Text

Annual Radiological Environmental Operating Report
	ML25135A075
Person / Time
Site:	Quad Cities
Issue date:	05/15/2025
From:	Hild D; Constellation Energy Generation
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	SVP-25-028
	Download: ML25135A075 (1)
	v • d • e

{{#Wiki_filter:Constellation.. SVP-25-028 May 15, 2025 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRG Docket Nos. 50-254 and 50-265 Annual Radiological Environmental Operating Report Pursuant to Technical Specifications Section 5.6.2, enclosed is the 2024 Radiological Environmental Operating Report for Quad Cities Nuclear Power Station. This Report contains the results of the Radiological Environmental Monitoring Program (REMP). In addition, the 2024 Radiological Groundwater Protection Program (RGPP) Report is included at the conclusion of the Annual Radiological Environmental Operating Report. Should you have any questions concerning this letter, please contact Blake Young at (309) 227-3200. Respectfully, II+~ Doug Hild Site Vice President Quad Cities Nuclear Power Station : Annual Radiological Environmental Operating Report cc: Regional Administrator-NRG Region Ill NRG Senior Resident Inspector - Quad Cities Nuclear Power Station Annual Radiological Environmental Operating Report

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page O of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Annual Radiological Environmental Operating Report 2024 Document Number: 50-254/50-265

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 1 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS.................................................................................. 3 2.0 EXECUTIVE

SUMMARY

............................................................................................................. 4 2.1 Summary of Conclusions................................................................................................. 5

3.0 INTRODUCTION

......................................................................................................................... 6 4.0 SITE DESCRIPTION AND SAMPLE LOCATIONS...................................................................... 7 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS.................. 8 6.0 MAPS OF COLLECTION SITE.................................................................................................. 15 7.0 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES.................................................................................................. 17 8.0 SAMPLING PROGRAM, PROGRAM MODIFICATION AND INTEPRETATION OF RESULTS.................................................................................................................................. 18 8.1 Environmental Direct Radiation Dosimetry Results......................................................... 18 8.2 Air Particulate and Radioiodine Sample Results............................................................. 19 8.3 Waterborne Sample Results.......................................................................................... 20 8.4 Ingestion Pathway Sample Results................................................................................ 21 9.0 LAND USE CENSUS................................................................................................................. 22 10.0 SAMPLE DEVIATIONS, ANOMALIES AND UNAVAILABILITY.................................................. 24 11.0 OTHER SUPPLEMENTAL INFORMATION............................................................................... 25 11.1 NEI 07-07 Onsite Radiological Groundwater Monitoring Program................................... 25 11.2 Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program...................... 25 11.3 Corrections to Previous Reports..................................................................................... 26 12.0 BIBLIOGRAPHY........................................................................................................................ 27 TABLES Table 1, Radiological Environmental Sampling Program - Exposure Pathway - Direct Radiation........... 8 Table 2, Radiological Environmental Sampling Program - Exposure Pathway - Airborne....................... 9 Table 3, Radiological Environmental Sampling Program - Exposure Pathway-Waterborne................ 10 Table 4, Radiological Environmental Sampling Program - Exposure Pathway - Ingestion.................... 11 Table 5, REMP Sampling Locations-Direct Radiation........................................................................ 12 Table 6, Reporting Levels for Radioactivity Concentrations in Environmental Samples......................... 17 Table 7, Maximum Values for the Limit of Detection............................................................................. 17 Table 8, Land Use Census-Nearest Receptors within 5 miles............................................................ 23 Table 9: Sample Deviation Summary................................................................................................... 24 Table 10, Quad Cities Data Summary Table........................................................................................ 29 Table 11, Weekly Air Particulate Gross Beta (E*3 pCi/m3)..................................................................... 34 Table 12, Quarterly Air Particulate Gamma Isotopic (pCi/m3 +/- 2 Sigma)............................................... 37 Table 13, Weekly Air Iodine 1-131 (E*3 pCi/m3)...................................................................................... 40 Table 14, Monthly/Bi-Weekly Milk 1-131 (pCi/L +/- 2 Sigma).................................................................... 43 Table 15, Monthly/Bi-Weekly Milk Gamma Isotopic (pCi/L +/- 2 Sigma).................................................. 44 Table 16, Annual Food Products Gamma Isotopic (pCi/kg Wet+/- 2 Sigma)........................................... 45

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 2 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 17, Monthly Surface Water Gross Beta (pCi/L +/- 2 Sigma)........................................................... 46 Table 18, Monthly Surface Water Gamma Isotopic (pCi/L +/- 2 Sigma)................................................... 47 Table 19, Quarterly Surface Water Tritium, lron-55, and Nickel-63 (pCi/L +/- 2 Sigma).......................... 49 Table 20, Quarterly Ground Water Tritium (pCi/L +/- 2 Sigma)................................................................ 50 Table 21, Quarterly Ground Water Gamma Isotopic (pCi/L +/- 2 Sigma)................................................. 51 Table 22, Semi-Annual Fish Gamma Isotopic (pCi/kg Wet+/- 2 Sigma).................................................. 52 Table 23, Semi-Annual Shoreline Sediment Gamma Isotopic (pCi/kg Dry+/- 2 Sigma).......................... 53 Table 24, Analytics Environmental Radioactivity Cross Check Program............................................... 57 Table 25, DOE's Mixed Analyte Performance Evaluation Program (MAPEP)........................................ 59 Table 26, ERA Environmental Radioactivity Cross Check Program...................................................... 61 FIGURES Figure 1, Potential exposure pathways to Members of the Public due to Plant Operations (7]................. 6 Figure 2, Map of Quad Cities REMP Sampling Locations-2 Mile Radius, 2024..................................... 15 Figure 3, Map of Quad Cities Sampling Locations-9.3 Mile Radius, 2024............................................ 16 Figure 4, Air Particulate: Analysis for Gross Beta, Average for All Indicator vs. Control Location.......... 19 ATTACHMENTS, Data Table Summary..................................................................................................... 29, Complete Data Table for All Analysis Results Obtained In 2024.................................... 34, Cross Check lntercomparison Program......................................................................... 54, Environmental Direct Radiation Dosimetry Results........................................................ 63

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 3 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 1.0 LIST OF ACRONYMS AND DEFINITIONS

1.

Airborne Activity Sampling: Continuous sampling of air through the collection of particulates and radionuclides on filter media.

2.

ARERR: Annual Radioactive Effluent Release Report

3.

AREOR: Annual Radiological Environmental Operating Report

4.

BWR: Boiling Water Reactor

5.

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.

6.

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

7.

Curie (Ci): A measure of radioactivity; equal to 3. 7 x 1010 disintegrations per second, or 2.22 x 1012 disintegrations per minute.

8.

Direct Radiation Monitoring: The measurement of radiation dose at various distances from the plant is assessed using Thermoluminescent Dosimeters (TLD), Optically Stimulated Luminescence Dosimeters (OSLO) and pressurized ionization chambers.

9.

EPA: Environmental Protection Agency

10.

GPI: Groundwater Protection Initiative

11.

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

12.

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

13.

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.

14.

ISFSI: Independent Spent Fuel Storage Installation

15.

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

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 4 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2

16.

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.

17.

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

18.

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

19.

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

20.

N/A: Not Applicable

21.

NEI: Nuclear Energy Institute

22.

NIST: National Institute of Standards and Technology.

23.

NRC: Nuclear Regulatory Commission

24.

ODCM: Offsite Dose Calculation Manual

25.

OSLO: Optically Stimulated Luminescence Dosimeter

26.

pCi/L: picocuries / Liter

27.

PWR: Pressurized Water Reactor

28.

REMP: Radiological Environmental Monitoring Program

29.

TLD: Thermoluminescent Dosimeter 2.0 EXECUTIVE

SUMMARY

Quad Cities Nuclear Power Station Units 1 and 2 Radiological Environmental Monitoring Program (REMP) was established prior to the station becoming operational to provide information on background radiation present in the area. The goal of Quad Cities REMP is to evaluate the impact of the station on the environment. Environmental samples from different media are monitored as part of the program in accordance with specifications detailed in the Offsite Dose Calculation Manual (ODCM).The program compares data from Indicator locations near the plant, to Control locations farther away from the site to assess operation impacts.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 5 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 The Annual Radiological Environmental Operating Report (AREOR) provides data obtained through analyses of environmental samples collected at Quad Cities for the reporting period of January 1st through December 31st, 2024. During that time period 1,529 analyses were performed on 1,413 samples. In assessing all the data gathered for this report and comparing these results with preoperational data and/or 10-year average values, it was concluded that the operation of Quad Cities, had no adverse radiological impact on the enviroment. 2.1 Summary of

Conclusions:

No measurable activities above background levels were detected. All values were consistent with historical results which indicate no adverse radiological environmental impacts associated with the operation of Quad Cities. Naturally occurring radionuclides are present in the Earth's crust and atmosphere and exists in detectable quantities throughout the world. It is common to detect naturally occurring radionuclides in many of the samples collected for REMP. Some examples of naturally occurring radionuclides that are frequently seen in samples are potassium-40, beryllium-7, actinium-228 (present as a decay product of radium-228), and radium-226. Additionally, some relatively long-lived anthropogenic radioisotopes, such as strontium-90 and cesium-137, are also seen in some REMP samples; these radionuclides exist in measurable quantities throughout the world as a result of fallout from historic atmospheric nuclear weapons testing. Detailed information on the exposure of the U.S. population to ionizing radiation can be found in NCRP Report No. 160 [1].

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 6 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2

3.0 INTRODUCTION

The Radiological Environmental Monitoring Program (REMP) provides data on measurable levels of radiation and radioactive materials in the environment. This program also evaluates the relationship between quantities of radioactive materials released from the plant and resultant doses to individuals from principal pathways of exposure. In this capacity, REMP provides a check on the effluent release program and dispersion modeling to ensure that concentrations in the environment due to radioactive effluents conform to the "As Low as Is Reasonably Achievable" (ALARA) design objectives of 1 O CFR 50, Appendix I [2], and implements the requirements of Section IV.B.2 and IV.B.3 of Appendix I. REMP is designed to conform to the Nuclear Regulatory Commission (NRC) Regulatory Guide 4.1 [3], NUREG 1301/1302 [4] [5], and the 1979 NRC Branch Technical Position [6]. 0 Deposition Li\\'estock products

- - - - Ingest'

~i C9. \\ Inhalation '4 \\ Deposition \\~ / 0

- ** Ingestion ***

0 ~ Marine produc'ls

- - - Ingestion

Radiation o

Radionuclides

.. * : Behavior of radionuclides Figure 1, Potential exposure pathways to Members of the Public due to Plant Operations [7]

Quality assurance aspects of the sampling program and TLD/OSLD data collection are conducted in accordance with Regulatory Guides 4.15 [8] and 4.13 [9]. REMP also adheres to the requirements of Illinois, Quad Cities Technical Specifications, and Offsite Dose Calculation Manual (ODCM). These governing documents dictate the environmental sampling, sample analysis protocols, data reporting and quality assurance requirements for the environmental monitoring program.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 7 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 The Annual Radiological Environmental Operating Report provides summaries of the environmental data from exposure pathways, interpretations of the data, and analyses of trends of the results. Routinely monitored pathways include ingestion, inhalation, and direct radiation. Routes of exposure are based on site specific information such as meteorology, receptor locations, and water usage around the plant. 4.0 SITE DESCRIPTION AND SAMPLE LOCATIONS The Quad Cities Nuclear Power Station (QCNPS), consisting of two 2,957 MWth boiling water reactors owned and operated by Constellation Energy Corporation, is located in Cordova, Illinois along the Mississippi River. Unit No.1 went critical on 16 March 1972. Unit No. 2 went critical on 02 December 1973. The site is located in northwestern Illinois, approximately 182 miles west of Chicago, Illinois. Quad Cities sampling media are selected based on site specific information such as meteorology, receptor locations, and water usage around the plant. Sampling and analysis frequencies are documented in the Offsite Dose Calculation Manual and site procedures. Required sampling, analysis frequencies and location of sample collected are captured in the following tables and figures: Figure 1, Potential exposure pathways to Members of the Public due to Plant Operations Table 1, Radiological Environmental Sampling Program - Exposure Pathway-Direct Radiation Table 2, Radiological Environmental Sampling Program-Exposure Pathway-Airborne Table 3, Radiological Environmental Sampling Program - Exposure Pathway - Waterborne Table 4, Radiological Environmental Sampling Program - Exposure Pathway - Ingestion Table 5, REMP Sampling Locations - Direct Radiation Map of Quad Cities REMP Sampling Locations-2 Mile Radius, 2024 Figure 3, Map of Quad Cities Sampling Locations-9.3 Mile Radius, 2024

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 8 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS Table 1, Radiological Environmental Sampling Program - Exposure Pathway - Direct Radiation Sample Location Description, Sampling Requirement Distance, and Direction Collection/ Type and Frequency of Analyses Frequency Direct Radiation Seventy-two OSLD monitoring stations with two or more dosimeters placed as follows: An inner ring of stations, one in each compass sector in the general area of the site boundary. Table 5 Quarterly Gamma dose/Quarterly An outer ring of stations, one in each compass sector at approximately 5 miles from the site; and Special interest areas, such as population centers, nearby recreation areas, and control stations

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 9 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 2, Radiological Environmental Sampling Program - Exposure Pathway-Airborne Sample Location Description, Sampling Requirement Collection/ Type and Frequency of Analyses Distance, and Direction Frequency Airborne Radioiodine and Particulates Q-01 Onsite 1, 0.5 miles N Particulate sampler: Analyze for gross Samples from 10 locations: Q-02 Onsite 2, 0.4 miles ENE beta radioactivity::?: 24 hours following Q-03 Onsite 3, 0.6 miles S filter change weekly. Perform gamma Four locations close to the site boundary in different Q-04 Nitrin, 1. 7 miles NE Continuous isotopic analysis on each sample when sectors of the highest calculated annual average Q-13 Princeton, 4.7 miles SW sampler gross beta activity is >10 times the ground level O/Q. operation yearly mean of control samples. Q-16 Low Moor, 5.7 miles NNW with sample Perform gamma isotopic analysis on Five samples from the vicinity of a community having Q-37 Meredosia Rd, 4.4 miles ENE collection composite sample (by location) the highest calculated annual average O/Q. Q-38 Fuller Rd, 4.7 miles E weekly quarterly. Q-41 Camanche Upstream, 4.3 miles One sample from Control Locations between 4 - 8 NNE Radioiodine canister: 1-131 analysis miles away in the least predominant wind direction. Q-42 LeClaire (C), 9.1 miles SSW weekly.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 10 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 3, Radiological Environmental Sampling Program - Exposure Pathway - Waterborne Requirement Sample Location Description, Distance, Sampling Collection/ Frequency Type and Frequency of and Direction Analyses Surface Water Gamma isotopic Monthly Monthly composite sample from Gross beta Monthly One sample upstream Q-33 Cordova, 3.1 miles SSW weekly grab samples; quarterly H-3 Quarterly (control) and one sample Q-34 Camanche(C), 4.4 miles NNE composite from weekly grab downstream (indicator) samples Fe-55 Quarterly Ni-63 Quarterly Groundwater Gamma isotopic Q-35 McMillan Well, 1.5 miles S Quarterly Two indicator location down Q-36 Cordova Well, 3.3 miles SSW Quarterly grab samples H-3 Quarterly gradient from the plant. Sediment from Shoreline Q-39 Cordova on Mississippi River,0.5 miles One sample upstream SW Semiannual grab samples Gamma isotopic ( control) and one sample Q-40 North of Albany on Mississippi Semiannually downstream (indicator) River(C),8.9 miles NE

