SVPLTR 18-0013, Annual Radiological Environmental Operating Report for 2017

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Annual Radiological Environmental Operating Report for 2017
ML18137A209
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 05/10/2018
From:
Exelon Generation Co, Teledyne Brown Engineering Environmental Services
To:
Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML18137A198 List:
References
SVPLTR# 18-0013
Download: ML18137A209 (120)


Text

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 2017 Prepared By Teledyne Brown Engineering Environmental Services Dresden Nuclear Power Station Morris, IL 60450 May 2018

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Table Of Contents I. Summary and Conclusions ................................................................................................ 1 II. Introduction ........................................................................................................................ 5 A Objectives of the REMP ........................................................................................ 5 B. Implementation of the Objectives .......................................................................... 5 Ill. Program Description ......................................................................................................... 6 A. Sample Collection .................................................................................................. 6 B. Sample Analysis .................................................................................................... 7 C. Data Interpretation ................................................................................................. 8 D. Program Exceptions .............................................................................................. 9 E. Program Changes ............................................................................................... 11 IV. Results and Discussion ................................................................................................. 11 A. Aquatic Environment ........................................................................................... 11

1. Surface Water ........................................................................................... 11
2. Ground Water ........................................................................................... 12
3. Fish ........................................................................................................... 12
4. Sediment ................................................................................................... 12 B. Atmospheric Environment ................................................................................... 13
1. Airborne .................................................................................................... 13
a. Air Particulates .............................................................................. 13
b. Airborne Iodine .............................................................................. 14
2. Terrestrial .................................................................................................. 14
a. Milk ................................................................................................ 14
b. Food Products ............................................................................... 14 C. Ambient Gamma Radiation ................................................................................. 15 D. Land Use Survey ................................................................................................. 15 E. Errata Data .......................................................................................................... 16 F. Summary of Results - Inter-laboratory Comparison Program ............................ 16

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Appendices Appendix A Radiological Environmental Monitoring Report Summary (Meets requirements of NUREG 1302)

Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Dresden Nuclear Power Station, 2017 Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical. Methods Tables Table B-1 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2017 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2017 Figures Figure B-1 Dresden Station Inner Ring OSLO Locations, Fish, Water, and Sediment Locations, 2017 Figure B-2 Dresden Station Fixed Air Sampling and OSLO Sites, Outer Ring OSLO Locations and Milk Location, 2017 Appendix C Data Tables and Figures Tables Table C-1.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-1.2 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-11.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-11.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 ii

Table C-111.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-Vl.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-Vll.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-Vll.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-Vlll.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table C-IX.1 Quarterly OSLO Results for Dresden Nuclear Power Station, 2017 Table C-IX.2 Mean Quarterly OSLO Results for the Inner Ring, Outer Ring, Other and Control Locations for Dresden Nuclear Power Station, 2017 Table C-IX.3 Summary of the Ambient Dosimetry Program for Dresden Nuclear Power Station, 2017 Figures Figure C-1 Surface Water - Gross Beta - Station D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2017 Figure C-2 Surface Water - Gross Beta - Stations D-54 (C) and D-57 (C)

Collected in the Vicinity of DNPS, 2003 - 2017 Figure C-3 Surface Water - Gross Beta - Stations D-21 and D-51 Collected in the Vicinity of DNPS, 2000 - 2017 Figure C-4 Surface Water - Tritium - Station D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2017 Figure C-5 Surface Water - Tritium - Station D-54 (C) and D-57 (C) Collected in the Vicinity of DNPS, 2003 - 2017 Figure C-6 Surface Water - Tritium - Stations D-21 and D-51 Collected in the Vicinity of DNPS, 2000- 2017 iii

Figure C-7 Ground Water - Tritium - Stations D-23 and D-35 Collected in the Vicinity of DNPS, 2000 - 2017 Figure C-8 Air Particulate - Gross Beta - Stations D-01 and D-02 Collected in the Vicinity of DNPS, 2000 - 2017 Figure C-9 Air Particulate - Gross Beta - Stations D-03 and D-04 Collected in the Vicinity of DNPS, 2000 - 2017 Figure C-10 Air Particulate - Gross Beta - Stations D-07 and D-12 (C) Collected in the Vicinity of DNPS, 2000 - 2017 Figure C-11 Air Particulate - Gross Beta - Stations D-45 and D-53 Collected in the Vicinity of DNPS, 2000 - 2017 Figure C-12 Air Particulate - Gross Beta - Stations D-08 and D-10 Collected in the Vicinity of DNPS, 2005 - 2017 Figure C-13 Air Particulate - Gross Beta - Stations D-13 and D-14 Collected in the Vicinity of DNPS, 2005 - 2017 Figure C-14 Air Particulate - Gross Beta - Stations D-55 and D-56 Collected in the Vicinity of DNPS, 2006 - 2017 Figure C-15 Air Particulate - Gross Beta - Station D-58 Collected in the Vicinity of DNPS, 2011 - 2017 Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2017 Table D-2 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2017 Table D-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2017 Appendix E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv

I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Dresden Nuclear Power Station (DNPS) of Exelon covers the period 1 January 2017 through 31 December 2017. During that time period 2,019 analyses were performed on 1,882 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.

In 2017, the Dresden Nuclear Power Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 4.89E+01 curies of fission and activation gasses, 2.90E+01 curies of Carbon-14 (C-14) and approximately 1.23E+01 curies of tritium. The dose from both liquid and gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public. The results of those calculations and their comparison to the allowable limits are excerpted from the Dresden Generating Station 2017 Annual Radioactive Effluent Release Report (Radiological Impact on Man, starting at page 79):

1. Doses to a Member of the Public due to Liquid Releases in 2017 (from 01/01/2017 to 12/31/2017):

UNITS 1, 2, 3 Total Body: 6.42E-07 mrem Organ: 6.42E-07 mrem UNIT 1 Total Body: N/A Organ: N/A UNIT2 Total Body: 3.21 E-07 mrem Organ: 3.21 E-07 mrem UNIT3 Total Body: 3.21 E-07 mrem Organ: 3.21 E-07 mrem The above annual liquid dose values are reported per Dresden-site (UNITS 1,2,3) as well as per each individual reactor unit (UNIT 1, UNIT 2, UNIT 3). Regulatory annual liquid dose limits are listed on page 1 section 1.d.3) and section 1.d.4), of the 2017 Annual Radioactive Effluent Release Report as well as in Dresden ODCM. The above annual liquid dose values are well below any regulatory limits.

2~ Doses to a Member of the Public due to Gaseous Releases in 2017 (from 01/01/2017 to 12/31/2017):

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UNITS 1, 2, 3 Gamma air (fission and activation gases): 1.58E-03 mrad Beta air (fission and activation gases): 8.32E-05 mrad Total Body (noble gases): 1.05E-03 mrem Skin (noble gases): 1.79E-03 mrem Organ - bone (radioiodines/tritium/particulates): 8.89E-02 mrem UNIT 1 Gamma air (fission and activation gases): N/A Beta air (fission and activation gases): N/A Total Body (noble gases): NIA Skin (noble gases): N/A Organ - bone (radioiodines/tritium/particulates): 2.71 E-03 mrem UNIT 2 Gamma air (fission and activation gases): 6.46E-04 mrad Beta air (fission and activation gases): 3.46E-05 mrad Total Body (noble gases): 4.29E-04 mrem Skin (noble gases): 7.35E-04 mrem Organ - bone (radioiodines/tritium/particulates): 4.24E-02 mrem UNIT3 Gamma air (fission and activation gases): 9.29E-04 mrad Beta air (fission and activation gases): 4.86E-05 mrad Total Body (noble gases): 6.17E-04 mrem Skin (noble gases): 1.05E-03 mrem Organ - bone (radioiodines/tritium/particulates): 4.53E-02 mrem The above annual gaseous dose values are reported per Dresden-site (UNITS 1,2,3) as well as per each individual reactor unit (UNIT 1, UNIT 2, UNIT 3). Regulatory annual gaseous dose limits are listed on page 1 section 1.a. and section 1.b.c., of the 2017 Annual Radioactive Effluent Release Report as well as in Dresden ODCM. The above annual gaseous dose values are well below any regulatory limits.

3. Doses to a Member of the Public due to Direct Radiation in 2017 (from 01/01/2017 to 12/31/2017):

UNITS 1, 2, 3 Total Body (skyshine): 8.78E+OO mrem UNIT 1 Total Body (skyshine): N/A UNIT2 Total Body (skyshine): 4.21 E+OO mrem 2

UNIT3 Total Body (skyshine): 4.57E+OO mrem The above annual direct dose values are reported per Dresden-site (UNITS 1,2,3) as well as per each individual reactor unit (UNIT 1, UNIT 2, UNIT 3). These numbers are calculated per ODCM methodologies, and are used to demonstrate compliance with 40CFR190 total dose limit requirements listed on page 1 section 1.e, of the 2017 Annual Radioactive Effluent Release Report as well as in Dresden ODCM.

4. Total body doses to the population and average doses to individuals in the population from all receiving-water-related-pathways are not applicable to Dresden Station. No downstream drinking water pathway exist within the specified distance of 10 kilometers (6.2 miles).
5. Total body doses to the population and average doses to individuals in the population from gaseous effluents to a distance of 50 miles from the site are not applicable to Dresden Station.
6. Doses from liquid and gaseous effluent to members of the public due to their activities inside the site boundary for the report period are not applicable to Dresden Station. Any member of the public who is onsite for a significant period of time is issued an Optical Stimulated Luminescent Dosimeter (OSLO) to monitor direct radiation exposure.
7. Liquid and Gaseous Effluent Radiation Monitors and Instrumentation Unavailability for the Period Beyond the Requirements of the ODCM, Including Sampling Deviation: For the report period, there were no radiation monitors that exceeded the ODCM-allowed inoperability time.
8. 40 CFR 190 / 10 CFR 72 Compliance:

The General Electric Hitachi Nuclear Energy Morris Operation (GEH Morris Operation) facility is physically located near Dresden Station, hence it is considered in the evaluation of the uranium fuel cycle on members of the public in the general environment.

Dresden decommissioning activities (Unit 1) and operations (Units 2 and 3) resulted in a maximum 8.89E-02 mrem organ dose and

8. 78E+OO mrem total body dose. The Radiological Environmental Monitoring Program (REMP) direct radiation monitoring at or near the site boundary demonstrates that total body dose calculations to account for skyshine as found in the ODCM are conservative.

No effluents were released from the Dresden Independent Spent Fuel Storage Installations (ISFSls) during 2017. REMP direct radiation monitoring at or near the site boundary demonstrates that 3

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the ISFSls do not result in measurable dose to the public.

According to the 2017 GEH Morris Operation 10 CFR 72.44(d)(3) report, dated 2/20/2018, for the 2017 calendar year, the maximum dose at their site boundary from direct radiation exposure was 3.83E-01 mrem. The maximum organ dose from site activities was 3.1 OE-07 mrem for 2017.

Maximum combined total body dose from Dresden Station and GEH Morris Operation activities was 9.16E+OO mrem during 2017, which was 36.64 % of the 40 CFR 190 limit of 25 mrem.

Maximum combined organ dose from Dresden and GEH Morris Operation activities was 8.89E-02 mrem during 2017. This was 0.36 % of the 40 CFR 190 limit of 25 mrem to any organ. The combined thyroid dose was 7.07E-02 mrem. This was 0.09 % of the 40 CFR 190 limit of 75 mrem.

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

Fish (commercially and recreationally important species), and sediment samples were analyzed for concentrations of gamma-emitting nuclides. No fission or activation products were detected in fish. Cesium-137 was detected in both sediment samples in 2017 at levels slightly higher than the level of detection.

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 lodine-131 (1-131) analyses were performed on weekly air samples. All results were less than the minimum detectable activity for 1-131.

Cow milk samples were analyzed for concentrations of 1-131 and gamma-emitting nuclides. All 1-131 results were less than the minimum detectable activity. No fission or activation products were detected. 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 Optically Stimulated Luminescent Dosimetry (OSLO). The relative comparison to control locations remains valid.

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

This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Landauer on samples collected during the period 1 January 2017 through 31 December 2017.

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 40CFR 190 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; 5

Ill. Program Description A. Sample Collection Samples for the DNPS REMP were collected for Exelon Nuclear by Environmental Incorporated Midwest Laboratory (EIML). This section describes the general collection methods used by EIML to obtain environmental samples for the DNPS REMP in 2017. Sample locations and descriptions can be found in Appendix B, Table B-1 and Figures B-1 and B-2. The collection methods used by EIML are listed in Table B-2.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water (SW), ground water (GW), fish (Fl) and sediment (SS). Samples were collected from three surface water locations (D-21, D-52 and D-57) and composited for analysis. Control locations were D-52 and D-57. Samples were collected quarterly or more frequently from two well water locations (D-23 and D-35). All samples were collected in new unused plastic bottles, which were rinsed with source water prior to collection. Fish samples comprising the flesh of freshwater drum, largemouth bass, and common carp were collected semiannually at two locations, D-28 and D-46 (Control). Sediment samples composed of recently deposited substrate were collected at one location semiannually, D-27.

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

Airborne iodine and particulate samples were collected at fourteen locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55, D-56 and D-58). The control location was D-12. Airborne iodine and particulate samples were obtained at each location using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The air filters and air iodine samples were replaced weekly and sent to the laboratory for analysis.

Terrestrial Environment Milk (M) samples are typically collected biweekly at one control location (D-25) from May through October and monthly from November through April. Other than D-25, there are no additional milking animals within 10 km (6.2 miles) of the site. All milk samples from D-25 were collected in 6

new unused two gallon plastic bottles from the bulk tank, preserved with sodium bisulfite and shipped promptly to the laboratory. Food products (FL) were collected annually in August 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 Each location consisted of two OSLO sets. The OSLO locations were placed on and around the DNPS site as follows:

An inner ring consisting of 17 locations (D-58, D-101, D-102, D-103, D-104, D-105, D-106, D-107, D-108, D-109, D-110, D-111, D-112a, D-113, D-114, D-115 and D-116) at or near the site boundary.

An outer ring consisting of 16 locations (D-201, D-202, D-203, D-204, D-205, D-206, D-207, D-208, D-209, D-210, D-211, D-212, D-213, D-214, D-215 and D-216) approximately 5 to 10 km (3.1 to 6.2 miles) from the site.

Other locations consisting of OSLO sets at the 13 air sampler locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-14, D-45, D-53, D-55, 0-56 and D-58).

The balance of one location (D-12) represents the control area OSLO set.

The OSLDs were exchanged quarterly and sent to Landauer for analysis.

B. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the DNPS REMP in 2017. The analytical procedures used by the laboratory are listed in Appendix B Table B-2.

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

1. Concentrations of beta emitters in surface water and air particulates.
2. Concentrations of gamma emitters in ground and surface water, air particulates, milk, fish, sediment and vegetation.
3. Concentrations of tritium in ground and surface water.

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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 groundwater, surface water, and vegetation twelve nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140 and La-140 were reported.

For fish, sediment, air particulate and milk eleven 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.

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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 2017 the DNPS REMP had a sample recovery rate greater than 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 SW D-57 02/24/17 Compositor down; grab sample taken for 02/24/17 Ml D-25 04/06/17 Sample lost in transit, recollected 04/20/17 AP/Al D-08 05/26/17 No apparent reason for low timer reading of 163.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> AP/Al D-10 06/23/17 Low reading of 164.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> possibly due to power outage from storms AP/Al D-01 07/07/17 Collector found power out at sampler; POC notified. Power restored on 07/07/17 at 16:24.

Estimated flow rate= 60 CFH.

GW D-23 07/14/17 No sample, homeowners absent. Collector will obtain next week. NOTE: Sample obtained 07/21/17.

AP/Al D-14 09/08/17 Collector found power out at sampler due to broken line; POC notified. Power restored by 14:00 hours on 09/08/17.

AP/Al D-53 09/29/17 Low reading of 141.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> due to work on line; station notified. Flow of 60 CFH based on 4 previous weeks.

SW D-57 09/29/17 Compositor pipe broken by heavy equipment work in area; station notified.

AP/Al D-53 10/06/17 Low reading of 149.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> due to power restoration AP/Al D-45 11/17/17 No apparent reason for low timer reading of 164.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AP/Al D-45 12/29/17 No apparent reason for low timer reading of 116.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />; timer working properly.

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Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Tt~e Code Date SW D-52 01/06/17 No sample; water frozen SW D-52 01/13/17 No sample; water frozen SW D-52 02/03/17 No sample; water frozen OSLO D-111-1 03/31/17 OSLO found missing during quarterly exchange, collector placed new 2nd quarter OSLO AP/Als ALL 04/07/17 Samples lost in transit OSLO D-205-2, 207-2 09/29/17 OSLDs missing during quarterly exchange; collector placed new 4th quarter OSLDs OSLO D-53-1 10/27/17 OSLO found missing during weekly visual check, collector placed Spare 1 EX000127215 GW D-23 11/10/17 No sample, house vacant, outside faucet inoperable. Station notified by collector.

GW D-23 12/08/17 No sample available SW D-57 12/15/17 Compositor down, collector unable to obtain grab sample, river frozen SW D-52 12/15/17 No sample; water frozen SW 0-52 12/29/17 No sample; water frozen SW 0-57 12/29/17 Compositor down, collector unable to obtain grab sample, river frozen OSLO 0-214-2 12/29/17 OSLO found missing during quarterly exchange; collector placed a new 1st quarter 2018 OSLO.

Each program exception was reviewed to understand the causes of the program exception. No sampling or maintenance errors were identified during the reporting period. 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.

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E. Program Changes As a result of previous issues with milk sampling (no dairy available to provide samples), Dresden Station instituted a plan for backup vegetation sampling, when needed. Because normal vegetation samples were available in accordance with the ODCM, backup vegetation samples were not needed in 2017. Inclusion of this plan as part of the ODCM is pending with the next ODCM change.

IV. Results and Discussion A. Aquatic Environment

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

Gross Beta Monthly composites from all locations were analyzed for concentrations of gross beta (Table C-1.1, Appendix C). Gross Beta was detected in 36 of 36 samples. The values ranged from 2. 7 to 10.1 pCi/1. Concentrations detected were consistent with those detected in previous years.

(Figures C-1, C-2 and C-3, Appendix C)

Tritium Quarterly composites from all locations were analyzed for tritium activity (Table C-1.2, Appendix C). One sample at indicator station D-21 was positive for tritium at a concentration of 265 pCi/L. Three samples at control station D-57 were positive for tritium. The values ranged from 448 to 1710 pCi/L. No samples from station D-52 were positive fortritium. 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.

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

Tritium Both locations were analyzed for tritium activity (Table C-11.1, Appendix C). Tritium was detected in 10 of 14 samples. The concentrations ranged from 303 to 504 pCi/1. 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 largemouth bass, common carp, and freshwater drum were collected at two locations (D-28 and D-46) semiannually. Location D-28 could be affected by Dresden's effluent releases. The following analysis was performed:

Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma-emitting nuclides (Table C-111.1, Appendix C).

Only naturally-occurring nuclides (not shown on the tables) were found at both locations. 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-12

emitting nuclides (Table C-IV.1, Appendix C). Cesium-137 (Cs-137) was found in both samples. The concentrations ranged from 134 pCi/kg dry to 144 pCi/kg dry.

B. Atmospheric Environment

1. Airborne
a. Air Particulates Continuous air particulate samples were collected from fourteen locations on a weekly basis. The fourteen locations were separated into four groups: On-site samplers (D-01, D-02 and D-03), Near-field samplers within 3.1 miles of the site (D-04, D-07, D-45, D-53, D-56 and D-58), Far-field samplers between 5 and 10 km (3.1 and 6.2 miles) from the site (D-08, D-10, D-14 and D-55) and the Control sampler between 10 and 30 km (6.2 and 18.6 miles) from the site (D-12). The following analyses were performed:

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

Detectable gross beta activity was observed at all locations.

Comparison of results among the four groups aid in determining the effects, if any, resulting from the operation of DNPS. The results from the On-Site locations ranged from 6 to 29E-3 pCi/m 3 with a mean of 16E-3 pCi/m 3 . The results from the Near-Field locations ranged from 5 to 29E-3 pCi/m 3 with a mean of 16E-3 pCi/m 3

  • The results from the Far-Field locations ran~ed from 5 to 29E-3 pCi/m 3 with a mean of 16E-3 pCi/m . The results from the Control location ranged from 9 to 26E-3 pCi/m 3 with a mean of 16E-3 pCi/m 3 .

Comparison of the 2017 air particulate data with previous year's data indicate no effects from the operation of DNPS.

In addition a comparison of the weekly mean values for 2017 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). Only 13

naturally-occurring nuclides (not shown on the tables) were found in these composite samples. No anthropogenic nuclides were detected and all required LLDs were met.

These samples were consistent with historical quarterly results. All other nuclides were less than the MDC.

b. Airborne Iodine Continuous air samples were collected from fourteen locations (D-01, D-02, D-03, D-04, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55, D-56 and D-58) and analyzed weekly for 1-131 (Table C-Vl.1, Appendix C). All results were less than the MDC for 1-131.
2. Terrestrial
a. Milk Milk (M) samples are typically collected biweekly at one control location (D-25) from May through October and monthly from November through April. Other than D-25, there are no additional milking animals within 10 kilometers (6.2 miles) of the site. The following analyses were performed:

lodine-131 Milk samples from location D-25 were analyzed for concentrations of 1-131. (Table C-Vll.1, Appendix C)

No 1-131 was detected and the LLD was met.

Gamma Spectrometry Milk samples from location D-25 were analyzed for concentrations of gamma-emitting nuclides.

(Table C-Vll.2, Appendix C) Only naturally-occurring nuclides (not shown on the tables) were found in all samples. No other gamma-emitting 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) 14

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 pertormed:

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

C. Ambient Gamma Radiation Forty-six OSLO locations were established around the site. Results of OSLO measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C.

Most OSLO measurements were below 30 mrem/quarter, with a range of 21.2 to 36.8 mrem/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 and D-12-02) were comparable.

D. Land Use Survey A Land Use Survey conducted on August 22, 2017 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 % degree sectors within 10 km (6.2 miles) around the site. The survey indicated changes in Sector B (NNE) which no longer has a livestock location, Sector P (WNW) with the nearest residence located at 3.2 miles instead of 3.7 miles, and at Sector Q (NW) with the nearest residence located at 2.2 miles instead of 2.6 miles. There were no changes required to the DNPS REMP as a result of this survey. The results of this survey are summarized below:

15

Distance in Miles from the DNPS Reactor Buildings Sector Residence Livestock Milk Farm Miles Miles Miles A N 1.5 1.4 B NNE 0.8 C NE 0.8 5.8 D ENE 0.7 1.7 E E 1.1 F ESE 1.0 G SE 0.6 H SSE 0.5 J s 0.5 16.0 K SSW 3.3 L SW 3.6 11.4 M WSW 5.8 N w 3.5 0.5 p WNW 3.2 0.5 Q NW 2.2 0.5 R NNW 0.8 1.0 E. Errata Data Corrections for the 2016 AREOR appear in Appendix E.

