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.CYAPCO FINAL STATUS SURVEY RELEASE RECORD SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 Prepared By: Reviewed Bv FSS Engineer J Date: ,L.,/co6 Datell/ZiJO(Date: 1 12(.,/.06 Approved By:_____________
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Technical Support Manager Revision 0 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD TABLE OF CONTENTS 1. SURVEY UNIT DESCRIPTION  
                                                                            **.......>
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3 2. CLA SSIFICATION BASIS ................................................................
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3 3. DATA QUALITY OBJECTIVES (DQO) .........................................
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5 4. SU RV EY D ESIG N .............................................................................
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8 5. SURVEY IM PLEM ENTATION ..........................................................
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11 6. SU RV EY RESU LTS ........................................................................
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12 7. Q UA LITY CON TRO L ......................................................................
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14 8. INVESTIGATIONS AND RESULTS .............................................
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14 9. REMEDIATION AND RESULTS ..................................................
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14 10. CHANGES FROM THE FINAL STATUS SURVEY PLAN ...... 14 11. DATA QUALITY ASSESSMENT (DQA) .......................................
 
14 12. A N O M A LIE S ..................................................................................
                        .CYAPCO FINAL STATUS SURVEY RELEASE RECORD SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 Prepared By:                           Date: ,L.,/co6 FSS Engineer    J Reviewed Bv                            Datell/ZiJO(
15 13. C O N C LU SIO N .................................................................................
Approved By:_____________              Date: 1 12(.,/.06 Technical Support Manager Revision 0
15 14. ATTACHMENTS  
 
........................................  
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD TABLE OF CONTENTS
... 16 14.1 Attachment 1 -Figures (4 pages including cover)14.2 Attachment 2 -Laboratory Data (137 pages including cover)14.3 Attachment 3 -DQA Results (16 pages including covers)TOTAL 173 Revision I SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD 1. SURVEY UNIT DESCRIPTION Survey Unit 9807-0000 (Subsurface Area associated with the Southwest Site Storage Area) is designated as Final Status Survey (FSS) Class B and consists of 1,983 m2 (0.5 acres) of uninhabited open land located approximately 1,860 feet from the reference coordinate system benchmark used at Haddam Neck Plant (HNP) (see Attachment 1). The surface area is bounded by Survey Unit 9520-0004.
: 1. SURVEY UNIT DESCRIPTION ......................................................                       3
The surface land unit that resides above this subsurface survey unit is relatively level open space of the peninsula.
: 2. CLA SSIFICATION BASIS ................................................................               3
The restoration of the peninsula for FSS has removed most of the surface interference in the survey unit.The reference coordinates associated with this survey unit are E007 through E0I10 by S089 through S093 (refer to 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 9807-0000 consisted of: a) A review of the 1OCFR50.75 (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 10CFR50.75(g)(1) database report and historical files shows a documented history of the Southwest Site Storage Area as a radioactive materials storage area. Examples of some of the major events are provided below.a) Plant Incident Report (PIR) 80-37 reported the discovery of three (3)discrete sources of elevated activity on the Southeast Site Storage area in March 1980, along with other areas around the site. The three (3)discrete sources were identified within adjacent Survey Units 9520-0001 and 9520-0002.
: 3. DATA QUALITY OBJECTIVES (DQO) .........................................                             5
The elevated areas were removed upon detection according to the .report.Revision 0 3 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000.RELEASE RECORD b) Health Physics surveys performed in 1983 and 1985 document the discovery of radioactive material (strainers, bolts, wood pallets, sections of pipe, etc.) on the peninsula.
: 4. SU RV EY D ESIG N .............................................................................     8
The 1985 survey documents the discovery of contaminated dirt under a pallet.c) Condition Report (CR) 05-0314: Documents the discovery of excavation spoils, intended for backfill, above the radiological criteria for use as backfill.
: 5. SURVEY IM PLEM ENTATION ..........................................................                 11
These spoils were likely located in Survey Units 9520-0003 and 9520-0004, based on a review of the documentation.
: 6. SU RV EY RESU LTS ........................................................................         12
According to the CR closure documentation, the affected spoils were removed and packaged for disposal.
: 7. Q UA LITY CON TRO L ......................................................................         14
Follow-up survey and sampling was performed and the results were below established action levels.A review of the "Initial and Supplemental Characterization Reports" as well as the previous "Classification Basis Summaries" was performed.
: 8. INVESTIGATIONS AND RESULTS .............................................                           14
Survey Unit 9807-0000 was originally part of subsurface Survey Unit 9805-0000, which was initially designated as Class C during the development of the LTP.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 (references 2-2 and 277 respectively).
: 9. REMEDIATION AND RESULTS ..................................................                             14
The second source document justified a Class C designation for those areas for which there was historical evidence of contamination above the Derived Concentration Guideline Levels (DCGLs -refer to Section 2 for definition and description of DCGL), but for which recent surveys had shown that decontamination efforts had occurred and that the radiological conditions were expected to be below the DCGLs. Additional justification for a Class C designation based on survey and sampling data was provided as another reference to the LTP by the "Haddam Neck Plant Historical Site Assessment Supplement".
: 10. CHANGES FROM THE FINAL STATUS SURVEY PLAN ......                                                     14
However, in March of 2006, Co-60 and Cs-137 were identified in subsurface soils in sufficient quantities to warrant radiological remediation.
: 11. DATA QUALITY ASSESSMENT (DQA) .......................................                               14
Radiological remediation was performed in July 2006. A new Class 1 survey unit, Survey Unit 9520-0004, and a new subsurface unit, Survey Unit 9807-0000, were established to bound the area of remediation.
: 12. AN O M A LIE S .................................................................................. 15
Remedial action was performed in July 2006. Although Co-60 has been identified in the past, Cs-137 was the only radionuclide with the potential to exceed the screening criteria following the remedial action. Statistical quantities (mean, median and standard deviation) from the 2006 remedial action survey are provided in Table 1.Revision 0 4 Revision 0 4 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD Minimum Observed Concentration (pCi/g): -1.79E-03 Maximum Observed Concentration (pCi/g): 2.24E-02 Mean (pCi/g): 6.84E-03 Median (pCi/g): 3.69E-03 Standard Deviation (pCi/g): 8.39E-03 The FSS Engineer performed a visual inspection and walk-down during September 2006 to assess the physical condition of the survey unit, evaluate access points, and travel paths and identify potentially hazardous conditions.
: 13. C ON CLU SIO N .................................................................................     15
: 14. ATTACHMENTS ........................................                                             ... 16 14.1 Attachment 1 - Figures (4 pages including cover) 14.2 Attachment 2 - Laboratory Data (137 pages including cover) 14.3 Attachment 3 - DQA Results (16 pages including covers)
TOTAL 173 Revision I
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD
: 1. SURVEY UNIT DESCRIPTION Survey Unit 9807-0000 (Subsurface Area associated with the Southwest Site Storage Area) is designated as Final Status Survey (FSS) Class B and consists of 1,983 m2 (0.5 acres) of uninhabited open land located approximately 1,860 feet from the reference coordinate system benchmark used at Haddam Neck Plant (HNP) (see Attachment 1). The surface area is bounded by Survey Unit 9520-0004. The surface land unit that resides above this subsurface survey unit is relatively level open space of the peninsula. The restoration of the peninsula for FSS has removed most of the surface interference in the survey unit.
The reference coordinates associated with this survey unit are E007 through E0I10 by S089 through S093 (refer to 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 9807-0000 consisted of:
a) A review of the 10CFR50.75 (g) (1) database, b) A review of the "InitialCharacterizationReport" and the "HistoricSite Assessment Supplement, "
c) Historic and current survey records review, d) Visual inspections and a "walkdown."
A review of the 10CFR50.75(g)(1) database report and historical files shows a documented history of the Southwest Site Storage Area as a radioactive materials storage area. Examples of some of the major events are provided below.
a) Plant Incident Report (PIR) 80-37 reported the discovery of three (3) discrete sources of elevated activity on the Southeast Site Storage area in March 1980, along with other areas around the site. The three (3) discrete sources were identified within adjacent Survey Units 9520-0001 and 9520-0002. The elevated areas were removed upon detection according to the .report.
Revision 0                                       3
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000
                          . RELEASE RECORD b) Health Physics surveys performed in 1983 and 1985 document the discovery of radioactive material (strainers, bolts, wood pallets, sections of pipe, etc.) on the peninsula. The 1985 survey documents the discovery of contaminated dirt under a pallet.
c) Condition Report (CR) 05-0314: Documents the discovery of excavation spoils, intended for backfill, above the radiological criteria for use as backfill. These spoils were likely located in Survey Units 9520-0003 and 9520-0004, based on a review of the documentation. According to the CR closure documentation, the affected spoils were removed and packaged for disposal. Follow-up survey and sampling was performed and the results were below established action levels.
A review of the "Initialand Supplemental CharacterizationReports" as well as the previous "Classification Basis Summaries" was performed. Survey Unit 9807-0000 was originally part of subsurface Survey Unit 9805-0000, which was initially designated as Class C during the development of the LTP.
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 (references 2-2 and 277 respectively). The second source document justified a Class C designation for those areas for which there was historical evidence of contamination above the Derived Concentration Guideline Levels (DCGLs -
refer to Section 2 for definition and description of DCGL), but for which recent surveys had shown that decontamination efforts had occurred and that the radiological conditions were expected to be below the DCGLs. Additional justification for a Class C designation based on survey and sampling data was provided as another reference to the LTP by the "Haddam Neck Plant HistoricalSite Assessment Supplement".
However, in March of 2006, Co-60 and Cs-137 were identified in subsurface soils in sufficient quantities to warrant radiological remediation. Radiological remediation was performed in July 2006. A new Class 1 survey unit, Survey Unit 9520-0004, and a new subsurface unit, Survey Unit 9807-0000, were established to bound the area of remediation.
Remedial action was performed in July 2006. Although Co-60 has been identified in the past, Cs-137 was the only radionuclide with the potential to exceed the screening criteria following the remedial action. Statistical quantities (mean, median and standard deviation) from the 2006 remedial action survey are provided in Table 1.
Revision 0                                       4 Revision 0                                       4
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD Minimum Observed Concentration (pCi/g):                   -1.79E-03 Maximum Observed Concentration (pCi/g):                   2.24E-02 Mean (pCi/g):                               6.84E-03 Median (pCi/g):                               3.69E-03 Standard Deviation (pCi/g):                       8.39E-03 The FSS Engineer performed a visual inspection and walk-down during September 2006 to assess the physical condition of the survey unit, evaluate access points, and travel paths and identify potentially hazardous conditions.
This survey area is affected by existing 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.
This survey area is affected by existing 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 results of radiological surveys performed over six years of restoration and the 2006 remedial action survey, it was concluded that there was a probability for residual radioactivity in concentrations less than the DCGLs, justifying a final survey unit classification of Class B (refer to Section 3). Note, due to the size of the survey unit, the sample to area frequency far exceeds the frequency requirement for Class A survey units of one sample every 500 m 2 as specified by LTP Section 5.7.3.2.2.
Based upon the results of radiological surveys performed over six years of restoration and the 2006 remedial action survey, it was concluded that there was a probability for residual radioactivity in concentrations less than the DCGLs, justifying a final survey unit classification of Class B (refer to Section 3). Note, due to the size of the survey unit, the sample to area frequency far exceeds the frequency requirement for Class A survey units of one sample every 500 m2 as specified by LTP Section 5.7.3.2.2.
: 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).
: 3. DATA QUALITY OBJECTIVES (DQO)
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.
FSS design and planning used the Data Quality Objective (DQO) process as described by the LTP, Procedure RPM 5.1-11, "Preparationof 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.
Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition.
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. Therefore, the survey unit does satisfy the primary objective of the FSS plan.
The baseline condition is technically known as the null hypothesis.
The primary objective of the FSS plan was to demonstrate that the level of residual radioactivity in Survey Unit 9807-0000 did not exceed the release Revision 0                                       5 Revision 0                                       5
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.
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD criteria specified in the LTP and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA).
Rejection of the null hypothesis would indicate that residual activity within the survey unit does not exceed the release criteria.
A fundamental precursor to survey design is to establish a relationship between the release criteria and some measurable quantity. This is done through the development of DCGLs. The DCGLs represent average levels of radioactivity above background levels and are presented in terms of surface or mass activity concentrations. Chapter 6 of the LTP describes in detail the modeling used to develop the DCGLs for soil (called Base Case Soil DCGL), existing groundwater radioactivity and future groundwater radioactivity that will be contributed by building basements and footings.
Therefore, the survey unit does satisfy the primary objective of the FSS plan.The primary objective of the FSS plan was to demonstrate that the level of residual radioactivity in Survey Unit 9807-0000 did not exceed the release Revision 0 5 Revision 0 5 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD 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.
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.
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.
Equation I HTotal =Hsoil +   HExistingGW+ HFutureGW The total dose under the LTP criteria is twenty-five (25) mrem/yr 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) mremryr 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.
Chapter 6 of the LTP describes in detail the modeling used to 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.
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.
Equation 1 shows the mathematical relationship between the three (3) components and the total dose.Equation I HTotal =Hsoil + HExistingGW  
This survey unit is not considered impacted by future groundwater radioactive contamination, as there are no buried concrete foundations or footings 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, therefore, zero (0) mrem/yr TEDE.
+ HFutureGW The total dose under the LTP criteria is twenty-five (25) mrem/yr TEDE from all three (3) components.
Equation 2 19 mrem/yrTotal = 17 mrem/yrsoil + 2 mrem/yrExisting   GW+ 0 mrem/yrFutureGw Revision 0                                     6
The allowable total dose under the Connecticut Department of Environmental Protection (CTDEP) radiological remediation standard for CY is nineteen (19) mremryr 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 not considered impacted by future groundwater radioactive contamination, as there are no buried concrete foundations or footings 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, therefore, zero (0) mrem/yr TEDE.Equation 2 19 mrem/yrTotal  
 
= 17 mrem/yrsoil  
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD The allowable dose for soil in this survey unit is seventeen (17) mrem/yr TEDE as shown by Equation 2 above. The concentration of residual radioactivity resulting in seventeen (17) mrem/yr TEDE is designated as the Operational DCGL, and has been established for the radionuclides of concern as provided in Table 2.
+ 2 mrem/yrExisting GW+ 0 mrem/yrFutureGw Revision 0 6 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD The allowable dose for soil in this survey unit is seventeen (17) mrem/yr TEDE as shown by Equation 2 above. The concentration of residual radioactivity resulting in seventeen (17) mrem/yr TEDE is designated as the Operational DCGL, and has been established for the radionuclides of concern as provided in Table 2.i-ti 16, H-3 4.12E+02 2.80E3+02 1.65E+01 C-14 5.66E+00 3.85E+00 2.26E-01 Mn-54 1.74E+01 1.18E+01 6.96E-01.Fe-55 2.74E+04 1.86E+04 1.1 OE+03 Co-60 3.81E+00 2.59E+00 1.52E-01 Ni-63 7.23E+02 4.92E+02 2.89E+01 Sr-90 1.55E+00 1.05E+00 6.20E-02 Nb-94 7.12E+00 4.84E+00 2.85E-01 Tc-99 1.26E+01 8.57E+00 5.04E-01 Ag-108mn 7.14E+00 4.86E+00 2.86E-01 Cs-134 4.67E+00 3.18E+00 1.87E-01 Cs-137 7.91E+00 5.38E+00 3.16E-01 Eu-152 1.01E+01 6.87E+00 4.04E-01 Eu-154 9.29E+00 6.32E+00 3.72E-01 Eu-155 3.92E+02 2.67E+02 1.57E+01 Pu-238 2.96E+01 2.01E+01 1.18E+00 Pu-239/240 2.67E+01 1.82E+01 1.07E+00 Pu-241 8.70E+02 5.92E+02 3.48E+01 Am-241 " 2.5 8E+O1 1.75E+01 1.03E+00 Cm-243/244 2.90E+O1 1.97E+01 1.16E+00 (1) Bold indicates those radionuclides considered to be Hard-to-Detect (HTD)(2) The Base Case Soil DCGLs for soil are specified by the LTP in Chapter 6 and are equivalent to 25 mrem/yr TEDE (3) The Operational DCGL is equivalent to 17 mrem/yr TEDE (4) The required MDC is equivalent to I 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 7 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD Another important facet of the DQO process is to identify the radionuclides of concern and determine the concentration variability.
iia.:"t**                    ,p_* i-ti
Soil samples were collected in 2006 during the remedial action survey. Cs-137 was the only gamma emitting radionuclide reported in concentrations with the potential for exceeding the screening criteria.
* 16, U.G?.4,,-z!*
The remedial action survey 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 would be the radionuclide of concern in Survey Unit 9807-0000 (refer to Section 3). Other radionuclides identified during this FSS would be evaluated to ensure adequate survey design.Surrogate DCGLs were not required for this survey unit via screening under LTP Section 5.4.7.2, "Gross Activity DCGLs". 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.
                                                                      * :.:*
The Elevated Measurement Comparison (EMC) did not apply to this survey unit since it is a Class B area and discrete, elevated areas of contamnination were not expected.The Sign Test was selected as the non-parametric statistical test. The use of the Sign Test did not require the selection or use of a background reference area, which simplified survey design and implementation.
H-3                     4.12E+02               2.80E3+02               1.65E+01 C-14                     5.66E+00               3.85E+00               2.26E-01 Mn-54                     1.74E+01               1.18E+01               6.96E-01
This approach was conservative since it included background Cs-137 as part of the sample set.Revision 0 8 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD The number of soil samples for FSS was determined in accordance with the LTP. The Lower Bound of the Gray Region (LBGR) was set in accordance with Procedure RPM 5.1-11 to 5.36 to maintain the relative shift (A/o) 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 (10 CFR 20, Subpart E). The result of the COMPASS computer run showed adequate power for the survey design.The survey design specified twenty-five (25) core soil samples for non-parametric statistical testing.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 f.or 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 B area.Judgmental sampling was not detennined to be necessary by the DQOs, based on the short distance between the area that was subjected to remedial action and FSS sample location 9807-0000-012F.
.         Fe-55                   2.74E+04               1.86E+04               1.1 OE+03 Co-60                   3.81E+00               2.59E+00                 1.52E-01 Ni-63                   7.23E+02             4.92E+02                 2.89E+01 Sr-90                   1.55E+00               1.05E+00               6.20E-02 Nb-94                     7.12E+00             4.84E+00                 2.85E-01 Tc-99                   1.26E+01               8.57E+00                 5.04E-01 Ag-108mn                   7.14E+00             4.86E+00                 2.86E-01 Cs-134                   4.67E+00               3.18E+00                 1.87E-01 Cs-137                   7.91E+00               5.38E+00               3.16E-01 Eu-152                   1.01E+01               6.87E+00               4.04E-01 Eu-154                   9.29E+00               6.32E+00               3.72E-01 Eu-155                   3.92E+02             2.67E+02                 1.57E+01 Pu-238                   2.96E+01             2.01E+01                 1.18E+00 Pu-239/240                 2.67E+01               1.82E+01               1.07E+00 Pu-241                   8.70E+02               5.92E+02               3.48E+01 Am-241 "                   2.5 8E+O1             1.75E+01               1.03E+00 Cm-243/244                   2.90E+O1               1.97E+01               1.16E+00 (1) Bold indicates those radionuclides considered to be Hard-to-Detect (HTD)
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 3.Tal 3-SmpeMasu  
(2) The Base Case Soil DCGLs for soil are specified by the LTP in Chapter 6 and are equivalent to 25 mrem/yr TEDE (3) The Operational DCGL is equivalent to 17 mrem/yr TEDE (4) The required MDC is equivalent to I 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                                           7
&#xfd;enehtjn t Loatonsi c~iit4d PS`Codiae Desi~giation2 Nlnhin'ies 9807-0000-001F 235632.88 669753.10 9807-0000-002F 23563,2.88 669784.48 9807-0000-003F 235632.88 669815.87 9807-0000-004F 235605.70 669737.40 9807-0000-005F 235605.70 669768.79 9807-0000-006F 235605.70 669800.18 9807-0000-007F 235605.70 669831.56 9807-0000-008F 235605.70 669862.95 9807-0000-009F 235578.52 669721.71 9807-0000-01 OF 235578.52 669753.10 9807-0000-01 IF 235578.52 669784.48 Revision 0 9 Revision 0 9 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD Table 0-02 235u5 6 58 9807-0000-012F 235578.52 669815.87 9807-0000-013F 235578.52 669847.25 9807-0000-014F 235578.52 669878.64 9807-0000-015F 235551.34 669737.40 9807-0000-016F 235551.34 669768.79 9807-0000-017F 235551.34 669800.18 9807-0000-018F 235551.34 669831.56 9807-0000-019F 235551.34 669862.95 9807-0000-020F 235551.34 669894.33 9807-0000-021F 235524.15 669784.48 9807-0000-022F 235524.1.5 669815.87 9807-0000-023F 235524.15 669847.25 9807-0000-024F 235524.15 669878.64 9807-0000-025F 235496.97 669862.95 Procedure RPM 5.1-11 specifies that 5% of the samples are required to be selected for HTD analysis.
 
Three (3) 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.
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 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 during the remedial action survey. Cs-137 was the only gamma emitting radionuclide reported in concentrations with the potential for exceeding the screening criteria. The remedial action survey data were used for the survey design and are provided in Table 1.
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 2.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 three (3) soil samples for "split sample" analysis by the off-site laboratory.
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.
These locations were selected randomly using the Microsoft Excel"RANDBETWEEN" function.
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.
The number of quality control soil samples was about 10% of twenty-five (25) samples.The LTP does not require scanning for elevated areas of radioactivity in subsurface survey units.For this Class B survey unit, the "Investigation Level" for soil sample measurement results are those levels specified in LTP, Table 5-8. Table 4 provides a synopsis of the survey design.Revision 0 10 Revision 0 10 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD~F~tiii j% -a BsisI.2.Survey Unit Land Area 1,983 m- Based on AutoCAD-LT 25 Number of Measurements (25 systematic grid) Based on LTP 5.7.3.2.2 0)Grid Spacing 9.6 m Based on triangular grid Administratively set to achieve Operational DCGL 5.3 8 pCi/g Cs-137 17 mrem/yr TEDE (2)The Operational DCGL meets Soil Investigation Level 5.38 pCi/g Cs-137 the LTP criteria for a Class B___ survey unit (1) Due to the size of the survey unit, the sample to area frequency far exceeds the frequency requirement for Class A survey units of one sample every 500 m 2 as specified by LTP Section 5.7.3.2.2 (2) The allowable dose for soil in this survey unit is 17 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 FSS field activities were conducted under Work Plan and Inspection Record (WP&IR) 2006-0038.
: 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 WP&IR package included a detailed FSS plan, job safety analysis, job planning checklist and related procedures for reference.
The DQO process determined that Cs-137 would be the radionuclide of concern in Survey Unit 9807-0000 (refer to Section 3). Other radionuclides identified during this FSS would be evaluated to ensure adequate survey design.
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.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.
Surrogate DCGLs were not required for this survey unit via screening under LTP Section 5.4.7.2, "Gross Activity DCGLs". 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.
Twenty-five (25) subsurface 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." Three (3) samples (9807-0000-003F, 9807-0000-008F and 9807-0000-013F) were randomly selected for HTD radionuclide analysis.The implementation of survey specific quality control measures included the collection of three (3) samples (9807-0000-012F, 9807-0000-018F and 9807-0000-024F) for "split sample" analysis.Revision 0 I1I Revision 0 11 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD 6. SURVEY RESULTS All field survey activities were conducted between September 13, 2006 and September 21, 2006.The off-site laboratory employed for the radiological analyses of samples was General Engineering Laboratories, LLC. The laboratory analyzed the twenty-five (25) samples collected for non-parametric statistical testing, and the associated field splits using gamma spectroscopy.
The Elevated Measurement Comparison (EMC) did not apply to this survey unit since it is a Class B area and discrete, elevated areas of contamnination were not expected.
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 standard deviations uncertainty).
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.
However, Cs-137 was the only radionuclide reported in concentrations exceeding the de-selection criteria.Cs-137 was identified in eight (8) of the twenty-five (25) samples collected for non-parametric statistical testing. Cs-137 was the primary radionuclide confirming the DQOs. The mean of the gamma spectroscopic analysis results for the sample population indicated that Cs-137 was present at levels lower than the concentrations of Cs-137 found in soil at off-site locations within the vicinity of the HNP as presented in the Health Physics TSD BCY-HP-0063.
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A summary of the twenty-five (25) samples collected for non-parametric statistical testing results is provided in Table 5.K: Table 5 Sumar of Soil ampl Results for the StatisticAl Sample Population Sampl Number =tCs-137" Fraction of the S a m le N u m b er ....< .. ., o .. , ..:. ....  
 
.... ......'=..,.. ..(pci/g) ..Op.erational DCGE.,L 9807-0000-001 F -7.91E-03 0.000 9807-0000-002F  
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD The number of soil samples for FSS was determined in accordance with the LTP. The Lower Bound of the Gray Region (LBGR) was set in accordance with Procedure RPM 5.1-11 to 5.36 to maintain the relative shift (A/o) 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 (10 CFR 20, Subpart E). The result of the COMPASS computer run showed adequate power for the survey design.
-2.76E-02 0.000 9807-0000-003F 4.02E-02 0.007 9807-0000-004F  
The survey design specified twenty-five (25) core soil samples for non-parametric statistical testing.
-1.26E-03 0.000 9807-0000-005F 1.87E-02 0.003 9807-0000-006F  
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 f.or 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 B area.
-8.34E-03 0.000 9807-0000-007F  
Judgmental sampling was not detennined to be necessary by the DQOs, based on the short distance between the area that was subjected to remedial action and FSS sample location 9807-0000-012F.
-1.54E-02 0.000 9807-0000-008F  
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 3.
-1.36E-02 0.000 9807-0000-009F 3.30E-02 0.006 9807-0000-01 OF 2.86E-02 0.005 9807-0000-01 IF -2.32E-02 0.000 9807-0000-012F 4.36E-02 0.008 9807-0000-013F  
Tal 3-SmpeMasu &#xfd;enehtjn Loatonsi  t           c~iit4d PS`Codiae Desi~giation2 Nlnhin'ies 9807-0000-001F               235632.88               669753.10 9807-0000-002F               23563,2.88             669784.48 9807-0000-003F               235632.88               669815.87 9807-0000-004F               235605.70               669737.40 9807-0000-005F               235605.70               669768.79 9807-0000-006F               235605.70               669800.18 9807-0000-007F               235605.70               669831.56 9807-0000-008F               235605.70               669862.95 9807-0000-009F               235578.52               669721.71 9807-0000-01 OF               235578.52               669753.10 9807-0000-01 IF               235578.52               669784.48 Revision 0                                     9 Revision 0                                     9
-2.5 1E-03 0.000 9807-0000-014F 8.18E-03 0.002 Revision I 12 Revision I 12 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD Summary ofSoil Sample .Resul ts for the Statistical
 
________________
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD Table 0-02                   235u5                   6   58 9807-0000-012F               235578.52               669815.87 9807-0000-013F               235578.52               669847.25 9807-0000-014F               235578.52               669878.64 9807-0000-015F               235551.34               669737.40 9807-0000-016F               235551.34               669768.79 9807-0000-017F               235551.34               669800.18 9807-0000-018F               235551.34               669831.56 9807-0000-019F               235551.34               669862.95 9807-0000-020F               235551.34               669894.33 9807-0000-021F               235524.15               669784.48 9807-0000-022F               235524.1.5             669815.87 9807-0000-023F               235524.15               669847.25 9807-0000-024F               235524.15               669878.64 9807-0000-025F               235496.97               669862.95 Procedure RPM 5.1-11 specifies that 5% of the samples are required to be selected for HTD analysis. Three (3) 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, "RadionuclidesPotentially Present at Haddam Neck Plant" and as provided in Table 2.
Population_
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 three (3) soil samples for "split sample" analysis by the off-site laboratory. These locations were selected randomly using the Microsoft Excel "RANDBETWEEN" function. The number of quality control soil samples was about 10% of twenty-five (25) samples.
_ _ _ _ _ _ _ _ _Sample Cs137 F, Fraction.of the.P....... .. ......,&#xfd; /g)' Operational DCGL." 9807-0000-015F 1.29E-02 0.002 9807-0000-016F 6.01E-03 0.001 9807-0000-017F 3.34E-02 0.006 9807-0000-018F 2.39E-03 0.000 9807-0000-019F  
The LTP does not require scanning for elevated areas of radioactivity in subsurface survey units.
-3.24E-04 0.000 9807-0000-020F 3.53E-02 0.007 9807-0000-021 F 0.OOE+00 0.000 9807-0000-022F 2.88E-02 0.005 9807-0000-023F 2.56E-02 0.005 9807-0000-024F 1.18E-02 0.002 9807-0000-025F 3.50E+00 0.651 (1) The Operational DCGL from Table 2 is 5.38 pCi/g for Cs-137 to achieve seventeen (17)mrem/yr TEDE The off-site laboratory also processed three (3) samples for HTD analysis as required by the sample plan. The requested analyses included alpha spectroscopy, gas proportional counting, and liquid scintillation depending on the radionuclide and the measurement method. All analyses met the required MDC.As previously stated in Section 4 of this report, the criteria for de-selection of a radionuclide is a concentration that is less than 5% of the Operational DCGL for individual radionuclides and less than 10% of the Operational DCGLs for aggregates.
For this Class B survey unit, the "Investigation Level" for soil sample measurement results are those levels specified in LTP, Table 5-8. Table 4 provides a synopsis of the survey design.
H-3 and Am-241 were the only HTDs identified above the accepted criteria for detection (i.e., a result greater than two standard deviations uncertainty).
Revision 0                                   10 Revision 0                                   10
The off-site laboratory prepared and reanalyzed two (2) of the three (3) original samples for H-3 at HNP's request; and performed H-3 analysis on five (5) other samples bordering the two (2) sample locations.
 
The results of all seven (7) samples were all less than the accepted criteria for detection.
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD
The highest result for Am-241 was about 4% of the Operational DCGL.__ _~.....fab  
                    ~F~tiii j%     -a                                             BsisI.2.
... le''"'8" -Hard-to-DetectSample.Ressu.is Sam.ple .Am-241 Fraction of Ope.atin.al  
Survey Unit Land Area                   1,983 m-               Based on AutoCAD-LT 25 Number of Measurements           (25 systematic grid)         Based on LTP 5.7.3.2.2 0)
.MDCGL 9807-0000-003F 7.13E-01 0.041 9807-0000-008F 5.32E-02 0.003 9807-0000-013F 9.35E-02 0.005 (I) The Operational DCGL from Table 2 is 17.5 pCi/g for Am-241 to achieve 17 mrem/yr TEDE Revision I.13 Revision I 13 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD 7. QUALITY CONTROL The off-site laboratory processed the split samples and performed gamma spectroscopy analysis.
Grid Spacing                       9.6 m               Based on triangular grid Administratively set to achieve Operational DCGL               5.3 8 pCi/g Cs-137             17 mrem/yr TEDE (2)
Ten percent (10%) of the samples were 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". Cs-137 was not detected in sufficient quantities in the field split results at the three (3) locations to evaluate in accordance with procedure.
The Operational DCGL meets Soil Investigation Level         5.38 pCi/g Cs-137         the LTP criteria for a Class B
Evaluation using the reported results for K-40 resulted in acceptable agreement between the field split results at these locations.
___                                  survey unit (1) Due to the size of the survey unit, the sample to area frequency far exceeds the frequency requirement for Class A survey units of one sample every 500 m2 as specified by LTP Section 5.7.3.2.2 (2)The allowable dose for soil in this survey unit is 17 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)
The sample analysis vendor, General Engineering Laboratories, LLC, maintains quality control and quality assurance plans as part of normal operation.
: 5. SURVEY IMPLEMENTATION FSS field activities were conducted under Work Plan and Inspection Record (WP&IR) 2006-0038. The WP&IR package included a detailed FSS plan, job safety analysis, job planning checklist and related procedures for reference.
Refer to Attachment 4 for data and data quality analysis results.8. INVESTIGATIONS AND RESULTS No investigations were performed.
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.
: 9. REMEDIATION AND RESULTS Remedial action was performed in July 2006. Although Co-60 has been identified in the past, Cs-137 was the only radionuclide with the potential to exceed the screening criteria following the remedial action. Health Physics TSD BCY-HP-0078, "ALARA Evaluation of Soil Remediation in Support of Final Status Survey, " has 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 No changes were made to the FSS plan.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.
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.
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.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 B.Revision 0 14 Revision 0 14 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD The preliminary data review consisted of calculating basic statistical quantities (e.g., mean, median, standard deviation).
Twenty-five (25) subsurface 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 Custodyfor FinalStatus Survey Samples."
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.For Cs-137, the range of the data, about five (5) standard deviations, indicated some variation, mainly as a result of one (1) sample that is higher in concentration than the rest of the data set. The difference between the mean and median was about 20% 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 significant positive skewness due to one (1) sample as confirmed by the calculated skew of 4.99.All data, assessments, and graphical representations are provided in Attachment 3.12. ANOMALIES No anomalies were noted.13. CONCLUSION Survey Unit 9807-0000 has met the final DQOs of the FSS plan. The ALARA criteria for soils as specified in Chapter 4 of the LTP were achieved.
Three (3) samples (9807-0000-003F, 9807-0000-008F and 9807-0000-013F) were randomly selected for HTD radionuclide analysis.
Elevated Measurement Comparison was not required.Cs-137 was 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 implementation of survey specific quality control measures included the collection of three (3) samples (9807-0000-012F, 9807-0000-018F and 9807-0000-024F) for "split sample" analysis.
The Retrospective Power Curve generated using COMPASS shows adequate power was achieved.
Revision 0                                               I1I Revision 0                                               11
The survey unit is properly designated as Class B.The dose contribution from soil is less than 1 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 not considered impacted by future groundwater radioactive contamination, as there are no underground structures, systems or components containing residual radioactive material within the groundwater saturated zone in the area (reference CY memo ISC 06-024); therefore, the dose contribution from future groundwater is zero (0) mrem/yr TEDE.Revision 0 15 Revision 0 15 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD 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.3 mrem/yr TEDE. Therefore, Survey Unit 9807-0000 is acceptable for unrestricted release.14. ATTACHMENTS 14.1 Attachment 1 -Figures 14.2 Attachment 2 -Laboratory Results 14.4 Attachment 3 -DQA Results Revision I 16 Revision 1 16 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 1 (FIGURES) j-CONNECT7CUT RIVER-r Connecticut Yankee Atomic Power Company Date By Figure 1 Site Map With Reference To Survey Unit 980 7-0000 November 2006 J I Q{-t-.-_ .7//4 7-//,6__/-I'a\/7-------Ill 1-2 17 i -L C,! / .14 (3 -7 I-L 19.,24 0 12.5 25 IFeet Legend A- 20/-/= Sample Point~1~ I 7---.4 ____--~23 9----22 Connecticut Yankee Atomic Power Company Survey Unit 9807-0000 Final Status Survey Design  
 
