Text

Annual Radiological Environmental Operating Report, 1 January Through 31 December 2013
	ML14136A147
Person / Time
Site:	Quad Cities
Issue date:	05/31/2014
From:	; Teledyne Brown Engineering Environmental Services
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML14136A147 (124)
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Docket No: 50-254 50-265 QUAD CITIES NUCLEAR POWER STATION UNITS I and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2013 Prepared By Teledyne Brown Engineering Environmental Services

-- Exelon Generatinm Quad Cities Nuclear Power Station Cordova, IL 61242 May 2014 Page I of 124

Intentionally left blank Page 2 of 124

Table Of Contents I. Sum m ary and Conclusions .............................................................................................. 1 II. Introduction ............................................................................................................. 3 A. Objectives of the REM P .................................................................................. 3 B. Im plementation of the Objectives .................................................................... 3 C. Radiation and Radioactivity ............................................................................ 3 D. Sources of Radiation ....................................................................................... 4 III. Program Description .................................................................................................. 5 A. Sam ple Collection ........................................................................................... 5 B. Sam ple Analysis .............................................................................................. 8 C. Data Interpretation ......................................................................................... 8 D. Program Exceptions ....................................................................................... 9 E. Program Changes ......................................................................................... 11 IV. Results and Discussion ......................................................................................... 12 A. Aquatic Environm ent .................................................................................... 12

1. Surface W ater ..................................................................................... 12

2. Ground W ater ..................................................................................... 12

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

4. Sedim ent ............................................................................................ 13 B. Atmospheric Environm ent ............................................................................. 14

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

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

b. Airborne Iodine ...................................................................... 15

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

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

b. Food Products ......................................................................... 15 C. Am bient Gam m a Radiation ........................................................................... 16 D. Independent Spent Fuel Storage .................................................................. 16 E. Land Use Survey ......................................................................................... 16 F. Errata Data .................................................................................................. 17 G. Summary of Results - Inter-laboratory Comparison Program .................... 18 Page 3 of 124

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for Quad Cities Nuclear Power Station, 2013 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, 2013 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2013 Figures Figure B-1 Quad Cities REMP Sampling Locations - 2 Mile Radius, 2013 Figure B-2 Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2013 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, 2013.

Table C-1.2 Concentrations of Tritium, Iron-55 and Nickel-63 in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table C-I1.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table C-I1.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

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Table C-1J1.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

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, 2013.

Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table C-VI.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table C-VII.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table C-VIII.1 Concentrations of Gamma Emitters in Food Product Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table C-IX.1 Quarterly OSLD Results for Quad Cities Nuclear Power Station, 2013.

Table C-IX.2 Mean Quarterly OSLD Results for the Inner Ring, Outer Ring, Other and Control Location for Quad Cities Nuclear Power Station, 2013.

Table C-IX.3 Summary of the Ambient Dosimetry Program for Quad Cities Nuclear Power Station, 2013.

Figures Figure C-1 Surface Water - Gross Beta - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2013.

Figure C-2 Surface Water - Tritium - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2013.

Figure C-3 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2013.

Figure C-4 Air Particulates - Gross Beta - Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2013.

Figure C-5 Air Particulates - Gross Beta - Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2013.

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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 - 2013.

Figure C-8 Air Particulates - Gross Beta - Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2013.

Figure C-9 Air Particulates - Gross Beta - Stations Q-41 and Q-42 (C) Collected in the Vicinity of QCNPS, 2009 - 2013.

Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2013 Table D-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2013 Table D-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2013 Table D-4 ERA (a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2013 Table D-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2013 Appendix E Errata Data Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv Page 6 of 124

I. Summary and Conclusions In 2013, the Quad Cities Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 73 curies of noble gas, 1.5E-03 curies of fission and activation products, 29 curies of Carbon-14 and approximately 79 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:

Gaseous and liquid radiation doses to members of the public at locations Location % of Applicable Estimated Age Site Unit Distance Direction Applicable Unit Effluents Organ Dose Group metance (meters) (ton (toward) Limit Limit Noble Gas Gamma - Air Dose 1.55E-03 All 1029 NNE 7.75E-03 20 mRad Noble Gas Beta -Air Dose 2.30e-04 All 1029 NNE 5.75E-04 40 mRad Iodine, Particulate Total Body 4,18E-02 Child 1029 NNE 4.18E-01 10 mrem C-14 & Tritium Iodine, Particulate Bone 2.01E-01 Child 1029 NNE 6.70E-01 30 mrem C-14 & Tritium Liquid Total Body 7.81 E-04 Adult Mississippi River 1.30E-02 6 mrem Liquid Liver 1.81 E-03 Child Mississippi River 9.05E-03 20 mrem Skyshine Total Body 7.76E+00 All 800 N 3.10E+01 25 mrem 40CFR190 Total Body (Gas + Liq+ 7.82E+00 All 800 N 3.13E+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 31.3%

of the 25 mrem/yr limit. The largest component of 40CFR190 dose is attributable to BWR skyshine from N-1 6. This value is conservatively calculated for the hypothetical maximum exposed member of the public.

This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Quad Cities Nuclear Power Station (QCNPS) by Exelon covers the period 01 January 2013 through 31 December 2013. During that time period, 1570 analyses were performed on 1457 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of QCNPS had no adverse radiological impact on the environment.

Surface water samples were analyzed for concentrations of gross beta, tritium, iron, nickel and gamma emitting nuclides. Ground water samples were analyzed for concentrations of tritium and gamma emitting nuclides. No fission or activation products were detected. Gross beta activities detected were Page 7 of 124

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-1 37 was detected in two sediment samples at location Q-40 (control). Occasionally Cs-1 37 is detected at very low levels (just above LLD) in sediment and is not distinguishable from background levels.

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 I-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 (OSLD). Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimeters were deployed and Thermoluminescent Dosimeters (TLD) were discontinued.

This change may result in a step change in readings, up or down, depending on site characteristics. The relative comparison to control locations remains valid.

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

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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 2013 through 31 December 2013.

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 Page 9 of 124

radioactive fallout that is normally present in environmental samples are cesium-1 37 and strontium-90. Some examples of radioactive materials released from a nuclear power plant are cesium-1 37, iodine-1 31, 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 Il.D-1 below).

Radioactivity is measured in curies. A curie is that amount of radioactive material needed to produce 37,000,000,000 nuclear disintegrations per second. This is an extremely large amount of radioactivity in comparison to environmental radioactivity. That is why radioactivity in the environment is measured in picocuries. One picocurie is equal to one trillionth of a curie.

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

Table II.D-1 Radiation Sources and Corresoondina Doses (1)

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

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

(4) Primarily from cigarette smoking (4.6 mrem), commercial air travel (3.4 mrem),

building materials (3.5 mrem), and mining and agriculture (0.8 mrem)

(5) Industrial, security, medical, educational, and research Page 10 of 124

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

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

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

Ill. Program Description A. Sample Collection Samples for the QCNPS REMP were collected for Exelon Nuclear by Environmental Inc. (Midwest Labs). This section describes the general sampling methods used by Environmental Inc. to obtain environmental samples for the QCNPS REMP in 2013. Sample locations and descriptions can be found in Table B-1 and Figures B-1 and B-2, Appendix B.

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

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

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

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

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

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

Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Page 12 of 124

Stimulated Luminescent Dosimeters (OSLD) were deployed and Thermoluminescent Dosimeters (TLD) were discontinued. This change may result in a step change in readings, up or down, depending on site characteristics. The relative comparison to control locations remains valid. OSLD technology is different than that used in a TLD but has the same purpose (to measure direct radiation).

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

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

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

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

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

The specific OSLD locations were determined by the following criteria:

1. The presence of relatively dense population;

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

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

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

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

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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 2013 and the type of analyses. The analytical procedures used by the TBE laboratory are listed in Table B-2.

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

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

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

3. Concentrations of tritium in ground and surface water.

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

5. Ambient gamma radiation levels at various site environs.

6. Concentrations of 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 Page 14 of 124

the fact) estimate of the presence of activity.

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

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

For surface water, groundwater and vegetation 12 nuclides, 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 2013 the QCNPS REMP had a sample recovery rate in excess of 97%. Sample anomalies and missed samples are listed in the tables below:

Table D-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection Reason Type Code Date SW Q-34 01/11/13 Required MDC was missed due to calculation error associated with TBE detector 08.

SW Q-34 02/15/13 Required MDC was missed due to calculation error associated with TBE detector 08.

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Table D-1 LISTING OF SAMPLE ANOMALIES (continued)

Sample Location Sample Location Collection Reason Type Code Date M Q-26 03/01/13 All required MDCs were achieved following recalculation of data from TBE detector 08.

A/I Q-37 06/28/13 Low reading of 149.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months possibly due to power outage from storms.

A/I Q-38 06/28/13 Low reading of 161.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months possibly due to power outage from storms.

A/I Q-02 06/28/13 Low reading of 161.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months possibly due to power outage from storms.

Table D-22 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date OSLD Q-112-1 03/01/13 OSLD missing in field; collector placed spare # 2X9 291558 8840 00010.

OSLD Q-202-2 03/01/13 OSLD missing in field; collector placed spare # 1X9 291558 8839 00009.

SW Q-33 01/04/13 No sample; water frozen SW Q-34 01/04/13 No sample; water frozen SW Q-33 01/18/13 - No sample; water frozen 02/01/13 SW Q-34 01/18/13 - No sample; water frozen 02/01/13 SW Q-33 02/21/13 - No sample; water frozen 03/22/13 SW Q-34 02/21/13 - No sample; water frozen 03/22/13

-10 Page 16 of 124

Table D-2 LISTING OF MISSED SAMPLES (continued)

Sample Location Collection Reason Type Code Date OSLD Q-210-4 06/28/13 OSLD found missing during quarterly exchange; collector placed new 3 rd quarter OSLD.

OSLD Q-212-1 06/28/13 OSLD found missing during quarterly exchange; pole replaced; collector placed new 3rd quarter OSLD.

OSLD Q-108-1 06/28/13 OSLD found missing during quarterly exchange; collector placed new 3 rd quarter OSLD.

OSLD Q-204-1 06/28/13 OSLD found missing during quarterly exchange; collector placed new 3 rd quarter OSLD.

AP Q-41 11/08/13 Anomalous result due to bad flow meter.

Sample result not valid due to unknown flow measurement.

AP Q-41 11/15/13 Flow meter in backup pump was found bad. Pump replaced. Sample not valid.

Sample result not valid due to unknown flow measurement.

SW Q-33 11/28/13 - No sample; water frozen 12/27/13 SW Q-34 11/28/13 - No sample; water frozen 12/27/13 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 2013.

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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 all 22 samples. The values ranged from 2.5 to 6.6 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C). The required LLD was met.

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

Iron and Nickel Quarterly composites of monthly collections were analyzed for Fe-55 and Ni-63 (Table C-I.2, Appendix C). No Fe-55 or Ni-63 were detected. The required LLDs were met.

Gamma Spectrometry Samples from both locations were analyzed monthly for gamma emitting nuclides (Table C-1.3, Appendix C). Naturally occurring K-40, Ra-226, and Th-228 were detected. 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:

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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). Naturally occurring K-40 was detected. 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).

Naturally occurring K-40 was detected in all samples. No nuclides associated with QCNPS were detected and all required LLDs were met.

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

Gamma Spectrometry Sediment samples from Q-39 and Q-40 were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). Cesium-137 was detected in two samples at location Q-40 (control). The concentrations were 81 and 82 pCi/kg wet. Occasionally Cs-137 is detected at very low levels (just above LLD) in sediment and is not distinguishable from background levels. No other nuclides potentially associated with QCNPS were detected and all required LLDs were met. Naturally occurring Be-7, K-40, Ra-226, Th-228, Page 19 of 124

and Th-232 were detected.

B. Atmospheric Environment

1. Airborne

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

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

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

Comparison of results among the four groups aid in determining the effects, if any, resulting from the operation of QCNPS. The results from the near-field locations (Group I) ranged from 4 to 56 E-03 pCi/m 3 with a mean of 19 E-03 pCi/m . The results from the far-field locations (Group II) ranged from 6 to 52 E-03 pCi/m 3 with a mean of 19 E-03 pCi/m 3 . The results from the Control location (Group Ill) ranged from 5 to 53 E-03 pCi/m 3 with a mean of 20 E-03 pCi/m 3 . Comparison of the 2013 air particulate data with previous year's data indicate no effects from the operation of QCNPS. In addition comparisons of the weekly mean values for 2013 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).

Naturally occurring Be-7, and K-40 were detected. No nuclides associated with QCNPS were detected and all required LLDs were met.

Page 20 of 124

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-VI.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:

Iodine-131 Milk samples from the location were analyzed for concentrations of 1-131 (Table C-VII.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-VII.2, Appendix C).

Naturally occurring K-40 was detected in all samples. No nuclides associated with QCNPS were detected and all required LLDs were met.

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

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-VIII.1, Appendix C). Naturally occurring Be-7, K-40, Ra-226, Th-228, and Th-232 were detected. No nuclides associated with QCNPS were detected and all required LLDs were met.

Page 21 of 124

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

All of the OSLD measurements were below 30 mRem/quarter, with a range of 15.1 to 26.7 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 2013 around QCNPS was performed by 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 22 of 124

Distance in Miles from QCNPS Sector Residence Livestock Milk Farm Miles Miles Miles N 0.6 2.7 NNE 3.8 3.1 NE 1.3 3.2 ENE 2.9 2.9 E 2.0 2.7 ESE 2.8 3.1 3.1 SE 2.5 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 Teledyne Brown Engineering (TBE) provides data results [activity, uncertainty and minimum detectable concentration {MDC}]. We are required to calculate the MDC using a multiplier of 4.66.

4.66 Zt MDA= A 2.22 (v)(y) (a)(6)

Where:

At = counting time for sample (minutes)

P3= background rate of instrument blank (cpm) 2.22 = dpm/pCi or: 2.22 x 106 dpm/ýLCi v = volume or mass of sample analyzed y = chemical yield E = efficiency of the counter Page 23 of 124

The formulas for calculating the activity, uncertainty and MDC are contained in the software of the counting equipment. For the gamma system, when the new detector number 08 was added to the system in January 2012, the default value of 3.29 was used to calculated the MDCs on detector 08. The activity and uncertainty were not affected. The multiplier has been changed from 3.29 to the required 4.66.

When the MDCs are recalculated using 4.66, the MDC values will increase by 41.6%. The greatest impact will be on the short-lived nuclides which have an LLD requirement, e.g. 1-131, Ba-140 and La-140. Which means there could be some missed LLDs which will be identified in the Errata Data Appendix table of the 2013 annual report. This is not a reportable issue for the NRC. There is also the possibility that naturally produced nuclides that were detected would become a non-detect, e.g Th-228, Th-230, etc.

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.

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.

Page 24 of 124

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, 178 out of 185 analyses performed met the specified acceptance criteria. Seven analyses (Sr-89 and Sr-90 in milk, Co-57, Zn-65 and Sr-90 in soil, Cs-1 34 in air particulate and Sr-90 in vegetation [two low warning in a row]) did not meet the specified acceptance criteria or internal QA requirements for the following reason:

1. Teledyne Brown Engineering's Analytics September 2013 Sr-89 in milk result of 63.9 pCi/L was lower than the known value of 96.0 pCi/L. The failure was a result of analyst error and was specific to the Analytics sample. Client samples for the associated time period were evaluated and no client samples were affected by this failure. NCR 13-15

2. Teledyne Brown Engineering's Analytics September 2013 Sr-90 in milk result of 8.88 pCi/L was lower than the known value of 13.2 pCi/L. The failure was a result of analyst error and was specific to the Analytics sample. Client samples for the associated time period were evaluated and no client samples were affected by this failure. NCR 13-15

3. & 4. Teledyne Brown Engineering's MAPEP September 2013 Co-57 and Zn-65 in soil were evaluated as failing the false positive test.

