ML11137A110: Difference between revisions
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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. | 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. | 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. | : 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. | : 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. | In addition, data were compared to previous years' operational data for consistency and trending. | ||
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: 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. | : 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: | 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. | 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: | : 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. | 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. | ||
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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) | 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) | ||
GR-B H-3 36 12 36 GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 4 8.8 (I 1/12)(5.1/14.5) 2000 217 (3/4)(189/246)15 <LLD 15 <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD 9.3 (24/24)(4.1/15.7) 63 I (2/8)(231/1030) 9.6 (12/12)(4.1/15.7) 631 (2/4)(231/1030) | GR-B H-3 36 12 36 GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 4 8.8 (I 1/12)(5.1/14.5) 2000 217 (3/4)(189/246)15 <LLD 15 <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD 9.3 (24/24)(4.1/15.7) 63 I (2/8)(231/1030) 9.6 (12/12)(4.1/15.7) 631 (2/4)(231/1030) | ||
D-57 CONTROL KANKAKEE RIVER AT WILL ROAD(CONTROL) | D-57 CONTROL KANKAKEE RIVER AT WILL ROAD(CONTROL) 2.0 MILES SE OF SITE D-57 CONTROL KANKAKEE RIVER AT WILL ROAD(CONTROL) 2.0 MILES SE OF SITE<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 0 0 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) | ||
SE OF SITE D-57 CONTROL KANKAKEE RIVER AT WILL ROAD(CONTROL) | |||
SE OF SITE<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 0 0 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 | ||
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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: | 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 (PCI/KG DRY)FE-59 CO-60 ZN-65 NA <LLD NA <LLD NA <LLD NB-95 ZR-95 CS-134 CS-137 BA-140 NA <LLD NA <LLD 150 <LLD 180 57 (1/2)NA <LLD NA NA NA NA NA NA NA 0 0 0 0 0 0 57 (1/2)D-27 INDICATOR DRESDEN LOCK AND DAM -DOWNSTREAM | 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)FE-59 CO-60 ZN-65 NA <LLD NA <LLD NA <LLD NB-95 ZR-95 CS-134 CS-137 BA-140 NA <LLD NA <LLD 150 <LLD 180 57 (1/2)NA <LLD NA NA NA NA NA NA NA 0 0 0 0 0 0 57 (1/2)D-27 INDICATOR DRESDEN LOCK AND DAM -DOWNSTREAM 0.8 MILES NW OF SITE 0 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) | ||
NW OF SITE 0 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 | ||
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Grundy County Road (indicator) | Grundy County Road (indicator) | ||
Ridge Road (indicator) | Ridge Road (indicator) | ||
Wildfeather (indicator) | Wildfeather (indicator) 1.4 miles WNW 1.1 miles ESE 2.0 miles SE 0.7 miles S 0.8 miles NW 11.3 miles SW 0.8 miles NW 0.3 miles NNE 0.4 miles S 0.8 miles W 2.6 miles S 3.8 miles SW 3.5 miles SSW 10.5 miles NW 3.7 miles NE 1.7 miles ENE 2.1 miles SSE 4.3 miles N 1.7 miles SE 0.9 miles NNW 1.2 miles ESE 0.8 miles NW 2.8 miles NE 3.2 miles SSE 3.9 miles SSW 1.6 miles NNW 12.8 miles ENE E. Fish D-28 D-46 Dresden Pool of Illinois River, Downstream (indicator) | ||
WNW 1.1 miles ESE 2.0 miles SE 0.7 miles S 0.8 miles NW 11.3 miles SW 0.8 miles NW 0.3 miles NNE 0.4 miles S 0.8 miles W 2.6 miles S 3.8 miles SW 3.5 miles SSW 10.5 miles NW 3.7 miles NE 1.7 miles ENE 2.1 miles SSE 4.3 miles N 1.7 miles SE 0.9 miles NNW 1.2 miles ESE 0.8 miles NW 2.8 miles NE 3.2 miles SSE 3.9 miles SSW 1.6 miles NNW 12.8 miles ENE E. Fish D-28 D-46 Dresden Pool of Illinois River, Downstream (indicator) | |||
DesPlaines River, Upstream (control)nt Dresden Lock and Dam, Downstream (indicator) | DesPlaines River, Upstream (control)nt Dresden Lock and Dam, Downstream (indicator) | ||
F. Sedimen D-27 G. Vegetation Quadrant 1 Quadrant 2 Quadrant 3 Quadrant 4 Control Chris Locknar Robert Pagliano Jim Bloom J.D. Carmichael Glasscock Farm 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 | F. Sedimen D-27 G. Vegetation Quadrant 1 Quadrant 2 Quadrant 3 Quadrant 4 Control Chris Locknar Robert Pagliano Jim Bloom J.D. Carmichael Glasscock Farm 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 | ||
Revision as of 14:57, 30 April 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
ExelknExelon Generation Company, LLC www.exeloncorp.com Dresden Nuclear Power Station Nuclear 65oo North Dresden Road MorTis, IL 60450-9765 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
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1 I1. Introduction
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3 A. O bjectives of the REM P .................................................................................
3 B. Im plem entation of the O bjectives
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3 I1l. Program Description
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4 A .Sam ple Collection
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4 B. Sam ple Analysis .............................................................................................
5 C .Data Interpretation
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6 D. Program Exceptions
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7 E. Program Changes ..........................................................................................
9 IV. Results and Discussion
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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
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11 b. Airborne Iodine .......................................................................
12 2. Terrestrial
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12 a. M ilk ...........................................................................................
12 b. Food Products .........................................................................
13 C .Am bient G am m a Radiation
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13 D. Land Use Survey ...........................................................................................
13 E. Errata Data ....................................................................................................
14 F. Summary of Results -Inter-laboratory Comparison Program .....................
14 Appendices Appendix A Tables Table A-1 Appendix B Tables Table B-1 Table B-2 Radiological Environmental Monitoring Report Summary Radiological Environmental Monitoring Program Annual Summary for the Dresden Nuclear Power Station, 2010 Location Designation, Distance & Direction, and Sample Collection
&Analytical Methods Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2010 Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2010 Figures Figure B-i Figure B-2 Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Table C-I1.1 Table C-I1.2 Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Locations, 2010 Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2010 Data Tables and Figures -Primary Laboratory Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.ii Table C-I11.1 Table C-IV.1 Table C-V.1 Table C-V.2 Table C-V.3 Table C-VI.1 Table C-VII.1 Table C-VII.2 Table C-VIII.1 Table C-IX.1 Table C-IX.2 Table C-IX.3 Figures Figure C-1 Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.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.Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Quarterly TLD Results for Dresden Nuclear Power Station, 2010.Mean Quarterly TLD Results for the Inner Ring, Outer Ring, Other and Control Locations for Dresden Nuclear Power Station, 2010.Summary of the Ambient Dosimetry Program for Dresden Nuclear Power Station, 2010.Surface Water -Gross Beta -Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 -2010.Surface Water -Gross Beta -Stations D-54 (C) and D-57 (C)Collected in the Vicinity of DNPS, 2002 -2010.Surface Water -Gross Beta -Station D-21 Collected in the Vicinity of DNPS, 2007 -2010.Surface Water -Tritium -Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 -2010.Surface Water -Tritium -Station D-54 (C) and D-57 (C) Collected in the Vicinity of DNPS, 2002 -2010.Surface Water -Tritium -Station D-21 Collected in the Vicinity of DNPS, 2007 -2010.iii Figure C-7 Figure C-8 Figure C-9 Figure C-10 Figure C-11 Figure C-12 Figure C-13 Figure C-14 Appendix D Tables Table D-1 Table D-2 Table D-3 Ground Water -Tritium -Stations D-23 and D-35 Collected in the Vicinity of DNPS, 2000 -2010.Air Particulate
-Gross Beta -Stations D-01 and D-02 Collected in the Vicinity of DNPS, 2000 -2010.Air Particulate
-Gross Beta -Stations D-03 and D-04 Collected in the Vicinity of DNPS, 2000 -2010.Air Particulate
-Gross Beta -Stations D-07 and D-1 2 (C) Collected in the Vicinity of DNPS, 2000 -2010.Air Particulate
-Gross Beta -Stations D-45 and D-53 Collected in the Vicinity of DNPS, 2000 -2010.Air Particulate
-Gross Beta -Stations D-08 and D-1 0 Collected in the Vicinity of DNPS, 2005 -2010.Air Particulate
-Gross Beta -Stations D-13 and D-14 Collected in the Vicinity of DNPS, 2005 -2010.Air Particulate
-Gross Beta -Stations D-55 and D-56 Collected in the Vicinity of DNPS, 2006 -2010.Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2010 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2010 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 AP/I D-07 AP/I AP/I AP/I AP/I AP/I D-07 D-02 D-03 D-07 D-01 03/05/10 -03/12/10 03/12/10 -03/19/10 03/26/10 -04/02/10 04/23/10 -04/30/10 04/23/10 -04/30/10 04/23/10 -04/30/10 05/21/10 -05/28/10 05/28/10 -06/25/10 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.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.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.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.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.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.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.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.SW D-21 Table D-1 LISTING OF SAMPLE.... .... ... .(c nin.. ..... .)Sample Location Collection Reason Type Code Date SW D-21 AP/I AP/I AP/I D-03 D-03 D-04 06/25/10 -07/30/10 07/23/10 -07/30/10 08/13/10 -08/20/10 08/13/10 -08/20/10 08/20/10 -08/27/10 08/27/10 -09/03/10 09/10/10 -09/17/10 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.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.Low run time of 136.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />; cause is unknown.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.Low run time of 152.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />; cause is unknown. Timer was replaced.Low run time of 135.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />; cause is unknown.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.
AP/I AP/I AP/I D-03 D-03 D-03 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 A N 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 J S 0.5 -16.0 K SSW 3.3 L SW 3.6 -11.4 M WSW 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.