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 11 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 4, Radiological Environmental Sampling Program - Exposure Pathway-Ingestion Requirement Sample Location Description, Distance, and Sampling Collection/ Type and Frequency Direction Frequency of Analyses Milk One sample from milking animals in three locations within 5km distance Gamma isotopic and having the highest dose potential. If Biweekly when animals 1-131 Biweekly when there are none, then one sample Q-26 Bill Stanley Dairy 3.5 miles ESE are on pasture; monthly animals are on pasture; from milking animals in each of at other times monthly at other times. three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr. Fish One sample of each commercially and recreationally important species Gamma isotopic in vicinity of site discharge. Q-24 Pool #14 Mississippi River, 0.5 miles SW Semiannually analysis on edible Q-29 Mississippi River (C), 1.0 miles N portions, each sample One sample of same species in areas not influenced by plant discharge Food Products Quadrant 1 Ken DeBaille 2.3 miles ENE Five locations producing vegetables Quadrant 2 Kent Wirth 3.0 ESE Gamma isotopic, each from areas irrigated by water in Quadrant 3 Amy Johnston 1.8 miles S Annually which liquid plant wastes have been Quadrant 4 James Fawcett 4.5 miles NW sample discharged and one sample collected from a control location. Control Kenneth Roeder 9.5 miles NE

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 12 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 5, REMP Sampling Locations-Direct Radiation Site# Location Type Sector Distance Description Q-01-1 Special Interest N 0.5 miles Onsite 1 Q-02-1 Special Interest ENE 0.4 miles Onsite 2 Q-03-1 Special Interest s 0.6 miles Onsite 3 Q-04-1 Special Interest NE 1.7 miles Nitrin Q-13-1 Special Interest SW 4.7 miles Princeton Q-16-1 Special Interest NNW 5.7 miles Low Moor Q-37-1 Special Interest ENE 4.4 miles Meredosia Q-38-1 Special Interest E 4.7 miles Fuller Road Q-41-1 Special Interest NNE 4.3 miles Camanche Q-42 Control SSW 8.7 miles LeClaire Q-101-1 Inner Ring N 0.6 miles Q-101-2 Inner Ring N 0.9 miles Q-102-1 Inner Ring NNE 1.3 miles Q-102-3 Inner Ring NNE 1.4 miles Q-103-1 Inner Ring NE 1.2 miles Q-103-2 Inner Ring NE 1.2 miles Q-104-1 Inner Ring ENE 1.1 miles Q-104-2 Inner Ring ENE 0.9 miles Q-105-1 Inner Ring E 0.8 miles Q-105-2 Inner Ring E 0.8 miles Q-106-2 Inner Ring ESE 0.7 miles Q-106-3 Inner Ring ESE 0.7 miles Q-107-2 Inner Ring SE 0.7 miles Q-107-3 Inner Ring SE 0.8 miles Q-108-1 Inner Ring SSE 1.0 miles Q-108-2 Inner Ring SSE 0.9 miles Q-109-1 Inner Ring s 0.9 miles

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 13 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 5, REMP Sampling Locations - Direct Radiation Site# Location Type Sector Distance Description Q-109-2 Inner Ring s 1.2 miles Q-111-1 Inner Ring SW 2.6 miles Q-111-2 Inner Ring SW 2.5 miles Q-112-1 Inner Ring WSW 2.5 miles Q-112-2 Inner Ring WSW 2.2 miles Q-113-1 Inner Ring w 2.5 miles Q-113-2 Inner Ring w 2.5 miles Q-114-1 Inner Ring WNW 2.1 miles Q-114-2 Inner Ring WNW 2.5 miles Q-115-1 Inner Ring NW 2.6 miles Q-115-2 Inner Ring NW 2.3 miles Q-116-1 Inner Ring NNW 2.3 miles Q-116-3 Inner Ring NNW 2.4 miles Q-201-1 Outer Ring N 4.2 miles Q-201-2 Outer Ring NNE 4.2 miles Q-202-1 Outer Ring NNE 4.4 miles Q-202-2 Outer Ring NNE 4.8 miles Q-203-1 Outer Ring NE 4.7 miles Q-203-2 Outer Ring NE 5.0 miles Q-204-1 Outer Ring ENE 4.7 miles Q-204-2 Outer Ring ENE 4.5 miles Q-205-1 Outer Ring E 4.7 miles Q-205-4 Outer Ring E 4.8 miles Q-206-1 Outer Ring ESE 4.8 miles Q-206-2 Outer Ring ESE 4.8 miles Q-207-1 Outer Ring SE 4.7 miles Q-207-4 Outer Ring SE 4.7 miles

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 14 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 5, REMP Sampling Locations-Direct Radiation Site# Location Type Sector Distance Description Q-208-1 Outer Ring SSE 4.3 miles Q-208-2 Outer Ring SSE 4.9 miles Q-209-1 Outer Ring s 4.7 miles Q-209-4 Outer Ring s 4.7 miles Q-210-1 Outer Ring SSW 4.1 miles Q-210-5 Outer Ring SSW 3.3 miles Q-211-1 Outer Ring SW 4.5 miles Q-211-2 Outer Ring SW 4.5 miles Q-212-1 Outer Ring WSW 4.9 miles Q-212-2 Outer Ring WSW 4.4 miles Q-213-1 Outer Ring w 4.3 miles Q-213-2 Outer Ring w 4.8 miles Q-214-1 Outer Ring WNW 4.7 miles Q-214-2 Outer Ring WNW 4.4 miles Q-215-1 Outer Ring NW 5.0 miles Q-215-2 Outer Ring NW 4.2 miles Q-216-1 Outer Ring NNW 4.6 miles Q-216-2 Outer Ring NNW 4.3 miles

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 15 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 6.0 MAPS OF COLLECTION SITE Figure 2, Map of Quad Cities REMP Sampling Locations-2 Mile Radius, 2024 North NNW NNE w i ~ / - L t f --..J II SE -} I SE ,~ UAO CITIES TATION ' alioM NOTE: All closlmeter locatiom cootain two cmimetere, ex rwrrt:sri,rJ corwention 102-1 I 102-tA

Annual Radiological Environmental Operating Report l YEAR: 2024 l Page 16 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Figure 3, Map of Quad Cities Sampling Locations-9.3 Mile Radius, 2024 A~tA.ftllll 1~ --- All dosimeter locations conuin two dosimeters. ex. numbering convention 102-1/102-IA

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 17 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 7.0 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Table 6, Reporting Levels for Radioactivity Concentrations in Environmental Samples Water Air Particulates Fish (pCi/kg-Food Radionuclide or Gases Milk (pCi/L) Products (pCi/L) (pCi/m3) wet) (pCi/Kg-wet) H-3 20,000<1> NA NA NA NA Mn-54 1,000 NA 30,000 NA NA Fe-59 400 NA 10,000 NA NA Co-58 1,000 NA 30,000 NA NA Co-60 300 NA 10,000 NA NA Zn-65 300 NA 20,000 NA NA Zr-Nb-95 400 NA NA NA NA 1-131 2 (2) 0.9 NA 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 NA NA 60 NA Table 7, Maximum Values for the Limit of Detection Water Air Particulates Fish Milk Food Products Sediment Radionuclide or Gases (pCi/L) (pCi/m3) (pCi/kg-wet) (pCi/L) (pCi/Kg-wet) (pCi/Kg-dry) GR-B 4 0.01 NA NA NA H-3 2,000 (3) NA NA NA NA Mn-54 15 NA 130 NA NA Fe-59 30 NA 260 NA NA Co-58, Co-60 15 NA 130 NA NA Zn-65 30 NA 260 NA NA Zr-Nb-95 15 NA NA NA NA 1-131 1 (4) 0.07 NA 1 60 Cs-134 15 0.05 130 15 60 Cs-137 18 0.06 150 18 80 Ba-La-140 15 NA NA 15 NA 1 For drinking water samples: If no drinking water pathway exists, a value of 30,000 pCi/L may be used. 2 If no drinking water pathway exists, a value of 20 pCi/I may be used NA NA NA NA NA NA NA NA 150 180 NA 3 If no drinking water pathway exists, a value of 3,000 pCi/L may be used. Some states may require a lower LLD for drinking water sources-per 40 CFR 141 Safe drinking water ACT. 4 If no drinking water pathway exists, a value of 15 pCi/1 may be used

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 18 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 8.0 SAMPLING PROGRAM, PROGRAM MODIFICATION AND INTEPRETATION OF RESULTS 8.1 At most nuclear stations, data was collected prior to plant operation to determine background radioactivity levels in the environment. Annual data is routinely compared to preoperational and/or 10-year average values to determine if changes in the environs are present. Strict comparison is difficult to make due to fallout from historical nuclear weapon testing. Cesium-137 can be routinely found in environmental samples as a results of above ground nuclear weapons testing. It is important to note, levels of Cs-137 in environment are observed to fluctuate, for example as silt distributions shift due to natural erosion and transport processes, Cs-137 may or may not be observed in sediment samples. Results from samples collected and analyzed during the year, 2024, are described below. In the following sections, results from direct radiation, air, water, and food products analyzed as part of REMP in 2024 will be discussed. Sampling program descriptions and deviations will also be discussed. Environmental Direct Radiation Dosimetry Results Dose is measured as net exposure (field reading less transit reading) normalized to 91-day quarters. Data is treated and analyzed consistent with ANSI/HPS N13.37-2014, which compares the measured dose for each location to the baseline background dose for that location. Environmental dose rates vary by location, depending on geological and land use considerations, and remain relatively constant for any given location (unless land use changes). Some facilities observe seasonal variation in environmental doses. Baseline Background Doses have been determined for both quarterly and annual measurements at each location using historical field measurements. ANSI/HPS N13.37-2014 uses the concept of minimum differential dose (MOD), which is the minimum facility-related dose that can be detected above background. Due to natural background variations and measurement sensitivities and uncertainties, minimum differential dose is not zero. MOD is calculated based on statistical performance of the dosimetry system in the environment and is site specific. Normalized doses that exceed the Minimum Differential Dose value above the Baseline Background Dose are considered to indicate Facility-Related Dose; a quality assurance review is performed to verify that any results indicating Facility-Related Dose are accurate. During the calendar year 2024, a total of 73 locations were monitored and data analyzed in accordance with the requirements in Attachment 4, Environmental Direct Radiation Dosimetry Results, provides the annual direct radiation dosimetry analysis. There was no direct radiation dose detected from the facility. All TLD/OSLD measurements were analyzed, and none were found to have radiation levels that had increased over normal background radiation levels.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 19 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 8.2 Air Particulate and Radioiodine Sample Results Air particulate filters and charcoal canisters were collected from locations specified in Table 2, Radiological Environmental Sampling Program - Exposure Pathway - Airborne. During the calendar year 2024, a total of 520 samples were collected and analyzed for gross beta, gamma emitters and iodine. Particulate samplers are used to continuously collect airborne particulates on a filter. The samples are analyzed for gross beta activity following filter changeout which occurs weekly. Gamma isotopic analysis is also performed on the samples collected at each location and is analyzed quarterly. Naturally occurring beryllium-? was detected on all the control and indicator samples at concentrations consistent with previous years. Radioiodine (1-131) analysis is performed weekly on radioiodine sample cartridges. All gross beta analyses of air particulate filters detected gross beta activity at levels consistent with previous years. All air particulate quarterly gamma composite samples were below the detection limit except for naturally occurring radionuclides. 20 18 16 14 a 12 0 10 Q. '? 8 w 6 4 2 0 Air Particulate: Analysis for Gross Beta, Indicator vs. Control 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 Year ..._Control..._Indicator Figure 4, Air Particulate: Analysis for Gross Beta, Average for All Indicator vs. Control Location Air particulate and radioiodine results from this monitoring period, 2024, were compared to 10-year average as shown in Figure 4, and there were no significant changes.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 20 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 8.3 Waterborne Sample Results 8.3.1 Surface Water (i.e., Bay, Lake etc.) Composite water samples are collected monthly at the upstream control location and at the downstream indicator locations. Monthly composite samples are analyzed for gamma emitters. Aliquots from the monthly composites are combined to form a quarterly composite which is then analyzed for tritium. During the calendar year 2024, a total of 32 surface water samples were collected and analyzed in accordance with the requirements in the ODCM and shown in Table 3, Radiological Environmental Sampling Program - Exposure Pathway - Waterborne. Gross Beta was detected in 22 of the 24 samples with a range of 3 to 7 pCi/L. The required LLD for Gross Beta was met for all samples. Samples from both locations were analyzed for gamma-emitting nuclides. No nuclides were detected and all required LLDs were met. Tritium concentrations in surface water were well below the EPA tritium drinking water limit of 20,000 pCi/L There has been no detectable tritium in any surface water samples in 2024 or the previous 10 years. Therefore, no trend has been established above the detection limit to plot on a trending graph. 8.3.2 REMP Groundwater Groundwater samples were collected from control location upgradient from the plant and indicator location down gradient from the plant. During the calendar year 2024, a total of 8 groundwater samples were collected from offsite monitoring wells and analyzed in accordance with the requirements in the ODCM and shown in Table 3: Radiological Environmental Sampling Program - Exposure Pathway - Waterborne. A total of 2 indicator samples were collected. These samples were analyzed for tritium and gamma quarterly. All groundwater samples were collected in new containers, which were rinsed with source water prior to collection. Samples from all locations were analyzed for gamma-emitting nuclides. No nuclides were detected and all required LLDs were met. Tritium concentrations in groundwater were well below the EPA tritium drinking water limit of 20,000 pCi/L. There has been no detectable tritium in any REMP groundwater samples in 2024 or the previous 10 years. Therefore, no trend has been established above the detection limit to plot on a trending graph. 8.3.3 Sediment from Shoreline Shoreline sediment collections were made in May and October of 2024 and analyzed for gamma-emitting isotopes. Samples are collected at both indicator and control locations. A total of 4 shoreline samples were analyzed in accordance with requirements in the ODCM and shown in Table 3, Radiological Environmental Sampling Program - Exposure Pathway - Waterborne No nuclides potentially associated with Quad Cities were detected and all required LLDs were met.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 21 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 8.4 Ingestion Pathway Sample Results 8.4.1 Milk Milk samples from milking animals were collected at 1 location within 5 km having the highest dose potential. Samples were collected January-December. Samples were analyzed for gamma-emitting isotopes and l-131(Low Level). No nuclides potentially associated with Quad Cities were detected and all required LLDs were met. 8.4.2 Fish A total of 8 fish samples were collected in 2024. These samples were analyzed for gamma emitting radionuclides in edible portions, in accordance with requirements of the ODCM and summarized in Table 4, Radiological Environmental Sampling Program - Exposure Pathway-Ingestion. These samples are collected from the indicator and control areas as required by the ODCM. Naturally occurring potassium-40 was identified in all fish samples with concentrations consistent with previous years. 8.4.3 Food Products A total of 1 O food product type samples were analyzed in 2024, for gamma emitting radionuclides in accordance with requirements of the ODCM, as summarized in Table 4, Radiological Environmental Sampling Program - Exposure Pathway - Ingestion. Naturally occurring potassium-40 was identified in all food products from indicator and control locations with concentrations consistent with previous years. Beryllium-7, also naturally reoccurring, was detected in five of the indicator samples and 1 of the control samples in 2024.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 22 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 9.0 LAND USE CENSUS An annual land use census is required by the Offsite Dose Calculation Manual and is performed to ensure that changes in the use of areas at or beyond the site boundary are identified and modifications to REMP are made if required by changes in land use. The land use census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR 50 [2]. NUREG-1301/1302 Control 3.12.2 specifies that "a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 mi.) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m2 (500 ft2) producing broad leaf vegetation. Note, per NUREG-1301/1302, Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. A Land Use Census was conducted during the calendar year, 2024, within the growing season to identify changes in land use, receptor locations, and new exposure pathways. The results for the 2024 Land Use Census are listed in Table 8, Land Use Census - Nearest Receptors within 5 miles. In summary, the highest D/Q locations for nearest garden, nearest residence and nearest milk animal did not change following the 2024 census.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 23 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 I Table 8, Land Use Census - Nearest Receptors within 5 miles I Sector Direction Nearest Distance Nearest Milk Distance Livestock Distance Residence (MIies) Animal (Miles) (Miles) A N 21116 River Road 0.60 North, Cordova, IL Sandy Gustafson, Hwy 67 and 3?1h Ave., B NNE 21918 River Road 1.20 3.1 N., Cordova, IL Comanche, IA 21421 Hwy 84, Bernard Gabriel, 12010 C NE 1.30 Meredosia Road, 3.2 Cordova, IL Albany, IL Ken Debaille, Debaille, 21404 266th D ENE 21404 266th Street 2.90 2.9 North Street, Cordova, IL Neumiller, 25432 9317 Fulfer Road, E E 206th Ave, 2.00 Albany, IL 5.5 Cordova, IL Jack Ward, 19323 Bill Stanley Dairy, Stanley, 18326 266th 18326 266th F ESE 266th Street, 2.80 Street North, 3.1 Street North, Cordova, 3.1 Cordova, IL Cordova, IL IL 18129 250th Street, Werner, 136Ave. North G SE 1.70 and 27?1h St., Cordova, 5.3 Cordova, IL IL C & J Morales, Julie Depauw, Near 14225 256th St., 1 27004 122nd H SSE 18909 Rt. 84, 1.10 Avenue.Port 6.6 mile West from 207-2 on 4.5 Cordova, IL Byron, IL 150th Ave./Hwy N Sonny Moorhusen, J s 18920 River Road, 0.75 Cordova, IL Robert 200 yards from "L" K SSW VanHorreweghe, 3.20 location; Intersection of 3.5 711 N. Main, 285th and Hwy. 67 Cordova, IL 26545 283rd Ave., 285th Ave. and Hwy 67, L SW Princeton. IA 2.90 Princeton, IA; West of 3.3 intersection M WSW 28202 283rd Ave., 2.20 27840 Hwy 67; Near 2.7 Princeton, IA 280th Street Annette Hamilton, N w 28439 Great River 2.60 290th Street and 260th 4.3 Road, Hwy 67, Ave., Princeton, IA. Princeton, IA p WNW 2971 Hwy 67, 2.70 Fawcett, 3697 292"d 3.8 Camanche, IA Street, Comanche, IA 2913 Hwy 67, 365th Ave. between a NW 2.60 292nd Street and 280th 4.7 Camanche, IA Street 3930 291 st Street, Lorenzen. 2882 and R NNW 2.10 2884 Hwy 67, 2.2 Camanche, IA Comanche, IA

