Text

Submittal of Annual Radiological Environmental Operating Report
	ML17132A189
Person / Time
Site:	Quad Cities
Issue date:	05/12/2017
From:	Darin S; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	SVP-17-039
	Download: ML17132A189 (116)
	v • d • e

Lon G n ration SVP-17-039 May 12, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRG Docket Nos. 50-254 and 50-265

Subject:

Annual Radiological Environmental Operating Report Pursuant to Technical Specifications Section 5.6.2, enclosed is the 2016 Radiological Erpvironmental Operating Report for Quad Cities Nuclear Power Station. This Report contains the results of the Radiological Environmental Monitoring Program (REMP). In addition, the 2016 Radiological Groundwater Protection Program (RGPP) Report is included as Appendix F of the enclosure.

Should you have any questions concerning this letter, please contact Wally J. Beck at (309) 227-2800.

Respectfully, Scott Darin Site Vice President Quad Cities Nuclear Power Station

Enclosure:

Annual Radiological Environmental Operating Report cc: Regional Administrator- NRG Region Ill NRG 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 1 and 2 Annual Radiological Environmental Operating Report 1 January through 31 December 2016 Prepared By Teledyne Brown Engineering Environmental Services Quad Cities Nuclear Power Station Cordova, IL 61242 May 2017

Intentionally left blank Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ..................................................................................................................... 2 A. Objectives of the REMP ...................................................................................... 3 B. Implementation of the Objectives ........................................................................ 3 C. Radiation and Radioactivity................................................................................. 3 D. Sources of Radiation ........................................................................................... 4 III. Program Description ...................................................................................................... 5 A. Sample Collection ............................................................................................... 5 B. Sample Analysis .................................................................................................. 7 C. Data Interpretation .............................................................................................. 8 D. Program Exceptions ............................................................................................ 9 E. Program Changes ............................................................................................. 11 IV. Results and Discussion ............................................................................................... 11 A. Aquatic Environment ......................................................................................... 11

1. Surface Water......................................................................................... 11

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

3. Fish ......................................................................................................... 12

4. Sediment................................................................................................. 13 B. Atmospheric Environment ................................................................................. 13

1. Airborne .................................................................................................. 13

a. Air Particulates............................................................................. 13

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

2. Terrestrial ................................................................................................ 14

a. Milk............................................................................................... 14

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

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for Quad Cities Nuclear Power Station, 2016 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, 2016 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2016 Figures Figure B-1 Quad Cities REMP Sampling Locations - 2 Mile Radius, 2016 Figure B-2 Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2016 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-I.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table C-I.2 Concentrations of Tritium, Iron-55 and Nickel-63 in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table C-I.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table C-II.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table C-II.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 ii

Table C-III.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 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, 2016 Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table C-VI.1 Concentrations of I-131 in Air Iodine Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table C-VII.1 Concentrations of I-131 in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table C-VIII.1 Concentrations of Gamma Emitters in Food Product Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table C-IX.1 Quarterly OSLD Results for Quad Cities Nuclear Power Station, 2016 Table C-IX.2 Mean Quarterly OSLD Results for the Inner Ring, Outer Ring, Other and Control Location for Quad Cities Nuclear Power Station, 2016 Table C-IX.3 Summary of the Ambient Dosimetry Program for Quad Cities Nuclear Power Station, 2016 Figures Figure C-1 Surface Water - Gross Beta - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2016 Figure C-2 Surface Water - Tritium - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2016 Figure C-3 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2016 Figure C-4 Air Particulates - Gross Beta - Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2016 Figure C-5 Air Particulates - Gross Beta - Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2016 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 - 2016 Figure C-8 Air Particulates - Gross Beta - Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2016 Figure C-9 Air Particulates - Gross Beta - Stations Q-41 and Q-42 (C) Collected in the Vicinity of QCNPS, 2009 - 2016 Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2016 Table D-2 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2016 Table D-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2016 Table D-4 ERA (a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2016 Table D-5 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2016 Appendix E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv

I. Summary and Conclusions In 2016, the Quad Cities Generating Station released to the environment through the radioactive effluent gaseous pathways, approximately 164 curies of noble gas, 1.36E-02 curies of fission and activation products, 29 curies of Carbon-14 and approximately 94 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 2016 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 3.53E-03 All 1029 NNE 1.77E-02 20 mRad Noble Gas Beta - Air Dose 4.13E-04 All 1029 NNE 1.03E-03 40 mRad Iodine, Particulate Total Body 4.29E-02 Child 1029 NNE 1.72E-01 25 mrem C-14 & Tritium Iodine, Particulate Thyroid 3.42E-01 Infant 1029 NNE 1.07E-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 7.42E+00 All 800 N 2.97E+01 25 mrem Total Body (Gas + Liq+

40CFR190 7.46E+00 All 800 N 2.98E+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 29.8%

of the 25 mrem/yr limit. The largest component of 40CFR190 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 2016 through 31 December 2016. During that time period, 1552 analyses were performed on 1437 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 Iodine-131 (I-131) analyses were performed on air samples. No I-131 was detected.

Cow milk samples were analyzed for concentrations of I-131 and gamma-emitting nuclides. No I-131 was detected. Concentrations of naturally-occurring isotopes (K-40 averaging 1310 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 (OSLD). 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 2016 through 31 December 2016.

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, Iodine-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 II.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 II.D-1 Radiation Sources and Corresponding Doses (1)

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 Industrial(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.

III. 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 2016. 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 (OSLD) 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).

Each location consisted of 2 OSLD sets. The OSLD 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 OSLD 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 2016 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 I-131 in air and milk

5. Ambient gamma radiation levels at various site environs

6. Concentrations of Iron-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), Iron-59 (Fe-59),

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

Niobium-95 (Nb-95), I-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, I-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 2016 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 Type Code Date AP/AI Q-42 03/17/16 Low reading of 163.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months due to power outage from storm AP/AI Q-01 03/18/16 Low reading of 164.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ; power out at air sampler in preparation for station outage.

Used flow of 62 cfh based on previous 4 weeks average.

Unable to field check pump.

AP/AI Q-01 04/01/16 Low reading of 45.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months due to recent power restoration AP/AI Q-02 04/01/16 Timer malfunction; estimated timer reading of 160.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Collector placed new timer.

Table D-1 LISTING OF SAMPLE ANOMALIES (contd)

Sample Location Collection Reason Type Code Date AP/AI Q-38 06/03/16 Low timer reading of 161.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months due to power outage AP/AI Field Check 10/01/16 Illinois side - unable to check pumps. Rotameter unavailable; FedEx would not leave at house.

NOTE: Field check performed on 10/05/16 AP/AI Q-37 11/04/16 Low timer reading of 131.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months due to power outage AP/AI Q-38 11/04/16 Low timer reading of 131.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months due to power outage Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date OSLD Q-205-4 01/01/16 OSLD found missing during Quarterly exchange; new 1st qtr 2016 OSLD placed SW Q-34 01/07/16 No sample; water frozen SW Q-33 01/15/16 No sample; water frozen SW Q-34 01/15/16 No sample; water frozen SW Q-33 01/22/16 No sample; water frozen SW Q-34 01/22/16 No sample; water frozen SW Q-33 02/04/16 No sample; water frozen SW Q-34 02/04/16 No sample; water frozen OSLD Q-216-1 02/04/16 OSLD missing during monthly check; collector placed Spare #1 291558 on 02/08/16 Table D-2 LISTING OF MISSED SAMPLES (contd)

Sample Location Collection Reason Type Code Date SW Q-33 02/11/16 No sample; water frozen SW Q-34 02/11/16 No sample; water frozen AP/AI Q-01 03/25/16 No power to sampler SW Q-33 12/15/16 No sample; water frozen SW Q-34 12/15/16 No sample; water frozen SW Q-33 12/22/16 No sample; water frozen SW Q-34 12/22/16 No sample; water frozen SW Q-33 12/29/16 No sample; water frozen SW Q-34 12/29/16 No sample; water frozen 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 2016.

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-I.1, Appendix C). Gross beta activity was detected in 24 of 24 samples. The values ranged from 2.6 to 5.9 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-I.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-I.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-I.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-II.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-II.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-III.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 was not detected in any of the samples. 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 7 to 47E-03 pCi/m3 with a mean of 16E-03 pCi/m3. The results from the far-field locations (Group II) ranged from 6 to 44E-03 pCi/m3 with a mean of 17E-03 pCi/m3. The results from the Control location (Group III) ranged from 9 to 36E-03 pCi/m3 with a mean of 17E-03 pCi/m3. Comparison of the 2016 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 2016 indicate no notable differences among the three groups (Figures C-4 through C-9, Appendix C).

Gamma Spectrometry 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 I-131 (Table C-VI.1, Appendix C). All results were less than the LLD for I-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:

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

Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma-emitting nuclides (Table C-VII.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-VIII.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 OSLD locations were established around the site. Results of OSLD measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C.

All of the OSLD measurements were approx. 30 mRem/quarter, with a range of 18.6 to 33.2 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 2016 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 1.6 -

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 2016.

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

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

2. ERA Evaluation Criteria ERAs evaluation report provides an acceptance range for control and warning limits with associated flag values. ERAs acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERAs SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

3. DOE Evaluation Criteria MAPEPs evaluation report provides an acceptance range with associated flag values.

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

For the TBE laboratory, 156 out of 160 analyses performed met the specified acceptance criteria. Four analyses (Milk - Sr-90, Vegetation -

Sr-90, and Water - H-3 samples) did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program.

Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities.

1. Teledyne Brown Engineerings MAPEP March 2016 air particulate cross check sample is now being provided to TBE by Analytics.

MAPEPs policy is to evaluate as failed non reported nuclides that were reported in the previous study. Since the Sr-90 was reported in the previous MAPEP study but not in this study MAPEP evaluated the Sr-90 for Soil as failed. NCR 16-14 The MAPEP March 2016 Sr-90 in vegetation was evaluated as failing a false positive test. In reviewing the data that was reported vs the data in LIMS, it was found that the error was incorrectly reported as 0.023 rather than the correct value of 0.230. If the value had been reported with the activity and correct uncertainty of 0.301 +/- 0.230, MAPEP would have evaluated the result as acceptable. NCR 16-14

2. Teledyne Brown Engineerings Analytics March 2016 milk Sr-90 result of 15 +/- .125 pCi/L was higher than the known value of 11.4 pCi/L with a ratio of 1.32. The upper ratio of 1.30 (acceptable with warning) was exceeded. After an extensive review of the data it is believed the technician did not rinse the filtering apparatus properly and some cross contamination from one of the internal laboratory spike samples may have been transferred to the analytics sample.

We feel the issue is specific to the March 2016 Analytics sample.

NCR 16-26

3. Teledyne Brown Engineerings ERA November 2016 sample for H-3 in water was evaluated as failing. A result of 918 pCi/L was reported incorrectly due to a data entry issue. If the correct value of 9180 had been reported, ERA would have evaluated the result as acceptable. NCR 16-34

4. Teledyne Brown Engineerings Analytics December 2016 milk Sr-90 sample result of 14.7 +/- .26 pCi/L was higher than the known value of 10 pCi/L with a ratio of 1.47. The upper ratio of 1.30 (acceptable with warning) was exceeded. The technician entered the wrong aliquot into the LIMS system. To achieve a lower error term TBE uses a larger aliquot of 1.2L (Normally we use .6L for client samples). If the technician had entered an aliquot of 1.2L into the LIMS system, the result would have been 12.2 pCi/L, which would have been considered acceptable. NCR 16-35 For the EIML laboratory, 198 of 203 analyses met the specified acceptance criteria. Five analyses (Water - Ba-133, Co-57; Soil - Ni-63, U-233/234, U-238) did not meet the specified acceptance criteria for the following reasons:

1. The Environmental Inc., Midwest Laboratorys ERA April 2016 water Ba-133 result of 65.2 pCi/L was higher than the known value of 58.8 pCi/L, exceeding the upper control limit of 64.9 pCi/L. The reanalysis result of 57.8 pCi/L fell within acceptance criteria.

2. The Environmental Inc., Midwest Laboratorys MAPEP February 2016 water Co-57 result of 1.38 Bq/L sample was higher than the known value of 0.00 Bq/L sample. This sample is considered a false positive.

3. The Environmental Inc., Midwest Laboratorys MAPEP August 2016 soil Ni-60 result of 648 Bq/kg was lower than the known value of 990 Bq/kg, exceeding the lower control limit of 693 Bq/kg.

Reanalysis with a smaller aliquot resulted in acceptable results. An investigation is in process to identify better techniques for analyzing samples with complex matrices.

4. The Environmental Inc., Midwest Laboratorys MAPEP August 2016 soil U-233/234 result of 46.8 Bq/kg was lower than the known value of 122 Bq/kg, exceeding the lower control limit of 85 Bq/kg.

MAPEP states that samples contain two fractions of Uranium; one that is soluble in concentrated HNO3 and HCL acid and one that is fundamentally insoluble in these acids. They also state that HF treatment cannot assure complete dissolution. Results are consistent with measuring the soluble form.

5. The Environmental Inc., Midwest Laboratorys MAPEP August 2016 soil U-238 result of 46.6 Bq/kg was lower than the known value of 121 Bq/kg, exceeding the lower control limit of 85 Bq/kg.

MAPEP states that samples contain two fractions of Uranium; one that is soluble in concentrated HNO3 and HCL acid and one that is fundamentally insoluble in these acids. They also state that HF treatment cannot assure complete dissolution. Results are consistent with measuring the soluble form.

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, 2016 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD: 2016 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 (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS SURFACE WATER GR-B 24 4 4 4.3 4.3 Q-34 CONTROL 0 (PCI/LITER) (12/12) (12/12) (12/12) CAMANCHE - UPSTREAM 2.6 - 5 3.1 - 5.9 3.1 - 5.9 4.4 MILES NNE OF SITE H-3 8 2000 <LLD <LLD - 0 FE-55 8 200 <LLD <LLD - 0 NI-63 8 5 <LLD <LLD - 0 GAMMA 24 MN-54 15 <LLD <LLD - 0 CO-58 15 <LLD <LLD - 0 A-1 FE-59 30 <LLD <LLD - 0 CO-60 15 <LLD <LLD - 0 ZN-65 30 <LLD <LLD - 0 NB-95 15 <LLD <LLD - 0 ZR-95 30 <LLD <LLD - 0 I-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 (PCI/LITER)

GAMMA 8 MN-54 15 <LLD NA - 0 CO-58 15 <LLD NA - 0 FE-59 30 <LLD NA - 0 CO-60 15 <LLD NA - 0 ZN-65 30 <LLD NA - 0 NB-95 15 <LLD NA - 0 ZR-95 30 <LLD NA - 0 I-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 of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2016 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD: 2016 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 (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS FISH GAMMA 8 (PCI/KG WET) MN-54 130 <LLD <LLD - 0 CO-58 130 <LLD <LLD - 0 FE-59 260 <LLD <LLD - 0 CO-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 A-2 SEDIMENT GAMMA 4 (PCI/KG DRY) MN-54 NA <LLD <LLD - 0 CO-58 NA <LLD <LLD - 0 FE-59 NA <LLD <LLD - 0 CO-60 NA <LLD <LLD - 0 ZN-65 NA <LLD <LLD - 0 NB-95 NA <LLD <LLD - 0 ZR-95 NA <LLD <LLD - 0 CS-134 150 <LLD <LLD - 0 CS-137 180 <LLD <LLD - 0 BA-140 NA <LLD <LLD - 0 LA-140 NA <LLD <LLD - 0 AIR PARTICULATE GR-B 514 10 17 17 17 Q-42 CONTROL 0 (PCI/TOTAL) (461/462) (52/52) (52/52) LECLAIRE (6/47) (9/36) (9/36) 8.7 MILES SSW 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, 2016 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD: 2016 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 (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS AIR PARTICULATE GAMMA 40 (PCI/TOTAL) MN-54 NA <LLD <LLD - 0 CO-58 NA <LLD <LLD - 0 FE-59 NA <LLD <LLD - 0 CO-60 NA <LLD <LLD - 0 ZN-65 NA <LLD <LLD - 0 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 A-3 AIR IODINE GAMMA 518 (E-3 PCI/CU.METER) I-131 70 <LLD <LLD - 0 MILK I-131 (LOW LVL) 19 1 <LLD NA - 0 (PCI/LITER)

