Text

Revision to 2024 Annual Radioactive Effluent Release Report
	ML25226A101
Person / Time
Site:	Dresden
Issue date:	08/08/2025
From:	Hardik Patel; Constellation Energy Generation
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	SVPLTR 25-0054
	Download: ML25226A101 (1)
	v • d • e

Constellation August 8, 2025 SVPL TR# 25-0054 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station Units 1, 2, and 3 Facility Operation License No. DPR-2 Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450 10 CFR 50 Appendix I Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRG Docket Nos.50-010, 50-237, and 50-249

Subject:

Revision to Dresden Nuclear Power Station 2024 Annual Radioactive Effluent Release Report Enclosed is a Revision to Constellation Dresden Nuclear Power Station 2024 Annual Radioactive Effluent Release Report, submitted in accordance with Section 6.9.A.4 of the Unit 1 Dresden Nuclear Power Station Technical Specifications and Section 5.6.3, "Radioactive Effluent Release Report," of the Units 2 and 3 Technical Specifications. The 2024 Annual Radioactive Effluent Release Report did not include a new milk sample location that was identified in June 2024. The input was corrected and is accurately reflected under the Land Use Census Changes.

Should you have any questions concerning this letter, please contact Daniel J. Murphy, Regulatory Assurance Manager, at (779) 231-7443.

Respectfully,

~2,.

Hardik Patel Site Vice President Dresden Nuclear Power Station 024 Annual Radioactive Effluent Release Report (Revised)

bee:

Constellation Document Control Desk Licensing Kevin Lueshen, Director - Corp Licensing and Regulatory Affairs Mark Humphrey, Sr. Manager - Corp Licensing, Dresden Nuclear Power Station Hardik Patel, Site Vice President - Dresden Nuclear Power Station Joseph Reda, Plant Manager - Dresden Nuclear Power Station Jake Murphy - Manager of Regulatory Assurance Michael McGuire - Sr Manager of Regulatory and Learning Programs Operations Director Tara Noah, Regulatory Assurance Erin Whitsell, Corporate Licensing Christopher Hisey, Manager of Chemistry and Radwaste Komail Haider, Chemistry Supervisor Joseph Jaegers, Sr Manager Site Radiation Protection SVP Numerical File - SVPLTR # 25-0054 ANI nuclear insurers REMP Coordinator - Dresden Nuclear Power Station SRRS 2C.111

Constellation Dresden Clean Energy Center Annual Radioactive Effluent Release Report 2024 Rev. 1 Document Numbers: 50-010/50-237/50-249 Units 1, 2, and 3

Annual Radioactive Effluent Release Report Rev. 1 YEAR: 2024 Page 1 of 64 Dresden Clean Ener Center 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

............................................................................................................................ 12 3.1 About Nuclear Power......................................................................................................... 12 3.2 About Radiation Dose........................................................................................................ 14 3.3 About Dose Calculation..................................................................................................... 15 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS.................................................................... 17 4.1 Regulatory Limits............................................................................................................... 17 4.2 Regulatory Limits for Gaseous Effluent Doses:................................................................ 18 4.3 Gaseous Effluent Monitoring........................................................................................... 19 4.4 Regulatory Limits for Liquid Effluent Doses...................................................................... 20 4.5 Liquid Effluent Monitoring.................................................................................................. 20 4.6 40 CFR 190 Regulatory Dose Limits for a Member of the Public..................................... 21 4.7 Onsite Doses (Within Site Boundary)................................................................................ 21 5.0 SUPPLEMENTAL INFORMATION................................................................................................ 22 5.1 Gaseous Batch Releases.................................................................................................. 22 5.2 Liquid Batch Releases....................................................................................................... 22 5.3 Abnormal Releases............................................................................................................ 23 5.4 Land Use Census Changes............................................................................................... 23 5.5 Meteorological Data........................................................................................................... 23 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days.................................. 23 5.7 Offsite Dose Calculation Manual (ODCM) Changes......................................................... 23 5.8 Process Control Program (PCP) Changes........................................................................ 23 5.9 Radioactive Waste Treatment System Changes.............................................................. 23 5.10 Direct Radiation.................................................................................................................. 23 5.11 Carbon-14.......................................................................................................................... 29 5.12 Errata/Corrections to Previous ARERRs........................................................................... 29 5.13 Other Supplemental lnformation........................................................................................ 30 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM................ 30 6.1 Voluntary Notification......................................................................................................... 30 7.0 BIBLIOGRAPHY............................................................................................................................ 31 TABLES Table 1, Dresden Clean Energy Center Unit 1 Dose Summary................................................................ 8 Table 2, Dresden Clean Energy Center Unit 2 Dose Summary................................................................ 9 Table 3, Dresden Clean Energy Center Unit 3 Dose Summary.............................................................. 10 Table 4, Total Annual Off site-Dose Comparison to 40 CFR 190 Limits for DCEC................................. 11

Annual Radioactive Effluent Release Report Rev. 1 YEAR: 2024 Page 2 of 64 Dresden Clean Energy Center TABLE OF CONTENTS Table 5, Gaseous Effluents Summation of All Releases Unit 1............................................................... 32 Table 6, Gaseous Effluents Summation of All Releases Unit 2............................................................... 33 Table 7, Gaseous Effluents Summation of All Releases Unit 3............................................................... 34 Table 8, Gaseous Effluents - Ground Level Release Batch Mode Unit 1............................................... 35 Table 9, Gaseous Effluents - Ground Level Release Continuous Mode Unit 1..................................... 36 Table 10, Gaseous Effluents - Ground Level Release Batch Mode Unit 2............................................. 37 Table 11, Gaseous Effluents - Ground Level Release Continuous Mode Unit 2................................... 38 Table 12, Gaseous Effluents - Ground Level Release Batch Mode Unit 3............................................. 39 Table 13, Gaseous Effluents - Ground Level Release Continuous Mode Unit 3................................... 40 Table 14, Gaseous Effluents - Mixed Level Release Batch Mode Unit 1............................................... 41 Table 15, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 1...................................... 42 Table 16, Gaseous Effluents-Mixed Level Release Batch Mode Unit 2............................................... 43 Table 17, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 2...................................... 44 Table 18, Gaseous Effluents - Mixed Level Release Batch Mode Unit 3............................................... 45 Table 19, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 3...................................... 46 Table 20, Gaseous Effluents - Elevated Level Release Batch Mode Unit 1........................................... 47 Table 21, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 1................................. 48 Table 22, Gaseous Effluents - Elevated Level Release Batch Mode Unit 2........................................... 49 Table 23, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 2................................. 50 Table 24, Gaseous Effluents - Elevated Level Release Batch Mode Unit 3........................................... 51 Table 25, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 3................................. 52 Table 26, Liquid Effluents - Summation of All Releases Unit 1............................................................... 53 Table 27, Liquid Effluents - Summation of All Releases Unit 2............................................................... 54 Table 28, Liquid Effluents - Summation of All Releases Unit 3............................................................... 55 Table 29, Liquid Effluents Batch Mode Unit 1.......................................................................................... 56 Table 30, Liquid Effluents Continuous Mode Unit 1................................................................................. 57 Table 31, Liquid Effluents Batch Mode Unit 2.......................................................................................... 58 Table 32, Liquid Effluents Continuous Mode Unit 2................................................................................. 59 Table 33, Liquid Effluents Batch Mode Unit 3.......................................................................................... 60 Table 34, Liquid Effluents Continuous Mode Unit 3................................................................................. 61 Table 35, Types of Solid Waste Summary Site........................................................................................ 62 Table 36, Major Nuclides Site................................................................................................................... 62 Table 37, Solid Waste Disposition Site.................................................................................................... 63 FIGURES Figure 1, Pressurized Water Reactor (PWR) [1]...................................................................................... 12 Figure 2, Boiling Water Reactor (BWR) [2].............................................................................................. 13 Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3].................................................... 14 Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6].............. 16

Annual Radioactive Effluent Release Report Rev. 1 TABLE OF CONTENTS ATTACHMENTS YEAR: 2024 Page 3 of 64 Dresden Clean Ener Center, ARERR Release Summary Tables (RG-1.21 Tables)...................................................... 32, Solid Waste Information.................................................................................................... 62, 2024 Annual RGPP Monitoring Report............................................................................. 64

Annual Radioactive Effluent Release Report YEAR: 2024 Page 4 of 64 Dresden Clean Ener Center 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 NRG and are typically listed in the ODCM.

13.

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

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

14.

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

15.

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

I Annual Radioactive Effluent Release Report YEAR: 2024 Page 5 of 64 Dresden Clean Ener Center

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: Off site Dose Calculation Manual

23.

OSLO: Optically Stimulated Luminescence Dosimeter

. 24.

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

25.