Intentionally left blank 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 (PCI/LITER)
GR-B H-3 36 12 36 GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 4 8.8 (I 1/12)(5.1/14.5) 2000 217 (3/4)(189/246)15 <LLD 15 <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD 9.3 (24/24)(4.1/15.7) 63 I (2/8)(231/1030) 9.6 (12/12)(4.1/15.7) 631 (2/4)(231/1030)
D-57 CONTROL KANKAKEE RIVER AT WILL ROAD(CONTROL) 2.0 MILES SE OF SITE D-57 CONTROL KANKAKEE RIVER AT WILL ROAD(CONTROL) 2.0 MILES SE OF SITE<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 0 0 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 (PCI/LITER)
ZR-95 1-131 CS-134 CS-137 BA- 140 30 <LLD 15 <LLD 15 <LLD 18 <LLD 60 <LLD 15 <LLD 2000 301 (12/16)(216/400)<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 LA-140<LLD 0 GROUND WATER (PCI/LITER)
H-3 16 NA 301 (12/12)(216/400)D-23 INDICATOR THORSEN WELL 0.7 MILES S OF SITE 0 GAMMA MN-54 16 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 (PCI/LITER)
CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 15 <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD 15 <LLD NA NA NA NA NA NA NA NA 0 0 0 0 0 1-131 0 0 0 CS-134* 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 (PCI/LITER)
CS-137 BA- 140 18 <LLD NA 60 <LLD NA 0 0 0 LA-140 15 <LLD NA FISH (PCI/KG WET)GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 130 <LLD 130 <LLD 260 <LLD 130 <LLD 260 <LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 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
,>I FISH (PCI/KG WET)SEDIMENT (PCI/KG DRY)NB-95 ZR-95 CS-134 CS-137 BA-140 NA <LLD NA <LLD 130 <LLD 150 <LLD NA <LLD NA <LLD NA <LLD NA <LLD<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 LA- 140 GAMMA MN-54 2 NA NA 0 CO-58 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 (PCI/KG DRY)FE-59 CO-60 ZN-65 NA <LLD NA <LLD NA <LLD NB-95 ZR-95 CS-134 CS-137 BA-140 NA <LLD NA <LLD 150 <LLD 180 57 (1/2)NA <LLD NA NA NA NA NA NA NA 0 0 0 0 0 0 57 (1/2)D-27 INDICATOR DRESDEN LOCK AND DAM -DOWNSTREAM 0.8 MILES NW OF SITE 0 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 (PCI/KG DRY)LA- 140 AIR PARTICULATE (E-3 PCI/CU.METER)
GR-B 676 GAMMA MN-54 52 CO-58 FE-59 CO-60 ZN-65 NB-95 NA <LLD 10 18 (621/624)(6/47)NA <LLD NA <LLD NA <LLD NA <LLD NA <LLD NA <LLD 19 (49/52)(8/40)<LLD<LLD<LLD<LLD<LLD<LLD 19 (51/52)(8/40)NA 0 0 0 0 0 0 0 D-08 INDICATOR PRAIRIE PARK 3.8 MILES SW OF SITE* 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 (E-3 PCI/CU.METER)
ZR-95 CS-134 CS-137 BA-140 LA-140 NA <LLD 50 <LLD 60 <LLD NA <LLD NA <LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 00 AIR IODINE (E-3 PCI/CU.METER)
MILK (PCI/LITER)
GAMMA 1-131 676 70 <LLD<LLD<LLD 0 1-131 19 19 I NA 0 GAMMA 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 (PCI/LITER)
CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 NA NA NA NA NA NA NA NA NA NA NA NA 15 NA 18 NA<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 0<LLD 0 0 CS-137<LLD* 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 (PCI/LITER)
BA-140 LA-140 GAMMA MN-54 60 NA 15 NA<LLD<LLD 0 0>VEGETATION (PCI/KG WET)10 NA <LLD<LLD 0 CO-58 FE-59 CO-60 ZN-65 NB-95 NA <LLD NA <LLD NA <LLD NA <LLD NA <LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 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 (PCI/KG WET)ZR-95 1-131 CS-134 CS-137 BA-140 LA- 140 NA <LLD 60 <LLD 60 <LLD 80 <LLD NA <LLD NA <LLD NA 24 (350/350)(19/33)<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 0<LLD DIRECT RADIATION (MILLI-ROENTGEN/QTR.)
TLD-QUARTERLY 358 22 (8/8)(19/25)30 (4/4)(28/32)D-201-1 INDICATOR 4.8 MILES N 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)
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 D-52 D-57 Illinois River at EJ&E Bridge (indicator)
DesPlaines River, Upstream (control)Kankakee River at Will Road (control)B. Ground/Well Water D-23 D-35 Thorsen Well (indicator)
Dresden Lock and Dam (indicator)
C. Milk -bi-weekly
/ monthly D-25 Biros Farm (control)D. Air Particulates
/ Air Iodine D-01 D-02 D-03 D-04 D-07 D-08 D-10 D-12 D-14 D-45 D-53 D-55 D-56 Onsite 1 (indicator)
Onsite 2 (indicator)
Onsite 3 (indicator)
Collins Road (indicator)
Clay Products (indicator)
Prairie Park (indicator)
Goose Lake Village (indicator)
Lisbon (control)Channahon (indicator)
McKinley Woods Road (indicator)
Grundy County Road (indicator)
Ridge Road (indicator)
Wildfeather (indicator) 1.4 miles WNW 1.1 miles ESE 2.0 miles SE 0.7 miles S 0.8 miles NW 11.3 miles SW 0.8 miles NW 0.3 miles NNE 0.4 miles S 0.8 miles W 2.6 miles S 3.8 miles SW 3.5 miles SSW 10.5 miles NW 3.7 miles NE 1.7 miles ENE 2.1 miles SSE 4.3 miles N 1.7 miles SE 0.9 miles NNW 1.2 miles ESE 0.8 miles NW 2.8 miles NE 3.2 miles SSE 3.9 miles SSW 1.6 miles NNW 12.8 miles ENE E. Fish D-28 D-46 Dresden Pool of Illinois River, Downstream (indicator)
DesPlaines River, Upstream (control)nt Dresden Lock and Dam, Downstream (indicator)
F. Sedimen D-27 G. Vegetation Quadrant 1 Quadrant 2 Quadrant 3 Quadrant 4 Control Chris Locknar Robert Pagliano Jim Bloom J.D. Carmichael Glasscock Farm 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 D-102-1 and -2 D-103-1 and -2 D-104-1 and-2 D-105-1 and -2 D-106-1 and -2 D-107-1 and -2 D-108-1 and -2 D-109-1 and -2 D-110-3 and -4 D-111-1 and -2 D-112a-1 and-2 D-113-1 and -2 D-114-1 and -2 D-115-1 and -2 D-116-1 and -2 Outer Ring D-201-1 and -2 D-202-1 and -2 D-203-1 and -2 D-204-1 and -2 D-205-1 and -2 D-206-1 and -2 D-207-1 and -2 D-208-1 and -2 D-209-1 and -2 D-210-1 and -2 D-211-1 and -2 D-212-3 and -4 D-213-1 and -2 D-214-1 and -2 D-215-1 and -2 D-216-1 and -2 1.0 miles N 1.3 miles NNE 1.2 miles NE 1.7 miles ENE 1.5 miles E 1.1 miles ESE 1.4 miles SE 1.9 miles SSE 0.8 miles S 0.9 miles SSW 0.6 miles SW 0.7 miles WSW 0.9 miles W 0.9 miles WNW 0.8 miles NW 1.0 miles NNW 4.8 miles N 5.1 miles NNE 4.7 miles NE 5.0 miles ENE 4.0 miles E 3.5 miles ESE 4.2 miles SE 4.9 miles SSE 4.1 miles S 4.9 miles SSW 4.8 miles SW 6.0 miles WSW 4.5 miles W 5.0 miles WNW 4.8 miles NW 4.9 miles NNW 0.8 miles NW 0.3 miles NNE 0.4 miles S 0.8 miles W 2.6 miles S 3.8 miles SW 3.5 miles SSW 3.7 miles NE 1.7 miles ENE 2.1 miles SSE 4.3 miles N 1.7 miles SE 10.5 miles NW Other D-01-1 and -2 D-02-1 and -2 D-03-1 and -2 D-04-1 and -2 D-07-1 and -2 D-08-1 and -2 D-10-1 and -2 D-14-1 and -2 D-45-1 and -2 D-53-1 and -2 D-55-1 and -2 D-56-1 and -2 Onsite 1 Onsite 2 Onsite 3 Collins Road Clay Products Prairie Park Goose Lake Village Channahon McKinley Woods Road Grundy County Road Ridge Road Wildfeather Control D-12-1 and -2 Lisbon 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 11s4 D42 S 14 13340 I 0 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 12 out U61u~ U04 =K N 0 5 WMin S t0 U Wimimm OFF= WE CALOILANN MNUAL fb AM lm 7w wLCAmmt AM NU ELKlI=* Ar Buming Lanlon0* ¥LaOmi* 'LV LflhIln 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 PERIOD 01/01/10 -01/29/10 02/05/10 -02/26/10 03/05/10 -03/26/10 04/02/10 -04/30/10 05/07/10 -05/28/10 06/04/10 -06/25/10 07/03/10 -07/30/10 08/06/10 -08/27/10 09/03/10 -09/24/10 10/01/10 -10/29/10 11/05/10 -11/26/10 12/03/10 -12/31/10 D-21 D-52 D-57 9.3 12.6 7.2< 3.8 7.4 7.4 14.5 5.1 9.4 9.9 5.2 8.6+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-2.6 2.6 2.6 2.6 2.2 3.0 2.3 2.4 2.5 2.1 3.3 (1)(1)5.8 9.5 10.0 7.9 12.1 7.1 7.7 10.9 8.3 8.9 10.4 9.6+/- 2.5+/- 2.7+/- 3.0+/- 1.6+/- 3.2+/- 2.3+/- 2.6+/- 2.7+/- 2.3+/- 2.5+/- 2.4+/- 3.1 4.2 9.5 7.4 9.2 8.0 14.6 11.9 6.0 12.8 4.1 12.4 15.7+/- 2.2+/- 2.5+/- 2.3+/- 1.5+/- 2.8+/- 3.1+/- 3.0+/- 2.4+/- 3.1+/- 2.2+/- 2.5+/- 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 PERIOD D-21 D-52 D-57 01/01/10 04/02/10 07/03/10 09/24/10-03/26/10-06/25/10-09/24/10-12/31/10 189 +/- 121< 159 246 +/- 134 216 +/- 109 178 162 199 159* 177< 157 231 +/- 132 1030 +/- 169 631 +/- 1130 MEAN 217 +/- 57* 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 PERIOD D-21 01/01/10 -01/29/01/29/10 -02/26/02/26/10 -03/26 03126110 -04/30 04/30/10 -05/28 06/04/10 -06/25/06/25/10 -07/30/07/30/10 -08/27/08/27/10 -09/24, 09/24/10 -10/29 10/29/10 -11/26 11/26/10 -12/31 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-1 37 Ba-140 La-140'10'10/10/10/10/10'10~10/10/10/10/10 (1)(1)MEAN<7<5<2<1<1<6<5<2<4<4<4<5<5<6<1<2<2<4<3<1<3<4<4<5<6<7<2<1<2<6<5<2<5<4<4<6< 11< 12<4<3<4<11< 10<4<8<9< 11< 14<4<6<1<1<1<5<5<2<6<4<5<5 12 12 3 3 3 12 12 3 10 9 8 11<7<5<2<2<2<5<6<2<4<4<6<6< 12< 11<3<3<3<9<8<3<9<7<8<11< 10<9<8<9<9<9< 15< 10< 13< 11<9< 11<5<6<1<1<1<6<5<1<4<4<4<5<7<7<2<1<2<6<5<2<6<4<6<6< 29< 27< 15< 15< 15< 24< 35< 18< 28< 26< 27< 27<8<8<5<4<5<7< 11<5<9<9<9< 10<8< 10<4<6<6<9<5<5<8<11<7<9 D-52 01/01/10 02/05/10 03/05/10 04/02/10 05/07/10 06/04/10 07/03/10 08/06/10 09/03/10 10/01/10 11/05/10 12/03/10 01/29/10 02/26/10 03/26/10 04/30/10 05/28/10 06/25/10 07/30/10 08/27/10 09/24/10 10/29/10 11/26/10 12/31/10<5<7<1<2<2<5<3<2<4<4<6<7< 12< 13<3<4<4< 12<7<4<8<9<8< 13<4<8<1<2<2<5<3<1<3<5<5<8< 11< 17<3<3<3< 12<6<3<8< 10< 12< 13<7<8<2<2<2<6<4<2<4<5<6<5<8< 13<3<3<4< 10<7<3<7<7< 11< 12<8< 12<7< 11< 11<8<9<9< 11< 13< 12< 11<5<7<1<2<2<5<3<1<3<5<6<6<5<8<1<2<2<6<3<2<4<4<7<6< 23< 37< 13< 19< 18< 26< 19< 15< 25< 29< 26< 31 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 PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 D-57 01/01/10 01/29/10 02/26/10 03/26/10 04/30/10 05/28/10 06/25/10 07/30/10 08/27/10 09/24/10 10/29/10 11/26/10-01/29/10-02/26/10-03/26/10-04/30/10-05/28/10-06/25/10-07/30/10-08/27/10-09/24/10-10/29/10-11/26/10-12/31/10<6<4<2<2<2<4<3<2<3<5<5<5<8<4<2<2<2<4<4<2<6<4<4<5< 12<7<5<4<4<9<9<4< 10<11<9< 14<7<4<2<2<2<4<3<2<4<5<5<5< 14<8<4<3<3<7<7<4< 10<9< 11< 13<5<4<2<2<2<4<4<2<5<5<5<7< 10<7<4<4<3<7<7<4<9<9<8< 10<9<7< 10< 13< 10<7< 10< 11< 15< 12< 10< 12<5<4<2<2<2<4<3<2<4<4<5<6<6<4<2<2<2<4<3<2<5<4<5<7< 29< 18< 19< 20< 17< 20< 23< 20< 28< 29< 25< 30<8<7<6<6<5<5<9<6<9< 11<9<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 PERIOD 01108/10 -01/08/10 02/12/10 -02/12/10 03/12/10 -03/12/10 04/09/10 -04/09/10 05/14/10 -05/14/10 06/11/10 -06/11/10 07/09/10 -07/09/10 08/13/10 -08/13/10 09/10/10 -09/10/10 10/08/10 -10/08/10 11/12/10 -11/12/10 12/10/10 -12/10/10 D-23 D-35 267 311 297 363 228 400 351 216 360 238 264 317+/- 116+/- 118+/- 113+/- 118+/- 116+/- 118+/- 116+/- 118+/- 126+/- 117+/- 114+/- 111< 168< 160< 160< 178 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 PERIOD D-23 01/08/10 -01/08/02/12/10 -02/12/03/12/10 -03/12/04/09/10 -04/09/05/14/10 -05/14/06/11/10 -06/11/07/09/10 -07/09/08/13/10 -08/13/09/10/10 -09/10/10/08/10 -10/08/11/12/10 -11/12/12/10/10 -12/10/Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 10 10 10 10 10 10 10 10 10 10 10 10<3<4<5<3<1<5<5<3<4<6<4<7<4<4<4<3<1<4<5<4<5<5<5<6<8<9<9<6<3<9< 11<8<9< 10<9< 13<3<4<4<3<1<4<5<3<4<4<4<7<7<8<9<5<2< 10< 10<7<8<8<9< 14<4<4<5<3<1<5<6<4<4<6<5<7 6 9 9 6 2 8 8 6 7 10 7 9< 15< 12< 12<8< 12< 11<9<8< 10<9< 11< 11<3<4<5<3<1<5<5<3<4<5<4<5<3<4<5<3<1<5<5<3<4<4<4<5< 30< 26< 27< 18< 16< 26< 24< 23< 26< 24< 25< 26< 10<9<7<7<5<8<7<8<8<6<7< 12 MEAN ( D-35 01/08/10 04/09/10 07/09/10 10108/10 01/08/10 04/09/10 07/09/10 10/08/10<3<3<4<5<4<3<5<4<9<7< 10< 10<3<3<4<6<7<6<9< 10<3<4<5<5<6<5<8<8< 14<9<8<8<3<3<4<5<4<3<4<6< 28< 21< 22< 26 11 6 8 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 PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-1 34 Cs-1 37 Ba-140 La-140 D-28 Freshwater Drum Largemouth Bass Largemouth Bass Channel catfish 05/17/10 05/17/10 10/11/10 10/12/10< 31< 50< 72< 18< 47< 66<74< 17< 127< 170< 144< 44 33 50 82 23< 76< 73< 153< 47<48< 65< 93< 15< 84< 127< 129< 31< 33< 47< 67< 19< 41< 56< 73< 20< 914< 1120< 375< 101< 241< 333< 139< 14 MEAN D-46 Common Carp Largemouth Bass Channel catfish Largemouth Bass 05/17/10 05/17/10 10/11/10 10/11/10< 40< 55< 63< 70<44< 73< 49< 78< 100< 177< 128< 148 38 35 56 84< 75< 109< 134< 163 57 80 84 89< 76< 139< 94< 129< 27< 49< 52< 72< 32< 55<64< 76< 891< 1350< 334< 422< 263< 458< 121< 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 PERIOD D-27 05/28/10 < 25 10/08/10 < 40 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140<32 <83 <28 <63 <26<36 < 78 < 39 < 77 < 47< 62 < 26< 64 < 33< 39 < 432 57 +/-34 < 226< 136< 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 PERIOD GROUP III I u IU i/lU 01/08/10 01/15/10 01/22/10 01/29/10 02/05/10 02/12/10 02/19/10 02/26/10 03/05/10 03/12/10 03/19/10 03/26/10 04/02/10 04/09/10 04/16/10 04/23/10 04/30/10 05/07/10 05/14/10 05/21/10 05/28/10 06/04/10 06/11/10 06/18/10 06/25/10 07/03/10 07/09/10 07/16/10 07/23/10 07/30/10 08/06/10 08/13/10 08/20/10 08/27/10 09/03/10 09/10/10 09/17/10 09/24/10 10/01/10 10/08/10 10/15/10 10/22/10 10/29/10 11/05/10 11/12/10 11/19/10 11/26/10 12/03/10 12/10/10 12/17/10 12/24/10 uilo IUOI 01/15/10 01/22/10 01/29/10 02/05/10 02/12/10 02/19/10 02/26/10 03/05/10 03/12/10 03/19/10 03/26/10 04/02/10 04/09/10 04/16/10 04/23/10 04/30/10 05/07/10 05/14/10 05/21/10 05/28/10 06/04/10 06/11/10 06/18/10 06/25/10 07/03/10 07/09/10 07/16/10 07/23/10 07/30/10 08/06/10 08/13/10 08/20/10 08/27/10 09/03/10 09/10/10 09/17/10 09/24/10 10/01/10 10/08/10 10/15/10 10/22/10 10/29/10 11/05/10 11/12/10 11/19/10 11/26/10 12/03/10 12/10/10 12/17/10 12/24/10 12/31/10 D-08 27 +/-4 31 +/- 5 33 +/- 4 22 +/- 5 27 +/- 5 16 +/- 4 23 +/- 5 24 +/- 4 8+/-4 16 +/-4 10 +/-4 18 +/-5 21 +/-5 8+/-4 21 +/-4 14 +/-4 18 +/-4 10 +/-4 9+/-4 12 +/-4 14 +/-4<9 14 +/-4 17 +/-4 13 +/-4 13 +/-4 16 +/-5 21 +/- 4 22 +/- 5 15 +/- 4 21 +/- 5 25 +/- 4 23 +/- 5 18 +/- 5 22 +/- 4 10 +/- 4 19 +/- 4 23 +/- 5 18 +/- 4 13 +/- 4 40 +/- 6 19 +/- 4 12 +/- 4 13 +/- 3 18 +/- 4 21 +/- 5 21 +/- 5 27 +/- 4 28 +/- 5 26 +/- 4 35 +/- 4 15 +/- 4 D-10 31 +/- 4 26 +/- 5 30 +/- 4 19 +/- 5 28 +/- 5 15 +/- 4 16 +/- 4 23 +/- 4 7+/-4 11 +/-4 11 +/-4 14 +/-5 19 +/-5 6+/-4 20 +/-4 12 +/-4 14 +/-4 10 +/-4 9+/-4 12 +/-4 13 +/-4 10 +/-6 10 +/-4 11 +/-4 13 +/-4 12 +/-4 21 +/-5 20 +/-4 20 +/-4 14 +/-4 20 +/-5 26 +/-4 24 +/-5 16 +/-5 23 +/-5 14 +/-4 21 +/-4 22 +/-5 17 +/-4 17 +/-4 36 +/-5 17 +/-4 15 +/-4 13 +/-3 19 +/-4 24 +/-5 26 +/-5 30 +/-4 32 +/-5 27 +/-4 36 +/-4 16 +/-4 D-14 26 +/-4 23 +/- 4 30 +/- 4 17 +/-4 25 +/-5 15 +/-4 16 +/-4 22 +/-4 6+/-4 12 +/-4 11 +/-4 15 +/-5 14 +/-4 7+/-4 20 +/-4 12 +/- 4 14 +/- 4<6 12 +/- 4 11 +/-4 13 +/-4 13 +/-6 16 +/-4 9+/-4 13 +/-4 12 +/-4 16 +/-5 19 +/-4 21 +/-5 18 +/-5 21 +/-5 23 +/-4 20 +/-5 18 +/-5 18 +/-4 14 +/-4 17 +/-4 18 +/-4 16 +/-4 14 +/-4 34 +/-5 20 +/-4 17 +/-4 10 +/-3 22 +/-5 21 +/-5 18 +/- 4 25 +/- 4 26 +/- 5 24 +/- 4 31 +/- 4 14 +/- 4 D-55 28 4 26 +/-5 32 +/-4 18 +/-4 22 +/-5 17 +/-4 18 +/-4 21 +/-4 8+/-4 10 +/-4 13 +/-4 19 +/-5 10 +/-4 6+/-4 21 +/-5 11 +/-4 13 +/-4 8+/-4 9+/-4 14 +/-4 15 +/-4 9+/-6 15 +/-4 11 +/-4 18 +/-4 12 +/-4 21 +/-5 22 +/-4 21 +/-5 14 +/-4 21 +/-5 27 +/-4 25 +/-5 16 +/-4 21 +/-4 13 +/- 4 21 +/- 4 23 +/- 5 18 +/- 4 20 +/- 5 37 +/- 5 24 +/- 4 17 +/- 4 12 +/- 3 22 +/- 5 21 +/- 5 27 +/- 5 29 +/- 4 27 +/- 5 27 +/- 4 30 +/- 4 20 +/- 4 GROUP IV D-12 26 +/-5 29 +/-4 21 +/-5 26 +/-5 14 +/- 4 14 +/- 4 19 +/- 4 8+/-4 11 +/-4 10 +/-4 22 +/-6 18 +/-5< 6 18 +/-4 11 +/-4 15 +/- 4< 6 10 +/- 4 13 +/- 4 15 +/- 4< 9 13 +/- 4 11 +/-4 14 +/-4 13 +/-4 19 +/-5 19 +/-4 21 +/-5 17 +/-5 22 +/-5 21 +/-4 23 +/-5 16 +/-4 22 +/-4 14 +/-4 19 +/-4 22 +/-5 16 +/-4 20 +/-5 40 +/-6 18 +/-4 22 +/-5 11 +/-3 19 +/-4 20 +/-5 13 +/-4 27 +/-4 27 +/-5 27 +/-4 36 +/-4 16 +/-4 U 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 COLLECTION MIN MAX MEAN +PERIOD 2SD GROUP II -NEAR-FIELD LOCATIONS COLLECTION MIN MAX MEAN +PERIOD 2SD GROUP III -FAR-FIELD LOCATIONS COLLECTION MIN MAX MEAN +PERIOD 2SD UI/UI/1U -Ul2I9IU1 01/29/10 -02/26/10 02/26/10 -04102110 04102110 -04/30/10 04/30/10 -05/28/10 05/28/10 -07/03/10 07/03/10 -07/30/10 07/30/10 -09/03/10 09/03/10 -10/01/10 10/01/10 -10/29/10 10/29/10 -12/03/10 12/03/10 -12/31/10 01/01/10 -12/31/10 15 14 7 6 7 9 13 16 12 13 12 12 42 28 19 20 14 16 47 31 26 36 28 34 26 +/- 14 20 +/- 10 13 +/- 8 13 +/- 9 11 +5 12 +4 21 + 17 21 +8 17 +9 21 + 18 21 +10 24 :114 UiU1/i1U -UllVWiU 01/29/10 -02/26/10 02/26/10 -04/02/10 04/02/10 -04/30/10 04/30/10 -05/28/10 05/28/10 -07/03/10 