-0.01 0.01-0.02 Lqgend-0.03 0.-0.03 12.5 25 F.t-0.01-0.01-0.01 0.04.Notes Reported Concentrations in pCi/g 0.02 O0 0.01-0.02-0.01 0.03 0.03 0.03 0.03 0.01 0.03 0.0.1 Connecticut Yankee Atomic Power Company Survey Unit 9807-0000 Final Status Survey Cs-13 7 Posting Plot SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 2 (LABORATORY DATA)
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD
General Narrative 1 General Narrative for Connecticut Yankee Atomic Power Co.Work Order: 172275 SDG: MSR#06-1282 October 04, 2006 Laboratory Identification:
: 6. SURVEY RESULTS All field survey activities were conducted between September 13, 2006 and September 21, 2006.
General Engineering Laboratories, LLC 2040 Savage Road Charleston, South Carolina 29407 (843) 556-8171 Summary Sample receipt The samples arrived at General Engineering Laboratories, LLC, Charleston, South Carolina on September 21, 2006 for analysis.
The off-site laboratory employed for the radiological analyses of samples was General Engineering Laboratories, LLC. The laboratory analyzed the twenty-five (25) samples collected for non-parametric statistical testing, and 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 standard deviations uncertainty). However, Cs-137 was the only radionuclide reported in concentrations exceeding the de-selection criteria.
Shipping container temperatures were checked, documented, and within specifications.
Cs-137 was identified in eight (8) of the twenty-five (25) samples collected for non-parametric statistical testing.               Cs-137 was the primary radionuclide confirming the DQOs. The mean of the gamma spectroscopic analysis results for the sample population indicated that Cs-137 was present at levels lower than the concentrations of Cs-137 found in soil at off-site locations within the vicinity of the HNP as presented in the Health Physics TSD BCY-HP-0063.
The samples were delivered with proper chain of custody documentation and signatures.
A summary of the twenty-five (25) samples collected for non-parametric statistical testing results is provided in Table 5.
All sample containers arrived without any visible signs of tampering or breakage.Sample Identification The laboratory received the following samples: Laboratory Identification 172275001 172275002 172275003 172275004 172275005 172275006 172275007 172275008 172275009 172275010 172275011 Sample Description 9807-0000-001F 9807-0000-002F 9807-0000-003F 9807-0000-004F 9807-0000-005F 9807-0000-006F 9807-0000-007F 9807-0000-008F 9807-0000-009F 9807-0000-010F 9807-0000-01 iF 2.
K: Table 5 Sumar of Soil ampl Results for the StatisticAl Sample Population Sampl     Number a mp*le N S        u m b er . . *.. ..< .. ., =tCs-137" o .. , ..:. ..* :.::*              Fraction
172275012 9807-0000-012F 172275013 9807-0000-01 2FS 172275014 9807-0000-013F 172275015 9807-0000-014F 172275016 9807-0000-0 15F 172275017 9807-0000-01 6F 172275018 9807-0000-017F 172275019 9807-0000-018F 172275020 9807-0000-018FS 172275021 9807-0000-019F 172275022 9907-0000-02OF 172275023 9807-0000-021iF 172275024 9807-0000-022F 172275025 9807-0000-023F 172275026 9807-0000-024F 172275027 9807-0000-024FS 172275028 9807-0000-025F Items of Note There are no items to note.Case Narrative Sample analyses were conducted using methodology as outlined in General Engineering Laboratories (GEL) Standard Operating Procedures.
                                                                      .. ,.;,*,..*.. .... of the ......'=.
Any technical or administrative problems during analysis, data review, and reduction are contained
                              .,..        .. (pci/g)         .     .       Op.erational DCGE.,L 9807-0000-001 F                     -7.91E-03                                 0.000 9807-0000-002F                       -2.76E-02                                 0.000 9807-0000-003F                       4.02E-02                                 0.007 9807-0000-004F                       -1.26E-03                                 0.000 9807-0000-005F                       1.87E-02                                 0.003 9807-0000-006F                       -8.34E-03                                 0.000 9807-0000-007F                       -1.54E-02                                 0.000 9807-0000-008F                       -1.36E-02                                 0.000 9807-0000-009F                       3.30E-02                                 0.006 9807-0000-01 OF                       2.86E-02                                 0.005 9807-0000-01 IF                     -2.32E-02                                 0.000 9807-0000-012F                       4.36E-02                                 0.008 9807-0000-013F                       -2.5 1E-03                               0.000 9807-0000-014F                       8.18E-03                                 0.002 Revision I                                                       12 Revision I                                                       12
'in the analytical case narratives in the enclosed data package.Analytical Request Twenty-five soil samples were analyzed for FSSGAM. Three soil samples were analyzed for FSSALL.Data Packag~e 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:
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD
Radiochemistry.
    *:*,Table,_54* Summary ofSoil Sample .Results for the Statistical Sample....*,:.
________________                       Population_             _ _   _ _ _ _   _ _   _
Sample                                  ,,*ei*Cs137                     Fraction.of F,            the.
P.......           *        .. .. ,&#xfd; /g)'         ....      Operational DCGL."
9807-0000-015F                             1.29E-02                         0.002 9807-0000-016F                             6.01E-03                         0.001 9807-0000-017F                             3.34E-02                         0.006 9807-0000-018F                             2.39E-03                         0.000 9807-0000-019F                             -3.24E-04                         0.000 9807-0000-020F                             3.53E-02                         0.007 9807-0000-021 F                           0.OOE+00                           0.000 9807-0000-022F                             2.88E-02                         0.005 9807-0000-023F                             2.56E-02                         0.005 9807-0000-024F                             1.18E-02                         0.002 9807-0000-025F                             3.50E+00                           0.651 (1) The Operational DCGL from Table 2 is 5.38 pCi/g for Cs-137 to achieve seventeen (17) mrem/yr TEDE The off-site laboratory also processed three (3) samples for HTD analysis as required by the sample plan.                         The requested analyses included alpha spectroscopy, gas proportional counting, and liquid scintillation depending on the radionuclide and the measurement method. All analyses met the required MDC.
As previously stated in Section 4 of this report, the criteria for de-selection of a radionuclide is a concentration that is less than 5% of the Operational DCGL for individual radionuclides and less than 10% of the Operational DCGLs for aggregates. H-3 and Am-241 were the only HTDs identified above the accepted criteria for detection (i.e., a result greater than two standard deviations uncertainty). The off-site laboratory prepared and reanalyzed two (2) of the three (3) original samples for H-3 at HNP's request; and performed H-3 analysis on five (5) other samples bordering the two (2) sample locations. The results of all seven (7) samples were all less than the accepted criteria for detection. The highest result for Am-241 was about 4% of the Operational DCGL.
__                 ...
_~.....fab       le''"'8" -Hard-to-DetectSample.Ressu.is Sam.ple                     .Am-241                   Fraction of Ope.atin.al
                                                                                .         MDCGL 9807-0000-003F                     7.13E-01                             0.041 9807-0000-008F                     5.32E-02                             0.003 9807-0000-013F                     9.35E-02                             0.005 (I) The Operational DCGL from Table 2 is 17.5 pCi/g for Am-241 to achieve 17 mrem/yr TEDE Revision I                                             .13 Revision I                                               13
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD
: 7. QUALITY CONTROL The off-site laboratory processed the split samples and performed gamma spectroscopy analysis. Ten percent (10%) of the samples were 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". Cs-137 was not detected in sufficient quantities in the field split results at the three (3) locations to evaluate in accordance with procedure. Evaluation using the reported results for K-40 resulted in acceptable agreement between the field split results at these locations.
The sample analysis vendor, General Engineering Laboratories, LLC, maintains quality control and quality assurance plans as part of normal operation. Refer to Attachment 4 for data and data quality analysis results.
: 8. INVESTIGATIONS AND RESULTS No investigations were performed.
: 9. REMEDIATION AND RESULTS Remedial action was performed in July 2006. Although Co-60 has been identified in the past, Cs-137 was the only radionuclide with the potential to exceed the screening criteria following the remedial action. Health Physics TSD BCY-HP-0078, "ALARA Evaluation of Soil Remediation in Support of Final Status Survey, " has 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 No changes were made to the FSS plan.
: 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.
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 B.
Revision 0                                   14 Revision 0                                   14
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD 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.
For Cs-137, the range of the data, about five (5) standard deviations, indicated some variation, mainly as a result of one (1) sample that is higher in concentration than the rest of the data set. The difference between the mean and median was about 20% 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 significant positive skewness due to one (1) sample as confirmed by the calculated skew of 4.99.
All data, assessments, and graphical representations are provided in Attachment 3.
: 12. ANOMALIES No anomalies were noted.
: 13. CONCLUSION Survey Unit 9807-0000 has met the final DQOs of the FSS plan. The ALARA criteria for soils as specified in Chapter 4 of the LTP were achieved. Elevated Measurement Comparison was not required.
Cs-137 was 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 B.
The dose contribution from soil is less than 1 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 not considered impacted by future groundwater radioactive contamination, as there are no underground structures, systems or components containing residual radioactive material within the groundwater saturated zone in the area (reference CY memo ISC 06-024); therefore, the dose contribution from future groundwater is zero (0) mrem/yr TEDE.
Revision 0                                   15 Revision 0                                   15
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD 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
    .3 mrem/yr TEDE. Therefore, Survey Unit 9807-0000 is acceptable for unrestricted release.
: 14. ATTACHMENTS 14.1 Attachment 1 - Figures 14.2 Attachment 2 - Laboratory Results 14.4 Attachment 3 - DQA Results Revision I                                       16 Revision 1                                       16
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 1 (FIGURES)
 
j-CONNECT7CUT RIVER-r Connecticut Yankee Atomic Power Company         Date         By Figure 1             Site Map With Reference To Survey Unit 980 7-0000 November2006 IJ
 
Q C,!      /    .
{-t-.-_ . 7                                           Legend
                                            /
i -L 14          A-20
                        //                         __/
7-
                            ,6                                                              = Sample Point (3   -7       I-L           0
                                                                                    .,24 12.5       25 IFeet
            -I 'a                                                    19
                          /
1-2                  /-
                                                                    -  -
                      \
7-------                                           ~23
/4
  /  ~1~
7--
4 ____
I Ill                -.
17                      22 9----
Connecticut Yankee Atomic Power Company Survey Unit 9807-0000 FinalStatus Survey Design
 
                                  -0.01 0.01
                    -0.02                                                           Lqgend
      -0.03                                                         0.
                                    -0.03                                             12.5   25 F.t
            -0.01                                   -0.01                       . Notes
-0.01 0.04                                                     Reported Concentrationsin 0.02                                                            O0            pCi/g 0.01
              -0.02
-0.01                                                     0.03 0.03 0.03 0.03 0.01 0.03 0.0.1 Connecticut Yankee Atomic Power Company Survey Unit 9807-0000 FinalStatus Survey Cs-13 7 PostingPlot
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 2 (LABORATORY DATA)
 
General Narrative 1
 
General Narrative for Connecticut Yankee Atomic Power Co.
Work Order: 172275 SDG: MSR#06-1282 October 04, 2006 Laboratory Identification:
General Engineering Laboratories, LLC 2040 Savage Road Charleston, South Carolina 29407 (843) 556-8171 Summary Sample receipt The samples arrived at General Engineering Laboratories, LLC, Charleston, South Carolina on September 21, 2006 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         Sample Identification     Description 172275001         9807-0000-001F 172275002          9807-0000-002F 172275003          9807-0000-003F 172275004          9807-0000-004F 172275005          9807-0000-005F 172275006          9807-0000-006F 172275007        9807-0000-007F 172275008          9807-0000-008F 172275009        9807-0000-009F 172275010        9807-0000-010F 172275011          9807-0000-01 iF 2.
 
172275012           9807-0000-012F 172275013           9807-0000-01 2FS 172275014           9807-0000-013F 172275015           9807-0000-014F 172275016           9807-0000-0 15F 172275017           9807-0000-01 6F 172275018           9807-0000-017F 172275019           9807-0000-018F 172275020           9807-0000-018FS 172275021           9807-0000-019F 172275022           9907-0000-02OF 172275023           9807-0000-021iF 172275024           9807-0000-022F 172275025           9807-0000-023F 172275026           9807-0000-024F 172275027           9807-0000-024FS 172275028           9807-0000-025F Items of Note There are no items to note.
Case Narrative Sample analyses were conducted using methodology as outlined in General Engineering Laboratories (GEL) Standard Operating Procedures. Any technical or administrative problems during analysis, data review, and reduction are contained 'inthe analytical case narratives in the enclosed data package.
Analytical Request Twenty-five soil samples were analyzed for FSSGAM. Three soil samples were analyzed for FSSALL.
Data Packag~e 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.
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.
Cheryl Jones Project Manager 3 List of current GEL Certifications as of 04 October 2006 State Certification Alaska UST-062 Arizona AZ0668 Arkansas 88-0651 CLIA 42D0904046 California 01151CA Colorado GenEngLabs Connecticut PH-0169 Dept. of Navy NFESC 413 EPA WG-15J FloridaINELAP E87156 Georgia E87156 (FIJNELAP)
Cheryl Jones Project Manager 3
Hawaii N/A Idaho N/A Illinois 200029 Indiana C-SC-01 Kansas E-10332 Kentucky 90129 Louisiana 03046 Maryland .270 Massachusetts M-SCO12 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/I 0585001/10120002 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 No. 2006-568 362 Injun Hollow Road, East Hampton, CT 06424 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)
List of current GEL Certifications as of 04 October 2006 State                     Certification Alaska                       UST-062 Arizona                       AZ0668 Arkansas                       88-0651 CLIA                       42D0904046 California                     01151CA Colorado                     GenEngLabs Connecticut                     PH-0169 Dept. of Navy                   NFESC 413 EPA                         WG-15J FloridaINELAP                     E87156 Georgia                 E87156 (FIJNELAP)
Priority:
Hawaii                           N/A Idaho                           N/A Illinois                       200029 Indiana                       C-SC-01 Kansas                       E-10332 Kentucky                         90129 Louisiana                         03046 Maryland                           .270 Massachusetts                   M-SCO12 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/I 0585001/10120002 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,
E] 30 D. Z 14 D. [] 7 D.Other: X <CIO /Sample Designation Date Time a Comment, Preservation Lab Sample lD 9807-0000-001 F 91O416-6' 1141P TS C BP X_9807-0000-00;I , Itq TS C BP X 9807-0000-003 F " / &#xfd;r7 TS C BP ->,t 2_9807-0000-0004/
 
OR , /5,23 TS C BP 9807-0000-0 0$5E 105 -TS C BP %_9807-0000-0 No F &*/.1P 1 105 TS C BP 9807-0000-Opr 1 WnI , j2p.53 TS C BP _9807-0000-Oc V= &#xfd;L j \ 5 TS C BP 9807-0000-0 A ?O TS C BP " .......__9807-0000-0-4,0 qJ14100 I 4 S' TS C BP 9807-0000-0 0\ 4{ c) TS C BP P_NOTES: PO #: 002332 MSR #: &4:/Zi ,. Z LTP QA Dl Radwaste QA [1 Non QA Samples Shipped Via: Internal Container M Fed Ex Temp.: Deg. C El UPS El Hand Custody Seale ?*~ Y0 1) Relinquished y Date/Time 2)'I.c eivr By D te/Time Custody Seal Intact?3Y0.0 W VA 0 76-1 E] Other 3) Relinquished y Date/Time
Chain of Custody and Supporting Documentation 5
: 4) Received B; Date/Time BillofLading#_Y
 
_ N _Bill of Lading #5) Relinquished By Date/Time
Health Physics Procedure                                                                                   GPP-GGGR-R5104-003-Attachment B-CY-001 Major Connecticut Yankee Atomic Power Company                                                   Chain of Custody Form                               No. 2006-568 362 Injun Hollow Road, East Hampton, CT 06424 860-267-2556 Project Name: Haddam Neck Decommissioning                                                       Analyses Requested         Lab Use Only Contact Name & Phone:                                                                                                       Comments:
: 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 No. 2006-569 362 Injun Hollow Road, East Hampton, CT 06424 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)
Jack McCarthy   860-267-3924                           Media   Sample   Container
Priority:
__Code                                                    Type       Size-Analytical Lab (Name, City, State):                               Code     &Type Code General Engineering Laboratories 2040 Savage Road Charleston, SC 29407 ATT: Cheryl Jones (843-556-8171)
0 30 D. N 14 D. 717 D. 4 Other: ___ ___Sample Designation Date Time -_ -- Comment, Preservation Lab Sample ID 9807-0000-0 j v TS C BP Vnu -,74d 00140 9807-0000-0 q I Lj.,P C)9 TS C BP V "__ o_9807-0000-0  
Other: E] 30 D. Z 14 D. [] 7 D.
' q.14.G 40, TS C BP X 9807-0000-0 tLk -0% ", 060 e., TS C BP 9807-0000-0 VdO o'lf-p C.q, , TS C BP __9807-0000-0 11 6,0 .c tav- TS C BP 9807-0000-0  
Priority:                                                                               X     <CIO                                               _.*-2C      /
\'t= Q1-t 046 TS C BP ___.....9807-0000-0  
Sample Designation                 Date         Time                                   a                                     Comment, Preservation         Lab Sample lD 9807-0000-001 F               91O416-6' 1141P           TS         C         BP     X_
\--F \ f- TS C BP __9807-0000-0  
9807-0000-00;I                         , Itq           TS         C         BP       X 9807-0000-003 F                 "           / &#xfd;r7       TS         C         BP     ->,t 2_
\ _S a .1 r- TS C BP _ __9807-0000-0  
9807-0000-0004/                   OR ,     /5,23       TS         C         BP 9807-0000-0 0$5E                             105 -       TS         C         BP       %_
\0,'F 0tt',6-O, vOz TS C BP --9807-0000-0o -m- V 1905 ,QC26 TS C BP I_NOTES: PO #: 002332 MSR #: o0 -1Z o LTP QA [ Radwaste QA 0 Non QA Samples Shipped Via: Internal Container Z Fed Ex Temp.: __ Deg, C EU[S D Hand Custody Sealel 1) Relinquished By Date/Time
9807-0000-0 No F                 &*/.1P     1 105       TS         C         BP 9807-0000-Opr                 1 WnI,j2p.53             TS         C         BP                                             _
: 2) e ev Date/Time Custody Seal Intact?_______ ______ ___L16 9&sect;/Q 0 n9 o El Other 3) Relinquished By Date/Time
9807-0000-Oc V=               C*W    &#xfd;Lj      \     5   TS         C         BP 9807-0000-0 A V*                              ?O       TS         C         BP         "                               __                                                .......
: 4) keceived 3y Date/Time YOl NO]Bill of Lading #5) Relinquished By Date/Time
9807-0000-0-4,0               qJ14100         I4 S'     TS         C         BP 9807-0000-0                   0\ WL*-Q&#xfd; c) 4{           TS         C         BPP_
: 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 No. 2006-570 362 Injun Hollow Road, East Hampton, CT 06424 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 AnalyicalCode General Engineering Laboratories 2040 Savage Road Charleston, SC 29407 ATT: Cheryl Jones (843-556-8171)
NOTES: PO #: 002332                   MSR #: &4:/Zi       ,. Z         LTP QA           Dl Radwaste QA       [1 Non QA   Samples Shipped Via:         Internal Container M Fed Ex                     Temp.: _* Deg. C El UPS
Priority:
                                                                                            *~                            El Hand                           Y0 Seale ?
1 30 D. Z 14 D. ZI 7 D.Other: _ __ _Sample Designation Date Time 4. 1 Comment, Preservation Lab Sample D)9807-0000-0'ZiI q-l 3j <9 f'6 TS C BP -,_9807-0000-0 ogm r,. -q --11-o(. TS C BP ?C_9807-0000-0 z: j, q- t-6<I', l5-- TS C BP -)9807-0000-0 .AI q-&#xfd;") TS C BP 9807-0000-0  
Custody
-;, _V-O(9 TS C BP-GC5WE g.Q5 ;7~ C? 10606 1 _____ __ _NOTES: PO #: 002332 MSR#: or) &- LTP QA E] Radwaste QA LI Non QA Samples Shipped Via: Internal Container Z Fed Ex Temp.: __ Deg. C 0uPs El Hand Custody Sealed?1) Relinquished By Date/Time
: 1) Relinquished y                           Date/Time         2)'I.c eivr By                           D te/Time                                     Custody Seal Intact?
: 2) Reivecfv .!ate/Time El-Other Custody Sentact?3) Relinquished By Date/Time
3Y0.0         W       VA                                   0   76-1   E] Other
: 4) Received byK Date/Time BillofLadig___YON___
: 3) Relinquished y                           Date/Time         4) Received B;                         Date/Time         BillofLading#_Y
Bill of Lading #5) Relinquished By Date/Time
_ _                        N Bill of Lading #
: 6) Received By Date/Time Connecticut Yankee Statement of Work for Analytical Lab Services .CY-ISC-SOW-001 Figure 1. Sample Check-in List .Date/Time Received:  
: 5) Relinquished By                           Date/Time         6) Received By                           Date/Time
.-1 O()'0c , SDG#: Work Order Number:______________________
 
_______Shipping Cdntainerfl:
Health Physics Procedure                                                                                         GPP-GGGR-R5104-003-Attachment B-CY-001 Major Connecticut Yankee Atomic Power Company                                                           Chain of Custody Form                           No. 2006-569 362 Injun Hollow Road, East Hampton, CT 06424 860-267-2556 Project Name: Haddam Neck Decommissioning                                                             Analyses Requested         Lab Use Only Contact Name & Phone:                                                                                                             Comments:
." t4 _-_2-_ .C" .hain of Custody# 5AO k l .'ciO: ." o tQ_ V 7e- d e_ -.vw' " .q ..-b C & " Z " * : 1. Custody Seals orffshipping container intact?.. -Yes t ]No [ A 2. Custody Seals dated and. signed? .Yes"[ I No [ ].A/l/4 3. Chain-of-Custody record sent? Yes *.NO 4" .Cooler temperature I I 5. Vermiculite/packing materials is: Wet [P Dry II, ]iiJ/6.' Number of samples in shipping container:
Media  Sample  Container Jack McCarthy 860-267-3924                                   Code   Type     Size-Analytical Lab (Name, City, State):                                   Code     &Type Code General Engineering Laboratories 2040 Savage Road Charleston, SC 29407 ATT: Cheryl Jones (843-556-8171)
: 7. Sample holding times exceeded?
Priority: 0 30 D. N 14 D. 717 D.                                                               4 Other:                           ___          ___
Yes[ No.y4*8. Samples have://tape -hazard labels custody seals ._ appropriate sample labels 9. Samples are:_4 1 good condition  
Sample Designation                   Date           Time       -_                                               --                 Comment, Preservation     Lab Sample ID 9807-0000-0 j v
.leaking-broken " have air bubbles 10. Were any.anomalies identified in sample receipt? Yes[] No,1 11.. .Description of anomalies (include sample numbers):
* TS     C         BP     Vnu                                     -,74d 00140 9807-0000-0                       q ILj.,P         C)9         TS     C         BP     V                                         "__     o_
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< Result is less than value reported a Result is greater than value reported RPD of sample and duplicate evaluated using +/-RL. Concentrations are cSX the RL A The TIC is a suspected aldol-condensation product* Target analyte was detected in the associated blank B Metals-Either presence of analyte detected in the associated blank, or MDL/IDL a sample value a 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 N 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.11 RADIOLOGICAL ANALYSIS 12 Radiochemistry Case Narrative Connecticut Yankee Atomic Power Co. (YANK)Work Order 172275 Method/Analysis Information Product: Alphaspec 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 572120 571426 571421 Sample ID 172275003 172275008 172275014 1201191303 1201191304 1201191305 1201191306 Client ID 9807-0000-003F 9807-0000-008F 9807-0000-013F Method Blank (MB)172114001(9530-0001-008F)
9807-0000-0         '           q.14.G         40,         TS       C       BP           X 9807-0000-0 tLk -               0%",060               e.,   TS       C       BP 9807-0000-0 VdO                       o'lf-p C.q,         , TS       C         BP                                                                       __
Sample Duplicate (DUP)172114001(9530-0001-008F)
9807-0000-0 11                         . 6,0 c     tav-     TS       C       BP 9807-0000-0 \'t=               Q1-t           046           TS       C         BP         ___.....
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-01 1 REV# 14.Calibration Information:
9807-0000-0     \--F                           \       f-   TS       C       BP                             __
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.
9807-0000-0 \       _S         a .1r-                       TS       C         BP                           _         __
13 Quality Control (QC) Information:
9807-0000-0 \0,'F               0tt',6-O,       vOz           TS       C       BP                               -       -
Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 172114001 (9530-0001-008F).
9807-0000-0o -m- V             1905               ,QC26     TS       C       BP         I_
QC Information All of the QC samples met the required acceptance limits.Technical Information:
NOTES: PO #: 002332                     MSR #: o0 -1Z o                   LTP QA         [   Radwaste QA             0   Non QA Samples Shipped Via:       Internal Container Z   Fed Ex               Temp.: __ Deg, C EU[S D Hand                       Custody Sealel
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.
: 1) Relinquished By                                 Date/Time       2)     eev                                  Date/Time                                 Custody Seal Intact?
_______     ______   ___L16                                                   9&sect;/Q       0 n9     o El Other
: 3) Relinquished By                                 Date/Time       4) keceived 3y                               Date/Time                                       YOl   NO]
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                             No. 2006-570 362 Injun Hollow Road, East Hampton, CT 06424 860-267-2556 Project Name: Haddam Neck Decommissioning                                                       Analyses Requested           Lab Use Only Contact Name & Phone:                                                                                                         Comments:
Media    Sample    Container Jack McCarthy 860-267-3924                               Code     Type       Size-Analytical Lab (Name, City, State):                               Code     &Type AnalyicalCode General Engineering Laboratories 2040 Savage Road Charleston, SC 29407 ATT: Cheryl Jones (843-556-8171)
Priority: 1 30 D. Z 14 D. ZI 7 D.
Other:                         _       __                                                                                                                           _
Sample Designation               Date         Time                                         4.         1                       Comment, Preservation     Lab Sample D) 9807-0000-0'ZiI               3j q-lf'6 <9                 TS       C         BP                     -,_
9807-0000-0 ogm r,. -         q-- 11-o(.     os-*        TS       C         BP       ?C_
9807-0000-0 z: j,             q- t-6<I',     l5--       TS       C         BP     -)
9807-0000-0 .AI               q-&#xfd;")         j*4"j 14o',*30  TS       C         BP 9807-0000-0 ;,   -_V-O(9           s*)                  TS       C         BP
      -GC5WEg.Q5 ;7~         C? 10606       1                                                                         _____                                 __   _
NOTES: PO #: 002332                   MSR#: or)     &-                 LTP QA           E] Radwaste QA         LI Non QA   Samples Shipped Via:     Internal Container Z Fed Ex                 Temp.: __ Deg. C 0uPs El   Hand                 Custody Sealed?
: 1) Relinquished By                             Date/Time                .!ate/Time
: 2) Reivecfv                                                 El-Other                 Custody Sentact?
: 3) Relinquished By                             Date/Time         4) Received byK                           Date/Time         BillofLadig___YON___
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 Check-in List         .
Date/Time Received:         .       - 1 O()'0c                       ,
SDG#:
_______
Work Order Number:______________________
C"hain of Custody#           5AO   k   l .'ciO
                                            . q . b.-. C&." Z "
* av.*
: . Cdntainerfl:
Shipping                    ."
              " o tQ_V7e-d e_  - t4 .vw' " _-_2-_                                :
: 1.        Custody Seals orffshipping container intact?..                        -Yes t ]No     [   A
: 2.         Custody Seals dated and.signed?                     .                 Yes"[ I No   [ ].A/l/4
: 3.         Chain-of-Custody record       sent? *.NO                             Yes 4".       Cooler temperature     I                 I
: 5.         Vermiculite/packing materials is:                                     Wet   [P Dry II,]iiJ/
6.'       Number of samples in shipping container:
: 7.         Sample holding times exceeded?                                         Yes[     No.y4
    *8. Samples have:
            //tape                                 -hazard   labels custody seals                 ._   appropriate sample labels
: 9. Samples are:
_4 1 good condition           .           leaking
                -broken                             " have air bubbles
: 10.       Were any.anomalies identified in sample receipt?                     Yes[] No,1 11..     .Description of anomalies (include sample numbers):
 
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
<     Result is   less than value reported a     Result is   greater than value reported RPD of sample and duplicate evaluated using +/-RL. Concentrations are cSX the RL A     The TIC is   a suspected aldol-condensation product
* Target analyte was detected in the associated blank B     Metals-Either presence of analyte detected in the associated blank, or MDL/IDL a sample value a 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 N       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.
11
 
RADIOLOGICAL ANALYSIS 12
 
Radiochemistry Case Narrative Connecticut Yankee Atomic Power Co. (YANK)
Work Order 172275 Method/Analysis Information Product:                                           Alphaspec Am241, Cm, Solid ALL FSS Analytical Method:                                 DOE EML HASL-300, Am-05-RC Modified Prep Method:                                       Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method:                 Dry Soil Prep Analytical Batch Number:                           572120 Prep Batch Number:                                 571426 Dry Soil Prep GL-RAD-A-021 Batch Number:           571421 Sample ID       Client ID 172275003      9807-0000-003F 172275008      9807-0000-008F 172275014      9807-0000-013F 1201191303      Method Blank (MB) 1201191304      172114001(9530-0001-008F) Sample Duplicate (DUP) 1201191305      172114001(9530-0001-008F) Matrix Spike (MS) 1201191306      Laboratory Control Sample (LCS)
SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-01 1 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: 172114001 (9530-0001-008F).
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:
Miscellaneous Information:
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
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.
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 14 Product: Alphaspec Pu, Solid-ALL FSS DOE EML HASL-300, Pu- 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 572121 571426 571421 Sample ID 172275003 172275008 172275014 1201191307 1201191308 1201191309 1201191310 Client ID 9807-0000-003F 9807-0000-008F 9807-0000-013F Method Blank (MB)172114001(9530-0001-008F)
Manual Integration No manual integrations were performed on data in this batch.
Sample Duplicate (DUP)172114001(9530-0001-008F)
Additional Comments Additional comments were not required for this sample set.
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-0 11 REV# 14.Calibration Information:
Qualifier information Manual qualifiers were not required.
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.
Method/Analysis Information 14
 
Product:                                           Alphaspec Pu, Solid-ALL FSS Analytical Method:                                  DOE EML HASL-300, Pu- I -RC Modified Prep Method:                                       Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method:                 Dry Soil Prep Analytical Batch Number:                           572121 Prep Batch Number:                                 571426 Dry Soil Prep GL-RAD-A-021 Batch Number:           571421 Sample ID       Client ID 172275003      9807-0000-003F 172275008      9807-0000-008F 172275014      9807-0000-013F 1201191307      Method Blank (MB) 1201191308    172114001(9530-0001-008F) Sample Duplicate (DUP) 1201191309    172114001(9530-0001-008F) Matrix Spike (MS) 1201191310      Laboratory Control Sample (LCS)
SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-0 11 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:
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: 172114001 (9530-0001-008F).
Blank Information The blank volume is representative of the sample volume in this batch.
QC Information All of the QC samples met the required acceptance limits.15 Technical Information:
Designated QC The following sample was used for QC: 172114001 (9530-0001-008F).
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.
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:
Miscellaneous Information:
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
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.
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: 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 572122 571426 571421 16 Sample ID Client ID 172275003 9807-0000-003F 172275008 9807-0000-008F 172275014 9807-0000-013F 1201191311 Method Blank (MB)1201191312 172114001(9530-0001-008F)
Manual Integration No manual integrations were performed on data in this batch.
Sample Duplicate (DUP)1201191313 172114001(9530-0001-008F)
Additional Comments Additional comments were not required for this sample set.
Matrix Spike (MS)1201191314 Laboratory Control Sample (LCS)SOP Reference Pr ocedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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:
Qualifier information Manual qualifiers were not required.
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.
Method/Analysis Information Product:                                           Liquid Scint Pu241, Solid-ALL FSS Analytical Method:                                  DOE EML HASL-300, Pu-I I-RC Modified Prep Method:                                       Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method:                 Dry Soil Prep Analytical Batch Number:                           572122 Prep Batch Number:                                 571426 Dry Soil Prep GL-RAD-A-021 Batch Number:           571421 16
 
Sample ID       Client ID 172275003       9807-0000-003F 172275008       9807-0000-008F 172275014       9807-0000-013F 1201191311     Method Blank (MB) 1201191312       172114001(9530-0001-008F) Sample Duplicate (DUP) 1201191313       172114001(9530-0001-008F) Matrix Spike (MS) 1201191314     Laboratory Control Sample (LCS)
SOP Reference Pr ocedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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 (0C) Information:
Quality Control (0C) Information:
Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 172114001 (9530-0001-008F).
Blank Information The blank volume is representative of the sample volume in this batch.
QC Information All of the QC samples met.the required acceptance limits.Technical Information:
Designated QC The following sample was used for QC: 172114001 (9530-0001-008F).
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.
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:
Miscellaneous Information:
NCR Documentation 17 Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
NCR Documentation 17
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: Analytical Method: Prep Method: Analytical Batch Number: Prep Batch Number: Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived EML HASL 300, 4.5.2.3 Dry Soil Prep 574335 571421 18 Sample ID 172275001 172275002 172275003 172275004 172275005 172275006 172275007 172275008 172275009 172275010 172275011 172275012 172275013 172275014 172275015 172275016 172275017 172275018 172275019 172275020 1201196536 1201196537 1201196538 ClientID 9807-0000-001F 9807-0000-002F 9807-0000-003F 9807-0000-004F 9807-0000-005F 9807-0000-006F 9807-0000-007F 9807-0000-008F 9807-0000-009F 9807-0000-01OF 9807-0000-01 IF 9807-0000-012F 9807-0000-012FS 9807-0000-013F 9807-0000-014F 9807-0000-015F 9807-0000-016F 9807-0000-017F 9807-0000-018F 9807-0000-018FS Method Blank (MB)172275001(9807-0000-00IF)
 
Sample Duplicate (DUP)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-013 REV# 12.Calibration Information:
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.
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.
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:                   Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Analytical Method:          EML HASL 300, 4.5.2.3 Prep Method:                Dry Soil Prep Analytical Batch Number:    574335 Prep Batch Number:          571421 18
 
Sample ID       ClientID 172275001       9807-0000-001F 172275002      9807-0000-002F 172275003      9807-0000-003F 172275004      9807-0000-004F 172275005      9807-0000-005F 172275006      9807-0000-006F 172275007      9807-0000-007F 172275008      9807-0000-008F 172275009      9807-0000-009F 172275010      9807-0000-01OF 172275011      9807-0000-01 IF 172275012      9807-0000-012F 172275013      9807-0000-012FS 172275014      9807-0000-013F 172275015      9807-0000-014F 172275016      9807-0000-015F 172275017      9807-0000-016F 172275018      9807-0000-017F 172275019      9807-0000-018F 172275020      9807-0000-018FS 1201196536    Method Blank (MB) 1201196537      172275001(9807-0000-00IF) Sample Duplicate (DUP) 1201196538      Laboratory Control Sample (LCS)
SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-013 REV# 12.
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:
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: 172275001 (9807-0000-OOIF).
Blank Information The blank volume is representative of the sample volume in this batch.
19 QC Information All of the QC samples met the required acceptance limits.Technical Information:
Designated QC The following sample was used for QC: 172275001 (9807-0000-OOIF).
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.
19
 
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:
Miscellaneous Information:
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
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.
A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.Qualifier information Qualifier Reason Analyte Cesium-137 Sample 172275013 UT5 U'Data rejected due to high peak-width.
Additional Comments Additional comments were not required for this sample set.
Data rejected due to interference.
Qualifier information Qualifier                   Reason                       Analyte         Sample UT5         Data rejected due to high peak-width.     Cesium-137      172275013 U'          Data rejected due to interference.         Cesium-134     172275017 Europium- 155   172275008 172275013 Ui           Data rejected due to low abundance.       Actinium-228    172275002 Cesium-134     172275003 172275006 172275007 172275008 172275012 172275015 172275018 1201196537 20
Cesium-134 172275017 Europium-155 Actinium-228 172275008 172275013 172275002 Ui Data rejected due to low abundance.
 
Cesium-134 172275003 172275006 172275007 172275008 172275012 172275015 172275018 1201196537 20 Method/Analysis Information Product: Analytical Method: Prep Method: Analytical Batch Number: Prep Batch Number: Sample ID 172275021 172275022 172275023 172275024 172275025 172275026 172275027 172275028 1201196539 1201196540 1201196541 Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived EML HASL 300, 4.5.2.3 Dry Soil Prep 574336.571423 Client ID 9807-0000-019F 9807-0000-020F 9807-0000-021F 9807-0000-022F 9807-0000-023F 9807-0000-024F 9807-0000-024FS 9807-0000-025F Method Blank (MB)172275028(9807-0000-025F)
Method/Analysis Information Product:                       Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Analytical Method:              EML HASL 300, 4.5.2.3 Prep Method:                    Dry Soil Prep Analytical Batch Number:        574336 Prep Batch Number:            .571423 Sample ID      Client ID 172275021      9807-0000-019F 172275022      9807-0000-020F 172275023      9807-0000-021F 172275024      9807-0000-022F 172275025      9807-0000-023F 172275026      9807-0000-024F 172275027      9807-0000-024FS 172275028      9807-0000-025F 1201196539      Method Blank (MB) 1201196540      172275028(9807-0000-025F) Sample Duplicate (DUP) 1201196541      Laboratory Control Sample (LCS)
Sample Duplicate (DUP)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-013 REV# 12.Calibration Information:
SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-013 REV# 12.
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.
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 (0C) Information:
Quality Control (0C) Information:
Blank Information The blank volume is representative of the samplevolume in this batch.21 Designated QC The following sample was used for QC: 172275028 (9807-0000-025F).
Blank Information The blank volume is representative of the samplevolume in this batch.
QC Information Refer to Non-Conformance Report.Technical Information:
21
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.
 
Designated QC The following sample was used for QC: 172275028 (9807-0000-025F).
QC Information Refer to Non-Conformance Report.
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:
Miscellaneous Information:
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents. The following NCR was generated for this SDG:
The following NCR was generated for this SDG: NCR 368031 was generated due to Failed RPD for DUP. 1. Failed RPD for DUP: The relative percent difference (172275028 and 120119654) for K-40 and Pb-212 did not meet the duplication criteria.
NCR 368031 was generated due to Failed RPD for DUP. 1. Failed RPD for DUP: The relative percent difference (172275028 and 120119654) for K-40 and Pb-212 did not meet the duplication criteria. 1.
1.K-40 and Pb-212 are naturally occurring nuclides.
K-40 and Pb-212 are naturally occurring nuclides. All other nuclides meet within the duplication criteria. Reporting results.
All other nuclides meet within the duplication criteria.
Additional Comments Additional comments were not required for this sample set..
Reporting results.Additional Comments Additional comments were not required for this sample set..Oualifier information Qualifier Reason Analyte Sample UI Data rejected due to high peak-width.
Oualifier information Qualifier                     Reason                       Analyte       Sample UI             Data rejected due to high peak-width. Cesium-137     172275023 UI             Data rejected due to interference.       Europium-155   172275023 UI             Data rejected due to low abundance.       Cesium- 134   172275021 172275022 172275024 172275025 1201196540 Method/Analysis Information 22
Cesium-137 172275023 UI Data rejected due to interference.
 
Europium-155 172275023 UI Data rejected due to low abundance.
Product:                                           GFPC, Sr9O, solid-ALL FSS Analytical Method:                                 EPA 905.0 Modified Prep Method:                                       Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method:                 Dry Soil Prep Analytical Batch Number:                           572301 Prep Batch Number:                                 571426 Dry Soil Prep GL-RAD-A-021 Batch Number:           571421 Sample ID       Client ID 172275003       9807-0000-003F 172275008       9807-0000-008F 172275014       9807-0000-01 3F 1201191723     Method Blank (MB) 1201191724     172275003(9807-0000-003F) Sample Duplicate (DUP) 1201191725     172275003(9807-0000-003F) Matrix Spike (MS) 1201191726     Laboratory Control Sample (LCS)
Cesium- 134 172275021 172275022 172275024 172275025 1201196540 Method/Analysis Information 22 Product: GFPC, Sr9O, solid-ALL FSS Analytical Method: EPA 905.0 Modified Prep Method: Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method: Dry Soil Prep Analytical Batch Number: 572301 Prep Batch Number: 571426 Dry Soil Prep GL-RAD-A-021 Batch Number: 571421 Sample ID Client ID 172275003 9807-0000-003F 172275008 9807-0000-008F 172275014 9807-0000-01 3F 1201191723 Method Blank (MB)1201191724 172275003(9807-0000-003F)
SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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.
Sample Duplicate (DUP)1201191725 172275003(9807-0000-003F)
Calibration Information:
Matrix Spike (MS)1201191726 Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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.
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.
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:
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: 172275003 (9807-0000-003F).
Blank Information The blank volume is representative of the sample volume in this batch.
23 QC Information All of the QC samples met the required acceptance limits.Technical Information:
Designated QC The following sample was used for QC: 172275003 (9807-0000-003F).
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.
23
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.
QC Information All of the QC samples met the required acceptance limits.
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 Product: Liquid Scint Tc99, Solid-ALL FSS Analytical Method: Analytical Batch Number: Sample liD 172275003 172275008 172275014 1201190771 1201190772 1201190773 1201190774 DOE EML HASL-300, Tc-02-RC Modified 571877 Client ID 9807-0000-003F 9807-0000-OOSF 9807-0000-013F Method Blank (MB)172275003(9807-0000-003F)
Technical Information:
Sample Duplicate (DUP)172275003(9807-0000-003F)
Holding Time All sample procedures for this sample set were performed within the required holding time.
Matrix Spike (MS)Laboratory Control Sample (LCS)24 SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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:
Preparation Information All preparation criteria have been met for these analyses.
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.
Sample Re-prep/Re-analysis None of the samples in this sample set required reprep or reanalysis.
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 Additional comments were not required for this sample set.
Oualifier information Manual qualifiers were not required.
Method/Analysis Information Product:                       Liquid Scint Tc99, Solid-ALL FSS Analytical Method:             DOE EML HASL-300, Tc-02-RC Modified Analytical Batch Number:      571877 Sample liD      Client ID 172275003      9807-0000-003F 172275008      9807-0000-OOSF 172275014      9807-0000-013F 1201190771      Method Blank (MB) 1201190772      172275003(9807-0000-003F) Sample Duplicate (DUP) 1201190773      172275003(9807-0000-003F) Matrix Spike (MS) 1201190774      Laboratory Control Sample (LCS) 24
 
SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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 (0C) Information:
Quality Control (0C) Information:
Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 172275003 (9807-0000-003F).
Blank Information The blank volume is representative of the sample volume in this batch.
QC Information All of the QC samples met the required acceptance limits.Technical Information:
Designated QC The following sample was used for QC: 172275003 (9807-0000-003F).
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.
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:
Miscellaneous Information:
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
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.
A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.25 Qualifier information Manual qualifiers were not required.Method/Analysis Information Product: Liquid Scint Fe55, Solid-ALL FSS DOE RESL Fe- 1, 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 571874 571426 571421 Sample ID 172275003 172275008 172275014 1201190757 1201190758 1201190759 1201190760 Client ID 9807-0000-003F 9807-0000-008F 9807-0000-013F Method Blank (MB)172275008(9807-0000-008F)
Additional Comments Additional comments were not required for this sample set.
Sample Duplicate (DUP)172275008(9807-0000-008F)
25
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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.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.
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:                                       Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method:                 Dry Soil Prep Analytical Batch Number:                           571874 Prep Batch Number:                                 571426 Dry Soil Prep GL-RAD-A-021 Batch Number:           571421 Sample ID       Client ID 172275003      9807-0000-003F 172275008      9807-0000-008F 172275014      9807-0000-013F 1201190757      Method Blank (MB) 1201190758      172275008(9807-0000-008F) Sample Duplicate (DUP) 1201190759      172275008(9807-0000-008F) Matrix Spike (MS) 1201190760      Laboratory Control Sample (LCS)
SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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.
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:
Quality Control (QC) Information:
Blank Information 26 The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 172275008 (9807-0000-008F).
Blank Information 26
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.
The blank volume is representative of the sample volume in this batch.
Designated QC The following sample was used for QC: 172275008 (9807-0000-008F).
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:
Miscellaneous Information:
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
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.
A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.Gualifier information Manual qualifiers were not required.Method/Analysis Information Product: Liquid Scint Ni63, Solid-ALL FSS* Analytical Method: DOE RESL Ni-1, Modified Prep Method: Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method: Dry Soil Prep Analytical Batch Number: 571876 Prep Batch Number: 571426 Dry Soil Prep GL-RAD-A-021 Batch Number: 571421 27 Sample ED 172275003 172275008 172275014 1201190767 1201190768 1201190769 1201190770 Client ID 9807-0000-003F 9807-0000-008F 9807-0000-013F Method Blank (MB)172275014(9807-0000-013F)
Additional Comments Additional comments were not required for this sample set.
Sample Duplicate (DUP)172275014(9807-0000-013F)
Gualifier information Manual qualifiers were not required.
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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:
Method/Analysis Information Product:                                           Liquid Scint Ni63, Solid-ALL FSS
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.
*Analytical Method:                                 DOE RESL Ni-1, Modified Prep Method:                                       Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method:                 Dry Soil Prep Analytical Batch Number:                           571876 Prep Batch Number:                                 571426 Dry Soil Prep GL-RAD-A-021 Batch Number:           571421 27
 
Sample ED       Client ID 172275003      9807-0000-003F 172275008      9807-0000-008F 172275014      9807-0000-013F 1201190767      Method Blank (MB) 1201190768      172275014(9807-0000-013F) Sample Duplicate (DUP) 1201190769      172275014(9807-0000-013F) Matrix Spike (MS) 1201190770      Laboratory Control Sample (LCS)
SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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 (0C) Information:
Quality Control (0C) Information:
Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 172275014 (9807-0000-013F).
Blank Information The blank volume is representative of the sample volume in this batch.
QC Information All of the QC samples met the required acceptance limits.Technical Information:
Designated QC The following sample was used for QC: 172275014 (9807-0000-013F).
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.
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:
Miscellaneous Information:
NCR Documentation 28 Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
NCR Documentation 28
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: Analytical Method: Analytical Batch Number: Sample ID 172275003 172275008 172275014 1201190793 1201190794 1201190795 1201190796 LSC, Tritium Dist, Solid-HTD2,ALL FSS EPA 906.0 Modified 571884 Client ID 9807-0000-003F 9807-0000-008F 9807-0000-013F Method Blank (MB)172275003(9807-0000-003F)
 
Sample Duplicate (DUP)172275003(9807-0000-003F)
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.
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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.Calibration Information:
Additional Comments Additional comments were not required for this sample set.
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.
Qualifier information Manual qualifiers were not required.
29 Quality Control (OC) Information:
Method/Analysis Information Product:                       LSC, Tritium Dist, Solid-HTD2,ALL FSS Analytical Method:            EPA 906.0 Modified Analytical Batch Number:      571884 Sample ID      Client ID 172275003      9807-0000-003F 172275008      9807-0000-008F 172275014      9807-0000-013F 1201190793      Method Blank (MB) 1201190794    172275003(9807-0000-003F) Sample Duplicate (DUP) 1201190795      172275003(9807-0000-003F) Matrix Spike (MS) 1201190796      Laboratory Control Sample (LCS)
Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 172275003 (9807-0000-003F).
SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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.
QC Information All of the QC samples met the required acceptance limits.Technical Information:
Calibration 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.
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.
29
 
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: 172275003 (9807-0000-003F).
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:
Miscellaneous Information:
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents. The following NCR was generated for this SDG:
The following NCR was generated for this SDG: NCR 365692 was generated due to Container scanning event for custody missed. 1. The analyst did not scan the samples 172275003, 172275008, and 172275014 into the batch prior to analysis, however the samples did remain in their custody at all times. 1. The error has been corrected and the analyst has been instructed on the proper scanning procedures.
NCR 365692 was generated due to Container scanning event for custody missed. 1. The analyst did not scan the samples 172275003, 172275008, and 172275014 into the batch prior to analysis, however the samples did remain in their custody at all times. 1. The error has been corrected and the analyst has been instructed on the proper scanning procedures. Reporting results.
Reporting results.Additional Comments Additional comments were not required for this sample set.Qualifier information Manual qualifiers were not required.Method/Analysis Information Product: Liquid Scint C14, Solid AII,FSS Analytical Method: EPA EERF C-0I Modified Analytical Batch Number: 571880 30 Sample ID Client ID 172275003 9807-0000-003F 172275008 9807-0000-008F 172275014 9807-0000-013F 1201190783 Method Blank (MB)1201190784 172275003(9807-0000-003F)
Additional Comments Additional comments were not required for this sample set.
Sample Duplicate (DUP)1201190785 172275003(9807-0000-003F)
Qualifier information Manual qualifiers were not required.
Matrix Spike (MS)1201190786 Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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:
Method/Analysis Information Product:                       Liquid Scint C14, Solid AII,FSS Analytical Method:             EPA EERF C-0I Modified Analytical Batch Number:       571880 30
Calibration Information All initial and continuing calibration requirements have been met.Standards Infor'mation 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.
 
