Text

Annual Radiological Environmental Operating Report
	ML12136A552
Person / Time
Site:	Quad Cities
Issue date:	05/11/2012
From:	Hanley T; Exelon Generation Co, Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	SVP-12-045
	Download: ML12136A552 (128)
	v • d • e

Exelon Generation Company, LLC www.exeloncorp.comr Exeokn.

Guad Cities Nuclear Power Station Nuclear 22710 2o6th Avenue North Cordova, IL61242-9740 SVP-12-045 May 11, 2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Annual Radiological Environmental Operating Report Pursuant to Technical Specifications Section 5.6.2, enclosed is the 2011 Radiological Environmental Operating Report for Quad Cities Nuclear Power Station. This report contains the results of the radiological environmental and meteorological monitoring programs. In addition, the 2011 Radiological Groundwater Protection Program (RGPP)

Report is included as Appendix E of the enclosure.

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

Respectfully, J4d, Z5. ý Tim Hanley Site Vice President Quad Cities Nuclear Power Station

Enclosure:

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

Enclosure Annual Radiological Environmental Operating Report

Docket No: 50-254 50-265 QUAD CITIES NUCLEAR POWER STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2011 Prepared By Teledyne Brown Engineering Environmental Services Exekans.

Nuclear Quad Cities Nuclear Power Station Cordova, IL 61242 May 2012 1 of 126

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Table Of Contents I. Sum m ary and Conclusions .............................................................................................. 1 Il. Introduction ..................................................................................................................... 3 A. Objectives of the REM P ................................................................................. 3 B. Im plem entation of the Objectives .................................................................... 3 C. Radiation and Radioactivity ............................................................................. 3 D. Sources of Radiation ...................................................................................... 4 Ill. Program Description ................................................................................................. 5 A. Sam ple Collection .......................................................................................... 5 B. Sam ple Analysis ............................................................................................. 7 C. Data Interpretation .......................................................................................... 8 D. Program Exceptions ........................................................................................ 9 E. Program Changes ........................................................................................ 13 IV. Results and Discussion .......................................................................................... 13 A. Aquatic Environm ent ................................................................................... 13

1. Surface W ater .................................................................................... 13

2. Ground W ater .................................................................................... 14

3. Fish ..................................................................................................... 14

4. Sedim ent ............................................................................................. 14 B. Atm ospheric Environm ent ............................................................................. 15

1. Airborne .............................................................................................. 15

a. Air Particulates ......................................................................... 15

b. Airborne Iodine ........................................................................ 16

2. Terrestrial .......................................................................................... 16

a. Milk ........................................................................................... 16

b. Food Products ........................................................................ 16 C. Am bient Gam m a Radiation ........................................................................... 17 D. Independent Spent Fuel Storage ................................................................. 17 E. Land Use Survey .......................................................................................... 17 F. Errata Data ................................................................................................... 18 G. Summary of Results - Inter-laboratory Comparison Program ..................... 19 3 of 126

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for Quad Cities Nuclear Power Station, 2011 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, 2011 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2011 Figures Figure B-1 Quad Cities REMP Sampling Locations - 2 Mile Radius, 2011 Figure B-2 Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2011 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-I.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table C-l.2 Concentrations of Tritium, Iron-55 and Nickel-63 in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table C-11.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table C-I1.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

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Table C-111.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

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, 2011.

Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table C-VI.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table C-VII.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table C-VIII.1 Concentrations of Gamma Emitters in Food Product Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table C-IX.1 Quarterly TLD Results for Quad Cities Nuclear Power Station, 2011.

Table C-IX.2 Mean Quarterly TLD Results for the Inner Ring, Outer Ring, Other and Control Location for Quad Cities Nuclear Power Station, 2011.

Table C-IX.3 Summary of the Ambient Dosimetry Program for Quad Cities Nuclear Power Station, 2011.

Figures Figure C-1 Surface Water - Gross Beta - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2011.

Figure C-2 Surface Water - Tritium - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2011.

Figure C-3 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2011.

Figure C-4 Air Particulates - Gross Beta - Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2011.

Figure C-5 Air Particulates - Gross Beta - Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2011.

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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-1 3 and Q-1 6 Collected in the Vicinity of QCNPS, 2005 - 2011.

Figure C-8 Air Particulates - Gross Beta - Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2011.

Figure C-9 Air Particulates - Gross Beta - Stations Q-41 and Q-42 (C) Collected in the Vicinity of QCNPS, 2009 - 2011.

Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2011 Table D-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2011 Table D-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2011 Table D-4 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2011 Table D-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2011 Appendix E Annual Radiological Groundwater Protection Program Report (ARGPPR) iii 6 of 126

I. Summary and Conclusions In 2011, the Quad Cities Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 280 curies of noble gas, fission and activation products and approximately 72 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 Applicable Estimated Age Location % Of Organ Dose Group Distance Direction Applicable Limit Effluents (meters) (toward) Limit Noble Gas Gamma - Air Dose 1.35E-03 All 1029 NNE 6.75E-03 20 mRad Noble Gas Beta - Air Dose 6.94e-04 All 1029 NNE 1.74E-03 40 mRad Iodine, Particulate & Total Body 4.20E-02 Child 1029 NNE 4.20E-01 10 mrem Tritium III Iodine, Particulate & Thyroid 1.00E+00 Infant 1029 NNE 3.33E+00 30 mrem TritiumI Liquid Total Body 1.04E-03 Adult Mississippi River 1.73E-02 6 mrem Liquid Liver 2.19E-03 Teen Mississippi River 1.10E-02 20 mrem Skyshine Total Body 7.59E+00 All 800 N 3.04E+01 25 mrem 40CFRI90 Total Body (Gas + Liq+ 7.63E+00 All 800 N 3.05E+01 25 mrem Skyshine)

The doses as a result of the radiological effluents released from the Quad Cities Generating Station were a very small percentage of the allowable limits, with the exception of 40CFR190 whole body radiation which was calculated to be 30.5%

of the 25 mrem/yr limit.

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 2011 through 31 December 2011. During that time period, 1529 analyses were performed on 1415 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.

On March 11, 2011 an earthquake off the Japanese islands produced a massive tsunami that caused a nuclear accident at four of the six Fukushima Daiichi reactors. In planning for the potential radioactive plume reaching the United States, Exelon Nuclear increased the sampling frequency and added additional analyses of select media from pathways that were expected to be the most sensitive to any increase in ambient radiation levels. Low level 1-131 analyses and gamma spectroscopy analyses were performed on air particulates, air 7 of 126

iodine, and milk, as appropriate.

The resulting radioactive plume was first detected in the environs of Quad Cities Nuclear Power Station on March 18, 2011. The final date of positive detection was April 08, 2011. The radionuclide identified was Iodine-131. Maximum activity levels found by media were 92.5E-3 pCi/m3 for air iodine. Samples collected were compared to offsite control locations to verify that these positive detections were not attributable to licensed activities at Quad Cities Station. All other radionuclides analyzed were below the MDC (Minimum Detectable Concentration).

The radioactive half-life of 1-131 is about 8 days. This short half-life allowed the affects of this radioactive plume to subside over about 3 weeks. As of April 09, 2011 no further impacts from the Fukushima Daiichi accident were evident.

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

Fish (commercially and recreationally important species) and sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish or sediment samples. 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 with the exception of 27 samples which were positive for 1-131. These positive results are directly attributed to the Fukushima event in March of 2011.

Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. No 1-131 was detected. Concentrations of naturally occurring isotopes (K-40 approximately 1400 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 thermoluminescent dosimeters. Levels detected were consistent with those observed in previous years.

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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), Mirion Technologies, and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2011 through 31 December 2011.

A. Objective of the REMP The objectives of the REMP are to:

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

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

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

1. Identifying significant exposure pathways.

2. Establishing baseline radiological data of media within those pathways.

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

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

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

Some radioactivity is a result of nuclear weapons testing. Examples of radioactive fallout that is normally present in environmental samples are 9 of 126

cesium-1 37 and strontium-90. Some examples of radioactive materials released from a nuclear power plant are cesium-137, iodine-131, strontium-90, and cobalt-60. Radiation is measured in units of millirem; much like temperature is measured in degrees. A millirem is a measure of the biological effect of the energy deposited in tissue. The natural and man-made radiation dose received in one year by the average American is 300 to 400 mrem (References 2, 3, 4 in Table II.D-1 below).

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

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

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

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

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

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

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

(5) Industrial, security, medical, educational, and research 10 of 126

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 2011. 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). The control location was Q-42. 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 April through October, and monthly from November through March. 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-Quad 1 Control, Q-Quad 1, Q-Quad 2, Q-Quad 3, and Q-Quad 4). The control location was Q-Quad 1 - Control. 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 Direct radiation measurements were made using thermoluminescent 12 of 126

dosimeters (TLD). Each location consisted of 2 TLD sets. The TLD 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 TLD 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 TLDs 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 TLDs 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 TLD 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 1/2 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 TLDs were exchanged quarterly and sent to Mirion Technologies for analysis.

B. Sample Analysis This section describes the general analytical methodologies used by TBE and Environmental Inc. (Midwest Labs) to analyze the environmental samples for radioactivity for the QCNPS REMP in 2011 and the type of analyses. The analytical procedures used by the laboratories are listed in Table B-2.

In order to achieve the stated objectives, the current program includes the 13 of 126

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 the fact) estimate of the presence of activity.

2. Net Activity Calculation and Reportina 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 14 of 126

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-1 34, Cs-1 37 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 2011 the QCNPS REMP had a sample recovery rate in excess of 99%. Sample anomalies and missed samples are listed in the tables below:

Table D-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection Reason Type Code Date A/I Q-16 01/21/11 Low reading of 164.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months due to power outage from ice storm.

A/I Q-41 02/04/11 Pump running; meter stopped; estimated run time of 171.0 hours0 days 0 hours 0 weeks 0 months .

Meter reset.

A/I Q-03 02/11/11 Timer malfunction; timer replaced.

Estimated run time of 168.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

A/I Q-37 02/18/11 Timer malfunction; timer replaced.

Estimated run time of 167.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

A/I Q-03 02/18/11 Pump malfunction; pump replaced.

Estimated flow rate of 62 CFH. Filter was white.

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Table D-1 LISTING OF SAMPLE ANOMALIES (continued)

Sample Location Collection Reason Type Code Date A/I Q-41 03/04/11 Low reading of 66.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months due to power outage from storms.

A/I Q-42 03/04/11 Low reading of 94.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months due to power outage from storms.

A/I Q-03 03/18/11 Low reading of 87.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months due to pump malfunction; pump removed for repair; pump replaced.

A/I Q-37 04/01/11 Low reading of 164.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to power outage.

A/I Q-03 04/08/11 Low reading of 33.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months due to possible lightning strike; ground fault reset.

A/I Q-37 05/06/11 Low reading of 39.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months due to tripped ground fault; ground fault reset.

A/I Q-03 05/06/11 Timer malfunction; Estimated time of 171.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

A/I Q-03 05/13/11 Timer replaced; estimated time of 171.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

A/I Q-03 05/27/11 Pump not running; reset ground fault.

A/I Q-02 06/24/11 Low reading of 65.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months due to power outage from storm.

A/I Q-37 07/15/11 Low reading of 68.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months due to tripped ground fault; possible lightning strike during storm.

A/I Q-41 07/15/11 Low reading of 68.0 hours0 days 0 hours 0 weeks 0 months due to power outage from storm.

A/I Q-38 07/22/11 Low reading of 168.0 hours0 days 0 hours 0 weeks 0 months due to power outage from storm. Estimated flowrate of 60 CFH.

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Table D-1 LISTING OF SAMPLE ANOMALIES (continued)

Sample Location Collection Reason Type Code Date A/I Q-02 08/05/11 Low reading of 65.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months possibly due to interrupted timer run. Filter appeared to have 7-day particulate accumulation.

Estimated time of 168.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

A/I Q-13 08/26/11 Low reading of 86.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months due to power outage from storm.

A/I Q-41 08/26/11 Low reading of 86.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months due to power outage from storm.

A/I Q-37 10/14/11 Pump off; low reading of 39.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months due to ground fault trip. Reset ground fault.

A/I Q-42 10/21/11 Low reading of 165.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months due to power outage caused by auto accident.

A/I Q-42 12/16/11 Vmax below 20; collector replaced pump on 12/17/11.

Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date SW Q-33 01/07/11 - 02/11/11 No sample; water frozen SW Q-34 01/07/11 - 02/11/11 No sample; water frozen Al Q-37 05/27/11 Air iodine cartridge damaged in removal from holder; charcoal particles lost.

A/I Q-03 06/03/11 Low reading of 3.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months due to ground fault malfunction; not enough hours for viable sample; no particulate on filters.

A/I Q-41 06/03/11 Low reading of 56.0 hours0 days 0 hours 0 weeks 0 months due to power outage from storm.

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Table D-2 LISTING OF MISSED SAMPLES (cniud

.MSSE SAPE (continued)

Tabl.D-.LISINGOF Sample Location Collection Reason Type Code Date A/I Q-03 06/10/11 Low reading of 48.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to pump malfunction; pump replaced on 06/08/11.

A/I Q-04 07/29/11 Power out; low reading of 18.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to power outage from storm. Estimated flowrate of 60 CFH.

A/I Q-13 07/29/11 Low reading of 13.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months due to power outage from storm.

A/I Q-37 07/29/11 Pump off; low reading of 19.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to ground fault trip from storm. Reset ground fault.

A/I Q-04 08/05/11 Low reading due to power restoration on 08/03/11.

A/I Q-37 09/09/11 Pump off; low reading of 26.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months due to ground fault trip from storm. Reset ground fault.

A/I Q-38 09/09/11 Pump off; low reading of 26.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months due to ground fault trip from storm. Reset ground fault.

A/I Q-38 09/16/11 Low reading of 2.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months due to tripped ground fault. Reset ground fault.

A/I Q-38 11/11/11 Low reading of 0.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months due to tripped ground fault. Reset ground fault.

A/I Q-38 11/18/11 Low reading of 0.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months due to pump malfunction; collector replaced pump.

The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program 18 of 126

implementation.

E. Program Changes Starting in the second quarter of 2011, surface water samples are also being analyzed for Iron-55 and Nickel-63.

Air particulate/iodine control location Q-07 has been removed from the program for 2011. Air particulate/iodine location Q-42 has been installed as the new control location.

IV. Results and Discussion A. Aquatic Environment

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

The following analyses were performed.

Gross Beta Samples from all locations were analyzed for concentrations of gross beta (Table C-I.1, Appendix C). Gross beta activity was detected in all 22 samples. The values ranged from 3.0 to 7.6 pCi/L. Concentrations detected were consistent with those detected in previous years and the control location (Figure C-1, Appendix C). The required LLD was met.

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

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

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

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

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

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-11.2, Appendix C). No nuclides 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 was analyzed for gamma emitting nuclides (Table C-111.1, Appendix C).

No nuclides 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:

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Gamma Spectrometry Sediment samples from Q-39 and Q-40 were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). No nuclides were detected and all required LLDs were met.

B. Atmospheric Environment

1. Airborne

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

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

Detectable gross beta activity was observed at all locations.

Comparison of results among the four groups aid in determining the effects, if any, resulting from the operation of QCNPS. The results from the near-field locations (Group I) ranged from 6 to 41 E-03 pCi/m 3 with a mean of 21 E-03 pCi/m . The results from the far-field locations (Group II) ranged from 5 to 45 E-03 pCi/m 3 with a mean of 21 E-03 pCi/m 3 . The results from the Control location (Group Ill) ranged from 8 to 38 E-03 pCi/m 3 with a mean of 22 E-03 pCi/m 3 . Comparison of the 2011 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 2011 indicate no notable differences among the three groups (Figures C-4 through C-6, Appendix C).

Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C). No 21 of 126

nuclides were detected and all required LLDs were met.

Additional sampling occurred in the weeks immediately following the Fukushima event in March of 2011. No nuclides were detected and all required LLDs were met.

b. Airborne Iodine Continuous air samples were collected from ten locations (Q-01, Q-02, Q-03, Q-04, Q-13, Q-16, Q-37, Q-38 Q-41 and Q-42) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). All results were less than the MDC with the exception of 27 samples which were positive for 1-131.

