ML20121A029

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Annual Radiological Environmental Operating Report - Part 1 of 4
ML20121A029
Person / Time
Site: Byron  Constellation icon.png
Issue date: 04/30/2020
From:
Teledyne Brown Engineering Environmental Services
To:
Exelon Generation Co, Office of Nuclear Reactor Regulation
Shared Package
ML20121A027 List:
References
BYRON 2020-0031
Download: ML20121A029 (56)
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-NRC.Docket No : 50-454 50-455 BYRON NUCLEAR GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2019 Prepared By Teledyne Brown Engineering Environmental Services t.llllw ExelonGeneration.

Byron Nuclear Generating Station Byron, IL 61010 April 2020

Intentionally left blank Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ...................................................................................................................... 2 A. Objectives of the REMP ....................................................................................... 2 B. Implementation of the Objectives ........................................................................ 2 Ill. Program Description ....................................................................................................... 3 A. Sample Collection ................................................................................................ 3 B. Sample Analysis .................................................................................................. 5 C. Data Interpretation ............................................................................................... 6 D. Program Exceptions ............................................................................................ 7 E. Program Changes ............................................................................................... 8 IV. Results and Discussion ................................................................................................. 9 A. Aquatic Environment ........................................................................................... 9

1. Surface Water ........................................................................................... 9
2. Ground Water ........................................................................................... 9
3. Fish ......................................................................................................... 10
4. Sediment ................................................................................................. 10 B. Atmospheric Environment ................................................................................. 11
1. Airborne .................................................................................................. 11
a. Air Particulates ............................................................................. 11
b. Airborne Iodine ............................................................................. 12
2. Terrestrial ................................................................................................ 12
a. Milk ............................................................................................... 12
b. Vegetation .................................................................................... 12 C. Ambient Gamma Radiation ............................................................................... 12 D. Land Use Survey ............................................................................................... 13 E. Errata Data ........................................................................................................ 13 F. Summary of Results- Inter-laboratory Comparison Program ........................... 13

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Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for Byron Nuclear Generating Station, 2019 Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Tables Table B-1 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Byron Nuclear Generating Station, 2019 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Byron Nuclear Generating Station, 2019 Figures Figure B-1 Inner Ring and Special Interest OSLO Locations of the Byron Nuclear Generating Station, 2019 Figure B-2 Outer Ring OSLO Locations of the Byron Nuclear Generating Station, 2019 Figure B-3 Onsite Air Sampling Locations of the Byron Nuclear Generating Station, 2019 Figure B-4 Offsite Air Sampling Locations of the Byron Nuclear Generating Station, 2019 Figure B-5 Ingestion and Waterborne Exposure Pathway Sampling Locations of the Byron Nuclear Generating Station, 2019 Appendix C Data Tables and Figures Tables Table C-1.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019.

Table C-1.2 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019.

Table C-1.3 Concentrations of Nickel-63 in Surface Water Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-1.4 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 ii

Table C-11.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-11.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-111.1 Concentrations of Nickel-63 and Gamma Emitters in Fish Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-IV .1 Concentrations of Nickel-63 and Gamma Emitters in Sediment Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-Vl.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-Vll.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-Vll.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-Vlll.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table C-IX.1 Quarterly OSLO Results for Byron Nuclear Generating Station, 2019 Table C-IX.2 Mean Quarterly OSLO Results for the Inner Ring, Outer Ring, Special Interest, Other and Control Locations for Byron Nuclear Generating Station, 2019 Table C-IX.3 Summary of the Ambient Dosimetry Program for Byron Nuclear Generating Station, 2019 Figures Figure C-1 Surface Water - Gross Beta - Stations BY-12 and BY-29 (C) Collected in the Vicinity of BNGS, 2000 - 2019 Figure C-2 Surface Water- Tritium - Stations BY-12 and BY-29 (C) Collected in the Vicinity of BNGS, 2000 - 2019 Figure C-3 Ground Water - Tritium - Station BY-14-1 Collected in the Vicinity of BNGS, 2000-2019 iii

Figure C-4 Ground Water - Tritium - Station BY-18-1 Collected in the Vicinity of BNGS, 2010 - 2019 Figure C-5 Ground Water - Tritium - Station BY-32 Collected in the Vicinity of BNGS, 2006 - 2019 Figure C-6 Ground Water - Tritium - Stations BY-35 Collected in the Vicinity of BNGS, 2006-2019 Figure C-7 Ground Water - Tritium - Stations BY-37 and BY-38 Collected in the Vicinity of BNGS, 2006 - 2019 Figure C-8 Air Particulate - Gross Beta - Stations BY-08 (C) and BY-21 Collected in the Vicinity of BNGS, 2000 - 2019 Figure C-9 Air Particulate - Gross Beta - Stations BY-22 and BY-23 Collected in the Vicinity of BNGS, 2000 - 2019 Figure C-10 Air Particulate - Gross Beta - Station BY-24 Collected in the Vicinity of BNGS, 2000 - 2019 Figure C-11 Air Particulate - Gross Beta - Stations BY-01 and BY-04 Collected in the Vicinity of BNGS, 2005 - 2019 Figure C-12 Air Particulate - Gross Beta - Station BY-06 Collected in the Vicinity of BNGS, 2005 - 2019 Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2019 Table D-2 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2019 Table D-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2019 Appendix E Effluent Report Appendix E-1 Data Tables and Figures Appendix F Meteorological Data Appendix G Errata data Appendix H Annual Radiological Groundwater Protection Program Report (ARGPPR) iv

I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Byron Nuclear Generating Station by Exelon covers the period 1 January 2019 through 31 December 2019. During that time period, 1,427 analyses were performed on 1,267 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of BNGS had no adverse radiological impact on the environment.

Surface water samples were analyzed for concentrations of gross beta, tritium, Nickel-63 (Ni-63), and gamma-emitting nuclides. Ground water samples were analyzed for concentrations of tritium and gamma-emitting nuclides. Gross beta activities detected were consistent with those detected in previous years. All surface water samples analyzed for Ni-63 were less than the minimum detectable concentration. Tritium detected in downstream surface water was well below reportable limits and consistent with expected levels as a result of permitted liquid discharges.

Fish (commercially and/or recreationally important species) and sediment samples were analyzed for concentrations of Ni-63 and gamma-emitting nuclides. Cesium-137 (Cs-137) was detected in 4 of 4 sediment samples with concentrations ranging from 139 - 242 pCi/kg. No other fission or activation products were detected.

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 weekly air samples. All results were less than the minimum detectable concentration for 1-131.

Cow milk samples were analyzed for concentrations of 1-131 and gamma- emitting nuclides. All 1-131 results were below the minimum detectable activity. No fission or activation products were found.

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 Dosimetry were deployed and Thermoluminescent Dosimetry (TLD) were discontinued. This change may have resulted in a step change in readings, up or down, depending on site characteristics. The relative comparison to control locations remains valid.

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

II. Introduction Byron Station, a two-unit PWR station, is located about two miles east of the Rock River and approximately three miles southwest of Byron in Ogle County, Illinois.

The reactors are designed to have capacities of 1,268 and 1,241 MW gross, respectively. Unit One loaded fuel in November 1984 and went on line February 2, 1985. Unit Two went on line January 9, 1987. The station has been designed to keep releases to the environment at levels below those specified in the codes of federal regulations.

This report covers those analyses performed by Teledyne Brown Engineering (TSE) 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.
8. 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 Ill. Program Description A. Sample Collection Samples for the 8NGS REMP were collected for Exelon Nuclear by Environmental Inc. (Midwest Labs). This section describes the general collection methods used by Environmental Inc. to obtain environmental samples for the 8NGS REMP in 2019. Sample locations and descriptions can be found in Table B-1 and Figures 8-1 through 8-5, Appendix 8.

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

Two gallon water samples were collected weekly from two surface water locations (8Y-12 and 8Y-29 [Control location]) and quarterly from six ground water locations (BY-14-1, 8Y-18-1, 8Y-32, 8Y-35, BY-37 and BY-38). All samples were collected in new unused plastic bottles, which were rinsed with source water prior to collection. Fish samples comprising the flesh of silver redhorse, shorthead redhorse, freshwater drum, common carp and channel catfish were collected semiannually at two locations, 8Y-29 (control) and 8Y-31. Sediment samples composed of recently deposited substrate were collected at two locations semiannually, BY-12 and BY-34 (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 weekly at eight locations (BY-01, BY-04, BY-06, BY-08, BY-21, BY-22, BY-23 and BY-24).

The control location was BY-08. Airborne iodine and air particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps ran continuously and sampled air at the rate of approximately one cubic foot per minute. The air 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 products. Milk samples were collected monthly from January through April and November through December, and biweekly May through October. The control location was BY-26-2 and the indicator location was BY-20-1. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite and shipped promptly to the laboratory.

Food products were collected annually in August at five locations (BY-Control, BY-Quad 1, BY-Quad 2, BY-Quad 3 and BY-Quad 4). Various types of samples were collected and placed in new unused 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 Dosimetry (OSLO) were deployed and Thermoluminescent Dosimetry (TLD) were discontinued. This change may result in a step change in readings, up or down, depending on site characteristics. The relative comparison to control locations remains valid.

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

In recent years, the industry recognized the need for a standard method of reporting environmental dosimetry results. In 2019, Exelon began assessing facility-related dose in accordance with ANSI N13.37-2014, Environmental Dosimetry- Criteria for System Design and Implementation.

