Text

Annual Radiological Environmental Operating Report
	ML20135H086
Person / Time
Site:	Quad Cities
Issue date:	05/14/2020
From:	Ohr K; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	SVP-20-035
	Download: ML20135H086 (111)
	v • d • e

Exelon Generation SVP-20-035 May 14, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRG Docket Nos. 50-254 and 50-265 Annual Radiological Environmental Operating Report Pursuant to Technical Specifications Section 5.6.2, enclosed is the 2019 Radiological Environmental Operating Report for Quad Cities Nuclear Power Station. This Report contains the results of the Radiological Environmental Monitoring Program (REMP). In addition, the 2019 Radiological Groundwater Protection Program (RGPP) Report is included as Appendix F of the enclosure.

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

~~~VQ~

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

Enclosure:

Annual Radiological Environmental Operating Report cc:

Regional Administrator-NRG Region Ill NRG Senior Resident Inspector - Quad Cities Nuclear Power Station

Docket No:

50-254 50-265 QUAD CITIES NUCLEAR POWER STATION UNITS 1and2 Annual Radiological Environmental Operating Report 1 January through 31 December 2019 Prepared By Teledyne Brown Engineering Environmental Services Exelon Generation,0 Quad Cities Nuclear Power Station Cordova, IL 61242 May 2020

Intentionally left blank

Table Of Contents I. Summary and Conclusions.............................................................................................. 1 II. Introduction..................................................................................................................... 3 A. Objectives of the REMP...................................................................................... 3 B. Implementation of the Objectives........................................................................ 3 C. Radiation and Radioactivity................................................................................. 3 D. Sources of Radiation........................................................................................... 4 Ill. Program Description...................................................................................................... 6 A. Sample Collection............................................................................................... 6 B. Sample Analysis.................................................................................................. 8 C. Data Interpretation.............................................................................................. 8 D. Program Exceptions............................................................................................ 9 E. Program Changes............................................................................................. 12 IV. Results and Discussion............................................................................................... 13 A. Aquatic Environment......................................................................................... 13

1. Surface Water......................................................................................... 13

2. Ground Water......................................................................................... 13

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

4. Sediment................................................................................................. 14 B. Atmospheric Environment................................................................................. 14 1. Airborne.................................................................................................. 14

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

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

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

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

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

Appendix A Tables Table A-1 Appendix B Tables Table B-1 Table B-2 Figures Figure B-1 Figure B-2 Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Table C-11.1 Table C-11.2 Appendices Radiological Environmental Monitoring Report Summary Radiological Environmental Monitoring Program Annual Summary for Quad Cities Nuclear Power Station, 2019 Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2019 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2019 Quad Cities REMP Sampling Locations - 2 Mile Radius, 2019 Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2019 Data Tables and Figures - Primary Laboratory Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Concentrations of Tritium, lron-55 and Nickel-63 in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 ii

Table C-111.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 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, 2019 Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Table C-Vl.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Table C-Vll.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Table C-Vll.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Table C-Vlll.1 Concentrations of Gamma Emitters in Food Product Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Table C-IX.1 Quarterly DLR Results for Quad Cities Nuclear Power Station, 2019 Table C-IX.2 Annual DLR Results Quad Cities Nuclear Power Station, 2019 Figures Figure C-1 Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 Figure C-7 Surface Water - Gross Beta - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2019 Surface Water - Tritium - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2019 Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2019 Air Particulates - Gross Beta - Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2019 Air Particulates - Gross Beta - Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2019.

Air Particulates - Gross Beta - Station Q-07 (C) Collected in the Vicinity of QCNPS, 2000 - 2010 Air Particulates - Gross Beta - Stations Q-13 and Q-16 Collected in the Vicinity of QCNPS, 2005 - 2019 iii

Figure C-8 Figure C-9 Appendix D Tables Table D-1 Table D-2 Table D-3 Table D-4 Table D-5 Appendix E Appendix F Air Particulates - Gross Beta - Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2019 Air Particulates - Gross Beta - Stations Q-41 and Q-42 (C) Collected in the Vicinity of QCNPS, 2009 - 2019 Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2019 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2019 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2019 ERA (a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2019 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2019 Errata Data Annual Radiological Groundwater Protection Program Report (ARGPPR) iv

I.

Summary and Conclusions In 2019, the Quad Cities Generating Station released to the environment th rough the radioactive effluent gaseous pathways, approximately 64.2 curies of noble gas, 7.87 E-03 curies of fission and activation products, 28.7 curies of Carbon-14 (C-14) and approximately 86.9 curies of tritium. The dose from both gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public. In 2019, Quad Cities Generating Station released to the environment, through the radioactive liquid effluent pathway, approximately 1.59E-01 curies of tritium. One liquid abnormal continuous release occurred from 04/16/2019 to 11/06/2019 as-part of remediation of a leak to onsite ground water. The results of those calculations and their comparison to the allowable limits were as follows:

NOTE:

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

Gaseous and liquid radiation doses to members of the public at locations Applicable Estimated Age Location

% of Site Effluents Organ Dose Group Distance Direction Applicable Limit Unit (meters)

(toward)

Limit Noble Gas Gamma - Air Dose 1.40E-03 All 1029 NNE 7.00E-03 20 mRad Noble Gas Beta - Air Dose 1.53E-04 All 1029 NNE 3.83E-04 40 mRad Iodine. Particulate Total Body 4.36E-02 Child 1029 NNE 1.74E-01 25 mrem C-14 & Tritium Iodine, Particulate Bone 2.01E-01 Child 1029 NNE 6.70E-01 30 mrem C-14 & Tritium Liquid Total Body 3.11E-07 N/A Mississippi River 5.18E-06 6

mrem Liquid Liver 3.11 E-07 N/A Mississippi River 1.56E-06 20 mrem Skyshine Total Body 7.69E+OO All 800 N

3.08E+01 25 mrem 40CFR190 Total Body (Gas+ Liq+

7.73E+OO All 800 N

3.09E+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 30.9% of the 25 mrem/yr limit. The largest component of 40CFR 190 dose is attributable to BWR skyshine from N-16. This value is conservatively calculated for the hypothetical maximum exposed member of the public.

This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Quad Cities Nuclear Power Station (QCNPS) by Exelon covers the period 01 January 2019 through 31 December 2019. During that time period, 1530 analyses were performed on 1418 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of QCNPS had no adverse radiological impact on the environment.

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

Fish (commercially and recreationally important species) and sediment samples were analyzed for concentrations of gamma-emitting nuclides. No fission or activation products were detected in fish samples. Cesium-137 (Cs-137) was not detected above the required LLD in any sediment samples.

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

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

Cow milk samples were analyzed for concentrations of 1-131 and gamma-emitting nuclides. No 1-131 was detected. Concentrations of naturally-occurring isotopes (K-40 averaging 1226 pCi/L) were consistent with those detected in previous years:

No fission or activation products were detected.

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

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

11.

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

This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Landauer on samples collected during the period 1 January 2019 through 31 December 2019.

A.

Objectives of the REMP The objectives of the REMP are to:

1.

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

2.

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

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

1.

Identifying significant exposure pathways

2.

Establishing baseline radiological data of media within those pathways

3.

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

Radiation and Radioactivity All matter is made of atoms. An atom is the smallest part into which matter can be broken down and still maintain all its chemical properties. Nuclear radiation is energy, in the form of waves or particles that is given off by unstable, radioactive atoms. Radioactive material exists naturally and has always been a part of our environment. The earth's crust, for example, contains radioactive uranium, radium, thorium and potassium. Some radioactivity is a result of nuclear weapons testing. Examples of radioactive fallout that is normally present in environmental samples are cesium-137 and strontium-90. Some examples of radioactive materials released from a nuclear power plant are cesium-137, iodine-131, strontium-90 and cobalt-60.

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

That is why radioactivity in the environment is measured in picocuries. One picocurie is equal to one trillionth of a curie.

D.

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

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

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

(millirem/year)

Internal, inhalation <2l 228 Medical <3l 300 External, space 33 Consumer <4l 13 Internal, ingestion 29 lndustria1<5l 0.3 External, terrestrial 21 Occupational 0.5 Weapons Fallout

<1 Nuclear Power Plants

<1 Approximate Total 311 Approximate Total 314 (1) Information from NCRP Reports 160 and 94 (2) Primarily from airborne radon and its radioactive progeny (3) Includes CT (147 mrem), nuclear medicine (77 mrem}, interventional f/uoroscopy (43 mrem) and conventional radiography and f/uoroscopy (33 mrem)

( 4) Primarily from cigarette smoking ( 4. 6 mrem), commercial air travel (3.4 mrem), building materials (3.5 mrem), and mining and agriculture (0.8 mrem)

(5) Industrial, security, medical, educational, and research Cosmic radiation from the sun and outer space penetrates the earth's atmosphere and continuously bombards us with rays and charged particles.

Some of this cosmic radiation interacts with gases and particles in the atmosphere, making them radioactive in turn. These radioactive byproducts from cosmic ray bombardment are referred to as cosmogenic radionuclides.

Isotopes such as beryllium-? and carbon-14 are formed in this way.

Exposure to cosmic and cosmogenic sources of radioactivity results in about 33 mrem of radiation dose per year.

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

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

Ill.

Program Description A.

Sample Collection Samples for the QCNPS REMP were collected for Exelon Nuclear by ATI Environmental Inc. (Midwest Labs). This section describes the general sampling methods used by Environmental Inc. to obtain environmental samples for the QCNPS REMP in 2019. Sample locations and descriptions can be found in Table B-1 and Figures B-1 and B-2, Appendix B.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, ground water, fish and sediment. Surface water samples were collected weekly from two locations, Q-33 and Q-34 (Control). Ground water samples were collected quarterly from two locations, Q-35 and Q-36. All water samples were collected in new containers, which were rinsed with source water prior to collection.

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

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

Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The air particulate filters and air iodine samples were replaced weekly and sent to the laboratory for analysis.

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

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

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

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

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

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

An other set consisting of 9 locations (Q-01, Q-02, Q-03, Q-04, Q-13, Q-16, Q-37, Q-38 and Q-41 ). The locations are at each of the air sample stations around the site.

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

The specific OSLO locations were determined by the following criteria:

1.

The presence of relatively dense population;

2.

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

3.

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

4.

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

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

B.

Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the QCNPS REMP in 2019 and the type of analyses. The analytical procedures used by the TBE laboratory are listed in Table B-2.

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

1.

Concentrations of beta emitters in surface water and air particulates

2.

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

3.

Concentrations of tritium (H-3) in ground and surface water

4.

Concentrations of 1-131 in air and milk

5.

Ambient gamma radiation levels at various site environs

6.

Concentrations of lron-55 (Fe-55) and Nickel-63 (Ni-63) in surface water C.

Data Interpretation The radiological and direct radiation data collected prior to Quad Cities Nuclear Power Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Quad Cities Nuclear Power Station was considered operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:

1.

Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5%

probability of falsely concluding that a blank observation represents a "real" signal. The LLD is intended as an a priori (a before the fact) estimate of a system (including instrumentation, procedure and sample type) and not as an a posteriori (after the fact) criteria for the presence of activity. All analyses were designed to achieve the required QCNPS detection capabilities for environmental sample analysis.

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

2.

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

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

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

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

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

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

For air iodine, one nuclide, 1-131 was reported.

Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.

D.

Program Exceptions For 2019 the QCNPS REMP had a sample recovery rate in excess of 96%.

Sample anomalies and missed samples are listed in the tables below:

Table D-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection Reason Type Code Date SW Q-33 01/04/19 1-131 detection not met by lab due to sample age when analyzed -

sample received by lab on 01/30/19 AP/Al Q-42 01/17/19 Lower reading of 167.0 hours0 days 0 hours 0 weeks 0 months due to power outage AP/Al Q-01 01/18/19 Low time of 45.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months due to recent power restoration Al Q-38 01/25/19 Cartridge slightly damaged in transit AP/Al Q-41 02/01/19 Lower reading of 149.2 hrs on 8-day period due to power outage (NOTE: timer reading 166.4 hrs during the 02/08/19 collection)

AP/Al Q-37 02/08/19 Lower reading of 151.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months due to power outage AP/Al Q-37 02/15/19 Lower reading of 151.5 hrs due to power outage (NOTE: timer reading 167.5 hrs during the 02/22/19 collection)

AP/Al Q-38 02/15/19 Lower reading of 141.4 hrs due to power outage (NOTE: timer reading 167.4 hrs during the 02/22/19 collection)

OSLO Q-102-3/3A 03/28/19 OSLDs found on the ground AP/Al Q-37 03/29/19 Power failure causing approximately 7 hrs difference Filter light - no indication of pump failure (pump timer, flow and AP Q-37 04/05/19 vacuum parameters show normal readings); Sample slightly damaged during exchange AP/Al Q-13 05/02/19 Lower reading of 151.3 hrs due to power outage (NOTE: on 05/09/19 timer indicated normal reading of 162.6 hrs)

Filter light - no indication of pump failure (pump timer, flow and AP Q-37 05/03/19 vacuum parameters show normal readings); Pump removed on 05/05/19 for more testing AP/Al Q-37 05/10/19 New pump placed on 05/05/19 due to previous pump's failure; filter shows normal residue AP Q-37 06/07/19 Filter slightly damaged during exchange AP Q-38 06/28/19 Filter light - pump operates normally (NOTE: during 07 /05/19 exchange in the filter residue looked normal)

Timer indicates approximately 3 hrs missing; power outage due to AP/Al Q-16 07/05/19 thunderstorms in the area (NOTE: on 07/11/19 timer indicated 143.1 hrs; normal reading for the 6-day period)

Timer indicates approximately 5 hrs missing; power outage due to AP/Al Q-42 07/05/19 thunderstorms in the area (NOTE: on 07 /11 /19 timer indicated 143.4 hrs; normal reading for the 6-dav period)

Ml Q-26 09/06/19 Shipment delivered to wrong address - returned to the collector; resent on 09/16/19 AP/Al ALL 09/06/19 Shipment delivered to wrong address - returned to the collector; SAMPLES resent on 09/16/19 Timer indicates approximately 5 hrs missing due to a power outage AP/Al Q-13 10/17/19

- crew working at the station (NOTE: during the next week's collection in the timer indicated 163.7 hrs; nominal value for the time interval)

AP/Al Q-13 12/26/19 Timer indicates approximately 10 hrs missing due to a pump failure

- pump exchanged Table D-2 LISTING OF MISSED SAMPLES Sample Location Collection Reason Type Code Date AP/Al Q-01 01/04/19 No sample; power outage WW Q-36 01/10/19 Sample leaked during transportation - new sampling date scheduled for 01/14/19 (NOTE: sample recollected on 01/14/19)

AP/Al Q-01 01/11/19 No sample; power outage SW Q-33 01/10/19 No sample; water frozen SW Q-33,Q-34 01/17/19 No sample; water frozen SW Q-33,Q-34 01/24/19 No sample; water frozen SW Q-33,Q-34 02/01/19 No sample; water frozen SW Q-34, Q-34 02/08/19 No sample; water frozen SW Q-34, Q-34 02/14/19 No sample; water frozen SW Q-34, Q-34 02/21/19 No sample; water frozen The carrier lost the package in the Chicago hub (Investigation Ml Q-26 03/01/19 started); New collection scheduled on 03/08/19 (NOTE: sample collected on 03/08/19)

Q-01, Q-02, The carrier lost the package in the Chicago hub (Investigation AP/Al Q-03, Q-04, 03/01/19 Q-37, Q-38 started); Sample found by carrier, shipped for testing on 03/26/19 SW Q-33, Q-34 03/21/19 No sample; water frozen OSLO Q-41-2 03/01/19 OSLO missing; may be in the frozen snow SW Q-33, Q-34 03/08/19 No sample; water frozen OSLO Q-41-2 03/08/19 OSLO missing; may be in the frozen snow (NOTE: OSLO found on 03/14/19, put back in place)

OSLO Q-216-2 03/27/19 OSLO found missing during the quarterly exchange Q-01, Q-02, The carrier erroneously sent the package to Mississippi AP/Al Q-03, Q-04, 06/14/19 (NOTE; the carrier returned the empty container after 3 weeks)

Q-37, Q-38 Ml Q-26 06/14/19 The carrier erroneously sent the package to Mississippi (NOTE; the carrier returned the empty container after 3 weeks)

Q-01, Q-02, The carrier misplaced the package - Case investigated by UPS AP/Al Q-03, Q-04, 06/21/19 and determined irretrievably lost (NOTE: new shipping Q-37, Q-38 arrangements made to prevent future sample losses)

The carrier misplaced the package - Case investigated by UPS Ml Q-26 06/21/19 and determined irretrievably lost (NOTE: new shipping arrangements made to prevent future sample losses)

Al Q-16 08/29/19 Cartridge missing in field OSLO Q-210-4, 09/07/19 OSLDs found missing during the monthly visual check Q-210-4A Sample Type OSLO OSLO SW Table D-2 LISTING OF MISSED SAMPLES (cont'd)

Location Collection Reason Code Date Q-210-1/1A, 09/25/19 OSLDs found missing during the quarterly check Q-203-1 Q-209-2 12/05/19 OSLO found missing during the monthly visual check Q-33, Q-34 12/19/19 No sample; water frozen The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

E.

Program Changes There were no program changes in 2019.

IV.

Results and Discussion A.

Aquatic Environment

1.

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

Gross Beta Samples from all locations were analyzed for concentrations of gross beta (Table C-1.1, Appendix C). Gross beta activity was detected in 19 of 22 samples. The values ranged from 2.7 to 8.4 pCi/L.

Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C). The required LLD was met.

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

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

The required LLDs were met.

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

2.

Ground Water Quarterly grab samples were collected at two locations (Q-35 and Q-36).

Both locations could be affected by Quad Cities' effluent releases. The following analyses were performed:

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

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

3.

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

Gamma Spectrometry The edible portion of fish samples from both locations were analyzed for gamma-emitting nuclides (Table C-111.1, Appendix C). No nuclides associated with QCNPS were detected and all required LLDs were met.

4.

Sediment Aquatic sediment samples were collected at two locations (Q-39 and Q-

40) semiannually. The location Q-39, located downstream, could be affected by Quad Cities' effluent releases. The following analysis was performed:

Gamma Spectrometry Sediment samples from Q-39 and Q-40 were analyzed for gamma-emitting nuclides (Table C-IV.1, Appendix C). Cesium-137 (Cs-137) was detected in two samples with concentrations ranging from 141 to 177 pCi/kg dry. No other nuclides potentially associated with QCNPS were detected and all required LLDs were met.

B.

Atmospheric Environment

1. Airborne

a.