These positive results are directly attributed to the Fukushima event in March of 2011. The required LLD was met.

2. Terrestrial

a. Milk Samples were collected from one location (Q-26) biweekly April through October and monthly November through March. 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). No nuclides were detected and all required LLDs were met.

b. Food Products Food product samples were collected at four locations plus a control location (Q-Quad 1 - Control, Q-Quad 1, Q-Quad 2, Q-Quad 3, and Q-Quad 4) annually during growing season.

Four locations, (Q-Quad 1, Q-Quad 2, Q-Quad 3 and Q-Quad 4) could be affected by Quad Cities' effluent releases. The following analysis was performed:

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

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

Most of the TLD measurements were below 30 mR/quarter, with a range of 16 to 31 mR/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 were no measurable changes in ambient gamma and radiation level as a result of ISFSI operations.

E. Land Use Survey A Land Use Survey conducted during August 2011 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 1/2 degree sectors around the site. The results from the land use census have not identified any locations, which yield a calculated dose or dose commitment, via the same pathway, that is at least 20% greater than at a location from which samples are currently being obtained. The results of this survey are summarized below.

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Distance in Miles from QCNPS Sector Residence Livestock Milk Farm Miles Miles Miles N 0.6 2.7 NNE 3.8 3.1 NE 1.3 -

ENE 2.9 2.9 E 2.0 2.7 ESE 2.8 3.1 3.1 SE 2.5 3.2 -

SSE 1.1 3.6 6.6,11.5 S 0.8 1.6 SSW 3.2 3.4 SW 2.9 3.3 WSW 2.2 2.7 -

W 2.6 4.3 4.6 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 The following errors were noted during a review of the 2009 and 2010 Annual Radiological Environmental Operating Reports (AREOR):

1. For the 2009 AREOR: In Part I, "Summary and Conclusions", it is stated that "1,436 analyses were performed on 1,534 samples".

These numbers were reversed. In reality, 1,534 analyses were performed on 1,436 samples. This is a documentation error only, and as such does not affect the sample results.

2. For the 2009 AREOR: In Part IV, "Results and Discussion",

Section E, "Land Use Survey", it was noted that the milk farm identified at 11.5 miles SSE from QCNPS was listed in the incorrect sector. This milk farm is actually located in the ESE sector. This did not affect sample results as this farm has declined to participate in the REMP program.

3. For the 2010 AREOR: In Part I, "Summary and Conclusions", it is stated that "1,425 analyses were performed on 1,519 samples".

These numbers were reversed. In reality, 1,519 analyses were performed on 1,425 samples. This is a documentation error only, and as such does not affect the sample results.

24 of 126

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.

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 primary laboratory, 14 out of 18 analytes met the specified acceptance criteria. Three analytes did not meet the specified acceptance criteria for the following reason:

1. Teledyne Brown Engineering's Analytics March 2011 Cr-51 in milk result of 398 pCi/L was higher than the known value of 298 pCi/L, 25 of 126

resulting in a found to known ratio of 1.34. NCR 11-13 was initiated to investigate this failure. There was a slightly high bias in all the gamma activities. The June gamma results in milk did not show a high bias. No further action was required.

2. Teledyne Brown Engineering's ERA May 2011 Gross Alpha in water result of 64.1 pCi/L was higher than the known value of 50.1 pCi/L, which exceeded the upper control limit of 62.9 pCi/L. NCR 11-08 was initiated to investigate this failure. The solids on the planchet exceeded 100 mg, which was beyond the range of the efficiency curve.

Teledyne Brown Engineering's MAPEP March 2011 Gross Alpha in air particulate result of 0.101 Bq/sample was lower than the known value of 0.659 Bq/sample, which exceeded the lower control limit of 0.198 Bq/sample. NCR 11-11 was initiated to investigate this failure. The air particulate filter was counted on the wrong side.

3. Teledyne Brown Engineering's ERA November 2011 Sr-89 in water result of 81.0 pCi/L was higher than the known value of 69.7 pCi/L, which exceeded the upper control limit of 77.9 pCi/L. NCR 11-16 was initiated to investigate this failure. The TBE reported value to known ratio of 1.16 fell within the acceptable range of +/- 20%, which TBE considers acceptable.

4. Teledyne Brown Engineering's MAPEP March 2011 Sr-90 in soil, air particulate and vegetation were non-reports that were evaluated as failed. NCR 11-11 was initiated to investigate these failures.

MAPEP evaluated the non-reports as failed due to not reporting a previously reported analyte.

For the secondary laboratory, Environmental, Inc., 12 out of 14 analytes met the specified acceptance criteria.

1. Environmental Inc.'s ERA October 2011 Cs-134 in water result of 38.8 pCi/L was higher than the known value of 33.4 pCi/L, which exceeded the upper control limit of 36.7 pCi/L. The sample was reanalyzed. The reanalyzed result of 32.9 was acceptable.

2. Environmental Inc.'s MAPEP February 2011 Sr-90 in air particulate result of 1.89 Bq/sample was higher than the known value of 1.36 Bq/sample, which exceeded the upper control limit of 1.77 Bq/sample. No errors were found in the calculation or procedure.

The reanalyzed result of 1.73 Bq/sample was acceptable.

3. Environmental Inc.'s MAPEP August 2011 Sr-90 in soil result of 219.4 Bq/kg, less than the known value of 320 Bq/kg, was below the lower control limit of 224 Bq/kg. The sample was reanalyzed in triplicate through a strontium column. The reanalyzed result of 304.2 Bq/kg was acceptable.

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

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APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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 4.7 5.1 5.1 Q-34 CONTROL 0 (PCI/LITER) (11/11) (11/11) (11/11) CAMANCHE - UPSTREAM (3.0/6.9) (3.3/7.6) (3.3/7.6) 4.4 MILES NNE OF SITE H-3 2000 <LLD <LLD 0 FE-55 6 200 <LLD <LLD 0 NI-63 6 5 <LLD <LLD 0 GAMMA 22 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 0

CO-60 15 <LLD <LLD 0 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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 t'

1-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 0

LA-140 15 <LLD <LLD 0 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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 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

FE-59 260 <LLD <LLD 0 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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 0

LA-140 NA <LLD <LLD 0 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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 4 (PCI/KG DRY) MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 w

CS-134 150 <LLD <LLD 0 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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 <LLD 0 (PCL/KG DRY)

BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 AIR PARTICULATE GR-B 507 10 21 22 23 Q- 13 INDICATOR 0 (E-3 PCIICU.METER) (450/455) (51/52) (50/51) PRINCETON (5/45) (8/38) (9/45) 4.7 MILES SW OF SITE GAMMA 40 MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 ON MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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 80 CS-134 50 <LLD <LLD 0 CS-137 60 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 00 0

AIR IODINE GAMMA 504 (E-3 PCI/CU.METER) 1-131 70 70 51 95 Q-03 INDICATOR 0 (24/452) (3/52) (3/49) ONSITE 3 (40/138) (36/66) (69/138) 0.6 MILES S OF SITE MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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 1-131 20 1 <LLD NA 0 (PCI/LITER)

GAMMA 20 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 NB-95 NA <LLD NA 0 w

ZR-95 NA <LLD NA 0 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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) (LID) MEASUREMENTS MILK CS-134 15 <LLD NA 0 (PCI/LITER)

CS-137 18 <LLD NA 0 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 C)

CO-60 NA <LLD <LLD 0 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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 VEGETATION ZN-65 NA <LLD <LLD 0 (PCI/KG WET)

NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 1-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0 CS-137 80 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 0

LA-140 NA <LLD <LLD 0 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2011 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY: CORDOVA IL REPORTING PERIOD: ANNUAL 2011 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 TLD-QUARTERLY 332 NA 24 24 28 Q-21 1-1 INDICATOR 0 (MILLI-ROENTGEN/QTR.) (324/324) (8/8) (4/4)

(16/31) (18/28) (22/31) 4.5 MILES SW 0O MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS 43 of 126

Intentionally left blank 44 of 126

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2011 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 0-36 Cordova Well (indicator) 3.3 miles SSW C. Milk - bi-weekly I monthly Q-26 Bill Stanley Dairy (indicator) 3.5 miles ESE D. Air Particulates / Air Iodine Q-01 Onsite 1 (indicator) 0.5 miles N Q-02 Onsite 2 (indicator) 0.4 miles ENE Q-03 Onsite 3 (indicator) 0.6 miles S Q-04 Nitrin (indicator) 1.7 miles NE Q-13 Princeton (indicator) 4.7 miles SW Q-16 Low Moor (indicator) 5.7 miles NNW Q-37 Meredosia Road (indicator) 4.4 miles ENE Q-38 Fuller Road (indicator) 4.7 miles E Q-41 Camanche (indicator) 4.3 miles NNE 0-42 LeClaire (control) 8.7 miles SSW E. Fish Q-24 Pool #14 of Mississippi River, Downstream (indicator) 0.5 miles SW 0-29 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 - TLD Inner Ring Q-101-1 0.6 miles N Q-101-2 0.9 miles N Q-102-1 1.3 miles NNE Q-102-3 1.4 miles NNE Q-103-1 and -2 1.2 miles NE Q-104-1 1.1 miles ENE Q-104-2 0.9 miles ENE Q-105-1 and -2 0.8 miles E Q-106-2 and -3 0.7 miles ESE Q-107-2 0.7 miles SE Q-107-3 0.8 miles SE Q-108-1 1.0 miles SSE Q-108-2 0.9 miles SSE B-1 45 of 126

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2011 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - TLD (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-112-1 2.5 miles WSW Q-1 12-2 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-115-1 2.6 miles NW Q-115-2 2.3 miles NW Q-116-1 2.3 miles NNW Q-116-3 2.4 miles NNW Outer Rinq Q-202-1 4.4 miles NNE 0-202-2 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 46 of 126

TABLE B-i: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2011 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - TLD (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 47 of 126

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2011 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 Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Surface Water Gross Beta Monthly composite from TBE, TBE-2008 Gross Alpha and/or gross beta activity in weekly grab samples various matrices Env. Inc., W(DS)-01 Determination of gross alpha and/or gross beta in water (dissolved solids or total residue)

Surface Water Tritium Quarterly composite from TBE, TBE-2011 Tritium analysis in drinking water by liquid weekly grab samples scintillation Env. Inc., T-02 Determination of tritium inwater (direct method)

Surface Water Iron and Nickel Quarterly composite from TBE, TBE-2006 Iron-55 invarious matrices weekly grab samples TBE, TBE-2013 Radionickel invarious matrices Ground Water Gamma Spectroscopy Quarterly grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Ground Water Tritium Quarterly grab samples TBE, TBE-2011 Tritium analysis in drinking water by liquid scintillation Env. Inc., T-02 Determination of tritium inwater (direct method)

Fish Gamma Spectroscopy Semi-annual samples TBE-2007 Gamma emitting radioisotope analysis collected via electroshocking or other Env. Inc., GS-01 Determination of gamma emitters by gamma techniques spectroscopy Sediment Gamma Spectroscopy Semi-annual grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy 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 Env. Inc., AP-02 Determination of gross alpha and/or gross beta in air particulate filters Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2007 Gamma emitting radioisotope analysis each station Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Iodine Gamma Spectroscopy Weekly composite of TBE, TBE-2007 Gamma emitting radioisotope analysis continuous air sampling through charcoal filter Env. Inc., 1-131-02 Determination of 1-131 in charcoal canisters by gamma spectroscopy (batch method)

Milk 1-131 Bi-weekly grab sample TBE, TBE-2012 Radioiodine in various matrices when cows are on pasture.

Monthly all other times Env. Inc., 1-131-01 Determination of 1-131 in milk by an ion exchange Milk Gamma Spectroscopy Bi-weekly grab sample TBE, TBE-2007 Gamma emitting radioisotope analysis when cows are on pasture.

Monthly all other times Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Food Products Gamma Spectroscopy Annual grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis Env. Inc., GS-01 Determination of gamma emitters by gamma I_ I I spectroscopy TLD Thermoluminescence Quarterly TLDs Mirion Technologies I Dosimetry I I B-4 48 of 126

West -Q i 2o 21i

07-2 WS SE S ESE South Figure B-1 Map Quad Cities REMP Sampling Locations - 2 Mile Radius, 2011 B-5 49 of 126

0 7W.% S0rf &^Pt#SAMPLEXS./TLO* SER is WAV 33 AOJ SSW 101-1.2 North 01 North' t02-1.3 NNIE 34 103-1.2 NE 36 104-' .2 ENE 04 HE NES 105-1.2 Eowt 13 5*

106--2.3 r 107-2.3 R 37 ENE 24 10*- T.2 SSE 100-1. South I f- 1:3 Sw I t2-1.2 *WS FIS Sziaic 113-1. Wmet 24 S*

, 47'.:3 vo 29 ot II i- 1.2 4 114-13 PNW -PRIMARW #4OA0S

-RIYERS/STWLAMS 44+ RA4LPOADS

-FENCE:

AMETEORMHOLGCM TOWER wwM SOAMI

M 51/4 1/2 III.

RES ____P QUAD CITIES MEWr __ "__ __ STATION S,,, , w r a.

_ FIGURE 6-1

, ,- " P*rEW.S REMP Sarnple Locatiorls 2 2-94 ; RE p c PfuVL EVELON CMELN-N TON RanF k R..cok ,71C"l ILUJNOIS 3 3-22-04 2W04 XEVS So" w_____________________

4 12-7-10 210 Jim wb r a ORNN f: kATHLEEN E. WLLJAMS Figure B-1 Legend Quad Cities REMP Sampling Locations - 2 Mile Radius, 2011 B-6 50 of 126

Figure B-2 Map Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2011 B-7 51 of 126

TLDS SECTOR LAIR SAUPL ,S/'r,. SECTOR *VSA1NM SNpLrs SECTOR North 01 North 33 SSW 102- ..3 NNE 02 iNc .34 103-- .2 NE 03 .35 Souath .36 SSW

, 04-1.2 04 "E I 05-1.2 ENE 13 sw 106-2,3 NNW n .IaLk ESECO 107-2.3 ESE 26 SSE 37 E?4E 108-1.2 35 Eqst 10-1. 2 South9 41 NNIE 11 1-1.2 Sw WSW 42 SSW *i FISH SETO 1 t'3-1.2 We0t 24 Sw

¶W4W 29Not 115-1.2 N'W 1I16-1 .3 - rIMARY ft0405 201 - 1 .2 N~orth 202-1 .2 NNE -SEXX)NDAWRY OAD2S 203-.I 2 N.E __MVES/5'rRIMAMS 204-1.2 9RACILROADS 40 NE 205-1.4 ENE East -FENCE 206-1,2 ESE A UEToropLoCicAkL TowER 207-1.4 Se 206-1.2 SSE 209-1 .4 South no. .

