ML16141A296

Annual Radiological Environmental Operating Report for 2015

ML16141A296
Person / Time
Site:	Quad Cities
Issue date:	05/13/2016
From:	Exelon Generation Co, Teledyne Brown Engineering Environmental Services
To:	Office of Nuclear Reactor Regulation
References
Download: ML16141A296 (121)

Text

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 2015 Prepared By Teledyne Brown Engineering Environmental Services Quad Cities Nuclear Power Station Cordova, IL 61242 May 2016 Page 1of122

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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 Ill. Program Description ...................................................................................................... 5 A. Sample Collection ............................................................................................... 5 B. Sample Analysis .................................................................................................. 7 C. Data Interpretation ................................................................................:............. 8 D. Program Exceptions ............................................................................................ 9 E. Program Changes ............................................................................................. 10 IV. Results and Discussion ............................................................................................... 10 A. Aquatic Environment ......................................................................................... 10

1. Surface Water. ........................................................................................ 10

2. Ground Water ...................................................*.......................................*1*1-

3. Fish ......................................................................................................... 11

4. Sediment. ......... :....................................................................................... 12 B. Atmospheric Environment ................................................................................. 12

1. Airborne .................................................................................................. 12

• a. Air Particulates ................................. ~ ........................................... 12

b. Airborne Iodine ................................ :........................................... 13

2. Terrestrial ............................................................. ~ .................................. 13

a. Milk ....................................... .' ........................................................ 13

b. Food Products ............................................................................. 13 C. Ambient Gamma Radiation ............................................................................... 14 D. Independent Spent Fuel Storage ............................. :... :.................................... 14 E. Land Use Surve-y ............................................................................................... 14 F. Errata Data ........................................................................................................ 15 G. Summary of Results - Inter-laboratory Comp~rison Program ......................... 15 Page 3of122

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for Quad Cities Nuclear Power Station, 2015 Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Tables Table B-1 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2015 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2015 Figures Figure B-1 Quad Cities REMP S(3mpling Locations.,... 2 Mile Radius, 2015 Figure B-2 Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2015 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

Table C-1.2 Concentrations of Tritium, lron-55 and Nickel-63 in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

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

Table C-11.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

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

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

Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in

, the Vicinity of Quad Cities Nuclear Power Station, 2015.

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

Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations In Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples,.

Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015:

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

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

Table C-VIL2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

Table C-Vlll.1 Concentrations of Gamma Emitters in Food Product Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

Table C-IX.1 Quarterly OSLO Results for Quad Cities Nuclear Power Station, 2015.

Table C-IX.2 Mean Quarterly OSLO Results for the Inner Ring, Outer Ring, Other and Control Location for Quad Cities Nuclear Power Station, 2015.

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

Figures Figure C-1 Surface Water - Gross Beta - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2015.

Figure C-2 Surface Water - Tritium - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2bOO - 2015.

Figure C-3 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2015.

Figure C-4 Air Particulates - Gross Beta - Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2015.

Figure C-5 Air Particulates - Gross Beta - Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2015.

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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 - 2015.

Figure C-8 Air Particulates - Gross Beta - Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2015.

Figure C-9 Air Particulates - Gross Beta - _Stations Q-41 and Q-42 (C) Collected in the Vicinity of QCNPS, 2009 - 2015.

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

Teledyne Brown Engineering, 2015 Table D-4 ERA (a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2015 Table D-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2015 Appendix E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv Page 6of122

I. Summary and Conclusions In 2015, the Quad Cities Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 124 curies of noble gas, 1.1 BE-02 curies of fission and activation products, 29 curies of Carbon-14 and approximately 85 curies of tritium. The dose from both liquid and gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public. The results of those calculations and their comparison to the allowable limits were as follows:

NOTE: Percen't of applicable limits are for Unit 1 and Unit 2 combined (Site)

Gaseous and liquid radiation doses to members of the public at locations Location %of Applicable Estimated Age Site Distance* Direction Applicable Unit Effluents Organ Dose Group Limit (meters) (toward) Limit Noble Gas Gamma - Air Dose 2.16E-03 All 1029 NNE 1.38E-02 20 mRad Noble Gas Beta - Air Dose 3.27E-04 All 1029 NNE 8.18E-04 40 mRad Iodine, Particulate Total Body 4.29E-02 Child 1029 NNE 4.29E-01 10 mrem C-14 & Tritium Iodine, Particulate Bone 3.42E-01 Child 1029 NNE 1.14E+OO 30 mrem C-14 & Tritium Liquid Total Body 8.71E-06 Adult Mississippi River 1.45E-04 6 mrem Liquid Liver 1.30E-05 Teen Mississippi River 6.50E-05 20 mrem Skyshine Total Body 7.72E+OO All 800 N 3.09E+01 25 mrem Total Body (Gas + Liq+

40CFR190 7.76E+OO All 800 N 3.10E+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 31.0%

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

This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Quad Cities Nuclear Power Station (QCNPS) by Exelon covers the period 01January2015 through 31 December 2015. During thattime period, 1.556 analyses were performed on 1444 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.

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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 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 1-131 analyses were performed on air samples. No 1-131 was detected.

Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. No 1-131 was detected. Concentrations of naturally occurring isotopes (K-40 approximately 1200 pCi/L) were consistent with those detected in previous years. No fission or activation products were detected.

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

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

The relative comparison to control locations remains valid. OSLO 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 2015 through 31 December 2015.

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A. Objective 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 11.D-1 below).

Radioactivity is measured in curies. A curie is that amount of radioactive material needed to produce 37,000,000,000 nuclear disintegrations per second. This is an extremely large amount of radioactivity in comparison to environmental radioactivity. That is why radioactivity in the environment Page 9of122

is measured in picocuries. One picocurie is equal to one trillionth of a curie.

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

Table 11.D-1 Radiation Sources and Corresponding Doses (1)

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

Internal, inhalation (ZJ 228 Medical <3l 300 4

External, space 33 Consumer ( l 13 Internal, ingestion 29 Industrial(5l 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), inteNentional 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-? 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 Page 10of122

the air we breathe (about 228 millirem/yr). The majority of a person's annual dose results from exposure to radon and thoron in the air we breathe. These gases and their radioactive decay products arise from the decay of naturally occurring uranium, thorium and radium in the soil and building products such as brick, stone and concrete. Radon and thoron levels vary greatly with location, primarily due to changes in the concentration of uranium and thorium in the soil. Residents at some locations in Colorado, New York, Pennsylvania and New Jersey have a

• higher annual dose as a result of higher levels of radon/thoron gases in these areas. In total, these various sources of naturally-occurring radiation and radioactivity contribute to a total dose of about 311 mrem per year.

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

Ill. Program Description A. Sample Collection Samples for the QCNPS REMP were collected for Exelon Nuclear by ATI Environmental Inc. (Midwest Labs). This section describes the general sampling methods used by Environmental Inc. to obtain environmental samples for the QCNPS REMP in 2015. 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 Page 11of122

recreationally important species were collected semiannually at two locations, Q-24 and Q-29 (Control). Sediment samples composed of recently deposited substrate were collected at two locations semiannually, Q-39 and Q-40 (Control).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, and airborne iodine. Airborne iodine and particulate samples were collected and analyzed at ten locations (Q-01, Q-02, Q-03, Q-04, Q-13, Q-16, Q-37, Q-38, Q-41 and Q-42 (control)). Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The air particulate filters and air iodine samples were replaced weekly and sent to the laboratory for analysis.

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

Food products were collected annually in July at five locations (Q-Control, Q-Quad 1, Q-Quad 2, Q-Quad 3, and Q-Quad 4). Various types of broadleaf and root vegetables were collected and placed in new plastic bags, and sent to the laboratory for analysis.

• Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimeters (OSLO) were deployed and Thermoluminescent Dosimeters (TLD) were discontinued. The relative comparison to control locations remains valid. OSLO technology is different than that used in a TLD but has the same purpose (to measure direct radiation).

Each location consisted of 2 OSLO sets. The OSLO locations were placed on and around the QCNPS site as follows: An inner ring consisting of 15 locations (Q-101, Q-102, Q-103, Q-104, Q-105, Q-106, Q-107, Q-108, Q-109, Q-111, Q-112, Q-113, Q-114, Q-115 and Q-116).

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These OSLDs are located in 15 of the 16 meteorological sectors in the general area of the site boundary (approximately 0.1 - 3 miles from the site). There are no OSLDs located in the SSW sector because this sector is located over water.

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

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

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

The specific OSLO locations were determined by the following criteria:

1. The presence of relatively dense population;

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

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

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

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

B. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the QCNPS REMP in 2015 and the type of analyses. The analytical procedures used by the TBE laboratory a~e 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 pa rticu Iates.

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

3. Concentrations of tritium in ground and surface water.

4. Concentrations of 1-131 in air and milk.

5. Ambient gamma radiation levels at various site environs.

6. Concentrations of Fe-55 and 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:

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For surface water, groundwater and vegetation 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140 and La-140 were reported.

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

For air iodine, one nuclide, 1-131 was reported Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.

D. Program Exceptions For 2015 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 There were no anomalies in 2015.

Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date SW Q-33 01/01/15 - No sample; water frozen.

03/05/15 SW Q-34 01/01/15- No sample; water frozen.

03/05/15 Al Q-04 04/17/15 - Iodine cartridge lost in shipment.

SW Q-33 12/31/15 Sample collected 12/31/15. Container leaked; collector returned for new sample on 01/02/16; water frozen.

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Table D-2 LISTING OF MISSED SAMPLES (continued)

Sample Location Collection Reason

. . :l Type Code Date OSLO Q-115-2 12/31/15 OSLO found missing during quarterly change out OSLO Q-107-2, 12/31/15 OSLDs were lost in transit to Landauer.

Q-Q205-4 The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

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

IV. Results and Discussion A. Aquatic Environment

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

The following analyses were performed:

Gross Beta Samples from all locations were analyzed for concentrations of gross beta (Table C-1.1, Appendix C). Gross beta activity was detected in 19 of 20 samples. The values ranged from 2.6 to 5.3 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C). The required LLD was met.

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

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

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

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

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

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

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

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

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

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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) ran~ed from 5 to 34 E-03 pCi/m with a mean of 17 E-03 3

pCi/m . The results from the far-field locations (Group II) 3 ranged from 5 to 33 E-03 pCi/m with a mean of 17 E-03 pCi/m 3 . The results from the Control location (Group Ill) ranged from 7 to 35 E-03 pCi/m 3 with a mean of 18 E-03 3

pCi/m . Comparison of the 2015 air particulate data with previous year's data indicate no effects from the operation of Page 18of122

QCNPS. In addition comparisons of the weekly mean values for 2015 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 1-131 (Table C-Vl.1, Appendix C). All results were less than the LLD for 1-131.

2. Terrestrial

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

The following analyses were performed:

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

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

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

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

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

All of the OSLO measurements were below 30 mRem/quarter, with a range of 17 .1 to 29.0 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 2015 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:

Page 20of122

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, 11.5 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 2015.

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 DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

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

Page 21of122

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

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

The MAPEP defines three levels of performance: Acceptable (flag ="A"), Acceptable with Warning (flag ="W"), and Not

=

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

For the TBE laboratory, 129 out of 139 analyses performed met the specified acceptance criteria. Ten analyses (AP - Cr-51, U-234/233, Gr A, Sr-90; Soil Sr-90; Water - Ni-63, Sr-89, Sr-90, U natural; Vegetation Sr-90 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 Engineering's Analytics' June 2015 air particulate Cr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio of 1.30 (accepta_ble with warning) was exceeded. The air particulate sample is counted at a distance above the surface of the detector to avoid detector summing which could alter the results. Chromium-51 has the shortest half-life (27.7 days) and the lowest gamma energy (320.08 keV) of this mixed nuclide sample. Additionally, Cr-51 has only one gamma energy and also has a low intensity (9.38 gamma photons produced per 100 disintegrations). This geometry produces a Page 22 of 122

larger error for the Cr-51 and other gamma emitters as any distance from the detector decreases the counting rate and the probability of accurately detecting the nuclide energy. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would .statistically be considered acceptable. NCR 15-18

2. Teledyne Brown Engineering's MAPEP March 2015 soil Sr-90 result of 286 Total Bq/kg was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. Incomplete digestion of samples causes some of the sample to be left behind and is not present in the digested sample utilized for analysis. The procedure has been updated to include a more robust digestion using stirring during the heating phase. The MAPEP September 2014 soil Sr-90 series prior to this study was evaluated as acceptable with a result of 694 and an acceptance range of 601 -1115 Bq/kg. The MAPEP September 2015 series soil Sr-90 after this study was evaluated as acceptable with a result of 429 and an acceptance range of 298 - 553 Bq/kg. We feel the issue is specific to the March 2015 MAPEP sample. NCR 15-13

3. Teledyne Brown Engineering's MAPEP March 2015 airparticulate U-234/233 result of 0.0211 +/- 0.0120 Sq/sample was higher than the known value of 0.0155 Sq/sample, exceeding the upper ,

acceptance range of 0.0202 Sq/sample. Although evaluated as a failure, taking into consideration the uncertainty, TBE's result would overlap with the known value, which is statistically considered acceptable. MAPEP spiked the sample with significantly more U-238 activity (a found to known ratio of 0.96) than the normal U-234/233. Due to the extremely low activity, it was difficult to quantify the U-234/233. NCR 15-13

4. Teledyne Brown Engineering's MAPEP March 2015 air particulate gross alpha result of 0.448 Sq/sample was lower than the known value of 1.77 Sq/sample, exceeding the lower acceptance range of 0.53 Sq/sample. The instrument efficiency used for gross alpha is determined using a non-attenuated alpha standard. The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency. When samples contain alpha particles that are embedded in the sample media, due to the size of the alpha particle, some of the alpha particles are absorbed by the media and cannot escape to be counted. When the sample media absorbs the alpha particles this is known as self-absorption or attenuation.

The calibration must include a similar configuration/media to correct for the attenuation. In order to correct the low bias, TBE will Page 23 of 122

create an attenuated efficiency for MAPEP air particulate filters.

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

- 1.53 Sq/sample. Unlike the MAPEP samples, air particulate Gross alpha ~nalyses for power plants are not evaluated as a direct count sample. Power plant air particulate filters for gross alpha go through an acid digestion process prior to counting and the digested material is analyzed. NCR 15-13

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

6. Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Sq/sample was lower than the known value of 2.18 Sq/sample, exceeding the lower acceptance range of 1.53 Sq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for the laboratories analyzing the cross checks. TBE suspects that this may be the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity. TBE will no longer analyze the air particulate Sr-90 through MAPEP but will participate in the Analytics cross check program to perform both Sr-89 and Sr-90 in the air particulate matrix. NCR 15-21

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

Page 24of122

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

8. & 9.Teledyne Brown Engineering's ERA May water Sr-89/90 results of 45.2 and 28.0 pCi/L, respectively were lower than the known values of 63.2 and 41.9 pCi/L, respectively, exceeding the lower acceptance limits of 51.1 and 30.8 pCi/L, respectively. The yields were on the high side of the TBE acceptance range, which indicates the present of excess calcium contributed to the yield, resulting in low results. NCR 15-09

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

The technician failed to dilute the original sample, but used the entfre 12 ml sample. When the results were recalculated without the dilution and using the 12 ml aliquot, the result of 57 .16 agreed with the assigned value of 56.2. NCR 15-19 For the ATI EIML laboratory, 90 of 94 analyses met the specified acceptance criteria. Four analyses (Water- Co-57, Fe-55; AP - Co-57; Soil - Sr-90) did not meet the specified acceptance criteria for the following reasons:

1. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 water Co-57 result of 10.2 Bq/L was lower than the known value of 29.9 Bq/L, exceeding the lower control limit of 20.9 Bq/L.

The reported value should have been 27.84, which would have been evaluated as acceptable. A data entry error resulted in a non-acceptable result.

2. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 AP Co-57 result of 0.04 Sq/sample was lower than the known value of 1.51 Bq/ sample, exceeding the lower control limit of 1.06 Sq/sample. The reported value should have been 1.58 Sq/sample, which would have been evaluated as acceptable. A data entry error resulted in a non-acceptable result.

3. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 soil Sr-90 result of 231 Bq/kg was lower than the known value of 425 Bq/kg, exceeding the lower control limit of 298 Bq/kg. The incomplete separation of calcium from strontium caused a failed low result. The reanalysis result of 352 Bq/kg fell within acceptance criteria.

4. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 water Fe-55 result of 4.2 Bq/L was lower than the known Page 25 of 122

value of 13.1 Bq/L, exceeding the lower control limit of 9.2 Bq/L.

The known activity was below the routine laboratory detection limits for the available aliquot fraction.

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

Page 26 of 122

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Page 27 of 122

Intentionally left blank Page 28of122

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL SUM.MARY FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTL'\'G PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WIIB IDGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION l\1EDIUMOR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER L!MlT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER GR-B 20 4 3.6 3.9 3.9 Q-34 CONTROL 0 (PCI/LffER) (10/10) (9/10) (9/10) CAMANCHE - UPSTREAM (2.9/4.9) (2.6/5.3) (2.6/5.3) 4.4 MILES NNE OF SITE H-3 8 2000 <LLD <LLD 0 FE-55 8 200 <LLD <LLD 0

>I NI-63 8 5 <LLD <LLD 0 GAMMA 20 MN-54 15 <LLD <LLD 0 C0-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 "ti I:>>

(IQ co N

\0 0

C0-60 15 <LLD <LLD 0 N

N

• THE MEAN AND 2 STANDARD DEVIATION V ALOES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREtv1ENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2015 Th'DICATOR COl'i'TROL LOCATION WITH IDGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQlHRED MEAN (M) MEAN (M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWERLIMIT (F) (F) (F) NAME NONROUT!NE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS ZN-65 30 <LLD <LLD 0 SURFACE WATER NB-95 15 <LLD <LLD 0 (PCI/LITER)

ZR-95 30 <LLD <LLD 0 N

I I-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 "ti LA-140 15 <LLD <LLD 0

~

(1) w 0

0

...... GROUNDWATER 1-1-3 8 2000 <LLD NA 0 N (PCI/LITER)

N

• THE .MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USJNG THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS JS JNDICATED JN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAJ\1E OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDnJMOR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN(M) MEAN(M) STATION# NU!vffiEROF PATHWAY SAMPLED ANALYSIS ANAL YSfS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFO.RlvlED OF DETECTlON RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GAMMA 8 MN-54 15 <LLD NA 0 GROUND WATER C0-58 15 <LLD NA 0 (PCl/LITER)

FE-59 30 <LLD NA 0

> I w

C0-60 15 <LLD NA 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA 0 ZR-95 30 <LLD NA 0

'"d I'll O<i (1) w I-131 15 <LLD NA 0 0

N N

CS-134 15 <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTL"IG PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL .MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWERLIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS CS-137 18 <LLD NA 0 GROUNDWATER BA-140 60 <LLD NA 0 (PCI/LITER)

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

'"'d po

{JC/

(1)

C0-60 130 <LLD <LLD 0 w

N 0

N ZN-65 260 <LLD <LLD 0 N

• THE MEAN AND 2 STANDARD DEV1ATION VALVES ARE CALCULATED USJNG THE POSITIVE VALVES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED JN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2015 INDICATOR CO~!ROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED "l\IBAN (M) MEAN (M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWERLIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RAi"JGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 FISH CS-134 130 <LLD <LLD 0

> I lJl (PCI/KG WET)

CS-137 150 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 SEDIMENT GAMMA 4 (PCI/KG DRY) MN-54 NA <LLD <LLD 0

'"d l>l (JC/

(1)

VJ VJ C0-58 NA <LLD <LLD 0 0

N N

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALVES FRACTION OF DETECTABLE MEASURElvIBNTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCK.ET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTL"iG PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WTI11 HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 SEDIMENT NB-95 NA <LLD <LLD 0 (PCI/KG DRY)

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

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) .MEAN (M) MEAN (M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFOR!VIBD OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED

!VIBASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE GR-B 520 10 17 18 18 Q-42 CONTROL 0 (E-3 PCJ/CU.METER) (465/468) (52/52) (52/52) LECLAIRE (5/37) (7/35) (7/35) 8.7 :tvfILES SSW OF SITE GAMMA 40 MN-54 NA <LLD <LLD 0

-.)

I C0-58 NA <LLD <LLD 0 AIR PARTICULATE FE-59 NA <LLD <LLD 0 (E-3 PC!/CU.METER)

C0-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 "d

~

(Jq

('1) w ZR-95 NA <LLD <LLD 0 u.

0.....,

N N

CS-134 50 <LLD <LLD 0

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCA TJONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTL"JG PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWERLIMIT (F) (F) (F) NAME NONROUTlNE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS CS-137 60 <LLD <LLD 0 BA-140 NA <LLD <LLD 0

>I 00 LA-140 NA <LLD <LLD 0 AIRIODINE GAi\1MA 519 (E-3 PCI/CU.l\IBTER) I-131 70 <LLD <LLD 0 MILK 1-131 20 <LLD NA 0 (PCI/LITER)

GAMMA 20 MN-54 NA <LLD NA 0 "O

~

(1)

(.;.) C0-58 NA <LLD NA 0 0\

0 N

N FE-59 NA <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN(M) STATION# NU!vlBEROF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFOR.lVlED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS C0-60 NA <LLD NA 0 ZN-65 NA <LLD NA 0

> I

\0 NB-95 NA <LLD NA 0 MILK ZR-95 NA <LLD NA 0 (PCI/LITER)

CS-134 15 <LLD NA 0 CS-137 18 <LLD NA 0 "d

Pl (IQ Cl>

w BA-140 60 <LLD NA 0

--..i 0

N N

LA-140 15 <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NA!\1E OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTli~G PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WITH HIGHEST A1'1"NUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION# NUrvIBEROF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORl'vlED PERFORl'vlED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) IvlEASUREMENTS VEGETATION GAMMA 20 (PCI/KG WET) MN-54 NA <LLD <LLD 0 C0-58 NA <LLD <LLD 0 0

I FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0 VEGETATION ZN-65 NA <LLD <LLD 0 (PCI/KG WET)

NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 N

N 1-131 60 <LLD <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN(M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUT!NE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED lvlEASUREMENT) (LLD) MEASUREMENTS CS-134 60 <LLD <LLD 0 CS-137 80 <LLD <LLD 0 I BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 DIRECT RADIA TTON OSLD-QUARTERLY 325 NA 20.7 22.8 25.4 Q-211-2 INDICATOR 0 (MJLLIREM/QTR.) (317/317) (8/8) (4/4) 4.5 MILES SW (14.9/29.4) (18.7/29.7) (22.5/29 .4)

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

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APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS Page 41of122

Intentionally left blank Page 42 of 122

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2015 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) 3.3milesSSW C. Milk - bi-weekly I monthly Q-26 Bill Stanley Dairy (indicator) 3.1 miles ESE D. Air Particulates I Air Iodine Q-01 Onsite 1 (indicator) 0.5 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) 4.7miles 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 4.5miles NW Control Charles Leavens 9.5 miles NE H. Environmental Dosimetry - OSLO Inner Ring Q-101-1 0.6 miles N Q-101-2 0.9 miles N Q-102-1 1.3 miles NNE Q-102-3 1.4 miles NNE Q-103-1 and -2 1.2 miles NE 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 B-1 Page 43 of 122

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2015 Location Location Description Distance & Direction From Site H. Environmental Dosimetrv- OSLO (continued)

Inner Ring Q-109-1 0.9 miles S Q-109-2 1.2 miles S Q-111-1 2.6miles SW Q-111-2 2.5milesSW Q-112-1 2.5 miles WSW Q-112-2 2.2milesWSW Q-113-1 and -2 2.5miles W Q-114-1 2.1 miles WNW Q-114-2 2.5miles WNW Q-115-1 2.6miles NW Q-115-2 2.3miles NW Q-116-1 2.3miles 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 milesW Q-213-2 4.8 milesW Q-214-1 4.7milesWNW 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 4.3miles NNW 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) 4.7miles 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 B-2 Page 44of122

TABLE 8-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2015 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - OSLO (continued)

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 Page 45of122

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2015 Sample Analysis Sampling Method Analytical Procedure Number Medium Surface Water Gamma Spectroscopy Monthly composite from TBE, TBE-2007 Gamma emitting radioisotope analysis weekly grab samples Surface Water Gross Beta Monthly composite from TBE, TBE-2008 Gross Alpha andfor gross beta activity in weekly grab samples various matrices Surface Water Tritium Quarterly composite from TBE, TBE-2011 Tritium analysis in drinking water by liquid weekly grab samples scintillation Surface Water Iron and Nickel Quarterly composite from TBE, TBE-2006 lron-55 in various matrices weekly grab samples TBE, TBE-2013 Radionickel in various matrices Ground Water Gamma 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 Fish Gamma Spectroscopy Semi-annual samples TBE-2007 Gamma emitting radioisotope analysis collected via electroshocking or other techniques Sediment Gamma Spectroscopy Semi-annual grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis Air Particulates Gross Beta One-week composite of TBE, TBE-2008 Gross Alpha andfor gross beta activity in continuous air sampling various matrices through glass fiber filter paper Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2007 Gamma emitting radioisotope analysis each station Air Iodine Gamma Spectroscopy Weekly composite of TBE, TBE-2007 Gamma emitting radioisotope analysis continuous air sampling through charcoal filter Milk 1-131 Bi-weekly grab sample TBE, TBE-2012 Radioiodine in various matrices when cows are on pasture.

Monthly all other times Milk Gamma Spectroscopy Bi-weekly grab sample TBE, TBE-2007 Gamma emitting radioisotope analysis when cows are on pasture.