GAMMA 19 MN-54 NA <LLD NA - 0 CO-58 NA <LLD NA - 0 FE-59 NA <LLD NA - 0 CO-60 NA <LLD NA - 0 ZN-65 NA <LLD NA - 0 NB-95 NA <LLD NA - 0 ZR-95 NA <LLD NA - 0 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, 2016 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD: 2016 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 (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS VEGETATION GAMMA 13 (PCI/KG WET) MN-54 NA <LLD <LLD - 0 CO-58 NA <LLD <LLD - 0 FE-59 NA <LLD <LLD - 0 CO-60 NA <LLD <LLD - 0 ZN-65 NA <LLD <LLD - 0 NB-95 NA <LLD <LLD - 0 ZR-95 NA <LLD <LLD - 0 I-131 60 <LLD <LLD - 0 CS-134 60 <LLD <LLD - 0 CS-137 80 <LLD <LLD - 0 A-4 BA-140 NA <LLD <LLD - 0 LA-140 NA <LLD <LLD - 0 DIRECT RADIATION OSLD-QUARTERLY 329 NA 24.1 25.6 27.9 Q-216-1 INDICATOR 0 (MILLI-ROENTGEN/QTR.) (321/321) (8/8) (3/3) 18 - 33.2 22.8 - 28.7 24.4 - 30.6 4.6 MILES NNW (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, 2016 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 miles S Q-36 Cordova Well (indicator) 3.3 miles SSW C. Milk - bi-weekly / monthly Q-26 Bill Stanley Dairy (indicator) 3.1 miles ESE D. Air Particulates / Air Iodine 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) 5.7 miles 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 (control) 8.7 miles SSW 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) 0.8 miles SSW 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 miles S Quadrant 4 Mike Fawcett 4.5 miles NW Control Charles Leavens 9.5 miles NE H. Environmental Dosimetry - OSLD 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, 2016 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - OSLD (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 2.6 miles SW Q-111-2 2.5 miles SW Q-112-1 2.5 miles WSW Q-112-2 2.2 miles WSW Q-113-1 and -2 2.5 miles W Q-114-1 2.1 miles WNW Q-114-2 2.5 miles WNW 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 3.3 miles SSW Q-211-1 and -2 4.5 miles SW Q-212-1 5.4 miles WSW Q-212-2 4.4 miles WSW Q-213-1 4.3 miles W Q-213-2 4.8 miles W 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 B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2016 Location Location Description Distance & Direction From Site Other 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) 5.7 miles 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 Control 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, 2016 Sample Analysis Sampling Method Analytical Procedure Number Medium Monthly composite Surface Gamma from weekly grab TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy samples Monthly composite Surface Gross Beta from weekly grab TBE, TBE-2008 Gross Alpha and/or gross beta activity in various matrices Water samples Surface Tritium Quarterly composite TBE, TBE-2011 Tritium analysis in drinking water by liquid scintillation Water from weekly grab samples Quarterly composite Surface Iron and Nickel from weekly grab TBE, TBE-2006 Iron-55 in various matrices Water samples TBE, TBE-2013 Radionickel in various matrices Gamma Ground Water Spectroscopy Quarterly grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis Ground Water Tritium Quarterly grab samples TBE, TBE-2011 Tritium analysis in drinking water by liquid scintillation Gamma Semi-annual samples Fish collected via TBE-2007 Gamma emitting radioisotope analysis Spectroscopy electroshocking or other techniques Sediment Gamma Semi-annual grab TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy samples Air One-week composite TBE, TBE-2008 Gross Alpha and/or gross beta activity in various matrices Gross Beta of continuous air Particulates sampling through glass fiber filter paper Air Gamma Quarterly composite of TBE, TBE-2007 Gamma emitting radioisotope analysis Particulates Spectroscopy each station Gamma Weekly composite of Air Iodine Spectroscopy continuous air TBE, TBE-2007 Gamma emitting radioisotope analysis sampling through charcoal filter Bi-weekly grab sample Milk I-131 when cows are on TBE, TBE-2012 Radioiodine in various matrices pasture. Monthly all other times Bi-weekly grab sample Gamma when cows are on Milk TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy pasture. Monthly all other times Food Gamma Annual grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis Products Spectroscopy Optically Quarterly OSLDs OSLD Stimulated comprised of two Landauer Incorporated Luminescence Al2O3:C Landauer Dosimetry Incorporated elements B-4

B-5 Figure B-1 Map Quad Cities REMP Sampling Locations - 2 Mile Radius, 2016

B-6 Figure B-1 Legend Quad Cities REMP Sampling Locations - 2 Mile Radius, 2016

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

Intentionally left blank Table C-I.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD Q-33 Q-34 01/07/16 - 01/29/16 2.8 +/- 1.6 3.5 +/- 1.8 02/19/16 - 02/26/16 3.8 +/- 1.9 3.1 +/- 1.8 03/03/16 - 03/25/16 4.4 +/- 1.8 4.9 +/- 2.0 04/01/16 - 04/29/16 4.7 +/- 1.7 3.9 +/- 1.6 05/05/16 - 05/26/16 4.4 +/- 1.8 5.9 +/- 1.9 06/03/16 - 06/30/16 3.1 +/- 1.6 3.1 +/- 1.6 07/07/16 - 07/28/16 3.8 +/- 1.6 4.2 +/- 1.7 08/04/16 - 08/25/16 2.6 +/- 1.5 4.4 +/- 1.6 09/01/16 - 09/29/16 4.5 +/- 1.8 4.6 +/- 1.7 10/07/16 - 10/27/16 5.0 +/- 1.9 4.8 +/- 1.9 11/03/16 - 11/24/16 4.2 +/- 2.1 4.4 +/- 2.1 12/01/16 - 12/08/16 4.9 +/- 2.0 4.4 +/- 1.9 MEAN +/- 2 STD DEV 4.0 +/- 1.6 4.3 +/- 1.6 Table C-I.2 CONCENTRATIONS OF TRITIUM, IRON, AND NICKEL IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD H-3 FE-55 NI-63 Q-33 01/07/16 - 03/25/16 < 170 < 197 < 4.1 04/01/16 - 06/30/16 < 188 < 109 < 3.7 07/07/16 - 09/29/16 < 191 < 105 < 3.5 10/07/16 - 12/08/16 < 198 < 129 < 4.3 MEAN - - -

Q-34 01/29/16 - 03/25/16 < 177 < 135 < 4.1 04/01/16 - 06/30/16 < 184 < 99 < 3.6 07/07/16 - 09/29/16 < 187 < 118 < 3.5 10/07/16 - 12/08/16 < 198 < 188 < 3.7 MEAN - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-1

Table C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Q-33 01/07/16 - 01/29/16 < 6 < 5 < 10 < 8 < 9 < 6 < 12 < 15 < 5 < 6 < 33 < 10 02/19/16 - 02/26/16 < 5 < 5 < 10 < 4 < 10 < 5 < 9 < 8 < 4 < 5 < 25 < 7 03/03/16 - 03/25/16 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 6 < 1 < 1 < 11 < 3 04/01/16 - 04/29/16 < 4 < 5 < 10 < 3 < 6 < 5 < 8 < 12 < 4 < 4 < 25 < 9 05/05/16 - 05/26/16 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 14 < 2 < 2 < 22 < 6 06/03/16 - 06/30/16 < 6 < 7 < 14 < 5 < 12 < 7 < 12 < 13 < 6 < 6 < 37 < 15 07/07/16 - 07/28/16 < 1 < 1 < 4 < 1 < 3 < 2 < 3 < 12 < 1 < 1 < 19 < 6 08/04/16 - 08/25/16 < 2 < 3 < 5 < 2 < 4 < 2 < 4 < 14 < 2 < 2 < 25 < 8 09/01/16 - 09/29/16 < 5 < 4 < 10 < 5 < 7 < 5 < 9 < 15 < 4 < 5 < 31 < 11 10/07/16 - 10/27/16 < 3 < 3 < 8 < 3 < 5 < 3 < 5 < 15 < 3 < 3 < 26 < 9 11/03/16 - 11/24/16 < 2 < 3 < 7 < 3 < 5 < 3 < 5 < 13 < 3 < 3 < 23 < 6 12/01/16 - 12/08/16 < 1 < 1 < 2 < 1 < 1 < 1 < 2 < 20 < 1 < 1 < 17 < 6 MEAN - - - - - - - - - - - -

C-2 Q-34 01/29/16 - 01/29/16 < 7 < 7 < 15 < 6 < 11 < 7 < 12 < 13 < 5 < 6 < 32 < 12 02/19/16 - 02/26/16 < 5 < 4 < 9 < 5 < 10 < 5 < 8 < 9 < 5 < 5 < 26 < 7 03/03/16 - 03/25/16 < 1 < 2 < 4 < 1 < 3 < 2 < 3 < 6 < 1 < 2 < 12 < 4 04/01/16 - 04/29/16 < 5 < 5 < 11 < 5 < 9 < 5 < 9 < 13 < 5 < 5 < 31 < 10 05/05/16 - 05/26/16 < 2 < 3 < 6 < 2 < 5 < 3 < 5 < 14 < 2 < 2 < 24 < 8 06/03/16 - 06/30/16 < 7 < 7 < 12 < 7 < 14 < 6 < 12 < 15 < 6 < 6 < 31 < 12 07/07/16 - 07/28/16 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 15 < 1 < 2 < 22 < 7 08/04/16 - 08/25/16 < 1 < 2 < 4 < 1 < 3 < 2 < 3 < 14 < 1 < 1 < 20 < 5 09/01/16 - 09/29/16 < 5 < 6 < 12 < 6 < 10 < 6 < 10 < 15 < 4 < 5 < 34 < 10 10/07/16 - 10/27/16 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 11 < 2 < 2 < 20 < 7 11/03/16 - 11/24/16 < 2 < 2 < 6 < 2 < 5 < 3 < 4 < 10 < 2 < 2 < 20 < 6 12/01/16 - 12/08/16 < 1 < 1 < 2 < 1 < 1 < 1 < 2 < 21 < 1 < 1 < 23 < 6 MEAN - - - - - - - - - - - -

Table C-II.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD Q-35 Q-36 01/07/16 - 01/07/16 < 191 < 191 04/07/16 - 04/07/16 < 169 < 173 07/07/16 - 07/07/16 < 165 < 164 10/14/16 - 10/14/16 < 198 < 192 MEAN - -

C-3

Table C-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Q-35 01/07/16 - 01/07/16 < 5 < 5 < 11 < 2 < 6 < 7 < 9 < 15 < 4 < 5 < 30 < 8 04/07/16 - 04/07/16 < 4 < 6 < 12 < 6 < 14 < 7 < 12 < 15 < 5 < 6 < 34 < 9 07/07/16 - 07/07/16 < 7 < 6 < 14 < 5 < 11 < 8 < 10 < 13 < 5 < 6 < 38 < 13 10/14/16 - 10/14/16 < 3 < 2 < 5 < 2 < 5 < 3 < 5 < 4 < 2 < 3 < 12 < 4 MEAN - - - - - - - - - - - -

Q-36 01/07/16 - 01/07/16 < 7 < 6 < 13 < 7 < 11 < 6 < 13 < 15 < 6 < 7 < 40 < 10 04/07/16 - 04/07/16 < 5 < 5 < 11 < 4 < 9 < 6 < 8 < 12 < 5 < 4 < 30 < 8 07/07/16 - 07/07/16 < 4 < 5 < 10 < 4 < 10 < 5 < 8 < 15 < 5 < 5 < 34 < 9 10/14/16 - 10/14/16 < 3 < 3 < 6 < 3 < 6 < 3 < 5 < 5 < 3 < 3 < 13 < 4 C-4 MEAN - - - - - - - - - - - -

Table C-III.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 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 Channel Catfish 05/05/16 < 62 < 46 < 86 < 45 < 117 < 46 < 97 < 39 < 44 < 202 < 68 Common Carp 05/05/16 < 78 < 65 < 146 < 68 < 141 < 80 < 120 < 64 < 60 < 339 < 117 Freshwater Drum 10/25/16 < 55 < 39 < 95 < 20 < 80 < 60 < 69 < 49 < 48 < 344 < 87 Shorthead Redhorse 10/25/16 < 43 < 43 < 104 < 40 < 93 < 51 < 106 < 39 < 47 < 286 < 113 MEAN - - - - - - - - - - -

Q-29 Common Carp 05/05/16 < 80 < 75 < 128 < 66 < 134 < 84 < 141 < 73 < 86 < 337 < 147 Largemouth Bass 05/05/16 < 62 < 59 < 108 < 52 < 116 < 62 < 94 < 51 < 67 < 286 < 72 C-5 Freshwater Drum 10/25/16 < 55 < 51 < 128 < 59 < 93 < 59 < 72 < 47 < 60 < 376 < 113 Largemouth Bass 10/25/16 < 51 < 47 < 99 < 46 < 142 < 54 < 101 < 45 < 48 < 320 < 84 MEAN - - - - - - - - - - -

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 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 05/27/16 < 88 < 119 < 222 < 85 < 232 < 137 < 201 < 93 < 107 < 911 < 299 10/18/16 < 81 < 103 < 217 < 88 < 204 < 117 < 174 < 85 < 114 < 683 < 141 MEAN - - - - - - - - - - -

Q-40 05/27/16 < 74 < 66 < 188 < 65 < 150 < 88 < 164 < 53 < 87 < 757 < 173 10/18/16 < 65 < 64 < 151 < 60 < 149 < 76 < 139 < 79 < 77 < 513 < 145 MEAN - - - - - - - - - - -

