Text

Haddam Neck - Final Status Survey Final Report - Phase Vii - Chapter 10
	ML071550108
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/29/2007
From:	VanNoordennen G P; Connecticut Yankee Atomic Power Co
To:	; Document Control Desk, NRC/FSME
References
	CY-07-089
	Download: ML071550108 (129)
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD -EAST HAMPTON, CT 06424-3099 MAY 2 9 2007 Docket No. 50-213 CY-07-089 Re: 10 CFR 50.82(a)(11)

U. S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D. C. 20555-0001 Haddam Neck Plant Final Status Survey Final Report -Phase VII -Chapter 10 The Haddam Neck Plant (HNP) License Termination Plan (LTP) (Section 1.4)describes the process of releasing land from the HNP Operating License. The HNP LTP Section 5.9.2 states that the Final Status Survey (FSS) Final Report will be prepared and submitted in a phased approach.Connecticut Yankee Atomic Power Company (CYAPCO) submitted the FSS Final Report for Phase VII on May 17, 20071. CYAPCO is hereby submitting the attached FSS Final Report -Phase VII -Chapter 10 Survey Unit Release Record. This Release Record was inadvertently misplaced in the process of copying and assembling the Phase VII report with the other survey unit release records. We apologize for any inconvenience this may have caused you.A request to release the NRC license from FSS areas covered under Phases III through VII will be submitted under separate cover.If you should have any questions regarding this submittal, please contact me at (860) 267-3196.Sincerely, G. P. van Noordennen Date Director, Regulatory Affairs and Quality Assurance 1 Gerard P. van Noordennen (CYAPCO) to USNRC Document Control Desk, Final Status Survey (FSS) Final Report -Phase VII, May 17, 2007.0j rV 55 _ I U.S. Nuclear Regulatory Commission CY-07-089/

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Final Status Survey (FSS) Final Report -Phase VII -Chapter 10 Survey Unit Release Record cc: S. J. Collins, NRC Region 1 Administrator T. B. Smith, NRC Project Manager, Haddam Neck Plant R. Lorson, Chief, Decommissioning Branch, NRC Region 1 E. L. Wilds, Jr., Director, CT DEP Radiation Division m ~Book 10 of 19 Final Status Survey Final Report Phase VII Appendix A9 Survey Unit Release Record 9312-0007, Radiologically Controlled Area / RRF BLDG/115 kV East Footprint May 2007 CYAPCO FINAL STATUS SURVEY RELEASE RECORD RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007/,0)-" ý? kl;,- z,,, //,-Prepared By: Reviewed By: Approved By:_FSS Engineer/2 Date: 3 /.--7 Date: ?-/<--#*Date: /i7/FSS Fýineer Te ica] Support Manager Revision 0 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD TABLE OF CONTENTS 1. SURVEY UNIT DESCRIPTION

...............................................................

3 2. CLASSIFICATION BASIS ........................................................................

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

6 4. SURVEY DESIG N ....................................................................................

9 5. SURVEY IMPLEMENTATION

...............................................................

12 6. SURVEY RESULTS ................................................................................

13 7. QUALITY CONTROL .............................................................................

19 8. INVESTIGATIONS AND RESULTS ......................................................

19 9. REMEDIATION AND RESULTS ............................................................

19 10. CHANGES FROM THE FINAL STATUS SURVEY PLAN .....................

19 11. DATA QUALITY ASSESSMENT (DQA) ................................................

19 12. A NO M A LIES ..........................................................................................

20 13. CO NC LUSIO N .......................................................................................

21 14. ATTACHM ENTS .....................................................................................

21 14.1 Attachment 1 -Figures (6 pages including cover)14.2 Attachment 2 -Scan Results (5 pages including cover)14.3 Attachment 3 -Laboratory Data (80 pages including cover)14.4 Attachment 4 -DQA Results (14 pages including covers)Total 127 Revision 0 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD SURVEY UNIT DESCRIPTION Survey Unit 9312-0007 (Radiologically Controlled Area, Radwaste Reduction Facility (RRF), 115 kV East Footprint) is designated as Final Status Survey (FSS)Class 1 and consists of approximately one thousand five hundred sixty six square meters (1,566 m 2) of uninhabited land and is located approximately sixteen hundred ninety four feet (1,694 ft) from the reference coordinate system benchmark used at Haddam Neck Plant (HNP) (see Attachment 1). The survey unit is bounded as follows: land Survey Unit 9312-0002 to the north (called north as oriented with the north to south flow of the Connecticut River), land Survey Unit 9312-0010 to the east, land Survey Units 9522-0006 and 9522-0007 to the south, and land Survey Unit 9312-0008 to the west. The survey unit is located along the south boundary of Survey Area 9312. As a result of demolition and remediation activities, the area topography is mostly flat and de-vegetated.

The reference coordinates associated with this survey unit are EQ 11 through EO 13 by S070 through S072 (refer to "HNP License Termination Plan" (LTP) 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) based on the Connecticut State Plane System North American Datum (NAD) 1927.2. CLASSIFICATION BASIS The survey unit was classified in accordance with Procedure RPM 5.1-10,"Survey Unit Classification." The "Classification Basis Summary" conducted for Survey Unit 9312-0007 consisted of: a) A review of the 10CFR50.75 (g) (1) database, b) A review of the "Initial Characterization Report" and the "Historic Site Assessment Supplement," c) Historic and current survey records review, d) Visual inspections and a "walkdown." A review of the "Initial and Supplemental Characterization Reports " as well as the previous "Classification Basis Summaries" was performed.

The source documents, the "Connecticut Yankee Haddam Neck Characterization Report" and "Initial Classification for Survey Areas at Connecticut Yankee", were incorporated by reference in LTP, Revision 0.During plant operation, Survey Unit 9312-0007 was a part of the radiological controlled area and the location of significant, radiologically contaminated structures and systems. Structures included the primary water storage tank and Revision 0 3 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD backup primary water storage tank.Major demolition and remediation activities began in 2002. All radioactive systems and components located inside the Containment Building, including the reactor vessel, were removed and appropriately packaged and shipped to an approved off-site disposal facility.

Interior structural surfaces inside the Containment Building were decontaminated to ensure contamination levels were acceptable for controlled demolition.

Interior walls and floors were then demolished and removed. The Containment liner was removed with the exception of the Incore Sump. The dose from residual radioactivity on the remaining steel and concrete in the sump was accounted for in the "Basement Fill Model". The Incore Sump was then filled with grout to the basement floor elevation.

The remaining interior surfaces inside the Containment shell were decontaminated.

Following decontamination, the Containment basement was filled with clean soil to the grade of the exterior open land. The above grade portion of the Containment structure was then demolished and removed. Confirmatory radiological surveys were performed throughout the demolition process. No above grade structures currently reside within Survey Area 9312.Outside of the containment shell, soil remediation began around the northeast, northwest and southeast quadrants of the survey unit. A large excavation was created to the north of the Containment that was designated as Excavation

1.This excavation included the area in the vicinity of the Refueling Water Storage Tank and the Primary Auxillary Building (PAB) corrider.

A second large excavation, also designated as Excavation

2 was located over the Service Building footprint.

A third excavation, designated as Excavation

3 was located in the area between the Containment Building and Spent Fuel Building (SFB).As adjacent structures were demolished, soil was excavated and removed. This process continued until bedrock was exposed. Subsurface structures and footings that remained following demolition and excavation include the Containment Mat, the Cable Vault wall, the Service Building east wall, a remnant of the PAB northwest wall, Waste Disposal Building footing and miscellaneous fragments of footings and slabs on the bedrock. As with the Containment basement shell, all excavations were backfilled with clean fill following the performance of a radiological assessment.

In Survey Area 9312, post-remediation soil samples were taken from the as-left surface soils under two (2) Survey and Sampling Work Plans, SSWP-06-08-000 and SSWP-06-12-001.

Thirty-five (35) post remediation surface soil samples were collected from the various locations within Survey Area 9312. All samples were collected and analyzed by gamma spectroscopy by an approved off-site laboratory.

Ten (10) of the thirty-five (35) post remediation samples collected were analyzed for the full suite of "Hard-to-Detect" (HTD) radionuclides Revision 0 4 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD specified in the LTP, Table 2-12, "Radionuclides Potentially Present at Haddam Neck Plant" and as provided in Table 3. Statistical quantities (mean, median and standard deviation) from the 2006 post-remediation survey conducted under SSWP-06-08-000 and SSWP-06-12-001 are provided in Table 1.Table 1 -Basic Statistical Quantities for Cs-137 and Co-60 from the 2006 Post Remediation Survey Cs-137 Co-60 (pCi/g) (pCi/g)Minimum Value: 1.32E-02 -5.OOE-02 Maximum Value: 1.70E+00 1.43E+00 Mean: 2.38E-01 1.08E-01 Median: 1.65E-01 1.46E-02 Standard Deviation:

3.10E-01 2.76E-01 A review of this sample data shows Cs-137 and Co-60 to be the primary radionuclides of concern, with both isotopes reported at fairly low concentrations.

The sample population as a whole was evaluated to assess the distribution of the detected radionuclides.

The radionuclide distribution percentage for each sample in the population was calculated by dividing the concentration of each detected radionuclide by the total activity concentration in the sample, expressing the abundance of the specific nuclide in the sample compared against the total activity.

The mean radionuclide distribution was then calculated by taking the average of the individual sample distribution fractions.

The results are provided in Table 2.Table 2 -Distribution Fraction for Detectable Radionuclides in Soil Sample Population Detected Radionuclide Distribution Fraction Cs-137 0.689 Co-60 0.311 No HTD radionuclides were positively identified in concentrations meeting the accepted criteria for detection (i.e., a result greater than two (2) standard deviations uncertainty).

Radionuclide screening or de-selection is a process where an individual radionuclide or aggregates may be considered insignificant and eliminated from the FSS. The criteria for de-selection are concentrations less than 5% for individual radionuclides and less than 10% for aggregates.

While Sr-90 was not identified in the soil characterization results, it was decided Revision 0 5 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD to include Sr-90 as a radionuclide of concern for this survey unit as Sr-90 was prevalent in the soils prior to remediation.

Therefore, all volumetric soil samples taken as part of the survey design for this survey unit were subjected to direct analysis for Sr-90.The FSS Engineer performed a visual inspection and walk-down during January 2007 to assess the physical condition of the survey unit, evaluate access points, travel paths and identify potentially hazardous conditions.

This survey area is affected by existing and future groundwater (reference CY memo ISC 06-024) which will be a source of dose from residual radioactivity, as discussed in Section 3 under the Data Quality Objectives.

Based upon the identification of radioactive material above the Derived Concentration Guideline Levels (DCGLs), and the need for radiological remediation, it was concluded that there was some probability for residual radioactivity in concentrations greater than the DCGLs, justifying a final survey unit classification of Class 1 (refer to Section 3).3. DATA QUALITY OBJECTIVES (DQO)FSS design and planning used 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 indicate that residual activity within the survey unit does not exceed the release criteria.The primary objective of the FSS plan was to demonstrate that the level of residual radioactivity in Survey Unit 9312-0007 did not exceed the release criteria specified in the LTP and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA).A fundamental precursor to survey design is to establish a relationship between the release criteria and some measurable quantity.

This is done through the development of DCGLs. The DCGLs represent average levels of radioactivity above background levels and are presented in terms of surface or mass activity concentrations.

Chapter 6 of the LTP describes in detail the modeling used to Revision 0 6 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD develop the DCGLs for soil (called Base Case Soil DCGL), existing groundwater radioactivity and future groundwater radioactivity that will be contributed by building basements and footings.The DCGLs presented in Chapter 6 of the LTP were developed for exposures from three (3) components, that is, residual radioactivity in soil, existing groundwater radioactivity, and future groundwater radioactivity from the burial of concrete foundations or footings from site buildings containing residual radioactivity.

Equation 1 shows the mathematical relationship between the three (3) components and the total dose.Equation 1 H Total = H Soil-+ HExistingGW

+ HFutureG W The total dose under the LTP criteria is twenty-five (25) mrem/yr Total Effective Dose Equivalent (TEDE) from all three (3) components.

The allowable total dose under the Connecticut Department of Environmental Protection (CTDEP)radiological remediation standard for CY is nineteen (19) mrem/yr TEDE. To satisfy both the LTP and CY CTDEP criteria, the dose from soil must be reduced when using the existing and future groundwater dose values discussed above.This survey area is affected by existing groundwater (reference CY memo ISC 06-024). Therefore, the dose contribution from existing groundwater is bounded by two (2) mrem/yr TEDE.This survey unit is considered impacted by future groundwater radioactive contamination, as there are underground foundations containing residual radioactive material within the groundwater saturated zone in the area (reference CY memo ISC 06-024). The dose contribution from future groundwater, the third dose component, is bounded by two (2) mrem/yr TEDE.Equation 2 19 mrem/yrTotal

= 15 mrem/yrsoil

+ 2 mrem/yrExisting Gw+ 2 mrem/yrFutureGW The allowable dose for soil in this survey unit is fifteen (15) mrem/yr TEDE as shown by Equation 2 above. The concentration of residual radioactivity resulting in fifteen (15) mrem/yr TEDE is designated as the Operational DCGL (DCGLop), and has been established for the radionuclides of concern as provided in Table 3.Revision 0 7 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD Table3- Radionuclide Specific Base Case Soil DCGLs, Operational DCGLs and Required Minimum Detectable Concentrations (MDCs)Radionuclide

() Base Case Soil Operational Required MDC DCGL DCGL (pC/g) (4)(pC/g) (2) (pC/g) (3)H-3 4.12E+02 2.47E+02 1.65E+01 C-14 5.66E+00 3.40E+00 2.26E-01 Mn-54 1.74E+01 1.04E+01 6.96E-01 Fe-55 2.74E+04 1.64E+04 1.1OE+03 Co-60 3.81E+00 2.29E+00 1.52E-01 Ni-63 7.23E+02 4.34E+02 2.89E+01 Sr-90 1.55E+00 9.30E-01 6.20E-02 Nb-94 7.12E+00 4.27E+00 2.85E-01 Tc-99 1.26E+01 7.56E+00 5.04E-01 Ag-108m 7.14E+00 4.28E+00 2.86E-01 Cs-134 4.67E+00 2.80E+00 1.87E-01 Cs-137 7.91E+00 4.75E+00 3.16E-01 Eu-152 1.01E+01 6.06E+00 4.04E-01 Eu-154 9.29E+00 5.57E+00 3.72E-01 Eu-155 3.92E+02 2.35E+02 1.57E+01 Pu-238 2.96E+01 1.78E+01 1.1 8E+00 Pu-239/240 2.67E+O1 1.60E+01 1.07E+00 Am-241 (5) 2.58E+01 1.55E+01 1.03E+00 Pu-241 8.70E+02 5.22E+02 3.48E+01 Cm-243/244 2.90E+O 1 1.74E+01 1.16E+00 (1) Bold indicates those radionucldies considered Hard to Detect (HTD)(2) The Base Case Soil DCGL(s) are specified by the LTP in Chapter 6 and are equivalent to twenty-five (25) mrem/yr TEDE (3) The Operational DCGL is equivalent to achieving fifteen (15) mrem/yr TEDE (4) The required MDC is equivalent to achieving one (1) mrem/yr TEDE (5) Americium-241 can be analyzed by gamma and alpha spectroscopy and is considered to be Easy to Detect (ETD). The preferred result is the alpha spectroscopy's when both analyses are performed Revision 0 8 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD Another important facet of the DQO process is to identify the radionuclides of concern and determine the concentration variability.

Soil samples were collected in 2006 to establish the radiological condition of Survey Unit 9312-0007 for FSS.Cs-137 and Co-60 were the two (2) gamma emitting radionuclides reported in concentrations with the potential for exceeding the release criteria.

Sr-90 was included as a radionuclide of concern due to it's prevalence in the soil prior to remediation.

The characterization data were used for the survey design and are provided in Table 1.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 required prior to issue and after the instrument had been used. Control and accountability of survey instruments was required to assure the quality and prevent the loss of data.As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. Results reported as less than Minimum Detectable Concentration (MDC) were not accepted for FSS. Sample report summaries included unique sample identification, analytical method, radionuclide, result, and uncertainty to two (2) standard deviations, laboratory data qualifiers, units, and the required and observed MDC.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. Guidance for preparing FSS plans is provided in Procedure RPM 5.1-11, "Preparation of Final Status Survey Plans".The FSS plan uses an integrated sample design that combines scanning surveys and sampling which can be either random or biased.The DQO process determined that Cs-137, Co-60 and Sr-90 would be the radionuclides of concern in Survey Unit 9312-0007 (refer to Section 3). The characterization survey did not include any other additional HTD radionuclides of concern for this survey unit. As Sr-90 concentrations were determined by direct analysis, surrogate DCGLs were not required as part of the survey design for this survey unit via screening under LTP Section 5.4.7.2, "Gross Activity DCGLs". Other radionuclides that were positively identified in concentrations greater than the screening criteria during the performance of this FSS would be evaluated to ensure adequate survey design.As the survey unit is classified as a Class 1 surface soils area, and discrete, elevated areas of contamination was possible, the application of the Elevated Measurement Comparison (EMC) remained an option.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.Revision 0 9 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD 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 Final Status Survey." The Lower Bound of the Gray Region (LBGR) was set in accordance with Procedure RPM 5.1-11 to 0.73 to achieve a relative shift (A/a)in the range of 1 and 3. The resulting adjusted relative shift was 2.0. A Prospective Power Curve was generated using COMPASS, a software package developed under the sponsorship of the United States Nuclear Regulatory Commission (USNRC) for implementation of the MARSSIM in support of the decommissioning license termination rule (1OCFR20, Subpart E). The result of the COMPASS computer run showed adequate power for the survey design. The survey design specified fifteen (15) surface soil samples for non-parametric statistical testing. Based upon a review of the historical information and Characterization Survey data, the acquisition of additional judgmental surface soil samples from within this survey unit was deemed unnecessary.

