Text

Submittal of 2022 Annual Radioactive Effluent Release Report
	ML23118A135
Person / Time
Site:	LaSalle, 07200072
Issue date:	04/28/2023
From:	Van Fleet J; Constellation Energy Generation
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
	RA23-028
	Download: ML23118A135 (1)
	v • d • e

LaSalle County Station Constellation. 2601 North 21'1 Road Marseilles, IL 61341 815-415-2000 Telephone RA23-028 10 CFR 50.36a April 28. 2023 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373, 50-374. and 72-70

Subject:

2022 Annual Radioactive Effluent Release Report Enclosed is the Constellation Energy Generation, LLC, 2022 Annual Radioactive Effluent Release Report for LaSalle County Station, submitted in accordance with 10 CFR 50.36a, "Technical specifications on effluents from nuclear power reactors," paragraph (a)(2), and Technical Specification 5.6.3, "Radioactive Effluent Release Report."

There are no regulatory commitments contained within this letter. Should you have any questions concerning this letter, please contact Mr. Daniel Mearhoff, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, tf,1',,:;J/d--

John Van Fleet Acting Site Vice President LaSalle County Station

Enclosures:

LaSalle County Nuclear Power Station Annual Radioactive Effluent Release Report (ARERR) for 2022 cc: Regional Administrator- NRC Region Ill NRC Senior Resident Inspector - LaSalle County Station

__,,. Constellation LaSalle County Station Units 1 and 2 Annual Radioactive Effluent Release Report 2022 Document Number: 50-373, 50-374, and 72-70

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 1 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 1.0 EXECUTIVE

SUMMARY

LaSalle County Station Units 1 and 2 (LAS) 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 Appendix I of 10 CFR 50 and by 40 CFR 190. Operational doses to the public during 2022 were calculated to be very small compared to 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 2.2, 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 disposal; and other information as required by site licensing documents.

In 2022 the Land Use Census dose assessments due to radioactive gaseous effluents showed that the critical receptor for LaSalle County Station Units 1 and 2 is the Infant, due to the pathways of inhalation, ground plane, vegetation, cow milk, and cow meat, at the hypothetical milk farm located in the ESE sector at 8000 meters.

The maximum Annual Organ Dose calculated for this receptor was 1.12E-01 , to the thyroid. This annual dose is a small fraction (3.73E-01 %) of the 10 CFR 50, Appendix I guideline of 30 mrem to the Maximum Organ per two reactor units sites.

Solid radioactive waste shipped offsite for disposal included 1.82E+02 Curies and 1.06E+03 m 3 , shipped in 42 shipments .

In addition to monitoring radioactive effluents, LAS has a Radiological Environmental Monitoring Program (REMP) that monitors for buildup of radioactivity in the offsite environment. Data from the REMP is published in the Annual Radiological Environmental Operating Report (AREOR).

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 2 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 TABLE OF CONTENTS 1.0 EXECUTIVE

SUMMARY

... ..................................... .. .................................................................. 1 2.0 LIST OF ACRONYMS AND DEFINITIONS .............. .................... .... ......... .. .. .... ................ ....... .. 4 2.2 Comparison to Regulatory Limits .. ... .. .. ... ..... ..... ... .... ........ .... ... ....... .. .. .... ......................... 6

3.0 INTRODUCTION

............. .. ....... ........ .............. ............................. ... ................. .. .... .. ............... .... 8 3.1 About Nuclear Power ............. .... .... ........... .. ...... ............... ..................... ... ................ .. ..... 8 3.2 About Radiation Dose ............... .. .................................................................................. 10 3.3 About Dose Calculation ........ .... ....... .... ....... ...... .... ... ... .... ... ........... ..... .... .. .... ................. 12 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS ................................................................. 14 4.1 Regulatory Limits .......................................................................................................... 14 4.2 Regulatory Limits for Gaseous Effluent Doses: ....................... .............................. ........ 14 4 .3 Regulatory Limits for Liquid Effluent Doses ...................... .... ....... ..... ................ ..... ... .. .. . 15 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public ......... .. ........... ............ 16 4.5 On site Doses (Within Site Boundary) ........... .... ............... ...... ..................... ................ ... 16 5.0 SUPPLEMENTAL INFORMATION .. .... .... ............. ........ ............. ... ... .... ...... .. .. .... ................ .... ... 17 5.1 Gaseous Batch Releases ....... ... ... ... .. ....... ...... ............... ...... ..... ......... ... .... .......... .. .. ... ... 17 5.2 Liquid Batch Releases .......................... ....... ... ... .... ... ..................................... ............... 17 5.3 Abnormal Releases .................. ... .................................... ........................................... .. 17 5.4 Land Use Census Changes .... ..... .......... .. .... .................................. ... ............................ 17 5.5 Meteorological Data ........................................................................................... ... ..... ... 17 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days ............................. ... 17