C-6

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP III PERIOD Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 12/31/15 - 01/08/16 14 +/- 4 16 +/- 4 12 +/- 4 16 +/- 4 29 +/- 5 18 +/- 4 18 +/- 4 17 +/- 4 22 +/- 5 26 +/- 5 01/07/16 - 01/15/16 20 +/- 4 22 +/- 4 25 +/- 5 22 +/- 4 28 +/- 4 23 +/- 4 23 +/- 4 27 +/- 5 25 +/- 4 29 +/- 4 01/15/16 - 01/22/16 21 +/- 4 18 +/- 4 22 +/- 4 21 +/- 4 24 +/- 5 17 +/- 4 22 +/- 4 18 +/- 4 21 +/- 4 17 +/- 4 01/22/16 - 01/29/16 17 +/- 4 15 +/- 4 18 +/- 4 16 +/- 4 21 +/- 4 19 +/- 4 15 +/- 4 15 +/- 4 18 +/- 4 18 +/- 4 01/29/16 - 02/05/16 16 +/- 4 15 +/- 4 21 +/- 5 15 +/- 4 19 +/- 5 12 +/- 4 19 +/- 4 21 +/- 5 15 +/- 5 16 +/- 5 02/04/16 - 02/12/16 15 +/- 4 17 +/- 4 22 +/- 4 20 +/- 4 21 +/- 4 16 +/- 4 23 +/- 4 14 +/- 4 19 +/- 4 21 +/- 4 02/11/16 - 02/19/16 10 +/- 4 18 +/- 4 15 +/- 4 19 +/- 4 16 +/- 4 14 +/- 4 9 +/- 4 11 +/- 4 14 +/- 4 18 +/- 4 02/19/16 - 02/26/16 10 +/- 4 15 +/- 4 16 +/- 4 14 +/- 4 14 +/- 4 12 +/- 4 10 +/- 3 11 +/- 4 14 +/- 4 13 +/- 4 02/26/16 - 03/04/16 12 +/- 4 15 +/- 4 16 +/- 4 16 +/- 4 20 +/- 5 17 +/- 4 12 +/- 3 15 +/- 4 19 +/- 4 19 +/- 4 03/03/16 - 03/11/16 14 +/- 4 15 +/- 4 17 +/- 4 18 +/- 4 14 +/- 4 14 +/- 4 16 +/- 4 14 +/- 4 17 +/- 4 15 +/- 4 03/10/16 - 03/18/16 10 +/- 3 12 +/- 3 11 +/- 3 12 +/- 3 13 +/- 4 13 +/- 3 14 +/- 4 11 +/- 3 20 +/- 4 17 +/- 4 03/17/16 - 03/25/16 (1) 8 +/- 4 11 +/- 4 11 +/- 4 6 +/- 3 9 +/- 3 9 +/- 4 9 +/- 4 10 +/- 3 10 +/- 3 03/25/16 - 04/01/16 10 +/- 5 11 +/- 4 8 +/- 3 8 +/- 3 11 +/- 4 9 +/- 3 8 +/- 3 11 +/- 4 12 +/- 4 10 +/- 4 04/01/16 - 04/08/16 13 +/- 4 16 +/- 4 12 +/- 4 15 +/- 4 15 +/- 4 14 +/- 4 14 +/- 4 17 +/- 4 14 +/- 4 17 +/- 5 04/07/16 - 04/15/16 12 +/- 4 11 +/- 4 13 +/- 4 14 +/- 4 13 +/- 4 11 +/- 3 9 +/- 4 10 +/- 4 12 +/- 3 12 +/- 4 04/15/16 - 04/22/16 16 +/- 4 23 +/- 4 20 +/- 4 18 +/- 4 18 +/- 4 18 +/- 4 15 +/- 4 17 +/- 4 18 +/- 4 20 +/- 4 04/22/16 - 04/29/16 14 +/- 4 14 +/- 4 14 +/- 4 13 +/- 4 10 +/- 3 13 +/- 4 13 +/- 4 12 +/- 4 14 +/- 4 13 +/- 4 04/29/16 - 05/06/16 9 +/- 4 7 +/- 4 11 +/- 4 9 +/- 4 8 +/- 4 10 +/- 4 9 +/- 4 9 +/- 4 7 +/- 4 9 +/- 4 05/05/16 - 05/13/16 13 +/- 4 11 +/- 4 15 +/- 4 13 +/- 4 12 +/- 4 11 +/- 4 12 +/- 4 14 +/- 4 15 +/- 4 12 +/- 4 05/12/16 - 05/20/16 14 +/- 4 18 +/- 4 11 +/- 4 11 +/- 4 13 +/- 4 14 +/- 4 14 +/- 4 15 +/- 4 12 +/- 4 16 +/- 4 05/19/16 - 05/27/16 21 +/- 5 20 +/- 4 12 +/- 4 18 +/- 4 20 +/- 4 19 +/- 4 17 +/- 4 20 +/- 4 18 +/- 4 18 +/- 4 05/26/16 - 06/03/16 12 +/- 4 14 +/- 4 11 +/- 4 13 +/- 4 11 +/- 3 12 +/- 3 11 +/- 4 12 +/- 4 12 +/- 3 11 +/- 3 06/03/16 - 06/10/16 13 +/- 4 14 +/- 4 12 +/- 4 14 +/- 4 11 +/- 4 11 +/- 4 10 +/- 3 12 +/- 3 12 +/- 4 12 +/- 4 06/09/16 - 06/17/16 18 +/- 4 13 +/- 4 16 +/- 4 14 +/- 4 18 +/- 4 17 +/- 4 16 +/- 4 16 +/- 4 16 +/- 4 19 +/- 4 06/17/16 - 06/24/16 16 +/- 4 17 +/- 4 13 +/- 4 12 +/- 4 15 +/- 4 7 +/- 3 12 +/- 4 16 +/- 4 14 +/- 3 16 +/- 4 06/24/16 - 07/02/16 13 +/- 3 10 +/- 3 11 +/- 3 14 +/- 3 15 +/- 4 13 +/- 4 13 +/- 3 10 +/- 3 12 +/- 4 12 +/- 4 06/30/16 - 07/08/16 8 +/- 4 12 +/- 4 13 +/- 5 7 +/- 4 10 +/- 4 13 +/- 4 11 +/- 4 11 +/- 4 10 +/- 4 9 +/- 4 07/07/16 - 07/15/16 13 +/- 4 12 +/- 4 15 +/- 4 15 +/- 4 18 +/- 4 14 +/- 4 14 +/- 4 15 +/- 4 13 +/- 4 13 +/- 4 07/14/16 - 07/22/16 14 +/- 4 17 +/- 4 16 +/- 4 13 +/- 4 14 +/- 4 17 +/- 4 16 +/- 4 13 +/- 4 16 +/- 4 12 +/- 4 07/22/16 - 07/30/16 17 +/- 4 16 +/- 4 16 +/- 4 16 +/- 4 19 +/- 5 19 +/- 5 16 +/- 4 11 +/- 4 17 +/- 5 14 +/- 5 07/28/16 - 08/05/16 18 +/- 4 15 +/- 4 22 +/- 5 19 +/- 4 21 +/- 4 19 +/- 4 19 +/- 4 22 +/- 5 26 +/- 4 18 +/- 4 08/04/16 - 08/12/16 17 +/- 4 19 +/- 4 22 +/- 5 18 +/- 4 19 +/- 4 21 +/- 4 16 +/- 4 19 +/- 4 20 +/- 4 21 +/- 4 08/12/16 - 08/19/16 20 +/- 4 19 +/- 4 22 +/- 4 18 +/- 4 20 +/- 5 22 +/- 5 19 +/- 4 19 +/- 4 19 +/- 5 22 +/- 5 08/18/16 - 08/26/16 12 +/- 4 14 +/- 4 10 +/- 4 10 +/- 4 14 +/- 4 14 +/- 4 12 +/- 4 9 +/- 4 13 +/- 4 14 +/- 4 08/25/16 - 09/02/16 16 +/- 4 13 +/- 3 18 +/- 4 11 +/- 3 16 +/- 4 14 +/- 3 13 +/- 3 15 +/- 4 15 +/- 4 16 +/- 4 09/01/16 - 09/09/16 (1) (1) (1) (1) 15 +/- 4 14 +/- 4 (1) (1) 14 +/- 4 12 +/- 4 09/08/16 - 09/16/16 18 +/- 4 15 +/- 4 16 +/- 4 11 +/- 4 12 +/- 4 21 +/- 4 16 +/- 4 16 +/- 4 13 +/- 4 18 +/- 4 09/15/16 - 09/23/16 21 +/- 4 21 +/- 4 24 +/- 5 20 +/- 4 20 +/- 4 23 +/- 4 18 +/- 4 23 +/- 4 21 +/- 4 21 +/- 4 09/22/16 - 10/01/16 14 +/- 4 7 +/- 3 14 +/- 4 14 +/- 4 20 +/- 4 18 +/- 4 15 +/- 4 12 +/- 3 19 +/- 4 20 +/- 4 09/29/16 - 10/07/16 13 +/- 4 15 +/- 4 16 +/- 5 17 +/- 5 13 +/- 3 15 +/- 4 16 +/- 4 13 +/- 4 13 +/- 3 14 +/- 4 10/07/16 - 10/16/16 19 +/- 4 20 +/- 4 17 +/- 4 17 +/- 4 19 +/- 5 18 +/- 5 17 +/- 4 17 +/- 4 20 +/- 5 16 +/- 5 10/13/16 - 10/21/16 13 +/- 5 17 +/- 5 15 +/- 5 13 +/- 5 16 +/- 4 21 +/- 4 15 +/- 5 17 +/- 5 14 +/- 4 16 +/- 4 10/20/16 - 10/28/16 16 +/- 4 16 +/- 4 9 +/- 4 13 +/- 4 14 +/- 4 15 +/- 4 16 +/- 4 18 +/- 4 14 +/- 4 14 +/- 4 10/27/16 - 11/04/16 30 +/- 5 27 +/- 5 30 +/- 5 33 +/- 5 27 +/- 5 27 +/- 5 42 +/- 7 43 +/- 7 29 +/- 5 32 +/- 5 11/03/16 - 11/12/16 20 +/- 4 19 +/- 4 23 +/- 4 24 +/- 4 20 +/- 5 22 +/- 5 23 +/- 4 26 +/- 4 25 +/- 5 26 +/- 5 11/10/16 - 11/19/16 44 +/- 6 47 +/- 6 36 +/- 5 39 +/- 6 32 +/- 5 37 +/- 5 42 +/- 6 44 +/- 6 33 +/- 5 36 +/- 5 11/17/16 - 11/25/16 8 +/- 4 10 +/- 4 10 +/- 4 10 +/- 4 15 +/- 4 14 +/- 4 8 +/- 4 10 +/- 4 15 +/- 4 16 +/- 4 11/24/16 - 12/02/16 26 +/- 4 22 +/- 4 20 +/- 4 27 +/- 5 21 +/- 4 24 +/- 4 21 +/- 4 26 +/- 4 23 +/- 4 24 +/- 4 12/01/16 - 12/09/16 15 +/- 4 14 +/- 4 13 +/- 4 16 +/- 4 14 +/- 4 12 +/- 4 11 +/- 4 19 +/- 4 13 +/- 4 14 +/- 4 12/08/16 - 12/16/16 19 +/- 4 22 +/- 4 25 +/- 5 23 +/- 5 15 +/- 4 19 +/- 4 21 +/- 4 27 +/- 5 21 +/- 4 22 +/- 5 12/15/16 - 12/23/16 28 +/- 5 30 +/- 5 29 +/- 5 27 +/- 5 27 +/- 4 21 +/- 4 29 +/- 5 30 +/- 5 27 +/- 4 27 +/- 5 12/22/16 - 12/30/16 24 +/- 4 22 +/- 4 19 +/- 4 26 +/- 5 20 +/- 4 19 +/- 4 18 +/- 4 25 +/- 4 17 +/- 4 21 +/- 4 MEAN +/- 2 STD DEV 16 +/- 12 17 +/- 13 17 +/- 12 16 +/- 12 17 +/- 11 16 +/- 10 16 +/- 14 17 +/- 15 17 +/- 10 17 +/- 11 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-7

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, 2016 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - NEAR-SITE LOCATIONS GROUP II - FAR-FIELD LOCATIONS GROUP III - CONTROL LOCATION COLLECTION MIN MAX MEAN COLLECTION MIN MAX MEAN COLLECTION MIN MAX MEAN PERIOD +/- 2SD PERIOD +/- 2SD PERIOD +/- 2SD 01/01/16 - 01/29/16 12 25 18 +/- 7 12/31/15 - 01/29/16 15 29 21 +/- 9 12/31/15 - 01/29/16 17 29 22 +/- 12 01/29/16 - 03/04/16 10 22 16 +/- 6 01/29/16 - 03/04/16 9 23 15 +/- 7 01/29/16 - 03/03/16 13 21 17 +/- 6 03/04/16 - 04/01/16 8 18 12 +/- 6 03/03/16 - 04/01/16 6 20 12 +/- 7 03/03/16 - 04/01/16 10 17 13 +/- 7 04/01/16 - 04/29/16 11 23 15 +/- 6 04/01/16 - 04/29/16 9 18 14 +/- 5 04/01/16 - 04/29/16 12 20 15 +/- 7 04/29/16 - 06/03/16 7 21 13 +/- 7 04/29/16 - 06/03/16 7 20 13 +/- 7 04/29/16 - 06/03/16 9 18 13 +/- 8 06/03/16 - 07/02/16 10 18 14 +/- 4 06/03/16 - 07/02/16 7 18 13 +/- 6 06/03/16 - 06/30/16 12 19 15 +/- 6 07/02/16 - 07/30/16 7 17 14 +/- 6 06/30/16 - 07/30/16 10 19 14 +/- 6 06/30/16 - 07/28/16 9 14 12 +/- 4 07/30/16 - 09/02/16 10 22 17 +/- 8 07/28/16 - 09/02/16 9 26 17 +/- 8 07/28/16 - 09/01/16 14 22 18 +/- 7 09/09/16 - 10/01/16 7 24 16 +/- 10 09/01/16 - 10/01/16 12 23 17 +/- 7 09/01/16 - 09/29/16 12 21 17 +/- 8 10/01/16 - 11/04/16 9 33 18 +/- 13 09/29/16 - 11/04/16 13 43 19 +/- 16 09/29/16 - 11/03/16 14 32 19 +/- 15 11/04/16 - 12/02/16 8 47 24 +/- 24 11/03/16 - 12/02/16 8 44 24 +/- 19 11/03/16 - 12/01/16 16 36 25 +/- 17 12/02/16 - 12/30/16 13 30 22 +/- 11 12/01/16 - 12/30/16 11 30 20 +/- 11 12/01/16 - 12/29/16 14 27 21 +/- 10 C-8 01/01/16 - 12/30/16 7 47 16 +/- 12 12/31/15 - 12/30/16 6 44 17 +/- 12 12/31/15 - 12/29/16 9 36 17 +/- 11

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-01 01/01/16 - 04/01/16 < 2 < 3 < 8 < 2 < 5 < 3 < 5 < 2 < 2 < 81 < 36 04/01/16 - 07/02/16 < 3 < 3 < 9 < 3 < 5 < 4 < 7 < 3 < 3 < 47 < 17 07/02/16 - 10/01/16 < 2 < 2 < 6 < 2 < 3 < 2 < 4 < 2 < 2 < 11 < 4 10/01/16 - 12/30/16 < 3 < 3 < 7 < 2 < 7 < 3 < 6 < 3 < 4 < 18 < 7 MEAN - - - - - - - - - - -

Q-02 01/01/16 - 04/01/16 < 2 < 3 < 8 < 2 < 7 < 4 < 6 < 3 < 3 < 55 < 20 04/01/16 - 07/02/16 < 2 < 3 < 7 < 2 < 4 < 2 < 4 < 2 < 1 < 28 < 8 07/02/16 - 10/01/16 < 2 < 3 < 5 < 2 < 5 < 2 < 4 < 3 < 3 < 12 < 4 10/01/16 - 12/30/16 < 2 < 2 < 6 < 3 < 5 < 2 < 5 < 2 < 2 < 16 < 4 MEAN - - - - - - - - - - -

C-9 Q-03 01/01/16 - 04/01/16 < 4 < 6 < 13 < 4 < 10 < 5 < 9 < 4 < 4 < 89 < 36 04/01/16 - 07/02/16 < 2 < 3 < 8 < 3 < 5 < 3 < 5 < 2 < 2 < 49 < 12 07/02/16 - 10/01/16 < 2 < 3 < 5 < 3 < 6 < 2 < 4 < 3 < 2 < 14 < 5 10/01/16 - 12/30/16 < 3 < 2 < 6 < 4 < 6 < 2 < 3 < 2 < 2 < 12 < 1 MEAN - - - - - - - - - - -

Q-04 01/01/16 - 04/01/16 < 3 < 3 < 6 < 2 < 7 < 4 < 6 < 3 < 2 < 65 < 18 04/01/16 - 07/02/16 < 2 < 2 < 6 < 3 < 6 < 3 < 6 < 2 < 2 < 42 < 15 07/02/16 - 10/01/16 < 4 < 4 < 9 < 3 < 8 < 4 < 9 < 4 < 5 < 21 < 10 10/01/16 - 12/30/16 < 3 < 4 < 7 < 3 < 8 < 4 < 7 < 4 < 3 < 17 < 8 MEAN - - - - - - - - - - -

Q-13 12/31/15 - 04/01/16 < 2 < 3 < 8 < 2 < 7 < 3 < 7 < 3 < 2 < 52 < 22 04/01/16 - 06/30/16 < 3 < 5 < 9 < 3 < 8 < 4 < 8 < 3 < 3 < 65 < 22 06/30/16 - 09/29/16 < 2 < 3 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 12 < 5 09/29/16 - 12/29/16 < 2 < 2 < 2 < 2 < 5 < 2 < 3 < 2 < 2 < 14 < 5 MEAN - - - - - - - - - - -