This standard is applicable to passive environmental dosimetry systems used to monitor areas surrounding radiological facilities to assess potential facility-related radiation doses and to verify compliance with public dose limits. Such environmental dosimetry systems include dosimeters which accumulate radiation dose and any readout device required to process the dosimeters. Passive dosimeters include optically stimulated luminescence (OSL) dosimeters which are deployed at field locations around a facility and exchanged periodically (e.g., quarterly). Facility-related dose is calculated using a statistical model that uses baseline historical data and accounts for transit and deploy dose. In 2019, none of the Byron Station field locations listed in this report exhibited facility-related dose as calculated in accordance with this standard.

Each location consisted of 2 OSLO sets. The OSLDs were exchanged quarterly and sent to Landauer for analysis. The OSLDs were placed at locations on and around the BNGS Station site as follows:

An inner ring consisting of 16 locations (BY-101, BY-102, BY-103, BY-104, BY-105, BY-106, BY-107, BY-108, BY-109, BY-110, BY-111, BY-112, BY-113, BY-114, BY-115 and BY-116) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from BNGS releases.

An outer ring consisting of 16 locations (BY-201, BY-202, BY-203, BY-204, BY-205, BY-206, BY-207, BY-208, BY-209, BY-210, BY-211, BY-212, BY-213, BY-214, BY-215 and BY-216) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.

A special interest set consisting of seven locations (BY-301-1, BY-301-2, BY-309-1, BY-309-2, BY-309-3, BY-309-4, and BY-314-2) to measure possible exposures from on-site storage facilities.

An other set consisting of seven locations (BY-01, BY-04, BY-06, BY-21, BY-22, BY-23 and BY-24) at locations where air samplers are present.

The balance of one location (BY-08) representing the control area.

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 1/2 degree sectors around the site, where estimated annual dose from BNGS, if any, would be most significant;
3. On hills free from local obstructions and within sight of the vents (where practical);
4. And near the closest dwelling to the vents in the prevailing downwind direction if applicable.

Two OSLDs were placed at each location above ground level. 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 BNGS REMP in 2019. The analytical procedures used by the laboratory are listed in Table B-2.

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

1. Concentrations of beta emitters in surface water and air particulates
2. Concentrations of gamma emitters in ground and surface water, air particulates, milk, fish, sediment and vegetation
3. Concentrations of tritium in ground and surface water
4. Concentrations of lodine-131 in air and milk
5. Concentrations of Nickel-63 in surface water, fish and sediment
6. Ambient gamma radiation levels at various site environs C. Data Interpretation The radiological and direct radiation data collected prior to Byron Nuclear Generating Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Byron Nuclear Generating 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) was 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 was intended as a before-the- fact estimate of a system (including instrumentation, procedure and sample type) and not as an after-the-fact criteria for the presence of activity. All analyses were designed to achieve the required BNGS detection capabilities for environmental sample analysis.

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

2. Net Activity Calculation and Reporting of Results Net activity for a sample was 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 was 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, ground water, milk and vegetation, twelve nuclides, 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.

For fish, sediment, and air particulates, eleven nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were 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 BNGS REMP had a sample recovery rate in excess of 99%.

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

TABLE 0-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection Type Code Date Reason AP BY-01 01/29/19 Small part of filter damaged during handing Rotameter arrived broken and could not be calibrated on AP/Al ALL 01/31/19 due date; Spare #2 calibrated on 02/07/19 and sent as replacement AP/Al BY-24 04/23/19 Run time meter would not reset - replaced OSLO BY-105-2 04/01/19 Dosimeter missing during exchange BY-12 Could not obtain sediment during May due to high river SEO 05/31/19 BY-24 levels - sample obtained on 06/18/19 Low timer reading due to power outage from raccoon AP/Al BY-23 06/11/19 contact AP/Al ALL 06/11/19 Possible low timer readings due to storms TLD missing during monthly checks - replaced with spare OSLO BY-103-3 09/03/19 1 EX00059280W - replaced on 09/04/19 No power to air sampler due to tripped breaker; restored AP/Al BY-08 09/17/19 power on 09/1 /19 Pump field checks delayed one week for new collector's AP/Al ALL 09/24/19 training; field checks performed on 10/0/19 Air sampler flow rate 66 cfh; unable to adjust, pump AP/Al BY-23 10/15/19 replaced on 10/17/19 with #184 AP/Al BY-23 10/22/19 Air sampler flow rate 70 cfh; pump adjusted to 60cfh TABLE D-2 LISTING OF MISSED SAMPLES Sample Location Collection Type Code Date Reason SW BY-29 01/02/19 Sample unobtainable due to ice on river BY-12 SW 01/22/19 Sample unobtainable due to ice on river BY-29 BY-12 SW 01/29/19 Sample unobtainable due to ice on river BY-29 SW BY-29 02/05/19 Sample unobtainable due to ice on river BY-12 SW 02/11/19 Sample unobtainable due to ice on river BY-29 BY-12 SW 02/19/19 Sample unobtainable due to ice on river BY-29 Air sampler found damaged - no sample obtained; AP/Al BY-21 02/19/19 replaced on 02/20/19 BY-12 SW 02/26/19 Sample unobtainable due to ice on river BY-29 BY-12 SW 03/05/19 Sample unobtainable due to ice on river BY-29 No power to the air sampler due to raccoon contact; no AP/Al BY-23 06/04/19 sample taken; no pp field check performed; repaired on 06/15/19 Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. Occasional equipment breakdowns and power outages were unavoidable.

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 (BY-12 and BY-29). Of these locations only BY-12 located downstream, could be affected by Byron Nuclear Generating Station's effluent releases. The following analyses were performed:

Gross Beta Samples from both locations were analyzed for concentrations of gross beta (Table C-1.1, Appendix C). The values ranged from 2.8 to 6.4 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C).

Tritium Quarterly composites of weekly collections were analyzed for tritium activity (Table C-1.2, Appendix C). Tritium was detected in one sample at a concentration of 828 pCi/L (Figure C-2, Appendix C). Tritium detected in downstream surface water was well below reportable limits and consistent with expected levels as a result of permitted liquid discharges.

Nickel Samples from both locations were analyzed for concentration of Ni-63 (Table C-1.3, Appendix C). All results were less than the minimum detectable concentration.

Gamma Spectrometry Samples from both locations were analyzed for gamma-emitting nuclides (Table C-1.4, Appendix C). No nuclides were detected, and all required LLDs were met.

2. Ground Water Quarterly grab samples were collected at six locations (BY-14-1, BY-18-1, BY-32, BY-35, BY-37 and BY-38). These locations could be affected by Byron Nuclear Generating Station's 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 was detected, and the required LLD was met (Figures C-3 through C-7, Appendix C).

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

3. Fish Fish samples comprised of silver red horse, shorthead redhorse, freshwater drum, common carp and channel catfish were collected at two locations (BY-29 and BY-31) semiannually. Location BY-31 could be affected by Byron Nuclear Generating Station's effluent releases.

The following analyses were performed:

Nickel The edible portion of fish samples from both locations was analyzed for Ni-63 (Table C-111.1, Appendix C). Nickel-63 was not detected and the required LLD was met.

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

4. Sediment Aquatic sediment samples were collected at two locations (BY-12 and BY-34) semiannually. BY-12, located downstream, could be affected by Byron Nuclear Generating Station's effluent releases. The following analyses were performed:

Nickel Sediment samples from both locations were analyzed for Ni-63 (Table C-IV.1, Appendix C). Ni-63 was not detected and the required LLD was met.

Gamma Spectrometry Sediment samples from both locations were analyzed for gamma-emitting nuclides (Table C-IV.1, Appendix C). Cesium-137 was detected in all samples. The concentrations ranged from 139 - 242 pCi/kg. No other nuclides were detected, and all required LLDs were met.

B. Atmospheric Environment

1. Airborne
a. Air Particulates Continuous air particulate samples were collected from eight locations on a weekly basis. The eight locations were separated into three groups: Nearsite samplers within 4 km of the site (BY-21, BY-22, BY-23 and BY-24), Far Field samplers between 4 and 10 km of the site (BY-01, BY-04 and BY-06) and the Control sampler between 10 and 30 km from the site (BY-08). The following analyses were performed:

Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-V.1 and C-V.2, Appendix C). Detectable gross beta activity was observed at all locations. Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of BNGS.

The results from the Nearsite locations (Group I) ranged from 4 to 32E-3 pCi/m 3 with a mean of 1SE-3 pCi/m 3 . The results from the Far Field locations (Group II) ranged from 5 to 33E-3 pCi/m 3 with a mean of 1SE-3 pCi/m 3. The results from the Control location (Group Ill) ranged from 6 to 33E-3 pCi/m 3 with a mean of 1SE-3 pCi/m 3

  • Comparison of the 2019 air particulate data with previous year's data indicate no effects from the operation of BNGS. In addition, a comparison of the weekly mean values for 2019 indicate no notable differences among the three groups (Figures C-8 through C-12, Appendix C).

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

b. Airborne Iodine Continuous air samples were collected from eight locations (BY-01, BY-04, BY-06, BY-08, BY-21, BY-22, BY-23 and BY-24) and analyzed weekly for 1-131 (Table C-Vl.1, Appendix C). All results were less than the minimum detectable concentration for 1-131.
2. Terrestrial
a. Milk Samples were collected from two locations (BY-20-1 and BY-26-2) monthly from January to April and November through December, and biweekly May through October. The following analyses were performed:

lodine-131 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-Vll.1, Appendix C). No nuclides were detected, and all required LLDs were met.

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

b. Vegetation Vegetation samples were collected at five locations (BY-Control, BY-Quad 1, BY-Quad 2, BY-Quad 3 and BY-Quad 4). Four locations (BY-Quad 1, BY-Quad 2, BY-Quad 3 and BY-Quad 4) could be affected by Byron Nuclear Generating Station's 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 were detected, and all required LLDs were met.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing OSLDs.