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 24 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 10.0 SAMPLE DEVIATIONS, ANOMALIES AND UNAVAILABILITY Sampling and analysis are performed for media types addressed in the Offsite Dose Calculation Manual. Sampling and analysis challenges may be experienced due to a multitude of reasons including environmental factors, loss of TLDs/OSLDs, contamination of samples, etc. To aid classification of sampling and analysis challenges experienced in 2024, the following three terms are used to describe the issues: Sample Anomalies, Sample Deviation, and Unavailable Samples. Media that experienced downtime (i.e., air samplers or water samplers) during a surveillance period are classified a "Sample Deviation". "Sample Anomalies" are defined as errors that were introduced to a sample once it arrived in the laboratory, errors that prevents the sample from being analyzed as it normally would, or may have altered the outcome of the analysis (i.e., cross contamination, human error). "Sample Unavailability" is defined as sample collection with no available sample (i.e., food crop, TLD). All required samples were collected and analyzed as scheduled except for the following: Table 9: Sample Deviation Summary Sample Type Collection Reason for not conducting REMP Plans for preventing Location Date or and Analysis Period sampling as required by ODCM reoccurrence AP-Gross Beta Q-03 7/19/24 Filter was washed out by heavy rains NIA Weather Dependent AP/Al-Gross Q-42 9/13/24 Timer broke down, so run time was The pump was Beta and 1-131 estimated. exchanged SW-Gross Beta Q-33 1/13/24-N/A and Gamma Q-34 1/26/24 No sample due to river being frozen Weather Dependent Isotopic SW-Gross Beta Q-33 12/6/24-NIA and Gamma Q-34 12/20/24 No sample due to river being frozen Weather Dependent Isotopic

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 25 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 11.0 11.1 11.2 Table 9: Sample Deviation Summary The OSLO was found missing after The OSLD OSLO Q-13-2 5/10/24 MidAmerican Energy removed the EX00083494OM was protective fence around air sampler. The installed as a premises search was unsuccessful. replacement 5/18/24 OSLO Q-112-1 2nd Quarter OSLD found missing in field. Premise 2024 search was unsuccessful 3rd Quarter OSLO found missing in field. It was OSLD Q-112-2A 2024 possibly dislodged by strong winds. Premise search was unsuccessful 3rd Quarter Both OSLOs were found missing. It was OSLD Q-113-2/2A 2024 possibly discarded during road work performed in the area 4 111 Quarter Both OSLOs were found missing. It was OSLD Q-112-1/1A 2024 possibly due to vandalism or strong wind activity 4111 Quarter Both OSLDs were found missing. It was OSLO Q-201-1/1A 2024 possibly discarded during road sign exchange by road workers. OTHER SUPPLEMENTAL INFORMATION NEI 07-07 Onsite Radiological Groundwater Monitoring Program Quad Cities Nuclear Power Station Units 1 and 2 has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater in order to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning. It is important to note, samples and results taken in support of NEI 07-07 on-site groundwater monitoring program are separate from the Radiological Environmental Monitoring Program (REMP). Results of the NEI 07-07 Radiological Groundwater Monitoring Program for onsite groundwater wells are provided in the ARERR. Independent Spent Fuel Storage Installation (ISFSI) Monitoring Program Quad Cities commenced use of an independent Spent Fuel Storage Installation (ISFSI) in December 2005. There are no measurable changes in ambient gamma radiation levels as a result of ISFSI operations.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 26 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 11.3 Corrections to Previous Reports There were no corrections to the previous reports in 2024.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 27 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 12.0 BIBLIOGRAPHY [1] NCRP, "Report No. 160, Ionizing Radiation Exposure of the Population of the United States," National Council on Radiation Protection, Bethesda, 2009. [2] "10 CFR 50, "Domestic Licensing of Production and Utilization Facilities"," US Nuclear Regulatory Commission, Washington, DC. [3] "Regulatory Guide 4.1, "Radiological Environmental Monitoring for Nuclear Power Plants", Revision 2," Nuclear Regulatory Commission, 2009. [4] "NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors,".," Nuclear Regulatory Commission, April 1991. [5] "NUREG-1302, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors,"," Nuclear Regulatory Commission, April 1991. [6] "Branch Technical Position, Revision 1," NRC000096, Submitted March 30, 2012, November 1979. [7] "Japan Atomic Energy Agency," 06 November 2020. [Online]. Available: https://www.jaea.go.jp/english/04/ntokai/houkan/houkan_02.html. [8] "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. [9] "Regulatory Guide 4.13, Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, Revision 2," Nuclear Regulatory Commision, June, 2019. [10] "NUREG/CR-2919, "XOQDOQ Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations,"," Nuclear Regulatory Commission, September, 1982. [11] "Measurements of Radionuclides in the environment Sampling and Analysis of plutonium in soil," Nuclear Regulatory Commission, 1974. [12] "Ionizing Radiation Exposure of the Population of the United States," Bethesda, MD, 2009. [13] Nuclear Regulatory Commission, 30 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-pwr.html. [Accessed October 2020). [14] "ICRP Publication 60, "ICRP Publication 60: 1990 Recommendations of the International Commission on Radiological Protection, 60," Annals of the ICRP Volume 21/1-3,," International Commission on Radiation Protection, October, 1991. [15] "NRC Resource Page," [Online]. Available: http://www.nrc.gov/about-nrc/radiation.html. [Accessed 10 November 2020]. [16] "NUREG-0133, Preparation of Effluent Technical Specifications for Nuclear Power Plants," Nuclear Regulatory Commission, 1987. [17] "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. [18] [Online]. Available: http://hps.org/hpspublications/radiationfactsheets.html. [Accessed 2020). [19] "NEI 07-07, "Industry Ground Water Protection Initiative-Final Guidance Document,"," Nuclear Energy Institute, Washington, D.C..

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 28 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 [20) "ANSI 13.37, Environmental Dosimetry-Criteria for System Design and Implementation," Health Physics Society (HPS), May, 2019. [21) "40 CFR Part 141, "National Primary Drinking Water Regulations,"," US Environmental Protection Agency, Washington, DC.. [22) Nuclear Regulatory Commission, 25 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-bwr.html. [Accessed October 2020). [23) "40 CFR 190- Environmental Radiation Protection Standards for Nuclear Power Operation," US Environmental Protection Agency, Washington, DC. [24) "NUREG-0324 - XOQDOQ, Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," Nuclear Regulatory Commission, September, 1977. [25) "NCRP Report No. 160- Ionizing Radiation Exposure of the Population of the United States," National Council on Radiation Protection and Measurements, Bethesda, MD, 2009. [26) "10 CFR 20- Standards for Protection Against Radiation," US Nuclear Regulatory Commission, Washington, DC.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 29 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2, Data Table Summary Table 10 Quad Cities Data Summary Table Type, Total Indicator Location with Highest Lower Annual Mean Number of Medium or Number of Means; Control Pathway Sampled Analyses Limit of Name Means (t6). Non routine Detection (f'). Distance Means Reported (Units) performed (LLD) Ranges and (t6) Ranges Measurements (e.g., 1-131, 400) Ranges Direction Q-37 Indicator Gross Beta, 520 10 18.5 (461/468) Meredosia 20 (51/52) 18.2 (52/52) 0 Road (4.8/54.9) 4.4 miles (10.6/37.3) (5.7/32.1) ENE Mn-54 NIA < LLD <LLD <LLD <LLD 0 Co-58 NIA < LLD < LLD <LLD <LLD 0 Air Particulates Fe-59 N/A <LLD < LLD < LLD <LLD 0 (E-03 pCi/m3) Co-60 N/A <LLD < LLD < LLD < LLD 0 Zn-65 N/A < LLD < LLD < LLD < LLD 0

Gamma, Nb-95 NIA

< LLD <LLD <LLD < LLD 0 40 Zr-95 NIA <LLD <LLD <LLD <LLD 0 1-131 N/A < LLD < LLD < LLD <LLD 0 Cs-134 50 <LLD < LLD < LLD <LLD 0 Cs-137 60 <LLD < LLD < LLD < LLD 0 Ba-140 NIA < LLD <LLD <LLD < LLD 0 La-140 NIA <LLD <LLD <LLD <LLD 0 Airborne Gamma,530 Radioiodine 70 <LLD < LLD < LLD < LLD 0 (E-03 pCi/m3) 1-131 Direct Radiation 4.5 (285/285) Q-211-2 7.7 (4/4) 7.4 (4/4) (mrem/qtr.) Gamma Dose, 289 N/A (-2.6/11.4) 4.5miles (4.6/10.3) (4.6/10.3) 0 SW 5 Mean and range are based on detectable measurements only. 6 Fraction are based on detectable measurements at specified locations is indicated in parentheses

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 30 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2, Data Table Summary Table 10* Quad Cities Data Summarv Table Indicator Location with Highest Annual Type, Total Number Lower Mean Number of Medium or Pathway of Analyses Limit of Mean5; Control Nonroutine Name Means(f6). Sampled (Units) performed Detection (f'). Distance Means Ranges Reported (e.g., 1-131, 400) (LLD) Range5 and (f6) Measurements Direction Ranges l-131(Low Level), 20 1 < LLD < LLD < LLD NIA 0 Mn-54 NIA <LLD <LLD <LLD NIA 0 Co-58 NIA < LLD <LLD <LLD NIA 0 Fe-59 NIA < LLD <LLD <LLD NIA 0 Co-60 NIA < LLD <LLD < LLD NIA 0 Milk (pCi/L) Zn-65 NIA < LLD < LLD < LLD NIA 0

Gamma, Nb-95 NIA

< LLD <LLD <LLD NIA 0 20 Zr-95 NIA < LLD < LLD < LLD NIA 0 Cs-134 15 < LLD <LLD <LLD NIA 0 Cs-137 18 < LLD <LLD <LLD NIA 0 Ba-140 60 <LLD <LLD <LLD NIA 0 La-140 15 < LLD < LLD < LLD NIA 0 Mn-54 NIA < LLD < LLD < LLD < LLD 0 Co-58 NIA < LLD < LLD <LLD < LLD 0 Fe-59 NIA < LLD <LLD <LLD < LLD 0 Co-60 NIA < LLD <LLD <LLD < LLD 0 Zn-65 NIA < LLD < LLD < LLD < LLD 0 Food Products

Gamma, Nb-95 NIA

< LLD < LLD < LLD < LLD 0 (pCilkg Wet) 10 Zr-95 NIA < LLD < LLD <LLD < LLD 0 1-131 60 < LLD <LLD <LLD < LLD 0 Cs-134 60 < LLD < LLD <LLD < LLD 0 Cs-137 80 < LLD < LLD < LLD < LLD 0 Ba-140 NIA < LLD < LLD < LLD < LLD 0 La-140 NIA < LLD <LLD < LLD < LLD 0 5 Mean and range are based on detectable measurements only. 6 Fraction are based on detectable measurements at specified locations is indicated in parentheses

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 31 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2, Data Table Summary Table 10* Quad Cities Data Summarv Table Indicator Location with Highest Annual Medium or Type, Total Number Lower Mean Pathway Sampled of Analyses Limit of Means; Name Means (Units) performed Detection (f6). Distance (t6) (e.g., 1-131, 400) (LLD) Ranges and Direction Range5 Q-34 Control 3.9 (11/12) Camanche-4.6 (11/12) Gross Beta, 24 4 Upstream (2.9/5.5) 4.4 miles (3.1/6.9) NNE H-3,8 2000 < LLD < LLD < LLD Fe-55, 8 200 <LLD < LLD <LLD Ni-63, 8 5 <LLD <LLD <LLD Surface Water Mn-54 15 < LLD < LLD < LLD (pCi/L) Co-58 15 < LLD < LLD < LLD Fe-59 30 <LLD <LLD <LLD Co-60 15 <LLD <LLD <LLD Zn-65 30 <LLD <LLD < LLD