Sample ID       Client ID 172275003       9807-0000-003F 172275008       9807-0000-008F 172275014       9807-0000-013F 1201190783     Method Blank (MB) 1201190784     172275003(9807-0000-003F) Sample Duplicate (DUP) 1201190785     172275003(9807-0000-003F) Matrix Spike (MS) 1201190786     Laboratory Control Sample (LCS)
SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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 Infor'mation 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 (OQC) Information:
Quality Control (OQC) Information:
Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 172275003 (9807-0000-003F).
Blank Information The blank volume is representative of the sample volume in this batch.
Designated QC The following sample was used for QC: 172275003 (9807-0000-003F).
QC Information
QC Information
.All of the QC samples met the required acceptance limits.Technical Information:
.All of the QC samples met the required acceptance limits.
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.
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:
Miscellaneous Information:
NCR Documentation 31 Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
NCR Documentation 31
A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.Gualifier 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.
 
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.
Gualifier 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:
Review Validation:
GEL requires all analytical data to be verified by a qualified data validator.
GEL requires all analytical data to be verified by a qualified data validator. In addition, all data designated for CLP or CLP-like packagihg will receive a third level validation upon completion of the data package.
In addition, all data designated for CLP or CLP-like packagihg will receive a third level validation upon completion of the data package.The following data validator verified the information presented in this case narrative:
The following data validator verified the information presented in this case narrative:
Reviewer/Date:
Reviewer/Date:
32 General Engineering Laboratories Form GEL-NCR Rev. 06105 NCR Report No.: 365692 Revision No.: COMPANY -WIDE NONCONFORMANCE REPORT Mo.Day Yr. Division:
32
Quality Criteria:
Type: 29-SEP-06 Radiochemistry Specifications Process Instrument Type: Test ! Method: Matrix Type: Client Code: LSC EPA 906.0 Modified Solid YANK Batch ID: Sample Numbers: 571884 See Below Potentially affected work order(s)(SDG):
172275(MSR#06-1282)
Application Issues: Container scanning event for custody missed Specification and Requirements NRG Disposition:
Nonconformance


==
General Engineering Laboratories                                                                                   NCR Report No.:    365692 Form GEL-NCR Revision No.:
Description:==
Rev. 06105 COMPANY       - WIDE NONCONFORMANCE REPORT Mo.Day Yr.                             Division:                         Quality Criteria:                     Type:
: 1. The analyst did not scan the samples 172275003, 172275008, and 172275014 into the batch prior to analysis, however the samples did remain in their custody at all times.1. The error has been corrected and the analyst has been instructed on the proper scanning procedures.
29-SEP-06                               Radiochemistry                   Specifications                         Process Instrument Type:                       Test ! Method:                   Matrix Type:                           Client Code:
Reporting results.Originator's Name: Amy Scott Quality Review: Data Validator/Group Leader: Melanie Aycock 01-OCT-06 29-SEP-06 Director: Page 1 33 General Engineering Laboratories Form GEL-NCR Rev. 06/05 NCR Report No;: 368031 Revision No.: 1 COMPANY- WIDE NONCONFORMANCE REPORT Mo.Day Yr. Division:
LSC                                    EPA 906.0 Modified                Solid                                 YANK Batch ID:                               Sample Numbers:
Quality Criteria:
571884                                  See Below Potentially affected work order(s)(SDG): 172275(MSR#06-1282)
Type: 05-OCT-06 Radiochemistry Specifications Process Instrument Type: Test / Method: Matrix Type: Client Code: GAMMA SPECTROMETER EML HASL 300, 4.5.2.3 Solid YANK Batch ID: Sample Numbers: .574336 See Below Potentially affected work order(s)(SDG):
Application Issues:
172275(MSR#06-1282),172873(MSR#06-1313),172875(MSR#06-1312),172879(MSR#06-1311)
Container scanning event for custody missed Specification and Requirements                                           NRG Disposition:
Application Issues: Failed RPD for DUP Specification and Requirements NRG Disposition:
Nonconformance
Nonconformance  


==
== Description:==
Description:==
: 1. The analyst did not scan the samples 172275003, 172275008, and      1. The error has been corrected and the analyst has been instructed on the 172275014 into the batch prior to analysis, however the samples did    proper scanning procedures. Reporting results.
: 1. Failed RPD for DUP: The relative percent difference (172275028
remain in their custody at all times.
: 1. K-40 and Pb-212 are naturally occurring nuclides.
Originator's Name:                                                        Data Validator/Group Leader:
All other nuclides and 120119654) for K-40 and Pb-212 did not meet the duplication meet within the duplication criteria.
Amy Scott                29-SEP-06                                        Melanie Aycock          01-OCT-06 Quality Review:
Reporting results.criteria.Originator's Name: Jimmy Hartley Quality Review: Data Validator/Group Leader: 05-OCT-06 Director: Page 1 34 SAMPLE DATA  
Director:
Page 1 33
 
General Engineering Laboratories                                                                                    NCR Report No;:    368031 Form GEL-NCR                                                                                                            Revision No.:  1 Rev. 06/05 COMPANY- WIDE NONCONFORMANCE REPORT Mo.Day Yr.                              Division:                        Quality Criteria:                      Type:
05-OCT-06                              Radiochemistry                  Specifications                          Process Instrument Type:                        Test / Method:                  Matrix Type:                            Client Code:
GAMMA SPECTROMETER                      EML HASL 300, 4.5.2.3            Solid                                  YANK Batch ID:                              Sample Numbers:                    .
574336                                  See Below Potentially affected work order(s)(SDG): 172275(MSR#06-1282),172873(MSR#06-1313),172875(MSR#06-1312),172879(MSR#06-1311)
Application Issues:
Failed RPD for DUP Specification and Requirements                                          NRG Disposition:
Nonconformance
 
== Description:==
: 1. Failed RPD for DUP: The relative percent difference (172275028     1. K-40 and Pb-212 are naturally occurring nuclides. All other nuclides and 120119654) for K-40 and Pb-212 did not meet the duplication       meet within the duplication criteria. Reporting results.
criteria.
Originator's Name:                                                       Data Validator/Group Leader:
Jimmy Hartley          05-OCT-06 Quality Review:
Director:
Page 1 34
 
SAMPLE DATA


==SUMMARY==
==SUMMARY==
35 GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Report for YANKOO Connecticut Yankee Atomic Power Co.Client SDG: MSR#06-1282 GEL Work Order: 172275 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
35
 
GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report for YANKOO Connecticut Yankee Atomic Power Co.
Client SDG: MSR#06-1282 GEL Work Order: 172275 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 General Engineering Laboratories, LLC standard operating procedures. Please direct any questions to your Project Manager, Cheryl Jones.
Reviewed by 36
 
GENERAL ENGINEERING 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:  October 5, 2006 Contact:    Mr. Jack McCarthy Project:    Soils PO# 002332 Client Sample ID:                  9807-0000-00IF                    Project:      YANK01204 Sample ID:                        172275001                        Client ID: YANK001 Matrix:                            TS                                Vol. Recv.:
Collect Date:                      13-SEP-06 Receive Date:                      21-SEP-06 Collector:                        Client Moisture:                          16.6%
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                            0.917    +/-0.197  0.0541  +/-0.197      0.119        pCi/g            MJH1 10/03/060635 574335      1 Americium-241                    U    0.0336    +/-0.0304    0.027 +/-0.0304      0,0556        pCilg Bismuth-212                              0.332    +/-0.297    0.136  +/-0.297      0.293        pCi/g Bismuth-214                              0.594  +/-0.0918  0.0352  +/-0.
Radiochemistry.
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.
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.
Cheryl Jones Project Manager 3 List of current GEL Certifications as of 16 October 2006 State Certification Alaska UST-062 Arizona AZ0668 Arkansas 88-0651 CLIA 42D0904046 California 01151CA Colorado GenEngLabs Connecticut PH-0169 Dept. of Navy NFESC 413 EPA WG-15J Florida/NELAP E87156 Georgia E87156 (FLINELAP)
Cheryl Jones Project Manager 3
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 C 1641 4 Chain of Custody and Supporting Documentation 5
 
Health Physics Procedure GPP.GGGR-R5104-003-Attachment B-CY-00 I Major Oh Connecticut Yankee Atomic Power Company Chain of Custody Form 2 362 lnjun Hollow Road, East Hampton, CT 06424 860-267-2556 Project Name: Haddam Neck Decommissioning Analyses Requested Lab Use Only Contact Name & Phone: Comments: Jack McCarthy 960-267-3924 Medie Sample Container______________________________
List of current GEL Certifications as of 16 October 2006 State                       Certification Alaska                         UST-062 Arizona                         AZ0668 Arkansas                         88-0651 CLIA                         42D0904046 California                       01151CA Colorado                       GenEngLabs Connecticut                       PH-0169 Dept. of Navy                     NFESC 413 EPA                           WG-15J Florida/NELAP                       E87156 Georgia                   E87156 (FLINELAP)
Code Type Size-Analytical Lab (Name, City, State): Code &Type General Engineering Laboratories Code 2040 Savage Road Charleston, SC 29407 ATT: CherylJones (843-556-8171)
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                         C 1641 4
Priority: " 30 D. E 14 D. 1[ 7 D. <Other: rn Sample Desi ation Date Time --Comment, Preservation Lab Sample ID 9807-0000-0I F 9146161 q M TS C P BP -9807-0000-0eO;I.
 
JA,_ TS C BP _9807-0000-003r.7 TS C BP _"_"_____'" 9807-0000-00 414106 YS3 TS C BP _z 9807-0000-0 Q D& JOST7 TS C BP -9807-0000-0 oJp F 106- TS C BP -9807-0000-0Otq A TS C BP --, 9807"0000"0c3%
Chain of Custody and Supporting Documentation 5
F 1W .:5-. TS C BP 9807-0000-0 o Tf: CTS IC BP _" 9807-0000-0.oo
 
: o. A T" TS C --BP t 9807-0000-0 t &#xfd;. IFlj 10 2 -1. TS C BP ---NOTES: PO #: 002332 MSR #: =-/0 ;7.t Z LTP QA 0 Radwaste QA E Non QA Samples Shipped Via: Internal Container[ Fed Ex Temp.: / Deg. C Tups EHand Custody Seals?1) Relinquihed  
Health Physics Procedure                                                                                   GPP.GGGR-R5104-003-Attachment B-CY-00 I Major Connecticut Yankee Atomic Power Company                                                     Chain of Custody Form                                       2 362 lnjun Hollow Road, East Hampton, CT 06424 860-267-2556 Project Name: Haddam Neck Decommissioning                                                       Analyses Requested               Lab Use Only Contact Name & Phone:                                                                                                               Comments:
.Date/Time 2Nceiv By^ .DteiTime Custody Seal Intact?3) Relinquished by Date/Fime 4 Receive~d BP Date/Time Billof _________
Jack McCarthy       960-267-3924
Y Y] N E Bi5 of LadRiug B 5) Relinquished By Date/Time
______________________________            Medie Code    Sample Type   Container Size-Analytical Lab (Name, City, State):                               Code     &Type General Engineering Laboratories                                             Code 2040 Savage Road Charleston, SC 29407 ATT: CherylJones (843-556-8171)
: 6) Received By Date/Time Healt&#xfd; Physics Procedure GPP-GGGR-R5104-003-Attachment B-CY-00 1 Major Connecticut Yankee Atomic Power Company Chain of Custody Form No. 2006-569 362 Injun Hollow Road, East Hampton, CT 06424 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): Codae &Type General Engineering Laboratories Code 2040 Savage Road Charleston, SC 29407 ATM: Cheryl Jones (843-556-8171)
Priority: " 30 D. E 14 D. 1[ 7 D.                                                         <
Priority:
Other:                                                                                       rn Sample Desi     ation             Date       Time         -       -
[130 D. Z 14 D. [17 D.Other: ri c " Sample Designation Date Time r F -Comment, Preservation Lab Sample ID 9807-0000-0  
* Comment, Preservation   Lab Sample ID Oh 9807-0000-0I F                 9146161       q M         TS       C         BP P           -
*, F= .,:e o _____TS CBP___...___
9807-0000-0eO;I.                     JA,_                 TS       C         BP                                                   _
9807-0000-0 L~ .% q-1 L4-(.p TS C BP ~, __ _______ @'oDn_______
9807-0000-003r.7                                         TS       C         BP                                     _"_"_____'"
9807-0000-0
9807-0000-00                   414106     YS3           TS       C         BP                                                   _z 9807-0000-0               D& Q              JOST7       TS       C         BP                                   -
{
9807-0000-0 oJp F                             106-       TS       C         BP                     -
TS C BP o 9807-0000-0 OLFs l'toL , TS C BP goo 9807-0000-0 j *.f'.o .TS C BP 9807-0000-0 14 IC 110- IOU ockibe' TS C BP )0 9807-0000-0 1 4 -cA D v- TS C BP 98700- %JF6-c4 TS C HP --________ _____9807-0000-0  
9807-0000-0Otq                 *.tA                      TS       C         BP         ,    --
,% ., TS C BP _9807-0000-0 t 'S, C BP , 9807-0000-0 xGW -." TS C BP .9807-0000-0-cre' v 9 tebeQ TS C HP --NOTES: PO #: 002332 MSR #: 04- 1t g-" LTP QA U Radwaste QA U Non QA Samples Shipped Via: Internal Container[ Fed Ex Temp.: _ Deg. C El uPS El Hand Custody Sealep YE NZ 1) Relinquished By Date/Tne 2) ee at/Time OtherCustody SetC Intact?_)_R __in______dByD__e/T
9807"0000"0c3% F                 1W.         :5-.       TS       C         BP 9807-0000-0 o                                             Tf: IC  CTS       BP                                                   _"
__ 2 e z)/O~ 9c Eq l [ Other 3) Relinquished By Date/Time
9807-0000-0.oo
: 4) &#xfd;,eceived 5y Date/Time Y CY N 0 Bill of Lading 9 5) Relinquished By Date/Time
: o.     *j1                        A T"         TS       C -     -BP       t 9807-0000-0 t &#xfd;.IFlj         10 2           -1.         TS       C         BP             -       -   -
: 6) Received By Date/Time Heallb Physics Procedure GPP-GGGR-R.5104-003-Attachment B-CY-001 Major Chain of Custody Form N.20-7 Connecticut Yankee Atomic Power Company No. 2o06-57o 362 Injun Hollow Road, East Hampton, CT 06424 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)
NOTES: PO #: 002332                   MSR #:         ;7.t
Priority:
                                                      =-/0           Z   LTP QA           0   Radwaste QA       E   Non QA         Samples Shipped Via:       Internal Container
El 330 D. Z 14 D.E 7 D.Other; W__CO)_Sample Designation Date Time Comment, Preservation.
[ Fed Ex                 Temp.: /     Deg. C Tups EHand                       Custody Seals?
Lab Sample ID 9807-0000-0?.'
: 1) Relinquihed       .                     Date/Time           2Nceiv       By^   .                     DteiTime                                         Custody Seal Intact?
1 q. rd -0 TS C BP -9807.000.-.mVFt w q4.o. I,.. Z7 TS CD RP.7 , --,-. -.- e ------_ _ _ _ _ __, 9807-0000-0 7,; .; 4Ll&#xfd;L _ D .-. TS C BP ..9807-0000-0" TS C BP -9807-0000-0 " li,-50 TS C BP 106JLP1 5E -TS C1 KP_ __ _NOTES: PO 4: 002332 MSR #: a&#xa3;6 Ii'". I LTP QA E Radwaste QA [ Non QA Samples Shipped Via: Internal Container ED Fed Ex Temp.: ' Deg. C El Hand Custody Sealed 1) Relinquished By Date/Time
: 3) Relinquished by                           Date/Fime           4 Receive~d BP                           Date/Time               Billof     _________         Y]
: 2) 1ve y )atefime Custody SeaY ntact?(?6 Other 3) Relinquished By Date/Time
Y     NE Bi5 of LadRiug B
: 4) Received DaterTime YD] N Bill of Lading #5) Relinquished By Date/Time
: 5) Relinquished By                           Date/Time           6) Received By                           Date/Time
: 6) Received By Date/Time Connecticut Yankee Statement of Work for Analytical Lab Services CY-ISC-SOW-OO1 Figure 1. Sample Check-in List.
 
Received:-.....  
Healt&#xfd; Physics Procedure                                                                                               GPP-GGGR-R5104-003-Attachment B-CY-00 1 Major Connecticut Yankee Atomic Power Company                                                               Chain of Custody Form                               No. 2006-569 362 Injun Hollow Road, East Hampton, CT 06424 860-267-2556 Project Name: Haddam Neck Decommissioning                                                                 Analyses Requested             Lab Use Only Contact Name &Phone:                                                                                                                     Comments:
...,Q.SDG#: 'Work Order Number. _- _____.______________._.-_._____  
Jack McCarthy 860-267-3924                                     Media   Sample   Container Code     Type       Size-Analytical Lab (Name, City, State):                                     Codae     &Type General Engineering Laboratories                                                   Code 2040 Savage Road Charleston, SC 29407 ATM: Cheryl Jones (843-556-8171)
.Shipping Cdatainer 7  Chain of Custody # -9 j6to- JLGf7C 1. Custody Seats.o 0shipping container intact?", Yes 1 ] No AI 414-2. Custody Seals dated and signed? .Yes,[ No [ 1 44.3. Chain-of-Custody recor d pret Ye )I 4. Coolert Imperatur 5. Vermiculite/packing materials is: Wet ( I Dry j',' I /vP 6. Number of samples in shipping conmtainr:  
Priority: [130 D.Z 14 D. [17 D.
"'" 7. Sample holding times exceeded?
Other:                                                                                         ri     c                                                 "
: .f I]NO 8. Samples havei lap Jiazard labels__.custody seals -Z2approp-iate sample labels 9. Samples arei.~J .god condition -leaking-broken .-have air bubbles 10. Were any anomalie.s identified in sarmple receipt? Yes [ ] No,?i 1. escripon of anomalies, (ilude staple numbers): Sample Custodian(Laboratory  
Sample Designation                   Date           Time                                     r     F                       -             Comment, Preservation     Lab Sample ID 9807-0000-0 *, F=.                               o                     CBP___...___                                                     ,:e    G*(,            _____TS 9807-0000-0 L~ .%                 q-1L4-(.p         G*d**        TS       C         BP     ~,       __               _______                     @'oDn_______
.<L 4 -Date, *Telepho.:
9807-0000-0 {                     *.iL4.oto                    TS       C         BP                                                           o 9807-0000-0 OLFs                     l'toL           ,       TS       C         BP                                                           goo 9807-0000-0 j                       *.f'.o       .             TS       C         BP 9807-0000-0 14   IC                 110- IOU     ockibe'       TS       C         BP       )0 9807-0000-0 1**j                      -cA         D4 v-         TS       C         BP 98700-%JF6-c4                                         TS       C         HP                 -       -                           ________                       _____
ed to, On ,By 9 Prep for additional analysis (and reanalysis)
9807-0000-0       ,%                 .,                       TS       C         BP                                                     _
9807-0000-0                         -*r*        t             T**
                                                                'S,     C         BP             ,
9807-0000-0 xGW                           -       ."           TS       C         BP       .
9807-0000-0-cre'     v           9 tebeQ                       TS       C         HP                 --
NOTES: PO #: 002332                         MSR #: 04-     1t g-"             LTP QA             U Radwaste QA           U     Non QA   Samples Shipped Via:       Internal Container
[   Fed Ex               Temp.:     _     Deg. C El uPS El   Hand                   Custody Sealep YE         NZ
: 1) Relinquished
_)_R              By
__in______dByD__e/T                        Date/Tne   __  22)     eee                                  at/Time z)/O~           9c   l EqOther
[     OtherCustody                      SetC Intact?
: 3) Relinquished By                                 Date/Time         4) &#xfd;,eceived 5y                               Date/Time                                           Y CY N 0 Bill of Lading 9 5)Relinquished By                                   Date/Time         6) Received By                                 Date/Time
 
Heallb Physics Procedure                                                                                   GPP-GGGR-R.5104-003-Attachment B-CY-001 Major Connecticut Yankee Atomic Power Company                                                    Chain of Custody Form                             N.20-7 No. 2o06-57o 362 Injun Hollow Road, East Hampton, CT 06424 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 330 D. Z 14 D.E 7 D.
Other;                                                                                   W__CO)_
Sample Designation               Date       Time                                                                             Comment, Preservation. Lab Sample ID 9807-0000-0?.' 1               q. rd -0         -*'"    TS         C         BP 9807.000.-.mVFt     *-        7 ,-- ,-. I,..Z7 w q4.o.                       TS  -.- eCD --- -RP.-                   - _
                                                                                                                  -
_   _     _     _   __,
9807-0000-0 7,; ;          . _4Ll&#xfd;L D.           -. TS         C         BP                       ..
9807-0000-0"7*F                                          TS         C         BP           -
9807-0000-0 -,.3q* "                         li,-50     TS         C         BP 106JLP1     5E       -TS           C1               KP_                                       __       _
NOTES: PO 4: 002332                   MSR #: a&#xa3;6 Ii'".             I   LTP QA         E   Radwaste QA       [   Non QA   Samples Shipped Via:       Internal Container ED Fed Ex                 Temp.: ' Deg. C El Hand                   Custody Sealed 1)Relinquished By                           Date/Time           2)     1ve     y                       )atefime                                   Custody SeaY ntact?
(?6         Other
: 3) Relinquished By                           Date/Time           4) Received                             DaterTime                                       YD]   N 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-OO1 Figure 1. Sample Check-in List.
Date/Tim*  Received:-.....                                                   . ..               ,Q.
SDG#:
  'Work Order Number.           _- _____.______________._.-_._____                                             .
7 Shipping Cdatainer                                 Chain of Custody #               -9     j6to- JLGf7C
: 1.     Custody Seats.o0shipping container intact?",                       Yes   1 ] No       AI 414-
: 2.       Custody Seals dated and signed?     .                             Yes,[     No [ 1   44
.3.         Chain-of-Custody recor d pret                                     Ye     )I
: 4.       Coolert                     Imperatur
: 5.       Vermiculite/packing materials is:                                 Wet   ( I Dry j',' I /vP
: 6.       Number of samples in shipping conmtainr:                                     "'"
: 7.       Sample holding times exceeded?           :         .           Y* I]NO f
: 8. Samples havei Jiazard labels l*ap
__.custody seals               -Z2approp-iate sample labels
: 9. Samples arei
                .~J .god condition                 -leaking
                -broken           .-                 have air bubbles
: 10.     Were any anomalie.s identified in sarmple receipt?               Yes [   ] No,?
i 1.       escripon of anomalies, (ilude staple numbers):
Sample Custodian(Laboratory                   4        -          .<L     Date,
* Telepho.:ed to,                                   On                   ,By 9
 
Prep for additional analysis (and reanalysis)


==Subject:==
==Subject:==
Line 496: Line 1,229:
Date: Tue, 10 Oct 2006 13:47:15 -0400 To: "Cheryl Jones" <cj@gel.com>
Date: Tue, 10 Oct 2006 13:47:15 -0400 To: "Cheryl Jones" <cj@gel.com>
CC: "Clyde Newson" <Newson@CYAPCO.com>
CC: "Clyde Newson" <Newson@CYAPCO.com>
Cheryl, Would prep and analyses the following samples under MSR 0601282 for H-3: 9807-0000-002F 9807-0000-003F (REANALYSIS) 9807-0000-006F 9807-0000-007F 9807-0000-008F (REANALYSIS) 9807-0000-013F (REANALYSIS).
Cheryl, Would prep and analyses the following samples under MSR 0601282 for H-3:
9807-0000-014F TAT IS REQUESTED AT 7 DAYS. RDL IS REQUESTED AT 3 PCI/G (3.OOE+00 PCI/G)Thank you.Jack 10 I of I 10/ 17/2006 2:5 0 PM Data Review Qualifier Definitions 11 Data Review Qualifier Definitions Qualifier Explanation
9807-0000-002F 9807-0000-003F (REANALYSIS) 9807-0000-006F 9807-0000-007F 9807-0000-008F (REANALYSIS) 9807-0000-013F (REANALYSIS).
* 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" Metals-%difference of sample and SD is >10%. Sample concentration must meet flagging criteria B Analytical holding time was exceeded h Preparation or preservation holding time was exceeded J Value is estimated N 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.GENERAL ENGINEERING LABOPATORIES, LLC a Member of THE GEL GROUP, INC.P.O. BOX 30712 Charleston, SC 29417 -2040 Savage Road (29407)Phone (B43) 556-8171 -FeI23) 766-1178 www.gel.com RADIOLOGICAL ANALYSIS 13 Radiochemistry Case Narrative Connecticut Yankee Atomic Power Co. (YANK)Work Order 173769 Method/Analysis Information Product: LSC, Tritium Dist, Solid -3 pCi/g Aiialytical Method: Analytical Batch Number: Sample ID 173769001 173769002 173769003 173769004 173769005 173769006 173769007 1201205181 1201205182 1201205183 1201205184 EPA 906.0 Modified 578364 Client ID 9807-0000-002F 9807-0000-003F 9807-0000-006F 9807-0000-007F 9807-0000-008F 9807-0000-013F 9807-0000-014F Method Blank (MB)173770001(9106-0001-1 12F) Sample Duplicate (DUP)173770001(9106-0001-112F)
9807-0000-014F TAT IS REQUESTED AT 7 DAYS. RDL IS REQUESTED AT 3 PCI/G (3.OOE+00 PCI/G)
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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.Calibration Information:
Thank you
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.
          .Jack 10 I of I                                                                             10/ 17/2006 2:5 0 PM
14 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: 173770001 (9106-0001-112F).
Data Review Qualifier Definitions 11
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.
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
"     Metals-%difference of sample and SD is         >10%. Sample concentration must meet flagging criteria B     Analytical holding time was exceeded h     Preparation or preservation holding time was exceeded J     Value is   estimated N     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.
GENERAL ENGINEERING LABOPATORIES, LLC a Member of THE GEL GROUP, INC.
P.O. BOX 30712 Charleston, SC 29417 - 2040 Savage Road (29407)
Phone (B43) 556-8171 -FeI23) 766-1178 www.gel.com
 
RADIOLOGICAL ANALYSIS 13
 
Radiochemistry Case Narrative Connecticut Yankee Atomic Power Co. (YANK)
Work Order 173769 Method/Analysis Information Product:                       LSC, Tritium Dist, Solid - 3 pCi/g Aiialytical Method:             EPA 906.0 Modified Analytical Batch Number:       578364 Sample ID       Client ID 173769001      9807-0000-002F 173769002      9807-0000-003F 173769003      9807-0000-006F 173769004      9807-0000-007F 173769005      9807-0000-008F 173769006      9807-0000-013F 173769007      9807-0000-014F 1201205181    Method Blank (MB) 1201205182      173770001(9106-0001-1 12F) Sample Duplicate (DUP) 1201205183      173770001(9106-0001-112F) Matrix Spike (MS) 1201205184    Laboratory Control Sample (LCS)
SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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.
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.
14
 
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: 173770001 (9106-0001-112F).
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:
Miscellaneous Information:
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
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.
A nonconformance report (NCR) was not generated for this SDG.Additional Comments The container ids were verified for samples 173769002 (9807-0000-003F) and 173769005 (9807-0000-008F).
Additional Comments The container ids were verified for samples 173769002 (9807-0000-003F) and 173769005 (9807-0000-008F).
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.
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:
Review Validation:
GEL requires all analytical data to be verified by a qualified data validator.
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.
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:
The following data validator verified the information presented in this case narrative:
15 Reviewer/Date:
15
16 SAMPLE DATA  
 
Reviewer/Date:
16
 
SAMPLE DATA


==SUMMARY==
==SUMMARY==
17 GENERAL ENGINEERING 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#06-1282 GEL Work Order: 173769 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.ND The analyte concentration is not detected above the detection limit.The above sample is reported on an "as received" basis.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 General Engineering Laboratories, LLC standard operating procedures.
 
Please direct any questions to your Project Manager, Cheryl Jones.Reviewed by 18 GENERAL ENGINEERING 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: October 18, 2006 Client Sample ID: 9807-0000-002F Proiect: YANK01204 Sample ID: 173769001 ClientID:
17
YANK001 Matrix: TS Vol. Recv.: Collect Date: 13-SEP-06 Receive Date: 21-SEP-06 Collector:
 
Client Parameter Qualifier
GENERAL ENGINEERING 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.
* Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist. Solid -3 pCi/g Tritium U 0.231 +/-1.43 1.19 +/-1.43 2.55 pCi/g DFAI 10/14/062310 578364 1 The following Analytical Methods were performed Method Description I EPA 906.0 Modified Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 +l-Rb. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on an "as received" basis.19 GENERAL ENGINEERING 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: October 18, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-003F Project: YANK0 1204 Sample ID: 173769002 Client ID: YANK001 Matrix: TS Vol. Recv.: Collect Date: 13-SEP-06 Receive Date: 21-SEP-06 Collector:
Client SDG: MSR#06-1282 GEL Work Order: 173769 The Qualifiers in this report are defined as follows:
Client Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid -3 pCi/g Tritium U 0.154 +1-1.28 1.07 +/-1.28 2.29 pCi/g DFAJ 10/14/062326 578364 1 The following Analytical Methods were perfonned Method Description I EPA 906.0 Modified Notes: The Qualifiers in this report are defined as follows: A quality control analyte recovery is outside of specified acceptance criteria< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product 13 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 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 an "as received" basis.20 GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address*:
* A quality control analyte recovery is outside of specified acceptance criteria
362 Injun Hollow Rd.........
**   Analyte is a surrogate compound U   Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.
East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: October 18, 2006 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
ND   The analyte concentration is not detected above the detection limit.
9807-0000-006F 173769003 TS 14-SEP-06 21-SEP-06 Client Project: YANK01204 Client ID: YANK00I Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis ISC, Tritium Dist, Solid -3 pCi/g Tritium U 0.0691 +/-1.64 1.37 +/-1.64 2.94 pCi/g DFAl 10/14/06 2343 578364 1 The following Analytical Methods wereperformed Method Description I EPA 906.0 Modified Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 GCUMS 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 R Sample results are rejected U Analyte was analyzed for, but not detected above the MIL, 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 an "as received" basis.21 GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power." " Address : 362 In jun Hollow Rd.........
The above sample is reported on an "as received" basis.
East Hampton, Connecticut 06424 Report Date: October 18, 2006 Contact: Mr. Jack McCarthy Project:.
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.
Soils PO# 002332 Client Sample ID: 9807-0000-007F Project: YANK01204 Sample ID: 173769004 Client ID: YANK001 Matrix: TS Vol. Recv.: Collect Date: 14-SEP-06 Receive Date: 21 -SEP-06 Collector:
This data report has been prepared and reviewed in accordance with General Engineering Laboratories, LLC standard operating procedures. Please direct any questions to your Project Manager, Cheryl Jones.
Client Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid -3 pCi/g Tritium U 0.00 +/-1.24 1.04 +/-1.24 2.23 pCi/g DFAI 10/14/06 2359 578364 1 The following Analytical Methods were performed Method Description EPA 906.0 Modified Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 an "as received" basis.22 GENERAL ENGINEERING 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: October 18, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-008F Proeect: YANKO1204 Sample ID: 173769005 Client ID: YANK001 Matrix: TS Vol. Recv.: Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector:
Reviewed by 18
Client Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid -3 pCifg Tritium U 0.575 +/-1.33 1.08 +/-1.33 2.31 pCilg DFAI 10/15/06 0015 578364 1 The following Analytical Methods were performed Method Description EPA 906.0 Modified Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 an "as received" basis.23 GENERAL ENGINEERING 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: October 18, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-013F Project: YANK01204 Sample ID: 173769006 Client ID: YANK001 Matrix: TS Vol. Recv.: Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector:
 
Client Parameter Qualifier Result Uncertainty LC TPU MDA 'Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid -3 pCi/g* Tritium U -0.875 +/-1.21 1.07 +/-1.21 2.30 pCi/g DFAI 10/15/06 0032 578364 1 The following Analytical Methods were performed Method Description EPA 906.0 Modified Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 b'y 4X or more 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 an "as received" basis.24 GENERAL ENGINEERING 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: October 18, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-014F Proiect: YANK01204 SamplelD:
GENERAL ENGINEERING 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: October 18, 2006 Contact:      Mr. Jack McCarthy Project:      Soils PO# 002332 Client Sample ID:                 9807-0000-002F               Proiect:     YANK01204 Sample ID:                         173769001                   ClientID: YANK001 Matrix:                           TS                           Vol. Recv.:
173769007 Client ID: YANK001 Matrix: .TS Vol. Recv.: Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector:
Collect Date:                       13-SEP-06 Receive Date:                     21-SEP-06 Collector:                         Client Parameter                   Qualifier
Client Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Disi, Solid -3 pCi/g Tritium U -1.34 +/-1.28 1.16 +/-1.28 2.49 pCi/g DFA1 10115/06 0048 578364 1 The following Analytical Methods were performed Method Description EPA 906.0 Modified Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 an "as received" basis.25 QUALITY CONTROL DATA 26 GENERAL ENGINEERING 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 Reuort Date: October 18, 2006 Page 1 of 2 East Hampton, Connecticut Contact: Mr. Jack McCarthy Workorder:
* Result   Uncertainty       LC     TPU         MDA     Units       DF Analyst Date     Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist. Solid - 3 pCi/g Tritium                           U   0.231       +/-1.43     1.19   +/-1.43     2.55     pCi/g           DFAI 10/14/062310 578364     1 The following Analytical Methods were performed Method             Description I                   EPA 906.0 Modified Notes:
173769 Parmnname NOM Sample Qual QC Units RPD% REC% Range AnIst Date Time Rad Liquid Scintillation Batch 578364 QC1201205182 173770001 DUP Tritium QC1201205184 LCS Tritium QC1201205181 MB Tritium QC1201205183 173770001 MS Tritium U 1.60 U Uncert: +/-5.76 TPU: +/-5.76-1.29+/-6.37+/-6.37 9.95+/-1.86+/-1.86 pCilg 0 (0% -100%) DFA I 10.4 Uncert: TPU: Uncert: TPU: 57.8 U Uncert: TPU: U -0.187+1-1.17+/-1.17 pCi/g pCilg pCi/g 96 (75%-125%)
The Qualifiers in this report are defined as follows
10/15/06 02:10 10/15/06 02:42 10/15/06 01:53 10/15/06 02:26 1.60+/-5.76+1-5.76 48.5+/-9.94+/-9.97 84 (75%-125%)
* A quality control analyte recovery is outside of specified acceptance criteria
Notes: The Qualifiers in this report are defined as follows: A B BD C D H J N/A R U U'X Y hi A quality control analyte recovery is outside of specified acceptance criteria Result is less than value reported Result is greater than value reported The TIC is a suspected aldol-condensation product Target analyte was detected in the associated blank Results are either below the MDC or tracer recovery is low Analyte has been confirmed by GCIMS 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 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 QC Samples were not spiked with this compound RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL Preparation or preservation holding time was exceeded '27 GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.geLcom QC Summary Workorder:
  <     Result is less than value reported
173769 Page 2 of 2 Parmname NOM Sample Qual QC Units RPD% REC% Range AnIst Date Time'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.^ 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.
  >     Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.
Wheore 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.28 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3 (DQA RESULTS)
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 +l-Rb. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on an "as received" basis.
19
 
