ML050870538

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Final Status Survey, Final Report Phase II, Appendix A7, Survey Unit Release Record 9528-0000, Southeast Mountain Side, Book 8 of 16
ML050870538
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 02/18/2005
From: Keyes C, Wager J
Connecticut Yankee Atomic Power Co
To:
Document Control Desk, NRC/FSME
References
CY-05-040 9528-0000
Download: ML050870538 (60)
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. X Final Status Survey Final Report Phase 11 Appendix A7 Survey Unit Release Record 9528-0000, Southeast Mountain Side February 2005 m -

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CYAPCO FINAL STATUS SURVEY RELEASE RECORD SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 Prepared By: pC FSS Engineer Date: Z. I 9.ez Reviewed FSS Pfruo t Lead Date: P2 b,

Date: S-\\i?\\

Approved By:

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD TABLE OF CONTENTS

1.

SURVEY UNIT DESCRIPTION.................................................... 3

2.

CLASSIFICATION BASIS....................................................

3

3.

DATA QUALITY OBJECTIVES (DQO)..............................................

5

4.

SURVEY DESIGN..................................................... 6

5.

SURVEY IMPLEMENTATION....................................................

9

6.

SURVEY RESULTS.................................................... 10

7.

QUALITY CONTROL...................................................

12

8.

INVESTIGATIONS AND RESULTS.................................................. 12

9.

REMEDIATION AND RESULTS...................................................

12

10. CHANGES FROM THE FINAL STATUS SURVEY PLAN.12
11. DATA QUALITY ASSESSMENT (DQA).13
12. ANOM ALIES........................................................................................ 14
13. CONCLUSION.15
14. ATTACHMENTS.15 14.1 Attachment 1 - Figures (5 pages including cover) 14.2 Attachment 2 - Sample and Statistical Data (39 pages including covers)

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD

1.

SURVEY UNIT DESCRIPTION Survey Unit (SU) 9528-0000, (Southeast Mountain Side) is designated as Final Status Survey (FSS) Class 3 and consists of approximately 508,000 m2 (126 acres) of uninhabited, undeveloped land located about a quarter of a mile (0.23 miles) from the center of the Haddam Neck Plant (HNP) Containment Building (see Attachment 1-Figure 1). Most of this area is open woodlands with patches of exposed rock, streams, old stone quarries and numerous stone walls. Access to the interior of the Southeast Mountainside area is limited to a gated haul road to the Southeast Landfill area and abandoned or seldom used logging paths and trails. An open clearing for power distribution lines, Area 9524, bounds the Southeast Mountainside survey unit to the east. Survey Units 9528-0002, 0003, 0004 and 9523-0000 bound the southern side; the Canal Road bounds the west and an access road (Wood Road) from the substation to the Discharge Canal bounds the north. The area topography, sloping to the south, is generally hilly, rocky terrain, which drain to form wetland areas with some small ponds and creeks.

The reference coordinates associated with SU 9528-0000 are E013 through E076 by S080 through S140 (see License Termination Plan Section 5.4.4). The reference coordinates provide the maximum dimensions of a rectangle containing this survey unit. Some areas contained in this rectangle may not be part of this survey unit. The boundary of the survey unit was defined using a Global Positioning System (GPS).

The historic files indicate that during the FSS of 9528-0000, several areas were identified along the southern border of this area that possibly contained plant related radioactive materials. Initially the area was subdivided and one additional survey unit, 9528-0001, was created. During the scoping survey of Unit 9528-0001, plant-related radionuclides were identified in a soil sample collected from an area along the Canal Road. Based on area limitations from the License Termination Plan (LTP), the decision was made to subdivide area 9528-0001, and create three new survey units 9528-0002, 0003 and 0004. As a result of this further division, Survey Unit 9528-0001 no longer existed.

2.

CLASSIFICATION BASIS The survey unit was classified in accordance with Procedure RPM 5.1-10, "Survey Unit ClassifIcation. " The historical information and scoping results provide sufficient data to designate SU 9528-0000 as Class 3 in November 2001.

The "Classification Basis Summary" conducted for SU 9538-0000 consisted of:

a) A review of the 10CFR50.75 (g) (1) database, b) A review of the "Initial Characterization Report" and "Historic Site Assessment Supplenment, "

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD c) Historic and current survey records review, d) Personal interviews, e) Visual inspections and a "walk down."

A review of the IOCFR50.75 (g) (1) database was completed. No events were identified for this survey unit.

A review of the "Initial and Supplemental Characterization Reports " as well as the previous "Classification Basis Summaries" provided no additional information pertinent to classification.

Radionuclide-specific analyses of soil samples collected from this survey unit prior to FSS identified only a few of the radionuclides listed in Table 2, principally Cs-137 and Co-60 infrequently.

Samples collected in this survey unit in support of the Independent Spent Fuel Storage Installation (ISFSI) were used to provide the basic statistical quantities listed in Table I and a basis for survey design. With the exception of Cs-137 and minor amounts of Co-60, the analyses of samples collected during this survey did not identify any of the gamma emitters in the Table 2 list of radionuclides.

Table 1 - Basis Statistical Quantities for Cesium-137 and Cobalt-60 from the Characterization Survey Parameter Cesium-137 Cobalt-60 Prmtr(pCilg)

(Pci/g)

Minimum Value:

0.027

-0.044 Maximum Value:

1.898 0.023 Mean:

0.857 0.001 Median:

0.804 0.001 Standard Deviation:

0.463 0.014 Discussions with veteran HNP personnel provided no additional information relative to classification of SU 9528-0000.

The Site Radiological Release Supervisor performed a "walkdown" of the area prior to classification and conducted several informal inspection tours of Area 9528 over an extended period of time observing that the area ranged from very hilly to gentle slopes interspersed with several flat or open locations. Areas along the Discharge Canal show indications of soil disturbance, debris, piles and mounds. There is no obvious evidence that a dirt road leading from the landfill area to the interior was used to transport plant related materials. This road is not paved and not maintained.

At the time of FSS, the dose impact from groundwater contamination was not considered.

The classification basis shows that the expected residual radioactivity in the survey unit would be below the site remediation criteria and are consistent with procedural guidance, thereby sufficient to justify final designation as Class 3.

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD

3.

DATA QUALITY OBJECTIVES (DQO)

The primary objective of the Final Status Survey Plan (FSSP) was to demonstrate that the level of residual radioactivity in Survey Unit 9528-0000 did not exceed the release criteria specified in the LTP, was below the 10 mrem/yr Administrative Level Derived Concentration Guideline Level (DCGL),

and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA).

FSS design and planning endorsed the use of the Data Quality Objective (DQO) process as described by the LTP, Procedure RPM 5.1-11, "Preparation of Final Status Survey Plan," and the "Multi-Agency Radiation Survey and Site Investigation Manual" (MARSSIM). A summary of the main features of the DQO process are provided herein.

The DQO process incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis. Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition. The baseline condition is technically known as the null hypothesis. Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection. In designing the survey plan, the underlying assumption, or null hypothesis was that residual activity in the survey unit exceeded the release criteria. Rejection of the null hypothesis would satisfy the release criteria objective of the FSS.

The DQO process determined that Cs-137 would be the radionuclide of concern during the 9528-0000 FSS process. Additionally, to provide conservatism, the Base Case DCGLs for radionuclides in soil was reduced by 60% to establish the Administrative Level DCGL.

Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the DCGL. Survey instrument response checks were performed before issue and after the instrument were used.

Control and accountability of survey instruments were maintained to assure the quality and prevent the loss of data.

Laboratory DQOs and analysis results were reported as actual calculated results.

Results reported as less than Minimum Detectable Concentration (<MDC) would not be accepted for FSS. Sample report summaries included unique sample identification, analytical method, radionuclide, result and uncertainty of two standard deviations (2a), laboratory data qualifiers, units and the required and observed MDC (Table 2).

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD Table 2-FSS DCGL Values and Required Minimum Detectable Concentrations Radionuclide Base Case Soil Administrative Level Required MDC DCGL (pCi/g) (

DCGL (pCi/g) 2 (pCi/g) (3)

H-3 4.1213+02 1.6513+02 1.6513+01 C-14 5.66E+00 2.26E+00 2.26E-01 Mn-54 1.74E+01 6.9613+00 6.96E-01 Fe-55 2.7413+04 1.1 OE+04 1.101E+03 Co-60 3.811E+00 1.52E+00 1.52E-01 Ag-108m 7.14E+00 2.86E+00 2.8613-01 Ni-63 7.2313+02 2.89E+02 2.89E+01 Sr-90 1.55E+00 6.20E-01 6.2013-02 Nb-94 7.12E+00 2.85E+00 2.8513-01 Tc-99 1.2613+01 5.04E+00 5.0413-01 Cs-134 4.67E+00 1.8713+00 1.87E-01 Cs-137 7.91E+00 3.1613+00 3.1613-01 Eu-152 1.0 IE+O 1 4.04E+00 4.04E-01 Eu-154 9.2913+00 3.7213+00 3.72E-01 Eu-155 3.9213+02 1.57E+02 1.5713+01 Pu-238 2.96E+01 1.18E+01 1.18E+00 Pu-239/240 2.6713+01 1.0713+01 1.07E+00 Pu-241 8.7013+02 3.4813+02 3.4813+01 Am-241 2.5813+01 1.0313+01 1.0313+00 Cm-243/244 2.9013+01 1.166E+01 1.1613+00

( 1) The Base Case DCULs tor soil are specified by the LTP in Chapter 6.

(2) The Administrative Level DCGL is 40% of the Base Case DCGL.

(3) The required MDC was 10% of the Administrative Level DCGL.

4.

SURVEY DESIGN The level of effort associated with planning a survey is based on the complexity of the survey and nature of the hazards. To assist the FSS Engineers when preparing survey plans for FSS, guidance is provided in Procedure RPM 5.1-11.

By design, the FSSP meets the ALARA criteria for soils as specified in Chapter 4 of the LTP.

The LTP specifies that the selection of the scan area size is judgmental for Class 3 areas. The fraction of scanning coverage was determined during the DQO process with the total amount, and location(s) based on the likelihood of finding elevated activity during FSS. Based on conditions found during the area inspection tours, six (6) areas, totaling 783 m2 the SU surface area, were selected for scanning in SU 9528-0000. The shape of several scan locations reflects the difficult topography of the region (e.g., exposed rock cliffs with steep banks). The shape had little impact on achieving the survey objectives since the locations were biased to identify areas with the highest potential for Revision I 6

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD elevated activity. Elevated areas of residual radioactivity were not considered likely based on Historical Site Assessment data and survey unit inspection tours.

Scans were also prescribed for a 1-meter radius around each random and biased Sample Measurement Location (SML).

Note: Initially the area contained six scan areas; however, SU 9528-0000 was subdivided prior to the development of this Release Record and only included three (3) of the original scan areas. This is discussed further in Section 10.

Thirty (30) soil samples collected during a scoping survey in the original Survey Area 9528 were used to determine the radiological concentration variability.

