re: draft supplemental removal site evaluation report ... · mwh is pleased to submit the enclosed...

1475 Pine Grove Road TEL 970-879-6260 Suite 109 FAX 970-879-9048 Steamboat Springs, CO 80487 www.mwhglobal.com

February 29, 2008

(Via E-Mail PDF)

Andrew Bain Remedial Project Manager, Superfund Program US EPA, Region 9 75 Hawthorne St. (SFD-8-2) 9th Fl. San Francisco, CA 94105 RE: Draft Supplemental Removal Site Evaluation Report Northeast Church Rock Mine Site Dear Mr. Bain, MWH is pleased to submit the enclosed Draft Supplemental Removal Site Evaluation Report for the Northeast Church Rock Mine Site in Church Rock, New Mexico. The report is being submitted on behalf of United Nuclear Corporation (UNC) in fulfillment of the Administrative Settlement Agreement and Order on Consent for Removal Site Evaluation, U.S. EPA Region 9 (EPA), CERCLA Docket No. 2006-28, dated September 27, 2006. The report was prepared in accordance with the Removal Site Evaluation Work Plan (MWH, 2006), and the Supplemental Removal Site Evaluation Work Plan, dated October 12, 2007 If you have any questions about this report, please do not hesitate to call me at (970) 879-6260 or Lance Hauer at (610) 992-7972. Sincerely, MWH Americas, Inc.

Toby Leeson Supervisory Hydrogeologist cc: Lance Hauer, General Electric Larry Bush, United Nuclear Corporation Arlene Luther, Navajo Nation Environmental Protection Agency Dave Taylor, Navajo Nation Department of Justice Project File

SDMS DOCID# 1128460

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Prepared for:

UNITED NUCLEAR CORPORATION P.O. Box 3077

Gallup, NM 87305

DRAFT

SUPPLEMENTAL REMOVAL SITE EVALUATION REPORT NORTHEAST CHURCH ROCK MINE SITE

February 29, 2008

Prepared by:

MWH 1475 Pine Grove Road

P.O. Box 774018 Steamboat Springs, Colorado 80477

(970) 879-6260

005376

February 2008 Northeast Church Rock * Supplemental Removal Site Evaluation Report ♦ TOC-i

MWH * 1475 Pine Grove Road, Suite 109 * Steamboat Springs, Colorado 80477 * (970) 879-6260

J:\1004747 UNC NE Church Rock\Documents\Reports & Tech Memos\Supplemental RSE Report 2/29/08 rtl

TABLE OF CONTENTS

Section No. Page No.

1.0 INTRODUCTION............................................................................................................................ 1 2.0 FIELD INVESTIGATION METHODS......................................................................................... 2

2.1 GAMMA SURVEY........................................................................................................................... 2 2.2 SURFACE SOIL SAMPLING AND ANALYSIS ............................................................................ 3

3.0 FINDINGS AND DISCUSSION ..................................................................................................... 4

3.1 GAMMA SURVEY RESULTS......................................................................................................... 4 3.2 SURFACE SOIL ANALYTICAL RESULTS................................................................................... 6

4.0 SUMMARY AND CONCLUSIONS............................................................................................... 7 5.0 REFERENCES................................................................................................................................. 9

LIST OF TABLES Table No. Description

3.1 Summary of Gamma Survey Results 3.2 Summary of Surface Soil Analytical Results

LIST OF FIGURES

Figure No. Description

1-1 Site Layout 2-1 Static Gamma Radiation Measurment Locations 2-2 Surface Soil Sample Locations 3-1 Results of Field Gamma Radiation Survey 3-2 Surface Soil Analytical Results

LIST OF APPENDICES

Appendix No. Description

A Gamma Survey Calibration Data, Survey Field Forms, and Regression Analysis

B Laboratory Anaytical Reports and Data Validation Results C Supplemental Removal Site Evaluation Analytical Results

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February 2008 Northeast Church Rock * Supplemental Removal Site Evaluation Report ♦ Page 1



1.0 INTRODUCTION This report presents the results of a Supplemental Removal Site Evaluation (SRSE) for the Northeast Church Rock Mine Site in Church Rock, New Mexico (the Site). The purpose of the SRSE was to further delineate the Field Screening Level (FSL) boundary at the margins of, and step-out areas, in three areas of the Site, as listed below. All investigation activities presented in this report were conducted in accordance with the RSE Work Plan (MWH, 2006). This SRSE was conducted in response to Environmental Protection Agency, Region 9 (EPA) comments dated August 17, 2007 on the Draft Removal Site Evaluation Report (MWH, 2007a) and in accordance with the Supplemental Removal Site Evaluation Work Plan (MWH, 2007b). Refer to the RSE Work Plan for details about the site, as well as the purpose and data quality objectives (DQOs) of the RSE. The EPA General Comment #1 (see comment letter from EPA, dated August 17, 2007) that addressed the need for a supplemental investigation stated:

During RSE fieldwork, EPA agreed with MWH’s biased survey to the grid and step-out protocol as a screening approach. Vent Holes 3/8, the Trailer Park, the parking area and the areas surrounding the residences were not delineated for extent of contamination. The northern boundary of NECR-1 has not been clearly defined. Given the RSE findings, additional assessment is required in these areas and should follow the same protocol as the other survey areas.

Therefore, the objective of the SRSE was to delineate the lateral extent of impacts based on the FSL boundary, in accordance with the RSE Work Plan in areas at the margins of and surrounding the following three survey areas, which are shown on Figure 1-1, Site Layout:

1) North of NECR-1 2) Trailer Park 3) Vents 3 and 8

The Parking Area is not included in this supplemental RSE because it was included in the RSE conducted in 2006, and the area north of the parking lot is addressed by the North of NECR-1 survey area. This can be seen by comparing Figures 1-2 and 3-1 of the Removal Site Evaluation Report (MWH, 2006). The SRSE used two investigation methods: static gamma radiation measurements and surface soil sampling, as described in Section 2.0. The DQOs for the SRSE were consistent with those for the Class 1 areas presented in Section 3.0 of the RSE Work Plan. Both the RSE and Supplemental RSE were conducted in accordance with the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM, EPA, 2000). Details on the DQOs can be found in the RSE Work Plan.

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2.0 FIELD INVESTIGATION METHODS

2.1 GAMMA SURVEY The gamma survey consisted of static direct gamma radiation level measurements (gamma survey). This gamma survey method provides the aerial distribution of Ra-226 concentrations in the top six-inches of the soil column and allows greater characterization of the areas compared to relying on surface soil sampling alone. The survey was conducted as described in Section 5.3.3 of the RSE Work Plan and is consistent with the flow diagram for selection of field survey instrumentation for direct measurements presented in Figure 4.2 of MARSSIM. The gamma survey measurements were collected at 80-foot triangular grid nodes cast on a random origin in accordance with MARSSIM, using the same protocol as the other survey areas specified in the RSE Work Plan. The locations of the gamma survey points are shown on Figure 2-1, Static Gamma Measurement Locations. The spatial extent of the grid extended beyond the initial survey area boundaries to assist with boundary delineation. The sample nodes were determined using Visual Sampling Plan (VSP), as explained in the RSE Work Plan. At Vents 3 and 8, and the Trailer Park where gamma surveying was previously conducted during the RSE, the supplemental gamma points that were less then 80 feet from the previous survey points were eliminated to prevent duplicate survey points. The gamma survey was continued laterally at Vents 3 and 8 until levels indicative of less than the FSL were encountered. In the area north of NECR-1, the gamma survey was extended west to the unnamed arroyo, north to the second unnamed arroyo that runs east-west, and east to the side of Red Water Pond Road. The areas around the home sites where EPA conducted removal actions were excluded from the gamma survey, as shown on Figure 2-1, based on EPA’s confirmation sample results. The gamma radiation level measurements consisted of one-minute static (stationary) gamma radiation counts per minute (CPM), with a 0.5-inch lead collimated Eberline SPA-3 2x2 NaI scintillation detector (SR#408522-33) and Ludlum 2221 Scaler/Ratemeter (SR#68782). Details of the instrumentation configuration and Standard Operating Procedures (SOPs) are described in the RSE Work Plan. Calibration of instrumentation, including the minimum detectable concentration (MDC) calculation, used during the SRSE gamma survey was performed in accordance with SOP-1 (MWH, 2006). Gamma survey and appropriate instrumentation function checks were performed in accordance with the SOP-3 (MWH, 2006). The one-minute static measurement survey MDC was calculated to be 0.61 pCi/g, similar to the 0.6 pCi/g MDC specified in the RSEWP, for the collimated detector using the background counts at the Site during the SRSE. Calibration documents and function check logs for instrumentation used during the SRSE are provided in Appendix A, Gamma Survey Calibration Data, Survey Field Forms, and Regression Analysis. The survey information, which included the point number and one minute gamma radiation counts, was logged with a TDS Ranger data logger. The data logger automatically logged the corresponding date, time and the actual survey point location coordinates with real-time differential correction. The survey date, the survey point ID, coordinates, and the gamma radiation readings in CPM, with any comment, were recorded in the Static Gamma Radiation Survey Field Forms, which are included in Appendix A. The static gamma results were converted to Ra-226 concentrations from the gamma survey results by developing a correlation using regression analysis between the supplemental gamma survey results and co-located surface soil samples analyzed for Ra-226. The previous regression equation for the step-out areas was not used to determine equivalent Ra-226 concentrations since the instrumentation used during the SRSE was re-calibrated. The Ra-226 equivalent concentrations presented later in this

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report are based on the applicable regression equations from the RSE and SRSE (i.e., equivalent Ra-226 concentrations from the RSE were not recalculated based on the SRSE regression equation.

2.2 SURFACE SOIL SAMPLING AND ANALYSIS Surface soil sampling was also conducted in the three survey areas included in the SRSE. Surface soil samples were collected at approximately 20 percent of the gamma survey points and collected manually as grab samples from 0 to 0.5 feet below ground surface (bgs), as per the RSE Work Plan (MWH, 2006). The locations of the surface soil samples are shown on Figure 2-2, Surface Soil Sample Locations. Any sample locations that were less than 80 feet from soil samples collected previously during the RSE were eliminated. Furthermore, soil sampling was not conducted in the areas around the home sites where the EPA conducted removal actions, as shown on Figure 2-2, based on EPA’s confirmation sample results. The samples were submitted to Energy Laboratories, Inc. and analyzed for:

• Radium-226 by EPA Method 901.1; and • Total uranium by EPA Method 6020/200.8.

The analyses were conducted in accordance with the Quality Assurance Project Plan (QAPP) presented in the RSE Work Plan (MWH, 2006). The data were verified and validated as per the QAPP, and underwent Level III (90%) and Level IV (10%) data validation.

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3.0 FINDINGS AND DISCUSSION

3.1 GAMMA SURVEY RESULTS This section presents the results of the gamma survey performed during the SRSE. A total of 379 static gamma radiation level measurements were performed between November 5 and 14, 2007 at Vent Holes 3 and 8, the Trailer Park, and the North of NECR-1 area. During the SRSE, 110 supplemental static gamma radiation level measurements were performed at Vent Holes 3 and 8 to assure that, with the 35 static gamma radiation level measurements performed during the RSE, a static gamma radiation measurement was performed at all 80-foot triangular grid nodes in the area, including in the step-out areas sufficient to delineate the FSL boundary. Likewise, 74 supplemental static gamma radiation level measurements were performed at the Trailer Park to assure that, with the 39 static gamma radiation level measurements performed in during the RSE, a static gamma radiation measurement was performed at all 80-foot triangular grid nodes in the area sufficient to delineate the FSL boundary. The supplemental gamma radiation surveys were extended to boundary delineation based on the criteria discussed in Section 2.2.4.1 of the RSE report (MWH, 2007a). At Vents 3 and 8 the survey extended to boundary delineation based on readings below the FSL. At the Trailer Park, the survey extended to boundary delineation as follows:

• To the road and boundary of NECR-1 to the north; • To the boundary of NECR-1 and Sandfill 1 to the west and southwest; and • To south and east until the readings were below the FSL.

The SRSE also included 195 static gamma radiation level measurements in the area north of NECR-1 to supplement the 149 step-out static gamma radiation measurements performed during the RSE. Pursuant to the agreed-upon SRSE work plan, the supplemental gamma radiation survey at NECR-1 extended to boundary delineation as follows:

• North to the east-west trending arroyo; • To the unnamed arroyo to the west; and • To one row of measurements immediately east of Red Water Pond Road.

In the areas where the gamma survey was discontinued based on the FSL, the gamma radiation counts (CPM) were used in the field based on the correlation made during the RSE, since the SRSE correlation could not be made until all the SRSE laboratory analyses were completed. As described below, the correlation was made after the field work was completed, and the results of the new regression equation resulted in a slight increase in equivalent Ra-226 concentrations compared to the RSE regression equation. As a result of this, there are two areas at the Trailer Park where the outermost survey points revealed equivalent Ra-226 concentrations that are slightly above the FSL of 2.24 pCi/g based on the revised regression equation. These areas are at the southern end and along the eastern boundary of the Trailer Park area. The area to the south is adjacent to Sandfill 1, which was surveyed during the RSE, and so additional measurements would not be warranted. The area on the eastern boundary is adjacent to a heavily wooded area with native soils and the equivalent Ra-226 concentrations were just above the FSL and so are sufficient to draw an approximate FSL boundary. A linear regression analysis was performed once the laboratory analytical data were completed to develop a correlation between gamma radiation levels and Ra-226 surface soil concentrations. A total of 379 static gamma radiation level measurements were performed during the SRSE. As discussed above, surface soil samples were collected at 63 of the static gamma radiation survey points and

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analyzed for Ra-226. Since the instruments were recalibrated after the RSE, only gamma radiation levels and surface soil sampling results for Ra-226 concentrations from these 63 locations were used to perform a linear regression analysis. Soil sampling results and gamma radiation levels from the RSE were not used for correlation of the SRSE gamma results. Gamma radiation levels and surface soil Ra-226 concentrations collected for the regression analysis at these 63 locations are included in Appendix. Review of the Ra-226 soil sampling results indicated that Ra-226 concentrations at five locations (Home-438, Home-454, Vent-404, Vent-414 and TP-426) were inconsistent with the gamma radiation levels, and appeared to be outliers, as shown in Appendix A. Ra-226 concentrations at some of these five locations were also inconsistent with total uranium concentrations, also shown in Appendix A. These data were not qualified or rejected based on the data validation, but were omitted from the regression analysis as outliers; inclusion of these data points would have reduced the R2 value of the regression analysis to 0.14, below the minimum specified value of 0.8, and would have reduced the Ra-226 concentrations estimated from the correlation to the gamma survey reported in Appendix C. The regression analysis is presented in Appendix A, which shows an R2 value of 0.9259, exceeding the minimum specified value of 0.8. This yields the following regression equation:

Ra-226 pCi/g = (0.0013 x gamma radiation level, CPM) – 4.5378 As discussed in the RSE report (MWH, 2007a), the gamma radiation survey data using this type of correlation provides data of a quality sufficient for field screening. Data collected with field instruments have the potential for error and low accuracy and are considered to be an estimated value, especially in areas with different contaminant distributions than the instrument calibration/correlation assumptions. All static gamma radiation levels in CPM from the SRSE were converted to surface soil Ra-226 concentrations using the above equation; inclusion of the omitted soil sampling values would have resulted in lower Ra-226 concentrations estimated from the correlation to the gamma survey. The results of the static gamma radiation survey are presented in Table 3.1, Summary of Gamma Survey Results, and on Figure 3-1, Results of Field Gamma Radiation Survey. Figure 3-1 includes both the RSE and SRSE surface soil analytical results. The gamma survey results in equivalent Ra-226 concentrations were as follows:

• North of NECR-1 – 195 measurements were made in the area. Concentrations ranged from <0.5 to 29.9 pCi/g (average 4.1 pCi/g); 122 measurements (63%) exceeded the FSL.

