Text

2023 Annual Radioactive Effluent Release Report (ARERR)
	ML24116A119
Person / Time
Site:	Byron
Issue date:	04/25/2024
From:	Welt H; Constellation Energy Generation
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	2024-0027
	Download: ML24116A119 (1)
	v • d • e

April 25, 2024 L TR:

BYRON 2024-0027 File 1D.101 2C.111 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Constellation Energy Generation. LLC (CEG)

Byron Station 4450 N. German Church Road Byron, IL 61010-9794 www.constellationenergy.com 10 CFR 50.36a Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455

Subject:

2023 Annual Radioactive Effluent Release Report (ARERR)

Enclosed is the Annual Radioactive Effluent Release Report for Byron Station. This report is being submitted in accordance with 10 CFR 50.36 a(2), 'Technical specifications on effluents from nuclear power reactors," and includes a summary of radiological liquid and gaseous effluents and solid waste released from the site from January 2023 through December 2023.

If you have any questions regarding this information, please contact Ms. Zoe Cox, Regulatory Assurance Manager, at (779) 231-6606.

Respectfully, Harris Welt Site Vice President Byron Station HW/AH/JNhh Enclosures cc: Regional Administrator-NRC Region Ill

April 25, 2024 L TR: BYRON 2024-0027 bee:

Illinois Emergency Management Agency - Division of Nuclear Safety - Byron Station (report only) - Rick Knutson Director, Licensing and Regulatory Affairs (without enclosures) - Kevin Lueshen Manager, Licensing - Braidwood/Byron (without enclosures) - Rebecca Steinman Regulatory Assurance Manager - Byron Station (without enclosures) - Zoe Cox NRC Coordinator - Byron Station (without enclosures) - Jerry Armstrong CEG Document Control Desk Licensing (all enclosures)

Byron Sr Chemist (without enclosures) - Ashley Hodzic Deputy Regional Administrator Office Assistant (without enclosures) - Carmen Oltenau

Constellation Byron Nuclear Generating Station Annual Radioactive Effluent Release Report 2023

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 1 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS................................................................................ 3 2.0 EXECUTIVE

SUMMARY

............................................................................................................ 5 2.1 Comparison to Regulatory Limits.................................................................................... 6

3.0 INTRODUCTION

........................................................................................................................ 9 3.1 About Nuclear Power...................................................................................................... 9 3.2 About Radiation Dose................................................................................................... 11 3.3 About Dose Calculation................................................................................................ 13 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS................................................................. 15 4.1 Regulatory Limits.......................................................................................................... 15 4.2 Regulatory Limits for Gaseous Effluent Doses:............................................................. 15 4.3 Regulatory Limits for Liquid Effluent Doses................................................................... 16 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public.................................. 17 5.0 SUPPLEMENTAL INFORMATION........................................................................................... 17 5.1 Gaseous Batch Releases............................................................................................. 17 5.2 Liquid Batch Releases.................................................................................................. 17 5.3 Abnormal Releases...................................................................................................... 18 5.4 Land Use Census Changes.......................................................................................... 18 5.5 Meteorological Data...................................................................................................... 18 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days................................ 18 5.7 Offsite Dose Calculation Manual (ODCM) Changes...................................................... 18 5.8 Process Control Program (PCP) Changes.................................................................... 18 5.9 Radioactive Waste Treatment System Changes........................................................... 18 5.1 O Other Supplemental Information................................................................................... 18 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM............... 20 6.1 Voluntary Notification.................................................................................................... 20 7.0 BIBLIOGRAPHY...................................................................................................................... 21 TABLES Table 1, Byron Clean Energy Center Unit 1 Dose Summary.................................................................. 6 Table 2, Byron Clean Energy Center Unit 2 Dose Summary.................................................................. 7 Table 3, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for BYR..................................... 8 Table 4, Gaseous Effluents Summation of All Releases Unit 1........................................................... 22 Table 5, Gaseous Effluents Summation of All Releases Unit 2........................................................... 23 Table 6, Gaseous Effluents - Mixed Level Release Batch Mode Unit 1............................................. 24 Table 7, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 1.................................... 25 Table 8, Gaseous Effluents - Mixed Level Release Batch Mode Unit 2............................................. 26 Table 9, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 2.................................... 27 Table 10, Liquid Effluents - Summation of All Releases Unit 1........................................................... 28 Table 11, Liquid Effluents - Summation of All Releases Unit 2........................................................... 30 Table 12, Liquid Effluents Batch Mode Unit 1...................................................................................... 31

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 2 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 13, Liquid Effluents Continuous Mode Unit 1.............................................................................. 32 Table 14, Liquid Effluents Batch Mode Unit 2...................................................................................... 33 Table 15, Liquid Effluents Continuous Mode Unit 2.............................................................................. 34 Table 16, Types of Solid Waste Summary Site.................................................................................... 35 Table 17, Major Nuclides..................................................................................................................... 35 Table 18, Solid Waste Disposition....................................................................................................... 36 FIGURES Figure 1, Pressurized Water Reactor (PWR) [1]..................................................................................... 9 Figure 2, Boiling Water Reactor (BWR) [2]........................................................................................... 10 Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3].................................................. 11 Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6]............. 13 ATTACHMENTS, ARERR Release Summary Tables (RG-1.21 Tables)................................................... 22, Solid Waste Information................................................................................................ 35, Meteorological Data...................................................................................................... 37

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 3 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 1.0 LIST OF ACRONYMS AND DEFINITIONS

1.

Alpha Particle (a): A charged particle emitted from the nucleus of an atom having a mass and charge equal in magnitude of a helium nucleus.

2.

BWR: Boiling Water Reactor

3.

Composite Sample: A series of single collected portions (aliquots) analyzed as one sample. The aiiquots making up the sampie are collected at time intervais that are very short compared to the composite period.

4.

Control: A sampling station in a location not likely to be affected by plant effluents due to its distance and/or direction from the Plant.

5.

Counting Error: An estimate of the two-sigma uncertainty associated with the sample results based on total counts accumulated.

6.

Curie (Ci): A measure of radioactivity; equal to 3.7 x 1010 disintegrations per second, or 2.22 x 1012 disintegrations per minute.

7.

Direct Radiation Monitoring: The measurement of radiation dose at various distances from the plant is assessed using thermoluminescent dosimeters (TLDs), optically stimulated luminescent dosimeters (OSLDs), and/or pressurized ionization chambers.

8.

Grab Sample: A single discrete sample drawn at one point in time.

9.

Indicator: A sampling location that is potentially affected by plant effluents due to its proximity and/or direction from the plant.

10.

Ingestion Pathway: The ingestion pathway includes milk, fish, drinking water and garden produce. Also sampled (under special circumstances) are other media such as vegetation or animal products when additional information about particular radionuclides is needed.

