Text

Radioactive Effluent Release Report for 2024
	ML25120A416
Person / Time
Site:	Quad Cities
Issue date:	04/30/2025
From:	Hild D; Constellation Energy Generation
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
	SVP-25-022
	Download: ML25120A416 (1)
	v • d • e

Constellation, SVP-25-022 April 30, 2025 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 Radioactive Effluent Release Report for 2024 10 CFR 50.36a Pursuant to Technical Specifications Section 5.6.3 and 10 CFR 50.36a, enclosed is the Quad Cities Nuclear Power Station Radioactive Effluent Release Report for January through December 2024.

Should you have any questions concerning this letter, please contact Blake Young at (309) 227-3200.

Doug Hild Site Vice President Quad Cities Nuclear Power Station Attachments:

1. 2024 Annual Radioactive Effluent Release Report cc:

Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Quad Cities Nuclear Power Station 2024 Annual Radioactive Effluent Release Report

~

Constellation Quad Cities Nuclear Power Station Annual Radioactive Effluent Release Report 2024

Annual Radioactive Effluent Release Report I YEAR: 2024 l Page 2 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS................................................................................ 4 2.0 EXECUTIVE

SUMMARY

............................................................................................................ 6 2.1 Comparison to Regulatory Limits.................................................................................... 7

3.0 INTRODUCTION

........................................................................................................................ 9 3.1 About Nuclear Power...................................................................................................... 9 3.2 About Radiation Dose................................................................................................... 10 3.3 About Dose Calculation................................................................................................ 12 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS................................................................. 14 4.1 Regulatory Limits.......................................................................................................... 14 4.2 Regulatory Limits for Gaseous Effluent Doses:............................................................. 14 4.3 Regulatory Limits for Liquid Effluent Doses................................................................... 15 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public.................................. 16 4.5 Onsite Doses (Within Site Boundary)............................................................................ 16 5.0 SUPPLEMENTAL INFORMATION........................................................................................... 16 5.1 Gaseous Batch Releases............................................................................................. 16 5.2 Liquid Batch Releases.................................................................................................. 17 5.3 Abnormal Releases...................................................................................................... 17 5.4 Land Use Census Changes.......................................................................................... 21 5.5 Meteorological Data...................................................................................................... 21 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days................................ 21 5.7 Offsite Dose Calculation Manual (ODCM) Changes...................................................... 22 5.8 Process Control Program (PCP) Changes.................................................................... 22 5.9 Radioactive Waste Treatment System Changes........................................................... 22 5.10 Other Supplemental Information................................................................................... 22 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM............... 24 6.1 Voluntary Notification.................................................................................................... 43 7.0 BIBLIOGRAPHY...................................................................................................................... 44 TABLES Table 1, Quad Cities Nuclear Power Station Units 1 and 2 Dose Summary........................................... 7 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for Quad Cities Station.............. 8 Table 3, Groundwater Protection Program Monitoring Well Sampling Locations.................................. 24 Table 4, Groundwater Protection Program Monitoring Well Tritium, Strontium, and Gross Alpha in Groundwater Samples (pCi/L+/- 2 sigma).............................................................................................. 31 Table 5, Groundwater Protection Program Monitoring Well Gamma Isotopic in Groundwater Samples (pCi/L+/- 2 sigma).................................................................................................................................. 34 Table 6, Groundwater Protection Program Monitoring Well Hard-To-Detects in Groundwater Samples

{pCi/L+/- 2 sigma).................................................................................................................................. 36 Table 7, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma)....................................................... 37

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 3 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 8, Gaseous Effluents Summation of All Releases {Unit 1 and 2}............................................... 45 Table 9, Gaseous Effluents - Ground Level Release Batch Mode {Unit 1 and 2}................................ 46 Table 10, Gaseous Effluents - Ground Level Release Continuous Mode {Unit 1 and 2}...................... 47 Table 11, Gaseous Effluents - Mixed Level Release Batch Mode {Unit 1 and 2}................................. 48 Table 12, Gaseous Effluents - Mixed Level Release Continuous Mode {Unit 1 and 2}........................ 49 Table 13, Gaseous Effluents - Elevated Level Release Batch Mode {Unit 1 and 2}............................. 50 Table 14, Gaseous Effluents - Elevated Level Release Continuous Mode {Unit 1 and 2}.................... 51 Table 15, Liquid Effluents - Summation of All Releases {Unit 1 and 2}............................................... 52 Table 16, Batch Mode Liquid Effluents {Unit 1 and 2}.......................................................................... 53 Table 17, Continuous Mode Liquid Effluents {Unit 1 and 2}................................................................. 54 Table 18, Types of Solid Waste Summary {Unit 1 and 2}..................................................................... 55 Table 19, Major Nuclides {Unit 1 and 2}............................................................................................... 55 Table 20, Solid Waste Disposition {Unit 1 and 2}................................................................................. 56 Table 21. Classification of Atmospheric Stability based on the 196-33 ft differential......................... 59 Table 22, Classification of Atmospheric Stability based on the 296-33 ft differential......................... 59 FIGURES Figure 1, Pressurized Water Reactor (PWR) [1] (omitted, not applicable to QCNPS)........................ N/A Figure 2, Boiling Water Reactor (BWR) (2)............................................................................................. 9 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]............. 12 Figure 5, Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Stations, 2024

............................................................................................................................................................ 27 Figure 6, Sentinel Monitoring Locations, Quad Cities Nuclear Power Station, 2024............................. 28 Figure 7, Radwaste Area Well Locations, Quad Cities Nuclear Power Station, 2024........................... 29 ATTACHMENTS, ARERR Release Summary Tables (RG-1.21 Tables)................................................... 45, Solid Waste Information................................................................................................ 55, Meteorological Data...................................................................................................... 57

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 4 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 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 aliquots making up the sample are collected at time intervals 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.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 5 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2

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.

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.

NRC: 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 1 O 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

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 6 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2

32.

TS: Technical Specification

33.

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

2.0 EXECUTIVE

SUMMARY

Quad Cities Nuclear Power Station Units 1 and 2 (Quad Cities Station) 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 2024 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 2024, the gaseous effluent dose assessments for locations from the Land Use Census showed that the critical receptor for Quad Cities Nuclear Power Station Units 1 and 2 is a Child. The maximum Annual Organ Dose calculated for this receptor was 2.05E-01 mRem to the bone.

The maximum dose calculated to any organ due to radioactive liquid effluents was 1.67E-03 mRem for Adult Liver.

Solid radioactive waste shipped offsite for processing or direct disposal included 7.95E+02 Curies and 1.09E+03 m3, shipped in 50 shipments.

In addition to monitoring radioactive effluents, Quad Cities Station 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: 2024 I Page 7 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 2.1 Comparison to Regulatory Limits During 2024 all solid, liquid, and gaseous radioactive effluents from Quad Cities Nuclear Power Station Units 1 and 2 were well below regulatory limits, as summarized in Table 1 and Table 2.

Table 1, Quad Cities Nuclear Power Station Units 1 and 2 Dose Summary1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Liquid Effluent Limit 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem Dose Limit, Total Body Dose 2.20E-08 7.88E-04 9.52E-09 1.42-05 Total Body

% of Limit l.47E-06 5.25E-02 6.35E-07 2.27-03 Liquid Effluent Limit 5mrem 5mrem 5mrem 5mrem Dose Limit, Max Organ Dose 1.82E-08 l.61E-03 7.89E-09 5.75E-05 Any Organ

% of Limit 4.40E-07 3.22E-02 l.90E-07 l.18E-03 Gaseous Effluent Limit 5 mrad 5 mrad 5 mrad 5 mrad Dose Limit, Gamma Air Dose 2.28E-04 2.28E-04 2.54E-04 2.76E-04 Gamma Air (Noble Gas)

% of Limit 4.SGE-03 4.SGE-03 5.08E-03 5.53E-03 Gaseous Effluent Limit 10 mrad 10 mrad 10 mrad 10 mrad Dose Limit, Beta Air Dose 1.90E-04 l.28E-04 l.77E-04 l.SGE-04 Beta Air (Noble Gas)

% of Limit 1.90E-03 l.28E-03 1.77E-03 l.SGE-03 Gaseous Effluent Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem Organ Dose Limit Max Organ Dose 4.89E-02 4.96E-02 5.31E-02 5.37E-02 (Iodine, Tritium, Particulates with

% of Limit 6.52E-01 6.62E-01 7.08E-01 7.16E-01

> 8-day half-life) 1 Table 1 demonstrates compliance with 10 CFR Part 50, App. I Limits.

Annual 3mrem 8.03E-04 2.68E-02 10 mrem l.67E-03 l.67E-02 10 mrad 9.86E-04 9.86E-03 20 mrad 6.SlE-04 3.25E-03 15 mrem 2.0SE-01 l.37E+00

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 8 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for Quad Cities Station2 Whole Body Thyroid Max Other Organ Gaseous3 6.54E-03 1.17E-02 6.82E-03 Carbon-14 4.00E-02 4.00E-02 2.00E-01 Liquid 8.03E-04 1.81 E-07 1.67E-03 Direct Shine 7.74E+00 7.74E+00 7.74E+00 Total Site Dose 7.79E+00 7.83E+00 8.15E+00 Total w/Other Nearby Facility4 7.79E+00 7.79E+00 7.95E+00 Limit 25 mrem 75 mrem 25 mrem

% of Limit 3.12E+01 1.04E+01 3.18E+01 2 Table 2 is a summation of Units to show compliance with 40 CFR Part 190 Limits.

3 Gaseous dose values in Table 2 include organ dose from Noble Gas, Iodine, Tritium, and particulates.

4 Other fuel cycle sources within 5 miles of the site are considered in this analysis. Quad Cities does not have other fuel cycle sources within 5 miles of the site.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 9 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2

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.

Containment Structure Figure 1, 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: 2024 I Page 10 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 3.2 About Radiation Dose All matter is made of atoms. An atom is the smallest part into which matter can be broken down and still maintain all its chemical properties. Nuclear radiation is energy, in the form of waves or particles that is given off by unstable, radioactive atoms.

Radioactive material exists naturally and has always been a part of our environment.

The earth's crust, for example, contains radioactive uranium, radium, thorium, and potassium. Some radioactivity is a result of nuclear weapons testing.