• Trailer Park – 74 measurements were made in the area. Concentrations ranged from 1.3 to

51.5 pCi/g (average 6.5 pCi/g); 60 measurements (81%) exceeded the FSL. • Vents 3 and 8 – 110 measurements were made in the area. Concentrations ranged from <0.5

to 51.8 pCi/g (average 2.2 pCi/g); 22 measurements (20%) exceeded the FSL.

These results are consistent with the results of the RSE. As shown on Figure 3-1, the FSL boundary changed only slightly at Vents 3 and 8 and the Trailer Park compared to that shown in the RSE report (MWH, 2007). In the North of NECR-1 area, the FSL boundary was expanded around the home sites and shows that areas between the EPA Removal Action areas contain Ra-226 concentrations in excess of the FSL, [although generally below the UMTRCA unrestricted use level from 40 CFR Part 192]. Additionally, 100% of the gamma radiation measurements performed adjacent to the east and west sides of Red Water Pond Road exceeded the FSL. The measurements adjacent to Red Water Pond Road may be associated with the former use of this road as a haul road for former mines located to the North of the NECR site. Additionally, as discussed in the RSE report, the area north

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of NECR-1 was part of the Kerr McGee (Quivera Mining Company) mine permit area. In 1990, the Department of Interior, Bureau of Land Management (BLM) issued Quivera Mining Company a conditional approval letter of their Abandonment and Reclamation Plan for the Quivera Mine (BLM, 1990). One of the conditions imposed by the BLM was that the Quivera Mine surface be cleaned up so that gamma radiation as measured one meter above the ground surface does not exceed 50 µR/hr above background at roadways, fence lines, vent holes protore storage areas, and mine ponds and 57 µR/hr at mine spoils areas above background (see Abandonment and Reclamation Plan, Quivera, 1987). Values of 50 µR/hr and 57 µR/hr are approximately equivalent to 23.7 pCi/g and 27 pCi/g, respectively, as discussed in Section 2.5 of the RSE Report.

3.2 SURFACE SOIL ANALYTICAL RESULTS Surface soil samples (≤0.5 feet bgs) were collected from each of the three survey areas, and analyzed for Ra-226 and total uranium, as explained in Section 2.2. The locations of each of the surface soil sample locations are shown on Figures 2-2, and the analytical results are shown on Figure 3-2, Surface Soil Analytical Results. Figure 3-2 includes both the RSE and SRSE surface soil analytical results. The analytical results are tabulated in Table 3.2, Summary of Surface Soil Analytical Results. The laboratory analytical reports and the results of the data validation are included in Appendix B, Laboratory Analytical Data and Data Validation Results. Additionally, the analytical laboratory report is included in Appendix C, Supplemental Removal Site Evaluation Analytical Results. The results of the Ra-226 analyses were as follows:

• North of NECR-1 - 41 samples were collected from the area, five of which were split samples. Concentrations ranged from 0.7 to 28.5 pCi/g (average 4.7 pCi/g); 20 out of 36 primary samples (55%) exceeded the FSL.

• Vents 3 and 8 - 10 samples were collected, one of which was a split sample. Concentrations

ranged from 0.9 to 8.9 pCi/g (average 2.9 pCi/g); five of the nine primary samples (55%) exceeded the FSL.

• Trailer Park - 19 samples were collected, one of which was a split sample. Concentrations

ranged from 0.3 to 3.1 pCi/g (average 1.3 pCi/g); two of the 19 primary samples (10%) exceeded the FSL.

None of the data were qualified or rejected based on the data validation (see Appendix B). These results were used to confirm and modify the FSL boundary determined using the static gamma survey results, as shown on Figures 3-1 and 3-2, and discussed in Section 3.1. As shown on Figure 3-2, the FSL boundary changed only slightly at Vents 3 and 8 and the Trailer Park compared to that shown in the RSE report (MWH, 2007). In the area north of NECR-1, the FSL boundary was expanded around the home sites and shows that areas between the EPA Removal Action areas contain Ra-226 in excess of the FSL [although generally below the UMTRCA unrestricted use level at 40 CFR Part 192]. Additionally, all results from soil samples collected adjacent to the east and west side of Red Water Pond Road exceeded the FSL, consistent with the gamma survey results. As noted above, the results adjacent to Red Water Pond Road may be associated with the use of this road as a haul road for mines located to the north of NECR. Uranium concentrations from all three areas ranged from 0.48 to 119.00 mg/kg (average 7.42 mg/kg). All results were below the uranium screening level of 200 mg/kg.

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4.0 SUMMARY AND CONCLUSIONS This report presents the results of the SRSE for the Northeast Church Rock Mine Site in Church Rock, New Mexico (the Site). The purpose of the SRSE was to further delineate the FSL boundary at the margins of, including step-out areas, in the following three areas of the Site:

4) North of NECR-1 5) Trailer Park 6) Vents 3 and 8

Investigation activities consisted of a static gamma radiation survey, collection of soils samples and analysis of Ra-226 and total uranium, which were conducted in accordance with the RSE Work Plan (MWH, 2006). The gamma survey consisted of one-minute static (stationary) gamma radiation counts per minute (CPM). The gamma survey measurements were collected at 80-foot triangular grid nodes cast on a random origin in accordance with MARSSIM (EPA, 2000) using the same protocol as the other survey areas specified in the RSE Work Plan (MWH, 2006). The locations of the gamma survey points are shown on Figure 2-1. Surface soil sampling was also conducted in the three survey areas included in the SRSE and collected as grab samples from 0 to 0.5 feet bgs, as per the RSE Work Plan (MWH, 2006). The locations of these samples are shown on Figure 2-2. The samples were submitted to Energy Laboratories, Inc. and analyzed for Ra-226 and total uranium. A linear regression analysis was performed once the laboratory analytical data were completed to develop a correlation between gamma radiation levels and equivalent Ra-226 surface soil concentrations in order to estimate surface soil Ra-226 concentrations from the gamma radiation level measurements. Several soil sampling results were excluded from the correlation as outliers; inclusion of this data would have produced lower Ra-226 results for the gamma survey. The results of the static gamma radiation survey in equivalent Ra-226 concentrations, based on the SRSE correlation, which are presented in Table 1 and Figure 3-1, were as follows:

• North of NECR-1 – 195 measurements were made in the area. Concentrations ranged from <0.5 to 29.9 pCi/g (average 4.1 pCi/g); 122 measurements (63%) exceeded the FSL.

• Trailer Park – 74 measurements were made in the area. Concentrations ranged from 1.3 to

51.5 pCi/g (average 6.5 pCi/g); 60 measurements (81%) exceeded the FSL. • Vents 3 and 8 – 110 measurements were made in the area. Concentrations ranged from <0.5

to 51.8 pCi/g (average 2.2 pCi/g); 22 measurements (20%) exceeded the FSL. These results are generally consistent with the results of the RSE. The results of the surface soil sample analytical results are presented in Table 3.2 and on Figure 3-2. The laboratory analytical reports and the results of the data validation are included in Appendix B. The results of the Ra-226 analyses were as follows:

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• North of NECR-1 - 41 samples were collected from the area, five of which were split samples. Concentrations ranged from 0.7 to 28.5 pCi/g (average 4.7 pCi/g); 20 out of 36 primary samples (55%) exceeded the FSL.

• Vents 3 and 8 - 10 samples were collected, one of which was a split sample. Concentrations

ranged from 0.9 to 8.9 pCi/g (average 2.9 pCi/g); five of the nine primary samples (55%) exceeded the FSL.

• Trailer Park - 19 samples were collected, one of which was a split sample. Concentrations

ranged from 0.3 to 3.1 pCi/g (average 1.3 pCi/g); two of the 19 primary samples (10%) exceeded the FSL.

The gamma survey and soil analytical results were used to revise the FSL boundary, as shown on Figures 3-1 and 3-2. The FSL boundary changed only slightly at Vents 3 and 8 and the Trailer Park compared to that shown in the RSE report (MWH, 2007). In the area north of NECR-1, the FSL boundary was expanded around the home sites and shows that areas between the EPA Removal Action areas contain Ra-226 in excess of the FSL [although generally below the UMTRCA unrestricted use level at 40 CFR Part 192]. Additionally, 100% of the gamma radiation measurements and soil analytical results from the east side of Red Water Pond Road exceeded the FSL. These results from samples collected adjacent ton Red Water Pond Road may be associated with the former use of the road as a haul road for mines located to the north of NECR. Uranium concentrations from all three areas ranged from 0.48 to 119.00 mg/kg (average 7.42 mg/kg). All results were below the uranium screening level of 200 mg/kg.

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5.0 REFERENCES Department of Interior, Bureau of Land Management (BLM), 1990. Letter to Quivera Mining Company,

Conditional Approval of January 1987 Abandonment and Reclamation Plan for the Church Rock I, IE and II Mines.

Quivira Mining Company, 1987. Church Rock I, IE and II Mines, Navajo Nation Lease 14-20-20603-9988, Church Rock, New Mexico, January.

Environmental Protection Agency (EPA), 2000. Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), EPA 402-R-97-016, Rev. 1.

MWH, 2007a. Removal Site Evaluation Report, Northeast Church Rock Mine Site, October. MWH, 2007b. Supplemental Removal Site Evaluation Work Plan, Northeast Church Rock Mine Site,

October. MWH, 2006. Removal Site Evaluation Work Plan, Northeast Church Rock Mine Site, August. Nuclear Regulatory Comission (NRC), 1989, Memorandum , Cleanup of Tailings at the Northeast Church

Rock Mine, October. United Nuclear Coporation (UNC), 1989. Tailings Sand Backfill Cleanup Verification Report, Northeast

Church Rock Mine, United Nuclear Corporation, License SUA-1475, Condition No. 33.

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TABLES

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Gamma Survey Point ID

Soil Sample Number Survey Date Easting (ft)1

Northing (ft)1

Gamma Radiation

Level (cpm)

Surface Soil Equivalent Ra-

226 (pCi/g)2

HO-001 11/8/2007 2523978.73 1695842.96 13,800 13.4HO-002 11/8/2007 2524002.03 1695909.64 8,143 6.0HO-003 11/8/2007 2524050.06 1695977.05 6,785 4.3HO-004 11/8/2007 2524089.46 1696048.31 5,842 3.1HO-005 11/8/2007 2524175.92 1696243.43 10,436 9.0HO-006 11/8/2007 2524176.97 1696324.72 9,805 8.2HO-007 11/8/2007 2524200.03 1696394.59 7,930 5.8HO-008 11/7/2007 2523685.17 1696460.39 6,752 4.2HO-009 11/7/2007 2523561.12 1696531.24 5,281 2.3HO-011 11/7/2007 2523723.16 1696530.18 5,599 2.7HO-012 11/7/2007 2523800.62 1696525.84 5,341 2.4HO-013 11/7/2007 2523967.37 1696527.87 6,004 3.3HO-014 428 11/7/2007 2524208.81 1696527.72 10,488 9.1HO-015 11/7/2007 2523522.25 1696600.25 5,492 2.6HO-016 11/7/2007 2523612.70 1696602.30 5,243 2.3HO-017 11/7/2007 2523765.00 1696608.47 5,222 2.3HO-018 11/7/2007 2523849.22 1696601.56 5,546 2.7HO-020 11/7/2007 2524005.81 1696596.82 6,115 3.4HO-021 11/7/2007 2523561.46 1696667.35 4,569 1.4HO-022 11/7/2007 2523643.18 1696668.91 4,489 1.3HO-023 11/7/2007 2523723.01 1696671.38 4,490 1.3HO-024 11/7/2007 2523811.77 1696660.79 5,261 2.3HO-025 11/7/2007 2523962.66 1696670.47 5,584 2.7HO-026 11/8/2007 2524191.80 1696673.63 12,619 11.9HO-027 11/7/2007 2522803.22 1696738.98 5,035 2.0HO-028 11/7/2007 2522887.68 1696738.61 4,971 1.9HO-029 11/7/2007 2523202.52 1696743.10 6,437 3.8HO-030 11/7/2007 2523290.24 1696738.60 5,299 2.4HO-031 11/7/2007 2523442.33 1696744.79 5,081 2.1HO-032 11/7/2007 2523528.61 1696741.94 4,988 1.9HO-033 11/7/2007 2523606.41 1696738.80 4,979 1.9HO-034 11/7/2007 2523687.43 1696737.16 5,438 2.5HO-035 11/7/2007 2523850.43 1696738.31 4,925 1.9HO-036 11/7/2007 2523925.81 1696742.19 4,972 1.9HO-037 11/7/2007 2524011.75 1696728.90 6,246 3.6HO-038 11/8/2007 2524167.43 1696742.07 12,276 11.4HO-039 11/7/2007 2522928.85 1696811.65 5,497 2.6HO-040 11/7/2007 2523323.27 1696812.24 5,840 3.1HO-041 11/7/2007 2523405.18 1696812.83 5,713 2.9HO-042 11/7/2007 2523488.17 1696807.87 4,862 1.8HO-043 11/7/2007 2523567.66 1696804.22 5,025 2.0HO-044 11/7/2007 2523730.10 1696807.83 5,185 2.2HO-045 11/8/2007 2523799.68 1696804.99 5,275 2.3HO-046 11/8/2007 2523879.12 1696805.94 5,254 2.3HO-047 11/8/2007 2523961.63 1696804.90 5,324 2.4HO-048 11/8/2007 2524151.40 1696815.00 5,946 3.2HO-049 11/7/2007 2522881.05 1696877.50 5,156 2.2HO-050 11/7/2007 2522967.45 1696882.05 7,602 5.3HO-051 11/7/2007 2523368.55 1696872.21 5,326 2.4

Table 3.1Summary of Gamma Survey Results

NECR1 Stepout/Home Sites

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Northing (ft)1

Gamma Radiation

Level (cpm)


