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Annual Radiological Environmental Operating Report for 2015
	ML16134A145
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Site:	Dresden
Issue date:	05/05/2016
From:	; Exelon Generation Co, Teledyne Brown Engineering Environmental Services
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
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Docket No: 50-01 O 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Environmental Operating Report 1 January Through 31 December 2015 Prepared By Teledyne Brown Engineering Enviromnental Services

rsar 6 ~~ ExelonGeneration~

Dresden Nuclear Power Station Morris, IL 60450 May 2016

Intentionally left blank Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ..............................................................................*...................................... 6 A. Objectives of the REMP ...................................................................................... 6 B. Implementation of the Objectives ........................................................................ 6 Ill. Program Description ....................................................................................................... 7 A. Sample Collection ............................................................................................... 7 B. Sample Analysis .................................................................................................. 8 C. Data Interpretation ...........................................................................................*.. 9 D. Program Exceptions ............... ,.......................................................................... 10 E. Program Changes ............................................................................................. 14 IV. Results and Discussion ............................................................................................... 14 A. Aquatic Environment ......................................................................................... 14

1. Surface Water. ........................................................................................ 14

2. Ground Water ......................................................................................... 14

3. Fish ......................................................................................................... 15

4. Sediment. ................................................................................................. 15 B. Atmospheric Environment .............. '. .................................................................. 16 1 . Airborne .................................................................................................. 16

a. Air Particulates ............................................................................. 16

b. Airborne Iodine ............................................................................ 17

2. Terrestrial ................................................................................................ 17

a. Milk............................................................................................... 17

b. Food Products ............................................................................. 17 C. Ambient Gamma Radiation ............................................................................... 18 D. Land Use Survey ............................................................................................... 18 E. Errata Data***************************************************~**************************************************** 19 F. Summary of Results - Inter-lab.oratory Comparison Program ........................... 19

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, 2015 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, 2015 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2015 '

Figures Figure B-1 Dresden Station Inner Ring OSLD Locations, Fish, Water, and Sediment Locations, 2015 Figure B-2 Dresden Station Fixed Air Sampling and OSLD Sites, Outer Ring OSLD Locations and Milk Location, 201.5 Appendix*C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of Gross Beta in Surface Water Samples Collected in

the Vicinity of Dresden Nuclear Power Station, 2015.

Table C-1.2 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table C-11 .1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table C-11.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

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Table C-111.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table C-IV.1 *Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015:

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, 2015.

Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table C-Vl.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table C-Vll.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table C-Vll.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table C-Vlll.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table C-IX.1 Quarterly OSLD Results for Dresden Nuclear Power Station, 2015.

Table C-IX.2 Mean Quarterly'OSLD Results for the Inner Ring, Outer Ring, Other and Control Locations for Dresden Nuclear Power Station, 2015.

Table C-IX.3 Summary of the Ambient Dosimetry Program for Dresden Nuclear Power Station, 2015.

Figures Figure C-1 Surface Water - Gross Beta - Station D-52 (C) Collected in the Vicinity

\

of DNPS, 2000 - 2015.

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

Collected in the Vicinity of DNPS, 2003 - 2015.

Figure C-3 Surfa.ce Water - Gross Beta - Stations D-21 and D-51 Collected in the Vicinity of DNPS, 2000 - 201.5.

Figure C-4 Surface Water - Tritium - Station D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2015.

Figure C-5 Surface Water - Tritium - Station D-54 (C) and D-57 (C) Collected in the Vicinity of DNPS, 2003 - 2015. '

Figure C-6 Surface Water - Tritium - Stations D-21 and D-51 Collected in the Vicinity of DNPS, 2000 - 2015.

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Figure C-7 Ground Water - Tritium - Stations D-23 and D-35 Collected in the Vicinity of DNPS, 2000 - 2015.

Figure C-8 Air Particulate - Gross Beta - Stations D-01 and D-02 Collected in the Vicinity of DNPS, 2000 - 2015.

Figure C-9 Air Particulate - Gross Beta ~ Stations D-03 and D-04 Collected in the Vicinity of DNPS, 2000 - 2015.

Figure C-10 Air Particulate - Gross Beta - Stations D-07 and D-12 (C) Collected in the Vicinity of DNPS, 2000 - 2015.

Figure C-11 Air Particulate - Gross Beta - Stations D-45 and D-53 Collected in the Vicinity of DNPS, 2000 - 2015.

Figure C-12 Air Particulate - Gross Beta - Stations D-08 and D-10 Collected in the Vicinity of DNPS, 2005 - 2015.

Figure C-13 Air Particulate - Gross Beta - Stations D-13 and D-14 Collected in the Vicinity of DNPS, 2005 - 2015.

Figure C-14 Air Particulate - Gross Beta - Stations D-55 and D-56 Collected in the Vicinity of DNPS, 2006 - 2015.

Figure C-15 Air Particulate - Gross Beta - Station D-58 Collected in the Vicinity of DNPS, 2011 - 2015.

Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 Table D-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 Table D-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2015 Appendix .E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv

I. Summlry and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Dresden Nuclear Power Station (DNPS) by Exelon covers the period 1 January 2015 through 31 December 2015. During that time period 2,029 analyses were performed on 1,892 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 2015, the Dresden Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 1.71 E+02 curies of fission and activation gasses, 2. 78E+01 curies of Carbon-14 and approximately 1.01 E+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 2015 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 2015 (from 01/01./2015 to 12/31/2015):

UNITS 1,2,3 Total Body: 2.38E-04 mrem Organ: 3.69E-04 mrem UNIT 1 Total Body: N/A Organ: NIA UNIT2 Total Body: 1.20E-06* mrem Organ: 1.20E-06 mrem UNIT3 Total Body: 2.37E-04 mrem Organ: 3.69E-04 mrem The above ann~al 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 2015 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 2015 (from 01/01/2015 to 12/31/2015):

UNITS 1,2,3 Gamma air (fission and activation gases): 3.64E-03 mrad Beta air (fission and activation gases): 9.26E-04 mrad Total Body (noble gases): 2.46E-03 mrem Skin (noble gases): 4.34E-03 mrem Organ - thyroid (radioiodines/tritium/particulates): 2.0QE-01 mrem UNIT 1 Gamma air (fission and activation gases): N/A Beta air (fission and activation gases): NIA Total Body (noble gases): N/A Skin (noble gases): N/A Organ - liver (radioiodines/tritium/particulates): 2.71 E-03 mrem UNIT2 Gamma air (fission and activation gases): 9.71 E-04 mrad Beta air (fission and activation gases): 3. 71 E-04 mrad Total Body (noble gases): 6.65E-04 mrem Skin (noble gases): 1.20E-03 mrem Organ - thyroid (radioiodines/tritium/particulates): 9.26E-02 mrem UNIT3 Gamma air (fission and activation gases): 2.67E-03 mrad Beta air (fission and activation gases): 5.55E-04 mrad Total Body (noble.gases): 1.79E-03 mrem Skin (noble gases): 3.15E-03 mrem Organ - thyroid (radioiodines/tritium/particulates): 1.0BE-01 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 2015 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 2015 (from 01/01/2015 to 12/31/2015):

UNITS 1,2,3 Total Body (skyshine): 8.64E+OO mrem

UNIT 1 Total Body (skyshine): N/A

.UNIT2 Total Body (skyshine): 4.19E+OO mrem UNIT3 Total Body (skyshine): 4.45E+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 2015 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 1O kilometers (6.2miles).

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 1

a significant period of time is issued an Optical Stimulated Luminescent Dosimeter (OSLO) to monitor direct radiation exposure.

7. Liquid arid Gaseous Effluent Radiation Monitors and Instrumentation Unavailability for the Period Beyond the Requirements of the ODCM, Including Sampling Deviation: None

8. 40CFR190 / 1OCFR72 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 2.05E-01 mrem organ .dose and 8.64E+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 2015. REMP direct radiation monitoring at or near the site boundary demonstrates that the ISFSls do not result in measurable dose to the public.

According to the 2015 GEH Morris Operation 1OCFR72.44(d)(3) report, dated 2/22/2016, for the 2015 calendar year, the maximum dose at their site boundary from direct radiation exposure was 4.11 E-01 mrem. The maximum organ dose from site activities was 1.33E-02 mrem for 2015.

Maximum combined total body dose from Dresden Station and GEH Morris Operation activities was 9.27E+OO mrem during 2015, which was 37.09 % of the 40CFR190 limit of 25 mrem.

Maximum combined organ dose from Dresden and GEH Morris Operation activities was 2.18E-01 mrem during 2015. This was 0.87 % of the 40CFR190 limit of 25 mrem to any organ. The combined thyroid dose was 2.13E-01 mrem. This was 0.28 % of the 40CFR190 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 not detected in 2015.

No fission or activation products were found in sediment.

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

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

Cow milk samples were analyzed for concentrations of 1-131.and gamma emitting nuclides due to the cows being sold. 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). Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry were deployed and Thermoluminescent Dosimetry (TLD) were discontinued. This change may result in a step change in readings, up or down, depending on site characteristics. The relative comparison to control locations remains valid.

OSLD technology is different than that used in a TLD but has the same purpose (to measure direct radiation).

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 2015 through 31 December 2015.

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 res.ult of the 40CFR190 uranium fuel cycle dose analysis for the calendar year are published in the station's Annual Radioactive Effluent Release Report.

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

The objectives of the REMP are to:

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

2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of expos1.Jr~.

B. Implementation of the Objectives

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The implementation of the objectives is accomplished by:

1. Identifying significant exposure pathways.

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

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

Ill. Program Description A. Sample Collection Samples for the DNPS REMP were collected for Exelon Nuclear by Environmental Incorporated Midwest Laboratory (EIML). This section describes the general collection methods used by EIML to obtain environmental samples for the ONPS REMP in 2015. Sample locations and descriptions can be found in Appendix 8, Table 8-1 and Figures 8-1 and 8-2. The collection methods used by EIML are listed in Table 8-2.

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, 0-52 and D-57) and composited for analysis. Control locations were 0-52 and 0-57. Samples were collected quarterly or more frequently from two well water locations (0-23 and 0-35). All samples were collected in new unused plastic bottles, which were rinsed with source water prior to collection. Fish samples comprising the flesh of common carp, river carpsucker, largemouth bass, channel catfish, and smallmouth buffalo 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 (0-01, D-02, 0-03, 0-04, D-07, 0-08, 0-10, 0-12, 0-14, 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 1O km (6.2 miles) of the site. All milk samples from D-25 were collected in

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

Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLO) were deployed and Thermoluminescent Dosimetry {TLD) were discontinued. This change may result in a step change in readings, up or down, depending on site characteristics. The relative comparison to control locations remains valid. OSLO technology is different than that used in a TLD but has the same purpose (to measure direct 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 (3.1to6.2 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, D-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 and EIML to analyze the environmental samples for radioactivity for the DNPS REMP in 2015. The analytical procedures used by the laboratories are listed in Appendix B Table B-2.

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

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

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

3. *Concentrations of tritium in ground and surface water.

4. I 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 presen*ce 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,

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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.

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 2015 the DNPS REMP had a sample recovery rate of approximately 98%, Sample anomalies and missed samples are listed in the tables below:

Table D-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection* Reason Type Code Date AP/I 0-01, 02, 03, 06/26/15 Low readings due to power 04,07,08, 10 outages from storms in area.

AP/I 0-53 07/03/15 No apparent reason for low reading of 153.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SW 0-21 07/31/15 Compositor out-of-service; grab sample taken.

AP/I D-01 08/14/15 Low reading of 1.49.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months due to timer malfunction; timer replaced.

AP/I 0-01 08/21/15 Low reading of 140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months ; pump found not running. Pump restarted itself while collector was present.

Collector let pump run for 20 minutes before leaving site.

-

Table D-1 LISTING OF SAMPLE ANOMALIES (continued)

Sample Location Collection Reason Type Code Date AP/I *D-04 08/21/15 Charcoal cartridge from D-04 (08/07/15 to 08/14/15) found in D-01 holder. Charcoal was inadvertently placed back in field at D-01 on 08/14/15. Two week runtime of 335 hours0.00388 days 0.0931 hours 5.539021e-4 weeks 1.274675e-4 months . EIML Non-conformance report #58 generated.

AP/I D-01 08/28/15 No apparent reason for low reading of 155.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

AP/I D-:03 09/04/15 No apparent reason for low reading of 155.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months AP/I D-07 09/04/15 Pump found off but warm; full collection period on timer and filter appeared to have similar particulate collection to other locations.

=

Estimated flow rate 60 cfh for calculations. Pump replaced.

AP/I D-02 10/23/15 T!mer malfunction; collector replaced timer. Estimated time@

16'7.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months based on previous weeks' time.

AP/I D-08 11/13/15 No power to sampler; wire detached due to storms/high winds; POC*

=

notified. Estimated flow rate 60 cfh for calculations based on previous 4 weeks' readings.

POC = Point of Contact (Dresden ODCM Chemist)

AP/I D-10 11/13/15 Low reading of 160.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months possibly due to power outages from storms/high winds in the _area.

AP/I D-08 11/27/15 Low reading of 163.0 hours0 days 0 hours 0 weeks 0 months due to recent power restoration.

Table D-1 LISTING OF SAMPLE ANOMALIES (continued}

Sample Location Collection Reason Type Code Date AP/I D-04 12/26/15 Pump malfunction; estimated flow rate of 60 cfh based on previous 4 weeks' readings.

Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Tyµe Code Date M D-25 01/01/15- No samples; farmer sold cows.

03/31/15 OSLO D-116-2 01/09/15 OSLO found missing during quarterly exchange*. Collector 51 placed new 1 quarter OSLO.

Reported as missed sample in 2014 AREOR.

OSLO D-104-1 06/05/15 OSLO found missing during monthly check. Collector placed Spare

2307.

OSLO D-111-1 07/03/15 OSLDs found missing during 201-1 .quarterly exchange. Collector placed new 3rd quarter OSLDs.

osLD D-206-1 07/03/15* OSLO lost in transit to vendor for analysis.

AP/I D-53 07/31/15 Low reading of 158.5 due to power outage. ComEd working at substation; power turned off.

AP/I 0 .. 04 08/14/15 Charcoal found missing during shipment. Charcoal located on 08/21/15 (see below).

Table D-2 LISTING OF MISSED SAMPLES <continued)

Sample Location Collection Reason Type Code Date AP/I D-01 08/21/1.5 Collector found charcoal cartridge from D-04 (08/07/15 to 08/14/15) in holder at D-01; no sample for week for D-01 cartridge. EIML on-conformance report #58 generated.

AP/I D-03 09/11/15 AP filter found white; hose found disconnected. No flow through sampler for week. Timer malfunction; timer replaced.

VE D-QUAD-2, 3, 09/24/15 After diligent search of quadrants, Control no root or broad leaf vegetables available.

AP/I D-03 10/30/15 Pump running in reverse; particulate matter on inside of filter and charcoal; Estimated flow of 60 cfh.

OSLO D-209-2 11/06/15 OSLO found missing during monthly visual check. Collector placed spare #1 000097492 Ex000683145.

AP/I D-08 11/20/15 No power to sampler; POC* notified.

POC = Point of Contact (Dresden ODCM Chemist)

M D-25 . 12/04/15 Farmer not milking at this time; no sample available.

OSLO D-07-2, 12/29/15 OSLDs found missing during D-203-2 quarterly exchange. Collector placed new 1st quarter OSLDs.

Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent.recurrence. Occasional equipment breakdowns and power outages were unavoidabl~.

The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

E. Program Changes There were no program changes in 2015.

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 33 of 36 samples. The values ranged from 3.5 to 13.2 pCi/I. Concentrations detected were consistent with those detected in previous years (Figures C-1, C-2 and C-3, Appendix C).

Tritium Quarterly composites from all locations were analyzed for tritium activity (Table C-1.2, Appendix C). Three samples at indicator station D-21 were positive for tritium at concentrations ranging from 211 to 419 pCi/L. Four samples at control station D-57 were positive for tritium. The values ranged from 639 to 1,680 pCi/L.

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

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

2. Ground Water Quarterly or more frequent grab samples were collected at two

locations (D-23 and D-35). These locations could be affected by Dresden's effluent releases and by sources upstream on the Kankakee River. The following analyses were performed:

Tritium

. All samples were analyzed for tritium activity (Table C-11.1, Appendix C). Tritium was detected in 12 of 16 samples. The concentrations ranged from 359 to 577 pCi/I. 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 common carp, river carpsucker, largemouth bass, channel catfish, and smallmouth buffalo were collected at two locations (D-28 and D-46) semiannually. Location D-28 could be affected by Dresden's effluent releases. The following analysis was performed:

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

Naturally occurring K-40 was found at 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 emitting nuclides (Table C-IV.1, Appendix C). No fission or activation products were detected.

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 ran~ed from 6 to 38 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m . The results from the Near-Field locations ran~ed from 6 to 38 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m . *The results from 3

the Far-Field locations ranged from 6 to 36 E-3 pCi/m with a 3

mean of 17 E-3 pCi/m . The results from the Control 3

location ranged from 7 to 31 E-3 pCi/m with a mean of 16 3

E-3 pCi/m . Comparison of the 2015 air particulate data with previous years data indicate no effects from the operation of DNPS. In addition a comparison of the weekly mean values for 2015 indicate no notable differences among the four groups (Figures C-8 through C-14, Appendix C).

Gamma Spectrometry Samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C).

Naturally occurring Be-7 was detected at levels consistent with previous years. 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, 0-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55, D-56 and D-58) and analy~ed weekly for 1-131 (Table C-VI .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-VI 1.2, Appendix C).

Naturally occurring K-40 activity was 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) when available. Four locations, (D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4) could be affected by Dresden's effluent releases. The following analysis was performed:

Gamma Spectrometry Samples from two locations were analyzed for gamma emitting nuclides (Table C-VI 11.1, Appendix C). No nuclides were detected and all required LLDs were met.

C. Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLO) were deployed and Thermoluminescent Dosimetry (TLD) were discontinued. This change may result in a step change in readings, up or down, depending on site characteristics. The relative comparison to control locations remains valid. OSLO technology is different than that used in a TLD but has *the same purpose (to measure direct 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 20.1 to 41.6 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-12-01and D-12-02}were comparable.

D. Land Use Survey A Land Use Survey conducted on August 22, 2015 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 1O km (6.2 miles) around the site. There were no changes required to the DNPS REMP as a result of this survey. The results of this survey are summarized below.

Distance in Miles from the DNPS Reactor Buildings Sector Residence Livestock Milk Farm Miles Miles Miles AN 1.5 1.4 BNNE o.8 6~o CNE 0.8 5.8 DENE 0.7 1.7 EE 1.1 FESE 1.0 GSE 0.6 HSSE 0.5 JS 0.5 16.0 KSSW 3.3 LSW 3.6 11.4 MWSW 5.8 NW* 3.5 0.5 PWNW 3.7 0.5 QNW 2.6 0.5 E. Errata Data There is no errata data for 2015.

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

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

2.

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

limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

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

The MAPEP defines three levels of performance: Acceptable

(flag "A"), Acceptable with Warning (flag "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% <bias< 30%). If the bias is greater than 30%, the results are deemed not acceptable.

For the TBE laboratory, 129 out of 139 analyses performed met the specified acceptance criteria. Ten analyses (AP - Cr-51, U-234/233, Gr A, Sr-90; Soil Sr-90; Water- Ni-3, Sr-89, Sr-90, U natural; Vegetation Sr-90 samples) did not meet the specified acceptance criteria for the following reasons:

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.

