SVPLTR 11-0022, Submittal of 2010 Annual Radiological Environmental Operating Report: Difference between revisions
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{{#Wiki_filter: | {{#Wiki_filter:Exelon Generation Company, LLC www.exeloncorp.com Exelkn Dresden Nuclear Power Station Nuclear 65oo North Dresden Road MorTis, IL60450-9765 May 13, 2011 SVPLTR # 11-0022 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 1, 2;-nd 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-010, 50-237, and 50-249 | ||
==Subject:== | ==Subject:== | ||
Dresden Nuclear Power Station 2010 Annual Radiological Environmental Operating Report Enclosed is the Exelon Dresden Nuclear Power Station 2010 Annual Radiological Environmental Operating Report, submitted in accordance with Section 6.9.A.3 of the Unit 1 Dresden Nuclear Power Station Technical Specifications and Section 5.6.2, "Annual Radiological Environmental Operating Report," of the Units 2 and 3 Technical Specifications. | Dresden Nuclear Power Station 2010 Annual Radiological Environmental Operating Report Enclosed is the Exelon Dresden Nuclear Power Station 2010 Annual Radiological Environmental Operating Report, submitted in accordance with Section 6.9.A.3 of the Unit 1 Dresden Nuclear Power Station Technical Specifications and Section 5.6.2, "Annual Radiological Environmental Operating Report," of the Units 2 and 3 Technical Specifications. | ||
This report provides the results of the radiological environmental monitoring program for the 2010 calendar year. | |||
In addition, Appendix F of the report contains the results of groundwater monitoring conducted in accordance with Exelon's Radiological Groundwater Protection Program, which is a voluntary program implemented in 2006. This information is being reported in accordance with a nuclear industry initiative. | |||
Should you have any questions concerning this letter, please contact Dennis Leggett, Regulatory Assurance Manager, at (815) 416-2800. | |||
Respectfully, Shane Marik Acting Site Vice President Dresden Nuclear Power Station Attachment - Annual Radiological Environmental Operating Report cc: Regional Administrator - NRC Region III NRC Senior Resident - Dresden Nuclear Power Station | |||
Docket No: 50- | |||
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 There were no program changes for 2010.IV. Results and Discussion A. Aquatic Environment | E. Program Changes There were no program changes for 2010. | ||
: 1. Surface Water Samples were composited or taken weekly and composited for analysis at three locations (D-21, D-52, and D-57). Of these locations only D-21 located downstream, could be affected by Dresden's effluent releases. | IV. Results and Discussion A. Aquatic Environment | ||
: 1. Surface Water Samples were composited or taken weekly and composited for analysis at three locations (D-21, D-52, and D-57). Of these locations only D-21 located downstream, could be affected by Dresden's effluent releases. The following analyses were performed: | |||
Gross Beta Monthly composites from all locations were analyzed for concentrations of gross beta (Table C-1.1, Appendix C). The values ranged from <3.8 to 15.7 pCi/I. Concentrations detected were consistent with those detected in previous years (Figures C-1, C-2, and C-3, Appendix C). | |||
Tritium Quarterly composites from all locations were analyzed for tritium activity (Table C-1.2, Appendix C). The indicator values ranged from <159 to 246 pCi/L. Control values ranged from <157 to 1,030 pCi/L. Concentrations detected were consistent with those detected in previous years (Figures C-4, C-5, and C-6, Appendix C). | |||
Gamma Spectrometry Monthly composites from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No nuclides were detected, and all required LLDs were met. | |||
: 2. Ground Water Quarterly or more frequent grab samples were collected at two locations (D-23 and D-35). These locations could be affected by Dresden's effluent releases and by sources upstream on the Kankakee River. The following analyses were performed: | |||
Tritium All samples were analyzed for tritium activity (Table C-11.1, Appendix C). D-35 values ranged from <160 to <178 pCi/L. D-23 values ranged from 216 to 400 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-7, Appendix C). | |||
Gamma Spectrometrv All samples were analyzed for gamma emitting nuclides (Table C-11.2, Appendix C). No nuclides were detected, and all required LLDs were met. | |||
: 3. Fish Fish samples comprised of channel catfish, largemouth bass, common carp and freshwater drum were collected at two locations (D-28 and D-46) semiannually. Location D-28 could be affected by Dresden'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-111.1, Appendix C). | |||
Naturally occurring K-40 was found at all stations and ranged from 2,980 to 4,640 pCi/kg wet. No fission or activation products were detected. | |||
: 4. Sediment Aquatic sediment samples were collected at one location (D-27) semiannually. This downstream location could be affected by Dresden's effluent releases. The following analysis was performed: | |||
Gamma Spectrometry Sediment samples from the location were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). Cesium-137 was detected in one sample at a concentration of 57 pCi/kg dry. The activity detected was consistent with those detected in previous years and is likely due to fallout from above-ground nuclear weapons testing. No other fission or activation products were detected. | |||
B. Atmospheric Environment | |||
: 1. Airborne | |||
: a. Air Particulates Continuous air particulate samples were collected from 13 locations on a weekly basis. The 13 locations were separated into four groups: On-site samplers (D-01, D-02, D-03), Near-field samplers within 4 km of the site (D-04, D-07, D-45, D-53 and D-56), Far-field samplers between 4 and 10 km from the site (D-08, D-10, D-14 and D-55) and the Control sampler between 10 and 30 km from the site (D-12). | |||
The following analyses were performed: | The following analyses were performed: | ||
Gross 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 four groups aid in determining the effects, if any, resulting from the operation of DNPS. The results from the On-Site locations ranged from 6 to 47 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. The results from the Near-Field locations ranged from 6 to 40 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. The results from the Far-Field locations ranged from 6 to 40 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3. The results from the Control location ranged from 8 to 40 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3. Comparison of the 2010 air particulate data with previous years data indicate no effects from the operation of DNPS. In addition a comparison of the weekly mean values for 2010 indicate no notable differences among the four groups (Figures C-8 through C-14, Appendix C). | |||
Gamma SDectrometrv 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 52 samples and ranged from 46.1 to 122 E-3 pCi/m 3 . K-40 was also detected in 3 samples. The concentration ranged from 25.0 to 43.5 E-3 pCi/m 3 . No anthropogenic nuclides were detected, and all required LLDs were met. | |||
: b. Airborne Iodine Continuous air samples were collected from 13 locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55 and D-56) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). Only naturally occuring nuclides were detected, and all required LLDs were met. | |||
: 2. Terrestrial | |||
Gross 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 four groups aid in determining the effects, if any, resulting from the operation of DNPS. The results from the On-Site locations ranged from 6 to 47 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3.The results from the Near-Field locations ranged from 6 to 40 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3.The results from the Far-Field locations ranged from 6 to 40 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3.The results from the Control location ranged from 8 to 40 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3.Comparison of the 2010 air particulate data with previous years data indicate no effects from the operation of DNPS. In addition a comparison of the weekly mean values for 2010 indicate no notable differences among the four groups (Figures C-8 through C-14, Appendix C). | |||
Gamma SDectrometrv 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 52 samples and ranged from 46.1 to 122 E-3 pCi/m 3.K-40 was also detected in 3 samples. The concentration ranged from 25.0 to 43.5 E-3 pCi/m 3.No anthropogenic nuclides were detected, and all required LLDs were met.b. Airborne Iodine Continuous air samples were collected from 13 locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55 and D-56) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). Only naturally occuring nuclides were detected, and all required LLDs were met.2. Terrestrial | |||
: a. Milk There are no indicator locations within 10 kilometers of the station. Samples were collected from one control location (D-25) biweekly May through October and monthly November through April. The following analyses were performed: | : a. Milk There are no indicator locations within 10 kilometers of the station. Samples were collected from one control location (D-25) biweekly May through October and monthly November through April. The following analyses were performed: | ||
Iodine-1 31 Milk samples from the location were analyzed for concentrations of 1-131 (Table C-VII.1, Appendix C). No nuclides were detected, and all required LLDs were met.Gamma Spectrometrv Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C). | Iodine-1 31 Milk samples from the location were analyzed for concentrations of 1-131 (Table C-VII.1, Appendix C). No nuclides were detected, and all required LLDs were met. | ||
Naturally occurring K-40 activity was found in all nineteen samples. The activities ranged from 1,070 to 1,480 pCi/I.No other nuclides were detected, and all required LLDs were met.b. Food Products Food product samples were collected at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4)when available. | Gamma Spectrometrv Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C). | ||
Four locations, (D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) could be affected by Dresden's effluent releases. | |||
The following analysis was performed: | Naturally occurring K-40 activity was found in all nineteen samples. The activities ranged from 1,070 to 1,480 pCi/I. | ||
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-VIII.1, Appendix C). Only naturally occurring nuclides were detected, and all required LLDs were met.C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Global Dosimetry 110 Environmental (CaF 2 and LiF) thermoluminescent dosimeters. | No other nuclides were detected, and all required LLDs were met. | ||
Forty-five 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 30 mR/quarter, with a range of 19 to 33 mR/quarter. | : b. Food Products Food product samples were collected at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) when available. Four locations, (D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) could be affected by Dresden's effluent releases. The following analysis was performed: | ||
A comparison of the Inner Ring, Outer Ring, and Other locations' data to the Control Location data, indicate that the ambient gamma radiation levels from the Control location (D-12-01, D-12-02) were comparable. | Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-VIII.1, Appendix C). Only naturally occurring nuclides were detected, and all required LLDs were met. | ||
C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Global Dosimetry 110 Environmental (CaF 2 and LiF) thermoluminescent dosimeters. Forty-five 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 30 mR/quarter, with a range of 19 to 33 mR/quarter. A comparison of the Inner Ring, Outer Ring, and Other locations' data to the Control Location data, indicate that the ambient gamma radiation levels from the Control location (D-12-01, D-12-02) were comparable. | |||
D. Land Use Survey A Land Use Survey conducted on 03 August 2010 around the Dresden Nuclear Power Station (DNPS) was performed by EIML for Exelon Nuclear to comply with Section 12.6.2 of the Dresden Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident or industrial facility, milk producing animal, and livestock in each of the sixteen 22 1/2 degree sectors within 10 km around the site. There were no changes required to the DNPS REMP as a result of this survey. The results of this survey are summarized below. | D. Land Use Survey A Land Use Survey conducted on 03 August 2010 around the Dresden Nuclear Power Station (DNPS) was performed by EIML for Exelon Nuclear to comply with Section 12.6.2 of the Dresden Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident or industrial facility, milk producing animal, and livestock in each of the sixteen 22 1/2 degree sectors within 10 km around the site. There were no changes required to the DNPS REMP as a result of this survey. The results of this survey are summarized below. | ||
Distance in Miles from the DNPS Reactor Buildings Sector Residence Livestock Milk Farm Miles Miles Miles | |||
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: | Distance in Miles from the DNPS Reactor Buildings Sector Residence Livestock Milk Farm Miles Miles Miles AN 1.5 1.4 B NNE 0.8 6.0 C NE 0.8 5.8 D ENE 0.7 1.7 EE 1.1 F ESE 1.0 G SE 0.6 - | ||
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. | H SSE 0.5 JS 0.5 - 16.0 K SSW 3.3 L SW 3.6 - 11.4 MWSW 5.8 - - | ||
For the primary laboratory, 16 out of 18 analytes met the specified acceptance criteria. | NW 3.5 0.5 P WNW 3.7 0.5 Q NW 2.6 0.5 R NNW 0.8 1.0 E. Errata Data There was no errata data discovered in 2010. | ||
Two analytes did not meet the specified acceptance criteria for the following reason: 1. Teledyne Brown Engineering's ERA November 2010 Sr-89 in water result of 77.8 pCi/L was higher than the known value of 68.5 pCi/L, resulting in a found to known ratio of 1.14. NCR 10-09 was initiated to investigate this failure. Since the ratio of 1.14 fell within an acceptance range of 20%, Teledyne considers this an acceptable result.2. Teledyne Brown Engineering's ERA November 2010 Zn-65 in water result of 11.0 pCi/L was lower than the known value of 102 pCi/L. NCR 10-09 was initiated to investigate this failure. The Zn-65 result of 111 was incorrectly reported as 11.0.For the secondary laboratory, Environmental, Inc., 14 out of 14 analytes met the specified acceptance criteria.The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data. | F. Summary of Results - Inter-Laboratory Comparison Program The primary laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix D). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria: | ||
Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT | : 1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of laboratory results 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, 16 out of 18 analytes met the specified acceptance criteria. Two analytes did not meet the specified acceptance criteria for the following reason: | |||
: 1. Teledyne Brown Engineering's ERA November 2010 Sr-89 in water result of 77.8 pCi/L was higher than the known value of 68.5 pCi/L, resulting in a found to known ratio of 1.14. NCR 10-09 was initiated to investigate this failure. Since the ratio of 1.14 fell within an acceptance range of 20%, Teledyne considers this an acceptable result. | |||
: 2. Teledyne Brown Engineering's ERA November 2010 Zn-65 in water result of 11.0 pCi/L was lower than the known value of 102 pCi/L. NCR 10-09 was initiated to investigate this failure. The Zn-65 result of 111 was incorrectly reported as 11.0. | |||
For the secondary laboratory, Environmental, Inc., 14 out of 14 analytes met the specified acceptance criteria. | |||
The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data. | |||
Intentionally left blank | |||
APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT | |||
==SUMMARY== | ==SUMMARY== | ||
Line 140: | Line 224: | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS 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 GR-B 36 4 8.8 9.3 9.6 D-57 CONTROL 0 (PCI/LITER) (I 1/12) (24/24) (12/12) KANKAKEE RIVER AT WILL ROAD(CONTROL) | ||
MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS 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 | (5.1/14.5) (4.1/15.7) (4.1/15.7) 2.0 MILES SE OF SITE H-3 12 2000 217 63 I 631 D-57 CONTROL 0 (3/4) (2/8) (2/4) KANKAKEE RIVER AT WILL ROAD(CONTROL) | ||
GR-B | (189/246) (231/1030) (231/1030) 2.0 MILES SE OF SITE GAMMA 36 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 CO-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 NB-95 15 <LLD <LLD 0 | ||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS 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 <LLD <LLD 0 (PCI/LITER) 1-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA- 140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 GROUND WATER H-3 16 2000 301 NA 301 D-23 INDICATOR 0 (PCI/LITER) (12/16) (12/12) THORSEN WELL (216/400) (216/400) 0.7 MILES S OF SITE GAMMA 16 MN-54 15 <LLD NA 0 | ||
MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS 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 (PCI/LITER) | * THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | ||
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER CO-58 15 <LLD NA 0 (PCI/LITER) | ||
MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER (PCI/LITER) | FE-59 30 <LLD NA 0 CO-60 15 <LLD NA 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA 0 ZR-95 30 <LLD NA 0 1-131 15 <LLD NA 0 CS-134 15 <LLD NA 0 | ||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER CS-137 18 <LLD NA 0 (PCI/LITER) | ||
MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER (PCI/LITER) | BA- 140 60 <LLD NA 0 LA-140 15 <LLD NA 0 FISH GAMMA (PCI/KG WET) MN-54 130 <LLD <LLD 0 CO-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 CO-60 130 <LLD <LLD 0 ZN-65 260 <LLD <LLD 0 | ||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS FISH NB-95 NA <LLD <LLD 0 (PCI/KG WET) | ||
MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS | ZR-95 NA <LLD <LLD 0 CS-134 130 <LLD <LLD 0 | ||
,>I CS-137 150 <LLD <LLD 0 BA-140 NA <LLD <LLD LA- 140 NA <LLD <LLD SEDIMENT GAMMA 2 (PCI/KG DRY) MN-54 NA <LLD NA 0 CO-58 NA <LLD NA 0 | |||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT FE-59 NA <LLD NA 0 (PCI/KG DRY) | ||
MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT (PCI/KG DRY) | CO-60 NA <LLD NA 0 ZN-65 NA <LLD NA 0 NB-95 NA <LLD NA 0 ZR-95 NA <LLD NA 0 CS-134 150 <LLD NA 0 CS-137 180 57 NA 57 D-27 INDICATOR 0 (1/2) (1/2) DRESDEN LOCK AND DAM - DOWNSTREAM 0.8 MILES NW OF SITE BA-140 NA <LLD NA 0 | ||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT LA- 140 NA <LLD NA 0 (PCI/KG DRY) | ||
MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT (PCI/KG DRY) | AIR PARTICULATE GR-B 676 10 18 19 19 D-08 INDICATOR (E-3 PCI/CU.METER) (621/624) (49/52) (51/52) PRAIRIE PARK (6/47) (8/40) (8/40) 3.8 MILES SW OF SITE GAMMA 52 MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 | ||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS 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 ZR-95 NA <LLD <LLD 0 (E-3 PCI/CU.METER) | ||
MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS 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 (E-3 PCI/CU.METER) | CS-134 50 <LLD <LLD 0 CS-137 60 <LLD <LLD 0 00 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 AIR IODINE GAMMA 676 (E-3 PCI/CU.METER) 1-131 70 <LLD <LLD 0 MILK 1-131 19 I NA <LLD 0 (PCI/LITER) | ||
GAMMA 19 MN-54 NA NA <LLD 0 | |||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK CO-58 NA NA <LLD 0 (PCI/LITER) | ||
MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK (PCI/LITER) | FE-59 NA NA <LLD 0 CO-60 NA NA <LLD 0 ZN-65 NA NA <LLD 0 NB-95 NA NA <LLD 0 ZR-95 NA NA <LLD 0 CS-134 15 NA <LLD 0 CS-137 18 NA <LLD 0 | ||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: | FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | ||
DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: | LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK BA-140 60 NA <LLD 0 (PCI/LITER) | ||
MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK (PCI/LITER) | LA-140 15 NA <LLD 0 VEGETATION GAMMA 10 | ||
> (PCI/KG WET) MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 | |||
* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) | |||
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL | ||
==SUMMARY== | ==SUMMARY== | ||
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) | |||
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF | |||
==SUMMARY== | ==SUMMARY== | ||
OF THE AMBIENT DOSIMETRY PROGRAM FOR DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/-2 S.D. | |||
INNER RING 128 19 30 24.6 +/- 4.9 OUTER RING 126 19 32 24.3 +/- 5.8 OTHER 96 19 33 24.2 +/- 4.8 CONTROL 8 19 25 22.3 +/- 3.7 INNER RING STATIONS - D-101-1, D-101-2, D-102-1, D-102-2, D-103-1, D-103-2, D-104-1, D-104-2, D-105-1, D-105-2, D-106-1, D-106-2, D-107-1, D-107-2, D-108-1, D-108-2, D-109-1, D-109-2, D-110-3, D-110o-4, D-111-1, D-111-2, D-112A-1, D-112A- | |||
B. Implementation of the Objectives | B. Implementation of the Objectives | ||
: 1. Dresden Nuclear Power Station will continue to perform routine sampling and radiological analysis of water from selected locations. | : 1. Dresden Nuclear Power Station will continue to perform routine sampling and radiological analysis of water from selected locations. | ||
: 2. Dresden Nuclear Power Station has implemented procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner. | |||
: 3. Dresden Nuclear Power Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends. | |||
: 4. If an adverse trend in groundwater monitoring analytical results is identified, further investigation will be undertaken. If the investigation identifies a leak or unidentified spill, corrective actions will be implemented. | |||
C. Program Description Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. Dresden uses 70 developed groundwater wells and surface water sample points in the RGPP. | |||
: 1. Sample Collection Sample locations can be found in Table A-I, Appendix A. | |||
Groundwater and Surface Water Water samples |
Revision as of 20:26, 12 November 2019
ML11137A110 | |
Person / Time | |
---|---|
Site: | Dresden ![]() |
Issue date: | 05/13/2011 |
From: | Marik S Exelon Generation Co, Exelon Nuclear |
To: | Document Control Desk, NRC/FSME, Office of Nuclear Reactor Regulation |
References | |
SVPLTR #11-0022 | |
Download: ML11137A110 (136) | |
Text
Exelon Generation Company, LLC www.exeloncorp.com Exelkn Dresden Nuclear Power Station Nuclear 65oo North Dresden Road MorTis, IL60450-9765 May 13, 2011 SVPLTR # 11-0022 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 1, 2;-nd 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos.50-010, 50-237, and 50-249
Subject:
Dresden Nuclear Power Station 2010 Annual Radiological Environmental Operating Report Enclosed is the Exelon Dresden Nuclear Power Station 2010 Annual Radiological Environmental Operating Report, submitted in accordance with Section 6.9.A.3 of the Unit 1 Dresden Nuclear Power Station Technical Specifications and Section 5.6.2, "Annual Radiological Environmental Operating Report," of the Units 2 and 3 Technical Specifications.
This report provides the results of the radiological environmental monitoring program for the 2010 calendar year.
In addition, Appendix F of the report contains the results of groundwater monitoring conducted in accordance with Exelon's Radiological Groundwater Protection Program, which is a voluntary program implemented in 2006. This information is being reported in accordance with a nuclear industry initiative.
Should you have any questions concerning this letter, please contact Dennis Leggett, Regulatory Assurance Manager, at (815) 416-2800.
Respectfully, Shane Marik Acting Site Vice President Dresden Nuclear Power Station Attachment - Annual Radiological Environmental Operating Report cc: Regional Administrator - NRC Region III NRC Senior Resident - Dresden Nuclear Power Station
Docket No: 50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS .1, 2 and 3 Annual Radiological Environmental Operating Report 1 January Through 31 December 2010 Prepared By Teledyne Brown Engineering Environmental Services Exelon.