F. Summary of Results - Inter-Laboratory Comparison Program The TBE Laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation, and water matrices for various analytes. The PE samples supplied by Analytics Inc.,

Environmental Resource Associates (ERA) and Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

A. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE evaluates the reported ratios based on internal QC requirements based on the DOE MAPEP criteria.

B. 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, National Environmental 16

Laboratory Accreditation Conference (NELAC), state-specific Performance Testing (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.

C. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values. MAPEP defines three levels of performance:

  • Acceptable (flag = "A") - result within +/- 20% of the reference value
  • Acceptable with Warning (flag = "W') - result falls in the+/- 20%

to +/- 30% of the reference value

  • Not Acceptable (flag = "N") - bias is greater than 30% of the reference value Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities.

For the TBE laboratory, 168 out of 173 analyses performed met the specified acceptance criteria. Five analyses did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program.

1. The ERA April 2017 two nuclides in water were evaluated as Not Acceptable. (NCR 17-09)
a. The Zn-65 result of 39.3 pCi/L, exceeded the lower acceptance limit of 47.2. The known value was unusually low for this study.

The sample was run in duplicate on two different detectors. The results of each were 39.3 +/- 18.2 pCi/L (46% error and lower efficiency) and 59.3 +/- 8.23 pCi/L (13.9% error and higher efficiency). The result from the 2nd detector would have been well within the acceptable range (47.2 - 65.9) and 110.2% of the known value of 53.8 pCi/L.

b. The Sr-89 result of 40.7 pCi/L exceeded the lower acceptance limit of 53.8. All associated QC and recoveries were reviewed and no apparent cause could be determined for the failure. The 17

prior three cross-check results were from 99 - 115% of the known values and the one that followed this sample (November, 2017) was 114% of the known value.

2. The DOE MAPEP August 2017 air particulate U-238 result of 0.115

+/- 0.025 Sq/sample was higher than the known value of 0.087 +/-

0.002 with a ratio of 1.32, therefore the upper ratio of 1.30 (acceptable with warning) was exceeded. TBE's result with error easily overlaps with the acceptable range. MAPEP does not evaluate results with any associated error. Also, the spike level for this sample was very low (2.35 pCi) compared to TBE's normal LCS of 6 pCi. TBE considers this result as passing. (NCR 17-15)

3. The Analytics September 2017 soil Cr-51 result was evaluated as Not Acceptable (Ratio of TBE to known result at 0.65). The reported value was 0.230 +/- 0.144 pCi/g and the known value was 0.355 +/- 0.00592 pCi/g. The sample was counted overnight for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />, however the Cr-51 was spiked at a very low level and had a counting error of 65%. Cr-51 has a 27-day half-life, making low-level quantification even more difficult. The error does not appear to have been taken into consideration for this result. If it had been evaluated with the error, the highest result would have been 105%

of the reference value, which is acceptable. Also, the known value is significantly lower than TBE's typical MDC for this nuclide in a soil matrix and would typically not be reported to clients (unless specified). The results of all of the previous cross-checks have been in the acceptable (80 -120%) range. TBE will evaluate further upon completion of the next ICP sample. (NCR 17-16)

4. The ERA November 2017 water Sr-90 sample was evaluated as Not Acceptable. TBE's result of 27.1 pCi/L exceeded the lower acceptance range (30.8 - 48.0 pCi/L). After reviewing the associated QC data for this sample, it was determined that although the spike recovery for Sr-90 was within TBE laboratory guidelines (70% -130%), both the spike result and the ERA result were biased low. The original cross-check sample was completely consumed and TBE was unable to reanalyze before submitting the result. TBE has modified the preparation process to avoid this situation for future cross-check samples. TBE also has enhanced LIMS programming to force a LCSD when a workgroup includes cross-check samples (as opposed to running a DUP). (NCR 17-19)

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

18

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2017 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010, 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: 2017 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION LOCATION WITH HIGHEST ANNUAL MEAN (M) NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M) MEAN(M) MEAN(M) STATION# NONROUTINE (UN/TOF ANALYSIS ANALYSIS OF DETECTION {F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS SURFACE WATER GR-8 36 4 6 5.9 7.4 0-52 CONTROL 0 (PCI/LITER) (12112) (24/24) (12112) DESPLAINES RIVER- UPSTREAM 3.6-9.1 2.7 - 10.1 3.4 - 10.1 1.1 MILES ESE OF SITE H-3 12 2000 265 902 902 D-57 CONTROL 0 (1/4) {3/8) (3/4) KANKAKEE RIVER AT WILL ROAD{CONTROL) 448- 1710 448- 1710 2.0 MILES SE OF SITE GAMMA 36 MN-54 15 <LLD <LLD 0 C0-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 C0-60 15 <LLD <LLD 0 LN-65 30 <LLD <LLD 0

)>

I NB-95 15 <LLD <LLD 0

~

ZR-95 30 <LLD <LLD 0

/-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 GROUND WATER H-3 14 2000 415 NA 415 D-23 INDICATOR 0 (PCliLITER) (10/14) {10/10) THORSEN WELL 303-504 303- 504 0.7 MILES S OF SITE GAMMA 14 MN-54 15 <LLD NA 0 C0-58 15 <LLD NA 0 FE-59 30 <LLD NA 0 C0-60 15 <LLD NA 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA 0 ZR-95 30 <LLD NA 0

/-131 15 <LLD NA 0 CS-134 15 <LLD NA 0 CS-137 18 <LLD NA 0 BA-140 60 <LLD NA 0 LA-140 15 <LLD NA 0 (M) The Mean Values are calculated using the positive values. (FJ Fraction of detectable measurement are indicated in parentheses

i TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2017 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010, 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: 2017 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION LOCATION WITH HIGHEST ANNUAL MEAN (M) NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN(M) STATION# NONROUTINE (UNITOF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS FISH GAMMA 8 (PCJIKG WET) MN-54 130 <LLD NA 0 C0-58 130 <LLD NA 0 FE-59 260 <LLD NA 0 C0-60 130 <LLD NA 0 ZN-65 260 <LLD NA 0 NB-95 NA <LLD NA 0 ZR-95 NA <LLD NA 0 CS-134 130 <LLD NA 0 CS-137 150 <LLD NA 0 BA-140 NA <LLD NA 0

)> LA-140 NA <LLD NA 0 I

I\)

SEDIMENT GAMMA 2 (PCIIKG DRY) MN-54 NA <LLD NA 0 C0-58 NA <LLD NA 0 FE-59 NA <LLD NA 0 C0-60 NA <LLD NA 0 ZN-65 NA <LLD NA 0 NB-95 NA <LLD NA 0 ZR-95 NA <LLD NA 0 CS-134 150 <LLD NA 0 CS-137 180 139 NA 139 D-27 INDICATOR 0 (2/2) (2/2) DRESDEN LOCK AND DAM - DOWNSTREAM 134 - 144 134-144 0.8 MILES NW OF SITE BA-140 NA <LLD NA 0 LA-140 NA <LLD NA 0 AIR PARTICULATE GR-B 714 10 16.2 16.1 16.9 D-53 INDICATOR 0 (PCJITOTAL) (663/663) (51/51) (51/51) GRUDY COUNTY ROAD 5.2-29 9.3-26 8.8-28.9 2.1 MILES SSE OF SITE (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2017 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010, 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: 2017 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION LOCATION WITH HIGHEST ANNUAL MEAN (M) NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M) MEAN (M) MEAN(M) STATION# NONROUTINE (UN/TOF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS AIR PARTICULATE GAMMA 56 (PCIITOTAL) MN-54 NA <LLD <LLD 0 C0-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 C0-60 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 BA-140 NA <LLD <LLD 0

)> LA-140 NA <LLD <LLD 0 I

w AIR IODINE GAMMA 714 (PCI/TOTAL) /-131 70 <LLD <LLD 0 MILK 1-131 (LOW LVL) 19 NA <LLD 0 (PCI/LITER)

GAMMA 19 MN-54 NA NA <LLD 0 C0-58 NA NA <LLD 0 FE-59 NA NA <LLD 0 C0-60 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 BA-140 60 NA <LLD 0 LA-140 15 NA <LLD 0 (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses L

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2017 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010, 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: 2017 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION LOCATION WITH HIGHEST ANNUAL MEAN (M) NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(fv~ MEAN (M) MEAN(M) STATION# NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS VEGETATION GAMMA 12 (PCIIKG WET) MN-54 NA <LLD <LLD 0 C0-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 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 l>I

.i:,.. LA-140 NA <LLD <LLD* 0 DIRECT RADIATION OSLD-QUARTERL Y 364 NA 26.9 24.5 32.7 D-110-4 INDICATOR 0 (MILLI-ROENTGENIQTR.) (3561356) (8/8) (4/4) 21.2- 36.8 21.8-28.6 29.4- 36.8 0.9 MILES SSW (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses

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

Intentionally left blank TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2017 Location Location Description Distance & Direction From Site A. Surface Water D-21 Illinois River at EJ&E Bridge (indicator) 1.4 miles WNW D-52 DesPlaines River at Will Road, Upstream (control) 1.1 miles ESE D-57 Kankakee River at Will Road (control) 2.0 miles SE B. Ground/Well Water D-23 Thorsen Well, Dresden Road (indicator) 0.7 miles s D-35 Dresden Lock and Dam (indicator) 0.8 miles NW C. Milk - bi-weekly / monthly D-25 Biros Farm (control) 11.4 miles SW D. Air Particulates / Air Iodine D-01 Onsite Station 1 (indicator) 0.8 miles NW D-02 Onsite Station 2 (indicator) 0.3 miles NNE D-03 Onsite Station 3 (indicator) 0.4 miles S D-04 Collins Road, on Station property(indicator) 0.8 miles W D-07 Clay Products, Dresden Road (indicator) 2.6 miles S D-08 Jugtown Road, Prairie Parks (indicator) 3.8 miles SW D-10 Goose Lake Road, Goose Lake Village (indicator) 3.5 miles SSW D-12 Quarry Road, Lisbon (control) 10.5 miles NW D-14 Center Street, Channahon (indicator) 3.7 miles NE D-45 McKinley Woods Road, Channahon (indicator) 1.7 miles ENE D-53 Will Road, Hollyhock (indicator) 2.1 miles SSE D-55 Ridge Road, Minooka (indicator) 4.3 miles N D-56 Will Road, Wildfeather (indicator) 1.7 miles SE D-58 Will Road, Marina (indicator) 1.1 miles ESE E. Fish D-28 Dresden Pool of Illinois River, Downstream (indicator) 0.9 miles NNW D-46 DesPlaines River, Upstream (control) 1.2 miles ESE F. Sediment D-27 Illinois River at Dresden Lock and Dam, Downstream 0.8miles NW (indicator)

G. Vegetation Quadrant 1 26726 & 26819 McKinley Woods Road 1.7 miles ENE Quadrant 2 3985 N. Will Road 2.1 miles SSE Quadrant 3 3250 Perch Court 2.5 miles SSW Quadrant 4 4740 Cemetery Road 2.1 miles W Control 2035 Old Mazon Road 11 miles SW B-1

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2017 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - OSLO Inner Ring D-58-1 and -2 1.1 miles ESE 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 0.9milesW D-114-1 and -2 0.9 miles WNW D-115-1 and -2 0.8 miles NW D-116-1 and-2 1.0 miles NNW Outer Ring D-201-1 and -2 4.8 miles N D-202-1 and -2 5.1 miles NNE D-203-1 and -2 4.7 miles NE D-204-1 and -2 5.0 miles ENE D-205-1 and -2 4.0 miles E D-206-1 and -2 3.5 miles ESE D-207-1 and -2 4.2 miles SE D-208-1 and -2 4.9 miles SSE D-209-1 and -2 4.1 miles S D-210-1 and -2 4.9 miles SSW D-211-1 and -2 4.8 miles SW D-212-3 and -4 6.0 miles WSW D-213-1 and -2 4.5 miles W D-214-1 and -2 5.0 miles WNW D-215-1 and -2 4.8 miles NW D-216-1 and -2 4.9 miles NNW Other Locations 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, on Station property 0.8miles W D-07-1 and -2 Clay Products, Dresden Road 2.6 miles S D-08-1 and -2 Jugtown Road, Prairie Parks 3.8miles SW D-10-1 and -2 Goose Lake Road, Goose Lake Village 3.5 miles SSW D-14-1 and -2 Center Street, Channahon 3.7 miles NE D-45-1 and -2 McKinley Woods Road, Channahon 1.7 miles ENE D-53-1 and -2 Will Road, Hollyhock 2.1 miles SSE D-55-1 and -2 Ridge Road, Minooka 4.3 miles N D-56-1 and -2 Will Road, Wildfeather 1.7 miles SE D-58-1 and -2 Will Road, Marina 1.1 miles ESE D-12-1 and -2 Lisbon 10.5 miles NW B-2

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2017 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium EIML-SPM-1, Environmental Incorporated Midwest Laboratory Sampling Procedures Monthly composite TBE, TBE-2007 Gamma emitting Manual sample or monthly radioisotope analysis Surface Water Gamma Spectroscopy 2 gallon composite from weekly TBE, TBE-2023 Compositing of samples grab samples.

EIML-COMP-01 procedure for compositing water and milk samples EIML-SPM-1, Environmental Incorporated Midwest Laboratory Sampling Procedures Monthly composite TBE, TBE-2008 Gross Alpha and/or Manual sample or monthly gross beta activity in various matrices Surface Water Gross Beta 2 gallon composite from weekly TBE, TBE-2023 Compositing of samples grab samples.

EIML-COMP-01 procedure for compositing water and milk samples EIML-SPM-1, Environmental Incorporated Midwest Laboratory Sampling Procedures TBE, TBE-2011 Tritium analysis in Quarterly composite of Manual CJ drinking water by liquid scintillation I Surface Water Tritium monthly composite 500 ml

(,I) TBE, TBE-2023 Compositing of samples samples.

EIML-COMP-01 procedure for compositing water and milk samples EIML-SPM-1, Environmental Incorporated TBE, TBE-2007 Gamma emitting Ground Water Gamma Spectroscopy Quarterly grab samples. Midwest Laboratory Sampling Procedures 2 gallon radioisotope analysis Manual EIML-SPM-1, Environmental Incorporated TBE, TBE-2011 Tritium analysis in Ground Water Tritium Quarterly grab samples. Midwest Laboratory Sampling Procedures 500 ml drinking water by liquid scintillation Manual Samples collected twice EIML-SPM-1, Environmental Incorporated annually via TBE, TBE-2007 Gamma emitting Fish Gamma Spectroscopy Midwest Laboratory Sampling Procedures 1000 grams (wet) electroshocking or other radioisotope analysis Manual techniques EIML-SPM-1, Environmental Incorporated TBE, TBE-2007 Gamma emitting Semi-annual grab Sediment Gamma Spectroscopy Midwest Laboratory Sampling Procedures 500 grams (dry) radioisotope analysis samples Manual

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2017 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Annual grab samples if dredging occurred EIML-SPM-1, Environmental Incorporated TBE, TBE-2007 Gamma emitting Dredging Spoils Gamma Spectroscopy within 1 mile of Dresden Midwest Laboratory Sampling Procedures 500 grams (dry) radioisotope analysis Station during the year. Manual One-week of continuous EIML-SPM-1, Environmental Incorporated 1 filter (approximately TBE, TBE-2008 Gross Alpha and/or Air Particulates Gross Beta air sampling through Midwest Laboratory Sampling Procedures 280 cubic meters gross beta activity in various matrices glass fiber filter paper Manual weekly)

TBE, TBE-2023 Compositing of samples Quarterly composite of Env. Inc., AP-03 Procedure for compositing air TBE, TBE-2007 Gamma emitting Air Particulates Gamma Spectroscopy 13 filters each station particulate filters for gamma spectroscopic radioisotope analysis analysis One- or two-week EIML-SPM-1, Environmental Incorporated 1 filter (approximately composite of continuous TBE, TBE-2007 Gamma emitting Air Iodine Gamma Spectroscopy Midwest Laboratory Sampling Procedures 280 cubic meters air sampling through radioisotope analysis Manual weekly) charcoal filter Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated TBE, TBE-2012 Radioiodine in various Milk 1-131 May through October. Midwest Laboratory Sampling Procedures 2 gallon matrices Monthly all other times Manual Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated TBE, TBE-2007 Gamma emitting Milk Gamma Spectroscopy May through October. Midwest Laboratory Sampling Procedures 2 gallon radioisotope analysis Monthly all other times Manual EIML-SPM-1, Environmental Incorporated TBE, TBE-2007 Gamma emitting Food Products Gamma Spectroscopy Annual grab samples. Midwest Laboratory Sampling Procedures 1000 grams radioisotope analysis Manual Quarterly OSLDs Optically Stimulated EIML-SPM-1, Environmental Incorporated comprised of two 2 dosimeters at each OSLD Luminescence Midwest Laboratory Sampling Procedures Landauer Incorporated Al203:C Landauer location Dosimetry Manual Incorporated elements.

11*1 11s.1.rD.a

~

  • 1U.Z
  • 114,12 11a,.211 DresdenNuctar Po.., Station Joliet Yum
  • Cfua II 1 *1
  • 'IUT-2 0 .

tn

====----===---

0 t 21CIIA ,...,.

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+ Sediment

  • war Figure B-1 Dresden Station Inner Ring OSLO Locations, Fish, Water, and Sediment Location, 2017 B-5

0 I 11Wlill llilllC:IIIIIC::IIMII*~======='

' 10

, ei ' J: ;

Figure B-2 Dresden Station Fixed Air Sampling and OSLO Sites, Outer Ring OSLO Locations and Milk Location, 2017 B-6

APPENDIX C DATA TABLES AND FIGURES

Intentionally left blank Table C-1.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD D-21 D-52 D-57 12/30/16 - 01/27/17 6.4 +/- 2.3 10.1 +/- 2.8 4.5 +/- 1.9 01/27/17 - 02/24/17 3.6 +/- 1.9 3.4 +/- 2.2 3.6 +/- 1.9 02/24/17 - 03/31/17 5.4 +/- 1.9 6.7 +/- 2.2 2.7 +/- 1.7 03/31/17 - 04/28/17 7.5 +/- 2.5 5.9 +/- 2.3 7.6 +/- 2.5 04/28/17 - 05/26/17 6.1 +/- 2.3 5.8 +/- 2.3 5.0 +/- 2.1 05/26/17 - 06/30/17 6.3 +/- 2.0 9.7 +/- 2.3 4.7 +/- 1.8 06/30/17 - 07/28/17 3.7 +/- 1.9 7.2 +/- 2.2 3.1 +/- 1.9 07/28/17 - 08/25/17 6.2 +/- 2.0 7.9 +/- 2.2 6.1 +/- 1.9 08/25/17 - 09/29/17 7.6 +/- 2.1 9.6 +/- 2.2 4.8 +/- 1.8 09/29/17 - 10/27/17 6.4 +/- 2.1 6.3 +/- 2.1 3.1 +/- 1.9 10/27/17 - 11 /24/17 6.8 +/- 2.0 6.7 +/- 2.2 2.8 +/- 1.8 11/24/17 - 12/22/17 9.1 +/- 2.3 9.8 +/- 2.4 5.5 +/- 1.9 MEAN+/- 2 STD DEV 6.3 +/- 3.0 7.4 +/- 4.1 4.5 +/- 3.0 Table C-1.2 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD D-21 D-52 D-57 01/20/17 - 03/31/17 < 194 < 189 < 192 04/07/17 06/30/17 < 194 < 192 448 +/- 141 07/07/17 - 09/29/17 265 +/- 126 < 183 548 +/- 136 09/29/17 - 12/29/17 < 193 < 196 1710 +/- 238 MEAN +/- 2 STD DEV 265 +/- 0 902 +/- 1403 THE MEAN AND 2 STANDARD DEV/A TION ARE CALCULATED USING THE POSITIVE VALUES C-1

. - ___ _ _ J

Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 D-21 12/30/16 - 01/27/17 < 6 < 5 < 14 <7 < 12 < 7 < 10 < 10 < 6 < 6 < 25 < 9 01/27/17 - 02/24/17 < 4 < 5 < 9 <5 < 11 <6 < 8 < 10 < 5 <6 < 28 < 8 02/24/17 - 03/31/17 < 8 < 8 < 14 <9 < 16 < 7 < 12 < 12 < 6 < 8 < 35 < 11 03/31/17 - 04/28/17 < 6 < 9 < 13 <7 < 13 < 7 < 12 < 10 < 8 <6 < 25 < 7 04/28/17 - 05/26/17 < 5 < 7 < 10 <9 < 16 < 9 < 10 < 13 < 6 <7 < 34 < 12 05/26/17 - 06/30/17 < 7 < 7 < 16 <8 < 17 < 8 < 14 < 13 < 8 < 8 < 35 < 14 06/30/17 - 07/28/17 < 5 < 6 < 13 < 6 < 14 < 6 < 11 < 8 < 7 < 6 < 30 < 10 07/28/17 - 08/25/17 < 5 < 5 < 11 <4 < 9 <6 < 9 < 13 < 5 <5 < 30 < 10 08/25/17 - 09/29/17 < 6 < 7 < 13 < 6 < 16 <7 < 12 < 12 < 8 < 8 < 32 < 11 09/29/17 - 10/27/17 < 6 < 7 < 8 <5 < 12 < 5 < 9 < 11 < 7 < 6 < 24 < 9 10/27/17 - 11/24/17 < 6 < 6 < 13 <7 < 10 < 8 < 11 < 10 < 6 < 8 < 30 < 10 11/24/17 - 12/29/17 < 7 < 8 < 19 <7 < 18 <9 < 13 < 12 < 9 < 9 < 36 < 15 MEAN D-52 01/20/17 - 01/27/17 < 10 < 8 < 20 <8 < 23 < 12 < 16 < 15 < 9 < 11 < 45 < 12 02/10/17 - 02/24/17 < 7 < 8 < 16 < 10 < 12 <9 < 12 < 13 <9 < 9 < 34 < 12

()

