Text

Annual Radiological Environmental Operating Report
	ML081370356
Person / Time
Site:	Dresden
Issue date:	05/15/2008
From:	Wozniak D; Exelon Generation Co, Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, SVPLTR # 08-0027
	Download: ML081370356 (133)
	v • d • e

Exelon Generation Company, LLC www.exeloncorp.com Exelno Dresden Nuclear Power Station Nuclear 650o North Dresden Road Morris, IL60450-9765 May 15, 2008 SVPLTR # 08-0027 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 1, 2, and 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-1 9 and DPR-25 NRC Docket Nos.50-010, 50-237, and 50-249

Subject:

2007 Annual Radiological Environmental Operating Report Enclosed is the Dresden Nuclear Power Station (DNPS) 2007 Annual Radiological Environmental Operating Report for Units 1, 2, and 3. Exelon Generation Company, LLC (EGC) is submitting this report in accordance with DNPS Unit 1 Technical Specification (TS),

6.9.A.3, "Annual Radiological Environmental Operating Report," and DNPS Units 2 and 3 TS 5.6.2, "Annual Radiological Environmental Operating Report." This report provides the results of the radiological environmental and meteorological monitoring programs for the 2007 calendar year.

In addition, Appendix F of the report contains the results of DNPS groundwater monitoring conducted in accordance with EGC 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 Bob Rybak, Acting Regulatory Assurance Manager, at (815) 416-2810.

Respectfully, David B. Wozniak ;

Site Vice President Dresden Nuclear Power Station Attachment - Annual Radiological Environmental Operating Report cc: Regional Administrator - NRC Region III NRC Senior Resident - Dresden Nuclear Power Station

Docket No: 50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Environmental Operating Report 1 January Through 31 December 2007 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Dresden Nuclear Power Station Morris, IL 60450 May 2008

Table Of Contents

1. Summary and Conclusions ..................... ................................................ 1

11. Introduction ....................................................................................... 3 A. Objectives of the REMP ................................................................ 3 B. Implementation of the Objectives ...................................................... 3 Ill. Program Description ..................................................... I....................... 4 A. Sample Collection ....................................................................... 4 B. Sample Analysis ......................................................................... 5 C. Data Interpretation....................................................................... 6 D. Program Exceptions...................................................................... 7 E. Program Changes ...................................... I................................. 9 IV. Results and Discussion ................................................... ................. 9 A. Aquatic Environment.................................................................... 9

1. Surface Water....................I....I............................................. 9

2. Ground Water ................. ................................................. 10

3. Fish .............................................................................. 11

4. Sediment ........................................................................ 11

5. Dredging Spoils ................................................................ 11 B. Atmospheric Environment............................................................. 12

1. Airborne ......................................................................... 12

a. Air Particulates .......................................... 12

b. Airborne Iodine ......................................................... 13

2. Terrestrial ........................................................................ 13

a. Milk ...................................................................... 13

b. Food Products.......................................................... 13 C. Ambient Gamma Radiation ........................................................... 14 D. Land Use Survey....................................................................... 14 E. Errata Data ......................... ... 15 F. Summary of Results - Inter-laboratory Comparison Program..................... 15

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Dresden Nuclear Power Station, 2007 Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Table Table B-i: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2007 Table B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2007 Figures Figure B-i: Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Locations, 2007 Figure B-2: Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2007 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-1.2 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-11.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

ii

Table C-1I.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-l11.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-IV.2 Concentrations of Gamma Emitters in Dredge Spoil Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-VI.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-VII.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-VIII.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table C-IX.1 Quarterly TLD Results for Dresden Nuclear Power Station, 2007.

Table C-IX.2 Mean Quarterly TLD Results for the Inner Ring, Outer Ring, Other and Control Locations for Dresden Nuclear Power Station, 2007.

Table C-IX.3 Summary of the Ambient Dosimetry Program for Dresden Nuclear Power Station, 2007.

Figures~

Figure C-1 Surface Water - Gross Beta - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2007.

Figure C-2 Surface Water - Gross Beta - Stations D-54 (C) and D-57 (C)

Collected in the Vicinity of DNPS, 2002 - 2007.

Figure C-3 Surface Water - Gross Beta - Station D-21 Collected in the Vicinity of DNPS, 2007.

iii

Figure C-4 Surface Water - Tritium - Stations D-51 and D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2007.

Figure C-5 Surface Water - Tritium - Station D-54 (C) and D-57 (C) Collected in the Vicinity of DNPS, 2002 - 2007.

Figure C-6 Surface Water - Tritium - Station D-21 Collected in the Vicinity of DNPS, 2007.

Figure C-7 Ground Water - Tritium - Stations D-23 and D-35 Collected in the Vicinity of DNPS, 2000 - 2007.

Figure C-8 Air Particulate - Gross.Beta - Stations D-01 and D-02 Collected in the Vicinity of DNPS, 2000 - 2007.

Figure C-9 Air Particulate - Gross Beta - Stations D-03 and D-04 Collected in the Vicinity of DNPS, 2000 - 2007.

Figure C-10 Air Particulate - Gross Beta - Stations D-07 and D-12 (C) Collected in the Vicinity of DNPS, 2000 - 2007.

Figure C-i 1 Air Particulate - Gross Beta - Stations D-45 and D-53 Collected in the Vicinity of DNPS, 2000 - 2007.

Figure C-12 Air Particulate - Gross Beta - Stations D-08 and D-10 Collected in the Vicinity of DNPS, 2005 - 2007.

Figure C-13 Air Particulate - Gross Beta - Stations D-13 and D-14 Collected in the Vicinity of DNPS, 2005 - 2007.

Figure C-14 Air Particulate - Gross Beta - Stations D-55 and D-56 Collected in the Vicinity of DNPS, 2006 - 2007.

Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2007 Table D-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2007 Table D-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2007 Table D-4 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2007 Table D-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2007 iv

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

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 2007 through 31 December 2007. During that time period, 2,026 analyses were performed on 1,877 samples. In assessing all the data gathered for this report it was concluded that the operation of DNPS had no adverse radiological impact on the environment.

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

Fish (commercially and recreationally important species), sediment and dredge spoil samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish. Sediment and dredge spoil samples had Cesium-137 concentrations consistent with levels observed in previous years. No plant-produced fission or activation products were found in sediment.

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

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

Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. All 1-131 results were below the minimum detectable activity.

Concentrations of naturally occurring K-40 were found. No fission or activation products were found.

Food product samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected.

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

Intentionally left blank

II. Introduction The Dresden Nuclear Power Station (DNPS), consisting of one retired reactor and two operating 912. MWe boiling water reactors owned and operated by Exelon Corporation, is located in Grundy County, Illinois. Unit No. 1 went critical in 1960 and was retired in 1978. Unit No. 2 went critical on 16 June 1970. Unit No. 3 went critical on 02 November 1971. The site is located in northern Illinois, approximately 12 miles southwest of Joliet, Illinois at the confluence of the Des Plaines and Kankakee Rivers where they form the Illinois River.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) Global Dosimetry, and Environmental Inc. Midwest Laboratory (EIML) on samples collected during the period 1 January 2007 through 31 December 2007.

An assessment of the station's radioactive effluent monitoring results and radiation dose via the principle pathways of exposure resulting from plant emissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area, an annual summary of meteorological conditions including wind speed, wind direction, and atmospheric stability, and the result of the 40CFR190 uranium fuel cycle dose analysis for the calendar year are published in the station's Annual Radioactive Effluent Release Report.

A. Objective of the Radiological Environmental Monitoring Program (REMP)

The objectives of the REMP are to:

1. Provide data on measurable levels of radiation and radioactive materials in the site environs.

2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.

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

1. Identifying significant exposure pathways.

2. Establishing baseline radiological data of media within those pathways.

3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.

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 2007. Sample locations and descriptions can be found in Table B-1 and Figures B-1 and B-2, Appendix B. The collection methods used by EIML are listed in Table B-2.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, ground water, fish, sediment, and dredge spoils. Samples were collected from five surface water locations (D-21, D-51, D-52, D-54 and D-57) and composited for analysis. Control locations were D-52, D-54, and D-57. Samples were collected quarterly or more frequently from two well water locations (D-23 and D-35). All samples were collected in new unused plastic bottles, which were rinsed with source water prior to collection. Fish samples comprising the flesh of channel catfish, largemouth bass, common carp and freshwater drum were collected semiannually at two locations, D-28 and D-46 (Control).

Sediment samples composed of recently deposited substrate were collected at one location semiannually, D-27. Samples were also collected from the spoils of dredging of the Illinois River downstream of Dresden Nuclear Power Station in 2007.

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, and food products. Airborne iodine and particulate samples were collected at fourteen locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-13, D-14, D-45, D-53, D-55 and D-56). The control location was D-12.

Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The air filters and air iodine samples were replaced weekly and sent to the laboratory for analysis.

Milk samples were collected biweekly at one control location (D-25) from May through October, and monthly from November through April. There are no milking animals within 10 km of the site. All samples were collected in new unused two gallon plastic bottles from the bulk tank at

each location, preserved with sodium bisulfite, and shipped promptly to the laboratory.

Food products were collected annually in September at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3, and D-Quad 4). The control location was D-Control. Various types of samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.

Ambient Gamma Radiation Direct radiation measurements were made using CaF 2 and LiF thermoluminescent dosimeters (TLD). Each location consisted of 2 TLD sets. The TLD locations were placed on and around the DNPS site as follows:

An inner ring consisting of 16 locations (D-101, D-102, D-103, D-104, D-105, D-106, D-107, D-108, D-109, D-110, D-111, D-112A, D-113, D-1 14, D-1 15 and D-116) at or near the site boundary.

An ou.terring consisting of 16 locations (0-201, 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-13, D-14, D-45, D-53, D-55, and D-56).

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

Two TLDs - each comprised of two CaF 2 and two LiF thermoluminescent phosphors enclosed in plastic - were placed at each location. The TLDs were exchanged quarterly and sent to Global Dosimetry for analysis.

B. Sample Analysis This section describes the general analytical methodologies used by TBE and EIML to analyze the environmental samples for radioactivity for the DNPS REMP in 2007. The analytical procedures used by the laboratories are listed in Table B-2.

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

1. Concentrations of beta emitters in surface water and air particulates.

2. Concentrations of gamma emitters in ground and surface water, air particulates, milk, fish, sediment, dredge spoil 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, Zr-95, Nb-95, 1-131, Cs-134, Cs-1 37, Ba-140, and La-140 were reported.

For fish, sediment, dredge spoil, air particulate and milk 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-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 2007 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 D-56 03/30/07 - 06/29/07 Ba-140 and La-140 MDCs were large due to delay in compositing sample; there are no LLD requirements for these isotopes for this type of sample.

AP/I D-08 06/15/07 - 06/22/07 Low timer reading of 78.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months on 06/22/07 - 06/29/07 06/22/07 due to loss of power to the sampler. Low reading of 77.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months on 06/29/07 due to recent repair and power restoration.

AP/N D-08 11/09/07 - 11/16/07 Sample pump reversed itself due to electrical problem.

AP/I D-1 0 08/17/07 - 08/24/07 Low timer reading of 146.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to storms in area.

AP/I D-1 2 06/15/07 - 06/22/07 Low timer reading of 162.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months due to storms in area.

AP/I D-13 02/09/07 - 02/16/07 Low timer reading of 165.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; cause is unknown.

Table D-1 LISTING OF SAMPLE ANOMALIES (continued' Sample Location Collection Reason Type Code Date AP/I D-14 02/16/07 - 02/24/07 Low timer reading of 84.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months on 02/23/07 - 03/02/07 02/24/07 due to break in power supply line. Low timer reading of 94.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months on 03/02/07 due to recent repair and power restoration.

AP/I D-14 08/17/07 - 08/24/07 Low timer reading of 146.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to storms in area.

AP/I D-14 08/24/07 - 08/31/07 Low timer reading of 62.1 likely due to faulty run time meter. Gross beta on this sample was unusually high.

AP/I D-14 09/14/07 - 09/21/07 Low timer reading of 163.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; cause is unknown.

AP/I D-55 04/06/07 - 04/13/07 Low timer reading of 157.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months due to construction in the area interrupting power.

SW D-21 09/07/07 - 09/28/07 Compositor out of service due to river flooding sample pump pit, monthly composite consisted of weekly grab samples.

SW D-21 11/02/07 - 11/30/07 Compositor out of service due to mechanical problems, monthly composite consisted of weekly grab samples.

TLD D-1 16-1 06/29/07 - 09/28/07 TLD was attached to utility pole that fell during storm, TLD relocated to pole with D-116-2 until repaired.

Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date TLD D-1 03-2 06-29/07 - 09/28/07 TLD missing during quarterly exchange due to suspected vandalism.

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 Surface water station D-54 was taken out of service on 06/28/07 and replaced with surface water station D-57, which was placed in service on 07/24/06.

Surface water station D-51 was taken out of service on 06/29/07 and replaced with surface water station D-21, which was placed in service on 03/30/07.

Air particulate, air iodine and TLD station D-13 was taken out of service on 06/29/07 and replaced with D-55, which was placed in service on 12/30/05.

Starting in 2007, the mean and two standard deviation values are calculated using the positive values only.

IV. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken weekly and composited for analysis at five locations (D-21, D-51, D-52, D-54 and D-57). Of these locations only D-51 and D-21 located downstream, could be affected by Dresden's effluent releases. The following analyses were performed:

Gros Rta Monthly composites from all locations were analyzed for concentrations of gross beta (Table C-1.1, Appendix C). The values ranged from 3.0 to 30.9 pCi/I. Concentrations detected were consistent with those detected in previous years (Figures C-1, C-2,

and C-3, Appendix C).

Quarterly composites from all locations were analyzed for tritium activity (Table C-1.2, Appendix C). The indicator value was 388 pCi/L. Control values ranged from 281 to 1130 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:

All samples were analyzed for tritium activity (Table C-11.1, Appendix C). D-35 values ranged from <160 to <190 pCi/L. D-23 values ranged from 321 to 622 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-7, Appendix C).

Gamma Spectrometry All samples were analyzed for gamma emitting nuclides (Table C-11.2, Appendix.C). No nuclides were detected, and all required LLDs were met.

3. Fish Fish samples comprised of channel catfish, largemouth bass, common carp and freshwater drum were collected at two locations (D-28 and D-46) semiannually. Location D-28 could be affected by Dresden's effluent releases. The following analysis was performed:

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

Naturally occurring K-40 was found at all stations and ranged from 2,260 to 4,780 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.l, Appendix C). Cesium-137 was detected in one sample.

Concentrations of the fission product Cs-1 37 was found in one sample at a concentration of 143 pCi/kg dry. The activity detected was consistent with those detected in previous years and is likely due to fallout from above-ground nuclear weapons testing. No other fission or activation products were detected.

5. Dredging Spoils Dredge Spoil samples were collected when the river was dredged in 2007. The following analysis was performed:

Gamma Spectrometry Dredge Spoil samples were analyzed for gamma emitting nuclides (Table C-IV.2, Appendix C). Cesium-137 was detected in two of the 10 samples analyzed at concentrations of 60 and 61 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 and D-56), Far-field samplers between 4 and 10 km from the site (D-08, D-10, D-13, D-14 and D-55) and the Control sampler between 10 and 30 km from the site (D-12). The following analyses were performed:

GrossBeta 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 45 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 51 E-3 pCi/m 3 with a mean of 21 E-3 pCi/m 3 . The results from the Far-Field locations ranyed from 5 to 73 E-3 pCi/m 3 with a mean of 21 E-3 pCi/m . The results from the Control location ranged from 9 to 49 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m 3 . Comparison of the 2007 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 2007 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 46 of 54 samples and ranged from 48.3 to 160 E-3 pCi/m 3 . No other nuclides were detected, and all required LLDs were met.

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-13, D-14, D-45, D-53, D-55 and D-56) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). No nuclides were detected, and all required LLDs were met.

2. Terrestrial

a. Milk Samples were collected from one location (D-25) biweekly May through October and monthly November through April.

The following analyses were performed:

lodineiM3 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 1,150 to 1,360 pCi/I.

No other nuclides were detected, and all required LLDs were met.

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

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-VIII.1, Appendix C). No nuclides were detected, and all required LLDs were met.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Global Dosimetry 110 Environmental (CaF 2 and LiF) thermoluminescent dosimeters. Forty-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 16 to 31 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 27 August 2007 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 11/2 degree sectors within 10 km around the site. There were no changes required to the DNPS REMP as a result of this survey.

The results of this survey are summarized below.

Distance in Miles from the DNPS Reactor Buildings Sector Residence Livestock Milk Farm Miles Miles Miles AN 1.5 1.4 B NNE 0.8 6.0 C NE 0.8 5.8 D ENE 0.7 1.7 EE 1.1 F ESE 1.0 G SE 0.6 H SSE 0.5 JS 0.5 16.0 K SSW 3.3 L SW 3.6 11.4 MWSW 5.8 NW 3.5 0.5 P WNW 3.7 0.5 Q NW 2.6 0.5 R NNW 0.8 1.0 E. Errata Data There was no errata data discovered in 2007.

F. Summary of Results - Inter-Laboratory Comparison Program The primary laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix D). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of laboratory results and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.

2. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's SOP for the Generation of

Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.

The MAPEP defines three levels of performance: Acceptable (flag =

"A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value.

Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% <

bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.

For the primary laboratory, 17 out of 19 analytes met the specified acceptance criteria. Two samples did not meet the specified acceptance criteria for the following reasons:

1. Teledyne Brown Engineering's Analytics March 2007 1-131 in charcoal result of 34.7 pCi was lower than the known value of 71.3, resulting in a found to known ratio of 0.49. A new technician counted the charcoal cartridge on the back rather than the face side. Due to decay of the 1-131, recounting could not be performed.

Counting the 2nd quarter Analytics charcoal cartridge on the face and the back resulted in approximately 220% more activity on the face of the cartridge. This indicates that we would have had acceptable results (ratio approximately 1.07) if the cartridge had been counted on the face side.

2. Teledyne Brown Engineering's ERA July 2007 Cs-1 34 result of 57.6 pCi/L exceeded the lower acceptance limit of 60.2 pCi/L. The high activity of the sample resulted in the lower acceptance limit of 8.66, although the ratio of found to known was 83.6%, which is considered acceptable by TBE.

For the secondary laboratory, 18 out of 19 analytes met the specified acceptance criteria. One sample did not meet the specified acceptance criteria for the following reasons:

1. Environmental Inc.'s ERA March 2007 air particulate Cs-137 result

of 345.3 pCi/L exceeded the upper control limit of 336 pCi/L. The reported result was calculated using composite filter geometry rather than the single filter geometry. The recalculated result of 305.8 pCi/filter fell within the acceptance limits.

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

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER. GR-B 45 4 9.3 7.4 11.4 D-21 INDICATOR 0 (PCI/LITER) (15/15) (30/30) (9/9) IL RIVER AT EJ&E BRIDGE (5/20.7) (3/30.9) (6.6/20.7) 1.4 MILES WNW OF SITE H-3 15 2000 388 661 661 D-57 CONTROL 0 (1/5) (3/10) (3/4) KANKAKEE RIVER AT WILL ROAD (CONTROL)

(281/1130) (281/1130) 2.0 MILES SE OF SITE GAMMA 45 MN-54 15 <LLD <LLD CO-58 15 <LLD <LLD FE-59 30 <LLD <LLD 0 CO-60 15 <LLD <LLD ZN-65 30 <LLD <LLD

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED' MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER NB-95 15 <LLD <LLD 0 (PCI/LITER)

I' ZR-95 30 <LLD <LLD 0 1-131 15 <LLD <LLD 0 CS- 134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA- 140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0

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, 2007

NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER H-3 16 2000 532 NA 532 D-23 INDICATOR 0 (PCI/LITER) (12/16) (12/12) THORSEN WELL (321/622) (321/622) 0.7 MILES S OF SITE GAMMA 16 MN-54 15 <LLD NA 0 CO-58 15 <LLD NA 0 FE-59 30 <LLD NA CO-60 15 <LLD NA 0 ZN-65 30 <LLD NA 0 NB-95 15. <LLD NA 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M).