5. 7 Offsite Dose Calculation Manual (ODCM) Changes ...... .......... ........... .... ................. ... ... 17 5.8 Process Control Program (PCP) Changes .... .................. .. ... ... ........... ........ ............... .... 17 5.9 Radioactive Waste Treatment System Changes ........... .... .................. .... ... .. ................. 17 5.10 Other Supplemental Information ....... ... .... ...... ..... .. ..... ....... .. ... ... ........ ...... ............. .... ..... 18 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM .......... .. ... 21 6.1 Voluntary Notification ................. .. ............... .... ..................... .... ............. ..... ..... .. ........ .... 25 7.0 BIBLIOGRAPHY ..... .. ...... ... ... ....... ... .......... .. .......... ... .............. ....... ........ .......... ...... .. .... .. ....... ... . 26 TABLES Table 1, LaSalle County Station Units 1 and 2 Dose Summary ............. .. ............................................... 6 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for LAS .... ... ..... ..... ....... ..... ... ..... 7 Table 3, Non-Occupationally Exposed Individual Dose .................................................... ........ ............ 16 Table 4, Groundwater Protection Program Monitoring Well Results ..... .. ............................................. . 22 Table 5, Gaseous Effluents Summation of All Releases from the Site ...... .. ............... ... .. ............... ...... 27 Table 6, Gaseous Effluents - Elevated Level Release Batch Mode Site ............................................ 28 Table 7, Gaseous Effluents - Elevated Level Release Continuous Mode Site ... .. .... ................ ........... . 29 Table 8, Liquid Effluents - Summation of All Releases Site ................................................................. 30 Table 9, Batch Mode Liquid Effluents Site ...... ..... ................ ............... ...... ...... .............. ........ ............... . 31 Table 10, Continuous Mode Liquid Effluents Site ................... .... ......... ... ....... .. ................. ............... ..... 32

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 3 of 59 Company: Constellation I Plant: LaSalle Countv Station Units 1 and 2 Table 11, Resins, Filters, and Evaporator Bottoms Summary for the LaSalle Site ............................... 33 Table 12, Dry Active Waste (DAW) Summary for the LaSalle Site ....................................................... 34 Table 13, Irradiated Components Summary for the LaSalle Site .......................................................... 35 Table 14, Other Waste Summary for the LaSalle Site .......................................................................... 36 Table 15, Sum of All Low-Level Waste Shipped from the LaSalle Site ................................................. 37 Table 16, Solid Waste Disposition for the LaSalle Site ......................................................................... 38 Table 17, Irradiated Fuel Shipments Disposition for the LaSalle Site ................................................... 38 Table 18, Classification of Atmospheric Stability .................................................................................. 39 FIGURES Figure 1, Pressurized Water Reactor (PWR) [1 ] ..................................................................................... 8 Figure 2, Boiling Water Reactor (BWR) [2] ............................................................................................. 9 Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3] .................................................. 1O Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6] ............. 12 ATTACHMENTS , ARERR Release Summary Tables (RG-1.21 Tables) ................................................... 27 , Solid Waste Information ................................................................................................ 33 , Meteorological Data ...................................................................................................... 39

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 4 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 2.0 LIST OF ACRONYMS AND DEFINITIONS

1. Airborne Activity Sampling: Sampling of air through the collection of particulates and radionuclides on filter media, collection of noble gases in a container, and collection of water vapor containing tritium.

2. 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.

3. BWR: Boiling Water Reactor

4. 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.

5. 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.

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

7. Curie (Ci): A measure of radioactivity; equal to 3.7 x 10 10 disintegrations per second, or 2.22 x 10 12 disintegrations per minute.

8. 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.

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

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

11. Ingestion Pathway: The ingestion pathway includes milk, fish, and garden produce. Meat or other food products may also be included.

12. ISFSI: Independent Spent Fuel Storage Installation

13. Lower Limit of Detection (LLD): The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with a 5% probability of a false conclusion that a blank observation represents "real" signal.