While MAPEP evaluated the results as failures, the gamma software listed the results as non identified nuclides. The two nuclides would never have been reported as detected nuclides to a client. MAPEP does not allow laboratories to put in qualifiers for the submitted data nor "less than" results. MAPEP evaluates results based on the relationship between the activity and the uncertainty. MAPEP spiked the soil sample with an extremely large concentration of Eu-1 52, which was identified by the gamma software as an interfering nuclide, resulting in forced activity results that were evaluated by MAPEP as detected Co-57 and Zn-65. No client samples were affected by these failures. NCR 13-14 Page 25 of 124

5. Teledyne Brown Engineering's MAPEP September 2013 Sr-90 in soil result of 664 Bq/kg was higher than the known value of 460 Bq/kg, exceeding the upper control limit of 598 Bq/kg. An incorrect Sr-90 result was entered into the MAPEP database. The correct Sr-90 activity of 322 Bq/kg would have been evaluated as acceptable with warning. No client samples were affected by this failure. NCR 13-14

6. Teledyne Brown Engineering's MAPEP September 2013 Cs-134 in air particulate activity of -0.570 Bq/sample was evaluated as a failed false positive test, based on MAPEP's evaluation of the result as a significant negative value at 3 standard deviations. A negative number would never have been reported as a detected nuclide to a client, therefore no client samples were affected by this failure.

NCR 13-14

7. Teledyne Brown Engineering's MAPEP September 2013 Sr-90 in vegetation result was investigated due to two low warnings in a row. It appears the September sample was double spiked with carrier, resulting in a low activity. With a recovery of around 50%

lower, the Sr-90 result would have fallen within the acceptance range. No client samples were affected by this issue. NCR 13-14 For the EIML laboratory, 89 of 92 analyses met the specified acceptance criteria. Three analyses (AP - Gross Alpha, Soil - Sr-90 and Co-57) did not meet the specified acceptance criteria for the following reasons:

1. Environmental Inc., Midwest Laboratory's MAPEP February 2013 air particulate gross alpha result of 0.14 Bq/total sample was lower than the known value of 1.20 Bq/total sample, exceeding the lower control limit of 0.36 Bq/total sample. The filter was recounted overnight. No significant activity could be detected.

2. Environmental Inc., Midwest Laboratory's MAPEP February 2013 soil Co-57 result of 408.40 Bq/kg was lower than the known value of 628.0 Bq/kg, exceeding the lower control limit of 440.0 Bq/kg.

The sample was reanalyzed using additional fuming nitric separations. The reanalysis result of 574.4 fell within the control limits.

3. Environmental Inc., Midwest Laboratory's MAPEP August 2013 soil Co-57 result of 699.60 Bq/kg was higher than the known value of 0.00 Bq/kg, exceeding the upper control limit of 5.00 Bq/kg.

Interference from Eu-152 resulted in misidentification of Co-57.

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 124

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Page 27 of 124

Intentionally left blank Page 28 of 124

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER GR-B 22 4 4.2 4.6 4.6 Q-34 CONTROL 0 (PCI/LITER) (1 1/11) (11/Il) (11/11) CAMANCHE - UPSTREAM (2.9/5.2) (2.5/6.6) (2.5/6.6) 4.4 MILES NNE OF SITE H-3 8 2000 <LLD <LLD 0 FE-55 8 200 <LLD <LLD 0 NI-63 8 5 <LLD <LLD 0 GAMMA 22 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 rJQ CO-60 15 <LLD <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER ZN-65 30 <LLD <LLD 0 (PCI/LITER)

NB-95 15 <LLD <LLD 0 ZR-95 30 <LLD <LLD 0 1-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 0Q 0

C)J

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, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER H-3 8 2000 <LLD NA 0 (PCI/LITER)

GAMMA 8 MN-54 15 <LLD NA 0 CO-58 15 <LLD NA 0 FE-59 30 <LLD NA 0 CO-60 15 <LLD NA 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA 0 0 ZR-95 30 <LLD NA 0 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)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER 1-131 15 <LLD NA 0 (PCI/LITER)

CS-134 15 <LLD NA 0 CS-137 18 <LLD NA 0 A

BA-140 60 <LLD NA 0 LA-140 15 <LLD NA 0 FISH GAMMA 8 (PCI/KG WET) MN-54 130 <LLD <LLD 0 CO-58 130 <LLD <LLD 0 "0

00 a

uJ t'J FE-59 260 <LLD <LLD 0 0

k)

A

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, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) 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 FISH CO-60 130 <LLD <LLD 0 (PCI/KG WET)

ZN-65 260 <LLD <LLD 0 NB-95 NA <LLD <LLD 0

(-A ZR-95 NA <LLD <LLD 0 CS-134 130 <LLD <LLD 0 CS-137 150 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD co IV)

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, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) 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 SEDIMENT GAMMA (PCI/KG DRY) MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 61 CO-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 a

CS-134 150 <LLD <LLD 0 4I.

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, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) 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 SEDIMENT CS-137 180 <LLD 82 82 Q-40 CONTROL (PCI/KG DRY) (2/2) (2/2) NORTH OF ALBANY (UPSTREAM)

(81/82) (81/82) 8.9 MILES NE OF SITE BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 AIR PARTICULATE GR-B 528 10 19 20 20 Q-41 INDICATOR (E-3 PCI/CU.METER) (473/475) (53/53) (51/51) CAMANCHE (4/56) (5/53) (8/51) 4.3 MILES NNE OF SITE GAMMA 40 MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 0 CO-60 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, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE ZN-65 NA <LLD <LLD 0 (E-3 PCI/CU.METER)

NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 00 CS-134 50 <LLD <LLD 0 CS-137 60 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0

0 AIR IODINE GAMMA 530 (E-3 PCI/CU.METER) 1-131 70 <LLD <LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (MN) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK 1-131 19 1 <LLD NA 0 (PCI/LrTER)

GAMMvA 19 MN-54 NA <LLD NA 0 CO-58 NA <LLD NA 0 FE-59 NA <LLD NA 0 CO-60 NA <LLD NA 0 ZN-65 NA <LLD NA 0 NB-95 NA <LLD NA 0 c0 ZR-95 NA <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK CS-134 15 <LLD NA 0 (PCI/LITER)

CS-137 18 <LLD NA u BA-140 60 <LLD NA 0

,0 LA-140 15 <LLD NA 0 VEGETATION GAMMA 10 (PCI/KG WET) MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 10 uo 00 00 CO-60 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, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA EL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN XM) 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 VEGETATION ZN-65 NA <LLD <LLD 0 (PCI/KG WET)

NB-95 NA <LLD <LLD ZR-95 NA <LLD <LLD 1-131 60 <LLD <LLD CS-134 60 <LLD <LLD 0 CS-137 80 <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, 2013 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 2013 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) 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 DIRECT RADIATION OSLD-QUARTERLY 328 NA 20.6 23.1 24.6 Q-21 1-1 INDICATOR 0 (MhLLIREM/QTR.) (320/320) (8/8) (4/4)

(15.1/26.7) (20.6/26.2) (21.9/26.7) 4.5 MILES SW 00 0

0 k)

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)

APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS Page 41 of 124

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TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2013 Location Location Description Distance & Direction From Site A. Surface Water Q-33 Cordova (indicator) 3.1 miles SSW Q-34 Camanche, Upstream (control) 4.4 miles NNE B. Ground/Well Water Q-35 McMillan Well (indicator) 1.5 miles S Q-36 Cordova Well (indicator) 3.3 miles SSW C. Milk - bi-weekly / monthly Q-26 Bill Stanley Dairy (indicator) 3.1 miles ESE D. Air Particulates / Air Iodine Q-01 Onsite I (indicator) 0.5 miles N Q-02 Onsite 2 (indicator) 0.4 miles ENE Q-03 Onsite 3 (indicator) 0.6 miles S Q-04 Nitrin (indicator) 1.7 miles NE Q-13 Princeton (indicator) 4.7 miles SW Q-16 Low Moor (indicator) 5.7 miles NNW Q-37 Meredosia Road (indicator) 4.4 miles ENE Q-38 Fuller Road (indicator) 4.7 miles E Q-41 Camanche (indicator) 4.3 miles NNE Q-42 LeClaire (control) 8.7 miles SSW E. Fish Q-24 Pool #14 of Mississippi River, Downstream (indicator) 0.5 miles SW Q-29 Mississippi River, Upstream (control) 1.0 miles N F. Sediment Q-39 Cordova, Downstream on Mississippi River (indicator) 0.8 miles SSW Q-40 North of Albany, Upstream on Mississippi River(control) 8.9 miles NE G. Food Products Quadrant 1 Ken DeBaille 2.3 miles ENE Quadrant 2 Dale Nimmic 3.0 miles ESE Quadrant 3 Amy Johnston 1.8 miles S Quadrant 4 Mike Fawcett 4.5 miles NW Control Charles Leavens 9.5 miles NE H. Environmental Dosimetry - OSLD Inner Ring Q-101-1 0.6 miles N Q-101-2 0.9 miles N Q-102-1 1.3 miles NNE Q-102-3 1.4 miles NNE Q-103-1 and-2 1.2 miles NE 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-I Page 43 of 124

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2013 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - OSLD (continued)

Inner Ring Q-109-1 0.9 miles S Q-109-2 1.2 miles S Q-111-1 2.6 miles SW Q-111-2 2.5 miles SW Q-1 12-1 2.5 miles WSW Q-112-2 2.2 miles WSW Q-113-1 and -2 2.5 miles W Q-1 14-1 2.1 miles WNW Q-1 14-2 2.5 miles WNW Q-1 15-1 2.6 miles NW Q-1 15-2 2.3 miles NW Q-1 16-1 2.3 miles NNW Q-116-3 2.4 miles NNW Outer Ring Q-201-1 and -2 4.2 miles N Q-202-1 4.4 miles NNE Q-202-2 4.8 miles NNE Q-203-1 4.7 miles NE Q-203-2 5.0 miles NE Q-204-1 4.7 miles ENE Q-204-2 4.5 miles ENE Q-205-1 4.7 miles E Q-205-4 4.8 miles E Q-206-1 and -2 4.8 miles ESE Q-207-1 and -4 4.7 miles SE Q-208-1 4.3 miles SSE Q-208-2 4.9 miles SSE Q-209-1 and -4 4.7 miles S Q-210-1 and -4* 4.1 miles SSW Q-210-5 3.3 miles SSW Q-211-1 and -2 4.5 miles SW Q-212-1 5.4 miles WSW Q-212-2 4.4 miles WSW Q-213-1 4.3 miles W Q-213-2 4.8 miles W Q-214-1 4.7 miles WNW Q-214-2 4.4 miles WNW Q-215-1 5.0 miles NW Q-215-2 4.2 miles NW Q-216-1 4.6 miles NNW Q-216-2 4.3 miles NNW Other Q-01 Onsite 1 (indicator) 0.5 miles N Q-02 Onsite 2 (indicator) 0.4 miles ENE Q-03 Onsite 3 (indicator) 0.6 miles S Q-04 Nitrin (indicator) 1.7 miles NE Q-13 Princeton (indicator) 4.7 miles SW Q-16 Low Moor (indicator) 5.7 miles NNW Q-37 Meredosia Road (indicator) 4.4 miles ENE Q-38 Fuller Road (indicator) 4.7 miles E Q-41 Camanche (indicator) 4.3 miles NNE B-2 Page 44 of 124

TABLE B-i: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2013 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - OSLD (continued)

Control Q-42 LeCLaire 8.7 miles SSW

Removed from ODCM in December 2006 and replaced by Q-210-5. Q-210-4 is for trending only B-3 Page 45 of 124

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2013 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 and/or 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 Iron-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 and/or 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 OSLD Optically Stimulated Quarterly OSLDs Landauer Incorporated Luminescence comprised of two A12 0 3 :C Dosimetry Landauer Incorporated elements B-4 Page 46 of 124

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Figure B-1 Map Quad Cities REMP Sampling Locations -2 Mile Radius, 2013

(OQ o0 Figure B-2 Map Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2013

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY Page 49 of 124

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Table C-I.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q-33 Q-34 PERIOD 01/11/13 - 01/11/13 3.5 +/- 1.4 (1) 2.5 + 1.2 (1) 02/08/13 -02115/13 4.5 +/- 1.6 (1) 5.0 +/- 1.6 (1) 03/29/13 - 03/29/13 4.9 + 1.5 (1) 6.6 +/- 1.6 (1) 04/05/13 - 04/25/13 2.9 +/- 1.5 6.1 +/- 1.6 05/03/13 - 05/31/13 5.2 +/- 1.3 4.3 +/- 1.3 06/07/13 - 06/28/13 4.6 +/- 1.5 4.4 +/- 1.6 07/05/13 - 07/26/13 5.2 +/- 1.4 4.3 +/- 1.3 08/02/13 - 08/29/13 4.0 +/- 1.5 4.8 +/- 1.5 09/05/13 - 09/27/13 3.9 +/- 1.3 3.8 +/- 1.2 10/04/13 - 10/31/13 3.0 +/- 1.4 4.6 +/- 1.5 11/08/13 - 11/22/13 4.4 + 1.2 4.7 +/- 1.2 12/05/13 - 12/27/13 (1) (1)

MEAN 4.2 +/- 1.6 4.6 +/- 2.2 Table C-I.2 CONCENTRATIONS OF TRITIUM, IRON, AND NICKEL IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION H-3 (DIST) FE-55 NI-63 PERIOD Q-33 01/11/13 - 03/29/13 < 186 (1) < 116 (1) < 3.7 (1) 04/05/13 - 06/28/13 < 194 < 93 < 3.4 07/05/13 - 09/27/13 < 196 < 135 < 4.3 10/04/13 - 11/22/13 < 182 (1) < 50 (1) < 4.7 (1)

MEAN Q-34 01/11/13 - 03/29/13 < 180 (1) < 188 (1) < 4.0 (1) 04/05/13 - 06/28/13 < 189 < 71 < 3.4 07/05/13 - 09/27/13 < 190 < 107 < 4.4 10/04/13 - 11/22/13 < 179 (1) < 137 (1) < 3.8 (1)

MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1 Page 51 of 124

Table C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-137 Ba-140 La-140 PERIOD Q-33 01/11/13 - 01/11/13 (1) < 1 <1 <3 <1 <2 <1 <2 < 12 <1 <1 < 16 <5 02/08/13 - 02/15/13 (1) < 1 <1 <2 <1 <2 <1 <2 < 13 <1 <1 < 16 <4 03/29/13 - 03/29/13 (1) <4 <5 < 10 <5 <9 <5 < 8. < 13 <4 <5 < 31 <7 04/05/13 - 04/25/13 <2 <2 <4 <2 <3 <2 <3 <9 <2 <2 < 16 <5 05/03/13 - 05/31/13 <3 <4 <9 <4 <6 <4 <7 < 12 <3 <4 < 26 <8 06/07/13 - 06/28/13 <1 <1 <2 <1 <2 <1 <2 < 13 <1 <1 < 16 <4 07/05/13 - 07/26/13 <3 <3 <8 <3 <7 <4 <6 <8 <3 <4 < 20 <5 08/02/13 - 08/29/13 <2 <2 <5 <2 <4 <2 <4 < 15 <2 <2 < 24 <8 09/05/13 - 09/27/13 <1 <1 <3 <1 <3 <1 <2 < 12 <1 <1 < 15 <4 10/04/13 - 10131/13 <2 <2 <5 <2 <4 <2 <4 < 12 <2 <2 < 22 <6 11/08/13 - 11/22/13 <3 <3 <6 <3 <5 <3 <5 < 14 <2 <3 < 26 <8 12/05/13 - 12/27/13 (1) -

MEAN Q-34 01/11/13 - 01/11/13 (1) <2 <2 <5 <2 <3 <2 <4 < 16 <2 <2 < 24 <8 02/08/13 - 02/15/13 (1) <1 <2 <4 <1 <3 <2 <3 < 17 <1 <1 < 24 <9 03/29/13 - 03/29/13 (1) <4 <5 < 11 <5 <9 <5 <7 < 11 <4 <4 < 27 <9 04/05/13 - 04/25/13 <2 <3 <7 <2 <5 <3 <5 < 11 <2 <2 < 23 <8 05/03/13 - 05/31/13 <4 <5 < 10 <4 < 10 <5 <9 < 14 <4 <4 < 31 <8 06/07/13 - 06/28/13 <1 <1 <2 <1 <1 <1 <2 < 13 <1 <1 < 16 <4 07/05/13 - 07/26/13 <4 <4 <9 <4 <9 <5 <8 < 10 <4 <5 < 27 <7 08/02/13 - 08/29/13 <2 <2 <5 <2 <4 <2 <4 < 15 <2 <2 < 24 <7 09/05/13 - 09/27/13 <2 <2 <4 <2 <3 <2 <3 < 15 <1 <1 < 22 <7 10/04/13 - 10/31/13 <1 <2 <4 <2 <3 <2 <3 <8 <1 <1 < 14 <5 11/08/13 - 11/22/13 <3 <4 <8 <3 <7 <4 <7 < 14 <3 <3 < 28 <9 12/05/13 - 12/27/13 (1)