07/03/10 -07/30/10 07/30/10 -09/03/10 09/03/10 -10/01/10 10/01/10 -10/29/10 10/29/10 -12/03/10 12/03/10 -12/31/10 11 10 8 8 6 10 12 15 13 10 11 12 31 28 19 24 17 17 24 28 24 40 32 38 25:+/- 9 20 +/- 10 13 +/- 6 14 +/- 9 12 +/- 6 13 +/- 4 19 +/- 7 21 +/- 7 17 +/- 7 22 +/- 20 21 +/- 11 26 +/- 16 U1/U1110 -u1l2911U 01/29/10 -02/26/10 02/26/10 -04/02/10 04/02/10 -04/30/10 04/30/10 -05/28/10 05/28/10 -07/03/10 07/03/10 -07/30/10 07/30/10 -09/03/10 09/03/10 -10/01/10 10/01/10 -10/29/10 10/29/10 -12/03/10 12/03/10 -12/31/10 17 15 6 6 8 9 14 16 10 12 10 14 33 28 21 21 15 18 22 27 23 40 30 36 26 +/- 11 20 +/- 9 12 9 14 + 10 11 +/-4 13 5 19 6 21 +/- 6 18 +/- 7 22 +/-=19 21 +/- 11 26 + 14 GROUP IV -CONTROL LOCATION COLLECTION MIN MAX MEAN +/-PERIOD 2SD 01/01/10 -01/29/10 21 29 25 +/- 6 01/29/10 -02/26/10 14 26 18 +/- 12 02126/10 -04/02/10 8 22 14 +/- 12 04/09/10 -04/30/10 11 18 14 +/- 7 05/07/10 -05/28/10 10 15 13 t 5 06/04/10 -07/03/10 11 14 13 +/- 3 07/03/10 -07/30/10 17 21 19 +/- 4 07/30/10 -09/03/10 16 23 21 +/- 6 09/03/10 -10/01/10 14 22 18 +/- 7 10/01/10 -10/29/10 18 40 25 +/- 20 10/29/10 -12103/10 11 27 18 +/- 13 12/03/10 -12/31/10 16 36 26 +/- 17 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 PERIOD D-01 01/01/10 -04/02/10 04/02/10 -07/03/10 07/03/10 -10/01/10 10/01/10 -12/31/10 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140<2<4<3<2<3<3<4<2<8<9<8<4<3<4<3<2<7<7<9<4<4<4<4<3<8<6<9<4<3<3<3<2<2<3<3<2* 131< 37* 113< 26< 63< 15< 46< 10 MEAN D-02 01/01/10 04/02/10 07/03/10 10/01/10-04/02/10-07/03/10-10/01/10-12/31/10<3<3<2<2<4<5<2<2<8<12<6<3<4<4<2<2<10<8<5<4<6<5<3<2<7<8<5<3<3<4<2<1<3<4<1<2* 172< 46< 63< 20< 85* 18< 22<11 MEAN-D-03 01/01/10 04/02/10 07/03/10 10/01/10 MEAN D-04 01/01/10 04/02/10 07/03/10 10/01/10-04/02/10-07/03/10-10/01/10-12/31/10<3<3<3<3<4<3<5<4<10<6<9<9<3<3<3<3<6<6<9<8<4<5<5<3<7<6<8<7<2<4<4<4<2<3<4<3* 126< 46* 122< 33< 47* 17< 31* 14-04/02/10-07/03110-10/01/10-12/31/10<4<4<3<2<5<5<3<2<12* 14<9<7<4<3<2<2<7<6<5<4<6<3<3<1<10<6<4<4<3<4<2<2<3<4<2<2* 187< 55< 88< 30< 81< 20<34< 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 PERIOD D-07 01/01/10 -04/02/10 04/02/10 -07/03/10 07/03/10 -10/01/10 10/01/10 -12/31/10 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140<3<4<2<2<2<4<5<2<9* 10< 15<6<3<5<4<3<7< 12<9<7<3<6<4<3<7<8<7<5<3<4<3<2<2<3<3<2* 147< 62* 114< 30* 58< 21< 42<8 MEAN D-08 01/01/10 04/02/10 07/03/10 10/01/10-04102/10-07/03/10-10/01/10-12/31/10<2<3<3<4<4<4<4<3<11<8< 10<8<2<3<5<3<6<9<8<7<4<5<5<4<7<6<5<5<3<3<3<3<2<2<3<3* 119< 39* 119< 37< 60* 17<44* 12 MEAN D-10 01/01/10 04/02/10 07/03110 10/01/10 MEAN D-12 01/01/10 04/02/10 07/03/10 10/01/10-04/02/10-07/03/10-10/01/10-12/31/10<2<3<3<3<4<5<3<3<11<11<7<7<3<4<2<2<7<9<6<8<3<5<4<3<6<9<6<5<3<3<2<3<2<4<2<3* 124< 57< 67< 36< 42* 14< 27* 16-04/02/10-07/03/10-10/01/10-12/31/10<4<3<2<2<5<5<3<2* 17* 10<9<6<3<4<3<3<9<7<8<7<5<5<4<3<8<8<7<5<3<3<3<2<3<4<2<2* 183* 51< 81< 29< 62< 24< 21< 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 PERIOD D-14 01/01/10 -04/02/10 04/02/10 -07/03/10 07/03/10 -10/01/10 10/01/10 -12/31/10 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140<3<3<3<2<4<3<4<3< 13<9< 11<7<3<4<3<3<9<8<7<6<4<3<4<3<7<5<7<4<3<3<3<2<2<4<3<2< 145< 57< 95< 32< 43< 22< 41< 15 MEAN D-45 01/01/10 -04/02/10 04/02/10 -07/03/10 07/03/10 -10/01/10 10/01/10 -12/31/10<4<4<4<3<4<5<4<4< 13< 13<8<9<2<3<3<2<7< 10<7<8<5<6<4<4< 10< 10<8<6<3<4<3<3<2<3<3<3< 191< 68< 108< 41< 72< 16< 31<9 MEAN D-53 01/01/10 -04/02/10 04/02/10 -07/03/10 07/03/10 -10/01/10 10/01/10 -12/31/10<3<4<2<2<3<4<4<3< 11< 12<9<4<3<3<2<3<6<9<5<5<4<4<4<2<6<9<5<4<3<4<2<2<2<4<2<2< 93< 56< 79< 27< 47< 27< 31< 10 MEAN D-55 01/01/10 -04/02/10 04/02/10 -07/03/10 07/03/10 -10/01/10 10/01/10 -12/31/10<4<4<3<3<6<4<3<3< 16< 14<8<6<2<4<3<3<8<9<7<6<6<5<4<4<8<6<8<6<3<4<3<3<3<4<3<3< 171<64< 91< 41< 70< 16< 30< 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 PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 D-56 01/01/10 -04/02/10 04/02/10 -07/03/10 07/03/10 -10/01/10 10/01/10 -12/31/10<4<3<2<2<6 <16 <5<4 <11 <4<4 <10 <2<2 <2 <2<9 <6 <9 <4 <4 <191<8 <5 <8 <3 <3 <41<7 <4 <6 <3 <3 <82<3 <1 <4 <1 <2 <21 9< 42< 27< 41<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 01/15/10 01/22/10 01/29/10 02/05/10 02/12/10 02/19/10 02/26/10 03/05/10 03/12/10 03/19/10 03/26/10 04/02/10 04/09/10 04/16/10 04/23/10 04/30/10 05/07/10 05/14/10 05/21/10 05/28/10 06/04/10 06/11/10 06/18/10 06/25/10 07/03/10 07/09/10 07/16/10 07/23/10 07/30/10 08/06/10 08/13/10 08/20/10 08/27/10 09/03/10 09/10/10 09/17/10 09/24/10 10/01/10 10/08/10 10/15/10 10/22/10 10/29/10 11/05/10 11/12/10 11/19/10 11/26/10 12/03/10 12/10/10 12/17/10 12/24/10-01/08/10-01/15/10-01/22/10-01/29/10-02/05/10-02/12/10-02/19/10-02/26/10-03/05/10-03/12/10-03/19/10-03/26/10-04/02/10-04/09/10-04/16/10-04/23/10-04/30/10-05/07/10-05/14/10-05/21/10-05/28/10-06/04/10-06/11/10-06/18/10-06/25/10-07/03/10-07/09/10-07/16/10-07/23/10-07/30/10-08/06/10-08/13/10-08/20/10-08/27/10-09/03/10-09/10/10-09/17/10-09/24/10-10/01/10-10/08/10-10/15/10-10/22/10-10/29/10-11/05/10-11/12/10-11/19/10-11/26/10-12/03/10-12/10/10-12/17/10-12/24/10-12/31/10< 26< 30< 43< 14< 32< 28< 23< 14< 21< 15< 29< 13< 26< 30< 30<6< 26< 16< 22< 14<24 (1)< 20< 49< 17< 24< 22< 17< 15< 27< 16< 31< 19< 21< 28< 26< 17< 29< 14< 46< 25< 58< 42< 27< 52< 44< 34< 33< 44< 50< 35< 67< 36< 49< 29< 24< 25< 32< 38< 23< 26< 21< 28< 29< 24< 26< 30< 29< 11< 27 (1)< 30< 22< 26< 25< 36< 50< 31< 24< 29< 40< 24< 15< 26< 17< 44< 21< 28< 26< 40< 29< 25< 46< 46< 58< 42< 27< 52< 44< 34< 33< 44< 50< 64< 67< 60< 49< 30< 43< 26< 18< 38< 23< 26< 21< 27< 29< 24< 26< 30< 29< 11< 27 (1)< 30< 22< 26< 25< 36< 50< 31< 24< 28< 40< 24< 27< 65 (1)< 31< 35< 26 (1)< 28 (1)< 33 (1)< 40< 36 (1)< 25< 46< 46< 58< 42< 27< 52< 44< 34< 33< 44< 50< 64< 67< 60< 48< 30< 43< 26< 32< 38< 10< 26< 21< 27< 29< 24< 26< 30< 29< 11< 26< 30< 22< 26< 24< 36< 49< 31< 24< 29< 40< 24< 27< 26< 31< 35< 9 (1)< 28< 26< 40< 29< 25< 46< 46< 56< 42< 27< 50< 44< 34< 33< 44< 50< 64< 67< 60< 49< 42< 43< 26< 32< 38< 23< 26< 12< 30 (1)< 25 (1)< 24< 36 (1)< 15< 28< 11< 38 (1)< 30< 30< 26< 30< 36< 51< 32< 26< 29< 40< 24< 27< 26< 31< 35< 21< 16< 11< 41< 45< 26< 44< 46< 58< 48< 32< 67< 50< 39< 50< 60< 50< 66< 59< 62< 48< 36< 36< 36< 33< 30< 28< 28< 36< 29< 28< 30< 28< 36< 27< 14< 27< 42<5< 39< 35< 34< 33< 26< 24< 37< 45< 27< 26< 26< 42< 49< 23< 23< 25< 40< 35< 19< 36< 52< 51< 40< 44< 61< 22< 36< 65< 65< 50< 62< 69< 60< 26< 15< 31< 57< 32< 30< 27< 28< 35< 29< 24< 29< 28< 35< 26< 14< 29< 39< 12< 38< 13< 32< 32< 26< 24< 36< 44< 26< 26< 26< 38< 48< 22< 22< 25< 38< 35< 18< 39< 47< 51< 39< 43< 60< 51< 36< 28<64< 51< 60< 69< 59< 60< 35< 31< 56< 32< 30< 27< 27< 35< 29< 24< 29< 28< 35< 26< 14< 29< 39< 12< 38<34< 32< 32< 25< 13< 36< 44< 26< 26< 26< 38< 48< 22< 22< 25< 38< 36< 18< 39< 46< 51< 17< 42< 25< 50< 19< 64< 27< 51< 60< 38< 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 01/01/10 01/08/10 01/15/10 01/22/10 01/29/10 02/05/10 02/12/10 02119/10 02/26/10 03/05/10 03/12/10 03/19/10 03/26/10 04/02/10 04/09/10 04/16/10 04/23/10 04/30/10 05/07/10 05/14/10 05/21/10 05/28/10 06/04/10 06/11/10 06/18/10 06/25/10 07/03/10 07/09/10 07/16/10 07/23/10 07/30/10 08/06/10 08/13/10 08/20/10 08/27/10 09/03/10 09/10/10 09/17/10 09/24/10 10/01/10 10/08/10 10/15/10 10/22/10 10/29/10 11/05/10 11/12/10 11/19/10 11/26/10 12/03/10 12/10/10 12/17/10 12/24/10-01/08/10-01/15/10-01/22/10-01/29/10-02/05/10-02/12/10-02/19/10-02/26/10-03/05/10-03/12/10-03/19/10-03/26/10-04/02/10-04/09/10-04/16/10-04/23/10-04/30/10-05/07/10-05/14/10-05/21/10-05/28/10-06/04/10-06/11/10-06/18/10-06/25/10-07/03/10-07/09/10-07/16/10-07/23/10-07/30/10-08/06/10-08/13/10-08/20/10-08/27/10-09/03/10-09/10/10-09/17/10-09/24/10-10/01/10-10/08/10-10/15/10-10/22/10-10/29/10-11/05/10-11/12/10-11/19/10-11/26/10-12/03/10-12/10/10-12/17/10-12/24/10-12/31/10 D-08< 20< 45< 15< 15< 35< 23< 29< 25< 30< 30< 17< 32< 36< 28< 28< 10< 36< 50< 30< 34< 30< 40< 51< 34< 26< 31< 22< 22< 38< 27< 18< 44< 16< 22< 21< 32< 19< 33< 41< 68< 58< 48< 32< 67< 52< 39< 50< 