226 (pCi/g)2


HO-052 11/7/2007 2523442.40 1696879.16 5,380 2.5HO-053 11/7/2007 2523600.03 1696875.11 5,694 2.9HO-054 11/7/2007 2523686.16 1696881.53 5,522 2.6HO-055 11/8/2007 2524004.52 1696873.87 5,435 2.5HO-056 11/8/2007 2524085.04 1696871.52 13,149 12.6HO-057 429 11/7/2007 2524158.99 1696874.22 7,577 5.3HO-058 11/7/2007 2523315.77 1696962.69 5,011 2.0HO-059 11/8/2007 2523403.25 1696937.06 4,913 1.8HO-060 11/8/2007 2523482.97 1696952.03 6,049 3.3HO-061 11/8/2007 2523644.43 1696949.95 5,093 2.1HO-062 11/8/2007 2524046.74 1696942.57 6,759 4.2HO-063 11/8/2007 2524121.63 1696941.23 7,961 5.8HO-064 11/8/2007 2523360.05 1697019.53 4,933 1.9HO-065 11/8/2007 2523449.16 1697012.06 4,679 1.5HO-066 11/8/2007 2523528.75 1697012.47 4,083 0.8HO-067 11/8/2007 2523608.52 1697010.52 5,271 2.3HO-068 11/8/2007 2524008.99 1697021.08 5,961 3.2HO-069 11/8/2007 2523239.02 1697083.58 4,968 1.9HO-070 11/8/2007 2523320.21 1697083.07 4,708 1.6HO-071 11/8/2007 2523399.33 1697085.51 5,299 2.4HO-072 11/8/2007 2523564.11 1697088.00 5,358 2.4HO-073 11/8/2007 2523641.57 1697081.87 5,096 2.1HO-074 11/8/2007 2523733.92 1697078.57 4,511 1.3HO-075 11/8/2007 2523971.23 1697082.07 5,265 2.3HO-076 11/8/2007 2524044.48 1697079.71 13,740 13.3HO-077 11/8/2007 2524124.87 1697090.04 9,168 7.4HO-078 11/8/2007 2523208.74 1697158.79 4,921 1.9HO-079 11/8/2007 2523368.20 1697153.88 5,039 2.0HO-080 11/8/2007 2523450.71 1697154.07 5,344 2.4HO-081 11/8/2007 2523529.75 1697152.06 4,530 1.4HO-082 11/8/2007 2523610.06 1697157.38 5,015 2.0HO-083 11/8/2007 2523767.95 1697156.17 4,972 1.9HO-084 11/8/2007 2523855.07 1697128.77 5,105 2.1HO-085 11/8/2007 2523928.85 1697154.75 5,266 2.3HO-086 430 11/7/2007 2524007.88 1697157.38 6,206 3.5HO-087 11/8/2007 2523243.01 1697224.88 5,685 2.9HO-088 11/8/2007 2523322.47 1697226.27 5,939 3.2HO-089 11/8/2007 2523402.10 1697225.67 5,272 2.3HO-090 11/8/2007 2523483.88 1697226.34 5,271 2.3HO-091 11/8/2007 2523642.30 1697223.18 4,564 1.4HO-092 11/8/2007 2523721.50 1697226.08 4,852 1.8HO-093 11/8/2007 2523803.71 1697226.62 4,965 1.9HO-094 11/8/2007 2523888.61 1697220.97 4,554 1.4HO-095 11/8/2007 2524009.83 1697238.84 7,218 4.8HO-096 11/8/2007 2523202.54 1697291.54 3,332 <0.5HO-097 11/8/2007 2523289.20 1697293.20 4,856 1.8HO-098 11/8/2007 2523366.84 1697293.93 5,472 2.6HO-099 11/8/2007 2523529.64 1697292.48 5,627 2.8HO-10 11/7/2007 2523640.36 1696530.23 6,241 3.6HO-100 11/8/2007 2523607.57 1697296.29 5,568 2.7

005389



Northing (ft)1

Gamma Radiation

Level (cpm)


226 (pCi/g)2


HO-101 11/8/2007 2523682.95 1697292.66 5,834 3.0HO-102 11/8/2007 2523763.18 1697295.23 5,477 2.6HO-103 11/8/2007 2523925.94 1697295.12 7,945 5.8HO-104 11/8/2007 2524007.00 1697287.00 10,306 8.9HO-105 431 11/7/2007 2524081.70 1697293.80 20,401 22.0HO-106 11/8/2007 2523241.01 1697360.72 5,440 2.5HO-107 11/8/2007 2523401.23 1697361.54 5,612 2.8HO-108 11/8/2007 2523481.44 1697361.67 5,316 2.4HO-109 11/8/2007 2523562.22 1697363.64 5,368 2.4HO-109 11/7/2007 2523927.42 1696597.90 4,669 1.5HO-110 11/8/2007 2523640.06 1697361.60 5,367 2.4HO-111 11/8/2007 2523800.77 1697364.45 5,429 2.5HO-112 432 11/7/2007 2523883.66 1697362.91 5,606 2.8HO-113 11/8/2007 2523967.12 1697358.20 7,854 5.7HO-114 11/8/2007 2524056.78 1697369.80 21,696 23.7HO-115 11/8/2007 2523368.51 1697432.82 5,708 2.9HO-116 11/8/2007 2523448.44 1697434.72 5,511 2.6HO-117 11/8/2007 2523529.39 1697430.90 4,586 1.4HO-118 11/8/2007 2523609.59 1697429.88 5,659 2.8HO-119 11/8/2007 2523770.22 1697430.98 5,136 2.1HO-120 11/8/2007 2523850.43 1697432.75 4,944 1.9HO-121 11/8/2007 2523930.52 1697431.41 5,562 2.7HO-122 11/8/2007 2524003.67 1697429.67 16,197 16.5HO-123 11/8/2007 2523401.27 1697497.82 6,556 4.0HO-124 11/8/2007 2523480.29 1697500.74 5,915 3.2HO-125 11/8/2007 2523560.45 1697500.84 5,013 2.0HO-126 11/8/2007 2523640.88 1697498.55 4,870 1.8HO-127 11/8/2007 2523801.49 1697496.45 5,128 2.1HO-128 11/8/2007 2523887.91 1697506.23 5,443 2.5HO-129 11/8/2007 2523965.16 1697494.64 18,610 19.7HO-130 433 11/7/2007 2524043.71 1697500.49 24,105 26.8HO-131 11/8/2007 2523449.11 1697574.18 9,018 7.2HO-132 11/8/2007 2523528.79 1697566.66 4,643 1.5HO-133 11/8/2007 2523609.69 1697569.39 4,636 1.5HO-134 11/8/2007 2523687.03 1697564.44 4,715 1.6HO-135 11/8/2007 2523845.97 1697562.84 5,461 2.6HO-136 11/8/2007 2523927.25 1697566.07 5,565 2.7HO-137 11/8/2007 2524001.25 1697564.79 12,046 11.1HO-138 11/8/2007 2523480.76 1697640.18 7,937 5.8HO-139 11/8/2007 2523638.88 1697639.06 4,980 1.9HO-140 11/8/2007 2523721.30 1697644.38 4,952 1.9HO-141 11/8/2007 2523803.79 1697644.39 5,004 2.0HO-142 11/8/2007 2523529.98 1697711.90 5,465 2.6HO-143 11/8/2007 2523689.01 1697705.46 4,517 1.3HO-144 11/8/2007 2523568.64 1697785.16 4,280 1.0HO-145 11/8/2007 2523657.48 1697781.12 5,552 2.7HO-146 434 11/7/2007 2524129.25 1696141.22 8,176 6.1HO-147 11/8/2007 2524188.04 1696462.66 24,617 27.5HO-148 435 11/7/2007 2523879.20 1696530.50 5,697 2.9HO-149 436 11/7/2007 2523687.36 1696601.10 4,846 1.8

005390



Northing (ft)1

Gamma Radiation

Level (cpm)


226 (pCi/g)2


HO-150 11/8/2007 2524183.13 1696602.47 26,529 29.9HO-151 437 11/7/2007 2523880.66 1696666.24 5,169 2.2HO-152 438 11/7/2007 2522967.15 1696740.99 10,242 8.8HO-153 439 11/7/2007 2523360.33 1696741.96 5,522 2.6HO-154 440 11/7/2007 2523767.25 1696738.50 5,186 2.2HO-155 441 11/7/2007 2522842.07 1696810.11 4,649 1.5HO-156 442 11/7/2007 2523646.38 1696804.32 5,064 2.0HO-157 443 11/7/2007 2524043.10 1696805.70 5,678 2.8HO-158 444 11/7/2007 2523520.13 1696876.29 5,794 3.0HO-159 445 11/7/2007 2523567.57 1696945.87 4,860 1.8HO-160 446 11/7/2007 2523969.35 1696947.01 5,121 2.1HO-161 447 11/7/2007 2523287.21 1697015.64 5,551 2.7HO-162 448 11/7/2007 2524066.83 1697015.95 14,628 14.5HO-163 449 11/7/2007 2523484.40 1697084.73 4,692 1.6HO-164 450 11/7/2007 2523281.94 1697156.72 4,461 1.3HO-165 451 11/7/2007 2523685.56 1697154.06 4,650 1.5HO-166 11/8/2007 2524099.76 1697168.02 19,972 21.4HO-167 452 11/7/2007 2523566.45 1697218.81 5,588 2.7HO-168 453 11/6/2007 2523440.37 1697293.30 5,563 2.7HO-169 454 11/6/2007 2523322.26 1697368.98 4,911 1.8HO-170 455 11/6/2007 2523282.99 1697428.75 7,166 4.8HO-171 456 11/6/2007 2523688.25 1697435.93 4,810 1.7HO-172 457 11/6/2007 2523326.43 1697499.40 6,388 3.8HO-173 458 11/6/2007 2523729.04 1697500.34 5,355 2.4HO-174 459 11/6/2007 2523364.61 1697565.30 6,374 3.7HO-175 460 11/6/2007 2523767.02 1697565.51 4,939 1.9HO-176 461 11/6/2007 2523558.63 1697636.63 5,291 2.3HO-177 462 11/6/2007 2523604.79 1697709.92 5,821 3.0HO-178 11/7/2007 2522989.24 1697575.01 4,281 1.0HO-179 11/7/2007 2523071.58 1697568.20 4,294 1.0HO-180 11/7/2007 2523150.00 1697567.00 4,141 0.8HO-181 11/7/2007 2523103.70 1697503.57 4,817 1.7HO-182 11/7/2007 2523182.14 1697450.19 7,526 5.2HO-183 11/7/2007 2523215.07 1697525.12 4,716 1.6HO-184 11/14/2007 2523432.29 1697640.43 4,842 1.8HO-185 11/14/2007 2523339.30 1697593.84 5,340 2.4HO-186 11/14/2007 2523262.25 1697482.24 7,298 4.9HO-187 11/14/2007 2523137.57 1697440.01 5,158 2.2HO-188 11/14/2007 2523189.08 1697364.64 5,487 2.6HO-189 11/14/2007 2523467.36 1697709.89 5,121 2.1N1-352 11/14/2007 2523879.27 1695843.48 7,705 5.5N1-353 11/14/2007 2523803.25 1695861.08 8,868 7.0N1-354 11/14/2007 2523703.27 1695861.19 10,183 8.7N1-355 11/14/2007 2523632.84 1695859.20 12,476 11.7N1-356 11/14/2007 2524000.48 1696109.21 5,568 2.7N1-357 11/14/2007 2523857.48 1696070.31 5,680 1.8

005391



Northing (ft)1

Gamma Radiation

Level (cpm)


226 (pCi/g)2


TP-101 11/6/2007 2522975.94 1694888.96 5,331 2.4TP-102 11/6/2007 2523098.30 1694903.52 4,836 1.7TP-103 418 11/6/2007 2523009.02 1694964.93 7,650 5.4TP-104 11/6/2007 2522869.90 1694941.39 5,808 3.0TP-105 11/6/2007 2522925.15 1694973.05 8,327 6.3TP-106 11/6/2007 2523098.69 1694971.08 6,180 3.5TP-107 419 11/6/2007 2523177.15 1695029.75 4,781 1.7TP-108 11/6/2007 2522886.93 1695042.01 6,311 3.7TP-109 11/6/2007 2522969.19 1695029.67 5,858 3.1TP-110 11/6/2007 2523051.96 1695032.90 4,522 1.3TP-111 11/6/2007 2522927.13 1695100.68 5,565 2.7TP-112 11/6/2007 2523217.07 1695098.17 4,750 1.6TP-113 11/6/2007 2523001.94 1695105.42 5,527 2.6TP-114 11/6/2007 2523081.60 1695104.14 8,949 7.1TP-115 420 11/6/2007 2522969.35 1695171.67 5,663 2.8TP-116 11/6/2007 2523205.53 1695167.59 6,734 4.2TP-117 11/6/2007 2523293.18 1695172.79 4,633 1.5TP-118 11/6/2007 2523045.07 1695171.20 5,804 3.0TP-119 11/6/2007 2523123.82 1695197.36 8,872 7.0TP-120 11/6/2007 2523004.83 1695244.01 5,554 2.7TP-121 11/6/2007 2523086.24 1695239.28 6,690 4.2TP-122 11/6/2007 2523162.03 1695244.30 10,337 8.9TP-123 11/6/2007 2523250.17 1695240.25 22,579 24.8TP-124 11/6/2007 2523336.65 1695244.97 5,210 2.2TP-125 421 11/6/2007 2523048.82 1695309.21 5,628 2.8TP-126 11/6/2007 2523129.97 1695315.45 6,588 4.0TP-127 427 11/6/2007 2523209.23 1695307.08 6,995 4.6TP-128 11/6/2007 2523285.32 1695304.18 5,836 3.0TP-129 423 11/6/2007 2523173.54 1695380.38 6,246 3.6TP-130 11/6/2007 2523090.63 1695386.99 5,713 2.9TP-131 11/6/2007 2523246.27 1695381.35 7,866 5.7TP-132 11/6/2007 2523332.76 1695376.50 12,723 12.0TP-133 424 11/6/2007 2523293.37 1695450.51 8,706 6.8TP-134 11/6/2007 2523090.04 1695526.90 5,842 3.1TP-135 11/6/2007 2523172.04 1695514.58 5,547 2.7TP-136 11/6/2007 2523409.43 1695542.91 9,501 7.8TP-137 425 11/6/2007 2523289.61 1695587.22 11,143 9.9TP-138 11/6/2007 2523049.59 1695587.35 5,979 3.2TP-139 11/6/2007 2523147.55 1695600.12 28,239 32.2TP-140 11/6/2007 2523388.57 1695607.47 7,445 5.1TP-141 11/6/2007 2523446.17 1695654.95 6,468 3.9TP-142 11/6/2007 2523246.32 1695663.84 10,725 9.4TP-143 11/6/2007 2523165.27 1695660.71 14,472 14.3TP-144 11/6/2007 2523325.15 1695657.21 15,515 15.6TP-145 11/6/2007 2523142.99 1695738.97 15,130 15.1TP-146 11/6/2007 2523222.18 1695739.97 11,552 10.5TP-147 426 11/6/2007 2523320.16 1695753.78 14,800 14.7TP-148 11/14/2007 2522895.70 1694892.19 5,362 2.4TP-149 11/14/2007 2522817.21 1694890.19 6,169 3.5

Trailer Park

005392



Northing (ft)1

Gamma Radiation

Level (cpm)


226 (pCi/g)2


TP-150 11/14/2007 2522781.67 1694948.65 5,058 2.0TP-151 11/14/2007 2522807.09 1695038.89 5,121 2.1TP-152 11/14/2007 2522858.65 1695123.08 5,195 2.2TP-153 11/14/2007 2522998.15 1695504.78 5,436 2.5TP-154 11/14/2007 2523049.06 1695443.34 6,889 4.4TP-155 11/14/2007 2523381.63 1695307.75 5,083 2.1TP-156 11/14/2007 2523415.67 1695384.00 5,795 3.0TP-157 11/14/2007 2523444.75 1695439.60 5,301 2.4TP-158 11/14/2007 2523482.47 1695516.01 5,525 2.6TP-159 11/14/2007 2523492.60 1695549.57 5,048 2.0TP-160 11/14/2007 2523589.94 1695756.00 43,086 51.5TP-161 11/14/2007 2523537.91 1695656.25 5,607 2.8TP-162 11/14/2007 2523567.05 1695727.74 5,693 2.9TP-163 11/14/2007 2523536.82 1695758.24 30,026 34.5TP-164 11/14/2007 2522969.42 1695436.57 5,448 2.5TP-165 11/14/2007 2523055.47 1695356.00 5,188 2.2TP-166 11/14/2007 2523488.26 1695392.51 5,301 2.4TP-167 11/14/2007 2523483.51 1695617.76 5,523 2.6TP-168 11/14/2007 2523668.87 1695749.83 5,622 2.8TP-169 11/14/2007 2523608.10 1695692.02 5,799 3.0TP-170 11/14/2007 2523870.65 1695749.34 6,007 3.3TP-171 11/14/2007 2523931.38 1695752.61 4,957 1.9TP-172 11/14/2007 2523888.84 1695735.74 4,615 1.5TP-173 11/14/2007 2523780.92 1695754.14 27,600 31.3TP-174 11/14/2007 2523776.87 1695741.71 5,316 2.4