Radionuclide-specific analyses of soil samples collected from this survey unit and adjacent land areas with similar history and physical characteristics have identified only a few radionuclides, principally Cs-137. The data collected prior to FSS indicated that the remaining radionuclides listed in Table 2 would not be present in quantities greater than 5% of the applicable Base Case DCGL in this survey unit at the time of FSS. It was unlikely that the aggregate concentration of the remaining radionuclides would exceed 10%; therefore, only Cs-137 was used in the survey planning of SU 9528-0000. The use of the 5% and 10% rule is consistent with the development of surrogate ratio DCGLs as described in the LTP.

The DQO process determined that Cs-137 would be the radionuclide of concern during the 9528-0000 FSS process. The Operation DCGL of 3.16 pCi/g for Cs-137 was used to demonstrate compliance with the release criteria.

Surrogate DCGLs are not required for this survey unit because of the radionuclide specific analysis and radionuclide de-selection in accordance with the 5% and 10% rule.

The Elevated Measurement Comparison (EMC) does not apply to this survey unit since discrete, elevated areas of contamination are not expected.

The Sign Test was selected as the non-parametric statistical test. The use of the Sign Test did not require the selection or use of a background reference area, which simplified survey design and implementation.

This approach was conservative since it included background Cs-137 as part of the sample set.

The number of soil samples for FSS was determined in accordance with Procedure RPM 5.1-12, "Determination of the Number of Surface Samples for FSS. " Survey design specified fifteen (15) surface soil samples for the Sign Test non-parametric statistical testing.

Although Procedure RPM 5.1-11 only specified that 5% of the samples be selected for Hard-to-Detect (HTD) analysis, two (2) soil samples or 14% were randomly selected for HTD radionuclide analysis by using the Microsoft Excel "RANDBETWEEN" function. Each sample would be sent for a full suite Revision I 7

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD analysis of the HTD radionuclides specified in the LTP, Table 2-12, "Radionuclides Potentially Present at Haddam Neck Plant."

The implementation of survey specific quality control measures as referenced by Procedure RPM 5.1-24, "Split Sample Assessment for Final Status Survey, "

included the collection of two (2) soil samples for "split sample" analysis by the off site laboratory. These locations were selected randomly using the Microsoft) Excel "RANDBETWEEN" function.

The number of quality control soil samples was determined to be 14% of fifteen (15) samples, rounded up to the next whole number.

The grid pattern and locations of the soil samples were determined using Visual Sample Plan (VSP) in accordance with Procedure RPM 5.1-14, "Identifying and Marking Surface Sample Locations for FSS. " Visual Sample Plan was created by Pacific Northwest National Laboratory (PNNL) for the United States Department of Energy. Random grid spacing with a random starting point was selected for sample design, which is appropriate for a Class 3 area.

Sample location and scan areas were identified using AutoCAD-Lt0 a commercially available plotting software with coordinates consistent with the Connecticut State Plane System. These coordinates were integrated with a GPS to locate sample and scan locations in the field. Sample Measurement Locations for the design are listed with the GPS coordinates in Table 3.

Table 3 -Sample Measurement Locations (SML) with Associated GPS Coordinates.

Designation Northing Easting 9528-0000-OOIF 236810.4 670098.6 9528-0000-002F 237229.7 670932.1 9528-0000-003F 236631.6 673216.3 9528-0000-004F 236638.1 671319 9528-0000-005F 237114.3 672652.1 9528-0000-007F 236374.8 671767.9 9528-0000-008F 235893.2 672424.6 9528-0000-009F 236616.3 673105.9 9528-0000-O0OF 236270.1 673964.4 9528-0000-01 IF 235878.7 671718.3 9528-0000-012F 236067 672900 9528-0000-013F 236960.5 673522.7 9528-0000-014F 236506.4 672139.7 9528-0000-01SF 236699.9 670236.1 NOTE: Sample 9528-0000-006F was located in Survey Unit 9528-0003.

For this Class 3 survey unit, the "Investigation Level" for area scanning and soil sample measurement results are those levels specified in LTP, Table 5-8, "Investigation Levels."

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD The Lower Bound of the Gray Region (LBGR) was adjusted in accordance with Procedure RPM 5.1-11 to 0.73 of the Operational DCGL to maintain the relative shift (A/a) in the range of 1 and 3. In a Class 3 survey unit the median concentration is expected to be below the LBGR, in which case a Prospective Power Curve would be unnecessary and was not generated.

The mean concentrations for Co-60 and Cs-137 identified during the scoping and characterization indicate this assumption to be true.

Table 4 provides a synopsis of the survey design.

Table 4 - Synopsis of the Survey Design Feature Design Criteria Basis Based on AutoCAD and Survey Unit Size 508,000 rn2 Visual Sample Plan calculations Type I (a) and Type II ()

were 0.05; relative shift Number of Measurements 14 (A/a) set at 2 by procedure, the LBGR was 0.73.

Random and Appropriate design for Class Grid Spacig Random Start 3 Area.

a S Not appropriate design for Interval Spacing NtApplicable Cls3radmapin Class 3 random sampling DCGL3.16 pCi/g Operational DCGL applied DCGL

_Cs-137 to field data (l)

Based on likelihood of Scan Survey Coverage 783 i 2

finding elevated readings in this particular Class 3 survey unit a i Detectable over Based on achieving the background Administrative Level DCGL I) The Operational DCGL was based on achieving an administrative level that was 40% of the soil DCGL and assuming no impact from radioactive contamination in groundwater or from buried concrete debris.

Note:Only fourteen (14) samples were used during data analysis. Sample 006F is located in Survey Unit 9528-0003. Scan Areas 2, 3, 4, and 5 results are excluded from this Release Record. See Section 10.

5.

SURVEY IMPLEMENTATION Final status survey field activities were conducted under Work Plan and Inspection Record (WP&IR) 24265-000-GEN-0000-00061-000.

The WP&IR package included a detailed FSSP, job safety analysis, job planning checklist and related procedures for reference. Daily briefings were conducted to discuss the expectations for job performance and the safety aspects of the survey. The Revision I 9

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD "Daily Survey Journal" was used to document field activities and other information pertaining to the FSS.

Survey activities occurred between November 6, 2001 and December 11, 2001.

Six (6) land areas (see Section 10), Scan Areas 1 through 6, were marked out using GPS coordinates consistent with the Connecticut State Plane System and scanned for elevated readings Scanning was performed with an Eberline E-600 using a SPA-3 sodium iodide detector. The E-600 was operated in the rate-meter mode and used with audio response. The probe was positioned as close to the ground as possible and was moved at a scan speed of about 0.5 meters per second.

Using GPS coordinates, SMLs were identified and marked with a surveyor's flag for identification. At each SML, a one (1) meter radius around the sample flag was scanned for elevated radiation levels.

Fourteen (14) surface soil samples were collected in random locations and packaged in accordance with HNP Procedure RPM 5.1-3, "Collection of Surface and Subsurface Soil, Shoreline Sediment, Asphalt and Liquid samples for Scoping, Characterization and Final Status Survey," and FSS design.

Samples were controlled, transported, stored, and transferred to the off site laboratory using Chain-of-Custody (COC) protocol in accordance with Procedure RPM 5.1-5, "Chain of Custody for Scoping, Characterization and Final Status Survey Samples."

Two (2) samples (003F and 007F) were selected for HTD radionuclide analysis.

Two (2) samples (007FD and 014FD) were selected for "split sample" analysis by the off site laboratory.

6.

SURVEY RESULTS No elevated readings were identified during scanning the SMLs. Scan Area I and 6 contained areas with elevated readings. In Scan Area 1, an outcropping of rock containing naturally occurring radioactive materials was identified as the source of the elevated reading. No samples were collected. In Scan Area 6, an investigation sample was collected from the elevated area designated ER-0001.

The investigation results are discussed in Section 8 of this report. Table 5 provides a summary of the Scan Area survey. All scan area results are provided in Attachment 2.

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD Table 5-Scan Area Results Highest Investigation Elevated Scan Logged Level Reading Ivstiample Area Reading (IDC-cpm)

Identification Samle 1

16,000 14,100 See Note 1 6

11,500 10,400 ER-0001 9528-000-027FBI 7

9,760 9,800 (I) The elevated reading was found in a rocky area and attributed to local mineral outcroppings with naturally occurring radioactive materials.

The off site laboratory employed for the radiological analyses of samples was Antech Co. in Madison, PA. The laboratory analyzed the fourteen (14) samples taken for non-parametric statistical testing, the associated duplicates and scan area samples using gamma spectroscopy.

Gamma spectroscopy analysis was performed to the required MDC. Cesium-137 was the only gamma-emitting radionuclides detected at statistically significant concentrations. A summary of the sample results is provided in Table 6.

Table 6-Summary of Soil Sam le Results Sample Number Cs-137 f-DCGL '

P C ilg 9528-0000-O0IF 0.14 0.04 9528-0000-002F 0.73 0.23 9528-0000-003F 0.57 0.18 9528-0000-004F 0.53 0.17 9528-0000-005F 0.94 0.30 9528-0000-007F 0.71 0.23 9528-0000-008F 0.67 0.21 9528-0000-009F 0.59 0.19 9528-0000-01OF 0.11 0.03 9528-0000-01 IF 0.77 0.24 9528-0000-012F 0.76 0.24 9528-0000-013F 0.50 0.16 9528-0000-014F 0.66 0.21 9528-0000-015F 0.56 0.18 (I) f-DCGL-fraction of the Administrative Level DCGL.

The off site laboratory processed the two (2) selected samples (003F and 007F) for HTD analysis including alpha spectroscopy, gas proportional counting and liquid scintillation depending on the radionuclide and the measurement method.

(The split sample 007FD was also analyzed for HTD.) Americium-241 was the only HTD radionuclide reported at statistically significant concentrations in the three samples (see Table 6 and Table 7). No further investigations were required.

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD Table 7-Hard-to-Detect Sample Results pCi/g I Sample Number -

Am-241 l f-DCGL("'

I 9528-0000-007F l

0.116 0.01 (1) f-DCGL-fraction of the Administrative Level DCGL

7.

QUALITY CONTROL The off site laboratory processed the split samples and performed gamma spectroscopy analysis. Fourteen percent (14%) of the samples were selected for analysis, which exceeds the 5% minimum required by the LTP. The data were evaluated using United States Nuclear Regulatory Commission (USNRC) acceptance criteria specified in Inspection Procedure 84750 as detailed in HNP Procedure RPM 5.1-24. There was acceptable agreement between field split results. The sample analysis vendor, Antech Co. in Madison, PA. maintains quality assurance and quality control plans as part of normal operation. Refer to for data and data quality analysis results.

8.

INVESTIGATIONS AND RESULTS One elevated location was identified during the judgmental area scanning in Scan Area 6 (see Table 9). The sample collected at this location (027FBI) indicated only Cs-137 at values that are consistent with the concentrations of Cs-137 found in soil at off site locations within the vicinity of the HNP as presented in Health Physics Technical Support Document (TSD) BCY-HP-0063, "Background Cs-137 Concentrations in Soil." No further investigations were required.

Table 9-Scan Area Sample Results Scan Elevated Cs-137 Sample Number Redn Cil f-DCGL(')

Area Reading p

6 9528-0000-027FBI ER-0001 0.527 0.166 (1) f-DCGL-fraction of the Administrative Level DCGL.

9.