Monthly all other times Food Products Gamma Spectroscopy Annual grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis OSLO Optically Stimulated Quarterly OSLDs Landauer Incorporated Luminescence comprised of two Ab03:C Dosimetry Landauer Incorporated elements B-4 Page 46 of 122

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APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY Page 49 of 122

Table C-1.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION Q-33 Q-34 PERIOD 01/03/14 - 01/30/14 (1) (1) 02/07/14 - 02/28/14 (1) (1) 03/12/15 - 03/27/15 3.4 +/- 1.5 5.3 +/- 1.7 04/03/15 - 04/30/15 3.6 +/- 1.6 3.3 +/- 1.6 05/07/15 - 05/29/15 3.1 +/- 1.6 2.6 +/- 1.6 06/04/15 - 06/26/15 3.7 +/- 1.7 4.4 +/- 1.8 07/02/15 - 07/30/15 2.9 +/- 1.6 3.2 +/- 1.6 08/07/15 - 08/27/15 3.4 +/- 1.8 3.5 +/- 1.8 09/03/15 - 09/24/15 3.6 +/- 1.6 < 2.3 10/01/15 - 10/29/15 4.7 +/- 2.1 4.2 +/- 2.0 11/05/15 - 11/27/15 3.3 +/- 1.7 4.6 +/- 2.1 12/04/15 - 12/31/15 4.9 +/- 1.5 4.5 +/- 1.5 MEAN 3.6 +/- 1.3 3.9 +/- 1.7 Table C-1.2 CONCENTRATIONS OF TRITIUM, IRON, AND NICKEL IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION H-3 (DIST) FE-55 Nl-63 PERIOD Q-33 03/12/15 - 03/27/15 < 197 < 118 < 4.2 04/03/15 - 06/26/15 < 189 < 177 < 3.9 07/02/15 - 09/24/15 < 192 < 116 < 3.9 10/01/15 - 12/25/15 < 189 < 156 < 3.3 MEAN Q-34 03/12/15 - 03/27/15 < 169 < 141 < 4.0 04/03/15 - 06/26/15 < 182 < 111 < 3.8 07/02/15 - 09/24/15 < 199 < 174 < 4.0 10/01/15 - 12/31/15 < 186 < 129 < 3.3 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-1 Page 51of122

Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER + 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-33 01/03/15 - 01/30/15 (1) 02/07/15 - 02/28/15 (1) 03/12/15 - 03/27/15 < 2 <2 <4 <2 <3 <2 < 3 < 11 < 1 <2 < 18 <5 04/03/15 - 04/30/15 < 2 <3 < 6 <2 <5 < 3 < 5 < 15 < 2 <2 < 26 <7 05/07/15 - 05/29/15 <2 <3 < 6 < 3 <5 < 3 < 5 < 12 < 2 <2 < 21 <7 06/04/15 - 06/26/15 <4 < 5 < 9 < 4 < 8 < 5 < 9 < 15 < 5 < 5 < 30 < 8 07/02/15 - 07/30/15 < 2 <2 < 5 <2 <4 <2 <4 < 12 <2 < 2 < 21 <6 08/07/15 - 08/27/15 <4 <4 < 10 < 5 <9 < 5 < 8 < 14 <4 < 5 < 32 < 10 09/03/15 - 09/24/15 < 13 < 8 < 19 < 8 < 21 <8 < 14 < 13 < 8 < 9 < 44 < 12 10/01/15 - 10/29/15 < 2 < 2 <4 <2 <3 <2 <3 < 9 <2 <2 < 16 < 5 11/05/15 - 11/27/15 < 5 < 5 < 14 < 7 < 10 <6 < 10 < 14 < 5 <6 < 26 < 11 12/04/15 - 12/25/15 < 3 <4 < 7 <4 <5 <3 <6 < 14 < 3 < 3 < 30 < 8

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Q-34 01/03/15 - 01/30/15 (1) 02/07/15 - 02/28/15 (1) 03/12/15 - 03/27/15 < 1 < 1 < 3 < 1 < 2 < 1 < 3 < 9 < 1 <2 < 15 < 5 04/03/ 15 - 04/30/ 15 < 3 <3 <6 < 3 <5 < 3 <6 < 14 <2 < 3 < 27 < 9 05/07/15 - 05/29/15 < 2 <2 < 5 <2 <4 < 2 <4 < 11 < 2 <2 < 21 < 7 06/04/15 - 06/26/15 < 5 <4 < 10 < 5 < 8 < 5 < 8 < 14 <4 < 5 < 36 < 9 07/02/15 - 07/30/15 <2 <2 <4 <2 <4 <2 <4 < 10 < 2 <2 < 18 < 5 08/07/15 - 08/27/15 <4 < 5 < 10 <4 < 9 <6 < 9 < 15 < 4 < 5 < 28 < 11 09/03/15 - 09/24/15 < 8 < 8 < 13 < 9 < 14 < 5 < 13 < 11 < 5 < 7 < 34 < 11 10/01/15 - 10/29/15 <2 <2 < 5 <2 <4 <2 <4 < 10 < 2 < 2 < 18 < 6 11/05/15 - 11/27/15 < 5 < 5 < 9 <4 < 8 < 5 < 10 < 12 < 5 < 6 < 37 < 9 12/04/15 - 12/31/15 < 5 < 5 < 10 < 5 < 9 < 5 <8 < 14 < 5 <4 < 30 < 12 MEAN

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Table C-11.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION Q-35 Q-36 PERIOD 01/09/15 - 01/09/15 < 170 < 173 04/10/15 - 04/10/15 < 194 < 195 07/09/15 - 07/09/15 < 180 < 182 10/08/15 - 10/08/15 < 198 < 196 MEAN C-3 Page 53 of 122

Table C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-35 01/09/15 - 01/09/15 < 4 < 5 < 10 < 5 < 9 <4 < 8 < 13 < 5 < 5 < 31 <8 04/10/15 - 04/10/15 < 5 < 6 < 12 < 6 < 11 <6 < 10 < 15 < 5 < 5 < 30 < 15 07/09/15 - 07/09/15 <4 <4 < 10 < 5 < 8 < 5 < 8 < 10 < 5 < 5 < 28 < 9 10/08/15 - 10/08/15 < 6 < 7 < 17 < 8 < 15 < 9 < 12 < 13 < 6 < 8 < 41 < 12 MEAN Q-36 01/09/15 - 01/09/15 <4 <4 < 8 <4 < 7 <4 < 8 < 13 < 5 <4 < 28 <6 04/10/15 - 04/10/15 < 4 < 4 < 9 < 5 < 8 < 5 < 8 < 13 <4 <4 < 27 <9 07/09/15 - 07/09/15 < 5 < 5 < 11 < 5 < 9 <6 < 10 < 10 < 5 < 6 < 25 <8 10/08/15 - 10/08/15 < 5 < 6 < 13 < 7 < 13 <7 < 10 < 12 < 6 < 7 < 30 < 10 MEAN

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Table C-111.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PC/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-24 Channel Catfish 05/27/15 < 73 < 69 < 155 < 80 < 75 < 81 < 150 < 73 < 67 < 558 < 127 Freshwater Drum 05/27/15 < 52 < 76 < 122 < 74 < 155 < 90 < 148 < 66 < 78 < 620 < 243 Common Carp 10/14/15 < 59 < 35 < 107 < 57 < 144 < 47 < 103 < 46 < 58 < 366 < 118 Largemouth Bass 10/14/15 < 55 < 51 < 138 < 61 < 116 < 72 < 137 < 60 < 63 < 322 < 86 MEAN Q-29 Quill back 05/27/15 < 80 < 82 < 154 < 73 < 133 < 99 < 107 < 73 < 92 < 542 < 80 Walleye 05/27/15 < 61 < 52 < 129 < 41 < 120 < 67 < 129 < 53 < 61 < 429 < 113 n

I Common Carp 10/14/15 < 89 < 78 < 139 < 92 < 169 < 114 < 157 < 95 < 91 < 383 < 120 Vl Shorthead Redhorse 10/14/15 < 58 < 44 < 106 < 63 < 97 < 66 < 110 < 55 < 61 < 318 < 96 MEAN

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PC/KG DRY+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-39 05/16/15 < 43 < 51 < 134 < 44 < 106 < 52 < 94 < 38 < 48 < 352 < 93 10/22/15 < 51 < 42 < 105 < 42 < 139 < 55 < 109 < 49 < 83 < 344 < 118 MEAN Q-40 05/16/15 < 43 < 53 < 119 < 40 < 116 < 57 < 93 < 47 < 53 < 360 < 114 10/22/15 < 86 < 79 < 202 < 101 < 147 < 106 < 182 < 85 < 129 < 566 < 173 MEAN n

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Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP Ill PERIOD Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 01/01/15 - 01/09/15 23 +/- 5 26 +/- 5 27 +/-5 26 +/- 5 31 +/- 5 24 +/- 4 21 +/- 5 15 +/-4 11 +/- 4 30 +/- 5 01/09/15 - 01/15/15 19 +/- 4 24 +/- 5 27 +/- 5 25+/-5 22+/-5 23+/-5 20 +/- 4 20 +/-4 23 +/- 5 24 +/- 5 01/15/15 - 01/22/15 15 +/- 4 17 +/- 4 17 +/- 4 16 +/- 4 22 +/- 5 17 +/- 4 17 +/- 4 17 +/- 4 20 +/- 4 25 +/- 5 01/22/15 - 01/29/15 8 +/-4 14 +/- 4 15 +/- 4 12+/-4 11+/-4 11+/-4 14 +/- 4 11 +/-4 12 +/- 4 17 +/- 4 01/29/15 - 02/05/15 16 +/- 4 20 +/- 4 19 +/-4 20 +/- 4 19 +/- 4 15 +/- 4 15 +/- 4 18 +/-4 18 +/- 4 18 +/- 4 02105/15 - 02/12115 15 +/- 4 24 +/- 5 26 +/-5 24 +/- 5 24 +/- 5 22 +/- 5 20 +/- 5 21 +/-5 24 +/- 5 25 +/- 5 02/12/15 - 02/20/15 19 +/- 4 27 +/-5 28 +/-5 29 +/- 5 28 +/- 4 24 +/- 4 26 +/- 5 25 +/-5 31 +/- 5 28 +/- 4 02120/15 - 02/26/15 23 +/- 4 33 +/- 5 29 +/-5 31 +/- 5 27 +/- 5 30 +/- 5 25 +/- 5 27 +/-5 37 +/- 6 35 +/- 6 02/26/15 - 03/05/15 19 +/- 4 21 +/-4 16 +/-4 21 +/- 4 18 +/- 4 16 +/- 4 15 +/- 4 23 +/-4 23 +/- 4 22 +/- 4 03/05/15 - 03/12115 12 +/- 3 17 +/- 4 17 +/- 4 15+/-4 13+/-4 11+/-4 12 +/- 3 14 +/-3 17 +/- 4 18 +/- 4 03/12/15 - 03/19/15 13 +/- 5 20 +/-5 19 +/- 5 16 +/- 5 17 +/- 4 16 +/- 4 15 +/- 5 14 +/- 4 19 +/- 4 21 +/- 5 03/19/15 - 03/27/15 15 +/- 4 12 +/-4 11 +/- 4 16 +/- 4 11 +/- 3 12 +/- 3 11 +/-4 12 +/-4 15 +/- 4 15 +/- 4 03/27/15 - 04/03/15 13 +/- 4 15 +/- 4 14 +/-4 20 +/- 4 14 +/- 4 12 +/- 4 13 +/-4 14 +/- 4 15 +/- 4 13 +/- 4 04/03/15 - 04/10/15 11 +/- 4 14 +/-4 14 +/-4 14 +/- 4 10 +/- 3 13 +/- 4 10 +/-3 12 +/- 4 16 +/- 4 17 +/- 4 04/10/15 - 04/17/15 16 +/- 4 14 +/-4 15 +/-4 15 +/- 4 14 +/- 4 16 +/- 4 9 +/- 4 16 +/-4 18 +/- 5 14 +/- 4 04/17/15 - 04/23/15 12 +/- 4 10 +/- 3 11 +/-3 9 +/- 3 13 +/- 4 -12 +/- 4 13 +/-4 10 +/- 3 12 +/- 4 12 +/- 4 04/23/15 - 05/01/15 12 +/- 3 9 +/-3 11 +/-3 10 +/- 3 15 +/- 4 15 +/- 4 10 +/-3 10 +/- 3 11 +/- 3 12 +/- 3 05/01/15 - 05/07/15 7+/-4 10 +/- 4 9 +/-4 10+/-4 10+/-4 9+/-4 6 +/-4 7 +/- 4 11 +/- 4 11 +/- 4 05/07/15 - 05/15/15 8 +/-3 10 +/-3 7 +/-3 9+/-3 11+/-3 9+/-3 6 +/-3 9 +/- 3 10 +/- 3 12 +/- 3 05/15/15 - 05/21/15 7 +/-4 6 +/-3 8+/-4 11 +/- 4 <7 < 6 6 +/- 3 7 +/- 3 7 +/- 4 7 +/- 4 05/21/15 - 05/29/15 12 +/- 4 11 +/-4 12 +/- 4 15 +/- 4 14 +/- 4 12 +/- 3 11 +/-4 12 +/- 4 14 +/- 4 12 +/- 3 05/29/15 - 06/04/15 9 +/-3 10 +/-3 11 +/- 4 13 +/- 4 12 +/- 4 14 +/- 4 11 +/-3 9 +/-3 8 +/- 4 15 +/- 4 06/04/15 - 06/11/15 13 +/- 4 15 +/-4 14 +/- 4 15 +/- 4 15 +/- 4 15 +/- 4 10 +/- 4 15 +/- 4 18 +/- 4 16 +/- 4 06/11 /15 - 06/18/15 6 +/- 3 7 +/- 3 8 +/-3 10 +/- 3 10 +/- 4 7 +/- 3 5 +/-3 8 +/-3 8 +/- 3 9 +/- 3 06/18/15 - 06/26/15 9 +/- 3 12 +/- 3 9 +/- 3 13 +/- 3 15 +/- 4 10 +/- 3 8+/-3 10 +/- 3 15 +/- 3 13 +/- 3 06/26/15 - 07/02115 11 +/- 4 14 +/- 4 12 +/- 4 12 +/- 4 10 +/- 4 13 +/- 4 10 +/- 4 10 +/- 4 12 +/- 4 15 +/- 4 07/02/15 - 07/09/15 12 +/- 4 11 +/- 4 17 +/- 4 14 +/- 4 15 +/- 4 12 +/- 4 10 +/- 3 12 +/- 4 11 +/- 4 15 +/- 4 07/09/15 - 07/17/15 5 +/-3 15 +/- 4 16 +/- 4 16 +/- 4 13 +/- 3 15 +/- 4 13 +/- 4 14 +/- 4 15 +/- 4 15 +/- 4 07/17/15 - 07/23/15 11 +/- 4 13 +/- 4 13 +/- 4 12 +/- 4 17 +/- 5 14 +/- 5 7 +/-4 10 +/- 4 13 +/- 5 11 +/- 4 07/23/15 - 07/31/15 13 +/- 4 20 +/- 4 18 +/- 4 15 +/- 4 20 +/- 4 18 +/- 4 13 +/- 4 15 +/- 4 15 +/- 4 18 +/- 4 07/31/15 - 08/07/15 13 +/- 4 13 +/- 4 19 +/- 5 23 +/- 5 20 +/- 4 18 +/- 4 13 +/- 4 19 +/- 5 14 +/- 4 19 +/- 4 08/07/15 - 08/14/15 16 +/- 4 22 +/- 5 21 +/- 4 13 +/- 4 21 +/- 5 < 5 12 +/- 4 22 +/- 5 16 +/- 4 18 +/- 4 08/14/15 - 08/21/15 17 +/- 4 20 +/- 4 27 +/- 5 17 +/- 4 18 +/- 4 33 +/- 5 15 +/- 4 12 +/- 4 17 +/- 4 19 +/- 4 08/21/15 - 08/27/15 10 +/- 4 16 +/- 4 16 +/- 4 15+/-4 12+/-5 11+/-5 10 +/- 4 15 +/- 4 10 +/- 5 10 +/- 4 08/27/15 - 09/03/15 27 +/- 5 34 +/- 6 27 +/- 5 27+/-5 32+/-5 30+/-5 21 +/- 5 31 +/- 5 25 +/- 5 32 +/- 5 09/03/15 - 09/11/15 22 +/- 4 24 +/- 4 28 +/- 5 22 +/- 4 30 +/- 5 27 +/- 4 20 +/- 4 25 +/- 4 25 +/- 4 24 +/- 4 09/11/15 - 09/17/15 19 +/- 4 20 +/- 4 19 +/- 4 19 +/- 4 23 +/- 5 18 +/- 5 8+/-3 18 +/- 4 21 +/- 5 20 +/- 5 09/17/15 - 09/24/15 11 +/- 4 14 +/- 4 15 +/- 4 13 +/- 4 17 +/- 4 18 +/- 4 10 +/- 4 15 +/- 4 11 +/- 4 14 +/- 4 09/24/15 - 10/01/15 18 +/- 4 10 +/- 3 18 +/- 4 16 +/- 3 16 +/- 4 22 +/- 4 16 +/- 3 20 +/- 4 23 +/- 4 22 +/- 4 10/01/15 - 10/08/15 17 +/- 4 13 +/- 4 23 +/- 5 22 +/- 5 14 +/- 4 15 +/- 4 12 +/- 4 14 +/- 4 17 +/- 4 14 +/- 4 10/08/15 - 10/16/15 13 +/- 4 16 +/- 4 12 +/- 4 11+/-4 18+/-4 18+/-4 14 +/- 4 13 +/-4 13 +/- 3 12 +/- 3 10/16/15 - 10/23/15 28 +/- 5 26 +/- 5 30 +/- 5 29 +/- 5 31 +/- 5 26 +/- 5 25 +/- 5 30 +/- 5 29 +/- 5 26 +/- 5 10/23/15 - 10/29/15 18 +/- 4 17 +/- 4 16 +/- 4 16 +/- 4 18 +/- 5 14 +/- 4 15 +/- 3 16 +/- 4 15 +/- 4 17 +/- 4 10/29/15 - 11/05/15 13 +/- 4 22 +/- 5 17 +/- 4 17 +/- 4 18 +/- 4 18 +/- 4 17 +/- 4 18 +/-4 20 +/- 4 18 +/- 4 11/05/15 - 11/13/15 23 +/- 5 21 +/- 4 26 +/- 5 24 +/- 5 23 +/- 4 22 +/- 4 21 +/- 5 30 +/-5 24 +/- 4 22 +/- 4 11/13/15 - 11/19/15 13 +/- 3 14 +/- 3 8 +/- 3 14 +/- 3 16 +/- 4 19 +/- 5 13 +/- 3 16 +/-4 20 +/- 5 19 +/- 5 11/19/15 - 11/27/15 15 +/- 5 14 +/- 5 19 +/- 5 13 +/- 4 12 +/- 4 14 +/- 4 15 +/- 5 15 +/-5 15 +/- 4 15 +/- 4 11/27/15 - 12/04115 19 +/-4 19 +/- 4 8 +/-3 21 +/- 4 22 +/- 4 19 +/- 4 18 +/- 4 21 +/-4 22 +/- 4 20 +/- 4 12104115 - 12/10115 28 +/-5 26 +/- 5 24 +/-4 28 +/- 5 31 +/- 5 31 +/- 5 30 +/- 5 26 +/-5 31 +/- 5 31 +/- 5 12110115 - 12117/15 13 +/-4 17 +/- 4 12 +/-4 14 +/- 4 14 +/- 4 14 +/- 4 16 +/- 4 12 +/- 4 14 +/- 4 11 +/- 4 12/17/15 - 12/25/15 25 +/- 5 29 +/- 5 30 +/-5 28+/-5 30+/-5 27+/-4 27 +/- 5 18 +/- 4 29 +/- 5 27 +/- 5 12125/15 - 12/31/15 19 +/-4 19 +/- 4 22 +/-4 20 +/- 4 15 +/- 4 12 +/- 4 17 +/- 4 26 +/-5 10 +/- 4 17 +/- 5 MEAN 15 +/- 11 17 +/- 13 17 +/- 13 17+/-12 18+/-13 17+/-13 14 +/- 12 16 +/- 12 17 +/- 13 18 +/- 13 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-7 Page 57 of 122

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, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA GROUP I - NEAR-SITE LOCATIONS GROUP II - FAR-FIELD LOCATIONS GROUP Ill - CONTROL LOCATION COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/-

PERIOD 2SD PERIOD 28D PERIOD 28D 01/01/15 - 01/29/15 8 27 19 +/- 12 01/01/15 - 01/30/15 11 31 18 +/- 11 01/01/15 - 01/29/15 17 30 24 +/- 11 01/29/15 - 02/26/15 15 33 24 +/- 11 01/29/15 - 02/27/15 15 37 24 +/- 11 01/29/15 - 02/26/15 18 35 26 +/- 14 02/26/15 - 04/03/15 11 21 16 +/- 6 02/26/15 - 04/03/15 11 23 15 +/- 7 02/26/15 - 04/03/15 13 22 18 +/- 8 04/03/15 - 05/01/15 9 16 12 +/- 5 04/03/15 - 05/01/15 9 18 13 +/- 5 04/03/15 - 04/30/15 12 17 14 +/- 5 05/01/15 - 05/29/15 6 15 10 +/- 5 04/30/ 15 - 05/29/15 6 14 9 +/- 5 04/30/15 - 05/29/15 7 12 11 +/- 4 05/29/15 - 07/02/15 6 15 11 +/- 5 05/29/15 - 07/03/15 5 18 11 +/- 6 05/29/15 - 07/02/15 9 16 14 +/- 6 07/02/15 - 07/31/15 5 20 14 +/- 7 07/02/15 - 08/01/15 7 20 13 +/- 6 07/02/15 - 07/31/15 11 18 15 +/- 6 07/31/15 - 09/03/15 10 34 20 +/- 12 07/31/15 - 09/04/15 10 36 19 +/- 15 07/31/15 - 09/03/15 10 32 20 +/- 16 09/03/15 - 10/01 /15 10 28 18 +/- 10 09/03/15 - 10/03/15 8 30 19 +/- 11 09/03/15 - 10/01/15 14 24 20 +/- 9 10/01/15 - 10/29/15 11 30 19 +/- 13 10/01/15 - 10/31/15 12 31 18 +/- 12 10/01/15 - 10/29/15 12 26 17 +/- 12 10/29/15 - 12/04/15 8 26 17 +/- 10 10/29/15 - 12/04/15 12 30 19 +/- 8 10/29/15 - 12/04/15 15 22 19 +/- 5 12/04/15 - 12/31/15 12 30 22 +/- 12 12/04/15 - 01/01/16 10 31 21 +/- 16 12/04/15 - 12/31/15 11 31 22 +/- 18 nI

°" 01/02/15 - 01/01/16 5 34 17 +/- 12 01/01/15 - 01/01/16 5 37 17 +/- 13 01/01/15 - 12/31/15 7 35 18 +/- 13

'"d

~C1l Vl

°"

0.....,

N N

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-01 01/02/15 - 04/03/15 < 3 < 5 < 14 <4 <7 <5 < 10 <4 <4 < 156 < 44 04/03/15 - 07/03/15 < 2 < 3 < 6 < 2 <4 <3 < 5 < 2 < 2 < 65 < 16 07/03/15 - 10/03/15 < 2 <4 < 9 <2 <6 < 4 <7 < 3 < 2 < 77 < 25 10/03/15 - 01/01/16 < 2 < 2 <4 < 1 < 3 <2 < 3 < 1 < 1 < 11 < 9 MEAN Q-02 01/02/15 - 04/03/15 < 3 < 5 < 9 <4 < 9 <6 <8 <3 < 3 < 147 < 46 04/03/15 - 07/03/15 < 3 < 3 < 11 < 3 < 7 < 3 < 6 < 2 <2 < 94 < 41 07/03/15 - 10/03/15 < 3 < 3 < 10 < 2 < 3 <3 < 6 < 3 < 2 < 76 < 40 10/03/15 - 01/01/16 < 3 <2 <6 < 2 < 5 <3 < 5 <2 < 2 < 25 < 8 MEAN

(")

I

\0 Q-03 01 /02/15 - 04/03/15 < 3 < 5 < 11 <3 < 8 <4 < 7 <3 < 3 < 144 < 43 04/03/15 - 07/03/15 < 2 < 3 < 8 < 2 < 6 <4 < 5 < 2 < 2 < 73 < 26 07/03/15 - 10/03/15 < 3 <4 < 15 <2 < 9 < 4 < 8 <4 < 4 < 107 < 38 10/03/15 - 01/01/16 < 1 < 2 < 5 < 1 <2 <2 < 3 < 2 <2 < 23 < 10 MEAN Q-04 01/02/15 - 04/03/15 < 3 <4 < 7 < 2 < 6 <4 < 6 < 3 < 2 < 107 < 42 04/03/15 - 07/03/15 <4 < 5 < 14 < 5 <7 < 6 < 11 <4 < 4 < 119 < 46 07/03/15 - 10/03/15 < 3 < 3 < 7 < 2 <8 <4 < 6 < 2 < 2 < 79 < 33 10/03/15 - 01/01 /16 < 3 <4 <8 < 3 <4 < 3 < 5 < 3 < 2 < 29 < 7 MEAN Q-13 01/01/15 - 04/03/15 < 5 < 6 < 12 <6 < 9 < 8 < 14 < 4 < 5 < 162 < 63 04/03/15 - 07/02/15 < 3 <4 < 9 <3 < 8 <4 < 8 < 3 < 3 < 77 < 39 "t:i I>>

(Jq 07/02/15 - 10/01/15 < 2 <4 < 10 < 3 < 5 <4 < 7 < 3 < 2 < 98 < 30 (I) 10/08/15 - 12/31/15 < 3 <3 <4 < 3 < 7 <3 < 5 < 3 < 2 < 34 < 11 VI

\0 0

....., MEAN N

N

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-16 01/01/15 - 04/03/15 <4 <4 < 12 < 3 < 9 < 5 < 8 < 3 < 3 < 159 < 55 04/03/15 - 07/02/15 <4 < 5 < 13 < 3 < 8 < 5 < 8 < 4 < 3 < 128 < 40 07/02/15 - 10/01/15 < 3 <4 < 8 <2 < 5 < 3 < 6 < 2 < 2 < 75 < 34 10/08/15 - 12/31/15 < 1 < 2 < 6 <2 <4 < 3 <4 < 2 <2 < 25 < 5 MEAN Q-37 01/02/15 - 04/03/15 <4 < 6 < 19 <4 < 11 < 7 < 10 <5 <4 < 197 < 66 04/03/15 - 07/03/15 <2 < 3 < 8 < 3 <5 < 3 < 5 <2 < 2 < 71 < 26 07/03/15 - 10/03/15 < 3 <4 < 10 < 3 < 8 <4 < 6 < 3 < 3 < 111 < 27 10/03/15 - 01/01/16 <2 < 2 < 3 <2 <4 < 3 < 5 < 2 <2 < 34 < 8 MEAN n

0 I

Q-38 01/02/15 04/03/15 04/03/15 07/03/15

<4

< 2 5

2 14 7

2 2

< 11

<4

<4

<2

< 9

<5

< 3

< 2

<4

<2 175 65 45 29 07/03/15 - 10/03/15 < 1 < 0 < 2 < 3 <5 < 1 <4 < 1 < 0 < 65 < 22 10/03/15 - 01/01/16 < 2 < 2 < 7 < 3 <5 <2 < 5 <2 < 2 < 24 < 5 MEAN Q-41 01/01/15 - 04/03/15 < 3 <4 < 13 < 3 < 7 <4 < 9 < 3 < 3 < 145 < 66 04/03/15 - 07/02/15 < 2 <4 < 7 < 2 < 5 <4 < 5 < 2 < 2 < 110 < 49 07/02/15 - 10/01/15 < 3 < 5 < 10 < 3 < 10 < 5 < 10 <4 < 3 < 141 < 50 10/08/15 - 12/31/15 < 1 < 2 < 2 < 2 <4 <2 <2 < 1 < 1 < 18 < 6 MEAN Q-42 01/01/15 - 04/03/15 <4 <6 < 12 <4 < 12 <6 < 11 < 5 < 4 < 202 < 33 04/03/15 - 07/02/15 < 3 <4 < 11 <3 < 6 <4 <6 < 2 < 3 < 77 < 25

'"d 07/02/15 - 10/01/15 <2 <4 < 11 <2 < 5 <4 <5 <2 < 2 < 71 < 57 (Jq (1) 10/08/15 - 12/31/15 < 1 <2 < 5 <2 < 5 <3 <2 <2 < 2 < 33 < 17 0\