Gamma, Nb-95 15

<LLD <LLD <LLD 24 Zr-95 30 <LLD <LLD <LLD 1-131 15 < LLD < LLD < LLD Cs-134 15 <LLD <LLD <LLD Cs-137 18 <LLD <LLD <LLD Ba-140 60 < LLD < LLD < LLD La-140 15 <LLD <LLD <LLD 5 Mean and range are based on detectable measurements only. 6 Fraction are based on detectable measurements at specified locations is indicated in parentheses Control Mean5 (t6). Ranges 4.6 (11/12) (3.1/6.9) < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Number of Non routine Reported Measurements 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 32 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2, Data Table Summary Table 10* Quad Cities Data Summarv Table Location with Highest Annual Type, Total Lower Indicator Mean Medium or Pathway Number of Limit of Means; Analyses Name Sampled (Units) performed Detection (fi). Distance Means (e.g., 1-131, 400) (LLD) Ranges and (f6) Direction Range5 Q-35 262 McMillian 262 H-3,8 2000 Well (1/9) 1.5 Miles (1/5) Mn-54 15 <LLD <LLD < LLD Co-58 15 < LLD < LLD <LLD Fe-59 30 < LLD < LLD <LLD Co-60 15 <LLD <LLD < LLD Ground Water Zn-65 30 <LLD <LLD <LLD (pCi/L)

Gamma, Nb-95 15

< LLD < LLD < LLD 8 Zr-95 30 <LLD <LLD < LLD 1-131 15 <LLD <LLD <LLD Cs-134 15 < LLD <LLD < LLD Cs-137 18 <LLD <LLD < LLD Ba-140 60 < LLD <LLD <LLD La-140 15 < LLD <LLD < LLD 5 Mean and range are based on detectable measurements only. 6 Fraction are based on detectable measurements at specified locations is indicated in parentheses Control Means(f6). Ranges NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA Number of Nonroutine Reported Measurements 0 0 0 0 0 0 0 0 0 0 0 0 0

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 33 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2, Data Table Summary Table 10* Quad Cities Data Summarv Table Indicator Location with Highest Annual Type, Total Number Lower Mean Medium or Pathway of Analyses Limit of Means; Name Sampled (Units) performed Detection (f'). Distance Means (e.g., 1-131, 400) (LLD) Ranges and (f6) Direction Ranges Mn-54 130 <LLD < LLD < LLD Co-58 130 <LLD <LLD < LLD Fe-59 260 < LLD < LLD < LLD Co-60 130 < LLD < LLD < LLD Zn-65 260 <LLD < LLD < LLD Fish Gamma.a Nb-95 NIA <LLD < LLD < LLD (pCi/kg Wet) Zr-95 NIA < LLD <LLD < LLD Cs-134 130 <LLD < LLD < LLD Cs-137 150 <LLD < LLD < LLD Ba-140 NIA < LLD <LLD < LLD La-140 NIA <LLD <LLD <LLD Mn-54 NIA <LLD < LLD < LLD Co-58 NIA <LLD < LLD < LLD Fe-59 NIA < LLD <LLD < LLD Co-60 NIA <LLD <LLD < LLD Zn-65 NIA <LLD < LLD < LLD Sediment Gamma,4 Nb-95 NIA <LLD < LLD < LLD (pCilkg Dry) Zr-95 NIA < LLD <LLD < LLD Cs-134 150 <LLD < LLD < LLD Cs-137 180 <LLD < LLD < LLD Ba-140 NIA < LLD <LLD < LLD La-140 N/A <LLD <LLD <LLD 5 Mean and range are based on detectable measurements only. 6 Fraction are based on detectable measurements at specified locations is indicated in parentheses Control Means(f6}. Ranges < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Number of Nonroutine Reported Measurements 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

Collection Date 12/29/2023 25 01/05/2024 25 01/12/2024 24 01/19/2024 11 01/26/2024 17 02/02/2024 12 02/09/2024 17 02/16/2024 26 02/23/2024 13 03/01/2024 14 03/08/2024 17 03/15/2024 13 03/23/2024 11 03/29/2024 10 04/05/2024 12 04/12/2024 15 04/19/2024 19 04/26/2024 15 05/03/2024 9 05/10/2024 12 05/18/2024 11 Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 34 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Q-01 +/- 5 +/- 5 +/- 4 +/- 4 +/- 4 +/- 4 +/- 4 +/- 4 +/- 4 +/- 4 +/- 4 +/- 3 +/- 4 +/- 3 +/- 4 +/- 4 +/- 4 +/- 4 +/- 3 +/- 3 +/- 4, Complete Data Table for All Analysis Results Obtained In 2024 Note: Throughout Attachment 2, bold data entries are for the reported concentration Table 11, Weekly Air Particulate Gross Beta (E-3 pCi/m3) Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 26 +/- 5 8 +/- 3 24 +/- 5 20 +/- 4 19 +/- 4 23 +/- 5 25 +/- 20 +/- 4 18 +/- 4 25 +/- 5 19 +/- 4 22 +/- 4 18 +/- 4 21 +/- 24 +/- 4 23 +/- 5 32 +/- 5 32 +/- 6 31 +/- 5 23 +/- 5 30 +/- 12 +/- 4 14 +/- 4 11 +/- 4 10 +/- 4 14 +/- 4 11 +/- 4 13 +/- 23 +/- 4 19 +/- 4 17 +/- 4 18 +/- 4 17 +/- 4 15 +/- 4 18 +/- 16 +/- 4 5 +/- 3 14 +/- 4 10 +/- 3 15 +/- 4 11 +/- 4 16 +/- 11 +/- 4 8 +/- 3 15 +/- 4 14 +/- 4 14 +/- 4 12 +/- 4 17 +/- 22 +/- 4 11 +/- 3 26 +/- 4 21 +/- 4 27 +/- 5 21 +/- 4 27 +/- 18 +/- 4 6 +/- 3 17 +/- 4 14 +/- 4 16 +/- 4 19 +/- 4 17 +/- 15 +/- 4 8 +/- 3 16 +/- 4 15 +/- 4 18 +/- 4 16 +/- 4 18 +/- 22 +/- 4 9 +/- 4 17 +/- 4 16 +/- 4 24 +/- 5 26 +/- 5 22 +/- 12 +/- 3 5 +/- 3 10 +/- 3 12 +/- 3 13 +/- 4 17 +/- 4 16 +/- 14 +/- 5 6 9 +/- 4 13 +/- 5 17 +/- 5 21 +/- 5 17 +/- 9 +/- 3 5 +/- 3 10 +/- 3 11 +/- 4 10 +/- 4 11 +/- 4 11 +/- 10 +/- 3 6 +/- 3 12 +/- 4 9 +/- 3 13 +/- 4 11 +/- 3 15 +/- 15 +/- 4 8 +/- 4 15 +/- 4 9 +/- 4 14 +/- 4 18 +/- 4 17 +/- 16 +/- 4 7 +/- 3 18 +/- 4 14 +/- 4 17 +/- 4 19 +/- 4 17 +/- 12 +/- 4 6 +/- 3 10 +/- 3 14 +/- 4 14 +/- 4 15 +/- 4 15 +/- 8 +/- 3 4 13 +/- 4 9 +/- 3 13 +/- 4 13 +/- 4 15 +/- 16 +/- 4 5 +/- 3 16 +/- 4 12 +/- 3 15 +/- 3 14 +/- 3 14 +/- 12 +/- 4 7 +/- 4 15 +/- 5 9 +/- 4 13 +/- 4 18 +/- 5 17 +/- Q-41 5 15 +/- 4 13 +/- 5 18 +/- 4 8 +/- 4 10 +/- 4 9 +/- 4 11 +/- 5 20 +/- 4 18 +/- 4 13 +/- 5 20 +/- 4 11 +/- 5 14 +/- 4 9 +/- 4 10 +/- 4 10 +/- 4 16 +/- 4 12 +/- 4 9 +/- 4 12 +/- 5 16 +/- Q-42 4 23 +/- 5 3 19 +/- 4 5 25 +/- 5 3 8 +/- 3 3 11 +/- 4 3 10 +/- 4 4 14 +/- 4 4 19 +/- 4 4 16 +/- 4 4 13 +/- 4 4 15 +/- 4 3 10 +/- 3 5 14 +/- 5 3 10 +/- 4 3 8 +/- 3 4 13 +/- 4 4 13 +/- 4 4 11 +/- 4 3 10 +/- 4 3 11

t 3 5

14 +/- 5

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 35 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 11, Weekly Air Particulate Gross Beta (E-3 pCi/m3) Cont'd Collection Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 Date 05/24/2024 9 +/- 3 4 5 9 +/- 4 9 +/- 4 11 +/- 4 12 +/- 4 8 +/- 3 6 +/- 3 6 +/- 3 05/31/2024 (2) (2) (2) (2) (2) (2) (2) (2) (2) (2) 06/07/2024 11 +/- 4 9 +/- 4 5 11 +/- 4 7 +/- 4 10 +/- 4 5 6 +/- 4 7 +/- 4 9 +/- 4 06/14/2024 19 +/- 4 14 +/- 4 5 20 +/- 4 12 +/- 4 24 +/- 5 21 +/- 4 13 +/- 4 17 +/- 4 24 +/- 5 06/21/2024 13 +/- 4 12 +/- 4 6 +/- 3 15 +/- 4 16 +/- 4 16 +/- 4 16 +/- 4 15 +/- 4 18 +/- 4 15 +/- 4 06/28/2024 14 +/- 4 8 +/- 3 6 +/- 3 12 +/- 4 15 +/- 4 12 +/- 4 13 +/- 4 10 +/- 4 12 +/- 4 12 +/- 4 07/05/2024 11 +/- 4 11 +/- 4 15 +/- 5 12 +/- 4 12 +/- 4 11 +/- 4 14 +/- 4 13 +/- 4 11 +/- 4 11 +/- 4 07/12/2024 15 +/- 4 16 +/- 4 7 +/- 4 11 +/- 4 12 +/- 4 16 +/- 4 16 +/- 4 15 +/- 4 14 +/- 4 14 +/- 4 07/19/2024 15 +/- 4 18 +/- 4 17 +/- 4(1) 12 +/- 4 17 +/- 4 16 +/- 4 15 +/- 4 16 +/- 4 13 +/- 4 16 +/- 4 07/26/2024 19 +/- 4 19 +/- 4 21 +/- 4 16 +/- 4 20 +/- 4 20 +/- 4 23 +/- 4 16 +/- 4 23 +/- 4 9 +/- 3 08/02/2024 20 +/- 4 23 +/- 4 20 +/- 4 25 +/- 5 20 +/- 4 25 +/- 4 24 +/- 4 21 +/- 4 28 +/- 5 22 +/- 4 08/09/2024 16 +/- 4 20 +/- 4 20 +/- 4 23 +/- 5 19 +/- 4 20 +/- 4 23 +/- 5 21 +/- 4 18 +/- 4 21 +/- 5 08/16/2024 16 +/- 4 17 +/- 4 16 +/- 4 17 +/- 4 13 +/- 4 17 +/- 4 17 +/- 4 14 +/- 4 13 +/- 4 19 +/- 4 08/23/2024 29 +/- 5 29 +/- 5 31 +/- 5 26 +/- 5 24 +/- 5 27 +/- 5 28 +/- 5 25 +/- 5 33 +/- 5 28 +/- 5 08/30/2024 20 +/- 4 17 +/- 4 19 +/- 4 21 +/- 4 14 +/- 4 18 +/- 4 19 +/- 4 14 +/- 4 19 +/- 4 19 +/- 4 09/06/2024 29 +/- 5 24 +/- 4 27 +/- 5 25 +/- 5 23 +/- 4 24 +/- 4 31 +/- 5 23 +/- 4 29 +/- 5 23 +/- 4 09/13/2024 29 +/- 5 30 +/- 5 30 +/- 5 25 +/- 5 32 +/- 5 29 +/- 5 26 +/- 5 28 +/- 5 28 +/- 5 29 +/- 5(1) 09/20/2024 20 +/- 4 23 +/- 5 24 +/- 5 23 +/- 5 22 +/- 4 27 +/- 5 23 +/- 5 19 +/- 4 25 +/- 5 24 +/- 5 09/27/2024 20 +/- 4 23 +/- 4 20 +/- 4 22 +/- 4 22 +/- 4 24 +/- 4 22 +/- 4 22 +/- 4 22 +/- 4 21 +/- 4 10/05/2024 30 +/- 5 27 +/- 5 30 +/- 5 28 +/- 5 19 +/- 4 5 +/- 3 37 +/- 6 27 +/- 5 27 +/- 5 30 +/- 5 10/11/2024 19 +/- 4 19 +/- 4 19 +/- 4 22 +/- 4 19 +/- 4 19 +/- 4 24 +/- 4 22 +/- 4 18 +/- 4 20 +/- 4 10/18/2024 28 +/- 5 23 +/- 5 28 +/- 5 26 +/- 5 29 +/- 5 28 +/- 5 33 +/- 5 26 +/- 5 28 +/- 5 29 +/- 5 <1> Refer to Sample Deviation Table (2) Sampling frequency was followed as prescribed in the ODCM, but the samples were lost in transit by the carrier and therefore analysis could not be performed.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 36 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 11, Weekly Air Particulate Gross Beta E-3 pCi/m3) Cont'd Collection Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 Date 10/25/2024 26 +/- 5 26 +/- 5 27 +/- 5 24 +/- 5 22 +/- 5 26 +/- 5 28 +/- 5 27 +/- 5 26 +/- 5 26 +/- 5 11/01/2024 17 +/- 4 14 +/- 4 16 +/- 4 14 +/- 4 13 +/- 4 15 +/- 4 19 +/- 4 14 +/- 4 17 +/- 4 16 +/- 4 11/08/2024 20 +/- 4 25 +/- 4 22 +/- 4 24 +/- 4 24 +/- 4 23 +/- 4 22 +/- 4 18 +/- 4 24 +/- 4 21 +/- 4 11/15/2024 28 +/- 5 27 +/- 5 28 +/- 5 26 +/- 5 22 +/- 5 22 +/- 5 24 +/- 5 24 +/- 5 25 +/- 5 28 +/- 5 11/22/2024 21 +/- 5 21 +/- 5 19 +/- 4 23 +/- 5 22 +/- 5 24 +/- 5 18 +/- 4 21 +/- 5 22 +/- 5 24 +/- 5 11/29/2024 23 +/- 4 23 +/- 4 24 +/- 5 27 +/- 5 31 +/- 5 22 +/- 4 25 +/- 5 26 +/- 5 22 +/- 4 27 +/- 5 12/06/2024 19 +/- 4 22 +/- 4 22 +/- 5 25 +/- 5 55 +/- 6 27 +/- 5 24 +/- 5 25 +/- 5 24 +/- 5 27 +/- 5 12/13/2024 34 +/- 5 34 +/- 5 30 +/- 5 29 +/- 5 27 +/- 5 36 +/- 5 32 +/- 5 35 +/- 5 32 +/- 5 32 +/- 5 12/20/2024 23 +/- 4 19 +/- 4 23 +/- 4 30 +/- 5 24 +/- 4 26 +/- 5 19 +/- 4 20 +/- 4 22 +/- 4 28 +/- 5 12/27/2024 24 +/- 5 23 +/- 5 23 +/- 5 23 +/- 5 26 +/- 5 28 +/- 5 22 +/- 5 25 +/- 5 25 +/- 5 29 +/- 5

