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Docket No:                              50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report Report No. 22 1 January Through 31 December 2006 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2007
Docket No:                              50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report Report No. 22 1 January Through 31 December 2006 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2007
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Table Of Contents I. Summary and Conclusions ............................................................................                  1 II. Introduction .............................................................................................. . . 3 A. Objectives of the REMP .....................................................................                3 B. Implementation of the Objectives ......................................................... 3 Ill. Program Description ..................................................................................              4 A. Sample Collection ...........................................................................                4 B. Sample Analysis ..............................................................................              6 C. Data Interpretation .............................................................      :................... 6 D. Program Exceptions .......................................................................... 8 E. Program Changes ............................................................................ 10 IV. Results and Discussion ............................................................................                10 A. Aquatic Environment ............................................................................            10
Table Of Contents I. Summary and Conclusions ............................................................................                  1 II. Introduction .............................................................................................. . . 3 A. Objectives of the REMP .....................................................................                3 B. Implementation of the Objectives ......................................................... 3 Ill. Program Description ..................................................................................              4 A. Sample Collection ...........................................................................                4 B. Sample Analysis ..............................................................................              6 C. Data Interpretation .............................................................      :................... 6 D. Program Exceptions .......................................................................... 8 E. Program Changes ............................................................................ 10 IV. Results and Discussion ............................................................................                10 A. Aquatic Environment ............................................................................            10
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Two-gallon water samples were collected monthly from continuous samplers located at two surface water locations (13B1 and 24S1) and four drinking water locations (15F4, 15F7, 16C2, and 28F3). Control locations were 24S1, and 28F3. All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, catfish/bullhead (bottom feeder) and sunfish (predator), were collected semiannually at two locations, 16C5 and 29C1 (control). Sediment samples composed of recently deposited substrate were collected at three locations semiannually, 16B2, 16C4 and 33A2 (control).
Two-gallon water samples were collected monthly from continuous samplers located at two surface water locations (13B1 and 24S1) and four drinking water locations (15F4, 15F7, 16C2, and 28F3). Control locations were 24S1, and 28F3. All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, catfish/bullhead (bottom feeder) and sunfish (predator), were collected semiannually at two locations, 16C5 and 29C1 (control). Sediment samples composed of recently deposited substrate were collected at three locations semiannually, 16B2, 16C4 and 33A2 (control).
Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, and milk.
Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, and milk.
Airborne iodine and particulate samples were collected and analyzed weekly at five locations (1OS3, 11 S1, 13C1, 14S1, and 22Gi). The control location was 22G1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air
Airborne iodine and particulate samples were collected and analyzed weekly at five locations (1OS3, 11 S1, 13C1, 14S1, and 22Gi). The control location was 22G1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.
 
at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.
Milk samples were collected biweekly at five locations (10F4, 18E1, 19B1, 23F1, and 25Cl) from April through November, and monthly from December through March. Two additional locations (25E1 and 36E1) were sampled quarterly. Locations 36E1 and 23F1 were controls. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory.
Milk samples were collected biweekly at five locations (10F4, 18E1, 19B1, 23F1, and 25Cl) from April through November, and monthly from December through March. Two additional locations (25E1 and 36E1) were sampled quarterly. Locations 36E1 and 23F1 were controls. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory.
Broad Leaf Vegetation were collected monthly at three locations (1 lS3, 13S3 and 31G1). The control location was 31G1. Thirteen different kinds of vegetation samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.
Broad Leaf Vegetation were collected monthly at three locations (1 lS3, 13S3 and 31G1). The control location was 31G1. Thirteen different kinds of vegetation samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.
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: 4. Concentrations of 1-131 in air and milk.
: 4. Concentrations of 1-131 in air and milk.
: 5. Ambient gamma radiation levels at various site environs.
: 5. Ambient gamma radiation levels at various site environs.
C. Data Interpretation The radiological and direct radiation data collected prior to LGS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this report, LGS was considered
C. Data Interpretation The radiological and direct radiation data collected prior to LGS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this report, LGS was considered operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:
 
operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:
: 1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required LGS detection limits for environmental sample analysis.
: 1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required LGS detection limits for environmental sample analysis.
The minimum detectable concentration (MDC) was defined as above with the exception that the measurement is an after the fact estimate of the presence of activity.
The minimum detectable concentration (MDC) was defined as above with the exception that the measurement is an after the fact estimate of the presence of activity.
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For sediment and broad leaf vegetation seven nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, Cs-1 34, and Cs-1 37 were reported.
For sediment and broad leaf vegetation seven nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, Cs-1 34, and Cs-1 37 were reported.
For air particulate six nuclides, Be-7, Mn-54, Co-58, Co-60, Cs-1 34, and Cs-1 37 were reported.
For air particulate six nuclides, Be-7, Mn-54, Co-58, Co-60, Cs-1 34, and Cs-1 37 were reported.
For milk five nuclides, K-40, Cs-134, Cs-137, Ba-140, and La-140 were reported.
For milk five nuclides, K-40, Cs-134, Cs-137, Ba-140, and La-140 were reported.
Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.
Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.
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10F4          06/13/06      06/27/06    07/25/06 18E1          06/13/06      06/27/06    07/25/06 19B11          06/13/06      06/27/06 23F1          06/13/06      06/27/06    07/25/06 25C1          06/13/06      06/27/06    07/25/06 Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. Occasional equipment breakdowns and power outages were unavoidable.
10F4          06/13/06      06/27/06    07/25/06 18E1          06/13/06      06/27/06    07/25/06 19B11          06/13/06      06/27/06 23F1          06/13/06      06/27/06    07/25/06 25C1          06/13/06      06/27/06    07/25/06 Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. Occasional equipment breakdowns and power outages were unavoidable.
The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.
The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.
E. Program Changes Three broad leaf vegetation locations, 11 S3, 13S3 and 31 G1 were added to Limerick's sampling program in 2006.
E. Program Changes Three broad leaf vegetation locations, 11 S3, 13S3 and 31 G1 were added to Limerick's sampling program in 2006.
Surface Water composite sampler at location 10F2 was removed from Limerick's sampling program since no water was drawn from the Delaware River for station cooling.
Surface Water composite sampler at location 10F2 was removed from Limerick's sampling program since no water was drawn from the Delaware River for station cooling.
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Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-l.2, Appendix C). All nuclides were less than the MDC.
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-l.2, Appendix C). All nuclides were less than the MDC.
: 2. Drinking Water Monthly samples were collected from continuous water samplers at four locations (15F4, 15F7, 16C2, and 28F3). Three locations (15F4, 15F7, and 16C2) could be affected by Limerick's effluent releases. The following analyses were performed:
: 2. Drinking Water Monthly samples were collected from continuous water samplers at four locations (15F4, 15F7, 16C2, and 28F3). Three locations (15F4, 15F7, and 16C2) could be affected by Limerick's effluent releases. The following analyses were performed:
     .Gross Beta Samples from all locations were analyzed for concentrations of total gross beta (Tables C-I1.1, Appendix C). The values ranged from <2.3 to 8.3 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C).
     .Gross Beta Samples from all locations were analyzed for concentrations of total gross beta (Tables C-I1.1, Appendix C). The values ranged from <2.3 to 8.3 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C).
Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-I1.2, Appendix C). Tritium activity was detected in one sample at a concentration of 177 pCi/L. The dose via the drinking water pathway was calculated at 0.018 mrem to a child (total body), which was 0.31% of the 10 CFR 50, Appendix I dose limit.
Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-I1.2, Appendix C). Tritium activity was detected in one sample at a concentration of 177 pCi/L. The dose via the drinking water pathway was calculated at 0.018 mrem to a child (total body), which was 0.31% of the 10 CFR 50, Appendix I dose limit.
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Historical levels of Cs-1 37 are shown in Figure C-2, Appendix C.
Historical levels of Cs-1 37 are shown in Figure C-2, Appendix C.
: 4. Sediment Aquatic sediment samples were collected at three locations (16B2, 16C4 and 33A2) semiannually. Of these locations two 16B2 and 16C4 located downstream, could be affected by Limerick's effluent releases. The following analysis was performed:
: 4. Sediment Aquatic sediment samples were collected at three locations (16B2, 16C4 and 33A2) semiannually. Of these locations two 16B2 and 16C4 located downstream, could be affected by Limerick's effluent releases. The following analysis was performed:
Gamma Soectrometrv Sediment samples from all three locations were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). Nuclides detected were naturally occurring Be-7, K-40 and the fission product Cs-137.
Gamma Soectrometrv Sediment samples from all three locations were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). Nuclides detected were naturally occurring Be-7, K-40 and the fission product Cs-137.
Beryllium-7 and K-40 were found at all stations and ranged from
Beryllium-7 and K-40 were found at all stations and ranged from
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Gro ss Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-V. 1 and C-V.2, Appendix C).
Gro ss Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-V. 1 and C-V.2, Appendix C).
Detectable gross beta activity was observed at all locations.
Detectable gross beta activity was observed at all locations.
Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of LGS. The results from the On-Site locations (Group I)
Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of LGS. The results from the On-Site locations (Group I) ranged from <6 to 31 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3 . The results from the Intermediate Distance location (Group II) ranged from <7 to 27 E-3 pCi/i 3 with a mean of 16 E-3 pCi/m . The results from the Distant locations (Group 1Il) ranged from'<7 to 35 E-3 pCi/M 3 with a mean of 17 E-3 pCi/m 3 . Comparison of the 2006 air particulate data with previous years data indicate no effects from the operation of LGS (Figure C-4, Appendix C). In addition a comparison of the weekly mean values for 2006 indicate no notable differences among the three groups (Figure C-5, Appendix C).
 
ranged from <6 to 31 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3 . The results from the Intermediate Distance location (Group II) ranged from <7 to 27 E-3 pCi/i 3 with a mean of 16 E-3 pCi/m . The results from the Distant locations (Group 1Il) ranged from'<7 to 35 E-3 pCi/M 3 with a mean of 17 E-3 pCi/m 3 . Comparison of the 2006 air particulate data with previous years data indicate no effects from the operation of LGS (Figure C-4, Appendix C). In addition a comparison of the weekly mean values for 2006 indicate no notable differences among the three groups (Figure C-5, Appendix C).
Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C).
Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C).
Naturally occurring Be-7 due to cosmic ray activity was detected in all samples. These values ranged from 43 to 126 E-3 pCi/m 3 . All other nuclides were less than the MDC.
Naturally occurring Be-7 due to cosmic ray activity was detected in all samples. These values ranged from 43 to 126 E-3 pCi/m 3 . All other nuclides were less than the MDC.
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The following analyses were performed:
The following analyses were performed:
odione-131 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VII. 1, Appendix C). All results were less than the MDC.
odione-131 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VII. 1, Appendix C). All results were less than the MDC.
Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C).
Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C).
Naturally occurring K-40 activity was found in all samples and ranged from 1,050 to 1,450 pCi/L. All other nuclides were less than the MDC.
Naturally occurring K-40 activity was found in all samples and ranged from 1,050 to 1,450 pCi/L. All other nuclides were less than the MDC.
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C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO 4 ) thermoluminescent dosimeters. Forty TLD locations were established around the site. Results of TLD measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C.
C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO 4 ) thermoluminescent dosimeters. Forty TLD locations were established around the site. Results of TLD measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C.
Most TLD measurements were below 10 mR/standard month, with a range of 5.5 to 12.8 mR/standard month. A comparison of the Site Boundary and Intermediate Distance data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Location 5H1 were consistently higher. The historical ambient gamma radiation data from Location 5H1 were plotted along with similar data from the Site, Intermediate Distance and Outer Ring Locations (Figure C-6, Appendix C). Location 5H1 has a historical high bias, but tracked with the data from all three groups. This bias is most likely due to radon emanating from the ground.
Most TLD measurements were below 10 mR/standard month, with a range of 5.5 to 12.8 mR/standard month. A comparison of the Site Boundary and Intermediate Distance data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Location 5H1 were consistently higher. The historical ambient gamma radiation data from Location 5H1 were plotted along with similar data from the Site, Intermediate Distance and Outer Ring Locations (Figure C-6, Appendix C). Location 5H1 has a historical high bias, but tracked with the data from all three groups. This bias is most likely due to radon emanating from the ground.
D. 10 CFR 20.2002 Permit Storage Area The results of the surface water aquatic monitoring program from Location 24S1 were used to determine if radioactivity from the permit storage area had made it to the Schuylkill River. The data obtained from the gamma analysis program did not detect any migration of radioactivity from the permit storage area.
D. 10 CFR 20.2002 Permit Storage Area The results of the surface water aquatic monitoring program from Location 24S1 were used to determine if radioactivity from the permit storage area had made it to the Schuylkill River. The data obtained from the gamma analysis program did not detect any migration of radioactivity from the permit storage area.
E. Land Use Survey A Land Use Survey conducted in August 2006 around Limerick Generating Station (LGS) was performed by Normandeau Associates, RMC Environmental Services Division for Exelon Nuclear to comply with Bases 3.3.2 of the Limerick's Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident, milk producing animal and garden of greater than 500 ft2 in each of the sixteen 22 1 degree sectors around the site. Four new gardens are included in the 2006 survey. The gardens are located in sectors ESE, SE, NNE and NNW. The distance and direction of all locations from the LGS reactor buildings were positioned using Global Positioning System (GPS) technology. There were no changes required to the LGS REMP, as a result of this survey. The results of this survey are summarized below.
E. Land Use Survey A Land Use Survey conducted in August 2006 around Limerick Generating Station (LGS) was performed by Normandeau Associates, RMC Environmental Services Division for Exelon Nuclear to comply with Bases 3.3.2 of the Limerick's Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident, milk producing animal and garden of greater than 500 ft2 in each of the sixteen 22 1 degree sectors around the site. Four new gardens are included in the 2006 survey. The gardens are located in sectors ESE, SE, NNE and NNW. The distance and direction of all locations from the LGS reactor buildings were positioned using Global Positioning System (GPS) technology. There were no changes required to the LGS REMP, as a result of this survey. The results of this survey are summarized below.
Distance in Miles from the LGS Reactor Buildings Sector          Residence            Garden          Milk Farm Miles              Miles            Miles 1N                0.6                1.8              4.7 2 NNE            0.5                1.8 3NE              0.7                1.6 4 ENE            0.6                0.7 5E                0.5                0.7 6 ESE            0.7                0.3 7SE              1.0                0.2 8 SSE            1.0                1.1 9S                0.8                1.2              4.2 10 SSW            1.0                1.0              2.0 11 SW              0.6                0.6 12 WSW            0.7                2.3              2.7 13W                0.7                0.8              2.8 14 WNW            0.7                0.8 15 NW              0.7                1.6 16 NNW            1.0                1.3 F. Summary of Results - Inter-laboratory Comparison Program
Distance in Miles from the LGS Reactor Buildings Sector          Residence            Garden          Milk Farm Miles              Miles            Miles 1N                0.6                1.8              4.7 2 NNE            0.5                1.8 3NE              0.7                1.6 4 ENE            0.6                0.7 5E                0.5                0.7 6 ESE            0.7                0.3 7SE              1.0                0.2 8 SSE            1.0                1.1 9S                0.8                1.2              4.2 10 SSW            1.0                1.0              2.0 11 SW              0.6                0.6 12 WSW            0.7                2.3              2.7 13W                0.7                0.8              2.8 14 WNW            0.7                0.8 15 NW              0.7                1.6 16 NNW            1.0                1.3 F. Summary of Results - Inter-laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices for 28 analytes (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria:
 
The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices for 28 analytes (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria:
: 1.      Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.
: 1.      Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.
: 2.      ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, -as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.
: 2.      ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, -as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.
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The MAPEP defines three levels of performance: Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% < bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.
The MAPEP defines three levels of performance: Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% < bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.
For the primary laboratory, 24 out of 28 analytes met the specified acceptance criteria. Four samples did not meet the specified acceptance criteria for the following reasons:
For the primary laboratory, 24 out of 28 analytes met the specified acceptance criteria. Four samples did not meet the specified acceptance criteria for the following reasons:
: 1.      Teledyne Brown Engineering's MAPEP Series 15 January 2006 soil Cs-1 34 was evaluated as a false positive, although TBE
: 1.      Teledyne Brown Engineering's MAPEP Series 15 January 2006 soil Cs-1 34 was evaluated as a false positive, although TBE considered the result a non-detect due to the peak not being identified by the gamma software. MAPEP suggests the Bi-214 is not being differentiated from the Cs-1 34 peak. When the ratio of activity to uncertainty exceeds 3, TBE will use a key line analysis rather than a weighted mean analysis when evaluating MAPEP non-detects.
 
considered the result a non-detect due to the peak not being identified by the gamma software. MAPEP suggests the Bi-214 is not being differentiated from the Cs-1 34 peak. When the ratio of activity to uncertainty exceeds 3, TBE will use a key line analysis rather than a weighted mean analysis when evaluating MAPEP non-detects.
: 2.      Teledyne Brown Engineering's MAPEP Series 15 January 2006 Sr-90 in vegetation result of 2.22 Bq/kg exceeded the upper acceptance range of 2.029 Bq/kg. The samples were analyzed in triplicate and the results averaged. One high result of 2.43 Bq/kg biased the submitted results on the high side. TBE was unable to determine the cause for the higher result. The Sr-90 in vegetation results for MAPEP Series 14 and MAPEP Series 16 were acceptable. No client samples were analyzed during the MAPEP Series 14 time period.
: 2.      Teledyne Brown Engineering's MAPEP Series 15 January 2006 Sr-90 in vegetation result of 2.22 Bq/kg exceeded the upper acceptance range of 2.029 Bq/kg. The samples were analyzed in triplicate and the results averaged. One high result of 2.43 Bq/kg biased the submitted results on the high side. TBE was unable to determine the cause for the higher result. The Sr-90 in vegetation results for MAPEP Series 14 and MAPEP Series 16 were acceptable. No client samples were analyzed during the MAPEP Series 14 time period.
: 3.      Teledyne Brown Engineering's MAPEP Series 15 January 2006 Pu-238 and Pu-239/240 in vegetation result of 2.22 Bq/kg failed the required acceptance ranges. TBE was evaluating the current preparation method for vegetation samples, which proved insufficient for the analyses. TBE does not perform isotopic Pu on client's vegetation samples.
: 3.      Teledyne Brown Engineering's MAPEP Series 15 January 2006 Pu-238 and Pu-239/240 in vegetation result of 2.22 Bq/kg failed the required acceptance ranges. TBE was evaluating the current preparation method for vegetation samples, which proved insufficient for the analyses. TBE does not perform isotopic Pu on client's vegetation samples.
Line 260: Line 238:
: 2.      Environmental Inc.'s MAPEP January 2006 vegetation Pu-238 result of 0.08 Bq/sample exceeded the lower control limit of 0.10 Bq/sample due to incomplete dissolution of the sample.
: 2.      Environmental Inc.'s MAPEP January 2006 vegetation Pu-238 result of 0.08 Bq/sample exceeded the lower control limit of 0.10 Bq/sample due to incomplete dissolution of the sample.
: 3.      Environmental Inc.'s MAPEP January 2006 air particulate Pu-238 result of 0.03 Bq/sample exceeded the lower control limit of 0.05 Bq/sample due to incomplete dissolution of the sample.
: 3.      Environmental Inc.'s MAPEP January 2006 air particulate Pu-238 result of 0.03 Bq/sample exceeded the lower control limit of 0.05 Bq/sample due to incomplete dissolution of the sample.
: 4.      Environmental Inc.'s MAPEP January 2006 soil Pu-238, Pu-239/240, U-233/234 and U-238 results of 14.6, 14.6, 13.5 and 15.4 Bq/kg, respectively, exceeded the lower control limits of
: 4.      Environmental Inc.'s MAPEP January 2006 soil Pu-238, Pu-239/240, U-233/234 and U-238 results of 14.6, 14.6, 13.5 and 15.4 Bq/kg, respectively, exceeded the lower control limits of 42.81, 32.09, 25.9 and 27.2 Bq/kg, respectively, due to incomplete dissolution of the sample.
 
42.81, 32.09, 25.9 and 27.2 Bq/kg, respectively, due to incomplete dissolution of the sample.
The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.
The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.
V. References
V. References
Line 268: Line 244:
: 2. Branch Technical Position Paper, Regulatory Guide 4.8, Revision 1, November 1979.
: 2. Branch Technical Position Paper, Regulatory Guide 4.8, Revision 1, November 1979.
: 3. Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.
: 3. Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.
c APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT  
c APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT  


Line 499: Line 474:


TABLE C-V.2                MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS (E-3 PCI/CU METER) IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 GROUP I - ON-SITE LOCATIONS              GROUP II- INTERMEDIATE DISTANCE                GROUP III- CONTROL LOCATIONS LOCATIONS COLLECTION        MIN. MAX. MEAN+/-        COLLECTION        MIN. MAX. MEAN +/-        COLLECTION          MIN. MAX. MEAN+/-
TABLE C-V.2                MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS (E-3 PCI/CU METER) IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 GROUP I - ON-SITE LOCATIONS              GROUP II- INTERMEDIATE DISTANCE                GROUP III- CONTROL LOCATIONS LOCATIONS COLLECTION        MIN. MAX. MEAN+/-        COLLECTION        MIN. MAX. MEAN +/-        COLLECTION          MIN. MAX. MEAN+/-
PERIOD                        2SD          PERIOD                        2SD            PERIOD                        2SD 1/3/2006 - 1/30/2006      9  19  13 +7    1/3/2006  1/30/2006      9 18  13 +/- 7      1/3/2006 - 1/30/2006      10  16  14 +/- 5 1/30/2006 - 2/27/2006      14  25  19 +7    1/30/2006  2/27/2006      11 23  18 +/- 11  1/30/2006 - 2/27/2006      16  24  20 +/- 7 2/27/2006 - 4/3/2006      6  23  15 +/-8    2/27/2006  4/3/2006        9 18  15 +/- 7    2/27/2006 - 4/3/2006        9  18  14 +/- 7
PERIOD                        2SD          PERIOD                        2SD            PERIOD                        2SD 1/3/2006 - 1/30/2006      9  19  13 +7    1/3/2006  1/30/2006      9 18  13 +/- 7      1/3/2006 - 1/30/2006      10  16  14 +/- 5 1/30/2006 - 2/27/2006      14  25  19 +7    1/30/2006  2/27/2006      11 23  18 +/- 11  1/30/2006 - 2/27/2006      16  24  20 +/- 7 2/27/2006 - 4/3/2006      6  23  15 +/-8    2/27/2006  4/3/2006        9 18  15 +/- 7    2/27/2006 - 4/3/2006        9  18  14 +/- 7 4/3/2006 - 5/1/2006  <7      22  12 +10    4/3/2006  5/1/2006        7 14  10 +/- 7    4/3/2006 - 5/1/2006    7      15  10 +/- 7 5/1/2006 - 5/30/2006  <6      18  11 +9    5/1/2006  5/30/2006  <7    12  10 +/- 5    5/1/2006 - 5/30/2006    7      15  11+/- 7 5/30/2006 - 7/3/2006      7  21  15 +/-8    5/30/2006  7/3/2006        8 14  10  5    5/30/2006 - 7/3/2006        8  31  16 +/- 17 7/3/2006 - 7/31/2006      16  27  21 +/-6    7/3/2006  7/31/2006      16 23  20  6    7/3/2006 - 7/31/2006    21    35  26 +/- 13 7/31/2006 - 8/28/2006      15  31  22 +10  7/31/2006  8/28/2006      17 24  21  7    7/31/2006 - 8/28/2006      13  27  21 +/- 12 8/28/2006 - 10/2/2006      6  22  15 -+10  8/28/2006  10/2/2006      7 21  15    10  8/28/2006 - 10/2/2006        8  22  16 +/- 10 10/2/2006 - 10/30/2006    9  29  16 +11  10/2/2006  10/30/2006    11 19  16  7    10/2/2006 - 10/30/2006      16  18  17 +/- 2 10/30/2006 - 11/27/2006 < 7    25  18 -+13 10/30/2006  11/27/2006      9 27  19    15 10/30/2006 - 11/27/2006      11  24  20 +/- 12 11/27/2006 - 1/2/2007      13  28  21 +10  11/27/2006  1/2/2007      13 25  20    13 11/2712006 - 1/2/2007        16  25  20 +/- 8 1/3/2006 - 1/2/2007  <6      31  17 +/- 7  12/28/2004 - 1/3/2006  < 7    27  16 +/- 8  12/28/2004 - 1/3/2006  < 7      35  17 +/- 9 c-9
                                                                                                                <
4/3/2006 - 5/1/2006  <7      22  12 +10    4/3/2006  5/1/2006        7 14  10 +/- 7    4/3/2006 - 5/1/2006    7      15  10 +/- 7
                                                                                                                <
5/1/2006 - 5/30/2006  <6      18  11 +9    5/1/2006  5/30/2006  <7    12  10 +/- 5    5/1/2006 - 5/30/2006    7      15  11+/- 7 5/30/2006 - 7/3/2006      7  21  15 +/-8    5/30/2006  7/3/2006        8 14  10  5    5/30/2006 - 7/3/2006        8  31  16 +/- 17
                                                                                                                <
7/3/2006 - 7/31/2006      16  27  21 +/-6    7/3/2006  7/31/2006      16 23  20  6    7/3/2006 - 7/31/2006    21    35  26 +/- 13 7/31/2006 - 8/28/2006      15  31  22 +10  7/31/2006  8/28/2006      17 24  21  7    7/31/2006 - 8/28/2006      13  27  21 +/- 12 8/28/2006 - 10/2/2006      6  22  15 -+10  8/28/2006  10/2/2006      7 21  15    10  8/28/2006 - 10/2/2006        8  22  16 +/- 10 10/2/2006 - 10/30/2006    9  29  16 +11  10/2/2006  10/30/2006    11 19  16  7    10/2/2006 - 10/30/2006      16  18  17 +/- 2 10/30/2006 - 11/27/2006 < 7    25  18 -+13 10/30/2006  11/27/2006      9 27  19    15 10/30/2006 - 11/27/2006      11  24  20 +/- 12 11/27/2006 - 1/2/2007      13  28  21 +10  11/27/2006  1/2/2007      13 25  20    13 11/2712006 - 1/2/2007        16  25  20 +/- 8 1/3/2006 - 1/2/2007  <6      31  17 +/- 7  12/28/2004 - 1/3/2006  < 7    27  16 +/- 8  12/28/2004 - 1/3/2006  < 7      35  17 +/- 9 c-9


TABLE C-V.3 CONCENTRATION OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC    COLLECTION              Be-7    Mn-54        Co-58        Co-60        Cs-134        Cs-137 PERIOD 10S3  01/03 - 04/03/06  < 83          < 4.9        < 8.0        < 4.4        < 2.7        < 4.1 04/03 - 07/03/06      61 +/- 27  < 3.7        < 4.4        < 5.0        < 3.1        < 3.3 07/03 - 10/02/06      77 +/- 28  < 1.8        < 3.1        < 1.6        <  1.5        < 1.5 10/02 - 01/02/07      64 +/- 16  < 2.1        <  2.4        < 2.1        < 2.2        < 2.2 MEAN          72 +/- 21      3.1 +/- 2.8    4.5 + 5.0    3.3 + 3.4    2.4 _ 1.4    2.8 + 2.3 11S1  01/03  - 04/03/06 < 98          < 6.3        <  8.7        < 2.8        < 5.0        < 3.5 04/03  - 07/03/06      65 +/- 30  < 2.5        <  4.7        < 3.2        < 2.7        < 2.9 07/03  - 10/02/06      64 +/- 39  < 2.6        <  4.8        < 1.7        < 2.3        < 2.5 10/02  - 01/02/07      71 +/- 22  < 3.4        <  3.7        < 3.5        < 2.8        < 3.2 MEAN          74 +/- 32      3.7 + 3.5    5.5 + 4.5    2.8 + 1.5    3.2 +/- 2.4    3.1 + 0.9 13C1  01/03  - 04/03/06      64  +/-  46 < 2.9        <  6.0        < 3.6        < 4.3        < 2.9 04/03  - 07/03/06      89  +/-  42 < 4.0        <  5.1        < 5.2        < 4.4        < 3.4 07/03  - 10/02/06      84  +/-  37 < 1.4        <  4.6        < 3.3        < 2.0        < 1.7 10/02  - 01/02/07      81  +/-  24 < 3.0        <  3.4        < 2.3        < 3.0        < 3.3 MEAN        80 +/- 22      2.8 +/- 2.1    4.8  2.2    3.6 +/- 2.4    3.4  2.2    2.8 +/- 1.5 14S1  01/03  - 04/03/06 < 76          < 5.5        <  5.7        < 4.2        < 5.6        < 4.8 04/03  - 07/03/06    81 +/- 41    < 4.3        <  7.3        < 3.5        < 3.5        < 3.4 07/03  - 10/02/06    57 +/- 47    < 2.2        <  3.8        < 2.4        < 2.2        < 2.2 10/02  - 01/02/07    82 +/- 30    < 2.5        <  3.8        < 1.5        < 2.8        < 3.0 MEAN        74 +/- 24      3.6 +/- 3.2    5.1 +/- 3.4    2.9 +/- 2.3    3.5 +/- 3.0    3.4 +/- 2.2 22G1  01/03  - 04/03/06 < 102          < 6.5        <  8.6        < 4.4        < 5.3        < 3.0 04/03  - 07/03/06    93 +/- 34    < 3.4        <  5.9        < 2.6        < 3.7        < 2.7 07/03  - 10/02/06    126 +/- 39    < 2.8        <  3.5        < 2.0        < 2.1        < 1.8 10/02  - 01/02/07    43 +/- 26    < 3.6        <  3.3        < 3.1        < 3.0        < 2.6 MEAN        91 +/- 70      4.1 +/- 3.4    5.3 + 4.9    3.0 +/- 2.0    3.5 +/- 2.7    2.5  1.0 C-10
TABLE C-V.3 CONCENTRATION OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC    COLLECTION              Be-7    Mn-54        Co-58        Co-60        Cs-134        Cs-137 PERIOD 10S3  01/03 - 04/03/06  < 83          < 4.9        < 8.0        < 4.4        < 2.7        < 4.1 04/03 - 07/03/06      61 +/- 27  < 3.7        < 4.4        < 5.0        < 3.1        < 3.3 07/03 - 10/02/06      77 +/- 28  < 1.8        < 3.1        < 1.6        <  1.5        < 1.5 10/02 - 01/02/07      64 +/- 16  < 2.1        <  2.4        < 2.1        < 2.2        < 2.2 MEAN          72 +/- 21      3.1 +/- 2.8    4.5 + 5.0    3.3 + 3.4    2.4 _ 1.4    2.8 + 2.3 11S1  01/03  - 04/03/06 < 98          < 6.3        <  8.7        < 2.8        < 5.0        < 3.5 04/03  - 07/03/06      65 +/- 30  < 2.5        <  4.7        < 3.2        < 2.7        < 2.9 07/03  - 10/02/06      64 +/- 39  < 2.6        <  4.8        < 1.7        < 2.3        < 2.5 10/02  - 01/02/07      71 +/- 22  < 3.4        <  3.7        < 3.5        < 2.8        < 3.2 MEAN          74 +/- 32      3.7 + 3.5    5.5 + 4.5    2.8 + 1.5    3.2 +/- 2.4    3.1 + 0.9 13C1  01/03  - 04/03/06      64  +/-  46 < 2.9        <  6.0        < 3.6        < 4.3        < 2.9 04/03  - 07/03/06      89  +/-  42 < 4.0        <  5.1        < 5.2        < 4.4        < 3.4 07/03  - 10/02/06      84  +/-  37 < 1.4        <  4.6        < 3.3        < 2.0        < 1.7 10/02  - 01/02/07      81  +/-  24 < 3.0        <  3.4        < 2.3        < 3.0        < 3.3 MEAN        80 +/- 22      2.8 +/- 2.1    4.8  2.2    3.6 +/- 2.4    3.4  2.2    2.8 +/- 1.5 14S1  01/03  - 04/03/06 < 76          < 5.5        <  5.7        < 4.2        < 5.6        < 4.8 04/03  - 07/03/06    81 +/- 41    < 4.3        <  7.3        < 3.5        < 3.5        < 3.4 07/03  - 10/02/06    57 +/- 47    < 2.2        <  3.8        < 2.4        < 2.2        < 2.2 10/02  - 01/02/07    82 +/- 30    < 2.5        <  3.8        < 1.5        < 2.8        < 3.0 MEAN        74 +/- 24      3.6 +/- 3.2    5.1 +/- 3.4    2.9 +/- 2.3    3.5 +/- 3.0    3.4 +/- 2.2 22G1  01/03  - 04/03/06 < 102          < 6.5        <  8.6        < 4.4        < 5.3        < 3.0 04/03  - 07/03/06    93 +/- 34    < 3.4        <  5.9        < 2.6        < 3.7        < 2.7 07/03  - 10/02/06    126 +/- 39    < 2.8        <  3.5        < 2.0        < 2.1        < 1.8 10/02  - 01/02/07    43 +/- 26    < 3.6        <  3.3        < 3.1        < 3.0        < 2.6 MEAN        91 +/- 70      4.1 +/- 3.4    5.3 + 4.9    3.0 +/- 2.0    3.5 +/- 2.7    2.5  1.0 C-10
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FIGURE C-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2006 1    14                                      ..                                            .    .      .      .        .
FIGURE C-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2006 1    14                                      ..                                            .    .      .      .        .
10 9    ....--                            ---- --.--.....            ---.---....... ..    ...----    ----          - --                ---    --.
10 9    ....--                            ---- --.--.....            ---.---....... ..    ...----    ----          - --                ---    --.
                                                                                                                                                        ---
8                i--                  i                        A,                    - - - ------.              ------
8                i--                  i                        A,                    - - - ------.              ------
I                                                  I~: Il..                                                    ,      ,  '
I                                                  I~: Il..                                                    ,      ,  '
Line 589: Line 557:
55 50              ............    ....... .......                                                              . . . . . . . . . .. . .. ....... .. . .
55 50              ............    ....... .......                                                              . . . . . . . . . .. . .. ....... .. . .
                                                                                                     . .. .............                                                                          - -2 C 450    ..        ....... . .. . :................................
                                                                                                     . .. .............                                                                          - -2 C 450    ..        ....... . .. . :................................
                                                  ... ...--                                                                                    ..................................                                .................            ..
40                                                                                                            ....
40                                                                                                            ....
                                                                                                                    ,                ..... .... .. .. ..
LGS CRITICALITY                                                                                                              .              .                .      .
LGS CRITICALITY                                                                                                              .              .                .      .
35                              UNIT NO. 1: 12/22/84 ......                                                              J.            .
35                              UNIT NO. 1: 12/22/84 ......                                                              J.            .
2switched 30    - ""....
2switched 30    - ""....
SUNIT
SUNIT NO. 2:08/11/89
                            ,:....
NO. 2:08/11/89
                                        .. .......................................
                                        ,......
                                                                                                                                                   /Note:            Second half of 2000 to reporting < MDC aciit.asd          te t d          ... ...          ... ..
                                                                                                                                                   /Note:            Second half of 2000 to reporting < MDC aciit.asd          te t d          ... ...          ... ..
Using MDC values result in a
Using MDC values result in a
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20    .        --                                                                                                                                                                                                    . ......-------.
20    .        --                                                                                                                                                                                                    . ......-------.
155-                ---------            ---.-                                                  ---.-
155-                ---------            ---.-                                                  ---.-
                                                                                              .-.-.-.-..        -.-.-.-
                                                                                                                    .-                      .-.-.. . .-.-.-..
                                                                                                                                      . . . -.-.-.-.                          . . . . . .-
                                                                                                                                                                             -.-.-..          .-..      .-      /                    -.    --------
                                                                                                                                                                             -.-.-..          .-..      .-      /                    -.    --------
                                                                                                                                                                                                                      ...      .
10        ........
10        ........
0 82      83        84      85          86    87          88              89              90        91      92        93      94      95      96              97      98    99        00  01    02        03      04  05      06 YEAR CONTROL = 29C1 Station 20S1 discontinued in 1995 C - 24
0 82      83        84      85          86    87          88              89              90        91      92        93      94      95      96              97      98    99        00  01    02        03      04  05      06 YEAR CONTROL = 29C1 Station 20S1 discontinued in 1995 C - 24
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1200                                                                      ------------------                      -- 16C 4 1000--                                                                                          33A2 10 0 0    . ....... * ......            . ........... I ........ I ....,...., ........ .. ..          ............................        .
1200                                                                      ------------------                      -- 16C 4 1000--                                                                                          33A2 10 0 0    . ....... * ......            . ........... I ........ I ....,...., ........ .. ..          ............................        .
E  8 00"o ~~~~~                          a-                          .0  0    I-- --I - - .--      .
E  8 00"o ~~~~~                          a-                          .0  0    I-- --I - - .--      .
                                                                                                                          ..
I-. . - -- --- ..- -I 600    -  ------------                ---------------------                                                            --------
I-. . - -- --- ..- -I
                                                                                                                            ...        ... .---
600    -  ------------                ---------------------                                                            --------
0 S 400--                                - ---                            - - - - --- - --                  - ---          - -
0 S 400--                                - ---                            - - - - --- - --                  - ---          - -
200
200 0        '77        ----------                                -    -    -
                                                                                          -
0        '77        ----------                                -    -    -
   -200 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 LGS CRITICALITY                                                                Yea r UNIT NO. 1: 12/22/84 UNIT NO. 2: 08/11189 CONTROL = 33A2 C -25
   -200 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 LGS CRITICALITY                                                                Yea r UNIT NO. 1: 12/22/84 UNIT NO. 2: 08/11189 CONTROL = 33A2 C -25