REMEDIATION AND RESULTS Historically, no remediation was performed in this survey unit prior to or as a result of the FSS. Health Physics TSD BCY-HP-0078, "ALARA Evaluation of Soil Remediation in Support of Final Status Survey," determined that remediation beyond that required to meet the release criteria to be unnecessary and that the remaining residual radioactivity in soil was ALARA.

10.

CHANGES FROM THE FINAL STATUS SURVEY PLAN The change made from the LTP, prior to this FSS, was a decrease in the concentrations for the Base Case DCGLsoils.

The LTP presents DCGLs that correspond to a Total Effective Dose Equivalent (TEDE) of 25 mrem/yr. This survey unit was evaluated against Administrative Level DCGLs that correspond to 10 mrem/yr.

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD The Field Instruction Sheets were revised during the performance of FSS Field activities to accommodate changes in survey protocol and improve the documentation process. For example, CYAPCO Oversight made a suggestion to separate field activities into two distinct documents (i.e., a Field Instruction Sheet for scans and a Field Instruction Sheet for samples). The separate Field Instruction Sheets were instituted for Survey Unit 9528 that allowed for scans and sampling to be performed out of sequence.

Prior to the development of this Release Record, a portion of Survey Unit 9528-0000 was subdivided along the Haul Road and three additional surveys units were created. Survey Units 9528-0002, 0003, and 0004 contained within their boundaries SMLs and Scan Areas that were previously part of the original FSSP for SU 9528-0000. Based on samples results obtained during the FSS of 9528-0000, a decision was made that sufficient samples were collected (14) within the new boundaries of 9528-0000 and that an adequate area was scanned for this Class 3 unit. Base upon the DQOs and data analysis, no further sampling or scanning was needed or performed.

Although the original survey plan was designed to the pre-LTP approval DCGL of 4.64 pCi/g Cs-137, data in this release record was assessed at the 3.16 pCi/g or 10 mrem/yr Administrative Level DCGL.

11.

DATA QUALITY ASSESSMENT (DQA)

The DQO sample design and data were reviewed in accordance with Procedure RPM 5.1-23, "Data Quality Assessment," for completeness and consistency.

The sampling design had adequate power as indicated by the Retrospective Power Curve. The Sign Test was performed on the data and compared to the original assumptions of the DQOs. All sample results were less than the release criteria. Therefore, the Sign Test shows that the survey unit passes Final Status Survey.

Documentation was complete and legible. Surveys and sample collection were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 3.

The preliminary data review consisted of converting the data into units relative to the release criteria (i.e., pCi/g) and calculating basic statistical quantities (e.g., mean, median, standard deviation).

The range of the data, about 3.6 standard deviations, demonstrates the variability of the terrain sampled. The difference between the mean and median was 15% of the standard deviation. The frequency plot indicates that the data is skewed negative.

All data, assessments and graphical representations are provided in Attachment 2.

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SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD

12.

ANOMALIES All data is considered valid including negative values, zeros, values reported below the MDC and values reported with uncertainties greater than two standard deviations.

Some radionuclides have been reported at low concentrations that are statistically significant at the 95% confidence level, but with a relatively high level of uncertainty.

The HTD results for sample 007F indicated the presence of Am-241 just above the MDC and greater than two standard deviations error. The HTD results for the duplicate sample (007FD) did not report Am-241. (Note: The MDC for the duplicate sample was a factor of 2.68 less than the original sample).

The gamma spectroscopy results for both samples did not identify the Am-241 key energy line (at 59 keV). The results are well below the required MDC for Am-241 and are a small fraction of the Administrative Level DCGL. The likely source of this radionuclide is the release from past atmospheric nuclear weapons testing, Chernobyl, and the bum-up and vaporization of the United States SNAP 17A satellite in the atmosphere given the extremely low levels reported.

Samples 001F and 015F indicated Eu-155 at low levels with respect to the Administrative Level DCGL. A review of the results indicates that the concentrations are almost equal to the MDC (the calculated MDC for Eu-155 was a factor of 70 less than the specified sensitivity). Furthermore, discussion with the laboratory indicates that the gamma spectroscopy peak search did not identify key energy lines associated with Eu-155. Therefore, the likely cause of the Eu-155 report is statistical fluctuation in counting system background exceeding the software parameters in the region of interest resulting in an apparent resulting activity based on calculated net results.

The reported MDCs in samples 003F, 007F and 007FD for HTD C-14, Sr-90, Tc-99 and Pu-239 radionuclides exceeded the required MDCs. It should be noted that all gamma emitting radionuclide MDCs met the required sensitivity.

This was identified during the data review and documented as a discrepancy.

The impact of this discrepancy was evaluated by using scaling factors generated for waste characterization found in Health Physics TSD BCY-HP-0049, "Waste Stream Consolidation 2001."

These factors are used to estimate HTD radionuclides in various waste streams at HNP. The most conservative scaling factors from the Fission Product Group were used to calculate the potential concentrations of these four radionuclides.

In all cases, the calculated radioactivity concentrations were less than 5% of the corresponding 10 mrem/yr. Administrative Level DCGLs.

During the survey of Scan Area 1, an outcropping of rock was identified as containing naturally occurring radioactive materials.

Initial survey with the Eberline E-600 using a SPA-3 sodium iodide detector gave a reading of 16,000 counts per minute (cpm). Geological occurrences of this type are discussed in Revision I 14 Revision I 14

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD the Health Physics TSD CY-HP-0150, "Investigation of Rock Outcropping Exhibiting Elevated Activity." This area was not sampled, but noted.

The data shows that the quantities of identified radionuclides do not represent quantities that would increase the requisite number of samples for non-parametric statistical sampling or cause the survey unit to fail to meet the release criteria. Most radionuclides were reported at levels near or below the required MDC.

13.

CONCLUSION Survey Unit 9528-0000 has met the DQOs of the Final Status Survey. For this survey unit, the ALARA criteria for soils as specified in Section 4 of the LTP were achieved. Elevated Measurement Comparison and remediation was not required.

The sample data passed the Sign Test.

The null hypothesis was rejected.

Evaluation of the data shows that none of the FSS design radionuclides or HTD soil concentration values exceeded the Operational DCGL or unity. No large anomalies were observed in the graphical representation of the data. The survey unit was properly designated as Class 3.

The Retrospective Power Curve generated using COMPASS shows adequate power was achieved.

This survey unit was evaluated for the potential impact by radioactive contamination in groundwater based on location, topography and current hydro-geologic sampling data as referenced in Health Physics TSD CY-HP-0193, "Assessment of Existing Groundwater Dose for Phase HI Release Areas of the Final Stalus Survey Report."

For SU 9528-0000, the only sample qualifying as detectable groundwater contamination is the September 2004 H-3 results for Monitoring Well 2 (439 pCi/L). Using the LTP 25 mrem/yr Groundwater DCGL of 625,000 pCi/l for H-3, the calculated dose is 0.003% of the 25 mrem DCGL or 0.000673 mrem/yr. The dose from existing groundwater contamination present in the monitoring wells within the capture zone for this survey unit is insignificant and need not be included in showing compliance with site unrestricted release criteria as defined in the LTP Section 5.4.7.2, "Gross Activity DCGLs.

14.

ATTACHMENTS 14.1 Attachment I - Figures 14.2 Attachment 2 - Sample and Statistical Data Revision I 15

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD Figures (4 Pages)

m m -

m m

m m

=

=

=

=-

m m

mm I

I J

Tw& Eampol 9528-0000 Scan Ar 7

2-Connecticut Yankee Atomic Power Company Site Map With Reference To Survey Unit 9528-0000 Dao IRSv Apri2004 0

CO(

m m

M M

M m

m m

m m

m m

m m

m 3 Auggaw AM400"IF 0

X96410010OF 6

3 3014ft1.e 9528-0000 3= Sample Location

(

= Scan Area No Scan Areas 1, 6 & 7 abown.

(Scan Areas 2. 3. 4,

& 5 are 1 9528-00020,

o00, 0004.

Sample 9628-0000-006 located In Survey Unit 9628-0003.)

-Mw

,fmme4P Area I

')

415F AnI Fig=e2^

Connecticut Yankee Atonuc Power Company Is Qf 9528-0000 Fmal Statm Survey Designl A^00 CO'0,Z-

m m

m m

m m

M M

M M

M M

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-a Am MmAh L a SUN-"

Om

£ MM),

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-L I Wgftlak 9528-0000 T.Mmgm Fgn e3AConnecticut Yankee Atomic Power Company DD R

Figr 3 9528-0000Final Status Surwey Cesium-137PostingPlot 1p 02W4O

m m

m m

m m

m m

m m

m m

m M

m Ann 7

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S-137.)

9528-0000 A

Am necticut Yankee Atomic Power CoL 9528-0000 Final Status Survey-Investigation Sample with Results.

Co t

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD Sample and Statistical Data

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD a Gamma Spectroscopy Data (17 Pages)

Table 1 (Continuedl page 6 of 6 Rawlse xdentiflatton

~~

9528-0000-O0llr Analytical 011117/0135 Parameter Method thite Act t Une OIOCI K-40 A-s24 pCI/g 1.4001 t 2.OLO IS.CE-1)

Xn-54 A-524 pcI/g 2.003-3 t 3.12-2 15.72-2)

Co-SO RA-100 pCL/g 1.201-2

  • 2.E8-3 M.ER-2)

Nb-94 A-S24 pci/g

-5.763-3 f 2.SE-2 (4.72-2)

CB-134 A-524 pCi/s 6.13E-3+/-t 2.91-2 (4.1,-2)

Ca-1=7 A-5J4 pCl/g 1.35B-1

  • 5.51-2 (7.48-2) 8u-152 A-S24 PCY/g 1.35Z-1 t 1.58-1 13.33-a)

NU-It4 A-524 pCi/g 3.29E-2 k 9.BE-2 (L.SZ-1) lo-Iss A-524 pyCil L.9IR-1 t L.08-1 1.5-11 T1-2vo A-534 pCU/N 3.430-1

  • S.51-2 (5.73-2)31-212 A-524 PCU/N 1.43B0
  • 6.2B-1 (B.1Z-12 1b-212 A-524 pci/0 1.1530
  • 2.23-1 ll.5B-l) 214 A-324 pCi/g G.D9E-1 t 1.48-1 44.43-1) ib-214 A-524 pCi/g 1.05B3 i l.SB-1 1

Ba-226 A-524 vCi/s 2.:GXO f 1.410 (1.31l Ac-228 A-524 pCi/p 1.330* 1.73-1 (1.58-1)

A-241fEs3 A-524 pCi/g 7.453-3 t 7.6E-2 (1.38-1l ICoIture ConetanLt ATM 2215-95 4

23.0 Act

  • thc IflDC) ln the activlty

.ith 2 ulpma i. CertaIaty end the macociated Minimum Isatoable ctann Atioan.