14. 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 five% probability of falsely concluding that a blank observation represents a true signal.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 5 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2

15. MDC: Minimum Detectable Concentration, essentially synonymous with MDA for the purposes of radiological monitoring.

16. Mean: The average, i.e., the sum of results divided by the number of results.

17. Microcurie (µCi): 3.7 x 104 disintegrations per second, or 2.22 x10 6 disintegrations per minute.

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

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

20. MWe: Megawatts Electric

21. MWTh: Megawatts Thermal

22. NA: Not Applicable

23. NEI: Nuclear Energy Institute

24. NRG: Nuclear Regulatory Commission

25. ODCM: Offsite Dose Calculation Manual

26. OSLO: Optically Stimulated Luminescence Dosimeter

27. Protected Area : The fenced area immediately surrounding the Plant. Access to the protected area requires a security badge or escort.

28. PWR: Pressurized Water Reactor

29. REC: Radiological Effluent Control

30. REMP : Radiological Environmental Monitoring Program

31. Restricted Area: Any area where access is controlled for the purpose of protecting individuals from exposure to radiation or radioactive materials.

32. SLCs: Selected Licensee Commitments

33. 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).

34. TLD: Thermoluminescent Dosimeter

35. TRM: Technical Requirements Manual

36. TS: Technical Specification

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 6 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 2.2 Comparison to Regulatory Limits During 2022 all solid, liquid, and gaseous radioactive effluents from LaSalle County Station Units 1 and 2 were well below regulatory limits, as summarized in Table 1 and Table 2.

Table 1, LaSalle County Station Units 1 and 2 Dose Summary 1 Liquid Effluents Quarter 1 Quarter 2 Quarter3 Quarter4 Annual Limit 3 mrem 3mrem 3 mrem 3mrem 6 mrem Total Body Dose 0.00+00 0.00+00 0.00+00 0.00+00 0.00+00

% of Limit 0.00+00 0.00+00 0.00+00 0.00+00 0.00+00 Limit 10 mrem 10 mrem 10 mrem 10 mrem 20 mrem Max Organ Dose 0.00+00 0.00+00 0.00+00 0.00+00 0.00+00

% of Limit 0.00+00 0.00+00 0.00+00 0.00+00 0.00+00 Gaseous Effluents Limit 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Gamma Air Dose 2 7.34E-04 9.10E-04 1.82E-04 2.42E-03 5.S0E-03

% of Limit 7.34E-03 9.10E-03 1.82E-03 2.42E-02 2.75E-02 Limit 20 mrad 20 mrad 20 mrad 20 mrad 40 mrad Beta Air Dose 4.35E-05 5.89E-05 1.30E-04 1.52E-04 3.84E-04

% of Limit 2.18E-04 2.95E-04 6.SOE-04 7.60E-04 9.60E-04 Limit 2.5 mrem 2.5 mrem 2.5 mrem 2.5 mrem 5mrem 3 4.90E-04 6.0?E-04 9.54E-04 1.62E-03 3.67E-03 NG Total Body Dose

% of Limit 1.96E-02 2.43E-02 3.82E-02 3.24E-02 1.47E-01 Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem NG Skin Dose 2 8.28E-04 1.03E-03 1.62E-03 2.74E-03 6.22E-03

% of Limit 1.10E-02 1.37E-02 2.16E-02 3.65E-02 4.15E-02 Limit 15 mrem 15 mrem 15 mrem 15 mrem 30 mrem Max Organ Dose 4 1.37E-02 1.25E-02 3.81E-02 4.76E-02 1.12E-01

% of Limit 9.13E-02 8.33E-02 2.54E-01 3.17E-01 3.73E-01 1 Table 1 demonstrates compliance with 10 CFR Part 50, App. I Limits.

2 WSW UAB Non-SB, All Age Groups 3 WSW UAB SB, All Age Groups 4 ESE Nearest Cow Milk/ Infant, Thyroid

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 7 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for LAS 1 Whole Body Thyroid Max Other Organ Gaseous 2 *3 1.31 E-02 1.12E-01 4.64E-02 Liquid O.O0E+00 0.00E+00 0.00E+00 Sky Shine & ISFSI 7.92E-01 - -

Total Site Dose 8.0SE-01 1.12E-01 4.64E-02 Total w/Other Nearby 8.0SE-01 1.12E-01 4.64E-02 Facility 4 Limit 25 mrem 75 mrem 25 mrem

% of Limit 3.22E+00 1.49E-01 1.86E-01 1 Table 2 is a summation of Units to show compliance with 40 CFR Part 190 Limits.

