Text

2014 Annual Radiological Environmental Operating Report
	ML15138A135
Person / Time
Site:	Dresden
Issue date:	05/14/2015
From:	Marik S; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	SVPLTR# 15-0034
	Download: ML15138A135 (135)
	v • d • e

nDresden Nuclear Power Station 16500 North Dresden Road Exelon Generation Moris, IL60450 815-942-2920 Telephone www.exeloncorp.comn May 14, 2015 SVPLTR# 15-0034 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station Units 1, 2, and 3 Facility Operation License No. DPR-2 Renewed Facility Operating License Nos. DPR-1 9 and DPR-25 NRC Docket Nos.50-010, 50-237, and 50-249

Subject:

Dresden Nuclear Power Station 2014 Annual Radiological Environmental Operating Report Enclosed is the Exelon Dresden Nuclear Power Station 2014 Annual Radiological Environmental Operating Report, submitted in accordance with Section 6.9.A.3 of the Unit 1 Dresden Nuclear Power Station Technical Specifications and Section 5.6.2, "Annual Radiological Environmental Operation Report," of the Units 2 and 3 Technical Specifications. This report provides the results of the radiological environmental monitoring program for the 2014 calendar year.

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

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

Respectfully, Site Vice President Dresden Nuclear Power Station Attachment - Annual Radiological Environmental Operating Report cc:

Regional Administrator - NRC Region III NRC Senior Resident - Dresden Nuclear Power Station

/10- S'SZ-cb

Docket No:

50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Environmental Operating Report 1 January Through 31 December 2014 Prepared By Teledyne Brown Engineering Environmental Services AmWExelon Generation.,

Dresden Nuclear Power Station Morris, IL 60450 May 2015

Intentionally left blank

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

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

4 A. Objectives of the REM P..................................................................................

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

4 III. Program Description................................................................................................

5 A. Sam ple Collection...........................................................................................

5 B. Sam ple Analysis............................................................................................

6 C. Data Interpretation.........................................................................................

7 D. Program Exceptions.......................................................................................

8 E. Program Changes.........................................................................................

11 IV. Results and Discussion.........................................................................................

11 A. Aquatic Environm ent....................................................................................

11

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

11

2. Ground W ater.....................................................................................

12

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

13

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

13 B. Atmospheric Environm ent...........................................................................

14

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

14

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

14

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

15

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

15

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

15

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

15 C. Am bient Gam m a Radiation...........................................................................

16 D. Land Use Survey..........................................................................................

16 E. Errata Data..................................................................................................

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

17 i

Appendices Appendix A Tables Table A-1 Appendix B Tables Table B-1 Table B-2 Figures Figure B-1 Figure B-2 Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Table C-11.1 Table C-11.2 Radiological Environmental Monitoring Report Summary (Meets requirements of NUREG 1302)

Radiological Environmental Monitoring Program Annual Summary for the Dresden Nuclear Power Station, 2014 Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2014 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2014 Dresden Station Inner Ring OSLD Locations, Fish, Water, and Sediment Locations, 2014 Dresden Station Fixed Air Sampling and OSLD Sites, Outer Ring OSLD Locations and Milk Location, 2014 Data Tables and Figures - Primary Laboratory Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

ii

Table C-111.1 Table C-IV.1 Table C-V.1 Table C-V.2 Table C-V.3 Table C-VI.1 Table C-VII. 1 Table C-VII.2 Table C-VIII.1 Table C-IX.1 Table C-IX.2 Table C-IX.3 Figures Figure C-1 Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Monthly and Yearly Mean Values of Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Quarterly OSLD Results for Dresden Nuclear Power Station, 2014.

Mean Quarterly OSLD Results for the Inner Ring, Outer Ring, Other and Control Locations for Dresden Nuclear Power Station, 2014.

Summary of the Ambient Dosimetry Program for Dresden Nuclear Power Station, 2014.

Surface Water - Gross Beta - Station D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2014.

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

Collected in the Vicinity of DNPS, 2003 - 2014.

Surface Water - Gross Beta - Stations D-21 and D-51Collected in the Vicinity of DNPS, 2000 - 2014.

Surface Water - Tritium - Station D-52 (C) Collected in the Vicinity of DNPS, 2000 - 2014.

Surface Water - Tritium - Station D-54 (C) and D-57 (C) Collected in the Vicinity of DNPS, 2003 - 2014.

Surface Water - Tritium - Stations D-21 and D-51 Collected in the Vicinity of DNPS, 2000 - 2014.

iii

Figure C-7 Figure C-8 Figure C-9 Figure C-10 Figure C-1 1 Figure C-12 Figure C-13 Figure C-14 Figure C-1 5 Appendix D Ground Water - Tritium - Stations D-23 and D-35 Collected in the Vicinity of DNPS, 2000 - 2014.

Air Particulate - Gross Beta - Stations D-01 and D-02 Collected in the Vicinity of DNPS, 2000 - 2014.

Air Particulate - Gross Beta - Stations D-03 and D-04 Collected in the Vicinity of DNPS, 2000 - 2014.

Air Particulate - Gross Beta - Stations D-07 and D-12 (C) Collected in the Vicinity of DNPS, 2000 - 2014.

Air Particulate - Gross Beta - Stations D-45 and D-53 Collected in the Vicinity of DNPS, 2000 - 2014.

Air Particulate - Gross Beta - Stations D-08 and D-1 0 Collected in the Vicinity of DNPS, 2005 - 2014.

Air Particulate - Gross Beta - Stations D-13 and D-14 Collected in the Vicinity of DNPS, 2005 - 2014.

Air Particulate - Gross Beta - Stations D-55 and D-56 Collected in the Vicinity of DNPS, 2006 - 2014.

Air Particulate - Gross Beta - Station D-58 Collected in the Vicinity of DNPS, 2011 - 2014.

Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2014 Table D-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2014 Table D-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2014 Appendix E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv

1.

Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Dresden Nuclear Power Station (DNPS) by Exelon covers the period 1 January 2014 through 31 December 2014. During that time period 1,924 analyses were performed on 1,839 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 2014, the Dresden Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 9.75E+01 curies of fission and activation gasses, 2.83E+01 curies of Carbon-14 and approximately 2.86E+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 2014 Annual Radioactive Effluent Release Report (page 35):

1.

Liquid Dose to a Member of the Public for 2014 Total Body: 3.97E-06 mrem Organ: 3.97E-06 mrem The above dose values are site totals. Liquid dose limits are assigned per unit (3 mrem/year/unit for total body, and 10 mrem/year/unit for any organ

- from page 1 of the 2014 Annual Radioactive Effluent Release Report).

Because the site values are significantly lower than the per unit limits, it can be concluded the effluent dose attributed to each unit is below the ODCM limits shown on page 1 of the 2014 Annual Radioactive Effluent Release Report.

2.

Airborne Effluent Dose to a Member of the Public for 2014 Gamma air (noble gases): 3.36E-03 mrad Beta air (noble gases): 2.12E-04 mrad Total Body (noble gases): 2.24E-03 mrem Skin (noble gases): 3.86E-03 mrem Organ - thyroid (particulate/iodine): 9.22E-02 mrem The above dose values are site totals. Airborne dose limits are assigned per unit (gamma air dose is 10 mrad/year/unit, beta air dose is 20 mrad/year/unit, organ dose limit is 15 mrem/year/unit - from page 1 of the 2014 Annual Radioactive Effluent Release Report) Because the site values are significantly lower than the per unit limits, it can be concluded the effluent dose attributed to each unit is below the ODCM limits shown on page 1 of the 2014 Annual Radioactive Effluent Release Report. Total body and skin doses due to noble gases are addressed as part of the 40CFR190 / 10CFR72 Compliance evaluation below.

3.

Direct Radiation Dose to a Member of the Public for 2014 Total Body (excluding skyshine): 1.80E+00 mrem Total Body (skyshine): 8.60E+00 mrem

4.

Total Body Doses to the Population and Average Doses to Individuals in the Population from All Receiving-Water-Related-Pathways: Not applicable for DNPS. No downstream drinking water pathway exist within the specified distance of 10 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: Not applicable for DNPS.

6.

Doses From Liquid and Gaseous Effluent to Members of the Public Due to Their Activities Inside the Site Boundary for the Report Period: Not applicable for DNPS. Any member of the public that is onsite for a significant period will be issued a Optical Stimulated Luminescent Dosimeter (OSLD).

7.

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

8.

40CFR190 / 10CFR72 Compliance The General Electric Hitachi Nuclear Energy Morris Operation (GE-Hitachi Morris Operation) facility is physically located near Dresden Station and, in addition to evolutions performed at Dresden station, is considered in the evaluation of the uranium fuel cycle on members of the public in the general environment for 40CFR1 90 compliance.

Dresden decommissioning activities (Unit 1) and operations (Units 2 and 3) resulted in a maximum 9.61 E-02 mrem organ dose and 1.04E+01 mrem total body dose. Radiological Environmental Monitoring Program (REMP) direct radiation monitoring at or near the site boundary (1.80E+00 mrem) demonstrates that total body dose calculations to account for skyshine are conservative.

No effluents were released from the Dresden Independent Spent Fuel Storage Installations (ISFSIs) during 2014. REMP direct radiation monitoring at or near the site boundary demonstrates that the ISFSIs do not result in measurable dose to the public.

According to the 2014 GE-Hitachi Morris Operation 10CFR72.44(d)(3) report, dated 2/24/2015, for the 2014 calendar year, the maximum dose at their site boundary from direct radiation exposure was 6.85E-01 mrem. The maximum organ dose from site activities was 1.34E-02 mrem for 2014.

Maximum combined total body dose from Dresden and GE-Hitachi Morris Operation activities was 1.11 E+01 mrem during 2014, which was 44.4 % of the 40CFR190 limit of 25 mrem.

Maximum combined organ dose from Dresden and GE-Hitachi Morris Operation activities was 1.1OE-01 mrem during 2014. This was 0.44 % of the 40CFR190 limit of 25 mrem to any organ. The combined thyroid dose was 1.06E-01 mrem. This was 0.14 % 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-1 37 was detected in both sediment samples at a concentration consistent with levels observed in previous years. No power station produced fission or activation products were found in sediment.

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

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

Cow milk samples were not analyzed in 2014 for concentrations of 1-131 and gamma emitting nuclides due to the cows being sold.

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 (OSLD). 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 2014 through 31 December 2014.

An assessment of the station's radioactive effluent monitoring results and radiation dose via the principle pathways of exposure resulting from plant emissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area, an annual summary of meteorological conditions including wind speed, wind direction and atmospheric stability and the result of the 40CFR1 90 uranium fuel cycle dose analysis for the calendar year are published in the station's Annual Radioactive Effluent Release Report.

A.

Objective of the Radiological Environmental Monitoring Program (REMP)

The objectives of the REMP are to:

1.

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

2.

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

B.

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

1.

Identifying significant exposure pathways.

2.

Establishing baseline radiological data of media within those pathways.

3.

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

Ill.

Program Description A.

Sample Collection Samples for the DNPS REMP were collected for Exelon Nuclear by Environmental Incorporated Midwest Laboratory (EIML). This section describes the general collection methods used by EIML to obtain environmental samples for the DNPS REMP in 2014. Sample locations and descriptions can be found in Appendix B, Table B-1 and Figures B-1 and B-2. The collection methods used by EIML are listed in Table B-2.

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

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

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

Terrestrial Environment Milk (M) samples are typically collected biweekly at one control location (D-25) from May through October and monthly from November through April. There are no milking animals within 10 km (6.2 miles) of the site.

All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite and shipped promptly to the laboratory. Food products (FL) were collected annually in September at five locations (D-Control, D-Quad 1, D-Quad 2, D-Quad 3 and D-Quad 4). The control location was D-Control. Various types of samples were collected and placed in new unused plastic bags and sent to the laboratory for analysis.

Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLD) 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).

Each location consisted of two OSLD sets. The OSLD 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 rinq consisting of 16 locations (D-201, D-202, D-203, D-204, D-205, D-206, D-207, D-208, D-209, D-210, D-211, D-212, D-213, D-214, D-215 and D-216) approximately 5 to 10 km (3.1 to 6.2 miles) from the site.

Other locations consisting of OSLD 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 OSLD 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 2014. The analytical procedures used by the laboratories are listed in Appendix B Table B-2.

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

1.

Concentrations of beta emitters in surface water and air particulates.

2.

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

3.

Concentrations of tritium in ground and surface water.

4.

Concentrations of 1-131 in air and milk.

5.

Ambient gamma radiation levels at various site environs.

C.

Data Interpretation For the purpose of this report, Dresden Nuclear Power Station was considered operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:

1.

Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required DNPS detection capabilities for environmental sample analysis.

The minimum detectable concentration (MDC) is calculated the same as the LLD with the exception that the measurement is an after the fact estimate of the presence of activity.

2.

Net Activity Calculation and Reportinq of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity effecting a negative number. An MDC was reported in all cases where positive activity was not detected.

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

For groundwater, surface water, and vegetation twelve nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-1 37, Ba-1 40 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 2014 the DNPS REMP had a sample recovery rate greater than 97%.

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 WW D-23 01/10/14 No sample; frozen pipes. Collector obtained sample 01/17/14.

AP/I D-02 01/24/14 No sample; Ross barrier would not open; collector will attempt to collect next period.

AP/I D-02 01/31/14 Sample has two week runtime due to inaccessibility last sample period; field check performed.

AP/I D-08 04/11/14 Controlled burn in field near air sampler; collector noted filter very dark with particulate matter.

AP/I D-02 04/18/14 Low reading of 154.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; no electricity to building. Collector unable to field check pump.

Estimated flow of 60 cfh used for TBE COC.

Table D-1 LISTING OF SAMPLE ANOMALIES (continued)

Sample Location Collection Reason Type Code Date AP/l D-53 04/18/14 No apparent reason for low reading of 164.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

AP/I D-53 04/25/14 No apparent reason for low reading of 150.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

AP/I D-53 05/02/14 No apparent reason for low reading of 150.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . If still low next period, collector will replace timer.

AP/I D-53 05/09/14 No apparent reason for low reading of 150.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Collector placed new timer.

AP/I D-53 05/16/14 No apparent reason for low reading of 141.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Two timers at location, both have same reading.

AP/I D-53 05/23/14 No apparent reason for low reading of 145.0 hours0 days 0 hours 0 weeks 0 months . Two timers at location, both have same reading.

Collector replaced pump.

AP/I D-01 07/04/14 Low reading of 99.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months possibly due to power outages from storms in the area.

AP/I D-04 07/04/14 Low reading of 97.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months possibly due to power outages from storms in the area.

AP/I D-12 07/04/14 Low reading of 127.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months possibly due to power outages from storms in the area.

AP/I D-10 07/25/14 Low reading of 137.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months possibly due to power outages from storms in the area.

Table D-1 LISTING OF SAMPLE ANOMALIES (continued)

Sample Location Collection Reason Type Code Date WG D-23 08/08/14 The LLDs for 1-131, Ba-140, and La-140 could not be met because Teledyne mistakenly did not analyze the sample for the gamma analysis when received. This error was discovered by Teledyne while assembling the AREOR. Upon discovering the error, the sample was analyzed for gamma. All LLDs with the exception of 1-131, Ba-140 and La-140 were met.

AP/I D-01 08/22/14 Low reading of 159 hours0.00184 days 0.0442 hours 2.628968e-4 weeks 6.04995e-5 months possibly due to work on power lines in the area.

AP/I D-02 08/22/14 Low reading of 159.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months possibly due to work on power lines in the area.

AP/I D-03 08/22/14 Low reading of 159.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months possibly due to work on power lines in the area.

AP/I D-04 08/22/14 Low reading of 159 hours0.00184 days 0.0442 hours 2.628968e-4 weeks 6.04995e-5 months possibly due to work on power lines in the area.

AP/l D-10 10/24/14 No apparent reason for low reading of 83.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date M

D-25 01/01/14 - 12/31/14 No sample; farmer sold cows.

AP/I D-03 01/03/14 - 06/27/14 No electricity. New power supply line installed. Power Restored 06/27/14.

Table D-2 LISTING OF MISSED SAMPLES (continued)

Sample Location Collection Reason Type Code Date OSLD D-109-1, 01/10/14 OSLDs found missing during D-201-1 quarterly exchange; collector placed D-201-2 new 1st quarter OSLDs. Note:

Collector found D-109-1 on 01/17/14.

OSLD D-106-1, 03/28/14 OSLDs found missing during D-113-1, quarterly exchange; placed new 2 nd D-203-1 quarter OSLDs. D-113-1 missing; D-106-1 and 203-1 had new utility poles placed; OSLIs gone OSLD D-203-1 06/27/14 OSLD found missing during quarterly exchange. Collector placed new 3 rd quarter OSLD.

OSLD D-116-2 01/09/15 OSLD found missing during quarterly exchange. Collector placed new quarterly OSLD.

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

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

E.

Program Changes No program changes in 2014.

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 all samples. The values ranged from 3.8 to 14.9 pCi/l. Concentrations detected were consistent with those detected in previous years (Figures C-1, C-2 and C-3, Appendix C).

Tritium Quarterly composites from all locations were analyzed for tritium activity (Table C-l.2, Appendix C). Two samples at indicator station D-21 were positive for tritium at a concentration of 233 and 1,050 pCi/L. Four samples at control station D-57 were positive for tritium. The values ranged from 535 to 1,280 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:

Trtium All samples were analyzed for tritium activity (Table C-I 1.1, Appendix C). Tritium was detected in eleven of sixteen samples.

The concentrations ranged from 329 to 678 pCi/l. Concentrations detected were consistent with those detected in previous years (Figure C-7, Appendix C).

12-

Gamma Spectrometry All samples were analyzed for gamma emitting nuclides (Table C-I1.2, Appendix C). No nuclides were detected and all required LLDs were met with the exception of the August D-23 sample for nuclides 1-131, Ba-140, and La-140. This occurred is due to the laboratory not analyzing the sample at time of receipt.

3.

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

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

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). Cesium-137 was detected in both samples. The concentrations ranged from 129 to 211 pCi/kg dry. The activity detected was consistent with those detected in previous years and is likely due to fallout from above-ground nuclear weapons testing. No other fission or activation products were detected.

B.

Atmospheric Environment

1.

Airborne

a.

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

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

Detectable gross beta activity was observed at all locations.

Comparison of results among the four groups aid in determining the effects, if any, resulting from the operation of DNPS. The results from the On-Site locations ranged from 5 to 30 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m. The results from the Near-Field locations ranged from 6 to 31 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m. The results from the Far-Field locations ranged from 8 to 35 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. The results from the Control location ranged from 8 to 28 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3. Comparison of the 2014 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 2014 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 and K-40 were 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, D-07, D-08, D-10, D-12, D-14, D-45, D-53, D-55, D-56 and D-58) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). All results were less than the MDC for 1-131.

2.

Terrestrial

a.

Milk There are no indicator locations within 10 kilometers of the station. Samples are typically collected from one control location (D-25) biweekly May through October and monthly November through April. The following analyses would be performed:

Iodine-131 Milk samples from the location are typically analyzed for concentrations of 1-131 (Table C-VII.1, Appendix C). 1-131 was not analyzed in 2014.

