Text

Annual Radiological Environmental Operating Report
	ML18130A254
Person / Time
Site:	Quad Cities
Issue date:	05/10/2018
From:	Ohr K; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	SVP-18-035
	Download: ML18130A254 (110)
	v • d • e

)L ML ,

Exelon Generation SVP-18-035 May 10, 2018 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities N1;1clear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 N RC Docket Nos. 50-254 and 50-265

Subject:

Annual Radiological Environmental Operating Report Pursuant to Technical Specifications Section 5.6.2, enclosed is the 2017 Radiological Environmental Operating Report for Quad Cities Nuclear Power Station. This Report contains the results of the Radiological Environmental Monitoring Program (REMP). In addition, the 2017 Radiological Groundwater Protection Program (RGPP) Report is included as Appendix F of the enclosure.

Should you have any questions concerning this letter, please contact Ms. Rebecca Craddick at (309) 227-3200.

R/?~

Kenneth S. Ohr Site Vice President Quad Cities Nuclear Power Station

Enclosure:

Annual Radiological Environmental Operating Report cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Quad Cities Nuclear Power Station

Enclosure Annual Radiological Environmental Operating Report

Docket No: 50-254 50-265 QUAD CITIES NUCLEAR POWER STATION UNITS 1and2 Annual Radiological Environmental Operating Report 1 January through 31 December 2017 Prepared By Teledyne Brown Engineering Envi ro nm e nta I Services Quad Cities Nuclear Power Station Cordova, IL 61242 May 2018

Intentionally left blank Table Of Contents I. Summary and Conclusions ................................................................................................ 1 II. Introduction ........................................................................................................................ 3 A. Objectives of the REMP ........................................................................................ 3

8. Implementation of the Objectives .......................................................................... 3 C. Radiation and Radioactivity ................................................................................... 3 D. Sources of Radiation ............................................................................................. 4 Ill. Program Description ......................................................................................................... 6 A. Sample Collection .................................................................................................. 6

8. Sample Analysis .................................................................................................... 8 C. Data Interpretation ................................................................................................. 8 D. Program Exceptions .............................................................................................. 9 E. Program Changes ............................................................................................... 11 IV. Results and Discussion ................................................................................................. 12 A. Aquatic Environment ........................................................................................... 12

1. Surface Water ........................................................................................... 12

2. Ground Water ........................................................................................... 12

3. Fish ........................................................................................................... 13

4. Sediment. .................................................................................................. 13

8. Atmospheric Environment ................................................................................... 14

1. Airborne .................................................................................................... 14

a. Air Particulates .............................................................................. 14

b. Airborne Iodine .............................................................................. 14

2. Terrestrial .................................................................................................. 15

a. Milk ................................................................................................ 15

b. Food Products ............................................................................... 15 C. Ambient Gamma Radiation ................................................................................. 15 D. Independent Spent Fuel Storage ........................................................................ 16 E. Land Use Survey ................................................................................................. 16 F. Errata Data ........................................................................................................... 17 G. Summary of Results - Inter-laboratory Comparison Program ........................... 17

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

Analytical Methods Tables Table B-1 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2017 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2017 Figures Figure B-1 Quad Cities REMP Sampling Locations - 2 Mile Radius, 2017 Figure B-2 Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2017 Appendix C Data Tables and Figures - Primary *Laboratory Tables Table C-1.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-1.2 Concentrations of Tritium, lron-55 and Nickel-63 in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-11.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-11.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 ii

Table C-111.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations In Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-Vl.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-Vll.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-Vll.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-Vlll.1 Concentrations of Gamma Emitters in Food Product Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table C-IX.1 Quarterly OSLO Results for Quad Cities Nuclear Power Station, 2017 Table C-IX.2 Mean Quarterly OSLO Results for the Inner Ring, Outer Ring, Other and Control Location for Quad Cities Nuclear Power Station, 2017 Table C-IX.3 Summary of the Ambient Dosimetry Program for Quad Cities Nuclear Power Station, 2017 Figures Figure C-1 Surface Water - Gross Beta - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2017 Figure C-2 Surface Water - Tritium - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2017 Figure C-3 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2017 Figure C-4 Air Particulates - Gross Beta - Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2017 Figure C-5 Air Particulates - Gross Beta - Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2017 iii

Figure C-6 Air Particulates - Gross Beta - Station Q-07 (C) Collected in the Vicinity of QCNPS, 2000 - 2010 Figure C-7 Air Particulates - Gross Beta - Stations Q-13 and Q-16 Collected in the Vicinity of QCNPS, 2005 - 2017 Figure C-8 Air Particulates - Gross Beta - Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2017 Figure C-9 Air Particulates - Gross Beta - Stations Q-41 and Q-42 (C) Collected in the Vicinity of QCNPS, 2009 - 2017 Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2017 Table D-2 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2017 Table D-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2017 Table D-4 ERA (a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2017 Table D-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2017 Appendix E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv

I. Summary and Conclusions In 2017, the Quad Cities Generating Station released to the environment through the radioactive effluent gaseous pathways, approximately 124 curies of noble gas, 1.37E-02 curies of fission and activation products, 28.6 curies of Carbon-14 and approximately 86 curies of tritium. The dose from both gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public.

There were no radioactive liquid releases in 2017 from Quad Cities Station. The results of those calculations and their comparison to the allowable limits were as follows:

NOTE: Percent of applicable limits are for Unit 1 and Unit 2 combined (Site)

Gaseous and liquid radiation doses to members of the public at locations Location %of Applicable Estimated Age Site Distance Direction Applicable Unit Effluents Organ Dose Group Limit

<meters) (toward) Limit Noble Gas Gamma - Air Dose 2.59E-03 All 1029 NNE 1.30E-02 20 mRad Noble Gas Beta - Air Dose 3.40E-04 All 1029 NNE 8.50E-04 40 mRad Iodine, Particulate Total Body 4.22E-02 Child 1029 NNE 1.69E-01 25 mrem C-14 & Tritium Iodine, Particulate Thyroid 2.66E-01 Infant 1029 NNE 8.87E-01 30 mrem C-14& Tritium Liquid Total Body 0 N/A Mississippi River 0 6 mrem Liquid Liver 0 N/A Mississippi River 0 20 mrem Skyshine Total Body 7.64E+OO All 800 N 3.06E+01 25 mrem Total Body (Gas + Liq+

40CFR190 7.68E+OO All 800 N 3.07E+01 25 mrem Skyshine)

The doses as a result of the radiological effluents released from the Quad Cities Generating Station were a very small percentage of the allowable limits, with the exception of 40CFR190 whole body radiation which was calculated to be 30.7%

of the 25 mrem/yr limit. The largest component of 40CFR 190 dose is attributable to BWR skyshine from N-16. This value is conservatively calculated for the hypothetical maximum exposed member of the public.

This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Quad Cities Nuclear Power Station (QCNPS) by Exelon covers the period 01 January 2017 through 31 December 2017. During that time period, 1564 analyses were performed on 1449 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of QCNPS had no adverse radiological impact on the environment.

Surface water samples were analyzed for concentrations of gross beta, tritium, iron, nickel and gamma-emitting nuclides. Ground water samples were analyzed for concentrations of tritium and gamma-emitting nuclides. No fission or activation products were detected. Gross beta activities detected were consistent with those detected in previous years and consistent with the control stations.

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 samples. Cesium-137 (Cs-137) was not detected above the required LLD in any sediment samples.

Air particulate samples were analyzed for concentrations of gross beta and gamma-emitting nuclides. No fission or activation products were detected.

High sensitivity lodine-131 (1-131) analyses were performed on air samples. No 1-131 was detected.

Cow milk samples were analyzed for concentrations of 1-131 and gamma-emitting nuclides. No 1-131 was detected. Concentrations of naturally-occurring isotopes (K-40 averaging 1234 pCi/L) were consistent with those detected in previous years. No fission or activation products were detected.

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

Environmental gamma radiation measurements were performed quarterly using Optically Stimulated Luminescence Dosimeters (OSLO). Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimeters were deployed and Thermoluminescent Dosimeters (TLD) were discontinued.

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 Quad Cities Nuclear Power Station (QCNPS), consisting of two 2,957 MWth boiling water reactors owned and operated by Exelon Corporation, is located in Cordova, Illinois along the Mississippi River. Unit No.1 went critical on 16 March 1972. Unit No. 2 went critical on 02 December 1973. The site is located in northwestern Illinois, approximately 182 miles west of Chicago, Illinois.

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

A. Objectives of the 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 C. Radiation and Radioactivity All matter is made of atoms. An atom is the smallest part into which matter can be broken down and still maintain all its chemical properties.

Nuclear radiation is energy, in the form of waves or particles that is given off by unstable, radioactive atoms. Radioactive material exists naturally and has always been a part of our environment. The earth's crust, for example, contains radioactive uranium, radium, thorium and potassium.

Some radioactivity is a result of nuclear weapons testing. Examples of radioactive fallout that is normally present in environmental samples are Cesium-137 and Strontium-90. Some examples of radioactive materials released from a nuclear power plant are Cesium-137, lodine-131, Strontium-90 and Cobalt-60.

Radiation is measured in units of millirem; much like temperature is measured in degrees. A millirem is a measure of the biological effect of the energy deposited in tissue. The natural and man-made radiation dose received in one year by the average American is 300 to 400 mrem (References 2, 3, 4 in Table 11.D-1 below). Radioactivity is measured in curies. A curie is that amount of radioactive material needed to produce 37,000,000,000 nuclear disintegrations per second. This is an extremely large amount of radioactivity in comparison to environmental radioactivity.

That is why radioactivity in the environment is measured in picocuries.

One picocurie is equal to one trillionth of a curie.

D. Sources of Radiation As mentioned previously, naturally-occurring radioactivity has always been a part of our environment. Table II D-1 shows the sources and doses of radiation from natural and man-made sources.

Table 11.D-1 1

Radiation Sources and Corresponding Doses <>

NATURAL MAN-MADE Radiation Dose Radiation Dose Source Source (millirem/year) (millirem/year)

Internal, inhalation <2> 228 Medical <3 > 300 External, space 33 Consumer <4> 13 Internal, ingestion 29 lndustria1<5> 0.3 External, terrestrial 21 Occupational 0.5 Weapons Fallout <1 Nuclear Power Plants <1 Approximate Total 311 Approximate Total 314 (1) Information from NCRP Reports 160 and 94 (2) Primarily from airborne radon and its radioactive progeny (3) Includes CT (147 mrem), nuclear medicine (77 mrem), interventional fluoroscopy (43 mrem) and conventional radiography and fluoroscopy (33 mrem)

(4) Primarily from cigarette smoking (4.6 mrem), commercial air travel (3.4 mrem), building materials (3.5 mrem), and mining and agriculture (0.8 mrem)

(5) Industrial, security, medical, educational, and research Cosmic radiation from the sun and outer space penetrates the earth's atmosphere and continuously bombards us with rays and charged particles. Some of this cosmic radiation interacts with gases and particles in the atmosphere, making them radioactive in turn. These radioactive byproducts from cosmic ray bombardment are referred to as cosmogenic radionuclides. Isotopes such as beryllium-7 and carbon-14 are formed in this way. Exposure to cosmic and cosmogenic sources of radioactivity results in about 33 mrem of radiation dose per year.

Additionally, natural radioactivity is in our body and in the food we eat (about 29 millirem/yr), the ground we walk on (about 21 millirem/yr) and the air we breathe (about 228 millirem/yr). The majority of a person's annual dose results from exposure to radon and thoron in the air we breathe. These gases and their radioactive decay products arise from the decay of naturally-occurring uranium, thorium and radium in the soil and building products such as brick, stone and concrete. Radon and thoron levels vary greatly with location, primarily due to changes in the concentration of uranium and thorium in the soil. Residents at some locations in Colorado, New York, Pennsylvania, and New Jersey have a higher annual dose as a result of higher levels of radon/thoron gases in these areas. In total, these various sources of naturally-occurring radiation and radioactivity contribute to a total dose of about 311 mrem per year.

In addition to natural radiation, we are normally exposed to radiation from a number of man-made sources. The single largest doses from

man-made sources result from therapeutic and diagnostic applications of x-rays and radiopharmaceuticals. The annual dose to an individual in the U.S. from medical and dental exposure is about 300 mrem. Consumer products, such as televisions and smoke detectors, contribute about 13 mrem/yr. Much smaller doses result from weapons fallout (less than 1 mrem/yr) and nuclear power plants. Typically, the average person in the United States receives about 314 mrem per year from man-made sources.

Ill. Program Description A. Sample Collection Samples for the QCNPS REMP were collected for Exelon Nuclear by ATI Environmental Inc. (Midwest Labs). This section describes the general sampling methods used by Environmental Inc. to obtain environmental samples for the QCNPS REMP in 2017. Sample locations and descriptions can be found in Table B-1 and Figures B-1 and B-2, Appendix B.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, ground water, fish and sediment.

Surface water samples were collected weekly from two locations, Q-33 and Q-34 (Control). Ground water samples were collected quarterly from two locations, Q-35 and Q-36. All water samples were collected in new containers, which were rinsed with source water prior to collection.

Fish samples comprising the edible portions of commercially and recreationally important species were collected semiannually at two locations, Q-24 and Q-29 (Control). Sediment samples composed of Recently-deposited substrate were collected at two locations semiannually, Q-39 and Q-40 (Control).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, and airborne iodine. Airborne iodine and particulate samples were collected and analyzed at ten locations (Q-01, Q-02, Q-03, Q-04, Q-13, Q-16, Q-37, Q-38, Q-41 and Q-42 (control)). 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 particulate filters and air iodine samples were replaced weekly and sent to the laboratory for analysis.

Terrestrial Environment The terrestrial environment was evaluated by performing radiological analyses on samples of milk and food product. Milk samples were collected biweekly at one location (Q-26) from May through October, and monthly from November through April. All samples were collected in new plastic containers from the bulk tank, preserved with sodium bisulfite, and shipped promptly to the laboratory.

Food products were collected annually in July at five locations (Q-Control, Q-Quad 1, Q-Quad 2, Q-Quad 3, and Q-Quad 4). Various types of broadleaf and root vegetables were collected and placed in new 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 Dosimeters (OSLO) were deployed and Thermoluminescent Dosimeters (TLD) were discontinued. The relative comparison to control locations remains valid. OSLO technology is different than that used in a TLD but has the same purpose (to measure direct radiation).

Each location consisted of 2 OSLO sets. The OSLO locations were placed on and around the QCNPS site as follows:

An inner ring consisting of 15 locations (Q-101, Q-102, Q-103, Q-104, Q-105, Q-106, Q-107, Q-108, Q-109, Q-111, Q-112, Q-113, Q-114, Q-115 and Q-116). These OSLDs are located in 15 of the 16 meteorological sectors in the general area of the site boundary (approximately 0.1 - 3 miles from the site). There are no OSLDs located in the SSW sector because this sector is located over water.

An outer ring consisting of 16 locations (Q-201, Q-202, Q-203, Q-204, Q-205, Q-206, Q-207, Q-208, Q-209, Q-210, Q-211, Q-212, Q-213, Q-214, Q-215 and Q-216). These OSLDs are located in each of the 16 meteorological sectors (approximately 6.0 - 8.0 km from the site)

An other set consisting of nine locations (Q-01, Q-02, Q-03, Q-04, Q-13, Q-16, Q-37, Q-38 and Q-41). The locations are at each of the air sample stations around the site.

The balance of one location (Q-42) is the control site.

The specific OSLO locations were determined by the following criteria:

1. The presence of relatively dense population;

2. Site meteorological data taking into account distance and elevation for each of the sixteen 22.5 degree sectors around the site, where estimated annual dose from QCNPS, if any, would be most significant;

3. On hills free from local obstructions and within sight of the stack (where practical);

4. Near the closest dwelling to the stack in the prevailing downwind direction.

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

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

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

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

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

6. Concentrations of lron-55 (Fe-55) and Nickel-63 (Ni-63) in surface water C. Data Interpretation The radiological and direct radiation data collected prior to Quad Cities Nuclear Power Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Quad Cities 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) is 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 is intended as an a priori (a before the fact) estimate of a system (including instrumentation, procedure and sample type) and not as an a posteriori (after the fact) criteria for the presence of activity. All analyses were designed to achieve the required QCNPS detection capabilities for environmental sample analysis.

The minimum detectable concentration (MDC) is defined above with the exception that the measurement is an a posteriori (after the fact) estimate of the presence of activity.

2. Net Activity Calculation and Reporting of Results Net activity for a sample is 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_

is reported in all cases where positive activity was not detected.

