Text

2011 Annual Radiological Environmental Operating Report
	ML12137A206
Person / Time
Site:	Dresden
Issue date:	05/11/2012
From:	Czufin D; Exelon Generation Co, Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	SVPLTR# 12-0025
	Download: ML12137A206 (135)
	v • d • e

Exelkn Exelon Generation Company, LLC www.exeloncorp.com Dresden Nuclear Power Station Nuclear 65oo North Dresden Road Morris, IL 60450-9765 May 11,2012 SVPLTR # 12-0025 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 2011 Annual Radiological Environmental Operating Report Enclosed is the Exelon Dresden Nuclear Power Station 2011 Annual Radiological Environmental Operating Report, submitted in accordance with Section 6.9.A.3 of the Unit 1 Dresden Nuclear Power Station Technical Specifications and Section 5.6.2, "Annual Radiological Environmental Operating Report," of the Units 2 and 3 Technical Specifications.

This report provides the results of the radiological environmental monitoring program for the 2011 calendar year.

In addition, Appendix F of the report contains the results of groundwater monitoring conducted in accordance with Exelon's Radiological Groundwater Protection Program, which'is a voluntary program implemented in 2006. This information is being reported in accordance with a nuclear industry initiative.

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

Respectfully, David M. Czufin q

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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 tp 4ý(Z1

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 2011 Prepared By Teledyne Brown Engineering Environmental Services Exel n Nuclear Dresden Nuclear Power Station Morris, IL 60450 May 2012

Intentionally left blank

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

1 I1. Introduction.............................................................................................................

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

3 B. Im plem entation of the Objectives..................................................................

3 I1l. Program Description................................................................................................

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

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

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

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

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

9 IV. Results and Discussion............................................................................................

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

9

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

9

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

10

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

11

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

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

11

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

11

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

11

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

12

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

13

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

13

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

13 C. Am bient G am m a Radiation.........................................................................

14 D. Land Use Survey..........................................................................................

14 E. Errata Data...................................................................................................

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

15

Appendices Appendix A Tables Table A-1 Appendix B Tables Table B-1 Table B-2 Fi-gures Figure B-1 Figure B-2 Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Table C-11.1 Table C-11.2 Radiological Environmental Monitoring Report Summary Radiological Environmental Monitoring Program Annual Summary for the Dresden Nuclear Power Station, 2011 Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2011 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2011 Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Locations, 2011 Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2011 Data Tables and Figures - Primary Laboratory Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

ii

Table C-111.1 Table C-IV.1 Table C-V. 1 Table C-V.2 Table C-V.3 Table C-VI.1 Table C-VII. 1 Table C-VII.2 Table C-VIII.1 Table C-IX.1 Table C-IX.2 Table C-IX.3 Figures Figure C-1 Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

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, 2011.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Quarterly TLD Results for Dresden Nuclear Power Station, 2011.

Mean Quarterly TLD Results for the Inner Ring, Outer Ring, Other and Control Locations for Dresden Nuclear Power Station, 2011.

Summary of the Ambient Dosimetry Program for Dresden Nuclear Power Station, 2011.

Surface Water - Gross Beta - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2011.

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

Collected in the Vicinity of DNPS, 2003 - 2011.

Surface Water - Gross Beta - Station D-21 Collected in the Vicinity of DNPS, 2007 - 2011.

Surface Water - Tritium - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2011.

Surface Water - Tritium - Station D-54 (C) and D-57 (C) Collected in the Vicinity of DNPS, 2003 - 2011.

Surface Water - Tritium - Station D-21 Collected in the Vicinity of DNPS, 2007 - 2011.

iii

Figure C-7 Figure C-8 Figure C-9 Figure C-10 Figure C-I 1 Figure C-12 Figure C-13 Figure C-14 Figure C-15 Ground Water - Tritium - Stations D-23 and D-35 Collected in the Vicinity of DNPS, 2000 - 2011.

Air Particulate - Gross Beta - Stations D-01 and D-02 Collected in the Vicinity of DNPS, 2000 - 2011.

Air Particulate - Gross Beta - Stations D-03 and D-04 Collected in the Vicinity of DNPS, 2000 - 2011.

Air Particulate - Gross Beta - Stations D-07 and D-12 (C) Collected in the Vicinity of DNPS, 2000 - 2011.

Air Particulate - Gross Beta - Stations D-45 and D-53 Collected in the Vicinity of DNPS, 2000 - 2011.

Air Particulate - Gross Beta - Stations D-08 and D-10 Collected in the Vicinity of DNPS, 2005 - 2011.

Air Particulate - Gross Beta - Stations D-13 and D-14 Collected in the Vicinity of DNPS, 2005 - 2011.

Air Particulate - Gross Beta - Stations D-55 and D-56 Collected in the Vicinity of DNPS, 2006 - 2011.

Air Particulate - Gross Beta - Station D-58 Collected in the Vicinity of DNPS, 2011.

Appendix D Tables Inter-Laboratory Comparison Program Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2011 Table D-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2011 Table D-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2011 Appendix E Appendix F Errata Data Annual Radiological Groundwater Protection Program Report (ARGPPR) iv

I.

Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Dresden Nuclear Power Station (DNPS) by Exelon covers the period 1 January 2011 through 31 December 2011. During that time period, 2,019 analyses were performed on 1,875 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.

On March 11, 2011 an earthquake off the Japanese islands produced a massive tsunami that caused a nuclear accident at four of the six Fukushima Daiichi reactors. In planning for the potential radioactive plume reaching the United States, Exelon Nuclear increased the sampling frequency and added additional analyses of select media from pathways that were expected to be the most sensitive to any increase in ambient radiation levels. Low level 1-131 analyses and gamma spectroscopy analyses were performed on air particulates, air iodine, and milk, as appropriate.

The resulting radioactive plume was first detected in the environs of Dresden Nuclear Power Station on March 18, 2011. The final date of positive detection was April 08, 2011. The radionuclide identified was Iodine-1 31. Maximum activity levels found by media were 115 E-3 pCi/m 3 for air iodine. Samples collected were compared to offsite control locations to verify that these positive detections were not attributable to licensed activities. All other radionuclides analyzed for were below MDL.

The radioactive half-life of 1-131 is about 8 days. This short half-life allowed the affects of this radioactive plume to subside over about 3 weeks. As of April 09, 2011 no further impacts from the Fukushima Daiichi accident was evident.

Surface water samples were analyzed for concentrations of gross beta, tritium and gamma emitting nuclides. Ground water samples were analyzed for concentrations of tritium and gamma emitting nuclides. No anthropogenic gamma emitting nuclides were detected. Gross beta and tritium activities detected were consistent with those detected in previous years.

Fish (commercially and recreationally important species), and sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish. Cesium-1 37 was detected in one sediment sample at a concentration consistent with levels observed in previous years. No plant-produced fission or activation products were found in sediment.

Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. Gross beta results at the indicator locations were consistent with those at the control location. No fission or activation products were detected.

High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity, with the exception of 36 samples which were positive for 1-131. These positive results are directly attributed to the Fukushima event in March 2011.

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.

II.

Introduction The Dresden Nuclear Power Station (DNPS), consisting of one retired reactor and two operating boiling water reactors owned and operated by Exelon Corporation, is located in Grundy County, Illinois. Unit No. 1 went critical in 1960 and was retired in 1978. Unit No. 2 went critical on 16 June 1970. Unit No. 3 went critical on 02 November 1971. The site is located in northern Illinois, approximately 12 miles southwest of Joliet, Illinois at the confluence of the Des Plaines and Kankakee Rivers where they form the Illinois River.

This report covers those analyses performed by Teledyne Brown Engineering (TBE), Mirion Technologies, and Environmental Inc. Midwest Laboratory (EIML) on samples collected during the period 1 January 2011 through 31 December 2011.

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.

Ill.

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 2011. Sample locations and descriptions can be found in Appendix B, Table B-1 and Figures B-1 and B-2. 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 (SW), ground water (GW), fish (FI),

and sediment (SS). Samples were collected from three surface water locations (D-21, D-52 and D-57) and composited for analysis. Control locations were D-52 and D-57. Samples were collected quarterly or more frequently from two well water locations (D-23 and D-35). All samples were collected in new unused plastic bottles, which were rinsed with source water prior to collection. Fish samples comprising the flesh of channel catfish, largemouth bass, common carp and freshwater drum were collected semiannually at two locations, D-28 and D-46 (Control).

Sediment samples composed of recently deposited substrate were collected at one location semiannually, D-27.

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate and airborne iodine (AP/I).

Airborne iodine and particulate samples were collected at fourteen 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, D-56, and D-58). 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.

Terrestrial Environment Milk (M) samples were collected biweekly at one control location (D-25) from March through October, and monthly from November through February. 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 (FL) 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 17 locations (D-58, D-101, D-102, D-103, D-104, D-105, D-106, D-107, D-108, D-109, D-110, D-111, D-112a, D-113, D-114, D-115 and D-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 13 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, D-56, and D-58).

The balance of one location (D-12) representing the control area.

Two TLDs - each comprised of two CaF2 and two LiF thermoluminescent phosphors enclosed in plastic - were placed at each location. The TLDs were exchanged quarterly and sent to Mirion Technologies for analysis.

B.

Sample Analysis This section describes the general analytical methodologies used by TBE and EIML to analyze the environmental samples for radioactivity for the DNPS REMP in 2011. The analytical procedures used by the laboratories are listed in Appendix B 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 Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity 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, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140, and La-140 were reported.

For fish, sediment, air particulate and milk 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.

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

D.

Program Exceptions For 2011 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 AP/I AP/l D-53 D-53 D-04 TLD D-205-1, D-205-2 01/07/11 - 01/14/11 01/14/11 - 01/21/11 01/28/11 - 02/04/11 02/04/11 03/11/11 - 03/18/11 04/15/11 - 04/22/11 04/15/11 - 04/22/11 Low reading of 166.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months due to work at substation.

Low reading of 144.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months due to work at substation.

No apparent reason for low reading of 150.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; possibly due to power outage from station.

TLDs moved to fence across road; utility poles TLDs were mounted on were removed.

No apparent reason for low reading of 162.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Low reading of 158.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months from power outage due to storms in the area.

Low reading of 144.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months from power outage due to storms in the area.

AP/I AP/I D-03 D-08 AP/I D-10 Table D-1 LISTING OF SAMPLE ANOMALIES (continued)

Sample Location Collection Reason Type Code Date AP/I D-12 AP/I AP/I AP/I AP/I AP/l AP/l SW D-1 0 D-10 D-12 D-45 D-58 D-03 D-21 04/15/11 - 04/22/11 04/22/11 - 04/29/11 05/06/11 - 05/13/11 05/06/11 - 05/13/11 05/06/11 - 05/13/11 05/27/11 - 06/03/11 06/03/11 - 06/10/11 07/01/11 08/05/11 - 08/12/11 08/19/11 - 08/26/11 08/19/11 - 08/26/11 09/30/11 11/25/11 11/25/11 Low reading of 149.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months from power outage due to storms in the area.

No apparent reason for low reading of 125.0 hours0 days 0 hours 0 weeks 0 months .

Air particulate filter shifted during collection period.

No apparent reason for low reading of 166.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

No apparent reason for low reading of 164.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

Low reading of 105.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months due to recent startup.

No apparent reason for low reading of 148.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Grab sample collected on 07/01/11; compositor back in service on 07/08/11.

Estimated run time of 161.0 hours0 days 0 hours 0 weeks 0 months ; timer replaced.

Estimated run time of 168.0 hours0 days 0 hours 0 weeks 0 months ; timer replaced.

Low reading of 15.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to blown fuse; fuse replaced.

Compositor not circulating, collector will check next week.

No electricity to unit; collector will check next week.

AP/I AP/l AP/I SW SW SW D-07 D-45 D-53 D-21 D-21 D-57 Table D-1 LISTING OF SAMPLE ANOMALIES (continued)

Sample Location Collection Reason Type Code Date AP/I D-12 12/02/11 - 12/09/11 No apparent reason for low reading of 102.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .

Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date There were no missed samples in 2011.

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 Air particulate/iodine station D-58 was added to the REMP program on May 27, 2011.

TLD locations D-58-1 and D-58-2 were added to the REMP program in the first quarter of 2011.

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 4.4 to 12.6 pCi/l. Concentrations detected were consistent with those detected in previous years (Figures C-1, C-2, and C-3, Appendix C).

Tritium Quarterly composites from all locations were analyzed for tritium activity (Table C-1.2, Appendix C). One sample at control station D-57 was positive for tritium at a concentration of 256 pCi/L.

Concentrations detected were consistent with those detected in previous years (Figures C-4, C-5, and C-6, Appendix C).

Gamma Spectrometry Monthly composites from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No nuclides were detected, and all required LLDs were met.

2.

Ground Water Quarterly or more frequent grab samples were collected at two locations (D-23 and D-35). These locations could be affected by Dresden's effluent releases and by sources upstream on the Kankakee River. The following analyses were performed:

Tritium All samples were analyzed for tritium activity (Table C-11.1, Appendix C). Tritium was detected in 11 of 16 samples. The concentrations ranged from 194 to 387 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-I1.2, 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 2,360 to 4,280 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-1 37 was detected in one sample at a concentrationof 51 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 14 locations on a weekly basis. The 14 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, D-56 and D-58), Far-field samplers between 4 and 10 km from the site (D-08, D-10, D-14 and D-55) and the Control sampler between 10 and 30 km from the site (D-12). The following analyses were performed:

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

Detectable gross beta activity was observed at all locations.

Comparison of results among the four groups aid in determining the effects, if any, resulting from the operation of DNPS. The results from the On-Site locations ranged from 6 to 42 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m 3. The results from the Near-Field locations ranged from 7 to 44 E-3 pCi/mi3 with a mean of 21 E-3 pCi/m 3. The results from the Far-Field locations ranged from 7 to 53 E-3 pCi/m 3 with a mean of 21 E-3 pCi/m 3. The results from the Control location ranged from 8 to 43 E-3 pCi/m 3 with a mean of 21 E-3 pCi/m 3. Comparison of the 2011 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 2011 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 50 of 55 samples and ranged from 38.5 to 151 E-3 pCi/m 3. K-40 was also detected in 2 of 55 samples.

The concentration ranged from 14.5 to 17.2 E-3 pCi/m 3.

No anthropogenic nuclides were detected, and all required LLDs were met. Additional sampling occurred in the weeks immediately following the Fukushima event in 2011.

All results were less than the MDC except for two samples that were positive for Be-7. The concentrations ranged from 259 to 261 E-03 pCi/m 3 These samples were consistent with historical quarterly results. All other nuclides were less than the MDC.

b.

Airborne Iodine Continuous air samples were collected from 14 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, D-56 and D-58) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). All results were less than the MDC except for 36 samples that were positive for 1-131.

These positive results are directly attributed to the Fukushima event in March of 2011.

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 March through October and monthly November through February. 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 1,130 to 1,420 pCi/l.

No other nuclides were detected, and all required LLDs were met. Additional sampling occurred in the weeks following the Fukushima event. All results were less than the MDC with the exception of naturally occurring K-40. The concentrations ranged from 1,210 to 1,490 pCi/I.

b.

Food Products Food product samples were collected at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) when available. Four locations, (D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) could be affected by Dresden's effluent releases. The following analysis was performed:

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-VIII.1, Appendix C). Only naturally occurring nuclides were detected, and all required LLDs were met.

C.

Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Mirion Technologies 110 Environmental (CaF2 and LiF) thermoluminescent dosimeters. Forty-six 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 14 to 38 mR/quarter. A comparison of the Inner Ring, Outer Ring, and Other locations' data to the Control Location data, indicate that the ambient gamma radiation levels from the Control location (D-12-01, D-12-02) were comparable.

D.

Land Use Survey A Land Use Survey conducted on 03 August 2011 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 2011.

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, 14 out of 18 analytes met the specified acceptance criteria. Four analytes did not meet the specified acceptance criteria for the following reason:

1. Teledyne Brown Engineering's Analytics March 2011 Cr-51 in milk result of 398 pCi/L was higher than the known value of 298 pCi/L, resulting in a found to known ratio of 1.34. NCR 11-13 was initiated to investigate this failure. There was a slightly high bias in all the gamma activities. The June gamma results in milk did not show a high bias. No further action was required.

2. Teledyne Brown Engineering's ERA May 2011 Gross Alpha in water result of 64.1 pCi/L was higher than the known value of 50.1 pCi/L, which exceeded the upper control limit of 62.9 pCi/L. NCR 11-08 was initiated to investigate this failure. The solids on the planchet exceeded 100 mg, which was beyond the range of the efficiency curve.

Teledyne Brown Engineering's MAPEP March 2011 Gross Alpha in air particulate result of 0.101 Bq/sample was lower than the known value of 0.659 Bq/sample, which exceeded the lower control limit of 0.198 Bq/sample. NCR 11-11 was initiated to investigate this failure. The air particulate filter was counted on the wrong side.

3. Teledyne Brown Engineering's ERA November 2011 Sr-89 in water result of 81.0 pCi/L was higher than the known value of 69.7 pCi/L, which exceeded the upper control limit of 77.9 pCi/L. NCR 11-16 was initiated to investigate this failure. The TBE reported value to known ratio of 1.16 fell within the acceptable range of +/- 20%, which TBE considers acceptable.

4. Teledyne Brown Engineering's MAPEP March 2011 Sr-90 in soil, air particulate and vegetation were non-reports that were evaluated as failed. NCR 11-11 was initiated to investigate these failures.

MAPEP evaluated the non-reports as failed due to not reporting a previously reported analyte.

For the secondary laboratory, Environmental, Inc., 12 out of 14 analytes met the specified acceptance criteria. Two analytes did not meet the specified acceptance criteria for the following reason:

1. Environmental Inc.'s ERA October 2011 Cs-1 34 in water result of 38.8 pCi/L was higher than the known value of 33.4 pCi/L, which exceeded the upper control limit of 36.7 pCi/L. The sample was reanalyzed. The reanalyzed result of 32.9 was acceptable.

2. Environmental Inc.'s MAPEP February 2011 Sr-90 in air particulate result of 1.89 Bq/sample was higher than the known value of 1.36 Bq/sample, which exceeded the upper control limit of 1.77 Bq/sample. No errors were found in the calculation or procedure.

The reanalyzed result of 1.73 Bq/sample was acceptable.

Environmental Inc.'s MAPEP August 2011 Sr-90 in soil result of 219.4 Bq/kg, less than the known value of 320 Bq/kg, was below the lower control limit of 224 Bq/kg. The sample was reanalyzed in triplicate through a strontium column. The reanalyzed result of 304.2 Bq/kg was acceptable.

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

Intentionally left blank

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2011 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

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

ANNUAL 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M).