11.

ISFSI: Independent Spent Fuel Storage Installation

12.

LLD: Lower Limit of Detection. An a priori measure of the detection capability of a radiochemistry measurement based on instrument setup, calibration, background, decay time, and sample volume. An LLD is expressed as an activity concentration. The MDA is used for reporting results. LLD are specified by a regulator, such as the NRC and are typically listed in the ODCM.

13.

MDA: Minimum Detectable Activity. For radiochemistry instruments, the MDA is the a posteriori minimum concentration that a counting system detects. The smallest concentration or activity of radioactive material in a sample that will yield a net count above instrument background and that is detected with 95%

probability, with only 5% probability of falsely concluding that a blank observation represents a true signal.

14.

MDC: Minimum Detectable Concentration. Essentially synonymous with MDA for the purposes of radiological monitoring.

15.

Mean: The sum of all of the values in a distribution divided by the number of values in the distribution, synonymous with average.

16.

Microcurie (µCi): 3.7 x 104 disintegrations per second, or 2.22 x106 disintegrations per minute.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 4 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station

17.

millirem (mrem): 1/1000 rem; a unit of radiation dose equivalent in tissue.

18.

Milliroentgen (mR): 1/1000 Roentgen; a unit of exposure to X-or gamma radiation.

19.

N/A: Not Applicable

20.

NEI: Nuclear Energy Institute

21.

NRG: Nuclear Regulatory Commission

22.

ODCM: Offsite Dose Calculation Manual

23.

OSLO: Optically Stimulated Luminescence Dosimeter

24.

Protected Area: A 1 O CFR 73 security term is an area encompassed by physical barriers and to which access is controlled for security purposes. The fenced area immediately surrounding the plant and around ISFSI are commonly classified by the licensee as "Protected areas." Access to the protected area requires a security badge or escort.

25.

PWR: Pressurized Water Reactor

26.

REC: Radiological Effluent Control

27.

REMP: Radiological Environmental Monitoring Program

28.

Restricted Area: A 10 CFRR 20 defined term where access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials.

29.

TEDE: Total Effective Dose Equivalent (TEDE) means the sum of the effective dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).

30.

TLD: Thermoluminescent Dosimeter

31.

TRM: Technical Requirements Manual

32.

TS: Technical Specification

33.

Unrestricted Area: An area, access to which is neither limited nor controlled by the licensee.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 5 of 37 Company: Constellation I Plant: Byron Nuclear Generatin~ Station 2.0 EXECUTIVE

SUMMARY

Byron Clean Energy Center (BYR) Radiological Effluent Control (REC) Program was established to limit the quantities of radioactive material that may be released based on calculated radiation doses or dose rates. Dose to Members of the Public due to radioactive materials released from the plant is limited by Technical Specifications, 10 CFR 20, and by 40 CFR 190. Operational doses to the public during 2023 were calculated to be within the limits required by regulation and compared to other sources of radiation dose and pose no health hazard. These doses are summarized and compared to the regulatory limits in Section 2.1 Comparison to Regulatory Limits below.

The Annual Radioactive Effluent Release Report (ARERR) is published per REC requirements and provides data related to plant operation, including: quantities of radioactive materials released in liquid and gaseous effluents; radiation doses to members of the public; solid radioactive waste shipped offsite for processing or direct disposal; and other information as required by site licensing documents.

In 2023, the gaseous effluent dose assessments for locations from the Land Use Census showed that the critical receptor for Byron Clean Energy Center is a child.

The maximum Annual Organ Dose calculated for this receptor was 2.21 E+00 mRem, to the bone.

The maximum dose calculated to any organ due to radioactive liquid effluents was 3.0SE-02 mRem, for a child GI-Lli.

Solid radioactive waste shipped offsite for processing or direct disposal included 1.90E+02 Curies and 8.01 E+02 m3, shipped in 41 shipments.

In addition to monitoring radioactive effluents, BYR has a Radiological Environmental Monitoring Program (REMP) that monitors for levels of radiation and radioactive materials in the local environment. Data from the REMP is published in the Annual Radiological Environmental Operating Report (AREOR).

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 6 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 2.1 Comparison to Regulatory Limits During 2023 all solid, liquid, and gaseous radioactive effluents from Byron Clean Energy Center were well below regulatory limits, as summarized in Table 1, Table 2, and Table 3.

Tab!e 1, Byron C!ean Energy Center Unit 1 Dose Summary1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent I umit 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3 mrem Dose Limit, Total Body Dose 7.25E-03 9.50E-04 5.04E-03 1.85E-03 1.51 E-02 Total Body

% of Limit 4.83E-01 6.33E-02 3.36E-01 1.23E-01 5.03E-01 Liquid Effluent I umit 5mrem 5 mrem 5 mrem 5 mrem 10 mrem Dose Limit, Max Organ Dose 7.32E-03 9.89E-04 5.05E-03 2.17E-03 1.54E-02 Any Organ

% of Limit 1.46E-01 1.98E-02 1.01 E-01 4.34E-02 1.54E-01 Gaseous Effluent I Limit 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Dose Limit, Gamma Air Dose 6.22E-05 3.54E-05 3.45E-05 3.78E-05 1.70E-04 Gamma Air (Noble Gas)

% of Limit 1.24E-03 7.08E-04 6.90E-04 7.56E-04 1.70E-03 Gaseous Effluent I Limit 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Dose Limit, Beta Air Dose 2.33E-05 1.14E-05 1.43E-05 1.40E-05 6.29E-05 Beta Air (Noble Gas)

% of Limit 2.33E-04 1.14E-04 1.43E-04 1.40E-04 3.15E-04 Gaseous Effluent I Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ Dose Limit Max Organ Dose 2.19E-01 2.90E-01 2.85E-01 2.90E-01 1.09E+00 (Iodine, Tritium, Particulates with

> 8-day half-life)

% of Limit 2.92E+00 3.87E+00 3.80E+00 3.87E+00 7.27E+00 1 Table 1 demonstrates compliance with 10 CFR Part 50, App I Limits.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 7 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 2, Byron Clean Energy Center Unit 2 Dose Summary2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent I umit 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3 mrem Dose Limit, Total Body Dose 7.25E-03 9.50E-04 5.04E-03 1.85E-03 1.51 E-02 Total Body

% of Limit A A~~J)1 6.33E-02

-, -.ac n1 1 '"l':>C /"\\1 5.03E-01

~

....,VI..-

'1,J I v.vuL--u 1 I.£.,.JL-u I Liquid Effluent I umit 5 mrem 5 mrem 5 mrem 5 mrem 10 mrem Dose Limit, Max Organ Dose 7.32E-03 9.89E-04 5.05E-03 2.17E-03 1.54E-02 Any Organ