GENERAL ENGINEERING 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: October 18, 2006 Contact:     Mr. Jack McCarthy Project:     Soils PO# 002332 Client Sample ID:                 9807-0000-003F               Project:     YANK0 1204 Sample ID:                         173769002                   Client ID: YANK001 Matrix:                           TS                           Vol. Recv.:
Collect Date:                       13-SEP-06 Receive Date:                       21-SEP-06 Collector:                         Client Parameter                   Qualifier   Result   Uncertainty       LC     TPU         MDA     Units       DF Analyst Date     Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid - 3 pCi/g Tritium                         U     0.154       +1-1.28     1.07   +/-1.28       2.29     pCi/g           DFAJ   10/14/062326 578364   1 The following Analytical Methods were perfonned Method             Description I                   EPA 906.0 Modified Notes:
The Qualifiers in this report are defined as follows:
A quality control analyte recovery is outside of specified acceptance criteria
  < Result is less than value reported
  >     Result is greater than value reported A The TIC is a suspected aldol-condensation product 13   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 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 an "as received" basis.
20
 
GENERAL ENGINEERING 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: October 18, 2006 Contact:     Mr. Jack McCarthy Project:     Soils PO# 002332 Client Sample ID:                 9807-0000-006F                Project:    YANK01204 Sample ID:                        173769003                    Client ID: YANK00I Matrix:                           TS                            Vol. Recv.:
Collect Date:                       14-SEP-06 Receive Date:                      21-SEP-06 Collector:                         Client Parameter                    Qualifier   Result   Uncertainty       LC     TPU         MDA     Units     DF Analyst Date     Time Batch Mtd Rad Liquid Scintillation Analysis ISC, Tritium Dist,Solid - 3 pCi/g Tritium                           U   0.0691       +/-1.64     1.37   +/-1.64     2.94     pCi/g           DFAl   10/14/06 2343 578364 1 The following Analytical Methods wereperformed Method             Description I                   EPA 906.0 Modified Notes:
The Qualifiers in this report are defined as follows:
* A quality control analyte recovery is outside of specified acceptance criteria
  <     Result is less than value reported
  >     Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 GCUMS 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 R Sample results are rejected U Analyte was analyzed for, but not detected above the MIL, 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 an "as received" basis.
21
 
GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Company:     Connecticut Yankee Atomic Power
        " " Address
              .        :   362 In jun Hollow Rd.........
East Hampton, Connecticut 06424                                             Report Date: October 18, 2006 Contact:     Mr. Jack McCarthy Project:. Soils PO# 002332 Client Sample ID:                   9807-0000-007F             Project:     YANK01204 Sample ID:                           173769004                 Client ID: YANK001 Matrix:                             TS                         Vol. Recv.:
Collect Date:                       14-SEP-06 Receive Date:                       21 -SEP-06 Collector:                           Client Parameter                     Qualifier   Result     Uncertainty     LC     TPU       MDA     Units       DF Analyst Date     Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid - 3 pCi/g Tritium                           U     0.00         +/-1.24     1.04   +/-1.24   2.23     pCi/g           DFAI   10/14/06 2359 578364 1 The following Analytical Methods were performed Method               Description EPA 906.0 Modified Notes:
The Qualifiers in this report are defined as follows:
* A quality control analyte recovery is outside of specified acceptance criteria
  <     Result is less than value reported
  >     Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 an "as received" basis.
22
 
GENERAL ENGINEERING 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: October 18, 2006 Contact:     Mr. Jack McCarthy Project:     Soils PO# 002332 Client Sample ID:                   9807-0000-008F               Proeect:   YANKO1204 Sample ID:                         173769005                   Client ID: YANK001 Matrix:                             TS                           Vol. Recv.:
Collect Date:                       14-SEP-06 Receive Date:                       21-SEP-06 Collector:                         Client Parameter                 Qualifier   Result   Uncertainty       LC     TPU         MDA     Units     DF Analyst Date     Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid - 3 pCifg Tritium                         U     0.575         +/-1.33     1.08   +/-1.33     2.31     pCilg           DFAI   10/15/06 0015 578364 1 The following Analytical Methods were performed Method             Description EPA 906.0 Modified Notes:
The Qualifiers in this report are defined as follows:
* A quality control analyte recovery is outside of specified acceptance criteria
  <   Result is less than value reported
  >   Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 an "as received" basis.
23
 
GENERAL ENGINEERING 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: October 18, 2006 Contact:     Mr. Jack McCarthy Project:     Soils PO# 002332 Client Sample ID:                 9807-0000-013F               Project:     YANK01204 Sample ID:                         173769006                   Client ID: YANK001 Matrix:                           TS                           Vol. Recv.:
Collect Date:                       14-SEP-06 Receive Date:                     21-SEP-06 Collector:                         Client Parameter                   Qualifier   Result   Uncertainty       LC     TPU         MDA     'Units       DF Analyst Date     Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid - 3 pCi/g
* Tritium                           U   -0.875     +/-1.21     1.07   +/-1.21     2.30     pCi/g           DFAI 10/15/06 0032 578364   1 The following Analytical Methods were performed Method             Description EPA 906.0 Modified Notes:
The Qualifiers in this report are defined as follows:
* A quality control analyte recovery is outside of specified acceptance criteria
  <     Result is less than value reported
  >     Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 b'y 4X or more 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 an "as received" basis.
24
 
GENERAL ENGINEERING 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: October 18, 2006 Contact:     Mr. Jack McCarthy Project:     Soils PO# 002332 Client Sample ID:                 9807-0000-014F               Proiect:     YANK01204 SamplelD:                           173769007                   Client ID:   YANK001 Matrix: .                         TS                           Vol. Recv.:
Collect Date:                       18-SEP-06 Receive Date:                       21-SEP-06 Collector:                         Client Parameter                   Qualifier   Result   Uncertainty       LC     TPU         MDA     Units       DF Analyst Date     Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Disi, Solid - 3 pCi/g Tritium                         U     -1.34       +/-1.28       1.16   +/-1.28     2.49     pCi/g           DFA1   10115/06 0048 578364 1 The following Analytical Methods were performed Method             Description EPA 906.0 Modified Notes:
The Qualifiers in this report are defined as follows:
* A quality control analyte recovery is outside of specified acceptance criteria
  <   Result is less than value reported
  >   Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 an "as received" basis.
25
 
QUALITY CONTROL DATA 26
 
GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary                               Reuort Date: October 18, 2006 Client:           Connecticut Yankee Atomic Power                                                                           Page 1 of 2 362 Injun Hollow Rd East Hampton, Connecticut Contact:           Mr. Jack McCarthy Workorder:         173769 Parmnname                                       NOM             Sample Qual             QC   Units   RPD%   REC%       Range   AnIst   Date Time Rad Liquid Scintillation Batch           578364 QC1201205182     173770001 DUP Tritium                                                   U           1.60   U           -1.29   pCilg      0          (0% - 100%) DFA I    10/15/06 02:10 Uncert:        +/-5.76            +/-6.37 TPU:          +/-5.76            +/-6.37 QC1201205184        LCS Tritium                                        10.4                                      9.95    pCi/g            96  (75%-125%)           10/15/06 02:42 Uncert:                             +/-1.86 TPU:                             +/-1.86 QC1201205181        MB Tritium                                                                      U         -0.187     pCilg                                    10/15/06 01:53 Uncert:                            +1-1.17 TPU:                              +/-1.17 QC1201205183      173770001  MS Tritium                                        57.8      U          1.60                48.5    pCi/g           84  (75%-125%)           10/15/06 02:26 Uncert:         +/-5.76             +/-9.94 TPU:        +1-5.76            +/-9.97 Notes:
The Qualifiers in this report are defined as follows:
A quality control analyte recovery is outside of specified acceptance criteria Result is less than value reported Result is greater than value reported A    The TIC is a suspected aldol-condensation product B    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 GCIMS 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 R    Sample results are rejected U    Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.
U' 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 RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL hi    Preparation or preservation holding time was exceeded       '
27
 
GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.geLcom QC Summary Workorder:       173769                                                                                                             Page 2 of 2 Parmname                                         NOM             Sample Qual             QC     Units RPD%           REC%         Range AnIst Date Time
'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.
^ 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.
Wheore 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.
28
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3 (DQA RESULTS)
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3A (PRELIMINARY DATA REVIEW)
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3A (PRELIMINARY DATA REVIEW)
PRELIMINARY DATA REVIEW FORM Survey Unit: 9807-0000 Survey Unit Name: Subsurface Area Associated with the Southwest Site Storage area Classification
 
: B Survey Media: Soil Type of Survey: Final Status Survey Type of Measurement:
PRELIMINARY DATA REVIEW FORM Survey Unit: 9807-0000 Survey Unit Name: Subsurface Area Associated with the Southwest Site Storage area Classification : B Survey Media: Soil Type of Survey: Final Status Survey Type of Measurement: Radionuclide Specific lumber of Measurements : 25 BASIC STATISTICAL QUANTITIES Cs-137 Target Level (pCi/g)     5.3 8E+00 Minimum Value:       -2.76E-02 Maximum Value:       3.50E+00 Mean :     1.49E-01 Median :     8.18E-03 Standard Deviation:     6.98E-01 Reported Results Cs-137 Concentration            Fraction of Sample Identification       (pCi/g)    Detect?  Target Level 9807-0000-001 F         -7.91E-03                  -0.001 9807-0000-002F          -2.76E-02                -0.005 9807-0000-003F            4.02E-02                  0.007 9807-0000-004F          - 1.26E-03                0.000 9807-0000-005F            1.87E-02                  0.003 9807-0000-006F          -8.34E-03                -0.002 9807-0000-007F          - 1.54E-02                -0.003 9807-0000-008F          -1.36E-02                -0.003 9807-0000-009F            3.30E-02                  0.006 9807-0000-01OF          2.86E-02                  0.005 9807-0000-01 IF          -2.32E-02                -0.004 9807-0000-012F          4.36E-02                   0.008 9807-0000-013F          -2.5 1E-03                 0.000 9807-0000-014F            8.18E-03                  0.002 9807-0000-015F            1.29E-02                 0.002 9807-0000-016F            6.01E-03                  0.001 9807-0000-017F            3.34E-02                 0.006 9807-0000-018F          2.39E-03                   0.000 9807-0000-019F          -3.24E-04                  0.000 9807-0000-020F          3.53E-02                   0.007 Submitted by/Date                                                                        1 of o 1
Radionuclide Specific lumber of Measurements
 
: 25 BASIC STATISTICAL QUANTITIES Cs-137 Target Level (pCi/g) 5.3 8E+00 Minimum Value: -2.76E-02 Maximum Value: 3.50E+00 Mean : 1.49E-01 Median : 8.18E-03 Standard Deviation:
PRELIMINARY DATA REVIEW FORM Reported Results Cs-137 Concentration          Fraction of Sample Identification    (pCi/g)      Detect? Target Level 9807-0000-021F        0.00E+00                0.000 9807-0000-022F        2.88E-02        +        0.005 9807-0000-023F        2.56E-02        +        0.005 9807-0000-024F        1.18E-02                0.002 9807-0000M025F        3.50E+00        +        0.651 Submitted by/Da2o                                              2 ofl1
6.98E-01 Sample Identification 9807-0000-001 F 9807-0000-002F 9807-0000-003F 9807-0000-004F 9807-0000-005F 9807-0000-006F 9807-0000-007F 9807-0000-008F 9807-0000-009F 9807-0000-01OF 9807-0000-01 IF 9807-0000-012F 9807-0000-013F 9807-0000-014F 9807-0000-015F 9807-0000-016F 9807-0000-017F 9807-0000-018F 9807-0000-019F 9807-0000-020F Reported Results Cs-137 Concentration (pCi/g)-7.91E-03-2.76E-02 4.02E-02-1.26E-03 1.87E-02-8.34E-03-1.54E-02-1.36E-02 3.30E-02 2.86E-02-2.32E-02 4.36E-02-2.5 1E-03 8.18E-03 1.29E-02 6.01E-03 3.34E-02 2.39E-03-3.24E-04 3.53E-02 Fraction of Detect? Target Level-0.001-0.005 0.007 0.000 0.003-0.002-0.003-0.003 0.006 0.005-0.004 0.008 0.000 0.002 0.002 0.001 0.006 0.000 0.000 0.007 Submitted by/Date o 1 of 1 PRELIMINARY DATA REVIEW FORM Sample Identification 9807-0000-021F 9807-0000-022F 9807-0000-023F 9807-0000-024F 9807-0000M025F Reported Results Cs-137 Concentration (pCi/g)0.00E+00 2.88E-02 2.56E-02 1.18E-02 3.50E+00 Fraction of Detect? Target Level 0.000+ 0.005+ 0.005 0.002+ 0.651 Submitted by/Da2o 2 ofl1 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3B (GRAPHICAL REPRESENTATION OF DATA)
 
FREQUENCY PLOT FOR CESIUM-137 Survey Unit: 9807-0000 Subsurface.Area Associated with the Survey Unit Name: Southwest Site Storage Area Mean: 1.49E-01 pCi/g Frequency Plot For Cs-137 25 20= 15 Er 10 U-5 0-2.76E-02 8.47E-01 1.72E+00 2.60E+00 3.47E+00 4.35E+00 Upper End Value (pCilg)Upper End Observation Observation Value Frequency Frequency-2.76E-02 1 4%8.47E-01 23 92%1.72E+00 0 0%2.60E+00 0 0%3.47E+00 0 0%4.35E+00 1 4%Total: 25 100%Submitted by/Da/e/I 1J21 job RevittJdbID yIte 1o 1 of 1 QUANTILE PLOT FOR CESIUM-137 Survey Unit: 9807-0000 Subsurface Area Associated with the Survey Unit Name: Southwest Site Storage Area Mean: 1.49E-01 pCi/g Quantile Plot For Cs-1 37 0)0.C-)3.47E+00 2.97E+00 2.47E+00 1.97E+00 1.47E+00 9.70E-01 4.70E-01-3. OOE-02 0 10 20 30 40 50 60 70 80 90 100 Percentage Cs-137 Rank Percentage
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3B (GRAPHICAL REPRESENTATION OF DATA)
-2.76E-02 1 3%-2.32E-02 2 10%-1.54E-02 3 17%-1.36E-02 4 23%-8.34E-03 5 30%-7.91 E-03 6 37%-2.51 E-03 7 43%-1.26E-03 8 50%-3.24E-04 9 57%0.00E+00 10 63%2.39E-03 11 70%6.01E-03 12 77%8.18E-03 13 83%1.18E-02 14 90%1.29E-02 15 97%1.87E-02 16 97%2.56E-02 17 97%2.86E-02 18 97%2.88E-02 19 97%3.30E-02 20 97%3.34E-02 21 97%3.53E-02 22 97%4.02E-02 23 97%4.36E-02 24 97%3.50E+00 25 97%Submitted by/Datv i -t /iiIziIoe;o Revi~<~d by/)~ate SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3C (SIGN TEST)
 
Connecticut Yankee Decommissioning Project Health Physics Procedure GPP-GGGR-R5121-001 Attachment A, Rev CY-001 MAJOR Sign Test Calculation Sheet For A Single Radionuclide or Gross Activity Measurements Survey Area Number: 9807 Survey Unit Number: 0000 Survey Area Name: Subsurface Area associated with the Southwest Site Storage Area WPIR#: 2006-0038 Classification:
FREQUENCY PLOT FOR CESIUM-137 Survey Unit: 9807-0000 Subsurface.Area Associated with the Survey Unit Name: Southwest Site Storage Area Mean: 1.49E-01      pCi/g Frequency Plot For Cs-137 25 20
B Type I (cx error): 0.05 (N): 25 Radionuclide:
            = 15 Er 10 U-5 0
Cs-137 DCGL: 5.38 Results (pCi/g) DCGL -Results Sign-7.9 1E-03 5.39E+00-2.76E-02 5.41E+00 1 4.02E-02 5.34E+00 I-1.26E-03 5.38E+O0 1 1.87E-02 5.36E+00-8.34E-03 5.39E+00-1.54E-02 5.40E+00-1 .36E-02 5.39E+00 1 3.30E-02 5.35E+00 2.86E-02 5.35E+00 I-2.32E-02 5.40E+00 1 4.36E-02 5.34E+00 1-2.51E-03 5.38E+00 8.18E-03 5.37E+00 1.29E-02 5.37E+00 1 6.01E-03 5.37E+00 1 3.34E-02 5.35E+00 2.39E-03 5.38E+00 1-3.24E-04 5.38E+00 1 3.53E-02 5.34E+00 Page 1 of I Connecticut Yankee Decommissioning Project Health Physics Procedure GPP-GGGR-R5121-001 Attachment A, Rev CY-001 MAJOR Survey Area Number: 9807 Survey Unit Number: 0000 Survey Area Name: Subsurface Area associated with the Southwest Site Storage Area WPIR#: 2006-0038 Classification:
                  -2.76E-02 8.47E-01      1.72E+00 2.60E+00 3.47E+00 4.35E+00 Upper End Value (pCilg)
B Type I (cc error): 0.05 (N): 25 Radionuclide:
Upper End    Observation  Observation Value      Frequency    Frequency
Cs-137 DCGL: 5.38 Results (pCi/g) DCGL -Results Sign 0.OOE+00 5.38E+00 1 2.88E-02 5.35E+00 1 2.56E-02 5.35E+00 1 1.18E-02 5.37E+00 1 3.50E+00 1.88E+00 1 Number of positive differences (S+): 25 Critical Value: 17 Performed by: -Independent Review Survey Unit Meets Acceptance Criterion Date: /A!/o 6 Date: ii/z, ao0.\Page 1 of 1 SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3D (QC SPLIT RESULTS)
                            -2.76E-02          1            4%
Health Phvsics Procedure 24265-000-GPP-GGGR-R5]24-000-Rev.CY-000 Attachment A HelhPAisPoeue-46-0-P-GRR 4O0-e.Y00Atcmn Split Sample Assessment Form Survey Area#: 9807 Survey.Unit  
8.47E-01        23          92%
#: 0000 Survey Unit name: Subsurface Area Associated with the Southwest Site Storage Area Sample Plan or WPIR#: 2005-0038 IvSML#: 9807-0000-012 Sample
1.72E+00         0            0%
2.60E+00          0            0%
3.47E+00          0            0%
4.35E+00          1            4%
Total:        25          100%
Submitted by/Da/e
                    /I1J21 job RevittJdbIDyIte                                                                1o 1 of 1
 
QUANTILE PLOT FOR CESIUM-137 Survey Unit: 9807-0000 Subsurface Area Associated with the Survey Unit Name: Southwest Site Storage Area Mean:     1.49E-01     pCi/g Quantile Plot For Cs-1 37 3.47E+00 2.97E+00
: 0)  2.47E+00 1.97E+00 0.
1.47E+00 9.70E-01 C-) 4.70E-01
            -3.OOE-02 0       10        20    30      40      50      60 70  80 90 100 Percentage Cs-137        Rank        Percentage
                                  -2.76E-02          1              3%
                                  -2.32E-02          2              10%
                                  -1.54E-02          3             17%
                                  -1.36E-02          4             23%
                                  -8.34E-03          5            30%
                                  -7.91 E-03        6            37%
                                  -2.51 E-03        7            43%
                                  -1.26E-03          8            50%
                                  -3.24E-04          9            57%
0.00E+00         10            63%
2.39E-03        11            70%
6.01E-03        12            77%
8.18E-03        13              83%
1.18E-02        14            90%
1.29E-02        15            97%
1.87E-02         16            97%
2.56E-02        17            97%
2.86E-02         18            97%
2.88E-02         19            97%
3.30E-02         20            97%
3.34E-02         21            97%
3.53E-02        22            97%
4.02E-02        23            97%
4.36E-02        24            97%
3.50E+00         25            97%
i      -t  /
Submitted by/Datv iiIziIoe;o Revi~<~d by/)~ate
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3C (SIGN TEST)
 
Connecticut Yankee Decommissioning Project                    GPP-GGGR-R5121-001 Attachment A, Health Physics Procedure                                                      Rev CY-001 MAJOR Sign Test Calculation Sheet For A Single Radionuclide or Gross Activity Measurements Survey Area Number: 9807 Survey Unit Number: 0000 Survey Area Name: Subsurface Area associated with the Southwest Site Storage Area WPIR#: 2006-0038 Classification: B        Type I (cx error): 0.05  (N): 25 Radionuclide: Cs-137      DCGL: 5.38 Results (pCi/g)        DCGL - Results                Sign
                    -7.9 1E-03              5.39E+00
                    -2.76E-02              5.41E+00                    1 4.02E-02                5.34E+00                    I
                    -1.26E-03              5.38E+O0                    1 1.87E-02              5.36E+00
                    -8.34E-03              5.39E+00
                    -1.54E-02              5.40E+00
                    -1 .36E-02              5.39E+00                    1 3.30E-02                5.35E+00 2.86E-02               5.35E+00                     I
                    -2.32E-02              5.40E+00                    1 4.36E-02               5.34E+00                     1
                    -2.51E-03               5.38E+00 8.18E-03              5.37E+00 1.29E-02              5.37E+00                     1 6.01E-03              5.37E+00                     1 3.34E-02               5.35E+00 2.39E-03              5.38E+00                     1
                    -3.24E-04              5.38E+00                     1 3.53E-02               5.34E+00 Page 1 of I
 
Connecticut Yankee Decommissioning Project                          GPP-GGGR-R5121-001 Attachment A, Health Physics Procedure                                                          Rev CY-001 MAJOR Survey Area Number: 9807 Survey Unit Number: 0000 Survey Area Name: Subsurface Area associated with the Southwest Site Storage Area WPIR#: 2006-0038 Classification: B          Type I (cc error): 0.05        (N): 25 Radionuclide: Cs-137      DCGL: 5.38 Results (pCi/g)          DCGL - Results                    Sign 0.OOE+00                 5.38E+00                         1 2.88E-02                 5.35E+00                         1 2.56E-02                  5.35E+00                         1 1.18E-02                5.37E+00                         1 3.50E+00                  1.88E+00                         1 Number of positive differences (S+): 25 Critical Value: 17            Survey Unit Meets Acceptance Criterion Performed by:            -                         Date:    /A!/o 6
                                  \
Independent Review                                  Date:    ii/z, ao0.
Page 1 of 1
 
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3D (QC SPLIT RESULTS)
 
Health Phvsics Procedure                 24265-000-GPP-GGGR-R5]24-000-Rev.CY-000 Attachment A HelhPAisPoeue-46-0-P-GRR                                             4O0-e.Y00Atcmn Split Sample Assessment Form Survey Area#: 9807       Survey.Unit #: 0000   Survey Unit name: Subsurface Area Associated with the Southwest Site Storage Area Sample Plan or WPIR#: 2005-0038                                       IvSML#: 9807-0000-012 Sample


== Description:==
== Description:==
ComparisonDof split samples collected from sample measurement      Plocation#12 and analyzed using gamma spectroscopy by off-site Vendor Laboratory. The standard sample was 9807-0000-0012F, the comparison sample was 9807-0000-012F5.
STANDARD                                                  COMPARISON Radionuclide  Activity  Standard  Resolution    Agreement      Activity    Standard    Comparison        Acceptable Value      Error                    Range        Value        Error          Ratio          (YIN)
K-40        13.9      5.65E-1      25      0.75  -1.33      13.7      5.70E-1          0.99            Y Comments/Corrective Actions: Not enough Cs-137 to              Table is provided to show acceptance criteria yield an acceptable Resolution                                  used to assess split samples.
Resolution      Agreement Range 4-7              0.5 -2.0 8-15              0.6 - 1.66 16-50            0.75 - 1.33 51-200            0.80 - 1.25
                                                                            >200            0.85- 1.18 ormed By:
                    /
(
2 Page 1 of 1


ComparisonDof split samples collected from sample measurement Plocation#12 and analyzed using gamma spectroscopy by off-site Vendor Laboratory.
Health Physics Procedure                   24265-000-GPP-GGGR-R5124-000-Rev.CY-000 Attachment A Health Physics Procedure                   24265-000-GPP-GGGR-R5 124-000-Rev.CY-000 Attachment A Split Sample Assessment Form Survey Area#: 980.7         Survey Unit #: 0000   Survey Unit name: Subsurface Area Associated with the Southwest Site Storage Area Sample Plan or WPIR#: 2005-0038                                         SML#: 9807-0000-018 Sample
The standard sample was 9807-0000-0012F, the comparison sample was 9807-0000-012F5.
STANDARD COMPARISON Radionuclide Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (YIN)K-40 13.9 5.65E-1 25 0.75 -1.33 13.7 5.70E-1 0.99 Y Comments/Corrective Actions: Not enough Cs-137 to yield an acceptable Resolution Table is provided to show acceptance criteria used to assess split samples.Resolution 4-7 8-15 16-50 51-200>200 Agreement Range 0.5 -2.0 0.6 -1.66 0.75 -1.33 0.80 -1.25 0.85- 1.18 ormed By:/2 (Page 1 of 1 Health Physics Procedure 24265-000-GPP-GGGR-R5124-000-Rev.CY-000 Attachment A Health Physics Procedure 24265-000-GPP-GGGR-R5 124-000-Rev.CY-000 Attachment A Split Sample Assessment Form Survey Area#: 980.7 Survey Unit #: 0000 Survey Unit name: Subsurface Area Associated with the Southwest Site Storage Area Sample Plan or WPIR#: 2005-0038 SML#: 9807-0000-018 Sample


== Description:==
== Description:==
Comparison of split samples collected from sample measurement-location #18 and analyzed using gamma spectroscopy by off-site Vendor Laboratory. The standard sample was 9807-0000-018F, the comparison sample was 9807-0000-01FS.
STANDARD                                                COMPARISON Radionuclide      Activity    Standard Resolution  Agreement    Activity    Standard    Comparison    Acceptable Value      Error                  Range      Value        Error        Ratio        (YIN)
K-40            13.2    5.55E-1      24      0.75- 1.33      13.3      6.05E-1        1.00          Y Comments/Corrective Actions: Not enough Cs-137 to                Table is provided to show acceptance criteria yield an acceptable Resolution                                    used to assess split samples.
Resolution    Agreement Range 4-7            0.5 -2.0 8-15          0.6 - 1.66 16 -50        0.75 - 1.33 51 -200        0.80 - 1.25
                                                                              >200          0.85- 1.18 C_/--Ie'6 ,&#xa2;'---
I Page 1 of I


Comparison of split samples collected from sample measurement-location
Health Physics Procedure                   24265-000-GPP-GGGR-R5124-000-Rev.CY-000 Attachment A Health Physics Procedure                   24265-000-GPP-GGGR-R5 124-000-Rev.CY-000 Attachment A Split Sample Assessment Form Survey Area#: 9807         Survey Unit #: 0000     Survey Unit name: Subsurface Area Associated with the Southwest Site Storage Area Sample Plan or WPIIR#: 2005-0038                                         SML#: 9807-0000-024 Sample
#18 and analyzed using gamma spectroscopy by off-site Vendor Laboratory.
The standard sample was 9807-0000-018F, the comparison sample was 9807-0000-01FS.
STANDARD COMPARISON Radionuclide Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (YIN)K-40 13.2 5.55E-1 24 0.75- 1.33 13.3 6.05E-1 1.00 Y Comments/Corrective Actions: Not enough Cs-137 to yield an acceptable Resolution Table is provided to show acceptance criteria used to assess split samples.Resolution 4-7 8-15 16 -50 51 -200>200 Agreement Range 0.5 -2.0 0.6 -1.66 0.75 -1.33 0.80 -1.25 0.85- 1.18 C_/-- Ie'6 ,&#xa2;'---I Page 1 of I Health Physics Procedure 24265-000-GPP-GGGR-R5124-000-Rev.CY-000 Attachment A Health Physics Procedure 24265-000-GPP-GGGR-R5 1 24-000-Rev.CY-000 Attachment A Split Sample Assessment Form Survey Area#: 9807 Survey Unit #: 0000 Survey Unit name: Subsurface Area Associated with the Southwest Site Storage Area Sample Plan or WPIIR#: 2005-0038 SML#: 9807-0000-024 Sample


== Description:==
== Description:==
Comparison of split samples collected from sample measurement location #24 and analyzed using gamma spectroscopy by off-site Vendor Laboratory. The standard sample was 9807-0000-024F, the comparison sample was 9807-0000-024FS.
STANDARD                                                    COMPARISON Radionuclide    Activity    Standard  Resolution    Agreement      Activity    Standard    Comparison      Acceptable Value        Error                    Range        Value        Error        Ratio          (Y/N)
K-40        12.1      5.40E-1      22        0.75-1.33      13.6        4.68E-1        1.12            Y t                      I            I              F          +/-            F              F F          4            +              F          +          4                F
              +          F          4            +              F          4-          4                F Comments/Corrective Actions: Not enough Cs-137 to                  Table is provided to show acceptance criteria yield an acceptable Resolution                                    used to assess split samples.
R1solution    Agreement Range 4-7            0.5 -2.0 8-15          0.6 - 1.66 16-50          0.75 - 1.33 51 -200        0.80 - 1.25
                                                                                >200          0.85- 1.18
                    /
Page 1 of I


Comparison of split samples collected from sample measurement location #24 and analyzed using gamma spectroscopy by off-site Vendor Laboratory.
SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3E (COMPASS DQA WITH POWER CURVE)
The standard sample was 9807-0000-024F, the comparison sample was 9807-0000-024FS.
STANDARD COMPARISON Radionuclide Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (Y/N)K-40 12.1 5.40E-1 22 0.75-1.33 13.6 4.68E-1 1.12 Y t I I F +/- F F F 4 + F + 4 F+ F 4 + F 4- 4 F Comments/Corrective Actions: Not enough Cs-137 to yield an acceptable Resolution Table is provided to show acceptance criteria used to assess split samples.R1solution 4-7 8-15 16-50 51 -200>200 Agreement Range 0.5 -2.0 0.6 -1.66 0.75 -1.33 0.80 -1.25 0.85- 1.18/Page 1 of I SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3E (COMPASS DQA WITH POWER CURVE)  
~DQA Surface Soil Report A s.s.e_ _s.s.me nt. s u. m m a ry ....... .... ...... ..........................
....... ............................................
............
_.........
Site: Planner(s):
Survey Unit Name: Report Number: Survey Unit Samples: Reference Area Samples: Test Performed:
Judgmental Samples: Assessment


==
                        ~DQA                              Surface Soil Report A s.s.e_ _s.s.me nt.s u.m ma ry          . ...... ....................................
Conclusion:==
_.........                          ....... ............................................
                                                                                                      ............
Site:                                        9807-0000 FSS Planner(s):                                  McCarthy Survey Unit Name:                            Subsurface Area Associated with the Southwest Site Report Number:                              1 Survey Unit Samples:                        25 Reference Area Samples:                      0 Test Performed:                              Sign                              Test Result:                  Not Performed Judgmental Samples:                          0                                  EMC Result:                   Not Performed Assessment


9807-0000 FSS McCarthy Subsurface Area Associated with the Southwest Site 1 25 0 Sign Test Result: Not Performed 0 EMC Result: Not Performed Reject Null Hypothesis (Survey Unit PASSES)Retrospective Power Curve=I-1 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0,1 0 t--0 Soil Prospective Power LBGR.DCGL 2 3 4 5 Concentration (p Ci/g), including background M 1-beta ....Actual Power Estimated Power-- -,Retrospecti.,e Power 6 COMPASS vl.0.0 11t/20/2006 Page I}}
== Conclusion:==
Reject Null Hypothesis (Survey Unit PASSES)
Retrospective Power Curve 1
0.9
                    =  0.8 0.7 0.6 0.5 0.4 t--
0.3 I- 0.2 0,1 0
0                               2           3             4           5                 6 Soil Concentration (pCi/g), including background Prospective Power            M   1-beta                 .... Actual Power LBGR.                              Estimated Power DCGL                      -- -   ,Retrospecti.,ePower COMPASS vl.0.0                                                 11t/20/2006                                                     Page I}}

Revision as of 01:49, 23 November 2019

Final Status Survey Final Report Phase V, Appendix A11, Survey Unit Release Record 9807-0000, Subsurface Area Associated with the Southwest Site Storage Area.
ML072900174
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 12/31/2006
From: Mccarthy J
Connecticut Yankee Atomic Power Co
To:
NRC/FSME
References
9807-0000
Download: ML072900174 (174)
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.CYAPCO FINAL STATUS SURVEY RELEASE RECORD SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 Prepared By: Date: ,L.,/co6 FSS Engineer J Reviewed Bv Datell/ZiJO(

Approved By:_____________ Date: 1 12(.,/.06 Technical Support Manager Revision 0

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD TABLE OF CONTENTS

1. SURVEY UNIT DESCRIPTION ...................................................... 3
2. CLA SSIFICATION BASIS ................................................................ 3
3. DATA QUALITY OBJECTIVES (DQO) ......................................... 5
4. SU RV EY D ESIG N ............................................................................. 8
5. SURVEY IM PLEM ENTATION .......................................................... 11
6. SU RV EY RESU LTS ........................................................................ 12
7. Q UA LITY CON TRO L ...................................................................... 14
8. INVESTIGATIONS AND RESULTS ............................................. 14
9. REMEDIATION AND RESULTS .................................................. 14
10. CHANGES FROM THE FINAL STATUS SURVEY PLAN ...... 14
11. DATA QUALITY ASSESSMENT (DQA) ....................................... 14
12. AN O M A LIE S .................................................................................. 15
13. C ON CLU SIO N ................................................................................. 15
14. ATTACHMENTS ........................................ ... 16 14.1 Attachment 1 - Figures (4 pages including cover) 14.2 Attachment 2 - Laboratory Data (137 pages including cover) 14.3 Attachment 3 - DQA Results (16 pages including covers)

TOTAL 173 Revision I

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD

1. SURVEY UNIT DESCRIPTION Survey Unit 9807-0000 (Subsurface Area associated with the Southwest Site Storage Area) is designated as Final Status Survey (FSS) Class B and consists of 1,983 m2 (0.5 acres) of uninhabited open land located approximately 1,860 feet from the reference coordinate system benchmark used at Haddam Neck Plant (HNP) (see Attachment 1). The surface area is bounded by Survey Unit 9520-0004. The surface land unit that resides above this subsurface survey unit is relatively level open space of the peninsula. The restoration of the peninsula for FSS has removed most of the surface interference in the survey unit.

The reference coordinates associated with this survey unit are E007 through E0I10 by S089 through S093 (refer to 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 9807-0000 consisted of:

a) A review of the 10CFR50.75 (g) (1) database, b) A review of the "InitialCharacterizationReport" and the "HistoricSite Assessment Supplement, "

c) Historic and current survey records review, d) Visual inspections and a "walkdown."

A review of the 10CFR50.75(g)(1) database report and historical files shows a documented history of the Southwest Site Storage Area as a radioactive materials storage area. Examples of some of the major events are provided below.

a) Plant Incident Report (PIR) 80-37 reported the discovery of three (3) discrete sources of elevated activity on the Southeast Site Storage area in March 1980, along with other areas around the site. The three (3) discrete sources were identified within adjacent Survey Units 9520-0001 and 9520-0002. The elevated areas were removed upon detection according to the .report.

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SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000

. RELEASE RECORD b) Health Physics surveys performed in 1983 and 1985 document the discovery of radioactive material (strainers, bolts, wood pallets, sections of pipe, etc.) on the peninsula. The 1985 survey documents the discovery of contaminated dirt under a pallet.

c) Condition Report (CR) 05-0314: Documents the discovery of excavation spoils, intended for backfill, above the radiological criteria for use as backfill. These spoils were likely located in Survey Units 9520-0003 and 9520-0004, based on a review of the documentation. According to the CR closure documentation, the affected spoils were removed and packaged for disposal. Follow-up survey and sampling was performed and the results were below established action levels.

A review of the "Initialand Supplemental CharacterizationReports" as well as the previous "Classification Basis Summaries" was performed. Survey Unit 9807-0000 was originally part of subsurface Survey Unit 9805-0000, which was initially designated as Class C during the development of the LTP.

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 (references 2-2 and 277 respectively). The second source document justified a Class C designation for those areas for which there was historical evidence of contamination above the Derived Concentration Guideline Levels (DCGLs -

refer to Section 2 for definition and description of DCGL), but for which recent surveys had shown that decontamination efforts had occurred and that the radiological conditions were expected to be below the DCGLs. Additional justification for a Class C designation based on survey and sampling data was provided as another reference to the LTP by the "Haddam Neck Plant HistoricalSite Assessment Supplement".

However, in March of 2006, Co-60 and Cs-137 were identified in subsurface soils in sufficient quantities to warrant radiological remediation. Radiological remediation was performed in July 2006. A new Class 1 survey unit, Survey Unit 9520-0004, and a new subsurface unit, Survey Unit 9807-0000, were established to bound the area of remediation.

Remedial action was performed in July 2006. Although Co-60 has been identified in the past, Cs-137 was the only radionuclide with the potential to exceed the screening criteria following the remedial action. Statistical quantities (mean, median and standard deviation) from the 2006 remedial action survey are provided in Table 1.

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SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD Minimum Observed Concentration (pCi/g): -1.79E-03 Maximum Observed Concentration (pCi/g): 2.24E-02 Mean (pCi/g): 6.84E-03 Median (pCi/g): 3.69E-03 Standard Deviation (pCi/g): 8.39E-03 The FSS Engineer performed a visual inspection and walk-down during September 2006 to assess the physical condition of the survey unit, evaluate access points, and travel paths and identify potentially hazardous conditions.

This survey area is affected by existing 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 results of radiological surveys performed over six years of restoration and the 2006 remedial action survey, it was concluded that there was a probability for residual radioactivity in concentrations less than the DCGLs, justifying a final survey unit classification of Class B (refer to Section 3). Note, due to the size of the survey unit, the sample to area frequency far exceeds the frequency requirement for Class A survey units of one sample every 500 m2 as specified by LTP Section 5.7.3.2.2.

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, "Preparationof 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. Therefore, the survey unit does satisfy the primary objective of the FSS plan.

The primary objective of the FSS plan was to demonstrate that the level of residual radioactivity in Survey Unit 9807-0000 did not exceed the release Revision 0 5 Revision 0 5

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD 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 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 I HTotal =Hsoil + HExistingGW+ HFutureGW The total dose under the LTP criteria is twenty-five (25) mrem/yr 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) mremryr 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 not considered impacted by future groundwater radioactive contamination, as there are no buried concrete foundations or footings 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, therefore, zero (0) mrem/yr TEDE.

Equation 2 19 mrem/yrTotal = 17 mrem/yrsoil + 2 mrem/yrExisting GW+ 0 mrem/yrFutureGw Revision 0 6

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD The allowable dose for soil in this survey unit is seventeen (17) mrem/yr TEDE as shown by Equation 2 above. The concentration of residual radioactivity resulting in seventeen (17) mrem/yr TEDE is designated as the Operational DCGL, and has been established for the radionuclides of concern as provided in Table 2.