I.-3 I

I-ID

(

r

(

(

Vt t

(

(

[

V (I

(IC

.. t r

f Table 1 (Cont4inued)

Page 3 of R sarnmle identifitation 02111-0124A 9S28-OD00 -002F Analytical (21/13/al)

Pamaineter Method Unito Act + Mc (MDC)

K-40 A-524 pCi/g 1.16E1 I 1.7B0 (6.31-1)

Hn-54 A-524 pCilg 1.40S--2

  • 3.72-2 (6.88-2)

Co-60 RA-100 pCifg 3.82B-3 t. 3.01-2 (S.72-2)

Vb-94 A-524 pCifg 1.75E-2 :i 3.1E-2 (5.52-2)

Cs-134 A-524 pCl/s 2.948-2

.4.32E-2 (6.92-2)

CS-137 A-524 pei/g 7.27E-1 t 1.2E-1 (7.3E-2) u-2.52 A-52&

pCifg 7.36E-2 +/- 1.7B-1 (3.32-1)

Eu-154 A-524 pCi/g

-4.042-4 t 9.2E-2 (1.7E-l)

Eu-155 A-524

.pCI/S 4.94E-Z h l.BR9-l (3.13-1)71-20B A-524 pCilg 3.97S-1.

8.4R-2 (6.5E-2)

Bi-212 A-524 pCi/g 1.43B0 j 6.38-1 (8.9E-1)

Ib-212 A-524

.p3iI

. 1,04E0 i 1.82-1 (1.32-1)

B1-212 7-524 pCi/g 9.45E-1 1 1.42-l (4.3E-1)

Fb-214 A-524 pCi/

1..2180 4 1.68-1 (1.48-1)

Ra-226 A-524 pCi/g 4.0620 1.780 (L.620)

Ac-228 A-524 pc/g

  • Q.97B-1 2.02-1 (I.SE-1)

Am-241(GS)

A-524 pCi/g 1.71B-1

  • 2.9E-1 (4.5E-1)

Moiature Content ASTM 2216-98 1

30.0 tD 0--'

a'I, 71

9 r

a.-

-3 9

w D"

Act t Utc (MMDC) in the activity Detectable Concentration.

with 2 sigma uncertaiinty and the associated Miniam

-U I-.-

-3

Table I (Continued)

Paie 5 oC 6 Bauple ld7dentiticetior 011. -0134A 9528-0000-003F Analytical (11/12/01)

Marurtar Method tnite

-At *4 Unc (MDC) 1-40 A-S21 pCL/g 1.0431 t 1.6E0 0 5.33-1)

Ia-54 A-S24 pCt/g 3.513-4 t 3.3E-2 (G.13-2)

Co-gO 0A-100 pCL/qg

-1.61H-3 t 3.23-2 (5.93-2) 8b-94 A-524 pCig

-. 78M--1

  • 3.01-2 (5.4E-2)

Ca-134 A-524 Pei/]

,3.156-2 4

3.03-1 (C.SE-2)

C.137 A-324 3Cig 5.111-1 t 1.05-1 (7.72-2)

Eu-1S2 A-524 pci/g 2.933-2 t l.C8-1 (3.21-1)

Nu-154 A-324 pci/g

-0.75-2 t 1.1-.-1

.33-1)

Nu-.55 A-524 pCI/g S.799-2 i 1.81-1 (3.22-12

'1-zoo A-52t pCi/g 2.43E-1.

  • 5.9B-2 (7.13-2)01-213 A-534 pi/9.

5.20E-1 f 4.7S-1 (3.2R-l 524 pCifg 7.271-1

  • 1.4K-I 11.43-1)81-214 A-524 pCi/s 6.71E-1
  • 1.33-1 f4 e21-1)

Pb:214 A-524 P(:ilg

  • 6.Sl8;-1 A 1.31:-1 ll.SR-2)

RR-226 A-524 PCi/g

.!i4R4

  • 1.10 12.120)

Ac-228 A-524 pCI/g S.g5l-l 2 1.6E-1 (2.2-13)

Am-241(09)

A-S24 Icilg

-1*2-2e.6B-1 (4.92-1)

Moisture Content At 2216-98 4

25.0 Act : Una (MIzi) in th activity with 2 wiga unceartanty and the associated Hinimm Detectabla conc*,tration.

1; a--

a,.I

  • II

(

I f

(

I r

(

[.

I

((

I

(

C

( -

TablS I

(Conbinued)

Page n of 8 SanPle Identification 0111-D129A 9528-0000-004?

Analytical (11/13/01)

Parameter Method

_units Act + Unc (MDC)

K-40 A-524 PCi/s 1.28E1 2.3S0 (8.7H-a)

Mn-54 A-524 pCi/g 6.31B-3

  • 6.18-2 (9.6E-2)

Ca-60 EA1-00 pCi/g 2.508-3 L 4.6B-2 (9.OE-2)

Nb-94 A-524 pCi/g

-1.19B-2 t 4.6B-2 (8.29-2)

Cs-134 A-524 pci/g

.4B3-2 i 5.78-2 (9.0E-2)

CB-137 A-524 pCIfg 5.328-1 1 i.3E-l (1.15-1)

Bu-2.S2 X-524 PC1Ig

-1.88E-1 3 2.0E-1 (3.23-1) su-154 A-524 PCM/9 1.00I-1

  • 1.48-1 (2.9E-1)

Xu-155 A-5a4 PCi/g 5.97E-2 + 2.7B-1 (4.7E-1)

T1-208 A-524 pCl/g 3.68B-1 +/- 9.2B-2 (1.13-1)

BL-212 A-524 PCL/g 9.71E-1 4 7.93-1 (1.3BO)

Pb-212 A-524 pCi4g 1.0930 i 2.1E-1 (1.95-1)

Bi-214 A-524 pMi/g 1.0730 +/- 1.9E-1 (S.58-1I Pb-214 A-52&

pCi/s 1.230O + 2.03-1 (1.73-1)

Ra-22G A-524.

pCi/g 3.09E0 F 1.8D0 (2.330)

Ac-228 A-524 PCIfg 1.0780 +/- 2.6E-1 (3.2Z-1)

MA-241(aS)

A-524 pCi/g

-1.203-1

  • 3.83-1 (6.7E-1)

Moisture Content AMTll 2216-98 1

39.0 r%3 2.0 in H.

I V,

Ol.

in.

t' Act

  • Unc (MDC) is the activity with 2 sigima uncertainty and the associated Z4ininTnu Datectn2le Concentration.

(I

(

(

(

(

( -

I I,

1. ' '

f

(. -

( '. -

(, -

CF 4

.@r-Table 1 (Continued)

Paqe 5 of 8 Sanle Identifieation D1L1-012hA 9528-Q000-OOSP Analytical (11/13/01)

Parameter Metbod Unito Act' + Unc (Mfl) x-40 A-524 pCi/g 1.07E1

  • 1.580' (5.08-1 Mn-54 A-S24 pCi/g 1.12R-2 +/- 3.6E-2 (6.6B-2)

Co-60 RA-100 p~ik

-1.098-2 t 3.33-2 (5.83-2) hb-94 A-524 pCi/g 1.153-2 +/- 3.18-2 (5.78.2)

Cn-134

,A-524 pei/g 4.95-2 j 4.IZ-2 (6.83-2)

Cr-137 A-524 pCi/g,

9.438,2 +/- 1.4B-1 (7.3X-2)

Eu-152 A-524 pCi/g 1.75E-1 3

1.5B-1 (3.2Z-1)

Eu-154 A-524 PCi/g 1.94E-2 t 9.48-2 tl.5E-1)

Eu-155 A-524 pCi/q 4.02E-2 + 1.88-1 (3.2E-1)

T1-200 A-S24 pCi/g 4.02E-1 +/- 6.78-2 (6.2E-2)

Bi-212 A-524 pCl/g 1.17E0 +/- 5.9E-1 (7.5E-1)

Pb-212 A-524 PC1/g.

1.14E0 i 1.8B-1 (1.2E-1)

Bi-214 A-524 pCl/9 1.14E0 +/- 1.6Z-L (4.0E-1)

Pb-214 A-524 pCi/g L.0980

1.4E-1 (1.39-1)

Ra-226 A-524 pCi/g 2.16B0 +/- 1.GEO (1.780)

Ac-228 A-524 pCi/g 7.638-1 i 1.EE-i (2.18-l)

An-241(GS)

A-524 pCi/g

-&.07E-2 k 2.7Z-1 (4.60-1)

Mciaturo Content ASTM 2216-98 I

23.0 F-Y~

-4 ts n

1'1 Act & Unc (iWC) is the activity with 2 sigma uncertainty and Detectable Concentration.

the associated Mininum

_0

(

( -

I I

(I' f

(

I '

(

I r

( '

(.r(.

Table 1 (Continuod)

Page 6 of B Sample Identifioation 0111-0127A S52 8-0000-007F Analytical (11113/01)

Parameter Method Units Act

  • Unc (MDfC X-40 A-524 pCi/g 1.41E11
  • 2.0E0 (S.41-1)

Mn-54 A-524 pCi/O 2.31E-2 j 3.2B-2 (6.3R-2)

Co-GO RA-100 pCi/g

-3.05E-2 +/- 3.0S-z (4.43-2)

Nb-94 A-524 pCi/g 3.28E-3 + 3.01-2 (5.51-2).

Ca-134 A-524 pCifg

-1.40H-2 t 3.0S-2 14.41-2)

Ca-137 A-524 pCi/1 7.11E-1

  • 1.3R-1 15.4B-2)

Eu-L52 A-524 pCi/g 1.25-1

  • 1.28-1 (2.9B-1)

Eu-154 A-524 pCi/g 5.28E-2 L l.13-l (2.1E-1)

Eu-155 A-524 pC2i/g 2.17B-2 + 1.0B-1 (1.7-1.)

T1-208 A-524 pCi/g 2.49B-1 b 4.7?-2 (S.!E-2)81-212 A-524 pCI/g 1.37E0 6.0B--1 (8.60-1)

Pb-212 A-524 pCi/g 1.08HO t 1.83-1 (1.1E-1)

Bi-214 A-524 pCi/g 1.04B0 ff 1.51-1

.(4.4E-1)

Pb-214 A-524 pCi/g 1.07110 t 1.3B-1 (L.2E-1)

Ra-225 A-524 pci/g 2.BlE0

  • 1.2EQ (1.5H0)

Ac-228 A-524 pci/g 7.60E-1 +/- 1.5E-1 (2.O-11 Am-241G8)

A-524 pei/g 4.10S-2 *f 7.4E-2 (I.31-1)

Mointure Content ASM 2216-98 I

37.0 C

al 6

I.-

5 cn

-3.

I'to I..

WI I.

IL w

Aot + Unc (tMC) iB the activity wlth 2 Jigma uncertainty and Uhe aenociate4 Minimum Detectable Concentration.

I-

C,

(,

f

( '

(.

(

(

(

1 '

(

r-.-

J Table 1 (Conti nued)

Page 7 oE a Sample Identification 0111 -0i2SA 952B-0000-007ED Analytical (11/13/01)

Parameter mathod Units Act :t Unc (MDC)

K-4 0 A-S24 pCi/g 1.30E1

  • 1.7EO (4.4E-1)

Mn-54 A-524 pCi/g

-1.12z-2 2.38-a. (.OE-2).

Co-60 IRI-100 pCi/g 3.74B-3 f 3.OE-2 (5.7S-2)

Wb-94 A-524 pCi/g

-2.S13-3 *t 2.6E-2 (4.7E-2)

Ca-134 A-524 pCi/g 9.97B-3 +/- 3,4E-2 (S.2E-2)

Ca-137 A-S24 pCi/g 4.92B-I +/- 9.BE-2 (S.7E-2)

Su-152 A-524 pCl/g 2.938-1.