V-101 11/5/2007 2520490.11 1695022.73 3,364 <0.5V-102 11/5/2007 2520584.25 1695023.90 3,856 0.5V-103 400 11/5/2007 2520201.02 1695087.68 3,915 0.6V-104 401 11/5/2007 2520684.33 1695091.44 3,565 <0.5V-105 11/5/2007 2520055.67 1695099.06 8,816 6.9V-106 11/5/2007 2520125.90 1695095.01 4,433 1.2V-107 11/5/2007 2520363.24 1695095.71 3,274 <0.5V-108 11/5/2007 2520443.49 1695089.06 3,419 <0.5V-109 11/5/2007 2520527.35 1695096.13 3,405 <0.5V-110 11/5/2007 2520766.90 1695088.51 5,169 2.2V-111 11/5/2007 2520857.95 1695095.85 5,036 2.0V-112 402 11/5/2007 2520244.85 1695164.73 4,884 1.8V-113 403 11/5/2007 2520646.09 1695164.76 3,791 <0.5V-114 11/5/2007 2520088.72 1695167.46 6,173 3.5V-115 11/5/2007 2520163.81 1695156.62 10,610 9.3V-116 11/5/2007 2520329.85 1695162.11 3,253 <0.5V-117 11/5/2007 2520410.59 1695159.19 3,133 <0.5V-118 11/5/2007 2520490.41 1695160.19 3,963 0.6V-119 11/5/2007 2520563.15 1695159.49 3,928 0.6V-120 11/5/2007 2520724.26 1695162.46 3,565 <0.5V-121 11/5/2007 2520810.77 1695160.67 3,745 <0.5V-122 11/5/2007 2520881.39 1695161.89 4,626 1.5V-123 404 11/5/2007 2520124.01 1695232.95 14,930 14.9V-124 405 11/5/2007 2520928.40 1695228.97 4,432 1.2

Vents 3 and 8

005393



Northing (ft)1

Gamma Radiation

Level (cpm)


226 (pCi/g)2


V-125 11/5/2007 2520043.19 1695230.53 4,459 1.3V-126 11/5/2007 2520203.39 1695231.92 3,790 <0.5V-127 11/5/2007 2520283.10 1695229.09 3,519 <0.5V-128 11/5/2007 2520364.25 1695227.39 3,804 <0.5V-129 11/5/2007 2520444.19 1695233.97 5,245 2.3V-130 11/5/2007 2520686.17 1695235.35 3,939 0.6V-131 11/5/2007 2520769.02 1695234.86 4,049 0.7V-132 11/5/2007 2520848.57 1695236.62 4,224 1.0V-133 11/5/2007 2521005.46 1695231.68 5,556 2.7V-134 11/5/2007 2520489.63 1695296.36 3,370 <0.5V-135 11/5/2007 2520570.38 1695297.22 3,197 <0.5V-136 11/5/2007 2520745.36 1695442.91 3,247 <0.5V-136 406 11/5/2007 2520969.31 1695298.84 4,155 0.9V-137 11/5/2007 2519928.37 1695304.74 4,042 0.7V-138 11/5/2007 2520004.63 1695302.75 4,285 1.0V-139 11/5/2007 2520090.46 1695303.80 6,878 4.4V-140 11/5/2007 2520247.46 1695305.49 4,013 0.7V-141 11/5/2007 2520328.68 1695296.24 2,974 <0.5V-142 11/5/2007 2520410.99 1695300.61 4,513 1.3V-143 11/5/2007 2520655.07 1695302.28 3,914 0.6V-144 11/5/2007 2520729.35 1695298.59 3,619 <0.5V-145 11/5/2007 2520809.11 1695304.46 3,626 <0.5V-146 11/5/2007 2520887.52 1695297.06 3,921 0.6V-147 407 11/5/2007 2520130.20 1695371.24 5,661 2.8V-148 408 11/5/2007 2520612.17 1695375.23 3,195 <0.5V-149 11/5/2007 2519805.98 1695368.69 4,141 0.8V-150 11/5/2007 2519884.06 1695365.95 3,946 0.6V-151 11/5/2007 2519962.94 1695368.80 4,987 1.9V-152 11/5/2007 2520203.05 1695367.14 6,887 4.4V-153 11/5/2007 2520284.65 1695364.23 3,233 <0.5V-154 11/5/2007 2520362.03 1695369.67 4,906 1.8V-155 11/5/2007 2520446.24 1695365.47 3,168 <0.5V-156 11/5/2007 2520690.79 1695361.24 3,799 <0.5V-157 11/5/2007 2520771.48 1695364.40 3,331 <0.5V-158 11/5/2007 2520846.30 1695375.97 3,730 <0.5V-159 11/5/2007 2520933.39 1695370.53 3,411 <0.5V-160 409 11/5/2007 2520245.01 1695436.74 4,222 1.0V-161 11/5/2007 2519929.92 1695438.50 4,793 1.7V-162 11/5/2007 2520330.96 1695437.34 3,125 <0.5V-164 11/5/2007 2520812.42 1695431.84 3,365 <0.5V-165 11/5/2007 2520890.48 1695436.20 3,287 <0.5V-166 410 11/5/2007 2520206.00 1695509.07 5,758 2.9V-167 11/6/2007 2519970.16 1695505.85 7,424 5.1V-168 11/6/2007 2520289.24 1695508.82 4,151 0.9V-169 11/6/2007 2520370.67 1695511.47 3,418 <0.5V-170 411 11/5/2007 2520406.64 1695580.11 3,384 <0.5V-171 11/6/2007 2519849.00 1695586.18 3,529 <0.5V-172 11/6/2007 2520249.97 1695580.01 6,218 3.5V-173 11/6/2007 2520484.49 1695584.70 2,835 <0.5V-174 11/6/2007 2519882.56 1695650.65 4,779 1.7

005394



Northing (ft)1

Gamma Radiation

Level (cpm)


226 (pCi/g)2


V-175 11/6/2007 2520207.52 1695649.29 5,130 2.1V-176 11/6/2007 2520285.45 1695646.02 5,167 2.2V-177 11/6/2007 2520342.51 1695646.20 4,441 1.2V-178 11/6/2007 2520442.03 1695650.17 3,210 <0.5V-179 412 11/5/2007 2519927.90 1695721.41 4,901 1.8V-180 413 11/5/2007 2520330.82 1695717.00 4,315 1.1V-181 11/6/2007 2520246.98 1695718.79 8,217 6.1V-182 11/6/2007 2520401.44 1695735.69 3,465 <0.5V-183 11/6/2007 2520480.60 1695721.14 3,904 0.5V-184 414 11/5/2007 2520051.88 1695786.66 43,297 51.7V-185 415 11/5/2007 2520444.67 1695792.31 3,800 <0.5V-186 11/6/2007 2519884.00 1695788.54 6,499 3.9V-187 11/6/2007 2519967.61 1695781.89 6,455 3.9V-188 11/6/2007 2520128.09 1695783.27 26,785 30.3V-189 11/6/2007 2520205.82 1695783.49 6,836 4.3V-190 11/6/2007 2520285.83 1695789.26 3,698 <0.5V-191 11/6/2007 2520372.03 1695788.16 3,372 <0.5V-192 416 11/5/2007 2520251.15 1695859.53 3,546 <0.5V-193 11/6/2007 2519926.18 1695853.66 5,308 2.4V-194 11/6/2007 2520326.39 1695854.67 4,031 0.7V-195 11/6/2007 2520408.24 1695860.83 2,877 <0.5V-196 417 11/5/2007 2520205.07 1695912.03 4,039 0.7V-197 11/6/2007 2520044.49 1695921.98 4,985 1.9V-198 11/6/2007 2520126.03 1695925.88 4,634 1.5V-199 11/14/2007 2520092.66 1695027.28 4,468 1.3V-200 11/14/2007 2519966.84 1695096.84 5,382 2.5V-201 11/14/2007 2520008.95 1695158.75 4,723 1.6V-202 11/14/2007 2519857.26 1695713.57 7,739 5.5V-203 11/14/2007 2519809.62 1695787.28 4,652 1.5V-204 11/14/2007 2519850.09 1695854.49 7,819 5.6V-205 11/14/2007 2520008.30 1695016.50 3,428 <0.5V-206 11/14/2007 2519765.84 1695713.16 4,225 1.0V-207 11/14/2007 2519723.68 1695786.19 5,174 2.2V-208 11/14/2007 2519761.79 1695854.96 4,195 0.9V-209 11/14/2007 2519802.07 1695926.64 3,483 <0.5V-210 11/14/2007 2519874.12 1695932.03 4,995 2.0

Notes:1. Easting and northing coordinates are based on New Mexico West State Plane, NAD 83.2. Equivalent Ra-226 concentrations are based on a revised regression equation using SRS results.

005395

Samp ID Ra-226 (pCi/g) Uranium (mg/kg)Reporting Limit 0.1 0.2Screening Level 2.24 200

Home-SS-428 9.2 24.00Home-SS-429 4.6 5.66Home-SS-430 2.9 4.48Home-SS-530 3.5 4.58Home-SS-431 18.7 18.20Home-SS-432 3.4 49.90Home-SS-433 28.5 36.00Home-SS-434 5.3 4.54Home-SS-435 2.5 7.26Home-SS-436 2.0 8.84Home-SS-536 2.0 7.30Home-SS-437 5.4 20.60Home-SS-438 1.3 13.30Home-SS-439 0.9 2.10Home-SS-440 2.5 5.44Home-SS-540 2.1 6.10Home-SS-441 0.7 0.81Home-SS-442 1.5 3.05Home-SS-443 2.0 6.88Home-SS-444 2.9 3.15Home-SS-445 1.3 2.42Home-SS-446 1.7 3.56Home-SS-447 2.5 3.99Home-SS-448 17.1 22.60Home-SS-449 1.1 3.07Home-SS-450 0.9 1.59Home-SS-550 1.2 1.78Home-SS-451 1.1 1.42Home-SS-452 4.1 4.58Home-SS-453 3.2 2.93Home-SS-454 26.6 14.50Home-SS-455 9.5 11.70Home-SS-456 1.8 2.37Home-SS-457 4.4 4.17Home-SS-458 1.4 3.90Home-SS-459 2.5 2.57Home-SS-460 1.9 4.10Home-SS-560 2.6 4.40Home-SS-461 1.2 1.76Home-SS-462 1.7 3.07Home-SS-463 4.8 6.24

Average 4.7 8.30Standard Deviation 6.5 9.98

Table 3.2Summary of Surface Soil Analytical Results

NECR-1 Step-Out/Home Sites

005396

Samp ID Ra-226 (pCi/g) Uranium (mg/kg)Reporting Limit 0.1 0.2Screening Level 2.24 200

Table 3.2Summary of Surface Soil Analytical Results

TP-SS-418 3.2 1.94TP-SS-419 0.9 1.07TP-SS-420 0.9 1.36TP-SS-520 1.4 1.49TP-SS-421 2.9 2.44TP-SS-423 2.1 2.30TP-SS-424 3.8 4.73TP-SS-425 8.9 8.55TP-SS-426 1.1 1.80TP-SS-427 4.1 2.55


Vent38-SS-400 0.6 1.00Vent38-SS-401 0.9 2.09Vent38-SS-402 2.9 7.41Vent38-SS-403 0.8 0.98Vent38-SS-404 1.4 1.36Vent38-SS-405 1.2 1.65Vent38-SS-406 0.3 0.51Vent38-SS-407 1.1 1.30Vent38-SS-408 0.6 0.64Vent38-SS-409 1.9 2.11Vent38-SS-410 3.1 2.87Vent38-SS-510 2.9 2.87Vent38-SS-411 0.5 0.60Vent38-SS-412 1.4 2.32Vent38-SS-413 1.8 2.69Vent38-SS-414 1.0 119.00Vent38-SS-415 0.8 1.07Vent38-SS-416 0.6 0.48Vent38-SS-417 1.1 1.19


2. Shaded cells indicate exceedance of the screening level.

1. Split samples are indicated by ID numbers in the 500s and are listed below their corresponding primary sample.

Notes:

Trailer Park

Vents 3 & 8

005397

FIGURES

005398

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7

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NON-ECONOMIC MATERIALSTORAGE AREA

NECR-2

MAGAZINE

SEDIMENT PAD

POND 2 POND 1

MILL WATER TANKS

SANDFILL NO.1

NECR-1

POND 3

VENT 3

NECR-2DRAINAGE

TRAILER PARK

SANDFILL NO. 2

BONEYARD

HOME SITES

FUEL STORAGE

SANDFILL NO. 3

1-X PLANT

VENT 8

STATIC GAMMA MEASUREMENT LOCATIONS SHOWING EQUIVALENT Ra-226 (pCi/g) CONCENTRATION

< 2.2

2.2 ~ 6.0

6.1 ~ 22.4

22.4 ~ 50

> 50

1. SURFACE TOPOGRAPHY GENERATED FROM AERIALPHOTOGRAPHS DATED MAY 2007 BY COOPER AERIAL SURVEYSCO. NEW MEXICO WEST STATE PLANE COORDINATES, NAD 83.

CONTOURS

STREAMS

ROADS

STRUCTURES

PERMIT BOUNDARY

SURVEY AREA BOUNDARY

MINE FEATURE BOUNDARY

EPA REMOVAL ACTION BOUNDARY

HOME SITE 0.5ACRE SURVEY AREA BOUNDAY

AREAS ABOVE FIELD SCREENING LEVEL

005398.001

1

2 4

3

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NECR-1

HO-437(5.4)(21)

HO-429(4.6)(6)

HO-440(2.5)(5)

HO-444(2.9)(3)

HO-447(2.5)(4)

HO-452(4.1)(5)

HO-453(3.2)(3)

HO-457(4.4)(4)

HO-459(2.5)(3)HO-463

(4.8)(6)

N1-173(4.6)(6)

N1-207(3.1)(8)

N1-307(3.8)(7)

HO-434(5.3)(5)

HO-430(2.9)(5)

HO-432(3.4)(50)

HO-435(2.5)(7)

CB-14(21)(NA)

CB-01(11.9)(NA)

HO-428(9.2)(24)

HO-431(18.7)(18)

HO-448(17.1)(23)

HO-448(17.1)(23)

HO-455(9.5)(12)

HO6-004(8.9)(10.2)

HO7-005(7.4)(9.2)

CB-03(9.7)(0)

N1-129(7)(8) N1-140

(15.8)(21)

N1-293(7)(21)

CB-13(19.2)(NA)

CB-11(19.6)(NA)

CB-09(18.9)(NA)

CB-12(21.4)(NA)

CB-02(10.6)(NA)

CB-04(11.4)(NA)

CB-05(15.8)(NA)

CB-06(15.7)(NA)

CB-07(14.9)(NA)

CB-08(14.4)(NA)

CB-10(21.2)(NA)

HO1-001(1.2)(1)

HO1-002(0.9)(1)

HO1-003(1)(1)

HO1-004(1.3)(1)

HO1-005(1.5)(1)

HO2-001(0.9)(1)

HO2-002(0.9)(1)

HO2-003(0.9)(1)

HO2-004(0.9)(1) HO2-005

(0.9)(1)HO3-001

(0.9)(1)

HO3-002(1.1)(1)

HO3-003(1.1)(1)

HO3-004(1.2)(1)

HO3-005(1.1)(1)

HO-436(2)(9)

HO-438(1.3)(13)

HO-439(0.9)(2)

HO-441(0.7)(1) HO-442

(1.5)(3)HO-443(2)(7)

HO-445(1.3)(2)

HO-446(1.7)(4)

HO-450(0.9)(2)

HO-451(1.1)(1)

HO-456(1.8)(2)

HO-458(1.4)(4)

HO-460(1.9)(4)

HO-461(1.2)(2)

HO-462(1.7)(3)

HO4-001(1.3)(1.1)

HO4-002(2.1)(1.5)

HO4-003(1.6)(1.5)

HO5-001(1)(0.8)

HO5-002(1.4)(1.1) HO5-003

(0.9)(0.9)

HO5-004(1.3)(1.4)