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS SURFACE WATER (PCI/LITER)

GR-B H-3 36 12 36 4

8.7 8.4 (12/12)

(24/24)

(6.0/12.1)

(4.4/12.6) 9.8 (12/12)

(6.8/12.6)

D-52 CONTROL DESPLAINES RIVER - UPSTREAM 1.1 MILES ESE OF SITE 0

0 2000

<LLD 15

<LLD GAMMA MN-54 CO-58 15

<LLD FE-59 30

<LLD CO-60 15

<LLD ZN-65 30

<LLD NB-95 15

<LLD

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES 256 (1/8)

<LLD

<LLD 256 (1/4) 0 0

0 0

D-57 CONTROL KANKAKEE RIVER AT WILL ROAD(CONTROL) 2.0 MILES SE OF SITE 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, 2011 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

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

ANNUAL 2011 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)

I'-

ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 30

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD

<LLD 0

0 0

GROUND WATER (PCI/LITER)

H-3 16 16 2000 288 (11/16)

(194/387)

NA 288 (11/12)

(194/387)

D-23 INDICATOR THORSEN WELL 0.7 MILES S OF SITE 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, 2011 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

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

ANNUAL 2011 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, 2011 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

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

ANNUAL 2011 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)

FISH (PCI/KG WET)

CS-137 BA-140 LA-140 GAMMA MN-54 CO-58 FE-59 CO-60 8

18

<LLD 60

<LLD 15

<LLD 130

<LLD 260

<LLD 130

<LLD 260

<LLD NA NA NA 0

0 0

<LLD

<LLD 0

0 0

ZN-65

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, 2011 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

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

ANNUAL 2011 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

0 2

NA NA 0

CO-58

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, 2011 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

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

ANNUAL 2011 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)

ON FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 NA

<LLD NA

<LLD 150

<LLD 180 51 (1/2)

NA

<LLD NA NA NA NA NA NA 0

0 0

0 NA 51 (1/2)

D-27 INDICATOR DRESDEN LOCK AND DAM - DOWNSTREAM 0.8 MILES NW OF SITE NA

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, 2011 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

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

ANNUAL 2011 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)

LA-140 AIR PARTICULATE (E-3 PCI/CU.METER)

GR-B 707 GAMMA MN-54 55 CO-58 FE-59 CO-60 ZN-65 NB-95 NA

<LLD 10 21 (650/655)

(6/53)

NA

<LLD NA

<LLD 21 (52/52)

(8/43)

<LLD

<LLD 22 (51/52)

(8/46)

NA 0

0 D-10 INDICATOR GOOSE LAKE VILLAGE 3.5 MILES SSW OF SITE 0

0 0

<LLD

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2011 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

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

ANNUAL 2011 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)

ZR-95 00 CS-134 CS-137 BA-140 LA-140 GAMMA 1-131 NA

<LLD 50

<LLD 60

<LLD NA

<LLD

<LLD 0

0 0

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

MILK (PCI/LITER) 707 70 62 56 (33/655)

(3/52)

(32/115)

(46/73) 76 (2/52)

(56/96)

D-14 INDICATOR CHANNAHON 3.7 MILES NE OF SITE 0

0 1-131 19 NA

<LLD

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2011 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

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

ANNUAL 2011 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)

GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 19 NA NA NA NA NA NA NA NA NA NA NA NA NA NA 15 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, 2011 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

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

ANNUAL 2011 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)

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

<LLD

<LLD 0

0 0

0 VEGETATION (PCIiKG WET) 10 CO-58 FE-59 CO-60 ZN-65 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-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2011 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

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

ANNUAL 2011 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)

NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 NA

<LLD NA

<LLD 60

<LLD 80

<LLD NA

<LLD NA 22 (360/360)

(14/38)

<LLD

<LLD 20 (8/8)

(16/24) 0 0

0 0

DIRECT RADIATION (MILLI-ROENTGEN/QTR-)

TLD-QUARTERLY 368 27 (4/4)

(22/33)

D-201-1 INDICATOR 4.8 MILES N

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

Intentionally left blank

APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS

Intentionally left blank

TABLE B-1:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2011 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 at Will Road, Upstream (control)

Kankakee River at Will Road (control)

B.

Ground/Well Water D-23 D-35 Thorsen Well, Dresden Road (indicator)

Dresden Lock and Dam (indicator)

C.

Milk - bi-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 D-58 Onsite Station 1 (indicator)

Onsite Station 2 (indicator)

Onsite Station 3 (indicator)

Collins Road, on Station property(indicator)

Clay Products, Dresden Road (indicator)

Jugtown Road, Prairie Parks (indicator)

Goose Lake Road, Goose Lake Village (indicator)

Quarry Road, Lisbon (control)

Center Street, Channahon (indicator)

McKinley Woods Road, Channahon (indicator)

Will Road at Hollyhock (indicator)

Ridge Road, Minooka (indicator)

Will Road, Wildfeather (indicator)

Will Road, Marina (indicator)

Dresden Pool of Illinois River, Downstream (indicator)

DesPlaines River, Upstream (control) 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 1.1 miles ESE 0.9 miles NNW 1.2 miles ESE 0.8 miles NW 2.8 miles NE 3.2 miles SSE 3.9 miles SSW 1.6 miles NNW 12.8 miles ENE E.

Fish D-28 D-46 F.

Sediment D-27 Illinois River at Dresden Lock and Dam, Downstream (indicator)

G.

Vegetation Quadrant 1 Quadrant 2 Quadrant 3 Quadrant 4 Control Chris Locknar Robert Pagliano Jim Bloom J.D. Carmichael Glasscock Farm B-1

TABLE B-I:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2011 Location Location Description Distance & Direction From Site H.

Environmental Dosimetry - TLD Inner Ring D-58-1 and -2 D-101-1 and -2 D-102-1 and -2 D-103-1 and -2 D-104-1 and -2 D-105-1 and -2 D-106-1 and -2 D-107-1 and -2 D-108-1 and -2 D-109-1 and -2 D-110-3 and -4 D-111-1 and -2 D-112A-1 and-2 D-113-1 and -2 D-114-1 and -2 D-115-1 and-2 D-116-1 and -2 Outer Ring D-201-1 and -2 D-202-1 and -2 D-203-1 and -2 D-204-1 and -2 D-205-1 and -2 D-206-1 and -2 D-207-1 and -2 D-208-1 and -2 D-209-1 and -2 D-210-1 and -2 D-211-1 and -2 D-212-3 and -4 D-213-1 and -2 D-214-1 and -2 D-215-1 and -2 D-216-1 and -2 1.1 miles ESE 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 Onsite 1 D-02-1 and -2 Onsite 2 D-03-1 and -2 Onsite 3 D-04-1 and -2 Collins Road, on Station property D-07-1 and -2 Clay Products, Dresden Road D-08-1 and -2 Jugtown Road, Prairie Parks D-10-1 and -2 Goose Lake Road, Goose Lake Village D-14-1 and -2 Center Street, Channahon D-45-1 and -2 McKinley Woods Road, Channahon D-53-1 and -2 Will Road at Hollyhock D-55-1 and -2 Ridge Road, Minooka D-56-1 and -2 Will 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, 2011 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, 2011 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Dredging Spoils Gamma Spectroscopy Annual grab samples if EIML-SPM-1, Environmental Incorporated 500 grams (dry)

TBE, TBE-2007 Gamma emitting dredging occurred Midwest Laboratory Sampling Procedures radioisotope analysis within 1 mile of Dresden Manual Station during the year.

Air Particulates Gross Beta One-week of continuous EIML-SPM-1, Environmental Incorporated 1 filter (approximately TBE, TBE-2008 Gross Alpha and/or air sampling through Midwest Laboratory Sampling Procedures 280 cubic meters gross beta activity in various matrices glass fiber filter paper Manual weekly)

Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting each station radioisotope analysis Env. Inc., AP-03 Procedure for compositing air particulate filters for gamma spectroscopic analysis Air Iodine Gamma Spectroscopy One-or two-week EIML-SPM-1, Environmental Incorporated 1 filter (approximately TBE, TBE-2007 Gamma emitting composite of continuous Midwest Laboratory Sampling Procedures 280 cubic meters radioisotope analysis air sampling through Manual weekly) charcoal filter Milk 1-131 Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2012 Radioiodine in various May through October.

Midwest Laboratory Sampling Procedures matrices Monthly all other times Manual Milk Gamma Spectroscopy Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting May through October.

Midwest Laboratory Sampling Procedures radioisotope analysis Monthly all other times Manual Food Products Gamma Spectroscopy Annual grab samples.

EIML-SPM-1, Environmental Incorporated 1000 grams TBE, TBE-2007 Gamma emitting Midwest Laboratory Sampling Procedures radioisotope analysis Manual TLD Thermoluminescence Quarterly TLDs EIML-SPM-1, Environmental Incorporated 2 dosimeters Mirion Technologies Dosimetry comprised of two Mirion Midwest Laboratory Sampling Procedures Technologies TLDs, Manual with two CaF 2 elements and two LiF elements in each TLD.

104.1 104" 114.1 115-2, 18"-1 105r4 113S.:

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iE saftnen m oos am~LO IUALV ininue5TO~M UNM1, 2. A3 WAIM&VL 8~LCCAM Figure B-1 Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Location, 2011 B-5

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10 I

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W Loadan 1w UZm0 Figure B-2 Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2011 B-6

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

Intentionally left blank

TABLE C-1.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD D-21 D-52 D-57 01/07/11 02104/11 03/04/11 04/01/11 05/06/11 05/27/11 07/01/11 08/05/11 09/02/11 10/07/11 11/04/11 12/02/11

- 01/28/11

- 02/25/11

- 03/25/11

- 04/29/11

- 05/27/11

- 06/24/11

- 07/29/11

- 08/26/11

- 09/30/11

- 10/28/11

- 11/25/11

- 12/30/11 7.9 7.1 7.1 9.9 12.1 8.3 9.8 7.5 9.5 7.3 11.9 6.0

+/- 3.6

+/- 2.4

+/- 3.0

+/- 3.2

+/- 2.9

+/- 2.6

+/- 2.9

+/- 1.7

+/- 2.0

+/- 3.2

+/- 2.0 10.0 12.5 9.0 9.6 10.8 7.7 (1) 10.8 6.8 (1) 8.8 11.9 (1) 12.6 7.4

+/- 3.8

+/- 3.0

+/- 3.4

+/- 3.3

+/- 2.9

+/- 2.6

+/- 2.9

+/- 1.5

+/- 2.3

+/- 3.2 (1)

+/- 2.1 11.6 +/- 3.4 5.0 +/- 2.1 4.5 +/- 2.0 7.1 +/- 3.1 6.5 +/- 2.9 11.7 +/- 2.9 8.1 +/- 2.5 5.5 +/- 2.6 5.2 +/- 1.4 4.4 +/- 1.9 8.2 +/- 2.9 6.6 +/- 2.1 MEAN 8.7 +/- 3.9 9.8 +/- 3.9 7.0 +/- 5.0 TABLE C-I.2 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD D-21 D-52 D-57 U1/U/i11 - 03i2,11 04/01/11 - 06/24/11 07/01/11 - 09/30/11 10/07/11 - 12/30/11

< 166

< 167

< 189

< 182

< 174

< 166

< 191

< 183 (1)

< 165 256 +/- 106

< 189

< 182 (1)

(1)

MEAN (1) SEE PROGRAM EXCPETIONS SECTION FOR EXPLANATION C-1

TABLE C-l.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD D-21 12/31/10 - 01/28/

01/28/11 - 02/25/

02/25/11 - 03/25/

03125/11 - 04/29/

04/29/11 - 05/271 05/27111 - 06/24/

06/24/11 - 07/29f 07/29/11 - 08/26 08/26/11 - 09/30/

09/30/11 - 10/28/

10/28/11 - 11/25/

11/25/11 - 12/30/

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

/11

,/11

'/11

'111

/1 1

/11

'/11

'111

/11

'111

<5

<2

<4

<1

<2

<4 (1) < 8

<4 (1) <4

<5 (1) < 6

<3 MEAN

<5

<2

<4

<1

<3

<5

<7

<5

<4

<6

<4

<2

<4

<1

<3

<6

<5

<4

<5

<3

< 13

<4

<9

<2

<6

13

< 14

< 10

10

<9

< 11

<8

<9

<3

<8

<3

<7

14

< 15

<9

<11

<12

<11

<7

<5

<2

<4

<1

<3

<5

<7

<4

<5

<4

<6

<2

<3

<1

<3

<7

<6

<4

<5

<3

< 12

<4

<9

<1

<5

<10

< 15

<7

<9

<11

< 12

<8

<9

<3

<6

<2

<5

<11

<5

<11

<14

<9

<6

<5

<2

<4

<1

<3

<6

< 10

<4

<5

<6

<4

<5

<2

<4

<1

<3

<6

<7

<4

<6

<8

<7

<3

<8

<3

<7

<2

<5

<9

< 13

<8

<9

< 10

<6

<8

<3

<6

<2

<5

<9

< 11

<7

<10

<9

<5

< 13

<6

< 15

< 11

<11

<14

< 13

< 12

<7

<13

< 11

<9

<13

<5

< 13

< 15

13

15

10

<10

10

15

<10

<9

<4

<2

<5

<1

<2

<5

<8

<5

<4

<5

<3

<4

<1

<3

<1

<3

<6

<5

<4

<5

<3

<5

<2

<4

<1

<3

<5

<8

<4

<5

<6

<4

<1

<3

<1

<3

<6

<4

<5

<6

<3

<13

< 32

14

20

< 34

< 38

29

21

27

28

22

29

10

27

<17

< 27

38

< 27

< 26

23

< 37

24

< 19

<10

<4

< 12

<4

<7

< 10

<11

<9

<6

<8

<9

<8

<10

<3

<7

<4

<8

<14

<8

<6

<8

< 12

<8

<5 D-52 01/07/11 02/04/11 03/04/11 04/01111 05/06/11 06/03/11 07/01/11 08/05/11 09/02/11 10/07/11 11/04/11 12/02/11 01/28/11 02/25/11 03/25/11 04/29/11 05/27/11 06/24/11 07/29/11 08/26/11 09/30/11 10/28/11 11/25/11 12/30/11

<5

<1

<3

<1

<3

<6

<5

<3

<5

<4

<3 MEAN

TABLE C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 D-57 12/31/10 01/28/11 02/25/11 03125111 04/29/11 05/27/11 06/24/11 07/29/11 08/26/11 09/30/11 10/28/11 11/25/11 MEAN

- 01/28/11

- 02/25/11

- 03/25/11

- 04/29/11

- 05/27/11

- 06/24/11

- 07/29/11

- 08/26/11

- 09/30/11

- 10/28/11

- 11/25/11

- 12/30/11

<5

<1

<3

<1

<3

<6

<4

<5

<6 (1) < 5

<3

<4

<1

<4

<1

<3

<6

<5

<4

<6

<5

<6

<3

<8

<3

<7

<2

<7

< 11 11

<9

< 11

< 13 11

<7

<4

<1

<4

<1

<3

<6

<7

<4

<5

<6

<3

<9

<3

<7

<1

<6

13

12

<8

<9

<11

<6

<5

<2

<4

<1

<4

<5

<6

<4

<5

<6

<5

<4

<8

<3

<7

<1

<6

< 8

<12

<7

< 10

<9

<10

<6

<14

<5

<15

<10

< 14

14

<10

< 11

< 14

15

<9

<8

<4

<1

<3

<1

<3

<5

<6

<4

<6

<4

<3

<6

<2

<4

<1

<3

<5

'6

<4

<5

<6

<5

<3

< 29

<11

29

13

28

< 33

30

27

< 37

<34

28

20

<7

<3

<8

<4

<7

< 13

<8

< 11

< 10

<7

<6

TABLE C-I1.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD D-23 D-35 01/14/11 02/11/11 03/11/11 04/15/11 05/13/11 06/10/11 07/15/11 08/12/11 09/09/11 10/14111 11/11/11 12/09/11

- 01/14111

- 02/11/11

- 03/11/11

- 04115/11

- 05/13/11

- 06/10/11

- 07/15/11

- 08/12/11

- 09/09/11

- 10/14111

- 11/11/11

- 12/09/11 325 232 310 317 258 253 262

< 193 387 386 194 246

+/- 110

+/- 109

+/- 121

+/- 127

+/- 128

+/- 117

+/- 135

+/- 138

+/- 134

+/- 114

+/- 133

153

< 178

< 191

< 187 MEAN 288 +/- 124 C-4

TABLES C-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-137 Ba-140 La-140 I

D-23 01/14/11 02/11/11 03/11/11 04/15/11 05/13/11 06/10/11 07/15/11 08/12/11 09/09/11 10/14/11 11/11/11 12/09/11 MEAN D-35 01/14/11 04/15/11 07/15/11 10/14/11

- 01/14/11

- 02/11/11

- 03/11/11

- 04/15/11

- 05/13/11

- 06/10/11

- 07/15/11

- 08/12/11

- 09/09/11

- 10/14/11

- li/li/li

- 12/09/11

- 01/14/11

- 04/15/11

- 07/15/11

- 10/14/11

<4

<3

<2

<1

<2

<6

<5

<4

<5

<2

<1

<7

<5

<3

<2

<1

<2

<6

<7

<6

<4

<5

<2

<7

<4

<9

<6

<5

<3

<5

< 13

< 12

<9

< 12

<3

< 14

< 12

<4

<2

<1

<2

<6

<7

<8

<5

<4

<6

<2

<1

<5

<3

<6

<4

<3

<2

<3

< 10

< 13

< 10

<7

< 10

<4

<2

< 12

<9

<4

<3

<1

<.1

<2

<6

<7

<6

<4

<7

<2

<1

<7

<6

<7

<5

<4

<3

<2

<3

<11

< 10

<8

< 11

<3

<2

< 11

<6

< 13

< 12

<9

<15

< 15

<15

<8

< 15

< 10

< 15

<8

< 11

< 14

< 15

<4

<3

<2

<1

<2

<6

<5

<6

<4

<3

<5

<2

<1

<5

<4

<3

<2

<1

<2

<5

<7

<6

<4

<6

<2

<1

<5

< 28

< 27

< 22

< 16

< 18

< 21

< 31

< 36

< 27

< 30

< 21

< 31

< 14

< 17

< 35

< 32

<9

<8

<7

<5

<6

<8

< 10

<7

< 11

<3

<5

< 12

<8 MEAN

TABLE C-1I1.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD SITE D-28 Freshwater Drum 05/11/11

< 54

< 77

< 170

< 64

< 158

< 99

< 137

< 80

< 57

< 1160

< 342 Largemouth Bass 05/11/11

< 68

< 78

< 183

< 58

< 132

< 74

< 141

< 54

< 59

< 1180

< 320 Common Carp 10/27/11

< 73

< 80

< 183

< 88

< 174

< 105

< 147

< 75

< 56

< 757

< 263 Largemouth Bass 10/27/11

< 57

< 81

< 170

< 83

< 128

< 70

< 92

< 63

< 60

< 709

< 185 MEAN D-46 Channel Catfish 05/11/11

< 64

< 89

< 209

< 58

< 126

< 92 Largemouth Bass 05/11/11

< 52

< 63

< 94

< 38

< 108

< 60 Common Carp 10/27/11

< 82

< 80

< 187

< 75

< 173

< 88 Largemouth Bass 10/27/11

< 87

< 95

< 192

< 79

< 179

< 90 C-)

< 133

< 57

< 107

< 49

< 156

< 78

< 139

< 69

<62

< 1330

< 372

< 43

< 791

< 338

< 77

< 815

< 277

<89

< 829

< 229 MEAN

TABLE C-IV.1 SITE COLLECTION PERIOD D-27 05/13/11 10/14/11 MEAN CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PC/KG DRY +/- 2 SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-1 34 Cs-137