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

PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER ZR-95 30 <LLD NA 0 (PCI/LITER) 1-131 15 <LLD NA 0 CS-134 15 <LLD NA 0 CS-137 18 <LLD NA BA-140 60 <LLD NA 0 LA-140 15 <LLD NA 0 FISH GAMMA 8 (PCI/KG WET) MN-54 130 <LLD <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME . NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS FISH CO-58 130 <LLD <LLD 0 (PCI/KG WET)

FE-59 260 <LLD <LLD 0 CO-60 130 <LLD <LLD ZN-65 260 <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD CS-134 130 <LLD <LLD

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS FISH CS-137 150 <LLD <LLD 0 (PCI/KG WET)

BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 SEDIMENT GAMMA (PCI/KG DRY) MN-54 NA <LLD NA 0 CO-58 NA <LLD NA 0 FE-59 NA <LLD NA 0 CO-60 NA <LLD NA 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION 4 NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT ZN-65 NA <LLD NA 0 (PCI/KG DRY)

NB-95 NA <LLD NA 0 ZR-95 NA <LLD NA 0 CS-134 150 <LLD NA 0 CS-137 180 143 NA 143 D-27 INDICATOR 0 (1/2) (1/2) DRESDEN LOCK AND DAM - DOWNSTREAM 0.8 MILES NW OF SITE BA-140 NA <LLD NA 0 LA- 140 NA <LLD NA 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DREDGE SPOILS GAMMA (PCI/KG DRY) MN4-54 NA <LLD NA 0 cc CO-58 NA <LLD NA 0 FE-59 NA <LLD NA 0 CO-60 NA <LLD NA 0 ZN-65 NA <LLD NA 0 NB-95 NA <LLD NA 0 ZR-95 NA <LLD NA 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION 4 NUMBER OF.

PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DREDGE SPOILS CS-134 150 <LLD NA 0 (PCI/KG DRY)

CS-137 180 60.9 NA 61.4 S-05 (DEEP) INDICATOR 0 (2/10) (I/l) RAILROAD BRIDGE (RR)

(60.4/61.4) 1.5 MILES WNW OF SITE BA-140 NA <LLD NA 0 LA-140 NA <LLD NA AIR PARTICULATE GR-B 702 10 21 20 22 D-14 INDICATOR 0 (E-3 PCI/CU.METER) (6501650) (52/52) (52/52) CHANNAHON (5/73) (9/49) (5/73) 3.7 MILES NE OF SITE GAMMA 54 MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED

MEASUREMENT) (LLD). MEASUREMENTS AIR PARTICULATE FE-59 NA <LLD <LLD 0 (E-3 PCI/CU.METER) 0 CO-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 CS-134 50 <LLD <LLD 0 CS-137 60 <LLD <LLD 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007

.NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE BA- 140 NA <LLD <LLD 0 (E-3 PCI/CU.METER)

LA-140 NA <LLD <LLD 0 AIR IODINE GAMMA 702 (E-3 PCI/CU.METER) 1-131 70 <LLD <LLD 0 MILK 1-131 (LOW LVL) 19 NA <LLD 0 (PCI/LITERM GAMMA 19 MN-54 NA NA <LLD 0 CO-58 NA 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-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: .50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK FE-59 NA NA <LLD (PCI/LITER)

CO-60 NA NA <LLD 0 ZN-65 NA NA <LLD 0 NB-95 NA NA <LLD 0 ZR-95 NA NA <LLD 0 CS-134 15 NA <LLD 0 CS-137 18 NA <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED

OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK BA- 140 60 NA <LLD 0 (PCI/LITER)

LA-140 15 NA <LLD 0 VEGETATION GAMMA 10 (PCI/KG WET) MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0

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, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION NB-95 NA <LLD <LLD 0 (PCI/KG WET)

ZR-95 NA <LLD <LLD 0 1-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0 CS-137 80 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0

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, 2007 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DIRECT RADIATION TLD-QUARTERLY 363 NA 22.3 20.4 26.5 D- 110-3 INDICATOR 0 (MILLI-ROENTGEN/QTR.) (355/355) (8/8) (4/4)

(16/31) (18/25) (24/29) 0.9 MILES SSW

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)

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

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2007 Location Location Description Distance & Direction From Site A Surface Water D-21 Illinois River at EJ&E Bridge (indicator) 1.4 miles WNW D-51 Dresden Lock and Dam, Downstream (indicator) 0.8 miles NW D-52 DesPlaines River, Upstream (control) 1.1 miles ESE D-54 Kankakee River, Upstream (control) 8.7 miles SE D-57 Kankakee River at Will Road (control) 2.0 miles SE B Ground/Well Water D-23 Thorsen Well (indicator) 0.7 miles S D-35 Dresden Lock and Dam (indicator) 0.8 miles NW

f. Milk - hi-weeklv I monthly D-25 Biros Farm (control) 11.3 miles SW n3 Air Parficrilates / Air Iodine D-0 1 Onsite 1 (indicator) 0.8 miles NW D-02 Onsite 2 (indicator) 0.3 miles NNE D-03 Onsite 3 (indicator) 0.4 miles S D-04 Collins Road (indicator) 0.8 miles W D-07 Clay Products (indicator) 2.6 miles S D-08 Prairie Park (indicator) 3.8 miles SW D-10 Goose Lake Village (indicator) 3.5 miles SSW D-12 Lisbon (control) 10.5 miles NW D-13 Minooka (indicator) 4.4 miles N D-14 Channahon (indicator) 3.7 miles NE D-45 McKinley Woods Road (indicator) 1.7 miles ENE D-53 Grundy County Road (indicator) 2.1 miles SSE D-55 Ridge Road (indicator) 4.3 miles N D-56 Wildfeather (indicator) 1.7 miles SE F Fish D-28 Dresden Pool of Illinois River, Downstream (indicator) 0.9 miles NNW D-46 DesPlaines River, Upstream (control) 1.2 miles ESE F Sediment D-27 Dresden Lock and Dam, Downstream (indicator) 0.8 miles NW F Dredge Spoils S-02 1.5 miles WNW S-03 1.5 miles WNW S-04 1.5 miles WNW S-05 1.5 miles WNW T-01 1.5 miles WNW G Vegetation Quadrant 1 Chris Locknar 2.8 miles NE Quadrant 2 Robert Pagliano 3.2 miles SSE Quadrant 3 Jim Bloom 3.9 miles SSW Quadrant 4 J.D. Carmichael 1.6 miles NNW Control Glasscock Farm 12.8 miles ENE B-I

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2007 Location Location Description Distance & Direction From Site H Fnvirnnmental Dosimetry - TI n Inner Ringj D-101-1 and -2 1.0 miles N D-102-1 and -2 1.3 miles NNE D-103-1 and -2 1.2 miles NE D-104-1 and -2 1.7 miles ENE D-105-1 and -2 1.5 miles E D-106-1 and -2 1.1 miles ESE D-107-1 and -2 1.4 miles SE D-108-1 and -2 1.9 miles SSE D-109-1 and -2 0.8 miles S D-110-3 and -4 0.9 miles SSW D-111-1 and -2 0.6 miles SW D-112a-1 and-2 0.7 miles WSW D-113-1 and -2 0,9 miles W D-114-1 and -2 0.9 miles WNW D-115-1 and-2 0.8 miles NW D-116-1 and -2 1.0 miles NNW Outer Ring D-201-1 and -2 4.8 miles N D-202-1 and -2 5.1 miles NNE D-203-1 and -2 4.7 miles NE D-204-1 and -2 5.0 miles ENE D-205-1 and -2 4.0 miles E D-206 -1 and -2 3.5 miles ESE D-207-1 and -2 4.2 miles SE D-208-1 and -2 4.9 miles SSE D-209-1 and -2 4.1 miles S D-210-1 and -2 4.9 miles SSW D-211-1 and -2 4.8 miles SW D-212-3 and -4 6.0 miles WSW D-213-1 and -2 4.5 miles W D-214-1 and -2 5.0 miles WNW D-215-1 and -2 4.8 miles NW D-216-1 and -2 4.9 miles NNW Oth- a D-01-1 and -2 Onsite 1 0.8 miles NW D-02-1 and -2 Onsite 2 0.3 miles NNE D-03-1 and -2 Onsite 3 0.4 miles S D-04-1 and -2 Collins Road 0.8 miles W D-07-1 and -2 Clay Products 2.6 miles S D-08-1 and -2 Prairie Park 3.8 miles SW D-10-1 and -2 Goose Lake Village 3.5 miles SSW D-13-1 and -2 Minooka 4.4 miles N D-14-1 and -2 Channahon 3.7 miles NE D-45-1 and -2 McKinley Woods Road 1.7 miles ENE D-53-1 and -2 Grundy County Road 2.1 miles SSE D-55-1 and -2 Ridge Road 4.3 miles.N D-56-1 and-2 Wildfeather 1.7 miles SE B-2

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2007 Location Location Description Distance & Direction From Site Control D-12-1 and -2 Lisbon 10.5 miles NW B-3

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2007 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, 2007 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 within Midwest Laboratory Sampling Procedures radioisotope analysis 1 mile of Dresden Manual.

Station during the year.

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

Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting each station radioisotope analysis Env. Inc., AP-03 Procedure for compositing air particulate filters for gamma spectroscopic analysis Air Iodine Gamma Spectroscopy One- or two~week EIML-SPM-1, Environmental Incorporated 1 filter (approximately TBE, TBE-2007 Gamma emitting composite of continuous Midwest Laboratory Sampling Procedures 280 cubic meters radioisotope analysis air sampling through Manual weekly) charcoal filter Milk 1-131 Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2012 Radioiodine in various May through October. Midwest Laboratory Sampling Procedures matrices Monthly all other times Manual Milk Gamma Spectroscopy Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting May through October. Midwest Laboratory Sampling Procedures radioisotope analysis Monthly all other times Manual Food Products Gamma Spectroscopy Annual grab samples. EIML-SPM-1, Environmental Incorporated 1000 grams TBE, TBE-2007 Gamma emitting Midwest Laboratory Sampling Procedures radioisotope analysis Manual TLD Thermoluminescence Quarterly TLDs EIML-SPM-1, Environmental Incorporated 2 dosimeters Global Dosimetry Dosimetry comprised of two Global Midwest Laboratory Sampling Procedures Dosimetry TLDs, with Manual two CaF 2 elements and two LiF elements in each TLD.

104-1 104,2 114-2 115-22 105-1 114-2 115-2.3 10&2 Crsalde Nucear Power Station D-52 110A Gefle 3f sebir: La 0 ~~ wasibm

¶8-.23 0 I 2 Kownew" OFFS! DOSM CALCULATION MANUAL OMESN STATION UWMS 1, 2. &3 It Fish TLD U Sediment water WATER SAMPLE LOCMr1O Figure B-1 Dresden Station Inner Ring TLD Locations, Fish, Water, and Sediment Location, 2007 B-6

201-1 12 o S 'IU o OMl* DOSE CALULATION wKiku"N"M OREM STATON UNITS 1, 2, &UL 3

Air SaflPOl LxaCi~f )AI SA=W,AO TID MSA T, OU=T

MIt Lmc*iOn RING1TltD W.CA11t, *4 IdilLtK WCA)TKIN p TLD iLocion Figure B-2 Dresden Station Fixed Air Sampling and TLD Sites, Outer Ring TLD Locations and Milk Location, 2007 BB-7

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

TABLE C-I.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION D-21 D-51 D-52 D-54 D-57

. PERIOD 01/05/07 - 01/26/07 (1) 5.1 +/- 2.0 8.1 +/- 2.3 3.6 +/- 1.8 5.7 +/- 2.1.

02/02/07 - 02/24/07 (1) 8.3 +/- 2.2 13 +/- 2.8 5.4 +/- 1.8 7.0 +/- 1.9 03/02/07 - 03/30/07 (1) 5.8 +/- 2.3 9.0 +/- 2.7 4.8 +/- 1.9 7.0 +/- 2.2 04/06/07 - 04/27/07 21 +/- 3.6 5.5 +/- 2.3 7.4 +/- 2.5 3.5 +/- 2.1 3.6 +/- 2.1 05/04/07 05/25/07 13 +/- 2.8 5.0 + 2.2 3.4 +/- 2.0 3.0 +/- 1.9 3.7 +/- 2.0 06/01/07 - 06/29/07 8.1 +/- 2.4 7.2 - 2.3 4.3 +/- 2.0 3.0 +/- 2.0 4.1 +/- 2.0 06/29/07 - 07/27/07 6.6 +/- 1.9 (1) 3.1 +/- 1.7 (1) 31 +/- 5.1 07/27/07 - 08/31/07 11 +/- 2.6 (1) 7.4 +/- 2.0 (1) 8.2 +/- 2.1 08/31/07 - 09/28/07 7.7 +/- 2.2 (1) 6.0 +/- 1.9 (1) 8.0 +/- 2.1 09/28/07 - 10/26/07 9.0 +/- 2.4 (1) 12 +/- 2.5 (1) 5.9 +/- 2.1 11/02/07 - 11/30/07 13 +/- 2.2 (1) 9.4 - 2.0 (1) 10 +/- 2.1 11/30/07 - 12/28/07 13 +/- 2.6 (1) 14 - 2.8 (1) 9.3 +/- 2.2 MEAN 11 +-8.6 6.2 +/- 2.7 8.0 +/- 7.0 3.9 +/- 2.0 8.6 +/- 15 TABLE C-1.2 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION D-21 D-51 D-52 D-54 D-57 PERIOD 01/05/07 - 03/30/07 (1) < 170 < 169 <169 < 165 04/06/07 - 06/29/07 < 171 < 171

167 < 168 281 +/- 117 06/29/07 - 09/28/07 < 186 (1) < 183 (1) 572 +/- 145 10/05/07 - 12/28/07 388 - 111 (1) < 164 (1) 1130 +/- 184 MEAN* 388 +/- 0 661 t 863

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

TABLE C-I.3 CONCENTRATIONS OF GAMMA EMITTERS INSURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-21 03/30/07 - 04/27/07 <3 <3 6 3 5 3 5 13 2 2 22 8 04/27/07 - 05/25/07 <1 < 2 4 3 2 3 14 21 6 05/25/07 - 06/29/07 <1 <2 3 3 2 3 13 19 6 06/29/07 - 07/27/07 <2 <2 4 2 3 2 3 13 2 20 6 07/27/07 - 08/31/07 <1 < 1 3 2 1 2 14 19 6 09/07/07 - 09/28/07 <1 <2 4 3 2 3 10 17 6 10/05/07 - 10/26/07 <.1 < 1 3 2 1 2 13 17 5 11/02/07 - 11/30/07 <2 <2 4 2 3 2 3 13 2 2 20 6 11/30/07 - 12/28/07 < .2 <2 4 2 4 2 4 12 2 2 31 9 C-)

MEAN D-51 01/05/07 01/26/07 <2 <2 4 2 3 2 3 14 1 2 < 21 7 02/02/07 02/24/07 < 2 <3 7 3 6 3 6 15 3 3 < 26 7 03/02/07 03/30/07 < 1 < 1 3 1 3 2 3 6 1 1 < 12 4 04/06/07 04/27/07 <3 <3 6 2 5 3 6 14 3 3 < 25 8 05/04/07 05/25/07 <1 <2 4 3 2 3 13 < 19 6 06/01/07 06/29/07 <1 <1 3 2 1 3 12 < 18 4 MEAN D-52 01/05/07 01/26/07 <2 <2 5 2 4 2 4 15 2 2 23 <7 02/02/07 02/24/07 <2 <2 5 2 4 2 4 12 2 2 20 <7 03/02/07 03/30/07 <2 <2 5 2 4 2 4 10 2 2 19 < 6 04/06/07 04/27/07 <2 <2 5 2 4 2 4 10 2 2 18 <6 05/04/07 05/25/07 < 1 <2 4 1 3 2 3 14 22 2 19 < 7 06/01/07 06/29/07 <2 <2 4 2 3 2 3 14 2 22 < 7 07/06/07 07/27/07 <1 <2 4 3 2 3 10 16 <6 2

08/03/07 08/31/07 <1 <.1 2 2 1 2 14 1 15 <5 09/07/07 09/28/07 <2 <2 4 2 3 2 3 13 21 21 < 7 10/05/07 10/26/07 < 1 < 1 3 1 2 1 2 13 2 17 < 5 11/02/07 11/30/07 <2 <2 4 2 3 2 3 13 1 2 20 <6 12/07/07 12/28/07 < 1 < 1 3 1 2 2 2 13 20 <6 MEAN

TABLE C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65. Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-54 01/04/07 - 01/25/07 < 1 1 2 1 2 2 8 1 12 4 02/01/07 - 02/23/07 < 3 3 6 3 5 3 5 14 3 25 7 03/01/07 - 03/29/07 < 1 1 3 1 3 2 3 7 1 12 4 04/05/07 04/26/07 < 2 3 7 3 5 3 6 13 2

- 26 8 05/03/07 - 05/31/07 < 2 3 6 2 5 3 5 13 2 26 9 06/07/07 - 06/28/07 < 1 2 4 1 3 2 3 12 1 19 6 (1)

(1)

U. (1)

(1)

MEAN D-57 12/30/06 01/26/07 1 2 <4 3 <2 <3 12 < 1 < 1 19 6 01/26/07 02/24/07 2 3 <6 5 <3 <5 13 <2 <2 21 8 02/24/07 03/30/07 2 2 <4 3 <2 <3 10 <2 <2 17 5 03/30/07 04/27/07 3 3 <6 6 < 3 < 5 13 <2 <3 23 8 04/27/07 05/25/07 2 <4 3 <2 <3 15 <1 <2 21 7 05/25/07 06/29/07 2 <4 3 <2 <3 13 < 1 <2 20 6 06/29/07 07/27/07 2 2 <5 3 <2 <3 13 <2 <2 21 7 07/27/07 08/31/07 1 1 <3 2 <. 1 <2 12 < 1 < 1 17 5 08/31/07 09/28/07 21 2 <5 4 <2 <4 14 <2 <2 23 8 09/28/07 10/26/07 2 1 <3 3 < 1 <3 14 < 1 < 1 19 6 10/26/07 11/30/07 1 2 <4 3 <2 <3 13 <2 <2 20 6 11/30/07 12/28/07 1 <3 2 < 1 <2 14 <1 < 1 19 5 MEAN (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION

TABLE C-I1.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION D-23 D-35 PERIOD 01/12/07 481 +/- 137 .< 187 02/09/07 564 +/- 144 03/09/07 521 +/- 138 04/13/07 613 +/- 126 < 160 05/11/07 598 +/- 134 06/08/07 577 +/- 128 07/13/07 506 +/- 126 < 161 08/10/07 622 +/- 134 09/14/07 526 +/- 130 10/12/07 547 +/- 141 < 190 11/09/07 321 +/- 126 12/14/07 503 +/- 136 MEAN 532 +/- 161 C-4