Nuclear Dresden Nuclear Power Station Morris, IL 60450 May 2011
Intentionally left blank Table Of Contents I. Sum m ary and Conclusions .............................................................................................. 1 I1. Introduction ................................................................................................................ 3 A. O bjectives of the REM P ................................................................................. 3 B. Im plem entation of the O bjectives .................................................................. 3 I1l. Program Description .................................................................................................. 4 A . Sam ple Collection .......................................................................................... 4 B. Sam ple Analysis ............................................................................................. 5 C . Data Interpretation .......................................................................................... 6 D. Program Exceptions ........................................................................................ 7 E. Program Changes .......................................................................................... 9 IV. Results and Discussion ............................................................................................. 9 A . Aquatic Environm ent ...................................................................................... 9
- 1. Surface W ater ...................................................................................... 9
- 2. G round W ater ................................................................................... 10
- 3. Fish .................................................................................................... 10
- 4. Sedim ent .............................................................................................. 10 B. Atm ospheric Environm ent ............................................................................ 11
- 1. Airborne ............................................................................................. 11
- a. Air Particulates ....................................................................... 11
- b. Airborne Iodine ....................................................................... 12
- 2. Terrestrial ........................................................................................... 12
- a. Milk ........................................................................................... 12
- b. Food Products ......................................................................... 13 C . Am bient G am ma Radiation .......................................................................... 13 D. Land Use Survey ........................................................................................... 13 E. Errata Data .................................................................................................... 14 F. Summary of Results - Inter-laboratory Comparison Program ..................... 14
Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Dresden Nuclear Power Station, 2010 Appendix B Location Designation, Distance & Direction, and Sample Collection &
Analytical Methods Tables Table B-1 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2010 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2010 Figures Figure B-i Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Locations, 2010 Figure B-2 Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2010 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table C-1.2 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table C-I1.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table C-I1.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
ii
Table C-I11.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
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 Dresden Nuclear Power Station, 2010.
Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table C-VI.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table C-VII.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table C-VIII.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table C-IX.1 Quarterly TLD Results for Dresden Nuclear Power Station, 2010.
Table C-IX.2 Mean Quarterly TLD Results for the Inner Ring, Outer Ring, Other and Control Locations for Dresden Nuclear Power Station, 2010.
Table C-IX.3 Summary of the Ambient Dosimetry Program for Dresden Nuclear Power Station, 2010.
Figures Figure C-1 Surface Water - Gross Beta - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2010.
Figure C-2 Surface Water - Gross Beta - Stations D-54 (C) and D-57 (C)
Collected in the Vicinity of DNPS, 2002 - 2010.
Figure C-3 Surface Water - Gross Beta - Station D-21 Collected in the Vicinity of DNPS, 2007 - 2010.
Figure C-4 Surface Water - Tritium - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2010.
Figure C-5 Surface Water - Tritium - Station D-54 (C) and D-57 (C) Collected in the Vicinity of DNPS, 2002 - 2010.
Figure C-6 Surface Water - Tritium - Station D-21 Collected in the Vicinity of DNPS, 2007 - 2010.
iii
Figure C-7 Ground Water - Tritium - Stations D-23 and D-35 Collected in the Vicinity of DNPS, 2000 - 2010.
Figure C-8 Air Particulate - Gross Beta - Stations D-01 and D-02 Collected in the Vicinity of DNPS, 2000 - 2010.
Figure C-9 Air Particulate - Gross Beta - Stations D-03 and D-04 Collected in the Vicinity of DNPS, 2000 - 2010.
Figure C-10 Air Particulate - Gross Beta - Stations D-07 and D-1 2 (C) Collected in the Vicinity of DNPS, 2000 - 2010.
Figure C-11 Air Particulate - Gross Beta - Stations D-45 and D-53 Collected in the Vicinity of DNPS, 2000 - 2010.
Figure C-12 Air Particulate - Gross Beta - Stations D-08 and D-1 0 Collected in the Vicinity of DNPS, 2005 - 2010.
Figure C-13 Air Particulate - Gross Beta - Stations D-13 and D-14 Collected in the Vicinity of DNPS, 2005 - 2010.
Figure C-14 Air Particulate - Gross Beta - Stations D-55 and D-56 Collected in the Vicinity of DNPS, 2006 - 2010.
Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2010 Table D-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2010 Table D-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)
Teledyne Brown Engineering, 2010 Appendix E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv
I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Dresden Nuclear Power Station (DNPS) by Exelon covers the period 1 January 2010 through 31 December 2010. During that time period, 1,936 analyses were performed on 1,801 samples. In assessing all the data gathered for this report it was concluded that the operation of DNPS had no adverse radiological impact on the environment.
Surface water samples were analyzed for concentrations of gross beta, tritium and gamma emitting nuclides. Ground water samples were analyzed for concentrations of tritium and gamma emitting nuclides. No anthropogenic gamma emitting nuclides were detected. Gross beta and tritium activities detected were consistent with those detected in previous years.
Fish (commercially and recreationally important species), and sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish. Cesium-1 37 was detected in one sediment sample at a concentration consistent with levels observed in previous years. No plant-produced fission or activation products were found in sediment.
Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. Gross beta results at the indicator locations were consistent with those at the control location. 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 activity.
Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. All 1-131 results were below the minimum detectable activity.
Concentrations of naturally occurring K-40 were found. No fission or activation products were found.
Food product samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected.
Environmental gamma radiation measurements were performed quarterly using thermoluminescent dosimeters. Levels detected were consistent with those observed in previous years.
Intentionally left blank
II. Introduction The Dresden Nuclear Power Station (DNPS), consisting of one retired reactor and two operating boiling water reactors owned and operated by Exelon Corporation, is located in Grundy County, Illinois. Unit No. 1 went critical in 1960 and was retired in 1978. Unit No. 2 went critical on 16 June 1970. Unit No. 3 went critical on 02 November 1971. The site is located in northern Illinois, approximately 12 miles southwest of Joliet, Illinois at the confluence of the Des Plaines and Kankakee Rivers where they form the Illinois River.
This report covers those analyses performed by Teledyne Brown Engineering (TBE), Mirion Technologies, and Environmental Inc. Midwest Laboratory (EIML) on samples collected during the period 1 January 2010 through 31 December 2010.
An assessment of the station's radioactive effluent monitoring results and radiation dose via the principle pathways of exposure resulting from plant emissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area, an annual summary of meteorological conditions including wind speed, wind direction, and atmospheric stability, and the result of the 40CFR190 uranium fuel cycle dose analysis for the calendar year are published in the station's Annual Radioactive Effluent Release Report.
A. Objective of the Radiological Environmental Monitoring Program (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.
III. Program Description A. Sample Collection Samples for the DNPS REMP were collected for Exelon Nuclear by EIML.
This section describes the general collection methods used by EIML to obtain environmental samples for the DNPS REMP in 2010. Sample locations and descriptions can be found in Table B-1 and Figures B-1 and B-2, Appendix B. The collection methods used by EIML are listed in Table B-2.
Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, ground water, fish, and sediment.
Samples were collected from three surface water locations (D-21, D-52 and D-57) and composited for analysis. Control locations were D-52 and D-57. Samples were collected quarterly or more frequently from two well water locations (D-23 and D-35). All samples were collected in new unused plastic bottles, which were rinsed with source water prior to collection. Fish samples comprising the flesh of channel catfish, largemouth bass, common carp and freshwater drum were collected semiannually at two locations, D-28 and D-46 (Control). Sediment samples composed of recently deposited substrate were collected at one location semiannually, D-27.
Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, and food products. Airborne iodine and particulate samples were collected at thirteen locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55 and D-56). The control location was D-12. Airbome 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 air filters and air iodine samples were replaced weekly and sent to the laboratory for analysis.
Milk samples were collected biweekly at one control location (D-25) from May through October, and monthly from November through April. There are no milking animals within 10 km of the site. 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.
Food products were collected annually in September at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3, and D-Quad 4). The control location was D-Control. Various types of 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 CaF 2 and LiF thermoluminescent dosimeters (TLD). Each location consisted of 2 TLD sets. The TLD locations were placed on and around the DNPS site as follows:
An inner ringq consisting of 16 locations (D-101, D-102, D-103, D-104, D-105, D-106, D-107, D-108, D-109, D-110, D-111, D-112A, D-113, D-114, D-115 and D-116) at or near the site boundary.
An outer rinq consisting of 16 locations (D-201, D-202, D-203, D-204, D-205, D-206, D-207, D-208, D-209, D-210, D-211, D-212, D-213, D-214, D-215 and D-216) approximately 5 to 10 km from the site.
An other set consisting of TLDs at the 12 air sampler locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-14, D-45, D-53, D-55, and D-56).
The balance of one location (D-12) representing the control area.
Two TLDs - each comprised of two CaF 2 and two LiF thermoluminescent phosphors enclosed in plastic - were placed at each location. The TLDs were exchanged quarterly and sent to Mirion Technologies for analysis.
B. Sample Analysis This section describes the general analytical methodologies used by TBE and EIML to analyze the environmental samples for radioactivity for the DNPS REMP in 2010. The analytical procedures used by the laboratories are listed in Table B-2.
In order to achieve the stated objectives, the current program includes the following analyses:
- 1. Concentrations of beta emitters in surface water and air particulates.
- 2. Concentrations of gamma emitters in ground and surface water, air particulates, milk, fish, sediment and vegetation.
- 3. Concentrations of tritium in ground and surface water.
- 4. Concentrations of 1-131 in air and milk.
- 5. Ambient gamma radiation levels at various site environs.
C. Data Interpretation For the purpose of this report, Dresden Nuclear Power Station 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 DNPS detection capabilities for environmental sample analysis.
The minimum detectable concentration (MDC) is calculated the same as the LLD with the exception that the measurement is an after the fact estimate of the presence of activity.
- 2. Net Activity Calculation and Reportingq 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 effecting a negative number. An MDC was reported in all cases where positive activity was not detected.
Gamma spectroscopy results for each type of sample were grouped as follows:
For ground and surface water and vegetation 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-1 37, Ba-1 40, and La-1 40 were reported.
For fish, sediment, air particulate and milk 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-1 34, Cs-1 37, 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 2010 the DNPS REMP had a sample recovery rate in excess of 99%.
Sample anomalies and missed samples are listed in the tables below:
Table D-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection Reason Type Code Date AP/I D-07 03/05/10 - 03/12/10 Low reading of 152.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on 03/12/10 due to power loss, likely due to lightning strike.
AP/I D-07 03/12/10 - 03/19/10 Low reading of 98.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> on 03/19/10 due to recent power restoration on 03/15/10.
AP/I D-07 03/26/10 - 04/02/10 Low run time of 169.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; cause is unknown.
AP/I D-02 04/23/10 - 04/30/10 Low run time of 169.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> due to electrical outage.
AP/I D-03 04/23/10 - 04/30/10 Low run time of 169.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> due to electrical outage.
AP/I D-07 04/23/10 - 04/30/10 Low run time of 167.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to electrical outage.
AP/I D-01 05/21/10 - 05/28/10 Estimated collection time of 165.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> due to failed timer. Timer was replaced.
SW D-21 05/28/10 - 06/25/10 Composite sampler was out of service due to pump failure. Grab samples drawn 06/17/10 - 08/03/10 and added to composite until sampler was repaired.
Table D-1 LISTING OF SAMPLE . ... . . .. ... . (c .....
nin.. .)
Sample Location Collection Reason Type Code Date SW D-21 06/25/10 - 07/30/10 Composite sampler was out of service due to pump failure. Grab samples drawn 06/17/10 - 08/03/10 and added to composite until sampler was repaired.
AP/I D-03 07/23/10 - 07/30/10 Low run time of 37.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; cause is unknown.
AP/I D-03 08/13/10 - 08/20/10 Low run time of 136.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />; cause is unknown.
AP/I D-04 08/13/10 - 08/20/10 Estimated collection time of 167.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to failed timer. Timer was replaced.
AP/I D-03 08/20/10 - 08/27/10 Low run time of 152.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />; cause is unknown. Timer was replaced.
AP/I D-03 08/27/10 - 09/03/10 Low run time of 135.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />; cause is unknown.
AP/I D-03 09/10/10 - 09/17/10 Low run time of 134.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />; cause is unknown. Second timer installed in parallel for troubleshooting, which indicated timers were accurate and previous low readings were due to power interruptions.
Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date TLD D-214 07/01/10 - 10/01/10 TLDs D-214-1 and D-214-2 were missing during quarterly exchange, likely due to removal by utility pole inspection crew.
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 There were no program changes for 2010.
IV. Results and Discussion A. Aquatic Environment
- 1. Surface Water Samples were composited or taken weekly and composited for analysis at three locations (D-21, D-52, and D-57). Of these locations only D-21 located downstream, could be affected by Dresden's effluent releases. The following analyses were performed:
Gross Beta Monthly composites from all locations were analyzed for concentrations of gross beta (Table C-1.1, Appendix C). The values ranged from <3.8 to 15.7 pCi/I. Concentrations detected were consistent with those detected in previous years (Figures C-1, C-2, and C-3, Appendix C).
Tritium Quarterly composites from all locations were analyzed for tritium activity (Table C-1.2, Appendix C). The indicator values ranged from <159 to 246 pCi/L. Control values ranged from <157 to 1,030 pCi/L. Concentrations detected were consistent with those detected in previous years (Figures C-4, C-5, and C-6, Appendix C).
Gamma Spectrometry Monthly composites from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No nuclides were detected, and all required LLDs were met.
- 2. Ground Water Quarterly or more frequent grab samples were collected at two locations (D-23 and D-35). These locations could be affected by Dresden's effluent releases and by sources upstream on the Kankakee River. The following analyses were performed:
Tritium All samples were analyzed for tritium activity (Table C-11.1, Appendix C). D-35 values ranged from <160 to <178 pCi/L. D-23 values ranged from 216 to 400 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-7, Appendix C).
Gamma Spectrometrv All samples were analyzed for gamma emitting nuclides (Table C-11.2, Appendix C). No nuclides were detected, and all required LLDs were met.
- 3. Fish Fish samples comprised of channel catfish, largemouth bass, common carp and freshwater drum were collected at two locations (D-28 and D-46) semiannually. Location D-28 could be affected by Dresden'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-111.1, Appendix C).
Naturally occurring K-40 was found at all stations and ranged from 2,980 to 4,640 pCi/kg wet. No fission or activation products were detected.
- 4. Sediment Aquatic sediment samples were collected at one location (D-27) semiannually. This downstream location could be affected by Dresden's effluent releases. The following analysis was performed:
Gamma Spectrometry Sediment samples from the location were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). Cesium-137 was detected in one sample at a concentration of 57 pCi/kg dry. The activity detected was consistent with those detected in previous years and is likely due to fallout from above-ground nuclear weapons testing. No other fission or activation products were detected.
B. Atmospheric Environment
- 1. Airborne
- a. Air Particulates Continuous air particulate samples were collected from 13 locations on a weekly basis. The 13 locations were separated into four groups: On-site samplers (D-01, D-02, D-03), Near-field samplers within 4 km of the site (D-04, D-07, D-45, D-53 and D-56), Far-field samplers between 4 and 10 km from the site (D-08, D-10, D-14 and D-55) and the Control sampler between 10 and 30 km from the site (D-12).
The following analyses were performed:
Gross 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 four groups aid in determining the effects, if any, resulting from the operation of DNPS. The results from the On-Site locations ranged from 6 to 47 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. The results from the Near-Field locations ranged from 6 to 40 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. The results from the Far-Field locations ranged from 6 to 40 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3. The results from the Control location ranged from 8 to 40 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3. Comparison of the 2010 air particulate data with previous years data indicate no effects from the operation of DNPS. In addition a comparison of the weekly mean values for 2010 indicate no notable differences among the four groups (Figures C-8 through C-14, Appendix C).
Gamma SDectrometrv 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 52 samples and ranged from 46.1 to 122 E-3 pCi/m 3 . K-40 was also detected in 3 samples. The concentration ranged from 25.0 to 43.5 E-3 pCi/m 3 . No anthropogenic nuclides were detected, and all required LLDs were met.
- b. Airborne Iodine Continuous air samples were collected from 13 locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55 and D-56) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). Only naturally occuring nuclides were detected, and all required LLDs were met.
- 2. Terrestrial
- a. Milk There are no indicator locations within 10 kilometers of the station. Samples were collected from one control location (D-25) biweekly May through October and monthly November through April. The following analyses were performed:
Iodine-1 31 Milk samples from the location were analyzed for concentrations of 1-131 (Table C-VII.1, Appendix C). No nuclides were detected, and all required LLDs were met.
Gamma Spectrometrv 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 nineteen samples. The activities ranged from 1,070 to 1,480 pCi/I.
No other nuclides were detected, and all required LLDs were met.
- b. Food Products Food product samples were collected at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) when available. Four locations, (D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) could be affected by Dresden's effluent releases. The following analysis was performed:
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-VIII.1, Appendix C). Only naturally occurring nuclides were detected, and all required LLDs were met.
C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Global Dosimetry 110 Environmental (CaF 2 and LiF) thermoluminescent dosimeters. Forty-five 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 30 mR/quarter, with a range of 19 to 33 mR/quarter. A comparison of the Inner Ring, Outer Ring, and Other locations' data to the Control Location data, indicate that the ambient gamma radiation levels from the Control location (D-12-01, D-12-02) were comparable.
D. Land Use Survey A Land Use Survey conducted on 03 August 2010 around the Dresden Nuclear Power Station (DNPS) was performed by EIML for Exelon Nuclear to comply with Section 12.6.2 of the Dresden Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident or industrial facility, milk producing animal, and livestock in each of the sixteen 22 1/2 degree sectors within 10 km around the site. There were no changes required to the DNPS REMP as a result of this survey. The results of this survey are summarized below.
Distance in Miles from the DNPS Reactor Buildings Sector Residence Livestock Milk Farm Miles Miles Miles AN 1.5 1.4 B NNE 0.8 6.0 C NE 0.8 5.8 D ENE 0.7 1.7 EE 1.1 F ESE 1.0 G SE 0.6 -
H SSE 0.5 JS 0.5 - 16.0 K SSW 3.3 L SW 3.6 - 11.4 MWSW 5.8 - -
NW 3.5 0.5 P WNW 3.7 0.5 Q NW 2.6 0.5 R NNW 0.8 1.0 E. Errata Data There was no errata data discovered in 2010.
F. Summary of Results - Inter-Laboratory Comparison Program The primary laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix D). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:
- 1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of laboratory results 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, 16 out of 18 analytes met the specified acceptance criteria. Two analytes did not meet the specified acceptance criteria for the following reason:
- 1. Teledyne Brown Engineering's ERA November 2010 Sr-89 in water result of 77.8 pCi/L was higher than the known value of 68.5 pCi/L, resulting in a found to known ratio of 1.14. NCR 10-09 was initiated to investigate this failure. Since the ratio of 1.14 fell within an acceptance range of 20%, Teledyne considers this an acceptable result.
- 2. Teledyne Brown Engineering's ERA November 2010 Zn-65 in water result of 11.0 pCi/L was lower than the known value of 102 pCi/L. NCR 10-09 was initiated to investigate this failure. The Zn-65 result of 111 was incorrectly reported as 11.0.
For the secondary laboratory, Environmental, Inc., 14 out of 14 analytes met the specified acceptance criteria.
The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.