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 Final Status Survey." Visual Sample Plan was created by Pacific Northwest National Laboratory (PNNL) for the United States Department of Energy. A systematic triangular grid pattern with a random starting point was selected for sample design, which is appropriate for a Class 1 area.Sample locations were identified using AutoCAD-LT, a commercially available plotting software package with coordinates consistent with the Connecticut State Plane System. These coordinates were integrated with a GPS to locate sample locations in the field. Sample Measurement Locations for the design are listed with the GPS coordinates in Table 4.Table 4 -Sample Measurement Locations with Associated GPS Coordinates Designation Northing Easting 9312-0007-001F 236590.70 668931.54 9312-0007-002F 236590.70 668967.43 9312-0007-003F 236559.62 668913.60 9312-0007-004F 236559.62 668949.49 9312-0007-005F 236559.62 668985.38 9312-0007-006F 236528.54 668895.66 9312-0007-007F 236528.54 668931.54 9312-0007-008F 236528.54 668967.43 Revision 0 10 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD Table 4 -(continued)

Designation Northing Easting 9312-0007-009F 236528.54 669003.32 9312-0007-OIOF 236497.46 668877.71 9312-0007-01IF 236497.46 668913.60 9312-0007-012F 236497.46 668949.49 9312-0007-013F 236497.46 668985.38 9312-0007-014F 236466.38 668931.54 9312-0007-015F 236466.38 668967.43 Procedure RPM 5.1-11 specifies that 5% of the samples are required to be selected for HTD analysis.

Two (2) soil samples, or about 10% of the number of samples that would be used for non-parametric statistical testing were randomly selected for HTD radionuclide analysis using the Microsoft Excel"RANDBETWEEN" function.

Each sample was sent off-site for a full suite analysis of the HTD radionuclides specified in the LTP, Table 2-12,"Radionuclides Potentially Present at Haddam Neck Plant" and as provided in Table 3.The LTP requires a minimum of 5% of the samples taken for non-parametric statistical testing be selected for QC evaluation.

The implementation of quality control measures as referenced by Procedure RPM 5.1-24, "Split Sample Assessment for Final Status Survey," included the collection of one (1) soil sample for "split sample" analysis by the off-site laboratory.

This location was selected randomly using the Microsoft Excel "RANDBETWEEN" function.The LTP specifies a required scanning coverage of 100% for outdoor Class 1 areas.For this Class 1 survey unit, the "Investigation Level" for area scanning and soil sample measurement results are those levels specified in LTP, Table 5-8. Table 5 provides a synopsis of the survey design.Revision 0 I1I RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD Table 5 -Synopsis of the Survey Design Feature Design Criteria Basis Survey Unit Land Area 1,566 m 2 Based on AutoCAD-LT Type 1 and Type 2 errors were 15 0.05, sigma was 0.14 the LBGR Number of Measurements was set at 0.73 to achieve a (15 systematic grid) Relative Shift in the range of 1 and 3 Grid Spacing 10.98 m Based on triangular grid 4.75 pCi/g Cs-137 Administratively set to achieve Operational DCGL 2.29 pCi/g Co-60 fifteen (15) mrem/yr TEDE (1)The Operational DCGL meets the Soil Investigation Level LTP criteria for a Class 1 survey 2.29 pCi/g Co-60 unit Scan Survey Area Approximately The LTP requires 100% area Coverage 100% of the area coverage for Class I survey units An instrument response greater Based upon a Minimum Detectable than the Scan Count Rate (MDCR) of 2,020 cpm Scan Investigation Level MDC(DCGLEMC) and a corresponding MDCsca, of of 2,590 cpm plus 12.07 pCi/g Cs-137 and 2.98 pCi/g ambient Co-60 background (1) The allowable dose for soil in this survey unit is fifteen (15) mrem/yr TEDE as the bounding dose from existing and future groundwater has been established based on field data (reference CY memo ISC 06-024)5. SURVEY IMPLEMENTATION Final status survey field activities were conducted under the Final Status Survey Plan (FSSP). The FSSP a 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"Daily Survey Journal" was used to document field activities and other information pertaining to the FSS.A single scan area was established that constituted approximately 100% of the surface area of Survey Unit 9312-0007.

Grid lines, one (1) meter wide, were painted on the ground of the scan area. A background survey was performed around the survey unit and it was determined that, using an Eberline E-600 with a SPA-3 sodium iodide detector, background ranged from 7,220 counts per minute (cpm) up to 12,400 cpm.Revision 0 12 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD The scan area was established and scanned for elevated readings (see Attachment 2 for all scan results).

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.Approximately 100% of the survey unit was scanned.Measurement locations were identified in North American Datum (NAD) 1927 coordinates using GPS coordinates; sample locations were identified and marked with a surveyor's flag or paint for identification.

At each sample location, a one (1) meter radius circle was established around the sample flag or paint mark was scanned for elevated radiation levels.Fifteen (15) surface soil samples were collected and packaged in accordance with Haddam Neck Plant (HNP) Procedure RPM 5.1-3, "Collection of Sample Media for 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 Final Status Survey Samples." Two (2) samples (9312-0007-002F and 9312-0007-014F) were randomly selected for HTD radionuclide analysis.The implementation of survey specific quality control measures included the collection of one (1) sample (9312-0007-003F) for "split sample" analysis.6. SURVEY RESULTS All field survey activities were conducted on January 23, 2007.The sample locations identified in the FSS plan were scanned over approximately a one (1) meter radius for elevated radiation levels. Table 5 provides an overview of the scan results for sample measurement locations.

Scan results are provided in Attachment 2.Table 5 -Scan Results for Sample Measurement Locations Sample Highest Logged Action Level (1)Measurement Reading (k' > Action Level (2)Location (kcpm) (cpm)1 11.40 12.50 NO 2 11.70 13.03 NO 3 8.03 11.33 NO 4 11.70 13.03 NO Revision 0 13 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD Table 5 -(continued)

Sample Highest Logged Action Level (1)Measurement Reading (kcpm) > Action Level (2)Location (kcpm)5 8.03 11.33 NO 6 11.90 13.46 NO 7 8.03 11.33 NO 8 11.90 13.46 NO 9 10.80 12.50 NO 10 11.90 13.46 NO 11 10.80 12.50 NO 12 8.41 11.00 NO 13 10.80 12.50 NO 14 8.41 11.00 NO 15 9.24 10.08 NO (1) The action level is based on a measurement above ambient background.

(2) The FSS plan requires movement of the sample measurement location to the area within the 1 meter radius yielding the response above the action level.The scan areas, that comprised approximately 100% of the total surface area for the survey unit, were scanned for elevated radiation levels. The areas were scanned in accordance with the FSS plan on January 23, 2007.Sixty (60) scan strips were initially established in this survey unit. No elevated measurement locations were identified during scanning.

Table 6 provides an overview of the scan area survey. Scan results are provided in Attachment 2.Revision 0 14 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD Table 6 -Scan Area Results Highest Action Scan Strips Logged Level (I) Elevated Reading Investigation Reading Identification Sample (kcpm) (kcpm)I thru 60 12.20 15.00 N/A N/A (1) The action level is based on a measurement above ambient background plus a conservative estimate of DCGLEMc equivalent of 2,590 cpm (2) ER is an abbreviation associated with the barcodes used in the field where ER stands for Elevated Reading.The off-site laboratory employed for the radiological analyses of samples was General Engineering Laboratories, LLC. The laboratory analyzed the fifteen (15)samples collected for non-parametric statistical testing, the associated field splits using gamma spectroscopy.

Gamma spectroscopy analysis was performed to the required MDCs. Gamma spectroscopy results identified some radionuclides meeting the accepted criteria for detection (i.e., a result greater than two (2)standard deviations uncertainty).

However, Cs-137 was the only gamma-emitting radionuclides reported in concentrations exceeding the de-selection criteria.Cs-137 was identified in five (5) and Co-60 was identified in none (0) of the fifteen (15) samples collected for non-parametric statistical testing. The mean of the gamma spectroscopic analysis results for the sample population indicated that Cs-137 was present at levels slightly higher than expected environmental levels for Cs-137 within the vicinity of the HNP as presented in the Health Physics TSD BCY-HP-0063.

A summary of the fifteen (15) samples collected for non-parametric statistical testing results is provided in Table 7.Table 7 -Summary of Gamma Spectroscopy Results for Surface Soil Samples Comprising the Statistical Sample Population Cs-137 Co-60 Sample Number pCi/g pCi/g 9312-0007-001F

-3.33E-03 1.19E-02 9312-0007-002F 7.16E-03 5.11E-04 9312-0007-003F 2.04E-02 4.25E-03 9312-0007-004F

-2.83E-04 2.58E-02 9312-0007-005F 8.94E-02 -1.42E-02 9312-0007-006F 2.49E-03 5.87E-03 Revision 0 15 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD Table 7 -Summary of Gamma Spectroscopy Results for Surface Soil Samples Comprising the Statistical Sample Population Cs-137 Co-60 Sample Number pCi/g pCi/g 9312-0007-007F 0.OOE+00 5.87E-03 9312-0007-008F 1.26E-02 -3.06E-03 9312-0007-009F 1.51E-02 -8.56E-03 9312-0007-01 OF 3.1 OE-02 -1.07E-02 9312-0007-01IF

-1.07E-02

-3.76E-03 9312-0007-012F

-3.70E-03 1.07E-02 9312-0007-013F 7.54E-02 1.40E-02 9312-0007-014F 1.01E-02 -1.17E-03 9312-0007-015F 8.77E-02 3.15E-02 In addition to Cs-137 and Co-60, Sr-90 was also identified during the DQO process as a radionuclide of concern. Subsequently, all samples were subjected to analysis by gas proportional counting for Sr-90. All analyses met the required minimum MDC.Sr-90 was positively identified (i.e., a result greater than two (2) standard deviations uncertainty) in one (1) of the fifteen (15) samples collected for non-parametric statistical testing. The results of the Sr-90 analysis for the statistical sample population are provided below in Table 8.Table 8 -Summary of Sr-90 Analysis Results for Surface Soil Samples Comprising the Statistical Sample Population Sample Number Sr-90 pCi/g 9312-0007-001IF

-7.12E-03 9312-0007-002F 4.39E-03 93142-0007-003F 8.79E-03 9312-0007-004F 1.94E-03 9312-0007-005F 4.24E-03 9312-0007-006F 1.25E-02 Revision 0 16 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD Table 8 -Summary of Sr-90 Analysis Results for Surface Soil Samples Comprising the Statistical Sample Population Sr-90 Sample Number pCi/g 1.43E-03 9312-0007-007F 14E0 931 2-0007-008F 2.36E-03 9312-0007-009F

-2.6 1E-03 93 12-0007-OIOF

-2.13E-04 9312-0007-OIF 1.38E-02 9312-0007-012F 1.71E-04 9312-0007-013F 1.36E-02 9312-0007-014F 1.10E-02 9312-0007-015F 1.46E-02 In addition to Sr-90, the off-site laboratory also processed, as required by the sample plan, two (2) samples for the full suite of HTD radionuclides as specified in LTP, Table 2-12, "Radionuclides Potentially Present at Haddam Neck Plant" and as provided in Table 3. The requested analyses included alpha spectroscopy, gas proportional counting, and liquid scintillation depending on the radionuclide and the measurement method. All analyses performed met the required minimum MDC. In one (1) Tritum (H-3) was detected at 0.2 Percent of the DCGL which is below the selection criteria discussed in Section 2. No additional HTD radionuclides were positively identified (i.e., a result greater than two (2) standard deviations uncertainty).

The "sum-of-fractions" or "unity rule" is the mathematical test used to evaluate compliance with radiological criteria for license termination when more than one radionuclide has been determined to be potentially present. The combination of the fractions of each detected radionuclide against their respective Operational DCGL must be less than or equal to one (1). The unity rule is: Equation 3 C, + C 2 Cý <1 DCGLI DCGL 2 DCGL, Where: Cn = concentration of radionuclide n and DCGLn = DCGL of radionuclide n.Revision 0 17 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD The results of the unity rule calculation for the radionuclides of concern in the statistical sample population for Survey Unit 9312-0007 are provided in Table 9 below. Note that since there were no positive detections for Co-60 (i.e., a result greater than two (2) standard deviations uncertainty).

This isotope has been de-selected and is not included in the unity calculations.

Table 9 -Results of Unity Calculation for Surface Soil Samples Comprising the Statistical Sample Population Sample Number Fraction of the Operational DCGL')(2)S Unity___________

Cs-137 Sr-90______

9312-0007-OO1F

-.OOE+00 9312-0007-002F 1.51E-03 4.72E-03 6.23E-03 9312-0007-003F 4.30E-03 9.45E-03 1.37E-02 9312-0007-004F 2.09E-03 2.09E-03 9312-0007-005F 1.88E-02 4.56E-03 2.34E-02 9312-0007-006F 5.25E-04 1.34E-02 1.40E-02 9312-0007-007F 0.OOE+00 1.54E-03 1.54E-03 9312-0007-008F 2.65E-03 2.54E-03 5.19E-03 9312-0007-009F 3.18E-03 3.18E-03 9312-0007-OIOF 6.53E-03 -6.53E-03 9312-0007-011F 1.48E-02 1.48E-02 9312-0007-012F 1.84E-04 1.84E-04 9312-0007-013F 1.59E-02 1.46E-02 3.05E-02 9312-0007-014F 2.13E-03 1.1 8E-02 1.40E-02 9312-0007-015F 1.85E-02 1.57E-02 3.42E-02 (1) The Operational DCGL from Table 2 is 4.75 pCi/g for Cs-137and 0.93 pCi/g for Sr-90 to achieve seventeen (15) mrem/yr TEDE respectively.

(2) Blank cells indicate that the radionuclide result was less than zero.Revision 0 18 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD 7. QUALITY CONTROL The off-site laboratory processed the split samples and performed gamma spectroscopy analysis.

One sample location was selected for analysis, which exceeds the 5% minimum required by the LTP. The data were evaluated using USNRC acceptance criteria specified in Inspection Procedure 84750 as detailed in HNP Procedure RPM 5.1-24, "Split Sample Assessment for Final Status Survey ". There was acceptable agreement between the field split results.The sample analysis vendor, General Engineering Laboratories, LLC, maintains quality control and quality assurance plans as part of normal operation.

Refer to Attachments 3 and 4 for data and data quality analysis results 8. INVESTIGATIONS AND RESULTS No investigative surveys were required or performed based on the sample and scan results.9. REMEDIATION AND RESULTS Radiological remedial action as described by MARSSIM Section 5.4 was performed in this survey unit prior to FSS. All excavations were characterized and backfilled with "clean" fill prior to performing FSS. In the area where remediation occurred, the ground area is comprised of barren dirt with no vegetation, and the soils have been graded relatively flat to the corresponding elevation of the adjacent survey units. The results for Cs-137 following remediation were well below the Operational DCGL provided in Table 3. 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 is unnecessary and that the remaining residual radioactivity in soil was ALARA.10. CHANGES FROM THE FINAL STATUS SURVEY PLAN The only change to the Final Status Survey Plan was to de-select Co-60 as a nuclide of concern from the Data Quality Assessment based on the fact that it was not positively identified in any of the samples.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. The evaluation of the Sign Test results demonstrates that the survey unit passes the unrestricted release criteria, thus, the null hypothesis is rejected.Revision 0 19 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD 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 1.The preliminary data review consisted of calculating basic statistical quantities (e.g., mean, median, standard deviation).

The mean and median values are well below the Operational DCGL. Also, the retrospective power curve shows that a sufficient number of samples were collected to achieve the desired power.Therefore, the survey unit meets the unrestricted release criteria with adequate power as required by the DQOs. The basic statistical quantities for the statistical sample population are provided below in Table 22.Table 10 -Basic Statistical Quantities for Cs-137 and Sr-90 from the Final Status Survey Cs-137 Sr-90 pCi/g pCi/g DCGLop: 4.75 0.93 Minimum Value: -1.07E-02

-7.12E-03 Maximum Value: 8.94E-02 1.46E-02 Mean: 2.22E-02 5.26E-03 Median: 1.01E-02 4.24E-03 Standard Deviation:

3.38E-02 6.73E-03 The range of the data, about 3.0 to 3.2 standard deviations for both radionuclides, was not a particularly large variation.

The difference between the mean and median was about 15% to 36% of the standard deviation which indicates some skewness in the data. The data was represented graphically through posting plots, a frequency plot, and a quantile plot. The frequency plot indicates a slight to diminishing skewness as confirmed by the calculated skew of 1.34 and -0.04 for Cs-137 and Sr-90 respectively.

All data, assessments, and graphical representations are provided in Attachment 4.12. ANOMALIES No anomalies were noted in the performance of this Final Status Survey.Revision 0 20 RADIOLOGICALLY CONTROLLED AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD 13. CONCLUSION Survey Unit 9312-0007 has met the final DQOs of the FSS plan. The ALARA criteria for soils as specified in Chapter 4 of the LTP were achieved.With the exception of Co-60 which was not positively identified in the sample results, all identified radionuclides of concern were used for statistical testing to determine the adequacy of the survey unit for FSS.The sample data passed the Sign Test. The null hypothesis was rejected.