MEAN 1z (I

k) (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-I1.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q-35 Q-36 PERIOD 01/11/13 - 01/11/13 < 184 < 185 04/12/13 - 04/12/13 < 169 < 168 07/12/13 - 07/12/13 < 193 < 187 10/11/13 - 10/11/13 < 170 < 169 MEAN - -

C-3 Page 53 of 124

Table C-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-35 01/11/13 - 01/11/13 < 1 <2 <4 <2 <3 <2 <3 <14 <1 <2 <21 <7 04/12/13 - 04/12/13 < 5 <6 <12 <4 <11 <6 <8 <12 <5 <5 < 29 < 12 07/12/13 - 07/12/13 < 4 <5 <10 <4 <10 <5 <8 <12 <4 <4 <25 <7 10/11/13 - 10/11/13 < 3 <4 <7 <3 <6 <4 <7 <15 <3 <3 <29 <9 MEAN Q-36 01/11/13 - 01/11/13 < 2 <2 <5 <2 <4 <2 <4 <14 <2 <2 <23 <9 04/12/13 - 04/12/13 < 4 <4 <10 <4 <9 <5 <8 <11 <4 <5 <25 <8 07/12/13 - 07/12/13 < 4 <3 <8 <4 <8 <4 <8 <11 <4 <4 <24 <7 10/11/13 - 10/11/13 < 4 <4 <10 <4 <9 <5 <8 <14 <4 <4 <32 < 11 MEAN "0

C

Table C-II1.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 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 Freshwater Drum 05/07/13 < 59 < 62 < 154 < 56 < 122 < 87 < 152 <64 < 62 < 941 < 283 Walleye 05/07/13 < 56 < 72 < 151 < 80 < 132 < 82 < 138 < 50 < 65 < 1058 < 338 Common Carp 10/02/13 < 64 < 66 < 200 < 62 < 133 < 86 < 161 < 56 < 58 < 1089 < 296 Golden Redhorse 10/02/13 < 56 < 63 < 146 < 57 < 112 < 88 < 114 < 59 < 68 < 1084 < 220 MEAN Q-29 Channel Catfish 05/08/13 < 66 < 78 < 194 < 62 < 128 < 81 < 114 < 57 < 70 < 1023 < 336 Largemouth Bass 05/08/13 < 40 < 55 < 122 < 53 < 126 < 73 < 113 < 47 < 51 < 971 < 352

( Common Carp 10/02/13 < 51 < 57 < 155 < 46 < 73 < 68 < 92 < 45 < 43 < 873 < 287 Largemouth Bass 10/02/13 < 60 < 77 < 233 < 77 < 139 < 105 < 162 < 60 < 82 < 1443 < 389 MEAN tA

Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED INTHE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 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 05/30/13 < 68 < 55 < 135 < 78 < 133 < 78 < 128 < 59 < 78 < 409 < 117 10/14/13 < 54 < 56 < 136 < 57 < 124 < 69 < 124 < 48 <64 < 577 < 173 MEAN Q-40 05/30/13 < 52 < 49 < 119 < 67 < 118 < 62 < 106 < 52 82 +/- 61 < 384 < 89 10/14/13 < 80 < 88 < 174 < 82 < 158 < 96 < 167 < 73 81 +/-54 < 1003 < 246 MEAN 82 +/- 1 -

00 0

I')

Table C-V.l CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I IGROUP 11 GROUP III PERIOD Q-01 Q-02 03 Q-04 Q-13 0-16 Q-37 0-38 0-41 Q-42 12/29/12 - 01/04/13 53 +/-7 56 +/-7 -52+/-7 46 +/-6 52 +/-6 40 +/-6 51 +/-7 44 +/-6 51 +/- 6 53-+/-6 01/04/13 - 01/11/13 43 +/- 6 34 +/- 5 36 +/- 5 30 +/- 5 36 +/- 5 29 +/- 5 28 +/- 5 27 +/- 5 34 +/- 5 40 +/- 6 01/11/13 - 01/18/13 24 +/- 5 26 +/- 5 24 +/- 5 25 +/- 5 20 +/- 4 17 +/- 4 17 +/-t4 24 +/- 5 23 +/- 5 27 +/- 5 01/18/13 - 01/25/13 21 +/-5 24 +/-5 16 +/-4 23 +/-5 17 +/-4 17 +/-4 18 +/-4 23 +/-5 22 +/- 5 23+/- 5 01/25/13 - 02/01/13 30 +/-5 38 +/-5 30 +/-5 27 +/-5 33 +/-5 34 +/-5 30 +/-5 30 +/-5 26 +/- 5 34+/- 5 02/01/13 - 02/08/13 33 +/- 5 32 +/- 5 31 +/- 5 26 +/- 4 31 +/- 5 26 +/- 4 30 +/- 5 41 +/- 5 30 +/- 5 34 +/- 5 02/08/13 - 02/15/13 17 +/- 4 23 +/- 5 16 +/- 4 18 +/- 4 20 +/- 4 13 +/- 4 17 +/- 4 19 +/- 4 17 +/- 4 20 +/- 4 02/15/13 - 02/21/13 13 +/- 4 4 +/- 2 16 +/- 4 15 +/- 4 13 +/- 5 13 +/- 5 11 +/- 4 15 +/- 4 20 +/- 5 18 +/- 5 02/22/13 - 03/01/13 12 +/- 4 15 +/- 4 10 +/- 4 10 +/- 4 10 +/- 4 13 +/- 4 14 +/- 4 11 +/- 4 12 +/- 4 11 +/- 4 03/01/13 - 03/07/13 15 +/-4 13 +/-4 15 +/-4 13 +/-4 9 +/-4 12 +/-4 14 +/-4 14 +/-4 12 +/-4 16+/- 4 03/08/13 - 03/16/13 19 +/-4 18 +/-4 19 +/-4 19 +/-4 17 +/-4 18 +/-4 20 +/-4 18 +/-4 13 +/-4 19 +/-4 03/16/13 - 03/22/13 19 +/-5 14 +/-5 19 +/-5 13 +/-5 19 +/-4 17 +/-4 16 +/-5 16 +/-5 17 +/-4 18+/- 4 03/22/13 -03/29/13 <5 8 +/-4 7 +/-3 9 +/-4 6 +/-3 7 +/-3 6 +/-3 8 +/-3 8 +/-4 9 +/-4 03/29/13 - 04/05/13 22 +/- 5 21 +/- 5 27 +/- 5 13 +/- 4 15 +/- 4 13 +/- 4 16 +/- 4 14 +/- 4 20 +/- 5 19 +/- 5 04/05/13 - 04/12/13 13 +/- 4 12 +/- 4 14 +/- 4 12 +/- 4 14 +/- 4 10 +/- 4 11 +/- 4 12 +/- 4 13 +/- 4 12 +/- 4 04/12/13 - 04/19/13 8 +/-3 8 +/-3 12 +/-4 9 +/-3 8 +/-3 6 +/-3 7 +/-3 9 +/-3 9 +/- 3 10+/- 3 04/19/13 -04/25/13 13 +/-4 12 +/-4 16 +/-4 16 +/-4 15 +/-5 16 +/-5 14 +/-4 12 +/-4 17 +/-5 15 +/-5 04/26/13 - 05/03/13 18 +/-4 20 +/-4 23 +/-4 20 +/-4 18 +/-4 20 +/-4 22 +/-4 16 +/-4 20 +/- 4 21 +/- 4 05/03/13 - 05/09/13 8 +/- 3 11 +/- 4 12 +/- 4 9 +/- 3 9 +/-4 9 +/- 4 10 +/- 4 9 +/- 3 12 +/- 4 8+/- 4 05/10/13 - 05/17/13 14 +/-4 13 +/-4 12 +/-4 16 +/-4 12 +/-3 19 +/-4 12 +/-4 15 +/-4 16 +/- 4 10 +/- 3 05/17/13 - 05/23/13 13 +/- 4 7 +/- 4 11 +/- 4 10 +/- 4 12 +/- 4 17 +/- 5 10 +/- 4 14 +/- 4 13 +/- 5 14 +/- 5 05/24/13 - 05/31/13 11 +/- 4 9 +/- 4 13 +/- 4 11 +/- 4 13 +/- 4 14 +/- 4 13 +/- 4 10 +/- 4 13 +/- 4 11 +/- 4 05/31/13 - 06/07/13 11 +/- 4 16 +/- 4 12 +/- 4 12 +/- 4 13 +/- 4 14 +/- 4 12 +/- 4 9 +/- 3 13 +/- 4 5+/- 3 06/07/13 - 06/14/13 17 +/-4 16 +/-4 16 +/-4 16 +/-4 18 +/-4 19 +/-4 17 +/-4 17 +/-4 19 +/-4 23+/- 4 06/14/13 - 06/21/13 12 +/- 4 12 +/- 4 13 +/- 4 15 +/- 4 15 +/- 4 15 +/- 4 16 +/- 4 14 +/- 4 15 +/- 4 11 +/- 4 06/21/13 -06/28/13 12 +/-4 9 +/-4 (1) 12 +/-4 16 +/-4 15 +/-4 11 +/-4 15 +/-4 (1) 17 +/-4 (1) 17 +/-4 14+/- 4 06/28/13 - 07/05/13 12 +/- 4 9 +/- 4 12 +/- 4 9 +/-4 12 +/- 4 12 +/- 4 11 +/- 4 11 +/- 4 12 +/- 4 10 +/- 4 07/05/13 -07/12/13 18 +/-4 16 +/-4 14 +/-4 14 +/-4 16 +/-4 10 +/-3 17 +/-4 16 +/-4 16 +/-4 19+/- 4 07/12/13 - 07/19/13 13 +/- 4 13 +/- 4 11 +/- 4 17 +/- 4 13 +/- 4 11 +/- 4 14 +/- 4 9 +/-4 13 +/- 4 14 +/- 4 07/19/13 - 07/26/13 14 +/- 4 12 +/- 4 12 +/- 4 13 +/- 4 15 +/- 4 10 +/- 4 14 +/- 4 14 +/- 4 14 +/- 4 12 +/- 4 07/26/13 -08/02/13 17 +/-4 15 +/-4 12 +/-4 17 +/-4 14 +/-4 13 +/-4 14 +/-4 12 +/-4 15 +/- 4 16+/- 4 08/02/13 - 08/10/13 19 +/-4 22 +/-4 21 +/-4 18 +/-4 22 +/-4 23 +/-4 19 +/-4 21 +/-4 20 +/- 4 23+/- 4 08/10/13 - 08/16/13 18 +/-5 19 +/-5 17 +/-5 15 +/-4 19 +/-5 18 +/-5 17 +/-5 15 +/-5 22 +/- 5 17+/- 4 08/16/13 -08/23/13 31 +/-5 29 +/-5 24 +/-5 24 +/-5 31 +/-5 34 +/-5 29 +/-5 28 +/-5 28 +/- 5 27+/- 5 08/23/13 -08/29/13 23 +/-5 22 +/-5 23 +/-5 9 +/-4 23 +/-5 16 +/-5 21 +/-5 <5 23 +/-5 20+/- 5 08/30/13 - 09/06/13 19 +/-4 21 +/-5 16 +/-4 17 +/-4 26 +/-5 18 +/-4 18 +/-4 18 +/-4 20 +/-4 23+/- 4 09/06/13 - 09/13/13 31 +/-5 28 +/-5 32 +/-5 24 +/-5 28 +/-5 26 +/-4 33 +/-5 29 +/-5 30 +/-5 27+/- 5 09/13/13 - 09/20/13 18 +/-4 17 +/-4 18 +/-4 10 +/-3 19 +/-4 16 +/-4 18 +/-4 16 +/-4 20 +/- 5 18+/- 4 09/21/13 - 09/27/13 17 +/-5 18 +/-5 16 +/-5 18 +/-5 19 +/-4 15 +/-4 16 +/-5 16 +/-5 22 +/- 5 17+/- 4 09/27/13 -10/04/13 23 +/-4 23 +/-4 24 +/-4 20 +/-4 22 +/-4 23 +/-4 22 +/-4 22 +/-4 26 +/-5 27 +/-5 10/04/13 - 10/11/13 16 +/- 4 23 +/- 4 18 +/- 4 7 +/- 2 19 +/- 4 21 +/- 5 20 +/- 4 17 +/- 4 23 +/- 5 20 +/- 4 10/12/13 - 10/18/13 13 +/-4 13 +/-4 16 +/-5 12 +/-4 19 +/-4 18 +/-4 14 +/-4 12 +/-4 14 +/- 4 15 +/-4 10/18/13 - 10/25/13 14 +/- 4 12 +/- 4 16 +/- 4 15 +/- 4 15 +/- 4 15 +/- 4 14 +/- 4 15 +/- 4 20 +/- 4 13 +/- 4 10/25/13 -10/31/13 19 +/-4 23 +/-5 17 +/-4 16 +/-4 14 +/-5 18 +/-5 19 +/-4 14 +/-4 20 +/- 5 16+/- 5 11/01/13 - 11/09/13 23 +/- 4 26 +/- 4 24 +/- 4 24 +/- 4 24 +/- 4 27 +/- 4 23 +/- 4 22 +/- 4 (1) 27 +/- 4 11/09113 - 11/15/13 18 +/- 5 9 +/-4 14 +/- 4 20 +/- 5 20 +/- 4 20 +/- 4 14 +/- 4 19 +/- 5 (1) 17 +/- 4 11/15/13 - 11/22/13 22 +/- 6 21 +/- 6 16 +/- 5 25 +/- 6 20 +/- 6 19 +/- 4 16 +/- 5 21 +/- 6 21 +/- 6 18 +/- 5 11/22/13 - 11/28/13 17 +/- 5 22 +/- 5 15 +/- 5 18 +/- 5 16 +/- 5 20 +/- 5 21 +/- 5 20 +/- 5 20 +/- 5 19 +/- 5 11/29/13 - 12/06/13 44 +/- 6 40 +/- 6 39 +/- 6 34 +/- 5 42 +/- 6 37 +/- 5 39 +/- 5 41 +/- 6 39 +/- 5 45 +/- 6 12/06/13 - 12/13/13 35 +/-5 36 +/-5 31 +/-5 32 +/-5 35 +/-5 35 +/-5 30 +/-5 37 +/-5 38 +/- 5 34 +/-5 12/13/13 -12/19/13 25 +/-5 30 +/-5 26 +/-5 15 +/-4 23 +/-5 29 +/-5 28 +/-5 22 +/-4 26 +/-5 30+/- 5 12/20/13 - 12/27/13 12 +/-4 26+/- 5 27+/- 5 25 +/-5 23 +/-4 29+/- 5 24+/-t5 31 +/-5 23+/-14 25+/- 4 12/27/13 - 01/03/14 27 +/- 5 28 +/- 5 36 +/- 5 25 +/- 5 29 +/- 5 28 +/- 5 28 +/- 5 32 +/- 5 34 +/- 5 27 +/- 5 MEAN 20 +/- 18 20 +/- 20 19 +/- 18 18 +/- 15 20 +/- 18 19 +/- 16 19 +/- 16 19 +/- 17 20 +/- 17 20 +/- 19 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-7 C-7 Page 57 of 124

Table C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS INAIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - NEAR-SITE LOCATIONS GROUP II - FAR-FIELD LOCATIONS GROUP III - CONTROL LOCATION COLLECTION MIN MAX MEAN + COLLECTION MIN MAX MEAN + COLLECTION MIN MAX MEAN +