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-16 12/31/15 - 04/01/16 < 3 < 5 < 12 < 4 < 10 < 4 < 8 < 4 < 4 < 77 < 32 04/01/16 - 06/30/16 < 3 < 3 < 6 < 1 < 7 < 3 < 6 < 2 < 3 < 55 < 21 06/30/16 - 09/29/16 < 2 < 3 < 5 < 2 < 5 < 3 < 4 < 2 < 2 < 14 < 7 09/29/16 - 12/29/16 < 3 < 3 < 4 < 2 < 6 < 2 < 4 < 2 < 3 < 14 < 4 MEAN - - - - - - - - - - -

Q-37 01/01/16 - 04/01/16 < 3 < 3 < 7 < 2 < 4 < 3 < 5 < 2 < 2 < 54 < 22 04/01/16 - 07/02/16 < 3 < 4 < 8 < 3 < 11 < 5 < 10 < 3 < 3 < 75 < 21 07/02/16 - 10/01/16 < 2 < 2 < 5 < 2 < 5 < 3 < 4 < 2 < 2 < 12 < 3 10/01/16 - 12/30/16 < 3 < 3 < 7 < 3 < 6 < 2 < 4 < 2 < 3 < 12 < 6 MEAN - - - - - - - - - - -

C-10 Q-38 01/01/16 - 04/01/16 < 1 < 2 < 4 < 1 < 3 < 2 < 2 < 1 < 1 < 32 < 6 04/01/16 - 07/02/16 < 3 < 4 < 8 < 3 < 7 < 3 < 6 < 3 < 3 < 55 < 18 07/02/16 - 10/01/16 < 3 < 2 < 5 < 3 < 6 < 2 < 6 < 2 < 3 < 14 < 6 10/01/16 - 12/30/16 < 3 < 2 < 6 < 3 < 7 < 2 < 4 < 3 < 3 < 13 < 4 MEAN - - - - - - - - - - -

Q-41 12/31/15 - 04/01/16 < 2 < 3 < 9 < 4 < 7 < 3 < 6 < 2 < 2 < 54 < 20 04/01/16 - 06/30/16 < 2 < 2 < 7 < 2 < 5 < 2 < 4 < 2 < 2 < 31 < 19 06/30/16 - 09/29/16 < 2 < 2 < 4 < 2 < 5 < 2 < 4 < 3 < 2 < 13 < 5 09/29/16 - 12/29/16 < 2 < 3 < 6 < 2 < 7 < 3 < 5 < 3 < 2 < 16 < 7 MEAN - - - - - - - - - - -

Q-42 12/31/15 - 04/01/16 < 3 < 4 < 7 < 4 < 6 < 3 < 7 < 3 < 2 < 70 < 22 04/01/16 - 06/30/16 < 3 < 2 < 9 < 2 < 6 < 3 < 5 < 2 < 2 < 49 < 17 06/30/16 - 09/29/16 < 4 < 4 < 7 < 3 < 9 < 4 < 6 < 3 < 4 < 15 < 9 09/29/16 - 12/29/16 < 3 < 3 < 6 < 1 < 8 < 3 < 5 < 3 < 3 < 16 < 7 MEAN - - - - - - - - - - -

Table C-VI-.1 CONCENTRATIONS OF I-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP III PERIOD Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 12/31/15 - 01/08/16 < 20 < 49 < 49 < 49 < 53 < 20 < 47 < 47 < 49 < 50 01/07/16 - 01/15/16 < 24 < 59 < 59 < 59 < 52 < 63 < 69 < 69 < 63 < 27 01/15/16 - 01/22/16 < 22 < 54 < 54 < 54 < 59 < 59 < 24 < 57 < 59 < 62 01/22/16 - 01/29/16 < 16 < 39 < 39 < 39 < 41 < 28 < 66 < 66 < 67 < 69 01/29/16 - 02/05/16 < 24 < 42 < 42 < 42 < 51 < 21 < 43 < 43 < 51 < 51 02/04/16 - 02/12/16 < 62 < 27 < 60 < 60 < 67 < 29 < 53 < 53 < 56 < 58 02/11/16 - 02/19/16 < 43 < 42 < 42 < 16 < 37 < 23 < 65 < 65 < 56 < 58 02/19/16 - 02/26/16 < 6 < 16 < 16 < 16 < 17 < 18 < 17 < 7 < 18 < 19 02/26/16 - 03/04/16 < 54 < 52 < 52 < 20 < 64 < 64 < 24 < 57 < 67 < 69 03/03/16 - 03/11/16 < 20 < 52 < 52 < 52 < 57 < 22 < 49 < 49 < 52 < 53 03/10/16 - 03/18/16 < 22 < 9 < 22 < 22 < 23 < 10 < 23 < 23 < 24 < 26 03/17/16 - 03/25/16 (1) < 41 < 41 < 41 < 21 < 21 < 25 < 28 < 24 < 25 03/25/16 - 04/01/16 < 53 < 8 < 15 < 14 < 15 < 33 < 59 < 59 < 60 < 63 04/01/16 - 04/08/16 < 12 < 31 < 32 < 31 < 37 < 43 < 36 < 36 < 18 < 44 04/07/16 - 04/15/16 < 66 < 66 < 68 < 66 < 44 < 22 < 52 < 52 < 19 < 46 04/15/16 - 04/22/16 < 22 < 56 < 58 < 56 < 21 < 50 < 56 < 51 < 55 < 56 04/22/16 - 04/29/16 < 26 < 66 < 68 < 66 < 65 < 28 < 69 < 69 < 67 < 70 04/29/16 - 05/06/16 < 34 < 34 < 14 < 34 < 43 < 22 < 42 < 42 < 53 < 54 05/05/16 - 05/13/16 < 61 < 61 < 25 < 61 < 65 < 69 < 65 < 65 < 69 < 30 05/12/16 - 05/20/16 < 18 < 42 < 44 < 42 < 45 < 25 < 56 < 56 < 60 < 62 05/19/16 - 05/27/16 < 30 < 54 < 55 < 54 < 60 < 55 < 27 < 50 < 54 < 57 05/26/16 - 06/03/16 < 11 < 28 < 29 < 28 < 23 < 12 < 36 < 37 < 29 < 30 06/03/16 - 06/10/16 < 23 < 52 < 54 < 52 < 69 < 61 < 47 < 16 < 60 < 63 06/09/16 - 06/17/16 < 26 < 67 < 69 < 69 < 63 < 64 < 29 < 68 < 64 < 67 06/17/16 - 06/24/16 < 32 < 58 < 60 < 59 < 51 < 57 < 64 < 64 < 57 < 59 06/24/16 - 07/02/16 < 42 < 18 < 44 < 44 < 65 < 58 < 39 < 39 < 22 < 61 06/30/16 - 07/08/16 < 65 < 65 < 68 < 68 < 26 < 25 < 60 < 63 < 56 < 58 07/07/16 - 07/15/16 < 64 < 64 < 67 < 67 < 67 < 67 < 65 < 64 < 65 < 68 07/14/16 - 07/22/16 < 56 < 56 < 58 < 58 < 22 < 22 < 61 < 61 < 56 < 58 07/22/16 - 07/30/16 < 7 < 17 < 18 < 18 < 25 < 29 < 19 < 10 < 29 < 30 07/28/16 - 08/05/16 < 62 < 62 < 64 < 27 < 59 < 21 < 63 < 63 < 60 < 62 08/04/16 - 08/12/16 < 16 < 38 < 39 < 39 < 33 < 27 < 27 < 31 < 27 < 28 08/12/16 - 08/19/16 < 45 < 19 < 46 < 46 < 55 < 45 < 36 < 36 < 45 < 18 08/18/16 - 08/26/16 < 20 < 52 < 54 < 54 < 57 < 24 < 57 < 57 < 62 < 65 08/25/16 - 09/02/16 < 65 < 65 < 67 < 67 < 29 < 58 < 55 < 55 < 22 < 60 09/01/16 - 09/09/16 < 26 < 62 < 64 < 64 (1) (1) < 58 < 23 < 62 < 65 09/08/16 - 09/16/16 < 61 < 61 < 63 < 63 < 66 < 25 < 62 < 62 < 28 < 68 09/15/16 - 09/23/16 < 56 < 24 < 58 < 58 < 61 < 23 < 55 < 55 < 60 < 62 09/22/16 - 10/01/16 < 18 < 33 < 34 < 34 < 42 < 31 < 45 < 45 < 57 < 59 09/29/16 - 10/07/16 < 22 < 52 < 54 < 54 < 39 < 33 < 24 < 44 < 33 < 34 10/07/16 - 10/16/16 < 34 < 34 < 35 < 35 < 23 < 65 < 33 < 33 < 66 < 30 10/13/16 - 10/21/16 < 22 < 62 < 64 < 64 < 49 < 25 < 62 < 62 < 49 < 51 10/20/16 - 10/28/16 < 22 < 57 < 59 < 59 < 65 < 27 < 54 < 54 < 60 < 63 10/27/16 - 11/04/16 < 17 < 41 < 42 < 42 < 43 < 15 < 46 < 46 < 38 < 39 11/03/16 - 11/12/16 < 48 < 49 < 50 < 21 < 63 < 49 < 38 < 38 < 49 < 20 11/10/16 - 11/19/16 < 9 < 23 < 23 < 23 < 26 < 29 < 25 < 25 < 29 < 13 11/17/16 - 11/25/16 < 25 < 61 < 63 < 63 < 59 < 54 < 56 < 55 < 21 < 56 11/24/16 - 12/02/16 < 47 < 47 < 21 < 49 < 51 < 51 < 48 < 48 < 51 < 21 12/01/16 - 12/09/16 < 23 < 42 < 44 < 44 < 45 < 22 < 48 < 48 < 51 < 53 12/08/16 - 12/16/16 < 45 < 45 < 20 < 47 < 49 < 65 < 60 < 60 < 64 < 26 12/15/16 - 12/23/16 < 53 < 53 < 55 < 28 < 57 < 48 < 45 < 45 < 48 < 27 12/22/16 - 12/30/16 < 26 < 61 < 63 < 63 < 68 < 43 < 40 < 40 < 43 < 17 MEAN - - - - - - - - - -

(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-11

Table C-VII.1 CONCENTRATIONS OF I-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION INDICATOR FARM PERIOD Q-26 01/01/16 < 0.9 02/05/16 < 0.4 03/04/16 < 0.4 04/01/16 < 0.9 05/06/16 < 0.7 05/20/16 < 1.0 06/03/16 < 0.9 06/17/16 < 1.0 07/02/16 < 0.4 07/15/16 < 0.9 07/30/16 < 0.5 08/12/16 < 0.6 08/26/16 < 0.7 09/09/16 < 0.8 09/23/16 < 0.5 10/07/16 < 0.7 10/21/16 < 0.7 11/04/16 < 0.7 12/02/16 < 0.9 MEAN -

C-12

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-26 01/01/16 < 5 < 4 < 13 < 5 < 12 < 5 < 8 < 4 < 5 < 26 < 8 02/05/16 < 6 < 8 < 21 < 7 < 20 < 8 < 14 < 7 < 8 < 41 < 14 03/04/16 < 7 < 8 < 16 < 7 < 17 < 8 < 11 < 7 < 7 < 41 < 12 04/01/16 < 7 < 6 < 14 < 5 < 18 < 7 < 11 < 6 < 5 < 28 < 5 05/06/16 < 8 < 8 < 19 < 7 < 20 < 8 < 17 < 8 < 9 < 50 < 15 05/20/16 < 4 < 5 < 12 < 5 < 10 < 5 < 7 < 4 < 5 < 30 < 8 06/03/16 < 5 < 4 < 12 < 6 < 13 < 5 < 9 < 5 < 6 < 32 < 8 06/17/16 < 7 < 9 < 19 < 7 < 18 < 7 < 12 < 7 < 8 < 42 < 11 07/02/16 < 9 < 8 < 23 < 9 < 20 < 10 < 17 < 7 < 9 < 49 < 13 07/15/16 < 8 < 8 < 14 < 8 < 18 < 8 < 15 < 9 < 7 < 32 < 13 07/30/16 < 7 < 7 < 13 < 6 < 15 < 6 < 11 < 6 < 6 < 47 < 14 08/12/16 < 8 < 9 < 16 < 7 < 19 < 8 < 17 < 8 < 9 < 43 < 7 C-13 08/26/16 < 8 < 9 < 19 < 7 < 17 < 9 < 14 < 10 < 7 < 51 < 12 09/09/16 < 7 < 9 < 18 < 9 < 14 < 7 < 13 < 7 < 7 < 39 < 15 09/23/16 < 5 < 5 < 12 < 6 < 11 < 5 < 9 < 5 < 5 < 28 < 8 10/07/16 < 10 < 8 < 22 < 10 < 20 < 11 < 15 < 12 < 12 < 49 < 8 10/21/16 < 4 < 4 < 11 < 5 < 10 < 6 < 9 < 4 < 5 < 30 < 9 11/04/16 < 6 < 7 < 14 < 7 < 15 < 8 < 12 < 6 < 7 < 39 < 13 12/02/16 < 7 < 9 < 22 < 6 < 21 < 8 < 14 < 8 < 9 < 42 < 12 MEAN - - - - - - - - - - -

Table C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 Q-CONTROL Lettuce 07/12/16 < 19 < 19 < 53 < 18 < 66 < 24 < 46 < 38 < 19 < 29 < 119 < 25 Onion 07/12/16 < 39 < 22 < 78 < 31 < 79 < 33 < 54 < 51 < 32 < 33 < 158 < 61 Potatoes 07/12/16 < 14 < 14 < 31 < 16 < 39 < 12 < 19 < 19 < 13 < 15 < 74 < 19 MEAN - - - - - - - - - - - -

Q-QUAD 1 Lettuce 07/13/16 < 42 < 31 < 64 < 26 < 71 < 36 < 59 < 51 < 35 < 43 < 142 < 47 Potatoes 07/13/16 < 20 < 20 < 43 < 18 < 49 < 17 < 35 < 27 < 16 < 19 < 81 < 27 MEAN - - - - - - - - - - - -

C-14 Q-QUAD 2 Carrots 07/12/16 < 45 < 42 < 91 < 52 < 89 < 41 < 84 < 57 < 38 < 43 < 194 < 49 Watermelon leaves 07/12/16 < 22 < 20 < 34 < 28 < 48 < 25 < 40 < 51 < 22 < 27 < 153 < 38 Zucchini leaves 07/12/16 < 34 < 32 < 80 < 31 < 55 < 33 < 49 < 53 < 26 < 33 < 140 < 35 MEAN - - - - - - - - - - - -

Q-QUAD 3 Broccoli 07/12/16 < 29 < 26 < 57 < 33 < 47 < 21 < 36 < 48 < 24 < 24 < 135 < 37 Horseradish 07/12/16 < 28 < 25 < 70 < 36 < 75 < 30 < 58 < 52 < 31 < 28 < 137 < 35 Sun Chokes 07/12/16 < 31 < 31 < 79 < 38 < 58 < 23 < 65 < 47 < 30 < 37 < 114 < 43 MEAN - - - - - - - - - - - -

Q-QUAD 4 Potatoes 07/13/16 < 28 < 30 < 65 < 35 < 66 < 32 < 58 < 54 < 28 < 36 < 142 < 33 Rhubarb leaves 07/13/16 < 26 < 24 < 61 < 25 < 62 < 24 < 49 < 43 < 27 < 25 < 131 < 23 MEAN - - - - - - - - - - - -