FIGURE C-4 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2006 150 135    ... .. . . . . . . ..        . .. .... . .. ....
FIGURE C-4 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2006 150 135    ... .. . . . . . . ..        . .. .... . .. ....
                                        ....                    . . . ...........
                                                                          . . .*                                  .
                                                                                                         . .. .. .... .. .      - -    G ro u p 1
                                                                                                         . .. .. .... .. .      - -    G ro u p 1
                                                                                                                               -.--- Group I 5--Group            III 12 0      . .... . . I  I.,..
                                                                                                                               -.--- Group I 5--Group            III 12 0      . .... . . I  I.,..
                              . .. . . . .. . . . . . . . . . . . . . . . . .. . . . . .
105Chernobyl
105Chernobyl
   " 10 5 ........ . . ... ..                              ...            .............
   " 10 5 ........ . . ... ..                              ...            .............
                                                                              . . . . . ...............
                                                                                                    . . . . . . . . . . . . . . . .. . .. -
E 90 S 75          *  **                          *    *      ***                                    -
E 90 S 75          *  **                          *    *      ***                                    -
LGS CRITICALITY                                                                        .
LGS CRITICALITY                                                                        .
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6 c i,                        !
6 c i,                        !
* i:              i        i 4
* i:              i        i 4
                                                                                  ; ., . . . . . . . . . . . . . . . . . . . . . . . .
85 86  87 88 89 90 91          92 93 94 95        96 97 98 99 00 01 02 03 04 05 06 07 YEAR NOTE: Control Station 51-11 became the only distant location beginning in 1995 C - 28
85 86  87 88 89 90 91          92 93 94 95        96 97 98 99 00 01 02 03 04 05 06 07 YEAR NOTE: Control Station 51-11 became the only distant location beginning in 1995 C - 28


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                                                                                               ;A:                  ..........................................................
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Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2007
Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2007
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Table Of Contents I. Summary and Conclusions ...........................................................................            1 II. Introduction ................................................................................................ 3 A. Objectives of the RGPP ..........................................................................      3 B. Implementation of the Objectives .........................................................            3 C. Program Description ..........................................................................        4 D. Characteristics of Tritium (H-3) .............................................................        5 Ill. Program Description ...................................................................................      6 A. Sample Analysis ..............................................................................        6 B. Data Interpretation ................................................................................. 6 C. Background Analysis .........................................................................          7
Table Of Contents I. Summary and Conclusions ...........................................................................            1 II. Introduction ................................................................................................ 3 A. Objectives of the RGPP ..........................................................................      3 B. Implementation of the Objectives .........................................................            3 C. Program Description ..........................................................................        4 D. Characteristics of Tritium (H-3) .............................................................        5 Ill. Program Description ...................................................................................      6 A. Sample Analysis ..............................................................................        6 B. Data Interpretation ................................................................................. 6 C. Background Analysis .........................................................................          7
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Strontium-90 was not detected at a concentration greater than the LLD of 2.0 picoCuries per liter (pCi/L) in any of the groundwater or surface water samples tested.
Strontium-90 was not detected at a concentration greater than the LLD of 2.0 picoCuries per liter (pCi/L) in any of the groundwater or surface water samples tested.
Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 10 of 29 groundwater monitoring locations. The tritium concentrations ranged from 158 +/- 103 pCi/L to 4,360 +/- 494 pCi/L. Most of the tritium that was detected in groundwater at the Station is on the west side of the Turbine building. It is likely that the tritium has migrated from the Unit 1 Condensate Storage Tank and or the auxiliary heating steam pipe leak to the monitoring well. The dose via the drinking water pathway was calculated at 0.451 mrem to a child (total body), which was 7.52% of the 10 CFR 50, Appendix I dose limit. All results for Sr-90 and gamma emitting nuclides were less than MDC.
Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 10 of 29 groundwater monitoring locations. The tritium concentrations ranged from 158 +/- 103 pCi/L to 4,360 +/- 494 pCi/L. Most of the tritium that was detected in groundwater at the Station is on the west side of the Turbine building. It is likely that the tritium has migrated from the Unit 1 Condensate Storage Tank and or the auxiliary heating steam pipe leak to the monitoring well. The dose via the drinking water pathway was calculated at 0.451 mrem to a child (total body), which was 7.52% of the 10 CFR 50, Appendix I dose limit. All results for Sr-90 and gamma emitting nuclides were less than MDC.
II. Introduction The Limerick Generating Station (LGS), consisting of two 3458 MWt boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No. 1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL to the western site boundary.                                  r This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2006.
II. Introduction The Limerick Generating Station (LGS), consisting of two 3458 MWt boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No. 1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL to the western site boundary.                                  r This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2006.
A.      Objective of the RGPP The long-term objectives of the RGPP are as follows:
A.      Objective of the RGPP The long-term objectives of the RGPP are as follows:
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: 6. Take necessary corrective actions to protect groundwater resources.
: 6. Take necessary corrective actions to protect groundwater resources.
B.      Implementation of the Objectives The objectives identified have been implemented at Limerick Generating Station as discussed below:
B.      Implementation of the Objectives The objectives identified have been implemented at Limerick Generating Station as discussed below:
: 1.      Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Connestoga Rovers and Associates (CRA) and the results and conclusions
: 1.      Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Connestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators as well as the public on an Exelon web site in station specific reports.
 
were made available to state and federal regulators as well as the public on an Exelon web site in station specific reports.
www*
www*
wexeloncorp com/nourcompanies/powergen/nuclear/Tritium.htm
wexeloncorp com/nourcompanies/powergen/nuclear/Tritium.htm
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: 5.      Limerick Generating Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.
: 5.      Limerick Generating Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.
C. Program Description Samples for the LGS RGPP Phase 1' were collected for Exelon Nuclear by Conestoga Rovers and Associates (CRA) and samples for Phase 2 were collected by on-site personnel and Normandeau Associates, RMC Environmental Services Division (RMC). This section describes the general collection methods used to obtain environmental samples for the LGS RGPP in 2006. Sample locations can be found in Table A-i, Appendix A.
C. Program Description Samples for the LGS RGPP Phase 1' were collected for Exelon Nuclear by Conestoga Rovers and Associates (CRA) and samples for Phase 2 were collected by on-site personnel and Normandeau Associates, RMC Environmental Services Division (RMC). This section describes the general collection methods used to obtain environmental samples for the LGS RGPP in 2006. Sample locations can be found in Table A-i, Appendix A.
: 1. Sample Collection Groundwater and Surface Water Samples of water were collected, managed, transported and analyzed in accordance with approved procedures following EPA methods. Both groundwater and surface water were collected. Sample locations, sample collection frequencies and analytical frequencies were controlled in accordance with approved station procedures. Contractor and/or station personnel were trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories were subject to internal quality assurance programs, industry
: 1. Sample Collection Groundwater and Surface Water Samples of water were collected, managed, transported and analyzed in accordance with approved procedures following EPA methods. Both groundwater and surface water were collected. Sample locations, sample collection frequencies and analytical frequencies were controlled in accordance with approved station procedures. Contractor and/or station personnel were trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories were subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits.
 
cross-check programs, as well as nuclear industry audits.
Station personnel reviewed and evaluated all analytical data deliverables as data were received.
Station personnel reviewed and evaluated all analytical data deliverables as data were received.
Analytical data results were reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to hydrogeologic conditions.
Analytical data results were reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to hydrogeologic conditions.
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Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-1 0 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.
Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-1 0 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.
Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.
Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.
Ill. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Limerick Generating Station RGPP in 2006.
Ill. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Limerick Generating Station RGPP in 2006.
In order to achieve the stated objectives, the current program includes the following analyses:
In order to achieve the stated objectives, the current program includes the following analyses:
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The pre-operational REMP contained analytical results from samples collected from both surface water and groundwater.
The pre-operational REMP contained analytical results from samples collected from both surface water and groundwater.
Monthly surface water sampling began in 1982, and the samples were analyzed for tritium as well as other radioactive analytes.
Monthly surface water sampling began in 1982, and the samples were analyzed for tritium as well as other radioactive analytes.
During the preoperational program tritium was detected at a maximum concentration of 420 pCi/L, indicating that these preoperational results were from nuclear weapons testing and are radioactively decaying as predicted. Gamma isotopic results from the
During the preoperational program tritium was detected at a maximum concentration of 420 pCi/L, indicating that these preoperational results were from nuclear weapons testing and are radioactively decaying as predicted. Gamma isotopic results from the preoperational program were all less than or at the minimum detectable concentration (MDC) level.
 
preoperational program were all less than or at the minimum detectable concentration (MDC) level.
: 1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others. Additional detail may be found by consulting references.
: 1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others. Additional detail may be found by consulting references.
: a. Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium.
: a. Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium.
Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.
Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.
A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.
A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.
: b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation
: b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected world wide from 1960 to 2006. RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons.
 
concentration data for samples collected world wide from 1960 to 2006. RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons.
Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time. Tritium concentrations in have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above. Water from previous years was naturally captured in groundwater. As a result, some well water sources today are affected by the surface water from the 1960s that contained elevated tritium activity.
Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time. Tritium concentrations in have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above. Water from previous years was naturally captured in groundwater. As a result, some well water sources today are affected by the surface water from the 1960s that contained elevated tritium activity.
: c. Surface Water Data Tritium concentrations are routinely measured in the Schuylkill and Delaware Rivers. Pennsylvania surface water data are typically less than 100 pCi/L.
: c. Surface Water Data Tritium concentrations are routinely measured in the Schuylkill and Delaware Rivers. Pennsylvania surface water data are typically less than 100 pCi/L.
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The radio-analytical laboratory is counting tritium results to an Exelon specified LLD of 200 pCi/L. Typically, the lowest positive measurement will be reported within a range of 40 -
The radio-analytical laboratory is counting tritium results to an Exelon specified LLD of 200 pCi/L. Typically, the lowest positive measurement will be reported within a range of 40 -
240 pCi/L or 140 +/- 100 pCi/L. Clearly, these sample results cannot be distinguished as different from background at this concentration.
240 pCi/L or 140 +/- 100 pCi/L. Clearly, these sample results cannot be distinguished as different from background at this concentration.
IV. Results and Discussion Gamma spectroscopy results for groundwater and surface water sample were reported for twelve nuclides (Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140 and La-140).
IV. Results and Discussion Gamma spectroscopy results for groundwater and surface water sample were reported for twelve nuclides (Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140 and La-140).
A. Groundwater Results Samples were collected from onsite wells throughout the year in accordance with the station radiological groundwater protection program.
A. Groundwater Results Samples were collected from onsite wells throughout the year in accordance with the station radiological groundwater protection program.
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No Sr-90 activity was detected in any of the ground water samples analyzed (Table B-I. 1, Appendix B).
No Sr-90 activity was detected in any of the ground water samples analyzed (Table B-I. 1, Appendix B).
Gamma Emitters Potassium-40 was detected in four of 38 samples. The concentrations ranged from 58 pCi/Liter to 119 pCi/Liter. No other gamma emitting nuclides were detected (Table B-I.2, Appendix B).
Gamma Emitters Potassium-40 was detected in four of 38 samples. The concentrations ranged from 58 pCi/Liter to 119 pCi/Liter. No other gamma emitting nuclides were detected (Table B-I.2, Appendix B).
B. Surface Water Results In accordance with the Station's radiological groundwater protection program surface water samples were collected from streams that transverses the site, as well as, from other water bodies that could influence the tritium concentration at Limerick. Analytical results and anomalies are discussed below.
B. Surface Water Results In accordance with the Station's radiological groundwater protection program surface water samples were collected from streams that transverses the site, as well as, from other water bodies that could influence the tritium concentration at Limerick. Analytical results and anomalies are discussed below.
Tritium Samples from 13 locations were analyzed for tritium activity (Table B-1.3, Appendix B). Tritium values ranged from < 141 to 2,020 pCi/L The Foundation Power Block Sump (FPBS) had the highest value of 2,020 pCi/L. The FPBS is located in the general area of wells P-12 and MW-LR-9.
Tritium Samples from 13 locations were analyzed for tritium activity (Table B-1.3, Appendix B). Tritium values ranged from < 141 to 2,020 pCi/L The Foundation Power Block Sump (FPBS) had the highest value of 2,020 pCi/L. The FPBS is located in the general area of wells P-12 and MW-LR-9.
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C. Drinking Water Well Survey A drinking water well survey was conducted during the summer 2006 by CRA (CRA 2006) around the Limerick Generating Station. CRA reviewed the Pennsylvania Groundwater Information System database to identify wells within a 1-mile radius from the center of the Station. Forty-six domestic withdrawal wells, two industrial wells, two commercial wells, and one institutional well were identified within the specified radius. The well depths range from 78 to 345 feet bgs, and they yield between 8 and 100 gallons per minute (gpm). All wells are completed in the Brunswick Formation.
C. Drinking Water Well Survey A drinking water well survey was conducted during the summer 2006 by CRA (CRA 2006) around the Limerick Generating Station. CRA reviewed the Pennsylvania Groundwater Information System database to identify wells within a 1-mile radius from the center of the Station. Forty-six domestic withdrawal wells, two industrial wells, two commercial wells, and one institutional well were identified within the specified radius. The well depths range from 78 to 345 feet bgs, and they yield between 8 and 100 gallons per minute (gpm). All wells are completed in the Brunswick Formation.
The Station has one potable supply well and one fire water well. The potable supply well is constructed as an open-rock borehole.
The Station has one potable supply well and one fire water well. The potable supply well is constructed as an open-rock borehole.
Groundwater was measured at a depth 102 feet bgs during a well pump replacement in 2004 (personal communication with Station, 2006). The pump was placed at a depth of approximately 294 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located approximately 175 feet east of the Reactor Building. The Station
Groundwater was measured at a depth 102 feet bgs during a well pump replacement in 2004 (personal communication with Station, 2006). The pump was placed at a depth of approximately 294 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located approximately 175 feet east of the Reactor Building. The Station estimates that the well is pumped at approximately 2 gpm. The fire water well is constructed as an open-rock borehole. Groundwater was encountered at 121 feet bgs during a well pump replacement in 2004. The well pump was placed at a depth of approximately 399 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located approximately 500 feet east of the cooling towers. The well is used only in an emergency fire situation; therefore, water use is estimated to be zero.
 
estimates that the well is pumped at approximately 2 gpm. The fire water well is constructed as an open-rock borehole. Groundwater was encountered at 121 feet bgs during a well pump replacement in 2004. The well pump was placed at a depth of approximately 399 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located approximately 500 feet east of the cooling towers. The well is used only in an emergency fire situation; therefore, water use is estimated to be zero.
D. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.
D. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.
E. Leaks, Spills, and Releases The Station records inadvertent release of radioactive liquids in accordance with 10 CFR 50.75)g). As part of the fleet wide assessment, a third party environmental engineering firm was contracted to evaluate historic releases, and determine if a potential pathway to the environment existed. Those releases that were determined to have potentially impacted groundwater were subsequently investigated as part of the fleet wide assessment. The hydrogeologic investigation determined that there is currently one radiological impacts to groundwater that is limited to the LGS site protected area boundary.
E. Leaks, Spills, and Releases The Station records inadvertent release of radioactive liquids in accordance with 10 CFR 50.75)g). As part of the fleet wide assessment, a third party environmental engineering firm was contracted to evaluate historic releases, and determine if a potential pathway to the environment existed. Those releases that were determined to have potentially impacted groundwater were subsequently investigated as part of the fleet wide assessment. The hydrogeologic investigation determined that there is currently one radiological impacts to groundwater that is limited to the LGS site protected area boundary.
F. Trends No trends have been identified.
F. Trends No trends have been identified.
G. Investigations Conclusions from the Phase 1 report have been made available to state and federal regulators and to the public. Currently no investigations are on going.
G. Investigations Conclusions from the Phase 1 report have been made available to state and federal regulators and to the public. Currently no investigations are on going.
H. Actions Taken
H. Actions Taken
: 1. Compensatory Actions There have been no station events requiring compensatory actions at the Limerick Generating Station.
: 1. Compensatory Actions There have been no station events requiring compensatory actions at the Limerick Generating Station.
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: 1. Conestoga Rovers and Associates, Fleetwide Assessment, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No. 045136(18), September 2006
: 1. Conestoga Rovers and Associates, Fleetwide Assessment, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No. 045136(18), September 2006
: 2. Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.
: 2. Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.
 
Intentionally Left Blank APPENDIX A LOCATION DESIGNATION
Intentionally Left Blank
 
APPENDIX A LOCATION DESIGNATION


TABLE A-1:  Radiological Groundwater Protection Program - Sampling locations for the Limerick Generating Station, 2006 I nfafinn                      Tii,r*            rlieft2nf-    QfIld    phnaa J- V                                J-MW-LR-1                        Monitoring Well    Onsite        1,2 MW-LR-2                        Monitoring Well    Onsite        1,2 MW-LR-3                        Monitoring Well    Onsite        1,2 MW-LR-4                        Monitoring Well    Onsite        1,2 MW-LR-5                        Monitoring Well    Onsite        1,2 MW-LR-6                        Monitoring Well    Onsite        1,2 MW-LR-7                        Monitoring Well    Onsite        1,2 MW-LR-8                        Monitoring Well    Onsite        1,2 MW-LR-9                        Monitoring Well    Onsite      2 P1l                            Monitoring Well    Onsite      2 P12                            Monitoring Well    Onsite        1 P14                            Monitoring Well    Onsite        1,2 P16                            Monitoring Well    Onsite        1,2 P17                            Monitoring Well    Onsite        1,2 P3                            Monitoring Well    Onsite        1,2 SP22                          Monitoring Well    Onsite        1,2 SW-LR-1                        Surface Water      Offsite      1,2 SW-LR-2                        Surface Water      Offsite      1 SW-LR-3                        Surface Water      Offsite      1 SW-LR-4                        Surface Water      Offsite      1 SW-LR-5                        Surface Water      Offsite      1 SW-LR-6                        Surface Water      Offsite      1 SW-LR-7                        Surface Water      Onsite        1 SW-LR-8                        Surface Water      Onsite      1,2 SW-LR-9                        Surface Water      Onsite      1,2 POWER BLOCK SUMP              Surface Water      Onsite      1 STILL CREEK                    Surface Water      Offsite      1 BRADSHAW RESERVE              Surface Water      Offsite      1 WADESVILLE MINE                Surface Water      Offsite      1 A-1
TABLE A-1:  Radiological Groundwater Protection Program - Sampling locations for the Limerick Generating Station, 2006 I nfafinn                      Tii,r*            rlieft2nf-    QfIld    phnaa J- V                                J-MW-LR-1                        Monitoring Well    Onsite        1,2 MW-LR-2                        Monitoring Well    Onsite        1,2 MW-LR-3                        Monitoring Well    Onsite        1,2 MW-LR-4                        Monitoring Well    Onsite        1,2 MW-LR-5                        Monitoring Well    Onsite        1,2 MW-LR-6                        Monitoring Well    Onsite        1,2 MW-LR-7                        Monitoring Well    Onsite        1,2 MW-LR-8                        Monitoring Well    Onsite        1,2 MW-LR-9                        Monitoring Well    Onsite      2 P1l                            Monitoring Well    Onsite      2 P12                            Monitoring Well    Onsite        1 P14                            Monitoring Well    Onsite        1,2 P16                            Monitoring Well    Onsite        1,2 P17                            Monitoring Well    Onsite        1,2 P3                            Monitoring Well    Onsite        1,2 SP22                          Monitoring Well    Onsite        1,2 SW-LR-1                        Surface Water      Offsite      1,2 SW-LR-2                        Surface Water      Offsite      1 SW-LR-3                        Surface Water      Offsite      1 SW-LR-4                        Surface Water      Offsite      1 SW-LR-5                        Surface Water      Offsite      1 SW-LR-6                        Surface Water      Offsite      1 SW-LR-7                        Surface Water      Onsite        1 SW-LR-8                        Surface Water      Onsite      1,2 SW-LR-9                        Surface Water      Onsite      1,2 POWER BLOCK SUMP              Surface Water      Onsite      1 STILL CREEK                    Surface Water      Offsite      1 BRADSHAW RESERVE              Surface Water      Offsite      1 WADESVILLE MINE                Surface Water      Offsite      1 A-1
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               /'
               /'
w!
w!
                                                          "%
WSW                                                    N N
WSW                                                    N N
0    500  1,000 1,500 2,000 Feet Figure 1      Phase 2 Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2006 A-2
0    500  1,000 1,500 2,000 Feet Figure 1      Phase 2 Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2006 A-2
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APPENDIX B DATA TABLES
APPENDIX B DATA TABLES


TABLE B-I.1  CONCENTRATIONS OF TRITIUM AND STRONIUM-90 IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION      H-3                  SR-90 STC              DATE MW-LR-1          05/17/06          183                < 0.72
TABLE B-I.1  CONCENTRATIONS OF TRITIUM AND STRONIUM-90 IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION      H-3                  SR-90 STC              DATE MW-LR-1          05/17/06          183                < 0.72 MW-LR-1          10/17/06          181                < 0.91 MW-LR-2          05/18/06          184                  0.9 MW-LR-2 DUP      05/18/06          169                  1.41 MW-LR-2          10/16/06          181                  1.35 MW-LR-2          10/17/06          185                  0.92 MW-LR-3          05/18/06          170                < 1.18 MW-LR-3          10/18/06          180                < 1.33 MW-LR-4          05/19/06          222 +/- 118          < 0.8 MW-LR-4          10/17/06    <    185      *        < 1.4 MW-LR-5          05/19/06          305  +/-    121        0.79 MW-LR-5          10/18/06    <    183                  1.11 MW-LR-5          10/18/06          236  ::1  118*      1.49 MW-LR-5          10/18/06          275  +/-1    137*      1.42 MW-LR-5          10/18/06          247  +/-    118*
* MW-LR-1          10/17/06          181                < 0.91 MW-LR-2          05/18/06          184                  0.9 MW-LR-2 DUP      05/18/06          169                  1.41
* MW-LR-2          10/16/06          181                  1.35
* MW-LR-2          10/17/06          185                  0.92 MW-LR-3          05/18/06          170                < 1.18 MW-LR-3          10/18/06          180                < 1.33 MW-LR-4          05/19/06          222 +/- 118          < 0.8 MW-LR-4          10/17/06    <    185      *        < 1.4 MW-LR-5          05/19/06          305  +/-    121        0.79 MW-LR-5          10/18/06    <    183                  1.11 MW-LR-5          10/18/06          236  ::1  118*      1.49 MW-LR-5          10/18/06          275  +/-1    137*      1.42 MW-LR-5          10/18/06          247  +/-    118*
MW-LR-5          10/18/06          209  +/-    129*
MW-LR-5          10/18/06          209  +/-    129*
MW-LR-6          05/17/06          182                  1.35
MW-LR-6          05/17/06          182                  1.35 MW-LR-6          10/16/06          180                  1.35 MW-LR-6          10/17/06          175                  1.34 MW-LR-7          05/18/06          166                  1.16 MW-LR-7          10/16/06          181                  1.49 MW-LR-7          10/18/06          167                  1.47 MW-LR-8          06/28/06          184  +/-    116 MW-LR-8          07/07/06          244  +/-    116*
* MW-LR-6          10/16/06          180                  1.35
* MW-LR-6          10/17/06          175                  1.34 MW-LR-7          05/18/06          166                  1.16
* MW-LR-7          10/16/06          181                  1.49
* MW-LR-7          10/18/06          167                  1.47 MW-LR-8          06/28/06          184  +/-    116 MW-LR-8          07/07/06          244  +/-    116*
MW-LR-8          08/16/06          246  +    124*      < 1.56 MW-LR-8          10/18/06    <    180                < 1.37
MW-LR-8          08/16/06          246  +    124*      < 1.56 MW-LR-8          10/18/06    <    180                < 1.37
* INDICATES DISTILLED ANALYSIS B-1
* INDICATES DISTILLED ANALYSIS B-1
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TABLE B-1.1  CONCENTRATIONS OF TRITIUM AND STRONIUM-90 IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION          DATE              H-3              SR-90 MW-LR-9          08/16/06        1500 +/- 210*                1.24 MW-LR-9          10/19/06    <  171                      1.33 MW-LR-9          10/19/06        238 +/- 120*                1.36 MW-LR-9          10/19/06    <  172 MW-LR-9          10/19/06    <  180 P1l              05/18/06    <  184                      1.35 Pll              10/17/06        204 +/- 118*                1.48
TABLE B-1.1  CONCENTRATIONS OF TRITIUM AND STRONIUM-90 IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION          DATE              H-3              SR-90 MW-LR-9          08/16/06        1500 +/- 210*                1.24 MW-LR-9          10/19/06    <  171                      1.33 MW-LR-9          10/19/06        238 +/- 120*                1.36 MW-LR-9          10/19/06    <  172 MW-LR-9          10/19/06    <  180 P1l              05/18/06    <  184                      1.35 Pll              10/17/06        204 +/- 118*                1.48
.Pll              10/17/06    <  187
.Pll              10/17/06    <  187
* 0.81 P11 DUP          05/18/06    <  185 P12              05/18/06        4360 +/-          494          1.3 P12              05/18/06        4350 +/-          199 P14              05/18/06        185                      0.89
* 0.81 P11 DUP          05/18/06    <  185 P12              05/18/06        4360 +/-          494          1.3 P12              05/18/06        4350 +/-          199 P14              05/18/06        185                      0.89 P14              10/17/06        180                      1.36 P16              05/18/06    <  182                <      0.94 P17              05/17/06    <  183                <      1.37 P17              10/18/06    <  174                <      1.48 P3              05/18/06        170                      1.12 P3              10/19/06        178                      1.46 SP22            05/19/06        165                      0.55 SP22            10/17/06        185
* P14              10/17/06        180                      1.36 P16              05/18/06    <  182                <      0.94 P17              05/17/06    <  183                <      1.37
* P17              10/18/06    <  174                <      1.48 P3              05/18/06        170                      1.12
* P3              10/19/06        178                      1.46 SP22            05/19/06        165                      0.55 SP22            10/17/06        185
* 1.4
* 1.4
* INDICATES DISTILLED ANALYSIS B-2
* INDICATES DISTILLED ANALYSIS B-2

Revision as of 15:47, 13 March 2020

Annual Radiological Environmental Operating Report 22 for 2006
ML071230217
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 04/30/2007
From:
Teledyne Brown Engineering Environmental Services
To:
Exelon Nuclear, Office of Nuclear Reactor Regulation
References
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Text

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Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report Report No. 22 1 January Through 31 December 2006 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2007

            • `*:::**::**:::**::*******:****::***::**::***:*`*****`*:***;*`***`*;::*

Table Of Contents I. Summary and Conclusions ............................................................................ 1 II. Introduction .............................................................................................. . . 3 A. Objectives of the REMP ..................................................................... 3 B. Implementation of the Objectives ......................................................... 3 Ill. Program Description .................................................................................. 4 A. Sample Collection ........................................................................... 4 B. Sample Analysis .............................................................................. 6 C. Data Interpretation .............................................................  :................... 6 D. Program Exceptions .......................................................................... 8 E. Program Changes ............................................................................ 10 IV. Results and Discussion ............................................................................ 10 A. Aquatic Environment ............................................................................ 10

1. Surface W ater ........................................................................... 10
2. Drinking Water ..................................................................... 10 3 . F ish .................................................................................... . . 11 4 . Se d im e nt ................................................................................... 11 B. Atmospheric Environment ................................................................. 12
1. Airborne ................................................................................ 12
a. Air Particulates ............................................................. 12
b. Airborne Iodine ............................................................. 13
2. Terrestrial .............................................................................. 13 a . Milk ................................................................................ 13
b. Broad Leaf Vegetation ................................................. 14 C. Ambient Gamma Radiation .............................................................. 14 D. 10 CFR 20.2002 Permit Storage Area .................................. ................... 15 E. Land Use Survey ............................................................................. 15 F. Summary of Results - Inter-Laboratory Comparison Program .................... 15 V. References .............................................................................................. 18

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Limerick Generating Station, 2006.

Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Tables Table B-I: Location Designation and Identification System for the Limerick Generating Station.

Table B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2006.

Table B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2006.

Figures Figure B-I: Environmental Sampling Locations Within One Mile of the Limerick Generating Station, 2006.

Figure B-2: Environmental Sampling Locations Between One and Five Miles from the Limerick Generating Station, 2006.

Figure B-3: Environmental Sampling Locations Greater Than Five Miles from the Limerick Generating Station, 2006.

Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-1.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2006.

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Table C-II. 1 Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-II.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-11.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-111.1 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-IV. 1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-VI. 1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-VII. 1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-VIII.1 Concentrations of Gamma Emitters in Broad Leaf Vegetation Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table C-IX. 1 Quarterly TLD Results for Limerick Generating Station, 2006.

Table C-IX.2 Mean Quarterly TLD Results for the Site Boundary, Middle and Control Locations for Limerick Generating Station, 2006.

Table C-IX.3 Summary of the Ambient Dosimetry Program for Limerick Generating Station, 2006.

Table C-X.1 Summary of Collection Dates for Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Figures Figure C-1 Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 - 2006.

Figure C-2 Mean Annual Cs-1 37 Concentrations in Fish Samples Collected in the Vicinity of LGS, 1982 - 2006.

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Figure C-3 Concentrations of Cs-1 37 in Sediment Samples Collected in the Vicinity of LGS, 1982 - 2006.

Figure C-4 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 - 2006.

Figure C-5 Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2006.

Figure C-6 Mean Quarterly Ambient Gamma Radiation Levels (TLD) in the Vicinity of LGS, 1985 - 2006.

Appendix D Data Tables and Figures - Comparison Laboratory Tables Table D-1.1 Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2006.

Table D-I.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2006.

Table D-I.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table D-II.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table D-11.2 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table D-Ill.1 Concentrations of 1-131 by Chemical Separation and Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Table D-IV.1 Summary of Collection Dates for Samples Collected in the Vicinity of Limerick Generating Station, 2006.

Eigures Figure D-1 Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between ENV and TBE, 2006.

Figure D-2 Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11 S1 and 11S2, 2006.

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Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2006.

Table E-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2006.

Table E-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2006.

Table E-4 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2006.

Table E-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2006.

Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) v

Intentionally Left Blank vi

1. Summary and Conclusions In 2006 the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 40 curies of noble gas, fission and activation products and approximately 64 curies of tritium.

The dose from both liquid and gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public. The results of those calculations and their comparison to the allowable limits were as follows:

Gaseous and liquid radiation doses to members of the public at locations Effluent Applicable Estimated Age Location  % of Limit Unit Organ Dose Group Distance Direction Applicable (meters) (toward) Limit Noble Gas Gamma - Air Dose 2.1 9E-03 All 762 SE 0.011% 20 mRad Noble Gas Beta - Air Dose 1.38E-03 All 762 SE 0.004% 40 mRad Noble Gas Total Body (Gamma) 1.45E-03 All 762 SE 0.015% 10 mrem Noble Gas Skin (Beta) 2.71 E-03 All 762 SE 0.009% 30 mrem Iodine, Particulate & Thyroid 4.71E-03 Infant 762 SE 0.016% 30 mrem Tritium Liquid Total Body 2.16E-03 Child Phila. Sub. Water 0.036% 6 mrem Liquid Liver 2.32E-03 Teen LGS Outfall 0.001% 20 mrem The doses as a result of the radiological effluents released from Limerick were a very small percentage of the allowable limits.

This report on the Radiological Environmental Monitoring Program conducted for the Limerick Generating Station (LGS) by Exelon covers the period 1 January 2006 through 31 December 2006. During that time period, 1,128 analyses were performed on 918 samples.

Surface and drinking water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Drinking water samples were also analyzed for concentrations of total gross beta. No fission or activation products were detected. Gross beta activities detected were consistent with those detected in previous years. Tritium was found at one downstream location at a concentration of 177 pCi/L, which was below the lower limit of detection of 200 pCi/L. The dose via the drinking water pathway was calculated at 0.018 mrem to a child (total body), which was 0.31% of the 10 CFR 50, Appendix I dose limit.

Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected.

Sediment samples collected below the discharge had elevated Cesium-1 37 concentrations that were the result of LGS discharges. No other Plant produced fission or activation products were found in sediment. The calculated dose to a teenager's skin and whole body was 1.1 3E-3 mrem and 9.66E-4 mrem, respectively. This dose represents 0.006% and 0.016%, respectively of the 10 CFR Part 50, Appendix I dose limits.

1

Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. Cosmogenic Be-7 was detected at levels consistent with those detected in previous years. No fission or activation products were detected.

High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable concentration.

Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. All 1-131 results were below the minimum detectable concentration. Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were found.

Broad Leaf Vegetation samples were analyzed for gamma emitting nuclides.

Concentrations of naturally occurring Be-7 and K-40 were detected. No activation or fission products were detected.

Environmental gamma radiation measurements were performed quarterly using thermoluminescent dosimeters. Levels detected were consistent with those observed in previous years.

Review of the gamma spectroscopy results from the surface water samples located at the Limerick intake (24S1) and downstream of the 10CFR20.2002 permitted storage area indicated no offsite radionuclide transport was evident.

A radiological groundwater protection program (RGPP) was established in 2006 as part of an Exelon Nuclear fleetwide assessment of potential groundwater intrusion from the operation of the Station. Well water samples were analyzed for tritium, Sr-90 and gamma emitters. Most tritium values were less than the lower limit of detection of 200 pCi/L. However, one well located near the Unit 1 Condensate Storage Tank dike had tritium as high as 4,360 pCi/L. It is likely that the tritium migrated from the Unit 1 Condensate Storage Tank and or the auxiliary heating steam pipe leak to the monitoring well. The dose via the drinking water pathway was calculated at 0.451 mrem to a child (total body),

which was 7.52% of the 10 CFR 50, Appendix I dose limit. All results for Sr-90 and gamma emitting nuclides were less than MDC.

In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of LGS had no adverse radiological impact on the environment.

2

II. Introduction The Limerick Generating Station (LGS), consisting of two 3458 MWt boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No. 1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL to the western site boundary.

A Radiological Environmental Monitoring Program (REMP) for LGS was initiated in 1971. Review of the 1971 through 1977 REMP data resulted in the modification of the program to comply with changes in the Environmental Report Operating License Stage (EROL) and the Branch Technical Position Paper (Rev. 1, 1979). The preoperational period for most media covers the periods 1 January 1982 through 21 December 1984 and was summarized in a separate report. This report covers those analyses performed by Teledyne Brown Engineering (TBE), Global Dosimetry, and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2006 through 31 December 2006.

On 6 July 1996 a 10CFR20.2002 permit was issued to Limerick for storage of slightly contaminated soils, sediments and sludges obtained from the holding pond, cooling tower and spray pond systems. These materials will decay to background while in storage. Final disposition will be determined at Station decommissioning.

A. Objective of the REMP The objectives of the REMP are to:

1. Provide data on measurable levels of radiation and radioactive materials in the site environs.
2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.

B. Implementation of the Objectives The implementation of the objectives is accomplished by:

1. Identifying significant exposure pathways.
2. Establishing baseline radiological data of media within those pathways.
3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.

Ill. Program Description A. Sample Collection Samples for the LGS REMP were collected for Exelon Nuclear by Normandeau Associates, RMC Environmental Services Division (RMC).

This section describes the general collection methods used by RMC to obtain environmental samples for the LGS REMP in 2006. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by RMC are listed in Table B-3.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, fish, and sediment.

Two-gallon water samples were collected monthly from continuous samplers located at two surface water locations (13B1 and 24S1) and four drinking water locations (15F4, 15F7, 16C2, and 28F3). Control locations were 24S1, and 28F3. All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, catfish/bullhead (bottom feeder) and sunfish (predator), were collected semiannually at two locations, 16C5 and 29C1 (control). Sediment samples composed of recently deposited substrate were collected at three locations semiannually, 16B2, 16C4 and 33A2 (control).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, and milk.

Airborne iodine and particulate samples were collected and analyzed weekly at five locations (1OS3, 11 S1, 13C1, 14S1, and 22Gi). The control location was 22G1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.

Milk samples were collected biweekly at five locations (10F4, 18E1, 19B1, 23F1, and 25Cl) from April through November, and monthly from December through March. Two additional locations (25E1 and 36E1) were sampled quarterly. Locations 36E1 and 23F1 were controls. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory.

Broad Leaf Vegetation were collected monthly at three locations (1 lS3, 13S3 and 31G1). The control location was 31G1. Thirteen different kinds of vegetation samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.

Ambient Gamma Radiation Direct radiation measurements were made using Panasonic 814 calcium sulfate (CaSO 4 ) thermoluminescent dosimeters (TLD). The TLD locations were placed on and around the LGS site as follows:

A site boundary ring consisting of 16 locations (36S2, 3S1, 5S1, 7S1, 10S3, 11S1, 13S2, 14S1, 18S2, 21S2, 23S2, 25S2, 26S3, 29S1, 31S1 and 34S2) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from LGS release.

An intermediate distance ring consisting of 16 locations (36D1, 2E1, 4E1, 7E1, 1OE1, 10F3, 13E1, 16F1, 19D1, 20F1, 24D1, 25D1, 28D2, 29E1, 31 D2, and 34E1) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.

The balance of eight locations (5H1, 6C1, 9C1, 13C1, 15D1, 17B1, 20D1 and 31 D1) representing control and special interests areas such as population centers, schools, etc.

The specific TLD locations were determined by the following criteria:

1. The presence of relatively dense population;
2. Site meteorological data taking into account distance and elevation for each of the sixteen-22 1/2 degree sectors around the site, where estimated annual dose from LGS, if any, would be most significant;
3. On hills free from local obstructions and within sight of the vents (where practical);
4. And near the closest dwelling to the vents in the prevailing downwind direction.

Two TLDs - each comprised of three CaSO 4 thermoluminescent phosphors enclosed in plastic - were placed at each location in a PVC conduit located approximately three feet above ground level. The TLDs were exchanged quarterly and sent to Global for analysis.

10CFR20.2002 Permit Storage Area The results of the surface water sampling program were used to determine if radioactive nuclide transport from the storage area into the Schuylkill River had occurred.

B. Sample Analysis This section describes the general analytical methodologies used by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the LGS REMP in 2006. The analytical procedures used by the laboratories are listed in Table B-3.

In order to achieve the stated objectives, the current program includes the following analyses:

1. Concentrations of beta emitters in drinking water, and air particulates.
2. Concentrations of gamma emitters in surface and drinking water, air particulates, milk, fish, broad leaf vegetation and sediment.
3. Concentrations of tritium in surface and drinking water.
4. Concentrations of 1-131 in air and milk.
5. Ambient gamma radiation levels at various site environs.

C. Data Interpretation The radiological and direct radiation data collected prior to LGS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this report, LGS was considered operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required LGS detection limits for environmental sample analysis.

The minimum detectable concentration (MDC) was defined as above with the exception that the measurement is an after the fact estimate of the presence of activity.

2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity affecting a negative number. An MDC was reported in all cases where positive activity was not detected.

If no positive activity was detected, then gamma spectroscopy MDC results for each type of sample were grouped as follows:

For surface and drinking water twelve nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-1 40, and La-1 40 were reported.

For fish nine nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, 1-131, Cs-1 34, and Cs-1 37 were reported.

For sediment and broad leaf vegetation seven nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, Cs-1 34, and Cs-1 37 were reported.

For air particulate six nuclides, Be-7, Mn-54, Co-58, Co-60, Cs-1 34, and Cs-1 37 were reported.

For milk five nuclides, K-40, Cs-134, Cs-137, Ba-140, and La-140 were reported.

Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.

D. Program Exceptions For 2006 the LGS REMP had a sample recovery rate in excess of 99%.

Exceptions are listed below:

1. Drinking Water composite sampler at location 16C2 was out of service during the following periods due to equipment malfunction:

10/30/06, 12/11/06 and 12/18/06 Grab samples were taken for the composite.

2. Drinking Water composite sampler at location 28F3 was out of service during the following weeks due to equipment malfunction or electrical failure:

9/5/06, 9/25/06, 10/2/06, 10/9/06 and 10/16/06 Grab samples were taken for the composites.

3. Drinking Water composite sampler at 1 5F4 was out of service on 10/23/06 - due to low volume. A partial grab sample was taken for the composite.
4. Drinking Water composite sampler at location 1 5F7 was out of service during the following weeks due to equipment malfunction:

8/8/06, 9/5/06 and 9/12/06 Grab samples were taken for the composites.

5. Surface Water composite sampler at location 13B1 was out of service during the following weeks:

1/17/06 - Low sample volume due to low river level.

2/13/06, 2/20/06 and 2/28/09 - due to a frozen intake line.

7/3/06, 7/10/06, 8/8/06, 9/5/06 and 9/11/06, 11/20/06 - due to river flooding.

9/25/06 - due to an electrical malfunction.

10/16/06 and 12/18/06 - due to equipment malfunction.

11/6/06 - due to a sample collection error.

Grab samples were taken for the composites.

6. Surface Water composite sampler at location 24S1 was out of service during the following weeks:

2/6/06, 4/3/06, 4/10/06, 4/17/06 and 7/3/06- due to equipment malfunction.

3/6/06 and 3/27/06 - due to an electrical malfunction.

Grab samples were taken for the composites.

7. Air particulate and air iodine samples had low sample volume at location 22G1 for week 29 due to electrical problems.
8. Air particulate and air iodine samples had low sample volume at location 14S1 for week 40 due to electrical problems.
9. During the third quarter, TLD samples were not available at location 25S2, due to vandalism.
10. A third type of broad leaf vegetation sample was not taken at location 13S3 due to the lack of available vegetation.
11. Milk 1-131 LLD of 1.0 pCi/L was missed due to the discontinuation and poor performance of two types of filter paper used in the 1-131 analysis. Although sample aliquots were increased (up to 8 liters, when possible) and count times extended (up to 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br />, in some cases), LLD requirements were missed due to low chemical yield and decay of the iodine during the investigation. TBE initiated NCR 06-13 to investigate and document this event. The following locations and dates were effected:

10F4 06/13/06 06/27/06 07/25/06 18E1 06/13/06 06/27/06 07/25/06 19B11 06/13/06 06/27/06 23F1 06/13/06 06/27/06 07/25/06 25C1 06/13/06 06/27/06 07/25/06 Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. Occasional equipment breakdowns and power outages were unavoidable.

The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

E. Program Changes Three broad leaf vegetation locations, 11 S3, 13S3 and 31 G1 were added to Limerick's sampling program in 2006.

Surface Water composite sampler at location 10F2 was removed from Limerick's sampling program since no water was drawn from the Delaware River for station cooling.

IV. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken from a continuous sampler at two locations (133B1 and 24S1) on a monthly schedule. Of these locations only 13B1 located downstream, could be affected by Limerick's effluent releases. The following analyses were performed.

Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-I. 1, Appendix C). No tritium activity was detected. The highest MDC calculated was <174 pCi/L.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-l.2, Appendix C). All nuclides were less than the MDC.

2. Drinking Water Monthly samples were collected from continuous water samplers at four locations (15F4, 15F7, 16C2, and 28F3). Three locations (15F4, 15F7, and 16C2) could be affected by Limerick's effluent releases. The following analyses were performed:

.Gross Beta Samples from all locations were analyzed for concentrations of total gross beta (Tables C-I1.1, Appendix C). The values ranged from <2.3 to 8.3 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C).

Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-I1.2, Appendix C). Tritium activity was detected in one sample at a concentration of 177 pCi/L. The dose via the drinking water pathway was calculated at 0.018 mrem to a child (total body), which was 0.31% of the 10 CFR 50, Appendix I dose limit.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-11.3, Appendix C). All nuclides were less than the MDC.

Fish Fish samples comprised of catfish/bullhead (bottom feeder) and sunfish (predator) were collected at two locations (16C5 and 29C1) in the spring and fall season. Location 16C5 could be affected by Limerick's effluent releases. The following analysis was performed:

Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-I11.1, Appendix C).

Naturally occurring K-40 was found at all stations and ranged from 2,750 to 3,320 pCi/kg wet and was consistent with levels detected in previous years. No other gamma emitting nuclides were found.

Historical levels of Cs-1 37 are shown in Figure C-2, Appendix C.

4. Sediment Aquatic sediment samples were collected at three locations (16B2, 16C4 and 33A2) semiannually. Of these locations two 16B2 and 16C4 located downstream, could be affected by Limerick's effluent releases. The following analysis was performed:

Gamma Soectrometrv Sediment samples from all three locations were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). Nuclides detected were naturally occurring Be-7, K-40 and the fission product Cs-137.

Beryllium-7 and K-40 were found at all stations and ranged from

<968 to 5,380 and 13,800 to 18,900 pCi/kg dry, respectively. The fission product Cs-1 37 was found at locations 16B2 and 16C4 and ranged from <117 to 172 and 134 to 429 pCi/kg dry, respectively.

The elevated Cs-1 37 activity was due to LGS radioactive effluent releases. The dose to a teenager's skin and whole body was conservatively calculated at 1.1 3E-3 mrem and 9.66E-4 mrem, respectively. These doses represent 0.006% and 0.016%,

respectively of the Appendix I to 10 CFR Part 50 dose limits. The activity detected was consistent with those detected in the pre-operational years. (Figure C-4, Appendix C). No other Limerick fission or activation products were found.

B. Atmospheric Environment

1. Airborne
a. Air Particulates Continuous air particulate samples were collected from five locations on a weekly basis. The five locations were separated into three groups: Group I represents locations within the LGS site boundary (10S3, 11S1, and 14S1),

Group II represents the location at an intermediate distance from the LGS site (13C1), and Group III represents the control location at a remote distance from LGS (22G1). The following analyses were performed:

Gro ss Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-V. 1 and C-V.2, Appendix C).

Detectable gross beta activity was observed at all locations.

Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of LGS. The results from the On-Site locations (Group I) ranged from <6 to 31 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3 . The results from the Intermediate Distance location (Group II) ranged from <7 to 27 E-3 pCi/i 3 with a mean of 16 E-3 pCi/m . The results from the Distant locations (Group 1Il) ranged from'<7 to 35 E-3 pCi/M 3 with a mean of 17 E-3 pCi/m 3 . Comparison of the 2006 air particulate data with previous years data indicate no effects from the operation of LGS (Figure C-4, Appendix C). In addition a comparison of the weekly mean values for 2006 indicate no notable differences among the three groups (Figure C-5, Appendix C).

Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C).

Naturally occurring Be-7 due to cosmic ray activity was detected in all samples. These values ranged from 43 to 126 E-3 pCi/m 3 . All other nuclides were less than the MDC.

b. Airborne Iodine Continuous air samples were collected from five locations (10S3, 1lS1, 14S1, 13C1, and 22G1) and analyzed weekly, for 1-131 (Table C-VI.1, Appendix C). All results were less than the MDC.
2. Terrestrial
a. Milk Samples were collected from five locations (10F4. 18E1, 19B1, 23F1, and 25C1) biweekly April through November and monthly December through March. Samples from two additional locations (36E1 and 25E1) were taken quarterly.

The following analyses were performed:

odione-131 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VII. 1, Appendix C). All results were less than the MDC.

Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C).

Naturally occurring K-40 activity was found in all samples and ranged from 1,050 to 1,450 pCi/L. All other nuclides were less than the MDC.

b. Broad Leaf Vegetation Three types of broad leaf vegetation samples were collected from three locations (1 lS3, 13S3 and 31G1) monthly from June through September. The following analysis was performed:

Gamma Spectrometry Each broad leaf vegetation sample was analyzed for concentrations of gamma emitting nuclides (Table C-VIII.I, Appendix C).

Cosmogenic Be-7 was found in 27 of 35 samples and ranged from <23 to 2180 pCi/kg wet. Naturally occurring K-40 was found in 34 of 35 samples and ranged from <177 to 8,430 pCi/kg wet. All other nuclides were less than the MDC.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO 4 ) thermoluminescent dosimeters. Forty TLD locations were established around the site. Results of TLD measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C.

Most TLD measurements were below 10 mR/standard month, with a range of 5.5 to 12.8 mR/standard month. A comparison of the Site Boundary and Intermediate Distance data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Location 5H1 were consistently higher. The historical ambient gamma radiation data from Location 5H1 were plotted along with similar data from the Site, Intermediate Distance and Outer Ring Locations (Figure C-6, Appendix C). Location 5H1 has a historical high bias, but tracked with the data from all three groups. This bias is most likely due to radon emanating from the ground.

D. 10 CFR 20.2002 Permit Storage Area The results of the surface water aquatic monitoring program from Location 24S1 were used to determine if radioactivity from the permit storage area had made it to the Schuylkill River. The data obtained from the gamma analysis program did not detect any migration of radioactivity from the permit storage area.

E. Land Use Survey A Land Use Survey conducted in August 2006 around Limerick Generating Station (LGS) was performed by Normandeau Associates, RMC Environmental Services Division for Exelon Nuclear to comply with Bases 3.3.2 of the Limerick's Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident, milk producing animal and garden of greater than 500 ft2 in each of the sixteen 22 1 degree sectors around the site. Four new gardens are included in the 2006 survey. The gardens are located in sectors ESE, SE, NNE and NNW. The distance and direction of all locations from the LGS reactor buildings were positioned using Global Positioning System (GPS) technology. There were no changes required to the LGS REMP, as a result of this survey. The results of this survey are summarized below.

Distance in Miles from the LGS Reactor Buildings Sector Residence Garden Milk Farm Miles Miles Miles 1N 0.6 1.8 4.7 2 NNE 0.5 1.8 3NE 0.7 1.6 4 ENE 0.6 0.7 5E 0.5 0.7 6 ESE 0.7 0.3 7SE 1.0 0.2 8 SSE 1.0 1.1 9S 0.8 1.2 4.2 10 SSW 1.0 1.0 2.0 11 SW 0.6 0.6 12 WSW 0.7 2.3 2.7 13W 0.7 0.8 2.8 14 WNW 0.7 0.8 15 NW 0.7 1.6 16 NNW 1.0 1.3 F. Summary of Results - Inter-laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices for 28 analytes (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria:

1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.
2. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, -as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.
3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.

The MAPEP defines three levels of performance: Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% < bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.

For the primary laboratory, 24 out of 28 analytes met the specified acceptance criteria. Four samples did not meet the specified acceptance criteria for the following reasons:

1. Teledyne Brown Engineering's MAPEP Series 15 January 2006 soil Cs-1 34 was evaluated as a false positive, although TBE considered the result a non-detect due to the peak not being identified by the gamma software. MAPEP suggests the Bi-214 is not being differentiated from the Cs-1 34 peak. When the ratio of activity to uncertainty exceeds 3, TBE will use a key line analysis rather than a weighted mean analysis when evaluating MAPEP non-detects.
2. Teledyne Brown Engineering's MAPEP Series 15 January 2006 Sr-90 in vegetation result of 2.22 Bq/kg exceeded the upper acceptance range of 2.029 Bq/kg. The samples were analyzed in triplicate and the results averaged. One high result of 2.43 Bq/kg biased the submitted results on the high side. TBE was unable to determine the cause for the higher result. The Sr-90 in vegetation results for MAPEP Series 14 and MAPEP Series 16 were acceptable. No client samples were analyzed during the MAPEP Series 14 time period.
3. Teledyne Brown Engineering's MAPEP Series 15 January 2006 Pu-238 and Pu-239/240 in vegetation result of 2.22 Bq/kg failed the required acceptance ranges. TBE was evaluating the current preparation method for vegetation samples, which proved insufficient for the analyses. TBE does not perform isotopic Pu on client's vegetation samples.

For the secondary laboratory, 20 out of 25 analytes met the specified acceptance criteria. Four samples did not meet the specified acceptance criteria for the following reasons:

1. Environmental Inc.'s ERA November 2006 water 1-131 result of 28.4 pCi/L exceeded the upper control limit of 27.3 pCi/L. The reported result was an average of three analyses, results ranged from 25.36 pCi/L to 29.23 pCi/L. A fourth analysis was performed, with a result of 24.89 pCi/L.
2. Environmental Inc.'s MAPEP January 2006 vegetation Pu-238 result of 0.08 Bq/sample exceeded the lower control limit of 0.10 Bq/sample due to incomplete dissolution of the sample.
3. Environmental Inc.'s MAPEP January 2006 air particulate Pu-238 result of 0.03 Bq/sample exceeded the lower control limit of 0.05 Bq/sample due to incomplete dissolution of the sample.
4. Environmental Inc.'s MAPEP January 2006 soil Pu-238, Pu-239/240, U-233/234 and U-238 results of 14.6, 14.6, 13.5 and 15.4 Bq/kg, respectively, exceeded the lower control limits of 42.81, 32.09, 25.9 and 27.2 Bq/kg, respectively, due to incomplete dissolution of the sample.

The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.

V. References

1. Environmental Report Operating License Stage, Limerick Generating Station, Units 1 and 2, Volumes 1-5 Philadelphia Electric Company.
2. Branch Technical Position Paper, Regulatory Guide 4.8, Revision 1, November 1979.
3. Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.

c APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2006 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER H-3 8 200 166 166 166 13B1 INDICATOR 0 (PCI/LITER) (0/4) (0/4) (0/4) VINCENT DAM

(<156/<174) (<154/<173) (<156/<174) 1.75 MILES SE OF SITE GAMMA 24 MN-54 15 4 4 4 24S1 CONTROL 0 (0/12) (0/12) (0/12) LIMERICK INTAKE

(<1/<8) (<2/<8) (<2/<8) 0.20 MILES SW OF SITE CO-58 15 4 4 4 24S1 CONTROL 0 (0/12) (0/12) (0/12) LIMERICK INTAKE

(<1/<7) (<2/<9) (<2/<9) 0.20 MILES SW OF SITE FE-59 30 9 9 9 13B1 INDICATOR 0 (0/12) (0/12) (0/12) VINCENT DAM

(<2/<17) (<4/< 15) (<2/<17) 1.75 MILES SE OF SITE CO-60 15 4 4 4 24S1 CONTROL 0 (0/12) (0/12) (0/12) LIMERICK INTAKE

(<1/<7) (<2/<9) (<2/<9) 0.20 MILES SW OF SITE ZN-65 30 9 9 9 24S1 CONTROL 0 (0/12) (0/12) (0/12) LIMERICK INTAKE

(<1/<17) (<4/<22) (<4/<22) 0.20 MILES SW OF SITE NB-95 15 4 4 4 24S1 CONTROL 0 (0/12) (0/12) (0/12) LIMERICK INTAKE

(<1/<8) (<2/<8) (<2/<8) 0.20 MILES SW OF SITE

  • THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING BOTH THE MDAs AND THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

A-1

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2006 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER ZR-95 30 7 7 7 24S1 CONTROL 0 (PCI/LITER) (0/12) (0/12) (0/12) LIMERICK INTAKE

(<1/<14) (<3/<14) (<3/<14) 0.20 MILES SW OF SITE 1-131 15 11 11 11 24S1 CONTROL 0 (0/12) (0/12) (0/12) LIMERICK INTAKE

(<4/< 19) (<5/< 17) (<5/<17) 0.20 MILES SW OF SITE CS-134 15 4 4 4 24S1 CONTROL 0 (0/12) (0/12) (0/12) LIMERICK INTAKE

(<1/<8) (<2/< 10) (<2/< 10) 0.20 MILES SW OF SITE CS-137 18 4 4 4 13B1 INDICATOR 0 (0/12) (0/12) (0/12) VINCENT DAM

(<1/<8) (<2/<8) (<1/<8) 1.75 MILES SE OF SITE BA-1 40 60 24 25 25 24S1 CONTROL 0 (0/12) (0/12) (0/12) LIMERICK INTAKE

(<7/<34) (<13/<43) (<`13/<43) 0.20 MILES SW OF SITE LA-140 15 8 8 8 13B1 INDICATOR 0 (0/12) (0/12) (0/12) VINCENT DAM

(<2/<12) (<5/< 12) (<2/< 12) 1.75 MILES SE OF SITE DRINKING WATER GR-B 48 4 4.2 3.8 4.6 15F4 INDICATOR 0 (PCI/LITER) (34/36) (11/12) (12/12) PHILADELPHIA SUBURBAN WATER COMPANY

(< 2.3/8.3) (< 2.3/ 5.5) (2.9/7.7) 8.62 MILES SE OF SITE H-3 16 200 166 165 172 15F7 INDICATOR 0 (1/12) (0/4) (1/4) PHOENIXVILLE WATER WORKS

(<153/177) (<156/<172) (<163/177) 6.33 MILES SSE OF SITE

  • THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING BOTH THE MDAs AND THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

A-2

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2006 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER GAMMA 48 (PCI/LITER) MN-54 15 4 4 4 15F7 INDICATOR 0 (0/36) (0/12) (0/12) PHOENIXVILLE WATER WORKS

(<1/<11) (<1/<7) (<1/<10) 6.33 MILES SSE OF SITE CO-58 15 4 4 5 15F4 INDICATOR 0 (0/36) (0/12) (0/12) PHILADELPHIA SUBURBAN WATER COMPANY

(<1/<11) (<1/<7) (<1/<11) 8.62 MILES SE OF SITE FE-59 30 9 9 9 15F4 INDICATOR 0 (0/36) (0/12) (0/12) PHILADELPHIA SUBURBAN WATER COMPANY

(<2/<21) (<3/<16) (<21<21) 8.62 MILES SE OF SITE CO-60 15 4 4 4 15F4 INDICATOR 0 (0/36) (0/12) (0/12) PHILADELPHIA SUBURBAN WATER COMPANY

(<1/<11) (<1/<6) (<1/<11) 8.62 MILES SE OF SITE ZN-65 30 9 8 9 15F7 INDICATOR 0 (0/36) (0/12) (0/12) PHOENIXVILLE WATER WORKS

(<1/<24) (<2/< 15) (<1/c23) 6.33 MILES SSE OF SITE NB-95 15 5 4 5 15F4 INDICATOR 0 (0/36) (0/12) (0/12) PHILADELPHIA SUBURBAN WATER COMPANY

(<1/<12) (<1 /<7) (<1/<12) 8.62 MILES SE OF SITE ZR-95 30 8 7 8 15F7 INDICATOR 0 (0/36) (0/12) (0/12) PHOENIXVILLE WATER WORKS

(<2/<18) (<2/< 12) (<2/<16) 6.33 MILES SSE OF SITE 1-131 15 12 11 12 15F4 INDICATOR 0 (0/36) (0/12) (0/12) PHILADELPHIA SUBURBAN WATER COMPANY

(<4/<30) (<51<28) (<4/<25) 8.62 MILES SE OF SITE

  • THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING BOTH THE MDAs AND THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

A-3

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2006 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER CS-134 15 4 4 5 15F4 INDICATOR 0 (PCI/LITER) (0/36) (0/12) (0/12) PHILADELPHIA SUBURBAN WATER COMPANY

(<1/<12) (<1/<8) (<1/<12) 8.62 MILES SE OF SITE CS-1 37 18 4 4 4 15F4 INDICATOR 0 (0/36) (0/12) (0/12) PHILADELPHIA SUBURBAN WATER COMPANY

(<1/<11) (<1/<8) (<1/<11) 8.62 MILES SE OF SITE BA-1 40 60 26 25 27 15F4 INDICATOR 0 (0/36) (0/12) (0/12) PHILADELPHIA SUBURBAN WATER COMPANY

(<7/<49) (<10/<49) (<9/<44) 8.62 MILES SE OF SITE LA-1 40 15 8 8 9 15F7 INDICATOR 0 (0/36) (0/12) (0/12) PHOENIXVILLE WATER WORKS

(<2/< 15) (<3/< 15) (<2/<14) 6.33 MILES SSE OF SITE BOTTOM FEEDER (FISH) GAMMA 4 (PCI/KG WET) K-40 N/A 3045 2775 3045 16C5 INDICATOR 0 (2/2) (2/2) (2/2) VINCENT POOL (2820/3270) (2750/2800) (2820/3270) DOWNSTREAM OF DISCHARGE MN-54 130 47 59 59 29C1 CONTROL 0 (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<33/<61) (<40/<78) (<40/<78) UPSTREAM OF INTAKE CO-58 130 64 65 65 29C1 CONTROL 0 (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<44/<85) (<47/<84) (<47/<84) UPSTREAM OF INTAKE FE-59 260 155 143 155 16C5 INDICATOR 0 (0/2) (0/2) (0/2) VINCENT POOL

(<126/<184) (<89/<196) (<126/<184) DOWNSTREAM OF DISCHARGE

  • THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING BOTH THE MDAs AND THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

A-4

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2006 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS BOTTOM FEEDER (FISH) CO-60 130 49 66 66 29C1 CONTROL 0 (PCI/KG WET) (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<39/<58) (<47/<85) (<47/<85) UPSTREAM OF INTAKE ZN-65 260 131 138 138 29C1 CONTROL 0 (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<81/<180) (<108/<167) (<108/<167) UPSTREAM OF INTAKE 1-131 N/A 689 236 689 16C5 INDICATOR 0 (0/2) (0/2) (0/2) VINCENT POOL

(<401/<977) (<1 33/<339) (<401/<977) DOWNSTREAM OF DISCHARGE CS-134 100 56 69 69 29C1 CONTROL 0 (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<41/<71) (<40/<99) (<40/<99) UPSTREAM OF INTAKE CS-1 37 100 57 63 63 29C1 CONTROL 0 (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<43/<70) (<34/<91) (<34/<91) UPSTREAM OF INTAKE PREDATOR (FISH) GAMMA 4 (PCI/KG WET) K-40 N/A 3120 3000 3120 16C5 INDICATOR 0 (2/2) (2/2) (2/2) VINCENT POOL (2920/3320) (2860/3140) (2920/3320) DOWNSTREAM OF DISCHARGE MN-54 130 49 61 61 29C1 CONTROL 0 (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<35/<62) (<41/<81) (<41/<81) UPSTREAM OF INTAKE CO-58 130 66 68 68 29C1 CONTROL 0 (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<48/<84) (<52/<84) (<52/<84) UPSTREAM OF INTAKE

  • THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING BOTH THE MDAs AND THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

A-5

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2006 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS PREDATOR (FISH) FE-59 260 153 147 153 16C5 INDICATOR 0 (PCI/KG WET) (0/2) (0/2) (0/2) VINCENT POOL

(<128/<178) (<125/<168) (<128/<178) DOWNSTREAM OF DISCHARGE CO-60 130 58 61 61 29C1 CONTROL (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<33/<82) (<40/<82) (<40/<82) UPSTREAM OF INTAKE ZN-65 260 128 142 142 29C1 CONTROL (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<82/<173) (<99/<185) (<99/<185) UPSTREAM OF INTAKE 1-131 N/A 614 247 614 16C5 INDICATOR (0/2) (0/2) (0/2) VINCENT POOL

(<434/<794) (<142/<352) (<434/<794) DOWNSTREAM OF DISCHARGE CS-134 100 50 65 65 29C1 CONTROL (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<35/<65) (<40/<90) (<40/<90) UPSTREAM OF INTAKE CS-1 37 100 55 64 64 29C1 CONTROL (0/2) (0/2) (0/2) POTTSTOWN VICINITY

(<40/<69) (<50/<77) (<50/<77) UPSTREAM OF INTAKE SEDIMENT GAMMA 6 (PCI/KG DRY) BE-7 N/A 3368 1004 4050 16B2 INDICATOR (4/4) (1/2) (2/2) LINFIELD BRIDGE (1560/5380) (<968/1040) (2720/5380) 1.35 MILES SSE OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING BOTH THE MDAs AND THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

A-6

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2006 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT K-40 N/A 16650 14400 17300 16B2 INDICATOR 0 (PCI/KG DRY) (4/4) (2/2) (2/2) LINFIELD BRIDGE (13800/18900) (14300/14500) (15700/18900) 1.35 MILES SSE OF SITE MN-54 N/A 95 90 110 16C4 INDICATOR 0 (0/4) (0/2) (0/2) VINCENT DAM

(<64/< 128) (<74/<1 06) (<93/<128) 2.18 MILES SSE OF SITE CO-58 N/A 99 94 111 16C4 INDICATOR 0 (0/4) (0/2) (0/2) VINCENT DAM

(<65/< 125) (<78/<110) (<98/<125) 2.18 MILES SSE OF SITE CO-60 N/A 103 83 105 16C4 INDICATOR 0 (0/4) (0/2) (0/2) VINCENT DAM

(<61/<141) (<72/<93) (<102/<107) 2.18 MILES SSE OF SITE 1-131 N/A 442 389 491 16C4 INDICATOR 0 (0/4) (0/2) (0/2) VINCENT DAM

(<369/<508) (<249/<529) (<474/<508) 2.18 MILES SSE OF SITE CS-1 34 150 100 93 121 16C4 INDICATOR 0 (0/4) (0/2) (0/2) VINCENT DAM

(<65/<134) (<60/<127) (<1 07/<134) 2.18 MILES SSE OF SITE CS-137 180 213 99 282 16C4 INDICATOR 0 (3/4) (0/2) (2/2) VINCENT DAM

(<117/429) (<90/<109) (134/429) 2.18 MILES SSE OF SITE AIR PARTICULATE GR-B 260 10 16 17 17 22G1 CONTROL 0 (E-3 PCI/CU.METER) (199/208) (49/52) (49/52) MANOR SUBSTATION (6/31) (<7/<35) (<7/<35) 17.73 MILES SW OF SITE

  • THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING BOTH THE MDAs AND THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

A-7

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2006 .

Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE GAMMA 20 (E-3 PC]/CU.METER) BE-7 N/A 75 91 91 22G1 CONTROL 0 (13116) (3/4) (3/4) MANOR SUBSTATION (57/<98) (43/126) (43/126) 17.73 MILES SW OF SITE MN-54 N/A 3.3 4.1 4.1 22G1 CONTROL 0 (0/16) (0/4) (0/4) MANOR SUBSTATION

(< 1.4/< 6.3) (< 2.8/< 6.5) (< 2.8/< 6.5) 17.73 MILES SW OF SITE CO-58 N/A 5.0 5.3 5.5 11S1 INDICATOR 0 (0/16) (0/4) (0/4) LGS INFORMATION CENTER

(< 2.4/< 8.7) (< 3.3/< 8.6) (< 3.7/< 8.7) 0.38 MILES ESE OF SITE CO-60 N/A 3.1 3.0 3.6 13C1 INDICATOR 0 (0/16) (0/4) (0/4) KING ROAD

(< 1.5/< 5.2) (< 2.0/< 4.4) (< 2.3/< 5.2) 2.84 MILES SE OF SITE CS-1 34 10 3.1 3.5 3.5 22G1 CONTROL 0 (0/16) (0/4) (0/4) MANOR SUBSTATION

(< 1.5/< 5.6) (< 2.1/< 5.3) (< 2.1/< 5.3) 17.73 MILES SW OF SITE CS-1 37 10 3.0 2.5 3.4 14S1 INDICATOR 0 (0/16) (0/4) (0/4) LONGVIEW ROAD

(< 1.5/< 4.8) (< 1.8/< 3.0) (< 2.2/< 4.8) 0.63 MILES SSE OF SITE AIR IODINE GAMMA 260 (E-3 PCI/CU.METER) 1-131 70 41 37 43 14S1 INDICATOR 0 (0/208) (0/52) (0/52) LONGVIEW ROAD

(<14/<142) (<12/<208) (<16/<142) 0.63 MILES SSE OF SITE

  • THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING BOTH THE MDAs AND THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

A-8

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2006 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK 1-131 (LOW LVL) 118 1 0.7 0.6 0.9 25C1 INDICATOR 0 (PCI/LITER) (0/92) (0/26) (0/22)

(< 0.2/< 7.4) (< 0.3/< 1.8) (< 0.3/< 7.4) 2.69 MILES WSW OF SITE GAMMA 118 K-40 N/A 1301 1272 1329 19B1 INDICATOR 0 (92/92) (22/22)

(26/26)

(1050/1450) (1150/1410) (1200/1450) 1.95 MILES SSW OF SITE CS-134 15 7 7 9 25E1 INDICATOR 0 (0/92) (0/26) (0/4)

(<2/<1 5) (<3/< 12) (<5/<11) 4.27 MILES WSW OF SITE CS-1 37 18 7 7 9 25E1 INDICATOR 0 (0/92) (0/26) (0/4)

(<2/<14) (<3/<11) (<5/<12) 4.27 MILES WSW OF SITE BA- 140 60 39 39 41 25E1 INDICATOR 0 (0/92) (0/26) (0/4)

(< 15/<56) (<13/<55) (<36/<51) 4.27 MILES WSW OF SITE LA-140 15 12 12 12 10F4 INDICATOR 0 (0/92) (0/26) (0/22)

(<41<15) (<4/<15) (<9/<15) 6.60 MILES ESE OF SITE BROAD LEAF VEGETATION GAMMA 35 (PCI/KG WET) BE-7 N/A 198 723 723 31G1 CONTROL 0 (16/23) (11/12) (11/12)

(<35/559) (<23/2180) (<23/2180)

  • THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING BOTH THE MDAs AND THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

A-9

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2006 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS BROAD LEAF VEGETATION K-40 N/A 4345 4354 4824 11 S3 INDICATOR 0 (PCI/KG WET) (23/23) (11/12) (12/12) LGS INFORMATION CENTER (1630/8430) (<177/6610) (2150/8430) 0.35 MILES ESE OF SITE MN-54 N/A 7 7 8 13S3 INDICATOR (0/23) (0/12) (0/11) VINCENT DAM

(<3/<1 8) (<2/< 14) (<3/<18) 0.24 MILES SE OF SITE CO-58 N/A 8 8 8 13S3 INDICATOR 0 (0/23) (0/12) (0/11) VINCENT DAM

(<3/<19) (<3/<15) (<4/<19) 0.24 MILES SE OF SITE CO-60 N/A 7 7 8 13S3 INDICATOR 0 (0/23) (0/12) (0/11) VINCENT DAM

(<3/<18) (<2/<15) (<3/< 18) 0.24 MILES SE OF SITE 1-131 60 33 32 36 13S3 INDICATOR 0 (0/23) (0/12) (0/11) VINCENT DAM

(< 15/<57) (< 14/<59) (<17/<57) 0.24 MILES SE OF SITE CS-1 34 60 7 7 8 13S3 INDICATOR 0 (0/23) (0/12) (0/11) VINCENT DAM

(<3/<20) (<2/<15) (<3/<20) 0.24 MILES SE OF SITE CS-1 37 80 7 7 8 13S3 INDICATOR 0 (0/23) (0/12) (0/11) VINCENT DAM

(<3/<19) (<2/<14) (<3/< 19) 0.24 MILES SE OF SITE DIRECT RADIATION TLD-QUARTERLY 159 N/A 8 9 9 13S2 INDICATOR 0 (MILLI-ROENTGEN/STD.MO.) (155/155) (4/4) (4/4) 500 KV SUBSTATION (6/13) (9/10) (11/13) 0.41 MILES SE OF SITE

  • THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING BOTH THE MDAs AND THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

A-10

APPENDIX B LOCATION DESIGNATION, DISTANCE &

DIRECTION, AND SAMPLE COLLECTION &

ANALYTICAL METHODS

TABLE B-I: Location Designation and Identification System for the Limerick Generating Station XXYZ- General code for identification of locations, where:

xx - Angular Sector of Sampling Location. The compass is divided into 36 sectors of 10 degrees each with center at Limerick's Units 1 and 2 off-gas vents. Sector 36 is centered due North, and others are numbered in a clockwise direction.

Y - Radial Zone of Sampling Location (in this report, the radial distance from the Limerick vent for all regional stations).

S: on-site location E  : 4-5 miles off-site A : 0-1 mile off-site F  : 5-10 miles off-site B : 1-2 miles off-site G  : 10-20 miles off-site C : 2-3 miles off-site H  : 20-100 miles off-site D : 3-4 miles off-site z - Station's Numerical Designation within sector and zone, using 1, 2, 3... in each sector and zone.

B-1

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2006 Location Location Description Distance & Direction From Site A Surface Water 113B1 Vincent Dam (indicator) 1.75 miles SE 24S1 Limerick Intake (control) 0.20 miles SW R Drinkina (Potable) Water 15F4 Philadelphia Suburban Water Company (indicator) 8.62 miles SE 15F7 Phoenixville Water Works (indicator) 6.33 miles SSE 16C2 Citizens Home Water Company (indicator) 2.66 miles SSE 28F3 Pottstown Water Authority (control) 5.84 miles WNW C Milk - hi-weekly / monthly 10F4 6.60 miles ESE 18E1 4.21 miles S 19B1 1.95 miles SSW 23F1 Control 5.02 miles SW 25C1 2.69 miles WSW D Milk - quarterly 25E1 4.27 miles WSW 36E1 Control 4.70 miles N F Air Particulates / Air Iodine 10S3 Keen Road 0.50 miles E 11S1 LGS Information Center 0.38 miles ESE 11S2 LGS Information Center 0.38 miles ESE 13C1 King Road 2.84 miles SE 14S1 Longview Road 0.63 miles SSE 22G1 Manor Substation (control) 17.73 miles SW F Fish 16C5 Vincent Pool (indicator) Downstream of Discharge 29C1 Pottstown Vicinity (control) Upstream of Intake G.Sediment 16B2 Linfield Bridge (indicator) 1.35 miles SSE 16C4 Vincent Dam (indicator) 2.18 miles SSE 33A2 Upstream of Intake (control) 0.84 miles NNW H Broad Leaf Vegetation 11S3 LGS Information Center 0.35 miles ESE 13S3 LGS 500 KV Yard 0.24 miles SE 31G1 Prout's Jollyview Farm 13.6 miles NW B-2

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2006 Location Location Description Distance & Direction From Site H Environmental flosimetry - TILD Site Boundary 36S2 Evergreen & Sanatoga Road 0.60 miles N 3S1 Sanatoga Road 0.44 miles NNE 5S1 Possum Hollow Road 0.45 miles NE 7S1 LGS Training Center 0.59 miles ENE 10S3 Keen Road 0.50 miles E 11S1 LGS Information Center 0.38 miles ESE 13S2 500 KV Substation 0.41 miles SE 14S1 Longview Road 0.63 miles SSE 18S2 Rail Line along Longview Road 0.26 miles S 21S2 Near Intake Building 0.19 miles SSW 23S2 Transmission Tower 0.53 miles SW 25S2 Sector Site Boundary 0.46 miles WSW 26S3 Met. Tower #2 0.40 miles W 29S1 Sector Site Boundary 0.55 miles WNW 31S1 Sector Site Boundary 0.26 miles NW 34S2 Met. Tower #1 0.58 miles NNW Intermediate Distance 36D1 Siren Tower No. 147 3.51 miles N 2E1 Laughing Waters GSC 4.76 miles NNE 4E1 Neiffer Road 4.78 miles NE 7E1 Pheasant Road 4.26 miles ENE 10E1 Royersford Road 3.94 miles E 10F3 Trappe Substation 5.58 miles ESE 13E1 Vaughn Substation 4.31 miles SE 16F1 Pikeland Substation 5.04 miles SSE 19D1 Snowden Substation 3.49 miles S 20F1 Sheeder Substation 5.24 miles SSW 24D1 Porters Mill Substation 3.97 miles SW 25D1 Hoffecker & Keim Streets 3.99 miles WSW 28D2 W. Cedarville Road 3.83 miles W 29E1 Prince Street 4.95 miles WNW 31D2 Poplar Substation 3.87 miles NW 34E1 Varnell Road 4.59 miles NNW Control and Special Interest 5H1 Birch Substation (control) 24.76 miles NE 6C1 Pottstown Landing Field 2.14 miles NE 9C1 Reed Road 2.15 miles E 13C1 King Road 2.84 miles SE 15D1 Spring City Substation 3.20 miles SE 17B1 Linfield Substation 1.60 miles S 20D1 Ellis Woods Road 3.06 miles SSW 31D1 Lincoln Substation 300 miles WNW B-3

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2006 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Water Gamma Spectroscopy Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis a continuous water radiological analysis (Limerick Generating Station) compositor. Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Surface Water Tritium Quarterly composite from RMC-ER5 Collection of water samples for 500 ml TBE, TBE-2011 Tritium analysis in drinking water by liquid a continuous water radiological analysis (Limerick Generating Station) scintillation compositor.

Env. Inc., T-02 Determination of tritium in water (direct method)

Drinking Water Gross Beta Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2008 Gross Alpha and/or gross beta activity in a continuous water radiological analysis (Limerick Generating Station) various matrices compositor.

Env. Inc., W(DS)-01 Determination of gross alpha and/or gross beta in water (dissolved solids or total residue)

Env. Inc., W(SS)-02 Determination of gross alpha and/or gross beta in water (suspended solids)

Drinking Water Gamma Spectroscopy Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis a continuous water radiological analysis (Limerick Generating Station) compositor. Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Drinking Water Tritium Quarterly composite from RMC-ER5 Collection of water samples for 500 ml TBE, TBE-2011 Tritium analysis in drinking water by liquid a continuous water radiological analysis (Limerick Generating Station) scintillation compositor.

Env. Inc., T-02 Determination of tritium in water (direct method)

Fish Gamma Spectroscopy Semi-annual samples RMC-ER6 Collection of fish samples for 1000 grams (wet) TBE-2007 Gamma emitting radioisotope analysis collected via radiological analysis (Limerick Generating Station) electroshocking or other Env. Inc., GS-01 Determination of gamma emitters by gamma techniques spectroscopy Sediment Gamma Spectroscopy Semi-annual grab RMC-ER7 Collection of sediment samples for 500 grams (dry) TBE, TBE-2007 Gamma emitting radioisotope analysis samples radiological analysis (Limerick Generating Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Particulates Gross Beta One-week composite of RMC-ER8 Collection of air particulate and air 1 filter (approximately TBE, TBE-2008 Gross Alpha and/or gross beta activity in continuous air sampling iodine samples for radiological analysis (Limerick 280 cubic meters various matrices through glass fiber filter Generating Station) weekly) paper Env. Inc., AP-02 Determination of gross alpha and/or gross beta in air particulate filters B-4

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2006 Sample Analysis Sampling Method, Collection Procedure Number Sample Size Analytical Procedure Number Medium Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis each station (approximately 3600 Env. Inc., AP-03 Procedure for compositing air cubic meters) Env. Inc., GS-01 Determination of gamma emitters by gamma particulate filters for gamma spectroscopic spectroscopy analysis Air Iodine Gamma Spectroscopy One-week composite of RMC-ER8 Collection of air particulate and air 1 filter (approximately TBE, TBE-2007 Gamma emitting radioisotope analysis continuous air sampling iodine samples for radiological analysis (Limerick 280 cubic meters through charcoal filter Generating Station) weekly) Env. Inc., 1-131-02 Determination of 1-131 in charcoal canisters by gamma spectroscopy (batch method)

Milk 1-131 Bi-weekly grab sample RMC-ER10 Collection of milk samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices when cows are on radiological analysis (Limerick Generating Station) pasture. Monthly all Env. Inc., 1-131-01 Determination of 1-131 in milk by anion other times exchange Milk Gamma Spectroscopy Bi-weekly grab sample RMC-ERI 0 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis when cows are on radiological analysis (Limerick Generating Station) pasture. Monthly all Env. Inc., GS-01 Determination of gamma emitters by gamma other times spectroscopy TLD Thermoluminescence Quarterly TLDs RMC-ER9 Collection of TLD samples for 2 dosimeters Global Dosimetry Dosimetry comprised of two radiological analysis (Limerick Generating Station)

Panasonic 814 (containing 3 each CaSO4 elements)

B-5

I

-nvironmental Sampling Locations witnin Une Mile of the Limerick Generating Station, 2006 B-6

LENE

  • I'**QQ#V

.0 Figure B-2 Environmental Sampling Locations Between One and Five Miles from the Limerick Generating Station, 2006 B-7

t-igure Iu-6 Environmental Sampling Locations Greater than Five Miles from the Limerick Generating Station, 2006 B-8

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

TABLE C-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION 13B1 24S1 PERIOD JAN-MAR < 174 < 173 APR-JUN < 166 < 167 JUL-SEP < 168 < 170 OCT-DEC < 156 < 154 MEAN 166 +/- 15 166 +/- 17 c-1

TABLE C-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-i 37 Ba-140 La-140 PERIOD 13B1 JAN <5 <5 <11 <6 < 12 <6 <10 < 11 <6 <6

  • 26 <10 FEB <6 <5 <11 <6 < 14 <6 <9 <8 <6 <6 < 24 < 10 MAR <6 <6 <14 <5 < 14 <6 < 10 < 12 <6 <6 < 31 < 12 APR <6 <6 <12 <6 <13 <6 < 10 <11 <6 <6 < 31 < 10 MAY <3 <3 <7 <3 <7 <4 <6 <19 <3 <3 < 32 <11 JUN <8 <7 < 17 <7 <17 <8 <14 <9 <8 <8 < 28 <10 JUL <2 <3 <6 <2 <5 <3 <5 < 14 <2 <2 < 24 <8 AUG <1 <2 <4 <1 <3 <2 <3 < 14 <1 <1 < 19 <6 SEP <1 <1 <2 <1 <1 <1 <1 <4 <1 <1 <7 <2 OCT <2 <2 <4 <2 <4 <2 <4 <6 <2 <2 <14 <5 NOV <4 <4 <8 <3 <7 <5 <7 <15 <4 <4 < 34 <9 DEC <3 <3 <7 <4 <8 <4 <6 <8 <4 < 4 < 19 <6 MEAN 4 +/- 4 4+/- 4 9 +/- 9 4 +/- 4 9 +/- 10 4 +/- 4 7 +/- 7 11 +/- 8 4 +/- 5 . 4 +/- 5 24 +/- 16 8 +/- 6 STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-1 37 Ba-140 La-140 PERIOD 24S1 JAN <8 <9 < 15 <8
  • 22 <7 <14 <15 < 10 <8 < 43 < 12 FEB <5 <5 <9 <5 <15 <5 <10 <8 <6 <6 < 25 <7 MAR <2 <2 <5 <2 <5 <2 <4 <5 <3 <2 <13 <5 APR <5 <4 <10 <5 <10 <4 <7 <9 <4 <5 < 23 <9 MAY <3 <3 <7 <3 <6 <3 <6 <17 <3 <3 < 30 <11 JUN <8 <8 <14 <9 <17 <8 < 14 <10 <8 <8 < 30 < 10 JUL <2 <2 <5 <3 <4 <3 <4 < 13 <2 < 2
  • 24 <7 AUG <2 <2 <6 <2 <4 <3 <4 < 15 <2 <2
  • 25 <8 SEP <3 <4 <7 <3 <6 <4 <7 < 13 <3 <4
  • 26 < 11 OCT <2 <2 <4 <2 <4 <2 <3 <7 <2 <2 <14 <5 NOV <3 <4 <9 <5 <8 <5 <8 < 14 <4 <4
  • 31 <9 DEC <4 <4 <11 <4 <7 <4 <8 <7 <4 <4
  • 21 < 7 MEAN 4 +/- 4 4 +/- 5 9 +/- 7 4 +/- 5 9 +/- 11 4 +/- 4 7 +/- 7 11 +/- 8 4 +/- 5 4 +/- 4 25 +/- 16 8 +/- 5 C-2

TABLE C-I1.1 CONCENTRATIONS OF TOTAL GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 15F4 15F7 16C2 28F3 PERIOD JAN 3.8 +/- 1.7 < 2.3 < 2.4 < 2.3 FEB 2.9 + 1.4 2.9 + 1.4 8.3 + 1.8 3.7 _+ 1.5 MAR 3.5 1.7 3.5 +/- 1.8 3.0 +/- 1.7 3.0 +/- 1.8

+

APR 4.6 1.7 3.2 1.6 3.8 +/- 1.7 3.1 +/- 1.6 MAY 4.2 +/- 1.6 5.7 +/- 1.7 4.9 + 1.6 4.3 +/- 1.6 JUN 4.7 +/- 1.7 4.4 +/- 1.7 4.7 + 1.7 4.9 1.8 JUL 4.9 +/- 1.8 4.7 +/- 1.8 3.5 +/- 1.7 2.7 +/- 1.7 AUG 7.7 1.9 5.1 +/- 1.8 4.2 + 1.7 4.4 _+

1.7 SEP 4.5 +/- 1.6 3.7 +/- 1.6 3.4 +/- 1.6 5.5 +/- 1.8

_+ +/- 1.5 OCT 4.8 1.6 2.8 +/- 1.4 2.8 +/- 1.4 3.7 NOV 3.9 1.4 3.1 +/- 1.3 5.4 +/- 1.6 3.7 _+ 1.4 DEC 5.6 +/- 2.5 5.6 2.5 3.9 2.4 4.9 +

2.4 MEAN 4.6 +/- 2.4 3.9 +/- 2.3 4.2 +/- 3.1 3.8 +/- 1.9 TABLE C-II.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 15F4 15F7 16C2 28F3 PERIOD JAN-MAR 172 < 172 < 172 < 172 APR-JUN 172 < 174 < 174 < 163 JUL-SEP 155 < 163 < 157 < 170 OCT-DEC 153 177 +/- 108 < 156 < 156 MEAN 163 + 21 172 +/- 12 165 +/- 19 165 +/- 15 C-3

TABLE C-II.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-1 37 Ba-140 La-140 PERIOD 15F4 JAN 5 <5 <11 <5 <11 <5 <9 <10 5 <5 25 <9 FEB 8 <7 <15 <7 <15 <7 <12 <12 8 <7 35 <9 MAR 5 <6 <11 <8 <13 <6 <10 <11 6 <6 31 <9 APR 6 <7 <12 <7 <14 <7 <12 <13 7 <7 34 <12 MAY 4 <4 <10 <4 <8 <5 <7 <4 4 <4 44 <15 JUN 11 <11

  • 21 <11 < 24 <12 <18 <15 12 11 43 <14 JUL 2 <2 <5 <2 <5 <3 <4 *14 2 <2 22 <8 AUG <1 <3 <1 <2 <1 <2 <13 1 <1 17 <6 SEP <1 <2 <1 <2 <1 <2 <4 1 <1 9 <3 OCT <1 <3 <1 <3 <1 <2 <5 1 <1 10 <3 NOV 3 <4 <10 <5 <9 <4 <7 <15 4 <4 32 <10 DEC 4 <4 <6 <2 <7 <4 <7 <9 4 <4 22 <7 MEAN 4 +/- 6 5 +/- 6 9 +/-+11 4 +/- 6 9 +/- 13 5 +/- 6 8 +/- # 10 +/- 8 5 +/- 7 4 +/-6 27 +/- 23 9 +/- 8 15F7 JAN 6 <6 *12 <7 *14 <6 <11 *12 7 <5 31
  • 10 FEB 8 <8 *16 <7 <18 <8 <14 <12 9 <8 38 <14 MAR 6 <6 *12 <5 <12 <5 <9 *10 5 <5 29 <11 APR 5 <5 *12 <6 <12 <5 <10 <12 6 <5 30 <9 MAY 3 <3 <8 <3 <6 <4 <6 <6 3 <3 35 <11 JUN 10 <10 < 20 <9 < 23 <11 <16 *13 11 <10 44 <12 JUL 2 <2 <4 <2 <4 <2 <4 *13 2 <2 24 <8 AUG 1 <2 <3 <1 <1

<3 <2 <3 *13 18 <6 SEP 1 <1 <2 <1 <1 <1 <1

<2 <4 7 <2 OCT 1 <2 <3 <1 <3 <2 <3 <6 <2 12 <4 NOV 4 <4 <8 <3 <8 <4 <9 <14 4 <4 28 < 10 DEC 4 <4 <8 <4 <10 <5 <8 <9 4 <4 25 <9 MEAN 4 +/- 6 5 +/- 6 9 +/- 11 4 +/- 5 9 +/-13 5 +/- 6 8 +/- 9 10 +/- 7 4 +/- 6 4 +/- 5 27 +/- 21 9 +/- 7 C-4

TABLE C-11.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER-SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD 16C2 JAN <6 <6 < 11 <7 < 13 <6 < 10 < 10 <6 <6 < 28 <9 FEB <6 <7 < 12 <7 < 16 <7 < 11 < 10 <8 <7 < 30 < 12 MAR <3 <3 <5 <3 <6 <3 <5 < 6 <3 <3 < 15 <5 APR <5 <5 < 10 <5 <11 <5 <9 < 10 <5 <5 < 24 <9 MAY <4 <5 < 11 <4 < 10 <9 <5

<5 <5 <5 <49 < 15 JUN <9 <7 < 18 <7 < 19 <8 < 14 <9 <9 <8 < 31 < 10 JUL <2 <2 <4 <2 <3 <2 <3 < 10 <2 <2 < 17 <5 AUG <1 <1 <4 <1 <3 <1 <3 < 12 <1 <1 < 19 <7 SEP <1 <1 <3 <1 <1 < 5

<2 <2 <1 <1 < 10 <3 OCT <2 <2 <5 <3 <4 <2 <4 <8 <2 <2 < 15 <4 NOV <4 <4 <9 <4 <8 <5 <8 < 15 <4 <4 < 30 <9 DEC <5 <4 <9 <4 < 10 <5 <8 <7 <4 <4 < 20 <7 MEAN 4+/-5 4+/-4 8+/-9 4_+/-4 9_+/-11 4_+/-5 7_+/-7 9_+/-6 4+/-5 4_+/-5 24_+/-21 8_+/-7 28F3 JAN <5 <6 < 13 <6 < 13 7 < 11 <11 <6 <7 31 < 10 FEB <7 <7 < 16 <6 < 15 7 < 12 <11 < 8 <8 33 < 10 MAR <2 <3 <5 < 2 <5 3 <5 <6 <3 <3 14 <5 APR <5 <5 <11 <6 < 12 6 < 10 < 11 <6 <5 29 < 11 MAY <4 <5 <11 <5 <9 5 <8 <4 <4 <4 49 < 15 JUN <6 <6 < 12 <"6 < 15 7 < 11 <8 <6 <8 23 <8 JUL <2 <2 <5 <2 <4 2 <4 < 13 <2 <2 21 <6 AUG <1 <2 <4 <5 <3 2 <3 < 14 <1 <2 21 <6 SEP <1 <1 <3 <1 <2 1 <5 <1

<2 <1 10 <3 OCT <2 <2 <4 <"2 <4 2 <3 <7 <2 <2 14 <4 NOV <4 <4 <9 <4 <6 4 < 6 < 15 <4 < 4 29 <8 DEC <4 <5 <11 <5 <:7 4 <7 <8 <4 <4 21 <6 MEAN 4+/-4 4_+/-4 9-+/-8 4_+/-4 8+/-10 4+/-4 7+/-7 9_+/-7 4_+/-5 4+/-5 25 +/- 21 8 + 7 C-5

TABLE C-111.1 CONCENTRATIONS OF GAMMA EMITTERS IN PREDATOR AND BOTTOM FEEDER (FISH)

SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Cs-i 34 Cs-1 37 PERIOD 16C5 PREDATOR 05/17/06 2920 +/- 783 < 62 < 84 < 178 < 82 < 173 < 794 < 65 < 69 11/14/06 3320 +/- 698 < 35 <48 < 128 < 33 < 82 < 434 < 35 <40 MEAN 3120 +/- 566 49 +/- 38 66 +/- 51 153 +/- 71 58 +/- 69 128 +/- 128 614 +/- 509 50 +/- 42 55 +/- 40 BOTTOM FEEDER 05/17/06 2820 +/- 723 < 61 < 85 < 184 < 58 < 180 < 977 < 71 < 70 11/14/06 3270 +/- 705 < 33 < 44 < 126 < 39 < 81 < 401 < 41 <43 MEAN 3045 +/- 636 47 +/- 39 64 +/- 58 155 +/- 82 49 +/- 27 131 +/- 140 689 +/- 815 56 +/- 43 57 +/- 38 29C1 PREDATOR 05/10/06 2860 +/- 1050 < 81 < 84 < 168 < 82 < 185 < 142 < 90 < 77 11/16/06 3140 +/- 754 < 41 < 52 < 125 <40 < 99 < 352 < 40 < 50 MEAN 3000 +/- 396 61 +/- 57 68 +/- 46 147 +/- 61 61 +/- 59 142 +/- 122 247 +/- 297 65 +/- 71 64 +/- 39 BOTTOM FEEDER 05/10/06 2750 +/- 912 < 78 < 84 < 196 < 85 < 167 < 133 < 99 < 91 11/16/06 2800 +/- 719 < 40 < 47 < 89 < 47 < 108 < 339 <40 < 34 MEAN 2775 +/- 71 59 +/- 54 65 +/- 53 143 +/- 151 66 +/- 54 138 +/- 83 236 +/- 291 69 +/- 83 63 +/- 80 C-6

TABLE C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA STC COLLECTION Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-1 37 PERIOD 1 6B2 06/09/06 5380 +/- 563 18900 +/- 933 < 64 < 65 < 61 < 369 < 65 172 +/- 42 10/31/06 2720 +/- 1050 15700 +/- 1850 < 97