1.

GE-1.

(3;3E-l)

Eu-154 A-524 pci/g

-7.67E-2 +/- 9.3E-2 (1.SE-1)

Eu-lSS A-524 pCi/s 1.25B-.

I 1.SE-L (2.SE-1)

TI-208 A-524 pCi/g 4.40--1 +/- 7.BE-2 (S.OE-2)

B3i-212 A-524 pCi/g 1.31B0 i 6.1E-1 (G.5E-1)

Pb-212 A-524

.pCig

  • 1.07ED j I.SE-I (9.7E-2)

Di-214

.A-524 pCi/g

.lOBO 2.3E-1 (3.5H-1).

Pb-214.

A-524 pCi/g 1.04EO +/- 1.2E-1

(.llE-l)

Ra-226 A-524 pCl/g 3.13E0 t 1.2EO (1.2EO)

Ac-228 A-524 pCi/g 9.3SE-1 i 1,4E-I1t9E-i)

Ain-241(GS)

A-324 pCi/g

-3.90B-2 + 2.5E-1 (4.4E-l)

Mointure Content MSTM 2216-98 33.0 Act

  • Unc (MDC) in the activity with 2 sigma uncertalnty and the associated Mininum Detectable Concentration.

I-Tt 11 I-CD

-u

-3.

(

I I

(

(I I'

I I

I

(:

Table 2 Gsneral Data Table BechteL Power Corporation Ant~cch Ltd. Project 21o. 01-1427N Soil characterization: 755s 24265-450-82.00.82E0 COC6595 Charge Order No. 24215-PBS-8-00445-Aby Haddam Neck Daecnisnioning Sample Identification 0111-02.2114 9520-0000-008F Analytical (11/13/01)

?Parameter Method 1nitg Act + Unc (MWX)

X-40 RA-lO0 pCi/g 1.1891 F L.6E0 15.6E-1)

Mn-54 RA-l2o pCl/g

-2.86E-2 *.3.48-2 (5.7E-2)

Co-60 RA-l0.

pCi/g

-. 923-3 t 3.2B-2 (6.0Z-2)

Db-94 RA-200 pCi/g

-1.36R-2 t 2.9R (5.0o-2)

Ca-134 RA-l00 pCi/g 1.41E-2 + 4.2B-2 (6.58-2)

Ca-137 RA-lO pCi/g 6.71B-1 :t 1.1E-1 (6.4E-2)

Ei-152 RA-100 pCi/g 1.35E-3.

1.5E-1 (3.0R-1)

Eu-154 Rh-1O0 pCi/g

-2.33E-2 9 9.93-2 (1.7H-1)

Eu-155 RA-lo1 pci/g 1.OEE-1 i 1.7E-1 (3.OE-1)

T1-200 RA-1O0 pcifg 4.24E-1 7.8E:-2 (6.7E-2)

Bi-212 RhA-00 pCi/g 1.76EQ A 6.EE-1.

(8.33-1)

Pb-212

  • 2RA-100 pCi/g 1.36E0 i 2.0E-1 (1.13-1)51-214 RA-1OO pCi/g 1.20t0 i 1.5B-l (4.3E-1)

Pb-214 RA-200 pCi/g 1.27E0 j 1.5E-1 (1.49-1)

Pa-226 RA-1OO pCi/g 1.86E0 t 1.4O (1.5mE)

Ac-228 RA-lO.

pCi/g 1.26E0 i 1.7E-1 (1.73-1) 7h-234(GS)

RA-100 pCi/g

-M U-235(GS)

RA-lO0 pCi/g AM-241(GS)

RA-100 pCi/g

-1.77E-2 + 3.0E-1 (5.28-1)

Moisture Content ASTH 2216-98 25.0

-E5 I-T

-4; 0

w in*

wIn R,

a F-coL W

Act 4 Unc (MDC) i4 the activity with 2 Eigma uincertainty Detectable ConCentration.

and the associated minimum

.1

TilSa 1 Ga nral DVaa Table Rachhal favor Corxorabion Antach Ltd. fteolont No. Ol-2429A SolS CbaractorlsatLonj 188, 24265-450-U2.0O.0230 CDC4#20S Chaego Ordexr No. 24263-VS-f8-00445-ACt Hladdaz Nezk Dacameialoning Pnle 1 of 6 Sample TdentifIcation Analytical (Ll/12/01)

Pprimetex method U*anits ct + Vnc (MlCI K-4C A-524 pi/g 1.33M t 1.720 (5.1B-1)

Ha-54 A-524 PCI/g 1.54S-2

  • 3.3-2 (t.3E-2) eMRo nh-lao0 pcl/g 1.4C0-2 2 3.08-2 16.2E-21 A-524 pt

/g 3.20B-3 t 2.9E-2 15.40-21 Cu-134 A-524 pCI/9 1.6C3-2 t 2.9Z-2 15.03-2)

Cn-237 A-524 pCI/g 5.93B-L 2 l.lB-l (S.43-2)

Eu-152 A-324 pc/g

.0-1.oax-i L.SR-.

(3.3z-1) 1U-154 1-524 pCl/g 2.678-2 k LOU-i (1.OE-S Bu-155 A-1;24 pCal/

7.25W-1 12lO-l.0-1 F1.1-1520

-524 pCl/g 2.99E-1 :L 5.2X-2 (5.29-2) 3I-212 A-524 pCa/g 9.331-L

  • 4.7E-1 17.23-1)

Pb-212 1-524 pCi/g 1.12B0 t L.9B-1 (1.28-11 81-214 A-52t rci/a 7.02U-1 J. 1.39-1 (3.9n 11 Pb-214 A-521 pCai/

9.528-1

  • 1.43-1 (1.23-12 Rs-226 A-524 pCi/g 2.6130
  • 1.lSO (1.420)

Ac-22S A-524 pCi/g 9.52S-S 2

1.7E-1 I1.B-0)

.Am-241CGS)

A-S24 pci/g 7.37S-2 t 7.53-2 (1.4H-1)

Mointure Content AM1 2216-98 22.0 Act *. 1c (HOC)

I+/- the activity with 2 asima uncertainty and the mamaciatod minimum Detectable Ogncuetzation.

U.

I--

1To.

8*

l o:

I.

9i II-to 1

rj<*'.

(ii

(*

(

I.

I f

(.

f r:

tr.

Tabla I (Continued)

Page 4 oE 8 samtle Identification Olll-0125A 9528-0000-010?

Analytical (11/13/01)

Parameter Hethad.

Units Act 4 Una (MDC)

X-40 A-524 pCi/g 1.24B1 - 1.7E0 (4.9E-1)

Nn-54 A-S24 pCi/s L.23B-2 t 2.9B-2 (5.69-2) co-60 RL-100 pCik

-4.90E-3 +/- 2.8B-2 (5.3ET21 A-524 pCL/g

-9.14E-3 +/- 2.BB-2 (4.-E-2)

CS-134 A-524 pCig 2.02E-2 + 3.53-2 (5.7E-2)

Cs-137 A-S24 1.08B-1 L 4.88-2 (6.0E-2)

Eu-152 A-524 pCi/g 1.658-2 E L.28-1 (2.4E-1)

Eu-254 A-524 pCi/g

-3.67E-2 +/- 9.18-2 (1.6E-1)

BU-155 A-524 pCi/g

.5.29E-2 +/- 1.6B-1 (2.86-1)

Tl-208 A-S24 pCi/g 2.033-1 : 5.1E-2 (5.8E-2)

Bi-212 A-524

  • pCi/g 1.25BD :t 5.6B-1 (7.OE-1)

Pb-212 A-S24 pCi/g 5.38B-1 jf 1..1E-1 (l,

OS-l) 1i-214 A-524 pCi/g 4.683-1 t 9.93-2 (4.48-1)

Pb-214 A-524 pCi/g.

4.22E-1 +/- 1.08-1 (1.33-1)

Ra-226 A-524 pCi/g 1.3480 lI.lEO (1.4EO)

Ao-220 A-524 pCi/g 4.03E-1 ': 1.6R-1 (1.8E-1)

Am-241(09)

A-524 pci/y

-3.35E-1 t 2.3E-1 (3.7E-1) mifiture Content ASTM 2216-98 g

3.70 Act +/- Uno (MDC) il the activity with 2 Siga uncertainty and ths anuociated Minimum Detectable Concentration.

R.

In

  • D -

I-

U tD:

-T

-3

( '

f f

(

(

(

(

f.

(

v f..

(.

(, -

Table 1 (Continuad)

Pagie 2 of 2 Sample Identification 0111-013nM 9528-0O00-011O Analytical (1/14/01)

Parameter Methnd

,Units Act 4. Unc (MDC)

K-40 A-524, pCi/g 9.7930 k 1;4EO (5.7E-1)

Mn-54 A-524 pCi/g 5.01E-4+/-i 3.SE-2 (S.211-2)

Co-60 RA-100 pCLZg 1.63S-2 b 3.28-2 (6.2H-2)

_lb-94 A-524 pCl/g 4.17B-3 t 3.13-2 (5;6E-2)

Cn-134 A-524 pCi/g 9.088-4

  • 3.83-2 (5.6H-2)

Ca-137 A-524 pCi/g 7.73E-1 1.28-1 (6.5S-2)

Eu-152 A-524 pCi/g 7.41B-2

  • 1.73-1 (3.3E-1)

Eu-154 A-524 pCi/g

-9.12-2 +/- 1.

E-2 (1.6-1)

Bu-155 A-524 pCi/g

-1.21E-4

  • 3.6E-1 (2.7H-1)

Tr-208 A-S24 pCi/g 4.31E-1 :t 6.6E-2 (6.OE-2) 3L-212 A-524 pCi/g 1.96SO 4 7.3B:1 (7.9E-1)

Pb-a212....

A-S24 prilzg 1.1230 - l. BE-1 l.22 Di-214 A-524 pCi/g 1.27E0 3 1.6E-1 (3.43-1)

Ph-214 A-524 Pci/g 1.432 En 1 l.g-l I

1.3E-1L)

Ra-226 A-524 pCi/g 3.56E0 :t 1.3EO (I.SEO)

Ac-228 A-524 pCi/g 1.04B0 s 1.5E-1 (1.93-.)

Am-241(GS)

A-524 pCilg 5.32E-2 j 2.0E-1 (3.55-1)

Mointure Content ASTH 2216-98 It 32.0 0*b-m

'3 2:

I.

A 5:

L.

tE}

'2 0-:

0i.

A (I.

Act +/- Una (NDC) ig the activity Detectable Concentratict.

with 2 ignma uncertainty and the associated minimum

Table I (Cantinued)

Page 4 oE _h Harmle Tdenti t ca tion OI11-023JA 9528-0 00-OllI Amalytical 9L2/12/02)

Pausetpr Method Unite Acnt 4 M~nc Me)

K-40 A-524 7C1/g 1.20BI. + 2.0E3o (6 OB-11 Yn-S4 A-424 g

<.71Z-3 j 4.23-2 IM.0E-2)

Co-st RA-100 pCi/g

-3.003-2 t 4.23-2 (7.8S-2) 11b-94 A-SZ4 pLU/b 2.D4S-1 tj 4.1BE-1 (8.22-2)

Cn-1t4 A-524 pCijg 2.94B-2 t 5.4B-2 It.98-2)

CJ-137 A-514 p4i/g 7.5EB-1 t I.SE-1.