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APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
SUMMARY
Intentionally left blank TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS 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 GR-B 36 4 8.8 9.3 9.6 D-57 CONTROL 0 (PCI/LITER) (I 1/12) (24/24) (12/12) KANKAKEE RIVER AT WILL ROAD(CONTROL)
(5.1/14.5) (4.1/15.7) (4.1/15.7) 2.0 MILES SE OF SITE H-3 12 2000 217 63 I 631 D-57 CONTROL 0 (3/4) (2/8) (2/4) KANKAKEE RIVER AT WILL ROAD(CONTROL)
(189/246) (231/1030) (231/1030) 2.0 MILES SE OF SITE GAMMA 36 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 CO-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 NB-95 15 <LLD <LLD 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS 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 <LLD <LLD 0 (PCI/LITER) 1-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA- 140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 GROUND WATER H-3 16 2000 301 NA 301 D-23 INDICATOR 0 (PCI/LITER) (12/16) (12/12) THORSEN WELL (216/400) (216/400) 0.7 MILES S OF SITE GAMMA 16 MN-54 15 <LLD NA 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER CO-58 15 <LLD NA 0 (PCI/LITER)
FE-59 30 <LLD NA 0 CO-60 15 <LLD NA 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA 0 ZR-95 30 <LLD NA 0 1-131 15 <LLD NA 0 CS-134 15 <LLD NA 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER CS-137 18 <LLD NA 0 (PCI/LITER)
BA- 140 60 <LLD NA 0 LA-140 15 <LLD NA 0 FISH GAMMA (PCI/KG WET) MN-54 130 <LLD <LLD 0 CO-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 CO-60 130 <LLD <LLD 0 ZN-65 260 <LLD <LLD 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS FISH NB-95 NA <LLD <LLD 0 (PCI/KG WET)
ZR-95 NA <LLD <LLD 0 CS-134 130 <LLD <LLD 0
,>I CS-137 150 <LLD <LLD 0 BA-140 NA <LLD <LLD LA- 140 NA <LLD <LLD SEDIMENT GAMMA 2 (PCI/KG DRY) MN-54 NA <LLD NA 0 CO-58 NA <LLD NA 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT FE-59 NA <LLD NA 0 (PCI/KG DRY)
CO-60 NA <LLD NA 0 ZN-65 NA <LLD NA 0 NB-95 NA <LLD NA 0 ZR-95 NA <LLD NA 0 CS-134 150 <LLD NA 0 CS-137 180 57 NA 57 D-27 INDICATOR 0 (1/2) (1/2) DRESDEN LOCK AND DAM - DOWNSTREAM 0.8 MILES NW OF SITE BA-140 NA <LLD NA 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT LA- 140 NA <LLD NA 0 (PCI/KG DRY)
AIR PARTICULATE GR-B 676 10 18 19 19 D-08 INDICATOR (E-3 PCI/CU.METER) (621/624) (49/52) (51/52) PRAIRIE PARK (6/47) (8/40) (8/40) 3.8 MILES SW OF SITE GAMMA 52 MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS 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 ZR-95 NA <LLD <LLD 0 (E-3 PCI/CU.METER)
CS-134 50 <LLD <LLD 0 CS-137 60 <LLD <LLD 0 00 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 AIR IODINE GAMMA 676 (E-3 PCI/CU.METER) 1-131 70 <LLD <LLD 0 MILK 1-131 19 I NA <LLD 0 (PCI/LITER)
GAMMA 19 MN-54 NA NA <LLD 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK CO-58 NA NA <LLD 0 (PCI/LITER)
FE-59 NA NA <LLD 0 CO-60 NA NA <LLD 0 ZN-65 NA NA <LLD 0 NB-95 NA NA <LLD 0 ZR-95 NA NA <LLD 0 CS-134 15 NA <LLD 0 CS-137 18 NA <LLD 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK BA-140 60 NA <LLD 0 (PCI/LITER)
LA-140 15 NA <LLD 0 VEGETATION GAMMA 10
> (PCI/KG WET) MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR DRESDEN NUCLEAR POWER STATION, 2010 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS, IL REPORTING PERIOD: ANNUAL 2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION ZR-95 NA <LLD <LLD 0 (PCI/KG WET) 1-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0 CS-137 80 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA- 140 NA <LLD <LLD 0 DIRECT RADIATION TLD-QUARTERLY 358 NA 24 22 30 D-201-1 INDICATOR 0 (MILLI-ROENTGEN/QTR.) (350/350) (8/8) (4/4)
(19/33) (19/25) (28/32) 4.8 MILES N
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
Intentionally left blank APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS
Intentionally left blank
TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2010 Location Location Description Distance & Direction From Site A. Surface Water D-21 Illinois River at EJ&E Bridge (indicator) 1.4 miles WNW D-52 DesPlaines River, Upstream (control) 1.1 miles ESE D-57 Kankakee River at Will Road (control) 2.0 miles SE B. Ground/Well Water 0.7 miles S D-23 Thorsen Well (indicator)
D-35 Dresden Lock and Dam (indicator) 0.8 miles NW C. Milk - bi-weekly / monthly D-25 Biros Farm (control) 11.3 miles SW D. Air Particulates / Air Iodine D-01 Onsite 1 (indicator) 0.8 miles NW D-02 Onsite 2 (indicator) 0.3 miles NNE D-03 Onsite 3 (indicator) 0.4 miles S D-04 Collins Road (indicator) 0.8 miles W D-07 Clay Products (indicator) 2.6 miles S D-08 Prairie Park (indicator) 3.8 miles SW D-10 Goose Lake Village (indicator) 3.5 miles SSW D-12 Lisbon (control) 10.5 miles NW D-14 Channahon (indicator) 3.7 miles NE D-45 McKinley Woods Road (indicator) 1.7 miles ENE D-53 Grundy County Road (indicator) 2.1 miles SSE D-55 Ridge Road (indicator) 4.3 miles N D-56 Wildfeather (indicator) 1.7 miles SE E. Fish D-28 Dresden Pool of Illinois River, Downstream (indicator) 0.9 miles NNW D-46 DesPlaines River, Upstream (control) 1.2 miles ESE F. Sedimennt D-27 Dresden Lock and Dam, Downstream (indicator) 0.8 miles NW G. Vegetation Quadrant 1 Chris Locknar 2.8 miles NE Quadrant 2 Robert Pagliano 3.2 miles SSE Quadrant 3 Jim Bloom 3.9 miles SSW Quadrant 4 J.D. Carmichael 1.6 miles NNW Control Glasscock Farm 12.8 miles ENE B-1
TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2010 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - TLD Inner Ring D-101-1 and -2 1.0 miles N D-102-1 and -2 1.3 miles NNE D-103-1 and -2 1.2 miles NE D-104-1 and-2 1.7 miles ENE D-105-1 and -2 1.5 miles E D-106-1 and -2 1.1 miles ESE D-107-1 and -2 1.4 miles SE D-108-1 and -2 1.9 miles SSE D-109-1 and -2 0.8 miles S D-110-3 and -4 0.9 miles SSW D-111-1 and -2 0.6 miles SW D-112a-1 and-2 0.7 miles WSW D-113-1 and -2 0.9 miles W D-114-1 and -2 0.9 miles WNW D-115-1 and -2 0.8 miles NW D-116-1 and -2 1.0 miles NNW Outer Ring D-201-1 and -2 4.8 miles N D-202-1 and -2 5.1 miles NNE D-203-1 and -2 4.7 miles NE D-204-1 and -2 5.0 miles ENE D-205-1 and -2 4.0 miles E D-206-1 and -2 3.5 miles ESE D-207-1 and -2 4.2 miles SE D-208-1 and -2 4.9 miles SSE D-209-1 and -2 4.1 miles S D-210-1 and -2 4.9 miles SSW D-211-1 and -2 4.8 miles SW D-212-3 and -4 6.0 miles WSW D-213-1 and -2 4.5 miles W D-214-1 and -2 5.0 miles WNW D-215-1 and -2 4.8 miles NW D-216-1 and -2 4.9 miles NNW Other D-01-1 and -2 Onsite 1 0.8 miles NW D-02-1 and -2 Onsite 2 0.3 miles NNE D-03-1 and -2 Onsite 3 0.4 miles S D-04-1 and -2 Collins Road 0.8 miles W D-07-1 and -2 Clay Products 2.6 miles S D-08-1 and -2 Prairie Park 3.8 miles SW D-10-1 and -2 Goose Lake Village 3.5 miles SSW D-14-1 and -2 Channahon 3.7 miles NE D-45-1 and -2 McKinley Woods Road 1.7 miles ENE D-53-1 and -2 Grundy County Road 2.1 miles SSE D-55-1 and -2 Ridge Road 4.3 miles N D-56-1 and -2 Wildfeather 1.7 miles SE Control D-12-1 and -2 Lisbon 10.5 miles NW B-2
TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2010 Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Sample Medium Surface Water Gamma Spectroscopy Monthly composite EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting sample or monthly Midwest Laboratory Sampling Procedures radioisotope analysis composite from weekly Manual grab samples.
TBE, TBE-2023 Compositing of samples EIML-COMP-01 procedure for compositing water and milk samples Surface Water Gross Beta Monthly composite EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2008 Gross Alpha and/or sample or monthly Midwest Laboratory Sampling Procedures gross beta activity in various matrices composite from weekly Manual grab samples.
TBE, TBE-2023 Compositing of samples EIML-COMP-01 procedure for compositing water and milk samples Surface Water Tritium Quarterly composite of EIML-SPM-1, Environmental Incorporated 500 ml TBE, TBE-2011 Tritium analysis in monthly composite Midwest Laboratory Sampling Procedures drinking water by liquid scintillation samples. Manual TBE, TBE-2023 Compositing of samples EIML-COMP-01 procedure for compositing water and milk samples Ground Water Gamma Spectroscopy Quarterly grab samples. EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting Midwest Laboratory Sampling Procedures radioisotope analysis Manual Ground Water Tritium Quarterly grab samples. EIML-SPM-1, Environmental Incorporated 500 ml TBE, TBE-2011 Tritium analysis in Midwest Laboratory Sampling Procedures drinking water by liquid scintillation Manual Fish Gamma Spectroscopy Samples collected twice EIML-SPM-1, Environmental Incorporated 1000 grams (wet) TBE-2007 Gamma emitting radioisotope annually via Midwest Laboratory Sampling Procedures analysis electroshocking or other Manual techniques Sediment Gamma Spectroscopy Semi-annual grab EIML-SPM-1, Environmental Incorporated 500 grams (dry) TBE, TBE-2007 Gamma emitting samples Midwest Laboratory Sampling Procedures radioisotope analysis Manual
TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2010 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Dredging Spoils Gamma Spectroscopy Annual grab samples if EIML-SPM-1, Environmental Incorporated 500 grams (dry) TBE, TBE-2007 Gamma emitting dredging occurred Midwest Laboratory Sampling Procedures radioisotope analysis within 1 mile of Dresden Manual Station during the year.
Air Particulates Gross Beta One-week of continuous EIML-SPM-1, Environmental Incorporated 1 filter (approximately TBE, TBE-2008 Gross Alpha and/or air sampling through Midwest Laboratory Sampling Procedures 280 cubic meters gross beta activity in various matrices glass fiber filter paper Manual weekly)
Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting each station radioisotope analysis Env. Inc., AP-03 Procedure for compositing air particulate filters for gamma spectroscopic analysis Air Iodine Gamma Spectroscopy One- or two-week EIML-SPM-1, Environmental Incorporated 1 filter (approximately TBE, TBE-2007 Gamma emitting composite of continuous Midwest Laboratory Sampling Procedures 280 cubic meters radioisotope analysis air sampling through Manual weekly) charcoal filter Milk 1-131 Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2012 Radioiodine in various May through October. Midwest Laboratory Sampling Procedures matrices Monthly all other times Manual Milk Gamma Spectroscopy Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting May through October. Midwest Laboratory Sampling Procedures radioisotope analysis Monthly all other times Manual Food Products Gamma Spectroscopy Annual grab samples. EIML-SPM-1, Environmental Incorporated 1000 grams TBE, TBE-2007 Gamma emitting Midwest Laboratory Sampling Procedures radioisotope analysis Manual TLD Thermoluminescence Quarterly TLDs EIML-SPM-1, Environmental Incorporated 2 dosimeters Mirion Technologies Dosimetry comprised of two Mirion Midwest Laboratory Sampling Procedures Technologies TLDs, Manual with two CaF 2 elements and two LiF elements in I each TLD. II
101-2 1044 11482 114-4 "&4 10512 Drmsuui Nuwea 113*.1 11s4 D42 S 14 13340 0 I 1
am MTIO ANUAL.&
,at 3E Rlh TWO SOdMMn Figure B-1 Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Location, 2010 B-5
out 12 U61u~ U04 =K N
0 5 WMin S t0 U Wimimm OFF= WE CALOILANN MNUAL
- Ar Buming Lanlon0
- ¥LaOmi fb AM hDMNIRM*SMM0.DSCUTEU
- 'LV LflhIln lm 7w wLCAmmt AM NU ELKlI=
Figure B-2 Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2010 B-6
APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY
Intentionally left blank TABLE C-I.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION D-21 D-52 D-57 PERIOD 01/01/10 - 01/29/10 9.3 +/- 2.6 5.8 +/- 2.5 4.2 +/- 2.2 02/05/10 - 02/26/10 12.6 +/- 2.6 9.5 +/- 2.7 9.5 +/- 2.5 03/05/10 - 03/26/10 7.2 +/- 2.6 10.0 +/- 3.0 7.4 +/- 2.3 04/02/10 - 04/30/10 < 3.8 7.9 +/- 1.6 9.2 +/- 1.5 05/07/10 - 05/28/10 7.4 +/- 2.6 12.1 +/- 3.2 8.0 +/- 2.8 06/04/10 - 06/25/10 7.4 +/- 2.2 (1) 7.1 +/- 2.3 14.6 +/- 3.1 07/03/10 - 07/30/10 14.5 +/- 3.0 (1) 7.7 +/- 2.6 11.9 +/- 3.0 08/06/10 - 08/27/10 5.1 +/- 2.3 10.9 +/- 2.7 6.0 +/- 2.4 09/03/10 - 09/24/10 9.4 +/- 2.4 8.3 +/- 2.3 12.8 +/- 3.1 10/01/10 - 10/29/10 9.9 +/- 2.5 8.9 +/- 2.5 4.1 +/- 2.2 11/05/10 - 11/26/10 5.2 +/- 2.1 10.4 +/- 2.4 12.4 +/- 2.5 12/03/10 - 12/31/10 8.6 +/- 3.3 9.6 +/- 3.1 15.7 +/- 4.0 MEAN 8.8 +/- 5.7 9.0 +/- 3.5 9.6 +/- 7.8 TABLE C-1,2 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION D-21 D-52 D-57 PERIOD 01/01/10 - 03/26/10 189 +/- 121 178
- 177 04/02/10 - 06/25/10 < 159 162 < 157 07/03/10 - 09/24/10 246 +/- 134 199 231 +/- 132 09/24/10 - 12/31/10 216 +/- 109 159 1030 +/- 169 MEAN 217 +/- 57 631 +/- 1130
- THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1
TABLE C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 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-1 37 Ba-140 La-140 PERIOD D-21 01/01/10 - 01/29/'10 <7 <6 < 11 <4 12 <7 < 12 < 10 <5 <7 < 29 <8 01/29/10 - 02/26/'10 <5 <7 < 12 <6 12 <5 < 11 <9 <6 <7 < 27 <8 02/26/10 - 03/26 /10 <2 <2 <4 <1 3 <2 <3 <8 <1 <2 < 15 <5
<1 <3 <9 <1 <1 < 15 <4 03126110 - 04/30 /10 <1 <1 <3 3 <2 04/30/10 - 05/28 /10 <1 <2 <4 <1 3 <2 <3 <9 <1 <2 < 15 <5 06/04/10 - 06/25//10 (1) <6 <6 <11 <5 12 <5 <9 <9 <6 <6 < 24 <7 (1) <5 <5 < 10 <5 12 <6 <8 < 15 <5 <5 < 35 < 11 06/25/10 - 07/30/'10 07/30/10 - 08/27/~10 <2 <2 <4 <2 3 <2 <3 < 10 <1 <2 < 18 <5 08/27/10 - 09/24,/10 <4 <5 <8 <6 10 <4 <9 < 13 <4 <6 < 28 <9 09/24/10 - 10/29 /10 <4 <4 <9 <4 9 <4 <7 < 11 <4 <4 < 26 <9 10/29/10 - 11/26 /10 <4 <4 < 11 <5 8 <6 <8 <9 <4 <6 < 27 <9 11/26/10 - 12/31 /10 <5 <6 < 14 <5 11 <6 <11 < 11 <5 <6 < 27 < 10 MEAN D-52 01/01/10 01/29/10 <5 <5 < 12 <4 < 11 <7 <8 <8 <5 <5 < 23 <8 02/05/10 02/26/10 <6 <7 < 13 <8 < 17 <8 < 13 < 12 <7 <8 < 37 < 10 03/05/10 03/26/10 <1 <1 <3 <1 <3 <2 <3 <7 <1 <1 < 13 <4 04/02/10 04/30/10 <2 <2 <4 <2 <3 <2 <3 < 11 <2 <2 < 19 <6 05/07/10 05/28/10 <2 <2 <4 <2 <3 <2 <4 < 11 <2 <2 < 18 <6 06/04/10 06/25/10 <4 <5 < 12 <5 < 12 <6 < 10 <8 <5 <6 < 26 <9 07/03/10 07/30/10 <3 <3 <7 <3 <6 <4 <7 <9 <3 <3 < 19 <5 08/06/10 08/27/10 <1 <2 <4 <1 <3 <2 <3 <9 <1 <2 < 15 <5 09/03/10 09/24/10 <3 <4 <8 <3 <8 <4 <7 < 11 <3 <4 < 25 <8 10/01/10 10/29/10 <4 <4 <9 <5 < 10 <5 <7 < 13 <5 <4 < 29 <11 11/05/10 11/26/10 <4 <6 <8 <5 < 12 <6 < 11 < 12 <6 <7 < 26 <7 12/03/10 12/31/10 <5 <7 < 13 <8 < 13 <5 < 12 < 11 <6 <6 < 31 <9 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION
TABLE C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 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 D-57 01/01/10 - 01/29/10 <6 <8 < 12 <7 < 14 <5 < 10 <9 <5 <6 < 29 <8 01/29/10 - 02/26/10 <4 <4 <7 <4 <8 <4 <7 <7 <4 <4 < 18 <7 02/26/10 - 03/26/10 <2 <2 <5 <2 <4 <2 <4 < 10 <2 <2 < 19 <6 03/26/10 - 04/30/10 <2 <2 <4 <2 <3 <2 <4 < 13 <2 <2 < 20 <6 04/30/10 - 05/28/10 <2 <2 <4 <2 <3 <2 <3 < 10 <2 <2 < 17 <5 05/28/10 - 06/25/10 <4 <4 <9 <4 <7 <4 <7 <7 <4 <4 < 20 <5 06/25/10 - 07/30/10 <3 <4 <9 <3 <7 <4 <7 < 10 <3 <3 < 23 <9 07/30/10 - 08/27/10 <2 <2 <4 <2 <4 <2 <4 < 11 <2 <2 < 20 <6 08/27/10 - 09/24/10 <3 <6 < 10 <4 < 10 <5 <9 < 15 <4 <5 < 28 <9 09/24/10 - 10/29/10 <5 <4 <11 <5 <9 <5 <9 < 12 <4 <4 < 29 < 11 10/29/10 - 11/26/10 <5 <4 <9 <5 < 11 <5 <8 < 10 <5 <5 < 25 <9 11/26/10 - 12/31/10 <5 <5 < 14 <5 < 13 <7 < 10 < 12 <6 <7 < 30 <9 MEAN
TABLE C-I1.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION D-23 D-35 PERIOD 01108/10 - 01/08/10 267 +/- 116 < 168 02/12/10 - 02/12/10 311 +/- 118 03/12/10 - 03/12/10 297 +/- 113 04/09/10 - 04/09/10 363 +/- 118 < 160 05/14/10 - 05/14/10 228 +/- 116 06/11/10 - 06/11/10 400 +/- 118 07/09/10 - 07/09/10 351 +/- 116 < 160 08/13/10 - 08/13/10 216 +/- 118 09/10/10 - 09/10/10 360 +/- 126 10/08/10 - 10/08/10 238 +/- 117 < 178 11/12/10 - 11/12/10 264 +/- 114 12/10/10 - 12/10/10 317 +/- 111 MEAN 301 +/- 119 C-4
TABLES C-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 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 D-23 01/08/10 - 01/08/ 10 <3 <4 <8 <3 <7 <4 6 < 15 <3 <3 < 30 < 10 02/12/10 - 02/12/ 10 <4 <4 <9 <4 <8 <4 9 < 12 <4 <4 < 26 <9 03/12/10 - 03/12/ 10 <5 <4 <9 <4 <9 <5 9 < 12 <5 <5 < 27 <7 04/09/10 - 04/09/ 10 <3 <3 <6 <3 <5 <3 6 <8 <3 <3 < 18 <7 05/14/10 - 05/14/ 10 <1 <1 <3 <1 <2 <1 2 < 12 <1 <1 < 16 <5 06/11/10 - 06/11/ 10 <5 <4 <9 <4 < 10 <5 8 < 11 <5 <5 < 26 <8 07/09/10 - 07/09/ 10 <5 <5 < 11 <5 < 10 <6 8 <9 <5 <5 < 24 <7 08/13/10 - 08/13/ 10 <3 <4 <8 <3 <7 <4 6 <8 <3 <3 < 23 <8 09/10/10 - 09/10/ 10 <4 <5 <9 <4 <8 <4 7 < 10 <4 <4 < 26 <8 10/08/10 - 10/08/ 10 <6 <5 < 10 <4 <8 <6 10 <9 <5 <4 < 24 <6 11/12/10 - 11/12/ 10 <4 <5 <9 <4 <9 <5 7 < 11 <4 <4 < 25 <7 12/10/10 - 12/10/ 10 <7 <6 < 13 <7 < 14 <7 9 < 11 <5 <5 < 26 < 12 MEAN
( D-35 01/08/10 01/08/10 <3 <4 <9 <3 <7 <3 <6 < 14 <3 <4 < 28 11 04/09/10 04/09/10 <3 <3 <7 <3 <6 <4 <5 <9 <3 <3 < 21 6 07/09/10 07/09/10 <4 <5 < 10 <4 <9 <5 <8 <8 <4 <4 < 22 8 10108/10 10/08/10 <5 <4 < 10 <6 < 10 <5 <8 <8 <5 <6 < 26 7 MEAN
TABLE C-I11.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-1 34 Cs-1 37 Ba-140 La-140 PERIOD D-28 Freshwater Drum 05/17/10 < 31 < 47 < 127 33 < 76 <48 < 84 < 33 < 41 < 914 < 241 Largemouth Bass 05/17/10 < 50 < 66 < 170 50 < 73 < 65 < 127 < 47 < 56 < 1120 < 333 Largemouth Bass 10/11/10 < 72 <74 < 144 82 < 153 < 93 < 129 < 67 < 73 < 375 < 139 Channel catfish 10/12/10 < 18 < 17 < 44 23 < 47 < 15 < 31 < 19 < 20 < 101 < 14 MEAN D-46 Common Carp 05/17/10 < 40 <44 < 100 38 < 75 57 < 76 < 27 < 32 < 891 < 263 Largemouth Bass 05/17/10 < 55 < 73 < 177 35 < 109 80 < 139 < 49 < 55 < 1350 < 458 Channel catfish 10/11/10 < 63 < 49 < 128 56 < 134 84 < 94 < 52 <64 < 334 < 121 Largemouth Bass 10/11/10 < 70 < 78 < 148 84 < 163 89 < 129 < 72 < 76 < 422 < 131 MEAN
TABLE C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PC/KG DRY +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-27 05/28/10 < 25 <32 <83 <28 <63 <26 < 62 < 26 < 39 < 432 < 136 10/08/10 < 40 <36 < 78 < 39 < 77 < 47 < 64 < 33 57 +/-34 < 226 < 63 MEAN
TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION GROUP I IGROUP 11 PERIOD D-01 D-02 D-03 D-04 D-07 0-45 D-53 D-56 01/01/10 - 01/08/10 33 +/-4 25 +/-4 27 +/-4 30 +/-4 31 +/-4 29 +/-4 28 +/-4 30+/- 4 01/08/10 - 01/15/10 26 +/-5 28 +/-5 26 +/-5 31 +/-5 24 +/-4 22 +/-4 25 +/-5 28 +/-5 01/15/10 - 01/22/10 23 +/-4 42 +/-5 30 +/-4 28 +/-4 28 +/-4 24 +/-4 25 +/-4 26+/- 4 01/22/10 - 01/29/10 15 +/-4 17 +/-4 23 +/-5 17 +/-4 17 +/-4 17 +/-4 20 +/-5 20 +/-5 01/29/10 -02/05/10 27 +/-5 28 +/-5 25 +/-5 28 +/-5 27 +/-5 26 +/-5 27 +/-5 28+/- 5 02/05/10 - 02/12/10 14 +/-4 15 +/-4 14 +/-4 10 +/-4 19 +/-4 18 +/-4 16 +/-4 13+/- 4 02/12/10 - 02/19/10 15 +/-4 17 +/-4 17 +/-4 16 +/-4 20 +/-4 16 +/-4 19 +/-4 15 +/-4 02/19/10 -02/26/10 20 +/-4 20 +/-4 22 +/-4 22 +/-4 17 +/-4 24 +/-4 22 +/-4 22+/-4 02/26/10 - 03/05/10 8 +/-4 9 +/-4 7 +/-4 12 +/-4 10 +/-4 12 +/-4 13 +/-4 8+/-4 03/05/10 -03/12/10 12 +/-4 14 +/-4 18 +/-4 9 +/-4 14 +/-5 (1) 14 +/-4 16 +/-4 16+/-4 03/12/10 - 03/19/10 8 +/-4 10 +/- 4 10 +/- 4 12 +/- 4 16 +/- 6 (1) 12 +/- 4 8 +/-4 11 +/-4 03/19/10 - 03/26/10 18 +/-5 13 +/-5 17 +/-5 15 +/-5 17 +/-5 16 +/-5 18+/-5 12+/-5 03/26/10 -04/02/10 17 +/-5 14 +/-4 19 +/-5 16 +/-4 15 +/-4 (1) 15 +/-4 13+/-4 19+/-5 04/02/10 - 04/09/10 8 +/- 4 7 +/- 4 6 +/- 4 10 +/- 4 10 +/- 4 9 +/-4 8 +/-4 11 +/-4 04/09/10 - 04/16/10 20 +/-5 20 +/-4 18 +/-4 18 +/-4 21 +/-4 24+/-5 20+/-4 22+/-5 04/16/10 - 04/23/10 10 +/- 4 12 +/- 4 14 +/- 4 13 +/- 4 14 +/- 4 11 +/-4 12 +/-4 13 +/- 4 04/23/10 - 04/30/10 14 +/-4 12 +/-4 (1) 14 +/-4 (1) 13 +/-4 12 +/-4 (1) 14+/-4 12+/-4 15 +/-4 04/30/10 - 05/07/10 7 +/-4 11 +/-4 9 +/-4 10 +/-4 11 +/-4 12+/-5 11+/-4 6+/-4 05/07/10 - 05/14/10 8 +/-4 9 +/-4 7 +/-3 7 +/-3 10 +/-4 9+/-4 10 +/-4 12+/-4 05/14/10 - 05/21/10 10 +/-4 11 +/-4 13 +/-4 16 +/-4 15 +/-4 12+/-4 12 +/-4 12+/-4 05/21/10 - 05/28/10 13 +/-4 (1) 14 +/-4 14 +/-4 17 +/-4 16 +/-4 16 +/-4 15 +/-4 17+/-4 05/28/10 - 06/04/10 9 +/- 6 11 +/- 6 12 +/- 6 12 +/- 6 <8 12 +/- 6 11 +/- 6 10 +/-6 06/04/10 - 06/11/10 16 +/-4 14 +/-4 15 +/-4 14 +/-4 16 +/-4 14 +/-4 10 +/-4 14+/-4 06/11/10 - 06/18/10 12 +/- 4 15 +/- 4 11 +/- 4 12 +/- 4 11 +/- 4 13 +/- 4 11 +/- 4 13 +/-4 06/18/10 - 06/25/10 13 +/-4 12 +/-4 12 +/-4 14 +/-4 16 +/-4 13 +/-4 17 +/-4 12+/-4 06/25/10 - 07/03/10 9 +/-3 10 +/-3 13 +/-4 10 +/-3 12 +/-4 12 +/-4 11 +/-4 13+/-4 07/03/10 - 07/09/10 16 +/-5 21 +/-5 21 +/-5 20 +/-5 20 +/-5 18 +/-5 18 +/-5 21+/-5 07/09/10 - 07/16/10 21 +/- 4 21 +/- 4 20 +/-4 22 +/-4 24 +/-4 20 +/-4 21 +/- 4 21 +/-4 07/16/10 - 07/23/10 20 +/-4 20 +/-4 20 +/-5 20 +/-4 20 +/-5 20 +/-4 12 +/-4 21+/-5 07/23/10 - 07/30/10 13 +/-4 15 +/-4 47 +/-19 (1) 14 +/-4 14 +/-4 15 +/-4 14 +/-4 21+/-5 07/30/10 - 08/06/10 17 +/-4 20 +/-5 22 +/-5 20 +/-5 25 +/-5 22 +/-5 18 +/-4 21+/-5 08/06/10 - 08/13/10 23 +/-4 31 +/-5 23 +/-4 20 +/-4 26 +/-4 28 +/-4 25 +/-4 26+/-4 08/13/10 -08/20/10 24 +/-5 20 +/-5 24 +/-6 (1) 22 +/-5 (1) 22 +/-5 23 +/-5 20 +/-5 28+/-5 08/20/10 - 08/27/10 17 +/-5 17 +/-4 16 +/-4 (1) 16 +/-4 17 +/-5 20 +/-5 18 +/-5 17+/-5 08/27/10 - 09/03/10 19 +/-4 21 +/-4 22 +/-5 (1) 20 +/-4 19 +/-4 20 +/-4 15 +/-4 16+/-4 09/03/10 - 09/10/10 12 +/-4 12 +/-4 15 +/-4 13 +/-4 16 +/-4 14 +/-4 13+/-4 13+/-4 09/10/10 - 09/17/10 17 +/-4 19 +/-4 26 +/-6 (1) 19 +/-4 18 +/-4 18 +/-4 21+/-4 13+/-4 09/17/10 - 09/24/10 18 +/-4 22 +/-5 15 +/-4 19 +/-4 21 +/-5 24 +/-5 22+/-5 20+/- 4 09/24/10 - 10/01/10 13 +/-4 14 +/-4 16 +/-4 13 +/-4 17 +/-4 18 +/-4 18+/-4 15+/- 4 10/01/10 - 10/08/10 16 +/-4 18 +/-4 18 +/-4 14 +/-4 14 +/-4 17 +/-5 18+/-4 17+/- 4 10/08/10 - 10/15/10 36 +/-5 35 +/-5 36 +/-5 36 +/-5 39 +/-5 38 +/-5 39+/-6 40+/- 6 10/15/10 - 10/22/10 21 +/- 4 17 +/-4 17 +/-4 19 +/-4 17 +/-4 20 +/-4 16+/-4 20+/- 4 10/22/10 - 10/29/10 14 +/-4 15 +/-4 13 +/-4 15 +/-4 16 +/-4 16 +/-4 10+/-4 15+/- 4 10/29/10 - 11/05/10 13 +/-3 12 +/-3 12 +/-3 16 +/-3 11 +/- 3 13 +/-3 13+/-3 12+/-3 11/05/10 - 11/12/10 23 +/-5 21 +/-4 18 +/-4 18 +/-4 23 +/-5 20 +/-4 20+/-4 22+/-5 11/12/10 - 11/19/10 24 +/- 5 22 +/- 5 25 +/- 5 24 +/- 5 23 +/- 5 19 +/- 4 19 +/-5 21 +/-5 11/19/10 - 11/26/10 20 +/- 5 20 +/- 5 24 +/- 5 22 +/- 5 21 +/- 5 25 +/- 5 20 +/-4 20 +/-4 11/26/10 - 12/03/10 26 +/- 4 28 +/- 4 23 +/- 4 32 +/- 4 31 +/- 4 29 +/- 4 24 +/-4 27 +/-4 12/03/10 - 12/10/10 26 +/-5 26 +/-5 26 +/-5 29 +/-5 25 +/-5 28 +/-5 27+/-5 33+/-5 12/10/10 -12/17/10 25 +/-4 29 +/-4 22 +/-4 31 +/- 4 29 +/-4 26 +/-4 21 +/-4 27+/-4 12/17/10 -12/24/10 31 +/- 4 32 +/-4 34 +/-4 38 +/-4 35 +/-4 28 +/-4 35+/-4 32+/-4 12/24/10 -12/31/10 14 +/-4 16 +/-4 12 +/-4 12 +/-4 12 +/-4 17 +/-4 14+/-4 15 +/-4 MEAN 17 +/-14 18 +/-15 19 +/-15 18 +/-14 19 +/-13 19 +/-12 18+/-13 19 +/-14
- THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES.
(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-8
TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP III I GROUP IV PERIOD D-08 D-10 D-14 D-55 D-12 U
u IU i/lU uiloIUOI 27 +/-4 31 +/- 4 26 +/-4 28 4 01/08/10 01/15/10 31 +/- 5 26 +/- 5 23 +/- 4 26 +/-5 26 +/-5 01/15/10 01/22/10 33 +/- 4 30 +/- 4 30 +/- 4 32 +/-4 29 +/-4 01/22/10 01/29/10 22 +/- 5 19 +/- 5 17 +/-4 18 +/-4 21 +/-5 01/29/10 02/05/10 27 +/- 5 28 +/- 5 25 +/-5 22 +/-5 26 +/-5 02/05/10 02/12/10 16 +/- 4 15 +/- 4 15 +/-4 17 +/-4 14 +/- 4 02/12/10 02/19/10 23 +/- 5 16 +/- 4 16 +/-4 18 +/-4 14 +/- 4 02/19/10 02/26/10 24 +/- 4 23 +/- 4 22 +/-4 21 +/-4 19 +/- 4 02/26/10 03/05/10 8+/-4 7+/-4 6+/-4 8+/-4 8+/-4 03/05/10 03/12/10 16 +/-4 11 +/-4 12 +/-4 10 +/-4 11 +/-4 03/12/10 03/19/10 10 +/-4 11 +/-4 11 +/-4 13 +/-4 10 +/-4 03/19/10 03/26/10 18 +/-5 14 +/-5 15 +/-5 19 +/-5 22 +/-6 03/26/10 04/02/10 21 +/-5 19 +/-5 14 +/-4 10 +/-4 18 +/-5 04/02/10 04/09/10 8+/-4 6+/-4 7+/-4 6+/-4 <6 04/09/10 04/16/10 21 +/-4 20 +/-4 20 +/-4 21 +/-5 18 +/-4 04/16/10 04/23/10 14 +/-4 12 +/-4 12 +/- 4 11 +/-4 11 +/-4 04/23/10 04/30/10 18 +/-4 14 +/-4 14 +/- 4 13 +/-4 15 +/- 4 04/30/10 05/07/10 10 +/-4 10 +/-4 <6 8+/-4 <6 05/07/10 05/14/10 9+/-4 9+/-4 12 +/- 4 9+/-4 10 +/- 4 05/14/10 05/21/10 12 +/-4 12 +/-4 11 +/-4 14 +/-4 13 +/- 4 05/21/10 05/28/10 14 +/-4 13 +/-4 13 +/-4 15 +/-4 15 +/- 4 05/28/10 06/04/10 <9 10 +/-6 13 +/-6 9+/-6 <9 06/04/10 06/11/10 14 +/-4 10 +/-4 16 +/-4 15 +/-4 13 +/- 4 06/11/10 06/18/10 17 +/-4 11 +/-4 9+/-4 11 +/-4 11 +/-4 06/18/10 06/25/10 13 +/-4 13 +/-4 13 +/-4 18 +/-4 14 +/-4 06/25/10 07/03/10 13 +/-4 12 +/-4 12 +/-4 12 +/-4 13 +/-4 07/03/10 07/09/10 16 +/-5 21 +/-5 16 +/-5 21 +/-5 19 +/-5 07/09/10 07/16/10 21 +/- 4 20 +/-4 19 +/-4 22 +/-4 19 +/-4 07/16/10 07/23/10 22 +/- 5 20 +/-4 21 +/-5 21 +/-5 21 +/-5 07/23/10 07/30/10 15 +/- 4 14 +/-4 18 +/-5 14 +/-4 17 +/-5 07/30/10 08/06/10 21 +/- 5 20 +/-5 21 +/-5 21 +/-5 22 +/-5 08/06/10 08/13/10 25 +/- 4 26 +/-4 23 +/-4 27 +/-4 21 +/-4 08/13/10 08/20/10 23 +/- 5 24 +/-5 20 +/-5 25 +/-5 23 +/-5 08/20/10 08/27/10 18 +/- 5 16 +/-5 18 +/-5 16 +/-4 16 +/-4 08/27/10 09/03/10 22 +/- 4 23 +/-5 18 +/-4 21 +/-4 22 +/-4 09/03/10 09/10/10 10 +/- 4 14 +/-4 14 +/-4 13 +/- 4 14 +/-4 09/10/10 09/17/10 19 +/- 4 21 +/-4 17 +/-4 21 +/- 4 19 +/-4 09/17/10 09/24/10 23 +/- 5 22 +/-5 18 +/-4 23 +/- 5 22 +/-5 09/24/10 10/01/10 18 +/- 4 17 +/-4 16 +/-4 18 +/- 4 16 +/-4 10/01/10 10/08/10 13 +/- 4 17 +/-4 14 +/-4 20 +/- 5 20 +/-5 10/08/10 10/15/10 40 +/- 6 36 +/-5 34 +/-5 37 +/- 5 40 +/-6 10/15/10 10/22/10 19 +/- 4 17 +/-4 20 +/-4 24 +/- 4 18 +/-4 10/22/10 10/29/10 12 +/- 4 15 +/-4 17 +/-4 17 +/- 4 22 +/-5 10/29/10 11/05/10 13 +/- 3 13 +/-3 10 +/-3 12 +/- 3 11 +/-3 11/05/10 11/12/10 18 +/- 4 19 +/-4 22 +/-5 22 +/- 5 19 +/-4 11/12/10 11/19/10 21 +/- 5 24 +/-5 21 +/-5 21 +/- 5 20 +/-5 11/19/10 11/26/10 21 +/- 5 26 +/-5 18 +/- 4 27 +/- 5 13 +/-4 11/26/10 12/03/10 27 +/- 4 30 +/-4 25 +/- 4 29 +/- 4 27 +/-4 12/03/10 12/10/10 28 +/- 5 32 +/-5 26 +/- 5 27 +/- 5 27 +/-5 12/10/10 12/17/10 26 +/- 4 27 +/-4 24 +/- 4 27 +/- 4 27 +/-4 12/17/10 12/24/10 35 +/- 4 36 +/-4 31 +/- 4 30 +/- 4 36 +/-4 12/24/10 12/31/10 15 +/- 4 16 +/-4 14 +/- 4 20 +/- 4 16 +/-4 MEAN 19 +/-14 19 +/-15 18 +/-12 19 +/-14 19 +/-13
- THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES.
C-9
TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP II - NEAR-FIELD LOCATIONS GROUP III - FAR-FIELD LOCATIONS GROUP IV- CONTROL LOCATION COLLECTION MIN MAX MEAN + COLLECTION MIN MAX MEAN + COLLECTION MIN MAX MEAN + COLLECTION MIN MAX MEAN +/-
PERIOD 2SD PERIOD 2SD PERIOD 2SD PERIOD 2SD UI/UI/1U - Ul2I9IU1 15 42 26 +/- 14 UiU1/i1U - UllVWiU 11 31 25:+/- 9 U1/U1110 - u1l2911U 17 33 26 +/- 11 01/01/10 - 01/29/10 21 29 25 +/- 6 01/29/10 - 02/26/10 14 28 20 +/- 10 01/29/10 - 02/26/10 10 28 20 +/- 10 01/29/10 - 02/26/10 15 28 20 +/- 9 01/29/10 - 02/26/10 14 26 18 +/- 12 02/26/10 - 04102110 7 19 13 +/- 8 02/26/10 - 04/02/10 8 19 13 +/- 6 02/26/10 - 04/02/10 6 21 12 9 02126/10 - 04/02/10 8 22 14 +/- 12 04102110 - 04/30/10 6 20 13 +/- 9 04/02/10 - 04/30/10 8 24 14 +/- 9 04/02/10 - 04/30/10 6 21 14 + 10 04/09/10 - 04/30/10 11 18 14 +/- 7 04/30/10 - 05/28/10 7 14 11 +5 04/30/10 - 05/28/10 6 17 12 +/- 6 04/30/10 - 05/28/10 8 15 11 +/-4 05/07/10 - 05/28/10 10 15 13 t 5 05/28/10 - 07/03/10 9 16 12 +4 05/28/10 - 07/03/10 10 17 13 +/- 4 05/28/10 - 07/03/10 9 18 13 5 06/04/10 - 07/03/10 11 14 13 +/- 3 07/03/10 - 07/30/10 13 47 21 + 17 07/03/10 - 07/30/10 12 24 19 +/- 7 07/03/10 - 07/30/10 14 22 19 6 07/03/10 - 07/30/10 17 21 19 +/- 4 07/30/10 - 09/03/10 16 31 21 +8 07/30/10 - 09/03/10 15 28 21 +/- 7 07/30/10 - 09/03/10 16 27 21 +/- 6 07/30/10 - 09/03/10 16 23 21 +/- 6 09/03/10 - 10/01/10 12 26 17 +9 09/03/10 - 10/01/10 13 24 17 +/- 7 09/03/10 - 10/01/10 10 23 18 +/- 7 09/03/10 - 10/01/10 14 22 18 +/- 7 10/01/10 - 10/29/10 13 36 21 + 18 10/01/10 - 10/29/10 10 40 22 +/- 20 10/01/10 - 10/29/10 12 40 22 +/-=19 10/01/10 - 10/29/10 18 40 25 +/- 20 10/29/10 - 12/03/10 12 28 21 +10 10/29/10 - 12/03/10 11 32 21 +/- 11 10/29/10 - 12/03/10 10 30 21 +/- 11 10/29/10 - 12103/10 11 27 18 +/- 13 12/03/10 - 12/31/10 12 34 24 :114 12/03/10 - 12/31/10 12 38 26 +/- 16 12/03/10 - 12/31/10 14 36 26 + 14 12/03/10 - 12/31/10 16 36 26 +/- 17 01/01/10 - 12/31/10 6 47 18 +/- 15 01/01/10 - 12/31/10 6 40 18 +/- 13 01/01/10 - 12/31/10 6 40 19 +/- 14 01/01/10 - 12/31/10 8 40 19 +/- 13 0