  • 108 < 141
  • 415 < 93 < 117 MEAN 4050 +/- 3762 17300 +/- 4525 80 +/- 48 87 +/- 61 101 +/- 114 392 +/- 65 79 +/- 40 145 +/- 78 16C4 06/09/06 1560 +/- 785 13800 +/- 1390 < 93
  • 98
  • 102 < 474
  • 134 429 +/- 104 10/31/06 3810 +/- 1050 18200 +/- 2510 < 128 < 125 < 107 < 508 < 107 134 +/- 114 MEAN 2685 +/- 3182 16000 +/- 6223 110 +/- 50 111 +/- 39 105 +/- 7 491 +/- 48 121 +/- 38 282 +/- 417 33A2 06/09/06 < 968 14500 +/- 1530
  • 106
  • 110 < 93 < 529
  • 127
  • 109 10/31/06 1040 +/- 550 14300 +/- 1450 < 74 < 78 < 72 < 249 < 60
  • 90 MEAN 1004 +/- 102 14400 +/- 283 90 +/- 45 94 +/- 45 83 +/- 29 389 +/- 396 93 +/- 95 99 +/- 27 C-7

TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I GROUP II GROUP Ill WEEK 10S3 liSi 14S1 13C1 22G1 1 5 lb +/- b 2 16 +/- 5 17 +/-5 16 +/- 5 14+/- 5 16 +/- 5 3 12 +/- 5 9+/-5 16 +/- 5 13 +/- 5 10 +/- 5 4 11 +/- 6 12 +/- 6 19 +/- 6 18 +/- 6 16 +/- 6 5 18 +/- 5 19+/- 5 23 +/- 5 22 +/-5 24 +/- 9 6 14 +/- 5 16 +/- 5 14 +/- 5 11 +/- 5 16 +/- 5 7 19 +/- 5 22 +/-5 20 +/- 5 18 +/- 5 19 +/- 5 8 25 +/- 6 20 +/-6 19 +/- 6 23 +/-6 22 +/- 6 9 12 +/- 5 16 +/- 5 13 +/- 5 15+/- 5 18 +/- 5 10 16 +/- 5 13 +/- 5 16 +/- 5 16 5 13 +/- 5 11 .18 +/- 5 12 +/- 5 16 +/- 5 16+/- 5 14 +/- 5 12 11 +/- 4 11 +/- 4 6+/-4 9+/-4 9+/-4 13 20 +/- 6 20 +/-5 23 +/-5 18+/- 5 17+/- 5 14 9+/- 5 14 +/- 5 13+/- 5 11 +/- 5 10+/- 5 15 22+/- 6 19+/- 5 16+/- 5 14 +/- 5 15+/- 5 16 7+/- 5 <7 <7 7+/-4 <7 17 <8 11 +/- 55q. <7 8+/-5 9+/-5 18 16 +/-4 9+/-4 5 13+/- 4 12+/- 4 13+/- 4 19 11 +/-5 9+/-5 <7 <7 <7 20 <7 <6 7 9 21 18 17 12 15 22 15 18 12 31 23 8 9 8 8 24 16 13 10 12 25 19 21 9 15 26 18 16 14 16 27 17 19 19 21 28 22 24 16 22 29 16 24 22 < 35 (1) 30 20 24 23 26 31 26 31 23 27 32 15 16 17 13 33 21 25 19 20 34 25 19 24 23 35 8 9 7 8 36 20 22 21 22 37 12 10 15 16 38 15 16 18 17 39 17 17 16 15 40 12 15 (1) 18 18 41 20 20 19 18 42 16 18 14 16 43 11 9 11 17 44 25 25 27 23 45 16 22 18 24 46 8 <7 9 11 47 25 22 23 21 48 21 26 24 25 49 26 24 24 22 50 25 28 25 22 51 15 15 13 16 52 16 19 13 16 MEAN 16 +/- 11 17 +/- 12 17 +/- 11 16 +/- 11 17 +/- 12 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-8

TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS (E-3 PCI/CU METER) IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 GROUP I - ON-SITE LOCATIONS GROUP II- INTERMEDIATE DISTANCE GROUP III- CONTROL LOCATIONS LOCATIONS COLLECTION MIN. MAX. MEAN+/- COLLECTION MIN. MAX. MEAN +/- COLLECTION MIN. MAX. MEAN+/-

PERIOD 2SD PERIOD 2SD PERIOD 2SD 1/3/2006 - 1/30/2006 9 19 13 +7 1/3/2006 1/30/2006 9 18 13 +/- 7 1/3/2006 - 1/30/2006 10 16 14 +/- 5 1/30/2006 - 2/27/2006 14 25 19 +7 1/30/2006 2/27/2006 11 23 18 +/- 11 1/30/2006 - 2/27/2006 16 24 20 +/- 7 2/27/2006 - 4/3/2006 6 23 15 +/-8 2/27/2006 4/3/2006 9 18 15 +/- 7 2/27/2006 - 4/3/2006 9 18 14 +/- 7 4/3/2006 - 5/1/2006 <7 22 12 +10 4/3/2006 5/1/2006 7 14 10 +/- 7 4/3/2006 - 5/1/2006 7 15 10 +/- 7 5/1/2006 - 5/30/2006 <6 18 11 +9 5/1/2006 5/30/2006 <7 12 10 +/- 5 5/1/2006 - 5/30/2006 7 15 11+/- 7 5/30/2006 - 7/3/2006 7 21 15 +/-8 5/30/2006 7/3/2006 8 14 10 5 5/30/2006 - 7/3/2006 8 31 16 +/- 17 7/3/2006 - 7/31/2006 16 27 21 +/-6 7/3/2006 7/31/2006 16 23 20 6 7/3/2006 - 7/31/2006 21 35 26 +/- 13 7/31/2006 - 8/28/2006 15 31 22 +10 7/31/2006 8/28/2006 17 24 21 7 7/31/2006 - 8/28/2006 13 27 21 +/- 12 8/28/2006 - 10/2/2006 6 22 15 -+10 8/28/2006 10/2/2006 7 21 15 10 8/28/2006 - 10/2/2006 8 22 16 +/- 10 10/2/2006 - 10/30/2006 9 29 16 +11 10/2/2006 10/30/2006 11 19 16 7 10/2/2006 - 10/30/2006 16 18 17 +/- 2 10/30/2006 - 11/27/2006 < 7 25 18 -+13 10/30/2006 11/27/2006 9 27 19 15 10/30/2006 - 11/27/2006 11 24 20 +/- 12 11/27/2006 - 1/2/2007 13 28 21 +10 11/27/2006 1/2/2007 13 25 20 13 11/2712006 - 1/2/2007 16 25 20 +/- 8 1/3/2006 - 1/2/2007 <6 31 17 +/- 7 12/28/2004 - 1/3/2006 < 7 27 16 +/- 8 12/28/2004 - 1/3/2006 < 7 35 17 +/- 9 c-9

TABLE C-V.3 CONCENTRATION OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 PERIOD 10S3 01/03 - 04/03/06 < 83 < 4.9 < 8.0 < 4.4 < 2.7 < 4.1 04/03 - 07/03/06 61 +/- 27 < 3.7 < 4.4 < 5.0 < 3.1 < 3.3 07/03 - 10/02/06 77 +/- 28 < 1.8 < 3.1 < 1.6 < 1.5 < 1.5 10/02 - 01/02/07 64 +/- 16 < 2.1 < 2.4 < 2.1 < 2.2 < 2.2 MEAN 72 +/- 21 3.1 +/- 2.8 4.5 + 5.0 3.3 + 3.4 2.4 _ 1.4 2.8 + 2.3 11S1 01/03 - 04/03/06 < 98 < 6.3 < 8.7 < 2.8 < 5.0 < 3.5 04/03 - 07/03/06 65 +/- 30 < 2.5 < 4.7 < 3.2 < 2.7 < 2.9 07/03 - 10/02/06 64 +/- 39 < 2.6 < 4.8 < 1.7 < 2.3 < 2.5 10/02 - 01/02/07 71 +/- 22 < 3.4 < 3.7 < 3.5 < 2.8 < 3.2 MEAN 74 +/- 32 3.7 + 3.5 5.5 + 4.5 2.8 + 1.5 3.2 +/- 2.4 3.1 + 0.9 13C1 01/03 - 04/03/06 64 +/- 46 < 2.9 < 6.0 < 3.6 < 4.3 < 2.9 04/03 - 07/03/06 89 +/- 42 < 4.0 < 5.1 < 5.2 < 4.4 < 3.4 07/03 - 10/02/06 84 +/- 37 < 1.4 < 4.6 < 3.3 < 2.0 < 1.7 10/02 - 01/02/07 81 +/- 24 < 3.0 < 3.4 < 2.3 < 3.0 < 3.3 MEAN 80 +/- 22 2.8 +/- 2.1 4.8 2.2 3.6 +/- 2.4 3.4 2.2 2.8 +/- 1.5 14S1 01/03 - 04/03/06 < 76 < 5.5 < 5.7 < 4.2 < 5.6 < 4.8 04/03 - 07/03/06 81 +/- 41 < 4.3 < 7.3 < 3.5 < 3.5 < 3.4 07/03 - 10/02/06 57 +/- 47 < 2.2 < 3.8 < 2.4 < 2.2 < 2.2 10/02 - 01/02/07 82 +/- 30 < 2.5 < 3.8 < 1.5 < 2.8 < 3.0 MEAN 74 +/- 24 3.6 +/- 3.2 5.1 +/- 3.4 2.9 +/- 2.3 3.5 +/- 3.0 3.4 +/- 2.2 22G1 01/03 - 04/03/06 < 102 < 6.5 < 8.6 < 4.4 < 5.3 < 3.0 04/03 - 07/03/06 93 +/- 34 < 3.4 < 5.9 < 2.6 < 3.7 < 2.7 07/03 - 10/02/06 126 +/- 39 < 2.8 < 3.5 < 2.0 < 2.1 < 1.8 10/02 - 01/02/07 43 +/- 26 < 3.6 < 3.3 < 3.1 < 3.0 < 2.6 MEAN 91 +/- 70 4.1 +/- 3.4 5.3 + 4.9 3.0 +/- 2.0 3.5 +/- 2.7 2.5 1.0 C-10

TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA GROUP I GROUP II GROUP III WEEK 10S3 11$1 14S1 13C1 22G1 1 < J* < it( <i < it < 24 2 < 28 < 27 < 27 < 27 < 15 3 < 32 < 31 < 31 < 30 < 15 4 <44 <42 < 42 < 42 < 28 5 <27 < 26 < 25 < 25 < 30 6 < 37 < 35 < 35 < 35 < 19 7 < 34 < 32 < 32 < 32 < 18 8 < 43 < 42 < 41 < 41 < 27 9 < 37 < 35 < 35 < 35 < 19 10 < 29 < 28 < 28 < 28 < 15 11 < 26 < 25 < 25 < 25 < 16 12 < 34 < 32 < 32 < 32 <21 13 < 41 < 39 < 39 < 39 < 26 14 <27 <26 < 26 <25 < 17 15 < 41 < 39 < 39 < 38 < 21 16 < 31 < 30 < 30 < 22 < 30 17 < 41 < 39 < 38 < 39 < 25 18 < 56 < 54 < 53 < 53 < 30 19 < 62 < 38 <68 < 68 < 68 20 < 52 < 50 < 49 < 49 < 25 21 < 69 < 66 < 66 < 65 < 43 22 < 33 < 32 < 32 < 32 < 48 23 < 62 < 59 < 44 < 58 < 69 24 < 40 < 51 < 51 < 50 < 51 25 < 39 < 37 < 37 < 37 < 30 26 < 28 < 30 < 30 < 32 < 17 27 < 35 < 57 < 58 < 58 < 58 28 < 53 < 57 < 58 < 59 < 32 29 < 63 < 60 < 63 < 62 < 208 (1) 30 < 25 < 28 < 28 < 28 < 23 31 < 30 < 33 < 33 < 34 < 27 32 < 35 < 38 < 30 < 39 < 39 33 < 33 < 29 . < 37 < 37 < 36 34 < 53 < 58 < 58 < 59 < 33 35 < 52 < 57 < 45 < 58 < 57 36 < 50 < 55 < 55 < 56 < 56 37 < 40 < 55 < 56 < 56 < 56 38 < 63 < 69 < 69 < 56 < 70 39 < 34 < 37 < 37 < 38 < 19 40 < 57 < 61 < 142 (1) < 63 < 34 41 < 31 < 42 < 44 < 43 < 43 42 < 24 < 20 < 26 < 26 < 25 43 < 32 < 44 < 44 < 45 < 46 44 < 14 < 16 < 16 < 16 < 12 45 < 18 < 33 < 34 <34 < 34 46 < 62 < 66 < 67 < 68 < 45 47 < 27 < 37 < 37 < 38 < 37 48 < 40 < 64 < 64 < 66 < 66 49 < 39 < 54 < 55 < 55 < 54 50 < 35 < 38 < 39 < 39 < 26 51 < 36 < 39 < 39 < 40 < 21 52 < 19 < 21 < 21 < 21 < 14 MEAN 39 +/- 26 41 +/- 27 43 +/- 39 42 +/- 28 37 58 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-11

TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARMS INDICATOR FARMS COLLECTION 23F1 36E1 10F4 18E1 19B1 25C1 25E1 PERIOD 01/11/06 < 0.5 < 0.4 < 0.4 < 0.5 < 0.4 < 0.5 < 0.4 02/14/06 < 0.7 < 0.2 < 0.5 < 0.7 < 0.6 03/14/06 < 0.5 < 0.4 < 0.5 < 0.3 < 0.4 04/04/06 < 0.4 < 0.4 < 0.4 < 0.3 < 0.8 < 0.4 < 0.3 04/17/06 < 0.5 < 0.4 < 0.5 < 0.6 < 0.6 05/02/06 < 0.6 < 0.4 < 0.6 < 0.4 < 0.3 05/16/06 < 0.6 < 0.9 < 0.6 < 0.6 < 0.4 05/30/06 < 0.6 < 0.5 < 0.5 < 0.7 < 0.6 06/13/06 < 1.3 (1) < 1.3 (1) < 1.8 (1) < 1.8 (1) < 1.1 (1) 06/27/06 < 1.1 (1) < 1.2 (1) < 1.9 (1) (1) (1)

< 1.3 < 7.4 07/12/06 < 0.4 < 0.6 < 0.7 < 0.5 < 0.6 < 0.9 < 0.9 07/25/06 < 1.8 (1) < 1.1 (1) < 1.1 (1) < 0.6 (1)

< 2.8 08/08/06 < 0.4 < 0.4 < 0.4 < 0.7 < 0.7 08/22/06 < 0.5 < 0.5 < 0.5 < 0.4 < 0.5 09/05/06 < 0.4 < 0.4 < 0.4 < 0.4 < 0.5 09/19/06 < 0.3 < 0.3 < 0.3 < 0.2 < 0.3 10/03/06 < 0.5 < 0.5 < 0.4 < 0.4 < 0.4 < 0.5 < 0.4 10/17/06 < 0.3 < 0.6 < 0.3 < 0.3 < 0.4 10/31/06 < 0.5 < 0.5 < 0.4 < 0.4 < 0.4 11/14/06 < 0.5 < 0.5 < 0.5 < 0.5 < 0.4 11/28/06 < 0.6 < 0.5 < 0.5 < 0.5 < 0.5 12/12/06 < 0.6 < 0.6 < 0.6 < 0.6 < 0.7 MEAN 0.6 +/- 0.7 0.5 +/- 0.2 0.6 +/- 0.6 0.6 +/- 0.9 0.6 +/- 0.7 0.9 +/- 3.1 0.5 +/- 0.5 (1) See Exceptions Section for Explanation C-12

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD 10F4 01/10/06 1220 +/- 160 < 10 < 10 < 30 < 12 02/14/06 1270 +/- 119 < 9 < 7 < 39 < 11 03/14/06 1360 +/- 147 < 7 < 8 <31 < 10 04/04/06 1420 +/- 143 < 8 < 8 < 38 < 11 04/17/06 1300 +/- 126 < 7 < 8 < 30 < 9 05/02/06 1290 +/- 155 < 9 < 9 < 41 < 12 05/16/06 1330 +/- 180 < 15 < 14 < 54 < 13 05/30/06 1240 +/- 115 < 7 < 7 < 47 < 14 06/13/06 1320 +/- 139 < 9 < 8 < 47 < 15 06/27/06 1380 +/- 133 < 11 < 10 < 46 < 13 07/11/06 1120 +/- 172 < 10 <9 < 44 < 12 07/25/06 1300 +/- 161 < 8 <9 < 34 < 11 08/08/06 1340 +/- 146 < 6 < 7 < 35 < 13 08/22/06 1230 +/- 129 < 5 < 6 < 38 < 12 09/05/06 1350 +/- 138 < 5 < 6 < 41 < 14 09/19/06 1280 +/- 186 < 8 <9 <43 < 14 10/03/06 1390 +/- 130 < 5 < 5 < 42 < 14 10/17/06 1320 +/- 122 < 5 < 5 < 46 < 13 10/31/06 1250 +/- 106 < 4 < 4 < 40 < 12 11/14/06 1290 +/- 113 < 2 < 2 < 24 < 10 11/28/06 1160 +/- 115 < 5 < 6 < 38 < 11 12/12/06 1300 +/- 175 < 7 < 9 <47 < 15 MEAN 1294 +/- 144 7 +/- 6 8 +/- 5 40 +/- 14 12 +/- 3 18E1 01/10/06 1400 +/- 128 < 9 < 8 < 28 < 10 02/14/06 1320 +/- 123 < 9 < 7 < 39 < 10 03/14/06 1300 +/- 127 < 8 < 7 < 25 < 9 04/04/06 1370 +/- 121 < 8 < 8 < 31 < 9 04/17/06 1310 +/- 153 < 10 < 9 < 36 < 14 05/02/06 1200 +/- 160 < 10 < 10 < 42 < 13 05/16/06 1380 +/- 167 < 8 < 9 <-44 < 11 05/30/06 1310 +/- 119 < 7 < 7 < 56 < 14 06/13/06 1220 +/- 111 < 7 <7 < 44 < 15 06/27/06 1280 +/- 210 < 13 < 11 < 48 < 15 07/11/06 1370 +/- 159 < 14 < 10 < 46 < 15 07/25/06 1270 +/- 80.5 < 5 < 5 < 21 < 7 08/08/06 1340 +/- 146 < 5 < 7 < 34 < 12 08/22/06 1050 +/- 166 < 8 < 9 < 55 < 13 09/05/06 1200 +/- 130 < 6 < 6 < 48 < 13 09/19/06 1340 +/- 180 < 6 <9 < 46 < 15 10/03/06 1400 +/- 138 < 6 <6 < 37 < 9 10/17/06 1320 +/- 112 < 3 < 5 < 37 < 14 10/31/06 1390 +/- 114 < 4 < 5 < 41 < 14 11/14/06 1210 +/- 130 < 2 < 4 < 40 < 10 11/28/06 1420 +/- 134 < 6 < 7 <47 < 13 12/12/06 1130 +/- 152 < 11 < 10 < 45 < 15 MEAN 1297 +/- 190 8 +/- 6 8 +/- 4 40 +/- 18 12 +/- 5 C-13

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC K-40 Cs-134 Cs-137 Ba-140 La-1 40 19B1 01/10/06 1450 t 161 < 10 < 10 < 35 < 9 02/14/06 1320 +/- 115 < 8 < 7 <34 < 10 03/14/06 1280 +/- 161 < 9 < 9 < 33 < 9 04/04/06 1420 +/- 133 < 9 < 9 < 40 < 12 04/17/06 1320 +/- 155 < 9 <9 < 44 < 11 05/02/06 1320 +/- 163 < 7 < 9 < 31 < 12 05/16/06 1270 +/- 144 < 9 < 8 < 39 < 11 05/30/06 1350 +/- 114 < 8 < 7 < 51 < 14 06/13/06 1270+/- 114 <6 < 7 < 44 < 13 06/27/06 1380 +/- 188 < 11 < 11 < 45 < 14 07/11/06 1200 125 <9 < 9 < 37 < 13 07/25/06 1350 72 < 3 < 3 < 15 < 4 08/08/06 1340 153 < 6 < 6 < 40 < 11 08/22/06 1380 +/- 184 < 7 < 8 < 52 < 14 09/05/06 1420 +/- 145 < 5 < 5 < 41 < 14 09/19/06 1430 +/- 195 < 7 <9 < 45 < 12 10/03/06 1300 +/- 139 <6 < 6 < 46 < 12 10/17/06 1200 +/- 123 <4 < 5 < 46 < 13 10/31/06 1250 101 <3 < 4 < 35 < 14 11/14/06 1360 121 < 4 < 4 < 51 < 13 11/28/06 1250 133 < 5 < 5 <36 < 10 12/12/06 1380 129 < 5 < 5 < 26 < 8 MEAN 1329 +/- 143 7 +/- 5 7 +/- 4 39 +/- 17 11 +/- 5 23F1 01/10/06 1280 +/- 177 < 7 < 8 < 23 < 6 02/14/06 1180 123 < 8 < 8 < 40 < 12 03/14/06 1300 +/- 144 < 9 < 8 < 32 < 10 04/04/06 1320 +/- 149 < 9 < 10 < 39 < 14 04/17/06 1300 +/- 132 < 7 <8 <34 < 12 05/02/06 1300 +/- 171 < 10 < 11 < 42 < 14 05/16/06 1320 +/- 149 < 7 < 8 < 33 < 12 05/30/06 1410 +/- 91.7 < 6 < 6 < 43 < 14 06/13/06 1210 +/- 111 < 6 < 6 < 40 < 15 06/27/06 1150 +/- 156 < 11 < 10 < 44 < 13 07/12/06 1210 +/- 149 < 12 < 8 < 39 < 12 07/25/06 1300 +/- 60.3 < 3 < 3 < 13 < 4 08/08/06 1220 +/- 152 < 7 < 7 < 45 < 13 08/22/06 1270 +/- 156 < 6 < 7 < 47 < 13 09/05/06 1240 +/- 147 < 5 < 6 < 41 < 13 09/19/06 1320 +/- 157 < 7 < 8 < 33 < 12 10/03/06 1260 +/- 146 < 5 < 6 < 43 < 11 10/17/06 1290 +/- 128 < 5 < 6 < 55 < 12 10/31/06 1370 +/- 145 < 5 < 6 < 54 < 15 11/14/06 1290 +/- 135 < 3 < 4 <38 < 9 11/28/06 1350 +/- 135 < 4 <6 <41 < 12 12/12/06 1240 +/- 146 < 7 <8 < 36 < 7 MEAN 1279 +/- 124 7 +/- 5 7 +/- 4 39 18 12 +/- 6 C-14

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC K-40 Cs-134 Cs-1 37 Ba-1 40 La-1 40 25C1 01/10/06 1130 +/- 240 <7 <8 < 23 <6 02/14/06 1300 +/- 99 <6 <6 < 27 <7 03/14/06 1260 +/- 128 <8 <9

  • 27 <9 04/04/06 1240 +/- 121 <7 <7 < 33 <9 04/17/06 1330 +/- 146 < 10 < 10 <43 < 11 05/02/06 1170 +/- 169 <12 < 10 <46 <13 05/16/06 1210 +/- 150 <8 <9 <40 <13 05/30/06 1300 +/- 97 <6 <6 <45 *14 06/13/06 1380 +/- 133 <8 <8 < 50 < 14 06/27/06 1410 +/- 136 <9 <8 < 35 < 10 07/11/06 1330 +/- 164 <11 < 11 <47 <11 07/25/06 1240 +/- 69.6 <4 <4 *17 <5 08/08/06 1300 +/- 163 <5 <6 <40 *12 08/22/06 1210 +/- 147 <5 <5
  • 32 < 15 09/05/06 1340 +/- 157 <6 <6 < 47 < 15 09/19/06 1340 +/- 175 <6 <7 < 34 < 12 10/03/06 1360 +/- 130 <4 <5 < 40 < 14 10/17/06 1380 + 95.7 <4 <4 < 36 <13 10/31/06 1180 + 126 <5 <5 <46 *15 11/14/06 1210 +/- 115 <2 <3 < 42 < 14 11/28/06 1330 + 140 <6 <6 < 42 *13 12/12/06 1260 + 140 <6 <6 < 29 *12 MEAN 1282 + 153 7+/-5 7+/-4 37 +/- 18 12 6 25E1 01/11/06 1250 +/- 129 <11 <8
  • 36 <11 04/04/06 1200 +/- 159 <10 <9 < 39 <12 07/11/06 1410 +/- 187 <11 <12
  • 51 <8 10/03/06 1390 +/- 120 <5 <5 < 39 <15 MEAN 1313 +/- 207 9+/-6 9+/-5 41 +/- 13 11 +/- 6 36E1 01/10/06 1190 +/- 157 12 < 10 <46 <13 04/04/06 1210 +/- 120 7 <6
  • 28 <11 07/11/06 1190 +/- 149 11 <10 < 39 < 10 10/03/06 1360 +/- 146 6 <7 < 47 <15 MEAN 1238 +/- 164 9+/-6 8+/-4 40 +/- 17 12 +/- 4 C-15

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION BE-7 K-40 MN-54 CO-58 CO-60 1-131 CS-134 CS-137 P F RIO"1" TYPF PERIOD TYPE 11S3 06/22/06 Cabbage < 155 5920 +/- 330 < 14 < 14 < 13 < 55 < 14 < 15 Collards < 138 5610 +/- 276 < 15 < 15 < 15 < 47 < 15 < 14 Lettuce < 82 2150 +/- 173 < 10 < 11 < 11 < 29 < 10 < 10 07/20/06 Cabbage 191 +/- 32 4190 +/- 95 <5 <5 <5 < 20 <5 <5 Collards 110 +/- 23 4340 +/- 77 <4 <4 <4 < 15 <4 <4 Parsley 390 + 38 8430 +/- 120 <5 <6 <6 < 19 <5 <5 08/24/06 Cabbage 117 + 32 4850 +/- 100 <4 < 5 <4 < 50 <4 <4 Collards 103 + 39 3870 +/- 101 <4 <5 <4 <43 <3 <4 Parsley 304 + 32 6710 +/- 92 <3 <3 <3 < 30 <3 <3 09/18/06 Cabbage 260 + 45 3510 +/- 109 <4 <5 <4 < 24 <4 <4 Collards 559 + 53 3500 +/- 118 <5 <5 <5 < 16 <4 <5 Brussel Sprout Leaves 320 + 53 4810 +/- 145 <5 <6 <7 < 17 <5 <6 Mean 227 +/- 289 4824 +/- 3333 < 7 <7 <7 < 30 <6 <7 13S3 06/22/06 Cabbage 102 +/- 97 3540 +/- 186 <11 <11 < 10 < 33 < 12 < 11 Collards < 95 4720 +/- 182 < 10 < 11 < 11 < 32 < 11 < 10 Lettuce < 168 4240 +/- 248 < 18 < 19 < 18 < 57 < 20 < 19 07/20/06 Cabbage 297 +/- 68 2870 +/- 136 <7 <8 <7 < 34 <7 <8 Collards 188 +/- 42 5140 +/- 105 <4 <5 <4 < 17 <4 <4 Cauliflower Leaves 351 +/- 119 4460 +/- 264 < 13 < 14 < 14 <45 < 13 < 14 08/24/06 Cabbage < 35 2370 +/- 96 <3 <4 <3 < 38 <3 <3 Collards 102 +/- 36 5060 +/- 93 <3 <4 <3 < 41 <3 <3 Cauliflower Leaves 119 +/- 38 4130 +/- 112 <4 <5 <4 <46 <4 <4 09/18/06 Cabbage <53 1630 +/- 107 <6 < 6 <5 < 18 <5 <5 Collards 319 +/- 53 3880 +/- 130 < 5 < 6 < 5 < 30 <5 <5 (1)

Mean 166 +/- 220 3822 +/- 2250 < 8 <8 <8 < 36 <8 <8 C-16

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/KG WET +/-:2 SIGMA STC COLLECTION BE-7 K-40 MN-54 CO-58 CO-60 1-131 CS-1 34 CS-1 37 PERIOD TYPE 31 G1 ub/22/Ob Cabbage z29 +/- 1uu b*tu +/- 24U < 14 < 1Z < 15 *46 < 15 < 14 Lettuce 184 t 64 3250 +/- 180 *10 <10 <11

  • 28 <10 *10 Zucchini Leaves 159 +/- 71 5480 +/- 227 <11 *12 <11
  • 38 <11 <12 7/20/2006 String Bean Leaves 817 +/- 47 5630 +/- 113 <5 <5 <5 *19 <4 <5 Yellow Squash Leaves 844 +/- 51 6180 +/- 122 <6 <6 <6
  • 22 <6 <6 Zuchini Leaves 754 +/- 40 5760 +/- 104 <3 <4 <4 *14 <3 <3 08/24/06 Cabbage < 23 2190 +/- 57 <2 <3 <2 < 24 <2 <2 Cucumber Leaves 680 +/- 57 6610 +/- 128 <5 <6 <5 < 59 <4 <5 Yellow Squash Leaves 328 +/- 57 < 177 <4 <4 <3 < 39 <3 <3 9/18/2006 Catalpa Leaves 938 +/- 94 3120 +/- 181 < 9 <10 <8 < 28 <8 <9 Sumac Leaves 1540 +/- 83 4610 +/- 166 < 6 <7 <6
  • 32 <6 <7 Sycamore Leaves 2180 +/- 130 2660 +/- 198 < 10 <10 <9 < 29 <9 <10 Mean 723 +/- 1259 4354 +/- 4093 < 7 <8 <7 <32 <7 (1) SEE PROGRAM EXCEPTION SECTION FOR EXPLANATION C-17

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR LIMERICK GENERATION STATION, 2006 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE +/- 2S. D.

36S2 8.1 + 1.4 8.1 +/- 0.5 7.3 +/- 0.4 9.0 +/- 0.7 7.9 -0.6 7.0 1.0 7.5 +/- 0.4 6.5 +/- 0.6 7.3 +/- 0.7 6.7 +/- 0.4 36D1 2E1 8.0 +/- 0.8 7.9 + 0.6 7.7 +/- 1.3 8.6 +/- 0.4 7.8 + 0.8 3S1 7.7 +/- 0.6 7.6 +/- 0.4 7.4 +/- 0.3 8.1 +/- 0.6 7.6 +/- 0.7 4E1 6.1 +/- 1.1 6.0 +/- 0.3 5.8 +/- 0.3 6.9 +/- 0.6 5.6 + 0.3 5Sl 8.8 +/- 0.6 8.8 +/- 0.6 8.4 +/- 0.4 9.0 11.5 9.0 +/- 1.4 5H1 9.0 +/- 1.2 8.9 +/- 0.5 8.5 +/- 1.1 9.8 +/- 0.6 8.6 +/-1 6C1 7.3 +/- 1.3 7.8 +/- 1.9 6.8 +/- 0.5 8.0 +/- 0.7 6.7 +/- 0.4 7S1 8.1 +/-0.6 7.9 + 1.4 7.8 +/- 0.7 8.5 + 0.6 8.0 +/- 0.4 7E1 7.9 +/- 1.2 7.9 +/- 0.6 7.9 +/- 0.4 8.6 +/- 0.6 7.1 +/- 0.7 9C1 7.3 +/- 1.2 7.2 + 0.1 6.8 +/- 0.3 8.1 +/- 0.7 6.9 +/- 0.4 10S3 8.0 +/- 0.6 8.0 + 0.3 7.7 +/- 0.1 8.4 + 0.9 7.9 +/- 0.6 10E1 7.7 +/- 0.9 7.7 +/- 0.5 7.4 +/- 0.6 8.4 +/- 0.7 7.4 +/- 0.5 10F3 7.5 + 1.4 7.5 + 0.5 7.3 +/- 0.8 8.4 +/- 0.4 6.7 +/- 0.3 11l1 9.1 +/- 1.4 8.9 + 0.8 8.2 +/- 0.3 9.7 +/- 2.5 9.6 +/- 1.4 13S2 11.6 +/- 1.6 11 +/- 0.6 11 +/- 0.7 12 +/- 0.6 12 - 0.7 13C1 6.0 +/- 1.4 6.3 +/- 0.4 5.5 +/- 0.4 6.8 +/- 0.4 5.3 +/- 0.6 13E1 7.6 +/- 1.9 7.1 + 0.4 7.5 +/- 0.9 8.9 +/- 0.7 6.8 +/- 0.4 14Sl 7.1 +/- 1.0 7.0 + 0.4 6.5 +/- 0.5 7.6 +/- 0.5 7.4 +/- 0.5 15D1 7.7 +/- 1.3 7.8 + 0.4 17.2 +/- 0.4 8.6 +/- 0.5 7.3 +/- 0.7 16F1 7.9 +/- 0.8 7.7 +/- 0.5 7.5 +/- 1.0 8.4 +/- 0.5 7.8 +/- 0.6 17B1 7.2 +/- 1.2 7.4 + 0.7 6.6 +/- 0.5 8.0 +/- 0.3 6.9 +/- 0.6 18S2 8.2 +/- 1.8 7.0 + 0.4 8.4 +/- 0.7 9.2 +/- 0.4 8.3 - 0.6 19D1 7.1 +/- 1.3 7.4 +/- 0.4 6.7 +/- 1.2 7.9 +/- 0.7 6.5 + 0.4 20D1 7.1 +/- 1.2 7.2 +/- 0.4 6.5 +/- 0.2 7.8 +/- 0.8 6.7 +/- 0.5 20F1 7.3 +/- 1.2 7.1 +/- 0.4 6.9 +/- 0.9 8.2 +/- 0.2 6.9 +/- 0.5 21S2 7.2 +/- 0.6 7.1 + 0.3 6.8 + 0.5 7.4 +/- 0.4 7.4 +/- 0.6

.23S2 7.3 +/- 1.1 6.9 + 0.6 6.7 +/- 0.7 7.8 +/- 0.5 7.6 +/- 0.7 24D1 6.5 +/- 1.4 7.0 +/- 0.6 5.8 +/- 0.8 7.2 +/- 0.2 6.1 +/- 0.5 25S2 6.7 +/- 0.5 6.8 +/- 0.8 6.4 +/- 0.6 (1) 6.8 +/- 0.4 25D1 6.4 +/- 1.3 6.9 +/- 0.3 5.8 +/- 0.3 7.1 +/- 0.8 5.9 +/- 0.5 26S3 7.0 +/- 0.8 7.0 + 0.9 6.5 +/- 0.7 7.5 +/- 0.8 7.1 - 0.5 28D2 6.9 +/- 1.0 7.3 +/- 0.3 6.4 +/- 0.5 7.4 +/- 0.6 6.6 +/- 0.6 29Sl 7.2.+ 0.9 7.3 + 0.3 6.5 +/- 0.6 7.4 +/- 0.2 7.4 + 1.0 29E1 7.4 +/- 2.0 8.6 + 0.7 6.3 +/- 0.1 7.8 +/- 0.7 6.9 +/- 0.4 31Sl 7.9 +/- 0.7 7.6 +/- 0.4 7.6 +/- 0.6 8.3 +/- 0.9 8.0 +/- 0.3 3101 8.9 1.1 9.0 + 0.8 8.5 +/- 0.3 9.6 +/- 0.5 8.4 +/- 0.5 31 D2 7.7 _ 1.2 7.9 +/- 0.6 7.4 +/- 0.3 8.5 +/- 0.5 7.1 - 0.3 34S2 7.9 + 1.1 8.1 +/- 0.5 7.4 +/- 0.9 8.6 11.6 7.6 - 0.3 34E1 7.3 + 1.2 7.7 + 0.6 6.7 +/- 0.5 8.0 + 0.4 6.9 _ 0.2 (1) SEE PROGRAM EXCEPTIONS FOR EXPLANATION C-18

TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, MIDDLE AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF MILLI-ROENTGEN/ STD. MONTH +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION SITE BOUNDARY MIDDLE CONTROL PERIOD +/- 2S. D.