< 80

< 90

< 226

< 92

< 185

< 100

< 180

< 57

< 89

< 49

< 46

< 105

< 58

< 123

< 57

< 95

<44 51 +/-:4 Ba-140

< 1410 4

< 287 La-140

< 356

< 98

....j

TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD GROUP I I

GROUP 11 0-01 D-02 D-03 D-04 0-07 D-45 D-53 D-56 D-58 12/31/10 01/07/111 01/14/11 01/21/111 01/28/11 02/04/11 02/11/11 02/18/11 02/25111 03/04/11 03/11/11 03/18/11 03/25/11 04101/111 04/08/11 04/15/11 04/22/11 04/29/11 05/06/11 05/13/11 05/20/11 05/27/11 06/03/11 06/10/11 06/17/11 06/24/11 07/01/11 07/08/11 07/15/11 07/22/11 07/29/11 08/05/11 08/12/11 08/19/11 08/26/11 09/02/11 09/09/11 09/16/11 09/23/11 09/30/11 10/07/11 10/14/11 10/21/11 10/28/11 11/04/1 1 11/11/11 1 1/1 8/11 11/25/1 1 12/02/1 1 12/09/11 12/16/11 12/23/11

-01/07/11

-01/14/111

-01/21/11

-01/28/111

-02/04/11

-02/11/11

-02/18/11

-02/25/11

-03/04/11

-03/11/11

-03/18/11

-03/25/11

-04/01/11

- 04/08/11

-04/15/11

-04/22/11

-04/29/11

-05/06/11

-05/13/11

-05/20/11

-05/27/11

-06/03/11

-06/10/11

-06/17/111

-06/24/11

-07/01/11

-07/08/111

-07/15/11

-07/22/11

-07/29/11

-08/05/11

-08/12/11

-08/19/11

-08/26/11

-09/02/11

-09/09/11

-09/16/11

-09/23/11

-09/30/11

-10/07/11

-10/14/11

-10/21/11

-10/28/11

-11/04/11

-11/11/11

-11/18/11

-11/25/11

-12/02/11

-12/09/11

-12/16/11

-12/23/11

-12/30/11 33 +/- 6 17 +/- 4 31 +/- 5 33 +/- 5 17 +/-5 23 +/-5 20 +/-4 13 +/-4 19 +/-4 16 +/-4 20 +/-5 31 +/-6 41 +/-6 19 t 5 19 +/- 4 15 +/- 4 12 +/-4 14 +/-4 13 +/-5

<6 12 +/-4 11 +/-4 22 +/-5 9+/-5 9+/-4 12 +/-4 20 +/-5 18 +/-5 22 +/-5 16 +/-4 26 +/-6 16 +/-5 16 +/-5 24 +/-6 29 +/-6 20 +/-5 22 +/-5 20 +/-4 16 +/-4 23 +/-5 35 +/-6 11 +/-4 30 t 5 30 +/- 5 17 +/- 5 25 +/- 5 19 +/- 5 18 +/- 4 21 +/- 5 27 +/- 5 23 +/- 5 18 +/- 4 39 +/-6 21 5

34 +/-5 32 +/-5 19 +/-5 26 +/-5 19 +/-4 14 +/-4 20 +/-4 13 +/-4 19 +/-5 28 +/-6 35 +/-5 14 t 5 14 +/- 4 16 +/- 4 7+/-4 8+/-4 11 +/-5 8+/-4 11 +/-4 11 +/-4 20 +/-4 10 +/-4 11 +/-4 13 +/-4 19 +/-5 17 5

21 +/-5 17 +/-4 26 +/-6 21 +/-5 19 +/-5 21 +/-5 33 +/-6 19 +/-4 19 +/-5 17 +/-4 15 +/-4 21 +/-5 31 +/-5 11 +/-4 28 +/-5 23 +/-5 16 +/-5 30 +/-5 22 +/-5 18 +/-4 22 +/-5 27 5

33 +/-5 22 +/-4 35 +/-6 21 +/-5 30 +/-5 36 +/-6 19 +/-5 21 +/-4 18 +/-4 10 +/-4 18 +/-4 12 +/- 4 21 +/- 5 24 +/-5 42 +/-6 22+/-t5 19 +/- 4 13 +/- 4 8+/-4 9+/-4 6+/-4

<6 10 t 4 16 +/- 5 21 +/- 5 12 +/- 5 8+/-4 16 +/-4 13 +/-5 15 5

15 +/-5 17 +/-4 28 t 6 15 +/- 5 17 +/- 5 18 +/- 5 26 +/- 5 21 +/- 5 15 +/- 4 17 +/- 4 16 +/- 4 27 +/- 5 41 +/-6 10 +/-4 23 5

22 +/-5 17 +/-5 25 +/-5 19 +/-5 14 +/-4 24 +/-5 26 +/-5 26 +/-5 18 +/-4 42 +/-6 22 +/-5 36 +/-5 31 +/-5 19 +/-6 24 +/-5 24 +/-5 14 +/-4 23 +/-5 13 +/-4 (1) 22 +/-5 31 +/-6 35 +/-5 22 +/-5 18 +/- 4 12 +/- 4 10 +/- 4 10 +/- 4 10 +/- 4

< 6 11 +/-4 13 +/-4 (1) 20 +/-4 13 +/-5 9+/-4 16 +/-4 19 +/-5 14 +/-5 17 +/-5 19 +/-4 20 +/-5 22 +/-5 20 +/-5 23 +/-5 28 +/-5 17 +/-4 16 +/-4 22 +/-4 15 +/-4 24 +/-5 37 +/-6 11 t+/-4 26 +/- 5 23 +/- 5 17 +/- 5 23 +/- 5 15 +/-5 19 +/-4 31 +/-6 35 +/-5 33 +/-5 20 +/-4 43 +/-6 19 +/-4 25 +/-5 28 +/-5 (1) 17 +/-5 22 t 5 20 +/- 4 15 +/- 4 20 +/- 5 15 +/- 4 22 t 5 28 +/-5 40 +/-6 21 +/-5 16 +/-4 13 +/-4 10 +/-4 11 +/-4 13 +/-4 10 +/-5 14 +/-4 17 +/-5 19 +/-4 11 +/-5 13 +/-4 16 +/-4 18 6

13 5

19 +/-5 18 +/-4 24 t 5 18 +/- 5 16 +/- 5 19 +/- 5 29 +/- 6 14 +/- 4 16 +/- 4 17 +/- 4 16 +/- 4 24 +/- 5 42 +/- 6 14 +/- 4 31 +/- 6 24 +/- 5 19 +/-5 27 +/-5 17 +/-5 15 +/-4 27 +/-5 28 +/-5 32 +/-5 23 +/-4 43 t 6 19 +/- 4 32 +/- 5 32 +/- 5 27 +/- 6 22 t 5 22 +/- 5 12 +/- 4 22 +/-5 17 +/-4 13 +/-5 30 +/-6 41 +/-6 23 +/- 5 16 +/- 4 11 +/-4 11 +/-4 11 +/-4 15 +/-5 8+/-4 13 +/-4 14 +/-5 24 +/-4 14 +/-5 10 +/-4 17 +/-4 18 +/-5 21 +/-5 16 +/-5 18 +/-5 24 +/-6 (1) 22 +/-6 18 +/-5 27 +/-6 27 +/-5 20 +/- 5 18 +/- 5 23 +/- 4 16 +/- 4 23 +/- 5 43 +/- 6 10 +/-4 26 +/-5 24 +/-5 21 +/-5 28 +/-5 16 +/-5 23 +/-5 28 +/- 6 24 +/- 4 26 +/- 5 26 +/- 5 44 +/-6 44+/- 6 18 +/-4 (1) 19+/- 4 31 +/-6 (1) 35+/- 5 33 +/-5 27+/- 5 17 +/-5 19 +/-5 21 +/-4 24+/- 5 19+/-4 19+/-4 10+/-4 13+/-4 19+/-4 18+/-4 11+/-4 12+/-4 24+/-6 20+/-5 30+/-6 23+/-5 42+/-6 44+/-6 21+/-5 17+/-5 15 +/-4 16+/-4 10 +/-4 12+/-4 8 +/-4 12+/-4 13+/-4 11+/-4 14+/-5 12+/-4 9+/-4 10+/-5 14+/-4 14+/-4 14+/-5 15+/-5 22+/-5 20+/-4 11+/-5 7+/-4 12+/-4 9+/-4 13+/-4 14+/-4 22+/-5 19+/-5 17+/-5 12+/-5 20+/-5 17+/-5 18+/-4 17+/-4 24+/-5 23+/-5 21+/-5 19+/-5 18+/-5 17+/-5 (1) <23 (1) 24+/-5 25+/-5 27+/-5 16+/-4 18 +/-4 15+/-4 15 +/-4 23+/-4 21 +/-4 20+/-4 22 +/-5 23+/-5 28 +/-5 35+/-6 36 +/-6 11+/-4 11+/-4 26+/-5 28+/-5 24+/-5 24+/-5 16+/-5 23+/-5 26+/-5 26+/-5 20+/-5 20+/-5 17+/-4 16+/-4 24+/-5 27+/-5 30+/-5 31+/-5 29+/-5 31+/-5 17+/-4 18+/-4 15 +/- 7 (1)(2) 21 +/- 5 14 +/- 8 10 +/- 4 15 +/- 4 16 +/- 5 13 +/-5 17 +/-5 19 +/-4 25 +/-5 20 +/-5 17 +/-5 24 +/-5 24 +/-5 18 +/-4 20 +/-5 20 +/- 4 18 +/- 4 26 +/- 5 32 +/- 5 14 +/-4 29 +/-5 26 +/-5 19 +/-5 30 +/-5 18 +/-5 16 +/-4 20 +/-5 32 +/- 5 29 +/- 5 19 +/- 4 MEAN 20 +/-14 20 +/-15 19 +/-16 21 +/-16 20 +/-15 21 +/-16

THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION (2) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-8 20 +/-16 20 +/-16 20 +/-12

TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP III I GROUP IV PERIOD D-08 D-10 D-14 D-55 D-12 12/31/10- 01/07/11 38 +/- 6 46 +/-+6 33 +/- 5 35 +/- 6 43 +/- 6 01/07/11

- 01/14/11 21 +/- 5 19 +/- 5 21 +/- 5 25 +/- 5 19 +/- 4 01/14/11

- 01/21/11 31 +/- 5 37 +/- 6 31 +/- 5 34 +/- 5 40 +/- 6 01/21/11 -01/28/11 33 +/- 5 39 +/-6 27 +/-5 29 +/- 5 33 +/-5 01/28/11

- 02/04/11 21 +/- 5 23 +/- 6 20 +/- 5 16 +/- 5 22 +/- 5 02/04/11 -02/11/11 19 +/-4 22 +/- 5 22 +/- 5 23 +/- 5 25 +/- 5 02/11/11

- 02/18/11 22 +/- 5 21 +/- 5 21 +/- 5

.21 +/- 5 18 +/- 4 02/18/11 -02/25/11 12 +/-4 12 +/-4 13 +/-4 16 +/-4 13 +/-4 02/25/11 -03/04/11 20 +/- 5 20 +/- 5 22 +/- 5 20 +/- 5 24 +/- 5 03/04/11 - 03/11/11 14 +/- 4 15 +/- 4 14 +/- 4 15 +/- 4 21 +/- 4 03/11/11

- 03/18/11 19 +/- 5 22 +/- 5 21 +/- 5 18 +/- 5 18 +/- 5 03/18/11

- 03/25/11 30 +/- 6 35 +/- 6 25 +/- 5 35 +/- 6 31 +/- 6 03125/11 -04101/11 39 +/- 6 36 +/- 6 37 +/- 6 53 +/- 6 40 +/- 6 04/01/11 -04/08/11 20 +/- 5 20 +/- 5 22 +/-5 18 +/-5 20 +/- 5 04/08/11

- 04/15/11 13 +/- 4 17 +/- 4 10 +/- 4 12,+/- 4 16 +/- 4 04/15/11

- 04/22/11 10 +/- 4 (1) 13 +/- 4 (1) 11 +/- 4 11 +/- 4 15 +/- 5 (1) 04/22/11

- 04/29/11 9 +/- 4 12 +/- 6 (1) 11 t 4 7 +/- 4 8 +/-4 04/29/11 - 05/06111 12 +/- 4 11 +/- 4 10 +/- 4 11 +/- 4 10 +/- 4 05/06/11 - 05/13/11 14 +/- 5

< 6 (1) 12 +/- 4 14 +/- 5 10 +4 05/13/11 -05/20/11 10 +/- 5 8 +/-+4 (1) 7 +/-4 9 +/-4 8

4 05/20/11 -05/27/11 12 +/- 4 16 +/- 4 15 +/- 4 13 +/- 4 12 4

05/27/11 -06/03/11 13 +/- 5 15 +/- 5 12 +/- 5 16 +/-5 14 5

06/03/11 - 06/10/11 21 +/- 4 21 +/- 5 23 +/- 5 23 +/- 5 19 +/-4 06/10/11 -06/17/11 9 t 5 10 +/- 4 9 +/- 4 13 +/- 5 9

4 06/17/11 - 06/24/11 10 +/- 4 10 +/- 4 10 +/- 4 13 +/- 4 12 + 4 06/24/11

- 07/01/11 20 +/- 4 11 +/- 4 17 +/- 4 16 +/- 4 16 +4 07/01/11

- 07/08/11 19 +/- 5 22 +/- 5 18 +/- 5 21 +/- 5 16 +/-5 07/08/11

- 07/15/11 18 +/- 5 14 +/- 5 15 +/- 5 15 +/- 5 16 +/- 5 07/15/11

- 07/22/11 16 +/- 5 20 +/- 5 21 +/- 5 15 +/- 5 15 +/- 5 07/22/11

- 07/29/11 19 +/- 4 19 +/- 4 20 +/- 4 21 +/- 5 17 +/-4 07/29/11 -08/05/11 23 +/- 5 22 +/- 5 22 +/- 5 26 +/-5 22+/- 5 08/05/11

- 08/12/11 22 +/- 5 22 +/- 5 21 +/- 5 22 +/- 5 15 +5 08/12/11

- 08/19/11 14 +/- 5 18 +/- 5 13 +/- 5 20 +/- 5 21 +/- 5 08/19/11 -08/26/11 25 +/-6 19 +/- 5 20 +/- 5 23 +/- 5 18 5

08/26/11 -09/02/11 30 +/-6 36 +/-6 28 +/- 5 28 +/-5 26 5

09/02/11 -09/09/11 20 +/--4 22 +/- 5 20 +/- 5 19 +/--4 19 +/-4 09/09/11 - 09116/11 13 +/- 4 14 +/- 4 17 +/- 4 20 +/- 5 14 +/- 4 09/16/11 - 09/23/11 19 +/- 4 22 +/- 4 13 +/- 4 21 +/- 4 19 +/- 4 09/23/11 - 09/30/11 15 +/- 4 15 +/- 4 16 +/- 4 16 +/- 4 21 +/- 5 09/30/11 -10/07/11 25 +/-5 25 +/-5 25-+/-5 26 +/--5 21 +/-4 10/07/11 -10/14/11 39 +/-6 46 +/-6 38 +/-6 39 +/-6 34 +/-6 10/14/11 - 10/21/11 11 +/- 4 16 +/- 4 12 +/- 4 13 +/- 4 12 +/- 4 10/21/11 - 10/28/11 27 +/- 5 28 +/- 5 31 +/- 6 29 +/- 5 24 +/- 5 10/28/11 - 11/04/11 23 +/- 5 23 +/- 5 28 +/- 5 25 +/- 5 22 +/- 5 11/04/11 -11/11/11 13 +/- 5 15 +/- 5 14 +/- 5 16 +/- 5 20 +/- 5 11/11/11 - 11/18/11 29 +/- 5 32 +/- 5 31 +/- 5 28 +/- 5 29 +/- 5 11/18/11 - 11/25/11 17 +/- 5 20 +/- 5 20 +/- 5 14 +/- 5 21 +/- 5 11/25/11 - 12/02/11 19 +/- 4 21 +/- 5 16 +/- 4 19 +/- 4 20 +4 12/02/11 - 12/09/11 24 +/- 5 25 +/- 5 28 +/- 6 30 +/- 6 31 +/- 8 (1) 12/09/11 - 12/16/11 33 +/- 5 29 +/- 5 33 +/- 5 26 +/- 4 31 + 5 12116/11 -12/23/11 33 +/- 5 30 +/-5 33 +/-5 30 +/-+5 30 +/-5 12/23/11 - 12/30/11 26 +/- 5 21 +/- 4 24 +/- 5 21 +/- 4 23 +/-4 MEAN 20 +/- 16 22 +/- 18 20 +/- 15 21 +/- 17 21 16

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

TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF E-3 PCIICU METER t 2 SIGMA GROUP I - ON-SITE LOCATIONS COLLECTION PERIOD 12/31/10 01/28/11 01/28/11 02/25/11 02/25/11 04101111 04/01/11 04/29/11 04/29/11

- 06/03/11 06/03/11 07/01/11 07/01/11 07/29/11 07/29/11 - 09/02/11 09/02/11 - 09/30/11 09/30/11

- 10/28/11 10/28/11

- 12/02/11 12/02/11 - 12/30/11 MIN MAX MEAN+

2SD GROUP II - NEAR-FIELD LOCATIONS COLLECTION MIN MAX MEAN +

PERIOD 2SD GROUP III - FAR-FIELD LOCATIONS COLLECTION MIN MAX MEAN +

PERIOD 2SD GROUP IV - CONTROL LOCATION COLLECTION MIN MAX MEAN +

PERIOD 2SD 17 39 10 26 12 42 7

22 6

16 8

22 13 22 15 33 15 22 10 41 14 30 18 33 0U t 14 18 +/- 9 24 +/- 19 15 +/- 9 11 5

14 +/- 10 17 5

22 + 11 18 5

24 +/-120 21 +/- 10 24 +8 12/31/1U

- U1/2/11 01/28/11 - 02/25/11 02/25/11 - 04/01/11 04/01/11 - 04/29/11 04/29/11 - 06/03/11 06/03/11 - 07/01/11 07/01/11 - 07/29/11 07/29/11 - 09/02/11 09/02/11 - 09/30/11 09/30/11 - 10/28/11 10/28/11

- 12/02/11 12/02/11 12/30/11 12/31/10 - 12/30/11 18 44 10 27 11 44 8

23 8

17 7

24 12 22 16 29 14 23 10 43 15 30 17 35 31 i8t:

19 9

25 +/- 20 15 9

12 1 4 15 9

17 5

22+/-7 18 5

25 + 19 21 +/-9 27 + 10 12/3111i0 -

V1/8i/1 01/28/11

- 02/25/11 02/25/11

- 04/01/11 04/01/11

- 04/29/11 04/29/11

- 06/03/11 06/03/11

- 07/01/11 07/01/11

- 07/29/11 07/29/11

- 09/02/11 09/02/11

- 09/30/11 09/30/11

- 10/28/11 10/28/11

- 12/02/11 12/02/11

- 12/30/11 12/31/10 - 12/30/11 1'9 12 14 7

7 9

14 13 13 11 13 21 46 23 53 22 16 23 22 36 22 46 32 33 J1 1 14 19 +/- 8 25 +/- 21 13 +/- 9 12 +/- 5 15 +/- 10 18:+/- 5 23 +/- 11 18:1 6 27 + 21 21 +/- 12 28 +/-8 12;1/1u -

l2IiW111 01/28/11 - 02/25/11 02/25/11 - 04/01/11 04/01/11 - 04/29/11 04/29/11 06/03/11 06/03/11 07/01/11 07/01/11 07/29/11 07/29/11 09/02/11 09/02/11 09/30/11 09/30/11 10/28/11 10/28/11 12/02/11 12/02/11 12/30/11 1'9 13 18 8