PERIOD 2SD PERIOD 2SD PERIOD 2SD 14IL-uI I1 U4IU 1/ 1I 10 01 12/29/12 02i/0113 17 bi 21 1d 01104/13 02/01/13 23 40 31 +/- 15 02/01/13 03/01/13 4 33 18 + 17 02/01/13 03/01/13 10 41 19 17 02/01/13 03/01/13 11 34 21 +/- 20 03/01/13 03/29/13 7 19 15 +/-8 03/01/13 03/29/13 6 20 13 9 03/01/13 03/29/13 9 19 16 +/- 9 03/29/13 05/03/13 8 27 15 +/-11 03/29/13 05/03/13 6 22 14 9 03/29/13 05/03/13 10 21 15 +/- 9 05/03/13 05/31/13 7 16 11 +/-5 05/03/13 05/31/13 9 19 13 5 05/03/13 05/31/13 8 14 11 +/- 4 05/31/13 06/28/13 9 17 13 +5 05/31/13 06/28/13 9 19 15 5 05/31/13 06/28/13 5 23 13 +/- 15 06/28/13 08/02/13 9 18 14 +/-5 06/28/13 08/02/13 9 17 13 4 06/28/13 08/02/13 10 19 14 +/- 7 08/02/13 08/30/13 9 31 21 +10 08/02/13 08/30/13 15 34 22 10 08/02/13 08/29/13 17 27 22 +/- 9 08/30/13 10/04/13 10 32 21 +11 08/29/13 10/04/13 15 33 22 10 08/29/13 10/04/13 17 27 22 +/- 10 10/04/13 11/01/13 7 23 16 +/-8 10/04/13 11/01/13 12 23 17 6 10/04/13 10/31/13 13 20 16 +/- 6 11/01/13 11/29/13 9 26 20 +9 10/31/13 11/29/13 14 27 20 6 10/31/13 11/28/13 17 27 21 +/- 9 11/29/13 01/03/14 12 44 30 +/- 16 11/28/13 01/03/14 40 52 31 12 11/28/13 01/03/14 53 53 32 + 16 0

ýo 12/29/12 - 01/03/14 4 56 19 +/- 18 12/28/12 - 01/03/14 6 52 19 +/- 17 12/28/12 - 01/03/14 5 53 20 +/- 19 0

00 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES 10 00 0

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF E-3 PCI/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 12/29/12 03/29/13 <2 <4 < 11 <3 <8 <5 <,5 <3 <3 < 110 < 39 03/29/13 06/28/13 <2 <3 <9 <2 <4 <3 < 5 <3 <2 < 56 < 29 06/28/13 09/27/13 <3 <3 <9 <2 <6 < 3 <6 <3 <3 < 69 < 29 09/27/13 01/03/14 <1 <2 <5 <1 <5 <2 <4 <2 <2 < 29 <7 MEAN Q-02 12/29/12 03/29/13 <3 <3 <9 <2 <9 <5 <7 <3 <3 < 104 < 48 03/29/13 06/28/13 <3 <3 <7 <3 <5 <3 <5 <2 <2 < 70 < 28 06/28/13 09/27/13 <2 <3 <7 <2 <5 <2 <6 <2 <2 < 62 < 28 09/27/13 01/03/14 <2 <3 <6 <2 <7 <3 <5 <3 <2 <34 <7 MEAN C.)

Q-03 12/29/12 03/29/13 <2 <3 <7 <3 <7 <4 <7 <3 <3 < 102 < 38 03/29/13 06/28/13 <2 <3 <8 <2 <4 <3 <5 <2 <2 < 59 < 37 06/28/13 09/27/13 <3 <4 < 10 <3 <7 <4 <6 <2 <3 < 80 < 29 09/27/13 01/03/14 <3 <5 <9 <3 <9 <5 <7 <3 <3 < 50 < 12 MEAN Q-04 12/29/12 03/29/13 <2 <3 < 11 <3 <7 <4 <7 <3 <2 < 97 < 42 03/29/13 06/28/13 <4 <4 < 11 <4 < 10 <6 < 10 <4 <4 < 105 < 43 06/28/13 09/27/13 <3 <3 < 12 <3 <8 <4 <6 <3 <3 < 94 < 33 09/27/13 01/03/14 <2 <3 <5 <2 <5 <3 <6 <2 <2 < 27 <9 MEAN Q-13 12/28/12 03/29/13 <2 <3 <7 <2 <5 <2 <4 <1 <1 < 88 < 38 03/29/13 06/28/13 <3 <4 <8 <2 <7 <3 <6 <2 <2 < 84 < 33

~0 06/28/13 09/27/13 <3 <3 <8 <2 <6 <3 <5 <2 <2 < 73 < 23 00 09/27/13 01/03/14 <2 <3 <8 <3 <7 <3 <6 <3 <3 < 38 < 16 0

MEAN

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS INAIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF E-3 PCI/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 12/28/12 - 03/29 /13 <3 <4 <8 <4 <6 <5 <8 <4 <3 < 113 < 49 03/29/13 - 06/28 /13 <2 <2 <7 <2 <8 <4 <4 <3 <2 < 82 < 42 06/28/13 - 09/27 /13 <2 <3 <9 <2 <8 <3 <5 <2 <3 < 74 < 39 09/27/13 - 01/03 /14 <3 <3 <9 <3 <9 <4 <7 <4 <3 < 36 < 15 MEAN Q-37 12/29/12 03/29/13 <5 <4 < 14 <3 < 13 <5 <9 <4 <3 < 144 < 42 03/29/13 06/28/13 <2 <3 <7 <2 <6 <3 <5 <2 <2 < 61 < 30 06/28/13 09/27/13 <2 <3 <7 <2 <6 <3 <6 <2 <2 < 91 < 25 09/27/13 01/03/14 <2 <2 <5 <2 <6 <2 <4 <2 <2 < 31 MEAN 0 Q-38 12/29/12 - 03/29/13 <3 <4 < 12 <3 <7 <5 <8 <3 <2 < 108 < 42 03/29/13 - 06/28/13 <4 <5 < 12 <4 < 10 <6 < 10 <3 <3 < 124 < 53 06/28/13 - 09/27/13 <2 <2 <8 <2 <6 <3 <5 <3 <2 < 57 < 28 09/27/13 - 01/03/14 <2 <3 <6 <3 <7 <3 <5 <2 <2 < 32 < 10 MEAN Q-41 12/28/12 - 03/29/13 <2 <4 <8 <2 <6 <3 <7 <2 <3 < 104 < 28 03/29/13 - 06/28/13 <3 <3 <6 <3 <6 <4 <4 <2 <2 < 87 < 16 06/28/13 - 09/27/13 <2 <4 <6 <3 <7 <4 <6 <3 <2 < 93 < 28 09/27/13 - 01/03/14 <3 <3 <7 <2 <5 <3 <6 <3 <2 <34 <9 MEAN Q-42 12/28/12 - 03/29/13 <2 <2 <7 <1 <3 <3 <5 <2 <1 < 56 < 22 03/29/13 - 06/28/13 <3 <3 <8 <2 <5 <3 <6 <3 <2 < 75 < 28

-o 06/28/13 - 09/27/13 <2 <3 <7 <3 <5 <3 <6 <2 <2 <54 < 28 09/27/13 - 01/03/14 <2 <3 <5 <2 <6 <3 <5 <2 <2 <22 < 11 0

0 MEAN k)

Table C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I I GROUP 11 I GROUP III PERIOD Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 12/29/12z -1/ U141 63 < 6.3 < 30 < 61 < (U < 57 01/04/13 -01/11/13 < 21 < 53 < 51 < 51 < 48 < 16 < 40 < 40 < 39 < 38 01/11/13 -01/18/13 < 41 < 41 < 39 < 17 < 39 < 17 < 43 < 43 < 44 < 44 01/18/13 -01/25/13 < 12 < 29 < 28 < 28 < 28 < 41 < 41 < 41 < 42 < 42 01/25/13 -02/01/13 < 54 < 54 < 52 < 52 < 22 < 21 < 52 < 52 < 52 < 52 02/01/13 -02/08/13 < 23 < 44 < 43 < 43 < 44 < 14 < 32 < 32 < 33 < 34 02/08/13 -02/15/13 < 19 < 34 < 33 < 33 < 31 < 17 < 34 < 34 < 33 < 33 02/15/13 -02/21/13 < 32 < 54 < 52 < 52 < 65 < 28 < 41 < 41 < 53 < 53 02/22/13 -03/01/13 < 15 < 35 < 34 < 34 < 29 < 29 < 12 < 33 < 30 < 29 03/01/13 -03/07/13 < 6 < 18 < 18 < 18 < 22 <8 < 12 < 12 < 16 < 16 03/08/13 -03/16/13 < 24 < 32 < 31 < 31 < 34 < 31 < 29 < 28 < 32 < 32 03/16/13 -03/22/13 < 23 < 39 < 38 < 38 < 31 < 19 < 46 < 46 < 39 < 39 03/22/13 -03/29/13 < 12 < 28 < 27 < 27 < 28 < 30 < 29 < 29 < 10 < 31 03/29/13 -04/05/13 < 12 < 37 < 36 < 36 < 34 < 13 < 24 < 24 < 24 < 24 04/05/13 -04/12/13 < 14 < 37 < 36 < 36 < 34 < 35 < 37 < 37 < 37 < 15 04/12/13 -04/19/13 < 33 < 57 < 55 < 55 < 53 < 35 < 69 < 69 < 70 < 69 04/19/13 -04/25/13 < 15 < 39 < 37 < 37 < 47 < 17 < 33 < 33 < 42 < 41 04/26/13 -05/03/13 < 66 < 66 < 69 < 69 < 41 < 39 < 46 < 69 < 62 < 61 05/03/13 -05/09/13 < 13 < 15 < 38 (1) < 38 < 49 < 26 < 50 < 49 < 63 < 63 05/10/13 -05/17/13 < 11 < 28 < 28 (1) < 27 < 32 < 13 < 28 < 28 < 33 < 33 05/17/13 - 05/23/13 < 55 < 57 < 22 < 55 < 70 < 28 < 55 < 55 < 69 < 69 05/24/13 - 05/31/13 < 21 < 41 < 41 < 39 < 37 < 24 < 63 < 63 < 59 < 58 05/31/13 - 06/07/13 < 53 < 55 < 55 < 21 < 56 < 19 < 46 < 46 < 48 < 46 06/07/13 - 06/14/13 < 12 < 33 < 33 < 32 < 34 < 14 < 32 < 31 < 33 < 32 06/14/13 - 06/21/13 < 43 < 45 < 45 < 43 < 17 < 19 < 43 < 43 < 46 < 45 06/21/13 - 06/28/13 < 27 < 65 (1) < 63 < 60 < 61 < 16 < 50 (1) < 46 (1) < 45 < 44 06/28/13 - 07/05/13 < 28 < 69 < 69 < 67 < 66 < 10 < 23 < 23 < 24 < 23 07/05/13 - 07/12/13 < 46 < 47 < 47 < 46 < 19 < 45 < 45 < 45 < 46 < 46 07/12/13 - 07/19/13 < 22 < 55 < 55 < 53 < 54 < 60 < 25 < 61 < 62 < 60 07/19/13 - 07/26/13 < 25 < 63 < 63 < 60 < 63 < 35 < 36 < 64 < 67 < 64 07/26/13 - 08/02/13 < 23 < 65 < 65 < 67 < 70 < 67 < 66 < 36 < 70 < 67 08/02/13 - 08/10/13 < 27 < 62 < 62 < 60 < 61 < 27 < 51 < 51 < 51 < 50 08/10/13 - 08/16/13 < 22 < 58 < 58 < 56 < 56 < 48 < 50 < 50 < 21 < 47 08/16/13 - 08/23/13 < 61 < 63 < 63 < 61 < 25 < 30 < 35 < 35 < 31 < 12 08/23/13 - 08/29/13 < 24 < 59 < 59 < 57 < 65 < 67 < 53 < 53 < 67 < 36 08/30/13 - 09/06/13 < 66 < 68 < 68 < 66 < 28 < 69 < 64 < 64 < 69 < 28 09/06/13 - 09/13/13 < 35 < 68 < 68 < 65 < 60 < 16 < 47 < 47 < 43 < 41 09/13/13 - 09/20/13 < 18 < 47 < 47 < 45 < 54 < 25 < 49 < 49 < 59 < 57 09/21/13 - 09/27/13 < 48 < 21 < 50 < 48 < 42 < 26 < 56 < 56 < 48 < 46 09/27/13 - 10/04/13 < 24 < 65 < 65 < 63 < 67 < 28 < 62 < 62 < 66 < 64 10/04/13 - 10/11/13 < 56 < 58 < 24 < 56 < 69 < 20 < 39 < 39 < 48 < 46 10/12/13 - 10/18/13 < 19 < 47 < 47 < 45 < 41 < 21 < 43 < 43 < 39 < 37 10/18/13 - 10/25/13 < 32 < 33 < 33 < 12 < 32 < 19 < 49 < 50 < 50 < 48 10/25/13 - 10/31/13 < 21 < 57 < 57 < 55 < 68 < 29 < 56 < 58 < 69 < 67 11/01/13 - 11/09/13 < 68 < 70 < 70 < 68 < 29 < 18 < 39 < 40 < 43 < 41 11/09/13 - 11/15/13 < 27 < 51 < 51 < 50 < 45 < 25 < 53 < 54 < 48 < 46 11/15/13 - 11/22/13 < 26 < 69 < 69 < 67 < 68 < 23 < 56 < 58 < 57 < 55 11/22/13 - 11/28/13 < 13 < 25 < 25 < 24 < 31 < 32 < 30 < 31 < 39 < 38 11/29/13 - 12/06/13 < 53 < 54 < 54 < 56 < 61 < 61 < 23 < 56 < 58 < 57 12/06/13 - 12/13/13 < 24 < 63 < 63 < 61 < 55 < 25 < 67 < 69 < 60 < 58 12/13/13 - 12/19/13 < 66 < 68 < 68 < 66 < 36 < 59 < 46 < 47 < 25 < 57 12/20/13 - 12/27/13 < 27 < 55 < 55 < 53 < 49 < 27 < 57 < 58 < 52 < 51 12/27/13 - 01/03/14 < 25 < 61 < 61 < 59 < 60 < 64 < 64 < 66 < 64 < 26 MEAN- - -

(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1 I c-il Page 61 of 124

Table C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED INTHE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION INDICATOR FARM PERIOD Q-26 01/04/13 < 0.5 02/01/13 < 0.6 03/01/13 (1) < 1.0 04/05/13 < 0.6 05/03/13 < 0.7 05/17/13 < 0.7 05/31/13 < 0.8 06/14/13 < 0.9 06/28/13 < 0.7 07/12/13 < 0.8 07/26/13 < 0.5 08/10/13 < 0.7 08/23/13 < 0.4 09/06/13 < 0.7 09/21/13 < 0.7 10/04/13 < 0.7 10/18/13 < 0.4 11/01/13 < 0.6 12/06/13 < 0.6 MEAN C-12 Page 62 of 124

Table C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-26 01/04/13 <4 <5 <11 <5 <9 <5 <7 <4 <4 < 30 <9 02/01/13 <5 <5 < 11 <6 < 12 <5 < 10 <4 <5 < 26 <8 03/01/13 <7 <8 < 17 <8 < 21 <8 < 13 <7 <8 < 41 < 11 04/05/13 <5 <5 < 13 <5 < 12 <5 < 10 <5 <5 < 35 <7 05/03/13 <6 <6 < 14 <8 < 14 <6 < 11 <5 <6 < 43 < 10 05/17/13 <4 <5 < 12 <5 < 11 <5 <8 <4 <4 < 30 <8 05/31/13 <4 <5 <8 <2 <6 <3 <5 <2 <4 < 16 < 11 06/14/13 <7 <7 < 18 <8 < 16 <7 < 12 <6 <6 < 42 < 12 06/28/13 <7 <5 < 17 <7 < 16 <6 < 11 <5 <7 < 30 <9 07/12/13 <6 <6 < 16 <7 < 15 <6 < 10 <5 <6 <34 < 13 07/26/13 <7 <9 < 18 <9 < 14 <8 < 13 <6 <6 < 48 < 15

(-I 08/10/13 <7 <6 < 14 <9 < 15 <8 < 11 <5 <7 < 35 < 10 08123/13 <5 <7 < 15 <6 < 15 <6 < 10 <6 <6 < 35 < 14 09/06/13 <5 <5 < 13 <6 < 12 <6 <9 <4 <5 < 44 < 14 09/21/13 <6 <7 < 15 <8 < 15 <6 < 11 <5 <8 < 41 < 10 10/04/13 <7 <7 < 14 <6 < 15 <7 < 13 <6 <8 < 49 < 12 10/18/13 <7 <6 < 14 <8 < 14 <7 < 12 <5 <7 < 32 <5 11/01/13 <6 <8 < 22 < 10 < 19 <9 < 13 <7 <9 < 50 <9 12/06/13 <8 < 10 < 22 < 11 < 24 < 11 < 19 <8 <8 < 56 < 11 MEAN 0

0 I'J

Table C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED INTHE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/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 Broccoli leaves 07/29/13 <8 <8 < 23 < 11 < 21 < 9 < 16 < 33 <7 <9 < 67 < 17 Potatoes & Onions 07/29/13 <7 <7 <19 <9 <17 <8 < 13 < 30 <6 <8 < 59 < 16 MEAN - - - - - - - - - - -

Q-QUAD 1 Cabbage 07/29/13 <6 <6 < 15 < 7 < 14 < 7 < 11 < 25 < 5 < 6 < 52 < 12 Potatoes 07/29/13 <6 < 7 < 17 < 8 < 15 < 7 < 11 < 27 < 6 < 6 < 55 < 15 MEAN - - - - - - - - - - -

Q-QUAD 2 Cabbage 07/29/13 <7 <9 <19 <9 <18 <9 < 14 <35 <7 <9 <67 < 17 Potatoes 07/29/13 <4 <5 <13 <6 <11 <5 <9 <16 <4 <4 <33 <9 MEAN - - - - - - - - - - -

Q-QUAD 3 Beets 07/29/13 <8 < 10 < 22 < 10 < 19 < 10 < 18 < 42 < 8 < 10 < 81 < 17 Cabbage 07/29/13 < 10 < 11 < 25 < 11 < 23 < 12 < 19 < 43 < 9 < 10 < 80 < 27 MEAN Q-QUAD 4 Potatoes 07/29/13 <4 <5 <14 <6 <11 <5 <9 <18 <4 <5 <37 < 12 Rhubarb leaves 07/29/13 <8 <9 <20 <9 <17 <9 < 16 < 36 < 8 < 8 < 70 < 17 MEAN 10 co

Table C-IX.1 QUARTERLY OSLD RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN-MAR APR-JUN JUL-SEP OCT-DEC CODE +/- 2 S.D.