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

The survey unit is properly designated as Class 1.The dose contribution from soil is 0.17 mrem/yr TEDE based on the average concentration of the samples used for non-parametric statistical sampling.This survey area is affected by existing groundwater (reference CY memo ISC 06-024); therefore the dose contribution from existing groundwater is bounded at two (2) mrem/yr TEDE.This survey unit is considered impacted by future groundwater radioactive contamination, as there are underground foundations containing residual radioactive material within the groundwater saturated zone in the area (reference CY memo ISC 06-024). The dose contribution from future groundwater, the third dose component, is bounded by two (2) mrem/yr TEDE.The average total dose from residual radioactivity in this survey unit, including exposures from the three (3) components as described in Section 3, that is, residual radioactivity in soil, existing groundwater radioactivity, and future groundwater radioactivity from the burial of concrete foundations or footings from site buildings containing residual radioactivity will not exceed 4.17 mremlyr TEDE. Therefore, Survey Unit 9312-0007 is acceptable for unrestricted release 14. ATTACHMENTS 14.1 Attachment 1 -Figures 14.2 Attachment 2 -Scan Results 14.3 Attachment 3 -Laboratory Results 14.4 Attachment 4 -DQA Results Revision 0 21 SOUTHWEST SITE STORAGE AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD ATTACHMENT 1 (FIGURES)Revision 0 00$00 ,-f2ff7a .Co hiast n S -wtn B 7Ohi NWlhhl -23737020 / Eletku9 -66739457 I'pJ--

RJMR-C 0 Connecticut Yankee Atomic Power Company Y Site Map With Reference To Survey Unit 9312-0007

-1V312-001 2 5 1r V312-0002 9 9522-0007 4 8 0 is 3 NoýNAD27C3,ýt 3 7 6 11 12 3 15 10 9522-0006 9312-00 08 I Date: March 2007 Figure 2 Connecticut Yankee Atomic Power Company SU 9312-0007 Final Status Survey Design I D. Randall

..13-0312-001 0 0.007 9522-0007 V312-0002 9.003 0.000 0. 013 5 5 0.089 0 Smplofti,I 0 IS M0 NAD27Co..0, S- Pbrn sy30 0.020 0.000 0.002-0.011 0.031.ff004 0.088 0~10 9522-0006 9312-0008 I I Date: March 2007 Figure 3 Connecticut Yankee Atomic Power Company SU9312-0007FSS Cs-137 Posting Plot I D. Randall A-

/17312-001 0.004 0.004 9522-0007 2097 0312-0002 rlO.04?3 QD = Sa.pklo ot 0.002 0.002 0.009 0.001 0.013 0.014-0.002 0.01 NAR"7Cý..00 0.000 0.015 0011 9522-0006 9312-0008 Figure 41 I Date: March 2007 Connecticut Yankee Atomic Power Company SU 9312-0007 FSS Sr-90 Posting Plot I I I 12 Randall i Figure 4 P312-0010 9522-0007 9522-0006 9312-0008 Connecticut Yankee Atomic Power Company SU 9312-0007 FSS Scan Area SOUTHWEST SITE STORAGE AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD ATTACHMENT 2 (SCAN RESULTS)Revision 0 Survey Unit 9312-0007 Scan Survey Results Sample Location Scans Survey Release Record Scan Area Results Survey Unit 93.12-0007 Alarm >Alarm Survey Location 9312-07-BL-00-01-0 9312-07-SL-00-01

-0 9312-07-BL-00-02-0 9312-07-SL-00-02-0 9312-07-BL-00-03-0 9312-07-SL-00-03-0 9312-07-BL-00-04-0 9312-07-SL-00-04-0 9312-07-BL-00-05-0 9312-07-SL-00-05-0 9312-07-BL-00-06-0 9312-07-SL-00-06-0 9312-07-BL-00-07-0 9312-07-SL-00-07-0 9312-07-BL-00-08-0 9312-07-SL-00-08-0 9312-07-BL-00-09-0 9312-07-SL-00-09-0 9312-07-BL-00-1 0-0 9312-07-SL-00-10-0 9312-07-BL-00-1 1-0 9312-07-SL-00-1 1-0 9312-07-BL-00-12-0 9312-07-SL-00-12-0 9312-07-BL-00-13-0 9312-07-SL-00-1 3-0 9312-07-BL-00-14-0 9312-07-SL-00-14-0 9312-07-BL-00-1 5-0 9312-07-SL-00-15-0 Log Date Log Time Reading 1/23/2007 13:20:00 1.1OE+04 1/23/2007 13:21:00 1.14E+04 1/23/2007 13:22:00 1.15E+04 1/23/2007 13:23:00 1.17E+04 1/23/2007 13:24:00 9.91E+03 1/23/2007 13:25:00 8.03E+03 1/23/2007 13:25:00 1.19E+04 1/23/2007 13:26:00 1.19E+04 1/23/2007 13:27:00 1.10E+04 1/23/2007 13:28:00 1.08E+04 1/23/2007 13:30:00 9.60E+03 1/23/2007 13:31:00 8.41E+03 1/23/2007 13:32:00 8.74E+03 1/23/2007 13:33:00 9.24E+03 1/23/2007 13:33:00 1.OOE+04 1/23/2007 13:35:00 1.12E+04 1/23/2007 13:36:00 9.54E+03 1/23/2007 13:37:00 1.04E+04 1/23/2007 13:39:00 7.93E+03 1/23/2007 13:40:00 8.OOE+03 1/23/2007 13:41:00 1.15E+04 1/23/2007 13:42:00 1.23E+04 1/23/2007 13:43:00 1.29E+04 1/23/2007 13:44:00 1.1OE+04 1/23/2007 13:45:00 1.05E+04 1/23/2007 13:46:00 1.12E+04 1/23/2007 13:47:00 8.67E+03 1/23/2007 13:49:00 8.56E+03 1/23/2007 13:50:00 9.93E+03 Level 1.25E+04 1.30E+04 1.13E+04 1.35E+04 1.25E+04 1.1OE+04 1.01E+04 1.14E+04 1.09E+04 9.20E+03 1.30E+04 1.45E+04 1.20E+04 1.00E+04 Level E-600 SIN 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 Probe SIN 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1/23/2007 13:51:00 1.07E+04 1.14E+04 3115/2007 Page 1 of I Survey Unit 9312-0007 Scan Survey Results Scan Strip Scans.Survey Release Record Scan Area Results Survey Unit 9312-0007 Log.DateL.g.TimeAlarm

>Alarm Log Date Log Time Reading Level Level E-600 SIN Probe SIN Survey Location 9312-07-BC-00-01-0 9312-07-SC-00-01-0 9312-07-BC-00-02-0 9312-07-SC-00-02-0 9312-07-BC-00-03-0 9312-07-SC-00-03-0 9312-07-BC-00-04-0 9312-07-SC-00-04-0 9312-07-BC-00-05-0 9312-07-SC-00-05-0 9312-07-BC-00-06-0 9312-07-SC-00-06-0 9312-07-BC-00-07-0 9312-07-SC-00-07-0 9312-07-BC-00-08-0 9312-07-SC-00-08-0 9312-07-BC-00-09-0 9312-07-SC-00-09-0 9312-07-BC-00-10-0 9312-07-SC-00-10-0 9312-07-6C-00-11-0 9312-07-SC-00-11-0 9312-07-BC-00-12-0 9312-07-SC-00-12-0 9312-07-BC-00-13-0 9312-07-SC-00-1 3-0 9312-07-BC-00-14-0 9312-07-SC-00-14-0 9312-07-BC-00-15-0 9312-07-SC-00-1 5-0 9312-07-BC-00-1 6-0 9312-07-SC-00-16-0 9312-07-BC-00-17-0 9312-07-SC-00-17-0 9312-07-BC-00-18-0 9312-07-SC-00-18-0 9312-07-BC-00-19-0 9312-07-SC-00-1 9-0 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/2312007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 1/23/2007 10:04:00 9.78E+03 1114 1014 10:07:00 10:08:00 10:12:00 10:14:00 10:16:00 10:20:00 10:23:00 10:25:00 10:30:00 10:31:00 10:38:00 10:41:00 10:44:00 10:45:00 10:48:00 10:53:00 10:56:00 10:57:00 10:58:00 11:01:00 11:04:00 11:04:00 11:06:00 11:08:00 11:10:00 11:10:00 11:13:00 11:14:00 11:16:00 11:16:00 11:18:00 10:00:00 10:08:00 10:09:00 10:10:00 10:11:00 10:12:00 1.00E+04 1.24E+04 1.03E+04 9.65E+03 1.29E+04 9.18E+03 1.05E+04 1.18E+04 1.11 E+04 9.01E+03 1.37E+04 8.68E+03 1.03E+04 1.13E+04 1.06E+04 8.74E+03 1.32E+04 8.36E+03 1.05E+04 1.10E+04 1.09E+04 1.0OE+04 1.35E+04 9.40E+03 1.07E+04 1.20E+04 1.11E+04 9.01 E+03 1.37E+04 1.O0E+04 1.06E+04 1.26E+04 1.08E+04 1.12E+04 1.34E+04 1.01E+04 1.12E+04 1.27E+04 1 .15E+04 1.06E+04 1.41E+04 1.03E+04 1.15E+04 1.29E+04 1.08E+04 1.02E+04 1.34E+04 7.22E+03 9.12E+03 9.81E+03 1.11E+04 1.13E+04 1.37E+04 1.06E+04 9.79E+03 1.32E+04 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1114 1117 1117 1117 1117 1117 1117 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1014 1008 1008 1008 1008 1008 1008 311512007 Page I of 3 Survey Unit 9312-0007 Scan Survey Results Scan Strip Scans Survey Location 9312-07-BC-00-20-0 9312-07-SC-00-20-0 9312-07-BC-00-21-0 9312-07-SC-00-21-0 9312-07-BC-00-22-0 9312-07-SC-00-22-0 9312-07-BC-00-23-0 9312-07-SC-00-23-0 9312-07-BC-00-24-0 9312-07-SC-00-24-0 9312-07-BC-00-25-0 9312-07-SC-00-25-0 9312-07-BC-00-26-0 9312-07-SC-00-26-0 9312-07-BC-00-27-0 9312-07-SC-00-27-0 9312-07-BC-00-28-0 9312-07-SC-00-28-0 9312-07-8C-00-29-0 9312-07-SC-00-29-0 9312-07-BC-00-30-0 9312-07-SC-00-30-0 9312-07-BC-00-31-0 9312-07-SC-00-31-0 9312-07-BC-00-32-0 9312-07-SC-00-32-0 9312-07-BC-00-33-0 9312-07-SC-00-33-0 9312-07-6C-00-34-0 9312-07-SC-00-34-0 9312-07-BC-00-35-0 9312-07-SC-00-35-0 9312-07-BC-00-36-0 9312-07-SC-00-36-0 9312-07-BC-00-37-0 9312-07-SC-00-37-0 9312-07-BC-00-38-0 9312-07-SC-00-38-0 9312-07-BC-00-39-0 9312-07-SC-00-39-0 9312-07-BC-00-40-0 9312-07-SC-00-40-0 9312-07-BC-00-41-0 9312-07-SC-00-41-0 Log Date Log Time 1123/2007 10:13:00 1/23/2007 10:14:00 1/23/2007 10:15:00 1/23/2007 10:16:00 1/23/2007 10:17:00 1/23/2007 10:18:00 1/23/2007 10:19:00 1/23/2007 10:20:00 1/23/2007 10:21:00 1/2312007 10:21:00 1/23/2007 10:22:00 1/23/2007 10:24:00 1/23/2007 10:24:00 1/23/2007 10:26:00 1/23/2007 10:26:00 1/23/2007 10:28:00 1/23/2007 10:28:00 1/23/2007 10:29:00 1/23/2007 10:30:00 1/23/2007 10:31:00 1/23/2007 10:31:00 1/23/2007 10:33:00 1/23/2007 10:34:00 1/23/2007 10:35:00 1/23/2007 10:36:00 1123/2007 10:36:00 1/23/2007 10:38:00 1/23/2007 10:39:00 1/23/2007 10:40:00 1/23/2007 10:42:00 1/23/2007 10:43:00 1/23/2007 10:44:00 1/23/2007 10:45:00 1/2312007 10:45:00 1/23/2007 10:46:00 1/23/2007 10:47:00 1/23/2007 10:48:00 1/23/2007 10:50:00 1/23/2007 10:50:00 1/23/2007 10:51:00 1/23/2007 10:52:00 1/23/2007 10:52:00 1/23/2007 13:18:00 1/23/2007 13:19:00 Alarm >Alarm Reading Level Level 1.04E+04 1.06E+04 1.30E+04 E-600 SIN Probe SIN 1117 1008 1117 1008 7.67E+03 9.55E+03 1.03E+04 1.15E+04 1.06E+04 1.41 E+04 1.07E+04 1.04E+04 1.33E+04 9.33E+03 7.88E+03 1.19E+04 7.89E+03 8.50E+03 1.05E+04 1.04E+04 1.09E+04 1.30E+04 1.03E+04 1.01E+04 1.29E+04 8.25E+03 7.73E+03 1.08E+04 8.25E+03 7.80E+03 1.08E+04 1.04E+04 1.17E+04 1.30E+04 1.10E+04 1.09E+04 1.36E+04 8.27E+03 8.28E+03 1.09E+04 7.76E+03 7.69E+03 1.04E+04 1.03E+04 1.09E+04 1.29E+04 1.08E+04 1.09E+04 1.34E+04 8.20E+03 7.39E+03 1.08E+04 7.66E+03 9.20E+03 1.03E+04 1.04E+04 1.10E+04 1.30E+04 1.09E+04 1.09E+04 1.35E+04 8.31 E+03 7.62E+03 1.09E+04 7.87E+03 9.95E+03 1.05E+04 1117 1117 1117 1117 1008 1008 1008 1008 1117 1008 1117 1008 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1117 1008 1117 1008 311512007 Page 2 of 3 Survey Unit 9312-0007 Scan Survey Results Scan Strip Scans Survey Location 9312-07-BC-00-42-0 9312-07-SC-00-42-0 9312-07-BC-00-43-0 9312-07-SC-00-43-0 9312-07-BC-00-44-0 9312-07-SC-00-44-0 9312-07-BC-00-45-0 9312-07-SC-00-45-0 9312-07-BC-00-46-0 9312-07-SC-00-46-0 9312-07-BC-00-47-0 9312-07-SC-00-47-0 9312-07-BC-00-48-0 9312-07-SC-00-48-0 9312-07-BC-00-49-0 9312-07-SC-00-49-0 9312-07-BC-00-50-0 9312-07-SC-00-50-0 9312-07-BC-00-51-0 9312-07-SC-00-51

-0 9312-07-BC-00-52-0 9312-07-SC-00-52-0 9312-07-BC-00-53-0 9312-07-SC-00-53-0 9312-07-BC-00-54-0 9312-07-SC-00-54-0 9312-07-BC-00-55-0 9312-07-SC-00-55-0 9312-07-BC-00-56-0 9312-07-SC-00-56-0 9312-07-BC-00-57-0 9312-07-SC-00-57-0 9312-07-BC-00-58-0 9312-07-SC-00-58-0 9312-07-BC-00-59-0 9312-07-SC-00-59-0 9312-07-BC-00-60-0 9312-07-SC-00-60-0 Alarm Log Date Log Time Reading Level 1/23/2007 13:20:00 1.14E+04 1/23/2007 13:24:00 1.20E+04 1.40E+04 1/23/2007 13:24:00 1.13E+04 1/23/2007 13:27:00 1.13E+04 1.39E+04 1/23/2007 13:28:00 7.94E+03 1/23/2007 13:29:00 8.09E+03 1.05E+04 1/23/2007 13:30:00 7.82E+03 1/23/2007 13:31:00 7.73E+03 1.04E+04 1/23/2007 13:36:00 1.01E+04 1/23/2007 13:39:00 1.16E+04 1.27E+04 1/23/2007 13:39:00 1.06E+04 1/23/2007 13:43:00 1.03E+04 1.32E+04 1/23/2007 13:45:00 7.75E+03 1/23/2007 13:46:00 8.92E+03 1.03E+04 1/23/2007 13:50:00 1.10E+04 1/23/2007 13:53:00 1.01E+04 1.36E+04 1/23/2007 13:53:00 1.08E+04 1/23/2007 13:58:00 1.18E+04 1.34E+04 1/23/2007 14:01:00 1.12E+04 1/23/2007 14:05:00 1.22E+04 1.38E+04 1/23/2007 14:06:00 1.24E+04 1/23/2007 14:09:00 1.14E+04 1.50E+04 1/23/2007 14:18:00 7.55E+03 1/23/2007 14:20:00 8.59E+03 1.01 E+04 1/23/2007 14:20:00 8.91E+03 1/23/2007 14:22:00 8.79E+03 1.1 5E+04 1/23/2007 14:22:00 8.77E+03 1/23/2007 14:23:00 9.54E+03 1.14E+04 1/23/2007 14:24:00 8.98E+03 1/23/2007 14:25:00 8.33E+03 1.16E+04 1/23/2007 14:27:00 7.96E+03 1/23/2007 14:27:00 9.76E+03 1.06E+04 1/23/2007 14:29:00 8.37E+03 1/23/2007 14:30:00 8.81 E+03 1.10E+04 1/23/2007 14:31:00 7.67E+03 1/23/2007 14:31:00 9.28E+03 1.03E+04 1/23/2007 14:32:00 9.30E+03 1/23/2007 14:33:00 8.10E+03 1.19E+04>Alarm Level E-600 SIN Probe SIN 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1117 1008 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 1114 1014 3M1512007 Page 3 of 3 SOUTHWEST SITE STORAGE AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD ATTACHMENT 3 (LABORATORY DATA)Revision 0 Laboratories LLC a member of The GEL Group INC P0 Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 February 2, 2007 www.gel.com Mr. Jack McCarthy Connecticut Yankee Atomic Power 362 Injun Hollow Rd East Hampton, Connecticut 06424 Re: Soils PO# 002332 Work Order: 179836 SDG: MSR#07-0054

Dear Mr. McCarthy:

GEL Laboratories, LLC (GEL) appreciates the opportunity to provide the enclosed analytical results for the sample(s) we received on January 30, 2007. This original data report has been prepared and reviewed in accordance with GEL's standard operating procedures.

Our policy is to provide high quality, personalized analytical services to enable you to meet your analytical needs on time every time. We trust that you will find everything in order and to your satisfaction.

If you have any questions, please do not hesitate to call me at (843) 556-8171, ext. 4243.Sincerely, Project Manager Purchase Order: 002332 Chain of Custody: 2007-00025 and 2007-00026 Enclosures problem solved Laboratories LLC a member of The GEL Group INC PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gel.com Connecticut Yankee Atomic Power Co.Soils PO# 002332 Work Order: 179836 SDG: MSR#07-0054 Laboratory ID 179836001 179836002 179836003 179836004 179836005 179836006 179836007 179836008 179836009 179836010 179836011 179836012 179836013 179836014 179836015 179836016 Client ID 9312-0007-002F 9312-0007-014F 9312-0007-001 F 9312-0007-003F 9312-0007-003FS 9312-0007-004F 9312-0007-005F 9312-0007-006F 9312-0007-007F 9312-0007-008F 9312-0007-009F 9312-0007-0 1OF 9312-0007-01IF 9312-0007-012F 9312-0007-013F 9312-0007-015F problem solved Table of Contents General Narrative

..................................................................

1 Chain of Custody Docum entation .......................................

5 Data Review Q ualifier Definitions

.......................................

10 Radiological Analysis ...........................................................

12 Sam ple Data Sum m ary .....................................................

31 Q uality Control Data ..........................................................

67 General Narrative 1 General Narrative for Connecticut Yankee Atomic Power Co.Work Order: 179836 SDG: MSR#07-0054 February 2, 2007 Laboratory Identification:

GEL Laboratories LLC 2040 Savage Road Charleston, South Carolina 29407 (843) 556-8171 Summary Sample receipt The samples arrived at GEL Laboratories LLC, Charleston, South Carolina on January 30, 2007 for analysis.Shipping container temperatures were checked, documented, and within specifications.

The samples were delivered with proper chain of custody documentation and signatures.

