Text

Annual Radiological Environmental Operating Report
	ML101380678
Person / Time
Site:	Dresden
Issue date:	05/14/2010
From:	Hanley T; Exelon Generation Co, Exelon Nuclear
To:	; Document Control Desk, NRC/FSME, Office of Nuclear Reactor Regulation
References
	SVPLTR # 10-0027
	Download: ML101380678 (128)
	v • d • e

Exeltons Exelon Generation Company, LLC www.exeloncorp.com Nuclear Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450-9765 May 14,,2010 SVPLTR # 10-0027 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 1, 2, and 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 2009 Annual Radiological Environmental Operating Report Enclosed is the Exelon Dresden Nuclear Power Station 2009 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 and meteorological monitoring programs for the 2009 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 2009. This information is being reported in accordance with a nuclear industry initiative.

Should you have any questions concerning this letter, please contact Mr. Dennis Leggett, Regulatory Assurance Manager, at (815) 416-2800.

Respectfully, Tim Hanley 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 2009 Prepared By Teledyne Brown Engineering Environmental Services Exeln..

Nuclear Dresden Nuclear Power Station Morris, IL 60450 May 2010

Table Of Contents I. Sum m ary and Conclusions..............................................................................................

J II. Introduction.............................................................................................................

3 A. O bjectives of the REM P.................................................................................

3 B. Im plem entation of the O bjectives..................................................................

3 Ill. Program Description................................................................................................

4 A. Sam ple Collection.........................................................................................

4 B. Sam ple Analysis............................................................................................

5 C. Data Interpretation.........................................................................................

6 D. Program Exceptions.......................................................................................

7 E. Program Changes.........................................................................................

8 IV. Results and Discussion............................................................................................

9 A. Aquatic Environm ent.......................................................................................

9

1. Surface W ater.....................................................................................

9

2. G round W ater.....................................................................................

9

3. Fish.....................................................................................................

10

4. Sedim ent............................................................................................

10

5. Dredging Spoils..................................................................................

11 B. Atm ospheric Environm ent...........................................................................

11

1. Airborne..............................................................................................

11

a. Air Particulates.........................................................................

11

b. Airborne Iodine......................................................................

12

2. Terrestrial............................................................................................

12

a. M ilk..........................................................................................

12

b. Food Products.........................................................................

13 C. Ambient Gamma Radiation.................................

13 D. Land Use Survey..........................................................................................

13 E. Errata Data...................................................................................................

14 F. Summary of Results - Inter-laboratory Comparison Program......................

14

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-I:

Appendix B Tables Table B-I:

Table B-2:

Radiological Environmental Monitoring Program Annual Summary for the Dresden Nuclear Power Station, 2009 Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2009 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2009 Figqures Figure B-I:

Figure B-2:

Appendix C Tables Table C-1.1:

Table C-1.2:

Table C-1.3:

Table C-11.1:

Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Locations, 2009 Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2009 Data Tables and Figures - Primary Laboratory Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

ii

Table C-II.2:

Table C-II1.1:

Table C-IV.1:

Table C-IV.2:

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:

Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of Gamma Emitters in Dredging Spoil Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

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, 2009.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Quarterly TLD Results for Dresden Nuclear Power Station, 2009.

Mean Quarterly TLD Results for the Inner Ring, Outer Ring, Other and Control Locations for Dresden Nuclear Power Station, 2009.

Summary of the Ambient Dosimetry Program for Dresden Nuclear Power Station, 2009.

Figures Figure C-1:

Figure C-2:

Figure C-3:

Figure C-4:

Surface Water - Gross Beta - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2009.

Surface Water - Gross Beta - Stations D-54 (C) and D-57 (C)

Collected in the Vicinity of DNPS, 2002 - 2009.

Surface Water - Gross Beta - Station D-21 Collected in the Vicinity of DNPS, 2007 - 2009.

Surface Water - Tritium - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2009.

iii

Figure C-5:

Figure C-6:

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:

Surface Water - Tritium - Station D-54 (C) and D-57 (C) Collected in the Vicinity of DNPS, 2002 - 2009.

Surface Water - Tritium - Station D-21 Collected in the Vicinity of DNPS, 2007 - 2009.

Ground Water - Tritium - Stations D-23 and D-35 Collected in the Vicinity of DNPS, 2000 - 2009.

Air Particulate - Gross Beta - Stations D-01 and D-02 Collected in the Vicinity of DNPS, 2000 - 2009.

Air Particulate - Gross Beta - Stations D-03 and D-04 Collected in the Vicinity of DNPS, 2000 - 2009.

Air Particulate - Gross Beta - Stations D-07 and D-12 (C) Collected in the Vicinity of DNPS, 2000 - 2009.

Air Particulate - Gross Beta - Stations D-45 and D-53 Collected in the Vicinity of DNPS, 2000 - 2009.

Air Particulate - Gross Beta - Stations D-08 and D-10 Collected in the Vicinity of DNPS, 2005 - 2009.

Air Particulate - Gross Beta - Stations D-13 and D-14 Collected in the Vicinity of DNPS, 2005 - 2009.

Air Particulate - Gross Beta - Stations D-55 and D-56 Collected in the Vicinity of DNPS, 2006 - 2009.

Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2009 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2009 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2009 Appendix E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv

1.

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 2009 through 31 December 2009. During that time period, 1,940 analyses were performed on 1,809 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), sediment and dredging spoils samples were analyzed for concentrations of gamma emitting nuclides.

No fission or activation products were detected in fish. Sediment and dredging spoils samples had Cesium-137 concentrations 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) Global Dosimetry, and Environmental Inc. Midwest Laboratory (EIML) on samples collected during the period 1 January 2009 through 31 December 2009.

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 40CFR1 90 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.

IlI.

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 2009. 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, sediment, and dredging spoils. 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. Samples were also collected from the spoils of dredging of the Illinois River downstream of Dresden Nuclear Power Station in 2009.

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. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The 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 ring 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-1 14, D-1 15 and D-1 16) at or near the site boundary.

An outer ring 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 Global Dosimetry 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 2009. 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-137, Ba-140, and La-140 were reported.

For fish, sediment, dredge spoil, 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-1 40 and La-1 40 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 2009 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-01 D-08 AP AP D-55 AP/I AP/I AP/I AP/I D-12 D-01 D-07 D-04 02/27/09 - 03/06/09 03/20/09 - 03/27/09 03/20/09 - 03/27/09 03/27/09 - 04/03/09 04/03/09 - 04/10/09 04/03/09 - 04/10/09 05/01/09 - 05/08/09 05/08/09 - 05/15/09 Low timer reading of 162.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ; cause is unknown.

Heavy accumulation on particulate filter; likely due to nearby field burning activities.

Heavy accumulation on particulate filter; likely due to nearby construction activities.

Low timer reading of 155.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ; cause is unknown.

Low timer reading of 162.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ; cause is unknown.

Low timer reading of 133.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; cause is unknown.

Estimated collection time of 165.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months due to failed timer. Timer was replaced.

Low timer reading of 158.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; likely due to storms in the area.

AP/I D-1 2 Table D-1 LISTING OF SAMPLE ANOMALIES (continued)

Sample Location Collection Reason Type Code Date AP/I D-02 12/18/09 - 12/24/09 Estimated collection time of 142.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to failed timer. Timer was replaced.

SW D-52 01/02/09 - 01/30/09 01/16/09 aliquot was not drawn; sample point frozen over.

SW D-57 12/26/08 - 01/30/09 Composite sampler damaged by ice on river. Grab samples drawn 01/09/09 - 01/23/09 and added to composite until sampler repaired.

TLD D-207-2 01/02/09 - 03/27/09 TLD on utility pole that fell during storm, placed TLD on new pole in same location.

Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date There were no missed samples for 2009.

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 2009.

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 <3.2 to 10.9 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-I.2, Appendix C). The indicator values ranged from <168 to 573 pCi/L. Control values ranged from <161 to 621 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-II. 1, Appendix C). D-35 values ranged from <172 to <181 pCi/L. D-23 values ranged from 250 to 725 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-7, Appendix C).

Gamma Spectrometry 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-I11.1, Appendix C).

Naturally occurring K-40 was found at all stations and ranged from 2,210 to 3,590 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.

Concentrations of the fission product Cs-137 was found in one sample at a concentration of 87 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.

5.

Dredging Spoils Dredging Spoil samples were collected when the river was dredged in 2009. The following analysis was performed:

Gamma Spectrometry Dredging Spoil samples were analyzed for gamma emitting nuclides (Table C-IV.2, Appendix C).

Cesium-137 was detected in four of the six samples analyzed and ranged from concentrations of 95 to 142 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 7 to 39 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m3. The results from the Near-Field locations ranged from 7 to 42 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m 3.

The results from the Far-Field locations ranged from 8 to 43 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m 3. The results from the Control location ranged from 8 to 42 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m 3. Comparison of the 2009 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 2009 indicate no notable differences among the four groups (Figures C-8 through C-14, Appendix C).

Gamma Spectrometry 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 48 of 52 samples and ranged from 43.4 to 114 E-3 pCi/m 3. K-40 was also detected in 1 sample at a concentration of 20.7 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-131 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 Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C).

Naturally occurring K-40 activity was found in all nineteen samples. The activities ranged from 1,100 to 1,370 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 occuring nuclides were detected, and all required LLDs were met.

C.

Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Global Dosimetry 110 Environmental (CaF2 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 35 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 04 August 2009 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 GSE 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 2009.

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, 17 out of 18 analytes met the specified acceptance criteria. One sample did not meet the specified acceptance criteria for the following reason:

1.

Teledyne Brown Engineering's Analytics June 2009 Zn-65 in AP result of 137 pCi/L was higher than the known value of 101 pCi/L, resulting in a found to known ratio of 1.36. NCR 09-23 was initiated to investigate this failure. The failure appears to be a result of a slightly high bias on Detector 7. A recount on Detector 17 resulted in a Zn-65 result of 101 pCi/L. The detector has been tagged out-of-service until a recalibration can be performed.

Detector 7 is not used for client samples.

For the secondary laboratory, Environmental, Inc., 11 out of 14 analytes met the specified acceptance criteria. Three samples did not meet the specified acceptance criteria for the following reasons:

1. Environmental Inc.'s ERA April 2009 Cs-137 in water result of 147.7 pCi/L exceeded the lower control limit of 151.0 pCi/L. All gamma emitters showed a low bias. A large plastic burr found on the base of the Marinelli kept the beaker from sitting directly on the detector. Recounting in a different beaker gave an acceptable result of 155.33 +/- 14.55 pCi/L.

2. Environmental Inc.'s ERA April 2009 H-3 in water result of 22819 pCi/L exceeded the upper control limit of 22300 pCi/L. A recount of the original vials averaged 23,009 pCi/L. Reanalysis results were acceptable at 19,170 pCi/L. No cause could be found for the failure.

3. Environmental Inc.'s MAPEP January 2009 Sr-90 in AP result of 0.93 exceeded the upper control limit of 0.83. Reanalysis results were acceptable at 0.54 +/- 0.12 Bq/filter. No cause could be found for the failure.

4. Environmental Inc.'s MAPEP July 2009 Sr-90 in soil result of 310.5 Bq/kg exceeded the lower control limit of 319 Bq/kg. Reanalysis results were acceptable at 363.3 Bq/kg. Incomplete separation of strontium from calcium could result in a higher recovery percentage and consequently lower reported activity.

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

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (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 36 4

7.8 (12/12)

(4.8/10.9) 6.9 (22/24)

(4.0/10.4) 560 (3/8)

(465/621) 7.8 (12/12)

(4.8/10.9) 560 (3/4)

(465/621)

D-21 INDICATOR IL RIVER AT EJ&E BRIDGE 1.4 MILES WNW OF SITE 0

H-3 12 36 2000 359 (2/4)

(181/537) 15

<LLD D-57 CONTROL 0

KANKAKEE RIVER AT WILL ROAD(CONTROL) 2.0 MILES SE OF SITE GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD

<LLD 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, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (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 LA-140 30

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD 2000 409 (12/16)

(250/725)

<LLD

<LLD 0

0 0

0 GROUND WATER (PCI/LITER)

H-3 16 16 NA 409 (12/12)

(250/725)

D-23 INDICATOR THORSEN WELL 0.7 MILES S OF SITE 0

GAMMA MN-54 15

<LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (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 NA NA NA NA NA NA NA NA 0

0 0

0 1-131 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, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (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 LA-140 GAMMA MN-54 FISH (PCI/KG WET) 8 18

<LLD 60

<LLD 15

<LLD 130

<LLD 260

<LLD 130

<LLD 260

<LLD NA NA NA 0

0 CO-58 FE-59 CO-60 ZN-65

<LLD

<LLD 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-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS FISH (PCI/KG WET)

SEDIMENT (PCI/KG DRY)

NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 GAMMA MN-54 NA

<LLD NA

<LLD 130

<LLD 150

<LLD NA

<LLD

<LLD 0

0 0

2 NA NA 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, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (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 NB-95 ZR-95 CS-134 CS-137 BA-140 NA

<LLD NA

<LLD 150

<LLD 180 87 (1/2)

NA

<LLD NA NA NA NA NA NA NA NA 0

0 0

87 (1/2)

D-27 INDICATOR DRESDEN LOCK AND DAM - DOWNSTREAM 0.8 MILES NW 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-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS SEDIMENT (PCI/KG DRY)

DREDGE SPOILS (PCI/KG DRY)

LA-140 GAMMA MN-54 NA

<LLD NA 0

.6 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 NA

<LLD NA

<LLD NA NA NA NA NA NA NA 0

0 0

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING TI-E 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, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS DREDGE SPOILS (PCI/KG DRY)

CS-134 CS-137 BA-140 LA-140

>0 150

<LLD 180 122 (4/6)

(95/142)

NA

<LLD NA

<LLD 10 20 (623/624)

(7/43)

NA

<LLD NA

<LLD NA NA NA NA 142 (I/i)

S-01D-NORTH SIDE INDICATOR PILE AT DRESDEN LOCK AND DAM 0.8 MILES NW OF SITE 0

0 0

AIR PARTICULATE (E-3 PCI/CU.METER)

GR-B 676 GAMMA MN-54 52 20 (52/52)

(8/42)

<LLD

<LLD 21 (52/52)

(8/41)

D-55 INDICATOR RIDGE ROAD 4.3 MILES N OF SITE 0

CO-58 FE-59 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, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (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)

CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 NA

<LLD NA

<LLD 50

<LLD 60

<LLD NA

<LLD

<LLD 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-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS AIR IODINE (E-3 PCI/CU.METER)

MILK (PCI/LITER)

GAMMA 1-131 676 70

<LLD I

NA

<LLD

<LLD 0

0 1-131 19 19 GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 NA NA NA NA NA NA NA NA NA NA NA NA

<LLD

<LLD 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-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS MILK (PCI/LITER)

ZR-95 CS-134 CS-137 BA-140 LA-140 GAMMA MN-54 NA NA 15 NA 18 NA 60 NA 15 NA

<LLD

<LLD 0

0 0

0 VEGETATION (PCI/KG WET) 10 CO-58 FE-59 NA

<LLD NA

<LLD

<LLD 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, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS VEGETATION (PCI/KG WET)

CO-60 ZN-65 NB-95 ZR-95 NA

<LLD NA

<LLD 60

<LLD 80

<LLD NA

<LLD

<LLD 0

0 0

1-131 CS-134 CS-137 BA-140 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, 2009 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS VEGETATION (PCI/KG WET)

LA-140 NA

<LLD NA 24.2 (352/352)

(19/35)

<LLD 21.6 (8/8)

(20/24) 0 DIRECT RADIATION (MILLI-ROENTGEN/QTR.)