Air Particulates Continuous air particulate samples were collected from ten locations on a weekly basis. The ten locations were separated into three groups: Near-field samplers within 4 km (2.5 miles) of the site (Q-01, Q-02, Q-03 and Q-04), far-field samplers between 4 and 10 km (2.5 - 6.2 miles) from the site (Q-13, Q-16, Q-37, Q-38 and Q-

41) and the Control sampler between 10 and 30 km (6.2 - 18.6 miles) from the site (Q-42). The following analyses were performed:

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

Comparison of results among the four groups aid in determining the effects, if any, resulting from the operation of QCNPS. The results from the near-field locations (Group I) ranged from 5 to 34E-03 pCi/m3 with a mean of 15E-03 pCi/m3. The results from the far-field locations (Group II) ranged from 4 to 38E-03 pCi/m3 with a mean of 15E-03 pCi/m3. The results from the Control location (Group Ill) ranged from 8 to 40E-03 pCi/m3 with a mean of 16E-03 pCi/m3.

Comparison of the 2019 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 2019 indicate no notable differences among the three groups (Figures C-4 through C-9, Appendix C).

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

b.

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

2.

Terrestrial

a.

Milk Samples were collected from one location (Q-26) biweekly May through October and monthly November through April. The following analyses were performed:

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

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

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

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

C.

Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing optically stimulated luminescence dosimeters. Forty-one OSLO locations were established around the site. Results of OSLO measurements are listed in Tables C-IX.1 and C-IX.2, Appendix C.

All of the OSLO measurements were< 20 mRem/quarter, with a range of 7.8 to 18.2 mRem/quarter. A comparison of the Inner Ring, Outer Ring and Other data to the Control Location data, indicate that the ambient gamma radiation levels from all the locations were comparable.

D.

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

E.

Land Use Survey A Land Use Survey conducted during August 2019 around QCNPS was performed by ATI Environmental Inc. (Midwest Labs) for Exelon Nuclear to comply with the Quad Cities' Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident and milk producing animals in each of the sixteen 22.5 degree sectors around the site. The results from the land use census have not identified any locations, which yield a calculated dose or dose commitment, via the same pathway, that is at least 20% greater than at a location from which samples are currently being obtained. The results of this survey are summarized below:

Sector N

NNE NE ENE E

ESE SE SSE s

SSW SW WSW w

WNW NW NNW Distance in Miles from QCNPS Residence Miles 0.6 1.2 1.3 2.9 2.0 2.8 1.7 1.1 0.8 3.2 2.9 2.2 2.6 2.7 2.6 2.1 Livestock Miles 2.7 3.1 3.2 2.9 5.5 3.1 5.3 4.5 4.8 3.5 3.3 2.7 4.3 3.8 4.7

.2.2 Milk Farm Miles 3.1 6.6 Of the above listed Milk Farms, only the farm located at 3.1 miles ESE of QCNPS, listed in the sample results section as Bill Stanley Dairy, has elected to participate in the QCNPS REMP program. Participation by local farmers is voluntary.

F.

Errata Data There is no errata data for 2019.

G.

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

were evaluated against the following pre-set acceptance criteria:

A.

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

B.

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

C.

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

Acceptable (flag = "A") - result within +/- 20% of the reference value Acceptable with Warning (flag = "W") - result falls in the +/- 20% to +/-

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

For the TBE laboratory, 119 out of 129 analyses performed met the specified acceptance criteria. Ten analyses did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program. A summary is found below:

1.

The ERA April 2019 water Cs-134 result was evaluated as Not Acceptable. The reported value was 15.2 pCi/L (error 2.82 pCi/L) and the known result was 12.1 pCi/L (acceptance range of 8.39 - 14.4 pCi/L). With the error, the reported result overlaps the acceptable range. This sample was run as the workgroup duplicate on a different detector with a result of 10.7 pCi/L (within acceptable range). (NCR 19-10)

2.

The ERA April 2019 water Sr-89 result was evaluated as Not Acceptable. The reported value was 44.9 pCi/L and the known result was 33.3 pCi/L (acceptance range of 24.5 - 40.1 pCi/L). The sample was only counted for 15 minutes instead of 200 minutes. The sample was re-prepped in duplicate and counted for 200 minutes with results of 30.7 +/- 5.37 pCi/L and 33.0 +/- 8.71 pCi/L. This was the 151 "high" failure for Sr-89 in 5 years. (NCR 19-11)

3.

The MAPEP February 2019 soil Sr-90 result was not submitted and therefore evaluated as Not Acceptable. The sample was run in duplicate, with results of -1.32 +/- 4.09 Bq/kg (<6.87) and -1.030 +/- 3.55 Bq/kg (<5.97). The known result was a false positive test (no significant activity). TBE did not submit a result because it appeared that the results may not be accurate. TBE analyzed a substitute soil Sr-90 sample from another vendor, with a result within the acceptable range. (NCR 19-12)

4.

The MAPEP February 2019 water Am-241 result was evaluated as Not Acceptable. The reported value was 0.764 +/- 0.00725 Bq/L with a known result of 0.582 Bq/L (acceptable range 0.407 - 0.757 Bq/L).

TBE's result falls within the upper acceptable range with the error. It appeared that a non-radiological interference was added and lead to an increased mass and higher result. (NCR 19-13)

5.

The MAPEP February 2019 vegetation Sr-90 result was evaluated as Not Acceptable. The reported result was -0.1060 +/- 0.0328 Bq/kg and the known result was a false positive test (no significant activity).

TBE's result was correct in that there was no activity. MAPEP's evaluation was a "statistical failure" at 3 standard deviations. (NCR 19-14)

6.

The ERA October 2019 water Gross Alpha result was evaluated as Not Acceptable. TBE's reported result was 40.5 +/- 10.3 pCi/L and the known result was 27.6 pCi/L (ratio of TBE to known result at 135%).

With the associated error, the result falls within the acceptable range (14.0 - 36.3 pCi/L). The sample was run as the workgroup duplicate on a different detector with a result of 30.8 +/- 9.17 pCi/L (within the acceptable range). This was the first failure for drinking water Gr-A since 2012. (NCR 19-23)

7.

The ERA October 2019 water Sr-90 result was evaluated as Not Acceptable. TBE's reported result was 32.5 +/- 2.12 pCi/L and the known result was 26.5 pCi/L (ratio of TBE to known result at 123%).

With the associated error, the result falls within the acceptable range (19.2 - 30.9 pCi/L). The sample was run as the workgroup duplicate on a different detector with a result of 20.0 +/- 1.91 pCi/L (within the acceptable range). Both TBE results are within internal QC limits. A substitute "quick response" sample was analyzed with an acceptable result of 18.6 pCi/L (known range of 13.2 - 22.1 pCi/L). (NCR 19-24)

8.

The MAPEP August 2019 soil Ni-63 result of 436 +/- 22.8 Bq/kg was evaluated as Not Acceptable. The known result was 629 Bq/kg (acceptable range 440 - 818 Bq/sample). With the associated error, the TBE result falls within the lower acceptance range. All associated QC was acceptable. No reason for failure could be found. This is the first failure for soil Ni-63 since 2012. (NCR 19-25).

9.

The MAPEP August 2019 water Am-241 result was not reported and therefore evaluated as Not Acceptable. Initial review of the results showed a large peak where Am-241 should be (same as the February, 2019 sample results). It is believed that Th-228 was intentionally added as an interference. The sample was re-prepped and analyzed using a smaller sample aliquot. The unusual large peak (Th-228) was seen again and also this time a smaller peak (Am-241 ).

The result was 436 +/- 22.8 Bq/L (acceptable range 0.365 +/- 0.679 Bq/L). Th-228 is not a typical nuclide requested by clients, so there is no analytical purpose to take samples through an additional separation step. TBE will pursue using another vendor for Am-241 water cross-checks that more closely reflects actual customer samples. (NCR 19-26)

10.

The Analytics September 2019 soil Cr-51 sample was evaluated as Not Acceptable. TB E's reported result of 0. 765 +/- 0.135 pCi/g exceeded the upper acceptance range (140% of the known result of 0.547 pCi/g). The TBE result was within the acceptable range (0.63 -

0.90 pCi/g) with the associated error. The Cr-51 result is very close to TBE's normal detection limit. In order to get a reportable result, the sample must be counted for 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months (1 Ox longer than client samples). There is no client or regulatory requirement for this nuclide and TBE will remove Cr-51 from the reported gamma nuclides going forward. (NCR 19-27)

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

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank

TABLE A*1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2019 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER:

50*254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD:

2019 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M)

MEAN(M)

STATION#

NONROUTINE (UNITOF ANALYSIS ANALYSIS OF DETECTION (F)

(F)

NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD)

RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS SURFACE WATER GR*B 22 4

4.7 5.2 5.2 Q-34 CONTROL 0

(PCllLITER)

(9/11)

(10/11)

CAMANCHE-UPSTREAM 2.7-8.4 3.6-7.5 3.6* 7.5 4.4 MILES NNE OF SITE H-3 8

2000

<LLD

<LLD 0

FE-55 8

200

<LLD

<LLD 0

Nl-63 8

5

<LLD

<LLD 0

GAMMA 22 MN-54 15

<LLD

<LLD 0

)>

C0-58 15

<LLD

<LLD 0

I FE-59 30

<LLD

<LLD 0

C0-60 15

<LLD

<LLD 0

ZN-65 30

<LLD

<LLD 0

NB-95 15

<LLD

<LLD 0

ZR-95 30

<LLD

<LLD 0

1-131 15

<LLD

<LLD 0

CS-134 15

<LLD

<LLD 0

CS-137 18

<LLD

<LLD 0

BA-140 60

<LLD

<LLD 0

LA-140 15

<LLD

<LLD 0

GROUND WATER H-3 8

2000

<LLD NA 0

(PCl/LITER)

GAMMA 8

MN-54 15

<LLD NA 0

C0-58 15

<LLD NA 0

FE-59 30

<LLD NA 0

C0-60 15

<LLD NA 0

ZN-65 30

<LLD NA 0

NB-95 15

<LLD NA 0

ZR-95 30

<LLD NA 0

1-131 15

<LLD NA 0

CS-134 15

<LLD NA 0

CS-137 18

<LLD NA 0

BA-140 60

<LLD NA 0

LA-140 15

<LLD NA 0

(M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2019 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER:

50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD:

2019 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M)

MEAN (M)

MEAN(M)

STATION#

NON ROUTINE (UNITOF ANALYSIS ANALYSIS OF DETECTION (F)

(F)

NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD}

RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS FISH GAMMA 8

(PCl/KG WET)

MN-54 130

<LLD

<LLD 0

C0-58 130

<LLD

<LLD 0

FE-59 260

<LLD

<LLD 0

C0-60 130

<LLD

<LLD 0

ZN-65 260

<LLD

<LLD 0

NB-95 NA

<LLD

<LLD 0

ZR-95 NA

<LLD

<LLD 0

CS-134 130

<LLD

<LLD 0

CS-137 150

<LLD

<LLD 0

BA-140 NA

<LLD

<LLD 0

l>

LA-140 NA

<LLD

<LLD 0

I I\\)

SEDIMENT GAMMA 4

(PCl/KG DRY)

MN-54 NA

<LLD

<LLD 0

C0-58 NA

<LLD

<LLD 0

FE-59 NA

<LLD

<LLD 0

C0-60 NA

<LLD

<LLD 0

ZN-65 NA

<LLD

<LLD 0

NB-95 NA

<LLD

<LLD 0

ZR-95 NA

<LLD

<LLD 0

CS-134 150

<LLD

<LLD 0

CS-137 180 177 141 177 Q-39 INDICATOR 0

(1/2)

CORDOVA-DOWNSTREAM MISSISSIPPI RIVER 0.8 MILES SSW OF SITE BA-140 NA

<LLD

<LLD 0

LA-140 NA

<LLD

<LLD 0

AIR PARTICULATE GR-B 506 10 15.4 15.7 17.7 Q-41 INDICATOR 0

(E-3 PC/ICU.METER)

(439/454)

(52/52)

CAMANCHE 4.3-38.1 7.7-39.7 8.1 - 38.1 4.3 MILES NNE OF SITE (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2019 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER:

50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD:

2019 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M)

MEAN (M)

MEAN(M)

STATION#

NON ROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F)

(F)

NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD)

RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS AIR PARTICULATE GAMMA 40 (E-3 PC/ICU.METER)

MN-54 NA

<LLD

<LLD 0

C0-58 NA

<LLD

<LLD 0

FE-59 NA

<LLD

<LLD 0

C0-60 NA

<LLD

<LLD 0

ZN-65 NA

<LLD

<LLD 0

NB-95 NA

<LLD

<LLD 0

ZR-95 NA

<LLD

<LLD 0

CS-134 50

<LLD

<LLD 0

CS-137 60

<LLD

<LLD 0

BA-140 NA

<LLD

<LLD 0

)>

LA-140 NA I

<LLD

<LLD 0

c.>

AIR IODINE GAMMA 506 (E-3 PC/ICU.METER) 1-131 70

<LLD

<LLD 0

MILK 1-131 (LOW LVL) 18 1

<LLD NA 0

(PCllL/TER)

GAMMA 18 MN-54 NA

<LLD NA 0

C0-58 NA

<LLD NA 0

FE-59 NA

<LLD NA 0

C0-60 NA

<LLD NA 0

ZN-65 NA

<LLD NA 0

NB-95 NA

<LLD NA 0

ZR-95 NA

<LLD NA 0

CS-134 15

<LLD NA 0

CS-137 18

<LLD NA 0

BA-140 60

<LLD NA 0

LA-140 15

<LLD NA 0

(M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2019 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER:

50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD:

2019 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN(M)

MEAN(M)

STATION#

NON ROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F)

(F)

NAME REPORTED MEASUREMENT)

PERFORMED PERFORMED (LLD)

RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS VEGETATION GAMMA 15 (PCllKG WET)

MN-54 NA

<LLD

<LLD 0

C0-58 NA

<LLD

<LLD 0

FE-59 NA

<LLD

<LLD 0

C0-60 NA

<LLD

<LLD 0

ZN-65 NA

<LLD

<LLD 0

NB-95 NA

<LLD

<LLD 0

ZR-95 NA

<LLD

<LLD 0

1-131 60

<LLD

<LLD 0

CS-134 60

<LLD

<LLD 0

CS-137 80

<LLD

<LLD 0

l>

BA-140 NA

<LLD

<LLD 0

I

.f>.

LA-140 NA

<LLD

<LLD 0

DIRECT RADIATION OSLD-QUARTERL Y 331 NA 12.2 13.9 16.5 Q-211-2 INDICATOR 0

(MILL/-ROENTGENIQTR.)

(323/323)

(8/8)

(4/4) 7.8-18.2 11.7-15.9 13.9-18.2 4.5 MILES SW (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

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

Intentionally left blank

TABLE B-1:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2019 Location Location Description Distance & Direction From Site A. Surface Water Q-33 Q-34 B.

Ground/Well Water Q-35 Q-36 C.

Milk - bi-weekly I monthly Q-26 D.

Air Particulates I Air Iodine Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 E.

Fish Q-24 Q-29 F.

Sediment Q-39 Q-40 G.

Food Products Quadrant 1 Quadrant 2 Quadrant 3 Quadrant 4 Control Cordova (indicator)

Camanche. Upstream (control)

McMillan Well (indicator)

Cordova Well (indicator)

Bill Stanley Dairy (indicator)

Onsite 1 (indicator)

Onsite 2 (indicator)

Onsite 3 (indicator)

Nitrin (indicator)

Princeton (indicator)

Low Moor (indicator)

Meredosia Road (indicator)

Fuller Road (indicator)

Camanche, Upstream (control)

Leclaire (control)

Pool #14 of Mississippi River, Downstream (indicator)

Mississippi River,.Upstream (control)

Cordova, Downstream on Mississippi River (indicator)

North of Albany, Upstream on Mississippi River (control)

Ken DeBaille Dale Nimmic Amy Johnston Mike Fawcett Charles Leavens H.

Environmental Dosimetry - OSLO Inner Ring Q-101-1 / Q-101-1A Q-101-2 / Q-101-2A Q-102-1 / Q-102-1A Q-102-3 / Q-102-3A Q-103-1 / Q-103-1A Q-103-2 / Q-103-2A Q-104-1 / Q-104-1A Q-104-2 I Q-104-2A Q-105-1 / Q-105-1A Q-105-2 I Q-105-2A Q-106-2 I Q-106-2A Q-106-3 I Q-106-3A Q-107-2 / Q-107-2A Q-107-3 / Q-107-3A Q-108-1 / Q-108-1A Q-108-2 / Q-108-2A Q-109-1 / Q-109-1A Q-109-2 I Q-109-2A Q-111-1 I Q-111-1A Q-111-2 / Q-111-2A B-1 3.1 miles SSW 4.4 miles NNE 1.5 miles S 3.3 miles SSW 3.1 miles ESE 0.5 miles N 0.4 miles ENE 0.6 miles S 1.7 miles NE 4.7 miles SW 5.7 miles NNW 4.4 miles ENE 4.7 miles E 4.3 miles NNE 8.7 miles SSW 0.5 miles SW 1.0 miles N 0.8 miles SSW 8.9 miles NE 2.3 miles ENE 3.0 miles ESE 1.8 miles S 4.5 miles NW 9.5 miles NE 0.6 miles N 0.9 miles N 1.3 miles NNE 1.4 miles NNE 1.2 miles NE 1.2 miles NE 1.1 miles ENE 0.9 miles ENE 0.8 miles E 0.8 miles E 0.7 miles ESE 0.7 miles ESE 0.7 miles SE 0.8 miles SE 1.0 miles SSE 0.9 miles SSE 0.9 miles S 1.2 miles S 2.6 miles SW 2.5 miles SW

TABLE B-1:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2019 Location Location Description H.