60< 50< 63< 63< 68 D-10< 48< 45< 35< 36< 35< 24< 29< 25< 30< 30< 28< 32< 15< 28< 28< 10< 35< 50< 30< 34< 30< 40< 51< 34< 26< 31< 22< 22< 38< 27< 42< 43< 16< 22< 21< 32< 45< 32< 18< 68< 56< 48< 32< 67< 52< 39< 50< 60< 49< 63< 63< 68 D-14< 48< 36< 36< 36< 35< 24< 30< 26< 31< 30< 28< 32< 37< 27< 29< 10< 15< 51< 13< 34< 35< 40< 33< 34< 24< 31< 22< 22< 38< 27< 42< 44< 16< 22< 21< 32< 45< 33< 41< 70< 58< 41< 25< 64< 52< 37< 65< 65< 52< 64< 69< 70 D-55< 60< 36< 32< 57< 33< 30< 28< 28< 36< 30< 24< 30< 28< 36< 27< 14< 27< 42< 13< 39< 35< 33< 27< 26< 24< 37< 45< 26< 26< 26< 39< 49< 23< 23< 25< 40< 35< 19< 36< 52< 51< 40< 44< 61< 52< 36< 65< 65< 28< 62< 69< 59 D-12< 47< 45< 36< 36< 35< 24< 29< 25< 30< 30< 28< 32< 36< 28< 12< 10< 35< 51< 30< 35< 30< 40< 51< 34< 26< 31< 22< 22< 38< 27< 42< 44< 16< 22< 21< 32< 45< 33< 42< 67< 28< 48< 32< 67< 52< 39< 50< 60< 50< 64< 63< 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 PERIOD 01/08/10 02/04/10 03/04/10 04/01/10 05/06/10 05/20/10 06/04/10 06/17/10 07/03/10 07/15/10 07/29/10 08/11/10 08/26/10 09/09/10 09/23/10 10/07/10 10/21/10 11/04/10 12/02/10 CONTROLFARM D-25< 0.2< 0.6< 0.7< 0.5< 0.9< 0.6< 0.5< 0.9< 0.7< 0.6< 0.6< 0.9< 0.9< 0.7< 0.6< 0.7< 1.0< 0.8< 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 PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-1 37 Ba-140 La-140 D-25 01/08/10 02/04/10 03/04/10 04/01/10 05/06/10 05/20/10 06/04/10 06/17/10 07/03/10 07/15/10 07/29/10 08/11/10 08/26/10 09/09/10 09/23/10 10/07/10 10/21/10 11/04/10 12/02/10<8<5<4<7<8<2<6<5<5<8<5<6<5<6<5<6<5<6<7<8<6<4<7<8<2<8<5<5<7<6<6<5<7<5<6<4<7<7< 16< 11< 10< 16< 13<6< 20< 11< 13< 16< 12< 15< 12< 17< 13< 12< 10< 17< 17<9<6<5<6<9<2<9<4<5<6<5<6<5<7<7<7<6<9<9< 18< 14<9< 13< 15<4< 17< 10< 11< 15< 11< 14< 13< 13< 12< 14< 11< 16< 16< 11<6<5<8<8<2<8<6<6<7<6<6<6<7<5<7<4<7<8< 13< 11<8< 12< 16<4< 11< 11<9< 12< 10<9<9< 12< 10< 10<8< 12< 12<7<5<4<7<7<2<6<5<5<7<5<6<4<6<5<5<4<5<6<7<5<5<7<9<2<8<6<5<8<5<6<5<6<6<6<5<6<6< 30< 23<21< 36< 47< 32< 40< 38< 25< 31< 48< 39< 46< 53< 24< 30< 23< 39<44< 12<7<6<9<15<8< 14< 10<7<8< 14<7< 13< 14<8< 10<7< 14< 13 I)00 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 PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 D-CONTROL Cabbage Sweet potatoes 09/11/10 09/11/10< 11 < 11< 11 < 15< 32 < 14 < 25< 39 < 18 < 32< 11< 14< 20 <51 < 10 < 10 <98< 26 < 55 < 11 < 13 < 111< 23< 28 MEAN I-D-QUAD 1 Cabbage Potatoes D-QUAD 2 Cabbage Beets D-QUAD 3 Broccoli Potatoes D-QUAD 4 Cabbage Potatoes 09/05/10 09/11/10< 10 < 11 <23 < 12 <23 < 13 <20 <43 <9 < 11 <87< 11 < 13 <29 < 17 <31 < 15 < 19 <58 < 11 < 14 <97 MEAN< 23< 26 09/05/10 09/11/10< 10 < 11 <29 < 11 < 27 < 13 < 18 <46 <9< 11 < 10 <31 < 14 <26 < 11 <20 <45 <9< 11 < 79< 10 < 84 MEAN< 29< 20< 25< 24 09/05/10 09/11/10 MEAN< 12 < 12 <30 < 14 <28 < 13 <22 <49 < 10 < 11< 11 < 11 < 30 < 15 <27 < 13 < 20 <47 < 11 < 11< 11 < 14 <30 < 14 <26 < 14 <27 <52 < 10 < 13<8 < 10 <22 < 11 <21 < 10 < 16 <37 <8 <9< 99< 97 09/05/10 09/11/10< 115 < 31< 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 CODE MEAN+/-2S.D.JAN -MAR APR -JUN JUL -SEP OCT- DEC u-u1-1 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-12-1 D-12-2 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 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-110-4 D-111-1 D-111-2 D-113-1 D-113-2 D-114-1 D-114-2 D-115-1 26.0 25.3 25.8 26.8 22.0 22.3 25.8 24.5 24.8 22.8 25.0 24.3 24.3 25.0 23.0 21.5 22.5 23.5 26.0 26.0 22.0 20.0 25.8 24.3 21.8 24.0 26.5 23.5 26.8 27.0 23.8 23.5 26.0 24.8 24.8 24.8 23.0 21.5 20.0 21.3 25.8 22.5 25.3 25.3 27.3 29.3 27.5 25.8 22.5 23.8 22.5 23.0 25.3+/- 3.3+/- 4.4+/- 3.4+/- 3.8+/- 1.6+/- 1.0+/- 1.0+/- 1.2+/- 4.1+/- 4.4+/- 5.2+/- 1.0+/- 2.5+/- 2.8+/- 3.3+/- 3.8+/- 3.5+/- 3.8+/- 0.0+/- 2.8+/- 2.3+/- 2.8+/- 1.9+/- 3.0+/- 3.4+/- 12.1+/- 4.2+/- 2.6+/- 3.0+/- 3.7+/- 2.5+/- 1.2+/- 1.6+/- 2.5+/- 1.0+/- 1.9+/- 2.3+/- 2.6+/- 2.3+/- 3.0+/- 3.4+/- 4.8+/- 3.0+/- 2.5+/- 2.5+/- 1.9+/- 3.8+/- 2.5+/- 3.8+/- 1.0+/- 2.6+/- 1.6+/- 3.0 28 26 28 28 22 23 26 25 27 24 26 24 26 25 23 23 22 22 26 26 23 20 26 25 22 22 26 23 26 26 24 24 27 26 25 24 22 22 21 22 26 25 24 25 26 28 26 26 25 24 21 23 26 26 26 24 27 23 22 26 24 22 22 22 25 24 24 21 23 21 24 26 28 21 19 25 22 20 33 27 25 26 28 24 24 26 23 25 25 24 20 19 20 25 20 26 27 27 29 28 27 21 24 23 23 26 24 22 25 24 21 22 25 24 25 20 24 24 23 24 23 19 22 22 26 25 21 19 27 25 21 21 24 22 26 25 22 23 26 25 25 24 22 23 21 20 24 21 24 25 27 30 26 24 21 23 22 22 23 26 27 26 28 22 22 26 25 25 25 28 24 24 27 25 21 25 26 26 25 23 22 25 25 24 20 29 24 29 29 25 23 25 25 24 26 24 21 19 23 28 24 27 24 29 30 30 26 23 24 24 24 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 CODE MEAN+/- 2 S.D.JAN -MAR APR -JUN JUL-SEP OCT -DEC D-1 15-2 D-1 16-1 D-116-2 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 D-1 12A-1 D-1 12A-2 25.5 27.5 26.8 29.8 29.0 26.0 24.5 23.5 23.3 21.5 22.0 25.3 23.8 23.8 25.3 22.5 24.5 21.3 21.8 20.0 21.5 23.3 25.8 25.8 24.8 22.5 22.5 21.5 20.8 28.3 28.0 28.0 28.0 25.0 26.5 23.5 23.0+/- 2.0 t 3.5+/- 4.4+/- 3.4+/- 2.3+/- 2.8+/- 2.6+/- 2.6+/- 5.0+/- 6.0+/- 4.9+/- 3.8+/- 5.3+/- 1.9+/- 4.4+/- 1.2+/- 2.0+/- 1.0+/- 2.5+/- 1.6+/- 2.6+/- 1.9+/- 3.4+/- 1.9+/- 1.0+/- 3.8+/- 2.6+/- 2.6+/- 1.0+/- 1.2+/- 2.0+/- 4.3+/- 3.7+/- 5.2+/- 2.6+/- 2.6+/- 4.9 26 27 26 29 28 28 25 23 24 20 24 24 26 24 26 22 24 22 22 21 23 24 24 27 25 23 24 22 21 28 27 28 27 24 27 25 23 24 26 25 28 28 25 24 22 20 20 19 24 22 23 26 23 24 21 20 20 21 23 25 25 24 21 22 20 20 (1)(1)26 26 22 25 23 23 26 30 30 32 30 26 26 25 23 26 21 28 26 25 27 23 26 21 22 20 22 22 28 25 25 25 21 21 21 29 29 31 30 28 28 24 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 PERIOD INNER RING+/- 2 S.D.OUTER RING OTHER CONTROL JAN-MAR APR-JUN JUL-SEP OCT-DEC 24.7 +/- 3.6 24.5 +/- 5.4 23.8 +/- 4.1 25.7 +/- 5.6 24.6 +/- 4.8 24.2 +/- 5.9 23.0 +/- 5.0 25.4 +/- 6.7 24.7 +/- 4.5 24.0 +/- 6.0 23.2 +/- 4.1 24.8 +/- 3.9 23.0 +/- 0.0 22.0 +/- 2.8 21.0 +/- 5.7 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 ANALYZED MINIMUM MAXIMUM PERIOD MEAN+/-2 S.D.INNER RING OUTER RING OTHER CONTROL 128 19 30 126 19 32 96 19 33 8 19 25 24.6 +/- 4.9 24.3 +/- 5.8 24.2 +/- 4.8 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 10.0I 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-J a.12.0 10.0 8.0 6.0 4.0 2.0{ I 0.0 4-01-27-05 09-04-05 04-12-06 11-18-06 06-26-07 D-52 (C) DesPlaines River-I ,,.,.16.0 14.0 12.0 10.0 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 CL (.)=0.12.0 10.0 8.0 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 C.32 28 24 20 16 12 8 4 V, jvý VýV":,Ajl Ivi 0 4 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 15 10 5 C.,.0.K 0 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( 1C1) 1 12442 12i-CI R-D-62 (C) Des Plalnes River 12-30-04 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 600 500 400 300 200 100~1 C.)0.04 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.\^VeýI-,o A00 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--100.-/\.-,.//~\/
7 -....-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 ,-I a..600 400 200 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 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 I No' srwte;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 3oQ c')S 30.0 0.9? 20.0 uJ 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 C.)9 W 50.0 40.0 30.0 20.0 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-ýall"-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 07-05 03-20-06 05-31-07 08-10-08 10-21-09 01-01-11 D-04 Collins Road E C.)9.wp C4 60.0 50.0 40.0 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-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 C-39 FIGURE C-10 (cont.)AIR PARTICULATES