Table C-IX.1 QUARTERLY OSLD RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN CODE +/- 2 S.D. JAN - MAR APR - JUN JUL - SEP OCT - DEC Q-01-1 22.4 +/- 4.7 20.4 20.4 24.9 24.0 Q-01-2 22.4 +/- 5.5 19.6 20.4 24.6 24.8 Q-02-1 23.6 +/- 6.6 20.1 24.2 22.2 27.8 Q-02-2 22.8 +/- 4.3 21.0 21.0 23.6 25.4 Q-03-1 22.3 +/- 7.2 19.2 19.1 25.6 25.2 Q-03-2 21.8 +/- 4.2 19.7 20.2 23.9 23.2 Q-04-1 24.1 +/- 5.6 21.4 21.9 26.8 26.1 Q-04-2 24.0 +/- 3.1 22.6 23.2 24.0 26.1 Q-13-1 24.5 +/- 5.4 23.0 21.5 27.2 26.3 Q-13-2 24.7 +/- 3.2 23.1 24.0 24.7 26.8 Q-16-1 22.7 +/- 5.4 21.0 19.9 25.5 24.5 Q-16-2 23.0 +/- 4.3 20.7 21.5 24.6 25.0 Q-37-1 26.3 +/- 5.4 23.1 25.0 29.1 27.8 Q-37-2 25.3 +/- 4.6 24.4 23.7 24.2 28.7 Q-38-1 26.2 +/- 3.6 24.1 25.3 27.1 28.1 Q-38-2 25.6 +/- 6.5 23.0 22.5 28.8 27.9 Q-41-1 25.5 +/- 6.6 22.8 22.6 27.1 29.3 Q-41-2 24.7 +/- 4.2 22.8 23.1 25.6 27.2 Q-42-1 25.5 +/- 5.8 23.2 22.8 28.7 27.1 Q-42-2 25.8 +/- 2.9 24.2 25.2 26.2 27.6 Q-101-1 23.4 +/- 6.0 20.5 21.0 25.6 26.3 Q-101-2 23.3 +/- 5.8 21.4 20.5 24.5 26.8 Q-102-1 24.2 +/- 3.8 22.4 22.6 26.1 25.5 Q-102-3 24.6 +/- 5.0 22.3 22.6 26.8 26.7 Q-103-1 22.3 +/- 3.3 21.3 20.6 23.2 24.1 Q-103-2 23.5 +/- 5.7 20.5 21.7 25.2 26.6 Q-104-1 23.2 +/- 3.7 21.9 21.4 24.0 25.4 Q-104-2 23.5 +/- 4.9 20.2 23.0 25.3 25.4 Q-105-1 22.8 +/- 5.0 19.4 22.5 24.5 24.8 Q-105-2 23.0 +/- 6.0 20.5 20.3 25.2 26.0 Q-106-2 23.7 +/- 4.3 20.8 23.4 25.8 24.7 Q-106-3 23.3 +/- 5.3 20.8 21.3 24.8 26.2 Q-107-2 22.6 +/- 3.3 20.5 22.3 24.5 23.1 Q-107-3 23.9 +/- 3.3 24.2 22.2 23.0 26.0 Q-108-1 23.4 +/- 4.8 21.3 21.4 25.6 25.4 Q-108-2 23.1 +/- 5.4 20.0 21.7 24.6 26.0 Q-109-1 23.7 +/- 3.6 (1) 21.7 24.5 25.0 Q-109-2 22.8 +/- 3.9 20.8 21.5 24.9 23.9 Q-111-1 23.2 +/- 2.9 21.3 22.9 24.8 23.6 Q-111-2 23.4 +/- 6.0 21.2 21.3 23.6 27.6 Q-112-1 23.1 +/- 4.6 22.2 20.3 25.0 25.0 Q-112-2 22.7 +/- 5.4 20.2 20.6 25.4 24.7 Q-113-1 23.3 +/- 3.9 20.6 22.9 24.6 24.9 Q-113-2 22.3 +/- 4.0 21.0 20.3 23.0 24.7 Q-114-1 22.3 +/- 7.0 19.4 19.2 24.3 26.1 Q-114-2 24.6 +/- 4.6 21.4 25.0 25.0 26.9 Q-115-1 22.7 +/- 4.5 20.0 21.9 25.2 23.7 Q-115-2 22.3 +/- 4.8 20.4 20.1 23.7 24.9 Q-116-1 25.1 +/- 5.1 23.5 22.7 26.0 28.3 Q-116-3 22.3 +/- 6.1 18.6 21.4 23.5 25.8 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-15

Table C-IX.1 QUARTERLY OSLD RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN CODE +/- 2 S.D. JAN - MAR APR - JUN JUL - SEP OCT - DEC Q-201-1 24.6 +/- 6.3 20.6 23.6 27.3 26.9 Q-201-2 25.7 +/- 5.9 22.3 24.1 28.0 28.3 Q-202-1 23.3 +/- 3.9 21.0 22.4 24.8 25.1 Q-202-2 23.5 +/- 4.9 21.2 21.6 25.4 25.9 Q-203-1 24.3 +/- 2.3 23.7 23.6 25.6 (1)

Q-203-2 27.1 +/- 3.7 25.7 25.3 28.6 28.8 Q-204-1 25.9 +/- 6.0 22.2 24.8 28.4 28.3 Q-204-2 27.0 +/- 3.7 25.5 25.4 28.0 29.1 Q-205-1 25.0 +/- 7.5 22.0 22.0 26.2 29.8 Q-205-4 27.6 +/- 8.6 22.8 26.6 27.9 33.2 Q-206-1 24.2 +/- 5.3 20.8 23.3 26.3 26.3 Q-206-2 23.1 +/- 3.8 20.7 22.4 24.5 24.8 Q-207-1 25.0 +/- 2.6 24.0 23.8 25.5 26.6 Q-207-4 25.3 +/- 7.4 21.3 23.1 29.1 27.6 Q-208-1 24.2 +/- 5.6 20.9 22.8 26.4 26.6 Q-208-2 26.5 +/- 4.6 24.5 24.5 28.1 28.8 Q-209-1 26.2 +/- 5.4 25.0 23.0 27.9 28.9 Q-209-4 24.2 +/- 6.6 20.4 22.9 25.2 28.1 Q-210-1 26.3 +/- 5.1 23.2 25.2 28.4 28.4 Q-210-4 25.8 +/- 5.8 23.1 23.7 26.8 29.4 Q-210-5 21.6 +/- 6.0 20.3 18.0 23.9 24.2 Q-211-1 26.9 +/- 7.0 23.0 24.9 29.5 30.2 Q-211-2 27.0 +/- 7.4 24.1 23.5 30.6 29.7 Q-212-1 23.9 +/- 6.3 20.0 22.8 25.4 27.2 Q-212-2 21.7 +/- 3.3 20.4 20.4 22.1 23.9 Q-213-1 23.2 +/- 7.1 20.6 20.3 24.0 27.9 Q-213-2 23.1 +/- 5.9 20.5 20.9 24.2 26.7 Q-214-1 23.9 +/- 6.6 19.8 22.7 26.4 26.8 Q-214-2 25.6 +/- 8.2 22.4 22.7 26.2 31.2 Q-215-1 23.7 +/- 6.5 20.1 21.8 26.6 26.3 Q-215-2 24.9 +/- 7.5 21.7 21.8 26.6 29.3 Q-216-1 27.9 +/- 6.3 24.4 (1) 28.6 30.6 Q-216-2 25.7 +/- 5.5 22.1 25.0 27.2 28.3 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16

TABLE C-IX.2 MEAN QUARTERLY OSLD RESULTS FOR THE INNER RING, OUTER RING, OTHER AND CONTROL LOCATION FOR QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATION STANDARD DEVIATIONS OF THE STATION DATA COLLECTION INNER RING PERIOD +/- 2 S.D. OUTER RING OTHER CONTROL JAN-MAR 21.0 +/- 2.4 22.1 +/- 3.5 21.8 +/- 3.2 23.7 +/- 1.4 APR-JUN 21.7 +/- 2.4 23.1 +/- 3.5 22.2 +/- 3.7 24.0 +/- 3.4 JUL-SEP 24.7 +/- 1.9 26.7 +/- 3.7 25.5 +/- 3.7 27.5 +/- 3.5 OCT-DEC 25.5 +/- 2.4 27.9 +/- 4.1 26.3 +/- 3.4 27.4 +/- 0.7 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF MILLIREM/QUARTER SAMPLES PERIOD PERIOD PERIOD MEAN LOCATION ANALYZED MINIMUM MAXIMUM +/- 2 S.D.

INNER RING 119 18.6 28.3 23.2 +/- 4.5 OUTER RING 130 18.0 33.2 24.9 +/- 6.1 OTHER 72 19.1 29.3 24.0 +/- 5.3 CONTROL 8 22.8 28.7 25.6 +/- 4.3 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-210-4, 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 - 2016 Q-33 Cordova 12.0 10.0 8.0 pCi/L 6.0 4.0 2.0 0.0 01-01-00 05-24-03 10-14-06 03-06-10 07-27-13 12-17-16 Q-34 (C) Camanche 12.0 10.0 8.0 pCi/L 6.0 4.0 2.0 0.0 01-01-00 05-24-03 10-14-06 03-06-10 07-27-13 12-17-16 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 - 2016 Q-33 Cordova 500 400 300 pCi/L 200 100 0

01-01-00 05-24-03 10-14-06 03-06-10 07-27-13 12-17-16 Q-34 (C) Camanche 500 400 300 pCi/L 200 100 0

01-01-00 05-24-03 10-14-06 03-06-10 07-27-13 12-17-16 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 - 2016 Q-35 McMillan Well 500 400 300 pCi/L 200 100 0

12-31-99 05-23-03 10-13-06 03-05-10 07-26-13 12-16-16 Q-36 Cordova Well 500 400 300 pCi/L 200 100 0

12-31-99 05-23-03 10-13-06 03-05-10 07-26-13 12-16-16 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 - 2016 Q-01 Onsite No. 1 70.0 60.0 50.0 10E-03 pCi/m3 40.0 30.0 20.0 10.0 0.0 01-01-00 04-01-04 07-01-08 10-01-12 01-01-17 Q-02 Onsite No. 2 70.0 60.0 50.0 10E-03 pCi/m3 40.0 30.0 20.0 10.0 0.0 01-01-00 04-01-04 07-01-08 10-01-12 01-01-17 C-21

FIGURE C-5 Air Particulates - Gross Beta- Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2016 Q-03 Onsite No. 3 60.0 50.0 10E-03 pCi/m3 40.0 30.0 20.0 10.0 0.0 01-01-00 04-01-04 07-01-08 10-01-12 01-01-17 Q-04 Nitrin 60.0 50.0 40.0 10E-03 pCi/m3 30.0 20.0 10.0 0.0 01-01-00 04-01-04 07-01-08 10-01-12 C-22

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

Collected in the Vicinity of QCNPS, 2000 - 2010 Q-07 (C) Clinton 70.0 60.0 50.0 10E-03 pCi/m3 40.0 30.0 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 - 2016 Q-13 Princeton 60.0 50.0 40.0 10E-03 pCi/m3 30.0 20.0 10.0 0.0 07-01-05 06-01-07 05-01-09 04-01-11 03-01-13 02-01-15 01-01-17 Q-16 Low Moor 60.0 50.0 40.0 30.0 20.0 10.0 0.0 07-01-05 06-01-07 05-01-09 04-01-11 03-01-13 02-01-15 01-01-17 AIR PARTICULATE 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 - 2016 Q-37 Meredosia Q-13 Road Princeton 60.0 50.0 50.0 10E-03 10E-03 pCi/m3 pCi/m3 40.0 40.0 30.0 30.0 20.0 20.0 10.0 10.0 0.0 07-01-05 0.0 06-01-07 05-01-09 04-01-11 03-01-13 02-01-15 01-01-17 12-31-04 02-28-05 04-30-05 06-30-05 08-31-05 10-31-05 12-31-05 Q-13Fuller Q-38 Princeton Road 60.0 60.0 50.0 50.0 40.0 40.0 10E-03 pCi/m3 30.0 30.0 20.0 20.0 10.0 0.0 10.0 12-31-04 02-28-05 04-30-05 06-30-05 08-31-05 10-31-05 12-31-05 0.0 07-01-05 06-01-07 05-01-09 04-01-11 03-01-13 02-01-15 01-01-17 AIR PARTICULATE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 C-25

FIGURE C-9 Air Particulates - Gross Beta- Station Q-41 Collected in the Vicinity of QCNPS, 2009 - 2016 Q-41 Camanche 60.0 50.0 40.0 10E-03 pCi/m3 30.0 20.0 10.0 0.0 01-01-09 01-01-11 01-01-13 01-01-15 01-01-17 Air Particulates - Gross Beta- Station Q-42 (C)

Collected in the Vicinity of QCNPS, 2010 - 2016 Q-42 LeClaire (Control) 60.0 50.0 40.0 10E-03 pCi/m3 30.0 20.0 10.0 0.0 12-31-10 03-13-12 05-25-13 08-06-14 10-18-15 12-29-16 C-26

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM

Intentionally left blank TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

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

March 2016 E11476 Milk Sr-89 pCi/L 97 86.7 1.12 A Sr-90 pCi/L 15 11.4 1.32 N(2)

E11477 Milk I-131 pCi/L 85.9 82.2 1.05 A Ce-141 pCi/L 106 98.4 1.08 A Cr-51 pCi/L 255 243 1.05 A Cs-134 pCi/L 134 130 1.03 A Cs-137 pCi/L 174 161 1.08 A Co-58 pCi/L 123 117 1.05 A Mn-54 pCi/L 141 117 1.21 W Fe-59 pCi/L 152 131 1.16 A Zn-65 pCi/L 193 179 1.08 A Co-60 pCi/L 259 244 1.06 A E11479 AP Ce-141 pCi 69 81.1 0.85 A Cr-51 pCi 242 201 1.20 W Cs-134 pCi 98.1 107.0 0.92 A Cs-137 pCi 136 133 1.02 A Co-58 pCi 91.9 97 0.95 A Mn-54 pCi 98.6 96.2 1.02 A Fe-59 pCi 98.8 108 0.91 A Zn-65 pCi 131 147 0.89 A Co-60 pCi 209 201 1.04 A E11478 Charcoal I-131 pCi 85.3 88.3 0.97 A E11480 Water Fe-55 pCi/L 1800 1666 1.08 A June 2016 E11537 Milk Sr-89 pCi/L 94.4 94.4 1.00 A Sr-90 pCi/L 13.4 15.4 0.87 A E11538 Milk I-131 pCi/L 96.8 94.5 1.02 A Ce-141 pCi/L 129 139 0.93 A Cr-51 pCi/L 240 276 0.87 A Cs-134 pCi/L 157 174 0.90 A Cs-137 pCi/L 117 120 0.98 A Co-58 pCi/L 131 142 0.92 A Mn-54 pCi/L 128 125 1.02 A Fe-59 pCi/L 132 122 1.08 A Zn-65 pCi/L 235 235 1.00 A Co-60 pCi/L 169 173 0.98 A June 2016 E11539 Charcoal I-131 pCi 86.1 89.4 0.96 A E11540 AP Ce-141 pCi 105 99.8 1.05 A Cr-51 pCi 216 198.0 1.09 A Cs-134 pCi 113 125 0.90 A Cs-137 pCi 94.5 86.6 1.09 A Co-58 pCi 101 102 0.99 A Mn-54 pCi 88.8 90.2 0.98 A Fe-59 pCi 82 87.5 0.94 A Zn-65 pCi 174 169 1.03 A Co-60 pCi 143 124 1.15 A E11541 Water Fe-55 pCi/L 164 186 0.88 A D-1

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

Identification Reported Known Ratio (c)