% of Limit 1.46E-01 1.98E-02 1.01 E-01 4.34E-02 1.54E-01 Gaseous Effluent I Limit 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Dose Limit, Gamma Air Dose 4.46E-05 1.69E-05 2.03E-05 1.76E-05 9.93E-05 Gamma Air (Noble Gas)

% of Limit 8.92E-04 3.38E-04 4.06E-04 3.52E-04 9.93E-04 Gaseous Effluent I Limit 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Dose Limit, Beta Air Dose 1.85E-05 4.S0E-06 9.54E-06 7.65E-06 4.05E-05 Beta Air (Noble Gas)

% of Limit 1.85E-04 4.S0E-05 9.54E-05 7.65E-05 2.03E-04 Gaseous Effluent I Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ Dose Limit Max Organ Dose 2.98E-01 2.SSE-01 3.02E-01 2.31 E-01 1.12E+O0 (Iodine, Tritium, Particulates with

> 8-day half-life)

% of Limit 3.97E+00 3.84E+00 4.03E+00 3.0SE+00 7.47E+00 2 Table 2 demonstrates compliance with 10 CFR Part 50, App. I Limits.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 8 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 3, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for BYR3 Whole Body Thyroid Max Other Organ Gaseous4 4.56E-01 4.56E-01 2.21 E+00 Liquid 3.02E-02 3.02E-02 3.08E-02 iSFSi 0.00E+00 0.00E+00 0.00E+00 Total Site Dose 4.86E-01 4.86E-01 2.24E+00 Total w/Other Nearby Facility5 4.86E-01 4.86E-01 2.24E+00 Limit 25 mrem 75 mrem 25 mrem

% of Limit 1.95E+00 6.48E-01 8.97E+00 3 Table 3 is a summation of Units to show compliance with 40 CFR Part 190 Limits.

4 Gaseous dose values in Table 3 include organ dose from Noble Gas, Iodine, Tritium, C-14, and particulates.

5 Other fuel cycle sources within 5 miles of the site are considered in this analysis.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 9 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station

3.0 INTRODUCTION

3.1 About Nuclear Power Commercial nuclear power plants are generally classified as either Boiling Water Reactors (BWRs) or Pressurized Water Reactors (PWRs), based on their design. A BWR includes a single coolant system where water used as reactor coolant boils as it passes through the core and the steam generated is used to turn the turbine generator for power production. A PWR, in contrast, includes two separate water systems: radioactive reactor coolant and a secondary system. Reactor coolant is maintained under high pressure, preventing boiling. The high-pressure coolant is passed through a heat exchanger called a steam generator where the secondary system water is boiled, and the steam is used to turn the turbine generator for power production.

Containment Struchre Figure 1, Pressurized Water Reactor (PWR) [1]

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 10 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 3.1 (Continued)

Containment Structure Figure 2, Boiling Water Reactor (BWR) [2]

Electricity is generated by a nuclear power plant similarly to the way that electricity is generated at other conventional types of power plants, such as those powered by coal or natural gas. Water is boiled to generate steam; the steam turns a turbine that is attached to a generator and the steam is condensed back into water to be returned to the boiler. What makes nuclear power different from these other types of power plants is that the heat is generated by fission and decay reactions occurring within and around the core containing fissionable uranium (U-235).

Nuclear fission occurs when certain nuclides (primarily U-233, U-235, or Pu-239) absorb a neutron and break into several smaller nuclides (called fission products) as well as producing some additional neutrons.

Fission results in production of radioactive materials including gases and solids that must be contained to prevent release or treated prior to release. These effluents are generally treated by filtration and/or hold-up prior to release. Releases are generally monitored by sampling and by continuously indicating radiation monitors. The effluent release data is used to calculate doses in order to ensure that dose to the public due to plant operation remains within required limits.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 11 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 3.2 About Radiation Dose Ionizing radiation, including alpha, beta, and gamma radiation from radioactive decay, has enough energy to break chemical bonds in tissues and result in damage to tissue or genetic material. The amount of ionization that will be generated by a given exposure to ionizing radiation is quantified as dose. Radiation dose is generally reported in units of millirem (mrem) in the US.

Terrestrial (background)-,

(3%)

Computed.. /

tomograpliy (medical)

(24%)

Nuclear medicine (medical)

{12%)

Space (background)

(5%)

lnterventional fluoroscopy.

(medical)

(7%)

Radon & thoron (background)

(37%)

.. Industrial

(<0.1%)

Occupational

(<0.1%)

Consumer Conventional radiography/fluoroscopy

{medical)

(5%)

(2%)

Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3]

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 12 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 3.2 (Continued)

The National Council on Radiation Protection (NCRP) has evaluated the population dose for the US and determined that the average individual is exposed to approximately 620 mrem per year [3]. There are many sources for radiation dose, ranging from natural background sources to medical procedures, air travel, and industrial processes. Approximately half (310 mrem) of the average exposure is due to natural sources of radiation including exposure to radon, cosmic radiation, and internal radiation and terrestrial due to naturally occurring radionuclides. The remaining 310 mrem of exposure is due to man-made sources of exposure, with the most significant contributors being medical (48% of total mrem per year) due to radiation used in various types of medical scans and treatments. Of the remaining 2%

of dose, most is due to consumer activities such as air travel, smoking cigarettes, and building materials. A small fraction of this 2% is due to industrial activities including generation of nuclear power.

Readers that are curious about common sources and effects of radiation dose that they may encounter can find excellent sources of information from the Health Physics Society, including the Radiation Fact Sheets [4], and from the US Nuclear Regulatory Commission website [5).

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 13 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 3.3 About Dose Calculation Concentrations of radioactive material in the environment resulting from plant operations are very small and it is not possible to determine doses directly using measured activities of environmental samples. To overcome this, dose calculations based on measured activities of effluent streams are used to model the dose impact for Members of the Public due to plant operation and effluents. There are several mechanisms that can result in dose to Members of the Public, including: Ingestion of radionuclides in food or water; Inhalation of radionuclides in air; Immersion in a plume of noble gases; and Direct Radiation from the ground, the plant or from an elevated plume.

0 0

~c Marine produc?s O

Radionuclides

...... : Behavior of radionuclides Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6]

Each plant has an Offsite Dose Calculation Manual (ODCM) that specifies the methodology used to obtain the doses in the Dose Assessment section of this report.

The dose assessment methodology in the ODCM is based on NRG Regulatory Guide 1.109 [7] and NUREG-0133 [8]. Doses are calculated by determining what the nuclide concentration will be in air, water, on the ground, or in food products based on plant effluent releases. Release points are continuously monitored to quantify what concentrations of nuclides are being released. For gaseous releases meteorological data is used to determine how much of the released activity will be present at a given location outside of the plant either deposited onto the ground or in gaseous form.

