:;;:154- -EP/\9011 M~ctifi~ct ,, 1.57E:?~ ____ 1.25E-01 1~25E=o~i-- - -7~86E~c12--,,~~~-u *---* pCi/g 20-04072-12
- 20-04072 Europium-155 EPA901.1 Modified 6.02E-02 6.89E-02 6.90E-02 U5E-01 U pCi/g 20-04072-12 TRG L1-12106L-CJGS-001-SB-A 08114/1913:30 4/25/2020
- 4/27/2020 Hol;:;;ium-1-66;:;;--* EPA901.1 Modified - 6.21E-02 6.76E-02 6.77E-02 9.36E U ,--- pCi/g==
20-04072-12 ' TRG L1-12106L-CJGS-001-SB-A 08/14/1913:30 4/25/2020, 4/27/2020. 20-04072 9.17E-02 ,--8.74E:02 ___ 8.76E-02 - 1'.23&01
- U pCi/g 20-04072-12 TRG L1-12106L-CJGS-001:SB:A - 08/14/191330 ! 4/2512020 4/27/2020 20-04072 lodin~:129* --
- EPA901.1M;dified 20-04072-12 TRG : L 1-12106L-CJGS-001-SB-A 08/14/1913:30 : 4/25/2020 : 4/27/2020 20-04072 : Potassium-40 EPA 901.1 Modified 1.95E+01----2~02E+OO 2.25E+OO U4E+OO *;;c~
1--20-04072-12 TRG L1-121-06L-CJGS-001-SB-A ---,--08/14/1913:30 4/25/2020 4127/2020 20-04072 Manganese-54 EPA901.1 Modified 3.61E-02 : 7.05E-02 : 7.05E-02 i 1.09E-01 i U : pCi/g i EPA901.1 Modified 1.21E-02 : 2.17E-02 2.17E-02 : 5.50E-02 i U , pCi/g 1--20:04072-12 i TRG L1-12106L-CJGS-001-SB-A 08/14/1913:30 ! 4/25/2020, 4/27/2020 20-04072 Molybdenum-93 20-04072-* Niobium-94 EPA901.1 Modified -3.10E-03 4.05E-02 4.05E-02 5.95E-02 : U pCi/g 20-04072-12 : TRG L1-12106L-CJGS-001-SB-A 08/14/1913:30 4/25/2020 4/27/2020 o8i14/1913:30 i 4/25/2020 4/27/2020 20-?4?7.~- -L~ad-210_ __ E_Pll9?11fv1~difi<e~ __ 1A1E+oo , 1.05E+OO _ 1.06E+oo 1.75E+oo _ LJ ..... p~ii~ ___ ,. 20~04072-12 : TRG L1-12106L-CJGS-001-SB-A Lead-212 EPA901.1 Modified 4.37E-01 9.77E-02 1.00E-01 1.33E-01 pCi/g 20-04072-12 TRG L1-12106L-CJGS-001-SB-A 08/14/1913:30 _ 4/25/2020 4/27/2020' 20-04072 . 20-04072 ; Lead-214 EPA901.1 Modified 6.06E-01 1.21E-01 1.25E-01 i 2.08E-01 ,c.,,,, pCi/g ,,,20-04072-12 TRG L1-12106L-CJGS-001-SB-A *--- ,,,.08/14/1913:30 o-4/25/2020 4/27/2020
! 1.25E-01 1A5E-01 U pCi/g 20-04072-12___ TRG L1-12106L-CJGS-001-SB-A 08/14/1913:30 i 4/25/2020 4/27/2020. 20-04072 ; Promethium-145 EPA901.1 Modified -2.10E-01 1-25E-01 Radium-226 EPA901.1 Modified -----6.70E-01 1.24E-01 1.29E-01 1.96E-01 --- -----* pCi/g 20:04072-12 TRG L1-12106L-CJGS-001-SB-A ---- 08/14/1913:30 [ 4/25/2020 4/27/2020 i 20-04072 20-04072-12 TRG-- ; L1-12106L-CJGS-001-SB-A 08/14/1913:30 j 4/25/2020 _ 4/27/2020 20-04072 : Antimony-125 EPA901.1 Modifi_ed 3-25E-02 j 1.02E-01 1.03E-01 i 1.69E-01 U pCilg 20-04072-12 TRG 1
L1-12106L-CJGS-001-SB-A 08/14/1913:30 I 4/25/2020, 4/27/2020 20-04072 Thorium-234 EPA901.1 Modified 1.10E+OO i 7.84E-01 7.86E-01 1.30E+OO U pCi/g 20-04072 Thallium-208 EPA 901.1 Modified 5.15E-01 1.24E-01 1.26E-01*T-i10E-01 pCi/g
*-20:04072-12 TRG L1-12106L-CJGS-001-SB-A -- -- 08/14/1913:30 , 4/25/2020 : 4/27/2020 3.09E-01 U pCi/g 20-04072-12 TRG L1-12106L-CJGS-001-SB-A 08/14/1913:30 i 4/25/2020 4/27/2020 20-04072 Uranium-235 EPA901.1 Modified J -1.06E-01 2.46E-01 2A6E-01 P=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laborato ry Control Sample;MBL=Blank;DU
( ~ EBER LINE ANALYTICAL EBERLINE ANALYTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621
ZS-WM-131
~