0 0

....., MEAN N

N

Table C-Vl-.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP I GROUP II I GROUP Ill PERIOD Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 61161115 - 61/69115 < 33 < 61 < 59 < 59 < 65 < 34 < 68 < 68 < 63 < 61 01/09/15 - 01/15/15 < 21 < 53 < 52 < 52 < 63 < 65 < 29 < 53 < 67 < 64 01/15/15 - 01/22/15 < 17 < 41 < 39 < 39 < 45 < 21 < 33 < 33 < 39 < 38 01/22/15 - 01/29/15 < 18 < 47 < 45 < 45 < 48 < 20 < 45 < 45 < 49 < 48 01/29/15 - 02/05/15 < 22 < 50 < 49 < 49 < 54 < 46 < 41 < 23 < 48 < 46 02/05/15 - 02/12/15 < 24 < 63 < 61 < 61 < 67 < 61 < 56 < 56 < 27 < 62 02/12/15 - 02/20/15 < 23 < 53 < 52 < 52 < 42 < 14 < 48 < 48 < 41 < 39 02/20/15 - 02/26/15 < 22 < 51 < 50 < 50 < 63 < 54 < 43 < 43 < 55 < 30 02/26/15 - 03/05/15 < 23 < 58 < 56 < 56 < 60 < 22 < 50 < 50 < 55 < 53 03/05/15 - 03/12/15 < 20 < 53 < 51 < 51 < 68 < 31 < 42 < 42 < 58 < 56 03/12/15 - 03/19/15 < 22 < 57 < 55 < 55 < 51 < 23 < 59 < 59 < 56 < 55 03/19/15 - 03/27/15 < 20 < 8 < 19 < 19 < 16 < 7 < 20 < 20 < 18 < 17 03/27/15 - 04/03/15 < 22 < 56 < 54 < 54 < 57 < 22 < 51 < 51 < 53 < 53 04/03/15 - 04/10/15 < 20 < 52 < 50 < 50 < 47 < 20 < 51 < 51 < 49 < 48 04/10/15 - 04/17/15 < 64 < 64 < 62 < 62 < 25 < 49 < 48 < 48 < 51 < 21 04/17/15 - 04/23/15 < 57 < 57 < 55 (1) < 65 < 36 < 48 < 48 < 60 < 57 04/23/15 - 05/01/15 < 44 < 44 < 42 < 42 < 65 < 66 < 62 < 53 < 58 < 56 05/01/15 - 05/07/15 < 61 < 61 < 59 < 23 < 69 < 69 < 63 < 38 < 43 < 42 05/07/15 - 05/15/15 < 55 < 55 < 53 < 53 < 18 < 20 < 24 < 22 < 19 < 19 05/15/15 - 05/21/15 < 63 < 63 < 61 < 62 < 35 < 46 < 62 < 41 < 37 < 40 05/21/15 - 05/29/15 < 58 < 58 < 56 < 48 < 41 < 40 < 62 < 62 < 53 < 52 05/29/15 - 06/04/15 < 37 < 38 < 36 < 53 < 67 < 25 < 53 < 53 < 68 < 66 06/04/15 - 06/11/15 < 55 < 55 < 53 < 53 < 68 < 68 < 65 < 62 < 69 < 65 06/11/15 - 06/18/15 < 49 < 49 < 47 < 52 < 59 < 58 < 52 < 57 < 65 < 64 06/18/15 - 06/26/15 < 62 < 62 < 60 < 60 < 63 < 61 < 60 < 48 < 48 < 49 06/26/15 - 07/02/15 < 57 < 58 < 56 < 56 < 54 < 52 < 48 < 58 < 62 < 63 07/02/15 - 07/09/15 < 15 < 38 < 37 < 37 < 41 < 17 < 37 < 37 < 40 < 39 07/09/15 - 07/17/15 < 61 < 62 < 60 < 59 < 23 < 41 < 45 < 45 < 41 < 22 07/17/15 - 07/23/15 < 53 < 53 < 22 < 51 < 64 < 23 < 48 < 48 < 59 < 58 07/23/15 - 07/31/15 < 55 < 30 < 53 < 53 < 58 < 52 < 49 < 19 < 52* < 52 07/31/15 - 08/07/15 < 28 < 64 < 64 < 63 < 57 < 52 < 33 < 60 < 52 .. < 53 08/07/15 - 08/14/15 < 53 < 52 < 53 < 53 < 22 < 53 < 52 < 52 < 54 < 22 08/14/15 - 08/21/15 < 14 < 36 < 36 < 36 < 35 < 66 < 70 < 70 < 67 < 28 08/21/15 - 08/27/15 < 34 < 13 < 33 < 33 < 4a < 55 < 38 < 38 < 23 < 55 08/27/15 - 09/03/15 < 67 < 65 < 65 < 65 < 26 < 64 < 69 < 69 < 25 < 65 09/03/15 - 09/11/15 < 36 < 35 < 35 < 35 < 12 < 40 < 45 < 45 < 40 < 17 09/11/15 - 09/17/15 < 36 < 19 < 35 < 35 < 44 < 59 < 49 < 49 < 59 < 30 09/17/15 - 09/24/15 < 14 < 36 < 36 < 36 < 38 < 51 < 49 < 49 < 51 < 21 09/24/15 - 10/01/15 < 18 < 44 < 44 < 44 < 63 < 61 < 44 < 44 < 61 < 25 10/01/15 - 10/08/15 < 11 < 28 < 28 < 28 < 32 < 13 < 28 < 28 < 32 < 32 10/08/15 - 10/16/15 < 26 < 66 < 66 < 66 < 64 < 28 < 70 < 70 < 66 < 69 10/16/15 - 10/23/15 < 18 < 44 < 44 < 44 < 39 < 15 < 42 < 42 < 35 < 37 10/23/15 - 10/29/15 < 13 < 33 < 33 < 33 < 53 < 61 < 39 < 39 < 26 < 62 10/29/15 - 11105/15 < 12 < 30 < 30 < 30 < 28 < 18 < 48 < 48 < 43 < 45 11/05/15 - 11/13/15 < 26 < 60 < 59 < 59 < 53 < 22 < 68 < 62 < 54 < 55 11/13/15 - 11/19/15 < 13 < 32 < 32 < 32 < 52 < 27 < 40 < 40 < 63 < 65 11/19/15 - 11/27/15 < 28 < 70 < 70 < 70 < 54 < 17 < 56 < 56 < 41 < 44 11/27/15 - 12/04/15 < 67 < 65 < 25 < 65 < 66 < 51 < 51 < 51 < 21 < 52 12/04/15 - 12/10/15 < 44 < 17 < 43 < 43 < 55 < 57 < 47 < 19 < 57 < 59 12/10/15 - 12/17/15 < 34 < 33 < 13 < 33 < 36 < 42 < 40 < 40 < 18 < 43 12/17/15 - 12/25/15 < 63 < 24 < 61 < 61 < 55 < 25 < 70 < 70 < 60 < 63 12/25/15 - 12/31/15 < 16 < 41 < 41 < 40 < 55 < 58 < 46 < 19 < 58 < 60 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-11 Page 61of122

Table C-Vll.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA INDICATOR FARM COLLECTION Q-26 PERIOD 01/02/15 < 0.7 02/06/15 < 0.7 03/06/15 < 0.8 04/03/15 < 0.5 05/01/15 < 1.0 05/15/15 < 0.4 05/29/15 < 0.5 06/12/15 < 0.6 06/27/15 < 0.6 07/10/15 < 0.7 07/24/15 < 0.5 08/07/15 < 0.4 08/21/15 < 0.7 09/04/15 < 0.5 09/18/15 < 0.4 10/07/15 < 0.7 10/17/15 < 0.9 10/31/15 < 0.7 11/13/15 < 0.8 12/04/15 < 0.4 MEAN C-12 Page 62of122

Table C-Vll.2 CONCENTRATIONS OF GAMMA EMiTTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-26 01/02/15 < 9 < 9 < 18 < 7 < 18 < 9 < 16 < 7 < 8 < 52 < 10 02/06/15 < 5 < 5 < 16 < 5 < 15 <7 < 9 < 5 <5 < 46 <9 03/06/15 < 5 < 6 < 15 < 5 < 16 <6 < 10 <4 <5 < 31 < 14 04/03/15 < 5 < 5 < 12 < 5 < 12 <6 <8 < 5 <6 < 32 < 10 05/01/15 <7 <7 < 14 < 6 < 16 < 7 < 11 < 6 < 7 < 39 < 11 05/15/15 < 5 <6 < 15 < 6 < 13 < 6 < 9 < 5 < 6 < 42 < 13 05/29/15 < 5 < 5 < 11 < 5 < 11 < 5 < 9 <4 < 5 < 28 <9 06/12/15 <7 < 5 < 16 < 7 < 14 <7 < 11 < 6 < 5 < 33 < 11 06/27/15 < 6 < 7 < 16 < 6 < 13 <7 < 11 < 6 < 7 < 32 <5 07/10/15 <7 < 7 < 17 < 7 < 17 <7 < 14 < 8 <7 < 35 <8 07/24/15 <4 <4 < 8 <4 < 9 <4 < 6 <4 <4 < 22 <6

(")

I 08/07/15 <9 < 12 < 23 < 10 < 17 < 8 < 17 < 9 < 9 < 53 < 13 w 08/21/15 < 6 <8 < 17 < 9 < 14 < 8 < 13 < 7 < 9 < 32 < 10 09/04/15 <6 <8 < 20 < 8 < 20 < 6 < 13 < 7 < 10 < 42 < 13 09/18/15 <8 < 9 < 21 < 7 < 20 < 9 < 16 < 8 < 10 < 39 <9 10/07/15 < 8 < 9 < 17 < 9 < 23 <8 < 16 < 7 < 9 < 39 <7 10/17/15 < 6 <7 < 20 < 7 < 20 < 9 < 16 < 7 < 7 < 34 <8 10/31/15 <6 <6 < 13 < 6 < 17 < 8 < 12 < 6 <7 < 44 < 12 11/13/15 <6 <6 < 13 < 7 < 14 <6 < 12 < 6 < 7 < 26 <8 12/04/15 < 8 <7 < 18 < 10 < 18 <7 < 15 < 7 < 8 < 42 < 14 MEAN

Table C-Vlll.1 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-CONTROL Cucumbers 07/22/15 < 8 < 11 < 29 < 9 < 21 < 10 < 18 < 66 < 10 < 10 < 124 < 23 Dill 07/22/15 < 13 < 15 < 38 < 13 < 36 < 14 < 25 < 58 < 12 < 14 < 120 < 29 Horseradish 07/22/15 < 11 < 11 < 30 < 11 < 26 < 12 < 21 < 58 < 9 < 11 < 104 < 31 Rhubarb leaves 07/22/15 < 13 < 14 < 34 < 12 < 27 < 13 < 22 < 59 < 11 < 12 < 112 < 27 MEAN Q-QUAD 1 Arugula 07/21/15 < 12 < 13 < 38 < 12 < 28 < 14 < 25 < 58 < 11 < 12 < 114 < 29 Potatoes 07/21/15 < 12 < 12 < 31 < 11 < 28 < 14 < 23 < 59 < 11 < 11 < 104 < 29 Radishes 07/21/15 < 7 < 8 < 21 < 8 < 17 < 8 < 14 < 51 < 6 < 8 < 80 < 24 Red Oak leaves 07/21/15 < 11 < 11 < 31 < 11 < 28 < 11 < 22 < 58 < 10 < 12 < 94 < 27 MEAN

(") Q-QUAD2 I

...... Cucumbers 07/22/15 < 11 < 13 < 23 < 10 < 25 < 12 < 21 < 63 < 10 < 12 < 124 < 33

""" Onions 07/22/15 <4 <4 < 11 < 5 < 12 < 6 < 8 < 26 < 4 < 6 < 40 < 11 Peppers 07/22/15 < 3 <4 < 10 < 5 < 9 <4 < 8 < 21 < 4 < 3 < 36 < 11 Tomatoes 07/22/15 < 10 < 10 < 25 < 9 < 21 < 10 < 17 < 46 < 8 < 9 < 82 < 22 Zucchini 07/22/15 < 10 < 11 < 25 < 9 < 23 < 11 < 21 < 52 < 8 < 11 < 100 < 25 MEAN Q-QUAD 3 Brussel Sprouts 07/21/15 < 8 < 8 < 22 < 9 < 18 < 11 < 15 < 59 < 7 < 10 < 93 < 16 Horseradish 07/21/15 < 8 < 8 < 13 < 6 < 17 < 7 < 13 < 42 < 7 < 10 < 65 < 16 Lettuce 07/21/15 < 9 < 8 < 30 < 10 < 21 < 11 < 20 < 57 < 8 < 8 < 104 < 24 Sun Chokes 07/21/15 < 10 < 10 < 23 < 8 < 20 < 10 < 18 < 52 < 8 < 11 < 92 < 24 MEAN Q-QUAD4 Cabbage 07/21/15 < 7 < 8 < 20 < 7 < 16 < 8 < 15 < 42 < 7 < 7 < 76 < 20 Carrots 07/21/15 < 8 < 9 < 22 < 8 < 19 < 10 < 18 < 58 < 8 < 8 < 88 < 21 Potatoes 07/21/15 <7 < 9 < 21 < 8 < 19 < 9 < 15 < 46 < 7 < 8 < 80 < 23 Rhubarb leaves 07/21/15 < 12 < 13 < 30 < 12 < 29 < 16 < 24 < 58 < 11 < 11 < 108 < 26 MEAN

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

Q-01-1 21.3 +/- 3.0 19.3 21.0 21.9 22.8 Q-01-2 21.1 +/- 4.2 18.3 23.3 21.6 21.2 Q-02-1 21.3 +/- 3.9 18.5 23.1 21.9 21.6 Q-02-2 21.5 +/- 5.0 18.2 20.8 23.4 23.5 Q-03-1 19.8 +/- 3.6 17.6 19.1 21.0 21.5 Q-03-2 21.0 +/- 3.2 19.1 22.9 20.5 21.6 Q-04-1 21.1 +/- 1.8 20.3 22.2 20.5 21.5 Q-04-2 22.1 +/- 4.3 19.0 23.5 22.2 23.6 Q-13-1 22.5 +/- 3.5 19.9 23.6 23.5 23.0 Q-13-2 22.3 +/- 4.2 20.0 21.2 23.4 24.6 Q-16-1 20.1 +/- 4.5 17.3 22.0 19.2 21.9 Q-16-2 20.9 +/- 5.2 17.1 23.0 21.2 22.1 Q-37-1 22.8 +/- 3.4 20.3 24.0 23.9 22.8 Q-37-2 23.1 +/- 4.3 20.0 24.8 24.1 23.5 Q-38-1 24.5 +/- 8.1 19.5 23.4 29.0 26.1 Q-38-2 24.4 +/- 4.3 21.3 26.1 25.5 24.5 Q-41-1 23.8 +/- 4.2 20.6 24.6 25.0 24.9 Q-41-2 23.4 +/- 4.7 19.9 24.2 24.1 25.2 Q-42-1 23.7 +/- 5.2 20.1 26.2 24.6 23.8 Q-42-2 24.1 +/- 4.7 21.1 26.2 23.4 25.8 Q-101-1 21.9 +/- 2.4 20.1 22.6 22.2 22.6 Q-101-2 21.9 +/- 4.9 18.2 22.7 23.2 23.3 Q-102-1 23.1 +/- 3.5 20.5 24.1 24.1 23,7 Q-102-3 21.6 +/- 3.1 20.0 22.9 21.4 23.3 Q-103-1 20.6 +/- 2.1 19.0 21.2 21.2 20.8 Q-103-2 20.3 +/- 3.3 17.8 20.7 21.1 21.4 Q-104-1 20.4 +/- 2.7 19.5 20.1 19.6 22.4 Q-104-2 21.4 +/- 3.4 18.9 21.8 22.8 21.9 Q-105-1 20.8 +/- 4.3 17.6 22.5 21.3 21.6 Q-106-2 21.7 +/- 4.0 18.7 23.2 22.2 22.5 Q-106-3 21.3 +/- 3.8 18.6 22.4 21.2 22.8 Q-107-2 20.9 +/- 4.7 18.2 22.2 22.3 (1)

Q-107-3 21.3 +/- 1.9 20.1 21.6 21.2 22.4 Q-108-1 21.4 +/- 4.8 18.0 23.1 23.1 21.5 Q-108-2 21.7 +/- 0.7 21.8 21.9 21.8 21.1 Q-109-1 22.5 +/- 5.5 18.7 25.3 22.5 23.3 Q-109-2 21.9 +/- 4.6 19.4 24.6 20.7 22.7 Q-111-1 22.0 +/- 2.8 20.2 22.1 22.2 23.6 Q-111-2 22.2 +/- 3.4 19.8 23.7 22.6 22.7 Q-112-1 22.5 +/- 4.0 19.8 23.7 22.3 24.3 Q-112-2 20.8 +/- 2.0 20.2 21.2 19.8 22.0 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-15 Page 65of122

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

Q-113-1 21.3 +/-2.7 19.3 22.0 21.8 22.1 Q-113-2 20.7 +/- 4.6 18.1 21.4 19.8 23.5 Q-114-1 21.2 +/- 2.5 19.9 21.5 20.7 22.8 Q-114-2 21.8 +/- 4.5 19.0 21.2 24.3 22.7 Q-115-1 22.1 +/- 4.3 19.0 23.3 22.4 23.7 Q-115-2 21.7 +/- 2.2 20.6 21.7 22.8 (1)

Q-116-1 22.7 +/- 2.8 21.4 24.4 23.3 21.8 Q-116-3 22.6 +/- 3.9 20.3 24.9 23.2 22.0 Q-201-1 23.2 +/- 5.5 19.1 24.1 24.6 24.9 Q-201-2 23.4 +/- 2.7 21.4 24.0 23.9 24.3 Q-202-1 22.6 +/- 3.8 20.0 24.3 22.2 23.7 Q-202-2 22.6 +/- 6.7 17.8 25.4 22.8 24.2 Q-203-1 22.3 +/- 2.6 20.5 22.8 22.2 23.6 Q-203-2 25.6 +/- 3.6 22.9 27.0 26.3 26.0 Q-204-1 23.8 +/- 3.2 21.4 24.6 24.9 24.3 Q-204-2 25.0 +/- 3.2 22.9 24.6 26.2 26.2 Q-205-1 24.3 +/- 5.4 20.5 26.8 24.7 25.2 Q-205-4 23.9 +/- 3.7 22.5 23.2 26.0 (1)

Q-206-1 22.6 +/- 3.4 20.1 23.5 23.9 22.9 Q-206-2 21.5 +/- 2.7 19.7 23.0 21.3 21.8 Q-207-1 22.9 +/- 2.6 21.1 23.3 22.9 24.2 Q-207-4 23.9 +/- 2.4 22.1 24.7 24.4 24.4 Q-208-1 23.6 +/- 5.7 21.3 26.2 21.0 26.0 Q-208-2 24.5 +/- 3.5 22.4 26.0 25.8 23.7 Q-209-1 22.8 +/- 1.8 21.7 23.2 23.7 22.4 Q-209-4 23.2 +/- 3.2 21.0 23.2 23.9 24.7 Q-210-1 24.5 +/- 1.0 23.9 25.1 24.5 24.5 Q-210-4 24.4 +/- 3.4 21.9 25.1 24.8 25.8 Q-210-5 20.4 +/- 2.2 18.8 21.3 20.4 21.0 Q-211-1 26.1 +/- 2.8 24.3 26.5 25.9 27.6 Q-211-2 26.5 +/- 2.6 25.1 28.2 26.6 25.9 Q-212-1 22.2 +/- 2.2 21.0 22.9 21.5 23.3 Q-212-2 20.0 +/- 2.3 18.4 19.8 20.6 21.0 Q-213-1 21.7 +/- 1.8 20.7 21.1 22.6 22.3 Q-213-2 21.0 +/- 2.6 19.1 21.6 21.4 21.9 Q-214-1 22.1 +/- 4.8 19.0 24.9 21.9 22.4 Q-214-2 21.8 +/- 3.6 19.1 22.6 22.3 23.1 Q-215-1 21.9 +/- 2.0 20.9 21.2 22.3 23.1 Q-215-2 24.1 +/- 4.2 21.4 26.2 25.2 23.4 Q-216-1 25.1 +/- 4.1 22.1 26.4 26.1 25.9 Q-216-2 23.5 +/- 1.8 22.7 24.5 24.0 22.8 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16 Page 66of122

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

JAN-MAR 19.4 +/- 2.1 21.1 +/- 3.4 19.2 +/- 2.4 20.6 +/- 1.4 APR-JUN 22.6 +/- 2.6 24.2 +/- 3.9 22.9 +/- 3.3 26.2 +/- 0.0 JUL-SEP 22.0 +/- 2.4 23.7 +/- 3.7 22.9 +/- 4.6 24.0 +/- 1.7 OCT-DEC 22.5 +/- 1.8 24.0 +/- 3.2 23.1 +/- 3.0 24.8 +/- 2.8 TABLE C-IX.3

SUMMARY

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

INNER RING 114 17.6 25.3 21.6 +/- 3.4 OUTER RING 131 17.8 28.2 23.2 +/- 4.3 OTHER 72 17.1 29.0 22.0 +/- 4.7 CONTROL 8 20.1 26.2 23.9 +/- 4.6 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, 0~204-2, 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 Page 67 of 122

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

Collected in the Vicinity of QCNPS, 2000 - 2015 Q-33 Cordova 12.0 10.0 8.0 j) 6.0 c.

4.0 2.0 0.0 --------+-----+-----li------+--

01-01-00 12-31-02 12-30-05 12-29-08 12-29-11 12-28-14 Q-34 (C) Camanche 12.0 10.0 8.0 (3 6.0 c.

4.0 2.0 0.0 --------+-----+-----li------+--

01-01-00 12-31-02 12-30-05 12-29-08 12-29-11 12-28-14 DUE TO VENDOR CHANGE,< VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-18 Page 68 of 122

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

Collected in the Vicinity of QCNPS, 2000 - 2015 Q-33 Cordova 500 400 300

...I

~C2.

200 100 0

01-01-00 12-31-02 12-30-05 12-29-08 12-29-11 12-28-14 Q-34 (C) Camanche 500 400 300 (3

C2.

200 100 0

01-01-00 12-31-02 12-30-05 12-29-08 12-29-11 12-28-14 DUE TO VENDOR CHANGE,< VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-19 Page 69 of 122

FIGURE C-3 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2015 Q-35 McMillan Well 500 400 300 0 Q.

200 100 0

12-31-99 12-31-02 12-31-05 12-31-08 01-01-12 01-01-15 Q-36 Cordova Well 500 400 300

...J 13Q.

200 100 0

12-31-99 12-31-02 12-31-05 12-31-08 01-01-12 01-01-15 DUE TO VENDOR CHANGE,< VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-20 Page 70 of 122

FIGURE C-4 Air Particulates - Gross Beta- Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2015 Q-01 Onsite No. 1 70.0 60.0

.., 50.0

§ 40.0 0

..,c.

0 30.0 uJ 0

..... 20.0 10.0 0.0 01-07-00 01-06-03 01-05-06 01-04-09 01-04-12 01-03-15 Q-02 Onsite No. 2 70.0 60.0

.., 50.0 E

~ 40.0 c.

9 30.0 w

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

01-07-00 01-06-03 01-05-06 01-04-09 01-04-12 01-03-15 C-21 Page 71of122

FIGURE C-5 Air Particulates - Gross Beta- Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2015 Q-03 Onsite No. 3 60.0 50.0 C') 40.0

§ 0

c. 30.0 C')

0 uJ 20.0 0

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

01-07-00 01-06-03 01-05-06 01-04-09 01-04-12 01-03-15 Q-04 Nitrin 60.0 50.0 C') 40.0

.E

~ 30.0 C')

0 uJ 20.0 0

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

01-07-00 01-06-03 01-05-06 01-04-09 01-04-12 01-03-15 C-22 Page 72 of 122

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 C')

§15_ 40.0 9 30.0 w

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

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 Page 73 of 122

FIGURE C-7 Air Particulates - Gross Beta- Stations Q-13 and Q-16 Collected in the Vicinity of QCNPS, 2005 - 2015 Q-13 Princeton 60.0 50.0

'E 40.0

~

..,c. 30.0 0

w 20.0 0

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

07-08-05 06-01-07 04-24-09 03-18-11 02-08-13 01-02-15 Q-16 Low Moor 60.0 50.0 40.0 30.0 20.0 10.0 0.0 - - - - - - + - - - - - + - - - - + - - - - - + - -

07-08-05 06-01-07 04-24-09 03-18-11 02-08-13 01-02-15 AIR PARTICULATE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 C-24 Page 74of122

FIGURE C-8 Air Particulates - Gross Beta- Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2015 Q-37 Meredosia Road 60.0 50.0 M 40.0

§ 0

M Q. 30.0

...~ 20.0 10.0 0.0 --------+-----+----+------1---

07-08-05 06-01-07 04-24-09 03-18-11 02-08-13 01-02-15 Q-38 Fuller Road 60.0 5o.o*

M 40.0

.§ 0

Q. ~0.0 suJ 0 20.0 10.0 0.0 +-----i-----+------1-----'-----&.--

07-08-05 06-01-07 04-24-09 03-18-11 02-08-13 01-02-15 AIR PARTICULATE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 C-25 Page 75of122

FIGURE C-9

• Air Particulates - Gross Beta- Stations Q-41 and Q-42 (C)

Collected in the Vicinity of QCNPS, 2009 - 2015 Q-41 Camanche 60.0 50.0 M 40.0

.E

~

M 30.0 9

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

01-03-09 03-17-10 05-29-11 08-09-12 10-21-13 01-02-15 Q-42 LeClaire (Control) 60.0 50.0 M 40.0

§ CJ

a. 30.0 M

9 w 20.0 0

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

12-31-10 10-20-11 08-08-12 05-28-13 03-17-14 01-04-15 10-24-15 C-26 Page 76of122

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM Page 77of122

Intentionally left blank Page 78 of 122

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

Identification Reported Known Ratio (c)

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

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

Cs-134 pCi 139 138 1.01 A Cs-137 pCi 111 106 1.05 A Co-58 pCi 54.0 57.8 0.93 A Mn-54 pCi 96.8 84.9 1.14 A Fe-59 pCi 162 128 1.27 w Zn-65 pCi 198 210 0.94 A Co-60 pCi 178 163 1.09 A E11236 Charcoal 1-131 pCi 93.9 80 1.17 A D-1 Page 79 of 122

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analy!ics Evaluation (d)

June 2015 E11238 Water Fe-55 pCi/L 1890 1790 1.06 A September 2015 E11289 Milk Sr-89 pCi/L 95.7 99.1 0.97 A Sr-90 pCi/L 15.4 16.4 0.94 A E11290 Milk 1-131 pCi/L 94.9 99.9 0.95 A Ce-141 pCi/L 228 213 1.07 A Cr-51 pCi/L 499 538 0.93 A Cs-134 pCi/L 208 212 0.98 A Cs-137 pCi/L 270 255 1.06 A Co-58 pCi/L 275 263 1.05 A Mn-54 pCi/L 320 290 1.10 A Fe-59 pCi/L 255 226 1.13 A Zn-65 pCi/L 392 353 1.11 A Co-60 pCi/L 350 330 1.06 A E11292 AP Ce-141 pCi 104 85.1 1.22 w Cr-51 pCi 262 215 1.22 w Cs-134 pCi 86.1 84.6 1.02 A Cs-137 pCi 93 102 0.91 A Co-58 pCi 106 105 1.01 A Mn-54 pCi 117 116 1.01 A Fe-59 pCi 94.8 90.2 1.05 A Zn-65 pCi 160 141 1.13 A Co-60 pCi 146 132 1.11 A E11291 Charcoal 1-131 pCi 85.9 81.7 1.05 A E11293 Water Fe-55 pCi/L 2090 1800 1.16 A E11294 Soil Ce-141 pCi/kg 209 222 0.94 A Cr-51 pCi/kg 463 560 0.83 A Cs-134 pCi/kg 231 221 1.05 A Cs-137 pCi/kg 311 344 0.90 A Co-58 pCi/kg 245 274 0.89 A Mn-54 pCi/kg 297 302 0.98 A Fe-59 pCi/kg 248 235 1.06 A Zn-65 pCi/kg 347 368 0.94 A Co-60 pCi/kg 328 344 0.95 A December 2015 E11354 Milk Sr-89 pCi/L 96.2 86.8 1.11 A Sr-90 pCi/L 14.8 12.5 1.18 A E11355 Milk 1-131 pCi/L 95.1 91.2 1.04 A Ce-141 pCi/L 117 129 0.91 A Cr-51 pCi/L 265 281 0.94 A Cs-134 pCi/L 153 160 0.96 A Cs-137 pCi/L 119 115 1.03 A Co-58 pCi/L 107 110 0.97 A Mn-54 pCi/L 153 145 1.06 A Fe-59 pCi/L 117 108 1.08 A Zn-65 pCi/L 261 248 1.05 A Co-60 pCi/L 212 213 1.00 A D-2 Page 80 of 122

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE3 OF 3)

Identification Reported Known Ratio (c)

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

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

(b} The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or 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 o. 70-0.80 or 1.20-1.30. N =Not Acceptable~ reported result falls outside the ratio limits of< o. 70 and> 1.30.

D-3 Page 81 of 122

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

TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)

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

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

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

Gr-S Sq/sample 0.7580 0.75 0.38-1.13 A 15-RdV32 Vegetation Cs-134 Sq/sample 8.08 7.32 5.12- 9.52 A Cs-137 Sq/sample 11.6 9.18 6.43 - 11.93 w Co-57 Sq/sample -0.0096 (1) A Co-60 Sq/sample 6.53 5.55 3.89 - 7.22 A Mn-54 Sq/sample 0.0058 (1) A Sr-90 Sq/sample 0.999 1.08 0.76 - 1.40 A Zn-65 Sq/sample -0.108 (1) A September 2015 15-MaW33 Water Am-241 Sq/L 1.012 1.055 0. 739 - 1.372 A Ni-63 Sq/L 11.8 8.55 5.99-11.12 N (4)

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

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

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

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

(a) Teledyne Brown Engineering reported result.

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

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

D-4 Page 82 of 122

TABLE D-3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)

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

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

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

Ba-133 pCi/L 80.6 82.5 63.9 - 90.8 A Cs-134 pCi/L 71.7 75.7 61.8 - 83.3 A Cs-137 pCi/L 187 189 170 - 210 A Co-60 pCi/L 85.7 84.5 76.0 - 95.3 A Zn-65 pCi/L 197 203 183 - 238 A Gr-A pCi/L 26.1 42.6 22.1 - 54.0 A Gr-B pCi/L 28.8 32.9 21.3-40.6 A 1-131 pCi/L 23.5 23.8 19.7 - 28.3 A U-Nat pCi/L 6.19 6.59 4.99- 7.83 A H-3 pCi/L 3145 3280 2770-3620 A November 2015 RAD-103 Water Sr-89 pCi/L 40.9 35.7 26.7 - 42.5 A Sr-90 pCi/L 29.3 31.1 22.7 - 36.1 A Ba-133 pCi/L 31.5 32.5 25.9 - 36.7 A Cs-134 pCi/L 59.65 62.3 50.6 - 68.5 A Cs-137 pCi/L 156 157 141 - 175 A Co-60 pCi/L 70.6 71.1 64.0 - 80.7 A Zn-65 pCi/L 145 126 113 - 149 A Gr-A pCi/L 38.2 51.6 26.9 - 64.7 A Gr-8 pCi/L 42.0 36.6 24.1 - 44.2 A 1-131 pCi/L 24.8 26.3 21.9- 31.0 A U-Nat pCi/L 146.90 56.2 45.7 - 62.4 N (2)

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

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

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within tl1e Control Limits and outside of the Warning Limit.