TABLES C-Il.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-137 Ba-140 La-140 PERIOD D-23 01/12/07 <4 <3 <7 <4 <7 <4 <7 <8 <3 <4 < 20 <7 02/09/07 <3 <4 <8 <4 <7 <4 <6 < 14 <3 <3 < 27 <9 03/09/07 <1 <2 <4 <2 <3 <2 <3 < 13 <1 <2 < 20 <6 04/13/07 <4 <3 <7 <3 <6 <4 <5 <9 <3 <4 < 22 <6 05/11/07 <4 <3 <8 <3 <7 <4 <8 < 11 <3 <. 3 < 23 <7 06/08/07 <2 <2 <5 <2 <4 <2 <4 <6 <2 <2 < 15 <5 07/13/07 <6 <6 < 12 <6 < 11 <6 < 10 < 15 <5 <6 < 35 < 13 08/10/07 <2 <2 <5 <2 <3 <2 <4 < 15 <1 <2 < 22 <8 09/14/07 <3 <3 <6 <3 <3 <2 <4 < 14 <2 <2 < 17 -< 7 C- 10/12/07 <2 <3 <6 <2 <3 <2 <5 <6 <2 <3 < 15 <6 11/09/07 <1 <2 <4 <1 <3 <2 <3 < 14 <1 <2 < 21 <6 12/14/07 <1 <2 <3 <1 <3 <2 <3 <7 <1 <2 < 14 <5 MEAN D-35 01/12/07 <5 <5 < 12 <5 <9 <5 <9 < 12 <5 <5 < 28 <10 04/13/07 <4 <5 < 10 <5 <8 <4 <7 < 11 <4 <4 < 26 <9 07/13/07 <5 <5 < 11 <5 < 11 <5 < 9. < 12 <5 <5 < 31 < 10 10/12/07 <6 <5 < 15 <5 < 10 <6 < 12 < 14 <5 <6 < 32 < 12 MEAN

TABLE C-1II11 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/KG +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-28 Channel Catfish 05/21/07 < 22

25

54 < 23

57 < 25 < 46 < 22 < 26 < 203 59 Largemouth Bass 05/21/07

23 < 25 < 55

18 < 50

23 < 44 < 19 < 24 < 164 48 Common Carp 10/16/07 < 26 < 30

82 < 26 < 56 < 33 < 52 < 23 < 25 < 445 114 Largemouth Bass 10/16/07 < 20 < 25 < 62 < 19 < 49 < 27 < 45 < 22 < 22 < 394 104 MEAN cm D-46 Channel Catfish 05/21/07 < 36 < 40 < 85 < 26 < 71 < 42 < 70 < 33 < 37 < 389 115 Freshwater Drum 05/21/07 < 26 < 29 < 59 < 23 < 61 < 31 < 46 < 27 < 26 < 219 60 Common Carp 10/16/07 < 27 < 31 < 81 < 27 < 55 < 33 < 55 < 24 < 28 < 483 138 Largemouth Bass 10/16/07 < 22 < 25 < 68 < 24 < 55 < 28 < 46 < 20 < 23 < 380 126 MEAN

TABLE C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/KG +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-27 05/11/07 < 73 < 99 < 177 < 63 < 185 < 106 < 187 < 73 143 +/- 55 < 1240 < 382 10/05/07 < 82 < 82 < 172 < 87 < 174 < 105 < 177 < 69 < 95 < 631 < 134 MEAN 143 +/- 0

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

TABLE C-IV.2 CONCENTRATIONS OF GAMMA EMITTERS IN DREDGE SPOIL SAMPLES COLLECTED IN THEVICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/KG +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD S-02 (DEEP) 11/09/07 67 < 83 < 163 < 67 < 163 < 88

137 < 62

80

950 < 311 S-02 (SHALLOW) 11/09/07 60 < 79 < 223 < 61 < 172 < 98

153

64 60 +/- 58 < 1120 < 356 S-03 (DEEP) 11/09/07 57 < 57 < 165 < 53 < 138 < 80

126

48 < 65 < 827 < 217 S-03 (SHALLOW) 11/09/07 69 < 64 < 183 < 62 < 138 < 79

136 < 51 < 63 < 964 < 235

(-

00 S-04 (DEEP) 11/09/07 68 < 88 < 216 < 64 < 196 < 99 < 142

69 < 84 < 1240 < 337 S-04 (SHALLOW) 11/09/07 98 < 120 < 301 < 83 < 211 < 122

230 < 77 < 111 < 1390 < 469 S-05 (DEEP) 11/09/07 50 < 58 < 130 < 43 < 123 < 80

118 < 42 61 +/- 29

750 < 268 S-05 (SHALLOW) 11/09/07 82 < 97 < 229 < 86 < 223 < 115

155 < 57 < 77 < 1240 < 463 T-01 (DEEP) 11/09/07 61 < 72 < 208 < 63 < 173 < 79

128 < 56 < 77 < 1190 < 264 T-01 (SHALLOW) 11/09/07 55 < 66 < 151 < 55 < 131 < 77 < 106 < 42

66 < 920 < 267 MEAN 61 +/- 1.4

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATEDUSING THE POSITIVE VALUES

TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA

COLLECTION GROUP I IGROUP 11 PERIOD D-01 D-02 D-03 D-04 D-07 D-45 D-53 D -56 12/30/06 -01/05/07 16 +/- 5 13 +/- b 13 +/- 5 14 +/- 5 -- 19 +/- 5 18 +/- 5 21 +/- 5, 16 +/-5 01/05/07 -01/12/07 19 +/-4. 117 +/-4 18 +/-4 18 +/-4 17 +/-4 20 +/-4 19 +/-4 17+/-4 01/12/07 -01/19/07 13 +/- 4 17 +/- 4 15 +/- 4 16 +/- 4 18 +/- 4 15 +/- 4 16 +/- 4 19 +/-4 01/19/07 -01/26/07 27 +/-5 36 +/-5 35 +/-5 27 +/-5 35 +/-5 28 +/-5 31 +/-5 32+/-5 01/26/07 -02/02/07 21 +/-4 24 +/-5 25 +/-5 24 +/-5 23 +/-5 24 +/-5 22 +/-5 26+/-5 02/02/07-02/09/07 *22 +/-5 19 +/-4 17 +/-4 20 +/-5 20 +/-5 23 +/-5 16 +/-4 18+/-t4 02/09/07 -02/16/07 21 +/-4 19 +/-4 19+/-+4 16 +/-4 18 +/-4 20 +/-4 20 +/-4 21+/-4 02/16/07 -02/24/07 27 +/-4 22 +/-4 22 +/-4 23 +/-4 21 +/- 4 21 +/-4 22 +/-4 15+/-4 02/24/07 -03/02/07 11 +/- 4 . 12 +/- 4 14 +/- 4 10 +/- 4 9 +/- 4 13 +/- 4 14 +/- 4 12 +/-4 03/02/07 -03/09/07 14 +/-4 *17 +/-4 15 +/-4 16 +/-4 16 +/-4 16 +/-4 20 +/-4 18+/-4 03/09/07 -03/16/07 21 +/- 4 20 +/- 4 20 +/- 4 21 +/- 4 15 +/- 4 23 +/- 4 19 +/- 4 21 +/-4 03/16/07 -03/23/07 17 +/- 4 14 +/- 4 17 +/- 4 15 +/- 4 16 +/- 4 20 +/- 4 15 +/- 4 17 +/-4 03/23/07-03/30/07 16 +/-4 15 +/-4 13 +/-4 12 +/-4 13 +/-4 11 +/-4 12 +/-4 8+/-4 03/30/07 -04/06/07 14 +/-4 17 +/-4 17 +/-4 15 +/-4 14 +/-4 13 +/-4 17 +/-4 14+/-4 04/06/07 -04/13/07 11 +/- 4 15 +/- 4

14 +/- 4 16 +/- 4 15 +/- 4 13 +/- 4 15 +/- 4 13 +/-4 04/13/07 -04/20/07 16 +/-4 17 +/-4 15 +/-4 20 +/-4 14 +/-4 17 +/-4 17 +/-4 16+/-4 04/20/07 -04/27/07 16 +/- 4 10 +/- 4 14 +/- 4 12 +/- 4 9 +/- 4 7 +/- 4 12 +/- 4 10 +/-4 04/27/07 -05/04/07 10 +/- 4 16 +/- 4 11 +/- 4 15 +/- 4 11 +/- 4 10 +/- 4 13 +/- 4 12 +/-4 05/04/07 -05/11/07 17 +/- 4 18 +/- 4 *19 +/- 4 20 +/- 4 22 +/- 4 18 +/- 4 25 +/- 5

22 +/-4 05/11/07 -05/18/07 13 +/- 4 10 +/-4 13 +/- 4 12 +/- 4 17 +/- 4 14 +/- 4 14 +/- 4 19 + 4 05/18/07 -05/25/07 21 +/-4 17+/-4 23 +/-4 17 +/-4 20 +/-4 20 +/-4 17 +/-4 20+/-4 05/25/07 -06/01/07 23 +/-4 19+/-4 18 +/-4 24 +/-4 20 +/-4 22 +/-4 21 +/- 4 23+/-4 06/01/07 -06/08/07 13 +/- 4 15 +/-4 13 +/- 4 15 +/- 4 15 +/- 4 15 +/- 4 18 +/- 4 17 +/-4 06/08/07 -06/15/07 18 +/-4 18+/-4 15 +/-4 22 +/-4 17 +/-4 17 +/-4 15 +/-4 18+/-4.

06/15/07-06/22/07 23 +/-5 26+/-5 20 +/-4 23 +/-5 25 +/-5 21 +/-4 19 +/-4 22+/-5 06/22/07 - 06/29/07 14 +/- 4 15 +/- 4 15 +/- 4 19 +/- 4 19 +/- 4 18 +/- 4 19 +/- 4 19 +/-4 06/29/07 - 07/06/07 13 +/- 4 17 +/- 4 15 +/- 4 13 +/- 4 16 +/- 4 16 +/- 4 17 +/- 4 16 +/-4 07/06/07 -07/13/07 14 +/-4 20+/-i4 23 +/-5 20 +/-4 20 +/-4 23 +/-5 25 +/-5 19+/-4 07/13/07 - 07/20/07 12 +/- 4 11 +/- 4 12 +/- 4 11 +/- 4 13 +/- 4 8 +/- 4 14 +/- 4 12 +/-4 07/20/07 - 07/27/07 18 +/-4 23 +/-5 20 +/-4 19 +/-4 19 +/-4 21 +/-5 24 +/-5 19+/-4 07/27/07 -08/03/07 27 +/-5 25 +/-5 25 +/-5 28 +/-5 24 +/-5 28 +/-5 25 +/-5 26+/-5 08/03/07 - 08/10/07 20 +/-4 23 +/-4 23 +/-4 23 +/-4 23 +/-4 21 +/-4 23 +/-4 21+/-4 08/10/07 - 08/17/07 22 +/-5 29 +/-5 26 +/-5 24 +/-5 23 +/-5 28 +/-5 24 +/-5 25+/-5 08/17/07 - 08/24/07 *13 +/- 4 15 +/- 4 10 +/- 4 11 +/- 4 10 +/- 4 11 +/- 4 12 +/- 4 15 +/-4 08/24/07 - 08/31/07 25 +/-5 25 +/-4 27 +/-5 29 +/-5 23 +/-5 27 +/-5 26 +/-5 27+/-5 08/31/07 -09/07/07 31 +/-5 35 +/-5 30 +/-5 33 +/-5 33 +/-5 27 +/-5 30 +/-5 28+/-5 09/07/07 - 09/14/07 11 +/- 4 18 +/- 4 11 +/- 4 18 +/- 4 16 +/- 4 17 +/- 4 13 +/- 4 13 +/-4 09/14/07 -09/21/07 24 +/-5 27 +/-5 .26 +/-5 23 +/-4 26 +/-5 24 +/-5 28+/-i5 25+/-5 09/21/07 -09/28/07 19 +/-5 24 +/-5 20 +/-5 24 +/-5 17 +/-5 18 +/-5 22+/-:t5 21+/-5 09/28/07,-10/05/07 30 +/-5 27 +/-5 30 +/-5 24 +/-5 33 +/-5 31 +/-5 29+/-5 32+/-5 10/05/07 -10/12/07 6 +/- 4 10 +/- 4 14 +/- 4 9 +/-4 13 +/- 5 8 +/-4 9 +/-4 11 +/-4 10/12/07 -10/19/07 22 +/-5 22 +/-5 24 +/-5 23 +/-5 26 +/-5 26 +/-5 22+/-5 29+/-5 10/19/07 -10/26/07 13 +/-4 17 +/-4 18 +/-4 15 +/-4 18 +/-4 23 +/-4 19+/-4 18+/-4 10/26/07 -11/02/07 15 +/- 4 14 +/- 4 19 +/- 4 19 +/- 4 17 +/- 4 20 +/- 5 17 +/-4 19 +/-4 11/02/07 -11/09/07 22 +/- 4 26 +/- 5 24 +/- 5 23 +/- 5 20 +/- 5 25 +/- 5 24 +/-5 23 +/-5 11/09/07 -11/16/07 23 +/- 5 30 +/- 5 25 +/- 5 25 +/- 5 28 +/- 5 23 +/- 5 26 +/-5 28 +/-5 11/16/07 -11/23/07 26 +/- 5 26 +/- 5 25 +/- 4 32 +/- 5 30 +/- 5 27 +/- 5 23 +/-4 28 +/-5 11/23/07 -11/30/07 28 +/- 5 28 +/- 5 29 +/- 5 32 +/- 5 31 +/- 5 28 +/- 5 28 +/-5 32 +/-5 11/30/07 -12/07/07

20 +/- 4 19 +/- 4 20 +/- 4 24 +/- 5 21 +/- 5 21 +/- 5 22 +/-5 23 +/-5 12/07/07-12/14/07 33 +/-5 35 +/-5 37 +/-6. 44 +/-6 36.+/-5 39 +/-6 35+/-5 39+/-+6 12/14/07 -12/21/07 41 +/-6 45 +/-6 38 +/-5 50 +/-6 47 +/-6 47 +/-6 40+/-6 51+/-6 12/21/07-12/28/07 28 +/-5 34 +/-5 31 +/-5 36 +/-5 37 +/-5 34 +/-5 31+/-5 32+/-5 MEAN 19 +/- 13 21 +/- 15 20 +/- 14 21 +/- 16 21 15 21 +/- 15 21 +/-13 21 +/-16 C -9

TABLE C-V.1 CONCENTRATIONS OF GROSS BETA INAIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION GROUP III I GROUP IV PERIOD D-08 D-10 D-13 D-14 D-55 D-12 12/30/06 - 01/05/07 21 +/- 5 17 +/- 5 19 +/- 5 15 +/- 4 22 +/- 5 18 +/- 5 01/05/07 - 01/12/07 16 +/- 4 19 +/- 4 18 +/-4 18 +/- 4 20 +/- 4 14 +/- 4 01/12/07 -01/19/07 16 +/- 4 20 +/- 4 19 +/-4 16 +/- 4 14 +/- 4 19 +/- 4 01/19/07 -01/26/07 34 +/- 5 35 +/- 5 38 +/- 5 31 +/- 5 34 +/- 5 33 +/- 5 01/26/07 -02/02/07 27 +/- 5 23 +/- 5 18 +/-4 25 +/- 5 27 +/- 5 27 +/- 5 02/02/07 -02/09/07 23 +/- 5 18 +/-4 20 +/- 5 20 +/- 5 26 +/- 5 14 +/- 4 02/09/07 -02/16/07 20 +/- 4 20 +/- 4 26 +/- 5 21 +/- 4 24 +/- 5 24 +/- 4 02/16/07 -02/24/07 24 +/- 4 27 +/- 4 22 +/-4 34 +/- 8 21 +/- 4 17 +/- 4 02/24/07 -03/02/07 14 +/- 4 15 +/-4 13 +/-4 9 +/-6 14 +/-4 15 +/- 4 03/02/07 -03/09/07 19 +/- 4 20 +/- 4 16 +/-4 15 +/- 4 14 +/- 4 15 +/- 4 03/09/07 -03/16/07 21 +/- 4 19 +/-4 19 +/- 4 21 +/- 4 19 +/- 4 17 +/- 4 03/16/07 -03/23/07 17 +/- 4 17 +/- 4 16 +/- 4 19 +/- 4 15 +/- 4 16 + 4 03/23/07 - 03/30/07 13 +/- 4 16 +/- 4 13 +/- 4 15 +/- 4 11 +/-4 10 +/- 4 03/30/07 -04/06/07 20 +/- 5 14 +/- 4 17 +/-4 15 +/- 4 15 +/- 4 11 +/- 4 04/06/07 -04/13/07 14 +/- 4 13 +/- 4 17 +/-4 15 +/- 4 20 +/- 4 13 +/- 4 04/13/07 - 04/20/07 19 +/- 4 15 +/- 4 14 +/- 4 17 +/- 4 13 +/- 4 19 +/- 4 04/20/07 - 04/27/07 13 +/- 4 10 +/-4 14 +/- 4 12 +/- 4 12 +/- 4 11 +/- 4 04/27/07 - 05/04/07 16 +/- 4 12 +/- 4 11 +/-4 15 +/- 4 14 +/- 4 11 +/- 4 05/04/07 - 05/11/07 25 +/- 5 20 +/- 4 22 +/-4 21 +/- 4 21 +/- 4 20 +/- 4 05/11/07 -05/18/07 13 +/- 4 17 +/- 4 . 13 +/-4 16 +/- 4 16 +/- 4 18 +/- 4 05/18/07 -05/25/07 24 +/- 5 15 +/- 4 23 +/- 5 17 +/- 4 23 +/- 4 13 +/- 4 05/25/07 -. 06/01/07 21 +/- 4 19 +/- 4 23 +/- 4 25 +/- 4 20 +/- 4 18 +/- 4 06/01/07 - 06/08/07 16 +/- 4 15 +/- 4 17 +/-4 19 +/-4 17 +/- 4 12 +/- 4 06/08/07 - 06/15/07 20 +/- 5 18 +/- 4 17 +/-4 18 +/-4 17 +/- 4 20 +/- 4 06/15/07 - 06/22/07 36 +/- 9 24 +/- 5 20 +/--4 25 +/- 5 27 +/- 5 20 +/- 4 06/22/07 - 06/29/07 10 +/- 7 15 +/- 4 16 +/- 4 18 +/-4 18 +/- 4 17 +/- 4 06/29/07 - 07/06/07 18 +/- 4 17 +/- 4 (1) 19 +/-4 17 +/- 4 15 +/- 4 07/06/07 - 07/13/07 19 +/- 4 24 +/- 5 15 +/-4 25 +/- 5 23 +/- 5 07/13/07 - 07/20/07 11 +/- 4 13 +/- 4 12 +/-4 15 +/- 4 13 +/- 4 07/20/07 - 07/27/07 18 +/- 4 21 +/- 5 22 +/-4 21 +/- 5 24 +/- 5 07/27/07 - 08/03/07 24 +/- 4 28 +/- 5 28 +/- 5 25+/- 5 23 +/- 4 08/03/07 - 08/10/07 24 +/- 4 25 +/- 4 18 +/- 4 24 +/- 4 17 +/- 4 08/10/07 - 08/17/07 24 +/- 5 24 +/- 5 22 +/- 5 21 +/- 5 23:+/-15 08/17/07 - 08/24/07 14 +/- 4 12 +/- 5 16 +/- 5 15 +/- 4 15 +/- 4 08/24/07 - 08/31/07 10 +/- 4 27 +/- 5 73 +/- 13 24 +/- 4 28 +/- 5 08/31/07 - 09/07/07 34 +/- 5 30 +/- 5 29 +/- 5 28 +/- 5 28 +/- 5 09/07/07 - 09/14/07 19 +/- 4 13 +/- 4 15 +/- 4 12 +/- 4 11 + 4 09/14/07 - 09/21/07 27 +/- 5 29 +/- 5 29 +/- 5 23 +/- 5 25 +/- 5 09/21/07 - 09/28/07 25 +/- 5 26 +/- 5 21 +/- 5 19 +/- 5 20 +/- 5 09/28/07 - 10/05/07 24 +/- 5 34 +/- 5 27 +/- 5 30 +/- 5 25 +/- 5 10/05/07 - 10/12/07 9 +/- 4 14 +/-4 10 +/- 4 7 +/- 4 9 +/- 4 10/12/07 - 10/19/07 27 +/- 5 25 +/- 5 30 +/- 5 23 +/- 5 22 +/- 5 10/19/07 - 10/26/07 15 +/- 4 21 +/- 4 20 +/- 4 16 +/- 4 19 +/- 4 10/26/07 - 11/02/07 22 +/- 5 21 +/- 5 21 +/- 5 15 +/- 4 14 +/- 4 11/02/07 - 11/09/07 25 +/- 5 25 +/- 5 26 +/-5 21 +/- 5 21 +/- 5 11/09/07 - 11/16/07 7 +/- 3 33 +/-5 5 +/- 4 22 +/- 5 26 +/- 5 11/16/07 - 11/23/07 61 +/- 6 29 +/- 5 27 +/-5 23 +/- 4 24 +/- 4 11/23/07 - 11/30/07 27 +/- 5 30 +/- 5 35 +/- 5 25 +/- 5 31 +/- 5 11/30/07 - 12/07/07 21 +/- 5 22 +/- 5 20 +/- 5 24 +/- 5 20 +/- 4 12/07/07 - 12/14/07 40 +/- 6 36 +/- 5 39 +/- 6 33 +/- 5 41 +/- 6 12/14/07 - 12/21/07 45+/- 6 50 +/- 6 48 +/- 6 39 +/- 6 49 +/- 6 12/21/07 - 12/28/07 31 +/- 5 38 +/- 5 40 +/- 6 32 +/- 5 30 +/- 5 MEAN 22 +/- 19 22 +/- 16 18 +/- 11 22 +/- 22 21 +/- 13 20 +/- 16 (1) SEE PROGRAM CHANGES SECTIONS FOR EXPLANATION C-10

TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS (E-3 PCI/CU METER) IN AIR PARTICULATE SAMPLE' COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 GROUP I - ON-SITE LOCATIONS GROUP II - NEAR-FIELD LOCATIONS GROUP III- FAR-FIELD LOCATIONS GROUP IV - CONTROL LOCATION COLLECTION MIN MAX MEAN +/- COLLECTION MIN MAX MEAN + COLLECTION MIN MAX MEAN +/- COLLECTION MIN MAX MEAN +

PERIOD 2SD PERIOD 2SD PERIOD 2SD PERIOD 2SD I zf;IOIv- - v

-

'IVU 10 I

vg

-

xU I a

--

I,41*U -

-/ý 4fuL*.l/ It- 0;..