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 37 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 12, Quarterly Air Particulate Gamma Isotopic (pCi/m3 +/- 2 Sigma) Station Nuclide Q1 Q2 Q3 Q4 Station Nuclide Q1 Q2 Q3 Q4 Mn-54 2 2 2 2 Mn-54 2 2 3 2 Co-58 2 3 3 2 Co-58 2 3 2 2 Fe-59 5 7 7 5 Fe-59 5 6 5 4 Co-60 2 3 3 3 Co-60 2 3 2 2 Zn-65 5 5 6 7 Zn-65 4 6 7 5 Q-01 Nb-96 2 3 3 2 Q-03 Nb-96 2 3 3 2 Zr-95 4 4 5 3 Zr-95 3 6 4 3 Cs-134 2 2 3 2 Cs-134 3 2 2 2 Cs-137 2 2 2 2 Cs-137 2 3 2 2 Ba-140 11 32 29 15 Ba-140 15 36 23 15 La-140 5 12 13 5 La-140 7 14 11 5 Mn-54 2 4 2 3 Mn-54 2 < 3 3 1 Co-58 2 6 2 2 Co-58 2 < 3 3 2 Fe-59 4 14 5 6 Fe-59 6 < 8 8 4 Co-60 3 4 2 3 Co-60 2 < 3 3 2 Zn-65 5 10 5 6 Zn-65 5 < 6 9 5 Q-02 Nb-96 2 5 2 3 Q-04 Nb-96 2 3 3 2 Zr-95 3 9 4 4 Zr-95 4 5 < 6 3 Cs-134 2 5 2 3 Cs-134 2 3 < 4 2 Cs-137 3 4 2 3 Cs-137 2 < 2 < 3 2 Ba-140 11 61 19 14 Ba-140 < 9 < 49 < 33 < 14 La-140 4 32 8 8 La-140 < 4 16 17 8

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 38 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 12, Quarterly Air Particulate Gamma Isotopic (pCi/m3 +/- 2 Sigma) Cont'd Station Nuclide Q1 Q2 Q3 Q4 Station Nuclide Q1 Q2 Q3 Q4 Mn-54 2 2 2 2 Mn-54 2 3 3 1 Co-58 2 3 2 3 Co-58 2 3 5 1 Fe-59 4 < 6 5 6 Fe-59 6 7 10 4 Co-60 2 3 3 3 Co-60 2 3 3 2 Zn-65 4 5 4 7 Zn-65 7 4 8 3 Q-13 Nb-96 2 3 3 3 Q-37 Nb-96 3 3 4 1 Zr-95 3 5 4 5 Zr-95 5 6 5 3 Cs-134 2 3 2 3 Cs-134 3 3 4 2 Cs-137 2 < 2 2 3 Cs-137 3 2 3 1 Ba-140 9 27 19 23 Ba-140 15 37 42 10 La-140 4 10 14 9 La-140 5 13 16 5 Mn-54 2 2 2 2 Mn-54 2 3 2 2 Co-58 2 2 2 2 Co-58 2 5 3 2 Fe-59 4 6 5 4 Fe-59 4 11 6 5 Co-60 2 3 2 2 Co-60 2 3 2 2 Zn-65 6 < 6 4 6 Zn-65 6 7 7 5 Q-16 Nb-96 2 3 2 3 Q-38 Nb-96 2 4 3 2 Zr-95 4 5 3 3 Zr-95 4 7 5 4 Cs-134 2 2 2 2 Cs-134 2 4 2 2 Cs-137 2 2 2 2 Cs-137 < 2 < 3 < 2 < 2 Ba-140 9 27 15 12 Ba-140 11 53 23 13 La-140 5 17 5 9 La-140 4 18 12 7

Annual Radiological Environmental Operating Report I YEAR: 2024 l Page 39 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 12, Quarterly Air Particulate Gamma Isotopic (pCi/m3 +/- 2 Sigma) Cont'd Station Nuclide Q1 Q2 Q3 Q4 Mn-54 2 < 2 2 2 Co-58 3 3 2 2 Fe-59 6 6 6 6 Co-60 2 3 1 2 Zn-65 6 6 5 6 Q-41 Nb-96 3 3 2 2 Zr-95 4 4 3 4 Cs-134 3 3 2 3 Cs-137 2 2 2 2 Ba-140 15 35 21 18 La-140 5 14 9 7 Mn-54 3 4 2 2 Co-58 2 5 2 < 2 Fe-59 6 11 4 < 6 Co-60 1 5 3 2 Zn-65 5 11 6 5 Q-42 Nb-96 3 4 3 < 2 Zr-95 4 8 4 4 Cs-134 2 5 2 2 Cs-137 2 5 2 2 Ba-140 12 76 < 24 16 La-140 4 38 10 3

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 40 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 13, Weekly Air Iodine 1-131 (E-3 pCi/m3) Collection Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 Date 12/29/2023 < 45 < 45 < 47 < 22 < 45 < 42 < 44 < 44 < 42 < 22 01/05/2024 < 66 < 66 < 32 < 66 < 51 < 51 < 28 < 68 < 51 < 52 01/12/2024 < 30 < 30 < 31 < 30 < 27 < 43 < 38 < 38 < 43 < 50 01/19/2024 < 42 < 42 < 29 < 41 < 41 < 45 < 46 < 46 < 45 < 22 01/26/2024 < 60 < 60 < 26 < 60 60 56 < 58 < 58 < 23 < 58 02/02/2024 < 47 < 47 < 20 < 47 < 46 < 20 < 31 < 31 < 30 < 31 02/09/2024 < 60 < 60 < 26 < 60 < 60 < 30 < 32 < 32 < 30 < 13 02/16/2024 < 53 < 53 < 23 < 53 < 53 < 57 < 60 < 60 < 24 < 59 02/23/2024 < 56 56 < 24 < 56 56 < 41 < 28 < 43 < 41 < 43 03/01/2024 < 60 < 25 < 62 < 60 < 59 < 55 < 55 < 24 < 55 < 57 03/08/2024 < 41 < 41 < 19 < 41 < 41 < 43 < 44 < 45 < 43 < 30 03/15/2024 < 30 < 30 < 24 < 30 < 30 34 < 34 < 35 34 < 23 03/23/2024 < 54 < 54 < 37 < 54 54 < 44 < 33 < 45 < 43 < 45 03/29/2024 < 58 < 58 < 25 < 58 < 57 < 40 < 41 < 42 < 40 < 32 04/05/2024 < 32 < 32 < 17 < 32 < 31 36 < 36 < 37 < 36 < 16 04/12/2024 < 27 36 < 37 < 36 36 < 48 < 48 < 50 < 48 < 21 04/19/2024 < 33 < 33 < 23 < 33 < 33 < 30 < 30 < 14 < 30 < 31 04/26/2024 < 52 < 52 < 22 < 52 < 52 < 46 < 46 < 48 < 46 < 20 05/03/2024 < 37 < 37 < 26 < 37 < 37 < 53 < 54 < 56 < 22 < 55 05/10/2024 < 38 < 38 < 17 < 38 < 38 < 15 < 36 < 37 < 36 < 37 05/18/2024 < 51 < 52 < 25 < 51 < 52 < 42 < 42 < 43 < 42 < 33

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 41 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 13, Weekly Air Iodine 1-131 (E-3 pCi/m3) Cont'd Collection Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 Date 05/24/2024 < 52 < 52 < 23 < 52 < 52 < 33 < 33 < 33 < 15 < 34 05/31/2024 < 42 < 42 < 18 < 42 < 42 < 62 < 62 < 62 < 62 < 30 06/07/2024 < 43 < 43 < 30 < 43 < 43 40 < 40 < 40 < 40 < 19 06/14/2024 < 35 < 35 < 24 < 35 < 35 < 25 < 33 < 33 < 33 < 34 06/21/2024 < 51 < 51 < 25 < 51 < 51 < 53 54 54 < 22 < 55 06/28/2024 < 50 < 50 < 24 < 51 < 52 < 36 < 37 < 37 36 < 18 07/05/2024 < 40 < 40 < 20 < 40 < 41 46 < 46 < 46 46 < 24 07/12/2024 < 41 < 41 < 20 < 42 < 41 < 35 < 35 < 35 < 35 < 19 07/19/2024 < 26 < 26 < 20 < 26 < 25 < 38 < 38 < 38 < 37 < 18 07/26/2024 < 40 < 41 < 42 < 20 < 40 < 42 < 42 < 42 21 < 44 08/02/2024 < 36 < 36 < 29 < 38 < 36 < 45 46 < 46 < 23 < 47 08/09/2024 < 29 < 29 < 30 < 13 < 29 < 16 < 16 < 16 < 16 11 08/16/2024 < 37 < 37 < 38 < 38 < 41 < 42 < 42 < 42 < 42 < 18 08/23/2024 < 25 < 25 < 20 < 26 < 26 < 40 < 40 < 18 < 40 < 41 08/30/2024 < 29 < 29 < 23 < 30 < 29 < 42 < 42 < 42 < 42 < 20 09/06/2024 < 45 < 45 < 22 < 46 < 44 < 38 < 38 < 38 38 < 44 09/13/2024 < 40 < 40 < 46 < 41 < 40 < 41 < 20 < 41 < 41 < 41(1) 09/20/2024 < 29 < 29 < 33 < 30 < 29 < 37 < 16 < 38 < 37 < 37 09/27/2024 < 17 < 17 < 8 < 17 < 17 < 17 < 13 < 17 < 17 < 17 10/05/2024 < 44 < 44 < 21 < 45 < 34 < 43 < 43 < 43 < 43 < 30 10/11/2024 < 45 < 45 < 21 < 47 < 45 < 53 < 53 < 53 < 53 < 39 10/18/2024 < 48 < 48 < 24 < 50 < 48 < 35 < 27 < 36 < 35 < 37 <1> Refer to Sample Deviation Table

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 42 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 13, Weekly Air Iodine 1-131 (E-3 pCi/m3) Cont'd Collection Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Q-42 Date 10/25/2024 < 47 < 47 < 21 < 49 < 47 < 39 < 39 < 39 < 43 < 40 11/01/2024 < 33 < 33 < 26 < 34 < 33 < 39 < 39 < 39 < 39 < 27 11/08/2024 < 55 < 55 < 63 < 57 < 55 < 60 < 60 < 60 < 60 < 26 11/15/2024 < 43 < 43 < 45 < 20 < 44 < 32 < 30 < 30 < 31 < 21 11/22/2024 < 36 36 < 25 < 37 < 36 < 31 < 41 < 41 < 41 < 43 11/29/2024 < 24 < 24 < 25 < 28 < 24 < 28 < 11 < 27 < 27 < 28 12/06/2024 < 25 < 25 < 17 < 26 < 25 < 29 < 19 < 28 < 28 < 29 12/13/2024 < 53 < 35 54 < 54 < 52 < 63 < 61 < 61 < 29 < 63 12/20/2024 < 42 < 42 < 20 < 43 < 42 < 38 < 37 < 37 < 37 < 20 12/27/2024 < 35 < 35 < 15 < 36 < 35 < 34 < 33 < 33 < 33 < 23

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 43 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 14, Monthly/Bi-Weekly Milk 1-131 (pCi/L +/- 2 Sigma) Collection Indicator Farm Date Q-26 01/05/2024 0.9 02/02/2024 0.9 03/01/2024 0.9 04/05/2024 0.8 04/19/2024 0.9 05/03/2024 0.8 05/18/2024 0.9 05/31/2024 0.8 06/14/2024 0.9 06/28/2024 0.8 07/12/2024 0.4 07/26/2024 0.7 08/09/2024 0.9 08/23/2024 0.7 09/06/2024 1.0 09/20/2024 0.5 10/05/2024 0.9 10/18/2024 0.7 11/01/2024 0.8 12/06/2024 < 0.8

Annual Radiological Environmental Operating Report l YEAR: 2024 I Page 44 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 15, Monthly/Bi-Weekly Milk Gamma Isotopic (pCi/L +/- 2 Sigma) Station Collection Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Dates 01/05/2024 4 6 15 6 15 7 11 7 6 28 10 02/02/2024 7 9 21 10 18 9 17 10 8 29 7 03/01/2024 7 8 15 7 19 9 13 8 7 37 9 04/05/2024 7 7 16 7 17 8 12 8 8 28 12 04/19/2024 7 7 17 7 15 8 12 8 6 32 7 05/03/2024 6 7 16 9 13 6 13 7 7 34 10 05/18/2024 7 7 15 7 17 6 12 7 7 27 9 05/31/2024 6 8 18 9 24 7 12 8 8 37 11 06/14/2024 8 8 19 10 19 8 13 9 7 44 9 06/28/2024 8 6 16 6 13 8 15 9 9 27 8 Q-26 07/12/2024 9 7 15 8 17 6 13 8 7 32 9 07/26/2024 6 7 14 8 15 6 10 6 6 24 8 08/09/2024 7 < 6 16 6 16 < 7 13 < 7 7 30 10 08/23/2024 6 6 18 8 17 8 13 9 6 22 10 09/06/2024 8 8 15 10 15 7 15 9 9 37 11 09/20/2024 7 7 15 9 16 8 14 8 6 24 11 10/05/2024 10 10 23 12 < 25 12 21 14 12 58 15 10/18/2024 7 9 21 10 < 17 < 7 < 13 < 10 < 8 < 39 < 8 11/01/2024 8 7 21 11 18 7 12 7 9 36 12 12/06/2024 8 7 18 6 < 19 6 11 < 6 8 34 12

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 45 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 16, Annual Food Products Gamma Isotopic (pCi/kg Wet+/- 2 Sigma) Station Collection Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Dates Q-Broccoli/Cabbage 08/01/2024 < 23 < 23 38 < 24 < 60 < 28 44 36 < 23 < 29 112 < 15 CONTROL Potatoes/Beets 08/01/2024 < 9 11 < 27 < 14 < 28 11 < 19 16 < 14 11 < 48 < 12 Kale 08/01/2024 11 < 18 44 17 < 42 < 15 < 37 27 < 17 < 24 < 82 31 Q-QUAD 1 Potatoes 08/01/2024 < 13 11 31 < 14 < 32 14 < 25 19 < 14 < 15 < 63 < 20 Lettuce 08/01/2024 < 30 < 32 < 65 < 25 < 50 34 < 55 49 < 35 < 45 < 128 31 Q-QUAD2 Onions 08/01/2024 < 17 < 20 < 38 < 22 < 37 < 20 < 33 37 < 20 < 23 102 < 26 Cabbage 08/01/2024 < 19 < 21 < 39 22 48 < 19 < 29 32 < 25 < 19 < 93 < 23 Q-QUAD3 Horseradish 08/01/2024 < 24 < 25 < 53 < 24 < 52 < 23 < 42 41 < 24 < 21 < 82 < 25 Kale 08/01/2024 < 26 < 29 64 < 33 56 < 24 < 37 38 < 22 < 20 77 < 24 Q-QUAD4 Turnip 08/01/2024 < 20 < 17 44 < 20 < 38 < 19 31 27 21 < 19 < 87 < 24

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 46 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 17, Monthly Surface Water Gross Beta (pCi/L +/- 2 Sigma) Collection Q-33 Q-34 Date 01/05/2024 4 +/- 2 6 +/- 2 02/02/2024 3 +/- 1 4 +/- 2 03/01/2024 4 +/- 2 3 04/05/2024 3 +/- 2 4 +/- 2 05/03/2024 3 +/- 2 4 +/- 2 06/07/2024 6 +/- 2 7 +/- 2 07/05/2024 5 +/- 2 4 +/- 2 08/02/2024 4 +/- 2 4 +/- 2 09/06/2024 4 +/- 2 3 +/- 2 10/05/2024 4 6 +/- 3 11/01/2024 5 +/- 2 4 +/- 2 12/27/2024 3 +/- 2 4 +/- 2