Ninety-one OSLO locations were established around the site. Results of OSLO measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C.

All OSLO measurements were below 26 mR/standard quarter, with a range of 12 to 25 mR/standard quarter. A comparison of the Inner Ring, Outer Ring, Special Interest, Other and Control Location data indicate that the ambient gamma radiation levels were comparable among the groups.

D. Land Use Survey A Land Use Survey conducted during August, 2019 around the Byron Nuclear Generating Station (BNGS) was performed by Environmental Inc.

(Midwest Labs) for Exelon Nuclear to comply with the Byron Nuclear Generating Station's Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident, livestock, and milk producing animals in each of the sixteen 22 % degree sectors. The results of this survey are summarized below:

Distance in Miles from the BNGS Vent Stacks Residence Livestock Milk Farm Sector Miles Miles Miles A N 1.2 5.9 B NNE 1.6 6.2 C NE 1.1 2.0 D ENE 1.4 3.7 E E 1.0 4.2 F ESE 1.5 1.5 G SE 1.7 3.5 H SSE 0.7 3.3 J s 0.6 0.7 K SSW 0.7 0.7 L SW 0.8 2.0 M wsw<aJ 1.6 0.8 4.5 N w 1.8 3.2 p WNW 1.6 1.6 11.5 Q NW 0.8 1.5 R NNW 0.9 1.4 (a)

Denotes the nearest industrial facility located at 1.5 miles E. Errata Data The 2018 AREOR contained a typographical error in Table D-2 Listing of Missed Samples. (See Appendix G)

F. Summary of Results - Inter-Laboratory Comparison Program The TBE Laboratory analyzed Performance Evaluation (PE) samples of air particulate, air iodine (charcoal), milk, soil, vegetation and water (including fish) matrices (Appendix D). The PE sample matrices were chosen based on the types of samples submitted to the primary laboratory for analysis.

The selected parameters for the PE samples are based on the appropriate matrices, methodologies and geometries, which include geometries that are comparable. The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Program (MAPEP) were evaluated against the following pre-set acceptance criteria:

1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of laboratory results and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.
2. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.
3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values. 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 1st "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. TB E'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 pCilL (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 Sq/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. TBE'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 <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> (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 BYRON NUCLEAR GENERATING STATION, 2019 NAME OF FACILITY: BYRON NUCLEAR GENERATING STATION DOCKET NUMBER: 50-454 & 50-455 LOCATION OF FACILITY: BYRON,IL REPORTING PERIOD: 2019 INDICATOR CONTROL REQUIRED LOCATIONS LOCATION LOCATION WITH HIGHEST ANNUAL MEAN (M) NUMBER OF MEDIUM OR TYPES OF NUMBER OF LOWER LIMIT MEAN(M) MEAN(M) MEAN(M) STATION# NONROUTINE PATHWAY SAMPLED ANALYSIS ANALYSES OF DETECTION (F) (F) (F) NAME REPORTED (Uint of Measurement) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS SURFACE WATER GR-B 23 4 4.4 4.3 4.4 BY-12 INDICATOR 0 (PCIA.ITER) (9/12) (9/11) (9/12) OREGON POOL OF ROCK RIVER* DOWNSTREAM 2.8

  • 6.4 2.9- 5.8 2.8
  • 6.4 4.5 MILES SSW OF SITE H*3 8 200 828 <LLD 828 BY-12 INDICATOR 0 (1/4) (1/4) OREGON POOL OF ROCK RIVER - DOWNSTREAM 4.5 MILES SSW OF SITE Nl-63 23 30 <LLD <LLD 0 GAMMA 23 MN-54 15 <LLD <LLD 0 C0-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 C0-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0

)> NB-95 15 <LLD <LLD 0 I

ZR-95 30 <LLD <LLD 0

/-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 24 200 <LLD NA 0 (PCIA.ITER)

GAMMA 24 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 FISH Nl-63 8 260 <LLD <LLD 0 (PCIA.ITER)

(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 BYRON NUCLEAR GENERATING STATION, 2019 NAME OF FACILITY: BYRON NUCLEAR GENERATING STATION DOCKET NUMBER: 50-454 & 50-455 LOCATION OF FACILITY: BYRON,IL REPORTING PERIOD: 2019 INDICATOR CONTROL REQUIRED LOCATIONS LOCATION LOCATION WITH HIGHEST ANNUAL MEAN (M) NUMBER OF MEDIUM OR TYPES OF NUMBER OF LOWER LIMIT MEAN(M) MEAN(M) MEAN(M) STATION# NONROUTINE PATHWAY SAMPLED ANALYSIS ANALYSES OF DETECTION (F) (F) (F) NAME REPORTED (Uint of Measurement) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS FISH GAMMA 8 (PC/IKG 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 LA-140 NA <LLD <LLD 0 SEDIMENT Nl-63 4 260 <LLD <LLD 0 (PCIIKG DRY)

GAMMA 4

)> MN-54 NA <LLD <LLD 0

~

I 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-137 180 154 217 217 BY-34 CONTROL 0 (2/2) (2/2) (2/2) ROCK RIVER UPSTREAM OF DISCHARGE 139 - 170 192- 242 192-242 2.6 MILES WNW OF SITE BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 AIR PARTICULATE GR-B 414 10 15 15 16 BY-21 INDICATOR 0 (E-3 PC/ICU.METER) (361/362) (52/52) (51/51) BYRON NEARSITE NORTH 4-33 6-33 5-32 0.3 MILES N OF SITE GAMMA 32 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 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 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 BYRON NUCLEAR GENERATING STATION, 2019 NAME OF FACILITY: BYRON NUCLEAR GENERATING STATION DOCKET NUMBER: 50-454 & 50-455 LOCATION OF FACILITY: BYRON, IL REPORTING PERIOD: 2019 INDICATOR CONTROL REQUIRED LOCATIONS LOCATION LOCATION WITH HIGHEST ANNUAL MEAN (M) NUMBER OF MEDIUM OR TYPES OF NUMBER OF LOWER LIMIT MEAN(M) MEAN(M) MEAN(M) STATION# NONROUTINE PATHWAY SAMPLED ANALYSIS ANALYSES OF DETECTION (F) (F) (F) NAME REPORTED (Uint of Measurement) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS AIR IODINE GAMMA 414 (E-3 PC/ICU.METER) 1-131 (GELi} 70 <LLD <LLD 0 MILK 1-131 (LOW LVL) 38 1 <LLD <LLD 0 (PCIA.ITER}

GAMMA MN-54 38 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 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0

)> BA-140 60 <LLD <LLD 0 I

c.,

LA-140 15 <LLD <LLD 0 VEGETATION GAMMA 10 (PCIIKG WE7) 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 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD DIRECT RADIATION OSLD-QUARTERLY 332 NA 20 17 23 BY-212-1 INDICATOR 0 (MILLIREMIQTR.} (328/328) (4/4) (4/4) 12-25 13 -18 20-24 4.7 MILES WSW (M) The Mean Values are calculated using the positive values. (F) Fraction of detectable measurement are indicated in parentheses.

Intentionally left blank 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, Byron Nuclear Generating Station, 2019 Location Location Description Distance & Direction From Site A. Surface Water BY-12 Oregon Pool of Rock River, Downstream 4.5 miles SSW BY-29 Byron, Upstream (control) 3.0 miles N B. Ground/Well Water BY-14-1 3200 North German Church Road 1.0 miles SSE BY-18-1 Calhoun 0.7miles SSW BY-32 Krueger Well 1.9 miles W BY-35 VanckoWell 1.9 miles WNW BY-37 Cavage Well 2.0 miles WNW BY-38 Steve Storz Well 2.0milesWNW C. Milk BY-20-1 Ron Snodgrass Farm 4.8milesWSW BY-26-2 Joseph Akins Farm (control) 12.2 miles WNW D. Air Particulates I Air Iodine BY-01 Byron 3.0 miles N BY-04 Paynes Point 5.0 miles SE BY-06 Oregon 4.7 miles SSW BY-08 Leaf River (control) 7.0milesWNW BY-21 Byron Nearsite North 0.3 miles N BY-22 Byron Nearsite Southeast 0.4 miles SE BY-23 Byron Nearsite South 0.6 miles S BY-24 Byron Nearsite Southwest 0.7 miles SW E. Fish BY-29 Byron, Upstream (control) 3.0 miles N BY-31 Byron, Discharge 2.6 miles WNW F. Sediment BY-12 Oregon Pool of Rock River, Downstream 4.6 miles SSW BY-34 Rock River, Upstream of Discharge (control) 2.6 miles WNW G. Vegetation Quadrant 1 3989 Cox Road, Stillman Valley 4.8 miles E Quadrant 2 6402 Brick Road, Oregon 4.8 miles SE Quadrant 3 2002 Deer Path Road, Byron 1.0 miles SW Quadrant 4 6315 River Rd., Byron 2.3miles SW Control 1725 Michigan Ave., Rockford 14.7 miles NNE H. Environmental Dosimetry - OSLD Inner Ring BY-101-1 and -2 0.3 miles N BY-102-1 1.0 miles NNE BY-102-2 1.0 miles NNE B-1

TABLE B-1 : Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Byron Nuclear Generating Station. 2019 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - OSLO (continued)