D-5 Page 83 of 122

TABLE D-4 ERA STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAMa ENVIRONMENTAL, INC., 2015 (Page 1 of 1)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control 0

Result b Result Limits Acceptance ERW-1444 04/06/15 Sr-89 59.71 +/- 5.44 63.20 51.10 - 71.20 Pass ERW-1444 04/06/15 Sr-90 43.41 +/- 2.43 41.90 30.80 - 48.10 Pass ERW-1448 04/06/15 Ba-133 77.75 +/- 4.69 82.50 69.30 - 90.80 Pass ERW-1448 04/06/15 Cs-134 68.82 +/- 3.08 75.70 61.80 - 83.30 Pass ERW-1448 04/06/15 Cs-137 -191.92 +/- 5.9 189 -170.00 - 210.0 Pass ERW-1448 04/06/15 Co-60 85.05 +/- 4.59 84.50 76.00 - 95.30 Pass ERW-1448 04/06/15 Zn-65 -195.97+/-12.0 203 -183.00 - 238.0 Pass ERW-1450 04/06/15 Gr. Alpha 34.05 +/- 1.90 42.60 22.10 - 54.00 Pass ERW-1450 04/06/15 Gr. Beta 26.93 +/- 1.12 32.90 21.30 - 40.60 Pass ERW-1453 04/06/15 1-131 22.47 +/- 0.83 23.80 19.70 - 28.30 Pass ERW-1456 04/06/15 Uranium 5.98 +/- 0.31 6.59 4.99 - 7.83 Pass ERW-1461 04/06/15 H-3 3,254 +/- 180 3280 2,770 - 3620 Pass ERW-5528 10/05/15 Sr-89 34.76 +/- 0.06 35.70 26. 70 - 42.50 Pass ERW-5528 10/05/15 Sr-90 29.23 +/- 0.06 31.10 22.70 - 36.10 Pass ERW-5531 10/05/15 Ba-133 30.91 +/- 0.53 32.50 25.90 - 36.70 Pass ERW-5531 10/05/15 Cs-134 57.40 +/- 2.57 62.30 50.69 - 68.50 Pass ERW-5531 10/05/15 Cs-137 -163.12 +/- 4.8 157 -141.00 - 175.0 Pass ERW-5531 10/05/15 Co-60 73.41 +/- 1.72 71.10 64.00 - 80.70 Pass ERW-5531 10/05/15 Zn-65 -138.94 +/- 5.7 126 -113.00 - 149.0 Pass ERW-5534 10/05/15 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 - 64.70 Pass ERW-5534 10/05/15 G. Beta 27.52 +/- 0.04 36.60 24.10 - 44.20 Pass ERW-5537 10/05/15 1-131 25.54 +/- 0.60 26.30 21.90 - 31.00 Pass ERW-5540 10/05/15 Uranium 53.30 +/- 0.55 56.20 45.70 - 62.40 Pass ERW-5543 10/05/15 H-3 21,260 +/- 351 21,300 18,700 - 23400.0 Pass

• 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 Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

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

D-6 Page 84of122

TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

ENVIRONMENTAL, INC., 2015 (Page 1 of 2)

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 2/1/2015 Ni-63 341 +/- 18 448 314 - 582 Pass MAS0-975 2/1/2015 Sr-90 523 +/- 12 653 457 - 849 Pass MAS0-975 2/1/2015 Cs-134 533 +/- 6 678 475 - 881 Pass MAS0-975 2/1/2015 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 2/1/2015 Co-57 0.5 +/- 1 0.0 NA c Pass MAS0-975 2/1/2015 Co-60 741 +/- 8 817 572 - 1062 Pass MAS0-975 2/1/2015 Mn-54 1,153 +/- 9 1, 198 839 - 1557 Pass MAS0-975 2/1/2015 Zn-65 892 +/- 18 1064 745 - 1383 Pass MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 0.654 0.458 - 0.850 Pass MAW-969 2/1/2015 Cs-134 21.09 +/- 0.25 23.5 16.5 - 30.6 Pass MAW-969 2/1/2015 Cs-137 19.63 +/- 0.34 19.1 13.4 - 24.8 Pass MAW-969 d 2/1/2015 Co-57 10.2 +/- 0.4 29.9 20.9 - 38.9 Fail MAW-969 2/1/2015 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 2/1/2015 H-3 569 +/- 13 563 394 - 732 Pass MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 6.88 4.82 - 8.94 Pass MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 0.00 NA c Pass MAW-969 2/1/2015 Ni-63 2.9 +/- 3 0.00 NA c Pass MAW-969 2/1/2015 Zn-65 16.54 +/- 0.85 18.3 12.8 - 23.8 Pass 0

MAW-969 2/1/2015 Pu-238 0.02 +/- 0.03 0.01 NA Pass MAW-969 2/1/2015 Pu-239/240 0.81 +/- 0.10 0.83 0.58 - 1.08 Pass MAW-969 2/1/2015 Sr-90 9.40 +/- 1.30 9.48 6.64 - 12.32 Pass MAW-950 2/1/2015 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 - 1.81 Pass MAW-950 2/1/2015 Gr. Beta 2.72 +/- 0.06 2.79 1.40 - 4.19 Pass MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 1.15 0.81 - 1.50 Pass MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 0.00 NAC Pass MAAP-978 e 2/1/2015 Co-57 0.04 +/- 0.04 1.51 1.06 - 1.96 Fail MAAP-978 2/1/2015 Co-60 0.01 +/- 0.02 0.00 NA c Pass MAAP-978 2/1/2015 Mn-54 1.11 +/- 0.08 1.02 0.71 - 1.33 Pass MAAP-978 2/1/2015 Zn-65 0.83 +/- 0.10 0.83 0.58 - 1.08 Pass MAAP-981 2/1/2015 Sr-89 38.12 +/- 1.01 47.5 33.3 - 61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/- 0.13 1.06 0.74 - 1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 - 3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 - 1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.13 7.32 5.12 - 9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 - 11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 - 7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NA c Pass D-7 Page 85 of 122

TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

ENVIRONMENTAL, INC., 2015 (Page 2 of 2)

Concentration a Known Control 0

Lab Code Date Analysis Laboratory result Activity Limits c Acceptance MAS0-4903 8/1/2015 Ni-63 556 +/- 18 682 477 - 887 Pass MAS0-4903 f 8/1/2015 Sr-90 231 +/-7 425 298 - 553 Fail MAS0-4903 f 8/1/2015 Sr-90 352 +/- 10 425 298 - 553 Pass MAS0-4903 8/1/2015 Cs-134 833 +/- 10 1,010 707 - 1313 Pass MAS0-4903 8/1/2015 Cs-137 808 +/- 11 809.00 566 - 1052 Pass MAS0-4903 8/1/2015 Co-57 1,052 +/- 10 1, 180 826 - 1534 Pass MAS0-4903 8/1/2015 Co-60 2 +/-2 1.3 NAe Pass MAS0-4903 8/1/2015 Mn-54 1,331 +/- 13 1,340 938 - 1742 Pass MAS0-4903 8/1/2015 Zn-65 686 +/- 15 662 463 - 861 Pass MAW-5007 8/1/2015 Cs-134 16.7 +/- 0.4 23.1 16.2 - 30 Pass MAW-5007 8/1/2015 Cs-137 -0.36 +/- 0.13 0 NA c Pass MAW-5007 8/1/2015 Co-57 21.8 +/- 0.4 20.8 14.6 - 27 Pass MAW-5007 8/1/2015 Co-60 17.3 +/- 0.3 17.1 12 - 22.2 Pass MAW-5007 8/1/2015 H-3 227.5 +/- 8.9 216 151 - 281 Pass MAW-5007 g 8/1/2015 Fe-55 4.2 +/- 14.1 13.1 9.2 - 17 Fail MAW-5007 8/1/2015 Mn-54 16.6 +/- 0.5 15.6 10.9 - 20.3 Pass MAW-5007 8/1/2015 Ni-63 9.1 +/- 2.6 8.55 5.99 - 11.12 Pass MAW-5007 8/1/2015 Zn-65 15.5 +/- 0.9 13.9 9.7 - 18.1 Pass MAW-5007 8/1/2015 Sr-90 4.80 +/- 0.50 4.80 3.36 - 6.24 Pass MAW-5007 8/1/2015 Gr. Alpha 0.41 +/- 0.04 0.43 0.13 - 0.73 Pass MAW-5007 8/1/2015 Gr. Beta 3.45 +/- 0.07 3.52 1.76 - 5.28 Pass MAAP-4911 8/1/2015 Sr-89 3.55 +/- 0.67 3.98 2.79 - 5.17 Pass MAAP-4911 8/1/2015 Sr-90 0.94 +/- 0.16 1.05 0.74 - 1.37 Pass MAAP-4907 8/1/2015 Gr. Alpha 0.30 +/- 0.04 0.90 0.27 - 1.53 Pass MAAP-4907 8/1/2015 Gr. Beta 1.85 +/- 0.09 1.56 0.78 - 2.34 Pass MAVE-4901 8/1/2015 Cs-134 5.56 +/- 0.16 5.80 4.06 - 7.54 Pass MAVE-4901 8/1/2015 Cs-137 -0.02 +/- 0.06 0.00 NA c Pass MAVE-4901 8/1/2015 Co-57 7.74 +/- 0.18 6.62 4.63 - 8.61 Pass MAVE-4901 8/1/2015 Co-60 4.84 +/- 0.15 4.56 3.19 - 5.93 Pass MAVE-4901 8/1/2015 Mn-54 8.25 +/- 0.25 7.68 5.38 - 9.98 Pass MAVE-4901 8/1/2015 Zn-65 5.78 +/- 0.29 5.46 3.82 - 7.10 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 Lab result was 27.84. Data entry error resulted in a non-acceptable result.

• Lab result was 1.58. Data entry error resulted in a non-acceptable result.

f The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.

g The known activity was below the routine laboratory detection limits for the available aliquot fraction.

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APPENDIX E ERRATA DATA Page 87 of 122

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There is no errata data for 2015.

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APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

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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 2015 Prepared By Teledyne Brown Engineering Environmental Services Quad Cities Nuclear Power Station Cordova, iL 61242 May 2016 Page 93of122

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Table Of Contents I. Summary and Conclusion ................................................................................................ 3 II. Introduction ..................................................................................................................... 5 A. Objectives of the RGPP ...................................................................................... 5

8. Implementation of the Objectives ........................................................................ 6 C. Program Description ........................................................................................... 6 Ill. Program Description ...................................................................................................... 7 A. Sample Analysis .................................................................................................. 7

8. Data Interpretation ............................................................................................... 7 IV. Results and Discussion ................................................................................................. 8 A. Groundwater Results ........................................................................................... 8

8. 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 Page 95 of 122

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2015 Figures Figure A-1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2015 Figure A-2 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2015 Appendix B Data Tables Tables Table B-1.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

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

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

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

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

Table B-111.1 Concentrations of Tritium in Groundwater Samples Collected and Anaylzed by Quad Cities Station Personnel, 2015.

ii Page 96of122

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 2015 through 31 December 2015.

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

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

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

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

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

In 2012 Conestoga-Rovers & Associates (CRA) completed a five-year update hydrogeologic investigation report for the Station (NE/ 07-07, Hydrogeologic Investigation Report, dated November 2012). The referenced report summarized station activities since the 2006 hydrogeologic investigation report, including Page 97 of 122

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 2015. During that time period, RGPP samples were collected from 43 locations.

2015 sample locations included thirty-six designated monitoring wells, two surface water monitoring points and five 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 Fe 55/Ni

63. Samples from eighteen of the designated monitoring wells and two 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 36,900 pCi/L in a monitoring well. Tritium was detected in one of the eight surface water samples at a concentration of 295 pCi/L.

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 was not detected at concentrations greater than the Lower Limit of Detection (LLD) of 10.0 pCi/L. Strontium-90 was not detected at concentrations great 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 10 designated groundwater locations during the first quarter sampling in 2015.

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

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

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Gross Beta (dissolved) was detected in nine of 10 groundwater locations. The concentrations ranged from 2.8 to 43.1 pCi/L.

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

Select Transuranics/Hard-To-Detect analyses was performed on one 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. Objective 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.

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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 Page 100 of 122

analytical data deliverables after initial review by the contractor.

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

Ill. Program Description This section covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2015.

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 2015.

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

1. Concentrations of gamma emitters in groundwater and surface water.

2. Concentrations of strontium in groundwater.

3. Concentrations of tritium in groundwater 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 Page 101of122

Cities Nuclear Power Station was considered operational at initial criticality. Several factors were important in the interpretation of the data:

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

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

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

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

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

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

IV. Results and Discussion A Groundwater Results Groundwater Samples were collected from on-site wells in accordance with the Page 102of122

station radiological groundwater protection program. Analytical results and anomalies are discussed below.

Tritium Samples from all locations were analyzed for tritium activity (Table B-1.1 & B-111.1 Appendix B). Tritium values ranged from the detection limit to 36,900 pCi/I. All samples obtained at the site boundaries were less then the detection limit of 200 pCi/L, with the exception of MW-QC-1121 sampled on 3/9/15 which showed activity of 403 pCi/L. Subsequent resample of MW-QC-1121 on 4/10/15 was less than detection limit of 200 pCi/L. The location most representative of potential offsite user of drinking water was

<200 pCi/L.

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

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions performed on designated groundwater locations during the 1st quarter in 2015.

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 nine of 10 groundwater locations. The concentrations ranged from 2.8 to 43.1 pCi/L.

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

Gamma Emitters No gamma emitting nuclides were detected other than naturally occurring K-40 in two samples at concentration of 27 pCi/L and 158 pCi/L (Table B-1.2, Appendix B).

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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-1.3 Appendix B).

B. Surface Water Results Surface Water Tritium Samples from two locations were analyzed for tritium activity.

Tritium was detected in one of the eight samples at a concentration of 295 pCi/L. (Table B-11.1 Appendix B).

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

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

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

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

F. Investigations Currently no investigations are on-going.

G. Actions Taken

1. Compensatory Actions There have been no station events requiring compensatory actions at the Quad Cities Nuclear Power Station in 2015.

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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.

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APPENDIX A LOCATION DESIGNATION Page 107 of 122

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TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations , Quad Cities Nuclear Power Station, 2015 Site Site Type Well Designation Minimum Sample Frequency MW-QC-1 Monitoring Well Plume Quarterly MW-QC-2 Monitoring Well Plume Quarterly MW-QC-3 Monitoring Well Plume Quarterly MW-QC-1011 Monitoring Well Idle Not Required MW-QC-101S Monitoring Well Idle Not Required MW-QC-102D Monitoring Well Plume Quarterly MW-QC-1021 Monitoring Well Plume Quarterly MW-QC-102S Monitoring Well Plume Quarterly MW-QC-1031 Monitoring Well Detection Quarterly MW-QC-104S Monitoring Well Detection Quarterly MW-QC-1051 Monitoring Well Plume Quarterly MW-QC-1061 Monitoring Well Plume Quarterly MW-QC-106S Monitoring Well Plume Quarterly MW-QC-1071 Monitoring Well Background Annual MW-QC-108D Monitoring Well Plume Quarterly MW-QC-1081 Monitoring Well Plume Quarterly MW-QC-108S Monitoring Well Plume Quarterly MW-QC-1091 Monitoring Well Plume Quarterly MW-QC-109S Monitoring Well Plume Quarterly MW-QC-1101 Monitoring Well Idle Not Required MW-QC-111 D1 Monitoring Well Idle Not Required MW-QC-111 D2 Monitoring Well Idle Not Required MW-QC-1111 Monitoring Well Idle Not Required MW-QC-1121 Monitoring Well Plume Quarterly MW-QC-1131 Monitoring Well Idle Not Required MW-QC-114 1 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 LITILE 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 WE LL #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 Page 109 of 122

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APPENDIX B DATA TABLES Page 113of122

Intentionally left blank Page 114of122

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

MW-QC-1 03/10/15 < 183 MW-QC-1 05/19/15 < 185 MW-QC-1 08/25/15 < 189 MW-QC-1 11/10/15 220 +/- 124 MW-QC-102D 03/10/15 982 +/- 167 MW-QC-102D 05/19/15 678 +/- 151 MW-QC-102D 08/25/15 886 +/- 160 MW-QC-102D 11/10/15 721 +/- 153 MW-QC-1021 03/10/15 379 +/- 137 MW-QC-1021 05/19/15 333 +/- 134 MW-QC-1021 08/25/15 < 191 MW-QC-1021 11/10/15 < 195 MW-QC-102S 03/10/15 < 187 MW-QC-102S 05/19/15 < 189 MW-QC-102S 08/25/15 < 191 MW-QC-102S 11/10/15 < 196 MW-QC-1031 03/10/15 < 187 < 3.7 < 0.9 < 1.6 < 0.5 8.3 +/- 1.3 < 1.6 MW-QC-1031 05/19/15 < 189 MW-QC-1031 08/25/15 < 191 MW-QC-1031 11/10/15 < 194 MW-QC-104S 03/10/15 < 183 < 3.7 < 0.9 < 2.1 < 0.5 < 2.5 < 1.6 MW-QC-104S 05/19/15 < 188 MW-QC-104S 08/25/15 < 190 MW-QC-104S 11/10/15 < 195 MW-QC-1051 03/10/15 507 +/- 142 MW-QC-1051 05/19/15 < 190 MW-QC-1051 08/25/15 < 188 MW-QC-1051 11/10/15 < 191 MW-QC-1061 03/10/15 < 180 MW-QC-1061 05/19/15 < 192 MW-QC-1061 08/25/15 < 190 MW-QC-1061 11/10/15 < 195 MW-QC-106S 03/10/15 < 191 MW-QC-106S 05/19/15 < 191 MW-QC-106S 08/25/15 < 190 MW-QC-106S 11/10/15 < 196 MW-QC-1071 03/09/15 < 185 MW-QC-108D 03/10/15 1500 +/- 207 MW-QC-108D 05/20/15 1280 +/- 192 MW-QC-108D 08/26/15 1240 +/- 187 MW-QC-108D 11/11/15 1360 +/- 205 MW-QC-1081 03/10/15 564 +/- 141 MW-QC-1081 05/20/15 Original 3110 +/- 367 MW-QC-1081 08/26/15 2430 +/- 301 MW-QC-1081 11/11/15 1620 +/- 228 MW-QC-108S 03/10/15 < 185 MW-QC-108S 05/20/15 Original 475 +/- 138 MW-QC-108S 08/26/15 < 189 MW-QC-108S 11/11/15 < 193 MW-QC-1091 03/10/15 < 185 MW-QC-1091 05/19/15 < 186 MW-QC-1091 08/25/15 < 191 MW-QC-1091 11/10/15 < 195 MW-QC-109S 03/10/15 < 186 B-1 Page 115of122

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A(8us) Gr-8 (Dis) Gr-8 (Sus)

MW-QC-109S 05/19/15 < 195 MW-QC-1098 08/25/15 < 188 MW-QC-1098 11/10/15 < 194 MW-QC-1121 03/09/15 Original 403 +/- 137 MW-QC-1121 05/18/15 < 191 MW-QC-1121 08/24/15 < 192 MW-QC-1121 11/09/15 < 194 MW-QC-2 03/10/15 < 184 MW-QC-2 05119/15 < 192 MW-QC-2 08/25115 < 189 MW-QC-2 11110115 < 193 MW-QC-3 03/15115 19900 +/- 2030 < 6.0 < 0.6 < 1.3 < 0.3 8.7 +/- 1.3 < 1.6 MW-QC-3 11/10/15 6890 +/- 741 QC-GP-10 03/09115 < 193 < 3.9 < 0.8 < 5.4 < 0.6 15.4 +/- 1.8 < 1.5 QC-GP-11 03/09/15 1360 +/- 197 < 4.0 < 0.9 < 5.7 < 0.6 8.4 +/- 1.6 < 1.5 QC-GP-12 03/10115 < 190 < 8.3 < 0.9 < 1.1 < 0.6 2.8 +/- 0.7 < 1.5 QC-GP-14 03/09115 4060 +/- 456 < 5.3 < 1.0 < 1.4 < 0.3 6.0 +/- 1.3 < 1.6 QC-GP-15 03/09/15 < 192 < 3.1 < 0.8 < 5.6 < 0.6 16.3 +/- 2.1 < 1.5 QC-GP-15 07128/15 < 188 QC-GP-16 03/09/15 17300 +/- 1770 < 3.9 < 0.7 < 1.1 < 0.3 4.2 +/- 1.0 < 1.6 QC-GP-18 03/09/15 31200 +/- 3150 < 4.0 < 0.8 < 3.5 < 0.3 43.1 +/- 2.7 < 1.6 WELL #9 DRY CASK STORAGE 03/11/15 < 193 B-2 Page 116of122

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DATE MW-QC-1031 03/10/15 < 49 < 48 <6 <6 < 11 < 6 < 9 < 6 < 10 < 14 <6 <6 < 33 <4 MW-QC-104S 03/10/15 < 43 < 53 <4 <4 < 8 <5 < 11 < 5 <8 < 10 <4 <4 < 22 < 9 MW-QC-1071 03/09/15 < 51 < 108 < 5 <6 < 11 <5 < 11 < 7 < 10 < 14 <6 < 5 < 34 < 9 QC-GP-10 03/09/15 < 15 < 34 < 1 < 1 <4 < 1 < 3 < 2 < 3 < 13 < 1 < 1 < 18 <6 QC-GP-11 03/09/15 < 17 < 32 < 1 <2 < 5 <2 < 3 <2 < 3 < 14 < 1 <2 < 21 <6 QC-GP-12 03/10/15 < 14 < 26 < 1 <2 < 3 < 1 < 3 <2 < 3 < 11 < 1 < 1 < 17 < 5 QC-GP-14 03/09/15 < 16 158 +/- 30 < 1 <2 < 3 <2 < 3 <2 < 3 < 14 < 1 < 1 < 21 < 6 QC-GP-15 03/09/15 < 16 < 13 < 1 < 2 <4 < 1 < 3 <2 <3 < 12 < 1 <2 < 20 < 6 QC-GP-15 07/28/15 < 44 < 83 <4 <4 < 8 < 5 < 10 < 5 <9 < 14 <4 <5 < 34 < 10 QC-GP-16 03/09/15 < 11 < 27 < 1 < 1 < 3 < 1 <2 < 1 <2 < 11 < 1 < 1 < 16 < 5 QC-GP-18 03/09/15 < 9 27 +/- 17 < 1 < 1 <2 < 1 < 2 < 1 <2 < 9 < 1 < 1 < 12 <4 QC-MW-3 03/15/15 < 18 < 28 <2 <2 <4 <2 <4 < 2 <4 < 12 < 2 <2 < 20 < 6 WELL #9 DRY CASK STORAGE 03/11/15 < 17 < 35 <2 <2 <4 <2 < 4 < 2 <3 < 12 < 2 <2 < 19 < 6 t:Ci I

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TABLE B-1.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 Fe-55 Ni-63 DATE QC-GP-15 03/09/15 < 0.08 < 0.09 < 0.02 < 0.07 < 0.18 < 0.02 < 0.07 < 0.04 < 160 < 4.7

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TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 QC-SW-1 3/31/2015 295 +/- 134 QC-SW-1 08/25/15 < 188 QC-SW-1 11109/15 < 193 QC-SW-2 3/31/2015 < 188 QC-SW-2 08/25/15 < 189 QC-SW-2 11/09/15 < 193 B-5 Page 119 of122

TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DATE QC-SW-1 03/31/15 < 72 < 170 < 8 < 7 < 15 < 7 < 17 < 9 < 14 < 12 < 7 < 7 < 32 < 12 QC-SW-2 03/31/15 < 49 < 60 <6 < 6 < 9 <6 < 10 < 7 < 12 < 13 < 6 <7 < 33 < 12 N

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TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2015 RESULTS IN UNITS OF PCl/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-1 03/09/15 9,776 Sentinel Well QC-GP-1 05/18/15 5,170 Sentinel Well QC-GP-1 08/24/15 9,240 Sentinel Well QC-GP-1 11/10/15 5,180 Sentinel Well QC-GP-2 03/11/15 <2,000 Sentinel Well QC-GP-2 05/20/15 <2,000 Sentinel Well QC-GP-2 08/26/15 <2,000 Sentinel Well QC-GP-2 11/10/15 <2,000 Sentinel Well QC-GP-3 03/09/15 <2,000 Sentinel Well QC-GP-4 03/09/15 23,900 Sentinel Well QC-GP-4 05/18/15 22,000 Sentinel Well QC-GP-4 08/25/15 11,700 Sentinel Well QC-GP-4 11/12/15 10,800 Sentinel Well QC-GP-5 03/09/15 <2,000 Sentinel Well QC-GP-5 05/20/15 <2,000 Sentinel Well QC-GP-5 08/26/15 <2,000 Sentinel Well QC-GP-5 11/09/15 <2,000 Sentinel Well QC-GP-6 03/09/15 <2,000 Sentinel Well QC-GP-6 05/18/15 <2,000 Sentinel Well QC-GP-6 07/28/15 <2,000 Sentinel Well QC-GP-6 11/09/15 <2,000 Sentinel Well QC-GP-7 03/09/15 <2,000 Sentinel Well QC-GP-7 05/20/15 <2,000 Sentinel Well QC-GP-7 07/28/15 <2,000 Sentinel Well QC-GP-7 11/09/15 <2,000 Sentinel Well QC-GP-8 03/09/15 <2,000 Sentinel Well QC-GP-9 03/09/15 23,400 Sentinel Well QC-GP-9 05/18/15 10,500 Sentinel Well QC-GP-9 08/24/15 21,400 Sentinel Well QC-GP-9 11/11/15 27,300 Sentinel Well QC-GP-10 03/09/15 <2,000 Sentinel Well QC-GP-10 05/20/15 <2,000 Sentinel Well QC-GP-10 08/26/15 <2,000 Sentinel Well QC-GP-10 11/09/15 <2,000 Sentinel Well QC-GP-11 03/09/15 <2,000 Sentinel Well QC-GP-11 05/19/15 2,580 Sentinel Well QC-GP-11 08/26/15 <2,000 Sentinel Well QC-GP-11 11/09/15 <2,000 Sentinel Well QC-GP-12 03/09/15 <2,000 Sentinel Well QC-GP-12 05/19/15 <2,000 Sentinel Well QC-GP-12 08/24/15 <2,000 Sentinel Well QC-GP-12 11/11/15 <2,000 Sentinel Well QC-GP-13 03/10/15 18,300 Sentinel Well QC-GP-13 05/19/15 7,030 Sentinel Well QC-GP-13 08/25/15 13,000 Sentinel Well QC-GP-13 11/11/15 12,600 Sentinel Well QC-GP-14 03/09/15 4,400 Sentinel Well QC-GP-14 05/19/15 7,030 Sentinel Well QC-GP-14 08/26/15 5,590 Sentinel Well QC-GP-14 11/09/15 4,200 Sentinel Well QC-GP-15 03/09/15 <2,000 Sentinel Well QC-GP-15 05/20/15 <2,000 Sentinel Well QC-GP-15 07/28/15 <2,000 Sentinel Well QC-GP-15 11/09/15 <2,000 Sentinel Well B-7 Page 121 of122

TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2015 RESULTS IN UNITS OF PCl/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-16 03/09/15 21,400 Sentinel Well QC-GP-16 05/18/15 <2,000 Sentinel Well QC-GP-16 08/24/15 <2,000 Sentinel Well QC-GP-16 11/11/15 2,610 Sentinel Well QC-GP-17 03/09/15 6,000 Sentinel Well QC-GP-17 05/18/15 2,420 Sentinel Well QC-GP-17 08/24/15 3,290 Sentinel Well QC-GP-17 11/11/15 <2,000 Sentinel Well QC-GP-18 03/09/15 36,900 Sentinel Well QC-GP-18 05/18/15 6,810 Sentinel Well QC-GP-18 08/24/15 2,030 Sentinel Well QC-GP-18 11/10/15 6,630 Sentinel Well MW-QC-3 05/18/15 10,500 Monitoring Well MW-QC-3 08/24/15 14,700 Monitoring Well MW-QC-1121 04/10/15 <200 Monitoring Well Well#1 03/12/15 <200 Production Well Well#1 09/15/15 <200 Production Well Well#5 03/12/15 <200 Production Well Well#5 09/15/15 <200 Production Well Well#? 03/12/15 <2000 Production Well

• Well#? 05/18/15 <2000 Production Well Well#? 09/15/15 <200 Production Well Well#? 11/11/15 <2,000 Production Well Well #10 03/12/15 <200 Production Well QC-SW-1 05/22/15 <200 Surface Water QC-SW-2 05/22/15 <200 Surface Water B-8 Page 122of122

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 2015 Prepared By Teledyne Brown Engineering Environmental Services Quad Cities Nuclear Power Station Cordova, IL 61242 May 2016 Page 1of122

Intentionally left blank Page 2of122

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 Ill. Program Description ...................................................................................................... 5 A. Sample Collection ............................................................................................... 5 B. Sample Analysis .................................................................................................. 7 C. Data Interpretation ................................................................................:............. 8 D. Program Exceptions ............................................................................................ 9 E. Program Changes ............................................................................................. 10 IV. Results and Discussion ............................................................................................... 10 A. Aquatic Environment ......................................................................................... 10

1. Surface Water. ........................................................................................ 10

2. Ground Water ...................................................*.......................................*1*1-

3. Fish ......................................................................................................... 11

4. Sediment. ......... :....................................................................................... 12 B. Atmospheric Environment ................................................................................. 12

1. Airborne .................................................................................................. 12

• a. Air Particulates ................................. ~ ........................................... 12

b. Airborne Iodine ................................ :........................................... 13

2. Terrestrial ............................................................. ~ .................................. 13

a. Milk ....................................... .' ........................................................ 13

b. Food Products ............................................................................. 13 C. Ambient Gamma Radiation ............................................................................... 14 D. Independent Spent Fuel Storage ............................. :... :.................................... 14 E. Land Use Surve-y ............................................................................................... 14 F. Errata Data ........................................................................................................ 15 G. Summary of Results - Inter-laboratory Comp~rison Program ......................... 15 Page 3of122

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for Quad Cities Nuclear Power Station, 2015 Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Tables Table B-1 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2015 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2015 Figures Figure B-1 Quad Cities REMP S(3mpling Locations.,... 2 Mile Radius, 2015 Figure B-2 Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2015 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

Table C-1.2 Concentrations of Tritium, lron-55 and Nickel-63 in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

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

Table C-11.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

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

ii Page 4of122

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

Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in

, the Vicinity of Quad Cities Nuclear Power Station, 2015.