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

September 2016 E11609 Milk Sr-89 pCi/L 90 90.9 0.99 A Sr-90 pCi/L 13.3 13.7 0.97 A E11610 Milk I-131 pCi/L 80.4 71.9 1.12 A Ce-141 pCi/L 81.3 93 0.87 A Cr-51 pCi/L 198 236 0.84 A Cs-134 pCi/L 122 136 0.90 A Cs-137 pCi/L 119 119 1.00 A Co-58 pCi/L 92.2 97.4 0.95 A Mn-54 pCi/L 156 152 1.03 A Fe-59 pCi/L 97.5 90.6 1.08 A Zn-65 pCi/L 189 179 1.06 A Co-60 pCi/L 131 135 0.97 A E11611 Charcoal I-131 pCi 52.4 59.9 0.87 A E11612 AP Ce-141 pCi 67.5 63.6 1.06 A Cr-51 pCi 192 161.0 1.19 A Cs-134 pCi 91.4 92.6 0.99 A Cs-137 pCi 93.9 80.8 1.16 A Co-58 pCi 66 66.4 0.99 A Mn-54 pCi 104 104 1.00 A Fe-59 pCi 60.5 61.8 0.98 A Zn-65 pCi 140 122 1.15 A Co-60 pCi 119 91.9 1.29 W E11613 Water Fe-55 pCi/L 1990 1670 1.19 A E11614 Soil Ce-141 pCi/g 0.153 0.175 0.87 A Cr-51 pCi/g 0.482 0.441 1.09 A Cs-134 pCi/g 0.270 0.254 1.06 A Cs-137 pCi/g 0.313 0.299 1.05 A Co-58 pCi/g 0.177 0.182 0.97 A Mn-54 pCi/g 0.340 0.285 1.19 A Fe-59 pCi/g 0.206 0.17 1.21 W Zn-65 pCi/g 0.388 0.335 1.16 A Co-60 pCi/g 0.284 0.252 1.13 A December 2016 E11699 Milk Sr-89 pCi/L 95 74.2 1.28 W Sr-90 pCi/L 14.7 10 1.47 N(3)

E11700 Milk I-131 pCi/L 97.5 97.4 1.00 A Ce-141 pCi/L 136 143 0.95 A Cr-51 pCi/L 247 280 0.88 A Cs-134 pCi/L 164 178 0.92 A Cs-137 pCi/L 120 126 0.95 A Co-58 pCi/L 139 146 0.95 A Mn-54 pCi/L 126 129 0.98 A Fe-59 pCi/L 114 125 0.91 A Zn-65 pCi/L 237 244 0.97 A Co-60 pCi/L 168 178 0.94 A E11701 Charcoal I-131 pCi 95.6 98 0.98 A D-2

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

Identification Reported Known Ratio (c)

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

December 2016 E11702 AP Ce-141 pCi 91.7 97.7 0.94 A Cr-51 pCi 210 192.0 1.09 A Cs-134 pCi 122 122 1.00 A Cs-137 pCi 93.9 86.4 1.09 A Co-58 pCi 92 100 0.92 A Mn-54 pCi 93.7 88.5 1.06 A Fe-59 pCi 84.9 84.5 1.00 A Zn-65 pCi 176 167 1.05 A Co-60 pCi 151 122 1.24 W E11702 AP Sr-89 pCi 79.1 92 0.86 A Sr-90 pCi 10 12.5 0.80 A E11703 Water Fe-55 pCi/L 2180 1800 1.21 W (a) Teledyne Brown Engineering reported result.

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

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

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

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

(2) NCR 16-26 was initiated (3) NCR 16-35 was initiated D-3

TABLE D-2 DOE's MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

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

March 2016 16-MaW34 Water Am-241 Bq/L 0.008 (1) A Ni-63 Bq/L 12.4 12.3 8.6-16.0 A Pu-238 Bq/L 1.4900 1.2440 0.871-1.617 A Pu-239/240 Bq/L 0.729 0.641 0.449-0.833 A 16-MaS34 Soil Ni-63 Bq/kg 1140 1250.0 875-1625 A Sr-90 Bq/kg 8.15 (1) A 16-RdF34 AP U-234/233 Bq/sample 0.1620 0.1650 0.116-0.215 A U-238 Bq/sample 0.163 0.172 0.120-0.224 A 16-GrF34 AP Gr-A Bq/sample 0.608 1.20 0.36-2.04 A Gr-B Bq/sample 0.8060 0.79 0.40-1.19 A 16-RdV34 Vegetation Cs-134 Bq/sample 10.10 10.62 7.43-13.81 A Cs-137 Bq/sample 6.0 5.62 3.93-7.31 A Co-57 Bq/sample 13.3000 11.8 8.3-15.3 A Co-60 Bq/sample 0.013 (1) A Mn-54 Bq/sample 0.0150 (1) A Sr-90 Bq/sample 0.301 (1) N(4)

Zn-65 Bq/sample 10.500 9.6 6.7-12.5 A September 2016 16-MaW35 Water Am-241 Bq/L 0.626 0.814 .570-1058 W Ni-63 Bq/L 12.4 17.2 12.0-22.4 A Pu-238 Bq/L 1.23 1.13 0.79-1.47 W Pu-239/240 Bq/L 0.0318 0.013 (1) A 16-MaS35 Soil Ni-63 Bq/kg 724 990 693-1287 A Sr-90 Bq/kg 747 894 626-1162 A 16-RdF35 AP U-234/233 Bq/sample 0.160 0.15 0.105-0.195 A U-238 Bq/sample 0.157 0.156 0.109-0.203 A 16-RdV35 Vegetation Cs-134 Bq/sample -0.103 (1) A Cs-137 Bq/sample 5.64 5.54 3.88-7.20 A Co-57 Bq/sample 7.38 6.81 4.77-8.85 A Co-60 Bq/sample 4.81 4.86 3.40-6.32 A Mn-54 Bq/sample 7.4 7.27 5.09-9.45 A Sr-90 Bq/sample 0.774 0.80 0.56-1.04 A Zn-65 Bq/sample 5.46 5.4 3.78-7.02 A (1) False positive test.

(a) Teledyne Brown Engineering reported result.

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

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

(4)NCR 16-14 was initiated D-4

TABLE D-3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

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

May 2016 RAD-105 Water Sr-89 pCi/L 48.9 48.2 37.8 - 55.6 A Sr-90 pCi/L 25.0 28.5 20.7 - 33.1 A Ba-133 pCi/L 53.1 58.8 48.7 - 64.9 A Cs-134 pCi/L 40.9 43.3 34.6 - 47.6 A Cs-137 pCi/L 84.8 78.4 70.6 - 88.9 A Co-60 pCi/L 108 102 91.8 - 114 A Zn-65 pCi/L 226 214 193 - 251 A Gr-A pCi/L 38.9 62.7 32.9 - 77.8 A Gr-B pCi/L 41.9 39.2 26.0 - 46.7 A I-131 pCi/L 24.1 26.6 22.1 - 31.3 A U-Nat pCi/L 4.68 4.64 3.39 - 5.68 A H-3 pCi/L 7720 7840 6790 - 8620 A November 2016 RAD-107 Water Sr-89 pCi/L 43.0 43.3 33.4-50.5 A Sr-90 pCi/L 30.0 33.6 24.6-38.8 A Ba-133 pCi/L 47.8 54.9 45.4-60.7 A Cs-134 pCi/L 72.9 81.8 67.0-90.0 A Cs-137 pCi/L 189 210 189-233 A Co-60 pCi/L 58.4 64.5 58.0-73.4 A Zn-65 pCi/L 243 245 220-287 A Gr-A pCi/L 37.2 68.4 35.9-84.5 A Gr-B pCi/L 35.1 33.9 22.1-41.6 A I-131 pCi/L 23.5 26.3 21.9-31.0 A U-Nat pCi/L 49.2 51.2 41.6-56.9 A H-3 pCi/L 918 9820 8540-10800 N(5)

MRAD-25 AP Gr-A pCi/Filter 56.8 71.2 23.9-111 A (a) Teledyne Brown Engineering reported result.

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

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

(5) NCR 16-34 was initiated D-5

TABLE D-4 ERA STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAMa MRAD Study, ENVIRONMENTAL, INC., 2016 Concentration a Laboratory ERA Control Lab Code b Date Analysis Result Result Limits Acceptance ERAP-1101 3/14/2016 Am-241 37.3 45.9 28.3 - 62.1 Pass ERAP-1101 3/14/2016 Co-60 637 623 482 - 778 Pass ERAP-1101 3/14/2016 Cs-134 251 304 193 - 377 Pass ERAP-1101 3/14/2016 Cs-137 1,273 1,150 864 - 1,510 Pass ERAP-1101 3/14/2016 Fe-55 < 162 126 39.1 - 246 Pass ERAP-1101 3/14/2016 Mn-54 < 2.64 < 50.0 0.00 - 50.0 Pass ERAP-1101 3/14/2016 Pu-238 68.0 70.5 48.3 - 92.7 Pass ERAP-1101 3/14/2016 Pu-239/240 54.1 54.8 39.70 - 71.60 Pass ERAP-1101 3/14/2016 Sr-90 139 150 73.3 - 225.0 Pass ERAP-1101 3/14/2016 U-233/234 59.3 64.8 40.2 - 97.7 Pass ERAP-1101 3/14/2016 U-238 55.5 64.2 41.5 - 88.8 Pass ERAP-1101 3/14/2016 Zn-65 428 356 255 - 492 Pass ERAP-1101 3/14/2016 Gr. Alpha 98.0 70.1 23.5 - 109 Pass ERAP-1101 3/14/2016 Gr. Beta 78.6 54.4 34.4 - 79.3 Pass ERSO-1105 3/14/2016 Am-241 1,030 1,360 796 - 1,770 Pass ERSO-1105 3/14/2016 Ac-228 1,540 1,240 795 - 1,720 Pass ERSO-1105 3/14/2016 Bi-212 1,550 1,240 330 - 1,820 Pass ERSO-1105 3/14/2016 Bi-214 3,100 3,530 2,130 - 5,080 Pass ERSO-1105 3/14/2016 Co-60 5,600 5,490 3,710 - 7,560 Pass ERSO-1105 3/14/2016 Cs-134 3,030 3,450 2,260 - 4,140 Pass ERSO-1105 3/14/2016 Cs-137 4,440 4,310 3,300 - 5,550 Pass ERSO-1105 3/14/2016 K-40 10,300 10,600 7,740 - 14,200 Pass ERSO-1105 3/14/2016 Mn-54 < 50.8 < 1000 0.0 - 1,000 Pass ERSO-1105 3/14/2016 Pb-212 1,140 1,240 812 - 1,730 Pass ERSO-1105 3/14/2016 Pb-214 3,190 3,710 2,170 - 5,530 Pass ERSO-1105 3/14/2016 Pu-238 680 658 396 - 908 Pass ERSO-1105 3/14/2016 Pu-239/240 460 496 324 - 0,685 Pass ERSO-1105 3/14/2016 Sr-90 7,740 8,560 3,260 - 13,500 Pass ERSO-1105 3/14/2016 Th-234 3,630 3,430 1,080 - 6,450 Pass ERSO-1105 3/14/2016 U-233/234 3,090 3,460 2,110 - 4,430 Pass ERSO-1105 3/14/2016 U-238 3,280 3,430 2,120 - 4,350 Pass ERSO-1105 3/14/2016 Zn-65 2,940 2,450 1,950 - 3,260 Pass ERW-1115 3/14/2016 Gr. Alpha 105.0 117.0 41.5 - 181.0 Pass ERW-1115 3/14/2016 Gr. Beta 76.2 75.5 43.2 - 112.0 Pass ERW-1117 3/14/2016 H-3 8,870 8,650 5,800 - 12,300 Pass ERVE-1108 3/14/2016 Am-241 1,930 2,120 1,300 - 2,820 Pass ERVE-1108 3/14/2016 Cm-244 1,294 1,560 764 - 2,430 Pass ERVE-1108 3/14/2016 Co-60 1,164 1,100 759 - 1,540 Pass ERVE-1108 3/14/2016 Cs-134 1,056 1,070 687 - 1,390 Pass ERVE-1108 3/14/2016 Cs-137 930 838 608 - 1,170 Pass ERVE-1108 3/14/2016 K-40 32,200 31,000 22,400 - 43,500 Pass ERVE-1108 3/14/2016 Mn-54 < 24.5 < 300 0.00 - 300 Pass ERVE-1108 3/14/2016 Zn-65 3,320 2,820 2,030 - 3,960 Pass D-6

TABLE D-4 ERA STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAMa MRAD Study, ENVIRONMENTAL, INC., 2016 Concentration a Laboratory ERA Control Lab Code b Date Analysis Result Result Limits Acceptance ERVE-1108 3/14/2016 Pu-238 3,410 2,810 1,680 - 3,850 Pass ERVE-1108 3/14/2016 Pu-239/240 4,120 3,640 2,230 - 5,010 Pass ERVE-1108 3/14/2016 Sr-90 8,120 8,710 4,960 - 11,500 Pass ERVE-1108 3/14/2016 U-233/234 4,350 4,160 2,740 - 5,340 Pass ERVE-1108 3/14/2016 U-238 4,220 4,120 2,750 - 5,230 Pass ERW-1111 3/14/2016 Am-241 113 121 81.5 - 162 Pass ERW-1111 3/14/2016 Co-60 1,120 1,050 912 - 1,230 Pass ERW-1111 3/14/2016 Cs-134 806 842 618 - 968 Pass ERW-1111 3/14/2016 Cs-137 1,190 1,100 934 - 1,320 Pass ERW-1111 3/14/2016 Mn-54 < 5.89 < 100 0.00 - 100 Pass ERW-1111 3/14/2016 Pu-238 159 138 102 - 172 Pass ERW-1111 3/14/2016 Pu-239/240 113 98.7 76.6 - 124 Pass ERW-1111 3/14/2016 U-233/234 46.9 52.7 39.6 - 68.0 Pass ERW-1111 3/14/2016 U-238 50.4 52.3 39.9 - 64.2 Pass ERW-1111 3/14/2016 Zn-65 1,160 1,010 842 - 1,270 Pass ERW-1111 3/14/2016 Fe-55 1,600 1,650 984 - 2,240 Pass ERW-1111 3/14/2016 Sr-90 430 434 283 - 574 Pass a

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

b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).