I 03/03/17 - 03/31/17 < 5 < 6 < 10 <6 < 13 < 6 < 10 < 7 <6 < 6 < 23 < 7 N 04/07/17 - 04/28/17 < 7 < 12 < 16 < 10 < 16 < 10 < 17 < 14 <9 < 11 < 42 < 12 05/05/17 - 05/26/17 < 8 < 7 < 19 <7 < 18 <8 < 15 < 11 < 11 < 9 < 35 < 10 06/02/17 - 06/30/17 < 6 < 7 < 14 < 7 < 13 <7 < 13 < 11 < 7 < 7 < 32 < 13 07/07/17 - 07/28/17 < 5 < 5 < 7 < 3 < 10 <5 < 7 < 9 <6 < 5 < 24 < 6 08/04/17 - 08/25/17 < 6 < 6 < 11 < 6 < 10 < 6 < 12 < 15 < 8 < 5 < 32 < 10 09/01/17 - 09/29/17 < 5 < 5 < 12 <5 < 13 < 6 < 6 < 8 < 6 < 5 < 26 < 11 10/06/17 - 10/27/17 < 10 < 11 < 16 < 10 < 21 <8 < 16 < 13 < 9 < 10 < 41 < 15 11/03/17 - 11/24/17 < 5 < 6 < 10 < 5 < 12 <4 < 8 < 8 <4 < 5 < 23 < 8 12/01/17 - 12/22/17 < 5 < 6 < 13 <5 < 12 < 6 < 10 < 14 <5 < 6 < 34 < 14 MEAN D-57 12/30/16 - 01/27/17 < 6 < 9 < 15 <7 < 18 < 8 < 16 < 11 < 9 < 9 < 34 < 11 01/27/17 - 02/24/17 < 6 < 7 < 14 < 6 < 14 < 5 < 11 < 10 < 8 < 7 < 28 < 11 03/03/17 - 03/31/17 < 6 < 6 < 11 < 6 < 13 < 6 < 11 < 10 < 7 < 7 < 29 < 7 03/31/17 - 04/28/17 < 9 < 6 < 10 < 11 < 19 < 8 < 12 < 13 < 9 < 7 < 26 < 12 04/28/17 - 05/26/17 < 8 < 7 < 15 < 8 < 19 < 8 < 12 < 14 < 8 < 9 < 37 < 12 05/26/17 - 06/30/17 < 7 < 9 < 14 < 9 < 20 < 8 < 12 < 14 < 9 < 8 < 30 < 11 06/30/17 - 07/28/17 < 7 < 5 < 15 < 8 < 13 < 6 < 13 < 12 < 9 < 7 < 29 < 8 07/28/17 - 08/25/17 < 4 < 5 < 12 < 6 < 9 < 7 < 10 < 13 < 5 < 5 < 36 < 13 08/25/17 - 09/29/17 < 6 < 6 < 11 < 8 < 12 < 8 < 12 < 11 < 8 < 8 < 38 < 10 09/29/17 - 10/27/17 < 6 < 8 < 15 < 6 < 14 < 7 < 15 < 11 < 8 < 9 < 34 < 10 10/27/17 - 11/24/17 <5 < 6 < 10 < 8 < 15 < 6 < 10 < 10 < 6 < 8 < 24 < 14 12/08/17 - 12/22/17 < 6 < 6 < 16 < 8 < 11 < 6 < 11 < 12 < 6 < 7 < 40 < 15 MEAN

Table C-11.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD D-23 D-35 01/13/17 - 01/13/17 362 +/- 137 < 187 02/10/17 - 02/10/17 504 +/- 144 03/10/17 - 03/10/17 362 +/- 131 04/14/17 - 04/14/17 303 +/- 134 < 194 05/11/17 - 05/11/17 463 +/- 138 06/09/17 - 06/09/17 330 +/- 128 07/21/17 - 07/21/17 495 +/- 145 < 185 08/11/17 - 08/11/17 488 +/- 134 09/08/17 - 09/08/17 390 +/- 128 10/13/17 - 10/13/17 449 +/- 132 < 182 11/10/17 - 11/10/17 (1) 12/08/17 - 12/08/17 (1)

MEAN +/- 2 STD DEV 415 +/- 148 THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-3 L

Tables C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 D-23 01/13/17 - 01/13/17 < 8 < 9 < 17 < 8 < 11 <9 < 13 < 13 <9 < 8 < 41 < 11 02/10/17 - 02/10/17 < 3 < 3 < 8 <4 < 7 < 3 < 6 < 9 <3 < 4 < 23 <7 03/10/17 - 03/10/17 < 5 < 6 < 13 <7 < 10 < 6 < 12 < 11 <7 < 7 < 26 < 9 04/14/17 - 04/14/17 < 7 < 7 < 11 < 6 < 16 < 7 < 11 < 11 <7 < 8 < 33 <7 05/11/17 - 05/11/17 < 5 < 5 < 10 < 6 < 10 <6 < 10 < 11 <5 < 7 < 27 <9 06/09/17 - 06/09/17 < 7 < 9 < 13 < 7 < 13 < 8 < 11 < 10 <8 < 7 < 31 <9 07/21/17 - 07/21/17 < 4 < 4 < 9 < 5 < 10 < 5 < 9 < 6 <5 <4 < 21 < 6 08/11/17 - 08/11/17 < 5 < 5 < 13 < 7 < 12 <7 < 10 < 8 <6 < 6 < 26 <9 09/08/17 - 09/08/17 < 2 < 2 < 5 < 2 <4 < 2 <4 < 9 <2 < 2 < 18 <6 10/06/17 - 10/06/17 < 6 < 7 < 12 < 7 < 13 <7 < 13 < 12 <6 < 8 < 34 <8 11/10/17 - 11/10/17 (1) 12/08/17 - 12/08/17 (1)

MEAN C')

I

~

D-35 01/13/17 - 01/13/17 < 8 < 8 < 16 < 9 < 10 < 9 < 13 < 11 < 7 < 10 < 44 < 11 04/14/17 - 04/14/17 < 5 < 4 < 8 < 3 < 9 < 4 < 7 < 6 < 5 <4 < 19 <7 07/14/17 - 07/14/17 < 8 < 7 < 17 < 7 < 15 < 8 < 12 < 12 < 7 < 7 < 34 < 10 10/13/17 - 10/13/17 < 6 < 7 < 8 < 5 < 10 < 6 < 11 < 10 < 8 < 7 < 32 < 12 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-111.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/KG WET+ 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 D-28 PREDIAOR Largemouth Bass 10/25/17 < 45 < 35 < 96 < 56 < 109 < 48 < 93 < 67 < 67 < 208 < 65 MEAN D-28 BOTTOM FEEDER Common Carp 05/03/17 < 43 < 44 < 80 < 39 < 84 < 45 < 55 < 38 < 42 < 195 < 51 Freshwater Drum 05/03/17 < 41 < 44 < 81 < 56 < 113 < 51 < 67 < 57 < 46 < 176 < 70 Common Carp 10/25/17 < 50 < 53 < 129 < 52 < 106 < 55 < 78 < 67 < 53 < 225 < 75 MEAN C)

I 0, D-46 PREDATOR Largemouth Bass 10/25/17 < 59 < 39 < 112 < 56 < 97 < 38 < 75 < 52 < 58 < 251 < 68 MEAN D-46 BOTTOM FEEDER Common Carp 05/03/17 < 52 < 50 < 109 < 52 < 119 < 59 < 94 < 61 < 58 < 277 < 71 Freshwater Drum 05/03/17 < 57 < 49 < 99 < 59 < 141 < 64 < 93 < 67 < 67 < 268 < 92 Common Carp 10/25/17 < 68 < 73 < 160 < 74 < 202 < 78 < 127 < 81 < 73 < 400 < 110 MEAN

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/KG DRY+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 D-27 05/27/17 < 60 < 66 < 138 < 71 < 135 < 71 < 125 < 75 134 +/- 64 < 324 < 82 10/18/17 < 100 < 134 < 258 < 141 < 223 < 108 < 205 < 128 144+/-117 < 422 < 137 MEAN +/- 2 STD DEV 139 +/- 15

(')

I 0,

THE MEAN AND 2 STANDARD DEV/AT/ON ARE CALCULATED USING THE POSITIVE VALUES L

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER+/- 2 SIGMA COLLECTION GROUP I GROUP II PERIOD D-01 D-02 D-03 D-04 D-07 D-45 D-53 D-56 D-58 12/30/16 - 01/06/17 18 +/- 4 17 +/- 4 17 +/- 4 21 +/- 4 16 +/- 4 24 +/- 4 19 +/- 4 20 +/- 4 21 +/-4 01/06/17 - 01/13/17 23 +/- 5 20 +/- 5 25 +/- 5 20 +/- 5 17 +/- 4 19 +/- 5 19 +/- 5 21 +/- 5 21 +/-5 01/13/17 - 01/20/17 17 +/- 4 13 +/- 4 15 +/- 4 14 +/- 4 16 +/- 4 13 +/- 4 16 +/- 4 17 +/- 4 16 +/-4 01/20/17 - 01/27/17 10 +/- 4 14 +/- 4 11 +/- 4 12 +/- 4 13 +/- 4 12 +/- 4 14 +/- 4 13 +/- 4 12 +/- 4 01/27/17 - 02/03/17 16 +/- 4 11 +/- 4 19 +/- 4 15 +/- 4 16 +/- 4 14 +/- 4 18 +/- 4 16 +/- 4 15 +/- 4 02/03/17 - 02/10/17 18 +/- 4 19 +/- 4 16 +/- 4 19 +/- 4 15 +/- 4 19 +/- 4 18 +/- 4 18 +/- 4 18 +/-4 02/10/17 - 02/17/17 16 +/- 5 19 +/- 5 19 +/- 5 18 +/- 4 15 +/- 4 15 +/- 4 17 +/- 5 20 +/- 5 20 +/-5 02/17/17 - 02/24/17 20 +/- 4 20 +/- 4 22 +/- 4 21 +/- 4 25 +/- 5 23 +/- 5 21 +/- 4 23 +/- 5 19 +/- 4 02/24/17 - 03/03/17 16 +/- 4 18 +/- 4 17 +/- 4 16 +/- 4 14 +/- 4 15 +/- 4 15 +/- 4 17 +/- 4 15 +/- 4 03/03/17 - 03/10/17 16 +/- 4 14 +/- 4 13 +/- 4 13 +/- 4 12 +/- 4 13 +/- 4 15 +/- 4 14 +/- 4 9 +/- 4 03/10/17 - 03/17/17 17 +/- 4 17 +/- 4 17 +/- 4 19 +/- 4 17 +/- 4 11 +/- 4 15 +/- 4 17 +/- 4 17 +/- 4 03/17/17 - 03/24/17 15 +/- 5 15 +/- 5 17 +/- 5 18 +/- 5 15 +/- 5 16 +/- 5 19 +/- 5 14 +/- 5 15 +/- 5 03/24/17 - 03/31/17 13 +/- 4 15 +/- 4 12 +/- 3 14 +/- 4 10 +/- 3 13 +/- 4 15 +/- 4 12 +/- 3 14 +/- 4 03/31/17 - 04/07/17 (1) (1) (1) (1) (1) . (1) (1) (1) (1) 04/07/17 - 04/14/17 10 +/- 4 14 +/-4 13 +/-4 9 +/- 4 12 +/- 4 12 +/- 4 12 +/- 4 6 +/-4 13 +/- 4 04/14/17 - 04/21/17 10 +/- 4 11 +/-4 14 +/-4 10 +/- 3 11 +/- 4 12 +/- 4 14 +/- 4 9 +/-4 10 +/- 3 04/21/17 - 04/28/17 6 +/- 3 9 +/-4 10 +/- 4 12 +/- 4 9 +/- 4 8 +/- 4 11 +/- 4 8 +/- 4 8 +/- 4 04/28/17 - 05/05/17 12 +/- 4 11 +/- 4 12 +/- 4 11 +/- 3 10 +/- 3 8 +/- 3 13 +/- 4 10 +/- 3 12 +/- 4 05/05/17 - 05/11/17 14 +/- 4 11 +/- 4 14 +/-4 15 +/- 4 16 +/- 5 12 +/- 4 13 +/- 4 10 +/- 4 11 +/- 4 05/11/17 - 05/19/17 17 +/- 4 14 +/-4 17 +/- 4 16 +/- 4 16 +/- 4 14 +/- 4 14 +/- 4 15 +/- 4 17 +/- 4 05/19/17 - 05/26/17 10 +/- 3 11 +/- 4 12 +/- 4 8 +/- 3 10 +/- 3 11 +/- 3 10 +/- 3 10 +/- 3 9 +/- 3 05/26/17 - 06/02/17 13 +/- 4 16 +/-4 19 +/-4 10 +/- 3 12 +/- 4 15 +/- 4 15 +/- 4 17 +/-4 15 +/- 4 06/02/17 - 06/09/17 14 +/- 4 14 +/-4 15 +/-4 15 +/- 4 14 +/- 4 14 +/- 4 17 +/- 4 14 +/-4 15 +/- 4 06/09/17 - 06/16/17 17 +/- 4 17 +/- 4 19 +/- 4 17 +/- 4 19 +/- 4 16 +/- 4 20 +/- 4 18 +/-4 18 +/- 4 06/16/17 - 06/23/17 11 +/- 4 12 +/-4 10 +/- 4 11 +/- 4 13 +/- 4 9 +/- 4 10 +/- 4 10 +/-4 10 +/- 4 06/23/17 - 06/30/17 12 +/- 4 7 +/- 3 10 +/-3 8 +/- 3 9 +/- 4 8 +/- 3 9 +/- 4 9 +/-4 11 +/- 4 06/30/17 - 07/07/17 18 +/- 7 21 +/-5 22 +/-5 15 +/- 4 22 +/- 5 20 +/- 4 23 +/- 5 17 +/-4 18 +/- 4 07/07/17 - 07/14/17 16 +/- 4 18 +/-4 17 +/- 4 14 +/- 4 17 +/- 4 14 +/- 4 18 +/- 4 15 +/-4 15 +/- 4 07/14/17 - 07/21/17 14 +/- 4 14 +/- 4 12 +/- 4 16 +/- 4 17 +/- 4 17 +/- 4 17 +/- 4 18 +/- 4 18 +/- 4 07/21/17 - 07/28/17 13 +/- 4 11 +/- 3 14 +/- 4 14 +/- 4 17 +/- 4 13 +/- 3 16 +/- 4 15 +/- 4 14 +/- 4 07/28/17 - 08/04/17 16 +/- 4 17 +/- 4 17 +/- 4 13 +/- 4 15 +/- 4 15 +/- 4 16 +/- 4 17 +/- 4 19 +/- 4 08/04/17 - 08/11/17 13 +/- 4 16 +/- 4 17 +/- 4 17 +/- 4 17 +/- 4 16 +/- 4 17 +/- 4 15 +/- 4 19 +/- 4 08/11/17 - 08/18/17 18 +/- 4 16 +/- 4 16 +/- 4 15 +/- 4 18 +/- 4 16 +/- 4 17 +/- 4 15 +/- 4 16 +/- 4 08/18/17 - 08/25/17 17 +/- 4 18 +/-4 17 +/- 4 17 +/- 4 16 +/- 4 17 +/- 4 20 +/- 4 17 +/-4 18 +/- 4 08/25/17 - 09/01/17 17 +/- 4 13 +/-4 19 +/-4 19 +/- 4 18 +/- 4 18 +/- 4 20 +/- 4 18 +/-4 17 +/- 4 09/01/17 - 09/08/17 17 +/- 4 13 +/-4 14 +/- 4 15 +/- 4 18 +/- 4 17 +/- 4 16 +/- 4 17 +/-4 18 +/- 4 09/08/17 - 09/15/17 14 +/- 4 10 +/-4 11 +/- 4 15 +/- 4 12 +/- 4 14 +/- 4 11 +/- 4 15 +/-4 11 +/- 4 09/15/17 - 09/22/17 25 +/- 5 25 +/-5 22 +/- 4 20 +/- 4 26 +/- 5 28 +/- 5 29 +/- 5 20 +/-4 27 +/- 5 09/22/17 - 09/29/17 25 +/- 4 29 +/- 5 26 +/- 4 26 +/- 5 25 +/- 4 27 +/- 5 29 +/- 5 26 +/-5 26 +/- 5 09/29/17 - 10/06/17 13 +/- 4 16 +/- 4 12 +/-4 12 +/- 4 15 +/- 4 18 +/- 4 20 +/- 5 17 +/-4 14 +/- 4 10/06/17 - 10/13/17 20 +/- 4 19 +/-4 19 +/-4 20 +/- 4 18 +/- 4 19 +/- 4 19 +/- 4 18 +/- 4 21 +/- 4 10/13/17 - 10/20/17 17 +/- 4 15 +/- 4 16 +/- 4 14 +/- 4 15 +/- 4 14 +/- 4 14 +/- 4 19 +/- 4 16 +/- 4 10/20/17 - 10/27/17 12 +/- 4 11 +/- 4 15 +/- 4 11 +/- 4 14 +/- 4 12 +/- 4 14 +/- 4 11 +/-4 13 +/- 4 10/27/17 - 11/03/17 10 +/- 4 11 +/-4 11 +/-4 6 +/- 3 11 +/- 4 5 +/- 3 9 +/- 4 10 +/- 4 9 +/-4 11/03/17 - 11/10/17 23 +/- 4 23 +/- 4 22 +/- 4 17 +/- 4 23 +/- 4 23 +/- 4 24 +/- 4 23 +/- 4 23 +/- 4 11/10/17 - 11/17/17 17 +/- 4 15 +/-4 15 +/-4 18 +/- 4 17 +/- 4 17 +/- 5 16 +/- 4 17 +/-4 22 +/- 5 11/17/17 - 11/24/17 23 +/- 5 20 +/-4 18 +/- 4 21 +/- 4 20 +/- 4 22 +/- 4 21 +/- 4 20 +/-4 23 +/- 4 11/24/17 - 12/01/17 19 +/- 4 22 +/-4 19 +/-4 19 +/- 4 16 +/- 4 18 +/- 4 18 +/- 4 19 +/-4 19 +/- 4 12/01/17 - 12/08/17 21 +/- 4 18 +/- 4 23 +/- 5 24 +/- 5 22 +/- 4 22 +/- 4 24 +/- 5 23 +/- 4 22 +/- 4 12/08/17 - 12/15/17 18 +/- 4 20 +/- 4 18 +/-4 20 +/- 4 15 +/- 4 20 +/- 5 14 +/- 4 21 +/-4 14 +/- 4 12/15/17 - 12/22/17 21 +/- 4 23 +/- 4 24 +/-4 22 +/- 4 23 +/- 4 15 +/- 4 25 +/- 4 24 +/-4 24 +/- 4 12/22/17 - 12/30/17 23 +/- 4 23 +/- 4 22 +/-4 22 +/- 4 22 +/- 4 27 +/- 6 23 +/- 4 20 +/- 4 24 +/- 4 MEAN 16 +/- 8 16 +/- 9 16 +/- 8 16 +/- 9 16 +/- 8 16 +/- 10 17 +/- 9 16 +/- 9 16 +/- 9 THE MEAN AND 2 STANDARD DEV/A TION ARE CA LC ULA TED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-7

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER+/- 2 SIGMA COLLECTION GROUP Ill GROUP IV PERIOD D-08 D-10 D-14 D-55 D-12 12/30/16 - 01/06/17 19 +/- 4 17 +/- 4 19 +/- 4 21 +/- 4 18 +/- 4 01 /06/17 - 01 /13/17 21 +/- 5 22 +/- 5 22 +/- 5 24 +/- 5 20 +/- 4 01/13/17 - 01/20/17 15 +/- 4 15 +/- 4 17 +/- 4 13 +/- 4 17 +/- 4 01/20/17 - 01/27/17 12 +/- 4 11 +/- 4 12 +/- 4 15 +/- 4 12 +/- 4 01/27/17 - 02103117 19 +/- 5 15 +/- 4 15 +/- 4 15 +/- 4 14 +/- 4 02103/17 - 02110117 21 +/- 5 15 +/- 4 19 +/- 4 17 +/- 4 13 +/- 4 02110117 - 02117117 19 +/- 5 16 +/- 5 15 +/- 5 15 +/- 4 17 +/- 5 02117117 - 02124117 19 +/- 4 22 +/- 4 18 +/- 4 19 +/- 4 20 +/- 4 02/24/17 - 03/03/17 15 +/- 4 13 +/- 4 16 +/- 4 14 +/- 4 15 +/- 4 03/03/ 17 - 03/ 10/17 16 +/- 4 13 +/- 4 13 +/- 4 14 +/- 4 13 +/- 4 03110/17 - 03/17/17 18 +/- 4 14 +/- 4 14 +/- 4 15 +/- 4 15 +/- 4 03117117 - 03124117 20 +/- 5 19 +/- 5 10 +/- 4 20 +/- 5 15 +/- 5 03124117 - 03131/17 15 +/- 4 15 +/- 4 14 +/- 4 12 +/- 3 13 +/- 4 03131117 - 04107/17 (1) (1) (1) (1) (1) 04/07117 - 04/14117 12 +/- 4 11 +/- 4 12 +/- 4 12 +/-4 11 +/- 4 04114117 - 04121117 12 +/- 4 14 +/- 4 12 +/-4 11 +/-4 12 +/- 4 04121117 - 04/28117 13 +/- 4 6 +/- 3 10 +/-4 11 +/-4 12 +/- 4 04128117 - 05/05117 13 +/- 4 9 +/- 3 11 +/-4 9 +/-3 10 +/- 3 05105/17 - 05/11/17 14 +/- 5 16 +/- 5 14 +/- 4 12 +/-4 13 +/- 4 05111/17 - 05119117 15 +/- 4 15 +/- 4 16 +/-4 18 +/-4 15 +/- 4 05119117 - 05126117 11 +/- 4 10 +/- 3 9 +/-3 11 +/-4 9 +/- 3 05126117 - 06102117 13 +/- 4 18 +/- 4 11 +/-4 12 +/-4 14 +/- 4 06102117 - 06109117 15 +/- 4 14 +/- 4 17 +/-4 20 +/-4 20 +/- 4 06109117 - 06116117 18 +/- 4 16 +/- 4 16 +/-4 20 +/-4 12 +/- 4 06116117 - 06123/17 14 +/- 4 10 +/- 4 10 +/-4 13 +/-4 10 +/- 4 06/23117 - 06130117 8 +/- 3 10 +/- 4 12 +/-4 10 +/-4 10 +/- 4 06130117 - 07107117 21 +/- 4 22 +/- 5 17 +/-4 19 +/-4 19 +/- 4 07107117 - 07114117 15 +/- 4 11 +/- 4 12 +/- 4 16 +/-4 18 +/- 4 07114117 - 07121117 19 +/- 4 21 +/- 4 15 +/-4 18 +/-4 20 +/- 4 07121/17 - 07128/17 15 +/- 4 12 +/- 3 17 +/-4 17 +/-4 15 +/- 4 07128117 - 08104/17 14 +/- 4 17 +/- 4 17 +/-4 14 +/-4 17 +/- 4 08104117 - 08111117 .15 +/- 4 20 +/- 4 17 +/-4 22 +/-4 17 +/- 4 08111117 - 08118/17 18 +/- 4 16 +/- 4 18 +/-5 19 +/-4 20 +/- 4 08/18117 - 08125/17 21 +/- 4 18 +/- 4 15 +/-4 18 +/-4 18 +/- 4 08/25/17 - 09101/17 15 +/- 4 19 +/- 4 18 +/-4 20 +/-4 16 +/- 4 09101/17 - 09108/17 18 +/- 5 14 +/- 4 12 +/-5 16 +/-4 15 +/- 4 09/08/17 - 09115/17 10 +/- 4 11 +/- 4 14 +/-4 11 +/-4 11 +/- 4 09/15117 - 09122/17 25 +/- 5 24 +/- 4 25 +/-5 25 +/-5 24 +/- 5 09/22117 - 09129117 25 +/- 4 26 +/- 5 29 +/-5 22 +/-4 26 +/- 5 09129117 - 10106117 14 +/- 4 15 +/- 4 14 +/-4 16 +/-4 17 +/- 4 10106117 - 10113/17 21 +/- 4 18 +/- 4 21 +/-4 15 +/-4 22 +/- 4 10/13117 - 10120/17 13 +/- 4 19 +/- 4 16 +/-4 19 +/-4 18 +/- 4 10120/17 - 10/27/17 12 +/- 4 10 +/- 4 11 +/- 4 13 +/- 4 14 +/- 4 10127/17 - 11/03117 8 +/- 3 7 +/- 3 5 +/- 3 10 +/-4 11 +/- 4 11103117 - 11110117 20 +/- 4 25 +/- 4 25 +/-5 24 +/-4 21 +/- 4 11110/17 - 11/17/17 13 +/- 4 16 +/- 4 14 +/-4 14 +/-4 16 +/- 4 11/17/17 - 11/24/17 19 +/- 4 20 +/- 4 23 +/-5 22 +/-5 20 +/- 4 11/24/17 - 12/01/17 19 +/- 4 16 +/- 4 19 +/-4 19 +/-4 20 +/- 4 12101117 - 12108/17 23 +/- 5 20 +/- 4 21 +/-5 20 +/- 4 22 +/- 4 12/08117 - 12/15/17 15 +/- 4 16 +/- 4 20 +/-5 18 +/-4 15 +/- 4 12/15117 - 12/22/17 24 +/- 4 19 +/- 4 22 +/-4 21 +/-4 23 +/- 4 12/22/17 - 12/30/17 21 +/- 4 20 +/- 4 21 +/-4 20 +/-4 19 +/- 4 MEAN +/- 2 STD DEV 16 +/- 8 16 +/- 9 16 +/- 9 16 +/- 8 16 +/- 8 THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-8