Environmental Dosimetry - OSLO (continued\\

Inner Ring (continued\\

Q-112-1 /Q-112-1A Q-112-2 / Q-112-2A Q-113-1 I Q-113-1A Q-113-2 I Q-113-2A Q-114-1 I Q-114-1A Q-114-2 / Q-114-2A Q-115-1 I Q-115-1A Q-115-2 / Q-115-2A Q-116-1 / Q-116-1A Q-116-3 / Q-116-3A Outer Ring Q-201-1 / Q-201-1A Q-201-2 / Q-201-2A Q-202-1 I 0~202-1A Q-203-1 I Q-203-1A Q-203-2 I Q-203-2A Q-204-1 I Q-204-1A Q-204-2 I Q-204-2A Q-205-1 I Q-205-1A Q-205-4 I Q-205-4A Q-206-1 I Q-206-1A Q-206-2 I Q-206-2A Q-207-1 I Q-207-1A Q-207-4 / Q-207-4A Q-208-1 / Q-208-1A Q-208-2 I Q-208-2A Q-209-1 I Q-209-1A Q-209-4 I Q-209-4A Q-210-1 I Q-210-1A Q-210-4* I Q-210-4A*

Q-210-5 I Q-210-5A Q-211-1 / Q-211-1A Q-211-2 / Q-211-2A Q-212-1 / Q-212-1A Q-212-2 / Q-212-2A Q-213-1 / Q-213-1A Q-213-2 I Q-213-2A Q-214-1 I Q-214-1A Q-214-2 I Q-214-2A Q-215-1 / Q-215-1A Q-215-2 / Q-215-2A Q-216-1 I Q-216-1A Q-216-2 / Q-216-2A Other Q-01-1 / Q-01-2 Q-02-1 I Q-02-2 Q-03-1 / Q-03-2 Q-04-1 I Q-04-2 Q-13-1 / Q-13-2 Q-16-1 / Q-16-2 Q-37-1 / Q-37-2 Q-38-1 I Q-38-2 Q-41-1 / Q-41-2 Control Q-42-1 / Q-42-2 Onsite 1 (indicator)

Onsite 2 (indicator)

Onsite 3 (indicator)

Nitrin (indicator)

Princeton (indicator)

Low Moor (indicator)

Meredosia (indicator)

Fuller Road (indicator)

Camanche (indicator)

Leclaire

Removed from ODCM in December 2006 and replaced by Q-210-5. Q-210-4 is for trending only B-2 Distance & Direction From Site 2.5 miles WSW 2.2 miles WSW 2.5miles W 2.5miles W 2.1 miles WNW 2.5 miles WNW 2.6 miles NW 2.3miles NW 2.3 miles NNW 2.4 miles NNW 4.2 miles N 4.4 miles NNE 4.8 miles NNE 4.7 miles NE 5.0 miles NE 4.7 miles ENE 4.5 miles ENE 4.7 miles E 4.8 miles E 4.8 miles ESE 4.8 miles ESE 4.7 miles SE 4.7 miles SE 4.3 miles SSE 4.9 miles SSE 4.7 miles S 4.7 miles S 4.1 miles SWW 4.1 miles SSW 3.3 miles SSW 4.5miles SW 4.5miles SW 5.4 miles WSW 4.4 miles WSW 4.3 miles W 4.8 milesW 4.7 miles WNW 4.4 miles WNW 5.0miles NW 4.2 miles NW 4.6 miles NNW 4.3 miles NNW 0.5 miles N 0.4 miles ENE 0.6 miles S 1.7 miles NE 4.7 miles SW 5.7 miles NNW 4.4 miles ENE 4.7 miles E 4.3 miles NNE 8.7 miles SSW

TABLE B-2:

Sample Medium Surface Water Surface Water Surface Water Surface Water Ground Water Ground Water Fish Sediment Air Particulates Air Particulates Air Iodine Milk Milk Food Products OSLO Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2019 Analysis Sampling Method Analytical Procedure Number Gamma Monthly composite from TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy weekly grab samples Gross Beta Monthly composite from TBE, TBE-2008 Gross Alpha and/or gross beta activity in various weekly grab samples matrices Tritium Quarterly composite from TBE, TBE-2011 Tritium analysis in drinking water by liquid scintillation weekly grab samples Iron and Nickel Quarterly composite from TBE, TBE-2006 lron-55 in various matrices weekly grab samples TBE, TBE-2013 Radionickel in various matrices Gamma Quarterly grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy Tritium Quarterly grab samples TBE, TBE-2011 Tritium analysis in drinking water by liquid scintillation Gamma Semi-annual samples Spectroscopy collected via electroshocking TBE-2007 Gamma emitting radioisotope analysis or other techniques Gamma Semi-annual grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy One-week composite of Gross Beta continuous air sampling TBE, TBE-2008 Gross Alpha and/or gross beta activity in various through glass fiber filter matrices paper Gamma Quarterly composite of each TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy station Gamma Weekly composite of Spectroscopy continuous air sampling TBE, TBE-2007 Gamma emitting radioisotope analysis through charcoal filter Bi-weekly grab sample when 1-131 cows are on pasture.

TBE, TBE-2012 Radioiodine in various matrices Monthly all other times Gamma Bi-weekly grab sample when Spectroscopy cows are on pasture.

TBE, TBE-2007 Gamma emitting radioisotope analysis Monthly all other times Gamma Annual grab samples TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy Optically Quarterly OSLDs comprised Stimulated Luminescence of two Al203:C Landauer Landauer Incorporated Dosimetry Incorporated elements B-3

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NOTE: All dosimeter locations contain two dosimeters, ex. numbering convention 102-1I102-1A Figure B-2 Map Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2019

Intentionally left blank

APPENDIX C DATA TABLES AND FIGURES

Intentionally left blank

Table C-1.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION PERIOD Q-33 Q-34 01/04/19 - 01/10/19 2.7 +/- 1.9

< 2.7 02/01/19 - 02/27/19 (1) 03/14/19 - 03/28/19 4.0 +/- 1.6 6.2 +/- 2.0 04/03/19 - 04/25/19 4.0 +/- 1.6 5.6 +/- 1.7 05/02/19 - 05/31/19 4.7 +/- 1.7 3.6 +/- 1.7 06/06/19 - 06/27/19 8.4 +/- 3.5 7.3 +/- 3.5 07/05/19 - 07/25/19 3.8 +/- 1.8 4.9 +/- 1.9 08/01/19 - 08/29/19

< 3.1 4.8 +/- 2.2 09/05/19 - 09/26/19 6.4 +/- 2.2 4.1 +/- 2.0 10/03/19 - 10/31/19 3.7 +/- 1.6 4.7 +/- 1.7 11/07/19 - 11/29/19 4.6 +/- 1.8 7.5 +/- 2.0 12/05/19 - 12/26/19

< 2.7 3.7 +/- 1.9 MEAN+/- 2 STD DEV 4.7 +/- 3.4 5.2 +/- 2.8 Table C-1.2 CONCENTRATIONS OF TRITIUM, IRON, AND NICKEL IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Q-33 01/04/19 - 03/28/19 04/05/19 - 06/27/19 07/05/19 - 09/26/19 10/03/19 - 12/26/19 MEAN Q-34 01 /04/19 - 03/28/19 04/03/19 - 06/27/19 07/05/19 - 09/26/19 10/03/19 -

12/26/19 MEAN H-3

< 190

< 177

< 193

< 187

< 188

< 196

< 194 FE-55

< 191

< 55

< 62

< 60

< 49

< 38

< 53

< 55 Nl-63

< 5.0

< 4.6

< 4.2

< 4.4

< 4.8

< 4.6

< 4.5

< 4.3 THE MEAN AND TWO STANDARD DEV/A TION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1

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Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 COLLECTION SITE PERIOD Q-33 01/04/19 - 01/04/19 02/01/19 - 02/27/19 (1) 03/14/19 - 03/28/19 04/03/19 - 04/25/19 05/02/19 - 05/31/19 06/06/19 - 06/27/19 07/05/19 - 07/25/19 08/01/19 - 08/29/19 09/05/19 - 09/26/19 10/03/19 - 10/31/19 11/07/19 - 11/29/19 12/05/19 - 12/26/19 MEAN Mn-54

<4

< 7

< 6

< 8

< 2

< 1

< 5

< 7

< 2

< 3 Q-34 01/04/19 - 01/10/19

< 2 02/01/19 - 02/27/19 (1) 03/14/19 - 03/28/19 04/03/19 - 04/25/19 05/02/19 - 05/31/19 06/06/19 - 06/27/19 07/05/19 - 07/25/19 08/01/19 - 08/29/19 09/05/19 - 09/26/19 10/03/19 - 10/31/19 11/07/19 - 11/29/19 12/05/19 - 12/26/19 MEAN

< 10

< 6

< 2

<4

< 5

< 9

< 2

< 2 Co-58

< 4

< 9

< 8

< 6

< 2

< 5

<6

< 9

< 2

< 3

< 11

< 6

< 9

< 2

< 5

< 6

< 2

< 2 RESULTS IN UNITS OF PCl/LITER + 2 SIGMA Fe-59

< 10

< 24

< 12

< 5

<4

< 11

< 13

< 14

< 5

< 6

< 18

< 10

< 16

<4

< 4

< 12

< 18

< 5

< 5 Co-60

<4

< 9

< 6

< 8

< 2

<2

<6

< 5

< 9

< 2

< 3

< 2

< 13

< 3

< 8

< 2

<4

< 5

< 10

< 3

< 3 Zn-65

< 8

< 15

< 17

< 15

<4

< 3

< 14

< 10

< 8

< 5

< 15

< 8

< 14

<4

< 3

< 10

< 11

< 15

<4

< 5 Nb-95

<4

< 10

< 7

< 6

< 2

< 7

< 6

< 7

< 3

< 10

< 7

<4

< 2

< 5

< 6

< 7

< 2

< 3 Zr-95

< 7

< 15

< 13

< 14

<4

< 3

< 9

< 15

<4

< 5

< 15

< 16

< 14

<4

< 4

< 6

< 9

< 13

<4

< 5 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION 1-131 (1)

< 12

< 11

< 13

< 12

< 9

< 14

< 10

< 7

< 14

< 15

< 10

< 12

< 8

< 10

< 13

< 11

< 6

< 7 Cs-134 Cs-137 Ba-140

<4

<46

< 13

<7

< 8

< 2

< 5

< 8

< 2

< 3

< 9

< 7

< 2

<4

<6

< 8

< 2

< 3

< 9

< 8

< 6

<2

< 2

< 5

< 9

< 2

< 3

< 2

< 11

< 8

< 9

< 2

< 5

< 6

< 8

<2

< 2

< 41

< 31

< 40

< 21

< 15

< 36

< 37

< 16

< 15

< 24

< 52

< 34

< 35

< 17

< 26

< 35

< 36

< 15

< 15 La-140

< 14

< 10

< 13

< 11

< 6

< 5

< 12

< 11

< 10

< 5

< 6

< 8

< 11

< 12

< 5

< 12

< 11

< 12

< 5

Table C-11.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION PERIOD Q-35 Q-36 01/10/19 - 01/14/19

< 189

< 189 04/12/19 - 04/12/19

< 182

< 188 07/11/19 - 07/11/19

< 194

< 193 10/10/19 - 10/10/19

< 173

< 170 MEAN C-3

Table C-11.2 COLLECTION SITE PERIOD Q-35 01/10/19 - 01/10/19 04/12/19 - 04/12/19 07/11/19 - 07/11/19 10/10/19 - 10/10/19 MEAN Q-36 01/14/19 - 01/14/19 04/12/19 - 04/12/19 07/11/19 - 07/11/19 10/10/19 - 10/10/19 0

I MEAN

~

CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER + 2 SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137

<6

< 6

< 10

< 6

< 9

< 6

< 9

< 7

< 8

< 7

< 11

< 7

< 14

< 7

< 12

< 9

< 7

< 6

< 7

< 15

< 7

< 15

< 7

< 14

< 11

< 8

< 6

< 9

<6

< 14

< 8

< 15

< 8

< 14

< 7

<6

< 6

< 8

< 9

< 10

< 9

< 13

< 7

< 8

< 9

< 16

< 9

< 18

< 9

< 16

< 13

< 10

< 9

< 8

< 7

< 17

< 11

< 15

< 7

< 13

< 11

< 7

< 17

< 7

< 14

< 8

< 14

< 8

< 7 Ba-140 La-140

< 24

< 12

< 30

< 11

< 31

< 9

< 36

< 12

< 20

< 8

< 37

< 13

< 38

< 14

< 34

< 14

Table C-111.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PC/KG WET+ 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-24 Shorthead Redhorse 05/23/19

< 50

< 67

< 172

< 92

< 120

< 67

< 98

< 60

< 49

< 269

< 121 Walleye 05/23/19

< 40

< 43

< 100

< 49

< 99

< 37

< 64

< 46

< 40

< 243

< 88 Freshwater Drum 10/23/19

< 46

< 65

< 137

< 75

< 114

< 61

< 106

< 71

< 73

< 364

< 76 Common Carp 10/23/19

< 40

< 35

< 88

< 43

< 95

< 49

< 72

< 46

< 44

< 163

< 63 MEAN Q-29 Largemouth Bass 05/23/19

< 41

< 31

< 82

< 56

< 63

< 45

< 77

< 45

< 259

< 97 Quillback 05/23/19

< 59

< 69

< 140

< 56

< 83

< 71

< 115

< 44

< 50

< 377

< 144 0

Largemouth Bass 10/23/19

< 39

< 48

< 120

< 56

< 79

< 46

< 78

< 28

< 48

< 227

< 69 I

CJ1 Freshwater Drum 10/23/19

< 38

< 31

< 77

< 32

< 76

< 42

< 68

< 56

< 42

< 201

< 57 MEAN

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I O>

Table C-IV.1 SITE Q-39 COLLECTION PERIOD 05130119 10111119 MEAN +/- 2 STD DEV Q-40 05130119 10111119 MEAN +/- 2 STD DEV Mn-54

< 76

< 83

< 57

< 78 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PC/KG DRY+/- 2 SIGMA Co-58

< 72

< 81

< 62

< 87 Fe-59

< 192

< 174

< 134

< 201 Co-60

< 72

< 82

< 65

< 84 Zn-65

< 119

< 223

< 142

< 225 Nb-95

< 84

< 80

< 76

< 91 Zr-95

< 135

< 133

< 105

< 172 Cs-134 Cs-137

< 84 177 +/- 83

< 110

< 120

< 88

< 112 177 +/- 0 141 +/- 55

< 133 141 +/- 0 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES Ba-140

< 531

< 347

< 356

< 512 La-140

< 103

< 120

< 118

< 103