HO5-005(2.1)(2.4)

N1-184(1.2)(3)

N1-238(1.6)(3)

N1-240(1.5)(4)

N1-262(1.4)(2)

N1-265(1.6)(2)

N1-289(1.8)(3)

HO-454(26.6)(15)

N1-131(41.5)(59) N1-138

(48.6)(20)

N1-164(35.7)(22)

CB-15(26.4)(NA)

HO-433(28.5)(36)

N1-126(50.9)(99) N1-127

(93.3)(177)

N1-133(54.7)(53)

N1-135(63.2)(81)

N1-137(52.6)(99)

N1-281(80.5)(83)

< 2.2

2.2 ~ 6.0

6.1 ~ 22.4

22.4 ~ 50

> 50

SURFACE SOIL SAMPLE LOCATIONS SHOWINGRa-226 LABORATORY RESULTS (pCi/g)

AS,U (mg/Kg)

NOT-ANALYZED

(2.7)(5.3)

NA


2. URANIUM VALUES ARE ROUNDED TO ZERO DECIMAL PLACES.

CONTOURS

STREAMS

ROADS

STRUCTURES

PERMIT BOUNDARY






005398.002

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FUEL STORAGE

POND 1

MILL WATERTANKS

TRAILER PARK

SANDFILL NO.1

TP-421(2.9)(2)

TP-427(4.1)(3)

S1-011(5.8)(3)

S1-021(2.3)(13)

S1-032(3.8)(3)

S1-053(5.4)(3)

S1-065(4.3)(3)

P12-076(2.2)(8)

N1-323(2.6)(2)

N1-326(5.2)(4)

TP-424(3.8)(5)

TP-418(3.2)(2)

S1-027(4.4)(1)

TP-001(12.5)(13)

TP-425(8.9)(9)

N1-005(8.9)(5)

N1-018(21.7)(17)

N1-023(18.3)(71)

N1-030(6.5)(9)

N1-068(12.8)(256)

N1-101(12.7)(27)

N1-103(17.7)(18)

N1-129(7)(8) N1-140

(15.8)(21)

N1-092(13.2)(18)

P12-050(13.7)(12)

P3-061(17.3)(28)

S1-030(14.3)(11)

S1-043(6.7)(2) S1-044

(11)(2)

S1-049(16.8)(41)

S1-050(15.7)(5)

S1-063(20.8)(7)

TP-423(2.1)(2)

TP-426(1.1)(2)

TP-420(0.9)(1)

N1-266(1.7)(58)

N1-316(1.3)(1)

P12-063(1.2)(1)

TP-419(0.9)(1)

TP-027(2.1)(2)

TP-024(2.1)(17)

S1-009(1.8)(2)

S1-017(2.1)(3)

S1-028(0.8)(1)

S1-041(1.3)(2)

S1-051(1.9)(1)

TP-009(33.2)(139)

TP-013(33.2)(44)

P12-024(26.9)(16)

N1-047(31.3)(28)

P12-071(49.9)(74)

N1-020(46.2)(52)

N1-028(26.3)(80)

N1-044(47.9)(58) N1-049

(29.3)(664)

N1-065(28.4)(59)

N1-067(38.3)(55)

N1-070(26.1)(50)

N1-093(35.7)(57)

N1-131(41.5)(59)

S1-068(47.3)(41)

N1-138(48.6)(20)

CA-18(40.4)(NA)

P12-014(96.9)(48)

P12-023(62.4)(29)

P12-035(78.5)(86)

P12-047(73.1)(38)

P12-058(655)(1080)

P12-069(161)(166)

P12-077(487)(423)

P12-082(177)(339)

N1-016(80.8)(758)

N1-026(68.4)(199)

N1-046(58.8)(176)

N1-090(84.8)(122)

N1-095(75.7)(209)

(93.3)(177)

N1-133(54.7)(53)

N1-135(63.2)(81)

N1-137(52.6)(99)

CA-17(185)(NA)

< 2.2

2.2 ~ 6.0

6.1 ~ 22.4

22.4 ~ 50

> 50


AS,U (mg/Kg)

NOT-ANALYZED

(2.7)(5.3)

NA

1. SURFACE TOPOGRAPHY GENERATED FROM AERIALPHOTOGRAPHS DATED MAY 2007 BY COOPER AERIAL SURVEYSCO. NEW MEXICO WEST STATE PLANE COORDINATES, NAD 83


CONTOURS

STREAMS

ROADS

STRUCTURES

PERMIT BOUNDARY






005398.003

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NON-ECONOMIC MATERIALSTORAGE AREA

NECR-2

MAGAZINE

SEDIMENT PAD

POND 2 POND 1

MILL WATER TANKS

SANDFILL NO.1

NECR-1

POND 3

VENT 3

NECR-2DRAINAGE

TRAILER PARK

SANDFILL NO. 2

BONEYARD

HOME SITES

FUEL STORAGE

SANDFILL NO. 3

1-X PLANT

VENT 8

STATIC GAMMA MEASUREMENT LOCATIONS SHOWING EQUIVALENT Ra-226 (pCi/g) CONCENTRATION

< 2.2

2.2 ~ 6.0

6.1 ~ 22.4

22.4 ~ 50

> 50


CONTOURS

STREAMS

ROADS

STRUCTURES

PERMIT BOUNDARY






005398.004

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2 4

3

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NECR-1

HO-437(5.4)(21)

HO-429(4.6)(6)

HO-440(2.5)(5)

HO-444(2.9)(3)

HO-447(2.5)(4)

HO-452(4.1)(5)

HO-453(3.2)(3)

HO-457(4.4)(4)

HO-459(2.5)(3)HO-463

(4.8)(6)

N1-173(4.6)(6)

N1-207(3.1)(8)

N1-307(3.8)(7)

HO-434(5.3)(5)

HO-430(2.9)(5)

HO-432(3.4)(50)

HO-435(2.5)(7)

CB-14(21)(NA)

CB-01(11.9)(NA)

HO-428(9.2)(24)

HO-431(18.7)(18)

HO-448(17.1)(23)

HO-448(17.1)(23)

HO-455(9.5)(12)

HO6-004(8.9)(10.2)

HO7-005(7.4)(9.2)

CB-03(9.7)(0)

N1-129(7)(8) N1-140

(15.8)(21)

N1-293(7)(21)

CB-13(19.2)(NA)

CB-11(19.6)(NA)

CB-09(18.9)(NA)

CB-12(21.4)(NA)

CB-02(10.6)(NA)

CB-04(11.4)(NA)

CB-05(15.8)(NA)

CB-06(15.7)(NA)

CB-07(14.9)(NA)

CB-08(14.4)(NA)

CB-10(21.2)(NA)

HO1-001(1.2)(1)

HO1-002(0.9)(1)

HO1-003(1)(1)

HO1-004(1.3)(1)

HO1-005(1.5)(1)

HO2-001(0.9)(1)

HO2-002(0.9)(1)

HO2-003(0.9)(1)

HO2-004(0.9)(1) HO2-005

(0.9)(1)HO3-001

(0.9)(1)

HO3-002(1.1)(1)

HO3-003(1.1)(1)

HO3-004(1.2)(1)

HO3-005(1.1)(1)

HO-436(2)(9)

HO-438(1.3)(13)

HO-439(0.9)(2)

HO-441(0.7)(1) HO-442

(1.5)(3)HO-443(2)(7)

HO-445(1.3)(2)

HO-446(1.7)(4)

HO-450(0.9)(2)

HO-451(1.1)(1)

HO-456(1.8)(2)

HO-458(1.4)(4)

HO-460(1.9)(4)

HO-461(1.2)(2)

HO-462(1.7)(3)

HO4-001(1.3)(1.1)

HO4-002(2.1)(1.5)

HO4-003(1.6)(1.5)

HO5-001(1)(0.8)

HO5-002(1.4)(1.1) HO5-003

(0.9)(0.9)

HO5-004(1.3)(1.4)

HO5-005(2.1)(2.4)

N1-184(1.2)(3)

N1-238(1.6)(3)

N1-240(1.5)(4)

N1-262(1.4)(2)

N1-265(1.6)(2)

N1-289(1.8)(3)

HO-454(26.6)(15)

N1-131(41.5)(59) N1-138

(48.6)(20)

N1-164(35.7)(22)

CB-15(26.4)(NA)

HO-433(28.5)(36)

N1-126(50.9)(99) N1-127

(93.3)(177)

N1-133(54.7)(53)

N1-135(63.2)(81)

N1-137(52.6)(99)

N1-281(80.5)(83)

< 2.2

2.2 ~ 6.0

6.1 ~ 22.4

22.4 ~ 50

> 50


AS,U (mg/Kg)

NOT-ANALYZED

(2.7)(5.3)

NA



CONTOURS

STREAMS

ROADS

STRUCTURES

PERMIT BOUNDARY






005398.005

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FUEL STORAGE

POND 1

MILL WATERTANKS

TRAILER PARK

SANDFILL NO.1

TP-421(2.9)(2)

TP-427(4.1)(3)

S1-011(5.8)(3)

S1-021(2.3)(13)

S1-032(3.8)(3)

S1-053(5.4)(3)

S1-065(4.3)(3)

P12-076(2.2)(8)

N1-323(2.6)(2)

N1-326(5.2)(4)

TP-424(3.8)(5)

TP-418(3.2)(2)

S1-027(4.4)(1)

TP-001(12.5)(13)

TP-425(8.9)(9)

N1-005(8.9)(5)

N1-018(21.7)(17)

N1-023(18.3)(71)

N1-030(6.5)(9)

N1-068(12.8)(256)

N1-101(12.7)(27)

N1-103(17.7)(18)

N1-129(7)(8) N1-140

(15.8)(21)

N1-092(13.2)(18)

P12-050(13.7)(12)

P3-061(17.3)(28)

S1-030(14.3)(11)

S1-043(6.7)(2) S1-044

(11)(2)

S1-049(16.8)(41)

S1-050(15.7)(5)

S1-063(20.8)(7)

TP-423(2.1)(2)

TP-426(1.1)(2)

TP-420(0.9)(1)

N1-266(1.7)(58)

N1-316(1.3)(1)

P12-063(1.2)(1)

TP-419(0.9)(1)

TP-027(2.1)(2)

TP-024(2.1)(17)

S1-009(1.8)(2)

S1-017(2.1)(3)

S1-028(0.8)(1)

S1-041(1.3)(2)

S1-051(1.9)(1)

TP-009(33.2)(139)

TP-013(33.2)(44)

P12-024(26.9)(16)

N1-047(31.3)(28)

P12-071(49.9)(74)

N1-020(46.2)(52)

N1-028(26.3)(80)

N1-044(47.9)(58) N1-049

(29.3)(664)

N1-065(28.4)(59)

N1-067(38.3)(55)

N1-070(26.1)(50)

N1-093(35.7)(57)

N1-131(41.5)(59)

S1-068(47.3)(41)

N1-138(48.6)(20)

CA-18(40.4)(NA)

P12-014(96.9)(48)

P12-023(62.4)(29)

P12-035(78.5)(86)

P12-047(73.1)(38)

P12-058(655)(1080)

P12-069(161)(166)

P12-077(487)(423)

P12-082(177)(339)

N1-016(80.8)(758)

N1-026(68.4)(199)

N1-046(58.8)(176)

N1-090(84.8)(122)

N1-095(75.7)(209)

(93.3)(177)

N1-133(54.7)(53)

N1-135(63.2)(81)

N1-137(52.6)(99)

CA-17(185)(NA)

< 2.2

2.2 ~ 6.0

6.1 ~ 22.4

22.4 ~ 50

> 50


AS,U (mg/Kg)

NOT-ANALYZED

(2.7)(5.3)

NA

1. SURFACE TOPOGRAPHY GENERATED FROM AERIALPHOTOGRAPHS DATED MAY 2007 BY COOPER AERIAL SURVEYSCO. NEW MEXICO WEST STATE PLANE COORDINATES, NAD 83


CONTOURS

STREAMS

ROADS

STRUCTURES

PERMIT BOUNDARY






005398.006

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POND 2

SEDIMENT PAD

NECR-2DRAINAGE

SANDFILL NO. 3

POND 3

POND 1

1-X PLANTVENT 8

VENT 3

P12-019(4.7)(8) P12-020

(2.2)(2)

P12-041(3)(4)

V38-031(2.2)(2)

P3-027(4.7)(19)

V38-410(3.1)(3)

P3-057(2.8)(5)

P3-063(3.8)(9)

CA-02(5.4)(NA)

CA-03(4.5)(NA)

CA-05(3.7)(NA)

CA-08(3.5)(NA)

V38-402(2.9)(7)

P12-076(2.2)(8)

V38-002(3.6)(5)

S3-027(4.5)(3)

SP-011(3.8)(27)

NE-005(2.6)(2)

S3-006(17.4)(119)

CA-16(6.2)(NA)

S3-026(19.6)(7)

SP-005(17.7)(14)

SP-020(12.8)(18)

V38-006(13.2)(19)

N1-005(8.9)(5)

N1-023(18.3)(71)

P12-056(11.2)(10)

P3-001(18.1)(42)

P3-015(18.8)(11)

P3-037(7.7)(10)

P3-038(20.9)(35)

P3-046(19.5)(34)

P3-061(17.3)(28)

CA-09(6.6)(NA)

S3-002(15.3)(43)

S3-008(1.4)(3)

SP-018(1.5)(2)

V38-034(1.4)(1)

V38-400(0.6)(1)

V38-401(0.9)(2)

V38-403(0.8)(1)

V38-405(1.2)(2)

V38-409(1.9)(2)

V38-411(0.5)(1)

V38-412(1.4)(2) V38-413

(1.8)(3)

V38-414(1)(119)

V38-415(0.8)(1)

V38-416(0.6)(1)

V38-417(1.1)(1)

N2-096(1.4)(4)

N2-109(1.6)(2)

NE-004(1.3)(5)

P12-009(1.7)(2) P12-011

(1.1)(1)P12-012(1.5)(2)

P12-032(1.6)(2)

P12-042(1)(2)

V38-408(0.6)(1)V38-407

(1.1)(1)

V38-406(0.3)(1)

P3-042(1.4)(2)

S3-017(1)(1)

CA-01(1.9)(NA)

CA-04(1.8)(NA)

CA-06(1.1)(NA)

CA-07(1.5)(NA)

CA-11(1.9)(NA)

S3-022(1.2)(1)

S3-012(1.4)(2)

V38-404(1.4)(1)

S3-004(1.4)(4)

SP-025(36.7)(22)

SP-026(27.1)(33)

SP-006(38.8)(22)

P12-024(26.9)(16)

P3-059(26.9)(63)

N1-044(47.9)(58)

P3-065(39.6)(68)

N(

CA-10(31.6)(NA)

S3-009(31.9)(41)

S3-010(33.4)(136)

S3-024(27.4)(7) S3-025

(26.9)(11)

SP-008(25.8)(20)

SP-015(33.4)(35)

P12-014(96.9)(48)

P12-023(62.4)(29)

P12-035(78.5)(86)

P12-047(73.1)(38)

P12-058(655)(1080)

V38-019(137)(358)

P12-069(161)(166)

P12-077(487)(423)

P12-082(177)(339

P3-007(259)(1020)

P3-014(875)(3970)

N1-016(80.8)(758)

N1(6

CA-17(185)(NA

S3-005(66.9)(86)

S3-014(123)(396)

SP-007(106)(92)

SP-012(118)(363) SP-014

(236)(366)

SP-021(85.6)(1640)

P3-029(312)(1240)

SP-022(104)(86)

< 2.2

2.2 ~ 6.0

6.1 ~ 22.4

22.4 ~ 50

> 50


AS,U (mg/Kg)

NOT-ANALYZED

(2.7)(5.3)