All sample containers arrived without any visible signs of tampering or breakage.Sample Identification The laboratory received the following samples: Laboratory Identification 179836001 179836002 179836003 179836004 179836005 179836006 179836007 179836008 179836009 179836010 179836011 179836012 179836013 179836014 179836015 179836016 Sample Description 9312-0007-002F 9312-0007-014F 9312-0007-OO1F 9312-0007-003F 9312-0007-003FS 9312-0007-004F 9312-0007-005F 9312-0007-006F 9312-0007-007F 9312-0007-008F 9312-0007-009F 9312-0007-OIOF 9312-0007-01 IF 9312-0007-012F 9312-0007-013F 9312-0007-015F Items of Note There are no items to note.Case Narrative Sample analyses were conducted using methodology as outlined in GEL Laboratories, LLC (GEL) Standard Operating Procedures.

Any technical or administrative problems during analysis, data review, and reduction are contained in the analytical case narratives in the enclosed data package.GEL Laboratories LLC P0 Box 30712 Chaleston, SC 29417 2040 Savage Road Charleston, SC 29407 P843.556.8171 F 843.755.1178 2 www.gol.com Analytical Request Fourteen soil samples were analyzed for FSSGAM and Strontium-90.

Two soil samples were analyzed for FSSALL.Data Package The enclosed data package contains the following sections:

General Narrative, Chain of Custody and Supporting Documentation, Data Review Qualifier Definitions, and data from the following fractions:

Radiochemistry.

I certify that this data package is in compliance with the SOW, both technically and for completeness, for other than the conditions detailed above. Release of the data contained in this hard copy data package has been authorized by the Laboratory Manager or a designee, as verified by the following signature.

aL74-'ýCheryl Jones Project Manager GEL Laboratories LLc POBox30712 Chadeston, SC29417 2040 Savage Road Charleson, SC 29407 P843.556.8171 F 843.766.1178 3 www.gol.com List of current GEL Certifications as of 31 January 2007 State I Certification Alaska UST-062 Arizona AZ0668 Arkansas 88-0651 CLIA 42D0904046 California 01 151CA Colorado GenEngLabs Connecticut PH-0169 Dept. of Navy NFESC 413 EPA WG-15J Florida/NELAP E87156 Georgia E87156 (FL/NELAP)

Hawaii N/A Idaho N/A Illinois 200029 Indiana C-SC-01 Kansas E-10332 Kentucky 90129 Louisiana 03046 Maryland 270 Massachusetts M-SC012 Michigan 9903 Nevada SC12 New Jersey SCO02 New Mexico FL NELAP E87156 New York 11501 North Carolina 233 North Carolina Drinking W 45709 North Dakota R- 158 Oklahoma 9904 Pennsylvania 68-00485 South Carolina 10120001/10585001/10120002 Tennessee 02934 Texas TX213-2006A Texas NELAP T104704235-06-TX U.S. Dept. of Agriculture S-52597 US Army Corps of Engineer N/A Utah 8037697376 GEL Vermont VT87156 Virginia 00151 Washington C1641 4 Chain of Custody and Supporting Documentation 5

Health Physics Procedure GPP-GGGR-R5104-003-Attachment B-CY-001 Major Connecticut Yankee Atomic Power Company Chain of Custody Form 362 Injun Hollow Road, East Hampton, CT 06424 No. 2007-00025 860-267-2556 Project Name: Haddam Neck Decommissioning Analyses Requested Lab Use Only Contact Name & Phone: Comments: Jack McCarthy 860-267-3924 Media Sample Container Code Type Size-Analytical Lab (Name, City, State): Code &Type General Engineering Laboratories Code 2040 Savage Road Charleston, SC 29407 ATT: Cheryl Jones (843-556-8171)

Priority:

El 30 D. [E 15 D. Z 7 D.Other: Ln VýSample Designation Date Time _ Comment, Preservation Lab Sample ID 9312-0007-OOIF 01-23-07 1322 TS G BP X 9312-0007-002F i 01-23-07 1324 TS G BP X 9312-0007-003F

01-23-07 1325 TS G BP X 9312-0007-003FS 01-23-07 1325 TS G BP X 9312-0007-004F zr 01-23-07 1327 TS G BP X 9312-0007-005F 01-23-07 1329 TS G BP X 9312-0007-006F

/ 01-23-07 1332 TS G BP X 9312-0007-007F 01-23-07 1333 TS G BP X 9312-0007-008F 01-23-07 1335 TS G BP X 9312-0007-009F F 01-23-07 1338 TS G BP X 9312-0007-01OF

' 01-23-07 1340 TS G BP X NOTES: PO #: 002332 MSR Z LTP QA E] Radwaste QA _] Non QA Samples Shipped Via: Internal Container T : 0 3L A Fed Ex Temp.: j__ Deg. C El uPs[] Hand Cust oV Sealed?N[]1Date/Time

2) Rec ived By Date/Time Custody Seal Intact?J- _ 2 /I. t, /, W ,3, " 0 q-36: E3 Other 3) Relinquished By Date/Time

4) Received By Date/Time

__N _Bill of Lading #5) Relinquished By Date/Time

6) Received By Date/Time Health Physics Procedure GPP-GGGR-R5104-003-Attachment B-CY-001 Major Connecticut Yankee Atomic Power Company Chain of Custody Form 362 Injun Hollow Road, East Hampton, CT 06424 No. 2007-00026 860-267-2556 Project Name: Haddam Neck Decommissioning Analyses Requested Lab Use Only Contact Name & Phone: Comments: Jack McCarthy 860-267-3924 Media Sample Container Code Type Size-Analytical Lab (Name, City, State): Code &Type General Engineering Laboratories Code 2040 Savage Road Charleston, SC 29407 ATT: Cheryl Jones (843-556-8171)

Priority:FII30 D. [] 15 D. Z 7 D.Other: 7 Sample Designation, Date Time ___I__ I Comment, Preservation Lab Sample ID 9312-0007-OIF J 01-23-07 1343 TS G BP X 9312-0007-012F

01-23-07 1345 TS G BP X 9312-0007-013F 01-23-07 1347 TS G BP X 9312-0007-014F 6 01-23-07 1349 TS G BP X 9312-0007-015F

,/ 01-23-07 1352 TS G BP X NOTES: PO #: 002332 MSR #:-, ZJ [ LTP QA E] Radwaste QA Fl Non QA Samples Shipped Via: Internal Container'Z Fed Ex Temp.: ._! Deg. C F1 UPS El Hand Custody Sealed?Csiy Sea Ninct 1) Re * " Date/Time

2) Receihd B y Date/Time Seal Intact?,07 !5' [Other 3) Relinquished By Date/Time

4) Received By Date/Time Y__ _N NI Bill of Lading #5) Relinquished By Date/Time

6) Received By Date/Time Connecticut Yankee Statement of Work for Analytical Lab Services-CY-ISC-SOW-001 Figure 1. Sample Chck-in List.Datefrime Received:_

0 C -c9:3n SDG#:- /V/7- ~ 5y .Work Order Number.-:

_ 7 Shipping Cdatainer ID1 Y!3.ýz --M V59 G ý Chain of Custody' n d~(X 2JOaoIe~-1.. " Custdy Seals oishipping container intact?:.. "Y.s/I(No[]

I --2. Custody Seals dated and signed? Yes No []3. Chain-of-Custody record present? Yes 0No [ ].4.. Cooler temperature

--' /5. Vermiculitalpacking materials is: W..., --.- -. .W e t [ ] D ry .6 .a m p l e h o l d i t e x c e d e d Y 7. Sample..holding times excee ded? .."...Yes [(1 No.. Samples have:* .tap ....- hazard labels...§utody seals Caroiaeame Pproriae saplelabels

9. Samples are-.4 good condition leaking.~broken -ý have air bubbles 10, Were any anomalies identified in sample receipt?11. O8ClJ~t~flof aomaie.(include sample numbers): Sample Custodian.Labon.to.

../ ., ..Date: , -Telephoned to:-y 8

[Fwd: Soil samples]

Subject:

[Fwd: Soil samples]From: Cheryl Jones <cj@gel.com>

Date: Mon, 29 Jan 2007 15:51:31 -0500 To: Amanda Rasco <ama01354@gel.com>

Original Message--------

Subject:

Soil samples Date: Mon, 29 Jan 2007 15:42:54 -0500 From: Arthur L. Hammond <Hammond@CYAPCO.com>

To: Cheryl Jones <cj@gel.com>

Cheryl, We are sending 35 samples to GEL today under two MSRs. MSRs 07-0054 and 07-0055. The requested TAT for the samples is 7 days. The requested analyses is FSSGAM and Sr-90 On all the samples and FSSALL on four (4) of the samples, see attached COCs. It is acceptable to use the traced/untraced Tc-99 process for these samples.Thank you, Arthur Cheryl A. Jones Project Manager/PM Team Leader GEL Laboratories, LLC 2040 Savage Road Charleston, SC (USA) 29407 Direct: 843.769.7388 Main: 843.556.8171 x 4243 Fax: 843.766.1178 E-mail: cj@gel.com Web: www.gel.com SCAN6974_000.pdf Content-Type:

Content-Encoding:

application/octet-stream base64 9 1/29/2007 4:02 PM Data Review Qualifier Definitions 10 Data Review Qualifier Definitions Qualifier Explanation

A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound c Result is less than value reported* Result is greater than value reported RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL A The TIC is a suspected aldol-condensation product B Target analyte was detected in the associated blank B Metals-Either presence of analyte detected in the associated blank, or MDL/IDL < sample value < PQL BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample d 5-day BOD-The 2:1 depletion requirement was not met for this sample E Organics-Concentration of the target analyte exceeds the instrument calibration range E Metals-%difference of sample and SD is >10%. Sample concentration must meet flagging criteria H Analytical holding time was exceeded h Preparation or preservation holding time was exceeded J Value is estimated" Metals-The Matrix spike sample recovery is not within specified control limits N Organics-Presumptive evidence based on mass spectral library search to make a tentative identification of the analyte (TIC). Quantitation is based on nearest internal standard response factor N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the reporting limit UI Gamma Spectroscopy-Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound z Paint Filter Test-Particulates passed through the filter, however no free liquids were observed.GEL Laboratories LLC P0 Box 30712 Chadeston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 543.766.1178 www.gel.com 11 RADIOLOGICAL ANALYSIS 12 Radiochemistry Case Narrative Connecticut Yankee Atomic Power Co. (YANK)Work Order 179836 Method/Analysis Information Product: AIphaspec Am241, Cm, Solid ALL FSS Analytical Method: DOE EML HASL-300, Am-05-RC Modified Prep Method: Dry Soil Prep GL-RAD-A-021 Method: Analytical Batch Number: Prep Batch Number: Dry Soil Prep GL-RAD-A-021 Batch Number: Ash Soil Prep Dry Soil Prep 606029 606003 606001 Sample ID 179836001 179836002 1201269930 1201269931 1201269932 1201269933 Client ID 9312-0007-002F 9312-0007-014F Method Blank (MB)179836001(9312-0007-002F)

Sample Duplicate (DUP)179836001(9312-0007-002F)

Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-01 I REV# 14.Calibration Information:

Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.

13 Quality Control (QC) Information:

Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 179836001 (9312-0007-002F).

QC Information All of the QC samples met the required acceptance limits.Technical Information:

Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis None of the samples in this sample set required reprep or reanalysis.

Miscellaneous Information:

NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.

A nonconformance report (NCR) was not generated for this SDG.Manual Integration No manual integrations were performed on data in this batch.Additional Comments Additional comments were not required for this sample set.Oualifier information Manual qualifiers were not required.Method/Analysis Information 14 Product-Alphaspec Pu, Solid-ALL FSS Analytical Method: DOE EML HASL-300, Pu-I I-RC Modified Prep Method: Dry Soil Prep GL-RAD-A-021 Method: Analytical Batch Number: Prep Batch Number: Dry Soil Prep GL-RAD-A-021 Batch Number: Ash Soil Prep Dry Soil Prep 606031 606003 606001 Sample ID 179836001 179836002 1201269935 1201269936 1201269937 1201269938 Client ID 9312-0007-002F 9312-0007-014F Method Blank (MB)179836001(9312-0007-002F)

Sample Duplicate (DUP)179836001(9312-0007-002F)

Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-01 I REV# 14.Calibration Information:

Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.

Oualitv Control (OC) Information:

Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 179836001 (9312-0007-002F).

QC Information All of the QC samples met the required acceptance limits.15 Technical Information:

Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis None of the samples in this sample set required reprep or reanalysis.

Miscellaneous Information:

NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.

A nonconformance report (NCR) was not generated for this SDG.Manual Integration No manual integrations were performed on data in this batch.Additional Comments Additional comments were not required for this sample set.Oualifier information Manual qualifiers were not required.Method/Analysis Information Product: Liquid Scint Pu241, Solid-ALL FSS DOE EML HASL-300, Pu-I I-RC Modified Analytical Method: Prep Method: Dry Soil Prep GL-RAD-A-021 Method: Analytical Batch Number: Prep Batch Number: Dry Soil Prep GL-RAD-A-021 Batch Number: Ash Soil Prep Dry Soil Prep 606032 606003 606001 16 Sample ID 179836001 179836002 1201269939 1201269940 1201269941 1201269942 Client ID 9312-0007-002F 9312-0007-014F Method Blank (MB)179836001(9312-0007-002F)

Sample Duplicate (DUP)179836001(9312-0007-002F)

Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-035 REV# 8.Calibration Information:

Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.

Quality Control (QC) Information:

Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 179836001 (9312-0007-002F).

QC Information All of the QC samples met the required acceptance limits.Technical Information:

Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis Sample 1201269940 (9312-0007-002F) was recounted due to low quench number.Miscellaneous Information:

NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from 17 referenced SOP or contractual documents.

A nonconformance report (NCR) was not generated for this SDG.Manual Integration No manual integrations were performed on data in this batch.Additional Comments Additional comments were not required for this sample set.Qualifier information Manual qualifiers were not required.Method/Analysis Information Product: Analytical Method: Prep Method: Analytical Batch Number: Prep Batch Number: Sample ID 179836001 179836002 179836003 179836004 179836005 179836006 179836007 179836008 179836009 179836010 179836011 179836012 179836013 179836014 179836015 179836016 1201271727 1201271728 1201271729 Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived EML HASL 300, 4.5.2.3 Dry Soil Prep 606828 606001 Client ID 9312-0007-002F 9312-0007-014F 9312-0007-001 F 9312-0007-003F 9312-0007-003FS 9312-0007-004F 9312-0007-005F 9312-0007-006F 9312-0007-007F 9312-0007-008F 9312-0007-009F 9312-0007-OIOF 9312-0007-01 IF 9312-0007-012F 9312-0007-013F 9312-0007-015F Method Blank (MB)179836001(9312-0007-002F)

Sample Duplicate (DUP)Laboratory Control Sample (LCS)18 SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-013 REV# 13.Calibration Information:

Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.

Quality Control (OCQ Information:

Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 179836001 (9312-0007-002F).

QC Information All of the QC samples met the required acceptance limits.Technical Information:

Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis None of the samples in this sample set required reprep or reanalysis.

Miscellaneous Information:

NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.

A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.19 Qualifier information Qualifier UI U'U'Reason Data rejected due to high peak-width.

Data rejected due to interference.

Data rejected due to low abundance.

Data rejected due to no valid peak.Analyte Cesium- 137 Manganese-54 Americium-241 Cesium- 134 Manganese-54 Thallium-208 Potassium-40 Sample 179836009 179836013 179836010 179836001 179836002 179836003 179836004 179836006 179836009 179836010 179836011 179836013 179836014 179836015 179836016 1201271728 179836004 1201271727 1201271727 UI Method/Analysis Information 20 Product: GFPC, Sr90, solid-ALL FSS Analytical Method: EPA 905.0 Modified Prep Method: Dry Soil Prep GL-RAD-A-021 Method: Analytical Batch Number: Prep Batch Number: Dry Soil Prep GL-RAD-A-021 Batch Number: Ash Soil Prep Dry Soil Prep 606155 606003 606001 Sample ID 179836001 179836002 179836003 179836004 179836005 179836006 179836007 179836008 179836009 179836010 179836011 179836012 179836013 179836014 179836015 179836016 1201270171 1201270172 1201270173 1201270174 Client ID 9312-0007-002F 9312-0007-014F 9312-0007-001F 9312-0007-003F 9312-0007-003FS 9312-0007-004F 9312-0007-005F 9312-0007-006F 9312-0007-007F 9312-0007-008F 9312-0007-009F 9312-0007-01 OF 9312-0007-01 IF 9312-0007-012F 9312-0007-013F 9312-0007-015F Method Blank (MB)179836001(9312-0007-002F)

Sample Duplicate (DUP)179836001(9312-0007-002F)

Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-004 REV# 10.Calibration Information:

Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).21 Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.

Quality Control (OC) Information:

Blank Information The blank volume is representative of the sample volumes in this batch.Designated QC The following sample was used for QC: 179836001 (9312-0007-002F).

QC Information All of the QC samples met the required acceptance limits.Technical Information:

Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis Samples were recounted due to low/high recovery.Chemical Recoveries All chemical recoveries meet the required acceptance limits for this sample set.Miscellaneous Information:

NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.

A nonconformance report (NCR) was not generated for this SDG.Additional Comments The sample and the duplicate, 1201270172 (9312-0007-002F) and 179836001 (9312-0007-002F), did not meet the relative percent difference requirement, however they do meet the relative error ratio requirement with value of 2.69.Qualifier information Manual qualifiers were not required.Method/Analysis Information 22 Product: Liquid Scint Tc99, Solid-ALL FSS Analytical Method: Analytical Batch Number: Sample ID 179836001 179836002 1201270179 1201270180 1201270181 1201270182 DOE EML HASL-300, Tc-02-RC Modified 606162 Client ID 9312-0007-002F 9312-0007-014F Method Blank (MB)179836001(9312-0007-002F)

Sample Duplicate (DUP)179836001(9312-0007-002F)

Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-005 REV# 13.Calibration Information:

Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.

Quality Control (OC) Information:

Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 179836001 (9312-0007-002F).

QC Information All of the QC samples met the required acceptance limits.Technical Information:

Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.23 Sample Re-prep/Re-analysis None of the samples in this sample set required reprep or reanalysis.

Miscellaneous Information:

NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.

A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.Qualifier information Manual qualifiers were not required.Method/Analysis Information Product: Liquid Scint Fe55, Solid-ALL FSS Analytical Method: DOE RESL Fe- 1, Modified Prep Method: Dry Soil Prep GL-RAD-A-021 Method: Analytical Batch Number: Prep Batch Number: Dry Soil Prep GL-RAD-A-021 Batch Number: Ash Soil Prep Dry Soil Prep 606165 606003 606001 Sample ID 179836001 179836002 1201270187 1201270188 1201270189 1201270190 Client ID 9312-0007-002F 9312-0007-014F Method Blank (MB)179836001(9312-0007-002F)

Sample Duplicate (DUP)179836001(9312-0007-002F)

Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-040 REV# 3.24 Calibration Information:

Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.