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA GROUP I GROUP II GROUP Ill COLLECTION PERIOD 0-01 0~02 0-03 0-04 0-13 0-16 0-37 0-38 Q-41 Q-42 01104119 - 01111119 01110119 - 01118119 01117119 - 01125/19 01124119 - 02101119 02101119 - 02108119 02108119 - 02114119 02114119 - 02122119 02122119 - 03101119 03101119 - 03108119 03108119 - 03116119 03114119 - 03122119 03121119 - 03129119 03128119 - 04105119 04105119 - 04112119 04112119 - 04119119 04119119 - 04125119 04125119 - 05103119 05102119 - 05110119 05109119 - 05117119 05116119 - 05124119 05123119 - 05131119 05131119 - 06107119 06106119 - 06113119 06113119 - 06120119 06120119 - 06128119 06127119 - 07105119 07105119 - 07112119 07111119 - 07119119 07118119 - 07126119 07125119 - 08102119 08101119 - 08109119 08109119 - 08116119 08115119 - 08124119 08122119 - 08131119 08129119 - 09106119 09105119 - 09114119 09112119 - 09120119 09119119 - 09128119 09126119 - 10104119 10103119 - 10111119 10110119 - 10119119 10117119 - 10125119 10124119 - 11101119 10131119 - 11108119 11107119 - 11115119 11115119 - 11122119 11122119 - 11129119 11129119 - 12106119 12105119 - 12113119 12112119 - 12120119 12119119 - 12128119 12126119 - 01103120 MEAN+/- 2 STD DEV (1) 19 +/- 11 19 +/- 4 23 +/- 4 13 +/- 4 16 +/- 4 22 +/- 4 23 +/- 4 20 +/- 4 13 +/- 4 13 +/- 4 16 +/- 4 7 +/- 3 10 +/- 4 8 +/- 3 13 +/- 4 6 +/- 4 14 +/- 4 13 +/- 4

< 5 11 +/- 4 16 +/- 4 (1)

(1) 19 +/- 5 18 +/- 4 13 +/- 4 5 +/- 3 12 +/- 4 14 +/- 4 14 +/- 4 8 +/- 3 18 +/- 4 14 +/- 4 26 +/- 5 14 +/- 4 27 +/- 5 15 +/- 4 13 +/- 4 14 +/- 4 14 +/- 3 15 +/- 5 8+/-4 18 +/- 4 25 +/- 5 16 +/- 4 16 +/- 4 13 +/- 4 24 +/- 5 30 +/- 5 28 +/- 4 12 +/- 4 16 +/- 12 26 +/- 5 18 +/- 4 15 +/- 4 27 +/- 5 14 +/- 4 19 +/- 4 25 +/- 5 20 +/- 4 22 +/- 4 14 +/- 4 8 +/- 3 14 +/- 4 8+/-4 8 +/- 3 9 +/- 3 11 +/- 4 6+/-4 9 +/- 3 17 +/- 4

< 5 9 +/- 3 11 +/- 4 (1)

(1) 15 +/- 4 15 +/- 4 13 +/- 4 13 +/- 3 10 +/- 4 14 +/- 4 18 +/- 4 17 +/- 4 13 +/- 3 13 +/- 4 16 +/- 4 14 +/- 3 21 +/- 5 15 +/- 4 11 +/- 4 20 +/- 4 11 +/- 3 10 +/- 4 10 +/- 4 14 +/- 4 15 +/- 4 20 +/- 4 15 +/- 4 10 +/- 3 26 +/- 5 34 +/- 5 28 +/- 4 18 +/- 5 15 +/- 12 27 +/- 5 18 +/- 4 20 +/- 4 25 +/- 4 17 +/- 4 17 +/- 4 25 +/- 5 20 +/- 4 14 +/- 4 12 +/- 4 14 +/- 4 15 +/- 4 6+/-3 7 +/- 3 8 +/- 3 15 +/- 4 7 +/- 4 11 +/- 3 15 +/- 4

< 5 8 +/- 3 18 +/- 4 (1)

(1) 17 +/- 4 17 +/- 4 7+/-3 15 +/- 4 7+/-4 13 +/- 3 17 +/- 4 14 +/- 4 14 +/- 3 12 +/- 4 22 +/- 5 14 +/- 3 24 +/- 5 14 +/- 4 7+/-3 16 +/- 4 13 +/- 3 12 +/- 5 11 +/- 4 14 +/- 4 23 +/- 5 17 +/- 4 13 +/- 4 11 +/- 3 24 +/- 5 30 +/- 5 32 +/- 5 14 +/- 5 16 +/- 12 24 +/- 5 13 +/- 4 16 +/- 4 19 +/- 4 15 +/- 4 17 +/- 4 19 +/- 4 15 +/- 4 16 +/- 4 12 +/- 4 8 +/- 3 13 +/- 4 5 +/- 3 7+/-3 8 +/- 3 10 +/- 4 8 +/- 4 9+/-3 13 +/- 4 6 +/- 3 12 +/- 4 19 +/- 4 (1)

(1) 17 +/- 4 12 +/- 4 9 +/- 4 12 +/- 3 9 +/- 4 11 +/- 3 17 +/- 4 16 +/- 4 16 +/- 3 16 +/- 4 15 +/- 4 15 +/- 4 29 +/- 5 17 +/- 4 15 +/- 4 13 +/- 4 10 +/- 3 12 +/- 5 10 +/- 4 19 +/- 4 26 +/- 5 20 +/- 4 14 +/- 4 13 +/- 4 16 +/- 4 34 +/- 5 31 +/- 5 (1) 15 +/- 12 26 +/- 5 23 +/- 5 17 +/- 4 15 +/- 4 19 +/- 4 18 +/- 4 20 +/- 4 23 +/- 4 12 +/- 4 19 +/- 4 18 +/- 5 12 +/- 4 20 +/- 4 25 +/- 4 21 +/- 5 26 +/- 5 14 +/- 4 19 +/- 4 16 +/- 5 19 +/- 5 13+/-3 11+/-3 15 +/- 4 5 +/- 3 9+/-3 10+/-3 8 +/- 3 8 +/- 3 8+/-3 8+/-3 12 +/- 4 15 +/- 5 8 +/- 4

< 5 12+/-4 11+/-3 15 +/- 4 13 +/- 4 8 +/- 3 10 +/- 4 9+/-3 9+/-3 16 +/- 5 13 +/- 5 12 +/- 4 13 +/- 4 10 +/- 4 10 +/- 4 16 +/- 4 14 +/- 4 15 +/- 3 16 +/- 4 16 +/- 5 12 +/- 4 11+/-3 11+/-3 12 +/- 4 8 +/- 4 10 +/- 3 14 +/- 4 19 +/- 4 20 +/- 4 19 +/- 5 17 +/- 5 19 +/- 4 20 +/- 4 12 +/- 4 14 +/- 4 17 +/- 4 16 +/- 4 18 +/- 4 17 +/- 4 18 +/- 4 20 +/- 4 19 +/- 5 20 +/- 5 15 +/- 4 15 +/- 4 13 +/- 4 13 +/- 4 14 +/- 4 14 +/- 4 17 +/- 4 15 +/- 4 10+/-4 11+/-4 20 +/- 4 15 +/- 4 21 +/- 4 22 +/- 4 17 +/- 4 19 +/- 4 13 +/- 4 15 +/- 4 12 +/- 4 13 +/- 4 24 +/- 5 22 +/- 5 32 +/- 5 32 +/- 5 19+/-4 30+/-5 18 +/- 5 19 +/- 4 15+/-10 16+/-11 22 +/- 5 15 +/- 4 18 +/- 4 22 +/- 4 12 +/- 4 17 +/- 5 24 +/- 5 10 +/- 4 6 +/- 3 12 +/- 4

< 4

< 5

< 4

<4

< 5

< 5 5 +/- 3 19 +/- 4

< 5 10 +/- 4 12 +/- 4 (1)

(1) 12 +/- 4 16 +/- 4 9+/-4 11 +/- 3 8 +/- 4 10 +/- 3 16 +/- 4 15 +/- 4 14 +/- 3

<4 13 +/- 4 12 +/- 3 20 +/- 5 11 +/- 4 11 +/- 4 15 +/- 4 12 +/- 3 12 +/- 5 11 +/- 4 16 +/- 4 18 +/- 5 17 +/- 4 12 +/- 4 13 +/- 4 23 +/- 5 29 +/- 5 27 +/- 4 13 +/- 5 15 +/- 11 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-7 11 +/- 4 10 +/- 3 12 +/- 3 17 +/- 4 11 +/- 4 10 +/- 4 15 +/- 4 8+/-3 17 +/- 4 16 +/- 4 14 +/- 4 9 +/- 3 7 +/- 3 6 +/- 3 4+/-3 11 +/- 4

< 5 9 +/- 3 12 +/- 4 7 +/- 3 7 +/- 3 11 +/- 4 (1)

(1)

< 4 11 +/- 3 8 +/- 4 10 +/- 3 9 +/- 4 14 +/- 4 19 +/- 4 11 +/- 4 15 +/- 3 11 +/- 4 15 +/- 4 13 +/- 3 21 +/- 5 20 +/- 4 15 +/- 4 16 +/- 4 11 +/- 3 17 +/- 5 8 +/- 4 18 +/- 4 25 +/- 5 15 +/- 4 13 +/- 4 11 +/- 3 20 +/- 4 35 +/- 5 28 +/- 4 15 +/- 5 13 +/- 12 28 +/- 5 17 +/- 4 10 +/- 3 29 +/- 5 18 +/- 4 16 +/- 5 25 +/- 4 25 +/- 5 18 +/- 4 16 +/- 5 14 +/- 4 12 +/- 4 9 +/- 3 9 +/- 4 8 +/- 4 14 +/- 5 11 +/- 4 15 +/- 4 15 +/- 4 12 +/- 4 10 +/- 3 16 +/- 5 19 +/- 4 13 +/- 4 13 +/- 4 19 +/- 4 12 +/- 4 15 +/- 4 15 +/- 4 15 +/- 4 20 +/- 4 20 +/- 5 18 +/- 4 11 +/- 4 19 +/- 4 18 +/- 4 24 +/- 5 19 +/- 5 14 +/- 4 13 +/- 4 16 +/- 4 17 +/- 5 16 +/- 4 18 +/- 4 26 +/- 5 19 +/- 5 18 +/- 4 15 +/- 4 31 +/- 5 37 +/- 6 38 +/- 5 27 +/- 5 18 +/- 13 25 +/- 5 19 +/- 4 13 +/- 4 8 +/- 3 16 +/- 4 17 +/- 5 30 +/- 5 24 +/- 5 18 +/- 4 9 +/- 5 11 +/- 3 16 +/- 4 8 +/- 3 9 +/- 4 10 +/- 4 14 +/- 5 8 +/- 4 11 +/- 4 13 +/- 4 8 +/- 4 13 +/- 4 19 +/- 5 16 +/- 4 11 +/- 4 13 +/- 4 17 +/- 4 13 +/- 4 15 +/- 4 13 +/- 4 15 +/- 4 18 +/- 4 19 +/- 5 19 +/- 4 13 +/- 4 18 +/- 4 21 +/- 4 24 +/- 5 17 +/- 5 8 +/- 3 9 +/- 3 17 +/- 4 14 +/- 4 11 +/- 4 14 +/- 4 14 +/- 4 15 +/- 4 11 +/- 4 12 +/- 4 26 +/- 5 40 +/- 6 24 +/- 5 24 +/- 5 16 +/- 13

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, 2019 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA GROUP I - NEAR-SITE LOCATIONS GROUP II - FAR-FIELD LOCATIONS GROUP Ill - CONTROL LOCATION COLLECTION MIN MAX MEAN COLLECTION MIN MAX MEAN COLLECTION MIN MAX MEAN PERIOD

+/-2SD PERIOD

+/-2SD 01/04/19 - 02/01/19 13 27 21 +/- 9 01/04/19 - 02/01/19 10 29 19 +/- 11 01/04/19 - 02/01/19 8

25 16 +/- 15 02/01/19 - 03/01/19 13 25 19 +/- 8 02/01/19 - 03/01/19 8

26 17 +/- 12 02/01/19 - 03/01/19 16 30 22 +/- 13 03/01 /19 - 03/29/19 8

22 14 +/- 7 03/01/19 - 03/29/19 5

19 14 +/- 8 03/01/19 - 03/28/19 9

18 13 +/- 9 03/29/19 - 05/03/19 5

15 8 +/- 5 03/28/19 - 05/03/19 4

15 9 +/- 5 03/28/19 - 05/02/19 8

14 10 +/- 5 05/03/19 - 05/31/19.

6 17 11 +/- 6 05/02/19 - 05/31/19 5

19 11 +/- 7 05/02/19 - 05/31/19 8

13 11 +/- 5 05/31/19 - 06/28/19 11 19 16 +/- 5 05/31 /19 - 06/28/19 10 19 13 +/- 5 05/31/19 - 06/27/19 11 19 15 +/- 7 06/28/19 - 08/02/19 5

18 12 +/- 7 06/27/19 - 08/02/19 8

19 12 +/- 6 06/27/19 - 08/01/19 13 17 14 +/- 3 08/02/19 - 08/31/19 8

18 15 +/- 5 08/01/19 - 08/31/19 11 20 16 +/- 7 08/01 /19 - 08/29/19 13 19 17 +/- 6 08/31/19 - 10/04/19 7

29 17 +/- 11 08/29/19 - 10/04/19 11 24 17 +/- 7 08/29/19 - 10/03/19 8

24 18 +/- 13 10/04/19 - 11/01/19 8

20 12 +/- 6 10/03/19 - 11/01/19 8

17 14 +/- 6 10/03/19 - 10/31/19 9

17 13 +/- 7 11/01/19 - 11/29/19 13 26 18 +/- 8 10/31/19 - 11/29/19 12 26 18 +/- 7 10/31/19 - 11/29/19 11 15 14 +/- 3 11/29/19 - 01/03/20 10 34 23 +/- 17 11 /29/19 - 01 /03/20 11 38 23 +/- 17 11/29/19 - 01/02/20 12 40 25 +/- 19 0

I 01/04/19 - 01/03/20 5

34 15 +/- 12 01/04/19 - 01/03/20 4

38 15 +/- 12 01/04/19 - 01/02/20 8

40 16 +/- 13 00

Table C~V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-01 01/11/19 - 03/29/19

<2

< 2

< 6

< 3

< 6

< 2

<4

< 2

< 3

< 22

< 10 03/29/19 - 06/28/19

< 3

< 6

< 3

< 5

< 3

< 5

<2

< 2

< 29

< 10 06/28/19 - 10/04/19

<2

< 2

< 4

< 2

< 6

< 3

<4

<2

< 18

< 6 10/04/19 - 01/03/20

< 2

< 5

< 3

< 7

< 3

< 5

< 3

<2

< 11

< 7 MEAN Q-02 01/04/19 - 03/29/19

< 2

< 9

< 2

< 5

< 3

< 5

< 2

< 16

< 6 03/29/19 - 06/28/19

< 3

<4

< 9

< 3

< 6

< 3

< 5

<4

< 2

< 37

< 6 06/28/19 - 10/04/19

< 3

< 5

< 3

< 5

< 3

<4

< 2

< 17

< 5 10/04/19 - 01/03/20

< 2

<4

< 2

< 4

< 2

< 3

< 1

< 2

< 10

< 5 MEAN 0

I Q-03 01/04/19 - 03/29/19

< 2

< 3

< 8

< 3

< 5

< 3

< 6

< 3

< 25

< 10

<O 03/29/19 - 06/28/19

< 3

<4

< 9

<4

< 7

<4

< 6

< 3

< 48

< 11 06/28/19 - 10/04/19

< 2

< 5

< 3

< 5

< 2

<4

< 2

< 13

< 6 10/04/19 - 01/03/20

< 2

< 3

< 2

< 3

< 2

< 1

< 11

<4 MEAN Q-04 01/04/19 - 03/29/19

<2

< 3

< 7

< 2

<4

< 2

< 5

<2

< 3

< 29

< 10 03/29/19 - 06/28/19

<2

< 2

< 7

< 3

< 6

< 3

< 5

<2

< 3

< 26

< 10 06/28/19 - 10/04/19

<2

<6

< 3

< 6

< 2

<4

<2

< 2

< 19

< 8 10/04/19 - 01/03/20

<4

< 4

< 9

< 4

< 8

<4

< 7

<4

< 22

< 7 MEAN Q-13 01/04/19 - 03/28/19

< 3

<4

< 9

<4

< 7

< 5

< 6

< 3

< 30

< 12 03/28/19 - 06/27/19

< 2

<.3

< 5

< 1

< 5

< 3

< 5

< 3

< 2

< 25

< 9 06/27/19 - 10/03/19

< 2

< 3

< 6

< 2

< 6

< 3

<4

< 2

< 16

< 8 10/03/19 - 01/02/20

< 2

< 4

< 2

< 3

<2

< 3

<2

< 2

< 12

< 2 MEAN

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-16 01/04/19 - 03/28/19

< 2

< 3

< 8

< 2

< 7

<2

< 5

< 3

< 2

< 27

<4 03/28/19 - 06/27/19

< 2

< 3

< 7

< 3

< 8

<2

< 5

< 2

< 26

< 13 06/27 /19 - 10/03/19

< 2

<4

< 2

< 6

<2

< 3

< 2

< 17

< 7 10/03/19 - 01102120

< 2

< 6

< 2

< 6

< 3

< 5

< 3

< 2

< 12

< 5 MEAN Q-37 01/04/19 - 03/29/19

< 2

< 3

< 2

< 5

< 2

< 5

< 2

< 22

< 9 03/29/19 - 06/28/19

< 3

<4

< 9

< 2

< 7

<4

< 7

<4

< 46

< 24 06/28/19 - 10/04/19

< 2

< 3

< 5

< 2

< 7

< 3

< 4

< 3

< 2

< 18

< 5 10/04/19 - 01 /03/20

< 3

<4

< 3

< 6

< 2

< 4

< 3

< 13

< 5 MEAN 0

I

~

Q-38 01/04/19 - 03/29/19

< 3

< 7

< 3

< 8

< 3

< 6

< 3

< 29

< 9 0

03/29/19 - 06/28/19

< 2

< 3

< 7

< 3

< 6

< 3

<4

< 3

< 31

< 12 06/28/19 - 10/04/19

< 3

< 7

<4

< 7

< 3

< 5

< 3

< 21

< 10 10/04/19 - 01/03/20

< 2

< 1

< 4

< 3

<4

< 2

< 1

< 11

< 3 MEAN Q-41 01/04/19 - 03/28/19

< 3

< 5

< 2

< 5

< 2

< 5

< 2

< 20

< 12 03/28/19 - 06/27/19

< 2

< 3

< 6

< 2

< 6

< 2

<4

< 2

<2

< 30

< 16 06/27/19 - 10/03/19

< 2

<4

< 2

<6

<2

<4

< 2

< 15

< 7 10/03/19 - 01 /02/20

< 2

< 1

< 5

< 2

< 5

< 2

< 1

<2

< 12

<4 MEAN Q-42 01/04/19 - 03/28/19

< 3

<4

< 9

< 3

< 7

<4

< 7

<4

< 3

< 34

< 8 03/28/19 - 06/27/19

< 2

<2

< 4

< 2

< 5

< 2

< 5

< 2

<2

< 25

<6 06/27/19 - 10/03/19

< 2

<2

< 5

< 2

< 5

< 2

< 3

< 2

<2

< 16

< 8 10/03/19 - 01 /02/20

< 3

<4

< 7

< 3

< 8

< 3

< 5

< 3

< 19

< 7 MEAN