JAN-MAR 7.8 +/- 1.1 7.5 +/- 0.6 8.9 +/- 0.0 APR-JUN 7.5 +/- 1.1 6.8 +/- 0.7 8.5 +/- 0.0 JUL-SEP 8.6 +/- 1.2 8.0 +/- 0.7 9.8 +/- 0.0 OCT-DEC 8.1 +/- 1.3 6.8 +/- 0.7 8.6 +/- 0.0 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN PRE-OP MEAN ANALYZED MINIMUM MAXIMUM +/- 2S. D. +/- 2S. D.

SITE BOUNDARY 63 6.4 12.4 8.0 +/- 1.2 7.6 +/- 2.4 MIDDLE DISTANCE 92 5.3 9.6 7.3 +/- 0.8 7.8 +/- 2.2 CONTROL 4 8.5 9.8 9.0 +/- 0.6 7.8 +/- 3.0 THE PRE-OPERATIONAL MEAN WAS CALCULATED FROM MONTHLY TLD READINGS 01/15/82 TO 12/02/84.

SITE BOUNDARY STATIONS - 36S2, 3S1, 5S1, 7S1, 10S3, 11S1, 13S2, 14S1, 18S2, 21S2, 23S2, 25S2, 26S3, 29S1, 31S1, 34S2 MIDDLE DISTANCE STATIONS - 36D1, 2E1, 4E1, 6C1, 7E1, 9C1, 10E1, 10F3, 13C1, 13E1, 15D1, 16F1, 17B1, 19D1, 20D1, 20F1, 24D1, 25D1, 28D2, 29E1, 31D1, 31D2, 34E1 CONTROL STATIONS - 5H1 C-19

TABLE C-X.1

SUMMARY

OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 SURFACE WATER (TRITIUM LIQUID SCINTILLATION)

COLLECTION PERIOD 13131 2451 JAN-MAR 01/03/06 - 04/03/06 01/03/06 - 04/03/06 APR-JUN 04/03/06 - 06/26/06 04/03/06 - 06/26/06 JUL-SEP 06/26/06 - 10/02/06 06/26/06 - 10/02/06 OCT-DEC 10/02/06 - 01/02/07 10/02/06 - 01/02/07 SURFACE WATER (GAMMA SPECTROSCOPY)

COLLECTION PERIOD 13131 24S11 JAN 01/03/06 -01/31/06 01/03/06 - 01/31/06 FEB 01/31/06 -02/28/06 01/31/06 - 02/28/06 MAR 02/28/06 -04/03/06 02/28/06 - 04/03/06 APR 04/03/06 -05/01/06 04/03/06 - 05/01/06 MAY 05/01/06 -05/30/06 05/01/06 - 05/30/06 JUN 05/30/06 -06/26/06 05/30/06 - 06/26/06 JUL 06/26/06 -07/31/06 06/26/06 - 07/31/06 AUG 07/31/06 -08/28/06 07/31/06 - 08/28/06 SEP 08/28/06 -10/02/06 08/28/06 - 10/02/06 OCT 10/02/06 -10/30/06 10/02/06 - 10/30/06 NOV 10/30/06 -11/27/06 10/30/06 - 11/27/06 DEC 11/27/06 -01/02/07 11/27/06 - 01/02/07 DRINKING WATER (TRITIUM)

COLLECTION PERIOD 15174 15F7 16C2 28F3 JAN-MAR 01/03/06 - 04/03/06 01/03/06 - 04/03/06 01/03/06 - 04/03/06 01/03/06 -04/03/06 APR-JUN 04/03/06 - 06/26/06 04/03/06 - 06/26/06 04/03/06 - 06/26/06 04/03/06 -06/26/06 JUL-SEP 06/26/06 - 10/02/06 06/26/06 - 10/02/06 06/26/06 - 10/02/06 06/26/06 -10/02/06 OCT-DEC 10/02/06 - 01/02/07 10/02/06 - 01/02/07 10/02/06 - 01/02/07 10/02/06 -01/02/07 DRINKING WATER (GROSS BETA & GAMMA SPECTROSCOPY)

COLLECTION PERIOD 15F4 15F7 16C2 28IF3 JAN 01/03/06 -01/31/06 01/03/06 - 01/31/06 01/03/06 - 01/31/06 01/03/06 - 01/31/06 FEB 01/31/06 -02/28/06 01/31/06 - 02/28/06 01/31/06 - 02/28/06 01/31/06 - 02/28/06 MAR 02/28/06 -04/03/06 02/28/06 - 04/03/06 02/28/06 - 04/03/06 02/28/06 - 04/03/06 APR 04/03/06 -05/01/06 04/03/06 - 05/01/06 04/03/06 - 05/01/06 04/03/06 - 05/01/06 MAY 05/01/06 -05/30/06 05/01/06 - 05/30/06 05/01/06 - 05/30/06 05/01/06 - 05/30/06 JUN 05/30/06 -06/26/06 05/30/06 - 06/26/06 05/30/06 - 06/26/06 05/30/06 - 06/26/06 JUL 06/26/06 -07/31/06 06/26/06 - 07/31/06 06/26/06 - 07/31/06 06/26/06 - 07/31/06 AUG 07/31/06 -08/28/06 07/31/06 - 08/28/06 07/31/06 - 08/28/06 07/31/06 - 08/28/06 SEP 08/28/06 -10/02/06 08/28/06 - 10/02/06 08/28/06 - 10/02/06 08/28/06 - 10/02/06 OCT 10/02/06 -10/30/06 10/02/06 - 10/30/06 10/02/06 - 10/30/06 10/02/06 - 10/30/06 NOV 10/30/06 -11/27/06 10/30/06 - 11/27/06 10/30/06 - 11/27/06 10/30/06 - 11/27/06 DEC 11/27/06 -01/02/07 11/27/06 - 01/02/07 11/27/06 - 01/02/07 11/27/06 - 01/02/07 C -2G

TABLE C-X.1

SUMMARY

OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 AIR PARTICULATE (GAMMA SPECTROSCOPY)

COLLECTION 10S3 1isi 14S1 13CS 22G1 PERIOD JAN-MAK Ul/Uj/Ub - U4/Ui/Ub Ul/UJ/Ub - U4/UJ/Ub Ul/Ul/Ub - U4/UJ/Ub Ul/UJ/Ub - U4/Ui/Ub Ul/UJ/Ub - U4/UJ/Ub APR-JUN 04/03/06 - 07/03/06 04/03/06 - 07/03/06 04/03/06 - 07/03/06 04/03/06 - 07/03/06 04/03/06 - 07/03/06 JUL-SEP 07/03/06 - 10/02/06 07/03/06 - 10/02/06 07/03/06- 10/02/06 07/03/06 - 10/02/06 07/03/06 - 10/02/06 OCT-DEC 10/02/06 - 01/02/07 10/02/06 - 01/02/07 10/02/06 - 01/02/07 10/02/06 - 01/02/07 10/02/06 - 01/02/07 AIR PARTICULATE (GROSS BETA & 1-131)

COLLECTION 10S3 11$1 14S1 13CS 22G1 PERIOD 1 UIIUIUu " UI IU@IU uI/UIuu - UIIUUIUo UIIUd/UO - UI/U*IUO UIIUJIUb - UIIUIU/U UjIIUJIUl - UII/U/Ub 2 01/09/06 - 01/17/06 01/09/06 - 01/17/06 01/09/06 - 01/17/06 01/09/06 - 01/17/06 01/09/06 - 01/17/06 3 01/17/06 - 01/24/06 01/17/06 - 01/24/06 01/17/06 - 01/24/06 01/17/06 - 01/24/06 01/17/06 - 01/24/06 4 01/24/06 - 01/30/06 01/24/06 - 01/30/06 01/24/06 - 01/30/06 01/24/06 - 01/30/06 01/24/06 - 01/30/06 5 01/30/06 - 02/06/06 01/30/06 - 02/06/06 01/30/06 - 02/06/06 01/30/06 - 02/06/06 01/30/06 - 02/06/06 6 02/06/06 - 02/13/06 02/06/06 - 02/13/06 02/06/06 - 02/13/06 02/06/06 - 02/13/06 02/06/06 - 02/13/06 7 02/13/06 - 02/21/06 02/13/06 - 02/21/06 02/13/06 - 02/21/06 02/13/06 - 02/21/06 02/13/06 - 02/21/06 8 02/21/06 - 02/27/06 02/21/06 - 02/27/06 02/21/06 - 02/27/06 02/21/06 - 02/27/06 02/21/06 - 02/27/06 9 02/27/06 - 03/06/06 02/27/06 - 03/06/06 02/27/06 - 03/06/06 02/27/06 - 03/06/06 02/27/06 - 03/06/06 10 03/06/06 - 03/13/06 03/06/06 - 03/13/06 03/06/06 - 03/13/06 03/06/06 - 03/13/06 03/06/06 - 03/13/06 11 03/13/06 - 03/20/06 03/13/06 - 03/20/06 03/13/06 - 03/20/06 03/13/06 - 03/20/06 03/13/06 - 03/20/06 12 03/20/06 - 03/27/06 03/20/06 - 03/27/06 03/20/06 - 03/27/06 03/20/06 - 03/27/06 03/20/06 - 03/27/06 13 03/27/06 - 04/03/06 03/27/06 - 04/03/06 03/27/06 - 04/03/06 03/27/06 - 04/03/06 03/27/06 - 04/03/06 14 04/03/06 - 04/10/06 04/03/06 - 04/10/06 04/03/06 - 04/10/06 04/03/06 - 04/10/06 04/03/06 - 04/10/06 15 04/10/06 - 04/17/06 04/10/06 - 04/17/06 04/10/06 - 04/17/06 04/10/06 - 04/17/06 04/10/06 - 04/17/06 16 04/17/06 - 04/24/06 04/17/06 - 04/24/06 04/17/06 - 04/24/06 04/17/06 - 04/24/06 04/17/06 - 04/24/06 17 04/24/06 - 05/01/06 04/24/06 - 05/01/06 04/24/06 - 05/01/06 04/24/06 - 05/01/06 04/24/06 - 05/01/06 18 05/01/06 - 05/09/06 05/01/06 - 05/09/06 05/01/06 - 05/09/06 05/01/06 - 05/09/06 05/01/06 - 05/09/06 19 05/09/06 - 05/15/06 05/09/06 - 05/15/06 05/09/06 - 05/15/06 05/09/06 - 05/15/06 05/09/06 - 05/15/06 20 05/15/06 - 05/22/06 05/15/06 - 05/22/06 05/15/06 - 05/22/06 05/15/06 - 05/22/06 05/15/06 - 05/22/06 21 05/22/06 - 05/30/06 05/22/06 - 05/30/06 05/22/06 - 05/30/06 05/22/06 - 05/30/06 05/22/06 - 05/30/06 22 05/30/06 - 06/05/06 05/30/06 - 06/05/06 05/30/06 - 06/05/06 05/30/06 - 06/05/06 05/30/06 - 06/05/06 23 06/05/06 - 06/12/06 06/05/06 - 06/12/06 06/05/06 - 06/12/06 06/05/06 - 06/12/06 06/06/06 - 06/12/06 24 06/12/06 - 06/19/06 06/12/06 - 06/19/06 06/12/06 - 06/19/06 06/12/06 - 06/19/06 06/12/06 - 06/19/06 25 06/19/06 - 06/26/06 06/19/06 - 06/26/06 06/19/06 - 06/26/06 06/19/06 - 06/26/06 06/19/06 - 06/26/06 26 06/26/06 - 07/03/06 06/26/06 - 07/03/06 06/26/06 - 07/03/06 06/26/06 - 07/03/06 06/26/06 - 07/03/06 27 07/03/06 - 07/10/06 07/03/06 - 07/10/06 07/03/06 - 07/10/06 07/03/06 - 07/10/06 07/03/06 - 07/10/06 28 07/10/06 - 07/17/06 0ý7/10/06 - 07/17/06 07/10/06 - 07/17/06 07/10/06 - 07/17/06 07/10/06 - 07/17/06 29 07/17/06 - 07/24/06 07/17/06 - 07/24/06 07/17/06 - 07/24/06 07/17/06 - 07/24/06 07/17/06 - 07/24/06 30 07/24/06 - 07/31/06 07/24/06 - 07/31/06 07/24/06 - 07/31/06 07/24/06 - 07/31/06 07/24/06 - 07/31/06 31 07/31/06 - 08/08/06 07/31/06 - 08/08/06 07/31/06 - 08/08/06 07/31/06 - 08/08/06 07/31/06 - 08/08/06 32 08/08/06 - 08/14/06 08/08/06 - 08/14/06 08/08/06 - 08/14/06 08/08/06 - 08/14/06 08/08/06 - 08/14/06 33 08/14/06 - 08/21/06 08/14/06 - 08/21/06 08/14/06 - 08/21/06 08/14/06 - 08/21/06 08/14/06 - 08/21/06 34 08/21/06 - 08/28/06 08/21/06 - 08/28/06 08/21/06 - 08/28/06 08/21/06 - 08/28/06 08/21/06 - 08/28/06 35 08/28/06 - 09/05/06 08/28/06 - 09/05/06 08/28/06 - 09/05/06 08/28/06 - 09/05/06 08/28/06 - 09/05/06 36 09/05/06 - 09/12/06 09/05/06 - 09/12/06 09/05/06 - 09/12/06 09/05/06 - 09/12/06 09/05/06 - 09/12/06 37 09/12/06 - 09/18/06 09/12/06 - 09/18/06 09/12/06 - 09/18/06 09/12/06 - 09/18/06 09/12/06 - 09/18/06 38 09/18/06 - 09/25/06 09/18/06 - 09/25/06 09/18/06 - 09/25/06 09/18/06 - 09/25/06 09/18/06 - 09/25/06 39 09/25/06 - 10/02/06 09/25/06 - 10/02/06 09/25/06 - 10/02/06 09/25/06 - 10/02/06 09/25/06 - 10/02/06 40 10/02/06 - 10/09/06 10/02/06 - 10/09/06 10/02/06 - 10/09/06 10/02/06 - 10/09/06 10/02/06 - 10/09/06 41 10/09/06 - 10/16/06 10/09/06 - 10/16/06 10/09/06 - 10/16/06 10/09/06 - 10/16/06 10/09/06 - 10/16/06 42 10/16/06 - 10/23/06 10/16/06 - 10/23/06 10/16/06 - 10/23/06 10/16/06 - 10/23/06 10/16/06 - 10/23/06 43 10/23/06 - 10/30/06 10/23/06 - 10/30/06 10/23/06 - 10/30/06 10/23/06 - 10/30/06 10/23/06 - 10/30/06 44 10/30/06 - 11/06/06 10/30/06 - 11/06/06 10/30/06 - 11/06/06 10/30/06 - 11/06/06 10/30/06 - 11/06/06 45 11/06/06 - 11/13/06 11/06/06 - 11/13/06 11/06/06 - 11/13/06 11/06/06 - 11/13/06 11/06/06 - 11/13/06 46 11/13/06 - 11/20/06 11/13/06 - 11/20/06 11/13/06 - 11/20/06 11/13/06 - 11/20/06 11/13/06 - 11/20/06 47 11/20/06 - 11/27/06 11/20/06 - 11/27/06 11/20/06 - 11/27/06 11/20/06 - 11/27/06 11/20/06 - 11/27/06 48 11/27/06 - 12/04/06 11/27/06 - 12/04/06 11/27/06 - 12/04/06 11/27/06 - 12/04/06 11/27/06 - 12/04/06 49 12/04/06 - 12/11/06 12/04/06 - 12/11/06 12/04/06 - 12/11/06 12/04/06 - 12/11/06 12/04/06 - 12/11/06 50 12/11/06 - 12/18/06 12/11/06 - 12/18/06 12/11/06 - 12/18/06 12/11/06 - 12/18/06 12/11/06 - 12/18/06 51 12/18/06 - 12/26/06 12/18/06 - 12/26/06 12/18/06 - 12/26/06 12/18/06 - 12/26/06 12/18/06 - 12/26/06 52 12/26/06 - 01/02/07 12/26/06 - 01/02/07 12/26/06 - 01/02/07 12/26/06 - 01/02/07 12/26/06 - 01/02/07 C -21

TABLE C-X.1

SUMMARY

OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 TLD STATION JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE 36S2 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 36D1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 2E1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 3S1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 4E1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 5S1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 5H1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 6C1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 7S1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 7E1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 9Cl 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 10S3 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 10E1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 10F3 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 11S1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 13S2 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 13C1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 13E1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 14S1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 15D1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 16F1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 17B1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 18S2 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 19D1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 20D1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 20F1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 21S2 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 23S2 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 24D1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 25S2 01/05/06 - 04/12/06 04/12/06 - 07/12/06 (1) 10/03/06 - 01/04/07 25D1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 - 10/03/06 10/03/06 - 01/04/07 26S3 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 28D2 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 29S1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 29E1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 31S1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 3101 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 31D2 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 34S2 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 34E1 01/05/06 - 04/12/06 04/12/06 - 07/12/06 07/12/06 10/03/06 10/03/06 - 01/04/07 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C -22

FIGURE C-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2006 1 14 .. . . . . .

10 9 ....-- ---- --.--..... ---.---....... .. ...---- ---- - -- --- --.

8 i-- i A, - - - ------. ------

I I~: Il.. , , '

7 - -- I - - r --

6'

-- p 3

44~- 4 ', i ' i

30. I ,-- [~*I - ,.- -

2I . . ... .... ..

1 -- in--CONTROL

-----INDICATOR 0 , I _ L ___I _ __ I r r I 1i 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 Note: 2005 analysis changed from Insoluble & Soluble to Total Gross Beta YEA R LGS CRITICALITY LGS CHANGED TO TOTAL GROSS BETA AT THE BEGINNING UNIT NO. 1: 12/22/84 OF 2005. PREVIOUS DATA INCLUDED SUMMATION OF LESS UNIT NO. 2: 08/11/89 THAN VALUES.

C -23

FIGURE C-2 MEAN ANNUAL CS-137 CONCENTRATIONS IN FISH SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2006 6 0 ...... . . . .. .. . . . ..................................... . ............... .. . . . . . . . . . . . . .

65 -- -- --- - -

60 -u16C5

. . . . ..5 . . .

55 50 ............ ....... ....... . . . . . . . . . .. . .. ....... .. . .

. .. ............. - -2 C 450 .. ....... . .. . :................................

40 ....

LGS CRITICALITY . . . .

35 UNIT NO. 1: 12/22/84 ...... J. .

2switched 30 - ""....

SUNIT NO. 2:08/11/89

/Note: Second half of 2000 to reporting < MDC aciit.asd te t d ... ... ... ..

Using MDC values result in a

a. 25 .- --............... . .................. .... ............... larger num ber. LLD < 150- -

, *

  • pCi/kg.. .

20 . -- . ......-------.

155- --------- ---.- ---.-

-.-.-.. .-.. .- / -. --------

10 ........

0 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 YEAR CONTROL = 29C1 Station 20S1 discontinued in 1995 C - 24

FIGURE C-3 CONCENTRATIONS OF CS-137 INSEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2006 1400 ...

1200 ------------------ -- 16C 4 1000-- 33A2 10 0 0 . ....... * ...... . ........... I ........ I ....,...., ........ .. .. ............................ .

E 8 00"o ~~~~~ a- .0 0 I-- --I - - .-- .

I-. . - -- --- ..- -I 600 - ------------ --------------------- --------

0 S 400-- - --- - - - - --- - -- - --- - -

200 0 '77 ---------- - - -

-200 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 LGS CRITICALITY Yea r UNIT NO. 1: 12/22/84 UNIT NO. 2: 08/11189 CONTROL = 33A2 C -25

FIGURE C-4 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2006 150 135 ... .. . . . . . . .. . .. .... . .. ....

. .. .. .... .. . - - G ro u p 1

-.--- Group I 5--Group III 12 0 . .... . . I I.,..

105Chernobyl

" 10 5 ........ . . ... .. ... .............

E 90 S 75 * ** * * *** -

LGS CRITICALITY .

L 60.. NO. 1:12/22/84 UNIT N. - -............ . ..

45 .. ... ... ... ...... ... .. . . . . ...... ...

3 0.. . .. . ... . . . . . . . .

15 U NO. 2:...08 1....89 .. .

0 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 YEAR C - 26

FIGURE C-5 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 2006 50 I

--- GROUP I

-- -GROUP II 40 +---------------------------------------------------------------------------------- -- ,-GROUP III 30 -

I-C.,

cv) 20 -

L6 10 0 II I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I 1 I I 1 I ! 1 I 1 1 4 8 12 16 20 24 28 32 36 40 44 48 52 WEEK NO.

C -27

FIGURE C-6 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (TLD)

IN THE VICINITY OF LGS, 1985 - 2006 13

  • SITE 12-- INTERMEDIATE

-M-- CONTROL 11 -- o-- Control 5H1

= ,~ q:, l 41 6q1k 8*

7= -: - -" - A- ,-...-- .....

6 c i,  !

  • i: i i 4

85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 YEAR NOTE: Control Station 51-11 became the only distant location beginning in 1995 C - 28

APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY

The following section contains data and figures illustrating the analyses performed by the quality control laboratory, Environmental Incorporated (ENV). Duplicate samples were obtained from several locations and media and split between the primary laboratory, Teledyne Brown Engineering (TBE) and Env. Comparison of the results for most media were within expected ranges.

D-1

Intentionally left blank D-2

TABLE D-I.1 CONCENTRATIONS OF TOTAL GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 16C2 PERIOD JAN 1.5 +/- 0.6 FEB 1.2 +/- 0.5 MAR 1.8 +/- 1.0 APR 5.2 +/- 1.2 MAY 2.4 +/- 1.0 JUN 1.7 +/- 0.6 JUL 1.8 +/- 0.6 AUG 2.1 +/- 1.5 SEP 1.9 +/- 0.6 OCT 2.4 +/- 1.0 NOV 2.9 +/- 1.1 DEC 2.4 +/- 0.8 MEAN 0.9 +/- 0.6 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 16C2 PERIOD JAN - MAR < 167 APR - JUN

  • 131 JUL - SEP < 183 SEP - DEC < 146 MEAN < 157 D-3

TABLE D-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-1 40 PERIOD 16C2 JAN < 4 <3 <6 <4 <5 <4 <4 <5 <4 <4 <8 <2 FEB < 3 <2 <5 <2 <3 <5 <2 <4 <3 <3 <9 <1 MAR < 3 <3 <5 <3 <2 <5 <2 <3 <4 <3 <11 <2 APR < 3 <4 <8 <1 <4 <4 <2 <3 <2 <3 <11 <2 MAY < 3 <4 <8 <2 <4 <5 <5 <4 <3 <4 <18 <5 JUN < 6 <5 <9 <3 <8 <10 <4 <4 <6 <4 < 22 <3 JUL < 3 <3 <5 <3 <6 <5 <4 <5 <2 <4 < 11 <2 AUG < 2 <3 < 13 <4 <6 <8 <4 <3 <4 <5 <12 <5 SEP < 2 <3 <5 <3 <3 <5 <3 <4 <3 <2 <18 <3 OCT < 4 <2 <6 <3 <5 <6 <5 <7 <2 <3

  • 21 <5 NOV < 3 <1 <3 <1 <5 <4 <3 <2 <3 <3 < 10 <3 DEC < 3 <4 <6 <3 <4 <6 <3 <4 <5 <4 < 16 <3 MEAN 3.1 +/- 1.9 3.0 +/- 2.1 6 +/- 5.3 2.6 +/- 1.8 4.5 +/- 3.2 5.5 +/- 3.5 3.2 +/- 2.0 4.1 +/- 2.7 3.3 +/- 2.3 3.4 +/- 1.7 14 +/- 9 3.1 +/- 2.4 D-4

TABLE D-11.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION 11S2 PERIOD 1 12 +/- b 2 19+/-4 3 15+/-4 4 20+/-5 5 20 +/-4 6 19+/-4 7 33 +/-4 8 28 +/-5 9 20 +/-4 10 18 +/- 4 11 24 +/- 5 12 8+/-4 13 31 5 14 19 4 15 21 5 16 9+4 17 15 4 18 22 + 4 19 15 5 20 7 4 21 24 4 22 20 5 23 8+/-4 24 18 +/- 4 25 23 +/- 4 26 23 +/- 5 27 24 +/- 5 28 24 +/- 5 29 30 +/- 5 30 27 +/- 5 31 37 5 32 18 5 33 26 5 34 31 5 35 9 4 36 26 5 37 11 5 38 31 5 39 21 4 40 25 5 41 26 5 42 22 4 43 11 4 44 29 5 45 23 5 46 19_4 47 24 5 48 30 +/-5 49 33 +/-5 50 31 +/- 5 51 22 +/- 4 52 21 +/- 4 MEAN 22 +/- 14 D-5

TABLE D-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Be-7 Mn-54 Co-58 Co-60 Cs-1 34 Cs-1 37 PERIOD 11S2 01/02 - 04/03/2006 96 0

  • 0.8 < 0.7 < 1.2 < 0.4
  • 0.3 04/03 - 07/03/2006 82+ 17
  • 1.0 < 1.1 <1.1
  • 0.7 < 0.7 07/03 - 10/02/2006 75 14 < 0.8 < 0.6 < 1.1
  • 0.8 < 0.5 10/02 - 01/02/2007 67 + 17 < 0.5
  • 1.0 < 0.6
  • 0.9 < 0.6 MEAN 80 +/- 25 0.8 +/- 0.4 0.9 +/- 0.5 1.0 +/- 0.5 0.7 +/- 0.4 0.5 +/- 0.3 D-6

TABLE D-I11.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION AND GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION 1-131 K-40 Cs-1 34 Cs-1 37 Ba-1 40 La- 140 PERIOD 19B1 01/10/2006

  • 0.2 1228 +/- 98 < 3.3 <3
  • 9.8
  • 1.4 04/04/2006
  • 0.2 1321 +/- 129 < 4.5
  • 1.7 <16 < 3.7 07/11/2006
  • 0.3 1380 +/- 104
  • 4.1
  • 3.6 *15 < 3.5 10/03/2006
  • 0.5 1413 +/- 113 < 4.5
  • 2.4 < 11
  • 2.4 MEAN 0.30 +/- 0.28 1335 +/- 162 4+/-1 3+/-2 13 +/- 5 3+/-2 10F4 01/10/2006 < 0.2 1200 +/- 138.6
  • 2.9 <6 < 22
  • 2.8 04/04/2006
  • 0.4 1322 +/- 120 < 4.7
  • 4.2
  • 21 < 5.3 07/11/2006 < 0.4 1399 +/- 112 <3
  • 2.7
  • 10 <3 10/03/2006 S0.5 1284 +/- 157 < 5.2 < 6.4
  • 19 < 3.2 MEAN 0.38 +/- 0.25 1301 +/- 165 4+/-2 5+/-3 18 +/- 11 4+/-2 25C1 01/10/2006 < 0.2 1338 +/- 168
  • 7.8 < 6.4
  • 18
  • 3.1 04/04/2006 < 0.2 1253 +/- 168
  • 4.1 < 3.9
  • 26 < 7.7 07/11/2006 < 0.4 1278 +/- 109
  • 2.3
  • 3.2
  • 18
  • 2.5 10/03/2006 < 0.4 1341 +/- 121
  • 3.8
  • 2.2
  • 9.0 < 2.5 MEAN 0.30 +/- 0.23 1303 +/- 88 5+/-5 4+/-4 17 +/- 13 4+/-5 D-7

TABLE D-IV.1

SUMMARY

OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2006 DRINKING WATER (GROSS BETA & GAMMA SPECTROSCOPY)

COLLECTION PERIOD 16C2 JAIN U IIUji1UO - U I/U/UO FEB 01/31/06 - 02/28/05 MAR 02/28/06 - 04/03/06 APR 04/03/06 - 05/01/06 MAY 05/01/06 - 05/30/06 JUN 05/30/06 - 06/26/06 JUL 06/26/06 - 07/31/06 AUG 07/31/06 - 08/28/06 SEP 08/28/06 - 10/02/06 OCT 10/02/06 - 10/30/06 NOV 10/30/06 - 11/27/06 DEC 11/27/06 - 01/02/07 AIR PARTICULATE (GAMMA SPECTROSCOPY)

COLLECTION PERIOD 11$S2 JAN-MAN U1/Uz/Ub5 - U4/Uj/Uo APR-JUN 04/03/06 - 07/03/06 JUL-SEP 07/03/06 - 10/02/06 OCT-DEC 10/02/06 - 01/02/07 AIR PARTICULATE (GROSS BETA)

COLLECTION COLLECTION PERIOD 11S2 PERIOD 11S2 U I/Uj-Uu - UI/UliUb UIIi fIUU UIIIUjIUb " U0 IU/Ub 2 01/09/06 - 01/17/06 01/28/00 07/10/06 - 07/17/06 3 01/17/06 - 01/24/06 01/29/00 07/17/06 - 07/24/06 4 01/24/06 - 01/30/06 01/30/00 07/24/06 - 07/31/06 5 01/30/06 - 02/06/06 01/31/00 07/31/06 - 08/08/06 6 02/06/06 - 02/13/06 02/01/00 08/08/06 - 08/14/06 7 02/13/06 - 02/21/06 02/02/00 08/14/06 - 08/21/06 8 02/21/06 - 02/27/06 02/03/00 08/21/06 - 08/28/06 9 02/27/06 - 03/06/06 02/04/00 08/28/06 - 09/05/06 10 03/06/06 - 03/13/06 02/05/00 09/05/06 - 09/12/06 11 03/13/06 - 03/20/06 02/06/00 09/12/06 - 09/18/06 12 03/20/06 - 03/27/06 02/07/00 09/18/06 - 09/25/06 13 03/27/06 - 04/03/06 02/08/00 09/25/06 - 10/02/06 14 04/03/06 - 04/10/06 02/09/00 10/02/06 - 10/09/06 15 04/10/06 - 04/17/06 02/10/00 10/09/06 - 10/16/06 16 04/17/06 - 04/24/06 02/11/00 10/16/06 - 10/23/06 17 04/24/06 - 05/01/06 02/12/00 10/23/06 - 10/30/06 18 05/01/06 - 05/09/06 02/13/00 10/30/06 - 11/06/06 19 05/09/06 - 05/15/06 02/14/00 11/06/06 - 11/13/06 20 05/15/06 - 05/22/06 02/15/00 11/13/06 - 11/20/06 21 05/22/06 - 05/30/06 02/16/00 11/20/06 - 11/27/06 22 05/30/06 - 06/05/06 02/17/00 11/27/06 - 12/04/06 23 06/05/06 - 06/12/06 02/18/00 12/04/06 - 12/11/06 24 06/12/06 - 06/19/06 02/19/00 12/11/06 - 12/18/06 25 06/19/06 - 06/26/06 02/20/00 12/18/06 - 12/26/06 26 06/26/06 - 07/03/06 02/21/00 12/26/06 - 01/02/07 D-8

FIGURE D-1 COMPARISON OF MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES SPLIT BETWEEN ENV AND TBE, 2006 10 9 . . . . . . . . . . . . . .-IE _ NV_ ------------------------------------------. .. ... ... .. .... ... .... .. ....