Gamma Spectrometry Milk samples are typically analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C).

Naturally occurring K-40 activity is typically found in all samples. Gamma emitting nuclides were not analyzed in 2014.

b.

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

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

C.

Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLD) 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). Forty-six OSLD locations were established around the site. Results of OSLD measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C.

Most OSLD measurements were below 30 mrem/quarter, with a range of 10.7 to 42.8 mrem/quarter. A comparison of the Inner Ring, Outer Ring and Other locations' data to the Control Location data, indicate that the ambient gamma radiation levels from the Control location (D-12-01and D-12-02) were comparable.

D.

Land Use Survey A Land Use Survey conducted on August 16, 2014 around the Dresden Nuclear Power Station (DNPS) was performed by EIML for Exelon Nuclear to comply with Section 12.6.2 of the Dresden Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident or industrial facility, milk producing animal, and livestock in each of the sixteen 22 1/2A degree sectors within 10 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 A N 1.5 1.4 B NNE 0.8 6.0 C NE 0.8 5.8 D ENE 0.7 1.7 EE 1.1 F ESE 1.0 G SE 0.6 H SSE 0.5 J S 0.5 16.0 K SSW 3.3 L SW 3.6 M WSW 5.8 N W 3.5 0.5 P WNW 3.7 0.5 Q NW 2.6 0.5 R NNW 0.8 1.0 E.

Errata Data There is no errata data for 2014.

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.

In reviewing our environmental inter-laboratory crosscheck programs, we identified 1) duplication of efforts on some matrices and isotopes and 2) that we are performing crosscheck samples on some matrices and isotopes that we do not perform for clients. Since the DOE MAPEP is designed to evaluate the ability of analytical facilities to correctly analyze for radiological constituents representative of those at DOE sites, the needed changes were made to the MAPEP program. Therefore, the following isotopes were removed from the MAPEP program:

Soil - gamma - will be provided by Analytics twice per year, starting in 2015. For 2014, one soil gamma is provided by MAPEP, the 2 nd soil gamma is provided by Analytics.

AP - gamma - is currently provided by Analytics.

Water - gamma, H-3, Sr-90, uranium, gross alpha and gross beta currently provided by ERA.

MAPEP evaluates non-reported (NR) analyses as failed if they were reported in the previous series.

For the TBE laboratory, 163 out of 169 analyses performed met the specified acceptance criteria. Six analyses (Ni-63, K-40 and 1-131 in water, and two Sr-90s and one Gross Alpha in AP samples) did not meet the specified acceptance criteria for the following reasons:

1.

Teledyne Brown Engineering's MAPEP March 2014 Ni-63 in water result of 32.7 +/- 1.69 Bq/L was overlooked when reporting the data but would have passed the acceptance range of 23.9 - 44.2 Bq/L.

NCR 14-04

2.

Teledyne Brown Engineering's MAPEP March 2014 K-40 in water result of 1.63 +/- 2.49 Bq/L was overlooked when reporting the data but would have passed the false positive test. NCR 14-04

3.

Teledyne Brown Engineering's ERA November 2014 1-131 in water result of 15.8 pCi/L was lower than the known value of 20.3 pCi/L, failing below the lower acceptance limit of 16.8. The result was evaluated as failed with a found to known ratio of 0.778. No cause could be found for the slightly low result. All ERA 1-131 evaluations since 2004 have been acceptable. NCR 14-08

4.

Teledyne Brown Engineering's MAPEP March 2014 Sr-90 in AP result of 0.822 Bq/sample was lower than the known value of 1.18 Bq/sample, falling below the lower acceptance limit of 0.83 Bq/sample. The rerun result was still low, but fell within the lower acceptance range of 0.836. The rerun result was statistically the same number as the original result. No cause could be found for the slightly low results. NCR 14-04

5.

Teledyne Brown Engineering's MAPEP September 2014 Sr-90 in AP result of 0.310 Bq/sample was lower than the known value of 0.703 Bq/sample. The gravimetric yield of 117% was very high (we normally see yields of 60% to 70%) and could account for the low activity. NCR 14-09

6.

Teledyne Brown Engineering's MAPEP September 2014 Gr-Alpha in AP result of 0.153 Bq/sample was lower than the known value of 0.53 Bq/sample. The AP sample was counted on the wrong side.

The AP was flipped over and recounted with acceptable results.

NCR 14-09 Intentionally left blank

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2014 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 2014 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS SURFACE WATER (PCI/LITER)

GR-B H-3 GAMMA MN-54 36 12 36 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 4

9.4 (12/12)

(6.2/14.9) 2000 642 (2/4)

(233/1050) 15

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 7

(24/24)

(3.8/12.4) 836 (4/8)

(535/1280) 9.4 (12/12)

(6.2/14.9) 836 (4/4)

(535/1280)

D-21 INDICATOR IL RIVER AT EJ&E BRIDGE 1.4 MILES WNW OF SITE D-57 CONTROL 0

KANKAKEE RIVER AT WILL ROAD(CONTROL) 2.0 MILES SE OF SITE

<LLD

<LLD 0

0 0

0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2014 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 2014 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN(M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS SURFACE WATER (PCI/LITER) 1-131 CS-134 CS-137 BA-140 LA-140 15

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD 2000 476 (11/16)

(329/678)

<LLD

<LLD 0

0 0

0 GROUND WATER (PCI/LITER)

H-3 16 16 NA 476 (11/12)

(329/678)

D-23 INDICATOR THORSEN WELL 0.7 MILES S OF SITE GAMMA MN-54 CO-58 FE-59 15

<LLD 15

<LLD 30

<LLD NA NA NA 0

0 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2014 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 2014 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

MEAN(M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS GROUND WATER (PCVLITER)

CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 15

<LLD 30

<LLD I5

<LLD 30

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD NA NA NA NA NA NA NA NA NA 0

0 0

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

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2014 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 2014 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN(M)

STATION #

NUMBEROF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS FISH (PCVKG WET)

GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 8

130

<LLD 130

<LLD 260

<LLD 130

<LLD 260

<LLD NA

<LLD 130

<LLD 150

<LLD

<LLD 0

0 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2014 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 2014 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN(M)

STATION #

NUMBEROF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS FISH (PC VKG WET)

BA-140 LA-140 GAMMA MN-54 SEDIMENT (PCI/KG DRY) 2 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 NA

<LLD NA

<LLD

<LLD NA NA NA NA NA NA NA 0

0 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2014 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 2014 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS SEDIMENT (PCI/KG DRY)

CS-134 CS-137 BA-140 LA-140 0>

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

GR-B 702 55 150

<LLD 180 170 (2/2)

(129/211)

NA

<LLD NA

<LLD 10 18 (648/650)

(5/35)

NA

<LLD NA

<LLD NA NA NA NA 0

0 170 (2/2)

(129/211)

D-27 INDICATOR DRESDEN LOCK AND DAM - DOWNSTREAM 0.8 MILES NW OF SITE 0

0 GAMMA MN-54 17 (52/52)

(8/28)

<LLD

<LLD 19 (52/52)

(6/31 )

D-56 INDICATOR WILDFEATHER 1.7 MILES SE OF SITE 0

CO-58 FE-59 CO-60 0

0 0

0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2014 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 2014 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN(M)

STATION #

NUMBEROF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS AIR PARTICULATE (E,3 PCI/CU.METER)

ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 GAMMA 1-131 NA

<LLD NA

<LLD 50

<LLD 60

<LLD NA

<LLD

<LLD 0

0 0

AIR IODINE (E-3 PCI/CU.METER) 702 70

<LLD

<LLD 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2014 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 2014 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS VEGETATION (PCI/KG WET) 00 GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 NA

<LLD NA

<LLD 60

<LLD

<LLD 0

0 0

10

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR DRESDEN NUCLEAR POWER STATION, 2014 NAME OF FACILITY: DRESDEN DOCKET NUMBER:

50-010 50-237 & 50-249 2014 LOCATION OF FACILITY: MORRIS IL REPORTING PERIOD:

ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS VEGETATION (PCI/KG WET)

CS-137 BA-140 LA-140 80

<LLD NA

<LLD NA 30.3 (355/355)

(10.7/42.8)

<LLD

<LLD 0

0 0

0 DIRECT RADIATION (MILLIREM/QTR.)

OSLD-QUARTERLY 363 28.8 (8/8)

(23/34.7) 35.2 (4/4)

(28.4/40.5)

D-1 10-4 INDICATOR 0.9 MILES SSW

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

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, 2014 Location Location Description Distance & Direction From Site A.

Surface Water D-21 D-52 D-57 Illinois River at EJ&E Bridge (indicator)

DesPlaines River at Will Road, Upstream (control)

Kankakee River at Will Road (control)

B.

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

Dresden Lock and Dam (indicator)

C.

Milk - bi-weekly / monthly D-25 Biros Farm (control)

D.

Air Particulates / Air Iodine D-01 D-02 D-03 D-04 D-07 D-08 D-10 D-12 D-14 D-45 D-53 D-55 D-56 D-58 Onsite Station 1 (indicator)

Onsite Station 2 (indicator)

Onsite Station 3 (indicator)

Collins Road, on Station property(indicator)

Clay Products, Dresden Road (indicator)

Jugtown Road, Prairie Parks (indicator)

Goose Lake Road, Goose Lake Village (indicator)

Quarry Road, Lisbon (control)

Center Street, Channahon (indicator)

McKinley Woods Road, Channahon (indicator)

Will Road, Hollyhock (indicator)

Ridge Road, Minooka (indicator)

Will Road, Wildfeather (indicator)

Will Road, Marina (indicator)

Dresden Pool of Illinois River, Downstream (indicator)

DesPlaines River, Upstream (control) 1.4 miles WNW 1.1 miles ESE 2.0 miles SE 0.7 miles S 0.8 miles NW 11.4 miles SW 0.8 miles NW 0.3 miles NNE 0.4 miles S 0.8 miles W 2.6 miles S 3.8 miles SW 3.5 miles SSW 10.5 miles NW 3.7 miles NE 1.7 miles ENE 2.1 miles SSE 4.3 miles N 1.7 miles SE 1.1 miles ESE 0.9 miles NNW 1.2 miles ESE 0.8 miles NW 2.8 miles NE 3.2 miles SSE 3.9 miles SSW 1.6 miles NNW 12.8 miles ENE E.

Fish D-28 D-46 F.

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

G.

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

TABLE B-i:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2014 Location Location Description Distance & Direction From Site H.

Environmental Dosimetry - OSLD Inner Ring D-58-1 and -2 D-101-1 and -2 D-102-1 and -2 D-103-1 and -2 D-104-1 and -2 D-105-1 and -2 D-106-1 and -2 D-107-1 and -2 D-108-1 and -2 D-109-1 and -2 D-110-3 and -4 D-111-1 and -2 D-112A-1 and -2 D-113-1 and -2 D-114-1 and -2 D-115-1 and -2 D-116-1 and -2 Outer Ring D-201-1 and -2 D-202-1 and -2 D-203-1 and -2 D-204-1 and -2 D-205-1 and -2 D-206-1 and -2 D-207-1 and -2 D-208-1 and -2 D-209-1 and -2 D-210-1 and -2 D-211-1 and -2 D-212-3 and -4 D-213-1 and -2 D-214-1 and -2 D-215-1 and -2 D-216-1 and -2 Other Locations D-01-1 and-2 D-02-1 and -2 D-03-1 and -2 D-04-1 and -2 D-07-1 and -2 D-08-1 and -2 D-10-1 and -2 D-14-1 and -2 D-45-1 and -2 D-53-1 and -2 D-55-1 and -2 D-56-1 and -2 D-58-1 and -2 1.1 miles ESE 1.0 miles N 1.3 miles NNE 1.2 miles NE 1.7 miles ENE 1.5 miles E 1.1 miles ESE 1.4 miles SE 1.9 miles SSE 0.8 miles S 0.9 miles SSW 0.6 miles SW 0.7 miles WSW 0.9 miles W 0.9 miles WNW 0.8 miles NW 1.0 miles NNW 4.8 miles N 5.1 miles NNE 4.7 miles NE 5.0 miles ENE 4.0 miles E 3.5 miles ESE 4.2 miles SE 4.9 miles SSE 4.1 miles S 4.9 miles SSW 4.8 miles SW 6.0 miles WSW 4.5 miles W 5.0 miles WNW 4.8 miles NW 4.9 miles NNW 0.8 miles NW 0.3 miles NNE 0.4 miles S 0.8 miles W 2.6 miles S 3.8 miles SW 3.5 miles SSW 3.7 miles NE 1.7 miles ENE 2.1 miles SSE 4.3 miles N 1.7 miles SE 1.1 miles ESE 10.5 miles NW Onsite 1 Onsite 2 Onsite 3 Collins Road, on Station property Clay Products, Dresden Road Jugtown Road, Prairie Parks Goose Lake Road, Goose Lake Village Center Street, Channahon McKinley Woods Road, Channahon Will Road, Hollyhock Ridge Road, Minooka Will Road, Wildfeather Will Road, Marina Control D-12-1 and -2 Lisbon B-2

TABLE B-2:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Dresden Nuclear Power Station, 2014 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Water Gamma Spectroscopy Monthly composite EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting sample or monthly Midwest Laboratory Sampling Procedures radioisotope analysis composite from weekly Manual grab samples.

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

TBE, TBE-2023 Compositing of samples EIML-COMP-01 procedure for compositing water and milk samples Surface Water Tritium Quarterly composite of EIML-SPM-1, Environmental Incorporated 500 ml TBE, TBE-2011 Tritium analysis in monthly composite Midwest Laboratory Sampling Procedures drinking water by liquid scintillation samples.

Manual TBE, TBE-2023 Compositing of samples EIML-COMP-01 procedure for compositing water and milk samples Ground Water Gamma Spectroscopy Quarterly grab samples.

EIML-SPM-1, Environmental Incorporated 2 gallon TBE, TBE-2007 Gamma emitting Midwest Laboratory Sampling Procedures radioisotope analysis Manual Ground Water Tritium Quarterly grab samples.

EIML-SPM-1, Environmental Incorporated 500 ml TBE, TBE-2011 Tritium analysis in Midwest Laboratory Sampling Procedures drinking water by liquid scintillation Manual Fish Gamma Spectroscopy Samples collected twice EIML-SPM-1, Environmental Incorporated 1000 grams (wet)

TBE, 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, 2014 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Dredging Spoils Gamma Spectroscopy Annual grab samples if EIML-SPM-1, Environmental Incorporated 500 grams (dry)

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

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

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

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

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

EIML-SPM-1, Environmental Incorporated 1000 grams TBE, TBE-2007 Gamma emitting Midwest Laboratory Sampling Procedures radioisotope analysis Manual OSLD 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 A120 3:C Landauer Manual I Incorporated elements.

I I

II

I l

L onI unca~a MP b

OMMM ZrTMlO WM 1, Z2A 3 0

11.0 Sediment WXMATMSIPLI LOATKMN Figure B-1 Dresden Station Inner Ring OSLD Locations, Fish, Water, and Sediment Location, 2014 B-5

a1l1-12 N

.25 0

I

=Wmm 0

io wk=mmm 9"IS.L OM1,N U WXUAL

Air SWIIPl Loalafl

M IP -1~

a TLD Lamafl Figure B-2 Dresden Station Fixed Air Sampling and OSLD Sites, Outer Ring OSLD Locations and Milk Location, 2014 B-6

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

F-Intentionally left blank

Table C-1.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION PERIOD 01/03/14 - 01/31/14 02/07/14 - 02/28/14 03/07/14 - 03/28/14 04/04/14 - 04/25/14 05/02/14 - 05/30114 06/06/14 - 06/27/14 07/04/14 - 07/25/14 08/01/14 - 08/29/14 09/05/14 - 09/26/14 10/03/14 - 10/31/14 11/07/14 - 11/28/14 12/05/14 - 12/26/14 D-21 D-52 D-57 6.5 +/- 1.7 9.4 +/- 1.6 6.6 +/- 2.2 8.5 +/- 2.5 10.7 +/- 2.9 14.9 +/- 3.2 7.0 +/- 2.6 7.6 +/- 2.4 14.5 +/- 3.3 8.4 +/- 2.7 12.2 +/- 2.6 6.2 +/- 2.1 9.4 1 6.1 3.8 +/- 1.4 12.4 +/- 2.0 9.2 +/- 2.7 8.2 +/- 2.5 6.1 +/- 2.3 8.0 +/- 2.4 6.5 +/- 2.6 5.2 +/- 2.3 12.0 +/- 3.1 7.4 +/- 2.6 8.9 +/- 2.7 12.3 +/- 2.6 6.7 +/- 1.7 5.0 +/- 1.5 4.3 +/- 2.0 4.5 +/- 2.0 5.8 +/- 2.4 5.3 +/- 1.8 4.9 +/- 2.4 4.7 +/- 2.1 6.4 +/- 2.3 4.8 +/- 2.3 9.9 +/- 2.4 6.7 +/- 2.1 MEAN 8.3 +/- 5.6 5.7 +/- 3.1 Table C-1.2 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01103/14 - 03/28/14 04104/14 - 06/27/14 07/04/14 - 09/26/14 10/03/14 - 12/26/14 D-21 D-52 D-57 1050 + 163

189 233 +/- 127

< 188 642 +/- 1155

< 171

< 187

< 186

183 1280 +/- 183 634 +/- 150 896 +/- 167 535 +/- 146 836 +/- 665 MEAN THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-1

Table C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD D-21 12/27/13 - 01/31/14 01/31/14 - 02/28/14 02/28/14 - 03/28/14 03/28/14 - 04/25/14 04/25/14 - 05/30/14 05/30/14 - 06/27114 06/27/14 - 07/25/14 07/25/14 - 08/29/14 08/29/14 - 09/26/14 09126/14 - 10/31/14 10/31/14 - 11/28/14 11/28/14 - 12/26/14 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140

<3

<4

<2

<4

<7

<3

<5

<3

<5

<3

<4

< 4

<2

<6

<5

<3

<5

<4

<5

<3

<4 8

9 4

14 13 7

12 7

8 MEAN

< 4

<4

<5

<2

<5

<9

<4

<5

<4

<6

<4

<3

<4

<2

<6

<5

<4

<t

<9

<8

<3

<9

<13

<6

< 12

<7

< 13

<5

<6

<7

<4

< 10

< 13

<3

<7

<11

< 10

<8

<7

<4

<2

<6

<4

<6

<4

<7

<3

<4

<3

<4

<2

<6

<7

<3

<4

<6

<5

<4

<6

<7

< 7

<3

<9

<12

<7

< 10

<7

<10

<5

<7

<5

<6

<7

<4

<9

< 15

<3

<7

<11

<8

<7

< 10

10

< 10

<7

13

< 12

10

15

<11

< 15

< 11

< 12

<8

<9

< 10

<7

12

< 13

<7

12

15

< 15

< 12

< 11

<4

<2

<5

<7

<3

<5

<3

<5

<3

<4

<3

<2

<4

<7

<2

<3

<5

<4

<3

<4

<5

<2

<7

<3

<6

<4

<5

<3

<4

<3

<4

<2

<5

<7

<2

<4

<5

<4

< 23

22

26

14

< 39

32

21

30

24

<34

22

< 24

20

<19

<15

29

< 36

<13

26

29

< 35

< 29

< 23

<7

<8

<4

< 12

<8

<5

< 11

<7

<13

<5

<9

<6

<7

<6

<4

<9

< 11

<3

<7

<9

< 10

<9

<7 D-52 01/03/14 02/07/14 03/07/14 04/04/14 05/02/14 06/06/14 07/04/14 08/01/14 09105/14 10/03/14 11/07/14 12/05/14

- 01/31114

- 02/28/14

- 03/28/14

- 04/25/14

- 05/30/14

- 06/27/14

- 07/25/14

- 08/29/14

- 09/26/14

- 10/31/14

- 11/28/14

- 12/26/14

<3

<4

<2

<5

<7

<2

<4

<5

<4

<3

<4

<2

<6

<2

<4

<5

<3

<4

<7

<6

<5

< 11 13

<3

<9

< 10

< 11

<8

<8 MEAN

Table C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/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 12/27/13 - 01/31/14