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 47 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 18, Monthly Surface Water Gamma Isotopic (pCi/L +/- 2 Sigma) Station Collection Dates Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 01/05/2024 - 01/05/2024 2 2 5 2 3 2 3 15 2 2 22 8 02/02/2024 02/23/2024 6 6 14 7 16 6 11 12 6 7 30 9 03/01/2024 03/29/2024 7 8 15 6 12 9 15 11 7 7 34 13 04/05/2024 04/26/2024 5 5 10 6 12 6 9 9 6 5 28 11 05/03/2024 - 05/31/2024 9 8 13 7 16 8 10 10 8 7 29 9 06/07/2024 06/28/2024 7 6 14 7 12 5 10 8 5 6 25 6 Q-33 07/05/2024 - 07/26/2024 7 7 15 6 15 6 9 10 6 7 29 14 08/02/2024 08/30/2024 7 8 16 6 13 9 15 12 8 7 33 12 09/06/2024 09/27/2024 5 7 13 4 12 6 8 10 6 6 27 8 10/05/2024 10/25/2024 4 5 10 5 11 5 7 7 6 5 22 9 11/01/2024 11/29/2024 7 < 6 14 8 10 6 9 13 6 5 27 13 12/27/2024 12/27/2024 6 5 14 5 12 6 7 11 7 7 32 9

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 48 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 18, Monthly Surface Water Gamma Isotopic (pCi/L +/- 2 Sigma) Cont'd Station Collection Dates Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 01/05/2024 01/05/2024 1 2 4 2 3 2 3 12 1 1 18 6 02/02/2024 02/23/2024 7 7 13 7 14 6 10 10 < 7 7 29 10 03/01/2024 03/29/2024 7 7 13 8 15 8 12 13 8 7 35 12 04/05/2024 04/26/2024 5 6 13 6 17 7 11 12 9 7 29 10 05/03/2024 05/31/2024 8 8 18 10 16 8 13 12 11 8 33 11 06/07/2024 06/28/2024 5 5 12 7 11 5 8 8 < 6 5 19 7 Q-34 07/05/2024 07/26/2024 5 5 11 5 8 6 10 8 < 6 5 27 8 08/02/2024 08/30/2024 7 7 13 8 14 7 12 10 < 7 7 30 7 09/06/2024 09/27/2024 5 5 11 6 12 6 10 11 < 4 < 7 25 10 10/05/2024 10/25/2024 5 5 9 6 9 5 8 8 < 6 5 22 7 11/01/2024 11/29/2024 5 5 12 5 10 4 9 11 5 5 26 7 12/27/2024 12/27/2024 5 7 12 9 12 6 10 9 < 7 7 26 7

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 49 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 19, Quarterly Surface Water Tritium, lron-55, and Nickel-63 (pCi/L +/- 2 Sigma ) Station Collection Dates H-3 Fe-55 Ni-63 01/05/2024 03/29/2024 180 60 5 04/05/2024 06/28/2024 198 62 4 Q-33 07/05/2024 09/27/2024 197 131 4 10/05/2024 12/27/2024 181 156 5 01/05/2024 03/29/2024 181 81 5 04/05/2024 06/28/2024 199 60 4 Q-34 07/05/2024 09/27/2024 192 79 4 10/05/2024 12/27/2024 177 140 5

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 50 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 20, Quarterly Ground Water Tritium (pCi/L +/- 2 Sigma) Collection Date Q-35 Q-36 01/12/2024 < 183 < 195 04/12/2024 < 189 < 188 07/12/2024 < 199 < 196 10/11/2024 < 186 < 187

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 51 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 21, Quarterly Ground Water Gamma Isotopic (pCi/L +/- 2 Sigma) Station Collection Dates Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 01/12/2024 01/12/2024 5 < 6 10 5 14 < 7 10 15 < 6 < 6 31 10 04/12/2024 04/12/2024 7 5 < 8 7 12 < 6 10 10 7 < 6 29 13 Q-35 07/12/2024 07/12/2024 7 < 6 21 7 14 < 6 11 9 < 6 < 8 29 13 10/11/2024 10/11/2024 7 < 6 11 7 15 7 12 10 < 8 7 33 9 01/12/2024 01/12/2024 6 < 6 12 7 13 < 6 10 14 < 7 < 6 31 13 04/12/2024 04/12/2024 7 8 12 8 15 7 15 14 < 8 10 37 15 Q-36 07/12/2024 07/12/2024 7 < 6 13 7 15 < 8 10 9 < 6 < 6 33 10 10/11/2024 10/11/2024 5 4 13 7 11 4 < 8 7 < 6 4 21 9

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 52 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 22, Semi-Annual Fish Gamma Isotopic (pCi/kg Wet+/- 2 Sigma) Station Collection Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Dates Common Carp 06/05/2024 < 50 < 53 115 < 49 < 120 < 58 < 96 58 52 < 284 < 80 Freshwater 06/05/2024 < 15 < 14 31 < 16 34 < 15 < 26 < 16 < 16 71 < 22 Drum Q-24 Common Carp 09/25/2024 72 < 85 < 210 < 64 < 221 < 75 < 115 < 76 < 67 < 724 < 302 Largemouth 09/25/2024 < 86 96 < 243 < 85 < 227 < 95 < 149 < 76 77 < 808 < 283 Bass Walleye 06/05/2024 < 41 < 47 91 < 64 < 120 < 41 < 79 < 52 < 50 < 156 < 60 White Bass 06/05/2024 < 60 < 52 132 < 62 < 114 < 56 < 85 < 60 < 60 < 300 < 100 Q-29 Channel Catfish 09/25/2024 < 61 < 64 169 < 71 < 161 < 98 < 147 < 84 < 75 < 574 < 184 Common Carp 09/25/2024 77 94 < 167 < 75 < 146 < 70 < 159 < 93 72 < 897 < 295

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 53 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 23, Semi-Annual Shoreline Sediment Gamma Isotopic (pCi/kg Dry+/- 2 Sigma) Station Collection Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Dates 05/26/2023 < 71 < 80 < 168 < 80 < 155 < 80 < 133 < 80 86 < 317 < 82 Q-39 10/20/2023 72 < 71 < 163 < 75 < 173 < 83 < 112 < 68 < 76 311 < 70 05/26/2023 < 91 < 70 < 154 < 112 < 203 < 69 < 147 < 104 < 88 < 320 < 88 Q-40 10/20/2023 < 75 77 < 166 < 93 < 192 96 < 136 < 92 < 85 < 348 < 131

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 54 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2, Cross Check lntercomparison Program Participation in cross check intercomparison studies is mandatory for laboratories performing analyses of REMP samples satisfying the requirements in the Offsite Site Dose Calculation Manual. lntercomparison studies provide a consistent and effective means to evaluate the accuracy and precision of analyses performed by a laboratory. Study results should fall within specified control limits and results that fall outside the control limits are investigated and corrected. Teledyne Brown Engineering Inc. (TBE) participated in the following proficiency testing studies provided by Eckert Ziegler Analytics, DOE's Mixed Analyte Performance Evaluation Program (MAPEP), and/or Environmental Resource Associates (ERA) in 2024. The Laboratory's intercomparison program results for 2024 are summarized below. For the TBE laboratory, 152 out of 167 analyses performed met the specified acceptance criteria. Fifteen analyses did not meet the specified acceptance criteria and were addressed through the TBE Corrective Action Program. A summary is found below: I. NCR 24-02: ERA March MRAD-40 study with Air Particulate AM-241 evaluated as "Not Acceptable." TBE reported 38.8 pCi/filter and the known value returned at 55.0 pCi/filter (range 39.3-73.3). The root cause investigation determined that the sample was not logged into the system correctly and therefore not prepared with the required tracer. To correct and prevent recurrence, personnel involved are to utilize a template to ensure all analyses are logged as required and the QA Manager will perform sample log review as a back up to ensure accuracy. Acceptable results returned in a later sample study, supporting effectiveness of corrective action. II. NCR 24-03: ERA March MRAD-40 air particulate study GR-B evaluated as "Not Acceptable." TBE reported 42.1 pCi/filter and the known value returned at 22.2 pCi/filter (range 13.5-33.5). The root cause investigation determined that alpha-to-beta crosstalk was more significant than normal which caused the beta activity to report falsely high data. To correct and prevent recurrence, personnel involved are to adjust the alpha-to-beta crosstalk via correction calculation measures when high alpha activities are observed. Acceptable results returned in a later sample study, supporting effectiveness of corrective action. 111. NCR 24-05: ERA April RAD-137 water study GR-A evaluated as "Not Acceptable." TBE reported 35.2 pCi/L and the known value returned at 52.6 pCi/L (range 39.6-65.6). The root cause investigation determined that the provided samples contained a solids content that was significantly higher than the typical client samples tested by the laboratory. A set aliquot volume for prior ERA samples was used and not adjusted to account for the sudden increase in solid content. To correct and prevent recurrence, new sample types were ordered from ERA that used Am-241 to better reflect client sample testing and acceptable results were achieved. Acceptable results returned in a later sample study, supporting effectiveness of corrective action. IV. NCR 24-06: E&Z Analytics March E14092 air particulate study Co-60 evaluated as

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 55 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 "Not Acceptable." TBE reported 168 pCi and the known value returned at 126 pCi. Additionally, March E14093 soil Ce-141 evaluated as "Not Acceptable." TBE reported 0.106pCi/g and the known value returned at 0.071pCi/g. The root cause investigation was unable to determine any anomaly thus no proposed corrective action. No recurrence has occurred. V. CAR 24-02 (CAR 23-31): MAPEP February 24-MaS50 soil study Fe-55 evaluated as "Not Acceptable." TBE reported 297 Bg/Kg and the known value returned at 650 Bg/Kb (range 455-845). The root cause investigation suspects that the current analytical procedure is not sufficient to add the interferences added to the sample by MAPEP. This investigation is still ongoing (See NCR 24-16) as the suggested corrective action did not provide desired results. VI. NCR 24-08: MAPEP February 24-MaS50 soil study Ni-63 evaluated as "Not Acceptable." TBE reported 1070 Bg/Kg and the known value returned at 1530 Bg/Kb (range 1071-1989). The root cause investigation suspected that the sample contained added interferences that are not typically seen in client samples. All QC efforts associated with the sample were acceptable and no anomalies found, even after reanalysis. To correct and prevent recurrence, samples suspected of additional interferences will include the addition of Ni-59 tracer to determine yield results when calculating results. TBE analytical procedure TBE-2013 was updated to include this change. VII. NCR 24-09: MAPEP February 24-MaSU50 urine study Zn-65 evaluated as "Not Acceptable." The root cause investigation determined that the sample was spiked lower than TBE's typical detection limit and client requirements. The report was revised by MAPEP indicating "Not Evaluated," resulting in this nuclide to not be considered a failure. VIII. NCR 24-10: MAPEP February 24-MaW50 water study Tc-99 evaluated as "Not Acceptable." TBE reported 9.958g/L and the known value returned 7.478g/L (range 5.23-9. 71 ). The root cause investigation suspects Thorium interference that was not removed during the column separation process of the analytical procedure; however, it cannot be confirmed as all QC efforts associated with the sample were acceptable and with no anomalies found. To potentially correct and prevent recurrence, an additional rinse step was added to the procedure. Acceptable results returned in a later sample study, supporting effectiveness of corrective action. IX. NCR 24-11: MAPEP February 24-RdV50 vegetation study Sr-90 evaluated as "Not Acceptable." TBE reported 0.276Bg/sample and the known value returned 0.529Bg/sample (range 0.370-0.688). The root cause investigation determined a laboratory accident resulting in a spilled (loss) of sample. No corrective action was performed as the cause was an unintentional sample spill. X. NCR 24-14: ERA September MRAD-41 air particulate study U-234/238 evaluated as "Not Acceptable." TBE reported 14.0/14.2 pCi/filter and the known value returned at 31.1/30.9 pCi/filter (range 23.1-36.9). The root cause investigation determined that the laboratory technician placed double the amount of tracer in the sample by error. To correct and prevent recurrence, samples that have been digested/leached with carrier/tracer added will have a label placed over the cap indicating it has already been

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 56 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 added. Additionally, the beaker that aliquot is put in should have markings to indicate carrier/tracer has already been added to the sample. XI. NCR 24-15: ERA September MRAD-41 water study Fe-55 evaluated as "Not Acceptable." TBE reported 615 pCi/L and the known value returned at 1230 pCi/L (range 723-1790). The root cause is still under investigation. XII. NCR 24-16: MAPEP August 24-MaS50 soil study Fe-55 evaluated as "Not Acceptable." TBE did not report a value and the known value returned 780Bg/Kg (range 546-1014). The root cause is still under investigation. XIII. NCR 24-17: MAPEP August 24-RdV51 vegetation study Sr-90 evaluated as "Not Acceptable." TBE reported 0.95Bg/sample and the known value returned 2.39Bg/sample (range 1.67-3.11). The root cause is still under investigation.

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 57 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 24, Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services Identification TBE Known RatioofTBE Evaluation MonthNear Number Matrix Nuclide Units Reported Value (a) to Analytics (b) Value Result March 2024 E14089 Milk Sr-89 pCi/L 79.6 78.2 1.02 A Sr-90 pCi/L 12.6 11.9 1.06 A E14090 Milk Ce-141 pCi/L 75.6 85.0 0.89 A Co-58 pCi/L -0.069 Not Measured Co-60 pCi/L 139 158 0.88 A Cr-51 pCi/L 212 230 0.92 A Cs-134 pCi/L 167 198 0.84 A Cs-137 pCi/L 158 171 0.93 A Fe-59 pCi/L 81.1 86.5 0.94 A 1-131 pCi/L 80.9 90.8 0.89 A Mn-54 pCi/L 173 183 0.95 A Zn-65 pCi/L 165 176 0.93 A E14091 Charcoal 1-131 pCi 90.1 90.3 1.00 A E14092 AP Ce-141 pCi 68.1 67.5 1.01 A Co-58 pCi 1.73 Not Measured Co-60 pCi 168 126 1.34 N(1l Cr-51 pCi 182 183 0.99 A Cs-134 pCi 157 157 1.00 A Cs-137 pCi 132 136.0 0.97 A Fe-59 pCi 70.3 68.6 1.02 A Mn-54 pCi 144 145 0.99 A Zn-65 pCi 125 140 0.89 A E14093 Soil Ce-141 pCi/g 0.106 0.071 1.48 N(1l Co-58 pCi/g -0.005 Not Measured Co-60 pCi/g 0.121 0.133 0.91 A Cr-51 pCi/g 0.198 0.194 1.02 A Cs-134 pCi/g 0.206 0.166 1.24 w Cs-137 pCi/g 0.207 0.209 0.99 A Fe-59 pCi/g 0.063 0.073 0.87 A Mn-54 pCi/g 0.140 0.153 0.91 A Zn-65 pCi/g 0.149 0.148 1.01 A E14094 AP Sr-89 pCi 83.9 90.6 0.93 A Sr-90 pCi 11.7 13.8 0.85 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limlts: A= Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported resultfalls within 0. 70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < o. 70 and > 1.30 (1) See NCR 24-06