-

+/- I I I olon-

&I#{, - U ICU I A 1. 0ý I A I nfný Ina IMnin, 4A ýo 11 1 02/02/07 - 03/02/07 11 27 19 +/-9 02/02/07 - 03/02/07 9 23 18+/- 8 02/02/07 03/02/07 9 34 20 +12 02/02/07 - 03/02/07 14 24 17 +/- 9 03/02/07 - 03/30/07 13 21 17 +5 03/02/07 - 03/30/07 8 23 16 8 03/02/07 03/30/07 11 21 17 +/-6 03/02/07 - 03/30/07 10 17 14 +/- 5 03/30/07 - 04/27/07 10 17 15 +4 03/30/07 - 04/27/07 7 20 14+/- 6 03/30/07 04/27/07 10 20 15 +/-5 .03/30/07 - 04/27/07 11 19 14 +/- 7 04/27/07 - 06/01/07 10 23 17 +8 04/27/07 - 06/01/07 10 25 18 8 04/27/07 06/01/07 11 25 18 +/-9 04/27/07 - 06/01/07 11 20 16 +/- 8 06/01/07 - 06/29/07 13 26 17 +/-8 06/01/07 - 06/29/07 15 25 19 6 06/01/07 06/29/07 10 36 19 +/-11 06/01/07 - 06/29/07 12 20 17 +/- 8 06/29/07 - 08/03/07 11 27 18 + 11 06/29/07 - 08/03/07 8 28 19 +/- 11 06/29/07 08/03/07 11 28 19 +/-10 06/29/07 - 08/03/07 13 24 19 +/- 10 08/03/07 - 08/31/07 10 29 21 +/-12 08/03/07 - 08/31/07 10 29 21 +/-12 08/03/07 08/31/07 10 73 23 +/- 28 08/03/07 - 08/31/07 15 28 21 +/- 12 08/31/07 - 09/28/07 11 35 23 +15 08/31/07 - 09128/07 13 33 23 +/- 12 08/31/07 09/28/07 12 34 24 +13 08/31/07 - 09/28/07 11 28 21 + 16 09/28/07 - 11/02/07 6 30 19 +/-14 09/28/07 - 11/02/07 8 33 20 +/- 14 09/28/07 11/02/07 7 34 21 +/- 14 09/28/07 - 11/02/07 9 25 18 +/- 13 11/02/07 - 11/30/07 22 30 26 +/-5 11/02/07 - 11/30/07 20 32 27 +/-7 11/02/07 11/30/07 5 61 26 +/- 25 11/02/07 - 11/30/07 21 31 26 + 8 11/30/07 - 12/28/07 19 45 32 +/- 17 11/30/07 - 12/28/07 21 51 36 + 19 11/30/07 12/28/07 20 50 35 +/-18 11/30/07 - 12/28/07 20 49 35 +/- 26 12/30/06 - 12/28/07 6 45 20 +/- 14 12/29/06 - 12/28/07 7 51 21 +/- 15 12/29/06 - 12/28/07 5 73 21 +/- 17 12/29/06 - 12/28/07 9 49 20 +/- 16

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-01 12/30/06 - 03/30/07 <4 <4 <10 <3 <9 <4 <7 <4 <3 < 85 < 21 03/30/07 - 06/29/07 <3 <5 < 14 <3 <5 <5 <8 <3 <2

316 < 114 06/29/07 - 09/28/07 <4 <8 < 32 <2 <9 <7 < 15 <4 <2 < 3790 < 1040 09/28/07 - 12/28/07 <2 <3 <7 <3 <5 <3 <5 <2 <2

46

16 MEAN D-02 12/30/06 - 03/30/07 <4 <4 <10 <3 <7 <4 <8 <3 <3

76 < 39 03/30/07 - 06/29/07 <2 <4 <16 <2 <8 <4 <8 <2 <3 < 326

98 06/29/07 - 09/28/07 <3 <6 < 36 <3 < 10 <9 < 20 <3 <3 < 3800 < 1040 09/28/07 - 12/28/07 <3 <3 <8 <2 <8 <4 <7 <3 <3 < 61 < 26 MEAN D-03 12/30/06 - 03/30/07 <3 <4 <11 <4 <9 <4 <7 <3 <3 < 77

21 03/30/07 - 06/29/07 <4 <6 <14 <3 <8 <6 < 10 <4 <3

419

136 06/29/07 - 09/28/07 <4 <7 <41 <4 <7 <11 *19 <4 <3 < 4740 < 1450 09/28/07 - 12/28/07 <3 <4 <7 <2 <9 <5 <6 <3 <3 < 61 < 26 MEAN D-04 12/30/06 - 03/30/07 <2 <3 <7 <2 <5 <3 <5 <2 <2

58 < 23 03/30/07 - 06/29/07 <3 <8 < 19 <3 <9 <7 <11 <4 <3 < 418 < 97 06/29/07 -. 09/28/07 <3 <7

26 <2 <8 <8 < 13 <3 <2 < 3080 < 1150 09/28/07 - 12/28/07 <3 <3 <6 <3 <6 <3 <5 <3 <2 < 49 < 20 MEAN

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-07 12/30/06 - 03/30, /07 <3 <5 < 11 <3 <8 .<4 <7 <4 <3 < 108 < 28 03/30/07 - 06/29/ '07 <2 <3 <13 <3 <7 <4 <7 <2 < 2

364

128 06/29/07 - 09/28/ /07 <3 <9 < 31 <3 <8 <9 < 18 <4 < 3

5220 < 1690 09/28/07 - 12/281'07 <3 <3 <7 <3 <6 <4 <6 <2 <2

51 < 18 MEAN D-08 12/30/06 - 03/30/07 <2 <3 <7 <2 <5 <3 <4 <2 < 2 < 54 < 18

<3 <4 <11 <3 <4 <5 <9 <3 < 2

293

128 03/30/07 - 06/29/07 06/29/07 - 09/28/07 <4 <9 < 43 <4 < 12 <9 <16 <4 <:3 < 5140 < 1700 09/28/07 - 12/28/07 <3 <4 < 11 <3 <8 <3 <7 <3 < 2

63

19 MEAN D-10 12/30/06 - 03/30/07 <3 <4 <11 <3 <7 <5 <8 <3 <'3 < 90 < 33 03/30/07 - 06/29/07 <3 <5 <12 <3 <10 <6 <10 <4 ':3

328

113 06/29/07 - 09/28/07 <4 <9 < 39 <4 < 10 <9 *17 <4 <3 < 4670 < 1720 09/28/07 - 12/28/07 <3 <4 <11 <3 <8 <4 <8 <3 <3

60

21 MEAN D-12 12/29/06 - 03/30/07 <3 <5 <10 <3 <7 <4 <7 <3 <'3 < 96

25 03/30/07 - 06/29/07 <3 <5 <12 <3 <7 <3 <7 <3 <2 < 246

65 06/29/07 - 09/28/07 <3 <9 < 39 <2 <11 <10 <15 <4 < 3

3890 < 1660 09/28/07 - 12/28/07 <2 <3 <7 <2 <5 <4 <5 <2 <'2 < 47 < 11 MEAN

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-13 12/29/06 - 03/30/07 <3 <4 <6 <3 <7 <4 <6 <3 <3 <84 < 31 03/30/07 - 06/29/07 <4 <6 <13 <3 <8 <6 <13 <3 <3 <412

147 (1)

(1)

MEAN D-14 12/29/06 - 03/30/07 <3 <5 <15 <5 <6 <5 <9 <3 <3 < 113

32 03/30/07 - 06/29/07 <3 <5 <13 <3 <7 <5 <8 <3 <2

356 < 96 06/29/07 - 09/28/07 <4 < 11 < 28 <4 <9 <9 <17 <4 <3 < 5360 < 898 09/28/07 - 12/28/07 <3 <4 <10 <4 <7 <5 <8 <3 <3

68

27 MEAN D-45 12/29/06 - 03/30/07 <2 <3 <8 <2 <7 <3 <7 <2 <2

60 <7 03/30/07 - 06/29/07 <3 <5 <14 <3 <6 <5 <8 <3 <2 < 341 < 115 06/29/07 - 09/28/07 <3 <6 < 26 <3 <8 <9 <12 <3 <3 < 3300 < 1090 09/28/07 - 12/28/07 <4 <3 <8 <4 <8 <4 <7 <4 <:4

63 < 22 MEAN D-53 12/30/06. - 03/30/07 <3 <2 <8 <3 <5 <2 <7 <2 <3 < 69 < 33 03/30/07 - 06/29/07 <4 <5 <18 <3 <9 <6 <10 <4 <3 < 469 < 169 06/29/07 - 09/28/07 <5 <9 < 36 <3 <10 <10 <17 <3 <3 < 4650 < 1120 09/28/07 - 12/28/07 <3 <3 <7 <2 <7 <4 <6 <3 <2 < 48 < 20 MEAN (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-55 12/29/06

03/30/07 <2 <2 <8 <3 <5 <3 <7 . <2 <2 <67 < 23 03/30/07 - 06/29/07 <4 <6 < 23 < 3 < 10 < 6 < 10 <3 <4 < 474 < 124 06/29/07 - 09/28/07 <4 <8 <34 <4 < 8 < 10 < 16 < 3 <3 < 5190 < 1100 09/28/07 - 12/28/07 <2 <4 <8 <2 <6 <3 <5 <3 <2 < 52 < 24 MEAN D-56 12/30/06 - 03/30/07 <2 <3 < 11 <3 < 11 <4 <8 <4 <4 < 80 < 32 03/30/07 - 06/29/07 <4 < 17 < 145 <4 <8 < 27 < 41 <4 <3 < 707000 (2) < 232000 (2) 06/29/07 - -09/28/07 <4 <7 < 32 <3 < 10 <9 < 19 <3 <3 < 4310 < 1470 09/28/07 - 12/28/07 <3 <4 <.8 <3 <7 <4 <6 <3 <3 < 63 < 25 MEAN (2) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I I GROUP 11 COLLECTION PERIOD D-01 D-02 D-03 D-04 D-07 D-45 D-53 0-56

<6 <6 <6 <6 < 11 < 12 *<12

-01/125/07 01/05/07 < 27

49

49 <.48 < 48 < 33 < 33

33

-01/12/07 01/12/07 < 27

27

27

26 < 48 < 31 < 31

32 01/19/07 -01/26/07 < 24

36

36

36 < 37 <.47 < 46

46 01/26/07 -02/02/07 < 27

44

44

43 < 45 < 39 < 39

39 02/02/07 -02/09/07 < 32

32

32

32 < 16 < 28 < 28

28 02/09/07 -02/16/07 < 48

27

48

48 < 49 < 51 < 50

50 02/16/07 -02/24/07 < 34

34 *<16

34 < 34 < 26 < 25

25 02/24/07 -03/02/07 < 38

39

39

38 < 21 < 44 < 42

42 03/02/07 -03/09/07 < 28

38

47

51 < 47 < 62 < 62

52 03/09/07 -03/16/07 < 28

28

28

28 < 15 < 20 < 19 < 11 03/16/07 -03/23/07 < 49

49

49

49 < 28 < 57 < 55

55 03/23/07 -03/30/07 < 54

55

55

55 < 30 < 50 < 48

48 63/30/07 -04/06/07 < 31

31

31

31 < 29 < 33 < 33

33 04/06/07 -04/13/07 < 31

31

31

31 < 26 < 36 < 35

26 04/13107 -04/20/07 < 50

50

49

50 < 33 < 58 < 57

57 04/20/07 -04/27/07 < 35

53

52

52 < 53 < 47 < 45 < 45 04/27/07 -05/04/07 < 61

61

61

61 < 34 < 61 < 60

60 05/04/07 -05/11/07 < 26

27

27

26 < 17 < 36 < 38

38 05/11/07 -05/18/07 < 49

49

49

49 < 31 < 48 < 45

45 05/18/07 -05/25/07 < 39

39

39

39 < 32 < 35 < 34

34 05/25/07 -06/01/07 < 45

45

45

45 < 25 < 17 < 16

16 06/01/07 -06/08/07 < 29

29

29

29 < 18 < 28 < 28

28 06/08/07 -06/15/07 < 22

22

22

21 < 14 < 18 < 18

17 06/15/07 -06/22/07 < 25

25

25

17 < 25 < 33 < 32

32 06/22/07 -06/29/07 < 33

34

34

33 < 27 < 50 < 34

34 06/29/07 -07/06/07 < 16

16

16

16 < 10 < 21 < 20

20 07/06/07 -07/13/07 < 39

39

39

39 < 24 < 49 < 47

47 07/13/07 -07/20/07 < 21

21

21

21 < 22 < 19 < 18 < 11 07/20/07 -07/27/07 < 42.

42 < 42

42 < 28 < 43 < 41 *<41 07/27/07 -08/03/07 < 58

58

58

58 < 47 < 65 < 64

64 08/03/07 -08/10/07 < 17

31

31

31 < 31 < 41 < 45

44 08/10/07 -08/17/07 < 38

69

69

69 < 69 < 70 < 44

44 08/17/07 -08/24/07 < 36

66

65

67 < 69 < 66 < 65

65 08/24/07 -08/31/07 < 41

66

66

68 < 69 < 26 < 38

38 06/31/07 -09/07/07 < 29

48

48

48 < 52 < 67 < 54

54 09/07/07 09/14/07 < 48 *<48 *<48 *<46 < 53 < 52 < 54

54 09/14/07 -09/21/07 < 23

34

34

34 < 32 < 41 < 46

46 09/21/07 -09/28/07 < 30

40

40

41 < 40 < 51 < 48 < 48 09/28/07 -10/05/07 < 29

53

53

49 < 54 < 52 < 49

49 10/05/07 -10/12/07 < 66

67

67

66 < 47 < 61 < 61

60 10/12/07 -10/19/07 < 39

22

40

39 < 40 < 40 < 36

36 10/19/07 -10/26/07 < 53

50

52

51 < 10 < 18 < 20

20 10/26/07 -11/02/07 < 54

56

23 < 54 < 52 < 67 < 66

66 11/02/07 -11/09/07 < 36

65

65

65 < 69 < 57 < 64

64 11/09/07 -11/16/07 < 51

51 < 51

28 < 52 < 46 < 51

51 11/16/07 -11/23/07 < 37

67

67

67 < 67 < 68 < 56

55 11/23/07 -11/30/07 < 30

30

30

30 < 19 < 29

28

28 11/30/07 -12/07/07 < 35

53

53

53 < 53 < 46

60

60 12/07/07 -12/14/07 < 15

28

28

27 < 28 < 35

28

28 12/14/07 -12/21/07 < 36

36

36

36 < 23 < 48

47

47 12/21/07 -12/28/07 < 31

56

56

56 < 56 < 59

58

58 MEAN C- 16

TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLCINGROUP III IGROUP IV PERIOD D-08 D-10 D-13 D-14 D-55 D-12 12/30/06 -01/05/07 < 31 < 31 < 27 < 20 < 11 <27 01/05/07 -01/12/07 < 33 < 49 < 49 < 49 < 33 < 49 01/12/07 -01/19/07 < 49 < 49 < 31 < 32 < 20 < 49 01/19/07 -01/26/07 < 24 < 43 < 44 < 44 < 47 < 44 01/26/07 -02/02/07 < 27 < 44 <<44 < 44 < 40 < 43 02/02/07 -02/09/07 < 33 < 33 < 33 < 18 < 28 < 32 02/09/07 -02/16/07 < 52 < 52 < 52 < 29 < 51 < 50 02/16/07 -02/24/07 < 36 < 36 < 36 < 62 < 25 < 36 02/24/07 -03/02/07 < 33 < 33 < 33 <33

< < 44. <33 03/02/07 -03/09/07 < 47 < 47 < 62 < 60 < 52 < 37 03/09/07 -03/16/07 < 15 < 15 < 10 < 20 < 19 < 15 03/16/07 -03/23/07 < 44 < 44 < 44 < 35 < 57 < 44 03/23/07 -03/30/07 < 57 < 57 < 59 < 39 < 50 < 59 03/30/07 -04/06/07 < 27 < 29 < 29 < 18 < 33 < 29 04/06/07 - 04/13/07 < 26 < 26 < 21 < 36 < 39 < 26 04/13/07 - 04/20/07 < 61 < 33 < 63 < 61 < 60 < 61 04/20/07 - 04/27/07 < 32 < 60 < 58 < 60 < 47 < 58 04/27/07 -05/04/07 < 58 < 58 < 59 < 35. <60 < 58 05/04/07 - 05/11/07 < 31 < 31 < 30 < 30 < 36 <-18 05/11/07 - 05/18/07 < 45 < 46 < 47 < 29 < 48 < 46 05/18/07 - 05/25/07 < 36 < 36 < 37 < 20 < 35 < 36 05/25/07 - 06/01/07 <46