8 9

15 15 14 12 20 23 4;3

,4 +/- Z 25 20 +/- 10 40 27 +/- 17 20 15 +/-+10 14 11 +/- 5 19 14 +/- 9 17 16 +/- 2 26 20 +/- 9 21 18 +/- 6 34 23 +/- 18 29 22 +/- 8 31 29 +/- 8 12/31/10 - 12/30/11 6

42 20 +/- 15 7

44 21 +/- 15 7

53 21 +/- 17 12/31/10 - 12/30/11 8

43 21 +/- 16

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD D-01 12/31/10 - 04/01/

04/01/11 - 07/01/

07/01/11 - 09/30/

09/30/11 - 12/30/

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

'111

'11

'111 MEAN D-02 12/31/10 04/01/11 07/01/11 09130/11 MEAN D-03 12/31/10 04/01/11 07/01/11 09/30/11 MEAN D-04 12/31/10 04/01/11 07/01/11 09/30/11 MEAN D-07 12/31/10 04/01/11 07/01/11 09/30/11 04/01/11 07/01/11 09/30/11 12/30/11 04/01/11 07/01/11 09/30/11 12/30/11 04/01/11 07/01/11 09/30/11 12/30/11 04/01/11 07/01/11 09/30/11 12130/11

<1

<2

<4

<1

<2

<3

<2

<1

<2

<3

<2

<3

<2

<4

<2

<3

<5

<2

<4

<3

<2

<3

<4

<5

<3

<2

<3

<5

<2

<4

< 13

<6

<7

< 10

<8

<6

<8

<6

<8

14

<10

<6

<8

< 15

<6

<7

<6

<1

<10

<2

<7

<3

<4

<2

<3

<1

<2

<3

<2

<3

<4

<7

<4

<7

<6

<7

<4

<6

<4

<8

< 10

<5

<6

<7

<6

<7

<2

<4

<3

<5

<2

<4

<3

<2

<3

<4

<5

<4

<3

<6

<3

<4

<5 6

3 5

5

<6

<5

<4

<5

<8

<9

<5

<6

<5

<10

<5

<6

<1

<3

<4

<1

<3

<2

<4

<2

<3

<4

<2

<4

<1

<2

<3

<4

<1

<3

<1

<2

<3

<4

<3

<2

<3

<4

<2

<3

82

< 62

< 19

56

88

< 74

< 21

36

117

< 59

18

52

< 242

70

< 20

< 42

< 287

< 54

< 26

<42

25

<9

22

<46

< 25

<5

16

< 47

< 26

<7

< 27

< 49

< 25

<8

< 16

< 102

< 26

<9 MEAN

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD D-08 12/31/10 - 04/01/

04/01/11

- 07/01/

07/01/11

- 09/30/

09130111

- 12/30/

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

!11

!11 MEAN

<3

< 3

<2

<3

<2

<2 D-10 12/31/10 04/01/11 07/01/11 09/30/11 MEAN D-12 03/11/11 03/18/11 03/25/11 04/01/11 12/31/10 04/01/11 07/01/11 09/30/11 MEAN D-14 12/31/10 04/01/11 07/01/11 09/30/11 MEAN 04/01/11 07/01/11 09/30/11 12/30/11 03/18/11 03/25/11 04/01/11 04/08/11 04/01/11 07/01/11 09/30/11 12/30/11

< 40

< 36

< 24

< 31

<3

<2

<3

<2

<3

<3<3

<4

<3

<4

<3

<2

< 45

30

< 18

24

<4

<2

<3

<5

<3

<11

<3

<8

<2

<8

<3

<8

<4

<7

<8

<4

< 82

< 54

< 41

< 63

<10

<9

<5

<8

< 11

<10

<6

<3

<2

<3

<2

< 36

< 26

< 33

< 28

<3

<2

<3

<2

<3

<7

<4

<5

<9

<7

<8

<6

<5

<64

< 90

< 59

< 76

<8

<6

<7

<5

<7

<8

<6

<7

<5

<4

<5

<4

<3

<4

<3

<2

< 39

22

< 30

< 37

<4

<5

<4

<2

<3

<4

<3

<9

<6

<8

<5

<7

<5

<4

< 63

< 39

41

< 46

<8

<5

<4

<5

<6

<5

<4

<2

<3

<4

<3

<2

< 37

<40

26

31

<4

<3

<2

<3

<4

<2

<4

<2

<3

<2

< 37

< 30

< 28

< 33

<3

<2

<3

<2

< 61

175

< 74

< 29

< 47

181

40

22

< 207

< 110

< 95

< 97

< 57

159

< 50

17

< 44

< 187

< 53

<19

< 17

< 101

< 22

<8

16

98

25

<5

61

51

< 55

<54

18

<62

< 26

<7

16

<56

< 26

<9

- 04/01/11

- 07/01/11

- 09/30/11

- 12/30/11 BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE 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-45 1Z/31/1U 04/01/11 07/01/11 09/30/11 MEAN D-53 12/31/10 04/01/11 07/01/11 09/30/11 MEAN D-55 12/31/10 04/01/11 07/01/11 09/30/11 MEAN D-56 12/31/10 04/01/11 07/01/11 09/30/11 MEAN D-58 05/30/11 07/01/11 09/30111

- U4/U1I11

- 07/01/11

- 09/30/11

- 12/30/11

- 04/01/11

- 07101/11

- 09/30/11

- 12/30/11

- 04/01/11

- 07/01/11

- 09/30/11

- 12/30/11

- 04/01/11

- 07/01/11

- 09/30/11

- 12/30/11

- 07/01/11

- 09/30/11

- 12/30/11

<3

<2

<3

<4

<3

<4

<2

<3

<4

<2

<3

<11

<3

<2

<4

<3

<4

<5

<4

<3

<6

<3

<5

<3

<2

<9

< 9

<7

<4

< 10

12

< 10

<7

<8

< 17

<8

<6

<10

<13

<6

<3

<2

<3

<4

<2

<3

<5

<3

<4

<3

<4

<2

<3

<6

< 9

<8

< 10

<8

<6

< 10

<7

<5

<3

<5

<3

<5

<2

<3

<4

<5

<2

<3

<5

<6

<5

<7

< 10

<8

<5

<6

<13

<4

<6

<7

<9

<4

<5

<3

<2

<3

<4

<3

<4

<2

<3

<4

<2

<3

<2

<3

<4

<3

<2

<3

<4

<3

<2

< 35

139

< 62

28

< 51

< 232

82

< 22

38

338

56

< 26

62

204

50

< 24

866

< 65

< 20

< 18

< 55

25

<9

< 19

83

30

<9

17

< 93

< 26

<11

23

<56

< 26

<4

< 305

31

<6

<8

<9

<5

<7

<17

<51

<8

<3

<10

<3

<2

<6

<2

<24

<18

<35

<11

<9

<5

<4

<7

<3

<6

<3

<4

<3

<3 MEAN

TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD GROUP I I

GROUP II ILI7 I IV 01/07/11 01/14/11 01/21/11 01/28/11 02/04/11 02/11/11 02/18/11 02/25/11 03/04/11 03/11/11 03/18/11 03/25/11 04/01/11 04108111 04/15/11 04/22/11 04/29/11 05/06/11 05/13/11 05/20/11 05/27/11 06/03/11 06/10/11 06/17/11 06/24/11 07/01/11 07/08/11 07/15/11 07/22/11 07/29/11 08/05/11 08/12/11 08/19/11 08/26/11 09/02/11 09/09/11 09/16/11 09/23/11 09/30/11 10/07/11 10/14/11 10/21/11 10/28/11 11/04/11 11/11/11 11/18/11 11/25/11 12/02/11 12/09/11 12/16/11 12/23/11 U IIUII I I

- 01/14/11

- 01/21/11

- 01/28/11

- 02/04/11

- 02/11/11

- 02/18/11

- 02/25/11

- 03/04/11

- 03/11/11

- 03/18/11

- 03/25/11

- 04/01/11

- 04/08/11

- 04/15/11

- 04/22/11

- 04/29/11

- 05/06/11

- 05/13/11

- 05/20/11

- 05/27/11

- 06/03/11

- 06/10/11

- 06/17/11

- 06124111

- 07/01/11

- 07/08/11

- 07/15/11

- 07/22/11

- 07/29/11

- 08/05/11

- 08/12/11

- 08/19/11

- 08/26/11

- 09/02/11

- 09/09/11

- 09/16/11

- 09/23/11

- 09/30/11

- 10/07/11

- 10/14/11

- 10/21/11

- 10/28/11

- 11104111

- 11/11/11

- 11/18/11

- 11/25/11

- 12/02/11

- 12/09/11

- 12/16/11

- 12/23/11

- 12/30/11 D-01

< 24

< 51

< 40

< 17

< 41

< 15

< 42

< 21

< 69

< 17

< 36 63 + 26 61 + 20 49 + 22

< 27

< 49

< 51

< 42

< 51

< 33

< 43

< 63

< 33

< 38

< 41

< 49

< 37

< 28

< 43

< 19

< 36

< 51

< 29

< 11

< 45

< 16

< 19

< 50

<6

< 22

< 26

< 37

< 28

< 15

< 33

< 19

< 25

< 21

< 26

< 57

< 30

< 43

< 52

<22

< 28

< 42

< 28

< 42

< 39

< 69

< 30

< 36 71 46

< 43

< 33

< 49

< 52

< 41

< 55

< 60

< 43

< 63

< 33

< 37

< 41

< 49

< 68

< 50

< 28

< 45

< 36

< 51

< 69

< 20

< 45

< 29

< 35

< 50

< 12

< 53

< 62

< 47

< 69

< 46

< 28

< 61

< 35

< 46

< 38

< 45

< 58

< 17 0-D-

-02 D-03

43

< 52

< 41

< 28

< 18

< 28

< 41

< 39

< 69

< 30

< 38 (1)

+ 26 90 +/- 2

+/- 16 51 +/- 2 49 + 2

< 31

< 49

< 52

< 41

< 51

< 60

< 43

< 66

< 38 (1)

< 38

< 41

< 49

< 68

< 49

< 44

< 36

< 51

< 69

< 20

< 45

< 29

<34

< 50

< 12

< 53

< 62

< 47

< 69

< 46

< 28

<61

< 34

< 46

< 38

< 46

< 57

< 30 7

3 9

D-04

< 43

< 51

< 38

< 28

< 46 (1)

< 27

< 26

< 39

< 69

< 30

< 36 67 +3 61 +2 46 -+2

< 26

< 49

< 51

< 42

< 51

< 60

< 43

< 63

< 33

< 38

< 41

< 49

< 68

< 51

< 43

<44

< 36

< 51

< 29

< 20

< 45

< 28

< 35

< 50

< 12

< 53

<64

< 47

< 68

< 46

< 28

< 58

< 35

< 46

< 38

< 46

< 57

< 30 5

2 0

U-U7 U-45

< 43

< 4f

< 30

< 48

<40

<44

< 28

< 35

< 42

< 33

< 28

< 42

< 61

< 37

< 32

< 30

< 53

< 31

< 51

< 38

< 43 74 +/- 27 91 +/- 32 60 +/- 19 43 +/- 27 58 +/- 37 47 +/- 32

< 36

< 30

< 39

< 69

< 42

< 60

< 18

< 37

< 69

< 33

< 60

< 64

< 50

< 52

< 61

< 40

<39

<54

< 21

< 22

<42

<36

< 49

< 29

< 68

< 37

< 51

< 60

< 43

< 45

< 47

< 36

< 33

< 53(1)

< 60

< 67

< 56

< 20

< 15(1)

< 25

< 31

< 28

< 37

< 35

< 61

< 22

< 32

< 12

< 42

< 53

< 41

< 62

< 55

< 47

< 43

< 69

< 66

< 46

< 62

<28

< 18

< 61

< 53

< 35

< 28

< 45

< 46

< 39

< 59

< 47

< 44

< 22

< 49

< 30

< 34

< '45

< 51 (1)

< 50 (1)

<34

< 32

< 41

< 60

< 34

< 50

< 44 73 +/- 27 63 +/- 22 39 +/- 22

< 32

< 68

< 59

< 36

< 59

< 68

< 21

< 38

< 55

< 39

< 35

< 58

< 39

< 68

<64

< 58

< 31

< 20

< 67 D-3

-56

-5

< 4b

< 22

< 43

<34

< 32

< 41

< 60

< 34

< 50

< 41 96 50 32

< 36

< 29

< 59

< 36

< 59

< 68

< 51

< 38

< 55

< 38

< 35

< 58

< 38

< 68

<64

< 58

< 31

< 20

< 67

_+

25 21 23

< 252 (1)

< 22

< 55

< 41

< 57

< 59

< 33

< 45

< 35

< 45

< 63

< 57

< 33

< 62

< 15

< 55

< 56

< 52

< 48

< 36

< 55

< 41

< 56

< 59

< 33

< 45

< 35

< 45

< 63

< 58

< 33

< 62

< 28

< 55

< 56

< 52

< 26

< 36

< 33 (1)(2)

< 55

< 65

< 19

< 58

< 39

< 68

< 64

< 57

< 31

<9

< 67

< 22

< 55

< 41

< 56

< 59

< 33

< 45

< 35

< 45

< 63

< 58

< 33

< 62

< 28

< 55

< 56

< 52

< 48

< 36 MEAN 58 +/- 16 59 +/- 36 63 +/- 46 58 +/- 22 64 +/- 17 60 +/- 54 59 +/- 35 59 +/- 65

THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION (2) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-14

TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 12/31110 - 01/07/11 01/07/11

- 01/14/11 01/14/11

- 01/21/11 01/21/11

- 01/28/11 01/28/11

- 02/04/11 02/04/11

- 02/11/11 02/11/11

- 02/18/11 02/18/11

- 02/25/11 02/25/11

- 03/04/11 03/04/11

- 03/11/11 03/11/11

- 03/18/11 03/18/11

- 03/25/11 03/25/11

- 04/01/11 04101111

- 04/08/11 04/08/11

- 04/15/11 04/15/11

- 04/22/11 04/22/11

- 04/29/11 04/29/11

- 05/06/11 05/06/11

- 05/13/11 05/13/11

- 05/20/11 05/20/11

- 05/27/11 05/27/11

- 06/03/11 06/03/11

- 06/10/11 06/10/11

- 06/17/11 06/17/11

- 06/24/11 06/24/11

- 07/01/11 07/01/11

- 07/08/11 07/08/11

- 07/15/11 07/15/11

- 07/22/11 07/22/11

- 07/29/11 07/29/11

- 08/05/11 08/05/11

- 08/12/11 08/12/11

- 08/19/11 08/19/11

- 08/26/11 08/26/11

- 09/02/11 09/02/11 - 09/09/11 09/09/11 - 09/16/11 09/16/11 - 09/23/11 09/23/11 - 09/30/11 09/30/11 - 10/07/11 10/07/11 - 10/14/11 10/14/11 - 10/21/11 10/21/11 - 10/28/11 10/28/11 - 11/04/11 11/04/11 - 11/11/11 11/11/11 - 11/18/11 11/18/11 - 11/25/11 11/25/11 - 12/02/11 12/02/11 - 12/09/11 12/09/11 - 12/16/11 12/16/11 - 12/23/11 12/23/11 - 12/30/11 u

<55

< 29

< 44

< 31

< 42

< 50

< 56

< 33

< 61

< 38

< 16 69 49 55

< 28

< 40

< 42

< 30

< 69

< 65

< 49

< 63

< 42

< 52

< 42

< 66

< 21

< 34

< 25

<19

< 17

< 23

< 69

<15

< 50

< 16

< 26

< 57

< 42

< 22

< 54

< 18

< 66

< 34

< 32

< 23

< 45

< 20

< 40

<19

< 40

< 14

)-Ub GROUP I U-lu

< 30

<44

< 31

< 42

< 50

< 56

< 33

< 61

< 38

+ 49 115 +/-

+/- 21 52 +/-

+/- 23 47 +/-

< 28

'1)

< 44 (1)

< 56 (1)

< 30

< 69 (1)

< 65

< 51

< 61

< 42

< 51

< 42

< 66

< 37

<64

< 45

< 43

< 31

<54

< 56

< 23

< 50

< 37

< 60

< 57

<8

< 40

<54

< 43

< 66

61

32

< 55

< 45

< 47

40

< 45

< 40

< 33 33 25 26

< b*

< 5:

< 4

< 3

< 4

< 5'

< 5,

< 3:

< 6

< 3

< 3, 9

< 4

< 2

< 6

< 2

< 3

< 51

< 6*

< 5'

< 3'

< 2

< 41

< 1

< 6

< 37

< 6

< 45

<44

< 31

< 5

< 5I

< 24

< 5C

< 3

< 6

< 5

< 4

< 5

< 4

< 28

< 6

< 32

< 55

< 47

< 4!

