ML071730442: Difference between revisions
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| number = ML071730442 | | number = ML071730442 | ||
| issue date = 03/07/2007 | | issue date = 03/07/2007 | ||
| title = Final Status Survey (FSS) Final Report - Phase | | title = Final Status Survey (FSS) Final Report - Phase VII - Chapter 7 of 19 - CYAPCO Final Status Survey Release Record Former Radiologically Controlled Area North of the Primary Auxillary Building and Tank Farm, Survey Unit 9312-0004 | ||
| author name = Wojtkowiak D | | author name = Wojtkowiak D | ||
| author affiliation = Connecticut Yankee Atomic Power Co | | author affiliation = Connecticut Yankee Atomic Power Co | ||
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No. above grade structures currently reside within Survey Unit 9312-0004. | No. above grade structures currently reside within Survey Unit 9312-0004. | ||
In Survey Area 9312, post-remediation soil samples were taken from the as-left surface soils under two (2) Survey and Sampling Work Plans, SSWP-06-08-000 and SSWP 12-001. Thirty-five (35) post remediation surface soil samples were collected from the various locations within Survey Area 9312. All samples were collected and analyzed by gamma spectroscopy by an approved off-site laboratory. | In Survey Area 9312, post-remediation soil samples were taken from the as-left surface soils under two (2) Survey and Sampling Work Plans, SSWP-06-08-000 and SSWP 12-001. Thirty-five (35) post remediation surface soil samples were collected from the various locations within Survey Area 9312. All samples were collected and analyzed by gamma spectroscopy by an approved off-site laboratory. | ||
Ten (10) of the thirty-five (35) post remediation samples collected were analyzed for the full suite of "Hard-to-Detect" (HTD) radionuclides specified in the LTP, Table 2-12, "Radionuclides Potentially Present at Haddam Neck Plant" and as provided in Table 3. Statistical quantities (mean, median and standard deviation) from the 2006 post-remediation survey conducted under SSWP-06-08-000 and SSWP-06-12-001 are provided in Table 1.Minimum Value: 1 .32E-02-5 .OOE-02 Maximum Value: 1 .70E+/-00 1 .43E+/-00 Mean: 2.38E-01 1.08E-01 Median: 1.65E-01 1.46E-02 Standard Deviation: | Ten (10) of the thirty-five (35) post remediation samples collected were analyzed for the full suite of "Hard-to-Detect" (HTD) radionuclides specified in the LTP, Table 2-12, "Radionuclides Potentially Present at Haddam Neck Plant" and as provided in Table 3. Statistical quantities (mean, median and standard deviation) from the 2006 post-remediation survey conducted under SSWP-06-08-000 and SSWP-06-12-001 are provided in Table 1.Minimum Value: 1 .32E-02-5 .OOE-02 Maximum Value: 1 .70E+/-00 1 .43E+/-00 Mean: 2.38E-01 1.08E-01 Median: 1.65E-01 1.46E-02 Standard Deviation: | ||
: 3. 1OE-0lI 2.76E-01 A review of this sample data shows Cs-137 and Co-60 to be the primary radionuclides of concern, with both isotopes reported at fairly low concentrations. | : 3. 1OE-0lI 2.76E-01 A review of this sample data shows Cs-137 and Co-60 to be the primary radionuclides of concern, with both isotopes reported at fairly low concentrations. | ||
The sample population as a whole was evaluated to assess the distribution of the detected radionuclides. | The sample population as a whole was evaluated to assess the distribution of the detected radionuclides. | ||
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Equation I shows the mathematical relationship between the three (3) components and the total dose.Equation 1 HTotal =Hs 0 oi +HExistingGw | Equation I shows the mathematical relationship between the three (3) components and the total dose.Equation 1 HTotal =Hs 0 oi +HExistingGw | ||
+HFuitureGW The total dose under the LTP criteria is twenty-five (25) mremlyr Total Effective Dose Equivalent (TEDE) from all three (3) components. | +HFuitureGW The total dose under the LTP criteria is twenty-five (25) mremlyr Total Effective Dose Equivalent (TEDE) from all three (3) components. | ||
The allowable total dose under the Connecticut Department of Environmental Protection (CTDEP)radiological remediation standard for CY is nineteen (19) mremlyr 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) mremlyr TEDE.This survey unit is considered impacted by future groundwater radioactive contamination, as there are underground foundations containing residual radioactive material within the groundwater saturated zone in the area (reference CY memo ISC 06-024). The dose contribution from future groundwater, the third dose component, is bounded by two (2) mremlyr TEDE.Revision 08 8 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD Equation 2 19 mremlyrrotal, = 15 mrem/yrs 0 ,il +/- 2 mremi/yrExisting Gw+/- 2 mremn/yrFutUrCGW The allowable dose for soil *in this survey unit is fifteen (15) mrem/yr TEDE as shown by Equation 2 above. The concentration of residual radioactivity resulting in fifteen (15) mrem/yr TEDE is designated as the Operational DCGL (DCGLOp), and has been es tablished for the radionuclides of concern as provided in Table 3.Revision 09 9 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD H-3 4.12E+02 2 .47E+02 1.65E+/-01 C-14 5.66E+00 3.40E+00 2.26E-01 Mn-54 1.74E+01 1.04E+/-01 6.96E-01I Fe-55 2.74E+04 1.64E+04 1. 1OE+03 Co-60 3.8 1 E+00 2.29E+/-00 1 .52E-0 1 Ni-63 7.23E+02 4.34E+02 2.89E+0 1 Sr-90 1.55E+00 9.30E-01 6.20E-02 Nb-94 7.12E+00 4.27E+00 2.85E-01 Tc-99 1.26E+01 7.56E+00 5.04E-01 Ag-lO8m 7.14E+00 4.28E+00 2.86E-01 Cs-134 4.67E+00 2.80E+/-00 1.87E-01 Cs-I 37 7.9 1E+00 4.75E+00 3.16E-01I Eu-152 1.O1E+01 6.06E+00 4.04E-01 Eu- 154 9.29E+00 5.57E+00 3.72E-0OI Eu-155 3.92E+02 2.35E+02 1.57E+01 Pu-238 2.96E+O1 Il.78E+01 | The allowable total dose under the Connecticut Department of Environmental Protection (CTDEP)radiological remediation standard for CY is nineteen (19) mremlyr 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) mremlyr TEDE.This survey unit is considered impacted by future groundwater radioactive contamination, as there are underground foundations containing residual radioactive material within the groundwater saturated zone in the area (reference CY memo ISC 06-024). The dose contribution from future groundwater, the third dose component, is bounded by two (2) mremlyr TEDE.Revision 08 8 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD Equation 2 19 mremlyrrotal, = 15 mrem/yrs 0 ,il +/- 2 mremi/yrExisting Gw+/- 2 mremn/yrFutUrCGW The allowable dose for soil *in this survey unit is fifteen (15) mrem/yr TEDE as shown by Equation 2 above. The concentration of residual radioactivity resulting in fifteen (15) mrem/yr TEDE is designated as the Operational DCGL (DCGLOp), and has been es tablished for the radionuclides of concern as provided in Table 3.Revision 09 9 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD H-3 4.12E+02 2 .47E+02 1.65E+/-01 C-14 5.66E+00 3.40E+00 2.26E-01 Mn-54 1.74E+01 1.04E+/-01 6.96E-01I Fe-55 2.74E+04 1.64E+04 1. 1OE+03 Co-60 3.8 1 E+00 2.29E+/-00 1 .52E-0 1 Ni-63 7.23E+02 4.34E+02 2.89E+0 1 Sr-90 1.55E+00 9.30E-01 6.20E-02 Nb-94 7.12E+00 4.27E+00 2.85E-01 Tc-99 1.26E+01 7.56E+00 5.04E-01 Ag-lO8m 7.14E+00 4.28E+00 2.86E-01 Cs-134 4.67E+00 2.80E+/-00 1.87E-01 Cs-I 37 7.9 1E+00 4.75E+00 3.16E-01I Eu-152 1.O1E+01 6.06E+00 4.04E-01 Eu- 154 9.29E+00 5.57E+00 3.72E-0OI Eu-155 3.92E+02 2.35E+02 1.57E+01 Pu-238 2.96E+O1 Il.78E+01 | ||
: 1. 18E+00 Pu-239/240 2.67E+01I 1.60E+01 1.07E+00 Am-241 5)2.58E+01 1.55E+01 1.03E+00 Pu-241 8.70E+02 5.22E+02 3.48E+0lI Cm-243/244 2.90E+0 1 1 .74E+0 1 1. 1 6E+00 (1)(2)(3)(4)(5)Bold indicates those radionucidies considered Hard to Detect (HTD)The Base Case Soil DCGL(s) are specified by the LTP in Chapter 6 and are equivalent to twenty-five (25) mremlyr TEDE The Operational DCGL is equivalent to achieving fifteen (15) mremlyr TEDE The required MDC is equivalent to achieving one (1) mrem/yr TEDE 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 performned Revision 0 1 10 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 9312-0004 RELEASE RECORD Another important facet of the DQO process is to identify the radionuclides of concern and determine the concentration variability. | : 1. 18E+00 Pu-239/240 2.67E+01I 1.60E+01 1.07E+00 Am-241 5)2.58E+01 1.55E+01 1.03E+00 Pu-241 8.70E+02 5.22E+02 3.48E+0lI Cm-243/244 2.90E+0 1 1 .74E+0 1 1. 1 6E+00 (1)(2)(3)(4)(5)Bold indicates those radionucidies considered Hard to Detect (HTD)The Base Case Soil DCGL(s) are specified by the LTP in Chapter 6 and are equivalent to twenty-five (25) mremlyr TEDE The Operational DCGL is equivalent to achieving fifteen (15) mremlyr TEDE The required MDC is equivalent to achieving one (1) mrem/yr TEDE 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 performned Revision 0 1 10 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 9312-0004 RELEASE RECORD Another important facet of the DQO process is to identify the radionuclides of concern and determine the concentration variability. | ||
Soil samples were collected in 2006 to establish the radiological condition of Survey Unit 93 12-0004 for FSS.Cs-137 and Co-60 were the two (2) gamma emitting radionuclides reported in concentrations with the potential for exceeding the release criteria. | Soil samples were collected in 2006 to establish the radiological condition of Survey Unit 93 12-0004 for FSS.Cs-137 and Co-60 were the two (2) gamma emitting radionuclides reported in concentrations with the potential for exceeding the release criteria. | ||
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However, Cs-137 and Co-60 were the only two gamma-emitting radionuclides reported in any appreciable concentration. | However, Cs-137 and Co-60 were the only two gamma-emitting radionuclides reported in any appreciable concentration. | ||
Cs-137 was identified in ten (10) and Co-60 was identified in three (3) of the fifteen (15) samples collected for non-parametric statistical testing. The mean of the gamma spectroscopic analysis results for the sample population indicated that Cs-137 was present at levels slightly higher than expected environmental levels for Cs-137 within the vicinity of the HNP as presented in the Health Physics TSD BCY-HP-0063. | Cs-137 was identified in ten (10) and Co-60 was identified in three (3) of the fifteen (15) samples collected for non-parametric statistical testing. The mean of the gamma spectroscopic analysis results for the sample population indicated that Cs-137 was present at levels slightly higher than expected environmental levels for Cs-137 within the vicinity of the HNP as presented in the Health Physics TSD BCY-HP-0063. | ||
A summary of the fifteen (15) samples collected for non-parametric statistical testing results is provided in Table 8.931 2-0004-OOIF 4.93E-02 1 .03E-02 931 2-0004-002F 8.7 1 E-02 -3.1 4E-05 931 2-0004-003F 1 .55E-0 1 2.69E-02 9312-0004-004F 1.09E-01 1.48E-02 Revision 0 1 17 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 931 2-0004-005F 6.04E-01 9.47E-02 931 2-0004-006F | A summary of the fifteen (15) samples collected for non-parametric statistical testing results is provided in Table 8.931 2-0004-OOIF 4.93E-02 1 .03E-02 931 2-0004-002F 8.7 1 E-02 -3.1 4E-05 931 2-0004-003F 1 .55E-0 1 2.69E-02 9312-0004-004F 1.09E-01 1.48E-02 Revision 0 1 17 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 931 2-0004-005F 6.04E-01 9.47E-02 931 2-0004-006F | ||
: 1. lOB-O1 3.6 1 E-02 9312-0004-007F 3.42E-02 3.16E-02 9312-0004-008F 1.99E-01 1.26E-02 9312-0004-009F 4.87E-02 3.24E-02 9312-0004-01IOF | : 1. lOB-O1 3.6 1 E-02 9312-0004-007F 3.42E-02 3.16E-02 9312-0004-008F 1.99E-01 1.26E-02 9312-0004-009F 4.87E-02 3.24E-02 9312-0004-01IOF | ||
-7.84E-03 | -7.84E-03 | ||
-1 .23E-02 9312-0004-0OIIF 2.11lE-03 | -1 .23E-02 9312-0004-0OIIF 2.11lE-03 | ||
-8.59E-03 9312-0004-01 2F 8.06E-03 -4.29E-04 9312-0004-013F 1.41E-02 6.56E-03 9312-0004-01 4F 2.28E-0 1 0.OOE+/-00 9312-0004-015SF 2.30E-02 -1.28E-02 In addition to Cs-137 and Co-60, Sr-90 was also identified during the DQO process as a radionuclide of concern. Subsequently, all samples were subjected to analysis by gas proportional counting for Sr-90. All analyses met the required minimum MDC.Sr-90 was positively identified (i.e., a result greater than two (2) standard deviations uncertainty) in nine (9) of the fifteen (15) samples collected for non-parametric statistical testing. The results of the Sr-90 analysis for the statistical sample population are provided below in Table 9.9312-0004-OOIF 2.60E-02 93 12-0004-002F 5.95E-02 931 2-0004-003 F 3.3 8E-02 931 2-0004-004F 5.97E-02 93 12-0004-005F 2.99E-02 931 2-0004-006F 7.7 1 E-03 Revision 0 1 18 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 9312-0004-007F 1 .57E-02 931 2-0004-008F | -8.59E-03 9312-0004-01 2F 8.06E-03 -4.29E-04 9312-0004-013F 1.41E-02 6.56E-03 9312-0004-01 4F 2.28E-0 1 0.OOE+/-00 9312-0004-015SF 2.30E-02 -1.28E-02 In addition to Cs-137 and Co-60, Sr-90 was also identified during the DQO process as a radionuclide of concern. Subsequently, all samples were subjected to analysis by gas proportional counting for Sr-90. All analyses met the required minimum MDC.Sr-90 was positively identified (i.e., a result greater than two (2) standard deviations uncertainty) in nine (9) of the fifteen (15) samples collected for non-parametric statistical testing. The results of the Sr-90 analysis for the statistical sample population are provided below in Table 9.9312-0004-OOIF 2.60E-02 93 12-0004-002F 5.95E-02 931 2-0004-003 F 3.3 8E-02 931 2-0004-004F 5.97E-02 93 12-0004-005F 2.99E-02 931 2-0004-006F 7.7 1 E-03 Revision 0 1 18 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 9312-0004-007F 1 .57E-02 931 2-0004-008F | ||
: 3. 1 OE-02 93 12-0004-009F 6.24E-02 93 12-0004-OIOF 5.89E-02 9312-0004-01IIF 6.3 1lE-02 93 12-0004-012F 3.05E-03 9312-0004-013F 1.83E-02 9312-0004-014F | : 3. 1 OE-02 93 12-0004-009F 6.24E-02 93 12-0004-OIOF 5.89E-02 9312-0004-01IIF 6.3 1lE-02 93 12-0004-012F 3.05E-03 9312-0004-013F 1.83E-02 9312-0004-014F | ||
-3.31E-03 93 12-0004-015F 5.67E-03 In addition to Sr-90, the off-site laboratory also processed, as required by the sample plan, two (2) samples for the full suite of HTD radionuclides as specified in LTP, Table 2-12, "Radionuclides Potentially Present at Haddam Neck Plant" and as provided in Table 3. The requested analyses included alpha spectroscopy, gas proportional counting, and liquid scintillation depending on the radionuclide and the measurement method. All analyses performed met the required minimum MDC. No additional HTD radionuclides were positively identified (i.e., a result greater than two (2) standard deviations uncertainty). | -3.31E-03 93 12-0004-015F 5.67E-03 In addition to Sr-90, the off-site laboratory also processed, as required by the sample plan, two (2) samples for the full suite of HTD radionuclides as specified in LTP, Table 2-12, "Radionuclides Potentially Present at Haddam Neck Plant" and as provided in Table 3. The requested analyses included alpha spectroscopy, gas proportional counting, and liquid scintillation depending on the radionuclide and the measurement method. All analyses performed met the required minimum MDC. No additional HTD radionuclides were positively identified (i.e., a result greater than two (2) standard deviations uncertainty). | ||
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1 .55E-0 1 2.72E-02 2.39E-02 The range of the data, about four (4) standard deviations for all three radionuclides, was not a particularly large variation. | 1 .55E-0 1 2.72E-02 2.39E-02 The range of the data, about four (4) standard deviations for all three radionuclides, was not a particularly large variation. | ||
The difference between the mean and median was about 3% to 15% of the standard deviation which indicates some skewness in the data. The data was represented graphically through posting plots, a frequency plot, and a quantile plot. The frequency plot indicates a slight positive skewness as confirmed by the calculated skew of 2.58 for Cs-137, 1.83 for Co-60 and 0.15 for Sr-90.All data, assessments, and graphical representations are provided in Attachment 4.12. ANOMALIES A small discrete particle exhibiting elevated activity was removed from the soil matrix of investigative soil sample 9312-0004-016-I. | The difference between the mean and median was about 3% to 15% of the standard deviation which indicates some skewness in the data. The data was represented graphically through posting plots, a frequency plot, and a quantile plot. The frequency plot indicates a slight positive skewness as confirmed by the calculated skew of 2.58 for Cs-137, 1.83 for Co-60 and 0.15 for Sr-90.All data, assessments, and graphical representations are provided in Attachment 4.12. ANOMALIES A small discrete particle exhibiting elevated activity was removed from the soil matrix of investigative soil sample 9312-0004-016-I. | ||
Analysis of the particle by the on-site laboratory indicated | Analysis of the particle by the on-site laboratory indicated | ||
: 0. 128 ýtCi of Co-60. The particle was segregated and properly disposed of as radioactive waste. Scan surveys of the area and subsequent bounding soil samples indicate that no additional discrete particles were present.13. CONCLUSION Survey Unit 9312-0004 has met the final DQOs of the FSS plan. The ALARA criteria for soils as specified in Chapter 4 of the LTP were achieved.An EMC calculation was performed for an area of elevated activity in accordance with LTP Section 5.8.3 and Equation 4 of this report. The results indicated that the area was less than unity. No further action is warranted. | : 0. 128 ýtCi of Co-60. The particle was segregated and properly disposed of as radioactive waste. Scan surveys of the area and subsequent bounding soil samples indicate that no additional discrete particles were present.13. CONCLUSION Survey Unit 9312-0004 has met the final DQOs of the FSS plan. The ALARA criteria for soils as specified in Chapter 4 of the LTP were achieved.An EMC calculation was performed for an area of elevated activity in accordance with LTP Section 5.8.3 and Equation 4 of this report. The results indicated that the area was less than unity. No further action is warranted. | ||
See Tables 13 through 16 of this report for specific information with regard to the EMC calculation. | See Tables 13 through 16 of this report for specific information with regard to the EMC calculation. | ||
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_______________________ | _______________________ | ||
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) | 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: | Priority: | ||
[L] 30 D. [- 15 D. Z 7 D.Other: ___Sample. Designation Date Time 1 C41441-omment, Preservation Lab Sample. ID 9312-0004-OOIF 1/30/07 1322 TS G BP X _____ __ __ __ _________9312-0004-002F 1/30/07 1325 TS G BP X __ ___________ | [L] 30 D. [- 15 D. Z 7 D.Other: ___Sample. Designation Date Time 1 C41441-omment, Preservation Lab Sample. ID 9312-0004-OOIF 1/30/07 1322 TS G BP X _____ __ __ __ _________9312-0004-002F 1/30/07 1325 TS G BP X __ ___________ | ||
_______931 2-0004-003F 1/30/07 1327 TS G BP X _____ __ _________9312-0004-004F 1/30/07 1329 TS G BP X ____________________ | _______931 2-0004-003F 1/30/07 1327 TS G BP X _____ __ _________9312-0004-004F 1/30/07 1329 TS G BP X ____________________ | ||
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9312-0004-OIOF 1/30/07 1343 TS G BP X _________________________ | 9312-0004-OIOF 1/30/07 1343 TS G BP X _________________________ | ||
NOTES: PO #: 002332 MSR #: 01 -Wo4(.,I LTP QA ElRadwaste QA LINon QA Samples Shipped Via: Internal C ntainer M Fed-Ex Temp.: ~Deg. C ElUP El Hand Custody,$eed? | NOTES: PO #: 002332 MSR #: 01 -Wo4(.,I LTP QA ElRadwaste QA LINon QA Samples Shipped Via: Internal C ntainer M Fed-Ex Temp.: ~Deg. C ElUP El Hand Custody,$eed? | ||
._U Relinqushed Da e im rcDate/TimeCutd c?L= IRI 7 #sý' El Other 3) Relinquished By Date/Time | ._U Relinqushed Da e im rcDate/TimeCutd c?L= IRI 7 #sý' El Other 3) Relinquished By Date/Time | ||
: 4) Receive~d Da~te'/Time Bill__of__Lading | : 4) Receive~d Da~te'/Time Bill__of__Lading | ||
__# Y N 5) Relinquished By Date/Time | __# Y N 5) Relinquished By Date/Time | ||
: 6) Received By Date/Time Health Physics Procedure Healh Pysis PoceureGPP-GGGR-R5,104-00.3 -Attaclhment B-CY-00 1 Major Connecticut Yankee Atomic Power Company Chain of Custody Form No. 2007-00032 362 Injun Hollow Road, East Hampton, CT 06424 860-267-2556 | : 6) Received By Date/Time Health Physics Procedure Healh Pysis PoceureGPP-GGGR-R5,104-00.3 -Attaclhment B-CY-00 1 Major Connecticut Yankee Atomic Power Company Chain of Custody Form No. 2007-00032 362 Injun Hollow Road, East Hampton, CT 06424 860-267-2556 | ||
____ _________________ | ____ _________________ | ||
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9312-0004-013F 1/30/07 1352 TS G BP X___ _________9312-0004-014F 1/30/07 1358 NTS G BP X________________ | 9312-0004-013F 1/30/07 1352 TS G BP X___ _________9312-0004-014F 1/30/07 1358 NTS G BP X________________ | ||
9312-0004-015F 1/30/07 1400 TS G BP X _________ | 9312-0004-015F 1/30/07 1400 TS G BP X _________ | ||
_______NOTES: PO #: 002332 MSR #: (D -oo4-3 LTP QA LIRadwaste QA LINon QA Samples Shipped Via: Int ernal Container SFed Ex Temp..: ...,Deg .C Li] Hand Custody ýd?'1) Relinquished B Date/Tfime | _______NOTES: PO #: 002332 MSR #: (D -oo4-3 LTP QA LIRadwaste QA LINon QA Samples Shipped Via: Int ernal Container SFed Ex Temp..: ...,Deg .C Li] Hand Custody ýd?'1) Relinquished B Date/Tfime | ||
: 2) Epce ved e Custody Seal Intact?y~~y~ ,~~- i m Other 3) Relinquished By Date/Time | : 2) Epce ved e Custody Seal Intact?y~~y~ ,~~- i m Other 3) Relinquished By Date/Time | ||
: 4) Received Bý Date/Time | : 4) Received Bý Date/Time | ||
___________ | ___________ | ||
Y N Bill of Lading #1 5) Relinquished By Date/Time | Y N Bill of Lading #1 5) Relinquished By Date/Time | ||
: 6) Received By Date/Time Health Physics Procedure Healh Pysis PoceureGPP-GGGR-R5.1 04-0.03-.Attach~ment B-CY-00 I Major Connecticut Yankee Atomic Power Company Chain, of Custody Form No 070033 362 Injun Hollow Road, East Hampton, CT 06424No2070 86.0-267-2556 | : 6) Received By Date/Time Health Physics Procedure Healh Pysis PoceureGPP-GGGR-R5.1 04-0.03-.Attach~ment B-CY-00 I Major Connecticut Yankee Atomic Power Company Chain, of Custody Form No 070033 362 Injun Hollow Road, East Hampton, CT 06424No2070 86.0-267-2556 | ||
____ ____________________ | ____ ____________________ | ||
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_____Project Name: Haddam Neck Decommissioning Analyses Requested ai Use only Contact Name & Phone: Comments: Jack McCarthy 860-267-3924 Media Sample Container________________________________ | _____Project Name: Haddam Neck Decommissioning Analyses Requested ai 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) n Prorthe: Rl 30 D. [] 15 D. Z 7 D.Other CIO Sample Designation Date Time -Cmment, Preservation Lab Sample ID 9312-0004-016-1 1/30/07 1320 TS G BP X _____________________ | 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) n Prorthe: Rl 30 D. [] 15 D. Z 7 D.Other CIO Sample Designation Date Time -Cmment, Preservation Lab Sample ID 9312-0004-016-1 1/30/07 1320 TS G BP X _____________________ | ||
NOTES: P0 #: 002332 MSR #: <D 7-co oVl. Z LTP QA LIRadwaste QA II] Non QA Samples Shipped Via: Internal Container SFed Ex Temp.: -Deg. C ElHand. CustodyS ed?jelinquished By Date/Time | NOTES: P0 #: 002332 MSR #: <D 7-co oVl. Z LTP QA LIRadwaste QA II] Non QA Samples Shipped Via: Internal Container SFed Ex Temp.: -Deg. C ElHand. CustodyS ed?jelinquished By Date/Time | ||
: 2) R eivrdB Date/Time Custody Seal Intact.?3) Relinquished By Date/Time | : 2) R eivrdB Date/Time Custody Seal Intact.?3) Relinquished By Date/Time | ||
: 4) Received By Bilo aig#Y N 5) Relinquished By Date/Time | : 4) Received By Bilo aig#Y N 5) Relinquished By Date/Time | ||
: 6) Received By Date/Time INL;. 0,111'r-0 | : 6) Received By Date/Time INL;. 0,111'r-0 | ||
Line 353: | Line 353: | ||
Quality Criteria:Tye 09-FEB-07 Radiochemistry SpecificationsPrcs Instrument Type: Test / Method: Matrix Type: Client Code: GEPO EPA 905.0 Modified SldYN Batch ID: Sample Numbers: 608308 See Below Potentially affected work order(s)(SDG): | Quality Criteria:Tye 09-FEB-07 Radiochemistry SpecificationsPrcs Instrument Type: Test / Method: Matrix Type: Client Code: GEPO EPA 905.0 Modified SldYN Batch ID: Sample Numbers: 608308 See Below Potentially affected work order(s)(SDG): | ||
180060(MSR#07-0063) | 180060(MSR#07-0063) | ||
Application Issues: RDL less than MDA Failed Recovery for MS/PS Specification and Requirements | Application Issues: RDL less than MDA Failed Recovery for MS/PS Specification and Requirements | ||
[NRG Disposition: | [NRG Disposition: | ||
Nonconformance | Nonconformance | ||
Line 404: | Line 404: | ||
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD1 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 ND Analyte concentration is not detected above the detection limit* Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification | Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD1 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 ND Analyte concentration is not detected above the detection limit* Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification | ||
* Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis._50 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector: | * Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis._50 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector: | ||
Moisture: 931 2-0004-007F 180060008 TS 30-JAN-07 02-FEB-07 Client 7.28%Proiect: Client ID: Vol. Recv.: YANK01 204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch D~Rad Alpha Spec Analysis Alphaspec Am24l, Cm, Solid ALL FSS Americium-241 U 0.0678+/-0.0899 0.00 +/-0.0903 Curium-242 Curium-243/244 Aiphaspec Pu, Solid-ALL FSS Plutonium-238 Plutonium-239/240 U 0.00 +/-0.0624 0.00 +/-0.0624 0.093 +/-0.105 0.00 +/-0.106 U 0.0187 +/-0.0497 | Moisture: 931 2-0004-007F 180060008 TS 30-JAN-07 02-FEB-07 Client 7.28%Proiect: Client ID: Vol. Recv.: YANK01 204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch D~Rad Alpha Spec Analysis Alphaspec Am24l, Cm, Solid ALL FSS Americium-241 U 0.0678+/-0.0899 0.00 +/-0.0903 Curium-242 Curium-243/244 Aiphaspec Pu, Solid-ALL FSS Plutonium-238 Plutonium-239/240 U 0.00 +/-0.0624 0.00 +/-0.0624 0.093 +/-0.105 0.00 +/-0.106 U 0.0187 +/-0.0497 | ||