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

Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations In Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples,.

Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015:

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

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

Table C-VIL2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

Table C-Vlll.1 Concentrations of Gamma Emitters in Food Product Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

Table C-IX.1 Quarterly OSLO Results for Quad Cities Nuclear Power Station, 2015.

Table C-IX.2 Mean Quarterly OSLO Results for the Inner Ring, Outer Ring, Other and Control Location for Quad Cities Nuclear Power Station, 2015.

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

Figures Figure C-1 Surface Water - Gross Beta - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2015.

Figure C-2 Surface Water - Tritium - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2bOO - 2015.

Figure C-3 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2015.

Figure C-4 Air Particulates - Gross Beta - Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2015.

Figure C-5 Air Particulates - Gross Beta - Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2015.

iii Page 5of122

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 - 2015.

Figure C-8 Air Particulates - Gross Beta - Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2015.

Figure C-9 Air Particulates - Gross Beta - _Stations Q-41 and Q-42 (C) Collected in the Vicinity of QCNPS, 2009 - 2015.

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

Teledyne Brown Engineering, 2015 Table D-4 ERA (a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2015 Table D-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2015 Appendix E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv Page 6of122

I. Summary and Conclusions In 2015, the Quad Cities Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 124 curies of noble gas, 1.1 BE-02 curies of fission and activation products, 29 curies of Carbon-14 and approximately 85 curies of tritium. The dose from both liquid and gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public. The results of those calculations and their comparison to the allowable limits were as follows:

NOTE: Percen't of applicable limits are for Unit 1 and Unit 2 combined (Site)

Gaseous and liquid radiation doses to members of the public at locations Location %of Applicable Estimated Age Site Distance* Direction Applicable Unit Effluents Organ Dose Group Limit (meters) (toward) Limit Noble Gas Gamma - Air Dose 2.16E-03 All 1029 NNE 1.38E-02 20 mRad Noble Gas Beta - Air Dose 3.27E-04 All 1029 NNE 8.18E-04 40 mRad Iodine, Particulate Total Body 4.29E-02 Child 1029 NNE 4.29E-01 10 mrem C-14 & Tritium Iodine, Particulate Bone 3.42E-01 Child 1029 NNE 1.14E+OO 30 mrem C-14 & Tritium Liquid Total Body 8.71E-06 Adult Mississippi River 1.45E-04 6 mrem Liquid Liver 1.30E-05 Teen Mississippi River 6.50E-05 20 mrem Skyshine Total Body 7.72E+OO All 800 N 3.09E+01 25 mrem Total Body (Gas + Liq+

40CFR190 7.76E+OO All 800 N 3.10E+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 31.0%

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

This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Quad Cities Nuclear Power Station (QCNPS) by Exelon covers the period 01January2015 through 31 December 2015. During thattime period, 1.556 analyses were performed on 1444 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.

Page 7of122

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 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 1-131 analyses were performed on air samples. No 1-131 was detected.

Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. No 1-131 was detected. Concentrations of naturally occurring isotopes (K-40 approximately 1200 pCi/L) were consistent with those detected in previous years. No fission or activation products were detected.

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

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

The relative comparison to control locations remains valid. OSLO 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 2015 through 31 December 2015.

Page 8of122

A. Objective 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 11.D-1 below).

Radioactivity is measured in curies. A curie is that amount of radioactive material needed to produce 37,000,000,000 nuclear disintegrations per second. This is an extremely large amount of radioactivity in comparison to environmental radioactivity. That is why radioactivity in the environment Page 9of122

is measured in picocuries. One picocurie is equal to one trillionth of a curie.

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

Table 11.D-1 Radiation Sources and Corresponding Doses (1)

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

Internal, inhalation (ZJ 228 Medical <3l 300 4

External, space 33 Consumer ( l 13 Internal, ingestion 29 Industrial(5l 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), inteNentional 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-? 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 Page 10of122

the air we breathe (about 228 millirem/yr). The majority of a person's annual dose results from exposure to radon and thoron in the air we breathe. These gases and their radioactive decay products arise from the decay of naturally occurring uranium, thorium and radium in the soil and building products such as brick, stone and concrete. Radon and thoron levels vary greatly with location, primarily due to changes in the concentration of uranium and thorium in the soil. Residents at some locations in Colorado, New York, Pennsylvania and New Jersey have a

• higher annual dose as a result of higher levels of radon/thoron gases in these areas. In total, these various sources of naturally-occurring radiation and radioactivity contribute to a total dose of about 311 mrem per year.

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

Ill. Program Description A. Sample Collection Samples for the QCNPS REMP were collected for Exelon Nuclear by ATI Environmental Inc. (Midwest Labs). This section describes the general sampling methods used by Environmental Inc. to obtain environmental samples for the QCNPS REMP in 2015. 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 Page 11of122

recreationally important species were collected semiannually at two locations, Q-24 and Q-29 (Control). Sediment samples composed of recently deposited substrate were collected at two locations semiannually, Q-39 and Q-40 (Control).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, and airborne iodine. Airborne iodine and particulate samples were collected and analyzed at ten locations (Q-01, Q-02, Q-03, Q-04, Q-13, Q-16, Q-37, Q-38, Q-41 and Q-42 (control)). Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The air particulate filters and air iodine samples were replaced weekly and sent to the laboratory for analysis.

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

Food products were collected annually in July at five locations (Q-Control, Q-Quad 1, Q-Quad 2, Q-Quad 3, and Q-Quad 4). Various types of broadleaf and root vegetables were collected and placed in new plastic bags, and sent to the laboratory for analysis.

• Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimeters (OSLO) were deployed and Thermoluminescent Dosimeters (TLD) were discontinued. The relative comparison to control locations remains valid. OSLO technology is different than that used in a TLD but has the same purpose (to measure direct radiation).

Each location consisted of 2 OSLO sets. The OSLO locations were placed on and around the QCNPS site as follows: An inner ring consisting of 15 locations (Q-101, Q-102, Q-103, Q-104, Q-105, Q-106, Q-107, Q-108, Q-109, Q-111, Q-112, Q-113, Q-114, Q-115 and Q-116).

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These OSLDs are located in 15 of the 16 meteorological sectors in the general area of the site boundary (approximately 0.1 - 3 miles from the site). There are no OSLDs located in the SSW sector because this sector is located over water.

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

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

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

The specific OSLO locations were determined by the following criteria:

1. The presence of relatively dense population;

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

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

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

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

B. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the QCNPS REMP in 2015 and the type of analyses. The analytical procedures used by the TBE laboratory a~e 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 pa rticu Iates.

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

3. Concentrations of tritium in ground and surface water.

4. Concentrations of 1-131 in air and milk.

5. Ambient gamma radiation levels at various site environs.

6. Concentrations of Fe-55 and 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:

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For surface water, groundwater and vegetation 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140 and La-140 were reported.

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

For air iodine, one nuclide, 1-131 was reported Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.

D. Program Exceptions For 2015 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 There were no anomalies in 2015.

Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date SW Q-33 01/01/15 - No sample; water frozen.

03/05/15 SW Q-34 01/01/15- No sample; water frozen.

03/05/15 Al Q-04 04/17/15 - Iodine cartridge lost in shipment.

SW Q-33 12/31/15 Sample collected 12/31/15. Container leaked; collector returned for new sample on 01/02/16; water frozen.

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Table D-2 LISTING OF MISSED SAMPLES (continued)

Sample Location Collection Reason

. . :l Type Code Date OSLO Q-115-2 12/31/15 OSLO found missing during quarterly change out OSLO Q-107-2, 12/31/15 OSLDs were lost in transit to Landauer.

Q-Q205-4 The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

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

IV. Results and Discussion A. Aquatic Environment

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

The following analyses were performed:

Gross Beta Samples from all locations were analyzed for concentrations of gross beta (Table C-1.1, Appendix C). Gross beta activity was detected in 19 of 20 samples. The values ranged from 2.6 to 5.3 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C). The required LLD was met.

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

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

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

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

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

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

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

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

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

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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) ran~ed from 5 to 34 E-03 pCi/m with a mean of 17 E-03 3

pCi/m . The results from the far-field locations (Group II) 3 ranged from 5 to 33 E-03 pCi/m with a mean of 17 E-03 pCi/m 3 . The results from the Control location (Group Ill) ranged from 7 to 35 E-03 pCi/m 3 with a mean of 18 E-03 3

pCi/m . Comparison of the 2015 air particulate data with previous year's data indicate no effects from the operation of Page 18of122

QCNPS. In addition comparisons of the weekly mean values for 2015 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 1-131 (Table C-Vl.1, Appendix C). All results were less than the LLD for 1-131.

2. Terrestrial

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

The following analyses were performed:

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

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

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

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

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

All of the OSLO measurements were below 30 mRem/quarter, with a range of 17 .1 to 29.0 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 2015 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:

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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, 11.5 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 2015.

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 DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:

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

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

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

The MAPEP defines three levels of performance: Acceptable (flag ="A"), Acceptable with Warning (flag ="W"), and Not

=

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

For the TBE laboratory, 129 out of 139 analyses performed met the specified acceptance criteria. Ten analyses (AP - Cr-51, U-234/233, Gr A, Sr-90; Soil Sr-90; Water - Ni-63, Sr-89, Sr-90, U natural; Vegetation Sr-90 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 Engineering's Analytics' June 2015 air particulate Cr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio of 1.30 (accepta_ble with warning) was exceeded. The air particulate sample is counted at a distance above the surface of the detector to avoid detector summing which could alter the results. Chromium-51 has the shortest half-life (27.7 days) and the lowest gamma energy (320.08 keV) of this mixed nuclide sample. Additionally, Cr-51 has only one gamma energy and also has a low intensity (9.38 gamma photons produced per 100 disintegrations). This geometry produces a Page 22 of 122

larger error for the Cr-51 and other gamma emitters as any distance from the detector decreases the counting rate and the probability of accurately detecting the nuclide energy. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would .statistically be considered acceptable. NCR 15-18

2. Teledyne Brown Engineering's MAPEP March 2015 soil Sr-90 result of 286 Total Bq/kg was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. Incomplete digestion of samples causes some of the sample to be left behind and is not present in the digested sample utilized for analysis. The procedure has been updated to include a more robust digestion using stirring during the heating phase. The MAPEP September 2014 soil Sr-90 series prior to this study was evaluated as acceptable with a result of 694 and an acceptance range of 601 -1115 Bq/kg. The MAPEP September 2015 series soil Sr-90 after this study was evaluated as acceptable with a result of 429 and an acceptance range of 298 - 553 Bq/kg. We feel the issue is specific to the March 2015 MAPEP sample. NCR 15-13

3. Teledyne Brown Engineering's MAPEP March 2015 airparticulate U-234/233 result of 0.0211 +/- 0.0120 Sq/sample was higher than the known value of 0.0155 Sq/sample, exceeding the upper ,

acceptance range of 0.0202 Sq/sample. Although evaluated as a failure, taking into consideration the uncertainty, TBE's result would overlap with the known value, which is statistically considered acceptable. MAPEP spiked the sample with significantly more U-238 activity (a found to known ratio of 0.96) than the normal U-234/233. Due to the extremely low activity, it was difficult to quantify the U-234/233. NCR 15-13

4. Teledyne Brown Engineering's MAPEP March 2015 air particulate gross alpha result of 0.448 Sq/sample was lower than the known value of 1.77 Sq/sample, exceeding the lower acceptance range of 0.53 Sq/sample. The instrument efficiency used for gross alpha is determined using a non-attenuated alpha standard. The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency. When samples contain alpha particles that are embedded in the sample media, due to the size of the alpha particle, some of the alpha particles are absorbed by the media and cannot escape to be counted. When the sample media absorbs the alpha particles this is known as self-absorption or attenuation.

The calibration must include a similar configuration/media to correct for the attenuation. In order to correct the low bias, TBE will Page 23 of 122

create an attenuated efficiency for MAPEP air particulate filters.

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

- 1.53 Sq/sample. Unlike the MAPEP samples, air particulate Gross alpha ~nalyses for power plants are not evaluated as a direct count sample. Power plant air particulate filters for gross alpha go through an acid digestion process prior to counting and the digested material is analyzed. NCR 15-13

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

6. Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Sq/sample was lower than the known value of 2.18 Sq/sample, exceeding the lower acceptance range of 1.53 Sq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for the laboratories analyzing the cross checks. TBE suspects that this may be the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity. TBE will no longer analyze the air particulate Sr-90 through MAPEP but will participate in the Analytics cross check program to perform both Sr-89 and Sr-90 in the air particulate matrix. NCR 15-21

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

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

8. & 9.Teledyne Brown Engineering's ERA May water Sr-89/90 results of 45.2 and 28.0 pCi/L, respectively were lower than the known values of 63.2 and 41.9 pCi/L, respectively, exceeding the lower acceptance limits of 51.1 and 30.8 pCi/L, respectively. The yields were on the high side of the TBE acceptance range, which indicates the present of excess calcium contributed to the yield, resulting in low results. NCR 15-09

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

The technician failed to dilute the original sample, but used the entfre 12 ml sample. When the results were recalculated without the dilution and using the 12 ml aliquot, the result of 57 .16 agreed with the assigned value of 56.2. NCR 15-19 For the ATI EIML laboratory, 90 of 94 analyses met the specified acceptance criteria. Four analyses (Water- Co-57, Fe-55; AP - Co-57; Soil - Sr-90) did not meet the specified acceptance criteria for the following reasons:

1. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 water Co-57 result of 10.2 Bq/L was lower than the known value of 29.9 Bq/L, exceeding the lower control limit of 20.9 Bq/L.

The reported value should have been 27.84, which would have been evaluated as acceptable. A data entry error resulted in a non-acceptable result.

2. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 AP Co-57 result of 0.04 Sq/sample was lower than the known value of 1.51 Bq/ sample, exceeding the lower control limit of 1.06 Sq/sample. The reported value should have been 1.58 Sq/sample, which would have been evaluated as acceptable. A data entry error resulted in a non-acceptable result.

3. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 soil Sr-90 result of 231 Bq/kg was lower than the known value of 425 Bq/kg, exceeding the lower control limit of 298 Bq/kg. The incomplete separation of calcium from strontium caused a failed low result. The reanalysis result of 352 Bq/kg fell within acceptance criteria.

4. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 water Fe-55 result of 4.2 Bq/L was lower than the known Page 25 of 122

value of 13.1 Bq/L, exceeding the lower control limit of 9.2 Bq/L.

The known activity was below the routine laboratory detection limits for the available aliquot fraction.

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

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APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

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Intentionally left blank Page 28of122

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL SUM.MARY FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTL'\'G PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WIIB IDGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION l\1EDIUMOR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER L!MlT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER GR-B 20 4 3.6 3.9 3.9 Q-34 CONTROL 0 (PCI/LffER) (10/10) (9/10) (9/10) CAMANCHE - UPSTREAM (2.9/4.9) (2.6/5.3) (2.6/5.3) 4.4 MILES NNE OF SITE H-3 8 2000 <LLD <LLD 0 FE-55 8 200 <LLD <LLD 0

>I NI-63 8 5 <LLD <LLD 0 GAMMA 20 MN-54 15 <LLD <LLD 0 C0-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 "ti I:>>

(IQ co N

\0 0

C0-60 15 <LLD <LLD 0 N

N

• THE MEAN AND 2 STANDARD DEVIATION V ALOES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREtv1ENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2015 Th'DICATOR COl'i'TROL LOCATION WITH IDGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQlHRED MEAN (M) MEAN (M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWERLIMIT (F) (F) (F) NAME NONROUT!NE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS ZN-65 30 <LLD <LLD 0 SURFACE WATER NB-95 15 <LLD <LLD 0 (PCI/LITER)

ZR-95 30 <LLD <LLD 0 N

I I-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 "ti LA-140 15 <LLD <LLD 0

~

(1) w 0

0

...... GROUNDWATER 1-1-3 8 2000 <LLD NA 0 N (PCI/LITER)

N

• THE .MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USJNG THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS JS JNDICATED JN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAJ\1E OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDnJMOR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN(M) MEAN(M) STATION# NU!vffiEROF PATHWAY SAMPLED ANALYSIS ANAL YSfS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFO.RlvlED OF DETECTlON RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GAMMA 8 MN-54 15 <LLD NA 0 GROUND WATER C0-58 15 <LLD NA 0 (PCl/LITER)

FE-59 30 <LLD NA 0

> I w

C0-60 15 <LLD NA 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA 0 ZR-95 30 <LLD NA 0

'"d I'll O<i (1) w I-131 15 <LLD NA 0 0

N N

CS-134 15 <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTL"IG PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL .MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWERLIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS CS-137 18 <LLD NA 0 GROUNDWATER BA-140 60 <LLD NA 0 (PCI/LITER)

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

'"'d po

{JC/

(1)

C0-60 130 <LLD <LLD 0 w

N 0

N ZN-65 260 <LLD <LLD 0 N

• THE MEAN AND 2 STANDARD DEV1ATION VALVES ARE CALCULATED USJNG THE POSITIVE VALVES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED JN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2015 INDICATOR CO~!ROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED "l\IBAN (M) MEAN (M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWERLIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RAi"JGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 FISH CS-134 130 <LLD <LLD 0

> I lJl (PCI/KG WET)

CS-137 150 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 SEDIMENT GAMMA 4 (PCI/KG DRY) MN-54 NA <LLD <LLD 0

'"d l>l (JC/

(1)

VJ VJ C0-58 NA <LLD <LLD 0 0

N N

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALVES FRACTION OF DETECTABLE MEASURElvIBNTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCK.ET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTL"iG PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WTI11 HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 SEDIMENT NB-95 NA <LLD <LLD 0 (PCI/KG DRY)

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

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) .MEAN (M) MEAN (M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFOR!VIBD OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED

!VIBASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE GR-B 520 10 17 18 18 Q-42 CONTROL 0 (E-3 PCJ/CU.METER) (465/468) (52/52) (52/52) LECLAIRE (5/37) (7/35) (7/35) 8.7 :tvfILES SSW OF SITE GAMMA 40 MN-54 NA <LLD <LLD 0

-.)

I C0-58 NA <LLD <LLD 0 AIR PARTICULATE FE-59 NA <LLD <LLD 0 (E-3 PC!/CU.METER)

C0-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 "d

~

(Jq

('1) w ZR-95 NA <LLD <LLD 0 u.

0.....,

N N

CS-134 50 <LLD <LLD 0

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCA TJONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTL"JG PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWERLIMIT (F) (F) (F) NAME NONROUTlNE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS CS-137 60 <LLD <LLD 0 BA-140 NA <LLD <LLD 0

>I 00 LA-140 NA <LLD <LLD 0 AIRIODINE GAi\1MA 519 (E-3 PCI/CU.l\IBTER) I-131 70 <LLD <LLD 0 MILK 1-131 20 <LLD NA 0 (PCI/LITER)

GAMMA 20 MN-54 NA <LLD NA 0 "O

~

(1)

(.;.) C0-58 NA <LLD NA 0 0\

0 N

N FE-59 NA <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN(M) STATION# NU!vlBEROF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFOR.lVlED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS C0-60 NA <LLD NA 0 ZN-65 NA <LLD NA 0

> I

\0 NB-95 NA <LLD NA 0 MILK ZR-95 NA <LLD NA 0 (PCI/LITER)

CS-134 15 <LLD NA 0 CS-137 18 <LLD NA 0 "d

Pl (IQ Cl>

w BA-140 60 <LLD NA 0

--..i 0

N N

LA-140 15 <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NA!\1E OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTli~G PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WITH HIGHEST A1'1"NUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION# NUrvIBEROF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORl'vlED PERFORl'vlED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) IvlEASUREMENTS VEGETATION GAMMA 20 (PCI/KG WET) MN-54 NA <LLD <LLD 0 C0-58 NA <LLD <LLD 0 0

I FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0 VEGETATION ZN-65 NA <LLD <LLD 0 (PCI/KG WET)

NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 N

N 1-131 60 <LLD <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2015 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN(M) MEAN(M) STATION# NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUT!NE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED lvlEASUREMENT) (LLD) MEASUREMENTS CS-134 60 <LLD <LLD 0 CS-137 80 <LLD <LLD 0 I BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 DIRECT RADIA TTON OSLD-QUARTERLY 325 NA 20.7 22.8 25.4 Q-211-2 INDICATOR 0 (MJLLIREM/QTR.) (317/317) (8/8) (4/4) 4.5 MILES SW (14.9/29.4) (18.7/29.7) (22.5/29 .4)

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

Intentionally left blank Page 40 of 122

APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS Page 41of122

Intentionally left blank Page 42 of 122

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2015 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) 3.3milesSSW C. Milk - bi-weekly I monthly Q-26 Bill Stanley Dairy (indicator) 3.1 miles ESE D. Air Particulates I Air Iodine Q-01 Onsite 1 (indicator) 0.5 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) 4.7miles 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 4.5miles NW Control Charles Leavens 9.5 miles NE H. Environmental Dosimetry - OSLO Inner Ring Q-101-1 0.6 miles N Q-101-2 0.9 miles N Q-102-1 1.3 miles NNE Q-102-3 1.4 miles NNE Q-103-1 and -2 1.2 miles NE 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 B-1 Page 43 of 122

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2015 Location Location Description Distance & Direction From Site H. Environmental Dosimetrv- OSLO (continued)

Inner Ring Q-109-1 0.9 miles S Q-109-2 1.2 miles S Q-111-1 2.6miles SW Q-111-2 2.5milesSW Q-112-1 2.5 miles WSW Q-112-2 2.2milesWSW Q-113-1 and -2 2.5miles W Q-114-1 2.1 miles WNW Q-114-2 2.5miles WNW Q-115-1 2.6miles NW Q-115-2 2.3miles NW Q-116-1 2.3miles 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 milesW Q-213-2 4.8 milesW Q-214-1 4.7milesWNW 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 4.3miles NNW 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) 4.7miles 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 B-2 Page 44of122

TABLE 8-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2015 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - OSLO (continued)

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 Page 45of122

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2015 Sample Analysis Sampling Method Analytical Procedure Number Medium Surface Water Gamma Spectroscopy Monthly composite from TBE, TBE-2007 Gamma emitting radioisotope analysis weekly grab samples Surface Water Gross Beta Monthly composite from TBE, TBE-2008 Gross Alpha andfor gross beta activity in weekly grab samples various matrices Surface Water Tritium Quarterly composite from TBE, TBE-2011 Tritium analysis in drinking water by liquid weekly grab samples scintillation Surface Water Iron and Nickel Quarterly composite from TBE, TBE-2006 lron-55 in various matrices weekly grab samples TBE, TBE-2013 Radionickel in various matrices Ground Water Gamma 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 Fish Gamma Spectroscopy Semi-annual samples TBE-2007 Gamma emitting radioisotope analysis collected via electroshocking or other techniques Sediment Gamma Spectroscopy Semi-annual grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis Air Particulates Gross Beta One-week composite of TBE, TBE-2008 Gross Alpha andfor gross beta activity in continuous air sampling various matrices through glass fiber filter paper Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2007 Gamma emitting radioisotope analysis each station Air Iodine Gamma Spectroscopy Weekly composite of TBE, TBE-2007 Gamma emitting radioisotope analysis continuous air sampling through charcoal filter Milk 1-131 Bi-weekly grab sample TBE, TBE-2012 Radioiodine in various matrices when cows are on pasture.

Monthly all other times Milk Gamma Spectroscopy Bi-weekly grab sample TBE, TBE-2007 Gamma emitting radioisotope analysis when cows are on pasture.