2 Gaseous dose values in Table 2 include organ dose from Noble Gas, Iodine, Tritium, Carbon-14, and particulates with half-lives> 8 days.

3 Individual groups with the highest dose are used: Total Body: all age groups for Noble Gas and the Infant for particulates, Individual age group sum is lower.

4 Other fuel cycle sources within 5 miles of the site do not exist.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 8 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2

3.0 INTRODUCTION

3.1 About Nuclear Power Commercial nuclear power plants are generally classified as either Boiling Water Reactors (BWRs) or Pressurized Water Reactors (PWRs), based on their design . A BWR includes a single coolant system where water used as reactor coolant boils as it passes through the core and the steam generated is used to turn the turbine generator for power production. 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 Stnictirc Figure 1, Pressurized Water Reactor (PWR) [1]

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 9 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 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 driven by coal or natural gas. Water is boiled to generate steam; the steam rotates 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 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 dose to the public due to plant operation remains within required limits.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 10 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 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.

Space (background)

(5%)

Terrestrial (background)

(3%)

,,,... Radon & thoron

/ (background)

/ (37%)

Computed / /

tomograph-y (medical)

(24%)

_Industrial

(<0.1%)

Nuclear medicine _ Occupational (medical) (<0.1%)

(12%) Consumer lnterventional fluoroscopy _ __.--

(medical) --

--- Conventional radiography/fluoroscopy (medical)

(2%)

(73/4) (5%)

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

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 11 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 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%) due to radiation used in various types of medical scans and treatments. Of the remaining 2% of dose, most is due to consumer activities such as air travel, smoking cigarettes, and building materials. A small fraction of this 2% is due to industrial activities including generation of nuclear power.

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

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 12 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 3.3 About Dose Calculation The concentrations of radioactive material in the environment resulting from plant operations are very small and it is not possible to determine doses directly using measured activities of environmental samples. To overcome this, Dose Calculations based on measured activities of effluent streams are used to model the dose impact for Members of the Public due to plant operation and effluents. There are several mechanisms that can result in dose to Members of the Public, including : Ingestion of radionuclides in food or water; Inhalation of radionuclides in air; Immersion in a plume of noble gases; and Direct Radiation from the ground, the plant or from an elevated plume.

.'.~position

- - - - lngcs Li\'cstock products

.: 0 ~

nn :Behavior of redionuclides Marine producla Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6]

The Offsite Dose Calculation Manual (ODCM) specifies the methodology used to obtain the doses in the Dose Assessment section of this report. The 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.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 13 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 3.3 (Continued)

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

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

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

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 14 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS 4.1 Regulatory Limits Regulatory limits are detailed in Station Licensing documents such as the Offsite Dose Calculation Manual (ODCM), Technical Specifications 5.5.1.b, 5.5.4 and 5.6.3, Quality Assurance Topical Report, and Updated Final Safety Analysis Report. These documents contain the limits to which LAS must adhere. LAS drives to maintain the philosophy to keep dose "as low as 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 LAS is well below the ODCM limits.

The 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. This data reveals that the radioactive effluents have an overall minimal dose contribution to the surrounding environment.

The annual whole body, skin and organ dose was computed using the 2022 source term using the dose calculation methodology provided in the ODCM. The calculated doses due to gaseous effluents to demonstrate compliance with offsite dose limits are presented in Table 1, LaSalle County Station Units 1 and 2 Dose Summary and Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for LAS.

4.2 Regulatory Limits for Gaseous Effluent Doses:

1. Fission and activation gases:

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

1) Less than or equal to 500 mrems/year to the total body

2) Less than or equal to 3000 mrems/year to the skin

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

1) Quarterly a) Less than or equal to 5 mrads gamma b) Less than or equal to 10 mrads beta

2) Yearly a) Less than or equal to 10 mrads gamma b) Less than or equal to 20 mrads beta

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 15 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 4.2 (Continued)

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 mrems/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 mrems to any organ

2) Yearly a) Less than or equal to 15 mrems to any organ 4.3 Regulatory Limits for Liquid Effluent Doses

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

a. Quarterly

1) Less than or equal to 1.5 mrems total body

2) Less than or equal to 5 mrems critical organ

b. Yearly

1) Less than or equal to 3 mrems total body

2) Less than or equal to 10 mrems critical organ

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 16 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public

1. Total Dose (40 CFR 190)

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

1) Less than or equal to 25 mrems, Total Body or any Organ except Thyroid.