: 0. 0221 +/-0.0497 U -0.00493 +/-0.0548 0.0495 +/-0.0548 0.084 0.0863 0.084 0.111 0.166 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MXA 02/05/07 1044 607169 MXA 02/05/07 1044 607170 MXA 02/06/07 1528 607171 Liquid Scint Pu24I1, Solid-A LL FSS Plutonium-241 Ui-1.15 +/-5.42 4.62 +/-5.42 9.81 Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL ESS 226 In growth Waived Actinium-228 UI Americium-241 U Bismuth-212 UI Bismuth-2 14 Cesium- 134 U Cesium-I 37 U Cobalt-60 U Europium-152 U Europium-154 U Europium-IS55 U Lead-21 2 Lead-214 Manganese-54 U Niobium-94 U Potassium-40 Radium-226 Silver-108m U Thallium-208 Rad Gas Flow Proportional Counting GFPC, Sr90, solid-ALL FSS Strontium-90 U Rad Liquid Scintillation Analysis 0.00 0.015 0.00 0.413 0.0609 0.0342 0.03 16-0.0353-0.0219 0.0254 0.538 0.508 0.0234 0.00138 9.40 0.4 13 0.0108 0.179+/-0. 191+/-0.0415+1-0.369+/-0.116+/-0.052+/-0.0315+/-0.0397+/-0.0805+1-0.106+/-0.0599+/-0.0801+/-0.102+/-0.0192+/-0.0276+1-1.13+1-0.116+/-0.0244+/-0.0576 0.161 0.0341 0.255 0.0481 0.0335 0.0305 0.037 0.0549 0.0862 0.0548 0.0316 0.0423 0.0244 0.0244 0.234 0.0481 0.0221 0.0271+/-0.191+/-0.0415+/-0.369+/-0.116+/-0.052+/-0.0315+/-0.0397+/-0.0805+/-0. 106+/-0.0599+/-0.0801+/-0.102+/-0.0192+/-0.0276+/-1.13+/-0.116+/-0.0244+/-0.0576 0.323 0.0682 0.509 0.096 0.0669 0.061 0.074 0.110 0.172 0.109 0.0632 0.0846 0.0488 0.0488 0.467 0.096 0.0441 0.0541 0.0411 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/05/07 1459 607292 KSDI1 02/09/07 0947 608308 0.0157 +/-0.0237 0.0179 +/-0.0237_91 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: 931 2-0004-007F 180060008 Project: Client ID: Vol. Recv.: YANK01204 YANKOO I Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch D~Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid -3 pCi/g Tritium U 0.792 +/-1.08 0.868 +/-1.08 1.82 pCi/g AXD2 02/03/07 0322 607149 Liquid Scint C14, Solid AIIFSS Carbon-14 U 0.00632 +/-0.0894 0.0749 +/-0.0894 0.153 pCilg AXD2 02/03/07 0201 607153 Liquid Scint FeSS, Solid-ALL ESS Iron-55 U -25.7 +/-46.1 31.2 +/-46.1 64.7 pCi/g MXP1 02/06/07 1559 607148 Liquid Scint Ni63, Solid-ALL FSS Nickel-63 U -0.51 +/-8.56 7.21 +/-8.56 15.1 pCi/g MXP1 02/06/07 1401 607147 Liquid Scint Tc99, Solid-ALL FSS Technetium-99 U 0.142 +/-0.183 0.150 +/-0.183 0.309 pCi/g MXPI 02/07/07 1402 607151 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I DOE EML HASL-300, Am-05-RC Modified 2 DOE EML HASL-300, Pu- I I1-RC Modified 3 DOE EML HASL-300, Pu- I I1-RC Modified 4 EML HASL 300, 4.5.2.3 5 EPA 905.0 Modified 6 EPA 905.0 Modified 7 EPA 906.0 Modified 8 EPA EERF C-01 Modified 9 DOE RESL Fe-I, Modified 10 DOE RESL Ni-I, Modified I I DOE EML HASL-300, Tc-02-RC Modified Surrogate/Tracer recovery Test Recovery % Acceptable Limits Americium-243 Plutonium-242 Plutonium-242 Strontium-90 Aiphaspec Am24l, Cm, Solid ALL Alphaspec Pu, Solid-ALL FSS Liquid Scint Pu24I, Solid-ALL FS GFPC, SOO0, solid-ALL FSS 81 95 99 66 (15%-125%) | : 0. 0221 +/-0.0497 U -0.00493 +/-0.0548 0.0495 +/-0.0548 0.084 0.0863 0.084 0.111 0.166 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MXA 02/05/07 1044 607169 MXA 02/05/07 1044 607170 MXA 02/06/07 1528 607171 Liquid Scint Pu24I1, Solid-A LL FSS Plutonium-241 Ui-1.15 +/-5.42 4.62 +/-5.42 9.81 Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL ESS 226 In growth Waived Actinium-228 UI Americium-241 U Bismuth-212 UI Bismuth-2 14 Cesium- 134 U Cesium-I 37 U Cobalt-60 U Europium-152 U Europium-154 U Europium-IS55 U Lead-21 2 Lead-214 Manganese-54 U Niobium-94 U Potassium-40 Radium-226 Silver-108m U Thallium-208 Rad Gas Flow Proportional Counting GFPC, Sr90, solid-ALL FSS Strontium-90 U Rad Liquid Scintillation Analysis 0.00 0.015 0.00 0.413 0.0609 0.0342 0.03 16-0.0353-0.0219 0.0254 0.538 0.508 0.0234 0.00138 9.40 0.4 13 0.0108 0.179+/-0. 191+/-0.0415+1-0.369+/-0.116+/-0.052+/-0.0315+/-0.0397+/-0.0805+1-0.106+/-0.0599+/-0.0801+/-0.102+/-0.0192+/-0.0276+1-1.13+1-0.116+/-0.0244+/-0.0576 0.161 0.0341 0.255 0.0481 0.0335 0.0305 0.037 0.0549 0.0862 0.0548 0.0316 0.0423 0.0244 0.0244 0.234 0.0481 0.0221 0.0271+/-0.191+/-0.0415+/-0.369+/-0.116+/-0.052+/-0.0315+/-0.0397+/-0.0805+/-0. 106+/-0.0599+/-0.0801+/-0.102+/-0.0192+/-0.0276+/-1.13+/-0.116+/-0.0244+/-0.0576 0.323 0.0682 0.509 0.096 0.0669 0.061 0.074 0.110 0.172 0.109 0.0632 0.0846 0.0488 0.0488 0.467 0.096 0.0441 0.0541 0.0411 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/05/07 1459 607292 KSDI1 02/09/07 0947 608308 0.0157 +/-0.0237 0.0179 +/-0.0237_91 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: 931 2-0004-007F 180060008 Project: Client ID: Vol. Recv.: YANK01204 YANKOO I Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch D~Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid -3 pCi/g Tritium U 0.792 +/-1.08 0.868 +/-1.08 1.82 pCi/g AXD2 02/03/07 0322 607149 Liquid Scint C14, Solid AIIFSS Carbon-14 U 0.00632 +/-0.0894 0.0749 +/-0.0894 0.153 pCilg AXD2 02/03/07 0201 607153 Liquid Scint FeSS, Solid-ALL ESS Iron-55 U -25.7 +/-46.1 31.2 +/-46.1 64.7 pCi/g MXP1 02/06/07 1559 607148 Liquid Scint Ni63, Solid-ALL FSS Nickel-63 U -0.51 +/-8.56 7.21 +/-8.56 15.1 pCi/g MXP1 02/06/07 1401 607147 Liquid Scint Tc99, Solid-ALL FSS Technetium-99 U 0.142 +/-0.183 0.150 +/-0.183 0.309 pCi/g MXPI 02/07/07 1402 607151 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I DOE EML HASL-300, Am-05-RC Modified 2 DOE EML HASL-300, Pu- I I1-RC Modified 3 DOE EML HASL-300, Pu- I I1-RC Modified 4 EML HASL 300, 4.5.2.3 5 EPA 905.0 Modified 6 EPA 905.0 Modified 7 EPA 906.0 Modified 8 EPA EERF C-01 Modified 9 DOE RESL Fe-I, Modified 10 DOE RESL Ni-I, Modified I I DOE EML HASL-300, Tc-02-RC Modified Surrogate/Tracer recovery Test Recovery % Acceptable Limits Americium-243 Plutonium-242 Plutonium-242 Strontium-90 Aiphaspec Am24l, Cm, Solid ALL Alphaspec Pu, Solid-ALL FSS Liquid Scint Pu24I, Solid-ALL FS GFPC, SOO0, solid-ALL FSS 81 95 99 66 (15%-125%) | ||
(15%-125%) | (15%-125%) | ||
Line 532: | Line 532: | ||
9312-0004-0211 2/13/07 1401 TS G BP X______________ | 9312-0004-0211 2/13/07 1401 TS G BP X______________ | ||
NOTES: PO #: 002332 MSR #: 07-0079 Z LTP QA El Radwaste QA LI Non QA Samples Shipped Via: Internal Container SFed Ex Temp.: ~IDeg. C fUPS El Hand Cu-q 5 dy Sealed?1) Relinquishd7 | NOTES: PO #: 002332 MSR #: 07-0079 Z LTP QA El Radwaste QA LI Non QA Samples Shipped Via: Internal Container SFed Ex Temp.: ~IDeg. C fUPS El Hand Cu-q 5 dy Sealed?1) Relinquishd7 | ||
~ Date/Time | ~ Date/Time | ||
: 2) Received By Date/Time% | : 2) Received By Date/Time% | ||
Custody Seal Intact?CA -ý -2/ .DJ-0 530 I:l Other 3) Relinquished By 7Date/Timne | Custody Seal Intact?CA -ý -2/ .DJ-0 530 I:l Other 3) Relinquished By 7Date/Timne | ||
: 4) Received By Date/Time Bl fLdn 5) Relinquished By Date/Time | : 4) Received By Date/Time Bl fLdn 5) Relinquished By Date/Time | ||
: 6) Received By Date/Time Connecticut Yankee -Statement of Work for AnalyXtical Lab Services -CY-4SC-SOW7VOjl Figure 1. -Sample Check-in List.Datle/Time Received: | : 6) Received By Date/Time Connecticut Yankee -Statement of Work for AnalyXtical Lab Services -CY-4SC-SOW7VOjl Figure 1. -Sample Check-in List.Datle/Time Received: | ||
40 -)t 7 3)SDG#:_S917 Work Order Number: I t--*Shipping, Cchtainer ID:?'1 2 'i ~V1 7)O3Chain of Custo~dy # -s)0Q -COO '3 I. Custody Seals. onT shipping container intact?..-e 4o(2. Custody Seats dated and signed? Yes N)~o 11 3. Chain-of-Custody record present? Yes ,ioj.4, Cooler-temperature | 40 -)t 7 3)SDG#:_S917 Work Order Number: I t--*Shipping, Cchtainer ID:?'1 2 'i ~V1 7)O3Chain of Custo~dy # -s)0Q -COO '3 I. Custody Seals. onT shipping container intact?..-e 4o(2. Custody Seats dated and signed? Yes N)~o 11 3. Chain-of-Custody record present? Yes ,ioj.4, Cooler-temperature | ||
Line 648: | Line 648: | ||
______J(Pcilg) | ______J(Pcilg) | ||
_____ Pci/g) ____ (pCilg) of DCGL 9312-0004-002F Cs-1 34 2.95E-02 0.025 4.64E-02 + 2.8E+00 0.011 9312-0004-003F | _____ Pci/g) ____ (pCilg) of DCGL 9312-0004-002F Cs-1 34 2.95E-02 0.025 4.64E-02 + 2.8E+00 0.011 9312-0004-003F | ||
'Cs-134 I3.81 E-02 0.3 .3E0 + 2,E0 0.1---- --- --- ---- --- --- --- ---- --- --- ---- --0--036- -- ---- ----- ----- -------- --E--- -- --- --- --------- --- --- -- 0 0 14--- -- -9312-0004-006F | 'Cs-134 I3.81 E-02 0.3 .3E0 + 2,E0 0.1---- --- --- ---- --- --- --- ---- --- --- ---- --0--036- -- ---- ----- ----- -------- --E--- -- --- --- --------- --- --- -- 0 0 14--- -- -9312-0004-006F | ||
:Mn-54 3.50E-02 0,020 3.68E-02 + 1.OE+01 0.003 9312-0004-007F | :Mn-54 3.50E-02 0,020 3.68E-02 + 1.OE+01 0.003 9312-0004-007F | ||
!Cs 134 6.09E-02 0.052 6.69E-02 + 2.8E+00 0,022 9312-0004-007F | !Cs 134 6.09E-02 0.052 6.69E-02 + 2.8E+00 0,022 9312-0004-007F | ||
!Mn-54 2.34E-02 0.019 4.88E-02 + 1.OE+01 0.002 9312-0004-0OlF | !Mn-54 2.34E-02 0.019 4.88E-02 + 1.OE+01 0.002 9312-0004-0OlF | ||
':Eu-155 I1.17E-01 0.113 1.23E-01 + 2.4E+02 0.000 9312-0004-011 F ;Eu 155 7.24E-02 0.066 1,22E-01 + 2.4E+02 0.000 9312-0004-014F | ':Eu-155 I1.17E-01 0.113 1.23E-01 + 2.4E+02 0.000 9312-0004-011 F ;Eu 155 7.24E-02 0.066 1,22E-01 + 2.4E+02 0.000 9312-0004-014F | ||
'Am-241 I3.56E-02 0.033 5.35E-02 + 1.6E+01 0.002 9312-0004-015F | 'Am-241 I3.56E-02 0.033 5.35E-02 + 1.6E+01 0.002 9312-0004-015F | ||
:Eu 155 4.88E-02 0.035 5.17E-02 + 2.4E+02 0.000 REVISION 0Pae2o2 Page 2 of2 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD ATTACHMENT 4B (GRAPHICAL REPRESENTATION OF DATA)Revision 0 FREQUENCY PLOT FOR CES1UM-.137 Survey Unit: 9312-0004 Survey Unit Name: RCA North of PAD & Tank Farm Mvean: 1.I IE-0i I PCi/g Frequency Plot For Cs-I 37 in LL 6-4-2 0-II LJ 9.41E-02 1.96E-01 2.98E-01 4.OOE-01 5.02E-01 6.04E-01 Upper End Value (pCilg)Upper End Observation Observation Value Frequency Frequency 9.41 E,-02 9 60%1.96Ei-0 1 3 20%2.98E-01 2 13%4.OOE-0 1 0 0%5.02E-01 0 0%6.04E-01, 1 7%Total: I15 100%Reviewed by/Date 1o I of I QUANTILE PLOT FOR CESIUM-1 37 Survey Unit: 9312-0004 Suirvey Unit Namne: R-CA North of PAL3 &I ank Farm Mean: 1.11 lE-OI pCi/g_______ | :Eu 155 4.88E-02 0.035 5.17E-02 + 2.4E+02 0.000 REVISION 0Pae2o2 Page 2 of2 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD ATTACHMENT 4B (GRAPHICAL REPRESENTATION OF DATA)Revision 0 FREQUENCY PLOT FOR CES1UM-.137 Survey Unit: 9312-0004 Survey Unit Name: RCA North of PAD & Tank Farm Mvean: 1.I IE-0i I PCi/g Frequency Plot For Cs-I 37 in LL 6-4-2 0-II LJ 9.41E-02 1.96E-01 2.98E-01 4.OOE-01 5.02E-01 6.04E-01 Upper End Value (pCilg)Upper End Observation Observation Value Frequency Frequency 9.41 E,-02 9 60%1.96Ei-0 1 3 20%2.98E-01 2 13%4.OOE-0 1 0 0%5.02E-01 0 0%6.04E-01, 1 7%Total: I15 100%Reviewed by/Date 1o I of I QUANTILE PLOT FOR CESIUM-1 37 Survey Unit: 9312-0004 Suirvey Unit Namne: R-CA North of PAL3 &I ank Farm Mean: 1.11 lE-OI pCi/g_______ | ||
Quantile Plot For Cs- 137 T00E -6.00E-01 ......-.4.00E-01 ............ | Quantile Plot For Cs- 137 T00E -6.00E-01 ......-.4.00E-01 ............ |
Revision as of 22:42, 12 July 2019
ML071730442 | |
Person / Time | |
---|---|
Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
Issue date: | 03/07/2007 |
From: | Wojtkowiak D Connecticut Yankee Atomic Power Co |
To: | NRC/FSME |
References | |
Download: ML071730442 (170) | |
Text
CYAPCO FINAL STATUS SURVEY RELEASE RECORD FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 Prepared.
B. I DW4LO(Reviewed By: FSS E!ngineer Approved.By:
_____eý&Techn'ical Support M~anager Date: 2)(5107 Date: //7 Date: / 7/6 R.evision 0
FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD TABLE OF CONTENTS 1. SURVEY UNIT DESCRIPTION...........................................
3 2. CLASSIFICATION BASIS .................................................
3 3. DATA QUALITY OBJECTIVES (DQO) ..................................
7 4. SURVEY DESIGN .........................................................
11 5. SURVEY IMPLEMENTATION
..........................................
14 6. SURVEY RESULTS .......................................................
15 7. QUALITY CONTROL.....................................................
20 8. INVESTIGATIONS AND RESULTS ....................................
21 9. REMEDIATION AND RESULTS........................................
24 10. CHANGES FROM THE FINAL STATUS SURVEY PLAN..........
24 11. DATA QUALITY ASSESSMENT (DQA)...............................
24 12. ANOMALIES
...............................................................
25 13. CONCLUSION..............................................................
25 14. ATTACHMENTS...........................................................
26 14.1 Attachment 1 -Figures (6 pages including cover)14.2 Attachment 2 -Scan Results (4 pages including cover)14.3 Attachment 3 -Laboratory Data (117 pages including cover)14.4 Attachment 4 -DQA Results (17 pages including covers)TOTAL 170 Revision 0 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 1. SURVEY UNIT DESCRIPTION Survey Unit 9312-0004 (northern portion of the former Radiologically Controlled Area (RCA)) is designated as Final Status Survey (FSS) Class 1 and has an area of approximately fifteen hundred-eighty six (1,586) square meters and is located approximately five hundred-six feet (506 ft) to the southeast of the site benchmark*used at Haddam Neck Plant (HNP) (see. Attachment 1). The survey unit is bounded as follows: land Survey Unit 9313-0000 to the north (called north as oriented with the north to south flow of the Connecticut River) and west, land Survey Unit 9312-0005*and land Survey Unit 93 12-0006 to the south and land Survey Unit 93 12-0009 to the east. As a result of demolition and remediation activities, the area topography is mostly flat and de-vegetated.
The survey unit has a moderate slope running from east to west.The reference coordinates associated with this survey unit are E008 through E014 by S065 through S067 (refer to "HNP License Termination Plan" (LTP) Section 5.4.4).The reference coordinates provide the maximum dimensions of a rectangle containing this survey unit. Some areas contained in this rectangle may not be part of this survey unit. The boundary of the survey unit was defined using a Global Positioning System (GPS) based on the Connecticut State Plane System North American Datum (NAD)1927.2. CLASSIFICATION BASIS The survey unit was classified in accordance with Procedure RPM 5.1-10, "Survey Unit Classification.
" The "Classification Basis Summary" conducted for Survey Unit 9312-0004 consisted of: a) A review of the I1OCFR5O.75 (g) (1) database, b) A review of the "Initial Characterization Report" and the "Historic Site Assessment Supplement, " c) Historic and current survey records review, d) Visual inspections and a "walkdown." A review of the "Initial and Supplemental Characterization Reports " as well as the previous "Classification Basis Summaries" was perform-ed.
The source documents, the "Connecticut Yankee Haddam Neck Characterization Report" and "Initial Classifcation for Survey Areas at Connecticut Yankee", were incorporated by reference in LTP, Revision 0.Revision 03 3 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD During plant operation, Survey Unit 9312-0004 was the location of significant reactor support structures and systems, encompassing the open land area between the north wall of the Primary Auxiliary Building (PAB), the area designated as the "Tank Farm" and the north boundary of the Radiologically Controlled Area (RCA), including all subsurface drains and utilities.
It served as the normal access point for personnel and equipment ingress and egress from the RCA.The PAB was a concrete structure located along the south boundary of this survey unit that was designed to house systems containing radioactive materials and to contain and control leakage occurring during routine operations as well as unusual conditions.
With the exception of various service water, gas and air systems, the majority of the systems within the PAB were radiologically contaminated.
The Tank Farm was an asphalt covered area located to the southeast of this survey unit where the Refueling Water Storage Tank (RWST), the Waste Test Tanks, the Aerated Drains Holdup Tank (ADHUT), the Borated Waste Storage Tank (BWST)and the Recycle Test Tanks (RTT's) were located. Rupture-containment dikes were constructed around the bases of these tanks. In addition, the area also contained sub-grade covered and shielded pipe trenches that housed subsurface piping and conduit associated with the tanks and other adjacent support systems. All of these tanks and systems had contained radioactive liquids over their history and were highly contaminated.
A review of the historical documentation indicated a significant number of operational events that may have impacted Survey Unit 9312-0004.
Operational events were considered to be spills and leakage from contaminated systems. These events would have had the most impact on the radiological condition of subsurface structures and footers; and the underlying soil and bedrock prior to system and structural decontamination and demolition.
Some of the major events are summarized as follows;* Diaphragm rupture, valve failure and gasket leakage from components associated with the Refueling Water Storage Tank (RWST) resulted in documented spills of radioactive liquid into the alleyway between the Containment structure and the PAB in November 1973, February 1976, December 1976, February 1978 and January 1979.* A frozen degassifier line in February 1979 caused the rupture of the diaphragm disc and led to leakage of reactor cavity water into the main stack drain and subsequently onto the surrounding area in the PAB alleyway.
The report estimated a release of mixed fission and activation products onto the ground and the storm drains." In July of 1979, contaminated water was released onto the stack and surrounding area from the PAB ventilation system.Revision 04 4 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD* A series of events in September 1979 resulted in the release of steam generator contents into the stack. The steam condensed in the stack ductwork and subsequently leaked 50 to 75 gallons of contaminated water onto the alleyway.All of the liquid was removed and the area was decontaminated.
- The degassifier rupture diaphragm actuated in December 1979 and vented gaseous contents up the stack and liquid contents near the base of the stack. The impacted areas and systems were storm sewers, roof drain lines, stack, stack duct and drain lines and the PAB roof. All impacted areas were remediated." In September of 1981 and again in October of 1981, contaminated water overflowed from the RWST hatch onto the nearby ground due to a valve misalignment and the activation of the thermo siphon heater.* Contaminated water from RWST cleanup hoses leaked onto the alleyway in April 1990. The area was decontaminated and released.* In September 1990 and July 1994, cracks in the welds located in the base of the RWST led to leakage of contaminated water onto the tank pedestal." An improperly fabricated flange led to water leakage from the RWST in November 1991 and January 1992.* During a rainstorm in August 1997, an overflow of water from the RWST catch basin area to an uncontrolled sand area was observed.
Analysis of the water indicated H-3, Co-60 and Cs-137. The Condition Report identified the catch basin overflow as a potential source of historical tritium contamination of the yard drains and external containment mat sump.* In June 1998, leakages from the RWST floor plates and manway port flanged joints were observed.
The water accumulated around the tank foundation and trough areas on the western side of the tank. Analysis of water samples from both leaking areas identified the source of both leakages as the RWST.* An HP survey in October 1998 revealed loose contamination at levels inside the catch containment at the base of the RWST.Major demolition and remediation activities began in 2002. All systems and components located inside this survey unit were removed and building structural surfaces were decontaminated to ensure contamination levels were acceptable for controlled demolition.
Confirmatory radiological surveys were performned throughout the demolition process. All above grade structures were then demolished to grade.Outside of the Containment shell, extensive soil remediation was performed in Survey Area 9312. A large excavation was created to the north of the Containment that was designated as Excavation
- 2. This excavation included the area in the vicinity of the RWST and the PAB corridor.
A second large excavation, designated as Excavation
- 1 was located over the PAB footprint.
A third excavation, designated as Excavation
- 3 was located in the area between the Containment Building and Spent Fuel Building (SFB). Soil was excavated and removed as adjacent structures Revision 05 5 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD were demolished.
This process continued until bedrock was exposed. Subsurface structures and footings that remained following demolition and excavation include the Containment Mat, the Cable Vault wall, the Service Building east wall, a remnant of the PAB northwest wall, the Waste Disposal Building footing, the "B" Switchgear Building footing and miscellaneous fragments of footings and slabs on the bedrock.As with the Containment basement shell, all excavations were backfilled following the performance of a radiological assessment.
No. above grade structures currently reside within Survey Unit 9312-0004.
In Survey Area 9312, post-remediation soil samples were taken from the as-left surface soils under two (2) Survey and Sampling Work Plans, SSWP-06-08-000 and SSWP 12-001. Thirty-five (35) post remediation surface soil samples were collected from the various locations within Survey Area 9312. All samples were collected and analyzed by gamma spectroscopy by an approved off-site laboratory.
Ten (10) of the thirty-five (35) post remediation samples collected were analyzed for the full suite of "Hard-to-Detect" (HTD) radionuclides specified in the LTP, Table 2-12, "Radionuclides Potentially Present at Haddam Neck Plant" and as provided in Table 3. Statistical quantities (mean, median and standard deviation) from the 2006 post-remediation survey conducted under SSWP-06-08-000 and SSWP-06-12-001 are provided in Table 1.Minimum Value: 1 .32E-02-5 .OOE-02 Maximum Value: 1 .70E+/-00 1 .43E+/-00 Mean: 2.38E-01 1.08E-01 Median: 1.65E-01 1.46E-02 Standard Deviation:
- 3. 1OE-0lI 2.76E-01 A review of this sample data shows Cs-137 and Co-60 to be the primary radionuclides of concern, with both isotopes reported at fairly low concentrations.
The sample population as a whole was evaluated to assess the distribution of the detected radionuclides.
The radionuclide distribution percentage for each sample in the population was calculated by dividing the concentration of each detected radionuclide by the total activity concentration in the sample, expressing the abundance of the specific nuclide in the sample compared against the total activity.The mean radionuclide distribution was then calculated by taking the average of the individual sample distribution fractions.
The results are provided in Table 2.Revision 06 6 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD Cs-137 0.689 Co-60 0.3 11 No HTD radionuclides were positively identified in concentrations meeting the accepted criteria for detection (i.e., a result greater than two (2) standard deviations uncertainty).
Radionuclide screening or de-selection is a process where an individual radionuclide or aggregates may be considered insignificant and eliminated from the FSS. The criteria for de-selection are concentrations less than 5% for individual radionuclides and less than 10% for aggregates.
While Sr-90 was not identified in the soil characterization results, it was decided to include Sr-90 as a radionuclide of concern for this survey unit as Sr-90 was prevalent in the soils prior to remediation.
Therefore, all volumetric soil samples taken as part of the survey design for this survey unit were subjected to direct analysis for Sr-90.The FSS Engineer performed a visual inspection and walk-down during January 2007 to assess the physical condition of the survey unit, evaluate access points, travel paths and identify potentially hazardous conditions.
This survey area is affected by existing and future groundwater (reference CY memo ISC 06-024) which will be a source of dose from residual radioactivity, as discussed in Section 3 under the Data Quality Objectives.
Based upon the identification of radioactive material above the Derived Concentration Guideline Levels (DCGLs), and the need for radiological remediation, it was concluded that there was some probability for residual radioactivity in concentrations greater than the DCGLs, justifying a final survey unit classification of Class 1 (refer to Section 3).3. DATA QUALITY OBJECTIVES (DQO)FSS design and planning used the Data Quality Objective (DQO) process as described by the LTP, Procedure RPM 5.1 -li, "Preparation of Final Status Survey Plan," and the "Multi-Agency Radiation Survey and Site Investigation Manual" (MARSSIM).
A summary of the main features of the DQO process are provided herein.The DQO process incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis.
Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition.
The baseline condition is technically known as the null hypothesis.
Revision 07 7 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection.
In designing the survey plan, the underlying assumption, or null hypothesis was that residual activity in the survey unit exceeded the release criteria.
Rejection of the null hypothesis would indicate that residual activity within the survey unit does not exceed the release criteria.The primary objective of the FSS plan was to demonstrate that the level of residual radioactivity in Survey Unit 9312-0004 did not exceed the release criteria specified in the LTP and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA).A fundamental precursor to survey design is to establish a relationship between the release criteria and some measurable quantity.
This is done through the development of DCGLs. The DCGLs represent average levels of radioactivity above background levels and are presented in terms of surface or mass activity concentrations.
Chapter 6 of the LTP describes in detail the modeling used to 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 I shows the mathematical relationship between the three (3) components and the total dose.Equation 1 HTotal =Hs 0 oi +HExistingGw
+HFuitureGW The total dose under the LTP criteria is twenty-five (25) mremlyr Total Effective Dose Equivalent (TEDE) from all three (3) components.
The allowable total dose under the Connecticut Department of Environmental Protection (CTDEP)radiological remediation standard for CY is nineteen (19) mremlyr 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) mremlyr TEDE.This survey unit is considered impacted by future groundwater radioactive contamination, as there are underground foundations containing residual radioactive material within the groundwater saturated zone in the area (reference CY memo ISC 06-024). The dose contribution from future groundwater, the third dose component, is bounded by two (2) mremlyr TEDE.Revision 08 8 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD Equation 2 19 mremlyrrotal, = 15 mrem/yrs 0 ,il +/- 2 mremi/yrExisting Gw+/- 2 mremn/yrFutUrCGW The allowable dose for soil *in this survey unit is fifteen (15) mrem/yr TEDE as shown by Equation 2 above. The concentration of residual radioactivity resulting in fifteen (15) mrem/yr TEDE is designated as the Operational DCGL (DCGLOp), and has been es tablished for the radionuclides of concern as provided in Table 3.Revision 09 9 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD H-3 4.12E+02 2 .47E+02 1.65E+/-01 C-14 5.66E+00 3.40E+00 2.26E-01 Mn-54 1.74E+01 1.04E+/-01 6.96E-01I Fe-55 2.74E+04 1.64E+04 1. 1OE+03 Co-60 3.8 1 E+00 2.29E+/-00 1 .52E-0 1 Ni-63 7.23E+02 4.34E+02 2.89E+0 1 Sr-90 1.55E+00 9.30E-01 6.20E-02 Nb-94 7.12E+00 4.27E+00 2.85E-01 Tc-99 1.26E+01 7.56E+00 5.04E-01 Ag-lO8m 7.14E+00 4.28E+00 2.86E-01 Cs-134 4.67E+00 2.80E+/-00 1.87E-01 Cs-I 37 7.9 1E+00 4.75E+00 3.16E-01I Eu-152 1.O1E+01 6.06E+00 4.04E-01 Eu- 154 9.29E+00 5.57E+00 3.72E-0OI Eu-155 3.92E+02 2.35E+02 1.57E+01 Pu-238 2.96E+O1 Il.78E+01
- 1. 18E+00 Pu-239/240 2.67E+01I 1.60E+01 1.07E+00 Am-241 5)2.58E+01 1.55E+01 1.03E+00 Pu-241 8.70E+02 5.22E+02 3.48E+0lI Cm-243/244 2.90E+0 1 1 .74E+0 1 1. 1 6E+00 (1)(2)(3)(4)(5)Bold indicates those radionucidies considered Hard to Detect (HTD)The Base Case Soil DCGL(s) are specified by the LTP in Chapter 6 and are equivalent to twenty-five (25) mremlyr TEDE The Operational DCGL is equivalent to achieving fifteen (15) mremlyr TEDE The required MDC is equivalent to achieving one (1) mrem/yr TEDE 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 performned Revision 0 1 10 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 9312-0004 RELEASE RECORD Another important facet of the DQO process is to identify the radionuclides of concern and determine the concentration variability.
Soil samples were collected in 2006 to establish the radiological condition of Survey Unit 93 12-0004 for FSS.Cs-137 and Co-60 were the two (2) gamma emitting radionuclides reported in concentrations with the potential for exceeding the release criteria.
Sr-90 was included as a radionuclide of concern due to it's prevalence in the soil prior to remediation.
The characterization data were used for' the survey design and are provided in Table 1.Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the DCGL. Survey instrument response checks were required prior to issue and after the instrument had been used. Control and accountability of survey instruments was required to assure the quality and prevent the loss of data.As part of the DQOs applied to laboratory processes, analysi s results were reported as actual calculated results. Results reported as less than Minimum Detectable Concentration (MDC) were not accepted for FSS. Sample report summaries included unique sample identification, analytical method, radionuclide, result, and uncertainty to two (2) standard deviations, laboratory data qualifiers, units, and the required and observed MDC.4. SURVEY DESIGN The level of effort associated with planning a survey is based on the complexity of the survey and nature of the hazards. Guidance for preparing FSS plans is provided in Procedure RPM 5.1-11, "Preparation of Final Status Survey Plans". The FSS plan uses an integrated sample design that combines scanning surveys and sampling which can be either random or biased.The DQO process determined that Cs-137, Co-60 and Sr-90 would be the radionuclides of concern in Survey Unit 9312-0004 (refer to Section 3). The characterization survey did not include any other additional HTD radionuclides of concern for this survey unit. As Sr-90 concentrations were determined by direct analysis, surrogate DCGLs were not required as part of the survey design for this survey unit via screening under LTP Section 5.4.7.2, "Gross Activity DCGLs". Other radionuclides that were positively identified in concentrations greater than the screening criteria during the performance of this FSS would be evaluated to ensure adequate survey design.As the survey unit is classified as a Class 1 surface soils area, and discrete, elevated areas of contamination was possible, the application of the Elevated Measurement Comparison (EMC) remained an option.The Sign Test was selected as the non-parametric statistical test. The use of the Sign Test did not require the selection or use of a background reference area, which simplified survey design and implementation.