NA



CONTOURS

STREAMS

ROADS

STRUCTURES

PERMIT BOUNDARY






005398.007

�

��

��

��

�

��

��

��

�

��

��

��

��

��

MAGAZINE

BONEYARD

NON-ECONOMICMATERIALSTORAGE AREA

NECR-2

NECR-2DRAINAGE

SANDFILL NO. 3

SANDFILL NO. 2

BY-002(2.2)(2)

CA-02(5.4)(NA)

(4.5)(NA)

CA-05(3.7)(NA)

S2-003(3.3)(4)

S2-015(4.4)(3)

N2-018(3.6)(2)

N2-037(4.6)(7)

N2-083(3.1)(3)

NE-005(2.6)(2)

S2-019(21.6)(28)

S3-006(17.4)(119)

S2-016(6.1)(3)

S3-026(19.6)(7)

N2-056(11.9)(4)

N2-069(8.9)(10)

CA-12(6.8)(NA)

CA-13(8.9)(NA)

CA-14(10.3)(NA)

CA-15(9.2)(NA)

S2-007(16.1)(7)

S2-011(6.2)(5) S2-012

(6.2)(26)

S3-002(15.3)(43)

S3-008(1.4)(3)

BY-004(1.6)(1)

N2-004(1.2)(2)

N2-033(2)(5)

N2-050(1.2)(2)

N2-096(1.4)(4)

N2-103(1.5)(2)

N2-109(1.6)(2)

NE-001(1.2)(1)

NE-002(1.7)(5)

NE-003(0.9)(1)

NE-004(1.3)(5)

S3-017(1)(1)

BY-003(1.1)(2)

CA-04(1.8)(NA)

CA-11(1.9)(NA)

S2-004(2)(2)

S2-006(1.2)(1)

S3-022(1.2)(1)

S2-010(1.2)(1)

S3-012(1.4)(2)

S2-014(0.8)(1)

S3-004(1.4)(4)

CA-10(31.6)(NA)

BY-001(45.9)(17)

S2-017(36)(9)

S2-020(27.7)(41)

S3-009(31.9)(41)

S3-010(33.4)(136)

N2-020(38.1)(66)

N2-027(35.3)(12)

S3-024(27.4)(7) S3-025

(26.9)(11)

N2-039(35.4)(30)

N2-052(23)(44)

N2-071(40)(46)

S3-005(66.9)(86)

N2-015(97.2)(107) N2-017

(55.3)(49)

S3-014(123)(396)

N2-035(160)(370)

< 2.2

2.2 ~ 6.0

6.1 ~ 22.4

22.4 ~ 50

> 50


AS,U (mg/Kg)

NOT-ANALYZED

(2.7)(5.3)

NA



CONTOURS

STREAMS

ROADS

STRUCTURES

PERMIT BOUNDARY






005398.008

APPENDICES

005399

APPENDIX A

GAMMA SURVEY CALIBRATION DATA, SURVEY FIELD FORMS AND REGRESSION ANALYSIS

005400

AVM Environmental Services Inc. Grants NM, 87020

Rate MeterJScaler Calibration

Model I!-~L!,~, 22 2 I

Calibration Source L uck[un P,l 508 ; /~ ,q 513 (finla J,^r 9, o L)

Threshold (input sensitivity), Found at 1 o o mV Left or Set at i o 0 mV

Window, Inlout 0-4 Window ~ l p mV

Pulser Amplitude Set @ 2 ~ 0 mV

Calibration Point (Pulser Setting) cum x multi~lier

As Found Reading

2LI LPw 2 L o 1 CPrq 2 Sr Q ~ O L P ~ I 3521, " /~3cr rn

Left or Set Reading

H V S ~ ~ @ 900 VDC

n .

7 / ~ l . / g L -- Date Calibrated B / /

005401

LUDLUM MEASUREMENTS, INC. CERTIFICATE OF CALIBRATION POST OFFICE BOX 8 10 PH. 325-235-5494

501 OAK STREET FAX NO. 325-235-4672

Model No. / Serial No. 500 / ) J $'s 13 SWEETWATER, TEXAS 79556, U.S.A.

CUSTOMER AVM ENVIRONMENTAL SERVICES CUSTOMER PO /C/d ORDER NO. 2571 38 1 303202

Date 14-Jun-06 Cal Due Date 14-Jun-07 Cal. Interval 1 Year Procedure M500. Rev. 5 /

New Instrument Instrument Received @within Tolerance Out of Tol. Requiring Repair Other-See Comments

T. 71 "F RH 42 % Alt 702.8 mm Hg d ~ e t e r Zeroed d e c h a n i c a l Check

PULSE WIDTH

Acceptable As Found As Left Range (ps) f 10%

Reference As Found As Left Acceptable Voltage Voltage Reading Voltage Reading Range k 5%

475 - 525

2000 V 1900 - 2100

G OF 0-99 IS ACCFPTABI F FOR INSTRUM

COMMENTS:

NEG PULSE

POS PULSE

PULSE AMPLITUDE

Ludlum Measurements, Inc, certifies that the above instrument has been calibrated by standards traceable to the National Institute of Standards and Technology. The calibration system conforms to the requirements of ANSIINCSL 2540-1-1994 and ANSI N323-1978.

Reference Instruments:

Frequency Counter Model Z Q D ~ SIN Gal Date 6 - 7 - 06 Oscilloscope Model v' 131; 0 SIN 908Y IO l CalDate 2 . 2 - Voltmeter Model f l dA@ 7 5 SIN 57390613 Cal Date J,7-/?, fig

I . S' 2 - Y

As Found As Left Reference Amplitude Amplitude Acceptable Amplitude Reading Reading Range * 10%

Calibrated By: Date )l/. d-6

Reviewed By:

Thls certiflcate shall no1 be reproduced excepl In full, wlthoul the wrltlen approval of Ludlum Meoswemenls. InC. FORM C 16- 1 04/09/2003

1 v I 0 0 mV

10 mV

1 mV

As Found As Left Reference Amplitude Amplitude Acceptable Amplitude Reading Reading Range * 10%

/ , 7 J , 6

4 V

400 mV

40 mV

4 mV

1.5-1.9

< 2.25

J IY

/oo m J 10 fii/ / * / / M

'-f,Z 1/ Yso mv 42 rnd $ 2 ~ I/

/ L/

/DO mu I D rnd I , / f i d

0.9 - 1.1

90 - 110

9 - 1 1

0.9 - 1.1

#, 2 v cfm m (/

‘ f R m d +,A M d

3.6 - 4.4

360 - 440

36 - 44

3.6 - 4.4

005402

Attachment B, SOP #RAD-01 AVM Environmental Services Inc.

ScalerlRatemeter - Detector Calibration Form

ScalerlRatemeter - -!fd -bulfJ.L #- ~e tec to r -";3n-~ djII3 - Qcp5-j,-L- 3;j

Source: Strength: 1%.

ScalerlRatemeter Threshl~old set @ 1 6'6' mV, Window INIOUT t$k.lT , Window & mV

Reading, CPM (Source)

Reading, CPM Background reading at designated function (Background) check location in office.

Count # Reading (CPM)

1 75sg 2;71* u q 2 1k4 V a-i I Q

3 75-72 '2i.e Ro 4 759 P avLl 5 7139 2$b$

Average 7-59 b A b'7 9

Count Readings with 1 percent U,O, can

directly under shielded probe on designated function check location in office.

5057 Count # SibJ 1

Reading (CPM)

- 2"h & b P 7" 9-31 .- /uc, 2q7

VDC (Instrument) VDC (DVM Fluke 8020B)

Input Sensitivity (THR), mV / c d

Function Check with 1 percent U,08 ore 111 can. Can Directly under the detector.

Acceptable Function check range is: '7' L3/ to /0&;?4/-7 CPM

Count Readings for Calibration Pad GPL (87.78 pCi/gm Ra-226) Bare (Uncollimated)

#I ~ L C " C ~ ' cpm #2 7 gq ' ib CPm

Collimated # I 395-95 cpm

#2 3 Y o' ig cpm #3 .7 $ 73 5- & cpm

#4 7 5 r 7 5- cpm #5 7 (* - I 7 q cpm

Average 7 b 15 cpm Eff(avg cpm/87 78 pcllgrn 3 G. L cpm/pCi/gm

#3 3cJ3i;L cpm

#4 Sqlbq CPm #5 3 9 3 g g CPm

Average sLf ;1Y I, cpm Eff d- i g cpmlpC1lgm

5-. 2 b - L> 7 Date

005403

005404

MDC CALCULATION, SPA-3, #408522-33

9.1 MDC for Static Garmna Radiation Measurement (for 0.05 probability for both false positive and false negative errors)

MDC = C x [3 + 4.65 (B"~)]

Where

C = Detector calibration factor, pCi/gm/cpm (for this survey as determined above). B = Number of background counts that are expected to occur while performing a sample measurement.

background count from the function check for the bare detector is 7596 cprn & the collimated detector is 2674 cpm, and the slope value is 0.001 15 pCi/gm/cpm (866 cpdpCi/gm) for the bare detector and 0.00223 pCi/gm/cpm (448 cpdpci lgm) for the collimated, then the MDC for a one minute static measurement would be:

MDC = 0.001 15 pCi/gm/cpm x [3 + 4.65 (7596 cpm)0'5 ] = 0.47 pCi1gm for the bare detector MDC = 0.00223 pCilgm/cpm x [3 + 4.65 (2674 cpm)0'5 ] = 0.54 pCi/gm for the collimated detector

9.2 MDC for Scan Gamma Radiation survey

The scan MDC is assumed for a scan rate of about 3 feet per second and a one second interval (based on a detector that is focused on about 36 - 42 inches diameter area at about 18 inches from ground surface). Also, a surveyor efficiency (p) of 0.5 is assumed. First calculate the Minimum Detectable Count Rate (MDCR) as follow:

MDCR = d' x (biO.') x (60li)

Where

d' = value for true positive and false positive proportion. A value of 1.38 will be used for 95% true and 60% false positive proportion.

bi = number of background counts in the interval i. ( cpd60 seclmin for one second interval).

For a detector background count of 7596 cpm, the MDCR for one second interval would be:

MDCR cprn = (1.38 ) x (7642 cprn x 1 sec x 1 mid60 ~ec ) ' . ~ x 60 seclmin = 932 cpm.

Then calculate the MDCR ,,,yo, using surveyor efficiency (p) of 0.5 as follow:

MDCR ,,,yo, = MDCRI~'.' = 945 ~ ~ m / ( 0 . 5 ~ . ~ ) = 1,3 1 8 cpm.

From the MDCR calculate the scan MDC using the following:

Scan MDC = MDCR cprn x C, pCi/gm/cpm

Where C = Detector calibration factor, pCi/gm/cpm (for this survey as determined above).

For a C of 0.001 15 pCi1gdcpm (847 cpmIpCilgm), the Scan MDC would be:

Scan MDC = 1,3 18 cprn x 0.001 15 pCi/gm/cpm = 1.52 pCi1gm

MDC for the collimated detector can be calculated using same formula. For a bkg rate of 2674, and slope value is 0.00223 pCi/gm/cpm (462 cpm/pCi/grn), a scan MDC (3 ft per second) would be 1.74 pcilgm

005405

Layout of Grants Calibration Site

Site

0 Pad GPB

Model 0 Pad GPT 0 GBAlGBB

Models 0 GBUIGBM 0 GBTIGBK

0 PadGPH

A

Pad GE2 PadGP? /y 0

-~- /@+'

O GL Models 0 GH 0 0 Pad GPK

9 e Pad GE4 P

Detail Map 17

June 1994

005406

Grants P Pads

2 in. i f

i - --------- -------- --- f

_______________-------

2 in. F'" 1

Plan

Table &5. Assigned Parameters

Section

Dry Bulk Partial Pad Concentration ( ~ C i l g ) ~

Density Density Designation RR-226 Th-232 K 4 0 (C#cm3)b H20 ( g ~ c r n ~ ) ~

0.58 k 0.82 0.01 k 0.06 51.53 k 1.46 1.96 0.127 & 87.78 k 14.32 0.50 k 0.10 15.58 & 1.02 1.90 0.165

G PH 375.74 k 45.14 0.61 & 0.10 15.93 1.62 1.91 0.142

GPT 6.57 2 3.14 30.23 k 0.80 14.94 k 1.02 1.89 0.146

'Uncertainties are 95 percent confidence level. Assigned values taken from George, Novak, and Price (1985). buncertainties for these values have not been determined. 'Pad does not have a hole as shown above. 'value not assigned.

June 1994

005407

AVM Environmental Services, Inc. ScalerIRatemeter - 2" x 2" Nal Detector Function Check

UNC's NECR Mine Site 4 .S--.iX -. 0 7

ScaIerlRaterneter ID Ld/d&Vl a Z L / , , JR* iP7kL Function Check Source ID 1% U,O,Ore in Sealed can Lo 7 7 y / 15- (a@J-=zJ

2" x 2" Detector ID 3 52 a ~08j=r~ -= Acceptable background Count (cpm) Range (20%) 2/37 to 3209 ([,//,~L.J@Q Acceptable Source Count (cprn) Range (20%) '7Qk3j to /@45&.c7

Note: (1) Battery Voltage for Ludlum 2221 must be >5.3 volts; (2) Threshhold must be at 100 mV; (3) Window Position must be OUT; (4) C.C. for Eberline ESP scaler must be 1.0+00

005408

. - AVM Environmental Services, Inc.

Micro R Meter Function Check Form UNC's NECR Mine Site

Micro R Meter: Ludlum 19, SR#76248 Function Check Source ID: 1% U3O8 Ore in Sealed can &zdJrexf~+J 6, L ~ / / u - ..I ?/&/./

Function Check @ Calibration 90 .../$b & 7 4n Acceptable Function Check Reading (uR1hr) Range (20%) 7%- to i G e

Note: (1) Battery Voltage must be within BAT TEST Range (2) Function Check Source must be placed in the circle on the front side of the meter

005409

AVM Environmental Services, Inc. Gamma Radiation Survey @ UNC's NECR Mine Site

Static Gamma,Radiation Survey Field Form

5pi3 .J , or r z~ . -3$ u M ' L JCT 7 ~ g ~ ~ ~ ~ ~ ~ ~ ,. ,- Instrumentation : ScalerIRatemeter ;-"' ' J' >*zy

Instrument Calibration Date: , Inshument Daily Function Check P:rformed: L/ 2"x2" NaI Detector

suwey h e m n i t Decsripaon !i-'?lq',f /"/&:> / k. J/Y

~.

Survey Date

i (

1 1

,.3

:

6 '

# I

]/l[f*/dll

' I

r ' l

l i

i g

;

,

Rad Survey Point IDlDescription

VENT38- 101

VENT38- 102

VENT38- 103

VENT38- 104

VENT38- 105

VENT38- 106

VENT38- 107

VENT38- 108

VENT38- 109

VENT38- 110

VENT38- 1 ! !

VENT38- 1 12

VENT38- 113

VENT38- 114

VENT38- 1 15

VENT38- 116

GAMMA RAD SURVEY POINT Coordinate (NAD Gamma Radiation

Reading, CPM

$ 3 6 4 385'-6 3 1 8 5 4 " - j h'C .PA

?{f /fJ yr(.33 .--A7"f 3

3x7'/"9 9405 - 5 / 6 7

Y8' Yd 3.79 / 4" / 73

P & d . #c eJA $3

1983 NM

Northing (feet) CornmenuMotes

Lot ID

0

0

1: 400

40 1

0

0

0

0

0

0

0

," 402

403

0

0

0

West)

Easling (feet)

VSP Grid Point (NAD 1983 NM

Northing (feet)

1,695.023.5

1,695,023.5

1,695,092.7

1,695,092.7

1,695,092.7

1,695,092.7

1,695,092.7

1,695,092.7

1,695,092.7

1,695,092.7

1,695,092.7

1,695,162.0

1,695,162.0

1,695?162.0

1,695,162.0

1,695,162.0

West)

Easting (feet)

2,520,486.9

2,520,566.9

2,520,206.9

2,520,686.9

2,520,046.9

2,520,126.9

2,520,366.9

2,520,446.9

2,520,526.9

2,520,766.9

2,520,846.9

2,520,246.9

2,520,646.9

2,520,086.9

2,520,166.9

2,520,326.9

005410


Static Gamma Radiation Survey Field Form

Instrumentation : ScalerEatemeter liA/kl rzr , f & ~ 7 ~ ~ c t o r , j f i ~ 3 t' ,, qc:vjyry3 :y-z,d" " 7

Instrument Calibration Date: - , Instrument Daily Function Check Performed: &'

2"x2" NaI Detector Collimated L.." Yes or No.