(O.6B-2)

SU-152 A-524 pCiwg

-2.768-2

  • 1.7B-1 (3.3E-1)

Eu-154 A-5124 pCi/g

-6.77E-2 +/- 1.21-1 2 3.33-2)

Sa-2SS A-S24 pCI/gq 9.468-2 t 2.9B-1 M3.5--11 Tl-203 1-524 PCI/g 2.54C-1

  • t.21-2 (7.43-21 Di-212 A-524 pCi/g 3.E9E-1.1 S.71S-1 tl.21n2

?D-.:t 524 pcilg 5.03Z-1 1 1.9B-1 41U.-1 11-214 A-524 p.l/g C.223-1 1

  • .AR-1 (1.62-21 lSb-214 A-52V pCi/g B.OS-1 4 1.99-1 (1.33-1)

Ra.-226 A-524 pci/9

  • 1.57B0.

1.3E0 (2.3803 AL-228 A-524 pCl/g 7.301-1 2.2C-1 (2.9B-1)

A-241(CM)

A-524 ICi/g

-6.02S-3 +/- 3.51-1 16.1E-11 Hoiature Content ASTH 2216-90 49.0

-3

£ A

5 to Act I Vonc (MC)

IN the actvittY C~tntnotal Conenrt%-tiat with 2 aigma uncartainty and the aceociated MSInuMn

Tubl. 1 (Contdjued) agqe 3 cf,6 Basyle 7dentiftcatlnn 011L-C132K

-521-O000-013F Analytical (la/12/l01 Varoter method Unit Act + UMc (MOD X-40 A-524 pCi/g 3.4930 0 1.580 (5.23-1)

Mn-5d A-524 pCI/g

-1.3or-2

  • 3.9B-2 I6.23-21 Cb-60 RA-100 pCI/g

-7.873-3 t 3.6i-2 (9.63-21 IM A-£s pCL/g

-3.17B-3

  • 3.SB-2 (6.38-2)

Cm-134 A-324 pCtjg

-2.15E-3

  • 4.6E-2 M6O9Z-21 C8-137 A-524 pC3i/g s.O3E-2.
  • 1.1*11 (3.02-2)

TM-152 Ji-524s yCtig 4.2211-2 :t 1.78-l (3.38-1)

Nu-154 A-124 pCLf9

-2.013-2 t 1.18-1 (2.12-13

_7u-1SS A-524 pCi/g 2.311-1.

2.1E-1 (3.BX-1) rl-209 A-524 pCI/g 3.37B-1 k 6.iE-2. (7.98-21 31-212 A-524 pCL/g 1.07*0

  • S.98-1
  • C1.410) v2b-2L2 A-524 pVCig 1.1280 i l.9B-1 (1.22-13 B1-214 A-5Z4.

pCI/9 7.438-1 t 0.6991 A.9U-13 Nb-214 R-51*

pCi/g 8.71-.

t 1.43-1 (1.634)

Ea-221 A-524 pCI/g 3.67B0

  • 1.6E0 C1.uEC Ac-223 A-524 pCl/g 1.0180
  • 2.13-1 12.12-3 A h-241(C) 1t-514 PCI/O 1.59Z-1
  • 3.3X-1

{.a1 Holeturn Content ACT3 2216-98 I

15.0 Act t Vnc (IDCI la the activity with 2 auic znceatainty and the satcciated lniamm Dmteockbl ConounteratLon.

.a.

1.

n

-o in

(

(

f ,

f

f f

(, -

('.,

(

I

(

t Tabla I General Data Table Bechtel Power Corporation Antech Led. Project Uo. 01-14251.

cll Characterization, FS~z 24265-450-82.00.1200 COC9598 Charga Ordos No. 24265-FBD-9-00445-ACI Haddam Iook Daormiusioning page I of 8 5amPle identification' olni- 022A 9528-0000-014r Anslytical.

(11/13/C1)

Parutaher Method Unitn Act :t Utic -(MDC)

K-40 A -524 pCl/g 1.08B1c 11.45C (3.7E-1)

Mn-54

-524 pCi/g

-2.74E-2 2.9sX-2 (4.7E-2)

Co-60 RA-100 pCi/g 2.44R-3 + 2.6E-2 (5.03-2)

Nb-94 A-524 pCij/g 2.30E-2 i 2.6E-2 (5.0B-2)

Ca-134 A-524 pCi/g

-1.613-3

  • 3.33 (4.99-2)

Cn-137 A-524 pci/g 6.57B-1 +/- 1.03-1 t5.3E-2)

Bu-152 A-524 pCi/g 8.578-2

  • 1.33-1 (2.6Z-1) 8u-154 A-524 pCi/J

-2.22H-2

  • 7.93-2 (1.3Z-1) 8u-155 A-524 pcilg

-1.97E-2

  • 1.3S-L (2.23-1)

Tl-208 A-524 3cl/g i.01-1 t 6.3E-2 (5.5E-2) fi-2lZ A-524 pCi/g 8.05R-1 k 4.03-1 (7.13-I)

Pb-2L2 A-524 pCi/g 9.27H-li +/-1.5l-1 (08.93-2)

Bi-214 A-534 rCity 1.10EO + 1.3E-1 (3.3Z-1)

Pb-214 A-524 pCtig 1.08EO i 1.4E-1 (1.1E-1)

Ra-225 A-524 pCi/g a.79sso +/- 1.2E0 (1.lRO)

Ac-228 A-524 pCi/g E.91E-1 it 1.48-1 (1.EE-1)

AM-241(ag)

A-524 pCi/g

-4.143-1 t 2.33-1 (3.18-1)

Moilsture Content AS774 2216-98 89.0 M

ID-am I-4 0

In I

911

'Si

-3 to D

m wl Act +/- Unc (MOC) La the activity Detectable Concentration.

with 2 sigis uncertainty and the associated Minimnum

( -

( -

(.

l

(

I I

(

(

I'

(

(

I

(

I (

Tabla I (Coneiruad)

Page 2 of a Sample Tdentification OllL-0123A.

9528-acuo-014MD Analytical (11/13/01)

Parameter

_Method units Act + UlnC -DCl K-40 A-524 pCi/g 9.55E0 t 1.4EO (4.4E-i)

Mn-54 A-524 pCi/g 3.B3E-3

  • 2.BE-2 15.1E-2)

Co-60 ftA-100 pCi/g

-3.43B-2 : 2.SE-2 (4.2E-2)

Nb-94 A-524 PCifg

-5.72B-4 th 2.83-2 '(S.CH-2)

CO-134 A-524 pCi4g

-1.25E-2 t 3.1X-2 (4.5E-2)

Cs-137 A-S24 pCi/g 2.20E-1 +/- S.OB-2

($.2E-2)

EU-152 A-524 pCilg 1.71Z-1

  • 1.2E-L (2.?E-1)

EU-154 A-524 pCifg

-S.33B-2 *8.1S-2 (1.3E-1)

Eu-L55 A-524 pCi/q

-1.04E-1 +/- 1.2K-1 (L.9H-I)

Tl-2oB A-524 pCL/g 2.SOE-1 j 5.8H-2 (4.93-2)

BM-232.

A-524 pCi/g 7.DOES-1 5.3B-1 (7.2R-1)

Pb-212 A-524 PCi/9 7.40E-1

BI-214 A-524 pCI/9 5.S4E-1 : 9.78-2 (2.BE-1)

Pb-214 T-S24 pCl/g 6.63B-L

  • 1.1E-1 (9.3E-2)

Rm-226 A-524 pCS/g 2.29a0 +/- 1.0O0 (1.OEO)

Aa-228 A-524 pCifg 7.23E-1 + 1.48-I (1.5E-1)

Am-241(GS)

A-524 pCi/g 2.67E-2 +/- L.68-I (2.8K-3) mointure Content ASTM 2216-98 1

73.0 2

-4 M

ID

.0.-

-3 I) m ACt

  • Unc (MOC) is the activity Detectable Concentration.

with 2 nigma uncertaintY and the associated Minimum

Tablm 1 (Cozntnue d) pacm~ 2 ofS a8mp1 Tdontjfication 0111- 013L 9523-8000-0lEF namlytlcal

.12./12/OLJ Parameter KetThd tnit Act 4 Unc IDC X-40 A-524 iC+/-/g 1.41B1 1 1.830 (3.1E-1)

Nn-54 A-524 palog 1.568-2 + 2.S9-2 15.3E-2)

Co-60 RA-LO*

pCi/g l.S6E-2 +/- 2.6E-2 (5.0-2)

Vb-94 A-524 pCi/g

-8.74B-3 :t 2.4E-2 (4.23-2)

CB-134 A-524 ptiqg 1.93B-2 t2.73-2 14,28-2)

C.-137 A-:24 pCI/S S.S78-1

  • 0.38-2 (5.58-2)

Su-152 A-S24 PCI/g 1.263-1 1.5E-1 (2.93-1) 8u-154 A-524 pCl/g

-1.3S3-2

  • 8.03-2 (1.3E-1) lu-1S5 A-524
  • Cl/g 1.763-1 t 0.98-2 (l.SE-1)
1-a08 A-52t pc+/-t(

5.12E-1 a 7.58-2 (4.9E-2)

Di-212 A-524 pC/ig 1.59BD C 6.31-1 (6.23-11 Pb-212 A-524 pCl/g 1.7310 i 2.43-1 (7.3-21 31i-14 A-524 pCl/g 1.2510 t 1.4E-1 (3.93-11 Pb-214 A-524 PaClg 1.4350 a 1.43-S (9.03-2)

Ra-226 A-524 pCi/g 3.3080 t 1.ED (9.51-1)

Ac-220 A-524 valls 1.47B0

  • 1.65-1 (1.33-i X--2411GS)

A-524 pCI/g

-1.17E-3 1 7.41-2 (1.23-1) m4oisture Content AM22 2216-98 10.0 Act: f Uhc (MC) in the activhty vith 2

clgma uncertainty and the ascsciatod 74inilmt eataot:I,1n Conoentatton.

ty K;

D~

Ul ID R

R ILl

(

F r f

. I

(. $,

(

I.

I t.'

1 i

I

, I I' ".