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

For surface water, groundwater and vegetation 12 nuclides, Manganese-54 (Mn-54), Cobalt-58 (Co-58), lron-59 (Fe-59),

Colbalt-60 (Co-60), Zinc-65 (Zn-65), Zirconium-95 (Zr-95),

Niobium-95 (Nb-95), 1-131, Cesium-134 (Cs-134), Cs-137, Barium-140 (Ba-140), and Lanthanum-140 (La-140) were reported.

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

For air iodine, one nuclide, 1-131 was 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 2017 the QCNPS REMP had a sample recovery rate in excess of 99%. Sample anomalies and missed samples are listed in the tables below:

Table D-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection Reason T;t~e Code Date AP/Al Q-13 03/09/17 Low reading of 124.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months due to power outage from storm AP/Al Q-41 04/20/17 Low reading of 170.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months due to power outage from storms OSLO Q-215-1 05/04/17 OSLD missing at monthly check; collector placed Spare #

00009 6800 2 91558 AP/Al Q-41 05/19/17 Low reading of 178.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months due to power outages from storms AP/Al Q-03 08/25/17 Low reading of 141.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months due to power outage for station maintenance AP/Al Q-42 09/21/17 Low treading of 131.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months due to power outage from storm AP/Al Q-37 09/22/17 Low reading of 164.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months due to power outage from storm AP/Al Q-38 09/22/17 Low reading of 164.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months due to power outage from storm Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason T;t~e Code Date SW Q-33 01/05/17 No sample; water frozen SW Q-34 01/05/17 No sample; water frozen SW Q-33 01/12/17 No sample; water frozen SW Q-34 01/12/17 No sample; water frozen SW Q-33 02/03/17 No sample; water frozen SW Q-34 02/03/17 No sample; water frozen SW Q-33 02/09/17 No sample; water frozen SW Q-34 02/09/17 No sample; water frozen Table D-2 LISTING OF MISSED SAMPLES (cont'd)

Sample Location Collection Reason T~~e Code Date SW Q-33 12/08/17 No sample; water frozen SW Q-33 12/15/17 No sample; water frozen SW Q-34 12/15/17 No sample; water frozen SW Q-33 12/29/17 No sample; water frozen SW Q-34 12/29/17 No sample; water frozen OSLO Q-04-1,-2 12/29/17 Lost in transit to dosimetry vendor The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

E. Program Changes There were no program changes in 2017.

IV. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken weekly and composited monthly at two locations (Q-33 and Q-34). Of these locations only Q-33, located downstream, could be affected by Quad Cities' effluent releases.

The following analyses were performed:

Gross Beta Samples from all locations were analyzed for concentrations of gross beta (Table C-1.1, Appendix C). Gross beta activity was detected in 23 of 24 samples. The values ranged from 1.9 to 5.7 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C). The required LLD was met.

Tritium Quarterly composites of weekly collections were analyzed for tritium activity (Table C-1.2, Appendix C). No tritium activity was detected (Figure C-2, Appendix C). The 2000 pCi/L OCDM and contractually required 200 pCi/L LLDs were met.

Iron and Nickel Quarterly composites of monthly collections were analyzed for Fe-55 and Ni-63 (Table C-1.2, Appendix C). No Fe-55 or Ni-63 were detected. The required LLDs were met.

Gamma Spectrometry Samples from both locations were analyzed monthly for gamma-emitting nuclides (Table C-1.3, Appendix C). No nuclides associated with QCNPS were detected and all required LLDs were met.

2. Ground Water Quarterly grab samples were collected at two locations (Q-35 and Q-36). Both locations could be affected by Quad Cities' effluent releases. The following analyses were performed:

Tritium Quarterly grab samples from the locations were analyzed for tritium activity (Table C-11.1, Appendix C). No tritium activity was detected (Figure C-3, Appendix C). The 2000 pCi/L OCDM and contractually required 200 pCi/L LLDs were met.

Gamma Spectrometry Samples from all locations were analyzed for gamma-emitting nuclides (Table C-11.2, Appendix C). No nuclides associated with QCNPS were detected and all required LLDs were met.

3. Fish Fish samples comprised of various commercially and recreationally important species were collected at two locations (Q-24 and Q-29) semiannually. Location Q-24 could be affected by Quad Cities' effluent releases. The following analysis was performed:

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

No nuclides associated with QCNPS were detected and all required LLDs were met.

4. Sediment Aquatic sediment samples were collected at two locations (Q-39 and Q-40) semiannually. The location Q-39, located downstream, could be affected by Quad Cities' effluent releases. The following analysis was performed:

Gamma Spectrometry Sediment samples from Q-39 and Q-40 were analyzed for gamma-emitting nuclides (Table C-IV.1, Appendix C). Cesium-137 (Cs-137) was detected in one sample at a concentration of 137 pCi/kg dry. No other nuclides potentially associated with QCNPS were detected and all required LLDs were met.

B. Atmospheric Environment

1. Airborne

a. Air Particulates Continuous air particulate samples were collected from ten locations on a weekly basis. The ten locations were separated into three groups: Near-field samplers within 4 km (2.5 miles) of the site (Q-01, Q-02, Q-03 and Q-04),

far-field samplers between 4 and 10 km (2.5 - 6.2 miles) from the site (Q-13, Q-16, Q-37, Q-38 and Q-41) and the Control sampler between 10 and 30 km (6.2 - 18.6 miles) from the site (Q-42). 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).

Comparison of results among the four groups aid in determining the effects, if any, resulting from the operation of QCNPS. The results from the near-field locations (Group I) ranged from 5 to 27E-03 pCi/m 3 with a mean of 16E-03 pCi/m 3 . The results from the far-field locations (Group II) ranged from 6 to 33E-03 pCi/m 3 with a mean of 16E-03 pCi/m 3 . The results from the Control location (Group Ill) ranged from 7 to 30E-03 pCi/m 3 with a mean of 16E-03 pCi/m3 . Comparison of the 2017 air particulate data with previous year's data indicate no effects from the operation of QCNPS. In addition comparisons of the weekly mean values for 2017 indicate no notable differences among the three groups (Figures C-4 through C-9, Appendix C).

Gamma Spectrometrv Weekly samples were composited quarterly and analyzed for gamma-emitting nuclides (Table C-V.3, Appendix C). No nuclides associated with QCNPS were detected and all required LLDs were met.

b. Airborne Iodine Continuous air samples were collected from ten locations (Q-01, Q-02, Q-03, Q-04, Q-13, Q-16, Q-37, Q-38, Q-41 and Q-42) and analyzed weekly for 1-131 (Table C-Vl.1, Appendix C). All results were less than the LLD for 1-131.

2. Terrestrial

a. Milk Samples were collected from one location (Q-26) biweekly May through October and monthly November through April.

The following analyses were performed:

lodine-131 Milk samples from the location were analyzed for concentrations of 1-131 (Table C-Vll.1, Appendix C). No 1-131 was detected and the LLD was met.

Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma-emitting nuclides (Table C-Vll.2, Appendix C). No nuclides associated with QCNPS were detected and all required LLDs were met.

b. Food Products Food product samples were collected at four locations plus a control location (Q-Control, Q-Quad 1, Q-Quad 2, Q-Quad 3 and Q-Quad 4) annually during growing season. Four locations, (Q-Quad 1, Q-Quad 2, Q-Quad 3 and Q-Quad 4) could be affected by Quad Cities' effluent releases. The following analysis was performed:

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

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing optically stimulated luminescence dosimeters. Forty-one OSLO locations were established around the site. Results of OSLO measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C.

All of the OSLO measurements were < 30 mRem/quarter, with a range of 11.6 to 27.9 mRem/quarter. A comparison of the Inner Ring, Outer Ring and Other data to the Control Location data, indicate that the ambient gamma radiation levels from all the locations were comparable.

D. Independent Spent Fuel Storage Installation QCNPS commenced use of an Independent Spent Fuel Storage Installation (ISFSI) in Dec 2005. There are no measurable changes in ambient gamma radiation levels as a result of ISFSI operations.

E. Land Use Survey A Land Use Survey conducted during August 2017 around QCNPS was performed by ATI Environmental Inc. (Midwest Labs) for Exelon Nuclear to comply with the Quad Cities' Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident and milk producing animals in each of the sixteen 22.5 degree sectors around the site. The results from the land use census have not identified any locations, which yield a calculated dose or dose commitment, via the same pathway, that is at least 20% greater than at a location from which samples are currently being obtained. The results of this survey are summarized below:

Distance in Miles from QCNPS Sector Residence Livestock Milk Farm Miles Miles Miles N 0.6 2.7 NNE 1.2 3.1 NE 1.3 3.2 ENE 2.9 2.9 E 2.0 4.5 ESE 2.8 3.1 3.1 SE 1.7 5.3 SSE 1.1 4.0 6.6 s 0.8 4.8 SSW 3.2 3.5 SW 2.9 3.3 WSW 2.2 2.7 w 2.6 4.3 WNW 2.7 3.8 NW 2.6 4.7 NNW 2.1 2.2 Of the above listed Milk Farms, only the farm located at 3.1 miles ESE of QCNPS, listed in the sample results section as Bill Stanley Dairy, has elected to participate in the QCNPS REMP program. Participation by local farmers is voluntary.

F. Errata Data There is no errata data for 2017.

G. Summary of Results - Inter-Laboratory Comparison Program Teledyne Brown Engineering Laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices for various analytes (Appendix D). The PE samples supplied by Analytics Inc., Environmental Resource Associates (ERA) and Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

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

B. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, National Environmental Laboratory Accreditation Conference (NELAC), state-specific Performance Testing (PT) program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable.

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

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

Acceptable (flag ="A") - result within +/- 20% of the reference value

Acceptable with Warning (flag ="W') - result falls in the +/- 20%

to +/- 30% of the reference value

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

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

1. The ERA April 2017 two nuclides in water were evaluated as Not Acceptable. (NCR 17-09)

a. The Zn-65 result of 39.3 pCi/L, exceeded the lower acceptance limit of 47.2. The known value was unusually low for this study.

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

b. The Sr-89 result of 40. 7 pCi/L exceeded the lower acceptance limit of 53.8. All associated QC and recoveries were reviewed and no apparent cause could be determined for the failure. The prior three cross-check results were from 99 - 115% of the known values and the one that followed this sample (November, 2017) was 114% of the known value.

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

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

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

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

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

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

(NCR 17-19)

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

Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

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

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2017 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50*254 &50*265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD: 2017 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M) MEAN(M) MEAN(M) STATION# NONROUTINE (UNITOF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS SURFACE WATER GR-8 24 4 4.2 4.2 4.2 Q-33 INDICATOR 0 (PC/JLITER) (12/12) (11/12) (12112) CORDOVA 1.9. 5.7 3.0. 5.4 1.9-5.7 3.1 MILES SSW OF SITE H-3 8 2000 <LLD <LLD 0 FE-55 8 200 <LLD <LLD 0 Nl-63 8 5 <LLD <LLD 0 GAMMA 24 MN-54 15 <LLD <LLD 0

)> C0-58 15 <LLD <LLD 0 I

~ FE-59 30 <LLD <LLD 0 C0-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 NB-95 15 <LLD <LLD 0 ZR-95 30 <LLD <LLD 0 1-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 GROUND WATER H-3 8 2000 <LLD NA 0 (PC I/LITER)

GAMMA 8 MN-54 15 <LLD NA 0 C0-58 15 <LLD NA - 0 FE-59 30 <LLD NA 0 C0-60 15 <LLD NA - 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA 0 ZR-95 30 <LLD NA 0 1-131 15 <LLD NA 0 CS-134 15 <LLD NA 0 CS-137 18 <LLD NA 0 BA-140 60 <LLD NA 0 LA-140 15 <LLD NA 0 (M) The Mean Values are calculated using the positive values. (F) Fraction ofdetectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2017 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD: 2017 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M) MEAN(M) MEAN(M) STATION# NONROUTINE (UNITOF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS FISH GAMMA 8 (PCllKG WET) MN-54 130 <LLD <LLD 0 C0-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 C0-60 130 <LLD <LLD 0 ZN-65 260 <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 CS-134 130 <LLD <LLD 0 CS-137 150 <LLD <LLD 0 BA-140 NA <LLD <LLD 0

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

I\)

SEDIMENT GAMMA 4 (PCllKG DRY) MN-54 NA <LLD <LLD 0 C0-58 NA <LLD <LLD - 0 FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD - 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 CS-134 150 <LLD <LLD 0 CS-137 180 137 <LLD 137 Q-39 INDICATOR 0 (1/2) (1/2) CORDOVA- DOWNSTREAM MISSISSIPPI RIVER 0.8 MILES SSW OF SITE BA-140 NA <LLD <LLD - 0 LA-140 NA <LLD <LLD 0 AIR PARTICULATE GR-8 520 10 16.3 16 17.5 Q-38 INDICATOR 0 (PC/lrOTAL) (467/468) (52/52) (52/52) FULLER ROAD 4.9-33 7.5-30 7.1 - 33 4. 7 MILES E OF SITE (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2017 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50*265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD: 2017 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M) MEAN(M) MEAN(M) STATION# NONROUTINE (UNITOF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS AIR PARTICULATE GAMMA 40 (PCJ!TOTAL) MN-54 NA <LLD <LLD 0 C0-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD - 0 ZR-95 NA <LLD <LLD 0 CS-134 50 <LLD <LLD 0 CS-137 60 <LLD <LLD - 0 BA-140 NA <LLD <LLD 0

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

~

AIR IODINE GAMMA 520 (E-3 PCVCU.METER) 1-131 70 <LLD <LLD 0 MILK 1*131 (LOWLVL) 19 1 <LLD NA 0 (PCJ/LITER)

GAMMA 19 MN-54 NA <LLD NA 0 C0-58 NA <LLD NA 0 FE-59 NA <LLD NA 0 C0-60" NA <LLD NA 0 ZN-65 NA <LLD NA 0 NB-95 NA <LLD NA 0 ZR-95 NA <LLD NA 0 CS-134 15 <LLD NA 0 CS-137 18 <LLD NA 0 BA-140 60 <LLD NA 0 LA-140 15 <LLD NA 0 (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2017 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD: 2017 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M) MEAN(M) MEAN(M) STATION# NONROUTINE (UNITOF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS VEGETATION GAMMA 19 (PCl/KG WET) MN-54 NA <LLD <LLD - 0 C0-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 1-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0 CS-137 80 <LLD <LLD 0

)>

I BA-140 NA <LLD <LLD - 0

.i::. LA-140 NA <LLD <LLD - 0 DIRECT RADIATION OSLD-QUARTERLY 327 NA 21.5 23.5 25.3 Q-211-2 INDICATOR 0 (MILL/-ROENTGENIQTR.) (319/319) (8/8) (4/4) 11.6-27.9 22-24.6 23.3-27.9 4.5 MILES SW (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

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

Intentionally left blank TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2017 Location Location Description Distance & Direction From Site A. Surface Water Q-33 Cordova (indicator) 3.1 miles SSW Q-34 Camanche, Upstream (control) 4.4 miles NNE B. Ground/Well Water Q-35 McMillan Well (indicator) 1.5 milesS Q-36 Cordova Well (indicator) 3.3milesSSW C Milk - bi-weekly I monthly Q-26 Bill Stanley Dairy (indicator) 3.1 miles ESE D. Air Particulates I Air Iodine Q-01 Onsite 1 (indicator) 0.5miles N Q-02 Onsite 2 (indicator) 0.4 miles ENE Q-03 Onsite 3 (indicator) 0.6 miles S Q-04 Nitrin (indicator) 1.7 miles NE Q-13 Princeton (indicator) 4.7milesSW Q-16 Low Moor (indicator) 5.7miles NNW Q-37 Meredosia Road (indicator) 4.4 miles ENE Q-38 Fuller Road (indicator) 4.7 miles E Q-41 Camanche (indicator) 4.3miles NNE Q-42 Leclaire (control) 8.7milesSSW E. Fish Q-24 Pool #14 of Mississippi River, Downstream (indicator) 0.5 miles SW Q-29 Mississippi River, Upstream (control) 1.0 miles N F. Sediment Q-39 Cordova, Downstream on Mississippi River (indicator) 0.8milesSSW Q-40 North of Albany, Upstream on Mississippi River(control) 8.9 miles NE G. Food Products Quadrant 1 Ken DeBaille 2.3 miles ENE Quadrant 2 Dale Nimmic 3.0 miles ESE Quadrant 3 Amy Johnston 1.8 milesS Quadrant4 Mike Fawcett 4.5miles NW Control Charles Leavens 9.5 miles NE H. Environmental Dosimetrv- OSLO Inner Ring Q-101-1 0.6 miles N Q-101-2 0.9 miles N Q-102-1 1.3 miles NNE Q-102-3 1.4 miles NNE Q-103-1 and-2 1.2 miles NE B-1