Intake patterns and nuclide bio-concentration factors are used to determine how much activity will be transferred into animal milk or meat. Finally, human ingestion factors and dose factors are used to determine how much activity will be consumed and how much dose the consumer will receive. Inhalation dose is calculated by determining the concentration of nuclides and how much air is breathed by the individual.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 14 of 37 Company: Constellation I Plant: Byron Nuclear GeneratinQ Station 3.3 (Continued)

For liquid releases, dilution and mixing factors are used to model the environmental concentrations in water. Drinking water pathways are modeled by determining the concentration of nuclides in the water at the point where the drinking water is sourced (e.g., taken from wells, rivers, or lakes). Fish and invertebrate pathways are determined by using concentration at the release point, bioaccumulation factors for the fish or invertebrate and an estimate of the quantity of fish consumed.

Each year a Land Use Census is performed to determine what potential dose pathways currently exist within a five-mile radius around the plant, the area most affected by plant operations. The Annual Land Use Census identifies the locations of vegetable gardens, nearest residences, milk animals and meat animals. The data from the census is used to determine who is the likely to be most exposed to radiation dose as a result of plant operation.

There is significant uncertainty in dose calculation results, due to modeling dispersion of material released and bioaccumulation factors, as well as assumptions associated with consumption and land-use patterns. Even with these sources of uncertainty, the calculations do provide a reasonable estimate of the order of magnitude of the exposure. Conservative assumptions are made in the calculation inputs such as the number of various foods and water consumed, the amount of air inhaled, and the amount of direct radiation exposure from the ground or plume, such that the actual dose received are likely lower than the calculated dose. Even with the built-in conservatism, doses calculated for the maximum exposed individual due to plant operation are a very small fraction of the annual dose that is received due to other sources. The calculated doses due to plant effluents, along with REMP results, serve to provide assurance that radioactive effluents releases are not exceeding safety standards for the environment or people living near the plant.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 15 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 4.0 4.1 DOSE ASSESSMENT FOR PLANT OPERATIONS Regulatory Limits Regulatory limits are detailed in station licensing documents such as the plant Technical Specifications and the Offsite Dose Calculation Manual (ODCM). These documents contain the limits to which BYR must adhere. BYR drives to maintain the philosophy to keep dose "as low as is reasonably achievable" (ALARA) and actions are taken to reduce the amount of radiation released to the environment. Liquid and gaseous release data show that the dose from BYR is well below the ODCM limits.

The instantaneous concentration of liquid radioactive material released shall be limited to ten times the concentration specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the total concentration released shall be limited to 2.0 x 10-4 microcuries/mL.

The annual whole body, skin and organ dose was computed using the 2023 source term using the dose calculation methodology provided in the ODCM. The calculated doses due to gaseous effluents are used to demonstrate compliance with offsite dose limits are presented in Table 1, Byron Clean Energy Center Unit 1 Dose Summary, Table 1, Byron Clean Energy Center Unit 1 Dose Summary, and Table 3, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for BYR.

4.2 Regulatory Limits for Gaseous Effluent Doses:

1.

Fission and activation gases:

a.

Noble gases dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

1)

Less than or equal to 500 mrem/year to the total body

2)

Less than or equal to 3000 mrem/year to the skin

b.

Noble gas air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the site boundary shall be limited to the following:

1)

Quarterly a)

Less than or equal to 5 mrads gamma b)

Less than or equal to 10 mrads beta

2)

Yearly a)

Less than or equal to 10 mrads gamma b)

Less than or equal to 20 mrads beta

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 16 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 4.2 (Continued) 4.3

2.

Iodine, tritium, and all radionuclides in particulate form with half-lives greater than 8 days.

a.

The dose rate for iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to areas at and beyond the site boundary shall be limited to the following:

1)

Less than or equal to 1500 mrem/yr to any organ

b.

The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 DAYS in gaseous effluents released, from each reactor unit, to areas at and beyond the site boundary shall be limited to the following:

1)

Quarterly a)

Less than or equal to 7.5 mrem to any organ

2)

Yearly a)

Less than or equal to 15 mrem to any organ Regulatory Limits for Liquid Effluent Doses

1.

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to unrestricted areas shall be limited to the following:

a.

Quarterly

1)

Less than or equal to 1.5 mrem total body

2)

Less than or equal to 5 mrem critical organ

b.

Yearly

1)

Less than or equal to 3 mrem total body

2)

Less than or equal to 10 mrem critical organ

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 17 of 37 Company: Constellation

/ Plant: Byron Nuclear Generating Station 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public 5.0 5.1 5.1.1 5.2 5.2.1

1.

Total Dose (40 CFR 190)

a.

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC in the unrestricted area due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to the following:

1)

Less than or equal to 25 mrem, Total Body or any Organ except Thyroid.

2)

Less than or equal to 75 mrem, Thyroid.

SUPPLEMENTAL INFORMATION Gaseous Batch Releases BYR Site

1. Number of Batch Releases

2. Total duration of batch releases

3. Maximum batch release duration

4. Average batch release duration

5. Minimum batch release duration Liquid Batch Releases BYR Site

1. Number of Batch Releases

2. Total duration of batch releases

3. Maximum batch release duration

4. Average batch release duration

5. Minimum batch release duration

6. Avg stream flow during periods of release of liquid effluent into a flowing stream Units minutes minutes minutes minutes Units minutes minutes minutes minutes Ft3/sec

average stream flow in calculating dose.

Quarter Quarter 1

2 92 76 1.93E+04 5.66E+03 3.80E+03 2.16E+02 2.10E+02 7.45E+01 4.00E+00 1.90E+01 Quarter Quarter 1

2 27 11 7.55E+03 1.17E+03 7.96E+02 2.39E+02 2.80E+02 1.07E+02 5.50E+01 3.90E+01 Quarter Quarter 3

4 7q 95 6.81E+03 1.62E+04 3.73E+02 3.21E+03 8.96E+01 1.70E+02 5.70E+01 1.80E+01 Quarter Quarter 3

4 21 22 6.55E+03 2.22E+03 4.87E+02 2.95E+02 3.12E+02 1.01 E+02 1.46E+02 4.70E+01 Annual 339 4.80E+04 3.80E+03 1.42E+02 4.00E+00 Annual 81 1.75E+04 7.96E+02 2.16E+02 3.90E+01

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 18 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 5.3 Abnormal Releases 5.3.1 Gaseous Abnormal Releases Number of releases 2

Total activity released 8.82E-05 Ci One release out of both Unit 1 and Unit 2 which lasted for 69 minutes.

5.3.2 Liquid Abnormal Releases 5.4 5.5 5.6 5.7 Number of releases 0

Total activity released 0 Ci Land Use Census Changes No changes to land use census in 2023.