TLD-QUARTERLY 360 29.5 (4/4)

(26/35)

D-201-2 INDICATOR (1) 4.8 MILES N (1) STATION D-214-2 ALSO HAD THE HIGHEST DOSE WITH A MEAN OF 29.5 MREM

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

TABLE B-1:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2009 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 - hi-weeklv / 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 0.8 miles NW 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)

Dt Dresden Lock and Dam, Downstream (indicator)

F.

Sedimen D-27 G.

Dredging Spoils S-01 T-01 Pile of dirt at Dresden Lock and Dam Pile of dirt at Dresden Lock and Dam H.

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, 2009 Location Location Description Distance & Direction From Site I. 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-1 10-3 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, 2009 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, 2009 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 Global Dosimetry Dosimetry comprised of two Global Midwest Laboratory Sampling Procedures Dosimetry TLDs, with Manual two CaF 2 elements and two LiF elements in each TLD.

104-1 1061 114.1 1 114,4 I

TO.M1 106,,

115-2N Druade Nuclea PGwW $talub 111314 11132 042 "3.4 a.

o U:

1Mb 1084 0

I 2spmu w"

OMfN DS am CU EMAAL 0111SrATM MWBF1, 2,& 3

rII Pbh TLID Sladimniet WATM OA4ZL5WTO Figure B-1 Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Location, 2009 B-5

12 IIY IRS

=====I IISIUli DRUSDIi 51TATIOXNI1 1,, & 3 CaM rTA WiI 2

Abr Sampdng Lacdon

MRl La will n*

TLaGSIof Figure B-2 Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2009 B-6

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

TABLE C-I.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/02/09 - 01/30/09 02/06/09 - 02/27/09 03/06/09 - 03/27/09 04/03/09 - 04/24/09 05/01/09 - 05/29/09 06/05/09 - 06/26/09 07/03/09 - 07/31/09 08/07/09 - 08/28/09 09/04/09 - 09/25/09 10/02/09 - 10/30/09 11/06/09 - 11/27/09 12/04/09 - 12/24/09 D-21 D-52 D-57 10 11 7.2 7.2 6.3 4.8 9.0 9.6 8.1 6.2 6.2 7.7

+/- 2.3

+/- 2.9

+/- 2.3

+/- 2.0

+/- 2.2

+/- 2.3

+/- 2.4

+/- 2.9

+/- 2.5

+/- 2.4

+/- 2.1

+/- 2.6 10 9.2 7.8 8.2 8.2 7.9 7.6 4.8 9.9 4.7 6.3 5.2

+/- 2.5

+/- 2.8

+/- 2.5

+/- 2.2

+/- 2.5

+/- 2.7

+/- 2.4

+/- 2.1

+/- 2.5

+/- 2.0

+/- 2.3 (1) 9.1 +/- 2.4 (1) 5.7 +/- 2.3 6.7 +/- 2.2 5.2 +/- 1.8 10 +/- 2.5

< 3.2 4.9 +/- 2.2 5.1 +/- 2.1 4.1 +/- 2.2

< 3.3 6.3 +/- 2.2 4.0 +/- 2.2 6:1 +/- 4.2 MEAN 7.8 +/- 3.7 7.5 +/- 3.7 TABLE C-I.2 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/02/09 - 03/27/09 03/27/09 - 06/26/09 07/03/09 - 09/25/09 10/02/09 - 12/24/09 D-21 D-52 D-57

< 168 537 +/- 133

< 168 181 +/- 109 359 +/- 503 168 182 169 161

< 174 465 +/- 134 621 +/- 135 594 +/- 129 560 +/- 167 MEAN

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1

TABLE C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD D-21 12/26/08 - 01/30 01/30/09 - 02/27 02/27/09 - 03/27 03/27/09 - 04/24/

04/24/09 - 05/29 05/29109 - 06/26/

06/26/09 - 07/31/

07/31/09 - 08/281 08/28/09 - 09/25/

09/25/09 - 10/30 10/30/09 - 11/27t 11/27/09 - 12/24/

Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140

/09

'09

/09

'09 MEAN

<4

<3

<1

<5

<4

<2

<4

<2

<1

<6

<5

<3

<2

<4

<5

<3

<1

<2

<7

<5

<4

<3

<2

<4

<5

<2

<1

<2

<1

<2

<6

<5

<3

<2

<9

< 10

<6

<3

<2

<4

< 15

< 10

<9

<8

<5

<6

<9

< 12

<5

<3

<4

<3

<4

< 12

< 11

<7

<4

<6

<3

<1

<7

<5

<4

<2

<4

<2

<1

<6

<5

<3

<2

<7

<8

<5

<2

< 15

< 10

<8

<4

<7

<8

<5

<2

<3

<2

<3

< 15

< 11

<9

<6

<3

<4

<5

<3

<1

<2

<8

<7

<5

<4

<3

<2

<4

<5

<3

<1

<2

<1

<2

<9

<5

<6

<3

<2

<7

<9

<5

<2

<1

<3.

< 12

<8

<7

<6

<5

<4

<7

<9

<4

<2

<3

<2

<3

< 11

<9

<5

<3

< 10

< 14

<8

< 10

<5

< 12

<7

<9

<8

<9

< 11

< 14

< 11

< 14

<6

< 11

<8

<9

< 11

<9

< 11

< 12

< 13

< 14

<3

<4

<3

<1

<5

<4

<2

<4

<5

<2

<1

<6

<4

<5

<2

<1

<4

<3

<1

<7

<6

<5

<4

<2

<4

<2

<1

<6

<3

<2

< 22

< 31

< 17

< 15

<9

< 19

< 11

< 24

< 21

< 24

< 25

< 36

< 14

< 16

< 14

< 17

< 27

< 28

< 25

< 24

< 21

<8

<9

<5

<3

<5

<3

< 10

<7

<8

< 10

<5

<4

<5

<4

<6

<9

<8

<9

<8

<6 D-52 01/02/09 02/06/09 03/06/09 04/03/09 05/01/09 06/05/09 07/03/09 08/07/09 09/04/09 10/02/09 11/06/09 12/04/09 01/30/09 02/27/09 03/27/09 04/24/09 05/29/09 06/26/09 07/31/09 08/28/09 09/25/09 10/30/09 11/27/09 12/24/09 MEAN

TABLE C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD D-57 12/26/08 - 01/30/

01/30/09 - 02/27/

02/27/09 - 03/27/

03/27/09 - 04/24/

04/24/09 - 05/29/

05/29/09 - 06/26/

06/26/09 - 07/31/

07/31/09 - 08/28/

08/28/09 - 09/25/

09/25/09 - 10/30/

10/30/09 - 11/27) 11/27/09 - 12/241 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 09

/09

'09

'09 t09

/09

'09

<4

<5

<3

<1

<2

<6

<5

<3

<1

<4

<5

<3

<2

<1

<2

<7

<5

<3

<2

<8

< 11

<6

<3

<4

<5

< 12

< 10

<6

<3

<5

<3

<1

<2

<6

<4

<2

<9

< 10

<5

<2

<3

< 11

<9

<6

<5

<3

<4

<5

<3

<2

<1

<2

<7

<5

<3

<2

<7

<9

<5

<3

<2

<3

<4

<9

<6

<5

<3

< 11

< 15

<8

< 11

<7

< 11

< 15

<9

<8

< 13

< 10

<4

<3

<1

<2

<5

<3

<1

<4

<5

<3

<1

<2

<7

<5

<3

<2

< 27

< 31

< 17

< 13

< 16

< 23

< 27

< 23

< 17

< 25

< 14

<9

<6

<5

<4

<6

<7

<9

<5

<7

<5 w-MEAN

TABLE C-I1.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/09/09 02/13/09 03/13/09 04/10/09 05/08/09 06/12/09 07/10/09 08/07/09 09/11/09 10/09/09 11/13/09 12/11/09 MEAN D-23 D-35 725 603 337 390 289 446 388 250 395 346 312 426

+/-

151 142 131 128 122 121 140 130 128 130 119 125

< 181

< 178

< 172 409 +/- 269

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-4

TABLES C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD D-23 01/09/09 02/13/09 03/13/09 04/10/09 05/08/09 06/12/09 07/10/09 08/07/09 09/11/09 10/09/09 11/13/09 12/11/09 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140

<1

<4

<3

<1

<2

<1

<4

<1

<2

<1

<2

<4

<2

<5

<3

<1

<2

<1

<4

<5

<1

<2

<1

<2

<5

<4

< 12

<7

<3

<5

<3

< 10

<9

< 11

<3

<4

<3

<5

< 12

<1

<4

<3

<2

<1

<2

<1

<4

<5

<4

<1

<2

<1

<2

<5

<3

<9

<6

<3

<2

<5

<2

<8

<9

< 10

<3

<4

<3

<2

<4

< 12

<2

<5

<3

<1

<2

<1

<5

<2

<1

<2

<5

<3

<8

<6

<2

<3

<4

<2

<7

<8

<9

<3

<4

<3

<2

<4

<9

<8

< 14

< 12

< 15

<5

<7

<9

< 10

< 12

<4

<9

< 12

< 10

<1

<4

<3

<1

<2

<1

<4

<5

<1

<2

<1

<2

<4

<2

<4

<3

<1

<2

<1

<4

<5

<1

<2

<1

<2

<5

< 13

< 28

< 26

< 17

< 20

< 13

< 23

< 29

< 32

<9

< 10

< 17

< 16

< 18

< 27

<5

< 12

< 10

<6

<5

<4

<8

<7

< 11

<3

<5

<6

< 10

(-i (J*

MEAN D-35 01/09/09 04/10/09 07/10/09 10/09/09 MEAN

TABLE C-I11.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 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-137 Ba-140 La-140 D-28 Freshwater Drum Largemouth Bass Common Carp Largemouth Bass 05/06/09 05/06/09 10/14/09 10/14/09

< 21

< 33

< 66

< 70

< 30

< 41

< 76

< 72

< 71

< 123

< 165

< 257

< 26

< 32

< 62

< 68

< 52

< 75

< 139

< 144

< 29

< 47

< 87

< 97

< 58

< 87

< 120

< 175

< 19

< 30

< 56

< 64

< 20

< 32

< 67

< 82

< 952

< 1410

< 1160

< 1300

< 240

< 326

< 346

< 504 MEAN D-46 Channel Catfish Common Carp Common Carp Largemouth Bass 05/06/09 05/06/09 10/14/09 10/14/09

< 26

< 33

< 36

< 55

< 30

< 48

<44

< 72

< 85

< 108

< 125

< 169

< 20

< 33

< 50

< 52

< 70

< 114

< 140

< 30

< 47

< 62

< 98

< 45

< 91

< 80

< 110

< 22

< 32

< 43

< 53

< 20

< 32

< 46

< 55

< 827

< 1500

< 774

< 1170

< 283

< 618

< 260

< 306 MEAN

TABLE C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PC/KG DRY +/- 2 SIGMA STC COLLECTION Mn-54 PERIOD Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 D-27 05/08/09 10/16/09

<76

< 93

<251

< 78

< 163

< 124

< 160

<70 87 +/- 69

< 1510

< 35

< 39

< 109

< 35

< 89

< 48

< 69

< 30

< 37

< 478

< 404

< 168 MEAN 87+/- 0

(-~I

-~1

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES

TABLE C-IV.2 STC S-01D-NORTH SIDE S-01D-SOUTH SIDE S-01S-NORTH SIDE S-01S-SOUTH SIDE T-01D

~

T-o1S COLLECTION PERIOD 05/15/09 05/15/09 05/15/09 05/15/09 05/15/09 05/15/09 MEAN CONCENTRATIONS OF GAMMA EMITTERS IN DREDGING SPOILS SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PC/KG DRY +/- 2 SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-

< 40

< 55

< 131

< 50

< 113

< 64

< 106

< 43 14

< 57

< 64

< 172

< 59

< 120

< 86

< 123

< 49

< 74

< 77

< 74

< 193

< 84

< 167

< 99

< 159

< 74

< 99

< 81

< 86

< 247

< 98

< 201

< 111

< 189

< 78 9

<5 4

< 60

< 148

< 56

< 128

< 76

< 111

< 51 12

< 86

< 93

< 270

< 78

< 196

< 107

< 187

< 67 12 12 137 2 +/- 49 5 +/- 65 7 +/- 56 3 +/- 73 2 +/- 39 U

Ba-140

< 676

< 710

< 847

< 1130

< 716

< 1080 La-140

< 135

< 234

< 253

< 322

< 204

< 288

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES

TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION GROUP I I

GROUP 11 PERIOD D-01 D-02 D-03 D-04 D-07 D-45 D-53 D-56 01/02/09-01/09/09 39 +/-6 36 +/-6 32 +/-5 27 +/-5 36 +/-6 39 +/-6 32 +/-5 37+/- 6 01/09/09