Quality Control (QC) Information:

Blank Information The blank volume is representative of the sample volumes in this batch.Designated QC The following sample was used for QC: 179836001 (9312-0007-002F).

QC Information All of the QC samples met the required acceptance limits.Technical Information:

Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis Samples were recounted due to low/high recovery.Miscellaneous Information:

NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.

A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.Oualifier information Manual qualifiers were not required.Method/Analysis Information 25 Product: Liquid Scint Ni63, Solid-ALL FSS Analytical Method: DOE RESL Ni-1, Modified Prep Method: Dry Soil Prep GL-RAD-A-021 Method: Analytical Batch Number: Prep Batch Number: Dry Soil Prep GL-RAD-A-021 Batch Number: Ash Soil Prep Dry Soil Prep 606163 606003 606001 Sample ID 179836001 179836002 1201270183 1201270184 1201270185 1201270186 Client ID 9312-0007-002F 9312-0007-014F Method Blank (MB)179836001(9312-0007-002F)

Sample Duplicate (DUP)179836001(9312-0007-002F)

Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-022 REV# 8.Calibration Information:

Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.

Quality Control (QC) Information:

Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 179836001 (9312-0007-002F).

QC Information All of the QC samples met the required acceptance limits.26 Technical Information:

Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis None of the samples in this sample set required reprep or reanalysis.

Miscellaneous Information:

NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.

A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.Qualifier information Manual qualifiers were not required.Method/Analysis Information Product: LSC, Tritium Dist, Solid -3 pCi/g Analytical Method: Analytical Batch Number: Sample ID 179836001 179836002 1201270195 1201270196 1201270197 1201270198 EPA 906.0 Modified 606167 Client ID 9312-0007-002F 9312-0007-014F Method Blank (MB)179837001(9312-0008-006F)

Sample Duplicate (DUP)179837001(9312-0008-006F)

Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-002 REV# 13.27 Calibration Information:

Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.

Quality Control (OC) Information:

Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 179837001 (9312-0008-006F).

QC Information All of the QC samples met the required acceptance limits.Technical Information:

Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis None of the samples in this sample set required reprep or reanalysis.

Miscellaneous Information:

NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.

A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.Qualifier information Manual qualifiers were not required.Method/Analysis Information 28 Product: Liquid Scint C14, Solid AII,FSS Analytical Method: Analytical Batch Number: Sample ID 179836001 179836002 1201270191 1201270192 1201270193 1201270194 EPA EERF C-01 Modified 606166 Client ID 9312-0007-002F 9312-0007-014F Method Blank (MB)179836001(9312-0007-002F)

Sample Duplicate (DUP)179836001(9312-0007-002F)

Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-003 REV# 8.Calibration Information:

Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.

Ouality Control (QC' Information:

Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 179836001 (9312-0007-002F).

QC Information All of the QC samples met the required acceptance limits.Technical Information:

Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.29 Sample Re-prep/Re-analysis None of the samples in this sample set required reprep or reanalysis.

Miscellaneous Information:

NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.

A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.Qualifier information Manual qualifiers were not required.Certification Statement Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless otherwise noted in the analytical case narrative.

Review Validation:

GEL requires all analytical data to be verified by a qualified data validator.

In addition, all data designated for CLP or CLP-like packaging will receive a third level validation upon completion of the data package.The following data validator verified the information presented in this case narrative:

Reviewer/Date:

b" z o-30 SAMPLE DATA

SUMMARY

31 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Report for YANK001 Connecticut Yankee Atomic Power Co.Client SDG: MSR#07-0054 GEL Work Order: 179836 The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification ND The analyte concentration is not detected above the detection limit.The above sample is reported on a dry weight basis except where prohibited by the analytical procedure.

Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the Certificate of Analysis.This data report has been prepared and reviewed in accordance with GEL Laboratories LLC standard operating procedures.

Please direct any questions to your Project Manager, Cheryl Jones.Reviewed by 32 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: 9312-0007-002F Project: YANK01204 Sample ID: 179836001 Client ID: YANK001 Matrix: TS Vol. Recv.: Collect Date: 23-JAN-07 Receive Date: 30-JAN-07 Collector:

Client Moisture:

8.9%Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Alpha Spec Analysis Alphaspec Am241, Cm, Solid ALL FSS Americium-241 U 0.0303 Curium-242 U -0.0361 Curium-243/244 U -0.0502+/-0.158+/-0.0751+/-0.164 0.123 0.0837 0.152+/-0.158+/-0.0752+/-0.164 Alphaspec Pu, Solid-ALL FSS Plutonium-238 U Plutonium-239/240 U Liquid Scint Pu241, Solid-ALL FSS Plutonium-241 U Rad Gamma Spec Analysis 0.327 0.252 0.384 0.151 0.0782 11.6 0.0727 +/-0.0998 0.00 +/-0.0566 0.0366 +/-0.100 0.00 +/-0.0566-3.0 +/-6.37 5.50 +/-6.37 Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 1.23 Americium-241 U 0.0388 Bismuth-212 0.719 Bismuth-214 0.701 Cesium-134 UI 0.00 Cesium-137 U 0.00716 Cobalt-60 U 0.000511 Europium-152 U -0.0201 Europium-154 U 0.0172 Europium-155 U 0.049 Lead-212 1.04 Lead-214 0.742 Manganese-54 U 0.00648 Niobium-94 U 0.0138 Potassium-40 16.8 Radium-226 0.701 Silver-108m U -0.0161 Thallium-208 0.321 Rad Gas Flow Proportional Counting+/-0.169+/-0.0604+/-0.191+/-0.0804+/-0.0254+/-0.0136+/-0.0148+/-0.049+/-0.050+/-0.0469+/-0.0944+/-0.0852+/-0.019+/-0.0126+/-1.18+/-0.0804+/-0.0125+/-0.0386 0.0395 0.0463 0.092 0.0217 0.015 0.0118 0.0125 0.0323 0.0373 0.0346 0.0179 0.0224 0.0125 0.0111 0.0876 0.0217 0.0104 0.0107+/-0.169+/-0.0604+/-0.191+/-0.0804+/-0.0254+/-0.0136+/-0.0148+/-0.049+/-0.050+/-0.0469+/-0.0944+/-0.0852+/-0.019+/-0.0126+/-1.18+/-0.0804+/-0.0125+/-0.0386 0.0789 0.0925 0.184 0.0434 0.0299 0.0235 0.0249 0.0646 0.0746 0.0692 0.0358 0.0447 0.025 0.0222 0.175 0.0434 0.0209 0.0214 0.0289 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g DXH2 02/01/07 0743 606029 1 DXH2 01/31/07 1554 606031 2 DXH2 02/01/07 0919 606032 3 MJHI 02/02/07 1921 606828 4 GFPC, Sr90, solid-ALL FSS Strontium-90 U Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid -3 pCi/g Tritium U 0.00439 +/-0.0156 0.0125 +/-0.0156 0.480 +/-0.303 0.445 +/-0.303 KSDI 02/03/07 1023 606155 5 AXD2 02/01/07 0130 606167 7 1.01 pCi/g 33 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: 9312-0007-002F 179836001 Project: YANK01204 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Rad Liquid Scintillation Analysis Liquid Scint C14, Solid All, FSS Carbon-14 U -0.0109 Liquid Scint Fe55, Solid-ALL FSS Iron-55 U 19.0 Liquid Scint Ni63, Solid-ALL FSS Nickel-63 U -9.21 Liquid Scint Tc99, Solid-ALL FSS Technetium-99 U -0.157 Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd+/-0.0671 0.0568 +/-0.0671+/-62.6 40.2 +/-62.6+/-11.8 10.2 +/-11.8+/-0.168 0.149 +/-0.168 0.119 83.7 21.2 0.315 pCi/g pCi/g pCi/g pCi/g AXD2 01/31/07 1600 606166 8 MXPI 02/03/07 0956 606165 9 MXPI 02/01/07 1505 606163 11 KXR1 02/04/07 2201 606162 12 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I DOE EML HASL-300, Am-05-RC Modified 2 DOE EML HASL-300, Pu-I 1-RC Modified 3 DOE EML HASL-300, Pu- I -RC Modified 4 EML HASL 300, 4.5.2.3 5 EPA 905.0 Modified 6 EPA 905.0 Modified 7 EPA 906.0 Modified 8 EPA EERF C-01 Modified 9 DOE RESL Fe-I, Modified 10 DOE RESL Fe-1, Modified II DOE RESL Ni-I, Modified 12 DOE EML HASL-300, Tc-02-RC Modified Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Americium-243 Plutonium-242 Plutonium-242 Strontium-90 Carrier/Tracer Recovery Alphaspec Am241, Cm, Solid ALL Alphaspec Pu, Solid-ALL FSS Liquid Scint Pu241, Solid-ALL FS GFPC, Sr90, solid-ALL FSS GFPC, Sr90, solid-ALL FSS 94 90 88 72 72 (15%-125%)

(15%-125%)

(25%-125%)

34 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-002F Project: YANKO 1204 Sample ID: 179836001 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd lron-59 Liquid Scint Fe55, Solid-ALL FS 78 (15%-125%)

Nickel-63 Liquid Scint Ni63, Solid-ALL FS 80 (25%-125%)

Carrier/Tracer Recovery Liquid Scint Ni63, Solid-ALL FS 80 (25%-125%)

Technetium-99 Liquid Scint Tc99, Solid-ALL FS 70 (15%-125%)

Carrier/Tracer Recovery Liquid Scint Tc99, Solid-ALL FS 70 (15%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.35 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-014F 179836002 TS 23-JAN-07 30-JAN-07 Client 6.53%Project: YANK01204 Client ID: YANKOO Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Alpha Spec Analysis Alphaspec Am241, Cm, Solid ALL FSS Americium-241 U -0.0183 Curium-242 U 0.0251 Curium-243/244 U 0.122 Alphaspec Pu, Solid-ALL FSS Plutonium-238 U -0.0342 Plutonium-239/240 U 0.0465 Liquid Scint Pu241, Solid-ALL FSS+/-0.0763+/-0.0665+/-0.159 0.0753 0.0296 0.0854+/-0.0763+/-0.0665+/-0.159 0.236 0.149 0.257 0.400 0.296 pCi/g pCi/g pCi/g pCi/g pCi/g DXH2 02/01/07 0743 606029 1 DXH2 01/31/07 1554 606031 2 DXH2 02/01/07 0935 606032 3+/-0.170 0.154 +/-0.170+/-0.144 0.102 +/-0.144 Plutonium-241 Rad Gamma Spec Analysis U 0.939 +/-9.72 8.11 +/-9.72 17.2 pCi/g Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.536 Americium-241 U 0.0208 Bismuth-212 0.423 Bismuth-214 0.474 Cesium-134 UI 0.00 Cesium-137 U 0.0101 Cobalt-60 U -0.00117 Europium-152 U -0.0169 Europium-154 U -0.00756 Europium-155 U 0.0483 Lead-212 0.538 Lead-214 0.476 Manganese-54 U 0.00296 Niobium-94 U-0.000998 Potassium-40 10.4 Radium-226 0.474 Silver-108m U 0.00133 Thallium-208 0.169 Rad Gas Flow Proportional Counting GFPC, Sr90, solid-ALL FSS Strontium-90 U 0.0111 Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid -3 pCi/g Tritium U 0.136+/-0.099+/-0.0194+/-0.139+/-0.0552+/-0.0168+/-0.0161+/-0.0131+/-0.0337+/-0.0334+/-0.038+/-0.0517+/-0.0594+/-0.0116+/-0.0125+/-0.777+/-0.0552+/-0.0143+/-0.0255 0.0327 0.0288 0.0736 0.0177 0.0131 0.0105 0.010 0.0273 0.0279 0.0275 0.0152 0.0199 0.0103 0.00949 0.0777 0.0177 0.00944 0.00944+/-0.099+/-0.0194+/-0.139+/-0.0552+/-0.0168+/-0.0161+/-0.0131+/-0.0337+/-0.0334+/-0.038+/-0.0517+/-0.0594+/-0.0116+/-0.0125+/-0.777+/-0.0552+/-0.0143+/-0.0255 0.0653 0.0576 0.147 0.0354 0.0261 0.0209 0.020 0.0545 0.0558 0.0549 0.0305 0.0398 0.0207 0.019 0.155 0.0354 0.0189 0.0189 0.024 1.06 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/02/07 1922 606828 4 KSDI 02/03/07 1023 606155 5 AXD2 02/01/07 0203 606167 7+/-0.0141 0.0104 +/-0.0141+/-0.294 0.468 +/-0.294 36 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: 9312-0007-014F 179836002 Proiect: YANK01204 Client ID: YANKOOl Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis Liquid Scint C14, Solid All, FSS Carbon-14 U 0.Liquid Scint Fe55, Solid-ALL FSS Iron-55 U Liquid Scint Ni63, Solid-ALL FSS Nickel-63 U Liquid Scint Tc99, Solid-ALL FSS Technetium-99 U 00626 +/-0.0779 0.0651 +/-0.0779 0.137 pCi/g+/-57.1 37.4 +/-57.1 78.1 pCi/g AXD2 01/31/07 1703 606166 8 MXP1 02/03/07 1012 606165 9 MXPI 02/01/07 1521 606163 11 KXRI 02/04/07 2218 606162 12+/-11.1 9.36 +/-11.1 19.4 pCi/g pCi/g 0.167 +/-0.206 0.165 +/-0.207 0.349 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I DOE EML HASL-300, Am-05-RC Modified 2 DOE EML HASL-300, Pu-I I-RC Modified 3 DOE EML HASL-300, Pu-11 -RC Modified 4 EML HASL 300, 4.5.2.3 5 EPA 905.0 Modified 6 EPA 905.0 Modified 7 EPA 906.0 Modified 8 EPA EERF C-01 Modified 9 DOE RESL Fe-I, Modified 10 DOE RESL Fe-1, Modified 11 DOE RESL Ni-1, Modified 12 DOE EML HASL-300, Tc-02-RC Modified Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Americium-243 Plutonium-242 Plutonium-242 Strontium-90 Carrier/Tracer Recovery Alphaspec Am241, Cm, Solid ALL Alphaspec Pu, Solid-ALL FSS Liquid Scint Pu241, Solid-ALL FS GFPC, Sr90, solid-ALL FSS GFPC, Sr90, solid-ALL FSS 82 79 61 80 80 (15%-125%)

(15%-125%)

(25%-125%)

37 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-014F Project: YANK01204 Sample ID: 179836002 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Iron-59 Liquid Scint Fe55, Solid-ALL FS 71 (15%-125%)

Nickel-63 Liquid Scint Ni63, Solid-ALL FS 86 (25%-125%)

Carrier/Tracer Recovery Liquid Scint Ni63, Solid-ALL FS 86 (25%-125%)

Technetium-99 Liquid Scint Tc99, Solid-ALL FS 65 (15%-125%)

Carrier/Tracer Recovery Liquid Scint Tc99, Solid-ALL FS 65 (15%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.38 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of AnaIv,~i~Certificateof Anaksis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-00IF 179836003 TS 23-JAN-07 30-JAN-07 Client 8.07%Project: Client ID: Vol. Recv.: YANK01204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 1.02 +/-0.183 Americium-241 U 0.0261 +/-0.0269 Bismuth-212 0.790 +/-0.277 Bismuth-214 0.654 +/-0.102 Cesium-134 UI 0.00 +/-0.027 Cesium-137 U -0.00333 +/-0.0208 Cobalt-60 U 0.0119 +/-0.021 Europium-152 U -0.0741 +/-0.058 Europium-154 U -0.00474 +/-0.0688 Europium-155 U 0.0148 +/-0.0471 Lead-212 1.01 +/-0.0991 Lead-214 0.741 +/-0.0928 Manganese-54 U 0.0294 +/-0.0188 Niobium-94 U -0.00341 +/-0.0171 Potassium-40 16.7 +/-0.909 Radium-226 0.654 +/-0.102 Silver-108m U -0.00757 +/-0.0168 Thallium-208 0.332 +/-0.049 Rad Gas Flow Proportional Counting 0.0599 0.0217 0.119 0.0271 0.0199 0.0156 0.0182 0.0353 0.0574 0.0336 0.0195 0.0251 0.0175 0.0148 0.147 0.0271 0.0122 0.015+/-0.183+/-0.0269+/-0.277+/-0.102+/-0.027+/-0.0208+/-0.021+/-0.058+/-0.0688+/-0.0471+/-0.0991+/-0.0928+/-0.0188+/-0.0171+/-0.909+/-0.102+/-0.0168+/-0.049 0.120 0.0434 0.238 0.0542 0.0398 0.0312 0.0365 0.0706 0.115 0.0671 0.039 0.0503 0.0349 0.0296 0.293 0.0542 0.0244 0.0301 0.0314 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJHI 02/02/07 1922 606828 1 GFPC, Sr9O, solid-ALL FSS Strontium-90 U -0.00712 +/-0.0154 0.0138 +/-0.0154 KSDI 02/03/07 1023 606155 2 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 01/30/07 1112 606001 The following Analytical Methods were performed Method Description 1 EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 39 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-OOIF Project: YANK01204 Sample ID: 179836003 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 71 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 71 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.40 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-003F 179836004 TS 23-JAN-07 30-JAN-07 Client 9.2%Project: Client ID: Vol. Recv.: YANK01204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma, Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 Americium-241 U Bismuth-212 Bismuth-214 Cesium-134 UI Cesium-137 Cobalt-60 U Europium-152 U Europium-154 U Europium-155 U Lead-212 Lead-214 Manganese-54 UI Niobium-94 U Potassium-40 Radium-226 Silver-108m U -Thallium-208 Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 U 0.562 0.0189 0.413 0.476 0.00 0.0204 0.00425-0.0078 0.0172 0.0118 0.587 0.502 0.00 0.00302 10.4 0.476 0.00605 0.173+/-0.092+/-0.0404+/-0.135+/-0.062+/-0.0166+/-0.0125+/-0.00872