1. Teledyne Brown Engineering's Analytics' June 2015 air particulate Cr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio of 1.30 (acceptable with warning) was exceeded. The air particulate sample is counted at a distance above the surface of the detector to avoid detector summing which could alter the results. Chromium-51 has the shortest half-life (27.7 days) and the lowest gamma energy (320.08 keV) of this mixed nuclide sample. Additionally, Cr-51 has only one gamma energy and also has a low intensity (9.38 gamma photons produced per 100 disintegrations). This geometry produces a larger error for the Cr-51 and other gamma emitters as any distance from the detector decreases the counting rate and the probability of accurately detecting the nuclide energy. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would statistically be considered acceptable. NCR 15-18

I

2. Teledyne Brown Engineering's MAPEP March 2015 soil Sr-90 result of 286 Total Bq/kg was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. Incomplete digestion of samples causes some of the sample to be left behind and is not present in the digested sample utilized for analysis. The procedure has been updated to include a more robust digestion using stirring during the heating phase. The MAPEP September 2014 soil Sr-90 series prior to this study was evaluated as acceptable with a result of 694 and an acceptance range of 601 -

1115 Bq/kg. The MAPEP September 2015 series soil Sr-90 after this study was evaluated as acceptable with a result of 429 and an acceptance range of 298 - 553 Bq/kg. We feel the issue is specific to the March 2015 MAPEP sample. NCR 15-13

3. Teledyne Brown l;:ngineering's MAPEP March 2015. air particulate U-234/233 result of 0.0211. +/- 0.0120 Bq/sample was higher than the known value of 0.0155 Sq/sample, exceeding the upper acceptance range of 0.0202 Sq/sample. Although evaluated as a failure, taking into consideration the uncertainty, TBE's result would overlap with the known value, which is statistically considered acceptable. MAPEP spiked the sample with significantly more U-238 activity (a found to known ratio of 0.96) than the normal U-234/233. Due to the extremely low activity, it was difficult to quantify the U-234/233. NCR 15-13

4. Teledyne Brown Engineering's MAPEP March 2015 air particulate gross alpha re~ult of 0.448 Bq/sample was lower than the known value of 1. 77 Sq/sample, exceeding the lower acceptance range of 0.53 Sq/sample. The instrument efficiency used for gross alpha is determined using a non-attenuated alpha standard. The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency. When samples contain alpha particles that are embedded in the sample media, due to the size of the alpha .

particle, some of the alpha particles are absorbed by the media and cannot esc;:ape to be counted. When the sample media absorbs the alpha particles this is known as self-absorption or attenuation.

The calibration must include a similar configuration/media to correct for the attenuation. In order to correct the low bias, TBE will create an attenuated efficiency for MAPEP air particulate filters.

The MAPEP September series air particulate gross alpha result of 0.47 Sq/sample was evaluated as acceptable with a range of 0.24

- 1.53 Bq/sample. Unlike the MAPEP samples, air particulate Gross alpha analyses for power plants are not evaluated as a direct count sample. Power plant air particulate filters for gross

alpha go through an acid digestion process prior to counting and the digested material is analyzed. NCR 15-13

5. Teledyne Brown Engineering's MAPEP September water Ni-63 result of 11.8 +/- 10.8 Bq/l was higher than the known value of 8.55 Bq/l, exceeding the upper acceptance range of 11.12 Bq/L. The Ni-63 half-life is approximately 100 years. Nickel-63 is considered to be a "soft" or low energy beta emitter, which means that the beta energy is very low. The maximum beta energy for Ni-63 is approximately 65 keV, much lower than other more comm.on nuclides such as Co-60 (maximum beta energy of 1549 keV). The original sample was run with a 10 ml aliquot which was not sufficient for the low level of Ni-63 in the sample. The rerun aliquot of 30 ml produced an acceptable result of 8.81 Bq/L. NCR 15-21

6. Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Bq/sample was lower than the known value of 2.18 Bq/sample, exceeding the lower acceptance range of 1.53 Bq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that*

have resulted in incomplete removal of the isotope of interest for the laboratories analyzing the cross checks. TBE suspects that this may be the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause -

interferences to either indicate lower activity or higher activity. TBE will no longer analyze the air particulate Sr-90 through MAPEP but will participate in the Analytics cross check program to perform both Sr-89 and Sr-90 in the air particulate matrix. NCR 15-21

7. Teledyne Brown Engineering's MAPEP September vegetation Sr-90 result of 0.386 Bq/sample was lower than the known value of 1.30 Bq/sample, exceeding the lower acceptance range of 0.91 Bq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for the laboratories analyzing the cross checks. TBE suspects that this maybe the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity.

Results from previous performance evaluations were reviewed and shown to be acceptable. NCR 15~21

8. & 9.Teledyne Brown Engineering's ERA May water Sr-89/90 results of 45.2 and 28.0 pCi/l, respectively were lower than the known values of 63.2 and 41.~ pCi/l, respectively, exceeding the lower acceptance limits of 51.1 and 30.8 pCi/L, respectively. The yields

were on the high side of the TBE acceptance range, which indicates the present of excess calcium contributed to the yield, resulting in low results. NCR 15-09

10. Teledyne Brown Engineering's ERA November water Uranium natural result of 146.9 pCi/l was higher than the known value of 56.2 pCi/l, exceeding the upper acceptance limit of 62.4 pCi/L.

The technician failed to dilute the original sample, but used the entire 12 ml sample. When the results were recalculated without the dilution and using the 12 ml aliquot, the result of 57 .16 agreed with the assigned value of 56.2. NCR 15-19

Intentionally left blank

'

I APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

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

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2015 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER GR-B 36 4 6.4 7.4 8.9 D-52 CONTROL 0 (PCI/LITER) (12/12) (21/24) (11/12) DESPLAINES RlVER - UPSTREAM (3.5/9.8) (3.7/13.2) (6.3/11.6) 1.1 MILES ESE OF SITE H-3 12 2000 292 1159 1159 D-57 CONTROL 0 (3/4) (4/8) (4/4) KANKAKEE RNER AT WILL ROAD( CONTROL)

(211/419) (639/1680) (639/1680) 2.0 MILES SE OF SITE GAMMA 36

>

......

I MN-54 15 <LLD <LLD 0 C0-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 C0-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 NB-95 15 <LLD <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2015 NAMEOFFACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN(M) MEAN (M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER ZR-95 30 <LLD <LLD 0 (PCI/LITER)

I-I31 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 16 2000 477 NA 477 D-23 INDICATOR 0 (PCI/LITER) (12116) (12/12) THORSEN WELL (359/577) (359/577) 0.7 MILES S OF SITE GAMMA 16 MN-54 15 <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2015 NAMEOFFACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATIONOFFACILITY: MORRIS IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL . LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN(M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER C0-58 15 <LLD NA 0 (PCI/LITER)

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 1-131 15 <LLD NA 0 CS-134 15 <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2015 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATIONOFFACILITY: MORRIS IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

{UNITOF PERFORMED PERFORMEP OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER CS-137 18 <LLD NA 0 (PCULITER)

BA-140 60 <LLD NA 0 LA-140 15 <LLD NA 0 FISH GAMMA 8 (PCI/KG WET) MN-54 130 <LLD <LLD 0 C0-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 C0-60 130 <LLD <LLD 0 ZN-65 260 <LLD <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2015 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

ZR-95 NA <LLD <LLD 0 CS-134 130 <LLD <LLD 0 CS-137 150 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 SEDIMENT GAMMA 2 (PCJ/KG DRY) MN-54 NA <LLD NA 0 C0-58 NA <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2015 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATIONOFFACILITY: MORRIS IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT FE-59 ' NA <LLD NA 0 (PCI/KG DRY)

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 <LLD NA 0 BA-140 NA <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2015 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN(M) MEAN (M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT LA-140 NA <LLD NA 0 (PCI/KG DRY)

AIR PARTICULATE GR-B 724 10 17 16 18 D-08 INDICATOR 0 (E-3 PCI/CU.METER) (671/672) (52/52) (50/51) PRAIRIE PARK (6/38) (7/31) (7/35) 3.8 MILES SW OF SITE GAMMA 56

>I

-.J MN-54 NA <LLD <LLD 0 C0-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0 AIR PARTICULATE ZN-65 NA <LLD <LLD 0 (E-3 PCI/CU.METER)

NB-95 NA <LLD <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2015 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATIONOFFACILITY: MORRIS IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT {F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE ZR-95 NA <LLD <LLD 0 (E-3 PCI/CU.METER)

CS-134 50 <LLD <LLD 0 CS-137 60 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 AIR IODINE GAMMA 724 (E-3 PCI/CU.METER) 1-131 70 <LLD <LLD 0 MILK I-131 17 NA NA <LLD 0 (PCI/LITER)

GAMMA 17 MN-54 NA NA <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2015 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK C0-58 NA NA <LLD 0 (PCIILITER)

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 60 NA <LLD 0 CS-137 80 NA <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2015 NAME OF FACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN(M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK BA-140 NA NA <LLD 0 (PCI/LITER)

LA-140 NA NA <LLD 0 VEGETATION GAMMA 4

~

,_. (PCI/KG WET) MN-54 NA <LLD <LLD 0 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

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2015 NAMEOFFACILITY: DRESDEN DOCKET NUMBER: 50-010 50-237 & 50-249 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION ZR-95 NA <LLD <LLD 0 (PCIIKGWED I-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0 CS-137 80 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 DIRECT RADIATION OSLD-QUARTERLY 361 NA 28.9 27.1 34.J D-215-1 INDICATOR 0 (MILLIREM/QTR.) (353/353) (8/8) (4/4)

(20.1/41.6) (24.1/32.9) (30/41.4) 4.8MILESNW

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

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

Intentionally left blank TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2015 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) 0.8miles NW C. Milk - bi-weekly I monthly D-25 Biros Farm (control) 11.4 miles SW D. Air Particulates I Air Iodine D-01 Onsite Station 1 (indicator) 0.8miles NW D-02 Onsite Station 2 (indicator) 0.3 miles NNE D-03 Onsite Station 3 (indicator) 0.4miles S D-04 Collins Road, on Station property(indicator) 0.8milesW D-07 Clay Products, Dresden Road (indicator) 2.6miles S D-08 Jugtown Road, Prairie Parks (indicator) 3.8miles SW D-10 Goose Lake Road, Goose Lake Village (indicator) 3.5miles SSW D-12 Quarry Road, Lisbon (control) 10.5 miles NW D-14 Center Street, Channahon (indicator) 3.7miles NE D-45 McKinley Woods Road, Channahon (indfcator) 1.7miles ENE D-53 Will Road, Hollyhock (indicator) 2.1 miles SSE D-55 Ridge Road, Minooka (indicator) 4.3miles N D-56 Will Road, Wildfeather (indicator) 1.7miles SE D-58 Will Road, Marina (indicator) 1.1 miles ESE E. Fish D-28 Dresden Pool of Illinois River, Downstream (indicator) 0.9miles 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 Chris Locknar 2.8miles NE Quadrant 2 Robert Pagliano 3.2miles SSE Quadrant 3 Jim Bloom 3.9milesSSW Quadrant 4 J.D. Carmichael 1.6 miles NNW Control Glasscock Farm 12.8 miles ENE B-1

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2015 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - OSLD 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 1.3miles NNE D-103-1 and -2 1.2miles 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 1.4miles SE D-108-1 and -2 1.9miles SSE D-109-1 and -2 0.8miles S D-110-3 and -4 0.9 miles SSW D-111-1 and -2 0.6miles SW D-112A-1 and-2 0.7 miles WSW D-113-1 and-2 0.9 miles W D-114-1 and -2 0.9milesWNW D-115-1 and-2 0.8miles NW D-116-1 and -2 1.0miles 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 4.9miles SSW D-211-1 and-2 4.8miles SW D-212-3 and -4 6.0milesWSW D-213-1 and -2 4.5miles W D-214-1 and -2 5.0milesWNW D-215-1 and -2 4.8miles NW D-216-1 and -2 4.9miles NNW Other Locations D-01-1 and -2 Onsite 1 0.8miles 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 0.8milesW D-07-1 and -2 Clay Products, Dresden Road 2.6 miles S D-08-1 and -2 Jugtown Road, Prairie Parks 3.8 miles SW D-10-1 and -2 Goose Lake Road, Goose Lake Village 3.5miles 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, 2015 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Water Gamma Spectroscopy Monthly composite EIML-SPM-1, Environmental Incorporated 2gallon TBE, TBE-2007 Gamma emitting sample or monthly Midwest Laboratory Sampling Procedures radioisotope analysis composite from weekly Manual grab samples.

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

TBE, TBE-2023 Compositing of samples EIML-COMP-01 procedure for compositing water and milk samples Surface Water Tritium Quarterly composite of EIML-SPM-1, Environmental Incorporated 500 ml TBE, TBE-2011 Tritium analysis in monthly composite Midwest Laboratory Sampling Procedures drinking water by liquid scintillation samples. Manual TBE, TBE-2023 Compositing of samples EIML-COMP-01 procedure for compositing water and milk samples Ground Water Gamma Spectroscopy Quarterly grab samples. EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting Midwest Laboratory Sampling Procedures radioisotope analysis Manual Ground Water Tritium Quarterly grab samples. EIML-SPM-1, Environmental .Incorporated 500ml TBE, TBE-2011 Tritium analysis in Midwest Laboratory Sampling Procedures drinking water by liquid scintillation Manual Fish Gamma Spectroscopy Samples collected twice EIML-SPM-1, Environmental Incorporated 1000 grams (wet) TBE, TBE-2007 Gamma emitting annually via Midwest Laboratory Sampling Procedures radioisotope analysis electroshocking or other Manual techniques Sediment Gamma Spectroscopy Semi-annual grab EIML-SPM-1, Environmental Incorporated 500 grams (dry) TBE, TBE-2007 Gamma emitting samples Midwest Laboratory Sampling Procedures radioisotope analysis Manual

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2015 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Dredging Spoils Gamma Spectroscopy Annual grab samples if EIML-SPM-1, Environmental Incorporated 500 grams (dry) TBE, TBE-2007 Gamma emitting dredging occurred Midwest Laboratory Sampling Procedures radioisotope analysis within 1 mile of Dresden Manual Station during the year.

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

Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting each station radioisotope analysis Env. Inc., AP-03 Procedure for compositing air particulate filters for gamma spectroscopic analvsis Air Iodine Gamma Spectroscopy One- or two-week EIML-SPM-1, Environmental Incorporated 1 filter (approximately TBE, TBE-2007 Gamma emitting composite of continuous Midwest Laboratory Sampling Procedures 280 cubic meters radioisotope analysis air sampling through Manual weekly) charcoal filter Milk 1-131 Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2012 Radioiodine in various May through October. Midwest Laboratory Sampling Procedures matrices Monthly all other times Manual Milk Gamma Spectroscopy Bi-weekly grab sample EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting May through October. Midwest Laboratory Sampling Procedures radioisotope analysis Monthly all other times Manual Food Products Gamma Spectroscopy Annual grab samples. EIML-SPM-1, Environmental Incorporated 1000 grams TBE, TBE-2007 Gamma emitting Midwest Laboratory Sampling Procedures radioisotope analysis Manual OSLO Optically Stimulated Quarterly OSLDs EIML-SPM-1, Environmental Incorporated 2 dosimeters at each Landauer Incorporated Luminescence comprised of two Midwest Laboratory Sampling Procedures location Dosimetry Al20a:C Landauer Manual Incorporated elements.

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APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

Intentionally left blank Table C-1.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION D-21 D-52 D-57 PERIOD 01/02115 - 01/30/15 5.9 +/- 2.1 6.8 +/- 2.2 3.8 +/- 1.8 02/06/15 - 02127/15 4.9 +/- 2.0 9.4. +/- 2.7 13.2 +/- 2.8 03/06/15 - 03/27/15 5.1 +/- 2;4 8.0 +/- 2.9 < 2.9 04/02115 - 04/24/15 7.0 +/- 2.2 8.8 +/- 2.5 3.7 +/- 1.9 05/01/15 - 05/29/15 8.3 +/- 2.6 10.7 +/- 3.1 4.6 +/- 2.3 06/05/15 - 06/26/15 6.1 +/- 1.8 7.3 +/- 2.7 4.5 +/- 2.0 07/03/15 - 07/31/15 4.8 +/- 2.0 (1) 9.0 +/- 2.4 < 2.3 08/07/15 - 08/28/15 9.7 .+/- 2.7 10.0 +/- 2.7 6.7 +/- 2.4 09/04/15 - 09/25/15 6.7 +/- 2.0 6.3 +/- 2.0 6.9 +/- 2.1 10/02/15 - 10/30/15 9.8 +/- 2.6 11.6 +/- 2.7 4.6 +/- 2.2 11/06/15 - 11/27/15 3.5 +/- 1.7 10.1 +/- 2.6 4.8 +/- 2.1 12104/15 - 12/26/15 4.8 :i: 1.9 < 2.8 4.5 +/- 2.0 MEAN 6.4 +/- 4.2 8.9 +/- 3.4 5.9 +/- 5.8 Table C-1.2 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION D-21 D-52 D-57 PERIOD 01/02115 - 03/27/15 211 +/- 133 < 199 1670 +/- 227 04/02115 - 06/26/15 < 186 < 188 639 +/- 150 07/03/15 - 09/25/15 247 +/- 133 < 199 646 +/- 158 10/02115 - 12126/15 419 +/- 142 < 195 ' 1680 +/- 235 MEAN 292 +/- 222 1159 +/- 1192 THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1

Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-21 12/26/14 - 01/30/15 < 5 < 5 < 10 <5 <9 <5 < 8 < 12 <4 <4 < 29 <9 01/30/15 - 02/27/15 < 4 <4 <7 <4 <7 <4 < 8 <9 <4 <4 < 22 <6 02127/15 - 03/27/15 < 2 <2 <4 <2 <3 <2 < 3 < 12 < 2 < 2 < 19 < 5 03/27/15 - 04/24/15 < 3 <3 < 8 <3 <6 <3 <6 < 13 <3 < 3 < 25 <8 04/24/15 - 05/29/15 < 2 <2 <4 <2 <3 < 2 < 3 <6 <2 <2 < 12 < 5 05/29/15 - 06/26/15 < 4 < 5 < 10 <4 < 5 <4 <8 < 10 <5 <4 < 25 <8 06/26/15 - 07/31/15 (1) <4 < 5 < 11 <6 < 11 <6 < 9 < 12 < 5 <5 <"29 < 8 07/31/15 - 08/28/15 < 7 <5 < 21 < 10 < 15 <9 < 14 < 11 <6 < 6 < 44 <4 08/28/15 - 09/25/15 < 7 <8 < 13 <8 < 15 <8 < 12 < 12 <7 < 7 < 37 < 14 09/25/15 - 10/30/15 <4 <3 < 8 <4 <8 <4 < 6 <8 < 3 <3 < 21 <8 10/30/15 - 11/27/15 <4 <4 < 8 <4 < 9 <5 < 9 < 10 <4 <5 < 28 <6 11/27/15 - 12/26/15 <4 <5 < 8 <4 < 8 <5 <7 < 14 <5 <4 < 33 < 10

()

I MEAN N

D-52 01/02115 - 01/30/15 <4 <4 < 9 <4 <5 .< 4 <7 < 10 < 3 < 4 < 25 <7 02/06/15 - 02127/15 <4 < 3 <7 <3 <7 < 4 < 7 <8 <3 <4 < 17 <5 03/06/15 - 03/27/15 <2 <2 <4 <2 <3 <2 <4 < 13 <2 <2 < 21 <6 04/02/15 - 04/24/15 <2 <2 <6 <2 <5 <2 <4 < 11 <2 <2 < 19 <7 05/01/15 - 05/29/15 <2 <2 <5 <2 <5 <2 <4 <8 <2 <2 < 14 < 5 06/05/15 - 06/26/15 <4 <4 < 13 <4 < 11 <7 < 10 < 12 < 5 < 5 < 37 <6 07/03/15 - 07/31/15 <6 <6 < 13 <6 < 12 < 6 <9 < 12 < 5 <6 < 31 < 11 08/07/15 - 08/28/15 <5 < 8 < 17 < 8 < 11 < 7 < 12 < 12 <7 <6 < 26 < 12 09/04/15 - 09/25/15 < 8 < 7 < 13 <6 < 17 < 8 < 12 < 13 <7 <7 < 34 < 14 10/02/15 - 10/30/15 <5 <5 < 10 <5 <9 <5 < 9 < 10 <5 <4 < 27 <8 11/06/15 - 11/27/15 <4 <4 <9 <4 <9 <5 < 8 < 11 <4 <4 < 23 < 7 12/04/15 - 12/26/15 <4 <3 <9 <4 <7 <4 < 8 < 12 <4 <4 < 25 <8 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-57 12/26/14 - 01/30/15 <3 <5 < 11 <5 < 10 <4 < 9 < 12 < 5 <4 < 26 <9 01/30/15 - 02/27/15 <5 <5 < 10 <4 < 9 <5 < 9 < 12 <4 <5 < 26 < 9 02/27/15 - 03/27/15 < 1 < 2 <4 < 1 < 3 <2 < 3 < 10 < 1 < 1 < 15 < 5 03/27/15 - 04/24/15 < 3 <4 <7 <3 <6 <3 <6 < 14 < 3 <3 < 29 < 9 04/24/15 - 05/29/15 <2 <2 <6 <2 < 5 <3 <4 <7 < 2 < 2 < 16 <6 05/29/15 - 06/26/15 <6 <7 < 15 <7 < 16 <7 < 12 < 15 < 6 < 8 < 39 < 14 06/26/15 - 07/31/15 <4 <4 <9 <4 <9 <5 <7 <8 <4 <4 < 21 <7 07/31/15 - 08/28/15 <7 < 7 < 13 <6 < 11 <8 < 11 < 12 < 5 <6 < 34 < 11 08/28/15 - 09/25/15 < 6 <8 <9 <4 < 12 <6 < 13 < 10 < 5 <6 < 34 < 10 09/25/15 - 10/30/15 <4 <4 <7 <4 < 7 <4 <7 < 10 <4 <4 < 22 <6 10/30/15 - 11/27/15 <4 <5 < 10 <6 < 10 <6 < 10 < 13 < 5 < 5 < 32 < 11 11/27/15 - 12/26/15 <4 <6 < 12 < 6 < 11 <6 < 10 < 14 <4 <6 < 36 < 12

()

I MEAN

\;.)