(

f-( '

Table I (Continued)

Paym 9 of 9 Sample Tdentification 0111-0215W 9528-0000-027PB1 Analytical (11/1S/01)

Parameter Method

_Units Act + Una (MDC)

K-40 RA-100 pei/g 1.15E1 +/- 1.6EO (4.93-1)

Mn-54 RA-100 pCifg 3.77B-3 t 3.5B (6.39-2)

Co-GO RA-100 pCi/g 7.34R-2 + 3.82-2 (7.99-2)

Nb-94 RA-100 pCLI/g

-1.66R-2 j 3.2E-2 (5.5E-21 Ca-134 RA-100 pCi/g 1.54E-2 t 3.7r-2 (5.78-2)

Ca-137 RA-100 pCi/g 5.272-1 & 9.23-2 (7.19-2)

Eu-152 EA-100 pCi/g

-4.343-2.ik i.GH-l (2.8B-1)

Eu-154 RA-100 pCI/g

-4.578-2 j 9.1n-2 (1.7E-11 EU-155 RA-100 pCi/g 1.32E-2 + 1.9B-1 (3.2E-1)

Tl-208 RA-100 pCi/g 4.00E-1

  • 6.22-2 (6.49-21 Bi-212 RA-100 pcifg 1.OOEO D

5.68-1 (l.lBO)

Pb-212 RA-100 pCi/g 1.1810O 2.O0-1 (1.23-1)

Bi-214 RA-l1O pCi/g S.66E-1

  • 1.3E-1 (3.4E-1)

Pb-.214 RA-100 pCi/9 9.:LOE-l +/-'L 163-1 (1.4B-I)

Ra-226 RA-100 pCi/g 1.982E0 +/- 1.30.

(1.8B0)

Ac-228 RA-1OD pCi/g 9.678-1 t 1.8E-1 (2.B11-1)

Am-241(dS)

RA-1OD pCi/g

-8.09E-2

  • 2.72-1 14.68-1)

Moisture Content ASTM 2216-98 IP D

I--

'1m I0-P.

M:

MD I'

I-Pi Act t tIac 114DC) in the activity with 2 eigma Uncertainty and Detectable Concentration.

the aesociated Minimum M)IP = In progneus.

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD b Hard-to-Detect Data (3 Pages)

Tab1 1 Osneral Data Table

  • Dchtel sovwr corporation Anteah Ltd.

cjeoot no. 01-14298

.OaLl Charaotrizatitony rAfs 24296-430-82.00-828O CDC2909 Charga brder No. 24265-18r-a-00443-A0C laddwa Hook Dsorznuiuoning amE,1 Xdenteicltien Analytical (1/1/al Vararetnr t4t00od Miits lCt U na (MO B-3 RA-420 pil/g 5.743-1 A 1.830 (3.280)

C-14 3A-420 pCi/S 1.7810 I l.00 (1.630) re-s A-5-7 p>/g 5.53H2 1 3.5I2 (4.8131)

KL-63 A-527 PCI/g 4.068-1 : 5.410 (9.3B0) 3r-89 RA-320 P3C/g 3.,0-1 1 S.0O-1 (8.11-1)

Sr-go RA-320 pci/g 9.418-3 t 4.6B-1 (8.42-1)

RA-450 pl/s

.7.73E-1 t 1.4B0 (2.3303 X-22 A-526 pCL/g 7.168-3 ; 6.8E-1 (1.380) up-237 Eichrom rCL/g 4.61S-2

  • 3.1E-2 12.53-2)

Pu-238 RA-220 pci/g 2.128;-2 t 3.1E-2 15.38-2)

Pu-23/240 RA-220 pCI/g 1.23B-1 i 6.73-2 (5,3E-21 Pu-241 RA-220 pti/g 0.00O i 2.030 (3.GR03 Ami2411AS) l2A-220 pci/d 2.733-2

  • 2.53-2 (3.18-2)

Cm-242 RA-220 ICi/g 5.043-3

Cz-243/244 RA-220 pci/g 2.483-3 *t 1.1-2 (3.13-2)

N iD I,.

r2 I

10 Act +/- InC imC) in the activity with 2 ais-a dotnctable Coancentration.

uncertainty and the aonociatod Mimiom

Table 1 Canirl Dta Tabe Sochtel lower Corporation antach Ltd. Irneat No. 01-14382 Soil Characterhations FSS 24265-450-82.00-0200 CoCUS98 Charge order na.

24255-FnS-3-00445-ACI Kadd~m Reak DaeotuhsalonIng Pias 1 of 2

_samyle Tdentificactin 0111-0127fl 3S21-O000-0077 Analytical (11/13/021 Parameter Method tnitn Aat + Une (MDCI 11-3 RA-420 pci/g 9.29Z-1 j 3.Geo (5.1EO)

C-24 RA-420 pCl/g 1.572-1

  • 1.760 (3.eso) t"':J A-527 13=/g 5.72E2 :t 3.6S2 tS(.11)

NI-E3 A-527 pCi/g 1.52EO f S.130

, (SO7B0J Sr-OY R IA-320 pai/g

-1.758-2 k 3.9B,1 1.IX-2.)

Sr-gc RA-32D prlIg 2.331-1 k 3.31-1 15.33-1)

TC-ig RA-450 pCI/g 1.16EO f 1.490 (2.4EO0 1-12s A-536 pCi/g

-5.658-1 1 7.23Z1 (1.2EO)

Np-237 Bichrom pr.i/g i.12Z-2

  • 1.63.2 12.11-2)

Pu-23a RA-220 pCi/g 0.00 O

  • 0.0e0 12.S3-2)

PU-232/240 RA-220 Pri/g

'6.65aS2

  • 5.1Z-2 12.93-2)

Yu-241 RA-220 pFC/g

-1.74E-1 +/- 1.930 4(3.413 IM-241(AS)

RA-220 pCI/g 2.261-2 *: 2.01-2

[1.42-21 CM-242 RA-220 pCi/g 2.231-3 tf l.0E-2 (2.SB-2)

Ch.242/244 RA-220 pOI/g

-4.S1E-3

  • 6.48-3 (3.48-21 Act
  • UOn (HlC) is tho activity with 2 aigma une rtainty and the cnnociatud KInfrun Datectabl Conacantratien.

la

  • to

.ul I

SO

Table 2 (CantLinuod)

P2qe I oF 2 Sar'le tdentiftcation

  • ll1-02o.n 3523-0000-007FD Analyt4ial (11/13/01)

Pmrethter Hotod Units act. uto (NDCI 11-3 Rk-420 pC+/-/9 C.35EC t 2.330 (3.480)

C-14 RA.420 pCi/g

-9.262-1 t 1.12O (2.030) 7Y-55 A-527 PC1/9 5.7802 3.6C2 (S.OB1)

A-527 Vci/g 4.3630 t 7.420 (1.221)

Sr-9g R3-320 pcl/g 8.983-1 k 4.3S-1 (4.43-1) ar-go KA-320 pzi/q

-1.868-1 t 3.2E-2.

(6.53-1)

Rc-A 31-450 pCi/g 2.1MG0

  • 1.6BO (2.530) 1-12 A-526 pCi/g 2.313-1 t 7.4B-1 (i.53O)

Up-237

'11chrom pci/9

-2.618-3 I.S.42-3 (3.38-21 PU-231 RA-220 pCh/g

-1.04E-2

(L.38-1)

Pu-239/240 31-220 pCL/g 2.083-2 t 4.21-2 16.23-21 PQ-241 RA-22C pcI/g 2.1220

RA-220 pcl/g 3.16Z-2

  • 2.9E-2 (4.1B-21 Ca-24i RA-220 pCL/g 2.69Z-3
  • 1.23-2 (3.4E-21 CL-243/244 RA-220 pci/g

-2.65U-3 +/- 5.33-3 13.3E-2)

Act i Duic (DC) in the activity with 2 aigma uncertainty and tha aanociated Hlninum Detectable Cocantraticn.

S.

ID I

. *g

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD c Sample and Scan Area Data (2 Pages)

Survey Release Record Scan Area Results Survey Unit 9528-0000 Scan Area 9528-0000 Scan Area 1 Survey

Background

Action Reading Log E-600 Location (cpm)

Level (gross cpm)

Log Date Time S/N 1

12500 14100 12600 11/7/2001 13:13:00 1112 2

12500 14100 14400 11/7/2001 13:14:00 1112 3

12500 14100 12100 1117/2001 13:16:00 1112 4

12500 14100 11900 11/7/2001 13:19:00 1112 5

12500 14100 11700 11/7/2001 13:22:00 1112 6

12500 14100 12500 11/7/2001 13:28:00 1112 7

12500 14100 12200 11/7/2001 13:31:00 1112 8

12500 14100 12900 11/7/2001 13:36:00 1112 9

12500 14100 12800 11/7/2001 13:40:00 1112 1o 12500 14100 15400 11/7/2001 13:45:00 1112 11i 12500 14100 11600 117/72001 13:46:00 1112 12 12500 14100 13100 11/7/2001 13:50:00 1112 13 12500 14100 15000 11/7/2001 13:55:00 1112 14 12500 14100 13000 11/7/2001 13:56:00 1112 15 12500 14100 11600 11/7/2001 14:00:00 1112 16 12500 14100 11900 11/2001 14:05:00 1112 17 12500 14100 11100 11/72001 14:09:00 1112 18 12500 14100 13000 11/72001 14:14:00 1112 19 12500 14100 11400 11/7/2001 14:22:00 1112 20 12500 14100 11700 11/7/2001 14:27:00 1112 21 12500 14100 12700 11/7/2001 14:30:00 1112 22 12500 14100 16000 11/7/2001 14:44:00 1112 Scan Area 9528-0000 Scan Area 6 Survey

Background

Action Reading Log E-600 Location (cpm)

Level (cpm)

(gross cpm)

Log Date Time S/N 1

9000 10400 8700 11/1012001 8:59:00 1113 2

9000 10400 8250 11/10/2001 9:00.00 1113 3

9000 10400 9250 11/10/2001 9:01.00 1113 4

9000 10400 9590 11/10/2001 9:04:00 1113 5

9000 10400 10400 11/10/2001 9:07:00 1113 6

9000 10400 8700 11/10/2001 9:09:00 1113 7

9000 10400 10900 Il/1o/2001 9:11:00 1113 8

9000 10400 9240 11/10/2001 9:12:00 1113 9

9000 10400 11500 11/10/2001 9:13:00 1113 10 9000 10400 9610 11/1012001 9:15:00 1113 1 1 9000 10400 9530 11/10/2001 9:16:00 1113 12 9000 10400 7530 11/1012001 9:19:00 1113 13 9000 10400 9340 11/1012001 9:20:00 1113 14 9000 10400 9860 11/10/2001 9:20.00 1113 15 9000 10400 8570 11/1012001 9:21:00 1113 16 9000 10400 9660 11/10/2001 9:23:00 1113 17 9000 10400 9280 11/10i2001 9:24:00 1113 18 9000 10400 10700 11/10/2001 9:24:00 1113 19 9000 10400 8860 11/102001 9:26:00 1113

Survey Release Record Scan Area Results Survey Unit 9528-0000 Scan Area 9528-0000 Scan Area 7 Survey

Background

Action Reading Log Log E-600 Location (cpm)

Level (cpm)

(gross cpm)

Date Time S/N 1

8500 9800 7000 1118t2001 14:22:00 1112 2

8500 9800 9000 11/8/2001 14:26:00 1112 3

8500 9800 7650 11/8/2001 14:26:00 1113 4

8500 9800 7960 11/8/2001 14:30:00 1112 5

8500 9800 7580 11(8/2001 14:32:00 1113 6

8500 9800 9360 1/8/2001 14:38:00 1112 7

8500 9800 7870 11/8/2001 14:44:00 1112 8

8500 9800 8710 11/8/2001 14:44:00 1113 9

8500 9800 9480 11/8/2001 14:48:00 1112 10 8500 9800 8340 11/8/2001 14:48:00 1113 s

