Text

5184-SR-09-0 Hematite Subsurface Sampling Report_Final (012418)
	ML18024A876
Person / Time
Site:	07000036
Issue date:	01/24/2018
From:	Jun Lee; Oak Ridge Institute for Science & Education
To:	James Smith; NRC/NMSS/DDUWP/MDB
	James Smith 301-415-6103
References
	DCN 5184-SR-09-0, DE-SC00146664, RFTA 17-004
	Download: ML18024A876 (73)
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INDEPENDENT CONFIRMATORY SURVEY REPORT FOR SUBSURFACE INVESTIGATIONS AND SAMPLING OF SURVEY UNITS LSA 10-05 AND LSA 10-14 AT THE HEMATITE DECOMMISSIONING PROJECT FESTUS, MISSOURI J. D. Lee FINAL REPORT January 2018 Prepared for U.S. Nuclear Regulatory Commission Further dissemination authorized to NRC only; other requests shall be approved by the originating facility or higher NRC programmatic authority.

ORAU provides innovative scientific and technical solutions to advance research and education, protect public health and the environment and strengthen national security. Through specialized teams of experts, unique laboratory capabilities and access to a consortium of more than 100 major Ph.D.-granting institutions, ORAU works with federal, state, local and commercial customers to advance national priorities and serve the public interest. A 501(c)(3) nonprofit corporation and federal contractor, ORAU manages the Oak Ridge Institute for Science and Education (ORISE) for the U.S. Department of Energy (DOE). Learn more about ORAU at www.orau.org.

NOTICES The opinions expressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge Associated Universities.

This report was prepared as an account of work sponsored by the United States Government.

Neither the United States Government nor the U.S. Department of Energy, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe on privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement or recommendation, or favor by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.

HDP Subsurface Confirmatory Survey 5184-SR-09-0 INDEPENDENT CONFIRMATORY SURVEY REPORT FOR SUBSURFACE INVESTIGATIONS AND SAMPLING OF SURVEY UNITS LSA 10-05 AND LSA 10-14 AT THE HEMATITE DECOMMISSIONING PROJECT FESTUS, MISSOURI Prepared by J. D. Lee Oak Ridge Institute for Science and Education P.O. Box 117 Oak Ridge, Tennessee 37831-0017 January 2018 FINAL REPORT Prepared for the U.S. Nuclear Regulatory Commission This document was prepared for the U.S. Nuclear Regulatory Commission (NRC) by the Oak Ridge Institute for Science and Education (ORISE) through an interagency agreement (NRC FIN No. F-1244) between the NRC and the U.S. Department of Energy (DOE). ORISE is managed by Oak Ridge Associated Universities under DOE contract number DE-SC0014664.

HDP Subsurface Confirmatory Survey ii 5184-SR-09-0 CONTENTS FIGURES.......................................................................................................................................................... iii TABLES............................................................................................................................................................. iii ACRONYMS.................................................................................................................................................... iv EXECUTIVE

SUMMARY

.............................................................................................................................. v

1. INTRODUCTION....................................................................................................................................... 1

2. SITE DESCRIPTION................................................................................................................................. 2

3. RADIONUCLIDES OF CONCERN...................................................................................................... 5

4. OBJECTIVES................................................................................................................................................ 7

5. PROCEDURES............................................................................................................................................ 7 5.1 Subsurface Sampling Location Selection....................................................................................... 7 5.2 Subsurface Sampling......................................................................................................................... 8 5.3 Sample Core Screening..................................................................................................................... 9 5.4 Borehole Logging.............................................................................................................................. 9 5.5 Decontamination, Waste Management, and Borehole Abandonment.................................... 10

6. SAMPLE ANALYSIS AND DATA INTERPRETATION............................................................... 11

7. FINDINGS AND RESULTS................................................................................................................... 11 7.1 Radiological Concentrations in Soil.............................................................................................. 11 7.2 Sample Core Screening................................................................................................................... 12 7.3 Borehole Logging............................................................................................................................ 13 7.4 Waste Sampling............................................................................................................................... 14

8.

SUMMARY

AND CONCLUSION........................................................................................................ 14

9. REFERENCES........................................................................................................................................... 15 APPENDIX A FIGURES APPENDIX B TABLES APPENDIX C CHEMICAL ANALYSIS RESULTS APPENDIX D MAJOR INSTRUMENTATION APPENDIX E SURVEY AND ANALYTICAL PROCEDURES

HDP Subsurface Confirmatory Survey iii 5184-SR-09-0 FIGURES Figure 2.1. Aerial Photo Showing Burial and Waste Handling Areas........................................................ 3 Figure 2.2. Burial Area LSAs............................................................................................................................ 3 Figure 2.3. LSAs 10-14 and 10-05 Looking Northwest............................................................................... 4 Figure 2.4. LSA 10-14 Looking West-Northwest with View of Waste Piles............................................ 4 Figure 2.5. LSAs 10-14 and 10-05 Backfill Depth (in feet) Topographic Map......................................... 5 Figure 3.1. Conceptual Site Models for Site-Specific DCGLWs.................................................................. 6 TABLES Table 3.1. Site-Specific Soil DCGLWs by Stratum........................................................................................ 6 Table 5.1. Bore Depth and Point of Interface Summary............................................................................. 8 Table 7.1. Range of Radionuclide Concentration in Soil Cores (pCi/g)................................................. 12 Table 7.2. Sample Core Screening Results................................................................................................... 12

HDP Subsurface Confirmatory Survey iv 5184-SR-09-0 ACRONYMS cpm counts per minute CsI cesium iodide DCGLW derived concentration guideline level DNAPL dense non-aqueous phase liquid DOE U.S. Department of Energy DP decommissioning plan DPT direct-push technology HDP Hematite Decommissioning Project ITP Intercomparison Testing Program LSA land survey area MDC minimum detectable concentration NaI sodium iodide NIST National Institute of Standards and Technology NRC U.S. Nuclear Regulatory Commission ORAU Oak Ridge Associated Universities ORISE Oak Ridge Institute for Science and Education PCE tetrachloroethylene pCi/g picocuries per gram PPE personal protective equipment RCRA Resource Conservation and Recovery Act ROC radionuclide of concern TAP total absorption peak TCE trichloroethylene TCLP Toxicity Characteristic Leaching Procedure WEC Westinghouse Electric Company, LLC

HDP Subsurface Confirmatory Survey v

5184-SR-09-0 INDEPENDENT CONFIRMATORY SURVEY REPORT FOR SUBSURFACE INVESTIGATIONS AND SAMPLING OF SURVEY UNITS LSA 10-05 AND LSA 10-14 AT THE HEMATITE DECOMMISSIONING PROJECT FESTUS, MISSOURI EXECUTIVE

SUMMARY

The U.S. Nuclear Regulatory Commission requested that the Oak Ridge Institute for Science and Education (ORISE) perform an independent confirmatory survey at the Hematite Decommissioning Project in Festus, Missouri. The survey units investigated during this confirmatory survey were land survey area (LSA) 10-05 and LSA 10-14, both of which are located within a portion of the site referred to as the documented burial area.

ORISE performed confirmatory survey activities, including subsurface soil sampling using direct-push technology, sample core scanning, and borehole scanning/data logging from October 16-19, 2017. ORISE collected a total of 44 samples consisting of 22 core samples taken from the backfill/native soil interface region, 21 composite samples collected from backfill elevations, and one composite waste profile sample. The results of the ORISE gamma and beta surveys, along with laboratory analytical results, did not identify any site-related contaminants above the respective uniform stratum derived concentration guideline level values (most restrictive) in the selected investigation areas in LSA 10-05 or 10-14.

HDP Subsurface Confirmatory Survey 1

5184-SR-09-0 INDEPENDENT CONFIRMATORY SURVEY REPORT FOR SUBSURFACE INVESTIGATIONS AND SAMPLING OF SURVEY UNITS LSA 10-05 AND LSA 10-14 AT THE HEMATITE DECOMMISSIONING PROJECT FESTUS, MISSOURI

1. INTRODUCTION Westinghouse Electric Company, LLC (WEC), a former fuel cycle facility near Festus, Missouri, operated from 1956 to 2001 manufacturing nuclear fuel from natural and enriched uranium. The site ceased operational activities in September 2001, and WEC is decommissioning the facility, now known as the Hematite Decommissioning Project (HDP). From its inception in 1956 through 1974, the facility was used primarily in support of government contracts that required the production of highly enriched uranium products. From 1974 through plant closure in 2001, the focus changed from government contracts to commercial fuel production. Specifically, operations included the conversion of uranium hexafluoride gas of various uranium enrichments to uranium oxide, uranium carbide, uranium dioxide pellets, and uranium metal. Secondary operations included research and development and uranium scrap recovery processes. The facilitys central land area and the site creek were impacted by the fuel fabrication activities. As part of the overall site decommissioning, WEC performed remediation of land areas, including former burial trenches. Depth of excavations varied with the maximum depth reached of 7.5 meters (24.5 feet), encountering the water table interface (phreatic zone) at some locations. Final status surveys were then performed and excavations were backfilled with soil that was either obtained from off-site borrow areas and/or on-site reuse soil stockpiles.

The U.S. Nuclear Regulatory Commission (NRC) is responsible for oversight of permitted decommissioning activities that are in accordance with the sites decommissioning plan and NRC License SNM-33. As the goal of the HDP is to release the site for unrestricted use, the NRC has opted to perform independent (third party) confirmatory investigations at the site in order to verify the final status radiological conditions. The NRC has requested support from the Oak Ridge Institute of Science and Education (ORISE) to perform independent confirmatory subsurface sampling to determine whether residual radioactive material above approved derived concentration guideline levels (DCGLWs) may be present within two of the remediated and backfilled HDP Land Survey Areas (LSAs). The excavations within these LSAs were backfilled prior to the performance of confirmatory surveys and sampling.

HDP Subsurface Confirmatory Survey 2

5184-SR-09-0

2. SITE DESCRIPTION The Hematite facility is located in Jefferson County, Missouri, less than 4 miles west of the town of Festus, Missouri and 35 miles south of the city of St. Louis. The site is surrounded by forest, agricultural lands, and low-density residential housing. The entire site consists of approximately 228 acres; however, the impacted portion of the site, referred to as the central tract, only includes approximately 19 acres. The central tract of the site is bounded by State Road P to the north, the northeast site creek to the east, Union-Pacific railroad tracks to the south, and the site creek/pond to the west.

LSAs 10-05 and 10-14 are located within the portion of the site referred to as the documented burial area. Both LSAs are located near an area of the site that was used for waste handling during the decommissioning. The proximity of staged waste material to LSAs 10-05 and 10-14 could have resulted in the migration of contaminated materials into the excavations due to runoff during heavy rain events.

Figure 2.1 shows the site overview with the burial pit and waste handling locations identified, and Figure 2.2 provides an overview of the site and identifies the location of the various LSAs.

Figures 2.3 and 2.4 present LSAs 10-05 and 10-14 following remediation and show the proximity of the waste piles to the excavations. Figure 2.5 displays the backfill depth topography following remediation.

HDP Subsurface Confirmatory Survey 3

5184-SR-09-0 Figure 2.1. Aerial Photo Showing Burial and Waste Handling Areas Figure 2.2. Burial Area LSAs

HDP Subsurface Confirmatory Survey 4

5184-SR-09-0 Figure 2.3. LSAs 10-14 and 10-05 Looking Northwest Figure 2.4. LSA 10-14 Looking West-Northwest with View of Waste Piles

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5184-SR-09-0 Figure 2.5. LSAs 10-14 and 10-05 Backfill Depth (in feet) Topographic Map

3. RADIONUCLIDES OF CONCERN The historical site operations at HDP resulted in several radionuclides of concern (ROCs). The primary ROCs are technetium-99 (Tc-99), thorium-232 (Th-232), radium-226 (Ra-226), uranium-234 (U-234), uranium-235 (U-235), and uranium (U-238). The isotopic abundances of uranium vary based on the enrichment levels of U-235 involved during fuel manufacturing and uranium scrap recovery. There has also been lesser impact due to secondary ROCs, including neptunium-237 (Np-237), plutonium-239/240 (Pu-239/240), and americium-241 (Am-241). DCGLWs were developed for all ROCs. The soil DCGLWs were based on a number of possible future site use exposure scenarios considering where the residual contamination may have been located in the various near surface and subsurface soil strata. These strata are represented in Figure 3.1. This subsurface investigation targeted the interface between the backfill cover and unsaturated zone, representing native soil. Table 3.1 provides the site-specific soil DCGLWs by stratum.