< < 46, < 46 < 35 < 16 < 46 06/01/07 - 06/08/07 < 29 < 29 < 29 < 18 < 28 < 29 06/08/07 -06/15/07 < 22 < 22 < 22 < 13 < 19 < 22 06/15/07 - 06/22/07 < 63 < 29 < 30 < 16 < 33 < 30 06/22/07 -06/29/07 < 60 < 27 < 50 < 22 < 35 < 28 06/29/07 - 07/06/07 < 30 < 30 (1) < 30 < 21 < 30 07/06/07 - 07/13/07 < 39 < 39 < 42 < 49 < 39 07/13/07 - 07/20/07 < 22 < 22 < 18 < 19 < 22 07/20/07 - 07/27/07 < 43 < 43 < 42 < 42 < 44 07/27/07 - 08/03/07 < 46 < 46 < 45 < 65 < 46 08/03/07 - 08/10/07 < 22 < 40 < 40 < 45 < 41 08/10/07 - 08/17/07 < 55 < 69 < 70 < 44 < 70 08/17/07 - 08/24/07 < 61 < 65 < 66 < 66 < 60 08/24/07 - 08/31/07 < 27 < 16 < 70 < 39 < 25 08/31/07 - 09/07/07 < 34 < 65 < 66 < 59 < 67 09/07/07 -09/14/07 < 53 < 53 < 53 < 54 < 29 09/14/07 -09/21/07 < 22 < 41 < 41 < 46 < 41 09/21/07 -09/28/07 < 49 < 49 < 50 < 50 < 49 09/28/07 -10/05/07 < 41 < 52 < 52 < 50 < 52 10/05/07 -10/12/07 < 55 < 57 < 53 < 61 < 57 10/12/07 -10/19/07 < 21 < 39 < 42 < 37 < 39 10/19/07 -10/26/07 < 9 < 10 < 10 < 19 < 9 10/26/07 -11/02/07 < 49 < 49 < 49 < 62 < 49 11/02/07 -11/09/07 < 43 < 54 < 57 < 69 < 54 11/09/07 -11/16/07 < 37 < 47 < 50 < 53 < 47 11/16/07 -11/23/07 < 37 < 68 < 68 < 56 < 68 11/23/07 -11/30/07 < 15 < 15 < 29 < 29 < 29 11/30/07 -12/07/07 < 25 < 45 < 46 < 62 < 46 12/07/07 -12/14/07 < 19 < 35 < 35 < 28 < 35 12/14/07 -12/21/07 < 38 < 38 < 38 < 48 < 38 12/21/07 -12/28/07 < 50 < 50 < 52 < 58 < 50 MEAN - -----

(1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C- 17

TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA CONTROL FARM COLLECTION D-25 PERIOD 01/04/07 < 0.8 02/01/07 < 0.4 03/01/07 < 0.6 04/05/07 < 0.7 05/04/07 < 0.6 05/18/07 < 0.5 06/01107 < 0.6 06/15/07 < 0.6 06/29/07 < 0.7 07/13/07 < 0.6 07/27107 < 0.5 08/08/07 < 0.5 08/24/07 < 0.8 09/06/07 < 0.5 09/21/07 < 0.4 10/05/07 < 0.7 10/19/07 < 0.7 11/01/07 < 0.9 12/06/07 < 0.7 MEAN C- 18

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED INTHE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95

Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-25 01/04/07 <7 <7 <16 <9 < 17 <7 <11 <6 <6 < 29 < 12 02/01/07 <6 < 10 <18 <8 < 21 <8 <15 <7 <8 < 39 < 15 03/01/07 <5 <5 <13 <5 <13 <5 <8 <4 <6

23 <7 04/05/07 <5 <5 < 13 <6 < 12 <5 <9 <5 <5

29 < 10 05/04/07 <4 <5 <11 <5 < 10 <5 <8 <4 <5 < 31 <7 05/18/07 <5 <5 <11 <5 <11 <5 <8 <4 <5 < 23 <6 06/01/07 <5 <6 < 14 <5 <11 <6 <9 <5 <5 < 40 < 12 06/15/07 <4 <5 *12 <4 <12 <5 <9 <4 <4 < 44 *13 I

06/29/07 <5 <3 < 12 <5 < 10 <5 <9 <3 <4 < 35 < 13 07/13/07 <6 <6 *15 <7 < 14 <7 <11 <5 <6

38 <9 07/27/07 <6 <5 <16 <6 *14 <7 <12 <5 <6

38 < 13 08/08/07 <6 <6 < 13 < 7 < 13 <7 < 11 <5 <6 < 35 < 12 08/24/07 <4 <4 <11 <3 <9 <5 <9 <4 <3 < 37 < 14 09/06/07 <8 <9 < 22 <9 <19 <7 < 14 <7 <7 < 43 < 15 09/21/07 <4 <5 <11 <5 < 12 <5 <9 <4 <5 < 27 <7 10/05/07 <7 <8 < 17 <8 <16 <7 <10 <7 <8 < 45 < 13 10/19/07 <2 <2 <6 <2 <5 <2 <4 <2 <2 < 18 <6 11/01/07 <7 <7 <19 <8 < 17 <8 <11 <6 <6 < 44 < 14 12/06/07 <6 <8 < 19 <6 < 17 <8 < 14 <6 <7 < 54 < 13 MEAN

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD

,U"IN I rUL Cabbage 09/07/07 < 10 < 9 < 25 < 10 < 21 < 11 < 15 < 22. < 9 < 9 <48 < 14 Potatoes 09/07/07 < 20 < 18 < 49 < 24 < 49 < 20 < 23 < 59 < 18 < 24 < 147 < 53 MEAN D-QUAD 1 Cabbage 08/31/07 <8 < 9 < 25 < 9 < 22 < 10 < 18 < 55 < 7 <9 < 98 < 25 Onions 08/31/07 < 5 < 7 < 19 < 6 < 13 < 8 < 12 < 21 < 5 < 6 < 134 < 46 MEAN (I D-QUAD 2 0o Beets 08/31/07 <4 <6 <15 <6 <12 <6 <10 <34 <4 <5 < 53 < 15 Cabbage 08/31/07 <4 <4 <12 <4 <9 <4 <8 <23 <3 <4 < 41 < 14 MEAN D-QUAD 3 Cabbage 08/31/07 <9 <9 <24 <8 <22 <11 <17 <59 <7 <9 <87 < 16 Onions 08/31/07 <5 <6 <15 <5 <12 <6 <11 <38 <5 <5 <63 < 19 MEAN D-QUAD 4 Beets 08/31/07 <5 <5 <15 <5 <12 <6 <10 <33 <4 <5 <54 < 17 Broccoli 08/31/07 <3 <4 <10 <3 <8 <4 <6 <22 <3 <3 <36 <8 MEAN

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2007 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 23.5 +/- 6.0 21 21 25 27 D-01-2 22.5 +/- 5.0 22 22 20 26 D-02-1 23.3 +/- 7.9 22 22 20 29 D-02-2 23.8 +/- 4.4 23 23 22 27 D-03-1 21.0 +/- 4.3 19 20 21 24 D-03-2 19.5 +/- 7.4 18 18 17 25 D-04-1 24.0 +/- 7.8 22 25 20 29 D-04-2 24.8 +/- 3.8 22 25 26 26 D-07-1 21.5 +/- 6.6 21 21 18 26 D-07-2 23.0 +/- 4.9 21 21 24 26 D-08-1 23.0 +/- 4.3 23 21 22 26 D-08-2 23.0 +/- 6.7 21 22 21 28 D-10-1 23.8 +/- 5.7 24 24 20 27 D-10-2 22.5 +/- 6.2 21 24 19 26 D-12-1 21.0 +/- 5.9 21 20 18 25 D-12-2 19.8 +/- 4.7 18 20 18 23 D-13-1 19.5 +/- 1.4 19 20 (1) (1)

D-13-2 19.0 +/- 0.0 19 19 (1) (1)

D-14-1 20.0 +/- 4.9 20 20 17 23 D-14-2 19.5 +/- 5.3 18 20 17 23 D-45-1 24.8 +/- 8.7 24 23 21 31 D-45-2 24.0 +/- 8.2 22 23 21 30 D-53-1 18.8 +/- 5.7 17 18 17 23 D-53-2 18.8 +/- 7.2 18 17 16 24 D-55-1 24.3 +/- 3.0 25 23 23 26 D-55-2 24.3 +/- 6.8 23 24 21 29 D-56-1 19.5 +/- 7.4 18 18 17 25 D-56-2 19.8 +/- 3.4 20 19 18 22 D-101-1 23.8 +/- 8.2 21 25 20 29 D-101-2 22.3 +/- 7.9 21 21 19 28 D-102-1 24.8 +/- 7.2 23 24 22 30 D-102-2 23.8 +/- 5.7 23 22 22 28 D-103-1 22.3 +/- 4.4 21 23 20 25 D-103-2 23.0 +/- 4.0 21 23 (2) 25 D-104-1 26.0 +/- 3:7 25 24 27 28 D-104-2 21.8 +/- 6.0 21 21 19 26 D-105-1 22.5 +/- 5.8 20 25 20 25 D-105-2 23.3 +/- 7.7 27 21 19 26 D-106-1 20.3 +/- 6.6 18 20 18 25 D-106-2 20.8 +/- 5.5 19 22 18 24 D-107-1 20.0 +/- 5.4 19 19 18 24 D-107-2 20.3 +/- 4.4 19 21 18 23 D-108-1 25.0 +/- 8,2 22 23 24 31 D-108-2 21.5 +/- 6.2 19 20 21 26 D-109-1 24.5 +/- 3.8 25 23 23 27 D-109-2 24.0 +/- 6.9 21 21 27 27 (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION (2) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-21

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2007 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-110-3 26.5 +/- 4.8 25 28 24 29 D-110-4 25.5 1 6.2 24 25 23 30 D-111-1 25.3 +/- 6.4 24 24 23 30 D-111-2 22.0 +/- 6.7 21 20 20 27 D-112A-1 21.8 +/- 4.4 20 21 21 25 D-112A-2 20.5 +/- 5.0 20 18 20 24 D-113-1 20.3 +/- 5.3 19 18 20 24 D-113-2 21.0 +/- 6.7 19 19 20 26 D-114-1 20.8 +/- 6.2 21 18 19 25 D-114-2 20.5 +/- 4.8 20 19 19 24 D-115-1 23.0 +/- 4.3 21 22 23 26 D-115-2 22.8 +/- 5.7 21 21 22 27 D-116-1 25.3 +/- 7.5 26 24 21 30 D-116-2 23.3 +/- 6.6 23 21 21 28 D-201-1 25.8 +/- 3.4 25 26 24 28 D-201-2 25.5 +/- 6.2 25 23 24 30 D-202-1 23.0 +/- 7.7 24 20 20 28 D-202-2 22.5 +/- 6.0 21 .19 25 25 D-203-1 21.0 +/- 5.4 20 20 19 25 D-203-2 20.0 +/- 5.4 19 18 19 24 D-204-1 21.3 +/- 3.8 21 20 20 24 D-204-2 20.3 +/- 6.6 20 18 18 25 D-205-1 23.0 +/- 6.3 21 24 20 27 D-205-2 22.0 +/- 8.2 21 19 20 28 D-206-1 20.8 +/- 5.7 20 19 19 25 D-206-2 23.8 +/- 9.0 21 24 20 30 D-207-1 21.3 +/- 3.0 22 22 19 .22 D-207-2 21.5 +/- 6.2 19 21 20 26 D-208-1 18.8 +/- 6.2 19 16 17 23 D-208-2 19.3 +/- 5.3 18 19 17 23 D-209-1 19.0 +/- 5.9 19 16 18 23 D-209-2 18.8 +/- 5.7 17 17 18 23 D-210-1 22.0 +/- 5.4 20 21 21 26 D-210-2 21.8 +/- 7.2 21 19 20 27 D-211-1 23.3 +/- 5.3 21 23 22 27 D-211w-2 23.3 +/- 6.8 23 22 20 28 D-212-3 19.3 +/- 3.8 19 18 18 22 D-212-4 20.5 +/- 5.3 21 19 18 24 D-213-1 20.0 +/- 5.9 19 20 17 24 D-213-2 18.8 +/- 5.7 17 17 18 23 D-214-1 25.0 +/- 6.7 23 24 23 30 D-214-2 25.3 +/- 5.7 25 25 22 29 D-215-1 26.3 +/- 6.4 24 25 25 31 D-215-2 25.0 +/- 8.5 27 22 21 30 D-216-1 22.3 +/- 6.6 22 20 20 27.

D-216-2 24.0 +/- 6.9 23 23 21 29 C - 22

TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE INNER RING, OUTER RING, OTHER AND CONTROL LOCATIONS FOR DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION INNER RING OUTER RING OTHER CONTROL PERIOD + 2 S.D.

JAN-MAR 21.5 +/- 4.7 21.2 +/- 4.9 20.9 +/- 4.3 19.5 +/- 4.2 APR-JUN 21.8 +/- 4.8 20.6 +/- 5.5 21.3 +/- 4.6 20.0 +/- 0.0 JUL-SEP 21.0 +/- 4.8 20.1 +/- 4.5 20.1 +/- 5.4 18.0 +/- 0.0 OCT-DEC 26.6 +/- 4.4 26.1 +/- 5.4 26.2 +/- 4.7 24.0 +/- 2.8 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/- 2 S.D.

INNER RING 127 18 31 22.7 +/- 6.5 OUTER RING 128 16 31 22.0 +/- 7.0 OTHER 100 16 31 22.1 +/- 6.6 CONTROL 8 18 25 20.4 +/- 5.1 INNER RING STATIONS - D-101-1, D-101-2, D-102-1, D-102-2, D-103-1, D-103-2, D-104-1, D-104-2, D-105-1, D-105-2, D-106-1, D-106-2, D-107-1, D-107-2, D-108-1, D-108-2, D-109-1, D-109-2, D-110-3, D-110-4, D-111-1, D-111-2, D-112A-1, D-112A-2, D-113-1, D-113-2, D-114-1, D-114-2, D-115-1, D-115-2, D-116-1, D-116-2 OUTER RING STATIONS - D-201-1, D-201-2, D-202-1, D-202-2, D-203-1, D-203-2, D-204-1, D-204-2, D-205-1, D-205-2, D-206-1, D-206-2, D-207-1, D-207-2, D-208-1, D-208-2, D-209-1, D-209-2, D-210-1, D-210-2, D-211-1, D-211-2, D-212-3, D-212-4, D-213-1, D-213-2, D-214-1, D-214-2, D-215-1, D-215-2, D-216-1, D-216-2 OTHER STATIONS - D-01-1, D-01-2, D-02-1, D-02-2, D-03-1, D-03-2, D-04-1, D704-2, D-07-1, D-07-2, D-08-1, D-08-2, D-10-1, D-10-2, D-13-1, D-13-2, D-14-1, D-14-2, D-45-1, D-45-2, D-53-1, D-53-2, D-55-1, D-55-2, D-56-1, D-56-2 CONTROL STATIONS - D-12-1, D-12-2 C - 23

Intentionally left blank C -24

FIGURE C-1 SURFACE WATER - GROSS BETA - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-51 Dresden Lock &.Dam 10.0 01-01-00 12-31-00 12-31-01 t2-31-02 12-.31-03 12-30-04 D-52 (C) DesPlaines River 14.0 12.0 10.0 CL 6.0 4.0 2-0 0.0 -

01-0o'- 12-31-00 12-31-01 12-31-02 12-31-03 12-3!(,0 C -25

FIGURE C-1 (cont.)

SURFACE WATER - GROSS BETA -.STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2007 D-51 Dresden Lock & Dam 12.0 10.0 8.0

--

6.0 o,.

4.0 2.0 0.0 i I 01/27/05 09/04/05 04/12/06 11/18/06 06/26/07 D-52 (C) DesPlaines River 14.0 12.0 10.0

.- 8.0 C.)

a.

6.0-4.0 2.0 0.0 L 01-27-05 08-28-05 03-29-06 10-28-06 05-29-07 12-28-07 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-26

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

COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-54 (C) Kankakee River 14.0 12.O -

10.0 8.0' I~

6.0 4.0-2.0-fin 01-01G-0I 12-31-00 12-31-01 12-31-02 12-3t-03 12-30-04 C-27

FIGURE C-2 (cont.)

SURFACE WATER - GROSS BETA - STATION D-54 (C) and D-57 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2007 D-54 (C) Kankakee River 14.0 -

12.0 -

10.0 -

-J 8.0-Ct.

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

.- 20 C-

a. 16-12 8-4 0

07/28/06 11/08/06 02/19/07 06/02/07 09/13/07 12/25/07 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 -28

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

-j

,..I a- 15.

10.

5.

)J I I I I 04/27/07 06/27/07 08/27/07 10/27/07 12/27/07 D-21 PLACED INTO SERVICE ON MARCH 30, 2007, REPLACED D-51 C -29

FIGURE C-4 SURFACE WATER - TRITIUM - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-51 Dresden Lock & Dam 2000 1wo 1400.

12100-14'0I 01,)1,-0.1 12-.314X]- 17-t33-01 1"14a02 !2-31-4C3 12- 30-04 D-52 (C) Des Plaines River 0m -

5000 400 -

200 100-10:

Ii-toot, x 12-al-cil 12-31412 12,4 '!)2,30.f64 C -30

FIGURE C-4 (cont.)

SURFACE WATER - TRITIUM - STATIONS D-51 and D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2007 D-51 Dresden Lock & Dam 2000 ý 1800 1600 1400 1200

-J 0.

1000 800 600 400-200 0

03/31/05 12/29/05 09/28/06 06/28/07 D-52 (C) Des Plaines River 600 500 400 300 200 0 0 100 0

03/31/05 10/18/05 05/07/06 11/24/06 06/13/07 12/31/07 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-31

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

COLLECTED IN THE VICINITY OF DNPS, 2002 - 2004 D-54 (C) Kankakee River 4W4 300 wo0 4 100+

-100 4 I 00-a-0 1 ;2-31-00 12-31 -01 173E-2 12-3$1:-M IZ-30-414 C - 32

FIGURE C-5 (cont.)

SURFACE WATER - TRITIUM - STATION D-54 (C) AND D-57 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2007 D-54 (C) Kankakee River 800 700 600 500 o.400 300 -

200 100 0

03/31/05 10/22/05 05/15/06 12/06/06 06/29/07 Location shared with Braidwood Station (BD-10).

D-57 (C) Kankakee River 1200 1000 800

' 600 400 200 0 r 12/20/06 03/23/07 06/24/07 09/25/07 12/27/07 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-33

FIGURE C-6 SURFACE WATER - TRITIUM - STATION D-21 COLLECTED IN THE VICINITY OF DNPS, 2007 D-21 Illinois River 450 400 350

.300 250 C.

200 150 100 50 0 -

06/29/07 08/28/07 10/27/07 12/26/07 D-21 REPLACED D-51 JUNE 29, 2007 C- 34

FIGURE C-7 GROUND WATER - TRITIUM - STATIONS D-23 and D-35 COLLECTED IN THE VICINITY OF DNPS, 2000- 2004 D-23 Thorsen Iw0o 600+

400

/'

200 0 i-01i-01-00 -3 r -31e01 a2-31d-12-31k 2 1.2-30-04 D-35 Dresden Lock and Dam 400 300 200 100

/

0

/ /

-200 4 12 00 12-31-01 12-,.%1-02 C-35

FIGURE C-7 (cont.)

GROUND WATER - TRITIUM - STATIONS D-23 and D-35 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2007 D-23 Thorsen 10001 63001

-S..-

CL 600 I

400 200 0-03/31/05 10/15/05 05/01/06 11/15/06 06/01/07 12/16/07 D-35 Dresden Lock and Dam 400-350]

300]

250]

-J CL 200--

50-0o 03-31-05 10-02-05 04-05-06 10-07-06 04-10-07 10-12-07 DUE TO VENDOR CHANGE IN 2005, <VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-36

FIGURE C-8 AIR PARTICULATES - GROSS BETA - STATIONS D-01 and D-02 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 0-01 Onsite .Station 1 fil eD]

4~O

'U 14 1 4-O D-02 Onsite Station 2 MIci1.