Table C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER+/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP 11 - NEAR-FIELD LOCATIONS GROUP Ill - 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 12/30/16 - 02/03/17 10 25 16 +/- 9 12/30/16 - 02/03/17 12 24 17 +/- 6 12/30/16 - 02/03/17 11 24 17 +/- 8 12/30/16 - 02/03/17 12 20 16 +/- 6 02/03/17 - 03/03/17 16 22 18 +/- 4 02/03/17 - 03/03/17 14 25 18 +/- 6 02/03/17 - 03/03/17 13 22 17 +/- 5 02/03/17 - 03/03/17 13 20 16 +/- 6 03/03/17 - 03/31/17 12 17 15 +/- 4 03/03/17 - 03/31/17 9 19 14 +/- 5 03/03/17 - 03/31/17 10 20 15 +/- 6 03/03/17 - 03/31/17 13 15 14 +/- 2 04/07/17 - 04/28/17 6 14 11 +/- 5 04/07/17 - 04/28/17 6 14 10 +/- 4 04/07/17 - 04/28/17 6 14 11 +/- 4 04/07/17 - 04/28/17 11 12 11 +/- 1 04/28/17 - 06/02/17 10 19 14 +/- 5 04/28/17 - 06/02/17 8 17 12 +/- 5 04/28/17 - 06/02/17 9 18 13 +/- 6 04/28/17 - 06/02/17 9 15 12 +/- 5 06/02/17 - 06/30/17 7 19 13 +/- 7 06/02/17 - 06/30/17 8 20 13 +/- 7 06/02/17 - 06/30/17 8 20 14 +/- 8 06/02/17 - 06/30/17 10 20 13 +/- 10 06/30/17 - 08/04/17 11 22 16 +/- 6 06/30/17 - 08/04/17 13 23 16 +/- 5 06/30/17 - 08/04/17 11 22 16 +/- 6 06/30/17 - 08/04/17 15 20 18 +/- 3 08/04/17 - 09/01/17 13 19 16 +/- 4 08/04/17 - 09/01/17 15 20 17 +/- 3 08/04/17 - 09/01/17 15 22 18 +/- 4 08/04/17 - 09/01/17 16 20 18 +/- 3 09/01/17 - 09/29/17 10 29 19 +/- 13 09/01/17 - 09/29/17 11 29 20 +/- 12 09/01/17 - 09/29/17 10 29 19 +/- 13 09/01/17 - 09/29/17 11 26 19 +/- 15 09/29/17 - 11/03/17 10 20 14 +/- 7 09/29/17 - 11/03/17 5 21 14 +/- 8 09/29/17 - 11/03/17 5 21 14 +/- 9 09/29/17 - 11/03/17 11 22 16 +/- 8 11/03/17 - 12/01/17 15 23 20 +/- 6 11/03/17 - 12/01/17 16 24 20 +/- 5 11/03/17 - 12/01/17 13 25 19 +/- 8 11/03/17 - 12/01/17 16 21 19 +/- 5 12/01/17 - 12/30/17 18 24 21 +/- 4 12/01/17 - 12/29/17 14 27 21 +/- 7 12/01/17 - 12/29/17 15 24 20 +/- 4 12/01/17 - 12/29/17 15 23 20 +/- 7 Q

I co 12/30/16 - 12/30/17 6 29 16 +/- 8 12/30/16 - 12/29/17 5 29 16 +/- 9 12/30/16 - 12/29/17 5 29 16 +/- 9 12/30/16 - 12/29/17 9 26 16 +/- 8

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 D-01 12/30/16 - 03/31/17 < 2 < 2 < 4 < 1 < 3 < 2 <4 < 2 < 2 < 10 < 3 04/07/17 - 06/30/17 < 3 < 2 < 7 < 3 < 4 < 3 <4 <2 < 2 < 15 < 5 06/30/17 - 09/29/17 < 4 < 4 < 14 <4 < 15 < 4 < 9 < 5 <4 < 37 < 17 09/29/17 - 12/29/17 < 2 < 3 < 7 < 3 < 6 < 3 < 5 < 3 < 3 < 23 < 8 MEAN D-02 12/30/16 - 03/31/17 < 3 < 2 < 6 < 3 ,< 6 < 2 <4 < 3 < 2 < 10 < 6 04/07/17 - 06/30/17 <4 < 5 < 9 <4 < 10 < 5 < 7 < 5 < 3 < 22 < 6 06/30/17 - 09/29/17 <2 < 2 < 4 < 2 < 5 < 3 <4 < 2 < 2 < 15 < 9 09/29/17 - 12/30/17 < 3 < 3 < 8 < 2 < 10 < 5 < 7 < 3 < 3 < 30 < 8 MEAN D-03 12/30/16 - 03/31/17 < 3 <4 <7 < 3 < 8 <4 < 7 <4 <4 < 20 < 7 04/07/17 - 06/30/17 < 2 <3 <4 <4 < 7 <3 < 5 <2 < 2 < 12 <4 06/30/17 - 09/29/17 < 2 <3 <7 < 3 < 6 <3 < 5 < 2 < 2 < 18 <7 09/29/17 - 12/30/17 < 2 <2 <4 < 1 < 5 <2 < 3 < 1 < 2 < 14 < 5

() MEAN I

0 D-04 12/30/16 - 03/31/17 < 2 < 2 <5 < 2 < 5 <2 <4 < 2 < 2 < 12 < 3 04/07/17 - 06/30/17 <4 < 4 <8 < 4 < 6 <3 < 6 < 3 < 3 < 24 < 5 06/30/17 - 09/29/17 <3 < 3 <7 < 4 < 8 <3 < 7 < 3 < 3 < 30 < 11 09/29/17 - 12/29/17 <2 < 2 <4 < 4 < 6 <3 <4 < 3 < 1 < 18 < 3 MEAN D-07 12/30/16 - 03/31/17 <2 < 2 < 7 < 2 < 6 < 3 < 3 < 3 < 2 < 14 <4 04/07/17 - 06/30/17 < 3 < 3 < 4 < 2 <4 < 3 <4 < 3 < 3 < 16 <6 06/30/17 - 09/29/17 <2 < 2 < 5 < 3 < 5 < 2 < 5 < 3 < 3 < 17 < 7 09/29/17 - 12/29/17 <2 < 3 < 7 < 3 <4 < 3 < 6 < 2 < 2 < 18 < 7 MEAN D-08 12/30/16 - 03/31/17 < 3 < 4 < 6 < 4 < 7 < 3 < 6 < 4 < 3 < 21 < 7 04/07/17 - 06/30/17 < 3 < 3 < 7 < 2 < 7 < 4 < 5 < 4 < 3 < 18 < 5 06/30/ 17 - 09/29/ 17 < 3 < 3 < 6 < 2 < 6 < 4 < 6 < 2 < 3 < 27 < 13 09/29/17 - 12/29/17 < 2 < 2 < 4 < 3 < 5 < 2 <4 < 2 < 2 < 18 <4 MEAN D-10 12/30/16 - 03/31/17 <2 < 2 <5 < 3 < 6 <2 < 4 < 2 < 2 < 13 < 5 04/07/17 - 06/30/17 < 3 <3 <7 < 3 < 6 <3 < 6 <4 < 3 < 18 < 5 06/30/17 - 09/29/17 < 3 <4 <9 <4 < 7 <4 < 6 <4 < 3 < 29 < 11 09/29/17 - 12/29/17 < 2 < 2 <6 < 2 < 5 <2 <4 < 3 < 3 < 20 < 10 MEAN

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 D-12 12/30/16 - 03/31/17 < 3 < 2 <4 < 3 <4 <2 <4 < 3 < 3 < 16 < 3 04/07/17 - 06/30/17 < 2 < 3 <5 < 2 < 6 <2 <4 < 3 < 2 < 15 < 3 06/30/ 17 - 09/29/17 < 2 < 2 <5 < 2 <4 <3 <4 <2 < 2 < 17 < 6 09/29/17 - 12/29/17 < 3 < 4 < 8 < 4 < 8 <3 < 6 < 3 < 3 < 27 < 6 MEAN D-14 12/30/16 - 03/31/17 <2 < 2 < 1 < 1 < 5 < 1 <3 < 2 < 1 < 9 <2 04/07/17 - 06/30/17 <2 < 2 <4 < 4 < 6 < 2 <4 < 2 < 2 < 15 < 7 06/30/17 - 09/29/17 <2 < 2 < 6 < 2 < 7 < 3 <5 < 2 < 2 < 21 < 11 09/29/17 - 12/29/17 <2 < 2 < 6 < 3 < 6 < 2 <4 < 3 < 2 < 17 <6 MEAN D-45 12/30/16 - 03/31/17 < 2 < 3 < 5 < 3 < 6 < 2 <4 < 3 <2 < 13 <4 04/07/17 - 06/30/17 < 4 < 4 < 5 < 4 < 10 <4 < 6 < 4 <4 < 24 < 8 06/30/17 - 09/29/17 < 4 < 4 < 8 <4 < 10 <4 <7 <4 < 4 < 34 < 14 09/29/17 - 12/29/17 < 3 < 2 < 6 <4 < 6 <4 <5 < 3 < 3 < 19 < 10 C')

I MEAN D-53 12/30/16 - 03/31/17 < 4 < 4 < 9 < 4 < 8 < 4 < 7 < 5 < 3 < 23 < 7 04/07/17 - 06/30/17 < 2 < 2 < 7 < 3 < 6 < 2 < 5 < 2 < 2 < 13 <6 06/30/17 - 09/29/17 < 2 < 2 < 5 < 2 < 3 < 3 < 3 < 2 < 2 < 18 <6 09/29/17 - 12/29/17 < 3 < 3 < 6 < 3 < 7 < 3 < 4 < 3 < 3 < 21 < 8 MEAN D-55 12/30/16 - 03/31/17 < 2 < 2 <4 < 3 < 5 < 2 <4 < 3 < 2 < 12 <2 04/07/17 - 06/30/17 < 3 < 2 <9 < 3 < 8 < 3 < 6 < 3 < 3 < 16 <4 06/30/17 - 09/29/17 < 2 < 2 <7 < 3 < 7 < 3 <4 < 2 < 3 < 24 < 11 09/29/17 - 12129/17 < 2 < 2 <5 < 3 < 5 < 2 <3 <2 < 2 < 13 < 5 MEAN D-56 12/30/16 - 03/31/17 < 3 < 3 < 4 < 1 < 6 < 3 <4 < 2 < 2 < 13 < 6 04/07/17 - 06/30117 < 3 < 3 < 6 < 3 < 7 < 4 < 7 <4 < 3 < 20 < 5 06/30/ 17 - 09/29117 < 3 < 3 < 8 <4 < 7 < 5 <7 < 4 < 3 < 32 < 11 09/29/17 - 12129/17 < 2 < 2 < 6 < 2 < 8 < 2 <4 < 3 < 2 < 17 < 7 MEAN D-58 12/30116 - 03131/17 < 3 < 4 <7 < 4 < 8 < 3 <6 <4 < 3 < 16 < 5 04/07/17 - 06130/17 < 3 < 2 <4 < 3 < 6 < 3 <4 <2 < 2 < 15 < 5 06/30/17 - 09/29/17 < 2 < 2 <8 < 2 < 5 < 2 <4 < 3 < 2 < 18 < 6 09/29117 - 12129/17 < 3 < 2 <5 < 2 < 6 < 2 < 5 < 2 < 2 < 18 < 6 MEAN

Table C-Vl.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER+ 2 SIGMA COLLECTION GROUP I GROUP II PERIOD D-01 D-02 D-03 D-04 D-07 D-45 D-53 D-56 D-58 12/30/16 - 01/06/17 < 38 < 38 < 38 < 16 < 37 < 24 < 39 < 39 < 37 01/06/17 - 01/13/17 < 32 < 31 < 30 < 32 < 22 < 45 < 45 < 46 < 17 01/13/17 - 01/20/17 < 16 < 39 < 37 < 38 < 39 < 39 < 41 < 42 < 39 01/20/17 - 01/27/17 < 10 < 23 < 24 < 23 < 23 < 23 < 20 < 20 < 20 01/27/17 - 02/03/17 < 14 < 32 < 30 < 32 < 31 < 35 < 36 < 35 < 14 02/03/17 - 02/10/17 < 23 < 64 < 65 < 65 < 66 < 48 < 55 < 54 < 54 02/10/17 - 02/17/17 < 21 < 50 < 50 < 48 < 51 < 27 < 55 < 54 < 52 02/17/17 - 02/24/17 < 23 < 56 < 54 < 54 < 56 < 44 < 34 < 34 < 33 02/24/17 - 03/03/17 < 22 < 52 < 52 < 54 < 51 < 44 < 44 < 45 < 46 03/03/17 - 03/10/17 < 12 < 28 < 27 < 27 < 27 < 48 < 45 < 44 < 44 03/10/17 - 03/17/17 < 17 < 48 < 47 < 46 < 47 < 49 < 53 < 51 < 51 03/17/17 - 03/24/17 < 14 < 33 < 32 < 33 < 32 < 15 < 32 < 32 < 31 03/24/17 - 03/31/17 < 16 < 38 < 37 < 39 < 38 < 20 < 35 < 35 < 36 03/31 /17 - 04/07/17 (1) (1) (1) (1) (1) (1) (1) (1) (1) 04/07/17 - 04/14/17 < 13 < 31 < 30 < 31 < 30 < 24 < 31 < 29 < 30 04/14/17 - 04/21/17 < 21 < 49 < 49 < 48 < 49 < 43 < 58 < 60 < 58 04/21/17 - 04/28/17 < 17 < 40 < 40 < 40 < 40 < 18 < 40 < 41 < 42 04/28/17 - 05/05/17 < 19 < 48 < 45 < 45 < 45 < 35 < 44 < 44 < 42 05105/17 - 05/11/17 < 21 < 51 < 50 < 49 < 50 < 21 < 45 < 45 < 45 05111/17 - 05/19/17 < 34 < 34 < 32 < 13 < 33 < 31 < 12 < 31 < 31 05119/17 - 05/26/17 < 43 < 18 < 43 < 40 < 42 < 22 < 47 < 47 < 47 05/26/17 - 06/02/17 < 20 < 47 < 47 < 44 < 46 < 28 < 28 < 29 < 11 06102/17 - 06/09/17 < 19 < 46 < 46 < 44 < 45 < 27 < 45 < 44 < 44 06/09/17 - 06/16/17 < 18 < 43 < 44 < 44 < 43 < 49 < 48 < 48 < 48 06/16/17 - 06/23/17 < 17 < 40 < 39 < 39 < 40 < 15 < 40 < 41 < 41 06/23/17 - 06/30/17 < 39 < 37 < 38 < 37 < 44 < 51 < 52 < 52 < 26 06/30/17 - 07107/17 < 31 < 40 < 40 < 39 < 39 < 42 < 43 < 43 < 19 07/07/17 - 07/14/17 < 20 < 45 < 45 < 46 < 45 < 43 < 44 < 44 < 18 07/14/17 - 07121117 < 15 < 36 < 35 < 34 < 35 < 16 < 57 < 57 < 57 07/21/17 - 07/28/17 < 23 < 53 < 53 < 53 < 53 < 41 < 51 < 51 < 52 07128/17 - 08/04/17 < 17 < 39 < 40 < 42 < 40 < 15 < 44 < 45 < 45 08/04/17 - 08/11/17 < 15 < 41 < 40 < 39 < 41 < 44 < 24 < 44 < 44 08/11/17 - 08/18/17 < 21 < 37 < 37 < 36 < 38 < 41 < 46 < 47 < 47 08/18/17 - 08/25/17 < 14 < 39 < 39 < 40 < 40 < 21 < 54 < 55 < 53 08/25/17 - 09/01/17 < 53 < 52 < 52 < 22 < 55 < 50 < 46 < 47 < 20 09/01/17 - 09/08/17 < 19 < 43 < 43 < 44 < 44 < 39 < 44 < 44 < 44 09/08117 - 09/15/17 < 17 < 39 < 38 < 39 < 39 < 18 < 41 < 41 < 41 09/15117 - 09/22/17 < 31 < 36 < 36 < 37 < 36 < 55 < 38 < 38 < 32 09/22/17 - 09/29/17 < 13 < 30 < 28 < 31 < 30 < 28 < 52 < 43 < 42 09/29/17 - 10/06/17 < 14 < 34 < 34 < 33 < 33 < 51 < 55 < 49 < 26 10/06/17 - 10/13/17 < 19 < 45 < 46 < 45 < 45 < 36 < 44 < 45 < 43 10/13/17 - 10/20/17 < 15 < 35 < 35 < 35 < 35 < 31 < 37 < 38 < 38 10/20/17 - 10/27/17 < 22 < 51 < 52 < 50 < 51 < 60 < 48 < 25 < 48 10/27/17 - 11/03/17 < 17 < 38 < 39 < 40 < 40 < 32 < 52 < 53 < 52 11/03/17 - 11/10/17 < 16 < 40 < 41 < 39 < 40 < 35 < 36 < 37 < 35 11/10/17 11/17/17 < 18 < 43 < 45 < 43 < 43 < 41 < 52 < 52 < 54 11/17/17 - 11/24/17 < 22 < 52 < 53 < 54 < 52 < 54 < 53 < 22 < 53 11/24/17 - 12/01/17 < 17 < 41 < 41 < 41 < 41 < 47 < 46 < 46 < 24 12101/17 - 12/08/17 < 17 < 40 < 42 < 41 < 41 < 38 < 54 < 54 < 55 12108/17 - 12/15/17 < 16 < 39 < 40 < 38 < 39 < 46 < 37 < 37 < 15 12/15/17 - 12/22/17 < 63 < 63 < 26 < 65 < 64 < 40 < 58 < 58 < 58 12/22/17 - 12/29/17 < 41 < 35 < 37 < 17 < 42 < 68 < 55 < 57 < 56 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-12

Table C-Vl.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCI/CU METER+ 2 SIGMA COLLECTION GROUP Ill GROUP IV PERIOD D-08 D-10 D-14 D-55 D-12 12/30/16 - 01/06/17 < 25 < 24 < 25 < 39 < 9 01/06/17 - 01/13/17 < 54 < 52 < 53 < 45 < 50 01/13/17 - 01/20/17 < 16 < 40 < 39 < 41 < 36 01120/17 - 01/27/17 < 9 < 22 < 23 < 20 < 22 01/27/17 - 02/03/17 < 31 < 30 < 32 < 35 < 29 02/03/17 - 02/10/17 < 22 < 49 < 50 < 55 < 47 02/10/17 - 02/17/17 < 51 < 50 < 51 < 55 < 49 02/17/17 - 02/24/17 < 44 < 44 < 44 < 33 < 16 02/24/17 - 03/03/17 < 43 < 44 < 44 < 45 < 24 03/03/17 - 03/10/17 < 51 < 50 < 48 < 44 < 19 03/10/17 - 03/17/17 < 22 < 51 < 50 < 51 < 48 03/17/17 - 03/24/17 < 39 < 39 < 39 < 32 < 38 03/24/17 - 03/31/17 < 47 < 46 < 47 < 36 < 46 03/31 /17 - 04/07/17 (1) (1) (1) (1) (1) 04/07/17 - 04/14/17 < 25 < 25 < 24 < 30 < 9 04/14/17 - 04/21/17 < 44 < 43 < 43 < 59 < 25 04/21/17 - 04/28/17 < 33 < 32 < 33 < 41 < 31 04/28/17 - 05/05/17 < 36 < 36 < 35 < 43 < 19 05/05/17 - 05/11/17 < 53 < 54 < 54 < 47 < 54 05/11/17 - 05/19/17 < 50 < 46 < 48 < 31 < 50 05/19/17 - 05/26/17 < 57 < 55 < 56 < 47 < 55 05/26/17 - 06/02/17 < 49 < 47 < 48 < 29 < 48 06/02/17 - 06/09/17 < 11 < 26 < 27 < 45 < 28 06/09/17 - 06/16/17 < 41 < 41 < 43 < 50 < 44 06/16/17 - 06/23/17 < 41 < 40 < 42 < 42 < 43 06/23/17 - 06/30/17 < 47 < 44 < 21 < 53 < 45 06/30/17 - 07/07/17 < 33 < 34 < 34 < 44 < 34 07/07/17 - 07/14/17 < 34 < 33 < 34 < 44 < 35 07/14/17 - 07/21/17 < 41 < 42 < 41 < 58 < 41 07/21/17 - 07/28/17 < 23 < 42 < 42 < 53 < 46 07/28/17 - 08/04/17 < 37 < 39 < 38 < 46 < 41 08/04/17 - 08/11/17 < 43 < 43 < 41 < 44 < 44 08/11/17 - 08/18/17 < 15 < 41 < 44 < 48 < 42 08/18/17 - 08/25/17 < 49 < 48 < 49 < 55 < 48 08/25/17 - 09/01/17 < 36 < 36 < 38 < 48 < 36 09/01/17 - 09/08/17 < 14 < 38 < 53 < 46 < 40 09/08/17 - 09/15/17 < 30 < 28 < 30 < 44 < 31 09/15/17 - 09/22/17 < 24 < 52 < 56 < 40 < 65 09/22/17 - 09/29/17 < 27 < 22 < 28 < 44 < 30 09/29/17 - 10/06/17 < 31 < 29 < 31 < 54 < 32 10/06/17 10/13/17 < 30 < 34 < 36 < 47 < 36 10/13/17 - 10/20/17 < 28 < 32 < 34 < 40 < 36 10/20/17 - 10/27/17 < 30 < 57 < 60 < 51 < 59 10/27/17 - 11/03/17 < 26 < 31 < 33 < 55 < 31 11/03/17 - 11/10/17 < 36 < 28 < 37 < 38 < 35 11/10/17 - 11/17/17 < 34 < 39 < 40 < 56 < 39 11/17/17 - 11/24/17 < 36 < 35 < 37 < 56 < 36 11/24/17 - 12/01/17 < 23 < 22 < 23 < 48 < 23 12/01/17 12/08/17 < 21 < 35 < 39 < 58 < 37 12/08/17 - 12/15/17 < 28 < 27 < 30 < 39 < 28 12/15/17 - 12/22/17 < 32 < 38 < 41 < 62 < 38 12/22/17 - 12/29/17 < 20 < 46 < 50 < 59 < 47 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-13