2) Less than or equal to 75 mrems, Thyroid.

4.5 Onsite Doses (Within Site Boundary)

This section evaluates dose to non-occupationally exposed workers and members of the public that may be onsite for various reasons. The report must include any other information as may be required by the Commission to estimate maximum potential annual radiation doses to the public resulting from effluent releases as required by 10 CFR 50.36a(a)(2). While within controlled or restricted areas, the limits from Sections 4.1 through 4.4 do not apply; however, 10 CFR 20.1301 dose limit of 100 mrem per year TEDE and dose rate limit of 2 mrem per hour from external sources continue to apply. Occupancy times within the controlled areas are generally sufficiently low to compensate for the increase in the atmospheric dispersion factor above the site boundary. Groups of concern include onsite non radiologically badged workers and National Guard located at the National Guard Headquarters. Use of a conservative assumption of 2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months s/year spent inside the site boundary for the non-dosimetry badged workers and 2500 hour0.0289 days 0.694 hours 0.00413 weeks 9.5125e-4 months s/year for the National Guard conservatively represents the most-exposed individual.

Table 3, Non-Occupationally Exposed Individual Dose Total Body Dose (mrem) External Dose Approx.

0cc.

Location Sector Distance Iodine, Factor TLD and (Meters) Noble Gas Particulate, C- Total Gamma 14 & H-3 Site Boundarv w 524 0.23 3.67E-03 4.34E-04 6.66E-01 6.?0E-01 National NNW 2400 0.29 5.60E-05 1.61 E-05 5.86E-02 5.87E-02 Guard

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 17 of 59 Companv: Constellation I Plant: LaSalle County Station Units 1 and 2 5.0 SUPPLEMENTAL INFORMATION 5.1 Gaseous Batch Releases 5.1.1 LAS Site There were no gaseous batch releases for 2022.

5.2 Liquid Batch Releases 5.2.1 LAS Site There were no liquid batch releases in 2022.

5.3 Abnormal Releases 5.3.1 Gaseous Abnormal Releases There were no abnormal releases for 2022.

5.3.2 Liquid Abnormal Releases There were no abnormal releases for 2022.

5.4 Land Use Census Changes There were no changes to the Land Use Census in 2022 that impacted the REC program .

5.5 Meteorological Data LaSalle meteorological monitoring program achieved 99.9% joint data recovery for 2022.

5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days There were no effluent monitoring time clocks exceeding 30 days during 2022 .

5.7 Offsite Dose Calculation Manual (ODCM) Changes There were no changes to the Offsite Dose Calculation Manual in 2022.

5.8 Process Control Program (PCP) Changes There were no changes to the Process Control Program processing systems or components in 2022.

5.9 Radioactive Waste Treatment System Changes There were no changes to the Radioactive Waste Treatment System in 2022.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 18 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 5.10 Other Supplemental Information 5.10.1 Average Energy

1. Not applicable - average energy is no longer used to determine dose to the public.

2. Measurements and Approximations of Total Radioactivity 5.10.2 Gaseous Effluents

1. The Containment Vent and Purge System (DW) is sampled prior to release by grab sample and analyzed for principal noble gas gamma emitters and H-3.

2. The Station Vent Stack (SVS) is sampled weekly by grab sample and analyzed for principal noble gas gamma emitters and H-3.

3. The Standby Gas Treatment (SBGT) System is sampled by grab sample whenever there is flow and analyzed for principal noble gas gamma emitters.

4. All release types as listed in 5.10.2.1 and 5.10.2.2 above are sampled at the SVS Wide Range Gas Monitor (WRGM), and those listed in 5.10.2.3 above are sampled at the SBGT WRGM whenever there is flow. These effluents are continuously sampled by charcoal cartridge and particulate filter paper. They are analyzed for iodines and principal gamma emitters, respectively. Particulate filter papers are composited and analyzed for gross alpha (monthly) and Fe-55, Sr 89, and Sr 90 (quarterly). Noble gases, gross beta and gamma are continuously monitored by noble gas monitors for the SVS and the SBGT System.