< 41

< 45

< 40

< 34 Ill IGROUP IV D-14 0-55 D-12 5

< 47

< 55 2

< 52

< 30 4

< 43

< 44 1

< 35

< 31 3

< 33

< 43 0

< 42

< 50 8

< 61

< 56 2

< 32

< 33 3

< 53

< 62 9

< 51

< 38 8

< 42

< 38 6 +/- 29 83 +/- 32 73 +/-28 6 +/- 21 47 +/- 21 46 +/- 24 4

< 27 49 +/- 25 7

< 27

< 35 9

< 69

< 43 (1) 6

< 60

< 43 0

< 37

< 30 9

< 63

< 70(1) 5

< 69

< 63 4

< 54

< 49 4

< 40

< 61 3

< 25

< 42 9

< 37

< 51 8

< 36

< 42 8

< 57

< 66 7

< 40

< 38 0

< 70

< 60 5

< 65

< 45 4

< 59

< 44 0

< 30

< 30 6

< 21

< 55 6

< 68

< 56 4

< 23

< 24 0

< 56

< 50 7

< 42

< 37 1

< 58

< 60 8

< 61

< 58 2

< 34

<42 1

< 45

< 41 5

< 36

< 30 3

< 45

< 43 8

<64

<66 2

< 59

< 61 2

< 33

< 32 5

< 63

< 55 7

< 28

< 45 6

< 52

< 46

< 25

< 62(1) 5

< 51

< 45 0

< 49

< 40

< 36

< 33 MEAN 58 +/- 20 71 +/- 76 76 +/- 57 65 +/- 51 56 +/- 30

THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION (2) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-15

TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/06/11 02/03/11 03/03/11 03131/11 04/07/11 04/21/11 05105111 05/19/11 06/02/11 06/16/11 06/30/11 07/14/11 07/28/11 08/11/11 08/25/11 09/08/11 09/22/11 10/06/11 10/20/11 11/03/11 12/01/11 CONTROL FARM D-25

< 0.7

< 0.6

< 0.5

< 0.6

< 0.7

< 0.6

< 0.7

< 0.5

< 0.7

< 0.9

< 0.7

< 0.8

< 0.9

< 0.8

< 0.7

< 0.8

< 0.7

< 0.9

< 0.6 MEAN BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT C-16

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD D-25 01/06/11 02/03/11 03/03/11 03/31/11 04/07/11 04/21111 05/05/11 05/19/11 06/02/11 06/16/11 06/30/11 07/14/11 07/28/11 08/11/11 08/25/11 09/08/11 09/22/11 10/06/11 10/20/11 11/03/11 12/01/11 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140

<5

<6

<5

<4

<5

<6

<5

<6

<8

<5

<6

<8

<5

<8

<6

<5

<7

<6

<7

<5

<7

<6

<5

<7

<6

<5

<8

<6

<7

< 10

< 18

14

< 14

14

< 12

< 11

< 13

17

< 15

14

13

18

17

<15

14

<11

17

13

< 17

17

<5

<8

<7

<6

<7

<6

<7

< 11

<8

<7

<8

<7

< 11

<7

<9

<7

< 11

14

14

< 14

10

< 11

<12

<11

14

16

<11

12

<15

18

15

15

< 11

< 17

<15

14

13

<5

<8

<6

<5

<6

<5

<7

<6

<7

<6

<7

<6

<8

<7

<9

13

10

< 11

<9

< 10

<10

< 11

13

<13

<11

< 11

<13

<15

<11

<13

<9

12

<10

12

< 11

<4

<6

<5

<4

<5

<4

<6

<5

<6

<7

<6

<5

<7

<5

<6

<5

<6

<5

<6

<5

<6

<7

<6

<7

<6

<5

<7

<6

<7

32

< 43

< 40

< 48

46

< 26

< 32

< 55

< 44

< 48

< 30

< 36

< 43

< 42

< 40

< 26

< 43

< 34

< 42

< 32

10

<12

<13

< 11

<13

<8

<10

<15

13

14

<8

<10

<9

<12

<13

< 10

<9

< 13

< 12

< 10

< 11 MEAN BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION Mn-54 PERIOD Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 L-C;UN I TUL Cabbage Carrots D-QUAD 1 Beet greens Beets D-QUAD 2 Cabbage Potatoes D-QUAD 3 Cabbage Sweet potatoes 09/24/11

< 17 09/24/11

< 15

< 18

< 36

< 18

< 39

< 18

< 29

< 34

< 14

< 15

< 77

< 18

<41

<22

< 37

< 18

<28

< 38

< 15

< 20

< 86

< 30

< 26 MEAN 09/24/11

< 19 09/24/11

< 19 MEAN 09/23/11

< 15 09/23/11

< 20

< 21

< 51

< 25

< 42

< 19

< 32

< 41

< 17

< 24

< 115

< 28

< 17

< 36

<24

< 53

< 19

< 33

< 38

< 17

< 23

< 96

<20

< 14

< 36

< 18

< 35

< 18

< 24

<42

< 12

< 16

< 91

< 23

< 17

< 43

< 28

< 49

< 16

< 34

< 45

< 15

< 20

< 114

< 25

< 16

< 47

< 27

< 43

< 19

< 38

< 15

< 19

< 100

< 21

< 14

< 34

< 14

< 31

< 19

< 23

< 38

< 13

< 14

< 88

<27 00 MEAN 09/23/11

< 19 09/23/11

< 14 MEAN D-QUAD 4 Broccoli Potatoes 09/24/11

< 13 09/24/11

< 8

< 15

<42

< 19

< 39

< 17

< 27

< 36

< 16

< 17

< 78

< 8

< 21

< 11

<20

< 11

< 14

< 23

< 8

< 9

< 55

< 25

< 14 MEAN

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2011 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 21.8 1 6.6 22 21 18 26 D-01-2 21.0 +/- 9.1 22 18 17 27 D-02-1 23.8 +/- 9.1 26 21 19 29 D-02-2 23.5 +/- 8.1 24 21 20 29 D-03-1 19.0 +/- 5.9 19 18 16 23 D-03-2 18.5 +/- 6.6 19 16 16 23 D-04-1 21.0 +/- 11.2 25 14 19 26 D-04-2 21.5 +/- 6.8 22 20 18 26 D-07-1 20.3 +/- 6.6 22 18 17 24 D-07-2 21.0 +/- 9.9 21 17 18 28 D-08-1 22.3 +/- 12.3 22 18 18 31 D-08-2 21.3 +/- 7.2 22 19 18 26 D-10-1 22.3 +/- 8.9 25 19 18 27 D-10-2 20.5 +/- 7.4 22 18 17 25 D-12-1 20.5 +/- 6.6 21 21 16 24 D-12-2 19.3 +/- 6.6 21 17 16 23 D-14-1 19.3 +/- 7.5 20 18 15 24 D-14-2 20.0 +/- 7.3 22 18 16 24 D-45-1 23.8 +/- 8.1 26 22 19 28 D-45-2 23.0 +/- 7.1 23 20 21 28 D-53-1 18.0 +/- 7.7 19 15 15 23 D-53-2 17.5 +/- 6.0 19 15 15 21 D-55-1 22.0 +/- 6.3 23 20 19 26 D-55-2 21.3 +/- 7.2 22 19 18 26 D-56-1 18.3 +/- 7.2 19 16 15 23 D-56-2 18.0 +/- 7.1 18 16 15 23 D-58-1 18.8 +/- 6.2 19 17 16 23 D-58-2 19.5 +/- 7.4 19 20 15 24 D-101-1 22.0 +/- 6.3 23 20 19 26 D-101-2 20.5 +/- 6.6 21 18 18 25 D-102-1 23.8 +/- 9.3 24 22 19 30 D-102-2 23.3 +/- 5.5 26 22 20 25 D-103-1 20.8 +/- 6.2 21 19 18 25 D-103-2 21.0 +/- 6.3 22 19 18 25 D-104-1 22.8 +/- 7.7 25 20 19 27 D-104-2 21,8 +/- 7.7 24 18 19 26 D-105-1 21.0 +/- 6.3 22 19 18 25 0-105-2 21.0 +/- 9.2 25 17 17 25 D-106-1 21.8 +/- 6.4 23 23 17 24 D-106-2 19.5 +/- 6.0 22 18 16 22 D-107-1 18.5 +/- 7.7 18 17 15 24 D-107-2 17.8 +/- 6.2 22 16 15 18 D-108-1 23.5 +/- 6.8 24 22 20 28 D-108-2 20.5 +/- 5.8 20 21 17 24 D-109-1 22.5 +/- 7.7 22 21 19 28 D-109-2 23.0 +/- 6.3 25 19 22 26 D-110-3 24.5 +/- 7.6 24 22 22 30 D-110-4 24.5 +/- 6.6 25 22 22 29 D-111-1 24.3 +/- 7.5 27 21 21 28 D-111-2 22.5 +/- 7.0 25 20 19 26 D-113-1 21.8 +/- 7.0 20 18 23 26 D-113-2 19.5 +/- 7.4 21 17 16 24 D-114-1 18.8 +/- 6.2 19 17 16 23 D-114-2 20.3 +/- 6.8 20 19 17 25 C-19

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS STATION CODE D-115-1 D-115-2 D-116-1 D-1 16-2 D-201-1 D-201-2 D-202-1 D-202-2 D-203-1 D-203-2 D-204-1 D-204-2 D-205-1 D-205-2 D-206-1 D-206-2 D-207-1 D-207-2 D-208-1 D-208-2 D-209-1 D-209-2 D-210-1 D-210-2 D-211-1 D-211-2 D-212-3 D-212-4 D-213-1 D-213-2 D-214-1 D-214-2 D-215-1 D-215-2 D-216-1 D-216-2 D-1 12A-1 D-112A-2 MEAN

+/- 2 S.D.

22.0 +/- 9.9 23.0 +/- 8.2 23.3 +/- 7.9 23.0 +/- 5.9 27.0 +/- 9.4 24.8 +/- 7.0 23.8 +/- 8.1 22.5 +/- 6.0 21.5 +/- 8.4 19.8 +/- 7.5 20.3 +/- 7.2 19.0 +/- 7.1 25.5 +/- 5.0 24.8 +/- 9.0 22.5 +/- 7.4 21.8 +/- 4.7 20.3 +/- 6.8 21.5 +/- 5.3 19.0 +/- 6.5 19.8 +/- 5.7 18.8 +/- 6.2 17.8 +/- 5.0 22.3 +/- 5.7 21.5 +/- 7.4 22.5 +/- 7.4 23.3 +/- 9.4 19.3 +/- 6.8 20.0 +/- 5.4 18.5 +/- 7.4 20.3 +/- 6.6 26.8 +/- 15.6 25.3 +/- 5.3 24.5 +/- 6.6 24.5 +/- 9.6 21.0 +/- 6.3 22.3 +/- 7.2 20.3 +/- 6.6 19.8 +/- 7.5 JAN - MAR APR - JUN JUL - SEP OCT - DEC 22 26 25 23 28 26 26 24 24 20 21 21 23 27 23 22 20 23 19 19 19 18 22 23 24 23 19 19 20 21 26 25 25 27 22 23 20 20 (1)

(1) 19 19 20 22 25 23 22 20 19 17 18 16 25 21 22 20 19 18 19 18 17 17 22 18 20 20 18 18 16 20 22 24 22 21 19 20 18 17 18 20 20 20 22 21 19 20 17 17 17 16 25 21 18 20 17 21 15 18 16 15 19 19 19 20 16 19 15 16 21 23 22 20 18 19 18 17 29 27 28 27 33 29 28 26 26 25 25 23 29 30 27 25 25 24 23 24 23 21 26 26 27 30 24 24 23 24 38 29 29 30 25 27 25 25 C-20

TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE INNER RING, OUTER RING, OTHEI AND CONTROL LOCATIONS FOR DRESDEN NUCLEAR POWER STATION, 2011 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 22.5 +/- 4.8 19.4 +/- 3.8 18.4 +/- 4.3 25.6 +/- 4.8 22.6 +/- 5.5 19.9 +/- 4.9 18.8 +/- 5.0 26.5 +/- 6.8 21.8 +/- 4.6 18.2 +/- 4.3 17.4 +/- 3.4 25.7 +/- 4.9 21.0 +/- 0.0 19.0 +/- 5.7 16.0 +/- 0.0 23.5 +/- 1.4 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER LOCATION SAMPLES PERIOD ANALYZED MINIMUM PERIOD MAXIMUM PERIOD MEAN

+/-2 S.D.

INNER RING OUTER RING OTHER CONTROL 136 15 128 96 8

15 14 16 30 21.5 +/- 7.2 38 21.9 +/- 8.1 31 20.8 +/- 7.9 24 19.9 +/- 6.3 INNER RING STATIONS - D-58-1, D-58-2, D-101-1, D-101-2, D-102-1, D-102-2, D-103-1, D-103-2, D-104-1, D-104-2, D-105-1, D-105-2, D-106-1, D-106-2, D-107-1, D-107-2, D-108-1, D-108-2, D-109-1, D-109-2, D-110-3, D-110-4, D-111-1, D-111-2, D-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-1 16-2, 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-1 2-1, D-1 2-2 C-21

FIGURE C-1 SURFACE WATER - GROSS BETA - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2011 D-51 Dresden Lock & Dam 12 10 8

6

,.J cj 4

2 o I 01-28-00 08-29-01 03-31-03 10-30-04 06-01-06 01-01-08 D-52 (C) DesPlaines River at Will Road C.

16 14 12 10 8

6 4

2 0

01-28-00 06-17-02 11-04-04 03-25-07 08-12-09 12-31-11 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-51 LOCATION REMOVED FROM PROGRAM JUNE 29, 2007 AND REPLACED WITH D-21 C-22

FIGURE C-2 SURFACE WATER - GROSS BETA - STATION D-54 (C) and D-57 (C)

COLLECTED IN THE VICINITY OF DNPS, 2003 - 2011 D-54 (C) Kankakee River

-j U) 14 12 10 8

6 4

2 0

01-31-03A.,

12-25-03 11-17-04 10-11-05 09-04-06 07-29-07 D-57 (C) Kankakee River at Will Road CL 32 28 24 20 16 12 8

4 0

07-28-06 08-29-07 09-29-08 10-31-09 12-02-10 01-03-12 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-23

FIGURE C-3 SURFACE WATER - GROSS BETA - STATION D-21 COLLECTED IN THE VICINITY OF DNPS, 2007 - 2011 D-21 Illinois River at EJ&E Bridge 30 25 20 15 10 5

-,,=

U 0 I 04-27-07 04-03-08 03-11-09 02-16-10 01-24-11 01-01-12 D-21 PLACED INTO SERVICE ON MARCH 30, 2007, REPLACED D-51 C-24

FIGURE C-4 SURFACE WATER - TRITIUM - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2011 D-51 Dresden Lock & Dam C-2000 1800 1600 1400 1200 1000 800 600 400 200 0

03-31-00 10-18-01 05-07-03 11-23-04 06-12-06 12-30-07 D-52 (C) Des Plaines River at Will Road 600 500 400 300 200 100 C.

04 03-31-00 08-06-02 12-11-04 04-18-07 08-23-09 12-29-11 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-51 LOCATION REMOVED FROM PROGRAM JUNE 29, 2007 AND REPLACED WITH D-21 C-25

FIGURE C-5 SURFACE WATER - TRITIUM - STATION D-54 (C) AND D-57 (C) COLLECTED IN THE VICINITY OF DNPS, 2003 - 2011 D-54 (C) Kankakee River C.

800 700 600 500 400 300 200 100 0

03-28-03 02-03-04 12-11-04 10-19-05 08-27-06 07-05-07 Location shared with Braidwood Station (BD-10).

D-57 (C) Kankakee River at Will Road

.-U3 0.

7000 6000 5000 4000 3000 2000 10000 0

12-20-06 12-23-07 12-25-08 12-28-09 12-31-10 01-03-12 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-26

FIGURE C-6 SURFACE WATER - TRITIUM - STATION D-21 COLLECTED IN THE VICINITY OF DNPS, 2007 - 2011 D-21 Illinois River at EJ&E Bridge 800 700 600 500 400 300 200

,-J C.)

1000L 06-29-07 05-23-08 04-17-09 03-1'2-10 02-04-11 12-30-11 D-21 REPLACED D-51 JUNE 29, 2007 C-27

FIGURE C-7 GROUND WATER - TRITIUM - STATIONS D-23 and D-35 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2011 D-23 Thorsen Well 1000 800 600 400 200 C-0 4-01-08-00 06-01-02 10-23-04 03-17-07 08-08-09 12-31-11 D-35 Dresden Lock and Dam C.

400 350 300 250 200 150 100 50 0

01-08-00 06-01-02 10-23-04 03-17-07 08-08-09 12-31-11 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-28

FIGURE C-8 AIR PARTICULATES - GROSS BETA - STATIONS D-01 and D-02 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2011 D-01 Onsite Station I 06 Qu 50.0 40.0 30.0 20.0 10.0 0.0 01-08-00 06-01-02 10-23-04 03-17-07 08-08-09 12-31-11 D-02 Onsite Station 2 c')

CL 9

40 50.0 40.0 30.0 20.0 10.0 0.0 1 01-08-00 06-01-02 10-23-04 03-17-07 08-08-09 12-31-11 D-02 No samples; power was restored on 09-16-05.

C-29

FIGURE C-9 AIR PARTICULATES - GROSS BETA - STATIONS D-03 and D-04 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2011 D-03 Onsite Station 3 C.)o,

,L 0

60.0 50.0 40.0 30.0 20.0 10.0 0.0 I 01-08-00 06-01-02 10-23-04 03-17-07 08-08-09 12-31-11 D-04 Collins Road on Station Property C.,

m 0

60.0 50.0 40.0 30.0 20.0 10.0 0.0 01-08-00 06-01-02 10-23-04 03-17-07 08-08-09 12-31-11 C-30

FIGURE C-10 AIR PARTICULATES - GROSS BETA - STATIONS D-07 and D-12 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2011 D-07 Clay Products, Dresden Road m

01 120.0 110.0 100.0 90.0 80.0 70.0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 01-08-00 06-01-02 10-23-04 03-17-07 08-08-09 12-31-11 D-12 (C), Quarry Road, Lisbon co)

Luj 80.0 70.0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 01-08-00 06-01-02 10-23-04 03-17-07 08-08-09 12-31-11 C-31

FIGURE C-1I AIR PARTICULATES - GROSS BETA - STATIONS D-45 and D-53 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2011 D-45 McKinley Woods Road, Channahon C,

a.

w uJ a

70.0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 01-08-00 06-01-02 10-23-04 03-17-07 08-08-09 12-31-11 D-53 Will Road at Hollyhock C.)

w C,

uJ a:

50.0 40.0 30.0 20.0 10.0 0.0 4-01-08-00 06-01-02 10-23-04 03-17-07 08-08-09 12-31-11 C-32

FIGURE C-12 AIR PARTICULATES - GROSS BETA - STATIONS D-08 and D-10 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2011 D-08 Jugtown Road, Prairie Parks 70.0 60.0 50.0 c')

E 40.0 a.

m 30.0 9

20.0 10.0 0.0 I 01-07-05 06-01-06 10-24-07 03-17-09 08-09-10 01-01-12 D-10 Goose Lake Road, Goose Lake Village 60.0 50.0 40.0 aL 30.0 c')

9 20.0 10.0 0.0 I 01-07-05 06-01-06 10-24-07 03-17-09 08-09-10 01-01-12 C-33

FIGURE C-13 AIR PARTICULATES - GROSS BETA - STATIONS D-13 and D-14 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2011 D-1 3 Minooka m

CL 50.0 40.0 30.0 20.0 10.0 0.0 I

I I

01-07-05 07-07-05 01-04-06 07-04-06 01-01-07 07-01-07 D-14 Center Street, Channahon 50.0 40.0 E

30.0 a.