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2017 Location Location Description Distance & Direction From Site H. Environmental Dosimetrv - OSLO (continued)

Inner Ring (continued)

Q-104-1 1.1 miles ENE Q-104-2 0.9 miles ENE Q-105-1 and -2 0.8 miles E Q-106-2 and -3 0.7 miles ESE Q-107-2 0.7 miles SE Q-107-3 0.8 miles SE Q-108-1 1.0 miles SSE Q-108-2 0.9 miles SSE Q-109-1 0.9 miles S Q-109-2 1.2 miles S Q-111-1 2.6milesSW Q-111-2 2.5milesSW Q-112-1 2.5milesWSW Q-112-2 2.2milesWSW Q-113-1 and -2 2.5 milesW Q-114-1 2.1 miles WNW Q-114-2 2.5milesWNW Q-115-1 2.6 miles NW Q-115-2 2.3 miles NW Q-116-1 2.3 miles NNW Q-116-3 2.4 miles NNW Outer Ring Q-201-1 and -2 4.2 miles N Q-202-1 4.4 miles NNE Q-202-2 4.8 miles NNE Q-203-1 4.7 miles NE Q-203-2 5.0 miles NE Q-204-1 4.7 miles ENE Q-204-2 4.5 miles ENE Q-205-1 4.7 miles E Q-205-4 4.8 miles E Q-206-1 and -2 4.8 miles ESE Q-207-1 and -4 4.7 miles SE Q-208-1 4.3 miles SSE Q-208-2 4.9 miles SSE Q-209-1 and -4 4.7 miles S Q-210-1 and -4

4.1 miles SSW Q-210-5 3.3milesSSW Q-211-1 and -2 4.5milesSW Q-212-1 5.4milesWSW Q-212-2 4.4 miles WSW Q-213-1 4.3 milesW Q-213-2 4.8 milesW Q-214-1 4.7 miles WNW Q-214-2 4.4 miles WNW Q-215-1 5.0 miles NW Q-215-2 4.2 miles NW Q-216-1 4.6 miles NNW Q-216-2 4.3 miles NNW B-2

TABLE 8-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2017 Location Location Description Distance & Direction From Site Q-01 Onsite 1 (indicator) 0.5 miles N Q-02 Onsite 2 (indicator) 0.4 miles ENE Q-03 Onsite 3 (indicator) 0.6 miles S Q-04 Nitrin (indicator) 1.7 miles NE Q-13 Princeton (indicator) 4.7 miles SW Q-16 Low Moor (indicator) 5.7miles NNW Q-37 Meredosia Road (indicator) 4.4 miles ENE Q-38 Fuller Road (indicator) 4.7 miles E Q-41 Camanche (indicator) 4.3 miles NNE Q-42 Leclaire 8.7 miles SSW

Removed from ODCM in December 2006 and replaced by Q-210-5. Q-210-4 is for trending only B-3

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2017 Sample Analysis Sampling Method Analytical Procedure Number Medium Gamma Monthly composite from TBE, TBE-2007 Gamma emitting radioisotope analysis Surface Water Spectroscopy weekly grab samples TBE, TBE-2008 Gross Alpha and/or gross beta activity in various Monthly composite from Surface Water Gross Beta matrices weekly grab samples Quarterly composite from TBE, TBE-2011 Tritium analysis in drinking water by liquid scintillation Surface Water Tritium weekly grab samples Quarterly composite from TBE, TBE-2006 lron-55 in various matrices Surface Water Iron and Nickel weekly grab samples TBE, TBE-2013 Radionickel in various matrices Gamma TBE, TBE-2007 Gamma emitting radioisotope analysis Ground Water Quarterly grab samples Spectroscopy Ground Water Tritium Quarterly grab samples TBE, TBE-2011 Tritium analysis in drinking water by liquid scintillation Semi-annual samples Gamma Fish collected via electroshocking TBE-2007 Gamma emitting radioisotope analysis Spectroscopy or other techniques Gamma TBE, TBE-2007 Gamma emitting radioisotope analysis Sediment Semi-annual grab samples Spectroscopy One-week composite of Air continuous air sampling TBE, TBE-2008 Gross Alpha and/or gross beta activity in various Gross Beta Particulates through glass fiber filter matrices paper Air Gamma Quarterly composite of each TBE, TBE-2007 Gamma emitting radioisotope analysis Particulates Spectroscopy station Weekly composite of Gamma Air Iodine continuous air sampling TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy through charcoal filter Bi-weekly grab sample when Milk 1-131 cows are on pasture. TBE, TBE-2012 Radioiodine in various matrices Monthly all other times Bi-weekly grab sample when Gamma Milk cows are on pasture. TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy Monthly all other times Food Gamma Annual grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis Products Spectroscopy Optically Quarterly OSLDs comprised Stimulated Landauer Incorporated OSLO of two Al203:C Landauer Luminescence Incorporated elements Dosimetry B-4

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Figure 8-1 Legend Quad Cities REMP Sampling Locations- 2 Mile Radius, 2017

APPENDIXC DATA TABLES AND FIGURES PRIMARY LABORATORY

Intentionally left blank Table C-1.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION PERIOD Q-33 Q-34 01120117 - 01126117 4.6 +/- 1.8 3.7 +/- 1.9 02116117 - 02124117 1.9 +/- 1.2 < 1.7 03103117 - 03131117 5.0 +/- 1.7 4.2 +/- 1.6 04106117 - 04127117 4.6 +/- 1.8 4.3 +/- 1.7 05104117 - 05125117 3.8 +/- 1.7 3.1 +/- 1.6 06102117 - 06129117 5.7 +/- 1.9 4.3 +/- 1.8 07107117 - 07127117 3.7 +/- 1.8 4.0 +/- 1.8 08103117 - 08131117 3.7 +/- 1.8 4.4 +/- 1.8 09107117 - 09128117 4.1 +/- 1.6 5.4 +/- 1.8 10105117 - 10126117 4.0 +/- 1.8 3.0 +/- 1.6 11102117 - 11130117 5.3 +/- 1.7 5.3 +/- 1.7 12108117 - 12122117 4.1 +/- 1.9 4.2 +/- 1.8 MEAN+/- 2 STD DEV 4.2 +/- 2.0 4.2 +/- 1.5 Table C-1.2 CONCENTRATIONS OF TRITIUM, IRON, AND NICKEL IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE PERIOD H-3 FE-55 Nl-63 Q-33 01120117 - 03131117 < 191 < 126 < 3.6 04106117 - 06129117 < 187 < 170 < 3.2 07107117 - 09128117 < 182 < 173 < 3.6 10105117 - 12/22117 < 185 < 117 < 4.6 MEAN Q-34 01120117 - 03131117 < 191 < 133 < 3.6 04106117 - 06129117 < 188 < 167 < 3.2 07107117 - 09128117 < 182 < 175 < 3.5 10105117 - 12/22117 < 180 < 78 < 4.7 MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-1

Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/LITER + 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Q-33 01/20/17 - 01/26/17 < 5 <5 < 12 <5 < 11 <6 < 9 < 14 <5 <6 <33 < 11 02/16/17 - 02/24/17 < 2 < 3 < 6 <3 < 5 <3 <5 < 10 <3 < 3 < 20 < 7 03/03/17 - 03/31/17 < 7 < 5 < 9 < 5 < 9 < 6 < 10 < 7 <6 <6 < 26 <6 04/06/17 - 04/27/17 < 5 <4 < 10 < 5 < 10 < 5 < 9 < 14 <4 < 5 < 27 < 11 05/04/17 - 05/25/17 < 2 < 3 <6 < 2 < 5 < 3 < 5 < 15 < 3 < 3 < 24 < 8 06/02/17 - 06/29/17 <6 < 5 < 10 < 5 < 11 < 5 < 9 < 15 <6 < 5 < 31 < 12 07/07/17 - 07/27/17 <6 < 5 < 11 < 8 < 11 <6 < 9 < 10 < 7 < 5 < 28 < 8 08/03/17 - 08/31/17 <2 < 2 <4 <2 <3 < 2 < 3 < 15 <2 <2 < 24 <6 09/07/17 - 09/28/17 < 3 < 3 < 8 <4 < 7 <4 <6 < 14 < 3 <4 < 29 < 9 10/05/17 - 10/26/17 < 2 <2 <6 <2 < 5 < 3 <4 < 12 <2 <2 < 23 <7 11/02/17 - 11/30/17 < 6 <7 < 10 <6 < 14 <8 < 12 < 12 < 8 <7 < 31 < 13 12/22/17 - 12/22/17 <2 < 2 < 6 < 3 < 5 < 3 <4 < 12 <3 <2 < 23 < 8 MEAN 0I I\)

Q-34 01/20/17 - 01/26/17 < 7 <6 < 14 < 5 < 13 < 7 < 11 < 14 < 6 < 7 < 32 < 12 02/16/17 - 02/24/17 < 2 < 3 <6 < 3 < 5 < 3 < 5 < 12 < 3 < 3 < 23 < 6 03/03/17 - 03/31/17 < 7 <6 < 18 <8 < 13 < 7 < 11 < 12 < 7 < 7 < 34 < 10 04/06/17 - 04/27/17 < 5 < 5 < 9 <6 <9 <5 <9 < 14 < 5 < 5 < 31 < 13 05/04/17 - 05/25/17 <2 <2 < 5 <2 <4 < 3 < 5 < 13 <2 < 2 < 23 < 7 06/02117 - 06/29/17 < 5 < 5 < 11 < 5 < 9 < 5 < 9 < 14 < 5 < 5 < 31 < 11 07/07/17 - 07/27/17 < 6 < 6 < 14 < 6 < 14 <7 < 11 < 10 < 6 <7 < 33 < 8 08/03/17 - 08/31/17 <2 <2 <4 <2 < 3 < 2 <4 < 15 < 2 < 2 < 22 < 8 09/07/17 - 09/28/17 < 3 < 3 < 7 < 3 < 5 < 3 < 5 < 12 < 3 < 3 < 21 < 8 10/05/17 - 10/26/17 < 2 < 2 < 5 <2 <4 <2 <4 < 11 <2 <2 < 20 <6 11/02/17 - 11/30/17 <4 < 5 < 10 < 6 < 9 < 6 < 11 < 8 <6 < 7 < 25 <7 12/08/17 - 12/22/17 <2 <2 < 6 <2 <4 < 3 <5 < 12 <2 <2 < 22 < 6 MEAN

Table C-11.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION PERIOD Q-35 Q-36 01/12/17 - 01/12117 < 186 < 179 04/13/17 - 04/13/17 < 189 < 192 07/14/17 - 07/14/17 < 189 < 187 10/12/17 - 10/12/17 < 179 < 178 MEAN C-3

Table C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/LITER + 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Q-35 01/12/17 - 01/12/17 < 5 < 5 < 12 < 6 < 9 < 6 < 10 < 10 <4 <6 < 30 < 10 04/13/17 - 04/13/17 <4 < 3 < 9 <4 < 7 <4 < 8 < 7 <4 < 3 < 20 < 5 07/14/17 - 07/14/17 < 5 <6 < 12 < 7 < 11 <6 < 12 < 10 < 6 < 6 < 27 < 7 10/12/17 - 10/12/17 <3 < 3 <6 < 3 <6 < 3 <6 <9 < 3 < 3 < 20 <6 MEAN Q-36 01/12/17 - 01/12/17 < 5 <8 < 15 <8 < 16 < 7 < 11 < 13 <6 <7 < 35 < 12 04/13/17 - 04/13/17 <6 < 5 < 11 <6 < 10 <6 < 11 < 8 < 6 < 6 < 22 < 9 07/14/17 - 07/14/17 < 7 <6 < 13 < 5 < 13 <7 < 11 < 10 < 8 < 7 < 25 < 9 10/12/17 - 10/12/17 < 1 <2 <4 < 1 < 3 < 2 < 3 < 15 < 1 < 1 < 20 <6 0I

~ MEAN

Table C-111.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PC/KG WET+ 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-24 Freshwater Drum 05/25/17 < 60 < 64 < 125 < 52 < 144 < 68 < 124 < 74 < 66 < 442 < 83 Quiffback 05/25/17 < 51 < 61 < 122 < 46 < 139 < 71 < 111 < 72 < 57 < 358 < 105 Freshwater Drum 10/26/17 < 52 < 59 < 145 < 62 < 131 < 62 < 109 < 63 < 63 < 300 < 83 Largemouth Bass 10/26/17 < 51 < 68 < 135 < 68 < 103 < 61 < 119 < 57 < 64 < 299 < 67 MEAN Q-29 Quillback 05/25/17 < 73 < 51 < 159 < 46 < 133 < 89 < 163 < 78 < 73 < 453 < 153 Shorthead Redhorse 05/25/17 < 66 < 68 < 130 < 60 < 134 < 75 < 129 < 80 < 64 < 462 < 88 C')

I Bigmouth Buffalo 10/26/17 < 34 < 37 < 83 < 47 < 75 < 41 < 55 < 42 < 36 < 171 < 65 C1I Largemouth Bass 10/26/17 < 73 < 65 < 130 < 50 < 168 < 76 < 116 < 73 < 75 < 377 < 144 MEAN

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PC/KG DRY+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-39 05/27/17 < 69 < 76 < 154 < 78 < 170 < 80 < 144 < 88 137 +/- 89 < 377 < 111 10/18/17 < 61 < 64 < 174 < 80 < 172 < 74 < 148 < 88 < 86 < 769 < 230 MEAN+/- 2 STD DEV 137 +/- 0 Q-40 05/27/17 < 70 < 77 < 165 < 67 < 135 < 71 < 132 < 88 < 89 < 391 < 103 10/18/17 < 57 < 46 < 127 < 59 < 108 < 60 < 78 < 74 < 66 < 277 < 91 MEAN 0I 0)