PWR: Pressurized Water Reactor

26.

REC: Radiological Effluent Control

27.

REMP: Radiological Environmental Monitoring Program

28.

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

29.

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

30.

TLD: Thermoluminescent Dosimeter

31.

TRM : Technical Requirements Manual

32.

TS: Technical Specification

33.

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

Annual Radioactive Effluent Release Report YEAR: 2024 Page 6 of 64 Dresden Clean Ener Center 2.0 EXECUTIVE

SUMMARY

Dresden Clean Energy Center (DCEC) 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 Dresden Clean Energy Center is the infant. The maximum Annual Organ Dose calculated for this receptor from the site was 2.14E-02 mrem to the thyroid.

The maximum dose calculated to any organ due to radioactive liquid effluents was 1.92E-09 mrem for child total body.

Solid radioactive waste shipped off site for processing or direct disposal included 1.48E+02 Curies and 1.02E+03 m3, shipped in 48 shipments.

In addition to monitoring radioactive effluents, DCEC 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 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Energy Center 2.1 Comparison to Regulatory Limits During 2024 all liquid and gaseous radioactive effluents from Dresden Clean Energy Center were well below regulatory limits, as summarized in Table 1, Dresden Clean Energy Center Unit 1 Dose Summary, Table 2, Dresden Clean Energy Center Unit 2 Dose Summary, Table 3, Dresden Clean Energy Center Unit 3 Dose Summary, and Table 4, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for DCEC.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 8 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Energy Center Table 1, Dresden Clean Energy Center Unit 1 Dose Summary1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Limit 1.5mrem 1.5 mrem 1.5 mrem 1.5 mrem 3mrem Dose Limit, Total Body Dose N/A N/A N/A N/A N/A Total Body

% of Limit N/A N/A N/A N/A N/A Liquid Effluent Limit 5mrem 5mrem 5mrem 5mrem 10 mrem Dose Limit, Max Organ Dose N/A N/A N/A N/A N/A Any Organ

% of Limit N/A N/A N/A N/A N/A Gaseous Effluent Limit 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Dose Limit, Gamma Air Dose N/A N/A N/A N/A N/A Gamma Air (Noble Gas)

% of Limit N/A N/A N/A N/A N/A Gaseous Effluent Limit 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Dose Limit, Beta Air Dose N/A N/A N/A N/A N/A Beta Air (Noble Gas)

% of Limit N/A N/A N/A N/A N/A Gaseous Effluent Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ Dose Limit Max Organ Dose 6.77E-04 6.77E-04 6.77E-04 6.77E-04 2.71E-03 (Iodine, Tritium, Particulates with

> 8-day half-life)

% of Limit 9.02E-03 9.02E-03 9.02E-03 9.02E-03 1.B0E-02 1 Table 1 demonstrates compliance with 10 CFR Part 50, App. I Limits.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 9 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Energy Center Table 2, Dresden Clean Energy Center Unit 2 Dose Summary1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Limit 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3mrem Dose Limit, Total Body Dose N/A 9.58E-10 N/A N/A 9.58E-10 Total Body

% of Limit N/A 6.39E-08 N/A N/A 3.19E-08 Liquid Effluent Limit 5mrem 5mrem 5mrem 5mrem 10 mrem Dose Limit, Max Organ Dose N/A 9.58E-10 N/A N/A 9.58E-10 Any Organ

% of Limit N/A 1.92E-08 N/A N/A 9.58E-09 Gaseous Effluent Limit 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Dose Limit, Gamma Air Dose 1.02E-04 9.95E-05 1.62E-04 1.18E-04 4.81E-04 Gamma Air (Noble Gas)

% of Limit 2.04E-03 1.99E-03 3.24E-03 2.36E-03 4.81E-03 Gaseous Effluent Limit 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Dose Limit, Beta Air Dose 3.15E-06 3.30E-06 5.75E-06 4.42E-06 1.66E-05 Beta Air (Noble Gas)

% of Limit 3.15E-05 3.30E-05 5.75E-05 4.42E-05 8.30E-05 Gaseous Effluent Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ Dose Limit Max Organ Dose 1.48E-03 1.99E-03 2.49E-03 1.68E-03 7.64E-03 (Iodine, Tritium, Particulates with

> 8-day half-life)

% of Limit 1.97E-02 2.65E-02 3.32E-02 2.24E-02 5.09E-02 1 Table 2 demonstrates compliance with 10 CFR Part 50, App. I Limits.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 1 O of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Enerav Center Table 3, Dresden Clean Energy Center Unit 3 Dose Summary1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Limit 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3mrem Dose Limit, Total Body Dose NIA 9.58E-10 NIA NIA 9.58E-10 Total Body

% of Limit NIA 6.39E-08 NIA NIA 3.19E-08 Liquid Effluent Limit 5mrem 5mrem 5mrem 5mrem 10 mrem Dose Limit, Max Organ Dose NIA 9.58E-10 NIA NIA 9.58E-10 Any Organ

% of Limit NIA 1.92E-08 NIA NIA 9.58E-09 Gaseous Effluent Limit 5mrad 5 mrad 5 mrad 5 mrad 10 mrad Dose Limit, Gamma Air Dose 6.09E-05 5.12E-05 9.24E-05 6.70E-05 2.72E-04 Gamma Air (Noble Gas)

% of Limit 1.22E-03 1.02E-03 1.85E-03 1.34E-03 2.72E-03 Gaseous Effluent Limit 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Dose Limit, Beta Air Dose 1.86E-06 1.79E-06 3.67E-06 2.53E-06 9.86E-06 Beta Air (Noble Gas)

% of Limit 1.86E-05 1.79E-05 3.67E-05 2.53E-05 4.93E-05 Gaseous Effluent Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ Dose Limit Max Organ Dose 3.43E-03 3.51E-03 3.43E-03 2.61E-03 1.30E-02 (Iodine, Tritium, Particulates with

% of Limit 4.57E-02 4.68E-02 4.57E-02 3.48E-02 8.67E-02

> 8-day half-life) 1 Table 3 demonstrates compliance with 10 CFR Part 50, App. I Limits.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 11 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Enerav Center Table 4, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for DCEC1 Whole Body Thyroid Max Other Organ Gaseous2 3.59E-03 2.0?E-02 3.96E-03 Carbon-14 1.03E-02 1.03E-02 5.16E-02 Liquid 1.92E-09 1.92E-09 1.92E-09 Direct Shine 5.10E+00 5.10E+00 5.10E+00 Total Site Dose 5.11 E+00 5.13E+00 5.16E+00 Total w/Other Nearby 5.21E+00 5.23E+00 5.25E+00 Facility3 Limit 25 mrem 75 mrem 25 mrem

% of Limit 20.8 6.97 21 1 Table 4 is a summation of Units to show compliance with 40 CFR Part 190 Limits.

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

3 Other fuel cycle sources within 5 miles of the site are considered in this analysis. GE Hitachi Morris Operations 2023 dose contribution 9.80E-02 mrem.

Annual Radioactive Effluent Release Report YEAR: 2024 Page 12 of 64

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Com an : Constellation Ener Generation Plant:

Dresden Clean Enerav Center

3.0 INTRODUCTION

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

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

Annual Radioactive Effluent Release Report YEAR: 2024 Page 13 of 64 Com an : Constellation Ener Generation Plant:

Dresden Clean Ener Center 3.1 (Continued)

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

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

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

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

Annual Radioactive Effluent Release Report YEAR: 2024 Page 14 of 64 Dresden Clean Ener Center 3.2 About Radiation Dose Ionizing radiation, including alpha, beta, and gamma radiation from radioactive decay, has enough energy to break chemical bonds in tissues and result in damage to tissue or genetic material. The amount of ionization that will be generated by a given exposure to ionizing radiation is quantified as dose. Radiation dose is generally reported in units of millirem (mrem) in the US.

Computed tomography (medical)

(24%)

Terrestrial (background)

(3%)

Nuclear medicine (medical)

(12%)

Space Internal (background)

(background)

(S3/4)

(5%)

lnterventional fluoroscopy (medical)

(7%)

Radon & thoron (background)

(37%)

Industrial

(<0.1%)

Occupational

(<0.1%)

Consumer Conventional radiography/fluoroscopy (medical)

{5%)

{2%)

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

Annual Radioactive Effluent Release Report YEAR: 2024 Page 15 of 64 Dresden Clean Ener Center 3.2 (Continued)

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

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

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

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 a 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.

Annual Radioactive Effluent Release Report Company: Constellation Energy Generation I Plant:

3.3 (Continued)

Gaseous effiuents 0

~

I CD I YEAR: 2024 I Page 16 of 64 Dresden Clean Enerav Center o

Raclionuclides

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

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

The dose assessment methodology in the ODCM is based on 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.