-GROSS BETA -STATIONS D-07 and D-12 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 -2010 D-07 Clay Products 0.CL C?o, 0J 60.0 50.0 40.0 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 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., c 20.0 ILl 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 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 IN THE VICINITY OF DNPS, 2006-2010 D-55 Ridge Road 50.0 40.0 30.0 0.9 20.0 uJ 10.0 0.0 06-06 01-05-07 01-04-08 01-02-09 01-01-10 12-31-10 D-56 Wildfeather 0.cq C?Lu 50.0 40.0 30.0 20.0 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 E6979-396 E6981-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 89.3 92.8 pCi/L 13.8 12.7 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 65.2 241 388 157 150 143 202 146 247 177 211 304 142 131 119 162 110 217 145 74.0 261 361 178 158 143 207 137 254 183 185 255 125 111 101 146 97 179 129 AP Ce-141 Cr-51 Cs-i 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 June 2010 E6980-396 E7132-396 E7133-396 E7135-396 pCi 80.2 85.6 0.96 1.09 0.88 0.92 1.07 0.88 0.95 1.00 0.98 1.07 0.97 0.97 1.14 1.19 1.14 1.18 1.18 1.11 1.14 1.21 1.12 0.94 0.88 0.95 0.86 0.97 0.96 0.90 0.96 0.91 0.98 1.02 0.96 0.96 0.97 1.04 0.96 1.06 1.04 1.07 1.06 0.98 1.04 0.96 A A A A A A A A A A A A A A A A A A A A W A Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 82.0 93.4 pCi/L 15.8 16.7 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 83.5 107 325 114 144 92.3 165 121 197 190 88.4 292 101 132 87.3 150 105 168 170 76.4 96.9 110 339 126 150 101 169 119 206 197 91.6 282 105 125 84.0 140 98.6 171 163 79.9 AP Ce-141 Cr-51 Cs-134.Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 E7134-396 pCi 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 E7230-396 E7232-396 E7231-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 85.0 92.8 pCi/L 12.6 14.7 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 80.2 130 235 83.2 95.1 77.3 121 96.4 216 172 122 228 79.9 93.8 71.5 113 73.8 186 163 94.1 130 234 93.0 94.5 73.7 119 91.1 204 171 119 214 85.3 86.7 67.6 110 83.6 187 157 AP Ce-141 Cr-51 Cs- 134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 0.92 0.86 0.85 1.00 1.00 0.89 1.01 1.05 1.02 1.06 1.06 1.01 1.03 1.07 0.94 1.08 1.06 1.03 0.88 0.99 1.04 1.04 0.95 1.00 0.91 December 2010 E7375-396 Milk E7376-396 Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 62.3 59.9 pCi/L 92.7 98.0 pCi/L 13.5 13.5 pCi/L 87.9 96.9 A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A W A A pCi/L not provided by Analytics for this study pCi/L 389 456 0.85 pCi/L 137 157 0.87 pCi/L 172 186 0.92 pCi/L 84.3 90.2 0.93 pCi/L 120 120 1.00 pCi/L 134 131 1.02 pCi/L 162 174 0.93 pCi/L 284 301 0.94 pCi not provided by Analytics for this study pci 387 365 1.06 pci 135 126 1.07 pCi 157 149 1.05 pCi 73.6 72.3 1.02 pCi 88.7 96 0.92 pCi 127 105 1.21 pCi 151 139 1.09 pCi 249 241 1.03 E7378-396 AP Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 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)(b)(c)(d)Teledyne Brown Engineering reported result.The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
Ratio of Teledyne Brown Engineering to Analytics results.Analytics evaluation based on TBE internal QC limits: A= Acceptable.
Reported result falls within ratio limits of 0.80-1.20.
W-Acceptable with warning. Reported result falls within 0. 70-0.80 or 1.20-1.30.
N = Not Acceptable.
Reported result falls outside the ratio limits of < 0. 70 and > 1.30.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 Sr-90 Ba-1 33 Cs-1 34 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 64.4 37.8 66.4 66.43 137.33 83.33 177 26.37 28.77 26.27 12967 77.8 39.3 70.3 39.9 117 53.5 11.0 35.1 35.5 27.9 13233 60.4 41.3 65.9 71.6 146 84.5 186 32.9 37.5 26.4 12400 68.5 43.0 68.9 43.2 123 53.4 102 42.3 36.6 27.5 12900 48.6 -68.2 30.4 -47.4 54.9 -72.5 58.4 -78.8 131 -163 76.0 -95.3 167- 219 16.9 -42.6 24.7 -45.0 21.9-31.1 10800 -13600 55.8 -76.7 31.7 -49.3 57.5 -75.8 34.5 -47.5 111-138 48.1 -61.3 91.8-122 21.9-53.7 24.0 -44.2 22.9 -32.3 11200 -14200 A A A A A A A A A A A N (1)A A A A A N (2)A A A A November2010 RAD-83 (1) Sr-89 TBE to known ratio of 1.14 fell within acceptable range 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 Engineering reported result.(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) ERA evaluation:
A=acceptable.
Reported result falls within the Warning Limits. NA=not acceptable.
Reported result falls outside of the Control Limits. CE=check for 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 1 0-GrW22 Water Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Water Gr-A Gr-B 1 0-MaS22 Soil Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 10-RdF22 1 0-GrF22 1 0-RdV22 September2010 10-MaW23 10-GrW23 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Water Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Water Gr-A Gr-B Bq/L -0.0942 Bq/L 58.5 Bq/L 27.2 Bq/L 0.0226 Bq/L 104 Bq/L 26.6 Bq/L 0.1029 Bq/L 42.0 Bq/L 0.5173 Bq/L 3.98 Bq/kg 665 Bq/kg 800 Bq/kg 508 Bq/kg 648 Bq/kg 893 Bq/kg 597 Bq/kg 221 Bq/kg -4.97 Bq/sample 1.81 Bq/sample 1.70 Bq/sample 0.0056 Bq/sample 2.65 Bq/sample 3.70 Bq/sample 0.0523 Bq/sample
-0.0627 Bq/sample 0.1533 Bq/sample 1.240 Bq/sample 4.48 Bq/sample 3.43 Bq/sample
-0.0117 Bq/sample 3.55 Bq/sample 0.007 Bq/sample
-0.0002 Bq/sample 8.12 Bq/L 27.1 Bq/L 41.8 Bq/L 33.2 Bq/L 26.5 Bq/L 500 Bq/L 0.024 Bq/L 8.10 Bq/L 30.8 Bq/L 2.36 Bq/L 6.37 733 779 522 622 849 559 288 2.13 1.49-2.77 1.53 1.07- 1.99 (1)2.473 1.731 -3.215 3.02 2.11 -3.93 (1)(1)513-953 545-1013 365-679 435-809 594-1104 391-727 202-374 (1)(1)60.6 42.4 -78.8 28.3 19.8 -36.8 (1)90.8 63.6 -118.0 26.9 18.8 -35.0 (1)40.7 28.5 -52.9 0.676 0.00 -1.352 3.09 1.55 -4.64 0.0427 1.29 0.00-0.854 0.65-1.94 A A A A A A A A A A A A A A A A W A A A A A W A A A A A A A A A A A A A A A A A A A A A 4.39 3.07 -5.71 3.06 2.14 -3.98 (1)3.27 2.29 -4.25 (1)(1)7.10 4.97 -9.23 31.4 22.0-40.8 44.2 30.9 -57.5 36.0 25.2 -46.8 28.3 19.8 -36.8 453.4 317.4 -589.4 (1)8.3 5.8 -10.8 31.0 21.7-40.3 1.92 0.58 -3.26 4.39 2.20 -6.59 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 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 837 680 2.78 350 853 721 2.24 287 940 670 343 820 699 265 658-1222 469-871 (1)240-446 574-1066 489-909 (1)186-345 10-RdF23 10-GrF23 10-RdV23 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 2.31-0.025 3.64 2.81 3.19 1.01 0.0310 Bq/sample 0.004 Bq/sample 0.473 2.98 2.09 -3.87 (1)4.08 2.86 -5.380 2.92 2.04 -3.80 3.18 2.23-4.13 1.01 0.71 -1.31 (1)(1)0.50 0.25 -0.75 4.79 3.35 -6.23 5.88 4.12- 7.64 8.27 5.79 -10.75 (1)6.287 4.401 -8.173 2.63 1.84 -3.42 5.3900 3.77 -7.01 A A A A A A A A W A A A A A A A A A A W A A A A Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 4.90 6.78 10.2 0.00 7.36 2.53 6.40 (1) False positive test.(a) Teledyne Brown Engineering reported result.(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) DOEIMAPEP evaluation:
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
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1 II. Introduction
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2 A. Objectives of the RGPP ................................................................................
3 B. Im plem entation of the O bjectives
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4 C. Program Description
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4 D. Characteristics of Tritium (H-3) .......................................................................
4 II. Program Description
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5 A. Sam ple Analysis .............................................................................................
5 B. Data Interpretation
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6 C. Background Analysis ......................................................................................
7 1. Background Concentrations of Tritium .................................................
7 IV. Results and Discussion
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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
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11 H. Actions Taken ...............................................................................................