Q-01-1 19.2 + 1.6 19.1 20.2 18.3 19.0 Q-01-2 18.6 + 4.9 15.1 20.2 18.6 20.4 Q-02-1 20.0 + 2.5 20.0 21.6 18.5 20.0 Q-02-2 19.0 + 3.3 18.4 21.2 17.3 18.9 Q-03-1 18.1 +2.3 17.2 19.7 17.4 18.2 Q-03-2 17.8 +/- 2.6 17.7 19.3 16.2 18.1 Q-04-1 19.7 + 2.0 19.2 21.0 18.7 19.7 Q-04-2 20.7 +/- 1.9 20.5 21.7 19.5 21.1 Q-13-1 21.1 +/-2.8 19.9 23.1 20.3 21.0 Q-13-2 21.9 +/- 3.7 20.9 24.2 20.0 22.3 Q-16-1 19.1 +/- 2.6 18.6 20.8 17.7 19.1 Q-16-2 18.8 +/- 3.2 17.2 20.5 17.6 19.8 Q-37-1 21.9 +/- 4.8 20.3 25.4 20.8 20.9 Q-37-2 21.9 +/- 1.4 21.5 22.2 21.1 22.7 Q-38-1 22.2 +/- 5.0 20.3 25.9 21.5 21.2 Q-38-2 22.6 +/- 5.0 19.5 25.4 22.0 23.4 Q-41-1 21.6 +/- 4.5 18.8 23.2 20.8 23.7 Q-41-2 21.8 +/- 5.7 19.7 26.0 21.2 20.4 Q-42-1 23.0 +/- 5.0 20.6 26.2 21.6 23.7 Q-42-2 23.1 +/- 3.7 21.3 25.3 21.9 23.8 Q-101-1 19.7 +/- 2.6 18.7 20.7 18.5 20.9 Q-101-2 20.1 +/- 1.3 19.1 20.4 20.1 20.6 Q-102-1 20.5 +/- 1.5 19.7 21.5 20.6 20.3 Q-102-3 20.2 +/- 3.4 19.6 22.6 18.6 20.1 Q-103-1 19.0 +/- 5.7 18.2 23.0 16.2 18.6 Q-103-2 19.0 +/- 3.5 18.4 21.4 17.2 19.1 Q-104-1 19.3 +/- 1.5 19.5 20.2 18.4 19.1 Q-104-2 20.2 +/- 4.5 19.2 23.4 18.2 20.1 Q-105-1 19.9 +/- 2.9 19.1 21.7 18.4 20.5 Q-105-2 19.9 +/- 4.5 19.0 23.1 17.9 19.7 Q-106-2 20.0 +/- 1.3 19.4 20.3 19.5 20.7 Q-106-3 19.3 +/- 2.4 18.0 20.4 18.6 20.3 Q-107-2 19.7 +/- 3.1 18.6 21.8 19.8 18.5 Q-107-3 19.8 +/- 2.3 19.7 21.4 18.6 19.5 Q-108-1 19.0 +/- 1.6 19.5 (1) 18.1 19.4 Q-108-2 19.5 +/- 3.6 17.7 21.0 18.2 21.1 Q-109-1 20.6 +/- 1.2 19.8 21.1 20.3 21.0 Q-109-2 19.6 +/- 4.7 18.8 22.8 17.2 19.7 Q-111-1 20.1 +/- 2.7 18.7 20.7 19.2 21.6 Q-111-2 19.7 +/- 0.7 19.2 20.1 19.8 19.7 Q-112-1 19.2 +/- 6.1 15.1 (1) 22.4 19.6 19.7 Q-112-2 19.9 +/- 4.3 18.1 22.5 18.2 20.9 Q-113-1 19.4 +/- 3.7 17.8 21.2 17.9 20.8 Q-113-2 19.2 +/- 2.3 18.6 20.3 17.8 19.9 Q-114-1 19.2 +/- 2.0 18.4 20.6 19.0 18.6 Q-114-2 20.0 +/- 2.6 20.2 21.6 18.5 19.5 Q-115-1 19.6 +/- 2.0 18.5 20.6 19.0 20.2 Q-115-2 19.2 +/- 3.8 19.2 21.7 17.1 18.6 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-15 Page 65 of 124

Table C-IX.1 QUARTERLY OSLD RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE +/- 2 S.D.

Q-116-1 21.5 +/- 4.1 20.0 24.5 20.9 20.5 Q-116-3 20.8 +/- 5.1 19.4 23.9 18.2 21.8 Q-201-1 20.7 +/- 3.9 19.6 23.6 19.8 19.6 Q-201-2 21.3 +/- 4.2 20.3 24.3 19.6 20.9 Q-202-1 19.7 +/- 1.4 19.3 20.4 18.9 20.2 Q-202-2 20.4 +/- 3.7 22.8(1) 20.9 18.5 19.5 Q-203-1 21.1 +/- 2.7 19.5 22.5 20.5 21.8 Q-203-2 23.9 +/- 2.7 22.8 24.9 22.7 25.2 Q-204-1 21.8 +/- 2.8 20.2 (1) 22.8 22.3 Q-204-2 23.7 +/- 3.3 22.2 25.8 24.2 22.6 Q-205-1 21.9 +/- 4.0 19.6 23.1 20.8 23.9 Q-205-4 23.5 +/- 2.8 22.1 25.3 22.6 23.8 Q-206-1 20.7 +/- 0.6 20.9 20.2 20.8 20.7 Q-206-2 19.8 +/- 4.4 18.8 22.7 17.6 19.9 Q-207-1 20.7 +/- 3.0 19.6 21.7 19.2 22.2 Q-207-4 22.4 +/- 3.9 21.2 25.2 21.0 22.3 Q-208-1 20.8 +/- 2.8 20.3 22.8 20.0 19.9 Q-208-2 22.8 +/- 4.1 21.0 24.9 21.1 24.3 Q-209-1 21.0 +/- 2.7 20.1 22.8 19.8 21.3 Q-209-4 22.3 +/- 4.2 22.6 24.9 19.8 21.8 Q-210-1 23.3 +/- 2.5 22.3 25.1 22.8 22.8 Q-210-4 22.2 +/- 2.1 21.9 (1) 21.4 23.4 Q-210-5 19.2 +/- 2.9 18.1 21.0 18.0 19.8 Q-211-1 24.6 +/- 4.0 21.9 26.7 24.6 25.1 Q-211-2 23.8 +/- 3.4 21.9 25.4 22.9 25.1 Q-212-1 21.6 +/- 0.9 21.4 (1) 21.2 22.1 Q-212-2 20.2 +/- 2.1 19.7 21.4 19.0 20.7 Q-213-1 20.1 +/- 3.7 19.2 21.4 18.0 21.9 Q-213-2 19.6 +/- 1.1 18.9 20.2 19.6 19.8 Q-214-1 21.0 +/- 3.1 19.9 22.7 19.4 21.8 Q-214-2 21.4 +/- 3.3 21.5 23.7 19.8 20.7 Q-215-1 19.9 +/- 1.7 18.6 20.3 20.0 20.5 Q-215-2 22.1 +/- 5.0 21.5 25.8 20.5 20.7 Q-216-1 22.2 +/- 2.7 21.4 23.4 20.6 23.2 Q-216-2 21.4 +/- 1.2 22.1 20.9 20.9 21.6 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16 Page 66 of 124

TABLE C-IX.2 MEAN QUARTERLY OSLD RESULTS FOR THE INNER RING, OUTER RING, OTHER, AND CONTROL LOCATION FOR QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATION OF THE STATION DATA COLLECTION INNER RING OUTER RING OTHER CONTROL PERIOD +/- 2 S.D.

JAN-MAR 18.8 +/- 1.9 20.7 +/- 2.7 19.1 +/- 3.1 21.0 +/- 1.0 APR-JUN 21.6 +/- 2.4 23.1 +/- 3.9 22.3 +/- 4.5 25.8 +/- 1.3 JUL-SEP 18.7 +/- 2.2 20.6 +/- 3.4 19.3 +/- 3.4 21.8 +/- 0.4 OCT-DEC 20.0 +/- 1.8 21.9 +/- 3.4 20.6 +/- 3.3 23.8 +/- 0.1 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF MILLIREM/QUARTER LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/- 2 S.D.

INNER RING 119 15.1 24.5 19.8 +/- 3.1 OUTER RING 129 17.6 26.7 21.5 +/- 3.9 OTHER 72 15.1 26.0 20.3 t 4.4 CONTROL 8 20.6 26.2 23.1 +/- 4.0 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-1 14-1, Q-1 14-2, Q-1 15-1, Q-1 15-2, Q-1 16-1, Q-1 16-3 OUTER RING STATIONS - Q-201-1, Q-201-2, Q-202-1, Q-202-2, Q-203-1, Q-203-2, Q-204-1, Q-204-2, Q-205-1, Q-205-4, Q-206-1, Q-206-2, Q-207-1, Q-207-4, Q-208-1, Q-208-2, Q-209-1, Q-209-4, Q-210-1, Q-210-4, Q-210-5, Q-211-1, Q-211-2, Q-212-1, Q-212-2, Q-213-1, Q-213-2, Q-214-1, Q-214-2, Q-215-1, Q-215-2, Q-216-1, Q-216-2 OTHER STATIONS - Q-01-1, Q-01-2, Q-02-1, Q-02-2, Q-03-1, Q-03-2, Q-04-1, Q-04-2, Q-13-1, Q-13-2, Q-16-1, Q-16-2, Q-37-1, Q-37-2, Q-38-1, Q-38-2, Q-41-1, Q-41-2 CONTROL STATIONS - Q-42-1, Q-42-2 C-17 Page 67 of 124

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

Collected in the Vicinity of QCNPS, 2000 - 2013 Q-33 Cordova 12.0 10.0 8.0

-I C., 6.0 4.0 2.0 0.0 !

01-01-00 10-19-02 08-06-05 05-24-08 03-12-11 12-28-13 Q-34 (C) Camanche 12.0 10.0 8.0

-I 6.0 a.

4.0 2.0 0.0 I 01-01-00 10-19-02 08-06-05 05-24-08 03-12-11 12-28-13 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C- 18 Page 68 of 124

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

Collected in the Vicinity of QCNPS, 2000 - 2013 Q-33 Cordova 500 400 300 C.)

0.

200 100 0 I 01-01-00 10-19-02 08-06-05 05-24-08 03-12-11 12-28-13 Q-34 (C) Camanche 500 400 300

-C 0.

200 100 0 -

01-01-00 10-19-02 08-06-05 05-24-08 03-12-11 12-28-13 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-19 Page 69 of 124

FIGURE C-3 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2013 Q-35 McMillan Well 500 400 300

-J a.

200 100 0 1 -

12-31-99 10-19-02 08-07-05 05-26-08 03-15-11 01-01-14 Q-36 Cordova Well 500 400 300

-J (V

200 100 0 1 12-31-99 10-19-02 08-07-05 05-26-08 03-15-11 01-01-14 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-20 Page 70 of 124

FIGURE C-4 Air Particulates - Gross Beta- Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2013 Q-01 Onsite No. I 70.0 60.0 50.0 40.0 CL uJ 30.0 9w 40 20.0 10.0 0.0 01-07-00 10-25-02 08-12-05 05-30-08 03-18-11 01-03-14 Q-02 Onsite No. 2 70.0 60.0 50.0 E

40.0 a.

CL 30.0 LU a

20.0 10.0 0.0 01-07-00 10-25-02 08-12-05 05-30-08 03-18-11 01-03-14 C-21 Page 71 of 124

FIGURE C-5 Air Particulates - Gross Beta- Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2013 Q-03 Onsite No. 3 60.0 50.0 40.0 E

CL 30.0 9

20.0 10.0 0.0 -

01-07-00 10-25-02 08-12-05 05-30-08 03-18-11 01-03-14 Q-04 Nitrin 60.0 50.0 40.0 E

M 30.0 9

wj 20.0 0

10.0 0.0 I 01-07-00 10-25-02 08-12-05 05-30-08 03-18-11 01-03-14 C-22 Page 72 of 124

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.)

E. 40.0 9 30.0 w~

Q 20.0 10.0 0.0 1 I I I I I 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 124

FIGURE C-7 Air Particulates - Gross Beta- Stations Q-13 and Q-16 Collected in the Vicinity of QCNPS, 2005 - 2013 Q-13 Princeton 60.0 50.0 40.0 C,

a.

30.0 9mJ E

20.0 10.0 0.0 07-08-05 03-20-07 11-29-08 08-11-10 04-22-12 01-02-14 Q-16 Low Moor 60.0 50.0 40.0 30.0 20.0 10.0 0.0 07-08-05 03-20-07 11-29-08 08-11-10 04-22-12 01-02-14 AIR PARTICULATE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 C-24 Page 74 of 124

FIGURE C-8 Air Particulates - Gross Beta- Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2013 Q-37 Meredosia Road 60.0 50.0 40.0 m

a.