/ \

I \

6 .. I

......... \5 .................................................................................................

6 . .. ..I .. .\ .\.............

A
..........................................................

I -- --

0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTH ENVIRONMENTAL INC. SOLUBLE AND INSOLUBLE FRACTIONS WERE COMBINED FOR TOTAL GROSS BETA COMPARISON.

D-9

FIGURE D-2 COMPARISON OF WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM LGS COLLOCATED LOCATIONS 11S1 AND 11S2, 2006

}o 50

-_ 11S2 -ENV

-*-I1S1 -TBE 4 0 .....................................................................................................

30 CL C.)

w. 20 10 0

1 4 7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO.

D-10

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2006 (PAGE 1 OF 3)

Identificaton Reported Known Ratio (c)

Month/Year Number Matrix Nudide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

March 2006 E4964-396 Milk Sr-89 pClL 91.5 99.2 0.92 A Sr-90 pCi/L 12.2 10.8 1.13 A E4965-396 Milk 1-131 pCi/L 74.4 78.0 0.95 A Ce-141 pCji/L 95.1 104 0.91 A Cr-51 pCi/L 278 280 0.99 A Cs-134 pQi/L 103 121 0.85 A Cs-1i37 pCi/L 87.6 88.8 0.99 A Co-58 pCi/L 93.9 105 0.89 A Mn-54 pCi/L 90.0 93.3 0.96 A Fe-59 pCi/L 83.0 86.6 0.96 A Zn-65 pCi/L 178 176 1.01 A Co-60 pC~i/L 118 128 0.92 A E4967-396 AP Ce-141 pai 89.9 74 1.21 W Cr-51 pai 253 200 1.27 W Cs-134 pa 71.5 86.1 0.83 A Cs-137 pCi 67.5 63.3 1.07 A Co-58 pa 79.7 74.6 1.07 A Mn-54 pa 74.9 67 1.12 A pa Fe-59 pa 75.5 61.8 1.22 W Zn-65 pal 146 126 1.16 A Co-60 91.2 91 1.00 A E4966-396 Charcoal 1-131 pCi 87.4 86.2 1.01 A June 2006 E5018-396 Milk Sr-89 pi/L 118 129 0.91 A Sr-90 pi/L 9.29 9.74 0.95 A E5019-396 Milk 1-131 49.9 63.2 0.79 W Ce-141 pCi/L 174 184 0.95 A Cr-51 pC, pCi/LlL 266 259 1.03 A Cs-134 pCi/L 111 127 0.88 A Cs-137 116 117 0.99 A Co-58 pCi/L 101 100 1.01 A Mn-54 pCi/L 144 146 0.98 A pi/L Fe-59 pCi/L 96.7 93.6 1.03 A Zn-65 pCi/L 182 185 0.98 A Co-60 126 129 0.98 A E5021-396 AP Ce-141 113 124 0.91 A p:li Cr-51 p:i 176 174 1.01 A Cs-134 p0 63.7 85.1 0.75 W Cs-1i37 p0 76.8 79.0 0.97 A Co-58 p0 63.1 67.4 0.94 A Mn-54 p0 102 99 1.04 A Fe-59 64.6 62.9 1.03 A Zn-65 p0i 131 125 1.05 A Co-60 81.6 86.5 0.94 A E5020-396 Charcoal 1-131 p10 65.4 65.9 0.99 A E-1

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2006 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

September 2006 E5120-396 Milk Sr-89 pCi/L 90.3 89.2 1.01 A Sr-90 pCi/L 11.6 12.4 0.94 A E5121-396 Milk 1-131 pCi/L 67.8 73.8 0.92 A Ce-141 pCi/L 85.0 86.0 0.99 A Cr-51 pCi/L 263 282 0.93 A Cs-1 34 pCi/L 74.7 85.0 0.88 A Cs-1 37 pCi/L 172 175 0.98 A Co-58 pCi/L 107 109 0.98 A Mn-54 pCi/L 110 113 0.98 A Fe-59 pCi/L 46.6 43.7 1.07 A Zn-65 pCi/L 144 145 0.99 A Co-60 pCi/L 127 134 0.95 A E5123-396 AP Ce-141 pCi 67.1 66.4 1.01 A Cr-51 pCi 223 217 1.03 A Cs-134 pCi 51.7 65.6 0.79 W Cs-1 37 pCi 134 135.0 0.99 A Co-58 pCi 84.8 84.3 1.01 A Mn-54 pCi 95.2 87 1.10 A Fe-59 pCi 41.6 33.7 1.23 W Zn-65 pCi 123 112 1.10 A Co-60 pCi 98.9 103 0.96 A Co-57 pCi 0.922 (1). NA NA E5122-396 Charcoal 1-131 pCi 77.7 90.7 0.86 A December 2006 E5172-396 Milk Sr-89 pCi/L 72.4 72.0 1.01 A Sr-90 pCi/L 7.05 5.90 1.19 A E5173-396 Milk 1-131 pCi/L 71.9 70.8 1.02 A Ce-141 pCi/L 268 294 0.91 A Cr-51 pCi/L 420 433 0.97 A Cs-1 34 pCi/L 128 147 0.87 A Cs-1 37 pCi/L 231 237 0.97 A Co-58 pCi/L 82.0 83.8 0.98 A Mn-54 pCi/L 113 111 1.02 A Fe-59 pCi/L 79.8 79.7 1.00 A Zn-65 pCi/L 170 164 1.04 A Co-60 pCi/L 265 281 0.94 A E5175-396 AP Ce-141 pCi 220 210 1.05 A Cr-51 pCi 343 309 1.11 A Cs-1 34 pCi 90.8 105 0.86 A Cs-1 37 pCi 185 169.0 1.09 A Co-58 pCi 65.0 59.7 1.09 A Mn-54 pCi 90.6 79 1.15 A Fe-59 pCi 70.7 56.7 1.25 W Zn-65 pCi 136 117 1.16 A Co-60 pCi 208 200 1.04 A E-2

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2006 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

December 2006 E5174-396 Charcoal 1-131 pCi 77.4 85.4 0.91 A (1) Impurity detected but not measured by Analytics.

(a) Teledyne Brown Engineeringreportedresult.

(b) The Analytics known value is equal to 100% of the parameterpresentin the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation.

(c) Ratio of Teledyne Brown Engineeringto Analytics results.

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable. Reported result falls within ratio limits of 0. 80-1.20.

W-Acceptable with warning. Reported result falls within 0. 70-0.80 or 1.20-1.30. N = Not Acceptable. Reported result falls outside the ratio limits of < 0. 70 and > 1.30.

E-3

TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2006 (PAGE 1 OF 1)

Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b) Control Limits Evaluation c)

May 2006 Rad 65 Water Sr-89 pCi/L 30.2 32.4 23.6- 41.1 A Sr-90 pCi/L 8.74 9.00 0.340-17.7 A Ba-1i33 pCi/L 10.9 10.0 1.34-18.7 A Cs- 134 pCi/L 39.7 43.4 34.7-52.1 A Cs-137 pCi/L 199 214 195 - 233 A Co-60 pCi/L ill 113.0 103- 123 A Zn-65 pCi/L 146 152 126- 178 A Gr-A pCi/L 22.9 21.3 12.1 -30.5 A Gr-B pCi/L 23.7 23.0 14.3-31.7 A Ra-226 pCi/L 2.64 3.02 2.23-3.81 A U-Nat pCi/L 74.9 69.1 57.1 - 81.1 A H-3 pCi/L 7950 8130 6720 - 9540 A Rad 65 Water 1-131 pCi/L 18.2 19.1 13.9-24.3 A November 2006 Rad 67 Water Sr-89 pCi/L 40.0 39.9 31.2- 48.6 A Sr-90 pCi/L 16.2 16.0 7.34-24.7 A Ba-133 pCi/L 65.0 70.2 58.1 -82.3 A Cs- 134 pCi/L 27.4 29.9 21.2- 38.6 A Cs-137 pCi/L 74.4 78.2 69.5-86.9 A Co-60 pCi/L 61.6 62.3 53.6- 71.0 A Zn-65 pCi/L 277 277 229- 325 A Gr-A pCi/L 23.3 28.7 16.3- 41.1 A Gr-B pCi/L 22.0 20.9 12.2- 29.6 A U-Nat pCi/L 3.18 3.20 0.00-8.40 A H-3 pCi/L 2930 3050 2430 - 3670 A Water 1-131 pCi/L 19.8 22.1 16.9- 27.3 A (a) Teledyne Brown Engineenng reportedresult.

(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetrnc and/or volumetric measurements made during standardpreparation.

(c) ERA evaluation:A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=checkfor Error. Reported result falls within the Control Limits and outside of the Warning Limit.

E-4

TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2006 (PAGE 1 OF 3)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

January 2006 06-MaWI 5 Water Am-241 Bq/L 1.29 1.30 0.91 -1.69 A Cs-1 34 Bq/L 79.2 95.1 66.57 - 123.63 A Cs-1 37 Bq/L -0.188 A Co-57 Bq/L 151 166.12 116.28 - 215.96 A Co-60 Bq/L 141 153.50 107.45- 199.55 A H-3 Bq/L 988 952.01 666.41 - 1237.61 A Fe-55 Bq/L 106.0 129.60 90.72 - 168.48 A Mn-54 Bq/L 297 315.00 220.50 - 409.50 A Ni-63 Bq/L 61.5 60.34 44.24 - 78.44 A Pu-238 Bq/L 0.961 0.91 0.64- 1.18 A Pu-239/240 Bq/L 0.00965 0.00710 (1) A Sr-90 Bq/L 12.6 13.16 9.2.1- 17.11 A Tc-99 Bq/L 22.5 23.38 16.37 - 30.39 A U-234/233 Bq/L 2.20 2.09 1.46-2.72 A U-238 Bq/L 2.23 2.17 1.52 - 2.82 A Zn-65 Bq/L 219 228.16 159.71 - 296.61 A 06-GrWl 5 Water Gr-A Bq/L 0.575 0.581 >0.0 - 1.162 A Gr-B Bq/L 1.52 1.13 0.56- 1.70 A 06-MaS15 Soil Am-241 Bq/kg 48.8 57.08 39.96 - 74.20 A Cs-1 34 Bq/kg 15.9 N(1)

Cs-1 37 Bq/kg 370 339.69 237.78 - 441.60 A Co-57 Bq/kg 667 656.29 459.40 - 853.18 A Co-60 Bq/kg 478 447.10 312.97 - 581.23 A Mn-54 Bq/kg 384 346.77 242.74 - 450.80 A Ni-63 Bq/kg 394 323.51 226.46 - 420.56 W K-40 Bq/kg 667 604 423 - 785 A Sr-90 Bq/kg 253 314.35 220.04 - 408.66 A Tc-99 Bq/kg 146 154.76 108.33 - 201.19 A Zn-65 Bq/kg 740 657.36 460.15 - 854.57 A 06-RdF15 AP Am-241 Bq/sample 0.0850 0.093 0.065 - 0.121 A Cs-1 34 Bq/sample 2.34 2.934 2.054 - 3.814 A Cs-1 37 Bq/sample 2.45 2.531 1.772 - 3.290 A Co-57 Bq/sample 3.87 4.096 2.867 - 5.325 A Co-60 Bq/sample 2.12 2.186 1.530 - 2.842 A Mn-54 Bq/sample 0.0206 A Pu-238 Bq/sample 0.0766 0.067 0.047 - 0.087 A Pu-239/240 Bq/sample 0.00520 0.00041 '(1) A Sr-90 Bq/sample 0.761 0.792 0.554 - 1.030 A U-234/233 Bq/sample 0.0217 0.020 0.014 - 0.026 A U-238 Bq/sample 0.0220 0.021 0.015 - 0.027 A Zn-65 Bq/sample 3.86 3.423 2.396 - 4.450 A 06-GrF15 AP Gr-A Bq/sample 0.257 0.361 >0.0 - 0.722 A Gr-B Bq/sample 0.398 0.481 0.241 - 0.722 A E-5

TABLE E-3 DOES MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2006 (PAGE 2 OF 3)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

January 2006 06-RdV1 5 Vegetation Am-241 Bqlsample 0.156 0.156 0.109 - 0.203 A Cs-134 Bq/sample 0.369 A Cs-137 Bqlsample 3.15 3.074 2.152 - 3.996 A Co-57 Bqlsample 10.1 8.578 6.005- 11.151 A Co-60 Bqlsample 4.69 4.520 3.164 - 5.876 A Mn-54 Bqlsample 6.53 6.247 4.373 - 8.121 A Pu-238 Bq/sample 0.183 0.137 0.096 - 0.178 N (2)

Pu-239/240 Bq/sample 0.111 0.164 0.115 - 0.213 N (2)

Sr-90 Bqfsample 2.22 1.561 1.093 - 2.029 N (2)

U-234/233 Bq/sample 0.208 0.208 0.146 - 0.270 A U-238 Bqlsample 0.176 0.216 0.151 - 0.281 A Zn-65 Bq/sample 10.5 9.798 6.859 - 12.737 A July 2006 06-MaW16 Water Am-241 Bq/L 2.09 2.31 1.62- 3.00 A Cs-134 Bq/L 99.8 112.82 78.98- 146.66 A Cs- 137 Bq/L 191 196.14 137.30 - 254.98 A Co-57 Bq/L 203 213.08 149.16 - 277.00 A Co-60 Bq/L 46.2 47.5 33.2-61.8 A H-3 Bq/L 471 428.85 300.20- 557.50 A Fe-55 Bq/L 173 165.4 115.8 - 215.0 A Ni-63 Bq/L 109 118.62 83.03- 154.21 A Pu-238 Bq/L 1.50 1.39 0.97- 1.81 A Pu-239/240 Bq/L 2.01 1.94 1.36-2.52 A Sr-90 Bq/L 13.7 15.69 10.98- 20.40 A Tc-99 Bq/L 29.0 27.15 19.00 - 35.29 A U-234/233 BqIL 2.19 2.15 1.50- 2.80 A U-238 Bq/L 2.25 2.22 1.55 -2.89 A Zn-65 Bq/L 178 176.37 123.46 - 229.28 A 06-GrW16 Water Gr-A Bq/L 1.52 1.033 >0.0 - 2.066 A Gr-B Bq/L 1.18 1.03 0.52-1.54 A 06-MaS16 Soil Am-241 Bq/kg 83.6 105.47 73.83-137.11 W Cs-134 Bq/kg 393 452.13 316.49 - 587.77 A Cs-137 Bq/kg 522 525.73 368.01 - 683.45 A Co-57 Bq/kg 636 676.33 473.43 - 879.23 A Co-60 Bq/kg 3.78 1.98 A (3)

Mn-54 Bq/kg 598 594.25 415.98- 772.52 A Ni-63 Bq/kg 571 627.3 470.6 - 874.0 A Pu-238 Bq/kg 71.2 82 57-107 A Pu-239240 Bq/Kg 0.487 0.93 A (3)

K-40 Bq/kg 615 604 423 - 785 A Sr-90 Bq/kg 178 223.3 156.3 - 290.3 W Tc-99 Bq/kg 175 218.01 152.61 - 283.41 *A U-234/233 Bq/kg 119 152.44 106.71 - 198.17 W U-238 Bq/kg 115 158.73 111.11 -206.35 W Zn-65 Bq/k~g 937 903.61 632.53- 1174.69 A E-6

TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2006 (PAGE 3 OF 3)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value(a) Value(b) Range Evaluation (c)

July 2006 06-RdF16 AP Am-241 Bq/sample 0.124 0.142 0.099-0.185 A Cs-134 Bq/sample 2.62 3.147 2.203 - 4.091 A Cs-137 Bq/sample 1.98 1.805 1.263 - 2.346 A Co-57 Bq/sample 2.65 2.582 1.807 - 3.357 A Co-60 Bq/sample 1.63 1.577 1.104 - 2.050 A Mn-54 Bq/sample 2.10 1.92 1.34-2.50 A Pu-238 Bq/sample 0.118 0.118 0.083-0.153 A Pu-239/240 Bq/sample 0.00822 NA A Sr-90 Bq/sample 0.549 0.62 0.43-0.81 A U-234/233 Bq/sample 0.140 0.134 0.094 - 0.174 A U-238 Bq/sample 0.136 0.139 0.097 - 0.181 A Zn-65 Bq/sample -0.163 NA A 06-GrF16 AP Gr-A Bq/sample 0.134 0.290 >0.0 - 0.580 A Gr-B Bq/sample 0.358 0.359 0.180 - 0.538 A (1) Falsepositive test (2) Evaluatedas a false positive by MAPEP although we consideredthe result a non-detect due to the peak not being identified by the gamma software. For Cs-134, MAPEP suggests the Bi-214 is not being differentiatedfrom the Cs-134 peak. See email attachedwith MAPEP results in Appendix A. NCR 06-07.

(3) Sr samples analyzed in tiplicate and one high result of 2.43 pCi/kg biased the submitted results on the high side. We were unable to determine the cause for the higher result. Since we do not analyze vegetation for isotpic Pu, no NCR was initiated for the Pu failure. MAPEP suggest pyrosulfate fusion preparationpriorto analysis for isotopic Pu in vegetation samples.

(4) Not detected, reported a statisticallyzero result. (Falsepositive test)

(a) Teledyne Brown Engineeringreportedresult.

(b) The MAPEP known value is equal to 100%/a of the parameterpresentin the standardas determined by gravimetricand/or volumetric measurementsmade during standardpreparation.

(c) DOE/MAPEPevaluation: A=acceptable,W=-acceptable with warning, N-not acceptable.

E-7

TABLE E-4 ERA(a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2006 (Page 1 of 2)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result (b) Result (c) Limits Acceptance STW-1 078 01/16/06 Sr-89 49.9 +/- 3.5 50.2 41.5 -58.9 Pass STW-1 078 01/16/06 Sr-90 31.5 +/- 1.5 30.7 22.0 - 39.4 Pass STW-1 079 01/16/06 Ba-133 86.5 +/- 4.1 95.0 78.6 -111.0 Pass STW-1 079 01/16/06 Co-60 96.3 +/- 4.1 95.3 86.6 -104.0 Pass STW-1 079 01/16/06 Cs-134 22.6 +/- 3.0 23.1 14.4 -31.8 Pass STW-1 079 01/16/06 Cs-1 37 109.0 +/- 5.9 111.0 101.0 - 121.0 Pass STW-1079 01/16/06 Zn-65 198.0 +/- 11.2 192.0 159.0 - 225.0 Pass STW-1 080 01/16/06 Gr. Alpha 10.8 +/- 1.4 9.6 1.0 - 18.3 Pass STW-1 080 01/16/06 Gr. Beta 56.9 +/- 1.9 61.9 44.6 - 79.2 Pass STW-1 081 01/16/06 Ra-226 4.3 +/- 0.4 4.6 3.4 -5.8 Pass STW-1 081 01/16/06 Ra-228 7.1 +/- 1.8 6.6 3.7 -9.5 Pass STW-1 081 01/16/06 Uranium 20.7 +/- 0.5 22.1 16.9 -27.3 Pass STW-1 088 04/10/06 Sr-89 29.0 +/- 1.8 32.4 23.7 -41.1 Pass STW-1 088 04/10/06 Sr-90 8.7 +/- 1.0 9.0 0.3 -17.7 Pass STW-1 089 04/10/06 Ba-1 33 10.3 +/- 0.4 10.0 1.3 -18.7 Pass STW-1 089 04/10/06 Co-60 114.0 +/- 2.8 113.0 103.0 - 123.0 Pass STW-1 089 04/10/06 Cs-134 41.9 + 1.4 43.4 34.7 -52.1 Pass STW-1 089 04/10/06 Cs-137 208.0 + 1.1 214.0 195.0 -233.0 Pass STW-1 089 04/10/06 Zn-65 154.0 +/- 0.8 152.0 126.0 -178.0 Pass STW-1 090 04/10/06 Gr. Alpha 13.4 + 1.1 21.3 12.1 -30.5 Pass STW-1 090 04/10/06 Gr. Beta 27.7 +/- 2.1 23.0 14.3 -31.7 Pass STW-1 091 04/10/06 1-131 22.0 +/- 0.3 19.1 13.9 -24.3 Pass STW-1 092 04/10/06 H-3 7960.0 + 57.0 8130.0 6720.0 - 9540.0 Pass STW-1 092 04/10/06 Ra-226 2.9 +0.4 3.0 2.2 -3.8 Pass STW-1 092 04/10/06 Ra-228 20.9 + 1.2 19.1 10.8 -27.4 Pass STW-1 092 04/10/06 Uranium 68.6 + 3.4 69.1 57.1 -81.1 Pass STW-1 094 07/10/06 Sr-89 15.9 + 0.7 19.7 11.0 -28.4 Pass STW-1 094 07/10/06 Sr-90 24.3 + 0.4 25.9 17.2 -34.6 Pass STW-1 095 07/10/06 Ba-133 94.9 +/- 8.9 88.1 72.9 - 103.0 Pass STW-1 095 07/10/06 Co-60 104.0 +/- 1.8 99.7 91.0 -108.0 Pass STW-1 095 07/10/06 Cs-134 48.7 + 1.3 54.1 45.4 -62.8 Pass STW-1 095 07/10/06 Cs-137 236.0 + 3.0 238.0 217.0 - 259.0 Pass STW-1 095 07/10/06 Zn-65 126.0 + 8.0 121.0 100.0 - 142.0 Pass STW-1 096 07/10/06 Gr. Alpha 10.9 + 1.0 10.0 1.3 -18.6 Pass STW-1 096 07/10/06 Gr. Beta 9.7 +/- 0.4 8.9 0.2 -17.5 Pass STW-1 097 07/10/06 Ra-226 11.0 +/- 0.5 10.7 7.9 -13.5 Pass STW-1 097 07/10/06 Ra-228 12.2 +/- 0.8 10.7 6.1 -15.3 Pass STW-1 097 07/10/06 Uranium 43.4 +/- 0.1 40.3 33.3 -47.3 Pass E-8

TABLE E-4 ERA(a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2006 (Page 2 of 2)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result (b) Result (c) Limits Acceptance STW-1 104 10/06/06 Sr-89 38.4 +/- 1.3 39.9 31.2 -45.7 Pass STW-1 104 10/06/06 Sr-90 15.5 +/- 0.5 16.0 7.3 -24.7 Pass STW-1 105 10/06/06 Ba-133 64.9 +/- 2.8 70.2 58.1 -82.3 Pass STW-1 105 10/06/06 Co-60 61.6 +/- 1.0 62.3 53.6 -71.0 Pass STW-1 105 10/06/06 Cs-134 29.0 +/- 0.9 29.9 21.2 -38.6 Pass STW-1 105 10/06/06 Cs-137 77.8 +/- 2.4 78.2 69.5 -86.9 Pass STW-1 105 10/06/06 Zn-65 293.0 +/- 2.4 277.0 229.0 - 325.0 Pass STW-1 106 10/06/06 Gr. Alpha 23.9 +/- 2.5 28.7 16.3 -41.1 Pass STW-1 106 10/06/06 Gr. Beta 23.7 +/- 1.4 20.9 12.2 -29.6 Pass STW-1107 (d) 10/06/06 1-131 28.4 +/- 1.2 22.1 16.9 -27.3 Fail STW-1 108 10/06/06 Ra-226 14.5 +/- 0.5 14.4 10.7 -18.1 Pass STW-1 108 10/06/06 Ra-228 6.6 +/- 0.4 5.9 3.3 -8.4 Pass STW-1 108 10/06/06 Uranium 2.9 +/- 0.1 3.2 0.0 - 8.4 Pass STW-1 109 10/06/06 H-3 3000.0 +/- 142.0 3050.0 2430.0 - 3670.0 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.

d The reported result was an average of three analyses, results ranged from 25.36 to 29.23 pCi/L.

A fourth analysis was performed, result of analysis, 24.89 pCi/L.

E-9

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) (a)

ENVIRONMENTAL, INC., 2006 (Page 1 of 3)

Concentration (b)

Known Control Lab Code (c) Date Analysis Laboratory result Activity Limits (d) Acceptance STVE-1082 01/01/06 Am-241 0.16 + 0.06 0.16 0.11 -0.20 Pass STVE-1082 01/01/06 Co-57 10.40 + 0.20 8.58 6.00 -11.15 Pass STVE-1082 01/01/06 Co-60 5.00 + 0.20 4.52 3.16 -5.88 Pass STVE-1082 (e) 01/01/06 Cs-134 < 0.20 0.00 Pass STVE-1082 01/01/06 Cs-137 3.40 + 0.20 3.07 2.15 -4.00 Pass STVE-1 082 01/01/06 Mn-54 6.90 + 0.20 6.25 4.37 -8.12 Pass STVE-1082 (f) 01/01/06 Pu-238 0.08 + 0.03 0.14 0.10 -0.18 Fail STVE-1 082 01/01/06 Pu-239/40 0.17 + 0.03 0.16 0.11 -0.21 Pass STVE-1 082 01/01/06 Sr-90 1.40 + 0.20 1.56 1.09 -2.03 Pass STVE-1 082 01/01/06 U-233/4 0.24 + 0.05 0.21 0.15 - 0.27 Pass STVE-1082 01/01/06 U-238 0.19 + 0.04 0.22 0.15 - 0.28 Pass STVE-1082 01/01/06 Zn-65 11.10 + 0.50 9.80 6.86 - 12.74 Pass STSO-1 083 01/01/06 Am-241 54.60 + 5.50 57.08 39.96 - 74.20 Pass STSO-1 083 01/01/06 Co-57 762.90 + 12.70 656.29 459.40 -853.18 Pass STSO-1 083 01/01/06 Co-60 504.90 + 3.10 447.10 312.97 -581.23 Pass STSO-1 083 (e) 01/01/06 Cs-134 < 1.70 0.00 Pass STSO-1 083 01/01/06 Cs-137 406.50 + 3.70 339.69 237.78 -441.60 Pass STSO-1 083 01/01/06 K-40 719.20 + 18.40 604.00 422.80 - 785.20 Pass STSO-1 083 01/01/06 Mn-54 415.60 + 4.80 346.77 242.74 - 450.80 Pass STSO-1 083 01/01/06 Ni-63 261.40 + 14.70 323.51 226.46 - 420.56 Pass STSO-1 083 01/01/06 Pu-238 14.60 + 2.90 61.15 42.81 -79.50 Fail STSO-1 083 01/01/06 Pu-239/40 14.60 + 2.40 45.85 32.09 - 59.61 Fail STSO-1 083 01/01/06 U-233/4 13.50 + 1.70 37.00 25.90 -48.10 Fail STSO-1 083 01/01/06 U-238 15.40 +/- 1.80 38.85 27.20 - 50.50 Fail STSO-1 083 01/01/06 Zn-65 783.40 +/- 7.00 657.36 460.15 -854.57 Pass STAP-1084 01/01/06 Gr. Alpha 0.26 +/- 0.02 0.36 0.00 -0.72 Pass STAP-1084 01/01/06 Gr. Beta 0.51 +/- 0.03 0.48 0.24 - 0.72 Pass STAP-1 085 01/01/06 Am-241 0.12 +/- 0.02 0.09 0.07 -0.12 Pass STAP-1 085 01/01/06 Co-57 4.32 +/- 0.10 4.10 2.87 - 5.32 Pass STAP-1 085 01/01/06 Co-60 2.24 +/- 0.16 2.19 1.53 - 2.84 Pass STAP-1085 01/01/06 Cs-134 2.96 +/- 0.19 2.93 2.05 - 3.81 Pass STAP-1085 01/01/06 Cs-137 2.64 +/- 0.20 2.53 .1.77 - 3.29 Pass STAP-1 085 (f) 01/01/06 Pu-238 0.03 +/- 0.01 0.07 0.05 - 0.09 Fail STAP-1 085 (e) 01/01/06 Pu-239/40 < 0.01 0.00 Pass STAP-1085 01/01/06 Sr-90 0.77 +/- 0.21 0.79 0.55 -1.03 Pass STAP-1085 01/01/06 U-233/4 0.03 +/- 0.01 0.02 0.01 - 0.03 Pass STAP-1085 01/01/06 U-238 0.02 +/- 0.01 0.02 0.01 - 0.03 Pass STAP-1085 01/01/06 Zn-65 3.94 +/- 0.44 3.42 2.40 - 4.45 Pass E -10

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) (a)

ENVIRONMENTAL, INC., 2006 (Page 2 of 3)

Concentration (b)

Known Control Lab Code (c) Date Analysis Laboratory result Activity Limits (d) Acceptance STW-1086 01/01/06 Am-241 1.29 + 0.05 1.30 0.91 -1.69 Pass STW-1086 01/01/06 Co-57 177.10 + 1.00 166.12 116.28 -215.96 Pass STW-1086 01/01/06 Co-60 158.30 + 1.00 153.50 107.45 -199.55 Pass STW-1086 01/01/06 Cs-134 96.40 + 1.50 95.10 66.57 -123.63 Pass STW-1086 (e) 01/01/06 Cs-137 < 0.80 0.00 Pass STW-1 086 01/01/06 Fe-55 102.50 + 18.10 129.60 90.72 -168.48 Pass STW-1086 01/01/06 H-3 956.60 + 16.50 952.01 666.41 -.1238.00 Pass STW-1 086 01/01/06 Mn-54 335.30 + 2.20 315.00 220.50 -409.50 Pass STW-1086 01/01/06 Ni-63 62.90 + 3.60 60.34 42.24 -78.44 Pass STW-1 086 01/01/06 Pu-238 0.96 + 0.07 0.91 0.70 -1.30 Pass STW-1086 (e) 01/01/06 Pu-239/40 < 0.20 0.00 Pass STW-1086 01/01/06 Sr-90 12.80 + 1.60 13.16 9.21 -17.11 Pass STW-1086 01/01/06 Tc-99 22.30 + 1.20 23.38 16.37 -30.39 Pass STW-1086 01/01/06 U-233/4 2.02 + 0.12 2.09 1.46 -2.72 Pass STW-1086 01/01/06 U-238 2.03 + 0.12 2.17 1.52 -2.82 Pass STW-1086 01/01/06 Zn-65 249.50 + 3.40 228.16 159.71 -296.61 Pass STW-1087 01/01/06 Gr. Alpha 0.59 + 0.10 0.58. 0.00 -1.16 Pass STW-1087 01/01/06 Gr. Beta 1.69 + 0.07 1.13 0.56 -1.70 Pass STVE-1 098 (e) 07/01/06 Co-57 <0.14 0.00 Pass STVE-1 098 (g) 07/01/06 Co-60 6.89 + 0.17 5.81 4.06 -7.55 Pass STVE-1098 07101/06 Cs-1 34 8.46 + 0.16 7.49 5.24 -9.73 Pass STVE-1 098 07/01/06 Cs-137 6.87 + 0.29 5.50 3.85 -7.14 Pass STVE-1098 07/01/06 Mn-54 10.36 + 0.29 8.35 5.85 -10.86 Pass STVE-1098 07/01/06 Zn-65 7.46 + 0.50 5.98 4.19 -7.78 Pass STSO-1 099 07/01/06 Am-241 130.00 + 11.60 105.47 73.83 -137.11 Pass STSO-1 099 07/01/06 Co-57 784.90 + 3.80 676.33 473.43 -879.23 Pass STSO-1 099 07/01/06 Co-60 2.10 + 0.90 1.98 0.00 -5.00 Pass STSO-1 099 07/01/06 Cs-134 500.70 + 7.40 452.13 316.49 -587.77 Pass STSO-1 099 07/01/06 Cs-137 624.20 + 4.90 525.73 368.01 -683.45 Pass STSO-1 099 07/01/06 K-40 701.30 + 3.40 604.00 423.00 -785.00 Pass STSO-1 099 07/01/06 Mn-54 699.20 + 5.20 594.25 415.98 -772.52 Pass STSO-1 099 07/01/06 Ni-63 614.40 + 17.10 672.30 470.60 -874.00 Pass.