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-01 01/01/10 - 04/02/10 <2 <3 <8 <3 <7 <4 <8 <3 <2
- 131 < 63 04/02/10 - 07/03/10 <4 <3 <9 <4 <7 <4 <6 <3 <3 < 37 < 15 07/03/10 - 10/01/10 <3 <4 <8 <3 <9 <4 <9 <3 <3
- 113 < 46 10/01/10 - 12/31/10 <2 <2 <4 <2 <4 <3 <4 <2 <2 < 26 < 10 MEAN D-02 01/01/10 - 04/02/10 <3 <4 <8 <4 <10 <6 <7 <3 <3
- 172 < 85 04/02/10 - 07/03/10 <3 <5 <12 <4 <8 <5 <8 <4 <4 < 46
- 18 07/03/10 - 10/01/10 <2 <2 <6 <2 <5 <3 <5 <2 <1 < 63 < 22 10/01/10 - 12/31/10 <2 <2 <3 <2 <4 <2 <3 <1 <2 < 20 <11 MEAN
- D-03 01/01/10 - 04/02/10 <3 <4 <10 <3 <6 <4 <7 <2 <2
- 126 < 47 04/02/10 - 07/03/10 <3 <3 <6 <3 <6 <5 <6 <4 <3 < 46
- 17 07/03/10 - 10/01/10 <3 <5 <9 <3 <9 <5 <8 <4 <4
- 122 < 31 10/01/10 - 12/31/10 <3 <4 <9 <3 <8 <3 <7 <4 <3 < 33
- 14 MEAN D-04 01/01/10 - 04/02/10 <4 <5 <12 <4 <7 <6 <10 <3 <3
- 187 < 81 04/02/10 - 07/03110 <4 <5
- 14 <3 <6 <3 <6 <4 <4 < 55 < 20 07/03/10 - 10/01/10 <3 <3 <9 <2 <5 <3 <4 <2 <2 < 88 <34 10/01/10 - 12/31/10 <2 <2 <7 <2 <4 <1 <4 <2 <2 < 30 < 10 MEAN
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-07 01/01/10 - 04/02/10 <3 <2 <9 <3 <7 <3 <7 <3 <2
- 147
- 58 04/02/10 - 07/03/10 <4 <4
- 10 <5 < 12 <6 <8 <4 <3 < 62 < 21 07/03/10 - 10/01/10 <2 <5 < 15 <4 <9 <4 <7 <3 <3
- 114 < 42 10/01/10 - 12/31/10 <2 <2 <6 <3 <7 <3 <5 <2 <2 < 30 <8 MEAN D-08 01/01/10 - 04102/10 <2 <4 <11 <2 <6 <4 <7 <3 <2
- 119 < 60 04/02/10 - 07/03/10 <3 <4 <8 <3 <9 <5 <6 <3 <2 < 39
- 17 07/03/10 - 10/01/10 <3 <4 < 10 <5 <8 <5 <5 <3 <3
- 119 <44 10/01/10 - 12/31/10 <4 <3 <8 <3 <7 <4 <5 <3 <3 < 37
- 12 MEAN D-10 01/01/10 - 04/02/10 <2 <4 <11 <3 <7 <3 <6 <3 <2
- 124 < 42 04/02/10 - 07/03/10 <3 <5 <11 <4 <9 <5 <9 <3 <4 < 57
- 14 07/03110 - 10/01/10 <3 <3 <7 <2 <6 <4 <6 <2 <2 < 67 < 27 10/01/10 - 12/31/10 <3 <3 <7 <2 <8 <3 <5 <3 <3 < 36
- 16 MEAN D-12 01/01/10 - 04/02/10 <4 <5
- 17 <3 <9 <5 <8 <3 <3
- 183 < 62 04/02/10 - 07/03/10 <3 <5
- 10 <4 <7 <5 <8 <3 <4
- 51 < 24 07/03/10 - 10/01/10 <2 <3 <9 <3 <8 <4 <7 <3 <2 < 81 < 21 10/01/10 - 12/31/10 <2 <2 <6 <3 <7 <3 <5 <2 <2 < 29 < 11 MEAN
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-14 01/01/10 - 04/02/10 <3 <4 < 13 <3 <9 <4 <7 <3 <2 < 145 < 43 04/02/10 - 07/03/10 <3 <3 <9 <4 <8 <3 <5 <3 <4 < 57 < 22 07/03/10 - 10/01/10 <3 <4 < 11 <3 <7 <4 <7 <3 <3 < 95 < 41 10/01/10 - 12/31/10 <2 <3 <7 <3 <6 <3 <4 <2 <2 < 32 < 15 MEAN D-45 01/01/10 - 04/02/10 <4 <4 < 13 <2 <7 <5 < 10 <3 <2 < 191 < 72 04/02/10 - 07/03/10 <4 <5 < 13 <3 < 10 <6 < 10 <4 <3 < 68 < 16 07/03/10 - 10/01/10 <4 <4 <8 <3 <7 <4 <8 <3 <3 < 108 < 31 10/01/10 - 12/31/10 <3 <4 <9 <2 <8 <4 <6 <3 <3 < 41 <9 MEAN D-53 01/01/10 - 04/02/10 <3 <3 < 11 <3 <6 <4 <6 <3 <2 < 93 < 47 04/02/10 - 07/03/10 <4 <4 < 12 <3 <9 <4 <9 <4 <4 < 56 < 27 07/03/10 - 10/01/10 <2 <4 <9 <2 <5 <4 <5 <2 <2 < 79 < 31 10/01/10 - 12/31/10 <2 <3 <4 <3 <5 <2 <4 <2 <2 < 27 < 10 MEAN D-55 01/01/10 - 04/02/10 <4 <6 < 16 <2 <8 <6 <8 <3 <3 < 171 < 70 04/02/10 - 07/03/10 <4 <4 < 14 <4 <9 <5 <6 <4 <4 <64 < 16 07/03/10 - 10/01/10 <3 <3 <8 <3 <7 <4 <8 <3 <3 < 91 < 30 10/01/10 - 12/31/10 <3 <3 <6 <3 <6 <4 <6 <3 <3 < 41 < 11 MEAN
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-56 01/01/10 - 04/02/10 <4 <6 <16 <5 <9 <6 <9 <4 <4 <1919 < 42 04/02/10 - 07/03/10 <3 <4 <11 <4 <8 <5 <8 <3 <3 <41 < 27 07/03/10 - 10/01/10 <2 <4 <10 <2 <7 <4 <6 <3 <3 <82 < 41 10/01/10 - 12/31/10 <2 <2 <2 <2 <3 <1 <4 <1 <2 <21 <7 MEAN
TABLE C-Vl.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I I GROUP II COLLECTION PERIOD D-01 D-02 D-03 D-04 D-07 D-45 D-53 D-56 01/01/10 - 01/08/10 < 26 < 49 < 49 < 48 < 49 < 48 < 26 < 60 01/08/10 - 01/15/10 < 30 < 29 < 30 < 30 < 42 < 36 < 15 < 35 01/15/10 - 01/22/10 < 43 < 24 < 43 < 43 < 43 < 36 < 31 < 31 01/22/10 - 01/29/10 < 14 < 25 < 26 < 26 < 26 < 36 < 57 < 56 01/29/10 - 02/05/10 < 32 < 32 < 18 < 32 < 32 < 33 < 32 < 32 02/05/10 - 02/12/10 < 28 < 38 < 38 < 38 < 38 < 30 < 30 < 30 02/12/10 - 02/19/10 < 23 < 23 < 23 < 10 < 23 < 28 < 27 < 27 02/19/10 - 02/26/10 < 14 < 26 < 26 < 26 < 26 < 28 < 28 < 27 02/26/10 - 03/05/10 < 21 < 21 < 21 < 21 < 12 < 36 < 35 < 35 03/05/10 - 03/12/10 < 15 < 28 < 27 < 27 < 30 (1) < 29 < 29 < 29 03/12/10 - 03/19/10 < 29 < 29 < 29 < 29 < 25 (1) < 28 < 24 < 24 03/19/10 - 03/26/10 < 13 < 24 < 24 < 24 < 24 < 30 < 29 < 29 03/26/10 - 04/02/10 < 26 < 26 < 26 < 26 < 36 (1) < 28 < 28 < 28 04/02/10 - 04/09/10 < 30 < 30 < 30 < 30 < 15 < 36 < 35 < 35 04/09/10 - 04/16/10 < 30 < 29 < 29 < 29 < 28 < 27 < 26 < 26 04/16/10 - 04/23/10 <6 < 11 < 11 < 11 < 11 < 14 < 14 < 14 04/23/10 - 04/30/10 < 26 < 27 (1) < 27 (1) < 26 < 38 (1) < 27 < 29 < 29 04/30/10 - 05/07/10 < 16 < 30 < 30 < 30 < 30 < 42 < 39 < 39 05/07/10 - 05/14/10 < 22 < 22 < 22 < 22 < 30 <5 < 12 < 12 05/14/10 - 05/21/10 < 14 < 26 < 26 < 26 < 26 < 39 < 38 < 38 05/21/10 - 05/28/10 <24 (1) < 25 < 25 < 24 < 30 < 35 < 13 <34 05/28/10 - 06/04/10 < 20 < 36 < 36 < 36 < 36 < 34 < 32 < 32 06/04/10 - 06/11/10 < 49 < 50 < 50 < 49 < 51 < 33 < 32 < 32 06/11/10 - 06/18/10 < 17 < 31 < 31 < 31 < 32 < 26 < 26 < 25 06/18/10 - 06/25/10 < 24 < 24 < 24 < 24 < 26 < 24 < 24 < 13 06/25/10 - 07/03/10 < 22 < 29 < 28 < 29 < 29 < 37 < 36 < 36 07/03/10 - 07/09/10 < 17 < 40 < 40 < 40 < 40 < 45 < 44 < 44 07/09/10 - 07/16/10 < 15 < 24 < 24 < 24 < 24 < 27 < 26 < 26 07/16/10 - 07/23/10 < 27 < 15 < 27 < 27 < 27 < 26 < 26 < 26 07/23/10 - 07/30/10 < 16 < 26 < 65 (1) < 26 < 26 < 26 < 26 < 26 07/30/10 - 08/06/10 < 31 < 17 < 31 < 31 < 31 < 42 < 38 < 38 08/06/10 - 08/13/10 < 19 < 44 < 35 < 35 < 35 < 49 < 48 < 48 08/13/10 - 08/20/10 < 21 < 21 < 26 (1) < 9 (1) < 21 < 23 < 22 < 22 08/20/10 - 08/27/10 < 28 < 28 < 28 (1) < 28 < 16 < 23 < 22 < 22 08/27/10 - 09/03/10 < 26 < 26 < 33 (1) < 26 < 11 < 25 < 25 < 25 09/03/10 - 09/10/10 < 17 < 40 < 40 < 40 < 41 < 40 < 38 < 38 09/10/10 - 09/17/10 < 29 < 29 < 36 (1) < 29 < 45 < 35 < 35 < 36 09/17/10 - 09/24/10 < 14 < 25 < 25 < 25 < 26 < 19 < 18 < 18 09/24/10 - 10/01/10 < 46 < 46 < 46 < 46 < 44 < 36 < 39 < 39 10/01/10 - 10/08/10 < 25 < 46 < 46 < 46 < 46 < 52 < 47 < 46 10/08/10 - 10/15/10 < 58 < 58 < 58 < 56 < 58 < 51 < 51 < 51 10/15/10 - 10/22/10 < 42 < 42 < 42 < 42 < 48 < 40 < 39 < 17 10/22/10 - 10/29/10 < 27 < 27 < 27 < 27 < 32 < 44 < 43 < 42 10/29/10 - 11/05/10 < 52 < 52 < 52 < 50 < 67 < 61 < 60 < 25 11/05/10 - 11/12/10 < 44 < 44 < 44 < 44 < 50 < 22 < 51 < 50 11/12/10 - 11/19/10 < 34 < 34 < 34 < 34 < 39 < 36 < 36 < 19 11/19/10 - 11/26/10 < 33 < 33 < 33 < 33 < 50 < 65 < 28 < 64 11/26/10 - 12/03/10 < 44 < 44 < 44 < 44 < 60 < 65 <64 < 27 12/03/10 - 12/10/10 < 50 < 50 < 50 < 50 < 50 < 50 < 51 < 51 12/10/10 - 12/17/10 < 35 < 64 < 64 < 64 < 66 < 62 < 60 < 60 12/17/10 - 12/24/10 < 67 < 67 < 67 < 67 < 59 < 69 < 69 < 38 12/24/10 - 12/31/10 < 36 < 60 < 60 < 60 < 62 < 60 < 59 < 59 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-15
TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP III I GROUP IV COLLECTION PERIOD D-08 D-10 D-14 D-55 D-12 01/01/10 - 01/08/10 < 20 < 48 < 48 < 60 < 47 01/08/10 - 01/15/10 < 45 < 45 < 36 < 36 < 45 01/15/10 - 01/22/10 < 15 < 35 < 36 < 32 < 36 01/22/10 - 01/29/10 < 15 < 36 < 36 < 57 < 36 01/29/10 - 02/05/10 < 35 < 35 < 35 < 33 < 35 02/05/10 - 02/12/10 < 23 < 24 < 24 < 30 < 24 02/12/10 - 02/19/10 < 29 < 29 < 30 < 28 < 29 02119/10 - 02/26/10 < 25 < 25 < 26 < 28 < 25 02/26/10 - 03/05/10 < 30 < 30 < 31 < 36 < 30 03/05/10 - 03/12/10 < 30 < 30 < 30 < 30 < 30 03/12/10 - 03/19/10 < 17 < 28 < 28 < 24 < 28 03/19/10 - 03/26/10 < 32 < 32 < 32 < 30 < 32 03/26/10 - 04/02/10 < 36 < 15 < 37 < 28 < 36 04/02/10 - 04/09/10 < 28 < 28 < 27 < 36 < 28 04/09/10 - 04/16/10 < 28 < 28 < 29 < 27 < 12 04/16/10 - 04/23/10 < 10 < 10 < 10 < 14 < 10 04/23/10 - 04/30/10 < 36 < 35 < 15 < 27 < 35 04/30/10 - 05/07/10 < 50 < 50 < 51 < 42 < 51 05/07/10 - 05/14/10 < 30 < 30 < 13 < 13 < 30 05/14/10 - 05/21/10 < 34 < 34 < 34 < 39 < 35 05/21/10 - 05/28/10 < 30 < 30 < 35 < 35 < 30 05/28/10 - 06/04/10 < 40 < 40 < 40 < 33 < 40 06/04/10 - 06/11/10 < 51 < 51 < 33 < 27 < 51 06/11/10 - 06/18/10 < 34 < 34 < 34 < 26 < 34 06/18/10 - 06/25/10 < 26 < 26 < 24 < 24 < 26 06/25/10 - 07/03/10 < 31 < 31 < 31 < 37 < 31 07/03/10 - 07/09/10 < 22 < 22 < 22 < 45 < 22 07/09/10 - 07/16/10 < 22 < 22 < 22 < 26 < 22 07/16/10 - 07/23/10 < 38 < 38 < 38 < 26 < 38 07/23/10 - 07/30/10 < 27 < 27 < 27 < 26 < 27 07/30/10 - 08/06/10 < 18 < 42 < 42 < 39 < 42 08/06/10 - 08/13/10 < 44 < 43 < 44 < 49 < 44 08/13/10 - 08/20/10 < 16 < 16 < 16 < 23 < 16 08/20/10 - 08/27/10 < 22 < 22 < 22 < 23 < 22 08/27/10 - 09/03/10 < 21 < 21 < 21 < 25 < 21 09/03/10 - 09/10/10 < 32 < 32 < 32 < 40 < 32 09/10/10 - 09/17/10 < 19 < 45 < 45 < 35 < 45 09/17/10 - 09/24/10 < 33 < 32 < 33 < 19 < 33 09/24/10 - 10/01/10 < 41 < 18 < 41 < 36 < 42 10/01/10 - 10/08/10 < 68 < 68 < 70 < 52 < 67 10/08/10 - 10/15/10 < 58 < 56 < 58 < 51 < 28 10/15/10 - 10/22/10 < 48 < 48 < 41 < 40 < 48 10/22/10 - 10/29/10 < 32 < 32 < 25 < 44 < 32 10/29/10 - 11/05/10 < 67 < 67 < 64 < 61 < 67 11/05/10 - 11/12/10 < 52 < 52 < 52 < 52 < 52 11/12/10 - 11/19/10 < 39 < 39 < 37 < 36 < 39 11/19/10 - 11/26/10 < 50 < 50 < 65 < 65 < 50 11/26/10 - 12/03/10 < 60 < 60 < 65 < 65 < 60 12/03/10 - 12/10/10 < 50 < 49 < 52 < 28 < 50 12/10/10 - 12/17/10 < 63 < 63 < 64 < 62 < 64 12/17/10 - 12/24/10 < 63 < 63 < 69 < 69 < 63 12/24/10 - 12/31/10 < 68 < 68 < 70 < 59 < 68 MEAN C-16
TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION CONTROLFARM PERIOD D-25 01/08/10 < 0.2 02/04/10 < 0.6 03/04/10 < 0.7 04/01/10 < 0.5 05/06/10 < 0.9 05/20/10 < 0.6 06/04/10 < 0.5 06/17/10 < 0.9 07/03/10 < 0.7 07/15/10 < 0.6 07/29/10 < 0.6 08/11/10 < 0.9 08/26/10 < 0.9 09/09/10 < 0.7 09/23/10 < 0.6 10/07/10 < 0.7 10/21/10 < 1.0 11/04/10 < 0.8 12/02/10 < 0.4 MEAN C-17
TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-1 37 Ba-140 La-140 PERIOD D-25 01/08/10 <8 <8 < 16 <9 < 18 < 11 < 13 <7 <7 < 30 < 12 02/04/10 <5 <6 < 11 <6 < 14 <6 < 11 <5 <5 < 23 <7 03/04/10 <4 <4 < 10 <5 <9 <5 <8 <4 <5 <21 <6 04/01/10 <7 <7 < 16 <6 < 13 <8 < 12 <7 <7 < 36 <9 05/06/10 <8 <8 < 13 <9 < 15 <8 < 16 <7 <9 < 47 <15 05/20/10 <2 <2 <6 <2 <4 <2 <4 <2 <2 < 32 <8 06/04/10 <6 <8 < 20 <9 < 17 <8 < 11 <6 <8 < 40 < 14 06/17/10 <5 <5 < 11 <4 < 10 <6 < 11 <5 <6 < 38 < 10 07/03/10 <5 <5 < 13 <5 < 11 <6 <9 <5 <5 < 25 <7 07/15/10 <8 <7 < 16 <6 < 15 <7 < 12 <7 <8 < 31 <8 07/29/10 <5 <6 < 12 <5 < 11 <6 < 10 <5 <5 < 48 < 14 08/11/10 <6 <6 < 15 <6 < 14 <6 <9 <6 <6 < 39 <7 I) 08/26/10 <5 <5 < 12 <5 < 13 <6 <9 <4 <5 < 46 < 13 00 09/09/10 <6 <7 < 17 <7 < 13 <7 < 12 <6 <6 < 53 < 14 09/23/10 <5 <5 < 13 <7 < 12 <5 < 10 <5 <6 < 24 <8 10/07/10 <6 <6 < 12 <7 < 14 <7 < 10 <5 <6 < 30 < 10 10/21/10 <5 <4 < 10 <6 < 11 <4 <8 <4 <5 < 23 <7 11/04/10 <6 <7 < 17 <9 < 16 <7 < 12 <5 <6 < 39 < 14 12/02/10 <7 <7 < 17 <9 < 16 <8 < 12 <6 <6 <44 < 13 MEAN
TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/KG WET +/- 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 D-CONTROL Cabbage 09/11/10 < 11 < 11 < 32 < 14 < 25 < 11 < 20 <51 < 10 < 10 <98 < 23 Sweet potatoes 09/11/10 < 11 < 15 < 39 < 18 < 32 < 14 < 26 < 55 < 11 < 13 < 111 < 28 MEAN D-QUAD 1 Cabbage 09/05/10 < 10 < 11 <23 < 12 <23 < 13 <20 <43 <9 < 11 <87 < 23 Potatoes 09/11/10 < 11 < 13 <29 < 17 <31 < 15 < 19 <58 < 11 < 14 <97 < 26 MEAN I- D-QUAD 2 Cabbage 09/05/10 < 10 < 11 <29 < 11 < 27 < 13 < 18 <46 <9 < 11 < 79 < 29 Beets 09/11/10 < 11 < 10 <31 < 14 <26 < 11 <20 <45 <9 < 10 < 84 < 20 MEAN D-QUAD 3 Broccoli 09/05/10 < 12 < 12 <30 < 14 <28 < 13 <22 <49 < 10 < 11 < 99 < 25 Potatoes 09/11/10 < 11 < 11 < 30 < 15 <27 < 13 < 20 <47 < 11 < 11 < 97 < 24 MEAN D-QUAD 4 Cabbage 09/05/10 < 11 < 14 <30 < 14 <26 < 14 <27 <52 < 10 < 13 < 115 < 31 Potatoes 09/11/10 <8 < 10 <22 < 11 <21 < 10 < 16 <37 <8 <9 < 75 < 20 MEAN
TABLE C-IX.1 QUARTERLY TLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT- DEC CODE +/-2S.D.
u-u1-1 26.0 +/- 3.3 28 26 24 26 D-01-2 25.3 +/- 4.4 26 26 22 27 D-02-1 25.8 +/- 3.4 28 24 25 26 D-02-2 26.8 +/- 3.8 28 27 24 28 D-03-1 22.0 +/- 1.6 22 23 21 22 D-03-2 22.3 +/- 1.0 23 22 22 22 D-04-1 25.8 +/- 1.0 26 26 25 26 D-04-2 24.5 +/- 1.2 25 24 24 25 D-07-1 24.8 +/- 4.1 27 22 25 25 D-07-2 22.8 +/- 4.4 24 22 20 25 D-08-1 25.0 +/- 5.2 26 22 24 28 D-08-2 24.3 +/- 1.0 24 25 24 24 D-10-1 24.3 +/- 2.5 26 24 23 24 D-10-2 25.0 +/- 2.8 25 24 24 27 D-12-1 23.0 +/- 3.3 23 21 23 25 D-12-2 21.5 +/- 3.8 23 23 19 21 D-14-1 22.5 +/- 3.5 22 21 22 25 D-14-2 23.5 +/- 3.8 22 24 22 26 D-45-1 26.0 +/- 0.0 26 26 26 26 D-45-2 26.0 +/- 2.8 26 28 25 25 D-53-1 22.0 +/- 2.3 23 21 21 23 D-53-2 20.0 +/- 2.8 20 19 19 22 D-55-1 25.8 +/- 1.9 26 25 27 25 D-55-2 24.3 +/- 3.0 25 22 25 25 D-56-1 21.8 +/- 3.4 22 20 21 24 D-56-2 24.0 +/- 12.1 22 33 21 20 D-101-1 26.5 +/- 4.2 26 27 24 29 D-101-2 23.5 +/- 2.6 23 25 22 24 D-102-1 26.8 +/- 3.0 26 26 26 29 D-102-2 27.0 +/- 3.7 26 28 25 29 D-103-1 23.8 +/- 2.5 24 24 22 25 D- 103-2 23.5 +/- 1.2 24 24 23 23 D-104-1 26.0 +/- 1.6 27 26 26 25 D-104-2 24.8 +/- 2.5 26 23 25 25 D-105-1 24.8 +/- 1.0 25 25 25 24 D- 105-2 24.8 +/- 1.9 24 25 24 26 D-106-1 23.0 +/- 2.3 22 24 22 24 D- 106-2 21.5 +/- 2.6 22 20 23 21 D-107-1 20.0 +/- 2.3 21 19 21 19 D-107-2 21.3 +/- 3.0 22 20 20 23 D-108-1 25.8 +/- 3.4 26 25 24 28 D-108-2 22.5 +/- 4.8 25 20 21 24 D-109-1 25.3 +/- 3.0 24 26 24 27 D-109-2 25.3 +/- 2.5 25 27 25 24 D-110-3 27.3 +/- 2.5 26 27 27 29 D-110-4 29.3 +/- 1.9 28 29 30 30 D-111-1 27.5 +/- 3.8 26 28 26 30 D-111-2 25.8 +/- 2.5 26 27 24 26 D-113-1 22.5 +/- 3.8 25 21 21 23 D-113-2 23.8 +/- 1.0 24 24 23 24 D-114-1 22.5 +/- 2.6 21 23 22 24 D-114-2 23.0 +/- 1.6 23 23 22 24 D-115-1 25.3 +/- 3.0 26 26 23 26 C-20
TABLE C-IX.1 QUARTERLY TLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL-SEP OCT - DEC CODE +/- 2 S.D.