This approach was conservative since it included background Cs-137 as part of the sample set.Revision 0 1 I I FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD The number of soil samples for FSS was determined in accordance with Procedure RPM 5.1-12, "Determination of the Number of Surface Samples for Final Status Survey." The Lower Bound of the Gray Region (LBGR) was set in accordance with Procedure RPM 5.1-11 to 0.73 to achieve a relative shift (A/cT) 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 Comimission (USNRC) for implementation of the MARS SIM in support of the decommissioning license termination rule (I1OCFR2O, Subpart E). The result of the COMPASS computer run showed adequate power for the survey design. The survey design specified fifteen (15) surface soil samples for non-parametric statistical testing. Based upon a review of the historical information and Characterization Survey data, the acquisition of additional judgmental surface soil samples from within this survey unit was deemed unnecessary.
The grid pattern and locations of the soil samples were determined using Visual Sample Plan (VSP) in accordance with Procedure RPM 5.1-14, "Identifying, and Marking Surface Sample Locations for Final Status Survey." Visual Sample Plan was created by Pacific Northwest National Laboratory (PNNL) for the United States Department of Energy. A systematic triangular grid pattern with a random starting point was selected for sample design, which is appropriate for a Class 1 area.Sample locations were identified using AutoCAD-LT, a commercially available plotting software package with coordinates consistent with the Connecticut State Plane System. These coordinates were integrated with a GPS to locate sample locations in the field. Sample Measurement Locations for the design are listed with the GPS coordinates in Table 4.9312-0004-OOIF 236829.64 668622.57 9312-0004-002F 236829.64 668658.88 9312-0004-003F 236798.19 668604.41 9312-0004-004F 236798.19 668640.72 93 12-0004-005F 236766.74 668549.94 9312-0004-006F 236766.74 668586.25 931 2-0004-007F 236766.74 668622.57 9312-0004-008F 236735.29 668531.78 Revision 0 1 12 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 931 2-0004-009F 236735.29 668568.10 9312-0004-OIOF 236703.84 668513.62 9312-0004-01IIF 236703.84
- 668549.94 9312-0004-012F 236672.39 668495.47 9312-0004-013F 236672.39 668531.78 9312-0004-01 4F 236640.94 668477.31 9312-0004-015F 236640.94 668513.62 Procedure RPM 5.1-11 specifies that 5% of the samples are required to be selected for HTD analysis.
Two (2) soil samples, or about 10% of the number of samples that would be used for non-parametric statistical testing were randomly selected for HTD radionuclide analysis using the Microsoft Excel "RANDBETWEEN" function.
Each sample was sent off-site for a full suite analysis of the HTD radionuclides specified in the LTP, Table 2-12, "Radionuclides Potentially Present at Haddam Neck Plant" and as provided in Table 3.The LTP requires a minimum of 5% of the samples taken for non-parametric statistical testing be selected for QC evaluation.
The implementation of quality control measures as referenced by Procedure RPM 5.1-24, "Split Sample Assessment for Final Status Survey," included the collection of one (1) soil sample for "split sample" analysis by the off-site laboratory.
This location was selected randomly using the Microsoft Excel "RANDBETWEEN" fuinction.
The LIP specifies a required scanning coverage of 100% for outdoor Class 1 areas.For this Class I survey unit, the "Investigation Level" for area scanning and soil sample measurement results are those levels specified in LTP, Table 5-8. Table 5 provides a synopsis of the survey design.Revision 0 1 13 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD Survey Unit Land Area 1,586 M 2 Based on AutoCAD-LT Type 1 and Type 2 errors were 15 0.05, sigma was 0. 14 pCi/g, the Number of Measurements LBGR was set at 0.73 to achieve a (15 systematic grid) Relative Shift in the range of 1 and 3 Grid Spacing 11.18 mn Based on triangular grid Opertioal CGL4.75 pCi/g Cs-137 Administratively set to achieve Opeatona DGL2.29 pCi/g Co-60 fifteen (15) mremlyr TEDE (1)4.75p~ig Cs137 The Operational DCGL meets the Soil Investigation Level 47pigCs17 LTP criteria for a Class I survey 2.29 pCi/g Co-60 unit Scan Survey Area Approximately The LTP requires 100% area Coverage 100% of the area coverage for Class I survey units An instrument response greater Based upon a Minimum Detectable than the Scan Count Rate (MD CR) of 2,020 cpm Scan Investigation Level MDC(DCGLEMC) and a corresponding MDC,,,aJ, of of 2,859 cpm plus 13.92 pCi/g Cs-137 and 3.23 pCi/g ambient Co-60 background (1) The allowable dose for soil in this survey unit is fifteen (15) mremlyr TEDE as the bounding dose from existing and future groundwater has been established based on field data (reference CY memo ISC 06-024)5. SURVEY IMPLEMENTATION Final status survey field activities were conducted under Work Plan and Inspection Record (WP&IR) 2006-0047.
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 informnation pertaining to the FSS.A single scan area was established that constituted approximately 100% of the surface area of Survey Unit 93 12-0004. Grid lines, one (1) meter wide, were painted on the ground of the scan area. A background survey was performed around the survey unit and it was determined that, using an Eberline E-600 with a SPA-3 sodium iodide detector, background ranged from 7,820 counts per minute (cpm) up to 12,000 cpm.Revision 0 1 14 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD The scan area was established and scanned for elevated readings (see Attachment 2 for all scan results).
Scanning was performed with an Eberline E-600 using a SPA-3 sodium iodide detector.
The E-600 was operated in the rate-meter mode and used with audio response.
The probe was positioned as close to the ground as possible and was moved at a scan speed of about 0.5 meters per second. Approximately 100% of the survey unit was scanned.Measurement locations were identified in North American Datum (NAD) 1927 coordinates using GPS coordinates; sample locations were identified and marked with a surveyor's flag or paint for identification.
At each sample location, a one (1) meter radius circle was established around the sample flag or paint mark was scanned for elevated radiation levels.Fifteen (15) surface soil samples were collected and packaged in accordance with Haddam Neck Plant (HNP) Procedure RPM 5.1-3, "Collection of Sample Media for Final Status Survey" and FSS design. Samples were controlled, transported, stored, and transferred to the off-site laboratory using Chain-of-Custody (COC) protocol in accordance with Procedure RPM 5.1-5, "Chain of Custody for Final Status Survey Samples." Two (2) samples (93 12-0004-007F and 9312-0004-012F) were randomly selected for HTD radionuclide analysis.The implementation of survey specific quality control measures included the collection of one (1) sample (93 12-0004-005F) for "split sample" analysis.6. SURVEY RESULTS All field survey activities were conducted between January 30, 2007 and February 13, 2007.The sample locations identified in the FSS plan were scanned over approximately a one (1) meter radius for elevated radiation levels. Table 6 provides an overview of the scan results for sample measurement locations.
Scan results are provided in Attachment 2.Revision 0 1 15 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 1 9.99 12.54 NO 2 11.20 13.16 NO 3 9.24 11.92 NO 4 10.50 11.46 NO 5 9.80 11.07 NO 6 8.14 11.01 NO 7 8.24 11.23 NO 8 9.34 11.29 NO 9 9.81 12.55 NO 10 8.35 11.69 NO 11 10.50 11.78 NO 12 8.24 11.27 NO 13 9.16 11.43 NO 14 10.20 13.06 NO 15 8.57 11.04 NO (1) The action level is based on a measurement in accordance with the FSS plan (MDC(DCGLEMc) of 2,859 cpm plus ambient background)
The scan area, that comprised approximately 100% of the total surface area for the survey unit, was scanned for elevated radiation levels. The area was scanned in accordance with the FSS plan on January 30, 2007.Twenty-six (26) scan strips were established in this survey unit. One elevated measurement location was identified during scanning.
Table 7 provides an overview of the scan area survey. Scan results are provided in Attachment 2.Revision 0 1 16 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 1 thru 10 1 9.85 1 13.26 1None None IlIthru 20 17.10 12.66 9312-04-ER-00-19-1 9312-0004-0161 21lthru 26 12.50 14.86 None None (1) The action level is based on a measurement in accordance with the FSS plan (MDC(DCGLEMc) f 2,859 cpm plus ambient background)
(2) ER is an abbreviation associated with the barcodes used in the field where ER stands for Elevated Reading.The off-site laboratory employed for the radiological analyses of samples was General Engineering Laboratories, LLC. The laboratory analyzed the fifteen (15)samples collected for non-parametric statistical testing, the associated field splits and the single investigation sample using gamma spectroscopy.
Gamma spectroscopy analysis was performed to the required MDCs. Gamma spectroscopy results identified some radionuclides meeting the accepted criteria for detection (i.e., a result greater than two (2) standard deviations uncertainty).
However, Cs-137 and Co-60 were the only two gamma-emitting radionuclides reported in any appreciable concentration.
Cs-137 was identified in ten (10) and Co-60 was identified in three (3) of the fifteen (15) samples collected for non-parametric statistical testing. The mean of the gamma spectroscopic analysis results for the sample population indicated that Cs-137 was present at levels slightly higher than expected environmental levels for Cs-137 within the vicinity of the HNP as presented in the Health Physics TSD BCY-HP-0063.
A summary of the fifteen (15) samples collected for non-parametric statistical testing results is provided in Table 8.931 2-0004-OOIF 4.93E-02 1 .03E-02 931 2-0004-002F 8.7 1 E-02 -3.1 4E-05 931 2-0004-003F 1 .55E-0 1 2.69E-02 9312-0004-004F 1.09E-01 1.48E-02 Revision 0 1 17 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 931 2-0004-005F 6.04E-01 9.47E-02 931 2-0004-006F
- 1. lOB-O1 3.6 1 E-02 9312-0004-007F 3.42E-02 3.16E-02 9312-0004-008F 1.99E-01 1.26E-02 9312-0004-009F 4.87E-02 3.24E-02 9312-0004-01IOF
-7.84E-03
-1 .23E-02 9312-0004-0OIIF 2.11lE-03
-8.59E-03 9312-0004-01 2F 8.06E-03 -4.29E-04 9312-0004-013F 1.41E-02 6.56E-03 9312-0004-01 4F 2.28E-0 1 0.OOE+/-00 9312-0004-015SF 2.30E-02 -1.28E-02 In addition to Cs-137 and Co-60, Sr-90 was also identified during the DQO process as a radionuclide of concern. Subsequently, all samples were subjected to analysis by gas proportional counting for Sr-90. All analyses met the required minimum MDC.Sr-90 was positively identified (i.e., a result greater than two (2) standard deviations uncertainty) in nine (9) of the fifteen (15) samples collected for non-parametric statistical testing. The results of the Sr-90 analysis for the statistical sample population are provided below in Table 9.9312-0004-OOIF 2.60E-02 93 12-0004-002F 5.95E-02 931 2-0004-003 F 3.3 8E-02 931 2-0004-004F 5.97E-02 93 12-0004-005F 2.99E-02 931 2-0004-006F 7.7 1 E-03 Revision 0 1 18 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 9312-0004-007F 1 .57E-02 931 2-0004-008F
- 3. 1 OE-02 93 12-0004-009F 6.24E-02 93 12-0004-OIOF 5.89E-02 9312-0004-01IIF 6.3 1lE-02 93 12-0004-012F 3.05E-03 9312-0004-013F 1.83E-02 9312-0004-014F
-3.31E-03 93 12-0004-015F 5.67E-03 In addition to Sr-90, the off-site laboratory also processed, as required by the sample plan, two (2) samples for the full suite of HTD radionuclides as specified in LTP, Table 2-12, "Radionuclides Potentially Present at Haddam Neck Plant" and as provided in Table 3. The requested analyses included alpha spectroscopy, gas proportional counting, and liquid scintillation depending on the radionuclide and the measurement method. All analyses performed met the required minimum MDC. No additional HTD radionuclides were positively identified (i.e., a result greater than two (2) standard deviations uncertainty).
The "sum-of-fractions" or "unity rule" is the mathematical test used to evaluate compliance with radiological criteria for license termnination when more than one radionuclide has been determined to be potentially present. The combination of the fractions of each detected radionuclide against their respective Operational DCGL must be less than or equal to one (1). The unity rule is: Equation 3 C, + C 2 C,, <1 DCGL, DCGL 2 DCGL,, Where: en = concentration of radionuclide n and DCGLn = DCGL of radionuclide n.The results of the unity rule calculation for the radionuclides of concern in the statistical sample population for Survey Unit 9312-0004 are provided in Table 10 below.Revision 0 1 19 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 9312-0004-OOIF 0.010 0.028 0.038 9312-0004-002F 0.018 -0.064 0.082 9312-0004-003F 0.033 0.012 0.036 0.081 9312-0004-004F 0.023 -0.064 0.087 9312-0004-005F 0.127 0.041 0.032 0.201 9312-0004-006F 0.023 0.016 -0.039 931 2-0004-007F 0.007 -- 0.007 9312-0004-008F 0.042 -0.033 0.075 9312-0004-009F
--0.067 0.067 9312-0004-OIOF
--0.063 0.063 9312-0004-01IIF
--0.068 0.068 9312-0004-012F
--9312-0004-013F
--- 0.000 9312-0004-014F 0.048 -- 0.048 9312-0004-015SF 0.005 -0.005 (1) "-" indicate that the radionuclide was not positively detected in the sample (2) The Operational DCGL from Table 2 is 4.75 pCi/g for Cs-137, 2.29 pCilg for Co-60 and 0.93 pCi/g for Sr-90 to achieve fifteen (15) mrem/yr TEDE respectively.
- 7. QUALITY CONTROL The off-site laboratory processed the split samples and performed gamma spectroscopy analysis.
One sample location was selected for analysis, which exceeds the 5% minimum required by the LTP. The data were evaluated using USNRC acceptance criteria specified in Inspection Procedure 84750 as detailed in HNP Procedure RPM 5.1-24, "Split Sample Assessment for Final Status Survey ".Evaluation using the reported results for Cs-137 resulted in acceptable agreement between the field-split results at this location.The sample analysis vendor, General Engineering Laboratories, LLC, maintains quality control and quality assurance plans as part of normal operation.
Refer to Attachments 3 and 4 for data and data quality analysis results Revision 0 2 20 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 8. INVESTIGATIONS AND RESULTS One (1) investigative surface soil sample was collected from a scan area exhibiting elevated scan readings.
This soil sample was analyzed for Cs-137, Co-60 and Sr-90 in accordance with the DQOs used during the survey design. The Investigative Sample designation is listed with the GPS coordinates in Table 11.Table I1I- Investigativ Samiple D)esignation wNith Associated P.Coordinates.
...-D~esigiilition
~ N>orthin Lasting 9312-0004-016-I 236786.36 668570.69 During the process of preparing this sample for transfer to the off-site laboratory in accordance with Procedure RPM 5.1-5, "Chain of Custody for Final Status Survey Samples", surveys performed discovered a small discrete particle of elevated activity within the soil sample matrix. The particle was segregated and removed from the soil matrix and analyzed using gamma spectroscopy by the on-site laboratory.
Results identified Co-60 with an indicated activity of 0.128 [tCi. Soil sample 9312-0004-016-I, minus the segregated Co-60 particle, was transferred to the off-site laboratory for analysis.
The sample is denoted as shown in Table 7, with the sample results shown in Table 12 below.Table 12 -Investigation Sample Resuilts'(s17Co-60 Sr90 UnitNY Fractio Saimple Niumber p)CFg pilg, 9312-0004-016-I 2.38E-01 3.60E+/-0 37E-02 1.663 (1) The Operational DCGL from Table 2 is 4.75 pCi/g for Cs-137, 2.29 pCi/g for Co-60 and 0.93 pCi/g for Sr-90 to achieve fifteen (15) mrem/yr TEDE respectively.
Cs-137, Co-60 and Sr-90 were all positively identified.
The sample contained sufficient concentrations of Co-60 to exceed the Operational DCGL of 2.29 pCi/g and sufficient concentrations of Cs-137, Co-60 and Sr-90 to exceed the "unity rule" parameter of "I". It was subsequently determined that five (5) additional surface soil samples would be necessary to adequately bound the area of elevated activity identified by the results of the investigation sample. Bounding sample locations were idetiied in Addendum 1 to the Final Status Survey Plan.An additional soil sample (sample number 93 12-0004-017-I) was taken at the same location as sample number 93 12-0004-016-I.
In addition, four (4) additional samples were taken at a distance of one (1) meter from the location of sample number 9312-0004-016-1, oriented relative to the compass points of north, east, south and west. The sample results and the results of the unity rule calculation for the radionuclides of concern in the bounding sample population are provided in Table 13 below.I Revision 0 2 21 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 9312-0004-017-I 1 .88E-01 2.19E-01-1.48E-02 0.135 9312;-0004-018-I
.1.96E-0 1 1 .62E-02 -4.54E.-03 0.041 9312-0004-019-1 7.62E-02 1 .25E-02 8.73E-03 0.022 9312-0004-020-I 8.09E-02 1.41E-02 -5 .53E-03 0.017 9312-0004-021-1I 1 .28E-0 1 0.OOE+/-00 j-2.46E-02 j 0.027 (1) The Operational DCGL from Table 2 is 4.75 pCilg for Cs-137, 2.29 pCi/g for Co-60 and 0.93 pCilg for Sr-90 to achieve fifteen (15) mremlyr TEDE respectively.
Cs-137 was positively identified in all and Co-60 was positively identified in two (2)of the five (5) additional bounding samples. Sr-90 was not positively identified in any of the bounding samples. The sample results indicated that the activity concentration of individual radionuclides were less than their respective Operational DCGL and the sum of all radionuclide fractions in each sample was less than the unity value of one (1). Subsequently, the area of elevated activity was deemed to be adequately bounded.The Elevated Measurement Comparison (EMC) protocol was applied to the area of elevated activity in accordance with LTP Section 5.8.3 and 5.4.7.4. The value used for the area factor for each area was determined from the area bounded by the adjacent samples at or below the DCGLOP. Due to the fact that the bounding samples were taken at a distance of one (1) meter from the area identified as elevated, the elevated area size was determined to be two (2) square meters.An Area Factor corresponding to the size of the elevated area was selected from Table 5-5, Area Factor for the Resident Farmer Scenario, in Section 5.4.7.4 of the LTP.The Area Factor selected is provided in Table 14.Co-60 6.67 Sr-90 616.00 Cs-137 14.10 Revision 0 2 22 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD Using the Area Factors presented in Table 14 and the results of the soil samples, the following EMC calculation was deduced;Equation 4+/-5 -'lvtd , DCGLOP (AreaFactor)x DCGLOP+ C~~l~evatedi 9<+/-(AreaFactor)x DCGLOP where: 3 = average concentration outside of the elevated area Celevated 1,2, = average concentration inside elevated area "i" The average concentration of the area within the survey unit outside of the elevated areas (6) was calculated by taking the average radionuclide concentration from all surface soil samples and subtracting the radionuclide concentration average from the elevated area. This information is presented in Table 15.DCGLop (pCi/g)4.75E+/-00 2.29E+/-00 9.30E-01 Average Concentration (3) (pCi/g) 1. 17E-0 I 2.47E-02 2.1 5E-02 Avg. Fraction of the DCGL 0.025 0.011 0.023 Avg. Unity for Balance of Survey Unit 10.05 8 The average concentration of the elevated area is presented in Table 16.Table 16 -Averag', Cmiceitrtiii jl'adotce dfo Ele vated Area1/2<~ Cs~-137 ~>C6-6OW sr-90 Area Factor 14.10 6.67 616.00 DCGLEMC (PCi/g): 6.70E+/-0 I 1 .53E+/-0 1 5 .73E+/-02 Avg. Concentration in Elevated Area: 2.38E-01 3.60E+/-00 7.45E-02 Avg. Concentration
-36: 1.21lE-01 3.58E+/-00 5.30E-02 Avg. Fraction of DCGL: 0.002 1 0.234 1 0.000 Avg. Unity for Elevated Area: 0.236 The sum of the average unity result for the elevated areas and the balance of the survey unit equates to 0.294. As this value is less than one (1), this survey unit passes the unity EMC test.Revision 0 23 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD 9. REMEDIATION AND RESULTS Radiological remedial action as described by MARSSIM Section 5.4 was performed in this survey unit prior to FSS. All excavations were characterized and backfilled with "clean" fill prior to performing FSS. In the area where remediation occurred, the ground area is comprised of barren dirt with no vegetation, and the soils have been graded relatively flat to the corresponding elevation of the adjacent survey units.The results for Cs- 13 7 following remediation
'were well below the Operational DCGL provided in Table 3. Health Physics TSD BCY-HP-0078, "ALARA Evaluation of Soil Remediation in Support of Final Status Survey, " determined that remediation beyond that required to meet the release criteria is unnecessary and that the remaining residual radioactivity in soil was ALARA.10. CHANGES FROM THE FINAL STATUS SURVEY PLAN An addendum to the FSS plan was initiated on February 13, 2006 to implement the acquisition of additional soil samples necessary to adequately bound the area of elevated activity identified by the investigative sample result.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 1.The preliminary data review consisted of calculating basic statistical quantities (e.g., mean, median, standard deviation).
The mean and median values are well below the Operational DCGL. Also, the retrospective power curve shows that a sufficient number of samples were collected to achieve the desired power. Therefore, the survey unit meets the unrestricted release criteria with adequate power as required by the DQOs. The basic statistical quantities for the statistical sample population are provided below in Table 17.Revision 0 2 24 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD DCGL 0 ,P: 4.75E+/-00 2.29E+/-00 9.30E-01 Minimum Value: -7.84E-03
-1.28E-02
-3.3 1E-03 Maximum Value: 6.04E-01 9.47E-02 6.3 1 E-02 Mean: 1.11E-01 1.55E-02 3.14E-02 Median: 4.93E-02 1.03E-02 2.99E-02 Standard Deviation:
1 .55E-0 1 2.72E-02 2.39E-02 The range of the data, about four (4) standard deviations for all three radionuclides, was not a particularly large variation.
The difference between the mean and median was about 3% to 15% of the standard deviation which indicates some skewness in the data. The data was represented graphically through posting plots, a frequency plot, and a quantile plot. The frequency plot indicates a slight positive skewness as confirmed by the calculated skew of 2.58 for Cs-137, 1.83 for Co-60 and 0.15 for Sr-90.All data, assessments, and graphical representations are provided in Attachment 4.12. ANOMALIES A small discrete particle exhibiting elevated activity was removed from the soil matrix of investigative soil sample 9312-0004-016-I.
Analysis of the particle by the on-site laboratory indicated
- 0. 128 ýtCi of Co-60. The particle was segregated and properly disposed of as radioactive waste. Scan surveys of the area and subsequent bounding soil samples indicate that no additional discrete particles were present.13. CONCLUSION Survey Unit 9312-0004 has met the final DQOs of the FSS plan. The ALARA criteria for soils as specified in Chapter 4 of the LTP were achieved.An EMC calculation was performed for an area of elevated activity in accordance with LTP Section 5.8.3 and Equation 4 of this report. The results indicated that the area was less than unity. No further action is warranted.
See Tables 13 through 16 of this report for specific information with regard to the EMC calculation.
All identified radionuclides of concern were used for statistical testing to determine the adequacy of the survey unit for FSS.Revision 0 2 25 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD The sample data passed the Sign Test. The null hypothesis was rejected.
The Retrospective Power Curve generated using COMPASS shows adequate power was achieved.
The survey unit is properly designated as Class 1.The dose contribution from soil is 0.96 mremlyr TEDE based on the average concentration of the samples used for non-parametric statistical sampling.This survey area is affected by existing groundwater (reference CY memo ISC 06-024); therefore the dose contribution from existing groundwater is bounded at two (2) mrem/yr TEDE.This survey unit is considered impacted by future groundwater radioactive contamination, as there are underground foundations containing residual radioactive material within the groundwater saturated zone in the area (reference CY memo ISC 06-024). The dose contribution from future groundwater, the third dose component, is bounded by two (2) mrem/yr TEDE.The average total dose from residual radioactivity in this survey unit, including exposures from the three (3) components as described in Section 3, that is, residual radioactivity in soil, existing groundwater radioactivity, and future groundwater radioactivity from the burial of concrete foundations or footings from site buildings containing residual radioactivity will not exceed 4.96 mremlyr TEDE. Therefore, Survey Unit 9312-0004 is acceptable for unrestricted release.14. ATTACHMENTS 14.1 Attachment 1 -Figures 14.2 Attachment 2 -Scan Results 14.3 Attachment 3 -Laboratory Results 14.4 Attachment 4 -DQA Results Revision 0 2 26 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD ATTACHMENT 1 (FIGURES)Revision 0 LAM-WdLazd 0 i '(0 M MAW7CN7~au.W.ýO Connacdtcut Yankcc Atomic Power Company Survey Unit 9312-000 U 9312-0009-7UU, 0001 9$4A2-0004 O0P4 9312-0002 9312-0005 0003 c 016 & ý9313-000q 019 g*D020"#2'1 0006 107 D005 9312-0001 0009 0008 0011 0 05 30 NOWI 0010 9312-0006 001.4 0¶12-6014-001i6 7-1 Figure2 Connectcut Yankee Atfomic Power Company Sample Location Map fir Survey Unit 9312-0004 I Date. Mamh 2007 I Reviaion 0 I_____ U I 9312-0009-0.238 & .9313-0000 UU.qp/-1 00.049 2-0004 00.155 4.076 O O.;0.110)Of 0O7 9312-000;-9-312-0005 c W~4/ý9312-0001 J./.604 00.049 O = Sin6 Lomkofo WaLhsh S- WIPLamob a O -hmbLjoLw 0 15 30 00.199 OOL 00 O-O.00 9312-0006 o00-0#o'~09&c~&22&o0.023-T I i. -"I.1 Fig=re3 Connectcut Yankee Atomic Powar Company Surmy Unit 9312-0004 Fina Status Survey Posting Plot for Cs-137 I DkAb March2007 I Revision.
0
________ U.-- I 9312-0009--
3.600 &0. 2f9 9313-000f0 (Uw. Wi V J c1 0.01 2-0004 oO.027 0.013 ck- 0. 014 9-.40 00.036 DelIý9312-000;9-312-0005 0 2 A.095 o0.032 (93112-.0001 oO. 013 0-0.0 1 O -Siwb LomoAwfo I5 30 cNOWm o-0.0 12 9312-0006 cfL0Eý7 c"M0 A Figure 4 Connectcut Yankee Atomic Power Company Survey Unit 9312-00)04 Finl Status Survey Postng Plot for Co-60 i Date. Mamh 2007 I Reviiiow.