ND no D.~+/- Du C-37

FIGURE C-8 (cont.)

AIR PARTICULATES - GROSS BETA - STATIONS D-01 and D-02 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2007 D-01 Onsite Station 1 50.0 40.0" E

30.0 C.,

0° 20.0 10.0 0.0 1 01/07/05 08/12/05 03/17/06 10/20/06 05/25/07 12/28/07 D-02 Onsite Station 2 50.0 E

c')

a.

0 Lut C.-

09-23-05 03-07-06 08-19-06 01-31-07 07-15-07 12-27-07 D-02 No samples; power was restored on 09-16-05.

DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-38

FIGURE C-9 AIR PARTICULATES - GROSS BETA - STATIONS D-03 and D-04 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-03 Onsite Station 3 i~fl 1

31 ?

It ii, an Ul-~4KI Iý-2* fta ,3 IŽ~3~~O4 D-04 Collins: Road

-M]

7-u IJO~-CL4 C-39

FIGURE C-9 (cont.)

AIR PARTICULATES - GROSS BETA - STATIONS D-03 and D-04 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2007 D-03 Onsite Station 3 50.0 40.0 E

30.0 0,.

C.,

9 20.0 10.0 0.0 4-01-07-05 08-12-05 03-17-06 10-20-06 05z25-07 12-28-07 D-04 Collins Road 60.0 50.0 C.)

40.0 0.

C., 30.0 9

LU 0

20.0 10.0 0.0 4--

01-07-05 08-12-05 03-17-06 10-20-06 05-25-07 12-28-07 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-40

FIGURE C-10 AIR PARTICULATES - GROSS BETA - STATIONS D-07 and D-12 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 D-07 Clay Products 1.)O 6.0]

wN Gi -D I x2a 1 Si ji 12211]t 17,-311-1ý73 12,3n-M 0-1 2 (C) Lisbon

.1 9 4:fJ

L cp~ .c~ 4K1 I;7-,tnei C-41

FIGURE C-10 (cont.)

AIR PARTICULATES - GROSS BETA - STATIONS D-07 and D-12 (C) COLLECTED IN THE VICINITY OF DNPS, 2005 - 2007 D-07 Clay Products 60.0 50.0 40.0 CL 0.

V~)

30.0 0U 20.0 10.0 0.0 01-07-05 08-12-05 03-17-06 10-20-06 05-25-07 12-28-07 06/10/05 - 06/17/05 no sample due to pump malfunction D-12 (C) Lisbon 60.0 -

50.0 -'

40.0 -

C-,

M. 30.0 9

wl 2 20.0 10-.0 5 0 1-07-05 08-12-05 03-17-06 10-20-06 05-25-07 12-28-07 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C - 42

FIGURE C-11 AIR PARTICULATES - GROSS BETA - STATIONS D-45 and D-53 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2004 0-45 McKinley Woods Road lOG 4.0 12 3 If'rl 1r~ki:rZ-D-53 Grundy County Road

~

a.j I V

N

&0;j

&91 pO*0i 1 12~~1~D2.

C - 43

FIGURE C-11 (cont.)

AIR PARTICULATES - GROSS BETA - STATIONS D-45 and D-53 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2007 D-45 McKinley Woods Road 50.0 40.0 E

30.0 CL 03.

20.0 10.0 0.0 -l 01-07-05 08-12-05 03-17-06 10-20-06 05-25-07 12-28-07 D-53 Grundy County Road 82.1 E

0.

CL m

en,I 0.0 +-

01-07-05 08-12-05 03-17-06 10-20-06 05-25-07 12-28-07 DUE TO VENDOR CHANGE, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C - 44

FIGURE C-12 AIR PARTICULATES - GROSS BETA - STATIONS D-08 and D-10 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2007 D-08 Prairie Park 70.0 60.0 czn n, E

G 40.0 9 30.0 Lu

- 20.0 10.0 0.0 I 01-07-05 08-12-05 03-17-06 10-20-06 05-25-07 12-28-07 D-10 Goose Lake Village 60.0 50.0 40.0 m 30.0 20.0 10.0 0.0 i 01-07-05 08-12-05 03-17-06 10-20-06 05-25-07 12-28-07 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C - 45

FIGURE C-13 AIR PARTICULATES - GROSS BETA - STATIONS D-13 and D-14 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2007 D-13 Minooka 50.0 40.0 E

30.0 0.

120.0 10.0 0.0 +--

01-07-05 07-06-05 01-02-06 07-01-06 12-28-06 06-26-07 D-14 Channahon 50.0 40.0 E

30.0 0'

20.0 10.0 0.0 i I I I I' I I 01-07-05 07-06-05 01-02-06 07-01-06 12-28-06 06-26-07 12-23-07 D-13 TAKEN OUT OF SERVICE JUNE 29, 2007 AND REPLACED WITH D-55 C-46

FIGURE C-14 AIR PARTICULATES - GROSS BETA - STATIONS D-55 and D-56 COLLECTED IN THE VICINITY OF DNPS, 2006-2007 D-55 Ridge Road 50.0 40.0 E

30.0 0.

20.0 10.0 0.0 I 01-06-06 05-30-06 10-21-06 03-14-07 08-05-07 12-27-07 D-56 Wildfeather 50.0 40.0.

E 30.0 C.)

CD, 20.0 10.0 0.0 I-07-25-06 12-02-06 04-11-07 08-19-07 12-27-07 D-55 NEW STATION DECEMBER 30, 2005 REPLACED D-13 JUNE 29, 2007 D-56 NEW STATION JULY 25, 2006 C-47

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

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

March 2007 E5255-396 Milk Sr-89 pCi/L 125 137 0.91 A Sr-90 pCi/L 10.8 10 1.08 A E5256-396 Milk 1-131 pCi/L 107 85.2 1.26 W Ce-141 pCi/L 269 297 0.91 A Cr-51 pCi/L 244 245 1.00 A Cs- 134 pCi/L 98.1 112 0.88 A Cs-1 37 pCi/L 227 234 0.97 A Co-58 pCi/L 92.5 98.8 0.94 A Mn-54 pCi/L 182.0 182 1.00 A Fe-59 pCi/L 108.0 106 1.02 A Zn-65 pCi/L 985 1000 0.99 A Co-60 pCi/L 143 152 0.94 ýA E5258-396 AP Ce-141 pCi 252 245 1.03 A Cr-51 pCi 204 202 1.01 A Cs-134 pCi 74.9 92.3 0.81 A Cs-137 pCi 190.0 197.0 0.96 A Co-58 pCi 79.7 81.6 0.98 A Mn-54 pCi 156 151 1.03 A Fe-59 pCi 99.1 87.2 1.14 A Zn-65 pCi 894 826 1.08 A Co-60 pCi 122 126 0.97 A E5257-396 Charcoal 1-131 pCi 34.7 71.3 0.49 N (1)

June 2007 E5384-396 Milk Sr-89 pqi/L 98.3 95.2 1.03 A Sr-90 pCi/L 16.1 12.9 1.25 W E5385-396 Milk 1-131 pCi/L 71.0 70.1 1.01 A Ce-141 pCi/L 176 200 0.88 A Cr-51 pCi/L 459 512 0.90 A Cs-134 pCi/L 197 242 0.81 A Cs-i 37 pCi/L 158 169 0.93 A Co-58 pCi/L 180 198 0.91 A Mn-54 pCi/L 163 166 0.98 A Fe-59 pCi/L 158 167 0.95 A Zn-65 pCi/L 318 334 0.95 A Co-60 pCi/L 212 238 0.89 A E5387-396 AP Ce-141 pCi 87.5 105 0.83 A Cr-51 pCi 232 268 0.87 A Cs-134 pCi 101 127 0.80 A Cs-137 pCi 78.9 88.5 0.89 A Co-58 pCi 91.8 104.0 0.88 A Mn-54 pCi 85.6 87 0.99 A Fe-59 pCi 89.8 87.3 1.03 A Zn-65 pCi 178 175 1.02 A Co-60 *pCi ill 125 0.89 A E5386-396 Charcoal 1-131 pCi 79.3 79.1 1.00 A D-1

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

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

September 2007 E5492-396 Milk Sr-89 pCi/L 99.0 94.9 1.04 A Sr-90 pCi/L 13.9 13.1 1.06 A E5493-396 Milk 1-131 pCi/L 81.9 85.2 0.96 A Ce-141 pCi/L 200 211 0.95 A Cr-51 pCi/L 271 289 0.94 A Cs-134 pCi/L 131 147 0.89 A Cs-1 37 pCi/L 131 131 1.00 A Co-58 pCi/L 114 114 1.00 A Mn-54 pCi/L 171 168 1.02 A Fe-59 pCi/L 117 111 1.05 A Zn-65 pCi/L 212 202 1.05 A Co-60 pCi/L 143 148 0.97 A E5495-396 AP Ce-141 pCi 128 136 0.94 A Cr-51 pCi 181 186 0.97 A Cs-134 pCi 85.9 94.7 0.91 A Cs-137 pCi 83.2 83.9 0.99 A Co-58 pCi 69.4 73.3 0.95 A Mn-54 pCi 112 108 1.04 A Fe-59 pCi 79.6 71.1 1.12 A Zn-65 pCi 159 130 1.22 W Co-60 pCi 92.0 95.2 0.97 A E5494-396 Charcoal 1-131 pCi 70.8 69.5 1.02 A December 2007 E5749-396 Milk Sr-89 pCi/L 87.6 93.7 0.93 A Sr-90 .pCi/L 15.5 15.2 1.02 A E5750-396 Milk 1-131 pCi/L 60.6 60.8 1.00 A Ce-141 pCi/L 137 141 0.97 A Cr-51 pCi/L 497 512 0.97 A Cs-1 34 pCi/L 117 137 0.85 A Cs-137 pCi/L 166 166 1.00 A Co-58 pCi/L 159 174 0.91 A Mn-54 pCi/L 190 190 1.00 A Fe-59 pCi/L 149 148 1.01 A Zn-65 pCi/L 231 234 0.99 A Co-60 pCi/L 198 211 0.94 A E57527396 AP Ce-141 pCi 88.6 93.4 0.95 A Cr-51 pCi 352 340 1.04 A Cs-1 34 pCi 84.6 91.2 0.93 A Cs-137 pCi ill 110.0 1.01 A Co-58 pCi 114 116.0 0.98 A Mn-54 pCi 135 126 1.07 A Fe-59 pCi 119 98.5 1.21 W Zn-65 pCi 172 155 1.11 A Co-60 pCi 137 141 0.97 A D-2

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

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

December 2007 E5751-396 Charcoal 1-131 pCi 65.8 74.1 0.89 A (1) New technician counted charcoalcartridgeon the back ratherthan the face, resulting in low activity. If the charcoalcartridge had been counted on the face, the ratio would have been approximately 1.07, which is acceptable. NCR 07-02 (a) Teledyne Brown Engineeringreported result.

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

(c) Ratio of Teledyne Brown Engineeringto Analytics results.

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

W-Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30. N = Not Acceptable. Reported result falls outside the ratio limits of < 0. 70 and > 1.30.

D-3

TABLE D-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 1 OF 1)

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

July 2007 Rad 70 Water Sr-89 pCi/L 58.6 58.2 49.5 - 66.9 A Sr-90 pCi/L 18.7 19.0 10.3- 27.7 A Ba-1 33 pCi/L 18.6 19.4 10.7-28.1 A Cs-134 pCi/L 57.6 68.9 60.2 - 77.6 N (1)

Cs-1 37 pCi/L 55.4 61.3 52.6 - 70.0 A Co-60 pCi/L 31.3 33.5 24.8 - 42.2 A Zn-65 pCi/L 49.0 54.6 45.2 - 64.0 A Gr-A pCi/L 26.8 27.1 15.4- 38.8 A Gr-B pCi/L 12 11.5 2.84 - 20.2 A 1-131 pCi/L 31.1 26.5 21.3- 31.7 A H-3 pCi/L 1700 1770 1180-2360 A October 2007 RAD 71 Water Sr-89 pCi/L 27.07 27.4 19.3 - 33.9 A Sr-90 pCi/L 17.40 18.2 12.9- 21.6 A Ba-1 33 pCi/L 12.57 12.6 8.64- 15.5 A Cs-1 34 pCi/L 63.33 71.1 58.0 - 78.2 A Cs-137 pCi/L 168 180 162 - 200 A Co-60 pCi/L 21.93 23.2 19.9- 28.3 A Zn-65 pCi/L 245.33 251 226 - 294 A Gr-A pCi/L 55.60 58.6 30.6 - 72.9 A Gr-B pCi/L 15.23 9.73 4.26 - 18.2 A 1-131 pCi/L 27.43 28.9 24.0 - 33.8 A H-3 pCi/L 9263.3 9700 8430- 10700 A (1) The Cs-134 TBE found/ERA known ratio is 83.6%, which TBE considersacceptable. NCR 07-07 (a) Teledyne.Brown Engineering reportedresult, (b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation.

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

D-4

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

TELEDYNE BROWN ENGINEERING, 2007 (PAGE 1 OF 1)

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

February 2007 07-MaW17 Water Cs-1 34 Bq/L 74.5 83.5 58.5 - 108.6 Cs-1 37 Bq/L 162 163.0 114-1 -211.9 Co-57 Bq/L 140 143.7 100.6- 186.8 Co-60 Bq/L 27.9 26.9 18.8-35.0 H-3 Bq/L 346 283.0 198.1 - 367.9 Mn-54 Bq/L 125 123.8 86.7- 160.9 Sr-90 Bq/L 8.90 8.87 6.21- 11.53 Zn-65 Bq/L 117 114.8 80.4- 149.2 07-GrW17 Water Gr-A Bq/L 0.502 0.327 >0.0 - 0.654 Gr-B Bq/L 0.975 0.851 0.426 - 1.277 07-MaS17 Soil Cs-134 Bq/kg 322 327.4 229.2 - 425.6 Cs-137 Bq/kg 893 799.7 559.8 - 1039.6 Co-57 Bq/kg 508.3 471.2 329.8 - 612.6 Co-60 Bq/kg 300.3 274.7 192.3 - 357.1 Mn-54 Bq/kg 779 685.2 479.6 - 890.8 K-40 Bq/kg 682 602 421 - 783 Sr-90 Bq/kg 293 319.0 223.3 - 414.7 Zn-65 Bq/kg 618.7 536.8 375.8 - 697.8 07-RdF17 AP Cs-134 Bq/sample 3.230 1.4960 2.9372 - 5.4548 Cs-137 Bq/sample 2.453 2.5693 1.7985 - 3.3401 Co-57 Bq/sample 3.067 2.8876 2.0213 - 3.7539 Co-60 Bq/sample 2.767 2.9054 2.0338 - 3.7770 Mn-54 Bq/sample 3.557 3.5185 2.4630 - 4.5741 Sr-90 Bq/sample 0.584 0.6074 0.4252 - 0.7896 Zn-65 Bq/sample 2.463 2.6828 1.8780 - 3.4876 07-GrF17 AP Gr-A Bq/sample 0.353 0.601 >0.0- 1.202 Gr-B Bq/sample 0.500 0.441 0.221 - 0.662 February 2007 07-RdV17 Vegetation Cs-134 Bq/sample 6.207 6.2101 4.3471 - 8.0731 A Cs-1 37 Bq/sample 7.80 6.9949 4.8964 - 9.0934 A Co-57 Bq/sample 8.64 8.1878 5.7315 -10.6441 A Co-60 Bq/sample 6.10 5.8215 4.0751 - 7.5680 A Mn-54 Bq/sample 9.41 8.4492 5.9144 - 10.9840 A K-40 Bq/sample 63.5 Not evaluated by MAPEP Sr-90 Bq/sample 1.51 1.5351 1.0746 - 1.9956 A Zn-65 Bq/sample 7.15 5.6991 3.9894 - 7.4088 W (a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value is equal to 100% of the parameterpresent in the standard as determined by gravimetricand/or volumetric measurements made during standardpreparation.

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

D-5

TABLE D-4 ERA(a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2007 (Page 1 of 2)

Concentration (pCi/L)

Lab Code

Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STAP-1116 03/19/07 Gr. Alpha 34.64 +/- 2.56 25.8 12.4 -39 Pass STAP-1 116 03/19/07 Gr. Beta 93.41 +/- 3.20 79.5 48.8-116 Pass STAP-1117 03/19/07 Co-60 1610.00 +/- 8.40 1300.0 1010.0 -1620 Pass STAP-i 117 03/19/07 Cs-1 34 1340.40 +/- 48.84 1120.0 732.0 -1380 Pass STAP- 1117e 03/19/07 Cs-137 345.30 +/- 8.20 255.0 192.0 -336 Fail STAP-1117' 03/19/07 Mn-54 < 5.0 0.0 Pass STAP-1l117 03/19/07 Sr-90 156.10 +/-+6.60 156.0 66.6-246 Pass STAP-1i117 03/19/07 Zn-65 363.80 +/- 11.90 245.0 208.0 -412 Pass STSO-1118 03/19/07 Ac-228 3097.77 +/- 94.96 2790.0 1790.0 -3930 Pass STSO-1 118 03/19/07 Bi-212 2467.87 +/- 114.33 2500.0 658.0 -3730 Pass STSO-1 118 03/19/07 Co-60 7847.40 +/- 86.60 7330.0 5340.0 -9820 Pass STSO-1 118 03/19/07 Cs-134 7910.60 +/- 356.88 7560.0 4850.0 -9070 Pass STSO-1118 03/19/07 Cs-137 4635.00 +/- 99.10 4300.0 3290.0 -5580 Pass STSO-1118 03/19/07 K-40 12201.60 +/- 423.20 11100.0 8050.0 -15000 Pass STSO- 1118 t 03/19/07 Mn-54 < 34.0 0.0 Pass STSO-1 118 03/19/07 Pb-212 2046.80 +/- 127.20 1730.0 1120.0 -2430 Pass STSO-1 118 03/19/07 Pb-214 4142.80 +/- 110.40 3330.0 1980.0 -4980 Pass STSO-1118 03/19/07 Sr-90 6163.30 +/- 791.60 7500.0 2610.0 -12400 Pass STSO-1i118 03/19/07 Th-234 4329.40 +/- 569.10 3590.0 2190.0 -4560 Pass STSO-1118T 03/19/07 Zn-65 0.00 +/- 0.00 0.0 0.0 -0 Pass STVE-1 119 03/19/07 Co-60 2827.90 +/- 62.40 2600.0 1760.0 -3720 Pass STVE-1 119 03/19/07 Cs- 134 654.80 +/- 48.40 579.0 308.0 -822 Pass STVE-1119 03/19/07 Cs-137 3307.30 +/- 58.80 2920.0 2150.0 -4060 Pass STVE-1119 03/19/07 K-40 40814.20 +/- 618.80 37900.0 27200.0 -53600 Pass T Pass STVE-1119 03/19/07 Mn-54 < 27.6 0.0 STVE-1119 03/19/07 Sr-90 8999.70 +/- 580.90 8890.0 4900.0 -11800 Pass STVE-l 119 03/19/07 Zn-65 474.30 +/- 45.70 366.0 267.0 -500 Pass STW-1120 03/19/07 Co-60 541.40 +/- 9.00 536.0 467.0 -631 Pass STW-1120 03/19/07 Cs-134 1623.80 +/- 66.10 1750.0 1290.0 -2020 Pass STW-1 120 03/19/07 Cs-137 1839.10 +/- 17.90 1850.0 1570.0 - 2220 Pass STW-1120' 03/19/07 Mn-54 <8.1 0.0 Pass STW-1120 03/19/07 Sr-90 949.40 +/- 16.70 989.0 630.0 -1320 Pass STW-1 120 03/19/07 Zn-65 2009.00 +/- 36.40 1910.0 1600.0 -2410 Pass STW-1121 04/09/07 Sr-89 30.7 +/- 4.3 35.4 26.7 -44.1 Pass STW-1 121 04/09/07 Sr-90 39.3 +/- 1.8 42.1 33.4 - 50.8 Pass D-6