Inner Ring BY-103-1 and -2 1.7 miles NE BY-103-3 0.4 miles NE BY-104-1 and -2 1.4 miles ENE BY-104-3 0.3miles ENE BY-105-1 and -2 1.3 miles E BY-106-1 and -2 1.4 miles ESE BY-107-1 and -2 1.4 miles SE BY-107-3 0.4 miles SE BY-108-1 0.7 miles SSE BY-108-2 0.6 miles SSE BY-109-1 and -2 0.6 miles S BY-110-1 and-2 0.7miles SSW BY-111-3 0.8 miles SW BY-111-4 0.9miles SW BY-112-3 and -4 0.8 miles WSW BY-113-1 and -2 0.7 milesW BY-114-1 and -2 0.8 miles WNW BY-115-1 and -2 1.0 miles NW BY-116-1 and -2 1.4 miles NNW BY-116-3 0.9 miles NNW Outer Ring BY-201-3 4.4 miles N BY-201-4 4.4 miles N BY-202-1 4.4 miles NNE BY-202-2 4.8 miles NNE BY-203-1 4.8 miles NE BY-203-2 4.7 miles NE BY-204-1 4.1 miles ENE BY-204-2 4.0 miles ENE BY-205-1 and -2 3.8 miles E BY-206-1 4.0 miles ESE BY-206-2 4.3 miles ESE BY-207-1 4.2 miles SE BY-207-2 3.9 miles SE BY-208-1 4.0 miles SSE BY-208-2 3.8 miles SSE BY-209-1 and -4 4.0 miles S BY-210-3 and -4 3.9 miles SSW BY-211-1 and -4 4.9 miles SW BY-212-1 and -4 4.7milesWSW BY-213-1 4.7milesW BY-213-4 4.7milesW BY-214-1 4.7 miles WNW BY-214-4 4.6 miles WNW BY-215-1 4.2milesNW BY-215-4 4.2 miles NW BY-216-1 4.Smiles NNW BY-216-2 4.7 miles NNW B-2

TABLE 8-1 : Radiological Environmental Monitoring Program - Sampling Locations. Distance and Direction, Byron Nuclear Generating Station, 2019 Location Location Description Distance & Direction From Site Special Interest BY-301-1 0.3 miles N BY-301-2 0.2 miles N BY-309-1 0.3 miles S BY-309-2 0.4 miles S BY-309-3 0.4 miles S BY-309-4 0.4 miles SSW BY-314-2 0.3milesWNW BY-01-1 and -2 3.0miles N BY-04-1 and -2 5.0 miles SE BY-06-1 and -2 4.7miles SSW BY-21-1 and -2 0.3miles N BY-22-1 and -2 0.4 miles SE BY 1 and -2 0.6 miles S BY-24-1 and -2 0.7miles SW BY-08-1 and -2 7.0 miles WNW 8-3

TABLE 8-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Byron Nuclear Generating Station , 2019 Sample Analysis Sampling Method Analytical Procedure Number Medium Monthly composite from Surface Water Gamma Spectroscopy TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis weekly grab samples.

Monthly composite from TBE, TBE-2008 Gross Alpha and/or Gross Beta Activity in Surface Water Gross Beta weekly grab samples. Various Matrices Monthly composite from Surface Water Nickel-63 TBE, TBE-2013 Radionickel Activity in Various Matrices weekly grab samples.

Quarterly composite from TBE, TBE-2011 Tritium Analysis in Drinking Water by Liquid Surface Water Tritium weekly grab samples. Scintillation Ground Water Gamma Spectroscopy Quarterly grab samples. TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis TBE, TBE-2011 Tritium Analysis in Drinking Water by Liquid Ground Water Tritium Quarterly grab samples.

Scintillation Semi-annual samples Fish Gamma Spectroscopy collected via electroshocking TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis or other techniques Semi-annual samples Fish Nickel-63 collected via electroshocking TBE, TBE-2013 Radionickel Activity in Various Matrices or other techniques Sediment Gamma Spectroscopy Semi-annual grab samples TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Sediment Nickel-63 Semi-annual grab samples TBE, TBE-2013 Radionickel Activity in Various Matrices One-week composite of continuous air sampling TBE, TBE-2008 Gross Alpha and/or Gross Beta Activity in Air Particulates Gross Beta through glass fiber filter Various Matrices paper Quarterly composite of continuous air sapling Air Particulates Gamma Spectroscopy TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis through glass fiber filter paper One-week composite of Air Iodine Gamma Spectroscopy continuous air sampling TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis through charcoal filter Bi-weekly grab sample when Milk 1-131 cows are on pasture. TBE, TBE-2012 Radioiodine in Various Matrices Monthly all other times Bi-weekly grab sample when Milk Gamma Spectroscopy cows are on pasture. TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Monthly all other times Vegetation Gamma Spectroscopy Annual grab samples. TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Optically Stimulated Quarterly OSLDs comprised OSLD Luminescence of two A'203:C Landauer Landauer Incorporated Dosimetry Incorporated elements.

B-4

Figure B-1 Inner Ring and Special Interest OSLD Locations of the Byron Nuclear Generating Station, 2019 B-5

lrw I

11 Figure 6.3b p uter Ri'lg Oosmeter Locations

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Figure B-2 Outer Ring OSLO Locations of the Byron Nuclear Generating Station, 2019 B-6

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  • Bwm Station Figure 8-4 Offsite Air Sampling Locations of the Byron Nuclear Generating Station, 2019 B-8

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  • 8 rSIOIUi f Al"ltlfl PAntNAV SAI.APLE t.OCA'TIONS ti f'lNfTUC..ff1 ~

Figure 8-5 Ingestion and Waterborne Exposure Pathway Sampling Locations of the Byron Nuclear Generating Station, 2019 B-9

Intentionally left blank B-10

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 BYRON NUCLEAR GENERATING STATION, 2019 RES ULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD BY-12 BY-29 01/08/19 - 01/15/19 < 3.0 < 3.0 02/05/19 - 02/05/19 < 2.8 (1) 03/12/19 - 03/26/19 4.2 +/- 1.7 5.4 +/- 1.8 04/02/19 - 04/30/19 3.0 +/- 2.0 2.9 +/- 2.0 05/07/19 05/28/19 3.5 +/- 2.0 4.0 +/- 2.0 06/04/19 - 06/24/19 < 2.8 < 2.9 07/02/19 - 07/30/19 5.7 +/- 2.8 3.7 +/- 2.5 08/06/19 - 08/27/19 4.1 +/- 1.9 5.1 +/- 2.1 09/03/19 - 09/24/19 5.6 +/- 2.0 3.5 +/- 1.8 10/01/19 - 10/29/19 6.4 +/- 2.1 5.8 +/- 2.1 11/05/19 - 11/26/19 4.2 +/- 2.0 4.5 +/- 2.0 12/03/19 - 12/30/19 2.8 +/- 1.8 4.1 +/- 1.9 MEAN +/- 2 STD DEV 4.4 +/- 2.5 4.3 +/- 1.9 Table C-1.2 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD BY-12 BY-29 01/08/19 - 03/26/19 < 193 < 198 04/02/19 - 06/24/19 < 187 < 186 07 /02/19 - 09/24/19 < 183 < 182 10/01/19 - 12/30/19 828 +/- 158 < 185 MEAN+/- 2 STD DEV 828 +/- 0 Table C-1.3 CONCENTRATIONS OF Nl-63 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD BY-12 BY-29 01/08/19 - 01/15/19 < 21 < 21 02/05/19 - 02/05/19 < 5 (1) 03/12/19 - 03/26/19 < 25 < 22 04/02/19 04/30/19 < 16 < 16 05/07/19 - 05/28/19 < 20 < 23 06/04/19 - 06/24/19 < 16 < 15 07/02/19 - 07/30/19 < 17 < 17 08/06/19 - 08/27/19 < 18 < 19 09/03/19 - 09/24/19 < 18 < 18 10/01/19 - 10/29/19 < 27 < 16 11/05/19 - 11/26/19 < 17 < 19 12/03/19 12/30/19 < 25 < 28 MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1

Table C-1.4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 BY-12 01102/19 - 01/15119 < 2 < 2 <5 < 2 <4 < 2 <4 < 13 < 2 < 2 < 27 <9 02/05119 - 02/05119 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 9 < 1 < 1 < 14 <4 03/12119 - 03126119 <3 < 3 <6 < 3 <6 <3 < 5 < 10 < 3 <3 < 20 <5 04102/19 - 04130119 < 2 < 2 < 5 < 2 <4 <2 <4 < 8 < 2 < 2 < 16 <5 05107119 - 05128119 < 1 < 2 <4 < 2 <3 < 2 <3 < 9 < 2 < 2 < 16 < 5 06104119 - 06124119 < 2 < 2 < 5 < 2 <4 < 2 <4 < 10 < 2 < 2 < 19 < 6 07102119 - 07130119 < 2 < 2 < 5 < 2 <4 < 2 <4 < 11 < 2 < 2 < 19 <7 08106119 - 08127119 <2 < 2 <5 < 2 <4 <2 < 4 < 10 < 2 <2 < 20 <6 09103119 - 09124119 < 2 < 2 < 5 < 2 <4 < 2 <4 < 8 < 2 < 2 < 15 <6 10101119 - 10129119 < 2 < 2 < 5 < 2 <4 < 2 <4 < 8 < 2 <2 < 15 <5 11105119 - 11126119 < 2 < 2 < 5 < 2 <4 < 2 < 4 < 9 < 2 < 2 < 17 <5 12/03119 - 12130119 < 2 < 2 < 5 < 2 <4 < 2 < 3 < 10 < 2 < 2 < 17 <7 MEAN 0I N