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA COLLECTION GROUP II GROUP Ill PERIOD Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 12/29/16 - 01/06/17 18 +/-4 22 +/-5 19 +/- 4 19 +/- 4 14 +/- 4 15 +/- 4 17 +/- 4 21 +/- 4 14 +/- 4 20 +/- 4 01/05/17 - 01/13/17 25 +/-5 16 +/-5 23 +/- 5 23 +/- 5 18 +/- 5 24 +/- 5 20 +/- 5 27 +/- 5 20 +/- 5 17 +/- 5 01/12/17 - 01/20/17 23 +/-4 11 +/-4 25 +/- 5 22 +/- 4 21 +/- 4 25 +/- 4 24 +/- 4 26 +/- 5 22 +/- 4 23 +/- 4 01/20/17 - 01/27/17 19 +/-4 18 +/-4 19 +/- 4 15 +/- 4 19 +/- 5 19 +/- 5 19 +/- 4 19 +/- 4 15 +/- 4 16 +/- 5 01/26/17 - 02/03/17 16 +/- 4 17 +/-4 13 +/- 4 13 +/- 4 21 +/- 4 16 +/- 4 15 +/- 4 13 +/- 4 17 +/- 4 16 +/- 4 02103/17 - 02/10/17 17 +/-4 20 +/-4 14 +/- 4 22 +/- 4 19 +/- 5 20 +/- 5 14 +/- 4 20 +/- 4 20 +/- 5 20 +/- 5 02109/17 - 02/17/17 16 +/- 4 17 +/-4 18 +/- 4 11+/-4 16+/-4 18 +/- 4 15 +/- 4 17 +/- 4 12 +/- 4 16 +/- 4 02116/17 - 02/24/17 16 +/-4 18 +/-4 20 +/- 4 20 +/- 4 18 +/- 4 17 +/- 4 16 +/- 4 18 +/- 4 16 +/- 3 18 +/- 4 02/24/17 - 03/03/17 16 +/- 4 18 +/-4 20 +/- 4 18 +/- 4 18 +/- 4 16 +/- 4 16 +/- 4 17 +/- 4 16 +/- 4 16 +/- 4 03/03/17 - 03/10/17 14 +/-4 14 +/-4 14 +/- 4 14 +/- 4 15 +/- 5 11+/-4 12+/-4 14+/-4 11 +/-4 12 +/-4 03/09/17 - 03/17/17 13 +/-4 14 +/-4 20 +/- 4 14 +/- 4 17 +/- 4 13 +/- 4 12 +/- 4 15 +/- 4 11 +/- 4 12 +/- 4 03/16/17 - 03/24/17 19 +/-4 18 +/-4 19 +/- 4 19 +/- 4 18 +/- 4 19 +/- 4 15 +/- 4 18 +/- 4 19 +/- 4 19 +/- 4 03/24/17 - 04/01/17 11 +/-3 9 +/- 3 12 +/- 3 10 +/- 3 10 +/- 3 8+/-3 9+/-3 12 +/- 3 10 +/- 3 13 +/- 4 03/31/17 - 04/07/17 9 +/-4 9 +/-4 11 +/- 4 11+/-4 12+/-4 11 +/- 4 9 +/-4 9 +/-4 10 +/- 4 10 +/- 4 04/06/17 - 04/14/17 19 +/-4 18 +/- 4 17 +/- 4 14 +/- 4 14 +/- 4 18 +/- 4 16 +/- 4 20 +/- 4 17 +/- 4 16 +/- 4 04/13/17 - 04/21/17 9 +/-3 6+/-3 8+/-3 11+/-4 10+/-3 11 +/- 4 9 +/-3 7 +/-3 13 +/- 4 17 +/- 4 04/21/17 - 04/28/17 11 +/-4 17 +/- 4 12 +/- 4 15+/-4 11+/-4 13+/-4 11+/-4 13 +/- 4 11 +/- 4 12 +/- 4 04/27/17 - 05/05/17 9 +/-3 11 +/- 4 12 +/- 4 13 +/- 4 12 +/- 4 10 +/- 3 8 +/-3 13+/-4 15 +/-4 11 +/-4 05/04/17 - 05/12/17 12 +/-3 13 +/- 4 14 +/- 4 20 +/- 4 19 +/- 4 18 +/- 4 16 +/- 4 16 +/- 4 19 +/- 4 16 +/- 4 05/11/17 - 05/19/17 17 +/-4 15 +/- 4 19 +/- 4 15 +/- 4 15 +/- 4 16 +/- 4 15 +/- 4 20 +/- 4 < 4 14 +/- 4 05/19/17 - 05/26/17 10 +/-4 11 +/- 4 13 +/- 4 10 +/- 4 10 +/- 4 7 +/-4 12 +/- 4 14 +/- 4 8 +/- 4 12 +/- 4 05/25/17 - 06/02117 15 +/-4 11 +/- 4 14 +/- 4 9 +/-4 13 +/- 4 16 +/- 4 12 +/- 4 16 +/- 4 16 +/- 4 12 +/- 3 06/02/17 - 06/09/17 16 +/-4 13 +/- 4 13 +/- 4 13 +/- 4 15 +/- 4 16 +/- 4 12 +/- 4 14 +/- 4 13 +/- 4 15 +/- 4 06/09/17 - 06/16/17 16 +/-4 12 +/- 4 13 +/- 4 12 +/- 4 16 +/- 5 17 +/- 5 12 +/- 4 17 +/- 4 12 +/- 4 14 +/- 4 06/15/17 - 06/23/17 14 +/-4 5+/-3 12 +/- 4 11+/-3 13+/-4 11+/-4 11+/-4 14 +/- 4 13 +/- 4 13 +/- 4 06/22/17 - 06/30/17 15 +/-4 15 +/- 4 13 +/- 4 12 +/- 4 14 +/- 4 14+/-4 11+/-4 12 +/- 4 10 +/- 4 12 +/- 4 06/29/17 - 07/07/17 19 +/-4 24 +/- 5 20 +/- 4 19 +/- 4 20 +/- 4 17 +/- 4 17 +/- 4 24 +/- 5 19 +/- 4 20 +/- 4 07/07/17 - 07/14/17 16 +/-4 13 +/- 4 16 +/- 4 14 +/- 4 16 +/- 5 18 +/- 5 12 +/- 4 18 +/- 4 13 +/- 4 12 +/- 4 07/13/17 - 07/22/17 7 +/-3 13 +/- 3 13 +/- 3 15 +/- 3 11 +/- 3 15 +/- 4 12 +/- 3 14 +/- 3 14 +/- 4 15 +/- 4 07/20/17 - 07/28/17 10 +/-3 8 +/-3 12 +/- 4 10 +/- 4 10 +/- 3 16 +/- 4 9 +/- 3 13 +/- 4 16 +/- 4 12 +/- 3 07/27/17 - 08/04/17 18 +/-4 11 +/- 4 12 +/- 4 14 +/- 4 16 +/- 4 16 +/- 4 14 +/- 4 17 +/- 4 15 +/- 4 11 +/- 4 08/03/17 - 08/11/17 18 +/- 4 19 +/- 4 18 +/- 4 17 +/- 4 19 +/- 4 19 +/- 4 15 +/- 4 16 +/- 4 17 +/- 3 12 +/- 3 08/11/17 - 08/18/17 10 +/- 4 16 +/- 4 16 +/- 4 17 +/- 4 17 +/- 4 16 +/- 4 13 +/- 4 14 +/- 4 13 +/- 4 16 +/- 4 08/17/17 - 08/25/17 21 +/-4 16 +/- 4 20 +/- 5 16 +/- 4 18 +/- 4 17 +/- 4 16 +/- 4 17 +/- 4 15 +/- 3 13 +/- 3 08/25/17 - 09/01/17 16 +/- 4 15 +/- 4 17 +/- 4 18 +/- 4 17 +/- 5 20 +/- 5 18 +/- 4 18 +/- 4 19 +/- 5 13 +/- 4 08/31/17 - 09/08/17 14 +/-4 17 +/- 4 15 +/- 4 18 +/- 4 18 +/- 4 17 +/- 4 14 +/- 4 15+/-4 13+/-4 11+/-4 09/07/17 - 09/15/17 19 +/-4 17 +/- 4 17 +/- 4 14 +/- 4 18 +/- 4 20 +/- 4 15 +/- 4 19 +/- 4 18 +/- 4 16 +/- 4 09/14/17 - 09/22117 25 +/-5 24 +/- 5 22 +/- 5 27 +/- 5 25 +/- 5 24+/-5 22+/-5 33 +/- 5 23 +/- 5 16 +/- 4 09/21/17 - 09/29/17 21 +/-4 21 +/- 5 21 +/- 4 22+/-5 20+/-4 21 +/- 4 18 +/- 4 24 +/- 5 23 +/- 5 19 +/- 4 09/28/17 - 10/06/17 18 +/-4 12 +/- 4 13 +/- 4 15 +/- 4 14 +/- 4 14 +/- 4 13 +/- 4 15 +/- 4 15 +/- 4 15 +/- 4 10/05/17 - 10/14/17 18 +/-4 17 +/- 4 19 +/- 4 19 +/- 4 21 +/- 5 21 +/- 5 13 +/- 4 21 +/- 4 22 +/- 5 16 +/- 4 10/12/17 - 10/21/18 24 +/-5 21 +/- 4 21 +/- 4 22 +/- 4 19 +/- 4 18 +/- 4 21 +/- 4 23 +/- 5 21 +/- 4 17 +/- 4 10/20/17 - 10/27/17 9 +/-4 11 +/- 4 11 +/- 4 8 +/-4 14 +/- 4 11+/-4 9+/-4 8 +/-4 17 +/- 5 16 +/- 4 10/26/17 - 11/04/17 11 +/-3 13 +/- 3 10 +/- 3 10 +/- 3 8 +/-3 6+/-3 9+/-3 9 +/-3 10 +/- 4 7 +/- 3 11/02/17 - 11/11/17 23 +/-5 22 +/- 4 19 +/- 4 26+/-5 23+/-4 25 +/- 4 24 +/- 5 26 +/- 5 21 +/- 4 30 +/- 5 11/10/17 - 11/18/17 18 +/-4 21 +/- 4 21 +/- 4 23 +/- 4 16 +/- 4 22 +/- 4 16 +/- 4 23 +/- 4 17 +/- 4 22 +/- 4 11/17/17 - 11/25/17 17 +/-4 17 +/- 4 24 +/- 5 22 +/- 4 27 +/- 5 24 +/- 5 19 +/- 4 21 +/- 4 23 +/- 4 29 +/- 5 11/24/17 - 12/01/17 21 +/-5 19 +/- 5 21 +/- 5 17 +/- 4 20 +/- 5 23 +/- 5 18 +/- 5 17 +/- 5 20 +/- 5 19 +/- 4 11/30/17 - 12/09/17 20 +/-4 17 +/- 4 22 +/- 4 22 +/- 4 21 +/- 4 23 +/- 4 21 +/- 4 20 +/- 4 24 +/- 4 20 +/- 4 12/08/17 - 12/15/17 20 +/-4 17 +/- 4 21 +/- 4 18 +/- 4 18 +/- 4 17 +/- 4 17 +/- 4 20 +/- 5 18 +/- 4 21 +/- 4 12/15/17 - 12/22/17 19 +/-4 24 +/- 4 27 +/- 5 22 +/- 4 23 +/- 4 25 +/- 5 20 +/- 4 25 +/- 5 23 +/- 4 21 +/- 4 12/22/17 - 12/29/17 18 +/-4 21 +/- 5 20 +/- 5 14 +/- 4 23 +/- 5 24 +/- 5 23 +/- 5 21 +/- 5 20 +/- 4 22 +/- 5 MEAN+/- 2STDDEV 16 +/- 9 16 +/- 9 17 +/- 9 16 +/- 9 17 +/- 8 17 +/- 10 15 +/- 8 18 +/- 10 16 +/- 8 16 +/- 9 THE MEAN AND TWO STANDARD DEV/AT/ON ARE CALCULATED USING THE POSITIVE VALUES C-7

TableC-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA GROUP I - NEAR-SITE LOCATIONS GROUP II - FAR-FIELD LOCATIONS GROUP Ill- CONTROL LOCATION COLLECTION MIN MAX MEAN COLLECTION MIN MAX MEAN COLLECTION MIN MAX MEAN PERIOD +/-2SD PERIOD +/-2SD PERIOD +/-2SD 12/30/16 - 02/03/17 11 25 19 +/- 8 12/30/16 - 02/03/17 13 27 20 +/- 7 12129/16 - 02103/17 16 23 18 +/- 6 02103/17 - 03/03/17 11 22 17 +/- 5 02/03/17 - 03/03/17 12 20 17 +/- 4 02103/17 - 03/03/17 16 20 17 +/- 4 03/03/17 - 04/01/17 9 20 14 +/- 7 03/03/17 - 04/01/17 8 19 13 +/- 7 03/03/17 - 03/31/17 12 19 14 +/- 7 04/01/17 - 04/28/17 6 19 12 +/- 8 03/31/17 - 04/28/17 7 20 12 +/- 7 03/31/17 - 04/27/17 10 17 14 +/- 7 04/28/17 - 06/02/17 9 20 13 +/- 6 04/27/17 - 06/02/17 7 20 14 +/- 7 04/27/17 - 06/02/17 11 16 13 +/- 4 06/02/17 - 06/30/17 5 16 13 +/- 5 06/02/17 - 06/30/17 10 17 13 +/- 4 06/02/17 - 06/29/17 12 15 13 +/- 3 06/30/17 - 08/04/17 7 24 14 +/- 9 06/29/17 - 08/04/17 9 24 15 +/- 7 06/29/17 - 08/03/17 11 20 14 +/- 7 08/04/17 - 09/01 /17 10 21 17 +/- 5 08/03/17 - 09/01/17 13 20 17 +/- 4 08/03/17 - 08/31/17 12 16 13 +/- 3 09101117 - 09/29/17 14 27 20 +/- 8 08/31/17 - 09/29/17 13 33 20 +/- 9 08/31/17 - 09/28/17 11 19 15 +/- 6 09/29/17 - 11/04/17 8 24 15 +/- 10 09/28/17 - 11/04/17 6 23 15 +/- 11 09/28/17 - 11/02/17 7 17 14 +/- 8 11/04/17 - 12/01/17 17 26 21 +/- 6 11/02/17 - 12101/17 16 27 21 +/- 7 11/02117 - 11/30/17 19 30 25 +/- 11 12/01/17 - 12129/17 14 27 20 +/- 6 11/30/17 - 12/29/17 14 15 21 +/- 5 11/30/17 - 12/29/17 20 21 21 +/- 1 0I co 12/30/16 - 12/29/17 5 27 16 +/- 9 12/29/16 - 12/29/17 6 33 16 +/- 9 12129/16 - 12/29/17 7 30 16 +/- 9

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-01 12130/16 - 04/01/17 <2 <2 <4 < 3 < 5 <2 < 3 <2 <2 < 19 <4 04/01 /17 - 06/30/17 <2 <2 < 5 <2 < 6 < 2 <5 <2 < 3 < 15 < 6 06/30/17 - 09/29/17 <2 <2 <6 <2 <7 < 3 < 5 <2 <2 < 39 < 20 09/29/17 - 12/29/17 <2 <2 < 5 < 3 < 6 < 3 <3 <2 <2 < 15 < 7 MEAN Q-02 12/30/16 - 04/01/17 <2 <2 < 6 < 2 < 5 < 2 <4 <2 <2 < 18 < 5 04/01/17 - 06/30/17 <3 <2 <4 <2 < 8 < 3 <4 < 3 <2 < 13 <7 06/30/17 - 09/29/17 <3 <2 < 6 < 3 < 7 < 3 <6 < 3 <2 < 54 < 23 09/29/17 - 12/29/17 <4 <4 < 10 <4 < 9 < 5 <6 <4 < 3 < 30 < 12 MEAN 0I co Q-03 12/30/16 - 04/01/17 <2 <2 < 5 <2 <4 <2 <3 <2 <2 < 15 <7 04/01/17 - 06/30/17 <3 < 3 < 5 < 3 < 7 <3 <5 < 3 < 3 < 15 < 5 06/30/17 - 09/29/17 <2 < 3 < 9 < 3 < 7 <4 <6 <3 < 3 < 55 < 18 09/29/17 - 12/29/17 <2 <2 < 5 <2 <4 <2 < 3 <2 <2 < 19 <8 MEAN Q-04 12/30/16 - 04/01/17 <2 <2 <4 < 3 <6 < 2 <4 <2 <2 < 17 <7 04/01/17 - 06/30/17 <2 <3 <6 < 3 < 5 < 2 <4 <2 <2 < 15 <7 06/30/17 - 09/29/17 <2 <2 < 7 < 3 <4 <2 < 5 <2 <2 < 44 < 22 09/29/17 - 12/29/17 < 3 < 3 < 7 < 3 < 5 < 3 <4 < 3 <2 < 17 < 7 MEAN Q-13 12/29/16 - 03/31/17 <2 <2 < 5 <2 < 7 <2 <5 <2 <2 < 16 <6 03/31 /17 - 06/29/17 <4 < 3 < 6 <4 < 9 <3 <8 <4 <4 < 24 < 11 06/29/17 - 09/28/17 <3 < 3 < 8 < 2 <6 < 3 < 5 <2 <2 < 45 < 12 09/28/17 - 12/29/17 < 3 <2 < 9 < 3 < 9 < 3 <6 <4 < 3 < 26 <7 MEAN

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-16 12/29/16 - 03/31/17 <2 < 3 < 6 < 3 <6 <3 <6 < 3 <3 < 23 <4 03/31/17 - 06/29/17 <3 < 3 <4 <2 < 6 <2 <4 < 3 <2 < 14 <6 06/29/17 - 09/28/17 <4 <4 < 13 <4 < 9 <4 < 8 <4 <3 < 60 < 32 09/28/17 - 12/29/17 < 3 <3 < 5 < 3 < 5 < 3 < 5 < 3 <2 < 21 <8 MEAN Q-37 12/30/16 - 04/01/17 < 3 < 3 < 7 < 3 < 6 <4 <7 <3 <3 < 22 < 8 04/01/17 - 06/30/17 <3 < 3 < 6 < 2 < 7 <3 <5 < 3 <3 < 20 <8 06/30/17 - 09/29/17 <2 <2 < 6 < 2 < 5 <2 < 5 <2 <2 < 43 < 12 09/29/17 - 12/29/17 <2 <2 < 5 < 2 < 5 <2 <4 <2 <2 < 15 <7 MEAN 0I