CL) 30.0 9

0=

20.0 10.0 0.0 07-08-05 03-20-07 11-29-08 08-11-10 04-22-12 01-02-14 Q-38 Fuller Road 60.0 50.0 40.0 E

C.,

30.0 9

III Q 20.0 10.0 0.0 07-08-05 03-20-07 11-29-08 08-11-10 04-22-12 01-02-14 AIR PARTICULATE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 C-25 Page 75 of 124

FIGURE C-9 Air Particulates - Gross Beta- Stations Q-41 and Q-42 (C)

Collected in the Vicinity of QCNPS, 2009 - 2013 Q-41 Camanche 60.0 50.0 40.0 CL~

30.0 LU 20.0 10.0 0.0 01-03-09 01-03-10 01-03-11 01-03-12 01-02-13 01-02-14 Q-42 LeClaire (Control) 60.0 50.0 E 40.0

a. 30.0 C',

OL 9J m

w 20.0 10.0 0.01-12-31-10 08-07-11 03-13-12 10-18-12 05-25-13 12-30-13 C-26 Page 76 of 124

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM Page 77 of 124

Intentionally left blank Page 78 of 124

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2013 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

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

March 2013 E10477 Milk Sr-89 pCi/L 120 99.7 1.20 A Sr-90 pCi/L 9.21 11.0 0.84 A E10478 Milk 1-131 pCi/L 87.1 100 0.87 A Ce-141 pCi/L 186 187 0.99 A Cr-51 pCi/L 463 472 0.98 A Cs-134 pCi/L 201 214 0.94 A Cs-137 pCi/L 262 266 0.98 A Co-58 pCi/L 200 208 0.96 A Mn-54 pCi/L 215 208 1.03 A Fe-59 pCi/L 266 252 1.06 A Zn-65 pCi/L 311 301 1.03 A Co-60 pCi/L 384 400 0.96 A E10480 AP Ce-141 pCi 95.3 95.6 1.00 A Cr-51 pCi 264 241 1.10 A Cs-1 34 pCi 123 109 1.13 A Cs-1 37 pCi 142 136 1.04 A Co-58 pCi 112 106 1.06 A Mn-54 pCi 115 106 1.08 A Fe-59 pCi. 139 129 1.08 A Zn-65 pCi 163 153 1.07 A Co-60 pCi 212 204 1.04 A E10479 Charcoal 1-131 pCi 90.1 92.6 0.97 A E10481 Water Fe-55 pCi/L 1840 1890 0.97 A June 2013 E10564 Milk Sr-89 pCi/L 110 95.0 1.16 A Sr-90 pCi/L 15.8 17.0 0.93 A E10545 Milk 1-131 pCi/L 92.6 95.5 0.97 A Ce-141 pCi/L 83.1 90.4 0.92 A Cr-51 pCi/L 253 250 1.01 A Cs-134 pCi/L 118 125 0.94 A Cs-1 37 pCi/L 143 151 0.95 A Co-58 pCi/L 87.1 94.0 0.93 A Mn-54 pCi/L 171 172 0.99 A Fe-59 pCi/L 125 120 1.04 A Zn-65 pCi/L 220 217 1.01 A Co-60 pCi/L 169 175 0.97 A E10547 AP Ce-141 pCi 56.8 56.7 1.00 A Cr-51 pCi 168 157 1.07 A Cs-134 pCi 85.2 78.4 1.09 A Cs-137 pCi 101 94.6 1.07 A Co-58 pCi 62.7 58.9 1.06 A Mn-54 pCi 125 108 1.16 A Fe-59 pCi 85.7 75.0 1.14 A Zn-65 pCi 169 136 1.24 W Co-60 pCi 116 110 1.05 A E10546 Charcoal 1-131 pCi 86.5 89.7 0.96 A D-1 Page 79 of 124

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2013 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

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

June 2013 E10549 Water Fe-55 pCi/L 1610 1610 1.00 A September2013 E10646 Milk Sr-89 pCi/L 63.9 96.0 0.67 N (1)

Sr-90 pCi/L 8.88 13.2 0.67 N (1)

E10647 Milk 1-131 pCi/L 93.9 98.3 0.96 A Ce-141 pCi/L NA (2)

Cr-51 pCi/L 272 277 0.98 A Cs-134 pCi/L 150 172 0.87 A Cs-1 37 pCi/L 125 131 0.95 A Co-58 pCi/L 105 108 0.97 A Mn-54 pCi/L 138 139 0.99 A Fe-59 pCi/L 125 130 0.96 A Zn-65 pCi/L 264 266 0.99 A Co-60 pCi/L 187 196 0.95 A E10672 AP Ce-141 pCi NA (2)

Cr-51 pCi 208 223 0.93 A Cs-1 34 pCi 143 139 1.03 A Cs-1 37 pCi 106 105 1.01 A Co-58 pCi 97.0 86.5 1.12 A Mn-54 pCi 116 112 1.04 A Fe-59 pCi 98.6 105 0.94 A Zn-65 pCi 219 214 1.02 A Co-60 pCi 166 158 1.05 A E10648 Charcoal 1-131 pCi 76.3 71.7 1.06 A E10673 Water Fe-55 pCi/L 1790 1690 1.06 A December2013 E10774 Milk Sr-89 pCi/L 97.3 93.8 1.04 A Sr-90 pCi/L 13.3 12.9 1.03 A E10775 Milk 1-131 pCi/L 89.7 96.1 0.93 A Ce-141 pCi/L 99.8 110 0.91 A Cr-51 pCi/L 297 297 1.00 A Cs-134 pCi/L 129 142 0.91 A Cs-137 pCi/L 126 126 1.00 A Co-58 pCi/L 116 112 1.04 A Mn-54 pCi/L 167 168 0.99 A Fe-59 pCi/L 117 110 1.06 A Zn-65 pCi/L 757 741 1.02 A Co-60 pCi/L 141 147 0.96 A E10777 AP Ce-141 pCi 85.1 88.0 0.97 A Cr-51 pCi 278 238 1.17 A Cs-134 pCi 123 114 1.08 A Cs-137 pCi 102 101 1.01 A Co-58 pCi 84.4 89.9 0.94 A Mn-54 pCi 132 135 0.98 A Fe-59 PCi 101 88.3 1.14 A Zn-65 pCi 506 595 0.85 A Co-60 pCi 118 118 1.00 A D-2 Page 80 of 124

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2013 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

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

December 2013 E10776 Charcoal 1-131 pCi 84.7 80.5 1.05 A E10778 Water Fe-55 pCi/L 2010 1910 1.05 A (1) Milk, Sr-89/90 - The failure was due to analyst error. No client samples were affected by this failure. NCR 13-15 (2) The sample was not spiked with Ce-14 1.

(a) Teledyne Brown Engineeringreported result.

(b) The Analytics known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation.

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

(d) Analytics evaluationbased on TBE internalQC limits: A= Acceptable, reportedresult falls within ratio limits of 0.80-1.20.

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

D-3 Page 81 of 124

TABLE D-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2013 (PAGE 1 OF 1)

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

May 2013 RAD-93 Water Sr-89 pCi/L 48.3 41.3 31.6 -48.4 A Sr-90 pCi/L 19.3 23.9 17.2 -28.0 A Ba-1 33 pCi/L 81.9 82.1 69.0 - 90.3 A Cs-134 pCi/L 40.9 42.8 34.2 - 47.1 A Cs-1 37 pCi/L 44.0 41.7 37.0 - 48.8 A Co-60 pCi/L 61.9 65.9 59.3 - 75.0 A Zn-65 pCi/L 202 189 170-222 A Gr-A pCi/L 34.2 40.8 21.1 -51.9 A Gr-B pCi/L 18.0 21.6 13.0 -29.7 A 1-131 pCi/L 23.8 23.8 19.7 -28.3 A U-Nat pCi/L 60.4 61.2 49.8 - 67.9 A H-3 pCi/L 3970 4050 3450 - 4460 A MRAD-1 8 Filter Gr-A pCi/filter Lost during processing November 2013 RAD-95 Water Sr-89 pCi/L 25.5 21.9 14.4 - 28.2 A Sr-90 pCi/L 14.3 18.1 12.8-21.5 A Ba-133 pCi/L 57.2 54.2 44.7 - 59.9 A Cs-134 pCi/L 83.3 86.7 71.1 -95.4 A Cs-137 pCi/L 201 206 185 -228 A Co-60 pCi/L 104 102 91.8 - 114 A Zn-65 pCi/L 361 333 300 - 389 A Gr-A pCi/L 29.5 42.8 22.2 - 54.3 A Gr-B pCi/L 30.1 32.2 20.8 - 39.9 A 1-131 pCi/L 23.1 23.6 19.6 -28.0 A U-Nat pCi/L 5.53 6.24 4.70 - 7.44 A H-3 pCi/L 17650 17700 15500 - 19500 A MRAD-1 9 Filter Gr-A pCi/filter 33.0 83.0 27.8-129 A (a) Teledyne Brown Engineeringreported result.

(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric end/or volumetric measurements made duringstandardpreparation.

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

D-4 Page 82 of 124

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

TELEDYNE BROWN ENGINEERING, 2013 (PAGE 1 OF 2)

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

March 2013 13-MaW28 Water Cs-134 Bq/L 21.0 24.4 17.1 -31.7 A Cs-1 37 Bq/L 0.0446 (1) A Co-57 Bq/L 28.3 30.9 21.6-40.2 A Co-60 Bq/L 18.2 19.56 13.69 - 25.43 A H-3 Bq/L 506 507 355-659 A Mn-54 Bq/L 25.7 27.4 19.2 - 35.6 A K-40 Bq/L 2.09 (1) A Sr-90 Bq/L 10.5 10.5 7.4- 13.7 A Zn-65 Bq/L 29.2 30.4 21.3-39.5 A 13-GrW28 Water Gr-A Bq/L 2.74 2.31 0.69 - 3.93 A Gr-B Bq/L 15.6 13.0 6.5- 19.5 A 13-MaS28 Soil Cs-134 Bq/kg 859 887 621-1153 A Cs-1 37 Bq/kg 633 587 411 -763 A Co-57 Bq/kg 0.256 (1) A Co-60 Bq/kg 738 691 484 - 898 A Mn-54 Bq/kg 0.671 (1) A K-40 Bq/kg 714 625.3 437.7 - 812.9 A Sr-90 Bq/kg 442 628 440-816 W Zn-65 Bq/kg 1057 995 697-1294 A 13-RdF28 AP Cs-1 34 Bq/sample 1.73 1.78 1.25-2.31 A Cs-137 Bq/sample 2.73 2.60 1.82-3.38 A Co-57 Bq/sample 2.38 2.36 1.65-3.07 A Co-60 Bq/sample 0.0302 (1) A Mn-54 Bq/sample 4.36 4.26 2.98 - 5.54 A Sr-90 Bq/sample 1.43 1.49 1.04 - 1.94 A Zn-65 Bq/sample 3.14 3.13 2.19-4.07 A 13-GrF28 AP Gr-A Bq/sample 0.767 1.20 0.36- 2.04 A Gr-B Bq/sample 0.871 0.85 0.43- 1.28 A 13-RdV28 Vegetation Cs-1 34 Bq/sample -0.197 (1) A Cs-137 Bq/sample 7.39 6.87 4.81 - 8.93 A Co-57 Bq/sample 9.87 8.68 6.08 - 11.28 A Co-60 Bq/sample 6.08 5.85 4.10 -7.61 A Mn-54 Bq/sample -0.0104 (1) A Sr-90 Bq/sample 1.28 1.64 1.15-2.13 W Zn-65 Bq/sample 6.84 6.25 4.38 -8.13 A September 2013 13-MaW29 Water Cs-134 Bq/L 29.1 30.0 21.0-39.0 A Cs-137 Bq/L 34.5 31.6 22.1-41.1 A Co-57 Bq/L 0.0358 (1) A Co-60 Bq/L 24.6 23.58 16.51 - 30.65 A H-3 Bq/L 2.45 (1) A Mn-54 Bq/L 0.0337 (1) A K-40 Bq/L 0.193 (1) A Sr-90 Bq/L 9.12 7.22 5.05 - 9.39 W Zn-65 Bq/L 38.1 34.6 24.2 -45.0 A 13-GrW29 Water Gr-A Bq/L 1.13 0.701 0.210 - 1.192 A Gr-B Bq/L 7.61 5.94 2.97 - 8.91 A D-5 Page 83 of 124

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

TELEDYNE BROWN ENGINEERING, 2013 (PAGE 2 OF 2)

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

September 2013 13-MaS29 Soil Cs-134 Bq/kg 1150 1172 820-1524 A Cs-1 37 Bq/kg 1100 977 684-1270 A Co-57 Bqlkg 670 (1) N (2)

Co-60 Bq/kg 502 451 316-586 A Mn-54 Bq/kg 758 674 472-876 A K-40 Bq/kg 796 633 443-823 W Sr-90 Bq/kg 664 460 322-598 N (2)

Zn-65 Bq/kg 210 (1) N (2) 13-RdF29 AP Cs-1 34 Bq/sample -0.570 (1) N (2)

Cs-137 Bq/sample 2.85 2.7 1.9-3.5 A Co-57 Bq/sample 3.30 3.4 2.4 - 4.4 A Co-60 Bq/sample 2.41 2.3 1.6-3.0 A Mn-54 Bq/sample 3.65 3.5 2.5-4.6 A Sr-90 Bq/sample 1.40 1.81 1.27 - 2.35 W Zn-65 Bq/sample 2.90 2.7 1.9-3.5 A 13-GrF29 AP Gr-A Bq/sample 0.872 0.9 0.3-1.5 A Gr-B Bq/sample 1.57 1.63 0.82-2.45 A 13-RdV29 Vegetation Cs-1 34 Bq/sample 5.29 5.20 3.64 -6.76 A Cs-1 37 Bq/sample 7.48 6.60 4.62 - 8.58 A Co-57 Bq/sample 0.0129 (1) A Co-60 Bq/sample 0.0523 (1) A Mn-54 Bq/sample 8.78 7.88 5.52 - 10.24 A Sr-90 Bq/sample 1.63 2.32 1.62 - 3.02 W (2)

Zn-65 Bq/sample 3.18 2.63 1.84-3.42 W (1) Falsepositive test.

(2) Soil, Co-57 & Zn-65 identified by gamma software as not detected, MAPEP evaluated as failing the false positive test. A large concentrationof Eu-152 was spiked into the sample, causinginterference in the analysis. Gamma software recognized the interference and identified them as not detected. MAPEP does not allow clients to enter non-detect designation.NCR 13-14 Soil, Sr incorrect results were submitted to MAPEP. Actual result was 332 bq/kg, which is with the acceptance range. NCR 13-14 AP, Cs- 134 - MAPEP evaluated the -0.570 as a failed false positive test. No client samples were affected by these failures. NCR 13-14 Vegetation, Sr it appearsthat the carrierwas double spiked into the sample, resulting in the low activity for this sample. NCR 13-14 (a) Teledyne Brown Engineering reportedresult.

(b) The MAPEP known value is equalto 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurements made duringstandardpreparation.

(c) DOEIMAPEPevaluation: A=acceptable, W=acceptablewith warning, N=not acceptable.

D-6 Page 84 of 124

TABLE D-4 ERA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2013 (Page 1 of 1)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result (b) Result (c) Limits Acceptance ERW-1593 04/08/13 Sr-89 43.6 +/- 4.3 41.30 31.6 -48.4 Pass ERW-1593 04/08/13 Sr-90 23.2 +/- 1.7 23.90 17.2 - 28.0 Pass ERW-1 596 04/08/13 Ba-133 74.80 4.00 82.10 69.00 90.30 Pass ERW-1 596 04/08/13 Co-60 65.50 3.42 65.90 59.30 75.00 Pass ERW-1 596 04/08/13 Cs-1 34 41.10 3.47 42.80 34.20 47.10 Pass ERW-1 596 04/08/13 Cs-1 37 42.30 4.03 41.70 37.00 48.80 Pass ERW-1 596 04/08/13 Zn-65 200.3 +/- 10.1 189.0 170.0 - 222.0 Pass ERW-1598 04/08/13 Gr. Alpha 34.30 1.98 40.80 21.10 51.90 Pass ERW-1 598 04/08/13 Gr. Beta 18.70 0.98 21.60 13.00 29.70 Pass ERW-1600 04/08/13 1-131 23.00 +/- 1.10 23.80 19.70 - 28.30 Pass ERW-1600 04/08/13 1-131(Gamma) 23.48 +/- 9.44 23.80 19.70 +/- 28.30 Pass ERW-1606 04/08/13 H-3 4041 +/- 194 4050 3450 - 4460 Pass ERW-6009 10/07/13 Sr-89 22.00 2.80 21.90 14.40 28.20 Pass ERW-6009 10/07/13 Sr-90 17.10 2.55 18.10 12.80 21.50 Pass ERW-6012 10/07/13 Ba-133 48.20 4.29 54.20 44.70 59.90 Pass ERW-6012 10/07/13 Co-60 100.8 +/- 4.7 102.0 91.8-114.0 Pass ERW-6012 10/07/13 Cs-1 34 87.30 4.35 86.70 71.10 95.40 Pass ERW-6012 10/07/13 Cs-1 37 199.6 +/- 7.4 206.0 185.0 - 228.0 Pass ERW-6012 10/07/13 Zn-65 356.2 +/- 13.2 333.0 300.0 - 389.0 Pass ERW-6015 10/07/13 Gr. Alpha 30.70 11.90 42.80 22.20 54.30 Pass ERW-6015 10/07/13 Gr. Beta 25.70 6.48 32.20 20.80 39.90 Pass ERW-6019 10/07/13 1-131 22.50 1.01 23.60 19.60 28.00 Pass ERW-6024 10/07/13 H-3 18397 695 17700 15500 19500 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b 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-7 Page 85 of 124