Table C-11.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION D-23 D-35 PERIOD 01/09/15 - 01/09/15 429 +/- 119 < 156 02/13/15 - 02/13/15 480 +/- 141 03/13/15 - 03/13/15 489 +/- 142 04/10/15 - 04/10/15 433 +/- 146 < 195 05/06/15 - 05/06/15 496 +/- 145 06/12/15 - 06/12/15 536 +/- 135 07110/15 - 07/10/15 505 +/- 146 < 198 08/14/15 - 08/14/15 483 +/- 137 09/11/15 - 09/11/15 406 +/- 131 10/09/15 - 10/09/15 528 +/- 148 < 198 11/13/15 - 11/13/15 359 +/- 142 12/11/15 - 12/11/15 577 +/- 141 MEAN 477 +/- 122 THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-4

Tables C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-23 01/09/15 - 01/09/15 < 10 < 9 < 24 < 9 < 17 < 10 < 20 < 12 < 8 < 10 < 48 .< 14 02/13/15 - 02/13/15 < 3 < 4 < 8 < 3 < 7 < 4 < 8 < 12 < 5 < 5 < 26 < 4 03/13/15 - 03/13/15 < 8 < 6 < 16 < 7 < 16 < 7 < 14 < 14 < 7 < 6 < 40 < 14 04/10/15 - 04/10/15 < 4 < 4 < 9 < 4 < 8 < 5 < 8 < 11 < 4 < 3 < 28 < 7 05/06/15 - 05/06/15 < 4 < 4 < 8 < 4 < 7 < 4 < T < 12 < 4 < 4 < 27 < 7 06/12/15 - 06/12/15 < 3 < 3 < 7 < 3 < 6 < 3 < 6 < 14 < 3 < 3 < 27 < 9 07/10/15 - 07/10/15 < 6 < 6 < 13 < 6 < 12 < 6 < 10 < 10 < 6 < 6 < 25 < 7 08/14/15 - 08/14/15 < 7 < 6 < 13 < 4 < 11 < 6 < 9 < 9 < 6 < 7 < 26 < 7 09/11/15 - 09/11/15 < 7 < 6 < 14 < 8 < 14 < 7 < 14 < 11 < 7 < 6 < 30 < 9 10/09/15 - 10/09/15 < 7 < 7 < 14 < 7 < 17 < 8 < 15 < 12 < 8 < 8 < 32 < 11 11/13/15 - 11/13/15 < 5 < 4 < 1.3 < 6 < 10 < 6 < 9 < 10 < 7 < 5 < 23 < 9 12/11/15 - 12/11/15 < 6 < 4 < 20 < 8 < 11 < 4 < 13 < 8 < 7 < 7 < 32 < 7 n

I MEAN V1 D-35 01/09/15 - of/09/15 < 7 < 8 < 13 < 8 < 16 < 7 < 16 < 11 < 7 < 8 < 32 < 10 04/10/15 - 04/10/15 < 4 < 6 < 11 < 4 < 7 < 5 < 7 < 11 < 4 < 4 < 30 < 10 07/10/15 - 07/10/15 < 5 < 5 < 10 < 4 < 11 < 7 < 8 < 8 < 4 < 6 < 26 < 8 10/06/15 - 10/06/15 < 6 < 8 < 14 < 6 < 12 < 7 < 12 < 14 < 6 < 7 < 35 < 11 MEAN

Table C-111.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-28 Common Carp 05/05/15 < 57 < 68 < 128 < 57 < 109 < 64 < 96 < 44 < 55 < 906 < 153 River Carpsucker 05/05/15 < 62 < 90 < 158 < 61 < 140 < 84 < 144 < 67 < 69 < 1021 < 363 Common Carp 10/22/15 < 44 < 58 < 130 < 57 < 125 < 73 < 103 < 60 < 63 < 376 < 122 Largemouth Bass 10/22/15 < 63 < 82 < 186 < 85 < 106 < 75 < 94 < 57 < 70 < 430 < 72 MEAN D-46 Channel Catfish 05/05/15 < 65 < 91 < 172 < 73 < 140 < 80 < 116 < 63 < 74 < 977 < 317 Largemouth Bass 05/05/15 < 62 < 68 < 174 < 58 < 131 < 92 < 139 < 60 < 64 < 983 < 291

() Common Carp 10/22/15 < 60 < 56 < 107 < 52 < 84 < 56 < 95 < 59 < 56 < 400 < 110 I

O'I Smallmouth Buffalo 10/22/15 < 60 < 84 < 173 < 95 < 131 < 94 < 108 < 82 < 98 < 444 < 165 MEAN

/

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF DRESDEN. NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PC/KG DRY+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-27 05/01/15 < 96 < 101 < 225 < 112 < 236 < 125 < 192 < 92 < 113 < 1044 < 303 10/06/15 . < 86 < 93 < 219 < 110 < 216 < 111 < 159 < 76 < 98 < 469 < 158 MEAN

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/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 01/02/15 - 01/09/15 21 +/- 4 24 +/- 5 25 +/- 5 23 +/- 4 21 +/- 4 22 +/- 4 21 +/- 4 24 +/- 5 24 +/- 5 01/09/15 - 01/16/15 25 +/- 5 25 +/- 5 22 +/- 5 22 +/- 5 25 +/- 5 20 +/- 4 21 +/- 4 19 +/- 4 24 +/- 5 01/16/15 - 01/23/15 23 +/- 5 24 +/- 5 21 +/- 4 18 +/- 4 16 +/- 4 19 +/-4 17 +/- 4 15 +/- 4 20 +/-4 01/23/15 - 01/30/15 17 +/- 4 10 +/- 4 10 +/- 4 10 +/- 4 10 +/- 4 14 +/-4 13 +/- 4 13 +/- 4 15 +/- 4 01/30/15 - 02106/15 16 +/- 4 17 +/- 4 18 +/- 4 18 +/- 4 18 +/- 4 14 +/-4 16 +/- 4 17 +/- 4 18 +/-4 02/06/15 - 02113/15 19 +/- 4 19 +/- 4 17 +/- 4 22 +/- 4 18 +/- 4 25 +/- 5 20 +/- 4 23 +/- 4 20 +/- 4 02/13/15 - 02120/15 32 +/- 5 28 +/- 5 30 +/- 5 37 +/- 6 29 +/- 5 26 +/- 5 30 +/- 5 29 +/- 5 32 +/- 5 02/20/15 - 02127/15 32 +/- 5 30 +/- 5 33 +/- 5 32 +/- 5 29 +/- 5 28 +/- 5 24 +/- 5 30 +/- 5 32 +/- 5 02/27/15 - 03/06/15 23 +/- 5 20 +/- 4 24 +/- 5 18 +/- 4 18 +/- 4 20 +/- 4 21 +/- 4 19 +/- 4 25 +/- 5 03/06/15 - 03/13/15 19 +/- 4 13 +/- 4 16 +/- 4 15 +/- 4 12 +/- 4 13 +/- 4 16 +/- 4 18 +/- 4 16 +/- 4 03/13/15 - 03/20/15 15 +/- 4 21 +/- 5 16 +/- 4 20 +/- 5 18 +/- 4 17 +/- 4 19 +/- 4 14 +/- 4 16 +/-4 03/20/15 - 03/27/15 10 +/-4 9 +/- 4 15 +/- 4 11 +/- 4 12 +/- 4 12 +/- 4 12 +/- 4 13 +/- 4 12 +/-4 03/27/15 - 04/02115 15 +/- 5 12 +/- 4 7 +/- 4 11 +/- 4 13 +/- 4 15 +/- 4 13 +/- 4 17 +/- 5 10 +/-4 04/02/15 - 04/10/15 11 +/- 3 10 +/- 3 14 +/- 3 9 +/- 3 9 +/- 3 9 +/- 3 11 +/- 3 11 +/- 3 10 +/- *3 04/10/15 - 04/17/15 17 +/- 5 12 +/- 4 15 +/- 4 10 +/- 4 16 +/- 5 12 +/-4 14 +/- 4 15 +/- 4 16 +/-4 04/17/15 - 04/24/15 13 +/- 4 11 +/- 4 11 +/- 4 13 +/- 4 16 +/- 4 15 +/- 4 13 +/- 4 17 +/- 4 12 +/-4 04/24/15 - 05/01 /15 12 +/- 4 10 +/- 4 8+/-4 12 +/- 4 7 +/- 3 10 +/- 4 9 +/- 4 9 +/- 4 9 +/-4 05/01/15 - 05/06/15 13 +/- 5 13 +/- 5 15 +/- 5 14 +/- 5 15 +/- 5 15 +/- 5 19 +/- 5 16 +/- 5 13 +/- 5 05/06/15 - 05/15/15 9 +/- 3 10 +/- 3 8 +/- 3 9 +/- 3 6 +/- 3 6 +/- 3 6 +/- 3 6 +/- 3 8 +/- 3 05/15/15 - 05/22/15 11 +/- 3 10 +/- 3 15 +/- 4 14 +/- 4 13 +/- 3 13 +/- 3 12 +/- 3 11 +/- 3 9 +/- 3 05/22115 - 05/29/15 20 +/-4 11 +/- 3 16 +/- 4 15 +/- 4 14 +/- 4 16 +/-4 16 +/- 4* 13 +/- 4 11 +/- 3 05/29/15 - 06/05/15 11 +/- 4 8 +/- 4 9 +/- 4 11 +/- 4 .9 +/- 4 10 +/- 4 9 +/- 4 13 +/- 4 11 +/-4 06/05/15 - 06/12115 12 +/- 4 11 +/- 4 14 +/- 4 13 +/- 4 16 +/- 4 13 +/-4 16 +/- 4 12 +/- 4 14 +/- 4 06/12/15 - 06/19/15 9 +/- 3 6 +/- 3 7 +/- 3 9 +/- 3 10 +/- 3 10 +/- 3 6 +/- 3 8 +/- 3 7 +/- 3 06/19/15 - 06/26/15 13 +/- 4 (1) 8 +/- 4 (1) 11 +/- 4 (1} 14 +/- 4 (1) 22+/-8(1} 12 +/- 4 9 +/- 4 10 +/- 4 12 +/-4 06/26/15 - 07/03/15 7 +/- 3 11 +/- 4 10 +/- 3 12 +/- 4 11 +/- 4 10 +/-4 12 +/- 4 (1) 12 +/- 4 12 +/-4 07/03/15 - 07/10/15 10 +/- 4 13 +/- 4 15 +/- 4 11 +/- 4 15 +/- 4 14 +/- 4 11 +/- 4 13 +/- 4 13 +/-4 07/10/15 - 07/17/15 12 +/- 3 12 +/- 3 14 +/- 4 9 +/- 3 12 +/- 3 10 +/- 3 12 +/- 3 6 +/- 3 13 +/-4 07/17/15 - 07/24/15 10 +/- 4 14 +/- 4 13 +/- 4 9 +/- 4 13 +/- 4 10 +/- 4 13 +/- 4 12 +/- 4 9 +/-4 07/24/15 - 07/31/15 19 +/- 4 14 +/- 4 17 +/- 4 15 +/- 4 21 +/- 4 21 +/- 5 (1} 18 +/- 4 17 +/-4 07/31/15 - 08/07/15 16 +/- 4 22 +/- 5 20 +/- 4 19 +/- 4 23 +/- 5 26 +/- 5 18 +/- 4 17- +/- 4 21 +/-4 08/07/15 - 08/14/15 21 +/- 5 (1) 21 +/- 4 21 +/- 4 19 +/- 4 20 +/- 4 19 +/- 4 20 +/- 4 21 +/- 4 20 +/-4 08/14/15 - 08/21 /15 (1) 19 +/- 4 20 +/- 4 24 +/- 5 20 +/- 4 21 +/- 4 20 +/- 4 21 +/- 4 24 +/- 5 08/21/15 - 08/28/15 15 +/- 4 16 +/- 4 12 +/- 4 14 +/- 4 15 +/- 4 14 +/- 4 16 +/- 4 14 +/- 4 13 +/-4 08/28/15 - 09/04/15. 34 +/- 6 24 +/- 5 38 +/- 6(1} 35 +/- 6 31 +/- 5(1} 33 +/- 6 26 +/- 5 31 +/- 5 34 +/- 6 09/04/15 - 09/11/15 29 +/- 5 31 +/- 5 (1) 28 +/- 5 28 +/- 5 38 +/- 6 28 +/- 5 26 +/- 5 31 +/- 5 09/11/15 - 09/18/15 15 +/- 4 13 +/- 4 15 +/- 4 18 +/- 4 15 +/- 4 23 +/- 4 18 +/- 4 16 +/- 4 12 +/-4 09/18/15 - 09/25/15 12 +/- 4 15 +/- 4 12 +/- 4 11 +/- 4 12 +/- 4 12 +/- 4 15 +/- 4 14 +/- 4 15 +/- 4 09/25/15 - 10/02/15 21 +/- 4 16 +/- 4 20 +/- 4 21 +/- 4 21 +/- 4 17 +/- 4 16 +/- 4 20 +/- 4 16 +/-4 10/02115 - 10/09/15 16 +/- 4 13 +/- 4 16 +/- 4 15 +/- 4 14 +/- 4 17 +/- 4 15 +/- 4 13 +/- 4 15 +/-4 10/09/15 - 10/16/15 18 +/- 5 17 +/- 4 13 +/- 4 13 +/- 4 15 +/- 4 13 +/-4 13 +/- 4 15 +/- 4 15 +/-4 10/16/15 - 10/23/15 25 +/- 5 23 +/- 5 (1) 27 +/- 5 28 +/- 5 22 +/- 5 26 +/- 5 23 +/- 5 30 +/- 5 25 +/- 5 10/23/15 - 10/30/15 15 +/- 4 14 +/-4 (1) 13 +/- 4 12 +/- 4 13 +/- 4 13 +/- 4 14 +/-4 12 +/-4 10/30/15 - 11/06/15 17 +/- 4 19 +/- 4 18 +/- 4 17 +/- 4 17 +/- 4 20 +/- 4 18 +/- 4 17 +/- 4 22 +/-4 11/06/15 - 11/13/15 28 +/- 5 23 +/- 5 23 +/- 5 25 +/- 5 24 +/- 5 24 +/- 5 21 +/- 5 21 +/-5 25 +/- 5 11/13/15 - 11/20/15 14 +/- 4 13 +/- 4 15 +/- 4 13 +/- 4 11 +/- 4 15 +/-4 14 +/- 4 14 +/- 4 13 +/-4 11/20/15 - 11/27/15 14 +/- 4 19 +/-4 17 +/- 4 22 +/- 4 17 +/- 4 17 +/-4 17 +/- 4 17 +/-4 16 +/-4 11/27/15 - 12/04/15 15 +/- 4 14 +/-4 16 +/- 4 17 +/-4 17 +/- 4 15 +/-4 17 +/- 4 17 +/-4 21 +/-4 12/04/15 - 12/11/15 31 +/- 5 29 +/-5 28 +/- 5 31 +/-'5 34 +/- 5 29 +/-5 30 +/- 5 34 +/- 5 31 +/- 5 12111/15 - 12118/15 16 +/- 4 15 +/- 4 14 +/- 4 16 +/- 4 15 +/- 4 14 +/-4 14 +/- 3 14 +/-4 16 +/-4 12/18/15 - 12/26/15 26 +/- 4 27 +/- 4 26 +/- 4 28 +/- 5(1) 27 +/- 5 30 +/- 5 26 +/- 5 26 +/- 4 26 +/-4 12/26/15 - 01/02/16 13 +/- 4 26 +/-5 18 +/- 5 19 +/- 5 21 +/- 5 15 +/- 4 19 +/- 5 20 +/-5 17 +/- 5 MEAN 17 +/- 13 17 +/- 13 17 +/- 13 17 +/- 14 17 +/- 13 17 +/- 13 16 +/- 11 17 +/- 12 17 +/- 14 THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-8