-01/16/09 30 +/-5 24 +/-4 33 +/- 5 35 +/-5 29 +/-5 26 +/-5 25 +/- 5 30+/- 5 01/16/09

-01/23/09 35 +/-5 38 +/-5 35 +/- 5 32 +/-5 36 +/- 5 34 +/-5 35 +/- 5 33+/- 5 01/23/09-01/30/09 31 +/-5 34 +/-5 35 +/-5 33 +/-5 34 +/-5 32 +/-5 386+/-6 36+/- 5 01/30/09- 02/06/09 14 +/-4 14 +/-4 14 +/-4 15 +/-4 19 +/-4 18 +/-4 13 +/-4 18+/- 4 02/06/09-02/13/09 25 +/-5 25 +/-5 24 +/-5 23 +/-5 22 +/-5 22 +/-5 25 +/-5 24+/- 5 02/13/09-02/20/09 23 +/-5 19 +/-4 22 +/-5 19 +/-4 22 +/-5 19 +/-4 23 +/-5 21+/- 5 02/20/09-02/27/09 26 +/-5 27 +/-5 25 +/-5 29 +/-5 20 +/-5 31 +/-5 24 +/-5 28+/- 5 02/27/09-03/06/09 22 +/-5 (1) 18 +/-4 25 +/-5 22 +/-4 23 +/-5 23 +/-5 20 +/-4 18 +/-4 03/06/09

-03/13/09 15 +/-4 17 +/-4 18 +/-4 21 +/-4 19 +/-4 21 +/-4 18

+/- 4 19 +/-4 03/13/09-03/20/09 19 +/-4 22 +/-4 22 +/-4 21 +/-4 23 +/-4 24 +/-5 22 +/-4 25+/- 5 03/20/09-03/27/09 23 +/-4 18 +/-4 21 +/-4 21+/-t4 20+/-t4 23+/-t4 22+/-t4 21+/-t4 03/27/09-04/03/09 10 +/-4 14 +/-4 12 +/-4 15 +/-4 12 +/-4 15 +/-4 12 +/-4 14 +/-4 04/03/09

-04/10/09 14 +/-4 (1) 20 +/-5 17 +/-4 16 +/-4 25 +/-6 (1) 16 +/-4 13 +/- 4 15 +/-4 04/10/09-04/17/09 22 +/-4 17 +/-4 20 +/-4 17 +/-4 22 +/-4 21 +/-4 19 +/- 4 16 +/-4 04/17/09 -04/24/09 14 +/-4 16 +/-4 16 +/-4 13 +/-4 16 +/-4 16 +/-4 15

+/- 4 15 +/-4 04/24/09 -05/01/09 7 +/- 3 11 +/- 3 12 +/- 4 10 +/- 3 10 +/- 3 13 +/- 4 12 +/- 4 13 +/- 4 05/01/09-05/08/09 19 +/-4 18 +/-4 22 +/-5 23 +/-5 (1) 14 +/-4 24 +/-5 22+/-t5 20+/-t4 05/08/09-05/15/09 8 +/-4 10 +/-4 8 +/-4 7+/-t4 8+/-t4 9+/-t4 7+/-4 9+/-4 05/15/09

-05/22/09 11 +/- 4 18 +/- 4 14 +/- 4 13 +/- 4 21 +/- 5 17 +/- 4 15 +/-4 15 +/-4 05/22/09 -05/29/09 11 +/- 4 16 +/- 4 15 +/- 4 15 +/- 4 14 +/- 4 12 +/- 4 15 +/-4 16 +/-4 05/29/09-06/05/09 13 +/-4 15 +/-4 15 +/-4 13 +/-4 16 +/-4 18 +/-4 12+/-4 15+/-4 06/05/09-06/12/09 9 +/-4 18+/-t4 14+/-t4 14 +/-4 15 +/-4 16 +/-4 13+/-4 13+/-4 06/12/09

-06/19/09 13 +/-4 14 +/-4 14 +/-4 13 +/-4 19 +/-4 15 +/-4 16 +/-4 18 +/-4 06/19/09-06/26/09 24 +/-4 22 +/-4 22 +/-4 22 +/-4 25 +/-4 21 +/-4 20+/-4 17 +/-4 06/26/09-07/03/09 8 +/-4 7 +/-4 8 +/-4 8 +/-4 9 +/-4 7 +/-4 16+/-4 10 +/-4 07/03/09-07/10/09 16 +/-4 17 +/-5 16 +/-4 13 +/-4 15 +/-4 11 +/-4 15+/-4 15 +/-4 07/10/09

-07/17/09 13 +/- 4 11 +/- 4 13 +/- 4 15 +/- 4 16 +/- 4 15 +/- 4 17

+/-5 17 +/- 5 07/17/09

-07/24/09 15 +/-4 19 +/-4 21

+/- 5 15 +/-4 16 +/-4 15+/-t4 15

+/-4 16 +/-4 07/24/09

-07/31/09 16+/-t4 17 +/-4 17 +/-4 12 +/-4 19 +/-4 16+/-t4 19 +/-4 13+/- 4 07/31/09

-08/07/09 11 +/- 4 20 +/- 5 19 +/- 5 19 +/- 5 18 +/- 4 19 +/- 4 21

+/-5 18 +/- 4 08/07/09

-08/14/09 17 +/-4 20 +/-5 20 +/- 5 21 +/-5 23 +/-5 20 +/-5 22 +/- 5 19 +/-5 08/14/09-08/21/09 17 +/-4 21 +/-5 24 +/-5 18 +/-4 19 +/-4 16 +/-4 18 +/-4 17 +/-4 08/21/09-08/28/09 7 +/-3 13 +/-4 15 +/-4 14 +/-4 13 +/-4 10 +/-4 9 +/-4 13 +/-4 08/28/09-09/04/09 21 +/-4 15 +/-4 19 +/-4 14 +/-4 16 +/-4 15 +/-4 17 +/-4 17 +/-4 09/04/09-09/11/09 34 +/-4 34 +/-4 36 +/-5 31 +/-4 34 +/-5 34 +/-5 32+/-t4 33+/-t4 09/11/09

-09/18/09 27 +/- 5 32 +/- 5 24 +/- 5 23 +/- 5 24 +/- 5 25 +/- 5 25 +/- 5 26 +/- 5 09/18/09-09/25/09 25 +/-5 21 +/-4 22 +/-4 22 +/-4 25 +/-5 23 +/-5 21 +/-5 27+/- 5 09/25/09-10/02/09 12 +/-4 13 +/-4 9 +/-4 12 +/-4 13 +/-4 13 +/-4 18 +/-4 13 +/-4 10/02/09

-10/09/09 11 +/- 4 10 +/- 4 8 +/- 3 12 +/- 4 8 +/- 4 11 +/- 4 13

+/- 4 11 +/- 4 10/09/09 -10/16/09 20 +/- 5 19 +/- 5 15 +/- 5 17 +/- 5 17 +/- 5 11 +/- 4 12

+/- 4 14 +/- 5 10/16/09-10/23/09 15 +/-4 18 +/-4 19 +/-4 19 +/-4 21 +/-4 16 +/-4 22 +/- 5 19 +/-4 10/23/09

-10/30/09 17 +/-5 14 +/-4 13 +/- 4 17 +/-5 20 +/-5 15 +/-4 18 +/- 5 13 +/-4 10/30/09

-11/06/09 16 +/- 4 19 +/- 4 18 +/- 4 14 +/- 4 15 +/- 4 17 +/- 4 16

+/- 4 16 +/- 4 11/06/09

-11/13/09 18 +/- 5 21 +/- 5 24 +/- 5 22 +/- 5 23 +/- 5 25 +/- 5 22 +/- 5 23 +/- 5 11/13/09

-11/20/09 18 +/- 4 16 +/- 4 12 +/- 4 17 +/- 4 15 +/- 4 23 +/- 4 14 +/- 4 17 +/- 4 11/20/09-11/27/09 25 +/-5 24 +/-5 20 +/-4 26 +/-5 29 +/-5 25 +/-5 27 +/-5 22+/- 5 11/27/09

-12/04/09 19 +/- 4 21 +/- 5 22 +/- 5 19 +/- 4 24 +/- 5 20 +/- 5 22 +/- 5 19 +/- 4 12/04/09 -12/11/09 22 +/- 4 24 +/- 4 26 +/- 4 23 +/- 4 26 +/- 4 21 +/- 4 27 +/- 4 21 +/- 4 12/11/09 -12/18/09 32 +/- 4 28 +/- 4 30 +/- 4 31 +/- 4 30 +/- 4 30 +/- 4 29 +/- 4 32 +/- 4 12/18/09-12/24/09 32+/-t6 37 +/-6 (1) 28 +/-6 32 +/-6 34 +/-6 34 +/-6 30 +/-6 42+/- 6 12/24/09-01/01/10 26 +/-4 26 +/-4 26+/-t4 26 +/-4 27 +/-4 26 +/-4 22 +/-4 27+/- 4 MEAN 19 +/-16 20 +/-14 20 +/-14 19 +/-14 21 +/-14 20 +/-14 20 +/-13 20+/- 15

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-9

TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION GROUP III IGROUP IV PERIOD D-08 D-10 D-14 D-55 D-12 01/02/09-01/09/09 34 +/-6 38 +/-6

-34

+/-5 37 +/-6 42+/- 6 01/09/09

-01/16/09 26 +/-5 28 +/-5 22 +/- 4 28 +/-5 26 +/- 5 01/16/09

-01/23/09 39 +/-5 30 +/-5 35 +/- 5 35 +/-5 30 +/-5 01/23/09-01/30/09 39 +/-6 34 +/-5 33 +/-5 37 +/-6 35+/- 5 01/30/09-02/06/09 19 +/-4 14 +/-4 22 +/-5 16 +/-4 19+/- 4 02/06/09-02/13/09 25 +/-5 24 +/-5 28 +/-5 28 +/-5 26 +/-5 02/13/09-02/20/09 22 +/-5 17 +/-4 21 +/-4 21 +/-4 23+/- 5 02/20/09-02/27/09 25 +/-5 24 +/-5 37 +/-6 28 +/-5 30+/- 5 02/27/09-03/06/09 22 +/-4 22 +/-4 21 +/-4 20 +/-4 19+/- 4 03/06/09

-03/13/09 19 +/-4 21 +/- 4 17 +/- 4 23 +/-5 20 +/- 4 03/13/09-03/20/09 24 +/-5 23 +/-4 26 +/-5 18 +/-4 25+/- 5 03/20/09

-03/27/09 22 +/-4 (1) 18 +/-4 21 +/-4 17 +/-4 (1) 22+/- 4 03/27/09

-04/03/09 12 +/-4 17 +/-4 13 +/- 4 8 +/-4 13 +/- 4 (1) 04/03/09

-04/10/09 15 +/-4 15 +/-4 17 +/- 4 12 +/-4 17 +/- 4 04/10/09

-04/17/09 18 +/-4 21 +/- 4 21

+/- 4 19 +/-4 21

+/- 4 04/17/09

-04/24/09 16 +/-4 18 +/-4 19 +/- 4 18 +/-4 14 +/- 4 04/24/09

-05/01/09 16 +/-4 12 +/-4 16 +/- 4 14 +/-4 13 +/- 4 05/01/09-05/08/09 24 +/-5 21 +/-5 24 +/-5 20 +/-4 20+/- 4 05/08/09-05/15/09 8 +/-4 8 +/-4 9 +/-4 10 +/-4 12 +/-4 (1) 05/15/09

-05/22/09 16 +/-4 14 +/-4 15 +/- 4 16 +/-4 16 +/- 4 05/22/09

-05/29/09 13 +/-4 15 +/-4 16 +/- 4 17 +/-4 14 +/- 4 05/29/09

-06/05/09 18 +/-4 14 +/-4 17 +/- 4 14 +/-4 17 +/- 4 06/05/09

-06/12/09 13 +/-4 15 +/-4 14 +/- 4 12 +/-4 12 +/- 4 06/12/09

-06/19/09 19 +/-4 17 +/-4 14 +/- 4 16 +/-4 18 +/- 4 06/19/09-06/26/09 20 +/-4 19 +/-4 24 +/-5 20 +/-4 18+/- 4 06/26/09

-07/03/09 10 +/-4

<5 10 +/- 4 12 +/-4 8 +/- 4 07/03/09

-07/10/09 13 +/-4 16 +/-4 16 +/- 4 14+/-4 10 +/- 4 07/10/09

-07/17/09 14 +/-4 15 +/-4 17 +/- 5 17+/-5 14 +/- 4 07/17/09

-07/24/09 16 +/- 4 11 +/- 4 19 +/- 5 17 +/-4 15 +/- 4 07/24/09

-07/31/09 17 +/-4 15 +/-4 17 +/-4 16+/-4 19+/- 4 07/31/09-08/07/09 17 +/-4 18 +/-4 18 +/-4 24+/-5 20+/- 5 08/07/09

-08/14/09 20 +/-5 19 +/-5 27 +/- 5 23+/-5 19 +/-5 08/14/09

-08/21/09 18 +/-4 20 +/-5 16 +/- 4 19+/-4 22 +/- 5 08/21/09

-08/28/09 12 +/-4 12 +/-4 13 +/- 4 15+/-4 15 +/- 4 08/28/09-09/04/09 18 +/-4 17 +/-4 15 +/-4 17+/-4 20+/- 4 09/04/09-09/11/09 37 +/-5 33 +/-4 43 +/-5 41+/-5 33 +/- 4.