210--1.5 SSW MIU AM L"/L0 211*1..2 Sw "Mi PNAW 6WS 214-- *WOU

.7 215-'.2 21 6-- .2 NPkM q 1/4 1/2 mik, ORAWINf REEAE__~w QU~AD C ITI ES DATE: A&W>

_____O"H~w STATIO N 4-1-' OMF4L IIUA~mCARL FIGUR~E 6-2 0" RtEVS REM- Samrple Locationis 2 2--" los REV

_______ Wrnk R..d ~ EXELAN G!2d.A110N CICGOLNI 3 3--22-04 2004 REVS 5.011 wriUkdI'd ___ _________________

4 '00 2003 REVS slake you"j

_im Wolkriam 5 112-7-101 2010 REVSS -d- -

-j-l - 1jIj~& OAW V W-.IATH117VU F WHI AMS Figure B-2 Legend Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2011 B-8 52 of 126

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY 53 of 126

Intentionally left blank 54 of 126

TABLE C-I.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q-33 Q-34 PERIOD 01/01/11 - 01/28/11 (1) (1) 02/18/11 - 02/25/11 5.5 +/-2.5 6.6 + 2.7 03/04/11 - 03/25/11 4.4 +/-2.7 4.1 +/- 1.9 04/01/11 - 04/29/11 3.7 +/-2.2 4.5 + 2.3 05/06/11 - 05/27/11 6.9 +/-2.6 5.4 + 2.6 06/03/11 - 06/24/11 4.0 +/-2.3 3.9 +/- 2.2 07/01/11 - 07/29/11 5.5 +/-2.1 7.6 +/- 2.2 08/05/11 - 08/26/11 6.8 +/-2.4 7.3 +/- 2.5 09/02/11 - 09/30/11 3.6 +/-1.8 3.3 +/- 1.7 10/06/11 - 10/27/11 3.0 +/-1.4 5.1 +/- 1.5 11/04/11 - 11/25/11 4.8 +/- 1.7 4.2 +/- 1.8 12/02/11 - 12/30/11 4.0 +/- 1.3 3.7 +/- 1.3 MEAN 4.7 +/- 2.6 5.1 +/- 3.0 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, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION H-3 FE-55 NI-63 PERIOD Q-33 02/15/11 - 03/25/11 162 04/01/11 - 06/24/11 167 < 176 (2) < 3.6 (2) 07/01/11 - 09/30/11 186 < 186 < 3.9 10/06/11 - 12/30/11 183 < 168 < 3.8 MEAN Q-34 02/15/11 - 03/25/11 161 04/01/11 - 06/24/11 167 < 88 (2) < 3.6 (2) 07/01/11 - 09/30/11 185 < 157 < 3.9 10/06/11 - 12/30/11 184 < 171 < 3.8 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION (2) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-1 55 of 126

TABLE C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 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 PERIOD Q-33 01/01/11 - 01/28/11 (1) -

02/18/11 - 02/25/11 <1 <1 <2 <1 <2 <1 <2 < 10 <1 <1 < 16 <5 03/04/11 - 03/25/11 <1 <2 <5 <1 <3 <2 <4 < 11 <1 <1 < 45 < 14 04/01/11 - 04/29/11 <2 <2 <2 <1 <3 <3 <3 <8 <1 <2 < 41 < 13 05/06/11 - 05/27/11 <1 <1 <3 <1 <1 <1 <2 < 14 <1 <1 < 16 <5 06/03/11 - 06/24/11 <1 <2 <4 <1 <3 <2 <3 < 13 <1 <1 < 19 <6 07/01/11 - 07/29/11 <2 <2 <4 <2 <4 <2 <3 <8 <2 <2 < 16 <6 08/05/11 - 08/26/11 <3 <3 <8 <3 <6 <3 <6 < 14 <3 <3 < 25 < 10 09/02/11 - 09/30/11 <5 <7 < 12 <5 < 13 <7 < 13 < 15 <6 <7 < 44 < 11 10/06/11 - 10/27/11 <3 <3 <7 <3 <6 <3 <5 < 14 <3 <3 < 27 < 10 11/04/11 - 11/25/11 <1 <1 <2 <1 <2 <1 <2 < 12 <1 <1 < 14 <4 12/02/11 - 12/30/11 <2 <2 <5 <2 <3 <2 <3 < 14 <1 <2 < 20 <8 MEAN Q-34 01/01/11 - 01/28/11 (1) 02/18/11 - 02/25/11 <1 <1 <2 <1 <2 <1 <2 < 10 <1 <1 < 14 <4

<1 <3 <2 <3 < 13 <1 <1 < 45 < 13 03/04/11 - 03/25/11 <2 <4 <1 04/01/11 - 04/29/11 <2 <2 <4 <1 <4 <2 <4 <9 <1 <2 < 48 < 13 05/06/11 - 05/27/11 <1 <1 <2 <1 <1 <1 <2 < 13 <1 <1 < 16 <4 06/03/11 - 06/24/11 <2 <2 <4 <2 <3 <2 <3 < 14 <1 <2 < 20 <7 07/01/11 - 07/29/11 <2 <2 <5 <2 <4 <2 <4 < 11 <2 <2 < 19 <5 08/05/11 - 08/26/11 <3 <3 <8 <3 <6 <4 <5 < 13 <3 <3 < 25 < 10 09/02/11 - 09/30/11 <7 <4 < 12 <7 < 16 <7 < 12 < 14 <6 <8 < 38 < 14 10/06/11 - 10/27/11 <2 <3 <6 <3 <6 <3 <5 < 15 <2 <3 < 27 <9 11/04/11 - 11/25/11 <1 <1 <2 <1 <1 <1 <1 < 10 <1 <1 <11 <4 12/02/11 - 12/30/11 <1 <2 <3 <1 <3 <2 <3 < 13 <1 <1 < 19 <6 MEAN 0.,

(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, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q-35 Q-36 PERIOD 01/14/11 - 01/14/11 < 151

152 04/15/11 - 04/15/11 < 177 < 178 07/15/11 - 07/15/11 < 192 < 194 10/14/11 - 10/14/11 < 163 < 164 MEAN C-3 57 of 126

TABLE C-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 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 01/14/11 - 01/14/11 <3 <3 <6 <3 <5 <4 <5 < 13 <2 <3 < 24 <7 04/15/11 - 04/15/11 <1 <1 <3 <1 <3 <2 <3 < 12 <1 <1 < 19 <6 07/15/11 - 07/15/11 <5 <5 < 12 <4 <8 <5 <9 < 12 <5 <5 < 26 <9 10/14/11 - 10/14/11 <5 <5 < 10 <4 <9 <6 <8 < 13 <4 <5 < 30 < 11 MEAN Q-36 01/14/11 - 01/14/11 <3 <3 <7 <3 <6 <4 <6 < 13 <3 <3 < 27 <9 04/15/11 - 04/15/11 <1 <1 <3 <1 <2 <1 <2 < 11 <1 <1 < 15 <5 07/15/11 - 07/15/11 <4 <4 < 10 <4 < 10 <5 <7 < 11 <4 <4 < 26 <8 10/14/11 - 10/14/11 <3 <3 <7 <3 <7 <4 <7 <9 <3 <4 < 22 <8 MEAN 00

TABLE C-I11.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 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-1 34 Cs-137 Ba-140 La-140 PERIOD Q-24 River Carpsucker 05/03/11 < 46 < 46 < 110 < 48 < 102 < 74 < 102 < 46 < 54 < 688 < 189 Walleye 05/03/11 < 32 < 29 < 66 < 37 < 59 < 38 < 66 < 26 < 19 < 410 < 99 Common Carp 10/26/11 < 52 < 58 < 126 < 61 < 105 < 67 < 118 < 55 < 55 < 573 < 159 Largemouth Bass 10/26/11 < 56 < 77 < 120 < 79 < 110 < 68 < 134 < 55

72 < 673

125 MEAN Q-29 Common Carp 05/03/11 < 28 < 41 < 105 < 45 < 68 < 43 < 55 < 32 < 35 < 517 < 159 Freshwater Drum 05/03/11 < 34 < 39 < 73 < 47 < 72 < 28 < 58 < 32 < 33 < 412 < 131 C-) Common Carp 10/26/11 < 50 < 39 < 96 < 63 < 89 < 38 < 90 < 38 < 46 < 494 < 113 Walleye 10/26/11 < 78 < 63 < 167 < 79 < 124 < 75 < 146 < 65 < 65 < 752 < 223 MEAN

(-I 0

TABLE C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 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-1 34 Cs-1 37 Ba-140 La-140 PERIOD PERIOD Q-39 05/26/11 < 88 < 92 < 279 < 106 < 178 < 120 < 170 < 65 < 86 < 1260 < 450 10/14/11 < 56 < 52 < 132 <64 < 109 < 59 < 96 < 51 < 52 < 322 < 106 MEAN Q-40 05/26/11 < 28 < 30 < 106 < 37 < 83 < 40 < 70 < 21 < 35 < 499 < 174 10/14/11 < 59 < 51 < 138 < 62 < 130 < 65 < 118 < 56 < 68 < 390 < 120 C-) MEAN 0

TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I I GROUP 11 I GROUP III PERIOD Q-01 -0 QJ-04 Q-1 3 Q,-16 Q-37 Q4-38 Q-41 12/31/10u - 01/07/11 41 +/-4 34 +/- 4 4U +/- 4 41 +/- 4 45 +/- 5 37 +/- 4 42 +/- 4 35 +/- 4 33 +/-4 37 +/- 4 (1) 01/07/11 - 01/14/11 18 +/-5 17 +/- 4 21 +/- 5 20 +/- 5 22 +/- 5 18 +/- 5 18 +/- 4 13 +/- 4 17 +/-5 19 +/- 5 34 +/-5 36 +/- 5 38 +/- 6 32 +/-5 40 +/-6 35 +/- 6 34 +/- 5 36 +/- 6 33 +/-5 37 +/- 6 01/214/11 - 01/28/11 34 +/-4 31 +/- 4 34 +/- 4 38 +/-4 37 +/- 4 36 +/- 4 22 +/- 4 37 +/- 4 38 +/-4 38 +/- 4 01/28/11 - 02/04/11 18 +/-4 18 +/- 4 18 +/- 4 20 +/- 4 18 +/-4 16 +/- 4 20 +/- 4 23 +/- 5 13 +/-4 18 +/- 4 02/04/11 - 02/11/11 22 +/- 5 24 +/- 5 22 +/- 5 19 +/- 4 21 +/- 5 23 +/- 5 24 +/- 5 25 +/- 5 22 +/-5 19 +/- 4 02/11/111 - 02/18/11 21 +/-4 22 +/- 4 <4 22 +/- 5 23 +/-5 22 +/- 4 18 +/- 4 26 +/- 5 19 +/-4 22 +/- 4 02/18/11 - 02/25/11 14 17 +/- 5 11 +/-4 15 +/- 5 14 +/-5 9 +/-4 14 +/- 5 13 +/- 5 15 +/-5 16 +/- 5

+/-5 02/25/11 - 03/04/11 22 24 +/- 5 18 +/- 4 23 +/-5 23 +/-5 21 +/-5 18 +/- 4 24 +/- 5 19 +/-9 24 +/- 7

+/-4 03/04/11 - 03/10/11 14 10 +/- 4 15 +/- 4 16 +/- 4 16 +/-5 16 +/-5 11 +/-4 12 +/- 4 13 +/-5 15 +/- 5

+/-4 03/10/11 - 03/18/11 7 24 +/- 5 39 +/- 10 (2) 15 +/- 5 19 +/-5 20 +/-5 25 +/- 5 22 +/- 5 18 +/-4 17 +/- 4 03/18/11 - 03/25/11 22 +/-5 27 +/- 5 20 +/- 5 29 +/- 6 33 +/-6 24 +/-5 27 +/- 5 31 +/- 6 30 +/-6 27 +/- 5 03/25/11 - 04/01/11 33 +/-6 33 +/- 6 34 +/-6 38 +/- 6 38 +/-6 32 +/-6 33 +/- 6 (2)33 +/- 6 35 +/-6 34 +/- 6 04/01/11 - 04/08/11 19 +/-4 14 +/- 4 22 +/- 15 (2)19 +/- 4 15 +/-4 18 +/- 4 18 +/- 4 19 +/- 4 21 +/-4 23 +/- 4 04/08/11 - 04/15/11 15 +/-4 14 +/- 4 14 +/- 4 15 +/- 4 13 +/- 4 15 +/- 4 17 +/- 4 17 +/- 4 18 +/-4 20 +/- 5 04/15/11 - 04/22/11 11 +/-4 19 +/- 4 15 +/- 4 18 +/- 4 18 +/- 4 13 +/- 4 15 +/- 4 17 +/- 4 17 +/-4 14 +/- 4 04/22/11 - 04/29/11 <5 6 +/-3 <5 7 +/-4 <5 5 +/-3 6+/- 3 6 +/-4 7 +/-4 <5 04/29/11 - 05/06/11 7+/- 3 11 +/-4 11 +/-4 (2) 10 +/- 4 14 +/- 4 11 +/-4 (2) 8 +/-4 10 +/-4 14 +/- 4 05/06/11 - 05/13/11 12 +/- 4 11 +/-4 9 +/-4 (2) 10 +/- 4 12 +/- 4 9 +/-4 10 +/- 4 11 +/-4 12 +/-4 12 +/- 4 05/13/11 - 05/19/11 8 +/-4 9 +/-4 10 +/- 4 10 +/- 4 9 +/-4 6 +/-4 9 +/-4 11 +/-4 9 +/-4 8+/-4 05/19/11 - 05/26/11 12 +/- 4 12 +/- 4 < 9 12 +/- 4 11 +/-4 8 +/-4 10 +/- 4 12 +/- 4 12 +/-4 13 +/-4 05/26/11 - 06/03/11 10 +/- 4 8 +/-4 (2) 13 +/- 4 19 +/- 4 13 +/- 4 14 +/- 4 15 +/- 4 (2) 14 +/-4 06/03/11 - 06/10/11 23 +/- 4 13 +/- 4 (2) 24 +/- 4 29 +/- 5 26 +/- 5 22 +/- 4 22 +/- 4 26 +/-5 15 +/-4 06/10/11 - 06/17/11 13 +/- 4 8 +/-4 16 +/- 5 14 +/- 5 16 +/- 5 9 +/-4 10 +/- 4 11 +/-4 10 +/-4 10 +/-4 06/17/11 - 06/24/11 10 +/- 3 25 +/- 9 (2) 12 +/- 4 10 +/- 4 13 +/- 4 13 +/- 4 12 +/- 4 11 +/- 4 12 +/-4 15 +/-4 06/24/11 - 07/01/11 15 +/- 4 14 +/- 4 13 +/- 4 14 +/- 4 16 +/- 4 14 +/- 4 15 +/- 4 15 +/- 4 16 +/-4 21 +/-4 07/01/11 - 07/08/11 17 +/- 4 16 +/- 4 22 +/- 5 20 +/- 5 20 +/- 5 23 +/- 5 12 +/- 4 17 +/- 5 22 16 +/-4 07/08/11 - 07/15/11 23 +/- 5 19 +/- 4 17 +/- 4 20 +/- 5 15 +/- 4 22 +/- 5 27 +/- 9 (2)16 +/- 4 34 +/-10 (2)18 +/-4 07/15/11 - 07/22/11 20 +/- 4 24 +/- 5 31 +/- 5 29 +/- 5 25 +/- 5 30 +/- 5 26 +/- 5 29 +/- 5 (2)28 +/-5 26 +/-5 07/22/11 - 07/29/11 15 +/- 4 17 +/- 4 16 +/- 4 (2) (2) 17 +/- 4 (2) 15 +/- 4 14 +/-4 17 +/-4 07/29/11 - 08/05/11 31 +/- 5 27 +/- 5 (2)22 +/- 5 21 +/- 7 +/-6 34 +/- 6 31 +/- 5 26 +/- 5 32 +/-5 29 +/- 5 08/05/11 - 08/12/11 19 +/- 5 18 +/- 5 17 +/- 5 16 +/- 5 +/-5 21 +/- 5 21 +/- 5 17 +/- 5 22 +/-5 24 +/- 5 08/12/11 - 08/19/11 18 +/- 5 21 +/- 5 23 +/- 5 20 +/- 5 36 +/-5 20 +/-5 18 +/- 5 17 +/- 5 22 27 +/- 5 08/19/11 - 08/26/11 24 +/- 4 20 +/- 4 26 +/- 5 27 +/- 5 21 +/-8 (2)24 +/- 5 22 +/- 4 24 +/- 4 24 +/-7 (2) 25 +/- 5 08/26/11 - 09/02/11 25 +/- 5 26 +/- 5 25 +/- 5 24 +/- 5 +/-5 29 +/- 5 31 +/- 5 13 +/- 4 30 33 +/- 5

+/-5 09/02/11 - 09/09/11 15 +/- 4 17 +/- 4 20 +/- 5 22 +/- 5 15 21 +/- 5 (2) (2) 25 20 +/- 5 21 09/09/11 - 09/16/11 16 +/- 4 17 +/- 4 17 +/- 4 14 +/- 4 15 14 +/- 4 16 +/- 4 (2) 16 14 +/- 4