~

0 Q-38 12/30/16 - 04/01/17 <2 <2 <6 < 1 < 3 <2 <3 <2 < 1 < 13 <7 04/01/17 - 06/30/17 <2 <2 <4 <2 <4 <2 <3 <3 <2 < 11 <6 06/30/17 - 09/29/17 <2 < 3 < 10 < 3 < 6 <4 < 6 < 3 <2 < 39 < 27 09/29/17 - 12/29/17 <2 <2 < 5 <2 <6 <2 < 3 <2 <3 < 15 <4 MEAN Q-41 12/29/16 - 03/31/17 < 3 < 3 <6 < 3 < 7 < 3 <6 <2 < 3 < 24 < 7 03/31/17 - 06/29/17 < 3 < 3 < 7 < 3 < 8 < 2 <4 < 3 < 3 < 18 <6 06/29/17 - 09/28/17 <2 < 3 < 10 < 3 < 8 <4 <6 <3 < 3 < 55 < 18 09/28/17 - 12/29/17 <2 < 3 <7 < 3 < 6 < 3 <3 <2 <2 < 17 <4 MEAN Q-42 12/29/16 - 03/31/17 < 3 <3 < 7 <4 <6 <4 <6 < 3 < 3 < 23 <8 03/31/17 - 06/29/17 <2 <2 <4 < 3 <6 < 2 < 5 < 3 < 2 < 14 <6 06/29/17 - 09/28/17 <3 <4 <8 < 3 < 8 < 3 < 5 <3 <2 < 61 < 16 09/28/17 - 12/29/17 <2 < 3 <7 < 3 <4 <3 <4 <3 <2 < 18 <4 MEAN

TABLE C-Vl.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP Ill PERIOD Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 12/29/16 - 01/06/17 < 15 < 36 < 37 < 37 < 38 < 37 < 35 < 35 < 37 < 15 01/05/17 - 01/13/17 < 16 < 39 < 40 < 40 < 41 < 40 < 38 < 38 < 40 < 22 01/12/17 - 01/20/17 < 19 < 45 < 46 < 46 < 41 < 14 < 41 < 41 < 37 < 37 01/20/17 - 01/27/17 < 21 < 50 < 51 < 51 < 59 < 41 <35 <35 < 41 < 17 01/26/17 - 02/03/17 < 67 < 67 < 69 < 69 < 24 < 55 <64 <64 < 55 < 21 02/03/17 - 02/10/17 < 14 < 40 < 41 < 41 < 56 < 67 <22 <49 < 67 < 68 02109/17 - 02/17/17 < 20 < 56 < 58 < 58 < 57 < 23 < 51 < 51 < 52 < 51 02/16/17 - 02/24/17 < 22 < 53 < 54 < 54 < 47 < 54 < 24 < 62 < 54 < 55 02/24/17 - 03/03/17 < 21 < 50 < 52 < 52 < 49 < 45 < 47 < 47 < 18 < 46 03/03/17 - 03/10/17 < 43 < 18 < 44 < 44 < 61 < 24 < 49 < 49 < 62 < 61 03/09/17 - 03/17/17 < 19 < 35 < 35 < 36 < 38 < 24 <43 <43 < 45 < 46 03/16/17 - 03/24/17 < 17 < 40 < 40 < 42 < 36 < 34 < 38 < 38 < 34 < 12 03/24/17 - 04/01 /17 < 37 < 38 < 38 < 39 < 19 < 34 < 29 < 29 < 34 < 13 03/31/17 - 04/07/17 < 36 < 36 < 36 < 16 < 38 < 36 <34 <34 < 36 < 20 04/06/17 - 04/14/17 < 15 < 35 < 35 < 36 < 39 < 19 <30 <30 < 34 < 34 04/13/17 - 04/21/17 < 49 < 49 < 49 < 50 < 19 < 12 < 31 < 31 < 30 < 30 04/21/17 - 04/28/17 < 20 < 47 < 47 < 48 < 51 < 38 < 35 < 14 < 38 < 38 04/27/17 - 05/05/17 <30 <58 < 57 < 59 < 59 < 35 < 63 < 63 < 65 < 65 05/04/17 - 05/12/17 < 19 < 46 < 46 < 48 < 48 < 49 <46 <46 < 19 < 49 05/11/17 - 05/19/17 < 67 < 67 < 67 < 27 < 62 < 49 < 53 < 22 < 50 < 49 05/19/17 - 05/26/17 < 19 < 45 < 45 < 45 < 58 < 69 <54 <54 < 69 < 27 05/25/17 - 06/02/17 < 10 < 25 < 25 < 25 < 20 < 40 <50 <50 < 17 < 39 06/02/17 - 06/09/17 < 25 < 57 < 57 < 57 < 57 < 35 < 69 < 69 < 68 < 68 06/09/17 - 06/16/17 < 22 < 49 < 49 < 49 < 60 < 69 < 56 < 56 < 69 < 37 06/15/17 - 06/23/17 < 18 < 44 < 44 < 43 < 48 < 27 <45 <45 < 49 < 49 06/22/17 - 06/30/17 <52 <53 < 53 < 18 < 58 < 66 < 61 < 31 < 66 < 66 06/29/17 - 07/07/17 < 33 < 64 < 64 < 64 < 55 < 51 < 59 < 59 < 50 < 28 07/07/17 - 07/14/17 < 34 < 34 < 34 < 34 < 19 < 48 < 36 < 14 < 47 < 48 07/13/17 - 07/22/17 < 35 < 15 < 35 < 35 < 44 < 46 < 37 < 37 < 46 < 26 07/20/17 - 07/28/17 < 17 < 40 < 40 < 40 < 39 < 44 <46 <46 < 44 < 17 07/27/17 - 08/04/17 < 22 < 53 < 53 < 53 < 57 < 27 <46 <46 < 49 < 49 08/03/17 - 08/11 /17 < 28 < 55 < 55 < 55 < 48 < 25 < 53 < 53 < 46 < 46 08/11/17 - 08/18/17 < 22 < 52 < 52 < 52 < 62 < 27 < 41 < 40 < 49 < 48 08/17/17 - 08/25/17 < 18 < 50 < 59 < 50 < 44 < 21 < 53 < 55 < 46 < 47 08/25/17 - 09/01/17 <20 <48 < 48 < 24 < 60 < 60 <54 <56 < 67 < 67 08/31/17 - 09/08/17 <20 <49 < 48 < 48 < 52 < 35 < 39 < 40 < 42 < 42 09/07/17 - 09/15/17 < 53 < 53 < 22 < 53 < 58 < 22 < 57 < 59 < 63 < 63 09/14/17 - 09/22/17 < 26 < 61 < 61 < 61 < 64 < 39 < 46 < 47 < 47 < 48 09/21/17 - 09/29/17 < 19 < 45 < 45 < 45 < 46 < 42 < 41 < 42 < 35 < 42 09/28/17 - 10/06/17 < 22 < 51 < 51 < 51 < 57 < 58 < 18 < 54 < 58 < 58 10/05/17 - 10/14/17 < 17 < 41 < 41 < 41 < 57 < 25 <33 <34 < 46 < 46 10/12/17 - 10/21/18 < 16 < 39 < 39 < 39 < 35 < 33 < 36 < 37 < 27 < 33 10/20/17 - 10/27/17 < 23 < 54 < 54 < 54 < 61 < 40 <43 <45 < 48 < 48 10/26/17 - 11 /04/17 < 18 < 42 < 42 < 42 < 56 < 44 < 34 < 35 < 44 < 37 11/02/17 - 11/11/17 < 24 < 56 < 56 < 56 < 52 < 32 < 42 < 43 < 38 < 38 11/10/17 - 11/18/17 <43 <43 < 43 < 19 < 48 < 28 <48 <50 < 54 < 53 11/17/17 - 11/25/17 < 15 < 36 < 36 < 36 < 39 < 42 < 38 < 39 < 34 < 42 11/24/17 - 12/01/17 < 18 < 50 < 50 < 50 < 51 < 28 < 52 < 53 < 53 < 53 11/30/17 - 12/09/17 < 19 < 35 < 35 < 35 < 40 < 54 < 16 < 48 < 52 < 52 12/08/17 - 12/15/17 < 17 < 50 < 49 < 49 < 43 < 23 <58 <60 < 50 < 50 12/15/17 - 12/22/17 <60 <60 < 60 < 60 < 21 < 35 < 67 < 69 < 66 < 66 12/22/17 - 12/29/17 <27 <64 < 64 < 63 < 63 < 46 <46 <48 < 38 < 45 MEAN C-11

Table C-Vll.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION INDICATOR FARM PERIOD Q-26 01/06/17 < 0.7 02/03/17 < 0.4 03/03/17 < 0.7 04/07/17 < 0.8 05/05/17 < 0.5 05/19/17 < 0.8 06/02/17 < 0.5 06/16/17 < 0.9 06/30/17 < 0.8 07/14/17 < 0.5 07/28/17 < 0.7 08/11/17 < 0.7 08/25/17 < 0.8 09/08/17 < 0.8 09/22117 < 0.6 10/06/17 < 0.4 10/21/17 < 1.0 11/04/17 < 0.5 12/01/17 < 0.7 MEAN C-12

Table C-Vll.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-26 01/06/17 <7 <6 < 13 <6 < 13 < 6 < 12 <6 < 7 < 30 < 9 02/03/17 <6 <7 < 15 < 6 < 13 <6 < 12 < 5 < 6 < 49 < 15 03/03/17 < 10 < 12 < 21 < 13 < 26 < 11 < 15 < 11 < 9 < 37 < 14 04/07/17 < 10 < 11 < 23 < 10 < 26 < 11 < 20 < 11 < 12 < 54 < 12 05/05/17 <7 <8 < 16 <7 < 12 <9 < 14 < 9 <9 < 39 < 14 05/19/17 <8 <9 < 21 < 8 < 17 < 7 < 11 <8 < 8 < 36 < 10 06/02117 < 7 < 8 < 21 < 9 < 21 < 10 < 16 < 10 < 10 < 40 < 14 06/16/17 < 8 < 9 < 18 < 8 < 21 < 9 < 16 < 9 < 9 < 50 < 14 06/30/17 < 6 < 8 < 11 < 7 < 15 <8 < 11 < 8 <6 < 34 < 12 07/14/17 < 6 <6 < 13 < 7 < 19 <6 < 10 < 8 < 7 < 28 <7 07/28/17 < 8 < 8 < 18 < 10 < 21 < 8 < 13 < 10 < 8 < 36 < 12 08/11/17 < 10 <9 < 21 < 10 < 20 < 9 < 15 < 10 < 9 < 42 < 12

(")

I (A) 08/25/17 <7 <8 < 19 <7 < 19 <8 < 14 < 8 < 8 < 46 < 13 09/08/17 <4 <4 < 9 < 5 < 8 <4 < 7 < 5 <4 < 24 < 7 09/22/17 < 7 < 8 < 14 <8 < 19 <8 < 12 < 7 < 9 < 32 < 12 10/06/17 <7 < 7 < 17 <7 < 16 <8 < 12 < 8 <8 < 35 < 9 10/21/17 <6 <9 < 17 <9 < 18 < 8 < 11 < 7 <8 < 31 <9 11/04/17 < 9 < 9 < 19 < 9 < 20 < 9 < 16 < 10 < 11 < 41 <9 12/01/17 < 9 < 9 < 20 < 10 < 21 < 9 < 17 <9 < 9 < 43 < 10 MEAN

Table C-Vlll.1 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Q-CONTROL Beets 07/25/17 < 43 < 47 < 94 < 52 < 105 < 48 < 78 < 51 < 50 < 47 < 172 < 48 Onion 07/25/17 < 21 < 22 < 42 < 16 < 50 < 18 < 46 < 33 < 22 < 29 < 96 < 27 Potatoes 07/25/17 < 19 < 20 < 46 < 23 < 51 < 19 < 33 < 24 < 25 < 21 < 73 < 23 Lettuce 07/27/17 < 34 < 32 < 79 < 31 < 84 < 33 < 59 < 58 < 46 < 47 < 185 < 59 MEAN Q-QUAD 1 Cabbage 07/25/17 < 37 < 30 < 52 < 36 < 62 < 37 < 56 < 40 < 31 < 41 < 137 < 33 Eggplant 07/25/17 < 29 < 36 < 74 < 42 < 83 < 36 < 51 < 49 < 45 < 38 < 149 < 47 Onions 07/25/17 < 29 < 36 < 62 < 33 < 81 < 32 < 59 < 41 < 35 < 35 < 131 < 37 MEAN 0I Q-QUAD 2

...lo.

~ Cabbage 07/25/17 < 23 < 24 < 52 < 30 < 39 < 22 < 32 < 26 < 22 < 23 < 80 < 28 Lettuce 07/25/17 < 48 < 47 < 103 < 46 < 97 < 50 < 79 < 57 < 50 < 54 < 180 < 60 Onions 07/25/17 < 39 < 32 < 77 < 45 < 77 < 42 < 45 < 46 < 41 < 47 < 129 < 37 Zucchini 07/25/17 < 22 < 20 < 37 < 22 < 38 < 21 < 34 < 28 < 26 < 26 < 95 < 24 MEAN Q-QUAD 3 Cilantro 07/25/17 < 42 < 37 < 70 < 36 < 102 < 43 < 73 < 48 < 47 < 50 < 149 < 38 Horseradish 07/25/17 < 23 < 24 < 57 < 27 < 60 < 24 < 45 < 31 < 25 < 28 < 93 < 26 Lettuce 07/25/17 < 44 < 42 < 78 < 49 < 108 < 42 < 69 < 49 < 44 < 44 < 166 < 49 Rutabaga 07/25/17 < 27 < 23 < 55 < 22 < 61 < 18 < 50 < 35 < 31 < 30 < 104 < 28 MEAN Q-QUAD4 Beets 07/25/17 < 19 < 19 < 43 < 21 < 51 < 19 < 33 < 24 < 22 < 22 < 80 < 24 Lettuce 07/25/17 < 31 < 34 < 74 < 27 < 67 < 34 < 51 < 40 < 33 < 35 < 136 < 31 Potatoes 07/25/17 < 29 < 27 < 68 < 24 < 72 < 29 < 50 < 30 < 33 < 27 < 87 < 27 Rhubarb leaves 07/25/17 < 34 < 35 < 85 < 39 < 82 < 42 < 83 < 42 < 49 < 38 < 141 < 31 MEAN

Table C-IX.1 QUARTERLY OSLO RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN CODE +/-2S.D. JAN-MAR APR-JUN JUL-SEP OCT- DEC Q-01-1 20.1 +/- 2.2 19.4 19.0 21.4 20.4 Q-01-2 21.4 +/- 2.0 20.0 21.7 21.7 22.3 Q-02-1 20.9 +/- 2.8 20.3 20.0 23.0 20.2 Q-02-2 20.9 +/- 3.6 20.1 18.8 21.7 22.9 Q-03-1 19.4 +/- 2.5 18.8 20.6 20.2 17.9 Q-03-2 19.1 +/- 1.9 18.7 18.1 20.4 19.0 Q-04-1 21.1 +/- 0.6 20.8 21.0 21.4 (1)

Q-04-2 21.2 +/- 2.0 21.3 22.2 20.2 (1)