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5184-SR-09-0 Figure 3.1. Conceptual Site Models for Site-Specific DCGLWs Table 3.1. Site-Specific Soil DCGLWs by Stratum Radionuclide DCGLW Values (pCi/g)a Shallowb Stratum Root Stratum Deep Stratum Excavation Scenario Uniform Stratum Uranium-234 508.5 235.6 2,890 872.4 195.4 Uranium-235+Dc 102.3 64.1 3,034 208.1 51.6 Uranium-238+Dc 297.6 183.3 3,028 551.1 168.8 Technetium-99 151.0 30.1 98,649 74.0 25.1 Thorium-232+Cd 4.7 2.0 9,279 5.2 2.0 Radium-226+Cd 5.0 2.1 13,029 5.4 1.9 a The reported limits are the activities of the parent radionuclide, as specified.

b The decommissioning plan uses shallow interchangeably with surface.

c+D refers to the parent radionuclide plus short-lived decay products.

d+C refers to the entire decay chain in secular equilibrium.

In addition to the radiological contaminants, dense non-aqueous phase liquid (DNAPL) organic compounds are also known to be present in the saturated or aquitard zones. Although DNAPLs are not the target objective of this investigation, the compounds were evaluated for health and safety and waste management purposes. Analytical results for DNAPL constituents are discussed in Section 7.4.

HDP Subsurface Confirmatory Survey 7

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4. OBJECTIVES The primary investigation objectives were to:

Conduct subsurface sampling of the backfill and native soil interface at pre-selected locations within both LSAs.

Determine if radionuclide concentrations satisfy the DCGLWs and/or indicate that residual contamination remains either at the interface or within the backfill column, based on downhole logging and/or screening of soil cores.

Evaluate confirmatory samples from the backfill material to ensure that any site-related contaminants detected are at levels that satisfy license conditions for off-site borrow and reuse soil.

5. PROCEDURES From October 16-19, 2017, ORISE performed confirmatory survey activities within LSAs 10-05 and 10-14. The activities were in accordance with a project-specific plan (ORISE 2017). The confirmatory survey activities were also conducted in accordance with the ORAU Radiological and Environmental Survey Procedures Manual and the ORAU Environmental Services and Radiation Training Quality Program Manual (ORAU 2016a and ORAU 2016b).

5.1 SUBSURFACE SAMPLING LOCATION SELECTION Subsurface sampling locations in LSAs 10-05 and 10-14 were selected based on professional judgment using available photographic records, such as those provided in Figures 2.3 and 2.4, and a backfill topographic map (Figure 2.5). The photographic records and maps were reviewed to identify storm water runoff pathways and accumulation points associated with the former waste staging areas that could have impacted LSAs 10-05 and/or 10-14. Once the areas with highest potential for impact were delineated, specific borehole locations were generated in those areas based on a random-start/systematic placement approach. Borehole locations were distributed proportional to the size of the associated area. The configuration of the investigation area and the random-start point resulted in 21 locations being plotted. Figure A.1 illustrates the location of these points in

HDP Subsurface Confirmatory Survey 8

5184-SR-09-0 relation to the LSA boundaries. Individual borehole locations were designated via global positioning coordinates using the NAD 1983 Missouri State Plane East Zone coordinate system.

5.2 SUBSURFACE SAMPLING Subsurface sampling and investigation was conducted at 21 locations throughout LSAs 10-05 and 10-14. The terminal penetration depth at each of the pre-selected locations was based on spatial data received from WEC and interpreted by ORISE. Figure A.2 presents an excavation depth map with the pre-selected sample locations identified. Table 5.1 summarizes the various borehole terminal depths achieved and estimated point of interface for each location.

Table 5.1. Bore Depth and Point of Interface Summary FIDa Sample IDs Coordinates (m)b Interface Depth (m)b Terminal Bore Depth (m)b Interface Backfill X

Y 0

5184S0184 5184S0183 252252 263634 5.8 6.1 1

5184S0192 5184S0191 252259 263634 5.2 6.1 2

5184S0198 5184S0197 252266 263634 6.4 6.7 3

5184S0194 5184S0193 252255 263640 5.2 6.1 4

5184S0196 5184S0195 252263 263640 6.1 6.7 5

5184S0204 5184S0203 252270 263640 6.4 7.3 6

5184S0186 5184S0185 252259 263622 3.4 4.6 7

5184S0188 5184S0187 252266 263622 3.0 4.6 8

5184S0190 5184S0189 252263 263628 4.0 4.6 9

5184S0200 5184S0199 252270 263628 3.4 4.6 10 5184S0202 5184S0201 252274 263634 4.9 6.1 11 5184S0214 5184S0213 252277 263640 5.8 7.6 12 5184S0216 5184S0215 252282 263640 5.2 6.1 13 5184S0212 5184S0211 252272 263646 5.2 6.1 14 5184S0218 5184S0217 252279 263646 5.2 6.1 15 5184S0206 5184S0205 252262 263652 4.9 6.1 16 5184S0210 5184S0209 252269 263652 4.9 6.1 17 5184S0220 5184S0219 252275 263652 4.3 5.5 18c 5184S0224 5184S0223 252282 263652 2.7 4.6 5184S0225 3.7 19 5184S0208 5184S0207 252265 263658 3.7 4.6 20 5184S0222 5184S0221 252272 263658 4.0 4.6 a Field identification b Units converted from feet to meters and rounded to one decimal place c Due to difficulty in identifying the native soil/backfill interface, two samples were collected

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5184-SR-09-0 Following soil core removal, a sample representative of the backfill/native soil interface was collected in equal portions from the 15-centimeter interval above and below the interface as identified by visual inspection and/or excavation depth information provided by WEC. Additionally, a single composite sample was collected per borehole consisting of equal volume aliquots taken from each of the incremental 1.5-meter cores. The composite sample was representative of the entire backfill layer at that borehole location.

5.3 SAMPLE CORE SCREENING Gamma scans of extracted cores were performed using a Ludlum Model 44-10 2-inch x 2-inch sodium iodide (NaI) scintillation detector. Beta scans were performed using Ludlum Model 44-142 plastic scintillation detector. Detectors were coupled to Ludlum Model 2221 ratemeter-scalers with audible indicators. Each soil core was scanned and the audio response monitored to identify the presence of any elevated direct radiation indicative of residual contamination. Beta and gamma detector response ranges were recorded individually for each of the 1.5-meter soil cores. In addition, cores were also screened for volatile organic compounds using a RAE Systems MiniRAE 3000 photoionization detector.

5.4 BOREHOLE LOGGING After the backfill/native soil interface was reached and the sample cores extracted, gamma radiation detection equipment connected to a ratemeter and Trimble Geo 7X datalogger was lowered into the borehole while observing the detectors audio response. Gamma radiation count rates were electronically logged at one-second intervals as the detector was lowered at a rate of approximately 25 centimeters per second.

It was initially planned to conduct borehole logging using only the NaI detector with the outer direct-push technology (DPT) casing in place. However, the inner diameter of the casing was too small to accept the NaI detector. The casing was removed in order to facilitate scanning, but the NaI detector could not consistently reach the backfill/native soil interface due to compression in the borehole following removal of the casing. A smaller diameter Ludlum Model 44-159-1 cesium iodide (CsI) detector was used in addition to the NaI. The CsI detector was able to reach the backfill/native soil interface at all borehole locations. A 30-second static gamma measurement was collected at the backfill/native soil interface and at approximately 1.5-meter intervals as the detector

HDP Subsurface Confirmatory Survey 10 5184-SR-09-0 was retrieved. Since the NaI detector failed to consistently reach the backfill/native soil interface, static measurement data were collected using primarily the CsI. Location 0 is the exception to this because the NaI was able to reach interface depth.

5.5 DECONTAMINATION, WASTE MANAGEMENT, AND BOREHOLE ABANDONMENT Investigation derived wastes included water generated during decontamination activities, excess soil sample cores, used DPT liners and caps, plastic sheeting from the decontamination pad, disposable personal protective equipment, and decontamination wipes.

All downhole equipment making contact with the native soil layer was decontaminated between boreholes. Decontamination consisted of a combination of dry wiping to remove visible soil and cleaning with a phosphate-free detergent solution. All liquids generated during decontamination activities were captured and containerized for on-site water treatment and discharge by WEC.

Excess soil collected from the backfill layer was containerized independently by borehole in sealable plastic buckets. Excess native soil from all boreholes was segregated from backfill material and placed into a single 55-gallon drum. A composite sample of the native soil was collected and submitted for radiological and Toxicity Characteristic Leaching Procedure (TCLP) analysis. All materials pending laboratory analysis were custody sealed, labeled, and stored onsite to await an appropriate disposition pathway determination.

Used DPT liners and caps and plastic sheeting were containerized separately in 55-gallon drums and left at the site pending laboratory analysis of associated soils. The small volume of personal protective equipment (PPE) generated was returned to ORISE for analysis by gamma spectroscopy.

All boreholes were immediately backfilled with bentonite from surface elevation to full depth.

Abandonment activities were conducted with oversight by a Missouri Department of Natural Resources representative to ensure the process was in accordance with local, state, and federal regulations.

HDP Subsurface Confirmatory Survey 11 5184-SR-09-0

6. SAMPLE ANALYSIS AND DATA INTERPRETATION Radiological samples and data collected at the site were transported to the ORISE facility in Oak Ridge, Tennessee for analysis and interpretation. Radiological sample custody was transferred to the ORISE Radiological and Environmental Analytical Laboratory. Radiological sample analyses were performed in accordance with the ORAU Radiological and Environmental Analytical Laboratory Procedures Manual (ORAU 2017). Soil samples were analyzed by gamma spectroscopy for U-238, U-235, Th-232, and Ra-226, and results were also reviewed for other site-specific gamma-emitting ROCs results were reported in units of picocuries per gram (pCi/g). All confirmatory soil samples were compared directly with the uniform stratum DCGLWs presented in Table 3.1.

Alpha spectroscopy was not performed; therefore, U-234 was calculated based on the U-238 to U-235 concentration ratio. Uranium-234 was calculated in the same manner as described in Section 14.1.4.3.3 of the approved decommissioning plan (DP) (WEC 2013).

Samples were analyzed for Tc-99 by chemical separation and liquid scintillation counting. Analytical results were reported in pCi/g.

In addition to radiological analysis, the native soils composite sample was submitted to a subcontracted laboratory for TCLP analysis. The primary analytes of concern include the DNAPL compounds trichloroethylene (TCE) and tetrachloroethylene (PCE). Data was compared to Resource Conservation and Recovery Act (RCRA) limits for the classification of characteristic hazardous wastes.

7. FINDINGS AND RESULTS 7.1 RADIOLOGICAL CONCENTRATIONS IN SOIL A complete summary of analytical results for ROCs identified as site-related contaminants are presented in Appendix B, Table B.1. ROC concentration ranges for interface and backfill soils, including summary statistics, are provided in Table 7.1. Radiological analysis indicates all ROCs are below their respective DCGLWs. Individual sample results were not corrected for background.

HDP Subsurface Confirmatory Survey 12 5184-SR-09-0 Table 7.1. Range of Radionuclide Concentration in Soil Cores (pCi/g)

ROC Uniform DCGLW Interface Backfill Composite Min Max Mean Stdev Min Max Mean Stdev Tc-99 25.1

-0.14 1.04 0.27 0.27

-0.26 0.55 0.11 0.22 U-234a 195.4 0.38 8.89 3.04 2.27 0.70 5.37 2.54 1.20 U-235 51.6 0.01 0.49 0.16 0.13 0.03 0.29 0.13 0.07 U-238 168.8 1.09 2.40 1.68 0.35 1.05 2.6 1.71 0.44 Th-232 2.0 0.99 1.43 1.20 0.11 1.09 1.48 1.26 0.10 Ra-226 1.9 0.82 1.13 0.98 0.09 0.794 1.04 0.92 0.07 a Appendix E provides the details for the calculation of U-234 concentration.