Examples of radioactive fallout that is normally present in environmental samples are Cesium-137 and Strontium-90. Some examples of radioactive materials released from a nuclear power plant are Cesium-137, lodine-131, Strontium-90, and Cobalt-60.

Radiation dose is measured in units of millirem; much like temperature is measured in degrees. A millirem is a measure of the biological effect of the energy deposited in tissue. The natural and man-made radiation dose received in one year by the average American is 300 to 400 mrem. Radioactivity is measured in curies. A curie is that amount of radioactive material needed to produce 37,000,000,000 nuclear disintegrations per second. 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.

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

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

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 11 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 In addition to natural radiation, we are normally exposed to radiation from a number of man-made sources. The single largest doses from man-made sources result from the therapeutic and diagnostic applications of x-rays and radiopharmaceuticals. The annual dose to an individual in the U.S. from medical and dental exposure is about 300 mrem. Consumer products, such as televisions and smoke detectors, contribute about 13 mrem/year. Much smaller does result from weapons fallout (less than 1 mrem/year) and nuclear power plants. Typically, the average person in the United States receives about 314 mrem/year from man-made sources.

Computed tomograplly (medical)

(24%)

Terrestrial (background)

(3%)

Nuclear medicine _

(medical)

(12%)

Space (background)

(5%)

lnterventional fluoroscopy (medical)

(7%)

Radon & thoron (background)

(37%)

Occupational

(<0.1o/o)

Consumer (2%)

Conventional radiography/fluoroscopy (medical)

(5%)

Figure 2, Sources of Radiation Exposure (NCRP Report No. 160) [3]

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]. 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: 2024 I Page 12 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 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

..c,c Marine produc:ls

*.. : Behavior of radionuclides Figure 3, Potential exposure pathways to Members of the Public due to Plant Operations [6]

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 13 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 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 NRC 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.

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: 2024 I Page 14 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 4.0 4.1 4.2 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 Quad Cities Station must adhere. Quad Cities Station 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 Quad Cities Station 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 104 microcuries/ml.

The annual whole body, skin and organ dose was computed using the 2024 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, Quad Cities Nuclear Power Station Units 1 and 2 Dose Summary and Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for Quad Cities Station.

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 1 O mrads gamma b)

Less than or equal to 20 mrads beta

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 15 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2

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 4.3 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 1 O mrem critical organ

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 16 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public

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.

4.5 Onsite Doses (Within Site Boundary)

Not applicable for Quad Cities Nuclear Power Station. Any member of the public that is onsite for a significant period will be issued a dosimeter.

5.0 SUPPLEMENTAL INFORMATION 5.1 Gaseous Batch Releases 5.1.1 Quad Cities Station Unit 1 & 2 Number of batch releases 0

Total time period for a batch release 0 minutes Maximum time period for a batch release 0 minutes Average time period for a batch release 0 minutes Minimum time period for a batch release 0 minutes No Gaseous Batch Releases for 2024.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 17 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 5.2 Liquid Batch Releases 5.2.1 Quad Cities Station Unit 1 & 2 Number of batch releases 1

Total time period for a batch release 7.940E+02 minutes Maximum time period for a batch release 7.940E+02 minutes Average time period for a batch release 7.940E+02 minutes Minimum time period for a batch release 7.940E+02 minutes Average total flow during period of release 6.877E+01 gpm 5.3 Abnormal Releases 5.3.1 Gaseous Abnormal Releases Number of releases 0

Total activity released 0 Ci No Gaseous Abnormal Releases for 2024.

5.3.2 Liquid Abnormal Releases Number of releases 3

Total activity released 4.17E-01 Ci

a. On March 10, 2021, groundwater sample results from well QC-GP-12 showed a tritium concentration of 2.8 million pCi/L. Sample results from nearby well QC-GP-16 showed a tritium concentration of 1.9 million pCi/L. QC-GP-12 and QC-GP-16 are located in the Condensate Storage Tank and ancillary piping area. Five additional groundwater monitoring wells were installed (Stick wells #1, #2, #4, and #5, and groundwater monitoring well MW-QC-11 ?S) for assistance with leak detection location and groundwater monitoring. A new remediation well was installed (MW-R-2O2) and remediation commenced on 3/15/21.

On March 10, 2021, the station contacted the Illinois Environmental Protection Agency (IEPA) and Illinois Emergency Management Agency (IEMA) to report a release of a radionuclide pursuant to 35 Ill. Adm. Code 1010.202. The station also notified the Nuclear Regulatory Commission (NRC) of the report to state agencies to satisfy 1 0CFR50. 72(b)(2)(xi), notification of the NRC for any event related to the health and safety of the public for which a notification to other government agencies has been or will be made (EN#55132).

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 18 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 I

As part of the investigation to identify the source, the "B" Condensate Storage Tank was drained and inspected. During the inspection a hole measuring 1/4" x 5/16" (approximately the width of a pencil) was discovered on the tank floor which allowed water to seep into the surrounding groundwater. The hole was repaired prior to returning to service. In October 2022 the "B" Condensate Storage Tank floor was restored to original tank floor thickness and "A" Condensate Storage Tank floor was returned to original tank floor thickness in January 2021.

On March 12, 2021, an extraction well (MW-R-2D2) was installed near the Contaminated Condensate Storage Tank area to assist in remediating the tritium activity in groundwater.

The extraction well began pumping groundwater on March 15, 2021, with effluent routed to Quad Cities Station's permitted outfall 001/002. Between March 15, 2021, and December 20, 2021, approximately 14.9 million gallons of groundwater was pumped from the vicinity of the Condensate Storage Tank and ancillary piping area for remediation purposes.

Remediation out of MW-R-2D2 is on-going. Prior to remediation QC-GP-12 tritium concentration was 3.2 million pCi/L. As of December 9, 2021, QC-GP-12 tritium concentration was 57,400pCi/L.

Upon initiation of routing to the discharge bay, samples were collected from each well on a daily basis to monitor for tritium concentration, gamma spectroscopy, and to create monthly composite samples to be analyzed for gross alpha, Fe-55, Ni-63, Sr-89, and Sr-90. LLDs and sampling requirements for this monitored abnormal release are identical to the requirements listed in the ODCM for routine liquid effluent analysis. Starting the week of August 9th 2021, due to consistently decreasing concentrations of tritium identified in the samples, sample collection was changed to a frequency of once per week. No other changes were made to the previously identified sampling and analysis frequency.

Samples were also obtained at the Discharge Bay outfall and analyzed for the same radionuclides and at the same frequency as the well samples. No samples of the discharge bay outfall showed detectable activity.

During the period that the wells were routed to the Discharge Bay, only tritium was detected in the well discharge at levels above the required limit of detection. A total of 3.62E+00 Ci of tritium was released to the Mississippi River via this abnormal release. The associated dose impact to members of the public from this abnormal release was calculated to be 2.65E-07 mRem to the Child/Liver dose pathway. The total body dose associated with this abnormal release was calculated to be 2.65E-07 mRem to the Child Total Body. The associated curies and doses due to this release were included in the 2021 Annual Radiological Effluent Release Report Summation of All Releases Table (page 6 of the 2021 ARERR), Mississippi River Continuous Mode (page 7 of the 2021 ARERR) and Radiological Impact on Man (page 18 of the 2021 ARERR).

Remediation of MW-R-2D2 continued through the 2022 calendar year, from January 1st through December 31st, 2022. A total of 1.65E+07 gallons were released to the Discharge Bay Outfall. Starting January 3rd, 2022, sampling frequency was reduced to once every two weeks. Samples have been consistently less than detectible values for Tritium (H-3) and all other analytes. Monthly composite samples continue to be analyzed for gross alpha, Fe-55, Ni-63, Sr-89, and Sr-90. LLDs and sampling requirements for this monitored abnormal

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 19 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 iind 2 release are identical to the requirements listed in the ODCM for routine liquid effluent analysis. During the period that the wells were routed to the discharge bay, no tritium was detected in the well discharge at levels above the required limit of detection.

Remediation of MW-R-2D2 continued through the 2023 calendar year, from January 1st through December 31st, 2023 with a bimonthly sampling frequency. A total of 1.16E+07 gallons were released to the Discharge Bay Outfall. Samples have been consistently less than detectible values for Tritium (H-3) and all other analytes. Monthly composite samples continue to be analyzed for gross alpha, Fe-55, Ni-63, Sr-89, and Sr-90. LLDs and sampling requirements for this monitored abnormal release are identical to the requirements listed in the ODCM for routine liquid effluent analysis. During the period that the wells were routed to the discharge bay, no tritium was detected in the well discharge at levels above the required limit of detection.

Remediation of MW-R-2D2 continued through a portion of the 2024 calendar year, from January 1st through September 16th, 2024. During this time, a total of 6.1 0E+06 gallons were released to the Discharge Bay Outfall. A monthly sampling frequency yielded a single detection of Tritium in the month of April which produced 5.56E-02 Ci of activity. The associated dose impact to members of the public from MW-R-2D2 was calculated to be 2.02E-08 mRem to the Child/Liver dose pathway. The total body dose associated with this abnormal release was calculated to be 2.02E-08 mRem to the Child Total Body.

Quad Cities Station resumed remediation in the Radwaste Vault area at monitoring wells QC-RW-1 and QC-GP-18 on June 14, 2023 after stopping remediation in the area in December of 2020 due to the underground Fire Protection Piping modification work in the area. During the period that the wells were routed to the Discharge Bay, only tritium was detected in the well discharge at levels above the required limit of detection. A total of 4.65E-02 Ci and 3.19E-01 Ci of tritium were released to the Mississippi River via the QC-GP-18 and QC-RW-1 abnormal releases, respectively. The associated dose impact to members of the public from the QC-GP-18 abnormal release was calculated to be 7.93E-07 mRem to the Child/Liver dose pathway. The total body dose associated with this abnormal release was calculated to be 7.93E-07 mRem to Child Total Body. The associated dose impact to members of the public from the QC-RW-1 abnormal release was calculated to be 1.05E-07 mRem to the Child/Liver dose pathway. The total body dose associated with this abnormal release was calculated to be 1.05E-07 mRem to the Child Total Body. The associated curies and doses due to the QC-GP-18 and QC-RW-1 releases are included in the 2023 Annual Radiological Effluent Release Report Summation of All Releases Table (page 6 of this report), Mississippi River Continuous Mode (page 7 of this report) and Radiological Impact on Man (pages 20-21 of this report).