09/11/09-09/18/09 30 +/-5 25 +/-5 29 +/-5 30+/-5 28+/- 5 09/18/09-09/25/09 28 +/-5 26 +/-5 23 +/-5 26+/-5 25+/- 5 09/25/09

-10/02/09 13 +/-4 17 +/-4 12 +/- 4 14+/-4 14 +/- 4 10/02/09

-10/09/09 11 +/- 4 10 +/- 4 10 +/- 4 13 +/-4 9 +/- 4 10/09/09

-10/16/09 11 +/- 4 10 +/- 4 14 +/- 5 15 +/-5 15 +/- 5 10/16/09

-10/23/09 20 +/-4 20 +/-4 17 +/- 4 18+/-4 19 +/- 4 10/23/09

-10/30/09 13 +/-4 13 +/-4 15 +/- 4 18+/-5 16 +/- 4 10/30/09

-11/06/09 12 +/- 4 17 +/- 4 18 +/- 4 22 +/-5 12 +/- 4 11/06/09

-11/13/09 19 +/- 5 23 +/- 5 19 +/- 5 26 +/-5 20 +/- 5 11/13/09

-11/20/09 19 +/- 4 14 +/- 4 14 +/- 4 17 +/-4 17 +/- 4 11/20/09-11/27/09 20 +/-4 27 +/-5 25 +/-5 27 +/-5 23+/- 5 11/27/09-12/04/09 21 +/-5 20 +/-5 19 +/-5 24 +/-5 19+/- 5 12/04/09

-12/11/09 23 +/- 4 22 +/- 4 27 +/- 4 27 +/- 4 20 +/- 4 12/11/09 -12/18/09 29 +/- 4 35 +/- 5 28 +/- 4 34 +/- 5 31 +/- 4 12/18/09-12/24/09 28 +/-6 30 +/-6 32 +/-6 39 +/-6 36+/- 6 12/24/09 -01/01/10 25 +/-4 29 +/-4 27 +/-4 23 +/-4 25+/- 4 MEAN 20 +/-15 20 +/-14 21 +/- 15 21 +/-16

.20 +/- 14

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION c-i1o

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, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP II - NEAR-FIELD LOCATIONS GROUP III - FAR-FIELD LOCATIONS GROUP IV - CONTROL LOCATION COLLECTION PERIOD 01/02/09 - 01/30/09 01/30/09 - 02127/09 02/27/09 - 04/03/09 04/03/09 - 05/01/09 05/01/09 - 05/29/09 05/29/09 - 07/03/09 07/03/09 - 07/31/09 07/31/09 - 08/28/09 08/28/09 - 10/02/09 10/02/09 - 10/30/09 10/30/09 - 11/27/09 11/27/09 - 01/01110 MIN MAX MEAN+/-

2SD 24 39 33 +/- 8 14 27 21 +/- 10 10 25 18 +/- 8 7

22 16 +/-8 8

22 14 +/- 9 7

24 14 +/- 11 11 21 16 +/- 5 7

24 17 +/- 10 9

36 23 +/- 17 8

20 15 +/-8 12 25 19 +/- 8 19 37 26 +/- 9 COLLECTION PERIOD 01/02/09 -

01/30/09 -

02/27/09 -

04/03/09 -

05/01/09 -

05/29/09 -

07/03/09 -

07/31/09 -

08/28/09 -

10/02/09 -

10/30/09 -

11/27/09 -

01/30/09 02/27/09 04103/09 05/01/09 05/29/09 07/03/09 07/31/09 08/28/09 10/02/09 10/30/09 11/27/09 01/01/10 MIN MAX MEAN+/-

2SD 25 39 33 +/- 8 13 31 22 +/- 9 12 25 20 +/- 7 10 25 16 +/- 8 7

24 15 +/- 10 7

25 15 +/-8 11 19 15 +/- 4 9

23 17 +/- 7 12 34 22 +/- 14 8

22 15 +/- 8 14 29 20 +/- 10 19 42 27 +/- 11 COLLECTION PERIOD 01/02/09 - 01/30/09 01/30/09 - 02/27/09 02/27/09 - 04/03/09 04/03/09 - 05/01/09 05/01/09 - 05/29/09 05/29/09 - 07/03/09 07/03/09 - 07/31/09 07/31/09 - 08/28109 08/28/09 - 10/02/09 10/02/09 - 10/30/09 10/30/09 - 11/27/09 11/27/09 - 01/01/10 MIN MAX MEAN +/-

2SD 22 39 33 +/- 10 14 37 23 +/- 11 8

26 19 +/- 9 12 21 17 +/- 5 8

24 15 +/- 10 10 24 16 +/- 8 11 19 16 +/- 4 12 27 18 +/- 8 12 43 25 +/- 18 10 20 14 +/- 7 12 27 20 +/- 10 19 39 27 +/- 10 COLLECTION PERIOD 01/02/09 01/30/09 02/27/09 04/03/09 05/01/09 05/29/09 07/03/09 07/31/09 08/28/09 10/02/09 10/30/09 11/27/09

- 01/30/09

- 02/27/09

- 04/03/09

- 05/01/09

- 05/29/09

- 07/03/09

- 07/31/09

- 08/28/09

- 10/02/09

- 10/30/09

- 11/27/09

- 01/01/10 MIN MAX MEAN+/-

2SD 26 42 33 +/- 13 19 30 25 t 10 13 25 20 +/- 9 13 21 16 +/- 7 12 20 15 +/- 7 8

18 15 +/- 9 10 19 14 +/- 7 15 22 19 +/- 6 14 33 24 +/- 15 9

19 15 +/- 8 12 23 18 +/- 9 19 36 26 +/- 14 8

42 20 +/- 14 01/02/09 - 01/01/10 7

39 20 +/- 15 01/02/09 - 01/01/10 7

42 20 +/- 14 01/02/09 - 01/01/10 8

43 20 +/- 15 01/02/09 - 01/01/10

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 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-01 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10

<3

<5

<4

<7

< 15

< 16

<7

<2

<3

< 3

<3

<6

< 10

<8

< 10

<3

<5

<4

<6

<9

<7

<3

<2

<3

<2

<4

< 65

< 541

< 560

< 47

< 21

< 237

< 174

< 23 MEAN C-)

D-02 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10 MEAN D-03 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10 MEAN D-04 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10

<4

<3

<4

<5

<6

<5

< 13

< 18

< 23

< 13

<4

<3

<4

<5

<8

<9

<4

<6

<7

<6

<7

<11

<7

<4

<3

<4

< 76

< 837

< 755

< 54

< 28

< 327

< 231

< 25

<4

<2

<3

<4

<5

<3

<10

< 12

< 14

<7

<3

<2

<3

<5

<8

<6

<8

<6

<4

<5

<6

<4

<8

<9

<8

<6

<3

<2

< 95

< 501

< 472

< 48

< 30

< 135

< 297

< 20

<2

<4

<3

<4

<3

<6

<5

<7

< 16

< 14

<9

<2

<4

<3

<2

<6

<7

<8

< 11

<3

<7

<6

<5

< 14

<8

<9

<2

<3

<4

<2

<3

<2

<4

< 61

< 662

< 471

< 63

< 11

< 280

< 296

< 24 MEAN

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 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-07 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10 MEAN D-08 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10 MEAN D-10 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10 MEAN D-12 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10

<4

<3

<5

<3

<5

<7

<4

< 11

< 17

< 20

<9

<3

<2

<4

<3

<8

<7

< 10

<7

<5

<9

<4

<7

< 12

< 15

<8

<3

<5

<3

<2

<3

< 90

< 644

< 816

< 55

< 31

< 244

< 320

< 21

<3

<5

<4

<5

<6

<5

< 11

<9

< 17

< 12

<3

<2

<3

<5

<7

<8

<7

<4

<5

<6

<5

<8

< 10

<9

<3

<4

<2

<3

<2

<4

< 84

< 671

< 502

< 67

< 34

< 245

< 285

< 31

<2

<3

<4

<2

<4

<6

<7

<3

<9

< 27

< 22

<7

<3

<4

<2

<6

<7

< 13

<7

< 4

<8

<7

<3

<6

< 13

< 12

<6

<3

<4

<3

< 68

< 826

< 774

< 57

< 24

< 198

< 348

< 23

<3

<4

<3

<5

<6

<4

< 12

< 14

< 20

< 12

<3

<2

< 10

<6

<7

<6

<5

<6

<5

<8

< 10

<7

<3

<84.

< 590

< 758

< 61

<34

< 216

< 303

< 25 MEAN

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD D-14 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-1 37 Ba-140 La-140

<3

<4

<3

<4

<6

<4

<3

< 10

< 18

< 14

<8

<3

<7

< 11

<7

<5

<4

<6

<3

<8

< 10

<9

<6

<3

<4

<3

<4

< 100

< 764

< 453

< 58

< 24

< 203

< 265

< 22 MEAN D-45 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10

<2

<4

<3

<4

<5

<3

<8

< 15

< 17

< 14

<2

<3

<6

<7

< 12

<8

<3

<5

<7

<5

<8

< 11

<8

<2

<5

<4

<2

<3

<4

< 44

< 532

< 781

< 68

< 11

< 182

< 313

< 30 MEAN D-53. 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10 MEAN D-55 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10

<3

<5

<7

<4

< 11

< 18

< 20

<9

<2

<3

<4

<3

<8

<9

< 11

<5

<7

<6

<3

<9

<11

<4

<3

<4

<3

< 102

< 811

< 791

< 43

< 22

< 281

< 315

< 19

<3

<2

<3

<6

<4

<6

<8

< 18

< 17

< 10

<3

<2

<4

<9

<6

<9

< 11

<5

<6

<8

< 10

<8

< 10

<3

<6

<3

<2

<3

< 85

< 635

< 680

< 73

< 31

< 244

< 142

< 14 MEAN

TABLE C-V.3 STC COLLECTION PERIOD D-56 01/02/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10 MEAN CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-1 377 Ba-140 La-140

<2

<4

<2

<4

<3

<5

<4

<6

< 19

< 18

< 10

<2

<3

<2

<5

<6

<8

< 10

<3

<7

<8

<5

<7

< 15

< 11

<8

<3

<4

<2

<3

<4

< 64

< 997

< 757

< 71

< 21

< 254

< 226

< 31

TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA GROUP[I GROUP II COLLECTION PERIOD D-01 D-02 D-03 D-04 D-07 D-45 D-53 D-56 01/02/09 -01/09/09

< 37

< 67

< 68

< 56

< 68

<67 01/09/09 -01/16/09

< 32

< 57

< 58

< 55

< 64

< 64 01/16/09 -01/23/09

< 15

< 8

< 15

< 25

< 25 01/23/09 -01/30/09

< 36

< 61

< 62

< 66

< 64

< 63 01/30/09 -02/06/09

< 38

< 39

< 30

< 38

< 39

< 33

< 43

< 44 02/06109-02/13109

< 14

< 25

< 26

< 29

< 41

< 41 02/13/09 -02/20/09

< 45

< 25

< 45

< 52

< 65

< 65 02/20/09 -02/27/09

< 15

< 23

< 25

< 23

< 23 02/27/09 -03/06/09

< 46 (1)

< 45

< 26

< 27

< 55

< 55 03/06/09 -03/13/09

< 10

< 18

< 19

< 25

< 25 03/13/09 - 03/20/09

< 20

< 37

< 42

< 41

< 41 03/20/09 -03/27/09

< 15

< 26

< 27

< 21

< 27

< 27 03/27/09 -04/03/09

< 37

< 69

< 68

< 61

< 58

< 58 04/03/09 -04/10/09

< 29 (1)

< 52

< 66 (1)

< 47

< 64

< 64 04/10/09-04/17/09

< 18

< 32

< 33

< 53

< 32

< 32 04/17/09 -04/24/09

< 28

< 42

< 63

< 62

< 61 04/24/09 -05/01/09

< 38

< 69

< 70

< 67

< 64

< 64 05/01/09 -05/08/09

< 43

< 65

< 65 (1)

< 65

< 69

< 66

< 66 05/08/09 -05/15/09

< 27

< 63

< 64

< 34

< 37

< 37 05/15/09 -05/22/09

< 36

< 65

< 66

< 48

< 40

< 37 05/22/09-05/29/09

< 40

< 59

< 61

< 26

< 19

< 25 05/29/09 -06/05/09

< 14

< 26

< 19

< 13

< 13 06/05/09 -06/12/09

< 27

< 28

< 27

< 54

< 58

< 57

< 57 06/12/09 -06/19/09

< 67

< 68

< 67

< 38

< 40

< 56

< 56 06/19/09 -06/26/09

< 68

< 65

< 54

< 30 06/26/09 -07/03/09

< 35

< 26

< 35

< 39

< 38

< 38 07/03/09 -07/10/09

< 43

< 57'

<57

< 57

< 68

< 47

< 45

< 25 07/10/09 -07/17/09

< 64

< 28

< 65

< 64

< 53

< 53 07/17/09 -07/24/09

< 65

< 57

< 38

< 37

< 37 07/24/09 -07/31/09

< 25

< 14

< 25

< 16

< 16 07/31/09 -08/07/09

< 37

< 39

< 26

< 39

< 38

< 37

< 37 08/07/09 -08/14/09

< 39

< 42

< 41

< 41 08/14/09 - 08/21/09

< 32

< 18

< 32

< 26

< 29

< 29 08/21/09 -08/28/09

< 34

< 38

< 36

< 35

.08/28/09 -09/04/09

< 29

< 66

< 69

< 68

< 65

< 64

< 64 09/04/09 -09/11/09

< 60

< 32

< 43

< 41

< 41 09/11/09 - 09/18/09

< 49

< 27

< 48

< 47

< 47 09/18/09 -09/25/09

< 60

< 62

< 61

< 63

< 64

< 47

< 26

< 46 09/25/09 -10/02/09

< 69

< 39

< 70

< 69

< 28

< 30

< 30 10/02/09 - 10/09/09

< 68

< 53

< 25

< 41

< 41 10/09/09 - 10/16/09

< 65

< 37

< 66

< 65

< 66

< 44

< 42

< 43 10/16/09 - 10/23/09

< 68

< 30

< 67

< 65

< 65 10/23/09 - 10/30/09

< 25

< 26

< 25

< 68

< 35

< 34

< 34 10/30/09 - 11/06/09

< 54

< 32

< 57

< 58

< 60

< 58

< 60 11/06/09 - 11/13/09

< 58

< 27

< 63

< 63 11/13/09 - 11/20/09

< 29

< 20

< 14

< 13

< 13 11/20/09 - 11/27/09

< 61

< 59

< 61

< 26

< 60 11/27/09 -12/04/09

< 52

< 53

< 51

< 30

< 65

< 62

< 62 12/04/09 -12/11/09

< 69

< 59

< 56

< 55

< 55 12/11/09 - 12/18/09

< 56

< 32

< 56

< 57

< 55

< 54

< 53 12/18/09 -12/24/09

< 52

< 22 (1)