0 I 1- nI 9312-0009--(Al. WMI 1~I-8mw~bLm~fr (DO. 026 0$42-0004 o / 6 9312-000;00.034 ,9312-0005 000-0S 9313-O0000
).009*D-0.006 1.025 00.008 04 Il (0-SwThc=kwy-WEtLmd iJ.030 I oO.062 9312-0001 cO. 031 cO.059 cf400 DO.06J 9312-0006 a~m maWw 4i.00 (OtAq06 6c0OOS A -S I -h.5 I Figum 5 Chaonwctct Yaakee Atomic Pop=r Company Sunve Unit 9312-000)4 Final Status Survey Potig gPlot for Sr-o I Date: Mambh2007 I Revigiow 0 Survey Unit 9312-0004 Survey Location 931 2-04-BL-00-01
-0 931 2-04-SL-00-01
-0 931 2-04-B L-00-02-0 931 2-04-S L-0 0-02-0 931 2-04-BL-00-03-0 931 2-04-SL-O0-03-0 931 2-04-BL-00-04-0 931 2-04-SL-00-04-0 931 2-04-BL-00-05-0 931 2-04-SL-00-05-0 931 2-04-BL-00-06-0 931 2-04-SL-00-06-0 931 2-04-BL-00-07-0 931 2-04-SL-00-07-0 931 2-04-BL-00-08-0 931 2-04-SL-00-08-0 9312-04-B L-00-09-0 9312-04-S L-00-09-0 9312-04-BL-00-1 0-0 931 2-04-SL-00-1 0-0 9312-04-BL-00-1 1-0 9312-04-SL-00-1 1 -0 931 2-04-BL-00-1 2-0 931 2-04-SL-00-1 2-0 931 2-04-BL-00-1 3-0 931 2-04-SL-00-1 3-0 931 2-04-BL-00-1 4-0 931 2-04-SL-00-1 4-0 9312-04-BL-00-1 5-0 9312-04-SL-00-1 5-0 Scan Survey Results Sample Location Scans Log Date 1/30/2007 1/30/2007 Log Time 13:22:00 13:23:00 Reading 9.68E+03 9.99E+03 Alarm >Alarm Level Level 1 .25E+04 E-600 S/N 1117 1117 Probe SIN 1008 1008 1/30/2007 13:24:00 1.03E+04 1/30/2007 13:25:00 1.12E+04 1/30/2007 13:26:00 9.06E+03 1/30/2007 13:27:00 9.24E+03 1/30/2007 13:28:00 8.60E+03 1/30/2007 13:28:00 1.05E+04 1/30/2007 13:31:00 8.21 E+03 1/30/2007 13:31:00 9.80E+03 1/30/2007 13:33:00 8.15E+03 1/30/2007 13:34:00 8.14E+03 1/30/2007 13:34:00 8.37E+03 1/30/2007 13:36:00 8.24E+03 1/30/2007 13:37:00 8.43E+03 1/30/2007 13:38:00 9.34E+03 1/30/2007 13:40:00 9.69E+03 1/30/2007 13:40:00 9.81 E+03 1 .32E+04 1.19E+04 1 .15E+04 1.11E+04 1. 1OE+04 1. 12E+04 1.13E+04 1 .25E+04 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1/30/2007 13:45:00 8.83E+03 1/30/2007 13:46:00 8.35E+03 1. 17E+04 1/30/2007 13:47:00 8.92E+03 1/30/2007 13:48:00 1.05E+04 1.18E+04 1/30/2007 13:49:00 8.41 E+03 1/30/2007 13:50:00 8.24E+03 1.13E+04 1/30/2007 13:52:00 8.57E+03 1/30/2007 13:52:00 9.16E+03 1.14E+04 1/30/2007 13:53:00 1.02E+04 1/30/2007 13:54:00 1.02E+04 1.31 E+04 1/30/2007 13:55:00 8.18E+03 1/30/2007 13:55:00 8.57E+03 1.10E+04 3/15/2007 31152007Page I of 1 Survey Unit 9312-0004 Survey Location 931 2-04-BC-O0-Dl -O 931 2-04-SC-O0-Ol -o 931 2-04-BC-00-02-0 9312-04-SC-00-02-0 931 2-04-BC-O0-03-D 9.31 2-04-SC-00-03-0 931 2-04-BC-0O-04-O 931 2-04-SC-0O-04-O 931 2-04-BC-0O-05-O 931 2-04-SC-00-05-O 931 2-04-BC-OD-06-O 931 2-04-SC-OO-06-O 931 2-04-BC-0O-07-O 931 2-04-SC-OO-07-O 931 2-04-BC-0O-08-O 931 2-04-S C-OO-08-0 931 2-04-BC-00-09-0 931 2-04-SC-D0-09-D 931 2-04-BC-DO-i 0-0 931 2-04-SC-DO-i 0-0 931 2-04-BC-DO-i 11-0 931 2-04-SC 11-0 931 2-04-BC-DO-i 2-0 9312-04-SC-DO-i 2-0 9312-04-BC-DO-i 3-0 9312-04-SC-DO-i 3-0 9312-04-BC-DO-i 4-0 9312-04-SC-DO-i 4-0 9312-04-BC-DO-i 5-0 9312-04-SC-DO-i 5-0 9312-04-BC-DO-i 6-0 9312-04-SC-DO-i 6-0 Scan Survey Results Scan Strip Scans Log Date Log Time Reading Alarm >Alarm E-600 SIN Probe SIN Level Level 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 1/30/2007 9:40:00 9:46:00 9:47:00 9:51 :00 9:52:00 9:57:00 9:58:00 10:04:00 10:05:00 10:09:00 10:10:00 10:14:00 10:15:00 10:18:00 10:19:00 10:22:00 10:23:00 10:26:00 10:29:00 10:34:00 9:39:00 9:46:00 9:46:00 9:52:00 9:54:00 10:00:00 10:00:00 10:04:00 10:06:00 10:10:00 10:11:00 10:15:00 9.38E+03 9.27E+03 8.93E+03 8. 54E+03 9.89Et03 9.78E+03 9.05E+03 9.26E+03 9.06E+03 9.14E+03 1 .04E+04 9.58E+03 9.15E+03 9.85E+03 9.56E+03 8.98E+03 9.04E+03 8.92E+03 8.62E+'03 8.77E+03 9.80E+03 9.40E+03 9.35E+03 8.51 E+03 7.82E+03 9.47E+03 8.87E+03 8.56E+03 8.62E+03 8.60E+03 8.52E+03 9.18E+03 1 .22E+04 1 .18E+04 1 .27E+04 1 .19E+04 1.19E+04 1 .33E+04 1 .20E+04 1 .24E+04 1.19E+04 1.15E+04 1.27E+04 1.22E+04 1 .07E+04 1.17E+04 1.15E+04 1.14E+04 1111 1111 1111 1111 1111 1111 1111 1111 1111 1111 1111 1111 1004 1004 1004 1004 1004 1004;1004 1004 1004 1004 1004 1004 1004 1004 1004 1004 1004 1004 1004 1004 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 3/15/2007 31152007Page 1 of 2 Survey Unit 9312-0004 931 2-04-BC-00-l 7-0 9312-04-30-00-1 7-0 931 2-04-BC-00-1 8-0 9312-04-30-00-1 8-0 931 2-04-BC-00-1 9-0 9512-04-30-00-1 9-0 931 2-04-ER-00-1 9-1 931 2-04-BC-00-20-0 9312-04-30-00-20-0 931 2-04-BC-00-21
-0 9312-04-30-00-21
-0 931 2-04-BC-00-22-0 9312-04-30-00-22-0 931 2-04-BC-00-23-0*
9312-04-30-00-23-0 931 2-04-BC-00-24-0 9312-04-30-00-24-0 931 2-04-BC-00-25-0 9312-04-30-00-25-0 931 2-04-BC-00-26-0 9312-04-30-00-26-0 Scan Survey Results Scan Strip Scans 1/30/2007 10:17:00 9.19E+03 1/30/2007 10:22:00 9.68E+03 1/30/2007 10:23:00 8.64E+03 1/30/2007 10:29:00 8.54E+03 1/30/2007 1/30/2007 1/30/2007 10:31 :00 10:44:00 13:20:00 8.69E+03 1.02E+04 1.71 E+04 1/30/2007 10:48:00 9.47E+03 1/30/2007 10:49:00 8.86E+03 1/30/2007 10:49:00 9.45E+03 1/30/2007 10:50:00 1.01 E+04 1/30/2007 10:50:00 1.04E+04 1/30/2007 10:51:00 1.OOE+04 1/30/2007 10:51:00 1.01 E+04 1/30/2007 10:53:00 1.12E+04 1/30/2007 10:53:00 1.17E+04 1/30/2007 10:54:00 1.15E+04 1/30/2007 10:54:00 1.13E+04 1/30/2007 10:55:00 1.25E+04 1/30/2007 10:56:00 1.20E+04 1/30/2007 10:57:00 1.13E+04 1.20E+04 1.15E+04 1.15E+04 1.15E+04 1 .23E+04 1.23E+04 1 .33E+04 1 .30E+04 1 .46E+04 1 .42E+04 1 .49E+04+1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1117 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 1008 3/15/2007 31152007Page 2 of 2 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD ATTACHMENT 3 (LABORATORY DATA)Revision 0 General Narrative I General Narrative for Connecticut Yankee Atomic Power Co.Work Order: 180060 SDG: MSR#07-0063 February 06, 2007 Laborato~ry Identification:
GEL Laboratories LLC 2040 Savage Road Charleston, South Carolina 29407 (843) 556-8171 Summarcy Sample receipt The samples arrived at GEL Laboratories LLC, Charleston, South Carolina on February 02, 2007 for analysis.Shipping container temperatures were checked, documented, and within specifications.
The samples were delivered with proper chain of custody documentation and signatures.
All sample containers arrived without any visible signs of tampering or breakage.Sample Identification The laboratory received the following samples: Laboratory Identification 180060001 180060002 180060003 180060004 180060005 180060006 180060007 180060008 180060009 180060010 180060011 180060012 180060013 180060014 180060015 180060016 180060017 Sample Description 9312-0004-001 F 931 2-0004-002F 931 2-0004-003F 931 2-0004-004F 931 2-0004-005F 931 2-0004-005FS 931 2-0004-006F 931 2-0004-007F 931 2-0004-008F 931 2-0004-009F 9312-0004-01 OF 9312-0004-01 IF 9312-0004-01 2F 9312-0004-01 3F 9312-0004-01 4F 9312-0004-015SF 9312-0004-016-1 Items of Note There are no items to note.Case Narrative GEL Laboratories LLc P0 Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 2 www.gol.com Sample analyses were conducted using methodology as outlined in GEL Laboratories, LLC (GEL) Standard Operating Procedures.
Any technical or administrative problems during analysis, data review, and reduction are contained in the analytical case narratives in the enclosed data package.Analytical Request Fifteen soil samples were analyzed for FSSGAM and Strontium-90.
Two soil samples were analyzed for FSSALL.Data Package-The enclosed data package contains the following sections:
General Narrative, Chain of Custody and Supporting Documentation, Data Review Qualifier Definitions, and data from the following fractions:
Radiochemistry.
I certify that this data package is in compliance with the SOW, both technically and.for completeness, for other than the conditions detailed above. Release of the data contained in this hard copy data package has been authorized by the Laboratory Manager or a designee, as verified by the following signature.
Cheryl Jones Project Manager GEL Laboratories LLc GELLaortoie u.c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston.
SC 29407 P 843.555.8171 F 843.755.1175 3 www.gaI.com List of current GEL Certifications as of 06 February 2007 State Certification Alaska UST-062 Arizona AZ0668 Arkansas 88-0651 CLIA 42DO904046 California 01151CA Colorado GenEngLabs Connecticut PH-01 69 Dept. of Navy NFESC 413 EPA WG-15J Florida/NELAP E87 156 Georgia E87 156 (FLINELAP)
Hawaii N/A Idaho N/A Illinois 200029 Indiana C-SC-01 Kansas E-10332 Kentucky 90129 Louisiana 03046 Maryland 270 Massachusetts M-SCOI 2 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 102934 Texas TX213-2006A Texas NELAP T104704235-06-TX U.S. Dept. of Agriculture 1S-52597 US Army Corps of Engineer N/A Utah ______1 8037697376 GEL Vermont 1VT87156 Virginia 00151f Washington 4
Chain of Custody and Supporting Documentation
-5 Health Physics Procedure Healh Pysis PoceureGPP-GGGR-R5 104-003-At~tac~hment B-CY-00 1 Major Connecticut Yankee Atomic Power Company Chain of Custody Form No 2007- 00034 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:
[L] 30 D. [- 15 D. Z 7 D.Other: ___Sample. Designation Date Time 1 C41441-omment, Preservation Lab Sample. ID 9312-0004-OOIF 1/30/07 1322 TS G BP X _____ __ __ __ _________9312-0004-002F 1/30/07 1325 TS G BP X __ ___________
_______931 2-0004-003F 1/30/07 1327 TS G BP X _____ __ _________9312-0004-004F 1/30/07 1329 TS G BP X ____________________
9312-0004-005F 1/30/07 1332 TS G BP X __ ____ ____ _______9312-0004-005FS 1/30/07 1332 TS G BP X __ ___________
9312-0004-006F 1/30/07 1335 TS G BP X ________ _________________
9312-0004-007F 1/30/07 1336 TS G BP X __________
9312-0004-008F 1/30/07 1337 TS G BP X ___ __________________
_______9312-0004-009F 1/30/07 1341 TS G BP X __ ___________
9312-0004-OIOF 1/30/07 1343 TS G BP X _________________________
NOTES: PO #: 002332 MSR #: 01 -Wo4(.,I LTP QA ElRadwaste QA LINon QA Samples Shipped Via: Internal C ntainer M Fed-Ex Temp.: ~Deg. C ElUP El Hand Custody,$eed?
._U Relinqushed Da e im rcDate/TimeCutd c?L= IRI 7 #sý' El Other 3) Relinquished By Date/Time
- 4) Receive~d Da~te'/Time Bill__of__Lading
__# Y N 5) Relinquished By Date/Time
- 6) Received By Date/Time Health Physics Procedure Healh Pysis PoceureGPP-GGGR-R5,104-00.3 -Attaclhment B-CY-00 1 Major Connecticut Yankee Atomic Power Company Chain of Custody Form No. 2007-00032 362 Injun Hollow Road, East Hampton, CT 06424 860-267-2556
____ _________________
_____Prjet am: adamNek ecmmssonngAnalyses Requested Lab Use Only Contct ame Phne:Comments:
JcMcaty860-267-3924 Media Sample contai~ner Jak c~rtyCode Type Size-Analytical Lab (Name, City, State): Code &Type: Geneal Eginerin LabratoiesCode 2040 Savage Road Charleston, SC 29407 ATT: Cheryl Jones (843-556-8.171)
C Priority:
E] 30 D. LI15 D. 0 7 D.Other: 0____00_Samp~le Designation-Date Time lj comment, Preservation Lab Sample ID 9312-0004-01 IF 1/30/07 1348 TS G, BP X _________9312-0004-012F 1/30/07 1349 TS G BP X_____________
9312-0004-013F 1/30/07 1352 TS G BP X___ _________9312-0004-014F 1/30/07 1358 NTS G BP X________________
9312-0004-015F 1/30/07 1400 TS G BP X _________
_______NOTES: PO #: 002332 MSR #: (D -oo4-3 LTP QA LIRadwaste QA LINon QA Samples Shipped Via: Int ernal Container SFed Ex Temp..: ...,Deg .C Li] Hand Custody ýd?'1) Relinquished B Date/Tfime
- 2) Epce ved e Custody Seal Intact?y~~y~ ,~~- i m Other 3) Relinquished By Date/Time
- 4) Received Bý Date/Time
___________
Y N Bill of Lading #1 5) Relinquished By Date/Time
- 6) Received By Date/Time Health Physics Procedure Healh Pysis PoceureGPP-GGGR-R5.1 04-0.03-.Attach~ment B-CY-00 I Major Connecticut Yankee Atomic Power Company Chain, of Custody Form No 070033 362 Injun Hollow Road, East Hampton, CT 06424No2070 86.0-267-2556
____ ____________________
_________________
_____Project Name: Haddam Neck Decommissioning Analyses Requested ai 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) n Prorthe: Rl 30 D. [] 15 D. Z 7 D.Other CIO Sample Designation Date Time -Cmment, Preservation Lab Sample ID 9312-0004-016-1 1/30/07 1320 TS G BP X _____________________
NOTES: P0 #: 002332 MSR #: <D 7-co oVl. Z LTP QA LIRadwaste QA II] Non QA Samples Shipped Via: Internal Container SFed Ex Temp.: -Deg. C ElHand. CustodyS ed?jelinquished By Date/Time
- 2) R eivrdB Date/Time Custody Seal Intact.?3) Relinquished By Date/Time
- 4) Received By Bilo aig#Y N 5) Relinquished By Date/Time
- 6) Received By Date/Time INL;. 0,111'r-0
Subject:
RE: Samples From: "Rick E. Gaul~t' <.GaLl~t@CYAPCO.comn>
Date: Thu., I Feb 2007 12:53:S9 -0500)To: "Chervl Jonc.," <c.i @iel.corn>
CC.- "Clyde Newson" <Newson @ CYA.PCO.com>, "Jeffrey D. Whgner" <Wagner@CY.APCO.corn>,"Dale Randall" <ranclallI@cyapco.comn>, "John McCarthy" <McCarthy
@C YAPCO.com>., "Arthur L.Hammond" <H arnri-ond
@CYA PCO.comn>Yes Cheryl that is acceptable.
Thanks for the quick response.Rick--------Original Message ---From.: Cheryl Jones [ma~iito:.cj@gel.corn]
Sent: Thursday, Februiary 01, 2007 12:40 PM To: Rick E. Gault Cc: Clyde Newson; Jeffrey D. Wagner; Dale Randall; John McCarthy; Arthur L. Hammond
Subject:
Re: Samples Rick, Thank you for forwarding the COCs. Please confirm that it is acceptable for GEL to use the traced/untraced Tc-99 process for these samples, since they are on a 7d TAT request.Thanks, Cheryl Rick E. Gault wrote: Cheryl;We're sending 18 samples (17-under MSR 07-0063 and 1-under MSR 07-0065) to GEL. All of the, samples have a 7 day TAT request. See attached COCs for requested analyses.Rick Gault CYAPCO 860-267-3672 Cheryl A. Jones Project Manager/PM Team Leader GEL Laboratories, LLC 2040 Savage Road Charleston, SC (USA) 29407 Direct: 843.769.7388 main: 843.556.8171.x 4243 Fax: 843.766.1178 E-mail: ci@g'el .com Web: com'V e~rv The information contained in this message is confidential and is intended only for the use of the individual or firm of record. If you are not 2/1/2007 2:47 P1 5) the intended recipient.
and have received this message in eirror, you are asked not to copy or distribute any of the. pages that follow. Please notify the sender i mmedi a t iv by telephonie or- email i:f you hw;.e receivet-1 thi!s communication ini err or and destroy the contents that do )-riot pertain to your huririess with The GEL. Group, INC.2 of 2 2/1/2007 2:47 P1 1-0 Connecticu t Yankee Statement of Work for Analytical Lab Services*CY-ISC-SOW-O0l Figure 1. Sample Chec~k-in List Date/Time Received:
-Ic\Q 1 SDG#t 2'Work Order Number: 0 &Shipping Ccfhtainer ID :1_' S~~I. Custody Seals. odishipping container intact?..2. Custody Seals dated and signed?3. Chain-of-Custody record present?4. Cooler temperature6 C 5.. Vermiculite/packing materials
ýis: 6.- Number of samples in shipping container:.
- 7. Sample holding times exceeded?A 1, L_~&~5T~7- 006!ý100 3..fýhIain of Custody #-6-Yes [t No [1 I\P!Yes[ j..No [I Yes/"I No [.Wet [1Dry /V] W Yes lNo.8. Samples have:*_____hazard labels/Zcustody seals ...Xappropriate samnple labels 9. Samples arei..Zin good condition
-___eaking b---roken
___have air bubbles 10. Were any anomalies identified in sample receipt? Yes HNo1 PI escription of anomalies, (include sample numbers): 11 SAMPLE-RECEIPT
& REVIEW FORM TM oft only Client;:mN SDGARCOC/Work Order:;~O~
IDate Received:
PM(A) Reviey (ensure non-conforming Htems are resolved prior to signing): Received By: ___________________
Sample Receipt Criteria ZCommentslQualifiers (Requaired for Non-Coisforming Ite I~ ipn containers received Circle Applicable:
seals broken damaged container leaking container (describe) intact and sealed.?Samples requiring cold Circle Coolant I ice bags blue ice dry ice none other describe).2 preservation within (4 + /- 2 C)?lRecord preservation method'Chain oif custody documents 3 included with shipment?4 Sample containers intact and Circle Applicable:
seals broken dam container leaki ng container other (describe) sealed?5 ISamples, requiring chemical Sample ID's. contain~ers;Paff and observed pH: preservation at proper pH?6VOA vials free of headspace Sample 11)s an tainers affected:-(defined as < 6mm bubble)?Are Encore coiitainers present?7 (If yes, immediately deliver to_ VOA laboratory)
__________________
8 Samples received within holding I' n et fetd time?_______________________________
9 Sample ID's on COC match 11D's Sample ID's and containers affected: on bottles?__________________________
Date & time on COC match d eSample ID's affected: to& time on bottles? ____________________________
Number of containers ived Sample ID's affected: match number indica eon COC?COG form is pro .ny signed in Irlnuispet
-7ie sectionsno-aiocie otctteRdito Sft ropfr ute Sed azad Iforatin ~ ~ I*If > x2 area background is observed on samples identified as "non-A Radiological Classifica-tion?
--, I Kx;_ P #- tN-~---a 0ý1 , B PCB Regulated?
Shipped as DOT Hazardous C Material?
If yes, contact Waste /IManager or ESH Manager.p Regulated as a Foreign Soil? 2 -L1V -UV lazard Class Shipped: JN#: PM (or PMA) review of Hazard classification:
-~ initials 12 4yt,- Date:2- V-7-j:-
Data Review Qualifier Definitions 13 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> 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 aliquiot 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-%6difference 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 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 Z Paint Filter Test-Particulates passed through the filter, however no free liquids were observed.GEL Laboratories LLc PO Box 30712 Charleston, Sc 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.765.1178 www.golicom 14 RADIOLOGICAL ANALYSIS 15 Radiochemistry Case Narrative Connecticut Yankee Atomic Power Co. (YANK)Work Order 180060 Method/Analysis Information Product: Alphaspec Am241, Cm, Solid ALL FSS Analytical Method: Prep Method: DOE EML HASL-300, Am-05-RC Modified 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 607169 607082 607077 Sample ID 180060008 180060013 1201272522 1201272523 1201272524 1201272525 Client ID 931 2-0004-007F 93 12-0004-012F Method Blank (MB)180060008(931 2-0004-007F)
Sample Duplicate (DUP)1 80060008(9312-0004-007F)
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-01 I REV# 14.Calibration Information:
Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.
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: 180060008 (93 12-0004-007F).
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 The sample and the duplicate, 1201272523 (931 2-0004-007F) and 180060008 (931 2-0004-007F), did not meet the relative percent difference requirement for CM-243/244, however they do meet the relative error ratio requirement with a value of 1 .07.Qualifier information Manual qualifiers were not required.Method/Analysis Information 17 Product: Product:Aiphaspec Pu, Solid-ALL FSS Analytical Method: DOE EML HASL-300, Pu- I Il-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 607170 607082 607077 Sample ID 180060008 180060013 1201272526 1201272527 1201272528 1201272529 Client ID 931 2-0004-007F 9312-0004-01 2F Method Blank (MB)180060008(9312-0004-007F)
Sample Duplicate (DUP)180060008(931 2-0004-007F)
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-01 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.
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: 180060008 (9312-0004-007F).
QC Information All of the QC samples met the required acceptance limits.7L8 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: Product:Liquid Scint Pu241, Solid-ALL FSS DOE EML HASL-300, Pu-lII -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 607171 607082 607077 1-9 Sample ID Client 11D 180060008 931 2-0004-007F 180060013 9312-0004-012F 1201272530 Method Blank (MB)1201272531 180060008(931 2-0004-007F)
Sample Duplicate (DUP)1201272532 180060008(9312-0004-007F)
Matrix Spike (MS)1201272533 Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-035 REV# 8.Calibration Information:
Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration.
date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.
Quality Control (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: 180060008 (9312-0004-007F).
QC Information All of the QC samples met the required acceptance limits.Technical Information:
Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis Samples were recounted due to quench numbers being outside of the calibration range.Miscellaneous Information:
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from 20 referenced SOP or contractual documents.
A nonconformance report (NCR) was not generated for this SDG.Manual Integration No manual integrations were performned on data in this batch.Additional Comments Additional comments were not required for this sample set.Qualifier information Manual qualifiers were not required.Method/Analys~is Information Product: Analytical Method: Prep Method: Analytical Batch Number: Prep Batch Number: Sample ID 180060001 180060002 180060003 180060004 180060005 180060006 180060007 180060008 180060009 180060010 180060011 180060012 180060013 180060014 180060015 180060016 180060017 1201272698 1201272699 1201272700 Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived EML HASL 300, 4.5.2.3 Dry Soil] Prep 607292 607077 Client ID 9312-0004-001IF 931 2-0004-002F 931 2-0004-003F 931 2-0004-004F 931 2-0004-005 F 931 2-0004-005FS 931 2-0004-006F 931 2-0004-007F 931 2-0004-008F 931 2-0004-009F 9312-0004-01 OF 93 12-0004-01 IF 9312-0004-01 2F 9312-0004-01 3F 9312-0004-01 4F 9312-0004-015SF 9312-0004-016-1 Method Blank (MB)180060001(9312-0004-001 F) Sample Duplicate (DUP)Laboratory Control Sample (LCS)21 SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-013 REV# 13.Calibration Information:
Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.
Quality Control (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: 180060001 (9312-0004-001F).
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.22 O~ualifier information Qualifier U'U'U'U'Reason Data rejected due to high counting uncertainty.
Data rejected due to high peak-width.
Data rejected due to interference.
Data rejected due to low abundance.
Analyte Thallium-208 Cobalt-60 Man ganese-54 Actinium-228 Bismuth-2 12 Cesium- 134 Sample 1201272698 180060015 1201272699 180060008 180060008 180060001 180060004 180060007 180060009 180060010 180060011 180060013 180060014 180060015 180060016 180060017 1201272699 180060010 180060011 1201272698 Europiumn-154 Lead-214 Method/Analysis Information 23 Product: Product:GFPC, Sr9O, solid-ALL FSS Analytical Method: EPA 905.0 Modified Prep Method: Dry Soil Prep GL-RAD-A-021 Method: Analytical Batch Number: Prep Batch Number: Dry Soil Prep GL-RAD-A-021 Batch Number: Ash Soil Prep Dry Soil Prep 608308 607082 607077 Sample ID 180060001 180060002 180060003 180060004 180060005 180060006 180060007 180060008 180060009 180060010 180060011 180060012 180060013 180060014 180060015 180060016 180060017 1201275063 1201275064 1201275065 1201275066 Client ID 9312-0004-OOIF 931 2-0004-002F 931 2-0004-003F 931 2-0004-004F 931 2-0004-005F 931 2-0004-005FS 931 2-0004-006F 931 2-0004-007F 931 2-0004-008 F 931 2-0004-009F 9312-0004-01IOF 93 12-0004-01 IF 9312-0004-01 2F 9312-0004-013F 931 2-0004-014F 9312-0004-015SF 9312-0004-016-1 Method Blank (MB)180060001(9312-0004-001 F) Sample Duplicate (DUP)I 80060001(9312-0004-OO1F)
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-004 REV# 10.Calibration Information:
Calibration Information All initial and continuing calibration requirements have been met.Standards Information 24 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 (00) Information:
Blank Information The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 180060001 (9312-0004-001F).
QC Information All of the QC samples met the required acceptance limits.Technical Information:
Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis Samples 180060015 (9312-0004-014F) and 180060017 (9312-0004-016-1) were recounted due to high MDAs. Samples 1201275065 (9312-0004-001F) and 1201275066 (LCS) were recounted due to low/high recovery.
Samples were reprepped due to low lcs recovery and high relative percent difference.
There was also alpha interference in the samples that may have biased the results. The samples could not be cleaned up due to low carrier net weights.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.
The following NCR was generated for this SDG: NCR 405548 was generated due to RDL less than MDA and Failed Recovery for MS/PS. 1. Matrix spike 1201275065 did not meet the recovery requirement due to the analyst error. The analyst did not spike the sample. The batch is a reprep. 2. The matrix spike did not meet the required detection limit due to the sample not being spiked. 1. The matrix spike passed on the initial batch, but there was alpha interference that elevated the activities.
The second prep does not show any interference.
Project manager notified.
Reporting results. 2. Reporting results 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 Tc99, Solid-ALL FSS Analytical Method: Analytical Batch Number: Sample ID 180060008 180060013 1201272496 1201272497 1201272498 1201272499 DOE EML HASL-300, Tc-02-RC Modified 607151 Client ID 9312-0004-007F 9312-0004-01 2F Method Blank (MB)180060008(931 2-0004-007F)
Sample Duplicate (DUP)180060008(9312-0004-007F)
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-005 REV# 13.Calibration Information:
Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.
Onalitv 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: 180060008 (931 2-0004-007F).
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.Oualifier information Manual qualifiers were not required.Method/Analysis Information Product: Liquid Scint Fe55, Solid-ALL FSS Analytical Method: DOE RESL Fe-I1, 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 607148 607082 607077 Sample ID 180060008 180060013 1201272488 1201272489 1201272490 1201272491 Client ID 931 2-0004-007F 9312-0004-01 2F Method Blank (MB)180060008(931 2-0004-007F)
Sample Duplicate (DUP)180060008(9312-0004-007F)
Matrix Spike (MS)Laboratory Control Sample (LCS)27 SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-040 REV# 3.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: 180060008 (93 12-0004-007F).
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.28 Qualifier information Manual qualifiers were not required.Method/Analysis Information Product: Liquid Scint Ni63, Solid-ALL FSS Analytical Method: DOE RESL Ni-i1, Modified Prep Method: Ash Soil Prep Dry Soil Prep GL-RAD-A-021 Method: Dry Soil Prep Analytical Batch Number: 607147 Prep Batch Number: 607082 Dry Soil Prep GL-RAD-A-021 Batch Number: 607077 Sample ID 180060008 180060013 1201272484 1201272485 1201272486 1201272487 Client ID 931 2-0004-007F 9312-0004-01 2F Method Blank (MB)180060008(931 2-0004-007F)
Sample Duplicate (DUP)180060008(931 2-0004-007F)
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-022 REV# 8.Calibration Information:
Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.
Oualitv Control (0C) Information:
Blank Information The blank volume is representative of the sample volume in this batch.29 Designated QC The following sample was used for QC: 180060008 (93 12-0004-007F).
QC Information All of the QC samples met the required acceptance limits.Technical Information:
Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis None of the samples in this sample set required reprep or reanalysis.
Miscellaneous Information:
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.Qualifier information Manual qualifiers were not required.Method/Analysis Information Product: LSC, Tritium Dist, Solid -3 pCi/g Analytical Method: Analytical Batch Number: Sample ID 180060008 180060013 1201272492 1201272493 1201272494 1201272495 EPA 906.0 Modified 607149 Client ID 931 2-0004-007F 9312-0004-01 2F Method Blank (MB)180060008(931 2-0004-007F)
Sample Duplicate (DUP)180060008(931 2-0004-007F)
Matrix Spike (MS)Laboratory Control Sample (LCS)30 SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-002 REV# 13.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: 180060008 (93 12-0004-007F).
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.31-Qualifier information Manual qualifiers were not required.Method/Analysis Information Product: Liquid Scint C14, Solid All,FSS Analytical Method: Analytical Batch Number: Sample ID 180060008 180060013 1201272504 1201272505 1201272506 1201272507 EPA EERF C-01 Modified 607153 Client ID 931 2-0004-007F 9312-0004-01 2F Method Blank (MB)180060008(931 2-0004-007F)
Sample Duplicate (DUP)180060008(931 2-0004-007F)
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-003 REV# 8.Calibration Information:
Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.
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: 180060008 (931 2-0004-007F).
QC Information All of the QC samples met the required acceptance limits.32 Technical Information:
Holding Time All sample procedures for this sample set were performed within the required holding time.Preparation Information All preparation criteria have been met for these analyses.Sample Re-prep/Re-analysis None of the samples in this sample set required reprep or reanalysis.
Miscellaneous Information:
NCR Documentation Nonconformance reports are generated to document any procedural anomalies that may deviate from referenced SOP or contractual documents.
A nonconformance report (NCR) was not generated for this SDG.Additional Comments Additional comments were not required for this sample set.Qualifier information Manual qualifiers were not required.Certification Statement Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless otherwise noted in the analytical case narrative.
Review Validation:
GEL requires all analytical data to be verified by a qualified data validator.
In addition, all data designated for CLP or CLP-like packaging will receive a third level validation upon completion of the data package.The following data validator verified the information presented in this case narrative:
Reviewer/Date:
AIýý33 GEL Laboratories LLC Form GEL-NCR Rev. 06/05 NCR Report No.: 405548 Revision No.: 1 COMPANY -WIDE NONCONFORMANCE REPORT Mo.Day Yr. Division:
Quality Criteria:Tye 09-FEB-07 Radiochemistry SpecificationsPrcs Instrument Type: Test / Method: Matrix Type: Client Code: GEPO EPA 905.0 Modified SldYN Batch ID: Sample Numbers: 608308 See Below Potentially affected work order(s)(SDG):
180060(MSR#07-0063)
Application Issues: RDL less than MDA Failed Recovery for MS/PS Specification and Requirements
[NRG Disposition:
Nonconformance
==
Description:==
- 1. Matrix spike 1201275065 did not meet the recovery requirement due to the analyst error. The analyst did not spike the sample. The batch is a repre p.2. The matrix spike did not meet the required detection limit due to the sample not being spiked.Originator's Name: 1. The matrix spike passed on the initial batch, but there was alpha interference that elevated the activities.
The second prep does not show any interference.
Project manager notified.
Reporting results.2. Reporting results Data Validator/Group Leader: Kenshalla Oston Quality Review: Director: 09-FEB-07 Heather Anderson 09-FEB-07 Page 1 34 SAMPLE DATA
SUMMARY
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Report for YANKOOlI Connecticut Yankee Atomic Power Co.Client SDG: MSR#07-0063 GEL Work Order: 180060 The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification ND The analyte concentration is not detected above the detection limit.The above sample is reported on a dry weight basis except where prohibited by the analytical procedure.