Survey AreatUnit Decsription Tm{ . S' I 4iv&; L.. . 3 1 ~ ~ I

Survey Dale 'Oil

Lot ID

Rad Survey Point ID/Description

GAMMA RAD SURVEY POINT Coordiuate (NAD 1983 NM West) Gamma Radiation

Reading, CPM

VSP Grid Point (NAD 1983 NM West)

Norfhing (feet) 1 Eating (feet) Northing (feet)

I

CommentsNotes Easting (feet)

005411



Instrumentat~on : s c a ~ e r m a t e m e t e r / r d / w ~ ~ i / ~ ~ ~ ~ e t e c t o r / I

Instrument Calibrat~on Date. <--2(; 422 , Instrument Daily Funct~on Check Performed: J 2"x2" NaI Detector Collimated Yes or No.

Survey AreaAJnit Decsription

Technician 0 4 w i 4 b ~ Reviewed by ///L{

I I VENT~I- 161 1 0 1 1,695,439.2 12,519,926.91

Date

1 1 ,5-/0]

/ "

t (

I

Lot ID

0

0

0

i3409

Rad Survey Point ID/Desc+itian

VENT38- 157

VENT38- 158

VENT38- 159

VENT38- 160

GAMMA RAD SURVEY POINT Coordinate (NAD 1983 NM West) Gamma Radiation

Reading, CPM

333 / 3 2 3 0

3 9// .t+zz2#

Northing (fact) CammentslNotes

Easting (feet)


Northing (feet)

1,695,369.9

1,695,369.9

1,695,369.9

1,695,439.2

Earling (feet)

2,520,766.9

2,520,846.9

2,520,926.9

2,520,246.9

005412



Instrumentation : Scaler/Ratemeter -etector

Instrument Calibration Date: .~T-ZL~'.."'? r

, Instrument Daily Function Check Performed:

2"x2" Nal Detector Collimated /'Yes r No. ~uL.t,$@ 3Rd Survey Area/Unit Decsription , I -

Reviewed by

005413



< Instrumentat~on scalermatemeter [,d b+. S 3 3- 1 ( 1 ~ x / A'JeteCtor 5fi? - 5 Li 0 Y 5-2 3 - 3 2

Instrument Cal~bratlon Date 5' %L, + ' ' I , Instrument Dally Funct~on Check Performed b@/

2"x2" NaI Detector ~ol l lmated Yes or - No.

Survey Areatunit Decsript~on \,fg -i & //J 1%

005414



Instrumentat,on : , c a , e r f i t e , e j d C h e , , o r 1% 9 3 + ~ A&/ - J V L Y ~ J ~ 2,. -Sjl

Inshument Cal~brat~on Date: Instrument Dady FunLon Check Performed: d

2"x2" NaI ~ e t e c t o r ~ol l lmated Yes or No.

Survey Area/Unit Drcsription 'zk' /" A

Survey Date


GAMMA RAD SURVEY POINT Coordinate (NAD 1983 NM West) ad survey point

IDIDescription Gamma Radiation

Reading, CPM Northing (feet) Northing (feet)

'Oil

ID Cornrncnts/Notes

Eating (feet) Eating (feel)

005415



'LL 5 f/&. , 2 .,,y L... &4.. 2 ff y~o&--s-.2& -33 Instrumentation : ScalerfRatemeter /,% " 2 2 2 I

,q -h <v - ,/ "

Instrument Calibration Date: , Instrument Daily Function Check Performed: z.

2'x2' Nal Detector ~ol l lmated L ~ e s or 9. Survey AreaAJnlt Decsnptlon Iry 1 bL+'k.+.

Gamma Radiation

Technician Reviewed by /p&"~,{

005416



uc S 7Si ~nstrumentation : ~ c a l e r ~ a t e m e t e r l- cf IWWF ,2:2 21 ' , d t e c t o r SP~, 4 30s 3~~ .. 39

Instrument Calibration Date: 5 .- 2 E, .- b '7 , Instrument Daily Function Check Performed: / /' 2"x2" NaI Detector Collimated v Yes or No.

I ,

Survey Araiuni t Decsription LC%. / r i b., L

005417



. I ,

Instrumentation : Sca lcr /Ratemeter~ ,&~l / ;X =-/ d8?F32), Detector [email protected] I #fl#I , 408527-',-33

Instrument Calibration Date: >j'asb .7 , Instrument Daily Function Check Performed: ./c P

2"x2" NaI Detector collimated Yes or No.

Survey AreaAJnit Decsription &O~"TG

Survey Date Soil

L0c ID

Rad Survey Point 1DiDescription

GAMMA RAD SURVEY POINT Coordulale (NAD 1983 NM West) Gamma Radiation

Reading, CPM Northing (fect)

COmmeutsMotes


Ensting (feet) Northing (feet) Ensting (feet)

005418



Instrumentation : , Detector 5k?de7 2 , /v&Z;, Ycbi5k?-- 3 3 , Instrument Daily Function Check Perfomed: i/c

S I 2"x2" Nal Detector Collimated Yes or No.

Survey Areamnit Decsription

005419



Instrumentatton , Detector . (#$-3 , /I/&: . L/L!~b"LZ--?~ Instrument Caltbration Date: 572% 7f , Instrument Daily Functton Check Performed. wf

2"r2' NaI Detector Coil~mated Yes or _ No

Survey AreaAJntt Decsript~on /A&@

Survey Date Rad Survey Point IDlDescription

HOME- 50 1 0 1 1,696,877.5 )1,522,965.01

HOME- 48

HOME- 49

soil

Loc ID

GAMMA RAD SURVEY POINT Coordinate (NAD 1983 NM West)

-

2,522,845.0

2,523,645.0

2,524,045.0

1,696,808.3

1,696,808.3

1,696,808.3

-

HOME- 155 441

HOME- 156 442

Gamma Radiation Reading, CPM


Northing (feet) 1 Easling (feel) Northing (fcet)

HOME- 157

0

o

I

Reviewed by -

Comments/Notes Eating (feet)

-

443

' t

'(

506 y 567g

1,696,s 10.7

1,696,877.5

2,523,365.0 HOME- 5 1

HOME- 52

HOME- 53

2,524,150.6

2,522,885.0

0

gii'dk -5)s k . ~

1,696,877.5

0

0

1,696,877.5

1,696,877.5

2,523,445.0

2,523,605.0

5380 5& qq

005420



i

Instmentat~on : Scaler/Ratemeter /:dd.kLqq ym/ki&&), Detector >p&- 7 ; ,4491 ,, qd @ 522-3.3 Instrument Calibration Date: ~;.-/&/$7 , Instrument Daily Function Check Performed: b4

I

2"r2" NaI Detector Collimated VF 4 e s or- No.

Survey A r e a n i t Decsript~on

Technician Reviewed by q d : ~

005421



Instnunentation : ScaleriRatemeter /g;&- 2 ~ z 1 / ; ~ k 4 ~ ) , Detector s#?-3 /yqc , ~/~t%-&2_-3 J

Instrument Calibration Date: f / Instrument Daily Function Check Performed: /' I

i"x2' N d Detector Collimated wf i e s or - No.

Survey Areamnit Decsrlption ihflq~.

005422



instrumentation : scalerinatemeter/i,&I.~ ~ Z I ! ~ S 7 ~ 5 2 $ ) , Detector 9 ! 3 ~ 4 / , , V~C--?;I Instrument Calibration Date: , Instrument Daily Function Check Performed: c(

2"xZ" NaI Detector Collimated No.

Survey AreaAJnit Decsription

1

/ / /

/ / / L / ~ ]

HOME- 128

HOME- 129

HOME- 130

HOME- 172

0

0

433

457

1,697,501:l

1,697,501 1

1,697,501.1

1,697,501.1

2,523,885 0

2,523,965 0

2,524,045.0

2,523,325.0

( <'k Y ! / /&/L"

2 WoS' 6 3278

005423



/ /' Instrumentation : ScalerIRaterneter ,.:,O6bmq zzrt / ~ t ~ / " d + ) ~ ~ t ~ ~ t ~ ~ - 3 , / & &it?5-2-~-33

.- Instrument Calibration Date: 5/3i/Ly? , hshurnent Daily Function Check Peiormed: by

i 1 ' x l U N ~ I Ddector collimated ;/ 6 s or - NO.

Survey A r e d n i t Decsription /%,?')fi

Technician

Gamma Radiatiou

// ~,/i,j? /

1 1

HOME- 176

HOME- I42

HOME- 143

461

0

o

1,697,639.6

1,697,708.9

1,697,708.9

2,523,565.0

2,123,525.0

2,523,685.0

5' z. 9 I $?& 5' i~./ 7

005424


Static Gamma Radiation Survey Field Form -~-.

~nstrumentation : ~calermatemeter /.w I 322 1 ( i C ~ * ~ t $ k ~ ~ ~ ~ ~ ~ ~ SPA- 3 iJ o X 4 2 3 -3.3

Instrument Calibration Date: :>'. .. 2 L - c') 7 , Instrument Daily Function Check Performed: L/"

214x2" Nal Detector collimated Yes or - No.

Survey Areaillnit Decsription ,.., e 5,' !/-4

Soil VSP Grid Point (NAD 1983 GAMMA RAD SURVEY POINT Coordinate (NAD

Survey Date Rad Survey Point NM West) 1983 NM West) Gamma Radiation

IDDescription Reading, CPM CommentsR*lotes

LOC ID Northing (feet) Easting (feet) Northing (feet) Easting (feet)

/ / /$ / f i '7 HOME- 178

L c' HOME- 179

1Y HOME- 180

1 I HOME- 181

005425



Instrumentation : ScalerlRatemete //ac>, i d o 8 f ; - . ~ 2 - 3 3

Instrument Calibration Date: 5' . .2 L o 7 , Instrument Daily Function Check Performed: d 2"x2" NaI Detector Collimated b/ Yes or No.

r c'l@ (I &$ Survey Areani t Decsription ,

I NECR-I SO:

Gamma Radiatton Reading, CPM

77&( f 'ghfi / ~ 1 8 3 *547&

$I%/&

Survey Date

b / / y / ~ 7 I

6 f

dt

dl

[ /

I

CommentsNotes

,07,2/4 ,.4fJ*flf<

GAMMA RAD SURVEY POINT Coordinate (NAD

NECR-I SO:

NECR-1 SO:

NECR-1 SO:

NECR-1 SO:

NECR-I SO:

NECR-1 SO:

NECR-1 SO:

NECR-1 SO:

NECR-I SO:

NECR-I SO:

NECR-I SO:

NECR-I SO:

Rad Survey Point IDlDescnpt~on

NECR-I SO: 352

NECR-I SO. )s 3 NECR-1 SO: j<t/

NECR-I SO: " * I <,." NECR-I SO. "ScJ NECR-1 SO:

NECR-I SO.

NECR- I SO:

NECR-1 SO:

NECR-I SO:

1983 NM

Northing (feet)

T

So11 Sample LOC ID

West)

Easting (feet)

005426

Figure A-3Gamma Radiation Level to Surface Soil Ra-226 Concentration Regression Analysis for Supplemental Radiation Survey

SPA-3 #408522-33 2x2 NaI Detector (0.5 inch Lead Collimated)

y = 0.0013x - 4.5378R2 = 0.9259

0.0

4.0

8.0

12.0

16.0

20.0

24.0

28.0

32.0

0 2,000 4,000 6,000 8,000 10,000 12,000 14,000 16,000 18,000 20,000 22,000 24,000 26,000

Gamma Radiation Level (CPM)

Ra-

226

Con

cent

ratio

n (p

Ci/g

m)

2.24 pCi/gm equivalent to 5214 CPM

005427


Soil Sample Loc ID

Gamma Radiation Level (cpm)

Ra-226 Lab (pCi/gm)

Toal Uranium Lab (mg/kg)

vent-103 400 3,915 0.6 1.00vent-104 401 3,565 0.9 2.09vent-112 402 4,884 2.9 7.41vent-113 403 3,791 0.8 0.98vent-124 405 4,432 1.2 1.65vent-136 406 4,155 0.3 0.51vent-147 407 5,661 1.1 1.30vent-148 408 3,195 0.6 0.64vent-160 409 4,222 1.9 2.11vent-166 410 5,758 3.1 2.87vent-170 411 3,384 0.5 0.60vent-179 412 4,901 1.4 2.32vent-180 413 4,315 1.8 2.69vent-185 415 3,800 0.8 1.07vent-192 416 3,546 0.6 0.48vent-196 417 4,039 1.1 1.19tp-103 418 7,650 3.2 1.94tp-107 419 4,781 0.9 1.07tp-115 420 5,663 0.9 1.36tp-125 421 5,628 2.9 2.44tp-129 423 6,246 2.1 2.30tp-133 424 8,706 3.8 4.73tp-137 425 11,143 8.9 8.55tp-127 427 6,995 4.1 2.55

home-14 428 10,488 9.2 24.00home-57 429 7,577 4.6 5.66home-86 430 6,206 2.9 4.48

home-105 431 20,401 18.7 18.20home-112 432 5,606 3.4 49.90home-130 433 24,105 28.5 36.00home-146 434 8,176 5.3 4.54home-148 435 5,697 2.5 7.26home-149 436 4,846 2.0 8.84home-151 437 5,169 5.4 20.60home-153 439 5,522 0.9 2.10home-154 440 5,186 2.5 5.44home-155 441 4,649 0.7 0.81home-156 442 5,064 1.5 3.05home-157 443 5,678 2.0 6.88home-158 444 5,794 2.9 3.15home-159 445 4,860 1.3 2.42home-160 446 5,121 1.7 3.56home-161 447 5,551 2.5 3.99home-162 448 14,628 17.1 22.60home-163 449 4,692 1.1 3.07home-164 450 4,461 0.9 1.59home-165 451 4,650 1.1 1.42home-167 452 5,588 4.1 4.58

Table A-1Regression Analysis Data

005428


Soil Sample Loc ID

Gamma Radiation Level (cpm)

Ra-226 Lab (pCi/gm)

Toal Uranium Lab (mg/kg)

Table A-1Regression Analysis Data

home-168 453 5,563 3.2 2.93home-170 455 7,166 9.5 11.70home-171 456 4,810 1.8 2.37home-172 457 6,388 4.4 4.17home-173 458 5,355 1.4 3.90home-174 459 6,374 2.5 2.57home-175 460 4,939 1.9 4.10home-176 461 5,291 1.2 1.76home-177 462 5,821 1.7 3.07home-182 463 7,526 4.8 6.24

home-152 438 10,242 1.3 13.30home-169 454 4,911 26.6 14.50

tp-147 426 14,800 1.1 1.80vent-123 404 14,930 1.4 1.36vent-184 414 43,297 1.0 119.00

Outliers

005429

APPENDIX B

LABORATORY ANALYTICAL REPORTS AND DATA VALIDATION RESULTS

005430

Page B-1

B1.0 DATA VERIFICATION REPORT B1.1 INTRODUCTION This report presents a summary of the verification results for the sample data collected as part of supplemental Removal Site Evaluation performed for United Nuclear Corporation (UNC) specific to the Northeast Church Rock (NECR) site. Samples were collected between November 5 and 8, 2007 and were analyzed by Energy Laboratories Incorporated of Casper, Wyoming. Samples were analyzed for the following:

• Total Uranium by U.S. EPA method SW846 6020 • Radium-226 by U.S. EPA method 901.1

The analytical results are expressed in terms of precision, accuracy, representativeness, comparability, and completeness (PARCC). This data evaluation is presented in terms of the PARCC criteria and was based on the specific criteria presented in the Quality Assurance Project Plan, United Nuclear Corporation, Northeast Church rock Site (QAPP), (MWH 2006): The analytical data were verified based on the results of the following data evaluation parameters or quality control (QC) samples:

• Compliance with the QAPP

• Sample preservation

• Sample extraction and analytical holding times

• Method and initial/continuing calibration blank (ICB/CCB) sample results

• Reporting limits (RL)

• Field replicate sample results

• Initial calibration (ICAL), initial calibration verification (ICV), and continuing calibration verification standards (CVS) results

• Interference check samples (ICS) (metals analysis only)

• Matrix spike/matrix spike duplicate (MS/MSD) sample results

• Laboratory control sample (LCS) and laboratory control sample duplicate (LCD) results

• Laboratory replicate results.