Annual Radioactive Effluent Release Report YEAR: 2024 Page 17 of 64 Dresden Clean Ener Center 3.3 (Continued) 4.0 4.1 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 the radiation dose due to 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.

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 DCEC must adhere. DCEC 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 DCEC 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 2.0E-04 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, Dresden Clean Energy Center Unit 1 Dose Summary, Table 2, Dresden Clean Energy Center Unit 2 Dose Summary, Table 3, Dresden Clean Energy Center Unit 3 Dose Summary, and Table 4, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for DCEC.

4.2 Annual Radioactive Effluent Release Report YEAR: 2024 Page 18 of 64 Dresden Clean Ener Center 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 m rads beta

2)

Yearly a)

Less than or equal to 10 mrads gamma b)

Less than or equal to 20 mrads beta

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 m rem/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

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 19 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Enerav Center 4.3 Gaseous Effluent Monitoring The 2/3 Chimney (elevated), and 2/3 Reactor Building Vent (mixed mode) are continuously sampled for iodine and particulates. These samples are obtained weekly and analyzed by gamma spectroscopy. The particulate filters are composited and sent to a vendor for gross alpha, Sr-89, Sr-90, Ni-63 and Fe-55 analysis quarterly. Noble gas grab samples of the 2/3 Chimney and 2/3 Reactor Building Vent are obtained weekly and analyzed by gamma spectroscopy. Contributing streams of the 2/3 Chimney and 2/3 Reactor Building Vent are also sampled and analyzed by gamma spectroscopy. Tritium samples of the 2/3 Chimney and 2/3 Reactor Building Vent are obtained monthly and analyzed by liquid scintillation.

Unit 1 Chemical Cleaning Building (mixed mode) effluents, as per ODCM requirements, only require continuous iodine and particulate sampling when ventilation is in service. Both trains of Unit 1 Chem Cleaning ventilation have been out of service since 2019 and 2021, respectively {IR 4281629 and 4460047).

Continuous sampling is not in progress. However, weekly Dresden Radiation Protection provide weekly air samples which are analyzed in the Dresden counting room.

For the 2/3 Chimney and 2/3 Reactor Building Vent effluents, the resultant activity concentration and measured flowrate at the release points are used to calculate the curies released. For the Chemical Cleaning Building effluent, the design basis flows are used to calculate curies released.

The Unit 1 Main Turbine Floor is used as an area to work on contaminated equipment. The Unit 1 Fuel Building is used as a storage area and potentially as a work area. The ventilation systems to these areas are no longer operational and the areas are at ambient pressure with the outside environment. The potential exists for airborne activity to be released to the environment through various points. Based on the work normally performed in these areas, an estimated 6.00E-06 Ci of Cs-137 was released via this path per month for a total of 7.20E-05 Ci during 2024.

The Unit 2/3 Heating Steam System has been contaminated in the past and occasionally contains low-level contamination. During normal operation, the condensate is converted to steam, a portion of which gets vented to the atmosphere.

If tritium was identified above minimum detectable activity in 2024, permits are generated for the appropriate activity released. This will continue to be monitored when the system is running.

The Chemistry Laboratory exhausts directly into the environment via its ventilation system and is not monitored. The activity concentration from the Offgas Recombiner samples taken weekly from each unit and the sample size (15 cc) was used to calculate a monthly activity released from each unit from the Chemistry Hot Lab fume hood. This activity was captured in the monthly 10CFR50 Appendix I calculation and is included in the noble gas totals in Table 11, Gaseous Effluents - Ground Level Release Continuous Mode Unit 2 and Table 13, Gaseous Effluents - Ground Level Release Continuous Mode Unit 3.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 20 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Energy Center 4.4 4.5 Regulatory Limits for Liquid Effluent Doses

1.

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

a.

Quarterly

1)

Less than or equal to 1.5 mrem total body

2)

Less than or equal to 5 mrem critical organ

b.

Yearly

1)

Less than or equal to 3 mrem total body

2)

Less than or equal to 10 mrem critical organ Liquid Effluent Monitoring The Waste Surge Tank (WST) utilized for river discharges is analyzed for gamma-emitting nuclides by gamma spectroscopy and for tritium by liquid scintillation prior to discharge. A representative portion of this sample is saved and composited with other discharges that occur du ring the calendar month.

The composite is sent to a vendor for analyses of gross alpha, Sr-89, Sr-90, Ni-63, and Fe-55. The tank volumes and activities are used to calculate the diluted activity released at the discharge point from batch discharges. If discharges from the Waste Surge Tank occurred, the information is captured in batch release information.

Containment Cooling Service Water (CCSW) is sampled from the Low-Pressure Coolant Injection (LPCI) heat exchangers monthly and analyzed for gamma-emitting nuclides by gamma spectroscopy. These samples are composited quarterly and analyzed for tritium, gross alpha, Sr-89, Sr-90, Fe-55, and Ni-63. Results are conservatively applied for each month of the quarter. Batch release volume is based on LPCI heat exchanger volume.

On-site storm sewers are sampled and analyzed for tritium content. The CBG well tritium concentration measured during each month of 2024 was used to calculate the released activity for each month via the storm sewers. The volume was based on the monthly rain fall over a 100,000 sqft area of the Site.

Water in the Sewage Treatment Plant (STP) effluent is routinely sampled and analyzed for tritium, gross alpha, Sr-89, Sr-90, Fe-55, and Ni-63.

Beginning in September 2019, groundwater from the West Tritium Remediation Well was monitored via the 2/3 Discharge Tunnel. Although this

Annual Radioactive Effluent Release Report YEAR: 2024 Page 21 of 64 Dresden Clean Ener Center is a planned continuous release, it is mentioned here due to its relatively short duration over this life of the plant.

The estimated calculated dose from all these releases was well below the regulatory limit of 25 mrem/yr for the whole body and 75 mrem/yr Thyroid as well as all quarterly dose limits.

4.6 40 CFR 190 Regulatory Dose Limits for a Member of the Public 4.7

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.

Onsite Doses (Within Site Boundary)

Dresden Clean Energy Center does not have members of the public or non-occupationally exposed individuals on site. Doses calculated to site boundary are sufficient in demonstrating these individuals do not receive dose exposure in excess of 100 mrem per year TEDE as per 10 CFR 20.1301 requirements.

Annual Radioactive Effluent Release Report I

YEAR: 2024 I

Page 22 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Energy Center 5.0 SUPPLEMENTAL INFORMATION 5.1 Gaseous Batch Releases 5.1.1 DCEC Site Units Quarter Quarter Quarter Quarter Annual 1

2 3

4

1. Number of Batch Releases 0

0 0

2. Total duration of batch releases minutes O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Maximum batch release duration minutes O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

4. Average batch release duration minutes O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

5. Minimum batch release duration minutes O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Number of batch releases 0

Total time period for a batch release 0.00E+00 minutes Maximum time period for a batch release 0.00E+00 minutes Average time period for a batch release 0.00E+00 minutes Minimum time period for a batch release 0.00E+00 minutes 5.2 Liquid Batch Releases 5.2.1 DCEC Site Units Quarter Quarter Quarter Quarter Annual 1

2 3

4

1. Number of Batch Releases 0

0 0

2. Total duration of batch releases minutes O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Maximum batch release duration minutes O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

4. Average batch release duration minutes O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

5. Minimum batch release duration minutes O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

6. Avg stream flow during periods of Ft3/sec release of liquid effluent into a N/A N/A N/A N/A N/A flowing stream Number of batch releases 0

Total time period for a batch release 0.00E+00 minutes Maximum time period for a batch release 0.00E+00 minutes Average time period for a batch release 0.00E+00 minutes Minimum time period for a batch release 0.00E+00 minutes Average total flow during period of release 0.00E+00 gpm

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 23 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Enerav Center 5.3 Abnormal Releases 5.3.1 Gaseous Abnormal Releases Number of releases 0

Total activity released O.OOE+OO Ci 5.3.2 Liquid Abnormal Releases Number of releases 0

Total activity released O.OOE+OO Ci 5.4 Land Use Census Changes 5.5 5.6 5.7 5.8 5.9 A new milk sample location was identified in June 2024 (IR 04780725). The corrective action to perform ODCM revision was not completed in a timely manner to include the new location in the REMP schedule however samples were taken and analyzed monthly. All samples were below LLD.

Meteorological Data Meteorological data collected for 2024 met the 90% data accumulation requirement.

Average data recovery was 99.8%. The Joint Frequency Distribution tables are available on site per request for 2024.

Effluent Radiation Monitors Out of Service Greater Than 30 Days No effluent radiation monitors were out of service greater than 30 days in 2024.

Offsite Dose Calculation Manual (ODCM) Changes No changes to the ODCM were made in 2024.