+/-4 09/16/11 - 09/23/11 21 +/- 4 12 +/- 4 21 +/- 4 16 +/- 4 21 +/-5 18 +/- 4 17 +/- 4 19 +/- 4 18 19 +/- 4

+/-4 09/23/11 - 09/30/11 16 +/- 4 14 +/- 4 21 +/- 4 17 +/- 4 1+/-4 20 +/- 4 21 +/- 4 16 +/- 4 20 20 +/- 4 09/30/11 - 10/06/11 33 +/- 5 30 +/- 5 33 +/- 5 37 +/- 5 +/-6 20 +/- 5 32 +/- 5 22 +/- 5 26 +/-6 26 +/- 6 10/06/11 - 10/14/11 33 +/- 5 35 +/- 5 33 +/- 5 23 +/- 5 24

~ 5 28 +/- 5 28 +/- 5 (2) (2) 30 +/-5 31 +/- 5 10 +/- 4 9 +/-4 8+/-4 6 +/-4 +/-4 8 +/-4 9 +/-4 7+/-4 12 +/-4 12 +/- 4 10/214/11 - 10/27111 21 30 +/- 5 34 +/-5 30 +/-5 26 +/- 4 +/-6 32 +/- 6 20 +/- 4 28 +/-5 34 +/-6 36 +/- 6 10/27/11 - 11/04/11 26 +/- 5 28 +/- 5 19 +/-5 18 +/- 5 +/-4 16 +/- 4 26 +/- 5 12 +/-2 17 +/-4 23 +/- 5 25 +/- 6 29 +/- 6 23 +/-6 27 +/- 6 +/-5 29 +/-5 37 +/- 6 (2) 32 +/-6 30 +/- 5 11/25/11 - 12/02/11 26 +/- 5 21 +/- 5 13 +/-5 17 +/- 5 15 19 +/-5 25 +/- 5 (2) 19 +/-6 24 +/- 6 12/02/11 - 12/09/11 20 +/- 5 20 +/- 5 20 +/-5 19 +/- 5 +/-4 17 +/-4 15 +/- 4 14 +/- 4 21 +/-4 20 +/- 4 20 +/- 4 15 +/- 4 14 +/- 4 16 +/- 4 +/-4 17 +/-4 20 +/- 4 17 +/- 4 19 +/-4 15 +/- 4 23 +/- 5 26 +/- 6 20 +/- 5 24 +/- 5 55 26 +/- 5 33 +/- 6 22 +/- 5 25 +/-5 27 +/- 5 12/09/11 - 12/16/11 32 +/- 5 30 +/- 5 29 +/- 5 31 +/- 5 +/-6 35 +/- 5 37 +/- 5 27 +/- 5 25 +/-5 29 +/- 5 12/16/11 - 12/23/11 35 +/- 5 37 +/- 5 31 +/- 5 33 +/- 5 55 35 +/-5 26 +/- 5 29 +/- 5 32 +/-5 37 +/- 5 12/23/11 - 12/230/11 18 +/- 4 16 +/- 4 18 +/- 5 19 +/- 4 +/-5 20 +/-5 21 +/- 5 16 +/- 4 20 +/-5 16 +/- 4 MEAN 20 +/-16 20 +/-17 21 +/-16 20 +/-16 23 +/-18 20 +/-17 21 +/- 17 19 +/-16 21 +/-16 22 +/- 16

THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION (2) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-7 61 of 126 C-7

TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - NEAR-SITE LOCATIONS GROUP II - FAR-FIELD LOCATIONS GROUP III - CONTROL LOCATIONS COLLECTION MIN MAX MEAN + COLLECTION MIN MAX MEAN +/- COLLECTION MIN MAX MEAN +

PERIOD 2SD PERIOD 2SD PERIOD 2SD I-.O Il IU U II01 I1 I, 12i/31/1u 01/28111 13 45 31 + 19 1Z/31/11u - U112W111 19v 38 32 01/28/11 02/25/11 11 24 19 +/-7 01/28/11 02/25/11 9 26 19 +9 01/28/11 - 02/25/11 16 22 19 +5 02/25/11 04/01/11 7 39 23 +/- 18 02/25/11 04/01/11 11 38 24 +/- 15 02/25/11 - 04/01/11 15 34 23 +/-15 04/01/11 04/29111 6 22 15 +/-9 04/01/11 04/29/11 5 21 14 +/- 10 04/01/11 - 04/22/11 14 23 19 +/-9 04/29/11 06/03/11 7 13 10 +/-3 04/29/11 06/03/11 6 19 11 +5 04/29/11 - 06/03/11 8 14 12 +/-5 06/03/11 07/01/11 8 25 15 +/- 10 06/03/11 07/01/11 9 29 16 +/- 12 06/03/11 - 07/01/11 10 21 15 +/-9 07/01/11 07/29/11 15 31 20 +/-9 07/01/11 07/29/11 12 34 22 +/- 13 07/01/11 - 07/29/11 16 26 19 +/-9 07/29/11 09/02/11 16 31 22 +/-8 07/29/11 09/02/11 13 36 25 +/- 12 07/29/11 - 09/02/11 24 33 27 +/-7 09/02111 09/30/11 12 22 17 +/-6 09/02/11 09/30/11 14 25 19 +/-6 09/02/11 - 09/30/11 14 20 18 +/-6 60 09/30/11 10/29/11 6 37 26 +/- 22 09/30/11 11/04/11 7 36 22 +/- 19 09/30/11 -11/04/11 12 36 26 +/- 18 10/29/11 12/03/11 13 29 21 +/- 10 10/29/11 12109/11 11 37 21 +/- 13 11/04/11 - 12/09/11 15 30 23 +/- 12 12/03/11 12/30/11 16 37 26 +/-13 12/03/11 12/30/11 16 41 28 +/- 15 12/09/11 - 12/30/11 16 37 27 +/- 21 12/31/10 - 12/30/11 6 41 21 +/- 16 12/31/10 - 12t30/11 5 45 21 +/- 17 12/31/10 - 12/30/11 8 38 22 +/- 16

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES 0

I',,

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 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-1 37 Ba-140 La-140 PERIOD Q-01 12/31/10 - 04/01/11 <4 <4 < 13 4 <9 <5 <6 <3 <4 < 182 < 79 04/01/11 - 07/01/11 <2 <3 <4 2 <7 <3 <6 <2 <2 < 130 < 23 07/01/11 - 09/30/11 <3 <3 <6 2 <4 <3 <4 <2 <2 < 78 < 38 09/30/11 - 12/30/11 <4 <3 <7 4 <6 <3 <5 <3 <3 < 24 <11 MEAN Q-02 12/31/10 04/01/11 <4 <5 < 15 3 <9 <6 <11 <4 <4 < 250 < 96 04/01/11 07/01/11 <2 <3 < 11 3 <7 <4 <5 <2 <2 < 109 < 40 07/01/11 09/30/11 <3 <3 <8 2 <6 <4 <6 <3 <3 < 99 < 57 09/30/11 12/30/11 <2 <2 <4 2 <4 <2 <3 <2 <2 < 16 <8 MEAN Q-03 12/31/10 04/01/11 <3 <5 < 13 <3 < 11 <6 <8 <4 <3 254 < 75 04/01/11 07/01/11 <3 <4 < 14 <4 <7 <4 <8 <3 <3 163 < 63 07/01/11 09/30/11 <4 <5 < 10 <3 <7 <4 <8 <4 <3 129 < 52 09/30/11 12/30/11 <3 <2 <4 <3 <4 <2 <4 <2 <2 16 <8 MEAN Q-04 12/31/10 04/01/11 <4 <6 < 17 <3 <9 <6 < 10 <4 <4 < 218 < 107 04/01/11 07/01/11 <2 <3 <9 <2 <7 <3 <6 <2 <2 < 114 < 62 07/01/11 09/30/11 <4 <5 < 14 <4 < 12 <6 < 11 <4 <4 < 190 < 65 09/30/11 12/30/11 <2 <2 <5 <2 <7 <2 <4 <2 <2 < 20 <5 MEAN Q-13 12/31/10 04/01/11 <3 <4 < 15 <4 <9 <5 < 10 <3 <3 < 197 < 93 04/01/11 07/01/11 <2 <4 < 10 <2 <8 <4 <7 <3 <2

139 < 50 07/01/11 09/30/11 <3 <4 < 11 <3 <7 <4 <6 <2 <2 < 108 < 31 09/30/11 12/30/11 <2 <3 <4 <3 <7 <3 <5 <3 <2 < 22 < 11 0

MEAN k)

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 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-1 37 Ba-140 La-140 PERIOD Q-16 12/31/10 - 04/01/11 <4 <4 < 12 <4 <7 <6 <9 <3 <3 < 268 < 98 04/01/11 - 07/01/11 <3 <5 < 16 <3 < 10 <6 < 11 <4 <3 < 251 < 53 07/01/11 - 09/30/11 <3 <4 < 14 <3 <9 <4 <6 <3 <2 < 115 < 58 09/30/11 - 12/30/11 <2 <3 <7 <3 <7 <3 <6 <3 <3 < 21 <8 MEAN Q-37 12/31/10 - 04/01/11 <3 <5 < 16 <3 <8 <5 <11 <3 <3 < 213 < 80 04/01/11 - 07/01/11 <2 <3 < 10 <4 <6 <3 <5 <2 <2 < 130 <44 07/01/11 - 09/30/11 <4 <6 < 14 <4 < 10 <6 < 11 <4 <3 < 154 < 42 09/30/11 - 12/30/11 <3 <4 <8 <4 <7 <4 <6 <3 <3 < 31 < 12 MEAN 0

Q-38 12/31/10 - 04/01/11 <4 <5 < 15 <4 <8 <6 < 12 <3 <4 < 244 < 86 04/01/11 - 07/01/11 <2 <4 <11 <3 <5 <3 <5 <3 <3 < 130 < 29 07/01/11 - 09/30/11 <3 <3 <9 <2 <8 <4 <9 <3 <3 < 141 < 51 09/30/11 - 12/30/11 <3 <2 <6 <3 <6 <3 <5 <2 <2 < 23 < 10 MEAN Q-41 12/31/10 - 04/01/11 <3 <5 < 16 <5 < 10 <5 <11 <4 <3 < 240 < 65 04/01/11 - 07/01/11 <4 <5 < 15 <4 <9 <6 <11 <4 <4 < 232 < 66 07/01/11 - 09/30/11 <3 <6 < 12 <4 <9 <5 <9 <4 <3 < 162 < 53 09/30/11 - 12/30/11 <2 <2 <6 <2 <5 <2 <4 <2 <2 < 17 <7 MEAN 0*

0O

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 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-1 34 Cs-137 Ba-140 La-140 PERIOD Q-42 03/10/11 - 03/18/11 < 21 < 16 <44 < 18 < 41 < 24 < 32 < 19 <18 < 86 < 38 03/18/11 - 03/25/11 < 30 < 26 <64 < 39 < 83 < 33 < 46 < 29 < 34 < 103 < 38 03/25/11 - 04/01/11 < 28 < 27 <48 < 32 < 66 < 29 < 47 < 32 < 23 < 98 < 40 04/01/11 - 04/08/11 < 29 < 21 < 52 < 25 < 72 < 30 < 46 < 31 < 30 < 104 <43 12/31/10 - 04/01/11 <4 <6 < 18 <2 < 10 <6 <9 <3 <4 < 219 < 117 04/01/11 - 07/01/11 <4 <5 < 15 <2 <7 <6 < 10 <4 <4 < 215 < 95 07/01/11 - 09/30/11 <4 <3 < 13 <3 <9 <4 <8 <3 <3 < 111 <54 09/30/11 - 12/30/11 <4 <4 < 11 <3 <6 <4 <7 <4 <4 <25 < 11 MEAN cI' BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT

TABLE C-VI-.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II IGROUP III I

PERIOD Q-01 Q-02GROUP Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 1 I/ IU - U lIIi II < 34 < 33 < 18 < 34 < 34 < 35 < 35 < 33 < 31 < 31 (1) 01/07/11 - 01/14/11 < 27 < 26 < 26 < 26 < 14 < 44 < 44 < 45 < 44 < 19 01/14/11 - 01/21/11 < 17 < 17 < 17 <9 < 17 <9 < 19 < 20 < 20 < 20 01/21/11 - 01/28/11 < 19 <34 < 34 < 35 < 37 < 17 < 36 < 38 < 39 < 39 01/28/11 - 02/04/11 < 29 < 28 < 28 < 29 < 16 <4 <8 <9 <8 <8 02/04/11 - 02/11/11 < 20 < 44 < 44 < 46 < 45 < 24 < 39 < 40 < 39 < 39 02/11/11 - 02/18/11 < 14 < 24 < 24 < 25 < 24 < 12 < 28 < 29 < 28 < 27 02/18/11 - 02/25/11 < 22 < 38 < 38 < 39 < 39 < 20 < 36 < 37 < 36 < 36 02/25/11 - 03/04/11 < 35 <34 <34 < 35 < 19 < 41 < 41 < 43 (2) < 31 (2) 03/04/11 - 03/10/11 < 28 < 49 < 49 < 51 < 64 <34 < 48 < 50 < 62 < 63 03/10/11 - 03/18/11 < 19 < 42 < 42 (2) < 44 < 51 < 66 < 55 < 24 < 66 < 67 03/18/11 - 03/25/11 56 +/- 36 79 +/- 38 78 +/- 30 73 +/- 29 80 +/- 41 78 +/- 32 89 +/- 29 93 +/- 30 77 +/- 27 66 +/- 29 03/25/11 - 04/01/11 86 +/- 26 74 +/- 25 69 +/- 30 63 +/- 21 74 +/- 26 57 +/- 28 47 +/- 28 (2) 80 +/- 27 48 +/- 32 52 +/- 37 04/01/11 - 04/08/11 44 +/- 20 58 +/- 19 138 +/- 80 (2) 48 +/- 32 < 28 < 44 40 +/- 22 < 39 54 +/- 23 36 +/- 21 04/08/11 - 04/15/11 < 36 < 29 < 39 < 35 < 22 < 39 < 29 < 28 < 36 < 35 04/15/11 - 04/22/11 < 20 < 46 < 46 < 48 < 49 < 35 < 62 < 63 < 64 < 65 04/22/11 - 04/29/11 <34 < 59 < 59 < 61 < 57 < 23 < 56 < 58 < 54 <54 04/29/11 - 05/06/11 < 37 < 65 <64 (2) < 67 < 67 < 31 (2) < 57 < 57 < 57 05/06/11 - 05/13/11 < 67 < 36 < 65 (2) < 67 < 68 < 58 < 55 < 57 < 58 < 25 05/13/11 - 05/19/11 < 57 < 57 < 57 < 59 < 43 < 65 < 48 < 49 < 28 < 66 05/19/11 - 05/26/11 < 65 < 63 (2) < 11 < 70 < 28 < 63 (2) < 25 < 28 < 28 05/26/11 - 06/03/11 < 69 < 67 (2) < 69 < 59 <54 < 61 < 63 (2) < 30 06/03/11 - 06/10/11 < 60 < 60 (2) < 60 < 41 < 41 < 58 < 60 < 41 < 42 06/10/11 - 06/17/11 < 45 < 45 < 47 < 47 < 46 < 65 < 64 < 66 < 66 < 62 06/17/11 - 06/24/11 < 27 < 69 (2) < 28 < 26 < 29 < 16 < 58 < 60 < 60 < 59 06/24/11 - 07/01/11 < 62 < 62 <64 < 64 < 28 < 41 < 40 < 41 < 41 < 23 07/01/11 - 07/08/11 <34 < 34 < 35 < 35 < 19 < 18 <41 < 42 < 42 < 42 07/08/11 - 07/15/11 < 32 < 57 < 59 < 59 < 57 < 33 < 53 (2) < 23 <54 (2) < 22 07/15/11 - 07/22/11 < 40 < 40 < 41 < 41 < 23 < 24 < 53 < 56 (2) < 56 < 57 07/22/11 - 07/29/11 < 21 < 48 < 50 (2) (2) < 25 (2) < 59 < 58 < 58 07/29/11 - 08/05/11 < 20 < 47 (2) < 48 (2) < 49 < 22 < 49 < 50 < 51 < 51 08/05/11 - 08/12/11 <8 < 15 < 15 < 15 <8 < 25 < 45 < 46 < 46 < 46 08/12/11 - 08/19/11 < 57 < 57 < 59 < 51 < 45 < 45 < 27 < 57 < 50 < 49 08/19/11 - 08/26/11 < 10 < 24 < 25 < 25 < 50 (2) < 12 < 20 < 21 < 41 (2) < 21 08/26/11 - 09/02/11 < 41 < 41 < 43 < 41 < 22 < 59 < 60 < 26 < 59 < 59 09/02/11 - 09/09/11 < 15 < 27 < 28 < 27 < 28 <11 (2) (2) < 25 < 25 09/09/11 - 09/16/11 < 19 < 35 < 36 < 35 <34 < 45 < 46 (2) < 19 < 45 09/16/11 - 09/23/11 <56 < 56 < 57 < 56 < 33 < 59 < 56 < 58 < 59 < 33 09/23/11 - 09/30/11 < 24 < 56 < 57 < 55 <54 < 59 < 63 < 65 < 61 < 33 09/30/11 - 10/06/11 < 20 < 47 < 49 < 47 < 62 < 27 < 49 < 50 < 65 < 65 10/06/11 - 10/14/11 < 22 < 39 <41 < 39 < 36 < 22 < 58 (2) (2) < 52 < 52 10/14/11 - 10/21/11 < 22 < 40 <41 < 40 < 41 < 18 < 43 < 45 < 45 < 45 (2) 10/21/11 - 10/27/11 < 25 < 11 < 26 < 25 < 39 < 37 < 46 < 47 < 70 < 69 10/27/11 - 11/04/11 < 24 < 57 < 59 < 57 < 55 < 27 < 48 < 50 < 47 < 28 11/04/11 - 11/11/11 < 38 < 39 < 22 < 38 < 34 <7 < 20 (2) < 18 < 18 11/11/11 - 11/17/11 < 22 < 51 < 52 < 51 < 65 < 25 < 38 (2) < 48 < 48 11/17/11 - 11/25/11 < 51 < 51 < 52 < 28 < 44 < 20 < 56 < 58 < 50 < 49 11/25/11 - 12/02/11 < 21 < 38 < 40 < 38 < 48 < 23 < 45 < 47 < 56 < 56 12/02/11 - 12/09/11 <64 < 64 < 66 <64 < 31 < 25 < 53 < 55 < 46 < 46 12/09/11 - 12/16/11 <24 < 57 < 58 < 57 < 57 < 29 < 54 < 54 < 55 < 54 (2) 12/16/11 - 12/23/11 < 23 < 37 < 38 < 37 < 37 < 18 < 34 <34 < 34 < 35 12/23/11 - 12/30/11 < 18 < 33 <34 < 32 < 36 < 24 < 57 < 57 < 58 < 58 MEAN 62 +/-43 70 +/-22 95 +/-75 61 +/- 25 77 +/- 8 67 +/- 29 59 +/- 53 86 +/- 18 60 +/-31 51 +/-30

THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION (2) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-12 66 of 126

TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA INDICATOR FARM COLLECTION Q-26 PERIOD 01/07/11 < 0.7 02/04/11 < 0.7 03/04/11 < 0.7 04/01/11 < 1.0 04/15/11 < 0.3 05/06/11 < 0.5 05/20/11 < 0.6 06/03/11 < 0.7 06/17/11 < 0.5 07/01/11 < 0.7 07/15/11 < 0.8 07/29/11 < 0.9 08/12/11 < 0.6 08/26/11 < 0.6 09/09/11 < 0.6 09/23/11 < 0.6 10/07/11 < 0.6 10/21/11 < 0.9 11/05/11 < 0.8 12/03/11 < 0.4 MEAN C-13 67 of 126

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 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 01/07/11 <4 <5 < 11 <5 < 10 <5 <8 <4 <5 < 27 <9 02/04/11 <4 <5 < 12 <5 < 12 <5 <8 <4 <4 < 36 < 13 03/04/11 <6 <6 < 14 <7 < 10 <7 <9 <4 <5 < 39 < 15 04/01/11 <2 <2 <5 <2 <4 <2 <3 <2 <2 < 20 <6 04/15/11 <1 <2 <4 <2 <3 <2 <3 <1 <2 < 15 <4 05/06/11 <6 <7 < 15 <8 < 15 <7 < 13 <6 <7 < 38 < 12 05/20/11 <5 <5 < 11 <5 < 10 <6 <8 <4 <5 <44 < 13 06/03/11 <8 <8 < 17 < 11 < 17 <9 < 16 <9 <8 < 38 < 13 06/17/11 <8 <7 < 18 < 10 < 16 <8

13 <6 <8 < 36 < 15 07/01/11 <6 <6 < 12 <7 < 11 <7 < 10 <6 <6 <34 < 12 07/15/11 <5 <6 < 13 <8 < 14 <6 <8 <5 <5 < 30 < 12 07/29/11 <7 <9 < 16 <8 < 15 <7 < 12 <6 <9 <44 < 11 08/12/11 <7 <6 < 15 <7 < 11 <6 < 11 <4 <5 < 45 <8 08/26/11 <6 <6 < 16 <5 < 15 <7 < 13 <7 <7 < 43 < 14 09/09/11 <6 <6 < 16 <7 < 15 <7 < 11 <6 <7 < 41 < 11 09/23/11 <6 <7 < 14 <8 < 13 <6 < 10 <6 <7 < 37 < 13 10/07/11 <8 <8 < 20 <9 < 22 <8 < 11 <6 <9 < 39 < 14 10/21/11 <9 <9 < 20 < 10 < 20 < 10 < 15 <8 < 10 < 45 < 12 11/05/11 <5 <7 < 16 <7 < 14 <6 < 12 <5 <6 < 36 < 10 12/03/11 <5 <5 < 10 <6 < 13 <6 <8 <5 <6 < 25 < 11 MEAN 00 0

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 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-1 34 Cs-137 Ba-140 La-140 PERIOD Q-CONTROL Onions 07/18/11 < 12 < 12 < 30 < 12 <25 < 15 < 24 < 54 < 13 < 14 < 112 < 25 Rhubarb Leaves 07/18/11 < 14 < 15 < 32 < 16 < 32 < 16 <23 <56 < 11 < 13 <99 <28 MEAN Q-QUAD 1 Kale 07/18/11 < 13 < 17 < 40 < 18 <38 < 17 < 32 < 52 < 13 < 12 < 118 < 24 Potatoes 07/18/11 < 15 < 17 < 38 < 16 <36 < 15 < 23 < 48 < 13 < 14 < 100 < 31 MEAN JI Q-QUAD 2 Onions 07/18/11 < 14 < 15 < 39 < 21 < 30 < 16 < 29 < 55 < 14 < 21 < 114 < 35 Rhubarb leaves 07/18/11 < 13 < 15 < 31 < 14 < 30 < 14 < 23 < 47 < 13 < 13 < 104 < 27 MEAN Q-QUAD 3 Onions 07/18/11 < 12 < 17 < 31 < 16 < 33 < 14 < 26 < 48 < 14 < 16 < 104 < 26 Spinach 07/18/11 <46 <56 < 154 <67 < 115 <68 <96 <46 <48 <56 < 506 < 147 MEAN Q-QUAD 4 Cabbage 07/18/11 < 14 < 17 < 22 < 13 < 32 < 15 <24 <44 < 11 < 13 <97 < 19 Potatoes 07/18/11 < 17 < 18 < 48 < 21 < 48 < 16 < 28 < 59 < 17 < 21 < 152 < 39 MEAN oC

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE +2 S.D.

+/- 2 S.D.

Q-01-1 23.3 +/- 7.2 24 26 18 25 Q-01-2 24.3 + 10.4 28 29 18 22 Q-02-1 23.5 + 7.4 24 28 19 23 Q-02-2 22.8 + 6.6 23 27 19 22 Q-03-1 22.3 + 9.1 23 28 17 21 Q-03-2 22.0 + 7.8 23 27 18 20 Q-04-1 24.8 + 7.7 27 27 19 26 Q-04-2 24.8 + 6.4 26 27 20 26 Q-13-1 23.8 + 7.9 27 27 19 22 Q-13-2 24.3 +/- 5.0 25 27 21 24 Q-16-1 21.5 +/- 6.2 22 24 17 23 Q-16-2 21.0 +/- 5.7 23 23 17 21 Q-37-1 26.3 +/- 6.0 27 29 22 27 Q-37-2 25.0 +/- 8.3 26 30 20 24 Q-38-1 24.8 +/- 9.1 26 30 19 24 Q-38-2 25.5 +/- 8.1 28 29 20 25 Q-41-1 22.5 +/- 6.8 24 26 18 22 Q-41-2 24.0 +/- 11.0 26 30 17 23 Q-42-1 24.5 +/- 9.0 25 27 18 28 Q-42-2 24.3 +/- 7.2 26 27 19 25 Q-101-1 23.0 +/- 9.1 26 27 17 22 Q-101-2 23.3 +/- 9.0 27 26 17 23 Q-102-1 26.5 +/- 10.4 28 28 19 31 Q-102-3 22.5 +/- 8.1 26 25 17 22 Q-103-1 23.5 +/- 8.4 23 28 18 25 Q-103-2 22.8 +/- 8.5 26 26 17 22 Q-104-1 22.3 +/- 6.6 23 26 18 22 Q-104-2 23.5 +/- 7.4 25 26 18 25 Q-105-1 23.8 +/- 6.8 25 28 21 21 Q-105-2 22.8 +/- 7.7 25 25 17 24 Q-106-2 23.5 +/- 8.7 26 25 17 26 Q-106-3 22.8 +/- 8.7 25 27 17 22 Q-107-2 22.3 +/- 7.5 23 26 17 23 Q-107-3 22.8 +/- 7.2 25 26 18 22 Q-108-1 23.0 +/- 9.4 25 28 17 22 Q-108-2 22.8 +/- 9.1 26 25 16 24 Q-109-1 23.8 +/- 7.9 27 27 19 22 Q-109-2 22.8 +/- 9.0 25 25 16 25 Q-111-1 23.0 +/- 6.9 24 26 18 24 Q-111-2 24.8 +/- 9.6 25 29 18 27 Q-112-1 24.5 +/- 10.6 25 31 18 24 Q-112-2 22.8 +/- 7.9 24 26 17 24 Q-113-1 23.3 +/- 9.0 26 27 17 23 Q-113-2 21.8 +/- 7.9 25 25 17 20 Q-114-1 22.5 +/- 6.2 23 25 18 24 Q-114-2 22.3 +/- 6.6 23 26 18 22 Q-115-1 22.5 +/- 7.7 24 26 17 23 Q-115-2 22.3 +/- 7.5 23 26 17 23 Q-116-1 24.3 +/- 6.2 24 27 20 26 Q-116-3 23.0 +/- 8.5 26 26 17 23 C-16 70 of 126

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGENIQUARTER +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL-SEP OCT-DEC CODE +/- 2 S.D.

Q-201-1 22.8 +/- 8.4 24 27 17 23 Q-201-2 24.8 +/- 9.1 26 30 19 24 Q-202-1 23.0 +/- 4.9 25 25 20 22 Q-202-2 23.3 +/- 6.2 25 26 19 23 Q-203-1 25.0 +/- 6.7 27 27 20 26 Q-203-2 26.5 +/- 10.1 30 29 19 28 Q-204-1 24.8 +/- 7.2 27 28 20 24 Q-204-2 26.8 +/- 6.6 29 29 22 27 Q-205-1 24.5 +/- 8.1 27 28 19 24 Q-205-4 25.5 +/- 8.1 28 29 20 25 Q-206-1 24.3 +/- 7.2 25 27 19 26 Q-206-2 23.3 +/- 7.7 25 27 18 23 Q-207-1 24.8 +/- 9.1 27 28 18 26 Q-207-4 25.0 +/- 9.1 29 28 19 24 Q-208-1 23.3 +/- 7.0 25 27 19 22 Q-208-2 25.8 +/- 8.5 25 29 20 29 Q-209-1 26.5 +/- 9.3 27 28 20 31 Q-209-4 24.5 +/- 9.0 27 28 18 25 Q-210-1 24.3 +/- 7.2 26 27 19 25 Q-210-4 25.0 +/- 7.1 28 27 20 25 Q-210-5 22.5 +/- 7.6 25 25 17 23 Q-211-1 28.3 +/- 8.4 31 30 22 30 Q-211-2 27.5 +/- 8.7 30 30 21 29 Q-212-1 25.5 +/- 7.4 27 28 20 27 Q-212-2 23.0 +/- 6.9 26 24 18 24 Q-213-1 23.8 +/- 7.2 27 26 19 23 Q-213-2 21.5 +/- 5.8 22 25 18 21 Q-214-1 23.8 +/- 6.8 24 27 19 25 Q-214-2 25.5 +/- 5.3 28 27 22 25 Q-215-1 22.8 +/- 6.8 24 26 18 23 Q-215-2 24.8 +/- 7.2 24 28 20 27 Q-216-1 24.5 +/- 7.4 27 26 19 26 Q-216-2 26.5 +/- 6.0 28 28 22 28 C-17 71 of 126

TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE INNER RING, OUTER RING, OTHER AND CONTROL LOCATION FOR QUAD CITIES NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER STANDARD DEVIATIONS OF THE STATION DATA COLLECTION INNER RING OUTER RING OTHER CONTROL PERIOD +/- 2 S.D.

JAN-MAR 24.9 +/- 2.7 26.5 +/- 4.0 25.1 +/- 3.8 25.5 +/- 1.4 APR-JUN 26.5 +/- 2.8 27.4 +/- 3.0 27.4 +/- 3.9 27.0 +/- 0.0 JUL-SEP 17.6 +/- 2.1 19.4 +/- 2.7 18.8 +/- 2.9 18.5 +/- 1.4 OCT-DEC 23.5 +/- 4.2 25.2 +/- 4.8 23.3 +/- 3.9 26.5 +/- 4.2 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR QUAD CITIES NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/-2 S.D.

INNER RING 120 16 31 23.1 +/- 7.4 OUTER RING 132 17 31 24.6 +/- 7.3 OTHER 72 17 30 23.7 +/- 7.3 CONTROL 8 18 28 24.4 +/- 7.6 INNER RING STATIONS - Q-101-1, Q-101-2, Q-102-1, Q-102-3, Q-103-1, Q-103-2, Q-104-1, Q-104-2, Q-105-1, Q-105-2, Q-106-2, Q-106-3, Q-107-2, Q-107-3, Q-108-1, Q-108-2, Q-109-1, Q-109-2, Q-111-1, Q-111-2, Q-112-1, Q-112-2, Q-113-1, Q-113-2, Q-114-1, Q-114-2, Q-115-1, Q-115-2, Q-116-1, Q-116-3 OUTER RING STATIONS - Q-201-1, Q-201-2, Q-202-1, Q-202-2, Q-203-1, Q-203-2, Q-204-1, 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-18 72 of 126

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

Collected in the Vicinity of QCNPS, 2000 - 2011 Q-33 Cordova 12.0 10.0 8.0 6.0 C.)

4.0 2.0 0.0 I 01-01-00 05-26-02 10-18-04 03-13-07 08-05-09 12-29-11 Q-34 (C) Camanche 12.0 10.0 8.0

-J C.) 6.0 4.0 2.0 0.0 i 01-01-00 05-26-02 10-18-04 03-13-07 08-05-09 12-29-11 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-19 73 of 126

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

Collected in the Vicinity of QCNPS, 2000 - 2011 Q-33 Cordova 500 400 300 0.