TABLE D-4 ERAIa) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2007 (Page 2 of 2)

Concentration (pCi/L)

Lab Code

Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 122 04/09/07 Ba-133 30.0 +/- 2.4 29.3 20.6 - 38.0 Pass STW-1 122 04/09/07 Co-60 118.5 +/- 3.9 119.0 109.0 - 129.0 Pass STW-1 122 04/09/07 Cs-134 52.6 +/- 2.3 54.3 45.6 - 63.0 Pass STW-1 122 04/09/07 Cs-137 49.5 +/- 3.8 50.3 41.6 -59.0 Pass STW-1 122 04/09/07 Zn-65 91.7 +/- 6.3 88.6 73.3 - 104.0 Pass STW-1 123 04/09/07 Gr. Alpha 33.8 +/- 3.5 56.5 32.0 -81.0 Pass STW-1 123 04/09/07 Gr. Beta 24.2 +/- 2.3 25.3 16.6 -34.0 Pass STW-1 124 04/09/07 1-131 19.2 +/- 1.2 18.9 13.7 -24.1 Pass STW-1 125 04/09/07 H-3 7540.0 +/- 255.0 8060.0 6660.0 - 9450.0 Pass STW-1 127 07/09/07 Sr-89 51.7 +/- 5.0 58.2 49.5 - 66.9 Pass STW-1 127 07/09/07 Sr-90 21.4 +/- 2.3 19.0 10.3 - 27.7 Pass STW-1 128 07/09/07 Ba-133 19.4 +/- 2.2 19.4 10.7 -28.1 Pass STW-1 128 07/09/07 Co-60 32.8 +/- 2.0 33.5 24.8 - 42.2 Pass STW-1 128 07/09/07 Cs-134 67.0 +/- 2.9 68.9 60.2 - 77.6 Pass STW-1 128 07/09/07 Cs-137 61.6 +/- 3.8 61.3 52.6 - 70.0 Pass STW-1 128 07/09/07 Zn-65 55.6 +/- 7.5 54.6 .45.2 - 64.0 Pass STW-1 129 07/09/07 Gr. Alpha 19.2 +/- 1.6 27.1 15.4 - 38.8 Pass STW-1 129 07/09/07 Gr. Beta 9.1 +/- 0.9 11.5 2.8 - 20.2 Pass STW-1 131 10/05/07 Sr-89 27.3 +/- 3.3 27.4 19.3 - 33.9 Pass STW-1 131 10/05/07 Sr-90 17.7 +/- 1.2 18.2 12.9 -21.6 Pass STW-1 132 10/05/07 Ba-1 33 12.2 +3.3 12.6 8.6 - 15.5 Pass STW-1132 10/05/07 Co-60 23.8 +/- 1.4 23.2 19.9 - 28.3 Pass STW-1 132 10/05/07 Cs-134 70.5 +/- 4.2 71.1 58.0 - 78.2 Pass STW-1 132 10/05/07 Cs-137 178.2 +/-3.3 180.0 162.0 - 200.0 Pass STW-1 132 10/05/07 Zn-65 263.9 +/- 6.9 251.0 226.0 - 294.0 Pass STW-1 133 10/05/07 Gr. Alpha 54.7 +/-2.1 58.6 30.6 - 72.9 Pass STW-1 133 10/05/07 Gr. Beta 11.9 +/-0.9 9.7 4.3 - 18.2 Pass STW- 1134 10/05/07 1-131 33.0 +/- 1.5 28.9 24.0 - 33.8 Pass STW-1 135 10/05/07 H-3 9965.0 + 250.0 9700.0 8430.0 - 10700.0 Pass Laboratory codes as follows: STvv (water), STAP (air filter), STSO (soil), STVE (vegetation).

a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

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

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

A high bias (- 20%) was observed in gamma results for air filters. A composite filter geometry was used in the calculations vs. a single filter geometry. Result of recalculation. Cs-1 37, 305.8 +/- 6.0 pCi/filter.

f Included in the testing series as a "false positive". No activity expected.

D-7

TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2007 (Page I of 1)

Concentration b (Page of 1)INC., 2007 1Concentration ENVIRONMENTAL, Known Control Lab Codec Date *Analysis Laboratory result Activity Limits d Acceptance STW-1110 01/01/07 Gr. Alpha 0.45 +/- 0.08 0.33 0.00 - 0.65 Pass STW-1110 01/01/07 Gr. Beta 0.90 +/- 0.14 0.85 0.43 - 1.28 Pass STW-1111 01/01/07 Co-57 151.60 +/- 10.00 143.70 100.60 - 186.80 Pass 83.50 STW-1111 01/01/07 Cs-134 79.20 +/- 8.00 58.50 - 108.60 Pass STW-i111 01/01/07 Cs-137 168.70 +/- 12.10 163.00 114.10 -211.90 Pass STW-1111 01/01/07 H-3 262.20 +/- 9.10 283.00 198.10 -367.90 Pass STW-1111 01/01/07 Mn-54 130.60 +/- 11.50 123.80 86.70 - 160.90 Pass STW-1111 01/01/07 Sr-90 9.60 +/- 1.40 8.87 6.21 -11.53 Pass STW-1111 01/01/07 Zn-65 123.70 +/- 17.00 114.80 80.40 - 149.20 Pass STSO-1 112 01/01/07 Co-57 501.20 +/- 2.90 471.20 329.80 -612.60 Pass STSO-1 112 01/01/07 Co-60 285.90 +/- 2.10 274.70 192.30 -357.10 Pass STSO-1 112 01/01/07 Cs-134 325.90 +/- 7.40 327.40 229.20 -425.60 Pass STSO-1112 01/01/07 Cs-137 855.70 +/- 4.60 799.70 559.80 -1039.60 Pass STSO-1 112 01/01/07 Mn-54 750.90 +/- 4.70 685.20 479.60 -890.80 Pass STAP-1i113 01/01/07 Gr. Alpha 0.27 +/- 0.04 0.60 0.00-1.20 Pass STAP-1i113 01/01/07 Gr. Beta 0.57 +/- 0.05 0.44 0.22 - 0.66 Pass STAP-i 114 01/01/07 Co-57 3.51 +/- 0.07 2.89 2.02 -3.75 Pass STAP-i 114 01/01/07 Co-60 2.98 +/- 0.10 2.91 2.03 - 3.78 Pass STAP-1 114 01/01/07 Cs-134 4.02 +/- 0.16 4.20 2.94 -5.45 Pass STAP-i 114 01/01/07 Cs-137 2.75 +/- 0.12 2.57 1.80 -3.34 Pass STAP-1 114 01/01/07 Mn-54 3.94 +/- 0.12 3.52 2.46 -4.57 Pass STAP-1 114 01/01/07 Sr-90 0.58 +/- 0.18. 0.61 0.43 -0.79 Pass STAP-1 114 01/01/07 Zn-65 2.70 +/- 0.10 2.68 1.88 -3.49 Pass STVE-1115 01/01/07 Co-57 8.90 +/- 0.20 8.19 5.73 -10.64 Pass STVE-1 115 01/01/07 Co-60 6.50 +/- 0.20 5.82 4.08 -7.57 Pass STVE-1115 01/01/07 Cs-134 6.90 +/- 0.30 6.21 4.35 -8.07 Pass STVE-1115 01/01/07 Cs-137 8.20 +/- 0.30 6.99 4.90 -9.09 Pass STVE-1115 01/01/07 Mn-54 10.10 +/- 0.30 8.46 5.91 -10.98 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

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

D-8

APPENDIX E ERRATA DATA

There is no errata data for 2007.

E- 1

APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Docket No: 50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2007 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Dresden Nuclear Power Station Norris, IL 60450 May 2008

Table Of Contents

1. Summary and Conclusions..................................................... I................. 1 11.Introduction ........................................................................................ 2 A. Objectives of the RGPP ................................................................ 3 B. Implementation of the Objectives...................................................... 4 C. Program Description .................................................................... 4

0. Characteristics of Tritium (H-3) ........................................................ 5 Ill. Program Description ............................................................................ 6 A. Sample Analysis......................................................................... 6 B. Data Interpretation....................................................................... 6 C. Background Analysis.................................................................... 7

1. Background Concentrations of Tritium ........................................ 7 IV. Results and Discussion ........................................................................ 9 A. Groundwater Results.................................................................... 9 B. Drinking Water Well Survey........................................................... 10 C. Summary of Results - Inter-laboratory Comparison Program .................... 10 D. Leaks, Spills, and Releases .......................................................... 10 E. Trends ................................................................................... 10 F. Investigations ........................................................................... 10 G. Actions Taken...........I................................................................ 11

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Appendices Appendix A Location Designation Tables Table A-1: Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2007 Figures Security-Related Information: Maps of the Dresden Nuclear Power Station have been withheld from public disclosure under 10CFR2.390 and N.J.S.A. 47:1A-1.1 Appendix B Data Tables Tables Table B-I.1 Concentrations of Tritium in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table B-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

Table B-11.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2007.

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

The Dresden power plant has experienced a number of leaks from underground lines and spills from above ground systems containing radioactive water over its 40-year history. These incidents have created a number of areas of localized contamination within the P.A. Isotopic analyses of groundwater in many of these areas show measurable concentrations of tritium (H-3). In addition, Strontium (Sr-90) was detected just above the Lower Limit of Detectability (LLD) in one of the wells within the P.A.

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

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

htm.

Dresden has a domestic water system that is supplied by two deep wells (1500 feet deep) that were installed about 50 years ago south of the P.A. Samples taken from domestic water supply and have never shown any detectable tritium concentration.

Tritium has a half-life of 12.3 years. This means that 40 years from now 90% of the tritium on site today will have decayed away to more stable elements.

Given the limited volume of contaminated groundwater on site, radioactive decay, slow groundwater movement, and dilution effects the conclusion of the HIR is that the operation of Dresden Nuclear Power Station had no adverse radiological impact on the environment. As a result there is little potential for contaminated groundwater on site to affect off-site drinking water.

II. Introduction Radiological Groundwater Monitoring Program (RGPP):

Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions.

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

The Dresden RGPP was established in 2006 and there have been no significant changes to this program. This program does not impact the operation of the plant and is independent of the REMP.

Developed groundwater wells are wells that were installed specifically for monitoring groundwater. These wells are equipped with screens and are properly sealed near the surface to avoid surface water intrusion. The wells were designed in accordance with appropriate codes and developed in accordance with appropriate standards and procedures. Dresden has groundwater monitoring wells identified as "shallow" (depths from 15 to 35 feet), "Intermediate" (depths from 35 to 55 feet) and "deep" (depths beyond 100 feet). All wells installed to a depth greater than 100 feet ("deep" wells) were found to be dry and removed from the RGPP. Surface water sample points are identified sample locations in the station's canals and cooling pond.

There are 71 sampling points in the RGPP:

Dresden has 39 developed groundwater monitoring wells within the Protected Area.

Some of these wells form a ring just inside the security fence and the remaining wells were installed near underground plant system piping that contains radioactive water.

Dresden has 26 developed groundwater monitoring wells outside the P.A. the majority of which form a ring just within the perimeter of the property.

Dresden has 6 surface water monitoring locations on the owner-controlled area sampled as part of the Dresden RGPP. These consist of one sample from each of the 5 different canals and one sample from the cooling pond.

The Dresden site-specific RGPP procedure identifies the historic 'events' that would affect the individual RGPP sample results. This procedure identifies threshold values for each sample point, which if exceeded, could be an indication of a new spill from an above ground system or a new leak in an underground pipe containing tritiated water.

The RGPP sample points are currently sampled on a frequency of twice per year.

During 2007, there were 194 analyses that were performed on 130 samples from 71

sample points.

Supplemental Radiological Groundwater Monitoring Program (SRGPP)7 Dresden also has a Supplemental Radiological Groundwater Monitoring Program (SRGPP) that provides short-term monitoring of a limited selection of monitoring points, mostly within the P.A., intended to identity relatively rapid changes in the groundwater tritium concentrations.

Sentinel Wells, sometimes referred to as "baby wells" are wells that were installed to monitor local shallow groundwater; typically in associated with a historic underground pipe leak. These wells are not constructed to code or developed to a standard. Most sentinel wells are from 6 to 12 feet deep and consist of 2" PVC pipe without screens.

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

Dresden has two basic storm water runoff sewer systems within the P.A: one sewer-system routes to the east, then north, and discharges into the Unit 1 intake canal, the second sewer-system routes to the west, then north, through a large Oil Separator, and discharges to the hot canal. Both the Unit 1 intake canal and the hot canal eventually route to the cooling pond.

The Dresden site-specific RGPP procedure identifies the historic 'events' that would affect the individual SRGPP 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.

During 2007 the Dresden SRGPP sampling included 3 sewers, 8 sentinel wells and a variety of RGPP wells. Samples were taken at a frequency of approximately every two weeks. There were 441 analyses performed on 441 samples from 17 different sample points.

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 SRGPP is to provide indication of short-term changes to groundwater tritium concentrations within the P.A.

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

Specific Objectives include:

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

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

3. Regularly assess analytical results to identify adverse trends.

4. Take necessary corrective actions to protect groundwater resources.

B. Implementation of the Objectives

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

2. Dresden Nuclear Power Station has implemented new 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. Ifthe investigation identifies a leak or unidentified spill, corrective actions will be implemented.

C. Program Description Dresden has a Radiological Groundwater Monitoring Program (RGPP) that provides long-term monitoring intended to verify the fleet-wide hydrogeologic study conclusions. Dresden uses 71 developed groundwater wells and surface water sample points in the RGPP.

Dresden also has a Supplemental Radiological Groundwater Monitoring Program (SRGPP) that provides short-term monitoring of a limited selection of monitoring points mostly within the P.A. intended to identity relatively rapid changes in the groundwater tritium concentrations. In addition to the 71 sampling points in the RGPP, the SRGPP also includes sampling of 9 sentinel wells, 39 sewers and 1-trench totaling 120 possible sample points.

1. Sample Collection Sample locations can be found in Table A-1 and Figures A-1 and A-2, Appendix A.

Groundwater and Surface Water Water samples are collected in accordance with the schedule delineated in the Dresden site-specific RGPP and SRGPP procedures. Analytical laboratories are subject to internal quality assurance programs, industry crosscheck programs, as well as nuclear industry audits. Station personnel review and evaluate the analytical results.

D. Characteristics of Tritium (H-3)

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

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

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

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

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

associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.

Ill. 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 2007.

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

1. Concentrations of gamma emitters in groundwater and surface water.

.2. Concentrations of strontium in groundwater and surface water.

3. Concentrations of tritium in groundwater and surface water.

B. Data Interpretation The radiological data collected prior to 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 specified by federal regulation as a 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 12 nuclides, K-40, 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.

C. Background Analysis A pre-operational radiological environmental monitoring program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, marine life, and foodstuffs. The results of the monitoring were detailed in the report entitled, Environmental Radiological Monitoring for Dresden Nuclear Power Nuclear Power Station, Commonwealth Edison Company, Annual Report 1986, May 1987.

1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others. Additional detail may be found by consulting references (CRA 2006).

a. Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the

bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

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

b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected world wide from 1960 to 2006.

RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time. Tritium concentrations in Midwest precipitation have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200-pCi/L detection limit from the external causes described above. Water from previous years and decades is naturally captured in groundwater, so some well water sources today are affected by the surface water from

the 1960s that was elevated in tritium.

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

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

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

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

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

Tritn um.

Of the 39 developed groundwater-monitoring wells inside the Protected Area, 28 wells show some level of tritium contamination ranging from just above LLD to 150,000 pCi/L.

Of the 26 developed groundwater-monitoring wells outside the Protected Area, 2 wells show tritium contamination just above LLD. One of these wells is located near the radwaste discharge line (about 200 yards north of the plant) that ruptured in 1999. The other well is about 1500 feet south of the Security Check point adjacent to the hot canal that had measurable concentrations of tritium from an upstream source.

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Gamma Emitters and Strontium Potassium-40 was detected in four of 64 samples. The concentrations ranged from 58 pCi/liter to 165 pCi/liter. No other gamma emitting nuclides were detected. (Table B-I.2, Appendix B).

B. Drinking Water Well Survey A drinking water well survey was conducted during the summer 2006 by CRA (CRA 2006) around the Dresden Nuclear Power Station.

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

D. Leaks, Spills, and Releases In the summer of 2004 elevated tritium concentrations were identified in sentinel wells by the HPCI suction line near the HPCI room. This line was found leaking and about one-half of the line was excavated and replaced.

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

There have been no incidences of a leaks or spills at Dresden Station in 2007.

E. Trends The tritium concentration in the water found near the 2004 HPCI leak is traveling to the west. Wells in the vicinity show that tritium levels have been trending down slightly.

F. Investigations Following a heavy rain in August of 2007, water was flowing into the Cribhouse basement through an underground electrical penetration. The water contained tritium at a concentration above LLD. Samples taken the

next day were showed higher concentrations of tritium suggesting an increasing trend.

Further monitoring showed the tritium concentration was steady for a few days then started decreasing. The flow decrease over the next several days then stopped completely. If this were a leak of an underground piping system we would expect that the flow would continue.

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

G. Actions Taken

1. Compensatory Actions No compensatory actions were taken as a result of the RGPP in 2007.

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

APPENDIX A TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations Dresden Nuclear Power Station, 2007 Site Site Type Location DSP-105 Monitoring Well 30 feet east of the east wall of the EM Shop DSP-106 Monitoring Well 65 feet east of east wall of EM Shop DSP- 107 Monitoring Well 9 feet east of the east Unit 1 Fuel Pool wall DSP-108 Monitoring Well 40 ft east of the Unit 1 Sphere DSP-117 Monitoring Well Northeast of Unit 1 Sphere; 825feet west of Ross Bridge DSP-121 Monitoring Well 72 feet north of 2/3 Intake Canal fence DSP-122 Monitoring Well 50 feet north of the Radwaste Tank Farm DSP-123 Monitoring Well Northeast corner of the Unit 1 Off-gas Building DSP-124 Monitoring Well 9 feet south of Floor Drain Collector Tank DSP-125 Monitoring Well Northeast corner of the Unit 2/3A CST DSP-126 Monitoring Well 21 feet northwest of the northwest bend in road behind Training Building DSP-147 Monitoring Well 325 feet west of Telemetry Bridge DSP-148 Monitoring Well 130 feet southeast of the Flow Regulating Station building DSP-149R Monitoring Well 35 feet south by southwest of the 138 KV yard fence DSP-150 Monitoring Well 85 feet east of the northeast corner of the Unit 1 Spent Fuel Pool pad DSP-151 Monitoring Well 65 feet north of the northeast corner of the Storeroom DSP-1 52 Monitoring Well 210 feet south by southeast of the southeast corner of Maintenance Garage DSP-153 Monitoring Well 150 feet east of the southeast corner of liquid hydrogen tank farm fence DSP-154 Monitoring Well 33 feet west of the track; 165 feet east of the Security Checkpoint DSP-1 56 Monitoring Well 70 feet east by northeast of the northwest corner of 138 KV yard fence DSP-157-1 (M) Monitoring Well 25 feet south of the south edge of the Employee Parking lot DSP-1 57-S Monitoring Well 25 feet south of the south edge of the Employee Parking lot DSP-158-1 (M) Monitoring Well 53 feet west of the Kankakee River; 33 feet west of the cinder track DSP- 158-S Monitoring Well 50 feet west of the Kankakee River; 33 feet west of the cinder track DSP-159-1 (M) Monitoring Well 250 feet west of the Thorsen house; 450 ft south of the plant access gate DSP- 159-S Monitoring Well 251 feet west of the Thorsen house; 450 ft south of the plant access gate MW-DN-101-1 Monitoring Well 60 feet north of the Unit 1 Diesel Fuel Storage MW-DN-101-S Monitoring Well 60 feet north of the Unit 1 Diesel Fuel Storage MW-DN-102-1 Monitoring Well 12 feet south of the southeast corner of the MUDS Building MW-DN-1 02-S Monitoring Well 13 feet south of the southeast corner of the MUDS Building MW-DN-103-1 Monitoring Well 280 feet west of the northwest corner of N-GET Building MW-DN-103-S Monitoring Well 281 feet west of the northwest corner of N-GET Building MW-DN-104-S Monitoring Well 50 feet north of Radwaste Tank Farm MW-DN-1 05-S Monitoring Well 65 feet north of the northeast corner of the Storeroom.