7.2 SAMPLE CORE SCREENING Each 1.5-meter section of sample core was scanned for both beta and gamma radiation using the instruments mentioned in Section 5.3. No audible indication of elevated radiation was identified during scanning. Beta scans ranged from 270 to 700 counts per minute (cpm), with an average background of approximately 450 cpm. Gamma scans ranged from 8,000 to 12,200 cpm, with an average background of approximately 9,500 cpm. A summary of the collected soil core screening data is provided in Table 7.2. No judgmental samples were collected based on scan results.

Table 7.2. Sample Core Screening Results FIDa Sample IDs Measurement Ranges (cpm)

Interface Backfill Beta Gamma 0

5184S0184 5184S0183 300 - 700 8,500 - 10,500 1

5184S0192 5184S0191 330 - 500 8,600 - 11,000 2

5184S0198 5184S0197 320 - 450 8,200 - 10,400 3

5184S0194 5184S0193 330 - 510 8,800 - 10,100 4

5184S0196 5184S0195 340 - 500 8,000 - 10,200 5

5184S0204 5184S0203 300 - 540 9,000 - 11,800 6

5184S0186 5184S0185 385 - 620 8,500 - 10,000 7

5184S0188 5184S0187 350 - 550 10,300 - 12,000 8

5184S0190 5184S0189 300 - 520 9,400 - 12,000 9

5184S0200 5184S0199 340 - 450 8,400 - 10,000 10 5184S0202 5184S0201 300 - 500 9,600 - 12,200 11 5184S0214 5184S0213 330 - 530 8,700 - 10,300 12 5184S0216 5184S0215 330 - 530 8,700 - 11,100 13 5184S0212 5184S0211 350 - 550 8,600 - 10,700 14 5184S0218 5184S0217 300 - 460 8,700 - 11,400 15 5184S0206 5184S0205 300 - 480 9,100 - 11,100 16 5184S0210 5184S0209 350 - 500 8,800 - 10,300

HDP Subsurface Confirmatory Survey 13 5184-SR-09-0 Table 7.2. Sample Core Screening Results FIDa Sample IDs Measurement Ranges (cpm)

Interface Backfill Beta Gamma 17 5184S0220 5184S0219 310 - 470 9,100 - 11,100 18 5184S0224 5184S0223 270 - 460 8,400 - 9,900 5184S0225 19 5184S0208 5184S0207 350 - 470 8,400 - 10,500 20 5184S0222 5184S0221 314 - 520 8,800 - 10,800 a field identification 7.3 BOREHOLE LOGGING There was no audible indication of elevated direct radiation identified during scanning.

Comprehensive results of all borehole logging data are provided in Appendix A, Figures A.3 and A.4 as histograms. Data for the NaI and CsI detectors were evaluated individually. Since the NaI was consistently unable to reach the backfill/native soil interface, scan data presented in the aforementioned histograms should not be considered representative of the entire study area. Results generated by the NaI rarely included data points collected from the backfill/native soil interface region. The exception to this statement would include scan data from Locations 0, 1, 18, and 20, which either reached the interface or came reasonably close.

Both figures indicate data are representative of background consistent with a normal distribution, where 97% of NaI data points and 99% percent of CsI data points fall within three standard deviations of the mean. It is noted that both histograms are bimodal. The lower intensity peak is related to detector response above and just inside of the borehole, while the higher intensity peak results from detector responses generated inside the borehole. Use of histograms in the evaluation of scan data is discussed further in Section E.3.2.

Static measurements were collected at various intervals as described in Section 5.4. Due to the inability of the NaI to consistently reach the backfill/native soil interface depth because of borehole compression, static measurements were collected and evaluated primarily with the CsI. It is noted that Location 0 was the first borehole surveyed and did not exhibit the same issues with borehole compression. As a result, static measurement data from Location 0 was collected with the NaI.

A complete evaluation of static measurement data indicates all measurements fall within the 1,900 cpm to 2,900 cpm background range for the CsI detector as established from the comprehensive collection of scan data. The minimum and maximum static CsI measurements were

HDP Subsurface Confirmatory Survey 14 5184-SR-09-0 2,000 cpm and 2,500 cpm, respectively. NaI measurements collected from Location 0 fall within the 16,000 cpm to 22,000 cpm background range established from collected data. As previously mentioned, NaI scan data consists primarily of the backfill layer. A complete summary of static measurement data is provided in Appendix B, Table B.2. An evaluation of the scan sensitivity of the CsI detector is presented in Appendix E.

7.4 WASTE SAMPLING TCLP results for the native soils composite sample were all below their respective characteristic hazardous waste limit. It is noted that PCE was present at 0.074 mg/L, which is still below the 0.7 mg/L regulatory limit for PCE characteristic hazardous waste. Results of TCLP analysis are provided in Appendix C. Radiological analysis of the composite waste sample indicates all ROCs are below their respective DCGLWs. Analytical results are presented in Appendix B, Table B.1 Gamma spectroscopy results indicated the PPE could be disposed of as regular trash.

8.

SUMMARY

AND CONCLUSION At NRCs request, ORISE conducted independent confirmatory subsurface investigations and sampling in the documented burial area. The areas investigated were LSAs 10-05 and 10-14. The survey was conducted October 16-19, 2017. The survey activities included subsurface soil sampling, sample core scanning, and borehole scanning/data logging. ORISE collected a total of 44 samples consisting of 22 samples taken from the backfill/native soil interface region, 21 composite samples collected from backfill elevations, and one composite waste profile sample. All individual confirmatory measurement results were below the respective uniform stratum DCGLW values (most restrictive) for the ROCs specified in the approved DP.

HDP Subsurface Confirmatory Survey 15 5184-SR-09-0

9. REFERENCES NRC 1998. Albequist, E.W., et al. Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions. NUREG-1507. U.S. Nuclear Regulatory Commission. Washington, D.C. January.

ORAU 2014. ORAU Radiation Protection Manual. Oak Ridge Associated Universities, Oak Ridge, Tennessee. October.

ORAU 2016a. ORAU Radiological and Environmental Survey Procedures Manual. Oak Ridge Associated Universities, Oak Ridge. Tennessee. November 10.

ORAU 2016b. ORAU Environmental Services and Radiation Training Quality Program Manual. Oak Ridge Associated Universities. Oak Ridge, Tennessee. November 9.

ORAU 2016c. ORAU Health and Safety Manual. Oak Ridge, Tennessee. January.

ORAU 2017. ORAU Radiological and Environmental Analytical Laboratory Procedures Manual. Oak Ridge Associated Universities. Oak Ridge, Tennessee. August 24.

ORISE 2017. Project-Specific Plan for Independent Confirmatory Subsurface Investigations and Sampling for the Hematite Decommissioning Project, Festus, Missouri. 5184-PL-04-0. Oak Ridge Institute for Science and Education. Oak Ridge, Tennessee. October 12.

WEC 2013. Hematite Decommissioning Plan Chapter 14: HEM 13-10; Revision 1.2. Westinghouse Electric Company, LLC. Festus, Missouri. February 12.

HDP Subsurface Confirmatory Survey 5184-SR-09-0 APPENDIX A FIGURES

HDP Subsurface Confirmatory Survey A-1 5184-SR-09-0 Figure A.1. Borehole Locations

HDP Subsurface Confirmatory Survey A-2 5184-SR-09-0 Figure A.2. Excavation Depth Map (in feet)

HDP Subsurface Confirmatory Survey A-3 5184-SR-09-0 Figure A.3. NaI Detector Borehole Logging Data Histogram Figure A.4. CsI Detector Borehole Logging Data Histogram 0

50 100 150 200 250 300 Frequency CPM NaI Results Frequency 0

20 40 60 80 100 120 140 160 180 Frequency cpm CsI Results Frequency

HDP Subsurface Confirmatory Survey 5184-SR-09-0 APPENDIX B TABLES

HDP Subsurface Confirmatory Survey B-1 5184-SR-09-0 Table B.1. ROC Concentration in Sample Cores (pCi/g)a, b Sample IDc Tc-99 MDC U-234d U-235 MDC U-238 MDC Th-232 MDC Ra-226 MDC Interface Samples 5184S0184 0.34