Data verification of the uranium data was performed by the MWH Project Chemist. Data verification of the radium-226 data was performed by Laboratory Data Consultants of Carlsbad, California. A level III verification was performed on all samples. The sample verification worksheet filled out by the MWH project chemist and the verification report by LDC are attached to this report. For a detailed discussion on how the data were evaluated refer to the original verification report in the RSE report. The results of the sample analyses are summarized in the main body of this report.

005431

Page B-2

B2.0 DATA VERIFICATION RESULTS B2.1 COMPLETENESS EVALUATION B2.1.1 Sampling Completeness B2.1.1.1 All samples and QC samples were collected as scheduled resulting in 100 percent completeness for this project. B2.1.2 Analytical Completeness B2.1.2.1 Based on the results of the data verification described in the following sections, all data are considered valid as reported. Analytical completeness was 100 percent, which met the 95 percent analytical completeness goal established in the QAPP. B2.2 REPRESENTATIVENESS EVALUATION Representativeness is a qualitative expression of the degree to which sample data accurately and precisely represent a characteristic of a population, a sampling point, or an environmental condition. Representativeness is maximized by ensuring that, for a given project, the number and location of sampling points and the sample collection and analysis techniques are appropriate for the specific investigation, and that the sampling and analysis program provides information that reflects "true" site conditions. Laboratory data were evaluated for representativeness by assessing compliance with the following:

• Laboratory compliance with the QAPP • Sample preservation • Sample extraction and analyses holding times • Method blank and ICB/CCB sample results • Reporting limits • Field replicates.

B2.2.1 Quality Assurance Project Plan Compliance Evaluation Based on the data verification, all samples were analyzed following the quality control criteria specified in the QAPP. B2.2.2 Sample Preservation Evaluation All samples were preserved as specified in the QAPP. B2.2.3 Holding Time Evaluation All analytical holding times were met. B2.2.4 Method Blank Evaluation No analytes were detected in any method blank B2.2.5 Initial and Continuing Calibration Blank Evaluation No sample data were qualified due to ICB/CCB data.

005432

Page B-3

B2.2.6 Reporting limit evaluation All sample data were reported to the RL established in the QAPP. B2.2.7 Field Replicate Evaluation The relative percent differences (RPDs) were less than the guidance RPD of 30 percent established in the QAPP except for one uranium result. The high RPD for these samples is due to the low concentration of uranium in the sample that even a small variation will create a large RPD. B2.3 ACCURACY EVALUATION Accuracy is a measure of the bias of a method or the level of agreement between a measurement and a known true value.

• ICAL, ICV, CVS results. • MS/MSD sample results • LCS and LCD results.

B2.3.1 Tune Standard Evaluation All tune standards were within the acceptance criteria specified in the laboratories’ SOPs. B2.3.2 Initial Calibration, Initial Calibration Verification, and Continuing Calibration

Verification Standards Evaluation All ICAL ,ICV and CVS results were within acceptance criteria. B2.3.3 Matrix Spike/Matrix Spike Duplicate Samples Evaluation All MS/MSD recoveries were within acceptance criteria. B2.3.4 Laboratory Control Sample/Laboratory Control Sample Duplicate Evaluation All LCD recoveries were with in the acceptance. B2.4 PRECISION EVALUATION Precision measures the reproducibility of measurements under a given set of conditions. B2.4.1 Matrix Spike/Matrix Spike Duplicate Sample Evaluation All MS/MSD RPDs were within acceptance criteria. B2.4.2 Laboratory Replicate Sample Evaluation All laboratory replicate RPDs were within acceptance criteria. B2.4.3 Field Replicate Evaluation The RPDs were less than the guidance RPD of 30 percent established in the QAPP except for one uranium result. The high RPD for this samples was due to the low concentration of uranium in the sample such that even a small variation created a large RPD.

005433

Page B-4

B2.6 Comparability Evaluation Comparability is a qualitative parameter that expresses the confidence that one data set may be compared to another. For this project, sample collection and analysis followed standard methods and the data were reported using standard units of measure as specified in the QAPP. In addition, QC data for this project indicate the data are comparable. As a result, the data from this project should be comparable to other data collected at this site using similar sample collection and analytical methodology.

005434

Page B-5

B3.0 DATA VERIFICATION SUMMARY Precision. Based on the MS/MSD sample, laboratory replicate sample, and field replicate results, the data are precise as reported. Accuracy. Based on the ICAL, ICV, CVS, MS/MSD, and LCS, the data are accurate as reported. Representativeness. Based on the results of the sample preservation and holding time evaluation; the method and ICB/CCB blank sample results; the field replicate sample evaluation; and the RL evaluation the data are considered representative of the site as reported. Comparability. Standard methods of sample collection and standard units of measure were used during this project. The analysis performed by the laboratory was in accordance with current EPA methodology and the QAPP. Completeness. Based on the results of the data verification, all data are considered valid as qualified.

005435

005436

005437

005438

005439

005440

005441

005442

005443

005444

005445

005446

005447

005448

005449

Analytical Method/Analytes: Metals Sample Collection Date(s): 11/05-08/07Laboratory: Energy Laboratories MW Job Number: Batch Identification: C007110543 Matrix: Groundwater : SolidField Duplicates: Home-SS-430 Home-SS-436

Home-SS-440 Home -SS-450Home-SS-460 TP-SS-420Vent38-SS-410

MS/MSD Parents: Home-SS-453 Home-SS-457Home-SS-433 Vent38-SS-405

Validation Complete: (Signature and Date) 02/22/08

SampleIdentification

LabIdentification

Hits(Y/N) Quals Comments

FootNotes

Home-SS-550 C07110543-001 Y FD of Home-SS-450

Home-SS-432 C07110543-002 YHome-SS-446 C07110543-003 YHome-SS-434 C07110543-004 YHome-SS-431 C07110543-005 YVent38-SS-410 C07110543-006 YHome-SS-450 C07110543-007 YVent38-SS-510 C07110543-008 Y FD of Vent38-SS-410

TP-SS-423 C07110543-009 YTP-SS-425 C07110543-010 YHome-SS-560 C07110543-011 Y FD of Home-SS-460

Home-SS-461 C07110543-012 YHome-SS-462 C07110543-013 YHome-SS-458 C07110543-014 YTP-SS-424 C07110543-015 YHome-SS-441 C07110543-016 YVent38-406 C07110543-017 YHome-SS-453 C07110543-018 YTP-SS-426 C07110543-019 YTP-SS-419 C07110543-020 YHome-SS-454 C07110543-021 YTP-SS-420 C07110543-022 YHome-SS-459 C07110543-023 YTP-SS-418 C07110543-024 YTP-SS-421 C07110543-025 YVent38-SS-402 C07110543-026 YHome-SS-438 C07110543-027 YHome-SS-439 C07110543-028 YHome-SS-449 C07110543-029 YHome-SS-430 C07110543-030 YHome-SS-463 C07110543-031 YHome-SS-447 C07110543-032 YVent38-SS-404 C07110543-033 YVent38-SS-407 C07110543-034 YHome-SS-443 C07110543-035 YHome-SS-451 C07110543-036 Y005450

Analytical Method/Analytes: Metals Sample Collection Date(s): 11/05-08/07Laboratory: Energy Laboratories MW Job Number: Batch Identification: C007110543 Matrix: Groundwater : SolidField Duplicates: Home-SS-430 Home-SS-436

Home-SS-440 Home -SS-450Home-SS-460 TP-SS-420Vent38-SS-410

MS/MSD Parents: Home-SS-453 Home-SS-457Home-SS-433 Vent38-SS-405

Validation Complete: (Signature and Date) 02/22/08

SampleIdentification

LabIdentification

Hits(Y/N) Quals Comments

FootNotes

Home-SS-530 C07110543-037 Y FD of Home-SS-430

Home-SS-433 C07110543-038 YVent38-SS-411 C07110543-039 YHome-SS-428 C07110543-040 YHome-SS-448 C07110543-041 YHome-SS-429 C07110543-042 YVent38-SS-400 C07110543-043 YHome-SS-436 C07110543-044 YHome-SS-437 C07110543-045 YHome-SS-536 C07110543-046 Y FD of Home-SS-436

Home-SS-440 C07110543-047 YHome-SS-435 C07110543-048 YHome-SS-442 C07110543-049 YHome-SS-540 C07110543-050 Y FD of Home-SS-440

Home-SS-452 C07110543-051 YVent38-SS-401 C07110543-052 YHome-SS-445 C07110543-053 YVent38-SS-408 C07110543-054 YHome-SS-444 C07110543-055 YHome-SS-455 C07110543-056 YHome-SS-460 C07110543-057 YHome-SS-457 C07110543-058 YTP-SS-520 C07110543-059 Y FD of TP-SS-420

Home-SS-456 C07110543-060 YVent38-SS-403 C07110543-061 YVent38-SS-415 C07110543-062 YVent38-SS-413 C07110543-063 YVent38-SS-416 C07110543-064 YVent38-SS-409 C07110543-065 YVent38-SS-417 C07110543-066 YVent38-SS-414 C07110543-067 YVent38-SS-412 C07110543-068 YTP-SS-427 C07110543-069 YVent38-SS-405 C07110543-070 Y

005451

Analytical Method/Analytes: MetalsLaboratory: Energy LaboratoriesBatch Identification: C07110543

Analysis Total MetalsSample ID Home -SS-550 Home-SS-432 Home-SS-446 Home-SS-434 Home-SS-431 Vent38-SS-410 Home-SS-450 Vent38-SS-510

Laboratory ID -001 -002 -003 -004 -005 -006 -007 -008

Hardcopy vs. Chain of Custody A A A A A A A A

Holding Time A A A A A A A A

Analyte List A A A A A A A A

Reporting Limits A A A A A A A A

Initial Calibration (All Methods) A A A A A A A A

Initial Check Blank (ICP & AA methods) A A A A A A A A

Continuing Calibration (All Methods) A A A A A A A A

Continuing Check Blank (ICP & AA methods) A A A A A A A A

Analysis Time A A A A A A A A

Method Blank A A A A A A A A

Laboratory Control Sample (all methods) A A A A A A A A

Laboratory Control Sample Duplicate (lab specific) N/A N/A N/A N/A N/A N/A N/A N/A

Matrix Spike/Matrix Spike Duplicate N/A N/A N/A N/A N/A N/A N/A N/A

Laboratory Replicate (lab specific) N/A N/A N/A N/A N/A N/A N/A N/A

Field Duplicate/Replicate A N/A N/A N/A N/A A A A

A indicates validation criteria were metN/A indicates not applicable

005452


AnalysisSample ID

Laboratory IDHardcopy vs. Chain of CustodyHolding TimeAnalyte ListReporting LimitsInitial Calibration (All Methods) Initial Check Blank (ICP & AA methods)Continuing Calibration (All Methods)Continuing Check Blank (ICP & AA methods)Analysis TimeMethod BlankLaboratory Control Sample (all methods)Laboratory Control Sample Duplicate (lab specific)Matrix Spike/Matrix Spike DuplicateLaboratory Replicate (lab specific)Field Duplicate/Replicate


Total MetalsTP-SS-423 TP-SS-425 Home-SS-560 Home-SS-461 Home-SS-462 Home-SS-458 TP-SS-424 Home-SS-441 Vent38-406

-009 -010 -011 -012 -013 -014 -015 -016 -017A A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A A

N/A N/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A N/A N/A N/A N/A N/A N/AN/A N/A A N/A N/A N/A N/A N/A N/A

005453


AnalysisSample ID



Total MetalsHome-SS-453 TP-SS-426 TP-SS-419 Home-SS-454 TP-SS-420 Home-SS-459 TP-SS-418 TP-SS-421 Vent38-SS-402

-018 -019 -020 -021 -022 -023 -024 -025 -026A A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A AA A A A A A A A A

N/A N/A N/A N/A N/A N/A N/A N/A N/AA N/A N/A N/A N/A N/A N/A N/A N/A

N/A N/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A N/A A N/A N/A N/A N/A

005454


AnalysisSample ID



Total MetalsHome-SS-438 Home-SS-439 Home-SS-449 Home-SS-430 Home-SS-463 Home-SS-447 Vent38-SS-404 Vent38-SS-407

-027 -028 -029 -030 -031 -032 -033 -034A A A A A A A AA A A A A A A AA A A A A A A AA A A A A A A AA A A A A A A AA A A A A A A AA A A A A A A AA A A A A A A AA A A A A A A AA A A A A A A AA A A A A A A A

N/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A A N/A N/A N/A N/A

005455


AnalysisSample ID



Total MetalsHome-SS-443 Home-SS-451 Home-SS-530 Home-SS-433 Vent38-SS-411 Home-SS-428 Home-SS-448 Home-SS-429


N/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A A N/A N/A N/A N/AN/A N/A N/A N/A N/A N/A N/A N/AN/A N/A A N/A N/A N/A N/A N/A

005456


AnalysisSample ID



Total MetalsVent38-SS-400 Home-SS-436 Home-SS-437 Home-SS-536 Home-SS-440 Home-SS-435 Home-SS-442 Home-SS-540


N/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A N/A N/A N/A N/A N/AN/A A N/A A A N/A N/A A

005457


AnalysisSample ID



Total MetalsHome-SS-452 Vent38-SS-401 Home-SS-445 Vent38-SS-408 Home-SS-444 Home-SS-455 Home-SS-460 Home-SS-457


N/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A N/A N/A N/A N/A AN/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A N/A N/A N/A A N/A

005458


AnalysisSample ID



Total MetalsTP-SS-520 Home-SS-456 Vent38-SS-403 Vent38-SS-415 Vent38-SS-413 Vent38-SS-416 Vent38-SS-409 Vent38-SS-417


N/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A N/A N/A N/A N/A N/AN/A N/A N/A N/A N/A N/A N/A N/AA N/A N/A N/A N/A N/A N/A N/A

005459


AnalysisSample ID



Total MetalsVent38-SS-414 Vent38-SS-412 TP-SS-427 Vent38-SS-405

-067 -068 -069 -070A A A AA A A AA A A AA A A AA A A AA A A AA A A AA A A AA A A AA A A AA A A A

N/A N/A N/A N/AN/A N/A N/A AN/A N/A N/A N/AN/A N/A N/A N/A

005460

APPENDIX C

REMOVAL AND SUPPLEMENTAL REMOVAL SITE EVALUATION ANALYTICAL RESULTS

005461