Where the analytical method has been performed under'NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the Certificate of Analysis.This data report has been prepared and reviewed in accordance with GEL Laboratories LLC standard operating pro e.Plase direct any questions to your Project Manager, Cheryl Jones.Reviewed by GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: 9312-0004-OOIF Project: YANKOI1204 Sample ID: 180060001 Client ID: YANKOO I Matrix: TS Vol. Recv.: Collect Date: 30-JAN-07 Receive Date: 02-FEB-07 Collector:
Client Moisture:
6.99%Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pi Rad Gamma Spec Analysis Gamma, Solid-ESS GAM & ALL FSS 226 In growth Waived Actinium-228 0.841 +/-0.177 0.0615 +/-0.177 0.123 pCi/g MJH1 02/05/07 1456 607292 Americium-241 U -0.0108 +/-0.110 0.0906 +/-0.110 0.181 pCi/g Bismuth-212 0.741 +/-0.302 0.143 +/-0.302 0.286 pCi/g Bismuth-214 0.786 +/-0.116 0.0325 +/-0.116 0.065 pCi/g Cesium-I 34 UI 0.00 +/-0.0336 0.0247 +/-0.0336 0.0494 pCi/g Cesium-137 0.0493 +/-0.039 0.0215 +/-0.039 0.043 pCi/g Cobalt-60 U 0.0103 +/-0.0263 0.0229 +/-0.0263 0.0457 pCi/g Europium-152 U 0.0522 +/-0.0891 0.0506 +/-0.0891 0.101 pCi/g Europium-I 54 U -0.048 +/-0.0877 0.0586 +/-0.0877 0.117 pCi/g Europium-ISS U 0.0559 +/-0.0796 0.0609 +/-0.0796 0.122 pCi/g Lead-21 2 0.830 +/-0.0875 0.029 +/-0.0875 0.0579 pCi/g Lead-2 14 0.942 +/-0.126 0.0343 +/-0.126 0.0686 pCi/g Manganese-54 U 0.0118 +/-0.0223 0.0202 +/-0.0223 0.0403 pCi/g Niobium-94 U 0.00166 +/-0.0212 0.0181 +/-0.0212 0.0361 pCi/g Potassium-40 13.9 +/-1.28 0.137 +/-1.28 0.274 pCi/g Radium-226 0.786 +/-0.116 0.0325 +/-0.116 0.065 pCi/g Silver-108m U -0.00159 +/-0.019 0.0167 +/-0.019 0.0334 pCi/g Thallium-208 0.240 +/-0.0524 0.0195 +/-0.0524 0.0389 pCi/g Rad Gas Flow Proportional Counting GFPC, SO9O, solid-ALL FSS Strontium-90 U 0.026 +/-0.0226 0.0157 +/-0.0226 0.0362 pCi/g KSDI1 02/09/07 0948 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 37 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-OOIF Project: YANK01204 Sample ID: 180060001 Client ID: YANKO0l Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch T Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 66 (25%-125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 66 (25%-I125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by 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 ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.Ul Gamma Spectroscopy--Uncertain identification
- 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.38R GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 931 2-0004-002F 180060002 TS 30-JAN-07 02-FEB-07 Client 12.7%Project: Client ID: Vol. Recv.: YANK0 1204 YANKOO 1 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P~Rad Gamma Spec Analysis Gamma, Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 1.13 +/-0.226 0.0688 +/-0.226 0.137 pCi/g MJH1 02/05/07 1456 607292 Americium-241 U 0.0442 +/-0.0818 0.0681 +/-0.0818 0.136 pCi/g Bismuth-212 0.783 +/-0.316 0.143 +/-0.316 0.285 pCi/g Bismuth-214 1.05 +/-0.139 0.0369 +/-0.139 0.0737 pCi/g Cesium-134 U 0.0295 +/-0.0248 0.0232 +/-0.0248 0.0464 pCi/g Cesium-137 0.0871 +/-0.0332 0.0192 +/-0.0332 0.0385 pCi/g Cobalt-60 U -3.140E- +/-0.0245 0.0205 +/-0.0245 0.041 pCi/g 05 Europium-152 U 0.00745 +/-0.073 0.0499 +/-0.073 0.0998 pCi/g Europium-154 U -0.0472 +/-0.0851 0.0562 +/-0.0851 0.112 pCi/g Europium-155 U 0.0363 +/-0.062 0.0569 +/-0.062 0.114 pCi/g Lead-212 1.00 +/-0.103 0.0295 +/-0.103 0.0589 pCi/g Lead-214 1.18 +/-0.141 0.0363 +/-0.141 0.0725 pCi/g Manganese-54 U 0.0156 +/-0.0239 0.0216 +/-0.0239 0.0433 pCi/g Niobium-94 U 0.0169 +/-0.0209 0.0186 +/-0.0209 0.0371 pCi/g Potassium-40 15.8 +/-1.31 0.185 +/-1.31 0.371 pCi/g Radium-226 1.05 +/-0.139 0.0369 +/-0.139 0.0737 pCi/g Silver-108m U 0.0103 +/-0.0197 0.0178 +/-0.0197 0.0355 pCi/g Thallium-208 0.289 +/-0.0525 0.0187 +/-0.0525 0.0374 pCi/g Rad Gas Flow Proportional Counting GFPC, 5r90, solid-ALL ESS Strontium-90 0.0595 +/-0.03 17 0.0196 +/-0.0317 0.0453 pCi/g KSDI1 02/09/07 0948 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 39)
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-002F Project: YANK0 1204 Sample ID: 180060002 Client ID: YANKO0l Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units 1W Analyst Date Time Batch D Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr9O, solid-ALL FSS 59 (25%-125%)
Carrier/Tracer Recovery GFPC, Sr9O, solid-ALL FSS 59 (25%-1 25%)Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.40 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 931 2-0004-003F 180060003 TS 30-JAN-07 02-FEB-07 Client 8.32%Proiect: Client ID: Vol. Recv.: YANK0 1204 YANKOO 1 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch 1P Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.783 +/-0.163 0.0616 +/-0.163 0.123 pCi/g MJHI1 02/05/07 1457 607292 Americium-241 U 0.0546 +/-0.0697 0.0585 +/-0.0697 0.117 pCi/g Bismuth-212 0.533 +/-0.239 0.119 +/-0.239 0.237 pCi/g Bismuth-214 0.548 +/-0.0869 0.0322 +/-0.0869 0.0645 pCi/g Cesium-134 U 0.0381 +/-0.0364 0.0216 +/-0.0364 0.0432 pCi/g Cesium-137 0.155 +/-0.0392 0.0195 +/-0.0392 0.039 pCi/g Cobalt-60 U 0.0269 +/-0.0239 0.0222 +/-0.0239 0.0443 pCi/g Europium-152 U -0.00239 +/-0.0617 0.0447 +/-0.0617 0.0894 pCi/g Europium-154 U -0.0149 +/-0.0649 0.0535 +/-0.0649 0.107 pCi/g Europium-155 U 0.0349 +/-0.0565 0.0503 +/-0.0565 0.101 pCi/g Lead-212 0.689 +/-0.076 0.0261 +/-0.076 0.0521 pCi/g Lead-214 0.653 +/-0.0967 0.0311 +/-0.0967 0.0622 pCi/g Manganese-54 U -0.00213 +/-0.0187 0.0161 +/-0.0187 0.0323 pCi/g Niobium-94 U 0.00746 +/-0.0169 0.0154 +/-0.0169 0.0307 pCi/g Potassium-40 11.8 +/-1.08 0.166 +/-1.08 0.332 pCi/g Radium-226 0.548 +/-0.0869 0.0322 +/-0.0869 0.0645 pCi/g Silver-108m U 0.00264 +/-0.0181 0.016 +/-0.0181 0.032 pCi/g Thallium-208 0.226 +/-0.0412 0.0155 +/-0.0412 0.0309 pCi/g Rad Gas Flow Proportional Counting GFPC, SO9O, solid-ALL FSS Strontium-90 U 0.0338 +/-0.0249 0.017 +/-0.025 0.0389 pCi/g KSDI 02/09/07 0948 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description 2 3 EML HASL 300, 4.5.2.3 EPA 905.0 Modified EPA 905.0 Modified 41 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils P04* 002332 Client Sample ID: 9312-0004-003F Project: YANK01204 Sample ID: 180060003 Client ID: YANKOOI Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU NMA Units DF Analyst Date Time Batch Di Surrogate/T racer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 68 (25%-I125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL ESS 68 (25%-125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.42 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 931 2-0004-004F 180060004 TS 30-JAN-07 02-FEB-07 Client 10.9%Project: Client ID: Vol. Recv.: YANKOI 204 YANKOO I Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P~Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.762 +/-0.184 0.0755 +/-0.184 0.151 pCi/g MIHI 02/05/07 1457 607292 Americium-241 U 0.0193 +/-0.0419 0.0361 +/-0.0419 0.0722 pCi/g Bismuth-212 0.623 +/-0.371 0.157 +/-0.371 0.314 pCi/g Bismuth-214 0.621 +/-0.115 0.0376 +/-0.115 0.0751 pCi/g Cesium-134 UI 0.00 +/-0.0303 0.0258 +/-0.0303 0.0516 pCi/g Cesium-137 0.109 +/-0.040 0.0236 +/-0.040 0.0471 pCi/g Cobalt-60 U 0.01 48 +/-0.0458 0.0274 +/-0.0458 0.0549 pCi/g Europium-152 U -0.00201 +/-0.0771 0.0531 +/-0.0771 0.106 pCi/g Europium-154 U -0.0991 +/-0.0912 0.0674 +/-0.0912 0.135 pCi/g Europium-155 U 0.0488 +/-0.0793 0.0543 +/-0.0793 0.109 pCi/g Lead-212 0.812 +/-0.106 0.0339 +/-0.106 0.0677 pCi/g Lead-214 0.819 +/-0.118 0.0429 +/-0.118 0.0858 pCi/g Manganese-54 U 0.0009 +/-0.0242 0.02 14 +/-0.0242 0.0429 pCi/g Niobium-94 U -0.00037 +/-0.0279 0.0205 +/-0.0279 0.041 pCi/g Potassium-40 13.7 +/-1.40 0.224 +/-1.40 0.448 pCi/g Radium-226 0.621 +/-0.115 0.0376 +/-0.115 0.0751 pCi/g Silver-108m U-0.000884
+/-0.0217 0.0193 +/-0.0217 0.0385 pCi/g Thallium-208 0.282 +/-0.056 0.0206 +/-0.056 0.0413 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 0.0597 +/-0.0298 0.0181 +/-0.0298 0.0417 pCi/g KSDI 02/09/07 0948 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I EML HASL 300,4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 43 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. lack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-004F Project: YANKOI1204 Sample ID: 180060004 Client ID: YANKO0l Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P~Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr9O, solid-ALL ESS 63 (25%-I125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL ESS 63 (25%-I125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD1 Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected* 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* QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.44 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils P04* 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 931 2-0004-005F 180060005 TS 30-JAN-07 02-FEB-07 Client 6.44%Project: Client ID: Vol. Recv.: YANK01204 YANKOOI Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pi Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.732 +/-0.162 0.0581 +/-0.162 0.116 pCi/g MJHI 02/05/07 1458 607292 Americium-241 U 0.0597 +/-0.0744 0.0632 +/-0.0744 0.126 pCi/g Bismuth-212 0.513 +/-0.253 0.127 +/-0.253 0.253 pCi/g Bismuth-214 0.643 +/-0.100 0.0317 +/-0.100 0.0634 pCi/g Cesium-134 U 0.0426 +/-0.0375 0.0245 +/-0.0375 0.0489 pCi/g Cesium-137 0.604 +/-0.0726 0.0184 +/-0.0726 0.0367 pCi/g Cobalt-60 0.0947 +/-0.034 0.015 +/-0.034 0.0299 pCi/g Europium-152 U 0.0145 +/-0.066 0.0492 +/-0.066 0.0984 pCi/g Europium-154 U -0.0191 +/-0.0571 0.0462 +/-0.0571 0.0923 pCi/g Europium-155 U 0.0315 +/-0.0607 0.0542 +/-0.0607 0.108 pCi/g Lead-21 2 0.738 +/-0.0782 0.0273 +/-0.0782 0.0546 pCi/g Lead-214 0.715 +/-0.103 0.0335 +/-0.103 0.067 pCi/g Manganese-54 U -0.00403 +/-0.019 0.0164 +/-0.019 0.0327 pCi/g Niobium-94 U 0.0165 +/-0.0186 0.0167 +/-0.0186 0.0335 pCi/g Potassium-40 11.6 +/-1.03 0.143 +1-1.03 0.286 pCi/g Radium-226 0.643 +/-0.100 0.0317 +/-0.100 0.0634 pCi/g Silver-1O8m U -0.00696 +/-0.0179 0.0154 +/-0.0179 0.0307 pCi/g Thallium-208 0.261 +/-0.0473 0.0149 +/-0.0473 0.0299 pCi/g Rad Gas Flow Proportional Counting GFPC, SO9O, solid-ALL FSS Strontium-90 U 0.0299 +/-0.0236 0.0159 +/-0.0236 0.0369 pCi/g KSDI 02/09/07 0948 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 45 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-005F Project: YANK01204 Sample ID: 180060005 Client ID: YANKO0l Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pi Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr9O, solid-ALL FSS 67 (25%-125%)
Carrier/Tracer Recovery GFPC, Sr9O, solid-ALL FSS 67 (25%-I125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected* Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +I-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Anal[3sis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 931 2-0004-005FS 180060006 TS 30-JAN-07 02-FEB-07 Client 6.59%Project: Client ID: Vol. Recv.: YANKO01204 YANKOO 1 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch D~Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.855 +/-0.183 0.061 +/-0.183 0.122 pCi/g MJHI 02/05/07 1458 607292 Americium-241 U -0.0956 +/-0.086 0.073 +/-0.086 0.146 pCi/g Bismuth-212 0.660 +/-0.300 0.134 +/-0.300 0.268 pCi/g Bismuth-214 0.577 +/-0.101 0.036 +/-0.101 0.0719 pCi/g Cesium-134 U 0.0314 +/-0.0233 0.0216 +/-0.0233 0.0432 pCi/g Cesium-137 0.741 +/-0.0785 0.0178 +/-0.0785 0.0355 pCi/g Cobalt-60 0.0853 +/-0.0497 0.0178 +/-0.0497 0.0356 pCi/g Europium-152 U -0.0089 +/-0.0782 0.0523 +/-0.0782 0.105 pCi/g Europium-154 U -0.0234 +/-0.0633 0.0515 +/-0.0633 0.103 pCi/g Europium-I 55 U 0.064 +/-0.0625 0.0579 +/-0.0625 0.116 pCi/g Lead-212 0.694 +/-0.0806 0.0273 +/-0.0806 0.0545 pCi/g Lead-214 0.641 +/-0.113 0.0358 +/-0.113 0.0715 pCi/g Manganese-54 U 0.00907 +/-0.0208 0.0188 +/-0.0208 0.0376 pCi/g Niobium-94 U 0.000806 +/-0.0197 0.0168 +/-0.0197 0.0335 pCi/g Potassium-40 10.2 +/-0.996 0.131 +/-0.996 0.262 pCi/g Radium-226 0.577 +/-0.101 0.036 +/-0.101 0.0719 pCi/g Silver-108m U -0.0158 +/-0.0213 0.0179 +/-0.0213 0.0358 pCi/g Thallium-208 0.218 +/-0.0423 0.0165 +/-0.0423 0.033 pCi/g Rad Gas Flow Proportional Counting GFPC, SO9O, solid-ALL FSS Strontium-90 0.0604 +/-0.0282 0.0165 +/-0.0283 0.0383 pCi/g KSD1 02/09/07 0947 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 47 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-005FS Project: YANK01204 Sample ID: 180060006 Client ID: YANKO0l Vol. Recv.: Parameter Quallifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch I Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 70 (25%-I125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 70 (25%-125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by CC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit* Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* 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.4R GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Certificateof A alvsis Company : Connecticut Yankee Atomic Power Address :362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 931 2-0004-006F 180060007 TS 30-JAN-07 02-FEB-07 Client 7.72%Project: Client ID: Vol. Recv.: YANK01204 YANKO0l Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch D~Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.847 +/-0.180 0.0617 +/-0.180 0.123 pCi/g MJHI1 02/05/07 1459 607292 Americium-241 U 0.0506 +/-0.0687 0.0579 +/-0.0687 0.116 pCi/g Bismuth-212 0.613 +/-0.281 0.166 +/-0.281 0.332 pCi/g Bismuth-214 0.540 +/-0.0921 0.0363 +/-0.0921 0.0726 pCi/g Cesium-I 34 UI 0.00 +/-0.0377 0.0251 +/-0.0377 0.0501 pCi/g Cesium-] 37 0.110 +/-0.0357 0.0187 +/-0.0357 0.0375 pCi/g Cobalt-60 U 0.0361 +/-0.0238 0.0228 +/-0.0238 0.0456 pCi/g Europium-152 U 0.0161 +/-0.0658 0.0518 +/-0.0658 0.104 pCi/g Europium-154 U -0.0102 +/-0.0788 0.0581 +/-0.0788 0.116 pCi/g Europium-155 U 0.033 +/-0.0605 0.0557 +/-0.0605 0.111 pCi/g Lead-212 0.754 +/-0.0818 0.0295 +/-0.0818 0.0589 pCi/g Lead-214 0.701 +/-0.104 0.0369 +/-0.104 0.0737 pCi/g Manganese-54 U 0.035 +/-0.0197 0.0184 +/-0.0197 0.0368 pCi/g Niobium-94 U 0.0154 +/-0.0203 0.018 +/-0.0203 0.0361 pCi/g Potassium-40 12.6 +/-1.13 0.148 +/-1.13 0.295 pCi/g Radium-226 0.540 +/-0.0921 0.0363 +/-0.0921 0.0726 pCi/g Silver-108m U 0.00968 +/-0.0329 0.0178 +/-0.0329 0.0355 pCi/g Thallium-208 0.203 +/-0.0448 0.018 +/-0.0448 0.036 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 U 0.00771 +/-0.0215 0.017 +/-0.0215 0.0391 pCi/g KSDI 02/09/07 0947 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I EML HASL 300,4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 49 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils P04* 002332 Client Sample ID: 9312-0004-006F Proiect: YANK01204 Sample ID: 180060007 Client ID: YANKOOlI Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch I Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL ESS 63 (25%-125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 63 (25%-I125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD1 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 ND Analyte concentration is not detected above the detection limit* Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis._50 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 931 2-0004-007F 180060008 TS 30-JAN-07 02-FEB-07 Client 7.28%Proiect: Client ID: Vol. Recv.: YANK01 204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch D~Rad Alpha Spec Analysis Alphaspec Am24l, Cm, Solid ALL FSS Americium-241 U 0.0678+/-0.0899 0.00 +/-0.0903 Curium-242 Curium-243/244 Aiphaspec Pu, Solid-ALL FSS Plutonium-238 Plutonium-239/240 U 0.00 +/-0.0624 0.00 +/-0.0624 0.093 +/-0.105 0.00 +/-0.106 U 0.0187 +/-0.0497
- 0. 0221 +/-0.0497 U -0.00493 +/-0.0548 0.0495 +/-0.0548 0.084 0.0863 0.084 0.111 0.166 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MXA 02/05/07 1044 607169 MXA 02/05/07 1044 607170 MXA 02/06/07 1528 607171 Liquid Scint Pu24I1, Solid-A LL FSS Plutonium-241 Ui-1.15 +/-5.42 4.62 +/-5.42 9.81 Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL ESS 226 In growth Waived Actinium-228 UI Americium-241 U Bismuth-212 UI Bismuth-2 14 Cesium- 134 U Cesium-I 37 U Cobalt-60 U Europium-152 U Europium-154 U Europium-IS55 U Lead-21 2 Lead-214 Manganese-54 U Niobium-94 U Potassium-40 Radium-226 Silver-108m U Thallium-208 Rad Gas Flow Proportional Counting GFPC, Sr90, solid-ALL FSS Strontium-90 U Rad Liquid Scintillation Analysis 0.00 0.015 0.00 0.413 0.0609 0.0342 0.03 16-0.0353-0.0219 0.0254 0.538 0.508 0.0234 0.00138 9.40 0.4 13 0.0108 0.179+/-0. 191+/-0.0415+1-0.369+/-0.116+/-0.052+/-0.0315+/-0.0397+/-0.0805+1-0.106+/-0.0599+/-0.0801+/-0.102+/-0.0192+/-0.0276+1-1.13+1-0.116+/-0.0244+/-0.0576 0.161 0.0341 0.255 0.0481 0.0335 0.0305 0.037 0.0549 0.0862 0.0548 0.0316 0.0423 0.0244 0.0244 0.234 0.0481 0.0221 0.0271+/-0.191+/-0.0415+/-0.369+/-0.116+/-0.052+/-0.0315+/-0.0397+/-0.0805+/-0. 106+/-0.0599+/-0.0801+/-0.102+/-0.0192+/-0.0276+/-1.13+/-0.116+/-0.0244+/-0.0576 0.323 0.0682 0.509 0.096 0.0669 0.061 0.074 0.110 0.172 0.109 0.0632 0.0846 0.0488 0.0488 0.467 0.096 0.0441 0.0541 0.0411 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MJH1 02/05/07 1459 607292 KSDI1 02/09/07 0947 608308 0.0157 +/-0.0237 0.0179 +/-0.0237_91 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: 931 2-0004-007F 180060008 Project: Client ID: Vol. Recv.: YANK01204 YANKOO I Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch D~Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid -3 pCi/g Tritium U 0.792 +/-1.08 0.868 +/-1.08 1.82 pCi/g AXD2 02/03/07 0322 607149 Liquid Scint C14, Solid AIIFSS Carbon-14 U 0.00632 +/-0.0894 0.0749 +/-0.0894 0.153 pCilg AXD2 02/03/07 0201 607153 Liquid Scint FeSS, Solid-ALL ESS Iron-55 U -25.7 +/-46.1 31.2 +/-46.1 64.7 pCi/g MXP1 02/06/07 1559 607148 Liquid Scint Ni63, Solid-ALL FSS Nickel-63 U -0.51 +/-8.56 7.21 +/-8.56 15.1 pCi/g MXP1 02/06/07 1401 607147 Liquid Scint Tc99, Solid-ALL FSS Technetium-99 U 0.142 +/-0.183 0.150 +/-0.183 0.309 pCi/g MXPI 02/07/07 1402 607151 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I DOE EML HASL-300, Am-05-RC Modified 2 DOE EML HASL-300, Pu- I I1-RC Modified 3 DOE EML HASL-300, Pu- I I1-RC Modified 4 EML HASL 300, 4.5.2.3 5 EPA 905.0 Modified 6 EPA 905.0 Modified 7 EPA 906.0 Modified 8 EPA EERF C-01 Modified 9 DOE RESL Fe-I, Modified 10 DOE RESL Ni-I, Modified I I DOE EML HASL-300, Tc-02-RC Modified Surrogate/Tracer recovery Test Recovery % Acceptable Limits Americium-243 Plutonium-242 Plutonium-242 Strontium-90 Aiphaspec Am24l, Cm, Solid ALL Alphaspec Pu, Solid-ALL FSS Liquid Scint Pu24I, Solid-ALL FS GFPC, SOO0, solid-ALL FSS 81 95 99 66 (15%-125%)
(15%-125%)
(25%-I125%)
(25%-125%)
52 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis A alvsis Company :Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: 9312-0004-007F 180060008 Project: Client ID: Vol. Recv.: YANK01 204 YANK0OI Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pi Carrier/Tracer Recovery Iron-59 Nickel-63 Carrier/Tracer Recovery Technetium-99 Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS Liquid Scint Fe55, Solid-ALL FS Liqui d Scint Ni63, Solid-ALL FS Liquid Scint Ni63, Solid-ALL FS Liquid Scint Tc99, Solid-ALL ES Liquid Scint Tc99, Solid-ALL ES 66 73 89 89 82 82 (25%-I 25%)(15%-I 25%)(25%-I125%)
(25%-I125%)
(15%-125%)
(15%-125%)
Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by 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 ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- 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.S53 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -wvww.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Corntact:
Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 931 2-0004-008F 180060009 TS 30-JAN-07 02-FEB-07 Client 6.45%Proiect: Client ID: Vol. Recv.: YANK01 204 YANKOO 1 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Di Rad Gamma Spec Analysis Gamma,Solid-FSS CAM & ALL FSS 226 In growth Waived Actinium-228 0.826 +/-0.169 0.0481 +/-0.169 0.0962 pCi/g MJHI 02/05/07 1500 607292 Americium-241 U 0.0252 +/-0.0729 0.0609 +/-0.0729 0.122 pCi/g Bismuth-212 0.481 +/-0.230 0.0973 +/-0.230 0.195 pCi/g Bismuth-214 0.616 +/-0.0906 0.0258 +/-0.0906 0.0515 pCi/g Cesium-134 UI 0.00 +/-0.0227 0.0179 +/-0.0227 0.0357 pCi/g Cesium-137 0.199 +/-0.0352 0.013 +/-0.0352 0.026 pCi/g Cobalt-60 U 0.0126 +/-0.017 0.0152 +/-0.017 0.0303 pCi/g Europium-152 U -0.0219 +/-0.0756 0.038 +/-0.0756 0.076 pCi/g Europium-154 U -0.0131 +/-0.0469 0.0375 +/-0.0469 0.0749 pCi/g Europium-I 55 U 0.031 +/-0.0752 0.0525 +/-0.0752 0.105 pCi/g Lead-2 12 0.775 +/-0.0771 0.0233 +/-0.0771 0.0466 pCi/g Lead-214 0.713 +/-0.0947 0.0266 +/-0.0947 0.0531 pCi/g Manganese-54 U 0.000242 +/-0.0159 0.0139 +/-0.0159 0.0278 pCi/g Niobium-94 U -0.00457 +/-0.0148 0.0123 +/-0.0148 0.0246 pCi/g Potassium-40 12.0 +/-0.969 0.125 +/-0.969 0.250 pCi/g Radium-226 0.616 +/-0.0906 0.0258 +/-0.0906 0.05 15 pCi/g Silver-108m U -0.00705 +/-0.0151 0.013 +/-0.0151 0.0259 pCi/g Thallium-208 0.202 +/-0.0407 0.0135 +/-0.0407 0.0269 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 U 0.031 +/-0.0245 0.0167 +/-0.0245 0.0386 pCi/g KSDI 02/09/07 0947 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description 2 3 EML HASL 300,4.5.2.3 EPA 905.0 Modified EPA 905.0 Modified-94 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-008F Project: YANK0 1204 Sample ID: 180060009 Client ID: YANKOOI Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Di Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 63 (25%-125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 63 (25%-125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by CC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy---Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* 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.