Q-13-1 21.7 +/- 3.8 20.8 23.5 23.1 19.5 Q-13-2 22.8 +/- 2.6 23.8 21.2 23.8 22.2 Q-16-1 20.7 +/- 3.2 20.6 18.5 21.6 22.1 Q-16-2 19.0 +/- 2.3 19.2 17.4 20.1 19.4 Q-37-1 22.4 +/- 1.6 23.6 21.8 22.2 22.1 Q-37-2 23.2 +/- 5.1 22.5 22.0 27.0 21.4 Q-38-1 23.9 +/- 1.4 24.3 23.8 24.4 22.9 Q-38-2 23.5 +/- 1.3 23.2 23.5 24.3 22.8 Q-41-1 22.2 +/- 1.4 21.7 22.3 23.1 21.6 Q-41-2 22.7 +/- 3.0 23.2 20.9 24.4 22.2 Q-42-1 23.7 +/- 1.0 23.5 23.7 24.4 23.3 Q-42-2 23.3 +/- 2.2 24.6 22.8 23.6 22.0 Q-101-1 20.6 +/- 1.2 20.5 19.7 21.0 21.0 Q-101-2 22.4 +/- 3.9 22.2 20.7 25.2 21.5 Q-102-1 21.6 +/- 1.7 20.9 21.2 22.8 21.3 Q-102-3 21.5 +/- 2.3 21.7 20.8 23.1 20.5 Q-103-1 20.0 +/- 2.8 19.7 20.1 21.7 18.3 Q-103-2 19.6 +/- 1.1 19.3 19.2 19.5 20.4 Q-104-1 17.5 +/- 8.4 19.9 17.6 21.0 11.6 Q-104-2 21.1 +/- 2.3 20.7 20.7 22.8 20.3 Q-105-1 20.1 +/- 1.7 20.9 19.8 20.6 19.0 Q-105-2 20.9 +/- 2.7 21.0 20.0 22.7 19.8 Q-106-2 20.1 +/- 2.9 20.1 19.9 21.9 18.4 Q-106-3 20.2 +/- 4.0 17.4 20.0 21.5 21.7 Q-107-2 20.0 +/- 2.7 20.4 19.1 21.7 18.8 Q-107-3 20.3 +/- 3.8 17.9 20.1 22.5 20.8 Q-108-1 21.5 +/- 3.5 21.2 20.8 24.0 19.9 Q-108-2 20.1 +/- 3.4 19.3 18.8 22.6 19.6 Q-109-1 21.4 +/- 2.7 20.7 20.5 23.4 20.8 Q-109-2 21.3 +/- 1.6 22.3 20.7 20.6 21.5 Q-111-1 21.1 +/- 3.7 22.7 18.5 22.2 21.0 Q-111-2 21.0 +/- 3.2 19.3 19.9 22.7 21.9 Q-112-1 20.3 +/- 3.0 21.0 19.5 22.1 18.7 Q-112-2 20.2 +/- 2.4 18.5 20.2 21.1 20.9 Q-113-1 19.9 +/- 1.3 20.1 19.9 20.5 19.0 Q-113-2 19.4 +/- 4.4 19.8 16.5 21.9 19.5 Q-114-1 20.0 +/- 3.3 18.5 18.9 22.1 20.3 Q-114-2 21.7 +/- 1.0 21.3 21.2 21.9 22.3 Q-115-1 20.3 +/- 1.9 20.3 19.4 (1) 21.3 Q-115-2 19.4 +/- 1.5 19.4 18.6 20.4 19.1 Q-116-1 22.4 +/- 2.1 22.4 23.0 23.2 20.9 Q-116-3 21.2 +/- 3.3 20.1 20.7 23.6 20.3 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-15

Table C-IX.1 QUARTERLY OSLO RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF MILLI REM/QUARTER+/- 2 STANDARD DEVIATIONS STATION MEAN CODE +/-2 S.D. JAN-MAR APR-JUN JUL-SEP OCT-DEC Q-201-1 21.3 +/- 1.6 20.3 21.1 22.3 21.3 Q-201-2 21.7 +/- 1.3 22.3 21.8 (1) 21.0 Q-202-1 19.5 +/- 1.5 18.7 19.2 20.5 19.7 Q-202-2 22.7 +/- 2.7 21.7 21.3 24.1 23.5 Q-203-1 23.0 +/- 3.1 22.3 21.9 22.6 25.3 Q-203-2 25.1 +/- 1.5 25.1 25.4 25.7 24.0 Q-204-1 23.6 +/- 2.4 22.8 22.3 24.8 24.3 Q-204-2 24.5 +/- 3.5 23.8 27.0 22.9 24.3 Q-205-1 22.1 +/- 3.1 20.7 21.1 24.2 22.3 Q-205-4 24.0 +/- 2.0 23.6 23.0 25.4 23.8 Q-206-1 21.6 +/- 3.6 22.2 19.1 23.3 21.8 Q-206-2 20.4 +/- 2.2 19.3 20.2 20.3 21.9 Q-207-1 21.3 +/- 3.4 20.5 19.7 23.6 21.4 Q-207-4 23.0 +/- 3.5 21.5 21.7 25.2 23.6 Q-208-1 21.6 +/- 2.2 21.4 20.7 23.2 21.2 Q-208-2 23.5 +/- 2.6 23.1 22.2 25.3 23.3 Q-209-1 23.0 +/- 5.2 20.1 21.6 25.8 24.5 Q-209-4 21.8 +/- 2.2 21.1 22.1 23.1 20.7 Q-210-1 24.0 +/- 3.4 25.1 21.7 25.4 23.8 Q-210-4 23.7 +/- 3.8 21.8 23.9 26.2 22.8 Q-210-5 19.1 +/- 0.6 19.0 19.5 18.9 18.8 Q-211-1 24.7 +/- 2.5 24.6 23.8 26.4 23.8 Q-211-2 25.3 +/- 4.3 26.2 23.7 27.9 23.3 Q-212-1 21.8 +/- 3.4 22.3 21.4 23.8 19.7 Q-212-2 19.5 +/- 2.0 20.4 19.2 20.1 18.2 Q-213-1 21.2 +/- 3.2 20.2 21.2 23.4 19.9 Q-213-2 20.3 +/- 3.2 20.9 18.3 22.1 19.8 Q-214-1 21.8 +/- 2.1 21.8 20.8 23.2 21.2 Q-214-2 22.6 +/- 4.1 22.8 21.6 25.4 20.7 Q-215-1 21.9 +/- 4.4 19.6 (1) 24.0 22.2 Q-215-2 23.2 +/- 2.6 23.8 21.4 24.4 23.3 Q-216-1 24.3 +/- 3.5 24.2 22.8 26.8 23.5 Q-216-2 22.9 +/- 2.2 24.0 22.4 23.6 21.6 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16

TABLE C-IX.2 MEAN QUARTERLY OSLO RESULTS FOR THE INNER RING, OUTER RING, OTHER AND CONTROL LOCATION FOR QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATION OF THE STATION DATA COLLECTION INNER RING PERIOD +/- 2 S.D. OUTER RING OTHER CONTROL JAN-MAR 20.3 +/- 2.6 22.0 +/- 3.8 21.2 +/- 3.6 24.1 +/- 1.6 APR-JUN 19.9 +/- 2.4 21.7 +/- 3.7 20.9 +/- 3.9 23.3 +/- 1.3 JUL-SEP 22.1 +/- 2.5 23.9 +/- 4.1 22.4 +/- 3.7 24.0 +/- 1.1 OCT-DEC 20.0 +/- 3.9 22.1 +/- 3.6 21.2 +/- 3.1 22.7 +/- 1.8 TABLE C-IX.3

SUMMARY

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

INNER RING 119 11.6 25.2 20.6 +/- 3.4 OUTER RING 130 18.2 27.9 22.4 +/- 4.1 OTHER 70 17.4 27.0 21.5 +/- 3.7 CONTROL 8 22.0 24.6 23.5 +/- 1.7 INNER RING STATIONS- Q-101-1, Q-101-2, Q-102-1, Q-102-3, Q-103-1, Q-103-2, Q-104-1, Q-104-2 Q-105-1, Q-105-2, Q-106-2, Q-106-3, Q-107-2, Q-107-3, Q-108-1, Q-108-2, Q-109-1, Q-109-2, Q-111-1, Q-111-2, Q-112-1, Q-112-2, Q-113-1, Q-113-2, Q-114-1, Q-114-2, Q-115-1, Q-115-2, Q-116-1, Q-116-3 OUTER RING STATIONS - Q-201-1, Q-201-2, Q-202-1, Q-202-2, Q-203-1, Q-203-2, Q-204-1, Q-204-2, Q-205-1, Q-205-4, Q-206-1, Q-206-2, Q-207-1, Q-207-4, Q-208-1, Q-208-2, Q-209-1, Q-209-4, Q-210-1, Q-210-5, Q-211-1, Q-211-2, Q-212-1, Q-212-2, Q-213-1, Q-213-2, Q-214-1, Q-214-2, Q-215-1, Q-215-2, Q-216-1, Q-216-2, OTHER STATIONS- Q-01-1, Q-01-2, Q-02-1, Q-02-2, Q-03-1, Q-03-2, Q-04-1, Q-04-2, Q-13-1, Q-13-2, Q-16-1, Q-16-2, Q-37-1, Q-37-2, Q-38-1, Q-38-2, Q-41-1, Q-41-2 CONTROL STATIONS - Q-42-1, Q-42-2 C-17

FIGURE C-1 Surface Water - Gross Beta - Stations Q-33 and Q-34 (C)

Collected in the Vicinity of QCNPS, 2000 - 2017 Q-33 Cordova 12.0 10.0 8.0 0 6.0 Q,

4.0 2.0 0.0 ----

01-01-00 - - 15-07 08-08-03 - - - 20-10

- - - 27-14

- - - 01-18 Q-34 (C) Camanche 12.0 10.0 8.0

...J

~ 6.0 Q,

4.0 2.0 0.0 ----------------------!

01-01-00 08-08-03 03-15-07 10-20-10 05-27-14 01-01-18 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-18

FIGURE C-2 Surface Water -Tritium - Stations Q-33 and Q-34 (C)

Collected in the Vicinity of QCNPS, 2000 - 2017 Q-33 Cordova 500 400 300 s0 Q.

200 100 OT-~~..- ..........~~~....-~~~.--~~~..--~~---.

01-01-00 08-08-03 03-15-07 10-20-10 05-27-14 01-01-18 Q-34 (C) Camanche 500 400 300

...I 5Q.

200 100 0

01-01-00 08-08-03 03-15-07 10-20-10 05-27-14 01-01-18 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-19

FIGURE C-3 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2017 Q-35 McMillan Well 500 400 300

..J

~CL 200 100 0

12-31-99 08-07-03 03-14-07 10-19-10 05-26-14 12-31-17 Q-36 Cordova Well 500 400 300

..J

~CL 200 100 0

12-31-99 08-07-03 03-14-07 10-19-10 05-26-14 12-31-17 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-20

FIGURE C-4 Air Particulates - Gross Beta- Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2017 Q-01 Onsite No. 1 70.0 60.0 50.0 M

§ 0 40.0 a.

q 30.0 w

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

01-01-00 07-01-04 01-01-09 07-01-13 01-01-18 Q-02 Onsite No. 2 70.0 60.0 50.0 M

E tia. 40.0 M

9 30.0 w

C)

...... 20.0 10.0 0.0 01-01-00 07-01-04 01-01-09 07-01-13 01-01-18 C-21

FIGURE C-5 Air Particulates - Gross Beta- Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2017 Q-03 Onsite No. 3 60.0 50.0

'E 4o.o

~

..,c.. 30.0 c;>

l!:I 20.0 10.0 0.0 - - - 01-04 01-01-00 ----- ----

01-01-09 - - - 01-18 07-01-13 -

Q-04 Nitrin 60.0 50.0

.., 40.0

~

..,'5. 30.0 c;>

w 20.0 Cl 10.0 0.0 _ _ _ __..,.._ _ _ _ _ _ _ _ _ _ _ ___

01-01-00 07-01-04 01-01-09 07-01-13 01-01-18 C-22

FIGURE C-6 Air Particulates - Gross Beta- Station Q-07 (C)

Collected in the Vicinity of QCNPS, 2000 - 201 O Q-07 (C) Clinton 70.0 60.0 50.0 M

§ 40.0 0

a.

M 0 30.0 uJ 0

20.0 10.0 0.0 01-07-00 01-26-02 02-15-04 03-06-06 03-25-08 04-14-10 This location was removed from the program in January 2011 due to updated annual average meteorology.

This data is retained in the report for historical comparision.

C-23

FIGURE C-7 Air Particulates - Gross Beta- Stations Q-13 and Q-16 Collected in the Vicinity of QCNPS, 2005 - 2017 Q-13 Princeton 60.0 50.0 C") 40.0

§ 0

Q. 30.0 C")

9

~ 20.0 10.0 0.0 + - - - - - - - - + - - - - - - l - - - + - - - - - - - -

07-01-05 08-01-07 09-01-09 10-01-11 11-01-13 12-01-15 01-01-18 Q-16 Low Moor 60.0 50.0 40.0 30.0 20.0 10.0 0.0 +----1------+------lf----+----1----+

07-01-05 08-01-07 09-01-09 10-01-11 11-01-13 12-01-15 01-01-18 AIR PART/GULA TE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 C-24

FIGURE C-8 Air Particulates - Gross Beta- Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2017 Q-37 Meredosia Road 60.0 50.0 C') 40.0

§ ca.

C')

30.0

'i'

...~ 20.0 10.0 0.0 + - - - - + - - - - + - - - - - + - - - + - - - - - + - - - - +

07-01-05 08-01-07 09-01-09 10-01-11 11-01-13 12-01-15 01-01-18 Q-38 Fuller Road 60.0 50.0 C') 40.0

.§ 0

Q, 30.0 C')

'i'

...~ 20.0 10.0 0.0 -------------4-----------

07-01-05 08-01-07 09-01-09 10-01-11 11-01-13 12-01-15 01-01-18 AIR PART/GULA TE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED JN JULY 2005 C-25

FIGURE C-9 Air Particulates - Gross Beta- Station Q-41 Collected in the Vicinity of QCNPS, 2009 - 2017 Q-41 Camanche 60.0 50.0 C") 40.0

.§ 0

a. 30.0 C")

q

...~ 20.0 10.0 0.0 +------------------+

01-01-09 04-01-11 07-01-13 10-01-15 01-01-18 Air Particulates - Gross Beta- Station Q-42 (C)

Collected in the Vicinity of QCNPS, 201 O - 2017 Q-42 LeClaire (Control) 60.0 50.0 C") 40.0

.§ 0

a. 30.0 C")

0

...w 20.0 0

10.0 0.0 + - - - - - + - - - - - t - - - - + - - - - - + - - - - - 1 12-31-10 05-26-12 10-20-13 03-16-15 08-09-16 01-03-18 C-26

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM

Intentionally left blank TABLE D.1 Analytics Environmental Radioactivity Cross Check Program Teled~ne Brown Ensineerins Environmental Services TBE Identification Known Ratio of TBE to MonthNear Matrix Nuclide Units Reported Evaluation (b)

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

A =Acceptable - reported result falls within ratio limits of 0.80-1.20 W =Acceptable with warning- reported result falls within 0. 70-0.80 or 1.20-1.30 N =Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and> 1.30 (Page 1 of 4)

D-1

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

A= Acceptable - reported result falls within ratio limits of 0.80-1.20 W= Acceptable with warning-reported result falls within 0.70-0.80or1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and > 1. 30 (Page 2 of 4)

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TABLE D.1 Analytics Environmental Radioactivity Cross Check Program Teled~ne Brown Ensineerin!il Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Analytics Result Value September 2017 E11914 Milk Sr-89 pCi/L 84.3 82.7 1.02 A Sr-90 pCi/L 12.6 12.1 1.04 A E11915 Milk Ce-141 pCi/L 93.9 87.0 1.08 A Co-58 pCi/L 115 117 0.98 A Co-60 pCi/L 265 262 1.01 A Cr-51 pCi/L 273 217 1.26 w Cs-134 pCi/L 186 201 0.93 A Cs-137 pCi/L 175 172 1.02 A Fe-59 pCi/L 137 125 1.09 A 1-131 pCi/L 78.0 71.0 1.10 A Mn-54 pCi/L 128 123 1.04 A Zn-65 pCi/L 206 184 1.12 A E11916 Charcoal 1-131 pCi 71.9 64.4 1.12 A E11917 AP Ce-141 pCi 80.1 86.3 0.93 A Co-58 pCi 110 116 0.95 A Co-60 pCi 277 260 1.07 A Cr-51 pCi 275 215 1.28 w Cs-134 pCi 192 199 0.96 A Cs-137 pCi 165 170 0.97 A Fe-59 pCi 122 124 0.98 A Mn-54 pCi 120 122 0.99 A Zn-65 pCi 175 183 0.96 A E11918 Water Fe-55 pCi/L 1630 1630 1.00 A E11919 Soil Ce-141 pCi/g 0.136 0.142 0.96 A Co-58 pCi/g 0.179 0.191 0.94 A Co-60 pCi/g 0.405 0.429 0.94 A Cr-51 pCi/g 0.230 0.355 0.65 N(1)

Cs-134 pCi/g 0.272 0.328 0.83 A Cs-137 pCi/g 0.336 0.356 0.94 A Fe-59 pCi/g 0.210 0.205 1.02 A Mn-54 pCi/g 0.210 0.201 1.05 A Zn-65 pCi/g 0.301 0.301 1.00 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A= Acceptable - reported result falls within ratio limits of 0.80-1.20 W =Acceptable with warning- reported result falls within 0. 70-0.80 or 1.20-1.30

=

N Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and > 1.30 (1) See NCR 17-16 (Page 3 of 4)

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

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

A = Acceptable - reported result falls within ratio limits of 0. 80-1. 20 W = Acceptable with warning - reported result falls within O. 70-0. 80 or 1. 20-1. 30 N = Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and > 1.30 (Page4 of4)