CL 20.0 10.0 0.0 I 01-07-05 06-01-06 10-24-07 03-17-09 08-09-10 01-01-12 D-13 TAKEN OUT OF SERVICE JUNE 29, 2007 AND REPLACED WITH D-55 C-34

FIGURE C-14 AIR PARTICULATES - GROSS BETA - STATIONS D-55 and D-56 COLLECTED IN THE VICINITY OF DNPS, 2006-2011 D-55 Ridge Road, Minooka 60.0 50.0 40.0 E

oC 30.0 co9 wo 20.0 10.0 0.0 I

01-06-06 03-19-07 05-29-08 08-09-09 10-20-10 12-31-11 D-56 Will Road, Wildfeather co CL 0di 40 50.0 40.0 30.0 20.0 10.0 0.0 I 07-25-06 08-26-07 09-26-08 10-28-09 11-29-10 12-31-11 D-55 NEW STATION DECEMBER 30, 2005 REPLACED D-13 JUNE 29, 2007 D-56 NEW STATION JULY 25, 2006 C-35

FIGURE C-15 AIR PARTICULATES - GROSS BETA - STATION D-58 COLLECTED IN THE VICINITY OF DNPS, 2011 D-58 Will Road Marina 40.0 30.0 20.0 C,,

9 10.0 0.0

-1 06-03-11 07-15-11 08-26-11 10-07-11 11-18-11 12-30-11 D-58 NEW STATION IN MAY OF 2011 C-36

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM

Intentionally left blank

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

March 2011 E7460-396 Milk E7461-396 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 98.8 97.4 pCi/L 15.2 15.8 1.01 0.96 A

A 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 92.9 96.9 0.96 A

not provided by Analytics for this study 398 298 1.34 N (1) 130 130 1.00 A

232 205 1.13 A

121 113 1.07 A

289 266 1.09 A

201 175 1.15 A

287 261 1.10 A

186 172 1.08 A

not provided by Analytics for this study E7463-396 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E7462-396 Charcoal 1-131 243 85.0 168 89.2 171 129 159 132 215 94.2 148 81.8 192 126 189 124 1.13 0.90 1.14 1.09 0.89 1.02 0.84 1.06 pCi 96.5 96.3 pCi/L 96.7 103 pCi/L 13.8 15.6 1.00 0.94 0.88 June 2011 E7851-396 Milk E7852-396 Milk E7854-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 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 110 68.1 186 164 140 141 136 128 263 189 49.9 95.6 104 83.8 90.7 74.5 62.0 140 119 103.0 79.9 206 190 138 152 138 123 261 195 42.9 110 102 74.0 81.3 73.9 66.1 140 104 1.07 0.85 0.90 0.86 1.01 0.93 0.99 1.04 1.01 0.97 1.16 0.87 1.02 1.13 1.12 1.01 0.94 1.00 1.14 0.89 A

A A

Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 E7853-396 pCi 76.2 86.1 D-1

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

September 2011 E8070-396 Milk E8071-396 Milk E8073-396 AP 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 90.8 pCi/L 13.2 14.7 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 74.2 66.9 249 116 106 95.4 147 53.1 175 150 66.6 263 139 110 108 152 57.5 190 156 89.2 66.7 226 128 114 97.5 151 54.8 180 157 67.5 229 130 115 98.6 153 55.5 183 159 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 1.12 0.90 0.83 1.00 1.10 0.91 0.93 0.98 0.97 0.97 0.97 0.96 0.99 1.15 1.07 0.96 1.10 0.99 1.04 1.04 0.98 0.96 1.00 0.82 0.91 E8072-396 Charcoal 1-131 pCi 77.6 80.6 pCi/L 93.3 93.1 pCi/L 12.7 15.4 December, 2011 E8230-396 Milk E8231-396 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 A

A A

A 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 82.5 90.2 not provided by Analytics for this study 465 566 0.82 A

142 171 0.83 A

185 210 0.88 A

177 221 0.80 A

208 241 0.86 A

164 183 0.90 A

259 291 0.89 A

224 270 0.83 A

not provided by Analytics for this study 344 368 0.93 A

105 111 0.95 A

129 137 0.94 A

145 144 1.01 A

137 157 0.87 A

119 119 1.00 A

145 190 0.76 W

168 176 0.95 A

E8233-396 AP Ce-1 41 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 D-2

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

December 2011 E8232-396 Charcoal 1-131 pCi 100 89.5 1.12 A

(1) Sample appears to be biased high. Corrective Action evaluated after the 2nd Quarter Analytics PE sample; no action required. NCR 11-13 (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, 2011 (PAGE 1 OF 1)

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

Value (b)

Control Limits Evaluation (c)

May 2011 RAD-85 MRAD-14 Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A pCi/L 59.8 pCi/L 42.5 pCi/L 73.3 pCi/L 64.9 pCi/L 74.6 pCi/L 87.8 pCi/L 103 pCi/L 64.1 pCi/L 51.8 pCi/L 27.4 pCi/L 38.5 pCi/L 10057 pCi/filter 79.7 pCi/L 81.0 pCi/L 35.5 pCi/L 90.7 pCi/L 36.6 pCi/L 44.7 pCi/L 118.7 pCi/L 80.2 pCi/L 34.2 pCi/L 39.3 pCi/L 22.9 pCi/L 46.8 pCi/L 15733 pCi/filter 44.6 63.2 42.5

.75.3 72.9 77.0 88.8 98.9 50.1 49.8 27.5 39.8 10200 51.1 -71.2 31.3-48.8 63.0 - 82.8 59.5 - 80.2 69.3 - 87.4 79.9-100 89.0-118 26.1 -62.9 33.8 - 56.9 22.9 - 32.3 32.2 - 44.4 8870-11200 74.3 38.5-112 A

A A

N (1)

A A

A N (2)

A A

A November 2011 RAD-87 69.7 41.4 96.9 33.4 44.3 119 76.8 53.2 45.9 27.5 48.6 17400 56.9 - 77.9 30.2 -47.2 81.8-106 26.3-36.7 39.4-51.7 107-133 68.9 - 92.5 27.8 - 66.6 30.9-53.1 22.9 - 32.3 39.4 - 54.0 15200- 19100 MRAD-15 58.4 30.3 - 87.8 A

(1) The solids on the planchet exceeded 100 mg, which was beyond the range of the efficiency curve. NCR 11-08 (2) Sr-89 TBE to known ratio of 1.16 fell within acceptable range of +/- 20%. No action required. NCR 11-16 (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 dunng standard preparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the Waming 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, 2011 (PAGE I OF 2)

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

Range Evaluation (c)

March 2011 11-MaW24 11-GrW24 Water Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Water Gr-A Gr-B 11-MaS24 11-RdF24 Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 11-GrF24 11-RdV24 September 2011 11-MaW25 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-57 Co-60 Mn-54 Sr-90 Zn-65 Water Cs-1 34 Cs-137 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Bq/L 19.1 21.5 Bq/L 29.0 29.4 Bq/L 0.139 Bq/L 23.9 24.6 Bq/L 265 243 Bq/L 31.8 31.6 Bq/L 94.8 91 Bq/L 9.64 8.72 Bq/L

-0.142 Bq/L 0.767 1.136 Bq/L 3.43 2.96 Bq/kg 612 680 Bq/kg 772 758 Bq/kg 910 927 Bq/kg 500 482 Bq/kg 0.607 Bq/kg 569 540 Bq/kg NR.

160 Bq/kg 1497 1359 Bq/sample 3.26 3.49 Bq/sample 2.36 2.28 Bq/sample 3.30 3.33 Bq/sample 0.0765 Bq/sample 2.84 2.64 Bq/sample NR 1.36 Bq/sample 3.30 3.18 Bq/sample 0.101 0.659 Bq/sample 1.23 1.323 Bq/sample 4.97 5.50 Bq/sample 0.0356 Bq/sample 10.8 9.94 Bq/sample 4.89 4.91 Bq/sample 6.42 6.40 Bq/sample NR 2.46 Bq/sample 3.07 2.99 Bq/L 16.0 19.1 Bq/L 0.0043 Bq/L 33.1 36.6 Bq/L 26.9 29.3 Bq/L 1011 1014 Bq/L 23.2 25.0 Bq/L 147 156 Bq/L 15.8 14.2 Bq/L 27.3 28.5 15.1 -28.0 20.6 - 38.2 (1) 17.2-32.0 170-316 22.1 -41.1 64-118 6.10- 11.34 (1) 0.341 - 1.931 1.48 -4.44 476 - 884 531 - 985 649-1205 337 - 627 (1) 378 - 702 112 -208 951 -1767 2.44 - 4.54 1.60 -2.96 2.33 - 4.33 (1) 1.85 - 3.43 0.95 - 1.77 2.23 -4.13 0.198 - 1.120 0.662 - 1.985 3.85-7.15 (1) 6.96 - 12.92 3.44 - 6.38 4.48 - 8.32 1.72 - 3.20 2.09 - 3.89 13.4 - 24.8 (1) 25.6 - 47.6 20.5-38.1 710-1318 17.5-32.5 109-203 9.9-18.5 20.0-37.1 A

A A

A N (2)

A A

N (2)

A N (3)

A A

N (2)

A A

A D-5

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

TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 2)

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

Value (b)

Range Evaluation (c)

September 2011 11-GrW25 11-MaS25 September 2011 11-RdF25 Water Gr-A Gr-B Soil Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/L 0.894 0.866 Bq/L 5.87 4.81 Bq/kg

-0.213 Bq/kg 1110 979 Bq/kg 1290 1180 Bq/kg 731 644 Bq/kg 987 848 Bq/kg 753 625 Bq/kg 276 320 Bq/kg 1870 1560 Bq/sample

-0.043 Bq/sample 3.09 2.60 Bq/sample 5.36 5.09 Bq/sample 3.41 3.20 Bq/sample 0.067 Bq/sample 1.84 1.67 Bq/sample 5.17 4.11 0.260 - 1.472 2.41 - 7.22 (1) 685-1273 826 - 1534 451 - 837 594 - 1102 438-813 224-416 1092-2028 (1) 1.82-3.38 3.56 - 6.62 2.24-4.16 (1) 1.17-2.17 2.88 - 5.34 11-GrF25 11 -RdV25 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 A

A A

W A

A A

A W

A A

A Bq/sample 0.0058 Bq/sample

-0.01 (1)

(1)

Bq/sample 0.0081 (1)

Bq/sample 4.94 4.71 3.30-6.12 Bq/sample 0.0639 (1)

Bq/sample 3.36 3.38 2.37 -4.39 Bq/sample 5.89 5.71 4.00 - 7.42 Bq/sample 1.31 1.26 0.88 - 1.64 Bq/sample 6.54 6.39 4.47 - 8.31 (f) False positive test.

(2) Evaluated as failed due to not reporting a previously reported analyte. NCR 11-11 (3) The filter for Gross Alpha was counted on the wrong side. Recounted on the correct side resulted in acceptable results. NCR I1-11 (a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) DOEIMAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.

D-6

APPENDIX E ERRATA DATA

Intentionally left blank

There is no errata data for 2011.

Intentionally left blank

APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Intentionally left blank

Docket No:

50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2011 Prepared By Teledyne Brown Engineering Environmental Services Exelkn.

Nuclear Dresden Nuclear Power Station Norris, IL 60450 May 2012

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

1 I1. Introduction.............................................................................................................

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

3 B. Im plem entation of the Objectives..................................................................

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

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

4 Ill. 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. Surface W ater Results..................................................................................

11 C. Precipitation W ater Results.........................................................................

12 D. Drinking W ater W ell Survey.........................................................................

12 E. Summary of Results - Inter-laboratory Comparison Program......................

13 F. Leaks, Spills, and Releases........................................................................

13 G. Trends..........................................................................................................

13 H. Investigations................................................................................................

13 I. Actions Taken................................................................................................

14

- i -

Appendices ARGPPR Appendix A Tables Table A-1 Figures ARGPPR Appendix B Location Designation Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2011 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 Tables Table B-1.1 Table B-1.2 Table B-1.3 Table B-11.1 Table B-11.2 Table B-11.3 Table B-Ill.1 Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Hard-To-Detects in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

Concentrations of Tritium in Precipitation Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2011.

- ii -

I.

Summary and Conclusions Dresden Station is situated on approximately 600 acres of land that borders the Illinois River to the north and the Kankakee River to the east. This land is referred to as the owner-controlled area. The Dresden power plant itself takes up a small parcel of the owner-controlled area and is surrounded by a security fence. The security fence defines what is known as the Protected Area (PA).

The Dresden power plant has experienced leaks from underground lines and spills from systems containing radioactive water over its 40-year history. These incidents have created a number of areas of localized contamination within the PA. Isotopic analyses of groundwater in many of these areas show measurable concentrations of tritium (H-3).

Dresden participated in a fleetwide hydrogeologic investigation in during the summer of 2006 in an effort to characterized groundwater movement at each site. This investigation also compiled a list of the historic spills and leaks as well as an detailed analysis on groundwater hydrology for Dresden Nuclear Generation Station. Combining the tritium concentration in a locally contaminated area with the speed and direction of groundwater in the vicinity can produce a contaminated groundwater plume projection. If the plume of contaminated groundwater passes through the path of a groundwater monitoring well, it can be anticipated that the tritium concentration in this well will increase to some maximum concentration, then decrease over time.

The fleetwide Hydrogeologic Investigation Report (HIR) shows that groundwater movement on the Dresden site is very slow. In addition, there is a confining rock layer, the Maquoketa Shale layer, about 55 feet below the surface that impedes groundwater movement below this depth.

Dresden has a domestic water system that is supplied by two deep wells (1500 feet deep) that were installed about 50 years ago south of the P.A. Samples taken from domestic water supply 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 has 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 89 sampling points in the RGPP:

Dresden has 45 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 8 surface water monitoring locations on the owner-controlled area sampled as part of the Dresden RGPP.

Dresden has 12 precipitation water monitoring locations sampled as part of the Dresden RGPP.

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 determined by the well detection category. Sixteen of the 89 wells are categorized as background monitoring wells and are sampled on a annual basis. The remaining 73 wells are sampled on a quarterly basis to maximize leak detection and contamination plume movement capability. During 2011, there were 693 analyses that were performed on 254 samples from 88 sampling points.

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.

These wells are categorized as idle wells and are used only for troubleshooting purposes.

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 I intake canal and the hot canal eventually route to the cooling pond. The Dresden Station RGPP has eight RGPP surface water sampling points to monitor these systems.

A.

Objectives of the RGPP The Objective of the RGPP is to provide long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. The objective of the site-specific RGPP is to provide indication of short-term changes to groundwater tritium concentrations within the PA.

If isotopic results of groundwater samples exceed the thresholds specified in this procedure it could be an indication of a new spill from an above ground system or a new leak in an underground pipe containing tritiated water.

Specific Objectives include:

1.

Perform routine water sampling and radiological analysis of water from selected locations.

2.

Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.

3.

Regularly assess analytical results to identify adverse trends.

4.

Take necessary corrective actions to protect groundwater resources.

B.

Implementation of the Objectives

1.

Dresden Nuclear Power Station will continue to perform routine sampling and radiological analysis of water from selected locations.

2.

Dresden Nuclear Power Station has implemented procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner.

3.

Dresden Nuclear Power Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.

4.

If an adverse trend in groundwater monitoring analytical results is identified, further investigation will be undertaken. If the investigation identifies a leak or unidentified spill, corrective actions will be implemented.

C.

Program Description Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. Dresden uses 89 developed groundwater wells and surface water sample points in the RGPP.

1.

Sample Collection Sample locations can be found in Table A-i, Appendix A.

Groundwater and Surface Water Water samples are collected in accordance with the schedule delineated in the Dresden site-specific RGPP procedures.

Analytical laboratories are subject to internal quality assurance programs, industry crosscheck programs, as well as nuclear industry audits. Station personnel review and evaluate the analytical results.

D.

Characteristics of Tritium (H-3)

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

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

Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium.

Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.

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

III.

Program Description A.

Sample Analysis This section describes the general analytical methodologies used by Teledyne Brown Engineers (TBE) to analyze the environmental samples for radioactivity for the Dresden Nuclear Power Station RGPP in 2011.

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

1.

Concentrations of gamma emitters in groundwater and surface water.

2.

Concentrations of strontium in groundwater and surface water.

3.

Concentrations of tritium in groundwater, surface water and precipitation water.

4.

Concentrations of gross alpha and gross beta in groundwater and surface water samples.

5.

Concentrations of Am-241 in groundwater and surface water.

6.

Concentrations of Cm-242 and Cm-243/244 in groundwater and surface water.

7.

Concentrations of Pu-238 and Pu-239/240 in groundwater and surface water.

8.

Concentrations of U-233/234, U-235 and U-238 in groundwater and surface water.

9.

Concentrations of Fe-55 in groundwater and surface water.

10.

Concentrations of Ni-63 in groundwater and surface water.

B.

Data Interpretation The radiological data collected prior to Dresden Nuclear Power Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Dresden Nuclear Power Station was considered operational at initial criticality. Several factors were important in the interpretation of the data:

1.

Lower Limit of Detection and Minimum Detectable Concentration The Lower Limit of Detection (LLD) is the minimum sensitivity value that must be achieved routinely by the analytical parameter.

2.

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

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

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

Gamma spectroscopy results for each type of sample were grouped as follows:

For groundwater and surface water 14 nuclides, Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-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 worldwide from 1960 to 2006.

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

Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time. Tritium concentrations in Midwest precipitation have typically been below 100 pCi/L since around 1980.

Tritium concentrations in wells may still be above the 200-pCi/L detection limit from the external causes described above. Water from previous years and decades is naturally captured in groundwater, so some well water sources today are affected by the surface water from the 1960s that was elevated in tritium.

c.

Surface Water Data Tritium concentrations are routinely measured in large surface water bodies, including Lake Michigan and the Mississippi River. Illinois surface water data were typically less than 100 pCi/L.

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

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

IV.

Results and Discussion Dresden Station initiated a Radiological Groundwater Protection Program (RGPP) in 2006.

A.

Groundwater Results Groundwater Samples were collected from on-site wells throughout the year in accordance with Dresden's RGPP. Analytical results and anomalies are discussed below.

Tritium Of the 69 developed groundwater-monitoring wells and one non-developed well sampled approximately half (34 wells) show some level of tritium contamination ranging from just above LLD to 85,000 pCi/L. The well with the highest concentration was MD-1 1. Of the 69 wells sampled only 3 had concentrations higher than United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L, however these wells are located onsite and not available as a drinking water source.

Although tritium is detected in a large number of these wells, it is important to note that the majority were installed in areas of historic spills or close to piping containing tritiated water (Table B-I.1, Appendix B).

Strontium Samples were collected and analyzed for strontium activity (Table B-II. 1.

Appendix B). Strontium was detected at a concentration greater than 1 pCi/I at one sampling location (MW-DN-1 05-S). The concentrations ranged from 2.1 to 4.3 pCi/L.

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples throughout the sampling year in 2011. Gross Alpha (dissolved) was detected in two groundwater locations (DSP-122 and MW-DN-107-S). The concentrations ranged from 6.4 to 6.9 pCi/L. Gross Alpha (suspended) was detected in three groundwater locations (MW-DN-102-1, MW-DN-107-S, MW-DN-122-1). The concentrations ranged from 2.0 to 3.2 pCi/L. Gross Beta (dissolved) was detected in all 15 of the groundwater locations (DSP-1 07, DSP-122, DSP-1 23, DSP-124, DSP-1 25, MD-1 1, MW-DN-1 02-1, MW-DN-1 02-S, MW-DN-1 04-S, MW-DN-106-S, MW-DN-107-S, MW-DN-1 08-1, MW-DN-1 13-1, MW-DN-113-S, and MW-DN-122-1). The concentrations ranged from 2.8 to 71.8 pCi/L. Gross Beta (suspended) was detected in two groundwater locations (MW-DN-107-S and MW-DN-122-1). The concentrations ranged from 5.9 to 6.5 pCi/L. The concentrations of Gross Alpha and Gross Beta, which are slightly above detectable levels, are considered to be background and are not the result of plant effluents.

Gamma Emitters Naturally-occurring K-40 was detected in one sample (MW-DN-120-1) at a concentration of 68 pCi/L. No other gamma emitting nuclides were detected (Table B-1.2, Appendix B).

Hard-To-Detects Hard-To-Detect analyses were performed on 16 groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-233/234, U-235 and U-238. The isotope U-233/234 was detected at eight of 16 groundwater monitoring locations (DSP-1 23, MW-DN-1 02-1, MW-DN-1 04-S, MW-DN-1 06-S, MW-DN-1 07-S, MW-DN-1 08-1, MW-DN-113-S, MW-DN-122-1). The 234 concentrations ranged from 0.17 to 1.09 pCi/L. The isotope U-238 was detected at seven of 16 groundwater monitoring locations (MW-DN-104-S, MW-DN-106-S, MW-DN-107-S, MW-DN-1 08-1, MW-DN-1 13-S, MW-DN-1 22-1, MW-DN-124-1).

The U-238 concentrations ranged from 0.15 to 0.85 pCi/L (Table B-1.3, Appendix B). The concentrations detected are considered background.