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H-3 4.12E+02 2.80E3+02 1.65E+01 C-14 5.66E+00 3.85E+00 2.26E-01 Mn-54 1.74E+01 1.18E+01 6.96E-01

. Fe-55 2.74E+04 1.86E+04 1.1 OE+03 Co-60 3.81E+00 2.59E+00 1.52E-01 Ni-63 7.23E+02 4.92E+02 2.89E+01 Sr-90 1.55E+00 1.05E+00 6.20E-02 Nb-94 7.12E+00 4.84E+00 2.85E-01 Tc-99 1.26E+01 8.57E+00 5.04E-01 Ag-108mn 7.14E+00 4.86E+00 2.86E-01 Cs-134 4.67E+00 3.18E+00 1.87E-01 Cs-137 7.91E+00 5.38E+00 3.16E-01 Eu-152 1.01E+01 6.87E+00 4.04E-01 Eu-154 9.29E+00 6.32E+00 3.72E-01 Eu-155 3.92E+02 2.67E+02 1.57E+01 Pu-238 2.96E+01 2.01E+01 1.18E+00 Pu-239/240 2.67E+01 1.82E+01 1.07E+00 Pu-241 8.70E+02 5.92E+02 3.48E+01 Am-241 " 2.5 8E+O1 1.75E+01 1.03E+00 Cm-243/244 2.90E+O1 1.97E+01 1.16E+00 (1) Bold indicates those radionuclides considered to be Hard-to-Detect (HTD)

(2) The Base Case Soil DCGLs for soil are specified by the LTP in Chapter 6 and are equivalent to 25 mrem/yr TEDE (3) The Operational DCGL is equivalent to 17 mrem/yr TEDE (4) The required MDC is equivalent to I 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 7

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 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 during the remedial action survey. Cs-137 was the only gamma emitting radionuclide reported in concentrations with the potential for exceeding the screening criteria. The remedial action survey 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 would be the radionuclide of concern in Survey Unit 9807-0000 (refer to Section 3). Other radionuclides identified during this FSS would be evaluated to ensure adequate survey design.

Surrogate DCGLs were not required for this survey unit via screening under LTP Section 5.4.7.2, "Gross Activity DCGLs". 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.

The Elevated Measurement Comparison (EMC) did not apply to this survey unit since it is a Class B area and discrete, elevated areas of contamnination were not expected.

The Sign Test was selected as the non-parametric statistical test. The use of the Sign Test did not require the selection or use of a background reference area, which simplified survey design and implementation. This approach was conservative since it included background Cs-137 as part of the sample set.

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SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD The number of soil samples for FSS was determined in accordance with the LTP. The Lower Bound of the Gray Region (LBGR) was set in accordance with Procedure RPM 5.1-11 to 5.36 to maintain the relative shift (A/o) 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 (10 CFR 20, Subpart E). The result of the COMPASS computer run showed adequate power for the survey design.

The survey design specified twenty-five (25) core soil samples for non-parametric statistical testing.

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 f.or 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 B area.

Judgmental sampling was not detennined to be necessary by the DQOs, based on the short distance between the area that was subjected to remedial action and FSS sample location 9807-0000-012F.

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 3.

Tal 3-SmpeMasu ýenehtjn Loatonsi t c~iit4d PS`Codiae Desi~giation2 Nlnhin'ies 9807-0000-001F 235632.88 669753.10 9807-0000-002F 23563,2.88 669784.48 9807-0000-003F 235632.88 669815.87 9807-0000-004F 235605.70 669737.40 9807-0000-005F 235605.70 669768.79 9807-0000-006F 235605.70 669800.18 9807-0000-007F 235605.70 669831.56 9807-0000-008F 235605.70 669862.95 9807-0000-009F 235578.52 669721.71 9807-0000-01 OF 235578.52 669753.10 9807-0000-01 IF 235578.52 669784.48 Revision 0 9 Revision 0 9

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD Table 0-02 235u5 6 58 9807-0000-012F 235578.52 669815.87 9807-0000-013F 235578.52 669847.25 9807-0000-014F 235578.52 669878.64 9807-0000-015F 235551.34 669737.40 9807-0000-016F 235551.34 669768.79 9807-0000-017F 235551.34 669800.18 9807-0000-018F 235551.34 669831.56 9807-0000-019F 235551.34 669862.95 9807-0000-020F 235551.34 669894.33 9807-0000-021F 235524.15 669784.48 9807-0000-022F 235524.1.5 669815.87 9807-0000-023F 235524.15 669847.25 9807-0000-024F 235524.15 669878.64 9807-0000-025F 235496.97 669862.95 Procedure RPM 5.1-11 specifies that 5% of the samples are required to be selected for HTD analysis. Three (3) 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, "RadionuclidesPotentially Present at Haddam Neck Plant" and as provided in Table 2.

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 three (3) soil samples for "split sample" analysis by the off-site laboratory. These locations were selected randomly using the Microsoft Excel "RANDBETWEEN" function. The number of quality control soil samples was about 10% of twenty-five (25) samples.

The LTP does not require scanning for elevated areas of radioactivity in subsurface survey units.

For this Class B survey unit, the "Investigation Level" for soil sample measurement results are those levels specified in LTP, Table 5-8. Table 4 provides a synopsis of the survey design.

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SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD

~F~tiii j% -a BsisI.2.

Survey Unit Land Area 1,983 m- Based on AutoCAD-LT 25 Number of Measurements (25 systematic grid) Based on LTP 5.7.3.2.2 0)

Grid Spacing 9.6 m Based on triangular grid Administratively set to achieve Operational DCGL 5.3 8 pCi/g Cs-137 17 mrem/yr TEDE (2)

The Operational DCGL meets Soil Investigation Level 5.38 pCi/g Cs-137 the LTP criteria for a Class B

___ survey unit (1) Due to the size of the survey unit, the sample to area frequency far exceeds the frequency requirement for Class A survey units of one sample every 500 m2 as specified by LTP Section 5.7.3.2.2 (2)The allowable dose for soil in this survey unit is 17 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 FSS field activities were conducted under Work Plan and Inspection Record (WP&IR) 2006-0038. The WP&IR package included a detailed FSS plan, 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.

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.

Twenty-five (25) subsurface 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 Custodyfor FinalStatus Survey Samples."

Three (3) samples (9807-0000-003F, 9807-0000-008F and 9807-0000-013F) were randomly selected for HTD radionuclide analysis.

The implementation of survey specific quality control measures included the collection of three (3) samples (9807-0000-012F, 9807-0000-018F and 9807-0000-024F) for "split sample" analysis.

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SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD

6. SURVEY RESULTS All field survey activities were conducted between September 13, 2006 and September 21, 2006.

The off-site laboratory employed for the radiological analyses of samples was General Engineering Laboratories, LLC. The laboratory analyzed the twenty-five (25) samples collected for non-parametric statistical testing, and 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 standard deviations uncertainty). However, Cs-137 was the only radionuclide reported in concentrations exceeding the de-selection criteria.

Cs-137 was identified in eight (8) of the twenty-five (25) samples collected for non-parametric statistical testing. Cs-137 was the primary radionuclide confirming the DQOs. The mean of the gamma spectroscopic analysis results for the sample population indicated that Cs-137 was present at levels lower than the concentrations of Cs-137 found in soil at off-site locations within the vicinity of the HNP as presented in the Health Physics TSD BCY-HP-0063.

A summary of the twenty-five (25) samples collected for non-parametric statistical testing results is provided in Table 5.

K: Table 5 Sumar of Soil ampl Results for the StatisticAl Sample Population Sampl Number a mp*le N S u m b er . . *.. ..< .. ., =tCs-137" o .. , ..:. ..* :.::* Fraction

.. ,.;,*,..*.. .... of the ......'=.

.,.. .. (pci/g) . . Op.erational DCGE.,L 9807-0000-001 F -7.91E-03 0.000 9807-0000-002F -2.76E-02 0.000 9807-0000-003F 4.02E-02 0.007 9807-0000-004F -1.26E-03 0.000 9807-0000-005F 1.87E-02 0.003 9807-0000-006F -8.34E-03 0.000 9807-0000-007F -1.54E-02 0.000 9807-0000-008F -1.36E-02 0.000 9807-0000-009F 3.30E-02 0.006 9807-0000-01 OF 2.86E-02 0.005 9807-0000-01 IF -2.32E-02 0.000 9807-0000-012F 4.36E-02 0.008 9807-0000-013F -2.5 1E-03 0.000 9807-0000-014F 8.18E-03 0.002 Revision I 12 Revision I 12

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD

    • ,Table,_54* Summary ofSoil Sample .Results for the Statistical Sample....*,:.

________________ Population_ _ _ _ _ _ _ _ _ _

Sample ,,*ei*Cs137 Fraction.of F, the.

P....... * .. .. ,ý /g)' .... Operational DCGL."

9807-0000-015F 1.29E-02 0.002 9807-0000-016F 6.01E-03 0.001 9807-0000-017F 3.34E-02 0.006 9807-0000-018F 2.39E-03 0.000 9807-0000-019F -3.24E-04 0.000 9807-0000-020F 3.53E-02 0.007 9807-0000-021 F 0.OOE+00 0.000 9807-0000-022F 2.88E-02 0.005 9807-0000-023F 2.56E-02 0.005 9807-0000-024F 1.18E-02 0.002 9807-0000-025F 3.50E+00 0.651 (1) The Operational DCGL from Table 2 is 5.38 pCi/g for Cs-137 to achieve seventeen (17) mrem/yr TEDE The off-site laboratory also processed three (3) samples for HTD analysis as required by the sample plan. The requested analyses included alpha spectroscopy, gas proportional counting, and liquid scintillation depending on the radionuclide and the measurement method. All analyses met the required MDC.

As previously stated in Section 4 of this report, the criteria for de-selection of a radionuclide is a concentration that is less than 5% of the Operational DCGL for individual radionuclides and less than 10% of the Operational DCGLs for aggregates. H-3 and Am-241 were the only HTDs identified above the accepted criteria for detection (i.e., a result greater than two standard deviations uncertainty). The off-site laboratory prepared and reanalyzed two (2) of the three (3) original samples for H-3 at HNP's request; and performed H-3 analysis on five (5) other samples bordering the two (2) sample locations. The results of all seven (7) samples were all less than the accepted criteria for detection. The highest result for Am-241 was about 4% of the Operational DCGL.

__ ...

_~.....fab le"'8" -Hard-to-DetectSample.Ressu.is Sam.ple .Am-241 Fraction of Ope.atin.al

. MDCGL 9807-0000-003F 7.13E-01 0.041 9807-0000-008F 5.32E-02 0.003 9807-0000-013F 9.35E-02 0.005 (I) The Operational DCGL from Table 2 is 17.5 pCi/g for Am-241 to achieve 17 mrem/yr TEDE Revision I .13 Revision I 13

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD

7. QUALITY CONTROL The off-site laboratory processed the split samples and performed gamma spectroscopy analysis. Ten percent (10%) of the samples were 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". Cs-137 was not detected in sufficient quantities in the field split results at the three (3) locations to evaluate in accordance with procedure. Evaluation using the reported results for K-40 resulted in acceptable agreement between the field split results at these locations.

The sample analysis vendor, General Engineering Laboratories, LLC, maintains quality control and quality assurance plans as part of normal operation. Refer to Attachment 4 for data and data quality analysis results.

8. INVESTIGATIONS AND RESULTS No investigations were performed.
9. REMEDIATION AND RESULTS Remedial action was performed in July 2006. Although Co-60 has been identified in the past, Cs-137 was the only radionuclide with the potential to exceed the screening criteria following the remedial action. Health Physics TSD BCY-HP-0078, "ALARA Evaluation of Soil Remediation in Support of Final Status Survey, " has 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 No changes were made to the FSS plan.
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.

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 B.

Revision 0 14 Revision 0 14

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD 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.

For Cs-137, the range of the data, about five (5) standard deviations, indicated some variation, mainly as a result of one (1) sample that is higher in concentration than the rest of the data set. The difference between the mean and median was about 20% 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 significant positive skewness due to one (1) sample as confirmed by the calculated skew of 4.99.

All data, assessments, and graphical representations are provided in Attachment 3.

12. ANOMALIES No anomalies were noted.
13. CONCLUSION Survey Unit 9807-0000 has met the final DQOs of the FSS plan. The ALARA criteria for soils as specified in Chapter 4 of the LTP were achieved. Elevated Measurement Comparison was not required.

Cs-137 was 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 B.

The dose contribution from soil is less than 1 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 not considered impacted by future groundwater radioactive contamination, as there are no underground structures, systems or components containing residual radioactive material within the groundwater saturated zone in the area (reference CY memo ISC 06-024); therefore, the dose contribution from future groundwater is zero (0) mrem/yr TEDE.

Revision 0 15 Revision 0 15

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD 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

.3 mrem/yr TEDE. Therefore, Survey Unit 9807-0000 is acceptable for unrestricted release.

14. ATTACHMENTS 14.1 Attachment 1 - Figures 14.2 Attachment 2 - Laboratory Results 14.4 Attachment 3 - DQA Results Revision I 16 Revision 1 16

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 1 (FIGURES)

j-CONNECT7CUT RIVER-r Connecticut Yankee Atomic Power Company Date By Figure 1 Site Map With Reference To Survey Unit 980 7-0000 November2006 IJ

Q C,! / .

{-t-.-_ . 7 Legend

/

i -L 14 A-20

// __/

7-

,6 = Sample Point (3 -7 I-L 0

.,24 12.5 25 IFeet

-I 'a 19

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Connecticut Yankee Atomic Power Company Survey Unit 9807-0000 FinalStatus Survey Design

-0.01 0.01

-0.02 Lqgend

-0.03 0.

-0.03 12.5 25 F.t

-0.01 -0.01 . Notes

-0.01 0.04 Reported Concentrationsin 0.02 O0 pCi/g 0.01

-0.02

-0.01 0.03 0.03 0.03 0.03 0.01 0.03 0.0.1 Connecticut Yankee Atomic Power Company Survey Unit 9807-0000 FinalStatus Survey Cs-13 7 PostingPlot

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 2 (LABORATORY DATA)

General Narrative 1

General Narrative for Connecticut Yankee Atomic Power Co.

Work Order: 172275 SDG: MSR#06-1282 October 04, 2006 Laboratory Identification:

General Engineering Laboratories, LLC 2040 Savage Road Charleston, South Carolina 29407 (843) 556-8171 Summary Sample receipt The samples arrived at General Engineering Laboratories, LLC, Charleston, South Carolina on September 21, 2006 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 Sample Identification Description 172275001 9807-0000-001F 172275002 9807-0000-002F 172275003 9807-0000-003F 172275004 9807-0000-004F 172275005 9807-0000-005F 172275006 9807-0000-006F 172275007 9807-0000-007F 172275008 9807-0000-008F 172275009 9807-0000-009F 172275010 9807-0000-010F 172275011 9807-0000-01 iF 2.

172275012 9807-0000-012F 172275013 9807-0000-01 2FS 172275014 9807-0000-013F 172275015 9807-0000-014F 172275016 9807-0000-0 15F 172275017 9807-0000-01 6F 172275018 9807-0000-017F 172275019 9807-0000-018F 172275020 9807-0000-018FS 172275021 9807-0000-019F 172275022 9907-0000-02OF 172275023 9807-0000-021iF 172275024 9807-0000-022F 172275025 9807-0000-023F 172275026 9807-0000-024F 172275027 9807-0000-024FS 172275028 9807-0000-025F Items of Note There are no items to note.

Case Narrative Sample analyses were conducted using methodology as outlined in General Engineering Laboratories (GEL) Standard Operating Procedures. Any technical or administrative problems during analysis, data review, and reduction are contained 'inthe analytical case narratives in the enclosed data package.

Analytical Request Twenty-five soil samples were analyzed for FSSGAM. Three soil samples were analyzed for FSSALL.

Data Packag~e 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.

Cheryl Jones Project Manager 3

List of current GEL Certifications as of 04 October 2006 State Certification Alaska UST-062 Arizona AZ0668 Arkansas 88-0651 CLIA 42D0904046 California 01151CA Colorado GenEngLabs Connecticut PH-0169 Dept. of Navy NFESC 413 EPA WG-15J FloridaINELAP E87156 Georgia E87156 (FIJNELAP)

Hawaii N/A Idaho N/A Illinois 200029 Indiana C-SC-01 Kansas E-10332 Kentucky 90129 Louisiana 03046 Maryland .270 Massachusetts M-SCO12 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/I 0585001/10120002 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 No. 2006-568 362 Injun Hollow Road, East Hampton, CT 06424 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 Code General Engineering Laboratories 2040 Savage Road Charleston, SC 29407 ATT: Cheryl Jones (843-556-8171)

Other: E] 30 D. Z 14 D. [] 7 D.

Priority: X <CIO _.*-2C /

Sample Designation Date Time a Comment, Preservation Lab Sample lD 9807-0000-001 F 91O416-6' 1141P TS C BP X_

9807-0000-00;I , Itq TS C BP X 9807-0000-003 F " / ýr7 TS C BP ->,t 2_

9807-0000-0004/ OR , /5,23 TS C BP 9807-0000-0 0$5E 105 - TS C BP %_

9807-0000-0 No F &*/.1P 1 105 TS C BP 9807-0000-Opr 1 WnI,j2p.53 TS C BP _

9807-0000-Oc V= C*W ýLj \ 5 TS C BP 9807-0000-0 A V* ?O TS C BP " __ .......

9807-0000-0-4,0 qJ14100 I4 S' TS C BP 9807-0000-0 0\ WL*-Qý c) 4{ TS C BPP_

NOTES: PO #: 002332 MSR #: &4:/Zi ,. Z LTP QA Dl Radwaste QA [1 Non QA Samples Shipped Via: Internal Container M Fed Ex Temp.: _* Deg. C El UPS

  • ~ El Hand Y0 Seale ?

Custody

1) Relinquished y Date/Time 2)'I.c eivr By D te/Time Custody Seal Intact?

3Y0.0 W VA 0 76-1 E] Other

3) Relinquished y Date/Time 4) Received B; Date/Time BillofLading#_Y

_ _ 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 No. 2006-569 362 Injun Hollow Road, East Hampton, CT 06424 860-267-2556 Project Name: Haddam Neck Decommissioning Analyses Requested Lab Use Only Contact Name & Phone: Comments:

Media Sample Container Jack McCarthy 860-267-3924 Code Type Size-Analytical Lab (Name, City, State): Code &Type Code General Engineering Laboratories 2040 Savage Road Charleston, SC 29407 ATT: Cheryl Jones (843-556-8171)

Priority: 0 30 D. N 14 D. 717 D. 4 Other: ___ ___

Sample Designation Date Time -_ -- Comment, Preservation Lab Sample ID 9807-0000-0 j v

  • TS C BP Vnu -,74d 00140 9807-0000-0 q ILj.,P C)9 TS C BP V "__ o_

9807-0000-0 ' q.14.G 40, TS C BP X 9807-0000-0 tLk - 0%",060 e., TS C BP 9807-0000-0 VdO o'lf-p C.q, , TS C BP __

9807-0000-0 11 . 6,0 c tav- TS C BP 9807-0000-0 \'t= Q1-t 046 TS C BP ___.....

9807-0000-0 \--F \ f- TS C BP __

9807-0000-0 \ _S a .1r- TS C BP _ __

9807-0000-0 \0,'F 0tt',6-O, vOz TS C BP - -

9807-0000-0o -m- V 1905 ,QC26 TS C BP I_

NOTES: PO #: 002332 MSR #: o0 -1Z o LTP QA [ Radwaste QA 0 Non QA Samples Shipped Via: Internal Container Z Fed Ex Temp.: __ Deg, C EU[S D Hand Custody Sealel

1) Relinquished By Date/Time 2) eev Date/Time Custody Seal Intact?

_______ ______ ___L16 9§/Q 0 n9 o El Other

3) Relinquished By Date/Time 4) keceived 3y Date/Time YOl NO]

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 No. 2006-570 362 Injun Hollow Road, East Hampton, CT 06424 860-267-2556 Project Name: Haddam Neck Decommissioning Analyses Requested Lab Use Only Contact Name & Phone: Comments:

Media Sample Container Jack McCarthy 860-267-3924 Code Type Size-Analytical Lab (Name, City, State): Code &Type AnalyicalCode General Engineering Laboratories 2040 Savage Road Charleston, SC 29407 ATT: Cheryl Jones (843-556-8171)

Priority: 1 30 D. Z 14 D. ZI 7 D.

Other: _ __ _

Sample Designation Date Time 4. 1 Comment, Preservation Lab Sample D) 9807-0000-0'ZiI 3j q-lf'6 <9 TS C BP -,_

9807-0000-0 ogm r,. - q-- 11-o(. os-* TS C BP ?C_

9807-0000-0 z: j, q- t-6<I', l5-- TS C BP -)

9807-0000-0 .AI q-ý") j*4"j 14o',*30 TS C BP 9807-0000-0 ;, -_V-O(9 s*) TS C BP

-GC5WEg.Q5 ;7~ C? 10606 1 _____ __ _

NOTES: PO #: 002332 MSR#: or) &- LTP QA E] Radwaste QA LI Non QA Samples Shipped Via: Internal Container Z Fed Ex Temp.: __ Deg. C 0uPs El Hand Custody Sealed?

1) Relinquished By Date/Time .!ate/Time
2) Reivecfv El-Other Custody Sentact?
3) Relinquished By Date/Time 4) Received byK Date/Time BillofLadig___YON___

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 Check-in List .

Date/Time Received: . - 1 O()'0c ,

SDG#:

_______

Work Order Number:______________________

C"hain of Custody# 5AO k l .'ciO

. q . b.-. C&." Z "

  • av.*
. Cdntainerfl:

Shipping ."

" o tQ_V7e-d e_ - t4 .vw' " _-_2-_  :

1. Custody Seals orffshipping container intact?.. -Yes t ]No [ A
2. Custody Seals dated and.signed? . Yes"[ I No [ ].A/l/4
3. Chain-of-Custody record sent? *.NO Yes 4". Cooler temperature I I
5. Vermiculite/packing materials is: Wet [P Dry II,]iiJ/

6.' Number of samples in shipping container:

7. Sample holding times exceeded? Yes[ No.y4
  • 8. Samples have:

//tape -hazard labels custody seals ._ appropriate sample labels

9. Samples are:

_4 1 good condition . leaking

-broken " have air bubbles

10. Were any.anomalies identified in sample receipt? Yes[] No,1 11.. .Description of anomalies (include sample numbers):

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

< Result is less than value reported a Result is greater than value reported RPD of sample and duplicate evaluated using +/-RL. Concentrations are cSX the RL A The TIC is a suspected aldol-condensation product

  • Target analyte was detected in the associated blank B Metals-Either presence of analyte detected in the associated blank, or MDL/IDL a sample value a 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 N 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.

11

RADIOLOGICAL ANALYSIS 12

Radiochemistry Case Narrative Connecticut Yankee Atomic Power Co. (YANK)

Work Order 172275 Method/Analysis Information Product: Alphaspec Am241, Cm, Solid ALL FSS Analytical Method: DOE EML HASL-300, Am-05-RC Modified Prep Method: Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method: Dry Soil Prep Analytical Batch Number: 572120 Prep Batch Number: 571426 Dry Soil Prep GL-RAD-A-021 Batch Number: 571421 Sample ID Client ID 172275003 9807-0000-003F 172275008 9807-0000-008F 172275014 9807-0000-013F 1201191303 Method Blank (MB) 1201191304 172114001(9530-0001-008F) Sample Duplicate (DUP) 1201191305 172114001(9530-0001-008F) Matrix Spike (MS) 1201191306 Laboratory Control Sample (LCS)

SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-01 1 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: 172114001 (9530-0001-008F).

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.

Qualifier information Manual qualifiers were not required.

Method/Analysis Information 14

Product: Alphaspec Pu, Solid-ALL FSS Analytical Method: DOE EML HASL-300, Pu- I -RC Modified Prep Method: Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method: Dry Soil Prep Analytical Batch Number: 572121 Prep Batch Number: 571426 Dry Soil Prep GL-RAD-A-021 Batch Number: 571421 Sample ID Client ID 172275003 9807-0000-003F 172275008 9807-0000-008F 172275014 9807-0000-013F 1201191307 Method Blank (MB) 1201191308 172114001(9530-0001-008F) Sample Duplicate (DUP) 1201191309 172114001(9530-0001-008F) Matrix Spike (MS) 1201191310 Laboratory Control Sample (LCS)

SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-0 11 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: 172114001 (9530-0001-008F).

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.

Qualifier information Manual qualifiers were not required.

Method/Analysis Information Product: Liquid Scint Pu241, Solid-ALL FSS Analytical Method: DOE EML HASL-300, Pu-I I-RC Modified Prep Method: Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method: Dry Soil Prep Analytical Batch Number: 572122 Prep Batch Number: 571426 Dry Soil Prep GL-RAD-A-021 Batch Number: 571421 16

Sample ID Client ID 172275003 9807-0000-003F 172275008 9807-0000-008F 172275014 9807-0000-013F 1201191311 Method Blank (MB) 1201191312 172114001(9530-0001-008F) Sample Duplicate (DUP) 1201191313 172114001(9530-0001-008F) Matrix Spike (MS) 1201191314 Laboratory Control Sample (LCS)

SOP Reference Pr ocedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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 (0C) Information:

Blank Information The blank volume is representative of the sample volume in this batch.

Designated QC The following sample was used for QC: 172114001 (9530-0001-008F).

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 17

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: Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Analytical Method: EML HASL 300, 4.5.2.3 Prep Method: Dry Soil Prep Analytical Batch Number: 574335 Prep Batch Number: 571421 18

Sample ID ClientID 172275001 9807-0000-001F 172275002 9807-0000-002F 172275003 9807-0000-003F 172275004 9807-0000-004F 172275005 9807-0000-005F 172275006 9807-0000-006F 172275007 9807-0000-007F 172275008 9807-0000-008F 172275009 9807-0000-009F 172275010 9807-0000-01OF 172275011 9807-0000-01 IF 172275012 9807-0000-012F 172275013 9807-0000-012FS 172275014 9807-0000-013F 172275015 9807-0000-014F 172275016 9807-0000-015F 172275017 9807-0000-016F 172275018 9807-0000-017F 172275019 9807-0000-018F 172275020 9807-0000-018FS 1201196536 Method Blank (MB) 1201196537 172275001(9807-0000-00IF) Sample Duplicate (DUP) 1201196538 Laboratory Control Sample (LCS)

SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-013 REV# 12.

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: 172275001 (9807-0000-OOIF).

19

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 Qualifier Reason Analyte Sample UT5 Data rejected due to high peak-width. Cesium-137 172275013 U' Data rejected due to interference. Cesium-134 172275017 Europium- 155 172275008 172275013 Ui Data rejected due to low abundance. Actinium-228 172275002 Cesium-134 172275003 172275006 172275007 172275008 172275012 172275015 172275018 1201196537 20

Method/Analysis Information Product: Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Analytical Method: EML HASL 300, 4.5.2.3 Prep Method: Dry Soil Prep Analytical Batch Number: 574336 Prep Batch Number: .571423 Sample ID Client ID 172275021 9807-0000-019F 172275022 9807-0000-020F 172275023 9807-0000-021F 172275024 9807-0000-022F 172275025 9807-0000-023F 172275026 9807-0000-024F 172275027 9807-0000-024FS 172275028 9807-0000-025F 1201196539 Method Blank (MB) 1201196540 172275028(9807-0000-025F) Sample Duplicate (DUP) 1201196541 Laboratory Control Sample (LCS)

SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering Laboratories, LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-013 REV# 12.

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 (0C) Information:

Blank Information The blank volume is representative of the samplevolume in this batch.

21

Designated QC The following sample was used for QC: 172275028 (9807-0000-025F).

QC Information Refer to Non-Conformance Report.

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. The following NCR was generated for this SDG:

NCR 368031 was generated due to Failed RPD for DUP. 1. Failed RPD for DUP: The relative percent difference (172275028 and 120119654) for K-40 and Pb-212 did not meet the duplication criteria. 1.

K-40 and Pb-212 are naturally occurring nuclides. All other nuclides meet within the duplication criteria. Reporting results.

Additional Comments Additional comments were not required for this sample set..

Oualifier information Qualifier Reason Analyte Sample UI Data rejected due to high peak-width. Cesium-137 172275023 UI Data rejected due to interference. Europium-155 172275023 UI Data rejected due to low abundance. Cesium- 134 172275021 172275022 172275024 172275025 1201196540 Method/Analysis Information 22

Product: GFPC, Sr9O, solid-ALL FSS Analytical Method: EPA 905.0 Modified Prep Method: Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method: Dry Soil Prep Analytical Batch Number: 572301 Prep Batch Number: 571426 Dry Soil Prep GL-RAD-A-021 Batch Number: 571421 Sample ID Client ID 172275003 9807-0000-003F 172275008 9807-0000-008F 172275014 9807-0000-01 3F 1201191723 Method Blank (MB) 1201191724 172275003(9807-0000-003F) Sample Duplicate (DUP) 1201191725 172275003(9807-0000-003F) Matrix Spike (MS) 1201191726 Laboratory Control Sample (LCS)

SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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).

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: 172275003 (9807-0000-003F).

23

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.

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 Additional comments were not required for this sample set.

Oualifier information Manual qualifiers were not required.

Method/Analysis Information Product: Liquid Scint Tc99, Solid-ALL FSS Analytical Method: DOE EML HASL-300, Tc-02-RC Modified Analytical Batch Number: 571877 Sample liD Client ID 172275003 9807-0000-003F 172275008 9807-0000-OOSF 172275014 9807-0000-013F 1201190771 Method Blank (MB) 1201190772 172275003(9807-0000-003F) Sample Duplicate (DUP) 1201190773 172275003(9807-0000-003F) Matrix Spike (MS) 1201190774 Laboratory Control Sample (LCS) 24

SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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 (0C) Information:

Blank Information The blank volume is representative of the sample volume in this batch.

Designated QC The following sample was used for QC: 172275003 (9807-0000-003F).

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.

25

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: Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method: Dry Soil Prep Analytical Batch Number: 571874 Prep Batch Number: 571426 Dry Soil Prep GL-RAD-A-021 Batch Number: 571421 Sample ID Client ID 172275003 9807-0000-003F 172275008 9807-0000-008F 172275014 9807-0000-013F 1201190757 Method Blank (MB) 1201190758 172275008(9807-0000-008F) Sample Duplicate (DUP) 1201190759 172275008(9807-0000-008F) Matrix Spike (MS) 1201190760 Laboratory Control Sample (LCS)

SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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.

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 26

The blank volume is representative of the sample volume in this batch.

Designated QC The following sample was used for QC: 172275008 (9807-0000-008F).

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.

Gualifier information Manual qualifiers were not required.

Method/Analysis Information Product: Liquid Scint Ni63, Solid-ALL FSS

  • Analytical Method: DOE RESL Ni-1, Modified Prep Method: Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method: Dry Soil Prep Analytical Batch Number: 571876 Prep Batch Number: 571426 Dry Soil Prep GL-RAD-A-021 Batch Number: 571421 27

Sample ED Client ID 172275003 9807-0000-003F 172275008 9807-0000-008F 172275014 9807-0000-013F 1201190767 Method Blank (MB) 1201190768 172275014(9807-0000-013F) Sample Duplicate (DUP) 1201190769 172275014(9807-0000-013F) Matrix Spike (MS) 1201190770 Laboratory Control Sample (LCS)

SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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 (0C) Information:

Blank Information The blank volume is representative of the sample volume in this batch.

Designated QC The following sample was used for QC: 172275014 (9807-0000-013F).

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 28

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-HTD2,ALL FSS Analytical Method: EPA 906.0 Modified Analytical Batch Number: 571884 Sample ID Client ID 172275003 9807-0000-003F 172275008 9807-0000-008F 172275014 9807-0000-013F 1201190793 Method Blank (MB) 1201190794 172275003(9807-0000-003F) Sample Duplicate (DUP) 1201190795 172275003(9807-0000-003F) Matrix Spike (MS) 1201190796 Laboratory Control Sample (LCS)

SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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.

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.

29

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: 172275003 (9807-0000-003F).

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. The following NCR was generated for this SDG:

NCR 365692 was generated due to Container scanning event for custody missed. 1. The analyst did not scan the samples 172275003, 172275008, and 172275014 into the batch prior to analysis, however the samples did remain in their custody at all times. 1. The error has been corrected and the analyst has been instructed on the proper scanning procedures. Reporting results.

Additional Comments Additional comments were not required for this sample set.

Qualifier information Manual qualifiers were not required.

Method/Analysis Information Product: Liquid Scint C14, Solid AII,FSS Analytical Method: EPA EERF C-0I Modified Analytical Batch Number: 571880 30

Sample ID Client ID 172275003 9807-0000-003F 172275008 9807-0000-008F 172275014 9807-0000-013F 1201190783 Method Blank (MB) 1201190784 172275003(9807-0000-003F) Sample Duplicate (DUP) 1201190785 172275003(9807-0000-003F) Matrix Spike (MS) 1201190786 Laboratory Control Sample (LCS)

SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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 Infor'mation 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 (OQC) Information:

Blank Information The blank volume is representative of the sample volume in this batch.

Designated QC The following sample was used for QC: 172275003 (9807-0000-003F).

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 31

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.

Gualifier 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 packagihg 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:

32

General Engineering Laboratories NCR Report No.: 365692 Form GEL-NCR Revision No.:

Rev. 06105 COMPANY - WIDE NONCONFORMANCE REPORT Mo.Day Yr. Division: Quality Criteria: Type:

29-SEP-06 Radiochemistry Specifications Process Instrument Type: Test ! Method: Matrix Type: Client Code:

LSC EPA 906.0 Modified Solid YANK Batch ID: Sample Numbers:

571884 See Below Potentially affected work order(s)(SDG): 172275(MSR#06-1282)

Application Issues:

Container scanning event for custody missed Specification and Requirements NRG Disposition:

Nonconformance

Description:

1. The analyst did not scan the samples 172275003, 172275008, and 1. The error has been corrected and the analyst has been instructed on the 172275014 into the batch prior to analysis, however the samples did proper scanning procedures. Reporting results.

remain in their custody at all times.

Originator's Name: Data Validator/Group Leader:

Amy Scott 29-SEP-06 Melanie Aycock 01-OCT-06 Quality Review:

Director:

Page 1 33

General Engineering Laboratories NCR Report No;: 368031 Form GEL-NCR Revision No.: 1 Rev. 06/05 COMPANY- WIDE NONCONFORMANCE REPORT Mo.Day Yr. Division: Quality Criteria: Type:

05-OCT-06 Radiochemistry Specifications Process Instrument Type: Test / Method: Matrix Type: Client Code:

GAMMA SPECTROMETER EML HASL 300, 4.5.2.3 Solid YANK Batch ID: Sample Numbers: .

574336 See Below Potentially affected work order(s)(SDG): 172275(MSR#06-1282),172873(MSR#06-1313),172875(MSR#06-1312),172879(MSR#06-1311)

Application Issues:

Failed RPD for DUP Specification and Requirements NRG Disposition:

Nonconformance

Description:

1. Failed RPD for DUP: The relative percent difference (172275028 1. K-40 and Pb-212 are naturally occurring nuclides. All other nuclides and 120119654) for K-40 and Pb-212 did not meet the duplication meet within the duplication criteria. Reporting results.

criteria.

Originator's Name: Data Validator/Group Leader:

Jimmy Hartley 05-OCT-06 Quality Review:

Director:

Page 1 34

SAMPLE DATA

SUMMARY

35

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Report for YANKOO Connecticut Yankee Atomic Power Co.

Client SDG: MSR#06-1282 GEL Work Order: 172275 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 General Engineering Laboratories, LLC standard operating procedures. Please direct any questions to your Project Manager, Cheryl Jones.

Reviewed by 36

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-00IF Project: YANK01204 Sample ID: 172275001 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 13-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 16.6%

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 0.917 +/-0.197 0.0541 +/-0.197 0.119 pCi/g MJH1 10/03/060635 574335 1 Americium-241 U 0.0336 +/-0.0304 0.027 +/-0.0304 0,0556 pCilg Bismuth-212 0.332 +/-0.297 0.136 +/-0.297 0.293 pCi/g Bismuth-214 0.594 +/-0.0918 0.0352 +/-0.0918 0.075 pCi/g Cesium-134 U 0.0178 +/-0.0337 0.0227 +/-0.0337 0.0486 pCi/g Cesium-137 U -0.00791 +/-0.0231 0.0166 +/-0.0231 0.0358 pCi/g

.Cobalt-60 U -0.032 +/-0.0272 0.0154 +/-0.0272 0.0349 pCilg Europium-152 U 0.00865 +/-0.0526 0.048 +/-0.0526 0.101 pCi/g Europium-154 U -0.00226 +1-0.0668 0.0569 +/-0.0668 0.125 pCi/g Europium-155 U 0.0769 +/-0.0755 0.0429 +/-0.0755 0.0889 pCi/g Lead-212 0.826 +/-0.0631 0.0264 +/-0.0631 0.0549 pCi/g Lead-214 0.596 +/-0.0873 0.0338 +/-0.0873 0.0711 pCi/g Manganese-54 U -0.00108 +/-0.0247 0.0207 +/-0.0247 0.0442 pCi/g Niobium-94 U -0.00289 +/-0.021 0.0177 +/-0.021 0.0378 pCi/g Potassium-40 12.6 +/-0.924 0.140 +/-0.924 0.321 pCi/g Radium-226 0.594 +/-0.0918 0.0352 +/-0.0918 0.075 pCi/g Silver-108m U 0.00205 +/-0.0182 0.0163 +/-0.0182 0.0344 pCi/g Thallium-208 0.288 +/-0.0486 0.0178 +/-0.0486 0.0381 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1745 571421 The following Analytical Methods were performed Method Description EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 37

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-00IF Proiect: YANK01204 Sample ID: 172275001 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.