MW-DN-106-S Monitoring Well 75 feet north of the 2/3 Intake Canal fence; east of the Unit 1 Intake Canal MW-DN- 107-S Monitoring Well 15 feet west by southwest of the Unit 1 CST MW-DN-108-1 Monitoring Well 7 feet southwest of the southwest corner of the Unit 1 Cribhouse MW-DN- 109-1 Monitoring Well 8 feet north of Chemistry Building MW-DN-109-S Monitoring Well 8 feet north of Chemistry Building MW-DN-110-1 Monitoring Well 25 feet west of the Waste Water Treatment (WWT) Building MW-DN-110-S Monitoring Well 25 feet west of the Waste Water Treatment (WWT) Building MW-DN- 111-S Monitoring Well 9 feet east of the Floor Drain Collector Tank MW-DN-1 12-1 Monitoring Well 100 feet south of the Chemistry Building A-1

TABLE A-I: Radiological Groundwater Protection Program - Sampling Locations Dresden Nuclear Power Station, 2007 Site Site Type Location MW-DN-1 12-S Monitoring Well 100 feet south of the Chemistry Building MW-DN-1 13-1 Monitoring Well 90 feet west of the southwest corner of the Administration Building MW-DN-1 13-S Monitoring Well 91 feet west of the southwest corner of the Administration Building MW-DN-1 14-1 Monitoring Well 50 feet east of the Unit 1 Clean Demineralized Water Tank MW-DN-1 14-S Monitoring Well 8 feet southwest of the Radiation protection Dept west access doors MW-DN-115-1 Monitoring Well 11 feet south of Instrument Maintenance Shop MW-DN_1 15-S Monitoring Well 12 feet south of Instrument Maintenance Shop MW-DN-1 16-1 Monitoring Well 75 feet south of the Calgon Building roll-up door MW-DN-1 16-S Monitoring Well 75 feet south of the Calgon Building roll-up door MW-DN-1 17-1 Monitoring Well 35 feet east by northeast of the Unit 1 Stack MW-DN-118-S Monitoring Well Southeast corner of the Unit I Fuel Pool MW-DN-1 19-1 Monitoring Well 20 feet east by northeast of the Unit 1 Sewage Ejector Building MW-DN-1 19-S Monitoring Well 21 feet east by northeast of the Unit 1 Sewage Ejector Building MW-DN-120-1 Monitoring Well 45 feet north by northeast of the Ross Bridge railing MW-DN- 120-S Monitoring Well 46 feet north by northeast of the Ross Bridge railing MW-DN-121-S Monitoring Well 7 feet west of the dirt road; 42 feet east of the 345KV yard fence MW-DN-122-1 Monitoring Well 150 feet north of Heineke Road; northeast of the G.E. Fuel Storage Facility MW-DN-122-S Monitoring Well 150 feet north of Heineke Road; northeast of the G.E. Fuel Storage Facility MW-DN-123-1 Monitoring Well 400 feet west of the Thorsen house; west of the Cold Canal MW-DN-123-S Monitoring Well 400 feet west of the Thorsen house; west of the Cold Canal MW-DN-124-1 Monitoring Well 10 feet south of the liquid nitrogen inerting tanks MW-DN-124-S Monitoring Well 10 feet south of the liquid nitrogen inerting tanks SW-DN-101 Surface Water Unit 2/3 Intake (DSP50) at the Ross Bridge SW-ON-i102 Surface Water Unit 2/3 Discharge (DSP20) at the Telemetry Bridge SW-DN-103 Surface Water Unit 2/3 Return Canal at the Discharge to the Intake Canal SW-DN-104 Surface Water Cold Canal (DSP34A) at the Cooling Tower walkway bridge SW-DN-105 Surface Water Hot Canal (DSP34B) at the Cooling Tower walkway bridge SW-DN-106 Surface Water Cooling Pond - Pool II at the east side of the Covered Bridge A-2

APPENDIX B DATA TABLES

TABLE B-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICNITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 DSP-105 05/10/07 301 +/- 109 DSP-1 05 10/23/07 193 +/- 122 DSP-106 05/21/07 2540 +/- 299 DSP-106 10/23/07 2670 +/- 339 DSP-107 05/21/07 7430 +/- 782 DSP-107 10/23/07 7380 +/- 802 DSP-108 05/21/07 1770 +/- 225 DSP-108 10/23/07 1790 +/- 251 DSP-117 05/02/07

161 DSP-1 17 10/30/07 < 194 DSP-121 05/02/07 < 154 DSP-121 10/30/07 < 188 DSP-122 05/11/07 3930 +/- 432 DSP-122 10/26/07 3990 +/- 467 DSP-123 05/21/07 12200 +/- 1260 DSP-123 10/26/07 11200 +/- 1180 DSP-124 05/21/07 28600+/- 2890 DSP-1 24 10/26/07 18700 +/- 1920 DSP-125 05/09/07 319 +/- 110 DSP-1 25 10/26/07 203 +/- 127 DSP-126 05/01/07 < 155 DSP-126 10/31/07 < 194 DSP-147 05/02/07 < 156 DSP-147 10/30/07 < 194 DSP-148 05/02/07 268 +/- 112 DSP-148 10/30/07 235 +/- 130 DSP-149R 05/02/07 463 +/- 116 DSP-149R 10/30/07 399 +/- 134 DSP-1 50 05/08/07 < 148 DSP-150 10/25/07 < 195 DSP-151 05/08/07 189 +/- 99 DSP-151 10/25/07 < 191 DSP-152 05/01/07 < 155 DSP-1 52 11/01/07 < 192 DSP-153 05/01/07 < 156 DSP-1 53 10/31/07 < 192 DSP-154 05/01/07 < 160 DSP-154 10/31/07 < 196 DSP-156 05/02/07 < 161 DSP-156 10/30/07 233 + 134 DSP-157M 05/01/07 < 157 DSP-1 57M 10/31/07 < 189 DSP-157S 05/01/07 < 154 DSP-157S 10/31/07 < 199 SAMPLES ARE DISTILLED FOR H-3 ANALYSIS B-I

TABLE B-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICNITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 DSP-1581 11/01/07

188 H-3 DSP-158M 05/01/07 < 153 DSP-158S 05/01/07 < 157 DSP-1 58S 11/01/07 < 199 DSP-159M 05/02/07 596 +/- 129 DSP-159M 10/29/07 416 +/- 140 DSP-159S 05/02/07 < 156 DSP-159S 10/29/07 < 198 MW-lOll 05/09/07 2420 +/- 286 MW-iOl 10/24/07 1830 +/- 258 MW-lOiS 05/09/07 < 148 MW-1i1S 10/24/07 195 +/- 128 MW-1 021 05/11/07 < 148 MW-1021 10/25/07 < 192 MW-1 02S 05/11/07 252 +/- 104 MW-102S 10/25/07 480 +/- 140 MW-1 031 05/01/07 356 +/- 112 MW-1031 11/01/07 188 +/- 120 MW-103S 05/01/07 < 147 MW-103S 11/01/07 < 179 MW-1 04S 05/11/07 246 +/- 104 MW-1 04S 10/26/07 382 +/- 134 MW-105S 05/08/07 178 +/- 101 MW-105S 10/25/07 < 192 MW-106S 05/02/07

145 MW-1 06S 10/30/07 < 177 MW-107S 05/21/07 255 +/- 105 MW-107S 10/25/07 2350 +/- 306 MW-1 081 05/11/07 < 156 MW-1 081 10/24/07 < 193 MW-1091 05/10/07 1090 +/- 167 MW-i 091 10/24/07 541 +/- 141 MW- 109S 05/10/07 254 +/- 109 MW-109S 10/24/07 < 190 MW-1101 05/08/07 429 +/- 119 MW-1101 10/24/07 525 +/- 143 MW-iiOS 05/08/07 < 156 MW-ilOS 10/24/07 < 192 MW-ilS 05/11/07 767 +/- 138 MW-11iS +/-

10/26/07 742 157 MW-1121 05/09/07 1410 +/- 197 MW-1 12S 05/09/07 < 160 SAMPLES ARE DISTILLED FOR H-3 ANALYSIS B-2

TABLE B-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICNITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 MW-1 131 05/08/07 < 157 MW-1 131 10/25/07 < 196 MW-113S 05/08/07 < 156 MW-113S 10/25/07 349 +/- 135 MW-1 141 05/21/07 7890 +/- 834 MW-1 141 10/26/07 9470 +/- 1010 MW-1 14S 05/10/07 1070 +/- 166 MW-1 14S 10/26/07 1530 +/- 229 MW-1151 05/09/07 < 151 MW-1 151 10/25/07 206 +/- 126 MW-115S 05/09/07 168 +/- 105 MW-1 15S 10/25/07 < 195 MW-1161 05/10/07 4390 +/- 486 MW-1161 10/24/07 4390 +/- 507 MW-1 16S 05/10/07 343 +/- 116 MW-116S 10/24/07 457 +/- 141 MW-1 171 05/11/07 250 +/- 103 MW-1 171 10/24/07 227 +/- 131 MW-1 18S 05/10/07 3180 +/- 361 MW-i 18S 10/23/07 1440 +/- 223 MW-1191 05/09/07 383 +/- 114 MW-1191 10/23/07 1670 +/- 242 MW-i 19S 05/09/07 < 146 MW-119S 10/23/07 < 196 MW-1 201 05/02/07 < 150 MW-1201 10/30/07 < 182 MW-120S 05/02/07 < 150 MW-120S 10/30/07 < 183 MW-121S 05/02/07 < 150 MW-121S 10/31/07 < 179 MW-1221 05/02/07 < 145 MW-1221 10/29/07 < 182 MW-122S 05/02/07 < 150 MW-122S 10/29/07 < 183 MW-1231 05/02/07 < 147 MW-1231 10/29/07 < 179 MW-123S 05/02/07 < 150 MW-123S 10/29/07 < 182 MW-1241 01/05/07 112000 +/- 5840 MW-1 241 05/21/07 105000 +/- 10500 MW-1241 10/26/07 125000 +/- 12500 MW-124S 01/05/07 82700 +/- 4380 MW-124S 05/21/07 137000 +/- 13700 MW-124S 10/26/07 114000 +/- 11400 SAMPLES ARE DISTILLED FOR H-3 ANALYSIS B-3

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED INTHE VICNITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 PERIOD DSP-105 10/23/07 10/23/07 < 70 < 2 <3 < <3 <4 <7 <3 < 42 DSP-106 10/23/07 10/23/07 < 76 <3 <4 < <3 <4 <8 <3 < 52 DSP-107 10/23/07 10/23/07 < 58 <3 <4 < <3 <4 <6 <3 < 49 DSP-108 10/23/07 10/23/07 < 38 <3 <3 < <3 <4 <6 <3 < 52 DSP-117 10/30/07 10/30/07 < 24 <1 <2 < ; 1 <2 <3 < 1 < 30 DSP-121 10/30/07 10/30/07 129 +/- 24 <2 <3 < <2 <3 <5 <2 < 43 DSP-122 10/26/07 10/26/07 < 26 <3 <3 < <3 <3 <5 <2 < 38 DSP-123 10/26/07 10/26/07 165 +/- 52 <3 <4 < <3 <4 < 6 <3 < 44 DSP-124. 10/26/07 10/26/07 < 17 <2 <2 < 1 <2 <3 <2 < 21 DSP-125 10/26/07 10/26/07 < 67 <3 <3 <2 <4 <7 <3 < 41 DSP-126 10/31/07 10/31/07 < 32 <2 <2 < <2 <3 <4 <2 < 36 DSP-147 10/30/07 10/30/07 < 46 <2 <3 < <2 < 3 <5 <2 < 42 DSP-148 10/30/07 10/30/07 < 45 <2 <3 < <2 <3 <5 <2 < 40 DSP-149R 10/30/07 10/30/07 < 14 <2 <2 < <2 <2 <4 <2

32 DSP-150 10/25/07 10/25/07 < 16 <2 <2 < <2 <2 <4 <2 < 24 DSP-1 51 10/25/07 10/25/07 < 44 <2 <3 < <2 <3 <5 <3 < 34 DSP-152 11/01/07 11/01/07 < 18 <2 <3 < <2 <3 <5 <2 < 39 DSP-153 10/31/07 10/31/07 < 19 <2 <3 < < 2 < 3 < 5 < 2 < 42 DSP-154 10/31/07 10/31/07 < 18 <2 <2 < <2 < 3 <4 <2 < 38 DSP-156 10/30/07 10/30/07 58 + 25 <2 <2 < <2 <2 <4 <2 < 35 DSP-157M 10/31/07 10/31/07 < 22 <1 <2 < < 1 <2 <3 < 1 < 29 DSP-157S 10/31/07 10/31/07 < 37 <2 <2 < <2 <3 <5 < 2 < 45 DSP-1581 11/01/07 11/01/07 < 32 <2 <2 < <2 <3 <4 <2 < 38 DSP-158S 11/01/07 11/01/07 < 30 < 2 <2 < <2 <2 <4 <2 < 32 DSP-159M 10/29/07 10/29/07 < 37 <2 <2 < <2 <2 <4 <2 < 41 DSP-159S 10/29/07 10/29/07

40 <2 <3 < < 2 <3 <4 < 2 < 44 MW-DN-1011 10/24/07 10/24/07 < 23 <3 <3 < <3 <3 <5 <3 < 38 MW-DN-101S 10/24/07 10/24/07 < 52 <2 <3 < <2 <3 <5 <3 < 34 MW-DN-1021 Orig 10/25/07 10/25/07 < 53 <2 <3 < <3 <3 <6 <3 < 37 MW-DN-1 021 Rerun 10/25/07 10/25/07 <2 <3 < <2 <4 <6 <2 < 260 MW-DN-102S 10/25/07 10/25/07 <2 <2 < <2 <2 <4 <2 < 27 MW-DN-1031 11/01/07 11/01/07 <4 <4 < <4 <5 <8 < 4 < 49

< 32

< 37

< 71

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICNITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 PERIOD A

MW-DN-103S 11/01/07 - 11/01/07 25 <3 < 4 <6 < 6 <3 MW-DN-104S 10/26/07 - 10/26/07 49 < 3 <2 <5 <6 <2 MW-DN-105S 10/25/07 - 10/25/07 58 <4 <3 <7 <6 <3 MW-DN-106S 10/30/07 - 10/30/07 57 <3 <3 < 6 <6 <3 MW-DN-107S 10/25/07 - 10/25/07 10 < 1 < 1 <2 <2 < 1 MW-DN-1081 10/24/07 - 10/24/07 49 <5 <5

10

10 <4 MW-DN-1091 10/24/07 10/24/07 114 <6 <6

13 < 10 <5 MW-DN-109S 10/24/07 - 10/24/07 46 <6 <5 <9 <9 <4 MW-DN-1 101 10/24/07 - 10/24/07 89 <5 <5 <9 <9 <4 I

Lh MW-DN-1 10S 10/24/07 - 10/24/07 23 <3 <2 <5 <5 <2 MW-DN- II1S 10/26/07 - 10/26/07 65 <4 <3 <7 < 7 <3 MW-DN-1 131 10/25/07 - 10/25/07 34 <4 <4 <8 < 7 <3 MW-DN-1 13S 10/25/07 - 10/25/07 32 <4 <3 <7 < 7 <c 3 MW-DN- 1141 10/26/07 - 10/26/07 78 <4 <3 <8 <8 <3 MW-DN-1 14S 10/26/07 - 10/26/07 26 <3 <3 <6 <5 <3 MW-DN-1151 10/25/07 - 10/25/07 69 <4 <3 < 7 <7 <3 MW-DN-1 15S 10/25/07 - 10/25/07 33 <4 <4 <7 <6 <3 MW-DN-1 161 10/24/07 - 10/24/07 77 <5 <5 <7 <8 <4 MW-DN- 116S 10/24/07 - 10/24/07 58 + 39< <4 <3 <6 <7 <3 MW-DN-1 171 10/24/07 - 10/24/07 58 < 4 <4 <8 <8 < 4 MW-DN-1 18S 10/23/07 - 10/23/07 54 <3 <4 <6 <6 <3 MW-DN-1 191 10/23/07 - 10/23/07 59 < 4 <4 <7 < 7 < 3 MW-DN-I 19S 10/23/07 - 10/23/07 59 <3 <3 <6 <7 <3 MW-DN-1201 10/30/07 - 10/30/07 61 <3 <3 <6 <6 <3 MW-DN-1 20S 10/30/07 - 10/30/07 22 <3 <3 <5 <6 <2 MW-DN-121S 10/31/07 - 10/31/07 69 <4 <3 <7 <6 <3 MW-DN-1221 10/29/07 - 10/29/07 25 <3 <3 <6 <6 <2 MW-DN-1 22S 10/29/07 - 10/29/07 51 <3 <3 <5 <6 <2 MW-DN-1231 10/29/07 - 10/29/07 25 <3 <3 < 6 <6 <3 MW-DN-123S 10/29/07 - 10/29/07 58 <3 <3 <5 <6 <2 MW-DN-1241 10/26/07 - 10/26/07 27 <4 <3 <7 <7 <3 MW-DN-124S 10/26/07 - 10/26/07 35 <4 <3 <8 <7 <3

TABLE B-II.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SW-DN-101 04/30/07 < 146 SW-DN-101 10/22/07 4670 +/- 535 SW-DN-102 04/30/07 < 143 SW-DN-102 10/22/07 1680 +/- 242 SW-DN-103 04/30/07 185 +/- 101 SW-DN-103 10/22/07 1340 +/- 212 SW-DN-104 . 04/30/07 < 147 SW-DN-104 10/22/07 1230 +/- 203 SW-DN-105 04/30/07 243 +/- 104 SW-DN-105 10/22/07 1710 +/- 246 SW-DN-106 04/30/07 < 149 SW-DN-106 10/22/07 1350 +/- 213 B-6

TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Be-7 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD SW-DN-101 10/22/07 < 21 < 40 <2 <2 <6 <2 <4 <3 <4 < 20 <2 <2 < 28 < 10 SW-DN-102 10/22/07 < 21 134 +/-24 <2 <2 <5 <2 <3 <2 <4 < 20 <2 <2 < 27 <7 SW-DN-103 10/22/07 < 21 < 17 <2 <2 <5 <2 <4 <2 <4 < 22 <2 <2 < 29 < 10 SW-DN-104 10/22/07 < 27 < 44 <2 <3 <6 <3 <6 <3 <5 < 27 <2 < 3 < 37 < 11 SW-DN-105 10/22/07 < 10 < 27 <1 <1 <2 <1 <2 <1 <2 <9 <,1 <1 < 13 <4 SW-DN-106 10/22/07 < 24 < 20 <2 <3 <6 <3 <6 <3 <5 < 24 <2 <2 < 33 < 12 t3

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