Monthly all other times Food Products Gamma Spectroscopy Annual grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis OSLO Optically Stimulated Quarterly OSLDs Landauer Incorporated Luminescence comprised of two Ab03:C Dosimetry Landauer Incorporated elements B-4 Page 46 of 122

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APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY Page 49 of 122

Table C-1.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION Q-33 Q-34 PERIOD 01/03/14 - 01/30/14 (1) (1) 02/07/14 - 02/28/14 (1) (1) 03/12/15 - 03/27/15 3.4 +/- 1.5 5.3 +/- 1.7 04/03/15 - 04/30/15 3.6 +/- 1.6 3.3 +/- 1.6 05/07/15 - 05/29/15 3.1 +/- 1.6 2.6 +/- 1.6 06/04/15 - 06/26/15 3.7 +/- 1.7 4.4 +/- 1.8 07/02/15 - 07/30/15 2.9 +/- 1.6 3.2 +/- 1.6 08/07/15 - 08/27/15 3.4 +/- 1.8 3.5 +/- 1.8 09/03/15 - 09/24/15 3.6 +/- 1.6 < 2.3 10/01/15 - 10/29/15 4.7 +/- 2.1 4.2 +/- 2.0 11/05/15 - 11/27/15 3.3 +/- 1.7 4.6 +/- 2.1 12/04/15 - 12/31/15 4.9 +/- 1.5 4.5 +/- 1.5 MEAN 3.6 +/- 1.3 3.9 +/- 1.7 Table C-1.2 CONCENTRATIONS OF TRITIUM, IRON, AND NICKEL IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION H-3 (DIST) FE-55 Nl-63 PERIOD Q-33 03/12/15 - 03/27/15 < 197 < 118 < 4.2 04/03/15 - 06/26/15 < 189 < 177 < 3.9 07/02/15 - 09/24/15 < 192 < 116 < 3.9 10/01/15 - 12/25/15 < 189 < 156 < 3.3 MEAN Q-34 03/12/15 - 03/27/15 < 169 < 141 < 4.0 04/03/15 - 06/26/15 < 182 < 111 < 3.8 07/02/15 - 09/24/15 < 199 < 174 < 4.0 10/01/15 - 12/31/15 < 186 < 129 < 3.3 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-1 Page 51of122

Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER + 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-33 01/03/15 - 01/30/15 (1) 02/07/15 - 02/28/15 (1) 03/12/15 - 03/27/15 < 2 <2 <4 <2 <3 <2 < 3 < 11 < 1 <2 < 18 <5 04/03/15 - 04/30/15 < 2 <3 < 6 <2 <5 < 3 < 5 < 15 < 2 <2 < 26 <7 05/07/15 - 05/29/15 <2 <3 < 6 < 3 <5 < 3 < 5 < 12 < 2 <2 < 21 <7 06/04/15 - 06/26/15 <4 < 5 < 9 < 4 < 8 < 5 < 9 < 15 < 5 < 5 < 30 < 8 07/02/15 - 07/30/15 < 2 <2 < 5 <2 <4 <2 <4 < 12 <2 < 2 < 21 <6 08/07/15 - 08/27/15 <4 <4 < 10 < 5 <9 < 5 < 8 < 14 <4 < 5 < 32 < 10 09/03/15 - 09/24/15 < 13 < 8 < 19 < 8 < 21 <8 < 14 < 13 < 8 < 9 < 44 < 12 10/01/15 - 10/29/15 < 2 < 2 <4 <2 <3 <2 <3 < 9 <2 <2 < 16 < 5 11/05/15 - 11/27/15 < 5 < 5 < 14 < 7 < 10 <6 < 10 < 14 < 5 <6 < 26 < 11 12/04/15 - 12/25/15 < 3 <4 < 7 <4 <5 <3 <6 < 14 < 3 < 3 < 30 < 8

('")

I MEAN N

Q-34 01/03/15 - 01/30/15 (1) 02/07/15 - 02/28/15 (1) 03/12/15 - 03/27/15 < 1 < 1 < 3 < 1 < 2 < 1 < 3 < 9 < 1 <2 < 15 < 5 04/03/ 15 - 04/30/ 15 < 3 <3 <6 < 3 <5 < 3 <6 < 14 <2 < 3 < 27 < 9 05/07/15 - 05/29/15 < 2 <2 < 5 <2 <4 < 2 <4 < 11 < 2 <2 < 21 < 7 06/04/15 - 06/26/15 < 5 <4 < 10 < 5 < 8 < 5 < 8 < 14 <4 < 5 < 36 < 9 07/02/15 - 07/30/15 <2 <2 <4 <2 <4 <2 <4 < 10 < 2 <2 < 18 < 5 08/07/15 - 08/27/15 <4 < 5 < 10 <4 < 9 <6 < 9 < 15 < 4 < 5 < 28 < 11 09/03/15 - 09/24/15 < 8 < 8 < 13 < 9 < 14 < 5 < 13 < 11 < 5 < 7 < 34 < 11 10/01/15 - 10/29/15 <2 <2 < 5 <2 <4 <2 <4 < 10 < 2 < 2 < 18 < 6 11/05/15 - 11/27/15 < 5 < 5 < 9 <4 < 8 < 5 < 10 < 12 < 5 < 6 < 37 < 9 12/04/15 - 12/31/15 < 5 < 5 < 10 < 5 < 9 < 5 <8 < 14 < 5 <4 < 30 < 12 MEAN

'"'d (IQ Cl>

Vl N

0 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION N

N

Table C-11.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION Q-35 Q-36 PERIOD 01/09/15 - 01/09/15 < 170 < 173 04/10/15 - 04/10/15 < 194 < 195 07/09/15 - 07/09/15 < 180 < 182 10/08/15 - 10/08/15 < 198 < 196 MEAN C-3 Page 53 of 122

Table C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-35 01/09/15 - 01/09/15 < 4 < 5 < 10 < 5 < 9 <4 < 8 < 13 < 5 < 5 < 31 <8 04/10/15 - 04/10/15 < 5 < 6 < 12 < 6 < 11 <6 < 10 < 15 < 5 < 5 < 30 < 15 07/09/15 - 07/09/15 <4 <4 < 10 < 5 < 8 < 5 < 8 < 10 < 5 < 5 < 28 < 9 10/08/15 - 10/08/15 < 6 < 7 < 17 < 8 < 15 < 9 < 12 < 13 < 6 < 8 < 41 < 12 MEAN Q-36 01/09/15 - 01/09/15 <4 <4 < 8 <4 < 7 <4 < 8 < 13 < 5 <4 < 28 <6 04/10/15 - 04/10/15 < 4 < 4 < 9 < 5 < 8 < 5 < 8 < 13 <4 <4 < 27 <9 07/09/15 - 07/09/15 < 5 < 5 < 11 < 5 < 9 <6 < 10 < 10 < 5 < 6 < 25 <8 10/08/15 - 10/08/15 < 5 < 6 < 13 < 7 < 13 <7 < 10 < 12 < 6 < 7 < 30 < 10 MEAN

(")

I

Table C-111.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PC/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-24 Channel Catfish 05/27/15 < 73 < 69 < 155 < 80 < 75 < 81 < 150 < 73 < 67 < 558 < 127 Freshwater Drum 05/27/15 < 52 < 76 < 122 < 74 < 155 < 90 < 148 < 66 < 78 < 620 < 243 Common Carp 10/14/15 < 59 < 35 < 107 < 57 < 144 < 47 < 103 < 46 < 58 < 366 < 118 Largemouth Bass 10/14/15 < 55 < 51 < 138 < 61 < 116 < 72 < 137 < 60 < 63 < 322 < 86 MEAN Q-29 Quill back 05/27/15 < 80 < 82 < 154 < 73 < 133 < 99 < 107 < 73 < 92 < 542 < 80 Walleye 05/27/15 < 61 < 52 < 129 < 41 < 120 < 67 < 129 < 53 < 61 < 429 < 113 n

I Common Carp 10/14/15 < 89 < 78 < 139 < 92 < 169 < 114 < 157 < 95 < 91 < 383 < 120 Vl Shorthead Redhorse 10/14/15 < 58 < 44 < 106 < 63 < 97 < 66 < 110 < 55 < 61 < 318 < 96 MEAN

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PC/KG DRY+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-39 05/16/15 < 43 < 51 < 134 < 44 < 106 < 52 < 94 < 38 < 48 < 352 < 93 10/22/15 < 51 < 42 < 105 < 42 < 139 < 55 < 109 < 49 < 83 < 344 < 118 MEAN Q-40 05/16/15 < 43 < 53 < 119 < 40 < 116 < 57 < 93 < 47 < 53 < 360 < 114 10/22/15 < 86 < 79 < 202 < 101 < 147 < 106 < 182 < 85 < 129 < 566 < 173 MEAN n

I 0\

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP Ill PERIOD Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 01/01/15 - 01/09/15 23 +/- 5 26 +/- 5 27 +/-5 26 +/- 5 31 +/- 5 24 +/- 4 21 +/- 5 15 +/-4 11 +/- 4 30 +/- 5 01/09/15 - 01/15/15 19 +/- 4 24 +/- 5 27 +/- 5 25+/-5 22+/-5 23+/-5 20 +/- 4 20 +/-4 23 +/- 5 24 +/- 5 01/15/15 - 01/22/15 15 +/- 4 17 +/- 4 17 +/- 4 16 +/- 4 22 +/- 5 17 +/- 4 17 +/- 4 17 +/- 4 20 +/- 4 25 +/- 5 01/22/15 - 01/29/15 8 +/-4 14 +/- 4 15 +/- 4 12+/-4 11+/-4 11+/-4 14 +/- 4 11 +/-4 12 +/- 4 17 +/- 4 01/29/15 - 02/05/15 16 +/- 4 20 +/- 4 19 +/-4 20 +/- 4 19 +/- 4 15 +/- 4 15 +/- 4 18 +/-4 18 +/- 4 18 +/- 4 02105/15 - 02/12115 15 +/- 4 24 +/- 5 26 +/-5 24 +/- 5 24 +/- 5 22 +/- 5 20 +/- 5 21 +/-5 24 +/- 5 25 +/- 5 02/12/15 - 02/20/15 19 +/- 4 27 +/-5 28 +/-5 29 +/- 5 28 +/- 4 24 +/- 4 26 +/- 5 25 +/-5 31 +/- 5 28 +/- 4 02120/15 - 02/26/15 23 +/- 4 33 +/- 5 29 +/-5 31 +/- 5 27 +/- 5 30 +/- 5 25 +/- 5 27 +/-5 37 +/- 6 35 +/- 6 02/26/15 - 03/05/15 19 +/- 4 21 +/-4 16 +/-4 21 +/- 4 18 +/- 4 16 +/- 4 15 +/- 4 23 +/-4 23 +/- 4 22 +/- 4 03/05/15 - 03/12115 12 +/- 3 17 +/- 4 17 +/- 4 15+/-4 13+/-4 11+/-4 12 +/- 3 14 +/-3 17 +/- 4 18 +/- 4 03/12/15 - 03/19/15 13 +/- 5 20 +/-5 19 +/- 5 16 +/- 5 17 +/- 4 16 +/- 4 15 +/- 5 14 +/- 4 19 +/- 4 21 +/- 5 03/19/15 - 03/27/15 15 +/- 4 12 +/-4 11 +/- 4 16 +/- 4 11 +/- 3 12 +/- 3 11 +/-4 12 +/-4 15 +/- 4 15 +/- 4 03/27/15 - 04/03/15 13 +/- 4 15 +/- 4 14 +/-4 20 +/- 4 14 +/- 4 12 +/- 4 13 +/-4 14 +/- 4 15 +/- 4 13 +/- 4 04/03/15 - 04/10/15 11 +/- 4 14 +/-4 14 +/-4 14 +/- 4 10 +/- 3 13 +/- 4 10 +/-3 12 +/- 4 16 +/- 4 17 +/- 4 04/10/15 - 04/17/15 16 +/- 4 14 +/-4 15 +/-4 15 +/- 4 14 +/- 4 16 +/- 4 9 +/- 4 16 +/-4 18 +/- 5 14 +/- 4 04/17/15 - 04/23/15 12 +/- 4 10 +/- 3 11 +/-3 9 +/- 3 13 +/- 4 -12 +/- 4 13 +/-4 10 +/- 3 12 +/- 4 12 +/- 4 04/23/15 - 05/01/15 12 +/- 3 9 +/-3 11 +/-3 10 +/- 3 15 +/- 4 15 +/- 4 10 +/-3 10 +/- 3 11 +/- 3 12 +/- 3 05/01/15 - 05/07/15 7+/-4 10 +/- 4 9 +/-4 10+/-4 10+/-4 9+/-4 6 +/-4 7 +/- 4 11 +/- 4 11 +/- 4 05/07/15 - 05/15/15 8 +/-3 10 +/-3 7 +/-3 9+/-3 11+/-3 9+/-3 6 +/-3 9 +/- 3 10 +/- 3 12 +/- 3 05/15/15 - 05/21/15 7 +/-4 6 +/-3 8+/-4 11 +/- 4 <7 < 6 6 +/- 3 7 +/- 3 7 +/- 4 7 +/- 4 05/21/15 - 05/29/15 12 +/- 4 11 +/-4 12 +/- 4 15 +/- 4 14 +/- 4 12 +/- 3 11 +/-4 12 +/- 4 14 +/- 4 12 +/- 3 05/29/15 - 06/04/15 9 +/-3 10 +/-3 11 +/- 4 13 +/- 4 12 +/- 4 14 +/- 4 11 +/-3 9 +/-3 8 +/- 4 15 +/- 4 06/04/15 - 06/11/15 13 +/- 4 15 +/-4 14 +/- 4 15 +/- 4 15 +/- 4 15 +/- 4 10 +/- 4 15 +/- 4 18 +/- 4 16 +/- 4 06/11 /15 - 06/18/15 6 +/- 3 7 +/- 3 8 +/-3 10 +/- 3 10 +/- 4 7 +/- 3 5 +/-3 8 +/-3 8 +/- 3 9 +/- 3 06/18/15 - 06/26/15 9 +/- 3 12 +/- 3 9 +/- 3 13 +/- 3 15 +/- 4 10 +/- 3 8+/-3 10 +/- 3 15 +/- 3 13 +/- 3 06/26/15 - 07/02115 11 +/- 4 14 +/- 4 12 +/- 4 12 +/- 4 10 +/- 4 13 +/- 4 10 +/- 4 10 +/- 4 12 +/- 4 15 +/- 4 07/02/15 - 07/09/15 12 +/- 4 11 +/- 4 17 +/- 4 14 +/- 4 15 +/- 4 12 +/- 4 10 +/- 3 12 +/- 4 11 +/- 4 15 +/- 4 07/09/15 - 07/17/15 5 +/-3 15 +/- 4 16 +/- 4 16 +/- 4 13 +/- 3 15 +/- 4 13 +/- 4 14 +/- 4 15 +/- 4 15 +/- 4 07/17/15 - 07/23/15 11 +/- 4 13 +/- 4 13 +/- 4 12 +/- 4 17 +/- 5 14 +/- 5 7 +/-4 10 +/- 4 13 +/- 5 11 +/- 4 07/23/15 - 07/31/15 13 +/- 4 20 +/- 4 18 +/- 4 15 +/- 4 20 +/- 4 18 +/- 4 13 +/- 4 15 +/- 4 15 +/- 4 18 +/- 4 07/31/15 - 08/07/15 13 +/- 4 13 +/- 4 19 +/- 5 23 +/- 5 20 +/- 4 18 +/- 4 13 +/- 4 19 +/- 5 14 +/- 4 19 +/- 4 08/07/15 - 08/14/15 16 +/- 4 22 +/- 5 21 +/- 4 13 +/- 4 21 +/- 5 < 5 12 +/- 4 22 +/- 5 16 +/- 4 18 +/- 4 08/14/15 - 08/21/15 17 +/- 4 20 +/- 4 27 +/- 5 17 +/- 4 18 +/- 4 33 +/- 5 15 +/- 4 12 +/- 4 17 +/- 4 19 +/- 4 08/21/15 - 08/27/15 10 +/- 4 16 +/- 4 16 +/- 4 15+/-4 12+/-5 11+/-5 10 +/- 4 15 +/- 4 10 +/- 5 10 +/- 4 08/27/15 - 09/03/15 27 +/- 5 34 +/- 6 27 +/- 5 27+/-5 32+/-5 30+/-5 21 +/- 5 31 +/- 5 25 +/- 5 32 +/- 5 09/03/15 - 09/11/15 22 +/- 4 24 +/- 4 28 +/- 5 22 +/- 4 30 +/- 5 27 +/- 4 20 +/- 4 25 +/- 4 25 +/- 4 24 +/- 4 09/11/15 - 09/17/15 19 +/- 4 20 +/- 4 19 +/- 4 19 +/- 4 23 +/- 5 18 +/- 5 8+/-3 18 +/- 4 21 +/- 5 20 +/- 5 09/17/15 - 09/24/15 11 +/- 4 14 +/- 4 15 +/- 4 13 +/- 4 17 +/- 4 18 +/- 4 10 +/- 4 15 +/- 4 11 +/- 4 14 +/- 4 09/24/15 - 10/01/15 18 +/- 4 10 +/- 3 18 +/- 4 16 +/- 3 16 +/- 4 22 +/- 4 16 +/- 3 20 +/- 4 23 +/- 4 22 +/- 4 10/01/15 - 10/08/15 17 +/- 4 13 +/- 4 23 +/- 5 22 +/- 5 14 +/- 4 15 +/- 4 12 +/- 4 14 +/- 4 17 +/- 4 14 +/- 4 10/08/15 - 10/16/15 13 +/- 4 16 +/- 4 12 +/- 4 11+/-4 18+/-4 18+/-4 14 +/- 4 13 +/-4 13 +/- 3 12 +/- 3 10/16/15 - 10/23/15 28 +/- 5 26 +/- 5 30 +/- 5 29 +/- 5 31 +/- 5 26 +/- 5 25 +/- 5 30 +/- 5 29 +/- 5 26 +/- 5 10/23/15 - 10/29/15 18 +/- 4 17 +/- 4 16 +/- 4 16 +/- 4 18 +/- 5 14 +/- 4 15 +/- 3 16 +/- 4 15 +/- 4 17 +/- 4 10/29/15 - 11/05/15 13 +/- 4 22 +/- 5 17 +/- 4 17 +/- 4 18 +/- 4 18 +/- 4 17 +/- 4 18 +/-4 20 +/- 4 18 +/- 4 11/05/15 - 11/13/15 23 +/- 5 21 +/- 4 26 +/- 5 24 +/- 5 23 +/- 4 22 +/- 4 21 +/- 5 30 +/-5 24 +/- 4 22 +/- 4 11/13/15 - 11/19/15 13 +/- 3 14 +/- 3 8 +/- 3 14 +/- 3 16 +/- 4 19 +/- 5 13 +/- 3 16 +/-4 20 +/- 5 19 +/- 5 11/19/15 - 11/27/15 15 +/- 5 14 +/- 5 19 +/- 5 13 +/- 4 12 +/- 4 14 +/- 4 15 +/- 5 15 +/-5 15 +/- 4 15 +/- 4 11/27/15 - 12/04115 19 +/-4 19 +/- 4 8 +/-3 21 +/- 4 22 +/- 4 19 +/- 4 18 +/- 4 21 +/-4 22 +/- 4 20 +/- 4 12104115 - 12/10115 28 +/-5 26 +/- 5 24 +/-4 28 +/- 5 31 +/- 5 31 +/- 5 30 +/- 5 26 +/-5 31 +/- 5 31 +/- 5 12110115 - 12117/15 13 +/-4 17 +/- 4 12 +/-4 14 +/- 4 14 +/- 4 14 +/- 4 16 +/- 4 12 +/- 4 14 +/- 4 11 +/- 4 12/17/15 - 12/25/15 25 +/- 5 29 +/- 5 30 +/-5 28+/-5 30+/-5 27+/-4 27 +/- 5 18 +/- 4 29 +/- 5 27 +/- 5 12125/15 - 12/31/15 19 +/-4 19 +/- 4 22 +/-4 20 +/- 4 15 +/- 4 12 +/- 4 17 +/- 4 26 +/-5 10 +/- 4 17 +/- 5 MEAN 15 +/- 11 17 +/- 13 17 +/- 13 17+/-12 18+/-13 17+/-13 14 +/- 12 16 +/- 12 17 +/- 13 18 +/- 13 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-7 Page 57 of 122

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, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA GROUP I - NEAR-SITE LOCATIONS GROUP II - FAR-FIELD LOCATIONS GROUP Ill - CONTROL LOCATION COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/-

PERIOD 2SD PERIOD 28D PERIOD 28D 01/01/15 - 01/29/15 8 27 19 +/- 12 01/01/15 - 01/30/15 11 31 18 +/- 11 01/01/15 - 01/29/15 17 30 24 +/- 11 01/29/15 - 02/26/15 15 33 24 +/- 11 01/29/15 - 02/27/15 15 37 24 +/- 11 01/29/15 - 02/26/15 18 35 26 +/- 14 02/26/15 - 04/03/15 11 21 16 +/- 6 02/26/15 - 04/03/15 11 23 15 +/- 7 02/26/15 - 04/03/15 13 22 18 +/- 8 04/03/15 - 05/01/15 9 16 12 +/- 5 04/03/15 - 05/01/15 9 18 13 +/- 5 04/03/15 - 04/30/15 12 17 14 +/- 5 05/01/15 - 05/29/15 6 15 10 +/- 5 04/30/ 15 - 05/29/15 6 14 9 +/- 5 04/30/15 - 05/29/15 7 12 11 +/- 4 05/29/15 - 07/02/15 6 15 11 +/- 5 05/29/15 - 07/03/15 5 18 11 +/- 6 05/29/15 - 07/02/15 9 16 14 +/- 6 07/02/15 - 07/31/15 5 20 14 +/- 7 07/02/15 - 08/01/15 7 20 13 +/- 6 07/02/15 - 07/31/15 11 18 15 +/- 6 07/31/15 - 09/03/15 10 34 20 +/- 12 07/31/15 - 09/04/15 10 36 19 +/- 15 07/31/15 - 09/03/15 10 32 20 +/- 16 09/03/15 - 10/01 /15 10 28 18 +/- 10 09/03/15 - 10/03/15 8 30 19 +/- 11 09/03/15 - 10/01/15 14 24 20 +/- 9 10/01/15 - 10/29/15 11 30 19 +/- 13 10/01/15 - 10/31/15 12 31 18 +/- 12 10/01/15 - 10/29/15 12 26 17 +/- 12 10/29/15 - 12/04/15 8 26 17 +/- 10 10/29/15 - 12/04/15 12 30 19 +/- 8 10/29/15 - 12/04/15 15 22 19 +/- 5 12/04/15 - 12/31/15 12 30 22 +/- 12 12/04/15 - 01/01/16 10 31 21 +/- 16 12/04/15 - 12/31/15 11 31 22 +/- 18 nI

°" 01/02/15 - 01/01/16 5 34 17 +/- 12 01/01/15 - 01/01/16 5 37 17 +/- 13 01/01/15 - 12/31/15 7 35 18 +/- 13

'"d

~C1l Vl

°"

0.....,

N N

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-01 01/02/15 - 04/03/15 < 3 < 5 < 14 <4 <7 <5 < 10 <4 <4 < 156 < 44 04/03/15 - 07/03/15 < 2 < 3 < 6 < 2 <4 <3 < 5 < 2 < 2 < 65 < 16 07/03/15 - 10/03/15 < 2 <4 < 9 <2 <6 < 4 <7 < 3 < 2 < 77 < 25 10/03/15 - 01/01/16 < 2 < 2 <4 < 1 < 3 <2 < 3 < 1 < 1 < 11 < 9 MEAN Q-02 01/02/15 - 04/03/15 < 3 < 5 < 9 <4 < 9 <6 <8 <3 < 3 < 147 < 46 04/03/15 - 07/03/15 < 3 < 3 < 11 < 3 < 7 < 3 < 6 < 2 <2 < 94 < 41 07/03/15 - 10/03/15 < 3 < 3 < 10 < 2 < 3 <3 < 6 < 3 < 2 < 76 < 40 10/03/15 - 01/01/16 < 3 <2 <6 < 2 < 5 <3 < 5 <2 < 2 < 25 < 8 MEAN

(")

I

\0 Q-03 01 /02/15 - 04/03/15 < 3 < 5 < 11 <3 < 8 <4 < 7 <3 < 3 < 144 < 43 04/03/15 - 07/03/15 < 2 < 3 < 8 < 2 < 6 <4 < 5 < 2 < 2 < 73 < 26 07/03/15 - 10/03/15 < 3 <4 < 15 <2 < 9 < 4 < 8 <4 < 4 < 107 < 38 10/03/15 - 01/01/16 < 1 < 2 < 5 < 1 <2 <2 < 3 < 2 <2 < 23 < 10 MEAN Q-04 01/02/15 - 04/03/15 < 3 <4 < 7 < 2 < 6 <4 < 6 < 3 < 2 < 107 < 42 04/03/15 - 07/03/15 <4 < 5 < 14 < 5 <7 < 6 < 11 <4 < 4 < 119 < 46 07/03/15 - 10/03/15 < 3 < 3 < 7 < 2 <8 <4 < 6 < 2 < 2 < 79 < 33 10/03/15 - 01/01 /16 < 3 <4 <8 < 3 <4 < 3 < 5 < 3 < 2 < 29 < 7 MEAN Q-13 01/01/15 - 04/03/15 < 5 < 6 < 12 <6 < 9 < 8 < 14 < 4 < 5 < 162 < 63 04/03/15 - 07/02/15 < 3 <4 < 9 <3 < 8 <4 < 8 < 3 < 3 < 77 < 39 "t:i I>>

(Jq 07/02/15 - 10/01/15 < 2 <4 < 10 < 3 < 5 <4 < 7 < 3 < 2 < 98 < 30 (I) 10/08/15 - 12/31/15 < 3 <3 <4 < 3 < 7 <3 < 5 < 3 < 2 < 34 < 11 VI

\0 0

....., MEAN N

N

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-16 01/01/15 - 04/03/15 <4 <4 < 12 < 3 < 9 < 5 < 8 < 3 < 3 < 159 < 55 04/03/15 - 07/02/15 <4 < 5 < 13 < 3 < 8 < 5 < 8 < 4 < 3 < 128 < 40 07/02/15 - 10/01/15 < 3 <4 < 8 <2 < 5 < 3 < 6 < 2 < 2 < 75 < 34 10/08/15 - 12/31/15 < 1 < 2 < 6 <2 <4 < 3 <4 < 2 <2 < 25 < 5 MEAN Q-37 01/02/15 - 04/03/15 <4 < 6 < 19 <4 < 11 < 7 < 10 <5 <4 < 197 < 66 04/03/15 - 07/03/15 <2 < 3 < 8 < 3 <5 < 3 < 5 <2 < 2 < 71 < 26 07/03/15 - 10/03/15 < 3 <4 < 10 < 3 < 8 <4 < 6 < 3 < 3 < 111 < 27 10/03/15 - 01/01/16 <2 < 2 < 3 <2 <4 < 3 < 5 < 2 <2 < 34 < 8 MEAN n

0 I

Q-38 01/02/15 04/03/15 04/03/15 07/03/15

<4

< 2 5

2 14 7

2 2

< 11

<4

<4

<2

< 9

<5

< 3

< 2

<4

<2 175 65 45 29 07/03/15 - 10/03/15 < 1 < 0 < 2 < 3 <5 < 1 <4 < 1 < 0 < 65 < 22 10/03/15 - 01/01/16 < 2 < 2 < 7 < 3 <5 <2 < 5 <2 < 2 < 24 < 5 MEAN Q-41 01/01/15 - 04/03/15 < 3 <4 < 13 < 3 < 7 <4 < 9 < 3 < 3 < 145 < 66 04/03/15 - 07/02/15 < 2 <4 < 7 < 2 < 5 <4 < 5 < 2 < 2 < 110 < 49 07/02/15 - 10/01/15 < 3 < 5 < 10 < 3 < 10 < 5 < 10 <4 < 3 < 141 < 50 10/08/15 - 12/31/15 < 1 < 2 < 2 < 2 <4 <2 <2 < 1 < 1 < 18 < 6 MEAN Q-42 01/01/15 - 04/03/15 <4 <6 < 12 <4 < 12 <6 < 11 < 5 < 4 < 202 < 33 04/03/15 - 07/02/15 < 3 <4 < 11 <3 < 6 <4 <6 < 2 < 3 < 77 < 25

'"d 07/02/15 - 10/01/15 <2 <4 < 11 <2 < 5 <4 <5 <2 < 2 < 71 < 57 (Jq (1) 10/08/15 - 12/31/15 < 1 <2 < 5 <2 < 5 <3 <2 <2 < 2 < 33 < 17 0\