UI Ganmma 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

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-002F Project: YANK01204 Sample ID: 172275002 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 13-SEP-06 Receive Date: 2 1-SEP-06 Collector: Client Iklr;*lIs 1A QO1 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Sohid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 UI 0.00 +/-0.199 0.163 +/-0.199 0.325 pCi/g MJHI 10/03/060650 574335 1 Americium-241 U 0.0381 +/-0.0369 0.0312 +/-0.0369 0.0624 pCi/g Bismuth-212 0.434 +/-0.350 0.179 +/-0.350 0.358 pCi/g Bismuth-214 0.556 +/-0.106 0.0356 +/-0.106 0.0711 pCi/g Cesiutn-134 U 0.035 +/-0.0431 0.0301 +/-0.0431 0.0601 pCi/g Cesiurn-137 U -0.0276 +/-0.0307 0.0211 +/-0.0307 0.0421 pCi/g Cobalt-60 U 0.0211 +1-0.0298 0.0272 +/-0.0298 0.0543 pCi/g Europium-152 LU -0.0121 +/-0.0687 0.0491 +/-0.0687 0.0981 pCi/g Europium-154 U 0.0712 +/-0.0952 0.0863 +/-0.0952 0.173 pCi/g Europium-155 U 0.0585 +/-0.0674 0.0466 +/-0.0674 0.0931 pCi/g Lead-212 0.740 +/-0.0888 0.0283 +/-0.0888 0.0566 pCi/g Lead-214 0.618 +/-0.109 0.0383 +/-0.109 0.0766 pCi/g Manganese-54 U -0.0246 +/-0.0275 0.0221 +/-0.0275 0.0441 pCi/g Niobium-94 U -0.00223 +/-0.0244 0.0214 +1-0.0244 0.0428 pCilg Potassium-40 12.6 +/-1.09 0.164 +/-1.09 0.327 pCi/g Radium-226 0.556 +/-0.106 0.0356 +/-0.106 0.0711 pCi/g Silver-108m U 0.00737 +/-0.0234 0.0173 +/-0.0234 0.0345 pCi/g Thallium-208 0.257 +/-0.0585 0.0233 +1-0.0585 0.0465 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I EMIL HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 39

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-002F Project: YANK01204 Sample ID: 172275002 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-003F Proiect: YANK01204 Sample ID: 172275003 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 13-SEP-06 Receive Date: 21-SEP-06 Collector: Client lMn i hll-P-IA 07-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 0.713 +/-0.277 0.0248 +/-0.293 0.125 pCilg TC1 09/28/06 1156 572120 1 Curium-242 U 0.00 +/-0.0579 0.00 +/-0.0579 0.080 pCilg Curium-243/244 U 0.0354 +/-0.080 0.043 +/-0.0801 0.161 pCilg Alphaspec Pu, Solid-ALL FSS Plutonium-238 U -0.0431 4-/-0.0532 0.057 +/-0.0532 0.175 pcilg TC1 09/28/060935 572121 2 Plutonium-239/240 U -0.00359 4 /-0.0698 0.0604 +/-0.0698 0.182 pCilg Liquid Scint Pu241, Solid-ALL FSS Plutonium-241 U 1.79 +/-8.11 6.73 +/-8.12 14.1 pCi/g TC1 09/29/06 2230 572122 3 Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.743 +/-0.218 0.0704 +/-0.218 0.152 pCi/g MJHI 10/03/060635 574335 4 Americium-241 U 0.014 4-0.0362 0.0304 +/-0.0362 0.0626 pCi/g Bismuth-212 0.547 +/-0.295 0.175 +/-0.295 0.370 pCi/g Bismuth-214 0.558 +/-0.109 0.0428 +/-0.109 0.0901 pCi/g Cesium-134 U] 0.00 /-0.0386 0.0286 +/-0.0386 0.0604 pCi/g Cesium-137 U 0.0402 4/-0.0327 0.0243 +/-0.0327 0.0512 pCi/g Cobalt-60 U 0.0104 +/-0.0285 0.0248 +/-0.0285 0.0536 pCi/g Europium-152 U 0.098 +/-0.0702 0.0562 +/-0.0702 0.117 pCi/g Europium-154 U -0.032 +/-0.0804 0.0651 +/-0.0804 0.141 pCi/g Europium-155 U -0.00541 +/-0.0571 0.0485 +/-0.0571 0.100 pCilg Lead-212 0.628 F/-0.0808 0.0384 +/-0.0808 0.079 pCi/g Lead-214 0.585 +/-0.110 0.0369 +/-0.110 0.0775 pCi/g Manganese-54 U -0.00284 +/-0,0262 0.0217 +/-0.0262 0.0462 pCi/g Niobium-94 U -0.00174 +/-0.0241 0.0204 +/-0.0241 0.0432 pCi/g Potassium-40 13.1 +/-0.962 0.206 +/-0.962 0.453 pCi/g Radium-226 0.558 +/-0.109 0.0428 +/-0.109 0.0901 pCi/g Silver-108m U 0.0131 +/-0.022 0.0204 +/-0.022 0.0427 pCi/g Thallium-208 0.247 F/-0.0581 0.0211 +/-0.0581 .0.0447 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr90, solid-ALL FSS Strontium-90 U -0.00839 +/-0.0152 0.014 +/-0.0152 0.0324 pCi/g KSDI 09/28/06 0957 572301 5 Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid-HTD2,ALL FSS Tritium 32.4 +/-8.92 5.77 +/-8.93 12.3 pCi/g DFA1 09/27/06 1825 571884 6 41

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332.

Client Sample ID: 9807-0000-003F Project: YANK01204 Sample lID: 172275003 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis Liquid Scint C14, Solid AII, FSS Carbon-14 U -0.0626 +1-0.105 0.0892 +/-0.105 0.181 pCi/g AXD2 09/25/06 1910 571880 7 Liquid Scint Fe55, Solid-ALL FSS lron-55 U -9.41 +/-37.1 26.5 +/-37.1 55.3 pCi/g MXPI 09/28/06 1737 571874 8 Liquid Scint Ni63, Solid-ALL FSS Nickel-63 U 2.54 +/-7.06 5.86 +/-7.06 12.1 pCi/g MXP1 09/29/06 1842 571876 9 Liquid Scint Tc99, Solid-ALL FSS Technetium-99 U 0.165 +/-0.222 0.183 +/-0.222 0.374 pCi/g KXRI 10/02/06 1055 571877 10 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB] 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I DOE EML HASL-300, Am-05-RC Modified 2 DOE EML HASL-300, Pu- 11-RC Modified 3 DOE EML HASL-300, Pu-I 1-RC Modified 4 EML HASL 300, 4.5.2.3 5 EPA 905.0 Modified 6 EPA 906.0 Modified 7 EPA EERF C-01 Modified 8 DOE RESL Fe-1, Modified 9 DOE RESL Ni-l, Modified 10 DOE EML HASL-300, Tc-02-RC Modified Surrogate/Tracer recovery Recovery% Acceptable Limits Americium-243 Alphaspec Am24 1,Cm, Solid ALL 94 (15%-125%)

Plutonium-242 Alphaspec Pu, Solid-ALL FSS 99 (15%-125%)

Carrier/Tracer Recovery Liquid Scint Pu241, Solid-ALL FS 95 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 92 (25%-125%)

Carrier/Tracer Recovery Liquid Scint Fe55, Solid-ALL FS 68 (15%-125%)

Carrier/Tracer Recovery Liquid Scint Ni63, Solid-ALL FS 70 (25%-125%)

Carrier/Tracer Recovery Liquid Scint Tc99, Solid-ALL FS 63 (15%-125%)

42

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.corn Certificate of Analysis Company: Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-003F Project: YANK01204 Sample ID: 172275003 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B Target analyte was detected in the associated blank BD Results are either below the MDC or tracer recovery is low C Analyte has been conftrmed 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 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.

43

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-004F Project: YANKIK0 1204 Sample ID: 172275004 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 13-SEP-06 Receive Date: 21 -SEP-06 Collector: Client Moisture: 14.4%

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Ganuna Spec Analysis Gamma,.Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.863 +/-0.169 0.0462 +/-0.169 0.101 pCi/g MJHIl 10/03/060640 574335 1 Americium-241 U -0.00206 +/-0.058 0.048 +/-0.058 0.0992 pCi/g Bismuth-212 0.377 +/-0.244 0.0985 +/-0.244 0.213 pCi/g Bismuth-214 0.646 +/-0.0986 0.0267 +/-0.0986 0.0568 pCi/g Cesium-134 U 0.0312 +/-0.0276 0.018 +/-0.0276 0.0384 pCi/g pCilg Cesium-137 U -0.00126 +/-0.0161 0.0141 +/-0.0161 0.0301 Cobalt-60 U 0.00622 +1-0.0174 0.0157 +/-0.0174 0.0344 pCi/g Europium-152 U 0.0205 +/-0.0405 0.0365 +/-0.0405 0.0767 pCi/g

.Europium-154 U -0.00568 +/-0.0572 0.0491 +/-0.0572 0.106 pCi/g Europium-155 U 0.0483 +/-0.0558 0.0388 +/-0.0558 0.0804 pCi/g Lead-212 0.775 +/-0.0787 0.0259 +/-0.0787 0.0535 pCi/g Lead-214 0.667 +/-0.0933 0.0269 +/-0.0933 0.0566 pCi/g Manganese-54 U -0.00358 +/-0.0178 0.015 +/-0.0178 0.0321 pCi/g Niobium-94 U 0.00439 +/-0.0152 0.0136 +/-0.0152 0.0289 pCilg Potassium--40 11.9 .+/-1.04 0.141 +/- 1.04 0.312 pCi/g Radium-226 0.646 +/-0.0986 0.0267 +/-0.0986 0.0568 pCi/g Silver-108m U 0.0023 +/-0.0131 0.0113 +/-0.0131 0.0241 pCi/g Thallium-208 0.264 +/-0.0477 0.0123 +/-0.0477 0.0265 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB 1 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 44

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-004F Proiect: YANK01204 Sample ID: 172275004 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 I Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more 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.

45

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-005F Project: YANK01204 Sample ID: 172275005 Client ID: YANK00l Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 14.5%

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 0.678 +/-0.170 0.056 +/-0.170 0.121 pCi/g MJH1 10/03/06 1051 574335 1 Americium-241 U -0.0294 +/-0.0785 0.0727 +/-0.0785 0.150 pCi/g Bismuth-212 0.485 +/-0.254 0.137 +/-0.254 0.292 pCilg Bismuth-214 0.598 +/-0.0828 0.0305 +/-0.0828 0.0647 pCi/g Cesium-134 U 0.0242 +/-0.0336 0.0214 +/-0.0336 0.0455 pCi/g Cesium-137 U 0.0187 +/-0.0195 0.0174 +/-0.0195 0.0369 pCi/g Cobalt-60 U 0.00172 +/-0.0209 0.018 +/-0.0209 0.0395 pCi/g Europium-152 U 0.00129 +/-0.0502 0.0443 +/-0.0502 0.093 pCi/g Europium-154 U -0.0127 +/-0.0667 0.0559 +/-0.0667 0.121 pCi/g Europium-155 U 0.0208. +/-0.0552 0.0506 +/-0.0552 0.105 pCi/g Lead-212 0.747 +/-0.0649 0.0259 +/-0.0649 0.0539 pCi/g Lead-214 0.625 +/-0.0802 0.0331 +/-0.0802 0.0693 pCi/g Manganese-54 U 0.0177 +/-0.0212 0.0193 +/-0.0212 0.0411 pCi/g Niobium-94 U -0.0084 +/-0.0177 0.0148 +/-0.0177 0.0316 pCi/g Potassium-40 12.1 +/-0.919 0.147 +/-0.919 0.330 pCi/g Radium-226 0.598 +/-0.0828 0.0305 +1-0.0828 0.0647 pCi/g Silver-108m U 0.00158 +/-0.0174 0.0151 +/-0.0174 0.0319 pCi/g Thallium-208 0.237 +/-0.0404 0.0179 +/-0.0404 0.0378 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I EMIL HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 46

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-005F Project: YANKO1204 Sample ID: 172275005 Client ID: YANyK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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.

47

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-00O-006F Project: YANK01204 Sample ID: 172275006 Client ID: YANKOOI Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21 -SEP-06 Collector: Client Moisture: 16.3%

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 1.07 +/-0.186 0.0767 +/-0.186 0.164 pCi/g MJH1 10/03/06 1049 574335 1 Americium-241 U 0.00123 +/-0.0301 0.0282 +/-0.0301 0.058 pCi/g Bismuth-212 0.559 +/-0.281 0.145 +/-0.281 0.311 pCi/g Bismuth-214 0.661 +/-0.101 0.0358 +/-0.101 0.0763 pCi/g Cesium-134 UI 0.00 +/-0.0326 0.027 +/-0.0326 0.0572 pCi/g Cesium-137 U -0.00834 +/-0.0233 0.0194 +/-0.0233 0.0414 pCi/g Cobalt-60 U -0.00223 +/-0.022 0.0184 +/-0.022 0.041 pCi/g Europium-152 U -0.0377 +1-0.0521 0.045 +/-0.0521 0.0949 pCi/g Europium- 154 U 0.0272 +/-0.072 0.0639 +/-0.072 0.139 pCi/g Europium-155 U 0.0135 +/-0.0507 0.0466 +/-0.0507 0.0962 pCi/g Lead-212 0.743 +/-0.0793 0.0384 +/-0.0793 0.079 pCi/g Lead-214 0.653 +/-0.0828 0.0328 +/-0.0828 0.0691 pCi/g Manganese-54 U 0.00649 +/-0.0239 0.0205 +/-0.0239 0.044 pCi/g Niobium-94 U 0.0181 +/-0.0214 0.0195 +/-0.0214 0.0414 pCi/g Potassium-40 12.9 +/-0.976 0.203 +/-0.976 0.448 pCi/g Radium-226 0.661 +/-0.101 0.0358 +/-0.101 0.0763 pCi/g Silver-108m U 0.000501 +/-0.0181 0.016 +/-0.0181 0.034 pCi/g Thallium-208 0.274 +/-0.0451 0.0198 +/-0.0451 0.042 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1745 571421 The following Analytical Methods were performed Method Description EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 48

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 lnjun Hollow Rd East Hampton, Connecticut 06424 Report Date: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-006F Project: YANK01204 Sample ID: 172275006 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B Target analyte was detected in the associated blank BD Results are either below the MDC or tracer recovery is low C Analyte has been confimned 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 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.

49

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-007F Proiect: YANKO1204 Sample ID: 172275007 Client ID: YANKOOl Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 16.3%

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamina,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 1.04 +/-0.231 0.0956 +/-0.231 0.204 pCi/g MJHI 10/03/06 0942 574335 1 Americium-241 U 0.0164 +/-0.0391 0.0342 +/-0.0391 0.0705 pCi/g Bismuth-212 0.619 +/-0.380 0.209 +/-0.380 0.443 pCi/g Bismuth-214 0.704 +/-0.150 0.0501 +/-0.150 0.105 pCi/g pci/g Cesium-134 U1 0.00 +1-0.0551 0.035 +/-0.0551 0.0737 pCi/g Cesium-137 U -0.0154 +/-0.0318 0.0259 +/-0.0318 0.055 pCi/g Cobalt-60 U 0.0125 +/-0.0307 0.0267 +/-0.0307 0.0582 pCi/g Europium-152 U -0.026 +/-0.0732 0.0599 +/-0.0732 0.126 pCi/g Europium-154 U 0.0051 +/-0.100 0.0842 +/-0.100 0.181 pCi/g Europium-155 U 0.0526 +/-0.0654 0.0562 +/-0.0654 0.116 pCi/g Lead-212 0.771 +/-0.0987 0.0509 +/-0.0987 0.104 Lead-214 0.915 +/-0.122 +/-0.122 0.0874 pCi/g 0.0416 Manganese-54 U -0.0344 +/-0.0384 0.0248 +/-0.0384 0.0529 pCi/g Niobium-94 U 0.0132 +/-0.031 0.0268 +/-0.031 0.0563 pCi/g Potassium-40 14.7 +/-1.13 0.236 +/-1.13 0.520 pCi/g Radium-226 0.704 +/-0.150 0.0501 +/-0.150 0.105 pCi/g pCi/g Silver-108m U -0.0191 +/-0.0299 0.0221 +/-0.0299 0.0464 pCi/g Thallium-208 0.300 +/-0.0768 0.0242 +/-0.0768 0.0513 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 50

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-007F Proiect: YANK01204 Sample ID: 172275007 ClientID: YANK00l Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.

U1 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.

51

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-008F Project: YANK01204 Sample ID: 172275008 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client lvlu0s1uIUe: 1990 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 0.0532 +/-0.0818 0.0254 +/-0.082 0.127 pCi/g TCI 09/28/06 1156 572120 1 Curium-242 U -0.00721 +/-0.0141 0.027 +/-0.0142 0.135 pCilg Curium-243/244 U -0.00679 i-l-0.0133 0.0254 +/-0.0133 0.127 pCi/g Alphaspec Pu, Solid-ALL FSS Plutonium-238 U 0.0937 +/-0.131 0.0738 +/-0.131 0.218 pCi/g TCI 09/28/06 1156 572121 2 Plutonium-239/240 U 0.00832 +/-0.079 0.0617 +!-0.079 0.194 pCi/g Liquid Scint Pu241, Solid-ALL FSS Plutonium-241 U 4.23 +/-8.60 7.03 +/-8.61 14.8 pCi/g TC1 09/29/06 2246 572122 3 Rad Gamma Spec Analysis GammaSolid-FSSGAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.976 +/-0.198 0.0581 +/-0.198 0.125 pCilg MJHIl 10/03/06 0943 574335 4 Americium-241 U -0.0602 +/-0.0632 0.0478 +/-0.0632 0.099 pCi/g Bismuth-212 0.758 +/-0.285 0.106 +/-0.285 0.229 pCi/g Bismuth-214 0.583 +/-0.106 0.029 +/-0.106 0.0618 pCi/g Cesium-134 UI 0.00 +/-0.0311 0.0234 +/-0.0311 0.0495 pCi/g Cesium-137 U -0.0136 +/-0.0191 0.0156 +/-0.0191 0.0335 pCi/g Cobalt-60 U 0.00942 +/-0.0186 0.0169 +/-0.0186 0.0373 pCi/g Europium-152 U -0.0506 +/-0.0475 0.0375 +/-0.0475 0.0793 pCi/g Europium-154 U 0.0206 +/-0.0594 0.0529 +/-0.0594 0.115 pCi/g Europium-155 UI 0.00 +/-0.0721 0.0427 +/-0.0721 0.0885 pCi/g Lead-212 0.855 +/-0.088 0.0236 +/-0.088 0.0492 pCi/g Lead-214 0.640 +/-0.0941 0.0296 +/-0.0941 0.0623 pCi/g Manganese-54 U 0.0129 +/-0.0261 0.0148 +/-0.0261 0.0321 pCilg Niobium-94 U 0.00328 +/-0.0155 0.0136 +/-0.0155 0.0293 pCi/g Potassium-40 15.0 +/-1.32 0.123 +/-1.32 0.282 pCi/g Radium-226 0.583 +/-0.106 0.029 +/-0.106 0.0618 pCi/g Silver-108m U 0.0147 +/-0.016 0:0144 +/-0.016 0.0304 pCi/g Thallium-208 0.284 +/-0.0503 0.0148 +/-0.0503 0.0316 pCi/g Rad Gas Flow Proportional Counting GFPC,Sr90, solid-ALL FSS Strontium-90 U 0.00217 +/-0.017 0.0139 +/-0.017 0.033 pCi/g KSDI 09/28/06 0734 572301 5 Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid-HTD2,ALL FSS Tritium 182 +/-16.1 6.41 +/-16.4 13.7 pCi/g DFA1 09/27/06 1841 571884 6 52

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-008F Project: YANK01204 Sample ID: 172275008 Client ID: YANKO01 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis Liquid Scint C14, Solid AII, FSS Carbon-14 U -0.0464 +/-0.099 0.0838 +/-0.099 0.170 pCi/g AXD2 09/25/06 2023 571880 7 Liquid Scint Fe55, Solid-ALL FSS Iron-55 U 0.774 +/-38.8 27.4 +/-38.8 57.2 pci/g MXPI 09/28/06 1753 571874 8 Liquid Scint Ni63, Solid-ALL FSS Nickel-63 U -6.65 +/-7.14 6.17 +/-7.14 12.7 pCi/g MXPJ 09/29/06 1929 571876 9 Liquid Sciti Tc99, Solid-ALL FSS Technetium-99 U -0.0457 +/-0.214 0.180 +/-0.214 0.368 pCi/g KXRI 10/02/06 1127 571877 10 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I DOE EML HASL-300, Am-05-RC Modified 2 DOE EML HASL-300, Pu- II-RC Modified 3 DOE EML HASL-300, Pu-i I-RC Modified 4 EML HASL 300,4.5.2.3 5 EPA 905.0 Modified 6 EPA 906.0 Modified 7 EPA EERF C-01 Modified 8 DOE RESL Fe-1, Modified 9 DOE RESL Ni-l, Modified 10 DOE EML HASL-300, Tc-02-RC Modified Surrogate/Tracer recovery Test Recovery% Acceptable Limits Americium-243 Alphaspec Am241, Cm, Solid ALL 82 (15%-125%)

Plutonium-242 Alphaspec Pu, Solid-ALL FSS 94 (15%-125%)

Carrier/Tracer Recovery Liquid Scint Pu241, Solid-ALL FE 91 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 83 (25%-125%)

Carrier/Tracer Recovery Liquid Scint Fe55, Solid-ALL FS 68 (15%-125%)

Carrier/Tracer Recovery Liquid Scint Ni63, Solid-ALL FS 66 (25%- 125%)

Carrier/Tracer Recovery Liquid Scint Tc99, Solid-ALL FS 63 (15%-125%)

53

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-008F Project: YANK01204 Sample ID: 172275008 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MI)A Units DF Analyst Date Time Batch Mtd Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-009F Project: YANK01204 Sample ID: 172275009 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 14%

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 1.04 +/-0.248 0.0903 +/-0.248 0.180 pCi/g MJHI 10/03/06 0953 574335 1 Americium-241 U 0.0151 +/-0.045 0.0347 +/-0.045 0.0694 pCi/g Bismuth-212 U 0.460 +/-0.476 0.232 +/-0.476 0.464 pCi/g Bismuth-214 0.642 +/-0.127 0.0505 +/-0.127 0.101 pCi/g Cesium- 134 U 0.0541 +/-0.0521 0.0356 +/-0.0521 0.0711 pCi/g Cesium-137 U 0.033 +/-0.0399 0.0297 +/-0.0399 0.0593 pCi/g

.Cobalt-60 U 0.00639 +/-0.0403 0.034 +/-0.0403 0.0679 pCi/g Europium-152 U -0.119 +/-0.112 0.055 +/-0.112 0.110 pCi/g Europium-154 U -0.0098 +/-0.139 0.0974 +/-0.139 0.195 pCi/g Europium-155 U 0.0758 +/-0.0709 0.0579 +/-0.0709 0.116 pCi/g Lead-212 0.719 +/-0.126 0.0395 +/-0.126 0.079 pCi/g Lead-214 0.805 +/-0.131 0.0432 +/-0.131 0.0863 pCi/g Manganese-54 U -0.00895 +/-0.0334 0.0278 +/-0.0334 0.0555 pCi/g Niobium-94 U 0.0464 +/-0.0345 0.0262 +/-0.0345 0.0525 pCi/g Potassium-40 12.8 +/-1.33 0.260 +/-1.33 0.520 pCi/g Radium-226 0.642 +/-0.127 0.0505 +/-0.127 0.101 pCi/g Silver-108m U -0.0253 +/-0.027 0.0212 +/-0.027 0.0424 pCi/g Thallium-208 0.269 +/-0.0623 0.030 +/-0.0623 0.0599 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 55

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-009F Project: YANK01204 Sample ID: 172275009 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-01 OF Project: YANK01204 Sample ID: 172275010 Client ID: YANKOO Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 13.7%

Parameter Qualifier Result Usncertainty 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 0.946 +/-0.187 0.0607 +/-0.187 0.128 pCi/g MJHI1 10/03/06 1320 574335 1 Americium-241 U 0.0349 +/-0.117 0.0919 +/-0.117 0.188 pCi/g Bismuth-212 0.501 +/-0.253 0.106 +/-0.253 0.225 pCi/g Bismuth-214 0.503 4-0.0831 0.0286 +/-0.0831 0.060 pCi/g Cesium-134 U 0.0333 4-0.0331 0.020 +/-0.0331 0.0419 pCi/g Cesium-137 0.0286 -/-0.0217 0.0135 +/-0.0217 0.0285 pCi/g Cobalt-60 U 0.0223 4/-0.0188 0.0177 +/-0.0188 0.0379 pCi/g Europium-152 U -0.00927 4-0.0519 0.0385 +/-0.0519 0.0799 pCi/g Europium-154 U -0.00156 4-0.0563 0.0482 +/-0.0563 0.103 pCi/g Europium-155 U 0.0644 +/-0.0532 0.047 +/-0.0532 0.0963 pCi/g Lead-212 0.873 4/-0.0895 0.0217 +/-0.0895 0.0448 pCi/g Lead-214 0.606 4-0.0895 0.0282 +/-0.0895 0.0586 pCi/g Manganese-54 U 0.0031 4-0.0171 0.0147 +/-0.0171 0.0311 pCi/g Niobium-94 U -0.00738 F/-0.0168 0.014 +/-0.0168 0.0295 pCi/g Potassiurn-40 12.7 +/-1.11 0.106 +/-1.11 0.238 pCi/g Radium-226 0.503 +-0.0831 0.0286 +/-0.0831 0.060 pCi/g Silver-108m U -0.0152 +/-0.0167 0.0134 +/-0.0167 0.0279 pCi/g Thallium-208 0.271 +/-0.0478 0.0142 +/-0.0478 0.0299 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB I 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 57

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-01OF Project: YANK01204 Sample ID: 172275010 Client ID: YANKOOI Vol.,Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mid

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-01 IF Project: YANK01204 Sample ID: 172275011 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 16.5%

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamna,.Solid-FSSGAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.999 +/-0.202 0.0658 +/-0.202 0.142 pCi/g MJHI 10/03/06 1321 574335 1 Americium-241 U -0.11 +/-0.0806 0.0678 +1-0.0806 0.139 pCi/g Bismuth-212 0.572 +/-0.334 0.149 +/-0.334 0.318 pCi/g Bismuth-214 0.604 +/-0.101 0.035 +/-0.101 0.0743 pCi/g Cesium-134 U 0.0109 +/-0.0337 0.0206 +/-0.0337 0.0441 pCi/g Cesium-137 U -0.0232 +/-0.0224 0.0172 +/-0.0224 0.0368 pCi/g Cobalt-60 U 0.0312 +/-0.0237 0.0212 +/-0.0237 0.0462 pCi/g Europium-152 U -0.0113 +/-0.0579 0.0501 +/-0.0579 0.105 pCi/g Europium-154 U -0.0377 +/-0.0663 0.0526 +/-0.0663 .0.116 pCi/g Europium-155 U 0.0637 +/-0.064 0.0574 +/-0.064 0.118 pCi/g Lead-212 0.892 +/-0.0934 0.0297 +/-0.0934 0.0615 pCi/g Lead-214 0.637 +/-0.099 0.0347 +/-0.099 0.0728 pCi/g Manganese-54 U 0.0212 +/-0.0239 0.0213 +/-0.0239 0.0452 pCi/g Niobium-94 U 0.0181 +/-0.0195 0.0175 +/-0.0195 0.0373 pCi/g Potassium-40 13.5 +/-1.18 0.137 +/-1.18 0.313 pCi/g Radium-226 0.604 +/-0.101 0.035 +/-0.101 0.0743 pCi/g Silver-108m U -0.00596 +/-0.0191 0.0162 +/-0.0191 0.0342 pCi/g Thallium-208 0.274 +/-0.0528 0.0187 +/-0.0528 0.0397 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1745 571421 The following Analytical Methods were performed Method Description EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defmed as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 59

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-01IF Project: YANK01204 Sample ID: 172275011 Client ID: YANK00I Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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.

60

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-012F Proiect: YANK01204 Sample ID: 172275012 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 1L fl Parameter Qualifier Result Uincertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamma,Solid-FSSGAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.909 +/-0.218 0.0682 +/-0.218 0.148 pCi/g MJHI 10/03106 1321 574335 1 Americium-241 U -0.0317 +/-0.155 0.0882 +/-0.155 0.182 pCi/g Bismuth-212 0.593 +/-0.345 0.161 +/-0.345 0.343 pCi/g Bismuth-214 0.657 +/-0.0919 0.0403 +/-0.0919 0.0854 pCi/g Cesium-134 UI 0.00 +/-0.0345 0.0287 +/-0.0345 0.0606 pCi/g Cesium-137 U 0.0436 +/-0.0365 0.0224 +/-0.0365 0.0476 pCi/g Cobalt-60 U -0.00429 +/-0.0219 0.0174 +/-0.0219 0.0392 pCi/g Europiurn-152 U 0.0138 +/-0.066 0.0562 +/-0.066 0.118 pCi/g Europium-154 U -0.0425 +/-0.0811 0.0627 +/-0.0811 0.137 pCi/g Europiurn-155 U 0.0464 +/-0.0703 0.0638 +/-0.0703 0.132 pCi/g Lead-212 0.893 +/-0.0692 0.0314 +/-0.0692 0.0652 pCi/g Lead-214 0.700 +/-0.104 0.0397 +/-0.104 0.0832 pCi/g Manganese-54 U 0.041 +/-0.0265 0.0215 +/-0.0265 0.046 pCi/g Niobium-94 U 0.0269 +/-0.021 0.0187 +/-0.021 0.0399 pCi/g Potassium-40 13.9 +/-1.13 0.189 +/-1.13 0.421 pCi/g Radium-226 0.657 +/-0.0919 0.0403 +/-0.0919 0.0854 pCi/g Silver-108m U -0.00418 +/-0.026 0.0185 +/-0.026 0.0391 pCi/g pCi/g Thallium-208 0.228 +/-0.0521 0.0214 +/-0.0521 0.0453 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 61

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-012F Project: YANK01204 Sample ID: 172275012 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-012FS Project: YAN-KO1204 Sample ID: 172275013 Client ID: YANKOO I Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 16.8%

Parameter Qualifier Result Uncertainty LC - TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gammna,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.848 +/-0.206 0.0808 +/-0.206 0.174 pCi/g MJHI 10/03/06 1321 574335 1 Americium-241 U -0.00901 +/-0.0398 0.0344 +/-0.0398 0.0707 pCilg Bismuth-212 0.794 +/-0.464 0.183 +/-0.464 0.390 pCi/g Bismuth-214 0.689 +/-0.120 0.045 +/-0.120 0.0951 pCi/g Cesium-134 U 0.0733 +/-0.0547 0.0352 +/-0.0547 0.0739 pCi/g Cesium-137 UI 0.00 +/-0.0737 0.0254 +/-0.0737 0.0537 pCi/g Cobalt-60 U -0.0099 +/-0.0316 0.0255 +/-0.0316 0.0555 pCi/g Europium-152 U 0.0273 +/-0.0711 0.0612 +/-0.0711 0.128 pCi/g Europium-154 U -0.0104 +1-0.099 0.0705 +/-0.099 0.153 pCi/g Europium-155 UI 0.00 +/-0.0984 0.0517 +/-0.0984 0.107 pCi/g Lead-212 0.737 +/-0.0899 0.0456 +1-0.0899 0.0937 pCi/g Lead-214 0.714 +/-0.104 0.0443 +/-0.104 0.0926 pCi/g Manganese-54 U 0.0221 +/-0.0316 0.0276 +/-0.0316 0.0585 pCi/g Niobium-94 U 0.0163 +/-0.0292 0.0256 +/-0.0292 0.0538 pCi/g Potassium--40 13.7 +/-1.14 0.234 +/-1.14 0.513 pCi/g Radium-226 0.689 +/-0.120 0.045 +/-0.120 0.0951 pCi/g Silver-108m U -0.0206 +/-0.0243 0.0205 +/-0.0243 0.0431 pCi/g Thallium-208 0.333 +/-0.0617 0.0233 +/-0.0617 0.0493 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 09/21/06 1745 571421 The following Analytical Methods were performed Method Description 1 EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 63

GENERAL ENGINEERING 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: October 5,2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-012FS Project: YANK01204 Sample ID: 172275013 Client ID: YANKOOI Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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

GENERAL ENGINEERING 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: October 5, 2006 Contact Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-013F Project: YANK01204 Sample ID: 172275014 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 14.6%

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 0.0935 +/-0.132 0.0561 +/-0.133 0.210 pCi/g TCI 09/28/06 1156 572120 1 Curium-242 U 0.00 -*4-0.0752 0.00 +/-0.0752 0.104 pCi/g Curium-243/244 U -0.026 - -/-0.0294 0.0561 +/-0.0296 0.210 pCi/g Alphaspec Pu, Solid-ALL FSS Plutonium-238 U 0.0164 +/-0.110 0.0863 +/-0.110 0.242 pCi/g TCI 09/28/06 1156 572121 2 Plutonium-239/240 U -0.0719 -/-0.0894 0.103 +/-0.0897 0.276 pCi/g Liquid Scint Pu241, Solid-ALL FSS Plutonium-241 U 4.77 +/-8.34 6.78 +/-8.35 14.2 pCi/g TC1 09/29/06 2302 572122 3 Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 1.02 +/-0.172 0.0702 +/-0.172 0.153 pCi/g MJHI 10/03/06 1322 574335 4 Americium-241 U -0.0146 -/-0.0306 0.0251 +/-0.0306 0.0518 pCi/g Bismuth-212 0.755 +/-0.351 0.153 +/-0.351 0.329 pCi/g Bismuth-214 0.547 +/-0.111 0.0394 +/-0.111 0.0838 pCi/g Cesium-134 U 0.0516 r/-0.0574 0.0281 +/-0.0574 0.0597 pCi/g Cesium-137 U -0.00251 4-0.0261 0.0217 +/-0.0261 0.0463 pCi/g Cobalt-60 U 0.0212 4-0.0288 0.0259 +/-0.0288 0.0566 pCi/g Europium-152 U -0.017 4-0.0579 0.0467 +/-0.0579 0.0986 pCi/g Europiumn-154 U -0.0293 +/-0.0998 0.0684 +/-0.0998 0.150 pCi/g Europium-155 U 0.0349 4/-0.0463 0.0427 +/-0.0463 0.0886 pCi/g Lead-212 0.791 P/-0.0798 0.0376 +/-0.0798 0.0775 pCi/g Lead-214 0.703 +/-0.097 0.0344 +/-0.097 0.0726 pCi/g Manganese-54 U 0.0418 F/-0.0282 0.021 +/-0.0282 0.0451 pCi/g Niobium-94 U 0.00697 F/-0.0239 0.0204 +/-0.0239 0.0433 pCi/g Potassium-40 15.2 +/-1.17 0.176 +/-1.17 0.400 pCi/g Radium-226 0.547 +/-0.111 0.0394 +/-0.111 0.0838 pCi/g Silver-108m U-0.000887 +/-0.0188 0.0163 +/-0.0188 0.0347 pCi/g Thallium-208 0.322 +/-0.0575 0.019 +/-0.0575 0.0406 pCi/g Rad Gas Flow Proportional Counting GFPC,Sr90, solid-ALL FSS Strontium-90 U 0.0134 +/-0.02'11 0.0159 +/-0.0211 0.0368 pCi/g KSDI 09/28/06 0734 572301 5 Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid-HTD2,ALL FSS Tritium U 3.43 +/-7.85 6.38 +/-7.85 13.6 pCi/g DFAI 09/27/06 1858 571884 6 65

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-00O0-013F Project: YANKO1204 Sample ID: 172275014 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis Liquid Scint C14, Solid AlI,FSS Carbon-14 U -0.115 +/-0.101 0.0866 +/-0.101 0.176 pCi/g AXD2 09/25/06 2135 571880 7 Liquid Scint Fe55, Solid-ALL FSS Iron-55 U -26.8 +/-36.1 26.4 +/-36.1 55.2 pCi/g MXPI 09/28/06 1809 571874 8 Liquid Scin Ni63, Solid-ALL FSS Nickel-63 U -3.05 +/-9.26 7.85 +/-9.26 16.2 pCi/g MXPI 09/29/06 2015 571876 9 Liquid Scint Tc99, Solid-ALL FSS Technetium-99 U 0.153 +/-0.193 0.159 +/-0.193 0.324 pCi/g KXRI 10/02/06 1159 571877 10 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I DOE EML HASL-300, Am-05-RC Modified 2 DOE EML HASL-300, Pu- II-RC Modified 3 DOE EML HASL-300, Pu-1 I-RC Modified 4 EML HASL 300, 4.5.2.3 5 EPA 905.0 Modified 6 EPA 906.0 Modified 7 EPA EERF C-0I Modified 8 DOE RESL Fe-I, Modified 9 DOE RESL Ni-1, Modified 10 DOE EML HASL-300, Tc-02-RC Modified Surrogate/Tracer recovery Test Recovery% Acceptable Limits Americium-243 Alphaspec Am241, Cm, Solid ALL 63 (15%-125%)

Plutonium-242 Alphaspec Pu, Solid-ALL FSS 93 (15%-125%)

Carrier/Tracer Recovery Liquid Scint Pu241, Solid-ALL Fý 100 (25%-125%)

Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 89 (25%-125%)

Carrier/Tracer Recovery Liquid Scint Fe55, Solid-ALL FS 66 (15%-125%)

Carrier/Tracer Recovery Liquid Scint Ni63, Solid-ALL FS 53 (25%-125%)

Carrier/Tracer Recovery Liquid Scint Tc99, Solid-ALL FS 72 (15%-125%)

66

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-013F Project: YANK01204 Sample ID: 172275014 Client ID: YANKOO Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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.

67

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-014F Project: YANK01204 Sample ID: 172275015 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 15%

Parameter Qualifier Result Ui icertainty 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 0.938 +/-0.203 0.0562 +/-0.203 0.123 pCi/g MJH1 10/03/06 1322 574335 1 Americium-241 U -0.00605 +/-0.0653 0.0549 +/-0.0653 0.114 pCi/g Bismuth-212 0.845 +/-0.285 0.119 +/-0.285 0.259 pCi/g Bismuth-214 0.584 +/-0.124 0.0344 +/-0.124 0.0732 pCi/g Cesium-134 UI 0.00 F/-0.0329 0.0263 +/-0.0329 0.0557 pCi/g Cesium-137 U 0.00818 Y-0.0237 0.0208 +/-0.0237 0.0441 pCi/g Cobalt-60 U 0.011 F/-0.0186 0.0163 +/-0.0186 0.0366 pCi/g Europium-152 U -0.0249 +/-0.0482 0.0388 +/-0.0482 0.0825 pCilg Europium-154 U 0.0465 F/-0.0658 0.0603 +/-0.0658 0.131 pCi/g Europium-155 U 0.0523 +/-0.0687 0.0453 +/-0.0687 0.0942 pCi/g Lead-212 0.950 +/-0.0975 0.0271 +/-0.0975 0.0565 pCi/g Lead-214 0.708 +/-0.109 0.0295 +/-0.109 0.0626 pCi/g Manganese-54 U 0.00474. +/-0.0277 0.0178 +/-0.0277 0.0383 pCi/g Niobium-94 U 0.0238 +/-0.0237 0.0166 +/-0.0237 0.0354 pCi/g Potassiunm-40 15.8 +/-1.38 0.128 +/-1.38 0.296 pCi/g Radium-226 0.584 +/-0.124 0.0344 +/-0.124 0.0732 pCi/g Silver-108m U -0.00146 +I-0.0178 0.0146 +1-0.0178 0.0311 pCi/g Thallium-208 0.307 +/-0.0526 0.0172 +/-0.0526 0.0368 pCi/g The following Prep Methods were performed Method - Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 68

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-014F Project: YANK01204 Sample ID: 172275015 Client ID: yANK001I Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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.

69

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-015F Project: YANK01204 Sample ID: 172275016 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 11.3%

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Ganima,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.702 +/-0.169 0.0373 +/-0.169 0.0864 pCi/g MJHl 10/03/06 1323 574335 1 Americium-241 U 0.0258 +/-0.0299 0.0297 +/-0.0299 0.0611 pCi/g Bismuth-212 0.486 +/-0.316 0.148 +/-0.316 0.318 pCi/g Bismuth-214 0.491 +/-0.103 0.0345 +/-0.103 0.0739 pCilg Cesium-134 U 0.0563 +/-0.048 0.027 +/-0.048 0.0573 .pCi/g Cesium-137 U 0.0129 +/-0.0242 0.0219 +/-0.0242 0.0466 pCi/g Cobalt-60 U 0.00658 +/-0.0246 0.0216 +/-0.0246 0.0477 pCi/g Europium-152 U -0.0298 +/-0.0474 0.0416 +/-0.0474 0.0883 pCi/g Europium-154 U -0.0013 +/-0.0656 0.056 +/-0.0656 0.124 pCi/g Europium-155 U 0.0486 +/-0.0744 0.0449 +1-0.0744 0.0929 pCi/g Lead-212 0.686 +/-0.0571 0.0278 +/-0.0571 0.0578 pCi/g Lead-214 0.552 +/-0.082 0.0324 +/-0.082 0.0684 pCi/g Manganese-54 U -0.00757 +/-0.028 0.0199 +/-0.028 0.0429 pCi/g Niobium-94 U-0.000502 +/-0.0218 0.0187 +/-0.0218 0.040 pCi/g Potassium-40 11.8 +/-1.02 0.181 +/-1.02 0.408 pCi/g Radium-226 0.491 +/-0.103 0.0345 +/-0.103 0.0739 pCi/g Silver-108m U -0.00694 +/-0.0193 0.0169 +/-0.0193 0.0358 pCi/g Thallium-208 0.215 +/-0.0455 0.0192 +/-0.0455 0.0411 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I EML HASL 300,4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 70

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-015F Project: YANK01204 Sample ID: 172275016 ClientID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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.