Table C-Vll.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION CONTROL FARM PERIOD D-25 01/04/17 < 0.6 02/01/17 < 0.8 03/01/17 < 0.5 04/20/17 < 0.7 05/04/17 < 0.8 05/18/17 < 0.7 05/31/17 < 0.8 06/15/17 < 1.0 06/28/17 < 0.7 07/12/17 < 0.4 07/27/17 < 0.8 08/10/17 < 0.6 08/24/17 < 0.6 09/06/17 < 0.4 09/21/17 < 0.4 10/05/17 < 0.8 10/19/17 < 0.4 11/01/17 < 0.8 12/06/17 < 0.7 MEAN C-14

Table C-Vll.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 D-25 01/04/17 <7 < 8 < 15 <8 < 17 < 8 < 13 < 6 <7 < 33 < 6 02/01/17 <8 < 7 < 11 <8 < 15 <8 < 11 < 6 < 7 < 29 < 11 3/1/2017 < 6 <7 < 15 <7 < 13 <7 < 14 < 7 < 8 < 41 < 10 04/20/17 <5 < 7 < 12 < 6 < 13 <6 < 10 <5 < 6 < 25 < 7 05/04/17 < 6 <7 < 17 <7 < 15 <8 < 10 < 8 < 7 < 33 < 8 05/18/17 <9 <7 < 16 <9 < 18 <7 < 14 < 8 < 8 < 31 < 10 05/31/17 <5 < 5 < 10 <4 < 11 <5 < 8 < 6 < 5 < 25 < 5 06/15/17 < 6 <7 < 12 <7 < 15 <7 < 12 < 7 < 7 < 25 < 8 07/12/17 < 10 < 11 < 23 < 10 < 21 < 10 < 18 < 11 < 9 < 47 < 14 06/28/17 <9 < 11 < 25 < 12 < 21 <9 < 17 < 12 < 9 < 46 < 13 07/27/17 < 10 < 11 < 26 < 13 < 21 <9 < 17 <9 < 9 < 38 < 13 08/10/17 <6 < 6 < 15 <7 < 15 <5 < 10 < 6 < 6 < 29 < 9 C)

~

I 08/24/17 < 8 < 7 < 16 <7 < 23 <9 < 12 < 11 < 8 < 33 < 12 en 09/06/17 < 5 < 6 < 11 < 6 < 12 <6 < 10 < 5 < 5 < 43 < 13 09/21/17 <7 < 9 < 20 < 8 < 20 <8 < 14 < 8 < 9 < 41 < 15 10/05/17 < 8 < 8 < 19 < 8 < 20 < 9 < 15 < 9 < 8 < 38 < 13 10/19/17 < 10 < 10 < 22 < 9 < 20 < 9 < 16 < 11 < 10 < 47 < 12 11/01/17 <5 <6 < 14 < 6 < 14 <5 <9 < 6 < 6 < 26 < 9 12/06/17 < 9 < 9 < 20 < 9 < 22 <9 < 16 < 10 < 8 < 39 < 10 MEAN

Table C-Vlll.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/KG WET+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 D-CONTROL Cucumbers 08/10117 < 23 < 19 < 48 < 21 < 51 < 22 < 42 < 37 < 25 < 23 < 107 < 23 Green cabbage 08/10/17 < 31 < 24 < 66 < 30 < 66 < 33 < 47 < 46 < 32 < 30 < 130 < 44 Potatoes 08110117 < 26 < 26 < 51 < 21 < 47 < 25 < 46 < 40 < 28 < 29 < 108 < 28 MEAN D-QUAD 1 Potato leaves 08/18117 < 38 < 36 < 74 < 38 < 84. < 40 < 62 < 56 < 40 < 41 < 164 < 45 Potatoes 08118117 < 45 < 50 < 97 < 54 < 89 < 53 < 89 < 59 < 57 < 55 < 199 < 58 MEAN

() D-QUAD 2 I

..lo.

a> Cabbage 07107117 < 26 < 24 < 52 < 29 < 68 < 27 < 36 < 31 < 22 < 27 < 84 < 13 Green Onions 07107117 < 45 < 48 < 87 < 52 < 99 < 51 < 83 < 58 < 51 < 46 < 150 < 55 Kohlrabi greens 07107117 < 24 < 21 < 50 < 24 < 55 < 24 < 32 < 27 < 22 < 21 < 91 < 24 MEAN 0-QUAD 3 Beet greens 07/28117 < 34 < 41 < 85 < 31 < 87 < 39 < 64 < 52 < 37 < 39 < 155 < 43 Red Beets 07/28117 < 30 < 31 < 44 < 27 < 52 < 24 < 47 < 41 < 29 < 30 < 133 < 36 MEAN D-QUAD4 Radish greens 07121117 < 29 < 31 < 52 < 37 < 71 < 29 < 46 < 42 < 33 < 33 < 127 < 36 Radishes 07121117 < 37 < 31 < 69 < 40 < 69 < 38 < 57 < 46 < 44 < 42 < 154 < 34 MEAN

Table C-IX.1 QUARTERLY OSLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF MREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN CODE +2 S.D. JAN - MAR APR- JUN JUL-SEP OCT-DEC D-01-1 27.8 +/- 4.5 26.5 26.9 31.2 26.7 D-01-2 28.4 +/- 5.1 26.9 26.9 32.2 27.7 D-02-1 28.4 +/- 5.0 26.2 28.1 31.9 27.2 D-02-2 29.4 +/- 3.1 27.5 29.4 31.3 29.2 D-03-1 24.7 +/- 5.6 23.5 23.3 28.9 23.1 D-03-2 24.7 +/- 4.9 24.4 22.6 28.2 23.7 D-04-1 28.2 +/- 6.2 25.8 26.7 32.7 27.5 D-04-2 27.8 +/- 4.2 25.9 26.7 30.7 27.7 D-07-1 27.2 +/- 4.7 25.5 25.8 30.6 26.7 D-07-2 27.2 +/- 5.3 25.1 26.2 31.1 26.4 D-08-1 28.3 +/- 4.9 26.0 27.7 31.8 27.7 D-08-2 28.0 +/- 5.1 25.3 27.1 31.4 28.3 D-10-1 27.6 +/- 7.5 25.1 27.1 33.0 25.0 D-10-2 28.0 +/- 5.2 25.4 26.9 31.5 28.0 D-12-1 24.9 +/- 5.3 24.5 22.3 28.6 24.3 D-12-2 24.0 +/- 4.6 23.0 21.8 27.2 23.9 D-14-1 25.4 +/- 5.2 23.4 23.1 28.6 26.3 D-14-2 26.3 +/- 4.0 24.9 25.0 29.2 26.2 D-45-1 27.4 +/- 5.8 25.8 25.8 31.7 26.1 D-45-2 27.5 +/- 5.8 26.3 26.0 31.9 25.9 D-53-1 24.9 +/- 8.6 21.7 23.2 29.8 23.5 ~1)

D-53-2 23.9 +/- 6.5 22.2 22.0 28.7 22.6 D-55-1 26.6 +/- 4.3 24.9 26.1 29.7 25.6 D-55-2 25.2 +/- 3.8 23.6 24.2 27.9 25.0 D-56-1 25.2 +/- 5.7 22.9 23.3 29.1 25.3 D-56-2 25.4 +/- 4.3 23.2 23.9 27.7 26.6 D-58-1 24.0 +/- 4.1 21.6 24.5 26.5 23.2 D-58-2 23.9 +/- 4.5 21.8 23.6 27.1 23.2 D-101-1 27.8 +/- 7.4 25.2 24.4 32.3 29.3 D-101-2 25.5 +/- 5.3 24.4 26.0 28.9 22.7 D-102-1 29.6 +/- 3.6 28.7 27.9 32.0 29.7 D-102-2 28.8 +/- 3.7 26.3 29.0 30.8 29.2 D-103-1 27.1 +/- 5.0 25.9 26.9 30.6 24.9 D-103-2 27.6+/-6.1 25.4 25.8 32.0 27.2 D-104-1 29.1 +/- 7.5 27.2 26.8 34.7 27.8 D-104-2 29.9 +/- 4.8 28.2 29.1 33.4 28.7 D-105-1 26.9 +/- 6.7 24.3 25.3 31.8 26.1 D-105-2 28.5 +/- 5.4 25.8 28.2 32.2 27.6 D-106-1 24.0 +/- 6.5 21.3 24.5 28.4 21.8 D-106-2 23.4 +/- 4.5 21.7 22.3 26.7 22.8 D-107-1 23.8 +/- 2.8 22.3 23.2 25.6 24.1 D-107-2 24.9 +/- 6.9 23.8 22.8 30.0 23.0 D-108-1 28.6 +/- 5.5 26.0 27.9 32.5 28.1 D-108-2 26.1 +/- 7.2 23.3 25.6 31.3 24.3 D-109-1 27.5 +/- 6.7 26.0 25.2 32.5 26.3 D-109-2 28.0 +/- 7.1 25.4 27.2 33.2 26.1 D-110-3 32.2 +/- 3.9 30.8 30.2 34.2 33.5 D-110-4 32.7 +/- 7.0 34.4 30.3 36.8 29.4 D-111-1 29.5 +/- 8.0 (1) 27.5 34.1 26.9 D-111-2 29.7 +/- 5.7 27.9 28.7 33.9 28.1 D-112A-1 25.9 +/- 6.7 23.7 22.9 30.3 26.7 D-112A-2 25.5 +/- 4.2 23.7 24.2 28.4 25.8 D-113-1 24.9 +/- 5.2 23.3 24.8 28.6 22.9 D-113-2 26.5 +/- 6.6 24.8 24.7 31.4 25.0 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-17

Table C-IX. 1 QUARTERLY OSLD RES ULTS FOR DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF MREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN CODE +/-2 S.D. JAN - MAR APR- JUN JUL-SEP OCT-DEC D-114-1 24.5 +/- 6.3 22.3 24.2 29.0 22.4 D-114-2 25.1 +/- 5.5 24.1 23.4 29.2 23.8 D-115-1 27.8 +/- 4.6 25.8 27.6 31.0 26.6 D-115-2 28.4 +/- 5.1 26.3 27.2 32.1 27.9 D-116-1 30.0 +/- 4.3 27.9 30.0 33.0 29.2 D-116-2 28.9 +/- 6.9 26.5 27.4 34.0 27.8 D-201-1 29.7 +/- 5.8 29.4 28.5 33.8 27.1 D-201-2 32.1 +/- 5.6 29.5 31.1 36.0 31.6 D-202-1 29.0 +/- 5.8 25.7 28.5 32.8 28.9 D-202-2 28.0 +/- 5.9 26.6 26.5 32.4 26.5 D-203-1 27.6 +/- 5.4 25.9 25.7 31.5 27.3 D-203-2 25.5 +/- 1.6 24.8 25.3 26.7 25.3 D-204-1 26.0 +/- 3.1 24.3 27.2 27.3 25.0 D-204-2 24.6 +/- 4.7 23.5 23.5 28.1 23.1 D-205-1 25.5 +/- 3.7 23.8 25.1 28.1 24.9 D-205-2 25.3 +/- 4.0 23.9 27.6 (1) 24.4 D-206-1 26.9 +/- 4.8 25.6 25.5 30.5 25.9 D-206-2 26.9 +/- 4.0 25.6 27.1 29.6 25.1 D-207-1 25.0+/-5.1 23.4 24.0 28.8 23.9 D-207-2 23.9 +/- 1.9 24.9 23.1 (1) 23.6 D-208-1 23.7 +/- 3.1 22.3 22.7 25.7 24.2 D-208-2 23.2 +/- 4.5 21.5 22.3 26.5 22.4 D-209-1 23.0 +/- 5.2 21.9 21.2 26.9 22.1 D-209-2 24.5 +/- 5.7 23.6 21.8 28.5 23.9 D-210-1 26.4 +/- 5.8 24.2 25.6 30.7 25.2 D-210-2 26.6 +/- 7.1 24.3 24.8 31.9 25.4 D-211-1 29.3 +/- 8.3 28.2 28.2 35.3 25.6 D-211-2 29.3 +/- 5.9 26.2 27.4 32.4 31.2 D-212-3 25.1 +/- 5.3 23.5 24.0 29.1 23.9 D-212-4 25.1 +/- 4.5 23.3 24.0 28.3 24.6 D-213-1 23.0 +/- 2.6 21.7 22.8 24.8 22.5 D-213-2 23.8 +/- 4.7 22.3 22.9 27.3 22.8 D-214-1 30.7 +/- 7.1 30.4 28.0 35.8 28.6 D-214-2 30.5 +/- 7.9 29.4 27.2 34.9 (1)

D-215-1 31.0+/-6.1 28.9 29.8 35.5 29.7 D-215-2 29.7 +/- 5.8 27.8 27.1 33.5 30.2 D-216-1 27.5 +/- 4.6 24.9 27.1 30.5 27.4 D-216-2 28.5 +/- 5.1 26.2 28.9 31.9 26.8 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-18

TABLE C-IX.2 MEAN QUARTERLY OSLO RESULTS FOR THE INNER RING, OUTER RING, OTHER AND CONTROL LOCATIONS FOR DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF MREM/QUARTER +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION INNER RING OUTER RING OTHER CONTROL PERIOD +/-2 S.D.

JAN-MAR 25.3 +/- 5.6 25.2 +/- 5.0 24.9 +/- 3.0 23.8 +/- 2.1 APR-JUN 26.2 +/- 4.6 25.8 +/- 5.0 25.6 +/- 3.9 22.1 +/- 0.7 JUL-SEP 31.1 +/- 5.2 30.5 +/- 6.5 30.5 +/- 3.2 27.9 +/- 2.0 OCT-DEC 26.2 +/- 5.4 25.8 +/- 5.2 26.2 +/- 3.4 24.1 +/- 0.6 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF MREM/QUARTER SAMPLES PERIOD PERIOD PERIOD MEAN LOCATION ANALYZED MINIMUM MAXIMUM +/-2 S.D.

INNER RING 135 21.3 36.8 27.2 +/- 6.9 OUTER RING 125 21.2 36.0 26.8 +/- 6.8 OTHER 96 21.7 33.0 26.8 +/- 5.5 CONTROL 8 21.8 28.6 24.5 +/- 4.7 INNER RING STATIONS- 0-101-1, D-101-2, D-102-1, D-102-2, 0-103-1, D-103-2, D-104-1, D-104-2, 0-105-1, 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, 0-111-1 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, D-58-1, D-58-2, OUTER RING STATIONS- D-201-1, D-201-2, 0-202-1, D-202-2, D-203-1, 0-203-2, D-204-1.D-204-2,0-205-1, 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, 0-210-1, D-210-2, 0-211-1, D-211-2, D-212-3, D-212-4, D-213-1, D-213-2, D-214-1, D-214-2, D-215-1, D-215-2, D-216-1, D-216-2 OTHER STATIONS- D-01-1, D-01-2, D-02-1, D-02-2, D-03-1, D-03-2, D-04-1, D-04-2, D-07-1,D-07-2,D-08-1 D-08-2, D-10-1, D-10-2, D-14-1, D-14-2, D-45-1, D-45-2, D-53-1, D-53-2, D-55-1, D-55-2, D-56-1, D-56-2 CONTROL STATIONS - D-12-1, D-12-2 C-19

FIGURE C-1 SURFACE WATER - GROSS BETA - STATION D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2017 D-52 (C) DesPlaines River at Will Road 16 14 12 10 4

2 0+-----.------.----~-----.---~

01-28-00 08-30-03 04-01-07 11-01-10 06-03-14 01-03-18 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-20

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

COLLECTED IN THE VICINITY OF DNPS, 2003 - 2017 D-54 (C) Kankakee River 14 12 10

_, 8 i3C. 6 4

2 0

01-31-03 12-25-03 11-17-04 10-11-05 09-04-06 07-29-07 D-57 (C) Kankakee River at Will Road 32 28 24 20 16 12 8

4 0 ---+-------l------4------+----+------I 07-28-06 06-23-08 05-20-10 04-15-12 03-12-14 02-06-16 01-02-18 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 0-54 LOCATION REMOVED FROM PROGRAM JUNE 28, 2007 AND REPLACED WITH 0-57 C-21

FIGURE C-3 SURFACE WATER - GROSS BETA - STATIONS D-21 and D-51 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2017 D-21 Illinois River at EJ&E Bridge 30 25 20

..I

~ 15 C.

10 5

0+-----1----1,-----1------+---1-----1 04-27-07 02-05-09 11-17-10 08-28-12 06-09-14 03-20-16 12-30-17 D-51 Dresden Lock & Dam 12 10 8

..I

~ 6 C.

4 2

0 +-----r----r-------.-----,-----,,-------r 01-28-00 04-24-01 07-20-02 10-15-03 01-09-05 04-06-06 07-02-07 D-21 PLACED INTO SERVICE ON MARCH 30, 2007, REPLACED D-51 D-51 LOCATION REMOVED FROM PROGRAM JUNE 29, 2007 AND REPLACED WITH D-21 C-22

FIGURE C-4 SURFACE WATER -TRITIUM - STATION D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2017 D-52 (C) Des Plaines River at Will Road 600 500

  • 400 0C. 300 200 100 0 -

03-31-00 10-19-03 05-08-07 11-25-10 06-14-14 01-01-18 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-23

FIGURE C-5 SURFACE WATER -TRITIUM - STATION D-54 (C) AND D-57 (C) COLLECTED IN THE VICINITY OF DNPS, 2003 - 2017 D-54 (C) Kankakee River 800 700 600 500 c3 400 C.

300 200 0+--~------¥-~--~---~---~---~--

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

D-57 (C) Kankakee River at Will Road 7000 6000 -

5000

..I 4000 G C. 3000 ..

2000 1000 0

12-20-06 10-22-08 08-25-10 06-27-12 04-30-14 03-02-16 01-03-18 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-24

FIGURE C-6 SURFACE WATER TRITIUM - STATIONS D-21 and D-51 m

COLLECTED IN THE VICINITY OF DNPS, 2000 - 2017 D-21 Illinois River at EJ&E Bridge 1200 1000 -

800

=:! 600 -

uC.

400 200 0

06-29-07 08-05-09 09-12-11 10-19-13 11-26-15 01-02-18 D-51 Dresden Lock & Dam 2000 1800 -

1600 1400 1200

=:!

u 1000 C.

800 600 400 200 0

03-31-00 10-18-01 05-07-03 11-23-04 06-12-06 12-30-07 D-21 REPLACED D-51 JUNE 29, 2007 0-51 LOCATION REMOVED FROM PROGRAM JUNE 29, 2007 AND REPLACED WITH 0-21 C-25

FIGURE C-7 GROUND WATER - TRITIUM - STATIONS D-23 and D-35 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2017 D-23 Thorsen Well 1000 800 600 u C.

400 200 0

01-08-00 08-10-03 03-12-07 10-12-10 05-14-14 12-14-17 D-35 Dresden Lock and Dam 400 350 300 250

! 200 uC.

150 100 50 0

01-08-00 08-13-03 03-18-07 10-21-10 05-26-14 12-29-17 DUE TO VENDOR CHANGE IN 2005, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MCD VALUES AFTER JULY 2005 C-26

FIGURE C-8 AIR PARTICULATES - GROSS BETA- STATIONS D-01 and D-02 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2017 D-01 Onsite Station 1 50.0 40.0

('")

§

(.)

30.0 C.

('")

~ 20.0 0

10.0 0.0 +-----~------~---~----

01-08-00 08-14-03 03-20-07 10-24-10 05-30-14 01-03-18 D-02 Onsite Station 2 50.0 40.0 M

§ 30.0

(.J C.

M 0

20.0 w

0 10.0 0.0 01-08-00 08-14-03 03-20-07 10-24-10 05-30-14 01-03-18 D-02 No samples; power was restored on 09-16-05.

C-27

FIGURE C-9 AIR PARTICULATES - GROSS BETA - STATIONS D-03 and D-04 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2017 D-03 Onsite Station 3 60.0 50.0

..., 40.0

.§ uc. 30.0 C')

9

~

.... 20.0 10.0 0.0 + - - - - + - - - - - + - - - - - - - - - l f - - - - - - l 01-08-00 08-14-03 03-20-07 10-24-10 05-30-14 01-03-18 D-04 Collins Road on Station Property 60.0 50.0

..., 40.0

.§ uc. 30.0 C')

9 w 20.0 0

10.0 0.0 + - - - - - - - - - - - - - 1 . - - - - - - 1 , - - - - - - 1 01-08-00 08-14-03 03-20-07 10-24-10 05-30-14 01-03-18 D-03 No samples; power was restored on 07-04-14.

C-28

FIGURE C-10 AIR PARTICULATES - GROSS BETA - STATIONS D-07 and D-12 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2017 D-07 Clay Products, Dresden Road 120.0 110.0 100.0 90.0

.., 80.0

.§ 70.0 u

C. 60.0 0 50.0 w 40.0

.... 30.0 0

20.0 10.0 0.0 01-08-00 08-14-03 03-20-07 10-24-10 05-30-14 01-03-18 D-12 (C), Quarry Road, Lisbon 80.0 70.0 60.0

.§ 50.0 uc. 40.0 0

w 30.o 0

20.0 10.0 0.0 - - - - - - - - - - - - - r - - - - - - - - 1 01-08-00 08-14-03 03-20-07 10-24-10 05-30-14 01-03-18 C-29 L

FIGURE C-11 AIR PARTICULATES - GROSS BETA- STATIONS D-45 and D-53 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2017 D-45 McKinley Woods Road, Channahon 70.0 60.0

.., 50.0

.§ 0Cl. 40.0 0 30.0 I.LI 0

20.0 10.0 0.0 01-08-00 08-14-03 03-20-07 10-24-10 05-30-14 01-03-18 D-53 Will Road, Hollyhock 50.0 40.0

.§ 30.0 uCl.