11-i -
Appendices Appendix A Tables Table A-1 Location Designation Figures Radiological Groundwater Protection Program -Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2010 Security-Related Information:
Maps of the Dresden Nuclear Power Station have been withheld from public disclosure under 1 0CFR2.390 and N.J.S.A. 47:1A-1.1 Appendix B Tables Table B-1.1 Table B-I.2 Table B-11.1 Table B-11.2 Data Tables Concentrations of Tritium and Strontium in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of Tritium and Strontium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2010.-ii -
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.
If the 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.2. Concentrations of tritium and strontium 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 DSP-106 DSP-107 DSP-108 DSP-1 17 DSP-121 DSP-122 DSP-123 DSP-124 DSP-125 DSP-126 DSP-147 DSP-148 DSP-149R DSP-150 DSP-151 DSP-152 DSP-153 DSP-154 DSP-156 DSP-157-1 DSP-157-S DSP-158-1 DSP-158-S DSP-159-1 DSP-159-S MW-DN-101-1 MW-DN-101-S MW-DN-102-1 MW-DN-102-S MW-DN-103-1 MW-DN-103-S MW-DN-104-S MW-DN-105-S MW-DN-106-S MW-DN-107-S MW-DN-108-1 MW-DN-109-1 MW-DN-109-S MW-DN-110-1 MW-DN-110-S MW-DN-111-S MW-DN-1 12-1 MW-DN-1 12-S MW-DN-1 13-1 MW-DN-1 13-S MW-DN-1 14-1 MW-DN-1 14-S MW-DN-1 15-1 MW-DN-1 15-S MW-DN-1 16-1 MW-DN-1 16-S MW-DN-1 17-1 MW-DN-1 18-S MW-DN-1 19-1 MW-DN-1 19-S MW-DN-120-1 MW-DN-120-S MW-DN-121-S MW-DN-122-1 MW-DN-122-S MW-DN-123-1 Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well 30 feet east of the east wall of the EM Shop 65 feet east of east wall of EM Shop 9 feet east of the east Unit 1 Fuel Pool wall 40 ft east of the Unit 1 Sphere Northeast of Unit 1 Sphere; 825 feet west of Ross Bridge 72 feet north of 2/3 Intake Canal fence 50 feet north of the Radwaste Tank Farm Northeast corner of the Unit 1 Off-gas Building 9 feet south of Floor Drain Collector Tank Northeast comer of the Unit 2/3A CST 21 feet northwest of the northwest bend in road behind Training Building 325 feet west of Telemetry Bridge 130 feet southeast of the Flow Regulating Station building 35 feet south by southwest of the 138 KV yard fence 85 feet east of the northeast comer of the Unit 1 Spent Fuel Pool pad 65 feet north of the northeast comer of the Storeroom 210 feet south by southeast of the southeast comer of Maintenance Garage 150 feet east of the southeast comer of liquid hydrogen tank farm fence 33 feet west of the track; 165 feet east of the Security Checkpoint 70 feet east by northeast of the northwest comer of 138 KV yard fence 25 feet south of the south edge of the Employee Parking lot 25 feet south of the south edge of the Employee Parking lot 53 feet west of the Kankakee River; 33 feet west of the cinder track 50 feet west of the Kankakee River; 33 feet west of the cinder track 250 feet west of the Thorsen house; 450 ft south of the plant access gate 251 feet west of the Thorsen house; 450 ft south of the plant access gate 60 feet north of the Unit 1 Diesel Fuel Storage 60 feet north of the Unit 1 Diesel Fuel Storage 12 feet south of the southeast comer of the MUDS Building 13 feet south of the southeast corner of the MUDS Building 280 feet west of the northwest comer of N-GET Building 281 feet west of the northwest comer of N-GET Building 50 feet north of Radwaste Tank Farm 65 feet north of the northeast comer of the Storeroom 75 feet north of the 2/3 Intake Canal fence; east of the Unit 1 Intake Canal 15 feet west by southwest of the Unit 1 CST 7 feet southwest of the southwest comer of the Unit 1 Cribhouse 8 feet north of Chemistry Building 8 feet north of Chemistry Building 25 feet west of the Waste Water Treatment (WWT) Building 25 feet west of the Waste Water Treatment (WWT) Building 9 feet east of the Floor Drain Collector Tank 100 feet south of the Chemistry Building 100 feet south of the Chemistry Building 90 feet west of the southwest comer of the Administration Building 91 feet west of the southwest comer of the Administration Building 50 feet east of the Unit 1 Clean Demineralized Water Tank 8 feet southwest of the Radiation protection Dept west access doors 11 feet south of Instrument Maintenance Shop 12 feet south of Instrument Maintenance Shop 75 feet south of the Calgon Building roll-up door 75 feet south of the Calgon Building roll-up door 35 feet east by northeast of the Unit 1 Stack Southeast corner of the Unit 1 Fuel Pool 20 feet east by northeast of the Unit 1 Sewage Ejector Building 21 feet east by northeast of the Unit 1 Sewage Ejector Building 45 feet north by northeast of the Ross Bridge railing 46 feet north by northeast of the Ross Bridge railing 7 feet west of the dirt road; 42 feet east of the 345KV yard fence 150 feet north of Collins Road; northeast of the G.E. Fuel Storage Facility 150 feet north of Collins Road; northeast of the G.E. Fuel Storage Facility 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 MW-DN-124-1 MW-DN-124-S SW-DN-101 SW-DN-102 SW-DN-103 SW-DN-104 SW-DN-105 SW-ON-106 Monitoring Well Monitoring Well Monitoring Well Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water 400 feet west of the Thorsen house; west of the Cold Canal 10 feet south of the liquid nitrogen inerting tanks 10 feet south of the liquid nitrogen inerting tanks Unit 2/3 Intake (DSP50) at the Ross Bridge Unit 2/3 Discharge (DSP20) at the Telemetry Bridge Unit 2/3 Return Canal at the Discharge to the Intake Canal Cold Canal (DSP34A) at the Cooling Tower walkway bridge Hot Canal (DSP34B) at the Cooling Tower walkway bridge 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 SITE DN-DSP-105 DN-DSP-105 DN-DSP-106 DN-DSP-106 DN-DSP-107 DN-DSP-107 DN-DSP-108 DN-DSP-108 DN-DSP-1 17 DN-DSP-117 DN-DSP-121 DN-DSP-121 DN-DSP-122 DN-DSP-122 DN-DSP-123 DN-DSP-123 DN-DSP-124 DN-DSP-124 DN-DSP-125 DN-DSP-125 DN-DSP-126 DN-DSP-126 DN-DSP-147 DN-DSP-147 DN-DSP-148 DN-DSP-148 DN-DSP-149R DN-DSP-149R DN-DSP-150 DN-DSP-150 DN-DSP-151 DN-DSP-151 DN-DSP-152 DN-DSP-152 DN-DSP-153 DN-DSP-153 DN-DSP-154 DN-DSP-154 DN-DSP-156 DN-DSP-1 56 DN-DSP-1571 DN-DSP-1571 DN-DSP-157S DN-DSP-157S DN-DSP-1581 DN-DSP-1581 DN-DSP-158S DN-DSP-158S DN-DSP-1591 DN-DSP-1591 DN-DSP-159S COLLECTION DATE 04/30/10 09/30/10 04/30/10 09/30/10 04/30/10 09/30/10 04/29/10 09/30/10 05/03/10 10/04/10 05/03/10 10/04/10 04/28/10 09/29/10 04/29/10 09/30/10 04/27/10 10/01/10 04/30/10 10/01/10 05/04/10 10/05/10 05/05/10 10/06/10 05/05/10 10/04/10 05/05/10 10/04/10 04/29/10 09/30/10 04/29/10 09/30/10 05/03/10 10/05/10 05/04/10 10/05/10 05/04/10 10/05/10 05/05/10 10/04/10 05/04/10 10/05/10 05/04/10 10/05/10 05/03/10 10/05/10 05/03/10 10/05/10 05/05/10 10/06/10 05/05/10 H-3 SR-90< 177< 188 3050 +/- 360 3260 +/- 392 5590 +/- 612 4630 +/- 526 1200 +/- 184 962 +/- 172< 171< 174< 172< 176 3780 +/- 433 2510 +/- 317 9610 +/- 1010 8280 +/- 889 7820 +/- 832 2200 +/- 289< 176 361 +/- 131< 173< 174< 175< 173 181 +/- 117 316 +/- 125 344 +/- 123 632 +/- 131< 176< 189< 176< 189< 173< 171< 157< 170< 156< 173 359 +/- 115 265 +/- 117< 177< 169< 155< 167< 179< 169< 156< 169< 177 311 +/- 119< 178< 0.8< 0.7< 0.6< 0.8< 0.7< 0.9< 0.7< 0.7< 0.9< 0.9< 1.0< 0.8< 0.8< 0.7< 0.8< 0.6< 0.8< 0.6< 0.8< 0.7< 0.7< 0.8< 0.8< 0.8< 0.7 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 SITE DN-DSP-159S MW-DN-1011 MW-DN-1011 MW-DN-101S MW-DN-101S MW-DN-1021 MW-DN-1021 MW-DN-102S MW-DN-102S MW-DN-1031 MW-DN-1031 MW-DN-103S MW-DN-103S MW-DN-104S MW-DN-104S MW-DN-105S