TABLE C-VI.1 COLLECTION PERIOD 01/04/19 - 01/11/19 01/10/19 - 01/18/19 01/17/19 - 01/25/19 01/24/19 - 02/01/19 02/01/19 - 02/08/19 02/08/19 - 02/15/19 02/14/19 - 02/22/19 02/22/19 - 03/01/19 03/01/19 - 03/08/19 03/08/19 - 03/16/19 03/14/19 - 03/22/19 03/21/19 - 03/29/19 03/28/19 - 04/05/19 04/05/19 - 04/12/19 04/12/19 - 04/19/19 04/19/19 - 04/26/19 04/25/19 - 05/03/19 05/02/19 - 05/10/19 05/09/19 - 05/17/19 05/16/19 - 05/24/19 05/23/19 - 05/31/1.9 05/31/19 - 06/07/19 06/06/19 - 06/13/19 06/13/19 - 06/20/19 06/20/19 - 06/28/19 06/27/19 - 07/05/19 07/05/19 - 07/12/19 07/11/19 - 07/19/19 07/18/19 - 07/26/19 07/25/19 - 08/02/19 08/01/19 - 08/09/19 08/09/19 - 08/16/19 08/15/19 - 08/24/19 08/22/19 - 08/31/19 08/29/19 - 09/06/19 09/05/19 - 09/14/19 09/12/19 - 09/20/19 09/19/19 - 09/28/19 09/26/19 - 10/04/19 10/03/19 - 10/11/19 10/10/19 - 10/19/19 10/17/19 - 10/25/19 10/24/19 - 11/01/19 10/31/19 - 11/08/19 11/07/19 - 11/15/19 11/15/19 - 11/22/19 11/22/19 - 11/29/19 11 /29/19 - 12/06/19 12/05/19 - 12/13/19 12/12/19 - 12/20/19 12/19/19 - 12/28/19 12/26/19 - 01/03/20 MEAN CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA Q-01 (1)

< 42

< 17

< 27

< 23

< 15

< 54

< 42

< 41

< 18

< 29

< 22

< 15

< 19

< 22

< 24

< 51

< 21

< 37

< 39

< 53 (1)

(1)

< 27

< 21

< 43

< 24

< 10

< 20

< 30

< 26

< 55

< 24

< 15

< 28

< 39

< 41

< 32

< 37

< 20

< 9

< 45

< 20

< 53

< 38

< 31

< 48

< 29

< 41

< 59 GROUP I Q-02

< 46

< 11

< 20

< 27

< 41

< 42

< 52

< 30

< 47

< 42

< 67

< 50

< 59

< 17

< 43

< 50

< 54

< 49

< 48

< 36

< 63

< 66 (1)

(1)

< 31

< 26

< 25

< 17

< 43

< 23

< 47

< 29

< 26

< 53

< 56

< 34

< 33

< 38

< 47

< 31

< 35

< 23

< 21

< 18

< 39

< 53

< 38

< 31

< 20

< 29

< 41

< 59 Q-03

< 46

< 11

< 20

< 27

< 41

< 42

< 52

< 49

< 47

< 42

< 67

< 50

< 59

< 17

< 43

< 50

< 54

< 21

< 48

< 36

< 63

< 22 (1)

(1)

< 31

< 26

< 25

< 41

< 43

< 23

< 47

< 24

< 26

< 53

< 56

< 34

< 33

< 38

< 47

< 13

< 35

< 23

< 21

< 43

< 39

< 53

< 18

< 31

< 48

< 29

< 41

< 59 Q-04

< 46

< 11

< 20

< 27

< 41

< 42

< 52

< 49

< 47

< 42

< 67

< 50

< 59

< 17

< 43

< 50

< 54

< 49

< 48

< 35

< 63

< 52 (1)

(1)

< 31

< 26

< 24

< 41

< 43

< 23

< 46

< 29

< 26

< 53

< 56

< 34

< 33

< 16

< 47

< 31

< 35

< 23

< 21

< 43

< 38

< 53

< 20

< 31

< 48

< 29

< 41

< 59 Q-13

< 56

< 6

< 23

< 10

< 42

< 53

< 25

< 33

< 47

< 65

< 58

< 57

< 50

< 17

< 44

< 60

< 63

< 55

< 52

< 30

< 58

< 65

< 26

< 52

< 30

< 8

< 31

< 47

< 45

< 25

< 40

< 35

< 14

< 26

< 54

< 46

< 30

< 49

< 46

< 33

< 20

< 22

< 49

< 33

< 45

< 40

< 16

< 51

< 35

< 47

< 27 Q-16

< 49

< 16

< 37

< 13

< 27

< 29

< 20

< 33

< 62

< 37

< 21

< 27

< 11

< 30

< 35

< 32

< 22

< 24

< 48

< 26

< 52

< 25

< 20

< 45

< 32

< 21

< 29

< 28

< 49

< 24 (1)

< 47

< 32

< 28

< 38

< 49

< 23

< 33

< 11

< 18

< 25

< 37

< 30

< 40

< 30

< 22

< 60

< 45

< 52 GROUP II Q-37

< 41

< 37

< 40

< 19

< 37

< 31

< 55

< 50

< 64

< 25

< 59

< 32

< 33

< 27

< 36

< 31

< 42

< 33

< 36

< 54

< 38

< 38 (1)

(1)

< 33

< 10

< 15

< 29

< 49

< 11

< 29

< 42

< 22

< 41

< 61

< 24

< 31

< 52

< 25

< 26

< 28

< 15

< 24

< 45

< 30

< 40

< 25

< 26

< 54

< 36

< 56 Q-38

< 22

< 35

< 39

< 18

< 32

< 33

< 53

< 49

< 62

< 20

< 57

< 30

< 32

< 26

< 35

< 30

< 40

< 33

< 35

< 52

< 37

< 38 (1)

(1)

< 33

< 23

< 36

< 29

< 49

< 26

< 33

< 41

< 18

< 40

< 59

< 24

< 30

< 50

< 24

< 21

< 27

< 17

< 23

< 44

< 29

< 39

< 20

< 25

< 52

< 35

< 54 Q-41

< 49

< 38

< 44

< 20

< 33

< 35

< 47

< 33

< 26

< 37

< 50

< 33

< 27

< 37

< 38

< 43

< 37

< 39

< 54

< 36

< 49

< 27

< 54

< 31

< 20

< 47

< 33

< 50

< 30

< 29

< 21

< 29

< 49

< 59

< 33

< 29

< 39

< 42

< 26

< 34

< 27

< 19

< 22

< 39

< 26

< 40

< 31

< 27

< 62

< 38

< 54 GROUP Ill Q-42

< 50

< 39

< 46

< 16

< 34

< 35

< 48

< 34

< 64

< 39

< 52

< 34

< 23

< 27

< 37

< 38

< 44

< 31

< 39

< 55

< 30

< 41

< 27

< 54

< 31

< 21

< 47

< 28

< 51

< 30

< 29

< 51

< 29

< 49

< 59

< 28

< 24

< 33

< 51

< 26

< 34

< 27

< 18

< 26

< 18

< 30

< 39

< 30

< 27

< 33

< 46

< 22 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-11

Table C-Vll.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION INDICATOR FARM PERIOD Q-26 01/04/19

< 0.8 02101/19

< 0.8 03108/19

< 0.8 04/05/19

< 1.0 05/03/19

< 0.6 05/17/19

< 0.8 05/31/19

< 0.8 06/14/19 (1) 06128/19

< 0.8 07112119

< 0.8 07/26/19

< 0.8 08/09/19

< 0.5 08124/19

< 0.9 09/06/19

< 0.8 09120119

< 0.8 10/04119

< 1.0 10/19/19

< 0.8 11/01/19

< 0.8 12106/19

< 1.0 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-12

Table C-Vll.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-26 01104119

<4

< 10

< 5

< 10

< 5

< 8

< 5

< 23

< 8 02101119

< 5

< 13

< 6

< 12

< 6

< 10

< 6

< 29

< 11 03108119

< 7

< 9

< 19

< 9

< 19

< 7

< 15

< 7

< 10

< 53

< 6 04105119

< 5

< 6

< 12

< 5

< 13

< 5

< 9

< 6

< 29

< 7 05103119

< 6

< 8

< 18

< 6

< 16

< 7

< 12

< 7

< 6

< 28

< 11 05117119

< 8

< 7

< 18

< 8

< 16

< 8

< 13

< 7

< 35

< 11 05131119

<6

< 8

< 19

< 8

< 15

< 8

< 14

< 7

< 8

< 41

< 12 06114119 (1) 06128119

< 7

< 6

< 13

< 5

< 15

< 7

< 11

< 7

< 31

< 7 07112119

< 7

< 14

< 7

< 16

< 7

< 12

< 6

< 7

< 27

< 7 07126119

< 7

< 9

< 17

< 6

< 18

< 7

< 13

< 8

< 7

< 35

< 9

(")

08109119

< 6

< 13

< 8

< 14

< 7

< 10

< 7

< 29

< 9 I

08124119

< 7

< 6

< 15

< 8

< 15

< 7

< 11

< 7

< 28

< 7 w

09106119

< 6

< 7

< 14

< 7

< 16

< 8

< 11

< 6

< 7

< 42

< 11 09120119

< 7

< 9

< 18

< 10

< 19

< 8

< 15

< 9

< 8

< 50

< 12 10104119

< 5

< 6

< 14

< 7

< 14

< 6

< 11

< 7

< 6

< 35

< 12 10119119

< 7

< 16

< 8

< 24

< 9

< 13

< 8

< 9

< 37

< 10 11101119

< 5

<6

< 15

< 6

< 17

< 5

< 10

<6

< 6

< 27

< 12 12106119

< 9

< 7

< 21

< 10

< 15

< 7

< 12

< 8

< 9

< 31

< 14 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-Vlll.1 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Q-CONTROL RADISHES/BROCCOLI 07/24/19

< 32

< 25

< 62

< 36

< 63

< 28

< 49

< 51

< 22

< 31

< 167

< 29 POTATOES 07/24/19

< 31

< 27

< 66

< 36

< 71

< 32

< 54

< 50

< 35

< 33

< 133

< 34 ONIONS 07/24/19

< 29

< 22

< 52

< 23

< 64

< 26

< 35

< 44

< 28

< 22

< 108

< 30 MEAN Q-QUAD 1 POTATOES 07/24/19

< 31

< 77

< 31

< 62

< 33

< 57

< 46

< 40

< 30

< 119

< 30 LETTUCE 07/24/19

< 31

< 56

< 25

< 60

< 31

< 50

< 33

< 28

< 121

< 46 PARSNIPS 07/24/19

< 39

< 37

< 70

< 44

< 91

< 40

< 61

< 52

< 43

< 30

< 183

< 55 MEAN 0

Q-QUAD 2 I

ZUCCHINI LEAVES 07/24/19

< 34

< 43

< 97

< 36

< 95

< 40

< 67

< 58

< 41

< 36

< 158

< 35

~

.j::.

CABBAGE 07/24/19

< 20

< 21

< 39

< 23

< 38

< 21

< 38

< 33

< 23

< 22

< 89

< 22 ONIONS 07/24/19

< 16

< 15

< 32

< 18

< 33

< 17

< 29

< 24

< 18

< 77

< 21 MEAN Q-QUAD 3 TURNIP GREENS 07/24/19

< 18

< 25

< 52

< 17

< 56

< 23

< 35

< 28

< 22

< 23

< 99

< 20 DILL 07/24/19

< 30

< 28

< 69

< 26

< 62

< 28

< 51

< 38

< 35

< 30

< 123

< 35 HORSERADISH 07/24/19

< 31

< 30

< 59

< 37

< 73

< 32

< 57

< 44

< 30

< 29

< 141

< 44 MEAN Q-QUAD4 CABBAGE 07/25/19

< 32

< 76

< 36

< 75

< 50

< 72

< 55

< 40

< 37

< 164

< 47 POTATOES 07/25/19

< 26

< 29

< 69

< 22

< 81

< 27

< 41

< 48

< 33

< 31

< 141

< 26 RHUBARB 07/25/19

< 23

< 15

< 35

< 22

< 54

< 25

< 42

< 38

< 19

< 24

< 95

< 30 MEAN

Table C-IX.1 QUARTERLY DLR RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2019 Location 2019 Normalized Net Dose, Max Monitoring Quarterly Ba+ MDDa (mrem/std. Qtr.)

Quarterly Facility Dose, Fa (mrem)

Location Baseline, Ba (mrem)

(mrem) 1 I

2 I

3 I

4 1

I 2

I 3

I 4

Other Q-01-1 11.02 15.6 10.3 12.3 11.1 12.6 ND ND ND ND Q-01-2 11.32 15.9 9.2 11.5 12.5 14.5 ND ND ND ND Q-02-1 11.9 16.4 8.8 14.0 13.7 13.0 ND ND ND ND Q-02-2 11.18 15.7 8.1 12.0 12.9 11.0 ND ND ND ND Q-03-1 10.35 14.9 8.8 10.1 10.8 9.4 ND ND ND ND Q-03-2 10.32 14.9 7.8 10.4 10.3 12.2 ND ND ND ND Q-04-1 11.84 16.4 9.2 10.6 11.2 13.3 ND ND ND ND Q-04-2 12.59 17.1 9.6 11.2 10.5 13.2 ND ND ND ND Q-13-1 13.05 17.6 9.7 12.5 14.6 14.3 ND ND ND ND Q-13-2 13.2 17.7 10.9 10.5 13.7 12.0 ND ND ND ND Q-16-1 10.93 15.5 9.0 10.0 9.8 11.5 ND ND ND ND Q-16-2 10.78 15.3 9.4 11.4 11.5 11.1 ND ND ND ND Q-37-1 13.65 18.2 11.1 13.4 11.9 14.3 ND ND ND ND Q-37-2 13.58 18.1 12.3 15.3 13.2 12.2 ND ND ND ND Q-38-1 14.55 19.1 9.8 12.8 14.6 16.9 ND ND ND ND Q-38-2 14.53 19.1 10.9 14.5 12.7 14.6 ND ND ND ND Q-41-1 13.69 18.2 11.0 11.7 12.5 15.1 ND ND ND ND Q-41-2 13.7 18.2 9.8 11.7 12.9 13.7 ND ND ND ND Q-42-1 14.29 18.8 12.4 13.8 15.7 13.6 ND ND ND ND Q-42-2 14.61 19.1 11.7 14.1 14.3 15.9 ND ND ND ND Inner Q-101-1 11.62 16.2 9.5 11.2 12.8 12.8 ND ND ND ND Q-101-2 12.19 16.7 8.8 12.8 12.1 13.1 ND ND ND ND Q-102-1 12.9 17.4 12.0 12.6 14.6 13.7 ND ND ND ND Q-102-3 12.23 16.8 10.9 11.7 12.9 11.0 ND ND ND ND Q-103-1 10.82 15.4 9.1 9.7 9.9 12.5 ND ND ND ND Q-103-2 10.78 15.3 8.0 11.2 12.7 11.3 ND ND ND ND Q-104-1 11.11 15.6 9.1 9.9 10.6 11.8 ND ND ND ND Q-104-2 11.94 16.5 9.1 10.6 11.0 12.3 ND ND ND ND Q-105-1 11.37 15.9 8.3 10.6 10.9 10.4 ND ND ND ND Q-105-2 11.68 16.2 10.4 10.7 11.2 13.4 ND ND ND ND Q-106-2 11.81 16.3 9.6 11.6 10.7 12.9 ND ND ND ND Q-106-3 11.47 16.0 9.1 11.3 11.3 11.9 ND ND ND ND Q-107-2 11.38 15.9 10.8 12.3 11.2 11.1 ND ND ND ND Q-107-3 11.54 16.1 9.6 11.1 11.3 12.0 ND ND ND ND Q-108-1 11.72 16.3 8.3 10.4 12.7 12.5 ND ND ND ND Q-108-2 11.44 16.0 9.4 11.3 10.6 11.7 ND ND ND ND Q-109-1 12.25 16.8 8.7 11.1 11.5 11.4 ND ND ND ND Q-109-2 11.79 16.3 9.3 11.9 11.2 13.1 ND ND ND ND Q-111-1 11.87 16.4 10.2 8.3 13.7 13.2 ND ND ND ND Q-111-2 11.94 16.5 10.2 14.3 13.2 15.2 ND ND ND ND Q-112-1 11.98 16.5 10.1 12.1 12 12.8 ND ND ND ND Q-112-2 11.35 15.9 8.5 11.1 12.1 10.6 ND ND ND ND Q-113-1 11.38 15.9 9.2 11.3 12.3 12.3 ND ND ND ND Q-113-2 10.82 15.4 7.9 10.2 11.7 10.8 ND ND ND ND Q-114-1 10.87 15.4 8.3 10.2 10.7 13.1 ND ND ND ND Q-114-2 12.21 16.7 10.6 13.4 12.3 13 ND ND ND ND Q-115-1 11.91 16.4 9.1 12.8 12.8 14.7 ND ND ND ND Q-115-2 10.99 15.5 9.1 11.1 12.9 13.8 ND ND ND ND Q-116-1 13.33 17.86 10.7 12.8 13.5 13.8 ND ND ND ND Q-116-3 12.14 16.67 10 10.9 14.1 14 ND ND ND ND C-15

Table C-IX.1 QUARTERLY DLR RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2019 Location 2019 Normalized Net Dose, Max Monitoring Quarterly Ba+ MDDa (mrem/std. Qtr.)