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 58 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 24, Analytics Environmental Radioactivity Cross Check Program Cont'd Teledyne Brown Environmental Services Month/Year Identification Matrix Nuclide Units TBE Reported Known Ratio of TBE to Evaluation Number Value Value (a) Analytics Result (b) September 2024 E14095 Milk Sr-89 pCi/L 88.0 92.3 0.95 A Sr-90 pCi/L 12.4 15.2 0.82 A E14096 Milk Ce-141 pCi/L 124 124 1.00 A Co-58 pCi/L 154 150 1.03 A Co-60 pCi/L 232 236 0.98 A Cr-51 pCi/L 284 274 1.04 A Cs-134 pCi/L 180.0 187 0.96 A Cs-137 pCi/L 126 127 0.99 A Fe-59 pCi/L 127.0 113 1.12 A 1-131 pCi/L 85.3 89.0 0.96 A Mn-54 pCi/L 162 162 1.00 A Zn-65 pCi/L 294 275 1.07 A E14097 Charcoal 1-131 pCi 98.8 92.6 1.07 A E14098 AP Ce-141 pCi 82.0 76.7 1.07 A Co-58 pCi 91.0 92.6 0.98 A Co-60 pCi 180 146 1.23 w Cr-51 pCi 208 170 1.22 w Cs-134 pCi 116 116 1.00 A Cs-137 pCi 83.1 78.9 1.05 A Fe-59 pCi 75.6 70.2 1.08 A Mn-54 pCi 101 100 1.01 A Zn-65 pCi 167 170 0.98 A E14099 Soil Ce-141 pCi/g 0.224 0.222 1.01 A Co-58 pCi/g 0.249 0.268 0.93 A Co-60 pCi/g 0.420 0.423 0.99 A Cr-51 pCi/g 0.492 0.492 1.00 A Cs-134 pCi/g 0.278 0.336 0.83 A Cs-137 pCi/g 0.276 0.295 0.94 A Fe-59 pCi/g 0.233 0.204 1.14 A Mn-54 pCi/g 0.279 0.290 0.96 A Zn-65 pCi/g 0.538 0.494 1.09 A E14100 AP Sr-89 pCi 79.8 82.7 0.96 A Sr-90 pCi 12.0 13.6 0.88 A Gr-A E14197 Liquid (Am241) pCi/L 47.6 50.1 0.95 A Gr-8 (Cs137) pCi/L 248 270 0.92 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limlts: A= Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and > 1.30

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page59 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 25, DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Teledyne Brown Engineering Environmental Services Identification TSE Known Acceptance Evaluation Month/Year Number Matrix Nuclide Units Reported Value Range (b) Value (a) February 2024 24-MaS50 Soil Fe-55 Sq/kg 297 650 455 - 845 N(3l Ni-63 Sq/kg 1070 1530 1071-1989 N!4l Tc-99 Sq/kg 325 336 235-437 A Th-228 Sq/kg 34.6 48.8 34.2 -63.4 w Th-230 Sq/kg 49.7 54.0 38.0- 70.0 A Th-232 Sq/kg 36.4 45.1 31.6 - 58.6 A 24-MaSU50 Urine Cs-134 Sq/L 1.12 1.36 0.95 -1.77 A Cs-137 Sq/L 2.00 2.23 1.56 - 2.90 A Co-57 Bq/L 1.06 1.26 0.88 -1.64 A Co-60 Bq/L 2.26 2.38 1.67 - 3.09 A K-40 Sq/L -1.80 NR Mn-54 Sq/L 1.44 1.51 1.06 -1.96 A U-234 Sq/L 0.00101 (1) A U-238 Sq/L 0.00228 (1) A Zn-65 Sq/L -0.42 0.84 0.59 -1.09 NE<5> 24-MaW50 Water Ni-63 Sq/L 0.338 0.80 (2) A Tc-99 Sq/L 9.95 7.47 5.23 - 9.71 N 24-RdV50 Vegetation Cs-134 Sq/sample 2.80 3.67 2.57 -4.77 w Cs-137 Sq/sample 2.21 2.57 1.80 - 3.34 A Co-57 Sq/sample 2.23 2.53 1.77 - 3.29 A Co-60 Sq/sample 2.42 2.96 2.07 - 3.85 A Mn-54 Sq/sample 0.033 (1) A Sr-90 Sq/sample 0.276 0.529 0.370 - 0.688 N!7l Zn-65 Sq/sample 6.83 8.02 5.61 - 10.43 A (a) The MAPEP known value is equal to 100% of the parameter present in the standard as detennined by gravimetric and/or volumetric measurements made during standard preparation (b) DOEIMAPEP evaluation: A= Acceptable - reported result falls within ratio limits of 0.80-1.20 W= Acceptable with warning-reported result falls within 0. 70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of< o. 70 and> 1.30 (1) False positive test (2) Sensitivity evaluation (3) See CAR 23 Analyte not on XCHK list (4) See NCR 24-08 (5) Not Evaluated (6) See NCR 24-10 (7) See NCR 24-11 (8) Not Reported (9) See NCR 24-16 (10) See NCR 24-17

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page60 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 25, DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Cont'd Teled~ne Brown Engineering Environmental Services Identification TSE Known Acceptance Evaluation Month/Year Matrix Nuclide Units Reported Value Number Value (a) Range (b) August2024 24-MaS51 Soil Fe-55 Sq/kg (8) 780 546-1014 N(9l Ni-63 Sq/kg 1140.00 1450.00 1015-1885 w Tc-99 Sq/kg 155.00 171.00 120 - 222 A Th-228 Sq/kg 38.00 43.30 30.3-56.3 A Th-230 Sq/kg 46.10 44.00 30.8-57.2 A Th-232 Sq/kg 38.90 42.60 29.8-55.4 A 24-MaW51 Water Ni-63 Sq/L 0.60 (1) A Tc-99 Sq/L 11.90 11.20 7.8 -14.6 A 24-RdV51 Vegetation Cs-134 Sq/sample 3.12 2.89 2.02 - 3.76 A Cs-137 Sq/sample 2.18 1.91 1.34 - 2.48 A Co-57 Sq/sample 0.00 (1) A Co-60 Sq/sample 2.24 2.01 1.41-2.61 A Mn-54 Sq/sample 3.76 3.53 2.47 -4.59 A Sr-90 Sq/sample 0.95 2.39 1.67 - 3.11 N<1oi Zn-65 Sq/sample 10.30 9.13 6.39 -11.87 A (a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) DOEIMAPEP evaluation: A= Acceptable - reported result falls within ratio limits of 0.80-1.20 W= Acceptable with warning - reported result falls within O. 70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of< 0. 70 and> 1.30 (1) False positive test (2) Sensitivity evaluation (3) See CAR 23 Analyte not on XCHK list (4) See NCR 24-0B (5) Not Evaluated (6) See NCR 24-10 (7) See NCR 24-11 (8) Not Reported (9) See NCR 24-16 (10) See NCR 24-17

Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 61 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 26, ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering Environmental Services Identification TBE Known Acceptance Evaluation Month/Year Number Matrix Nuclide Units Reported Value(a) Limits (b) Value March 2024 MRAD-40 Water Am-241 pCi/L 101 139 95.4-178 A Fe-55 pCi/L 2185 2480 1460-3610 A Pu-238 pCi/L 62.0 70.4 42.3 - 91.2 A Pu-239 pCi/L 61.2 76.5 47.3-94.3 A Soil Am-241 pCi/kg NR 1880 1020- 2660 Pu-238 pCi/kg 667 512 255-778 A Pu-239 pCi/kg 562 545 297 - 784 A Sr-90 pCi/kg 4050 3630 1130 - 5650 A U-234 pCi/kg 3040 4360 2040- 5710 A U-238 pCi/kg 3270 4320 2370- 5800 A AP Am-241 pCi/filter 38.8 55.0 39.3-73.3 N(1l Fe-55 pCi/filter 387 386 141 - 616 A Pu-238 pCi/filter 45.9 41.1 31.0- 50.5 A Pu-239 pCi/filter 54.9 56.1 41.9 - 67.7 A U-234 pCi/filter 11.1 11.6 8.60 - 13.6 A U-238 pCi/filter 12.8 11.5 8.68 - 13.7 A GR-A pCi/filter 116 95.9 50.1 -158 A GR-8 pCi/filter 42.1 22.2 13.5 - 33.5 N(2l April 2024 RAD-137 Water Ba-133 pCi/L 62.8 65.9 50.1 - 81.7 A Cs-134 pCi/L 51.0 57.8 42.8-72.8 A Cs-137 pCi/L 153 186 149 - 223 A Co-60 pCi/L 92.1 98.8 79.7-118 A Zn-65 pCi/L 208 240 188 - 292 A GR-A pCi/L 35.2 52.6 39.6-65.6 N13l GR-8 pCi/L 49 46.5 33.9 - 59.1 A U-Nat pCi/L 56.0 59.3 52.8-65.8 A H-3 pCi/L 19,000 21,300 18,200 - 24,400 A Sr-89 pCi/L 48.9 52.2 37.8 - 66.6 A Sr-90 pCi/L 32.6 37.6 32.0-43.2 A 1-131 pCi/L 21.8 25.1 21.7-28.5 A (a) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (b) ERA evaluation: A = Acceptable