+/-0.0347+/-0.030+/-0.0403+/-0.0528+/-0.0575+/-0.0093+/-0.0104+/-0.702+/-0.062+/-0.0077+/-0.025 0.0254 +/-0.092 0.0341 +/-0.0404 0.0506 +/-0.135 0.013 +/-0.062 0.00952 +/-0.0166 0.00786 +/-0.0125 0.00754 +/-0.00872 0.0211 0.0227 0.027 0.0127 0.0148 0.00764 0.00706 0.0617 0.013 0.00663 0.00716+/-0.0347+/-0.030+/-0.0403+/-0.0528+/-0.0575+/-0.0093+/-0.0104+/-0.702+/-0.062+/-0.0077+/-0.025 0.0508 0.0681 0.101 0.0259 0.019 0.0157 0.0151 0.0422 0.0453 0.0539 0.0253 0.0296 0.0153 0.0141 0.123 0.0259 0.0133 0.0143 0.0301 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/02/07 1923 606828 I 0.00879 +/-0.017 0.0132 +/-0.017 KSD1 02/03/07 1023 606155 2 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 41 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-003F Project: YANK01204 Sample ID: 179836004 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 77 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 77 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.42 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd Contact: Project: East Hampton, Connecticut 06424 Mr. Jack McCarthy Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-003FS 179836005 TS 23-JAN-07 30-JAN-07 Client 10.1%Project: YANK01204 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.689 +/-0.140 Americium-241 U 0.0512 +/-0.0629 Bismuth-212 0.447 +/-0.267 Bismuth-214 0.412 +/-0.0848 Cesium-134 U 0.0361 +/-0.0298 Cesium-137 U 0.0191 +/-0.0225 Cobalt-60 U -0.0104 +/-0.020 Europium-152 U 0.033 +/-0.0642 Europium-154 U 0.00869 +/-0.0642 Europium-155 U 0.0638 +/-0.0686 Lead-212 0.524 +/-0.0746 Lead-214 0.500 +/-0.0965 Manganese-54 U 0.013 +/-0.0255 Niobium-94 U -0.0223 +/-0.0215 Potassium-40 10.7 +/-1.00 Radium-226 0.412 +/-0.0848 Silver-108m U -0.022 +/-0.0232 Thallium-208 0.186 +/-0.0408 Rad Gas Flow Proportional Counting 0.0654 0.0531 0.170 0.0322 0.022 0.0201 0.0151 0.0488 0.0508 0.052 0.0316 0.0343 0.0201 0.0163 0.151 0.0322 0.0167 0.0154+/-0.140+/-0.0629+/-0.267+/-0.0848+/-0.0298+/-0.0225+/-0.020+/-0.0642+/-0.0642+/-0.0686+/-0.0746+/-0.0965+/-0.0255+/-0.0215+/-1.00+/-0.0848+/-0.0232+/-0.0408 0.131 0.106 0.340 0.0644 0.0439 0.0403 0.0302 0.0976 0.102 0.104 0.0631 0.0685 0.0402 0.0325 0.301 0.0644 0.0333 0.0309 0.0243 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/03/07 1022 606828 1 GFPC, Sr9O, solid-ALL FSS Strontium-90 U 0.00724 +/-0.0137 0.0105 +/-0.0137 KSDI 02/03/07 1023 606155 2 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 43 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-003FS Project: YANK01204 Sample ID: 179836005 Client ID: YANKOOI Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, SrO0, solid-ALL FSS 84 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 84 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.44 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-004F 179836006 TS 23-JAN-07 30-JAN-07 Client 8.81%Project: YANK01204 Client ID: YANKOO Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 1.18 +/-0.257 Americium-241 U -0.0331 +/-0.0717 Bismuth-212 0.813 +/-0.453 Bismuth-214 1.10 +/-0.176 Cesium-134 UI 0.00 +/-0.071 Cesium-137 U-0.000283

+/-0.0336 Cobalt-60 U 0.0258 +/-0.0367 Europium-152 U 0.0266 +/-0.096 Europium-154 U -0.0822 +/-0.122 Europium-155 U 0.0585 +/-0.0958 Lead-212 1.19 +/-0.130 Lead-214 1.13 +/-0.160 Manganese-54 U 0.0384 +/-0.0343 Niobium-94 U 0.0182 +/-0.0327 Potassium-40 18.3 +/-1.45 Radium-226 1.10 +/-0.176 Silver-108m U -0.0318 +/-0.0264 Thallium-208 0.353 +/-0.0721 Rad Gas Flow Proportional Counting 0.113 0.0393 0.215 0.0483 0.0355 0.0294 0.0331 0.0651 0.095 0.0607 0.0363 0.0447 0.0319 0.026 0.254 0.0483 0.0209 0.0285+/-0.257+/-0.0717+/-0.453+/-0.176+/-0.071+/-0.0336+/-0.0367+/-0.096+/-0.122+/-0.0958+/-0.130+/-0.160+/-0.0343+/-0.0327+/-1.45+/-0.176+/-0.0264+/-0.0721 0.227 0.0785 0.430 0.0965 0.0709 0.0589 0.0661 0.130 0.190 0.121 0.0726 0.0894 0.0637 0.052 0.508 0.0965 0.0417 0.057 0.0298 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/03/07 1023 606828 1 GFPC, Sr90, solid-ALL FSS Strontium-90 U 0.00194 +/-0.0157 0.0129 +/-0.0157 KSD1 02/03/07 1023 606155 2 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 01/30/07 1112 606001 The following Analytical Methods were performed Method Description 1 EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 45 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-004F Proiect: YANK0 1204 Sample ID: 179836006 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery % Acceptable Limits Strontium-90 GFPC, Sr9O, solid-ALL FSS 71 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 71 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.46 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-005F 179836007 TS 23-JAN-07 30-JAN-07 Client 8.61%Project: Client ID: Vol. Recv.: YANK01204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.869 +/-0.207 Americium-241 U 0.0521 +/-0.113 Bismuth-212 0.546 +/-0.334 Bismuth-214 0.648 +/-0.124 Cesium-134 U 0.0513 +/-0.0355 Cesium-137 0.0894 +/-0.0421 Cobalt-60 U -0.0142 +/-0.0244 Europium-152 U -0.022 +/-0.0702 Europium-154 U 0.00937 +/-0.0787 Europium-155 U 0.0528 +/-0.0923 Lead-212 1.02 +/-0.105 Lead-214 0.763 +/-0.115 Manganese-54 U 0.0072 +/-0.024 Niobium-94 U 0.0128 +/-0.0216 Potassium-40 15.5 +/-1.36 Radium-226 0.648 +/-0.124 Silver-108m U -0.0182 +/-0.0204 Thallium-208 0.314 +/-0.0571 Rad Gas Flow Proportional Counting 0.068 0.0938 0.161 0.0352 0.0269 0.0171 0.019 0.053 0.0668 0.0598 0.0319 0.038 0.0213 0.019 0.184 0.0352 0.0169 0.0177+/-0.207+/-0.113+/-0.334+/-0.124+/-0.0355+/-0.0421+/-0.0244+/-0.0702+/-0.0787+/-0.0923+/-0.105+/-0.115+/-0.024+/-0.0216+/-1.36+/-0.124+/-0.0204+/-0.0571 0.136 0.187 0.321 0.0703 0.0538 0.0343 0.038 0.106 0.134 0.120 0.0637 0.076 0.0426 0.0379 0.367 0.0703 0.0337 0.0353 0.0293 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/03/07 1023 606828 1 GFPC, Sr90, solid-ALL FSS Strontium-90 U 0.00424 +/-0.0158 0.0127 +/-0.0158 KSDI 02/03/07 1024 606155 2 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I EML HASL 300,4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 47 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-005F Proiect: YANK01204 Sample ID: 179836007 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 71 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 71 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.48 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-006F 179836008 TS 23-JAN-07 30-JAN-07 Client 8.44%Proiect: Client ID: Vol. Recv.: YANK01204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma, Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.483 Americium-241 U 0.0165 Bismuth-212 0.535 Bismuth-214 0.541 Cesium-134 U 0.0199 Cesium-137 U 0.00249 Cobalt-60 U 0.00587 Europium-152 U 0.0122 Europium-154 U -0.0579 Europium-155 U 0.017 Lead-212 0.644 Lead-214 0.584 Manganese-54 U 0.0025 Niobium-94 U 0.00146 Potassium-40 11.9 Radium-226 0.541 Silver-108m U 0.000469 Thallium-208 0.203 Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 U 0.0125+/-0.160+/-0.108+/-0.329+/-0.107+/-0.0244+/-0.024+/-0.0195+/-0.0634 F/-0.0746+/-0.0623 F/-0.0738+/-0.101+/-0.0222+/-0.0199+/-1.13+/-0.107+/-0.0184+/-0.0486 0.0653 0.0901 0.137 0.0355 0.0207 0.0206 0.017 0.0474 0.0576 0.0574 0.0278 0.0338 0.0196 0.017 0.133 0.0355 0.0162 0.0181+/-0.160+/-0.108+/-0.329+/-0.107+/-0.0244+/-0.024+/-0.0195+/-0.0634+/-0.0746+/-0.0623+/-0.0738+/-0.101+/-0.0222+/-0.0199+/-1.13+/-0.107+/-0.0184+/-0.0486 0.131 0.180 0.274 0.071 0.0415 0.0412 0.034 0.0948 0.115 0.115 0.0555 0.0676 0.0391 0.0339 0.266 0.071 0.0324 0.0361 0.0262 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/03/07 1024 606828 1 KSD1 02/03/07 1024 606155 2+/-0.0154 0.0115 +/-0.0154 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 01/30/07 1112 606001 The following Analytical Methods were performed Method Description 1 EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 49 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-006F Proeect: YANKO 1204 Sample ID: 179836008 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, Sr9O, solid-ALL FSS 87 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 87 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.Ul Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.50 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd Contact: Project: East Hampton, Connecticut 06424 Mr. Jack McCarthy Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-007F 179836009 TS 23-JAN-07 30-JAN-07 Client 11%Project: Client ID: Vol. Recv.: YANKO 1204 YANKOOI Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.511 +/-0.186 Americium-241 U -0.0406 +/-0.100 Bismuth-212 0.534 +/-0.222 Bismuth-214 0.459 +/-0.090 Cesium-134 UI 0.00 +/-0.0401 Cesium-137 UI 0.00 +/-0.0409 Cobalt-60 U 0.00976 +/-0.0219 Europium-152 U -0.0163 +/-0.0772 Europium-154 U 0.0203 +/-0.0639 Europium-155 U 0.0515 +/-0.0597 Lead-212 0.722 +/-0.080 Lead-214 0.593 +/-0.0916 Manganese-54 U -0.0023 +/-0.022 Niobium-94 U 0.00304 +/-0.0209 Potassium-40 12.6 +/-1.17 Radium-226 0.459 +/-0.090 Silver-108m U 0.0129 +/-0.0176 Thallium-208 0.239 +/-0.0477 Rad Gas Flow Proportional Counting 0.0618 0.0809 0.113 0.0328 0.0215 0.0165 0.0193 0.0461 0.0555 0.0558 0.0264 0.031 0.019 0.0168 0.136 0.0328 0.0162 0.0158+/-0.186+/-0.100+/-0.222+/-0.090+/-0.0401+/-0.0409+/-0.0219+/-0.0772+/-0.0639+/-0.0597+/-0.080+/-0.0916+/-0.022+/-0.0209+/-1.17+/-0.090+/-0.0176+/-0.0477 0.124 0.162 0.225 0.0656 0.043 0.033 0.0386 0.0921 0.111 0.112 0.0528 0.062 0.038 0.0335 0.271 0.0656 0.0323 0.0316 0.0244 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/03/07 1024 606828 1 GFPC, Sr9O, solid-ALL FSS Strontium-90 U 0.00143 +/-0.0129 0.0106 +/-0.0129 KSDI 02/03/07 1024 606155 2 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 01/30/07 1112 606001 The following Analytical Methods were performed Method Description 1 EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 51 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd Contact: Project: East Hampton, Connecticut 06424 Mr. Jack McCarthy Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: 9312-0007-007F 179836009 Project: Client ID: Vol. Recv.: YANK01204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Strontium-90 GFP(Carrier/Tracer Recovery GFP(Recovery%

Acceptable Limits C, Sr90, solid-ALL FSS C, Sr90, solid-ALL FSS 86 86 (25%-125%)

(25%-125%)

Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.52 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 931 2-0007-008F 179836010 TS 23-JAN-07 30-JAN-07 Client 6.7%Proiect: Client ID: Vol. Recv.: YANKO1204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 1.05 +/-0.164 Americium-241 UI 0.00 +/-0.0297 Bismuth-212 0.747 +/-0.287 Bismuth-214 0.706 +/-0.101 Cesium-134 UI 0.00 +/-0.0279 Cesium-137 U 0.0126 +/-0.0194 Cobalt-60 U -0.00306 +/-0.0189 Europium-152 U -0.0363 +/-0.0483 Europium-154 U -0.0334 +/-0.0562 Europium-155 U 0.0342 +/-0.0419 Lead-212 0.925 +/-0.0956 Lead-214 0.706 +/-0.0876 Manganese-54 U 0.0242 +/-0.0203 Niobium-94 U 0.0245 +/-0.0198 Potassium-40 17.3 +/-1.19 Radium-226 0.706 +/-0.101 Silver-108m U -0.0128 +/-0.0156 Thallium-208 0.360 +/-0.0482 Rad Gas Flow Proportional Counting 0.0507 0.0253 0.119 0.0291 0.020 0.0169 0.0157 0.0385 0.0459 0.0388 0.022 0.0275 0.0147 0.0146 0.130 0.0291 0.0134 0.0148+/-0.164+/-0.0297+/-0.287+/-0.101+/-0.0279+/-0.0194+/-0.0189+/-0.0483+/-0.0562+/-0.0419+/-0.0956+/-0.0876+/-0.0203+/-0.0198+/-1.19+/-0.101+/-0.0156+/-0.0482 0.101 0.0505 0.238 0.0583 0.0399 0.0337 0.0315 0.0769 0.0918 0.0775 0.044 0.055 0.0294 0.0291 0.261 0.0583 0.0268 0.0296 0.0298 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJHI 02/03/07 1348 606828 I GFPC, Sr9O, solid-ALL FSS Strontium-90 U 0.00236 +/-0.0159 0.013 +/-0.0159 KSDI 02/03/07 1024 606155 2 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 53 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-008F Project: YANK01204 Sample ID: 179836010 Client ID: YANKOOl Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, Sr9O, solid-ALL FSS 76 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr9O, solid-ALL FSS 76 (25%-125%)

Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.54 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: 9312-0007-009F Project: YANK01204 Sample ID: 179836011 Client ID: YANKOO Matrix: TS Vol. Recv.: Collect Date: 23-JAN-07 Receive Date: 30-JAN-07 Collector:

Client Moisture:

6.03%Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 1.01 +/-0.152 Americium-241 U 0.036 +/-0.0493 Bismuth-212 0.681 +/-0.222 Bismuth-214 0.676 +/-0.0774 Cesium-134 UI 0.00 +/-0.0179 Cesium-137 U 0.0151 +/-0.0155 Cobalt-60 U -0.00856 +/-0.0165 Europium-152 U -0.0128 +/-0.0433 Europium-154 U -0.0207 +/-0.0452 Europium-155 U 0.052 +/-0.0451 Lead-212 0.975 +/-0.0852 Lead-214 0.722 +/-0.0823 Manganese-54 U 0.00777 +/-0.0146 Niobium-94 U -0.00152 +/-0.0115 Potassium-40 16.6 +/-1.13 Radium-226 0.676 +/-0.0774 Silver-108m U -0.00734 +/-0.0114 Thallium-208 0.285 +/-0.0349 Rad Gas Flow Proportional Counting 0.0415 0.0377 0.0793 0.0193 0.0144 0.0114 0.0113 0.0285 0.037 0.0324 0.0168 0.0204 0.0113 0.0101 0.0869 0.0193 0.00968 0.011+/-0.152+/-0.0493+/-0.222+/-0.0774+/-0.0179+/-0.0155+/-0.0165+/-0.0433+/-0.0452+/-0.0451+/-0.0852+/-0.0823+/-0.0146+/-0.0115+/-1.13+/-0.0774+/-0.0114+/-0.0349 0.083 0.0753 0.159 0.0385 0.0287 0.0228 0.0225 0.057 0.074 0.0648 0.0337 0.0408 0.0225 0.0201 0.174 0.0385 0.0194 0.0219 0.0343 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJHI 02/03/07 1348 606828 1 KSD1 02/03/07 1024 606155 2 GFPC, Sr90, solid-ALL FSS Strontium-90 U -0.00261 +/-0.0177 0.0151 +/-0.0177 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 55 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-009F Project: YANK01204 Sample ID: 179836011 Client ID: YANKOOI Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, Sr9O, solid-ALL FSS 68 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 68 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.56 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-OIOF 179836012 TS 23-JAN-07 30-JAN-07 Client 7.33%Proiect: Client ID: Vol. Recv.: YANK01204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.566 +/-0.107 Americium-241 U -0.0131 +/-0.0424 Bismuth-212 0.525 +/-0.169 Bismuth-214 0.458 +/-0.0646 Cesium-134 U 0.0158 +/-0.0168 Cesium-137 0.031 +/-0.011 Cobalt-60 U -0.0107 +/-0.0136 Europium-152 U 0.00378 +/-0.0314 Europium-154 U -0.029 +/-0.0365 Europium-155 U 0.0451 +/-0.0327 Lead-212 0.607 +/-0.0554 Lead-214 0.533 +/-0.0597 Manganese-54 U 0.0138 +/-0.0142 Niobium-94 U -0.0111 +/-0.0135 Potassium-40 10.9 +/-0.815 Radium-226 0.458 +/-0.0646 Silver-108m U 0.00501 +/-0.0107 Thallium-208 0.187 +/-0.0281 Rad Gas Flow Proportional Counting 0.031 0.0325 0.0688 0.0176 0.0122 0.0094 0.00926 0.0247 0.0285 0.0274 0.0144 0.0173 0.00843 0.00885 0.0738 0.0176 0.00844 0.00924+/-0.107+/-0.0424+/-0.169+/-0.0646+/-0.0168+/-0.011+/-0.0136+/-0.0314+/-0.0365+/-0.0327+/-0.0554+/-0.0597+/-0.0142+/-0.0135+/-0.815+/-0.0646+/-0.0107+/-0.0281 0.062 0.0649 0.138 0.0351 0.0244 0.0188 0.0185 0.0494 0.0569 0.0549 0.0287 0.0346 0.0168 0.0177 0.147 0.0351 0.0169 0.0185 0.0304 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJHI 02/03/07 1349 606828 1 GFPC, Sr90, solid-ALL FSS Strontium-90 U-0.000213