5. The Off Gas Post Treatment (OG Post) system is sampled weekly by grab sample for principle noble gas gamma emitters. The post treatment sample point was added in 2022 to the gaseous effluent program. Reg Guide 1.21 part 1.2 states major release points on gaseous effluents should be monitored to avoid dilution effects. Therefore, the total curies released in 2022 increased compared to previous effluent reports.

5.10.3 Liquid Effluents

1. Batch waste release tanks are sampled and analyzed for principal gamma emitters, 1-131, dissolved and entrained noble gases, H-3, gross alpha, Sr-89, Sr-90 and Fe-55.

2. Continuous releases are sampled continuously in proportion to the rate of flow of the effluent stream and by grab sample. Samples are analyzed for principal gamma emitters, 1-131, dissolved and entrained noble gases, H-3, gross alpha, Sr-89, Sr-90 and Fe-55.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 19 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2

3. LaSalle Unit 1 During refueling outage L1R19 , chemical cleaning of the condenser was conducted by first utilizing an acidic solution then, upon completion, a planned release of the acidic solution to the cooling lake. The planned release to the lake included a pH range to ensure NPDES compliance. The release was planned to be radiologically clean. During the chemical cleaning, leakage was observed from the circulating water expansion joints, collecting in the condenser pit area inside the plant. The 60,000 gallons of leakage were removed from the condenser pit area to temporary storage (frac) tanks for disposition. Sampling identified low level activity due to the leakage flow path across the condenser external surfaces and condenser pit flooring. Tritium, cobalt-60, and manganese-54, and cesium-137 were the isotopes present. The low pH of the frac tank contents complicated treatment options. The addition of high pH lake water to frac tank water was used to adjust the pH of the acidic solution prior to discharge. The pH adjustment resulted in a 5: 1 dilution rendering radioactivity less than ODCM required effluent LLDs. However, a dose calculation was performed utilizing consumption of fish from the lake as well as the maximum observed activity values in the frac tanks prior to pH adjustment, as a bounding case. The resulting Adult Total Body dose was 1.82E-05 mrem and to the Teenager Liver 2.74E-05 mrem. A member of the public that consumes fish from onsite sources are subject to 100 mrem dose limit per 10 CFR 20.1301. This dose represents less than 2.74E-05% of the limit. Measured values at the plant's permitted outfall, the cooling pond blowdown to the Illinois River, remained undetectable as counted to effluent LLDs. Additionally, fish from the cooling lake were sampled and analyzed with results below detection limits.

5.10.4 Temporary Outside Tanks In 2022 no temporary tanks were used that exceeded 1O Curies of activity excluding tritium.

5.10 .5 Independent Spent Fuel Storage Installation 0SFSI) Monitoring Program During the period January 1, through December 31, 2022, no radioactive effluents were released from the LaSalle Nuclear Station Independent Spent Fuel Storage Installation (ISFSI). Also, during this period, no casks were transferred to the outdoor concrete ISFSI storage pad. There are a total of 49 casks on the pad.

5.10 .6 Carbon-14 Carbon-14 (C-14) is a naturally occurring radionuclide with a 5730-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 LaSalle County Station 2022 total curies of C-14 released is based upon the following assumptions:

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 20 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2

a normalized C-14 production rate of 5.1 Ci/GWt-yr,

a gaseous release fraction of 0.99,

a reactor power rating of 3546 MWt (per Unit),

a Unit 1 equivalent full power operation of 336.7 days and a Unit 2 equivalent full power operation of 358.4 days.

In accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," the NRC recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate. Carbon-14 production and release estimates were calculated using EPRI Report 1021106, "Estimation of Carbon-14 in Nuclear Plant Gaseous Effluents".

This calculation uses active core coolant mass, average neutron flux by energy and reactor coolant nitrogen concentrations to determine Carbon-14 generation based upon an effective full power year. The estimated generation for LaSalle County Station Units 1 and 2 during 2022 was 34.29 Ci of C-14 produced.

Public dose estimates were performed using methodology from the ODCM which is based on Regulatory Guide 1.109 methodology. Carbon dioxide is assumed to make up 20-30% of the Carbon-14 gaseous emissions from PWR stations and 95% of gaseous emissions from BWR stations. At LAS the total 34.29 Ci of C-14 produced only 95% is released as CO2 (32.57 Ci), which then can be incorporated into the environment for dose analysis. C-14 dose is included in dose calculation results in Table 1 and Table 2.