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

Teled~ne Brown Ensineerins Environmental Services TBE Identification Known Acceptance MonthNear Matrix Nuclide Units Reported Evaluation (bl Number Value (a) Range Value February 2017 17-MaS36 Soil Ni-63 Sq/kg -5.512 (1) A Sr-90 Sq/kg 571 624 437-811 A 17-MaW36 Water Am-241 Sq/L 0.693 0.846 0.592 - 1.100 A Ni-63 Sq/L 13.4 12.2 8.5 - 15.9 A Pu-238 Sq/L 0.7217 0.703 0.492 - 0.914 A Pu-239/240 Sq/L 0.9277 0.934 0.654 - 1.214 A 17-RdF36 AP U-234/233 Sq/sample 0.0911 0.104 0.073-0.135 A U-238 Sq/sample 0.0967 0.107 0.075 - 0.139 A 17-RdV36 Vegetation Cs-134 Sq/sample 6.44 6.95 4.87 - 9.04 A Cs-137 Sq/sample 4.61 4.60 3.22- 5.98 A Co-57 Sq/sample -0.0229 (1) A Co-60 Sq/sample 8.52 8.75 6.13 - 11.38 A Mn-54 Sq/sample 3.30 3.28 2.30-4.26 A Sr-90 Sq/sample 1.30 1.75 1.23 -2.28 w Zn-65 Sq/sample 5.45 5.39 3.77 - 7.01 A August 2017 17-MaS37 Soil Ni-63 Sq/kg 1130 1220 854 - 1586 A Sr-90 Sq/kg 296 289 202-376 A 17-MaW37 Water Am-241 Sq/L 0.838 0.892 0.624 - 1.160 A Ni-63 Sq/L -0.096 (1) A Pu-238 Sq/L 0.572 0.603 0.422 - 0. 784 A Pu-239/240 Sq/L 0.863 0.781 0.547 - 1.015 A 17-RdF37 AP U-234/233 Sq/sample 0.103 0.084 0.059-0.109 w U-238 Sq/sample 0.115 0.087 0.061 - 0.113 N (2l 17-RdV37 Vegetation Cs-134 Sq/sample 2.34 2.32 1.62 - 3.02 A Cs-137 Sq/sample 0.05 (1) A Co-57 Sq/sample 3.32 2.8 2.0 - 3.6 A Co-60 Sq/sample 2.09 2.07 1.45 - 2.69 A Mn-54 Sq/sample 2.90 2.62 1.83- 3.41 A Sr-90 Sq/sample 1.17 1.23 0.86 -1.60 A Zn-65 Sq/sample 6.07 5.37 3.76-6.98 A (a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) DOEIMAPEP evaluation:

A =Acceptable - reported result falls within ratio limits of 0.80-1.20 W =Acceptable with warning - reported result falls within 0. 70-0.80or1.20-1.30 N =Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and> 1.30 (1) False positive test (2) See NCR 17-15 (Page 1 of 1)

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TABLE D.3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services TBE ldentrification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation Cb)

Number Value<a> Limits Value March 2017 MRAD-26 AP GR-A pCi/sample 76.3 85.5 28.6 - 133 A April 2017 RAD-109 Water Ba-133 pCi/L 49.2 49.7 40.8- 55.1 A Cs-134 pCi/L 83.2 90.1 74.0- 99.1 A Cs-137 pCi/L 202 206 185 - 228 A Co-60 pCi/L 51.2 54.7 49.2 - 62.7 A Zn-65 pCi/L 39.3 53.8 47.2- 65.9 Nc1>

GR-A pCi/L 53.6 75.0 39.5- 92.3 A GR-B pCi/L 42.7 38.5 25.5-46.0 A U-Nat pCi/L 50.1 55.6 45.2 - 61.7 A H-3 pCi/L 7080 6850 5920- 7540 A Sr-89 pCi/L 40.7 66.2 53.8 - 74.3 Nc1>

Sr-90 pCi/L 26.9 26.7 19.3-31.1 A 1-131 pCi/L 26.7 29.9 24.9-34.9 A September 2017 MRAD-27 AP GR-A pCi/sample 40.9 50.1 16.8- 77.8 A AP GR-B pCi/sample 58.0 61.8 39.1 - 90.1 A October 2017 RAD-111 Water Ba-133 pCi/L 71.3 73.7 61.7-81.1 A Cs-134 pCi/L 43.0 53.0 42.8 -58.3 A Cs-137 pCi/L 48.2 52.9 47.6-61.1 A Co-60 pCi/L 69.0 69.5 62.6- 78.9 A Zn-65 pCi/L 335 348 313 - 406 A GR-A pCi/L 32.5 35.6 18.3-45.8 A GR-B pCi/L 24.3 25.6 16.0 - 33.6 A U-Nat pCi/L 36.6 37.0 30.0-40.9 A H-3 pCi/L 6270 6250 5390- 6880 A 1-131 pCi/L 26.4 24.2 20.1 - 28.7 A November 2017 1113170 Water Sr-89 pCi/L 57.1 50.0 39.4 - 57.5 A Sr-90 pCi/L 27.1 41.8 30.8 -48.0 N c2>

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

(b) ERA evaluation:

=

A Acceptable - Reported value falls within the Acceptance Limits

=

N Not Acceptable - Reported value falls outside of the Acceptance Limits (1) See NCR 17-09 (2) See NCR 17-19 (Page 1of1)

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APPENDIX E ERRATA DATA

There is no errata data for 2017 APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Intentionally left blank Docket No: 50-254 50-265 QUAD CITIES NUCLEAR POWER STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report 1 January through 31December2017 Prepared By Teledyne Brown Engineering Environmental Services 1

Exelon Generation,y Quad Cities Nuclear Power Station Cordova, IL 61242 April 2018

Intentionally left blank Table Of Contents I. Summary and Conclusion .................................................................................................. 3 II. Introduction ........................................................................................................................ 5 A. Objectives of the RGPP ........................................................................................ 5 B. Implementation of the Objectives .......................................................................... 6 C. Program Description ............................................................................................. 6 Ill. Program Description ........................................................................................................ 7 A. Sample Analysis .................................................................................................... 7 B. Data Interpretation ........... '. ..................................................................................... 7 IV. Results and Discussion ................................................................................................... 8 A. Groundwater Results ............................................................................................. 8 B. Surface Water Results ........................................................................................ 10 C. Summary of Results - Inter-laboratory Comparison Program ........................... 10 D. Leaks, Spills, and Releases ................................................................................ 10 E. Trends .................................................................................................................. 10 F. Investigations ....................................................................................................... 10 G. Actions Taken ..................................................................................................... 10

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2017 Figures Figure A-1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2017 Figure A-2 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2017 Appendix B Data Tables Tables Table B-1.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table B-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table B-1.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table B-11.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2017 Table B-111.1 Concentrations of Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel, 2017 ii

I. Summary and Conclusions This report on the Radiological Groundwater Protection Program (RGPP) conducted for the Quad Cities Nuclear Power Station (QCNPS) by Exelon Nuclear covers the period 01 January 2017 through 31 December 2017.

In 2006, Exelon undertook a Fleetwide Assessment of groundwater at and in the vicinity of its nuclear power generating facilities for the presence of radionuclides.

The data collected from the Quad Cities Station as part of the Fleetwide Assessment was summarized in a report entitled "Hydrogeologic Investigation Report, Fleetwide Assessment, Quad Cities Generation Station, Cordova, Illinois", dated September 2006. This report was submitted to the Illinois Environmental Protection Agency (IEPA) in September 2006. The Quad Cities Hydrogeologic Investigation Report concluded that tritium had not migrated off Site at detectable concentrations.

Following the Fleetwide Assessment, Exelon continued groundwater monitoring for radionuclides at the Site. As a result of this monitoring, Exelon detected higher than expected tritium levels in the vicinity of the station's Service Building and Turbine Building. Quad Cities undertook supplemental investigative activities to determine and characterize the source of the tritium. These investigative activities included completion of an aquifer pumping test, installation of sentinel monitoring wells in the vicinity of the Service Building and Turbine Building, and several additional rounds of hydraulic monitoring and groundwater sampling. The collected groundwater data was utilized to assist with an extensive underground piping inspection program to locate the source of the tritium.

In May 2008, during the underground piping inspection program, Exelon located a small leak in the Unit 1 Residual Heat Removal (RHR) suction line located near the Service Building/ Turbine Building area. The line was isolated and through further testing, Exelon determined it to be a source of the monitored tritium levels. In June 2008, the line was repaired, thereby eliminating this source of tritiated water.

In a letter dated June 5, 2008, Exelon informed the Illinois Environmental Protection Agency (IEPA) of its plan to prepare a Migration Control Plan (MCP) to minimize migration of the tritium plume offsite. The MCP was submitted to the IEPA July 17, 2008. The MCP listed Monitored Natural Attenuation as the preferred remediation option.

In 2012 Conestoga-Rovers & Associates (CRA) completed a five-year update hydrogeologic investigation report for the Station (NE/ 07-07, Hydrogeologic Investigation Report, dated November 2012). In 2017 GHD (formerly CRA) completed a five-year update hydrogeologic investigation report for the Station (NE/ 07-07, Hydrogeologic Investigation Report, dated November 2017). The referenced reports summarized station activities since the 2006 hydrogeologic investigation report, including changes at the Station as well as RGPP sampling activities and groundwater flow.

The RGPP designates wells into categories. Well designation categories include background, detection, elevated, long-term shut down, plume and idle. The RGPP also requires the sampling of surface water locations that may be impacted due to a spill or release.

This report covers groundwater samples, collected from the environment on .

station property in 2017. During that time period, RGPP samples were collected from 42 locations.

2017 sample locations included 36 designated monitoring wells, 2 surface water monitoring points and 4 production wells (two of which are used for site drinking water). Sample frequency and analysis varies with well designation. Typical frequency/analysis include quarterly for tritium and annual for gamma, gross alpha, gross beta, strontium, select transuranics and lron-55 (Fe-55)/Nickel-63 (Ni-63). Samples from 18 of the designated monitoring wells and 2 surface water sample points were collected by a contractor (Environmental Inc.) and analyzed by a contract lab (Teledyne Brown). The remaining sample locations are collected by site personnel and analyzed for tritium/gamma onsite by station personnel or by Teledyne Brown for tritium/gamma and other parameters.

Tritium concentrations ranged from less than the LLD of 200 pCi/L at the site boundaries up to 25,200 pCi/L in a monitoring well. Tritium concentrations were less than the LLD of 200 pCi/L in surface water monitoring locations.

Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater samples. In the case of tritium, Exelon specified that its contract laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation. Most of the tritium that was detected in groundwater at the Station is on the south and west side of the Reactor/Turbine buildings.

Strontium-89 (Sr-89) was not detected at concentrations greater than the Lower Limit of Detection (LLD) of 10.0 pCi/L. Strontium-90 (Sr-90) was not detected at concentrations greater than the Lower Limit of Detection (LLD) of 1.0 pCi/L.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on 9 designated groundwater locations during the first quarter sampling in 2017.

Gross Alpha (dissolved) was not detected at any of the groundwater locations.

Gross Alpha (suspended) was not detected at any of the groundwater locations.

Gross Beta (dissolved) was detected in 8 of 9 groundwater locations. The concentrations ranged from 1.3 pCi/L to 58.6 pCi/L.

Gross Beta (suspended) was not detected at any of the groundwater locations.

Select Transuranics/Hard-To-Detect analyses were performed on 1 monitoring well designated as "elevated" (QC-GP-15). The analyses included Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, U-238, Fe-55 and Ni-

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

In assessing all the data gathered for this report, it was concluded that the operation of QCNPS had no adverse radiological impact on the environment offsite of QCNPS.

II. Introduction The Quad Cities Nuclear Power Station (QCNPS), consisting of two 2957 MWth boiling water reactor owned and operated by Exelon Corporation, is located in Cordova, Illinois along the Mississippi River. Unit No. 1 went critical on 16 March 1972. Unit No. 2 went critical on 02 December 1973. The site is located in northern Illinois, approximately 182 miles west of Chicago, Illinois.

A. Objectives of the RGPP The long-term objectives of the RGPP are as follows:

1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources

2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface

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

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

5. Regularly assess analytical results to identify adverse trends

6. Take necessary corrective actions to protect groundwater resources B. Implementation of the Objectives The objectives identified have been implemented at Quad Cities Nuclear Power Station as discussed below:

1. Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Conestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators in station specific reports.

2. The Quad Cities Nuclear Power Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.

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

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

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

C. Program Description

1. Sample Collection Sample locations can be found in Table A-1 and Figures A-1 &

A-2, Appendix A.

Groundwater and Surface Water Samples of water are collected, managed, transported and analyzed in accordance with approved procedures following regulatory methods. Both groundwater and surface water are collected. Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures. Contractor and/or station personnel are trained in the collection, preservation management, analysis and shipment of samples, as well as in documentation of sampling events.

Analytical laboratories are subject to internal quality assurance programs, inter-laboratory cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables after initial review by the contractor.

Analytical data results are reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to hydrogeologic conditions.

Ill. Program Description This section covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2017.

A. Sample Analysis This section describes the general analytical methodologies used by TBE and station personnel to analyze the environmental samples for radioactivity for the Quad Cities Nuclear Power Station RGPP in 2017.

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

1. Concentrations of gamma emitters in groundwater and surface water

2. Concentrations of strontium in groundwater

3. Concentrations of tritium in groundwater and surface water

4. Concentration 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-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 Quad Cities Nuclear Power Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Quad Cities Nuclear Power Station was considered operational at initial criticality. Several factors were important in the interpretation of the data:

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is specified by federal regulation as a minimum sensitivity value that must be achieved routinely by the analytical parameter.

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

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

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

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

Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the Annual Radiological Environmental Operating Report (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.

IV. Results and Discussion A. Groundwater Results Groundwater Samples were collected from on-site wells 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-1.1 & B-111.1 Appendix B). Tritium values ranged from the detection limit to 25,200 pCi/L. All samples obtained at the site boundaries were less than the detection limit of 200 pCi/L, with the exception of MW-QC-1121 sampled on 2/28/17, which showed activity of 218 pCi/L. The location most representative of potential offsite user of drinking water was <200 pCi/L.

Strontium Sr-89 was not detected above the Lower Limit of Detection of 10.0 pCi/L. Sr-90 was not detected above the Lower Limit of Detection (LLD) of 1.0 pCi/L (Table B-1.1 Appendix B)

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions performed on designated groundwater locations during the 1st quarter in 2017.

Gross Alpha (dissolved) was not detected at any of the groundwater locations.

Gross Alpha (suspended) was not detected at any of the groundwater locations.

Gross Beta (dissolved) was detected in 8 of 9 groundwater locations. The concentrations ranged from less than LLD of 1.3 pCi/L to 58.6 pCi/L.

Gross Beta (suspended) was not detected at any of the groundwater locations (Table B-1.1 Appendix B).

Gamma Emitters No gamma-emitting nuclides were detected other than naturally-occurring K-40 in one sample at a concentration of 104 pCi/L (Table B-1.2, Appendix B).

Select Transu ran ics/Hard-To-Detect Select Transuranics/Hard-To-Detect analyses was performed on one groundwater location. The analyses included Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, U-238, Fe-55 and Ni-63. All hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs. (Table B-1.3 Appendix B).

B. Surface Water Results Surface Water Tritium Samples from 2 locations were analyzed for tritium activity. Tritium concentrations were less than the LLD of 200 pCi/L. A surface water sample was not obtained during the 3rd quarter of 2017 from location SW-QC-2 due to insufficient water level at this location due to former spray canal being drained to support fish hatchery operations. (Table B-11.1 Appendix B).

Gamma Emitters No gamma-emitting nuclides were detected at either surface water locations. (Table B-11.2, Appendix B).

C. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.

D. Leaks, Spills, and Releases No leaks, spills or releases were identified during the year.

E. Trends Overall, groundwater tritium concentrations have been decreasing over time at the Station.

F. Investigations Currently no investigations are on-going.

G. Actions Taken

1. Compensatory Actions There have been no station events requiring compensatory actions at the Quad Cities Nuclear Power Station in 2017.

2. Actions to Recover/Reverse Plumes No actions were required to recover or reverse groundwater plumes.

Quad Cities Station Migration Control Plan (MCP) continues to employ Monitored Natural Attenuation for remediation of H-3 plume.