D-1 15-2 25.5 +/- 2.0 26 24 26 D-1 16-1 27.5 t 3.5 27 26 30 D-116-2 26.8 +/- 4.4 26 25 30 D-201-1 29.8 +/- 3.4 29 28 32 D-201-2 29.0 +/- 2.3 28 28 30 D-202-1 26.0 +/- 2.8 28 25 26 D-202-2 24.5 +/- 2.6 25 24 26 D-203-1 23.5 +/- 2.6 23 22 25 D-203-2 23.3 +/- 5.0 24 20 23 D-204-1 21.5 +/- 6.0 20 20 26 D-204-2 22.0 +/- 4.9 24 19 21 D-205-1 25.3 +/- 3.8 24 24 28 D-205-2 23.8 +/- 5.3 26 22 26 D-206-1 23.8 +/- 1.9 24 23 25 D-206-2 25.3 +/- 4.4 26 26 27 D-207-1 22.5 +/- 1.2 22 23 23 D-207-2 24.5 +/- 2.0 24 24 26 D-208-1 21.3 +/- 1.0 22 21 21 D-208-2 21.8 +/- 2.5 22 20 22 D-209-1 20.0 +/- 1.6 21 20 20 D-209-2 21.5 +/- 2.6 23 21 22 D-210-1 23.3 +/- 1.9 24 23 22 D-210-2 25.8 +/- 3.4 24 25 28 D-211-1 25.8 +/- 1.9 27 25 25 D-211-2 24.8 +/- 1.0 25 24 25 D-212-3 22.5 +/- 3.8 23 21 25 D-212-4 22.5 +/- 2.6 24 22 21 D-213-1 21.5 +/- 2.6 22 20 21 D-213-2 20.8 +/- 1.0 21 20 21 D-214-1 28.3 +/- 1.2 28 (1) 29 D-214-2 28.0 +/- 2.0 27 (1) 29 D-215-1 28.0 +/- 4.3 28 26 31 D-215-2 28.0 +/- 3.7 27 26 30 D-216-1 25.0 +/- 5.2 24 22 28 D-216-2 26.5 +/- 2.6 27 25 28 D-1 12A-1 23.5 +/- 2.6 25 23 24 D-1 12A-2 23.0 +/- 4.9 23 23 26 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-21
TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE INNER RING, OUTER RING, OTHER AND CONTROL LOCATIONS FOR DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER STANDARD DEVIATIONS OF THE STATION DATA COLLECTION INNER RING OUTER RING OTHER CONTROL PERIOD +/- 2 S.D.
JAN-MAR 24.7 +/- 3.6 24.6 +/- 4.8 24.7 +/- 4.5 23.0 +/- 0.0 APR-JUN 24.5 +/- 5.4 24.2 +/- 5.9 24.0 +/- 6.0 22.0 +/- 2.8 JUL-SEP 23.8 +/- 4.1 23.0 +/- 5.0 23.2 +/- 4.1 21.0 +/- 5.7 OCT-DEC 25.7 +/- 5.6 25.4 +/- 6.7 24.8 +/- 3.9 23.0 +/- 5.7 TABLE C-IX.3
SUMMARY
OF THE AMBIENT DOSIMETRY PROGRAM FOR DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/-2 S.D.
INNER RING 128 19 30 24.6 +/- 4.9 OUTER RING 126 19 32 24.3 +/- 5.8 OTHER 96 19 33 24.2 +/- 4.8 CONTROL 8 19 25 22.3 +/- 3.7 INNER RING STATIONS - D-101-1, D-101-2, D-102-1, D-102-2, D-103-1, D-103-2, D-104-1, D-104-2, D-105-1, D-105-2, D-106-1, D-106-2, D-107-1, D-107-2, D-108-1, D-108-2, D-109-1, D-109-2, D-110-3, D-110o-4, D-111-1, D-111-2, D-112A-1, D-112A-2, D-113-1, D-113-2, D-114-1, D-114-2, D-115-1, D-115-2, D-116-1, D-116-2 OUTER RING STATIONS - D-201-1, D-201-2, D-202-1, D-202-2, D-203-1, D-203-2, D-204-1, D-204-2, D-205-1, D-205-2, D-206-1, D-206-2, D-207-1, D-207-2, D-208-1, D-208-2, D-209-1, D-209-2, D-210-1, D-210-2, D-211-1, D-211-2, D-212-3, D-212-4, D-213-1, D-213-2, D-214-1, D-214-2, D-215-1, D-215-2, D-216-1, D-216-2 OTHER STATIONS - D-01-1, D-01-2, D-02-1, D-02-2, D-03-1, D-03-2, D-04-1, D-04-2, D-07-1, D-07-2, D-08-1, D-08-2, D-10-1, D-10-2, D-14-1, D-14-2, D-45-1, D-45-2, D-53-1, D-53-2, D-55-1, D-55-2, D-56-1, D-56-2 CONTROL STATIONS - D-12-1, D-12-2 C-22
FIGURE C-1 SURFACE WATER - GROSS BETA - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-51 Dresden Lock & Dam 10.0 0*-04 I 1 0 I I 014)140G 12-41-00) 12481-1 12-31-02 12-31-03 12-.30-04 D-52 (C) DesPlaines River 14.0 12.0 10.0 8.0 4.0 2-0 0.0 4-01-0140 12-31-00 12-31-01 12-31-02 12-41-03 12-30-04 C-23
FIGURE C-1 (cont.)
SURFACE WATER - GROSS BETA - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2010 D-51 Dresden Lock & Dam 12.0 10.0 8.0
-J a.
6.0 4.0 { I 2.0 0.0 4-01-27-05 09-04-05 04-12-06 11-18-06 06-26-07 D-52 (C) DesPlaines River 16.0 14.0 12.0 10.0
-I
,,.,. 8.0 6.0 4.0 2.0 0.0 01-27-05 04-05-06 06-12-07 08-18-08 10-25-09 01-01-11 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-51 LOCATION REMOVED FROM PROGRAM JUNE 29, 2007 AND REPLACED WITH D-21 C-24
FIGURE C-2 SURFACE WATER - GROSS BETA - STATION D-54 (C)
COLLECTED IN THE VICINITY OF DNPS, 2002 - 2004 D-54 (C) Kankakee River 14.0 r 12.0 10.0-.ý
&.0+
4.0 +
2.o+
UL" 01-01-00 12-31-0 12-31-01 12-31-02 12-31-03 12-0.0 C-25
FIGURE C-2 (cont.)
SURFACE WATER - GROSS BETA - STATION D-54 (C) and D-57 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2010 D-54 (C) Kankakee River 14.0 12.0 10.0 8.0
(.)=
CL 0.
6.0 4.0 2.0 no I I I I 01-27-05 09-04-05 04-12-06 11-18-06 06-26-07 D-57 (C) Kankakee River 32 28 24 20 C. 16 12 8 V, 4
0 4 jvý VýV":,Ajl Ivi 07-28-06 06-17-07 05-06-08 03-26-09 02-13-10 01-03-11 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-54 LOCATION REMOVED FROM PROGRAM JUNE 28, 2007 AND REPLACED WITH D-57 C-26
FIGURE C-3 SURFACE WATER - GROSS BETA - STATION D-21 COLLECTED IN THE VICINITY OF DNPS, 2007 - 2010 D-21 Illinois River 30 25 20 C.,.
0.
15 10 5
0 K -
04-27-07 01-21-08 10-16-08 07-12-09 04-07-10 01-01-11 D-21 PLACED INTO SERVICE ON MARCH 30, 2007, REPLACED D-51 C-27
FIGURE C-4 SURFACE WATER - TRITIUM - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-51 Dresden Lock & Dam 2000,
,$am 18000 1400, ld]omw 1200 1000 wo M01,0,0 D*-'1-00 ( 1C1) 1 12442R- 12i-CI 12-30-04 D-62 (C) Des Plalnes River am0 500+
4W +
aw +
9wc I.
0+
PC WoJ 01.Ot,,i0 1"4.00 1"41-01 12-31-02 1"14D3o 12630-04 C-28
FIGURE C-4 (cont.)
SURFACE WATER - TRITIUM - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2010 D-51 Dresden Lock & Dam 2000 1800 1600 1400 1200
,-J 3 1000 0.
800 600 400 200 0
03-31-05 12-29-05 09-28-06 06-28-07 D-52 (C) Des Plaines River 600 500 400
~1 C.)
300 0.
200 100 04 03-31-05 05-25-06 07-19-07 09-11-08 11-05-09 12-30-10 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-51 LOCATION REMOVED FROM PROGRAM JUNE 29, 2007 AND REPLACED WITH D-21 C-29
FIGURE C-5 SURFACE WATER - TRITIUM - STATION D-54 (C)
COLLECTED IN THE VICINITY OF DNPS, 2002 - 2004 D-54 (C) Kankakee River am -w am +
4dOO 3O +
I.
1100.
\^Veý I
A00 -,o a.-G t~l-w *24m-ol 112-31-MO 124-w- 124304" C-30
FIGURE C-5 (cont.)
SURFACE WATER - TRITIUM - STATION D-54 (C) AND D-57 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2010 D-54 (C) Kankakee River 800 700 600 500
,-J 400 C.
300 200 100 0
03-31-05 12-30-05 09-30-06 07-01-07 Location shared with Braidwood Station (BD-10).
D-57 (C) Kankakee River 7000 6000 5000 4000 L 3000 2000 1000 0
12-20-06 10-11-07 08-01-08 05-23-09 03-14-10 01-03-11 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-57 NEW STATION JULY 24, 2006. REPLACED D-54 ON JUNE 28, 2007 C-31
FIGURE C-6 SURFACE WATER - TRITIUM - STATION D-21 COLLECTED IN THE VICINITY OF DNPS, 2007 - 2010 D-21 Illinois River 800 700 600 500 400 300 200 100 0
06-29-07 03-11-08 11-22-08 08-05-09 04-18-10 12-30-10 D-21 REPLACED D-51JUNE 29, 2007 C-32
FIGURE C-7 GROUND WATER - TRITIUM - STATIONS D-23 and D-35 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-23 Thorsen 1000 Boo+
400
/
-~
400 200f I I 01-01-00 12-31-00 12-31-01 12-31-02 1 2-31-W 12-30-04 D-35 Dresden Lock and Dam 400 -r
.00 +
200+
it100.
0- /\.-,.//~\/ 7 -....
-100.-
-200 4-01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 C-33
FIGURE C-7 (cont.)
GROUND WATER - TRITIUM - STATIONS D-23 and D-35 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2010 D-23 Thorsen 1000 1 800 600
,-I a..
400 200 VA, V\./
013 03-31-05 05-25-06 07-19-07 09-11-08 11-05-09 12-30-10 D-35 Dresden Lock and Dam 400 350 300 250 200 \/\ / - -- --
a.
150 100 50 0 -
03-31-05 05-25-06 07-19-07 09-11-08 11-05-09 12-30-10 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-34
FIGURE C-8 AIR PARTICULATES - GROSS BETA - STATIONS D-01 and D-02 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-01 Cnslte Station 1 l0.A jIQ 0.041 911-0-00 124-31-0 ID'02 Ounsite Station 2 No' srwte; I
4.
D0.04-
,014%4)0- 04i4X 124i-W t2--n-03 C-35
FIGURE C-8 (cont.)
AIR PARTICULATES - GROSS BETA - STATIONS D-01 and D-02 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2010 D-01 Onsite Station I 50.0 40.0 S 3oQ c')
30.0 0.
9?
uJ 20.0 10.0 0.0 I 01-07-05 03-20-06 05-31-07 08-10-08 10-21-09 01-01-11 D-02 Onsite Station 2 50.0 40.0 30.0 C.)
9 20.0 W
10.0 0.0 1 09-23-05 10-13-06 11-02-07 11-21-08 12-11-09 12-31-10 D-02 No samples; power was restored on 09-16-05.
DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-36
FIGURE C-9 AIR PARTICULATES - GROSS BETA - STATIONS D-03 and D-04 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-03 Onsit Station 3 10.0
.0.0 ii M~
.010 I-ý all"-O i~-i1~~ 124's- 12-31-0S 12-W."
D-04 CcdIlin~s Road 44 C.D 4--
1241.00 1241-01 .12-31.UZ 12-Wm.0 C-37
FIGURE C-9 (cont.)
AIR PARTICULATES - GROSS BETA - STATIONS D-03 and D-04 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2010 D-03 Onsite Station 3 50.0 40.0 30.0 20.0 Lu 10.0 0.0 -
01-07-05 03-20-06 05-31-07 08-10-08 10-21-09 01-01-11 D-04 Collins Road 60.0 50.0 40.0 E
C.) 30.0 9.
9*
wp C4 20.0 10.0 0.0 I-01-07-05 03-20-06 05-31-07 08-10-08 10-21-09 01-01-11 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-38
FIGURE C-10 AIR PARTICULATES - GROSS BETA - STATIONS D-07 and D-12 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-07 Clay Prod~u.t 1~~'
4A~
2dU 12414w 12~.C1 124142 1Z.30,2O.
D-12 (C) Lis~bon, U
I I
Mmi-w U-35-0 12414M 1249-M 124143 t0*.44 C-39
FIGURE C-10 (cont.)
AIR PARTICULATES - GROSS BETA - STATIONS D-07 and D-12 (C) COLLECTED INTHE VICINITY OF DNPS, 2005 - 2010 D-07 Clay Products 60.0 50.0 40.0 0.
CL 30.0 o,
C?
0J 20.0 10.0 0.0 I 01-07-05 03-20-06 05-31-07 08-10-08 10-21-09 01-01-11 06/10/05 - 06/17/05 no sample due to pump malfunction D-12 (C) Lisbon 60.0 50.0 40.0 E
0L 30.0 20.0 10.0 0.0 i 01-07-05 03-20-06 05-31-07 08-10-08 10-21-09 01-01-11 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-40
FIGURE C-1I AIR PARTICULATES - GROSS BETA - STATIONS D-45 and D-53 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D45 McKinley Woods Road I
12-91430 12-St4i 1244142, 112-314M 12-3D-04 0-53 Grurndy Comn4y Roed 4JD 010140 1*41401 12414D 124t.0U 1"40-04 C-41
FIGURE C-11 (cont.)
AIR PARTICULATES - GROSS BETA - STATIONS D-45 and D-53 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2010 D-45 McKinley Woods Road 50.0 40.0 E
30.0 0.
C.,
cILl 20.0 10.0 0.0 4-01-07-05 03-20-06 05-31-07 08-10-08 10-21-09 01-01-11 D-53 Grundy County Road 82.0 LU 0.0 I 01-07-05 03-20-06 05-31-07 08-10-08 10-21-09 01-01-11 DUE TO VENDOR CHANGE, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-42
FIGURE C-12 AIR PARTICULATES - GROSS BETA - STATIONS D-08 and D-10 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2010 D-08 Prairie Park 70.0 60.0 50.0 E 40.0 a.
V' 30.0 w
' 20.0 10.0 0.0 i 01-07-05 03-20-06 05-31-07 08-10-08 10-21-09 01-01-11 D-10 Goose Lake Village 60.0 50.0 40.0 E
- 0. 30.0 9
20.0 10.0 0.0 4-01-07-05 03-20-06 05-31-07 08-10-08 10-21-09 01-01-11 C-43
FIGURE C-13 AIR PARTICULATES - GROSS BETA - STATIONS D-13 and D-14 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2010 D-13 Minooka 50.0 40.0 30.0 C.)
C.)
9 20.0 1L0 10.0 0.0 -
01-07-05 07-07-05 01-04-06 07-04-06 01-01-07 07-01-07 D-14 Channahon 50.0 40.0 30.0 U
a.
CL 9 20.0 10.0 0.0 4-01-07-05 03-20-06 05-31-07 08-10-08 10-21-09 01-01-11 D-13 TAKEN OUT OF SERVICE JUNE 29, 2007 AND REPLACED WITH D-55 C-44
FIGURE C-14 AIR PARTICULATES - GROSS BETA - STATIONS D-55 and D-56 COLLECTED INTHE VICINITY OF DNPS, 2006-2010 D-55 Ridge Road 50.0 40.0 30.0 0.
9 20.0 uJ 10.0 0.0 -
01-06-06 01-05-07 01-04-08 01-02-09 01-01-10 12-31-10 D-56 Wildfeather 50.0 40.0 30.0 0.
cq C? 20.0 Lu 10.0 0.0 I 07-25-06 06-14-07 05-03-08 03-23-09 02-10-10 12-31-10 D-55 NEW STATION DECEMBER 30, 2005 REPLACED D-13 JUNE 29, 2007 D-56 NEW STATION JULY 25, 2006 C-45
Intentionally left blank APPENDIX D INTER-LABORATORY COMPARISON PROGRAM
Intentionally left blank TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2010 (PAGE 1 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)
March 2010 E6978-396 Milk Sr-89 pCi/L 89.3 92.8 0.96 A Sr-90 pCi/L 13.8 12.7 1.09 A E6979-396 Milk 1-131 pCi/L 65.2 74.0 0.88 A Ce-141 pCi/L 241 261 0.92 A Cr-51 pCi/L 388 361 1.07 A Cs-1 34 pCi/L 157 178 0.88 A Cs-1 37 pCi/L 150 158 0.95 A Co-58 pCi/L 143 143 1.00 A Mn-54 pCi/L 202 207 0.98 A Fe-59 pCi/L 146 137 1.07 A Zn-65 pCi/L 247 254 0.97 A Co-60 pCi/L 177 183 0.97 A E6981-396 AP Ce-141 pCi 211 185 1.14 A Cr-51 pCi 304 255 1.19 A Cs-i 34 pCi 142 125 1.14 A Cs-137 pCi 131 111 1.18 A Co-58 pCi 119 101 1.18 A Mn-54 pCi 162 146 1.11 A Fe-59 pCi 110 97 1.14 A Zn-65 pCi 217 179 1.21 W Co-60 pCi 145 129 1.12 A E6980-396 Charcoal 1-131 pCi 80.2 85.6 0.94 A June 2010 E7132-396 Milk Sr-89 pCi/L 82.0 93.4 0.88 Sr-90 pCi/L 15.8 16.7 0.95 E7133-396 Milk 1-131 pCi/L 83.5 96.9 0.86 Ce-141 pCi/L 107 110 0.97 Cr-51 pCi/L 325 339 0.96 Cs-134 pCi/L 114 126 0.90 Cs-137 pCi/L 144 150 0.96 Co-58 pCi/L 92.3 101 0.91 Mn-54 pCi/L 165 169 0.98 Fe-59 pCi/L 121 119 1.02 Zn-65 pCi/L 197 206 0.96 Co-60 pCi/L 190 197 0.96 E7135-396 AP Ce-141 pCi 88.4 91.6 0.97 Cr-51 pCi 292 282 1.04 Cs-134 pCi 101 105 0.96
.Cs-137 pCi 132 125 1.06 Co-58 pCi 87.3 84.0 1.04 Mn-54 pCi 150 140 1.07 Fe-59 pCi 105 98.6 1.06 Zn-65 pCi 168 171 0.98 Co-60 pCi 170 163 1.04 E7134-396 Charcoal 1-131 pCi 76.4 79.9 0.96 A D-1
TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2010 (PAGE 2 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analvtics Evaluation (d)
September2010 E7229-396 Milk Sr-89 pCi/L 85.0 92.8 0.92 A Sr-90 pCi/L 12.6 14.7 0.86 A E7230-396 Milk 1-131 pCi/L 80.2 94.1 0.85 A Ce-141 pCi/L 130 130 1.00 A Cr-51 pCi/L 235 234 1.00 A Cs-1 34 pCi/L 83.2 93.0 0.89 A Cs-1 37 pCi/L 95.1 94.5 1.01 A Co-58 pCi/L 77.3 73.7 1.05 A Mn-54 pCi/L 121 119 1.02 A Fe-59 pCi/L 96.4 91.1 1.06 A Zn-65 pCi/L 216 204 1.06 A Co-60 pCi/L 172 171 1.01 A E7232-396 AP Ce-141 pCi 122 119 1.03 A Cr-51 pCi 228 214 1.07 A Cs- 134 pCi 79.9 85.3 0.94 A Cs-1 37 pCi 93.8 86.7 1.08 A Co-58 pCi 71.5 67.6 1.06 A Mn-54 pCi 113 110 1.03 A Fe-59 pCi 73.8 83.6 0.88 A Zn-65 pCi 186 187 0.99 A Co-60 pCi 163 157 1.04 A E7231-396 Charcoal 1-131 pCi/L 62.3 59.9 1.04 A December 2010 E7375-396 Milk Sr-89 pCi/L 92.7 98.0 0.95 A Sr-90 pCi/L 13.5 13.5 1.00 A E7376-396 Milk 1-131 pCi/L 87.9 96.9 0.91 A Ce-141 pCi/L not provided by Analytics for this study Cr-51 pCi/L 389 456 0.85 A Cs-134 pCi/L 137 157 0.87 A Cs-137 pCi/L 172 186 0.92 A Co-58 pCi/L 84.3 90.2 0.93 A Mn-54 pCi/L 120 120 1.00 A Fe-59 pCi/L 134 131 1.02 A Zn-65 pCi/L 162 174 0.93 A Co-60 pCi/L 284 301 0.94 A E7378-396 AP Ce-141 pCi not provided by Analytics for this study Cr-51 pci 387 365 1.06 A Cs-134 pci 135 126 1.07 A Cs-1 37 pCi 157 149 1.05 A Co-58 pCi 73.6 72.3 1.02 A Mn-54 pCi 88.7 96 0.92 A Fe-59 pCi 127 105 1.21 W Zn-65 pCi 151 139 1.09 A Co-60 pCi 249 241 1.03 A D-2
TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2010 (PAGE 3 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)
December 2010 E7377-396 Charcoal 1-131 pCi 79.6 84.2 0.95 A (a) Teledyne Brown Engineeringreported result.
(b) The Analytics known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation.
(c) Ratio of Teledyne Brown Engineeringto Analytics results.
(d) Analytics evaluationbased 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.