On July 3, 2023, the station contacted the Illinois Environmental Protection Agency (IEPA) and Illinois Emergency Management Agency (IEMA) to report a release of a radionuclide pursuant to 35 Ill. Adm. Code 1010.202. The station also notified the Nuclear Regulatory Commission (NRC) of the report to state agencies to satisfy 1 0CFR50. 72(b)(2)(xi),

notification of the NRC for any event related to the health and safety of the public for which a notification to other government agencies has been or will be made (EN#56606).

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 20 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Station personnel performed an evaluation of SSC's (Systems, Structures and Components) and identified leakage from a degraded weld seam at the bottom of the Waste Collector Tank (WCT) within the Radwaste Building. Liquids from this system were leaking onto the concrete floor. The tritium concentration in the WCT is over 5 million pCi/L. The WCT was taken out of service and drained on July 17, 2023, and repairs were completed on July 19, 2023. After removing the standing water in the WCT room, station personnel identified two cracks in the concrete floor. These cracks, as well as seams along the perimeter of the room, were identified as a potential pathway to groundwater.

Five additional monitoring wells (QC-GP-19 through QC-GP-23) were installed on July 13 through 19, 2023, between the Radwaste Building and Cribhouse, to assist in delineating the tritium plume. On July 25, 2023, extraction well QC-RW-2 was installed and began pumping water on July 27, 2023, to assist in the remediation of the groundwater plume. QC-RW-2 originally started pumping at 20 gpm, but the groundwater extraction rate was increased to 25 gpm on July 28, 2023, and it has since been operating at this extraction rate. The operation of the extraction well at its current pumping rate has lowered the water table in the area of the Radwaste Building and Cribhouse by approximately three to nine feet and QC-RW-2 appears to be effectively capturing the known extent of the tritium plume.

An additional well was installed at the beginning of November 2023, downgradient of the Main Chimney to evaluate if impacted groundwater was migrating north of the Cribhouse prior to the installation of extraction well QC-RW-2. Tritium has not been detected in samples collected from this additional well since being installed. Additionally, well sampling frequency was increased to monitor tritium concentrations. It should be noted that the newly installed wells are currently not a part of the station's RGPP program.

Remediation out of QC-RW-2 is on-going, with a total of 1.32E+07 gallons released to the Discharge Bay Outfall during the 2024 calendar year. Monthly composite samples continue to be analyzed for gross alpha, Fe-55, Ni-63, Sr-89, and Sr-90. LLDs and sampling requirements for this monitored abnormal release are identical to the requirements listed in the ODCM for routine liquid effluent analysis. During the period that the wells were routed to the discharge bay, only tritium was detected in the well discharge at levels above the required limit of detection. A total of 2.72E-01 Ci of tritium was released to the Mississippi River via QC-RW-2. The associated dose impact to members of the public from QC-RW-2 was calculated to be 8.46E-08 mRem to the Child/Liver dose pathway. The total body dose associated with this abnormal release was calculated to be 8.46E-08 mRem to the Child Total Body.

b. On 4/5/2024, Operations notified Chemistry of an increase in activity on the Unit 2 Service Water Radiation Monitor. Samples were collected and found to contain long-lived Reactor Water Nuclides. Sampling was continued daily until no activity was recorded, ending on 4/10/2024 at 0905. It could not be determined where the source of activity originated. A conservative total of 1.84E+08 gallons were discharged during the release period. The discharge was found to contain the nuclides Mn-54, Co-58, Co-60 and Zn-65. These accounted for a total activity released of 8.99E-02 Ci. The total body and organ dose associated with the activity of this release was calculated to be 7.BBE-04 mRem to the Child Total Body and 1.61 E-03 to the Adult Liver, respectively.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 21 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 5.4 Land Use Census Changes No changes in the Land Use Census for the 2024 calendar year.

5.5 Meteorological Data

5.6 In 2024, Quad Cities Station meteorological monitoring program produced 78,791 hours0.00916 days 0.22 hours 0.00131 weeks 3.009755e-4 months of valid data out of a possible 79,056 hours6.481481e-4 days 0.0156 hours 9.259259e-5 weeks 2.1308e-5 months , resulting in an overall data recovery rate of 99. 7%.

Effluent Radiation Monitors Out of Service Greater Than 30 Days On 07/07/23, the River Discharge Tank Flow Rate Monitor was determined to be non-functional. The 30-day restoration requirement per ODCM Section 12.2.1. was surpassed due to parts and resource availability. On 10/18/24, a batch liquid release was performed, and the ODCM Section 12.2.1. Applicability statement of "When Flow is Present in the System" was entered and the 30-day restoration requirement was surpassed. ODCM Section 12.2.1. "Radioactive Liquid Monitoring Instrumentation",

Condition F.1., Condition F.2., as well as Condition G. were entered at time of the liquid batch release.

Effluent Number of Date Range Out Reason Out of Additional Radiation Days Out of Service >30 Notes (ODCM Monitor Name Service of Service Days or TS)

River Discharge Parts and ODCM 12.2.1 07/07/2023 -

Condition F, Tank Flow Rate 664 Current Date resource Required Monitor availability Action F.2 The Main Chimney High Range Noble Gas Monitor was deemed out of service on 9/30/24 due to scheduled preventative maintenance on the Victoreen. The 7-day restoration requirement per ODCM Section 12.2.2. was surpassed due to ongoing equipment issues. The Main Chimney High Range Noble Gas Monitor was returned to service on 10/09/24 following troubleshooting and completion of the scheduled maintenance.

Effluent Number of Date Range Out Reason Out of Additional Radiation Days Out of Service >7 Notes (ODCM Monitor Name Service of Service Days or TS)

Initially OOS due to scheduled Main Chimney maintenance, ODCM 12.2.2 High Range 9/30/2024-ingoing Condition F, Noble Gas 9

10/09/2024 equipment issue Required Action Monitor prevented the F.2 instrument from being returned in a timely manner.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 22 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 5.7 Offsite Dose Calculation Manual (ODCM} Changes No changes to the site ODCM in the 2024 calendar year.

5.8 Process Control Program (PCP) Changes No changes to the site Process Control Program (PCP) in the 2024 calendar year.

5.9 Radioactive Waste Treatment System Changes No changes to the site Radioactive Waste Treatment System during the 2024 calendar year.

5.10 Other Supplemental Information 5.10.1 Outside Tanks No onsite tanks exceeding ODCM or TS requirements in the 2024 calendar year.

5.10.2 Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program ISFSI dose contribution occurs in the form of direct radiation, as no liquid or gas releases are expected to occur. Subsequent dose contribution from this array as well as historical uranium fuel cycle operations is within 40CFR190 and 10CFR72.104 limits. There were no radioactive effluents released from the QCNPS ISFSI in 2024.

The report prepared in accordance with ISFSI requirements is submitted separately from the ARERR.

5.10.3 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.

Quad Cities has estimated its Carbon-14 generation and release in accordance with EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 23 of 59 9ompany: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Effluents". The Quad Cities estimate of 2.84E+01 Ci of Carbon-14 and the resultant 2.84E+01 Ci 14CO2 released is based upon a normalized Carbon-14 production rate of 5.1 OE+OO Ci/GWTh-yr, a gaseous release fraction of 1.00, a Carbon-14 CO2 fraction of 1.00, a reactor power rating of 2957 MWTh/unit for 2 units, and a calculated Effective Full Power days based upon Total Core Therms data. The maximum expected annual dose contribution from Carbon-14 has been calculated to be 2.0BE-01 mrem/yr organ dose and 4.15E-02 mrem/yr total body dose. This was obtained using maximum gross thermal capacity maintained for 365 days for both units.

The estimated generation for Quad Cities Nuclear Power Station Units 1 and 2 during 2024 was 2.90E+01 Ci. Public dose estimates were performed using methodology from the ODCM.

The total body and thyroid dose associated with Carbon-14 release was found to be 4.00E-02 (child), while the maximum dose to other organs was found to be 2.00E-01 (child/bone).

Carbon-14 dose is included in dose calculation results in Table 2.

5.10.4 Errata/Corrections to Previous ARERRs None

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 24 of 59 Company: Constellation l;>lant: Quad Cities Nuclear Power Station Units 1 and 2 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM Quad Cities Nuclear Power Station Units 1 and 2 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.

During 2024, Quad Cities Station collected and analyzed groundwater samples in accordance with the requirements of approved procedures following regulatory methods.

This section is included in this report to communicate results of NEI 07-07 Radiological Groundwater Monitoring Program. Monitoring wells installed as part of GPI program are sampled and analyzed as summarized in Table 3, Groundwater Protection Program Monitoring Well Sampling Locations. In addition to reporting results from NEI 07-07 monitoring wells, voluntary communications to offsite governmental agencies for onsite leaks or spills per NEI 07-07 Objective 2.2, are also reported as part of this report. It is important to note, samples and results taken in support of NEI 07-07 groundwater monitoring program are not part of the Radiological Environmental Monitoring Program (REMP) but should be reported as part of ARERR.