Quarterly Facility Dose, Fa (mrem)

Location Baseline, Ba (mrem)

(mrem) 1 I

2 I

3 I

4 1

I 2

I 3

I 4

Outer Q-201-1 12.86 17.39 8.7 10.2 12.3 14.1 ND ND ND ND Q-201-2 13.58 18.11 12.1 14.2 13.5 14.5 ND ND ND ND Q-202-1 11.55 16.08 8.8 10.6 12.4 13.4 ND ND ND ND Q-202-2 12.64 17.17 9.7 14 13.4 14.6 ND ND ND ND Q-203-1 13.12 17.65 11 12.8 LOST 14.4 ND ND ND ND Q-203-2 15.73 20.26 13.2 13.9 15 16.3 ND ND ND ND Q-204-1 14.03 18.56 11.5 12.1 14.1 14.7 ND ND ND ND Q-204-2 15.33 19.86 14 14.8 15.3 17.7 ND ND ND ND Q-205-1 13.57 18.1 11.1 12.6 11.8 15.8 ND ND ND ND Q-205-4 15.16 19.69 10.4 15.7 15.7 14.7 ND ND ND ND Q-206-1 12.57 17.1 9.7 11.9 13.2 11.2 ND ND ND ND Q-206-2 11.46 15.99 10.8 11.6 11.8 13.6 ND ND ND ND Q-207-1 12.88 17.41 9.9 12.5 16.3 15.1 ND ND ND ND Q-207-4 13.72 18.25 10 12.8 15.7 15 ND ND ND ND Q-208-1 12.94 17.47 9.8 13.1 13.4 13.3 ND ND ND ND Q-208-2 14.47 19 10.7 13.9 14.5 13.6 ND ND ND ND Q-209-1 13.45 17.98 13 13.5 14.3 17 ND ND ND ND Q-209-4 13.19 17.72 11.7 12.7 13.3 15 ND ND ND ND Q-210-1 14.97 19.5 11.5 15.2 LOST 15.7 ND ND ND ND Q-210-4 14.5 19.03 11.3 13.9 14.4 17.2 ND ND ND ND Q-210-5 10.51 15.04 8.2 9.8 10.5 10.5 ND ND ND ND Q-211-1 16.11 20.64 12.7 14.4 16.8 17 ND ND ND ND Q-211-2 16.28 20.81 13.4 15.5 18.1 19 ND ND ND ND Q-212-1 12.93 17.46 10 13.2 12.5 13.5 ND ND ND ND Q-212-2 10.76 15.29 8.6 11 10.7 11.7 ND ND ND ND Q-213-1 11.9 16.43 8.3 12 13.4 12 ND ND ND ND Q-213-2 11.36 15.89 9

10 13.1 12.5 ND ND ND ND Q-214-1 12.54 17.07 10.6 10.7 14.1 12.9 ND ND ND ND Q-214-2 13.31 17.84 11.5 14 15.6 14.7 ND ND ND ND Q-215-1 12.02 16.55 9

11.4 13 14.8 ND ND ND ND Q-215-2 13.89 18.42 12.6 13.4 14.5 13.2 ND ND ND ND Q-216-1 14.94 19.47 13.8 15.6 16.5 14.6 ND ND ND ND Q-216-2 13.72 18.25 LOST 13.4 16.4 15.6 ND ND ND ND C-16

Table C-IX.2 ANNUAL DLR RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2019 Annual Baseline, Normalized Annual Monitoring Location BA(mrem)

BA+ MDDA (mrem)

Annual Dose, MA Facility Dose, FA (mrem/yr)

Other Q-01-1 44.07 52.9 46.3 ND Q-01-2 45.26 54.1 47.7 ND Q-02-1 47.61 56.5 49.5 ND Q-02-2 44.72 53.6 44.0 ND Q-03-1 41.42 50.3 39.1 ND Q-03-2 41.3 50.2 40.7 ND Q-04-1 45 53.9 44.3 ND Q-04-2 47.83 56.7 44.5 ND Q-13-1 52.21 61.1 51.1 ND Q-13-2 52.78 61.6 47.1 ND Q-16-1 43.73 52.6 40.3 ND Q-16-2 43.11 52.0 43.4 ND Q-37-1 54.61 63.5 50.7 ND Q-37-2 54.33 63.2 53.0 ND Q-38-1 55.31 64.2 54.1 ND Q-38-2 55.23 64.1 52.7 ND Q-41-1 54.76 63.6 50.3 ND Q-41-2 54.81 63.7 48.1 ND Q-42-1 57.16 66.0 55.5 ND Q-42-2 58.46 67.3 56.0 ND Inner Q-101-1 46.47 55.3 46.3 ND Q-101-2 48.77 57.6 46.8 ND Q-102-1 51.59 60.4 52.9 ND Q-102-3 48.9 57.8 46.5 ND Q-103-1 43.29 52.1 41.2 ND Q-103-2 43.12 52.0 43.2 ND Q-104-1 42.2 51.1 41.4 ND Q-104-2 47.75 56.6 43.0 ND Q-105-1 45.49 54.3 40.2 ND Q-105-2 46.73 55.6 45.7 ND Q-106-2 47.23 56.1 44.8 ND Q-106-3 45.89 54.7 43.6 ND Q-107-2 43.25 52.1 45.4 ND Q-107-3 46.16 55.0 44.0 ND Q-108-1 44.52 53.4 43.9 ND Q-108-2 45.75 54.6 43.0 ND Q-109-1 46.53 55.4 42.7 ND Q-109-2 47.17 56.0 45.5 ND Q-111-1 47.48 56.3 45.4 ND Q-111-2 47.75 56.6 52.9 ND Q-112-1 45.53 54.4 47 ND Q-112-2 45.4 54.3 42.3 ND Q-113-1 45.52 54.4 45.1 ND Q-113-2 43.3 52.2 40.6 ND Q-114-1 43.46 52.3 42.3 ND Q-114-2 48.83 57.7 49.3 ND Q-115-1 45.26 54.1 49.4 ND Q-115-2 41.76 50.6 46.9 ND Q-116-1 53.32 62.17 50.8 ND Q-116-3 48.55 57.4 49 ND C-17

Table C-IX.2 ANNUAL DLR RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2019 Annual Baseline, Normalized Annual Monitoring Location BA(mrem)

BA+ MDDA (mrem)

Annual Dose, MA Facility Dose, FA (mrem/yr)

Outer Q-201-1 48.87 57.72 45.3 ND Q-201-2 51.6 60.45 54.3 ND Q-202-1 46.2 55.05 45.2 ND Q-202-2 50.58 59.43 51.7 ND Q-203-1 49.87 58.72 38.2 ND Q-203-2 62.91 71.76 58.4 ND Q-204-1 53.31 62.16 52.4 ND Q-204-2 61.34 70.19 61.8 ND Q-205-1 54.28 63.13 51.3 ND Q-205-4 57.6 66.45 56.5 ND Q-206-1 50.28 59.13 46 ND Q-206-2 45.85 54.7 47.8 ND Q-207-1 51.51 60.36 53.8 ND Q-207-4 54.89 63.74 53.5 ND Q-208-1 51.77 60.62 49.6 ND Q-208-2 57.89 66.74 52.7 ND Q-209-1 53.81 62.66 57.8 ND Q-209-4 52.76 61.61 52.7 ND Q-210-1 59.88 68.73 42.4 ND Q-210-4 55.09 63.94 56.8 ND Q-210-5 42.02 50.87 39 ND Q-211-1 64.43 73.28 60.9 ND Q-211-2 65.14 73.99 66 ND Q-212-1 49.15 58 49.2 ND Q-212-2 40.89 49.74 42 ND Q-213-1 47.61 56.46 45.7 ND Q-213-2 45.46 54.31 44.6 ND Q-214-1 50.14 58.99 48.3 ND Q-214-2 53.24 62.09 55.8 ND Q-215-1 45.69 54.54 48.2 ND Q-215-2 55.56 64.41 53.7 ND Q-216-1 56.78 65.63 60.5 ND Q-216-2 54.87 63.72 45.4 ND C-18

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

Collected in the Vicinity of QCNPS, 2000 - 2019 Q-33 Cordova 12.0 10.0 8.0

...I

~

6.0

c.

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

01-01-00 01-01-04 01-01-08 01-01-12 01-01-16 01-01-20 Q-34 (C) Camanche 12.0 10.0 8.0

...I

~

6.0

c.

4.0 2.0 0.0 +----------+------+-----+------i 01-01-00 01-01-04 01-01-08 01-01-12 01-01-16 01-01-20 DUE TO VENDOR CHANGE, <VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-19

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

Collected in the Vicinity of QCNPS, 2000 - 2019

...J

~*

c.

...J

~

c.

Q-33 Cordova 500 400 300 200 100 0-1-~___..,__-+-~~~-.-~~~......-~~~~~~~--.

01-01-00 01-01-04 01-01-08 01-01-12 01-01-16 01-01-20 Q-34 (C) Camanche 500 400 300 200 100 0-1-~~~-t-V~~~-+-~~~---~~~-1-~~~-i 01-01-00 01-01-04 01-01-08 01-01-12 01-01-16 01-01-20 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-20

FIGURE C-3 Ground Water -Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2019

...J 5

c.

(3 c.

Q-35 McMillan Well 500 400 300 200 100 O+-'---..:;.....J0~-¥-~~~-4-~~~-1-~~~-1-~~~-1 12-31-99 12-31-03 12-31-07 12-31-11 12-31-15 12-31-19 Q-36 Cordova Well 500 400 300 200 100 O+---v~~..y-~~~-+-~~~-1-~~~-1-~~~-1 12-31-99 12-31-03 12-31-07 12-31-11 12-31-15 12-31-19 DUE TO VENDOR CHANGE, <VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-21

FIGURE C-4 Air Particulates - Gross Beta-Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2019 70.0 60.0 50.0

(")

.§ (3

40.0 Q.

t?

30.0 w

0.....

20.0 10.0 Q-01 Onsite No. 1 0.0 +------+---~----+--------1----1 01-07-00 70.0 60.0 50.0

(")

.§ (3

40.0 Q.

g 30.0 w

~

20.0 10.0 01-07-04 01-07-08 01-07-12 01-07-16 01-07-20 Q-02 Onsite No. 2 0.0 --~f-----l-----+----+------1 01-07-00 01-07-04 01-07-08 01-07-12 01-07-16 01-07-20 C-22

FIGURE C-5 Air Particulates - Gross Beta-Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 20QQ-;.*2&1'9 60.0 50.0 C')

40.0

.§ u

a.

30.0 C')

9 w 20.0 0.....

10.0 0.0 01-07-00 60.0 50.0 C')

40.0 E n

a.

C')

30.0 9 w 20.0 0....,

10.0 Q-03 Onsite No. 3 01-07-04 01-07-08 01-07-12 01-07-16 01-07-20 Q-04 Nitrin 0.0 +-----1------1------1------1-----1 01-07-00 01-07-04 01-07-08 01-07-12 01-07-16 01-07-20 C-23

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 M

.E 40.0 u

c.

M 30.0 0 w 0

20.0 10.0 0.0 01-07-00 03-19-02 05-29-04 08-09-06 10-19-08 12-30-10 This location was removed from the program in January 2011 due to updated annual average meteorology.

This data is retained in the report for historical comparision.

C-24

FIGURE C-7 Air Particulates - Gross Beta-Stations Q-13 and Q-16 Collected in the Vicinity of QCNPS, 2005 - 2019 60.0 50.0

<')

40.0

.§ i:3 Q.

30.0

<')

9

~ 20.0 10.0 Q-13 Princeton 0.0 +-----------------11--------1 07-08-05 02-20-09 10-05-12 05-20-16 01-03-20 Q-16 Low Moor 60.0 50.0 40.0 30.0 20.0 10.0 0.0 +---------------1--------1 07-08-05 02-20-09 10-05-12 05-20-16 01-03-20 AIR PART/GULA TE GROSS BETA ANALYSES OF FAR FIELD LOCA T/ONS STARTED IN JULY 2005 C-25

FIGURE C-8 Air Particulates - Gross Beta-Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2018 Q-37 Meredosia Road 60.0 50.0 M

40.0

.E u Q.

30.0 M 9 w 20.0 0

~

10.0 0.0 07-08-05 02-21-09 10-07-12 05-23-16 01-07-20 Q-38 Fuller Road 60.0 50.0 M

40.0

.E u 30.0 Q.

~~

M 0

uJ 20.0 0....

10.0 0.0 07-01-05 02-15-09 10-02-12 05-19-16 01-04-20 AIR PART/GULA TE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 C-26

FIGURE C-9 Air Particulates - Gross Beta-Station Q-41 Collected in the Vicinity of QCNPS, 2009 - 2019 Q-41 Camanche 60.0 50.0 40.0

..§ u Q.

30.0 9

w 20.0 0....

10.0 0.0 01-03-09 10-05-11 07-06-14 04-06-17 01-06-20 Air Particulates - Gross Beta-Station Q-42 (C)

Collected in the Vicinity of QCNPS, 2010 - 2019 60.0 50.0

'E 4o.o 0

Q.

30.0 9

~ 20.0 10.0 Q-42 LeClaire (Control) 0.0 -----+----------if-------1 12-31-10 04-02-13 07-04-15 10-04-17 01-05-20 C-27

Intentionally left blank

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM

Intentionally left blank

Analytics Environmental Radioactivity Cross Check Program Table D.1 Teledyne Brown Engineering Environmental Services Identification TBE Known Ratio of TBE to Month/Year Number Matrix Nuclide Units Reported Value (al Analytics Result Evaluation (bl Value March 2019 E12468A Milk Sr-89 pCi/L 87.1 96 0.91 A

Sr-90 pCi/L 12.6 12.6 1.00 A

E12469A Milk Ce-141 pCi/L 113 117 0.97 A

Co-58 pCi/L 153 143 1.07 A

Co-60 pCi/L 289 299 0.97 A

Cr-51 pCi/L 233 293 0.80 A

Cs-134 pCi/L 147 160 0.92 A

Cs-137 pCi/L 193 196 0.98 A

Fe-59 pCi/L 153 159 0.96 A

1-131 pCi/L 91.5 89.5 1.02 A

Mn-54 pCi/L 149 143 1.04 A

Zn-65 pCi/L 209 220 0.95 A

E12470 Charcoal 1-131 pCi 77.5 75.2 1.03 A

E12471 AP Ce-141 pCi 60.7 70.2 0.87 A

Co-58 pCi 87.9 85.8 1.02 A

Co-60 pCi 175 179 0.98 A

Cr-51 pCi 165 176 0.94 A

Cs-134 pCi 91.2 95.9 0.95 A

Cs-137 pCi 120 118 1.02 A

Fe-59 pCi 108 95.3 1.13 A

Mn-54 pCi 94.2 85.7 1.10 A

Zn-65 pCi 102 132 0.77 w

E12472 Water Fe-55 pCi/L 2230 1920 1.16 A

E12473 Soil Ce-141 pCi/g 0.189 0.183 1.03 A

Co-58 pCi/g 0.209 0.224 0.93 A

Co-60 pCi/g 0.481 0.466 1.03 A

Cr-51 pCi/g 0.522 0.457 1.14 A

Cs-134 pCi/g 0.218 0.250 0.87 A

Cs-137 pCi/g 0.370 0.381 0.97 A

Fe-59 pCi/g 0.263 0.248 1.06 A

Mn-54 pCi/g 0.248 0.223 1.11 A

Zn-65 pCi/g 0.371 0.344 1.08 A

E12474 AP Sr-89 pCi 88.3 95.2 0.93 A

Sr-90 pCi 11.7 12.5 0.94 A

August 2019 E12562 Soil Sr-90 pCi/g 4.710 6.710 0.70 w

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

Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0. 80-1. 20 W =Acceptable with warning - reported result falls within 0. 70-0.80 or 1.20-1.30 N =Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and> 1.30 (Page 1of2)

Analytics Environmental Radioactivity Cross Check Program Table D.1 Teledyne Brown Engineering Environmental Services Identification TBE Known Ratio of TBE to MonthNear Number Matrix Nuclide Units Reported Value (a)

Analytics Result Evaluation (bl Value September 2019 E12475 Milk Sr-89 pCi/L 70.0 93.9 0.75 w

Sr-90 pCi/L 12.0 12.9 0.93 A

E12476 Milk Ce-141 pCi/L 150 167 0.90 A

Co-58 pCi/L 170 175 0.97 A

Co-60 pCi/L 211 211 1.00 A

Cr-51 pCi/L 323 331 0.98 A

Cs-134 pCi/L 180 207 0.87 A

Cs-137 pCi/L 147 151 0.97 A

Fe-59 pCi/L 156 148 1.05 A

1-131 pCi/L 81.1 92.1 0.88 A

Mn-54 pCi/L 160 154 1.04 A

Zn-65 pCi/L 303 293 1.03 A

E12477 Charcoal 1-131 pCi 95.9 95.1 1.01 A

E12478 AP Ce-141 pCi 129 138 0.93 A

Co-58 pCi 128 145 0.88 A

Co-60 pCi 181 174 1.04 A

Cr-51 pCi 292 274 1.07 A

Cs-134 pCi 166 171 0.97 A

Cs-137 pCi 115 125 0.92 A

Fe-59 pCi 119 123 0.97 A

Mn-54 pCi 129 128 1.01 A

Zn-65 pCi 230 242 0.95 A

E12479 Water Fe-55 pCi/L 1810 1850 0.98 A

E12480 Soil Ce-141 pCi/g 0.305 0.276 1.10 A

Co-58 pCi/g 0.270 0.289 0.93 A

Co-60 pCi/g 0.358 0.348 1.03 A

Cr-51 pCi/g 0.765 0.547 1.40 N(1i Cs-134 pCi/g 0.327 0.343 0.95 A

Cs-137 pCi/g 0.308 0.321 0.96 A

Fe-59 pCi/g 0.257 0.245 1.05 A

Mn-54 pCi/g 0.274 0.255 1.07 A

Zn-65 pCi/g 0.536 0.485 1.11 A

E12481 AP Sr-89 pCi 95.9 91.9 1.04 A

Sr-90 pCi 12.3 12.6 0.97 A

E12563 Soil Sr-90 pCi/g 0.392 0.360 1.09 A

(a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0. 80-1. 20 W =Acceptable with warning - reported result falls within 0. 70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0. 70 and > 1. 30 (1) See NCR 19-27 (Page 2 of 2)

DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Table D.2 Teledyne Brown Engineering Environmental Services Identification TBE Known Acceptance Month/Year Number Matrix Nuclide Units Reported Value (a)

Range Evaluation <bl Value February 2019 19-GrF40 AP Gross Alpha Sq/sample 0.184 0.528 0.158 - 0.898 A

Gross Beta Sq/sample 0.785 0.948 0.474 - 1.422 A

19-MaS40 Soil Ni-63 Bq/kg 420 519.0 363 - 675 A

Sr-90 Bq/kg (1)

NRl3l 19-MaW40 Water Am-241 Bq/L 0.764 0.582 0.407 - 0.757 NC4l Ni-63 Bq/L 4.72 5.8 4.1-7.5 A

Pu-238 Bq/L 0.443 0.451 0.316 - 0.586 A

Pu-239/240 Bq/L

-0.00161 0.0045 (2)

A 19-RdF40 AP U-234/233 Sq/sample 0.1138 0.106 0.074-0.138 A

U-238 Sq/sample 0.107 0.110 0.077 - 0.143 A

19-RdV40 Vegetation Cs-134 Sq/sample 2.14 2.44 1.71-3.17 A

Cs-137 Sq/sample 2.22 2.30 1.61 - 2.99 A

Co-57 Sq/sample 2.16 2.07 1.45 - 2.69 A

Co-60 Sq/sample 0.02382 (1)

A Mn-54 Sq/sample

-0.03607 (1)

A Sr-90 Sq/sample

-0.1060 (1)

NC5J Zn-65 Sq/sample 1.35 1.71 1.20 - 2.22 w

August 2019 19-GrF41 AP Gross Alpha Sq/sample 0.192 0.528 0.158 - 0.898 w

Gross Beta Sq/sample 0.722 0.937 0.469 - 1.406 A

19-MaS41 Soil Ni-63 Bq/kg 436 629 440 - 818 NC6l Sr-90 Bq/kg 444 572 400 - 744 w

19-MaW41 Water Am-241 Bq/L NR<7l Ni-63 Bq/L 7.28 9.7 6.8 - 12.6 w

Pu-238 Bq/L 0.0207 0.0063 (2)

A Pu-239/240 Bq/L 0.741 0.727 0.509 - 0.945 A

19-RdF41 AP U-234/233 Sq/sample 0.0966 0.093 0.065 - 0.121 A

U-238 Sq/sample 0.0852 0.096 0.067-0.125 A

19-RdV41 Vegetation Cs-134 Sq/sample 0.0197 (1)

A Cs-137 Sq/sample 3.21 3.28 2.30 - 4.26 A

Co-57 Sq/sample 4.62 4.57 3.20 - 5.94 A

Co-60 Sq/sample 4.88 5.30 3.71-6.89 A

Mn-54 Sq/sample 4.54 4.49 3.14 - 5.84 A

Sr-90 Sq/sample 0.889 1.00 0.70 - 1.30 A

Zn-65 Sq/sample 2.78 2.85 2.00 - 3.71 A

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

A= Acceptable - reported result falls within ratio limits of0.80-1.20 W =Acceptable with warning-reported result falls within 0. 70-0.80 or 1.20-1.30 N =Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and> 1.30 (1) False positive test (2) Sensitivity evaluation (3) See NCR 19*12 (4) See NCR 19*13 (5) See NCR 19-14 (6) See NCR 19*25 (Page 1 of 1)

(7) See NCR 19*26

ERA Environmental Radioactivity Cross Check Program Table D.3 Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value<*>

Limits Value April 2019 Rad-117 Water Ba-133 pCi/L 26.3 24.1 18.6-27.8 Cs-134 pCi/L 15.2 12.1 8.39 - 14.4 Cs-137 pCi/L 33.6 33.1 28.8 - 39.4 Co-60 pCi/L 11.9 11.5 8.67 - 15.5 Zn-65 pCi/L 87.1 89.2 80.3 - 107 GR-A pCi/L 19 19.3 9.56 - 26.5 GR-B pCi/L 20.2 29.9 19.1 - 37.7 U-Nat pCi/L 55.5 55.9 45.6 - 61.5 H-3 pCi/L 21500 21400 18700 - 23500 Sr-89 pCi/L 44.9 33.3 24.5 - 40.1 Sr-90 pCi/L 24.5 26.3 19.0-30.7 1-131 pCi/L 28.9 28.4 23.6-33.3 October 2019 Rad-119 Water Ba-133 pCi/L 42.7 43.8 35.7 - 48.8 Cs-134 pCi/L 53.5 55.9 45.2 - 61.5 Cs-137 pCi/L 77.7 78.7 70.8-89.2 Co-60 pCi/L 51.5 53.4 48.1 - 61.3 Zn-65 pCi/L 36.6 34.0 28.5 - 43.1 GR-A pCi/L 40.5 27.6 14.0 - 36.3 GR-B pCi/L 36.3 39.8 26.4-47.3 U-Nat pCi/L 27.66 28.0 22.6-31.1 H-3 pCi/L 22800 23400 20500 - 25700 Sr-89 pCi/L 47.1 45.5 35.4 - 52.7 Sr-90 pCi/L 32.5 26.5 19.2 - 30.9 1-131 pCi/L 26.0 23.9 19.8 - 28.4 December 2019 QR 1204190 Water Sr-90 pCi/L 20.1 18.6 13.2-22.1 (a) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(b) ERA evaluation:

A =Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits (1) See NCR 19-10 (2) See NCR 19-11 (3) See NCR 19-23 (4) See NCR 19-24 A

N<1>

A A

A N<2>

A A

A N<3>

A A

N<4>

A A

(Page 1 of 1)

APPENDIX E ERRATA DATA

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There is no errata data for 2019.