200 100 0 I 01-01-00 05-26-02 10-18-04 03-13-07 08-05-09 12-29-11 Q-34 (C) Camanche 500 400 300

-j 0O 200 100 0 -

01-01-00 05-26-02 10-18-04 03-13-07 08-05-09 12-29-11 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-20 74 of 126

FIGURE C-3 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2011 Q-35 McMillan Well 500 400 300

-J a.

200 100 0 ,1-12-31-99 05-25-02 10-17-04 03-12-07 08-04-09 12-28-11 Q-36 Cordova Well 500 400 300

,.I CL 200 100 0 4-12-31-99 05-25-02 10-17-04 03-12-07 08-04-09 12-28-11 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-21 75 of 126

FIGURE C-4 Air Particulates - Gross Beta- Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2011 Q-01 Onsite No. I 70.0 60.0 50.0 E

40.0 uJ 30.0 C

20.0 10.0 .

0.0 01-07-00 05-31-02 10-22-04 03-16-07 08-07-09 12-30-11 Q-02 Onsite No. 2 70.0 60.0 50.0 40.0 0.

C-,

LU 30.0 C?

20.0 10.0 0.0 01-07-00 05-31-02 10-22-04 03-16-07 08-07-09 12-30-11 C-22 76 of 126

FIGURE C-5 Air Particulates - Gross Beta- Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2011 Q-03 Onsite No. 3 60.0 50.0 40.0 m

30.0 LU CD 20.0 10.0 0.0 01-07-00 05-31-02 10-22-04 03-16-07 08-07-09 12-30-11 Q-04 Nitrin 60.0 50.0 40.0 M

30.0 CL m 20.0 10.0 0.0 01-07-00 05-31-02 10-22-04 03-16-07 08-07-09 12-30-11 C-23 77 of 126

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 E

40.0 0.

30.0 ILU

'- 20.0 10.0 0.0 1-01-07-00 01-26-02 02-15-04 03-06-06 03-25-08 04-14-10 This location was removed from the program due to updated annual average meteorology.

C-24 78 of 126

FIGURE C-7 Air Particulates - Gross Beta- Stations Q-13 and Q-16 Collected in the Vicinity of QCNPS, 2005 - 2011 Q-13 Princeton 60.0 50.0 40.0 C) a.

30.0 9

w C 20.0 10.0 0.0 -

07-08-05 10-24-06 02-09-08 05-27-09 09-12-10 12-29-11 Q-16 Low Moor 60.0 50.0 40.0 30.0 20.0 10.0 0.0 07-08-05 10-24-06 02-09-08 05-27-09 09-12-10 12-29-11 AIR PARTICULATE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 C-25 79 of 126

FIGURE C-8 Air Particulates - Gross Beta- Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2011 Q-37 Meredosia Road 60.0 50.0 40.0 m

C., 30.0 9

uJ 20.0 10.0 0.0 I 07-08-05 10-24-06 02-09-08 05-27-09 09-12-10 12-29-11 Q-38 Fuller Road 60.0 50.0 40.0 0.

C',

30.0 9

20.0 10.0 0.0 I 07-08-05 10-24-06 02-09-08 05-27-09 09-12-10 12-29-11 AIR PARTICULATE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 C-26 80 of 126

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

Collected in the Vicinity of QCNPS, 2009 - 2011 Q-41 Camanche 50.0 40.0 30.0 C,

9.

9p 20.0 uJ.

C 10.0 0.0 -

01-03-09 08-09-09 03-15-10 10-19-10 05-25-11 12-29-11 Q-42 LeClaire (Control) 40.0 30.0 C) w3 20.0 9C' 10.0 0.0 -

12-31-10 03-14-11 05-26-11 08-07-11 10-19-11 12-31-11 C-27 81 of 126

Intentionally left blank 82 of 126

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM 83 of 126

Intentionally left blank 84 of 126

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

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

March 2011 E7460-396 Milk Sr-89 pCi/L 98.8 97.4 1.01 A Sr-90 pCi/L 15.2 15.8 0.96 A E7461-396 Milk 1-131 pCi/L 92.9 96.9 0.96 A Ce-141 pCi/L not provided by Analytics for this study Cr-51 pCi/L 398 298 1.34 N (1)

Cs-134 pCi/L 130 130 1.00 A Cs-137 pCi/L 232 205 1.13 A Co-58 pCi/L 121 113 1.07 A Mn-54 pCi/L 289 266 1.09 A Fe-59 pCi/L 201 175 1.15 A Zn-65 pCi/L 287 261 1.10 A Co-60 pCi/L 186 172 1.08 A E7463-396 AP Ce-141 pCi not provided by Analytics for this study Cr-51 pCi 243 215 1.13 A Cs-1 34 pCi 85.0 94.2 0.90 A Cs-1 37 pCi 168 148 1.14 A Co-58 pCi 89.2 81.8 1.09 A Mn-54 pCi 171 192 0.89 A Fe-59 pCi 129 126 1.02 A Zn-65 pCi 159 189 0.84 A Co-60 pCi 132 124 1.06 A E7462-396 Charcoal 1-131 pCi 96.5 96.3 1.00 A June 2011 E7851-396 Milk Sr-89 pCi/L 96.7 103 0.94 A Sr-90 pCi/L 13.8 15.6 0.88 A E7852-396 Milk 1-131 pCi/L 110 103.0 1.07 A Ce-141 pCi/L 68.1 79.9 0.85 A Cr-51 pCi/L 186 206 0.90 A Cs-134 pCi/L 164 190 0.86 A Cs-137 pCi/L 140 138 1.01 A Co-58 pCi/L 141 152 0.93 A Mn-54 pCi/L 136 138 0.99 A Fe-59 pCi/L 128 123 1.04 A Zn-65 pCi/L 263 261 1.01 A Co-60 pCi/L 189 195 0.97 A E7854-396 AP Ce-141 pCi 49.9 42.9 1.16 A Cr-51 pCi 95.6 110 0.87 A Cs-1 34 pCi 104 102 1.02 A Cs-137 pCi 83.8 74.0 1.13 A Co-58 pCi 90.7 81.3 1.12 A Mn-54 pCi 74.5 73.9 1.01 A Fe-59 pCi 62.0 66.1 0.94 A Zn-65 pCi 140 140 1.00 A Co-60 pCi 119 104 1.14 A E7853-396 Charcoal 1-131 pCi 76.2 86.1 0.89 A D-1 85 of 126

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

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

September2011 E8070-396 Milk Sr-89 pCi/L 102 90.8 1.12 A Sr-90 pCi/L 13.2 14.7 0.90 A E8071-396 Milk 1-131 pCi/L 74.2 89.2 0.83 A Ce-141 pCi/L 66.9 66.7 1.00 A Cr-51 pCi/L 249 226 1.10 A Cs- 134 pCi/L 116 128 0.91 A Cs-137 pCi/L 106 114 0.93 A Co-58 pCi/L 95.4 97.5 0.98 A Mn-54 pCi/L 147 151 0.97 A Fe-59 pCi/L 53.1 54.8 0.97 A Zn-65 pCi/L 175 180 0.97 A Co-60 pCi/L 150 157 0.96 A E8073-396 AP Ce-141 pCi 66.6 67.5 0.99 A Cr-51 pCi 263 229 1.15 A Cs-i 34 pCi 139 130 1.07 A Cs-137 pCi 110 115 0.96 A Co-58 pCi 108 98.6 1.10 A Mn-54 pCi 152 153 0.99 A Fe-59 pCi 57.5 55.5 1.04 A Zn-65 pCi 190 183 1.04 A Co-60 pCi 156 159 0.98 A E8072-396 Charcoal 1-131 pCi 77.6 80.6 0.96 A December, 2011 E8230-396 Milk Sr-89 pCi/L 93.3 93.1 1.00 A Sr-90 pCi/L 12.7 15.4 0.82 A E8231-396 Milk 1-131 pCi/L 82.5 90.2 0.91 A Ce-141 pCi/L not provided by Analytics for this study Cr-51 pCi/L 465 566 0.82 A Cs-134 pCi/L 142 171 0.83 A Cs-137 pCi/L 185 210 0.88 A Co-58 pCi/L 177 221 0.80 A Mn-54 pCi/L 208 241 0.86 A Fe-59 pCi/L 164 183 0.90 A Zn-65 pCi/L 259 291 0.89 A Co-60 pCi/L 224 270 0.83 A E8233-396 AP Ce-141 pCi not provided by Analytics for this study Cr-51 pCi 344 368 0.93 A Cs-1 34 pCi 105 111 0.95 A Cs-1 37 pCi 129 137 0.94 A Co-58 pCi 145 144 1.01 A Mn-54 pCi 137 157 0.87 A Fe-59 pCi 119 119 1.00 A Zn-65 pCi 145 190 0.76 W Co-60 pCi 168 176 0.95 A D-2 86 of 126

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

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

December 2011 E8232-396 Charcoal 1-131 pCi 100 89.5 1.12 A (1) Sample appearsto be biasedhigh. Corrective Action evaluated after the 2nd QuarterAnalytics PE sample; no action required. NCR 11-13 (a) Teledyne Brown Engineeringreportedresult.

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

(c) Ratio of Teledyne Brown Engineeringto Analytics results.

(d) Analytics evaluation basedon TBE internal QC limits: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20.

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

D-3 87 of 126

TABLE D-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE I OF 1)

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

May 2011 RAD-85 Water Sr-89 pCi/L 59.8 63.2 51.1 -71.2 A Sr-90 pCi/L 42.5 42.5 31.3 -48.8 A Ba-133 pCi/L 73.3 75.3 63.0 - 82.8 A Cs- 134 pCi/L 64.9 72.9 59.5 - 80.2 A Cs-137 pCi/L 74.6 77.0 69.3 - 87.4 A Co-60 pCi/L 87.8 88.8 79.9- 100 A Zn-65 pCi/L 103 98.9 89.0-118 A Gr-A pCi/L 64.1 50.1 26.1 -62.9 N (i)

Gr-B pCi/L 51.8 49.8 33.8 - 56.9 A 1-131 pCi/L 27.4 27.5 22.9 - 32.3 A U-Nat pCi/L 38.5 39.8 32.2-44.4 A H-3 pCi/L 10057 10200 8870-11200 A MRAD-14 Filter Gr-A pCi/filter 79.7 74.3 38.5-112 A November 2011 RAD-87 Water Sr-89 pCi/L 81.0 69.7 56.9 - 77.9 N (2)

Sr-90 pCi/L 35.5 41.4 30.2 -47.2 A Ba-133 pCi/L 90.7 96.9 81.8- 106 A Cs-1 34 pCi/L 36.6 33.4 26.3 - 36.7 A Cs-137 pCi/L 44.7 44.3 39.4-51.7 A Co-60 pCi/L 118.7 119 107- 133 A Zn-65 pCi/L 80.2 76.8 68.9 - 92.5 A Gr-A pCi/L 34.2 53.2 27.8 - 66.6 A Gr-B pCi/L 39.3 45.9 30.9 - 53.1 A 1-131 pCi/L 22.9 27.5 22.9 - 32.3 A U-Nat pCi/L 46.8 48.6 39.4 - 54.0 A H-3 pCi/L 15733 17400 15200- 19100 A MRAD-15 Filter Gr-A pCi/filter 44.6 58.4 30.3 - 87.8 A (1) The solids on the planchet exceeded 100 mg, which was beyond the range of the efficiency curve. NCR 11-08 (2) Sr-89 TBE to known ratio off. 16 fell within acceptable range of +/- 20%. No action required. NCR 11-16 (a) Teledyne Brown Engineeringreportedresult.

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

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

D-4 88 of 126

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

TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 2)

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

March 2011 11-MaW24 Water Cs-134 Bq/L 19.1 21.5 15.1 -28.0 A Cs-137 Bq/L 29.0 29.4 20.6 - 38.2 A Co-57 Bq/L 0.139 (1) A Co-60 Bq/L 23.9 24.6 17.2 - 32.0 A H-3 Bq/L 265 243 170-316 A Mn-54 Bq/L 31.8 31.6 22.1 -41.1 A K-40 Bq/L 94.8 91 64-118 A Sr-90 Bq/L 9.64 8.72 6.10-11.34 A Zn-65 Bq/L -0.142 (1) A 11-GrW24 Water Gr-A Bq/L 0.767 1.136 0.341 -1.931 A Gr-B Bq/L 3.43 2.96 1.48 - 4.44 A 11 -MaS24 Soil Cs-1 34 Bq/kg 612 680 476-884 A Cs-1 37 Bq/kg 772 758 531 -985 A Co-57 Bq/kg 910 927 649-1205 A Co-60 Bq/kg 500 482 337-627 A Mn-54 Bq/kg 0.607 (1) A K-40 Bq/kg 569 540 378-702 A Sr-90 Bq/kg NR 160 112-208 N (2)

Zn-65 Bq/kg 1497 1359 951-1767 A 11-Rd F24 AP Cs-134 Bq/sample 3.26 3.49 2.44 - 4.54 A Cs-1 37 Bq/sample 2.36 2.28 1.60 - 2.96 A Co-57 Bq/sample 3.30 3.33 2.33 - 4.33 A Co-60 Bq/sample 0.0765 (1) A Mn-54 Bq/sample 2.84 2.64 1.85 - 3.43 A Sr-90 Bq/sample NR 1.36 0.95 - 1.77 N (2)

Zn-65 Bq/sample 3.30 3.18 2.23-4.13 A 11-GrF24 AP Gr-A Bq/sample 0.101 0.659 0.198 - 1.120 N (3)

Gr-B Bq/sample 1.23 1.323 0.662 - 1.985 A 11-RdV24 Vegetation Cs-134 Bq/sample 4.97 5.50 3.85 - 7.15 A Cs-1 37 Bq/sample 0.0356 (1) A Co-57 Bq/sample 10.8 9.94 6.96-12.92 A Co-60 Bq/sample 4.89 4.91 3.44 - 6.38 A Mn-54 Bq/sample 6.42 6.40 4.48 - 8.32 A Sr-90 Bq/sample NR 2.46 1.72 - 3.20 N (2)

Zn-65 Bq/sample 3.07 2.99 2.09 - 3.89 A September 2011 11-MaW25 Water Cs-1 34 Bq/L 16.0 19.1 13.4-24.8 A Cs- 137 Bq/L 0.0043 (1) A Co-57 Bq/L 33.1 36.6 25.6 - 47.6 A Co-60 Bq/L 26.9 29.3 20.5 - 38.1 A H-3 Bq/L 1011 1014 710 - 1318 A Mn-54 Bq/L 23.2 25.0 17.5 - 32.5 A K-40 Bq/L 147 156 109-203 A Sr-90 Bq/L 15.8 14.2 9.9- 18.5 A Zn-65 Bq/L 27.3 28.5 20.0 - 37.1 A D-5 89 of 126

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

TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 2)

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

September 2011 11-GrW25 Water Gr-A Bq/L 0.894 0.866 0.260 - 1.472 A Gr-B Bq/L 5.87 4.81 2.41 - 7.22 A 11-MaS25 Soil Cs- 134 Bq/kg -0.213 (1) A Cs-1 37 Bq/kg 1110 979 685-1273 A Co-57 Bq/kg 1290 1180 826 - 1534 A Co-60 Bq/kg 731 644 451 - 837 A Mn-54 Bq/kg 987 848 594 - 1102 A K-40 Bq/kg 753 625 438-813 W Sr-90 Bq/kg 276 320 224-416 A Zn-65 Bq/kg 1870 1560 1092-2028 A September 2011 11-RdF25 AP Cs-134 Bq/sample -0.043 (1) A Cs-137 Bq/sample 3.09 2.60 1.82 -3.38 A Co-57 Bq/sample 5.36 5.09 3.56 - 6.62 A Co-60 Bq/sample 3.41 3.20 2.24-4.16 A Mn-54 Bq/sample 0.067 (1) A Sr-90 Bq/sample 1.84 1.67 1.17-2.17 A Zn-65 Bq/sample 5.17 4.11 2.88 - 5.34 W 11-GrF25 AP Gr-A Bq/sample 0.0058 (1) A Gr-B Bq/sample -0.01 (1) A 11-RdV25 Vegetation Cs-1 34 Bq/sample 0.0081 (1) A Cs-1 37 Bq/sample 4.94 4.71 3.30 - 6.12 A Co-57 Bq/sample 0.0639 (1) A Co-60 Bq/sample 3.36 3.38 2.37 - 4.39 A Mn-54 Bq/sample 5.89 5.71 4.00 - 7.42 A Sr-90 Bq/sample 1.31 1.26 0.88 - 1.64 A Zn-65 Bq/sample 6.54 6.39 4.47 - 8.31 A (1) Falsepositive test (2) Evaluated as failed due to not reportinga previously reported analyte. NCR 11-11 (3) The filterfor Gross Alpha was counted on the wrong side. Recounted on the correct side resulted in acceptable results. NCR 11-11 (a) Teledyne Brown Engineeringreportedresult.