D-3
TABLE D-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2010 (PAGE 1 OF 1)
Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b) Control Limits Evaluation (c)
May 2010 RAD-81 Water Sr-89 pCi/L 64.4 60.4 48.6 - 68.2 A Sr-90 pCi/L 37.8 41.3 30.4 - 47.4 A Ba-1 33 pCi/L 66.4 65.9 54.9 - 72.5 A Cs-1 34 pCi/L 66.43 71.6 58.4 - 78.8 A Cs-137 pCi/L 137.33 146 131 - 163 A Co-60 pCi/L 83.33 84.5 76.0 - 95.3 A Zn-65 pCi/L 177 186 167- 219 A Gr-A pCi/L 26.37 32.9 16.9 - 42.6 A Gr-B pCi/L 28.77 37.5 24.7 - 45.0 A 1-131 pCi/L 26.27 26.4 21.9-31.1 A H-3 pCi/L 12967 12400 10800 - 13600 A November2010 RAD-83 Water Sr-89 pCi/L 77.8 68.5 55.8 - 76.7 N (1)
Sr-90 pCi/L 39.3 43.0 31.7 - 49.3 A Ba-133 pCi/L 70.3 68.9 57.5 - 75.8 A Cs-134 pCi/L 39.9 43.2 34.5 - 47.5 A Cs-137 pCi/L 117 123 111-138 A Co-60 pCi/L 53.5 53.4 48.1 -61.3 A Zn-65 pCi/L 11.0 102 91.8-122 N (2)
Gr-A pCi/L 35.1 42.3 21.9-53.7 A Gr-B pCi/L 35.5 36.6 24.0 - 44.2 A 1-131 pCi/L 27.9 27.5 22.9 - 32.3 A H-3 pCi/L 13233 12900 11200 - 14200 A (1) Sr-89 TBE to known ratio of 1.14 fell within acceptablerange of +/- 20%. No action required.NCR 10-09 (2) Zn-65 result of 111 was incorrectly reported as 11.0. No action required. NCR 10-09 (a) Teledyne Brown Engineeringreported result.
(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation.
(c) ERA evaluation: A=acceptable. Reportedresult 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.
D-4
TABLE D-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING, 2010 (PAGE 1 OF 2)
Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)
March 2010 10-MaW22 Water Cs-1 34 Bq/L -0.0942 (1) A Cs-1 37 Bq/L 58.5 60.6 42.4 - 78.8 A Co-57 Bq/L 27.2 28.3 19.8 -36.8 A Co-60 Bq/L 0.0226 (1) A H-3 Bq/L 104 90.8 63.6 - 118.0 A Mn-54 Bq/L 26.6 26.9 18.8 - 35.0 A Sr-90 Bq/L 0.1029 (1) A Zn-65 Bq/L 42.0 40.7 28.5 - 52.9 A 10-GrW22 Water Gr-A Bq/L 0.5173 0.676 0.00 - 1.352 A Gr-B Bq/L 3.98 3.09 1.55 - 4.64 A 10-MaS22 Soil Cs-134 Bq/kg 665 733 513-953 A Cs-137 Bq/kg 800 779 545-1013 A Co-57 Bq/kg 508 522 365-679 A Co-60 Bq/kg 648 622 435-809 A Mn-54 Bq/kg 893 849 594-1104 A K-40 Bq/kg 597 559 391-727 A Sr-90 Bq/kg 221 288 202-374 W Zn-65 Bq/kg -4.97 (1) A 10-RdF22 AP Cs-134 Bq/sample 1.81 2.13 1.49-2.77 A Cs-1 37 Bq/sample 1.70 1.53 1.07- 1.99 A Co-57 Bq/sample 0.0056 (1) A Co-60 Bq/sample 2.65 2.473 1.731 - 3.215 A Mn-54 Bq/sample 3.70 3.02 2.11 - 3.93 W Sr-90 Bq/sample 0.0523 (1) A Zn-65 Bq/sample -0.0627 (1) A 10-GrF22 AP Gr-A Bq/sample 0.1533 0.0427 0.00-0.854 A Gr-B Bq/sample 1.240 1.29 0.65-1.94 A 10-RdV22 Vegetation Cs-1 34 Bq/sample 4.48 4.39 3.07 - 5.71 A Cs-137 Bq/sample 3.43 3.06 2.14 - 3.98 A Co-57 Bq/sample -0.0117 (1) A Co-60 Bq/sample 3.55 3.27 2.29 - 4.25 A Mn-54 Bq/sample 0.007 (1) A Sr-90 Bq/sample -0.0002 (1) A Zn-65 Bq/sample 8.12 7.10 4.97 - 9.23 A September2010 10-MaW23 Water Cs-1 34 Bq/L 27.1 31.4 22.0-40.8 A Cs-1 37 Bq/L 41.8 44.2 30.9 - 57.5 A Co-57 Bq/L 33.2 36.0 25.2 - 46.8 A Co-60 Bq/L 26.5 28.3 19.8 -36.8 A H-3 Bq/L 500 453.4 317.4 - 589.4 A Mn-54 Bq/L 0.024 (1) A Sr-90 Bq/L 8.10 8.3 5.8 - 10.8 A Zn-65 Bq/L 30.8 31.0 21.7-40.3 A 10-GrW23 Water Gr-A Bq/L 2.36 1.92 0.58 - 3.26 A Gr-B Bq/L 6.37 4.39 2.20 - 6.59 A D-5
TABLE D-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING, 2010 (PAGE 2 OF 2)
Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)
September 2010 10-MaS23 Soil Cs- 134 Bq/kg 837 940 658-1222 A Cs-1 37 Bq/kg 680 670 469-871 A Co-57 Bq/kg 2.78 (1) A Co-60 Bq/kg 350 343 240-446 A Mn-54 Bq/kg 853 820 574-1066 A K-40 Bq/kg 721 699 489-909 A Sr-90 Bq/kg 2.24 (1) A Zn-65 Bq/kg 287 265 186-345 A 10-RdF23 AP Cs-134 Bq/sample 2.31 2.98 2.09 - 3.87 W Cs-1 37 Bq/sample -0.025 (1) A Co-57 Bq/sample 3.64 4.08 2.86 - 5.380 A Co-60 Bq/sample 2.81 2.92 2.04 - 3.80 A Mn-54 Bq/sample 3.19 3.18 2.23-4.13 A Sr-90 Bq/sample 1.01 1.01 0.71 - 1.31 A Zn-65 Bq/sample 0.0310 (1) A 10-GrF23 AP Gr-A Bq/sample 0.004 (1) A Gr-B Bq/sample 0.473 0.50 0.25 - 0.75 A 10-RdV23 Vegetation Cs-1 34 Bq/sample 4.90 4.79 3.35 - 6.23 A Cs-1 37 Bq/sample 6.78 5.88 4.12- 7.64 A Co-57 Bq/sample 10.2 8.27 5.79 - 10.75 W Co-60 Bq/sample 0.00 (1) A Mn-54 Bq/sample 7.36 6.287 4.401 - 8.173 A Sr-90 Bq/sample 2.53 2.63 1.84 - 3.42 A Zn-65 Bq/sample 6.40 5.3900 3.77 - 7.01 A (1) False positive test.
(a) Teledyne Brown Engineeringreportedresult.
(b) The MAPEP known value is equal to 100% of the parameterpresent in the standardas determinedby gravimetricand/or volumetric measurements made during standardpreparation.
(c) DOEIMAPEPevaluation: A=acceptable, W-acceptable with warning, N=not acceptable.
D-6
APPENDIX E ERRATA DATA
Intentionally left blank There is no errata data for 2010.
E-1
Intentionally left blank APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)
Intentionally left blank Docket No: 50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2010 Prepared By Teledyne Brown Engineering Enviromnental Services Exelkns.
Nuclear Dresden Nuclear Power Station Norris, IL 60450 May 2011
Intentionally left blank
Table of Contents I. Sum m ary and Conclusions ........................................................................................ 1 II. Introduction ................................................................................................................ 2 A. Objectives of the RGPP ................................................................................ 3 B. Im plem entation of the O bjectives .................................................................. 4 C. Program Description ..................................................................................... 4 D. Characteristics of Tritium (H-3) ....................................................................... 4 II. Program Description .................................................................................................. 5 A. Sam ple Analysis ............................................................................................. 5 B. Data Interpretation ........................................................................................... 6 C. Background Analysis ...................................................................................... 7
- 1. Background Concentrations of Tritium ................................................. 7 IV. Results and Discussion ............................................................................................. 9 A. Groundwater Results ...................................................................................... 9 B. Surface W ater Results ................................................................................. 10 C. Drinking W ater W ell Survey .......................................................................... 10 D. Summary of Results - Inter-laboratory Comparison Program ...................... 10 E. Leaks, Spills, and Releases ......................................................................... 10 F. Trends ............................................................................................................ 11 G . Investigations ............................................................................................... 11 H. Actions Taken ............................................................................................... 11
- i-
Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2010 Figures Security-Related Information: Maps of the Dresden Nuclear Power Station have been withheld from public disclosure under 10CFR2.390 and N.J.S.A. 47:1A-1.1 Appendix B Data Tables Tables Table B-1.1 Concentrations of Tritium and Strontium in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table B-I.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table B-11.1 Concentrations of Tritium and Strontium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.
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I. Summary and Conclusions Dresden Station is situated on approximately 600 acres of land that borders the Illinois River to the north and the Kankakee River to the east. This land is referred to as the owner-controlled area. The Dresden power plant itself takes up a small parcel of the owner-controlled area and is surrounded by a security fence. The security fence defines what is known as the Protected Area (PA).
The Dresden power plant has experienced a number of leaks from underground lines and spills from above ground systems containing radioactive water over its 40-year history. These incidents have created a number of areas of localized contamination within the PA. Isotopic analyses of groundwater in many of these areas show measurable concentrations of tritium (H-3).
Dresden participated in a fleetwide hydrogeologic investigation in during the summer of 2006 in an effort to characterized groundwater movement at each site. This investigation also compiled a list of the historic spills and leaks. Combining the tritium concentration in a locally contaminated area with the speed and direction of groundwater in the vicinity can produce a contaminated groundwater plume projection. Ifthe plume of contaminated groundwater passes through the path of a groundwater monitoring well, it can be anticipated that the tritium concentration in this well will increase to some maximum concentration, then decrease over time.
The fleetwide Hydrogeologic Investigation Report (HIR) shows that groundwater movement on the Dresden site is very slow. In addition, there is a confining rock layer, the Maquoketa Shale layer, about 55 feet below the surface that impedes groundwater movement below this depth.
Dresden has a domestic water system that is supplied by two deep wells (1500 feet deep) that were installed about 50 years ago south of the P.A. Samples taken from domestic water supply and have never shown any detectable tritium concentration.
Tritium has a half-life of 12.3 years. This means that 40 years from now 90% of the tritium on site today will have decayed away to more stable elements.
Given the limited volume of contaminated groundwater on site, radioactive decay, slow groundwater movement, and dilution effects the conclusion of the HIR is that the operation of Dresden Nuclear Power Station had no adverse radiological impact on the environment. As a result there is little potential for contaminated groundwater on site to affect off-site drinking water.
II. Introduction Radiological Groundwater Monitoring Program (RGPP):
Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions.
Dresden uses developed groundwater wells and surface water sample points in the RGPP.
The Dresden RGPP was established in 2006 and there have been no significant changes to this program. This program does not impact the operation of the plant and is independent of the REMP.
Developed groundwater wells are wells that were installed specifically for monitoring groundwater. These wells are equipped with screens and are properly sealed near the surface to avoid surface water intrusion. The wells were designed in accordance with appropriate codes and developed in accordance with appropriate standards and procedures. Dresden has groundwater monitoring wells identified as "shallow" (depths from 15 to 35 feet), "Intermediate" (depths from 35 to 55 feet) and "deep" (depths beyond 100 feet). All wells installed to a depth greater than 100 feet ("deep" wells) were found to be dry and removed from the RGPP. Surface water sample points are identified sample locations in the station's canals and cooling pond.
There are 70 sampling points in the RGPP:
- Dresden has 39 developed groundwater monitoring wells within the Protected Area.
Some of these wells form a ring just inside the security fence and the remaining wells were installed near underground plant system piping that contains radioactive water.
- Dresden has 25 developed groundwater monitoring wells outside the P.A. the majority of which form a ring just within the perimeter of the property.
- Dresden has 6 surface water monitoring locations on the owner-controlled area sampled as part of the Dresden RGPP. These consist of one sample from each of the 5 different canals and one sample from the cooling pond.
The Dresden site-specific RGPP procedure identifies the historic 'events' that would affect the individual RGPP sample results. This procedure identifies threshold values for each sample point, which if exceeded, could be an indication of a new spill from an above ground system or a new leak in an underground pipe containing tritiated water.
The RGPP sample points are currently sampled on a frequency of twice per year.
During 2010, there were 276 analyses that were performed on 138 samples from 70 sampling points.
Supplemental Radiological Groundwater Monitoring Program:
Dresden also has a Supplemental Radiological Groundwater Monitoring Program that provides short-term monitoring of a limited selection of monitoring points, mostly within the PA, intended to identify relatively rapid changes in the groundwater tritium concentrations.
Sentinel Wells, sometimes referred to as "baby wells" are wells that were installed to monitor local shallow groundwater; typically in associated with a historic underground pipe leak. These wells are not constructed to code or developed to a standard. Most sentinel wells are from 6 to 12 feet deep and consist of 2" PVC pipe without screens.
Dresden has two basic storm water runoff sewer systems within the P.A: one sewer-system routes to the east, then north, and discharges into the Unit 1 intake canal, the second sewer-system routes to the west, then north, through a large Oil/Water Separator, and discharges to the hot canal. Both the Unit 1 intake canal and the hot canal eventually route to the cooling pond.
A. Objectives of the RGPP The Objective of the RGPP is to provide long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. The objective of the site-specific RGPP is to provide indication of short-term changes to groundwater tritium concentrations within the PA.
If isotopic results of groundwater samples exceed the thresholds specified in this procedure it could be an indication of a new spill from an above ground system or a new leak in an underground pipe containing tritiated water.
Specific Objectives include:
- 1. Perform routine water sampling and radiological analysis of water from selected locations.
- 2. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.
- 3. Regularly assess analytical results to identify adverse trends.
- 4. Take necessary corrective actions to protect groundwater resources.
B. Implementation of the Objectives
- 1. Dresden Nuclear Power Station will continue to perform routine sampling and radiological analysis of water from selected locations.
- 2. Dresden Nuclear Power Station has implemented procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner.
- 3. Dresden Nuclear Power Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.
- 4. If an adverse trend in groundwater monitoring analytical results is identified, further investigation will be undertaken. If the investigation identifies a leak or unidentified spill, corrective actions will be implemented.
C. Program Description Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. Dresden uses 70 developed groundwater wells and surface water sample points in the RGPP.
- 1. Sample Collection Sample locations can be found in Table A-I, Appendix A.
Groundwater and Surface Water Water samples are collected in accordance with the schedule delineated in the Dresden site-specific RGPP procedures.
Analytical laboratories are subject to internal quality assurance programs, industry crosscheck programs, as well as nuclear industry audits. Station personnel review and evaluate the analytical results.
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-10 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 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.
III. Program Description A. Sample Analysis This section describes the general analytical methodologies used by Teledyne Brown Engineers (TBE) to analyze the environmental samples for radioactivity for the Dresden Nuclear Power Station RGPP in 2010.
In order to achieve the stated objectives, the current program includes the following analyses:
- 1. Concentrations of gamma emitters in groundwater and surface water.
B. Data Interpretation The radiological data collected prior to Dresden Nuclear Power Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Dresden Nuclear Power 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 the minimum sensitivity value that must be achieved routinely by the analytical parameter.
- 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.
Gamma spectroscopy results for each type of sample were grouped as follows:
For groundwater and surface water 14 nuclides, Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-1 40 and La-1 40 were reported.
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, marine life, and foodstuffs. The results of the monitoring were detailed in the report entitled, Environmental Radiological Monitoring for Dresden Nuclear Power Nuclear Power Station, Commonwealth Edison Company, Annual Report 1986, May 1987.
- 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 (CRA 2006).
- 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 worldwide from 1960 to 2006.
RadNet provides tritium precipitation concentration data for samples collected at stations throughout 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 Midwest precipitation 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 and decades is naturally captured in groundwater, so some well water sources today are affected by the surface water from the 1960s that was elevated in tritium.
- c. Surface Water Data Tritium concentrations are routinely measured in large surface water bodies, including Lake Michigan and the Mississippi River. Illinois surface water data were typically less than 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. These sample results cannot be distinguished as different from background at this
concentration.
IV. Results and Discussion Dresden Station initiated a Radiological Groundwater Protection Program (RGPP) in 2006.
A. Groundwater Results Groundwater Samples were collected from on-site wells throughout the year in accordance with Dresden's RGPP. Analytical results and anomalies are discussed below.
Tritium Inside the Protected Area:
Of the 39 developed groundwater-monitoring wells inside the Protected Area, a little more than half (23 wells) show some level of tritium contamination ranging from just above LLD to 77,400 pCi/L. Although tritium is detected in a large number of these wells, it is important to note that the majority were installed in areas of historic spills or close to piping containing tritiated water (Table B-1.1, Appendix B).
Outside the Protected Area:
Of the 25 developed groundwater-monitoring wells on station property outside the Protected Area, 4 wells have a tritium concentration at or just slightly above the level of detectability (181 pCi/L to 632 pCi/L).
Three of the four wells with detectable tritium were installed in a cluster just north of the Protected Area near a historic Radwaste line break. The concentration of tritium in one of these wells reached a maximum of 76,000 pCi/L in March of 2002. The tritium concentration has been trending down and all three are now very near the lower limit of detectability.
One of the four wells with detectable tritium is about 200 yards south of the security access Check Point adjacent to the cold canal. It is believed that the tritium concentration in the cold canal is influenced by an upstream source. The tritium concentration reached a maximum of 784
pCi/L in late 2005 and has been trending down since.
Gamma Emitters No gamma emitting nuclides were detected (Table B-1.2, Appendix B).
B. Surface Water Results Surface Water Samples were collected from six surface water locations throughout the year in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.
Tritium Samples from all locations were analyzed for tritium activity (Table B-11.1, Appendix B). Tritium values ranged from the detection limit to 544 pCi/l.
The measurable concentrations of tritium are from an upstream source.
Gamma Emitters No gamma emitting nuclides were detected (Table B-11.2, Appendix B).
C. Drinking Water Well Survey No drinking water well surveys were conducted in 2010.
D. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE and Environmental Inc. (Midwest Labs) are presented in the AREOR.
E. Leaks, Spills, and Releases On November 27, 2010 a hose fitting ruptured that was connected to a portable storage tank containing tritium-contaminated groundwater collected from an on-site excavation. The rupture was caused by freezing and leakage was stopped the same day. An estimated 1 .12E+04 gallons containing 1.12E-04 curies of tritium was released to the environment.
10-
F. Trends The tritium concentration in the water found near the 2004 HPCI leak is traveling to the west. Wells in the vicinity show that tritium levels have been trending down slightly.
G. Investigations No investigations were performed in 2010.
H. Actions Taken
- 1. Compensatory Actions A groundwater collection and treatment system was used during the excavation and replacement of the underground Unit 3 Low Pressure Coolant Injection (LPCI) suction line. As with the groundwater collection and treatment systems employed during the excavation work associated with the 2004, 2006, and 2009 leak repairs, the groundwater was processed through the RadWaste System.
- 2. Actions to Recover/Reverse Plumes No actions were taken in 2010 by Dresden Station in an effort to reverse plume movement.