< 52

< 51

< 49

< 48

< 48 12/24/09 - 01/01/10

< 38

< 69

< 70

< 53

< 49

< 49 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-i16

TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA GROUP III IGROUP IV COLLECTION PERIOD D-08 D-10 D-14 D-55 D-12 01/02/09 -

01/09/09

< 47

< 59

< 58

< 69

< 59 01/09/09

- 01/16/09

< 43

< 54

< 53

< 66

< 54 01/16/09

-01123/09

< 15

< 25

< 15 01/23/09

-01/30/09

< 40

< 66

< 66 01/30/09

-02/06/09

< 18

< 32

< 33

< 43

< 32 02/06/09

-02/13/09

< 23

< 30

< 29

< 42

< 29 02/13/09

-02/20/09

< 41

< 52

< 50

< 66

< 52 02/20/09

-02/27/09

< 14

< 25

< 24

< 25 02/27/09

-03/06/09

< 21

< 26

< 27

< 57

< 26 03/06/09

-03/13/09

< 15

< 19

< 27

< 19 03/13/09 03/20/09

< 23

< 42

< 42 03/20/09

-03/27/09

< 13

< 21

< 27

< 21 03/27/09

-04/03/09

< 62

< 49

< 61

< 60

< 66 (1) 04/03/09

-04/10/09

< 37

< 47

< 65

< 47 04/10/09

-04/17/09

< 53

< 33

< 22 04/17/09

-04/24/09

< 51

< 52

< 59

< 52 04/24/09

-05/01/09

< 67

< 54

< 67

< 67 05/01/09

-05/08/09

< 35

< 69

< 66

< 69 05/08/09 - 05/15/09

< 61

< 60

< 61

< 38

< 65 (1) 05/15/09 - 05/22/09

< 39

< 49

< 48

< 37

< 48 05/22/09 - 05/29/09

< 59

< 60

< 26

< 60 05/29/09 - 06/05/09

< 15

< 19

< 14

< 19 06/05/09 - 06/12/09

< 56

< 54

< 58

< 35

< 54 06/12/09 - 06/19/09

< 53

< 52

< 53

< 58

< 53 06/19/09 - 06/26/09

< 66

< 64

< 54

< 53

< 28 06/26/09 - 07/03/09

< 36

< 35

< 39

< 36 07/03/09 - 07/10/09

< 68

< 47

< 68 07/10/09 -07/17/09

< 57

< 53

< 57 07/17/09 - 07/24/09

< 57

< 38

< 26

< 57 07/24/09 - 07/31/09

< 35

< 16

< 35 07/31/09 - 08/07/09

< 25

< 26

< 38

< 26 08/07/09 - 08/14/09

< 42

< 41

< 24 08/14/09 - 08/21/09

< 11

< 26

< 29

< 26 08/21/09 - 08/28/09

< 22

< 38

< 36

< 38 08/28/09 -09/04/09

< 39

< 40

< 65

< 39 09/04/09 - 09/11/09

< 32

< 19

< 42

< 32 09/11/09 - 09/18/09

< 54

< 53

< 48

< 54 09/18/09

- 09/25/09

< 66

< 47

< 46

< 66 09/25/09

-10/02/09

< 61

< 58

< 29

< 60 10/02/09

-10/09/09

< 54

< 45

< 44

< 54 10/09/09 10/16/09

< 54

< 44

< 30 10/16/09

-10/23/09

< 65

< 67

< 65 10/23/09

-10/30/09

< 68

< 38

< 35

< 68 10/30/09

-11/06/09

< 52

< 60

< 52 11/06/09

-11/13/09

< 58

< 64

< 58 11/13/09

-11/20/09

< 27

< 28

< 14

< 28 11/20/09 -11/27/09

< 59

< 61

< 59 11/27/09

-12/04/09

< 61

< 64

< 61 12/04/09

-12/11/09

< 63

< 56

< 31

< 63 12/11/09

-12/18/09

< 61

< 55

< 61 12/18/09

-12/24/09

< 45

< 48

< 45 12/24/09

-01/01/10

< 67

< 69

< 53

< 69 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-I17

TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/01/09 02/05/09 03/05/09 04/02/09 05/07/09 05/20/09 06/04/09 06/18/09 07/02/09 07/16/09 07/30/09 08/12/09 08/27/09 09/10/09 09/24/09 10/08/09 10/21/09 11/05/09 12/03/09 CONTROLFARM D-25

< 0.8

< 0.6

< 0.4

< 0.8

< 0.5

< 0.7

< 0.4

< 0.6

< 0.8

< 0.7

< 0.6

< 0.7

< 0.6

< 0.5 MEAN C-18

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 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-1 34 Cs-137 Ba-140 La-140 D-25 01i01i09 02/05/09 03/05/09 04/02/09 05/07/09 05/20/09 06/04/09 06/18/09 07/02/09 07/16/09 07/30/09 08/i 2/09 08127/09 09/10/09 09/24/09 10/08/09 10/21/09 11/05/09 12/03/09

<4

<2

<7

<4

<2

<7

<3

<4

<6

<5

<4

<7

<5

<2

<7

<5

<3

<8

<3

<4

<5

<4

<5

<4

<6

<7

<5

<6

<5

<8

<5

< 13

<6

< 17

< 13

<7

< 15

<7

< 12

< 11

< 12

<9

< 15

< 11

< 14

< 10

< 18

< 14

<5

<2

<7

<5

<2

<6

<3

<4

<5

<3

<7

<5

<6

<5

< 10

<5

< 10

<4

< 17

< 11

<5

< 15

<7

< 10

<9

<8

< 10

<9

< 14

< 17

< 12

< 10

< 15

< 12

<5

<2

<7

<5

<3

<8

<3

<5

<4

<5

<4

<7

<6

<7

<4

<8

<6

<8

<4

< 13

<9

<4

< 10

<5

<8

<9

<8

<9

<5

< 10

< 12

< 10

< 11

<8

< 15

< 10

<4

<2

<7

<4

<2

<6

<3

<4

<3

<4

<2

<6

<5

<4

<7

<5

<4

<2

<6

<5

<2

<7

<3

<4

<3

<7

<6

<5

<8

<5

< 43

< 19

< 48

< 38

< 43

<54

< 22

< 40

< 39

< 25

< 43

< 24

< 30

< 28

< 30

< 35

< 22

< 46

< 45 12 6

11 13 14 15 6

10 11 9

10 7

13 7

14 13 MEAN

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 PERIOD Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 D-CONTROL Cabbage Potatoes D-QUAD 1 Cabbage Carrots 09/12/09

< 11

< 17 09/12/09

< 19

< 23

<42

<17

<36

< 15

< 51

< 23

< 50

< 24

< 28

< 38

< 13

< 38

< 42

< 17

< 15

< 90

< 29

< 17

< 108

< 29 MEAN 09/11/09

< 17

< 19 09/11/09

< 19

< 18

< 48

< 26

< 43

< 24

< 42

< 16

< 45

< 21

< 38

< 58

< 16

< 35

< 42

< 15

< 21

< 120

< 38

< 17

< 100

< 34 MEAN D-QUAD 2 0

Cabbage Carrots 09/11/09

< 8

< 7 09/11/09

< 14

< 13

<18

<6

<16

<9

< 37

< 13

< 30

< 15

< 21

< 7

< 28

< 37

< 12

<7

<40

< 14

<92

< 12

< 23 MEAN D-QUAD 3 Cabbage Onions D-QUAD 4 Beets Cabbage 09/12/09

< 12

< 10 09/12/09

< 8

< 10

< 22

< 8

< 25

< 13

< 24

< 10

< 23

< 11

< 19

<25

<8

< 16

<20

<8

<9

<58

< 11

< 52

< 16

< 15 MEAN 09/12/09

< 12

< 13 09/12/09

< 17

< 21

< 33

< 14

< 34

< 14

< 56

< 14

< 45

< 22

< 24

< 30

< 10

<34

<45

< 17

< 14

< 77

< 25

< 21

< 110

< 33 MEAN

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE 2 S.D.

D-01-1 24.5 +/- 4.8 27 22 23 26 D-01-2 24.0 +/- 4.0 27 23 23 23 D-02-1 26.8 +/- 4.1 28 29 25 25 D-02-2 25.3 +/- 2.5 27 25 25 24 D-03-1 21.5 +/- 3.5 23 20 20 23 D-03-2 21.8 +/- 6.2 26 19 20 22 D-04-1 25.8 +/- 2.5 27 24 26 26 D-04-2 24.0 +/- 3.7 26 22 23 25 D-07-1 24.0 +/- 3.3 26 24 22 24 D-07-2 23.5 +/- 2.6 24 23 22 25 D-08-1 25.3 +/- 7.7 31 24 23 23 D-08-2 25.5 +/- 2.6 26 24 27 25 D-10-1 25.3 +/- 3.4 27 25 23 26 D-10-2 23.3 +/- 3.8 26 22 22 23 D-12-1 22.3 +/- 2.5 24 21 22 22 D-12-2 21.0 +/- 2.8 23 20 21 20 D-14-1 21.5 +/- 3.8 24 22 20 20 D-14-2 23.8 +/- 2.5 25 22 24 24 D-45-1 26.0 +/- 4.9 27 24 29 24 D-45-2 25.3 +/- 1.9 26 25 26 24 D-53-1 21.0 +/- 2.8 23 21 20 20 D-53-2 20.8 +/- 3.4 23 19 20 21 D-55-1 25.0 +/- 2.8 27 24 25 24 D-55-2 24.0 +/- 2.8 26 23 24 23 D-56-1 21.3 +/- 1.0 22 21 21 21 D-56-2 21.0 +/- 4.3 24 21 19 20 D-101-1 25.0 +/- 2.8 27 24 25 24 D-101-2 22.8 +/- 3.4 25 22 23 21 D-102-1 28.5 +/- 6.8 33 25 27 29 D-102-2 25.8 +/- 2.5 27 26 24 26 D-103-1 23.5 +/- 2.6 25 24 23 22 D-103-2 23.8 +/- 3.0 26 23 23 23 D-104-1 27.0 +/- 3.7 29 25 28 26 D-104-2 24.0 +/- 7.1 29 24 22 21 D-105-1 23.8 +/- 1.9 25 23 24 23 D-105-2 24.3 +/- 3.0 26 23 23 25 D-106-1 23.3 +/- 5.3 27 21 22 23 D-106-2 21.5 +/- 2.6 23 20 22 21 D-107-1 21.8 +/- 5.7 26 21 20 20 D-107-2 21.5 +/- 6.2 26 21 20 19 D-108-1 24.8 +/- 3.4 27 25 24 23 D-108-2 23.8 +/- 2.5 25 24 24 22 D-109-1 25.3 +/- 5.3 29 23 24 25 D-109-2 25.8 +/- 2.5 27 26 24 26 D-110-3 28.3 +/- 3.4 30 26 28 29 D-110-4 27.5 +/- 2.6 28 27 26 29 D-111-1 26.8 +/- 4.1 28 25 25 29 D-111-2 26.0 +/- 6.7 31 24 25 24 D-113-1 21.8 +/- 3.4 24 20 22 21 D-113-2 23.5 +/- 5.3 24 22 27 21 D-114-1 22.5 +/- 2.6 24 22 21 23 D-114-2 23.0 +/- 2.3 24 22 24 22 C-21

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE

+/- 2 S.D.

D-115-1 24.5 +/- 2.6 26 23 24 25 D-115-2 25.3 +/- 2.5 27 25 24 25 D-116-1 26.0 +/- 3.7 27 24 25 28 D-116-2 26.0 +/- 7.1 31 24 23 26 D-201-1 28.5 +/- 4.8 31 27 26 30 D-201-2 29.5 +/- 8.1 35 27 26 30 D-202-1 26.0 +/- 1.6 26 26 25 27 D-202-2 24.0 +/- 2.8 26 23 23 24 D-203-1 25.0 +/- 3.7 26 24 23 27 D-203-2 22.5 +/- 3.5 24 21 21 24 D-204-1 22.3 +/- 4.1 25 22 20 22 D-204-2 22.8 +/- 3.0 24 22 21 24 D-205-1 24.5 +/- 3.8 26 22 26 24 D-205-2 23.5 +/- 4.8 27 22 22 23 D-206-1 23.3 +/- 4.4 24 21 22 26 D-206-2 24.3 +/- 2.5 26 23 24 24 D-207-1 23.0 +/- 4.9 24 26 21 21 D-207-2 23.8 +/- 3.4 26 (1) 23 22 24 D-208-1 22.5 +/- 6.0 27 21 21 21 D-208-2 22.5 +/- 5.3 26 23 21 20 D-209-1 20.8 +/- 3.0 23 20 20 20 D-209-2 21.5 +/- 3.8 22 24 20 20 D-210-1 23.8 +/- 4.1 26 21 24 24 D-210-2 25.8 +/- 5.5 29 27 23 24 D-211-1 25.0 +/- 5.4 29 23 24 24 D-211-2 25.0 +/- 8.2 31 23 22 24 D-212-3 22.5 +/- 4.8 26 21 22 21 D-212-4 21.8 +/- 4.4 25 21 21 20 D-213-1 21.3 +/- 3.8 24 20 20 21 D-213-2 20.5 +/- 2.0 22 20 20 20 D-214-1 27.3 +/- 3.0 28 29 26 26 D-214-2 29.5 +/- 2.6 28 31 29 30 D-215-1 29.0 +/- 5.9 32 26 31 27 D-215-2 27.3 +/- 3.0 28 25 28 28 D-216-1 23.3 +/- 3.0 25 22 22 24 D-216-2 26.0 +/- 2.3 27 25 25 27 D-112A-1 22.3 +/- 4.4 25 20 23 21 D-112A-2 22.3 +/- 2.5 24 22 21 22 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-22

TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE INNER RING, OUTER RING, OTHER AND CONTROL LOCATIONS FOR DRESDEN NUCLEAR POWER STATION, 2009 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 26.7 +/- 4.7 23.3 +/- 3.8 23.8 +/- 4.1 23.9 +/- 5.7 26.5 +/- 5.7 23.5 +/- 5.5 23.2 +/- 5.6 24.1 +/- 6.1 25.8 +/- 4.0 22.8 +/-_4.4 23.0 +/- 5.1 23.4 +/- 3.8 23.5 +/- 1.4 20.5 +/- 1.4 21.5 +/- 1.4 21.0 +/- 2.8 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR DRESDEN NUCLEAR POWER STATION, 2009 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 33 24.4 +/- 5.3 128 20 35 24.3 +/- 6.3 96 19 31 23.7 +/- 4.9 8

20 24 21.6 +/- 2.8 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-110-4, 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-23

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 01-01-00 12-31-00 1241-01 12-31-02 12-31-03 12-30-04 D-52 (C) DesPlaines River 0.0 01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 C-24

FIGURE C-1 (cont.)