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Docket No:

50-254 50-265 QUAD CITIES NUCLEAR POWER STATION UNITS 1and2 Annual Radiological Groundwater Protection Program Report 1 January through 31 December 2019 Prepared By Teledyne Brown Engineering Environmental Services

, *u,+r Exelon Gene tion{,)

Quad Cities Nuclear Power Station Cordova, IL 61242 April 2020

Intentionally left blank

Table Of Contents I. Summary and Conclusions.............................................................................................. 3 II. Introduction...................................................................................................................... 5 A. Objectives of the RGPP....................................................................................... 5 B. Implementation of the Objectives........................................................................ 6 C. Program Description............................................................................................ 6 Ill. Program Description....................................................................................................... 7 A. Sample Analysis.................................................................................................. 7 B. Data Interpretation............................................................................................... 8 IV. Results and Discussion................................................................................................. 9 A. Groundwater Results........................................................................................... 9 B. Surface Water Results....................................................................................... 10 C. Summary of Results - Inter-laboratory Comparison Program.......................... 10 D. Leaks, Spills, and Releases.............................................................................. 1 O E. Trends................................................................................................................ 10 F. Investigations..................................................................................................... 1 O G. Actions Taken.................................................................................................... 11

Appendix A Tables Table A-1 Figures Figure A-1 Figure A-2 Appendix B Tables Table B-1.1 Table B-1.2 Table B-1.3 Table B-11.1 Table B-11.2 Table B-111.1 Appendices Location Designation Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2019 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2019 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2019 Data Tables Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2019 Concentrations of Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel, 2019 ii

I.

Summary and Conclusions 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 on the Radiological Groundwater Protection Program (RGPP) conducted for the Quad Cities Nuclear Power Station (QCNPS) by Exelon Nuclear covers the period 01 January 2019 through 31 December 2019.

The Quad Cities Nuclear Power Station (QCNPS) has experienced leaks from underground piping and spills from systems containing radioactive water over its 40+ year history. These incidents have created a few areas of localized contamination within the owner-controlled area. The liquid scintillation analyse$,

of groundwater in some of these areas show measurable concentrations of tritium (H-3).

On March 28, 2018, approximately three to four feet of water was observed in a Radwaste Piping Vault, located adjacent to monitoring well QC-GP-18. Samples were collected from the water in the vault as well as the groundwater in QC-GP-

18. Both samples had tritium concentration of approximately 4.5 million pCi/L.

Approximately 5,000 gallons of water was pumped from the vault and processed through the Station's Radwaste System on March 28, 2018. Remediation of the groundwater near the RW Pipe Vault began on March 29, 2018 via pumping from monitoring well QC-GP-18 and processing through the Stations Radwaste System.

On March 29, 2018, the station contacted the Illinois Environmental Protection Agency (IEPA) and Illinois Emergency Management Agency (IEMA) to report a release of a radionuclide pursuant to 35 Ill. Adm. Code 1010.202. The station also notified the Nuclear Regulatory Commission (NRC) of these report to state agencies to satisfy 1 OCFR50.72(b)(2)(xi), notification of the NRC for any event related to the health and safety of the public for which a notification to other government agencies has been or will be made (EN#53299).

The cause of release into the vault and QC-GP-18 was determined to be a leaking pipe clamp located within the RW Pipe Vault and degraded seams in the concrete vault which allowed water to seep from the vault into the surrounding groundwater. The pipe clamp was repaired and the concrete/degraded seams in the vault sealed.

On April 2, 2018, a remediation well (RW-1) was installed near the vault and QC-GP-18 to assist in remediating the tritium activity in groundwater. The remediation well began pumping groundwater on April 10, 2018 for processing through the Station's Radwaste System. On May 2, 2018 effluent from RW-1 was routed to the Discharge bay for release. On May 7, 2018 effluent from QC-GP-18 was routed to the Discharge Bay for release. On November 24, 2018, both well remediation pumps were shut down for the winter season.

Remediation of the groundwater tritium activity in vicinity of the RW Pipe Vault resumed on April 16, 2019 via pumping from remediation well QC-RW-1 with pump effluent routed to the Discharge Bay for release. Active pumping for remediation was discontinued for remainder of 2019 on November 6, 2019 due to winter weather. Between April 16, 2019 and November 6, 2019, approximately 1.1 million gallons of groundwater was pumped from the vicinity of the RW Pipe Vault for remediation purposes.

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

This report covers groundwater samples collected from the environment on station property in 2019. During that period, RGPP samples were collected from 43 locations.

2019 sample locations included 36 designated monitoring wells, 2 surface water monitoring points and 4 production wells (two of which are used for site drinking water), and 1 remediation well. Sample frequency and analysis varies with well designation. Typical frequency/analysis include quarterly for tritium and annual for gamma, gross alpha, gross beta, strontium, select transuranics and lron-55 (Fe-55)/Nickel-63 (Ni-63), depending on the designated well category. Samples from 18 of the designated monitoring wells and 2 surface water sample points were collected by a contractor (Environmental Inc.) and analyzed by a contract lab (Teledyne Brown). The remaining sample locations are collected by site personnel and analyzed for tritium/gamma onsite by station personnel or by Teledyne Brown for tritium/gamma and other parameters.

In the case of tritium, Exelon specified that its contract laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation.

Most of the tritium that was detected in groundwater at the Station is on the south and west side of the Reactor/Turbine buildings. Tritium concentrations ranged from less than the LLD of 200 pCi/L up to 60, 100 pCi/L in a monitoring well.

Tritium concentrations were less than the LLD of 200 pCi/L in surface water monitoring locations.

Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM).

Strontium-89 (Sr-89) was not detected at concentrations greater than the Lower Limit of Detection (LLD) of 10.0 pCi/L. Strontium-90 (Sr-90) was detected at one location with concentrations ranging from 4.5 - 7.1 pCi/L.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples in 2019.

Gross Alpha (dissolved) was not detected at concentrations greater than the Lower Limit of Detection (LLD). Gross Alpha (suspended) was not detected at concentrations greater than the Lower Limit of Detection (LLD).

Gross Beta (dissolved) was detected at 2 locations with concentrations ranging from 4.1 pCi/L to 13.9 pCi/L. Gross Beta (suspended) was not detected at concentrations greater than the Lower Limit of Detection (LLD).

Select Transuranic/Hard-To-Detect analyses were performed on 1 monitoring well. The analyses included Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, U-238, Fe-55 and Ni-63. U-234 was detected at one location with a concentration of 0.58 pCi/L. U-238 was detected at one location at a concentration of 0.38 pCi/L. U-234 and U-238 are commonly found in groundwater at low concentrations due to the naturally-occurring Radium (Uranium) Decay Series. All other Select Transuranic/Hard-To-Detect nuclides were not detected at concentrations greater than their respective MDCs.

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

II.

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

A.

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

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

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

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

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

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources B.

Implementation of the Objectives.

The objectives identified have been implemented at QCNPS 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 QCNPS reports describe the local hydrogeologic regime.

Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.

3.

QCNPS will continue to perform routine sampling and radiological analysis of water from selected locations.

4.

QCNPS has implemented procedures to identify and report leaks, spills, or other detections with potential radiological significance in a timely manner.

5.

QCNPS 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.

111.

Program Description This section covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2019.

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 2019.

Sample analysis and frequency is based upon well location, assessed risk, and site hydrogeology as described in the RGPP.

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

1.

Concentrations of gamma emitters in groundwater and surface water

2.

Concentrations of strontium in groundwater

3.

Concentrations of tritium in groundwater and surface water

4.

Concentration of gross alpha and gross beta in groundwater

5.

Concentrations of Am-241 in groundwater

6.

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

7.

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

8.

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

9.

Concentrations of Fe-55 in groundwater

10. Concentrations of Ni-63 in groundwater B.

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

1.

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

2.

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

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

Each result has two values calculated. Exelon reports the TPU by following the result with plus or minus +/-the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.

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

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 RGPP. Analytical results and anomalies are discussed below:

Tritium Samples from all locations were analyzed for tritium activity (Table B-1.1 &

B-111.1 Appendix B). Tritium values ranged from less than LLD of 200 pCi/L to 60, 100 pCi/L. Samples obtained near the site boundaries ranged from <200 pCi/L to 230 pCi/L. Based on Quad Cities 2017 GHD Hydrogeological Investigation Report, "there is no risk of exposure associated with groundwater ingestion off Station property", "there is no risk of exposure associated with groundwater ingestion at the Station" and "there is no current risk of exposure associated with surface water users off the Station property. The location most representative of potential offsite user of drinking water was <200 pCi/L.

Strontium Sr-89 was not detected above the Lower Limit of Detection of 10.0 pCi/L.

Sr-90 was detected at one location with concentrations ranging from 4.5 -

7.1 pCi/L. All other sample results were not above the Lower Limit of Detection (LLD) of 1.0 pCi/L. (Table B-1.1 Appendix B)

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions performed on designated groundwater locations in 2019.

Gross Alpha (dissolved) was not detected at concentrations greater than the LLD. Gross Alpha (suspended) was not detected at concentrations greater than the LLD.

Gross Beta (dissolved) was detected at.2 locations. The concentrations ranged from 4.1 pCi/L to 13.9 pCi/L. Gross Beta (suspended) was not detected at concentrations greater than the LLD. (Table B-1.1 Appendix B)

Gamma Emitters No gamma-emitting nuclides were detected above the LLD.

(Table B-1.2, Appendix B).

Select Transuranics/Hard-To-Detect Select Transuranic/Hard-To-Detect analyses were performed on 1 groundwater location. The analyses included Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, U-238, Fe-55 and Ni-63.

U-234 was detected at one location with a concentration of 0.58 pCi/L.

U-238 was detected at one location with a concentration of 0.38 pCi/L.

U-234 and U-238 are commonly found in groundwater at low concentrations due to the naturally-occurring Radium (Uranium) Decay Series. The concentrations of U-234 and U-238 discussed above are considered to be background and are not the result of station effluents. All other Select Transuranic/Hard-To-Detect nuclides were not detected at concentrations greater than their respective MDCs.

(Table B-1.3 Appendix B).

B.

Surface Water Results Tritium Samples from 2 locations were analyzed for tritium activity. Tritium concentrations were less than the LLD of 200 pCi/L. (Table B-11.1 Appendix B).

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

C.

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

D.

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

E.

Trends The March 28, 2018 Radwaste Pipe Vault release was >99% remediated as of November 6, 2019. 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 2019.

2. Actions to Recover/Reverse Plumes Remediation of the groundwater tritium activity in vicinity of the RW Pipe Vault resumed on April 16, 2019, via pumping from remediation well QC-RW-1 with pump effluent routed to the Discharge Bay for release. Active pumping for remediation was discontinued for the remainder of 2019 on November 6, 2019, due to winter weather.

Between April 16, 2019 and November 6, 2019, approximately 1.1 million gallons of groundwater was pumped from the vicinity of the RW Pipe Vault for remediation purposes. Quad Cities Station Migration Control Plan (MCP) continues to employ Monitored Natural Attenuation for remediation of legacy H-3 plumes.

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APPENDIX A LOCATION DESIGNATION

TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations Quad Cities Nuclear Power Station, 2019 Site Site Type Well Designation Minimum Sample Frequency MW-QC-1 Monitoring Well Plume Quarterly MW-QC-2 Monitoring Well Plume Quarterly MW-QC-3 Monitoring Well Plume Quarterly MW-QC-1011 Monitoring Well Idle Not Required MW-QC-101$

Monitoring Well Idle Not Required MW-QC-1020 Monitoring Well Plume Quarterly MW-QC-1021 Monitoring Well Plume Quarterly MW-QC-102S Monitoring Well Plume Quarterly MW-QC-1031 Monitoring Well Detection Quarterly MW-QC-104S Monitoring Well Detection Quarterly MW-QC-1051 Monitoring Well Plume Quarterly MW-QC-1061 Monitoring Well Plume Quarterly MW-QC-106S Monitoring Well Plume Quarterly MW-QC-1071 Monitoring Well