MW-DN-105S MW-DN-106S MW-DN-106S MW-DN-1081 MW-DN-1081 MW-DN-1091 MW-DN-1091 MW-DN-109S MW-DN-109S MW-DN-1101 MW-DN-1101 MW-DN-110S MW-DN-110S MW-DN-111S MW-DN-111S MW-DN-1 121 MW-DN-1 121 MW-DN-1 12S MW-DN-1 12S MW-DN-1 131 MW-DN-1 131 MW-DN-1 13S MW-DN-1i13S MW-DN-1 141 MW-DN-1 141 MW-DN-1 14S MW-DN-1 14S MW-DN-1 151 MW-DN-1 151 MW-DN-1 15S MW-DN-1i15S MW-DN-1 161 MW-DN-1 161 MW-DN-1 16S MW-DN-1 16S COLLECTION DATE 10/06/10 04/29/10 09/29/10 04/29/10 09/29/10 04/27/10 09/28/10 04/27/10 09/28/10 05/04/10 10/06/10 05/04/10 10/06/10 04/28/10 09/29/10 04/29/10 09/30/10 05/03/10 10/04/10 04/28/10 09/29/10 04/28/10 09/28/10 04/28/10 09/28/10 04/28/10 09/29/10 04/28/10 09/29/10 04/27/10 10/01/10 04/27/10 09/28/10 04/27/10 09/28/10 04/27/10 09/28/10 04/27/10 09/28/10 04/30/10 10/01/10 04/30/10 10/01/10 04/30/10 09/30/10 04/30/10 09/30/10 04/28/10 09/29/10 04/28/10 09/29/10 H-3* 168 1140 +/- 169 741 +/- 156* 164* 162 214 +/- 110 230 +/- 131* 163* 189* 172* 180* 170* 173* 166 521 +/- 138* 166* 200* 175* 178* 162* 196* 162* 189* 167* 199 178 +/- 108* 196* 160* 163 922 +/- 150 892 +/- 146 1390 +/- 193 1290 +/- 184* 167* 161* 173* 164* 174 SR-90* 0.8* 0.7< 0.6* 0.7< 0.7* 0.8* 0.8* 0.7 3.8 +/- 0.4< 0.8< 0.6* 0.8* 0.9* 0.7* 0.8* 0.7< 0.7< 0.9* 0.7* 0.9< 0.8* 0.9* 0.6* 0.8* 0.7< 0.9* 163 5870 6140 1570 1340 185 356* 173 237 3650 1460 282 337+/- 640+/- 659+/- 219+/- 189+/- 116+/- 113+/- 110+/- 420+/- 195+/- 119+/- 114 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 SITE MW-DN-1 171 MW-DN-118S MW-DN-1 18S MW-DN-1 191 MW-DN-1 191 MW-DN-1 19S MW-DN-1 19S MW-DN-1201 MW-DN-1201 MW-DN-120S MW-DN-120S MW-DN-121S MW-DN-121S MW-DN-1221 MW-DN-1221 MW-DN-122S MW-DN-122S MW-DN-1231 MW-DN-1231 MW-DN-123S MW-DN-123S MW-DN-1241 MW-DN-1241 MW-DN-124S MW-DN-124S COLLECTION DATE 04/29/10 04/30/10 09/30/10 04/29/10 09/29/10 04/29/10 09/29/10 05/03/10 10/04/10 05/03/10 10/04110 05/05/10 10/06/10 05/05/10 10/06/10 05/05/10 10/06/10 05/05/10 10/06/10 05/05/10 10/06/10 04/30/10 10/01/10 04/30/10 10/01/10 H-3 SR-90* 177 929 3980 576 461* 161* 189* 171* 176* 175* 174* 173* 176* 171* 175* 172* 178* 173* 160* 171< 153 73200 77400 51200 819+/- 153+/- 438+/- 128+/- 134* 0.7* 0.9* 0.6* 0.8* 0.8* 1.0* 0.9* 0.8* 0.7* 0.8< 0.7* 0.9+/- 6400+/- 7750+/- 5140+/- 160 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 PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DN-DSP-105 09/30/10 DN-DSP-106 09/30/10 DN-DSP-107 09/30/10 DN-DSP-108 09/30/10 DN-DSP-1 17 10/04/10 DN-DSP-121 10/04/10 DN-DSP-122 09/29/10 DN-DSP-123 09/30/10 DN-DSP-124 10/01/10 DN-DSP-125 10/01/10 DN-DSP-126 10/05/10 DN-DSP-147 10/06/10 DN-DSP-148 10/04/10 DN-DSP-149R 10/04/10 DN-DSP-150 09/30/10 DN-DSP-151 09/30/10 DN-DSP-152 10/05/10 DN-DSP-153 10/05/10 DN-DSP-154 10/05/10 DN-DSP-156 10/04/10 DN-DSP-1571 10/05/10 DN-DSP-157S 10/05/10 DN-DSP-1581 10/05/10 DN-DSP-158S 10/05/10 DN-DSP-1591 10/06/10 DN-DSP-159S 10/06/10 MW-DN-1011 09/29/10 MW-DN-101S 09/29/10 MW-DN-1021 09/28/10 MW-DN-102S 09/28/10 MW-DN-1031 10/06/10 MW-DN-103S 10/06/10 MW-DN-104S 09/29/10 MW-DN-105S 09/30/10 MW-DN-106S 10/04/10< 41 < 39<44 <62< 43 < 86<38 <34< 36 < 36< 31 < 53< 44 < 109< 41 < 41<41 < 38<44 <42< 40 < 85< 43 < 103< 39 < 35< 37 < 73< 42 < 41< 42 < 69< 42 < 46< 44 < 37< 36 < 35< 32 < 36< 37 < 32< 33 < 29< 39 < 75< 41 < 42< 41 < 50< 42 < 38<32 <38< 40 < 35< 36 < 73< 37 < 79< 37 < 65< 41 < 93< 47 < 100< 47 < 38< 37 < 85<4 <4 <9<5 <4 <9<5 <5 <12<4 <4 <9<3 <4 <9<3 <4 <9<5 <5 <10<4 <4 <11<4 <5 <9<5 <5 <9<4 <5 <11<5 <5 <11<4 <4 <9<4 <4 <8<4 <4 <8<4 <3 <9<4 <5 <8<4 <4 <10<4 <4 <9<3 <4 <10<4 <4 <11<3 <3 <8<4 <5 <9<5 <5 <13<4 <5 <10<4 <4 <9<3 <3 <7<5 <5 <10<3 <4 <9<4 <4 <10<4 <4 <8<5 <6 <10<5 <4 <11<5 <5 <10<4 <4 <11<,5 <lO<3 <9<5 <9<4 <7<3 <7<3 <6<5 <12<4 <10<4 <8<5 <9<4 <8<5 <10<4 <9<4 <7<4 <9<4 <7<4 <9<4 <8<4 <7<4 <7<4 <8<4 <7<4 <8<5 <8<4 <9<4 <9<3 <6<4 <9<4 <8<4 <8<5 <8<5 <11<5 <10<4 <9<4 <8<,5 <8<5 <8<5 <9<4 <7<4 <7<4 <7<5 <10<5 <8<4 <8<5 <8<5 <8<5 <8<4 <8<4 <7<4 <8<5 <7<5 <7<4 <8<5 <6<4 <6<5 <8<4 <7<5 <8<5 <9<5 <9<5 <7<4 <6<5 <8<4 <7<5 <7<4 <8<5 <9<5 <10<6 <8<5 <8< 14 < 4 < 5 < 32 < 12< 14 < 4 < 4 < 32 < 10<15 <4 <3 <30 <9<14 <4 <4 <28 <7<12 <3 <3 <27 <7<12 <3 <3 <27 <9<14 <4 <5 <34 <9< 14 < 4 < 4 < 31 < 7<15 <4 <5 <30 <7< 14 < 4 < 5 < 29 < 12<15 <4 <4 <33 <11< 14 < 5 < 5 < 35 < 10<15 <4 <4 <34 <9<14 <4 <4 <29 <8<13 <4 <4 <30 <8<14 <4 <4 <29 <8<15 <4 <5 <33 <9<14 <4 <4 <31 <9< 14 < 4 < 4 < 30 < 10< 14 < 3 < 4 < 25 < 11<13 <3 <4 <27 <9<13 <4 <3 <26 <8<14 <4 <4 <34 <12< 14 < 5 < 6 < 36 < 13< 13 < 4 < 5 < 30 < 10<13 <4 <4 <30 <8<11 <3 <3 <24 <7<14 <4 <5 <34 <11< 13 < 3 < 4 < 27 < 10< 13 < 4 < 4 < 26 < 10<11 <4 <4 <27 <6< 14 < 4 < 5 < 31 < 13<13 <4 <5 <34 <12<14 <4 <4 <30 <9<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 f-A MW-DN-1081 09/29/10 MW-DN-1091 09/28/10 MW-DN-109S 09/28/10 MW-DN-1101 09/29/10 MW-DN-110S 09/29/10 MW-DN-111S 10/01/10 MW-DN-1 121 09/28/10 MW-DN-1 12S 09/28/10 MW-DN-1 131 09/28/10 MW-DN-1 13S 09/28/10 MW-DN-1141 10/01/10 MW-DN-1 14S 10/01/10 MW-DN-1 151 09/30/10 MW-DN-1 15S 09/30/10 MW-DN-1 161 09/29/10 MW-DN-1i16S 09/29/10 MW-DN-1 18S 09/30/10 MW-DN-1 191 09/29/10 MW-DN-1 19S 09/29/10 MW-DN-1201 10/04/10 MW-DN-120S 10/04/10 MW-DN-121S 10/06/10 MW-DN-1221 10/06/10 MW-DN-122S 10/06/10 MW-DN-1231 10/06/10 MW-DN-123S 10/06/10 MW-DN-1241 10/01/10 MW-DN-124S 10/01/10<43 <34< 45 < 45< 38 <92< 42 < 82< 45 < 49<41 <94< 38 < 42<44 <36< 50 < 38< 35 < 39< 40 < 28<44 <55< 42 < 87< 43 < 43< 37 < 77< 42 < 90< 45 < 88< 39 < 39< 39 < 36< 36 < 38< 41 < 38< 40 < 49< 34 < 33< 55 < 107< 38 < 64< 58 <54< 49 < 41< 38 < 38<4 <4 <9 <3 <8<5 <6 <12 <5 <9<4 <4 <10 <4 <10<4 <5 <9 <5 <8<4 <4 <9 <5 <6<4 <5 <8 <5 <8<4 <4 <9 <4 <8<5 <5 <9 <5 <8<4 <4 <8 <4 <9<4 <5 <11 <4 <10<5 <4 <9 <4 <9<4 <5 <8 <4 <10<5 <5 <10 <5 <10<5 <4 <9 <4 <9<3 <4 <9 <4 <8<5 <5 <10 <4 <9<4 <5 <11 <4 <9<4 <4 <8 <3 <6<4 <5 <9 <5 <7<4 <4 <10 <4 <8<4 <4 <10 <4 <9<4 <5 <9 <5 <10<4 <4 <10 <4 <8<5 <5 <10 <5 <9<5 <4 <11 <4 <8<6 <6 <16 <7 <13<4 <4 <11 <4 <7<4 <4 <8 <4 <7<5 <7<5 <9<5 <8<5 <8<4 <8<5 <8<5 <7<5 <7<5 <7<6 <9<5 <8<5 <8<4 <9<5 <8<4 <7<5 <7<6 <9<4 <7<5 <7<5 <8<5 <8<5 <9<5 <6<6 <10<5 <7<6 <12<5 <8<5 <8<14 <4 <4 <30 <8<15 <4 <5 <35 <10<14 <4 <5 <34 <9<15 <4 <5 <31 <10<13 <4 <4 <35 <9<11 <4 <5 <28 <6<14 <4 <4 <29 <7<15 <4 <4 <30 <10<14 <4 <4 <31 <11<15 <4 <5 <35 <10<11 <4 <5 <29 <8<12 <4 <5 <29 <9<15 <4 <5 <27 <10<13 <4 <4 <28 <7<14 <4 <4 <30 <9<13 <4 <4 <30 <9<15 <5 <5 <34 <11<13 <4 <4 <27 <8<15 <4 <4 <29 <9<15 <3 <4 <29 <9<14 <4 <5 <31 <11<14 <4 <4 <28 <11<12 <3 <4 <27 <8<15 <5 <5 <34 <12<14 <4 <3 <28 <8<14 <5 <6 <40 <13<13 <4 <4 <31 <6<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 SITE SW-DN-101 SW-DN-101 SW-DN-102 SW-DN-102 SW-DN-103 SW-DN-103 SW-DN-104 SW-DN-104 SW-DN-105 SW-DN-105 SW-DN-106 SW-DN-106 COLLECTION DATE 05/03/10 10/04/10 05/03/10 10/04/10 05/03/10 10/04/10 05/04/10 10/04/10 05/04/10 10/04/10 05/04/10 10/04/10 H-3 SR-90< 171 315 +/- 117* 173 340 +/- 121* 171 335 +/- 118* 175 372 +/- 126* 157 387 +/- 127* 159 544 +/- 128< 0.9< 0.7< 0.6< 0.8< 0.6< 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 SW-DN-101 SW-DN-102 SW-DN-103 SW-DN-104 SW-DN-105 SW-DN-106 COLLECTION Be-7 PERIOD 10/04/10 < 37 10/04/10 < 40 10/04/10 < 37 10/04/10 < 40 10/04/10 < 42 10/04/10 < 42 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< 35< 38< 41<40< 39< 42<4<4<4<4<4<5<5<4<4<4<4<3<8<8< 10< 11< 10<8<4<4<5<4<5<4<8<8< 10<9<8<7<4<4<4<5<4<5<7<7<8<8<8<8< 14< 14< 15< 15< 15< 13<3<4<4<4<4<4<5<4<4<5<4<5< 31< 31< 28< 33< 31< 31<9<8< 10< 11<6<9