+/-0.0155 0.013 +/-0.0155 KSDI 02/03/07 1024 606155 2 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 57 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-O1OF Proiect: YANK01204 Sample ID: 179836012 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 63 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 63 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.58 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-01IF 179836013 TS 23-JAN-07 30-JAN-07 Client 10.1%Project: YANK01204 Client ID: YANKOO Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 1.05 Americium-241 U 0.0203 Bismuth-212 0.683 Bismuth-214 0.628 Cesium-134 UI 0.00 Cesium-137 U -0.0107 Cobalt-60 U -0.00376 Europium-152 U -0.0182 Europium-154 U 0.0545 Europium-155 U 0.0268 Lead-212 0.997 Lead-214 0.711 Manganese-54 Ul 0.00 Niobium-94 U -0.00128 Potassium-40 17.3 Radium-226 0.628 Silver-108m U -0.00473 +Thallium-208 0.307 Rad Gas Flow Proportional Counting GFPC, Sr90, solid-ALL FSS Strontium-90 U 0.0138+/-0.150+/-0.0779+/-0.154+/-0.0723+/-0.0245+/-0.0113+/-0.0114+/-0.034+/-0.0616+/-0.0487+/-0.0862+/-0.0755+/-0.0157+/-0.0104+/-1.11+/-0.0723/-0.00996+/-0.0355 0.0319 0.064 0.0698 0.017 0.0122 0.0092 0.00937 0.0257 0.0289 0.0367 0.0156 0.0174 0.00885 0.0087 0.082 0.017+/-0.150+/-0.0779+/-0.154+/-0.0723+/-0.0245+/-0.0113+/-0.0114+/-0.034+/-0.0616+/-0.0487+/-0.0862+/-0.0755+/-0.0157+/-0.0104+/-1. 11+/-0.0723 0.0638 0.128 0.140 0.0341 0.0243 0.0184 0.0187 0.0514 0.0578 0.0734 0.0313 0.0349 0.0177 0.0174 0.164 0.0341 0.0172 0.0183 0.0309 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/03/07 1349 606828 1 KSD1 02/03/07 1024 606155 2 0.00859 +/-0.00996 0.00913 +/-0.0355+/-0.0181 0.0134 +/-0.0181 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 59 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-011F Project: YANKO 1204 Sample ID: 179836013 Client ID: YANKOOl Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 71 (25 %-125%)Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 71 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.60 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-012F 179836014 TS 23-JAN-07 30-JAN-07 Client 9.01%Proiect: Client ID: Vol. Recv.: YANKO1204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.872 Americium-241 U 0.0275 Bismuth-212 0.448 Bismuth-214 0.818 Cesium-134 Ul 0.00 Cesium-137 U -0.0037 Cobalt-60 U 0.0107 Europium-152 U -0.0252 Europium-154 U 0.000514 Europium-155 U 0.0368 Lead-212 0.941 Lead-214 0.844 Manganese-54 U -9.960E-+/-0.132+/-0.0699+/-0.175+/-0.0948+/-0.0273+/-0.0149+/-0.014+/-0.043+/-0.0492+/-0.0482+/-0.0881+/-0.0931+/-0.0141+/-0.0135+/-1.11+/-0.0948+/-0.0121+/-0.0388 0.0398 0.0458 0.0922 0.022 0.016 0.0125 0.0124 0.032 0.0357 0.0347 0.0182 0.0222 0.0123 0.0115 0.104 0.022 0.0105 0.0119+/-0.132+/-0.0699+/-0.175+/-0.0948+/-0.0273+/-0.0149+/-0.014+/-0.043+/-0.0492+/-0.0482+/-0.0881+/-0.0931+/-0.0141+/-0.0135+/-1.11+/-0.0948+/-0.0121+/-0.0388 0.0796 0.0915 0.184 0.044 0.0319 0.0249 0.0248 0.0641 0.0713 0.0693 0.0364 0.0444 0.0245 0.023 0.208 0.044 0.021 0.0237 0.0261 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJHI 02/03/07 1350 606828 I Niobium-94 U Potassium-40 Radium-226 Silver-108m U 0 Thallium-208 Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 U C 05 0.00457 15.6 0.818.000242 0.302 1.000171 +/-0.0137 0.0115 +/-0.0137 KSDI 02/03/07 1025 606155 2 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 61 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-012F Project: YANK01204 Sample ID: 179836014 Client ID: YANKOOI Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 80 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 80 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.62 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd Contact: Project: East Hampton, Connecticut 06424 Mr. Jack McCarthy Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-013F 179836015 TS 23-JAN-07 30-JAN-07 Client 11%Proiect: Client ID: Vol. Recv.: YANKO 1204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 1.21 +/-0.163 Americium-241 U 0.061 +/-0.0497 Bismuth-212 0.767 +/-0.212 Bismuth-214 1.03 +/-0.113 Cesium-134 UI 0.00 +/-0.0253 Cesium-137 0.0754 +/-0.0217 Cobalt-60 U 0.014 +/-0.0161 Europium-1 52 U -0.00491 +/-0.0494 Europium-154 U 0.00029 +/-0.0503 Europium-155 U 0.0536 +/-0.0471 Lead-212 1.12 +/-0.0956 Lead-214 1.16 +/-0.116 Manganese-54 U 0.0204 +/-0.0213 Niobium-94 U -0.00307 +/-0.0162 Potassium-40 16.1 +/-1.16 Radium-226 1.03 +/-0.113 Silver-108m U 0.00267 +/-0.0192 Thallium-208 0.351 +/-0.0412 Rad Gas Flow Proportional Counting 0.0441 0.0414 0.114 0.0247 0.0175 0.0126 0.0139 0.0358 0.0377 0.0386 0.0209 0.0253 0.0126 0.0124 0.101 0.0247 0.0122 0.0124+/-0.163+/-0.0497+/-0.212+/-0.113+/-0.0253+/-0.0217+/-0.0161+/-0.0494+/-0.0503+/-0.0471+/-0.0956+/-0.116+/-0.0213+/-0.0162+/-1.16+/-0.113+/-0.0192+/-0.0412 0.0882 0.0826 0.227 0.0494 0.035 0.0252 0.0278 0.0716 0.0753 0.0772 0.0418 0.0505 0.0252 0.0247 0.202 0.0494 0.0243 0.0249 0.020 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/03/07 1351 606828 1 GFPC, Sr90, solid-ALL FSS Strontium-90 U 0.0136 +/-0.0123 0.00871 +/-0.0123 KSD1 02/03/07 1025 606155 2 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 63 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-013F Proiect: YANK01204 Sample ID: 179836015 ClientID:

YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 98 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 98 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.64 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 5, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:

Moisture: 9312-0007-015F 179836016 TS 23-JAN-07 30-JAN-07 Client 11.9%Proiect: Client ID: Vol. Recv.: YANKO1204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.714 Americium-241 U 0.0315 Bismuth-212 0.638 Bismuth-214 0.692 Cesium-134 UI 0.00 Cesium-137 0.0877 Cobalt-60 U 0.0315 Europium-152 U -0.0149 Europium-154 U 0.0136 Europium-155 U 0.0413 Lead-212 0.866 Lead-214 0.612 Manganese-54 U 0.0131 Niobium-94 U 0.0175 Potassium-40 13.2 Radium-226 0.692 Silver-108m U -0.00232 Thallium-208 0.301 Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 U 0.0146+/-0.140+/-0.024+/-0.207+/-0.0949+/-0.0278+/-0.0304+/-0.0356+/-0.0482+/-0.0624+/-0.0452+/-0.0858+/-0.0779+/-0.0242+/-0.0168+/-0.827+/-0.0949+/-0.0142+/-0.0429 0.059 0.0197 0.110 0.0264 0.0185 0.0151 0.0164 0.0341 0.053 0.0305 0.0178 0.0247 0.0155 0.0135 0.130 0.0264 0.0123 0.014+/-0.140+/-0.024+/-0.207+/-0.0949+/-0.0278+/-0.0304+/-0.0356+/-0.0482+/-0.0624+/-0.0452+/-0.0858+/-0.0779+/-0.0242+/-0.0168+/-0.827+/-0.0949+/-0.0142+/-0.0429 0.118 0.0395 0.219 0.0527 0.037 0.0303 0.0327 0.0682 0.106 0.0609 0.0356 0.0494 0.0309 0.0269 0.260 0.0527 0.0245 0.0279 0.028 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/03/07 1351 606828 I+/-0.0167 0.0123 +/-0.0167 KSDI 02/03/07 1025 606155 2 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 01/30/07 1112 606001 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 65 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 5, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0007-015F Project: YANK01204 Sample ID: 179836016 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Surrogate/Tracer recovery Test Recovery%

Acceptable Limits Strontium-90 GFPC, Sr9O, solid-ALL FSS 80 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr9O, solid-ALL FSS 80 (25%-125%)

Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.66 I. .I QUALITY CONTROL DATA 67 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Client: Connecticut Yankee Atomic Power 362 Injun Hollow Rd Reoort Date: February 5, 2007 Page 1 of 9 East Hampton, Connecticut Contact: Mr. Jack McCarthy Workorder:

179836 Parmname NOM Sample Qual QC Units RPD%REC% Range Anlst Date Time Rad Alpha Spec Batch 606029 QC1201269931 Americium-241 Curium-242 Curium-243/244 QC1201269933 Americium-241 Curium-242 Curium-243/244 QC 1201269930 Americium-241 179836001 DUP U 0.0303 Uncert: +/-0.158 TPU: +/-0.158 U -0.0361 Uncert: +/-0.0751 TPU: +/-0.0752 U -0.0502 Uncert: +/-0.164 TPU: +/-0.164 LCS MB 13.0 Uncert: TPU: Uncert: TPU: 15.6 Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: U -0.0117+/-0.0702+/-0.0702 U 0.00126+/-0.0685+/-0.0685 U 0.125+/-0.165+/-0.165 12.7+/-1.17+/-2.02 U -0.0203+/-0.023+/-0.0231 14.8+/-1.26+/-2.30 U 0.0301+/-0.058+/-0.0582 U -0.00707+/-0.0594+/-0.0594 U 0.103+/-0.116+/-0.117 pCi/g 452 pCi/g 214 pCi/g 468 Curium-242 Curium-243/244 QC1201269932 179836001 MS Americium-241 pCi/g pCi/g pCi/g pCi/g pCi/g-pCi/g pCi/g pCi/g-pCi/g 95 (75%-125%)

(0% -100%) DXH2 02/01/07 07:43 (0%- 100%)(0%- 100%)98 (75%-125%)

Curium-242 14.0 Uncert: TPU Uncert: TPU 16.8 Uncert: TPU U 0.0303+/-0.158+/-0.158 U -0.0361+/-0.0751+/-0.0752 U -0.0502+/-0.164+/-0.164 U 13.0+/-1.35+/-2.22 0.0316+/-0.138+/-0.138 17.9+/-1.59+/-2.90 93 (75%-125%)

Curium-243/244 107 (75%-125%)

Batch 606031 QC1201269936 179836001 DUP Plutonium-238 U 0.0727 U 0.130 pCi/g 57 (0% -100%) DXH2 01/31/07 15:54 68 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:

179836 Page 2 of 9 Parmname Rad Alpha Spec Batch 606031 Plutonium-239/240 QC1201269938 LCS Plutonium-238 Plutonium-239/240 QC1201269935 MB Plutonium-238 Plutonium-239/240 NOM Sample Qual OC Units RPD% REC% Range Anist Date Time Uncert: +/-0.0998 TPU: +/-0.100 U 0.00 Uncert: +/-0.0566 TPU: +/-0.0566 U+/-0.196+/-0.197-0.0516+/-0.0413+/-0.0418 pCi/g 200 (0% -100%)(75%-125%)

Uncert: TPU: 12.9 Uncert: TPU: Uncert: TPU: Uncert: TPU: U 0.0519+/-0.226+/-0.226 12.7+/-1.25+/-1.95 U 0.0132+/-0.143+/-0.143 U -0.0224+/-0.0767+/-0.0767 pCi/g-Pci/g pCi/g Pci/g PCi/g pCi/g 98 (75%-125%)

QC1201269937 179836001 MS Plutoniurn-238 Plutonium-239/240 U 0.0727 Uncert: +/-0.0998 TPU: +/-0.100 13.9 U 0.00 Uncert: +/-0.0566 TPU: +/-0.0566 U -3.0 Uncert: +/-6.37 TPU: +/-6.37 U-0.014+/-0.0723+/-0.0723 13.5+/-1.29+/-2.03 97 (75%-125%)

(75%- 125%)Batch 606032 QC1201269940 179836001 DUP Plutonium-241 U-3.33+/-7.09+/-7.09 pCi/g 0 (0% -100%) DXH2 QC1201269942 LCS Plutonium-241 QC1201269939 MB Plutonium-241 140 Uncert: TPU: Uncert: TPU: 142 U Uncert: TPU: 108+/-11.6+/-15.7 U -3.23+/-6.45+/-6.45 138+/-13.9+/-19.8 pCi/g Pci/g pCi/g-77 (75%-125%)

02/02/07 08:14 02/01/07 11:12 02/01/07 10:24 02/01/07 10:56 QC1201269941 179836001 MS Plutonium-241 Rad Gamma Spec Batch 606828 QC1201271728 179836001 DUP Actinium-228

-3.0+/-6.37+/-6.37 97 (75%-125%)

1.23+/-0.169 Uncert: 1.05+/-0.171+/-0.171 pCi/g 16 (0%- 100%) MJHI 02/03/07 14:21 69 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:

179836 Page 3 of 9 QC Units RPD% REC% Range Anlst Date Time Parmname NOM Sample Qual Rad Gamma Spec Batch 606828 Americium-241 Bismuth-212 Bismuth-214 Cesium- 134 Cesium- 137 Cobalt-60 Europium-152 Europium-154 Europium-155 TPU: +/-0.169 U 0.0388 U 0.0232 Uncert: +/-0.0604

+/-0.0848 TPU: +/-0.0604

+/-0.0848 0.719 0.596 Uncert: +/-0.191 +/-0.164 TPU: +/-0.191 +/-0.164 0.701 0.620 Uncert: +/-0.0804

+/-0.0835 TPU: +/-0.0804

+/-0.0835 UI 0.00 UT 0.00 Uncert: +/-0.0254

+/-0.0289 TPU: +/-0.0254

+/-0.0289 U 0.00716 U 0.00661 Uncert: +/-0.0136

+/-0.0173 TPU: +/-0.0136

+/-0.0173 U 0.000511 U -0.0118 Uncert: +/-0.0148

+/-0.0157 TPU: +/-0.0148

+/-0.0157 U -0.0201 U -0.00777 Uncert: +/-0.049 +/-0.0447 TPU: +/-0.049 +/-0.0447 U 0.0172 U 0.0117 Uncert: +/-0.050 +/-0.0491 TPU: +/-0.050 +/-0.0491 U 0.049 U 0.0383 Uncert: +/-0.0469

+/-0.0524 TPU: +/-0.0469

+/-0.0524 1.04 0.988 Uncert: +/-0.0944

+/-0.087 TPU: +/-0.0944

+/-0.087 0.742 0.749 Uncert: +/-0.0852

+/-0.0829 TPU: +/-0.0852

+/-0.0829 U 0.00648 U 0.0136 Uncert: +/-0.019 +/-0.0164 TPU: +/-0.019 +/-0.0164 U 0.0138 U 0.00545 Uncert: +/-0.0126

+/-0.0139 TPU: +/-0.0126

+/-0.0139 16.8 16.8 Uncert: +/-1.18 +/-1.28 TPU: +/-1.18 +/-1.28 0.701 0.620 Uncert: +/-0.0804

+/-0.0835 TPU: +/-0.0804

+/-0.0835 U -0.0161 U -0.0109 Uncert: +/-0.0125

+/-0.015 pCi/g 50 pCi/g 19 pCi/g 12 pCi/g 53 pCi/g 8 pCi/g 218 pCig 89 pCi/g 38 pCi/g 25 pCi/g 5 pCi/g I pCi/g 71 pCi/g 87 pCi/g 0 pCi/g 12 pCi/g 39 (0%- 100%)(0%- 100%)(0%- 100%)(0%- 100%)(0%- 100%)(0%- 100%)(0% -100%)(0%- 100%)(0%- 100%)(0% -20%)(0% -20%)(0%- 100%)(0%- 100%)(0%- 20%)(0%- 100%)(0%- 100%)Lead-212 Lead-214 Manganese-54 Niobium-94 Potassium-40 Radium-226 Silver- 108m 70 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:

179836 Parmname Rad Gamma Spec Batch 606828 Page 4 of 9 REC% Range AnIst Date Time NOM Sample Qual QC Units RPD%Thallium-208 QC 1201271729 Actinium-228 Americium-241 Bismuth-212 TPU: +/-0.0125 0.321 Uncert: +/-0.0386 TPU: +/-0.0386+/-0.015 0.306+/-0.0408+/-0.0408 pCi/g 5 (0%- 100%)LCS Bismuth-214 Cesium- 134 Cesium- 137 Cobalt-60 Europium-152 Europium-154 Europium-155 Uncert: TPU: 23.4 Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: 9.48 Uncert: TPU: 13.7 Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: U 0.442+/-0.604+/-0.00 26.2+/-3.48+/-0.00 U -0.0757+/-1.16+/-0.00 U -0.184+/-0.226+/-0.00 U -0.0238+/-0.158+/-0.00 10.2+/-0.786+/-0.00 15.7+/-1.24+/-0.00 U 0.116+/-0.310+/-0.00 U 0.134+/-0.315+/-0.00 U 0.245+/-0.325+/-0.00 U -0.0391+/-0.198+/-0.00 U 0.277+/-0.223+/-0.00 U 0.0761+/-0.212+/-0.00 U 0.0951+/-0.113+/-0.00 U -0.159 pci/g pCilg pCilg pCi/g pCilg pCilg pCi/g pCilg pCilg pCilg pCi/g pCilg pCilg-pCilg pcilg 108 (75%-125%)

114 (75%-125%)

112 (75%-125%)

02/05/07 07:45 Lead-212 Lead-214 Manganese-54 Niobium-94 Potassium-40 71 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:

179836 Parmname Rad Gamma Spec Batch 606828 Page 5 of 9 QC Units RPD% REC% Range AnIst Date Time NOM Sample Oual..... F---Radium-226 Silver- 108m Thallium-208 QCI1201271727 Actinium-228 Americium-241 Bismuth-212 Bismuth-214 Cesium-134 Cesium- 137 Cobalt-60 Europium-152 MB Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU:+/-0.961+/-0.00 U -0.184+/-0.226+/-0.00 U 0.107+/-0.122+/-0.00 U 0.027+/-0.120+/-0.00 U 0.00519+/-0.0433+/-0.0433 U -0.111+/-0.0244+1-0.0244 U -0.0102+/-0.0665+/-0.0665 U 0.0186+/-0.0263+/-0.0263 U 0.00816+/-0.00603