Revision 0 20 . . 04 07 2 Information Use ZIONSOLUTIONSru An EnergySo/u6ons Company REC'D APR 2 5 2020 Attachment _l :-- _Cbain-_of-C_ufitody_F--91111 Analysis Type Preser Remarks Sample Date Sample Sampl Matrix Sample Sample Container vative Sample ID Time eLog Type Type Qty Vol Unit FULL SUITE and 5 ROC NA NA gm Plastic bag 1 11 2012 1045 NA NA Concr ete 120.18 B2-06207C-JFCCV-002- 0.0-0.5
- FULL SUITE and 5 ROC 129.04 NA NA gm Plastic bag 1 11 2012 1045 B2-06207C-JFCCV-002- 0.5-1.0 NA NA Concr ete FULL SUITE and 5 ROC NA NA 115.89 Plastic bag 1 11 2012 1008 NA Concr ete gm B2-06104C-JFCCV-003- 0.5-1.0 NA FULL SUITE and 5 ROC NA NA gm Plastic bag 1 11 2012 1008 NA Concr ete 118.77 B2-06104C-JFCCV-003- 1.0-1.5 NA FULL SUITE and 5 ROC NA NA gm Plastic bag 1 06 2018 1130 NA NA Concr ete 298.87 B 1-0620 lA-FSFC-009-CV FULL SUITE and 5 ROC NA NA gm Plastic bag 1 06 2018 0900 NA NA Concr ete 231.42 B l-0620tA-FSWC-041-CV FULL SUITE and 5 ROC NA NA gm Plastic bag 1 06 2018 1300 NA Concr ete 259.58 B 1-06201A-FSWC-050-CV NA FULL SUITE and 5 ROC NA NA gm Plastic bag 1 06 2018 1450 NA NA Concr ete 244.20 B l-06202A-FSFC-028-CV FULL SUITE and 5 ROC NA NA gm Plastic bag 1 06 2018 1344 NA NA Concr ete 274.50 B 1-06202A-FSWC-033CV FULL SUITE and 5 ROC NA u, B l-06202A-FS WC-040-CV NA NA Concr ete 389.08 gm Plastic bag 1 06 2018 1030 NA ,,. FULL SUITE and 5 ROC NA NA ~ }Bl-06214A-FSFC-001-CV Plastic bag 1 05 2018 1515 NA NA Concr ete 298.3 gm Laboratory:
1.1. Eberline Labs Date Submitted To Lab:
#A Ship Container No.:
NA Cooler Temperature: NA frll211~n~ rl-w Time: 1Zr~r:rl r Kitkt1 Date:
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- Date:
04/24/2020 Time: lt'-15 ()4/Ji/J?Dm N t{ 5 I hCQ rt;rt-tfl,ori-1 owN, Wate: 6¥;7-i I 7-6 JO .
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/ ~ ZS-WM-131 Revision 0 ZIONSOLUTIONSrrc An EnergySo/utions Company 20"'"04072 Information Use REC'D APR 2 5 2020 Attachment 1 - Chain-of-Custody Fonn Sample ID Sam Matrix Sample Sample Container Sample Date Sample Analysis Type Preserv Remarks pie Type Time ative Log Vol Unit Type Qty
- y FULL SUITE and 5 ROC NA NA B2-08101A-BJFC-007-CV 0.0-0.5 NA NA Concrete 120.18 gms Plastic 1 05-09-2012 1422
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j32-08101A-BJFC-007-CV 0.5-1.0 B2-08201-CJWC-A018-CV 0.0-0.5
~-08201-CJWC-A018-CV 0.5-1.0 tO NA NA NA NA NA NA Concrete Concrete Concrete 175.02 123,37 132.37 gms !mlS gms Plastic Plastic Plastic I
1 1 05-09-2012 05-10-2012 05-10-2012 1422 1256 1256 FULL SUITE and 5 ROC FULL SUITE and 5 ROC FULL SUITE and 5 ROC NA NA NA NA NA NA L2-10214C-RJGS-001-SM-A NA NA Sediment 561.53 gms Marinelli 1 05-07-2019 0745 FULL SUITE and 5 ROC NA NA
\\ FULL SUITE and 5 ROC L 1-12109L-CJGS-001-SB-A NA NA Soil 145.65 gms Marinelli 1 08-21-2019 1025 NA NA l?-
L 1-12106L-CJGS-OO I-SB-A NA NA Soil 174.32 gms Marinelli 1 08-14-2019 1330 FULL SUITE and 5 ROC NA NA Laboratory: Date Submitted To Lab: Ship Container No.: Cooler Temperature: rffc~Number: 1.1. Eberline Labs NA NA NA 1 olf1( OiJe111'&i1 9iJ3?-. OXJ.-'f OD 0 Rj~by~ Date: 04/24/2020 Time: 11 '-/-S' byi ~ I 1 1(11-(; - IC.
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