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 931 2-0004-009F 180060010 TS 30-JAN-07 02-FEB-07 Client 6.27%Proiect: Client ID: Vol. Recv.: YANK01204 YANK0O I Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch D~Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL ESS 226 In growth Waived Actinium-228 0.861 +/-0.281 0.102 +/-0.281 0.203 pCi/g MJHI 02/05/07 1614 607292 Americium-241 U -0.00635 +/-0.0548 0.0455 +/-0.0548 0.0909 pCi/g Bismuth-212 0.871 +/-0.406 0.225 +/-0.406 0.450 pCi/g Bismuth-214 0.629 +/-0.140 0.0556 +/-0.140 0.111 pCilg Cesium-134 UI 0.00 +/-0.0617 0.0375 +/-0.0617 0.0749 pCi/g Cesium-137 U 0.0487 +/-0.0508 0.0297 +/-0.0508 0.0594 pCi/g Cobalt-60 U 0.0324 +/-0.0341 0.0308 +/-0.0341 0.0615 pCi/g Europium-152 U -0.0769 +/-0.101 0.0743 +/-0.101 0.149 pCi/g Europium-154 UI1 0.00 +/-0.135 0.0948 +/-0.135 0.190 pCi/g Europium-155 U 0.00827 +/-0.080 0.0738 +/-0.080 0.148 pCi/g Lead-212 0.746 +/-0.103 0.0409 +/-0.103 0.0817 pCi/g Lead-214 0.473 +/-0.126 0.0551 +/-0.126 0.110 pCi/g Manganese-54 U 0.00242 +/-0.0338 0.0298 +/-0.0338 0.0595 pCi/g Niobium-94 U -0.00921 +/-0.032 0.0266 +/-0.032 0.0532 pCi/g Potassium-40 11.8 +/-1.33 0.246 +/-1.33 0.492 pCi/g Radium-226 0.629 +/-0.140 0.0556 +/-0.140 0.111 pCi/g Silver-108m U -0.00257 +/-0.0298 0.0263 +/-0.0298 0.0525 pCi/g Thallium-208 0.236 +/-0.0637 0.0302 +/-0.0637 0.0604 pCi/g Rad Gas Flow Proportional Counting GFPC, SO9O, solid-ALL FSS Strontium-90 0.0624 +/-0.0306 0.019 +/-0.0306 0.0433 pCi/g KSDI1 02/09/07 0947 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Anallsis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004--009F Project: YANK01204 Sample ID: 180060010 Client ID: YANKOOI Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P~Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 60 (25%-I125%)
CarrierfTracer Recovery GFPC, Sr90, solid-ALL FSS 60 (25%-125%)
Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* 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.57 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO#t 002332 Report Date: February 9, 2007 Client Sample ID: 9312-0004-01IOF Project: YANK01204 Sample ID: 180060011 Client ID: YANK00l Matrix: TS Vol. Recv.: Collect Date: 30-JAN-07 Receive Date: 02-FEB-07 Collector:
Client Moisture:
7.37%Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch 1 Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.876 +/-0.223 0.0804 +/-0.223 0.161 pCi/g MIHI1 02/05/07 1722 607292 Americium-241 U 0.0304 +/-0.0432 0.0364 +/-0.0432 0.0728 pCilg Bismuth-212 U 0.343 +/-0.503 0.195 +/-0.503 0.390 pCilg Bismuth-214 0.577 +/-0.114 0.0416 +/-0.114 0.0831 pCi/g Cesium-134 UI 0.00 +/-0.0452 0.0331 +/-0.0452 0.0661 pCi/g Cesium-]137 U -0.00784 +/-0.0309 0.0256 +/-0.0309 0.0512 pCilg Cobalt-60 U -0.0123 +/-0.0317 0.0252 +/-0.0317 0.0503 pCilg Europium-152 U 0.013 +/-0.0944 0.0587 +/-0.0944 0.117 pCi/g Europium-154 UI 0.00 +/-0.114 0.0695 +/-0.114 0.139 pCilg Europium-155 U 0.1 17 +/-0.113 0.0615 +/-0.113 0.123 pCi/g Lead-2 12 0.929 +/-0.120 0.034 +/-0.120 0.0679 pCi/g Lead-214 0.647 +/-0.122 0.0417 +/-0.122 0.0833 pCi/g Manganese-54 U 0.0208 +/-0.0284 0.0262 +/-0.0284 0.0524 pCi/g Niobium-94 U -0.0162 +/-0.0264 0.0209 +/-0.0264 0.0418 pCi/g Potassium-40 13.6 +/-1.47 0.164 +/-1.47 0.327 pCi/g Radium-226 0.577 +/-0.114 0.0416 +/-0.114 0.0831 pCi/g Silver-108m U 0.00891 +/-0.0243 0.0218 +/-0.0243 0.0435 pCi/g T'hallium-208 0.377 +/-0.0627 0.0199 +/-0.0627 0.0398 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 0.0589 +/-0.0265 0.0157 +/-0.0266 0.036 1 pCi/g KSDI1 02/09/07 0947 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I EML HASL 300,4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 58 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils P04* 002332 Client Sample ID: 9312-0004-OIOF Project: YANKOl1204 Sample ID: 180060011 Client ID: YANKOO I Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch I Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 68 (25%-I125%)
Carrier/Tracer Recovery GFPC, SrOO, solid-ALL FSS 68 (25%-125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.13D Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.Ul Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* 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.S59 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company :Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils P04* 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 9312-0004-01IIF 180060012 TS 30-JAN-07 02-FEB-07 Client 6.62%Project: Client ID: Vol. Recv.: YANK01 204 YANKOO I Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pt Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.609 +/-0.264 0.0991 +/-0.264 0.198 pCilg MJH1 02/05/07 1723 607292 Americium-241 U 0.0257 +/-0.0473 0.0393 +/-0.0473 0.0786 pCilg Bismuth-212 0.553 +/-0.357 0.204 +/-0.357 0.408 pCilg Bismuth-214 0.588 +/-0.132 0.0485 +/-0.132 0.0969 pCilg Cesium-134 U 0.0362 +/-0.0494 0.0365 +/-0.0494 0.073 pCilg Cesium-137 U 0.00211 +/-0.0342 0.0305 +/-0.0342 0.061 pCi/g Cobalt-60 U -0.00859 +/-0.0433 0.0296 +/-0.0433 0.059 1 pCi/g Europium-152 U -0.0213 +/-0.0925 0.0602 +/-0.0925 0.120 pCi/g Europium-154 U -0.0254 +/-0.126 0.103 +/-0.126 0.206 pCi/g Europium-155 U 0.0724 +/-0.0656 0.0611 +/-0.0656 0.122 pCi/g Lead-212 0.719 +/-0.0946 0.0292 +/-0.0946 0.0584 pCi/g Lead-214 0.678 +/-0.129 0.0441 +/-0.129 0.0882 pCi/g Manganese-54 U 0.00377 +/-0.0307 0.0271 +/-0.0307 0.0542 pCi/g Niobium-94 U 0.00336 +/-0.0288 0.0257 +/-0.0288 0.05 14 pCi/g Potassium-40 11.6 +/-1.19 0.176 +/-1.19 0.352 pCi/g Radium-226 0.588 +/-0.132 0.0485 +/-0.132 0.0969 pCi/g Silver-108m U -0.00283 +/-0.0263 0.0228 +/-0.0263 0.0456 pCi/g Thallium-208 0.253 +/-0.0584 0.0245 +/-0.0584 0.049 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL ESS Strontium-90 0.0631 +/-0.0269 0.0152 +/-0.0269 0.0353 pCi/g KSD1 02/09/07 0947 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I EML HASL 300,4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 60 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-OIIF Project: YANK01204 Sample ID: 180060012 Client ID: YANKOOI Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P~Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 -GFPC, Sr90, solid-ALL FSS 68 (25%-I125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL ESS 68 (25%-125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.13D Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by CC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected* Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +f-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -wvww.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 9312-0004-012F 180060013 TS 30-JAN-07 02-FEB-07 Client 6.36%Project: Client ID: Vol. Recv.: YANK01204 YANKOOI Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pi Rad Alpha Spec Analysis Alphaspec Am24J1, Cm, Solid ALL FSS Americium-241 U -Curium-242 U Curium-243/244 U Aiphaspec Pu, Solid-ALL FSS Plutonium-238 U Plutonium-239/240 U -Liquid Scint Pu24J/, Solid-A LL FSS Plutonium-241 U-0.0251 +/-0.0551 0.00 +/-0.0552 0.00 +/-0.0566 0.00 +/-0.0566 0.0562 +/-0.0779 0.00 +/-0.0783 0.0339 +/-0.0765 0.0412 +/-0.0766).00635 +/-0.0534 0.0238 +/-0.0534 1.22 +/-6.92 5.74 +/-6.92 0.0762 0.0783 0.0762 0.154 0.119 pCi/g pCi/g pCi/g pCi/g pCi/g 12.2 pCilg Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 Americium-241 U Bismuth-2 12 Bismuth-2 14 Cesium-134 UI Cesium-137 U Cobalt-60 U-0 Europium-152 U -Europium-154 U Europium-ISS U Lead-212 Lead-21 4 Manganese-54 U Niobium-94 U Potassium-40 Radium-226 Silver-108m U -Thallium-208 Rad Gas Flow Proportional Counting GFPC, SOO0, solid-ALL FSS Strontium-90 U Rad Liquid Scintillation Analysis 0.548 0.0181 0.295 0.490.0.00 0.00806).000429 0.000724-0.0131 0.0658 0.529 0.527 0.0129 0.009 16 9.48 0.490 0.001 18 0.187+/-0.101+/-0.0684+/-0.151+/-0.0654+/-0.0253+/-0.0162+/-0.0131+/-0.0385+/-0.0395+/-0.0395+/-0.0532+/-0.0659+/-0.0187+/-0.0112+/-0.792+/-0.0654+/-0.012+/-0.031 0.0357 0.0577 0.0741 0.0197 0.01 26 0.0107 0.011 0.0283 0.0327 0.0334 0.0162 0.01 93 0.00995 0.00987 0.0947 0.01 97 0.009 15 0. 0093 2+/-0.101+/-0.0684+/-0.151+/-0.0654+/-0.0253+/-0.0162+/-0.0131+/-0.0385+/-0.0395+/-0.0395+/-0.0532+/-0.0659+/-0.0187+/-0.01 12+/-0.792+/-0.0654+/-0.0 12+/-0.031I 0.07 14 0.115 0.148 0.0393 0.0252 0.02 13 0.022 0.0565 0.0653 0.0668 0.0323 0.0385 0.0199 0.01 97 0.189 0.0393 0.0183 0.01 86 0.0413 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g MXA 02/05/07 1044 607169 MX 20/7 04677 MXA 02/06/07 1544 607171 MJHI1 02/05/07 1939 607292 KSDI 02/09/07 0947 608308 0.00305 +/-0.0221 0.0182 +/-0.0221 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address :362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: 9312-0004-01 2F 180060013 Project: Client ID: Vol. Recv.: YANK01204 YANK00l Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch D~Rad Liquid Scintillation Analysis LSC, Tritium Dist, Solid -3 pCi/g Tritium U -0.611 +1-1.04 0.900 +/-1.04 1.89 pCi/g AXD2 02/03/07 0354 607149 Liquid Scint C14, Solid Afl, FSS Carbon-14 U 0.023 +/-0.0861 0.0718 +/-0.0861 0.147 pCi/g AXD2 02/03/07 0302 607153 Liquid Scint FeSS, Solid-ALL FSS Iron-55 U -13.7 +/-47.4 32.2 +/-47.4 67.2 pCi/g MXPI 02/06/07 1615 607148 Liquid Scint Ni63, Solid-ALL FSS Nickel-63 U -4.96 +/-8.95 7.74 +/-8.95 16.3 pCi/g MXPI 02/06/07 1417 607147 Liquid Scint Tc99, Solid-ALL FSS Technetium-99 U 0.166 +/-0.192 0.157 +/-0.192 0.323 pCi/g MXPI 02/07/07 1433 607151 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I DOE EML HASL-300, Am-05-RC Modified 2 DOE EML HASL-300, Pu-]I -RC Modified 3 DOE EML HASL-300, Pu-]I -RC Modified 4 EML HASL 300,4.5.2.3 5 EPA 905.0 Modified 6 EPA 905.0 Modified 7 EPA 906.0 Modified 8 EPA EERF C-01 Modified 9 DOE RESL Fe-I, Modified 10 DOE RESL Ni-I, Modified I1I DOE EML HASL-300, Tc-02-RC Modified Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Americium-243 Plutonium-242 Plutonium-242 Strontium-90 Alphaspec Am24l, Cm, Solid ALL Aiphaspec Pu, Solid-ALL FSS Liquid Scint Pu241, Solid-ALL FS GFPC, SOO0, solid-ALL FSS 8I 89 80 69 (15%-I 25%)(15%-I125%)
(25%-1 25%)(25%-1 25%)
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -wvww.gel.com Certificate of Analysis Company :Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: 93 12-0004-0 12F 180060013 Project: Client ID: Vol. Recv.: YANK01204 YANKOOI Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch bi Carrier/Tracer Recovery Iron-59 Nickel-63 Carrier/Tracer Recovery Technetium-99 Carrier/Tracer Recovery GFPC, SrOO, solid-ALL ESS Liquid Scint Fe55, Solid-ALL FS Liquid Scint Ni63, Solid-ALL FS Liquid Scint Ni63, Solid-ALL FS Liquid Scint Tc99, Solid-ALL FS Liquid Scint Tc99, Solid-ALL FS 69 61 87 87 79 79 (25%-I125%)
(15%-I125%)
(25%-I125%)
(25%-I125%)
(15%-125%)
(15%-125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by CC/M[S analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- 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 +I-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.64 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www gel.com Certificate of Analysis Certificate ofA alvsis Company :Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: Febnuary 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 9312-0004-013F 180060014 TS 30-JAN-07 02-FEB-07 Client 7.69%Project: Client ID: Vol. Recv.: YANK01204 YANK001 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.872 +1-0.142 0.0359 +/-0.142 0.0717 pCi/g MJHI 02/05/07 1939 607292 Americium-241 U 0.0212 +/-0.0423 0.0353 +/-0.0423 0.0706 pCi/g Bismuth-212 0.611 +/-0.186 0.0796 +/-0.186 0.159 pCi/g Bismuth-214 0.585 +/-0.0773 0.0193 +/-0.0773 0.0385 pCi/g Cesium-] 34 UI 0.00 +/-0.0219 0.0136 +1-0.0219 0.0272 pCi/g Cesium-] 37 U 0.0141 +/-0.0172 0.0108 +/-0.0172 0.0215 pCi/g Cobalt-60 U 0.00656 +/-0.0128 0.0111 +/-0.0128 0.0222 pCi/g Europium-152 U-0.000931
+/-0.054 0.0281 +1-0.054 0.0562 pCi/g Europium-154 U -0.0165 +/-0.0404 0.0332 +/-0.0404 0.0663 pCi/g Europium-I 55 U 0.0313 +/-0.0436 0.0292 +/-0.0436 0.0584 pCi/g Lead-212 0.850 +/-0.0785 0.016 +/-0.0785 0.03 19 pCi/g Lead-214 0.666 +/-0.0771 0.0199 +/-0.0771 0.0398 pCi/g Manganese-54 U -0.00673 +/-0.0125 0.0106 +/-0.0125 0.0213 pCi/g Niobium-94 U 0.00494 +/-0.0113 0.00973 +/-0.0113 0.0195 pCi/g Potassium-40 12.9 +/-0.922 0.0944 +/-0.922 0.189 pCi/g Radium-226 0.585 +/-0.0773 0.0193 +/-0.0773 0.0385 pCi/g Silver-108m U -0.00942 +/-0.011 0.00935 +/-0.011 0.0187 pCi/g Thallium-208 0.286 +/-0.0396 0.00961 +/-0.0396 0.0192 pCi/g Rad Gas Flow Proportional Counting GFPC, SO9O, solid-ALL FSS Strontium-90 U 0.0183 +/-0.0215 0.0157 +/-0.0215 0.0362 pCi/g KSDI 02/09/07 0947 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description 2 EML HASL 300, 4.5.2.3 EPA 905.0 Modified 3 EPA 905.0 Modified GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils P04* 002332 Client Sample ID: 9312-0004-013F Project: YANK01204 Sample ID: 180060014 Client ID: YANKO0l Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pi Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr9O, solid-ALL FSS 67 (25 %-125%)Carrier/Tracer Recovery GFPC, Sr9O, solid-ALL FSS 67 (25%-I125%)
Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* 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.
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company :Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils P04* 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 9312-0004-014F 180060015 TS 30-JAN-07 02-FEB-07 Client 8.49%Proiect: Client ID: Vol. Recv.: YANKOI 204 YANKOO I Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pt Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 1.01 +/-0.176 0.0609 +/-0.176 0.122 pCi/g MJHI 02/05/07 1940 607292 Americium-241 U 0.0356 +/-0.0327 0.0268 +/-0.0327 0.0535 pCi/g Bismuth-212 0.850 +/-0.250 0.129 +/-0.250 0.258 pCi/g Bismuth-214 0.759 +/-0.111 0.0321 +/-0.111 0.0642 pCi/g Cesium-134 UI 0.00 +1-0.0343 0.0211 +/-0.0343 0.0422 pCi/g Cesium-137 0.228 +/-0.0375 0.019 +/-0.0375 0.038 pCi/g Cobalt-60 UI1 0.00 +/-0.0464 0.0154 +/-0.0464 0.0308 pCilg Europium-152 U 0.00245 +/-0.057 0.0437 +/-0.057 0.0873 pCi/g Europium-154 U -0.0237 +/-0.065 0.0534 +/-0.065 0.107 pCi/g Europium-IS55 U 0.0581 +/-0.0622 0.0404 +/-0.0622 0.0808 pCi/g Lead-212 0.977 +/-0.103 0.0227 +/-0.103 0.0453 pCi/g Lead-214 0.804 +/-0.102 0.031 +/-0.102 0.0619 pCi/g Manganese-54 U -0.014 +/-0.0209 0.0176 +/-0.0209 0.0352 pCi/g Niobium-94 U -0.00675 +/-0.0192 0.0159 +/-0.0192 0.0317 pCi/g Potassium-40 14.2 +/-1.08 0.149 +/-1.08 0.297 pCi/g Radium-226 0.759 +/-0.111 0.0321 +/-0.111 0.0642 pCi/g Silver-108m U -0.0144 +/-0.0175 0.0147 +/-0.0175 0.0295 pCi/g Thallium-208 0.310 +/-0.0498 0.0171 +/-0.0498 0.0341 pCi/g Rad Gas Flow Proportional Counting GFPC, SO9O, solid-ALL FSS Strontium-90 U -0.00331 +/-0.0242 0.0209 +/-0.0242 0.0497 pCi/g KSDI 02/09/07 1149 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description 2 3 EML HASL 300, 4.5.2.3 EPA 905.0 Modified EPA 905.0 Modified 67 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-014F Project: YANK01204 Sample ID: 180060015 Client ID: YANKO0l Vol. Recv.: Parameter Quallifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pt Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 66 (25%-125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 66 (25%-I125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* 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.
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Cerfiricate ofA alvsis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 9312-0004-01 5F 180060016 TS 30-JAN-07 02-FEB-07 Client 9.79%Project: Client ID: Vol. Recv.: YANK01204 YANKOOI Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.566 +/-0.108 0.0312 +/-0.108 0.0623 pCi/g MJHI 02/05/07 1940 607292 Americium-241 U 0.0305 +/-0.0347 0.0293 +/-0.0347 0.0586 pCi/g Bismuth-212 0.425 +/-0.137 0.0679 +/-0.137 0.136 pCi/g Bismuth-214 0.457 +/-0.0599 0.0166 +/-0.0599 0.0331 pCilg Cesium-134 UI 0.00 +/-0.0126 0.0106 +/-0.0126 0.0213 pCi/g Cesium-137 0.023 +/-0.0151 0.00798 +/-0.0151 0.016 pCi/g Cobalt-60 U -0.0128 +/-0.0103 0.00783 +/-0.0103 0.0157 pCi/g Europium-152 U 0.00158 +/-0.0344 0.0235 +/-0.0344 0.0471 pCi/g Europium-154 U 0.00665 +/-0.0328 0.0281 +/-0.0328 0.0562 pCi/g Europium-155 U 0.0488 +/-0.0347 0.0258 +/-0.0347 0.0517 pCi/g Lead-212 0.521 +/-0.0497 0.0134 +/-0.0497 0.0268 pCi/g Lead-214 0.475 +/-0.057 0.0172 +/-0.057 0.0344 pCi/g Manganese-54 U -0.00187 +/-0.012 0.00895 +/-0.012 0.0179 pCi/g Niobium-94 U 0.00321 +/-0.0101 0.00795 +/-0.0101 0.0159 pCi/g Potassium-40 9.54 +/-0.699 0.075 +/-0.699 0.150 pCi/g Radium-226 0.457 +/-0.0599 0.0166 +/-0.0599 0.033 1 pCi/g Silver-108m U 0.00322 +/-0.00884 0.00794 +/-0.00884 0.0159 pCi/g Thallium-208 0.179 +/-0.0276 0.00809 +/-0.0276 0.0162 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 U 0.00567 +/-0.0227 0.0184 +/-0.0227 0.042 pCi/g KSDI 02/09/07 0947 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified f69 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-015F Project: YANK01204 Sample ID: 180060016 Client ID: YANK001 Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Di Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontdumn-90 GFPC, Sr90, solid-ALL FSS 63 (25%-125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 63 (25%-I125%)
Notes: The Qualifiers in this report are defined as follows:* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected* Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI 'Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +I-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.70 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Anal3Lsis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 9, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 9312-0004-016-1 180060017 TS 30-JAN-07 02-FEB-07 Client 10.1%Proiect: Client ID: Vol. Recv.: YANKO 1204 YANKOO 1 Parameter Qualifier ResulIt Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P~Rad Gamma Spec Analysis Gamma,Solid-FSS GAM &ALL FSS 226 In growth Waived Actinium-228 0.729 +/-0.132 0.0535 +/-0.132 0.107 pCi/g MIHI 02/05/07 1941 607292 Americium-241 U 0.0711 +/-0.106 0.0657 +/-0.106 0.131 pCi/g Bismuth-212 0.687 +/-0.226 0.0934 +/-0.226 0.187 pCi/g Bismuth-214 0.574 +/-0.0796 0.0217 +1-0.0796 0.0435 pCi/g Cesium-I 34 UI 0.00 +/-0.0345 0.0156 +/-0.0345 0.0311 pCi/g Cesium-I 37 0.238 +/-0.0325 0.0124 +/-0.0325 0.0248 pCi/g Cobalt-60 3.60 +/-0.201 0.0107 +/-0.201 0.0213 pCi/g Europium-152 U -0.0106 +/-0.0419 0.0307 +1-0.0419 0.0614 pCi/g Europium-154 U -0.0281 +1-0.0357 0.029 +/-0.0357 0.058 pCi/g Europium-155 U 0.0684 +/-0.0546 0.0369 +/-0.0546 0.0737 pCi/g Lead-212 0.718 +/-0.0659 0.0183 +1-0.0659 0.0365 pCi/g Lead-214 0.660 +/-0.0743 0.02 17 +/-0.0743 0.0434 pCi/g Manganese-54 U 0.00534 +/-0.0154 0.0136 +/-0.0154 0.0272 pCi/g Niobium-94 U 0.00375 +/-0.0133 0.0114 +/-0.0133 0.0228 pCi/g Potassium-40 11.7 +/-0.801 0.0817 +/-0.801 0.163 pCi/g Radium-226 0.574 +/-0.0796 0.0217 +/-0.0796 0.0435 pCilg Silver-108m U 0.000259 +/-0.0119 0.0106 +/-0.0119 0.0211 pCilg Thallium-208 0.223 +/-0.0323 0.0113 +/-0.0323 0.0225 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 U 0.0379 +/-0.0318 0.0211 +/-0.0318 0.050 pCi/g KSDI 02/09/07 1149 608308 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 LXM2 02/02/07 1207 607077 The following Analytical Methods were performed Method Description I EML HASL 300,4.5.2.3 2 3 EPA 905.0 Modified EPA 905.0 Modified 71 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Anal3Lsis Company :Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 9, 2007 Contact:.
Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 93 12-0004-016-I Project: YANK01204 Sample ID: 180060017 Client ID: YANKO0l Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pi Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS -67 (25%-I125%)
Carrier/Tracer Recovery GFPC, SrOO, solid-ALL F55 67 (25%-125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected* Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* 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.72 QUALITY CONTROL DATA 73 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary lient : Connecticut Yankee Atomic Power 362 Injun Hollow Rd Renort Date: February 9, 2007 Page 1 of 9 East Hampton, Connecticut ontact: Mr. Jack McCarthy Vorkorder:
180060 irmname id Alpha Spec itch 607169 NOM Sample Qual QC Units RPD%REC% Range Anlst Date Time menicium-24 I urium-242 urium-243/244 QC1201272525 mericium-241 180060008 DUP u 0.0678 Uncert: +/-0.0899 TPU: +/-0.0903 U 0.00 Uncert: +/-0.0624 TPU: +/-0.0624 0.093 Uncert: +/-0.105 TPU: +/-0.106 LCS urium-242 ufium-243/244 QC1201272522 MB mericium-241 11.5 Uncert: TPU: Uncert: TPU: 13.8 Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: U 0.0777+1-0.0956+/-0.0961 U 0.0284+/-0.0557+/-0.0559 U 0.0277+/-0.0542+/-0.0544 11.5+1-1.08+/-1.88 U 0.00+/-0.0531+/-0.0531 13.8+/-1.19+/-2.20 U 0.0233+/-0.0576+/-0.0577 U 0.0279+/-0.0546+/-0.0547 U 0.0549+/-0.0761+/-0.0764 urium-242 pCi/g 14 pCi/g 200 pCi/g 108 pCi/g pCi/g pCi/g pCi/g pGi/g pCi/g pCi/g pCi/g pCi/g (0% -100%)vAXAI 02/05/07 10:44 (0% -100%)(0% -100%)100 (75%-125%)
100 (75%-125%)
urium-243/244 QC1201272524.mericium-241 180060008 MS urium-242 11.8 Uncert: TPU: Uncert: TPU: 14.2 Uncert: TPU: U 0.0678+/-0.0899+/-0.0903 U 0.00+/-0.0624+/-0.0624 0.093+/-0.105+/-0.106 Uj 12.4+/1-.13+/-2.00 0.00+/-0.0536+/-0.0536 13.1+/-1.16+/-2.09 105 (75%-125%)
urium-243/244 92 (75%-125%)
itch 607170 QC1201272527 180060008 DUP lutonium-238 U 0.01 87 U -0.00617 pCi/g 397 (0% -100%) AXAI 02/05/07 10:44 74 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Vorkorder:
180060 Page 2 of 9 itrmname NOM Sample OQual QC Units RPD%REC%Range Anist Date Time id Alpha Spec itch 607170 Iutonium-239/240 QC1201272529 LCS lutonium-238 lutonium-239/240 QC1201272526 MB Iutonium-238 lutonium-239/240 Uncert: +/-0.0497 TPU: +/-0.0497 U -0.00493 Uncert: +1-0.0548 TPU: +1-0.0548 Uncert: TPU: 11.4 Uncert: TPU: Uncert: TPU: Uncert: TPU:+/-0.0519+/-0.0519 U -0.0123+/-0.0532+/-0.0533 U 0.0439+/-0.0701+/-0.0703 10.9+/-1.03+/- 1.61 U 0.0231+/-0.0454+/-0.0454 U 0.0528+/-0.0808+1-0.081 Pci/g 86 pCi/g pCi/g Pci/g PCi/g PCi/g pCi/g (0% -100%)(75%-I 25%)96 (75%-125%)
QC1201272528 180060008 MIS lutonium-238 lutonium-239/240 itch 607171 u 0.0187 Uncert: +/-0.0497 TPU: +/-0.0497 11.8 U -0.00493 Uncert: +/-0.0548 TPU: +/-0.0548 U -1.15 Uncert: +/-5.42 TPU: +/-5.42 0.128+/-0.119+/-0.120 12.5+/-1.14+/-1.83 (75%-I125%)
106 (75%-125%)
QC1201272531 180060008 DUP Iutonium-24 I U 4.55+/-6.78+/-6.80 pCi/g 0 (0% -100%) AXAI 02/06/07 16:16 QC1201272533 LCS lutonium-24 I QC1201272530 MB lutonium-241 134 Uncert: TPU: Uncert: TPU: 134 U Uncert: TPU: 109+/- 10.3+/-14.7 U -0.392+/-5.74+/-5.74 Pci/g Pci/g PCilg 81 (75%-125%)
02/06/07 16:48 02/06/07 16:00 02/06/07 16:32 QC1201272532 180060008 MIS lutonium-241 id Gamma Spec itch 607292 QC1201272699 180060001 DUP ctinium-228
-1.15+/-5.42+/-5.42 128+/-12.0+/-17.4 95 (75%-125%)
0.841+/-0.177 Uncert: 0.951+/-0.138+/-0.138 pCi/g 12 (0% -100%) MIHI 02/05/07 19:42 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Vorkorder:
180060 Page 3 of 9 irmname id Gamma Spec ktch 607292 NOM Sample Qual QC Units RPD%REC % Range Anlst Date Time.mericium-24 1 ismuth-212 ismuth-214 esium-1 34 esiumn- 137 obalt-60 uropium-]
52 uropium- 154 uropium-155 TPU: +1-0.177 u -0.0108 Uncert: +/-0.110 TPU: +/-0.1 10 0.741 Uncert: +/-0.302 TPU: +/-0.302 0.786 Uncert: +/-0.116 TPU: +1-0.116 Ul 0.00 Uncert: +/-0.0336 TPU: +/-0.033 6 0.0493 Uncert: +/-0.039 TPU: +/-0.039 u 0.0103 Uncert: +/-0.0263 TPU: +/-0.0263 u 0.0522 Uncert: +/-0.089 1 TPU: +/-0.0891 u -0.048 Uncert: +/-0.0877 TPU: +/-0.0877 u 0.0559 Uncert: +/-0.0796 TPU: +/-0.0796 0.830 Uncert: +/-0.0875 TPU: +/-0.0875 0.942 Uncert: +/-0.126 TPU: +/-0.126 U 0.0118 Uncert: +/-0.0223 TPU: +/-0.0223 U 0.00166 Uncert: +/-0.0212 TPU: +/-0.0212 13.9 Uncert: +/-1.28 TPU: +/-1.28 0.786 Uncert: +/-0.116 TPU: +/-0.1 16 U -0.001 59 Uncert: +/-0.019 U 0.0463+/-0.049+/-0.049 0.527+/-0.139+/-0.139 0.888+/-0.0953+/-0.0953 UI 0.00+1-0.0175+/-0.0175 0.0421+/-0.0212+/-0.0212 U -0.00208+1-0.0106+/-0.0106 U -0.0197+/-0.033+/-0.033 U 0.0232+/-0.0363+/-0.0363 U 0.0288+/-0.0432+/-0.0432 0.847+/-0.0714+1-0.0714 1.00+/-0.0964+/-0.0964 UI 0.00+/-0.0115+/-0.0115 U -0.00248+/-0.00937
+1-0.00937 14.7+/-0.960+/-0.960 0.888+/-0.0953+1-0. 095 3 U 0.000346+/-0.00893 pCilg 321 pCilg 34 pCilg 12 pCi/g 37 pCi/g 16 pCilg 302 pCi/g 443 pCi/g 572 pCilg 64 pCilg 2 pCilg 6 pCilg 44 pCilg 1000 pCilg 6 pCilg 12 pCilg 311 (0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -20%)(0% -20%)(0% -100%)(0% -100%)(0% -20%)(0% -100%)(0% -100%)ead-21 2 ead-214 Ianganese-54 iobium-94 Dtassium-40 adium-226 ilver-I 08m 7 6 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Vorkorder:
180060 Page 4 of 9 irmname NOM Sample Qua]QC Units RPD%REC%Range Anist Date Time id Gamma Spec itch 607292 hallium-208 TPU: +1-0.019 0.240 Uncert: +/-0.0524 TPU: +/-0.0524+/-0.00893 0.259+/-0.0312+/-0.0312 pCilg 8 (0% -100%)ctiniumn-228 mericium-241 LCS ismuth-21 2 ismuth-214 esium-1 34 esium-1 37 obalt-60 uropium- 152 uropium-154 uropium-1 55 Uncert: TPU: 23.4 Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: 9.48 Uncert: TPU: 13.7 Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: U 0.176+/-0.618+/-0.618 26.3+/-3.14+/-3. 14 U 0.291+/-1.05+/- 1.05 U -0.0684+1-0.235+/-0.235 U 0.0412+/-0.139+/-0.139 9.80+/-0.876+/-0.876 14.6+/-1.13+/-1.13 U 0.0333+/-0.303+/-0.303 U -0.121+/-0.269+/-0.269 U -0.305+/-0.310+/-0.3 10 U -0.136+/-0.198+/-0.198 U -0.0135+/-0.251+/-0.251 U 0.0609+/-0.149+/-0.149 U 0.0443+/-0.117+/-0.117 U -0.161 pCi/g pCi/g Pci/g Pci/g pCi/g pCi/g Pci/g Pci/g Pci/g Pci/g Pci/g PCi/g pCi/g Pci/g Pci/g 103 (75%-125%)
107 (75%-125%)
112 (75%-125%)
02/05/07 16:14 ead-212 ead-214 Ianganese-54 iobium-94 cotassium-40 77 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Vorkorder:
180060 irmname id Gamma Spec itch 607292 Page 5 of 9 REC% Range AnIst Date Time NOM Sample Qual_QC Units RPD%/adium-226 liver-I 08m hallium-208 QC1201272698 ctinium-228 mericiumn-24 I MB ismuth-2 12 ismuth-21 4 esium- 134 esium-1 37 Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU:+/-1.01+/-1.01 U -0.0684+/-0.235+1-0. 235 U 0.067+/-0.117+/-0.117 U 0.00159+/-0.126+/-0.126 U 0.023+/-0.0316+/-0.0316 U -0.00428+/-0.007 89+/-0.00789 U 0.0107+/-0.0697+/-0.0697 U 0.0025+/-0.0321+/-0.0321 U -0.00223+/-0.0114+/-0.0114 U 0.000367+/-0.00873
+/-0.00873 U 0.00472+/-0.0119+/-0.0119 U 0.00821+/-0.021+/-0.021 U 0.00578+/-0.0385+/-0.0385 U 0.0085+/-0.0142+/-0.0142 U 0.000933+/-0.0237+/-0.0237 UT 0.00+/-0.017+/-0.0 17 PCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 02/05/07 19:41 (75%-1 25%)obalt-60 uropium-152 uropium- 154 uropium- 155 ead-21 2 ead-214 78 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Vorkorder:
180060 Page 6 of 9 REC% Rani~e AnIst irmnamne NOM Sample ual OC Units RPD%Date Time id Gamma Spec itch 607292 langanese-54 iobium-94 otassium-40 adium-226 ilver-108m hallium-208 id Gas Flow itch Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: U 0.0039+/-0.00905
+/-0.00905 U 0.0122+/-0.0127+/-0.0127 U 0.155+/-0.118+/-0.1 18 U 0.0025+/-0.0321+/-0.0321 U -0.000433+/-0.00734
+/-0.00734 UI 0.00+/-0.0144+/-0.0144 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 608308 QC1201275064 180060001 DUP trontium-90 QC1201275066 LCS trontium-90 QC 1201275063 M B trontium-90 QC1201275065 180060001 MIS trontium-90 id Liquid Scintillation itch 607147 QC1201272485 180060008 DUP ickel-63 U 0.026 Uncert: +/-0.0226 TPU: +/-0.0226 1.47 Uncert: TPU: U 0.021+/-0.0247+/-0.0247 1.27+/-0.135+/-0.140 U 0.0282+/-0.0248+/-0.0248 U 0.220+/-0.196+/-0.196 pCi/g 0 (0% -100%) KSD1 pCi/g pCi/g pCi/g 86 (75%-125%)
02/09/07 09:47 02/09/07 11:49 02/09/07 09:47 02/09/07 11:50 Uncert: TPU: 12.1 U 0.026 Uncert: +/-0.0226 TPU: +/-0.0226 2* (75%-125%)
U -0.51 Uncert: +/-8.56 TPU: +/-8.56 U -4.16+/-8.95+/-8.95 pCi/g 0 (0% -100%) \IXPI1 02/06/07 14:49 02/06/07 15:21 QC 1201272487 LCS ickel-63 QC 1201272484 M B ickel-63 556 Uncert: TPU: 495+/-22.5+/-28.6 pCi/g pCi/g 89 (75%-125%)
U -1.71 02/06/07 14:33 79 GEL LABORATORIES LLC 2040 Savage Road Chiarleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Vorkorder:
180060 Page 7 of 9 irmname id Liquid Scintillation itch 607147 NOM Sample Qual OC Units RPD%REC %Range AnIst Date Time Uncert: TPU: QC1201272486 180060008 MIS ickel-63 itch 607148 QC1201272489 180060008 DUP on-55 QC1201272491 LCS on-55 QC1201272488 MB on-55 QC1201272490 180060008 NIS on-55 itch 607149 QC1201272493 180060008 DUP ritiurn 585 U Uncert: TPU:+/-8.49+/-8.49 518+/-24.3+/-30.8-0.51+/-8.56+/-8.56 pCilg 89 (75%-125%)
02/06/07 15:05 U -25.7 Uncert: +/-46.1 TPU: +/-46.1 U 9.81+/-46.6+/-46.6 pCi/g 0 (0% -100%) \4XP1 1200 Uncert: TPU: Uncert: TPU: 1230 U Uncert: TPU: 1210+/-70.3+/-97.7 U -36.9+/-42.9+/-42.9 pCilg pCilg pCilg 101 (75%-125%)
02/06/07 16:49 02/06/07 17:22 02/06/07 16:32 02/06/07 17:06-25.7+/-46.1+/-46.1 1300+/-78.2+/- 107 106 (75%-125%)
U 0.792 Uncert: +/-1 .08 TPU: +/-1.08 U 0.231+/-1.02+/-1.02 pCilg 0 (0% -100%) '\XD2 02/03/07 04:57 QC1201272495 LCS ritiurn QCl1201272492 M B ritiurn 6.34 Uncert: TPU: Uncert: TPU: 6.63 U Uncert: TPU: 6.39+1-0.789+/-0.797 U 0.236+1-0.536+/-0.536 pCilg pCilg pCilg 101 (75%-125%)
02/03/07 06:00 02/03/07 04:25 02/03/07 05:29 QC1201272494 180060008 MIS ritiurn itch 607151 QC1201272497 180060008 DUP echnetiurn-99 QC 1201272499 LCS echnetium-99 0.792+/-1.08+/-i n0X 6.25+/-1.39+/-1 19 94 (75%-125%)
u 0.142 Uncert: +/-0.183 TPU: +/-0.183 16.7 Uncert: TPU: U 0.168+/-0.194+/-0.194 15.3+/-0.623+/-0.730 pCilg 0 (0% -100%) VIXPI 02/07/07 15:37 02/07/07 16:24 pCilg 92 (75%-125%)
R0 GEL LABORATORIES LLC 2040 Savage Road Chiarleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Vorkorder:
180060 Page 8 of 9 Ranige Anist irmname ud Liquid Scintillation itch 607151 QC 1201272496 M B echnetium-99 QC1201272498 180060008 MS echnetium-99 itch 607153 QC1201272505 180060008 DUP arbon- 14 QC1201272507 LCS arbon- 14 NOM Uncert: TPU: 16.9 U Uncert: TPU: Sample Qual OC Units RPD% REC%Date Time U 0.219+/-0.185+/-0.185 pCilg pCi/g 02/07/07 15:05 02/07/07 16:08 0.142+/-0.183+/-0.183 U 0.00632 Uncert: +/-0.0894 TPU: +/-0.0894 U 15.7+/-0.678+/-0.7 83 0.0751+/-0.0914+/-0.0914 6.61+/-0.181+/-0.208 93 (75%-125%)
pCilg 0 (0% -100%) AkXD2 QC1201272504 MB arbon-14 6.65 Uncert: TPU: Uncert: TPU: U 0.00424+/-0.0855+/-0. 085 5 pCilg pCilg pCilg 99 (75%-125%)
02/03/07 05:06 02/03/07 07:09 02/03/07 04:04 02/03/07 06:08 QC1201272506 180060008 MIS arbon-14 6.81 U 0.00632 Uncert: +/-0.0894 TPU: +/-0.0894 6.89+/-0.187+/-0.216 101 (75%-125%)
4otes: Fhe Qualifiers in this report are defined as follows: A B BD C D H J N/A ND R U UI A quality control analyte recovery is outside of specified acceptance criteria Analyte is a surrogate compound Result is less than value reported Result is greater than value reported The TIC is a suspected aldol-condensation product For General Chemistry and Organic analysis the target analyte was detected in the associated blank.Results are either below the MDC or tracer recovery is low Analyte has been confirmed by CC/MS analysis Results are reported from a diluted aliquot of the sample Analytical holding time was exceeded Value is estimated Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more Analyte concentration is not detected above the detection limit Sample results are rejected Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.Gamma Spectroscopy--Uncertain identification Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier 81I GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Vorkorder:
180060 Page 9 of 9 irmname NOM Sample Qua] QC Units RPD% REC% Range Anist Date Time x Y QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +/-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded VIA indicates that spike recovery limits do not apply when sample concentration exceeds spike conc. by a fact6r 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 imple is greater than five times (5X) the contract required detection limit (RL). In cases where either the sample or duplicate value is!ss than 5X the RL, a control limit of +/- the RL is used to evaluate the DUP result.or PS, PSD, and SDILT results, the values listed are the measured amounts, not final concentrations.