<4

< 9

<4

<8

< 5

<7

< 11

<4

<25

< 7 01/31/14 - 02/28/14

< 6

< 12

< 5

< 13

< 6

< 10

< 15

< 7

< 6

< 34

< 9 02/28/14 - 03/28/14

< 5

< 11

< 4

< 9

< 5

< 10

< 12

< 5

< 31

< 8 03/28/14 - 04/25/14

< 2

< 6

< 2

< 5

< 2

< 4

< 6

< 2

< 14

< 5 04/25/14 - 05/30/14

< 6

< 5

< 13

< 6

< 11

< 5

< 9

< 13

< 4

< 5

< 25

< 9 05/30/14 - 06/27/14

< 8

< 7

< 15

< 8

< 13

< 6

< 11

< 10

< 7

< 6

< 27

< 9 06/27/14 - 07/25/14

< 5

< 10

< 5

< 10

< 5

< 8

< 11

< 5

< 25

< 7 07/25/14 - 08/29/14

<4

< 5

< 9

< 5

< 8

< 5

< 8

< 14

<4

< 5

< 29

< 8 08/29/14 - 09/26/14

< 4

< 9

< 3

< 9

< 4

< 8

< 13

< 4

< 25

< 8 09/26/14 - 10/31/14

< 4

< 8

< 3

< 7

< 4

< 7

< 13

< 5

< 4

< 30

< 6 10/31/14 - 11/28/14

< 3

< 7

< 3

< 6

< 4

< 6

< 11

< 3

< 23

< 7 11/28/14 - 12/26/14

< 6

< 8

< 4

< 12

< 6

< 10

< 13

< 5

< 6

< 27

< 14 MEAN

Table C-II.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/17/14 - 01/17/14 02/14/14 - 02/14/14 03/14/14 - 03/14/14 04/11/14 - 04/11/14 05/09/14 - 05/09/14 06/13/14 - 06/13/14 07/11/14 - 07/11/14 08/08/14 - 08/08/14 09/12/14 - 09/12/14 10/10/14 - 10/10/14 11/14/14 - 11/14/14 12/12/14 - 12/12/14 MEAN D-23 D-35

< 183 (1) 329 +/- 119 470 +/- 141 390 +/- 123 595 +/- 141 495 +/- 148 426 +/- 130 333 +/- 119 551 +/- 146 443 +/- 142 678 +/- 149 522 +/- 146 476 +/- 216

< 165

164

< 174

< 168 THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-4

Tables C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 SITE COLLECTION PERIOD D-23 01/17/14 - 01/17 02/14/14 - 02/14 03/14/14 - 03/14 04/11/14 - 04111 05/09/14 - 05/09 06113/14 - 06/13 07/11/14 - 07/11 08/08/14 - 08/08 09/12/14 - 09/12 10/10/14 - 10/10 11/14/14 - 11/14 12/12/14 - 12/12 Nb-95 Zr-95 1-131 Cs-134 Cs-1 37 Ba-140 La-140 114

/14

/14 (1) < 5

<3

<5

<3

<7

<7 (1) < 1

<4

<2

<8

<4

<5

<3

<6

<3

<4

<6

<7

<4

<3

<2

<8

<4

<1

<4

<8

<2

< 10

<6

< 13

<6

<8

< 12

< 13

< 28

<7

<4

<21

<9

<6

<3

<5

<3

<4

<7

< 0.4

<3

<2

<9

<4

<13

< 7

<10

<14

<6

<7

<3

<5

<8

<3

<11

<6

<9

<13

<5

<6

<4

<6

<8

<3

<7

<4

<5

<10

<3

<16

<8

<12

<11

<6

<5

<7

<8

<12

<7

<2

<5

<8

<0.5

<7

<5

<7

<11

<4

<3

<2

<3

<9

<2

<13

<8

<13

<8

<6

<4

<7

<8

<4

<6

<3

<6

<3

<4

<6

<5

< 0.4

<4

<2

<9

<4

< 36

< 20

32

19

23

32

29

24

16

< 40

22

<9

<5

< 11

<5

<8

< 13

< 12

<8

<4

< 14

<6 MEAN D-35 01/10/14 04/11/14 07/11/14 10/10/14 01/10/14 04/11/14 07/11/14 10/10/14

<1

<4

<7

<1

<2

<1

<8

<4

<15

<8

<4

<2

<1

<7

<4

<13

<9

<3

<2

<1

<7

<1

<8

<10

<4

<14

<12

<8

<3

<8

<2

<1

<4

<8

<2

<9

<2

<25

<7

< 34

< 13

<14

<5 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-III.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION Mn-54 PERIOD Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 D-28 Freshwater Drum Largemouth Bass Common Carp Golden Redhorse D-46 Common Carp Freshwater Drum Largemouth Bass Smallmouth Buffalc 05/22/14 05/22/14 10/07/14 10/07/14 71 74 49 52 57 65 51 47 179 145 103 124

< 70

< 62

< 46

< 49 131 142 100 126

< 83

< 88

< 53

< 61

< 118

< 146

< 89

< 111 63 66 45 52 73 79 44 56

< 645

< 729

< 386

< 361 208 211 129 122 MEAN 05/21)14 05/22/14 10/07/14 10/07/14 50 78 43 38 66 83 44 49 119 192 102 99

<54

< 72

< 31

< 51 122 144 105 103

< 62

< 86

< 58

< 44

< 101

< 172

< 87

< 85 46 77 45 39 56 72 56 40

< 548

< 745

< 328

< 329 131 214 120 120 0)

MEAN

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PC/KG DRY +/- 2 SIGMA SITE COLLECTION Mn-54 PERIOD Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 D-27 05/30/14 10/03/14

< 70

< 94

< 168

< 100

< 158

< 73

< 143

< 119

< 109

< 290

< 139

< 245

< 140

< 182

< 66

< 98 129 1 86

< 400 211 +/- 109 < 1029

< 104

< 307 MEAN 170 +/- 116

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 01/03114 - 01/10/14 01/10/14 - 01/17/14 01/17/14 - 01/24/14 01/24/14 - 01/31/14 01/31/14 - 02/07/14 02/07/14 - 02/14/14 02/14/14 - 02/20/14 02/20/14 - 02/28/14 02/28/14 - 03/07/14 03/07/14 - 03/14/14 03/14/14 - 03/21/14 03/21/14 - 03/28/14 03/28/14 - 04/04/14 04/04/14 - 04/11/14 04/11/14 - 04/18/14 04/18/14 - 04/25/14 04/25/14 - 05/02/14 05/02/14 - 05/09/14 05/09/14 - 05/16/14 05/16/14 - 05/23/14 05/23/14 - 05/30/14 05/30/14 - 06/06/14 06/06/14 - 06/13/14 06/13/14 - 06/20/14 06/20/14 - 06/27/14 06/27/14 - 07/04/14 07/04/14 - 07/11/14 07/11/14 - 07/18/14 07/18/14 - 07/25/14 07/25/14 - 08/01/14 08/01/14 - 08/08/'14 08/08/14 - 08/15/14 08/15/14 - 08/22/14 08/22/14 - 08/29/14 08/29/14 - 09/05/14 09/05/14 - 09/12/14 09/12/14 - 09/19/14 09/19/14 - 09/26/14 09/26/14 - 10/03/14 10/03/14 - 10/10/14 10/10/14 - 10/17/14 10/17/14 - 10/24/14 10/24/14 - 10/31/14 10/31/14 - 11/07/14 11/07/14 - 11/14/14 11/14/14 - 11/21/14 11/21/14 - 11/28/14 11/28/14 - 12/05/14 12/05/14 - 12/12/14 12/12/14 - 12/19/14 12/19/14 - 12/26/14 12/26/14 - 01/02/15 D-01 29 +/- 5 23 +/- 5 19 +/- 4 15 +/- 4 20 +/- 5 28 +/- 5 19 +/- 5 26 +/- 5 21 +/- 5 21 +/- 5 13 +/- 4 17 +/-4 15 +/-4 18 +/-5 24 5

13 +/-4 6+/-3 16 +/-4 13 +/- 4 16 +/- 4 14 +/- 4 11 +/-4 11 +/-4 12 +/-4 17 +/-4 8+/-5 11 +/-4 16 +/-4 22 +/-4 16 +/-4 21

+/-5 14 +/-4 19 +/-5 15 +/-4 21 +/-5 16 +/-4 17 +/-5 21 +/-4 17 +/-4 14 +/-4 13 +/-4 10 +/- 4 15 +/- 4 14 +/- 4 12 +/- 4 17 +/- 4 23 +/- 5 25 +/- 5 30 +/- 5 21 +/- 4 20 +/- 4 22 +/-4 GROUP I D-02 27 +/- 5 17 +/- 4 (1) 16 +/-2 (1) 20 +/- 5 24 +/- 5 18 +/- 5 22 +/- 4 21 +/- 5 21 +/- 5 8+/-4 13 +/-4 12 +/-4 12 +/-4 16 4

(1) 10 +/-4 5+/-3 13 +/-4 8+/-3 12 +/-4 12 +/-4 14 +/-4 14 +/-4 14 +/-4 15 +/-4 (1) 9+/-4 14 +/-4 14 +/-4 26 +/-5 17 +/-4 25 +/- 5 17 +/- 4 (1) 24 +/-5 (1) 16 +/- 4 19 +/-5 21 +/-4 22 +/-5 21 +/-4 21

+/-4 21

+/-5 12 +/-4 13 +/-4 19 +/-4 14 +/-4 14 +/-4 18 +/-4 21 +/-5 24 +/-5 29 +/-5 23 +/- 4 20 +/- 4 25 +/- 5 2

1 2

2 2

2 D-03 (1)

(1)

(1)5 (1)

(1)

(1)5 845 0+/-4 855 U

D-04 28 +/- 5 25 +/- 5 21 +/- 4 18 +/- 4 23 +/- 5 31 +/- 5 21 +/- 5 28 +/- 5 22 +/- 5 19 +/- 5 16 +/- 4 17 +/- 4 15 +/- 4 19 +/- 5 18 +/- 4 13 +/- 5 9+/-4 18 +/-4 12 +/-4 15 +/-4 15 +/-4 11 +/-4 13 +/-4 19 +/-4 12 +/-4 12 +/-6 13 +/- 4 13 +/- 4 24 +/- 4 21 +/- 5 24 +/- 5 16 +/- 4 (1) 19 +/- 5 16 +/- 4 21 +/- 5 14 +/- 4 20 +/- 5 26 +/- 5 15 +/- 4 15 +/-4 12 +/-4 11 +/-4 17 +/-4 16 +/-4 13 +/- 4 21 +/- 4 22 +/- 5 24 +/- 5 31 +/- 5 25 +/- 5 27 +/- 5 23 +/- 5 D-07 26+/- 5 22+/- 5 18 +/- 4 17 +/- 4 21 +/- 5 27 +/- 5 24 +/- 5 23 +/- 4 20 +/- 4 20 +/- 5 14 +/- 4 13 +/- 4 13 +/- 4 17 +/- 4 16 +/- 4 13 +/- 4 6+/-3 13 +/-4 10 +/-4 14 +/-4 16 +/-4 15 +/-4 13 +/-4 14 +/-4 13 +/- 4 (1) 13 +/- 4 13 +/- 4 11 +/-4 27 +/-5 18 +/-4 23 +/-5 16 +/-4 (1) 22 +/-5 16 +/-4 23 +/-5 12 +/-4 19 +/-5 28 +/-5 20 +/-4 12 +/-4 11

+/-4 12 +/-4 15 +/- 4 16 +/- 4 13 +/- 4 18 +/- 4 25 +/- 5 23 +/- 5 25 +/- 5 24 +/- 5 22+/- 4 23 +/- 5 I

GROUP 11 D-45 21 +/- 4 26 +/- 5 20 +/- 4 14 +/- 4 22 +/- 5 30 +/- 5 21 +/- 5 26 +/- 5 21 +/- 5 20 +/- 5 13 +/- 4 16 +/- 4 14 +/- 4 15 +/- 4 16 +/- 4 10 +/- 4 8+/-4 16 +/-4 15 +/-4 17 +/-4 11 +/-4 17 +/-4 17 +/-4 18 +/-4 15 +/-4 10 +/-3 12 +/-4 14 +/-4 25 +/-4 16 +/-4 24 +/-5 14 +/-4 17 +/-5 16 +/-4 22 +/-5 17 +/-4 17 +/- 5 24 +/- 5 20 +/- 4 16 +/- 4 13 +/- 4 14 +/-4 15 +/-4 14 +/-4 11 +/-4 18 +/-4 19 +/-4 23 +/-5 27 +/-5 19 +/- 4 20 +/- 4 22 +/- 5 0-53 23 +/- 4 22 +/- 5 21 +/- 4 15 +/- 4 24 +/- 5 31 +/- 5 18 +/- 5 23 +/- 4 19 +/- 4 18 +/- 5 11 +/-4 14 +/-4 18 +/-4 15 +/-4 16 +/-4 10 5

<5 13 +/-4 11 +/-4 11 +/-4 17 +/-4 11 +/-4 13 +/-4 14 +/-4 15 +/-4 14 +/-4 14 +/-4 13 +/-4 25 +/- 4 18 +/- 4 24 +/- 5 15 +/- 4 21 +/- 5 13 +/- 4 20 +/- 5 12 +/- 4 18 +/- 5 18 +/- 4 21 +/- 4 15 +/- 4 8+/-4 12 +/-4 19 +/-4 14 +/-4 12 +/-4 17 +/-4 22 +/-5 28 +/-5 23 +/-5 22 +/- 4 19 +/- 4 28 +/- 5 U

0-56 29 +/- 5 26 +/- 5 20 +/- 4 16 +/- 4 24 +/- 5 31 +/- 5 25 +/- 5 25 +/- 5 24 +/- 5 19 +/- 5 14 +/- 4 17 +/- 4 16 +/- 4 17 +/- 5 (1) 19 +/- 4 (1) 14 +/- 4 (1) 6+/-3 (1) 12 +/-4 (1) 17 +/-4 (1) 18 +/-4 18 +/-4 19 +/-4 13 +/-4 13 +/-4 16 +/-4 9+/-4 12 +/-4 12 +/-4 26 +/-4 18 +/-4 24 +/-5 14 +/-4 24 +/-5 20 +/-4 22 +/-5 18 +/-4 19 +/-5 22 +/-4 19 +/-4 14 +/-4 12 +/-4 12 +/-4 20 +/-5 21 +/-5 14 +/- 4 24 +/- 5 20 +/- 4 22 +/- 5 27 +/- 5 26 +/- 5 21 +/- 4 20 +/- 4 0-58 23 +/- 4 23 +/- 5 20 +/- 4 14 +/- 4 19 +/-5 30 +/-5 24 +/-5 24 +/-4 23 +/-5 21 +/-5 15 +/-4 14 +/-4 13 +/-4 15 +/- 4 16 +/- 4 13 +/- 4 8+/-4 11 +/-4 11 +/-4 13 +/-4 13 +/-4 11 +/-4 13 +/-4 15 +/-4 11 +/-4 8+/-3 15 +/-4 13 +/-4 25 +/- 4 19 +/- 5 20 +/- 5 15 +/- 4 18 +/- 5 15 +/- 4 19 +/- 5 15 +/- 4 18 +/- 5 20 +/- 4 18 +/- 4 15 +/- 4 11 +/-4 11 +/-4 17 +/-4 12 +/-4 13 +/-4 21 +/-5 19 +/-4 24 +/-5 29 5

22 +/-4 23 +/-5 23 5

U MEAN 17 +/-10 17 +/-11 18 +/-10 19 +/-11 18 +/-11 18 +/-10 17 +/-11 19 +/-11 17 +/-10 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, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD GROUP III D-08 D-10 UI/U.5/14 01/10/14 01/17/14 01/24/14 01/31/14 02/07/14 02/14/14 02/20/14 02/28/14 03/07/14 03/14/14 03/21/14 03/28/14 04/04/14 04/11/14 04/18/14 04/25/14 05/02/14 05/09/14 05/16/14 05/23/14 05/30/14 06/06/14 06/13/14 06/20/14 06/27/14 07104/14 07/11/14 07/18/14 07/25/14 08/01/14 08/08/14 08/15/14 08/22/14 08/29/14 09/05114 09/12/14 09/19/14 09/26/14 10/03/14 10/10/14 10/17/14 10/24/14 10/31/14 11/07/14 11/14/14 11/21/14 11128/14 12/05/14 12/12/14 12/19/14 12/26/14

- U1i1U/14

- 01/17114

- 01/24/14

- 01/31/14

- 02/07/14

- 02/14/14

- 02/20/14

- 02/28/14

- 03/07/14

- 03/14/14

- 03/21/14

- 03/28/14

- 04/04/14

- 04/11/14

- 04/18/14

- 04/25/14

- 05/02/14

- 05/09/14

- 05/16/14

- 05/23/14

- 05/30/14

- 06/06/14

- 06/13/14

- 06/20/14

- 06/27/14

- 07/04/14

- 07/11/14

- 07/18/14

- 07/25/14

- 08/01/14

- 08/08/14

- 08/15/14

- 08/22/14

- 08/29/14

- 09/05/14

- 09/12/14

- 09/19/14

- 09/26/14

- 10/03/14

- 10/10/14

- 10/17/14

- 10/24/14

- 10/31/14

- 11/07/14

- 11/14/14

- 11/21/14

- 11/28/14

- 12/05/14

- 12/12/14

- 12/19/14

- 12/26/14

- 01/02/15 29 +/- 5 18 +/- 4 21 +/- 4 13 +/- 4 24 +/- 5 35 +/- 5 18 +/- 5 19 +/- 4 20 +/- 5 22 +/- 5 11 +/-4 17 4

15+/- 4 15 +/-4 16 +/-4 11 +/-4 8+/-4 12 +4 10 +/-4 15 +/-4 13 +/-4 11 +4 12 +4 13 +/-4 19 4