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

ENVIRONMENTAL, INC., 2013 (Page 1 of 2)

Concentration (a)

Known Control Lab Code (b) Date Analysis Laboratory result Activity Limits (c) Acceptance MAAP-738 02/01/13 Co-57 2.58 +/- 0.06 2.36 1.65 - 3.07 Pass MAAP-738 02/01/13 Co-60 0.01 +/- 0.03 0.00 0.00 -0.10 Pass MAAP-738 02/01/13 Cs-1 34 1.82 +/- 0.13 1.78 1.25 - 2.31 Pass MAAP-738 02/01/13 Cs-1 37 2.93 +/- 0.10 2.60 1.82 -3.38 Pass MAAP-738 02/01/13 Mn-54 4.87 +/- 0.13 4.26 2.98 - 5.54 Pass MAAP-738 02/01/13 Sr-90 1.39 +/- 0.14 1.49 1.04-1.94 Pass MAAP-738 02/01/13 Zn-65 3.84 +/- 0.20 3.13 2.19 -4.07 Pass MAAP-738 d 02/01/13 Gr. Alpha 0.14 +/- 0.03 1.20 0.36 - 2.04 Fail (1)

MAAP-738 02/01/13 Gr. Beta 0.93 +/- 0.06 0.85 0.43 - 1.28 Pass MAW-806 02/01/13 Co-57 31.20 0.40 30.90 21.60 40.20 Pass MAW-806 02/01/13 Co-60 19.70 +/- 0.30 16.56 13.69 - 25.43 Pass MAW-806 02/01/13 Cs-134 23.20 +/- 0.50 24.40 17.10 - 31.70 Pass MAW-806 02/01/13 Cs-1 37 0.03 +/- 0.12 0.00 0.00 - 1.00 Pass MAW-806 02/01/13 Fe-55 34.00 +/- 3.30 44.00 30.80 - 57.20 Pass MAW-806 02/01/13 H-3 511.60 +/- 12.50 507.00 355.00 - 659.00 Pass MAW-806 02/01/13 K-40 2.20 +/- 0.90 0.00 0.00 - 5.00 Pass MAW-806 02/01/13 Mn-54 27.60 +/- 0.50 27.40 19.20 - 35.60 Pass MAW-806 02/01/13 Sr-90 9.30 +/- 0.80 10.50 7.40 - 13.70 Pass MAW-806 02/01/13 Zn-65 31.60 +/- 0.80 30.40 21.30 - 39.50 Pass MAW-811 02/01/13 Gr. Alpha 1.87 +/- 0.09 2.31 0.69 - 3.93 Pass MAW-811 02/01/13 Gr. Beta 13.04 +/- 0.13 13.00 6.50 - 19.50 Pass MASO-739 02/01/13 Co-57 0.60 +/- 0.50 0.00 0.00 - 5.00 Pass MASO-739 02/01/13 Co-60 739.20 +/- 28.50 691.00 484.00 - 898.00 Pass MASO-739 02/01/13 Cs-134 863.30 +/- 34.10 887.00 621.00 - 1153.00 Pass MASO-739 02/01/13 Cs-137 661.80 +/- 25.70 587.00 411.00 - 763.00 Pass MASO-739 02/01/13 K-40 745.80 +/- 33.30 625.30 437.70 - 812.90 Pass MASO-739 02/01/13 Mn-54 1.10 +/- 1.00 0.00 0.00 - 5.00 Pass MASO-739 02/01/13 Zn-65 1109.60 +/- 44.10 995.00 697.00 - 1294.00 Pass MASO-744 e 02/01/13 Sr-90 408.40 +/- 14.00 628.00 440.00 - 816.00 Fail (2)

MAVE-747 02/01/13 Co-57 10.37 +/- 0.17 8.68 6.08-11.28 Pass MAVE-747 02/01/13 Co-60 6.48 +/- 0.17 5.85 4.10 -7.61 Pass MAVE-747 02/01/13 Cs-134 0.02 +/- 0.04 0.00 0.00 -0.10 Pass MAVE-747 02/01/13 Cs-1 37 7.79 +/- 0.21 6.87 4.81 - 8.93 Pass MAVE-747 02/01/13 Mn-54 0.00 +/- 0.05 0.00 0.00 -0.10 Pass MAVE-747 02/01/13 Zn-65 7.29 +/- 0.33 6.25 4.38 -8.13 Pass MASO-5043 f 08/01/13 Co-57 699.60 +/- 3.90 0.00 0.00 - 5.00 Fail (3)

MASO-5043 08/01/13 Cs-134 1191.70 +/- 23.00 1172.00 820.00 - 1524.00 Pass MASO-5043 08/01/13 Cs-137 1072.00 +/- 5.10 977.00 684.00 - 1270.00 Pass MASO-5043 08/01/13 K-40 760.00 +/- 16.20 633.00 443.00 - 823.00 Pass MASO-5043 08/01/13 Mn-54 753.80 +/- 4.90 674.00 472.000 - 876.000 Pass D-8 Page 86 of 124

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

ENVIRONMENTAL, INC., 2013 (Page 2 of 2)

Concentration (a)

Known Control Lab Code (b) Date Analysis Laboratory result Activity Limits (c) Acceptance MASO-5043 08/01/13 Sr-90 383.90 +/- 14.50 460.00 322.00 - 598.00 Pass MASO-5043 08/01/13 Zn-65 -351.50 +/- 5.50 0.00 0.00 - 0.00 Pass MAW-5094 08/01/13 Co-57 0.01 +/- 0.09 0.00 0.00 - 5.00 Pass MAW-5094 08/01/13 Co-60 23.20 +/- 0.32 23.58 16.51 - 30.65 Pass MAW-5094 08/01/13 Cs-134 27.60 +/- 0.58 30.40 21.00 - 39.00 Pass MAW-5094 08/01/13 Cs-137 32.31 +/- 0.52 31.60 22.10 -41.10 Pass MAW-5094 08/01/13 Fe-55 39.20 +/- 3.50 53.30 37.30 - 69.30 Pass MAW-5094 08/01/13 Gr. Alpha 0.54 +/- 0.05 0.70 0.21 -1.19 Pass MAW-5094 08/01/13 Gr. Beta 5.85 +/- 0.09 5.94 2.97 - 8.91 Pass MAW-5094 08/01/13 H-3 1.20 +/- 3.00 0.00 0.00 - 5.00 Pass MAW-5094 08/01/13 K-40 2.22 +/- 0.90 0.00 0.00 - 5.00 Pass MAW-5094 08/01/13 Mn-54 0.010 +/- 0.11 0.00 0.00 - 5.00 Pass MAW-5094 08/01/13 Sr-90 6.40 +/- 0.60 7.22 5.05 - 9.39 Pass MAW-5094 08/01/13 Zn-65 35.30 +/- 0.90 34.60 24.20 - 45.00 Pass MAVE-5046 08/01/13 Co-57 0.01 +/- 0.03 0.00 0.00 - 0.00 Pass MAVE-5046 08/01/13 Co-60 0.00 +/- 0.04 0.00 0.00 - 0.00 Pass MAVE-5046 08/01/13 Cs-1 34 5.71 +/- 0.23 5.20 3.64 - 6.76 Pass MAVE-5046 08/01/13 Cs-1 37 7.64 +/- 0.20 6.60 4.62 - 8.58 Pass MAVE-5046 08/01/13 Mn-54 9.08 +/- 0.24 7.88 5.52 - 10.24 Pass MAVE-5046 08/01/13 Zn-65 2.92 +/- 0.25 2.63 1.84 -3.42 Pass MAAP-5046 08/01/13 Co-57 3.48 +/- 0.14 3.40 1.90 - 3.50 Pass MAAP-5046 08/01/13 Co-60 2.44 +/- 0.08 3.40 1.60 - 3.00 Pass MAAP-5046 08/01/13 Cs-1 34 0.01 +/- 0.03 0.00 0.02 - 0.04 Pass MAAP-5046 08/01/13 Cs-1 37 3.09 +/- 0.13 2.70 1.90 -3.50 Pass MAAP-5046 08/01/13 Gr. Alpha 0.28 +/- 0.04 0.90 0.27 -1.53 Pass MAAP-5046 08/01/13 Gr. Beta 1.90 +/- 0.08 1.63 0.82 - 2.45 Pass MAAP-5046 08/01/13 Mn-54 3.95 +/- 0.12 3.50 2.50 - 4.60 Pass MAAP-5046 08/01/13 Sr-90 1.69 +/- 4.10 1.81 1.27 - 2.35 Pass MAAP-5046 08/01/13 Zn-65 3.27 +/- 0.18 2.70 2.50 - 4.60 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.

(1) The filter was recounted overnight, no significant alpha activity could be detected.

(2) The sample was reanalyzed using additional fuming nitric separations. Result of reanalysis: 574.4 +/- 35.2 Bq/kg.

(3) Interference from Eu-1 52 resulted in misidentification of Co-57.

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APPENDIX E ERRATA DATA Page 89 of 124

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Due to an incorrect setting on gamma detector 08, 3.29 rather than 4.66 was used in the MDC calculation. Nonconformance 13-07 was initiated and corrective actions have been implemented to address this issue. All samples counted on detector 08 were reprocessed using the correct calculation. As a result, all MDCs for these samples have increased by 41.6%. The previously reported activities and uncertainties were not affected. In some cases, the increased MDC resulted in missed LLDs. All samples with MDCs affected by this issue follow. The samples with missed LLDs are shown in the table for 2012, and 2013. All other required LLDs were met.

E-1 Page 91 of 124

2012 START END REQUIRED REVISED CLIENT ID DATE DATE MATRIX NUCLIDE MDC MDC UNITS 1Q12 Q-01 12/30/11 03/30/12 Air Particulate ....

1Q12 Q-02 12/30/11 03/30/12 Air Particulate ....

1Q12 Q-41 12/30/11 03/30/12 Air Particulate ....

Q-26 01/06/12 01/06/12 Milk ....

Q-35 01/13/12 01/13/12 Ground Water 1-131 <15 <19.28 pCi/L Q-35 01/13/12 01/13/12 Ground Water La-140 <15 <15.06 pCi/L Q-26 03/02/12 03/02/12 Milk ....

QC-GP-12 03/05/12 RGPP 1-131 <15 <18.12 pCi/L QC-SW-1 03/05/12 03/05/12 RGPP ....

2Q12 Q-13 03/30/12 06/29/12 Air Particulate ....

Q-33 04/06/12 04/27/12 Surface Water ....

Q-34 05/03/12 05/24/12 Surface Water 1-131 <15 <20.26 pCi/L Q-26 06/29/12 06/29/12 Milk Ba-140 <60 <64.32 pCi/L Q-26 06/29/12 06/29/12 Milk La-140 <15 <20.12 pCi/L Vegetation Q-QUAD 4 (Cabbage) 07/10/12 07/10/12 (Cs-1 37 only) ....

Q-26 08/24/12 08/24/12 Milk La-140 <15 <17.97 pCi/L Q-34 09/07/12 09/28/12 Surface Water ....

4Q12 Q-04 09/28/12 12/29/12 Air Particulate ....

Q-34 11/02/12 11/30/12 Surface Water ....

Required LLDs were achieved.

E-2 Page 92 of 124

2013**

START END REQUIRED REVISED CLIENT ID DATE DATE MATRIX NUCLIDE MDC MDC UNITS Q-34 01/11/13 01/11/13 Surface Water 1-131 <15 <15.63 pCi/L Q-34 02/08/13 02/15/13 Surface Water 1-131 <15 <16.83 pCi/L Q-26 1 03/01/13 1 03/01/13 Milk I I I I

Required LLDs were achieved.

- The 2013 data has been included in this errata section as it was encompassed in the time period from detector TBE-08 being placed into service to the time that the MDC calculation error was discovered. Actual data reported for 2013 uses the corrected MDC values.

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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 2013 Prepared By Teledyne Brown Engineering Environmental Services

,=" Exeton Generation, Quad Cities Nuclear Power Station Cordova, IL 61242 May 2014 Page 97 of 124

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Table Of Contents I. Sum m ary and Conclusion ............................................................................................ 3 I1. Introduction ............................................................................................................. 5 A. Objectives of the RG PP .................................................................................. 5 B. Im plem entation of the Objectives .................................................................... 6 C. Program Description ...................................................................................... 6 II1. Program Description .................................................................................................. 7 A. Sam ple Analysis .............................................................................................. 7 B. Data Interpretation ......................................................................................... 7 IV. Results and Discussion ........................................................................................... 8 A. Groundwater Results ....................................................................................... 8 B. Surface W ater 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 99 of 124

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2013 Fi-gures Figure A-1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2013 Figure A-2 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2013 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, 2013.

Table B-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table B-1.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table B-11.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2013.

Table B-Ill.1 Concentrations of Tritium in Groundwater Samples Collected and Anaylzed by Quad Cities Station Personnel, 2013.

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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 2013 through 31 December 2013.

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

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

In 2012 Conestoga-Rovers & Associates (CRA) completed a five-year update hydrogeologic investigation report for the Station (NEI 07-07, Hydrogeologic Investigation Report, dated November 2012). The referenced report summarized station activities since the 2006 hydrogeologic investigation report, including Page 101 of 124

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 and surface water samples, collected from the environment on station property in 2013. During that time period, RGPP samples were collected from 43 locations. The 43 locations include two new monitoring wells. One well is located southwest of the U-2 Main Power Transformer (MW-QC-3) and the other well is located near the Radwaste Max Recycle building (QC-GP-18).

2013 sample locations included thirty-six designated monitoring wells, two surface water monitoring points and five production wells (three of which are used for site drinking water). Sample frequency and analysis varies with well designation. Typical frequency/analysis include quarterly for tritium and annually for gamma, gross alpha, gross beta, strontium, select transuranics and Fe-55/Ni-63. Samples from seventeen 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 49,800 pCi/L in a monitoring well. Tritium concentrations ranged from less than the LLD of 200 pCi/L up to 326 pCi/Lin surface water monitoring locations.

Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater samples. In the case of tritium, Exelon specified that its 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 eight designated groundwater locations during the first quarter sampling in 2013 and on the two new wells in the 4 th qtr 2013. Gross Page 102 of 124

Alpha (dissolved) was detected in one groundwater sample at a concentration of 1.1 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations. Gross Beta (dissolved) was detected in 10 of 10 groundwater locations. The concentrations ranged from 1.8 to 51.0 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations.

Hard-To-Detect analyses was performed on one monitoring well designated as "elevated" (QC-GP-15) and the two new monitoring wells. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238. 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.

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 Page 104 of 124

nuclear industry audits. Station personnel review and evaluate all analytical data deliverables after initial review by the contractor.

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

Ill. Program Description This section covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2013.

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 2013.

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

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

2. Concentrations of strontium in groundwater.

3. Concentrations of tritium in groundwater and surface water.

4. Concentration of gross alpha and gross beta in groundwater.

5. Concentrations of Am-241 in groundwater.

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

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

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

9. Concentrations of Fe-55 in groundwater.

10. Concentrations of Ni-63 in groundwater.

B. Data Interpretation The radiological data collected prior to Quad Cities Nuclear Power Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Quad Cities Nuclear Power Station was considered operational at initial Page 105 of 124

criticality. Several factors were important in the interpretation of the data:

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

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

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

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

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

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

IV. Results and Discussion A. Groundwater Results Groundwater Samples were collected from on-site wells in accordance with the station radiological groundwater protection program. Analytical Page 106 of 124

results and anomalies are discussed below.

Tritium Samples from all locations were analyzed for tritium activity (Table B-1.1 & B-1ll.1 Appendix B). Tritium values ranged from the detection limit to 49,800 pCi/l. All samples obtained at the site boundaries were less then the 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 and 4th quarter sampling in 2013. Gross Alpha (dissolved) was detected in one groundwater location at a concentration of 1.1 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations. Gross Beta (dissolved) was detected in ten of ten groundwater locations. The concentrations ranged from 1.8 to 51.0 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations (Table B-1.1 Appendix B).

Gamma Emitters No gamma emitting nuclides were detected other than naturally occurring K-40 in one sample at a concentration of 47 pCi/L (Table B-1.2, Appendix B).

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

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

Tritium concentrations ranged from less than the LLD of 200 pCi/I up to 326 pCi/L. (Table B-II.1 Appendix B).