(b) The MAPEP known value is equal to 100% of the parameterpresent in the standardas determinedby gravimetricand/or volumetric measurements made duringstandardpreparation.

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

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TABLE D-4 ERA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAMa ENVIRONMENTAL, INC., 2011 (Page I of 1)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance STW-1 243 04/04/11 Sr-89 68.2 +/- 5.8 63.2 51.1 -71.2 Pass STW-1243 04/04/11 Sr-90 44.3 +/- 2.4 42.5 31.3 -48.8 Pass STW-1244 04/04/11 Ba-133 69.8 +/- 3.9 75.3 63.0 - 82.8 Pass STW-1 244 04/04/11 Co-60 87.9 +/- 3.8 88.8 79.9 -100.0 Pass STW-1244 04/04/11 Cs-134 69.5 +/- 3.7 72.9 59.5 - 80.2 Pass STW-1244 04/04/11 Cs-137 77.9 +/- 5.3 77.0 69.3 -87.4 Pass STW-1244 04/04/11 Zn-65 105.2 +/- 8.4 98.9 89.0 -118.0 Pass STW-1245 04/04/11 Gr. Alpha 41.5 +/- 2.3 50.1 26.1 - 62.9 Pass STW-1245 04/04/11 Gr. Beta 48.9 +/- 1.8 49.8 33.8 - 56.9 Pass STW-1246 04/04/11 1-131 26.6 +/- 1.7 27.5 22.9 - 32.3 Pass STW-1248 04/04/11 H-3 10322 +/-285 10200.0 8870-11200 Pass STW-1256 10/07/11 Sr-89 68.7 +/- 6.0 69.7 56.9 - 77.9 Pass STW-1 256 10/07/11 Sr-90 36.9 +/- 2.4 41.1 30 472 Pass STW-1257 10/07/11 Ba-1 33 88.2 +/- 7.8 96.9 81.8 -106.0 Pass STW-1257 10/07/11 Co-60 116.5 +/- 7.1 119.0 107.0 -133.0 Pass STW-1257d 10/07/11 Cs-1 34 38.8 +/- 8.0 33.4 26.3 -36.7 Fail STW-1 257 10/07/11 Cs-137 45.6 +/- 7.3 44.3 39.4 -51.7 Pass STW-1257 10/07/11 Zn-65 84.9 +/- 15.4 76.8 68.9 -92.5 Pass STW-1258 10/07/11 Gr. Alpha 35.7 +/- 3.8 53.2 27.8 -66.6 Pass STW-1258 10/07/11 Gr. Beta 36.1 +/- 3.3 45.9 30.9 -53.1 Pass STW-1 259 10/07/11 1-131 25.0 +/- 1.1 27.5 22.9 -32.3 Pass STW-1 261 10/07/11 H-3 17435 +/-382 17400 15200 -19100 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 The sample was reanalyzed. Result of reanalysis was acceptable, 32.9 +/- 7.4 pCi/L.

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TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2011 (Page 1 of 2)

Concentration b Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STW-1237 02/01/11 Co-57 < 0.2 0.00 Pass STW-1237 02/01/11 Co-60 24.10 +/- 0.40 24.60 17.20 - 32.00 Pass STW-1237 02/01/11 Cs- 134 19.80 +/- 0.40 21.50 15.10 - 28.00 Pass STW-1237 02/01/11 Cs- 137 29.40 +/- 0.50 29.40 20.60 - 38.20 Pass STW-1237 02/01/11 H-3 238.90 +/- 8.80 243.00 170.00 - 316.00 Pass STW-1237 02/01/11 K-40 95.40 +/- 3.10 91.00 64.00 - 118.00 Pass STW-1237 02/01/11 Mn-54 32.50 +/- 0.60 31.60 22.10 - 41.10 Pass STW-1237 02/01/11 Sr-90 8.70 +/- 0.70 8.72 6.10 - 11.34 Pass STW-1237 02/01/11 Zn-65 < 0.5 0.00 Pass STW-1238 02/01/11 Gr. Alpha 0.82 +/- 0.07 1.14 0.34 -1.93 Pass STW-1238 02/01/11 Gr. Beta 2.82 +/- 0.07 2.96 1.48 -4.44 Pass STVE-1239 02/01/11 Co-57 11.27 +/- 0.21 9.94 6.96 - 12.92 Pass STVE-1239 02/01/11 Co-60 4.95 +/- 0.16 4.91 3.44 - 6.38 Pass STVE-1239 02/01/11 Cs-1 34 5.18 +/- 0.19 5.50 3.85 -7.15 Pass STVE-1239 02/01/11 Cs-1 37 < 0.09 0.00 Pass STVE-1239 02/01/11 Mn-54 6.91 +/- 0.25 6.40 4.48 - 8.32 Pass STVE-1239 02/01/11 Zn-65 3.10 +/- 0.32 2.99 2.09 - 3.89 Pass STSO-1240 02/01/11 Co-57 984.10 +/- 4.10 927.00 649.00 - 1205.00 Pass STSO-1240 02/01/11 Co-60 540.70 +/- 3.00 482.00 337.00 - 627.00 Pass STSO-1240 02/01/11 Cs-1 34 726.70 +/- 5.92 680.00 476.00 - 884.00 Pass STSO-1240 02/01/11 Cs-1 37 883.10 +/- 4.70 758.00 531.00 - 985.00 Pass STSO-1240 02/01/11 K-40 622.70 +/- 16.70 540.00 378.00 - 702.00 Pass STSO-1240 02/01/11 Mn-54 -0.30 +/- 1.00 0.00 Pass STSO-1240 02/01/11 Zn-65 1671.00 +/- 13.10 1359.00 951.00 - 1767.00 Pass STAP-1241 02/01/11 Co-57 3.48 +/- 0.06 3.33 2.33 -4.33 Pass STAP-1241 02/01/11 Co-60 0.00 +/- 0.02 0.00 -0.10 -0.10 Pass STAP-1 241 02/01/11 Cs-1 34 3.44 +/- 0.27 3.49 2.44 -4.54 Pass STAP-1241 02/01/11 Cs-1 37 2.46 +/- 0.27 2.28 1.60 -2.96 Pass STAP-1241 02/01/11 Gr. Alpha 0.39 +/- 0.05 0.66 0.20 -1.12 Pass STAP-1241 02/01/11 Gr. Beta 1.54 +/- 0.07 1.32 0.66 -1.99 Pass STAP-1241 02/01/11 Mn-54 2.90 +/- 0.10 2.64 1.85 -3.43 Pass STAP-1241 e 02/01/11 Sr-90 1.89 +/- 0.15 1.36 0.95 - 1.77 Fail STAP-1 241 02/01/11 Zn-65 3.80 +/- 0.18 3.18 2.23 -4.13 Pass STVE-1250 08/01/11 Co-57 0.01 +/- 0.02 0.00 Pass STVE-1250 08/01/11 Co-60 3.57 +/- 0.13 3.38 2.37 - 4.39 Pass STVE-1 250 08/01/11 Cs-134 -0.02 +/- 0.04 0.00 -0.10 -0.10 Pass STVE-1 250 08/01/11 Cs-137 5.28 +/- 0.20 4.71 3.30 -6.12 Pass STVE-1 250 08/01/11 Mn-54 6.48 +/- 0.22 5.71 4.00 - 7.42 Pass STVE-1 250 08/01/11 Zn-65 7.35 +/- 0.34 6.39 4.47 - 8.31 Pass D-8 92 of 126

TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)8 ENVIRONMENTAL, INC., 2011 (Page 2 of 2)

Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STSO-1251 08/01/11 Co-57 1333.90 +/- 4.20 1180.00 826.00 - 1534.00 Pass STSO-1251 08/01/11 Co-60 701.30 +/- 3.40 644.00 451.00 - 837.00 Pass STSO-1251 08/01/11 Cs-1 34 0.71 +/- 1.05 0.00 Pass STSO-1251 08/01/11 Cs- 137 1106.00 +/- 5.60 979.00 685.00 - 1273.00 Pass STSO-1251 08/01/11 K-40 749.20 +/- 19.00 625.00 438.00 - 813.00 Pass STSO-1251 08/01/11 Mn-54 984.30 +/- 5.40 848.00 594.00 - 1102.00 Pass STSO-1251 f 08/01/11 Sr-90 219.40 +/- 16.70 320.00 224.00 - 416.00 Fail STSO-1251 08/01/11 Zn-65 1639.90 +/- 11.40 1560.00 1092.00 - 2028.00 Pass STAP-1252 08/01/11 Co-57 5.06 +/- 0.08 5.09 3.56 - 6.62 Pass STAP-1252 08/01/11 Co-60 3.13 +/- 0.09 3.20 2.24 -4.16 Pass STAP-1252 08/01/11 Cs-1 34 0.01 +/- 0.03 0.00 -0.10 -0.10 Pass STAP-1252 08/01/11 Cs-1 37 2.61 +/- 0.09 2.60 1.82 -3.38 Pass STAP-1252 08/01/11 Mn-54 0.01 +/- 0.03 0.00 -0.10 -0.10 Pass STAP-1 252 08/01/11 Sr-90 1.65 +/- 0.16 1.67 1.17 -2.17 Pass STAP-1 252 08/01/11 Zn-65 4.46 +/- 0.23 4.11 2.88 - 5.34 Pass STW-1254 08/01/11 Co-57 37.20 +/- 0.50 36.60 25.60 - 47.60 Pass STW-1 254 08/01/11 Co-60 28.80 +/- 0.40 29.30 20.50 - 38.10 Pass STW-1 254 08/01/11 Cs-134 18.00 +/- 0.60 19.10 13.40 - 24.80 Pass STW-1254 08/01/11 Cs-137 0.06 +/- 0.13 0.00 Pass STW-1 254 08/01/11 H-3 1039.90 +/- 17.90 1014.00 710.00 - 1318.00 Pass STW-1 254 08/01/11 K-40 161.40 +/- 4.10 156.00 109.00 - 203.00 Pass STW-1 254 08/01/11 Mn-54 25.70 +/- 0.50 25.00 17.50 - 32.50 Pass STW-1 254 08/01/11 Sr-90 15.60 +/- 1.80 14.20 9.90 - 18.50 Pass STW-1254 08/01/11 Zn-65 30.20 +/- 0.90 28.50 20.00 - 37.10 Pass STW-1255 08/01/11 Gr. Alpha 0.72 +/- 0.12 0.87 0.26 -1.47 Pass STW-1 255 08/01/11 Gr. Beta 4.71 +/- 0.15 4.81 2.41 - 7.22 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

d 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.

e No errors found in calculation or procedure, results of reanalysis; 1.73 Bq/filter.

f The analyses were repeated through a strontium column; mean result of triplicate analyses, 304.2 Bq/kg.

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APPENDIX E ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR) 95 of 126

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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 2011 Prepared By Teledyne Brown Engineering Environmental Services Exelkn .

Nuclear Quad Cities Nuclear Power Station Cordova, IL 61242 May 2012 97 of 126

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Table Of Contents I. Sum m ary and Conclusion ........................................................................................... 3 I1. Introduction ..................................................................................................................... 7 A. O bjectives of the RG PP ................................................................................. 7 B. Im plem entation of the O bjectives .................................................................... 7 C. Program Description ..................................................................................... 8 Ill. Program Description ................................................................................................. 8 A. Sam ple Analysis ............................................................................................. 8 B. Data Interpretation ........................................................................................... 9 IV. Results and Discussion .......................................................................................... 10 A . G roundwater Results .................................................................................... 10 B. Surface W ater Results ................................................................................. 11 C. Summary of Results - Inter-laboratory Comparison Program ...................... 12 D. Leaks, Spills, and Releases ........................................................................ 12 E. Trends ............................................................................................................... 12 F. Investigations ................................................................................................. 12 G . Actions Taken ............................................................................................... 12 99 of 126

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2011 Figures Figure A-1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2011 Figure A-2 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2011 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, 2011.

Table B-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table B-1.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table B-11.1 Concentrations of Tritium and Strontium in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2011.

Table B-Ill.1 Concentrations of Tritium in Groundwater Samples Collected and Anaylzed by Quad Cities Station Personnel, 2011.

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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 2011 through 31 December 2011.

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

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

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

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

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

In 2011 Conestoga-Rovers & Associates (CRA) completed a five-year update hydrogeologic investigation report for the Station (NEI 07-07, Hydrogeologic Investigation Report, dated May 2011). The referenced report summarized station activities since the 2006 hydrogeologic investigation report, including 101 of 126

changes at the Station as well as RGPP sampling activities and groundwater flow. In 2011 the Station also performed a 5 year review and update of the site risk assessments of Systems, Structures, and Components (SSCs) that contain or could contain licensed material and for which there is a credible mechanism for licensed material to reach groundwater.

A 2011 change to the RGPP consisted of designating wells into categories. Well designation categories include background, detection, elevated, long-term shut down, plume, and idle. The RGPP also requires the sampling of surface water locations that may be impacted due to a spill or release.

This report covers groundwater samples, collected from the environment on station property in 2011. During that time period, RGPP samples were collected from 40 locations.

2011 sample locations included thirty-three designated monitoring wells, two surface water monitoring points, 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, gross 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 207,000 pCi/L in a monitoring well. Tritium concentrations ranged from less than the LLD of 200 pCi/L to 679 pCi/L in surface water monitoring locations.

Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater samples. In the case of tritium, Exelon specified that it's 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-90 was not detected at concentrations greater than the Lower Limit of Detection (LLD) of 1.0 pCi/L.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second and third quarter sampling in 2011. Gross Alpha (dissolved) was detected in one groundwater sample at a concentration of 2.4 pCi/L. Gross Alpha (suspended) was not 102 of 126

detected at any of the groundwater locations. Gross Beta (dissolved) was detected in 8 of 9 groundwater locations. The concentrations ranged from 2.2 to 20.1 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations.

Hard-To-Detect analyses was performed on one upgradient monitoring well location (MW-QC-1071) to establish background levels and on one monitoring well designated as "elevated" (QC-GP-15). 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.

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

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

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

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

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

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

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

B. Implementation of the Objectives The objectives identified have been implemented at Quad Cities Nuclear Power Station as discussed below:

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

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

3. Quad Cities Nuclear Power Station will continue to perform routine 105 of 126

sampling and radiological analysis of water from selected locations.

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

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

C. Program Description

1. Sample Collection Sample locations can be found in Table A-1 and Figures A-1 & A-2, Appendix A.

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

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

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

Ill. Program Description This section covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2011.

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 2011.

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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 and surface water.

3. Concentrations of tritium in groundwater and surface water.

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

5. Concentrations of Am-241 in groundwater.

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

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

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

9. Concentrations of Fe-55 in groundwater.

10. Concentrations of Ni-63 in groundwater.

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

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

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

Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from calibration standards, sample volume or weight 107 of 126

measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of a measurement created by statistical process (counting error) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated. Exelon reports the TPU by following the result with plus or minus +/- the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.

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

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

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

IV. Results and Discussion A. Groundwater Results Groundwater Samples were collected from on-site wells in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.