SURFACE WATER - GROSS BETA - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2009 D-51 Dresden Lock & Dam 12.0 10.0 8.0 6.0 4.0 2.0

-J 0.

0.0 I-01-27-05 09-04-05 04-12-06 11-18-06 06-26-07 D-52 (C) DesPlaines River

.- I 0.

16.0 14.0 12.0 10.0 8.0 6.0 4.0 2.0 0.0 01-27-05 01-22-06 01-17-07 01-12-08 01-06-09 01-01-10 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-25

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 T 12.0+

10.0+

8.0 1.

6.0+

2.0 nflID I

I 01-01-00 12-31-00 12-31-01 12-31-02 12-3-.03 12-30.04 C-26

FIGURE C-2 (cont.)

SURFACE WATER - GROSS BETA - STATION D-54 (C) and D-57 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2009 D-54 (C) Kankakee River 14.0 12.0 10.0

.J 8.0

0.

6.0 4.0 2.0 0.0 01-27-05 09-04-05 04-12-06 11-18-06 06-26-07 D-57 (C) Kankakee River 32 28 24 20 16 12 8

4 0

07-28-06 04-04-07 12-10-07 08-16-08 04-23-09 12-29-09 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-27

FIGURE C-3 SURFACE WATER - GROSS BETA - STATION D-21 COLLECTED IN THE VICINITY OF DNPS, 2007 - 2009 D-21 Illinois River 30 25 20 15 10 5

-J C.)

0 I-04-27-07 11-09-07 05-23-08 12-05-08 06-19-09 01-01-10 D-21 PLACED INTO SERVICE ON MARCH 30, 2007, REPLACED D-51 C-28

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 2300.

-a-.

,o.1-o 1~1.0 0.1.1 12.31-02 124ý1-03

'92-30044 D-52 (C) Des Plalnes IRver ew T 4w +

3004.

I 300 +

1Ow*

D +

01-Olt-W 1:2.01-01 l'"1-02 12-31-03 i-M0 C-29

FIGURE C-4 (cont.)

SURFACE WATER - TRITIUM - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2009 D-51 Dresden Lock & Dam 2000 1800 1600 1400 1200 o

1000 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 C.

200 100 0

03-31-05 03-13-06 02-23-07 02-05-08 01-17-09 12-30-09 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-30

FIGURE C-5 SURFACE WATER - TRITIUM - STATION D-54 (C)

COLLECTED IN THE VICINITY OF DNPS, 2002 - 2004 D-54 (C) Kankakee River 400 300 100 +

\\flllo O+

-100

,Q1r-O1-@0 C-31

FIGURE C-5 (cont.)

SURFACE WATER - TRITIUM - STATION D-54 (C) AND D-57 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2009 D-54 (C) Kankakee River 800 700 600 500

.- I 400 300 200 100 0

3/31/2005 12/30/2005 9/30/2006 7/1/2007 Location shared with Braidwood Station (BD-10).

D-57 (C) Kankakee River 7000 6000 5000 4000 c

3000 2000 1000 0

12-20-06 07-29-07 03-06-08 10-13-08 05-22-09 12-29-09 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-32

FIGURE C-6 SURFACE WATER - TRITIUM - STATION D-21 COLLECTED IN THE VICINITY OF DNPS, 2007 - 2009 D-21 Illinois River 800 700 600 500 400 300 200 100

,J 0.

0 06-29-07 12-29-07 06-29-08 12-29-08 06-30-09 12-30-09 D-21 REPLACED D-51JUNE 29, 2007 C-33

FIGURE C-7 GROUND WATER - TRITIUM - STATIONS D-23 and D-35 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-23 Thorsen 1000 -

80 +

'I 60 +

/~>

400 /

200 +

04-4)1-00 12-31-00 12-31-01 12-,31-2 12-31-03 12-30-04 D-35 Dresden Lock and Dam 200 +

iL 100.

0-7.

-100+

01-01-00 12-31-00 12-31-01 12-31.02 12-31-03 12.30.04 C-34

FIGURE C-7 (cont.)

GROUND WATER - TRITIUM - STATIONS D-23 and D-35 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2009 D-23 Thorsen 1000 1 800

-/ I

-I 0

600 400 200 0

3/31/2005 3/13/2006 2/23/2007 2/5/2008 1/17/2009 12/30/2009 D-35 Dresden Lock and Dam

-J 12.

400 350 300 250 200 150 100 50 031 03-31-05 03-13-06 02-23-07 02-05-08 01-17-09 12-30-09 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-35

FIGURE C-8 AIR PARTICULATES - GROSS BETA - STATIONS D-01 and D-02 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D,01 OOiWN, Station I 4109 20t0o ID.O2 Onsite Stati~on 2 C]

1241-W C-36

FIGURE C-8 (cont.)

AIR PARTICULATES - GROSS BETA - STATIONS D-01 and D-02 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2009 D-01 Onsite Station I 50.0 40.0 E

30.0 C.,

c?

20.0 ulCD 10.0 0.0 *I*-

01-07-05 01-06-06 01-05-07 01-04-08 01-02-09 01-01-10 D-02 Onsite Station 2 Cl CL 50.0 40.0 30.0 20.0 10.0 0.0 09-23-05 06-10-06 02-25-07 11-12-07 07-29-08 04-15-09 12-31-09 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-37

FIGURE C-9 AIR PARTICULATES - GROSS BETA - STATIONS D-03 and D-04 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D,03, Onsite Station 3

.BJD 440 1"1431-D-04 C61Nins Rca4 WoD 4§.G to 2A, iZal-W 12-M-im

'02-3142 Ib0'04, C-38

FIGURE C-9 (cont.)

AIR PARTICULATES - GROSS BETA - STATIONS D-03 and D-04 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2009 D-03 Onsite Station 3 50.0 40.0 30.0 C.)

a.

20.0 10.0 0.0 I-01-07-05 01-06-06 01-05-07 01-04-08 01-02-09 01-01-10 D-04 Collins Road E

a.

Iol0, 60.0 50.0 40.0 30.0 20.0 10.0 0.0 01-07-05 01-06-06 01-05-07 01-04-08 01-02-09 01-01-10 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-39

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 Products IcLff I

V 4.0 CAD 4-12-al-im 12-ft-01 1241-42

IZZM4, D42 ((C) Lisibon lag lala 4.0 2.0 4-'D D1-IM-o 12k31-4S l2-2aý04 C-40

FIGURE C-10 (cont.)

AIR PARTICULATES - GROSS BETA - STATIONS D-07 and D-12 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2009 D-07 Clay Products 60.0 50.0 40.0

0. 30.0 9

o 20.0 10.0 0.0 I 01-07-05 01-06-06 01-05-07 01-04-08 01-02-09 01-01-10 06/10/05 - 06/17/05 no sample due to pump malfunction D-12 (C) Lisbon 60.0 50.0 40.0 E

C.)

0. 30.0 9

o 20.0 10.0 0.0 01-07-05 01-06-06 01-05-07 01-04-08 01-02-09 01-01-10 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-41

FIGURE C-1I AIR PARTICULATES - GROSS BETA - STATIONS D-45 and D-53 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-45 McKinley Woods Road 4.0 2.10 124t,41 12431W,(

D-53 Grundy Cournty 114-d MDe 01O1'O

'92-31.0M 1241,01 1241-m Ma~im 2-44 C-42

FIGURE C-11 (cont.)

AIR PARTICULATES - GROSS BETA - STATIONS D-45 and D-53 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2009 D-45 McKinley Woods Road 50.0 40.0 C')E 30.0 a..

9 20.0 1L0 10.0 0.0 I-01-07-05 01-06-06 01-05-07 01-04-08 01-02-09 01-01-10 D-53 Grundy County Road 82.0 L.)

C,,

w Q

0.0 I 01-07-05 01-06-06 01-05-07 01-04-08 01-02-09 01-01-10 DUE TO VENDOR CHANGE, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3,TO E-03 PCI/M3 C-43

FIGURE C-12 AIR PARTICULATES - GROSS BETA - STATIONS D-08 and D-10 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2009 D-08 Prairie Park 70.0 60.0 50.0 E 40.0 a.

30.0 Lu 0'-20.0 10.0 L 0.07-0 1-07-05 01-06-06 01-05-07 01-04-08 01-02-09 01-01-10 D-1O Goose Lake Village 60.0 50.0 40.0 E

0L 30.0 20.0 10.0 0.0.1.-

01-07-05 01-06-06 01-05-07 01-04-08 01-02-09 01-01-10 C-44

FIGURE C-13 AIR PARTICULATES - GROSS BETA - STATIONS D-13 and D-14 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2009 D-13 Minooka 50.0 40.0 30.0 0.

9 20.0 10.0 0.0 4-01-07-05 07-07-05 01-04-06 07-04-06 01-01-07 07-01-07 D-14 Channahon 50.0 40.0 E 30.0 20.0 10.0 0.0 01-07-05 01-06-06 01-05-07 01-04-08 01-02-09 01-01-10 D-13 TAKEN OUT OF SERVICE JUNE 29, 2007 AND REPLACED WITH D-55 C-45

FIGURE C-14 AIR PARTICULATES - GROSS BETA - STATIONS D-55 and D-56 COLLECTED IN THE VICINITY OF DNPS, 2006-2009 D-55 Ridge Road 50.0 40.0 30.0 a.

20.0 w

CD 10.0 0.0 01-06-06 09-06-06 05-07-07 01-05-08 09-04-08 05-05-09 01-03-10 D-56 Wildfeather 50.0 40.0 30.0 CL a.

0d, 20.0 10.0 0.0 I

I I

I 07-25-06 02-19-07 09-16-07 04-12-08 11-07-08 06-04-09 12-30-09 D-55 NEW STATION DECEMBER 30, 2005 REPLACED D-13 JUNE 29, 2007 D-56 NEW STATION JULY 25, 2006 C-46

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

March 2009 E6533-396 E6534-396 E6536-396 E6535-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 102 97.7 pCi/L 14.9 15.6 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 66.7 87.5 275 82.0 111 114 136 112 160 142 120 385 113 149 153 155 118 195 190 79.3 94.9 305 93.7 111 119 128 99.9 156 142 115 371 114 135 145 155 121 189 173 1.04 0.96 0.84 0.92 0.90 0.88 1.00 0.96 1.06 1.12 1.03 1.00 1.04 1.04 0.99 1.10 1.06 1.00 0.98 1.03 1.10 AP Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi 82.8 79.4 pCi/L 107 112 pCi/L 19.0 16.7 June 2009 E6742-396 E6743-396 E6745-396 E6744-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-i 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 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 98.1 260 389 144.0 185 86.9 133 126 173 298 186 262 101 135 61 83.1 84 137 202 102.0 284 400 166

192, 91.9 137 122 175 312 163 231 95 ill 53 79 70 101 180 1.04 0.96 1.14 0.96 0.92 0.97 0.87 0.96 0.95 0.97 1.03 0.99 0.96 1.14 1.13 1.06 1.22 1.16 1.05 1.19 1.36 1.12 0.96 A

A A

W A

A A

N (1)

A A

A AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi 92.2 95.8 D-1

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

September 2009 E6897-396 E6898-396 E6900-396 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 113 pCi/L 17.4 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 89.2 249 213 104.0 172 96.3 201 154 213 154 181 145 71.8 115 62 129 97 110 98.7 107 18.8 98.6 275 221 123 185 99.4 206 147 204 160 161 130 72 109 58 121 98 120 94.1 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 December 2009 E6899-396 E6946-396 E6947-396 pCi 89.5 92.3 pCi/L 131 131 pCi/L 19.3 17.9 1.06 0.93 0.90 0.91 0.96 0.85 0.93 0.97 0.98 1.05 1.04 0.96 1.12 1.12 0.99 1.06 1.06 1.07 0.98 0.92 1.05 0.97 1.00 1.08 0.91 0.96 0.93 0.88 0.91 0.95 1.00 0.99 0.94 0.94 1.00 1.04 0.90 1.02 1.03 0.89 1.17 0.88 1.03 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 79.2 193 512 222 163 200 178 176 326 240 103 290 116 93.4 111 81.0 106 155 135 87.3 202 548 253 179 211 178 178 345 256 103 280 129 91.5 108 90.8 90.8 176 131 A

A A

A E6949-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi pCi D-2

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

December 2009 E6948-396 Charcoal 1-131 pCi 93.3 93.9 0.99 A

(1) Detector 7 appears to have a slightly high bias. Detector 7 was removed from service until it can be recalibrated. NCR 09-23 (a) Teledyne Brown Engineering reported result.

(b) 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.

(c) Ratio of Teledyne Brown Engineering to Analytics results.