Table 3, Groundwater Protection Program Monitoring Well Sampling Locations Site Site Type Well Designation Minimum Sample Frequency MW-QC-1 Monitoring Well Source Quarterly MW-QC-2 Monitoring Well Mid-Field Semi-Annual MW-QC-3 Monitoring Well Source Quarterly MW-QC-101I Monitoring Well Idle Not Required MW-QC-101S Monitoring Well Idle Not Required MW-QC-102D Monitoring Well Perimeter Annual MW-QC-102I Monitoring Well Mid-Field Semi-Annual MW-QC-102S Monitoring Well Perimeter Annual MW-QC-103I Monitoring Well Source Quarterly MW-QC-104S Monitoring Well Source Quarterly MW-QC-105I Monitoring Well Source Quarterly MW-QC-106I Monitoring Well Mid-Field Semi-Annual

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 25 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 3, Groundwater Protection Program Monitoring Well Sampling Locations (Cont'd)

Site Site Type Well Designation Minimum Sample Frequency MW-QC-106S Monitoring Well Mid-Field Semi-Annual MW-QC-107I Monitoring Well

Background

Annual MW-QC-108O Monitoring Well Perimeter Annual MW-QC-108I Monitoring Well Mid-Field Semi-Annual MW-QC-108S Monitoring Well Perimeter Annual MW-QC-109I Monitoring Well Mid-Field Semi-Annual MW-QC-109S Monitoring Well Perimeter Annual MW-QC-110I Monitoring Well Idle Not Required MW-QC-111O1 Monitoring Well Idle Not Required MW-QC-11102 Monitoring Well Idle Not Required MW-QC-111I Monitoring Well Idle Not Required MW-QC-112I Monitoring Well Perimeter Annual MW-QC-113I Monitoring Well Idle Not Required MW-QC-114I Monitoring Well Idle Not Required MW-QC-115S Monitoring Well Idle Not Required MW-QC-116S Monitoring Well Idle Not Required MW-QC-117S Monitoring Well Source Quarterly MW-R-2O2 Remediation Well Mid-Field Semi-Annual SURFACE WATER #1 Surface Water Idle Not Required SURFACE WATER #2 Surface Water Idle Not Required WELL#l Production Well Idle Not Required WELL#S Production Well Idle Not Required WELL #6 LITTLE FISH Production Well Idle Not Required WELL#7 Production Well Idle Not Required BIG FISH WELL WELL#8 Production Well Idle Not Required FIRE TRAINING WELL WELL#9 Production Well

Background

Annual Dry Cask Storage WELL#l0 Production Well Idle Not Required FISH HOUSE WELL WELL#ll Production Well Idle Not Required SPRAY CANAL WELL STPSAND Production Well Idle Not Required POINT WELL QC-GP-1 Sentinel Well Source Quarterly QC-GP-2 Sentinel Well Source Quarterly QC-GP-3 Sentinel Well Idle Not Required

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 26 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 3, Groundwater Protection Program Monitoring Well Sampling Locations (Cont'd)

Site Site Type Well Designation Minimum Sample Frequency QC-GP-4 Sentinel Well Source Quarterly QC-GP-5 Sentinel Well Source Quarterly QC-GP-6 Sentinel Well Idle Not Required QC-GP-7 Sentinel Well Idle Not Required QC-GP-8 Sentinel Well Idle Not Required QC-GP-9 Sentinel Well Source Quarterly QC-GP-10 Sentinel Well Source Quarterly QC-GP-11 Sentinel Well Idle Not Required QC-GP-12 Sentinel Well Source Quarterly QC-GP-13 Sentinel Well Idle Not Required QC-GP-14 Sentinel Well Mid-Field Semi-Annual QC-GP-15 Sentinel Well Source Quarterly QC-GP-16 Sentinel Well Idle Not Required QC-GP-17 Sentinel Well Source Quarterly QC-GP-18 Sentinel Well Source Quarterly QC-GP-19 Monitoring Well Source Quarterly QC-GP-20 Monitoring Well Idle Not Required QC-GP-21 Monitoring Well Idle Not Required QC-GP-22 Monitoring Well Source Quarterly QC-GP-23 Monitoring Well Idle Not Required QC-GP-24 Monitoring Well Source Quarterly QC-RW-1 Remediation Well Mid-Field Semi-Annual QC-RW-2 Remediation Well Mid-Field Semi-Annual

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 27 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units MAPS OF COLLECTION SITES I

111111 11111 I I I 1!!! 11 !

11 I i I I !! i I 1 and 2 Figure 4, Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Stations, 2024

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 28 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Figure 5, Sentinel Monitoring Locations, Quad Cities Nuclear Power Station, 2024

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 29 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units

(

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I _II QC*GP-1' e QCGP-22 ~

QC*GP 10 QC GP*19

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--====---=== Feel Figure 6, Radwaste Area Well Locations, Quad Cities Nuclear Power Station, 2024

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 30 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Radiological Groundwater Monitoring Program tritium results are summarized in Table 4, Groundwater Protection Program Monitoring Well Tritium, Strontium, and Gross Alpha in Groundwater Samples (pCi/L +/- 2 sigma). Strontium-90 was detected at one location with concentrations ranging from 3.1 - 10.7 pCi/L. Gross Alpha (Dissolved) was detected in two locations with concentrations ranging from 1.9 - 5.5 pCi/L.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 31 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 4, Groundwater Protection Program Monitoring Well Tritium, Strontium, and Gross Alpha in Groundwater Samples (pCi/L +/- 2 sigma)

Site Collection Date H-3 Sr-89 Sr-90 Gr-A(Dis)

Gr-A(Sus)

MW-QC-1 2/21/2024 199 5.9 0.9 16.3 8.2 MW-QC-1 5/6/2024 225

+/-

128 MW-QC-1 9/4/2024 187 MW-QC-1 10/9/2024 192 MW-QC-102D 2/22/2024 182 MW-QC-1021 2/22/2024 181 MW-QC-1021 9/4/2024 184 MW-QC-102S 2/22/2024 178 MW-QC-1031 2/22/2024 179 8.2 0.9 0.7 0.8 MW-QC-1031 5/7/2024 193 MW-QC-1031 9/4/2024 187 MW-QC-1031 10/7/2024 191 MW-QC-104S 2/22/2024 1300

+/-

203 8.0 0.9 1.9

+/-

1.1 0.8 MW-QC-104S 5/7/2024 460

+/-

137 MW-QC-104S 9/4/2024 1290

+/-

205 MW-QC-104S 10/7/2024 6320

+/-

702 MW-QC-1051 2/22/2024 184 9.8 0.9 1.2 0.8 MW-QC-1051 5/7/2024 195 MW-QC-1051 9/4/2024 187 MW-QC-1051 10/7/2024 194 MW-QC-1061 2/21/2024 176 MW-QC-1061 9/4/2024 188 MW-QC-106S 2/21/2024 179 MW-QC-106S 9/4/2024 190 MW-QC-1071 2/21/2024 199 MW-QC-108D 2/21/2024 192 MW-QC-1081 2/22/2024 374

+/-

130 MW-QC-1081 9/4/2024 281

+/-

127 MW-QC-108S 2/21/2024 180 MW-QC-1091 2/21/2024 183 MW-QC-1091 9/4/2024 187 MW-QC-109S 2/21/2024 192 MW-QC-1121 2/21/2024 197 MW-QC-117S 2/22/2024 192 6.2 1.0 0.6 0.8 MW-QC-117S 5/7/2024 191 MW-QC-117S 9/4/2024 186

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 32 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 4, Groundwater Protection Program Monitoring Well Tritium, Strontium, and Gross Alpha in Groundwater Samples (pCi/L +/- 2 sigma) (Cont'd)

Site Collection Date H-3 Sr-89 Sr-90 Gr-A(Dis)

Gr-A(Sus)

MW-QC-117S 10/7/2024 190 MW-QC-2 2/21/2024 194 MW-QC-2 9/4/2024 761

+/-

155 MW-QC-2 9/4/2024 785

+/-

159 Reanalysis MW-QC-3 2/21/2024 533

+/-

147 7.6 0.8 1.0 0.8 MW-QC-3 5/6/2024 917

+/-

173 MW-QC-3 9/4/2024 245

+/-

126 MW-QC-3 10/7/2024 194 MW-R-2D2 2/19/2024 769

+/-

163 MW-R-2D2 9/3/2024 498

+/-

137 QC-GP-1 2/19/2024 195 6.8 0.9 2.8 2.5 QC-GP-1 5/7/2024 192 QC-GP-1 9/3/2024 200 QC-GP-1 10/7/2024 192 QC-GP-10 2/19/2024 191 3.0 0.6 4.0 3.3 QC-GP-10 5/6/2024 188 QC-GP-10 9/3/2024 190 QC-GP-10 10/7/2024 190 QC-GP-12 2/19/2024 424

+/-

135 7.7 0.9 2.9 2.6 QC-GP-12 5/7/2024 333

+/-

113 QC-GP-12 9/3/2024 574

+/-

142 QC-GP-12 10/7/2024 194 QC-GP-14 2/20/2024 193 QC-GP-14 9/5/2024 1970

+/-

269 QC-GP-14 9/5/2024 1850

+/-

260 Recount QC-GP-14 9/5/2024 1520

+/-

226 Reanalysis QC-GP-15 2/19/2024 195 7.4 0.9 3.3 2.6 QC-GP-15 5/6/2024 188 QC-GP-15 9/3/2024 194 QC-GP-15 10/7/2024 187 QC-GP-17 2/19/2024 191 5.3 0.8 3.0 2.6 QC-GP-17 5/7/2024 184 QC-GP-17 9/3/2024 819

+/-

161 QC-GP-17 10/7/2024 255

+/-

126 QC-GP-19 9/3/2024 1520

+/-

226 QC-GP-19 10/9/2024 2390

+/-

311 QC-GP-19 11/19/2024 3240

+/-

391 7.0 0.9 1.4 0.8

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 33 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 4, Groundwater Protection Program Monitoring Well Tritium, Strontium, and Gross Alpha in Groundwater Samples (pCi/L +/- 2 sigma) (Cont'd)

Site Collection Date H-3 Sr-89 Sr-90 Gr-A(Dis)

QC-GP-2 2/19/2024 189 6

1.0 3.0 QC-GP-2 5/6/2024 187 QC-GP-2 9/3/2024 190 QC-GP-2 10/7/2024 197 QC-GP-22 9/5/2024 413

+/-

136 QC-GP-22 9/5/2024 478

+/-

141 Recount QC-GP-22 9/5/2024 367

+/-

130 Reanalysis QC-GP-22 10/9/2024 216

+/-

125 QC-GP-22 11/19/2024 227

+/-

125 7.5 1.0 0.8 QC-GP-24 9/5/2024 194 QC-GP-24 10/9/2024 430

+/-

137 QC-GP-24 11/19/2024 193

+/-

119 7.5 1.0 5.5

+/-

1.8 QC-GP-24 11/19/2024 3.9

+/-

1.4 Reanalysis QC-GP-4 2/19/2024 797

+/-

163 4.7 0.8 4.1 QC-GP-4 5/6/2024 820

+/-

162 QC-GP-4 9/3/2024 1340

+/-

208 QC-GP-4 10/7/2024 1500

+/-

231 QC-GP-5 2/19/2024 194 6.0 7.0

+/-

1.2 4.3 QC-GP-5 5/6/2024 191 6.9 3.1

+/-

0.9 QC-GP-5 6/6/2024 9.3 10.7

+/-

0.8 QC-GP-5 9/3/2024 194 8.5 8.1

+/-

0.8 QC-GP-5 10/7/2024 192 8.7 4.0

+/-

0.8 QC-GP-9 2/19/2024 795

+/-

163 7.9 0.8 3.8 QC-GP-9 5/7/2024 960

+/-

175 QC-GP-9 9/3/2024 1360

+/-

209 QC-GP-9 10/7/2024 691

+/-

157 QC-RW-1 2/19/2024 4620

+/-

530 QC-RW-1 9/3/2024 306

+/-

133 QC-RW-1 9/3/2024 242

+/-

126 QC-RW-2 9/5/2024 4450

+/-

508 QC-RW-2 9/5/2024 4490

+/-

514 Recount QC-RW-2 9/5/2024 4040

+/-

471 Reanalysis QC-RW-2 11/19/2024 3620

+/-

424 WELL#9DRY 2/19/2024 196 CASK STORAGE Gr-A(Sus) 2.5 0.8 0.8 1.0 2.5 3.3 3.3

~

Constellation Quad Cities Nuclear Power Station Table 5, Groundwater Protection Program Monitoring Well Gamma Isotopic in Groundwater Samples (pCi/L +/- 2 sigma)