BY-29 01108119 - 01115119 <3 < 3 < 8 < 3 <6 <4 < 6 < 9 < 3 < 3 < 37 < 11 02/05119 - 02/05119 (1) 03112119 - 03126119 < 2 < 2 < 6 < 3 < 5 <3 < 5 < 8 < 3 < 3 < 18 <6 04102/19 - 04130119 < 2 < 2 <5 < 2 <4 < 2 <4 < 8 < 2 < 2 < 17 <5 05107119 - 05128119 < 2 < 2 < 5 <2 <4 <2 <4 < 12 < 2 < 2 < 19 <7 06104119 - 06124119 < 2 < 2 <4 < 1 < 3 < 2 < 3 < 7 < 2 < 2 < 14 < 5 07102/19 - 07130119 <2 < 3 <6 < 2 <4 < 3 <4 < 14 <2 <2 < 23 <7 08106119 - 08127119 < 2 < 2 < 5 < 2 <4 < 2 <4 < 8 < 2 < 2 < 17 <5 09103119 - 09124119 < 2 < 2 <4 < 2 <4 < 2 < 3 < 7 < 2 < 2 < 14 < 5 10101119 - 10129119 < 2 < 2 <4 <2 <4 < 2 < 3 < 8 < 2 < 2 < 15 <4 11105119 - 11126119 <2 < 2 <4 < 2 < 3 < 2 < 3 < 8 < 2 < 2 < 14 < 5 12103119 - 12130119 <2 < 2 <5 <2 <4 <2 <4 < 12 < 2 <2 < 22 <6 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-11.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD BY-14-1 BY-18-1 BY-32 BY-35 BY-37 BY-38 01/08/19 - 01/08/19 < 192 < 195 < 197 < 195 < 193 < 195 04/09/ 19 - 04/09/ 19 < 187 < 190 < 190 < 186 < 187 < 188 07/09/19 - 07/09/19 < 196 < 192 < 193 < 196 < 195 < 195 10/08/19 - 10/08/19 < 181 < 175 < 172 < 175 < 173 < 175 MEAN C-3

Table C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 BY-14-1 01/08/19 - 01/08/19 < 8 <7 < 14 <8 < 16 < 9 < 13 < 9 <7 < 8 < 28 < 10 04/09/19 - 04/09/19 <4 <4 < 9 <4 < 8 <4 < 7 < 7 <4 <4 < 18 <6 07/09/19 - 07/09/19 <7 < 6 < 14 <7 < 15 < 7 < 13 < 10 <7 < 6 < 28 < 11 10/08/19 - 10/08/19 <7 <9 < 17 <7 < 17 < 9 < 15 < 12 <8 < 9 < 40 < 15 MEAN BY-18-1 01/08/19 - 01/08/19 <6 < 5 < 11 < 6 < 13 < 8 < 10 < 8 <7 <6 < 22 < 7 04/09/19 - 04/09/19 <4 < 3 < 8 <4 < 6 <4 < 7 < 7 <4 <4 < 19 < 8 07/09/19 - 07/09/19 <8 < 7 < 18 <8 < 14 <8 < 11 < 7 <8 <8 < 25 < 12 10/08/19 - 10/08/19 <7 < 7 < 16 <7 < 18 < 8 < 11 < 12 <7 < 7 < 29 < 9 MEAN BY-32 01/08/19 - 01/08/19 < 5 < 7 < 13 < 6 < 15 < 8 < 11 < 7 <8 < 7 < 25 < 9 C)

~

04/09/19 07/09/19 10/08/19 04/09/19 07/09/19 10/08/19 7

7 5

6 7

7 17 13 13

<9

<6

<7 14 15 12 7

6 6

12 12 10 14 9

9

<7

<9

<5 7

7 7

38 24 26 9

13 10 MEAN BY-35 01/08/19 - 01/08/19 < 7 < 3 < 10 <7 < 13 < 5 < 10 < 6 <6 < 6 < 18 < 6 04/09/19 - 04/09/19 < 5 < 6 < 16 <6 < 11 < 7 < 12 < 13 <9 < 7 < 33 < 14 07/09/19 - 07/09/19 < 6 < 6 < 15 < 10 < 18 < 7 < 13 <8 < 10 <7 < 30 <9 10/08/19 - 10/08/19 < 5 < 7 < 13 < 8 < 9 < 8 < 12 < 10 <6 < 5 < 27 < 13 MEAN BY-37 01/08/19 - 01/08/19 <7 <6 < 11 <6 < 12 < 6 < 11 < 7 <8 <7 < 23 < 8 04/09/19 - 04/09/19 < 6 < 6 < 11 <7 < 15 < 7 < 11 < 12 <6 < 5 < 29 < 11 07/09/19 - 07/09/19 <7 <5 < 11 <9 < 12 < 7 < 13 < 9 <7 <6 < 26 < 9 10/08/19 - 10/08/19 < 6 <8 < 15 < 10 < 17 < 8 < 14 < 12 <8 < 8 < 32 < 13 MEAN BY-38 01/08/19 - 01/08/19 < 6 <7 < 14 <6 < 16 < 6 < 13 < 7 <6 < 6 < 24 < 5 04/09/19 - 04/09/19 <4 < 3 < 8 <3 < 8 <4 < 6 < 7 <4 < 4 < 18 <6 07/09/19 - 07/09/19 <5 <6 < 15 < 10 < 13 < 6 < 14 < 10 <8 < 8 < 32 < 9 10/08/19 - 10/08/19 < 5 <5 < 14 < 8 < 11 < 8 < 12 < 8 <5 < 7 < 24 < 14 MEAN

Table C-111.1 CONCENTRATIONS OF NICKEL-63 AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD Ni-63 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 BY-29 Silver Redhorse 05/23/19 - 05/23/19 < 86 < 51 < 69 < 155 < 60 < 120 < 61 < 129 < 67 < 51 < 347 < 145 Shorthead Redhorse 05/23/19 - 05/23/19 < 107 < 47 < 71 < 140 < 80 < 137 < 61 < 111 < 77 < 61 < 417 < 110 Freshwater Drum 10/23/19 - 10/23/19 < 108 < 60 < 55 < 144 < 60 < 145 < 57 < 78 < 60 < 51 < 250 < 67 Shorthead Redhorse 10/23/19 - 10/23/19 < 188 < 48 < 38 < 113 < 45 < 87 < 46 < 68 < 59 < 46 < 175 < 52 MEAN BY-31 Silver Redhorse 05/23/19 - 05/23/19 < 88 < 61 < 48 < 112 < 59 < 118 < 50 < 94 < 47 < 43 < 262 < 131

(') Common Carp 05/23/19 - 05/23/19 < 79 < 53 < 55 < 144 < 42 < 101 < 78 < 91 < 45 < 63 < 466 < 118 I

u, Channel Catfish 10/23/19 - 10/23/19 < 132 < 37 < 53 < 102 < 50 < 152 < 47 < 61 < 42 < 48 < 183 < 74 Common Carp 10/23/19 - 10/23/19 < 157 < 44 < 39 < 93 < 58 < 141 < 55 < 87 < 35 < 49 < 281 < 105 MEAN

Table C-IV.1 CONCENTRATIONS OF NICKEL-63 AND GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA COLLECTION SITE PERIOD Ni-63 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 BY-12 06/18/19 - 06/18/19 <227 <95 <98 < 219 <96 <233 <98 <180 <114 170+/-109 <398 <99 10/22/19 - 10/22/19 < 164 < 62 < 54 < 106 < 61 < 125 < 61 < 107 < 80 139 +/- 65 < 240 < 69 MEAN +/- 2 STD DEV 154 +/- 45 BY-34 06/18/19 - 06/18/19 < 233 < 95 < 84 < 137 < 72 < 171 < 87 < 142 < 108 192 +/- 81 < 352 < 74 10/22/19 - 10/22/19 < 190 < 57 < 55 < 121 < 67 < 121 < 57 < 102 < 83 242 +/- 65 < 235 < 71 MEAN+/- 2 STD DEV 217 +/- 71

(')

I 0)

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER+/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP Ill PERIOD BY-21 BY-22 BY-23 BY-24 BY-01 BY-04 BY-06 BY-08 01/02/19 - 01/08/19 30 +/- 6 23 +/- 5 24 +/- 5 29 +/- 6 28 +/- 6 31 +/- 6 24 +/- 5 30 +/- 6 01/08/19 - 01/15/19 17 +/- 4 15 +/- 4 17 +/- 4 15 +/- 4 15 +/- 4 16 +/- 4 15 +/- 4 15 +/- 4 01/15/19 - 01/23/19 14 +/- 4 12 +/- 4 12 +/- 4 8 +/- 4 15 +/- 4 12 +/- 4 11 +/- 4 17 +/- 4 01/22/19