Process Control Program (PCP) Changes No changes to PCP were made in 2024.

Radioactive Waste Treatment System Changes No changes to the radioactive waste treatment system were made in 2024.

5.10 Direct Radiation There are five identified sources of direct radiation dose that meets the definition referenced in 10CFR72.104 and must be added to the gaseous and liquid effluents dose. They are:

1.

Skyshine

2.

West Independent Spent Fuel Storage Installation (ISFSI) Pad

3.

East ISFSI Pad

4.

Condensate Storage Tanks (CST)

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 24 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Energy Center

5.

General Electric Facility is located southwest of the plant on Collins Road.

5.10.1 Skyshine The radioactivity source that results in the most significant off site radiation dose at the Dresden Clean Energy Center is skyshine resulting from 16N decay inside turbines and steam piping.

The 16N that produces the skyshine effect is formulated through neutron activation of the oxygen atoms in the reactor coolant as the coolant passes through the operating reactor core.

The 16N travels with the steam produced in the reactor to the steam-driven turbine. While the 16N is in transport, it radioactively decays with a half-life of about 7 seconds and produces 6-7 MeV gamma rays. Typically, offsite dose points are shielded from a direct view of components containing 16N, but there can be skyshine at offsite locations due to scattering of gamma rays off the mass of air above the steam lines and turbine.

The dose rate due to skyshine has been found to have the following dependencies:

1.

The dose rate decreases as distance from the station increases.

2.

The dose rate increases non-linearly as the power production level increases.

3.

The dose rate increases when hydrogen is added to the reactor coolant, an action taken to improve reactor coolant chemistry characteristics.

To calculate offsite dose due to skyshine in each time period, DCEC must track the following parameters:

1.

The total gross energy Eh produced with hydrogen being added.

2.

The total gross energy Eo produced without hydrogen being added.

The turbines at the site are sufficiently close to each other so that energy generated by the two operating units may be summed together. Because the hydrogen addition system is normally in-service during plant operation, the conservative assumption that all power is generated during hydrogen addition can be used.

An initial estimate of skyshine dose is calculated using equation 5-1 on page 11.5.4 in the Dresden Off site Dose Calculation Manual with the following assumptions from Table 5.1 on page 11.5-11 :

Parameters for Calculations of N-16 Skyshine Radiation from Dresden Units 2 and 3 Shielding Location Occupancy Occupancy Factor Number K Activity Hours (OH}

Factor (OF}

(SF}

Distance (R}

1 Living at Home 8344 0.95 0.7 800 2

Fishing 416 0.05 1

610

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 25 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Enerav Center These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of the public using Equation 5-1. If desired, more realistic parameters could be used in place of these to refine the estimate. For example, one could determine whether the nearest resident really fishes the specified number of hours at the specified location.

1.

The amount of time in a year that a maximally exposed fisherman would spend fishing near the site is estimated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per week for 8 months per year.

This yields an estimate of:

a.

[12 hours/week] x [(8 months/yr)/(12 months/yr)] x [52 weeks/yr]= 416 hour0.00481 days 0.116 hours 6.878307e-4 weeks 1.58288e-4 months s/yr

b.

The remaining time is assumed to be spent at the nearest residence.

2.

Distance to nearest residence (See ODCM Table 4-1).

a.

Estimated from a drawing of the site.

b.

The OFk is the quotient of the number of hours a location is occupied and the number of hours in a year. Thus OHk/8760 hours= OFk rounded to the 0.01 digit.

3.

A survey of the nearest residents revealed that as they do enjoy fishing, they spend far less time than the above estimate. In addition, because they live on the Kankakee River, they enjoy fishing at their homes rather than the designated 610 meters from the plant. As such, these assumptions have been adjusted to calculate a more accurate dose to the nearest resident at 868 meters from the plant with 8000 occupancy hours per year. This yielded a dose from Unit 2 due to skyshine of 2.29 mrem and 2.11 mrem from Unit 3 for a total of 4.40 mrem for the site.

5.10.2 Independent Spent Fuel Storage Installation There are currently two ISFSI pads (east and west) located within the Protected area of the Dresden station. These casks contain the spent fuel from the reactor, and the pad is designed to store the spent fuel until a more suitable location is available. Optically stimulated luminescence dosimeters (OSLO) are placed on the fence around the pads and exchanged semi-annually to measure the direct dose from the ISFSI pad. The dose from each location is summed to acquire an annual dose for that specific location a known distance from the casks.

The equation for a point source is used (DR,*D,2= DR2*D22) to calculate the annual dose to the nearest member of the public. The OSLO with the highest annual reading was used because they have a lesser contribution by percent of background radiation lending to more accuracy in the dose attributable only to the ISFSI pad.

Annual Radioactive Effluent Release Report

1.

West ISFSI Pad Dose Calculations Q1 Q2 0R1 (mrem) (mrem) (mrem/yr) 0 1 (ft) 23 24 25 26 27 28 599.0 781.4 399.5 131.9 303.1 224.0 938.1 948.2 458.7 137.5 338.6 254.9

a.

West ISFSI Pad 1537.1 136.18 1729.6 91.38 858.2 98.41 269.4 89.99 641.7 61.4 478.9 117.3 YEAR: 2024 Page 26 of 64 Dresden Clean Ener Center 0R2 02 (ft)

(mrem/yr) 2640 4.09 2640 2.07 2640 1.19 2640 0.31 2640 0.35 2640 0.95

Annual Radioactive Effluent Release Report Company: Constellation Enerav Generation I Plant:

2.

East ISFSI Pad Dose Calculations 17 18 19 20 21 22 Q1 Q2 DR1 (mrem) (mrem)

(mrem/yr) 57.5 58.3 115.8 73 74.6 147.6 61.4 63.9 125.3 64.7 78.4 143.1 227.6 282.1 509.7 67.6 79.2 146.8

a.

East ISFSI Pad ifflffiltiil*

1 Grunctt::7 LEJ 88.84 99.39 102.3 117.0 118.4 97.39 D2 (ft) 2660 2660 2660 2660 2660 2660 I YEAR: 2024 I Page 27 of 64 Dresden Clean Enerav Center DR2 (mrem/yr) 0.13 0.21 0.19 0.28 1.01 0.20 The highest annual dose received from the ISFSI pads were locations 21 and 23. These results and distances from the center of the pad were used to calculate a dose of 4.09E+00 mrem/yr for the West pad and 1.01 E+00 mrem/yr for the East pad. This resulted in a combined annual dose of 5.1 0E+00 mrem due to direct radiation from storage of spent fuel on the IFSFI pads.

Annual Radioactive Effluent Release Report YEAR: 2024 Page 28 of 64 Dresden Clean Ener Center 5.10.3 Condensate Storage Tank (CST)

The Condensate Storage Tanks (A and B) are a source of make-up water and has become contaminated through the operation of the plant. Although the level of contamination of the water inside the tank isn't at a level to produce a measurable dose rate, tanks are specifically listed in 40CFR 190 and a calculation of the annual dose to the nearest resident must be performed.

OSLO (07), was placed on the northeast perimeter fence of the 2/3 Condensate Storage Tank identical to those on the ISFSI pad, and as such will use the same methodology to calculate an annual dose.

1.

CST Dose Calculations Q1 Q2 DR1 (mrem) (mrem} (mrem/yr}

71117.41141.31 258.7 17 2/3 Condensate Storage Tanks D2 (ft}

2540 DR2 (mrem/yr}

0.012 Distance to Nearest Resident The approximate distance from the dosimeter on the fence to the edge of the tank is 17 ft.

Using the same equation and the distance to the nearest residence (2543 ft.)

DR1*Dl=DR2*D22 it yields an annual dose of 1.20E-02 mrem. These calculations are very conservative because the measured dose is almost entirely from background and not from the plant or storage tanks.

Annual Radioactive Effluent Release Report YEAR: 2024 Page 29 of 64 Dresden Clean Ener Center 5.10.4 GE Hitachi Nuclear Energy Facility This facility is located southwest of the Dresden Clean Energy Center on Collins Rd and is the location of a de facto high-level radioactive waste storage site that holds 772 tons of spent nuclear fuel. The used fuel from various nuclear generating sites across the country are stored in a spent fuel pool. The following table was taken from the NRC Technical Specifications for Safety Renewed License SNM-2500 for the GE Hitachi Energy Americas LLC Appendix A:

Since the source of radiation from the site is from the Uranium fuel cycle, the site is also required to ensure that the requirements of 40CFR190 and 10CFR72 are met.

Therefore, an Annual Operating Report is generated and submitted to the NRC to demonstrate that the regulatory limits are not exceeded to members of the public.