5.10.7 Errata/Corrections to Previous ARERRs There are no corrections to previous ARERRs.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 21 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM LaSalle County Station Units 1 and 2 has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document [9]. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning.

This section is included in this report to communicate results of NEI 07-07 Radiological Groundwater Monitoring Program. Monitoring wells installed as part of GPI program are sampled and analyzed on a frequency based upon well location, assessed risk, and site hydrogeology as described in the RGPP. In addition to reporting results from NEI 07-07 monitoring wells, new voluntary communications made for onsite leaks or spills per NEI 07-07 Objective 2.2, are also reported as part of this report. It is important to note, samples and results taken in support of NEI 07-07 groundwater monitoring program are not part of the Radiological Environmental Monitoring Program (REMP) but are reported as part of AREOR.

During 2022, LAS collected and analyzed groundwater samples in accordance with the requirements of EN-LA-408-4160. Samples from 19 different locations were analyzed for tritium activity with values ranging from <LLD to 5,790 pCi/L. There is no feasible pathway into a drinking water supply based on the hydrogeological study conducted as LaSalle. Also, based on established aquifer flow paths the location most representative of potential offsite release into groundwater was also less than the detection limit.

Hard-to-detect analyses were performed on 6 groundwater locations in accordance with the LaSalle RGPP and to aid in establishing background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, and U-238. U-234 was detected in 4 of 6 samples and concentrations ranged from 0.44 to 3.28 pCi/L. U-238 was detected in 4 of 6 samples and concentrations ranged from 0.37 to 1.96 pCi/L. U-234 and U-238 are commonly found in groundwater at low concentrations due to the naturally occurring Radium (Uranium)

Decay Series. The concentrations of U-234 and U-238 are considered to be background and are not the result of plant effluents.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 22 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 Table 4, Groundwater Protection Program Monitoring Well Results Number of Average Type of Number of Maximum Concentration Well Name Positive Concentration 1 Analysis Analyses (pCi/L)

Detections (pCi/L)

HP-2 Tritium 0 1 N/A N/A HP-5 Tritium 0 1 N/A NIA HP-7 Tritium 0 4 NIA NIA Sr-89 0 1 NIA NIA Sr-90 0 1 NIA NIA HP-10 Tritium 0 1 NIA NIA MW-LS-104S Tritium 4 4 621 842 Sr-89 0 1 NIA NIA Sr-90 0 1 NIA NIA Am-241 0 1 NIA NIA Cm-242 0 1 NIA NIA CM-2431244 0 1 NIA NIA Pu-238 0 1 NIA NIA Pu-2391240 0 1 NIA NIA U-234 0 1 NIA NIA U-235 0 1 NIA NIA U-238 0 1 NIA NIA Fe-55 0 1 NIA NIA Ni-63 0 1 NIA NIA MW-LS-105S Tritium 0 4 NIA NIA Sr-89 0 1 NIA NIA Sr-90 0 1 NIA NIA MW-LS-106S Tritium 0 1 NIA NIA MW-LS-107S Tritium 0 4 NIA NIA Sr-89 0 1 NIA NIA Sr-90 0 1 NIA NIA Am-241 0 1 NIA NIA Cm-242 0 1 NIA NIA CM-2431244 0 1 NIA NIA Pu-238 0 1 NIA NIA Pu-2391240 0 1 NIA NIA U-234 1 1 3.28 3.28 U-235 0 1 NIA NIA 1 Results <MDA should not be included in the average concentration calculation.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 23 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 Table 4, Groundwater Protection Program Monitoring Well Results Number of Average Type of Number of Maximum Concentration Well Name Positive Concentration 1 ,

Analysis Analyses (pCilL)

Detections (pCilL)

U-238 1 1 1.96 1.96 Fe-55 0 1 NIA NIA Ni-63 0 1 NIA NIA MW-LS-111S Tritium 0 1 NIA NIA OIL SEPARATOR Tritium 0 4 NIA NIA Sr-89 0 1 NIA NIA Sr-90 0 1 NIA NIA Am-241 0 1 NIA NIA Cm-242 0 1 NIA NIA CM-2431244 0 1 NIA NIA Pu-238 0 1 NIA NIA Pu-2391240 0 1 N/A N/A U-234 1 1 0.67 0.67 U-235 0 1 NIA NIA U-238 1 1 0.48 0.48 Fe-55 0 1 NIA NIA Ni-63 0 1 NIA NIA RW-LS-100S Tritium 4 4 880 1380 Sr-89 0 1 N/A N/A Sr-90 0 1 N/A N/A Am-241 0 1 NIA N/A Cm-242 0 1 NIA N/A CM-243/244 0 1 NIA N/A Pu-238 0 1 NIA NIA Pu-2391240 0 1 NIA NIA U-234 0 1 NIA N/A U-235 0 1 N/A N/A U-238 0 1 N/A N/A Fe-55 0 1 N/A N/A Ni-63 0 1 NIA N/A RW-LS-101S Tritium 6 6 1037 1400 Sr-89 0 1 NIA NIA Sr-90 0 1 NIA NIA Am-241 0 1 N/A N/A Cm-242 0 1 N/A N/A