+/- 0.36 0.60 1.8

+/-

2.0 0.09

+/-

0.10 0.26 1.50

+/- 0.54 0.94 1.27

+/- 0.19 0.28 0.979

+/-

0.070 0.097 5184S0186 0.93

+/- 0.36 0.55 2.7

+/-

2.7 0.14

+/-

0.14 0.34 1.91

+/- 0.77 1.46 1.43

+/- 0.25 0.36 0.94

+/-

0.10 0.13 5184S0188 0.03

+/- 0.33 0.59 1.2

+/-

2.4 0.05

+/-

0.10 0.25 2.01

+/- 0.62 0.97 1.19

+/- 0.19 0.29 0.965

+/-

0.072 0.101 5184S0190 0.31

+/- 0.36 0.60 7.3

+/-

2.4 0.40

+/-

0.13 0.29 2.40

+/- 0.77 1.24 1.23

+/- 0.21 0.31 0.883

+/-

0.094 0.119 5184S0192 0.12

+/- 0.36 0.62 7.1

+/-

3.1 0.39

+/-

0.17 0.39 1.8

+/-

1.1 2.3 1.23

+/- 0.19 0.28 0.871

+/-

0.095 0.140 5184S0194 0.16

+/- 0.37 0.64 8.9

+/-

2.2 0.49

+/-

0.12 0.37 2.1

+/-

1.1 2.4 1.18

+/- 0.19 0.30 0.868

+/-

0.097 0.146 5184S0196

-0.14

+/- 0.35 0.64 4.1

+/-

1.9 0.22

+/-

0.10 0.226 1.92

+/- 0.55 0.80 1.34

+/- 0.17 0.18 0.914

+/-

0.060 0.080 5184S0198 0.20

+/- 0.36 0.62 2.9

+/-

2.3 0.15

+/-

0.12 0.30 1.63

+/- 0.65 1.22 1.22

+/- 0.19 0.27 1.063

+/-

0.099 0.114 5184S0200 0.12

+/- 0.36 0.63 4.5

+/-

2.4 0.24

+/-

0.13 0.29 2.03

+/- 0.99 2.03 1.202

+/- 0.099 0.193 0.975

+/-

0.094 0.126 5184S0202 0.05

+/- 0.37 0.65 4.6

+/-

1.3 0.246

+/- 0.070 0.219 2.03

+/- 0.59 0.86 1.17

+/- 0.17 0.23 0.984

+/-

0.064 0.085 5184S0204 1.04

+/- 0.39 0.58 1.2

+/-

2.0 0.051

+/- 0.089 0.212 1.54

+/- 0.51 0.84 1.15

+/- 0.15 0.19 1.004

+/-

0.071 0.098 5184S0206 0.23

+/- 0.34 0.59 3.3

+/-

2.6 0.18

+/-

0.14 0.31 1.2

+/-

1.1 2.4 1.07

+/- 0.16 0.22 1.025

+/-

0.092 0.110 5184S0208 0.22

+/- 0.33 0.57 1.0

+/-

1.7 0.046

+/- 0.078 0.186 1.23

+/- 0.41 0.71 1.03

+/- 0.12 0.13 0.909

+/-

0.054 0.069 5184S0210 0.52

+/- 0.36 0.58 2.2

+/-

1.8 0.117

+/- 0.095 0.222 1.31

+/- 0.51 0.96 0.99

+/- 0.16 0.26 0.828

+/-

0.078 0.092 5184S0212 0.34

+/- 0.35 0.59 0.4

+/-

5.6 0.01

+/-

0.15 0.35 1.09

+/- 0.92 2.08 1.37

+/- 0.18 0.23 1.072

+/-

0.098 0.125 5184S0214 0.36

+/- 0.36 0.60 1.5

+/-

2.2 0.069

+/- 0.098 0.247 1.87

+/- 0.55 0.78 1.23

+/- 0.16 0.17 1.115

+/-

0.069 0.085 5184S0216 0.22

+/- 0.34 0.59 1.3

+/-

2.8 0.06

+/-

0.13 0.30 1.44

+/- 0.62 1.22 1.12

+/- 0.19 0.31 1.08

+/-

0.11 0.16 5184S0218 0.15

+/- 0.32 0.55 3.7

+/-

3.0 0.20

+/-

0.16 0.38 1.49

+/- 0.94 2.03 1.17

+/- 0.16 0.23 1.088

+/-

0.099 0.128 5184S0220 0.25

+/- 0.35 0.59 1.4

+/-

1.8 0.065

+/- 0.087 0.206 1.34

+/- 0.46 0.81 1.33

+/- 0.17 0.21 0.957

+/-

0.068 0.091 5184S0222 0.05

+/- 0.34 0.59 2.2

+/-

2.0 0.11

+/-

0.10 0.24 1.56

+/- 0.68 1.34 1.26

+/- 0.18 0.22 1.003

+/-

0.094 0.111 5184S0224 0.17

+/- 0.35 0.61 1.4

+/-

3.7 0.06

+/-

0.16 0.39 2.0

+/-

1.0 2.0 1.10

+/- 0.17 0.27 0.862

+/-

0.091 0.134 5184S0225 0.28

+/- 0.34 0.57 2.2

+/-

2.6 0.11

+/-

0.13 0.31 1.57

+/- 0.64 1.21 1.16

+/- 0.18 0.24 1.13

+/-

0.10 0.12 Backfill Composite Samples 5184S0183 0.01

+/- 0.34 0.60 3.9

+/-

2.4 0.21

+/-

0.13 0.30 1.88

+/- 0.64 1.18 1.17

+/- 0.19 0.27 0.829

+/-

0.089 0.115 5184S0185

-0.01

+/- 0.32 0.58 3.4

+/-

3.4 0.18

+/-

0.18 0.42 1.9

+/-

1.1 2.4 1.48

+/- 0.21 0.29 0.99

+/-

0.11 0.16 5184S0187

-0.08

+/- 0.32 0.58 0.7

+/-

2.3 0.030

+/- 0.096 0.157 1.05

+/- 0.53 1.09 1.25

+/- 0.18 0.26 0.963

+/-

0.092 0.113 5184S0189 0.01

+/- 0.35 0.62 3.5

+/-

3.3 0.18

+/-

0.17 0.40 2.6

+/-

1.1 2.2 1.22

+/- 0.18 0.27 0.906

+/-

0.098 0.146 5184S0191 0.19

+/- 0.32 0.55 2.0

+/-

2.0 0.10

+/-

0.10 0.24 1.72

+/- 0.56 0.90 1.18

+/- 0.17 0.22 0.853

+/-

0.074 0.110

HDP Subsurface Confirmatory Survey B-2 5184-SR-09-0 Table B.1. ROC Concentration in Sample Cores (pCi/g)a, b Sample IDc Tc-99 MDC U-234d U-235 MDC U-238 MDC Th-232 MDC Ra-226 MDC 5184S0193 0.25

+/- 0.36 0.61 3.8

+/-

2.1 0.20

+/-

0.11 0.26 2.22

+/- 0.63 0.88 1.13

+/- 0.17 0.25 0.860

+/-

0.075 0.113 5184S0195

-0.17

+/- 0.36 0.65 1.8

+/-

3.1 0.08

+/-

0.14 0.34 2.33

+/- 0.78 1.30 1.41

+/- 0.22 0.31 0.92

+/-

0.10 0.13 5184S0197

-0.10

+/- 0.34 0.61 4.3

+/-

3.1 0.23

+/-

0.17 0.40 1.7

+/-

1.3 2.9 1.25

+/- 0.20 0.28 1.00

+/-

0.10 0.13 5184S0199 0.09

+/- 0.37 0.65 3.1

+/-

1.8 0.167

+/- 0.095 0.218 1.56

+/- 0.52 0.88 1.28

+/- 0.17 0.22 0.974

+/-

0.065 0.090 5184S0201

-0.26

+/- 0.34 0.62 5.4

+/-

2.4 0.29

+/-

0.13 0.30 2.19

+/- 0.69 1.10 1.21

+/- 0.19 0.27 0.898

+/-

0.088 0.110 5184S0203

-0.19

+/- 0.35 0.64 1.6

+/-

2.2 0.08

+/-

0.11 0.26 1.43

+/- 0.46 1.05 1.22

+/- 0.19 0.27 0.910

+/-

0.087 0.10 5184S0205 0.01

+/- 0.32 0.57 3.1

+/-

2.9 0.17

+/-

0.16 0.38 1.06

+/- 0.90 2.03 1.30

+/- 0.18 0.25 0.933

+/-

0.092 0.127 5184S0207 0.55

+/- 0.37 0.60 1.8

+/-

2.0 0.09

+/-

0.10 0.24 1.55

+/- 0.53 0.90 1.10

+/- 0.15 0.20 0.856

+/-

0.077 0.092 5184S0209 0.47

+/- 0.37 0.60 2.5

+/-

2.5 0.13

+/-

0.13 0.31 1.43

+/- 0.92 2.00 1.27

+/- 0.17 0.23 0.811

+/-

0.088 0.132 5184S0211 0.50

+/- 0.36 0.59 2.3

+/-

1.8 0.119

+/- 0.093 0.218 1.76

+/- 0.51 0.76 1.09

+/- 0.15 0.21 0.975

+/-

0.065 0.088 5184S0213 0.13

+/- 0.33 0.57 1.6

+/-

2.0 0.08

+/-

0.10 0.24 1.35

+/- 0.58 1.14 1.29

+/- 0.19 0.25 0.890

+/-

0.09 0.115 5184S0215 0.07

+/- 0.33 0.58 2.8

+/-

3.3 0.14

+/-

0.17 0.40 2.0

+/-

1.1 2.3 1.40

+/- 0.18 0.25 1.04

+/-

0.10 0.14 5184S0217 0.36

+/- 0.34 0.56 1.6

+/-

2.0 0.079

+/- 0.095 0.223 1.51

+/- 0.48 0.76 1.16

+/- 0.16 0.20 0.982

+/-

0.068 0.094 5184S0219 0.21

+/- 0.34 0.58 1.6

+/-

2.5 0.07

+/-

0.11 0.26 2.20

+/- 0.73 1.20 1.38

+/- 0.21 0.30 1.04

+/-

0.11 0.14 5184S0221 0.11

+/- 0.35 0.60 1.4

+/-

2.8 0.07

+/-

0.14 0.34 1.21

+/- 0.91 2.03 1.30

+/- 0.17 0.22 0.794

+/-

0.087 0.131 5184S0223 0.11

+/- 0.33 0.58 1.0

+/-

2.8 0.047

+/- 0.085 0.215 1.18

+/- 0.41 0.70 1.27

+/- 0.16 0.20 0.915

+/-

0.059 0.081 Native Soil Waste Sample Composite 5184S0226 0.07

+/- 0.34 0.60 1.8

+/-

1.8 0.09

+/-

0.09 0.21 1.58

+/- 0.48 0.72 1.20

+/- 0.17 0.23 0.949

+/-

0.067 0.089 a Uncertainties represent the total propagated uncertainties reported at the 95% confidence level.

b Individual sample results are not corrected for background contributions.

c Refer to Figure A.1 for sample locations.

dAppendix E provides the details for the calculation of U-234 concentration.

LSA Location ID Interface Depth (m)

Measurement Depth (m)

Static Measurementa (cpm) 1.8 17206 3.0 19648 4.3 19370 5.5 19754 Min 17206 Max 19754 Average 18995 1.5 2050 2.4 2260 3.7 2322 5.2 2330 Min 2050 Max 2330 Average 2241 1.5 2010 3.0 2384 4.6 2354 6.4 2450 Min 2010 Max 2450 Average 2300 1.5 2090 2.4 2314 3.7 2212 5.2 2412 Min 2090 Max 2412 Average 2257 1.5 2156 3.0 2270 4.6 2528 6.1 2346 Min 2156 Max 2528 Average 2325 1.5 2206 3.0 2306 4.6 2278 6.4 2328 Min 2206 Max 2328 Average 2280 14-10 14-10 14-10 14-10 0b 5.8 1

5.2 14-10 14-10 2

6.4 3

5.2 4

6.1 5

6.4 Table B.2. Static Measurement Results HDP Subsurface Confirmatory Survey B-3 5184-SR-09-0

LSA Location ID Interface Depth (m)

Measurement Depth (m)

Static Measurementa (cpm)

Table B.2. Static Measurement Results 1.5 2292 3.4 2182 Min 2182 Max 2292 Average 2237 1.5 2400 3.0 2418 Min 2400 Max 2418 Average 2409 1.5 2078 3.0 2348 4.0 2346 Min 2078 Max 2348 Average 2257 1.5 2142 3.4 2350 Min 2142 Max 2350 Average 2246 1.5 2224 3.0 2466 4.9 2368 Min 2224 Max 2466 Average 2353 1.5 2244 3.0 2330 4.6 2394 5.8 2202 Min 2202 Max 2394 Average 2293 1.5 2112 3.0 2166 5.2 2496 Min 2112 Max 2496 Average 2258 1.5 2224 3.0 2142 5.2 2460 Min 2142 Max 2460 Average 2275 14-10 14-10 14-10 14-05 14-05 14-10 14-10 14-10 6

3.4 7

3.0 10 4.9 11 5.8 8

4.0 9

3.4 12 5.2 13 5.2 HDP Subsurface Confirmatory Survey B-4 5184-SR-09-0

LSA Location ID Interface Depth (m)

Measurement Depth (m)

Static Measurementa (cpm)

Table B.2. Static Measurement Results 1.5 2218 3.0 2174 5.2 2416 Min 2174 Max 2416 Average 2269 1.5 2134 3.0 2366 Min 2134 Max 2366 Average 2250 1.5 2060 3.0 2198 4.9 2366 Min 2060 Max 2366 Average 2208 1.5 2326 3.0 2136 4.3 2198 Min 2136 Max 2326 Average 2220 1.5 2200 2.7 2210 3.7 2204 Min 2200 Max 2210 Average 2205 1.8 2226 3.7 2154 Min 2154 Max 2226 Average 2190 1.5 2078 3.0 2398 4.0 2314 Min 2078 Max 2398 Average 2263 14-05 14-05 14-05 14-05 14-05 14-05 14-05 4.9 a 30 second static measurement was collected and converted to units of counts per minute.

b First borehole did not present compression issues. No comparable CsI data collected.

20 4.0 18 2.7 19 3.7 16 4.9 17 4.3 14 5.2 15 HDP Subsurface Confirmatory Survey B-5 5184-SR-09-0

HDP Subsurface Confirmatory Survey 5184-SR-09-0 APPENDIX C CHEMICAL ANALYSIS RESULTS

November 15, 2017 Mr. Jason Lee Oak Ridge Associated Universities PO Box 117 Oak Ridge, Tennessee 37831 Re: Soil Analysis for Chemical Constituents Work Order: 436338

Dear Mr. Lee:

GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for the sample(s) we received on October 26, 2017. This original data report has been prepared and reviewed in accordance with GELs standard operating procedures.

Our policy is to provide high quality, personalized analytical services to enable you to meet your analytical needs on time every time. We trust that you will find everything in order and to your satisfaction. If you have any questions, please do not hesitate to call me at (843) 556-8171, ext. 4504.

Sincerely, PM_SIGN_HERE Erin Trent Project Manager Purchase Order: 603523 Enclosures Page 1 of 28 HDP Subsurface Confirmatory Survey C-1 5184-SR-09-0

Reviewed by USER_SIGN_HERE GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 (843) 5568171 www.gel.com Certificate of Analysis Report ORAU002 ORAU (603523)

Client SDG: 436338 GEL Work Order: 436338 Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the Certificate of Analysis.

The designation ND, if present, appears in the result column when the analyte concentration is not detected above the limit as defined in the U qualifier above.

This data report has been prepared and reviewed in accordance with GEL Laboratories LLC standard operating procedures. Please direct any questions to your Project Manager, Erin Trent.