0 0

....., MEAN N

N

Table C-Vl-.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP I GROUP II I GROUP Ill PERIOD Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 61161115 - 61/69115 < 33 < 61 < 59 < 59 < 65 < 34 < 68 < 68 < 63 < 61 01/09/15 - 01/15/15 < 21 < 53 < 52 < 52 < 63 < 65 < 29 < 53 < 67 < 64 01/15/15 - 01/22/15 < 17 < 41 < 39 < 39 < 45 < 21 < 33 < 33 < 39 < 38 01/22/15 - 01/29/15 < 18 < 47 < 45 < 45 < 48 < 20 < 45 < 45 < 49 < 48 01/29/15 - 02/05/15 < 22 < 50 < 49 < 49 < 54 < 46 < 41 < 23 < 48 < 46 02/05/15 - 02/12/15 < 24 < 63 < 61 < 61 < 67 < 61 < 56 < 56 < 27 < 62 02/12/15 - 02/20/15 < 23 < 53 < 52 < 52 < 42 < 14 < 48 < 48 < 41 < 39 02/20/15 - 02/26/15 < 22 < 51 < 50 < 50 < 63 < 54 < 43 < 43 < 55 < 30 02/26/15 - 03/05/15 < 23 < 58 < 56 < 56 < 60 < 22 < 50 < 50 < 55 < 53 03/05/15 - 03/12/15 < 20 < 53 < 51 < 51 < 68 < 31 < 42 < 42 < 58 < 56 03/12/15 - 03/19/15 < 22 < 57 < 55 < 55 < 51 < 23 < 59 < 59 < 56 < 55 03/19/15 - 03/27/15 < 20 < 8 < 19 < 19 < 16 < 7 < 20 < 20 < 18 < 17 03/27/15 - 04/03/15 < 22 < 56 < 54 < 54 < 57 < 22 < 51 < 51 < 53 < 53 04/03/15 - 04/10/15 < 20 < 52 < 50 < 50 < 47 < 20 < 51 < 51 < 49 < 48 04/10/15 - 04/17/15 < 64 < 64 < 62 < 62 < 25 < 49 < 48 < 48 < 51 < 21 04/17/15 - 04/23/15 < 57 < 57 < 55 (1) < 65 < 36 < 48 < 48 < 60 < 57 04/23/15 - 05/01/15 < 44 < 44 < 42 < 42 < 65 < 66 < 62 < 53 < 58 < 56 05/01/15 - 05/07/15 < 61 < 61 < 59 < 23 < 69 < 69 < 63 < 38 < 43 < 42 05/07/15 - 05/15/15 < 55 < 55 < 53 < 53 < 18 < 20 < 24 < 22 < 19 < 19 05/15/15 - 05/21/15 < 63 < 63 < 61 < 62 < 35 < 46 < 62 < 41 < 37 < 40 05/21/15 - 05/29/15 < 58 < 58 < 56 < 48 < 41 < 40 < 62 < 62 < 53 < 52 05/29/15 - 06/04/15 < 37 < 38 < 36 < 53 < 67 < 25 < 53 < 53 < 68 < 66 06/04/15 - 06/11/15 < 55 < 55 < 53 < 53 < 68 < 68 < 65 < 62 < 69 < 65 06/11/15 - 06/18/15 < 49 < 49 < 47 < 52 < 59 < 58 < 52 < 57 < 65 < 64 06/18/15 - 06/26/15 < 62 < 62 < 60 < 60 < 63 < 61 < 60 < 48 < 48 < 49 06/26/15 - 07/02/15 < 57 < 58 < 56 < 56 < 54 < 52 < 48 < 58 < 62 < 63 07/02/15 - 07/09/15 < 15 < 38 < 37 < 37 < 41 < 17 < 37 < 37 < 40 < 39 07/09/15 - 07/17/15 < 61 < 62 < 60 < 59 < 23 < 41 < 45 < 45 < 41 < 22 07/17/15 - 07/23/15 < 53 < 53 < 22 < 51 < 64 < 23 < 48 < 48 < 59 < 58 07/23/15 - 07/31/15 < 55 < 30 < 53 < 53 < 58 < 52 < 49 < 19 < 52* < 52 07/31/15 - 08/07/15 < 28 < 64 < 64 < 63 < 57 < 52 < 33 < 60 < 52 .. < 53 08/07/15 - 08/14/15 < 53 < 52 < 53 < 53 < 22 < 53 < 52 < 52 < 54 < 22 08/14/15 - 08/21/15 < 14 < 36 < 36 < 36 < 35 < 66 < 70 < 70 < 67 < 28 08/21/15 - 08/27/15 < 34 < 13 < 33 < 33 < 4a < 55 < 38 < 38 < 23 < 55 08/27/15 - 09/03/15 < 67 < 65 < 65 < 65 < 26 < 64 < 69 < 69 < 25 < 65 09/03/15 - 09/11/15 < 36 < 35 < 35 < 35 < 12 < 40 < 45 < 45 < 40 < 17 09/11/15 - 09/17/15 < 36 < 19 < 35 < 35 < 44 < 59 < 49 < 49 < 59 < 30 09/17/15 - 09/24/15 < 14 < 36 < 36 < 36 < 38 < 51 < 49 < 49 < 51 < 21 09/24/15 - 10/01/15 < 18 < 44 < 44 < 44 < 63 < 61 < 44 < 44 < 61 < 25 10/01/15 - 10/08/15 < 11 < 28 < 28 < 28 < 32 < 13 < 28 < 28 < 32 < 32 10/08/15 - 10/16/15 < 26 < 66 < 66 < 66 < 64 < 28 < 70 < 70 < 66 < 69 10/16/15 - 10/23/15 < 18 < 44 < 44 < 44 < 39 < 15 < 42 < 42 < 35 < 37 10/23/15 - 10/29/15 < 13 < 33 < 33 < 33 < 53 < 61 < 39 < 39 < 26 < 62 10/29/15 - 11105/15 < 12 < 30 < 30 < 30 < 28 < 18 < 48 < 48 < 43 < 45 11/05/15 - 11/13/15 < 26 < 60 < 59 < 59 < 53 < 22 < 68 < 62 < 54 < 55 11/13/15 - 11/19/15 < 13 < 32 < 32 < 32 < 52 < 27 < 40 < 40 < 63 < 65 11/19/15 - 11/27/15 < 28 < 70 < 70 < 70 < 54 < 17 < 56 < 56 < 41 < 44 11/27/15 - 12/04/15 < 67 < 65 < 25 < 65 < 66 < 51 < 51 < 51 < 21 < 52 12/04/15 - 12/10/15 < 44 < 17 < 43 < 43 < 55 < 57 < 47 < 19 < 57 < 59 12/10/15 - 12/17/15 < 34 < 33 < 13 < 33 < 36 < 42 < 40 < 40 < 18 < 43 12/17/15 - 12/25/15 < 63 < 24 < 61 < 61 < 55 < 25 < 70 < 70 < 60 < 63 12/25/15 - 12/31/15 < 16 < 41 < 41 < 40 < 55 < 58 < 46 < 19 < 58 < 60 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-11 Page 61of122

Table C-Vll.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA INDICATOR FARM COLLECTION Q-26 PERIOD 01/02/15 < 0.7 02/06/15 < 0.7 03/06/15 < 0.8 04/03/15 < 0.5 05/01/15 < 1.0 05/15/15 < 0.4 05/29/15 < 0.5 06/12/15 < 0.6 06/27/15 < 0.6 07/10/15 < 0.7 07/24/15 < 0.5 08/07/15 < 0.4 08/21/15 < 0.7 09/04/15 < 0.5 09/18/15 < 0.4 10/07/15 < 0.7 10/17/15 < 0.9 10/31/15 < 0.7 11/13/15 < 0.8 12/04/15 < 0.4 MEAN C-12 Page 62of122

Table C-Vll.2 CONCENTRATIONS OF GAMMA EMiTTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-26 01/02/15 < 9 < 9 < 18 < 7 < 18 < 9 < 16 < 7 < 8 < 52 < 10 02/06/15 < 5 < 5 < 16 < 5 < 15 <7 < 9 < 5 <5 < 46 <9 03/06/15 < 5 < 6 < 15 < 5 < 16 <6 < 10 <4 <5 < 31 < 14 04/03/15 < 5 < 5 < 12 < 5 < 12 <6 <8 < 5 <6 < 32 < 10 05/01/15 <7 <7 < 14 < 6 < 16 < 7 < 11 < 6 < 7 < 39 < 11 05/15/15 < 5 <6 < 15 < 6 < 13 < 6 < 9 < 5 < 6 < 42 < 13 05/29/15 < 5 < 5 < 11 < 5 < 11 < 5 < 9 <4 < 5 < 28 <9 06/12/15 <7 < 5 < 16 < 7 < 14 <7 < 11 < 6 < 5 < 33 < 11 06/27/15 < 6 < 7 < 16 < 6 < 13 <7 < 11 < 6 < 7 < 32 <5 07/10/15 <7 < 7 < 17 < 7 < 17 <7 < 14 < 8 <7 < 35 <8 07/24/15 <4 <4 < 8 <4 < 9 <4 < 6 <4 <4 < 22 <6

(")

I 08/07/15 <9 < 12 < 23 < 10 < 17 < 8 < 17 < 9 < 9 < 53 < 13 w 08/21/15 < 6 <8 < 17 < 9 < 14 < 8 < 13 < 7 < 9 < 32 < 10 09/04/15 <6 <8 < 20 < 8 < 20 < 6 < 13 < 7 < 10 < 42 < 13 09/18/15 <8 < 9 < 21 < 7 < 20 < 9 < 16 < 8 < 10 < 39 <9 10/07/15 < 8 < 9 < 17 < 9 < 23 <8 < 16 < 7 < 9 < 39 <7 10/17/15 < 6 <7 < 20 < 7 < 20 < 9 < 16 < 7 < 7 < 34 <8 10/31/15 <6 <6 < 13 < 6 < 17 < 8 < 12 < 6 <7 < 44 < 12 11/13/15 <6 <6 < 13 < 7 < 14 <6 < 12 < 6 < 7 < 26 <8 12/04/15 < 8 <7 < 18 < 10 < 18 <7 < 15 < 7 < 8 < 42 < 14 MEAN

Table C-Vlll.1 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-CONTROL Cucumbers 07/22/15 < 8 < 11 < 29 < 9 < 21 < 10 < 18 < 66 < 10 < 10 < 124 < 23 Dill 07/22/15 < 13 < 15 < 38 < 13 < 36 < 14 < 25 < 58 < 12 < 14 < 120 < 29 Horseradish 07/22/15 < 11 < 11 < 30 < 11 < 26 < 12 < 21 < 58 < 9 < 11 < 104 < 31 Rhubarb leaves 07/22/15 < 13 < 14 < 34 < 12 < 27 < 13 < 22 < 59 < 11 < 12 < 112 < 27 MEAN Q-QUAD 1 Arugula 07/21/15 < 12 < 13 < 38 < 12 < 28 < 14 < 25 < 58 < 11 < 12 < 114 < 29 Potatoes 07/21/15 < 12 < 12 < 31 < 11 < 28 < 14 < 23 < 59 < 11 < 11 < 104 < 29 Radishes 07/21/15 < 7 < 8 < 21 < 8 < 17 < 8 < 14 < 51 < 6 < 8 < 80 < 24 Red Oak leaves 07/21/15 < 11 < 11 < 31 < 11 < 28 < 11 < 22 < 58 < 10 < 12 < 94 < 27 MEAN

(") Q-QUAD2 I

...... Cucumbers 07/22/15 < 11 < 13 < 23 < 10 < 25 < 12 < 21 < 63 < 10 < 12 < 124 < 33

""" Onions 07/22/15 <4 <4 < 11 < 5 < 12 < 6 < 8 < 26 < 4 < 6 < 40 < 11 Peppers 07/22/15 < 3 <4 < 10 < 5 < 9 <4 < 8 < 21 < 4 < 3 < 36 < 11 Tomatoes 07/22/15 < 10 < 10 < 25 < 9 < 21 < 10 < 17 < 46 < 8 < 9 < 82 < 22 Zucchini 07/22/15 < 10 < 11 < 25 < 9 < 23 < 11 < 21 < 52 < 8 < 11 < 100 < 25 MEAN Q-QUAD 3 Brussel Sprouts 07/21/15 < 8 < 8 < 22 < 9 < 18 < 11 < 15 < 59 < 7 < 10 < 93 < 16 Horseradish 07/21/15 < 8 < 8 < 13 < 6 < 17 < 7 < 13 < 42 < 7 < 10 < 65 < 16 Lettuce 07/21/15 < 9 < 8 < 30 < 10 < 21 < 11 < 20 < 57 < 8 < 8 < 104 < 24 Sun Chokes 07/21/15 < 10 < 10 < 23 < 8 < 20 < 10 < 18 < 52 < 8 < 11 < 92 < 24 MEAN Q-QUAD4 Cabbage 07/21/15 < 7 < 8 < 20 < 7 < 16 < 8 < 15 < 42 < 7 < 7 < 76 < 20 Carrots 07/21/15 < 8 < 9 < 22 < 8 < 19 < 10 < 18 < 58 < 8 < 8 < 88 < 21 Potatoes 07/21/15 <7 < 9 < 21 < 8 < 19 < 9 < 15 < 46 < 7 < 8 < 80 < 23 Rhubarb leaves 07/21/15 < 12 < 13 < 30 < 12 < 29 < 16 < 24 < 58 < 11 < 11 < 108 < 26 MEAN

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

Q-01-1 21.3 +/- 3.0 19.3 21.0 21.9 22.8 Q-01-2 21.1 +/- 4.2 18.3 23.3 21.6 21.2 Q-02-1 21.3 +/- 3.9 18.5 23.1 21.9 21.6 Q-02-2 21.5 +/- 5.0 18.2 20.8 23.4 23.5 Q-03-1 19.8 +/- 3.6 17.6 19.1 21.0 21.5 Q-03-2 21.0 +/- 3.2 19.1 22.9 20.5 21.6 Q-04-1 21.1 +/- 1.8 20.3 22.2 20.5 21.5 Q-04-2 22.1 +/- 4.3 19.0 23.5 22.2 23.6 Q-13-1 22.5 +/- 3.5 19.9 23.6 23.5 23.0 Q-13-2 22.3 +/- 4.2 20.0 21.2 23.4 24.6 Q-16-1 20.1 +/- 4.5 17.3 22.0 19.2 21.9 Q-16-2 20.9 +/- 5.2 17.1 23.0 21.2 22.1 Q-37-1 22.8 +/- 3.4 20.3 24.0 23.9 22.8 Q-37-2 23.1 +/- 4.3 20.0 24.8 24.1 23.5 Q-38-1 24.5 +/- 8.1 19.5 23.4 29.0 26.1 Q-38-2 24.4 +/- 4.3 21.3 26.1 25.5 24.5 Q-41-1 23.8 +/- 4.2 20.6 24.6 25.0 24.9 Q-41-2 23.4 +/- 4.7 19.9 24.2 24.1 25.2 Q-42-1 23.7 +/- 5.2 20.1 26.2 24.6 23.8 Q-42-2 24.1 +/- 4.7 21.1 26.2 23.4 25.8 Q-101-1 21.9 +/- 2.4 20.1 22.6 22.2 22.6 Q-101-2 21.9 +/- 4.9 18.2 22.7 23.2 23.3 Q-102-1 23.1 +/- 3.5 20.5 24.1 24.1 23,7 Q-102-3 21.6 +/- 3.1 20.0 22.9 21.4 23.3 Q-103-1 20.6 +/- 2.1 19.0 21.2 21.2 20.8 Q-103-2 20.3 +/- 3.3 17.8 20.7 21.1 21.4 Q-104-1 20.4 +/- 2.7 19.5 20.1 19.6 22.4 Q-104-2 21.4 +/- 3.4 18.9 21.8 22.8 21.9 Q-105-1 20.8 +/- 4.3 17.6 22.5 21.3 21.6 Q-106-2 21.7 +/- 4.0 18.7 23.2 22.2 22.5 Q-106-3 21.3 +/- 3.8 18.6 22.4 21.2 22.8 Q-107-2 20.9 +/- 4.7 18.2 22.2 22.3 (1)

Q-107-3 21.3 +/- 1.9 20.1 21.6 21.2 22.4 Q-108-1 21.4 +/- 4.8 18.0 23.1 23.1 21.5 Q-108-2 21.7 +/- 0.7 21.8 21.9 21.8 21.1 Q-109-1 22.5 +/- 5.5 18.7 25.3 22.5 23.3 Q-109-2 21.9 +/- 4.6 19.4 24.6 20.7 22.7 Q-111-1 22.0 +/- 2.8 20.2 22.1 22.2 23.6 Q-111-2 22.2 +/- 3.4 19.8 23.7 22.6 22.7 Q-112-1 22.5 +/- 4.0 19.8 23.7 22.3 24.3 Q-112-2 20.8 +/- 2.0 20.2 21.2 19.8 22.0 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-15 Page 65of122

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

Q-113-1 21.3 +/-2.7 19.3 22.0 21.8 22.1 Q-113-2 20.7 +/- 4.6 18.1 21.4 19.8 23.5 Q-114-1 21.2 +/- 2.5 19.9 21.5 20.7 22.8 Q-114-2 21.8 +/- 4.5 19.0 21.2 24.3 22.7 Q-115-1 22.1 +/- 4.3 19.0 23.3 22.4 23.7 Q-115-2 21.7 +/- 2.2 20.6 21.7 22.8 (1)

Q-116-1 22.7 +/- 2.8 21.4 24.4 23.3 21.8 Q-116-3 22.6 +/- 3.9 20.3 24.9 23.2 22.0 Q-201-1 23.2 +/- 5.5 19.1 24.1 24.6 24.9 Q-201-2 23.4 +/- 2.7 21.4 24.0 23.9 24.3 Q-202-1 22.6 +/- 3.8 20.0 24.3 22.2 23.7 Q-202-2 22.6 +/- 6.7 17.8 25.4 22.8 24.2 Q-203-1 22.3 +/- 2.6 20.5 22.8 22.2 23.6 Q-203-2 25.6 +/- 3.6 22.9 27.0 26.3 26.0 Q-204-1 23.8 +/- 3.2 21.4 24.6 24.9 24.3 Q-204-2 25.0 +/- 3.2 22.9 24.6 26.2 26.2 Q-205-1 24.3 +/- 5.4 20.5 26.8 24.7 25.2 Q-205-4 23.9 +/- 3.7 22.5 23.2 26.0 (1)

Q-206-1 22.6 +/- 3.4 20.1 23.5 23.9 22.9 Q-206-2 21.5 +/- 2.7 19.7 23.0 21.3 21.8 Q-207-1 22.9 +/- 2.6 21.1 23.3 22.9 24.2 Q-207-4 23.9 +/- 2.4 22.1 24.7 24.4 24.4 Q-208-1 23.6 +/- 5.7 21.3 26.2 21.0 26.0 Q-208-2 24.5 +/- 3.5 22.4 26.0 25.8 23.7 Q-209-1 22.8 +/- 1.8 21.7 23.2 23.7 22.4 Q-209-4 23.2 +/- 3.2 21.0 23.2 23.9 24.7 Q-210-1 24.5 +/- 1.0 23.9 25.1 24.5 24.5 Q-210-4 24.4 +/- 3.4 21.9 25.1 24.8 25.8 Q-210-5 20.4 +/- 2.2 18.8 21.3 20.4 21.0 Q-211-1 26.1 +/- 2.8 24.3 26.5 25.9 27.6 Q-211-2 26.5 +/- 2.6 25.1 28.2 26.6 25.9 Q-212-1 22.2 +/- 2.2 21.0 22.9 21.5 23.3 Q-212-2 20.0 +/- 2.3 18.4 19.8 20.6 21.0 Q-213-1 21.7 +/- 1.8 20.7 21.1 22.6 22.3 Q-213-2 21.0 +/- 2.6 19.1 21.6 21.4 21.9 Q-214-1 22.1 +/- 4.8 19.0 24.9 21.9 22.4 Q-214-2 21.8 +/- 3.6 19.1 22.6 22.3 23.1 Q-215-1 21.9 +/- 2.0 20.9 21.2 22.3 23.1 Q-215-2 24.1 +/- 4.2 21.4 26.2 25.2 23.4 Q-216-1 25.1 +/- 4.1 22.1 26.4 26.1 25.9 Q-216-2 23.5 +/- 1.8 22.7 24.5 24.0 22.8 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16 Page 66of122

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

JAN-MAR 19.4 +/- 2.1 21.1 +/- 3.4 19.2 +/- 2.4 20.6 +/- 1.4 APR-JUN 22.6 +/- 2.6 24.2 +/- 3.9 22.9 +/- 3.3 26.2 +/- 0.0 JUL-SEP 22.0 +/- 2.4 23.7 +/- 3.7 22.9 +/- 4.6 24.0 +/- 1.7 OCT-DEC 22.5 +/- 1.8 24.0 +/- 3.2 23.1 +/- 3.0 24.8 +/- 2.8 TABLE C-IX.3

SUMMARY

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

INNER RING 114 17.6 25.3 21.6 +/- 3.4 OUTER RING 131 17.8 28.2 23.2 +/- 4.3 OTHER 72 17.1 29.0 22.0 +/- 4.7 CONTROL 8 20.1 26.2 23.9 +/- 4.6 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, 0~204-2, 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 Page 67 of 122

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

Collected in the Vicinity of QCNPS, 2000 - 2015 Q-33 Cordova 12.0 10.0 8.0 j) 6.0 c.

4.0 2.0 0.0 --------+-----+-----li------+--

01-01-00 12-31-02 12-30-05 12-29-08 12-29-11 12-28-14 Q-34 (C) Camanche 12.0 10.0 8.0 (3 6.0 c.

4.0 2.0 0.0 --------+-----+-----li------+--

01-01-00 12-31-02 12-30-05 12-29-08 12-29-11 12-28-14 DUE TO VENDOR CHANGE,< VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-18 Page 68 of 122

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

Collected in the Vicinity of QCNPS, 2000 - 2015 Q-33 Cordova 500 400 300

...I

~C2.

200 100 0

01-01-00 12-31-02 12-30-05 12-29-08 12-29-11 12-28-14 Q-34 (C) Camanche 500 400 300 (3

C2.

200 100 0

01-01-00 12-31-02 12-30-05 12-29-08 12-29-11 12-28-14 DUE TO VENDOR CHANGE,< VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-19 Page 69 of 122

FIGURE C-3 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2015 Q-35 McMillan Well 500 400 300 0 Q.

200 100 0

12-31-99 12-31-02 12-31-05 12-31-08 01-01-12 01-01-15 Q-36 Cordova Well 500 400 300

...J 13Q.

200 100 0

12-31-99 12-31-02 12-31-05 12-31-08 01-01-12 01-01-15 DUE TO VENDOR CHANGE,< VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-20 Page 70 of 122

FIGURE C-4 Air Particulates - Gross Beta- Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2015 Q-01 Onsite No. 1 70.0 60.0

.., 50.0

§ 40.0 0

..,c.

0 30.0 uJ 0

..... 20.0 10.0 0.0 01-07-00 01-06-03 01-05-06 01-04-09 01-04-12 01-03-15 Q-02 Onsite No. 2 70.0 60.0

.., 50.0 E

~ 40.0 c.

9 30.0 w

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

01-07-00 01-06-03 01-05-06 01-04-09 01-04-12 01-03-15 C-21 Page 71of122

FIGURE C-5 Air Particulates - Gross Beta- Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2015 Q-03 Onsite No. 3 60.0 50.0 C') 40.0

§ 0

c. 30.0 C')

0 uJ 20.0 0

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

01-07-00 01-06-03 01-05-06 01-04-09 01-04-12 01-03-15 Q-04 Nitrin 60.0 50.0 C') 40.0

.E

~ 30.0 C')

0 uJ 20.0 0

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

01-07-00 01-06-03 01-05-06 01-04-09 01-04-12 01-03-15 C-22 Page 72 of 122

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 C')

§15_ 40.0 9 30.0 w

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

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 Page 73 of 122

FIGURE C-7 Air Particulates - Gross Beta- Stations Q-13 and Q-16 Collected in the Vicinity of QCNPS, 2005 - 2015 Q-13 Princeton 60.0 50.0

'E 40.0

~

..,c. 30.0 0

w 20.0 0

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

07-08-05 06-01-07 04-24-09 03-18-11 02-08-13 01-02-15 Q-16 Low Moor 60.0 50.0 40.0 30.0 20.0 10.0 0.0 - - - - - - + - - - - - + - - - - + - - - - - + - -

07-08-05 06-01-07 04-24-09 03-18-11 02-08-13 01-02-15 AIR PARTICULATE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 C-24 Page 74of122

FIGURE C-8 Air Particulates - Gross Beta- Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2015 Q-37 Meredosia Road 60.0 50.0 M 40.0

§ 0

M Q. 30.0

...~ 20.0 10.0 0.0 --------+-----+----+------1---

07-08-05 06-01-07 04-24-09 03-18-11 02-08-13 01-02-15 Q-38 Fuller Road 60.0 5o.o*

M 40.0

.§ 0

Q. ~0.0 suJ 0 20.0 10.0 0.0 +-----i-----+------1-----'-----&.--

07-08-05 06-01-07 04-24-09 03-18-11 02-08-13 01-02-15 AIR PARTICULATE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 C-25 Page 75of122

FIGURE C-9

• Air Particulates - Gross Beta- Stations Q-41 and Q-42 (C)

Collected in the Vicinity of QCNPS, 2009 - 2015 Q-41 Camanche 60.0 50.0 M 40.0

.E

~

M 30.0 9

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

01-03-09 03-17-10 05-29-11 08-09-12 10-21-13 01-02-15 Q-42 LeClaire (Control) 60.0 50.0 M 40.0

§ CJ

a. 30.0 M

9 w 20.0 0

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

12-31-10 10-20-11 08-08-12 05-28-13 03-17-14 01-04-15 10-24-15 C-26 Page 76of122

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM Page 77of122

Intentionally left blank Page 78 of 122

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

Identification Reported Known Ratio (c)

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

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

Cs-134 pCi 139 138 1.01 A Cs-137 pCi 111 106 1.05 A Co-58 pCi 54.0 57.8 0.93 A Mn-54 pCi 96.8 84.9 1.14 A Fe-59 pCi 162 128 1.27 w Zn-65 pCi 198 210 0.94 A Co-60 pCi 178 163 1.09 A E11236 Charcoal 1-131 pCi 93.9 80 1.17 A D-1 Page 79 of 122

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analy!ics Evaluation (d)

June 2015 E11238 Water Fe-55 pCi/L 1890 1790 1.06 A September 2015 E11289 Milk Sr-89 pCi/L 95.7 99.1 0.97 A Sr-90 pCi/L 15.4 16.4 0.94 A E11290 Milk 1-131 pCi/L 94.9 99.9 0.95 A Ce-141 pCi/L 228 213 1.07 A Cr-51 pCi/L 499 538 0.93 A Cs-134 pCi/L 208 212 0.98 A Cs-137 pCi/L 270 255 1.06 A Co-58 pCi/L 275 263 1.05 A Mn-54 pCi/L 320 290 1.10 A Fe-59 pCi/L 255 226 1.13 A Zn-65 pCi/L 392 353 1.11 A Co-60 pCi/L 350 330 1.06 A E11292 AP Ce-141 pCi 104 85.1 1.22 w Cr-51 pCi 262 215 1.22 w Cs-134 pCi 86.1 84.6 1.02 A Cs-137 pCi 93 102 0.91 A Co-58 pCi 106 105 1.01 A Mn-54 pCi 117 116 1.01 A Fe-59 pCi 94.8 90.2 1.05 A Zn-65 pCi 160 141 1.13 A Co-60 pCi 146 132 1.11 A E11291 Charcoal 1-131 pCi 85.9 81.7 1.05 A E11293 Water Fe-55 pCi/L 2090 1800 1.16 A E11294 Soil Ce-141 pCi/kg 209 222 0.94 A Cr-51 pCi/kg 463 560 0.83 A Cs-134 pCi/kg 231 221 1.05 A Cs-137 pCi/kg 311 344 0.90 A Co-58 pCi/kg 245 274 0.89 A Mn-54 pCi/kg 297 302 0.98 A Fe-59 pCi/kg 248 235 1.06 A Zn-65 pCi/kg 347 368 0.94 A Co-60 pCi/kg 328 344 0.95 A December 2015 E11354 Milk Sr-89 pCi/L 96.2 86.8 1.11 A Sr-90 pCi/L 14.8 12.5 1.18 A E11355 Milk 1-131 pCi/L 95.1 91.2 1.04 A Ce-141 pCi/L 117 129 0.91 A Cr-51 pCi/L 265 281 0.94 A Cs-134 pCi/L 153 160 0.96 A Cs-137 pCi/L 119 115 1.03 A Co-58 pCi/L 107 110 0.97 A Mn-54 pCi/L 153 145 1.06 A Fe-59 pCi/L 117 108 1.08 A Zn-65 pCi/L 261 248 1.05 A Co-60 pCi/L 212 213 1.00 A D-2 Page 80 of 122

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE3 OF 3)

Identification Reported Known Ratio (c)

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

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

(b} The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or 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 o. 70-0.80 or 1.20-1.30. N =Not Acceptable~ reported result falls outside the ratio limits of< o. 70 and> 1.30.

D-3 Page 81 of 122

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

TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)

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

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

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

Gr-S Sq/sample 0.7580 0.75 0.38-1.13 A 15-RdV32 Vegetation Cs-134 Sq/sample 8.08 7.32 5.12- 9.52 A Cs-137 Sq/sample 11.6 9.18 6.43 - 11.93 w Co-57 Sq/sample -0.0096 (1) A Co-60 Sq/sample 6.53 5.55 3.89 - 7.22 A Mn-54 Sq/sample 0.0058 (1) A Sr-90 Sq/sample 0.999 1.08 0.76 - 1.40 A Zn-65 Sq/sample -0.108 (1) A September 2015 15-MaW33 Water Am-241 Sq/L 1.012 1.055 0. 739 - 1.372 A Ni-63 Sq/L 11.8 8.55 5.99-11.12 N (4)

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

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

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

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

(a) Teledyne Brown Engineering reported result.

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

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

D-4 Page 82 of 122

TABLE D-3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)

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

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

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

Ba-133 pCi/L 80.6 82.5 63.9 - 90.8 A Cs-134 pCi/L 71.7 75.7 61.8 - 83.3 A Cs-137 pCi/L 187 189 170 - 210 A Co-60 pCi/L 85.7 84.5 76.0 - 95.3 A Zn-65 pCi/L 197 203 183 - 238 A Gr-A pCi/L 26.1 42.6 22.1 - 54.0 A Gr-B pCi/L 28.8 32.9 21.3-40.6 A 1-131 pCi/L 23.5 23.8 19.7 - 28.3 A U-Nat pCi/L 6.19 6.59 4.99- 7.83 A H-3 pCi/L 3145 3280 2770-3620 A November 2015 RAD-103 Water Sr-89 pCi/L 40.9 35.7 26.7 - 42.5 A Sr-90 pCi/L 29.3 31.1 22.7 - 36.1 A Ba-133 pCi/L 31.5 32.5 25.9 - 36.7 A Cs-134 pCi/L 59.65 62.3 50.6 - 68.5 A Cs-137 pCi/L 156 157 141 - 175 A Co-60 pCi/L 70.6 71.1 64.0 - 80.7 A Zn-65 pCi/L 145 126 113 - 149 A Gr-A pCi/L 38.2 51.6 26.9 - 64.7 A Gr-8 pCi/L 42.0 36.6 24.1 - 44.2 A 1-131 pCi/L 24.8 26.3 21.9- 31.0 A U-Nat pCi/L 146.90 56.2 45.7 - 62.4 N (2)

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

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

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within tl1e Control Limits and outside of the Warning Limit.