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

D-7

TABLE D-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

ENVIRONMENTAL, INC., 2016 Concentration a Reference Known Control b

Lab Code Date Analysis Laboratory result Activity Limits c Acceptance MASO-1053 2/1/2016 Ni-63 1,206 +/- 20 1250 875 - 1625 Pass MASO-1053 2/1/2016 Sr-90 0.65 +/- 1.27 0.00 NA c Pass MASO-1053 2/1/2016 Tc-99 0.1 +/- 5.5 0.0 NA c Pass MASO-1053 2/1/2016 Cs-134 908 +/- 26 1030 721 - 1339 Pass MASO-1053 2/1/2016 Cs-137 0.10 +/- 6.20 0.00 NA c Pass MASO-1053 2/1/2016 Co-57 1058 +/- 26 992 694 - 1290 Pass MASO-1053 2/1/2016 Co-60 1229 +/- 28 1190 833 - 1547 Pass MASO-1053 2/1/2016 Mn-54 1235 +/- 43 1160 812 - 1508 Pass MASO-1053 2/1/2016 Zn-65 753 +/- 64 692 484 - 900 Pass MASO-1053 2/1/2016 K-40 753 +/- 140 607 425 - 789 Pass MASO-1053 2/1/2016 Am-241 79 +/-6 103 72 - 134 Pass MASO-1053 2/1/2016 Pu-238 73.9 +/- 9.2 63.6 44.5 - 82.7 Pass MASO-1053 2/1/2016 Pu-239/240 0.76 +/- 1.34 0.21 NA d Pass MASO-1053 2/1/2016 U-234/233 45.0 +/- 5.1 45.9 32.1 - 59.7 Pass MASO-1053 2/1/2016 U-238 129 +/-9 146 102 - 190 Pass MAW-989 2/1/2016 Am-241 0.018 +/- 0.015 0.00 NA c Pass MAW-989 2/1/2016 H-3 0.2 +/- 2.8 0.0 NA c Pass MAW-989 2/1/2016 Ni-63 12.8 +/- 2.7 12.3 8.6 - 16.0 Pass MAW-989 2/1/2016 Sr-90 8.70 +/- 1.20 8.74 6.12 - 11.36 Pass MAW-989 2/1/2016 Tc-99 -1.1 +/- 0.6 0.0 NA c Pass MAW-989 2/1/2016 Cs-134 15.5 +/- 0.3 16.1 11.3 +/- 20.9 Pass MAW-989 2/1/2016 Cs-137 23.7 +/- 0.5 21.2 14.8 - 27.6 Pass MAW-989e 2/1/2016 Co-57 1.38 +/- 0.12 0.00 NA c Fail MAW-989 2/1/2016 Co-60 12.5 +/- 0.3 11.8 8.3 - 15.3 Pass MAW-989 2/1/2016 Mn-54 12.2 +/- 0.4 11.1 7.8 - 14.4 Pass MAW-989 2/1/2016 Zn-65 15.7 +/- 0.7 13.6 9.5 - 17.7 Pass MAW-989 2/1/2016 K-40 288 +/-5 251 176 - 326 Pass MAW-989 2/1/2016 Fe-55 17.3 +/- 7.0 16.2 11.3 - 21.1 Pass MAW-989 2/1/2016 Ra-226 0.710 +/- 0.070 0.718 0.503 - 0.933 Pass MAW-989 2/1/2016 Pu-238 1.280 +/- 0.110 1.244 0.871 +/- 1.617 Pass MAW-989 2/1/2016 Pu-239/240 0.640 +/- 0.080 0.641 0.449 - 0.833 Pass MAW-989 2/1/2016 U-234/233 1.39 +/- 0.12 1.48 1.04 - 1.92 Pass MAW-989 2/1/2016 U-238 1.43 +/- 0.12 1.53 1.07 - 1.99 Pass MAW-893 2/1/2016 Gross Alpha 0.600 +/- 0.050 0.673 0.202 - 1.144 Pass MAW-893 2/1/2016 Gross Beta 2.10 +/- 0.06 2.15 1.08 - 3.23 Pass MAW-896 2/1/2016 I-129 3.67 +/- 0.20 3.85 2.70 - 5.01 Pass MAAP-1056 2/1/2016 Gross Alpha 0.39 +/- 0.05 1.20 0.36 - 2.04 Pass MAAP-1056 2/1/2016 Gross Beta 1.03 +/- 0.07 0.79 0.40 - 1.19 Pass MAAP-1057 2/1/2016 Sr-90 1.34 +/- 0.15 1.38 0.97 +/- 1.79 Pass MAAP-1057 2/1/2016 Cs-134 -0.01 +/- 0.03 0.00 NA c Pass MAAP-1057 2/1/2016 Cs-137 2.57 +/- 0.10 2.30 1.61 - 2.99 Pass D-8 (Page 1 of 3)

TABLE D-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

ENVIRONMENTAL, INC., 2016 Concentration a Reference Known Control b

Lab Code Date Analysis Laboratory result Activity Limits c Acceptance MAAP-1057 2/1/2016 Co-57 3.01 +/- 0.06 2.94 2.06 - 3.82 Pass MAAP-1057 2/1/2016 Co-60 4.28 +/- 0.10 4.02 2.81 - 5.23 Pass MAAP-1057 2/1/2016 Mn-54 4.90 +/- 0.13 4.53 3.17 - 5.89 Pass MAAP-1057 2/1/2016 Zn-65 4.09 +/- 0.18 3.57 2.50 - 4.64 Pass MAAP-1057 2/1/2016 Am-241 0.059 +/- 0.015 0.0805 0.0564 - 0.1047 Pass MAAP-1057 2/1/2016 Pu-238 0.066 +/- 0.020 0.0637 0.0446 - 0.0828 Pass MAAP-1057 2/1/2016 Pu-239/240 0.074 +/- 0.020 0.099 NA d Pass MAAP-1057 2/1/2016 U-234/233 0.151 +/- 0.026 0.165 0.116 - 0.215 Pass MAAP-1057 2/1/2016 U-238 0.160 +/- 0.026 0.172 0.120 - 0.224 Pass MAVE-1050 2/1/2016 Cs-134 9.83 +/- 0.19 10.62 7.43 - 13.81 Pass MAVE-1050 2/1/2016 Cs-137 6.06 +/- 0.19 5.62 3.93 - 7.31 Pass MAVE-1050 2/1/2016 Co-57 13.8 +/- 0.2 11.8 8.3 - 15.3 Pass MAVE-1050 2/1/2016 Co-60 0.022 +/- 0.040 0.00 NA c Pass MAVE-1050 2/1/2016 Mn-54 0.009 +/- 0.044 0.000 NA c Pass MAVE-1050 2/1/2016 Zn-65 10.67 +/- 0.39 9.60 6.70 - 12.50 Pass f

MASO-4780 8/1/2016 Ni-63 648 +/- 14 990 693 - 1287 Fail MASO-4780g 8/1/2016 Ni-63 902 +/- 46 990 693 - 1287 Pass MASO-4780 8/1/2016 Sr-90 757 +/- 16 894 626 - 1162 Pass MASO-4780 8/1/2016 Tc-99 559 +/- 12 556 389 - 723 Pass MASO-4780 8/1/2016 Cs-134 0.93 +/- 2.92 0.00 NA c Pass MASO-4780 8/1/2016 Cs-137 1061 +/- 12 1067 747 - 1387 Pass MASO-4780 8/1/2016 Co-57 1178 +/-8 1190 833 - 1547 Pass MASO-4780 8/1/2016 Co-60 841 +/-9 851 596 - 1106 Pass MASO-4780 8/1/2016 Mn-54 0.69 +/- 2.53 0.00 NA c Pass MASO-4780 8/1/2016 Zn-65 724 +/- 19 695 487 - 904 Pass MASO-4780 8/1/2016 K-40 566 +/- 52 588 412 - 764 Pass MASO-4780 8/1/2016 Am-241 0.494 +/- 0.698 0.000 NA c Pass MASO-4780 8/1/2016 Pu-238 69.7 +/- 7.4 70.4 49.3 - 91.5 Pass MASO-4780 8/1/2016 Pu-239/240 53.9 +/- 6.3 53.8 37.7 - 69.9 Pass MASO-4780h 8/1/2016 U-233/234 46.8 +/- 3.9 122 85 - 159 Fail MASO-4780h 8/1/2016 U-238 46.6 +/- 3.9 121 85 - 157 Fail MAW-4776 8/1/2016 I-129 4.40 +/- 0.20 4.54 3.18 - 5.90 Pass MAVE-4782 8/1/2016 Cs-134 -0.01 +/- 0.05 0.00 NA c Pass MAVE-4782 8/1/2016 Cs-137 6.18 +/- 0.20 5.54 3.88 - 7.20 Pass MAVE-4782 8/1/2016 Co-57 8.13 +/- 0.16 6.81 4.77 - 8.85 Pass MAVE-4782 8/1/2016 Co-60 5.30 +/- 0.15 4.86 3.40 - 6.32 Pass MAVE-4782 8/1/2016 Mn-54 8.08 +/- 0.24 7.27 5.09 - 9.45 Pass MAVE-4782 8/1/2016 Zn-65 6.24 +/- 0.36 5.40 3.78 - 7.02 Pass MAAP-4784 8/1/2016 Sr-90 1.18 +/- 0.10 1.03 0.72 - 1.34 Pass MAAP-4784 8/1/2016 Cs-134 1.58 +/- 0.08 2.04 1.43 - 2.65 Pass D-9 (Page 2 of 3)

TABLE D-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

ENVIRONMENTAL, INC., 2016 Concentration a Reference Known Control b

Lab Code Date Analysis Laboratory result Activity Limits c Acceptance MAAP-4784 8/1/2016 Cs-137 1.85 +/- 0.09 1.78 1.25 - 2.31 Pass MAAP-4784 8/1/2016 Co-57 2.39 +/- 0.52 2.48 1.74 - 3.22 Pass MAAP-4784 8/1/2016 Co-60 3.22 +/- 0.08 3.26 2.28 - 4.24 Pass MAAP-4784 8/1/2016 Mn-54 2.82 +/- 0.12 2.75 1.93 - 3.58 Pass MAAP-4784 8/1/2016 Zn-65 -0.015 +/- 0.062 0.00 NA c Pass MAAP-4784 8/1/2016 Am-241 -0.001 +/- 0.006 0.00 NA c Pass MAAP-4784 8/1/2016 Pu-238 0.075 +/- 0.022 0.069 0.049 - 0.090 Pass MAAP-4784 8/1/2016 Pu-239/240 0.048 +/- 0.015 0.054 0.038 - 0.070 Pass MAAP-4784 8/1/2016 U-234/233 0.151 +/- 0.036 0.150 0.105 - 0.195 Pass MAAP-4784 8/1/2016 U-238 0.147 +/- 0.034 0.156 0.109 - 0.203 Pass MAW-4778 8/1/2016 H-3 365 +/- 11 334 234 - 434 Pass MAW-4778 8/1/2016 Fe-55 23.6 +/- 16.3 21.5 15.1 +/- 28.0 Pass MAW-4778 8/1/2016 Ni-63 17.0 +/- 2.8 17.2 12.0 +/- 22.4 Pass MAW-4778 8/1/2016 Sr-90 0.17 +/- 0.28 0.00 NA c Pass MAW-4778 8/1/2016 Tc-99 9.50 +/- 0.41 11.60 8.10 - 15.10 Pass MAW-4778 8/1/2016 Cs-134 22.6 +/- 0.4 23.9 16.7 - 31.1 Pass MAW-4778 8/1/2016 Cs-137 0.018 +/- 0.117 0.00 NA c Pass MAW-4778 8/1/2016 Co-57 27.6 +/- 0.2 27.3 19.1 +/- 35.5 Pass MAW-4778 8/1/2016 Co-60 0.018 +/- 0.090 0.00 NA c Pass MAW-4778 8/1/2016 Mn-54 16.2 +/- 0.4 14.8 10.4 - 19.2 Pass MAW-4778 8/1/2016 Zn-65 19.3 +/- 0.7 17.4 12.2 - 22.6 Pass MAW-4778 8/1/2016 K-40 286 +/-6 252 176 - 328 Pass MAW-4778 8/1/2016 Ra-226 1.48 +/- 0.09 1.33 0.93 - 1.73 Pass MAW-4778 8/1/2016 Pu-238 1.09 +/- 0.13 1.13 0.79 - 1.47 Pass MAW-4778 8/1/2016 Pu-239/240 0.003 +/- 0.011 0.016 NA d Pass MAW-4778 8/1/2016 U-234/233 1.80 +/- 0.13 1.86 1.30 - 2.42 Pass MAW-4778 8/1/2016 U-238 1.77 +/- 0.13 1.92 1.34 - 2.50 Pass MAW-4778 8/1/2016 Am-241 0.678 +/- 0.086 0.814 0.570 +/- 1.058 Pass a

Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).

c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.

d Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.

e The laboratory properly identified the Sn-75 interfering peak in the vicinity of Co-57 and stated so in the comment field. MAPEP requires results to be reported as an activity with an uncertainty. Since the calculated uncertainty was less than the activity MAPEP interpreted the submitted result as a "false positive" resulting in a failure.

f Original analysis for Ni-63 failed.

g Reanalysis with a smaller aliquot resulted in acceptable results. An investigation is in process to identify better techniques for analyzing samples with complex matrices.

h MAPEP states that samples contain two fractions of Uranium; one that is soluble in concentrated HNO3 and HCl acid and one that is "fundamentally insoluble in these acids". They also state that HF treatment can not assure complete dissolution.

Results are consistent with measuring the soluble form.

D-10 (Page 3 of 3)

TABLE D-6 Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)a RAD Study, ENVIRONMENTAL, INC., 2016 Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance ERW-1392 4/4/2016 Sr-89 43.5 +/- 4.3 48.2 37.8 - 55.6 Pass ERW-1392 4/4/2016 Sr-90 27.5 +/- 1.9 28.5 20.7 - 33.1 Pass ERW-1394 b 4/4/2016 Ba-133 65.2 +/- 3.8 58.8 48.7 - 64.9 Fail ERW-1394 c 4/4/2016 Ba-133 57.8 +/- 5.3 58.8 48.7 - 64.9 Pass ERW-1394 4/4/2016 Cs-134 43.7 +/- 3.0 43.3 34.6 - 47.6 Pass ERW-1394 4/4/2016 Cs-137 86.1 +/- 5.3 78.4 70.6 - 88.9 Pass ERW-1394 4/4/2016 Co-60 108 +/- 44 102 91.8 - 114 Pass ERW-1394 4/4/2016 Zn-65 240 +/- 13 214 193 - 251 Pass ERW-1397 4/4/2016 Gr. Alpha 52.0 +/- 2.2 62.7 32.9 - 77.8 Pass ERW-1397 4/4/2016 Gr. Beta 33.9 +/- 1.2 39.2 26.0 - 46.7 Pass ERW-1400 4/4/2016 I-131 24.7 +/- 0.6 26.6 22.1 - 31.3 Pass ERW-1402 4/4/2016 Ra-226 15.6 +/- 0.5 15.2 11.3 - 17.4 Pass ERW-1402 4/4/2016 Ra-228 5.28 +/- 0.76 5.19 3.12 - 6.93 Pass ERW-1403 4/4/2016 Uranium 4.02 +/- 0.42 4.64 3.39 - 5.68 Pass ERW-1405 4/4/2016 H-3 8,150 +/- 270 7,840 6,790 - 8,620 Pass SPW-2845 7/7/2015 Ba-133 60.3 +/- 5.7 64.7 53.9 - 71.2 Pass SPW-2845 7/7/2015 Cs-134 48.8 +/- 9.3 50.1 40.3 - 55.1 Pass SPW-2845 7/7/2015 Cs-137 101 +/-8 89.8 80.8 - 101 Pass SPW-2845 7/7/2015 Co-60 65.1 +/- 5.8 59.9 53.9 - 68.4 Pass SPW-2845 7/7/2015 Zn-65 288 +/- 29 265 238 - 310 Pass ERW-3485 7/11/2016 Sr-89 43.3 +/- 6.5 53.3 42.3 - 60.9 Pass ERW-3485 7/11/2016 Sr-90 39.0 +/- 2.8 39.2 28.8 - 45.1 Pass ERW-3487 7/11/2016 Ba-133 83.3 +/- 4.9 82.9 69.7 - 91.2 Pass ERW-3487 7/11/2016 Cs-134 62.5 +/- 4.4 65.3 53.1 - 71.8 Pass ERW-3487 7/11/2016 Cs-137 98.1 +/- 5.6 95.2 85.7 - 107 Pass ERW-3487 7/11/2016 Co-60 122 +/-5 117 105 - 131 Pass ERW-3487 7/11/2016 Zn-65 124 +/-9 113 102 - 134 Pass ERW-3490 7/11/2016 Gr. Alpha 46.6 +/- 2.2 48.1 25.0 - 60.5 Pass ERW-3490 7/11/2016 Gr. Beta 26.8 +/- 1.1 28.6 18.2 - 36.4 Pass ERW-3492 7/11/2016 I-131 23.7 +/- 1.0 24.9 20.7 - 29.5 Pass ERW-3493 7/11/2016 Ra-226 12.9 +/- 0.4 12.3 9.2 - 14.2 Pass ERW-3493 7/11/2016 Ra-228 5.8 +/- 0.8 5.8 3.5 - 7.6 Pass ERW-3493 7/11/2016 Uranium 32.8 +/- 0.8 25.2 28.4 - 39.3 Pass ERW-3495 7/11/2016 H-3 12,400 +/- 334 12,400 10,800 - 13,600 Pass a

Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b No reason determined for failure of Ba-133 result.

c The result of reanalysis (Compare to original result, footnoted "b" above).