40CFR190 states that the annual whole-body dose to a member of the public shall not exceed 25 m rem/yr from all sources of the uranium fuel cycle. This distinction dictates that the sum of the dose from the operation of the Dresden Nuclear Power Station and the GE Hitachi Nuclear Energy site cannot cause a member of the public to exceed a whole-body dose of 25 mrem/year. As a result, communication from the two sites is necessary to exchange the calculated dose contributions to ensure this requirement is met. The dose contribution from the GE Hitachi site for the 2024 year was 9.B0E-02 mrem.

5.11 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.

The Carbon-14 activity released is determined using Electric Power Research Institute Report 1021106 Boiling Water Reactor proxy value of 5.1 Ci per GWth year, gaseous release fraction of 0.99%, a carbon dioxide fraction of 0.95, a reactor power rating of 2957 MWt for Units 2 and 3. The resultant dose due to C-14 was calculated using the C-14 worksheet. The equivalent full power days (EFPD) of operation of Unit 2 was: 364.2 EFPD and Unit 3 was: 335.6 EFPD which resulted in 15.05 Ci of C-14 from Unit 2 and 13.87 Ci from Unit 3 being produced in 2024. The calculated dose from C-14 produced from Unit 2 was 5.37E-03 mrem/yr (Total Body-Child) and 4.94E-03 mrem/yr (Total Body-Child) for Unit 3 for a Station total of: 1.03E-02 mrem/yr. The calculated dose from C-14 produced from Unit 2 was 2.68E-02 mrem/yr (Bone-Child) and 2.47E-02 mrem/yr (Bone-Child) for Unit 3.

C-14 activities are included in Table 23, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 2 and Table 25, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 3.

5.12 Errata/Corrections to Previous ARERRs None

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 30 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Eneray Center 5.13 Other Supplemental Information 5.13.1 Temporary Outside Tanks No tank exceeded ODCM or Tech Specs limits in 2024.

6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM Dresden Clean Energy Center has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document [9]. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning.

Refer to Attachment 3, 2024 Annual RGPP Monitoring Report for information regarding Dresden's Radiological Groundwater Monitoring Program for 2024.

6.1 Voluntary Notification During 2024, Dresden Clean Energy Center did not make a voluntary NEI 07-07 notification to State/Local officials, NRC, and to other stakeholders required by site procedures.

Annual Radioactive Effluent Release Report YEAR: 2024 Page 31 of 64 Dresden Clean Ener Center 7.0 BIBLIOGRAPHY

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

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

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

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

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

[Accessed 2020].

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

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

https:/ /www.jaea.go.jp/english/04/ntokai/houkan/houkan _ 02.htm I.

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

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

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

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

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

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

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

Nuclear Regulatory Commission, July, 2007.

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 32 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Energy Center, ARERR Release Summary Tables (RG-1.21 Tables) 1.0 GASEOUS EFFLUENTS Table 5, Gaseous Effluents Summation of All Releases Unit 11 A. Fission & Activation Quarter Quarter Quarter Quarter Est. Total Gases Unit 1

2 3

4 Annual Error%

1. Total Release Ci N/A N/A N/A N/A N/A 1.31E+01

2. Average release rate for µCi/sec N/A N/A N/A N/A N/A the period B. lodine-131

1. Total Release Ci N/A N/A N/A N/A N/A 2.60E+01

2. Average release rate for µCi/sec N/A N/A N/A N/A N/A the period C. Particulates

1. Total Release Ci 1.B0E-05 1.B0E-05 1.B0E-05 1.80E-05 7.20E-05 2.94E+01

2. Average release rate for µCi/sec 2.29E-06 2.29E-06 2.26E-06 2.26E-06 2.28E-06 the period D. Tritium

1. Total Release Ci N/A N/A N/A N/A N/A 7.56E+00

2. Average release rate for µCi/sec N/A N/A N/A N/A N/A the period E. Gross Alpha

1. Total Release Ci N/A N/A N/A N/A N/A 2.94E+01

2. Average release rate for µCi/sec N/A N/A N/A N/A N/A the period F. Carbon-14

1. Total Release Ci N/A N/A N/A N/A N/A

2. Average release rate for µCi/sec N/A N/A N/A N/A N/A the period 1 % of limit is provided in Table 1, Dresden Clean Energy Center Unit 1 Dose Summary

Annual Radioactive Effluent Release Report YEAR: 2024 Page 33 of 64 Dresden Clean Ener Center Table 6, Gaseous Effluents Summation of All Releases Unit 21 A. Fission & Activation Quarter Quarter Quarter Quarter Est. Total Gases Unit 1

2 3

4 Annual Error%

1. Total Release Ci 3.30E+00 2.99E+00 3.21E+00 2.26E+00 1.18E+01 1.31E+01

2. Average release rate for µCi/sec 4.20E-01 3.80E-01 4.04E-01 2.84E-01 3.72E-01 the period B. lodine-131

1. Total Release Ci 2.S0E-05 3.36E-05 4.18E-05 2.63E-05 1.27E-04 2.60E+01

2. Average release rate for µCi/sec 3.17E-06 4.27E-06 5.26E-06 3.31 E-06 4.00E-06 the period C. Particulates

1. Total Release Ci 5.77E-05 5.20E-05 2.14E-04 1.93E-04 5.16E-04 2.94E+01

2. Average release rate for µCi/sec 7.33E-06 6.62E-06 2.69E-05 2.42E-05 1.63E-05 the period D. Tritium

1. Total Release Ci 9.08E+00 1.16E+01 3.94E+00 4.09E+00 2.87E+01 7.56E+00

2. Average release rate for µCi/sec 1.16E+00 1.47E+00 4.96E-01 5.14E-01 9.07E-01 the period E. Gross Alpha

1.

Total Release Ci

<LLD

<LLD 2.94E+01

2. Average release rate for µCi/sec N/A N/A N/A N/A N/A the period F. Carbon-14

1. Total Release Ci 3.71E+00 3.71E+00 3.72E+00 3.76E+00 1.51E+01

2. Average release rate for µCi/sec 4.72E-01 4.54E-01 4.68E-01 4.73E-01 4.71E-01 the period 1 % of limit is provided in Table 1, Dresden Clean Energy Center Unit 1 Dose Summary

Annual Radioactive Effluent Release Report YEAR: 2024 Page 34 of 64 Dresden Clean Ener Center Table 7, Gaseous Effluents Summation of All Releases Unit 31 A. Fission & Activation Quarter Quarter Quarter Quarter Est. Total Gases Unit 1

2 3

4 Annual Error%

1. Total Release Ci 2.18E+00 1.58E+00 1.83E+00 1.34E+00 6.92E+00 1.31E+01

2. Average release rate for µCi/sec 2.77E-01 2.01E-01 2.30E-01 1.68E-01 2.19E-01 the period B. lodine-131

1. Total Release Ci 5.76E-05 5.95E-05 5.80E-05 4.11E-05 2.16E-04 2.60E+01

2. Average release rate for µCi/sec 7.33E-06 7.57E-06 7.30E-06 5.18E-06 6.84E-06 the period C. Particulates

1. Total Release Ci 1.32E-04 9.61 E-05 2.52E-04 2.84E-04 7.64E-04 2.94E+01

2. Average release rate for µCi/sec 1.67E-05 1.22E-05 3.17E-05 3.57E-05 2.42E-05 the period D. Tritium

1. Total Release Ci 1.94E+01 1.80E+01 5.60E+00 5.82E+00 4.88E+01 7.56E+00

2. Average release rate for µCi/sec 2.46E+00 2.29E+00 7.0SE-01 7.32E-01 1.54E+00 the period E. Gross Alpha

1. Total Release Ci

<LLD

<LLD 2.94E+01

2. Average release rate for µCi/sec N/A N/A N/A N/A N/A the period F. Carbon-14

1. Total Release Ci 3.67E+00 3.72E+00 3.57E+00 2.77E+00 1.39E+01

2. Average release rate for µCi/sec 4.67E-01 4.73E-01 4.49E-01 3.48E-01 4.33E-01 the period 1 % of limit is provided in Table 1, Dresden Clean Energy Center Unit 1 Dose Summary

Annual Radioactive Effluent Release Report YEAR: 2024 Page 35 of 64 Dresden Clean Ener Center Table 8, Gaseous Effluents - Ground Level Release Batch Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter~

, -:-__ I for year Released Fission Gases Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Iodines 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A I Particulates I

Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium I

H-3 I Ci I N/A N/A N/A N/A N/A Gross Alpha I

Alpha I Ci II N/A I

N/A I

N/A II N/A I

Carbon-14 C-14 Ci I N/A I

N/A I

N/A II N/A I

~

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 36 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Energy Center Table 9, Gaseous Effluents - Ground Level Release Continuous Mode Unit 1 Radionuclide