Background

Annual MW-QC-108D Monitoring Well Plume Quarterly MW-QC-1081 Monitoring Well Plume Quarterly MW-QC-108S Monitoring Well Plume Quarterly MW-QC-1091 Monitoring Well Plume Quarterly MW-QC-109S Monitoring Well Plume Quarterly MW-QC-1101 Monitoring Well Idle Not Required MW-QC-11101 Monitoring Well Idle Not Required MW-QC-11102 Monitoring Well Idle Not Required MW-QC-1111 Monitoring Well Idle Not Required MW-QC-1121 Monitoring Well Plume Quarterly MW-QC-1131 Monitoring Well Idle Not Required MW-QC-1141 Monitoring Well Idle Not Required MW-QC-115S Monitoring Well Idle Not Required MW-QC-116S Monitoring Well Idle Not Required SURFACE WATER #1 Surface Water Surface Water Quarterly SURFACE WATER #2 Surface Water Surface Water Quarterly WELL #1 Production Well Idle Not Required WELL#5 Production Well Idle Not Required WELL #6 LITTLE FISH Production Well Idle Not Required WELL #7 BIG FISH WELL Production Well Plume Quarterly WELL #8 FIRE TRAINING WELL Production Well Idle Not Required WELL #9 Dry Cask Storage Production Well

Background

Annual WELL #10 FISH HOUSE WELL Production Well Idle Not Required WELL #11 SPRAY CANAL WELL Production Well Idle Not Required STP SAND POINT WELL Production Well Idle Not Required QC-GP-1 Sentinel Well Plume Quarterly QC-GP-2 Sentinel Well Plume Quarterly QC-GP-3 Sentinel Well Idle Not Required QC-GP-4 Sentinel Well Plume Quarterly QC-GP-5 Sentinel Well Plume Quarterly QC-GP-6 Sentinel Well Plume Quarterly QC-GP-7 Sentinel Well Plume Quarterly QC-GP-8 Sentinel Well Idle Not Required QC-GP-9 Sentinel Well Plume Quarterly QC-GP-10 Sentinel Well Detection Quarterly QC-GP-11 Sentinel Well Detection Quarterly QC-GP-12 Sentinel Well Detection Quarterly QC-GP-13 Sentinel Well Plume Quarterly QC-GP-14 Sentinel Well Detection Quarterly QC-GP-15 Sentinel Well Elevated Quarterly QC-GP-16 Sentinel Well Detection Quarterly QC-GP-17 Sentinel Well Plume Quarterly QC-GP-18 Sentinel Well Plume Quarterly QC-RW-1 Remediation Well NA Not Required Note: Idle designated wells are not required to be sampled as part of the RGPP A-1

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APPENDIX B DATA TABLES

Intentionally left blank

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION Gr-A Gr-A Gr-8 Gr-B SITE DATE H-3 Sr-89 Sr-90 (Dis)

(Sus)

(Dis)

(Sus)

MW-QC-1 02/26/19 236 +/- 126 MW-QC-1 05/21/19

< 198 MW-QC-1 08/20/19 397 +/- 138 MW-QC-1 12/03/19 331 +/- 126 MW-QC-2 02/26/19

< 191 MW-QC-2 05/21/19

< 190 MW-QC-2 08/20/19

< 194 MW-QC-2 12/03/19

< 185 MW-QC-3 02/26/19 1060 +/- 174 MW-QC-3 02/26/19 NP 1180 +/- 186 MW-QC-3 05/21/19 579 +/- 146 MW-QC-3 05/21/19 NP 664 +/- 151 MW-QC-3 08/20/19 279 +/- 129

< 6.3

< 0.8 MW-QC-3 08/20/19 NP 193 +/- 124 MW-QC-3 12/03/19 427 +/- 133 MW-QC-3 12/03/19 MP 375 +/- 128 MW-QC-1020 02/26/19 335 +/- 129 MW-QC-1020 02/26/19 NP 1440 +/- 208 MW-QC-1020 05/21/19 763 +/- 149 MW-QC-1020 05/21/19 NP 1280 +/- 201 MW-QC-1020 08/20/19 746 +/- 159 MW-QC-1020 08/20/19 NP 814 +/- 160 MW-QC-1020 12/03/19 812 +/- 161 MW-QC-1020 12/03/19 NP 1150 +/- 185 MW-QC-1021 02/25/19 251 +/- 125 MW-QC-1021 05/21/19 258 +/- 125 MW-QC-1021 08/20/19

< 197 MW-QC-1021 12/03/19

< 191 MW-QC-102S 02/25/19

< 191 MW-QC-102S 05/21/19

< 185 MW-QC-102S 08/20/19

< 198 MW-QC-102S 12/03/19

< 192 MW-QC-1031 02/26/19

< 196

< 5.9

< 0.7

< 1.1

< 0.5 4.1 +/- 0.8

< 1.5 MW-QC-1031 05/21/19

< 186 MW-QC-1031 08/20/19

< 196 MW-QC-1031 12/03/19

< 192 MW-QC-104S 02/26/19 744 +/- 148

< 8.5

< 0.7

< 1.4

< 0.5 13.9 +/- 1.6

< 1.5 MW-QC-104S 02/26/19 NP 879 +/- 160 MW-QC-104S 05/21/19

< 175 MW-QC-104S 05/21/19 NP

< 193 MW-QC-104S 08/20/19

< 198 MW-QC-104S 08/20/19 NP

< 193 MW-QC-104S 12/03/19

< 190 MW-QC-104S 12/03/19 NP 204 +/- 121 MW-QC-1051 02/26/19 617 +/- 147 MW-QC-1051 05/21/19

< 194 MW-QC-1051 08/20/19 1040 +/- 174 MW-QC-1051 12/03/19

< 192 MW-QC-1061 02/26/19

< 191 B-1

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION Gr-A Gr-A Gr-B Gr-B SITE DATE H-3 Sr-89 Sr-90 (Dis)

(Sus)

(Dis)

(Sus)

MW-QC-1061 05/21/19

< 190 MW-QC-1061 08/20/19

< 193 MW-QC-1061 12/03/19

< 193 MW-QC-106S 02/26/19 230 +/- 127 MW-QC-106S 05/21/19

< 188 MW-QC-106S 08/20/19

< 197 MW-QC-106S 12/03/19

< 191 MW-QC-1071 02/25/19

< 185 MW-QC-108D 02/25/19 261 +/- 126 MW-QC-108D 02/25/19 NP 308 +/- 131 MW-QC-108D 05/20/19

< 196 MW-QC-108D 05/20/19 NP 261 +/- 131 MW-QC-108D 08/19/19

< 195 MW-QC-108D 08/19/19 NP

< 190 MW-QC-108D 12/02/19

< 184 MW-QC-1080 12/03/19 NP

< 186 MW-QC-1081 02/25/19

< 186 MW-QC-1081 05/20/19 413 +/- 140 MW-QC-1081 08/19/19

< 192 MW-QC-1081 12/02/19

< 183 MW-QC-108S 02/25/19 247 +/- 126 MW-QC-108S 05/20/19

< 193 MW-QC-108S 08/19/19

< 193 MW-QC-108S 12/02/19

< 183 MW-QC-1091 02/26/19

< 183 MW-QC-1091 05/20/19

< 196 MW-QC-1091 08/20/19

< 189 MW-QC-1091 12/03/19

< 182 MW-QC-109S 02/26/19

< 189 MW-QC-109S 05/20/19

< 197 MW-QC-109S 08/20/19

< 194 MW-QC-109S 12/03/19

< 181 MW-QC-1121 02/25/19

< 189 MW-QC-1121 05/20/19

< 195 MW-QC-1121 08/19/19

< 197 MW-QC-1121 12/02/19

< 181 QC-GP-1 03/12/19 634 +/- 146

< 4.5

< 0.6 QC-GP-1 05/22/19 348 +/- 137 QC-GP-1 05/22/19 NP 382 +/- 139 QC-GP-1 08/06/19 NP 200 +/- 130 QC-GP-1 08/06/19 271 +/- 131 QC-GP-1 12/04/19 NP 615 +/- 149 QC-GP-1 12/04/19 605 +/- 147 QC-GP-4 02/27/19 NP 9000 +/- 953 QC-GP-4 02/27/19 8730 +/- 925 QC-GP-4 05/22/19 6390 +/- 701 QC-GP-4 05/22/19 NP 5600 +/- 623 QC-GP-4 08/05/19 NP 10600 +/- 1120 QC-GP-4 08/05/19 11700 +/- 1230 B-2

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, 2019 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION Gr-A Gr-A Gr-B Gr-B SITE DATE H-3 Sr-89 Sr-90 (Dis)

(Sus)

(Dis)

(Sus)

QC-GP-4 12/05/19 NP 7530 +/- 816 QC-GP-4 12/05/19 8560 +/- 919 QC-GP-5 02/27/19 209 +/- 129

< 8.4 4.5 +/- 0.8 QC-GP-5 05/23/19 513 +/- 142

< 9.9 5.3 +/- 0.7 QC-GP-5 08/05/19

< 6.0 6.5 +/- 1.0 QC-GP-5 12/04/19

< 7.7 7.1 +/- 0.7 QC-GP-6 02/27/19

< 195

< 6.6

< 0.9 QC-GP-7 02/27/19 272 +/- 133

< 5.9

< 0.7 QC-GP-9 02/28/19 NP 5390 +/- 603 QC-GP-9 02/28/19 3790 +/- 440 QC-GP-9 05/23/19 1830 +/- 254 QC-GP-9 05/23/19 NP 2950 +/- 361 QC-GP-9 08/06/19 NP 4430 +/- 501 QC-GP-9 08/06/19 5140 +/- 573 QC-GP-9 12/04/19 NP 4570 +/- 522 QC-GP-9 12/04/19 4860 +/- 547 QC-GP-10 02/27/19

< 195

< 4.8

< 0.4

< 1.8

< 0.5 QC-GP-11 03/01/19 292 +/- 133

< 7.8

< 0.7

< 4.4

< 0.9 QC-GP-12 02/28/19 203 +/- 128

< 8.3

< 0.7

< 0.8

< 0.5 QC-GP-13 02/27/19 NP 6910 +/- 747 QC-GP-13 02/27/19 11200 +/- 1170 QC-GP-13 05/22/19 4230 +/- 488 QC-GP-13 05/22/19 NP 4740 +/- 538 QC-GP-13 08/05/19 NP 4670 +/- 528 QC-GP-13 08/08/19 4450 +/- 506 QC-GP-13 12/05/19 NP 3290 +/- 398 QC-GP-13 12/05/19 3190 +/- 386 QC-GP-14 02/28/19 205 +/- 130

< 7.8

< 0.7

< 1.9

< 0.5 QC-GP-15 02/27/19

< 188

< 5.7

< 0.5

< 3.5

< 0.5 QC-GP-16 02/28/19 2790 +/- 346

< 6.4

< 0.6

< 1.7

< 0.5 QC-GP-17 02/28/19 NP 799 +/- 158 QC-GP-17 02/28/19 710 +/- 154 QC-GP-17 05/22/19 211 +/- 129 QC-GP-17 05/22/19 NP 344 +/- 136 QC-GP-17 08/06/19 NP 2610 +/- 325 QC-GP-17 08/06/19 3010 +/- 363 QC-GP-17 12/04/19 NP 1440 +/- 220 QC-GP-17 12/04/19 1440 +/- 219 QC-GP-18 02/25/19 NP 24000 +/- 2450 QC-GP-18 02/25/19 20800 +/- 2130

< 3.8

< 0.2

< 2.1

< 0.5 QC-GP-18 05/22/19 762 +/- 157 QC-GP-18 05/22/19 NP 1050 +/- 184 QC-GP-18 08/06/19 NP 1280 +/- 197 QC-GP-18 08/06/19 1010 +/- 173 QC-GP-18 12/04/19 NP 10100 +/- 1070 QC-GP-18 12/04/19 10300 +/- 1100 WELL#9 DRY 05/22/19

< 197 CASK STORAGE B-3

TABLE 8-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 MW-QC-1031 02/26/19

< 42

< 105

< 5

< 13

<6

< 12

<6

< 10

< 15

< 6

< 5

< 33

< 9 MW-QC-104S 02/26/19

< 45

< 56

< 5

< 6

< 9

< 7

< 11

< 6

< 10

< 13

< 6

< 32

< 9 MW-QC-1071 02/25/19

< 42

< 97

< 6

< 5

< 11

< 5

< 12

< 6

< 10

< 15

< 5

< 6

< 32

< 10 MW-QC-3 02/26/19

< 52

< 119

<6

<4

< 14

< 8

< 11

< 6

< 12

< 13

<6

< 33

< 12 QC-GP-10 08/05/19

< 61

< 89

< 7

< 6

< 14

<6

< 14

< 8

< 11

< 15

< 6

< 7

< 30

< 12 QC-GP-11 08/06/19

< 62

< 145

< 7

< 8

< 15

< 10

< 16

< 7

< 15

< 13

< 9

< 8

< 44

< 14 QC-GP-12 08/06/19

< 58

< 151

< 8

< 18

< 7

< 10

< 7

< 12

< 14

< 5

< 37

< 12 QC-GP-14 08/06/19

< 58

< 50

< 6

< 13

< 7

< 14

< 7

< 12

< 13

< 7

< 6

< 34

< 14 QC-GP-15 08/05/19

< 45

< 70

< 6

<6

< 15

< 7

< 11

< 6

< 14

< 13

< 7

<6

< 34

< 12 QC-GP-16 08/06/19

< 55

< 108

< 8

< 7

< 12

< 8

< 15

< 6

< 12

< 14

< 9

< 7

< 36

< 8 QC-GP-18 06/17/19

< 64

< 72

< 7

< 8

< 17

< 8

< 20

< 8

< 14

< 11

< 8

< 38

< 13 OJ QC-GP-18 08/06/19

< 61

< 65

< 7

< 6

< 13

< 8

< 13

< 7

< 12

< 13

< 8

<6

< 27

< 12 I

~

WELL#9 DRY 05/22/19

< 26

< 3

< 6

< 3

< 6

< 3

< 5

< 14

< 3

< 23

< 8 CASK STORAGE

TABLE B-1.3 CONCENTRATIONS OF HARD-TO-DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 Fe-55 Ni-63 MW-QC-3 08/20/19

< 31

< 4.4 MW-QC-1031 08/20/19

< 52

< 4.4 QC-GP-1 03/12/19

< 100

< 3.8 QC-GP-5 02/27/19

< 86

< 4.2 QC-GP-6 02/27/19

< 66

< 4.3 QC-GP-7 02/27/19

< 31

< 4.6 QC-GP-15 02/27/19

< 162

< 4.3 QC-GP-18 02/25/19

< 0.02

< 0.04

< 0.02

< 0.16

< 0.06 0.58 +/- 0.18

< 0.02 0.38 +/- 0.14

< 182

< 4.3 CD I

01

TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER + 2 SIGMA COLLECTION SITE DATE H-3 QC-SW-1 02/26/19 (1)

QC-SW-1 05/20/19

< 196 QC-SW-1 08/19/19

< 190 QC-SW-1 12/02/19

< 183 QC-SW-2 02/26/19 (1)

QC-SW-2 05/20/19

< 192 QC-SW-2 08/19/19

< 193 QC-SW-2 12/02/19

< 183 (1) No Sample - Canal Frozen B-6

TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2019 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 QC-SW-1 05/20/19

< 45

< 82

< 5

< 6

< 14

< 5

< 12

< 5

< 9

< 14

< 6

< 5

< 30

< 15 QC-SW-2 05/20/19

< 56

< 61

< 6

< 13

< 5

< 11

< 8

< 9

< 13

< 6

<6

< 33

< 12 CJ I

TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2019 RESULTS IN UNITS OF PCl/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-1 03/12/19

<2,000 Sentinel Well QC-GP-1 05/22/19

<2,000 Sentinel Well QC-GP-1 08/06/19

<2,000 Sentinel Well QC-GP-1 11/05/19

<2,000 Sentinel Well QC-GP-1 12/04/19

<2,000 Sentinel Well QC-GP-2 02/27/19

<2,000 Sentinel Well QC-GP-2 05/22/19

<2,000 Sentinel Well QC-GP-2 08/05/19

<2,000 Sentinel Well QC-GP-2 12/04/19

<2,000 Sentinel Well QC-GP-3 05/22/19

<2,000 Sentinel Well QC-GP-4 02/27/19 9,460 Sentinel Well QC-GP-4 05/22/19 5,120 Sentinel Well QC-GP-4 08/05/19 11,700 Sentinel Well QC-GP-4 12/05/19 8,640 Sentinel Well QC-GP-5 02/27/19

<2,000 Sentinel Well QC-GP-5 05/23/19

<2,000 Sentinel Well QC-GP-5 08/05/19

<2,000 Sentinel Well QC-GP-5 12/04/19

<2,000 Sentinel Well QC-GP-6 02/27/19

<2,000 Sentinel Well QC-GP-6 05/23/19

<2,000 Sentinel Well QC-GP-6 08/05/19

<2,000 Sentinel Well QC-GP-6 12/04/19

<2,000 Sentinel Well QC-GP-7 02/27/19

<2,000 Sentinel Well QC-GP-7 05/22/19

<2,000 Sentinel Well QC-GP-7 08/05/19

<2,000 Sentinel Well QC-GP-7 12/04/19

<2,000 Sentinel Well QC-GP-8 05/22/19

<2,000 Sentinel Well QC-GP-9 02/28/19 3,930 Sentinel Well QC-GP-9 05/23/19

<2,000 Sentinel Well QC-GP-9 08/06/19 5,290 Sentinel Well QC-GP-9 12/04/19 4,390 Sentinel Well QC-GP-10 02/27/19

<2,000 Sentinel Well QC-GP-10 05/23/19

<2,000 Sentinel Well QC-GP-10 08/05/19

<2,000 Sentinel Well QC-GP-10 12/04/19

<2,000 Sentinel Well QC-GP-11 03/01/19

<2,000 Sentinel Well QC-GP-11 05/23/19

<2,000 Sentinel Well QC-GP-11 08/06/19

<2,000 Sentinel Well QC-GP-11 12/04/19

<2,000 Sentinel Well QC-GP-12 02/28119

<2,000 Sentinel Well QC-GP-12 05/22/19

<2,000 Sentinel Well QC-GP-12 08/06/19

<2,000 Sentinel Well QC-GP-12 12/05/19

<2,000 Sentinel Well QC-GP-13 02/27/19 9,930 Sentinel Well QC-GP-13 05/22/19 4,000 Sentinel Well QC-GP-13 08/08/19 4,490 Sentinel Well QC-GP-13 12/05/19 3,630 Sentinel Well QC-GP-14 02/28/19

<2,000 Sentinel Well QC-GP-14 05/23/19

<2.000 Sentinel Well QC-GP-14 08/06/19

<2,000 Sentinel Well QC-GP-14 12/04/19

<2,000 Sentinel Well B-8

TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2019 RESULTS IN UNITS OF PCl/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-15 02/27/19

<2,000 Sentinel Well QC-GP-15 05/23/19

<2,000 Sentinel Well QC-GP-15 08/05/19

<2,000 Sentinel Well QC-GP-15 12/04/19

<2,000 Sentinel Well QC-GP-16 02/28/19 2,540 Sentinel Well QC-GP-16 05/22/19

<2,000 Sentinel Well QC-GP-16 08/06/19 2,480 Sentinel Well QC-GP-16 12/04/19

<2,000 Sentinel Well QC-GP-17 02/28/19

<2,000 Sentinel Well QC-GP-17 05/22/19

<2,000 Sentinel Well QC-GP-17 08/06/19 3,600 Sentinel Well QC-GP-17 12/04/19

<2,000 Sentinel Well QC-GP-18 01/07/19 33,200 Sentinel Well QC-GP-18 02/25/19 18,500 Sentinel Well QC-GP-18 03/12/19 17,300 Sentinel Well QC-GP-18 04/08/19 14,600 Sentinel Well QC-GP-18 04/16/19 5,080 Sentinel Well QC-GP-18 04/22/19 5,040 Sentinel Well QC-GP-18 04/29/19

<2,000 Sentinel Well QC-GP-18 05/06/19

<2,000 Sentinel Well QC-GP-18 05/13/19

<2,000 sentinel Well QC-GP-18 05/20/19

<2,000 Sentinel Well QC-GP-18 05/28/19

<2,000 Sentinel Well QC-GP-18 06/03/19

<2,000 Sentinel Well QC-GP-18 06/10/19

<2,000 Sentinel Well QC-GP-18 06/17/19

<2,000 Sentinel Well QC-GP-18 07/01/19

<2,000 Sentinel Well QC-GP-18 07/15/19

<2,000 Sentinel Well QC-GP-18 07/29/19

<2,000 Sentinel Well QC-GP-18 08/06/19

<2,000 Sentinel Well QC-GP-18 08/12/19

<2,000 Sentinel Well QC-GP-18 08/26/19 2,320 Sentinel Well QC-GP-18 09/09/19

<2,000 Sentinel Well QC-GP-18 09/23/19

<2,000 Sentinel Well QC-GP-18 10/07/19

<2,000 Sentinel Well QC-GP-18 10/21/19 5,560 Sentinel Well QC-GP-18 11/04/19 9,640 Sentinel Well QC-GP-18 12/04/19 10,600 Sentinel Well MW-QC-3 08/06/19

<2,000 Monitoring Well MW-QC-3 11/05/19

<2,000 Monitoring Well MW-QC-1031 08/06/19

<2,000 Monitoring Well MW-QC-1031 11/05/19

<2,000 Monitoring Well QC-RW-1 01/07/19 52,800 Remediation Well QC-RW-1 02/25/19 27,800 Remediation Well QC-RW-1 03/12/19 42,500 Remediation Well QC-RW-1 04/08/19 43,500 Remediation Well QC-RW-1 04/16/19 42,700 Remediation Well QC-RW-1 04/22/19 60,100 Remediation Well QC-RW-1 04/29/19 42,900 Remediation Well QC-RW-1 05/06/19 45,200 Remediation Well QC-RW-1 05/13/19 50,700 Remediation Well B-9

TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2019 RESULTS IN UNITS OF PCl/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-RW-1 05/20/19 56,900 Remediation Well QC-RW-1 05/28/19 54,700 Remediation Well QC-RW-1 06/03/19 47,300 Remediation Well QC-RW-1 06/10/19 50,300 Remediation Well QC-RW-1 06/17/19 55,600 Remediation Well QC-RW-1 07/01/19 52,300 Remediation Well QC-RW-1 07/15/19 43,500 Remediation Well QC-RW-1 07/29/19 42,600 Remediation Well QC-RW-1 08/06/19 42,400 Remediation Well QC-RW-1 08/12/19 47,400 Remediation Well QC-RW-1 08/26/19 48,200 Remediation Well QC-RW-1 09/09/19 41,700 Remediation Well QC-RW-1 09/23/19 32,700 Remediation Well QC-RW-1 10/07/19 32,000 Remediation Well QC-RW-1 10/21/19 35,700 Remediation Well QC-RW-1 11/04/19 40,500 Remediation Well QC-RW-1 12/04/19 31,300 Remediation Well Well#1 05/14/19

<200 Production Well Well#1 10/17/19

<200 Production Well Well#5 05/14/19

<200 Production Well Well#5 10/17/19

<200 Production Well Well#?

02/28/19

<2,000 Production Well Well#?

05/20/19

<2,000 Production Well Well#?

08/19/19

<2,000 Production Well Well#?

12/02/19

<2,000 Production Well B-10

SVP-20-035, Annual Radiological Environmental Operating Report

Contents

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Enclosure:

SUMMARY

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SVP-20-035, Annual Radiological Environmental Operating Report

Text

Subject:

Enclosure:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Background

Background

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