The Qualifiers in this report are defined as follows:

A quality control analyte recovery is outside of specified acceptance criteria

- Analyte is a Tracer compound

- Analyte is a surrogate compound J Value is estimated U Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.

for Page 2 of 28 HDP Subsurface Confirmatory Survey C-2 5184-SR-09-0

Certificate of Analysis GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Report Date: November 15, 2017 Parameter Result Units Qualifier Analyst Date Time DF Batch Method RL DL PF Mercury Analysis-CVAA Metals Analysis-ICP Semi-Volatile-GC/MS Volatile Organics 1718693 1713664 1713446 1717560 1414 2045 1922 2017 mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L 11/15/17 11/10/17 10/31/17 11/09/17 MTM1 JWJ JLD1 JP1 0.002 0.300 0.050 0.050 0.050 0.100 0.300 0.050 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 10.0 10.0 10.0 50.0 10.0 10.0 10.0 10.0 10.0 1

1 1

1 10 10 10 10 10 10 10 10 10 Mr. Jason Lee

Contact:

Oak Ridge Associated Universities Company :

PO Box 117 Oak Ridge, Tennessee 37831 Address :

Soil Analysis for Chemical Constituents Project:

436338001 Soil 19-OCT-17 13:30 26-OCT-17 5184S0226 ORAU00200 Project:

ORAU002 Client ID:

Client Sample ID:

Receive Date:

Client Sample ID:

Matrix:

Collect Date:

Collector:

0.00067 0.050 0.010 0.010 0.010 0.033 0.060 0.010 15.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 18.5 15.0 3.33 3.33 3.33 16.7 3.33 3.33 3.33 3.33 3.33 1

2 3

4 U

U U

U J

U U

U Mercury Arsenic Barium Cadmium Chromium Lead Selenium Silver 1,4-Dichlorobenzene 2,4,5-Trichlorophenol 2,4,6-Trichlorophenol 2,4-Dinitrotoluene Hexachlorobenzene Hexachlorobutadiene Hexachloroethane Nitrobenzene Pentachlorophenol Pyridine m,p-Cresols o-Cresol 1,1-Dichloroethylene 1,2-Dichloroethane 1,4-Dichlorobenzene 2-Butanone Benzene Carbon tetrachloride Chlorobenzene Chloroform Tetrachloroethylene TCLP Hg in Solid "As Received" TCLP ICP Metals - 1311/3010A/6010C "As Received" TCLP SVOA-1311/3510C/8270D "As Received" TCLP Volatiles, Solid "As Received" ND ND 1.03 ND 0.0633 ND 0.0711 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND 74.2 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 0.005 0.005 0.005 0.005 0.005 0.005 0.005 0.005 0.005 0.005 0.005 0.005 Page 3 of 28 HDP Subsurface Confirmatory Survey C-3 5184-SR-09-0

Certificate of Analysis GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Report Date: November 15, 2017 Parameter Result Units Qualifier Analyst Date Time DF Batch Method RL DL PF Volatile Organics ug/L ug/L 10.0 10.0 10 10 Mr. Jason Lee

Contact:

Oak Ridge Associated Universities Company :

PO Box 117 Oak Ridge, Tennessee 37831 Address :

Soil Analysis for Chemical Constituents Project:

436338001 5184S0226 ORAU00200 Project:

ORAU002 Client ID:

Sample ID:

Client Sample ID:

Surrogate/Tracer Recovery Recovery%

Test Acceptable Limits 3.33 3.33 U

U Trichloroethylene Vinyl chloride TCLP Volatiles, Solid "As Received" ND ND 2-Fluorobiphenyl Nitrobenzene-d5 p-Terphenyl-d14 2,4,6-Tribromophenol 2-Fluorophenol Phenol-d5 1,2-Dichloroethane-d4 Bromofluorobenzene Toluene-d8 TCLP SVOA-1311/3510C/8270D "As Received" TCLP SVOA-1311/3510C/8270D "As Received" TCLP SVOA-1311/3510C/8270D "As Received" TCLP SVOA-1311/3510C/8270D "As Received" TCLP SVOA-1311/3510C/8270D "As Received" TCLP SVOA-1311/3510C/8270D "As Received" TCLP Volatiles, Solid "As Received" TCLP Volatiles, Solid "As Received" TCLP Volatiles, Solid "As Received" 66 81 87 50 46 28 104 100 98 (32%-112%)

(36%-115%)

(36%-121%)

(32%-124%)

(15%-88%)

(15%-91%)

(71%-134%)

(70%-131%)

(74%-124%)

The following Prep Methods were performed:

SW846 1311 SW846 1311 SW846 1311 SW846 3010A SW846 3510C SW846 7470A Prep SW846 1311 TCLP Leaching SW846 1311 TCLP Leaching SW846 1311 TCLP Volatiles Prep ICP-TRACE TCLP by SW846 3010A 3510C BNA TCLP/SPLP Prep-GC/MS Analysis EPA 7470A Mercury Prep TCLP Liquid 10/26/17 10/26/17 10/26/17 10/27/17 10/31/17 11/14/17 1713251 1713252 1713253 1713663 1713445 1718692 1445 1445 1450 0951 0500 1414 JP2 JP2 JP2 SXW1 DXF4 AXS5 Method Description Analyst Date Time Prep Batch The following Analytical Methods were performed:

1 2

3 4

Method Description SW846 7470A SW846 3010A/6010C SW846 3510C/8270D SW846 8260B Analyst Comments Nominal 250 250 250 500 500 500 50.0 50.0 50.0 Result 166 203 217 252 231 142 521 501 489 ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L Notes:

Page 4 of 28 HDP Subsurface Confirmatory Survey C-4 5184-SR-09-0

Certificate of Analysis GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Report Date: November 15, 2017 Parameter Result Units Qualifier Analyst Date Time DF Batch Method RL DL PF Mr. Jason Lee

Contact:

Oak Ridge Associated Universities Company :

PO Box 117 Oak Ridge, Tennessee 37831 Address :

Soil Analysis for Chemical Constituents Project:

436338001 5184S0226 ORAU00200 Project:

ORAU002 Client ID:

Sample ID:

Client Sample ID:

Lc/LC: Critical Level PF: Prep Factor RL: Reporting Limit SQL: Sample Quantitation Limit Column headers are defined as follows:

DF: Dilution Factor DL: Detection Limit MDA: Minimum Detectable Activity MDC: Minimum Detectable Concentration Page 5 of 28 HDP Subsurface Confirmatory Survey C-5 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Metals Analysis-ICP 1713664 Batch Arsenic Barium Cadmium Chromium Lead Selenium Silver Arsenic Barium Cadmium Chromium Lead Selenium Parmname Mr. Jason Lee

Contact:

Oak Ridge Associated Universities PO Box 117 Oak Ridge, Tennessee November 15, 2017 Report Date:

Units mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L Anlst Date Time JWJ 11/10/17 20:47 11/10/17 20:44 QC 0.0572 0.945 ND 0.0314 ND ND ND 5.23 5.06 4.93 4.98 5.18 4.82 NOM Sample ND 1.03 ND 0.0633 ND 0.0711 ND Range (0%-20%)

(+/-0.050)

(80%-120%)

Qual J

U J

U U

U QC1203906605 436338001 QC1203906604 200 8.4 N/A 67.6 N/A 200 N/A REC%

105 101 98.5 99.6 104 96.4 5.00 5.00 5.00 5.00 5.00 5.00 DUP LCS 436338 Workorder:

U U

U J

U

^

RPD%

Page 1 of 16 Page 6 of 28 HDP Subsurface Confirmatory Survey C-6 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Metals Analysis-ICP 1713664 Batch Silver Arsenic Barium Cadmium Chromium Lead Selenium Silver Arsenic Barium Cadmium Chromium Lead Selenium Parmname Units mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L mg/L Anlst Date Time JWJ 11/10/17 20:44 11/10/17 20:38 11/10/17 20:49 QC 4.87 ND ND ND ND ND ND ND 5.22 10.7 0.949 4.90 4.99 1.00 NOM Sample ND 1.03 ND 0.0633 ND 0.0711 Range (80%-120%)

(75%-125%)

Qual U

U U

QC1203906603 QC1203905601 436338001 REC%

97.3 104 96.3 94.5 96.8 99.2 92.9 5.00 5.00 10.0 1.00 5.00 5.00 1.00 MB MS 436338 Workorder:

U U

U J

RPD%

Page 2 of 16 Page 7 of 28 HDP Subsurface Confirmatory Survey C-7 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Metals Analysis-ICP 1713664 Batch Silver Arsenic Barium Cadmium Chromium Lead Selenium Silver Arsenic Barium Cadmium Chromium Lead Selenium Parmname Units mg/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L mg/L mg/L mg/L mg/L mg/L mg/L Anlst Date Time JWJ 11/10/17 20:49 11/10/17 20:51 11/10/17 20:41 QC 0.479 ND 21.1 ND 1.31 ND ND ND ND 0.0221 ND 0.023 ND ND NOM Sample ND ND 103 ND 6.33 ND 7.11 ND Range (75%-125%)

(0%-10%)

Qual U

U J

U U

J U

U QC1203906607 436338001 QC1203905602 N/A 2.6 N/A 3.58 N/A N/A N/A REC%

95.4 0.503 SDILT TB 436338 Workorder:

U U

J U

RPD%

Page 3 of 16 Page 8 of 28 HDP Subsurface Confirmatory Survey C-8 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Metals Analysis-ICP Metals Analysis-Mercury Semi-Volatile-GC/MS 1713664 1718693 1713446 Batch Batch Batch Silver Mercury Mercury Mercury Mercury Mercury Mercury 1,4-Dichlorobenzene 2,4,5-Trichlorophenol 2,4,6-Trichlorophenol 2,4-Dinitrotoluene Parmname Units mg/L mg/L mg/L mg/L mg/L ug/L mg/L ug/L ug/L ug/L ug/L Anlst Date Time JWJ MTM1 JLD1 11/10/17 20:41 11/15/17 14:18 11/15/17 14:13 11/15/17 14:09 11/15/17 14:16 11/15/17 14:19 11/15/17 14:11 10/31/17 14:11 QC ND ND 0.0217 ND 0.021 ND ND 34.3 43.8 42.8 45.9 NOM Sample ND ND ND Range (80%-120%)

(75%-125%)

(0%-10%)

(38%-96%)

(55%-116%)

(55%-120%)

(57%-124%)

Qual U

U U

QC1203919366 436338001 QC1203919365 QC1203919364 QC1203905601 436338001 QC1203919368 436338001 QC1203905602 QC1203906080 N/A N/A REC%

109 105 69 88 86 92 0.020 0.020 50.0 50.0 50.0 50.0 DUP LCS MB MS SDILT TB LCS 436338 Workorder:

U U

U RPD%

Page 4 of 16 Page 9 of 28 HDP Subsurface Confirmatory Survey C-9 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Semi-Volatile-GC/MS 1713446 Batch Hexachlorobenzene Hexachlorobutadiene Hexachloroethane Nitrobenzene Pentachlorophenol Pyridine m,p-Cresols o-Cresol 2,4,6-Tribromophenol 2-Fluorobiphenyl 2-Fluorophenol Nitrobenzene-d5 Phenol-d5 p-Terphenyl-d14 1,4-Dichlorobenzene Parmname Units ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L Anlst Date Time JLD1 10/31/17 14:11 10/31/17 11:37 QC 42.8 27.8 32.0 49.3 48.7 23.4 37.2 38.1 85.2 38.5 53.4 46.1 32.5 46.0 ND NOM Sample Range (54%-115%)

(35%-98%)

(36%-96%)

(53%-115%)

(41%-116%)

(27%-89%)

(43%-102%)

(41%-101%)

(32%-124%)

(32%-112%)

(15%-88%)

(36%-115%)

(15%-91%)

(36%-121%)

Qual U

QC1203906079 REC%

86 56 64 99 97 47 74 76 85 77 53 92 33 92 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 100 50.0 100 50.0 100 50.0 MB 436338 Workorder:

RPD%

Page 5 of 16 Page 10 of 28 HDP Subsurface Confirmatory Survey C-10 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Semi-Volatile-GC/MS 1713446 Batch 2,4,5-Trichlorophenol 2,4,6-Trichlorophenol 2,4-Dinitrotoluene Hexachlorobenzene Hexachlorobutadiene Hexachloroethane Nitrobenzene Pentachlorophenol Pyridine m,p-Cresols o-Cresol 2,4,6-Tribromophenol 2-Fluorobiphenyl 2-Fluorophenol Nitrobenzene-d5 Parmname Units ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L Anlst Date Time JLD1 10/31/17 11:37 QC ND ND ND ND ND ND ND ND ND ND ND 84.4 40.8 55.0 50.3 NOM Sample Range (32%-124%)

(32%-112%)

(15%-88%)

(36%-115%)

Qual U

U U

REC%

84 82 55 101 100 50.0 100 50.0 436338 Workorder:

RPD%

Page 6 of 16 Page 11 of 28 HDP Subsurface Confirmatory Survey C-11 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Semi-Volatile-GC/MS 1713446 Batch Phenol-d5 p-Terphenyl-d14 1,4-Dichlorobenzene 2,4,5-Trichlorophenol 2,4,6-Trichlorophenol 2,4-Dinitrotoluene Hexachlorobenzene Hexachlorobutadiene Hexachloroethane Nitrobenzene Pentachlorophenol Pyridine m,p-Cresols o-Cresol 2,4,6-Tribromophenol Parmname Units ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L Anlst Date Time JLD1 10/31/17 11:37 10/31/17 15:45 QC 35.6 52.3 161 215 212 210 203 139 153 232 287 152 193 192 413 NOM Sample ND ND ND ND ND ND ND ND ND ND ND ND 392 Range (15%-91%)

(36%-121%)

(28%-97%)

(42%-120%)

(39%-124%)

(45%-125%)

(40%-118%)

(26%-98%)

(29%-94%)

(38%-123%)

(35%-121%)

(24%-93%)

(36%-120%)

(34%-109%)

(32%-124%)

Qual QC1203906081 435603014 REC%

36 105 64 86 85 84 81 55 61 93 115 61 77 77 83 100 50.0 250 250 250 250 250 250 250 250 250 250 250 250 500 MS 436338 Workorder:

U U

RPD%

Page 7 of 16 Page 12 of 28 HDP Subsurface Confirmatory Survey C-12 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Semi-Volatile-GC/MS 1713446 Batch 2-Fluorobiphenyl 2-Fluorophenol Nitrobenzene-d5 Phenol-d5 p-Terphenyl-d14 1,4-Dichlorobenzene 2,4,5-Trichlorophenol 2,4,6-Trichlorophenol 2,4-Dinitrotoluene Hexachlorobenzene Hexachlorobutadiene Hexachloroethane Nitrobenzene Pentachlorophenol Pyridine Parmname Units ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L Anlst Date Time JLD1 10/31/17 15:45 10/31/17 16:16 QC 179 275 224 170 224 145 213 205 203 202 129 137 216 281 141 NOM Sample 157 171 202 118 191 ND ND ND ND ND ND ND ND ND ND Range (32%-112%)

(15%-88%)

(36%-115%)

(15%-91%)

(36%-121%)

(0%-30%)

Qual QC1203906082 435603014 10 1

3 4

0 7

11 7

2 7

REC%

72 55 90 34 90 58 85 82 81 81 52 55 86 112 57 250 500 250 500 250 250 250 250 250 250 250 250 250 250 250 MSD 436338 Workorder:

U U

RPD%

Page 8 of 16 Page 13 of 28 HDP Subsurface Confirmatory Survey C-13 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Semi-Volatile-GC/MS 1713446 Batch m,p-Cresols o-Cresol 2,4,6-Tribromophenol 2-Fluorobiphenyl 2-Fluorophenol Nitrobenzene-d5 Phenol-d5 p-Terphenyl-d14 1,4-Dichlorobenzene 2,4,5-Trichlorophenol 2,4,6-Trichlorophenol 2,4-Dinitrotoluene Hexachlorobenzene Hexachlorobutadiene Hexachloroethane Parmname Units ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L Anlst Date Time JLD1 10/31/17 16:16 10/31/17 13:09 QC 165 164 408 170 220 203 141 231 ND ND ND ND ND ND ND NOM Sample ND ND 392 157 171 202 118 191 Range (0%-30%)

(0%-30%)

(32%-124%)

(32%-112%)

(15%-88%)

(36%-115%)

(15%-91%)

(36%-121%)

Qual U

U U

QC1203905603 15 16 REC%

66 66 82 68 44 81 28 93 250 250 500 250 500 250 500 250 TB 436338 Workorder:

U U

RPD%

Page 9 of 16 Page 14 of 28 HDP Subsurface Confirmatory Survey C-14 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Semi-Volatile-GC/MS Volatile-GC/MS 1713446 1717560 Batch Batch Nitrobenzene Pentachlorophenol Pyridine m,p-Cresols o-Cresol 2,4,6-Tribromophenol 2-Fluorobiphenyl 2-Fluorophenol Nitrobenzene-d5 Phenol-d5 p-Terphenyl-d14 1,1-Dichloroethylene 1,2-Dichloroethane 1,4-Dichlorobenzene Parmname Units ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L Anlst Date Time JLD1 JP1 10/31/17 13:09 11/09/17 10:53 QC ND ND ND ND ND 391 190 227 228 155 217 48.1 47.8 46.4 NOM Sample Range (32%-124%)

(32%-112%)

(15%-88%)

(36%-115%)

(15%-91%)

(36%-121%)

(66%-126%)

(74%-122%)

(71%-120%)

Qual U

U U

QC1203916313 REC%

78 76 45 91 31 87 96 96 93 500 250 500 250 500 250 50.0 50.0 50.0 LCS 436338 Workorder:

RPD%

Page 10 of 16 Page 15 of 28 HDP Subsurface Confirmatory Survey C-15 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Volatile-GC/MS 1717560 Batch 2-Butanone Benzene Carbon tetrachloride Chlorobenzene Chloroform Tetrachloroethylene Trichloroethylene Vinyl chloride 1,2-Dichloroethane-d4 Bromofluorobenzene Toluene-d8 1,1-Dichloroethylene 1,2-Dichloroethane 1,4-Dichlorobenzene 2-Butanone Parmname Units ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L Anlst Date Time JP1 11/09/17 10:53 11/09/17 13:14 QC 243 46.2 49.5 46.9 47.3 48.2 48.1 54.1 50.4 49.6 49.6 ND ND ND ND NOM Sample Range (55%-138%)

(72%-121%)

(72%-140%)

(74%-120%)

(76%-123%)

(69%-129%)

(74%-125%)

(65%-137%)

(71%-134%)

(70%-131%)

(74%-124%)

Qual U

U U

U QC1203916312 REC%

97 92 99 94 95 96 96 108 101 99 99 250 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 MB 436338 Workorder:

RPD%

Page 11 of 16 Page 16 of 28 HDP Subsurface Confirmatory Survey C-16 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Volatile-GC/MS 1717560 Batch Benzene Carbon tetrachloride Chlorobenzene Chloroform Tetrachloroethylene Trichloroethylene Vinyl chloride 1,2-Dichloroethane-d4 Bromofluorobenzene Toluene-d8 1,1-Dichloroethylene 1,2-Dichloroethane 1,4-Dichlorobenzene 2-Butanone Benzene Parmname Units ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L Anlst Date Time JP1 11/09/17 13:14 11/09/17 21:14 QC ND ND ND ND ND ND ND 50.5 49.8 48.9 41.6 47.2 33.4 172 41.1 NOM Sample ND ND ND ND ND Range (71%-134%)

(70%-131%)

(74%-124%)

(59%-130%)

(69%-130%)

(55%-125%)

(25%-143%)

(66%-125%)

Qual U

U U

QC1203916314 437257001 REC%

101 100 98 83 94 67 69 82 50.0 50.0 50.0 50.0 50.0 50.0 250 50.0 PS 436338 Workorder:

U U

U RPD%

Page 12 of 16 Page 17 of 28 HDP Subsurface Confirmatory Survey C-17 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Volatile-GC/MS 1717560 Batch Carbon tetrachloride Chlorobenzene Chloroform Tetrachloroethylene Trichloroethylene Vinyl chloride 1,2-Dichloroethane-d4 Bromofluorobenzene Toluene-d8 1,1-Dichloroethylene 1,2-Dichloroethane 1,4-Dichlorobenzene 2-Butanone Benzene Carbon tetrachloride Parmname Units ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L Anlst Date Time JP1 11/09/17 21:14 11/09/17 21:42 QC 41.4 38.2 43.9 35.4 40.1 46.3 52.2 50.5 49.5 40.4 44.8 31.7 162 39.1 39.7 NOM Sample ND ND ND ND ND ND 51.6 49.9 49.5 ND ND ND ND ND ND Range (66%-143%)

(64%-124%)

(71%-129%)

(60%-130%)

(65%-131%)

(58%-140%)

(71%-134%)

(70%-131%)

(74%-124%)

(0%-20%)

Qual QC1203916315 437257001 3

5 5

6 5

4 REC%

83 76 88 71 80 93 104 101 99 81 90 63 65 78 79 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 250 50.0 50.0 PSD 436338 Workorder:

U U

RPD%

Page 13 of 16 Page 18 of 28 HDP Subsurface Confirmatory Survey C-18 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Volatile-GC/MS 1717560 Batch Chlorobenzene Chloroform Tetrachloroethylene Trichloroethylene Vinyl chloride 1,2-Dichloroethane-d4 Bromofluorobenzene Toluene-d8 1,1-Dichloroethylene 1,2-Dichloroethane 1,4-Dichlorobenzene 2-Butanone Benzene Carbon tetrachloride Chlorobenzene Parmname Units ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L ug/L Anlst Date Time JP1 11/09/17 21:42 11/09/17 17:00 QC 35.4 42.0 32.8 37.6 45.6 50.3 49.6 49.3 ND ND ND ND ND ND ND NOM Sample ND ND ND ND ND 51.6 49.9 49.5 Range (0%-20%)

(0%-20%)

(71%-134%)

(70%-131%)

(74%-124%)

Qual U

U U

QC1203905604 8

5 8

7 2

REC%

71 84 66 75 91 101 99 99 50.0 50.0 50.0 50.0 50.0 50.0 50.0 50.0 TB 436338 Workorder:

U U

U RPD%

Page 14 of 16 Page 19 of 28 HDP Subsurface Confirmatory Survey C-19 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Volatile-GC/MS 1717560 Batch Chloroform Tetrachloroethylene Trichloroethylene Vinyl chloride 1,2-Dichloroethane-d4 Bromofluorobenzene Toluene-d8 Parmname Units ug/L ug/L ug/L ug/L ug/L ug/L ug/L Anlst Date Time JP1 11/09/17 17:00 QC ND ND ND ND 51.6 50.5 49.4 NOM Sample Range (71%-134%)

(70%-131%)

(74%-124%)

Qual U

U U

U The Qualifiers in this report are defined as follows:

REC%

103 101 99 50.0 50.0 50.0 436338 Workorder:

A B

C D

E E

FB H

J JNX N

N N

Analyte is a surrogate compound Result is less than value reported Result is greater than value reported The TIC is a suspected aldol-condensation product The target analyte was detected in the associated blank.

Analyte has been confirmed by GC/MS analysis Results are reported from a diluted aliquot of the sample

%difference of sample and SD is >10%. Sample concentration must meet flagging criteria Concentration of the target analyte exceeds the instrument calibration range Mercury was found present at quantifiable concentrations in field blanks received with these samples. Data associated with the blank are deemed invalid for reporting to regulatory agencies Analytical holding time was exceeded Value is estimated Non Calibrated Compound Metals--The Matrix spike sample recovery is not within specified control limits Organics--Presumptive evidence based on mass spectral library search to make a tentative identification of the analyte (TIC). Quantitation is based on nearest internal standard response factor Presumptive evidence based on mass spectral library search to make a tentative identification of the analyte (TIC). Quantitation is based on nearest RPD%

Notes:

Page 15 of 16 Page 20 of 28 HDP Subsurface Confirmatory Survey C-20 5184-SR-09-0

QC Summary GEL LABORATORIES LLC 2040 Savage Road Charleston, SC 29407 - (843) 556-8171 - www.gel.com Parmname Page 16 of 16 Units Anlst Date Time QC NOM Sample Range Qual REC%

436338 Workorder:

N/A N1 ND NJ P

Q R

U UJ X

Y Y

^

h internal standard response factor RPD or %Recovery limits do not apply.

See case narrative Analyte concentration is not detected above the detection limit Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Organics--The concentrations between the primary and confirmation columns/detectors is >40% different. For HPLC, the difference is >70%.

One or more quality control criteria have not been met. Refer to the applicable narrative or DER.

Sample results are rejected Analyte was analyzed for, but not detected above the MDL, MDA, MDC or LOD.

Compound cannot be extracted Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Other specific qualifiers were required to properly define the results. Consult case narrative.

QC Samples were not spiked with this compound RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL. Qualifier Not Applicable for Radiochemistry.

Preparation or preservation holding time was exceeded N/A indicates that spike recovery limits do not apply when sample concentration exceeds spike conc. by a factor of 4 or more or %RPD not applicable.

^ The Relative Percent Difference (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptance criteria when the sample is greater than five times (5X) the contract required detection limit (RL). In cases where either the sample or duplicate value is less than 5X the RL, a control limit of +/- the RL is used to evaluate the DUP result.