+/-0.00603 U 0.00131+/-0.00557

+/-0.00557 U 0.00242+/-0.00675

+/-0.00675 U -0.00564+/-0.0169+/-0.0169 U -0.0192+/-0.0158+/-0.0158 U 0.00133+/-0.0175+/-0.0175 U -0.0118+/-0.0156+/-0.0156 U 0.00362+/-0.0215+/-0.0215 pcilg pcilg pCilg pCilg pCilg pCilg pcilg pCilg pCilg pCilg pCilg pCilg-pCi/g PCilg pcilg (75%-125%)

02/03/07 13:52 Europium-154 Europium-155 Lead-212 Lead-214 72 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:

179836 Page 6 of 9 Parmname Rad Gamma Spec Batch 606828 Manganese-54 NOM Sample Qual OC Units RPD%REC% Ranue Anist Date Time Niobium-94 Potassium-40 Radium-226 Silver- 108m Thallium-208 Rad Gas Flow Batch Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: U 0.000195+/-0.0057+/-0.0057 U -0.00422+/-0.00717

+/-0.00717 UI 0.00+/-0.139+/-0.139 U 0.0186+/-0.0263+/-0.0263 U -0.00139+/-0.00535

+/-0.00535 UI 0.00+/-0.0116+/-0.0116 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 606155 QC1201270172 Strontium-90 179836001 DUP U 0.00439 Uncert: +/-0.0156 TPU: +/-0.0156 QC1201270174 LCS Strontium-90 QC1201270171 MB Strontium-90 QC1201270173 179836001 MS Strontium-90 Rad Liquid Scintillation Batch 606162 QC1201270180 179836001 DUP Technetium-99 QC1201270182 LCS Technetium-99 QC1201270179 MB Technetium-99 0.0411+/-0.0216+/-0.0217 1.34+/-0.100+/-0.108 pCi/g 161 (0% -100%) KSDI 1.46 Uncert: TPU: Uncert: TPU: 3.20 U Uncert: TPU: U -0.00686+/-0.0108+/-0.0108 pCi/g pCi/g pCi/g 92 (75%-125%)

02/03/07 10:25 02/03/07 10:25 02/03/07 10:25 02/03/07 10:25 0.00439+/-0.0156+/-0.0156 3.18+/-0.206+/-0.227 100 (75%-125%)

U -0.157 Uncert: +/-0.168 TPU: +/-0.168 U-0.0277+/-0.173+/-0.173 13.0+/-0.533+/-0.622 pCi/g 0 (0% -100%) KXRI 13.1 Uncert: TPU: pCi/g 99 (75%-125%)

02/04/07 23:28 02/05/07 00:03 02/04/07 23:11 U 0.158 pCi/g 73 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:

179836 Parmname Rad Liquid Scintillation Batch 606162 Page 7 of 9 QC Units RPD% REC% Range Anist Date Time NOM Sample Qual QC1201270181 179836001 MS Technetium-99 Uncert: TPU: 12.5 U Uncert: TPU:+/-0.165+/-0.165 11.0+/-0.498+/-0.568-0.157+/-0.168+/-0.168 pCilg 88 (75%-125%)

02/04/07 23:46 Batch 606163 QC1201270184 179836001 DUP Nickel-63 QC1201270186 LCS Nickel-63 QC1201270183 MB Nickel-63 QC0201270185 179836001 MS Nickel-63 U -9.21 Uncert: +/-11.8 TPU: +/-11.8 U 5.27+/-10.9+/-10.9 pCi/g 0 (0% -100%) MXPI 563 Uncert: TPU: Uncert: TPU: 567 U Uncert: TPU: 508+/-21.7+/-28.4 U -3.09+/-10.3+/-10.3 pCi/g pCi/g pCi/g 90 (75%-125%)

02/01/07 16:26 02/01/07 16:59 02/01/07 16:10 02/01/07 16:43-9.21+/- 11.8+/-11.8 554+/-29.4+/-35.6 98 (75%-125%)

Batch 606165 QC1201270188 179836001 DUP Iron-55 U 19.0 Uncert: +/-62.6 TPU: +/-62.6 U 18.9+/-69.3+/-69.3 pCi/g 0 (0% -100%) VIXPI QC1201270190 LCS Iron-55 QC1201270187 MB Iron-55 1190 Uncert: TPU: Uncert: TPU: 1200 U Uncert: TPU: 1150+/-92.4+/-113 U 18.3+/-53.3+/-53.3 pCi/g pCi/g pCi/g 96 (75%-125%)

02/03/07 11:33 02/03/07 11:50 02/03/07 11:01 02/03/07 11:17 QC1201270189 179836001 MS Iron-55 19.0+/-62.6+/-62.6 1160+/-90.9+/-111 96 (75%-125%)

Batch 606166 QC1201270192 179836001 DUP Carbon- 14 QC1201270194 LCS Carbon- 14 U -0.0109 Uncert: +/-0.0671 TPU: +/-0.0671 U-0.0517+/-0.0701+/-0.0701 6.54+/-0.434+/-0.446 pCi/g 0 (0% -100%) %XD2 01/31/07 21:13 6.65 Uncert: TPU: pCi/g 98 (75%-125%)

01/31/07 22:33 74 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:

179836 Page 8 of 9 Parmname Rad Liquid Scintillation Batch 606166 QC1201270191 MB Carbon- 14 NOM Sample Qua] QC Units RPD% REC% Range Anist Date Time Uncert: TPU: U -0.0597+/-0.0694+/-0.0694 pCilg pCi/g 01/31/07 20:10 01/31/07 22:15 QC1201270193 179836001 MS Carbon- 14 7.19 U Uncert: TPU:-0.0109+/-0.0671+/-0.0671 Batch 606167 QC1201270196 179837001 DUP Tritium QC1201270198 LCS Tritium QC1201270195 MB Tritium QC1201270197 179837001 MS Tritium U 0.452 Uncert: +/-0.306 TPU: +/-0.306 U 6.92+/-0.479+/-0.491 0.369+/-0.341+/-0.341 6.14+/-0.510+/-0.513 96 (75%-125%)

pCi/g 0 (0% -100%) 'XD2 6.39 Uncert: TPU: Uncert: TPU: 6.48 U Uncert: TPU: U 0.0228+/-0.133+/-0.133 pCi/g pCi/g pCi/g 96 (75%-125%)

02/01/07 04:13 02/01/07 05:03 02/01/07 03:40 02/01/07 04:46 0.452+/-0.306+/-0.306 5.16+/-0.813+/-0.814 80 (75%-125%)

Notes: The Qualifiers in this report are defined as follows:*A B BD C D H J N/A ND R U UI A quality control analyte recovery is outside of specified acceptance criteria Analyte is a surrogate compound Result is less than value reported Result is greater than value reported The TIC is a suspected aldol-condensation product For General Chemistry and Organic analysis the target analyte was detected in the associated blank.Results are either below the MDC or tracer recovery is low Analyte has been confirmed by GC/MS analysis Results are reported from a diluted aliquot of the sample Analytical holding time was exceeded Value is estimated Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more Analyte concentration is not detected above the detection limit Sample results are rejected Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.Gamma Spectroscopy--Uncertain identification Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier 75 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:

179836 Page 9 of 9 Parmname NOM Sample Qual QC Units RPD% REC% Range AnIst Date Time X Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded N/A indicates that spike recovery limits do not apply when sample concentration exceeds spike conc. by a factor of 4 or more.** Indicates analyte is a surrogate compound.A The Relative Percent Difference (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptence criteria when the sample is greater than five times (5X) the contract required detection limit (RL). In cases where either the sample or duplicate value is less than 5X the RL, a control limit of +/- the RL is used to evaluate the DUP result.For PS, PSD, and SDILT results, the values listed are the measured amounts, not final concentrations.

Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the QC Summary.76 SOUTHWEST SITE STORAGE AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD ATTACHMENT 4 (DQA RESULTS)Revision 0 SOUTHWEST SITE STORAGE AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD ATTACHMENT 4A (PRELIMINARY DATA REVIEW)Revision 0 Health Physics Procedure GPP-GGGR-R5121-001 Attachment B, Rev. CY-001 MAJOR Preliminary Data Review Form -Samples for the Sign Test Survey Unit: 9312- 0007 Survey Unit Name: Radiologically Controlled Area/ RRF Bldg./1 15kV East Footprint Classification:

1 Survey Media: Soil Type of Survey: Final Status Survey Type of Measurement:

Gross Measurement Number of Measurements:

15 Operational DCGL: 1 BASIC STATISTICAL QUANTITIES Cs-137 Sr-90 Minimum Value: -1.07E-02

-7.12E-03 Maximum Value: 8.94E-02 1.46E-02 Mean: 2.22E-02 5.26E-03 Median: 1.01E-02 4.24E-03 Standard Deviation:

3.38E-02 6.73E-03 RADIONUCLIDE CONCENTRATION (pCi/g)NUMBER Cs-137 Sr-90 Identified?

Identified?

9312-0007-OOIF

-3.33E-03

-7.12E-03 N N 9312-0007-002F 7.16E-03 4.39E-03 N N 9312-0007-003F 2.04E-02 8.79E-03 Y N 9312-0007-004F

-2.83E-04 1.94E-03 N N 9312-0007-005F 8-94E-02 4.24E-03 Y N 9312-0007-006F 2.49E-03 1.25E-02 N N 9312-0007-007F 0.OOE+00 1.43E-03 N N 9312-0007-008F 1.26E-02 2.36E-03 N N 9312-0007-009F 1.51 E-02 -2.61E-03 N N 9312-0007-OIOF 3.1OE-02 -2.13E-04 Y N 9312-0007-01 1F -1.07E-02 1.38E-02 N N 9312-0007-012F

-3.70E-03 1.71E-04 N N 9312-0007-013F 7.54E-02 1.36E-02 Y Y 9312-0007-014F 1.01E-02 1.1OE-02 N N 9312-0007-015F 8.77E-02 1.46E-02 Y N Performed By: lI2,I Date: _-____-0 _Independent Review: / Date: 7u- 2 O,-U1 SOUTHWEST SITE STORAGE AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD ATTACHMENT 4B (GRAPHICAL REPRESENTATION OF DATA)Revision 0 Health Physics Procedurc (jGGR-R5123-Rev.CY-001 Attachi-nent C Quantile Plot For Cesium -137 Survey Unit: 9312-0007 Survey Unit Name: Radiologically Controlled Area/ RRF Bldg./ 115kV Fast Footprint Mean: 2.22F-02 pCi/g C.)0.0 (U C 0 0 1.OOE-01 8.OOE-02 6.00E-02 4.00E-02 2.00E-02 O.OOE+O0-2.OOE-02 4 *--m ----------4 4 80 14 20 40 60 Percentage Cs-1 37 Rank Percentage

-1.07E-02 1 3 %-370E-03 2 10 %-3.33E-03 3 17 %-2.83E-04

.4 23 %0.0E+00 5 30 %2.49E-03 6 37 %7.16E-03 7 43 %1,01E-02 8 50 %1-26E-02 9 57 %1.51 E-02 10 63 %2.04E-02 11 70 %3.1OE-02 12 77 %7.54E-02 13 83 %8-77E-02 14 90 %8.94E-02 15 97 %Prepared By: Reviewed By: f/,, /Date: Date: J~f tHealth Physics Procedure (;GGIZ-R5123-Rev.CY-001 Attachment C Quantile Plot For Strontium

-90 Survey Unit: 9312-0007 Survey Unit Name: Discharge Canal Mean: 5.26L-03 pCi/g CO, 0.0 C.2.O0E-02 1.50E-02 1.OOE-02 5.00E-03 O.OOE+00-5.OOE-03-1.OOE-02., P

20 40 60 80 1 $0 Percentage Sr-90 Rank Percentage

-7.12E-03 1 3 %-2.61E-03 2 10 %-2.14E-04 3 17 %1.71E-04 4 23 %1.43E-03 5 30 %1.94E-03 6 37 %2 36E-03 7 43 %4.24E-03 8 50 %4.39E-03 9 57 %8.79E-03 10 63 %1 1OE-02 11 70 %125E-02 12 77 %1.36E-02 13 83 %1.38E-02 14 90 %1.46E-02 15 97 %Prepared By: Reviewed By: I, (I Date: Date:

I lealth Physics Procedure G(i(iR-R5123-Rev.(CY-001 Attachment C Frequency Plot For Cesium-137 Survey U Jnil: 9312-0007 Survey Unit Name: Radiologically Controlled Footprint Area/ RRF Blidg./i l5kV Fast Mean: 0.022 pCi/g 0)0*4)LL.6 5 4 3 2 1 0 0.00 0.02 0.04 0.06 0.08 0.10 Upper End Value (pCilg)Upper End Value 0.00 002 0.04 0.06 0.08 0.10 Total Observation Frequency 5 5 2 0 1 2 Observation

%Frequency 33%33%13%0%7%13%15 100%Prepared By:.1/<,. ?_Date: j 2ý S , /Reviewed By: Date:

I fealth Physics ProcedUre GGGR-R5 123-Rev.CY-001 Attachment C Frequency Plot For Strontium

-90 Survey Unit: 9312-0007 Survey Unit Name: Radiologically Controlled Area/ RRF Bldg./ II 5kV East Footprint Mean: 5.26E-03 pCi/g C., 4)0*L.7 6 5 4 3 2 1 0 i 0.000 0.005 0.010 0.015 0.020 Upper End Value (pCilg)Upper End Observation Observation

%Value Frequency Frequency 0.000 -3 20%0.005 6 40%0.010 1 7%0.015 5 33%0.020 0 0%Total 15 100%Prepared By: I D~ate: D~ate: Revewd y:L Reviewed By:./

SOUTHWEST SITE STORAGE AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD ATTACHMENT 4C (SIGN TEST)Revision 0 Health Physics Procedure GPP-GGGR-R5121-000 Attachment A, Rev. CY-001 MAJOR Sign Test Calculation Sheet For Multiple Radionuelisdes Survey Unit Number: 9312-0007 Survey Unit Name: Radiologically Controlled Area/ RRF Bldg./1 15kV East Footprint Classification:

I TYPE I (a error):0.05 TYPE I (13 error):0.051 Radionuclides:

Cs-137 Sr-90 Survey Design DCGL (pCi/g): 4.75 0.93 Results Cs-137 Results Sr-90 Weighted Sum (W,) DCGL-Result Sign-3.33E-03

-7.12E-03

-8.36E-03 1.01E+00 1 7.16E-03 4.39E-03 6.23E-03 9.94E-01 1 2.04E-02 8.79E-03 1.37E-02 9.86E-01 1-2.83E-04 1.94E-03 2.03E-03 9.98E-01 1 8.94E-02 4.24E-03 2.34E-02 9.77E-01 1 2.49E-03 1.25E-02 1.40E-02 9.86E-01 1 0.OOE+00 1.43E-03 1.54E-03 9.98E-01 1 1.26E-02 2.36E-03 5.19E-03 9.95E-01 1 1.51E-02 -2.61E-03 3.72E-04 1.OOE+00 1 3.1OE-02 -2.13E-04 6.30E-03 9.94E-01 1-1.07E-02 1.38E-02 1.26E-02 9.87E-01 1-3.70E-03 1.71E-04 -5.95E-04 1.OOE+00 I 7.54E-02 1.36E-02 3.05E-02 9.70E-01 I 1.01E-02 1.10E-02 1.40E-02 9.86E-01 1 8.77E-02 1.46E-02 3.42E-02 9.66E-01 1 Number of Positive Differences (S+): 15 Critical Value: 11 Survey Unit: Meets Acceptance Criterion PerformedBy:

Date:_______

Independent Review: Date: Page 1 of 1 SOUTHWEST SITE STORAGE AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD ATTACHMENT 4D (QC SPLIT RESULTS)Revision 0 Connecticut Yankee Decommissioning Project Health Physics Procedure 24265-000-GPR-GGGR-R5124-000 Attachment A Split Sample Assessment Form Sure Area SuIrvey 0007 Survey .Radiologically Controlled.Area/." RRF Bldg//115kV East:9312 Unit #: 0007 Unit Name: Footprint Sample Plan or WPIR#: 9312-0007 FSSP SML #: 9312-0007-003 Sample

Description:

Comparison of split samples collected from sample measurement location #3 and analyzed using gamma spectroscopy by an off-site vendor laboratory.

The standard sample was 9312-0007-003F the comparison sample was 9312-0007-003FS.

STANDARD COMPARISON Radionuclide Activity Standard Resolution Agreement Activity Standard Comparison Acceptable (Y/N)Value Error Range Value Error Ratio Cs-137 2.04E-02 6.25E-03 3 NONE- 1.91E-02 1.13E-02 0.94 N/A Co-60 4.25E-03 4.36E-03 1 NONE --1.04E-02 1.OOE-02 -2.45 N/A K-40 1.04E+01 3.51E-01 30 0.75- 1.33 1.07E+01 5.OOE-01 1.03 Y[ _________________

_______________

_________________

_______________

__________________

_____________

_______________

____________________j___

Comments/Corrective Actions: In consideration of the Cs-137 and Co-60 results, guidance for agreement ranges, obtained from USNRC Inspection Procedure 84750, does not address resolution ratios less than 4, therefore, a determination of acceptability for such rations cannot be made. Since K-40 was found to be present at an acceptable level of agreement, no further action is warranted.

Table is provided to show acceptance criteria used to assess split samples.Resolution Agreement Range 4 8 16 51 7 15 50 200> 200 0.50 0.60 0.75 0.80 0.85 2.00 1.66 1.33 1.25 1.18 Performed By: WPIR -Work Plan and Inspection Record SML -Sample Measurement Location designation Page I of I SOUTHWEST SITE STORAGE AREA /RRF BLDG. / 115KV EAST FOOTPRINT SURVEY UNIT 9312-0007 RELEASE RECORD ATTACHMENT 4E (COMPASS POWER CURVE)Revision 0 (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:==

9312-0007 Class1 DR /P RCA / RRF Bldg./ 115 kV East Footprint 1 15 0 Sign Test Result: Not Performed 0 EMC Resulti Not Performed Reject Null Hypothesis (Survey Unit PASSES)Retrospective Power Curve-- 0.9"" 0.80.7 0.6 0.3 04202 01'- 0 ZEEI -_i- I 0.0 0,2 04 0.6 0.8 1.0 Unity Rule Sum-of-Ratios, including background Prospective Power U 1 -beta .Actual Power LBGR --Estimated Power DCGL ---- Retrospective Power 12 COMPASS vI.0.0 3/2012007 Page I

ML071550108

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