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 24 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 Table 4, Groundwater Protection Program Monitoring Well Results Number of Average Type of Number of Maximum Concentration Well Name Positive Concentration 1 Analysis Analyses (pCi/L)

Detections (pCi/L)

CM-243/244 0 1 N/A N/A Pu-238 0 1 NIA NIA Pu-239I240 0 1 N/A N/A U-234 1 1 0.44 0.44 U-235 0 1 N/A NIA U-238 1 1 0.37 0.37 Fe-55 0 1 N/A N/A Ni-63 0 1 N/A NIA TW-LS-114S Tritium 0 4 N/A N/A TW-LS-116S Tritium 5 5 3096 3550 Sr-89 0 1 NIA NIA Sr-90 0 1 NIA N/A TW-LS-117S Tritium 0 4 NIA N/A Sr-89 0 1 N/A N/A Sr-90 0 1 NIA NIA TW-LS-118S Tritium 4 4 4030 5790 Sr-89 0 1 NIA NIA Sr-90 0 1 NIA NIA Am-241 0 1 N/A N/A Cm-242 0 1 N/A N/A CM-243I244 0 1 NIA NIA Pu-238 0 1 NIA NIA Pu-239I240 0 1 NIA NIA U-234 1 1 1.46 1.46 U-235 0 1 N/A NIA U-238 1 1 1.18 1.18 Fe-55 0 1 NIA NIA Ni-63 0 1 N/A NIA TW-LS-119S Tritium 0 4 N/A NIA Sr-89 0 1 NIA N/A Sr-90 0 1 N/A N/A TW-LS-120S Tritium 0 4 N/A NIA Sr-89 0 1 N/A NIA Sr-90 0 1 NIA N/A TW-LS-121S Tritium 0 2 N/A N/A

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 25 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 6.1 Voluntary Notification During 2022, LaSalle County Station Units 1 and 2 did not make any voluntary NEI 07-07 notification to State/Local officials, NRC, and to other stakeholders required by site procedures.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 26 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 7.0 BIBLIOGRAPHY

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

[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] [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 1O November 2020].

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

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

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

Nuclear Regulatory Commission, Ocotober, 1977.

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

Nuclear Regulatory Commission, 1987.

[9] "NEI 07 Industry Ground Water Protection Initiative - Final Guidance Document, Rev. 1,"

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

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

[11] "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.

[12] "1 O CFR 50 - Domestic Licensing of Production and Utilization Facilities," US Nuclear Regulatory Commission, Washington, DC.

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

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

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

[16] "40 CFR Part 141, "National Primary Drinking Water Regulations,"," US Environmental Protection Agency, Washington, DC ..

[17] "40 CFR 190 - Environmental Radiation Protection Standards for Nuclear Power Operation," US Environmental Protection Agency, Washington, DC.

[18] "10 CFR 20 - Standards for Protection Against Radiation," US Nuclear Regulatory Commission, Washington, DC.

Annual Radioactive Effluent Release Report I YEAR: 2022 I Page 27 of 59 Company: Constellation I Plant: LaSalle County Station Units 1 and 2 Attachment 1, ARERR Release Summary Tables (RG-1.21 Tables) 1.0 GASEOUS EFFLUENTS Table 5, Gaseous Effluents Summation of All Releases from the Site Est. Total A. Fission & Activation Gases Unit Quarter 1 Quarter 2 Quarter 3 Quarter4 Total Error%

1. Total Release Ci 9.30E+01 1.30E+02 3.25E+02 3.18E+02 8.66E+02 2.50E+01

2. Average release rate for the period µCi/sec 1.18E+01 1.65E+01 4.12E+01 4.04E+01 1.10E+02