9 20.0 w

0 10.0 0.0 01-08-00 08-14-03 03-20-07 10-24-10 05-30-14 01-03-18 C-30

FIGURE C-12 AIR PARTICULATES - GROSS BETA - STATIONS D-08 and D-10 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2017 D-08 Jugtown Road, Prairie Parks 70.0 60.0 50.0 M

E

~ 40.0 Q.

9 30.0 w

~ 20.0 10.0 0.0 + - - - - - - - - - - - - - - - - - - - - - 1 01-07-05 03-08-07 05-06-09 07-05-11 09-02-13 11-01-15 12-30-17 D-10 Goose Lake Road, Goose Lake ViUage 60.0 50.0 M 40.0

§

(.)

Q. 30.0 M

C

...llJ C 20.0 10.0 0.0 - - - - - - - - - - - - - - - - - - - - - 1 01-07-05 03-08-07 05-06-09 07-05-11 09-02-13 11-01-15 12-30-17 C-31

FIGURE C-13 AIR PARTICULATES - GROSS BETA - STATIONS D-13 and D-14 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2017 D-13 Minooka 50.0 40.0 E 30.0

[i

..,Cl.

~ 20.0 0

10.0 0.0 - - - - - - - i - - - - - t - - - - t - - - - + - -

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

.§ 30.0 i:3 Cl.

0 w 20.0

....0 10.0 0.0 - - - - + - - - - + - - - - - + - - - - - + - - - - t - - - - - 1 01-07-05 03-08-07 05-06-09 07-05-11 09-02-13 11-01-15 12-30-17 D-13 TAKEN OUT OF SERVICE JUNE 29, 2007 AND REPLACED WITH D-55 C-32

_J

FIGURE C-14 AIR PARTICULATES - GROSS BETA - STATIONS D-55 and D-56 COLLECTED IN THE VICINITY OF DNPS, 2006-2017 D-55 Ridge Road, Minooka 70.0 60.0

.., 50.0

.E 0 40.0

..,C.

0 30.0 I.LI 0

..... 20.0 10.0 0.0 01-06-06 01-06-08 01-05-10 01-05-12 01-04-14 01-04-16 01-03-18 D-56 Will Road, Wildfeather 50.0 40.0

.E 30.0 0C.

9 20.0 w

0 10.0 0.0 + - - - - - + - - - - - - - - - - + - - - - - - + - - - - - I 07-25-06 06-20-08 05-17-10 04-12-12 03-09-14 02-03-16 12-30-17 D-55 NEW STATION DECEMBER 30, 2005 REPLACED D-13 JUNE 29, 2007 D-56 NEW STATION JULY 25, 2006 C-33

FIGURE C-15 AIR PARTICULATES - GROSS BETA- STATION D-58 COLLECTED IN THE VICINITY OF DNPS, 2011-2017 D-58 Will Road Marina 60.0 50.0

~ 40.0

[>

c. 30.0 M

9

...~ 20.0 10.0 0.0 + - - - - + - - - - - - ' - + - - - - f - - - - - l f - - - - - l 06-03-11 07-08-12 08-13-13 09-18-14 10-24-15 11-28-16 01-03-18 D-58 NEW STATION IN MAY OF 2011 C-34

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM

Intentionally left blank TABLE D.1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation (bl Number Value (a) Analytics Result Value March 2017 E11811 Milk Sr-89 pCi/L 87 97.7 0.89 A Sr-90 pCi/L 12.4 16.2 0.77 A E11812 Milk Ce-141 pCi/L 135 145 0.93 A Co-58 pCi/L 153 150 1.02 A Co-60 pCi/L 182 183 1.00 A Cr-51 pCi/L 258 290 0.89 A Cs-134 pCi/L 104 120 0.87 A Cs-137 pCi/L 142 140 1.02 A Fe-59 pCi/L 135 129 1.05 A 1-131 pCi/L 92.6 97.9 0.95 A Mn-54 pCi/L 173 164 1.05 A Zn-65 pCi/L 208 199 1.04 A E11813 Charcoal 1-131 pCi 92 93.9 0.98 A E11814 AP Ce-141 pCi 99.9 101 0.99 A Co-58 pCi 95.4 104 0.92 A Co-60 pCi 140 127 1.10 A Cr-51 pCi 211 201 1.05 A Cs-134 pCi 82.1 83.2 0.99 A Cs-137 pCi 92.8 97.0 0.96 A Fe-59 pCi 107 89.3 1.20 A Mn-54 pCi 106 114 0.93 A Zn-65 pCi 137 138 0.99 A E11816 Soil Ce-141 pCi/g 0.258 0.250 1.03 A Co-58 pCi/g 0.241 0.258 0.93 A Co-60 pCi/g 0.312 0.315 0.99 A Cr-51 pCi/g 0.439 0.500 0.88 A Cs-134 pCi/g 0.176 0.207 0.85 A Cs-137 pCi/g 0.304 0.317 0.96 A Fe-59 pCi/g 0.210 0.222 0.95 A Mn-54 pCi/g 0.292 0.283 1.03 A Zn-65 pCi/g 0.353 0.344 1.03 A E11815 Water Fe-55 pCi/L 1600 1890 0.85 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) 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 (Page 1 of4) 0-1

_J

TABLE D.1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation (bl Number Value (a) Analytics Result Value June 2017 E11844 Milk Sr-89 pCi/L 81.3 92.6 0.88 A Sr-90 pCi/L 12.1 13.5 0.90 A E11846 Milk Ce-141 pCi/L 142 151 0.94 A Co-58 pCi/L 147 155 0.95 A Co-60 pCi/L 185 191 0.97 A Cr-51 pCi/L 321 315 1.02 A Cs-134 pCi/L 168 188 0.89 A Cs-137 pCi/L 148 150 0.99 A Fe-59 pCi/L 116 115 1.01 A 1-131 pCi/L 102 93.6 1.09 A Mn-54 pCi/L 168 172 0.98 A Zn-65 pCi/L 195 204 0.96 A E11847 Charcoal 1-131 pCi 87.9 84.8 1.04 A E11845 AP Sr-89 pCi 70.8 79.1 0.90 A Sr-90 pCi 9.10 11.5 0.79 w E11848 AP Ce-141 pCi 112 116 0.96 A Co-58 pCi 119 119 1.00 A Co-60 pCi 171 146 1.17 A Cr-51 pCi 270 241 1.12 A Cs-134 pCi 152 144 1.05 A Cs-137 pCi 114 115 0.99 A Fe-59 pCi 94.1 88.3 1.07 A Mn-54 pCi 139 132 1.06 A Zn-65 pCi 141 156 0.90 A E11849 Water Fe-55 pCi/L 1840 1890 0.97 A July 2017 E11901 AP GR-A pCi 50.1 44.2 1.13 A GR-B pCi 218 233 0.93 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) 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 (Page 2 of 4)

D-2

TABLE D.1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation (bl Number Value (al Analytics Result Value September 2017 E11914 Milk Sr-89 pCi/L 84.3 82.7 1.02 A Sr-90 pCi/L 12.6 12.1 1.04 A E11915 Milk Ce-141 pCi/L 93.9 87.0 1.08 A Co-58 pCi/L 115 117 0.98 A Co-60 pCi/L 265 262 1.01 A Cr-51 pCi/L 273 217 1.26 w Cs-134 pCi/L 186 201 0.93 A Cs-137 pCi/L 175 172 1.02 A Fe-59 pCi/L 137 125 1.09 A 1-131 pCi/L 78.0 71.0 1.10 A Mn-54 pCi/L 128 123 1.04 A Zn-65 pCi/L 206 184 1.12 A E11916 Charcoal 1-131 pCi 71.9 64.4 1.12 A E11917 AP Ce-141 pCi 80.1 86.3 0.93 A Co-58 pCi 110 116 0.95 A Co-60 pCi 277 260 1.07 A Cr-51 pCi 275 215 1.28 w Cs-134 pCi 192 199 0.96 A Cs-137 pCi 165 170 0.97 A Fe-59 pCi 122 124 0.98 A Mn-54 pCi 120 122 0.99 A Zn-65 pCi 175 183 0.96 A E11918 Water Fe-55 pCi/L 1630 1630 1.00 A E11919 Soil Ce-141 pCi/g 0.136 0.142 0.96 A Co-58 pCi/g 0.179 0.191 0.94 A Co-60 pCi/g 0.405 0.429 0.94 A Cr-51 pCi/g 0.230 0.355 0.65 N (1l Cs-134 pCi/g 0.272 0.328 0.83 A Cs-137 pCi/g 0.336 0.356 0.94 A Fe-59 pCi/g 0.210 0.205 1.02 A Mn-54 pCi/g 0.210 0.201 1.05 A Zn-65 pCi/g 0.301 0.301 1.00 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) 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 (1) See NCR 17-16 (Page 3 of4)

D-3

TABLE D.1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Analytics Result Value December 2017 E12054 Milk Sr-89 pCi/L 92.1 92.3 1.00 A Sr-90 pCi/L 18.3 16.9 1.09 A E12055 Milk Ce-141 pCi/L 97.8 98.3 0.99 A Co-58 pCi/L 92.3 89.9 1.03 A Co-60 pCi/L 176 173 1.02 A Cr-51 pCi/L 226 242 0.93 A Cs-134 pCi/L 118 125 0.95 A Cs-137 pCi/L 148 141 1.05 A Fe-59 pCi/L 123 113 1.08 A 1-131 pCi/L 66.0 57.8 1.14 A Mn-54 pCi/L 173 161 1.08 A Zn-65 pCi/L 233 211 1.10 A E12056 Charcoal 1-131 pCi 48.1 47.5 1.01 A E12057A AP Ce-141 pCi 108 111 0.97 A Co-58 pCi 89.5 102 0.88 A Co-60 pCi 223 196 1.14 A Cr-51 pCi 311 274 1.13 A Cs-134 pCi 141 142 1.00 A Cs-137 pCi 162 160 1.01 A Fe-59 pCi 121 129 0.94 A Mn-54 pCi 177 182 0.97 A Zn-65 pCi 203 239 0.85 A E12058 Water Fe-55 pCi/L 1970 1740 1.13 A E12059 AP Sr-89 pCi 71.2 87.4 0.81 A Sr-90 pCi 12.9 16.0 0.81 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) 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< O. 70 and > 1.30 (Page 4 of4)

D-4

TABLE D.2 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (bl Number Value (a) Range Value February 2017 17-MaS36 Soil Ni-63 Bq/kg -5.512 (1) A Sr-90 Bq/kg 571 624 437-811 A 17-MaW36 Water Am-241 Bq/L 0.693 0.846 0.592 - 1.100 A Ni-63 Bq/L 13.4 12.2 8.5-15.9 A Pu-238 Bq/L 0.7217 0.703 0.492 - 0.914 A Pu-239/240 Bq/L 0.9277 0.934 0.654-1.214 A 17-RdF36 AP U-234/233 Bq/sample 0.0911 0.104 0.073- 0.135 A U-238 Bq/sample 0.0967 0.107 0.075 - 0.139 A 17-RdV36 Vegetation Cs-134 Bq/sample 6.44 6.95 4.87 - 9.04 A Cs-137 Bq/sample 4.61 4.60 3.22 - 5.98 A Co-57 Bq/sample -0.0229 (1) A Co-60 Sq/sample 8.52 8.75 6.13-11.38 A Mn-54 Sq/sample 3.30 3.28 2.30 - 4.26 A Sr-90 Sq/sample 1.30 1.75 1.23 - 2.28 w Zn-65 Sq/sample 5.45 5.39 3.77 - 7.01 A August 2017 17-MaS37 Soil Ni-63 Sq/kg 1130 1220 854 - 1586 A Sr-90 Sq/kg 296 289 202 - 376 A 17-MaW37 Water Am-241 Sq/L 0.838 0.892 0.624-1.160 A Ni-63 Sq/L -0.096 (1) A Pu-238 Sq/L 0.572 0.603 0.422 - 0.784 A Pu-239/240 Sq/L 0.863 0.781 0.547-1.015 A 17-RdF37 AP U-234/233 Sq/sample 0.103 0.084 0.059 - 0.109 w U-238 Sq/sample 0.115 0.087 0.061-0.113 N (2l 17-RdV37 Vegetation Cs-134 Sq/sample 2.34 2.32 1.62- 3.02 A Cs-137 Sq/sample 0.05 (1) A Co-57 Sq/sample 3.32 2.8 2.0 - 3.6 A Co-60 Sq/sample 2.09 2.07 1.45 - 2.69 A Mn-54 Bq/sample 2.90 2.62 1.83 - 3.41 A Sr-90 Bq/sample 1.17 1.23 0.86 - 1.60 A Zn-65 Sq/sample 6.07 5.37 3.76 - 6.98 A (a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) DOEIMAPEP evaluation:

=

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 (1) False positive test (2) See NCR 17-15 (Page 1 of 1)

D-5

TABLE 0.3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services TBE ldentrification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (bl Number Value(a) Limits Value March 2017 MRAD-26 AP GR-A pCi/sample 76.3 85.5 28.6 -133 A April 2017 RAD-109 Water Ba-133 pCi/L 49.2 49.7 40.8 - 55.1 A Cs-134 pCi/L 83.2 90.1 74.0 - 99.1 A Cs-137 pCi/L 202 206 185 - 228 A Co-60 pCi/L 51.2 54.7 49.2 - 62.7 A Zn-65 pCi/L 39.3 53.8 47.2 - 65.9 N (1)

GR-A pCi/L 53.6 75.0 39.5 - 92.3 A GR-B pCi/L 42.7 38.5 25.5 - 46.0 A U-Nat pCi/L 50.1 55.6 45.2 - 61.7 A H-3 pCi/L 7080 6850 5920 - 7540 A Sr-89 pCi/L 40.7 66.2 53.8 - 74.3 N (1)

Sr-90 pCi/L 26.9 26.7 19.3-31.1 A 1-131 pCi/L 26.7 29.9 24.9 - 34.9 A September 2017 MRAD-27 AP GR-A pCi/sample 40.9 50.1 16.8 - 77.8 A AP GR-B pCi/sample 58.0 61.8 39.1 - 90.1 A October 2017 RAD-111 Water Ba-133 pCi/L 71.3 73.7 61.7- 81.1 A Cs-134 pCi/L 43.0 53.0 42.8 - 58.3 A Cs-137 pCi/L 48.2 52.9 47.6- 61.1 A Co-60 pCi/L 69.0 69.5 62.6 - 78.9 A Zn-65 pCi/L 335 348 313 - 406 A GR-A pCi/L 32.5 35.6 18.3 - 45.8 A GR-B pCi/L 24.3 25.6 16.0 - 33.6 A U-Nat pCi/L 36.6 37.0 30.0 - 40.9 A H-3 pCi/L 6270 6250 5390 - 6880 A 1-131 pCi/L 26.4 24.2 20.1 - 28.7 A November 2017 1113170 Water Sr-89 pCi/L 57.1 50.0 39.4 - 57.5 A Sr-90 pCi/L 27.1 41.8 30.8 - 48.0 N (2)

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

(b) ERA evaluation:

A = Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits (1) See NCR 17-09 (2) See NCR 17-19 (Page 1 of 1)

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APPENDIX E ERRATA DATA

Intentionally left blank ERRATA FOR 2016 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REORTS (AREOR)

The following information was erroneously reported on Section I. Summary and Conclusions, Page 2 of the 2016 AREOR. The incorrect values are in (italics) and the corrected values are in BOLD.

2. Doses to a Member of the Public due to Gaseous Releases in 2016 (from 01/01/2016 to 12/31/2016):

UNITS 1, 2, 3 Gamma air (fission and activation gases): (3.32E-03) 2.32 E-03 mrad Beta air (fission and activation gases): (7.91 E-04) 1.12E-04 mrad Total Body (noble gases): (2.51E-03) 1.54E-03 mrem Skin (noble gases): (4.30E-03) 2.63E-03 mrem Organ - bone (radioiodines/tritium/particulates): (9.34E-02) 9.33E-02 mrem UNIT 1 Gamma air (fission and activation gases): NIA Beta air (fission and activation gases): N/A Total Body (noble gases): N/A Skin (noble gases): N/A Organ - bone (radioiodines/tritium/particulates): 1.87E-03 mrem UNIT2 Gamma air (fission and activation gases): (8. 75E-04) 5.96E-04 mrad Beta air (fission and activation gases): (2.0BE-04) 3.21 E-05 mrad Total Body (noble gases): (6.64E-04) 3.96E-04 mrem Skin (noble gases): (1.13E-03) 6.78E-04 mrem Organ - bone (radioiodines/tritium/particulates): 4.51 E-02 mrem UNIT3 Gamma air (fission and activation gases): (2.45E-03) 1.72E-03 mrad Beta air (fission and activation gases): (5.83E-04) 8.04E-05 mrad Total Body (noble gases): (1.84E-03) 1.1 SE-03 mrem Skin (noble gases): (3.17E-03) 1.95E-03 mrem Organ - bone (radioiodines/tritium/particulates): 4.72E-02 mrem E-1

Intentionally left blank APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Intentionally left blank Docket No: 50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Groundwater Protection Program Report 1 January through 31 December 2017 Prepared By Teledyne Brown Engineering Environmental Services xelon Generation~;

Dresden Nuclear Power Station Morris, IL 60450 May 2018

Intentionally left blank Table of Contents I. Summary and Conclusions ................................................................................................ 1 II. Introduction ........................................................................................................................ 2 A. Objectives of the RGPP ........................................................................................ 3 B. Implementation of the Objectives .......................................................................... 4 C. Program Description .............................................................................................. 4 D. Characteristics of Tritium (H-3) ............................................................................. 5 Ill. Program Description ......................................................................................................... 5 A. Sample Analysis .................................................................................................... 5 B. Data Interpretation ......................................................................... :....................... 6 C. Background Analysis ............................................................................................. 7

1. Background Concentrations of Tritium ....................................................... 7 IV. Results and Discussion ................................................................................................... 9 A. Groundwater Results ............................................................................................. 9 B. Surface Water Results ......................................................................................... 11 C. Precipitation Water Results ................................................................................. 11 D. Drinking Water Well Survey ................................................................................ 11 E. Summary of Results - Inter-laboratory Comparison Program ............................ 11 F. Leaks, Spills, and Releases ................................................................................. 11 G. Trends ................................................................................................................. 12 H. Investigations ....................................................................................................... 12 I. Actions Taken ....................................................................................................... 12

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Appendices ARGPPR Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2017 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 ARGPPR Appendix B Data Tables Tables Table B-1.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table B-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table B-1.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table B-11.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017 Table B-111.1 Concentrations of Tritium in Precipitation Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2017

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

The Dresden power plant has experienced leaks from underground lines and spills from systems containing radioactive water over its 50 year history. These incidents have created a number of areas of localized contamination within the PA. The liquid scintillation analyses of groundwater in many of these areas show measurable concentrations of tritium (H-3).

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

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

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

Tritium has a half-life of 12.3 years. This means that 40 years from now 90% of the tritium on site today will have decayed away to more stable elements. Given the limited volume of contaminated groundwater on site, radioactive decay, slow groundwater movement, and dilution effects, the conclusion of the HIR is that the operation of Dresden Nuclear Power Station has no adverse radiological impact on the environment. As a result there is little potential for contaminated groundwater on site to affect off-site drinking water.

11. 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 REM P.

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 96 sampling points in the RGPP:

Dresden has 47 developed groundwater monitoring wells within the Protected Area (PA). 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 30 developed groundwater monitoring wells outside the PA the majority of which form a ring just within the perimeter of the property.

Dresden has 12 surface water monitoring locations on the owner-controlled area sampled as part of the Dresden RGPP. Three of these locations are monitored for level only and have no analyses in the accompanying tables.

Dresden has 4 precipitation water monitoring locations sampled as part of the Dresden RGPP. An additional 8 locations were studied in 2011 through 2012, but only 4 locations are currently permanently a part of the RGPP program.

Dresden has 1 sentinel well and 2 CST leak detection valves. These 3 sampling points are not constructed to code or developed to a standard. These sampling points are idle and only used for qualitative troubleshooting.

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

The RGPP sample points are currently sampled on a frequency determined by the well detection category in accordance with site document EN-DR-408-4160, Dresden RGPP Reference Material. During 2017, there were 621 analyses that were performed on 278 samples from 84 sampling points.

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

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

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

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

Specific Objectives include:

1. Perform routine water sampling and radiological analysis of water from selected locations.
2. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.
3. Regularly assess analytical results to identify adverse trends.
4. Take necessary corrective actions to protect groundwater resources.

B. Implementation of the Objectives

1. Dresden Nuclear Power Station will continue to perform routine sampling and radiological analysis of water from selected locations.
2. Dresden Nuclear Power Station has implemented procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner.
3. Dresden Nuclear Power Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.
4. If an adverse trend in groundwater monitoring analytical results is identified, further investigation will be undertaken. If the investigation identifies a leak or unidentified spill, corrective actions will be implemented.

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

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

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

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

D. Characteristics of Tritium (H-3)

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

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

Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity and in special production reactors, where the isotopes lithium-? and/or boron-10 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface and therefore tritiated water will travel at the same velocity as the average groundwater velocity.

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

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

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 2017.

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.
3. Concentrations of tritium in groundwater, surface water and precipitation water.
4. Concentrations of gross alpha and gross beta in groundwater.
5. Concentrations of Am-241 in groundwater.
6. Concentrations of Cm-242 and Cm-243/244 in groundwater.
7. Concentrations of Pu-238 and Pu-239/240 in groundwater.
8. Concentrations of U-233/234, U-235 and U-238 in groundwater.
9. Concentrations of Fe-55 in groundwater.
10. Concentrations of Ni-63 in groundwater.

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

Several factors were important in the interpretation of the data:

1. Lower Limit of Detection and Minimum Detectable Concentration The Lower Limit of Detection (LLD) is the minimum sensitivity value that must be achieved routinely by the analytical parameter.
2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.

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

Exelon reports the TPU by following the result with plus or minus+/-

the estimated sample standard deviation as TPU that is obtained by propagating all sources of analytical uncertainty in measurements.

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

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

For groundwater and surface water 14 nuclides, Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140 and La-140 were reported.

C. Background Analysis A pre-operational radiological environmental monitoring program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, marine life, and food stuffs. 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 ther*monuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research, and weapons production continue to influence tritium concentrations in the environment.

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

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

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

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

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

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

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

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

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

Tritium Following historic ground tritium-contamination events at Dresden Station routine sampling and analyses continue, both inside and outside the protected area, in accordance with site procedure EN-DR-408-4160, Dresden Station RGPP Reference Material.

Low level tritium was detected from January through December 2017 in several sampling and testing locations (Table B-1.1, Appendix B); however, overall tritium concentrations have been trending down.