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable. Reported result falls within ratio limits of O.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, 2009 (PAGE 1 OF 1)

Identification Reported Known Month/Year Number Media Nuclide Units Value (a)

Value (b)

Control Limits Evaluation (c)

April 2009 RAD 77 Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 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 57.4 pCi/L 30.6 pCi/L 55.2 pCi/L 65.8 pCi/L 157 pCi/L 86.4 pCi/L 85.5 pCi/L 47.7 pCi/L 45.2 pCi/L 25.2 pCi/L 19733 pCi/L 64.75 pCi/L 30.30 pCi/L 97.9 pCi/L 76.8 pCi/L 59.9 pCi/L 121 pCi/L 115 pCi/L 19.6 pCi/L 28.5 pCi/L 22.1 pCi/L 16133 48.3 31.4 52.7 72.9 168 88.9 84.4 54.2 43.5 26.1 20300 62.2 30.7 92.9 79.4 54.6 117 99.5 23.2 26.0 22.2 16400 37.8 - 55.7 22.9 - 36.4 43.4 - 58.3 59.5 - 80.2 151 -187 80.0-100 76.0- 101 28.3 - 67.7 29.1 - 50.8 21.7 - 30.8 17800 - 22300 50.2 - 70.1 22.4 - 35.6 78.3 - 102 65.0 - 87.3 49.1 - 62.9 105-131 89.6-119 11.6-31.1 16.2-33.9 18.4-26.5 14300 - 18000 N (i)

A A

A October 2009 RAD 79 (1) Calculation did not allow for Y-90 ingrowth on the Sr-89 mount. NCR 09-14 (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, 2009 (PAGE 1 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

Range Evaluation (c)

March 2009 09-MaW20 Water Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Water Gr-A Gr-B 09-GrW20 09-MaS20 Soil Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/L 18.8 22.5 Bq/L 0.0601 Bq/L 17.0 18.9 Bq/L 16.1 17.21 Bq/L 332 330.9 Bq/L 13.8 14.7 Bq/L 6.88 7.21 Bq/L 13.2 13.6 Bq/L 0.529 0.635 Bq/L 1.87 1.27 Bq/kg 433 467 Bq/kg 649 605 Bq/kg

-0.120 Bq/kg 3.91 4.113 Bq/kg 339 307 Bq/kg 644 570 Bq/kg 245 257 Bq/kg 272 242 Bq/sample 2.77 2.93 Bq/sample 1.41 1.52 Bq/sample 1.24 1.30 Bq/sample 1.33 1.22 Bq/sample 2.42 2.2709 Bq/sample 0.713 0.64 Bq/sample 1.30 1.36 Bq/sample 0.188 0.348 Bq/sample 0.313 0.279 09-RdF20 09-GrF20 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B 18.5-29.3 (1) 13.2 -24.6 12.05 - 22.37 231.6 - 430.2 10.26-19.06 5.05-9.37 9.5-17.7

>0.0 - 1.270 0.64-1.91 327 - 607 424 - 787 (1)

(2) 215-399 399 - 741 180 - 334 169-315 2.05 - 3.81 1.06-1.98 0.91 -1.69 0.85-1.59 1.5898 - 2.9522 0.448 - 0.832 0.95 - 1.77

>0.0 - 0.696 0.140 - 0.419 2.38 - 4.42 0.65-1.21 1.65-3.07 (1) 1.61 -2.99 (4) 0.882 -1.638 0.948 - 1.760 22.5 - 41.9 28.8 - 53.6 25.6 - 47.6 10.8-20.0 443.9 - 824.3 (1) 9.09-16.89 18.8-35.0

>0.0 - 2.094 3.77-11.30 A

A A

March 2009 09-RdV20 September 2009 09-MaW21 Vegetation Cs-1 34 Bq/sample 3.48 3.40 Cs-137 Bq/sample 1.15 0.93 Co-57 Bq/sample 3.12 2.36 Co-60 Bq/sample

-0.0105 Mn-54 Bq/sample 2.98 2.3 K-40 Bq/sample 64.1 Sr-90 Bq/sample 1.09 1.260 Zn-65 Bq/sample 1.73 1.3540 A

W N (3)

A W

A A

Water Cs-1 34 Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Water Gr-A Gr-B Bq/L 26.5 32.2 Bq/L 37.2 41.2 Bq/L 32.2 36.6 Bq/L 14.0 15.40 Bq/L 705 634.1 Bq/L

-0.1015 Bq/L 13.9 12.99 Bq/L 26.2 26.9 Bq/L 1.27 1.047 Bq/L 9.70 7.53 09-GrW21 A

A D-5

TABLE D-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP1 TELEDYNE BROWN ENGINEERING, 2009 (PAGE 2 OF 2)

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

Range Evaluation (c)

September 2009 09-MaS21 Soil Am-241 Cs-134 Cs-137 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 Bq/kg 74.7 0.554 706 606 350 876 425 505 1370

-0.02 1.4 5.98 1.01 5.16 0.925 4.39 89.8 62.9-116.7 (1) 669 468-870 586 410-762 327.000 229-425 796 557-1035 375 263-488 455 319-592 1178 825-1531 09-RdF21 09-GrF21 09-RdV21 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 1.4 6.48 1.03 5.49 0.0835 3.93 (1) 0.98-1.82 4.54 - 8.42 0.72-1.34 3.84-7.14 0.585 - 1.086 2.75-5.11 A

A A

A Bq/sample 0.357 0.659

>0.0 - 1.318 Bq/sample 1.403 1.320 0.66 - 1.98 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample

-0.0027 2.36 2.58 8.36 57.8 1.73

-0.59 (1) 2.43 1.70-3.16 2.57 1.80 - 3.34 7.9 5.5-10.3 (4) 1.78 1.25-2.31 (1)

(1) False positive test.

(2) Sensativity evaluation.

(3) Homogeniety problem. MAPEP requires using entire sample but due to geometry limitations we can only use part of the sample. NCR 09-13 (4) Not evaluated by MAPEP.

(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

There is no errata data for 2009.

E-1

Intentionally left blank

APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

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 2009 Prepared By Teledyne Brown Engineering Environmental Services Exelkn.

Nuclear Dresden Nuclear Power Station Norris, IL 60450 May 2010

Table of Contents I. Sum m ary and Conclusions..........................................................................................

1 II. Introduction.............................................................................................................

2 A. O bjectives of the RG PP..................................................................................

3 B. Im plem entation of the O bjectives..................................................................

4 C. Program Description.......................................................................................

4 D. Characteristics of Tritium (H-3)......................................................................

4 II1. Program Description................................................................................................

5 A. Sam ple Analysis............................................................................................

5 B. Data Interpretation..........................................................................................

6 C. Background Analysis.....................................................................................

7

1. Background Concentrations of Tritium.................................................

7 IV. Results and Discussion............................................................................................

9 A. G roundwater Results.....................................................................................

9 B. Drinking W ater W ell Survey.........................................................................

10 C. Summary of Results - Inter-laboratory Comparison Program......................

10 D. Leaks, Spills, and Releases.........................................................................

11 E. Trends..........................................................................................................

11 F. Investigations.................................................................................................

11 G. Actions Taken..............................................................................................

12

Appendices Appendix A Tables Table A-1:

Location Designation Figqures Appendix B Tables Table B-1.1 Table B-1.2 Table B-11.1 Table B-11.2 Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2009 Security-Related Information: Maps of the Dresden Nuclear Power Station have been withheld from public disclosure under 10CFR2.390 and N.J.S.A. 47:1A-1.1 Data Tables Concentrations of Tritium in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2009.

- 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 (P.A.).

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 P.A. 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. The results of the HIR are available on:

[http://www.exeloncorp.com/ourcompanies/powerqen/nuclear/Tritium

.html.

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 71 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 26 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 2009, there were 213 analyses that were performed on 142 samples from 71 sampling points.

Supplemental Radiologqical Groundwater Monitoring Program (SRGPP):

Dresden also has a Supplemental Radiological Groundwater Monitoring Program (SRGPP) that provides short-term monitoring of a limited selection of monitoring points, mostly within the P.A., intended to identity 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.

Many sentinel wells were installed near an underground HPCI suction line and were subsequently removed as part of the excavation and repair of that line.

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 P.A.

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 71 developed groundwater wells and surface water sample points in the RGPP.

1.

Sample Collection Sample locations can be found in Table A-I, Figures A-1 and A-2, and, 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 is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.

IIl.

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 2009.

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 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 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-140 and La-140 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 world wide from 1960 to 2006.

RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons.

Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time. Tritium concentrations in 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 (22 wells) show some level of tritium contamination ranging from just above LLD to - 100,000 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.

Outside the Protected Area:

Of the 26 developed groundwater-monitoring wells on station property outside the Protected Area, 5 wells have a tritium concentration at or just slightly above the level of detectability (208 pCi/L to 322 pCi/L).

Three (3) of the five 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 75,000 pCi/L in March of 2003. The tritium concentration has been trending down and all three are now very near the lower limit of detectability.

One (1) of the five 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 780 pCi/L in late 2005 and has been trending down since.

One (1) of the five wells with detectable tritium is just south of the Protected Area fencing 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 350 pCi/L in May of 2007 and has been trending down since.

Gamma Emitters Potassium-40 was detected in six of 65 samples. The concentrations ranged from 40 pCi/liter to 95 pCi/liter. No other 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-II. 1, Appendix B). Tritium values ranged from the detection limit to 690 pCi/I.

The measurable concentrations of tritium are from an upstream source.

Gamma Emitters Potassium-40 was detected in one of six samples, at a concentration of 75 pCi/liter. No other gamma emitting nuclides were detected. (Table B-11.2, Appendix B).

C.

Drinking Water Well Survey A drinking water well survey was conducted during the summer 2006 by CRA (CRA 2006) around the Dresden Nuclear Power Station. No tritium was detected in the drinking water source.

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 In the summer of 2004 elevated tritium concentrations were identified in sentinel wells within the Protected Area by the HPCI suction line near the HPCI room adjacent to the Reactor Building. This line was found leaking and about one-half of the line was excavated and replaced.

In January of 2006 there was an increase in tritium concentration in two sentinel wells within the Protected Area near the HPCI suction line adjacent to the 2/3B Contaminated Storage Tank (2/3B CST), about 100 feet from the Reactor Building. This suggested that the other half of the HPCI suction line was leaking. The line was excavated and pressure tested. It was determined that this line was not leaking. The line did show some indications of degradation and as a result, this half of the line was replaced.

In June of 2009 a slightly elevated tritium concentration was detected in a sewer within the Protected Area. The sewer was isolated and an investigation identified a small leak in an underground 24-inch cross-tie line that connected Unit 1 and Unit 2/3 CSTs. The leak was found just east of the Reactor Building wall. The line was excavated and a carbon-fiber rap was selected as the permanent repair option. The excavation was backfilled in September of 2009.

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 Following a heavy rain in August of 2007, water was flowing into the Cribhouse basement through an underground electrical penetration. The water contained tritium at a concentration above LLD. Samples taken the next day showed higher concentrations of tritium suggesting an increasing trend.

Further monitoring showed the tritium concentration was steady for a few days then started decreasing. The flow decrease over the next several days then stopped completely. If this were a leak of an underground piping system we would expect that the flow would continue and the tritium concentration would continue to increase by several orders of magnitude. Therefore, the detected tritium is believed to be from a historic spill, possibly from the RadWaste Tank Farm which is in the vicinity. In 2008 berms were installed under the tanks in the RadWaste Tank Farm. This berm is designed to capture any possible future spills.

Following a heavy rain in September of 2008 water was again detected entering the Cribhouse through the electrical penetration. Analysis of the samples collected showed no detectible tritium.

There is currently no flow through any Cribhouse electrical penetrations and Dresden continues to monitor in the vicinity of the Cribhouse basement.

H.

Actions Taken

1.

Compensatory Actions A groundwater collection and treatment system was used during the excavation and repair of the 24-inch underground cross-tie line between the Unit 1 to Unit 2/3 CSTs. As with the groundwater collection and treatment systems employed during the excavation work associated with the 2004 and 2006 leak repairs, the groundwater was processed through the RadWaste System.

These compensatory actions were particularly effective in that the measured tritium contamination in vicinity of the 24-inch underground cross-tie line is near the lower limits of detectability.

2.

Actions to Recover/Reverse Plumes No actions were taken in 2009 by Dresden Station in an effort to reverse plume movement.

APPENDIX A LOCATION DISTANCE

TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2009 Site Site Type Location DSP-105 DSP-106 DSP-107 DSP-108 DSP-117 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-1 10-1 MW-DN-1 1 0-S MW-DN-111-S MW-DN-1 12-1 MW-DN-1 12-S MW-DN-113-1 MW-DN-1 13-S MW-DN-1 14-1 MW-DN-1 14-S MW-DN-1 15-1 MW-DN-i 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 Monitodng 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 comer 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 corner 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 comer 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 corner 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 Heineke Road; northeast of the G.E. Fuel Storage Facility 150 feet north of Heineke Road; northeast of the G.E. Fuel Storage Facility 400 feet west of the Thorsen house; west of the Cold Canal A-i

TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2009 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-DN-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

TABLE B-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 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-1 17 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-156 DN-DSP-157-1 DN-DSP-157-1 DN-DSP-157-S DN-DSP-157-S DN-DSP-158-1 COLLECTION DATE 05/21/09 10/01/09 05/21/09 10/01/09 05/22/09 10/01/09 05/22/09 09/30/09 05/26/09 10/05/09 05/26/09 10/05/09 05/19/09 09/29/09 05/22/09 09/30/09 05/22/09 10/02/09 05/21/09 10102/09 05/27/09 10/06/09 05/26/09 10/06/09 05/26/09 0105/09 05/26/09 10/05/09 05/18/09 10/01/09 05/18/09 10/01/09 05/27/09 10/06/09 05/27/09 10/06/09 05/27/09 10/06/09 05/26/09 10/05/09 05/27/09 10/07/09 05/27/09 10/07/09 05/27/09 H-3 298 +/- 115

< 196 3390 +/- 388 2870 +/- 332 6420 +/- 689 5720 +/- 614 1250 + 181 985 +/- 191

< 170

< 187

< 185

< 183 3780 +/- 427 2730 +/- 322 10900 +/- 1130 8570 +/- 895 6880 +/- 735 16600 +/- 1690 200 +/- 109

< 188

< 185

< 182'