Intentionally left blank APPENDIX A LOCATION DISTANCE
Intentionally left blank TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2010 Site Site Type Location DSP-105 Monitoring Well 30 feet east of the east wall of the EM Shop DSP-106 Monitoring Well 65 feet east of east wall of EM Shop DSP-107 Monitoring Well 9 feet east of the east Unit 1 Fuel Pool wall DSP-108 Monitoring Well 40 ft east of the Unit 1 Sphere DSP-1 17 Monitoring Well Northeast of Unit 1 Sphere; 825 feet west of Ross Bridge DSP-121 Monitoring Well 72 feet north of 2/3 Intake Canal fence DSP-122 Monitoring Well 50 feet north of the Radwaste Tank Farm DSP-123 Monitoring Well Northeast corner of the Unit 1 Off-gas Building DSP-124 Monitoring Well 9 feet south of Floor Drain Collector Tank DSP-125 Monitoring Well Northeast comer of the Unit 2/3A CST DSP-126 Monitoring Well 21 feet northwest of the northwest bend in road behind Training Building DSP-147 Monitoring Well 325 feet west of Telemetry Bridge DSP-148 Monitoring Well 130 feet southeast of the Flow Regulating Station building DSP-149R Monitoring Well 35 feet south by southwest of the 138 KV yard fence DSP-150 Monitoring Well 85 feet east of the northeast comer of the Unit 1 Spent Fuel Pool pad DSP-151 Monitoring Well 65 feet north of the northeast comer of the Storeroom DSP-152 Monitoring Well 210 feet south by southeast of the southeast comer of Maintenance Garage DSP-153 Monitoring Well 150 feet east of the southeast comer of liquid hydrogen tank farm fence DSP-154 Monitoring Well 33 feet west of the track; 165 feet east of the Security Checkpoint DSP-156 Monitoring Well 70 feet east by northeast of the northwest comer of 138 KV yard fence DSP-157-1 Monitoring Well 25 feet south of the south edge of the Employee Parking lot DSP-157-S Monitoring Well 25 feet south of the south edge of the Employee Parking lot DSP-158-1 Monitoring Well 53 feet west of the Kankakee River; 33 feet west of the cinder track DSP-158-S Monitoring Well 50 feet west of the Kankakee River; 33 feet west of the cinder track DSP-159-1 Monitoring Well 250 feet west of the Thorsen house; 450 ft south of the plant access gate DSP-159-S Monitoring Well 251 feet west of the Thorsen house; 450 ft south of the plant access gate MW-DN-101-1 Monitoring Well 60 feet north of the Unit 1 Diesel Fuel Storage MW-DN-101-S Monitoring Well 60 feet north of the Unit 1 Diesel Fuel Storage MW-DN-102-1 Monitoring Well 12 feet south of the southeast comer of the MUDS Building MW-DN-102-S Monitoring Well 13 feet south of the southeast corner of the MUDS Building MW-DN-103-1 Monitoring Well 280 feet west of the northwest comer of N-GET Building MW-DN-103-S Monitoring Well 281 feet west of the northwest comer of N-GET Building MW-DN-104-S Monitoring Well 50 feet north of Radwaste Tank Farm MW-DN-105-S Monitoring Well 65 feet north of the northeast comer of the Storeroom MW-DN-106-S Monitoring Well 75 feet north of the 2/3 Intake Canal fence; east of the Unit 1 Intake Canal MW-DN-107-S Monitoring Well 15 feet west by southwest of the Unit 1 CST MW-DN-108-1 Monitoring Well 7 feet southwest of the southwest comer of the Unit 1 Cribhouse MW-DN-109-1 Monitoring Well 8 feet north of Chemistry Building MW-DN-109-S Monitoring Well 8 feet north of Chemistry Building MW-DN-110-1 Monitoring Well 25 feet west of the Waste Water Treatment (WWT) Building MW-DN-110-S Monitoring Well 25 feet west of the Waste Water Treatment (WWT) Building MW-DN-111-S Monitoring Well 9 feet east of the Floor Drain Collector Tank MW-DN-1 12-1 Monitoring Well 100 feet south of the Chemistry Building MW-DN-1 12-S Monitoring Well 100 feet south of the Chemistry Building MW-DN-1 13-1 Monitoring Well 90 feet west of the southwest comer of the Administration Building MW-DN-1 13-S Monitoring Well 91 feet west of the southwest comer of the Administration Building MW-DN-1 14-1 Monitoring Well 50 feet east of the Unit 1 Clean Demineralized Water Tank MW-DN-1 14-S Monitoring Well 8 feet southwest of the Radiation protection Dept west access doors MW-DN-1 15-1 Monitoring Well 11 feet south of Instrument Maintenance Shop MW-DN-1 15-S Monitoring Well 12 feet south of Instrument Maintenance Shop MW-DN-1 16-1 Monitoring Well 75 feet south of the Calgon Building roll-up door MW-DN-1 16-S Monitoring Well 75 feet south of the Calgon Building roll-up door MW-DN-1 17-1 Monitoring Well 35 feet east by northeast of the Unit 1 Stack MW-DN-1 18-S Monitoring Well Southeast corner of the Unit 1 Fuel Pool MW-DN-1 19-1 Monitoring Well 20 feet east by northeast of the Unit 1 Sewage Ejector Building MW-DN-1 19-S Monitoring Well 21 feet east by northeast of the Unit 1 Sewage Ejector Building MW-DN-120-1 Monitoring Well 45 feet north by northeast of the Ross Bridge railing MW-DN-120-S Monitoring Well 46 feet north by northeast of the Ross Bridge railing MW-DN-121-S Monitoring Well 7 feet west of the dirt road; 42 feet east of the 345KV yard fence MW-DN-122-1 Monitoring Well 150 feet north of Collins Road; northeast of the G.E. Fuel Storage Facility MW-DN-122-S Monitoring Well 150 feet north of Collins Road; northeast of the G.E. Fuel Storage Facility MW-DN-123-1 Monitoring Well 400 feet west of the Thorsen house; west of the Cold Canal A-1
TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2010 Site Site Type Location MW-DN-123-S Monitoring Well 400 feet west of the Thorsen house; west of the Cold Canal MW-DN-124-1 Monitoring Well 10 feet south of the liquid nitrogen inerting tanks MW-DN-124-S Monitoring Well 10 feet south of the liquid nitrogen inerting tanks SW-DN-101 Surface Water Unit 2/3 Intake (DSP50) at the Ross Bridge SW-DN-102 Surface Water Unit 2/3 Discharge (DSP20) at the Telemetry Bridge SW-DN-103 Surface Water Unit 2/3 Return Canal at the Discharge to the Intake Canal SW-DN-104 Surface Water Cold Canal (DSP34A) at the Cooling Tower walkway bridge SW-DN-105 Surface Water Hot Canal (DSP34B) at the Cooling Tower walkway bridge SW-ON-106 Surface Water Cooling Pond - Pool II at the east side of the Covered Bridge A-2
APPENDIX B DATA TABLES
Intentionally left blank TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 DN-DSP-105 04/30/10 < 177 DN-DSP-105 09/30/10 < 188 < 0.8 DN-DSP-106 04/30/10 3050 +/- 360 DN-DSP-106 09/30/10 3260 +/- 392 < 0.7 DN-DSP-107 04/30/10 5590 +/- 612 DN-DSP-107 09/30/10 4630 +/- 526 < 0.6 DN-DSP-108 04/29/10 1200 +/- 184 DN-DSP-108 09/30/10 962 +/- 172 < 0.8 DN-DSP-1 17 05/03/10 < 171 DN-DSP-117 10/04/10 < 174 < 0.7 DN-DSP-121 05/03/10 < 172 DN-DSP-121 10/04/10 < 176 < 0.9 DN-DSP-122 04/28/10 3780 +/- 433 DN-DSP-122 09/29/10 2510 +/- 317 < 0.7 DN-DSP-123 04/29/10 9610 +/- 1010 DN-DSP-123 09/30/10 8280 +/- 889 < 0.7 DN-DSP-124 04/27/10 7820 +/- 832 DN-DSP-124 10/01/10 2200 +/- 289 < 0.9 DN-DSP-125 04/30/10 < 176 DN-DSP-125 10/01/10 361 +/- 131 < 0.9 DN-DSP-126 05/04/10 < 173 DN-DSP-126 10/05/10 < 174 < 1.0 DN-DSP-147 05/05/10 < 175 DN-DSP-147 10/06/10 < 173 < 0.8 DN-DSP-148 05/05/10 181 +/- 117 DN-DSP-148 10/04/10 316 +/- 125 < 0.8 DN-DSP-149R 05/05/10 344 +/- 123 DN-DSP-149R 10/04/10 632 +/- 131 < 0.7 DN-DSP-150 04/29/10 < 176 DN-DSP-150 09/30/10 < 189 < 0.8 DN-DSP-151 04/29/10 < 176 DN-DSP-151 09/30/10 < 189 < 0.6 DN-DSP-152 05/03/10 < 173 DN-DSP-152 10/05/10 < 171 < 0.8 DN-DSP-153 05/04/10 < 157 DN-DSP-153 10/05/10 < 170 < 0.6 DN-DSP-154 05/04/10 < 156 DN-DSP-154 10/05/10 < 173 < 0.8 DN-DSP-156 05/05/10 359 +/- 115 DN-DSP-1 56 10/04/10 265 +/- 117 < 0.7 DN-DSP-1571 05/04/10 < 177 DN-DSP-1571 10/05/10 < 169 < 0.7 DN-DSP-157S 05/04/10 < 155 DN-DSP-157S 10/05/10 < 167 < 0.8 DN-DSP-1581 05/03/10 < 179 DN-DSP-1581 10/05/10 < 169 < 0.8 DN-DSP-158S 05/03/10 < 156 DN-DSP-158S 10/05/10 < 169 < 0.8 DN-DSP-1591 05/05/10 < 177 DN-DSP-1591 10/06/10 311 +/- 119 < 0.7 DN-DSP-159S 05/05/10 < 178 B-1
TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 DN-DSP-159S 10/06/10
- 168
- 0.8 MW-DN-1011 04/29/10 1140 +/- 169 MW-DN-1011 09/29/10 741 +/- 156
- 0.7 MW-DN-101S 04/29/10
- 164 MW-DN-101S 09/29/10
- 162 < 0.6 MW-DN-1021 04/27/10 214 +/- 110 MW-DN-1021 09/28/10 230 +/- 131
- 0.7 MW-DN-102S 04/27/10
- 163 MW-DN-102S 09/28/10
- 189 < 0.7 MW-DN-1031 05/04/10
- 172 MW-DN-1031 10/06/10
- 180
- 0.8 MW-DN-103S 05/04/10
- 170 MW-DN-103S 10/06/10
- 173
- 0.8 MW-DN-104S 04/28/10
- 166 MW-DN-104S 09/29/10 521 +/- 138
- 0.7 MW-DN-105S 04/29/10
- 166 MW-DN-105S 09/30/10
- 200 3.8 +/- 0.4 MW-DN-106S 05/03/10
- 175 MW-DN-106S 10/04/10
- 178 < 0.8 MW-DN-1081 04/28/10
- 162 MW-DN-1081 09/29/10
- 196 < 0.6 MW-DN-1091 04/28/10
- 162 MW-DN-1091 09/28/10
- 189
- 0.8 MW-DN-109S 04/28/10
- 167 MW-DN-109S 09/28/10
- 199
- 0.9 MW-DN-1101 04/28/10 178 +/- 108 MW-DN-1101 09/29/10
- 196
- 0.7 MW-DN-110S 04/28/10
- 160 MW-DN-110S 09/29/10
- 163
- 0.8 MW-DN-111S 04/27/10 922 +/- 150 MW-DN-111S 10/01/10 892 +/- 146
- 0.7 MW-DN-1 121 04/27/10 1390 +/- 193 MW-DN-1 121 09/28/10 1290 +/- 184 < 0.7 MW-DN-1 12S 04/27/10
- 167 MW-DN-1 12S 09/28/10
- 161 < 0.9 MW-DN-1 131 04/27/10
- 173 MW-DN-1 131 09/28/10
- 164
- 0.7 MW-DN-1 13S 04/27/10
- 174 MW-DN-1i13S 09/28/10
- 163
- 0.9 MW-DN-1 141 04/30/10 5870 +/- 640 MW-DN-1 141 10/01/10 6140 +/- 659 < 0.8 MW-DN-1 14S 04/30/10 1570 +/- 219 MW-DN-1 14S 10/01/10 1340 +/- 189
- 0.9 MW-DN-1 151 04/30/10 185 +/- 116 MW-DN-1 151 09/30/10 356 +/- 113
- 0.6 MW-DN-1 15S 04/30/10
- 173 MW-DN-1i15S 09/30/10 237 +/- 110
- 0.8 MW-DN-1 161 04/28/10 3650 +/- 420 MW-DN-1 161 09/29/10 1460 +/- 195
- 0.7 MW-DN-1 16S 04/28/10 282 +/- 119 MW-DN-1 16S 09/29/10 337 +/- 114 < 0.9 B-2
TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 MW-DN-1 171 04/29/10
- 177 MW-DN-118S 04/30/10 929 +/- 153 MW-DN-1 18S 09/30/10 3980 +/- 438
- 0.7 MW-DN-1 191 04/29/10 576 +/- 128 MW-DN-1 191 09/29/10 461 +/- 134
- 0.9 MW-DN-1 19S 04/29/10
- 161 MW-DN-1 19S 09/29/10
- 189
- 0.6 MW-DN-1201 05/03/10
- 171 MW-DN-1201 10/04/10
- 176
- 0.8 MW-DN-120S 05/03/10
- 175 MW-DN-120S 10/04110
- 174
- 0.8 MW-DN-121S 05/05/10
- 173 MW-DN-121S 10/06/10
- 176
- 1.0 MW-DN-1221 05/05/10
- 171 MW-DN-1221 10/06/10
- 175
- 0.9 MW-DN-122S 05/05/10
- 172 MW-DN-122S 10/06/10
- 178
- 0.8 MW-DN-1231 05/05/10
- 173 MW-DN-1231 10/06/10
- 160
- 0.7 MW-DN-123S 05/05/10
- 171 MW-DN-123S 10/06/10 < 153
- 0.8 MW-DN-1241 04/30/10 73200 +/- 6400 MW-DN-1241 10/01/10 77400 +/- 7750 < 0.7 MW-DN-124S 04/30/10 51200 +/- 5140 MW-DN-124S 10/01/10 819 +/- 160
- 0.9 B-3
TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 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 DN-DSP-105 09/30/10 < 41 < 39 <4 <4 <9 <,5 <lO <,5 <8 < 14 < 4 < 5 < 32 < 12 DN-DSP-106 09/30/10 <44 <62 <5 <4 <9 <3 <9 <5 <8 < 14 <4 < 4 < 32 < 10 DN-DSP-107 09/30/10 < 43 < 86 <5 <5 <12 <5 <9 <5 <9 <15 <4 <3 <30 <9 DN-DSP-108 09/30/10 <38 <34 <4 <4 <9 <4 <7 <4 <7 <14 <4 <4 <28 <7 DN-DSP-1 17 10/04/10 < 36 < 36 <3 <4 <9 <3 <7 <4 <7 <12 <3 <3 <27 <7 DN-DSP-121 10/04/10 < 31 < 53 <3 <4 <9 <3 <6 <4 <7 <12 <3 <3 <27 <9 DN-DSP-122 09/29/10 < 44 < 109 <5 <5 <10 <5 <12 <5 <10 <14 <4 <5 <34 <9 DN-DSP-123 09/30/10 < 41 < 41 <4 <4 <11 <4 <10 <5 <8 < 14 <4 < 4 < 31 < 7 DN-DSP-124 10/01/10 <41 < 38 <4 <5 <9 <4 <8 <4 <8 <15 <4 <5 <30 <7 DN-DSP-125 10/01/10 <44 <42 <5 <5 <9 <5 <9 <5 <8 < 14 < 4 < 5 < 29 < 12 DN-DSP-126 10/05/10 < 40 < 85 <4 <5 <11 <4 <8 <5 <8 <15 <4 <4 <33 <11 DN-DSP-147 10/06/10 < 43 < 103 <5 <5 <11 <5 <10 <5 <8 < 14 < 5 < 5 < 35 < 10 DN-DSP-148 10/04/10 < 39 < 35 <4 <4 <9 <4 <9 <4 <8 <15 <4 <4 <34 <9 DN-DSP-149R 10/04/10 < 37 < 73 <4 <4 <8 <4 <7 <4 <7 <14 <4 <4 <29 <8 DN-DSP-150 09/30/10 < 42 < 41 <4 <4 <8 <4 <9 <4 <8 <13 <4 <4 <30 <8 DN-DSP-151 09/30/10 < 42 < 69 <4 <3 <9 <4 <7 <5 <7 <14 <4 <4 <29 <8 DN-DSP-152 10/05/10 < 42 < 46 <4 <5 <8 <4 <9 <5 <7 <15 <4 <5 <33 <9 DN-DSP-153 10/05/10 < 44 < 37 <4 <4 <10 <4 <8 <4 <8 <14 <4 <4 <31 <9 DN-DSP-154 10/05/10 < 36 < 35 <4 <4 <9 <4 <7 <5 <6 < 14 < 4 < 4 < 30 < 10 DN-DSP-156 10/04/10 < 32 < 36 <3 <4 <10 <4 <7 <4 <6 < 14 < 3 < 4 < 25 < 11 DN-DSP-1571 10/05/10 < 37 < 32 <4 <4 <11 <4 <8 <5 <8 <13 <3 <4 <27 <9 DN-DSP-157S 10/05/10 < 33 < 29 <3 <3 <8 <4 <7 <4 <7 <13 <4 <3 <26 <8 DN-DSP-1581 10/05/10 < 39 < 75 <4 <5 <9 <4 <8 <5 <8 <14 <4 <4 <34 <12 DN-DSP-158S 10/05/10 < 41 < 42 <5 <5 <13 <5 <8 <5 <9 < 14 < 5 < 6 < 36 < 13 DN-DSP-1591 10/06/10 < 41 < 50 <4 <5 <10 <4 <9 <5 <9 < 13 < 4 < 5 < 30 < 10 DN-DSP-159S 10/06/10 < 42 < 38 <4 <4 <9 <4 <9 <5 <7 <13 <4 <4 <30 <8 MW-DN-1011 09/29/10 <32 <38 <3 <3 <7 <3 <6 <4 <6 <11 <3 <3 <24 <7 MW-DN-101S 09/29/10 < 40 < 35 <5 <5 <10 <4 <9 <5 <8 <14 <4 <5 <34 <11 MW-DN-1021 09/28/10 < 36 < 73 <3 <4 <9 <4 <8 <4 <7 < 13 < 3 < 4 < 27 < 10 MW-DN-102S 09/28/10 < 37 < 79 <4 <4 <10 <4 <8 <5 <7 < 13 < 4 < 4 < 26 < 10 MW-DN-1031 10/06/10 < 37 < 65 <4 <4 <8 <5 <8 <4 <8 <11 <4 <4 <27 <6 MW-DN-103S 10/06/10 < 41 < 93 <5 <6 <10 <5 <11 <5 <9 < 14 < 4 < 5 < 31 < 13 MW-DN-104S 09/29/10 < 47 < 100 <5 <4 <11 <5 <10 <5 <10 <13 <4 <5 <34 <12 MW-DN-105S 09/30/10 < 47 < 38 <5 <5 <10 <4 <9 <6 <8 <14 <4 <4 <30 <9 MW-DN-106S 10/04/10 < 37 < 85 <4 <4 <11 <4 <8 <5 <8 <13 <4 <5 <30 <9
TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 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 MW-DN-1081 09/29/10 <43 <34 <4 <4 <9 <3 <8 <5 <7 <14 <4 <4 <30 <8 MW-DN-1091 09/28/10 < 45 < 45 <5 <6 <12 <5 <9 <5 <9 <15 <4 <5 <35 <10 MW-DN-109S 09/28/10 < 38 <92 <4 <4 <10 <4 <10 <5 <8 <14 <4 <5 <34 <9 MW-DN-1101 09/29/10 < 42 < 82 <4 <5 <9 <5 <8 <5 <8 <15 <4 <5 <31 <10 MW-DN-110S 09/29/10 < 45 < 49 <4 <4 <9 <5 <6 <4 <8 <13 <4 <4 <35 <9 MW-DN-111S 10/01/10 <41 <94 <4 <5 <8 <5 <8 <5 <8 <11 <4 <5 <28 <6 MW-DN-1 121 09/28/10 < 38 < 42 <4 <4 <9 <4 <8 <5 <7 <14 <4 <4 <29 <7 MW-DN-1 12S 09/28/10 <44 <36 <5 <5 <9 <5 <8 <5 <7 <15 <4 <4 <30 <10 MW-DN-1 131 09/28/10 < 50 < 38 <4 <4 <8 <4 <9 <5 <7 <14 <4 <4 <31 <11 MW-DN-1 13S 09/28/10 < 35 < 39 <4 <5 <11 <4 <10 <6 <9 <15 <4 <5 <35 <10 MW-DN-1141 10/01/10 < 40 < 28 <5 <4 <9 <4 <9 <5 <8 <11 <4 <5 <29 <8 MW-DN-1 14S 10/01/10 <44 <55 <4 <5 <8 <4 <10 <5 <8 <12 <4 <5 <29 <9 MW-DN-1 151 09/30/10 < 42 < 87 <5 <5 <10 <5 <10 <4 <9 <15 <4 <5 <27 <10 f-A MW-DN-1 15S 09/30/10 < 43 < 43 <5 <4 <9 <4 <9 <5 <8 <13 <4 <4 <28 <7 MW-DN-1 161 09/29/10 < 37 < 77 <3 <4 <9 <4 <8 <4 <7 <14 <4 <4 <30 <9 MW-DN-1i16S 09/29/10 < 42 < 90 <5 <5 <10 <4 <9 <5 <7 <13 <4 <4 <30 <9 MW-DN-1 18S 09/30/10 < 45 < 88 <4 <5 <11 <4 <9 <6 <9 <15 <5 <5 <34 <11 MW-DN-1 191 09/29/10 < 39 < 39 <4 <4 <8 <3 <6 <4 <7 <13 <4 <4 <27 <8 MW-DN-1 19S 09/29/10 < 39 < 36 <4 <5 <9 <5 <7 <5 <7 <15 <4 <4 <29 <9 MW-DN-1201 10/04/10 < 36 < 38 <4 <4 <10 <4 <8 <5 <8 <15 <3 <4 <29 <9 MW-DN-120S 10/04/10 < 41 < 38 <4 <4 <10 <4 <9 <5 <8 <14 <4 <5 <31 <11 MW-DN-121S 10/06/10 < 40 < 49 <4 <5 <9 <5 <10 <5 <9 <14 <4 <4 <28 <11 MW-DN-1221 10/06/10 < 34 < 33 <4 <4 <10 <4 <8 <5 <6 <12 <3 <4 <27 <8 MW-DN-122S 10/06/10 < 55 < 107 <5 <5 <10 <5 <9 <6 <10 <15 <5 <5 <34 <12 MW-DN-1231 10/06/10 < 38 < 64 <5 <4 <11 <4 <8 <5 <7 <14 <4 <3 <28 <8 MW-DN-123S 10/06/10 < 58 <54 <6 <6 <16 <7 <13 <6 <12 <14 <5 <6 <40 <13 MW-DN-1241 10/01/10 < 49 < 41 <4 <4 <11 <4 <7 <5 <8 <13 <4 <4 <31 <6 MW-DN-124S 10/01/10 < 38 < 38 <4 <4 <8 <4 <7 <5 <8 <14 <4 <4 <30 <8
TABLE B-I1.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 SW-DN-101 05/03/10 < 171 SW-DN-101 10/04/10 315 +/- 117 < 0.9 SW-DN-102 05/03/10
- 173 SW-DN-102 10/04/10 340 +/- 121 < 0.7 SW-DN-103 05/03/10
- 171 SW-DN-103 10/04/10 335 +/- 118 < 0.6 SW-DN-104 05/04/10
- 175 SW-DN-104 10/04/10 372 +/- 126 < 0.8 SW-DN-105 05/04/10
- 157 SW-DN-105 10/04/10 387 +/- 127 < 0.6 SW-DN-106 05/04/10
- 159 SW-DN-106 10/04/10 544 +/- 128 < 0.9 B-6
TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 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 SW-DN-101 10/04/10 < 37 < 35 <4 <5 <8 <4 <8 <4 <7 < 14 <3 <5 < 31 <9 SW-DN-102 10/04/10 < 40 < 38 <4 <4 <8 <4 <8 <4 <7 < 14 <4 <4 < 31 <8 SW-DN-103 10/04/10 < 37 < 41 <4 <4 < 10 <5 < 10 <4 <8 < 15 <4 <4 < 28 < 10 SW-DN-104 10/04/10 < 40 <40 <4 <4 < 11 <4 <9 <5 <8 < 15 <4 <5 < 33 < 11 SW-DN-105 10/04/10 < 42 < 39 <4 <4 < 10 <5 <8 <4 <8 < 15 <4 <4 < 31 <6 SW-DN-106 10/04/10 < 42 < 42 <5 <3 <8 <4 <7 <5 <8 < 13 <4 <5 < 31 <9