... r 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Iodines 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Particulates Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Cs-137 Ci 1.80E-05 1.80E-05 1.80E-05 1.80E-05 7.20E-05 Total for Period Ci 1.80E--05 1.80E--05 1.80E--05 1.80E--05 7.20E--05 llll1Ul11 H-3 Ci N/A N/A N/A N/A I

N/A I

Gross Alpha Alpha Ci N/A N/A N/A N/A I

N/A I

Carbon-14 C-14 Ci I N/A I

NIA I

N/A I

N/A II N/A I

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 37 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Energy Center Table 10, Gaseous Effluents-Ground Level Release Batch Mode Unit 2

~

dionuclide Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total f::*, ---

II Fission Gases Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Iodines 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Particulates Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium I

H-3 I Ci II N/A I

N/A I

N/A Gross Alpha Alpha Ci N/A N/A N/A N/A I

N/A I

Carbon-14 C-14 Ci II N/A N/A N/A N/A N/A

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 38 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Energy Center Table 11, Gaseous Effluents - Ground Level Release Continuous Mode Unit 2 11onu1;11de Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 L

~,_

I Fission Gases Ar-41 Ci 4.81 E-08 2.52E-08 3.53E-08 6.40E-08 1.73E-07 Kr-85 Ci

<LLD

<LLD Kr-85m Ci 9.71E-09 7.72E-09 1.14E-08 1.74E-08 4.62E-08 Kr-87 Ci 5.79E-08 5.67E-08 6.88E-08 1.0BE-07 2.92E-07 Kr-88 Ci 3.46E-08 3.25E-08 4.05E-08 6.41 E-08 1.72E-07 Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci 1.S0E--07 1.22E--07 1.56E--07 2.54E--07 6.82E--07 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD l

pum H-3 Ci

<LLD

Alpha Ci I

<LLD I

<LLD II

<LLD I

Carbon-14 C-14 Ci

<LLD

Annual Radioactive Effluent Release Report YEAR: 2024 Page 39 of 64 Dresden Clean Ener Center Table 12, Gaseous Effluents-Ground Level Release Batch Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 T-~-I for year Released Fission Gases Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Iodines 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A I Particulates I

Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium I

H-3 I Ci I N/A N/A N/A N/A N/A Gross Alpha I

Alpha I Ci I N/A N/A N/A N/A N/A Carbon-14 I

C-14 I Ci II N/A I

N/A I

N/A

Annual Radioactive Effluent Release Report YEAR: 2024 Page 40 of 64 Dresden Clean Ener Center Table 13, Gaseous Effluents - Ground Level Release Continuous Mode Unit 3 r=

uclide ased Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year 11 c:~~:,.,n Gases Ar-41 Ci 2.82E-08 1.84E-08 3.16E-08 9.36E-08 1.72E-07 Kr-85m Ci 2.35E-08 1.84E-08 1.99E-08 1.37E-08 7.54E-08 Kr-87 Ci 1.19E-07 1.09E-07 1.08E-07 7.73E-08 4.12E-07 Kr-88 Ci 8.44E-08 6.S0E-08 6.78E-08 4.69E-08 2.64E-07 Xe-133 Ci

<LLD 8.69E-10

<LLD

<LLD 8.69E-10 Xe-135 Ci 1.51E-07 1.10E-07 1.23E-07 8.41 E-08 4.67E-07 Xe-135m Ci 3.09E-07 2.35E-07 2.53E-07 2.44E-07 1.04E-06 Xe-138 Ci 1.13E-06 8.97E-07 9.25E-07 9.87E-07 3.94E-06 Total for Period Ci 1.84E-06 1.45E-06 1.53E-06 1.55E-06 6.37E-06 Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3

.84E-04

<LLD

<LLD 5.84E-04 Gross Alpha Alpha Ci

<LLD

<LLD I

Carbon-14 C-14 Ci

<LLD

Annual Radioactive Effluent Release Report YEAR: 2024 Page 41 of 64 Dresden Clean Ener Center Table 14, Gaseous Effluents - Mixed Level Release Batch Mode Unit 1 nuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4

~

~-r year ased on Gases Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Iodines 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Particulates Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium I

H-3 I Ci I NIA N/A N/A N/A NIA Gross Alpha I

Alpha I Ci I N/A N/A N/A N/A N/A Carbon-14 I

C-14 I Ci I N/A N/A N/A N/A N/A

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 42 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Energy Center Table 15, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 1

~

r 1 Quarter 2 Quarter 3 Quarter 4 To*-* ~--,

Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Particulates Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium H-3 Ci N/A N/A NIA N/A N/A Al-1..-

"I' -~

Alpha Ci N/A N/A N/A N/A N/A Carbon-14 C-14 Ci II rt/A N/A N/A N/A N/A

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 43 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Enerav Center Table 16, Gaseous Effluents - Mixed Level Release Batch Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3

n.

~

A

..... ~I for year Released Fission Gases Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Iodines 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Particulates Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium H-3 Ci N/A N/A N/A N/A I

N/A I

Gross Alpha Alpha Ci II N/A N/A N/A N/A N/A Carbon-14 I

C-14 I Ci II N/A I

N/A I

N/A

Annual Radioactive Effluent Release Report YEAR: 2024 Page 44 of 64 Dresden Clean Ener Center Table 17, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Qu.. *-.

-:-...... 1 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

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD rticulates Mn-54 Ci

<LLD

<LLD 9.66E-07 9.66E-07 Co-60 Ci

<LLD

<LLD 6.15E-06 6.15E-06 Zn-65 Ci

<LLD

<LLD 2.53E-06 2.53E-06 Total for Period Ci

<LLD

<LLD 9.65E-06 9.65E-06 Tritium H-3 Ci I 1.61E+00 I

1.81E+00 I

1.85E+00 I

2.56E+00 I

7.83E+

r::mcc Alpha Alpha Ci

<LLD

<LLD II

-LLD Carbon-14 C-14 Ci

<LLD

Annual Radioactive Effluent Release Report YEAR: 2024 Page 45 of 64 Dresden Clean Ener Center Table 18, Gaseous Effluents - Mixed Level Release Batch Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A I Particulates I

Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A

~um H-3 Ci N/A N/A N/A N/A N/A

,-. *~~ A,_.__

Alpha Ci I N/A I

N/A I

NIA Carbon-14 C-14 Ci I N/A I

N/A I

N/A

Annual Radioactive Effluent Release Report YEAR: 2024 Page 46 of 64 Dresden Clean Ener Center Table 19, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4

~- -

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

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Cr-51 Ci

<LLD

<LLD 4.92E-07 4.92E-07 Mn-54 Ci

<LLD

<LLD 5.35E-06 5.35E-06 Co-60 Ci

<LLD

<LLD 9.15E-06 9.15E-06 Zn-65 Ci

<LLD

<LLD 3.65E-06 3.65E-06 Total for Period Ci

<LLD

<LLD 1.86E-05 1.86E-05 Tritium H-3 C

3.34E+00 3.00E+00 3.62E+00 1.39E+01 Gross Alpha Alpha C1 II

-LLD

<LLD

<LLD I

Carbon-14 C-14 Ci

<LLD

Annual Radioactive Effluent Release Report YEAR: 2024 Page 47 of 64 Dresden Clean Ener Center Table 20, Gaseous Effluents - Elevated Level Release Batch Mode Unit 1 ll:;;~de Units Quarter 1 Quarter 2 Quarter 3 Qu

~

fnr **---

Fission Gases Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A NIA NIA Iodines 1-131 Ci N/A NIA N/A N/A NIA 1-133 Ci N/A N/A N/A NIA NIA 1-135 Ci N/A N/A N/A NIA NIA Total for Period Ci NIA NIA NIA NIA NIA Particulates Co-58 Ci N/A NIA N/A NIA NIA Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A NIA NIA N/A NIA Sr-90 Ci N/A NIA NIA N/A NIA Cs-134 Ci N/A N/A N/A N/A N/A Total for Period Ci NIA N/A N/A NIA NIA Tritium I

H-3 I Ci II NIA I

NIA I

NIA II NIA I

I Gross Alpha I

Alpha Ci N/A N/A NIA N/A I

N/A I

Carbon-14 I

C-14 I Ci I NIA NIA NIA NIA NIA

Annual Radioactive Effluent Release Report YEAR: 2024 Page 48 of 64 Dresden Clean Ener Center Table 21, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Iodines 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A D-,..:~,,I-*~~

Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium H-3 Ci N/A N/A N/A N/A I

N/A I

Gross Alpha Alpha Ci N/A N/A N/A N/A N/A 11 Carbon-14 C-14 Ci N/A N/A N/A N/A N/A

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 49 of 64 Company: Constellation EnerQY Generation I Plant:

Dresden Clean Energy Center Table 22, Gaseous Effluents - Elevated Level Release Batch Mode Unit 2 Radionuclide Units I Quarter 1 I Quarter 2 I Quarter 3 I Quarter 4 I Total for year Released Fission Gases Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A