< 182

< 181 341 209 357 322

+

+/-

130 122 116 129

< 163

< 179

< 164

< 194

< 135

< 183

< 138

< 182

< 137

< 187 312 +/- 113 275 +/- 126

< 134

< 179

< 138

< 177

< 134 B-1

TABLE B-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE DN-DSP-158-1 DN-DSP-158-S DN-DSP-158-S DN-DSP-159-1 DN-DSP-159-1 DN-DSP-159-S DN-DSP-159-S MW-DN-101-1 MW-DN-101-1 MW-DN-i101-S MW-DN-101-S MW-DN-102-1 MW-DN-102-1 MW-DN-102-S MW-DN-102-S MW-DN-103-1 MW-DN-103-1 MW-DN-103S MW-DN-103S MW-DN-104-S MW-DN-104-S MW-DN-105-S MW-DN-105-S MW-DN-106-S MW-DN-106-S MW-DN-107-S MW-DN-107-S MW-DN-108-1 MW-DN-108-1 MW-DN-109-1 MW-DN-109-1 MW-DN-109-S MW-DN-109-S MW-DN-110-1 MW-DN-110-1 MW-DN-110-S MW-DN-110-S MW-DN-111-S MW-DN-111-S MW-DN-1 12-1 MW-DN-1 12-1 MW-DN-1 12-S MW-DN-1 12-S MW-DN-1 13-1 MW-DN-1 13-1 COLLECTION DATE 10/06/09 05/27/09 10/06/09 05/27/09 10/07/09 05/27/09 10/07/09 05/ 18/09 09/30/09 05/18/09 09/30/09 05/20/09 10/02/09 05/20/09 10/02/09 05/27/09 10/07/09 05/27/09 10/07/09 05/19/09 09/29/09 05/18/09 10/01/09 05/26/09 10/05/09 05/20/09 10/02/09 05/19/09 09/30/09 05/19/09 09/29/09 05/19/09 09/29/09 05/19/09 09/29/09 05/19/09 09/29/09 05/21/09 10/02/09 05/19/09 09/29/09 05/19/09 09/29/09 05/20/09 10/02/09 H-3

< 195

< 136

< 194 308 +/- 129 243 +/- 127

< 139

< 196 1750 +/- 229 1780 +/- 239

< 185

183

185

< 185 250 +/- 123

< 189

162 208 +/- 123

< 164

< 183

< 184 246 +/- 124

< 186

< 178

< 165

< 182 243 +/- 112 1120 +/- 180

< 183

< 181

< 184

< 187 246 +/- 121 224 +/- 123

< 174 203 +/- 120

< 169

< 181 452 522 1450 1250

< 170

185

< 160

< 188

+

128 127 200 192 B-2

TABLE B-1.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-DN-1 13-S MW-DN-1 13-S MW-DN-1 14-1 MW-DN-1 14-1 MW-DN-1 14-S MW-DN-1 14-S MW-DN-1 15-1 MW-DN-1 15-1 MW-DN-1 15-S MW-DN-1 15-S MW-DN-1 16-1 MW-DN-1 16-1 MW-DN-1 16-S MW-DN-1 16-S MW-DN-1 17-1 MW-DN-1 17-1 MW-DN-1 18-S MW-DN-1 18-S MW-DN-1 19-1 MW-DN-1 19-1 MW-DN-1 19-S MW-DN-1 19-S MW-DN-120-1 MW-DN-120-1 MW-DN-120-S MW-DN-120-S MW-DN-121-S MW-DN-121-S MW-DN-122-1 MW-DN-122-1 MW-DN-122-S MW-DN-122-S MW-DN-123-1 MW-DN-123-1 MW-DN-123-S MW-DN-123-S MW-DN-124-1 MW-DN-124-1 MW-DN-124-S MW-DN-124-S COLLECTION DATE 05/20/09 10/02/09 05/21/09 10/01/09 05/20/09 10/01/09 05/20/09 10/01/09 05/20109 10/01/09 05/19/09 09/30/09 05/19/09 09/30/09 05/18/09 09/30109 05/21/09 10/01/09 05/18/09 09/30/09 05/18109 09/30/09 05/26/09 10/05/09 05/26/09 10/05/09 05/26/09 10/06/09 05/26/09 10/06/09 05/26/09 10/06/09 05/26/09 10/07/09 05/26/09 10/07/09 05/22/09 10/02/09 05/22/09 10/02/09 H-3 328 +/- 119

< 189 8650 +/- 903 7140 +/- 755 1950 +/- 242 1320 +/- 211 413 +/- 125 273 +/- 145 172 +/- 111

< 196 1950 +/- 242 3310 +/- 378 398 +/- 123 262 +/- 141

< 162

< 190 3120 +/- 356 1240 +/- 203 1810 +/- 238 536 +/- 160

< 179

< 187 490 +/- 139 149 169 198 167 153 166 200 165 196 162 148 164 178 108000 84200 65100 68500

+/- 10700

+/- 8390

+/- 5920

+/- 6870 B-3

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC 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 DSP-103S 10/07/09 DSP-105 10/01/09 DSP-106 10/01/09 DSP-107 10/01/09 DSP-108 09/30/09 DSP-1 17 10/05/09 DSP-121 10/05/09 DSP-122 09/29/09 DSP-123 09/30/09 DSP-124 10/02/09 DSP-i25 10/02/09 DSP-126 10/06/09 DSP-147 10/06/09 DSP-148 10/05/09 DSP-149R 10/05/09 DSP-i15 10/01/09 DSP-151 10/01/09 DSP-152 10/06/09 DSP-153 10/06/09 DSP-154 10/06/09 DSP-156 10/05/09 DSP-157-I 10/07109 DSP-157-S 10/07/09 DSP-158-1 10/06/09 DSP-158-S 10/06/09 DSP-159-4 10/07/09 DSP-159-S 10/07/09 MW-D -1901- 09/30/09 MW-DN-101-S 09/30/09 MW-DN-102-I 10/02/09 MW-DN-102-S 10/02/09 MW-DN-1 03-1 10/07/09

< 43

< 70

< 5

< 34

< 62

< 4

< 43

< 96

< 4

< 45

< 38

< 5

< 43

< 97

< 5

< 34

< 31

< 3

< 37

< 36

< 4

< 46

< 49

< 6

< 30

< 35

< 3

< 38

< 45

< 4

< 33

< 29

< 3

< 35

< 75

< 4

< 33 70 +/-42

< 4

< 28

< 27

< 3

< 30

< 61

< 3

<41

< 96

<4

< 44

< 49

< 4

< 34

< 76

< 4

< 28

< 61

< 3

< 34

< 82

< 4

< 31

< 29

< 3

<38

<27

<4

< 33

< 39

< 4

< 30

< 3

< 31

< 27

< 3

<29 75+/-38

<3

< 25

< 2

< 44

< 36

< 5

< 26 60 +/-32

< 3

< 32

< 36

< 4

< 28

< 58

< 3

< 42

< 46

< 5

<4

<5

<3

<4

<3

<4

<3

<4

<3

<5

<4

<3

<4

<3

<5

<3

<5

<8

<4

<8

<3

<11

<4

<12

<6

<9

<4

<8

<4

<9

<5

<11

<4

<7

<3

<9

<3

<8

<3

<9

<4

<7

<4

<7

<3

<8

<3

<10

<5

<11

<5

<10

<4

<9

<4

<10

<5

<7

<3

<7

<4

<8

<4

<6

<4

<7

<3

<6

<3

<7

<3

<11

<4

<6

<2

<8

<4

<7

<3

<12

<5

<9

<5

<9

< 11

<8

<7

<10

<7

< 10

<5

<8

<7

<6

<9

<10

<9

<8

<9

<7

<8

<7

<6

<5

<6

<9

<5

<7

<6

< 11

<5

<4

<5

<6

<5

<4

<5

<4

<6

<7

<5

<4

<5

<3

<5

<3

<4

<3

<6

<3

<4

<3

<6

<7

<8

< 10

<7

<9

<6

<9

<7

<8

<7

<6

<9

<7

<8

<7

<5

<6

<5

<10

<5

<6

<9

<11

<4

<9

<3

<11

<4

<13

<5

<13

<4

<12

<3

<15

<3

<14

<4

<9

<3

<9

<4

<8

<3

<14

<4

<13

<3

<12

<3

<12

<3

<11

<5

<12

<4

<14

<4

<13

<3

<14

<4

<15

<3

<14

<4

<14

<4

<12

<3

<12

<3

<11

<3

<9

<3

<15

<4

<10

<2

<11

<3

<9

<3

<13

<5

<4

<6

<5

<3

<4

<6

<3

<5

<4

<3

<5

<4

<3

<4

<3

<5

<2

<4

<3

<5

<32

<8

<21

<6

<28

<9

<29

<7

<32

<8

<26

<8

<28

< 11

<32

<9

<19

<6

<20

<9

<22

<6

<28

<9

<31

<6

<23

<8

<25

<9

<26

< 10

<30

< 11

<28

< 10

<27

<9

<32

< 10

<26

<9

<29

<9

<28

<8

<22

<7

<25

<9

<23

<7

<21

<7

<33

< 12

<20

<7

<22

< 10

<22

<8

<30

< 11

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC 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-i 40 La-140 MW-DN-104-S 09/29/09 MW-DN-105-S 10/01/09 MW-DN-106-S 10/05/09 MW-DN-107-S 10/02/09 MW-DN-108-1 09/30/09 MW-DN-109-1 09/29/09 MW-DN-109-S 09/29/09 MW-DN-110-1 09/29/09 MW-DN-110-S 09/29/09 t

MW-DN-111-S 10/02/09 6

MW-DN-1 12-1 09/29/09 MW-DN-1 12-S 09/29/09 MW-DN-1 13-1 10/02/09 MW-DN-1 13-S 10/02/09 MW-DN-1 14-1 10/01/09 MW-DN-1 14-S 10/01/09 MW-DN-1 15-1 10/01/09 MW-DN-1 15-S 10/01/09 MW-DN-1 16-1 09/30/09 MW-DN-1 16-S 09/30/09 MW-DN-120-1 10/05/09 MW-DN-120-S 10/05/09 MW-DN-121-S 10/06/09 MW-DN-122-1 10/06/09 MW-DN-122-S 10/06/09 MW-DN-123-1 10/07/09 MW-DN-123-S 10/07/09 MW-DN-124-1 10/02/09 MW-DN-124-S 10/02/09 MW-DN-1 17-1 09/30/09 MW-DN-1 18-S 10/01/09 MW-DN-1 19-1 09/30/09 MW-DN-1 19-S 09/30/09

< 31 72 +/- 41

< 3

< 40

< 79

< 4

< 40

< 76

< 4

< 42 95 +/- 57

< 4

< 37

< 39

< 4

< 30

< 27

< 3

< 27

< 20

< 3

< 48

< 45

< 5

< 38

< 67

< 4

< 53

< 46

< 4

<32

<74

<4

< 53

< 80

< 4

< 47

< 41

< 4

< 46

< 119

< 5

<42

< 91

<4

< 48

< 38

< 5

< 38

< 79

< 4

< 21

< 19

< 2

< 15

< 13

< 1

< 16

<28

<2

< 29

< 62

< 3

< 40

< 79

< 4

<45

<44

<4

< 45

< 131

< 6

< 35

< 85

< 4

< 40

< 37

< 5

<45

<44

<4

<24

< 16

<2

<22

< 18

<2

< 18

< 2

< 17 40 +/-25

< 2

<20

< 19

<2

< 17

< 15

< 2

<3

<5

<4

<5

<3

<4

<3

<5

<4

<5

<4

<5

<6

<5

<4

<5

<4

<2

<4

<5

<4

<5

<4

<2

<7

< 11

<9

< 10

<8

<7

<6

< 12

<9

< 10

<9

< 10

< 11

<7

< 11

<8

<5

<4

<8

< 10

<9

< 11

<9

< 10

<9

<5

<4

<5

<4

<3

<4

<5

<3

<4

<7

<4

<6

<5

<4

<3

<2

<1

<2

<4

<6

<4

<3

<2

<7

<9

<7

<9

<8

<6

<9

<8

< 10

<8

<9

< 11

< 10

<9

<6

<4

<3

<6

<9

<8

<9

<7

<8

<4

<3

<4

<3

<4

<5

<4

<5

<4

<3

<5

<6

<5

<6

<4

<2

<4

<5

<2

<3

<2

<6

<8

<7

<6

<5

<9

<8

< 10

<8

<9

< 10

<9

<8

<9

<8

<4

<3

<7

<9

<6

<8

<9

<8

<4

<5

<4

<3

<4

<3

<13

<3

<14

<4

<15

<3

<13

<4

<12

<3

<13

<3

<12

<3

<23

<5

<18

<3

<21

<5

<17

<3

<23

<4

<12

<5

<12

<5

<13

<4

<13

<4

<10

<4

<13

<2

<9

<1

<10

<1

<14

<4

<14

<4

<14

<4

<15

<4

<14

<4

<13

<4

<14

<4

<13

<2

<13

<2

<11

<2

<11

<2

<12

<2

<11

<2

<3

<4

<3

<4

<5

<4

<5

<4

<5

<4

<2

<3

<4

<5

<4

<2

<25

<8

<34

< 11

<30

< 10

<28

<9

<25

<8

<27

<7

<25

<8

<49

< 15

<38

< 12

<43

< 10

<32

< 13

< 44

< 12

<29

< 11

<34

<6

<31

< 10

<33

<9

<25

<7

<22

<6

<16

<5

<18

<6

<24

< 11

<31

<9

<32

< 10

<25

< 10

<30

<9

<29

<9

<30

< 10

<23

<7

<23

<7

<19

<6

<17

<5

<21

<6

<18

<5

TABLE B-II.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 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 05/26/09 10/05/09 05/26/09 10/05/09 05/26/09 10/05/09 05/26/09 10/05/09 05/26/09 10/05/09 05/26/09 10105/09 175 +/- 110

< 188

< 163

< 184 260 +/- 116

< 184 690 +/- 137

< 180 245 +/- 115

< 182 245 +/- 113

< 182 B-6

TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Be-7 PERIOD 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 SW-DN-101 SW-DN-102 SW-DN-103 SW-DN-104 SW-DN-105 SW-DN-106 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09

< 41

< 36

< 35

< 37

< 44

< 41 84

<4

<5

<12

<5

<8

<5

<8

< 15

<4

<33 90

<4

<5

<10

<5

<8

<5

<8

<13

<4 61

<3

<4

<9

<3

<8

<4

<6

<13

<3 27

<4

<9

<4

<9

<5

<8

<14

<4 75 +/-50 <5

<4

<12

<4

<9

<5

<9

<15

<4 82

<4

<11

<4

<7

<5

<9

<14

<4

<28

<4

<25

<4

<33

<5

<29

<4

<30

< 11

< 10

< 11

SVPLTR 10-0027, Annual Radiological Environmental Operating Report

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