All other hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs.

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-I.1, Appendix B). Tritium values ranged from the detection limit to 449 pCi/I.

The measurable concentrations of tritium are from an upstream source.

Strontium Samples were collected and analyzed for strontium activity (Table B-II. 1.

Appendix B). Strontium was not detected in any samples above the LLD of 1 pCi/l.

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on surface water samples throughout the sampling year in 2011. Gross Alpha (dissolved) was not detected in any of the six surface water locations. Gross Alpha (suspended) was detected in two of six surface water locations (SW-DN-1 01, SW-DN-1 03). The concentrations ranged from 1.1 to 1.4 pCi/L. Gross Beta (dissolved) was detected in all six of the surface water locations. The concentrations ranged from 3.4 to 5.0 pCi/L. Gross Beta (suspended) was detected in one of the six surface water locations (SW-DN-101) at a concentration of 2.9 pCi/L. The concentrations of Gross Alpha and Gross Beta, which are slightly above detectable levels, are considered to be background and are not the result of plant effluents.

Gamma Emitters Naturally occurring K-40 was detected in one sample (SW-DN-1 05) at a concentration of 101 pCi/L. No other gamma emitting nuclides were detected (Table B-11.2, Appendix B).

Hard-To-Detects Hard-To-Detect analyses were performed on six surface water locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-233/234, U-235 and U-238. The isotope U-233/234 was detected at all six surface water monitoring locations. The 234 concentrations ranged from 0.41 to 0.80 pCi/L. The isotope U-238 was detected at all six surface water monitoring locations. The U-238 concentrations ranged from 0.40 to 0.60 pCi/L (Table B-11.3, Appendix B). The concentrations detected are considered background.

All other hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs.

C.

Precipitation Water Results Precipitation Water Samples were collected from 12 precipitation water locations throughout the year in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.

Tritium Samples from 12 locations were analyzed for tritium activity (Table B-I11. 1, Appendix B). Tritium values ranged from the detection limit to 273 pCi/l.

D.

Drinking Water Well Survey No drinking water well surveys were conducted in 2011.

E.

Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE and Environmental Inc. (Midwest Labs) are presented in the AREOR.

F.

Leaks, Spills, and Releases In August 2011, Dresden Station personnel was removing insulation from Condensate Storage Tank line 2/3-3333-6 in order to evaluate condition of piping for proactive repair or replacement. During the removal of the piping insulation, two pin hole leaks were created during the process of chiseling the insulation from the piping. Pin hole leaks were immediately stopped. Source water was 2.793E6 pCi/I and leakage volume is unknown but was reported to be less than half a gallon. All groundwater in the excavation area was collected and treated by the station radiological waste system.

G.

Trends The tritium concentration in the water found near the 2010 LPCI leak is traveling to the east due to the restabilization of the groundwater in the area after dewatering activities to support excavation. The elevated tritium concentrations are expected for the wells in the vicinity (MW-DN-124-S, and MW-DN-1 24-1) as the plume continues to reside in this area.

Tritium concentrations in DSP-1 07, DSP-1 08, DSP-122, DSP-1 23, DSP-149R, MW-DN-1011, MW-DN-1121, MW-DN-1 14S, MW-DN-1161, MW-DN-1 191, and MW-DN-1 241 are decreasing over time.

H.

Investigations Between May and December 2010 there was an excavation project near MW-DN-124S to put a carbon fiber wrap on lines connected to the condensate storage tank (CST). A hole was discovered and repaired in the LPCI line during the excavation project. However, station personnel could not determine if the hole in the pipe was due to deterioration or from excavation activities. Groundwater entering the excavation was extracted and processed through the Station's Radiological Waste system. During the time of the dewatering activities to support excavation of the subject piping, the tritium concentration in MW-DN-124S decreased significantly (from approximately 70,000 - 80,000 pCi/L to approximately 1,000 pCi/L).

Upon completion of the excavation project and groundwater extraction activities, the tritium concentration in MW-DN-124-S returned to near pre-pumping concentrations (approximately 110,000 pCi/I) in June 2011.

The tritium concentration in MW-DN-124S has fluctuated between 11,000 pCi/L (February 2011) and 120,000 (April 2011) in 2011. The elevated tritium concentrations are expected as the plume continues to move through the area.

Actions Taken

1.

Compensatory Actions When the pin hole leaks were identified in August 2011, the pin hole leaks were immediately stopped and the piping was reinforced. All groundwater in the excavation area was collected and treated by the station radiological waste system.

Three additional monitoring wells (MW-DN-125S, -126S, and -

127S) were installed in May 2011 to further evaluate the tritium plume in the area of MW-DN-124S in 2011. These three wells were sampled in 2011 and show no adverse trends.

2.

Actions to Recover/Reverse Plumes No actions were taken in 2011 by Dresden Station in an effort to reverse plume movement.

ARGPPR APPENDIX A LOCATION DESIGNATION

Intentionally left blank

TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2011 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-M DSP-157-S DSP-158-1 DSP-158-M DSP-158-S DSP-159-1 DSP-159-M DSP-159-S MW-DN-101-1 MW-DN-101-S MW-DN-102-1 MW-DN-102-S MW-DN-103-1 MW-DN-103-S MW-DN-104-S MW-DN-105-S MW-DN-106-S MW-DN-107-S MW-DN-108-1 MW-DN-109-1 MW-DN-109-S MW-DN-110-1 MW-DN-110-S MW-DN-11 1-S MW-DN-1 12-1 MW-DN-112-S MW-DN-1 13-1 MW-DN-113-S MW-DN-1 14-1 MW-DN-1 14-S MW-DN-1 15-1 MW-DN-1 15-S MW-DN-1 16-1 MW-DN-1 16-S MW-DN-1 17-1 MW-DN-118-S MW-DN-1 19-1 MW-DN-119-S MW-DN-120-1 MW-DN-120-S MW-DN-121-S Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well 30 feet east of the east wall of the EM Shop 65 feet east of east wall of EM Shop 9 feet east of the east Unit 1 Fuel Pool wall 40 ft east of the Unit 1 Sphere Northeast of Unit 1 Sphere; 825 feet west of Ross Bridge 72 feet north of 2/3 Intake Canal fence 50 feet north of the Radwaste Tank Farm Northeast 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 comer of the Storeroom 210 feet south by southeast of the southeast comer of Maintenance Garage 150 feet east of the southeast comer of liquid hydrogen tank farm fence 33 feet west of the track; 165 feet east of the Security Checkpoint 70 feet east by northeast of the northwest comer of 138 KV yard fence 25 feet south of the south edge of the Employee Parking lot 25 feet south of the south edge of the Employee Parking lot 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 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 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 comer of the Storeroom 75 feet north of the 2/3 Intake Canal fence; east of the Unit 1 Intake Canal 15 feet west by southwest of the Unit 1 CST 7 feet southwest of the southwest comer of the Unit 1 Cribhouse 8 feet north of Chemistry Building 8 feet north of Chemistry Building 25 feet west of the Waste Water Treatment (WWv) 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 A-1

TABLE A-i:

Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2011 Site Site Type Location MW-DN-122-1 MW-DN-122-S MW-DN-123-1 MW-DN-123-S MW-DN-124-1 MW-DN-124-S MW-DN-125-S MW-DN-126-S MW-DN-127-S MD-11 SW-DN-101 SW-DN-102 SW-DN-103 SW-DN-104 SW-DN-105 SW-DN-106 FW-1 FW-2 FW-3 FW-4 FW-5 FW-6 FW-7 FW-8 FW-9 FW-10 FW-1 1 FW-12 Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water 150 feet north of Collins Road; northeast of the G.E. Fuel Storage Facility 150 feet north of Collins Road; northeast of the G.E. Fuel Storage Facility 400 feet west of the Thorsen house; west of the Cold Canal 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 40 feet east of 2/3 B CST 15 feet south of fence around Unit 2/3 A CST and B CST (outside of fence) 20 feet south of Unit 3 HRSS Piping located between Condensate Storage 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 Precipitation 40 feet southwest of Unit 2/3 Off-gas Filter Building access door, north end of guardrail Precipitation 50 feet East of Chem Feed Trailer Precipitation South of Stock Truck Bay rollup door Precipitation Southeast comer of Unit 3 RB Interlock Precipitation East of Unit 2/3 Intake Ross barrier Precipitation North of Unit 1 Chimney Precipitation Southeast of Unit 2 TB Trackway Precipitation Southwest comer of 2/3 CST on fence Precipitation South of MUDS Building on Security fence Precipitation At the fence at the northwest corner of the SBO Building Precipitation 30 feet east of the east wall of the EM shop; at the stanchion for RGPP well DSP-1 05 Precipitation 60 feet southeast of the southwest comer of the Admin Building; on the security fence A-2

ARGPPR APPENDIX B DATA TABLES

Intentionally left blank

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE DSP-105 DSP-105 DSP-105 DSP-105 DSP-106 DSP-106 DSP-106 DSP-106 DSP-107 DSP-107 DSP-107 DSP-107 DSP-108 DSP-108 DSP-108 DSP-108 DSP-117 DSP-121 DSP-122 DSP-122 DSP-122 DSP-122 DSP-122 DSP-122 DSP-122 DSP-123 DSP-123 DSP-123 DSP-123 DSP-124 DSP-124 DSP-124 DSP-124 DSP-124 DSP-125 DSP-125 DSP-125 DSP-125 DSP-126 DSP-126 DSP-147 DSP-147 DSP-148 DSP-148 DSP-148 DSP-148 DSP-149R DSP-149R DSP-149R DSP-149R COLLECTION DATE 02/23/11 06107/11 08/04/11 12/01111 02/23/11 06/07/11 08/04/11 12/01/11 02/23/11 06/03/11 08104111 11/30/11 02/23/11 06/09/11 08/04/11 11/30/11 02/28/11 02/28/11 02/22/11 02/22/11 06/10/11 08/05/11 11/29/11 11/29/11 Rec 11/29/11 Rea 02/23/11 06/10/11 08105/11 11130111 02/25/11 06/07/11 06/07/11 Rea 08/03/11 11/29/11 02/24/11 06/02/11 08/02/11 11128111 03/02/11 06/13/11 03/02/11 06/13/11 02/28/11 06/01/11 08/08/11 12/05/11 02128111 06/01/11 08/08/11 12/05/11 H-3 SR-90 GR-A (DIS)

GR-A (SUS)

GR-B (DIS)

GR-B (SUS) ount nalysis <

218 +/- 107 278 +/- 111 198 193 3060 +/- 350 3030 +/- 352 2980 +/- 350 2710 +/- 327 3830 +/- 426 4200 +/- 466 3740 +/- 421 3550 +/- 407 1260 +/- 175 976 +/- 158 858 +/- 155 873 +/- 167 165 164 854 +/- 141 922 +/- 153 2300 +/- 280 1480 +/- 205 193 193 185 7740 +/- 816 3410 +/- 388 2880 +/- 338 2590 +/- 314 5240 +/- 568 11700 +/- 1210 11700 +/- 1210 7040 +/- 749 9600 +/- 1010 226 +/- 112 176 177 198 165 165 167 166 293 +/- 117 341 +/- 127 189 237 +/- 125 258 +/- 115 211 +/- 120 189 181

0.8

< 0.8

< 0.6

< 0.8

0.8

< 1.1

<0.3

< 0.6

< 0.8

< 0.5

< 0.9

< 0.8

< 0.6 6.9 +/- 2.5

< 0.2

< 0.9

<0.9

< 4.9 7.0 +/- 1.2

< 1.1

< 0.6

< 1.3 44.6 +/- 2.5

< 1.1 7.9 +/- 1.3

< 1.7 13.0 +/- 1.5

< 1.7 27.3 +/- 3.8

< 4.0 nalysis B-1

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 GR-A (DIS)

GR-A (SUS)

GR-B (DIS)

GR-B (SUS)

DSP-150 DSP-150 DSP-150 DSP-150 DSP-151 DSP-151 DSP-151 DSP-151 DSP-152 DSP-153 DSP-154 DSP-154 DSP-156 DSP-1 56 DSP-1 56 DSP-156 DSP-1 57-1 DSP-1 57-M DSP-1 57-S DSP-157-S DSP-158-M DSP-158-S DSP-159-1 DSP-159-M DSP-1 59-S DSP-159-S MD-1I MD-11 MD-11 MD-11 MD-11 MW-DN-101-1 MW-DN-101-1 MW-DN-101-1 MW-DN-101-1 MW-DN-101-S MW-DN-101-S MW-DN-101-S MW-DN-101-S MW-DN-102-1 MW-DN-102-1 MW-DN-102-1 MW-DN-102-1 MW-DN-102-S MW-DN-102-S MW-DN-102-S MW-DN-102-S MW-DN-103-1 MW-DN-103-1 MW-DN-103-S 02/23/11 06/13/11 08/04/11 12/01/11 02/23/11 06/13/11 08/04/11 12/01/11 03/01/11 03/02/11 03/01/11 06/07/11 02/28/11 06/01/11 08/08/11 12/05/11 06/08/11 03/01/11 03/01/11 06108/11 03/01/11 03/01/11 06/08/11 03/02/11 03/02/11 06/08/11 06/02/11 08/02/11 11/28/11 11/28/11 11/28/11 02/23/11 06/09/11 08/05/11 11/30/11 02/23/11 06/09/11 08/05/11 11/30/11 02/24/11 06/03/11 08/03/11 12/02/11 02/24/11 06/03/11 08/03/11 12/02/11 3/1/2011 06/08/11 03/01/11

< 164

< 162

< 181

< 192

< 167

< 183

<184

< 194

< 169

< 165

< 167

< 168 301 +/- 117 330 +/- 126 252 +/- 129

< 187

< 171

< 164

< 166

< 172

< 159

< 167 357 +/- 126 267 +/- 115

< 159

< 171 6800 +/- 722 47900 +/- 4600 79400 +/- 7950 Recount 85000 +/- 8540 Reanalysis 82900 +/- 8320 897 + 148 1100 + 168 947 + 157 989 +/- 161

166

170

168

<184

167

171

170

183

163 195 + 115

< 168

186

148

171

171

<0.8

< 0.8

< 0.7

< 0.8

<0.7

< 1.0

< 3.2

< 0.6 71.8 +/- 3.6

< 1.8

< 0.8

< 0.9

< 0.8

< 1.0

< 0.7

< 9.4 2.0 1.2 4.4 +/- 1.0

<2.1

< 3.6 32.8 +/- 7.8

< 7.3 B-2

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-DN-103-S MW-DN-104-S MW-DN-104-S MW-DN-104-S MW-DN-104-S MW-DN-104-S MW-DN-104-S MW-DN-104-S MW-DN-105-S MW-DN-105-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-107-S MW-DN-108-1 MW-DN-108-1 MW-ON-108-1 MW-DN-108-1 MW-DN-109-1 MW-DN-109-1 MW-DN-109-1 MW-DN-109-1 MW-DN-109-S MW-DN-109-S MW-DN-109-S MW-DN-109-S MW-DN-110-1 MW-DN-110-1 MW-DN-110-1 MW-DN-110-1 MW-DN-110-S MW-DN-110-S MW-DN-110-S MW-DN-110-S MW-DN-111-S MW-DN-111-S MW-DN-111-S MW-DN-111-S MW-DN-1 12-1 MW-DN-1 12-1 MW-DN-1 12-1 MW-DN-112-1 MW-DN-1 12-S MW-DN-1 12-S MW-DN-1 12-S MW-DN-1 12-S COLLECTION DATE 06/08/11 02/22/11 06/10/11 08/05/11 11/29/11 11/29/11 Reo 11/29/11 Rea 11/29/11 Rea 02/23/11 06/13/11 08/04/11 12/01/11 02/28/11 06/01/11 06/02/11 08/05/11 12/02/11 02/22/11 06/10/11 08/05/11 11/30/11 02/22/11 06/13/11 08/03/11 11/29/11 02/22/11 06/13/11 08/03/11 11/29/11 02/22/11 06/10/11 08/03/11 11/29/11 02/22/11 06/10/11 08/03/11 11/29/11 02/25/11 06107/11 08/03/11 11/29/11 02/22/11 06/02/11 08/03/11 11/29/11 02/22/11 06/02/11 08/03/11 11/29/11 H-3 SR-90 GR-A (DIS)

GR-A (SUS)

GR-B (DIS)

GR-B (SUS) ount nalysis nalysis

< 169 185 +/- 110

< 168

< 169 1950 +/- 250 1820 +/- 235 1860 +/- 240 1920 +/- 247

< 166

167

171

169

147

171 944 +/- 155 626 +/- 141 747 +/- 142

<164

169

171

< 166

164 184 +/- 109

167

165 197 +/- 110 239 +/- 114

165

176 212 +/- 109 202 +/- 115

179 239 +/- 119

160

166

182

172 224 +/- 111

172

177 300 +/- 123 1010 +/- 158 361 +/- 116 261 +/- 121

172

160

171

179

169

< 0.7

< 2.4

< 0.6 23.3 +/- 2.1

< 1.7 4.3 +/- 0.5 2.2 +/- 0.4

< 0.6 2.1 +/- 0.4

< 0.8

< 0.6

< 1.0

< 0,8

< 0.9

< 1.4

< 1.2 3.6 t 1.4

< 2.0 68.5 +/- 3.0 5.9 +/- 1.5 15.1 +/- 1.6

< 1.7 6.4 +/- 3.2 2.5 +/- 0.7

< 1.4

< 0.6 B-3

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-DN-113-1 MW-DN-1 13-1 MW-DN-1 13-1 MW-DN-1 13-1 MW-DN-1 13-S MW-DN-1 13-S MW-DN-113-S MW-DN-1 13-S MW-DN-114-1 MW-DN-114-1 MW-DN-114-1 MW-DN-114-1 MW-DN-1 14-S MW-DN-1 14-S MW-DN-1 14-S MW-DN-115-1 MW-DN-1 15-1 MW-DN-1 15-1 MW-DN-1 15-1 MW-DN-1 15-S MW-DN-1 15-S MW-DN-1 15-S MW-DN-115-S MW-DN-1 16-1 MW-DN-1 16-1 MW-DN-1 16-1 MW-DN-1 16-1 MW-DN-1 16-S MW-DN-1 16-S MW-DN-116-S MW-DN-116-S MW-DN-118-S MW-DN-1 18-S MW-DN-118-S MW-DN-i 18-S MW-DN-1 19-1 MW-DN-1 19-1 MW-DN-1 19-1 MW-DN-1 19-S MW-DN-119-S MW-DN-1 19-S MW-DN-120-1 MW-DN-120-S MW-DN-121-S COLLECTION DATE 02/24/11 06/03/11 08/03/11 12/02/11 02/24/11 06/03/11 08/03/11 12/02/11 02/24/11 06/03/11 08/03/11 12/01/11 06/03/11 08/03/11 12/01/11 02/24/11 06/09/11 08/04/11 12/01/11 02/24/11 06/09/11 08/04/11 12/01/11 02/22/11 06/10/11 08/05/11 11/30/11 02/22/11 06/10/11 08/05/11 11/30/11 02/23/11 06/07/11 08/04/11 11/30/11 06/09/11 08/05/11 11/30/11 06/09/11 08/05/11 11/30/11 02/28/11 02/28/11 03/02/11 H-3 SR-90 GR-A (DIS)

GR-A (SUS)

GR-B (DIS)