Indicates that a Quality Control parameter was not within specifications.

For PS, PSD, and SDILT results, the values listed are the measured amounts, not final concentrations.

Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the QC Summary.

RPD%

Page 21 of 28 HDP Subsurface Confirmatory Survey C-21 5184-SR-09-0

Technical Case Narrative ORAU (ORAU)

SDG #: 436338 GC/MS Volatile Product: Volatile Organic Compounds (VOC) by Gas Chromatograph/Mass Spectrometer Analytical Method: SW846 8260B Analytical Procedure: GL-OA-E-038 REV# 26 Analytical Batch: 1717560 TCLP Preparation Method: SW846 1311 TCLP Preparation Procedure: GL-LB-E-006 REV# 21 TCLP Preparation Batch: 1713253 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 436338001 5184S0226 1203905604 Tumble Blank (TB) 1203916312 Method Blank (MB) 1203916313 Laboratory Control Sample (LCS) 1203916314 437257001(NonSDG) Post Spike (PS) 1203916315 437257001(NonSDG) Post Spike Duplicate (PSD)

The samples in this SDG were analyzed on an "as received" basis.

Data Summary:

All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.

Technical Information Sample Dilutions/Methanol Dilutions Due to problems associated with the nature of the TCLP matrix, volatile extracts are routinely diluted before analysis. The dilution factor does not increase detection limits above the regulatory limits required by the client.

Analyte 436338 001 Several 10X GC/MS Semivolatile Product: Analysis of Semivolatile Organic Compounds by Gas Chromatography/Mass Spectrometry Analytical Method: SW846 3510C/8270D Page 22 of 28 HDP Subsurface Confirmatory Survey C-22 5184-SR-09-0

Analytical Procedure: GL-OA-E-009 REV# 39 Analytical Batch: 1713446 Preparation Method: SW846 3510C Preparation Procedure: GL-OA-E-013 REV# 32 Preparation Batch: 1713445 TCLP Preparation Method: SW846 1311 TCLP Preparation Procedure: GL-LB-E-006 REV# 21 TCLP Preparation Batch: 1713252 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 436338001 5184S0226 1203905603 Tumble Blank (TB) 1203906079 Method Blank (MB) 1203906080 Laboratory Control Sample (LCS) 1203906081 435603014(NonSDG) Matrix Spike (MS) 1203906082 435603014(NonSDG) Matrix Spike Duplicate (MSD)

The samples in this SDG were analyzed on an "as received" basis.

Data Summary:

There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable.

Metals TCLP Preparation Method: SW846 1311 TCLP Preparation Procedure: GL-LB-E-006 REV# 21 TCLP Preparation Batch: 1713251 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 436338001 5184S0226 1203905602 Tumble Blank (TB) 1203905601 436338001(5184S0226S) Matrix Spike (MS)

The samples in this SDG were analyzed on an "as received" basis.

Data Summary:

There are no exceptions, anomalies or deviations from the specified methods. All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable.

Product: Determination of Metals by ICP Page 23 of 28 HDP Subsurface Confirmatory Survey C-23 5184-SR-09-0

Analytical Method: SW846 3010A/6010C Analytical Procedure: GL-MA-E-013 REV# 30 Analytical Batch: 1713664 Preparation Method: SW846 3010A Preparation Procedure: GL-MA-E-008 REV# 19 Preparation Batch: 1713663 TCLP Preparation Method: SW846 1311 TCLP Preparation Procedure: GL-LB-E-006 REV# 21 TCLP Preparation Batch: 1713251 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification 436338001 5184S0226 1203905602 Tumble Blank (TB) 1203906603 Method Blank (MB)ICP 1203906604 Laboratory Control Sample (LCS) 1203906607 436338001(5184S0226L) Serial Dilution (SD) 1203906605 436338001(5184S0226D) Sample Duplicate (DUP) 1203905601 436338001(5184S0226S) Matrix Spike (MS)

The samples in this SDG were analyzed on an "as received" basis.

Data Summary:

All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.

Technical Information Preparation Information The samples and associated matrix QC were prepared at a ten times or greater dilution factor to minimize potential interferences arising from the high sodium content in the TCLP leaching solution.

Product: Mercury Analysis Using the Perkin Elmer Automated Mercury Analyzer Analytical Method: SW846 7470A Analytical Procedure: GL-MA-E-010 REV# 36 Analytical Batch: 1718693 Preparation Method: SW846 7470A Prep Preparation Procedure: GL-MA-E-010 REV# 36 Preparation Batch: 1718692 TCLP Preparation Method: SW846 1311 TCLP Preparation Procedure: GL-LB-E-006 REV# 21 TCLP Preparation Batch: 1713251 The following samples were analyzed using the above methods and analytical procedure(s).

GEL Sample ID# Client Sample Identification Page 24 of 28 HDP Subsurface Confirmatory Survey C-24 5184-SR-09-0

436338001 5184S0226 1203905602 Tumble Blank (TB) 1203919364 Method Blank (MB)CVAA 1203919365 Laboratory Control Sample (LCS) 1203919368 436338001(5184S0226L) Serial Dilution (SD) 1203919366 436338001(5184S0226D) Sample Duplicate (DUP) 1203905601 436338001(5184S0226S) Matrix Spike (MS)

The samples in this SDG were analyzed on an "as received" basis.

Data Summary:

All sample data provided in this report met the acceptance criteria specified in the analytical methods and procedures for initial calibration, continuing calibration, instrument controls and process controls where applicable, with the following exceptions.

Technical Information Preparation Information The samples and associated matrix QC were prepared at a ten times or greater dilution factor to minimize potential interferences arising from the high sodium content in the TCLP leaching solution.

Certification Statement Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless otherwise noted in the analytical case narrative.

Page 25 of 28 HDP Subsurface Confirmatory Survey C-25 5184-SR-09-0

Page 26 of 28 HDP Subsurface Confirmatory Survey C-26 5184-SR-09-0

Page 27 of 28 HDP Subsurface Confirmatory Survey C-27 5184-SR-09-0

State Certification Alaska Arkansas CLIA California Colorado Connecticut Delaware DoD ELAP/ ISO17025 A2LA Florida NELAP Foreign Soils Permit Georgia Georgia SDWA Hawaii Idaho Chemistry Idaho Radiochemistry Illinois NELAP Indiana Kansas NELAP Kentucky SDWA Kentucky Wastewater Louisiana NELAP Louisiana SDWA Maryland Massachusetts Michigan Mississippi Nebraska Nevada New Hampshire NELAP New Jersey NELAP New Mexico New York NELAP North Carolina North Carolina SDWA North Dakota Oklahoma Pennsylvania NELAP Puerto Rico S.Carolina Radchem South Carolina Chemistry Tennessee Texas NELAP Utah NELAP Vermont Virginia NELAP Washington West Virginia UST0110 880651 42D0904046 2940 SC00012 PH0169 SC00012 2567.01 E87156 P3301500283, P3301500253 SC00012 967 SC00012 SC00012 SC00012 200029 CSC01 E10332 90129 90129 03046 (AI33904)

LA170010 270 MSC012 9976 SC00012 NEOS2613 SC0001220181 205415 SC002 SC00012 11501 233 45709 R158 9904 6800485 SC00012 10120002 10120001 TN 02934 T1047042351712 SC00012201724 VT87156 460202 C780 997404 List of current GEL Certifications as of 15 November 2017 Page 28 of 28 HDP Subsurface Confirmatory Survey C-28 5184-SR-09-0

HDP Subsurface Confirmatory Survey 5184-SR-09-0 APPENDIX D MAJOR INSTRUMENTATION

HDP Subsurface Confirmatory Survey D-1 5184-SR-09-0 The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the author or his employer.

D.1 SCANNING AND MEASUREMENT INSTRUMENT/DETECTOR COMBINATIONS D.1.1 GAMMA Ludlum NaI Scintillation Detector Model 44-10, Crystal: 5.1 cm x 5.1 cm (Ludlum Measurements, Inc., Sweetwater, Texas) coupled to:

Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, Texas) coupled to:

Trimble Geo 7X (Trimble Navigation Limited, Sunnyvale, California)

Ludlum CsI Scintillation Detector Model 44-159-1, Crystal: 18 mm x 18 mm (Ludlum Measurements, Inc., Sweetwater, Texas) coupled to:

Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, Texas) coupled to:

Trimble Geo 7X (Trimble Navigation Limited, Sunnyvale, California)

D.1.2 BETA Ludlum Plastic Scintillation Detector Model 44-142 (Ludlum Measurements, Inc., Sweetwater, Texas) coupled to:

Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, Texas)

D.2 LABORATORY ANALYTICAL INSTRUMENTATION High-Purity, Extended Range Intrinsic Detector CANBERRA/Tennelec Model No: ERVDS30-25195 (Canberra, Meriden, Connecticut)

Used in conjunction with:

Lead Shield Model G-11 (Nuclear Lead, Oak Ridge, Tennessee) and Multichannel Analyzer Canberras Gamma Software Dell Workstation (Canberra, Meriden, Connecticut)

High-Purity, Intrinsic Detector Model No. GMX-45200-5 CANBERRA Model No: GC4020

HDP Subsurface Confirmatory Survey D-2 5184-SR-09-0 (Canberra, Meriden, Connecticut)

Used in conjunction with:

Lead Shield Model G-11 Lead Shield Model SPG-16-K8 (Nuclear Data)

Multichannel Analyzer Canberras Gamma Software Dell Workstation (Canberra, Meriden, Connecticut)

Tri-Carb Liquid Scintillation Analyzer Model 3100 (Packard Instrument Co., Meriden, Connecticut)

HDP Subsurface Confirmatory Survey 5184-SR-09-0 APPENDIX E SURVEY AND ANALYTICAL PROCEDURES

HDP Subsurface Confirmatory Survey E-1 5184-SR-09-0 E.1 PROJECT HEALTH AND SAFETY ORISE performed all survey activities in accordance with the ORAU Health and Safety Manual, the ORAU Radiation Protection Manual, and the ORAU Radiological and Environmental Survey Procedures Manual (ORAU 2016c, ORAU 2014, and ORAU 2016a). Prior to on-site activities, a work-specific hazard checklist was completed for the project and discussed with field personnel. The planned activities were thoroughly discussed with site personnel prior to implementation to identify hazards present. Additionally, prior to performing work, a pre-job briefing and walk-down of the survey areas were completed with field personnel to identify hazards present and discuss safety concerns.

Should ORISE have identified a hazard not covered in the ORAU Radiological and Environmental Survey Procedures Manual (ORAU 2016a)or the projects work-specific hazard checklist for the planned survey and sampling procedures, work would not have been initiated or continued until it was addressed by an appropriate job hazard analysis and hazard controls.

E.2 CALIBRATION AND QUALITY ASSURANCE Calibration of all field instrumentation was based on standards/sources, traceable to National Institute of Standards and Technology (NIST).

Field survey activities were conducted in accordance with procedures from the following ORAU documents:

ORAU Radiological and Environmental Survey Procedures Manual (ORAU 2016a)

ORAU Environmental Services and Radiation Training Quality Program Manual (ORAU 2016b)

ORAU Radiological and Environmental Analytical Laboratory Procedures Manual (ORAU 2017)

The procedures contained in these manuals were developed to meet the requirements of the U.S. Department of Energy (DOE) Order 414.1D and the U.S. Nuclear Regulatory Commission Quality Assurance Manual for the Office of Nuclear Material Safety and Safeguards and contain measures to assess processes during their performance.

Quality control procedures include:

Daily instrument background and check-source measurements to confirm that equipment operation is within acceptable statistical fluctuations.

HDP Subsurface Confirmatory Survey E-2 5184-SR-09-0

Participation in Mixed-Analyte Performance Evaluation Program, NIST Radiochemistry Intercomparison Program, and DOE Radiological and Environmental Science Laboratory Intercomparison Test Program.

Training and certification of all individuals performing procedures.

Periodic internal and external audits.

E.3 SURVEY PROCEDURES E.3.1 SAMPLE CORE SCANS Scans for elevated radiation were performed by passing the detector slowly over the surface of the core sample. A Ludlum Model 44-10 NaI detector was used for gamma radiation and a Ludlum Model 44-142 plastic scintillator was used for beta radiation. The detectors were used as a qualitative means to identify elevated radiation levels in excess of background identified by an increase in the audible signal from the indicating instrument.