8500 9800 6790 11/8/2001 15:03:00 1112 12 8500 9800 7290 11/8/2001 15:04:00 1113 13 8500 9800 9670 11/8/2001 15:08:00 1113 14 8500 9800 8470 11/8/2001 15:07:00 1112 15 8500 9800 7720 11/8/2001 15:12:00 1113 16 8500 9800 8080 11/8n2001 15:12:00 1112 17 8500 9800 7970 11/8/2001 15:16:00 1113 18 8500 9800 8790 11/8/2001 15:16:00 1112 19 8500 9800 9100 11/8/2001 15:20:00 1112 20 8500 9800 9130 11/8/001 15:21:00 1113 21 8500 9800 9760 118182001 15:24:00 1113 22 8500 9800 8210 11/8/2001 15:25:00 1112 23 8500 9800 8630 11/8/2001 15:26:00 1113 24 8500 9800 9670 11/8/2001 15:27:00 1112 25 8500 9800 7900 11/8/2001 15:29:00 1 12

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD d Split Sample Assessment Forms (2 Pages)

Health Physics Procedure 24265-000-GPP-GGGR-R5 124-000-Rev.CY-000 Attachment A Health Physics Procedure 24265-000-GPP-GGGR-R5 124-000-Rev.CY-000 Attachment A Split Sample Assessment Form Survey Area#: 9528 l Survey Unit #: 0000 Survey Unit name: Southeast Mountain Side Sample Plan or WPIR#: 24265-000-GEN-0000-00061-000 SML#: 9528-0000-007F/7FD Sample

Description:

Comparison of split samples collected to depth (beyond 15 cm) from sample measurement location #7 and analyzed using gamma spectroscopy by off-site Vendor Laboratory.

STANDARD COMPARISON Radionuclide Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (Y/N) pCi/g pCi/g Cs-137 0.711 0.13 11.7 0.6-1.66 0.492 0.088 0.69 Y

Comments/Corrective Actions: N/A Table is provided to show acceptance criteria used to assess split samples.

Resolution Agreement Range 4-7 0.5-2.0 8 -15 0.6 -1.66 16 -50 0.75 -1.33 51 -200 0.80 - 1.25

>200 0.85 -1.18 rned By:l Date l

we Date:

?11 (0.

_s I

Z(

Q.ts 1I/r I

'7I Page 1 of 1

Health Physics Procedure 24265-000-GPP-GGGR-R5124-000-Rev.CY-000 Attachment A Health Physics Procedure 24265-000-GPP-GGGR-R5 1 24-O00-Rev.CY-000 Attachment A Split Sample Assessment Form Survey Area#: 9528 l Survey Unit #: 0000 I Survey Unit name: Southeast Mountain Side Sample Plan or WPIR#: 24265-000-GEN-0000-00061 -000 lSML#: 9528-0000-0014F/FD Sample

Description:

Comparison of split samples collected to depth (beyond 15 cm) from sample measurement location # 14 and analyzed using gamma spectroscopy by off-site Vendor Laboratory.

STANDARD COMPARISON Radionuclide Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (YIN) pCilg pCi/g K-40 10.8 1.4 7.7 0.6-1.66 9.55 1.4 0.88 Y

Comments/Corrective Actions: N/A Table is provided to show acceptance criteria used to assess split samples.

Resolution Agzreement Range 4 -7 0.5 - 2.0 8 -15 0.6 -1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 -1.25

>200 0.85 - 1.18 Pni d By:

Date Revi ye 1

Date:

,7 (.

Page I of I

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD e Preliminary Data Review Form (1 Page)

Heath Physics Procedure 24265-000-GPP-GGGR-R5123-000-Rev.CY-000 Attachment B PRELIMINARY DATA REVIEW FORM Survey Unit:

Survey Unit Name:

Classification:

Survey Media:

Type of Survey:

Type of Measurement:

Number of Measurements:

Operational DCGL (pCitg) 9528-0000 Southeast Mountain side 3

Soil Final Status Survey Radionuclide Specific 14 3.16pCi/g w

St BASIC STATISTICAL QUANTITIES Cs-137 Minimum Value:

1.08E-01 Maximum Value:

9.43E-01 Mean:

5.89E-01 Median:

6.25E-01 andard Deviation:

2.29E-01 NUMBER 9528-0000-OOF 9528-0000-002F 9528-0000-003F 9528-0000-004F 9528-0000-005F 9528-0000-007F 9528-0000-008F 9528-0000-009F 9528-0000-01OF 9528-0000-01 IF 9528-0000-012F 9528-0000-013F 9528-0000-014F 9528-0000-01SF eviewed by/Date RADIONUCLIDE CONCENTRATION (pCi/g)

Cs-137 Identified?

1.35E-01 Y

7.27E-01 Y

5.71E-01 Y

5.32E-0 Y

9.43E-0I Y

7.1 1E-0I Y

6.71E-01 Y

5.93E-01 Y

1.08E-01 Y

7.73E-01 Y

7.58E-01 Y

5.03E-01 Y

6.57E-01 Y

5.57E-01 Y

"? k

-7 /,.v 9-

1 of 1

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD f Graphical Representation of Data (2 Pages)

Health Physics Procedure

-24265-000-GPP-GGGR-R5 123-000-Rev.CY-000 Attachment C Health Physics Procedure 24265-000-GPP-GGGR-R5 1 23-000-Rev.CY-O00 Attachment C DATA FREQUENCY PLOT Survey Unit:

Survey Unit Name:

9528-0000 Southeast Mountain Side Survey Area Frequency Plot For Cesium-137

+

.1 0.16 0.4 0.46 0.52 0.58 0.64 0.7 0.76 0.82 0.94 Upper End Value (pCisg)

Bins Observation Observation %

Upper End Value Frequency Frequency 0.1 0

0%

0.16 2

14%

0.22 0

0°/° 0.28 0

00%

0.34 0

0%h 0.4 0

0%

0.46 0

0%

0.52 1

7%

0.58 3

21%

0.64 1

7%

0.7 2

14%

0.76 3

21%

0.82 1

7%

0.88 0

0%

0.94 0

0%

1 1

7%

Total:

14 100%

I (3. Qz~-

Submitted By/Date 9

  • 7 w

/-7 /lbC

.I Gus I

,5~eweaB'f1Date I. -,

V

Health Physics Procedure 24265-000-GPP-GGGR-R5123-000-Rev.CY-000 Attachment C Health Physics Procedure 24265-000-GPP-GGGR-R5 1 23-000-Rev.CY-000 Attachment C Survey Unit:

Survey Unit Name:

DATA QUANTILE PLOT 9528-0000 Southeast Mountain Side Survey Area Quantile Plot For Cesium-137 0.85 --

o aL.

0

,85.--Nv o

0.65

-i_

0.25 0.05... r.

0 20 40 60 80 100 Percentage Cs-137 Rank Percentage 1.08E-01 1

4%

1.35E-01 2

11%

5.03E-01 3

18%

5.32E-01 4

25%

5.57E-01 5

32%

5.71E-01 6

3h9%

5.93 E-01 7

46%

6.57E-01 8

54%

6.71E-01 9

61%

7.1 IE-OI 10 68%

7.27E-01 11 75%

7.58E-01 12 82%

7.73E-01 13 89%

9.43 E-01 14 96%

Submitted By/Date RVewved By/Date

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD g Sign Test Calculation (1 Page)

Health Physics Procedure 246-0-P-GRR1100RvC 0 Attahmn _

Health Physics Procedure 24265-000-GPP-GGGR-R5 12 1-000-Rev.CY-000 Attachment B Sign Test Calculation Sheet for a Single Radionuclide Survey Unit Number: 9528-0000 Survey Unit Name: Southeast Mountain Side WP&IRX: 24265-000-GEN-0000-00061-000 Classification: 3 TYPE I (a error): 0.05 TYPE II (13 error): 0.05 Radionuclide:

Cesium-137 Survey Design DCGL (pCi/g):

3.16 Results (pCi/g)

DCGL - Results Sign 0.135 3.03 1

0.727 2.43 1

0.571 2.59 1

0.532 2.63 1

0.943 2.22 1

0.711 2.45 1

0.671 2.49 1

0.593 2.57 1

0.108 3.05 1

0.773 2.39 1

0.758 2.40 1

0.503 2.66 1

0.657 2.50 1

-0.557 2.60 1

Number Of Positive Differences (S+):

14 Critical Value: 11 Survey Unit: Meets Acceptance Criterion Cow Performed By:

Independent Review By:

Date:

.k \\

4. ()

Date:

2 /

y/6*7 I

Page 1 of I

SOUTHEAST MOUNTAIN SIDE SURVEY UNIT 9528-0000 RELEASE RECORD h COMPASS DQA Surface Soil Report with Retrospective Power Curve (2 Pages)

DQA Surface Soil Report Assessment Summary Site:

Planner(s):

Survey Unit Name:

Report Number:

Survey Unit Samples:

Reference Area Samples:

Test Performed:

Judgmental Samples:

Assessment

Conclusion:

9528-0000 C.E.Davis Southeast Mountain Side 1

14 0

Sign Test Result:

Not Performed 0

EMC Result:

Not Performed Reject Null Hypothesis (Survey Unit PASSES)

Retrospective Power Curve W.,

a 0.9 0-

.Z 0.8 a

'-'0.7 ii 0.6 W. 0.5 5.3 R 0.4 4a 0.3 e

A; 0.2 L.

Q 0.1 A.

0

-A_-_.

Is I 7

I_

__l

. 1 z__

I

-I -I I

I I

I 5

+=--

0.5 1.0 1.5 2.0 2.5 3.0 Soil Coxcextraloax (pCif/g hiluiing backgrouxd Prospective Power 1-beta

- Actual Power LBGR Estikated Power DCGL Retrospective Power 3.5 c::c e5Vp

co5 COMPASS vl.0.0

'111112005 Page 1 COMPASS v1.0.0

/'

1/12005 Page 1

DQA Surface Soil Report Survey Unit Data NOTE:

Type=S

'indicates survey unit sample.

Type = 'R-Indicates reference area sample.

Sample Number 9528-0000-001 F 9528-0000-002F 9528-0000-003F 9528-0000-004F 9528-0000-005F 9528-0000-007F 9528-0000-008F 9528-0000-009F 9528-0000-01OF 9528-0000-01 1 F 9528-0000-012F 9528-0000-01 3F 9528-0000-014F 9528-0000-015F Type S

S S

S S

S S

S S

S S

S S

S Cs-137 (pCig) 0.14 0.73 0.57 0.53 0.94 0.71 0.67 0.59 0.11 0.77 0.76 0.5 0.66 0.56 Basic Statistical Quantities Summary Statistic Survey Unit Backaround DQO Results Sample Number 14 N/A N=13 Mean (pCi/g)

Median (pCi/g)

Std Dev (pCi/g)

High Value (pCi/g)

Low Value (pCi/g) 0.59 NMA 0.8 0.63 N/A N/A 0.23 N/A 0.24 0.94 NMA N/A 0.11 N/A N/A 1/11 005 COMPASS v1.0.0 Page 2

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