Collection Site Date Be-7 K-40 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 MW-QC-1 2/21/2024

< 14

< 15

< 1

< 3

< 2

< 3

< 2

< 3

< 2

< 8

< 3 MW-QC-102D 2/22/2024

< 17

< 18

< 2

< 4

< 2

< 4

< 2

< 4

< 2

< 10

< 3 MW-QC-1021 2/22/2024

< 18

< 37

< 2

< 4

< 2

< 4

< 2

< 3

< 4

< 2

< 10

< 3 MW-QC-102S 2/22/2024

< 11 25

+/-

15

< 1

< 3

< 1

< 3

< 1

< 2

< 3

< 1

< 8

< 3 MW-QC-1031 2/22/2024

< 14

< 15

< 2

< 3

< 2

< 3

< 2

< 3

< 4

< 2

< 9

< 3 MW-QC-104S 2/22/2024

< 16

< 31

< 2

< 4

< 2

< 4

< 2

< 3

< 4

< 2

< 10

< 3 MW-QC-1051 2/22/2024

< 14

< 28

< 2

< 4

< 2

< 3

< 2

< 3

< 2

< 9

< 3 MW-QC-1061 2/21/2024

< 17

< 32

< 2

< 4

< 2

< 4

< 2

< 3

< 4

< 2

< 10

< 4 MW-QC-106S 2/21/2024

< 19

< 38

< 2

< 4

< 2

< 5

< 2

< 4

< 2

< 11

< 3 MW-QC-1071 2/21/2024

< 18

< 33

< 2

< 4

< 2

< 4

< 2

< 4

< 2

< 10

< 3 MW-QC-108D 2/21/2024

< 10

< 21

< 2

< 3

< 1

< 2

< 1

< 6

< 2 MW-QC-1081 2/22/2024

< 14

< 33

< 1

< 3

< 2

< 3

< 2

< 3

< 2

< 8

< 3 MW-QC-108S 2/21/2024

< 14

< 26

< 2

< 3

< 2

< 3

< 2

< 3

< 2

< 8

< 3 MW-QC-1091 2/21/2024

< 18

< 21

< 2

< 5

< 2

< 4

< 2

< 4

< 2

< 10

< 4 MW-QC-109S 2/21/2024

< 16

< 18

< 2

< 4

< 2

< 4

< 2

< 4

< 2

< 10

< 3 MW-QC-1121 2/21/2024

< 18

< 40

< 2

< 4

< 2

< 4

< 2

< 4

< 5

< 2

< 11

< 3 MW-QC-117S 2/22/2024

< 17

< 32

< 2

< 4

< 2

< 4

< 2

< 3

< 4

< 2

< 10

< 4 MW-QC-2 2/21/2024

< 17

< 39

< 2

< 5

< 2

< 5

< 2

< 4

< 2

< 11

< 4 MW-QC-3 2/21/2024

< 14

< 34

< 2

< 3

< 2

< 3

< 2

< 3

< 2

< 9

< 3 MW-R-2D2 2/19/2024

< 13

< 2

< 3

< 1

< 3

< 1

< 3

< 6

< 2

< 1

< 12

< 4

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 35 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 5, Groundwater Protection Program Monitoring Well Gamma Isotopic in Groundwater Samples {pCi/L +/- 2 sigma) Cont'd Collection Site Date Be-7 K-40 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 QC-GP-1 2/19/2024

< 16

< 32

< 2

< 4

< 2

< 3

< 2

< 3

< 8

< 2

< 14

< 5 QC-GP-10 2/19/2024

< 14

< 24

< 1

< 4

< 1

< 3

< 2

< 3

< 8

< 2

< 1

< 14

< 5 QC-GP-12 2/19/2024

< 17

< 36

< 2

< 5

< 2

< 4

< 2

< 4

< 8

< 2

< 14

< 5 QC-GP-14 2/20/2024 14

< 15

< 2

< 4

< 1

< 3

< 2

< 3

< 7

< 2

< 1

< 14

< 5 QC-GP-15 2/19/2024

< 17

< 28

< 2

< 5

< 2

< 4

< 2

< 3

< 8

< 2

< 15

< 5 QC-GP-17 2/19/2024

< 17

< 31

< 2

< 4

< 2

< 4

< 2

< 3

< 7

< 2

< 14

< 5 QC-GP-19 11/19/2024

< 17

< 45

< 2

< 4

< 2

< 4

< 2

< 4

< 3

< 2

< 9

< 3 QC-GP-2 2/19/2024

< 16

< 15

< 2

< 4

< 2

< 3

< 2

< 3

< 8

< 2

< 15

< 5 QC-GP-22 11/19/2024

< 18

< 33

< 2

< 4

< 2

< 5

< 2

< 4

< 3

< 2

< 9

< 3 QC-GP-24 11/19/2024

< 20

< 34

< 2

< 4

< 2

< 5

< 2

< 4

< 3

< 2

< 9

< 3 QC-GP-4 2/19/2024

< 17

< 16

< 2

< 4

< 2

< 3

< 2

< 3

< 8

< 2

< 15

< 5 QC-GP-5 2/19/2024

< 15

< 13

< 2

< 4

< 2

< 3

< 2

< 3

< 8

< 2

< 1

< 15

< 5 QC-GP-9 2/19/2024

< 18

< 34

< 2

< 4

< 2

< 3

< 2

< 3

< 8

< 2

< 15

< 4 QC-RW-1 2/19/2024

< 16

< 15

< 2

< 4

< 2

< 4

< 2

< 3

< 7

< 2

< 15

< 5 QC-RW-2 11/19/2024

< 14

< 28

< 2

< 3

< 2

< 3

< 2

< 3

< 2

< 6

< 3 WELL#9 2/19/2024

< 12

< 11

< 1

< 3

< 1

< 3

< 1

< 2

< 7

< 1

< 13

< 4

~

Constellation Quad Cities Nuclear Power Station Table 6, Groundwater Protection Program Monitoring Well Hard-To-Detects in Groundwater Samples (pCi/L +/- 2 sigma)5 No Groundwater Samples Analyzed for Hard-To-Detects in 2024 5 Strontium 89/90 included in Table 5.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 37 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 7, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma)

Site Collection Date Activity Aquifer QC-GP-1 2/19/2024

<2,000 Sentinel Well QC-GP-1 5/7/2024

<2,000 Sentinel Well QC-GP-1 9/3/2024

<2,000 Sentinel Well QC-GP-1 10/7/2024

<2,000 Sentinel Well QC-GP-2 2/19/2024

<2,000 Sentinel Well QC-GP-2 5/6/2024

<2,000 Sentinel Well QC-GP-2 9/3/2024

<2,000 Sentinel Well QC-GP-2 10/7/2024

<2,000 Sentinel Well QC-GP-4 2/19/2024

<2,000 Sentinel Well QC-GP-4 5/6/2024

<2,000 Sentinel Well QC-GP-4 9/3/2024

<2,000 Sentinel Well QC-GP-4 10/7/2024

<2,000 Sentinel Well QC-GP-5 2/19/2024

<2,000 Sentinel Well QC-GP-5 5/6/2024

<2,000 Sentinel Well QC-GP-5 9/3/2024

<2,000 Sentinel Well QC-GP-5 10/7/2024

<2,000 Sentinel Well QC-GP-9 2/19/2024

<2,000 Sentinel Well QC-GP-9 5/7/2024

<2,000 Sentinel Well QC-GP-9 9/3/2024

<2,000 Sentinel Well QC-GP-9 10/7/2024

<2,000 Sentinel Well QC-GP-10 2/19/2024

<2,000 Sentinel Well QC-GP-10 5/6/2024

<2,000 Sentinel Well QC-GP-10 9/3/2024

<2,000 Sentinel Well QC-GP-10 10/7/2024

<2,000 Sentinel Well QC-GP-12 1/8/2024

<2,000 Sentinel Well QC-GP-12 2/19/2024

<2,000 Sentinel Well QC-GP-12 5/7/2024

<2,000 Sentinel Well QC-GP-12 9/3/2024

<2,000 Sentinel Well QC-GP-12 10/7/2024

<2,000 Sentinel Well QC-GP-14 2/20/2024

<2,000 Sentinel Well QC-GP-14 9/5/2024

<2,000 Sentinel Well QC-GP-15 2/19/2024

<2,000 Sentinel Well QC-GP-15 5/6/2024

<2,000 Sentinel Well QC-GP-15 9/3/2024

<2,000 Sentinel Well QC-GP-15 10/7/2024

<2,000 Sentinel Well

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 38 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 7, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma) (Cont'd)

Site Collection Date Activity Aquifer QC-GP-17 1/8/2024

<2,000 Sentinel Well QC-GP-17 2/19/2024

<2,000 Sentinel Well QC-GP-17 5/7/2024

<2,000 Sentinel Well QC-GP-17 9/3/2024

<2,000 Sentinel Well QC-GP-17 10/7/2024

<2,000 Sentinel Well QC-GP-19 1/8/2024

<2,000 Sentinel Well QC-GP-19 2/19/2024

<2,000 Sentinel Well QC-GP-19 5/6/2024

<2,000 Sentinel Well QC-GP-19 9/3/2024

<2,000 Sentinel Well QC-GP-19 10/9/2024 3,360 Sentinel Well QC-GP-19 11/19/2024 3,300 Sentinel Well QC-GP-20 1/8/2024