  • 01/29/19 18 +/- 4 21 +/- 5 28 +/- 5 24 +/- 5 20 +/- 4 22 +/- 5 18 +/- 4 24 +/- 5 01/29/19 - 02/05/19 20 +/- 4 17 +/- 4 18 +/- 4 19 +/- 4 18 +/- 4 13 +/- 4 17 +/- 4 17 +/- 4 02/05/19
  • 02/11 /19 16 +/- 5 14 +/- 4 16 +/- 5 15 +/- 4 12 +/- 4 13 +/- 4 11 +/- 4 13 +/- 4 02111/19 - 02/19/19 (1) 16 +/- 4 19 +/- 4 18 +/- 4 21 +/- 4 15 +/- 4 19 +/- 4 19 +/- 4 02/19/19 - 02/26/19 21 +/- 6 18 +/- 5 21 +/- 5 22 +/- 5 14 +/- 5 18 +/- 5 20 +/- 5 20 +/- 5 02/26/19
  • 03/05/19 25 +/- 5 21 +/- 5 14 +/- 4 21 +/- 5 18 +/- 4 15 +/- 4 18 +/- 4 19 +/- 4 03/05/19 - 03/12/19 11 +/- 4 12 +/- 4 14 +/-4 15 +/- 4 13 +/- 4 12 +/- 4 10 +/- 3 12 +/- 4 03/12/19 - 03/19/19 10 +/- 4 15 +/- 4 14 +/- 4 12 +/- 4 12 +/- 4 14 +/- 4 12 +/- 4 11 +/- 4 03/19/19 - 03/26/19 17 +/- 4 16 +/- 4 14 +/- 4 12 +/- 4 13 +/- 4 14 +/- 4 16 +/- 4 16 +/- 4 03/26/19 - 04/02/19 10 +/- 4 13 +/- 4 16 +/-4 9 +/- 3 17 +/- 4 17 +/- 4 14 +/- 4 14 +/- 4 04/02/19 - 04/09/19 11 +/- 3 14 +/- 4 14 +/- 4 13 +/- 4 18 +/- 4 12 +/- 4 14 +/- 4 12 +/- 3 04/09/19 - 04/16119 6 +/- 3 6 +/- 3 6 +/- 3 7 +/- 3 6 +/- 3 6 +/- 3 5 +/- 3 6 +/- 3 04/16/19 - 04/23119 12 +/- 4 12 +/- 4 12 +/- 4 11 +/- 4 11 +/- 4 10 +/- 4 11 +/- 4 13 +/- 4 04/23/19 - 04130/19 13 +/- 4 11 +/- 4 11 +/- 4 11 +/- 4 11 +/- 4 12 +/- 4 15 +/- 4 13 +/- 4 04/30/19 - 05107/19 10 +/- 4 6 +/- 3 5 +/- 3 8 +/- 3 7 +/- 3 5 +/- 3 8 +/- 4 8 +/- 3 05107 /19 - 05/14119 10 +/- 3 12 +/- 4 8 +/- 3 12 +/- 4 9 +/- 3 8 +/- 3 13 +/- 4 10 +/- 4 05/14/19 - 05/20/19 11 +/- 4 13 +/- 5 9 +/- 4 10 +/- 4 12 +/- 4 15 +/- 5 11 +/- 4 9 +/- 4 05/20/19 - 05/28/19 7 +/- 3 7 +/- 3 9 +/- 3 9 +/- 3 8 +/- 3 9 +/- 3 11 +/- 3 7 +/- 3 05/28/19 - 06104119 14 +/- 4 11 +/- 4 (1) 9+/-4 16 +/- 4 12 +/- 4 12 +/- 4 11 +/- 4 06/04/19 - 06/11/19 16 +/- 4 20 +/- 4 17 +/- 5 16 +/- 4 16 +/- 4 19 +/- 4 17 +/- 4 14 +/- 4 06/11/19 - 06118/19 14 +/- 4 10 +/- 4 10 +/- 4 12 +/- 4 15 +/- 4 14 +/- 4 11 +/- 4 12 +/- 4 06/18/19 - 06/24119 13 +/- 4 14 +/- 4 15 +/- 4 14 +/- 4 14 +/- 4 15 +/- 4 14 +/- 4 15 +/- 4 06/24/19
  • 07102/19 18 +/- 4 17 +/- 4 15 +/- 3 16 +/- 4 15 +/- 3 18 +/- 4 17 +/- 4 17 +/- 4 07/02/19 - 07109/19 10 +/- 4 9 +/- 4 9 +/-4 8 +/- 4 11 +/- 4 8 +/- 3 10 +/- 4 11 +/- 4 07/09119 - 07/16119 16 +/- 4 14 +/- 4 14 +/- 4 16 +/- 4 13 +/- 4 14 +/- 4 15 +/- 4 17 +/- 4 07/16119 - 07/23119 12 +/- 4 12 +/- 4 10 +/- 4 13 +/- 4 8 +/- 4 10 +/- 4 11 +/- 4 11 +/- 4 07/23/19 - 07/30/19 14 +/- 4 13 +/- 4 16 +/- 4 15 +/- 4 14 +/- 4 16 +/- 4 18 +/- 4 15 +/- 4 07/30/19 - 08106119 16 +/- 4 16 +/- 4 17 +/- 4 14 +/- 4 15 +/- 4 13 +/- 4 16 +/- 4 18 +/- 4 08/06/19 - 08/13119 19 +/- 4 16 +/- 4 18 +/- 4 18 +/- 4 18 +/- 4 17 +/- 4 17 +/- 4 18 +/- 4 08/13/19 - 08/20/19 15 +/- 4 15 +/- 4 17 +/- 4 18 +/- 5 16 +/- 4 15 +/- 4 16 +/- 4 17 +/- 4 08120/19 - 08127119 10 +/- 4 12 +/- 4 12 +/- 4 13 +/- 4 10 +/- 4 11 +/- 4 13 +/- 4 14 +/- 4 08/27/19 - 09/03119 16 +/- 4 17 +/- 4 19 +/- 4 14 +/- 4 17 +/- 4 19 +/- 4 19 +/- 4 18 +/- 4 09/03/19 - 09/10119 12 +/- 4 16 +/- 4 16 +/- 4 18 +/- 4 13 +/- 4 17 +/- 4 15 +/- 4 14 +/- 4 09/10/19 - 09/17119 17 +/- 5 18 +/- 5 16 +/- 4 18 +/- 5 17 +/- 5 19 +/- 5 19 +/- 5 15 +/- 10 09/17/19 - 09124119 24 +/- 5 22 +/- 5 24 +/- 5 26 +/- 5 20 +/- 5 26 +/- 5 21 +/- 5 23 +/- 5 09/24119 - 10/01/19 16 +/- 4 12 +/- 4 15 +/- 4 17 +/- 4 15 +/- 4 13 +/- 4 17 +/- 4 12 +/- 4 10101/19 - 10/08/19 12 +/- 4 10 +/- 4 12 +/- 4 12 +/- 4 10 +/- 4 11 +/- 4 11 +/- 4 10 +/- 3 10/08/19 - 10115119 19 +/- 5 13 +/- 4 20 +/- 4 15 +/- 4 20 +/- 5 19 +/- 5 18 +/- 5 16 +/- 4 10/15/19 - 10/22119 14 +/- 4 12 +/- 4 12 +/- 4 16 +/- 4 17 +/- 4 14 +/- 4 14 +/- 4 16 +/- 4 10/22/19 - 10/29119 14 +/- 4 7 +/- 4 12 +/- 4 12 +/- 4 12 +/- 4 12 +/- 4 10 +/- 4 9 +/- 4 10/29/19 - 11/05/19 11 +/- 4 11 +/- 4 12 +/- 4 12 +/- 4 11 +/- 4 12 +/- 4 11 +/- 4 10 +/- 4 11/05/19 - 11/12119 20 +/- 4 11 +/- 4 9 +/- 4 11 +/- 4 19 +/- 4 13 +/- 4 19 +/- 4 19 +/- 4 11/12/19 - 11/19/19 24 +/- 4 24 +/- 4 24 +/- 4 25 +/- 5 24 +/- 4 28 +/- 5 26 +/- 5 27 +/- 5 11119/19 - 11/26/19 15 +/- 4 16 +/- 4 16 +/- 4 12 +/- 4 12 +/- 4 16 +/- 4 17 +/- 4 14 +/- 4 11/26/19 - 12/03119 5 +/- 3 4 +/- 3 7 +/- 3 7 +/- 3 < 4 5 +/- 3 5 +/- 3 8 +/- 3 12/03/19 - 12/10/19 18 +/- 4 17 +/- 4 16 +/- 4 18 +/- 4 18 +/-4 19 +/- 4 20 +/- 4 19 +/- 4 12/10/19 - 12117119 29 +/- 5 25 +/- 5 17 +/- 4 30 +/- 5 25 +/- 5 28 +/- 5 27 +/- 5 24 +/- 5 12/17/19 - 12/23119 32 +/- 6 32 +/- 6 29 +/- 6 32 +/- 6 33 +/- 6 31 +/- 6 32 +/- 6 33 +/- 6 12/23/19 - 12/30119 27 +/- 5 24 +/- 4 20 +/- 4 21 +/- 4 21 +/- 4 26 +/- 5 20 +/- 4 23 +/- 4 MEAN+/- 2 STD DEV 16 +/- 12 15 +/- 11 15 +/- 10 15 +/- 12 15 +/- 10 15 +/- 12 15 +/- 10 15 +/- 11 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-7

Table C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - NEARSITE LOCATIONS GROUP II - FAR FIELD LOCATIONS GROUP Ill - CONTROL LOCATIONS COLLECTION MIN MAX MEAN COLLECTION MIN MAX MEAN COLLECTION MIN MAX MEAN PERIOD +/-2SD PERIOD +/-2SD PERIOD +/-2SD 01/02/19 - 01/29/19 8 30 19 +/- 13 01/02/19 - 01/29/19 11 31 19 +/- 12 01/02/19 - 01/29/19 15 30 21 +/- 13 01 /29/19 - 02/26/19 14 22 18 +/- 5 01/29/19 - 02/26/19 11 21 16 +/- 7 01/29/19 - 02/26/19 13 20 17 +/- 6 02/26/19 - 04/02/19 9 25 15 +/- 8 02/26/19 - 04/02/19 10 18 14 +/- 5 02/26/19 - 04/02/19 11 19 14 +/- 7 04/02/19 - 04/30/19 6 14 11 +/- 6 04/02/19 - 04/30/19 5 18 11 +/- 8 04/02/19 - 04/30/19 6 13 11 +/- 6 04/30/19 - 06/04/19 5 14 10 +/- 5 04/30/19 - 06/04/19 5 16 10 +/- 6 04/30/19 - 06/04/19 7 11 9+/-3 06/04/19 - 07/02/19 10 20 15 +/- 6 06/04/19 - 07/02/19 11 19 15 +/- 4 06/04/19 - 07/02/19 12 17 15 +/- 4 07/02/19 - 07/30/19 8 16 13 +/- 5 07/02/19 - 07/30/19 8 18 12 +/- 7 07/02/19 - 07/30/19 11 17 14 +/- 6 07/30/19 - 09/03/19 10 19 15 +/- 5 07/30/19 - 09/03/19 10 19 15 +/- 5 07/30/19 - 09/03/19 14 18 17 +/- 3 09/03/19 - 10/01 /19 12 26 18 +/- 8 09/03/19 - 10/01/19 13 26 18 +/- 7 09/03/19 - 10/01/19 12 23 16 +/- 9 10/01/19 - 10/29/19 7 20 13 +/- 6 10/01/19 - 10/29/19 10 20 14 +/- 7 10/01/19 - 10/29/19 9 16 13 +/- 8 10/29/19 - 12/03/19 4 25 14 +/- 13 10/29/19 - 12/03/19 5 28 16 +/- 14 10/29/19 - 12/03/19 8 27 15 +/- 16 C)