Meteorological Data In 2023, Byron Generating Station met the 90% data accumulation requirement. Joint Frequency Distribution tables are available on site per request.

Effluent Radiation Monitors Out of Service Greater Than 30 Days No effluent radiation monitors were out of service for greater than 30 days in 2023.

Offsite Dose Calculation Manual (ODCM) Changes No ODCM changes were made in 2023.

5.8 Process Control Program (PCP) Changes No PCP changes were made in 2023.

5.9 Radioactive Waste Treatment System Changes No waste treatment system changes were made in 2023.

5.10 Other Supplemental Information 5.10.1 Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program There were no irradiated fuel shipments during the 2023 reporting period. An Independent Spent Fuel Storage Installation (ISFSI) campaign began in 2010 when used fuel was removed from the Spent Fuel Pool (SFP), placed into six (6) casks, each containing 32 fuel bundles, and transferred to an outdoor storage pad. No additional casks were placed on the pad in 2011. In 2012, eight (8) additional casks were placed on the pad for a total of fourteen (14) casks. No additional casks were

Annual Radioactive Effluent Release Report I YEAR: 2023 I

Page 19 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station placed on the pad in 2013 or 2014. In 2015, six (6) additional casks were placed on the pad for a total of twenty (20) casks. In 2016, six (6) additional casks were placed on the pad No additional casks were placed on the pad in 2017. In 2018, five (5) additional casks were placed on the pad In 2019, six (6) additional casks were placed on the pad. In 2020, no additional casks were added. In 2021. six (6) additional casks were placed on the pad In 2022, seven (7) additional casks were placed on the pad for a total of fifty (50). In 2023, no additional casks were placed on the pad. Prior to the first !SFSI campaign, additional dosimeters were placed at the site boundary nearest to the storage pad (in between the pad and the nearest resident) for the purpose of measuring any potential offsite dose to the public from the storage pad Since dosimeters were placed, data from the dosimeters, when compared to the existing environmental dosimeters in the surrounding area, have shown no statistical difference. As a result, there is currently no offsite dose contribution from the ISFSI facility or any other on-site storage facility, including the Dry Active Waste (DA\\fv~ Building and the Old Steam Generator (OSG) Storage Building, as evidenced by dosimetry data that is indistinguishable from the existing environmentai dosimeters.

5.10.2 Carbon-14 Carbon-14 (C-14) is a naturally occurring radionuclide with a 5,730-year half-life.

Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Nuclear power plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.

In accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," the NRC recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate. Carbon-14 production and release estimates were calculated using active core coolant mass, average neutron flux by energy and reactor coolant nitrogen concentrations to determine Carbon-14 generation based upon an effective full power year. The estimated generation for Byron Clean Energy Center during 2023 was 8.46E+00 Curies.

Public dose estimates were performed using methodology from the ODCM which is based on Regulatory Guide 1.109 methodology. C-14 is accounted for in the gaseous dose is included in dose calculation results in Table 3.

5.10.3 Errata/Corrections to Previous ARERRs None

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 20 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM Byron Clean Energy Center has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative -

Final Guidance Document [9]. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater in order to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning.

In 2023, fourteen (14) monitoring wells were sampled in total. Groundwater samples were obtained in March, June, August, and October for tritium. In addition, Sr-89 and Sr-90 analyses were performed on select wells for the samples obtained in June in accordance with site procedures and the Nuclear Energy Institute (NEI) 07-07, Groundwater Protection Initiative. None of these samples showed detectable concentrations of Sr-89/Sr-90. Two wells contained levels of tritium above the lower limit of detection (LLD) of 200 pCi/L. They were AR-4 (265 pCi/L in June, 252 pCi/L in Oct) and AR-11 (420 pCi/L in June, 380 pCi/L in October). Wells AR-4 and AR-11 are near the Circulating Water Slowdown piping, where historical leakage through vacuum breakers was known to have occurred. These wells have exhibited an overall decreasing trend since 2006. Tritium was not detected in well AR-7, located on-site just west of plant structures, in 2023. All groundwater well sample results are well below the drinking water standard of 20,000 pCi/L tritium. None of the site groundwater wells are used for drinking water, however, should any of the water in these aquifers migrate to off-site wells used for drinking, the off-site dose consequence from tritium present in these wells would be negligible. AMO Environmental Decisions, a nuclear utility groundwater consultant, has reviewed the 2023 RGPP data and concluded there is no evidence of new or ongoing tritium leak(s) at the site.

Comprehensive report of the groundwater and drinking samples can be found in the AREOR.

6.1 Voluntary Notification During 2023, Byron Clean Energy Center did not make a voluntary NEI 07-07 notification to State/Local officials, NRC, and to other stakeholders required by site procedures.

Annual Radioactive Effluent Release Report I YEAR: 2023 I

Page 21 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 7.0 BIBLIOGRAPHY

[1] Nuclear Regulatory Commission, 30 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-pwr.html. [Accessed October 2020].

[2] Nuclear Regulatory Commission, 25 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-bwr.html. [Accessed October 2020].

[3] "NCRP Report No. 160 - Ionizing Radiation Exposure of the Population of the United States,"

National Council on Radiation Protection and Measurements, Bethesda, MD, 2009.

[4] Health Physics Society, [Online]. Available: http://hps.org/hpspublications/radiationfactsheets.html.

[Accessed 2020].

[5] "NRC Resource Page," [Online]. Available: http://www.nrc.gov/about-nrc/radiation.html. [Accessed 10 November 2020].

[6] "Japan Atomic Energy Agency," 06 November 2020. [Online]. Available:

https://www.jaea.go.jp/english/04/ntokai/houkan/houkan_02.html.

[7] "Regulatory Guide 1.109 - Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50, Appendix I," Nuclear Regulatory Commission, Ocotober, 1977.

[8] "NUREG-0133 - Preparation of Effluent Technical Specifications for Nuclear Power Plants,"

Nuclear Regulatory Commission, 1987.

[9] "NEI 07 Industry Ground Water Protection Initiative -

Final Guidance Document, Rev. 1,"

Nuclear Energy Institute, Washington, D.C., 2019.

[1 O] "10 CFR 50 - Domestic Licensing of Production and Utilization Facilities," US Nuclear Regulatory Commission, Washington, DC.

[11] "40 CFR 190 - Environmental Radiation Protection Standards for Nuclear Power Operation," US Environmental Protection Agency, Washington, DC.

[12] "10 CFR 20 - Standards for Protection Against Radiation," US Nuclear Regulatory Commission, Washington, DC.

[13] "40 CFR 141 - National Primary Drinking Water Regulations," US Environmental Protection Agency, Washington, DC..