<2,000 Sentinel Well QC-GP-20 2/19/2024

<2,000 Sentinel Well QC-GP-20 5/6/2024

<2,000 Sentinel Well QC-GP-20 9/3/2024

<2,000 Sentinel Well QC-GP-20 10/9/2024

< 2000 Sentinel Well QC-GP-21 1/8/2024 2,090 Sentinel Well QC-GP-21 2/19/2024 3,480 Sentinel Well QC-GP-21 5/6/2024

< 2000 Sentinel Well QC-GP-21 9/3/2024

< 2000 Sentinel Well QC-GP-21 10/9/2024

< 2000 Sentinel Well QC-GP-22 1/8/2024

< 2000 Sentinel Well QC-GP-22 2/19/2024

< 2000 Sentinel Well QC-GP-22 5/6/2024

< 2000 Sentinel Well QC-GP-22 9/5/2024

< 2000 Sentinel Well QC-GP-22 10/9/2024

< 2000 Sentinel Well QC-GP-22 11/19/2024

< 2000 Sentinel Well QC-GP-23 1/8/2024 5,890 Sentinel Well QC-GP-23 2/19/2024 11,300 Sentinel Well QC-GP-23 5/6/2024 3,610 Sentinel Well QC-GP-23 9/3/2024 6,080 Sentinel Well QC-GP-23 10/9/2024

<2000 Sentinel Well

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 39 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 7, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma) (Cont'd)

Site Collection Date Activity Aquifer QC-GP-24 1/8/2024

<2000 Sentinel Well QC-GP-24 2/19/2024

<2000 Sentinel Well QC-GP-24 5/6/2024

< 2000 Sentinel Well QC-GP-24 9/5/2024

<2000 Sentinel Well QC-GP-24 10/9/2024

< 2000 Sentinel Well QC-GP-24 11/19/2024

<2000 Sentinel Well QC-RW-1 1/8/2024 4,740 Sentinel Well QC-RW-1 2/19/2024 5,530 Sentinel Well QC-RW-1 5/6/2024 6,710 Sentinel Well QC-RW-1 9/3/2025

< 2000 Sentinel Well QC-RW-1 10/9/2024

< 2000 Sentinel Well QC-RW-2 1/2/2024 10,800 Remediation Well QC-RW-2 1/5/2024 11,000 Remediation Well QC-RW-2 1/8/2024 10,100 Remediation Well QC-RW-2 1/10/2024 10,600 Remediation Well QC-RW-2 1/12/2024 11,300 Remediation Well QC-RW-2 1/17/2024 10,700 Remediation Well QC-RW-2 1/19/2024 10,300 Remediation Well QC-RW-2 1/22/2024 9,650 Remediation Well QC-RW-2 1/24/2024 8,040 Remediation Well QC-RW-2 1/26/2024 7,370 Remediation Well QC-RW-2 1/29/2024 10,400 Remediation Well QC-RW-2 1/31/2024 9,180 Remediation Well QC-RW-2 2/2/2024 9,410 Remediation Well QC-RW-2 2/5/2024 8,780 Remediation Well QC-RW-2 2/7/2024 9,960 Remediation Well QC-RW-2 2/9/2024 7,510 Remediation Well QC-RW-2 2/12/2024 8,740 Remediation Well QC-RW-2 2/14/2024 9,040 Remediation Well QC-RW-2 2/16/2024 7,960 Remediation Well QC-RW-2 2/19/2024 8,220 Remediation Well QC-RW-2 2/21/2024 8,240 Remediation Well

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page40 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 7, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma) (Cont'd)

Site Collection Date Activity Aquifer QC-RW-2 2/23/2024 8,230 Remediation Well QC-RW-2 2/26/2024 7,230 Remediation Well QC-RW-2 2/28/2024 7,300 Remediation Well QC-RW-2 3/1/2024 6,960 Remediation Well QC-RW-2 3/4/2024 5,750 Remediation Well QC-RW-2 3/6/2024 7,180 Remediation Well QC-RW-2 3/8/2024 7,510 Remediation Well QC-RW-2 3/11/2024 6,280 Remediation Well QC-RW-2 3/13/2024 6,800 Remediation Well QC-RW-2 3/15/2024 6,300 Remediation Well QC-RW-2 3/18/2024 6,980 Remediation Well QC-RW-2 3/20/2024 5,780 Remediation Well QC-RW-2 3/22/2024 6,240 Remediation Well QC-RW-2 3/25/2024 6,240 Remediation Well QC-RW-2 3/27/2024 7,480 Remediation Well QC-RW-2 3/29/2024 6,070 Remediation Well QC-RW-2 4/1/2024 6,780 Remediation Well QC-RW-2 4/3/2024 5,910 Remediation Well QC-RW-2 4/5/2024 7,080 Remediation Well QC-RW-2 4/8/2024 8,110 Remediation Well QC-RW-2 4/10/2024 9,890 Remediation Well QC-RW-2 4/12/2024 8,520 Remediation Well QC-RW-2 4/15/2024 7,410 Remediation Well QC-RW-2 4/17/2024 7,750 Remediation Well QC-RW-2 4/19/2024 7,040 Remediation Well QC-RW-2 4/22/2024 8,350 Remediation Well QC-RW-2 4/24/2024 7,640 Remediation Well QC-RW-2 4/26/2024 6,830 Remediation Well QC-RW-2 4/29/2024 6,800 Remediation Well QC-RW-2 5/6/2024 6,750 Remediation Well QC-RW-2 5/13/2024 9,050 Remediation Well QC-RW-2 5/20/2024 9,890 Remediation Well

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 41 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 7, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma) (Cont'd)

Site Collection Date Activity Aquifer QC-RW-2 5/28/2024 8,390 Remediation Well QC-RW-2 6/3/2024 7,340 Remediation Well QC-RW-2 6/10/2024 6,530 Remediation Well QC-RW-2 6/17/2024 5,570 Remediation Well QC-RW-2 6/24/2024 7,510 Remediation Well QC-RW-2 7/1/2024 8,760 Remediation Well QC-RW-2 7/8/2024 8,550 Remediation Well QC-RW-2 7/15/2024 7,930 Remediation Well QC-RW-2 7/22/2024 6,340 Remediation Well QC-RW-2 7/29/2024 4,680 Remediation Well QC-RW-2 8/6/2024 4,790 Remediation Well QC-RW-2 8/12/2024 4,780 Remediation Well QC-RW-2 8/19/2024 4,940 Remediation Well QC-RW-2 8/26/2024 7,320 Remediation Well QC-RW-2 9/5/2024 3,340 Remediation Well QC-RW-2 9/9/2024 5,100 Remediation Well QC-RW-2 9/16/2024 6,170 Remediation Well QC-RW-2 9/23/2024 4,350 Remediation Well QC-RW-2 10/1/2024 4,330 Remediation Well QC-RW-2 10/8/2024 4,810 Remediation Well QC-RW-2 10/14/2024 5,690 Remediation Well QC-RW-2 10/21/2024 4,220 Remediation Well QC-RW-2 10/28/2024 4,060 Remediation Well QC-RW-2 11/4/2024 3,000 Remediation Well QC-RW-2 11/11/2024 4,090 Remediation Well QC-RW-2 11/18/2024 5,970 Remediation Well QC-RW-2 11/19/2024 3,330 Remediation Well QC-RW-2 11/25/2024 5,450 Remediation Well QC-RW-2 12/2/2024 4,890 Remediation Well QC-RW-2 12/9/2024 4,940 Remediation Well QC-RW-2 12/16/2024 5,150 Remediation Well QC-RW-2 12/23/2024 3,480 Remediation Well QC-RW-2 12/30/2024 5,090 Remediation Well

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page42 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 7, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma) (Cont'd)

Site Collection Date Activity Aquifer MW-R-2D2 1/8/2024

<2,000 Remediation Well MW-R-2D2 2/19/2024

<2,000 Remediation Well MW-R-2D2 3/4/2024

<2,000 Remediation Well MW-R-2O2 3/18/2024

<2,000 Remediation Well MW-R-2D2 4/1/2024

<2,000 Remediation Well MW-R-2D2 4/15/2024

<2,000 Remediation Well MW-R-2D2 5/7/2024

<2,000 Remediation Well MW-R-2D2 5/20/2024

<2,000 Remediation Well MW-R-2O2 8/6/2024

<2,000 Remediation Well MW-R-2D2 8/19/2024

<2,000 Remediation Well MW-R-2D2 9/3/2024

<2,000 Remediation Well MW-R-2D2 9/9/2024

<2,000 Remediation Well MW-QC-1031 5/7/2024

<2,000 Monitoring Well MW-QC-1031 10/7/2024

<2,000 Monitoring Well MW-QC-104S 1/8/2024 6,380 Monitoring Well MW-QC-104S 5/7/2024

<2,000 Monitoring Well MW-QC-104S 10/7/2024 6,480 Monitoring Well MW-QC-1051 5/7/2024

<2,000 Monitoring Well MW-QC-1051 10/7/2024

<2,000 Monitoring Well MW-QC-1 5/6/2024

<2,000 Monitoring Well MW-QC-1 10/9/2024

<2,000 Monitoring Well MW-QC-3 1/8/2024

<2,000 Monitoring Well MW-QC-3 5/6/2024

<2,000 Monitoring Well MW-QC-3 10/7/2024

<2,000 Monitoring Well MW-QC-117S 5/7/2024

<2,000 Monitoring Well MW-QC-117S 10/7/2024

<2,000 Monitoring Well Well #1 3/25/2024

<200 Production Well Well#l 10/11/2024

<200 Production Well Well#9 2/19/2024

<200 Production Well Well #10 2/19/2024

<200 Production Well Well#10 9/5/2024

<200 Production Well

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page43 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 6.1 Voluntary Notification During 2024, Quad Cities Nuclear Power Station Units 1 and 2 did not make a voluntary NEI 07-07 notification to State/Local officials, NRC, or to other stakeholders required by site procedures.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 44 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 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] (omitted).

[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 1 O 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.