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP Ill !GROUP IV PERIOD 0-08 0-10 0-14 0-55 0-12 61162115 - 61/69115 29 +/- 5 23 +/- 4 25 +/- 5 24 +/- 5 26 +/- 4 01/09/15 - 01/16/15 19 +/- 4 23 +/- 5 24 +/- 5 17 +/- 4 19 +/- 4 01/16/15 - 01/23/15 20 +/- 4 21 +/- 4 23 +/- 5 19 +/- 4 21 +/- 4 01/23/15 - 01/30/15 11 +/- 4 12 +/- 4 14 +/- 4 11 +/- 4 9 +/- 4 01/30/15 - 02/06/15 < 5 18 +/- 4 16 +/- 4 13 +/- 4 16 +/- 4 02/06/15 - 02/13/15 20 +/- 4 20 +/- 4 20 +/- 4 20 +/- 4 16 +/- 4 02/13/15 - 02/20/15 33 +/- 5 34 +/- 5 30 +/- 5 30 +/- 5 25 +/- 5 02/20/15 - 02/27/15 30 +/- 5 31 +/- 5 33 +/- 5 30 +/- 5 26 +/- 5 02/27/15 - 03/06/15 18 +/- 4 22 +/- 4 14 +/- 4 21 +/- 4 21 +/- 4 03/06/15 - 03/13/15 12 +/- 4 11 +/- 4 16 +/- 4 13 +/- 4 17 +/- 4 03/13/15 - 03/20/15 20 +/- 5 14 +/- 4 19 +/- 4 13 +/- 4 16 +/- 4 03/20/15 - 03/27/15 12 +/- 4 13 +/- 4 10 +/- 4 14 +/- 4 11 +/- 4 03/27/15 - 04/02/15 11 +/- 4 10 +/- 4 13 +/- 4 10 +/- 4 10 +/- 4 04/02/15 - 04/10/15 12 +/- 3 11 +/- 3 9 +/- 3 13 +/- 3 10 +/- 3 04/10/15 - 04/17/15 16 +/- 4 16 +/- 4 17 +/- 4 14 +/- 4 12 +/- 4 04/17/15 - 04/24/15 13 +/- 4 16 +/- 4 15 +/- 4 13 +/- 4 13 +/- 4 04/24/15 - 05/01/15 10 +/- 4 6 +/- 3 10 +/- 4 8 +/- 3 8 +/- 4 05/01 /15 - 05/06/15 16 +/- 5 14 +/- 5 14 +/- 5 13 +/- 5 11 +/- 4 05/06/15 - 05/15/15 8 +/- 3 7 +/- 3 7 +/- 3 6 +/- 3 8 +/- 3 05/15/15 - 05/22/15 12 +/- 3 12 +/- 3 10 +/- 3 12 +/- 3 8 +/- 3 05/22/15 - 05/29/15 17 +/- 4 15 +/- 4 19 +/- 4 15 +/- 4 14 +/- 4 05/29/15 - 06/05/15 12 +/- 4 12 +/- 4 10 +/- 4 11 +/- 4 9 +/- 4 06/05/15 - 06/12/15 15 +/- 4 12 +/- 4 11 +/- 4 11 +/- 4 12 +/- 4 06/12/15 - 06/19/15 7 +/- 3 8 +/- 3 9 +/- 3 8 +/- 3 7 +/- 3 06/19/15 - 06/26/15 12 +/- 4 (1) 9 +/- 4 (1) 12 +/- 4 11 +/- 4 11 +/- 4 06/26/15 - 07/03/15 11 +/-4 14 +/- 4 10 +/- 4 13 +/- 4 9 +/- 3 07/03/15 - 07/10/15 16 +/- 4 16 +/- 4 18 +/- 4' 15 +/- 4 14 +/- 4 07/10/15 - 07/17/15 14 +/- 4 12 +/- 4 15 +/- 4 16 +/- 4 14 +/- 4 07/17/15 - 07/24/15 15 +/- 4 16 +/- 4 16 +/- 4 12 +/- 4 11 +/- 4 07/24/15 - 07/31/15 18 +/-4 22 +/- 4 21 +/- 5 19 +/- 4 19 +/- 4 07/31/15 - 08/07/15 23 +/- 5 18 +/- 4 19 +/- 4 22 +/- 4 21 +/- 4 08/07/15 - 08/14/15 19 +/- 4 14 +/- 4 19 +/- 4 22 +/- 5 18 +/- 4 08/14/15 - 08/21/15 20 +/- 4 20 +/- 4 21 +/- 5 19 +/- 4 22 +/- 5 08/21/15 - 08/28/15 14 +/- 4 16 +/- 4 14 +/- 4 15 +/- 4 15 +/- 4 08/28/15 - 09/04/15 35 +/- 6 27 +/- 5 36 +/- 6 32 +/- 6 31 +/- 6 09/04/15 - 09/11/15 31 +/- 5 29 +/- 5 27 +/- 5 31 +/- 5 31 +/- 5 09/11/15 - 09/18/15 13 +/- 4 15 +/- 4 16 +/- 4 17 +/- 4 17 +/- 4 09/18/15 - 09/25/15 11 +/- 4 11 +/- 4 13 +/- 4 8+/-4 14 +/- 4 09/25/15 - 10/02/15 19 +/- 4 22 +/- 4 14 +/- 4 18 +/- 4 20 +/- 4 10/02/15 - 10/09/15 16 +/-4 13 +/- 4 14 +/- 4 14 +/- 4 13 +/- 4 10/09/15 - 10/16/15 17 +/- 4 17 +/- 4 18 +/- 4 16 +/- 4 15 +/- 4 10/16/15 - 10/23/15 25 +/- 5 25 +/- 5 24 +/- 5 24 +/- 5 26 +/- 5 10/23/15 - 10/30/15 13 +/- 4 15 +/- 4 11 +/- 4 15 +/- 4 16 +/- 4 10/30/15 - 11/06/15 20 +/- 4 19 +/- 4 18 +/- 4 18 +/- 4 16 +/- 4 11/06/15 - 11/13/15 30 +/-6(1) 21 +/- 5 (1) 21 +/- 5 19 +/- 5 20 +/- 5 11/13/15 - 11/20/15 (1) 14 +/- 4 15 +/- 4 18 +/- 5 12 +/- 4 11/20/15 - 11/27/15 18 +/- 4 (1) 15 +/- 4 18 +/- 4 18 +/- 4 17 +/- 4 11/27/15 - 12/04/15 17 +/- 4 16 +/- 4 17 +/- 4 14 +/- 4 15 +/- 4 12/04/15 - 12111/15 30 +/- 5 35 +/- 6 29 +/- 5 31 +/- 5 24 +/- 5 12/11/15 - 12/18/15 17 +/- 4 16 +/- 4 14 +/- 4 18 +/- 4 14 +/- 4 12/18/15 - 12/26/15 28 +/- 5 27 +/- 5 23 +/- 4 22 +/- 4 29 +/- 5 12/26/15 - 01/02/16 24 +/- 5 17 +/- 4 17 +/- 5 18 +/- 5 21 +/- 5 MEAN 18 +/- 14 17 +/- 13 17 +/- 12 17 +/- 12 16 +/- 12 THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-9

Table C*V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA GROUP 1- ON-SITE LOCATIONS GROUP II - 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 01/02/15 - 01/30/15 10 25 20 +/- 11 01/02115 - 01/30/15 10 25 19 +/- 9 01/02/15 - 01/30/15 11 29 20 +/- 11 01/02/15 - 01/30/15 9 21 17 +/- 10 01 /30/15 - 02127/15 16 33 24 +/- 14 01/30/15 - 02/27/15 14 37 24 +/- 12 01/30/15 - 02127/15 13 34 25 +/- 14 01/30/15 - 02/27/15 16 26 21 +/- 11 .

02/27/15 - 04/02/15 7 24 16 +/- 10 02/27115 - 04/02/15 10 25 15 +/- 7 02/27/15 - 04/02/15 10 22 14 +/- 8 02/27/15 - 04/02115 10 21 15 +/- 9 04/02/15 - 05/01 /15 8 17 12 +/- 5 04/02/15 - 05/01/15 7 17 12 +/- 6 04102/15 - 05/01115 6 17 12 +/- 6 04102/15 - 05/01 /15 8 13 11 +/- 5 05/01/15 - 05/29/15 8 20 12 +/- 7 05/01/15 - 05/29/15 6 19 12 +/- 8 05/01/15 - 05/29/15 6 19 12 +/- 8 05/01/15 - 05/29/15 8 14 10 +/- 6 05/29/15 - 07/03/15 6 14 10 +/- 5 05/29/15 - 07/03/15 6 22 11 +/- 6 05/29/15 - 07/03/15 7 15 11 +/- 4 05/29/ 15 - 07/03/15 7 12 9 +/- 4 07/03/15 - 07/31/15 10 19 13 +/- 5 07/03/15 - 07/31/15 6 21 13 +/- 7 07/03/15 - 07/31/15 12 22 16 +/- 5 07/03/15 - 07/31/15 11 19 14 +/- 6 07/31/15 - 09/04/15 12 38 21 +/- 14 07/31/15 - 09/04/15 13 35 22 +/- 12 07/31/15 - 09/04/15 14 36 21 +/- 13 07/31/15 - 09/04/15 15 31 21 +/- 12 09/04/15 - 10/02115 12 31 18 +/- 13 09/04/15 - 10/02/15 11 38 20 +/- 14 09/04/15 - 10/02/15 8 31 18 +/- 15 09/04/15 - 10/02/15 14 31 21 . +/- 15 10/02/15 - 10/30/15 13 27 18 +/- 10 10/02/15 - 10/30/15 12 30 17 +/- 11 10/02115 - 10/30/15 11 25 17 +/- 9 10/02/ 15 - 10/30/15 13 26 18 +/- 11 10/30/15 - 12/04/15 13 28 18 +/- 8 10/30/15 - 12/04/15 11 25 18 +/- 8 10/30/15 - 12/04/15 14 30 18 +/- 7 10/30/15 - 12/04/15 12 20 16 +/- 6

(') 12/04/15 - 01 /02/16 13 31 22 +/- 13 12/04/15 - 01/02116 23 +/- 14 23 +/- 13 I 14 34 12/04/15 - 01/02/16 14 35 12/04/15 - 01/02/16 14 29 22 +/- 12

......

0 01/02/15 - 01/02116 6 38 17 +/- 13 01/02115 - 01/02/16 6 38 17 +/- 13 01/02115 - 01/02/16 6 36 17 +/- 13 01/02/15 - 01/02/16 7 31 16 +/- 12

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-01 01/02/15 - 04/02/15 < 2 < 3 < 11 < 3 < 7 < 3 < 6 < 2 < 3 < 66 < 38 04/02/15 - 07/03/15 < 3 < 5 < 12 < 3 < 8 < 4 < 9 < 4 < 4 < 126 < 29 07/03/15 - 10/02/15 < 3 < 4 < 12 < 3 < 7 < 4 < 7 < 3 < 2 < 96 < 48 10/02/15 - 01/02/16 < 2 < 2 < 5 < 3 < 4 < 2 < 4 < 2 < 2 < 19 < 5 MEAN D-02 01/02/15 - 04/02/15 < 2 < 2 < 5 < 2 < 5 < 2 < 4 < 2 < 2 < 67 < 19 04/02/15 - 07/03/15 < 3 < 3 < 11 < 4 < 9 < 4 < 7 < 3 < 3 < 62 < 52 07/03/15 - 10/02/15 < 4 < 4 < 13 < 4 < 10 < 6 < 9 < 4 < 3 < 106 < 49 10/02/15 - 01/02/16 < 3 < 3 < 6 < 2 < 7 < 3 < 5 < 3 < 3 < 31 < 8 MEAN

(')

I

...... < 7 2 < < 3 < 5 < 2 < 2 < 81 < 31

...... D-03 01/02/15 - 04/02/15 < 2 < 2 < 5 04/02/15 - 07/03/15 < 2 < 3 < 7 < 2 < 7 < 3 < 7 < 2 < 3 < 105 < 33 07/03/15 - 10/02/15 < 2 < 2 < 7 < 2 < 4 < 2 < 5 < 2 < 2 < 69 < 20 10/02/15 - 01/02/16 < 5 < 5 < 12 < 4 < 10 < 5 < 10 < 4 < 4 < 50 < 14 MEAN D-04 01/02/15 - 04/02/15 < 3 < 3 < 8 < 2 < 7 < 3 < 5 < 2 < 2 < 88 < 41 04/02/15 - 07/03/15 < 2 < 3 < 9 < 2 < 7 < 3 < 5 < 2 < 2 < 73 < 34 07/03/15 - 10/02/15 < 3 < 5 < 11 < 2 < 9 < 4 < 7 < 3 < 3 < 77 < 43 10/02/15 - 01/02/16 < 3 < 3 < 3 < 3 < 6 < 3 < 5 < 3 < 3 < 29 < 5 MEAN D-07 01/02/15 - 04/02/15 < 2 < 3 < 7 < 1 < 5 < 3 < 5 < 2 < 2 < 70 < 24 04/02/15 - 07/03/15 < 4 < 6 < 16 < 4 < 12 < 5 < 8 < 4 < 4 < 118 < 42 07/03/15 - 10/02/15 < 3 < 4 < 9 < 3 < 4 < 3 < 5 < 3 < 2 < 76 < 26 10/02/15 - 01/02/16 < 2 < 3 < 6 < 2 < 5 < 3 < 4 < 2 < 2 < 27 < 10 MEAN

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-08 01/02/15

04/02/15 < 3 < 4 < 11 < 3 < 7 < 5 < 8 < 3 < 4 < 112 < 56 04/02/15 - 07/03/15 < 3 < 3 < 12 *< 3 < 8 < 4 < 7 < 3 < 3 < 76 < 46 07/03/15 - 10/02/15 < 2 < 3 < 11 < 2 < 7 < 4 < 8 < 2 < 2 < 82 < 33 10/02/15 - 01/02/16 < 4 < 4 < 8 < 4 < 6 < 5 < 7 < 4 < 3 < 43 < 18 MEAN D-10 01/02/15 - 04/02/15 < 2 < 3 < 8 < 2 < 5 < 3 < 6 < 2. < 2 < 87 ,< 44 04/02/15 - 07/03/15 < 3 < 5 < 12 < 4 < 9 < 6 < 8 < 4 < 4 < 122 < 49 07/03/15 - 10/02/15 < 4 < 4 < 14 < 3 < 7 < 5 < 11 < 4 < 3 < 137 < 37 10/02/15 - 01/02/16 < 2 < 2 < 4 < 2 < 4 < 2 < 5 < 2 < 2 1< 27 < 6 MEAN

(")

,__.

I N D-12 01/02/15 - 04/02/15 < 3 < 4 < 11 < 3 < 8 < 4 < 8 < 3 < 3 < 130 < 38 04/02/15 - 07/03/15 < 2 < 4 < 10 < 2 < 7 < 3 < 4 < 2 < 2 < 75 < 40 07/03/15 - 10/02/15 < 2 < 3 < 10 < 3 < 7 < 4 < 6 < 3 < 3 < 78 < 39 10/02/15 - 01/02/16 < 2 < 2 < 6 < 2 < 6 < 2 < 4 < 2 < 2 < 21 < 11 MEAN D-14 01 /02/15 - 04/02/15 < 2 < 2 < 7 < 2 < 5 < 3 < 5 < 2 < 1 < 70 < 28 04/02/15 - 07/03/15 < 1 < 2 < 5 < 2 < 3 < 2 < 3 < 1 < 1 < 39 < 20 07/03/15 - 10/02/15 < 2 < 2 < 5 < 2 < 6 < 3 < 4 < 2 < 2 < 59 < 25 10/02/15 - 01/02/16 < 2 < 4 < 9 < 4 < 6 < 3 < 4 < 3 < 3 < 34 < 16 MEAN D-45 01/02/15 - 04/02/15 < 2 < 3 < 10 < 3 < 6 < 3 < 6 < 2 < 2 < 86 < 39 04/02/15 - '07/03/15 < 2 < 3 < 7 < 2 < 4 < 3 < 5 < 2 < 2 < 68 < 34 07/03/15 - 10/02/15 < 3 < 3 < 7 < 3 < 5 < 3 < 6 < 3 < 2 < 80 < 29 10/02/15

01/02/16 < 2 < 3 < 6 < 2 < 6 < 3 < 5 < 2 < 2 < 26 < 7 MEAN

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-53 01/02/15 - 04/02/15 < 2 < 2 < 9 < 2 < 7 < 3 < 7 < 2 < 1 < 78 < 34 04/02/15 - 07/03/15 < 2 < 3 < 7 < 2 < 5 < 3 < 4 < 2 < 2 < 56 < 28 07/03/15 - 10/02/15 < 2 < 3 < 6 < 2 < 5 < 3 < 5 < 3 < 1 < 68 < 36 10/02/15 - 01/02/16 < 2 < 3 < 7 < 2 < 6 < 2 < 4 < 3 < 2 < 27 < 10 MEAN D-55 01/02/15 - 04/02/15 < 3 < 4 < 9 < 3 < 6 < 4 < 7 < 2 < 3 < 110 < 41 04/02/15 - 07/03/15 < 2 < 2 < 6 < 2 < 5 < 3 < 4 < 2 < 2 < 66 < 31 07/03/15 - 10/02/15 < 3 < 2 < 8 < 3 < 8 < 4 < 5 < 3 < 2 < 86 < 28 10/02/15 - 01/02/16 < 5 < 4 < 10 < 5 < 11 < 5 < 8 < 4 < 4 < 43 < 22 MEAN

(')

I

......

w D-56 01/02/15 - 04/02/15 < 2 < 4 < 9 < 2 < 6 < 3 < 6 < 3 < 2 < 99 < 34 04/02/15 - 07/03/15 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 1 < 55 < 23 07/03/15 - 10/02/15 < 2 < 3 < 9 < 3 < 5 < 3 < 6 < 2 < 2 < 74 < 30 10/02/15 - 01/02/16 < 2 < 3 < 7 < 3 < 6 < 3 < 5 < 3 < 2 < 24 < 5 MEAN D-58 01/02/15 - 04/02/15 < 4 < 6 < 17 < 4 < 10 < 7 < 11 < 4 < 4 < 179 < 68 04/02/15 - 07/03/15 < 3 < 3 < 10 < 3 < 7 < 4 < 6 < 2 < 2 < 88 < 38 07/03/15 - 10/02/15 < 3 < 4 < 10 < 2 < 6 < 3 < 6 < 2 < 2 < 58 < 33 10/02/15 - 01 /02/16 < 3 < 3 < 6 < 2 < 7 < 3 < 5 < 3 < 2 < 29 < 13 MEAN

Table C-Vl.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/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 61762115 - 01709115 < 14 < 38 < 38 < 37 < 38 < 41 < 47 < 47 < 47 01/09/15 - 01/16/15 < 36 < 36 < 36 < 36 < 31 < 31 < 33 < 33 < 33 01/16/15 - 01/23/15 < 9 < 24 < 24 < 24 < 25 < 25 < 27 < 26 < 26 01/23/15 - 01/30/15 < 64 < 64 < 64 < 64 < 23 < 49 < 47 < 18 < 47 01/30/15 - 02106/15 < 15 < 40 < 40 < 40 < 40 < 52 < 47 < 47 < 20 02/06/15 - 02113/15 < 30 < 68 < 68 < 68 < 69 < 68 < 60 < 60 < 60 02/13/15 - 02/20/15 < 16 < 40 < 40 < 40 < 41 < 32 < 43 < 43 < 43 02/20/15 - 02127/15 < 36 < 15 < 36 < 36 < 36 < 34 < 39 < 39 < 39 02/27/15 - 03/06/15 < 20 < 45 < 45 < 45 < 45 < 42 < 49 < 49 < 49 03/06/15 - 03/13/15 < 28 < 28 < 11 < 28 < 29 < 33 < 36 < 36 < 36 03/13/15 - 03/20/15 < 28 < 62 < 62 < 62 < 62 < 40 < 62 < 62 < 62 03/20/15 - 03/27/15 < 46 < 45 < 45 < 46 < 46 < 49 < 53 < 52 < 52 03/27/15 - 04/02/15 < 16 < 43 < 43 < 42 < 44 < 47 < 40 < 39 < 39 04/02/15 - 04/10/15 < 69 < 69 < 69 < 69 < 30 < 51 < 58 < 58 < 58 04/10/15 - 04/17/15 < 51 < 52 < 52 < 51 < 70 < 67 < 67 < 20 < 27 04/17/15 - 04/24/15 < 69 < 69 < 69 < 69 < 29 < 66 < 66 < 66 < 66 04/24/15 - 05/01/15 < 47 < 48 < 48 < 48 < 41 < 38 < 37 < 37 < 37 05/01/15 - 05/06/15 < 66 < 65 < 65 < 66 < 55 < 30 < 69 < 69 < 69 05/06/15 - 05/15/15 < 52 < 52 < 52 < 37 < 39 < 20 < 29 < 29 < 29 05/15/15 - 05/22115 < 69 < 69 < 69 < 70 < 69 < 65 < 70 < 61 < 61 05/22/15 - 05/29/15 < 27 < 27 < 27 <: 27 < 68 < 66 < 66 < 66 < 66 05/29/15 - 06/05/15 < 50 < 51 < 50 < 53 < 51 < 44 < 44 < 66 < 66 06/05/15 - 06/12/15 < 25 < 27 < 27 < 27 < 43 < 21 < 21 < 44 < 43 06/12/15 - 06/19/15 < 61 < 62 < 62 < 59 < 58 < 62 < 24 < 63 < 63 06/19/15 - 06/26/15 <i4(1) <54(1) <i4(1) <i3(1) <!9(1) < 53 < 21 < 51 < 51 06/26/15 - 07/03/15 < 69 < 30 < 68 < 69 < 69 < 67 <56 (1) < 51 < 51 07/03/15 - 07/10/15 < 59 < 23 < 59 < 59 < 59 < 69 < 68 < 68 < 68 07/10/15 - 07/17/15 < 55 < 55 < 55 < 55 < 65 < 45 < 44 < 43 < 24 07/17/15 - 07/24/15 < 39 < 39 < 39 < 39 < 15 < 39 < 43 < 41 < 43 07/24/15 - 07/31/15 < 67 < 68 < 68 < 67 < 45 < 53 (1) < 50 < 22 07/31/15 - 08/07/15 < 60 < 59 < 59 < 59 < 23 < 28 < 52 < 51 < 51 08/07/15 - 08/14/15 < .5 (1) < 40 < 38 < iO (1) < 40 < 15 < 34 < 35 < 35 08/14/15 - 08/21/15 <;3 (1) < 68 < 61 <i3 (1) < 64 < 65 < 68 < 65 < 68 08/21/15 - 08/28/15 < 68 < 63 < 61 < 63 < 25 < 47 < 44 < 44 < 44 08/28/15 - 09/04/15 < 50 < 49 < 54 < 50 < 19 < 21 < 42 < 42 < 43 09/04/15 - 09/11/15 < 65 < 66 (1) < 22 <;1 (1) < 70 < 69 < 68 < 28 09/11/15 - 09/18/15 < 27 < 64 <i4 (1) < 64 < 65 < 51 < 48 < 48 < 19 09/18/15 - 09/25/15 < 66 < 27 < 67 < 67 < 67 < 54 < 53 < 29 < 54 09/25/15 - 10/02/15 < 17 < 40 < 40 < 40 < 40 < 26 < 63 < 63 < 65 10/02/15 - 10/09/15 < 37 < 68 < 68 < 68 < 68 < 54 < 51 < 18 < 52 10/09/15 - 10/16/15 < 16 < 37 < 38 < 38 < 38 < 48 < 20 < 47 < 48 10/16/15 - 10/23/15 < 46 <47 (1) < 46 < 46 < 21 < 64 < 26 < 62 < 62 10/23/15 - 10/30/15 < 26 < 62 (1) < 62 < 63 < 46 < 44 < 18 < 45 10/30/15 - 11/06/15 < 21 < 50 < 51 < 50 < 50 < 38 < 34 < 34 < 35 11/06/15 - 11/13/15 < 17 < 43 < 43 < 43 < 44 < 39 < 49 < 49 < 50 11/13/15 - 11/20/15 < 29 < 69 < 67 < 69 < 68 < 25 < 62 < 59 < 61 11/20/15 - 11/27/15 < 25 < 66 < 66 < 66 < 66 < 61 < 57 < 24 < 59 11/27/15 - 12104/15 < 18 < 44 < 46 < 44 < 46 < 51 < 45 < 45 < 47 12/04/15 - 12111/15 < 45 < 46 < 46 < 46 < 64 < 36 < 34 < 34 < 26 12/11/15 - 12118/15 < 63 < 34 < 63 < 65 < 65 < 60 < 63 < 65 < 65 12/18/15 - 12126/15 < 10 < 25 < 26 <!6 (1) < 26 < 13 < 27 < 25 < 26 12/26/15 - 01/02/16 < 44 < 43 < 44 < 44 < 19 < 20 < 36 < 36 < 38 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-14