E.3.2 BOREHOLE LOGGING Scans for elevated gamma radiation were performed by passing Ludlum Model 44-10 NaI and Ludlum Model 44-159-1 CsI detectors slowly down the borehole. The detectors were used as a qualitative means to identify elevated radiation levels in excess of background. Identification of elevated radiation levels that could exceed the site criteria were determined based on an increase in the audible signal and evaluation of subsequent logged data.

Histograms were generated by dividing logged detector data into a series of intervals (bins) and plotting it against the number of results falling within each bin (frequency). Histograms were then evaluated to determine the frequency distribution of results and to identify the presence of any outliers indicative of contamination. A symmetrically shaped histogram represents a normal distribution indicative of background conditions.

Scan sensitivity of the CsI detector was evaluated using an adapted method of that presented in NUREG-1507 (NRC 1998). MicroShield, version 7.03, was used to determine the exposure rate from the assumed contamination geometry. The source term was modeled as an annular cylinder with diameter of 40.6 cm and a height of 30.5 cm, the inner annulus had a diameter of 5.08 cm, representing the borehole. Exposure rate-to-concentration ratios (in units of R/hr per pCi/g) were

HDP Subsurface Confirmatory Survey E-3 5184-SR-09-0 generated for each of the gamma-emitting ROCs, including short-lived decay products. Exposure rates were evaluated at the center of the annulus. The source material was assumed to be concrete as MicroShield does not have a soil matrixwith a density of 1.3 g/cm3. Net instrument responses due to individual ROC concentrations equal to their respective DCGLW were calculated using the exposure rate-to-concentration ratios. Scan MDCs were calculated based on the minimum detectable exposure rate from a surveyor with an efficiency of 0.5 (NUREG-1507 default). Both the net instrument response due to an ROC concentration at the DCGLW and down-hole scan MDCs are presented in Table E.1 below.

Table E.1. Borehole Scan Sensitivity for the CsI Detector ROC R/hra R/hr/

pCi/g R/hr at DCGL net cpm at DCGLw cpm/

R/hr Scan MDC (pCi/g) 3% EU 5.32E-01 1.75E-02 2.97 2,350 791 125 20% EU 3.98E-01 1.31E-02 2.25 2,181 969 136 Th-232 1.83E+02 6.00E+00 18.01 1,858 103 2.8 Ra-226 1.23E+02 4.04E+00 11.31 1,189 105 4.1 Scan MDC Inputs Bkg 2,300 cpm d'

3.28 i

1 s

MDCR 1218 cpm bi 38.3 cpm MDCRsurveyor 1723 cpm a Calculated from Microshield based on an annular cylinder geometry and a ROC concentration of 30.5 pCi/g E.3.3 SOIL SAMPLING Soil sampling was facilitated using DPT equipment with a dual-tube core collection system. The system consisted of an outer rod (stainless steel casing) and smaller diameter inner rod housing the plastic sample collection liner approximately 1.5 meters in length. Rods were advanced vertically into the soil in 1.5-meter (5-foot) increments. The soil core was then extracted and a new liner inserted into the casing to collect the next incremental soil core. After each incremental core was collected, the sample tube was delivered to ORISE personnel for scanning and sample collection. Soil samples representative of the backfill/native soil interface were collected in equal portions from the 15-centimeter interval above and below the interface, using a clean garden trowel and transferred into a new sample container. In addition, a single composite sample was collected per borehole

HDP Subsurface Confirmatory Survey E-4 5184-SR-09-0 consisting of equal volume aliquots taken from each incremental core. The samples were not field sieved and were delivered to the laboratory as collected.

E.4 RADIOLOGICAL ANALYSIS E.4.1 GAMMA SPECTROSCOPY Samples were dried, mixed, crushed, and/or homogenized as necessary, and a portion sealed in a 0.5-liter Marinelli beaker. The quantity placed in the beaker was chosen to reproduce the calibrated counting geometry. Net material weights were determined and the samples counted using intrinsic, high purity, germanium detectors coupled to a pulse height analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system. All total absorption peaks (TAPs) associated with the ROCs were reviewed for consistency of activity. Spectra were also reviewed for other identifiable TAPs. TAPs used for determining the activities of ROCs and the typical associated MDCs for a one-hour count time are presented in Table E.2.

Table E.2. Typical MDCs Radionuclidea TAP (keVb)

MDC (pCi/g)

U-235 143.76 0.24 U-238 by Th-234 63.29 0.75 Th-232 by Ac-228 911.20 0.12 Ra-226 by Pb-214 351.92b 0.24 a Spectra were also reviewed for other identifiable TAPs.

b kilo electron volt E.4.2 TC-99 ANALYSIS Technetium-99 was analyzed by using the Oak Ridge Radiological and Environmental Analytical Laboratory procedures AP5 and CP4. The samples were processed such that any technetium was converted into the pertechnatate anion. The pertechnatate anion was selectively absorbed on a chromatographic resin. Interfering elements were not retained under the correct conditions. The resin was counted with an appropriate liquid scintillation counting cocktail. The typical MDC for this procedure was 0.28 pCi/g.

HDP Subsurface Confirmatory Survey E-5 5184-SR-09-0 E.4.3 DETECTION LIMITS Detection limits, referred to as MDCs, were based on 95% confidence level. Because of variations in background levels, measurement efficiencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument.

E.4.4 U-234 CALCULATION The U-234 concentration was calculated by using the method specified in WEC 2013. First, the U-238 to U-235 ratio was calculated. The corresponding U-234 to U-235 ratio, determined using Table 14-5 in Chapter 14 of the HDP DP, was multiplied by the U-235 concentration to yield the U-234 concentration. If the U-238 to U-235 ratio was not specified in Table 14-5, the U-234 to U-235 value was linearly interpolated. If the U-235 value was negative, a U-234 to U-235 ratio of 21.07 was assumedthe ratio for natural uranium. The uncertainty for the calculated U-234 value was propagated assuming the U-234 to U-235 ratio had no uncertainty. The uranium enrichment was determined based on the U-238 to U-235 ratio in the same manner as the U-234 to U-235 ratio.

Table E.3, presented below, details the calculation of U-234.

Table E.3. U-234 Calculation Sample ID U-235 (pCi/g)

U-238 (pCi/g)

U-238/

U-235 U-234/

U-235 Enrichment

(%)

U-234 (pCi/g) 5184S0184 0.09

+/-

0.1 1.5

+/-

0.54 16.67 20.09 0.9 1.81

+/-

2.01 5184S0186 0.14

+/-

0.14 1.91

+/-

0.77 13.64 19.54 1.1 2.74

+/-

2.74 5184S0188 0.05

+/-

0.1 2.01

+/-

0.62 40.20 24.47 0.3 1.22

+/-

2.45 5184S0190 0.4

+/-

0.13 2.4

+/-

0.77 6.00 18.31 2.5 7.32

+/-

2.38 5184S0192 0.39

+/-

0.17 1.8

+/-

1.1 4.62 18.16 3.2 7.08

+/-

3.09 5184S0194 0.49

+/-

0.12 2.1

+/-

1.1 4.29 18.14 3.5 8.89

+/-

2.18 5184S0196 0.221

+/-

0.1 1.92

+/-

0.55 8.69 18.70 1.7 4.13

+/-

1.87 5184S0198 0.15

+/-

0.12 1.63

+/-

0.65 10.87 19.06 1.4 2.86

+/-

2.29 5184S0200 0.24

+/-

0.13 2.03

+/-

0.99 8.46 18.67 1.8 4.48

+/-

2.43 5184S0202 0.246

+/-

0.07 2.03

+/-

0.59 8.25 18.63 1.8 4.58

+/-

1.30 5184S0204 0.051

+/-

0.089 1.54

+/-

0.51 30.20 22.59 0.5 1.15

+/-

2.01 5184S0206 0.18

+/-

0.14 1.2

+/-

1.1 6.67 18.40 2.2 3.31

+/-

2.58 5184S0208 0.046

+/-

0.078 1.23

+/-

0.41 26.74 21.94 0.5 1.01

+/-

1.71 5184S0210 0.117

+/-

0.095 1.31

+/-

0.51 11.20 19.11 1.3 2.24

+/-

1.82 5184S0212 0.01

+/-

0.15 1.09

+/-

0.92 109.00 37.51 0.1 0.38

+/-

5.63 5184S0214 0.069

+/-

0.098 1.87

+/-

0.55 27.10 22.01 0.5 1.52

+/-

2.16 5184S0216 0.06

+/-

0.13 1.44

+/-

0.62 24.00 21.43 0.6 1.29

+/-

2.79 5184S0218 0.2

+/-

0.16 1.49

+/-

0.94 7.45 18.51 2

3.70

+/-

2.96

HDP Subsurface Confirmatory Survey E-6 5184-SR-09-0 Table E.3. U-234 Calculation Sample ID U-235 (pCi/g)

U-238 (pCi/g)

U-238/

U-235 U-234/

U-235 Enrichment

(%)

U-234 (pCi/g) 5184S0220 0.065

+/-

0.087 1.34

+/-

0.46 20.62 20.81 0.72 1.35

+/-

1.81 5184S0222 0.11

+/-

0.1 1.56

+/-

0.68 14.18 19.64 1

2.16

+/-

1.96 5184S0224 0.06

+/-

0.16 2

+/-

1 33.33 23.18 0.4 1.39

+/-

3.71 5184S0225 0.11

+/-

0.13 1.57

+/-

0.64 14.27 19.65 1

2.16

+/-

2.55 5184S0183 0.21

+/-

0.13 1.88

+/-

0.64 8.95 18.74 1.7 3.94

+/-

2.44 5184S0185 0.18

+/-

0.18 1.9

+/-

1.1 10.56 19.01 1.4 3.42

+/-

3.42 5184S0187 0.03

+/-

0.096 1.05

+/-

0.53 35.00 23.49 0.4 0.70

+/-

2.26 5184S0189 0.18

+/-

0.17 2.6

+/-

1.1 14.44 19.68 1

3.54

+/-

3.35 5184S0191 0.1

+/-

0.1 1.72

+/-

0.56 17.20 20.18 0.8 2.02

+/-

2.02 5184S0193 0.2

+/-

0.11 2.22

+/-

0.63 11.10 19.10 1.3 3.82

+/-

2.10 5184S0195 0.08

+/-

0.14 2.33

+/-

0.78 29.13 22.39 0.5 1.79

+/-

3.13 5184S0197 0.23

+/-

0.17 1.7

+/-

1.3 7.39 18.50 2

4.25

+/-

3.14 5184S0199 0.167

+/-

0.095 1.56

+/-

0.52 9.34 18.81 1.6 3.14

+/-

1.79 5184S0201 0.29

+/-

0.13 2.19

+/-

0.69 7.55 18.52 2

5.37

+/-

2.41 5184S0203 0.08

+/-

0.11 1.43

+/-

0.46 17.88 20.31 0.8 1.62

+/-

2.23 5184S0205 0.17

+/-

0.16 1.06

+/-

0.9 6.24 18.34 2.4 3.12

+/-

2.93 5184S0207 0.09

+/-

0.1 1.55

+/-

0.53 17.22 20.19 0.8 1.82

+/-

2.02 5184S0209 0.13

+/-

0.13 1.43

+/-

0.92 11.00 19.08 1.3 2.48

+/-

2.48 5184S0211 0.119

+/-

0.093 1.76

+/-

0.51 14.79 19.74 1

2.35

+/-

1.84 5184S0213 0.08

+/-

0.1 1.35

+/-

0.58 16.88 20.13 0.9 1.61

+/-

2.01 5184S0215 0.14

+/-

0.17 2.0

+/-

1.1 14.29 19.65 1

2.75

+/-

3.34 5184S0217 0.079

+/-

0.095 1.51

+/-

0.48 19.11 20.53 0.8 1.62

+/-

1.95 5184S0219 0.07

+/-

0.11 2.2

+/-

0.73 31.43 22.82 0.4 1.60

+/-

2.51 5184S0221 0.07

+/-

0.14 1.21

+/-

0.91 17.29 20.20 0.8 1.41

+/-

2.83 5184S0223 0.047

+/-

0.085 1.18

+/-

0.41 25.11 21.64 0.6 1.02

+/-

2.83 5184S0226 0.09

+/-

0.09 1.58

+/-

0.48 17.56 20.25 0.8 1.82

+/-

1.82

ML18024A876

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