[10] "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] "1 O CFR 20 - Standards for Protection Against Radiation," US Nuclear Regulatory Commission, W~shington, 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.

~

Constellation.

Quad Cities Nuclear Power Station, ARERR Release Summary Tables (RG-1.21 Tables) 1.0 GASEOUS EFFLUENTS Table 8, Gaseous Effluents Summation of All Releases (Unit 1 & 2} 6 A.

Fission & Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est.Total Error%

1.

Total Release Ci 2.32E+01 1.82E+01 2.30E+01 2.21E+01 1.27E+01

2.

Average release rate for the period

µCi/sec 2.95E+OO 2.31E+OO 2.89E+OO 2.78E+OO B.

Iodine

1.

Total Iodine-131 Ci 1.87E-05

<LLD 1.92E-05

<LLD 4.17E+01 I

2.

Average release rate for the period

µCi/sec 2.38E-06 N/A 2.42E-06 N/A C.

Particulates

1.

Particulates with half-lives >8 days Ci 1.40E-03 4.75E-04 6.92E-04 1.10E-03 3.22E+01 I

2.

Average release rate for the period

~1Ci/sec 1.78E-04 6.0SE-05 8.70E-05 1.39E-04 D.

Tritium

1.

Total Release Ci 1.97E+01 2.17E+01 1.67E+01 1.92E+01 6.30E+OO I

2.

Average release rate for the period

µCi/sec 2.51E+OO 2.76E+OO 2.10E+OO 2.42E+OO E.

Gross Alpha

1.

Total Release Ci

<LLD

2.

Average release rate for the period

~1Ci/sec NIA N/A NIA NIA F.

Carbon-14

1.

Total Release Ci 6.86E+OO 7.04E+OO 7.52E+OO 7.57E+OO

2.

Average release rate for the period

µCi/sec 8.72E-01 8.96E-01 9.46E-01 9.52E-01 6 % of limit is provided in Table 1, Quad Cities Nuclear Power Station Units 1 and 2 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 46 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 9, Gaseous Effluents - Ground Level Release Batch Mode Units 1 & 27 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci NIA NIA NIA NIA NIA Kr-85 Ci NIA NIA NIA NIA NIA Kr-85m Ci NIA NIA NIA NIA NIA Kr-87 Ci NIA NIA NIA NIA NIA Kr-88 Ci NIA NIA NIA NIA NIA Xe-133 Ci NIA NIA NIA NIA NIA Xe-135 Ci NIA NIA NIA NIA NIA Xe-135m Ci NIA NIA NIA NIA NIA Xe-138 Ci NIA NIA NIA NIA NIA Total for Period Ci NIA NIA NIA NIA NIA Iodines 1-131 Ci NIA NIA NIA NIA NIA 1-133 Ci NIA NIA NIA NIA NIA 1-135 Ci NIA NIA NIA NIA NIA Total for Period Ci NIA NIA NIA NIA NIA Particulates Mn-54 Ci NIA NIA NIA NIA NIA Co-58 Ci NIA NIA NIA NIA NIA Fe-59 Ci NIA NIA NIA NIA NIA Co-60 Ci NIA NIA NIA NIA NIA Sr-89 Ci NIA NIA NIA NIA NIA Sr-90 Ci NIA NIA NIA NIA NIA Mo-99 Ci NIA NIA NIA NIA NIA Cs-134 Ci NIA NIA NIA NIA NIA Cs-137 Ci NIA NIA NIA NIA NIA Ce-141 Ci NIA NIA NIA NIA NIA Ce-144 Ci NIA NIA NIA NIA NIA Total for Period Cl NIA NIA NIA NIA NIA Tritium H-3 Ci NIA NIA NIA NIA NIA Gross Alpha Alpha Ci NIA NIA NIA NIA NIA Carbon-14 C-14 Ci NIA NIA NIA NIA NIA 7 Quad Cities performed no Gaseous Batch Releases in 2024.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 47 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 10, Gaseous Effluents - Ground Level Release Continuous Mode Units 1 & 28 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci NIA NIA NIA NIA NIA Kr-85 Ci NIA NIA NIA NIA NIA Kr-85m Ci NIA NIA NIA NIA NIA Kr-87 Ci NIA NIA NIA NIA NIA Kr-88 Ci NIA NIA NIA NIA NIA Xe-133 Ci NIA NIA NIA NIA NIA Xe-135 Ci NIA NIA NIA NIA NIA Xe-135m Ci NIA NIA NIA NIA NIA Xe-138 Ci NIA NIA NIA NIA NIA Total for Period Ci NIA NIA NIA NIA NIA Iodines 1-131 Ci NIA NIA NIA NIA NIA 1-133 Ci NIA NIA NIA NIA NIA 1-135 Ci NIA NIA NIA NIA NIA Total for Period Ci NIA NIA NIA NIA NIA Particulates Mn-54 Ci NIA NIA NIA NIA NIA Co-58 Ci NIA NIA NIA NIA NIA Fe-59 Ci NIA NIA NIA NIA NIA Co-60 Ci NIA NIA NIA NIA NIA Sr-89 Ci NIA NIA NIA NIA NIA Sr-90 Ci NIA NIA NIA NIA NIA Mo-99 Cs-134 Ci NIA NIA NIA NIA NIA Cs-137 Ce-141 Ci NIA NIA NIA NIA NIA Ce-144 Total for Period Ci NIA N/A N/A NIA N/A 8 Quad Cities performed no Ground Level Gaseous Releases in 2024.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 48 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 11, Gaseous Effluents - Mixed Level Release Batch Mode Units 1 & 29 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci NIA NIA NIA NIA NIA Kr-85 Ci NIA NIA NIA NIA NIA Kr-85m Ci NIA NIA NIA NIA NIA Kr-87 Ci NIA NIA NIA NIA NIA Kr-88 Ci NIA NIA NIA NIA NIA Xe-133 Ci NIA NIA NIA NIA NIA Xe-135 Ci NIA NIA NIA NIA NIA Xe-135m Ci NIA NIA NIA NIA NIA Xe-138 Ci NIA NIA NIA NIA NIA Total for Period Ci NIA NIA NIA NIA NIA Iodines 1-131 Ci NIA NIA NIA NIA NIA 1-133 Ci NIA NIA NIA NIA NIA 1-135 Ci NIA NIA NIA NIA NIA Total for Period Ci NIA NIA NIA NIA NIA Particulates Co-58 Ci NIA NIA NIA NIA NIA Co-60 Ci NIA NIA NIA NIA NIA Sr-89 Ci NIA NIA NIA NIA NIA Sr-90 Ci NIA NIA NIA NIA NIA Cs-134 Ci NIA NIA NIA NIA NIA Total for Period Ci NIA NIA NIA NIA NIA Tritium H-3 Ci NIA NIA NIA NIA NIA Gross Alpha Alpha Ci NIA NIA NIA NIA NIA Carbon-14 C-14 Ci NIA NIA NIA NIA NIA 9 Quad Cities performed no Gaseous Batch Releases in 2024.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 49 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 12 Gaseous Effluents - Mixed Level Release Continuous Mode Units 1 & 210 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci 1.47E+01 9.17E+00 1.33E+01 1.12E+01 4.84E+01 Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci 1.47E+01 9.17E+00 1.33E+01 1.12E+01 4.84E+01 Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Cr-51 Ci 5.78E-05

<LLD

<LLD 5.78E-05 Mn-54 Ci 7.05E-05 2.10E-05

<LLD

<LLD 9.15E-05 Fe-55 Ci 6.10E-04

<LLD

<LLD 6.10E-04 Co-58 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-60 Ci 3.40E-04 2.10E-04 1.33E-04 8.42E-05 7.67E-04 Zn-65 Ci 1.39E-05

<LLD

<LLD 1.39E-05 Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Mo-99 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Total for Period Ci 1.09E-03 2.31E-04 1.33E-04 8.42E-05 1.54E-03 Tritium H-3 Ci 3.01E+00 2.79E+00 2.91E+00 4.17E+00 1.29E+01 Gross Alpha Alpha Ci

<LLD

<LLD Carbon-14 C-14 Ci 2.06E-01 2.11E-01 2.26E-01 2.27E-01 8.69E-01 10 All LLDs comply with requirements listed in the ODCM.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 50 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 13, Gaseous Effluents - Elevated Level Release Batch Mode Units 1 & 211 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci NIA NIA NIA NIA NIA Kr-85 Ci NIA NIA NIA NIA NIA Kr-85m Ci NIA NIA NIA NIA NIA Kr-87 Ci NIA NIA NIA NIA NIA Kr-88 Ci NIA NIA NIA NIA NIA Xe-133 Ci NIA NIA NIA NIA NIA Xe-135 Ci NIA NIA NIA NIA NIA Xe-135m Ci NIA NIA NIA NIA NIA Xe-138 Ci NIA NIA NIA NIA NIA Total for Period Ci NIA NIA NIA NIA NIA Iodines 1-131 Ci NIA NIA NIA NIA NIA 1-133 Ci NIA NIA NIA NIA NIA 1-135 Ci NIA NIA NIA NIA NIA Total for Period Ci NIA NIA NIA NIA NIA Particulates Co-58 Ci NIA NIA NIA NIA NIA Co-60 Ci NIA NIA NIA NIA NIA Sr-89 Ci NIA NIA NIA NIA NIA Sr-90 Ci NIA NIA NIA NIA NIA Cs-134 Ci NIA NIA NIA NIA NIA Total for Period Cl NIA NIA NIA NIA NIA Tritium H-3 Ci NIA NIA NIA NIA NIA Gross Alpha Alpha Ci NIA NIA NIA NIA NIA Carbon-14 C-14 Ci NIA NIA NIA NIA NIA 11 Quad Cities performed no Gaseous Batch Releases in 2024.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 51 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 14, Gaseous Effluents - Elevated Level Release Continuous Mode Units 1 & 212 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci 4.63E-01 8.32E-01 6.40E-01 8.88E-01 2.82E+00 Kr-85 Ci 1.32E-01

<LLD

<LLD 1.32E-01 Kr-85m Ci 5.19E-02 5.86E-02 5.63E-02 6.31E-02 2.30E-01 Kr-87 Ci 2.20E-01 2.29E-01 2.53E-01 2.69E-01 9.71 E-01 Kr-88 Ci 1.31 E-01 1.36E-01 1.46E-01 1.62E-01 5.75E-01 Xe-131m Ci