Intentionally left blank APPENDIX A LOCATION DESIGNATION

TABLEA-1: Radiological Groundwater Protection Program - Sampling Locations Quad Cities Nuclear Power Station, 2017 Site Site Type Well Designation Minimum Sample Frequency MW-QC-1 Monitoring Well Plume Quarterly MW-QC-2 Monitoring Well Plume Quarterly MW-QC-3 Monitoring Well Plume Quarterly MW-QC-1011 Monitoring Well Idle Not Required MW-QC-101S Monitoring Well Idle Not Required MW-QC-102D Monitoring Well Plume Quarterly MW-QC-1021 Monitoring Well Plume Quarterly MW-QC-102S Monitoring Well Plume Quarterly MW-QC-1031 Monitoring Well Detection Quarterly MW-QC-104S Monitoring Well Detection Quarterly MW-QC-1051 Monitoring Well Plume Quarterly MW-QC-1061 Monitoring Well Plume Quarterly MW-QC-106S Monitoring Well Plume Quarterly MW-QC-1071 Monitoring Well Background Annual MW-QC-108D Monitoring Well Plume Quarterly MW-QC-1081 Monitoring Well Plume Quarterly MW-QC-108S Monitoring Well Plume Quarterly MW-QC-1091 Monitoring Well Plume Quarterly MW-QC-109S Monitoring Well Plume Quarterly MW-QC-1101 Monitoring Well Idle Not Required MW-QC-11101 Monitoring Well Idle Not Required MW-QC-11102 Monitoring Well Idle Not Required MW-QC-1111 Monitoring Well Idle Not Required MW-QC-1121 Monitoring Well Plume Quarterly MW-QC-1131 Monitoring Well Idle Not Required MW-QC-1141 Monitoring Well Idle Not Required MW-QC-115S Monitoring Well Idle Not Required MW-QC-116S Monitoring Well Idle Not Required SURFACE WATER #1 Surface Water Surface Water Quarterly SURFACE WATER #2 Surface Water Surface Water Quarterly WELL#1 Production Well Idle Not Required WELL#5 Production Well Idle Not Required WELL #6 LITTLE FISH Production Well Idle Not Required WELL #7 BIG FISH WELL Production Well Plume Quarterly WELL #8 FIRE TRAINING WELL Production Well Idle Not Required WELL #9 Dry Cask Storage Production Well Background Annual WELL #10 FISH HOUSE WELL Production Well Idle Not Required WELL #11 SPRAY CANAL WELL Production Well Idle Not Required STP SAND POINT WELL Production Well Idle Not Required QC-GP-1 Sentinel Well Plume Quarterly QC-GP-2 Sentinel Well Plume Quarterly QC-GP-3 Sentinel Well Idle Not Required QC-GP-4 Sentinel Well Plume Quarterly QC-GP-5 Sentinel Well Plume Quarterly QC-GP-6 Sentinel Well Plume Quarterly QC-GP-7 Sentinel Well Plume Quarterly QC-GP-8 Sentinel Well Idle Not Required QC-GP-9 Sentinel Well Plume Quarterly QC-GP-10 Sentinel Well Detection Quarterly QC-GP-11 Sentinel Well Detection Quarterly QC-GP-12 Sentinel Well Detection Quarterly QC-GP-13 Sentinel Well Plume Quarterly QC-GP-14 Sentinel Well Detection Quarterly QC-GP-15 Sentinel Well Elevated Quarterly QC-GP-16 Sentinel Well Detection Quarterly QC-GP-17 Sentinel Well Plume Quarterly QC-GP-18 Sentinel Well Plume Quarterly Note: Idle designated wells are not required to be sampled as part of the RGPP A-1

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QUAD CITIES GENERATING STATION Cordova, Qlinois FIGUREA-2 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2017

APPENDIX B DATA TABLES

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

MW-QC-1 02/28/17 < 190 MW-QC-1 05/31/17 < 182 MW-QC-1 09/11/17 < 194 MW-QC-1 11/16/17 Original 262 +/- 115 MW-QC-1 11/16/17 Recount 284 +/- 117 MW-QC-1 11/16/17 Reanalysis 201 +/- 103 MW-QC-2 02/28/17 < 190 MW-QC-2 05/31/17 < 181 MW-QC-2 09/11/17 < 193 MW-QC-2 11/16/17 < 168 MW-QC-3 02/28/17 22700 +/- 2330 MW-QC-3 05/31/17 8240 +/- 878 MW-QC-3 09/11/17 4910 +/- 555 MW-QC-3 11/16/17 3950 +/- 447 MW-QC-102D 02/28/17 661 +/- 150 MW-QC-102D 05/31/17 750 +/- 146 MW-QC-102D 09/11/17 554 +/- 146 MW-QC-102D 11/16/17 470 +/- 126 MW-QC-1021 02/28/17 < 188 MW-QC-1021 05/31/17 < 181 MW-QC-1021 09/11/17 < 192 MW-QC-1021 11/16/17 < 171 MW-QC-102S 02/28/17 < 191 MW-QC-102S 05/31/17 < 172 MW-QC-102S 09/11/17 < 197 MW-QC-102S 11/16/17 < 172 MW-QC-1031 02/28/17 < 188 < 5.2 < 0.8 < 1.7 < 0.7 7.3 +/- 1.2 < 1.4 MW-QC-1031 05/31/17 < 173 MW-QC-1031 09/11/17 < 193 MW-QC-1031 11/16/17 < 171 MW-QC-104S 02/28/17 < 190 < 5.3 < 0.6 < 2.3 < 0.7 15.4 +/- 1.7 < 1.4 MW-QC-104S 05/31/17 < 173 MW-QC-104S 09/11/17 < 195 MW-QC-104S 11/16/17 < 168 MW-QC-1051 02/28/17 < 187 MW-QC-1051 05/31/17 < 176 MW-QC-1051 09/11/17 < 193 MW-QC-1051 11/16/17 < 170 MW-QC-1061 02/28/17 < 188 MW-QC-1061 05/31/17 < 171 MW-QC-1061 09/11/17 < 190 MW-QC-1061 11/16/17 < 173 MW-QC-106S 02/28/17 < 191 MW-QC-106S 05/31/17 < 177 MW-QC-106S 09/11/17 < 195 MW-QC-106S 11/16/17 < 172 B-1

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

MW-QC-1071 02/27/17 < 191 MW-QC-108D 02/28/17 586 +/- 141 MW-QC-108D 06/01/17 465 +/- 128 MW-QC-108D 09/11/17 544 +/- 144 MW-QC-108D 11/15/17 378 +/- 123 MW-QC-1081 02/28/17 < 187 MW-QC-1081 06/01/17 1150 +/- 183 MW-QC-1081 09/11/17 < 194 MW-QC-1081 11/15/17 < 169 MW-QC-108S 02/28/17 260 +/- 126 MW-QC-108S 06/01/17 < 178 MW-QC-108S 09/11/17 315 +/- 133 MW-QC-108S 11/15/17 566 +/- 132 MW-QC-1091 02/28/17 < 187 MW-QC-1091 05/31/17 < 182 MW-QC-1091 09/11/17 < 192 MW-QC-1091 11/16/17 < 172 MW-QC-109S 02/28/17 < 192 MW-QC-109S 05/31/17 < 174 MW-QC-109S 09/11/17 < 197 MW-QC-109S 11/16/17 < 169 MW-QC-1121 02/27/17 218 +/- 124 MW-QC-1121 05/31/17 < 180 MW-QC-1121 09/11/17 < 195 MW-QC-1121 11/15/17 < 170 QC-GP-10 02/27/17 < 184 < 4.2 < 0.8 < 3.0 < 0.5 10.8 +/- 1.8 < 1.5 QC-GP-11 03/01/17 < 189 < 2.8 < 0.6 < 1.4 < 0.5 5.6 +/- 1.4 < 1.5 QC-GP-12 02/27/17 < 186 < 2.9 < 0.7 < 0.9 < 0.5 < 1.3 < 1.5 QC-GP-14 03/01/17 376 +/- 138 < 8.2 < 0.8 < 2.1 < 1.0 8.7 +/- 1.5 < 1.6 QC-GP-14 03/01/17 Recount 7.6 +/- 1.5 QC-GP-15 02/27/17 < 186 < 3.1 < 0.8 < 4.1 < 0.5 16.0 +/- 2.3 < 1.5 QC-GP-16 02/27/17 3740 +/- 430 < 4.6 < 0.9 < 1.4 < 1.0 4.6 +/- 1.1 < 1.6 QC-GP-18 03/06/17 21100 +/- 2160 < 4.5 < 0.6 < 8.3 < 2.2 58.6 +/- 4.8 < 3.3 WELL #9 DRY CASK 03/07/17 < 187 Balded values indicate LLD was not met due to the high solid content in the sample B-2

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 MW-QC-1031 02/28/17 < 50 < 67 < 5 < 5 < 13 <5 < 11 < 6 < 10 < 14 <6 < 5 < 28 < 10 MW-QC-104S 02/28/17 < 56 < 126 <5 < 6 < 10 <6 < 11 < 7 < 12 < 14 <6 <6 < 32 < 9 MW-QC-1071 02/27/17 < 60 < 140 <6 <6 < 13 <6 < 12 < 8 < 10 < 14 <8 < 8 < 43 < 9 QC-GP-10 02/27/17 < 35 < 31 <4 <4 < 9 <4 <6 < 5 <6 < 13 <4 <4 < 31 < 8 QC-GP-11 03/01/17 < 42 < 33 <4 <4 < 10 <4 < 7 < 5 < 8 < 12 <4 <4 < 27 < 10 QC-GP-12 02/27/17 < 32 < 62 < 3 <4 <7 <3 <6 <4 <6 < 10 <4 <3 < 24 < 7 QC-GP-14 03/01/17 < 40 < 110 < 5 <4 <8 <6 < 10 <5 <8 < 13 < 5 < 5 < 34 < 8 QC-GP-15 02/27/17 < 27 < 23 <3 < 3 <6 <2 < 5 < 3 < 5 < 11 <3 < 3 < 22 < 5 QC-GP-15 09/12/17 < 34 < 55 < 3 < 3 < 8 <4 <7 <4 < 6 < 13 <4 <4 < 25 < 10 QC-GP-18 09/12/17 < 38 < 67 <4 <4 < 8 <4 < 7 <4 < 8 < 13 <5 < 3 < 28 < 11 QC-GP-16 02/27/17 < 38 < 88 <4 <4 <8 <4 < 7 <4 < 6 < 14 <4 <4 < 28 < 9 al QC-GP-18 03/06/17 < 44 104 +/- 65 < 5 < 5 <8 <5 < 10 < 6 < 8 < 11 <6 <6 < 25 < 9 I

(.I) WELL #9 DRY CASK 03/07/17 < 70 < 144 <8 <7 < 15 < 8 < 12 < 9 < 13 < 13 < 10 < 9 < 40 < 13

TABLE B-1.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 Fe-55 Ni-63 QC-GP-15 02/27/17 < 0.12 < 0.11 < 0.10 < 0.00 < 0.00 < 0.19 < 0.08 < 0.16 < 191 < 4.3 CD Ji.

TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/LITER + 2 SIGMA COLLECTION SITE DATE H-3 SW-QC-1 02/27/17 < 191 SW-QC-1 05/30/17 < 181 SW-QC-1 09/11/17 < 195 SW-QC-1 11/15/17 < 171 SW-QC-2 02/27/17 < 187 SW-QC-2 05/30/17 < 180 SW-QC-2 11/15/17 < 171 B-5

TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2017 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 SW-QC-1 02/27/17 < 54 < 39 < 5 <6 < 12 < 5 < 10 <6 < 11 < 13 <6 < 6 < 31 < 11 SW-QC-2 02/27/17 < 43 < 47 < 5 < 5 < 9 <4 < 10 <6 < 8 < 11 <4 < 5 < 25 < 10

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TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2017 RESULTS IN UNITS OF PCl/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-1 02/27/17 3,230 Sentinel Well QC-GP-1 05/30/17 <2,000 Sentinel Well QC-GP-1 09/12/17 <2000 Sentinel Well QC-GP-1 11/13/17 <2000 Sentinel Well QC-GP-2 02/27/17 <2,000 Sentinel Well QC-GP-2 05/31/17 <2,000 Sentinel Well QC-GP-2 09/12/17 <2,000 Sentinel Well QC-GP-2 11/14/17 <2,000 Sentinel Well QC-GP-3 02/28/17 <2,000 Sentinel Well QC-GP-4 02/28/17 9,510 Sentinel Well QC-GP-4 05/30/17 4,780 Sentinel Well QC-GP-4 09/12/17 21,800 Sentinel Well QC-GP-4 09/18/17 16,300 Sentinel Well QC-GP-4 11/13/17 14,000 Sentinel Well QC-GP-5 02/27/17 <2,000 Sentinel Well QC-GP-5 05/31/17 <2,000 Sentinel Well QC-GP-5 09/12/17 <2,000 Sentinel Well QC-GP-5 11/14/17 <2,000 Sentinel Well QC-GP-6 02/27/17 <2,000 Sentinel Well QC-GP-6 05/31/17 <2,000 Sentinel Well QC-GP-6 09/12/17 <2,000 Sentinel Well QC-GP-6 11/14/17 <2,000 Sentinel Well QC-GP-7 02/27/17 <2,000 Sentinel Well QC-GP-7 05/31/17 <2,000 Sentinel Well QC-GP-7 09/12/17 <2,000 Sentinel Well QC-GP-7 11/14/17 <2,000 Sentinel Well QC-GP-8 02/27/17 <2,000 Sentinel Well QC-GP-9 02/27/17 13,400 Sentinel Well QC-GP-9 05/31/17 <2000 Sentinel Well QC-GP-9 09/12/17 8,400 Sentinel Well QC-GP-9 11/13/17 15,200 Sentinel Well QC-GP-10 02/27/17 <2,000 Sentinel Well QC-GP-10 05/31/17 <2,000 Sentinel Well QC-GP-10 09/12/17 <2,000 Sentinel Well QC-GP-10 11/14/17 <2,000 Sentinel Well QC-GP-11 03/01/17 <2,000 Sentinel Well QC-GP-11 05/30/17 <2,000 Sentinel Well QC-GP-11 09/13/17 <2,000 Sentinel Well QC-GP-11 11/16/17 <2,000 Sentinel Well QC-GP-12 02/27/17 <2,000 Sentinel Well QC-GP-12 05/30/17 <2,000 Sentinel Well QC-GP-12 09/13/17 <2,000 Sentinel Well QC-GP-12 11/17/17 <2,000 Sentinel Well QC-GP-13 03/01/17 6,690 Sentinel Well QC-GP-13 06/01/17 <2000 Sentinel Well QC-GP-13 09/13/17 3,810 Sentinel Well QC-GP-13 11/17/17 6,280 Sentinel Well QC-GP-14 03/01/17 <2000 Sentinel Well QC-GP-14 05/30/17 4,020 Sentinel Well QC-GP-14 09/13/17 <2000 Sentinel Well QC-GP-14 11/16/17 <2,000 Sentinel Well QC-GP-15 02/27/17 <2,000 Sentinel Well QC-GP-15 05/31/17 <2,000 Sentinel Well QC-GP-15 09/12117 <2,000 Sentinel Well QC-GP-15 11/14/17 <2,000 Sentinel Well B-7

TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2017 RESULTS IN UNITS OF PCl/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-16 02/27/17 5,290 Sentinel Well QC-GP-16 05/30/17 <2,000 Sentinel Well QC-GP-16 09/13/17 4,760 Sentinel Well QC-GP-16 11/13/17 3,530 Sentinel Well QC-GP-17 02/27/17 <2000 Sentinel Well QC-GP-17 05/30/17 <2000 Sentinel Well QC-GP-17 09/12/17 2,030 Sentinel Well QC-GP-17 11/13/17 3,620 Sentinel Well QC-GP-18 02/27/17 24,800 Sentinel Well QC-GP-18 03/06/17 24,500 Sentinel Well QC-GP-18 04/18/17 24,700 Sentinel Well QC-GP-18 05/22/17 25,200 Sentinel Well QC-GP-18 05/30/17 23,400 Sentinel Well QC-GP-18 07/17/17 16,900 Sentinel Well QC-GP-18 09/12/17 9,330 Sentinel Well QC-GP-18 11/14/17 17,800 Sentinel Well MW-QC-3 03/06/17 12,700 Monitoring Well MW-QC-3 04/18/17 6,950 Monitoring Well MW-QC-3 07/17/17 2,120 Monitoring Well Well#1 05/15/17 <200 Production Well Well#1 11/07/17 <200 Production Well Well#5 05/15/17 <200 Production Well Well#5 11/07/17 <200 Production Well Well#? 02/27/17 <2,000 Production Well Well#? 06/05/17 <2,000 Production Well Well#? 09/12/17 <2,000 Production Well Well#? 11/16/17 <2,000 Production Well B-8

SVP-18-035, Annual Radiological Environmental Operating Report

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