~dines 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A NIA Particulates Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium H-3 Ci N/A N/A N/A N/A II N/A I

Gross Alpha Alpha Ci N/A N/A N/A N/A N/A Carbon-14 C-14 Ci N/A N/A N/A N/A N/A

Annual Radioactive Effluent Release Report YEAR: 2024 Page 50 of 64 Dresden Clean Ener Center Table 23, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 2 d

Un,_

~--*.er 1 Quarter 2 Quarter 3 Quarter 4 Total for year Fission Gases Ar-41 Ci 9.13E-01 6.13E-01 8.25E-01 4.55E-01 2.81E+00 Kr-85 Ci 7.63E-03 5.08E-03

<LLD

<LLD 1.27E-02 Kr-85m Ci 2.09E-01 2.71E-01 2.00E-01 4.12E-02 7.21E-01 Kr-87 Ci 2.60E-02 3.05E-02 6.11E-02 5.76E-02 1.75E-01 Kr-88 Ci 4.17E-02 1.15E-01 1.27E-01 2.97E-02 3.13E-01 Xe-133 Ci 5.33E-01 4.46E-01 2.84E-01 1.16E-01 1.38E+00 Xe-135 Ci 3.33E-01 2.44E-01 4.35E-02 4.28E-02 6.63E-01 Xe-135m Ci 1.24E+00 9.65E-01 3.30E-01 2.82E-01 2.81E+00 Xe-138 Ci

<LLD 2.97E-01 1.34E+00 1.23E+00 2.88E+00 Total for Period Ci 3.30E+00 2.99E+00 3.21E+00 2.26E+00 1.18E+01 1-131 Ci 2.50E-05 3.36E-05 4.18E-05 2.63E-05 1.27E-04 1-133 Ci 1.79E-04 2.38E-04 3.31 E-04 3.82E-04 1.13E-03 1-135 Ci 7.81E-05 7.37E-05

<LLD

<LLD 1.52E-04 Total for Period Ci 2.82E-04 3.45E-04 3.73E-04 4.0SE-04 1.41E-03 Particulates Mn-54 Ci 9.04E-06 1.63E-06 2.98E-05 2.12E-05 6.17E-05 Co-58 Ci 2.57E-06 2.99E-06 2.35E-05 1.90E-05 4.80E-05 Co-60 Ci 3.71E-05 3.65E-05 1.04E-04 8.52E-05 2.63E-04 Zn-65 Ci 7.06E-06

<LLD 4.04E-05 3.36E-05 8.10E-05 Sr-89 Ci 1.88E-06 5.76E-06 4.96E-06 4.99E-06 1.76E-05 Sn-117m Ci

<LLD 5.16E-06 4.02E-06 1.90E-05 2.82E-05 Ce-144 Ci

<LLD

<LLD 7.64E-06

<LLD 7.64E-06 Total for Period Ci 5.77E-05 5.20E-05 2.14E-04 1.83E-04 5.07E-04 Tritium I

H-3 I Ci II 7.48E+00 I

9.75E+00 I

2.09E+00 I

1.53E+00 II 2.08E+01 I

I Gross Alpha Alpha Ci

<LLD

<LLD Carbon-14 C-14 Ci 3.71E+00 3.71E+00 3.72E+00 3.76E+00 1.49E+01

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 51 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Enerav Center Table 24, Gaseous Effluents - Elevated Level Release Batch Mode Unit 3 ionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci N/A N/A N/A N/A N/A Kr-85 Ci N/A N/A N/A N/A N/A Kr-85m Ci N/A N/A N/A N/A N/A Kr-87 Ci N/A N/A N/A N/A N/A Kr-88 Ci N/A N/A N/A N/A N/A Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Xe-135m Ci N/A N/A N/A N/A N/A Xe-138 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Iodines 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A 1-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Particulates Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium I

H-3 I Ci I N/A N/A N/A N/A N/A Gross Alpha Alpha Ci II N/A N/A N/A N/A N/A Carbon-14 C-14 Ci II N/A N/A N/A N/A I

N/A I

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 52 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Energy Center Table 25, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 3 Radionuclide Un,_

1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci 4.31E-01 2.16E-01 1.40E-01 2.37E-01 1.02E+00 Kr-85 Ci 6.68E-03 3.70E-03

<LLD

<LLD 1.04E-02 Kr-85m Ci 6.69E-02 4.09E-02 1.90E-02 2.92E-02 1.56E-01 Kr-87 Ci 2.45E-02 2.43E-02 4.54E-02 2.80E-02 1.22E-01 Kr-88 Ci

<LLD 4.78E-03 2.44E-02 1.58E-02 4.S0E-02 Xe-133 Ci 1.32E-01 1.01 E-01 7.09E-02 9.10E-02 3.94E-01 Xe-135 Ci 3.12E-01 1.75E-01 4.03E-02 2.61 E-02 5.54E-01 Xe-135m Ci 1.20E+00 7.34E-01 2.90E-01 1.86E-01 2.41E+00 Xe-138 Ci

<LLD 2.79E-01 1.20E+00 7.24E-01 2.20E+00 Total for Period Ci 2.18E+00 1.58E+00 1.83E+00 1.34E+00 6.92E+00 Iodines 1-131 Ci 5.76E-05 5.95E-05 5.80E-05 4.11E-05 2.16E-04 1-133 Ci 4.17E-04 4.03E-04 4.07E-04 5.65E-04 1.79E-03 1-135 Ci 1.68E-04 1.67E-04

<LLD

<LLD 3.35E-04 Total for Period Ci 6.43E--04 6.29E--04 4.65E--04 6.06E--04 2.34E--03 Particulates Mn-54 Ci 2.02E-05 2.22E-06 3.87E-05 3.06E-05 9.18E-05 Co-58 Ci 5.72E-06 5.65E-06 2.83E-05 2.81 E-05 6.77E-05 Co-60 Ci 8.71E-05 7.26E-05 1.28E-04 1.23E-04 4.10E-04 Zn-65 Ci 1.66E-05 0.00E+00 4.16E-05 5.13E-05 1.10E-04 Sr-89 Ci 1.88E-06 5.76E-06 4.96E-06 4.99E-06 1.76E-05 Sn-117m Ci

<LLD 9.91 E-06 4.52E-06 2.79E-05 4.23E-05 Ce-144 Ci

<LLD

<LLD 6.35E-06

<LLD 6.35E-06 Total for Period Ci 1.32E--04 9.61E--05 2.52E--04 2.65E--04 7.45E--04 1~m I

H-3 I Ci I 1.54E+01 1.47E+01 2.60E+00 2.19E+00 3.48E+01 ss Alpha Alpha Ci I

<LLD I

<LLD 14 C-14 Ci 3.67E+00 3.72E+00 3.57E+00 2.77E+00 1.37E+01

Annual Radioactive Effluent Release Report YEAR: 2024 Page 53 of 64 Dresden Clean Ener Center 2.0 LIQUID EFFLUENTS Table 26, Liquid Effluents - Summation of All Releases Unit 11 Quarter Quarter Quarter Quarter Annual Est. Total A. Fission & Activation Products Unit 1

2 3

4 Error%

1. Total Release Ci N/A N/A N/A N/A N/A 1.95E+01

2.

Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A B. Tritium

1. Total Release Ci N/A N/A N/A N/A N/A 2.37E+00

2. Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A C. Dissolved & Entrained Gases

1. Total Release Ci N/A N/A N/A N/A N/A 2.03E+01

2. Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A D. Gross Alpha Activity

1. Total Release Ci N/A N/A N/A N/A N/A 2.00E+01

2. Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A E. Volume of Waste Released Liters N/A N/A N/A N/A N/A (prior to dilution)

F. Volume of Dilution Water Used Liters N/A N/A N/A N/A N/A During Period 1 % of limit is provided in Table 1, Dresden Clean Energy Center Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 54 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Energy Center Table 27, Liquid Effluents - Summation of All Releases Unit 21 A. Fission & Activation Products Unit Quarter Quarter Quarter Quarter Annual Est. Total 1

2 3

4 Error%

1. Total Release Ci

<LLD

<LLD 1.95E+01

2.

Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A B. Tritium

1. Total Release Ci

<LLD 2.62E-04

<LLD

<LLD 2.62E-04 2.37E+00

2. Average diluted concentration

µCi/ml N/A 6.64E-13 N/A N/A 6.64E-13 C. Dissolved & Entrained Gases

1. Total Release Ci

<LLD

<LLD 2.03E+01

2. Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A D. Gross Alpha Activity

1. Total Release Ci

<LLD

<LLD 2.00E+01

2. Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A E. Volume of Waste Released Liters

<LLD 1.46E+05

<LLD

<LLD 1.46E+05 (prior to dilution)

F. Volume of Dilution Water Used Liters

<LLD 3.95E+11

<LLD

<LLD 3.95E+11 During Period 1 % of limit is provided in Table 1, Dresden Clean Energy Center Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 55 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Energy Center Table 28, Liquid Effluents - Summation of All Releases Unit 31 A. Fission & Activation Products Unit Quarter Quarter Quarter Quarter Annual Est. Total 1

2 3

4 Error%

1. Total Release Ci

<LLD

<LLD 1.95E+01

2.

Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A B. Tritium

1. Total Release Ci

<LLD 2.62E-04

<LLD

<LLD 2.62E-04 2.37E+00

2. Average diluted concentration

µCi/ml N/A 6.64E-13 N/A N/A 6.64E-13 C. Dissolved & Entrained Gases

1. Total Release Ci

<LLD

<LLD 2.03E+01

2. Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A D. Gross Alpha Activity

1. Total Release Ci

<LLD

<LLD 2.00E+01

2. Average d ii uted concentration

µCi/ml N/A N/A N/A N/A N/A E. Volume of Waste Released Liters

<LLD 1.46E+05

<LLD

<LLD 1.46E+05 (prior to dilution)

F. Volume of Dilution Water Used Liters

<LLD 3.95E+11

<LLD

<LLD 3.95E+11 During Period 1 % of limit is provided in Table 1, Dresden Clean Energy Center Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 56 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Energy Center Table 29, Liquid Effluents Batch Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission and Activation Products Cr-51 Ci N/A N/A N/A N/A N/A Mn-54 Ci N/A N/A N/A N/A N/A Fe-55 Ci N/A N/A N/A N/A N/A Fe-59 Ci N/A N/A N/A N/A N/A Co-57 Ci N/A N/A N/A N/A N/A Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Nb-95 Ci N/A N/A N/A N/A N/A Zn-65 Ci N/A N/A N/A N/A N/A Ag-110m Ci N/A N/A N/A N/A N/A 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Cs-137 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium I

H-3 I Ci II N/A I

N/A I

N/A Gross Alpha I

Alpha I Ci II N/A I

N/A I

N/A Entrained Gases Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 57 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Enerav Center Table 30, Liquid Effluents Continuous Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission and Activation Products Cr-51 Ci N/A N/A N/A N/A N/A Mn-54 Ci N/A N/A N/A N/A N/A Fe-55 Ci N/A N/A N/A N/A N/A Fe-59 Ci N/A N/A N/A N/A N/A Co-57 Ci N/A N/A N/A N/A N/A Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Nb-95 Ci N/A N/A N/A N/A N/A Zn-65 Ci N/A N/A N/A N/A N/A Ag-110m Ci N/A N/A N/A N/A N/A 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Cs-137 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A NIA N/A N/A NIA Tritium H-3 Ci N/A NIA N/A N/A N/A Gross Alpha Alpha Ci N/A N/A N/A N/A N/A Entrained Gases Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A

Annual Radioactive Effluent Release Report l YEAR: 2024 I Page 58 of 64 Company: Constellation Ener~:av Generation I Plant:

Dresden Clean Enerav Center Table 31, Liquid Effluents Batch Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission and Activation Products Cr-51 Ci N/A N/A N/A N/A N/A Mn-54 Ci N/A N/A N/A N/A N/A Fe-55 Ci N/A N/A N/A N/A N/A Fe-59 Ci N/A N/A N/A N/A N/A Co-57 Ci N/A N/A N/A N/A N/A Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Nb-95 Ci N/A N/A N/A N/A N/A Zn-65 Ci N/A N/A N/A N/A N/A Ag-110m Ci N/A N/A N/A N/A N/A 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Cs-137 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium H-3 Ci N/A N/A N/A N/A N/A Gross Alpha Alpha Ci N/A N/A N/A N/A N/A Entrained Gases Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 59 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Energy Center Table 32, Liquid Effluents Continuous Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released I Fission and Activation Products I

Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Ag-110m Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3 Ci

<LLD 2.62E-04

<LLD

<LLD II 2.62E-04 Gross Alpha I

Alpha I Ci I

<LLD

<LLD Entrained Gases Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

Annual Radioactive Effluent Release Report YEAR: 2024 Page 60 of 64 Dresden Clean Ener Center Table 33, Liquid Effluents Batch Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission and Activation Products Cr-51 Ci N/A N/A N/A N/A N/A Mn-54 Ci N/A N/A N/A N/A N/A Fe-55 Ci N/A N/A N/A N/A N/A Fe-59 Ci N/A N/A N/A N/A N/A Co-57 Ci N/A N/A N/A N/A N/A Co-58 Ci N/A N/A N/A N/A N/A Co-60 Ci N/A N/A N/A N/A N/A Sr-89 Ci N/A N/A N/A N/A N/A Sr-90 Ci N/A N/A N/A N/A N/A Nb-95 Ci N/A N/A N/A N/A N/A Zn-65 Ci N/A N/A N/A N/A N/A Ag-110m Ci N/A N/A N/A N/A N/A 1-131 Ci N/A N/A N/A N/A N/A 1-133 Ci N/A N/A N/A N/A N/A Cs-134 Ci N/A N/A N/A N/A N/A Cs-137 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A N/A Tritium H-3 Ci N/A N/A N/A N/A N/A Gross Alpha Alpha Ci N/A N/A N/A N/A N/A Entrained Gases Xe-133 Ci N/A N/A N/A N/A N/A Xe-135 Ci N/A N/A N/A N/A N/A Total for Period Ci N/A N/A NIA N/A N/A

Annual Radioactive Effluent Release Report YEAR: 2024 Page 61 of 64 Dresden Clean Ener Center Table 34, Liquid Effluents Continuous Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission and Activation Products Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Ag-110m Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3 Ci

<LLD 2.62E-04

<LLD

'),::')C J\\A Gross Alpha Alpha Ci II

<LLD

<LLD Entrained Gases Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 62 of 64 Company: Constellation Energy Generation I Plant:

Dresden Clean Energy Center, Solid Waste Information 1.0 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Table 35, Types of Solid Waste Summary Site Total Volume Total Activity Types of Waste (m3)

(Ci)

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

1.46E+02 1.40E+02

b. Dry compressible waste, contaminated equip, etc.

4.49E+02 3.24E-01

c. Irradiated components, control rods, etc.

0.00E+00 0.00E+00

d. Other (describe) 6.31 E+00 6.02E-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 36, Major Nuclides Site Major Nuclide Composition Curies

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

Co-60 51.42 7.17E+01 Cs-137 21.27 2.96E+01 Fe-55 17.22 2.40E+01 Ni-63 3.10 4.32E+00 Mn-54 2.69 3.75E+0O Zn-65 1.80 2.51E+00

b. Dry compressible waste, contaminated equip, etc.

Fe-55 42.70 1.39E-01 Co-60 33.54 1.09E-01 Mn-54 5.63 1.83E-02 Cs-137 3.84 1.25E-02 Zn-65 3.64 1.18E-02 Cr-51 3.51 1.14E-02 Ni-63 2.61 8.48E-03 Co-58 1.28 4.16E-03 Fe-59 1.09 3.52E-03

Annual Radioactive Effluent Release Report YEAR: 2024 Page 63 of 64 Com

Constellation Ener Generation Plant:

Dresden Clean Ener Center, Solid Waste Information Table 36, Major Nuclides Site Major Nuclide Composition Curies C. Irradiated components, control rods, etc.

None

d. Other (describe)

Fe-55 52.38 3.15E-03 Co-60 31.51 1.90E-03 Mn-54 6.06 3.65E-04 Cr-51 2.59 1.56E-04 Zn-65 2.54 1.53E-04 Co-58 1.27 7.63E-05 3.0 SOLID WASTE DISPOSITION Table 37, Solid Waste Disposition Site Number of Mode of Transportation Destination Shipments 10 Hittman Transport Energy Solution Services (Bear Creek) 1560 Bear Creek Road 22 Hittman Transport Energy Solutions Clive CWF Clive Containerized Waste Facility Energy Solution, LLC 1

Hittman Transport Clive Bulk Waste Facility - Treatment Facility 9

Hittman Transport Energy Solution Clive BWF Clive Bulk Waste Facility 4.0 IRRADIATED FUEL DISPOSITION None

Annual Radioactive Effluent Release Report I YEAR: 2024 I Page 64 of 64 Company: Constellation Enerav Generation I Plant:

Dresden Clean Energy Center, 2024 Annual RGPP Monitoring Report

SVPLTR 25-0054, Revision to 2024 Annual Radioactive Effluent Release Report

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SVPLTR 25-0054, Revision to 2024 Annual Radioactive Effluent Release Report

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Subject:

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