<LLD 2.28E-02

<LLD

<LLD 2.28E-02 Xe-133 Ci 1.33E-01 8.62E-02 1.42E-01 1.60E-01 5.21 E-01 Xe-135 Ci 2.22E-01 1.88E-01 2.12E-01 2.35E-01 8.57E-01 Xe-135m Ci 1.52E+00 1.55E+00 1.72E+00 1.89E+00 6.68E+00 Xe-138 Ci 5.67E+00 5.91E+00 6.53E+00 7.26E+00 2.54E+01 Total for Period Ci 8.54E+00 9.01E+00 9.70E+00 1.09E+01 3.82E+01 Iodines 1-131 Ci 1.87E-05

<LLD 1.92E-05

<LLD 3.79E-05 1-133 Ci 3.97E-04 1.19E-04 3.27E-04 2.64E-04 1.11E-03 1-135 Ci

<LLD

<LLD Total for Period Cl 4.16E-04 1.19E-04 3.46E-04 2.64E-04 1.15E-03 Particulates Cr-51 Ci

<LLD

<LLD Mn-54 Ci 3.11E-05 2.45E-05 1.04E-04 1.64E-04 3.24E-04 Co-58 Ci

<LLD

<LLD 5.59E-05 5.59E-05 Fe-59 Ci

<LLD

<LLD Co-60 Ci 2.46E-04 2.20E-04 4.37E-04 7.32E-04 1.64E-03 Zn-65 Ci 3.45E-05

<LLD

<LLD 5.69E-05 9.14E-05 Sr-89 Ci

<LLD

<LLD 1.76E-05 9.10E-06 2.67E-05 Sr-90 Ci

<LLD

<LLD Mo-99 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Total for Period Ci 3.12E-04 2.45E-04 5.59E-04 1.02E-03 2.14E-03 Tritium H-3 Ci 1.67E+01 1.89E+01 1.38E+01 1.51 E+01 6.45E+01 Gross Alpha Alpha Ci

<LLD

<LLD Carbon-14 C-14 Ci 6.65E+00 6.83E+00 7.29E+00 7.34E+00 2.81E+01 12 All LLDs comply with requirements listed in the ODCM.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 52 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 2.0 LIQUID EFFLUENTS Table 15, Liquid Effluents - Summation of All Releases Units 1 & 213 A.

Fission & Activation Products Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Est. Total Error%

1.

Total Release Ci

<LLD 8.99E-02

<LLD 2.76E-03 4.B0E+00

2.

Average diluted concentration

~1Ci/ml NIA 2.17E-10 N/A 7.39E-12 B.

Tritium

1.

Total Release Ci 4.96E-02 2.32E-01 4.54E-02 1.78E-01 4.10E+00 I

2.

Average diluted concentration

µCi/ml 1.94E-10 5.62E-10 9.18E-11 4.77E-10 C.

Dissolved & Entrained Gases

1.

Total Release Ci

<LLD

<LLD 4.80E+00 I

2.

Average diluted concentration

~1Ci/ml NIA NIA N/A NIA D.

Gross Alpha Activity

1.

Total Release Ci

<LLD

<LLD 1.47E+01 E.

Volume of Waste Released (prior Liters 1.80E+07 1.20E+10 2.03E+07 1.28E+07 to dilution)

F.

. Volume of Dilution Water Used Liters 2.55E+11 4.13E+11 4.94E+11 3.73E+11 During Period 13 % of limit is provided in Table 1, Quad Cities Nuclear Power Station Units 1 and 2 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 53 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 16, Batch Mode Liquid Effluents Unis 1 & 214 Radionuclide Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Fission and Activation Products 1<'

~~

Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD 4.59E-05 4.59E-05 Fe-55 Ci

<LLD

<LLD 1.67E-03 1.67E-03 Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD 5.00E-04 5.00E-04 Zn-65 Ci

<LLD

<LLD 4.0SE-04 4.0SE-04 Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Mo-99 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 1.34E-04 1.34E-04 Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD 2.75E-03 2.75E-03 Tritium H-3 Ci

<LLD

<LLD 1.78E-01 1.78E-01 Gross Alpha Alpha Ci

<LLD

<LLD Entrained Gases Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-133m Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD 14 All LLDs comply with requirements listed in the ODCM.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 54 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 17, Continuous Mode Liquid Effluents Unit 1 & 215 Radionuclide Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Fission and Agtlv!Jtion Products Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD 1,09E-02

<LLD

<LLD 1,09E-02 Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD 3,39E-03

<LLD

<LLD 3,39E-03 Co-58 Ci

<LLD 3,85E-02

<LLD

<LLD 3,85E-02 Co-60 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Sr-89 Ci

<LLD 3.70E-02

<LLD

<LLD 3,70E-02 Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Mo-99 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 Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Total for Period Ci

<LLD 8,99E-02

<LLD

<LLD 8,99E-02 Tritium H-3 Ci 4,96E-02 2.32E-01 4.54E-02

<LLD 3,27E-01 Gross Alpha Alpha Ci

<LLD

<LLD Entrained Gases Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-133m Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD 15 All LLDs comply with requirements listed in the ODCM.

,=, Constellation, Quad Cities Nuclear Power Station, Solid Waste Information 1.0 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Table 18, Types of Solid Waste Summary Units 1 & 2 Total Volume Total Activity Types of Waste (m3)

(Ci)

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

1.48E+02 7.92E+02

b. Dry compressible waste, contaminated equip, etc.

8.94E+02 2.98E+00

c. Irradiated components, control rods, etc.

0.00E+00 0.00E+00

d. Other (describe) 4.62E+01 8.37E-03 Est. Total Error

(%)

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

ARE REPORTED. [NOTE 1]

Table 19, Major Nuclides Units 1 & 2 Major Nuclide Composition Curies

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

Fe-55 48.09 3.81E+02 Co-60 42.49 3.37E+02 Cs-137 2.61 2.07E+01 Zn-65 2.54 2.01E+01 Mn-54 2.51 1.99E+01 Ni-63 1.42 1.13E+01

b. Dry compressible waste, contaminated equip, etc.

Co-60 48.42 1.44E+00 Fe-55 37.39 1.12E+00 Mn-54 6.93 2.07E-01 Zn-65 3.31 9.88E-02 Cs-137 1.53 4.55E-02

c. Irradiated components, control rods, etc.

None NIA NIA

d. Other (describe)

Fe-55 54.66 4.58E-03 Co-60 34.16 2.86E-03 Mn-54 5.09 4.27E-04 Zn-65 2.07 1.74E-04 Ni-63 1.76 1.47E-04

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 56 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 3.0 SOLID WASTE DISPOSITION Table 20, Solid Waste Disposition Units 1 & 2 Number of Mode of Transportation Shipments Destination 32 HITTMAN TRANSPORT EnergySolutions LLC, Clive Disposal Site Containerized Waste Facility 18 HITTMAN TRANSPORT EnergySolutions Services Inc, (Oakridge) 1560 Bear Creek Road 4.0 IRRADIATED FUEL DISPOSITION No Irradiated Fuel Shipments were made in the reporting year.

~

Constellation.

Quad Cities Nuclear Power Station 1.0 1.1, Meteorological Data METEOROLOGICAL DATA

SUMMARY

Joint Frequency Distributions

1.

Period of Record: 2024

2.

Stability Class: All

a.

Periods of calm (hours): 181

b.

Hours of missing data: 105

c.

Meteorological data are reported in number of hours for all stability classes.

d.

Elevation: 33 ft.

Wind Speed (mph)

Wind 1-3 4-7 8-12 13-18 19-24

>24 Direction N

63 209 138 17 0

0 NNE 79 142 78 12 0

0 NE 138 179 72 2

0 0

ENE 170 230 49 1

0 0

E 276 312 150 5

0 0

ESE 260 323 144 20 0

0 SE 178 289 37 4

0 0

SSE 160 236 39 1

0 0

s 104 199 58 0

0 0

SSW 134 378 104 1

0 0

SW 135 264 102 8

0 0

WSW 122 250 101 20 0

0 w

144 435 192 76 0

0 WNW 141 407 401 59 3

0 NW 98 287 140 8

0 0

NNW 67 224 102 0

0 0

VARIABLE 0

0 0

0 Total 2269 4364 1907 234 3

0 Total 427 311 391 450 743 747 508 436 361 617 509 493 847 1011 533 393 0

8777

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 58 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2

3.

Stability Class: All Wind Direction N

NNE NE ENE E

ESE SE SSE s

SSW SW WSW w

WNW NW NNW VARIABLE Total

a.

Periods of calm (hours): 1

b.

Hours of missing data: 20

c.

Meteorological data are reported in number of hours for all stability classes.

d.

Elevation: 296 ft 1-3 4-7 8-12 13 -18 19-24

>24 11 50 167 159 31 0

8 68 142 107 37 1

12 47 135 130 25 3

12 67 142 99 18 2

12 85 213 136 19 3

6 50 159 209 124 39 5

79 208 226 70 26 7

65 204 230 93 18 9

58 143 243 108 37 8

76 189 258

' 117 40 10 91 125 194 71 16 12 82 130 143 63 20 19 103 176 215 90 47 9

75 227 294 121 53 9

83 235 376 151 44 10 64 182 169 43 4

0 0

159 1143 2777 3188 1181 353 Total 418 363 352 340 468 587 614 617 598 688 507 450 650 779 898 472 0

8801

Annual Radioactive Effluent Release Report

-1 YEAR: 2024 [

Page 59 of 59 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 21, Classification of Atmospheric Stability based on the 196-33 ft differential.

Stability Condition Pasquill Categories Percentage Extremely Unstable A

7.22 Moderately Stable B

3.12 Slightly Unstable C

6.10 Neutral D

39.54 Slightly Stable E

28.02 Moderately Stable F

8.49 Extremely Stable G

7.50 Table 22, Classification of Atmospheric Stability based on the 296-33 ft differential.

Stability Condition Pasquill Categories Percentage Extremely Unstable A

2.36 Moderately Stable B

5.34 Slightly Unstable C

7.22 Neutral D

43.34 Slightly Stable E

26.16 Moderately Stable F

9.09 Extremely Stable G

6.51

SVP-25-022, Radioactive Effluent Release Report for 2024

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SVP-25-022, Radioactive Effluent Release Report for 2024

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