13 4

20 +/- 4 10 +/- 4 20 +/- 4 15 +/- 4 25 +/- 5 18 +/- 4 19 +/- 5 15 +/- 4 22+/-5 13 +/- 4 13 +/- 4 21 t 4 17 +/- 4 14 +/- 4 10 +/- 4 11 +/-4 20 +/-5 17 +/-4 14 +/-4 16 4

21 +5 24 +/-5 29 +/-5 24+/- 5 21 +4 21 +/-4 29 20 19 16 22 26 17 24 20 23 13 16 14 (1) 18 19 15 11 14 9

19 15 15 10 17 13 9

20 12 34 21 27 16 19 16 18 19 16 24 19 18 10 26 19 15 12 20 18 23 28 23 18 22

+/-4

+/-5

+/-4

+/-5

+/-4

+4

+/-4

+/-5

+/-4

+4

+5

+/-4

+/-6

+/-5

+/-4

+/-5

+/-4

+/-5

+/-4

+/-5

+/-4

+4

+/-4

+/-8

+/-5

+/-4

+4

+/-4

+/-5

+5

+/-4

+4 0-14 18+/-4 21 +/-5 24 +/-5 16 +/-4 20 +/-5 27 +/-5 19 5

24 +/-4 18+/- 4 18+/- 5 14 +/-4 13+/- 4 20 +/-5 20 +/-5 16 +/-4 13+/- 4 8+/-4 16+/- 4 8+/-4 14+/- 4 14 +/- 4 12 +/- 4 12 +/- 4 13 +/- 4 9+/-3 13 +/-4 13 4

13 +/-4 25 +/-4 20 +/-4 24 +/-5 17 +/-4 20 +/-5 14 +/-3 23 +/-5 18 +/-4 22 +/-5 21 +/-4 24 +/-5 19 +/-4 16 +/-4 (1) 12 +/- 4 15+/- 4 14 +/-4 11 +/-4 20 +/-4 20 +/-4 25 +/-5 28 +/-5 20 +/-4 22 +/-4 21 +4 D-55 27 +/- b 21 +/- 5 17 +/- 4 16 +/- 4 23 +/- 5 26 +/- 5 24 +/- 5 22 +/- 4 22 +/- 5 20 +/- 5 12 +/- 4 13 +/- 4 17 +/- 4 19 +/- 5 19 +/- 4 12 +/- 4

<5 13 +/- 4 8+/-4 13 4

16 +/-4 14 +/-4 14 +/-4 16 +/-4 13+/- 4 15 +/-4 11 4

11 +/-4 25 +/-4 19 4

24 +/-5 15 +/-4 19 5

17 4

21 +/-5 17+/- 4 17 +/-5 23 +/-5 18 +/- 4 16 +/- 4 13 +/- 4 12 +/- 4 16 +/- 4 14 +/- 4 10 +/- 4 22 +/- 5 23 +/- 5 22 +/- 5 28 +/- 5 23 +/- 5 25 +/- 5 18 +/- 4 GROUP IV D-12 26*+/-5 23 +/-5 19 +/-4 14+/- 4 20+/- 5 28 +/-5 21 +5 24+/- 4 18 +/- 4 12 +/- 4 11 +/-4 15+/- 4 13+/- 4 15 4

16+/- 4 12 +/-4 8+/-4 14+/- 4 8+/-4 16+/- 4 13+/- 4 15+/- 4 12+/- 4 17+/- 4 14 +/-4 16 5

17+/- 4 12 +/-4 27 +/-5 15 +/-4 23 +/- 5 16 +/- 4 22+/-5 16 +/- 4 21 +/- 5 18 +/- 4 23 +/- 5 21 +/- 4 24 +/- 5 13 +/- 4 9+/-4 13+/- 4 17+/- 4 12 +/-4 11 +4 20 +/-4 21 +/-5 23 +/-5 27 +/-5 22+/-4 21 +/-4 23 +5 U

(1)

MEAN 17 +/- 11 18 +/- 11 18 +/- 10 18 +/- 10 17 +/- 10 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, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP II - NEAR-FIELD LOCATIONS GROUP III - FAR-FIELD LOCATIONS GROUP IV - CONTROL LOCATION COLLECTION MIN MAX MEAN +

PERIOD 2SD COLLECTION MIN MAX MEAN +

PERIOD 2SD 01103/14 - 01/31/14 01/31/14 - 02/28/14 02128/14 - 04/04114 04104114

- 05/02/14 05/02/14 - 05/30/14 05/30/14 - 07/04/14 07104/14 - 08/01/14 08/01/14 - 08/29/14 08/29/14 - 10/03/14 10/03/14 - 10/31/14 10/31/14 - 11/28/14 11/28/14 - 01/02/15 01/03/14 - 01/02/15 15 18 8

5 8

8 10 14 16 10 10 20 29 21 +/- 11 28 22 +/- 7 21 16 +/- 9 24 13 +/- 12 16 13 +/- 5 17 12 +/- 6 27 17 +/- 11 25 19 +/- 7 24 19 +/- 5 21 14 +/- 7 23 17 +/- 8 30 24 +/-6 01/03/14 01/31/14 01/31/14 02/28/14 02/28/14 04/04114 04/04/14 05/02/14 05/02/14 05/30/14 05/30/14 07/04/14 07104/14 08/01/14 08/01/14 - 08/29/14 08/29/14 - 10/03/14 10/03/14 - 10131/14 10/31/14 - 11/28/14 11/28/14 - 01/02/15 14 29 18 31 11 24 6

19 10 18 8

19 11 27 13 24 12 28 8

20 11 25 19 31 21 +/- 8 25 +/- 8 17 +/-7 13+/- 8 14 5

13+/- 5 17 +/-11 19+/- 8 19+/- 7 14 +/- 6 17+/- 8 24 +/-6 01/03/14 - 01/31/14 01/31/14 02/28/14 02/28/14 04104114 04/04/14 05/02/14 05/02/14 05/30/14 05/30/14 07/04/14 07/04/14 08/01/14 08/01/14 08/29/14 08/29/14 - 10/03/14 10/03/14 - 10/31/14 10/31/14 - 11/28/14 11/28/14 - 01/02/15 13 17 11 8

8 9

10 14 13 10 10 18 29 35 23 20 19 19 34 27 24 26 23 29 20 +/- 10 23 +/- 9 17 7

15 +/-8 13+/- 6 13+/- 5 18 +/- 13 19 +/-8 19+/- 7 15+/- 9 17+/- 8 23 +/-6 01/03/14 - 01/31/14 01/31/14 - 02/28/14 02/28/14 - 04104114 04/04/14 - 05/02/14 05/02/14 - 05/30/14 05/30/14 - 07/04/14 07/04114 - 08/01/14 08/01/14 - 08/29/14 08/29/14 - 10/03/14 10/03/14 - 10/31/14 10/31/14 - 11/28/14 11/28/14 - 01/02/15 14 26 21 +/- 10 20 28 23 +/- 7 11 18 14+/- 6 8

16 13 8

8 16 13 7

12 17 15+/- 4 12 27 18 +/-13 16 23 19 8

18 24 21+/- 4 9

17 13 6

11 21 16 11 21 27 23 4

8 28 17 +/-10 i

5 30 17 +/- 10 01/03/14 - 01/02/15 6

31 18 +/- 10 01/03/14 - 01/02/15 8

35 18 +/- 10 01/03/14 - 01/02/15

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD 0-01 01/03/14 - 04/04114 04/04/14 - 07/04/14 07/04/14 - 10/03/14 10/03/14 - 01/02/15 MEAN D-02 01/03/14 - 04/04/14 04/04/14 - 07/04/14 07/04/14 - 10/03/14 10/03/14 - 01/02/15 MEAN D-03 01/03/14 - 04/04/14 04/04/14 - 07/04/14 07/04/14 - 10/03/14 10/03/14 - 01/02/15 MEAN D-04 01/03/14 - 04/04/14 04/04/14 - 07/04/14 07/04/14 - 10/03/14 10/03/14 - 01/02115 MEAN D-07 01/03/14 - 04/04/14 04/04/14 - 07/04/14 07/04/14 - 10/03/14 10/03/14 - 01/02/15 MEAN Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140

<~ r

~

<3

<A

<).'3

<5

<4

<2

<3

<2

<3

<2

<4

<3

<4

<3

<4

<3

< 11

<7

< 12

<6

<8

<7

<9

<2

<1

<4

<2

<7

<5

< 10

<4

<3

<5

<2

<4

<3

<6

<8

<4

<7

<6

<3

<4

<2

<3

<2

<3

<2

<3

<2

<3

< 79

< 93

< 59

< 27

< 64

80

< 32

< 21

<16

< 24

<7

< 25

<34

< 15

<5

<8

<6

<4 (1)-

< 38

<4

<2

<3

<2

<4

< 45

<5

<3

<4

<3

<2

<3

<6

< 127

13

<9

< 25

<4

<2

< 113

<9

<7

< 51

<5

<3

< 11

<8

<6

<5

< 10

<9

<4

<2

<4

<2

<4

<7

<6

<5

<6

<9

<5

<4

<2

<4

<5

<3

< 89

10

<6

<7

<8

<7

<6

<4

<6

<8

<7

< 46

<3

<2

<3

<2

<3

<4

< 38

<4

<3

< 1092

< 128

< 41

<3

<2

<3

<4

< 44

68

< 96

< 35

65

<21

< 22

< 28

< 32

<16

<9

< 25

< 45

< 21

< 25

< 80

< 159

< 73 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 i'.

D-08 01/03/14 04104/14 07104/14 10/03/14 MEAN D-10 01/03/14 04/04/14 07/04114 10/03/14 MEAN D-12 01/03/14 04104/14 07/04/14 10/03/14 MEAN D-14 01/03/14 04/04/14 07/04/14 10/03/14 MEAN D-45 01/03/14 04/04/14 07104/14 10/03/14 04104114 07/04/14 10/03/14 01/02/15 04/04/14 07/04/14 10/03/14 01/02/15 04/04/14 07/04114 10/03/14 01/02/15 04/04/14 07/04/14 10/03/14 01/02/15 04/04/14 07/04/14 10/03/14 01/02/15

<2

<3

<2

<3

<2

<3

<2

<4

<2

<2 2

3 3

3 2

3 3

5

<4

<3

<2

<3

<4

<2

<3

<4

<2

<7

<6

<5

<8

<5

12

< 10

<9

<6

<8

<7

<6

< 10

<7

<3

<2

<3

<2

<4

<3

<2

<3

<2

<3

<2

<1

<5

<6

<5

<7

<4

<9

<6

<7

<5

<3

<7

<6

<4

<5

<6

<5

<3

<2

<3

<4

<3

<4

<3

<4

<3

<4

<1

<3

<4

<2

<5

<4

<6

<5

<4

<9

<8

<6

<4

<5

<6

<4

<5

<6

<4

<2

<2 2

3 2

3 3

2

<2

<1

<2

<4

<3

<2

<3

<2

27

56

85

< 47

28

65

< 74

56

< 42

68

118

32

23

< 84

88

< 34

32

< 81

< 44

<7

< 25

< 26

15

< 10

< 22

< 21

< 27

< 24

< 32

< 20

<8

< 25

< 33

< 12

12

< 23

< 37

<10 2

2 3

2

<3

<2

<2 MEAN

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD D-53 01/03/14 - 04/04/14 04/04/14 - 07/04/14 07/04/14 - 10/03/14 10/03/14 - 01/02/15 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 MEAN C-)

D-55 01/03/14 - 04/04114 04/04/14 - 07/04/14 07/04/14 - 10/03/14 10/03/14 - 01/02/15 MEAN D-56 01/03/14 - 04104/14 04/04/14 - 07/04/14 07/04/14 - 10/03/14 10/03/14 - 01/02/15 MEAN D-58 01/03/14 - 04/04/14 04/04/14 - 07104/14 07/04/14 - 10/03/14 10/03/14 - 01/02/15

<2

<3

<4

<2

<4

<3

<2

<3

<4

<3

<4

<3

<6

<5

<2

<4

<3

<4

<3

<2

<5

<3

<8

<7

<8

<9

<7

< 14

< 11

<6

<8

< 10

<9

<6

<9

< 13

<8

<3

<2

<3

<5

<2

<4

<3

<2

<4

<3

<5

<6

<9

<11

<4

<7

<4

<8

<3

<4

<3

<5

<2

<5

<4

<3

<2

<3

<6

<3

<5

<6

<7

<5

< 10

<4

<9

<6

<4

<3

<7

< 11

<6

<3

<2

<3

<2

<4

<3

<2

<3

<2

<4

<2

<3

<2

<3

<2

<4

<2

<4

<2

<3

<2

29

< 59

< 78

< 57

< 27

90

< 133

32

< 52

< 77

< 80

< 41

24

< 97

148

< 47

18

25

< 35

< 14

< 10

< 35

< 58

<10

< 22

< 20

29

< 15

<9

< 22

< 50

19 MEAN

Table C-VIA CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I PERIOD D-01 D-02 U11UJ/14

-U111U/14

< Zb

< 6b 01/10/14

-01/17/14

< 50

< 51 01/17/14

-01/24/14

< 54 (1) 01/24/14

-01/31/14

< 42

< 21 (1) 01/31/14

-02/07/14

< 44

< 45 02/07/14

-02/14/14

< 69

< 69 02/14/14

-02/20/14

< 25

< 65 02/20/14

-02/28/14

< 12

< 31 02/28/14

-03/07/14

< 40

< 40 03/07/14

-03/14/14

< 65

< 25 03/14/14

-03/21/14

< 20

< 51 03/21/14

-03/28/14

< 58

< 60 03/28/14

-04/04/14

< 12

< 20 04/04/14

-04/11/14

< 61

< 61 04/11/14

-04/18/14

< 18

< 50 (1) 04/18/14

-04/25/14

< 54

< 57 04/25/14

-05/02/14

< 22

< 56 05/02/14

-05/09/14

< 47

< 47 05/09/14

-05/16/14

< 24

< 56 05/16/14

-05/23/14

< 50

< 51 05/23/14

-05/30/14

< 45

< 45 05/30/14

-06/06/14

< 56

< 56 06/06/14

-06/13/14

< 65

< 65 06/13/14

-06/20/14

< 60

< 61 06/20/14

-06/27/14

< 27

< 63 06/27/14

-07/04/14

< 57 (1)

< 36 07/04/14

-07/11/14

< 56

< 57 07/11/14

-07/18/14

< 55

< 53 07/18/14

-07/25/14

< 22

< 22 07/25/14

-08/01/14

< 50

< 51 08/01/14

-08/08/14

< 65

< 66 08/08/14

-08/15/14

< 37

< 38 08/15/14 - 08/22114

< 23 (1)

< 44 (1) 08/22/14 - 08/29/14

< 69

< 70 08/29/14 - 09/05/14

< 21

< 49 09/05/14 - 09/12/14

< 56

< 20 09/12/14 - 09/19/14

< 68

< 64 09/19/14 - 09/26/14

< 63

< 63 09/26/14 - 10/03/14

< 22

< 56 10/03/14 - 10/10/14

< 57

< 57 10/10/14 - 10/17/14

< 17

< 45 10/17/14 -

10/24114

< 50

< 50 10/24/14 - 10/31/14

< 11

< 28 10/31/14 - 11/07/14

< 20

< 52 11/07/14 - 11/14/14

< 11

< 28 11/14/14 - 11/21/14

< 14

< 36 11/21/14 - 11/28/14

< 17

< 44 11/28/14 - 12/05/14

< 15

< 39 12/05/14 - 12/12/14

< 25

< 50 12/12/14 - 12/19/14

< 28

< 67 12/19/14 - 12/26/14

< 34

< 62 12/26/14 - 01/02/15

< 28

< 63 I

D-03

( 1)

4(1)

(1)0 (1)9 (1)2 (1)3 (1)5

(1)

(1)7 (1)5 (1)0 (1)8 (1)2 (1)8

<36

57

53

< 66

63 0-04

< 50

< 54

< 42

< 44

< 69

< 65

< 30

< 40

< 65

< 51

< 24

< 19

< 61

< 47

< 56

< 47

< 56

< 50

< 45

< 56

< 65

< 60

< 65

< 58 (1)

< 56

< 53

< 22

< 50

< 65

< 37

< 44 (1)

< 69

< 49

< 52

< 63

< 56

< 22

< 45

< 50

< 28

< 51

< 27

< 36

< 44

< 40

< 49

< 66

< 62

< 63 D-07

<b

< 51

< 54

< 43

< 65

< 31

< 40

< 66

< 53

< 58

< 20

< 24

< 46

< 54

< 57

< 48

< 56

< 51

< 44

< 58

< 67

< 63

< 65

< 22

< 23

< 9

< 28

< 26

< 44

< 42

< 70

< 50

< 51

< 30

< 66

< 57

< 58

< 45

< 18

< 28

< 51

< 28

< 34

< 44

< 39

< 51

< 69

< 60

< 63 GROUP 11 D-45 D-53 0-56 0-58

< ~u

< 57

< 31

< 45

< 41

< 63

< 64

< 34

< 40

< 67

< 51

< 55

< 20

< 64

< 40

< 69

< 56

< 49

< 62

< 49

< 45

< 64

< 66

< 29

< 62

< 41

< 23

< 39

< 12

< 52

< 38

< 41

< 60

< 61

< 48

< 44

< 58

< 69

< 59

< 55

< 29

< 27

< 63

< 41

< 45

< 51

< 56

< 33

< 65

< 61

< 23

< 57

< 42

< 45

< 48

< 62

< 65

< 35

< 40

< 67

< 50

< 40

< 19

< 57

< 48 (1)

< 50 (1)

< 68 (1)

< 69 (1)

< 67 (1)

< 53 (1)

< 48

< 68

< 63

< 64

< 61

< 17

< 59

< 60

< 26

< 52

< 64

< 41

< 38

< 64

< 54

< 58

< 64

< 51

< 67

< 58

< 59

< 54

< 29

< 63

< 47

< 43

< 63

< 61

< 59

< 62

< 64

< 58

< 57

< 42

< 19

< 48

< 62

< 64

< 35

< 40

< 66

< 50

< 40

< 19

< 57

< 47

< 44

< 64

< 57

< 45

< 48

< 68

< 63

< 64

< 65

< 41

< 59

< 60

< 26

< 52

< 68

< 17

< 38

< 63

< 54

< 58

< 64

< 54

< 67

< 57

< 54

< 29

< 64

< 47

< 41

< 62

< 61

< 59

< 62

< 63

< 58

< 57

-c 42

< 45

< 48

< 26

< 64

< 35

< 17

< 66

< 47

< 40

< 19

< 57

< 47

< 44

< 64

< 57

< 45

< 29

< 68

< 34

< 64

< 65

< 41

< 59

< 60

< 26

< 52

< 68

< 41

< 38

< 26

< 54

< 58

< 64

< 54

< 67

< 57

< 54

< 29

< 64

< 47

< 43

< 62

< 61

< 59

< 62

< 63

< 58 MEAN-(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1 4

Table C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP III IGROUP IV PERIOD D-08 D-10 0-14 D-55 D-12 0llU3114 -