Gamma Emitters No gamma emitting nuclides were detected (Table B-II.2, Appendix B).

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

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

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

F. Investigations Currently no investigations are on-going.

G. Actions Taken

1. Compensatory Actions There have been no station events requiring compensatory actions at the Quad Cities Nuclear Power Station in 2013.

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 109 of 124

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TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2013 Site Site Type Well Designation Minimum Sample Frequency MW-QC-1 Monitoring Well Plume Quarterly MW-QC-2 Monitoring Well Plume Quarterly MW-QC-3 Monitoring Well Plume Quarterly MW-QC-101I Monitoring Well Idle Not Required MW-QC-101S Monitoring Well Idle Not Required MW-QC-102D Monitoring Well Plume Quarterly MW-QC-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-111D1 Monitoring Well Idle Not Required MW-QC-1 11 D2 Monitoring Well Idle Not Required MW-QC-1111 Monitoring Well Idle Not Required MW-QC-1 121 Monitoring Well Plume Quarterly MW-QC-1 131 Monitoring Well Idle Not Required MW-QC-1 141 Monitoring Well Idle Not Required MW-QC-1 15S Monitoring Well Idle Not Required MW-QC-116S Monitoring Well Idle Not Required SURFACE WATER #1 Surface Water Surface Water Quarterly SURFACE WATER #2 Surface Water Surface Water Quarterly WELL #1 Production Well Idle Not Required WELL #5 Production Well Idle Not Required WELL #6 LITTLE FISH Production Well Idle Not Required WELL #7 BIG FISH WELL Production Well Plume Quarterly WELL #8 FIRE TRAINING WELL Production Well Idle Not Required WELL #9 Dry Cask Storage Production Well Background Annual WELL #10 FISH HOUSE WELL Production Well Idle Not Required WELL #11 SPRAY CANAL WELL Production Well Idle Not Required STP SAND POINT WELL Production Well Idle Not Required QC-GP-1 Sentinel Well Plume Quarterly QC-GP-2 Sentinel Well Plume Quarterly QC-GP-3 Sentinel Well Idle Not Required QC-GP-4 Sentinel Well Plume Quarterly QC-GP-5 Sentinel Well Plume Quarterly QC-GP-6 Sentinel Well Plume Quarterly QC-GP-7 Sentinel Well Plume Quarterly QC-GP-8 Sentinel Well Idle Not Required QC-GP-9 Sentinel Well Plume Quarterly QC-GP-10 Sentinel Well Detection Quarterly QC-GP-11 Sentinel Well Detection Quarterly QC-GP-12 Sentinel Well Detection Quarterly QC-GP-13 Sentinel Well Plume Quarterly QC-GP-14 Sentinel Well Detection Quarterly QC-GP-15 Sentinel Well Elevated Quarterly QC-GP-16 Sentinel Well Detection Quarterly QC-GP-17 Sentinel Well Plume Quarterly QC-GP-18 Sentinel Well Plume Quarterly Note: Idle designated wells are not required to be sampled as part of the RGPP A-I Page 111 of 124

t'J 0

FIGURE A-1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2013

FIGURE A-2 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2013

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APPENDIX B DATA TABLES Page 115 of 124

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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, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (DIS) Gr-A (SUS) Gr-B (DIS) Gr-B (SUS)

MW-QC-102D 03/19/13 1730 +/- 230 MW-QC-102D 05/21/13 1590 +/- 213 MW-QC-102D 07/30/13 1740 +/- 234 MW-QC-102D 11/05/13 1270 +/- 176 MW-QC-1021 03/19/13 < 172 MW-QC-1021 05/21/13 < 167 MW-QC-1021 07/30/13 1370 +/- 199 MW-QC-1021 11/05/13 246 +/- 121 MW-QC-102S 03/19/13 < 173 MW-QC-102S 05/21/13 < 171 MW-QC-102S 07/30/13 < 190 MW-QC-102S 11/05/13 < 169 MW-QC-1031 03/19/13 < 176 < 5.7 < 0.6 < 0.9 < 0.8 7.2 +/- 1.2 < 1.6 MW-QC-1031 05/21/13 < 167 MW-QC-1031 07/30/13 < 192 MW-QC-1031 11/05/13 < 172 MW-QC-104S 03/19/13 < 174 < 5.7 < 0.8 < 1.1 < 0.8 8.1 +/- 1.3 < 1.6 MW-QC-104S 05/21/13 183 +/- 111 MW-QC-104S 07/30/13 < 195 MW-OC-104S 11/05/13 326 +/- 126 MW-QC-1051 03/19/13 943 +/- 151 MW-QC-1051 05/21/13 < 168 MW-QC-1051 07/30/13 < 193 MW-QC-1051 11/05/13 264 +/- 124 MW-QC-1061 03119/13 < 174 MW-QC-1061 05/21/13 < 166 MW-QC-1061 07/30/13 < 193 MW-QC-1061 11/05/13 < 200 MW-QC-106S 03/19/13 < 175 MW-QC-106S 05121113 < 170 MW-QC-106S 07/30/13 < 195 MW-QC-106S 11/05/13 < 172 MW-QC-1071 03/18/13 < 171 MW-QC-1071 05/20/13 < 171 MW-QC-108D 03/19/13 2340 +/- 288 MW-QC-108D 05/22/13 1330 +/- 186 MW-QC-108D 07/31/13 1690 +/- 229 MW-QC-108D 11/06/13 1720 +/- 218 MW-QC-1081 03/19/13 < 169 MW-QC-1081 05/22/13 4090 +/- 455 MW-QC-1081 07/31/13 6260 +/- 679 MW-QC- 1081 11/06/13 2660 +/- 307 MW-QC-108S 03/19/13 < 173 MW-QC-108S 05/22/13 363 +/- 124 MW-QC-108S 07/31/13 521 +/- 146 MW-QC-108S 11/06/13 < 171 MW-QC-1091 03119/13 < 177 MW-QC-1091 05/21/13 234 +/- 116 MW-QC-1091 07/30113 < 193 MW-QC-1091 11/05/13 < 172 B-1 Page 117 of 124

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (DIS) Gr-A (SUS) Gr-B (DIS) Gr-B (SUS)

MW-QC-109S 03/19/13 < 177 MW-QC-109S 05/21/13 < 165 MW-CC-109S 07/30/13 < 196 MW-OC-109S 11/05/13 < 172 MW-QC-1121 03/18/13 < 177 MW-OC-1 121 05/20/13 < 167 MW-CC-1121 07/29113 < 193 MW-CC-1121 11/04/13 < 172 MW-OC-1 03/19/13 < 177 MW-QC-1 05/21/13 < 171 MW-OC-1 07/30/13 < 191 MW-QC-1 11/05/13 < 172 MW-QC-2 03/19/13 < 173 MW-OC-2 05/21/13 < 166 MW-QC-2 07/30113 < 195 MW-QC-2 11/05/13 < 171 MW-QC-3 11/25/13 1730 +/- 221 < 4.1 < 0.8 1.1 + 0.7 < 1.9 10.9 +/- 1.2 < 3.2 OC-GP-10 03/17/13 < 189 < 5.4 < 1.0 < 1.7 < 0.6 9.4 +/- 1.4 < 1.6 QC-GP-11 03/17/13 617 +/- 155 < 5.3 < 0.8 < 1.3 < 0.6 5.5 +/- 1.2 < 1.6 QC-GP-12 03/18/13 < 192 < 5.5 < 0.8 < 0.7 < 0.6 1.8 t 0.8 < 1.4 QC-GP-14 03/17/13 4080 +/- 450 < 5.3 < 0.9 < 2.4 < 0.8 4.7 +/- 1.4 < 2.1 QC-GP-15 03/18/13 330 +/- 137 < 5.2 < 0.9 < 3.3 < 1.0 16.3 +/- 2.2 < 1.9 QC-GP-16 03/17/13 1670 +/- 216 < 5.0 < 0.8 < 1.7 < 0.8 2.6 +/- 1.1 < 2.1 QC-GP-18 12/08/13 4740 +/- 514 < 6.7 < 0.8 < 2.7 < 3.0 51.0 +/- 2.4 < 3.8 WELL 9 DRY CASK STORAGE 06/14/13 < 183 B-2 Page 118 of 124

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/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 03/19/13 < 55 < 68 <6 <7 < 11 <7 < 18 <7 <11 14 <7 <5 < 36 < 10 MW-QC-104S 03/19/13 < 66 < 41 <6 <6 < 12 <6 < 11 <7 <11 14 <6 <6 < 33 < 10 MW-QC-1071 03/18/13 < 46 < 124 <5 <6 < 14 <7 < 12 <6 <8 13 <5 <5 < 31 <9 QC-GP-10 03/17/13 < 15 < 12 <1 <2 <3 <1 <3 <2 <3 10 <1 <2 < 16 <5 QC-GP-1 1 03/17/13 < 18 < 13 <2 <2 <4 <1 <3 <2 <3 11 <2 <2 < 20 <5 QC-GP-12 03/18/13 < 25 < 21 <2 <3 <6 <2 <5 <3 <5 14 <2 <3 < 24 <8 QC-GP-14 03/17/13 < 12 < 10 <1 <1 <3 <1 <2 <1 <2 8 <1 <1 < 13 <4 OC-GP-15 03/18/13 < 24 < 19 <2 <3 <5 <2 <4 <3 <4 14 <2 <2 < 23 <7 QC-GP-15 09/12/13 < 18 < 15 <2 <2 <5 <2 <4 <2 <3 12 <2 <2 <21 <7 QC-GP-16 03/17/13 < 18 < 41 <1 <2 <4 <1 <3 <2 <3 14 <2 <2 < 21 <5 QC-GP-18 12/08/13 < 48 < 45 <5 <7 < 10 <6 < 13 <6 <9 13 <5 <6 < 35 < 10 MW-QC-3 11/25/13 < 21 47 +/- 30 <2 <2 <5 <2 <4 <2 <4 13 <2 <2 < 23 <7 WELL 9 DRY CASK STORAGE 06/14/13 < 37 < 39 <4 <5 < 10 <4 <9 <5 <7 13 <4 <5 < 31 <7

~0 0

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TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/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 03/18/13 < 0.16 < 0.09 < 0.02 < 0.06 < 0.09 < 0.03 < 0.02 < 0.03 < 94 < 4.2 QC-GP-18 12/08/13 < 0.13 < 0.04 < 0.09 < 0.05 < 0.05 < 0.10 < 0.15 < 0.14 < 147 < 5.0 MW-QC-3 11/25/13 < 0.07 < 0.06 < 0.02 < 0.02 < 0.06 < 0.19 < 0.07 < 0.19 < 70 " < 4.3 00 (b

C 0

TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SURFACE WATER #1 03/18/13 < 177 SURFACE WATER #1 05/20/13 < 167 SURFACE WATER #1 07/29/13 323 + 136 SURFACE WATER #1 11/04/13 223 +/- 121 SURFACE WATER #2 03/18/13

178 SURFACE WATER #2 05/20/13 < 169 SURFACE WATER #2 07/29/13 261 + 133 SURFACE WATER #2 11/04113 326 - 128 B-5 Page 121 of 124

TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2013 RESULTS IN UNITS OF PCI/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 SURFACE WATER #2 03/18/13 < 52 < 43 <5 <4 <12 <5 <9 <5 <8 <13 <5 <5 <31 <8 0q

TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2013 RESULTS IN UNITS OF PCI/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-1 3/17/2013 10,900 Shallow Aquifer QC-GP-1 5/16/2013 <2,000 Shallow Aquifer QC-GP-1 9/11/2013 6,600 Shallow Aquifer QC-GP-1 11/4/2013 5,510 Shallow Aquifer QC-GP-2 3/18/2013 <2,000 Shallow Aquifer QC-GP-2 5/16/2013 3,300 Shallow Aquifer QC-GP-2 9/11/2013 <2,000 Shallow Aquifer QC-GP-2 11/4/2013 <2,000 Shallow Aquifer QC-GP-3 5/16/2013 <2,000 Shallow Aquifer QC-GP-4 3/17/2013 49,300 Shallow Aquifer QC-GP-4 5/16/2013 27,800 Shallow Aquifer QC-GP-4 9/11/2013 48,800 Shallow Aquifer QC-GP-4 11/4/2013 48,700 Shallow Aquifer QC-GP-5 3/18/2013 <2,000 Shallow Aquifer QC-GP-5 5/16/2013 <2,000 Shallow Aquifer QC-GP-5 9/11/2013 <2,000 Shallow Aquifer QC-GP-5 11/4/2013 <2,000 Shallow Aquifer QC-GP-6 3/18/2013 <2,000 Shallow Aquifer QC-GP-6 5/16/2013 <2,000 Shallow Aquifer QC-GP-6 9/11/2013 <2,000 Shallow Aquifer QC-GP-6 11/4/2013 <2,000 Shallow Aquifer QC-GP-7 3/18/2013 <2,000 Shallow Aquifer QC-GP-7 5/16/2013 <2,000 Shallow Aquifer QC-GP-7 9/11/2013 <2,000 Shallow Aquifer QC-GP-7 11/4/2013 <2,000 Shallow Aquifer QC-GP-8 5/16/2013 <2,000 Shallow Aquifer QC-GP-9 3/18/2013 <2,000 Shallow Aquifer QC-GP-9 5/16/2013 <2,000 Shallow Aquifer QC-GP-9 9/11/2013 21,800 Shallow Aquifer QC-GP-9 11/4/2013 49,800 Shallow Aquifer QC-GP-10 3/17/2013 <2,000 Shallow Aquifer QC-GP-10 5/16/2013 <2,000 Shallow Aquifer QC-GP-10 9/11/2013 <2,000 Shallow Aquifer QC-GP-10 11/4/2013 <2,000 Shallow Aquifer QC-GP-11 3/17/2013 <2,000 Shallow Aquifer QC-GP-1 1 5/16/2013 <2,000 Shallow Aquifer QC-GP-11 9/12/2013 <2,000 Shallow Aquifer QC-GP-11 11/4/2013 <2,000 Shallow Aquifer QC-GP-12 3/18/2013 <2,000 Shallow Aquifer QC-GP-12 5/16/2013 <2,000 Shallow Aquifer QC-GP-12 9/11/2013 <2,000 Shallow Aquifer QC-GP-12 11/4/2013 <2,000 Shallow Aquifer QC-GP-13 3/18/2013 13,300 Shallow Aquifer QC-GP-13 5/16/2013 19,600 Shallow Aquifer QC-GP-13 9/12/2013 30,200 Shallow Aquifer QC-GP-13 11/4/2013 31,400 Shallow Aquifer QC-GP-14 3/17/2013 4,530 Shallow Aquifer QC-GP-14 5/16/2013 2,000 Shallow Aquifer QC-GP-14 9/11/2013 7,670 Shallow Aquifer QC-GP-14 11/4/2013 5,450 Shallow Aquifer QC-GP-15 3/18/2013 <2,000 Shallow Aquifer QC-GP-15 5/16/2013 <2,000 Shallow Aquifer QC-GP-15 9/12/2013 <2,000 Shallow Aquifer QC-GP-15 11/4/2013 <2,000 Shallow Aquifer B-7 Page 123 of 124

TABLE B-l1l.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2013 RESULTS IN UNITS OF PCI/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-16 3/17/2013 <2,000 Shallow Aquifer QC-GP-16 5/16/2013 <2,000 Shallow Aquifer QC-GP-16 9/11/2013 5,270 Shallow Aquifer QC-GP-16 11/4/2013 11,100 Shallow Aquifer QC-GP-17 3/17/2013 <2,000 Shallow Aquifer QC-GP-17 5/16/2013 <2,000 Shallow Aquifer QC-GP-17 9/11/2013 3,230 Shallow Aquifer QC-GP-17 11/4/2013 10,400 Shallow Aquifer MW-QC-106S 8/2/2013 <2,000 Shallow Aquifer MW-QC-1061 8/2/2013 <2,000 Shallow Aquifer Well #1 3/15/2013 <200 Well #1 6/14/2013 <200 Well #1 12/17/2013 <200 Well #5 6/14/2013 <200 Well #5 12/17/2013 <200 Well #7 3/24/2013 <200 Well #7 6/14/2013 <200 Well #7 9/26/2013 <2,000 Well #7 12/4/2013 <2,000 Well #10 6/14/2013 <200 Well #10 12/17/2013 <200 B-8 Page 124 of 124

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