[14] "NUREG-0324 - XOQDOQ, Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," Nuclear Regulatory Commission, September, 1977.

[15] "NUREG-1301 - Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors," Nuclear Regulatory Commission, April 1991.

[16] "NUREG-1302 - Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors," Nuclear Regulatory Commission, April 1991.

[17] "Regulatory Guide 4.13 - Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, Revision 2," Nuclear Regulatory Commision, June, 2019.

[18] "Regulatory Guide 4.15 - Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) -- Effluent Streams and the Environment,"

Nuclear Regulatory Commission, July, 2007.

Annual Radioactive Effluent Release Report l YEAR: 2023 l Page 22 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station, ARERR Release Summary Tables (RG-1.21 Tables) 1.0 GASEOUS EFFLUENTS Table 4, Gaseous Effluents Summation of All Releases Unit 1 6 A. Fission & Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual

1. Total Release Ci 2.15E-01 1.01 E-01 1.70E-01 1.36E-01 6.22E-01

2. Average release rate for

µCi/sec 2.76E-02 1.28E-02 2.14E-02 1.71 E-02 the period B. Iodine

1. Total Iodine - 131 Ci

<LLD

2. Average release rate for

~1Ci/sec

<LLD

<LLD the period C. Particulates

1. Particulates with half-lives Ci

<LLD

> 8 days

2. Average release rate for

~1Ci/sec

<LLD

<LLD the period D. Tritium 1. Total Release Ci 5.61E+00 3.63E+00 1.66E+00 3.43E+00 1.43E+01

2. Average release rate for

~tCi/sec 1.06E-01 4.62E-01 2.09E-01 4.32E-01 4.53E-01 the period E. Gross Alpha

1. Total Release Ci

<LLD

2. Average release rate for

~1Ci/sec

<LLD

<LLD the period F. Carbon-14

1. Total Release Ci 8.28E-01 1.11 E+00 1.10E+00 1.12E+00 4.16E+0O

2. Average release rate for

µCi/sec 1.06E-01 1.41 E-01 1.39E-01 1.41 E-01 1.32E-01 the period 6 % of limit is provided in Table 1, Byron Clean Energy Center Unit 1 Dose Summary

Annual Radioactive Effluent Release Report l YEAR: 2023 l Page 23 of 37 Company: Constellation

! Plant: Byron Nuclear Generatin~ Station Table 5, Gaseous Effluents Summation of All Releases Unit 2 7 A. Fission & Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual

1. Total Release Ci 1.86E-01 3.38E-02 1.26E-01 8.25E-02 4.28E-01

2. Average release rate for

~LCilsec 2.39E-02 4.30E-03 1.59E-02 1.04E-02 5.45E-02 the period B. Iodine

1. Total Iodine -131 Ci

<LLD

2. Average release rate for

~LCilsec NIA NIA NIA NIA NIA the period C. Particulates

1. Particulates with half-lives Ci

<LLD

> 8 days

2. Average release rate for

~LCilsec NIA NIA NIA NIA NIA the period D. Tritium

1. Total Release Ci 2.31 E+01 1.10E+01 1.71E+01 1.21 E+01 6.33E+02

2. Average release rate for

~LCilsec 2.97E+00 1.40E+00 2.15E+00 1.52E+00 8.04E+00 the period E. Gross Alpha

1. Total Release Ci

<LLD

2. Average release rate for

~LCilsec NIA NIA N/A NIA N/A the period F. Carbon-14

1. Total Release Ci 1.13E+00 1.10E+00 1.17E+00 8.98E-01 4.30E+0O

2. Average release rate for

~LCi/sec 1.45E-01 1 A0E-01 1.47E-01 1.13E-01 5.45E-01 the period 7 % of limit is provided in Table 1, Byron Clean Energy Center Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 24 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 6, Gaseous Effluents - Mixed Level Release Batch Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci 1.01 E-01 6.41 E-02 5.97E-02 6.53E-02 2.90E-01 Kr-85m Ci 1.88E-03

<LLD

<LLD 1.97E-04 2 08E-03 Kr-87 Ci 2.27E-04

<LLD

<LLD 2.27E-04 Kr-88 Ci 2.19E-03

<LLD

<LLD 4.30E-05 2.23E-03 Kr-131 m Ci 7.32E-05

<LLD 6.45E-05

<LLD 1.38E-04 Xe-133m Ci 2.90E-03

<LLD 6.28E-05 1.03E-03 3.99E-03 Xe-133 Ci 6.74E-02 3.61 E-02 2.77E-02 5.75E-02 1.89E-01 Xe-135 Ci 3.47E-02 4.06E-04 2.92E-04 1.19E-02 4.73E-02 Total for Period Ci 2.11E-01 1.01 E-01 8.78E-02 1.36E-01 5.35E-01 Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3 Ci 2.20E-01 7.05E-02 1.11 E-01 1.24E-01 5.26E-01 Gross Alpha Alpha Ci

<LLD

<LLD Carbon-14 C-14 Ci

<LLD

<LLn

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 25 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 7, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD Xe-133m Ci

<LLD

<LLD Xe-133 Ci 4.17E-03

<LLD 8.24E-02

<LLD 8.66E-02 Xe-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium I

H-3 I Ci I 5.39E+00 3.56E+00 1.55E+00 3.31E+00 E+01 Gross Alpha Alpha Ci

<LLD

<LLD Carbon-14 C-14 Ci 8.28E-01 1.11 E+00 1.10E+00 1.12E+00 4.17E+00

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 26 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 8, Gaseous Effluents - Mixed Level Release Batch Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released l~nGases Ar-41 Ci 6.85E-02 3.11 E-02 3.41 E-02 2.84E-02 1.62E-01 Kr-85m Ci 1.88E-03

<LLD

<LLD 1.97E-04 2.08E-03 Kr-87 Ci 2.27E-04

<LLD

<LLD 2.27E-04 Kr-88 Ci 2.19E-03

<LLD

<LLD 4.30E-05 2.23E-03 Xe-131m Ci 7.32E-05

<LLD 6.45E-05

<LLD 1.38E-04 Xe-133m Ci 2.90E-03

<LLD 6.28E-05 1.03E-03 3.99E-03 Xe-133 Ci 7.10E-02 2.67E-03 9.39E-03 4.10E-02 1.24E-01 Xe-135 Ci 3.47E-02 3.89E-05 1.21 E-04 1.18E-02 4.67E-02 Total for Period Ci 1.81 E-01 3.38E-02 4.38E-02 8.25E-02 3.42E-01 Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3 Ci II 0 "6E-02 9.09E-02 6.56E-02 1.13E-01 3.62E-01 II Gross Alpha Alpha Ci

<LLD

<LLD Carbon-14 C-14 Ci

<LLD

<LLn

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 27 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 9, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Kr-131m Ci