I 12/03/19 - 12/30/19 16 32 24 +/- 12 12/03/19 - 12/30/19 18 33 25 +/- 11 12/03/19 - 12/30/19 19 33 25 +/- 12 co 01/02/19 - 12/30/19 4 32 15 +/- 11 01/02/19 - 12/30/19 5 33 15 +/- 11 01/02/19 - 12/30/19 6 33 15 +/- 11

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 BY-01 01/02/19 - 04/02/19 < 3 < 5 < 12 <4 < 6 <4 < 8 <4 < 2 < 196 < 60 04/02/19 - 07/02/19 < 3 < 6 < 12 <3 <5 < 5 <9 <3 <2 < 338 < 127 07/02/19 - 10/01/19 < 3 <4 < 12 < 3 < 6 <4 <7 <3 < 2 < 193 < 79 10/01/19 - 12/30/19 < 2 < 4 < 8 < 1 < 5 < 3 <5 < 2 < 1 < 126 < 34 MEAN BY-04 01/02/19 - 04/02/19 < 2 <4 < 11 < 2 <7 <4 < 7 < 3 < 2 < 187 < 8 04/02/19 - 07/02/19 < 2 <3 < 12 < 2 < 5 <5 < 5 < 3 < 2 < 272 < 84 07/02/19 - 10/01/19 < 3 < 3 < 13 < 2 <6 <4 < 7 < 3 < 2 < 162 < 87 10/01/19 - 12/30/19 < 2 <4 < 14 < 3 < 6 < 3 < 7 < 3 < 2 < 192 < 79 MEAN

(')

I U)

BY-06 01/02/19 - 04/02/19 <3 <4 < 14 < 3 <8 <5 < 8 < 3 < 3 < 230 < 86 04/02/19 - 07/02/19 <3 < 5 < 16 < 2 <7 <5 < 7 < 3 < 2 < 290 < 117 07/02/19 - 10/01/19 < 2 < 2 < 9 < 2 <5 <3 < 5 < 2 < 2 < 131 < 52 10/01/19 - 12/30/19 < 2 < 3 < 8 < 3 <6 <4 < 8 < 2 < 2 < 139 < 86 MEAN BY-08 01/02/19 - 04/02/19 <2 <3 < 13 <3 <8 <4 < 7 <3 < 3 < 179 < 70 04/02/19 - 07/02/19 <2 < 3 < 11 < 3 < 6 <4 < 7 <2 < 2 < 247 < 80 07/02/19 - 10/01/19 <2 < 3 < 12 < 2 <4 <4 < 7 < 2 < 2 < 104 < 64 10/01/19 - 12/30/19 < 2 <4 < 8 <2 < 6 <3 < 6 < 2 < 2 < 161 < 33 MEAN

Table C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 BY-21 01/02/19 - 04/02/19 <3 < 6 < 13 <4 < 7 <6 < 10 <4 < 3 < 272 < 89 04/02/19 - 07/02/19 < 3 < 5 < 12 < 3 < 9 < 5 <7 < 2 < 2 < 315 < 141 07/02/19 - 10/01/19 <3 < 3 < 11 <3 < 6 <4 <6 <2 < 3 < 175 < 72 10/01/19 - 12/30/19 <2 < 3 < 11 < 2 < 6 <4 < 7 < 3 < 2 < 181 < 84 MEAN BY-22 01/02/19 - 04/02/19 < 3 <4 < 7 < 2 < 6 <4 < 9 < 3 < 3 < 204 < 79 04/02/19 - 07/02/19 <2 <3 < 15 < 3 <6 <4 < 7 < 2 < 2 < 259 < 125 07/02/19 - 10/01/19 < 3 <4 < 8 < 2 < 6 <4 < 9 < 3 < 2 < 174 < 55 10/01/19 - 12/30/19 < 3 < 4 < 15 < 4 < 8 <4 < 8 < 3 < 3 < 211 < 59 0I MEAN

~

0 BY-23 01/02/19 - 04/02/19 <3 < 5 < 12 < 4 <8 <5 < 9 <4 <3 < 224 < 74 04/02/19 - 07/02/19 < 3 <4 < 11 <4 <7 <4 <8 <3 < 2 < 306 < 116 07/02/19 - 10/01/19 < 3 < 4 < 14 < 2 < 5 <4 <6 < 3 <2 < 204 < 80 10/01/19 - 12/30/19 < 2 < 2 < 8 < 3 <4 < 3 <6 < 2 < 2 < 149 < 46 MEAN BY-24 01/02/19 - 04/02/19 < 2 < 3 < 10 < 3 < 7 <3 <7 < 2 < 2 < 163 < 52 04/02/19 - 07/02/19 < 2 <4 < 8 < 3 < 6 <4 < 6 < 2 <2 < 237 < 88 07/02/19 - 10/01/19 < 2 < 3 < 10 < 2 < 5 < 3 < 8 < 2 < 2 < 187 < 35 10/01/19 - 12/30/19 < 1 < 3 < 8 < 2 < 5 <4 <4 < 2 < 2 < 156 < 46 MEAN

Table C-Vl.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP Ill PERIOD BY-21 BY-22 BY-23 BY-24 BY-01 BY-04 BY-06 BY-08 01/02/19 - 01/08/19 < 31 < 31 < 31 < 31 < 19 < 18 < 15 < 18 01/08/19 - 01/15/19 < 46 < 46 < 46 < 46 < 54 < 55 < 55 < 54 01/15/19 - 01/23/19 < 60 < 50 < 50 < 60 < 62 < 51 < 63 < 52 01/22/19 - 01/29/19 < 55 < 62 < 63 < 56 < 49 < 55 < 48 < 53 01/29/19 - 02/05/19 < 63 < 63 < 64 < 64 < 49 < 51 < 51 < 49 02/05/19 - 02/11/19 < 45 < 45 < 44 < 44 < 53 < 51 < 52 < 52 02/11/19 - 02/19/19 (1) < 48 < 48 < 49 < 41 < 42 < 42 < 42 02/19/19 - 02/26/19 < 52 < 46 < 47 < 46 < 29 < 28 < 29 < 29 02/26/19 - 03/05/19 < 48 < 48 < 48 < 48 < 25 < 26 < 26 < 26 03/05/19 - 03/12/19 < 63 < 63 < 62 < 62 < 54 < 53 < 53 < 53 03/12/19 - 03/19/19 < 33 < 33 < 33 < 34 < 51 < 51 < 50 < 50 03/19/19 - 03/26/19 < 46 < 46 < 46 < 46 < 66 < 65 < 66 < 66 03/26/19 - 04/02/19 < 44 < 44 < 44 < 44 < 31 < 32 < 32 < 32 04/02/19 - 04/09/19 < 39 < 39 < 40 < 40 < 27 < 26 < 26 < 26 04/09/19 - 04/16/19 < 59 < 59 < 59 < 59 < 29 < 36 < 35 < 35 04/16/19 - 04/23/19 < 41 < 41 < 41 < 41 < 35 < 34 < 34 < 35 04/23/19 - 04/30/19 < 41 < 40 < 40 < 17 < 34 < 34 < 34 < 34 04/30/19 - 05/07/19 < 42 < 42 < 42 < 42 < 23 < 24 < 24 < 24 05/07/19 - 05/14/19 < 45 < 45 < 45 < 45 < 31 < 30 < 30 < 30 05/14/19 - 05/20/19 < 28 < 15 < 27 < 27 < 30 < 30 < 30 < 30 05/20/19 - 05/28/19 < 52 < 52 < 52 < 51 < 32 < 32 < 32 < 32 05/28/19 - 06/04/19 < 18 < 17 (1) < 17 < 29 < 29 < 30 < 30 06/04/19 - 06/11/19 < 11 < 39 < 45 < 39 < 26 < 27 < 26 < 26 06/11/19 - 06/18/19 < 53 < 53 < 53 < 53 < 32 < 31 < 32 < 32 06/18/19 - 06/24/19 < 28 < 28 < 28 < 28 < 58 < 58 < 58 < 59 06/24/19 - 07/02/19 < 15 < 45 < 46 < 45 < 35 < 36 < 36 < 36 07/02/19 - 07/09/19 < 36 < 36 < 35 < 35 < 51 < 51 < 51 < 21 07/09/19 - 07/16/19 < 56 < 56 < 55 < 23 < 32 < 33 < 33 < 34 07/16/19 - 07/23/19 < 29 < 29 < 29 < 30 < 16 < 16 < 16 < 16 07/23/19 - 07/30/19 < 55 < 55 < 55 < 55 < 33 < 33 < 33 < 34 07/30/19 - 08/06/19 < 26 < 23 < 54 < 54 < 31 < 31 < 31 < 31 08/06/19 - 08/13/19 < 43 < 43 < 43 < 43 < 21 < 26 < 26 < 26 08/13/19 - 08/20/19 < 28 < 28 < 12 < 34 < 42 < 41 < 41 < 41 08/20/19 - 08/27/19 < 48 < 48 < 48 < 48 < 25 < 61 < 61 < 62 08/27/19 - 09/03/19 < 38 < 62 < 59 < 61 < 36 < 36 < 35 < 29 09/03/19 - 09/10/19 < 44 < 43 < 43 < 18 < 36 < 36 < 36 < 36 09/10/19 - 09/17/19 < 37 < 37 < 15 < 36 < 26 < 25 < 26 < 60 09/17/19 - 09/24/19 < 65 < 65 < 65 < 65 < 39 < 39 < 39 < 39 09/24/19 - 10/01/19 < 23 < 63 < 61 < 61 < 52 < 49 < 48 < 48 10/01/19 - 10/08/19 < 40 < 28 < 27 < 27 < 40 < 41 < 35 < 39 10/08/19 - 10/15/19 < 26 < 26 < 24 < 25 < 24 < 24 < 25 < 24 10/15/19 - 10/22/19 < 59 < 59 < 49 < 58 < 38 < 38 < 39 < 38 10/22/19 - 10/29/19 < 53 < 53 < 53 < 53 < 41 < 42 < 42 < 42 10/29/19 - 11/05/19 < 15 < 15 < 15 < 15 < 10 < 22 < 22 < 23 11/05/19 - 11/12/19 < 18 < 18 < 18 < 18 <9 < 22 < 22 < 22 11/12/19 - 11/19/19 < 41 < 41 < 41 < 49 < 60 < 61 < 61 < 61 11/19/19 - 11/26/19 < 68 < 68 < 68 < 68 < 50 < 50 < 50 < 50 11/26/19 - 12/03/19 < 36 < 36 < 36 < 36 < 34 < 34 < 35 < 35 12/03/19 - 12/10/19 < 28 < 28 < 28 < 28 < 41 < 41 < 41 < 41 12/10/19 - 12/17/19 < 21 < 21 < 21 < 17 < 32 < 33 < 33 < 33 12/17/19 - 12/23/19 < 24 < 52 < 53 < 52 < 58 < 58 < 58 < 58 12/23/19 - 12/30/19 < 53 < 53 < 53 < 53 < 50 < 50 < 50 < 50 MEAN (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 BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION CONTROL FARM INDICATOR FARM PERIOD BY-26-2 BY-20-1 01/02/19 < 0.8 < 0.7 02/05/19 < 0.7 < 0.6 03/05/19 < 0.6 < 0.6 04/02/19 < 0.8 < 0.9 05/07/19 < 0.7 < 0.6 05/20/19 < 0.8 < 1.0 06/04/19 < 0.6 < 0.5 06/18/19 < 0.9 < 0.9 07/02/19 < 0.8 < 0.8 07/16/19 < 0.5 < 0.5 07/30/19 < 0.8 < 0.7 08/13/19 < 0.8 < 0.7 08/27/19 < 0.7 < 0.7 09/10/19 < 1.0 < 0.9 09/24/19 < 0.7 < 0.7 10/08/19 < 0.8 < 0.8 10/22/19 < 0.9 < 0.9 11/05/19 < 0.6 < 0.9 12/03/19 < 0.7 < 0.8 MEAN C-12