Table C-Vl.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP Ill !GROUP IV PERIOD D-08 D-10 D-14 D-55 D-12 61/62115 - 61/69/15 < 17 < 39 < 41 < 48 < 41 01/09/15 - 01/16/15 < 31 < 31 < 13 < 18 < 31 01/16/15 - 01/23/15 < 11 < 25 < 25 < 27 < 25 01/23/15 - 01/30/15 < 55 < 55 < 55 < 48 < 55 01/30/15 - 02/06/15 < 28 < 51 < 52 < 48 < 52 02/06/15 - 02/13/15 < 36 < 66 < 68 < 61 < 68 02/13/15 - 02/20/15 < 13 < 32 < 32 < 43 < 32 02/20/15 - 02/27/15 < 14 < 34 < 34 < 40 < 33 02/27/15 - 03/06/15 < 14 < 41 < 42 < 49 < 41 03/06/15 - 03/13/15 < 13 < 32 < 32 < 38 < 32 03/13/15 - 03/20/15 < 22 < 40 < 40 < 62 < 41 03/20/15 - 03/27/15 < 20 < 47 < 49 < 54 < 48 03/27/15 - 04/02/15 < 21 < 48 < 47 < 42 < 47 04/02/15 - 04/10/15 < 51 < 51 < 21 < 60 < 51 04/10/15 - 04/17/15 < 65 < 63 < 67 < 67 < 65 04/17/15 - 04/24/15 < 29 < 66 < 66 < 67 < 66 04/24/15 - 05/01/15 < 43 < 43 < 38 < 35 < 38 05/01/15 - 05/06/15 < 52 < 21 < 54 < 67 < 54 05/06/15 - 05/15/15 < 38 < 20 < 20 < 30 < 20 05/15/15 - 05/22115 < 64 < 64 < 65 < 62 < 25 05/22/15 - 05/29/15 < 69 < 68 < 68 < 66 < 68 05/29/15 - 06/05/15 < 52 < 51 < 17 < 64 < 44 06/05/15 - 06/12/15 < 42 < 43 < 21 < 44 < 43 06/12/15 - 06/19/15 < 60 < 62 < 60 < 64 < 62 06/19/15 - 06/26/15 <i6(1) <36 (1) < 63 < 53 < 67 06/26/15 - 07/03/15 < 36 < 64 < 67 < 52 < 66 07/03/15 - 07/10/15 < 66 < 66 < 65 < 27 < 65 07/10/15 - 07/17/15 < 65 < 65 < 30 < 46 < 65 07/17/15 - 07/24/15 < 39 < 39 < 39 < 43 < 21 07/24/15 - 07/31/15 < 19 < 45 < 48 < 53 < 48 07/31/15 - 08/07/15 < 66 < 66 < 67 < 51 < 66 08/07/15 - 08/14/15 < 37 < 35 < 39 < 36 < 37 08/14/15 - 08/21 /15 < 27 < 65 < 67 < 69 < 65 08/21/15 - 08/28/15 < 64 < 62 < 66 < 17 < 64 08/28/15 - 09/04/15 < 50 < 48 < 51 < 44 < 51 09/04/15 - 09/11/15 < 58 < 58 < 60 < 69 < 56 09/11/15 - 09/18/15 < 59 < 59 < 61 < 50 < 61 09/18/15 - 09/25/15 < 33 < 32 < 34 < 56 < 32 09/25/15 - 10/02/15 < 65 < 65 < 66 < 66 < 63 10/02/15 - 10/09/15 < 65 < 64 < 65 < 52 < 63 10/09/15 - 10/16/15 < 37 < 37 < 37 < 49 < 37 10/16/15 - 10/23/15 < 47 < 47 < 48 < 66 < 48 10/23/15 - 10/30/15 < 38 < 38 < 38 < 46 < 36 10/30/15 - 11/06/15 < 37 < 15 < 38 < 35 < 37 11/06/15 - 11/13/15 <'.1 (1) < 41 (1) < 39 < 50 < 37 11/13/15 - 11/20/15 (1) < 65 < 65 < 64 < 65 11/20/15 - 11/27/15 < ;3 (1) < 61 < 62 < 60 < 59 11/27/15 - 12/04/15 < 21 < 50 < 51 < 49 < 49 12/04/15 - 12/11/15 < 64 < 66 < 15 < 37 < 64 12111/15 - 12/18/15 < 26 < 58 < 60 < 69 < 58 12/18/15 - 12/26/15 < 31. < 32 < 32 < 26 < 31 12/26/15 - 01/02/16 < 46 < 47 < 48 < 40 < 46 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-15

Table C-Vll.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA FARM COLLECTION D-25 PERIOD 01/06/15 (1) 02/06/15 (1) 03/06/15 (1) 04/02/15 < 0.4 05/06/15 < 0.6 05/21/15 < 0.7 06/04/15 < 0.9 06/18/15 < 0.7 07/01/15 < 0.8 07116/15 < 0.3 07/30/15 < 0.6 08/13/15 < 0.8 08/27/15 < 0.6 09/10/15 < 0.6 09/24/15 < 0.4 10/08/15 < 0.7 10/22/15 < 0.3 11/05/15 < 0.5 12104/15 (1)

MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16

Table C-Vll.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 , Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD D-25 01/06/15 (1) 02/06/15 (1) 03/06/15 (1) 04/02/15 < 8 < 9 < 18 <: 7 < 17 < 10 < 16 < 8 < 9 < 59 < 9 05/06/15 < 3 < 3 < 8 < 3 < 7 < 3 < 6 < 3 < 3 < 28 < 9 05/21/15 < 8 < 8 < 14 < 9 < 18 < 10 < 16 < 7 < 8 < 52 < 12 06/04/15 < 9 < 7 < 24 < 11 < 22 < 10 < 14 < 7 < 8 < 42 < 14 06/18/15 < 6 < 9 < 15 < 5 < 16 < 7 < 11 < 6 < 8 < 37 < 13 07/01/15 < 6 < 6 < 15 < 8 < 12 <. 6 < 10 < 6 < 6 < 36 < 10 07/16/15 < 9 < 7 < 15 < 8 < 14 < 8 < 14 < 7 < 7 < 49 < 11 07/30/15 < 6 < 6 < 15 < 6 < 14 < 6 < 13 < 6 < 6 < 38 < 15

(') < 9 < 14 < 9 < 9 < 48 < 13 I 08/13/15 < 9 < 9 < 18 < 8 < 20

......

-....)

08/27/15 < 8 < 7 < 15 < 12 < 26 < 10 < 17 < 6 < 9 < 39 < 11 09/10/15 < 6 < 6 < 15 < 8 < 15 < 6 < 12 < 5 < 7 < 25 < 9 09/24/15 < 8 < 6 < 20 < 6 < 20 < 8 < 11 < 8 < 8 < 36 < 12 10/08/15 < 6 < 6 < 15 < 6 < 14 < 7 < 12 < 6 < 7 < 31 < 6 10/22/15 < 7 < 7 < 17 < 8 < 15 < 7 < 13 < 7 < 7 < 32 < 5 11/05/15 < 6 < 7 < 18 < 7 < 16 < 7 < 11 < 5 < 7 < 29 < 7 12/04/15 (1)

MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-Vlll.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 . La-140 PERIOD D-CONTROL 09/24/15 ( 1) 09/24/15 ( 1)

MEAN D-QUAD 1 Cabbage 09/24/15 < 20 < 18 < 51 < 17 < 36 < 18 . < 34 < 52 < 18 < 21 < 101 < 37 Turnips 09/24/15 < 25 < 27 < 74 < 29 < 71 < 25 < 48 < 55 < 19 < 27 < 132 < 23 MEAN D-QUAD2 09/24/15 (1) 09/24/15 (1)

("')

I

...... MEAN 00 D-QUAD 3 09/24/15 (1)

. 09/24/15 (1)

MEAN D-QUAD 4 Broccoli 09/24/15 < 21 < 24 < 56 < 18 < 53 < 22 < 38 < 54 < 20 < 24 < 115 < 26 Carrots 09/24/15 < 18 < 14 < 35 < 15 < 42 < 18 < 32 < 40 < 14 < 18 < 79 < 27 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-IX.1 QUARTERLY OSLO RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF MREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN-MAR APR-JUN JUL-SEP OCT-DEC CODE +2S.D.

B-61-1 29.9 +/- 6.3 34.3 29.6 28.5 27.6 D-01-2 29.5 +/- 6.2 34.0 28.0 28.9 27.0 D-02-1 29.6 +/- 8.5 35.6 27.4 29.3 26.0 D-02-2 31.9 +/- 6.4 36.3 32.1 29.6 29.4 D-03-1 26.2 +/- 10.3 33.6 24.0 25.5 21.8 D-03-2 25.8 +/- 6.2 30.3 24.8 24.8 23.2 D-04-1 30.6 +/- 7.0 35.6 29.9 29.2 27.5 D-04-2 29.4 +/- 6.3 33.0 27.8 30.9 25.9 D-07-1 28.6 +/- 9.0 35.3 26.0 27.0 26.0 D-07-2 29.9 +/- 9.0 35.0 26.6 28.1 (1)

D-08-1 29.9 +/- 10.0 37.0 .27.5 29.3 25.6 D-08-2 29.3 +/- 9.5 35.4 28.3 29.6 23.9 D-10-1 28.7 +/- 8.4 34.7 25.6 28.4 26.1 D-10-2 29.9 +/- 4.8 33.4 28.2 29.3 28.6 D-12-1 27.4 +/- 7.7 32.9 26.8 25.7 24.1 D-12-2 26.9 +/- 7.8 32.7 24.7 25.4 24.6 D-14-1 25.8 +/- 6.9 30.8 25.0 23.5 23.7 D-14-2 27.9 +/- 6.4 32.6 26.5 26.6 25.7 D-45-1 30.5 +/- 6.1 34.7 29.9 29.9 27.4 D-45-2 32.3 +/- 6.0 36.7 30.5 31.4 30.4 D-53-1 25.9 +/- 9.6 32.9 25.0 22.7 22.9 D-53-2 25.0 +/- 9.4 31.4 24.8 23.7 20.1 D-55-1 28.6 +/- 6.8 33.2 28.3 27.8 25.0 D-55-2 29.3 +/- 6.3 33.8 28.5 28.6 26.4 D-56-1 25.1 +/- 7.1 30.3 24.1 23.3 22.6 D-56-2 25.3 +/- 6.2 29.8 24.7 23.6 23.0 D-58-1 25.9 +/- 6.7 30.7 24.0 25.7 23.2 D-58-2 24.5' +/- 5.9 28.7 23.1 24.2 21.9 D-101-1 30.2 +/- 6.2 34.5 29.2 30.0 27.2 D-101-2 27.8 +/- 9.4 34.4 26.5 26.7 23.4 D-102-1 30.7 +/- 8.4 36.2 27.1 31.6 27.8 D-102-2 30.8 +/- 5.8 34.6 30.6 30.6 27.5 D-103-1 29.2 +/- 9.8 36.3 27.9 27.7 25.0 D-103-2 29.9 +/- 8.5 35.3 26.3 31.1 26.7 D-104-1 30.1 +/- 10.1 35.9 (1) 28.1 26.4 D-104-2 32.0 +/- 9.4 37.9 33.0 30.0 26.9 D-105-1 29.1 +/- 8.7 35.2 29.2 26.0 26.0 D-105-2 30."6 +/- 8.6 37.0 27.6 28.8 29.1 D-106-1 27.7 +/- 8.1 33.7 25.8 26.2 25.0 D-106-2 25.7 +/- 9.4 32.7 23.7 23.4 23.0 D-107-1 26.3 +/- 9.7 33.4 24.8 24.4 22.5 D-107-2 26.2 +/- 7.9 31.9 24.2 25.5 23.1 D-108-1 30.5 +/- 10.2 38.1 28.7 27.5 27.8 D-108-2 28.2 +/- 10.3 35.7 25.8 27.1 24.2 D-109-1 29.3 +/- 10.1 36.1 26.2 29.9 24.8 D-109-2 29.2 +/- 9.5 35.9 28.3 27.7 24.7 D-110-3 33.0 +/- 5.9 37.4 - 31.5 31.3 31.6 D-110-4 33.0 +/- 5.0 36.1 31.9 30.2 33.6 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-19

Table C-IX.1 QUARTERLY OSLO RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF MREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN-MAR APR-JUN JUL-SEP OCT-DEC CODE +2S.D.

D-111-1 32.4 +/- 11.9 39.2 (1) 29.9 28.1 D-111-2 30.1 +/- 7.8 35.8 27.7 27.7 29.0 D-113-1 26.8 +/- 9.9 34 22.8 25.4 24.8 D-113-2 28.0 +/- 9.1 34.6 24.8 27.1 25.3 D-114-1 26.6 +/- 10.2 33.8 25.5 25.3 21.8 D-114-2 27.7 +/- 10.3 35.3 24.5 26.5 24.6 D-115-1 29.0 +/- 10.8 36.9 27.5 26.8 24.7 D-115-2 30.4 +/- 8.0 36.4 28.2 28.7 28.2 D-116-1 31.6 +/- 10.2 39.1. 29.0 30.0 28.1 D-116-2 31.3 +/- 9.2 38.0 29.0 30.2 27.9 D-201-1 33.9 +/- 9.2 39.2 (1) 31.2 31.3 D-201-2 33.3 +/- 10.5 40.8 30.0 33.0 29.4 D-202-1 31.6 +/- 6.9 36.7 30.4 29.4 29.8 D-202-2 28.9 +/- 7.5 34.3 27.7 27.6 25.8 D-203-1 28.7 +/- 5.8 32.6 27.6 28.7 25.7 D-203-2 28.9 +/- 6.8 32.8 27.2 26.6 (1)

D-204-1 27.4 +/- 7.8 32.8 26.6 26.5 23.6 D-204-2 26.1 +/- 9.1 32.6 23.2 25.7 22.8 D-205-1 26.8 +/- 7.2 31.7 27.1 25.1 23.3 D-205-2 27.8 +/- 9.8 35.1 25.4 25.8 24.9 D-206-1 28.7 +/- 11.6 35.0 (1) 27.4 23.6 D-206-2 28.9 +/- 8.1 34.9 26.7 26.6 27.3 D-207-1 26.2 +/- 11.9 35.1 23.1 23.8 22.9 D-207-2 26.7 +/- 9.4 33.7 24.6 23.7 24.9 D-208-1 26.3 +/- 9.8 33.6 23.9 24.3 23.3 D-208-2 25.2 +/- 10.0 32.4 23.4 24.1 20.8 D-209-1 25.6 +/- 11.1 33.6 21.4 24.8 22.4 D-209-2 26.5 +/- 13.5 34.2 21.9 23.3 (1)

D-210-1 29.1 +/- 9.0 35.7 27.6 27.3 25.6 D-210-2 29.5 +/- 11.1 37.5 27.4 28.4 24.7 D-211-1 31.1 +/- 10.0 38.5 29.6 28.5 27.8 D-211-2 30.4 +/- 9.3 37.0 28.8 29.5 26.1 D-212-3 27.1 +/- 8.3 33.1 23.5 26.4 25.5 D-212-4 27.8 +/- 11.7 36.2 25.9 26.1 22.8 D-213-1 25.4 +/- 12.7 34.8 23.4 22.6 20.8 D-213-2 25.8 +/- 10.4 33.4 24.2 23.5 21.9 D-214-1 32.3 +/- 12.1 40.7 29.1 32.4 26.9 D-214-2 33.6 +/- 10.7 40.0 36.1 29.6 28.8 D-215-1 34.1 +/- 10.2 41.4 31.5 33.3 30.0 D-215-2 31.7 +/- 8.9 37.6 30.1 32.2 27.0 D-216-1 29.5 +/- 10.2 36.8 28.6 27.4 25.1 D-216-2 . 32.9 +/- 11.7 41.6 29.7 31.1 29.3 D-112A-1 27.9 +/- 9.4 34.8 26.8 24.8 25.2 D-112A-2 27.3 +/- 11.5 35.2 26.2 26.1 21.5 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-20 .

TABLE C-IX.2 MEAN QUARTERLY OSLO RESULTS FOR THE INNER RING, OUTER RING, OTHER AND CONTROL LOCATIONS FOR DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF MREM/QUARTER +/- 2 STANDARD DEVIATION OF THE STATION DATA COLLECTION INNER RING OUTER RING OTHER CONTROL PERIOD +/-2S.D.

JAN-MAR 35.3 +/- 4.4 35.8 +/- 5.8 33.7 +/- 4.1 32.8 +/- 0.3 APR-JUN 27.1 +/- 5.1 26.9 +/- 6.5 27.2 +/- 4.4 25.8 +/- 3.0 JUL-SEP 27.7 +/- 4.5 27.4 +/- 6.1 27.5 +/- 5.2 25.6 +/- 0.4 OCT-DEC 25.9 +/- 5.5 25.5 +/- 5.7 25.4 +/- 5.0 24.4 +/- 0.7 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF MREM/QUARTER LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN ANALVZED MINIMUM MAXIMUM +/- 2 S.D.

INNER RING 134 21.5 39.2 29.0 +/- 8.9 OUTER RING 124 20.8 41.6 29.0 +/- 10.1 OTHER 95 20.1 37.0 28.5 +/- 7.8 CONTROL 8 24.1 32.9 27.1 +/- 7.2 INNER RING STATIONS- D-101-1, D-101-2, D-102-1, D-102-2, D-103-1, D-103-2, D-104-1, D-104-2, D-105-1, D-105-2, D-106-1, D-106-2, D-107-1, D-107-2, D-108-1, D-108-2, D-109-1, D-109-2, D-110-3, D-110-4, D-111-1, D-111-2, D-112A-1, D-112A-2, D-113-1, D-113-2, D-114-1, D-114-2, D-115-1, D-115-2, D-116-1, D-116-2, D-58-1, D-58-2 OUTER RING STATIONS- D-201-1, D-201-2, D-202-1, D-202-2, D-203-1, D-203-2, D-204-1, D-204-2, D-205-1, D-205-2, D-206-1, D-206-2, D-207-1, D-207-2, D-208-1, D-208-2, D-209-1, D-209-2, D-210-1, D-210-2, D-211-1, D-211-2, D-212-3, D-212-4, D-213-1, D-213-2, D-214-1, D-214-2, D-215-1, D-215-2, D-216-1, D-216-2 OTHER STATIONS - D-01-1, D-01-2, D-02-1, D-02-2, D-03-1, D-03-2, D-04-1, D-04-2, D-07-1, D-07-2, D-08-1, D-08-2, D-10-1., D-10-2, D-14-1, D-14-2, D-45-1, D-45-2, D-53-1, D-53-2, D-55-1, D-55-2, D-56-1, D-56-2 CONTROL STATIONS- D-12-1, D-12-2 C-21

FIGURE C-1 SURFACE WATER - GROSS BETA - STATION D-52 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2015 D-52 (C) DesPlaines River at Will Road 16 14 12 10 4

2 o+-~~~--~~~--~~~~~~~~~~~~

01-28-00 01-22-03 01-16-06 01-10-09 01-05-12 12-30-14 DUE TO VENDOR CHANGE IN 2005, <VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-22

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

COLLECTED IN THE VICINITY OF DNPS, 2003 - 2015 D-54 (C) Kankakee River 14 12 10 B

!