<LLD

<LLD Xe-133m Ci

<LLD

<LLD Xe-133 Ci 4.17E-03

<LLD 8.24E-02

<LLD 8.66E-02 Xe-135 Ci

<LLD

<LLD Total for Period Ci 4.17E-03

<LLD 8.24E-02

<LLD 8.GGE-02 Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium I

H-3 I Ci II 2.30E+01 I 1.09E+01 I

1.70E+01 I 1.20E+01 II 6.29E+01 I

I Gross Alpha I

I Alpha I Ci II

<LLD I

<LLD II

<LLD I

Carbon-14 I

C-14 I Ci II 1.13E+00 I 1.10E+00 I 1.17E+00 I 8.98E-01 II 4.30E+00 I

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 28 of 37 Company: Constellation I Plant: Byron Nuclear Generatin~ Station 2.0 LIQUID EFFLUENTS Table 40, Liquid Effluents - Summation of All Releases Unit 1 8 A. Fission & Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Products

1. Total Release Ci 2.40E-03 7.05E-04 6.61E-04 4.98E-03 8.76E-03

2. Average diluted

µCi/ml 6.63E-10 2.87E-10 1.79E-10 2.0SE-09 3.21 E-09 concentration B. Tritium

1. Total Release Ci 7.86E+02 9.87E+01 4.94E+02 1.87E+02 1.57E+03

2. Average diluted

~LCilmL 2.17E-04 4.03E-05 1.34E-04 7.84E-05 4.?0E-04 concentration C. Dissolved & Entrained Gases

1. Total Release Ci 4.45E-04

<LLD

<LLD 1.55E-04 6.00E-04

2. Average diluted

µCi/ml 1.23E-10 N/A N/A 6.49E-11 1.85E-10 concentration D. Gross Alpha Activity

1. Total Release Ci 4.45E-04

<LLD

<LLD 1.55E-04 6.00E-04 E. Volume of Waste Liters 3.62E+09 2.45E+09 3.69E+09 2.39E+09 1.22E+10 Released (prior to dilution)

F. Volume of Dilution Water Liters 7.24E+09 4.90E+09 7.38E+09 4.77E+09 2.43E+10 Used During Period 8 % of limit is provided in Table 1, Byron Clean Energy Center Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 29 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 11, Liquid Effluents - Summation of All Releases Unit 2 9 A Fission & Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Products

1. Total Release Ci 2.40E-03 7.0SE-04 6.61 E-04 4.98E-03 8.76E-03

2. Average diluted

~tCi/mL 6.63E-10 2.87E-10 1.79E-10 2.0SE-09 3.21 E-09 concentration B. Tritium

1. Total Release Ci 7.86E+02 9.87E+01 4.94E+02 1.87E+02 1.57E+03

2. Average diluted

~tCi/mL 2.17E-04 4.03E-05 1.34E+04 7.84E-05 4.?0E-04 concentration C. Dissolved & Entrained Gases 1 Total Release Ci 4.45E-04

<LLD

<LLD 1.55E-04 6.00E-04

2. Average diluted

~tCi/mL 1.23E-10 N/A N/A 6.49E-11 1.85E-10 concentration D. Gross Alpha Activity

1. Total Release Ci 4.45E-04

<LLD

<LLD 1.55E-04 6.00E-04 E. Volume of Waste Liters 3.62E+09 2.45E+09 3.69E+09 2.39E+09 1.22E+10 Released (prior to dilution)

F. Volume of Dilution Liters 7.24E+09 4.90E+09 7.38E+09 4.77E+09 2.43E+10 Water Used During Period 9 % of limit is provided in Table 1, Byron Clean Energy Center Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 30 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Error Analysis The following is an estimate of the errors associated with effluent monitoring and analysis. The estimate is calculated using the square root of the sum of the squares methodology.

1.

Gaseous Effluents Qme=3.33%

RM=N/A ECe=5%

Stdcse/Smplcse=5%

me=N/A Total error= 7.8%

2.

Liquid Effluents Qme=3.33%

RM=N/A ECe=N/A Stdcse/Smplcse=5%

qme=2.22%

Total error= 6.4%

3.

Waste Resin Qme=10.0%

RM=N/A ECe=5%

Stdcse/Smplcse=5%

me=1.0%

Total error= 12.3%

4.

DAW, Mechanical Filters, and Contaminated Metal Qme=10.0%

RM=N/A ECe=N/A Stdcse/Smplcse=5%

qme=N/A Instrument calibration error= 10%

Total error= 11.2%

Orne= the process quantity measurement error associated with the release point (e.g. flow, level measurements)

RM = error associated with the radiation monitor used in quantifying releases through the release point ECe = error associated with the collection efficiency of the sample media Stdcse = one-sigma counting error associated with the counting instrument of interest Smplcse = one-sigma counting error associated with a sample of a given geometry that is used for the release point of interest qme = sample quantity measurement error associated with the sample of interest

Annual Radioactive Effluent Release Report I YEAR: 2023

[

Page 31 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 52, Liquid Effluents Batch Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission and Activation Products Te-123m Ci 2.64E-05

<LLD

<LLD 6.25E-05 8.89E-05 Cr-51 Ci 1.69E-04 8.17E-05

<LLD 2.56E-04 5.07E-04 Mn-54 Ci 1.39E-05

<LLD 1.16E-05 2.12E-06 2.76E-05 Fe-59 Ci

<LLD

<LLD 3.13E-06 3.13E-06 Co-57 Ci 9.74E-06

<LLD

<LLD 9.74E-06 Co-58 Ci 1.09E-03 3.89E-04 1.10E-04 2.77E-04 1.87E-03 Co-60 Ci 6.37E-04 1.23E-04 4.05E-04 1.47E-04 1.31 E-03 Br-82 Ci 1.22E-06

<LLD

<LLD 1.22E-06 Nb-95 Ci 7.85E-06 7.11E-06 1.00E-06 2.93E-06 1.89E-05 Ru-105 Ci

<LLD 3.90E-06

<LLD

<LLD 3.90E-06 Sb-124 Ci

<LLD 1.26E-05 9.74E-06

<LLD 2.24E-05 Sb-125 Ci 6.65E-06 8.78E-05 1.23E-04

<LLD 2.1 SE-04 Te-125m Ci 3.99E-04

<LLD

<LLD 4.04E-03 4.44E-03 Te-132 Ci 3.70E-05

<LLD

<LLD 2.29E-05 5.99E-05 1-132 Ci 2.14E-06

<LLD

<LLD 1.64E-04 1.67E-04 Total for Period Ci 2.40E-03 7.0SE-04 6.61 E-04 4.98E-03 8.75E-03 Tritium H-3 Ci 5.81E+02 8.03E+01 4.73E+02 1.58E+02 1.29E+03 Gross Alpha Alpha Ci