Vhere the analytical method has been performed under NELAP certification, the analysis has met all of the ,quirements of the NELAC standard unless qualified on the QC Summary.832 General Narrative I General Narrative for Connecticut Yankee Atomic Power Co.Work Order: 180812 SDG: MSR#07-0079 February 19,2007 Laborator~y Identification:
GEL Laboratories LLC 2040 Savage Road Charleston, South Carolina 29407 (843) 556-8171 Summary Sample receipt The samples arrived at GEL Laboratories LLC, Charleston, South Carolina on February 16, 2007 for analysis.Shipping container temperatures were checked, documented, and within specifications.
The samples were delivered with proper chain of custody documentation and signatures.
All sample containers arrived without any visible signs of tampering or breakage.Sample Identification The laboratory received the following samples: Laboratory Sample Identification Description 180812001 9312-0004-0171 180812002 9312-0004-0181 180812003 9312-0004-0191 180812004 9312-0004-0201 180812005 9312-0004-0211 Items of Note There are no items to note.Case Narrative Sample analyses were conducted using methodology as outlined in GEL Laboratories, LLC (GEL) Standard Operating Procedures.
Any technical or administrative problems during analysis, data review, and reduction are contained in the analytical case narratives in the enclosed data package.Analytical Request Five soil samples were analyzed for FSSGAM and Strontium-90.
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.
GEL Laboratories u..c PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 543.7565.1178 2 www.gal~com 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.
Project Manager GEL Laboratories LLc GELLaortoresuc PO Box 30712 Charleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.558.8171 F5843.765.1178 3 www.gal.com List of current GEL Certifications as of 19 February 2007 State Certification Alaska UST-062 Arizona AZ0668 Arkansas88-065 1 CLIA 42DO904046 California 01151CA Colorado GenEngLabs Connecticut PH-01 69 Dept. of Navy NFESC 413 EPA WG-15J Florida/NELAP E87156 Georgia E87 156 (FL/NELAP)
Hawaii N/A Idaho N/A Illinois 200029 Indiana C-SC-01 Kansas E-10332 Kentucky 90129 Louisiana 03046 Maryland 270 Massachusetts M-SCO1 2 Michigan 9903 Nevada SCI2 New Jersey SCO02 New Mexico FL NELAP E87 156 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 T]04704235-06-TX U.S. Dept. of Agriculture S-52597 US Army Corps of Engineer N/A Utah 8037697376 GEL Vermont VT87 156 Virginia Washington 00151 C1641 4 Chain of Custody and Supporting Documentation 9
Connecticut Yankee Atomic Power Company Chain of Custody Foirm No. 2007-00038 362 Injun Hollow Road, East Hampton, CT 06424 860-267-2556
_____ ______________________
Project Name: Haddam Neck Decommissioning
--Analyses Requested Lab Use On-ly Contact Name & Phone: Comments: JcMcaty860-267-3924 Media Sample Container Jak c~rtyCode 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)
C Prorthe: LI 30 D. F-1 15 D. Z 7 D.Sample Designation Date Time I ý4 ý44 1 1 Comment, Preservation Lab Sample ID 9312-0004-0171 2/13/07 1350 TS G BP X.__ ___________
_______9312-0004-0181 2/13/07 1355 TS G BP X _______________________
9312-0004-0191 2/13/07 1356 TS G BP X _____ ____________________
9312-0004-0201 2/13/07 1400 TS G BP X _________________
9312-0004-0211 2/13/07 1401 TS G BP X______________
NOTES: PO #: 002332 MSR #: 07-0079 Z LTP QA El Radwaste QA LI Non QA Samples Shipped Via: Internal Container SFed Ex Temp.: ~IDeg. C fUPS El Hand Cu-q 5 dy Sealed?1) Relinquishd7
~ Date/Time
- 2) Received By Date/Time%
Custody Seal Intact?CA -ý -2/ .DJ-0 530 I:l Other 3) Relinquished By 7Date/Timne
- 4) Received By Date/Time Bl fLdn 5) Relinquished By Date/Time
- 6) Received By Date/Time Connecticut Yankee -Statement of Work for AnalyXtical Lab Services -CY-4SC-SOW7VOjl Figure 1. -Sample Check-in List.Datle/Time Received:
40 -)t 7 3)SDG#:_S917 Work Order Number: I t--*Shipping, Cchtainer ID:?'1 2 'i ~V1 7)O3Chain of Custo~dy # -s)0Q -COO '3 I. Custody Seals. onT shipping container intact?..-e 4o(2. Custody Seats dated and signed? Yes N)~o 11 3. Chain-of-Custody record present? Yes ,ioj.4, Cooler-temperature
.S. VcWriiculitelpack Ing materials is: .Wet[Cj Dry[ (,I AAI'C. Number of Samples in shipping container.
____________________
- 7- Sample hol. ding times exceeded?
- Yes [JNo -.8. .Samples have:'jape hazard labels-custody seals -appropriate sample labels 9. Samples are: iiigood condition -l..eaking
-~broken -have air bubbles 10. Were any anomalies identified in sample receipt? Yes liNOW(J* i. -.Decritio ofanoalies.(include sample numbeirs):
$ample. CustoianfLaboratozy..I
-~- D t.~ 1U ) Ck3 Telephoned to.~0 B'7 SW 0 SAMPLE RECEIPT & REVIEW FORM PM use only Client: Cca{yClj u') +- ýZw "e SDG/ARCOCIWork Order: k gt2 Date Received:
~4- ~=~PM(A) Re~view uure non-conforming items are resolved prior to signing):&Received By:I Sample Receipt Criteria Z z Comments/Qualifiers (Required for Nonl-Conforming Items)1 Sh -ipping containers received Circle Applicable:
seals broken damaged container leaking container other (describe) intact and sealed? L___________________/________
Samples. requiring cold Circle Coolant # ice bags blue ice dry ice other describe)2 preservation within (4 +1- 2CQ?Record preservation method. ___ I___________________________
3Chain of custody documents included with shipment?
______________/____________
4 Sample containers intact and Circle Applicable:
seals broken damaged container leaking container other (describe)
_sealed? ________/_______________I______
5 Samples requiring chemical Sample ID's. containers affected and observed pH: preservation at proper pH?____________________________
6 VO vils ree f hadsaceSample ID's and-containers affected:-(defined as < 6mm bubble)? _________________________
Are Encore containers present?7 (If yes, immediately deliver to__VOA laboratory)
_________________________
8 Samples received within holding Id's and tests affected: time? ______________________________
9 Sample ID's on COC match ID's Sample ID's and containers affected: on bottles?10Date & .time on COC match date Sample 113's affected: 10& time on bottles?____________________________
11Number of containers received Sample ID's affected: match number indicated on COC?11COC for is properly signed in 12relinquished/received sections?14Air Bill ,Tracking
- 's, & 7LAY~ )' ?00c3 14Additional Comments 9" -7 G ~~~RSO RAD Receipt #_____________
Sod~. Haar Inomain2 *If > x2 area background is observed on samples identified as "non-Suspecte Haar Inomton 9 E -regulated/non-radioactive", contact the Radiation Safety group for futhffer cz i investigation.
A Radiological Classification?
--Maximum Counts Observed*:
BPCB Regulated?
S hipped as DOT Hazardous j~CMaterial?
If yes, contact Waste Hazard Clas Shipped: lManager or ESH Manager. UN!#: D3 Regulated as a Foreign Soil?-PM (or PMA) review of Hazard classification:
L-~ Initials -Date: N2 -.6-7 R Data Review Qualifier Definitions 9
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* Result is greater than value reported RPD of sample end duplicate evaluated using +/-RL. Concentrations are <5X the RL A The TIC is a suspected aldol-condensation product B Target analyte was detected in the associated blank B Metals-Either presence of analyte detected in the associated blank, or MDL/IDL < sample value < PQL BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample d 5-day BOD-The 2:1 depletion requirement was not met for this sample E Organics-Concentration of the target analyte exceeds the instrument calibration range E Metals-%difference of sample and SD is >10-. Sample concentration must meet flagging criteria H Analytical holding time was exceeded h Preparation or preservation holding time was exceeded J Value is estimated 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 UT Gamma Spectroscopy-Uncertain identification X Consult Case Narrative, Data Summery package, or Project Manager concerning this qualifier Y QC Samples were not spiked with this compound Z Paint Filter Test-Particulates passed through the filter, however no free liquids were observed.GEL Laboratories LLc PO Box 30712 Chafleston, SC 29417 2040 Savage Road Charleston, SC 29407 P 843.556.8171 F 843.766.1178 www.gol~com I10 RADIOLOGICAL ANALYSIS 11 Radiochemistry Case Narrative Connecticut Yankee Atomic Power Co. (YANK)Work Order 180812 Method/Analysis Information Product: Analytical Method: Prep Method: Analytical Batch Number: Prep Batch Number: Sample ID 180812001 180812002 180812003 180812004 180812005 1201280354 1201280355 1201280356 Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived EML HASL 300, 4.5.2.3 Dry Soil Prep 610737 610663 Client ID 9312-0004-0171 9312-0004-0181 9312-0004-0191 9312-0004-0201 9312-0004-0211 Method Blank (MB)180812001(9312-0004-0171)
Sample Duplicate (DUP)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-013 REV# 13.Calibration Information:
Calibration Information All initial and continuing calibration requirements have been met.Standards Information Standard solution(s) for these analyses are NIST traceable and used before the expiration date(s).Sample Geometry All counting sources were prepared in the same geometry as the calibration standards.
12 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: 180812001 (9312-0004-0171).
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 U'U'Data rejected due to high peak-width.
Data rejected due to low abundance.
Analyte Cobalt-60 Cesium- 134 Sample 180812005 180812001 180812002 180812003 180812004 180812005 180812003 1201280354 Europium-I 55 Cesium- 137 U'Data rejected due to no valid peak.13 Method/Analysis Information Product: GFPC, Sr90, solid-ALL FSS Analytical Method: EPA 905.0 Modified Prep Method: Dry Soil Prep GL-RAD-A-021 Method: Analytical Batch Number: Prep Batch Number: Dry Soil Prep GL-RAD-A-021 Batch Number: Ash Soil Prep Dry Soil Prep 610704 610665 610663 Sample ID 180812001 180812002 180812003 180812004 180812005 1201280317 1201280318 1201280319 1201280320 Client ID 9312-0004-0171 9312-0004-0181 9312-0004-0191 9312-0004-0201 9312-0004-0211 Method Blank (MB)180812001(9312-0004-0171)
Sample Duplicate (DUP)180812001(9312-0004-0171)
Matrix Spike (MS)Laboratory Control Sample (LCS)SOP Reference Procedure for preparation, analysis and reporting of analytical data are controlled by GEL Laboratories LLC as Standard Operating Procedure (SOP). The data discussed in this narrative has been analyzed in accordance with GL-RAD-A-004 REV# 11.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 14 The blank volume is representative of the sample volume in this batch.Designated QC The following sample was used for QC: 180812001 (93 12-0004-0171).
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 Al.1 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.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:
is K4&6" ZN10, Reviewer/Date:-
16 SAMP-LE DATA
SUMMARY
17 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Report for YANK001 Connecticut Yankee Atomtic Power Co.Client SDG: MSR#07-0079 GEL Work Order: 180812 The Qualifiers in this report are defined as follows:*A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification ND The analyte concentration is not detected above the detection limit.The above sample is reported on a dry weight basis except where prohibited by the analytical procedure.
Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the Certificate of Analysis.This data report has been prepared and reviewed in accordance with GEL Laboratories LLC standard operating procedures.
Please direct any questions to your Project Manager, Cheryl Jones.Reviewed byW 18 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils P04* 002332 Report Date: February 21, 2007 Client Sample ID: 9312-0004-0171 Project: YANK01204 Sample ID: 180812001 Client ID: YANKO0l Matrix: TS Vol. Recv.: Collect Date: 13-FEB-07 Receive Date: 16-FEB-07 Collector:
Client Moisture:
5.63%Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P~Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.656 +1-0.114 0.0321 +/-0.114 0.0641 pCi/g MJHI 02/17/07 1316 610737 Americium-241 U 0.0484 +/-0.0578 0.0475 +/-0.0578 0.0949 pCi/g Bismuth-212 0.387 +/-0.122 0.0644 +/-0.122 0.129 pCi/g Bismuth-214 0.510 +1-0.0659 0.0165 +/-0.0659 0.0329 pCi/g Cesium-134 UI 0.00 +1-0.0156 0.0105 +/-0.0156 0.0209 pCi/g Cesium-137 0.188 +/-0.0252 0.00908 +/-0.0252 0.0181 pCi/g Cobalt-60 0.219 +/-0.0304 0.00872 +/-0.0304 0.0174 pCi/g Europium-152 U -0.0101 +/-0.0386 0.0233 +/-0.0386 0.0465 pCi/g Europium-154 U -0.00744 +/-0.0334 0.0277 +/-0.0334 0.0553 pCi/g Europium-ISS U 0.0321 +/-0.0338 0.0264 +/-0.0338 0.0528 pCi/g Lead-212 0.683 +/-0.0607 0.0134 +/-0.0607 0.0267 pCi/g Lead-214 0.612 +/-0.0654 0.0163 +/-0.0654 0.0326 pCi/g Manganese-54 U 0.0107 +/-0.0116 0.00887 +/-0.0116 0.0177 pCi/g Niobium-94 U 0.00043 +/-0.00954 0.00803 +/-0.00954 0.0161 pCi/g Potassium-40 11.0 +/-0.843 0.0675 +/-0.843 0.135 pCi/g Radium-226 0.5 10 +/-0.0659 0.0165 +/-0.0659 0.0329 pCi/g Silver-I 08m U 0.00776 +/-0.00867 0.00779 +/-0.00867 0.0156 pCi/g Thallium-208 0.200 +/-0.0274 0.00857 +/-0.0274 0.0171 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 U -0.0148 +/-0.0185 0.0181 +/-0.0185 0.0428 pCi/g KSDI 02/20/07 1133 610704 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 02/16/07 1032 610663 The following Analytical Methods were performed Method Description I EML HASL 300, 4.5.2.3 2 EPA 905.0 Modified 19 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analy:sis Company :Connecticut Yankee Atomic Power Address : 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 21, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-0171 Project: YANK01204 Sample ID: 180812001 Client ID: YANKO0l Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr9O, solid-ALL FSS 75 (25%-125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 75 (25%-125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GCJMS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* QC Samples were not spiked with this compound A RPD of sample and duplicate evaluated using +f-RL. Concentrations are <5X the RL h Preparation or preservation holding time was exceeded The above sample is reported on a dry weight basis.20 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 21, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 9312-0004-0181 180812002 TS 1 3-FEB-07 1 6-FEB-07 Client 7.22%Project: Client ID: Vol. Recv.: YANKO01204 YANKOO I Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P~Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.753 +/-0.140 0.0393 +/-0.140 0.0785 pCi/g MJHI 02/17/07 1316 610737 Americium-241 U 0.0326 +1-0.0219 0.0179 +/-0.0219 0.0358 pCi/g Bismuth-212 0.459 +/-0.148 0.0897 +/-0.148 0.179 pCi/g Bismuth-214 0.690 +/-0.0878 0.0222 +/-0.0878 0.0444 pCi/g Cesium-134 UI 0.00 +/-0.0217 0.0148 +/-0.0217 0.0295 pCi/g Cesium-137 0.196 +/-0.0314 0.0125 +/-0.0314 0.0249 pCi/g Cobalt-60 U 0.0162 +/-0.0198 0.0116 +/-0.0198 0.0232 pCi/g Europium-152 U -0.0327 +/-0.0415 0.0292 +/-0.0415 0.0583 pCi/g Europium-154 U -0.0171 +/-0.0416 0.0342 +/-0.0416 0.0683 pCi/g Europium-ISS U 0.00311 +/-0.0413 0.0274 +/-0.0413 0.0548 pCi/g Lead-212 0.739 +/-0.0779 0.0157 +/-0.0779 0.0313 pCi/g Lead-214 0.658 +/-0.0783 0.0211 +/-0.0783 0.0422 pCi/g Manganese-54 U 0.01 25 +/-0.0124 0.0113 +/-0.0124 0.0226 pCi/g Niobium-94 U 0.0109 +/-0.0129 0.011I +/-0.0129 0.0221 pCi/g Potassium-40 11.4 +/-0.786 0.0998 +/-0.786 0.200 pCi/g Radium-226 0.690 +/-0.0878 0.0222 +/-0.0878 0.0444 pCi/g Silver-I 08m U -0.0106 +/-0.0119 0.0101 +/-0.0119 0.0201 pCi/g Thallium-208 0.250 +/-0.0382 0.0116 +/-0.0382 0.0231 *pCi/g Rad Gas Flow Proportional Counting GFPC, SO9O, solid-ALL ESS Strontium-90 U -0.00454 +/-0.0201 0.0177 +/-0.0201 0.0422 pCi/g KSDI 02/20/07 1133 610704 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 IMBI1 02/16/07 1032 610663 The following Analytical Methods were performed Method Description I EML HASL 300,4.5.2.3 2 EPA 905.0 Modified Surrogate/Tracer recovery Test Recovery%
Acceptable Limits 21 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 21, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-0181 Project: YANKO01204 Sample ID: 180812002 Client ID: YANKOOI Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pi Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, SrOO, solid-ALL FSS 76 (25%-125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 76 (25%-125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.Ul Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* 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.22 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address :362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 21, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 93 12-0004-0191 180812003 TS 1 3-FEB-07 16-FEB-07 Client 9.77%Project: Client ID: Vol. Recv.: YANK01204 YANKOO 1 Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P~Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 Ingrowth Waived Actinium-228 0.781 +/-0.114 0.0205 +/-0.114 0.0409 pCi/g MJHI 02/17/07 1317 610737 Americium-241 U 0.00859 +/-0.0563 0.0453 +/-0.0563 0.0905 pCi/g Bismuth-212 0.368 +/-0.139 0.0482 +/-0.139 0.0964 pCi/g Bismuth-2 14 0.608 +/-0.0685.
0.0132 +/-0.0685 0.0263 pCi/g Cesium-134 UI 0.00 +/-0.0152 0.00848 +/-0.0152 0.0169 pCi/g Cesium-1 37 0.0762 +/-0.0146 0.00666 +/-0.0146 0.0133 pCi/g Cobalt-60 U 0.0125 +/-0.00794 0.0072 +/-0.00794 0.0144 pCi/g Europium-152 U 0.0114 +/-0.0271 0.0185 +/-0.0271 0.0369 pCi/g Europium-154 U 0.0145 +/-0.0282 0.0207 +/-0.0282 0.0415 pCi/g Europium-155 UI 0.00 +/-0.0337 0.0249 +/-0.0337 0.0497 pCi/g Lead-21 2 0.776 +/-0.0666 0.011 +/-0.0666 0.022 pCi/g Lead-214 0.686 +/-0.0658 0.0129 +/-0.0658 0.0258 pCi/g Manganese-54 U 0.013 +/-0.0121 0.00703 +/-0.0121 0.0141 pCi/g Niobium-94 U 0.00263 +/-0.00767 0.00648 +/-0.00767 0.013 pCi/g Potassium-40 11.0 +/-0.712 0.0581 +/-0.7 12 0.116 pCi/g Radium-226 0.608 +/-0.0685 0.0132 +/-0.0685 0.0263 pCi/g Silver-108m U -0.0027 +/-0.00701 0.00601 +/-0.00701 0.012 pCi/g Thallium-208 0.237 +/-0.0275 0.00649 +/-0.0275 0.013 pCi/g Rad Gas Flow Proportional Counting GFPC, Sr9O, solid-ALL FSS Strontium-90 U 0.00873 +/-0.0232 0.0179 +/-0.0232 0.0431 pCi/g KSDI 02/20/07 1133 610704 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 02/16/07 1032 610663 The following Analytical Methods were performed Method Description I EML HASL 300,4.5.2.3 2 EPA 905.0 Modified Surrogate/Tracer recovery Test Recovery%
Acceptable Limits 23 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 21, 2007 Contact, Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 9312-0004-0191 Project: YANK01204 Sample ID: 180812003 Client ID: YANKO0l Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pi Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 .GFPC, Sr9O, solid-ALL FSS 70 (25%-125%)
Carrier/Tracer Recovery GFPC, Sr9O, solid-ALL FSS 70 (25%-125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound*c Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by CC/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 ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* 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.24 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company : Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 21, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 9312-0004-0201 180812004 TS 13-FEB-07 16-FEB-07 Client 9.93%Project: Client ID: Vol. Recv.: YANK01204 YANKOO I Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P'Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.719 +1-0.109 0.0369 +/-0.109 0.0737 pCilg MIHI 02/17/07 1317 610737 Americium-241 U 0.0224 +/-0.0184 0.0136 +/-0.0184 0.0272 pCilg Bismuth-212 0.457 +/-0.185 0.074 +/-0.185 0.148 pCi/g Bismuth-214 0.567 +/-0.0806 0.0189 +/-0.0806 0.0377 pCi/g Cesium-] 34 UI 0.0301 +/-0.0167 0.0134 +/-0.0167 0.0268 pCi/g Cesium-137 0.0809 +/-0.0211 0.00984 +/-0.0211I 0.01 97 pCi/g Cobalt-60 U 0.0141 +/-0.0147 0.0129 +/-0.0147 0.0258 pCi/g Europium-152 U -0.00691 +/-0.0425 0.0248 +/-0.0425 0.0496 pCi/g Europium-154 U 0.0215 +/-0.0502 0.0369 +/-0.0502 0.0738 pCi/g Europium-ISS U 0.0418 +/-0.0322 0.0216 +/-0.0322 0.0432 pCi/g Lead-21 2 0.692 +/-0.0672 0.013 +/-0.0672 0.0261 pCi/g Lead-214 0.596 +/-0.073 0.0174 +/-0.073 0.0347 pCi/g Manganese-54 U 0.00273 +/-0.0125 0.0108 +/-0.0125 0.0216 pCi/g Niobium-94 U -0.00124 +/-0.0118 0.0102 +/-0.0118 0.0204 pCi/g Potassium-40 10.4 +/-0.565 0.071 +/-0.565 0.142 pCi/g Radium-226 0.567 +/-0.0806 0.0189 +/-0.0806 0.0377 pCi/g Silver-108m U -0.00743 +/-0.0103 0.00857 +/-0.0103 0.0171 pCi/g Thallium-208 0.241 +/-0.0322 0.00982 +/-0.0322 0.0196 pCi/g Rad Gas Flow Proportional Counting GFPC, SO9O, solid-ALL FSS Strontium-90 U -0.00553 +/-0.0207 0.0184 +/-0.0207 0.0438 pCi/g KSDI 02/20/07 1133 610704 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 02/16/07 1032 610663 The following Analytical Methods were performed Method Description I EML HASL 300,4.5.2.3 2 EPA 905.0 Modified Surrogate/Tracer recovery Test Recovery%
Acceptahle Limits 25 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company :Connecticut Yankee Atomic Power Address 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date: February 21, 2007 Contact& Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 93 12-0004-0201 Project: YANK01204 Sample ID: 180812004 Client ID: YANKOGI Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch D~Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr9O, solid-ALL FSS 67 (25%-1 25%)Carrier/Tracer Recovery GFPC, Sr9O, solid-ALL FSS 67 (25%-] 25%)Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma Spectroscopy--Uncertain identification
- Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* 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.
GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Report Date: February 21, 2007 Client Sample ID: Sample ID: Matrix: Collect Date: Receive Date: Collector:
Moisture: 9312-0004-0211 180812005 TS 13-FEB-07 16-FEB-07 Client 9.35%Proiect: Client ID: Vol. Recv.: YANKO 1204 YANKO0 I Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch Pi Rad Gamma Spec Analysis Gamma,Solid-FSS GAM & ALL FSS 226 In growth Waived Actinium-228 0.754 +/-0.107 0.0203 +/-0.107 0.0405 pCi/g MJHI 02/17/07 1317 610737 Americium-241 U 0.053 +/-0.033 0.0272 +/-0.033 0.0543 pCi/g Bismuth-212 0.474 +/-0.118 0.0434 +/-0.118 0.0868 pCi/g Bismuth-214 0.521 +/-0.0616 0.0114 +/-0.0616 0.0227 pCi/g Cesium-134 UI 0.00 +/-0.0114 0.00754 +/-0.0114 0.0151 pCi/g Cesium-137 0.128 +/-0.0158 0.00608 +/-0.0158 0.0122 pCilg Cobalt-60 UI 0.00 +/-0.0122 0.00597 +/-0.0122 0.0119 pCi/g Europium-152 U -0.00262 +/-0.0282 0.017 +/-0.0282 0.0339 pCi/g Europium-154 U 0.0157 +/-0.0242 0.018 +/-0.0242 0.0359 pCi/g Europium-ISS U 0.0261 +/-0.0297 0.0205 +/-0.0297 0.041 pCi/g Lead-212 0.706 +/-0.0583 0.0102 +/-0.0583 0.0203 pCi/g Lead-214 0.612 +/-0.0631 0.0122 +/-0.0631 0.0243 pCi/g Manganese-54 U 0.00876 +/-0.0139 0.00604 +/-0.0139 0.0121 pCi/g Niobium-94 U 0.00645 +/-0.00697 0.00598 +/-0.00697 0.012 pCi/g Potassium-40 11.2 +/-0.720 0.0514 +/-0.720 0.103 pCi/g Radium-226 0.521 +/-0.0616 0.0114 +/-0.0616 0.0227 pCi/g Silver-lO8m U -0.00267 +/-0.00662 0.0057 +/-0.00662 0.0114 pCi/g Thallium-208 0.226 +/-0.026 0.00587 +/-0.026 0.0117 pCi/g Rad Gas Flow Proportional Counting GFPC, SO9O, solid-ALL ESS Strontium-90 U -0.0246 +/-0.0148 0.0172 +/-0.0148 0.0409 pCi/g KSDI 02/20/07 1133 610704 The following Prep Methods were performed Method Description Analyst Date Time Prep Batch Dry Soil Prep Dry Soil Prep GL-RAD-A-021 JMBI 02/16/07 1032 610663 The following Analytical Methods were performed Method Description I EML HASL 300,4.5.2.3 2 EPA 905.0 Modified Surrogate/Tracer recovery Test Recovery%
Acceptable Limits 27 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com Certificate of Analysis Company: Connecticut Yankee Atomic Power Address: 362 Injun Hollow Rd East Hampton, Connecticut 06424 Report Date:. February 21, 2007 Contact: Mr. Jack McCarthy Project: Soils PO# 002332 Client Sample ID: 93 12-0004-0211 Project: YANKOI2O4 Sample ID: 180812005 Client ID: YANKO0l Vol. Recv.: Parameter Qualifier Result Uncertainty LC TPU MDA Units DF Analyst Date Time Batch P Surrogate/Tracer recovery Test Recovery%
Acceptable Limits Strontium-90 GFPC, Sr90, solid-ALL FSS 79 (25%-125%)
Carrier/Tracer Recovery GFPC, Sr90, solid-ALL FSS 79 (25%-I125%)
Notes: The Qualifiers in this report are defined as follows* A quality control analyte recovery is outside of specified acceptance criteria**Analyte is a surrogate compound* Result is less than value reported* Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC/MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.Ul Gamma Spectroscopy--Uncertain identification X Consult Case Narrative, Data Summary package, or Project Manager concerning this qualifier* 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.28 QUALITY CONTROL DATA 29 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Client: Connecticut Yankee Atomic Power 362 Injun Hollow Rd Renort Date: February 21, 2007 Page 1 of 5 East Hampton, Connecticut Contact: Mr. Jack McCarthy Workorder:
180812 Parinname NOM Sample Oual OC Units RPD%REC% Ran2e Anlst Date Time Rad Gamma Spec Batch 610737 Actinium-228 Americium-24 I Bismuth-2 12 Bismuth-2 14 Cesium-I 134 Cesium- 137 Cobalt-60 Europium-I 52 Europium-154 Europium-155 Lead-212 180812001 DUP 0.656 Uncert: +/-0.114 TPU: +/-0.114 U 0.0484 Uncert: +/-0.0578 TPU: +/-0.0578 0.387 U ncert: +/-0.122 TPU: +/-0.122 0.5 10 Uncert: +/-0.0659 TPU: +/-0.0659 U 1 0.00 Uncert: +/-0.0156 TPU: +/-0.0156 0.188 Uncert: +/-0.0252 TPU: +/-0.0252 0.2 19 Uncert: +/-0.0304 TPU: +/-0.0304 U -0.0101 Uncert: +/-0.0386 TPU: +/-0.0386 u -0.00744 Uncert: +/-0.0334 TPU: +/-0.0334 U 0.0321 Uncert: +/-0.0338 TPU: +/-0.0338 0.683 Uncert: +/-0.0607 TPU: +/-0.0607 0.612 Uncert: +/-0.0654 TPU: +/-0.0654 u 0.0107 Uncert: +/-0.0116 TPU: +/-0.01 16 U 0.00043 Uncen: +/-0.00954 TPU: +/-0.00954 0.76 1+/-0.144+/-0.144 U 0.0675+/-0.0802+/-0.0802 0.461+/-0.226+/-0.226 0.539+/-0.0945+/-0.0945 U 0.0326+/-0.0202+/-0.0202 0.227+/-0.041+/-0.041 0.224+/-0.0424+/-0.0424 U -0.0261+/-0.0586+/-0.0586 U -0.0124+/-0.0545+/-0.0545 U 0.0512+/-0.0547+/-0.0547 0.666+/-0.0734+/-0.0734 0.595+/-0.0883+/-0.0883 U 0.0172+/-0.0204+/-0.0204 U 0.00147+/-0.016+/-0.0 16 pCi/g 15 pCi/g 33 pCilg 17 pCi/g 6 pCi/g 33 pCilg 19 pCi/g 2 pCi/g 88 pCi/g 50 pCi/g 46 pCi/g 3 pCi/g 3 pCi/g 46 pCi/g 110 (0% -100%) MIHI 02/19/07 09:14 (0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -100%)(0% -20%)(0% -20%)(0% -100%)(0% -100%)Lead-214 Manganese-54 Niobium-94 30 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:
180812 Page 2 of 5 Parmname NOM Sample Qua] QC Units RPD% REC% Range AnIst Date Time Rad Gamma Spec Batch 610737 Potassium-40 Radium-226 Silver- lO8m Thallium-208 QC1201280356 Actinium-228 Americium-24 I 11.0 Uncert: +/-0.843 TPU: +/-0.843 0.510 Uncert: +/-0.0659 TPU: +/-/-0.0659 u 0.00776 Uncert: +/-0.00867 TPU: +/-0.00867 0.200 Uncert: +/-0.0274 TPU: +/-0.0274 LCS Bismuth-212 Bismuth-214 Cesium- 134 Cesium- 137 Uncert: TPU: 23.4 Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: 9.47 Uncert: TPU: 13.6 Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: 11.1+/-0.952+/-0.952 0.539+/-0.0945+/-0.0945 U -0.00815+/-0.0167+/-0.0167 0.2 14+/-0.0422+/-0.0422 U 0.375+/-0.617+/-0.617 24.8+/-2.84+/-2.84 U 0.529+/-0.984+/-0.984 U -0.0269+/-0.219+/-0.219 U -0.0253+/-0.162+/-0.162 9.76+/-0.885+/-0.885 14.5+/-1.13+/-1.13 U 0.0784+/-0.296+/-0.296 U 0.0374+/-0.284+/-0.284 U 0.205+/-0.308+/-0.308 U 0.0384+/-0.161+/-0.161 U -0.0579+/-0.223 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pci/g 02/19/07 09:20 pCi/g I pCi/g 6 pCi/g 8090 pCi/g 7 106 (75%-125%)
(0% -20%)(0% -100%)(0%- 100%)(0%- 100%)103 (75%-125%)
106 (75%-125%)
Cobalt-60 Europium-152 Europium-154 Europium-155 Lead-212 Lead-214 IT GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:
180812 Page 3 of 5 Parmname NOM Sample Qual OC Units RPD% REC% Range Anist Date Time Rad Gamma Spec Batch 610737 TPU: Manganese-54 Niobium-94 Potassium-40 Radium-226 Silver- 108m Thallium-208 QC1 201280354 Actinium-228 Americium-24 1 Bismuth-2 12 Bismuth-214 Cesium- 134 Cesium- 137 Cobalt-60 Europium-152 Europium-I 54 Europium-155 MB Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU:+/-0.223 U -0.035+/-0.136+/-0.136 U -0.0694+/-0.135+/-0.135 U 0.510+1-0.944+/-0.944 U -0.0269+/-0.219+/-0.219 U 0.0725+/-0.175+/-0.175 U -0.0252+/-0.121+/-0.121 U -0.0283+/-0.106+/-0.106 U -0.275+/-0.0446+/-0.0446 U 0.0239+/-0.2 15+/-0.215 U 0.0109+/-0.0598+/-0.0598 U -0.00686+/-0.0273+/-0.0273 UI 0.00+/-0.0261+/-0.0261 U 0.0305+/-0.0273+/-0.0273 U -0.076+/-0.0739+/-0.0739 U -0.0483+/-0.0728+/-0.0728 U 0.031 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pci/g (75 %-125%)02/19/07 09:13 32 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:
180812 Parmname Rad Gamma Spec Batch 610737 Page 4 of 5 Range Anist Date Time NOM Sample Qual OC Units RPD% REC%Lead-212 Lead-214 Manganese-54 Niobium-94 Potassiumn-40 Radiumn-226 Silver-I 08m Thallium-208 Rad Gas Flow Batch Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU: Uncert: TPU:+/-0.0506+/-0.0506 U 0.0329+/-0.0555+/-0.0555 U -0.0535+/-0.0519+/-0.0519 U -0.0373+/-0.0243+/-0.0243 U 0.00643+/-0.0245+/-0.0245 U 0.124+/-0.306+/-0.306 U 0.0109+/-0.0598+/-0.0598 U 0.00645+/-0.0205+/-0.0205 U 0.00571+/-0.0305+/-0.0305 pCi/g pCilg pCilg pCilg pCilg pCilg pCi/g pCi/g 610704 QC1201280318 180812001 DUP Strontiumn-90 Q01201280320 LCS Strontium-90 QC1201280317 MB Strontiumn-90 QC1201280319 180812001 MS Strontium-90 U -0.0148 Uncert: +/-0.0185 TPU: +/-0.0185 1.49 Uncert: TPU: U -0.00319+/-0.0247+/-0.0247 1.45+/-0.110+/-0.119 U -0.00394+/-0.0241+/-0.0241 pCi/g 0 (0% -100%) KSD1 pCi/g pCi/g pCi/g 98 (75%-125%)
02/20/07 11:33 02/20/07 11:33 02/20/07 11:33 02/20/07 11:33 U ncert: TPU: 4.87 U -0.0148 Uncert: +/-0.0185 TPU: +/-0.0 185 4.62+/-0.355+/-0.382 95 (75%-125%)
Notes: The Qualifiers in this report are defined as follows: 33 GEL LABORATORIES LLC 2040 Savage Road Charleston SC 29407 -(843) 556-8171 -www.gel.com QC Summary Workorder:
180812 Page 5 of 5* A quality control analyte recovery is outside of specified acceptance criteria** Analyte is a surrogate compound< Result is less than value reported> Result is greater than value reported A The TIC is a suspected aldol-condensation product B For General Chemistry and Organic analysis the target analyte was detected in the associated blank.BD Results are either below the MDC or tracer recovery is low C Analyte has been confirmed by GC[MS analysis D Results are reported from a diluted aliquot of the sample H Analytical holding time was exceeded J Value is estimated N/A Spike recovery limits do not apply. Sample concentration exceeds spike concentration by 4X or more ND Analyte concentration is not detected above the detection limit R Sample results are rejected U Analyte was analyzed for, but not detected above the MDL, MDA, or LOD.UI Gamma S pectroscopy--
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 REC % Rang-e 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.A The Relative Percent Difference (RPD) obtained from the sample duplicate (DUP) is evaluated against the acceptence criteria when the sample is greater than five times (5X) the contract required detection limit (RL). In cases where either the sample or duplicate value is less than 5X the RL, a control limit of +/- the RL is used to evaluate the DUP result.For PS, PSD, and SDILT results, the values listed are the measured amounts, not final concentrations.
Where the analytical method has been performed under NELAP certification, the analysis has met all of the requirements of the NELAC standard unless qualified on the QC Summary.34 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 9312-0004 RELEASE RECORD ATTACHMENT 4 (DQA RESULTS)Revision 0 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD ATTACHMENT 4A (PRELIMINARY DATA REVIEW)Revision 0 RCA North of PAB Tank Farm SURVEY UNIT 93 12-0004 RELEASE RECORD Attachment 4 Survey Unit: Area Description Classification Survey Media Type of Survey Number of Measurements 93 12-0004 RCA North of PAB & Tank Farm Surface Soils Final Status Survey 15 Static, 6 Investigative STATISTICS on TOTAL POPULATION STATISTICS on NON-PARAMETRIC POPULATION DCGLOp (pCilg): Minimum Value: Maximum Value: Mean: Median: Standard Deviation:
Cs-I 37 4.75E+00-7.84E-03 7,41E-01 1.51E-01 9.81 E-02 1 .86E-01 Co-60 2.29E+00-1 .28E-02 3.60E+00 1 .90E-01 1 .34E-02 7.63E-01 Sr-90 9.30E-01-2.46E-02 6.31 E-02 2,40E-02 2.22E-02 2.77E-02 DCGL~p (pCilg): Minimum Value: Maximum Value: Mean: Median: Standard Deviation:
Cs-i 37 4.75E+00-7.84E-03 6.04E-01 1.1lE-01 4.93E-02 1 .55E-01 Co-60 2.29E+00-1 .28E-02 9.47E-02 1 .55E-02 1 .03E-02 2.72E-02 Sr-9O 9.30E-01-3.31 E-03 6.31 E-02 3.14E-02 2.99E-02 2.39E-02 Cs-I 37 Co-60 Sr-9O Sample ID GSCodnts Result 2a MDA Idniid Resulit 2a MDA Idniid Result 2a MDA Ietfe North East (pcilg) _____ pcilgl (pcilg) ____ (pigltcilg)
________ (pcilg)931 2-0004-001 F 236829.64 668622.57 4.93E-02 0.039 4.30E-02 + 1 .03E-02 0.026 4.57E-02 2.60E-02 0.023 3.62E-02 +9312-0004-002F 236829.64 668658.88 8.71E-02 0.033 3.85E-02 + -3.14E-05 0.025 4.10E-02 5.95E-02 0.032 4.53E-02 +9312-0004-003F 236798,19 668604.41 1.55E-01 0.039 3.90E-02 + 2.69E-02 0.024 4.43E-02 + 3.38E-02 0.025 3.89E-02 +9312-0004-004F 236798.19 668640.72 1.09E-01 0.040 4.71 E-02 + 1.48E-02 0.046 5.49E-02 5.97E-02 0.030 4.17E-02 +9312-0004-005F 236766.74 668549.94 6.04E-01 0.073 3.67E-02 + 9.47E-02 0.034 2.99E-02 + 2.99E-02 0.024 3.69E-02 +9312-0004-006F 236766.74 668586.25 1.10E-01 0.036 3.75E-02 + 3.61 E-02 0.024 4.56E-02 + 7.71 E-03 0.022 3.91 E-02 9312-0004-007F 236766.74 668622.57 3.42E-02 0.032 6.10E-02 + 3.16E-02 0.040 7.40E-02 1.57E-02 0.024 .4.11iE-02 9312-0004-008F 236735.29 668531.78 1.99E-01 0.035 2.60E-02 + 1.26E-02 0.017 3.03E-02 3.10E-02 0.025 3.86E-02 +9312-0004-009F 236735.29 668568.10 4.87E-02 0.051 i~5.94E-02 3.24E-02 i~0.034 i~6.115E-02 i ~ 6.24E-02 0.031 4.33E-02 +9312-04O F 236703.84 668513.62
-7.84E-03 0.031 i~5.12E-02
-~ 1.23E-02 i0.032 i~5.03E-02 i ~ 5.89E-02 0.027 3.61 E02 +Fraction of DCGL 0.043 0.082 0.08 1 0.094 0.20 1 0.047 0.038 0.08 1 0.09 1 0.056 REVISION 0 Pg f Page I of 2 RCA North of PAB Tank Farm SURVEY UNIT 93 12-0004 RELEASE RECORD Attachment 4 Cs-I 37 Co-60 Sr-90 Sample ID GPS Coordinates Result 2a MDA Idniid Result 2, MDA Idniid Result 2a MDA Ietfe Ndenithe Eas Identifie Identified Pc/g (c/g (C 9312-0004-011lF 236703.84 668549.94 2.11 E-03 0.034 6.10E-02 -8.59E-03 0.043 5,91 E-02 6.31 E-02 0.027 3.53E-02 +9312-0004-012F 236672.39 668495.47 8.06E-03 0.016 2.13E-02 -4.29E-04 0.013 2 0-23.05E-03 0.022 4.13E-02 9312-0004-013F 236672.39 668531.78 1.41 E-02 0.017 2 5-26.56E-03 0.013 2 2-21.83E-02 0.022 36E0 9312-0004-014F 236640.94 668477.31 2.28E-01 0.038 3.80E-02 + 0 OOE+00 0.046 3.08E-02 -3.31E-03 0.024 4.97E-02 9312-0004-015F 236640.94 668513.62 2.30E-02 0.015 1,60E-02 + -1.28E-02 0.010 1,57E-02 5.67E-03 0.023 4.20E-02 9312-0004-005FS 236766.74 668549.94 7.41E-01 0.079 3.55E-02 + 8.53E-02 0.050 3.56E-02 + 6.04E-02 0.028 3.83E-02 9312-0004-016-1 236786.38 668570.69 2.38E-01 0.033 2.48E-02 + 3.60E+00 0.201 2.13E-01 + 3.79E-02 0.032 5.OOE 02 +9312-0004-017-1 236786.38 668570.69 1.88E-01 0.025 1.81 E-02 + 2.19E-01 0.030 1.74E-02 + -1.48E-02 0.019 4.28E-02 9312-0004-018-1 236788.42 668567.97 1.96E-01 0.031 2.49E-02 + 1.62E-02 0.020 2.32E-02 -4.54E-03 0.020 4.22E-02 9312-0004-019-1 236789.01 668572.91 7.62E-02 0.015 1.33E-02 + 1.25E-02 0.008 1,44E-02 + 8.73E-03 ,0.023 4 1E02 9312-0004-020-1 236784.31 66857359 8.09E-02 0.021 1.4E02 + 1 4E-02 0.015 2.58E-02 -5.53E-03 0.021 4.38E-02 9312-0004-021-1 236783.75 558568.68 1.28E-01 0.016 1.22E-02 + 0.OOE+00 0.012 1.19E-02 -2.46E-02 0.015 4.09E-02 Fraction of DCGL 0.065 0.005 0,026 0.044 0.005 0.258 1.663 0.119 0.043 0.03 1 0.017 0.000 OTHER RADIONUCLIDES Sample ID IIsotope Rsuit 2o MD Identified ICLP Fato__________________________[
______J(Pcilg)
_____ Pci/g) ____ (pCilg) of DCGL 9312-0004-002F Cs-1 34 2.95E-02 0.025 4.64E-02 + 2.8E+00 0.011 9312-0004-003F
'Cs-134 I3.81 E-02 0.3 .3E0 + 2,E0 0.1---- --- --- ---- --- --- --- ---- --- --- ---- --0--036- -- ---- ----- ----- -------- --E--- -- --- --- --------- --- --- -- 0 0 14--- -- -9312-0004-006F
- Mn-54 3.50E-02 0,020 3.68E-02 + 1.OE+01 0.003 9312-0004-007F
!Cs 134 6.09E-02 0.052 6.69E-02 + 2.8E+00 0,022 9312-0004-007F
!Mn-54 2.34E-02 0.019 4.88E-02 + 1.OE+01 0.002 9312-0004-0OlF
':Eu-155 I1.17E-01 0.113 1.23E-01 + 2.4E+02 0.000 9312-0004-011 F ;Eu 155 7.24E-02 0.066 1,22E-01 + 2.4E+02 0.000 9312-0004-014F
'Am-241 I3.56E-02 0.033 5.35E-02 + 1.6E+01 0.002 9312-0004-015F
- Eu 155 4.88E-02 0.035 5.17E-02 + 2.4E+02 0.000 REVISION 0Pae2o2 Page 2 of2 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD ATTACHMENT 4B (GRAPHICAL REPRESENTATION OF DATA)Revision 0 FREQUENCY PLOT FOR CES1UM-.137 Survey Unit: 9312-0004 Survey Unit Name: RCA North of PAD & Tank Farm Mvean: 1.I IE-0i I PCi/g Frequency Plot For Cs-I 37 in LL 6-4-2 0-II LJ 9.41E-02 1.96E-01 2.98E-01 4.OOE-01 5.02E-01 6.04E-01 Upper End Value (pCilg)Upper End Observation Observation Value Frequency Frequency 9.41 E,-02 9 60%1.96Ei-0 1 3 20%2.98E-01 2 13%4.OOE-0 1 0 0%5.02E-01 0 0%6.04E-01, 1 7%Total: I15 100%Reviewed by/Date 1o I of I QUANTILE PLOT FOR CESIUM-1 37 Survey Unit: 9312-0004 Suirvey Unit Namne: R-CA North of PAL3 &I ank Farm Mean: 1.11 lE-OI pCi/g_______
Quantile Plot For Cs- 137 T00E -6.00E-01 ......-.4.00E-01 ............
.2.O 0.OOE+00 -5 ' -.~ .......N.... .02E0 2 0608 0 Percentage
..........................
.______________
.__..__.........................._...
...... .Cs 137 Rank Percentage
-7.8413-03 1 3.3%2.11b.E-03 2 10.0%8.06E-03 3 16.7%1.4 1 E-02 4 23.3%2.30E-02 5 30.0%3.42.11-02 6 36.7%4.87E3-02 7 43.3%4.93E3-02 8 50.0%8.71 E-02 9 56.7%1.09E3-01 10 63.3%1. 103-0 1 11 70.0%1.55E-01 12 76.7%1.99.E-01I 13 83.3%2.28E3-0 1 14 90.0%6.04E3-01 15 96.7%Sub ited by/ ate Reviewed by/Date QUANTILE PLOT FOR CESIUM-i137 Survey Unit: 9312-0004 Survey Unit Name: RCA North of PAB & Tank Farmn Mean: 1.II1E-01I pCi/g Quantile Plot For Cs-I 37 7.OOE:01 0r)+S5.00E-01--
C 4.00E-01-.2 3.00E-01 C.0 2.00E-01 l.OQE-Ol W-0.00E+00 0 20 40 60 80 100 Percentage Cs- 137 Rank Percentage
-7.84E-03 2.11 E-03 8.06E-03 1.41 E-02 2.30E-02 3 .42E-02 4.87E-02 4.93E-02 8.7 1LE-02 1 .09E-0 I 1.I1OE-01I 1 .55E-01 1 .99E-01 2.28E-01 6.04E-0 1 1 2 3.4 5 6 7 8 9 10 11 12 13 14 15 3.3%10.0%16.7%23.3%30.0%36.7%43.3%50.0%56.7%63.3%70.0%76.7%83.3%90.0%96.7%Sub itte a31-sk7 Su td by/ ate Reviewed by/Date FREQUENCY PLOT FOR COBALT-60 Survey Unit: 9312-0004 Survey Unit Name: RCA North of PAI3 & Tank Farm Mean: 1.55E-02 pCi/g Frequency Plot For Co-60 10 8 U.2 0 5.12E-03 2.30E-02 4.10E-02 5.89E-02 7.68E-02 9.47E-02 Upper End Value (pCi/g)Upper End Observation Observation Value Frequency Frequency 5.12E-03 6 40%2.30E-02 4 27%4. 1 OE-02 4 27%5.89E-02 0 0%7.68E-02 0 0%9.47E-02 1 7%Total: 15 100%*bmjilele by/Date Reviewed by/Date 1o 1 of 1 QUANTILE PLOT FOR COBALT-60 Survey Unit: 9312-0004 Survey Unit Name: RCA North of PAB & Tank Farm Mean: 1.55E-02 pCi/g Quantile Plot For Co-60 1 .20E-01 1.OQE-Ol S8. 00E-02.2 4 6. OOE-02 C 0-2.OOE-02[ Ii!-~ --~----------
U *U------~ -------------------------~
Mu.0 20 40 60 80 100 Percentage Co-60 Rank Percentage
-1.28E-02-1 .23E-02-8.59E-03-4.29E-04-3. 14E-05 0.OOE+00 6.56E-03 1.03E-02 1 .26E-02 1 .48E-02 2.69E-02 3. 16E-02 3 .24E-02 3.61 E-02 9.47E-02 1 2 3.4 5 6 7 8 9 10 11 12 13 14 15 3.3%10.0%16.7%23.3%30.0%36.7%43.3%50.0%56.7%63.3%70.0%76.7%83.3%90.0%96.7%;jS 5) 07 S6!::; erax L. 1,4~~0,VI~
7/nI -Reviewed y/Date FREQUENCY PLOT FOR STRONTIUM-90 Survey Unit: 93 12-0004 Survey Unit Name: RCA North of PAB & Tank Farm Mean: 3.14E-02 pCi/g Frequency Plot For Sr-90 U.6 5 4 3 2 1 0 i i I i m m -ý7.76E-03 1.88E-02 2.99E-02 4.10E-02 5.20E-02 6.31E-02 Upper End Value (pC i/g)Upper End Observation Observation Value Frequency Frequency 7.76E-03 4 27%1.88E-02 2 13%2.99E-02 1 7%4.I1OE-02 3 20%5.20E-02 0 0%6.3 1E-02 5 33%Total: 15 100%W~IOJ11~oWAJ VAk 315)0-7 Sul t¶teb/ae Reviewed by/Date 1o 1 of I QUANTILE PLOT FOR STRONTIUM-90 Survey Unit: 9312-0004 Survey Unit Name: RCA North of PAB & Tank Farm Mean: 3.14E-02 pCi/g Quantile Plot For Sr-90 C.0.0 (U 7.OOE-02 6.00E-02 5.00E-02 4.00E-02 3. OQE-02 2.00E-02 I .00E-02~zzx iizr~z~ I -L 0.00E+00-1 .00E-02 0 20 40 60 80 100 Percentage Sr-90 Rank Percentage
-3.3 1 E-03 3 .05E-03 5.67E-03 7.71 E-03 1.57E-02 1 .83E-02 2.60E-02 2.99E-02 3.I1OE-02 3.38E-02 5.89E-02 5.95E-02 5 .97E-02 6.24E-02 6.3 1 E-02 1 2 3.4 5 6 7 8 9 10 11 12 13 14 15 3.3%10.0%16.7%23.3%30.0%36.7%43.3%50.0%56.7%63.3%70.0%76.7%83.3%90.0%96.7%-D. waxmw 1.4 V.3J 5i0o7 Su @febjDate Reviewed by/Date FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD ATTACHMENT 4C (SIGN TEST)Revision 0 Connecticut Yankee Decommissioning Project Health Physics Procedure GPP-GGGR-.R5121
-001 Attachment B, Rev.CY.-O01 MAJOR Sign Test Calculation Sheet for Multiple Radionuclides Survey Area Number: 9312 Survey Unit Number: 0004 IWPIR #: N/A Survey Area Name: RCA North of PAB Classification:
1 TY PE I (a error): 0.05 N: 15& Tank Farm Radionuclides:
1 st Radionuclide 2 d Radionuclide 3 rd Radionuclide 4 th Radionuclide Cs-i 37 Co-60 Sr-90 DCGL: 4.75E+00 2.29E+00 9.30E-01 Results 1 st Results 2 nd Results 3 rd Results 4 th Weighted Sum 1-_We Sign Radionuclide Radionuclide Radionuclide Radionuclide (WI)(pCilg) (pCi/g) (pCi/g) (pCi/g)4.93E-02 1.03E-02 2.60E-02 _______0.04 0.96 + 1 8.71 E-02 -3.14E-05 5.95E-02 0.08 0.92 + 1 1 .55E-01 2.69E-02 3.38E-02 _______0.08 0.92 + 1 1 .09E-01 1 .48E-02 5.97E-02 0.09 0.91 + 1 6.04E-01 9.47E-02 2.99E-02 ________0.20 0.80 + 1 1.10E-01 3.61 E-02 7.71 E-03 _______0.05 0.95 + 1 3.42E-02 3.16E-02 1.57E-02 0.04 0.96 + 1 1.99E-01 1.26E-02 3.10OE-02 0.08 0.92 + 1 4.87E-02 3,24E-02 6.24E-02 ________0.09 0.91 + 1-7.84E-03
-1 .23E-02 5.89E-02 0.06 0.94 + 1 2.11 E-03 -8,59E-03 6.31 E-02 _______0.06 0.94 + 1 8.06E-03 -4.29E-04 3.05E-03 ________0.00 1.00 + 1 1.41 E-02 6.56E-03 1.83E-02 _______0.03 0.97 +1 __2.28E-01 0.OOE+00 -3.31 E-03 _______0.04 0.96 +1 2.30E-02 -1.28E-02 5,67E-03 ________0.01 0.99 + 1 Number of positive differences (S+)i 15 Critical Value 11 David Woitkowiak Survey Unit Meets -the Acceptance Criteria Performed by: Independent Revie wby: 40di~e~l4 ZM,,~Date: Date: 2/2812007 5 15/i0 -7 Page 1 of 1 FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD ATTACHMENT 4D (QC SPLIT RESULTS)Revision 0 Health Physics Procedure 24265-000-61"P-CjCjCR-R5124-000-R.ev.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 I: 9312 Survey Unit # 0004 Survey Unit Name: RCA North of PA 1 & Tank Farm Sample Plan or WP.IR#: N/A SML#: 9312-0004-005 Sample
Description:
Comparison of split samples collected fromn sample measurement location #3 and analyzed using gamma spectroscopy by off-sitc Vendor Laboratory.
Tlhe standard sample was 931 2-0004-005F, the comparison sample was 93 12-0004-OO5FS.
STrANDARD COMPARISON Radionuclide Activity Standard Resolution~
Agreement Activity Standard Comparison Acceptable Value Err or Range Value Error Ratio (YIN)Cs- 13 7 6.04E-01 0.036 17 0.75 -1.33 7.41 E-0l1 0.393 1.23 Y C.ormentsf~orrective Axctions:
None.Iable is providuc to snow acceptance criteria used to assess split samples.Resol ution 4-7 8-15 16 -50 51 -200>200 Areement Rangee 0.5 -20 0.6 -1.66 0,75 -1.33 0.80 -1.25 0.85- 1.18 Y: IDatc: ()Page I Of I FORMER RADIOLOGICALLY CONTROLLED AREA NORTH OF THE PRIMARY AUXILIARY BUILDING AND TANK FARM SURVEY UNIT 93 12-0004 RELEASE RECORD ATTACHMENT 4E (COMPASS POWER CURVE)Revision 0 DQA Surface Soil Report Assessment Summary Site: Planner(s):
Survey Unit Name: Report Number: Survey Unit Samples-Reference Area Samples.Test Performed:
Judgmental Samples.Assessment
==
Conclusion:==
9312 Wojo 9312-0004 1 15 0 Sign Test Result: Not Performed 0 EMIC Result Not Performed Reject Null Hypothesis (Survey Unit PASSES)Retrospective Power Curve C 0.9~t08 0.6 043~0.2~.02*' 01 zz1zz_ _-.;zuiz_ _ _+-I---- ---~_4-I _ -~_AZ!_ ___ ___ -_ __ ---I nix'__ _0ý0 02 0.4 0,6 0.8 1 .0 Unity Rule Sunt-ofRaties, including background
--Prospective Power U 1 -beta -Actual Power-LBGR --Estimated Power DCGL -- -Retrospective Power 1 .2 COMPASS 0l.0.035207Pg1 3/5/2007 Page I