Table C-Vll.2 CONCENTRATIONS OF GAMMA EMMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 BY-20-1 01/02/19 < 6 < 7 < 19 < 8 < 16 < 7 < 13 < 8 <7 < 33 < 8 02/05/19 <7 <8 < 17 < 10 < 17 < 7 < 11 < 7 < 8 < 29 < 11 03/05/19 <7 <7 < 17 < 10 < 16 <9 < 15 < 8 < 8 < 33 < 7 04/02/19 <7 <7 < 14 < 9 < 18 < 7 < 12 < 9 < 8 < 31 < 13 05/07/19 <7 <8 < 13 < 6 < 17 < 6 < 12 < 7 <7 < 24 < 8 05/20/19 < 6 <7 < 15 < 8 < 17 <7 < 12 < 7 < 7 < 22 < 9 06/04/19 <9 <9 < 19 < 13 < 22 < 9 < 15 < 12 < 12 < 40 < 10 06/18/19 <8 <9 < 22 < 12 < 24 < 10 < 15 < 7 < 8 < 42 < 9 07/02/19 <4 <4 <9 < 5 < 9 <4 <6 < 5 <4 < 15 < 5 07/16/19 < 6 < 6 < 13 < 6 < 11 < 5 < 10 < 6 < 5 < 23 < 5 07/30/19 <6 <8 < 16 < 9 < 17 <7 < 13 < 9 < 8 < 38 < 11 08/13/19 <8 <8 < 18 < 9 < 16 <8 < 13 < 8 < 9 < 31 < 8 08/27/19 <7 <7 < 17 < 7 < 15 < 7 < 11 < 6 < 6 < 38 < 14 09/10/19 <8 < 10 < 19 < 9 < 26 < 10 < 15 < 7 < 8 < 40 < 11 09/24/19 <8 < 8 < 18 < 11 < 21 <8 < 14 < 8 < 8 < 36 < 10 10/08/19 < 8 <9 < 23 < 10 < 25 < 9 < 15 < 8 < 10 < 44 < 15 0I 10/22/19 < 9 < 8 < 18 < 8 < 20 < 8 < 16 < 8 <9 < 26 < 10 (A) 11/05/19 <6 <6 < 16 < 5 < 18 < 8 < 12 < 7 < 8 < 27 < 7 12/03/19 < 9 < 9 < 21 < 9 < 23 <8 < 16 < 9 < 11 < 30 < 12 MEAN BY-26-2 01/02/19 < 8 <8 < 21 < 10 < 18 < 9 < 16 < 10 < 9 < 43 < 11 02/05/19 < 7 <7 < 13 <8 < 14 < 6 < 11 < 7 < 7 < 27 < 10 03/05/19 < 9 < 9 < 22 < 10 < 24 < 10 < 17 < 11 < 9 < 42 < 11 04/02/19 < 9 < 8 < 17 < 7 < 17 < 7 < 13 < 9 < 7 < 36 < 13 05/07/19 < 9 < 9 < 16 < 9 < 16 < 8 < 11 < 8 < 11 < 33 < 11 05/20/19 < 8 < 7 < 15 <7 < 16 < 6 < 11 < 8 < 7 < 30 <8 06/04/19 < 7 < 8 < 19 < 9 < 19 < 7 < 14 < 9 < 8 < 40 < 12 06/18/19 <6 <8 < 15 <9 < 18 < 7 < 10 < 8 < 8 < 37 < 11 07/02/19 < 3 <4 < 9 < 4 < 9 < 3 < 7 < 5 < 3 < 12 <4 07/16/19 < 8 < 7 < 18 < 10 < 18 < 9 < 15 < 8 < 8 < 32 <9 07/30/19 < 7 <8 < 20 <8 < 17 < 8 < 18 < 10 < 9 < 43 < 12 08/13/19 < 6 <6 < 11 <7 < 17 < 8 < 12 < 7 < 7 < 26 <7 08/27/19 < 7 < 7 < 14 <6 < 18 < 6 < 13 < 7 < 6 < 31 < 10 09/10/19 < 9 < 10 < 21 < 10 < 19 < 8 < 14 < 10 < 8 < 37 < 12 09/24/19 <9 <9 < 21 < 11 < 22 < 9 < 14 < 11 < 10 < 45 < 7 10/08/19 <7 < 7 < 17 < 8 < 19 < 6 < 12 < 8 < 8 < 34 < 12 10/22/19 < 7 < 7 < 18 < 11 < 16 < 7 < 13 < 8 < 7 < 21 < 7 11/05/19 < 7 <7 < 16 <7 < 15 < 8 < 14 < 8 < 7 < 25 <7 12/03/19 <7 <8 < 14 <7 < 15 < 7 < 12 < 7 < 7 < 34 < 8 MEAN

Table C-Vlll.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/KG WET+/- 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 BY-CONTROL Cabbage 08/12/19 < 14 < 15 < 31 < 21 < 40 < 20 < 23 < 20 < 18 < 21 < 75 < 19 Zucchini 08/12/19 < 13 < 13 < 24 < 17 < 30 < 18 < 24 < 16 < 17 < 12 < 60 < 14 MEAN BY-QUAD 1 Beet Leaves 08/13/19 < 21 < 18 < 37 < 20 < 45 < 18 < 33 < 24 < 23 < 23 < 79 < 22 Beets 08/13/19 < 30 < 28 < 59 < 32 < 58 < 31 < 54 < 39 < 34 < 33 < 124 < 32 MEAN BY-QUAD 2 C) Cabbage 08/14/19 < 20 < 18 < 42 < 24 < 40 < 26 < 36 < 29 < 24 < 25 < 99 < 28 I

..lo. Potatoes 08/14/19 < 25 < 29 < 71 < 38 < 74 < 35 < 52 < 46 < 28 < 36 < 112 < 44

~

MEAN BY-QUAD 3 Carrots/Rutabaga 08/14/19 < 28 < 22 < 61 < 32 < 53 < 32 < 42 < 35 < 30 < 26 < 103 < 38 Cabbage 08/14/19 < 33 < 24 < 67 < 28 < 70 < 32 < 39 < 44 < 32 < 26 < 116 < 32 MEAN BY-QUAD 4 Cabbage 08/13/19 < 22 < 20 < 46 < 27 < 51 < 22 < 43 < 38 < 23 < 24 < 117 < 37 Zucchini 08/13/19 < 21 < 21 < 40 < 16 < 42 < 20 < 32 < 35 < 21 < 17 < 64 < 16 MEAN

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