<LLD

<LLD Entrained Gases Ar-41 Ci

<LLD

<LLD 1.21 E-06 1.21 E-06 Xe-133 Ci 4.41 E-04

<LLD

<LLD 1.54E-04 5.95E-04 Xe-135 Ci 4.17E-06

<LLD

<LLD 4.17E-06 Total for Period Ci 4.45E-04

<LLD

<LLD 1.55E-04 6.00E-04

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 32 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 63, Liquid Effluents Continuous Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission and Activation Products Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Ag-110m Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3 Ci 2.04E+02 1.85E+01 2.12E+01 2.97E+01 2.74E+02 Gross Alpha Alpha Ci

<LLD

<LLD Entrained Gases Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 33 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 74, Liquid Effluents Batch Mode Unit 2 Radionuclide Untts I Quarter 1 I

Quarter 2 I

Quarter 3 I

Quarter 4 I Total for year Released Fission and Activation Products Te-123m Ci 2.64E-05

<LLD

<LLD 6.25E-05 I

8.89E-05 I

Cr-51 Ci 1.69E-04 8.17E-05

<LLD 2.56E-04 5.0?E-04 Mn-54 Ci 1.39E-05

<LLD 1.16E-05 2.12E-06 2.76E-05 Fe-59 Ci

<LLD

<LLD 3.13E-06 3.13E-06 Co-57 Ci 9.74E-06

<LLD

<LLD 9.74E-06 Co-58 Ci 1.09E-03 3.89E-04 1.10E-04 2.77E-04 1.87E-03 Co-60 Ci 6.37E-04 1.23E-04 4.0SE-04 1.47E-04 1.31 E-03 Br-82 Ci 1.22E-06

<LLD

<LLD 1.22E-06 Nb-95 Ci 7.85E-06 7.11E-06 1.00E-06 2.93E-06 1.89E-05 Ru-105 Ci

<LLD 3.90E-06

<LLD

<LLD 3.90E-06 Sb-124 Ci

<LLD 1.26E-05 9.74E-06

<LLD 2.24E-05 Sb-125 Ci 6.65E-06 8.78E-05 1.23E-04

<LLD 2.18E-04 Te-125m Ci 3.99E-04

<LLD

<LLD 4.04E-03 4.44E-03 Te-132 Ci 3.?0E-05

<LLD

<LLD 2.29E-05 5.99E-05 1-132 Ci 2.14E-06

<LLD

<LLD 1.64E-04 1.67E-04 Total for Period Ci 2.40E-03 7.0SE-04 6.61E-04 4.98E-03 8.75E-03 Tritium H-3 Ci 5.81E+02 8.03E+01 4.73E+02 1.58E+02 1.29E+03 Gross Alpha Alpha Ci

<LLD

<LLD Entrained Gases Ar-41 Ci

<LLD

<LLD 1.21 E-06 1.21 E-06 Xe-133 Ci 4.41 E-04

<LLD

<LLD 1.54E-04 5.95E-04 Xe-135 Ci 4.17E-06

<LLD

<LLD 4.17E-06 Total for Period Ci 4.45E-04

<LLD

<LLD 1.55E-04 6.00E-04

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 34 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station Table 85, Liquid Effluents Continuous Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission and Activation Products Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Ag-110m Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3 Ci 2.04E+02 1.85E+01 2.12E+01 2.97E+01 2.74E+02 Gross Alpha Alpha Ci I

<LLD I

<LLD II

<LLD I

Entrained Gases Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 35 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station, Solid Waste Information 1.0 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Table 16, Types of Solid Waste Summary Site Total Volume Total Activity Types of Waste (m3)

(Ci)

a. Spent resins, filter sludqes, evaporator bottoms, etc.

1.60E+02 1.89E+02

b. Dry compressible waste, contaminated equip, etc.

4.96E+02 9 00E-01

c. Irradiated components, control rods, etc.

0.00E+00 0.00E+00

d. Other (describe) 1.45E+02 4.88E-02 Est Total Error

(%)

25 25 25 25 2.0 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY WASTE TYPE) ONLY >1%

ARE REPORTED. [NOTE 1)

Table 97, Major Nuclides Major Nuclide Composition Curies

a. Spent resins, filter slud~es, evaporator bottoms, etc.

Ni-63 42.31 7.22E+01 Co-60 22.72 4.01 E+01 Fe-55 14.94 2.83E+01 H-3 10.91 2.06E+01 Co-58 3.43 6.49E+00 Mn-54 3.05 5.78E+00

b. Dry compressible waste, contaminated equip, etc.

Co-60 24.85 2.24E-01 Fe-55 20.35 1.83E-01 Cr-51 18.60 1.67E-01 Co-58 10.44 9.39E-02 Ni-63 9.79 8.80E-02 H-3 7.76 6.98E-02 Nb-95 2.80 2.52E-02 Zr-95 1.80 1.62E-02 Sb-125 1.52 1.36E-02 Mn-54 1.33 1.20E-02

c. Irradiated components, control rods, etc.

N/A N/A

d. Other (describe)

Co-60 28.30 1.38E-02 Fe-55 22.87 1.12E-02 Cr-51 15.04 7.33E-03 Co-58 11.36 5.54E-03 Ni-63 10.95 5.34E-03 Nb-95 3.23 1.58E-03 H-3 2.47 1.21 E-03 Zr-95 1.79 8.71 E-04 Sb-125 1.77 8.65E-04 Mn-54 1.43 7.00E-04

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 36 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 3.0 SOLID WASTE DISPOSITION Table 10, Solid Waste Disposition Number of Mode of Transportation Destination Shipments 15 Hittman Transport Services Energy Solutions Bear Creek Facility -

Oak Ridge, TN 1

Landstar System, Inc Energy Solutions Bear Creek Facility -

Oak Ridge, TN 11 Hittman Transport Services Energy Solutions -- Memphis 2

Hittman Transport Services Waste Control Specialist LC Compact Waste Disposal Facility 5

Hittman Transport Services Energy Solutions Clive Disposal Site -

Clive, UT 8

Hittman Transport Services Gallagher Road Processing Facility -

Kingston, TN 42 Total 4.0 IRRADIATED FUEL DISPOSITION No irradiated fuel disposition in 2023.

Annual Radioactive Effluent Release Report I YEAR: 2023 I

Page 37 of 37 Company: Constellation I Plant: Byron Nuclear Generating Station 1.0 1.1 1.2, Meteorological Data METEOROLOGICAL DATA

SUMMARY

Joint Frequency Distributions Joint Frequency Distribution tables are available on site pei request for 2023 Stability class Stability class information can be found in the Joint Frequency Distribution tables for 2023.

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