71

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic P.ower Address : 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-016F Project: YANK01204 Sample ID: 172275017 Client ID: YANKOOI Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 15.5%

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis GammaSolid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.803 +/-0.139 0.0499 +/-0.139 0.106 pCi/g MiHi 10/03/06 1323 574335 1 Americium-241 U -0.0807 +/-0.109 0.0814 +/-0.109 0.169 pCi/g Bismuth-212 0.705 +/-0.192 0.099 +/-0.192 0.211 pCi/g Bismuth-214 0.588 +/-0.0736 0.0279 +/-0.0736 0.0585 pCi/g Cesium-134 UI 0.00 +/-0.0229 0.0134 +/-0.0229 0.0287 pCi/g Cesium-137 U 0.00601 +/-0.0211 0.0157 +/-0.0211 0.0331 pCi/g Cobalt-60 U -0.00939 +/-0.0171 0.0139 +/-0.0171 0.0302 pCi/g Europium-152 U -0.0448 +/-0.0436 0.0367 +/-0.0436 0.0767 pCi/g Europium-154 U 0.0344 +/-0.0517 0.047 +/-0.0517 0.101 pCi/g Europiurn-155 U -0.03 +/-0.0552 0.0492 +/-0.0552 0.102 pCi/g Lead-212 0.776 +/-0.0539 0.0231 +/-0.0539 0.0479 pCi/g Lead-214 0.679 +/-0.0763 0.0287 +/-0.0763 0.0599 pCi/g Manganese-54 0.0304 +/-0.0219 0.0132 +/-0.0219 0.0281 pCi/g Niobium-94 U 0.00961 +/-0.0156 0.0142 +/-0.0156 0.0298 pCi/g Potassium-40 14.1 +/-0.801 0.117 +/-0.801 0.258 pCi/g Radium-226 0.588 +/-0.0736 0.0279 +/-0.0736 0.0585 pCi/g Silver-108m U 0.00385 +/-0.0144 0.0127 +/-0.0144 0.0267 pCi/g Thallium-208 0.264 +/-0.0388 0.0122 +/-0.0388 0.026 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1745 571421 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 72

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-016F Proiect: YANK01204 Sample ID: 172275017 Client ID: YANKOOI Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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.

73

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-017F Proiect: YANK01204 Sample ID: 172275018 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 2 1-SEP-06 Collector: Client Moisture: 14.2%

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gammna,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.687 +/-0.127 0.0429 +/-0.127 0.0915 pCi/g MJH1 10/03/06 1323 574335 1 Americium-241 U 0.0675 +1-0.0841 0.0478 +/-0.0841 0.0987 pCi/g Bismuth-212 0.582 +/-0.214 0.0884 +/-0.214 0.188 pCi/g

+/-0.0692 0.0241 +/-0.0692 0.0506 pCi/g Bismuth-214 0.537 Cesium-134 U1 0.00 +/-0.0214 0.0165 +/-0.0214 0.0347 pCi/g 0.0119 +/-0.0292 0.0253 pCi/g Cesium-137 0.0334 +/-0.0292 U 0.00613 +/-0.0115 0.0126 +/-0.0115 0.0272 pCi/g Cobalt-60 Europium-152 U -0.011 +/-0.0452 0.0348 +/-0.0452 0.0725 pCi/g 0.0391 +/-0.0437 0.0839 pCi/g Europium-154 U 0.0334 +/-0.0437 0.0445 +/-0.0471 0.0916 pCi/g Europium-155 U 0.0628 +/-0.0471 Lead-212 0.727 +/-0.0505 0.0214 +/-0.0505 0.0441 pCi/g Lead-214 0.545 +/-0.0642 0.0253 +/-0.0642 0.0527 pCi/g Manganese-54 U 0.0189 +/-0.0168 0.012 +/-0.0168 0.0256 pCi/g Niobium-94 U 0.00811 +/-0.0127 0.0117 +/-0.0127 0.0247 pCi/g 0.0872 +/-0.696 0.195 pCi/g Potassium-40 12.8 +/-0.696 Radium-226 0.537 +/-0.0692 0.0241 +/-0.0692 0.0506 pCi/g Silver-108m U -0.00478 +/-0.0128 0.0109 +/-0.0128 0.0229 pCi/g pCi/g Thallium-208 0.244 +/-0.0341 0.0115 +/-0.0341 0.0244 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB1 09/21106 1745 571421 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 74

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-017F Project: YANK01204 Sample ID: 172275018 Client lID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.

UT 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.

75

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-018F Proiect: YANK01204 Sample ID: 172275019 Client ID: YANKOO Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector. Client Moisture; 14.8%

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 Ingrowrh Waived Actinium-228 0.923 +/-0.174 0.068 +/-0.174 0.136 pCi/g MJH1 10/03/06 1338 574335 1 Americium-241 U 0.0219 +/-0.0658 0.0546 +/-0.0658 0.109 pCi/g Bismuth-212 0.440 +/-0.270 0.126 +/-0.270 0.252 pCi/g Bismuth-214 0.464 +/-0.0854 0.0291 +/-0.0854 0.0582 pCi/g Cesium-134 U 0.0248 +/-0.0274 0.0208 +/-0.0274 0.0415 pCi/g Cesium-137 U 0.00239 +/-0.0186 0.016 +/-0.0186 0.032 pCi/g Cobalt-60 U -0.00503 +/-0.0201 0.0164 +/-0.0201 0.0329 pCi/g Europium-152 U -0.0649 +/-0.0619 0.0411 +/-0.0619 0.0821 pCi/g Europium-154 U 0.0374 +/-0.0633 0.0564 +/-0.0633 0.113 pCi/g Europium-155 U 0.0114 +/-0.0528 0.0483 +/-0.0528 0.0965 pCi/g Lead-212 0.691 +/-0.0767 0.0251 +i-0.0767 0.0501 pCi/g Lead-214 0.624 +/-0.0813 0.0297 +/-0.0813 0.0594 pCi/g Manganese-54 U 0.0193 +/-0.0205 0.0153 +/-0.0205 0.0305 pCi/g Niobium-94 U 0.00598 +/-0.0168 0.0153 +/-0.0168 0.0305 pCi/g Potassium-40 13.2 +/-1.11 0.152 +/-1.11 0.304 pCi/g Radium-226 0.464 +/-0.0854 0.0291 +/-0.0854 0.0582 pCi/g Silver-108m U 0.00189 +/-0.0166 0.0147 +/-0.0166 0.0294 pCi/g Thallium-208 0.251 +/-0.0431 0.0153 +/-0.0431 0.0305 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMiBI 09/21/06 1745 571421 The following Analytical Methods were performed Method Description 1 EMNL HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 76

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-018F Project: YANK01204 Sample ID: 172275019 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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.

77

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-018FS Proiect: YANK01204.

Sample ID: 172275020 Client ED: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector: Client lMni~tiir" 1A 10/-

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamrna,Solid-FSSGAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.691 +/-0.160 0.0638 +/-0.160 0.127 pCi/g MJHI 10/03/06 1338 574335 1 Americium-241 U 0.000277 +/-0.0873 0.0698 +/-0.0873 0.140 pCi/g Bismuth-212 0.470 +/-0.304 0.135 +/-0.304 0.271 pCi/g Bismuth-214 0.547 +/-0.110 0.0369 +1-0.110 0.0738 pCi/g Cesium-134 U 0.0256 +/-0.0423 0.0229 +/-0.0423 0.0459 pCi/g Cesium-137 U 0.00688 +/-0.021 0.0183 +/-0.021 0.0366 pCi/g Cobalt-60 U 0.0011 +/-0.0226 0.0191 +/-0.0226 0.0383 pCi/g Europium-152 U 0.00634 +/-0.0716 0.0485 +/-0.0716 0.097 pCi/g Europium-154 U -0.0402 +/-0.0712 0.0566 +/-0.0712 0.113 pCi/g Europium-155 U -0.0112 +/-0.0615 0.0533 +/-0.0615 0.107 pCi/g Lead-212 0.799 +/-0.0923 0.0276 +/-0.0923 0.0553 pCi/g Lead-214 0.544 +/-0.102 0.0333 +/-0.102 0.0666 pCi/g Manganese-54 U 0.0253 +/-0.024 0.0201 +/-0.024 0.0402 pCi/g Niobium-94 U -0.00717 +/-0.0195 0.016 +/-0.0195 0.0319 pCi/g Potassium-40 13.3 +/-1.21 0.138 +/-1.21 0.275 pCi/g Radium-226 0.547 +/-0.110 0.0369 +/-0.110 0.0738 pCi/g Silver-108m U 0.000576 +/-0.0187 0.0163 +/-0.0187 0.0326 pCi/g Thallium-208 0.268 +/-0.0467 0.0177 +/-0.0467 0.0353 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1745 571421 The following Analytical Methods were performed Method Description 1 EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 78

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-018FS Project: YANK01204 Sample ID: 172275020 Client ID: YANKOOI Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MIDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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.

79

GENERAL ENGINEERING 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 Report Date: October 5, 2006 East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-019F Project: YANK01204 Sample ID: 172275021 ClientID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 16.4%

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 0.781 +/-0.176 0.0467 +/-0.176 0.0998 pCi/g MJHI 10/02/06 1140 574336 1 Americium-241 U -0.0732 +/-0.111 0.0891 +/-0.111 0.183 pCi/g Bismuth-212 0.448 +/-0.205 0.114 +/-0.205 0.240 pCi/g Bismuth-214 0.550 +/-0.0849 0.0243 +/-0.0849 0.0514 pCi/g Cesium-134 UI 0.00 +/-0.0362 0.0187 +/-0.0362 0.0393 pCi/g Cesium-137 U-0.000324 +/-0.0172 0.0152 +/-0.0172 0.032 pCi/g Cobalt-60 U 0.0165 +/-0.0175 0.0164 +/-0.0175 0.0353 pCi/g Europium-152 U -0.00565 +/-0.0423 0.0372 +/-0.0423 0.0774 pCi/g Europium-154 U 0.0409 +/-0.0545 0.050 44-0.0545 0.107 pCi/g Europium-155 U 0.0304 +/-0.0501 0.0458 +/-0.0501 0.094 pCi/g Lead-212 0.736 +/-0.0767 0.0221 +/-0.0767 0.0456 pCi/g Lead-214 0.535 +/-0.0837 0.0272 +/-0.0837 0.0566 pCi/g Manganese-54 U 0.0163 +/-0.0197 0.0146 +/-0.0197 0.031 pCi/g Niobium-94 U 0.0159 +/-0.0221 0.0155 +/-0.0221 0.0324 pCi/g Potassium-40 13.2 +/-1.16 0.128 +/-1.16 0.280 pCi/g Radium-226 0.550 +/-0.0849. 0.0243 +/-0.0849 0.0514 pCi/g Silver-108m U 0.0141 +/-0.0142 0.013 +/-0.0142 0.0272 pCi/g Thallium-208 0.280 +/-0.0459 0.0121 +/-0.0459 0.0257 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1749 571423 The following Analytical Methods were performed Method Description EMIL HASL 300,4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 80

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-019F Project: YANK01204 Sample ID: 172275021 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 dr6 weight basis.

81

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-020F Project: YANK01204 Sample ID: 172275022 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 15.3%

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis GammaSolid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.903 +/-0.174 0.0588 +/-0.174 0.127 pCi/g MJHI 10/02/06 1342 574336 1 Americium-241 U 0.0644 +/-0.0757 0.071 +/-0.0757 0.145 pCi/g Bismuth-212 0.768 +/-0.253 0.122 +/-0.253 0.262 pCi/g Bismuth-214 0.500 +/-0.0932 0.0321 +/-0.0932 0.068 pCi/g Cesium-134 UI 0.00 +/-0.0427 0.0229 +/-0.0427 0.0484 pCi/g Cesium-137 U 0.0353 +/-0.0213 0.0183 +/-0.0213 0.0388 pCitg Cobalt-60 U 0.00823 +/-0.0247 0.019 +/-0.0247 0.0415 pCi/g Europium-152 U 0.00463 +/-0.0538 0.0479 +/-0.0538 0.100 pCi/g Europium-154 U 0.00445 +/-0.067 0.0576 +/-0.067 0.125 pCi/g Europium-155 U 0.0843 +/-0.0702 0.0481 +/-0.0702 0.0992 pCi/g Lead-212 0.904 +/-0.0912 0.0272 +/-0.0912 0.0563 pCi/g Lead-214 0.599 +/-0.0939 0.0341 +/-0.0939 0.0713 pCi/g Manganese-54 U 0.0201 +/-0.0415 0.0181 +/-0.0415 0.0385 pCi/g Niobium-94 U 0.0139 +/-0.0214 0.0168 +/-0.0214 0.0355 pCi/g Potassium-40 14.1 +/-1.21 0.156 +/-1.21 0.347 pCi/g Radium-226 0.500 +/-0.0932 0.0321 +/-0.0932 0.068 pCi/g Silver-108m U -0.0173 +/-0.0177 0.0144 +/-0.0177 0.0305 pCi/g Thallium-208 0.283 +/-0.0422 0.016 +/-0.0422 0.0339 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep .. Dry Soil Prep GL-RAD-A-021 JMB1 09/21/06 1749 571423 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 82

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-020F Proiect: YANK01204 Sample ID: 172275022 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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.

83

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000--021F Proiect: YANK01204 Sample ID: 172275023 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 2 1-SEP-06 Collector: Client Moisture: 14.2%

Parameter Qualifier Result U ncertalnty 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 0.804 +/-0.168 0.0754 +/-0.168 0.161 pCi/g MJHI 10/02/06 1342 574336 1 Americium-241 U 0.00322 +/-0.0321 0.0295 +/-0.0321 0.0607 pCi/g Bismuth-212 U 0.341 +/-0.296 0.169 +/-0.296 0.357 pCi/g Bismuth-214 0.573 +/-0.0993 0.0365 +/-0.0993 0.0772 pCi/g Cesium-134 U 0.0536 +/-0.0434 0.0277 +/-0.0434 0.0582 pCi/g Cesium-137 UI 0.00 +/-0.0652 0.0212 +/-0.0652 0.0448 pCi/g Cobalt-60 U -0.026 +/-0.0285 0.0219 +/-0.0285 0.0474 pCi/g Europium-152 U 0.0168 +/-0.0573 0.0505 +/-0.0573 0.106 pCi/g Europium-154 U 0.0284 +/-0.0712 0.0628 +/-0.0712 0.136 pCi/g Europium-155 Ul 0.00 +/-0.0795 0.0449 +/-0.0795 0.0928 pCi/g Lead-212 0.605 +/-0.0705 0.0398 +/-0.0705 0.0817 pCi/g Lead-214 0.597 +/-0.0881 0.0356 +/-0.0881 0.0744 pCi/g Manganese-54 U 0.0308 +/-0.0275 0.0227 +/-0.0275 0.048 pCi/g Niobium-94 U .- 0.0104 +/-0.021 0.0175 +/-0.021 0.0371 pCi/g Potassium-40 11.8 +/- 1.02 0.189 +/-1.02 0.415 pCi/g Radium-226 0.573 +/-0.0993 0.0365 +/-0.0993 0.0772 pCi/g Silver-108m U 0.00472 +/-0.0192 0.0176 +/-0.0192 0.0371 pCi/g Thallium-208 0.217 +/-0.0616 0.0209 +/-0.0616 0.044 pCi/g The following Prep Methods were performed Method Description Analyst Date Time PrepBatch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1749 571423 The following Analytical Methods were performed Method Description EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are def'ied as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 84

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-021F Project: YANK01204 Sample ID: 172275023 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B Target analyte was detected in the associated blank BD Results are either below the MIDC 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 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.

85

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-022F Project: YANK01204 Sample ID: 172275024 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21 -SEP-06 Collector: Client Moisture: 12.7%

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Gamnnia,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.768 +/-0.137 0.0508 +/-0.137 0.108 pCi/g MJHI 10/02/06 1343 574336 1 Americium-241 U 0.040 +/-0.104 0.0846 +/-0.104 0.175 pCilg Bismuth-212 0.533 +/-0.205 0.103 +/-0.205 0.219 pCi/g Bismuth-214 0.569 +/-0.0753 0.0272 +/-0.0753 0.0571 pCilg Cesium-134 Ut 0.00 +/-0.023 0.0168 +/-0.023 0.0355 pCi/g Cesium-137 U 0.0288 +/-0.0254 0.0144 +/-0.0254 0.0303 pCi/g Cobalt-60 U 0.0109 +/-0.0158 0.0145 +/-0.0158 0.0312 pCi/g Europium-152 U -0.00332 +/-0.0447 0.0351 +/=0.0447 0.0734 pCi/g Europium-154 U -0.0303 +/-0.0481 0.0393 +/-0.0481 0.0849 pCi/g Europium-155 U 0.0221 +/-0.0517 0.0485 +/-0.0517 0.100 pCi/g Lead-212 0.813 +/-0.0536 0.0216 +/-0.0536 0.0449 pCi/g Lead-214 0.604 +/-0.0652 0.025 +/-0.0652 0.0524 pCi/g Manganese-54 U -0.0119 +/-0.0153 0.0125 +/-0.0153 0.0266 pCi/g Niobium-94 U 0.00375 +/-0.0147 0.0132 +/-0.0147 0.0277 pCUg Potassium-40 13.8 +/-0.766 0.124 +/-0.766 0.271 pCi/g Radium-226 0.569 +/-0.0753 0.0272 +/-0.0753 0.0571 pCi/g Silver-108m U 0.0117 +/-0.0139 0.0128 +/-0.0139 0.0267 pCi/g Thallium-208 0.257 +/-0.0386 0.0133 +/-0.0386 0.0279 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 09/21/06 1749 571423 The following Analytical Methods were performed Method Description 1 EML HASL 300,4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 86

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-022F Project: YANK01204 Sample ID: 172275024 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greaterthan value reported A The TIC is a suspected aldol-condensation product B 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 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.

87

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-023F Proiect: YANK01204 Sample ID: 172275025 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector: Client 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 Jngrowth Waived Actinium-228 0.672 +/-0.128 0.0409 +/-0.128 0.0868 pCi/g MJHI 10/02/06 1343 574336 1 Americium-241 U -0.00365 +/-0.0563 0.0487 +/-0.0563 0.100 pCi/g Bismuth-212 0.548 +/-0.201 0.0816 +/-0.201 0.173 pCi/g Bismuth-214 0.488 +/-0.0713 0.0212 +/-0.0713 0.0446 pCi/g Cesium-134 UI 0.00 +/-0.0277 0.0158 +/-0.0277 0.0331 pCilg Cesium-137 0.0256 +/-0.0242 0.011 +/-0.0242 0.0233 pCi/g Cobalt-60 U -0.00147 +/-0.0139 0.0115 +/-0.0139 0.0249 pCi/g Europium- 152 U -0.0189 +1-0.0344 0.0304 +/-0.0344 0.0634 pCi/g Europium- 154 U -0.0143 +/-0.0401 0.0326 +/-0.0401 0.0702 pCi/g Europium- 155 U 0.0701 +/-0.0625 0.0379 +/-0.0625 0.078 pCi/g Lead-212 0.699 +/-0.0454 0.0228 +/-0.0454 0.0468 pCilg Lead-214 0.564 +/-0.0661 0.0215 +/-0.0661 0.0448 pCi/g Manganese-54 U 0.0035 +/-0.0129 0.0116 +/-0.0129 0.0245 pCi/g Niobium-94 U 0.008 +/-0.0121 0.0113 +/-0.0121 0.0236 pCi/g Potassium-40 13.1 +/-0.645 0.074 +/-0.645 0.166 pCi/g Radium-226 0.488 +/-0.0713 0.0212 +/-0.0713 0.0446 pCi/g Silver-108m U -0.0015 +/-0.0115 0.0102 +/-0.0115 0.0213 pCi/g Thallium-208 0.214 +/-0.0277 0.0111 +/-0.0277 0.0233 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JiB 1 09/21/06 1749 571423 The following Analytical Methods were performed Method Description I EMIL HASL 300,4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 88

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.comn Certificate of Analysis Company: Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-023F Proiect: YANKO01204 Sample ID: 172275025 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.

UI Ganmma 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.

89

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-024F Proiect: YANK01204 Sample ID: 172275026 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 16.2%

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 0.755 +/-0.141 0.0509 +/-0.141 0,108 pCi/g MJH1 10/02/06 1502 574336 1 Americium-241 U -0.00337 +/-0.113 0.0931 +/-0.113 0.191 pCi/g Bismuth-212 0.520 +/-0.195 0.118 +/-0.195 0.248 pCi/g Bismuth-214 0.498 +/-0.074 0.0235 +/-0.074 0.0497 pCi/g Cesium-134 U 0.0263 +/-0.0258 0.0187 +/-0.0258 0.0393 pCi/g Cesium-137 U 0.0118 +/-0.0306 0.0149 +/-0.0306 0.0314 pCi/g Cobalt-60 U 0.00876 +/-0.0288 0.0171 +/-0.0288 0.0368 pCi/g Europiurn-152 U -0.0197 +/-0.0448 0.0388 +/-0.0448 0.0806 pCi/g Europium-154 U -0.035 +/-0.051 0.0415 +/-0.051 0.0899 pCilg Europiurn-155 U 0.0896 +/-0.0847 0.0448 +/-0.0847 0.092 pCilg Lead-212 0.679 +/-0.0775 0.025 +/-0.0775 0.0514 pCi/g Lead-214 0.518 +/-0.0749 0.0278 +/-0.0749 0.0578 pCi/g Manganese-54 U 0.0111 +/-0.0156 0.0152 +/-0.0156 0.0321 pCi/g Niobium-94 U -0.00861 +/-0.015 0.0127 +/-0.015 0.0268 pCilg Potassiumn-40 12.1 +/-1.08 0.158 +/-1.08 0.342 pCi/g Radium-226 0.498 +/-0.074 0.0235 +/-0.074 0.0497 pCi/g Silver-108m U -0.013 +/-0.0145 0.0119 +/-0.0145 0.025 pCi/g Thallium-208 0.282 +/-0.0417 0.0155 +/-0.0417 0.0325 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMB I 09/21/06 1749 571423 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 90

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-024F Project: YANK01204 Sample ID: 172275026 Client ID: YANKOO0 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B Target analyte was detected in the associated blank BD Results are either below the MDC or tracer recovery is low C Analyte has been confirnmed 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 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.

91

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-024FS Proiect: YANK01204 Sample ID: 172275027 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector: Client Moisture: 16.9%

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis GammaSolid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.888 . +/-0.160 0.0592 +/-0.160 0.128 pCi/g MJHI 10/02/06 1502 574336 1 Americium-241 U -0.00511 +/-0.0266 0.0232 +/-0.0266 0.0477 pCi/g Bismuth-212 0.445 +/-0.344 0.127 +/-0.344 0.274 pCilg Bismuth-214 0.652 +/-0.0902 0.0265 +/-0.0902 0.057 pCi/g Cesium-134 U 0.0396 +/-0.0287 0.0245 +/-0.0287 0.0519 pCi/g Cesium-137 U 0.00396 +/-0.0217 0.0188 +/-0.0217 0.040 pCi/g Cobalt-60 U 0.0056 +/-0.0266 0.0228 +/-0.0266 0.0494 pCi/g Europium-152 U -0.00788 +/-0.0485 0.0406 +/-0.0485 0.0855 pCi/g Europium-154 U -0.0118 +/-0.0725 0.0599 +/-0.0725 0.130 pCi/g Europium-155 U 0.0372 +/-0.0537 0.0381 +/-0.0537 0.0788 pCi/g Lead-212 0.809 +/-0.0568 0.0238 +/-0.0568 0.0495 pCi/g Lead-214 0.636 +/-0.0814 0.0266 +/-0.0814 0.0563 pCi/g Manganese-54 U 0.00309 +/-0.0214 0.0181 +/-0.0214 0.0388 pCi/g Niobium-94 U 0.0104 +/-0.0189 0.0168 +/-0.0189 0.0357 pCi/g Potassium-40 13.6 +/-0.935 0.154 +/-0.935 0.347 pCi/g Radium-226 0.652 +/-0.0902 0.0265 +/-0.0902 0.057 pCi/g Silver-108m U -0.00209 +/-0.016 0.0142 +/-0.016 0.030 pCi/g Thallium-208 0.287 +/-0.048 0.0166 +/-0.048 0.0354 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMIBI 09/21/06 1749 571423 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 92

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-024FS Proiect: YANK01204 Sample ID: 172275027 Client ID: YANKOOI Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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.

93

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.corn Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-025F Proiect: YANK01204 Sample ID: 172275028 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 2 1-SEP-06 Collector: Client s bLUI I.

oVt 1/70 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Gamma Spec Analysis Ganima,Solid-FSSGAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.575 +/-0.137 0.0443 +/-0.137 0.0963 pCi/g MJH 1 10/02/06 1502 574336 1 Americium-24t U-0.000377 +/-0.0553 0.0502 +/-0.0553 0.104 pCi/g Bismuth-212 0.487 +/-0.229 0.0981 +/-0.229 0.211 pCi/g Bismuth-214 *0.606 +/-0.0922 0.0315 +4-0.0922 0.0663 pCi/g Cesium- 134 U 0.027 +/-0.0188 0.018 4/-0.0188 0.0382 pCi/g.

Cesium-137 3.50 +/-0.317 0.0156 +/-0.317 0.0332 pCi/g Cobalt-60 0.089 +/-0.0294 0.0116 +/-0.0294 0.0262 pCi/g Europium-152 U -0.0197 +/-0.049 0.042 +/-0.049 0.0877 pCi/g Europium-154 U -0.0211 +/-0.0462 0.038 +/-0.0462 0.0839 pCi/g Europium- 155 U 0.0382 +/-0.0686 0.0412 +/-0.0686 0.0852 pCi/g Lead-212 0.583 +/-0.066 0.0234 +/-0.066 0.0484 pCi/g Lead-214 0.695 .+/-0.107 0.0316 +/-0.107 0.0658 pCi/g Manganese-54 U 0.0169 +/-0.0161 0.015 +/-0.0161 0.0321 pCi/g Niobium-94 U -0.00138 +/-0.0123 0.0107 +/-0.0123 0.0231 pCi/g Potassium-40 9.02 +/-0.922 0.121 +/-0.922 0.271 pCi/g Radium-226 0.606 +/-0.0922 0.0315 +/-0.0922 0.0663 pCi/g Silver-108m U -0.0159 +/-0.0205 0.0168 +/-0.0205 0.035 pCi/g Thallium-208 0.186 +/-0.0436,/ 0.0154 +/-0.0436 0.0325 pCi/g The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI .09/21/06 1749 571423 The following Analytical Methods were performed Method Description 1 EML HASL 300,4.5.2.3 Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported 94

GENERAL ENGINEERING 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: October 5, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-025F Project: YANK01204 Sample ID: 172275028 Client ID: YANK001 Vol. Recv.:

Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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.

95

.1 QUALITY CONTROL DATA 1.

96

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Revort Date: October 5, 2006 Client : Connecticut Yankee Atomic Power Page 1 of 12 362 Injun Hollow Rd East Hampton, Connecticut Contact: Mr. Jack McCarthy Workorder: 172275 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Alpha Spec Batch 572120 QC1201191304 172114001 DUP Americium-241 U 0.0864 U 0.0286 pCi/g 101 (0% - 100%) TCI 09/28/06 11:56 Uncert: +/-0.105 +/-0.0554 TPU: +/-0.106 +/-0.0555 Curium-242 U 0.00 U -0.0072 pCi/g 200 (0%- 100%)

Uncert: +/-0.0553 +/-0.0141 TPU: +/-0.0553 +/-0.0141 Curium-243/244 U 0.0664 U -0.00672 pCi/g 245 (0%- 100%)

Uncert: +/-0.0911 +/-0.0132 TPU: +/-0.0915 +/-0.0132 QC1201191306 LCS Americium-241 11.4 12.6 PCi/g 111 (75%-125%)

Uncert: +/-1.20 TPU: +/-1.96 Curium-242 U 0.0299 Pqi/g Uncert: +/-0.0586 TPU: +1-0.0588 Curium-243/244 13.7 14.4 PCi/g 105 (75%-125%)

Uncert: +/-1.28 TPU: +/-2.18 QC1201191303 MB Amnericium-241 U 0.00455 PCi/g Uncert: +/-0.0226 TPU: +/-0.0227 Curium-242 U 0.00 pCi/g Uncert: +/-0.0581 TPU: +/-0.0581 Curium-243/244 U -0.0704 pCilg Uncert: +/-0.0436 TPU: +/-0.0445 QCI201191305 172114001 MS Americium-241 12.0 U 0.0864 12.9 PCi/g 108 (75%-125%)

Uncert: +1-0.105 +/-1.10 TPU +/-0.106 +/-1.85 Curium-242 U 0.00 U -0.0126 pCi/g Uncert: +/-0.0553 +/-0.0175 TPU +/-0.0553 +/-0.0175 Curium-243/244 14.5 U 0.0664 14.4 pCi/g 99 (75%-125%)

Uncert: +/-0.0911 +/-1.16 TPU +/-0.0915 +/-2.03 Batch 572121 QC1201191308 172114001 DUP Plutonium-238 U 0.102 U 0.0358 pCi/g 96 (0%- 100%) TCI 09/28/06 11:56 97

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 172275 Page 2 of 12 Parmname NOM Sample Qual QC Units RPD% REC% Range Arist Date Time Rad Alpha Spec Batch 572121 Uncert: +/-0.0996 +/-0.0808 TPU: +/-0.100 +/-0.0809 Plutonium-239/240 U 0.062 U -0.0313 pCi/g 608 (0%- 100%)

Uncert: +/-0.077 +/-0.0909 TPU: +/-0.0773 +/-0.091 QC1onum20193108 U 0.0404 pCi/g (75%-125%)

Uncert: +1-0.0758 Plutonium-239/4 TPU: +/-0.0759 10.5 11.2 pCi/g 107 (75%-125%)

Uncert: +/-1.07 TPU: +/-1.73 QC 1201191307 NIB Plutonium-238 U 0.00363 pCi/g 09/28/06 11:56 Uncert: +/-0.114 TPU: +/-0.114 Plutoniurn-239/240 U 0.0618 pCi/g Uncert: +/-0.107 TPU: +/-0.107 QC1201191309 172114001 MS Plutonium-238 U 0.102 U 0.0976 pCi/g (750%-125%) 09/28/06 11:56 Uncert: +/-0.0996 +/-0.102 TPU: +/-0.100 +/-0.103 PILutoniuni-239/240 11.1 U 0.062 11.9 PCi/g 107 (75%-125%)

Uncert: +/-0.077 +/-1.09 TPU: +/-0.0773 +/-1.79 Batch 572122 QC1201191312 172114001 DUP Plutonium-241 U 6.10 U 4.20 pCi/g 0 (0%- 100%) TCI 09/29/06 23:34 Uncert: +/-8.99 +/-8.54 TPU: +/-9.01 +/-8.55 QC120I 191314 LCS Plutonium-241 132 112 pCi/g 85 (75%-125%) 09/30/06 00:06 Uncert: +/-12.9 TPU: +/-17.0 QC1201191311 MB Plutonium-241 U 2.21 pCi/g 09/29/06 23:18 Uncert: +/-8.86 TPU: +/-8.86 QC1201191313 172114001 MS Plutonium-241 144 U 6.10 141 pCi/g 98 (75%-125%) 09/29/06 23:50 Uncert: +/-8.99 *+/-14.2 TPU: +/-9.01 +/-19.8 Rad Gamma Spec Batch 574335 QC1201196537 172275001 DUP Actinium-228 0.917 0.812 pCi/g 12 (0% - 100%) MJH1 10/03/06 15:37 Uncert: +/-0.197 +/-0.158

+/-0.158 98

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 172275 Page 3 of 12 Parnname NOM Sample Oual OC Units RPD% REC% Ranme Anist Date Time Rad Gamma Spec Batch 574335 TPU: +/-0.197 Americium-241 U 0.0336; U -0.0128 pCi/g 445 (0%- 100%)

Uncert: +/-0.0304 +/-0.111 TPU: +/-0.0304 +/-0.111 Bismuth-212 0.332 0.683 pCi/g 69 (0% - 100%)

Uncert: +/-0.297 +/-0.354 TPU: +/-0.297 +/-0.354 Bismuth-214 0.594 0.535 pCi/g 10 (0% - 100%)

Uncert: +/-0.0918 +/-0.115 TPU: +/-0.0918 +/-0.115 Cesium- 134 U 0.0178 UI 0.00 pCig 121 (0% - 100%)

Uncert: +/-0.0337 +/-0.0427 TPU: +/-0.0337 +/-0.0427 Cesium-137 U -0.00791 U 0.00068 pCi/g 238 (0%- 100%)

Uncert: +/-0.0231 +/-0.026 TPU: +/-0.0231 +/-0.026 Cobalt-60 U -0.032 U 0.0131 pCi/g 478 (0%- 100%)

Uncert: +/-0.0272 +/-0.0256 TPU: +/-0.0272 +/-0.0256 Europium- 152 U 0.00865 U -0.0158 pCi/g 685 (0%- 100%)

Uncert: +/-0.0526 +/-0.0636 TPU: +/-0.0526 +/-0.0636 Europium- 154 U -0.00226 U -0.00675 pCi/g 100 (0%- 100%)

Uncert: +/-0.0668 +/-0.0738 TPU: +/-0.0668 +/-0.0738 Europium-155 U 0.0769 U 0.0493 pCi/g 44 (0%- 100%)

Uncert: +/-0.0755 +/-0.0876 TPU: +/-0.0755 +/-0.0876 Lead-212 0.826 0.826 pCi/g 0 (0%-20%)

Uncert: +/-0.0631 +/-0.0726 TPU: +/-0.0631 +/-0.0726 Lead-214 0.596 0.633 pCi/g 6 (0%- 20%)

Uncert: +/-0.0873 +/-0.106 TPU: +/-0.0873 +/-0.106 Manganese-54 U -0.00108 U 0.00343 pCi/g 384 (0%- 100%)

Uncert: +/-0.0247 +/-0.0231 TPU: +/-0.0247 +/-0.0231 Niobium-94 U -0.00289 U 0.00591 pCi/g 584 (0% - 100%)

Uncert: +/-0.021 +/-0.0228 TPU: +/-0.021 +/-0.0228 Potassium-40 12.6 14.3 pCi/g 13 (0% - 20%)

Uncert: +/-0.924 +-/-1.11 TPU: +/-0.924 +/- 1.11 Radium-226 0.594 0.535 pCi/g 10 (0% - 100%)

Uncert: +/-0.0918 +/-0.115 TPU: +1-0.0918 +/-0.115 Silver- 108m U 0.00205 U 0.0158 pCi/g 154 (0% - 100%)

Uncert: +/-0.0182 +/-0.0215 99

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 172275 Page 4 of 12 Parmnaame NOM Sample Qual QC Units RPD% REC% Range Anist Date Time Rad Gamma Spec Batch 574335 TPU: +/-0.0182 +/-0.0215 Thallium-208 0.288 0.314 pCi1g 9 (0% - 100%)

Uncert: +/-0.0486 +/-0.0534 TPU: +/-0.0486 +/-0.0534 LCS Actinium-228 U -0.336 pCi/g 10/03/06 16:53 Uncert: +/-0.735 TPU: +/-0.735 Americiuro-24 1 23.4 24.1 pCi/g 103 (75%-125%)

Uncert: +/-0.538 TPU: +/-0.538 Bismuth-212 U -0.539 pCilg Uncert: +/-1.04 TPU: +/-1.04 Bismuth-214 U 0.040 pCi/g Uncert: +/-0.261 TPU: +/-0.261 Cesium- 134 U 0.0448 pCi/g Uncert: +/-0.159 TPU: +/-0.159 Cesium-137 9.56 10.6 PCi/g 110 (75%-125%)

Uncert: +/-0.503 TPU: +/-0.503 Cobalt-60 14.4 15.0 104 (75%-125%)

Uncert: +/-0.670 pci/g TPU: +/-0.670 Europium- 152 U 0.0391 Uncert: +/-0.272 pCi/g TPU: +/-0.272 Europium-154 *U -0.103 Uncert: +/-0.271 TPU: +/-0.271 Europium- 155 U -0.192 Uncert: +/-0.281 pCilg TPU: +/-0.281 Lead-212 U 0.138 Uncert: +/-0.155 pCi/g TPU: +/-0.155 Lead-214 U -0.0121 Uncert: +/-0.202 pci/g TPU: +/-0.202 Manganese-54 U -0.0546 Uncert: +/-0.141 pCi/g TPU: +1-0.141 Niobium-94 U -0.0363 Uncert: +/-0.124 pci/g TPU: +/-0.124 Potassi um-40 U 0.981 100

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 172275 Page 5 of 12 Parmname NOM Sample Qual QC Units RPD% REC% Range AnIst Date Time Rad Gamma Spec Batch 574335 Uncert: +/-1.13 TPU: +/-1.13 Radium-226 U 0.040 pci/g (75%-125%)

Uncert: +/-0.261 TPU: +/-0.261 Silver-I O8m U -0.0285 pCi/g Uncert: +/-0.111 TPU: +/-0.111 Thallium-208 U -0.016 pci/g Uncert: +/-0.114 TPU: +/-0.114 QC1201196536 MB Actinium-228 U -0.00373 pCi/g 10/03/06 13:39 Uncert: +/-0.0552 TPU: +/-0.0552 Americium-241 U 0.00356 Uncert: +/-0.0133

+/-0.0133 pci/g TPU:

Bismuth-212 U 0.0546 Uncert: +/-0.117 pCi/g TPU: +/-0.117 Bismuth-214 U 0.0344 Uncert: +/-0.0333 pCi/g TPU: +/-0.0333 Cesium-134 U 0.00511 Uncert: +1-0.0185 TPU: +/-0.0185 Cesium- 137 U -0.0066 pCi/g Uncert: +/-0.0168 TPU: +/-0.0168 Cobalt-60 U -0.000135 Uncert: +/-0.0192 pci/g TPU: +/-0.0192 Europium- 152 U 0.0299 Uncert: +1-0.0364 pCi/g TPU: +/-0.0364 Europium- 154 U -0.00197 Uncert: +/-0.0618 pCi/g TPU: +/-0.0618 Europium- 155 U -0.00897 Uncert: +/-0.0242 TPU: +/-0.0242 Lead-212 U 0.0427 Uncert: +/-0.0416

+/-0.0416 pCi/g TPU:

Lead-214 U 0.023 Uncert: +/-0.0276 TPU: +/-0.0276 101

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 172275 Page 6 of 12 Parmname NOM Sample Qual QC Units RPD% REC% Range Anlst Date Time Rad Gamma Spec Batch 574335 Manganese.54 U 0.00276 pCi/g Uncert: +/-0.0147 TPU: +/-0.0147 Niobium-94 U 0.0082 Uncert: +/-0.0143 TPU: +/-0.0143 Potassium-40 U 0.223 pCi/g Uncert: +/-0.193 TPU: +/-0.193 Radium-226 U 0.0344 pCi/g Uncert: -+/-0.0333 TPU: +/-0.0333 Silver- 108m U -0.000323 Uncert: +/-0.0132 pcilg TPU: +/-0.0132 Thallium-208 U 0.00536 Uncert: +/-0.0248 TPU: +/-0.0248 Batch 574336 QC 1201196540 172275028 DUP Actinium-228 0.575 0.630 pCi/g 9 (0% - 100%) MJHI 10/03/06 06:14 Uncert: +/-0.137 +/-0.144 TPU: +/-0.137 +/-0.144 Americium-241 U -0.000377 U -0.000296 pCi/g 24 (0%- 100%)

Uncert +/-0.0553 +/-0.0229 TPU: +/-0.0553 +/-0.0229 Bismuth-212 0.487 0.548 pCi/g 12 (0%- 100%)

Uncert: +/-0.229 +/-0.181 TPU: +/-0.229 +/-0.181 Bismuth-214 0.606 0.535 pCi/g 12 (0%- 100%)

Uncert: +/-0.0922 +/-0.0773 TPU: +/-0.0922 +/-0.0773 Cesium-134 U 0.027 UI 0.00 pCi/g 72 (0%- 100%)