C3Cl.

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 s0 16 .

Cl.

12 8

4 0+-~~-+~~~-+-~~---;~~~-i-~~---+-~

07-28-06 04-03-08 12-09-09 08-16-11 04-22-13 12"28-14 DUE TO VENDOR CHANGE IN 2005, <VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-54 LOCATION REMOVED FROM PROGRAM JUNE 28, 2007 AND REPLACED WITH D-57 C-23

FIGURE C-3 SURFACE WATER - GROSS BETA - STATIONS D-21 and D-51 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2015 D-21 Illinois River at EJ&E Bridge 30 25 20 5(.) 15 Q.

10 5

0+-~~-1-~~~+-~~--+-~~~+--~~---~~

04-27-07 11-08-08 05-23-10 12-05-11 06-18-13 12-31-14 D-51 Dresden Lock & Dam 12 10 8

...I

6

(.)

Q.

4 2

0 01-28-00 08-29-01 03-31-03 10-30-04 06-01-06 01-01-08 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-24

FIGURE C-4 SURFACE WATER - TRITIUM - STATION D-52 (C) COLLECTED IN THE VICINITY OF DNPS,. 2000 - 2015 D-52 (C) Des Plaines River at Will Road 600 500 400 s

(,)

300 Cl.

200 100 0

03-31-00 03-13-03 02-22-06 02-03-09 01-16-12 12-28-14 DUE TO VENDOR CHANGE IN 2005, <VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-25

FIGURE C-5 SURFACE WATER - TRITIUM - STATION D-54 (C) AND D-57 (C) COLLECTED IN THE VICINITY OF DNPS, 2003 - 2015 D-54 (C) Kankakee River 800 700 600 500

!

uc. 400 300 200 100 0

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

D-57 (C) Kankakee River at Will Road 7000 6000 5000 4000

!

uc. 3000 2000 1000 O.J-:s1'....:_~~-=-...Y...-,-~~~~-=~SL......Y..~.---~~-.---~-

12-20-06 04-22-08 08-24-09 12-26-10 04-28-12 08-30-13 01-01-15 DUE TO VENDOR CHANGE IN 2005, <VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 D-57 NEW STATION JULY 24, 2006. REPLACED D-54 ON JUNE 28, 2007 C-26

~-----------------------------~

FIGURE C-6 SURFACE WATER - TRITIUM - STATIONS D-21 and D-51 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2015 D-21 Illinois River at EJ&E Bridge 1200 1000 800 50 600 c.

400 200 0+---~---~------~---~--

06-29-07 12-28-08 06-29-10 12-29-11 06-29-13 12-29-14 D-51 Dresden Lock & Dam 2000 1800 1600 1400 1200 s

0 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 D-51 LOCATION REMOVED FROM PROGRAM JUNE 29, 2007 AND REPLACED WITH D-21 C-27

FIGURE C-7 GROUND WATER - TRITIUM - STATIONS D-23 and D-35 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2015 D-23 Thorsen Well 1000 800 600

$

CJ c.

400 200 0

01-08-00 01-06-03 01-04-06 01-02-09 01-01-12 12-30-14 D-35 Dresden Lock and Dam 400 350 300 250

...I

~c. 200 150 100 50 0

01-08-00 01-06-03 01-04-06 01-02-09 01-01-12 12-30-14 DUE TO VENDOR CHANGE IN 2005, <VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-28

FIGURE C-8 AIR PARTICULATES - GROSS BETA - STATIONS D-01 and D-02 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2015 D-01 Onsite Station 1 50.0 40.0

-.M_E 30.0 0

Cl.

M

i: 20.0

....

0 10.0 0.0 +-----------------------------

01-08-00 01-07-03 01-06-06 01-05-09 01-05-12 01-04-15 D-02 Onsite Station 2 50.0 40.0 M

.E 30.0 0a.

C')

'i' 20.0 w

0

.....

10.0 0.0 01-08-00 01-07-03 01-06-06 01-05-09 01-05-12 01-04-15 0-02 No samples; power was restored on 09-16-05.

C-29

FIGURE C-9 AIR PARTICULATES*- GROSS BETA - STATIONS D-03 and D-04 COLLECTED IN THE VICINITY OF DNPS, 2000 -2015 D-03 Onsite Station 3 60.0 50.0 M 40.0

~

0

c. 30.0 M

0 w 20.0

....

0 10.0 0.0 01-08-00 10-26-02 08-13-05 05-31-08 03-19-11 01-04-14 D-04 Colllns Road on Station Property 60.0 50.0 M 40.0

~

0

c. 30.0 sw 20.0

....

0 10.0 0.0 +-----t----+----+-----t-----

01-06-06 01-05-09 01-05-12 01-04-15 01-08-00 01-07-03 D-03 No samples; power was restored on 07-04-14.

C-30

FIGURE C-10

'

AIR PARTICULATES - GROSS BETA- STATIONS. D-07 and D-12 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2015 D-07 Clay Products, Dresden Road 120.0 110.0 100.0 90.0

..,

.e 80.0 0c. 70.0

..,

0 60.0 50.0

...w 0 40.0 30.0 20.0 10.0 0.0 01-08-00 01-07-03 01-06-06 01-05-09 01-05-12 01-04-15 D-12 (C), Quarry Road, Lisbon 80.0 70.0 60.0 C')

§ 50.0 0

c. 40.0 C')

0 w 30.0

...

0 20.0 10.0 0.0 + - - - - - + - - - + - - - - - + - - - + - - - - + -

01-08-00 01-07-03 01-06-06 01-05-09 01-05-12 01-04-15 C-31

FIGURE C-11 AIR PARTICULATES - GROSS BETA - STATIONS D-45 and D-53 COtLECTED IN THE VICINITY OF DNPS, 2000 - 2015 D-45 McKinley Woods Road, Channahon 70,0 60.0

..., 50.0

.E 40.0 0c.

..., 30.0

~

....

0 20.0 10.0 0.0 01-08-00 01-07-03 01-06-06 01-05-09 01-05-12 01-04-15 D-53 Will Road, Hollyhock 50.0 40.0 C"'I

§ 30.0 0

c.

C"'I 9 20.0 w

....

0 10.0 0.0 +----l----f----------1-------___.-

01-08-00 01-07-03 01-06-06 01-05-09 01-05-12 01-04-15 C

.FIGURE C-12 AIR PARTICULATES - GROSS BETA - STATIONS 0-08 and 0-10 COLLECTED IN THE VICINITY OF.DNPS, 2005 - 2015 D-08 Jugtown Road, Prairie Parks 70.0 60.0 50.0

"'0

§ 40.0 c.

~ 30.0

~ 20.0 10.0 0.0 _ _ _ _ _ _ _.....__ _ _ _ _ _ _ _ _ _ __

01-07-05 01-06-07 01-04-09 01-03-11 01-01-13 12-31-14 D-10 Goose Lake Road, Goose Lake Village 60.0 50.0

"' 40.0

§ 0

c. 30.0 q

~ 20.0

.....

10.0 0.0 _ _ _ _ _ _ _ _ _ _ _.....__ _ _ _ _ _ _ _ _ _ __

01.-07-05 01-06-07 01-04-09 01-03-11 01-01-13 12-31-14 C-33

FIGURE C-13 AIR PARTICULATES - GROSS BETA - STATIONS D-13 and D-14 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2015 D-13 Minooka 50.0 40.0 M'

§ 30.0 0

a.

M 0

...w 20.0 0

10.0 0.0 +-----+----+---~----+------1----

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 M'

§ 30.0 0

a.

M Cjl 20.0 w

...

0 10.0 0.0 -----+-------------------

01-07-05 01-06-07 01-04-09 01-03-11 01-01-13 12-31-14 0-13 TAKEN OUT OF SERVICE JUNE 29, 2007 AND REPLACED WITH 0-55 C-34

FIGURE C-14 AIR PARTICULATES - GROSS BETA - STATIONS D-55 and D-56 COLLECTED IN THE VICINITY OF DNPS, 2006-2015 D-55 Ridge Road, Minooka 70.0 60.0 50.0 M

E

~ 40.0 c.

9 30.0 w

~ 20.0 10.0 0.0 + - - - - - t - - - - + - - - - - t - - - - + - - - - - t - - -

01-06-06 10-24-07 08-10-09 05-28-11 03-14-13 12-30-14 D-56 Will Road, Wildfeather 50.0 40.0 M

§ 30.0 0

c.

M Ct> 20.0 w

...

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

07-25-06 04-01-08 12-08-09 08-16-11 04-23-13 12-30-14 D-55 NEW §)TATION DECEMBER 30, 2005 REPLACED D-13 JUNE 29, 2007 D-56 NEW STATION JULY 25, 2006

FIGURE C-15 AIR PARTICULATES - GROSS BETA - STATION D-58 COLLECTED IN THE VICINITY OF DNPS,- 2011-2015 D-58 Will Road Marina 60.0 50~0

~ 40.0

~

a. 30.0 q

ig 20.0

....

"'------------------1------

10.0 0.0 06-03-11 02-20-12 11-08-12 07-28-13 04-16-14 01-03-15 09-22-15 D-58 NEW STATION IN MAY OF 2011 C-36

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM

Intentionally left blank TABLE D-3.1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF3)

Identification Reported Known Ratio (c)

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

March 2015 E11181 Milk Sr-89 pCi/L 88.9 97.2 0.91 A Sr-90 pCi/L 12.2 17.4 0.70 w E11182 Milk 1-131 pCi/L 61.3 65.1 0.94 A Ce-141 pCi/L 104 113 0.92 A Cr-51 pCi/L 265 276 0.96 A Cs-134 pCi/L 138 154 0.90 A Cs-137 pCi/L 205 207 0.99 A Co-58 pCi/L 178 183 0.97 A Mn-54 pCi/L 187 188 0.99 A Fe-59 pCi/L 182 177 1.03 A Zn-65 pCi/L 345 351 0.98 A Co-60 pCi/L 379 405 0.94 A E11184 AP Ce-141 pCi 107 85.0 1.26 w Cr-51 pCi 261 224 1.17 A Cs-134 pCi 74.6 77.0 0.97 A Cs-137 pCi 99.6 102 0.98 A Co-58 pCi 99.8 110 0.91 A Mn-54 pCi 99.2 96.9 1.02 A Fe-59 pCi 109 119 0.92 A Zn-65 pCi 188 183 1.03 A Co-60 pCi 200 201 1.00 A E11183 Charcoal 1-131 pCi 82.9 85.4 0.97 A E11185 Water Fe-55 pCi/L 1950 1900 1.03 A June 2015 E11234 Milk Sr-89 pCi/L 94.9 92.6 1.02 A Sr-90 pCi/L 14.3 12.7 1.13 A E11238 Milk 1-131 pCi/L 93.2 95.9 0.97 A Ce-141 pCi/L Not provided for this study Cr-51 pCi/L 349 276 1.26 w Cs-134 pCi/L 165 163 1.01 A Cs-137 pCi/L 143 125 1.14 A Co-58 pCi/L 82.0 68.4 1.20 A Mn-54 pCi/L 113 101 1.12 A Fe-59 pCi/L 184 151 1.22 w Zn-65 pCi/L 269 248 1.08 A Co-60 pCi/L 208 193 1.08 A E11237 AP Ce-141 pCi Not provided for this study Cr-51 pCi 323 233 1.39 N (1)

Cs-134 pCi 139 138 1.01 A Cs-137 pCi 111 106 1.05 A Co-58 pCi 54.0 57.8 0.93 A Mn-54 pCi 96.8 84.9 1.14 A Fe-59 pCi 162 128 1.27 w Zn-65 pCi 198 210 0.94 A Co-60 pCi 178 163 1.09 A E11236 Charcoal* 1-131 pCi 93.9 80 1.17 A D-1

TABLE D-3.1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE20F3)

Identification Reported Known Ratio (c)

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

June 2015 E11238 Water Fe-55 pCi/L 1890 1790 1.06 A September2015 E11289 Milk Sr-89 pCi/L 95.7 99.1 0.97 A Sr-90 pCi/L 15.4 16.4 0.94 A E11290 Milk 1-131 pCi/L 94.9 99.9 0.95 A Ce-141 pCi/L 228 213 1.07 A Cr-51 pCi/L 499 538 0.93 A Cs-134 pCi/L 208 212 0.98 A Cs-137 pCi/L 270 255 1.06 A Co-58 pCi/L 275 263 1.05 A Mn-54 pCi/L 320 290 1.10 A Fe-59 pCi/L 255 226 1.13 A Zn-65 pCi/L 392 353 1.11 A Co-60 pCi/L 350 330 1.06 A E11292 AP Ce-141 pCi 104 85.1 1.22 w Cr-51 pCi 262 215 1.22 w Cs-134 pCi 86.1 84.6 1.02 A Cs-137 pCi 93 102 0.91 A Co-58 pCi 106 105 1.01 A Mn-54 pCi 117 116 1.01 A Fe-59 pCi 94.8 90.2 1.05 A Zn-65 pCi 160 141 1.13 A Co-60 pCi 146 132 1.11 A E11291 Charcoal 1-131 pCi 85.9 81.7 1.05 A E11293 Water Fe-55 pCi/L 2090 1800 1.16 A E11294 Soil Ce-141 pCi/kg 209 222 0.94 A Cr-51 pCi/kg 463 560 0.83 A Cs-134 pCi/kg 231 221 1.05 A Cs-137 pCi/kg 311 344 0.90 A Co-58 pCi/kg 245 274 0.89 A Mn-54 pCi/kg 297 302 0.98 A Fe-59 pCi/kg 248 235 1.06 A Zn-65 pCi/kg 347 368 0.94 A Co-60 pCi/kg 328 344 0.95 A December 2015 E11354 Milk Sr-89 pCi/L 96.2 86.8 1.11 A Sr-90 pCi/L 14.8 12.5 1.18 A E11355 Milk 1-131 pCi/L 95.1 91.2 1.04 A Ce-141 pCi/L 117 129 0.91 A Cr-51 pCi/L 265 281 0.94 A Cs-134 pCi/L 153 160 0.96 A Cs-137 pCi/L 119 115 1.03 A Co-58 pCi/L 107 110 0.97 A Mn-54 pCi/L 153 145 1.06 A Fe-59 pCi/L 117 108 1.08 A Zn-65 pCi/L 261 248 1.05 A Co-60 pCi/L 212 213 1.00 A D-2

TABLE D-3.1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE30F3)

Identification Reported Known Ratio (c)

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

December 2015 E11357 AP Ce-141 pCi 89.9 84.0 1.07 A Cr-51 pCi 215 184 1.17 A Cs-134 pCi 103 105 0.98 A Cs-137 pCi 76.6 74.8 1.02 A Co-58 pCi 76.2 71.9 1.06 A Mn-54 pCi 91.4 94.4 0.97 A Fe-59 pCi 78.6 70.3 1.12 A Zn-65 pCi 173 162 1.07 A Co-60 pCi 138 139 0.99 A E11422 AP Sr-89 pCi 98.0 96.9 1.01 A Sr-90 pCi 10.0 14.0 0.71 w E11356 Charcoal 1-131 pCi 74.9 75.2 1.00 A E11358 Water Fe-55 pCi/L 2160 1710 1.26 w E11353 Soil Ce-141 pCi/kg 252 222 1.14 A Cr-51 pCi/kg 485 485 1.00 A Cs-134 pCi/kg 319 277 1.15 A Cs-137 pCi/kg 292 276 1.06 A Co-58 pCi/kg 193 190 1.02 A Mn-54 pCi/kg 258 250 1.03 A Fe-59 pCi/kg 218 186 1.17 A Zn-65 pCi/kg 457 429 1.07 A Co-60 pCi/kg 381 368 1.04 A (1) AP Cr Cr-51 /1as t/1e shortest half-life and the weakest gamma energy of the mixed nuclide sample, which produces a large error. Taking into account the error, the lowest value would be 119% ofthereference value, which would be considered acceptable. NCR 15*18 (a) Teledyne Brown Engineering reported result.

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

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

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0.80-1.20.

W-Acceptable with warning, reported result falls within 0. 70-0.80or1.20-1.30. N =Not Acceptable, reported result falls outside the ratio limits of< 0. 70 and > 1.30.

D-3

TABLE D-3.2 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)

Identification Reported Known Acceptance MonthNear Number Media Nuclide* Units Value (a) Value (b) Range Evaluation (c)

March 2015 15-MaW32 Water Am-241 Sq/L 0.632 0.654 0.458 - 0.850 A Ni-63 Sq/L 2.5 (1) A Pu-238 Sq/L 0.0204 0.0089 (2) A Pu-239/240 Sq/L 0.9 0.8 0.582 - 1.082 A 15-MaS32 Soil Ni-63 Sq/kg 392 448.0 314- 582 A Sr-90 Sq/kg 286 653 487 - 849 N (3) 15-RdF32 AP Sr-90 Sq/sample -0.0991 (1) A U-234/233 Sq/sample 0.0211 0.0155 0.0109 - 0.0202 N (3)

U-238 Sq/sample 0.095 0.099 0.069- 0.129 A 15-GrF32 AP Gr-A Sq/sample 0.448 1.77 0.53 - 3.01 N (3)

Gr-S Sq/sample 0.7580 0.75 0.38 -1.13 A 15-RdV32 Vegetation Cs-134 Sq/sample 8.08 7.32 5.12 - 9.52 A Cs-137 Sq/sample 11.6 9.18 6.43 -11.93 w Co-57 Sq/sample -0.0096 (1) A Co-60 Sq/sample 6.53 5.55 3.89- 7.22 A Mn-54 Sq/sample 0.0058 (1) A Sr-90 Sq/sample 0.999 1.08 0.76 - 1.40 A Zn-65 Sq/sample -0.108 (1) A September 2015 15-MaW33 Water Am-241 Sq/L 1.012 1.055 0.739 - 1.372 A Ni-63 Sq/L 11.8 8.55 5.99 -11.12 N (4)

Pu-238 Sq/L 0.727 0.681 0.477 - 0.885 A Pu-239/240 Sq/L 0.830 0.900 0.630-1.170 A 15-MaS33 Soil Ni-63 Sq/kg 635 682 477 -887 A Sr-90 Sq/kg 429 425 298 - 553 A 15-RdF33 AP Sr-90 Sq/sample 1.48 2.18 1.53 -2.83 N (4)

U-234/233 Sq/sample 0.143 0.143 0.100-0.186 A U-238 Sq/sample 0.149 0.148 0.104-0.192 A 15-GrF33 AP Gr-A Sq/sample 0.497 0.90 0.27 -1.53 A Gr-S Sq/sample 1.34 1.56 0.78 - 2.34 A 15-RdV33 Vegetation Cs-134 Sq/sample 6.10 5.80 4.06- 7.54 A Cs-137 Sq/sample 0.0002 (1) A Co-57 Sq/sample 8.01 6.62 4.63 - 8.61 w Co-60 Sq/sample 4.97 4.56 3.19- 5.93 A Mn-54 Sq/sample 8.33 7.68 5.38 - 9.98 A Sr-90 Sq/sample 0.386 1.30 0.91 - 1.69 N (4)

(1) False positive test. Zn-65 Sq/sample 6.07 5.46 3.82- 7.10 A (2) Sensitivity evaluation.

(3) Soil Sr incomplete digestion of the sample resulted in low results; AP U-2341233 - extremely low activity was dffficult to quantify AP Gr-A - the MAPEP filter has the activity embedded in the filter. To coffected the low bias, TBE will create an attenuated efficiency for MAPEP samples. NCR 15-13 (4) Water Ni-63 extremely low activity was difficult to quantify; AP & Vegetation Sr-90 was lost during separation, possible from substance added by MAPEP NCR 15-21.

(a) Teledyne Brown Engineering reported result.