Tritium Samples from all locations were analyzed for tritium activity (Table B-1.1 & B-Ill.1 Appendix B). Tritium values ranged from the detection limit to 207,000 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-90 was not detected above the Lower Limit of Detection (LLD) of 1.0 pCi/L (Table B-I.1 Appendix B) 108 of 126

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions performed on groundwater samples during the second and third quarter sampling in 2011. Gross Alpha (dissolved) was detected in one groundwater sample at a concentration of 2.4 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations. Gross Beta (dissolved) was detected in 8 of 9 groundwater locations. The concentrations ranged from 2.2 to 20.1 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations (Table B-1.1 Appendix B).

Gamma Emitters No gamma emitting nuclides were detected (Table B-1.2, Appendix B)

Hard-To-Detect Hard-To-Detect analyses were performed on one groundwater location and one sentinel well to establish background levels. 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).

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

Tritium was detected above the detection limit of 200 pCi/I in three of 8 samples. The concentrations ranged from 341 to 679 pCi/L (Table B-11.1 Appendix B).

Strontium Strontium-90 was not detected above the Lower Limit of Detection (LLD) of 1.0 pCi/L (Table B-11.1 Appendix B).

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

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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 2011.

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 111 of 126

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TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2011 Site Site Type Well Designation Minimum Sample Frequency MW-QC-1 Monitoring Well Plume Quarterly MW-QC-2 Monitoring Well Plume Quarterly MW-QC-1011 Monitoring Well Idle Not Required MW-QC-101S Monitoring Well Idle Not Required MW-QC-102D Monitoring Well Plume Quarterly MW-QC-1021 Monitoring Well Plume Quarterly MW-QC-102S Monitoring Well Plume Quarterly MW-QC-1031 Monitoring Well Detection Quarterly MW-QC-104S Monitoring Well Detection Quarterly MW-QC-1051 Monitoring Well Plume Quarterly MW-QC-1061 Monitoring Well Plume Quarterly MW-QC-106S Monitoring Well Plume Quarterly MW-QC-1071 Monitoring Well Background Annual MW-QC-108D Monitoring Well Plume Quarterly MW-QC-1081 Monitoring Well Plume Quarterly MW-QC-108S Monitoring Well Plume Quarterly MW-QC-1091 Monitoring Well Plume Quarterly MW-QC-109S Monitoring Well Plume Quarterly MW-QC-1101 Monitoring Well Idle Not Required MW-QC-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-i 16S 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 Note: Idle designated wells are not required to be sampled as part of the RGPP A-1 113 of 126

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Intentionally left blank 116 of 126

APPENDIX B DATA TABLES 117 of 126

Intentionally left blank 118 of 126

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, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 GR-A (DIS) GR-A (SUS) GR-B (DIS) GR-B (SUS)

QC-GP-10 08/10/11 < 0.8 < 0.9 < 1.4 9.9 +/- 1.4 < 1.6 QC-GP-1 1 08/11/11 < 0.6 < 0.9 < 1.4 5.4 +/- 1.2 < 1.6 QC-GP-12 08/11/11 < 0.4 < 0.8 < 0.5 2.2 +/- 0.8 < 1.6 QC-GP-14 08/11/11 < 0.7 < 1.0 < 0.5 4.6 +/- 1.1 < 1.6 QC-GP-15 08/10/11 < 0.6 < 4.3 < 0.8 16.5 +/- 1.9 < 1.4 QC-GP-16 08/11/11 < 0.6 < 1.0 < 0.8 4.4 +/- 1.1 < 1.4 MW-QC-1 03/08/11 < 177 MW-QC-1 05/24/11 < 181 MW-QC-1 07/19/11 < 178 MW-QC-1 11/08/11 < 182 MW-QC-102D 03/08/11 2520 +/- 307 MW-QC-102D 05/24/11 3330 +/- 382 MW-QC-102D 07/19/11 3120 +/- 365 MW-QC-102D 11/09/11 1880 +/- 240 MW-QC-1021 03/08/11 602 t 137 MW-QC-1021 05/24/11 457 +/- 139 MW-QC-1021 07/19/11 461 +/- 139 MW-QC-1021 11/09/11 355 +/- 121 MW-QC-1 02S 03/08/11 < 177 MW-QC-1 02S 05/24/11 < 185 MW-QC-102S 07/19/11 < 186 MW-QC-102S 11/09/11 < 166 MW-QC-1031 03/08/11 < 179 MW-QC-1031 05/24/11 < 183 MW-QC-1031 07/19/11 < 184 < 0.7 < 1.2 < 0.5 12.3 +/- 1.4 < 1.6 MW-QC-1031 11/08/11 < 165 MW-QC-104S 03/08/11 9420 +/- 990 MW-QC-104S 05/24/11 1240 +/- 183 MW-QC-104S 07/19/11 555 +/- 145 < 0.8 2.4 +/- 1.5 <0.6 20.1 +/- 2.0 < 1.9 MW-QC-104S 11/08/11 489 +/- 130 MW-QC-1051 03/08/11 85500 +/- 8570 MW-QC-1051 05/24/11 < 184 MW-QC-1051 07/19/11 407 +/- 121 MW-QC-1051 11/08/11 10700 +/- 1110 MW-QC-1061 03/08/11 < 179 MW-QC-1061 05/24/11 < 184 MW-QC-1061 07/19/11 < 167 MW-QC-1061 11/08/11 < 162 MW-QC-106S 03/08/11 < 178 MW-QC-106S 05/24/11 < 182 MW-QC-106S 07/19/11 < 175 MW-QC-106S 11/08/11 < 166 MW-QC-1071 05/23/11 < 185 < 0.7 < 1.2 < 0.6 < 1.8 < 2.0 MW-QC-108D 03/09/11 1480 +/- 208 MW-QC-108D 05/25/11 1540 +/- 211 B-1 119 of 126

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, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 GR-A (DIS) GR-A (SUS) GR-B (DIS) GR-B (SUS)

MW-QC-108D 07/20/11 1840 +/- 231 MW-QC-108D 11/09/11 2300 +/- 278 MW-QC-1081 03/09/11

183 MW-QC-1081 05/25/11 3710 +/- 419 MW-QC-1081 07/20/11 6730 +/- 712 MW-QC-1081 11/09/11 529 +/- 130 MW-QC-108S 03/09/11

176 MW-QC-108S 05/25/11

184 MW-QC-108S 07/20/11 399 +/- 129 MW-QC-108S 11/09/11

168 MW-QC-1091 03/08/11

179 MW-QC-1091 05/24/11 266 +/- 129 MW-QC-1091 07/19/11

161 MW-QC-1091 11/08/11

167 MW-QC-109S 03/08/11

178 MW-QC-109S 05/24/11

184 MW-QC-109S 07/19/11

162 MW-OC-109S 11/08/11

167 MW-QC-1 121 03/07/11

178 MW-QC-1 121 05/23/11

188 MW-QC-1 121 07/18/11

161 MW-QC-1 121 11/07/11 < 167 MW-QC-2 03/08/11 < 176 MW-QC-2 05/24/11 < 185 MW-QC-2 07/19/11 < 162 MW-QC-2 11/08/11 < 172 B-2 120 of 126

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 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 QC-GP-10 08/10/11 < 20 < 17 <2 <2 <5 <2 4 <2 <4 < 11 <2 <2 < 19 <7 QC-GP-1 1 08/11/11 < 18 < 14 <2 <2 <4 <2 3 <2 <4 <9 <2 <2 < 17 <5 QC-GP-12 08/11/11 < 17 < 29 <2 <2 <4 <2 3 <2 <4 <9 <2 <2 < 16 <6 QC-GP-14 08/11/11 < 18 < 34 <2 <2 <5 <2 4 <2 <3 <9 <2 <2 < 17 <5 QC-GP-15 08/10/11 < 18 <34 <2 <2 <5 <2 4 <2 <4 <9 <2 <2 < 19 <7 QC-GP-16 08/11/11 < 14 < 22 <1 <2 <4 <1 3 <2 <3 <7 <1 <2 < 15 <4 MW-QC-1031 07/19/11 < 30 < 27 <3 <3 <7 <3 6 <4 <5 < 13 <3 <3 < 25 <8 MW-QC-104S 07/19/11 < 39 < 81 <4 <4 < 10 <4 9 <5 <8 < 14 <4 <4 < 32 < 12 MW-QC-1071 05/23/11 < 33 < 31 <3 <4 <9 <3 7 <4 <6 < 15 <4 <4 < 29 <9 0,,

TABLE B-1.3 CONCENTRATIONS OF HARD-TO-DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION AM-241 CM-242 CM-243/244 PU-238 PU-239/240 U-233/234 U-235 U-238 FE-55 NI-63 DATE QC-GP-15 08/10/11 < 0.14 < 0.07 < 0.13 < 0.17 < 0.06 < 0.09 < 0.03 < 0.04 < 73 < 4.4 MW-QC-1071 05/23111 < 0.17 < 0.12 < 0.12 < 0.03 < 0.10 < 0.02 < 0.05 < 0.06 < 149 < 3.8 0

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TABLE B-II.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 SURFACE WATER #1 03/07/11 < 179 SURFACE WATER #1 05/23/11 < 181 SURFACE WATER #1 07/18/11 373 +/- 121 < 0.9 SURFACE WATER #1 11/07/11 679 +/- 150 SURFACE WATER #2 03/07/11 < 181 SURFACE WATER #2 05/23/11 < 180 SURFACE WATER #2 07/18/11 341 +/- 118 < 0.9 SURFACE WATER #2 11/07/11 < 189 B-5 123 of 126

TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2011 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 #1 07/18/11 <37 <39 <4 <4 <9 <3 <8 <5 <7 <15 <4 <4 <29 <9 SURFACE WATER #2 07/18/11 <34 <70 <3 <4 <7 <3 <8 <4 <7 <14 <4 <3 <28 <8 0,

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TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2011 RESULTS IN UNITS OF PCI/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-1 01/06/11 25,500 Shallow Aquifer QC-GP-1 06/15/11 16,300 Shallow Aquifer QC-GP-1 08/10/11 15,000 Shallow Aquifer QC-GP-1 10/25/11 21,000 Shallow Aquifer QC-GP-2 01/06/11 <2,000 Shallow Aquifer QC-GP-2 04/06/11 <2,000 Shallow Aquifer QC-GP-2 06/16/11 <2,000 Shallow Aquifer QC-GP-2 08/10/11 <2,000 Shallow Aquifer QC-GP-2 10/25/11 <2,000 Shallow Aquifer QC-GP-3 06/15/11 <2,000 Shallow Aquifer QC-GP-4 01/06/11 44,100 Shallow Aquifer QC-GP-4 04/06/11 37,600 Shallow Aquifer QC-GP-4 06/15/11 71,200 Shallow Aquifer QC-GP-4 08/10/11 63,300 Shallow Aquifer QC-GP-4 10/25/11 58,900 Shallow Aquifer QC-GP-5 01/06/11 2,270 Shallow Aquifer QC-GP-5 04/06/11 <2,000 Shallow Aquifer QC-GP-5 06/16/11 15,800 Shallow Aquifer QC-GP-5 08/10/11 <2,000 Shallow Aquifer QC-GP-5 10/25/11 <2,000 Shallow Aquifer QC-GP-6 01/06/11 <2,000 Shallow Aquifer QC-GP-6 04/06/11 <2,000 Shallow Aquifer QC-GP-6 06/16/11 <2,000 Shallow Aquifer QC-GP-6 08/10/11 <2,000 Shallow Aquifer QC-GP-6 10/25/11 <2,000 Shallow Aquifer QC-GP-7 01/06/11 <2,000 Shallow Aquifer QC-GP-7 04/06/11 <2,000 Shallow Aquifer QC-GP-7 06/16/11 5,200 Shallow Aquifer QC-GP-7 08/10/11 3,110 Shallow Aquifer QC-GP-7 10/25/11 <2,000 Shallow Aquifer QC-GP-9 01/06/11 45,100 Shallow Aquifer QC-GP-9 04/06/11 <2,000 Shallow Aquifer QC-GP-9 04/29/11 12,900 Shallow Aquifer QC-GP-9 06/15/11 <2,000 Shallow Aquifer QC-GP-9 08/10/11 <2,000 Shallow Aquifer QC-GP-9 10/26/11 11,400 Shallow Aquifer QC-GP-10 01/06/11 <2,000 Shallow Aquifer QC-GP-10 04/06/11 <2,000 Shallow Aquifer QC-GP-10 06/16/11 <2,000 Shallow Aquifer QC-GP-10 08/10/11 <2,000 Shallow Aquifer QC-GP-10 10/25/11 <2,000 Shallow Aquifer QC-GP-11 01/06/11 2,710 Shallow Aquifer QC-GP-1 1 04/07/11 <2,000 Shallow Aquifer QC-GP-1 1 06/17/11 29,100 Shallow Aquifer QC-GP-1 1 08/11/11 6,170 Shallow Aquifer QC-GP-11 10/26/11 <2,000 Shallow Aquifer QC-GP-12 01/06/11 <2,000 Shallow Aquifer QC-GP-12 04/06/11 <2,000 Shallow Aquifer QC-GP-12 06/17/11 <2,000 Shallow Aquifer QC-GP-12 08/11/11 <2,000 Shallow Aquifer QC-GP-12 10/26/11 <2,000 Shallow Aquifer QC-GP-13 01/06/11 95,500 Shallow Aquifer B-7 125 of 126

TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2011 RESULTS IN UNITS OF PCI/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-13 04/06/11 18,000 Shallow Aquifer QC-GP-13 04/29/11 51,100 Shallow Aquifer QC-GP-13 06/16111 115,000 Shallow Aquifer QC-GP-13 08/10/11 98,700 Shallow Aquifer QC-GP-13 10/26/11 53,100 Shallow Aquifer QC-GP-14 01/06/11 3,350 Shallow Aquifer QC-GP-14 01/13/11 4,180 Shallow Aquifer QC-GP-14 04/07/11 50,700 Shallow Aquifer QC-GP-14 04/29/11 83,300 Shallow Aquifer QC-GP-14 06/17/11 102,000 Shallow Aquifer QC-GP-14 08/11/11 66,900 Shallow Aquifer QC-GP-14 10/26/11 5,840 Shallow Aquifer QC-GP-15 01/06/11 <2,000 Shallow Aquifer QC-GP-1 5 04/06/11 <2,000 Shallow Aquifer QC-GP-1 5 06/16/11 <2,000 Shallow Aquifer QC-GP-1 5 08/10/11 <2,000 Shallow Aquifer QC-GP-15 10/25/11 <2,000 Shallow Aquifer QC-GP-16 01/06/11 97,700 Shallow Aquifer QC-GP-16 04/06/11 207,000 Shallow Aquifer QC-GP-16 04/29/11 14,400 Shallow Aquifer QC-GP-16 06/17/11 81,700 Shallow Aquifer QC-GP-16 08/11/11 113,000 Shallow Aquifer QC-GP-16 10/26/11 115,000 Shallow Aquifer QC-GP-17 01/06/11 51,100 Shallow Aquifer QC-GP-1 7 01/13/11 66,400 Shallow Aquifer QC-GP-17 04/06/11 93,500 Shallow Aquifer QC-GP-17 04/29/11 5,180 Shallow Aquifer QC-GP-17 06/17/11 54,000 Shallow Aquifer QC-GP-17 08/11/11 34,200 Shallow Aquifer QC-GP-17 10/26/11 68,900 Shallow Aquifer MW-QC-1051 01/13/11 91,100 Shallow Aquifer MW-QC-1051 04/07/11 <2000 Shallow Aquifer Well #1 03/07/11 <200 Well #1 06/16/11 <200 Well #1 09/20/11 <200 Well #5 03/07/11 <200 Well #5 06/16/11 <200 Well #5 09/20/11 <200 Well #7 03/07/11 <200 Well #7 06/16/11 <200 Well #7 09/20/11 <200 Well #7 12/06/11 <200 Well #9 06/16/11 <200 Well #9 09/20/11 <200 Well #10 03/07/11 <200 Well #10 06/16/11 <200 Well #10 09/20/11 <200 B-8 126 of 126

SVP-12-045, Annual Radiological Environmental Operating Report

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