1/11U/14

< W5

< =

< bb

,b

< 5 01/10/14 - 01/17/14

< 58

< 25

< 58 01/17/14 - 01/24/14

< 54

< 31

< 32

< 44

< 31 01/24/14 - 01/31/14

< 50

< 48

< 50 01/31/14 - 02/07/14

< 41

< 19

< 46

< 41 02/07/14 - 02/14/14

< 62

< 63

< 62 02/14/14 -02/20/14

< 65

< 64

< 65

< 64 02/20/14 - 02/28/14

< 31

< 34

< 36

< 34 02/28/14 - 03/07/14

< 41

< 42

< 41 03/07/14 - 03/14/14

< 66

< 67

< 68

< 67 03/14/14 - 03/21/14

< 53

< 51

< 53

< 51 03/21/14 - 03/28/14

< 56

< 58

< 55

< 38

< 55 03/28/14 - 04/04/14

< 20

< 19

< 20

< 20 04/04/14 - 04/11/14

< 62 (1)

< 63

< 64

< 59

< 64 04/11/14 - 04/18/14

< 46

< 40

< 47

< 40 04/18/14 - 04/25/14

< 32

< 69

< 45

< 69 04/25/14 - 05/02/14

< 57

< 53

< 54

< 65

< 54 05/02/14 - 05/09/14

< 48

< 20

< 49

< 59

< 49 05/09/14 - 05/16/14

< 56

< 61

< 62

< 57

< 62 05/16/14 - 05/23/14

< 48

< 49

< 47

< 20 05/23/14 - 05/30/14

< 51

< 50

< 45

< 50 05/30/14 - 06/06114

< 63

< 62

< 27

< 58

< 64 06/06/14 - 06/13/14

< 60

< 66

< 60 06/13/14 - 06/20/14

< 62

< 63

< 68

< 63 06/20/14 - 06/27/14

< 66

< 25

< 62

< 66

< 62 06127/14 - 07/04/14

< 41

< 53 (1) 07/04114 - 07/11/14

< 50

< 54

< 61

< 54 07/11/14 - 07/18/14

< 65

< 68

< 66

< 60

< 66 07/18/14 - 07/25/14

< 28

< 34

< 28

< 27

< 28 07/25/14 - 08/01/14

< 52

< 53

< 23

< 53 08/01/14 - 08/08/14

< 69

< 68

< 70

< 70 08/08/14 - 08/15/14

< 44

< 24

< 41

< 44 08/15/14 - 08/22/14

< 14

< 41

< 39

< 41 08/22/14 - 08/29/14

< 67

< 36

< 60

< 66 08/29/14 - 09/05/14

< 37

< 59

< 61

< 58

< 60 09/05/14 - 09/12/14

< 20

< 49

< 48

< 55

< 48 09/12/14 - 09/19/14

< 62

< 64

< 68

< 63 09/19/14 - 09/26/14

< 24

< 58

< 58 09/26/14 - 10/03/14

< 29

< 69

< 69 10/03/14 - 10/10/14

< 25

< 59

< 59 10/10/14 - 10/17/14

< 24

< 56

< 59

< 56 10/17/14 - 10/24/14

< 44

< 61 (1)

< 44

< 54

< 44 10/24/14 - 10/31/14

< 11

< 27

< 31

< 27 10/31/14 - 11/07/14

< 26

< 63

< 63 11/07/14 - 11/14/14

< 17

< 41

< 43

< 48

< 41 11/14/14 - 11/21/14

< 45

< 19

< 45

< 44

< 45 11121/14 - 11/28/14

< 23

< 54

< 63

< 54 11/28/14 - 12/05/14

< 55

< 54

< 62

< 22 12/05/14 - 12/12/14

< 63

< 61

< 63

< 61

< 63 12/12/14 - 12/19/14

< 64

< 25

< 65

< 64 12/19/14 - 12/26/14

< 21

< 61

< 63

< 61 12/26/14 - 01/02/15

< 66

< 62

< 58

< 66 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-I5

Table C-VII.1 COLLECTION PERIOD CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA FARM D-25 (1) Samples were not available in 2014 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/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 (1) Samples were not available in 2014 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 PERIOD Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-137 Ba-140 La-140 U-CUN I KUL Beets Cabbage D-QUAD 1 Kale Turnips D-QUAD 2 Cabbage Potatoes 09/20/14

< 11

< 11 09/20/14

< 13

< 16 MEAN 09/19/14

< 17

< 16 09/19/14

< 17

< 18 MEAN 09/20/14

< 14

< 13 09/20/14

< 9

< 10

< 29

< 11

< 25

< 10

< 29

< 12

< 29

< 16

< 39

< 16

< 39

< 16

39

< 16

< 38

< 19

34

< 13

< 31

< 15

< 23

< 9

< 23

< 11

< 26

< 11

< 24

< 16

22

< 11

< 22

< 11

35

< 15

< 35

< 15

< 30

< 13

< 31

< 11

< 20

< 24

< 8

< 27

< 33

< 12

< 26

< 44

< 12

< 28

< 48

< 15

< 26

< 32

< 12

< 20

< 26

< 9

< 24

< 39

< 12

< 20

< 27

< 9

< 26

< 44

< 14

< 20

< 30

< 10 00

11

< 53

< 14

< 85

17

19 MEAN D-QUAD 3 Cabbage 09/20/14

< 12

< 14 Sweet potatoes 09/20/14

< 10

< 16

< 103

< 22

< 17

< 106

< 30

< 14 80

< 18

< 11 63

< 13

< 13 87

< 20

< 9 61

< 13

< 16 91

< 22

' 12 67

< 15 MEAN D-QUAD 4 Turnip greens Turnips 09/20/14

< 13

< 14 09/20/14

< 12

< 11 MEAN

Table C-IX.1 QUARTERLY OSLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF MREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION CODE MEAN 4.,-) q* n' JAN - MAR APR - JUN JUL - SEP OCT - DEC u-u1-1 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-12-1 D-12-2 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 D-58-1 D-58-2 D-101-1 D-101-2 D-102-1 D-102-2 D-103-1 D-103-2 D-104-1 D-104-2 D-105-1 D-105-2 D-106-1 D-106-2 D-107-1 D-107-2 D-108-1 D-108-2 D-109-1 D-109-2 D-110-3 D-110-4 D-111-1 31.4 1 11.8 31.4 + 9.9 31.9 +/- 4.6 32.1 +/- 10.2 28.0 +/- 8.2 28.0 +/- 7.1 31.0 + 8.6 30.0 + 10.0 31.0 + 10.3 29.9 + 7.7 29.7 +/- 8.7 31.9 +/- 8.8 31.1 +/-9.0 30.4 + 10.4 29.5 + 9.3 28.2 + 8.0 27.6 + 6.3 30.5 :t 7.7 32.5 + 8.5 33.5 t 11.2 27.6 +/- 10.5 27.7 +/- 8.5 31.7 +/- 17.3 30.5 +/- 13.1 27.1 +/- 5.5 26.5 +/- 8.2 28.2 +/- 11.1 26.9 +/- 5.9 31.4 +/- 10.2 30.7 +/- 7.3 32.9 +/- 10.3 32.3 +/- 9.6 29.9 +/- 6.8 29.2 +/- 7.1 30.8 +/- 7.4 31.3 +/- 10.5 29.7 +/- 12.3 31.5 +/- 7.7 29.7 +/- 2.8 27.9 +/- 8.2 27.8 +/- 7.1 27.5 +/- 8.2 31.9 +/- 11.3 30.4 +/- 7.2 30.0 +/- 6.6 30.2 +/- 12.8 34.8 +/- 8.6 35.2 +/- 10.1 33.5 +/- 11.3 ZZ.15 24.3 28.5 24.8 22.6 24.8 24.7 22.9 24.1 24.8 23.3 26.0 24.7 23.4 23.6 23.0 23.2 24.9 26.5 25.2 22.4 22.3 21.7 22.7 23.7 21.0 21.5 23.4 24.3 26.2 25.7 25.1 24.8 25.8 26.0 23.9 20.8 26.2 (1) 22.5 23.1 22.4 24.5 25.3 26.1 21.0 28.6 28.4 25.1 33.9 33.5 35.2 29.4 27.6 33.6 33.4 35.6 33.6 31.4 33.3 32.9 33.1 31.0 29.7 28.7 32.2 32.6 35.5 29.3 26.7 30.8 32.0 29.3 29.0 30.3 28.1 32.9 32.5 33.9 33.9 31.4 31.2 31.7 33.5 31.0 33.9 29.3 28.3 29.9 28.8 33.9 31.7 32.6 31.8 36.3 35.4 35.2 35.5 33.2 35.9 32.4 33.0 33.8 33.7 34.2 31.9 33.0 36.5 35.1 35.3 34.7 32.4 30.6 33.5 35.9 37.4 34.2 29.4 42.8 38.4 29.3 30.2 34.5 30.2 36.5 34.6 38.0 35.0 31.9 33.2 35.0 36.1 35.0 34.7 31.2 32.5 31.1 32.2 38.0 33.8 32.9 35.9 38.6 40.5 36.9 JZ.1 32.0 32.2 32.6 27.5 26.4 31.9 29.9 30.2 29.3 31.2 31.7 31.7 29.6 28.7 27.5 27.7 31.5 35.1 35.8 24.5 32.3 31.4 28.8 25.9 25.9 26.3 25.7 31.7 29.6 34.0 35.1 31.3 26.6 30.6 31.8 31.9 31.0 28.5 28.1 27.0 26.6 31.2 30.8 28.5 31.9 35.7 36.5 36.7 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-19

Table C-IX.1 QUARTERLY OSLD RESULTS FOR DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF MREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION CODE MEAN

+9.

n "

JAN - MAR APR-JUN JUL-SEP OCT - DEC D-111-2 D-1 13-1 D-1 13-2 D-114-1 D-1 14-2 D-115-1 D-115-2 D-116-1 D-116-2 D-201-1 D-201-2 D-202-1 D-202-2 D-203-1 D-203-2 D-204-1 D-204-2 D-205-1 D-205-2 D-206-1 D-206-2 D-207-1 D-207-2 D-208-1 D-208-2 D-209-1 D-209-2 D-210-1 D-210-2 D-211-1 D-211-2 D-212-3 D-212-4 D-213-1 D-213-2 D-214-1 D-214-2 D-215-1 D-215-2 D-216-1 D-216-2 D-1 12A-1 D-112A-2 30.2 +/- 11.7 29.5 +/- 3.6 29.7 +/- 9.8 28.6 +/- 7.2 28.0 +/- 8.8 30.6 +/- 8.0 32.3 +/- 10.5 34.5 +/- 7.5 32.8 +/- 10.4 34.1 +/- 11.2 34.5 +/- 8.4 31.5 +/- 8.2 30.5 +/- 8.8 31.2 +/- 1.6 29.5 +/- 4.9 29.0 +/- 8.0 28.0 +/- 7.0 28.1 +/- 9.4 29.5 +/- 9.2 30.9 +/- 9.0 30.2 +/- 7.9 29.1 +/- 6.0 29.0 +/- 7.4 26.8 +/- 9.1 27.3 +/- 4.0 22.9 +/- 17.5 32.4 +/- 12.8 29.3 +/- 7.6 30.4 +/- 8.5 32.8 +/- 11.8 30.8 +/- 10.0 28.1 +/- 8.1 28.2 +/- 7.1 27.0 +/- 7.4 27.2 +/- 6.5 33.2 +/- 5.7 32.5 +/- 10.6 33.9 +/- 9.9 32.3 +/- 9.5 31.5 +/- 14.4 34.0 +/- 3.7 29.3 +/- 8.1 30.1 +/- 9.6 21.9 (1) 23.4 23.4 21.9 25.0 25.1 30.0 27.1 28.2 28.3 25.7 24.4 (1) 26.4 23.1 23.0 21.7 22.6 25.0 25.4 25.7 23.6 20.5 25.6 22.5 41.7 23.6 26.1 24.6 24.0 22.8 23.5 21.8 22.6 28.9 24.8 26.8 25.4 22.2 31.3 24.4 23.3 33.4 29.5 31.8 29.8 29.9 31.8 34.7 35.4 34.2 37.7 37.4 34.2 31.8 (1) 31.1 30.5 29.2 31.5 31.9 33.2 34.0 29.9 30.5 29.6 29.1 10.7 30.2 30.7 30.6 38.0 31.4 32.6 29.4 29.7 28.7 35.1 34.8 35.8 34.3 33.6 34.6 30.1 32.3 35.1 31.3 34.8 31.6 32.2 34.5 37.3 39.0 37.2 40.0 36.7 34.5 34.8 31.7 31.8 32.1 31.2 31.7 31.9 35.3 32.7 32.8 31.9 30.6 28.9 29.9 30.7 31.9 36.1 35.9 36.0 29.2 32.0 29.6 30.1 34.5 36.8 38.2 36.2 39.5 35.4 34.2 34.3 30.4 27.7 28.6 29.6 28.0 31.0 32.0 33.6 (1) 30.6 35.4 31.6 31.0 30.6 28.8 30.2 28.7 27.4 31.7 30.0 28.5 27.9 30.1 26.3 25.5 28.5 27.1 30.9 28.6 32.6 31.6 27.9 27.7 27.0 27.2 34.1 33.6 34.8 33.3 30.6 34.8 28.4 30.6 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-20

TABLE C-IX.2 MEAN QUARTERLY OSLD RESULTS FOR THE INNER RING, OUTER RING, OTHER AND CONTROL LOCATIONS FOR DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF MREM/QUARTER +/- 2 STANDARD DEVIATION OF THE STATION DATA COLLECTION PERIOD INNER RING

+/-2 S.D.

OUTER RING OTHER CONTROL JAN-MAR APR-JUN JUL-SEP OCT-DEC 24.6 +/- 4.4 32.1 +/- 4.4 34.7 +/- 5.1 30.5 +/- 5.9 25.2 +/- 7.7 31.7 +/- 9.4 33.5 +/- 6.0 30.1 +/- 5.4 24.0 +/- 3.3 32.0 +/- 5.2 34.2 +/- 6.0 30.3 +/- 5.7 23.3 +/- 0.8 30.4 +/- 1.8 33.6 +/- 3.3 28.1 +/- 1.7 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF MREM/QUARTER LOCATION SAMPLES PERIOD ANALYZED MINIMUM PERIOD MAXIMUM PERIOD MEAN

+ 2 S.D.

INNER RING OUTER RING OTHER CONTROL 133 126 20.8 10.7 40.5 41.7 42.8 34.7 30.6 +/- 8.9 30.1 +/- 9.5 30.1 +/- 9.2 28.8 +/- 8.1 96 21.0 8

23.0 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-1 16-2, 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 - 2014 D-52 (C) DesPlaines River at Will Road

-I C

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 - 2014 D-54 (C) Kankakee River a.

14 12 10 8

6 4

2 0

01-31-03 p$~

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

4 0

07-28-06 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 - 2014 D-21 Illinois River at EJ&E Bridge C) 0.

30 25 20 15 10 5

0 04-27-07 11-08-08 05-23-10 12-05-11 06-18-13 12-31-14 D-51 Dresden Lock & Dam 0.

12 10 8

6 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 - 2014 D-52 (C) Des Plaines River at Will Road 600 500 400 300 200 100 U

0.

o 4-03-31-00 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 VALUE,'

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 - 2014 D-54 (C) Kankakee River 800 700 600 500

-j 400 CL 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 c

3000 2000 1000 0

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 VALUEc 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 - 2014 D-21 Illinois River at EJ&E Bridge 1200 1000 800

-J 0.

600 400 200 0

06-29-07 12-28-08 06-29-10 12-29-11 06-29-13 12-29-14 D-51 Dresden Lock & Dam

-L C.)

2000 1800 1600 1400 1200 1000 800 600 400 200 0

03-31-00 10-18-01 05-07-03 11-23-04 06-12-06 12-30-07 D-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 - 2014 D-23 Thorsen Well 1000 800 600 400 200 UJ 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 C-0.

400 350 300 250 200 150 100 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 - 2014 D-01 Onsite Station 1 50.0 40.0 30.0 o.o 9

0 20.0 Lu 10.0 0'01-08-00 01-07-03 01-0'6-06 01-0,5-09 01-0'5-12 01-04-15 D-02 Onsite Station 2 CL) 9'u 0

50.0 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-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 - 2014 D-03 Onsite Station 3 60.0 50.0 e

40.0 E

C.)

0L 30.0 co o

20.0 10.0 0.0 I 01-08-00 10-26-02 08-13-05 05-31-08 03-19-11 01-04-14 D-04 Collins Road on Station Property coE 5C.

9 Lu C?

60.0 50.0 40.0 30.0 20.0 10.0 0.0 1-01-08-00 01-07-03 01-06-06 01-05-09 01-05-12 01-04-15 C-30

FIGURE C-10 AIR PARTICULATES - GROSS BETA - STATIONS D-07 and D-12 (C) COLLECTED IN THE VICINITY OF DNPS, 2000 - 2014 D-07 Clay Products, Dresden Road m

C-)

0.

C, w

120.0 110.0 100.0 90.0 80.0 70.0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 01-08-00 01-07-03 01-06-06 01-05-09 01-05-12 01-04-15 D-12 (C), Quarry Road, Lisbon C,,

U 9CD w

80.0 70.0 60.0 50.0 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 C-31

FIGURE C-1I AIR PARTICULATES - GROSS BETA - STATIONS D-45 and D-53 COLLECTED IN THE VICINITY OF DNPS, 2000 - 2014 D-45 McKinley Woods Road, Channahon 70.0 60.0 50.0 40.0 30.0 E

C) a.

9uJw 0

20.0 -W 1 10.0-0 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 30.0 9

20.0 uL 10.0 0.0 4--

01-08-00 01-07-03 01-06-06 01-05-09 01-05-12 01-04-15 C-32

FIGURE C-12 AIR PARTICULATES - GROSS BETA - STATIONS D-08 and D-10 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2014 D-08 Jugtown Road, Prairie Parks E

C.,

UJ C

70.0 60.0 50.0 40.0 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 E

C.,

u-J 9Cl 60.0 50.0 40.0 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 C-33

FIGURE C-13 AIR PARTICULATES - GROSS BETA - STATIONS D-13 and D-14 COLLECTED IN THE VICINITY OF DNPS, 2005 - 2014 D-13 Minooka M

C) 9Iii O

C-50.0 40.0 30.0 20.0 10.0 0.0 4 I I I

I 01-07-05 07-07-05 01-04-06 07-04-06 01-01-07 07-01-07 D-14 Center Street, Channahon 50.0 91 CL mJ 9p 12-31-14 D-13 TAKEN OUT OF SERVICE JUNE 29, 2007 AND REPLACED WITH D-55 C-34

AIR PARTICULATES -

D-56 COLLECTED IN FIGURE C-14 GROSS BETA - STATIONS D-55 and THE VICINITY OF DNPS, 2006-2014 D-55 Ridge Road, Minooka 70.0 60.0 50.0 E

40.0 a.