GR-B (SUS)

< 163

< 172

< 179

< 185

< 159

< 170

< 177

< 185 7770 +/- 818 6590 +/- 705 1770 +/- 232 7190 +/- 762 1640 +/- 218

180

< 190 342 +/- 115

< 174 235 +/- 122 279 +/- 128 215 +/- 107 242 +/- 121 265 +/- 125

< 187 390 +/- 118 191 +/- 116 328 +/- 127 276 +/- 131 307 +/- 112 399 +/- 128 346 +/- 129 449 +/- 142 2820 +/- 325 1300 +/- 187 800 +/- 153 1100 +/- 173

< 174

< 185

< 184

< 175

< 183

< 185

< 145

< 146

< 165

< 0.9

< 0.5

<2.3

< 1.2

< 0.6 2.8 +/- 0.8

< 2.0 8.7 +/- 1.8

< 1.8

< 0.9

<0.7

< 0.7

< 0.9 B-4

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-DN-122-1 MW-DN-122-1 MW-DN-122-1 MW-DN-122-S MW-DN-122-S MW-DN-123-1 MW-DN-123-S MW-DN-124-1 MW-DN-124-1 MW-DN-124-1 MW-DN-124-1 MW-DN-124-S MW-DN-124-S MW-DN-124-S MW-DN-124-S MW-DN-125-S MW-DN-125-S MW-DN-125-S MW-DN-126-S MW-DN-126-S MW-DN-126-S MW-DN-126-S MW-DN-126-S MW-DN-126-S MW-DN-127-S MW-DN-127-S MW-DN-127-S COLLECTION DATE 03/02/11 03/02/11 06/13/11 03/02/11 06/13/11 03/02111 03/02/11 02/25/11 06/06/11 08/02/11 12/02/11 02/25/11 06/06/11 08/02/11 12/02/11 06/06/11 08/02/11 12/02/11 06/06/11 08/02/11 12/02/11 12/02111 Rec 12/02/11 Rea 12/02/11 Rea 06/06/11 08/02/11 12/02/11 H-3 SR-90 GR-A (DIS*

GR-A ('SUS*

GR-B (DIS*

GR-B (SUS*

GR-A (DIS)

GR-A (SUS)

GR-13 (DIS)

GR-13 (SLIS)

< 144

162

<144

165

145

146 57400 t 5770 73100 +/- 7340 50200 +/- 4310 53900 +/- 5410 28600 +/- 2900 43500 +/- 4390 67300 +/- 6740 51500 +/- 5190

173

170

< 186

< 174

< 172 2420 +/- 293 2640 +/- 317 2930 +/- 342 3120 +/- 364 192 +/- 117 269 +/- 122 474 +/- 143

< 0.8

<0.7

< 0.9

< 0.6

< 0.8

< 1.4 3.2 +/- 1.7 3.3 +/- 1.9 6.5 +/- 2.25

<2.1

<0.3 18.0 +/- 1.8

< 1.1

< 0.9

< 0.6

< 0.6 ount nalysis nalysis B-5

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 DATE Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DSP-105 06/07/11 DSP-105 08/04/11 DSP-106 06/07/11 DSP-106 08/04/11 DSP-107 02/23111 DSP-107 06/03/11 DSP-107 08/04/11 DSP-108 06/09/11 DSP-108 08/04/11 DSP-122 02/22/11 DSP-123 02/23/11 DSP-123 06/10/11 DSP-123 08/05/11 DSP-124 02/25/11 DSP-124 06/07/11 DSP-125 06/02/11 DSP-126 06/13/11 DSP-147 06/13/11 DSP-154 06/07/11 DSP-157-1 06/08/11 DSP-157-S 06/08/11 DSP-159-1 06108/11 DSP-159-S 06/08/11 MW-DN-1 01 -I 06/09/11 MW-DN-101-I 08/05/11 MW-DN-101-S 06/09/11 MW-DN-101-S 08/05/11 MW-DN-102-1 06/03/11 MW-DN-1 02-S 06/03/11 MW-DN-103-1 06/08/11 MW-DN-103-S 06/08/11 MW-DN-104-S 02/22/11 MW-DN-105-S 02/23/11 MW-DN-1 05-S 06/13/11 MW-DN-105-S 08/04/11

< 12

< 35

<27

<56

< 13

< 10

< 26

< 56

< 20

< 39

< 11

<25

< 34

< 83

<8

<18

< 31

< 33

<38

<34

< 21

< 45

<8

<11

< 26

< 16

< 32

<10

<8

< 47

< 87

< 41

< 63

< 28

< 33

<10

<9

< 11

<25

< 12

<25

<6

<4

< 10

< 31

< 41

< 43

< 30

< 28

< 47

< 122

< 25

< 52

< I

<1

< 3

<3

<6

<1

<2

<3

<6

<2

<5

<1

<2

<4

<9

<1

<2

<3

<7

<3

<8

<2

<5

<1

<2

<3

<6

<2

<4

<1

<2

<5

<12

<4

<5

<9

<3

<7

<1

<2

<1

<2

<1

<3

<1

<3

<5

<4

<10

<3

<6

<10

<3

<6

<5

<6

<12

<5

<6

<13

<6

<5

<14

<4

<5

<8

<1

<3

<2

<4

<3

<4

<8

<3

<7

<1

<2

<3

<6

<1

<2

<3

<7

<2

<4

<1

<2

<4

<8

<1

<2

<3

<6

<4

<8

<2

<5

<1

<3

<6

<2

<3

<1

<2

<5

<11

<4

<9

<3

<6

<1

<2

<1

<2

<1

<2

<1

<2

<5

<7

<3

<6

<5

<14

<3

<6

<5

<12

<5

<14

<6

<12

<5

<8

<1

<3

<1

<3

<4

<8

<3

<6

<2

<3

<6

<1

<3

<5

<2

<4

<1

<2

<4

<7

<1

<3

<6

<4

<6

<2

<4

<1

<3

<5

<2

<3

<1

<2

<6

<8

<4

<7

<4

<6

<1

<2

<1

<2

<1

<2

<1

<2

<6

<9

<3

<6

<11

<3

<5

<6

<11

<6

<11

<6

<10

<5

<7

<2

<3

<2

<3

<4

<8

<4

<6

<11

<1

<7

<3

<12

<1

<7

<3

<8

<2

<13

<1

<9

<4

<10

<1

<8

<3

<15

<4

<8

<2

<8

<1

<6

<3

<6

<2

<9

<1

<15

<5

<15

<4

<13

<3

<10

<1

<10

<1

<14

<1

<7

<0

<13

<1

<14

<5

<8

<3

<12

<5

<7

<3

<13

<7

<15

<7

<15

<5

<13

<3

<6

<1

<7

<1

<14

<3

<8

<3

<1

<3

<1

<3

<2

<1

<4

<1

<3

<4

<2

<1

<3

<2

<1

<5

<4

<3

<1

<0

<1

<6

<4

<5

<3

<7

<6

<5

<1

<2

<4

<17

<5

<18

<5

<16

<6

<18

<7

<16

<5

<16

<4

<23

<8

<12

<4

<20

<6

<28

< 10

<17

<5

<10

<3

<16

<5

<12

<4

<12

<4

<34

<9

<28

< 10

<25

<7

<14

<5

<12

<4

<18

<5

<9

<3

<18

<6

<29

<9

<19

<6

< 30

< 12

<18

<5

< 33

< 11

< 31

< 12

< 35

< 14

<29

<7

<11

<3

<14

<4

<32

<8

<21

<6

< 64 68 +/- 43

< 58

< 86

< 48

< 102

< 43

<89

< 13

< 12

<16

< 33

<39

< 40

< 31

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DATE MW-DN-106-S 06/01/11 MW-DN-107-S 12/02/11 MW-DN-108-1 02/22/11 MW-DN-108-1 06/10/11 MW-DN-108-1 08/05/11 MW-DN-109-1 06/13/11 MW-DN-109-S 06/13/11 MW-DN-1 13-1 06/03/11 MW-DN-1 13-S 06/03111 MW-DN-1 15-1 06/09/11 MW-DN-1 15-S 06109111 MW-DN-1 16-1 06/10/11 MW-DN-1 16-1 08/05/11 MW-DN-1 16-S 06/10/11 MW-DN-1 16-S 08/05/11 MW-DN-1 18-S 06/07/11 MW-DN-1 18-S 08/04/11 MW-DN-1 19-1 06/09/11 MW-DN-1 19-S 06/09/11 MW-DN-122-1 03/02/11 MW-DN-122-1 06/13/11 MW-DN-122-S 06/13/11 MW-DN-124-1 02/25/11 MW-DN-124-1 06106111 MW-DN-124-S 06/06/11 MW-DN-125-S 06/06/11 MW-DN-126-S 06/06/11 MW-DN-127-S 06/06/11 MD-11 06/02/11

< 62

< 63

< 55

< 144

< 16

< 14

< 62

< 115

< 35

< 73

< 43

< 105

< 37

< 32

< 78

< 64

< 48

< 42

< 51

< 64

<51

<46

< 32

< 34

< 33

< 30

< 46

< 91

< 38

< 72

< 41

< 86

< 34

< 75

< 49

< 60

< 51

< 113

< 48

< 123

< 37

< 36

< 37

< 44

< 23

< 53

<46

<47

< 40

< 70

< 47

< 76

< 43

< 37

< 46

< 41

< 48

< 44

<6

<8

<7

<2

<6

<7

<4

<5

<3

<4

<7

<6

<5

<6

<4

<3

<4

<5

<4

<5

<4

<6

<5

<6

<5

<4

<5

<3

<4

<5

<4

<5

<6

<5

<6

<13

< 14

<4

< 11

<8

< 11

<9

< 11

<9

12

< 10

<7

<9

10

10

< 11

13

12

<9

<8

<5

< 10

<9

< 11

<8

< 10

< 11

<5

<7

<2

<6

<4

<5

<3

<6

<5

<3

<4

<5

<7

<5

<4

<2

<5

<4

<5

<4

<13

<6

<15

<8

<3

<2

<14

<7

<8

<5

<8

<4

<7

<4

<11

<7

<9

<7

<9

<7

<13

<7

<9

<5

<6

<4

<8

<6

<7

<4

<8

<5

<9

<4

<10

<5

<13

<8

<9

<7

<5

<8

<4

<5

<3

<10

<5

<7

<5

<8

<6

<9

<6

<10

<5

<10

<5

<10

< 11

<3

< 11

<7

<10

<6

<9

<11

<8

<5

<9

<8

<7

<9

< 11

<10

<7

<5

<9

<8

<9

<8

<9

<8

<15

<6

<14

<6

<7

<1

<15

<6

<9

<3

<15

<4

<15

<3

<14

<7

<14

<5

<13

<5

<13

<6

<11

<4

<9

<3

<11

<5

<10

<4

<13

<4

<10

<3

<13

<5

<12

<5

<14

<5

<14

<4

<15

<3

<8

<2

<15

<4

<14

<4

<15

<4

<15

<4

<15

<5

<14

<5

<2

<7

<4

<5

<4

<7

<6

<5

<6

<5

<3

<5

<4

<6

<5

<4

<3

<5

<4

<5

< 38

< 39

13

< 36

< 23

< 37

< 29

41

< 38

29

< 34

< 24

< 20

31

< 26

< 32

< 26

< 34

< 33

< 32

< 34

< 29

<18

32

< 28

32

31

< 36

< 31

<15

<4

<13

<9

<8

<9

<8

<11

<8

< 10

<9

<11

10

<13

<9

<10

10

<6

< 10

<6

< 10

< 11

<8

< 12

TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION AM-241 DATE CM-242 CM-243/244 PU-238 PU-239/240 U-233/234 U-235 U-238 FE-55 NI-63 IDSP-107 DSP-122 DSP-123 DSP-124 DSP-125 MD-11 MW-DN-102-1 MW-DN-102-S MW-DN-104-S MW-DN-106-S MW-DN-107-S MW-DN-108-1 MW-DN-1 13-1 MW-DN-1 13-S MW-DN-122-1 MW-DN-124-1 02/23/11 02/22/11 02/23/11 02/25/11 06/02/11 06/02/11 06/03/11 06/03/11 02/22/11 06/01/11 12/02/11 02/22/11 06/03/11 06103/11 03/02/11 02/25/11

< 0.10

< 0.12

< 0.15

< 0.19

< 0.08

< 0.14

< 0.08

< 0.14

< 0.13

< 0.15

< 0.13

< 0.10

< 0.06

< 0.12

< 0.14

< 0.04

< 0.07

< 0.08

< 0.14

< 0.05

< 0.08

< 0.10

< 0.08

< 0.05

< 0.04

< 0.07

< 0.10

< 0.03

< 0.05

< 0.08

< 0.02

< 0.03

< 0.09

< 0.04

< 0.12

< 0.08

< 0.04

< 0.15

< 0.05

< 0.03

< 0.06

< 0.10

< 0.02

< 0.12

< 0.03

< 0.05

< 0.02

< 0.09

< 0.10

< 0.14

< 0.06

< 0.20

< 0.16

< 0.08

< 0.13

< 0.14

< 0.13

< 0.16

< 0.05

< 0.08

< 0.04

< 0.02

< 0.09

< 0.10

< 0.04

< 0.09

< 0.08

< 0.07

< 0.05

< 0.06

< 0.02

< 0.03

< 0.09

< 0.17 0.17 +/- 0.10

< 0.04

< 0.13

< 0.06 0.58 +/- 0.21

< 0.11 0.85 +/- 0.36 1.09 +/- 0.26 0.37 +/- 0.23 0.38 +/- 0.17

< 0.09 0.54 +/- 0.23 0.32 +/- 0.15

< 0.05

< 0.02

< 0.08

< 0.04

< 0.06

< 0.03

< 0.06

< 0.20

< 0.06

< 0.05

< 0.09

< 0.03

< 0.02

< 0.07

< 0.03

< 0.05

< 0.08

< 145

< 4.2

< 0.16

< 130

< 4.2

< 0.07

< 149

< 4.3

< 0.06

< 64

< 4.2

< 0.19

< 95

< 3.4

< 0.08

< 123

< 3.7

< 0.11

< 199

< 3.7

< 0.11

< 80

< 3.4 0.44 +/- 0.26

< 136

< 4.2 0.85 +/- 0.22

< 193

< 3.7 0.43 +/- 0.24

< 151

< 3.9 0.21 +/- 0.12

< 141

< 4.2

< 0.06

< 164

< 3.7 0.30 +/- 0.17

< 122

< 3.7 0.35 +/- 0.16

< 184

< 3.8 0.15 +/- 0.09

< 189

< 4.2

,0

TABLE B-II.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE SW-DN-101 SW-DN-101 SW-DN-101 SW-DN-101 SW-DN-102 SW-ON-102 SW-DN-102 SW-DN-102 SW-DN-103 SW-DN-103 SW-DN-103 SW-DN-103 SW-DN-104 SW-DN-104 SW-DN-104 SW-DN-104 SW-DN-105 SW-DN-105 SW-DN-105 SW-DN-105 SW-DN-106 SW-DN-106 SW-DN-106 SW-DN-106 COLLECTION DATE 02/28/11 06/01/11 08/08/11 12/05/11 02/28/11 06/01/11 08/08/11 12/05/11 02/28/11 06101/11 08/08/11 12105/11 03/02/11 06/01/11 08/08/11 12/05/11 03/02/11 06101/11 08/08/11 12/05/11 03/02/11 06/01/11 08/08/11 12/05/11 H-3 SR-90 GR-A (DIS)

GR-A (SUS) GR-B (DIS)

GR-B (SUS)

< 148 449 +/- 129

< 191

< 185 345 +/- 106 214 t 119

< 190

< 187 248 +/- 102 178 +/- 117

< 191

< 184 216 +/- 101 183 +/- 120

< 189

< 185 185 +/- 99

< 171 282 +/- 129

< 188 200 +/- 115

< 172

< 192

< 183

<0.9

< 0.9

< 1.0

< 0.9

< 1.0

< 1.1

< 1.1 1.4 +/- 0.9 4.6 +/- 1.2 2.9 +/- 1.4

<0.7 3.8 +/- 1.3

< 1.8 1.1 +/- 0.7 3.4 + 1.3

< 1.9

< 1.1

< 0.5

< 1.1

< 0.5 4.7 +/- 1.3

< 1.9 5.0 +/- 1.4

< 1.9 4.0 +/- 1.3

< 1.9

<1.0

<1.1

<0.5 B-9

TABLE B-1I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 DATE 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 06/01/11 06/01/11 06/01/11 06/01/11 06/01/11 06/01/11

< 44

< 47

< 48

< 41

< 43

< 42

<46

<4

<33

< 5

<42

< 5

<98

< 5 101 +/- 54 < 4

<38

<3

<5

<8

<9

<5

<4

<9

<8

< 11

10

< 10

<5

<7

<14

<4

<5

<28

<10

<6

<9

<14

<5

<30

<12

<5

<9

<14

<5

<4

<32

<9

<5

<9

<14

<5

<31

<8

<5

<8

<14

<5

<32

<9

<5

<9

<15

<5

<4

<34

<11

<5

<8

<4

<5

<9

<4

<5

<9

<4

TABLE B-II.3 CONCENTRATIONS OF HARD TO DETECTS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE SW-DN-101 SW-DN-1 02 SW-DN-1 03 SW-DN-104 SW-DN-105 SW-DN-106 COLLECTION AM-241 DATE 06/01/11

< 0.13 06/01/11

< 0.12 06/01/11

< 0.04 06/01/11

< 0.05 06/01/11

< 0.02 06/01/11

< 0.06 CM-242 CM-243/244 PU-238 PU-239/240 U-233/234 U-235 U-238 FE-55 NI-63

< 0.10

< 0,06

< 0.05

< 0.04

< 0.13

< 0.05

< 0.03

< 0.02

< 0.17

< 0.06

< 0.19

< 0.10

< 0.13

< 0.07

< 0.11

< 0.05

< 0.17

< 0.05 0.41 0.44 0,67 0.80 0:55 0.49

+/- 0.18

+/- 0.23

+/- 0.32

+/- 0.21

+/- 0.20

< 0.03

< 0.07

< 0.09

< 0.07

< 0.08 0.55 0.53 0.41 0.48 0.40 0.60

+/- 0.22

+/- 0.20

+ 0.18

+/- 0.24

+/- 0.19

+/- 0.21

<94

< 125

< 106

< 93

< 107

< 140

< 3.8

< 3.7

TABLE B-II.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION DATE SITE FW-1 FW-1 FW-10 FW-10 FW-11 FW-1 1 FW-12 FW-12 FW-2 FW-2 FW-3 FW-3 FW-4 FW-5 FW-6 FW-7 FW-7 FW-8 FW-8 FW-9 FW-9 H-3 02/22/11 06/10/11 02/22/11 12/01/11 02/22/11 12/01/11 02/22/11 12/02/11 02/22/11 06/10/11 02/22/11 06110111 02/22/11 02/22/11 02/22/11 02/22/11 08/04/11 02/22/11 08/02/11 02/22/11 08/03/11

< 163

< 172

< 164

< 185

< 164

< 187

< 164

< 191

< 166

< 169 273 t 114

< 171

< 164

< 169

< 165

< 164

< 171

< 165

< 170 223 t 111

< 169 B-12

SVPLTR 12-0025, 2011 Annual Radiological Environmental Operating Report

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