D-11

Intentionally left blank APPENDIX E ERRATA DATA

There is no errata data for 2016 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 31 December 2016 Prepared By Teledyne Brown Engineering Environmental Services Quad Cities Nuclear Power Station Cordova, IL 61242 April 2017

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 III. 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 i

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2016 Figures Figure A-1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2016 Figure A-2 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2016 Appendix B Data Tables Tables Table B-I.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table B-I.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table B-I.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table B-II.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table B-II.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2016 Table B-III.1 Concentrations of Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel, 2016 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 2016 through 31 December 2016.

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 (NEI 07-07, Hydrogeologic Investigation Report, dated November 2012). The referenced report summarized station activities since the 2006 hydrogeologic investigation report, including changes at the Station as well as RGPP sampling activities and groundwater flow.

A 2011 change to the RGPP consisted of designating 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 2016. During that time period, RGPP samples were collected from 42 locations.

2016 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 Iron-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 21,300 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 2016.

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 9 of 9 groundwater locations. The concentrations ranged from 1.5 to 50.4 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.

III. Program Description This section covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2016.

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 2016.

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, I-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-I.1 & B-III.1 Appendix B). Tritium values ranged from the detection limit to 21,300 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-112I sampled on 2/29/16 and 12/5/16, which showed activity of 212 pCi/L and 273 pCi/L respectively. 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-I.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 2016.

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 9 of 9 groundwater locations. The concentrations ranged from 1.5 to 50.4 pCi/L.

Gross Beta (suspended) was not detected at any of the groundwater locations (Table B-I.1 Appendix B).

Gamma Emitters No gamma-emitting nuclides were detected other than naturally-occurring K-40 in two samples at concentration of 61 pCi/L and 67 pCi/L (Table B-I.2, Appendix B).

Select Transuranics/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-I.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. Surface water samples were not obtained during the 4th quarter of 2016 due to both sample locations (former spray canal) being drained to support fish hatchery operations. (Table B-II.1 Appendix B).

Gamma Emitters No gamma-emitting nuclides were detected other than naturally-occurring K-40 in one sample at a concentration of 91 pCi/L.

(Table B-II.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 2016.

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

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2016 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-101I Monitoring Well Idle Not Required MW-QC-101S Monitoring Well Idle Not Required MW-QC-102D Monitoring Well Plume Quarterly MW-QC-102I Monitoring Well Plume Quarterly MW-QC-102S Monitoring Well Plume Quarterly MW-QC-103I Monitoring Well Detection Quarterly MW-QC-104S Monitoring Well Detection Quarterly MW-QC-105I Monitoring Well Plume Quarterly MW-QC-106I Monitoring Well Plume Quarterly MW-QC-106S Monitoring Well Plume Quarterly MW-QC-107I Monitoring Well Background Annual MW-QC-108D Monitoring Well Plume Quarterly MW-QC-108I Monitoring Well Plume Quarterly MW-QC-108S Monitoring Well Plume Quarterly MW-QC-109I Monitoring Well Plume Quarterly MW-QC-109S Monitoring Well Plume Quarterly MW-QC-110I Monitoring Well Idle Not Required MW-QC-111D1 Monitoring Well Idle Not Required MW-QC-111D2 Monitoring Well Idle Not Required MW-QC-111I Monitoring Well Idle Not Required MW-QC-112I Monitoring Well Plume Quarterly MW-QC-113I Monitoring Well Idle Not Required MW-QC-114I 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

A-2 FIGURE A-1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2016

A-3 FIGURE A-2 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2016

APPENDIX B DATA TABLES

Intentionally left blank TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

MW-QC-1 03/01/16 < 194 MW-QC-1 05/17/16 < 186 MW-QC-1 07/26/16 < 165 MW-QC-1 12/06/16 < 178 MW-QC-2 03/01/16 < 194 MW-QC-2 05/17/16 < 185 MW-QC-2 07/26/16 < 166 MW-QC-2 12/06/16 < 196 MW-QC-3 03/01/16 3480 +/- 414 MW-QC-3 05/17/16 2470 +/- 308 MW-QC-3 07/26/16 1940 +/- 251 MW-QC-3 12/06/16 13200 +/- 1360 MW-QC-102D 03/01/16 698 +/- 152 MW-QC-102D 05/17/16 778 +/- 149 MW-QC-102D 07/26/16 788 +/- 143 MW-QC-102D 12/06/16 877 +/- 158 MW-QC-102I 03/01/16 < 191 MW-QC-102I 05/17/16 < 179 MW-QC-102I 07/26/16 < 164 MW-QC-102I 12/06/16 291 +/- 127 MW-QC-102S 03/01/16 < 193 MW-QC-102S 05/17/16 < 179 MW-QC-102S 07/26/16 < 164 MW-QC-102S 12/06/16 < 180 MW-QC-103I 03/01/16 < 194 < 5.6 < 0.3 < 1.4 < 0.7 7.2 +/- 1.1 < 1.5 MW-QC-103I 05/17/16 < 180 MW-QC-103I 07/26/16 < 165 MW-QC-103I 12/06/16 < 181 MW-QC-104S 03/01/16 < 193 < 9.9 < 0.4 < 4.2 < 0.7 19.9 +/- 1.9 < 1.5 MW-QC-104S 05/17/16 < 178 MW-QC-104S 07/26/16 < 163 MW-QC-104S 12/06/16 < 180 MW-QC-105I 03/01/16 < 195 MW-QC-105I 05/17/16 < 175 MW-QC-105I 07/26/16 < 165 MW-QC-105I 12/06/16 < 178 MW-QC-106I 03/01/16 < 192 MW-QC-106I 05/17/16 < 181 MW-QC-106I 07/26/16 < 165 MW-QC-106I 12/06/16 < 180 MW-QC-106S 03/01/16 < 196 MW-QC-106S 05/17/16 < 178 MW-QC-106S 07/26/16 < 161 MW-QC-106S 12/06/16 < 179 MW-QC-107I 02/29/16 < 195 MW-QC-107I 05/16/16 < 174 MW-QC-108D 03/02/16 1100 +/- 186 MW-QC-108D 05/18/16 1720 +/- 237 MW-QC-108D 07/27/16 1220 +/- 181 MW-QC-108D 12/07/16 660 +/- 146 MW-QC-108I 03/02/16 286 +/- 132 MW-QC-108I 05/18/16 969 +/- 167 Bolded values indicate LLD was not met due to the high solid content in the sample B-1

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

MW-QC-108I 07/27/16 1240 +/- 184 MW-QC-108I 12/07/16 215 +/- 121 MW-QC-108S 03/02/16 < 196 MW-QC-108S 05/18/16 < 185 MW-QC-108S 07/27/16 < 163 MW-QC-108S 12/07/16 402 +/- 135 MW-QC-109I 03/01/16 < 198 MW-QC-109I 05/17/16 < 182 MW-QC-109I 07/26/16 < 165 MW-QC-109I 12/06/16 < 178 MW-QC-109S 03/01/16 < 193 MW-QC-109S 05/17/16 < 183 MW-QC-109S 07/26/16 < 164 MW-QC-109S 12/06/16 < 179 MW-QC-112I 02/29/16 212 +/- 130 MW-QC-112I 05/16/16 < 184 MW-QC-112I 07/25/16 < 162 MW-QC-112I 12/05/16 273 +/- 124 QC-GP-10 02/29/16 < 163 < 7.8 < 0.4 < 4.3 < 0.6 14.3 +/- 1.9 < 1.6 QC-GP-11 02/29/16 451 +/- 137 < 6.7 < 0.4 < 2.2 < 0.6 6.0 +/- 1.5 < 1.6 QC-GP-12 03/02/16 < 193 < 8.8 < 0.5 < 0.8 < 0.6 1.5 +/- 0.7 < 1.6 QC-GP-14 02/29/16 3370 +/- 399 < 5.2 < 0.3 < 2.4 < 0.6 5.4 +/- 1.4 < 1.6 QC-GP-15 02/29/16 < 192 < 6.2 < 0.5 < 5.3 < 0.6 17.4 +/- 3.4 < 1.6 QC-GP-16 02/29/16 6100 +/- 668 < 7.1 < 0.4 < 1.9 < 0.6 4.6 +/- 1.2 < 1.6 QC-GP-18 02/29/16 11300 +/- 1180 < 3.9 < 0.8 < 11.5 < 0.6 50.4 +/- 5.1 < 1.6 WELL 9 DRY CASK 3/1/2016 < 186 Bolded values indicate LLD was not met due to the high solid content in the sample B-2

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 MW-QC-103I 03/01/16 < 57 < 49 < 6 < 6 < 14 < 6 < 13 < 8 < 11 < 13 < 6 < 6 < 33 < 8 MW-QC-104S 03/01/16 < 47 < 54 < 5 < 5 < 11 < 6 < 11 < 5 < 8 < 12 < 4 < 5 < 29 < 10 MW-QC-107I 02/29/16 < 52 < 54 < 6 < 5 < 13 < 5 < 12 < 7 < 12 < 13 < 6 < 7 < 30 < 10 QC-GP-10 02/29/16 < 43 < 40 < 4 < 4 < 10 < 4 < 9 < 4 < 8 < 15 < 3 < 5 < 31 < 12 QC-GP-11 02/29/16 < 36 61 +/- 40 < 4 < 4 < 9 < 4 < 7 < 4 < 7 < 14 < 3 < 4 < 27 < 9 QC-GP-12 03/02/16 < 49 < 90 < 5 < 5 < 12 < 4 < 10 < 6 < 9 < 14 < 5 < 5 < 28 < 13 QC-GP-14 02/29/16 < 29 < 29 < 3 < 3 < 8 < 3 < 6 < 3 < 6 < 12 < 3 < 3 < 25 < 9 QC-GP-15 02/29/16 < 35 < 32 < 4 < 4 < 9 < 4 < 7 < 4 < 7 < 13 < 3 < 4 < 26 < 9 QC-GP-15 07/26/16 < 20 < 39 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 12 < 2 < 2 < 20 < 8 QC-GP-16 02/29/16 < 19 < 16 < 2 < 2 < 4 < 2 < 4 < 2 < 4 < 8 < 2 < 2 < 16 < 4 QC-GP-18 02/29/16 < 23 67 +/- 36 < 2 < 2 < 5 < 2 < 5 < 3 < 5 < 9 < 2 < 2 < 19 < 6 B-3 WELL 9 DRY CASK 03/01/16 < 29 < 52 < 3 < 3 < 7 < 3 < 6 < 3 < 6 < 10 < 3 < 3 < 22 < 8

TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/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 02/29/16 < 0.12 < 0.14 < 0.04 < 0.02 < 0.08 < 0.02 < 0.02 < 0.02 < 150 < 4.4 B-4

TABLE B-II.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE DATE H-3 SW-QC-1 02/29/16 < 194 SW-QC-1 05/16/16 < 183 SW-QC-1 07/25/16 < 163 SW-QC-2 02/29/16 < 193 SW-QC-2 05/16/16 < 185 SW-QC-2 07/25/16 < 167 B-5

TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2016 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 SW-QC-1 02/29/16 < 43 < 49 < 5 < 5 < 8 < 7 < 9 < 7 < 9 < 10 < 5 < 7 < 33 < 13 SW-QC-2 02/29/16 < 40 91 +/- 60 < 4 < 4 < 9 < 4 < 9 < 4 < 8 < 11 < 4 < 5 < 26 < 9 B-6

TABLE B-III.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2016 RESULTS IN UNITS OF PCI/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-1 02/29/16 6,390 Sentinel Well QC-GP-1 05/16/16 <2,000 Sentinel Well QC-GP-1 07/25/16 3,140 Sentinel Well QC-GP-1 12/05/16 2,850 Sentinel Well QC-GP-2 02/29/16 <2,000 Sentinel Well QC-GP-2 05/16/16 <2,000 Sentinel Well QC-GP-2 07/25/16 <2,000 Sentinel Well QC-GP-2 12/05/16 <2,000 Sentinel Well QC-GP-3 05/16/16 <2,000 Sentinel Well QC-GP-4 02/29/16 13,300 Sentinel Well QC-GP-4 05/16/16 11,500 Sentinel Well QC-GP-4 07/25/16 10,900 Sentinel Well QC-GP-4 12/05/16 15,700 Sentinel Well QC-GP-5 02/29/16 <2,000 Sentinel Well QC-GP-5 05/17/16 <2,000 Sentinel Well QC-GP-5 07/25/16 <2,000 Sentinel Well QC-GP-5 12/05/16 <2,000 Sentinel Well QC-GP-6 02/29/16 <2,000 Sentinel Well QC-GP-6 05/17/16 <2,000 Sentinel Well QC-GP-6 07/25/16 <2,000 Sentinel Well QC-GP-6 12/05/16 <2,000 Sentinel Well QC-GP-7 02/29/16 <2,000 Sentinel Well QC-GP-7 05/17/16 <2,000 Sentinel Well QC-GP-7 07/26/16 <2,000 Sentinel Well QC-GP-7 12/05/16 <2,000 Sentinel Well QC-GP-8 05/17/16 <2,000 Sentinel Well QC-GP-9 02/29/16 21,300 Sentinel Well QC-GP-9 05/19/16 8,690 Sentinel Well QC-GP-9 07/26/16 18,900 Sentinel Well QC-GP-9 12/05/16 12,100 Sentinel Well QC-GP-10 02/29/16 <2,000 Sentinel Well QC-GP-10 05/16/16 <2,000 Sentinel Well QC-GP-10 07/26/16 <2,000 Sentinel Well QC-GP-10 12/05/16 <2,000 Sentinel Well QC-GP-11 02/29/16 <2,000 Sentinel Well QC-GP-11 05/19/16 <2,000 Sentinel Well QC-GP-11 07/25/16 <2,000 Sentinel Well QC-GP-11 12/06/16 <2,000 Sentinel Well QC-GP-12 03/02/16 <2,000 Sentinel Well QC-GP-12 05/17/16 <2,000 Sentinel Well QC-GP-12 07/25/16 <2,000 Sentinel Well QC-GP-12 12/06/16 <2,000 Sentinel Well QC-GP-13 03/01/16 7,080 Sentinel Well QC-GP-13 05/16/16 7,940 Sentinel Well QC-GP-13 07/26/16 6,090 Sentinel Well QC-GP-13 12/06/16 5,220 Sentinel Well QC-GP-14 02/29/16 2,600 Sentinel Well QC-GP-14 05/19/16 3,220 Sentinel Well QC-GP-14 07/25/16 4,570 Sentinel Well QC-GP-14 12/06/16 <2,000 Sentinel Well QC-GP-15 02/29/16 <2,000 Sentinel Well QC-GP-15 05/17/16 <2,000 Sentinel Well QC-GP-15 07/26/16 <2,000 Sentinel Well QC-GP-15 12/05/16 <2,000 Sentinel Well QC-GP-16 02/29/16 4,990 Sentinel Well B-7

TABLE B-III.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2016 RESULTS IN UNITS OF PCI/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-16 05/17/16 <2,000 Sentinel Well QC-GP-16 07/25/16 4,820 Sentinel Well QC-GP-16 12/05/16 4,290 Sentinel Well QC-GP-17 02/29/16 3,880 Sentinel Well QC-GP-17 05/17/16 10,100 Sentinel Well QC-GP-17 07/25/16 17,900 Sentinel Well QC-GP-17 12/05/16 2,030 Sentinel Well QC-GP-18 02/29/16 11,600 Sentinel Well QC-GP-18 05/16/16 18,300 Sentinel Well QC-GP-18 07/25/16 14,700 Sentinel Well QC-GP-18 12/05/16 10,600 Sentinel Well Well #1 05/26/16 <200 Production Well Well #1 10/31/16 <200 Production Well Well #5 05/26/16 <200 Production Well Well #5 10/31/16 <200 Production Well Well #7 03/01/16 <2,000 Production Well Well #7 05/18/16 <2,000 Production Well Well #7 07/27/16 <2,000 Production Well Well #7 12/06/16 <2,000 Production Well B-8

SVP-17-039, Submittal of Annual Radiological Environmental Operating Report

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