C 30.0 tU C-20.0 10.06-0 0.0 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 4

30.0 i5 o, 20.0 10.0 0.0 -I---

07-25-06 04-01-08 12-08-09 08-16-11 04-23-13 12-30-14 D-55 NEW STATION DECEMBER 30, 2005 REPLACED D-13 JUNE 29, 2007 D-56 NEW STATION JULY 25, 2006 C-35

FIGURE C-15 AIR PARTICULATES - GROSS BETA - STATION D-58 COLLECTED IN THE VICINITY OF DNPS, 2011-2014 D-58 Will Road Marina 60.0 50.0 e~40.0 E

4.

30.0 9

o 20.0 10.0 0.0 I

I I

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

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM

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TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

March 2014 E10854 E10855 E10857 E10856 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 95.1 91.7 pCi/L 10.9 15.1 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 96.6 112 449 186 250 248 292 230 312 321 53.0 232 100 122 122 135 111 140 187 98.5 119 491 210 253 268 297 219 323 337 53.9 223 95.3 115 121 135 99.3 147 153 AP Ce-141 Cr-51 Cs-134 Cs-1i37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 June 2014 E10858 E10913 E10914 E10916 El10915 E10917 pCi 74.1 76.4 pCi/L 2090 1760 pCi/L 85.9 91.3 pCi/L 13.8 14.5 1.04 0.72 0.98 0.94 0.91 0.89 0.99 0.93 0.98 1.05 0.97 0.95 0.98 1.04 1.05 1.06 1.01 1.00 1.12 0.95 1.22 0.97 1.19 0.94 0.95 0.95 0.90 1.01 0.91 1.03 0.94 0.99 1.04 1.00 0.97 1.03 1.13 1.00 1.06 1.05 0.99 0.95 1.02 1.07 1.00 A

Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-1i37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 86.5 111 255 147 123 105 155 106 251 218 95.1 215 122 95.1 88.7 115 72.6 193 179 90.9 124 253 162 120 112 156 102 252 224 92.6 190 122 89.8 84.1 116 76.7 189 168 AP Ce-141 Cr-51 Cs-134 Cs-1i37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi 85.6 85.2 Water Fe-55 pCi/L 1680 1810 D-I 0.93 A

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b)

TBE/Analytics Evaluation (d)

September 2014 E10946 E10947 E10949 E10948 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 90.7 96.9 pCi/L 14.0 16.4 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 92.0 117 281 141 186 137 138 162 75.2 286 97.8 212 106 131 85.7 92.8 113 53.2 202 97.6 126 288 158 193 143 142 158 73.0 297 82.1 188 103 126 93.0 92.3 103 47.5 193 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 Soil Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi 83.9 89.8 pCi/L 2010 1720 0.94 0.85 0.94 0.93 0.98 0.89 0.96 0.96 0.97 1.03 1.03 0.96 1.19 1.13 1.03 1.04 0.92 1.01 1.10 1.12 1.05 0.93 1.17 1.12 0.94 0.93 1.09 0.93 1.16 1.02 1.08 1.02 0.90 0.83 0.90 0.94 0.99 0.95 0.98 0.94 0.98 1.05 0.97 0.95 E10950 E10951 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.208 0.398 0.216 0.398 0.197 0.242 0.238 0.117 0.447 0.186 0.425 0.233 0.365 0.211 0.209 0.233 0.108 0.438 December 2014 El 1078 El1079 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 85.7 95.7 pCi/L 12.9 15.6 A

A A

A pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 85.9 205 402 156 194 122 220 183 287 224 95.1 219 406 164 198 130 225 175 297 235 D-2

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

December 2014 El1081 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 pCi pCi pCi pci pCi pCi pCi pCi pCi pCi 96.4 171 73.1 99.0 57.5 107 74.2 144 114 102 190 76.9 92.6 60.8 105 81.6 139 110 0.95 0.90 0.95 1.07 0.95 1.02 0.91 1.04 1.04 0.95 0.89 A

A A

El1080 El1082 pCi 93.5 98.2 pCi/L 1760 1970 (a)

(b)

(C)

(d)

Teledyne Brown Engineering reported result.

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

Ratio of Teledyne Brown Engineering to Analytics results.

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

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

D-3

TABLE D-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 1 OF 1)

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

Value (b)

Limits Evaluation (c)

May 2014 RAD-97 MRAD-20 Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A Water Sr-89 Sr-90 Ba-1i33 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A pCi/L 38.25 pCi/L 24.65 pCi/L 89.1 pCi/L 45.55 pCi/L 91.15 pCi/L 65.10 pCi/L 244 pCi/L 45.65 pCi/L 27.95 pCi/L 23.75 pCi/L 9.61 pCi/L 8435 pCi/filter 28.0 pCi/L 30.4 pCi/L 18.6 pCi/L 46.8 pCi/L 88.0 pCi/L 99.0 pCi/L 92.5 pCi/L 325 pCi/L 29.9 pCi/L 27.5 pCi/L 15.8 pCi/L 5.74 pCi/L 6255 pCi/filter 27.3 36.7 26.5 87.9 44.3 89.1 64.2 235 61.0 33.0 25.7 10.2 8770 27.5 - 43.6 19.2 - 30.9 74.0 - 96.7 35.5 - 48.7 80.2-101 57.8 - 73.1 212-275 31.9-75.8 21.4-40.7 21.3-30.3 7.95-11.8 7610 - 9650 A

A A

46.0 15.4-71.4 November 2014 RAD-99 31.4 21.8 49.1 89.8 98.8 92.1 310 37.6 27.4 20.3 5.80 6880 22.8 - 38.1 15.6 -25.7 40.3 - 54.5 73.7 - 98.8 88.9-111 82.9-104 279 - 362 19.4 -48.1 17.3 - 35.3 16.8 - 24.4 4.34 - 6.96 5940 - 7570 A

A A

N(1)

A A

MRAD-21 36.9 12.4 - 57.3 A

(1) The Iodine-131 was evaluated as failed with a ratio of 0. 778. No cause could be found for the slighly low activity. TBE would evaluate this as acceptabi/e with warning. A rerun was not possible due to 1-131 decay. All ERA Iodine-131 evaluations since 2004 have been acceptable. NCR 14-08 (a) Teledyne Brown Engineering reported result.

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

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

D-4

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

TELEDYNE BROWN ENGINEERING, 2014 (PAGE 1 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide*

Units Value (a)

Value (b)

Range Evaluation (c)

March 2014 14-MaW30 14-MaS30 Water Am-241 Cs-134 Cs-137 Co-57 Co-60 H-3'*

Mn-54 Ni-63 Pu-238 Pu-239/240 K-40 Sr-90**

U-234/233"*

U-238"*

Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L BqIL Bq/L Bq/L Bq/L Bq/L BqIL Bq/L Bq/L Bq/L Bq/kg Bq/kg Bq/kg Bq/kg Bqlkg Bq/kg Bqlkg Bq/kg 0.764 20.7 28.0 26.5 15.6 NR 13.5 NR 0.911 0.751 NR NR NR NR

-0.201 2.02 1300 1069 1.32 1510 669 4.14 763 0.720 23.1 28.9 27.5 16.0 321 13.9 34.0 0.828 0.676 8.51 0.225 1.45 1238 966 1.22 1430 622 695 0.504 - 0.936 16.2-300 20.2 - 37.6 19.3 - 35.8 11.2 -20.8 225-417 9.7-18.1 23.8-44.2 0.580- 1.076 0.473 - 0.879 (1) 5.96-11.06 0.158 - 0.293 1.02-1.89 (1)

(1) 867-1609 676-1256 (2) 1001 - 1859 435 - 809 (1) 487 - 904 Soil Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 A

A A

N (3)

A N (3)

N (3)

A A

A N (3)

N (3)

A A

14-RdF30 14-GrF30 14-RdV30 AP Cs-134"*

Cs-137**

Co-57"*

Co-60"*

Mn-54"*

Sr-90 Zn-65**

AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample NR Bq/sample NR Bq/sample NR Bq/sample NR Bq/sample NR Bq/sample 0.8220 Bq/sample NR Bq/sample 0.606 Bq/sample 0.7507 Bq/sample 5.96 Bq/sample 5.06 Bq/sample 11.8 Bq/sample 7.34 Bq/sample 8.95 Bq/sample 1.23 Bq/sample 8.91 1.91 1.34-2.48 1.76 1.23 - 2.29 (1) 1.39 0.97-1.81 (1) 1.18 0.83-1.53 (1) 1.77 0.53-3.01 0.77 0.39-1.16 6.04 4.74 10.1 6.93 8.62 1.46 7.86 4.23 - 7.85 3.32-6.16 7.1 - 13.1 4.85 - 9.01 6.03-11.21 1.02-1.90 5.50 - 10.22 A

A A

D-5

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

TELEDYNE BROWN ENGINEERING, 2014 (PAGE 2 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide*

Units Value (a)

Value (b)

Range Evaluation (c)

September 2014 14-MaW31 14-MaS31 Water Am-241 Cs-134-Cs-137**

Co-57***

Co-60**

Mn-54**

Ni-63 Pu-238 Pu-239/240 K-40'**

Zn-65***

Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 0.705 NR NR NR NR NR 24.07 0.591 0.0153 NR NR NR NR NR NR NR NR 694 NR 0.88 0.62-1.14 (1) 18.4 12.9-23.9 24.7 17.3-32.1 12.4 8.7-16.1 14.0 9.8-18.2 24.6 17.2-32.0 0.618 0.433 - 0.803 0.0048 (2) 161 113-209 10.9 7.6 - 14.2 Soil Cs-134***

Cs-137***

Co-57***

Co-60**

Mn-54***

K-40***

Sr-90 Zn-65"*

622 1116 779 1009 824 858 541 435-809 (1) 781-1451 545-1013 706-1312 577-1071 601-1115 379-703 A

N (4)

A A

A N (4)

N (4)

A N (3)

N (4)

A 14-RdF31 14-GrF31 AP Sr-90 Bq/sample 0.310 0.703 0.492 - 0.914 September 2014 14-RdV31 AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample 0.153 0.53 0.16-0.90 Bq/sample 0.977 1.06 0.53-1.59 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 7.31 8.93 10.8 6.31 7.76 0.738 7.16 7.38 8.14 9.2 6.11 7.10 0.85 6.42 5.17-9.59 5.70 - 10.58 6.4-12.0 4.28 - 7.94 4.97 - 9.23 0.60-1.11 4.49 - 8.35 A

A A

The MAPEP cross check isotope list has been reduced due to duplication of effort or analysis not being performed for clients.

Starting 3Q14, these nuclides will no longer be part of the TBE cross check program due to duplication of effort or analysis not being performed for clients. MAPEP evaluates non-reported analyses as failed if they were reported in the previous series.

All future gamma cross check samples for these isotopes will be provided by Analytics.

(1) False positive test.

(2) Sensitivity evaluation (3) Water, Ni-63 overlooked when reporting, but the result of 32.7 +- 1.69 would have passed the acceptance criteria. NCR 14-04 Water, the non-detected K-40 was overlooked when reporting, but would have passed the false positive test. NCR 14-04 AP, Sr-90 rerun was within the low range of the acceptqance criteria. The original and rerun results were statistically the same. No cause could be identified for the slightly low Sr-90 activity. NCR 14-04 For non reported (NR) analyses, MAPEP evaluates as failed if they were reported in the previous series. NCR 14-04 (4) AP, Sr-90 gravimetric yield was very high at 117%. Could indicate larger than normal amounts of calcium in the AP. A second fuming HNO 3 separation would be required to remove the excess calcium; The Gross Alpha AP was counted on the wrong side. NCR 14-09 AP, Gr-Beta was counted on the wrong side. When flipped over and recounted the results were acceptable. NCR 14-09 For non reported (NR) analyses, MAPEP evaluates as failed if they were reported in the previous series. NCR 14-09 (a) Teledyne Brown Engineering reported result.

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

(c) DOE/MAPEP evaluation: A=acceptable, W=acceptable with waming, N=not acceptable.

D-6

APPENDIX E ERRATA DATA

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There is no errata data for 2014.

Intentionally left blank

APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Intentionally left blank

Docket No:

50-010 50-237 50-249 DRESDEN NUCLEAR POWER STATION UNITS 1, 2 and 3 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2014 Prepared By Teledyne Brown Engineering Environmental Services m Exelon Generation.

Dresden Nuclear Power Station Morris, IL 60450 May 2015

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

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

2 A. Objectives of the RGPP.......................................

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

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

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

4 Ill. Program Description................................................................................................

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

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

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

7

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

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

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

9 B. Surface W ater Results..................................................................................

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

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

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

12 F. Leaks, Spills, and Releases........................................................................

12 G. Trends..........................................................................................................

12 H. Investigations................................................................................................

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

13

- i -

Appendices ARGPPR Appendix A Tables Table A-1 Figures ARGPPR Appendix B Tables Table B-1.1 Location Designation Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Dresden Nuclear Power Station, 2014 Security-Related Information: Maps of the Dresden Nuclear Power Station have been withheld from public disclosure under 10CFR2.390 and N.J.S.A. 47:1A-1.1 Data Tables Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Concentrations of Tritium in Precipitation Water Samples Collected in the Vicinity of Dresden Nuclear Power Station, 2014.

Table B-1.2 Table B-1.3 Table B-11.1 Table B-11.2 Table B-Ill.1

- 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 98 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 11 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 6 sentinel wells. These wells are not constructured to code or developed to a standard. The majority of these wells 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 2014, there were 674 analyses that were performed on 256 samples from 98 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.

3.

Take necessary corrective actions to protect groundwater resources.

B.

Implementation of the Objectives

1.

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

2.

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

3.

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

4.

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

C.

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

1.

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

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

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

D.

Characteristics of Tritium (H-3)

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

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

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

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

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

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 2014.

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

1.

Concentrations of gamma emitters in groundwater and surface water.

2.

Concentrations of strontium in groundwater.

3.

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

4.

Concentrations of gross alpha and gross beta in groundwater.

5.

Concentrations of Am-241 in groundwater.

6.

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

7.

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

8.

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

9.

Concentrations of Fe-55 in groundwater.

10.

Concentrations of Ni-63 in groundwater.

B.

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

1.

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

2.

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

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

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

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

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

C.

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

1.

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

a.

Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of 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 extemal 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 Routine sampling and analysis, performed per CY-DR-120-5200, Radiological Monitoring of Sewage and Wastewater Effluent, identified elevated tritium concentration in the Sewage Treatment Plant (STP) effluent. IR 1669137 was written and an investigation was performed.

Subsequently, elevated tritium concentration found in the monitoring well MD-11 near the 2/3 Condensate Storage Tanks (CSTs) indicated a possible tank leak. Using the corrective action programs and the guidance of CY-DR-170-2020, Abnormal Radiological Release, further actions were taken to locate the source of elevated tritium. The investigation determined the leak into the ground was from the 2/3 B CST, with infiltration into the STP system via a breach in a nearby sanitary sewer line. Repairs were made to the CST and STP line, a sampling and analysis plan was initiated, and routine monitoring continues at the CST area and at the STP. Tritium concentration in the STP effluent has trended down indicating that the leak has been repaired. Overall, tritium concentrations are decreasing near the CST, as well as across the Station. Tritium concentrations in MW-DN-124S and MW-DN-1241 continue to be closely monitored for the existing plume in this area. Wells that exceed the United States Environmental Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L are located onsite and are not available as a drinking water source (Table B-1.1, Appendix B).

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 at locations DSP-108, MW-DN-105S, MW-DN-1081. The concentrations ranged from 0.7 to 1.1 pCi/L.

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter of 2014 (Table B-1.1, Appendix B). Gross Alpha (dissolved) was detected at three groundwater locations. The concentrations ranged from 1.6 to 6.0 pCi/L. Gross Alpha (suspended) was detected at one groundwater location at a concentration of 2.5 pCi/L. Gross Beta (dissolved) was detected at 28 of the groundwater locations. The concentrations ranged from 2.3 to 34.1 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 three samples. 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 isotope U-233/234 and U-238 was detected at one of the two groundwater monitoring locations. The concentration of U-234 was 0.68 pCi/L and the concentration U-238 was 0.61 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-II.1, Appendix B). Tritium values ranged from the detection limit to 1,020 pCi/l.

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 2014.

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 2014.

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-Ill.1, Appendix B). Tritium was not detected in any samples.

D.

Drinking Water Well Survey No drinking water well surveys were conducted in 2014.

E.

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

F.

Leaks, Spills, and Releases During 2014 a leak at the 2/3 B CST infiltrated the STP influent piping, resulting in an abnormal release of tritium through the STP effluent. Prior to the CST leak there were no indications of contaminated site leakage into groundwater. Early detection monitoring of the sewage treatment plant effluent and pulling additional samples from the CST area helped find the CST leak.

G.

Trends Overall, tritium concentrations are decreasing near the source of the CST tritium release as well as across the Station. The Station continued to implement the tritium monitoring plan with weekly/monthly sampling of a subset of shallow and intermediate aquifer wells, sewage treatment plant water, and storm sewer water. In November 2014 the sample frequency for several wells, showing no indication of being affected by the CST release, were reduced from monthly to quarterly because there was no evidence indicating the plume was migrating in those directions. An elevated concentration persists in the area of the CST.

H.

Investigations An investigation was performed into elevated tritium at the STP effluent which identified elevated tritium concentration in well MD-1 1 near the 2/3 CSTs. The investigation determined the leak into the ground was from the 2/3 B CST, with infiltration into the STP system via a breach in a nearby sanitary sewer line.

1.

Actions Taken

1.

Compensatory Actions Repairs were made to the CST and STP line, a sampling and analysis plan was initiated, and increased routine monitoring continues at the CST area and at the STP.

2.

Actions to Recover/Reverse Plumes Remediation options are being pursued to lower tritium levels in the localized area of the 2/3 CSTs.