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

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

D-4

TABLE D-3.3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)

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

May 2015 RAD-101 Water Sr-89 pCi/L 45.2 63.2 51.1 - 71.2 N (1)

Sr-90 pCi/L 28.0 41.9 30.8 -48.1 N (1)

Ba-133 pCi/L 80.6 82.5 63.9 - 90.8 A Cs-134 pCi/L 71.7 75.7 61.8 - 83.3 A Cs-137 pCi/L 187 189 170 - 210 A Co-60 pCi/L 85.7 84.5 76.0-95.3 A Zn-65 pCi/L 197 203 183 - 238 A Gr-A pCi/L 26.1 42.6 22.1 - 54.0 A Gr-B pCi/L 28.8 32.9 21.3 -40.6 A 1-131 pCi/L 23.5 23.8 19.7 - 28.3 A U-Nat pCi/L 6.19 6.59 4.99- 7.83 A H-3 pCi/L 3145 3280 2770-3620 A MRAD-22 Filter Gr-A pCi/filter 28.3 62.2 20.8 - 96.6 A November 2015 RAD-103 Water Sr-89 pCi/L 40.9 35.7 26.7 -42.5 A Sr-90 pCi/L 29.3 31.1 22.7- 36.1 A Ba-133 pCi/L 31.5 32.5 25.9 - 36.7 A Cs-134 pCi/L 59.65 62.3 50.6-68.5 A Cs-137 pCi/L 156 157 141 - 175 A Co-60 pCi/L 70.6 71.1 64.0 - 80.7 A Zn-65 pCi/L 145 126 113-149 A Gr-A pCi/L 38.2 51.6 26.9-64.7 A Gr-B pCi/L 42.0 36.6 24.1 -44.2 A 1-131 pCi/L 24.8 26.3 21.9-31.0 A U-Nat pCi/L 146.90 56.2 45.7 - 62.4 N(2)

H-3 pCi/L 21100 21300 18700 - 23400 A MRAD-23 Filter Gr-A pCi/filter Lost during processing (1) Yield on the high side of our acceptance range indicates possibility of calcium interference. NCR 15-09 (2) Technician failed to dilute original sample. If dilulted, the result would have been 57.1, which fell within the acceptance limits. NCR 15-19 (a) Teledyne Brown Engineering reported result.

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

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

D-5

Intentionally left blank APPEN'DIX E ERRATA DATA

Intentionally left blank There is no errata data for 2015.

Intentionally left blank APPEND.IX 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 2015 Prepared By Teledyne Brown Engineering Environmental Services Dresden Nuclear Power Station Morris, IL 60450 May 2016

--- -

Intentionally left blank

Table of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ........................ ,..................................,.......................................................... 2 A. Obj,ectives of the RGPP ...................................................................................... 3 B. Implementation of the Objectives ........................................................................ 4 C. Program Description ............................ ~ .............................................................. 4 D. Characteristics of Tritium (H-3) ..................................,......................................... 4 111. 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 ............................................................................... 12 D. Drinking Water Well Survey .............................................................................. 12 E. Summary of Results- Inter-laboratory Comparison Program .......................... 12 F. Leaks, Spills, and Releases .............................................................................. 12 G. Trends ................................................................................................................ 12 H. Investigations .................................................................................................... 12 I. Actions Taken ...................................................................................................... 13

-i-

Appendices ARGPPR Appenqix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2015 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, 2015.

Table B-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table B-1.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table B-11.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

Table B-111.1 Concentrations of Tritium in Precipitation Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2015.

- ii -

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

The Dresden power plant has experienced leaks from underground lines and spills from systems containing radioactive water over its 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 in 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.

II. Introduction Radiological Groundwater Monitoring Program (RGPP):

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

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

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

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

There are 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.

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 constructured 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 2015, there were 580 analyses that were performed on 270 samples from 80 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 eleven 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-7 and/or boron-10 are activated to produce tritium.

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

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

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 2015.

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 fo summarize background measurements of tritium in various media performed by others. Additional detail may be found by consulting references (CRA 2006).

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

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

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

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

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

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

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

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

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

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

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

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

Tritium Following historic ground tritium-contamination events at Dresden Station (EN-DR-408-4160, Revision 4, Attachment 3), routine sampling and analyses continue, both inside and outside the protected areas.

Low level tritium was detected from January through December 2015 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, MW-DN-1241, MW-DN-124S, and MW-DN-126S are the only 4 locations with tritium concentrations above 20,000 pCi/L. The highest level ever reached during calendar year 2015 was 1,000,000 pCi/L by MD-11 (sample collected on 2/17/2015).

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 strontium-89 and strontium-90 activity (Table B-1.1, Appendix B). Strontium-89 was not detected in any of the samples. Strontium-90 was detected in two samples at location MW-DN-105S. The concentrations were 1.2 and 1.3 pCi/L.

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter of 2014 (Table B-1.1, Appendix B). Gross Alpha (dissolved) was detected at two groundwater locations. The concentrations were 4.3 and 5.2 pCi/L. Gross Alpha (suspended) was detected at one groundwater location at a concentration of 3.2 pCi/L. Gross Beta (dissolved) was detected at 31 of the groundwater locations. The concentrations ranged from 2.3 to 46.0 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations. The concentrations of Gross Alpha and Gross Beta, which are slightly above detectable levels, are considered to be background and are not the result of plant effluents.

Gamma Emitters Naturally-occurring K-40 was detected in one sample. No other gamma emitting nuclides were detected (Table B-1.2, Appendix B).

Hard-To-Detects Hard-To-Detect analyses were performed on two groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-233/234, U-235 and U-238. The isotopes U-233/234 and U-238 were detected at one of the two groundwater monitoring locations. The concentration of U-234 was 0.71 pCi/L and the concentration U-238 was 0.26 pCi/L (Table B-1.3, Appendix B). The concentrations detected are considered background.

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

B. Surface Water Results Surface Water Samples were collected from eleven 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 2,270 pCi/I.

The measurable concentrations of tritium are from an upstream source.

Strontium Samples were not analyzed for strontium activity (Table B-11.1. Appendix B).

Gross Alpha and Gross Beta (dissolved and suspended)

Samples were not analyzed for Gross Alpha and Gross Beta in 2015.

Gamma Emitters No gamma emitting nuclides were detected (Table B-11.2, Appendix B).

Hard-To-Detects Samples were not analyzed for Hard-To-Detect analyses in 2015.

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 2015.

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

F. Leaks, Spills, and Releases No leaks, spills, and releases occurred in 2015.

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 4, Attachment 3). Two remediation wells were installed in August 2015 to pump tritiated water out of the ground, and active remediation started in December 2015.

H. Investigations No investigations performed in 2015.

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 since December 2015.

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TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2015 Site Site Type Location DSP-105 Monitoring Well 30 feet east of the east wall of the EM Shop DSP-106 Monitoring Well 6.5 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 213 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 comer 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 210 feet south by southeast of the southeast corner of Maintenance Garage DSP-153 Monitoring Well 150 feet east of the southeast comer of liquid hydrogen tank farm fence, DSP-154 Monitoring Well 33 feet vvest 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 comer 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 213 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 0AfWT) Building MW-DN-110-S Monitoring Well 25 feet west of the Waste Water Treatment 0AfWT) Building 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 comer 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 '1z°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 MW-DN-121-S Monitoring Well 7 feet west of the dirt road; 42 feet east of the 345KV yard fence A-1

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2015 Site Site Type Location 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 213 B CST MW-DN-126-S Monitoring Well 15 feet south of fence around Unit 213 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 213 main chimney MW-DN-MD-11 Monitoring Well Piping located between Condensate Storage Tanks.

DSP-131 Surface Water Storm water- 35 ft NE of the Unit 213 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 fl SE of the Unit 1 diesel fuel transfer shed.

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 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 Cl:limney FW-7 Precipitation Southeast of Unit 2 TB Trackway FW-8 Precipitation Southwest comer 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 comer 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 corner of the Admin Building; on the security fence A-2

ARGPPR APPENDIX 8 DATA TABLES

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..--------------------------------~--------

TABLE B*l.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

CBG 11/30/15 Original 18500 +/- 1890 CBG 11/30/15 Recount 15100 +/- 1560 CBG 11/30/15 Rerun 14700 +/- 1520 DSP-105 02125/15 < 164 DSP-105 06/03/15 < 171 < 7.2 < 0.8 < 1.9 < 0.9 6.3 +/- 1.3 < 1.5 DSP-105 09/16/15 < 195 DSP-105 12117/15 < 193 DSP-106 02/25/15 1920 +/- 240 DSP-106 06/03/15 2180 +/- 269 < 8.5 < 0.7 < 1.6 < 0.9 4.6 +/- 1.1 < 1.5 DSP-106 09/16/15 1830 +/- 242 DSP-106 12117115 1760 +/- 241 DSP-107 02125/15 2410 +/- 288 DSP-107 06/03/15 2260 +/- 274 < 7.8 < 0.7 < 1.7 < 0.9 5.6 +/- 1.2 < 1.5 DSP-107 09/15/15 1810 +/- 241 DSP-107 12116/15 1990 +/- 263 DSP-108 02125/15 635 +/- 133 DSP-108 06/03/15 665 +/- 153 < 8.3 < 0.8 < 5.8 < 0.9 15.0 +/- 1.9 < 1.5 DSP-108 09/15/15 - 500 +/- 147 DSP-108 12/16/15 589 +/- 146 DSP-122 02124/15 1610 +/- 211 DSP-122 06/01115 933 +/- 168 DSP-122 09/14/15 883 +/- 167 DSP-122 11/16/15 1150 +/- 185 DSP-123 02125/15 1290 +/- 182 DSP-123 06/02115 1490 +/- 204 < 9.1 < 0.7 < 2.8 < 0.9 15.8 +/- 1.9 < 1.5 DSP-123 09/15/15 1100 +/- 175 DSP-123 12/16/15 1310 +/- 199 DSP-124 03/02/15 1350 +/- 189 DSP-124 06/09/15 2360 +/- 291 DSP-124 09/17/15 - 2540 +/- 310 DSP-124 12118/15 2500 +/- 311 DSP-125 02/17115 7780 +/- 785 DSP-125 06/09/15 2720 +/- 326 < 7.0 < 0.6 < 35.4 < 0.9 44.6 +/- 5.6 < 3.9 DSP-125 09/16/15 1810 +/- 240 DSP-125 11/30/15 1950 +/- 255 DSP-125 06/16/15 < 190 DSP-131 02124/15 302 +/- 129 DSP-131 06/01/15 293 +/- 135 DSP-131 09/14/15 < 190 DSP-131 12/16/15 305 +/- 135 DSP-132 02124/15 2140 +/- 261 DSP-132 06/01115 3630 +/- 411 DSP-132 09/15/15 3880 +/- 442 DSP-132 11/19/15 Original 230 +/- 134 DSP-132 11119/15 Recount 297 +/- 132 DSP-132 11/19/15 Rerun 308 +/- 133 DSP-133 06/15/15 < 195 DSP-133 11/17115 < 195 DSP-147 06115115 < 190 DSP-148 03/03/15 237 +/- 121 DSP-148 06/16115 < 191 DSP-148 09111/15 193 +/- 126 DSP-148 12/15/15 < 192 DSP-149R 03/03115 489 +/- 138 DSP-149R 06116115 388 +/- 135 DSP-149R 09/11115 326 +/- 134 DSP-149R 12/15/15 494 +/- 144 B-1

TABLE B*l.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/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-150 03/02/15 < 173 DSP-150 06/03/15 < 189 DSP-150 09/16/15 < 194 DSP-150 12/17/15 < 189 DSP-151 03/02/15 < 187 DSP-151 06/03/15 < 187 DSP-151 09/16/15 < 193 D8P-151 12/17/15 < 192 D8P-154 06/15/15 < 189 D8P-156 03/03/15 < 175 D8P-156 06/16/15 230 +/- 132 D8P-156 09/11/15 Original 193 +/- 126 D8P-156 09/11/15 Recount 238 +/- 130 D8P-156 12/15/15 < 193 D8P-1571 06/16/15 < 188 D8P-1578 06/16/15 < 190 D8P-1591 06/16/15 243 +/- 134 D8P-1598 06/16/15 < 192 MD-11 02/17/15 1000000 +/- 103000 MD-11 11/30/15 800000 +/- 74700 < 5.2 < 0.6 < 1.0 < 0.7 26.9 +/- 1.7 < 1.4 MW-DN-1011 02/24/15 726 +/- 151 MW-DN-1011 06/02/15 813 +/- 162 < 7.8 < 0.6 < 1.3 < 0.9 10.6 +/- 1.3 < 1.5 MW-DN-1011 09/15/15 612 +/- 152 MW-DN-1011 12/16/15 653 +/- 149 MW-DN-1018 02/24/15 < 178 MW-DN-1018 06/02/15 < 179 < 7.7 < 0.7 4.3 +/- 2.4 < 1.0 15.6 +/- 2.8 < 1.6 MW-DN-101S 09/15/15 < 195 MW-DN-1018 12/16/15 < 193 MW-DN-1021 03/13/15 < 182 MW-DN-1021 06/09/15 < 168 < 6.2 < 0.6 < 4.1 < 0.4 9.2 +/- 1.6 < 1.6 MW-DN-1021 09/17/15 < 195 MW-DN-1021 12/18/15 < 191 MW-DN-1028 03/13/15 < 185 MW-DN-1028 06/09/15 < 173 < 5.6 < 0.6 < 28.3 < 2.1 46.0 +/- 18.7 < 3.8 MW-DN-102S 09/17/15 < 190 MW-DN-1028 12/18/15 < 194 MW-DN-1031 06/16/15 < 192 MW-DN-1038 06/16/15 < 190 MW-DN-1048 02/24/15 < 178 MW-DN-1048 06/01/15 < 186 MW-DN-1048 09/14/15 Original 320 +/- 135 MW-DN-1048 09/14/15 Recount 202 +/- 131 MW-DN-1048 09/14/15 Rerun 420 +/- 135 MW-DN-1048 11/16/15 Original 452 +/- 143 MW-DN-1048 11/16/15 Recount 406 +/- 145 MW-DN-1048 11/16/15 Rerun 472 +/- 143 MW-DN-1058 03/02/15 < 176 < 1.9 1.3 +/- 0.0 MW-DN-1058 06/03/15 < 182 < 7.4 < 0.7 MW-DN-1058 09/16/15 < 191 < 4.5 < 0.7 MW-DN-1058 12/17/15 Original < 193 < 4.8 1.2 +/- 1.0 MW-DN-1058 12/17/15 Recount 1.2 +/- 1.0 MW-DN-1068 06/16/15 < 183 MW-DN-1078 02/16115 186 +/- 120 MW-DN-1078 06/08/15 < 174 MW-DN-1078 09/17115 267 +/- 136 MW-DN-1078 11130115 < 191 MW-DN-1081 02/24115 < 177 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, 2015 RESULTS IN UNITS OF PCl/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-1081 06/02/15 < 172 < 7.6 < 0.8 < 1.9 < 1.2 19.3 +/- 1.9 < 1.5 MW-DN-1081 09/15/15 < 195 MW-DN-1081 11/23/15 < 191 MW-DN-1081 12118/15 < 188 MW-DN-1091 02118/15 < 177 MW-DN-1091 06/01/15 518 +/- 143 < 7.6 < 0.6 < 3.8 < 0.5 7.9 +/- 1.2 < 1.4 MW-DN-1091 09/14/15 < 190 MW-DN-1091 11/16/15 < 199 MW-DN-109S 02118/15 < 177 MW-DN-109S 06/01/15 296 +/- 133 < 7.3 < 0.6 < 2.0 < 0.5 13.7 +/- 2.8 < 1.4 MW-DN-109S 09/14/15 < 196 MW-DN-109S 11/16/15 < 199 MW-DN-110I 02118/15 < 177 MW-DN-1101 06/01/15 < 181 MW-DN-110I 09/14/15 < 194 MW-DN-110I 11/16/15 < 196 MW-DN-110S 02118/15 < 177 MW-DN-110S 06/01/15 < 184 MW-DN-110S 09/14/15 < 191 MW-DN-110S 11/16/15 < 198 MW-DN-111S 03/02115 < 156 MW-DN-111S 06/09/15 182 +/- 116 MW-DN-111S 09/17/15 < 193 MW-DN-111S 12118/15 < 185 MW-DN-1121 02118/15 < 178 MW-DN-1121 06/01/15 < 183 MW-DN-1121 09/14/15 < 196 MW-DN-1121 11/16/15 < 197 MW-DN-112S 02118/15 < 175 MW-DN-1128 06/01/15 < 187 MW-DN-112S 09/14/15 < 192 MW-DN-112S 11/16/15 < 195 MW-DN-1131 02117/15 < 172 MW-DN-1131 06/08/15 < 174 < 6.8 < 0.6 < 1.5 < 0.4 4.8 +/- 1.2 < 1.6 MW-DN-1131 09/17/15 < 197 MW-DN-1131 12/18/15 < 187 MW-DN-113S 02/17/15 < 177 MW-DN-113S 06/08/15 < 177 < 8.4 < 0.6 < 1.5 3.2 +/- # 6.5 +/- 1.2 < 1.7 MW-DN-113S 09/17/15 < 192 MW-DN-113S 12118/15 < 186 MW-DN-1141 02116/15 6040 +/- 645 MW-DN-1141 06/08/15 8260 +/- 873 MW-DN-1141 09/16/15 7630 +/- 812 MW-DN-1141 12117/15 Original < 187 MW-DN-1141 12117/15 Recount < 191 MW-DN-114S 02/16/15 < 185 MW-DN-114S 06/08/15 < 172 MW-DN-114S 09/16/15 < 196 MW-DN-114S 12117/15 Original 10700 +/- 1110 MW-DN-114S 12/17/15 Recount 10900 +/- 1140 MW-DN-114S 12117/15 Rerun 11600 +/- 1200 MW-DN-1151 03/02/15 471 +/- 124 MW-DN-1151 06/03/15 471 +/- 142 MW-DN-1151 09/16/15 330 +/- 133 MW-DN-1151 12117/15 343 +/- 133 MW-DN-115S 03/02/15 < 180 MW-DN-115S 06/03/15 < 177 B-3

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, 2015 RESULTS IN UNITS OF PCl/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-115S 09/16/15 < 189 MW-DN-115S 12117/15 < 190 MW-DN-1161 02124/15 266 +/- 132 MW-DN-1161 06/02115 336 +/- 135 < 6.1 < 0.6 < 4.2 < 0.5 23.6 +/- 2.2 < 1.4 MW-DN-1161 09/15/15 < 189 MW-DN-1161 11/23/15 288 +/- 132 MW-DN-1161 12/22/15 493 +/- 140 MW-DN-116S 02124/15 214 +/- 127 MW-DN-116S 06/02115 243 +/- 127 < 6.4 < 0.7 5.2 +/- 1.8 < 0.5 11.6 +/- 1.5 < 1.4 MW-DN-116S 09/15/15 < 188 MW-DN-116S 11/23/15 396 +/- 138 MW-DN-116S 12122115 186 +/- 123 MW-DN-1171 12/16/15 < 185 MW-DN-1171R 09/15/15 < 191 < 2.3 < 0.6 < 0.9 < 0.7 14.7 +/- 1.5 < 1.8 MW-DN-118S 02/25/15 316 +/- 135 MW-DN-118S 06/03/15 561 +/- 146 < 5.4 < 0.8 < 0.9 < 0.5 7.9 +/- 1.3 < 1.4 MW-DN-118S 09/15/15 217 +/- 127 MW-DN-118S 12116/15 307 +/- 131 MW-DN-1191 02125/15 < 187 MW-DN-1191 06/02/15 < 183 < 5.2 < 0.5 < 3.2 < 0.5 28.9 +/- 2.4 < 1.4 MW-DN-1191 09/16/15 < 191 MW-DN-1191 12116/15 < 188 MW-DN-119S 02125/15 < 191 MW-DN-119S 06/02/15 < 181 < 5.3 < 0.6 < 5.0 < 0.5 21.0 +/- 3.1 < 1.4 MW-DN-119S 09/16/15 < 189 MW-DN-119S 12116/15 < 187 MW-DN-1221 06/15/15 < 195 MW-DN-122S 06/15/15 < 193 MW-DN-1241 02116/15 37700 +/- 3790 MW-DN-1241 06/09/15 33700 +/- 3410 < 7.2 < 0.6 < 4.1 < 1.3 24.9 +/- 4.0 < 3.9 MW-DN-1241 09/17/15 34100 +/- 3460 MW-DN-1241 12/18/15 32800 +/- 3320 MW-DN-124S 02116/15 20200 +/- 2050 MW-DN-124S 06/09/15 8790 +/- 926 < 5.8 < 0.5 < 5.8 < 1.3 36.7 +/- 4.6 < 3.9 MW-DN-124S 09/17/15 6080 +/- 661 MW-DN-124S 12118/15 4090 +/- 463 MW-DN-125S 02117/15 < 189 MW-DN-125S 06/08/15 < 177 < 5.8 < 0.7 < 1.4 < 1.9 < 2.5 < 3.6 MW-DN-125S 09/17/15 < 193 MW-DN-125S 12/18/15 < 187 MW-DN-126S 02116/15 21000 +/- 2140 MW-DN-126S 06/08/15 5380 +/- 585 < 7.5 < 0.6 < 6.7 < 1.3 16.5 +/- 4.0 < 3.9 MW-DN-126S 09/17/15 Original 8740 +/- 926 MW-DN-126S 09/17/15 Recount 7730 +/- 819 MW-DN-126S 09/17/15 Rerun 8130 +/- 857 MW-DN-1268 11/30/15 4080 +/- 461 MW-DN-1278 02116/15 1070 +/- 171 MW-DN-1278 06/08/15 670 +/- 139 < 6.5 < 0.7 < 1.1 < 1.3 2.3 +/- 1.0 < 2.5 MW-DN-1278 09/17/15 199 +/- 129 MW-DN-1278 12118/15 Original 524 +/- 141 MW-DN-1278 12118/15 Recount 614 +/- 148 MW-DN-1348 03/02/15 < 156 MW-DN-1348 06/15/15 < 195 < 6.2 < 0.7 < 3.8 < 0.3 12.6 +/- 1.8 < 1.4 MW-DN-1348 09/11/15 < 193 MW-DN-1348 11/18/15 < 197 MW-DN-1358 03/02/15 < 153 MW-DN-1358 06/15/15 < 195 < 6.7 < O.B < 1.7 < 0.3 8.8 +/- 1.4 < 1.4 B-4