D-5 Page 83 of 122

TABLE D-4 ERA STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAMa ENVIRONMENTAL, INC., 2015 (Page 1 of 1)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control 0

Result b Result Limits Acceptance ERW-1444 04/06/15 Sr-89 59.71 +/- 5.44 63.20 51.10 - 71.20 Pass ERW-1444 04/06/15 Sr-90 43.41 +/- 2.43 41.90 30.80 - 48.10 Pass ERW-1448 04/06/15 Ba-133 77.75 +/- 4.69 82.50 69.30 - 90.80 Pass ERW-1448 04/06/15 Cs-134 68.82 +/- 3.08 75.70 61.80 - 83.30 Pass ERW-1448 04/06/15 Cs-137 -191.92 +/- 5.9 189 -170.00 - 210.0 Pass ERW-1448 04/06/15 Co-60 85.05 +/- 4.59 84.50 76.00 - 95.30 Pass ERW-1448 04/06/15 Zn-65 -195.97+/-12.0 203 -183.00 - 238.0 Pass ERW-1450 04/06/15 Gr. Alpha 34.05 +/- 1.90 42.60 22.10 - 54.00 Pass ERW-1450 04/06/15 Gr. Beta 26.93 +/- 1.12 32.90 21.30 - 40.60 Pass ERW-1453 04/06/15 1-131 22.47 +/- 0.83 23.80 19.70 - 28.30 Pass ERW-1456 04/06/15 Uranium 5.98 +/- 0.31 6.59 4.99 - 7.83 Pass ERW-1461 04/06/15 H-3 3,254 +/- 180 3280 2,770 - 3620 Pass ERW-5528 10/05/15 Sr-89 34.76 +/- 0.06 35.70 26. 70 - 42.50 Pass ERW-5528 10/05/15 Sr-90 29.23 +/- 0.06 31.10 22.70 - 36.10 Pass ERW-5531 10/05/15 Ba-133 30.91 +/- 0.53 32.50 25.90 - 36.70 Pass ERW-5531 10/05/15 Cs-134 57.40 +/- 2.57 62.30 50.69 - 68.50 Pass ERW-5531 10/05/15 Cs-137 -163.12 +/- 4.8 157 -141.00 - 175.0 Pass ERW-5531 10/05/15 Co-60 73.41 +/- 1.72 71.10 64.00 - 80.70 Pass ERW-5531 10/05/15 Zn-65 -138.94 +/- 5.7 126 -113.00 - 149.0 Pass ERW-5534 10/05/15 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 - 64.70 Pass ERW-5534 10/05/15 G. Beta 27.52 +/- 0.04 36.60 24.10 - 44.20 Pass ERW-5537 10/05/15 1-131 25.54 +/- 0.60 26.30 21.90 - 31.00 Pass ERW-5540 10/05/15 Uranium 53.30 +/- 0.55 56.20 45.70 - 62.40 Pass ERW-5543 10/05/15 H-3 21,260 +/- 351 21,300 18,700 - 23400.0 Pass

• 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 Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

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

D-6 Page 84of122

TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

ENVIRONMENTAL, INC., 2015 (Page 1 of 2)

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 2/1/2015 Ni-63 341 +/- 18 448 314 - 582 Pass MAS0-975 2/1/2015 Sr-90 523 +/- 12 653 457 - 849 Pass MAS0-975 2/1/2015 Cs-134 533 +/- 6 678 475 - 881 Pass MAS0-975 2/1/2015 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 2/1/2015 Co-57 0.5 +/- 1 0.0 NA c Pass MAS0-975 2/1/2015 Co-60 741 +/- 8 817 572 - 1062 Pass MAS0-975 2/1/2015 Mn-54 1,153 +/- 9 1, 198 839 - 1557 Pass MAS0-975 2/1/2015 Zn-65 892 +/- 18 1064 745 - 1383 Pass MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 0.654 0.458 - 0.850 Pass MAW-969 2/1/2015 Cs-134 21.09 +/- 0.25 23.5 16.5 - 30.6 Pass MAW-969 2/1/2015 Cs-137 19.63 +/- 0.34 19.1 13.4 - 24.8 Pass MAW-969 d 2/1/2015 Co-57 10.2 +/- 0.4 29.9 20.9 - 38.9 Fail MAW-969 2/1/2015 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 2/1/2015 H-3 569 +/- 13 563 394 - 732 Pass MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 6.88 4.82 - 8.94 Pass MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 0.00 NA c Pass MAW-969 2/1/2015 Ni-63 2.9 +/- 3 0.00 NA c Pass MAW-969 2/1/2015 Zn-65 16.54 +/- 0.85 18.3 12.8 - 23.8 Pass 0

MAW-969 2/1/2015 Pu-238 0.02 +/- 0.03 0.01 NA Pass MAW-969 2/1/2015 Pu-239/240 0.81 +/- 0.10 0.83 0.58 - 1.08 Pass MAW-969 2/1/2015 Sr-90 9.40 +/- 1.30 9.48 6.64 - 12.32 Pass MAW-950 2/1/2015 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 - 1.81 Pass MAW-950 2/1/2015 Gr. Beta 2.72 +/- 0.06 2.79 1.40 - 4.19 Pass MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 1.15 0.81 - 1.50 Pass MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 0.00 NAC Pass MAAP-978 e 2/1/2015 Co-57 0.04 +/- 0.04 1.51 1.06 - 1.96 Fail MAAP-978 2/1/2015 Co-60 0.01 +/- 0.02 0.00 NA c Pass MAAP-978 2/1/2015 Mn-54 1.11 +/- 0.08 1.02 0.71 - 1.33 Pass MAAP-978 2/1/2015 Zn-65 0.83 +/- 0.10 0.83 0.58 - 1.08 Pass MAAP-981 2/1/2015 Sr-89 38.12 +/- 1.01 47.5 33.3 - 61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/- 0.13 1.06 0.74 - 1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 - 3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 - 1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.13 7.32 5.12 - 9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 - 11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 - 7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NA c Pass D-7 Page 85 of 122

TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

ENVIRONMENTAL, INC., 2015 (Page 2 of 2)

Concentration a Known Control 0

Lab Code Date Analysis Laboratory result Activity Limits c Acceptance MAS0-4903 8/1/2015 Ni-63 556 +/- 18 682 477 - 887 Pass MAS0-4903 f 8/1/2015 Sr-90 231 +/-7 425 298 - 553 Fail MAS0-4903 f 8/1/2015 Sr-90 352 +/- 10 425 298 - 553 Pass MAS0-4903 8/1/2015 Cs-134 833 +/- 10 1,010 707 - 1313 Pass MAS0-4903 8/1/2015 Cs-137 808 +/- 11 809.00 566 - 1052 Pass MAS0-4903 8/1/2015 Co-57 1,052 +/- 10 1, 180 826 - 1534 Pass MAS0-4903 8/1/2015 Co-60 2 +/-2 1.3 NAe Pass MAS0-4903 8/1/2015 Mn-54 1,331 +/- 13 1,340 938 - 1742 Pass MAS0-4903 8/1/2015 Zn-65 686 +/- 15 662 463 - 861 Pass MAW-5007 8/1/2015 Cs-134 16.7 +/- 0.4 23.1 16.2 - 30 Pass MAW-5007 8/1/2015 Cs-137 -0.36 +/- 0.13 0 NA c Pass MAW-5007 8/1/2015 Co-57 21.8 +/- 0.4 20.8 14.6 - 27 Pass MAW-5007 8/1/2015 Co-60 17.3 +/- 0.3 17.1 12 - 22.2 Pass MAW-5007 8/1/2015 H-3 227.5 +/- 8.9 216 151 - 281 Pass MAW-5007 g 8/1/2015 Fe-55 4.2 +/- 14.1 13.1 9.2 - 17 Fail MAW-5007 8/1/2015 Mn-54 16.6 +/- 0.5 15.6 10.9 - 20.3 Pass MAW-5007 8/1/2015 Ni-63 9.1 +/- 2.6 8.55 5.99 - 11.12 Pass MAW-5007 8/1/2015 Zn-65 15.5 +/- 0.9 13.9 9.7 - 18.1 Pass MAW-5007 8/1/2015 Sr-90 4.80 +/- 0.50 4.80 3.36 - 6.24 Pass MAW-5007 8/1/2015 Gr. Alpha 0.41 +/- 0.04 0.43 0.13 - 0.73 Pass MAW-5007 8/1/2015 Gr. Beta 3.45 +/- 0.07 3.52 1.76 - 5.28 Pass MAAP-4911 8/1/2015 Sr-89 3.55 +/- 0.67 3.98 2.79 - 5.17 Pass MAAP-4911 8/1/2015 Sr-90 0.94 +/- 0.16 1.05 0.74 - 1.37 Pass MAAP-4907 8/1/2015 Gr. Alpha 0.30 +/- 0.04 0.90 0.27 - 1.53 Pass MAAP-4907 8/1/2015 Gr. Beta 1.85 +/- 0.09 1.56 0.78 - 2.34 Pass MAVE-4901 8/1/2015 Cs-134 5.56 +/- 0.16 5.80 4.06 - 7.54 Pass MAVE-4901 8/1/2015 Cs-137 -0.02 +/- 0.06 0.00 NA c Pass MAVE-4901 8/1/2015 Co-57 7.74 +/- 0.18 6.62 4.63 - 8.61 Pass MAVE-4901 8/1/2015 Co-60 4.84 +/- 0.15 4.56 3.19 - 5.93 Pass MAVE-4901 8/1/2015 Mn-54 8.25 +/- 0.25 7.68 5.38 - 9.98 Pass MAVE-4901 8/1/2015 Zn-65 5.78 +/- 0.29 5.46 3.82 - 7.10 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 Lab result was 27.84. Data entry error resulted in a non-acceptable result.

• Lab result was 1.58. Data entry error resulted in a non-acceptable result.

f The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.

g The known activity was below the routine laboratory detection limits for the available aliquot fraction.

D-8 Page 86of122

APPENDIX E ERRATA DATA Page 87 of 122

/

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There is no errata data for 2015.

Page 89 of 122

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APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Page 91of122

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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 2015 Prepared By Teledyne Brown Engineering Environmental Services Quad Cities Nuclear Power Station Cordova, iL 61242 May 2016 Page 93of122

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Table Of Contents I. Summary and Conclusion ................................................................................................ 3 II. Introduction ..................................................................................................................... 5 A. Objectives of the RGPP ...................................................................................... 5

8. Implementation of the Objectives ........................................................................ 6 C. Program Description ........................................................................................... 6 Ill. Program Description ...................................................................................................... 7 A. Sample Analysis .................................................................................................. 7

8. Data Interpretation ............................................................................................... 7 IV. Results and Discussion ................................................................................................. 8 A. Groundwater Results ........................................................................................... 8

8. 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 Page 95 of 122

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2015 Figures Figure A-1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2015 Figure A-2 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2015 Appendix B Data Tables Tables Table B-1.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2015.

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

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

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

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

Table B-111.1 Concentrations of Tritium in Groundwater Samples Collected and Anaylzed by Quad Cities Station Personnel, 2015.

ii Page 96of122

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 2015 through 31 December 2015.

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

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

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

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

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

In 2012 Conestoga-Rovers & Associates (CRA) completed a five-year update hydrogeologic investigation report for the Station (NE/ 07-07, Hydrogeologic Investigation Report, dated November 2012). The referenced report summarized station activities since the 2006 hydrogeologic investigation report, including Page 97 of 122

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 2015. During that time period, RGPP samples were collected from 43 locations.

2015 sample locations included thirty-six designated monitoring wells, two surface water monitoring points and five 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 Fe 55/Ni

63. Samples from eighteen of the designated monitoring wells and two 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 36,900 pCi/L in a monitoring well. Tritium was detected in one of the eight surface water samples at a concentration of 295 pCi/L.

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 was not detected at concentrations greater than the Lower Limit of Detection (LLD) of 10.0 pCi/L. Strontium-90 was not detected at concentrations great 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 10 designated groundwater locations during the first quarter sampling in 2015.

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

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

Page 98 of 122

Gross Beta (dissolved) was detected in nine of 10 groundwater locations. The concentrations ranged from 2.8 to 43.1 pCi/L.

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

Select Transuranics/Hard-To-Detect analyses was performed on one 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. Objective 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.

Page 99 of 122

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 Page 100 of 122

analytical data deliverables after initial review by the contractor.

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

Ill. Program Description This section covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2015.

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 2015.

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

1. Concentrations of gamma emitters in groundwater and surface water.

2. Concentrations of strontium in groundwater.

3. Concentrations of tritium in groundwater 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 Page 101of122

Cities Nuclear Power Station was considered operational at initial criticality. Several factors were important in the interpretation of the data:

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

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

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

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

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

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

IV. Results and Discussion A Groundwater Results Groundwater Samples were collected from on-site wells in accordance with the Page 102of122

station radiological groundwater protection program. Analytical results and anomalies are discussed below.

Tritium Samples from all locations were analyzed for tritium activity (Table B-1.1 & B-111.1 Appendix B). Tritium values ranged from the detection limit to 36,900 pCi/I. All samples obtained at the site boundaries were less then the detection limit of 200 pCi/L, with the exception of MW-QC-1121 sampled on 3/9/15 which showed activity of 403 pCi/L. Subsequent resample of MW-QC-1121 on 4/10/15 was less than detection limit of 200 pCi/L. The location most representative of potential offsite user of drinking water was

<200 pCi/L.

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

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions performed on designated groundwater locations during the 1st quarter in 2015.

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 nine of 10 groundwater locations. The concentrations ranged from 2.8 to 43.1 pCi/L.

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

Gamma Emitters No gamma emitting nuclides were detected other than naturally occurring K-40 in two samples at concentration of 27 pCi/L and 158 pCi/L (Table B-1.2, Appendix B).

Page 103 of 122

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-1.3 Appendix B).

B. Surface Water Results Surface Water Tritium Samples from two locations were analyzed for tritium activity.

Tritium was detected in one of the eight samples at a concentration of 295 pCi/L. (Table B-11.1 Appendix B).

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

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

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

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

F. Investigations Currently no investigations are on-going.

G. Actions Taken

1. Compensatory Actions There have been no station events requiring compensatory actions at the Quad Cities Nuclear Power Station in 2015.

Page 104 of 122

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.

Page 105 of 122

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APPENDIX A LOCATION DESIGNATION Page 107 of 122

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TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations , Quad Cities Nuclear Power Station, 2015 Site Site Type Well Designation Minimum Sample Frequency MW-QC-1 Monitoring Well Plume Quarterly MW-QC-2 Monitoring Well Plume Quarterly MW-QC-3 Monitoring Well Plume Quarterly MW-QC-1011 Monitoring Well Idle Not Required MW-QC-101S Monitoring Well Idle Not Required MW-QC-102D Monitoring Well Plume Quarterly MW-QC-1021 Monitoring Well Plume Quarterly MW-QC-102S Monitoring Well Plume Quarterly MW-QC-1031 Monitoring Well Detection Quarterly MW-QC-104S Monitoring Well Detection Quarterly MW-QC-1051 Monitoring Well Plume Quarterly MW-QC-1061 Monitoring Well Plume Quarterly MW-QC-106S Monitoring Well Plume Quarterly MW-QC-1071 Monitoring Well Background Annual MW-QC-108D Monitoring Well Plume Quarterly MW-QC-1081 Monitoring Well Plume Quarterly MW-QC-108S Monitoring Well Plume Quarterly MW-QC-1091 Monitoring Well Plume Quarterly MW-QC-109S Monitoring Well Plume Quarterly MW-QC-1101 Monitoring Well Idle Not Required MW-QC-111 D1 Monitoring Well Idle Not Required MW-QC-111 D2 Monitoring Well Idle Not Required MW-QC-1111 Monitoring Well Idle Not Required MW-QC-1121 Monitoring Well Plume Quarterly MW-QC-1131 Monitoring Well Idle Not Required MW-QC-114 1 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 LITILE 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 WE LL #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 Page 109 of 122

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APPENDIX B DATA TABLES Page 113of122

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TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

MW-QC-1 03/10/15 < 183 MW-QC-1 05/19/15 < 185 MW-QC-1 08/25/15 < 189 MW-QC-1 11/10/15 220 +/- 124 MW-QC-102D 03/10/15 982 +/- 167 MW-QC-102D 05/19/15 678 +/- 151 MW-QC-102D 08/25/15 886 +/- 160 MW-QC-102D 11/10/15 721 +/- 153 MW-QC-1021 03/10/15 379 +/- 137 MW-QC-1021 05/19/15 333 +/- 134 MW-QC-1021 08/25/15 < 191 MW-QC-1021 11/10/15 < 195 MW-QC-102S 03/10/15 < 187 MW-QC-102S 05/19/15 < 189 MW-QC-102S 08/25/15 < 191 MW-QC-102S 11/10/15 < 196 MW-QC-1031 03/10/15 < 187 < 3.7 < 0.9 < 1.6 < 0.5 8.3 +/- 1.3 < 1.6 MW-QC-1031 05/19/15 < 189 MW-QC-1031 08/25/15 < 191 MW-QC-1031 11/10/15 < 194 MW-QC-104S 03/10/15 < 183 < 3.7 < 0.9 < 2.1 < 0.5 < 2.5 < 1.6 MW-QC-104S 05/19/15 < 188 MW-QC-104S 08/25/15 < 190 MW-QC-104S 11/10/15 < 195 MW-QC-1051 03/10/15 507 +/- 142 MW-QC-1051 05/19/15 < 190 MW-QC-1051 08/25/15 < 188 MW-QC-1051 11/10/15 < 191 MW-QC-1061 03/10/15 < 180 MW-QC-1061 05/19/15 < 192 MW-QC-1061 08/25/15 < 190 MW-QC-1061 11/10/15 < 195 MW-QC-106S 03/10/15 < 191 MW-QC-106S 05/19/15 < 191 MW-QC-106S 08/25/15 < 190 MW-QC-106S 11/10/15 < 196 MW-QC-1071 03/09/15 < 185 MW-QC-108D 03/10/15 1500 +/- 207 MW-QC-108D 05/20/15 1280 +/- 192 MW-QC-108D 08/26/15 1240 +/- 187 MW-QC-108D 11/11/15 1360 +/- 205 MW-QC-1081 03/10/15 564 +/- 141 MW-QC-1081 05/20/15 Original 3110 +/- 367 MW-QC-1081 08/26/15 2430 +/- 301 MW-QC-1081 11/11/15 1620 +/- 228 MW-QC-108S 03/10/15 < 185 MW-QC-108S 05/20/15 Original 475 +/- 138 MW-QC-108S 08/26/15 < 189 MW-QC-108S 11/11/15 < 193 MW-QC-1091 03/10/15 < 185 MW-QC-1091 05/19/15 < 186 MW-QC-1091 08/25/15 < 191 MW-QC-1091 11/10/15 < 195 MW-QC-109S 03/10/15 < 186 B-1 Page 115of122

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A(8us) Gr-8 (Dis) Gr-8 (Sus)

MW-QC-109S 05/19/15 < 195 MW-QC-1098 08/25/15 < 188 MW-QC-1098 11/10/15 < 194 MW-QC-1121 03/09/15 Original 403 +/- 137 MW-QC-1121 05/18/15 < 191 MW-QC-1121 08/24/15 < 192 MW-QC-1121 11/09/15 < 194 MW-QC-2 03/10/15 < 184 MW-QC-2 05119/15 < 192 MW-QC-2 08/25115 < 189 MW-QC-2 11110115 < 193 MW-QC-3 03/15115 19900 +/- 2030 < 6.0 < 0.6 < 1.3 < 0.3 8.7 +/- 1.3 < 1.6 MW-QC-3 11/10/15 6890 +/- 741 QC-GP-10 03/09115 < 193 < 3.9 < 0.8 < 5.4 < 0.6 15.4 +/- 1.8 < 1.5 QC-GP-11 03/09/15 1360 +/- 197 < 4.0 < 0.9 < 5.7 < 0.6 8.4 +/- 1.6 < 1.5 QC-GP-12 03/10115 < 190 < 8.3 < 0.9 < 1.1 < 0.6 2.8 +/- 0.7 < 1.5 QC-GP-14 03/09115 4060 +/- 456 < 5.3 < 1.0 < 1.4 < 0.3 6.0 +/- 1.3 < 1.6 QC-GP-15 03/09/15 < 192 < 3.1 < 0.8 < 5.6 < 0.6 16.3 +/- 2.1 < 1.5 QC-GP-15 07128/15 < 188 QC-GP-16 03/09/15 17300 +/- 1770 < 3.9 < 0.7 < 1.1 < 0.3 4.2 +/- 1.0 < 1.6 QC-GP-18 03/09/15 31200 +/- 3150 < 4.0 < 0.8 < 3.5 < 0.3 43.1 +/- 2.7 < 1.6 WELL #9 DRY CASK STORAGE 03/11/15 < 193 B-2 Page 116of122

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DATE MW-QC-1031 03/10/15 < 49 < 48 <6 <6 < 11 < 6 < 9 < 6 < 10 < 14 <6 <6 < 33 <4 MW-QC-104S 03/10/15 < 43 < 53 <4 <4 < 8 <5 < 11 < 5 <8 < 10 <4 <4 < 22 < 9 MW-QC-1071 03/09/15 < 51 < 108 < 5 <6 < 11 <5 < 11 < 7 < 10 < 14 <6 < 5 < 34 < 9 QC-GP-10 03/09/15 < 15 < 34 < 1 < 1 <4 < 1 < 3 < 2 < 3 < 13 < 1 < 1 < 18 <6 QC-GP-11 03/09/15 < 17 < 32 < 1 <2 < 5 <2 < 3 <2 < 3 < 14 < 1 <2 < 21 <6 QC-GP-12 03/10/15 < 14 < 26 < 1 <2 < 3 < 1 < 3 <2 < 3 < 11 < 1 < 1 < 17 < 5 QC-GP-14 03/09/15 < 16 158 +/- 30 < 1 <2 < 3 <2 < 3 <2 < 3 < 14 < 1 < 1 < 21 < 6 QC-GP-15 03/09/15 < 16 < 13 < 1 < 2 <4 < 1 < 3 <2 <3 < 12 < 1 <2 < 20 < 6 QC-GP-15 07/28/15 < 44 < 83 <4 <4 < 8 < 5 < 10 < 5 <9 < 14 <4 <5 < 34 < 10 QC-GP-16 03/09/15 < 11 < 27 < 1 < 1 < 3 < 1 <2 < 1 <2 < 11 < 1 < 1 < 16 < 5 QC-GP-18 03/09/15 < 9 27 +/- 17 < 1 < 1 <2 < 1 < 2 < 1 <2 < 9 < 1 < 1 < 12 <4 QC-MW-3 03/15/15 < 18 < 28 <2 <2 <4 <2 <4 < 2 <4 < 12 < 2 <2 < 20 < 6 WELL #9 DRY CASK STORAGE 03/11/15 < 17 < 35 <2 <2 <4 <2 < 4 < 2 <3 < 12 < 2 <2 < 19 < 6 t:Ci I

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TABLE B-1.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 Fe-55 Ni-63 DATE QC-GP-15 03/09/15 < 0.08 < 0.09 < 0.02 < 0.07 < 0.18 < 0.02 < 0.07 < 0.04 < 160 < 4.7

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TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 QC-SW-1 3/31/2015 295 +/- 134 QC-SW-1 08/25/15 < 188 QC-SW-1 11109/15 < 193 QC-SW-2 3/31/2015 < 188 QC-SW-2 08/25/15 < 189 QC-SW-2 11/09/15 < 193 B-5 Page 119 of122

TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 DATE QC-SW-1 03/31/15 < 72 < 170 < 8 < 7 < 15 < 7 < 17 < 9 < 14 < 12 < 7 < 7 < 32 < 12 QC-SW-2 03/31/15 < 49 < 60 <6 < 6 < 9 <6 < 10 < 7 < 12 < 13 < 6 <7 < 33 < 12 N

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TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2015 RESULTS IN UNITS OF PCl/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-1 03/09/15 9,776 Sentinel Well QC-GP-1 05/18/15 5,170 Sentinel Well QC-GP-1 08/24/15 9,240 Sentinel Well QC-GP-1 11/10/15 5,180 Sentinel Well QC-GP-2 03/11/15 <2,000 Sentinel Well QC-GP-2 05/20/15 <2,000 Sentinel Well QC-GP-2 08/26/15 <2,000 Sentinel Well QC-GP-2 11/10/15 <2,000 Sentinel Well QC-GP-3 03/09/15 <2,000 Sentinel Well QC-GP-4 03/09/15 23,900 Sentinel Well QC-GP-4 05/18/15 22,000 Sentinel Well QC-GP-4 08/25/15 11,700 Sentinel Well QC-GP-4 11/12/15 10,800 Sentinel Well QC-GP-5 03/09/15 <2,000 Sentinel Well QC-GP-5 05/20/15 <2,000 Sentinel Well QC-GP-5 08/26/15 <2,000 Sentinel Well QC-GP-5 11/09/15 <2,000 Sentinel Well QC-GP-6 03/09/15 <2,000 Sentinel Well QC-GP-6 05/18/15 <2,000 Sentinel Well QC-GP-6 07/28/15 <2,000 Sentinel Well QC-GP-6 11/09/15 <2,000 Sentinel Well QC-GP-7 03/09/15 <2,000 Sentinel Well QC-GP-7 05/20/15 <2,000 Sentinel Well QC-GP-7 07/28/15 <2,000 Sentinel Well QC-GP-7 11/09/15 <2,000 Sentinel Well QC-GP-8 03/09/15 <2,000 Sentinel Well QC-GP-9 03/09/15 23,400 Sentinel Well QC-GP-9 05/18/15 10,500 Sentinel Well QC-GP-9 08/24/15 21,400 Sentinel Well QC-GP-9 11/11/15 27,300 Sentinel Well QC-GP-10 03/09/15 <2,000 Sentinel Well QC-GP-10 05/20/15 <2,000 Sentinel Well QC-GP-10 08/26/15 <2,000 Sentinel Well QC-GP-10 11/09/15 <2,000 Sentinel Well QC-GP-11 03/09/15 <2,000 Sentinel Well QC-GP-11 05/19/15 2,580 Sentinel Well QC-GP-11 08/26/15 <2,000 Sentinel Well QC-GP-11 11/09/15 <2,000 Sentinel Well QC-GP-12 03/09/15 <2,000 Sentinel Well QC-GP-12 05/19/15 <2,000 Sentinel Well QC-GP-12 08/24/15 <2,000 Sentinel Well QC-GP-12 11/11/15 <2,000 Sentinel Well QC-GP-13 03/10/15 18,300 Sentinel Well QC-GP-13 05/19/15 7,030 Sentinel Well QC-GP-13 08/25/15 13,000 Sentinel Well QC-GP-13 11/11/15 12,600 Sentinel Well QC-GP-14 03/09/15 4,400 Sentinel Well QC-GP-14 05/19/15 7,030 Sentinel Well QC-GP-14 08/26/15 5,590 Sentinel Well QC-GP-14 11/09/15 4,200 Sentinel Well QC-GP-15 03/09/15 <2,000 Sentinel Well QC-GP-15 05/20/15 <2,000 Sentinel Well QC-GP-15 07/28/15 <2,000 Sentinel Well QC-GP-15 11/09/15 <2,000 Sentinel Well B-7 Page 121 of122

TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2015 RESULTS IN UNITS OF PCl/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-16 03/09/15 21,400 Sentinel Well QC-GP-16 05/18/15 <2,000 Sentinel Well QC-GP-16 08/24/15 <2,000 Sentinel Well QC-GP-16 11/11/15 2,610 Sentinel Well QC-GP-17 03/09/15 6,000 Sentinel Well QC-GP-17 05/18/15 2,420 Sentinel Well QC-GP-17 08/24/15 3,290 Sentinel Well QC-GP-17 11/11/15 <2,000 Sentinel Well QC-GP-18 03/09/15 36,900 Sentinel Well QC-GP-18 05/18/15 6,810 Sentinel Well QC-GP-18 08/24/15 2,030 Sentinel Well QC-GP-18 11/10/15 6,630 Sentinel Well MW-QC-3 05/18/15 10,500 Monitoring Well MW-QC-3 08/24/15 14,700 Monitoring Well MW-QC-1121 04/10/15 <200 Monitoring Well Well#1 03/12/15 <200 Production Well Well#1 09/15/15 <200 Production Well Well#5 03/12/15 <200 Production Well Well#5 09/15/15 <200 Production Well Well#? 03/12/15 <2000 Production Well

• Well#? 05/18/15 <2000 Production Well Well#? 09/15/15 <200 Production Well Well#? 11/11/15 <2,000 Production Well Well #10 03/12/15 <200 Production Well QC-SW-1 05/22/15 <200 Surface Water QC-SW-2 05/22/15 <200 Surface Water B-8 Page 122of122