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APPENDIX A LOCATION DISTANCE

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TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2014 Site Site Type Location DSP-105 DSP-106 DSP-107 DSP-108 DSP-1 17 DSP-121 DSP-122 DSP-123 DSP-124 DSP-125 DSP-126 DSP-147 DSP-148 DSP-149R DSP-1 50 DSP-151 DSP-152 DSP-153 DSP-154 DSP-156 DSP-157-1 DSP-157-M DSP-157-S DSP-158-1 DSP-158-M DSP-158-S DSP-159-1 DSP-159-M DSP-159-S MW-DN-101-1 MW-DN-101-S MW-DN-102-1 MW-DN-102-S MW-DN-103-1 MW-DN-103-S MW-DN-104-S MW-DN-105-S MW-DN-106-S MW-DN-107-S MW-DN-108-1 MW-DN-109-1 MW-DN-109-S MW-DN-110-1 MW-DN-110-S MW-DN-111-S MW-DN-112-1 MW-DN-112-S MW-DN-1 13-1 MW-D N-113-S MW-DN-114-1 MW-DN-114-S MW-DN-115-1 MW-DN-115-S MW-DN-116-1 MW-DN-116-S MW-DN-117-1 MW-DN-118-S MW-DN-119-1 MW-DN-119-S MW-DN-120-1 MW-DN-120-S MW-DN-121-S Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well 30 feet east of the east wall of the EM Shop 65 feet east of east wall of EM Shop 9 feet east of the east Unit 1 Fuel Pool wall 40 ft east of the Unit 1 Sphere Northeast of Unit 1 Sphere; 825 feet west of Ross Bridge 72 feet north of 2/3 Intake Canal fence 50 feet north of the Radwaste Tank Farm Northeast corner of the Unit 1 Off-gas Building 9 feet south of Floor Drain Collector Tank Northeast comer of the Unit 2/3A CST 21 feet northwest of the northwest bend in road behind Training Building 325 feet west of Telemetry Bridge 130 feet southeast of the Flow Regulating Station building 35 feet south by southwest of the 138 KV yard fence 85 feet east of the northeast comer of the Unit I Spent Fuel Pool pad 65 feet north of the northeast corner of the Storeroom 210 feet south by southeast of the southeast corner of Maintenance Garage 150 feet east of the southeast comer of liquid hydrogen tank farm fence 33 feet west of the track; 165 feet east of the Security Checkpoint 70 feet east by northeast of the northwest comer of 138 KV yard fence 25 feet south of the south edge of the Employee Parking lot 25 feet south of the south edge of the Employee Parking lot 25 feet south of the south edge of the Employee Parking lot 53 feet west of the Kankakee River 33 feet west of the cinder track 53 feet west of the Kankakee River; 33 feet west of the cinder track 50 feet west of the Kankakee River; 33 feet west of the cinder track 250 feet west of the Thorsen house; 450 ft south of the plant access gate 250 feet west of the Thorsen house; 450 ft south of the plant access gate 251 feet west of the Thorsen house; 450 ft south of the plant access gate 60 feet north of the Unit 1 Diesel Fuel Storage 60 feet north of the Unit 1 Diesel Fuel Storage 12 feet south of the southeast comer of the MUDS Building 13 feet south of the southeast comer of the MUDS Building 280 feet west of the northwest corner of N-GET Building 281 feet west of the northwest corner of N-GET Building 50 feet north of Radwaste Tank Farm 65 feet north of the northeast comer of the Storeroom 75 feet north of the 2/3 Intake Canal fence; east of the Unit 1 Intake Canal 15 feet west by southwest of the Unit 1 CST 7 feet southwest of the southwest comer of the Unit 1 Cribhouse 8 feet north of Chemistry Building 8 feet north of Chemistry Building 25 feet west of the Waste Water Treatment (WWT) Building 25 feet west of the Waste Water Treatment (WWT) Building 9 feet east of the Floor Drain Collector Tank 100 feet south of the Chemistry Building 100 feet south of the Chemistry Building 90 feet west of the southwest corner of the Administration Building 91 feet west of the southwest corner of the Administration Building 50 feet east of the Unit 1 Clean Demineralized Water Tank 8 feet southwest of the Radiation protection Dept west access doors 11 feet south of Instrument Maintenance Shop 12 feet south of Instrument Maintenance Shop 75 feet south of the Calgon Building roll-up door 75 feet south of the Calgon Building roll-up door 35 feet east by northeast of the Unit 1 Stack Southeast comer of the Unit 1 Fuel Pool 20 feet east by northeast of the Unit 1 Sewage Ejector Building 21 feet east by northeast of the Unit 1 Sewage Ejector Building 45 feet north by northeast of the Ross Bridge railing 46 feet north by northeast of the Ross Bridge railing 7 feet west of the dirt road; 42 feet east of the 345KV yard fence A-1

TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations, Dresden Nuclear Power Station, 2014 Site Site Type Location MW-DN-122-1 MW-DN-122-S MW-DN-123-1 MW-DN-123-S MW-DN-124-1 MW-DN-124-S MW-DN-125-S MW-DN-126-S MW-DN-127-S MW-DN-134-S MW-DN-135-S MW-DN-136-S MW-DN-137-S MW-DN-140-S MW-DN-141-S MW-DN-MD-11 DSP-131 DSP-132 SW-DN-101 SW-DN-102 SW-DN-103 SW-DN-104 SW-DN-1 05 SW-DN-106 FW-1 FW-2 FW-3 FW-4 FW-5 FW-6 FW-7 FW-8 FW-9 FW-10 FW-11 FW-12 Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Precipitation Precipitation Precipitation Precipitation Precipitation Precipitation Precipitation Precipitation Precipitation Precipitation Precipitation Precipitation 150 feet north of Collins Road; northeast of the G.E. Fuel Storage Facility 150 feet north of Collins Road; northeast of the G.E. Fuel Storage Facility 400 feet west of the Thorsen house; west of the Cold Canal 400 feet west of the Thorsen house; west of the Cold Canal 10 feet south of the liquid nitrogen inerting tanks 10 feet south of the liquid nitrogen inerting tanks 40 feet east of 2/3 B CST 15 feet south of fence around Unit 2/3 A CST and B CST (outside of fence) 20 feet south of Unit 3 HRSS 20-ft North of Mausoleum Building 20-ft East of Mausoleum Building 14.5-ft South of Mausoleum Building 20-ft West of Mausoleum Building East of MW-DN-1 04S at SW comer outside of 2/3 crib house North of 'A' Waste Tank next to 2/3 main chimney Piping located between Condensate Storage Tanks.

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

Unit 2/3 Intake (DSP50) at the Ross Bridge Unit 2/3 Discharge (DSP20) at the Telemetry Bridge Unit 2/3 Return Canal at the Discharge to the Intake Canal Cold Canal (DSP34A) at the Cooling Tower walkway bridge Hot Canal (DSP34B) at the Cooling Tower walkway bridge Cooling Pond - Pool II at the east side of the Covered Bridge 40 feet southwest of Unit 2/3 Off-gas Filter Building access door, north end of guardrail 50 feet East of Chem Feed Trailer South of Stock Truck Bay rollup door Southeast comer of Unit 3 RB Interlock East of Unit 2/3 Intake Ross barrier North of Unit 1 Chimney Southeast of Unit 2 TB Trackway Southwest comer of 2/3 CST on fence South of MUDS Building on Security fence At the fence at the northwest comer of the SBO Building 30 feet east of the east wall of the EM shop; at the stanchion for RGPP well DSP-1 05 60 feet southeast of the southwest comer of the Admin Building; on the security fence A-2

ARGPPR APPENDIX B DATA TABLES

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TABLE B4.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE CBE CBG DSP-105 DSP-105 DSP-105 DSP-105 DSP-1 06 DSP-106 DSP-106 DSP-106 DSP-1 07 DSP-107 DSP-107 DSP-107 DSP-108 DSP-108 DSP-108 DSP-108 DSP-122 DSP-122 DSP-122 DSP-1 22 DSP-123 DSP-123 DSP-123 DSP-1 23 DSP-124 DSP-124 DSP-124 DSP-124 DSP-125 DSP-125 DSP-125 DSP-125 DSP-125 DSP-125 DSP-1 25 DSP-126 DSP-131 DSP-1 31 DSP-1 31 DSP-1 31 DSP-1 31 DSP-1 32 DSP-132 DSP-132 DSP-132 DSP-1 32 DSP-1 32 DSP-1 32 DSP-1 32 DSP-147 DSP-148 DSP-148 DSP-148 DSP-148 DSP-149R DSP-149R DSP-149R COLLECTION DATE 11/24/14 11124/14 03/11/14 06/02/14 08/29/14 11/05/14 03/11114 06/02/14 08/29/14 11/05/14 03/10/14 06/02/14 08/29/14 11/05/14 03/10/14 06/02/14 08/29/14 11/05/14 03/05/14 05/29/14 08/27/14 11/04/14 03/10/14 05/30/14 08/28/14 11/04/14 03/28/14 06/04/14 08/26/14 11/10/14 03/27/14 05/27/14 Original 05/27/14 Reanaly, 05/27/14 Recount 08/25/14 11/05/14 11/24/14 06/09/14 03/27/14 06/02/14 08/25/14 11/10/14 11/24/14 03/27/14 05/30/14 Original 05/30/14 ReanalyE 05/30/14 Recount 08/25/14 11/10/14 11/24/14 Original 11/24/14 Recount 06/09/14 03/31/14 06/10/14 09/04/14 11/11/14 03/31/14 06/10/14 09/04/14 H-3

< 149 609 +/- 126

< 155

< 182

< 161

< 156 1940 +/- 239 1840 +/- 247 1810 +/- 228 1720 +/- 220 2200 +/- 267 2280 +/- 286 2200 +/- 265 2000 +/- 246 647 +/- 133 525 +/- 138 407 +/- 121 420 +/- 119 785 +/- 150 682 +/- 156 733 +/- 136 804 +/- 140 1740 +/- 221 1530 +/- 211 1240 +/- 174 1430 +/- 193 1060 +/- 163 1450 +/- 209 3280 +/- 369 4330 +/- 474

< 167 48200 +/- 4440 0is 48500 +/- 4850 51300 +/- 5170 19500 +/- 1980 13500 +/- 1390 11500 +/- 1190

< 187 175

+/- 112 403

+/- 132

< 159 636

+/- 134 789

+/- 137

< 171 52000 +/- 4640

is 51600 +/- 4540 45300 +/- 4300 3120 +/- 355 1750 +/- 222 416 +/- 116 357 +/- 138 Sr-89

< 3.3

< 3.3 Sr-90

0.7

< 0.6 Gr-A (Dis)

Gr-A (Sus)

Gr-B (Dis) Gr-B (Sus)

< 2.4

< 0.7

< 2.0

< 0.7

<3.1

< 2.8

< 3.0

< 2.0

< 2.2

< 0.6 1.1 +/- 0.5 < 12.4

< 0.6

0.6

< 0.6

< 1.9

< 1.9 7.2 +/- 2.0 < 2.8 4.3 +/- 1.8 < 2.8 9.3 +/- 2.0 < 2.8 28.1 +/- 3.3 < 2.8 14.1 +/- 2.4 < 2.5 34.1 +/- 6.6 < 2.5

< 3.8

< 0.7

< 2.5

< 6.8

< 4.3

< 3.6

< 4.8

< 3.5

< 0.6

0.5

0.8

0.5

183

< 184 237 +/- 131 311 258 316 429 458

+/- 113

+/- 122

+ 136

+/- 141

1121 B-1

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE DSP-149R 11/11/14 H-3 Sr-89 Sr-90 Gr-A (Dis)

Gr-A (Sus)

Gr-B (Dis) Gr-B (Sus)

DSP-150 DSP-150 DSP-150 DSP-150 DSP-151 DSP-i 51 DSP-i 51 DSP-i 51 DSP-i 54 DSP-156 DSP-156 DSP-156 DSP-156 DSP-1571 DSP-157S DSP-1591 DSP-159S MD-i1 MD-i1 MD-11 MW-DN-1011 MW-DN-1011 MW-DN-1011 MW-DN-1011 MW-DN-IOIS MW-DN-10IS MW-DN-101S MW-DN-101S MW-DN-1021 MW-DN-1021 MW-DN-1021 MW-DN-1021 MW-DN-102S MW-DN-102S MW-DN-102S MW-DN-102S MW-DN-1031 MW-DN-103S MW-DN-104S MW-DN-104S MW-DN-104S MW-DN-104S MW-DN-105S MW-DN-105S MW-DN-105S MW-DN-105S MW-DN-106S MW-DN-107S MW-DN-107S MW-DN-107S MW-DN-107S MW-DN-1081 MW-DN-1081 MW-DN-1081 MW-DN-1081 MW-DN-1091 MW-DN-1091 MW-DN-1091 03/11/14 06/02/14 08/28114 11/05/14 03/11/14 06/02/14 08/29/14 11/05/14 06/09/14 03/31/14 06/10114 09/04114 11/11/14 06/09/14 06/09/14 06/10/14 06/10/14 11/24/14 11/24/14 11/24/14 03/10/14 05/30/14 08/28/14 11/04/14 03(10114 05/30/14 08/28/14 11/04/14 03/27/14 06/04/14 08/26/14 11/10/14 03/27/14 06/04/14 08126/14 11/10/14 06/09/14 06/09/14 03/05/14 05/29/14 08/27/14 11/04/14 03/11/14 06/02/14 08/29/14 11/05/14 06/10/14 03/27/14 06/04/14 08/26/14 11/05/14 03/28/14 05/30/14 08/28/14 11/04/14 03/05/14 05/29/14 08/27/14 459 + 135

< 163

< 183

< 157

< 173

< 165

< 187

< 157

< 173

< 185 333 +/- 139

< 186 273 +/- Il1 224 +/- 123

< 185

< 187 325 +/- 135 Original Reanalysis Recount 186 1310000 +/-

1350000 +/-

1450000 +/-

690 +/-

868 +/-

641 +/-

800 +/-

160 192 156 173 160 174 160 190 191 184 157 193 184 184 181 192 163 192 164 182 165 193 186 190 182 125000 < 2.9 125000 140000 134 166

< 4.6 130 153

< 0.5

< 0.6

< 2.3

< 1.2

< 4.4

< 0.5

< 2.7

< 0.6

< 2.2

< 0.8 6.0 +/- 2.8 < 1.2 12.9 +/- 2.2 < 2.7 12.7 +/- 2.4 < 2.7

< 6.0

< 2.8 21.4 +/- 7.4 < 2.8

< 3.0

< 19.9

< 0.6

< 3.6

< 2.3

< 6.2

< 3.1

< 0.9 1.0 +/- 0.2

< 0.8

< 1.0 2120 + 261 1420 +/- 203

< 176

< 157

< 162

< 191

< 181

< 194

< 162

< 4.8 0.7 +/- 0.4 < 1.7

< 1.2

< 1.2 22.6 +/- 2.4 < 2.7 2.5 +/- 1.2 < 2.7

< 4.6

< 0.8

< 0.9 B-2

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE MW-DN-1091 MW-DN-109S MW-DN-109S MW-DN-109S MW-DN-109S MW-DN-1 101 MW-DN-1101 MW-DN-1 101 MW-DN-1101 MW-DN-1 10S MW-DN-1 10S MW-DN-110S MW-DN-110S MW-DN-111S MW-DN-111S MW-DN-111S MW-DN-111S MW-DN-1 121 MW-DN-1 121 MW-DN-1 121 MW-DN-1 121 MW-DN-1 12S MW-DN-1 12S MW-DN-1 12S MW-DN-1 12S MW-DN-1 131 MW-DN-1 131 MW-DN-1 131 MW-DN-1 131 MW-DN-1 13S MW-DN-1 13S MW-ON-1 13S MW-DN-1i3S MW-DN-1 141 MW-DN-1 141 MW-DN-1 141 MW-DN-1 141 MW-DN-1 141 MW-DN-1 141 MW-DN-1 14S MW-DN-1 14S MW-DN-1 14S MW-DN-1 14S MW-DN-1 151 MW-DN-1 151 MW-DN-1 151 MW-ON-1 151 MW-ON-1 15S MW-DN-1 15S MW-DN-1 15S MW-DN-1 15S MW-DN-1 161 MW-DN-1 161 MW-DN-1 161 MW-DN-1 161 MW-ON-1 16S MW-DN-1 16S MW-DN-1 16S MW-ON-1 16S DATE 11/04/14 03/05/14 05/29/14 08/27/14 11/04/14 03/05/14 05/29/14 08/27/14 11/04/14 03/05/14 05/29/14 08/27/14 11/04/14 03/28/14 06/04/14 08/26/14 11/10/14 03/05/14 05/29/14 08/27/14 11/04/14 03/05/14 05/29/14 08/27/14 11/04/14 03/31/14 06/04/14 08/27/14 11/10/14 03/27/14 06/04/14 08/27/14 11/10/14 03/27/14 06/04/14 06/04/14 06/04/14 08/25/14 11/05/14 03/27/14 06/04/14 08/25/14 11/05/14 03/11/14 06/02/14 08/25/14 11/05/14 03/11/14 06/02/14 08/25/14 11/05/14 03/10/14 05/30/14 08/28/14 11/04/14 03/10/14 05/30/14 08/28/14 11/04/14 H-3 Sr-89 Sr-90 Gr-A (Dis)

Gr-A (Sus)

Gr-B (Dis) Gr-B (Sus)

I

< 189

< 181

< 192

< 161

< 196

< 181

< 192

< 160

< 192

< 181

< 192

< 165

< 195 323 + 136

< 182

< 164

< 194

< 181

< 195

< 163

< 197

< 183

< 188

< 166

< 192

< 184

< 183

< 162

< 196

< 188

< 182

< 167

< 192 6080 +/- 653 Original

< 183 Reanalysis 170 +/- 106 Recount < 194 5690 +/- 611 4980 +/- 547

< 188

< 183

< 164

< 192

< 3.7

< 0.6

< 2.2

< 0.7

< 2.4

< 0.7

< 4.0

< 1.5

<2.1

< 1.2

1.2 12.0 +/- 4.6 < 2.7 3.3 +/- 1.7 < 2.7 2.5 +/- 1.4 7.6 +/- 2.1 <2.6 322 273 271 379

+/- 117

+/- 124

+/- 115

+/- 117

< 179

< 178

< 163

< 184 735 +/- 139 205 +/- 129 306 +/- 119 358 +/- 116 229 +/- 109

< 192 195 +/- 111 307 +/- 115

< 5.2

< 0.7

< 5.9

< 0.6

< 3.0

< 1.2

< 1.2 20.7 +/- 2.6 < 2.7 2.3 +/- 1.3 < 2.7 B-3

TABLE B4.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION DATE SITE H-3 Sr-89 Sr-90 Gr-A (Dis)

Gr-A (Sus)

Gr-B tDis) Gr-B (Sus)

MW-DN-118S MW-DN-1 18S MW-DN-1 18S MW-DN-1 18S MW-DN-1191 MW-DN-1 191 MW-DN-1 191 MW-DN-1 191 MW-DN-1 19S MW-DN-1 19S MW-DN-1 19S MW-DN-1 19S MW-DN-1221 MW-DN-122S MW-DN-1241 MW-DN-1241 MW-DN-1241 MW-DN-1241 MW-DN-1241 MW-DN-1241 MW-DN-124S MW-DN-124S MW-DN-124S MW-DN-124S MW-DN-124S MW-DN-124S MW-DN-125S MW-DN-125S MW-DN-125S MW-DN-125S MW-DN-126S MW-DN-126S MW-DN-126S MW-DN-126S MW-DN-126S MW-DN-126S MW-DN-126S MW-DN-126S MW-DN-126S MW-DN-127S MW-DN-127S MW-DN-127S MW-DN-127S MW-DN-127S MW-DN-127S MW-DN-134S MW-DN-134S MW-DN-134S MW-DN-134S MW-DN-135S MW-DN-135S MW-DN-135S MW-DN-135S MW-DN-136S MW-DN-136S MW-DN-136S MW-DN-136S MW-DN-137S MW-DN-137S 03/10/14 06/02/14 08/29/14 11/05/14 03/10/14 05/30/14 08/28/14 11/04/14 03/10/14 05/30/14 08/28/14 11/04/14 06/10114 06/10/14 03/28/14 03/28/14 03/28/14 06/04/14 08/26/14 11/10/14 03/28/14 03/28114 03/28/14 06/04/14 08/26/14 11/10/14 03/28/14 06/04/14 08/26/14 11/10/14 03/27/14 391 1 122 440 +/- 129 386 + 122 394 + 120