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, 2015 RESULTS IN UNITS OF PCl/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-135S 09/11/15 < 191 MW-DN-135S 11/18/15 < 195 MW-DN-136S 03/02/15 < 152 MW-DN-136S 06/15/15 < 193 < 4.1 < 0.8 < 6.5 < 0.3 23.4 +/- 3.8 < 1.4 MW-DN-136S 09/11/15 < 186 MW-DN-136S 11/18/15 < 195 MW-DN-137S 03/02/15 < 157 MW-DN-137S 09/11/15 < 187 MW-DN-137S 11/18/15 < 192 < 5.6 < 0.7 < 5.6 < 0.4 26.2 +/- 2.2 < 1.4 MW-DN-140S 02124/15 367 +/- 137 MW-DN-140S 06/02/15 747 +/- 157 MW-DN-140S 09/14/15 534 +/- 143 MW-DN-140S 11/16/15 762 +/- 154 MW-DN-141S 02/24/15 681 +/- 158 MW-DN-141S 06/02/15 3640 +/- 409 < 5.3 < 0.5 < 1.3 < 0.5 25.8 +/- 2.0 < 1.4 MW-DN-141S 09/14/15 3050 +/- 364 MW-DN-1418 11/16/15 3200 +/- 377 B-5

TABLE B*l.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn;54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DATE DSP-105 02/25/15 < 49 < 98 < 5 < 5 < 12 < 5 < 12 < 6 <9 < 14 <5 <5 < 33 < 10 DSP-105 06/03/15 < 31 < 63 < 3 < 3 <8 <4 <6 <4 <6 < 10 <3 <4 < 22 < 8 DSP-105 . 09/16/15 < 58 < 107 <6 < 7 < 16 <7 < 16 < 9 < 12 < 12 <7 <:7 <*35 < 13 DSP-105 12/17/15 < 40 < 41 <4 <5 < 9 <4 <6 < 5 <7 < 13 <4 <5 < 31 < 8 DSP-106 02/25/15 < 42 < 108 <5 < 6 < 11 <4 <9 < 5 < 8 < 14 <4 <5 < 31 <7 DSP-106 06/03/15 < 31 < 68 < 3 < 3 <7 < 3 <6 <4 <6 <7 <3 <3 < 17 <6 DSP-106 09/16/15 < 71 < 148 < 5 < 5 < 12 < 8 < 14 < 6 < 15 < 14 <6 <7 < 29 < 10 DSP-106 12/17/15 < 41 < 69 <4 < 4 <8 <3 <6 < 5 < 8 < 15 < 3 <4 < 28 < 7 DSP-107 02/25/15 < 41 < 79 < 5 < 5 < 11 <5 < 10 <4 < 8 < 13 <4 <5 < 30 < 12 DSP-107 06/03/15 < 28 < 27 < 3 < 3 <7 <3 < 6 < 3 <6 <7 <3 <3 < 17 <6 DSP-107 09/15/15 < 44 < 61 <7 <6 < 16 < 5 < 12 < 7 < 9 < 11 <5 <6 < 35 < 11 DSP-107 12/16/15 < 33 < 74 < 3 <4 <8 < 4 < 8 < 4 < 7 < 13 <3 < 3 < 26 < 10 DSP-108 02/25/15 < 41 < 35 <4 <4 <8 <4 <7 <4 < 8 < 13 <4 <4 < 29 < 8 DSP-108 06/03/15 < 44 < 78 <4 <5 < 12 <4 < 9 < 5 <8 < 13 <5 <4 < 32 <9 to I DSP-108 09/15/15 < 58 < 73 <7 < 7 < 15 <7 < 17 < 8 < 16 < 13 <7 < 9 < 35 < 14 O'\

DSP-108 12/16/15 < 39 < 88 <4 < 5 < 10 < 5 < 10 < 5 < 9 < 15 <5 <4 < 32 < 12 DSP-123 02/25/15 < 44 < 45 <4 < 5 < 10* < 5 < 10 < 6 < 9 < 14 <4 <4 < 31 < 10 DSP-123 06/02/15 < 38 < 76 < 3 <4 <8 < 3 <7 <4 < 7 < 10 <3 <4 < 24 < 8 DSP-123 09/15/15 < 53 < 55 <6 < 6 < 15 <6 < 13 < 7 < 10 < 11 <5 <6 < 31 < 11 DSP-123 12/16/15 < 40 < 46 <4 <4 < 10 <4 < 8 < 5 <8 < 14 <4 <4 < 30 < 11 DSP-125 06/09/15 < 17 < 31 <2 < 2 <4 <2 < 3 <2 <4 <6 <2 <2 < 13 <4 DSP-126 06/16/15 < 40 < 33 <4 <4 < 10 <4 < 8 <4 < 8 < 14 <4 <4 < 30 < 10 DSP-131 06/01/15 < 48 < 49 <5 < 5 < 12 < 6 < 11 < 6 < 10 < 15 <5 <5 < 36 < 12 DSP-132 06/01/15 < 36 < 47 <4 < 4 < 10 <4 < 10 <5 < 8 < 13 <4 <4 < 29 < 13 DSP-133 06/15/15 < 46 < 88 < 5 < 5 < 12 <6 < 11 < 7 <9 < 15 < 5 < 5 < 31 < 12 DSP-133 11/17/15 < 32 < 73 <3 < 3 <6 <3 <7 < 3 <6 <6 <3 <4 < 18 <6 DSP-147 06/15/15 < 40 < 79 <4 < 5 < 10 <4 < 9 < 5 < 9 < 15 <4 <4 < 29 <9 DSP-154 06/15/15 < 41 < 79 <4 < 5 < 12 <4 < 11 < 5 < 8 < 14 <4 <4 < 29 < 10 DSP-1571 06/16/15 < 40 < 94 <4 < 5 < 10 < 5 < 9 < 5 < 8 < 14 <4 <4 < 30 < 10 DSP-1578 06/16/15 < 46 < 73 < 5 < 6 < 12 < 6 < 8 < 5 < 9 < 13 <5 <6 < 40 < 10 DSP-1591 06/16/15 < 33 < 41 < 3 < 4 < 10 <4 < 7 <4 < 8 < 13 <4 <3 < 28 < 11 DSP-1598 06/16/15 < 16 < 15 < 1 <2 <4 <2 < 3 <2 <3 <7 < 1 <2 < 13 < 5 MD-11 11/30/15 < 42 < 40 <4 <5 < 10 < 5 < 9 < 5 < 8 < 12 <4 <4 < 28 < 8 MW-DN-1011 02/24/15 < 37 < 72 <4 <4 < 10 < 5 < 9 < 5 < 8 < 13 <4 <4 < 30 < 10 MW-DN-1011 06/02/15 < 47 < 83 <4 < 5 < 10 <4 < 12 < 5 < 9 < 15 <4 <5 < 32 < 10 MW-DN-1011 09/15/15 < 75 < 71 < 8 < 6 < 12 < 5 < 18 < 7 < 9 < 11 <6 <8 < 44 < 11 MW-DN-1011 12/16/15 < 37 < 72 < 4 < 4 <9 <4 < 8 < 5 < 7 < 15 <4 <4 < 29 < 8 MW-DN-1018 02/24/15 < 35 < 73 < 4 <4 <8 <4 < 8 <4 < 7 < 13 <4 <4 < 27 < 7 MW-DN-1018 06/02/15 < 42 < 82 <4 < 5 < 9 <4 < 8 <4 <8 < 14 <4 <4 < 27 < 9 MW-DN-1018 09/15/15 < 71 < 109 < 8 < 7 < 14 <9 < 18 < 7 < 13 < 14 <6 < 9 < 40 < 10 MW-DN-1018 12/16/15 < 44 < 75 <4 <4 < 10 < 5 < 8 < 5 < 8 < 15 <4 <5 < 31 < 13

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DATE MW-DN-1021 06/09/15 < 15 < 28 < 2 < 2 <4 <2 <3 <2 < 3 <5 <2 <2 < 11 <4 MW-DN-1028 06/09/15 < 22 < 21 < 2 < 3 < 5 <2 <4 < 3 <4 <7 <2 <2 < 16 < 5 MW-DN-1031 06/16/15 < 16 < 15 < 2 < 2 <4 <2 <3 < 2 <3 <7 <2 <2 < 14 < 5 MW-DN-1038 06/16/15 < 16 < 35 < 2 < 2 <4 < 2 <3 < 2 < 3 <7 < 1 <2 < 13 < 5 MW-DN-1068 06/16/15 < 13 < 24 < 1 < 1 < 3 < 1 <3 < 1 < 3 <6 <1 < 1 < 12 <4 MW-DN-1081 02/24/15 < 42 < 42 < 4 < 4 < 10 <4 <8 < 5 < 8 < 12 <4 <4 < 28 < 10 MW-DN-1081 06/02115 < 42 < 44 < 3 < 5 <9 <5 <8 < 5 <8 < 13 <4 <5 < 27 < 12 MW-DN-1081 09/15/15 < 58 < 150 <7 < 7 < 15 <9 < 13 < 7 < 11 < 15 <6 < 9 < 33 < 14 MW-DN-1081 12/18/15 < 50 < 53 < 5 <5 < 11 <3 < 10 < 6 < 8 < 15 <5 < 6 < 36 < 10 MW-DN-1091 06/01/15 < 40 < 44 <4 <4 < 12 <4 <7 < 5 <8 < 14 <4 < 5 < 32 < 9 MW-DN-1098 06/01/15 < 36 < 34 <4 < 3 <7 <3 <8 <4 <7 < 11 <3 < 3 < 29 < 8 MW-DN-1131 06/08/15 < 24 < 56 < 2 < 3 <6 <3 <5 < 3 <5 <8 <2 < 3 < 17 <5 MW-DN-1138 06/08/15 < 19 < 41 < 2 <2 <5 <2 <4 < 2 <4 <6 <2 <2 < 13 <4 MW-DN-1161 02/24/15 < 21 < 19 < 2 < 2 <5 <2 <4 <2 <4 <7 <2 <2 < 15 <4 to MW-DN-1161 06/02115 < 30 < 20 < 3 <4 <7 < 3 <6 <3 <6 < 10 <3 <3 < 22 < 8

~

MW-DN-1161 09/15/15 < 53 < 71 < 6 < 6 < 13 < 8 < 13 <7 < 11 < 13 <6 < 8 < 38 < 11 MW-DN-1161 12/22115 < 62 < 68 < 7 < 7 < 15 <7 < 17 <8 < 14 < 15 <7 <8 < 42 < 13 MW-DN-1168 02/24/15 < 19 < 20 < 2 <2 < 5 <2 <4 < 2 <4 <7 <2 <2 < 15 < 5 MW-DN-1168 06/02115 < 35 < 76 < 3 <3 <9 <3 <6 <4 <6 < 12 <4 <4 < 23 < 7 MW-DN-1168 09/15/15 < 66 < 57 < 6 <7 < 13 <5 < 13 < 6 < 11 < 13 <7 <6 < 40 < 11 MW-DN-1168 12/22115 -< 41 < 36 < 5 <5 < 11 <4 < 10 < 5 <8 < 12 <5 <6 < 25 < 5 MW-DN-1171 12/16/15 < 28 < 57 < 3 < 3 <8 < 3 <6 < 3 <6 < 10 < 3 < 3 < 22 <8 MW-DN-1171R 09/15/15 < 60 < 77 <6 < 7 < 14 <7 < 13 < 7 < 12 < 12 <7 < 7 < 34 < 12 MW-DN-1188 02/25/15 < 14 < 32 < 1 < 1 <3 < 1 <3 < 2 <3 < 14 < 1 < 1 < 21 <6 MW-DN-1188 06/03/15 < 49 < 107 < 4 <4 < 10 <5 < 8 < 5 < 8 < 15 <4 <5 < 33 < 10 MW-DN-1188 09/15/15 < 60 < 89 < 6 < 7 < 16 <7 < 15 <7 < 13 < 13 < 6 <7 < 36 < 11 MW-DN-1188 12/16/15 < 23 < 43 < 2 < 3 < 6 <2 < 5 < 3 <4 <8 <2 <2 < 17 < 5 MW-DN-1191 06/02115 < 49 < 59 < 6 <6 < 13 <6 < 12 < 7 < 11 < 15 <5 <6 < 40 < 11 MW-DN-1198 06/02115 < 36 < 36 < 4 < 5 < 8 <4 < 9 <4 < 7 < 11 <4 <4 < 27 < 8 MW-DN-1221 06/15/15 < 13 < 13 < 1 < 1 < 3 < 1 <3 < 1 < 3 <6 < 1 < 1 < 12 <4 MW-DN-1228 06/15/15 < 17 < 27 < 1 <2 <4 < 1 <3 < 2 <3 <8 <2 <2 < 15 <4 MW-DN-1241 06/09/15 < 26 183 +/- 35 < 3 < 3 <6 <3 <6 < 3 < 5 <7 < 3 < 3 < 17 <6 MW-DN-1241 12/18/15 < 38 < 40 < 4 <4 <8 <3 <7 <5 < 8 < 15 <4 <4 < 30 < 8 MW-DN-1248 06/09/15 < 21 < 43 < 2 < 3 <5 <3 <5 < 3 <4 <7 < 2 < 2 < 16 < 5 MW-DN-1248 12/18/15 < 23 < 22 < 2 < 2 < 5 <2 <4 < 2 <4 <8 <2 <2 < 16 <4 MW-DN-1258 06/08/15 < 23 < 23 < 3 < 3 <5 <2 < 5 < 3 < 5 <8 <2 <2 < 18 < 5 MW-DN-1268 06/08/15 < 20 < 25 < 2 <2 <5 <2 <5 < 2 <4 <6 <2 <2 < 14 < 5 MW-DN-1278 06/08/15 < 18 < 15 < 2 <2 <4 <2 <4 << 2 <3 <6 <2 <2 < 14 <4 MW-DN-1348 06/15/15 < 15 < 12 < 1 < 2 <3 < 1 < 3 < 2 <3 <7 < 1 < 1 < 14 <4 MW-DN-1358 06/15/15 < 17 < 26 <2 <2 <4 <2 <3 < 2 <3 <8 < 1 <2 < 15 < 5 MW-DN-1368 06/15/15 < 40 < 30 <4 <4 < 11 <4 <9 < 5 <8 < 14 <4 < 5 < 28 < 9 L__ __

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DATE MW-DN-1378 11/18/15 < 30 < 67 <4 < 3 <8 <4 < 9 <4 <6 <7 <4 <4 < 17 <6 MW-DN-1418 06/02/15 < 42 < 43 <4 <4 <9 <4 <7 < 5 <7 < 14 <4 <4 < 36 < 6 to I

00

l TABLE B-1.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 Fe-55 Ni-tl3 DATE MW-DN-1241 06/09/15 < 0.17 < 0.03 < 0.12 < 0.04 < 0.10 < 0.09 < 0.09 < 0.05 < 139 < 3.6 MW-DN-124S 06/09/15 Original < 0.07 < 0.07 < 0.04 < 0.09 < 0.07 0.52 +/- 0.21 < 0.11 < 0.09 < 164 < 2.9 MW-DN-124S 06/09/15 Recount 0.55 +/- 0.22 < 0.03 0.26 +/- 0.14 MW-DN-124S 06/09/15 Rerun 0.71 +/- 0.25 < 0.06 0.26 +/- 0.15

TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE_ VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 CBE 12/17/15 < 188 SW-DN-101 03/03/15 373 +/- 117 SW-DN-101 06/15/15 < 192 SW-DN-101 09/11/15 < 185 SW-DN-101 11/17/15 2070 +/- 267 SW-DN-101 11/17/15 1720 +/- 237 SW-DN-101 11/17/15 2270 +/- 288 SW-DN-101 12/14/15 1120 +/- 178 SW-DN-102 03/03/15 312 +/- 114 SW-DN-102 06/15/15 526 +/- 149 SW-DN-102 09/11/15 327 +/- 129 SW-DN-'102 11/17/15 789 +/- 153 SW-DN-102 11/17/15 701 +/- 158 SW-DN-102 11/17/15 1060 +/- 175 SW-DN-103 03/03/15 337 +/- 115 SW-DN-103 06/15/15 346 +/- 141 SW-DN-103 09/11/15 < 189 SW-DN-103 11/17/15 1090 +/- 177 SW-DN-103 11/17/15 929 +/- 171 SW-DN-103 11/17/15 1170 +/- 186 SW-DN-104 03/03/15 438 +/- 122 SW-DN-104 06/15/15 596 +/- 154 SW-DN-104 09/11/15 395 +/- 140 SW-DN-104 11/17115 1200 +/- 186 SW-DN-104 11/17/15 946 +/- 171 SW-DN-104 11/17/15 1520 +/- 219 SW-DN-105 03/03/15 370 +/- 117 SW-DN-105 06/15/15 < 194 SW-DN-105 09/11/15 < 189 SW-DN-105 11/17/15 1270 +/- 193 SW-DN-105 11/17/15 1190 +/- 189 SW-DN-105 11/17/15 1440 +/- 209 SW-DN-106 03/03/15 396 +/- 119 SW-DN-106 06/15/15 609 +/- 154 SW-DN-106 09/11/15 848 +/- 160 SW-DN-106 09/11/15 928 +/- 164 SW-DN-106 09/11/15 817 +/- 158 B-10

l TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DATE SW-DN-101 06/15/15 < 19 < 17 <2 <2 <5 <2 <4 <2 <4 <9 <2 <2 < 18 <6 SW-DN-102 06/15/15 < 18 < 37 <2 <2 <4 <2 <4 < 2 <4 <9 <2 <2 < 17 <6 SW-DN-103 06/15/15 < 14 < 16 <2 <2 <4 <2 <3 < 2 <3 < 7 < 1 < 1 < 14 < 5 SW-DN-104 06/15/15 < 39 < 81 <4 <4 <9 <4 <7 <4 <8 < 14 <4 <4 < 29 < 11 SW-DN-105 06/15/15. < 15 < 28 < 1 <2 <3 < 1 < 3 <2 < 3 <8 < 1 < 1 < 14 <4 SW-DN-106 06/15/15 < 15 < 13 < 1 <2 <4 < 1 < 3 < 2 <3 <7 < 1 < 1 < 14 < 5

TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 FW-1 06/01/15 < 190 FW-10 06/02/15 < 188 FW-11 06/03/15 < 182 FW-12 06/08/15 < 175 B-12

Docket No: 50-01 O 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Environmental Operating Report 1 January Through 31 December 2015 Prepared By Teledyne Brown Engineering Enviromnental Services

rsar 6 ~~ ExelonGeneration~