The vast majority of these locations showed a range of tritium contamination from LLD to values less than 20,000 pCi/L.

MD-11 and MW-DN-124-1 were the only 2 locations with tritium concentrations above 20,000 pCi/L. The highest level ever reached during calendar year 2017 was 195,000 pCi/L by MD-11 (sample collected on 02/17/2017).

It is important to note that wells that exceed the United States Environmental Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L were due to the 2014 2/3B CST Leak. The exceedances are located within Station property, and do not serve as a drinking water source.

Strontium Samples were collected and analyzed for Sr-89 and Sr-90 activity (Table B-1.1, Appendix B). Sr-89 was not detected in any of the samples. Sr-90 was detected in 3 samples at location MW-DN-105S. The concentrations ranged from 0.8 to 1.7 pCi/L.

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter of 2017 (Table B-1.1, Appendix B). Gross Alpha (dissolved) was detected in 1 groundwater location with a concentration of 6.3 pCi/L.

Gross Alpha (suspended) was detected in 5 groundwater locations with concentrations ranging from 1.8 to 18.6 pCi/L. Gross Beta (dissolved) was detected at 30 of the groundwater locations. The concentrations ranged from 1.1 to 124 pCi/L. Gross Beta (suspended) was detected in 5 groundwater locations with concentrations ranging from 1. 7 to 49.4 pCi/L.

The concentrations of Gross Alpha and Gross Beta, which are slightly above detectable levels, are considered to be background and are not the result of plant effluents.

Gamma Emitters Only naturally-occurring nuclides were detected in 4 samples. No other gamma-emitting nuclides were detected (Table B-1.2, Appendix B).

Hard-To-Detects Hard-To-Detect analyses were performed on 4 groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-233/234, U-235 and U-238. U-233/234 and U-238 were detected at MW-DN-119-1. The concentrations were 0.84 pCi/L and 0.44 pCi/L respectively (Table B-1.3, Appendix B). Ni-63 was detected in both samples taken at MW-DN-119-1.

The concentrations ranged from 32.3 to 58.9 pCi/L. All other hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs.

B. Surface Water Results Surface Water Samples were collected from 9 surface water locations throughout the year in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below:

Tritium Samples from all locations were analyzed for tritium activity (Table B-11.1, Appendix B). Tritium values ranged from the detection limit to 1,740 pCi/1.

The measurable concentrations of tritium are from an upstream source.

Gamma Emitters No gamma-emitting nuclides were detected in any surface water samples.

(Table B-11.2, Appendix B)

C. Precipitation Water Results Precipitation Water Samples were collected from 4 precipitation water locations throughout the year in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.

Tritium Samples from 4 locations were analyzed for tritium activity (Table B-111.1, Appendix B). Tritium was not detected in any samples.

D. Drinking Water Well Survey No drinking water well surveys were conducted in 2017.

E. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the AREOR.

F. Leaks, Spills, and Releases No leaks, spills, and releases occurred in 2017.

J

G. Trends Overall, tritium concentrations are decreasing across the Station. The Station continued to implement the tritium monitoring plan with monthly/quarterly sampling of a subset of shallow and intermediate aquifer wells, sewage treatment plant water, and storm sewer water.

An elevated concentration persists in the area of the Condensate Storage Tanks (Event 20 in EN-DR-408-4160, Revision 6, Attachment 3). As of December 2015, active remediation was implemented. Two remediation wells were installed in August 2015, however, the West remediation well is capable of enough recharge for active remediation.

H. Investigations No investigations performed in 2017.

I. Actions Taken

1. Compensatory Actions None.
2. Actions to Recover/Reverse Plumes In August 2015, two remediation wells were installed by the CSTs.

The intent is to pump tritiated water out of the ground. The water is processed through the liquid radwaste system. Active remediation was initiated in December 2015. Remediation continued through 2017.

APPENDIX A LOCATION DESIGNATION

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2017 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; 825 feet west of Ross Bridge DSP-121 Monitoring Well 72 feet north of 2/3 Intake Canal fence DSP-122 Monitoring Well 50 feet north of the Radwaste Tank Farm DSP-123 Monitoring Well Northeast corner of the Unit 1 Off-gas Building DSP-124 Monitoring Well 9 feet south of Floor Drain Collector Tank DSP-125 Monitoring Well Northeast 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-152 Monitoring Well 21 O 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-156 Monitoring Well 70 feet east by northeast of the northwest corner of 138 KV yard fence DSP-157-1 Monitoring Well 25 feet south of the south edge of the Employee Parking lot DSP-157-M Monitoring Well 25 feet south of the south edge of the Employee Parking lot DSP-157-S Monitoring Well 25 feet south of the south edge of the Employee Parking lot DSP-158-1 Monitoring Well 53 feet west of the Kankakee River; 33 feet west of the cinder track DSP-158-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 Monitoring Well 250 feet west of the Thorsen house; 450 ft south of the plant access gate DSP-159-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-102-S Monitoring Well 13 feet south of the southeast corner of the MUDS Building MW-DN-103-1 Monitoring Well 280 feet west of the northwest 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-105-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) Buildi[lg MW-DN-111-S Monitoring Well 9 feet east of the Floor Drain Collector Tank MW-DN-112-1 Monitoring Well 100 feet south of the Chemistry Building MW-DN-112-S Monitoring Well 100 feet south of the Chemistry Building MW-DN-113-1 Monitoring Well 90 feet west of the southwest corner of the Administration Building MW-DN-113-S Monitoring Well 91 feet west of the southwest corner of the Administration Building MW-DN-114-1 Monitoring Well 50 feet east of the Unit 1 Clean Demineralized Water Tank MW-DN-114-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-115-S Monitoring Well 12 feet south of Instrument Maintenance Shop MW-DN-116-1 Monitoring Well 75 feet south of the Calgon Building roll-up door MW-DN-116-S Monitoring Well 75 feet south of the Calgon Building roll-up door MW-DN-117-1 Monitoring Well 35 feet east by northeast of the Unit 1 Stack MW-DN-118-S Monitoring Well Southeast corner of the Unit 1 Fuel Pool MW-DN-119-1 Monitoring Well 20 feet east by northeast of the Unit 1 Sewage Ejector Building MW-DN-119-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 A-1

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2017 Site Site Type Location MW-DN-121-S Monitoring Well 7 feet west of the dirt road; 42 feet east of the 345KV yard fence MW-DN-122-1 Monitoring Well 150 feet north of Collins Road; northeast of the G.E. Fuel Storage Facility MW-DN-122-S Monitoring Well 150 feet north of Collins Road; northeast of the G.E. Fuel Storage Facility MW-DN-123-1 Monitoring Well 400 feet west of the Thorsen house; west of the Cold Canal MW-DN-123-S Monitoring Well 400 feet west of the Thorsen house; west of the Cold Canal MW-DN-124-1 Monitoring Well 1O feet south of the liquid nitrogen inerting tanks MW-DN-124-S Monitoring Well 1O feet south of the liquid nitrogen inerting tanks MW-DN-125-S Monitoring Well 40 feet east of 2/3 B CST MW-DN-126-S Monitoring Well 15 feet south of fence around Unit 2/3 A CST and B CST (outside of fence)

MW-DN-127-S Monitoring Well 20 feet south of Unit 3 HRSS MW-DN-134-S Monitoring Well 20-ft North of Mausoleum Building MW-DN-135-S Monitoring Well 20-ft East of Mausoleum Building MW-DN-136-S Monitoring Well 14.5-ft South of Mausoleum Building MW-DN-137-S Monitoring Well 20-ft West of Mausoleum Building MW-DN-140-S Monitoring Well East of MW-DN-104S at SW corner outside of 2/3 crib house MW-DN-141-S Monitoring Well North of 'A' Waste Tank next to 2/3 main chimney MD-11 Sample Piping located between Condensate Storage Tanks.

Location DSP-131 Surface Water Storm water- 35 ft NE of the Unit 2/3 heating boiler 150,000 gallon diesel fuel storage tank 15 ft W of the hot canal fence - underneath Security Block DSP-132 Surface Water Storm water - 150 ft NE of the Unit 1 Sphere. The sewer is in the middle of the road with a solid cover (no slots). There are two other sewers in the vicinity with solid covers on them, but both have the word "SANITARY" on the cover. The sewer is 66 ft SE of the Unit 1 diesel fuel transfe[ shed.

DSP-133 Surface Water Storm water ditch north of Pre-Access Facility SW-DN-101 Surface Water Unit 2/3 Intake (DSP50) at the Ross Bridge SW-DN-102 Surface Water Unit 2/3 Discharge (DSP20) at the Telemetry Bridge SW-DN-103 Surface Water Unit 2/3 Return Canal at the Discharge to the Intake Canal SW-DN-104 Surface Water Cold Canal (DSP34A) at the Cooling Tower walkway bridge SW-DN-105 Surface Water Hot Canal (DSP34B) at the Cooling Tower walkway bridge SW-DN-106 Surface Water Cooling Pond - Pool II at the east side of the Covered Bridge 2/3 Discharge Hot Canal Level Surface Water 2/3 Discharge Hot Canal Headworks 2/3 Cribhouse Cold Canal Level Surface Water 2/3 Cribhouse Unit 1 Cribhouse Intake Level Surface Water Unit 1 Cribhouse FW-1 Precipitation 40 feet southwest of Unit 2/3 Off-gas Filter Building access door; north end of guardrail FW-2 Precipitation 50 feet East of Chem Feed Trailer FW-3 Precipitation South of Stock Truck Bay rollup door FW-4 Precipitation Southeast corner of Unit 3 RB Interlock FW-5 Precipitation East of Unit 2/3 Intake Ross barrier FW-6 Precipitation North of Unit 1 Chimney FW-7 Precipitation Southeast of Unit 2 TB Trackway FW-8 Precipitation Southwest corner of 2/3 CST on fence FW-9 Precipitation South of MUDS Building on Security fence FW-10 Precipitation At the fence at the northwest corner of the SBO Building FW-11 Precipitation 30 feet east of the east wall of the EM shop; at the stanchion for RGPP well DSP-105 FW-12 Precipitation 60 feet southeast of the southwest comer of the Admin Building; on the security fence A-2

Intentionally left blank APPENDIX B DATA TABLES

Intentionally left blank TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LJTER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

CBE 03/13/17 < 187 CBE 05/23/17 < 182 CBE 08/25/17 < 179 CBG 05/23/17 4760 +/- 533 CBG 08/25/17 6810 +/- 732 DSP-105 02/16/17 < 194 DSP-105 05/17/17 < 195 < 5.3 < 0.6 < 1.8 < 0.6 7.1 +/- 1.3 < 1.4 DSP-105 08/23/17 < 190 DSP-105 11/08/17 < 180 DSP-106 02/16/17 1680 +/- 231 DSP-106 05/17/17 1840 +/- 247 < 6.1 < 0.8 < 1.5 < 0.6 6.8 +/- 1.2 < 1.4 DSP-106 08/23/17 1700 +/- 237 DSP-106 11/08/17 1700 +/- 234 DSP-107 02/15/17 2120 +/- 273 DSP-107 05/17/17 1940 +/- 254 < 6.7 < 0.7 < 2.7 < 0.6 11.5 +/- 1.6 < 1.4 DSP-107 08/23/17 2160 +/- 282 DSP-107 11/08/17 2030 +/- 266 DSP-108 02/15/17 492 +/- 145 DSP-108 05/17/17 457 +/- 140 < 7.1 < 0.9 < 3.8 < 0.6 19.4 +/- 2.1 < 1.4 DSP-108 08/22/17 455 +/- 138 DSP-108 11/08/17 379 +/- 131 DSP-122 02/13117 660 +/- 151 DSP-122 05/15117 641 +/- 148 DSP-122 08/21/17 399 +/- 134 DSP-122 11/07/17 537 +/- 136 DSP-123 02/15/17 908 +/- 164 DSP-123 05/16/17 927 +/- 162 < 5.5 < 0.7 < 1.7 < 0.6 8.1 +/- 1.3 < 1.4 DSP-123 08/22/17 760 +/- 152 DSP-123 11/08/17 649 +/- 143 DSP-124 02/20/17 1520 +/- 216 DSP-124 05/23/17 1350 +/- 200 DSP-124 08/29117 839 +/- 159 DSP-124 11/09117 1040 +/- 172 DSP-125 02117/17 398 +/- 138 DSP-125 05/24/17 281 +/- 133 < 5.5 < 0.8 < 10.7 2.2 +/- 1.0 27.4 +/- 4.4 < 1.9 DSP-125 08/25117 192 +/- 123 DSP-125 11/09/17 < 185 DSP-126 05/18/17 < 186 DSP-131 08/29/17 < 188 DSP-131 11/09/17 < 183 DSP-132 08/29/17 788 +/- 153 DSP-132 11/09/17 3570 +/- 414 DSP-133 09101/17 < 191 DSP-133 11/09/17 < 186 DSP-147 05/18/17 < 189 DSP-148 02122/17 301 +/- 132 DSP-148 05122/17 229 +/- 127 DSP-148 09/01117 233 +/- 125 DSP-148 11/07/17 < 180 DSP-149R 02/22/17 376 +/- 138 DSP-149R 05/22/17 498 +/- 142 DSP-149R 09/01/17 430 +/- 134 DSP-149R 11/07117 287 +/- 128 DSP-150 02/16/17 < 196 DSP-150 05/17/17 < 188 DSP-150 08/22117 < 188 DSP-150 11/08117 < 181 DSP-151 02/16/17 < 192 DSP-151 05/17/17 < 188 DSP-151 08/23/17 < 188 DSP-151 11/08/17 < 183 DSP-154 05/18/17 < 188 DSP-156 02122/17 < 195 DSP-156 05/22117 < 185 DSP-156 09/01/17 < 185 DSP-156 11/07/17 < 182 DSP-157-1 05/25/17 < 186 DSP-157-S 05/25/17 < 188 DSP-159-1 05/24/17 205 +/- 126 B-1 I

L

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

DSP-159-S 05124117 < 192 MD-11 02117117 195000 +/- 19200 < 6.0 < 0.4 < 1.7 < 0.3 29.9 +/- 1.8 < 1.6 MD-11 05124117 159000 +/- 15800 MD-11 08/25117 130000 +/- 12900 MD-11 11/09/17 114000 +/- 11300 < 3.9 < 0.6 < 1.2 < 0.8 21.6 +/- 1.5 < 1.7 MW-DN-101-1 02115117 568 +/- 148 MW-DN-101-1 05/16117 518 +/- 142 < 5.4 < 0.8 < 4.8 < 0.6 13.3 +/- 1.8 < 1.4 MW-DN-101-1 08/22117 485 +/- 133 MW-DN-101-1 11/08117 410 +/- 132 MW-DN-101-S 02115117 < 191 MW-DN-101-S 05/16117 Otiginal < 190 < 7.5 < 0.8 < 6.6 6.9 +/- 2.2 < 6.6 < 3.8 MW-DN-101-S 05/16117 Recount 6.6 +/- 2.4 MW-DN-101-S 08/22117 < 190 MW-DN-101-S 11108117 < 186 MW-DN-102-1 02117117 < 160 MW-DN-102-1 05/19117 < 188 < 5.3 < 0.8 < 13.8 < 2.3 < 9.5 < 3.8 MW-DN-102-1 08124117 < 184 MW-DN-102-1 11/08117 < 188 MW-DN-102-S 02117117 < 190 MW-DN-102-S 05119117 < 191 < 7.2 < 0.9 < 35.2 < 3.8 45.7 +/- 15.3 < 7.8 MW-DN-102-S 08124117 < 186 MW-DN-1 02-S 11/08117 < 184 MW-DN-1 03-1 05/24117 < 187 MW-DN-103-S 05124117 < 189 MW-DN-1 04-S 02/13117 < 190 MW-DN-1 04-S 05115117 < 188 MW-DN-104-S 08/21117 255 +/- 126 MW-DN-1 04-S 11107117 264 +/- 124 MW-DN-105-S 02/16117 < 195 < 8.8 1.6 +/- 0.5 MW-DN-105-S 05117117 < 186 < 6.7 < 0.9 MW-DN-105-S 08/23/17 < 187 < 4.8 0.8 +/- 0.3 MW-DN-105-S 11/08117 < 180 < 4.3 1.7 +/- 0.3 MW-DN-106-S 05/22117 < 190 MW-DN-107-S 02117117 < 194 MW-DN-107-S 05/24117 < 191 MW-DN-107-S 08125117 < 186 MW-DN-107-S 11/09117 < 185 MW-DN-108-1 02/14117 < 190 MW-DN-108-1 05/16117 Original < 195 < 5.7 < 0.9 < 3.4 17.7 +/- 4.2 7.6 +/- 3.2 49.4 +/- 4.7 MW-DN-108-1 05/16117 Recount 18.6 +/- 4.4 MW-DN-1 08-1 08/21117 < 184 MW-DN-108-1 11107/17 < 183 MW-DN-1 09-1 02113117 398 +/- 138 MW-DN-109-1 05/15117 361 +/- 135 < 5.9 < 0.8 < 4.0 < 1.8 6.1 +/- 3.4 < 3.9 MW-DN-109-1 08129/17 511 +/- 138 MW-DN-109-1 11107/17 376 +/- 133 MW-DN-1 09-S 02/13117 < 192 MW-DN-109-S 05115/17 < 189 < 5.8 < 0.9 < 5.9 < 1.8 14.1 +/- 5.0 < 3.9 MW-DN-109-S 08129117 < 186 MW-DN-109-S 11107/17 < 185 MW-DN-110-1 02/13117 < 190 MW-DN-110-1 05/15117 < 192 MW-DN-110-1 08/21117 < 184 MW-DN-110-1 11107117 < 185 MW-DN-11 0-S 02/20117 < 189 MW-DN-11 0-S 05/15117 < 191 MW-DN-11 0-S 08/21117 < 189 MW-DN-110-S 11107/17 < 187 MW-DN-111-S 02120/17 261 +/- 138 MW-DN-111-S 05123/17 289 +/- 131 MW-DN-111-S 08/29/17 384 +/- 134 MW-DN-111-S 11109/17 209 +/- 122 MW-DN-112-1 02113/17 < 191 MW-DN-112-1 05/15117 < 188 MW-DN-112-1 08/29/17 < 187 MW-DN-112-1 11/09/17 < 182 MW-DN-112-S 02113/17 < 195 MW-DN-112-S 05/15117 < 196 MW-DN-112-S 08/29117 < 190 B-2

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-8 (Dis) Gr-8 (Sus)

MW-DN-112-S 11/09/17 < 185 MW-DN-113-1 02/17/17 < 197 MW-DN-113-1 05/19/17 < 197 < 5.8 < 0.8 < 3.9 < 1.9 < 5.1 < 3.9 MW-DN-113-1 08/24/17 < 182 MW-DN-113-1 11/08/17 < 181 MW-DN-113-S 02/17/17 < 198 MW-DN-113-S 05/19/17 < 196 < 7.5 < 0.9 < 3.2 7.6 +/- 2.1 < 4.7 10.0 +/- 2.8 MW-DN-113-S 08/24/17 < 186 MW-DN-113-S 11/08/17 < 184 MW-DN-114-1 02/17/17 6150 +/- 669 MW-DN-114-1 05/23/17 3310 +/- 392 MW-DN-114-1 08/29/17 2100 +/- 275 MW-DN-114-1 11/08/17 7240 +/- 779 MW-DN-114-S 02/17/17 301 +/- 136 MW-DN-114-S 05/23/17 250 +/- 135 MW-DN-114-S 08/29/17 6360 +/- 694 MW-DN-114-S 11/08/17 < 184 MW-DN-115-1 02/16/17 202 +/- 129 MW-DN-115-1 05/19/17 301 +/- 139 MW-DN-115-1 08/25/17 408 +/- 134 MW-D N-115-1 11/08/17 373 +/- 131 MW-DN-115-S 02/16/17 < 190 MW-DN-115-S 05/19/17 < 195 MW-DN-115-S 08/25/17 < 188 MW-DN-115-S 11/08/17 < 183 MW-DN-116-1 02/14/17 < 189 MW-DN-116-1 05/16/17 < 198 < 9.7 < 0.7 < 3.8 < 0.6 16.2 +/- 2.0 < 1.4 MW-DN-116-1 08/21/17 < 198 MW-DN-116-1 11/07/17 223 +/- 122 MW-DN-116-S 02/14/17 < 188 MW-DN-116-S 05/16/17 < 198 < 7.2 < 1.0 < 3.8 < 1.0 16.5 +/- 2.0 < 2.0 MW-DN-116-S 08/21/17 < 194 MW-DN-116-S 11/07/17 < 180 MW-DN-117-1 02/14/17 < 190 MW-DN-117-1 05/16/17 < 193 MW-DN-117-1 08/29/17 < 194 MW-DN-117-1 11/07/17 < 184 < 3.6 < 0.5 < 1.0 < 0.8 2.4 +/- 0.7 < 1.7 MW-DN-118-S 02/15/17 287 +/- 133 MW-DN-118-S 05/17/17 < 192 < 9.8 < 0.9 < 2.3 < 0.8 7.9 +/- 1.4 < 1.4 MW-DN-118-S 08/23/17 < 193 MW-DN-118-S 11/08/17 < 183 MW-DN-119-1 02/15/17 < 194 MW-DN-119-1 05/23/17 Original < 194 < 6.2 < 0.9 < 28.9 < 2.8 124 +/- 11.4 < 4.0 MW-DN-119-1 05/23/17 Recount 120 +/- 11.2 MW-DN-119-1 08/29/17 < 193 MW-DN-119-1 11/08/17 < 184 MW-DN-119-1 11/17/17 < 179 < 3.6 < 0.5 6.3 +/- 2.5 < 0.9 28.5 +/- 2.8 < 2.6 MW-DN-119-S 02/15/17 < 193 MW-DN-119-S 05/23/17 Original < 194 < 4.2 < 0.7 < 1.6 1.8 +/- 1.0 2.3 +/- 0.9 1.7 +/- 1.1 MW-DN-119-S 05/23/17 Recount 2.0 +/- 0.9 MW-DN-119-S 08/29/17 < 192 MW-DN-119-S 11/08/17 < 178 MW-DN-122-1 05/25/17 < 196 MW-DN-122-S 05/25/17 < 198 MW-DN-124-1 02/20/17 27900 +/- 2830 MW-DN-124-1 05/19/17 25300 +/- 2580 < 6.4 < 0.8 < 7.2 < 2.8 9.6 +/- 4.0 < 4.0 MW-DN-124-1 08/25/17 29300 +/- 2990 MW-DN-124-1 11/09/17 24500 +/- 2490 MW-DN-124-S 02/20/17 Original 7960 +/- 850 MW-DN-124-S 02/20/17 Reanalysis 7520 +/- 804 MW-DN-124-S 05/19/17 293 +/- 136 < 9.0 < 0.9 < 6.4 < 2.9 < 5.5 4.5 +/- 2.6 MW-DN-124-S 08/25/17 205 +/- 128 MW-DN-124-S 11/09/17 2700 +/- 328 MW-DN-125-S 02/16/17 < 190 MW-DN-125-S 05/23/17 < 197 < 4.7 < 0.7 < 30.0 < 2.9 < 11.5 < 4.0 MW-DN-125-S 08/25/17 < 197 MW-DN-125-S 11/09/17 < 182 MW-DN-126-S 02/17/17 2740 +/- 332 MW-DN-126-S 05/24/17 1460 +/- 215 < 4.7 < 0.7 < 6.9 < 2.8 < 5.7 < 4.0 MW-DN-126-S 08/25/17 1730 +/- 247 B-3