STSO-1 099 07/01/06 Pu-238 79.90 + 5.80 82.00 57.00 -107.00 Pass STSO-1099 (e) 07/01/06 Pu-239/40 < 0.70 0.00 Pass STSO-1 099 07/01/06 U-233/4 150.50 + 5.90 152.44 106.71 -198.17 Pass STSO-1 099 07/01/06 U-238 151.60 + 6.00 158.73 111.11 -206.35 Pass STSO-1 099 07/01/06 Zn-65 1021.90 + 9.20 903.61 632.53 -1175.00 Pass E-11

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) (a)

ENVIRONMENTAL, INC., 2006 (Page 3 of 3)

Concentration U Known Control Lab Code (c) Date Analysis Laboratory result Activity Limits (d) Acceptance STAP-1100 07/01/06 Am-241 0.16 +/- 0.03 0.14 0.10 -0.19 Pass STAP-1100 07/01/06 Co-57 2.17 +/- 0.06 2.58 1.81 -3.36 Pass STAP-1100 07/01/06 Co-60 1.38 +/- 0.07 1.58 1.10 -2.05 Pass STAP-1100 07/01/06 Cs-134 2.52 +/- 0.13 3.15 2.20 -4.09 Pass STAP-1100 07/01/06 Cs-137 1.64 +/- 0.08 1.81 1.26 -2.35 Pass STAP-1100 07/01/06 Mn-54 1.76 +/- 0.18 1.92 1.34 -2.50 Pass STAP-1100 07/01/06 Pu-238 0.09 +/- 0.02 0.12 0.08 -0.15 Pass STAP-1100 07/01/06 Sr-90 0.66 +/- 0.21 0.62 0.43 -0.81 Pass STAP-1100 07/01/06 U-233/4 0.15 +/- 0.02 0.13 0.09 -0.17 Pass STAP-1100 07/01/06 U-238 0.13 +/- 0.02 0.14 0.10 -0.18 Pass STAP-1100 (e) 07/01/06 Zn-65 < 0.07 0.00 Pass STAP-1101 07/01/06 Gr. Alpha 0.08 +/- 0.03 0.29 0.00 -0.58 Pass STAP-1101 07/01/06 Gr. Beta 0.41 +/- 0.05 0.36 0.18 -0.54 Pass STW-1102 07/01/06 Gr. Alpha 0.76 +/- 0.07 1.03 0.00 -2.07 Pass STW-1102 07/01/06 Gr. Beta 1.23 +/- 0.06 1.03 0.52 -1.54 Pass STW-1103 07/01/06 Am-241 1.86 +/- 0.09 2.31 1.62 -3.00 Pass STW-1103 07/01/06 Co-57 224.10 +/- 1.20 213.08 149.16 -277.00 Pass STW-1103 07/01/06 Co-60 49.40 +/- 0.50 47.50 33.20 -61.80 Pass STW-1103 07/01/06 Cs-1 34 112.70 +/- 0.90 112.82 78.97 -146.66 Pass STW-1103 07/01/06 Cs-137 206.60 +/- 1.40 196.14 137.30 -254.98 Pass STW-1103 07/01/06 Fe-55 138.40 +/- 5.40 165.40 115.80 -215.00 Pass STW-1103 07/01/06 H-3 446.50 +/- 11.80 428.85 300.20 -557.50 Pass STW-1103 (e) 07/01/06 Mn-54 < 0.30 0.00 Pass STW-1103 07/01/06 Ni-63 116.70 +/- 3.60 118.62 83.03 -154.21 Pass STW-1103 07/01/06 Pu-238 1.27 +/- 0.07 1.39 0.97 -1.81 Pass STW-1103 07/01/06 Pu-239/40 1.67 +/- 0.08 1.94 1.36 -2.52 Pass STW-1103 07/01/06 Sr-90 16..40 +/- 1.90 15.69 10.98 -20.40 Pass STW-1103 07/01/06 Tc-99 29.40 +/- 1.10 27.15 19.00 -35.29 Pass STW-1103 07/01/06 U-233/4 1.97 +/- 0.08 2.15 1.50 -2.80 Pass STW-1103 07/01/06 U-238 1.97 +/- 0.08 2.22 1.55 -2.89 Pass STW-1103 07/01/06 Zn-65 192.50 +/- 2.40 176.37 123.46 -229.28 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.

e Included in the MAPEP as a false positive.

f Difficulties with the analyses for transuranics isotopes in solid samples (Filters, Soil and vegetation),

were attributed to incomplete dissolution of the samples. Soil samples were repeated, results of reanalyses:

Pu-238, 53.1 +/- 5.3 bq/kg. Pu-239/240, 42.4 +/- 4.7 bq/kg. U-233/4, 33.3 +/- 3.5 bq/kg. U-238, 35.5 +/- 3.6 bq/kg.

g The July vegetation sample was provided in two separate geometries, (100 ml. and 500 ml.). Results reported here used the 500 ml. standard size geometry. Results for the 100 ml. geometry showed approximately a 15% higher bias.

E - 12

APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2006 Prepared By Teledyne Brown Engineering Environmental Services Exel..

Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2007

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Table Of Contents I. Summary and Conclusions ........................................................................... 1 II. Introduction ................................................................................................ 3 A. Objectives of the RGPP .......................................................................... 3 B. Implementation of the Objectives ......................................................... 3 C. Program Description .......................................................................... 4 D. Characteristics of Tritium (H-3) ............................................................. 5 Ill. Program Description ................................................................................... 6 A. Sample Analysis .............................................................................. 6 B. Data Interpretation ................................................................................. 6 C. Background Analysis ......................................................................... 7

1. Background Concentrations of Tritium .......................................... 8 IV. Results and Discussion ............................................................................ 10 A. Groundwater Results ........................................................................ 10 B. Surface W ater Results .................................................................... 11 C. Drinking W ater W ell Survey ............................................................... 11 D. Summary of Results - Inter-laboratory Comparison Program ................... 12 E. Leaks, Spills, and Releases ................................... 12 F. Trends ......................................................................................... 12 G. Investigations ................................................................................ 12 H. Actions Taken ................................................................................ 13 V. References .............................................................................................. 13 i

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2006, Figures Figure 1 Phase 2 Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2006 Appendix B Data Tables Tables Table B-1.1 Concentrations of Tritium and Stronium-90 in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2006.

Table B-1.2 Concentrations of Gamma Emitters in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2006.

Table B-11.1 Concentrations of Tritium and Stronium-90 in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2006.

Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2006.

Hi

I. Summary and Conclusions This report on the Radiological Groundwater Protection Program (RGPP) conducted for the Limerick Generating Station (LGS) by Exelon Nuclear covers the period 01 January 2006 through 31 December 2006.

In 2006, Exelon instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of Limerick Generating Station. This evaluation involved numerous station personnel and contractor support personnel.

This is the first in a series of annual reports on the status of the RGPP conducted at LGS. This report covers groundwater and surface water samples, collected from the environment, both on and off station property in 2006. During that time period, 179 analyses were performed on 64 samples from 29 locations.

The monitoring was conducted in two phases. Phase 1 of the monitoring was part of a comprehensive study initiated by Exelon to determine whether groundwater or surface water at and in the vicinity of Limerick Generating Station had been adversely impacted by any releases of radionuclides.

Phase 1 was conducted by Conestoga Rovers and Associates (CRA) and the conclusions were made available to state and federal regulators as well as the public on an Exelon web site www. exeloncorp com/ourcompanies/powergen/nuclear/Tritium htm Phase 2 of the RGPP was conducted by Exelon corporate and station personnel to initiate follow up of Phase 1 and to begin long-term monitoring at groundwater and surface water locations selected during Phase 1. All analytical results from both the Phase 1 and Phase 2 monitoring are reported herein.

In assessing all the data gathered for this report, it was concluded that the operation of Limerick Generating Station had no adverse radiological impact on the environment offsite of LGS. There are no know active releases into the groundwater at Limerick Generating Station.

Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater or surface water samples. In the case of tritium, Exelon specified that it's laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation.

1-

Strontium-90 was not detected at a concentration greater than the LLD of 2.0 picoCuries per liter (pCi/L) in any of the groundwater or surface water samples tested.

Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 10 of 29 groundwater monitoring locations. The tritium concentrations ranged from 158 +/- 103 pCi/L to 4,360 +/- 494 pCi/L. Most of the tritium that was detected in groundwater at the Station is on the west side of the Turbine building. It is likely that the tritium has migrated from the Unit 1 Condensate Storage Tank and or the auxiliary heating steam pipe leak to the monitoring well. The dose via the drinking water pathway was calculated at 0.451 mrem to a child (total body), which was 7.52% of the 10 CFR 50, Appendix I dose limit. All results for Sr-90 and gamma emitting nuclides were less than MDC.

II. Introduction The Limerick Generating Station (LGS), consisting of two 3458 MWt boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No. 1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL to the western site boundary. r This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2006.

A. Objective of the RGPP The long-term objectives of the RGPP are as follows:

1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.
2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.
3. Perform routine water sampling and radiological analysis of water from selected locations.
4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.
5. Regularly assess analytical results to identify adverse trends.
6. Take necessary corrective actions to protect groundwater resources.

B. Implementation of the Objectives The objectives identified have been implemented at Limerick Generating Station as discussed below:

1. Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Connestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators as well as the public on an Exelon web site in station specific reports.

www*

wexeloncorp com/nourcompanies/powergen/nuclear/Tritium.htm

2. The Limerick Generating Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.
3. Limerick Generating Station will continue to perform routine sampling and radiological analysis of water from selected locations.
4. Limerick Generating Station has implemented new procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner.
5. Limerick Generating Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.

C. Program Description Samples for the LGS RGPP Phase 1' were collected for Exelon Nuclear by Conestoga Rovers and Associates (CRA) and samples for Phase 2 were collected by on-site personnel and Normandeau Associates, RMC Environmental Services Division (RMC). This section describes the general collection methods used to obtain environmental samples for the LGS RGPP in 2006. Sample locations can be found in Table A-i, Appendix A.

1. Sample Collection Groundwater and Surface Water Samples of water were collected, managed, transported and analyzed in accordance with approved procedures following EPA methods. Both groundwater and surface water were collected. Sample locations, sample collection frequencies and analytical frequencies were controlled in accordance with approved station procedures. Contractor and/or station personnel were trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories were subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits.

Station personnel reviewed and evaluated all analytical data deliverables as data were received.

Analytical data results were reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to hydrogeologic conditions.

D. Characteristics of Tritium (H-3)

Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen. The most common form of tritium is tritium oxide, which is also called "tritiated water." The chemical properties of tritium are essentially those of ordinary hydrogen.

Tritiated water behaves the same as ordinary water in both the environment and the body. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.

Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-1 0 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.

Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.

Ill. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Limerick Generating Station RGPP in 2006.

In order to achieve the stated objectives, the current program includes the following analyses:

1. Concentrations of gamma emitters in groundwater and surface water.
2. Concentrations of strontium in groundwater and surface water.
3. Concentrations of tritium in groundwater and surface water.

B. Data Interpretation The radiological data collected prior to Limerick Generating Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Limerick Generating Station was considered operational at initial criticality.

Several factors were important in the interpretation of the data:

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criterion for the presence of activity. All analyses were designed to achieve the required OCGS detection capabilities for environmental sample analysis.

The minimum detectable concentration (MDC) is defined above with the exception that the measurement is an after the fact estimate of the presence of activity.

2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.

Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of a measurement created by statistical process (counting error) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated. Exelon reports the TPU by following the result with plus or minus +/- the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.

Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the AREOR.

C. Background Analysis A pre-operational radiological environmental monitoring program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, aquatic life, and foodstuffs. The results of the monitoring were detailed in the report entitled, Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.

The pre-operational REMP contained analytical results from samples collected from both surface water and groundwater.

Monthly surface water sampling began in 1982, and the samples were analyzed for tritium as well as other radioactive analytes.

During the preoperational program tritium was detected at a maximum concentration of 420 pCi/L, indicating that these preoperational results were from nuclear weapons testing and are radioactively decaying as predicted. Gamma isotopic results from the preoperational program were all less than or at the minimum detectable concentration (MDC) level.

1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others. Additional detail may be found by consulting references.
a. Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium.

Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.

b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected world wide from 1960 to 2006. RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons.

Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time. Tritium concentrations in have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above. Water from previous years was naturally captured in groundwater. As a result, some well water sources today are affected by the surface water from the 1960s that contained elevated tritium activity.

c. Surface Water Data Tritium concentrations are routinely measured in the Schuylkill and Delaware Rivers. Pennsylvania surface water data are typically less than 100 pCi/L.

The USEPA RadNet surface water data typically has a reported 'Combined Standard Uncertainty' of 35 to 50 pCi/L.

According to USEPA, this corresponds to a +/-70 to 100 pCi/L 95% confidence bound on each given measurement.

Therefore, the typical background data provided may be subject to measurement uncertainty of approximately +/- 70 to 100 pCi/L.

The radio-analytical laboratory is counting tritium results to an Exelon specified LLD of 200 pCi/L. Typically, the lowest positive measurement will be reported within a range of 40 -

240 pCi/L or 140 +/- 100 pCi/L. Clearly, these sample results cannot be distinguished as different from background at this concentration.

IV. Results and Discussion Gamma spectroscopy results for groundwater and surface water sample were reported for twelve nuclides (Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140 and La-140).

A. Groundwater Results Samples were collected from onsite wells throughout the year in accordance with the station radiological groundwater protection program.

Analytical results and anomalies are discussed below.

Tritium Samples from 16 locations were analyzed for tritium activity (Table B-I. 1, Appendix B). Tritium values ranged from <165 to 4,360 pCi/L. Well P-12 had the highest value of 4,360 pCi/L. After the results from well P-12 were confirmed well MW-LR-9 was dug directly over P-12 to the aquifer depth. Results from well MW-LR-9 ranged from <171 to 1,500 pCi/L. It was likely that tritium had migrated from the Unit 1 Condensate Storage Tank and or the auxiliary heating steam pipe leak to monitoring wells P-12 and MW-LR-9. The tritium migration pathway could be directly from the Unit 1 Condensate Storage Tank dike through bedrock fractures to P-12 and MW-LR-9. However, a more likely pathway is from the Unit 1 Condensate Storage Tank dike and or the auxiliary heating steam pipe leak through bedrock fractures to the drain system around the power block and into the Power Block Foundation Sump. From the drain system, the tritiated water could then migrate through bedrock fractures to P-12 and MW-LR-9. No other wells showed any elevated tritium results indicated that this contamination was localized to wells P-12 and MW-LR-

9. The dose via the drinking water pathway was calculated at 0.451 mrem to a child (total body), which was 7.52% of the 10 CFR 50, Appendix I dose limit.

No Sr-90 activity was detected in any of the ground water samples analyzed (Table B-I. 1, Appendix B).

Gamma Emitters Potassium-40 was detected in four of 38 samples. The concentrations ranged from 58 pCi/Liter to 119 pCi/Liter. No other gamma emitting nuclides were detected (Table B-I.2, Appendix B).

B. Surface Water Results In accordance with the Station's radiological groundwater protection program surface water samples were collected from streams that transverses the site, as well as, from other water bodies that could influence the tritium concentration at Limerick. Analytical results and anomalies are discussed below.

Tritium Samples from 13 locations were analyzed for tritium activity (Table B-1.3, Appendix B). Tritium values ranged from < 141 to 2,020 pCi/L The Foundation Power Block Sump (FPBS) had the highest value of 2,020 pCi/L. The FPBS is located in the general area of wells P-12 and MW-LR-9.

Strontium No Sr-90 activity was detected in any of surface water samples analyzed (Table B-1.3, Appendix B).

Gamma Emitters No gamma emitting nuclides were detected in any of the surface water samples analyzed (Table B-1.4, Appendix B).

C. Drinking Water Well Survey A drinking water well survey was conducted during the summer 2006 by CRA (CRA 2006) around the Limerick Generating Station. CRA reviewed the Pennsylvania Groundwater Information System database to identify wells within a 1-mile radius from the center of the Station. Forty-six domestic withdrawal wells, two industrial wells, two commercial wells, and one institutional well were identified within the specified radius. The well depths range from 78 to 345 feet bgs, and they yield between 8 and 100 gallons per minute (gpm). All wells are completed in the Brunswick Formation.

The Station has one potable supply well and one fire water well. The potable supply well is constructed as an open-rock borehole.

Groundwater was measured at a depth 102 feet bgs during a well pump replacement in 2004 (personal communication with Station, 2006). The pump was placed at a depth of approximately 294 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located approximately 175 feet east of the Reactor Building. The Station estimates that the well is pumped at approximately 2 gpm. The fire water well is constructed as an open-rock borehole. Groundwater was encountered at 121 feet bgs during a well pump replacement in 2004. The well pump was placed at a depth of approximately 399 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located approximately 500 feet east of the cooling towers. The well is used only in an emergency fire situation; therefore, water use is estimated to be zero.

D. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.

E. Leaks, Spills, and Releases The Station records inadvertent release of radioactive liquids in accordance with 10 CFR 50.75)g). As part of the fleet wide assessment, a third party environmental engineering firm was contracted to evaluate historic releases, and determine if a potential pathway to the environment existed. Those releases that were determined to have potentially impacted groundwater were subsequently investigated as part of the fleet wide assessment. The hydrogeologic investigation determined that there is currently one radiological impacts to groundwater that is limited to the LGS site protected area boundary.

F. Trends No trends have been identified.

G. Investigations Conclusions from the Phase 1 report have been made available to state and federal regulators and to the public. Currently no investigations are on going.

H. Actions Taken

1. Compensatory Actions There have been no station events requiring compensatory actions at the Limerick Generating Station.
2. Installation of Monitoring Wells After phase 1 was completed two additional wells were added to the program. Wells MW-LR-8 and MW-LR-9 were drilled near the Unit 1 condensate storage tank dike to 'monitor groundwater tritium levels in that area. No new wells were required to be installed as a result of the phase 2 study.
3. Actions to Recover/Reverse Plumes No actions were required to recover or reverse groundwater plumes.

V. References

1. Conestoga Rovers and Associates, Fleetwide Assessment, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No. 045136(18), September 2006
2. Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.

Intentionally Left Blank APPENDIX A LOCATION DESIGNATION

TABLE A-1: Radiological Groundwater Protection Program - Sampling locations for the Limerick Generating Station, 2006 I nfafinn Tii,r* rlieft2nf- QfIld phnaa J- V J-MW-LR-1 Monitoring Well Onsite 1,2 MW-LR-2 Monitoring Well Onsite 1,2 MW-LR-3 Monitoring Well Onsite 1,2 MW-LR-4 Monitoring Well Onsite 1,2 MW-LR-5 Monitoring Well Onsite 1,2 MW-LR-6 Monitoring Well Onsite 1,2 MW-LR-7 Monitoring Well Onsite 1,2 MW-LR-8 Monitoring Well Onsite 1,2 MW-LR-9 Monitoring Well Onsite 2 P1l Monitoring Well Onsite 2 P12 Monitoring Well Onsite 1 P14 Monitoring Well Onsite 1,2 P16 Monitoring Well Onsite 1,2 P17 Monitoring Well Onsite 1,2 P3 Monitoring Well Onsite 1,2 SP22 Monitoring Well Onsite 1,2 SW-LR-1 Surface Water Offsite 1,2 SW-LR-2 Surface Water Offsite 1 SW-LR-3 Surface Water Offsite 1 SW-LR-4 Surface Water Offsite 1 SW-LR-5 Surface Water Offsite 1 SW-LR-6 Surface Water Offsite 1 SW-LR-7 Surface Water Onsite 1 SW-LR-8 Surface Water Onsite 1,2 SW-LR-9 Surface Water Onsite 1,2 POWER BLOCK SUMP Surface Water Onsite 1 STILL CREEK Surface Water Offsite 1 BRADSHAW RESERVE Surface Water Offsite 1 WADESVILLE MINE Surface Water Offsite 1 A-1

1 Mile Radius

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C' /

N NNW

, NE

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WNWi/

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w!

WSW N N

0 500 1,000 1,500 2,000 Feet Figure 1 Phase 2 Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2006 A-2

APPENDIX B DATA TABLES

TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONIUM-90 IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION H-3 SR-90 STC DATE MW-LR-1 05/17/06 183 < 0.72 MW-LR-1 10/17/06 181 < 0.91 MW-LR-2 05/18/06 184 0.9 MW-LR-2 DUP 05/18/06 169 1.41 MW-LR-2 10/16/06 181 1.35 MW-LR-2 10/17/06 185 0.92 MW-LR-3 05/18/06 170 < 1.18 MW-LR-3 10/18/06 180 < 1.33 MW-LR-4 05/19/06 222 +/- 118 < 0.8 MW-LR-4 10/17/06 < 185 * < 1.4 MW-LR-5 05/19/06 305 +/- 121 0.79 MW-LR-5 10/18/06 < 183 1.11 MW-LR-5 10/18/06 236  ::1 118* 1.49 MW-LR-5 10/18/06 275 +/-1 137* 1.42 MW-LR-5 10/18/06 247 +/- 118*

MW-LR-5 10/18/06 209 +/- 129*

MW-LR-6 05/17/06 182 1.35 MW-LR-6 10/16/06 180 1.35 MW-LR-6 10/17/06 175 1.34 MW-LR-7 05/18/06 166 1.16 MW-LR-7 10/16/06 181 1.49 MW-LR-7 10/18/06 167 1.47 MW-LR-8 06/28/06 184 +/- 116 MW-LR-8 07/07/06 244 +/- 116*

MW-LR-8 08/16/06 246 + 124* < 1.56 MW-LR-8 10/18/06 < 180 < 1.37

  • INDICATES DISTILLED ANALYSIS B-1

TABLE B-1.1 CONCENTRATIONS OF TRITIUM AND STRONIUM-90 IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE H-3 SR-90 MW-LR-9 08/16/06 1500 +/- 210* 1.24 MW-LR-9 10/19/06 < 171 1.33 MW-LR-9 10/19/06 238 +/- 120* 1.36 MW-LR-9 10/19/06 < 172 MW-LR-9 10/19/06 < 180 P1l 05/18/06 < 184 1.35 Pll 10/17/06 204 +/- 118* 1.48

.Pll 10/17/06 < 187

  • 0.81 P11 DUP 05/18/06 < 185 P12 05/18/06 4360 +/- 494 1.3 P12 05/18/06 4350 +/- 199 P14 05/18/06 185 0.89 P14 10/17/06 180 1.36 P16 05/18/06 < 182 < 0.94 P17 05/17/06 < 183 < 1.37 P17 10/18/06 < 174 < 1.48 P3 05/18/06 170 1.12 P3 10/19/06 178 1.46 SP22 05/19/06 165 0.55 SP22 10/17/06 185
  • 1.4
  • INDICATES DISTILLED ANALYSIS B-2

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION STC DATE BE-7 K-40 MN-54 CO-58 FE-59 CO-S0 ZN-55 NB*E ZR-95 1-131 CS-12L C~-127 RA-lifl I A..lAfl MW-LR-1 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 05/17/06 39 <3 <3 <6 <3 < 10 <4 <:5 <4 <6 <3 <12 <4 MW-LR-1 10/17/06 < 37 33 <4 <5 <9 <9

<6 < 10 <5 < 12 <4 <4 <26 <7 MW-LR-2 05/18/06 < 41 < 43 5 <5 <9 <5 < 16 <6 <9 <8 <8 <5 22 7 MW-LR-2 10/16/06 < 43 58 +/- 46 5 <5 < 10 <6 <9 <6 <9 < 14 <4 <5 30 12 MW-LR-2 10/17/06 < 33 < 61 3 <3 <7 <3 <6 <4 <6 <9 <3 <4 23 8 MW-LR-2 DUP 05/18/06 < 29 < 31 3 <3 < 6 <3 < 12 <4 <6 <5 <7 <4 14 5 MW-LR-3 05/18/06 < 45 < 56 <5 <6 <11 <6 <16 <6 <9 <8 <8 <6 <22 <8 MW-LR-3 10/18/06 < 51 < 52 <5 <5 <11 <4 <11 <6 <9 <14 <4 <5 <36 <11 MW-LR-4 05/19/06 < 45 < 56 <6 <5 <12 <5 <14 <6 <9 <8 <6 <5 <24 < 9 MW-LR-4 10/17/06 < 39 < 85 <4 <4 <8 <4 <8 <4 <7 <12 <4 <4 < 28 < 11 MW-LR-5 05/19/06 50 72 6 6 11 6 22 7 9 9 10 6 24 8 MW-LR-5 10/18/06 48 74 4 4 8 5 10 5 8 14 4 5 30 12 MW-LR-5 10/18/06- 40 99 4 4 7 4 8 5 8 15 4 4 33 10 MW-LR-5 10/18/06 38 42 5 5 11 7 8 5 9 15 4 4 32 11 MW-LR-6 05/17/06 27 < 50 3 3 6 4 -9 4 6 4 5 4 13 5 MW-LR-6 10/16/06 49 < 50 4 5 14 5 11 6 9 16 4 5 35 9 MW-LR-6 10/17/06 43 119 +/- 61 5 6 11 7 10 5 10 16 6 6 35 12 MW-LR-7 05/18/06 < 29 < 49 <3 <3 <7 <3 <12 <4 <6 <5 <6 <4 <15 <5 MW-LR-7 10/16/06 < 20 < 18 <2 <2 <5 <3 <4 <2 <4 <7 <2 <2 <15 <5 MW-LR-7 10/18/06 < 45 < 93 <5 <5 <12 <7 <10 <6 <9 <14 <5 <6 <31 <8 B-3

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS INWELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION 2006 RESULTS INUNITS OF PCI/UTER +/- 2 SIGMA STC DATE BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS4-34 CS-137 BA-140 LA-140 ZR-95 1-131 MW-LR-8 08/16/06 <45 <62 <6 <6 < 13 <7 < 10 <7 <10 <7 <5 <6 < 25 <7 MW-LR-8 10/18/06 <32 < 29 <3 <3 <8 <3 <6 <4 <6 < 12 <3 <3 <26 <6 MW-LR-9 08/16/06 <39 61 +/- 55 <5 <5 < 10 <4 <8 <6 <7 <5 <4 <5 < 17 <6 MW-LR-9 10/19/06 <38 < 87 <4 <4 < 12 <5 <7 <5 <9 < 14 <4 <5 < 31 <9.

MW-LR-9 10/19/06 <35 < 79 <3 <4 <9 <4 <5 <4 <7 < 12 <4 <4 < 27 <7 P1l 05/18/06 <48 < 48 <5 <5 < 11 <6 < 15 <7 <9 < 8 <7 <6 <23 <7 P1l 10/17/06 <43 79 +/- 49 <5 <4 < 11 <4 <10 <5 <8 < 16 <4 <4 <29 < 14 P11 DUP 05/18/06 <43 < 52 <5 <5 < 10 <5 < 16 <5 <9 <8 <8 <6 <22 <8 P12 05/18/06 < 39 < 76 <5 <5 <8 <4 <14 <5 <8 <7 <7 <5 <21 <6 P14 05/18/06 < 46 < 56 <5 <5 <10 <6 <13 <6 <9 <8 <6 <6 <25 <8 P14 10/17/06 < 43 < 116 <4 <5 <10 <3 <10 <5 <10 <16 <4 <5 <33 <12 P16 05/18/06 < 47 < 50 <5 <6 <13 <6 <16 <6 <9 <9 <7 <6 <22 <9 P17 05/17/06 < 33 < 62 <4 <4 <8 <4 <9 <4 <7 <5 <5 <4 <16 <5 P17 10/18/06 < 52 < 97 <5 <5 <10 <5 <8 <6 <10 <13 <5 <5 <34 <12 P3 05/18/06 < 38 < 46 <5 <5 <9 <4 <13 <5 <8 <6 <6 <5 <20 <7 P3 10/19/06 < 42 < 40 <4 <5 <10 <5 <10 <5 <7 <12 <4 <4 <29 <10 SP22 05/19/06 < 53 < 52 <5 <6 <12 <6 <14 <6 <10 <9 <7 <6 <27 <9 SP22 10/17/06 < 42 < 74 <4 <5 <11 <5 <9 <6 <8 <16 <4 <4 <34 <13 B-4

TABLE B-Il.1 CONCENTRATIONS OF TRITIUM AND STRONIUM-90 IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION 2006 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION LOCATION DATE H-3 SR-90 SW-LR-1 05/22/06 < 150 < 1.5 SW-LR-1 10/16/06 < 187 * < 1.59 SW-LR-2 05/22/06 < 152 < 1.46 SW-LR-3 05/22/06 < 154 < 1.59 SW-LR-4 05/22/06 158 + 103 < 1.49 SW-LR-5 05/22/06 < 141 < 1.23 SW-LR-5 DUP 05/22/06 < 152 < 1.89 SW-LR-6 05/22/06 184 + 108 < 1.35 SW-LR-7 05/22/06 < 150 < 1.84 SW-LR-8 05/19/06 523 + 137 < 0.7 SW-LR-8 10/16/06 < 176 * < 1.26 SW-LR-9 05/19/06 < 166 < 1.15 SW-LR-9 10/16/06 < 183 * < 1.5 SW-LR-9 DUP 05/19/06 < 172 < 0.89 BRADSHAW RESERVOIR 05/31/06 < 166 < 1.73 POWER BLOCK SUMP 05/31/06 2020 + 154 < 1.83 STILL CREEK 05/31/06 < 165 < 1.63 WADESVILLE MINE 05/31/06 < 165 < 1.28

  • INDICATES DISTILLED ANALYSIS B-5

TABLE B141.2 CONCENTRATIONS OF GAMMA EMITTERS INSURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE BE-7 K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 C~S-137 BA-140 LA-140 SW-LR-1 05/22/06 <16 < 19 <2 <2 <4 <2 <5 <2 <3 <3 <2 <2 <9 <3 SW-LR-1 10116106 < 37 < 76 <4 <4 <8 <4 <8 <4 <7 <12 <4 <4 < 27 <6 SW-LR-2 05/22/06 < 48 < 47 <5 <5 <9 <5 < 11 <5 <10 <9 <6 <5 < 23 <8 SW-LR-3 05/22/06 < 30 < 33 <3 <3 <7 <4 <7 <3 <6 <6 <4 <3 < 17 <5 SW-LR-4 05/22/06 < 30 < 33 <3 <4 <7 <3 <8 <4 <6 <6 <4 <4 < 16 <5 SW-LR-5 05/22/06 < 43 < 46 <5 <5 <9 <5 < 10 <5 <9 <9 <5 <5 < 23 <8 SW-LR-5 DUP 05/22/06 <34 < 65 <4 <4 <8 <4 <9 <4 <7 <7 <5 <4 < 20 <6 SW-LR-6 05/22/06 < 43 < 45 <6 <5 <11 <5 < 14 <6 <9 <10 <6 <5 <26 <8 SW-LR-7 05/22/06 < 48 < 87 <5 <5 <10 <5 < 12 <5 <9 <10 <5 <5 < 25 <9 SW-LR-8 05/19/06 < 45 < 49 <4 <5 <9 <5 < 11 <5 <8 <8 <5 <5 <22 <7 SW-LR-8 10/16/06 < 40 < 117 <4 <4 <9 <3 <8 <4 <10 <16 <4 <4 < 35 <11 SW-LR-9 05/19/06 <51 < 50 <6 <6 <13 <6 < 12 <6 <10 <9 "<5 <7 < 27 <8 SW-LR-9 10/16/06 < 61 < 57 <6 <7 <15 <6 <14 <7 <8 <22 <6 <7 < 53 < 11 SW-LR-9 DUP 05/19/06 < 39 < 42 <5 <5 <10 <5 <10 <5 <8 <7 <5 <5 < 21 <7 BRADSHAW 05/31/06 <56 < 53 <5 <6 < 12 <5 <11 <6 <10 < 20 <6 <6 < 40 <12 RESERVOIR POWER BLOCK 05/31/06 < 49 < 47 < 5 <5 < 12 < 5 < 12 < 5 < 10 < 16 < 6 <5 <37 <12 SUMP STILL CREEK 05/31/06 < 49 < 46 < 5 <5 < 12 <5 <11 <6 <9 <17 <6 <5 <38 <12 WADESVILLE MINE 05/31/06 < 47 < 40 < 5 <5 < 11 <4 <10 <5 <9 <16 <5 <5 <35 <11 B -6

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