< 178

< 191

< 180 264 + 113

< 178

< 190

< 180

< 161

< 192

< 194 Original 19200 +/- 1960 Reanalysis 16200 + 1660 Recount 16600 t 1710 36700 +/- 3720 40300 +/- 3990 34300 +/- 3460 Original 42200 +/- 4160 Reanalysis 35700 + 3600 Recount 38000 + 3850 13500 + 1400 11500 +/- 1180 9570 + 995

< 182

< 171

< 177

< 160 882 + 164

< 2.3

< 0.7

< 4.9

< 0.8

< 4.4

< 0.5

< 1.8

< 2.4

< 4.2

< 10.0

< 4.7

< 4.8

< 13.1

< 1.8

< 2.8

< 1.2

< 1.2 7.0 +/- 1.8 <2.6 20.2 +/- 2.5 < 3.7 16.8 +/- 2.7 < 2.7 8.2 +/- 2.4 < 2.7 12.6 +/- 4.5 < 2.7

< 6.6

< 2.7 5.4 +/- 2.4 < 2.7

< 2.8

< 2.5

< 0.7

< 2.3

< 0.6 06/04/14 Original 06/04/14 Reanalysis 06/04/14 Recount 08/26/14 11/10/14 Original 11/10/14 Reanalysis 11/10/14 Recount 11/25/14 03/27/14 06/04/14 08/26/14 11/05/14 Original 11/05/14 Reanalysis 11/05/14 Recount 03/11/14 06/09/14 09/04/14 11/03/14 03/11/14 06/09/14 09/04/14 11/03/14 03/11/14 06/09/14 09/04/14 11/03/14 03/11/14 06/09/14 29700 +/- 3020 35600 +/- 3590 36900 +/- 3720 12400 +/- 1280 45900 +/- 4140 45300 +/- 4570 48800 +/- 4880 19200 +/- 1950 447 +/- 143 301 +/- 128 591 +/- 144 1160 +/- 178 979 +/- 157 1010 +/- 171 186 194 151 151 177 193 148 183 183 196 147 149 177 197

< 2.2

< 3.4

< 0.8

< 0.6

< 2.5

< 0.8

< 5.3

< 1.2

< 3.8

< 0.8

< 3.9

< 0.6

< 3.0

< 0.5

< 3.2

< 0.4 3.7 +/- 1.7 < 0.7 1.6 +/- 1.0 < 0.7 13.9 +/- 5.0 < 2.7 6.1 +/- 1.3 < 1.7 6.4 +/- 1.2 < 1.7 11.5 +/- 4.2 < 1.7 8.7 +/- 4.4 < 2.8

< 4.5

< 4.9

< 0.7

< 1.1 B-4

TABLE B4.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION DATE SITE H-3 Sr-89 Sr-90 Gr-A (Dis)

Gr-A (Susl Gr-B tDis) Gr-B (Sus)

MW-DN-1375 MW-DN-137S MW-DN-140S MW-DN-140S MW-DN-140S MW-DN-140S MW-DN-140S MW-DN-141S MW-DN-141S MW-DN-141S MW-DN-141S MW-DN-141S U1 INTAKE 09/04114 11/03/14 03/05/14 05/29/14 Original 05/29/14 Recount 08/27/14 11104/14 03/05114 05/29114 Original 05/29/14 Recount 08/27/14 11/04/14 11/24/14

< 155

< 151 898 +/- 157 1290 +/- 189 1240 +/- 185 1190 +/- 175 837 +/- 136 949 +/- 160 1630 +/- 221 1700 +/- 228 778 +/- 155 928 +/- 145 484 +/- 120

< 5.6

< 0.6

< 2.1

< 1.2 30.5 +/- 2.7 < 2.7

< 5.2

< 0.8 B-5

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 to CBE CBG DSP-105 DSP-105 DSP-105 DSP-105 DSP-106 DSP-106 DSP-106 DSP-106 DSP-107 DSP-107 DSP-107 DSP-107 DSP-108 DSP-108 DSP-108 DSP-108 DSP-123 DSP-123 DSP-123 DSP-123 DSP-125 DSP-125 DSP-126 DSP-131 DSP-131 DSP-132 DSP-132 DSP-147 DSP-154 DSP-1571 DSP-157S DSP-1591 DSP-159S MD-11 MW-DN-1011 MW-DN-1011 MW-DN-1011 MW-DN-1011 MW-DN-101S MW-DN-101S 11/24/14 11/24/14 03/11/14 06/02/14 08/29/14 11/05/14 03/11/14 06/02/14 08/29/14 11/05/14 03/10/14 06/02/14 08/29/14 11/05/14 03/10/14 06/02/14 08/29/14 11/05/14 03/10/14 05/30/14 08/28/14 11/04/14 05/27/14 11/24/14 06/09/14 06/02/14 11/24/14 05/30/14 11/24/14 06/09/14 06/09/14 06/09/14 06/09/14 06/10/14 06/10/14 11/24/14 03/10/14 05/30/14 08/28/14 11/04/14 03/10/14 05/30/14

< 38

< 33

< 12

< 30

< 60

< 31

< 17

< 46

< 47

< 27

< 20

< 37

< 35

< 29

< 19

< 43

<44

< 30

< 17

< 56

< 41

< 29

< 45

< 35

< 13

41

< 32

< 53

< 32

< 17

< 21

< 19

< 16

< 22

< 18

< 31

< 18

< 56

< 46

< 27

< 18

< 41

< 33

< 32

< 12

< 21

< 61

< 25

< 31

< 80

< 47

< 34

< 38

< 71

35

< 66

< 46

< 75

< 85

< 56

< 33

< 111

<84

< 56

< 77

< 68

< 12

< 104

< 32

123

< 63 40

< 41

< 19

< 31

< 24

< 35

< 75

14

< 38

< 98

< 61

<3

<4

<1

<2

<3

<6

<7

<3

<2

<4

<5

<4

<5

<3

<2

<5

<4

<3

<4

<3

<2

<4

<6

<3

<2

<7

<5

<3

<4

<5

<4

<1

<4

<6

<3

+/-23 <2

<2

<3

<2

<3

<2

<5

<6

<5

<4

<3

<9

<8

<3

<6

< 15

<7

<4

< 10

< 13

<7

<5

< 10

<7

<4

<8

< 14

<8

<4

< 15

< 11

<8

< 11

<9

<3

< 10

<8

< 11

<8

<4

<5

<4

<6

<4

<7

<5

< 11

<7

<4

<9

<4

<8

<3

<7

<1

<3

<2

<5

<6

<16

<3

<6

<2

<3

<5

<8

<5

<10

<3

<5

<2

<4

<5

<7

<3

<6

<3

<6

<2

<4

<3

<7

<6

<11

<3

<6

<2

<4

<7

<14

<6

<8

<3

<6

<4

<8

<4

<8

<1

<3

<4

<8

<3

<6

<7

<9

<3

<7

<2

<4

<2

<4

<2

<4

<2

<3

<2

<5

<2

<3

<6

<2

<4

<8

<10

<4

<10

<3

<5

<2

<3

<7

<8

<4

<7

<4

<7

<1

<2

<3

<6

<8

< 14

<3

<6

<2

<3

<5

<9

<6

<10

<3

<5

<2

<4

<7

<4

<7

<4

<6

<2

<3

<4

<7

<6

<13

<3

<5

<2

<3

<8

<11

<4

<6

<4

<7

<6

<8

<4

<8

<1

<3

<4

<7

<4

<7

<6

<11

<4

<6

<2

<3

<2

<4

<2

<4

<2

<3

<5

<2

<3

<6

<2

<4

<6

<10

<6

<10

<3

<6

<2

<3

<4

<9

< 14

<4

< 11

< 15

< 12

<6

< 13

< 15

< 11

<7

< 14

< 10

< 15

<6

< 14

< 15

< 14

<6

< 14

< 15

< 14

< 13

< 15

<5

< 14

< 13

< 15

< 13

<7

<8

<7

<6

<8

<6

< 13

<6

< 13

< 14

<7

< 10

<3

<4

<3

<1

<3

<7

<3

<2

<4

<5

<6

<2

<3

<2

<4

<3

<2

<3

<4

<5

<3

<2

<6

<4

<5

<3

<5

<3

<4

<1

<4

<5

<3

<5

<7

<3

<4

<2

<3

<2

<7

<5

<4

<2

<3

<2

<5

<4

< 29

< 28

<8

< 23

< 39

< 24

< 13

< 32

< 31

< 21

< 15

< 28

< 21

< 28

< 13

< 29

< 39

< 27

< 13

< 32

< 29

< 28

< 10

< 31

< 27

< 33

< 26

< 14

< 17

< 15

< 12

< 16

< 13

< 23

< 14

< 41

< 33

< 27

< 14

< 19

<9

<8

<3

<5

< 12

<8

<4

<7

< 10

<8

<5

< 11

<7

<8

<5

<8

< 15

<8

<4

< 12

<8

<9

< 10

<3

< 12

<9

<8

<7

<4

<5

<4

<5

<4

<8

<4

< 12

< 10

<9

<4

<9 39 +/-:24 <2

<2

<50

<4

<5

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 '

1-131 Cs-134 Cs-137 Ba-140 La-140 MW-DN-101S 08/28/14 MW-DN-101S 11/04/14 MW-DN-1021 06/04/14 MW-DN-102S 06/04/14 MW-DN-1031 06/09/14 MW-DN-103S 06/09/14 MW-DN-106S 06/10/14 MW-DN-1081 03/28/14 MW-DN-1081 05/30/14 MW-DN-1081 08/28/14 MW-DN-1081 11/04/14 MW-DN-1091 05/29/14 MW-DN-109S 05/29/14 MW-DN-1131 06/04/14 MW-DN-1 13S 06/04/14 MW-DN-1161 03/10/14 MW-DN-1161 05/30/14 MW-DN-1161 08/28/14 MW-DN-1161 11/04/14 MW-DN-116S 03/10/14 MW-DN-1 16S 05/30/14 MW-DN-116S 08/28/14 MW-DN-1 16S 11/04/14 MW-DN-1 18S 03/10/14 MW-DN-118S 06/02/14 MW-DN-1 18S 08/29/14 MW-DN-1 18S 11/05/14 MW-DN-1 191 05/30/14 MW-DN-1 19S 05/30/14 MW-DN-1221 06/10/14 MW-DN-122S 06/10/14 MW-DN-1241 06/04/14 MW-DN-1241 11/10/14 MW-DN-124S 06/04/14 MW-DN-124S 11/10/14 MW-DN-125S 06/04/14 MW-DN-126S 06/04/14 MW-DN-126S 11/25/14 MW-DN-127S 06/04/14 MW-DN-134S 06/09/14 MW-DN-135S 06/09/14 MW-DN-136S 06/09/14

< 49

< 55

< 27

< 20

< 50

< 106

< 49

< 105

< 21

< 17

< 15

< 16

< 31

< 49

< 53

< 61

< 137

< 52

< 41

< 26

< 36

< 50

< 101

<54

<97

< 33

< 78

< 48

< 35

< 10

< 53

< 103

< 40

< 57

< 28

< 23

< 17

< 15

<54

< 107

< 36

< 117

< 25

< 42

< 16

<32

< 37

< 33

< 55

< 45

< 19

<31

< 64

< 48

< 56

<44

<4

<11

<2

<3

<6

<4

<5

<12

<5

<6

<12

<2

<4

<2

<4

<2

<4

<5

<6

<11

<6

<7

<14

<4

<6

<14

<2

<3

<6

<5

<7

<11

<5

<6

<11

<3

<7

<4

<9

<1

<2

<6

<9

<6

<5

<11

<3

<7

<2

<4

<5

<13

<3

<4

<8

<3

<7

<2

<4

<3

<4

<8

<6

<10

<2

<5

<6

<13

<6

<11

<4

<10

<3

<5

<10

<5

<10

<2

<4

<2

<4

<2

<4

<11

<5

<13

<4

<11

<3

<6

<9

<10

<3

<6

<4

<8

<1

<2

<6

<10

<4

<9

<3

<5

<2

<4

<7

<11

<5

<8

<3

<5

<2

<3

<7

<5

<10

<2

<3

<6

<12

<8

<9

<2

<5

<2

<4

<2

<9

<2

<5

<3

<9

<3

<6

<5

<10

<3

<6

<5

<6

<4

<6

<1

<2

<4

<2

<4

<5

<7

<3

<5

<9

<6

<9

<2

<4

<2

<4

<2

<3

<6

<10

<7

<10

<5

<12

<3

<5

<6

<10

<6

<10

<3

<6

<4

<8

<1

<2

<6

<9

<5

<10

<3

<5

<2

<3

<5

<11

<4

<7

<3

<5

<2

<3

<4

<7

<6

<11

<2

<4

<7

<12

<6

<9

<2

<4

<2

<4

<5

<6

<3

<5

<8

<3

<6

<4

<8

<2

<5

<3

<4

<3

<6

<1

<2

<4

<2

<4

14

< 14

<8

<7

<6

< 15

14

14

< 15

13

12

< 10

< 13

<4

< 13

<15

15

<6

14

< 13

<6

<13

< 15

< 10

<15

< 14

<8

< 11

<7

<13

<8

14

< 10

<9

<11

<6

<9

<5

<2

<4

<5

<4

<6

<2

<5

<6

<7

<6

<3

<5

<6

<5

<3

<4

<5

<1

<5

<6

<5

<6

<2

<3

<2

<5

<7

<3

<4

<2

<4

<5

<6

<2

<6

<7

<6

<2

<5

<2

<3

<4

<3

<4

<3

<2

<3

<1

<2

< 33

< 25

< 32

<34

16

< 14

< 12

< 35

< 40

<34

25

< 32

< 35

23

31

<9

<34

30

28

< 13

< 35

30

< 26

12

< 26

36

17

< 35

<16

16

30

15

29

19

32

< 27

18

<24

<11

17

16

< 11

<6

<11

<12

<5

<4

< 12

< 11

< 12

<8

<6

< 13

<6

<8

<2

<8

<10

<9

<4

<7

<10

<9

<4

<8

< 10

<6

<7

< 10

<5

<4

<14

<5

<8

<6

<13

<8

<7

<8

<4

<5

<21 49+/-23 <2

<2

<5

<20

<36

<2

<5

<41

<57

<5

<4

<13

<26

<22

<3

<6

<42

<45

<4

<10

<30

<64

<3

<7

<44

<99

<5

<10

<27

<84

<4

<3

<6

<22

<18

<3

<4

<31

<35

<3

<4

<8

<13

<10

<1

<3

<20

<16

<2

<5

<20

<17

<2

<4

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-DN-137S MW-DN-141S Ul INTAKE COLLECTION Be-7 DATE 06/09/14

< 16 05/29/14

< 37 11/24/14

< 21 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

< 32

< 41

< 22

<1

<4

<2

<4

<2

<4

<1

<10

<5

<4

<2

<3

<7

<4

<2

<6

<2

<3

<7

<4

<7

<1

<11

<4

<9

<2

<4

<2

<13

<4

< 27

< 10

<17

<5 60

TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE CBE CBG DSP-125 DSP-1 31 DSP-1 32 MD-1I MW-DN-1241 MW-DN-124S MW-DN-126S Ul INTAKE COLLECTION Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 DATE 11/24/14

< 0.09

< 0.15

< 0.10 11/24/14

< 0.16

< 0.04

< 0.11

< 0.11 11/24/14

< 0.06

< 0.07

< 0.03

< 0.17

< 0.15 11/24/14

< 0.13

< 0.09

< 0.05

< 0.05 11/24/14

< 0.13

< 0.06

< 0.14

< 0.16

< 0.17 11124/14

< 0.09

< 0.02

< 0.17

< 0.10 06/04/14

< 0.11

< 0.05

< 0.08

< 0.09

< 0.09 06104/14

< 0.09

< 0.08

< 0.06

< 0.08

< 0.09 11/25/14

< 0.07

< 0.03

< 0.07

< 0.03

< 0.08 11/24/14

< 0.02

< 0.08

< 0.04

< 0.13

< 0.09 U-234 U-235 U-238 Fe-55 Ni-63

< 0.02

< 0.07

< 0.06

< 0.04

< 0.05

< 0.14

< 0.19

< 0.07 0.68

< 0.02

< 0.06

< 0.04

< 0.05

< 0.06

< 0.02

< 0.13

< 0.06

+ 0.20 < 0.02

< 0.02

< 0.07

< 0.03

< 0.04

< 0.02

< 0.19

< 0.15

< 0.05 0.61 +/- 0.18

< 185

< 82

< 153

< 186

< 155

< 164

< 141

< 154

< 121

< 103

< 4.2

< 4.5

< 4.2

< 4.1

< 3.8

< 4.6

< 4.0

< 3.8

< 3.9

< 4.3

TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE SW-DN-101 SW-DN-101 SW-DN-101 SW-DN-101 SW-DN-102 SW-DN-102 SW-DN-102 SW-DN-102 SW-DN-103 SW-DN-103 SW-DN-103 SW-DN-103 SW-DN-104 SW-DN-104 SW-DN-104 SW-DN-104 SW-DN-105 SW-DN-105 SW-DN-105 SW-DN-105 SW-DN-106 SW-DN-106 SW-DN-106 SW-DN-106 COLLECTION DATE 03/11/14 06/10/14 09/04/14 11/11/14 03/11/14 06/10/14 09/04/14 11/11/14 03/11/14 06/10/14 09/04/14 11/11/14 03/11/14 06/09/14 09/04/14 11/11/14 03/11/14 06/09/14 09/04/14 11/11/14 03/11/14 06/09/14 09/04/14 11/11/14 H-3 180 343 +/- 141 150 151 772 +/- 154 963 +/- 171 150 338 +/- 132 889 +/- 161 950 +/- 170 152 408 +/- 115 1150 +/- 174 871 +/- 167 152 352 +/- 111 628 +/- 146 885 +/- 168 150 295 +/- 110 722 +/- 153 1020 +/- 174 150 363 +/- 114 B-10

TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE SW-DN-101 SW-DN-102 SW-DN-103 SW-DN-104 SW-DN-105 SW-DN-106 COLLECTION Be-7 DATE 06/10/14

< 22 06/10/14

< 19 06/10/14

< 18 06/09/14

< 17 06/09/14

< 20 06/09/14

< 20 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

< 44

< 16

< 30

< 41

< 47

<2

<5

<2

<5

<2

<4

<2

<4

<2

<4

<2

<4

<2

<4

<2

<3

<2

<3

<2

<4

<2

<4

<2

<3

<2

<5

<2

<4

<2

<4

<2

<5

<2

<4

<2

<4

<8

<7

<6

<7

<2

<2 18 15 15 12 15 16

<6

<5

<4

<5

TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED IN THE VICINITY OF DRESDEN NUCLEAR POWER STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 FW-1 FW-10 FW-11 FW-12 05/29/14 05/30/14 05/30/14 05/30/14 194 191 194 196 B-12

SVPLTR 15-0034, 2014 Annual Radiological Environmental Operating Report

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