TABLE 8-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

MW-DN-126-S 11/08/17 < 179 MW-DN-127-S 02/20/17 978 +/- 168 MW-DN-127-S 05/19/17 822 +/- 158 < 6.7 < 0.9 < 5.9 < 0.8 12.6 i 1.9 < 1.4 MW-DN-127-S 08/24/17 < 194 MW-DN-127-S 11/08/17 < 181 MW-DN-134-S 02/22/17 < 189 MW-DN-134-S 05/18/17 < 186 < 8.5 < 0.7 < 1.1 < 0.8 1.1 +/- 0.7 < 1.4 MW-DN-134-S 08/30/17 < 194 MW-DN-134-S 11/07/17 < 180 MW-DN-135-S 02/22/17 < 196 MW-DN-135-S 05/18/17 < 188 < 6.0 < 0.9 < 2.1 < 0.8 9.1 +/- 1.6 < 1.4 MW-DN-135-S 08/30/17 < 197 MW-DN-135-S 11/07/17 < 178 MW-DN-136-S 02/22/17 < 189 MW-DN-136-S 05/18/17 < 188 < 5.1 < 0.6 < 3.7 < 1.8 8.5 +/- 4.2 < 3.9 MW-DN-136-S 08/30/17 < 198 MW-DN-136-S 11/07/17 < 179 MW-DN-137-S 02/22/17 < 192 MW-DN-137-S 05/18/17 < 185 < 4.8 < 0.7 < 5.5 < 2.6 13.1 +/- 4.7 < 4.4 MW-DN-137-S 08/30/17 < 194 MW-DN-137-S 11/07/17 < 177 MW-DN-140-S 02/13/17 447 +/- 141 MW-DN-140-S 05/23/17 462 +/- 135 MW-DN-140-S 08/21/17 447 +/- 141 MW-DN-140-S 11/17/17 441 +/- 130 MW-DN-141-S 02/13/17 915 +/- 163 MW-DN-141-S 05/16/17 1660 i 231 < 7.6 < 0.7 < 0.8 < 0.8 8.5 +/- 0.9 < 1.4 MW-DN-141-S 08/21/17 1030 +/- 167 MW-DN-141-S 11/09/17 1130 +/- 179 MW-DN-142-S 02/22/17 < 191 MW-DN-142-S 05/22/17 < 181 < 4.8 < 1.0 < 3.0 < 0.6 18.7 +/- 2.7 1.8 +/- 0.9 MW-DN-142-S 08/31/17 < 170 MW-DN-142-S 11/07/17 < 180 MW-DN-143-S 02/22/17 < 192 MW-DN-143-S 05/22/17 < 182 < 6.1 < 0.8 < 4.7 < 1.8 9.7 +/- 3.9 < 3.9 MW-DN-143-S 08/31/17 < 173 MW-DN-143-S 11/07/17 < 180 MW-DN-144-S 02/22/17 < 192 MW-DN-144-S 05/22/17 < 187 < 4.4 < 0.6 < 4.8 < 1.9 12.4 +/- 4.1 < 3.9 MW-DN-144-S 08/30/17 < 171 MW-DN-144-S 11/07/17 < 179 B-4

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DSP-105 02/16/17 < 38 < 78 < 4 < 4 < 10 <4 < 9 < 5 < 7 < 13 <4 < 5 < 29 < 11 DSP-105 05/17/17 < 24 < 39 < 2 < 2 < 6 < 2 < 4 < 3 < 4 < 14 < 2 < 2 < 23 < 8 DSP-105 08/23/17 < 30 < 66 < 3 < 3 < 7 < 3 < 6 < 3 <6 < 13 < 4 < 3 < 26 < 8 DSP-105 11/08/17 < 44 < 100 < 5 < 5 < 9 <4 < 10 < 5 < 8 < 9 < 5 < 5 < 21 < 7 DSP-106 02/16/17 < 37 < 40 < 4 < 4 < 9 < 3 <7 < 5 < 8 < 13 < 5 < 4 < 31 < 10 DSP-106 05/17/17 < 19 < 32 < 2 < 2 < 5 <2 < 4 < 2 <4 < 13 < 2 < 2 < 21 < 8 DSP-106 08/23/17 < 33 < 71 < 4 < 4 < 8 <4 <7 <4 < 6 < 13 < 4 < 4 < 28 < 8 DSP-106 11/08/17 < 41 < 96 < 5 < 5 < 11 <4 < 7 < 5 < 8 < 10 < 5 < 5 < 23 < 7 DSP-107 02/15/17 < 34 < 57 < 3 < 4 < 8 <4 < 6 <4 < 7 < 13 < 3 < 4 < 31 < 8 DSP-107 05/17/17 < 18 < 16 < 2 < 2 < 5 <2 < 3 < 2 <4 < 13 < 2 < 2 < 20 < 7 DSP-107 08/23/17 < 38 < 35 < 4 < 4 < 8 <4 < 8 <4 < 7 < 15 <4 < 4 < 31 < 8 DSP-107 11/08/17 < 65 < 73 < 7 < 7 < 15 < 7 < 16 < 7 < 13 < 12 < 7 < 8 < 35 < 11 DSP-108 02/15/17 < 40 < 63 < 4 < 4 < 9 <4 < 9 < 5 < 8 < 13 < 4 < 4 < 33 < 10 DSP-108 05/17/17 < 22 < 46 < 2 < 2 < 6 < 2 <4 < 3 <4 < 14 < 2 < 2 < 24 < 8 DSP-108 08/22/17 < 37 < 31 < 4 < 4 < 9 <4 < 8 <4 < 7 < 13 <4 < 4 < 30 < 11 DSP-108 11/08/17 < 57 < 66 < 6 < 6 < 15 < 6 < 12 < 6 < 11 < 12 < 8 < 6 < 30 < 9 DSP-123 02/15/17 < 40 < 85 < 4 < 4 < 10 <4 < 10 <4 < 8 < 15 < 5 < 4 < 33 < 8 DSP-123 05/16/17 < 17 < 27 < 2 < 2 <4 <2 < 3 <2 < 3 < 12 < 2 < 2 < 20 < 7 OJ I DSP-123 08/22/17 < 34 < 89 < 3 < 3 < 9 <4 < 8 <4 < 7 < 15 < 4 < 4 < 30 < 13 en DSP-123 11/08/17 < 44 < 97 < 5 < 6 < 9 < 4 < 9 < 5 < 10 < 10 < 6 < 5 < 27 < 7 DSP-125 05124/17 < 50 < 59 < 6 < 4 < 11 < 5 < 10 < 7 < 10 < 15 < 6 < 6 < 40 < 13 DSP-126 05/18/17 < 23 < 45 < 2 < 3 < 6 <2 < 5 < 3 < 5 < 14 < 2 < 2 < 25 < 8 DSP-147 05/18/17 < 20 < 17 < 2 < 2 < 5 <2 <4 < 2. < 4 < 13 < 2 < 2 < 21 < 7 DSP-154 05/18/17 < 21 < 17 < 2 < 2 < 5 <2 < 4 <2 < 4 < 13 < 2 < 2 < 22 <7 DSP-157-1 05/25/17 < 43 < 44 < 5 < 5 < 10 < 5 < 9 < 5 < 8 < 13 < 6 < 5 < 29 < 10 DSP-157-S 05/25/17 < 45 95 +/- 63 < 6 < 6 < 14 < 7 < 10 < 5 < 11 < 15 < 6 < 6 < 38 < 8 DSP-159-1 05/24/17 < 39 < 103 < 5 < 5 < 10 < 4 < 10 < 5 < 9 < 14 < 5 < 4 < 27 < 8 DSP-159-S 05/24/17 < 48 < 84 < 5 < 5 < 9 < 5 < 10 < 6 < 11 < 15 < 6 < 6 < 32 < 5 MD-11 02/17/17 < 43 < 44 < 5 < 5 < 11 < 5 < 9 < 5 < 8 < 13 < 6 < 5 < 35 < 9 MD-11 11/09/17 < 39 < 72 < 5 < 4 < 10 < 5 < 9 < 5 < 8 < 8 < 5 < 5 < 23 < 6 MW-DN-101-1 02/15/17 < 42 < 31 < 4 < 4 < 9 <4 < 8 < 5 < 8 < 14 < 5 < 5 < 27 < 10 MW-DN-101-1 05/16/17 < 19 < 34 < 2 < 2 <4 <2 <4 <2 < 3 < 13 < 2 < 2 < 21 < 6 MW-DN-101-1 08/22/17 < 38 < 68 < 3 < 4 < 10 < 4 <7 <4 < 7 < 15 < 5 < 4 < 28 < 10 MW-DN-101-1 11/08/17 < 59 < 142 < 6 < 6 < 13 <6 < 10 <7 < 11 < 14 < 7 < 8 < 32 < 12 MW-DN-101-S 02/15/17 < 41 < 27 < 3 < 4 < 10 <3 < 7 <4 < 6 < 15 < 5 < 4 < 30 < 9 MW-DN-101-S 05/16/17 < 20 < 15 < 2 < 2 < 5 <2 <4 < 2 <4 < 14 < 2 < 2 < 23 < 8 MW-DN-101-S 08/22/17 < 27 < 29 < 3 < 3 < 7 < 3 <6 < 3 < 6 < 12 < 3 < 3 < 24 < 6 MW-DN-101-S 11/08/17 < 55 < 50 < 6 < 5 < 9 < 5 < 12 < 7 < 11 < 14 < 7 < 5 < 29 < 10 MW-DN-102-1 05/19/17 < 24 43 +/- 27 < 2 < 2 < 5 <2 <4 < 2 < 4 < 14 < 2 < 2 < 23 < 6 MW-DN-102-S 05/19/17 < 30 < 27 < 3 < 4 < 7 <3 < 7 <4 <6 < 15 <4 < 3 < 31 < 11 MW-DN-103-1 05/24117 < 37 < 73 < 4 < 5 < 10 <4 < 8 <4 < 7 < 12 < 5 < 4 < 30 < 9 MW-DN-103-S 05/24/17 < 41 < 94 < 5 < 5 < 14 <4 < 9 < 5 < 8 < 15 < 5 < 5 < 31 < 12 MW-DN-106-S 05122/17 < 35 < 61 < 3 < 4 < 8 <3 < 7 <4 < 6 < 14 < 4 < 3 < 28 < 10 MW-DN-108-1 02/14/17 < 38 < 32 < 3 < 4 < 8 < 3 < 7 <4 < 8 < 13 <4 < 4 < 29 < 8 MW-DN-108-1 05/16/17 < 23 < 47 < 2 < 3 < 6 < 2 <4 < 3 < 5 < 14 < 2 < 2 < 24 < 8

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 MW-DN-108-1 08/21/17 < 30 < 31 < 3 < 3 < 7 <3 < 6 < 3 < 6 < 14 < 3 < 3 < 27 < 10 MW-DN-108-1 11/07/17 < 60 < 108 < 6 < 6 < 8 <6 < 12 <6 < 10 < 12 <5 < 7 < 31 < 13 MW-DN-109-1 05/15/17 < 17 < 33 < 2 < 2 <4 <2 < 3 < 2 < 3 < 12 < 2 < 2 < 20 < 6 MW-DN-109-S 05/15/17 < 17 < 16 < 2 < 2 <5 <2 < 3 < 2 < 3 < 12 < 2 < 2 < 20 < 6 MW-DN-113-1 05/19/17 < 26 < 36 < 2 < 3 < 6 < 2 < 5 < 3 < 5 < 14 < 3 < 3 < 25 < 6 MW-DN-113-S 05/19/17 60 +/- 22 < 48 < 2 < 2 < 5 <2 < 4 < 3 < 4 < 11 <2 < 2 < 20 < 7 MW-DN-116-1 02/14/17 < 35 < 94 < 4 < 5 < 7 <4 < 9 <5 < 7 < 15 < 5 < 4 < 32 < 10 MW-DN-116-1 05/16/17 < 21 < 33 < 2 < 2 < 6 < 2 < 4 <2 < 5 < 14 < 2 < 2 < 24 < 8 MW-DN-116-1 08/21/17 < 25 < 19 < 2 < 3 < 6 <2 < 5 < 3 < 5 < 13 < 3 < 2 < 21 < 7 MW-DN-116-1 11/07/17 < 50 < 110 < 5 < 4 < 10 < 6 < 11 < 5 < 10 < 12 < 5 < 5 < 32 < 9 MW-DN-116-S 02/14/17 < 28 < 47 < 3 < 3 <7 <3 < 6 < 3 < 5 < 12 < 3 < 3 < 22 < 6 MW-DN-116-S 05/16/17 < 20 < 32 < 2 < 2 <5 <2 < 4 < 2 < 4 < 13 < 2 < 2 < 20 <7 MW-DN-116-S 08/21/17 < 24 < 22 < 2 < 3 < 6 <2 < 5 < 3 < 5 < 14 < 3 < 3 < 25 < 8 MW-DN-116-S 11/07/17 < 64 < 125 < 8 < 7 < 16 <8 < 15 < 8 < 14 < 15 < 7 < 8 < 34 < 12 MW-DN-117-1 02/14/17 < 26 < 63 < 2 < 3 < 6 < 2 < 5 <3 < 5 < 12 < 3 < 3 < 23 < 8 MW-DN-117-1 05/16/17 < 20 < 34 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 13 <2 < 2 < 22 < 6 MW-DN-117-1 08/29/17 < 31 < 27 < 3 < 3 < 7 < 3 < 6 <3 < 6 < 9 < 3 < 3 < 20 < 6 MW-DN-117-1 11/07/17 < 46 < 46 < 5 < 5 < 14 < 6 < 12 <5 < 9 < 11 < 5 < 7 < 30 < 8 III I MW-DN-118-S 02/15/17 < 39 < 83 < 4 < 4 < 10 <4 < 10 <5 < 8 < 15 < 4 < 4 < 34 < 9 O')

MW-DN-118-S 05/17/17 < 18 < 14 < 2 < 2 < 5 < 2 < 4 <2 <4 < 11 < 2 < 2 < 19 < 7 MW-DN-118-S 08/23/17 < 28 < 22 < 3 < 3 <7 <3 < 6 < 3 < 6 < 14 <3 < 3 < 26 <7 MW-DN-118-S 11/08/17 < 71 < 131 < 6 < 6 < 15 <8 < 13 < 6 < 11 < 13 < 8 < 7 < 35 < 12 MW-DN-119-1 05/23/17 < 37 < 37 < 4 < 4 < 9 <4 < 7 < 5 < 8 < 14 < 5 < 4 < 29 < 9 MW-DN-119-1 11/17/17 < 67 < 59 < 6 < 6 < 14 <6 < 13 < 7 < 11 < 14 < 8 < 7 < 35 < 10 MW-DN-119-S 05/23/17 < 42 < 98 < 4 < 5 < 10 <4 < 8 < 5 < 8 < 15 < 5 < 5 < 31 < 12 MW-DN-122-1 05/25/17 < 41 < 35 < 5 < 4 < 11 <5 < 8 <4 < 8 < 15 <4 < 4 < 29 < 11 MW-DN-122-S 05/25/17 < 47 < 91 < 5 < 5 < 11 < 5 < 9 <5 < 9 < 15 < 5 < 5 < 31 < 12 MW-DN-124-1 05/19/17 < 20 < 37 < 2 < 2 < 5 <2 <4 < 2 <4 < 11 < 2 < 2 < 19 < 7 MW-DN-124-1 11/09/17 < 47 < 49 < 5 < 5 < 11 <4 < 10 <5 < 9 < 9 < 6 < 5 < 25 < 6 MW-DN-124-S 05/19/17 < 30 < 27 < 3 < 3 < 6 <3 < 5 <3 < 5 < 15 < 3 < 3 < 28 < 10 MW-DN-124-S 11/09/17 < 70 < 120 < 8 < 8 < 16 <9 < 18 < 8 < 15 < 14 < 9 < 8 < 41 < 13 MW-DN-125-S 05/23/17 < 39 < 72 < 4 < 4 <9 <4 <7 <4 < 7 < 14 < 3 < 4 < 30 <8 MW-DN-126-S 05/24/17 < 51 < 75 < 4 < 5 < 10 < 6 < 12 < 5 < 9 < 14 < 6 < 4 < 32 < 10 MW-DN-127-S 05/19/17 < 24 < 47 < 2 < 3 < 7 <2 <5 < 3 < 5 < 12 < 3 < 2 < 24 < 8 MW-DN-134-S 05/18/17 < 26 < 26 < 3 < 3 < 6 <3 <5 < 3 < 5 < 14 < 3 < 3 < 23 < 7 MW-DN-135-S 05/18/17 < 20 < 33 < 2 < 2 < 5 <2 <4 < 2 < 4 < 12 < 2 < 2 < 20 < 7 MW-DN-136-S 05/18/17 < 23 < 48 < 2 < 2 < 5 <2 <4 < 3 < 4 < 13 < 2 < 2 < 21 < 8 MW-DN-137-S 05/18/17 < 17 < 18 < 2 < 2 < 4 <2 <3 < 2 < 3 < 10 < 2 < 2 < 17 < 6 MW-DN-141-S 05/16/17 < 15 < 24 < 1 < 2 < 4 < 1 <3 < 2 < 3 < 11 < 2 < 1 < 17 < 5 MW-DN-142-S 05/22/17 < 45 < 40 < 5 < 4 < 10 <5 <9 < 5 < 8 < 14 < 5 < 4 < 34 < 12 MW-DN-143-S 05/22/17 < 31 < 33 < 3 < 4 < 8 <4 < 6 < 4 < 6 < 13 < 4 < 3 < 25 < 10 MW-DN-144-S 05/22/17 < 44 73 +/- 47 < 4 < 5 < 11 <4 <9 < 5 < 7 < 15 < 5 < 4 < 28 < 12

TABLE B-1.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-233/234 U-235 U-238 Fe-55 Ni-63 MD-11 02/17/17 < 0.07 < 0.06 < 0.11 < 0.05 < 0.13 < 0.03 < 0.04 < 0.06 < 157 < 3.3 11/09/17 < 0.19 < 0.03 < 0.09 < 0.03 < 0.07 < 0.13 < 0.19 < 0.13 < 133 < 3.4 MW-DN-119-1 05/23/17 < 174 58.9 +/- 3.9 05/23/17 Reanalysis 46.8 +/- 13.5 05/23/17 Reanalysis 45.6 +/- 3.2 05/23/17 Reanalysis 48.0 +/- 7.1 11/17/17 < 0.10 < 0.02 < 0.08 < 0.13 < 0.13 0.84 +/- 0.30 < 0.04 0.44 +/- 0.21 < 187 42.7 +/- 3.3 11/17/17 Recount 46.4 +/- 3.5 11/17/17 Recount 47.3 +/- 11.8 11/17/17 Reanalysis 32.3 +/- 3.5 MW-DN-124-1 05/19/17 < 0.19 < 0.19 < 0.13 < 0.19 < 0.12 < 0.10 < 0.16 < 0.16 < 179 < 4.1 MW-DN-124-S 05/19/17 < 0.1 < 0.13 < 0.05 < 0.13 < 0.03 < 0.11 < 0.05 < 0.04 < 160 < 4.0 CJ I

-...I

TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 DSP-131 02/20/17 284 +/- 133 DSP-131 05/24/17 < 188 DSP-132 02/20/17 463 +/- 141 DSP-132 05/23/17 1740 +/- 236 DSP-133 02/23/17 < 190 DSP-133 05/22/17 < 189 SW-DN-101 02/22/17 < 194 SW-DN-101 05/22/17 < 186 SW-DN-101 09/01/17 < 178 SW-DN-101 11/09/17 696 +/- 144 SW-DN-102 02/22/17 363 +/- 138 SW-DN-102 05/22/17 554 +/- 137 SW-DN-102 09/01/17 962 +/- 161 SW-DN-102 11/09/17 1410 +/- 196 SW-DN-103 02/22/17 356 +/- 132 SW-DN-103 05/22/17 596 +/- 139 SW-DN-103 09/01/17 877 +/- 155 SW-DN-103 11/09/17 1160 +/- 181 SW-DN-104 02/23/17 424 +/- 139 SW-DN-104 05/25/17 566 +/- 137 SW-DN-104 08/30/17 613 +/- 137 SW-DN-104 11/09/17 1280 +/- 193 SW-DN-105 02/23/17 292 +/- 131 SW-DN-105 05/25/17 394 +/- 131 SW-DN-105 08/30/17 287 +/- 120 SW-DN-105 11/09/17 1450 +/- 209 SW-DN-106 02/23/17 292 +/- 131 SW-DN-106 05/22/17 681 +/- 139 SW-DN-106 08/30/17 1000 +/- 164 SW-DN-106 11/09/17 1410 +/- 206 B-8

TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DSP-131 05/24/17 < 43 < 43 <4 <5 < 10 < 5 < 10 <5 < 9 < 14 <5 < 5 < 32 < 10 DSP-132 05/23/17 < 38 < 39 <* 3 <4 < 10 < 3 < 7 <4 <7 < 14 < 5 <4 < 25 < 10 DSP-133 05/22/17 < 49 < 80 <4 <4 < 12 < 5 < 9 < 6 < 9 < 14 <6 < 5 < 34 < 10 SW-DN-101 05/22/17 < 27 < 55 < 3 < 4 <7 < 3 < 6 < 3 < 6 < 12 < 3 < 3 < 22 < 6 SW-DN-102 05/22/17 < 34 < 59 < 3 < 4 < 9 <4 < 8 <4 < 6 < 13 < 3 <4 < 25 < 10 SW-DN-103 05/22/17 < 34 < 82 < 3 < 4 <8 < 3 < 6 <4 < 6 < 15 <4 <3 < 29 < 10 SW-DN-104 05/25/17 < 43 < 98 < 5 < 5 < 12 <4 < 9 < 5 < 8 < 15 < 5 < 5 < 27 < 10 SW-DN-105 05/25/17 < 51 < 41 < 5 < 5 < 12 <5 < 12 <6 < 11 < 15 < 6 < 6 < 41 < 9 SW-DN-106 05/22/17 < 38 < 70 < 4 < 4 <9 < 4 < 8 <4 < 7 < 15 < 4 <4 < 28 < 9 OJ I

co

TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 FW-1 05/15/17 < 177 FW-10 05/23/17 < 177 FW-11 05/17/17 < 175 FW-12 05/24/17 < 178 B-10