Uncert: +/-0.0188 +/-0.0445 TPU: +/-0.0188 +1-0.0445 Cesium-137 3.50 U 0.0209 pCi/g 198* (0%-20%)

Uncert: +/-0.317 +/-0.0312 TPU: +/-0.317 +/-0.0312 Cobalt-60 0.089 U 0.00347 pCi/g 185 (0%- 100%)

Uncert: +/-0.0294 +/-0.0186 TPU: +/-0.0294 +/-0.0186 Europium-152 U -0.0197 U -0.00689 pCi/g 96 (0%- 100%)

Uncert: +/-0.049 +/-0.0417 TPU: +/-0.049 +/-0.0417 Europium-154 U -0.0211 U 0.081 pCi/g 341 (0%- 100%)

Uncert: +/-0.0462 +/-0.109 TPU: +/-0.0462 +/-0.109 Europium-155 U 0.0382 U 0.0429 pCilg 12 (0%- 100%)

102

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 172275 Page 7 of 12 Parmname NOM Sample Qual QC Units RPD% REC% Range AnIst Date Time Rad Gamma Spec Batch 574336 Uncert: +/-0.0686 +/-0.047 TPU: +/-0.0686 +/-0.047 Lead-212 0.583 0.738 pCi/g 23* (0%-20%)

Uncert: +/-0.066 +/-0.0492 TPU: +/-0.066 +/-0.0492 Lead-214 0.695 0.589 pCi/g 17 (0% - 20%)

Uncert: +/-0.107 +/-0.0747 TPU: +/-0.107 +/-0.0747 Manganese-54 u 0.0169 U 0.0287 pCi/g 52 (0%- 100%)

Uncert: +/-0.0161 +/-0.0174 TPU: +/-0.0161 +/-0.0174 Niobium-94 U -0.00138 U 0.0073 pCi/g 293 (0%- 100%)

Uncert: +/-0.0123 +/-0.0179 TPU: +/-0.0123 +/-0.0179 Potassium-40 9.02 12.2 pCi/g 30* (0%-20%)

Uncert: +/-0.922 +/-0.876 TPU: +/-0.922 +/-0.876 Radium-226 0.606 0.535 pCi/g 12 (0%- 100%)

Uncert: +/-0.0922 +/-0.0773 TPU: +/-0.0922 +/-0.0773 Silver- 108m U -0.0159 U 0.0066 pCi/g 483 (0%-100%)

Uncert: +/-0.0205 +/-0.014 TPU: +/-0.0205 +/-0.014 Thallium-208 0.186 0.254 pCi/g 31 (0%- 100%)

Uncert: +/-0.0436 +/-0.0405 TPU: +/-0.0436 +1-0.0405 QCI201196541 LCS Actinium-228 U -0.000391 PCi/g 10/03/06 07:26 Uncert: +/-0.575 TPU: +/-0.575 Americium-241 23.4 25.5 pCi/g 109 (75%-125%)

Uncert: +/-2.52 TPU: +/-2.52 Bismuth-212 U -0.528 pCi/g Uncert: +/-0.989 TPU: +/-0.989 Bismuth-214 U 0.0129 pCi/g Uncert: +/-0.236 TPU: +/-0.236 Cesium- 134 U -0.0169 Uncert: +/-0.145 TPU: +/-0.145 Cesium- 137 9.56 10.1 106 (75%-125%)

Uncert: +/-0.768 TPU: +/-0.768 Cobalt-60 14.3 14.6 pci/g 102 (75%-125%)

Uncert: +/-1.01 TPU: +/-1.01 103

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 172275 Page 8 of 12 Parmname NOM Samnle Oual OC Units RPPD% REC% Range Anrist Date Time Rad Gamma Spec Batch 574336 Europium- 152 -0.0086.1 Uncert: +/-0.365 pCi/g TPU: +/-0.305 Europium- 154 0.382 Uncert: +/-0.275 Pci/g TPU: +/-0.275 Europium- 155 -0.0392 Uncert: +/-0.332 TPU: +/-0.332 Lead-212 -0.11 pCi/g Uncert: +/-0.163 TPU: +1-0.163 Lead-214 0.185 Pcilg Uncert: +/-0.234 TPU: +/-0.234 Manganese-54 -0.00693 pCilg Uncert: +/-0.128 TPU: +/-0.128 Niobium-94 -0.0972 Uncert: +/-0.118 TPU: +/-0.118 Potassium-40 0.676 Pci/g Uncert: +/- 1.06 TPU: +/-1.06 Radium-226 0.0129 pCi/g (75%- 125%)

Uncert: +/-0.236 TPU: +/-0.236 Silver- 108m -0.0142 Pci/g Uncert: +/-0.119 TPU: +/-0.119 Thallium-208 0.100 Pci/g Uncert: +/-0.123 TPU: +/-0.123 QC1201196539 MB Actinium-228 U 0.0435 Pci/g 10/03/06 06:13 Uncert: +/-0.091 TPU: +/-0.091 Americium-241 U -0.0204 pCi/g Uncert: +/-0.055 TPU: +/-0.055 Bismuth-212 U -0.00499 Pci/g Uncert: +/-0.109 TPU: +/-0.109 Bismuth-214 U 0.0577 Pci/g Uncert: +/-0.031 TPU: +/-0.031 Cesium- 134 U 0.00937 Pci/g Uncert: +/-0.0158 104

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 172275 Page 9of 12 Parmname NOM Sample Qual QC Units RPD% REC% Range Anist Date Time Rad Gamma Spec Batch 574336 TPU: +/-0.0158 Cesium-137 U -0.00291 pCi/g Uncert: +/-0.0137 TPU: +/-0.0137 Cobalt-60 U 0.000491 pCi/g Uncert: +/-0.0155 TPU: +/-0.0155 Europium-152 U -0.00472 pCi/g Uncert: +/-0.0376 TPU: +/-0.0376 Europium- 154 U 0.00671 pCi/g Uncert: +/-0.0299 TPU: +/-0.0299 Europium- 155 U 0.0139 pCi/g Uncert: +/-0.0336 TPU: +/-0.0336 Lead-212 U 0.0167 pCilg Uncert: +/-0.0287 TPU: +/-0.0287 Lead-214 U 0.0536 pCilg Uncert: +/-0.0433 TPU: +/-0.0433 Manganese-54 U -0.00217 pCilg Uncert: +1-0.0116 TPU: +/-0.0116.

Niobium-94 U 0.0106 pCi/g Uncert: +/-0.0136 TPU: +/-0.0136 Potassium-40 U 0.0767 pCi/g Uncert: +/-0.436 TPU: +/-0.436 Radium-226 U 0.0577 pCi/g Uncert: +/-0.031 TPU: +/-0.031 Silver-108m U 0.0117 pCi/g Uncert: +/-0.0122 TPU: +/-0.0122 Thallium-208 U 0.0111 pCi/g Uncert: +/-0.0142 TPU: +/-0.0142 Rad Gas Flow Batch 572301 QC1201191724 172275003 DUP Strontium-90 u -0.00839 U 0.00318 pCi/g 0 (0% - 100%) KSDI 09/28/06 07:35 Uncert: +/-0.0152 +/-0.0168 TPU: +/-0.0152 +/-0.0168 QC1201191726 LCS Strontium-90 1.56 1.44 pCi/g 92 (75%-125%) 09/28/06 07:35 105

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 172275 Page 10of 12 Parmname NOM Sample Qual QC Units RPD% REC% Range AnIst Date Time Rad Gas Flow Batch 572301 Uncert: +/-0.103 TPU: +/-0.113 QC1201191723 MB Strontium-90 U -0.00844 pCi/g 09/28/06 07:34 Uncert: +/-0.0137 TPU: +/-0.0137 QC1201191725 172275003 MS Strontium-90 2.99 U U-0.00839 2.97 pCi/g 99 (75%-125%) 09/28/06 07:35 Uncert: +/-0.0152 +/-0.209 TPU: +/-0.0152 +/-0.220 Rad Liquid Scintillation Batch 571874 QC1201190758 172275008 DUP Iron-55 U 0.774 U -16.1 pCi/g 0 (0% - 100%) VIXPI 09/28/06 18:42 Uncert: +/-38.8 +/-34.9 TPU +/-38.8 +/-34.9 QC1201190760 LCS Iron-55 693 549 pCi/g 79 (75%-125%) 09/28/06 19:14 Uncert: +/-53.2 TPU: +/-65.2 QC1201190757 MB Iron-55 U 0.248 pCi/g 09/28/06 18:26 Uncert: +/-31.9 TPU: +/-31.9 QC1201190759- 172275008 MS Iron-55 712 U 0.774 595 pCi/g 84 (75%-125%) 09/28/06 18:58 Uncert: +1-38.8 +/-55.5 TPU +/-38.8 +/-68.7 Batch 571876 QC1201190768 172275014 DUP Nickel-63 U -3.05 U -6.06 0 (0%- 100%) VIXPI 09/29/06 21:48 Uncert: +/-9.26 +/-6.04 TPU +/-9.26 +/-6.04 pCi/g QC12011 90770 LCS Nickel-63 573 461 80 (75%-125%) 09/29/06 23:21 Uncert: +/-14.5

.TPU: +/-21.3 QCI201196767 MB Nickel-63 U -1.34 pCi/g 09/29/06 21:01 Uncert: +/-6.42 TPU: +/-6.42 QC1201190769 172275014 MS Nickel-63 575 U -3.05 546 pCilg 95 (75%-125%) 09/29/06 22:34 Uncert: +/-9.26 +1-16.4 TPU: +/-9.26 +/-24.7 Batch 571877 QC1201190772 172275003 DUP Technetium-99 U 0.165 U -0.0959 pCi/g 0 (0% -100%) KXR1 10/02/06 13:02 106

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 172275 Page 11 of 12 Parmname NOM Sample Qual .QC Units RPD% REC% Range Anist Date Time Rad Liquid Scintillation Batch 571877 Uncert: +/-0.222 +/-0.189 TPU: +/-0.222 +/-0.189 QC1201190774 LCS Technetium-99 13.1 12.6 pCi/g 96 (75%-125%) 10/02/06 14:05 Uncert: +/-0.360 TPU: +/-0.480 QC1201190771 MB Technetium-99 U -0.0467 pCi/g 10/02/06 12:30 Uncert: +/-0.168 TPU: +/-0.168 QC1201190773 172275003 MS Technetium-99 12.4 U 0.165 11.6 pCilg 94 (75%-125%) 10/02/06 13:33 Uncert: +/-0.222 +/-0.372 TPU: +/-0.222 +/-0.474 Batch 571880 QC1201190784 172275003 DUP Carbon- 14 U -0.0626 U -0.15 pCilg 0 (0% - 100%) kXD2 09/26/06 00:01 Uncert: +/-0.105 +/-0.103 TPU: +/-0.105 -/-0.103 QC1201190786 LCS Carbon- 14 6.47 6.36 pCilg 98 (75%-125%) 09/26/06 02:26 Uncert: +/-0.181 TPU: +1-0.206 QC1201190783 MB Carbon-14 U -0.0559 pCilg 09/25/06 22:48 Uncert: +/-0.0984 TPU: +/-0.0984 QC1201190785 172275003 MS Carbon- 14 6.82 U -0.0626 6.60 pCilg 97 (75%-125%) 09/26/06 01:13 Uncert: +/-0.105 +/-0.190 TPU: +/-0.105 +/-0.216 Batch 571884 QC1201190794 172275003 DUP Tritium 32.4 43.4 pCi/g 29 (0% - 100%) DFA I 09/27/06 19:30 Uncert: +/-8.92 +/-9.76 TPU: +/-8.93 +1-9.79 QC1201190796 LCS Tritium 52.4 47.9 pCi/g 91 (75%-125%) 09/27/06 20:03 Uncert: +/-8.75 TPU: +/-8.79 QC1201190793 MB Tritium U -1.35 pCi/g 09/27/06 19:14 Uncert: +/-5.87 TPU: +/-5.87 QC1201190795 172275003 MS Tritium 52.5 32.4 88.6 pci/g 107 (75%-125%) 09/27/06 19:47 Uncert: +/-8.92 +/-10.7 TPU: +/-8.93 +/-10.8 107

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Workorder: 172275 Page 12 of 12 Parnmame NOM Sample Qua] QC Units RPD% REC% Range Anist Date Timie Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 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.

^ 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.

108

General Narrative 1

General Narrative for Connecticut Yankee Atomic Power Co.

Work Order: 173769 SDG: MSR#06-1282 October 16, 2006 Laboratory Identification:

General Engineering Laboratories, LLC 2040 Savage Road Charleston, South Carolina 29407 (843) 556-8171 Summary Sample receipt The samples arrived at General Engineering Laboratories, LLC, Charleston, South Carolina on September 21, 2006 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 Sample Identification Description 173769001 9807-0000-002F 173769002 9807-0000-003F 173769003 9807-0000-006F 173769004 9807-0000-007F 173769005 9807-0000-008F 173769006 9807-0000-013F 173769007 9807-0000-014F Items of Note Jack McCarthy requested H3 analysis of the samples listed above via email on 10/10/06.

Case Narrative Sample analyses were conducted using methodology as outlined in General Engineering Laboratories (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.

Analytical Request Seven soil samples were analyzed for Tritium.

2

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.

Cheryl Jones Project Manager 3

List of current GEL Certifications as of 16 October 2006 State Certification Alaska UST-062 Arizona AZ0668 Arkansas 88-0651 CLIA 42D0904046 California 01151CA Colorado GenEngLabs Connecticut PH-0169 Dept. of Navy NFESC 413 EPA WG-15J Florida/NELAP E87156 Georgia E87156 (FLINELAP)

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 C 1641 4

Chain of Custody and Supporting Documentation 5

Health Physics Procedure GPP.GGGR-R5104-003-Attachment B-CY-00 I Major Connecticut Yankee Atomic Power Company Chain of Custody Form 2 362 lnjun Hollow Road, East Hampton, CT 06424 860-267-2556 Project Name: Haddam Neck Decommissioning Analyses Requested Lab Use Only Contact Name & Phone: Comments:

Jack McCarthy 960-267-3924

______________________________ Medie Code Sample Type Container Size-Analytical Lab (Name, City, State): Code &Type General Engineering Laboratories Code 2040 Savage Road Charleston, SC 29407 ATT: CherylJones (843-556-8171)

Priority: " 30 D. E 14 D. 1[ 7 D. <

Other: rn Sample Desi ation Date Time - -

  • Comment, Preservation Lab Sample ID Oh 9807-0000-0I F 9146161 q M TS C BP P -

9807-0000-0eO;I. JA,_ TS C BP _

9807-0000-003r.7 TS C BP _"_"_____'"

9807-0000-00 414106 YS3 TS C BP _z 9807-0000-0 D& Q JOST7 TS C BP -

9807-0000-0 oJp F 106- TS C BP -

9807-0000-0Otq *.tA TS C BP , --

9807"0000"0c3% F 1W. :5-. TS C BP 9807-0000-0 o Tf: IC CTS BP _"

9807-0000-0.oo

o. *j1 A T" TS C - -BP t 9807-0000-0 t ý.IFlj 10 2 -1. TS C BP - - -

NOTES: PO #: 002332 MSR #: ;7.t

=-/0 Z LTP QA 0 Radwaste QA E Non QA Samples Shipped Via: Internal Container

[ Fed Ex Temp.: / Deg. C Tups EHand Custody Seals?

1) Relinquihed . Date/Time 2Nceiv By^ . DteiTime Custody Seal Intact?
3) Relinquished by Date/Fime 4 Receive~d BP Date/Time Billof _________ Y]

Y NE Bi5 of LadRiug B

5) Relinquished By Date/Time 6) Received By Date/Time

Healtý Physics Procedure GPP-GGGR-R5104-003-Attachment B-CY-00 1 Major Connecticut Yankee Atomic Power Company Chain of Custody Form No. 2006-569 362 Injun Hollow Road, East Hampton, CT 06424 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): Codae &Type General Engineering Laboratories Code 2040 Savage Road Charleston, SC 29407 ATM: Cheryl Jones (843-556-8171)

Priority: [130 D.Z 14 D. [17 D.

Other: ri c "

Sample Designation Date Time r F - Comment, Preservation Lab Sample ID 9807-0000-0 *, F=. o CBP___...___ ,:e G*(, _____TS 9807-0000-0 L~ .% q-1L4-(.p G*d** TS C BP ~, __ _______ @'oDn_______

9807-0000-0 { *.iL4.oto TS C BP o 9807-0000-0 OLFs l'toL , TS C BP goo 9807-0000-0 j *.f'.o . TS C BP 9807-0000-0 14 IC 110- IOU ockibe' TS C BP )0 9807-0000-0 1**j -cA D4 v- TS C BP 98700-%JF6-c4 TS C HP - - ________ _____

9807-0000-0 ,% ., TS C BP _

9807-0000-0 -*r* t T**

'S, C BP ,

9807-0000-0 xGW - ." TS C BP .

9807-0000-0-cre' v 9 tebeQ TS C HP --

NOTES: PO #: 002332 MSR #: 04- 1t g-" LTP QA U Radwaste QA U Non QA Samples Shipped Via: Internal Container

[ Fed Ex Temp.: _ Deg. C El uPS El Hand Custody Sealep YE NZ

1) Relinquished

_)_R By

__in______dByD__e/T Date/Tne __ 22) eee at/Time z)/O~ 9c l EqOther

[ OtherCustody SetC Intact?

3) Relinquished By Date/Time 4) ý,eceived 5y Date/Time Y CY N 0 Bill of Lading 9 5)Relinquished By Date/Time 6) Received By Date/Time

Heallb Physics Procedure GPP-GGGR-R.5104-003-Attachment B-CY-001 Major Connecticut Yankee Atomic Power Company Chain of Custody Form N.20-7 No. 2o06-57o 362 Injun Hollow Road, East Hampton, CT 06424 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 330 D. Z 14 D.E 7 D.

Other; W__CO)_

Sample Designation Date Time Comment, Preservation. Lab Sample ID 9807-0000-0?.' 1 q. rd -0 -*'" TS C BP 9807.000.-.mVFt *- 7 ,-- ,-. I,..Z7 w q4.o. TS -.- eCD --- -RP.- - _

-

_ _ _ _ __,

9807-0000-0 7,; ; . _4LlýL D. -. TS C BP ..

9807-0000-0"7*F TS C BP -

9807-0000-0 -,.3q* " li,-50 TS C BP 106JLP1 5E -TS C1 KP_ __ _

NOTES: PO 4: 002332 MSR #: a£6 Ii'". I LTP QA E Radwaste QA [ Non QA Samples Shipped Via: Internal Container ED Fed Ex Temp.: ' Deg. C El Hand Custody Sealed 1)Relinquished By Date/Time 2) 1ve y )atefime Custody SeaY ntact?

(?6 Other

3) Relinquished By Date/Time 4) Received DaterTime YD] N 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-OO1 Figure 1. Sample Check-in List.

Date/Tim* Received:-..... . .. ,Q.

SDG#:

'Work Order Number. _- _____.______________._.-_._____ .

7 Shipping Cdatainer Chain of Custody # -9 j6to- JLGf7C

1. Custody Seats.o0shipping container intact?", Yes 1 ] No AI 414-
2. Custody Seals dated and signed? . Yes,[ No [ 1 44

.3. Chain-of-Custody recor d pret Ye )I

4. Coolert Imperatur
5. Vermiculite/packing materials is: Wet ( I Dry j',' I /vP
6. Number of samples in shipping conmtainr: "'"
7. Sample holding times exceeded?  : . Y* I]NO f
8. Samples havei Jiazard labels l*ap

__.custody seals -Z2approp-iate sample labels

9. Samples arei

.~J .god condition -leaking

-broken .- have air bubbles

10. Were any anomalie.s identified in sarmple receipt? Yes [ ] No,?

i 1. escripon of anomalies, (ilude staple numbers):

Sample Custodian(Laboratory 4 - .<L Date,

  • Telepho.:ed to, On ,By 9

Prep for additional analysis (and reanalysis)

Subject:

Prep for additional analysis (and reanalysis)

From: "John McCarthy" <McCarthy@CYAPCO.com>

Date: Tue, 10 Oct 2006 13:47:15 -0400 To: "Cheryl Jones" <cj@gel.com>

CC: "Clyde Newson" <Newson@CYAPCO.com>

Cheryl, Would prep and analyses the following samples under MSR 0601282 for H-3:

9807-0000-002F 9807-0000-003F (REANALYSIS) 9807-0000-006F 9807-0000-007F 9807-0000-008F (REANALYSIS) 9807-0000-013F (REANALYSIS).

9807-0000-014F TAT IS REQUESTED AT 7 DAYS. RDL IS REQUESTED AT 3 PCI/G (3.OOE+00 PCI/G)

Thank you

.Jack 10 I of I 10/ 17/2006 2:5 0 PM

Data Review Qualifier Definitions 11

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

" Metals-%difference of sample and SD is >10%. Sample concentration must meet flagging criteria B Analytical holding time was exceeded h Preparation or preservation holding time was exceeded J Value is estimated N 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.

GENERAL ENGINEERING LABOPATORIES, LLC a Member of THE GEL GROUP, INC.

P.O. BOX 30712 Charleston, SC 29417 - 2040 Savage Road (29407)

Phone (B43) 556-8171 -FeI23) 766-1178 www.gel.com

RADIOLOGICAL ANALYSIS 13

Radiochemistry Case Narrative Connecticut Yankee Atomic Power Co. (YANK)

Work Order 173769 Method/Analysis Information Product: LSC, Tritium Dist, Solid - 3 pCi/g Aiialytical Method: EPA 906.0 Modified Analytical Batch Number: 578364 Sample ID Client ID 173769001 9807-0000-002F 173769002 9807-0000-003F 173769003 9807-0000-006F 173769004 9807-0000-007F 173769005 9807-0000-008F 173769006 9807-0000-013F 173769007 9807-0000-014F 1201205181 Method Blank (MB) 1201205182 173770001(9106-0001-1 12F) Sample Duplicate (DUP) 1201205183 173770001(9106-0001-112F) Matrix Spike (MS) 1201205184 Laboratory Control Sample (LCS)

SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by General Engineering 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.

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.

14

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: 173770001 (9106-0001-112F).

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 The container ids were verified for samples 173769002 (9807-0000-003F) and 173769005 (9807-0000-008F).

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:

15

Reviewer/Date:

16

SAMPLE DATA

SUMMARY

17

GENERAL ENGINEERING 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#06-1282 GEL Work Order: 173769 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.

ND The analyte concentration is not detected above the detection limit.

The above sample is reported on an "as received" basis.

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 General Engineering Laboratories, LLC standard operating procedures. Please direct any questions to your Project Manager, Cheryl Jones.

Reviewed by 18

GENERAL ENGINEERING 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: October 18, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-002F Proiect: YANK01204 Sample ID: 173769001 ClientID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 13-SEP-06 Receive Date: 21-SEP-06 Collector: Client Parameter Qualifier

  • Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist. Solid - 3 pCi/g Tritium U 0.231 +/-1.43 1.19 +/-1.43 2.55 pCi/g DFAI 10/14/062310 578364 1 The following Analytical Methods were performed Method Description I EPA 906.0 Modified Notes:

The Qualifiers in this report are defined as follows

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 +l-Rb. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on an "as received" basis.

19

GENERAL ENGINEERING 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: October 18, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-003F Project: YANK0 1204 Sample ID: 173769002 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 13-SEP-06 Receive Date: 21-SEP-06 Collector: Client Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid - 3 pCi/g Tritium U 0.154 +1-1.28 1.07 +/-1.28 2.29 pCi/g DFAJ 10/14/062326 578364 1 The following Analytical Methods were perfonned Method Description I EPA 906.0 Modified Notes:

The Qualifiers in this report are defined as follows:

A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported

> Result is greater than value reported A The TIC is a suspected aldol-condensation product 13 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 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 an "as received" basis.

20

GENERAL ENGINEERING 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: October 18, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-006F Project: YANK01204 Sample ID: 173769003 Client ID: YANK00I Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis ISC, Tritium Dist,Solid - 3 pCi/g Tritium U 0.0691 +/-1.64 1.37 +/-1.64 2.94 pCi/g DFAl 10/14/06 2343 578364 1 The following Analytical Methods wereperformed Method Description I EPA 906.0 Modified Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 GCUMS 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 R Sample results are rejected U Analyte was analyzed for, but not detected above the MIL, 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 an "as received" basis.

21

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power

" " Address

.  : 362 In jun Hollow Rd.........

East Hampton, Connecticut 06424 Report Date: October 18, 2006 Contact: Mr. Jack McCarthy Project:. Soils PO# 002332 Client Sample ID: 9807-0000-007F Project: YANK01204 Sample ID: 173769004 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21 -SEP-06 Collector: Client Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid - 3 pCi/g Tritium U 0.00 +/-1.24 1.04 +/-1.24 2.23 pCi/g DFAI 10/14/06 2359 578364 1 The following Analytical Methods were performed Method Description EPA 906.0 Modified Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 an "as received" basis.

22

GENERAL ENGINEERING 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: October 18, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-008F Proeect: YANKO1204 Sample ID: 173769005 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid - 3 pCifg Tritium U 0.575 +/-1.33 1.08 +/-1.33 2.31 pCilg DFAI 10/15/06 0015 578364 1 The following Analytical Methods were performed Method Description EPA 906.0 Modified Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 an "as received" basis.

23

GENERAL ENGINEERING 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: October 18, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-013F Project: YANK01204 Sample ID: 173769006 Client ID: YANK001 Matrix: TS Vol. Recv.:

Collect Date: 14-SEP-06 Receive Date: 21-SEP-06 Collector: Client Parameter Qualifier Result Uncertainty LC TPU MDA 'Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid - 3 pCi/g

  • Tritium U -0.875 +/-1.21 1.07 +/-1.21 2.30 pCi/g DFAI 10/15/06 0032 578364 1 The following Analytical Methods were performed Method Description EPA 906.0 Modified Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 b'y 4X or more 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 an "as received" basis.

24

GENERAL ENGINEERING 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: October 18, 2006 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9807-0000-014F Proiect: YANK01204 SamplelD: 173769007 Client ID: YANK001 Matrix: . TS Vol. Recv.:

Collect Date: 18-SEP-06 Receive Date: 21-SEP-06 Collector: Client Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Mtd Rad Liquid Scintillation Analysis LSC, Tritium Disi, Solid - 3 pCi/g Tritium U -1.34 +/-1.28 1.16 +/-1.28 2.49 pCi/g DFA1 10115/06 0048 578364 1 The following Analytical Methods were performed Method Description EPA 906.0 Modified Notes:

The Qualifiers in this report are defined as follows:

  • A quality control analyte recovery is outside of specified acceptance criteria

< Result is less than value reported

> Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 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 an "as received" basis.

25

QUALITY CONTROL DATA 26

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.gel.com QC Summary Reuort Date: October 18, 2006 Client: Connecticut Yankee Atomic Power Page 1 of 2 362 Injun Hollow Rd East Hampton, Connecticut Contact: Mr. Jack McCarthy Workorder: 173769 Parmnname NOM Sample Qual QC Units RPD% REC% Range AnIst Date Time Rad Liquid Scintillation Batch 578364 QC1201205182 173770001 DUP Tritium U 1.60 U -1.29 pCilg 0 (0% - 100%) DFA I 10/15/06 02:10 Uncert: +/-5.76 +/-6.37 TPU: +/-5.76 +/-6.37 QC1201205184 LCS Tritium 10.4 9.95 pCi/g 96 (75%-125%) 10/15/06 02:42 Uncert: +/-1.86 TPU: +/-1.86 QC1201205181 MB Tritium U -0.187 pCilg 10/15/06 01:53 Uncert: +1-1.17 TPU: +/-1.17 QC1201205183 173770001 MS Tritium 57.8 U 1.60 48.5 pCi/g 84 (75%-125%) 10/15/06 02:26 Uncert: +/-5.76 +/-9.94 TPU: +1-5.76 +/-9.97 Notes:

The Qualifiers in this report are defined as follows:

A quality control analyte recovery is outside of specified acceptance criteria Result is less than value reported Result is greater than value reported A The TIC is a suspected aldol-condensation product B 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 GCIMS 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 R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.

U' 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 RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL hi Preparation or preservation holding time was exceeded '

27

GENERAL ENGINEERING LABORATORIES, LLC 2040 Savage Road Charleston SC 29407 - (843) 556-8171 - www.geLcom QC Summary Workorder: 173769 Page 2 of 2 Parmname NOM Sample Qual QC Units RPD% REC% Range AnIst Date Time

'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.

^ 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.

Wheore 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.

28

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3 (DQA RESULTS)

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3A (PRELIMINARY DATA REVIEW)

PRELIMINARY DATA REVIEW FORM Survey Unit: 9807-0000 Survey Unit Name: Subsurface Area Associated with the Southwest Site Storage area Classification : B Survey Media: Soil Type of Survey: Final Status Survey Type of Measurement: Radionuclide Specific lumber of Measurements : 25 BASIC STATISTICAL QUANTITIES Cs-137 Target Level (pCi/g) 5.3 8E+00 Minimum Value: -2.76E-02 Maximum Value: 3.50E+00 Mean : 1.49E-01 Median : 8.18E-03 Standard Deviation: 6.98E-01 Reported Results Cs-137 Concentration Fraction of Sample Identification (pCi/g) Detect? Target Level 9807-0000-001 F -7.91E-03 -0.001 9807-0000-002F -2.76E-02 -0.005 9807-0000-003F 4.02E-02 0.007 9807-0000-004F - 1.26E-03 0.000 9807-0000-005F 1.87E-02 0.003 9807-0000-006F -8.34E-03 -0.002 9807-0000-007F - 1.54E-02 -0.003 9807-0000-008F -1.36E-02 -0.003 9807-0000-009F 3.30E-02 0.006 9807-0000-01OF 2.86E-02 0.005 9807-0000-01 IF -2.32E-02 -0.004 9807-0000-012F 4.36E-02 0.008 9807-0000-013F -2.5 1E-03 0.000 9807-0000-014F 8.18E-03 0.002 9807-0000-015F 1.29E-02 0.002 9807-0000-016F 6.01E-03 0.001 9807-0000-017F 3.34E-02 0.006 9807-0000-018F 2.39E-03 0.000 9807-0000-019F -3.24E-04 0.000 9807-0000-020F 3.53E-02 0.007 Submitted by/Date 1 of o 1

PRELIMINARY DATA REVIEW FORM Reported Results Cs-137 Concentration Fraction of Sample Identification (pCi/g) Detect? Target Level 9807-0000-021F 0.00E+00 0.000 9807-0000-022F 2.88E-02 + 0.005 9807-0000-023F 2.56E-02 + 0.005 9807-0000-024F 1.18E-02 0.002 9807-0000M025F 3.50E+00 + 0.651 Submitted by/Da2o 2 ofl1

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3B (GRAPHICAL REPRESENTATION OF DATA)

FREQUENCY PLOT FOR CESIUM-137 Survey Unit: 9807-0000 Subsurface.Area Associated with the Survey Unit Name: Southwest Site Storage Area Mean: 1.49E-01 pCi/g Frequency Plot For Cs-137 25 20

= 15 Er 10 U-5 0

-2.76E-02 8.47E-01 1.72E+00 2.60E+00 3.47E+00 4.35E+00 Upper End Value (pCilg)

Upper End Observation Observation Value Frequency Frequency

-2.76E-02 1 4%

8.47E-01 23 92%

1.72E+00 0 0%

2.60E+00 0 0%

3.47E+00 0 0%

4.35E+00 1 4%

Total: 25 100%

Submitted by/Da/e

/I1J21 job RevittJdbIDyIte 1o 1 of 1

QUANTILE PLOT FOR CESIUM-137 Survey Unit: 9807-0000 Subsurface Area Associated with the Survey Unit Name: Southwest Site Storage Area Mean: 1.49E-01 pCi/g Quantile Plot For Cs-1 37 3.47E+00 2.97E+00

0) 2.47E+00 1.97E+00 0.

1.47E+00 9.70E-01 C-) 4.70E-01

-3.OOE-02 0 10 20 30 40 50 60 70 80 90 100 Percentage Cs-137 Rank Percentage

-2.76E-02 1 3%

-2.32E-02 2 10%

-1.54E-02 3 17%

-1.36E-02 4 23%

-8.34E-03 5 30%

-7.91 E-03 6 37%

-2.51 E-03 7 43%

-1.26E-03 8 50%

-3.24E-04 9 57%

0.00E+00 10 63%

2.39E-03 11 70%

6.01E-03 12 77%

8.18E-03 13 83%

1.18E-02 14 90%

1.29E-02 15 97%

1.87E-02 16 97%

2.56E-02 17 97%

2.86E-02 18 97%

2.88E-02 19 97%

3.30E-02 20 97%

3.34E-02 21 97%

3.53E-02 22 97%

4.02E-02 23 97%

4.36E-02 24 97%

3.50E+00 25 97%

i -t /

Submitted by/Datv iiIziIoe;o Revi~<~d by/)~ate

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3C (SIGN TEST)

Connecticut Yankee Decommissioning Project GPP-GGGR-R5121-001 Attachment A, Health Physics Procedure Rev CY-001 MAJOR Sign Test Calculation Sheet For A Single Radionuclide or Gross Activity Measurements Survey Area Number: 9807 Survey Unit Number: 0000 Survey Area Name: Subsurface Area associated with the Southwest Site Storage Area WPIR#: 2006-0038 Classification: B Type I (cx error): 0.05 (N): 25 Radionuclide: Cs-137 DCGL: 5.38 Results (pCi/g) DCGL - Results Sign

-7.9 1E-03 5.39E+00

-2.76E-02 5.41E+00 1 4.02E-02 5.34E+00 I

-1.26E-03 5.38E+O0 1 1.87E-02 5.36E+00

-8.34E-03 5.39E+00

-1.54E-02 5.40E+00

-1 .36E-02 5.39E+00 1 3.30E-02 5.35E+00 2.86E-02 5.35E+00 I

-2.32E-02 5.40E+00 1 4.36E-02 5.34E+00 1

-2.51E-03 5.38E+00 8.18E-03 5.37E+00 1.29E-02 5.37E+00 1 6.01E-03 5.37E+00 1 3.34E-02 5.35E+00 2.39E-03 5.38E+00 1

-3.24E-04 5.38E+00 1 3.53E-02 5.34E+00 Page 1 of I

Connecticut Yankee Decommissioning Project GPP-GGGR-R5121-001 Attachment A, Health Physics Procedure Rev CY-001 MAJOR Survey Area Number: 9807 Survey Unit Number: 0000 Survey Area Name: Subsurface Area associated with the Southwest Site Storage Area WPIR#: 2006-0038 Classification: B Type I (cc error): 0.05 (N): 25 Radionuclide: Cs-137 DCGL: 5.38 Results (pCi/g) DCGL - Results Sign 0.OOE+00 5.38E+00 1 2.88E-02 5.35E+00 1 2.56E-02 5.35E+00 1 1.18E-02 5.37E+00 1 3.50E+00 1.88E+00 1 Number of positive differences (S+): 25 Critical Value: 17 Survey Unit Meets Acceptance Criterion Performed by: - Date: /A!/o 6

\

Independent Review Date: ii/z, ao0.

Page 1 of 1

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3D (QC SPLIT RESULTS)

Health Phvsics Procedure 24265-000-GPP-GGGR-R5]24-000-Rev.CY-000 Attachment A HelhPAisPoeue-46-0-P-GRR 4O0-e.Y00Atcmn Split Sample Assessment Form Survey Area#: 9807 Survey.Unit #: 0000 Survey Unit name: Subsurface Area Associated with the Southwest Site Storage Area Sample Plan or WPIR#: 2005-0038 IvSML#: 9807-0000-012 Sample

Description:

ComparisonDof split samples collected from sample measurement Plocation#12 and analyzed using gamma spectroscopy by off-site Vendor Laboratory. The standard sample was 9807-0000-0012F, the comparison sample was 9807-0000-012F5.

STANDARD COMPARISON Radionuclide Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (YIN)

K-40 13.9 5.65E-1 25 0.75 -1.33 13.7 5.70E-1 0.99 Y Comments/Corrective Actions: Not enough Cs-137 to Table is provided to show acceptance criteria yield an acceptable Resolution used to assess split samples.

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

>200 0.85- 1.18 ormed By:

/

(

2 Page 1 of 1

Health Physics Procedure 24265-000-GPP-GGGR-R5124-000-Rev.CY-000 Attachment A Health Physics Procedure 24265-000-GPP-GGGR-R5 124-000-Rev.CY-000 Attachment A Split Sample Assessment Form Survey Area#: 980.7 Survey Unit #: 0000 Survey Unit name: Subsurface Area Associated with the Southwest Site Storage Area Sample Plan or WPIR#: 2005-0038 SML#: 9807-0000-018 Sample

Description:

Comparison of split samples collected from sample measurement-location #18 and analyzed using gamma spectroscopy by off-site Vendor Laboratory. The standard sample was 9807-0000-018F, the comparison sample was 9807-0000-01FS.

STANDARD COMPARISON Radionuclide Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (YIN)

K-40 13.2 5.55E-1 24 0.75- 1.33 13.3 6.05E-1 1.00 Y Comments/Corrective Actions: Not enough Cs-137 to Table is provided to show acceptance criteria yield an acceptable Resolution used to assess split samples.

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

>200 0.85- 1.18 C_/--Ie'6 ,¢'---

I Page 1 of I

Health Physics Procedure 24265-000-GPP-GGGR-R5124-000-Rev.CY-000 Attachment A Health Physics Procedure 24265-000-GPP-GGGR-R5 124-000-Rev.CY-000 Attachment A Split Sample Assessment Form Survey Area#: 9807 Survey Unit #: 0000 Survey Unit name: Subsurface Area Associated with the Southwest Site Storage Area Sample Plan or WPIIR#: 2005-0038 SML#: 9807-0000-024 Sample

Description:

Comparison of split samples collected from sample measurement location #24 and analyzed using gamma spectroscopy by off-site Vendor Laboratory. The standard sample was 9807-0000-024F, the comparison sample was 9807-0000-024FS.

STANDARD COMPARISON Radionuclide Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (Y/N)

K-40 12.1 5.40E-1 22 0.75-1.33 13.6 4.68E-1 1.12 Y t I I F +/- F F F 4 + F + 4 F

+ F 4 + F 4- 4 F Comments/Corrective Actions: Not enough Cs-137 to Table is provided to show acceptance criteria yield an acceptable Resolution used to assess split samples.

R1solution Agreement Range 4-7 0.5 -2.0 8-15 0.6 - 1.66 16-50 0.75 - 1.33 51 -200 0.80 - 1.25

>200 0.85- 1.18

/

Page 1 of I

SUBSURFACE AREA ASSOCIATED WITH THE SOUTHWEST SITE STORAGE AREA SURVEY UNIT 9807-0000 RELEASE RECORD ATTACHMENT 3E (COMPASS DQA WITH POWER CURVE)

~DQA Surface Soil Report A s.s.e_ _s.s.me nt.s u.m ma ry . ...... ....................................

_......... ....... ............................................

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

Site: 9807-0000 FSS Planner(s): McCarthy Survey Unit Name: Subsurface Area Associated with the Southwest Site Report Number: 1 Survey Unit Samples: 25 Reference Area Samples: 0 Test Performed: Sign Test Result: Not Performed Judgmental Samples: 0 EMC Result: Not Performed Assessment

Conclusion:

Reject Null Hypothesis (Survey Unit PASSES)

Retrospective Power Curve 1

0.9

= 0.8 0.7 0.6 0.5 0.4 t--

0.3 I- 0.2 0,1 0

0 2 3 4 5 6 Soil Concentration (pCi/g), including background Prospective Power M 1-beta .... Actual Power LBGR. Estimated Power DCGL -- - ,Retrospecti.,ePower COMPASS vl.0.0 11t/20/2006 Page I

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