Reported value falls within the Acceptance Umits N = Not Acceptable - Reported value falls outside of the Acceptance Umits (1) See NCR 24-02 (2) See NCR 24-03 (3) See NCR 24-05 (4) See NCR 24-15 (5) See NCR 24-14
Annual Radiological Environmental Operating Report I YEAR: 2024 I Page62 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 26, ERA Environmental Radioactivity Cross Check Program Cont'd Teled:tne Brown Engineering Environmental Services Identification TBE Known Acceptance MonthNear Matrix Nuclide Units Reported Evaluation (b) Number Value Value(a) Limits September 2024 MRA0-41 Water Am-241 pCi/L 108.0 117.0 80.3 -150 A Fe-55 pCi/L 615 1230 723-1790 N<> Pu-238 pCi/L 99 103 61.9 - 133 A Pu-239 pCi/L 123 133 82.3 -164 A Soil Am-241 pCi/kg 1320 1110 599 - 1570 A Pu-238 pCi/kg 1380 1860 928 - 2830 A Pu-239 pCi/kg 796 1030 561 -1480 A Sr-90 pCi/kg 3240 4730 1470 - 7370 A U-234 pCi/kg 2540 2860 1340- 3750 A U-238 pCi/kg 2390 2840 1560 - 3810 A AP Am-241 pCi/filter 27.0 29.1 20.8 - 38.8 A Fe-55 pCi/filter 644 800 292 - 1280 A Pu-238 pCi/filter 22.3 21.5 16.2 -26.4 A Pu-239 pCi/filter 30.6 32.4 24.2 - 39.1 A U-234 pCi/filter 14.0 31.1 23.1 - 36.4 NC5l U-238 pCi/filter 14.2 30.9 23.3 - 36.9 N(5l GR-A pCi/filter 80.0 72.4 37.8-119 A GR-8 pCi/filter 57.5 47.9 29.0 - 72.4 A October 2024 RAD-139 Water Ba-133 pCi/L 30.3 27.4 15.5 - 39.3 A Cs-134 pCi/L 73.3 80.2 63.0- 97.4 A Cs-137 pCi/L 46.6 46.3 23.3 - 69.3 A Co-60 pCi/L 44.2 45.3 31.6 - 59.0 A Zn-65 pCi/L 104 114.0 75.0 -153 A GR-A pCi/L 47.6 51.7 38.9-64.5 A GR-B pCi/L 44.2 48.1 35.2 - 61.0 A U-Nat pCi/L 28.3 26.90 23.6 - 30.2 A H-3 pCi/L 4,690 5,320 3870-6770 A Sr-89 pCi/L 57.5 44.2 30.6 - 57.8 A Sr-90 pCi/L 37.3 35.6 30.2 - 41.0 A 1-131 pCi/L 28.3 26.3 22.7 - 29.9 A (a) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (b) ERA evaluation: A = Acceptable - Reported value falls within the Acceptance Umits N = Not Acceptable - Reported value falls outside of the Acceptance Umits (1) See NCR 24-02 (2) See NCR 24-03 (3) See NCR 24-05 (4) See NCR 24-15 (5) See NCR 24-14
Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 63 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2, Environmental Direct Radiation Dosimetry Results ~,.. :.. Ba+MDDa Nonnallzed Quarterly Monitoring Data, lllci Quarterly
~
Monitoring Basellne, Location Ba(mrem) (mrem) (mrem) 1 2 3 ~ 0-01 11.4 15.78 5.3 3.1 3.2 0-02 11.7 16.08 6.4 3.5 2.1 0-03 10.7 15.08 5.3 4.3 1.8 0-04 12.4 16.78 9.5 4.8 2.1 0-13 13.2 17.58 5.2 8.1 3.1 0-16 10.9 15.28 6.8 4.3 2.5 0-37 13.7 18.08 9.6 4.4 3.8 0-38 14.8 19.18 11.2 4.3 ND (3) 041 13.7 18.08 5.7 3.9 4.9 042 14.5 18.88 8 9.5 5 0-101-1 11.8 16.18 8.5 2.5 4.5 0-101-2 12.4 16.78 9.6 1.2 2.9 0-102-1 13.1 17.48 7.8 6.8 5.5 0-102-3 12.4 16.78 8.5 2.6 4.2 0-103-1 11.1 15.48 8.2 4 3.2 0-103-2 11.1 15.48 6.9 5.1 2.7 0-104-1 11.4 15.78 7.3 5.4 2.8 0-104-2 12 16.38 8.4 3.5 2.8 0-105-1 11.5 15.88 7.7 2.5 3.1 MDDa = Quarterly Minimum Differential Dose = 4.38 mrem MDDA = Annual Minimum Differential Dose= 10.32 mrem ND = Not Detected, where Mas (Ba+MDDa) or MA s (BA+MDDA) 4 2.2 1.6 ND (3) 1.9 3.8 4.9 0.4 8.2 5.2 7.2 ND (3) ND (3) ND (3) 0.7 0 ND (3) ND (3) ND (3) 0 l ~ Ba = Quarterly Normalized Mean Background for a monitoring location (mrem) BA = Annual Normalized Mean Background for a monitoring location (mrem) MA = Normalized Annual Dose (mrem) (1) = Environmental Dosimetry lost for this period (2) = OSLD lost in transit (3) = Dose less than detectable Quarterly Faclllty Dose, Fa=Mo-Ba (mrem, or "NDn If FoS IIDDo) ~ 1 2 3 4 ND ND ND ND ND ND ND ND ND ND ND ND (3) ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND (3) ND ND ND ND ND ND ND ND ND ND ND ND ND (3) ND ND ND ND (3) ND ND ND ND (3) ND ND ND ND ND ND ND ND ND ND ND ND (3) ND ND ND ND (3) ND ND ND ND (3) ND ND ND ND BA+MDDA Annual
~~Basellne, BA(mrem)~~
~~(mram) 1,~~
45.7 56.02 46.8 57.12 42.8 53.12 49.3 59.62 52.9 63.22 43.7 54.02 55 65.32 59.2 69.52 54.6 64.92 57.8 68.12 47.2 57.52 49.8 60.12 52.3 62.62 49.8 60.12 44.4 54.72 44.3 54.62 45.2 55.52 47.8 58.12 46.2 56.52 AMual Faclllty
~~Dose, fA=MA-BA Annual Monitoring (mrem,or Data.MA "NDn If (mrem)~~
FASMDDA) 13.8 ND 13.6 ND 11.1 ND 18.3 ND 20.2 ND 18.5 ND 18.2 ND 12.9 ND 19.7 ND 29.7 ND 14.8 ND 12.1 ND 19.8 ND 16 ND 15.4 ND 14.1 ND 14.8 ND 13.5 ND 13.3 ND
1 Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 64 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2, Environmental Direct Radiation Dosimetry Results Cont'd BQ+ Ml>OQ Nonnallzad Quarterly Monitoring Data, Mei Quarterly Monitoring
~~Basellne, Location Ba (mram)~~
(mrem) (mrem) 1 2 3 Q-105-2 11.7 16.08 8.7 4.7 3.4 Q-106-2 12.1 16.48 7.1 2.4 2.2 Q-106-3 11.7 16.08 8.6 4.9 1.8 Q-107-2 11.6 15.98 6.9 3.5 2.7 Q-107-3 11.7 16.08 9.5 3.2 3.1 Q-108-1 11.9 16.28 7.9 2 4 Q-108-2 11.6 15.98 7.8 0.2 3.4 Q-109-1 12.4 16.78 8.9 5.2 4.1 Q-109-2 12 16.38 7.7 3.2 3.7 Q-111-1 12.1 16.48 5.8 3 1.6 Q-111-2 12.1 16.48 5.6 5.2 1.7 Q-112-1 12 16.38 3.1 5.1 1.3 Q-112-2 11.4 15.78 3 1.7 0.8 Q-113-1 11.5 15.88 3.1 5.3 2.8 Q-113-2 10.9 15.28 4.1 4.4 N/A (1) Q-114-1 10.9 15.28 4.9 3.5 1.1 Q-114-2 12.6 16.98 6.4 7.2 3.4 Q-115-1 12.1 16.48 5.3 4.8 3.7 Q-115-2 11.3 15.68 3 6 1.4 MDDa = Quarterly Minimum Differential Dose= 4.38 mrem MDDA = Annual Minimum Differential Dose = 10.32 mrem ND = Not Detected, where Ma :5 (Ba+MDDa) or MA :5 (BA+MDDA) 4 ND (3) ND (3) 0.8 ND (3) ND (3) ND (3) ND (3) ND (3) 0.4 5.8 3.3 N/A (1) 2.5 1.5 0.2 1.8 2 3 4.9
~~Ii 1,~~
Ba= Quarterly Normalized Mean Background for a monitoring location (mrem) BA = Annual Normalized Mean Background for a monitoring location (mrem) MA = Normalized Annual Dose (mrem) ( 1) = Environmental Dosimetry lost for this period (2) = OSLO lost in transit (3) = Dose less than detectable Quarterly Facility Dose, Annual
~~Basellne, Fci=llci-Ba (mntm)~~
(mrem, or "ND" If FQS MDDq) ~. 1 2 3 4 ND ND ND ND (3) 47 ND ND ND ND (3) 48.2 ND ND ND ND 46.9 ND ND ND ND (3) 46.5 ND ND ND ND (3) 46.9 ND ND ND ND (3) 47.7 ND ND ND ND (3) 46.6 ND ND ND ND (3) 49.5 ND ND ND ND 48 ND ND ND ND 48.5 ND ND ND ND 48.5 ND ND ND NIA (1) 47.9 ND ND ND ND 45.4 ND ND ND ND 45.9 ND ND N/A(1) ND 43.4 ND ND ND ND 43.8 ND ND ND ND 50.3 ND ND ND ND 48.5 ND ND ND ND 45.4 - BA+ MDDA (mrem) 57.32 58.52 57.22 56.82 57.22 58.02 56.92 59.82 58.32 58.82 58.82 58.22 55.72 56.22 53.72 54.12 60.62 58.82 55.72 Annual Faclllty
~~Dose, Annual FA=MA-BA Monitoring (mram,or Data, MA "ND" If (mram)~~
FAS MDDA) 15.4 ND 10.2 ND 16.1 ND 12.8 ND 13.4 ND 11.9 ND 9.6 ND 17.8 ND 15 ND 17.6 ND 15.8 ND 9.5 ND 8 ND 12.7 ND 11.6 ND 11.3 ND 19 ND 16.8 ND 15.3 ND
Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 65 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2, Environmental Direct Radiation Dosimetry Results Cont'd ~- Ba+ MDDo Quarl8rty Normalized Quarterly Monitoring Data, Ma M~nltortng
~~Basallne,~~
.,-1 Location Ba (mrem) (mrem) (mrem) 1 2 3 Q-116-1 13.4 17.78 5.6 8.5 3.7 Q-116-3 12.3 16.68 6.1 6.7 3.3 Q-201-1 13 17.38 6.1 3.4 3.4 Q-201-2 13.7 18.08 6.7 7.2 5 Q-202-1 11.6 15.98 5.1 5.3 1.4 Q-202-2 12.9 17.28 3.9 2.6 2 Q-203-1 13.3 17.68 6 7.3 4.8 Q-203-2 15.8 20.18 11 5.2 6.4 Q-204-1 14.2 18.58 11.1 6.9 3.8 Q-204-2 15.4 19.78 10.3 7.4 7.9 Q-205-1 13.8 18.18 10 4.8 7.1 Q-205-4 15.4 19.78 11.2 3.9 6.6 Q-206-1 12.9 17.28 9.7 4.4 5.2 Q-206-2 11.8 16.18 7.8 6.3 4.3 Q-207-1 13.1 17.48 9.4 4.3 5.4 Q-207-4 13.7 18.08 11.4 5.1 5.8 Q-208-1 13.1 17.48 9.3 3.7 3.6 Q-208-2 14.6 18.98 10.6 7.6 7.3 MDDa = Quarterly Minimum Differential Dose =4.38 mrem MDDA = Annual Minimum Differential Dose = 10.32 mrem ,~ ND = Not Detected, where Ma :5 (Ba+MDDa) or MA :5 (BA+MDDA) 4.5 3.5 N/A(1) 6.4 0.1 1.3 4.5 2.5 2.6 2.8 1.5 1.3 1 ND (3) 2.9 2.4 ND (3) 1.3 Ba= Quarterly Normalized Mean Background for a monitoring location (mrem) BA = Annual Normalized Mean Background for a monitoring location (mrem) MA = Normalized Annual Dose (mrem) (1) = Environmental Dosimetry lost for this period (2) = OSLO lost in transit (3) = Dose less than detectable Quarterlyifaclllty Dose, Annual Fa=McrBca
~~Basallne, a,.~~
(mrem) (mrem, or "ND" H fQ$ MDDo) 1 2 3 4 ND ND ND ND 53.8 ND ND ND ND 49.3 ND ND ND N/A (1) 52 ND ND ND ND 54.8 ND ND ND ND 46.5 ND ND ND ND 51.6 ND ND ND ND 53.2 ND ND ND ND 63.2 ND ND ND ND 56.9 ND ND ND ND 61.6 ND ND ND ND 55.4 ND ND ND ND 61.3 ND ND ND ND 51.5 ND ND ND ND (3) 47.2 ND ND ND ND 52.5 ND ND ND ND 55 ND ND ND ND (3) 52.3 ND ND ND ND 58.4 a,.+ MOO,. (mrem) 64.12 59.62 62.32 65.12 56.82 61.92 63.52 73.52 67.22 71.92 65.72 71.62 61.82 57.52 62.82 65.32 62.62 68.72 Annual Faclllty
~~Dose, Annual F,.-=M,.-8,.~~
Monitoring (mram,or Data, M,. "ND" H (mrem) F,.$ MOD,.) 22.3 ND 16.3 ND 12.9 ND 25.3 ND 8.8 ND 10.4 ND 22.6 ND 25.1 ND 24.4 ND 28.4 ND 23.4 ND 25.5 ND 20.3 ND 16.1 ND 22 ND 24.7 ND 16.3 ND 26.8 ND
Annual Radiological Environmental Operating Report I YEAR: 2024 I Page 66 of 66 Company: Constellation I Plant: Quad Cities Nuclear Power Station Units 1 and 2, Environmental Direct Radiation Dosimetry Results Cont'd '~ '~ Bo+ MDDa Quarterly Nonnallzed Quarterly Monitoring Data, Ilea Monitoring
~~Baseline, Location~~
. Bo 1, (mntm) (mntm) (mntm) 1,,...,, 1 2 3 Q-209-1 14 18.38 10.7 6.2 6.3 O-209-4 13.3 17.68 10.2 6.4 3.9 Q-210-1 15 19.38 7.4 7.2 4 Q-210-4 14.6 18.98 7.5 9 3.8 Q-210-5 10.7 15.08 6.3 1.3 ND (3) Q-211-1 16.1 20.48 7.4 8.2 5.2 Q-211-2 16.5 20.88 10.3 8.6 4.6 Q-212-1 12.9 17.28 7 8.6 3.7 Q-212-2 10.6 14.98 4.4 3.2 ND (3) Q-213-1 11.9 16.28 5.2 6.3 4.2 Q-213-2 11.4 15.78 3.9 4.4 0.3 Q-214-1 12.7 17.08 6.2 4.2 3.4 Q-214-2 13.6 17.98 7.8 5.8 5.5 Q-215-1 12.5 16.88 5.5 5 4.4 Q-215-2 13.9 18.28 7.6 11.3 5.7 Q-216-1 15.4 19.78 7.9 7.2 5.4 Q-216-2 14.1 18.48 5.1 6.8 4.3 MDDa = Quarterly Minimum Differential Dose= 4.38 mrem MDDA = Annual Minimum Differential Dose = 10.32 mrem ND = Not Detected, where Mas (Ba+MDDa) or MA s (BA+MDDA) 4 1.6 4.4 5.7 3.3 ND (3) 7.1 7.3 5.3 1.1 4.4 2.5 3 4.8 3.2 5.4 5.8 4 1,,.
~~, 1, Ba = Quarterly Normalized Mean Background for a monitoring location (mrem)~~
BA = Annual Normalized Mean Background for a monitoring location (mrem) MA = Normalized Annual Dose (mrem) (1) = Environmental Dosimetry lost for this period (2) = OSLD lost in transit (3) = Dose less than detectable Quarterly Facility Dose, I.*' Annual Fa=Mo-Bca
~~Baseline, 8-.~~
(mram) ~ (mrem, or"ND" lffQS.IIDDo) 1 2 3 4 ND ND ND ND 56 ND ND ND ND 53.1 ND ND ND ND 60 ND ND ND ND 58.6 ND ND ND (3) ND (3) 42.7 ND ND ND ND 64.4 ND ND ND ND 66 ND ND ND ND 51.7 ND ND ND (3) ND 42.5 ND ND ND ND 47.8 ND ND ND ND 45.6 ND ND ND ND 50.7 ND ND ND ND 54.4 ND ND ND ND 50.1 ND ND ND ND 55.7 ND ND ND ND 61.6 ND ND ND ND 56.4 BA+ IIDDA (mrem) 66.32 63.42 70.32 68.92 53.02 74.72 76.32 62.02 52.82 58.12 55.92 61.02 64.72 60.42 66.02 71.92 66.72 -. ~-.- Annual Facility
~~Dose, FA~-BA Annual (mntm, Monitoring or"ND" Data, MA If (mrem)~~
FAS MDDA) 24.8 ND 24.9 ND 24.3 ND 23.6 ND 6 ND 27.9 ND 30.8 ND 24.6 ND 8.4 ND 20.1 ND 11.1 ND 16.8 ND 23.9 ND 18.1 ND 30 ND 26.3 ND 20.2 ND
Intentionally left blank
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 1 of 31 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Annual Radiological Groundwater Protection Program Report 2024 Document Number: 50-254/50-265
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 2 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS................................................................................. 3
~~2.0 INTRODUCTION~~
........................................................................................................................ 5 2.1 About Nuclear Power...................................................................................................... 5 2.2 About Radiation Dose..................................................................................................... 7 2.3 About Dose Calculation................................................................................................... 9 3.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM................ 12 3.1 Voluntary Notification.................................................................................................... 29 4.0 BIBLIOGRAPHY....................................................................................................................... 30 TABLES Table 1, Groundwater Protection Program Monitoring Well Sampling Locations................................... 12 Table 2, Groundwater Protection Program Monitoring Well Tritium, Strontium, and Gross Alpha in Groundwater Samples (pCi/L +/- 2 sigma)............................................................................................. 18 Table 3, Groundwater Protection Program Monitoring Well Gamma Isotopic in Groundwater Samples (pCi/L +/- 2 sigma)................................................................................................................................. 21 Table 4, Groundwater Protection Program Monitoring Well Hard-To-Detects in Groundwater Samples (pCi/L +/- 2 sigma)................................................................................................................................. 23 Table 5, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma)....................................................... 24 FIGURES Figure 1, Pressurized Water Reactor (PWR) [1]..................................................................................... 5 Figure 2, Boiling Water Reactor (BWR) [2]............................................................................................. 6 Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3]..................................................... 7 Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6]............... 10 Figure 5, Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Stations, 2024 ............................................................................................................................................................ 15 Figure 6, Radwaste Area Well Locations, Quad Cities Nuclear Power Station, 2024............................ 16
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 3 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 1.0 LIST OF ACRONYMS AND DEFINITIONS
1.
~~Alpha Particle (a): A charged particle emitted from the nucleus of an atom having a mass and charge equal in magnitude of a helium nucleus.~~
2.
~~BWR: Boiling Water Reactor~~
3.
Composite Sample: A series of single collected portions (aliquots) analyzed as one sample. The aliquots making up the sample are collected at time intervals that are very short compared to the composite period.
4.
~~Control: A sampling station in a location not likely to be affected by plant effluents due to its distance and/or direction from the Plant.~~
5.
~~Counting Error: An estimate of the two-sigma uncertainty associated with the sample results based on total counts accumulated.~~
6.
~~Curie (Ci): A measure of radioactivity; equal to 3. 7 x 1010 disintegrations per second, or 2.22 x 1012 disintegrations per minute.~~
7.
Direct Radiation Monitoring: The measurement of radiation dose at various distances from the plant is assessed using thermoluminescent dosimeters (TLDs), optically stimulated luminescent dosimeters (OSLDs), and/or pressurized ionization chambers.
8.
~~Grab Sample: A single discrete sample drawn at one point in time.~~
9.
~~Indicator: A sampling location that is potentially affected by plant effluents due to its proximity and/or direction from the plant.~~
~~10.~~
Ingestion Pathway: The ingestion pathway includes milk, fish, drinking water and garden produce. Also sampled (under special circumstances) are other media such as vegetation or animal products when additional information about particular radionuclides is needed.
~~11.~~
~~ISFSI: Independent Spent Fuel Storage Installation~~
~~12.~~
LLD: Lower Limit of Detection. An a priori measure of the detection capability of a radiochemistry measurement based on instrument setup, calibration, background, decay time, and sample volume. An LLD is expressed as an activity concentration. The MDA is used for reporting results. LLD are specified by a regulator, such as the NRC and are typically listed in the ODCM.
~~13.~~
MDA: Minimum Detectable Activity. For radiochemistry instruments, the MDA is the a posteriori minimum concentration that a counting system detects. The smallest concentration or activity of radioactive material in a sample that will yield a net count above instrument background and that is detected with 95% probability, with only 5% probability of falsely concluding that a blank observation represents a true signal.
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page4 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2
~~14.~~
~~MDC: Minimum Detectable Concentration. Essentially synonymous with MDA for the purposes of radiological monitoring.~~
~~15.~~
~~Mean: The sum of all of the values in a distribution divided by the number of values in the distribution, synonymous with average.~~
~~16.~~
~~Microcurie (µCi): 3.7 x 104 disintegrations per second, or 2.22 x106 disintegrations per minute.~~
~~17.~~
~~millirem (mrem): 1/1000 rem; a unit of radiation dose equivalent in tissue.~~
~~18.~~
~~Milliroentgen (mR): 1/1000 Roentgen; a unit of exposure to X-or gamma radiation.~~
~~19.~~
~~N/A: Not Applicable~~
~~20.~~
~~NEI: Nuclear Energy Institute~~
~~21.~~
~~NRC: Nuclear Regulatory Commission~~
~~22.~~
~~ODCM: Offsite Dose Calculation Manual~~
~~23.~~
~~OSLO: Optically Stimulated Luminescence Dosimeter~~
~~24.~~
Protected Area: A 1 O CFR 73 security term is an area encompassed by physical barriers and to which access is controlled for security purposes. The fenced area immediately surrounding the plant and around ISFSI are commonly classified by the licensee as "Protected areas." Access to the protected area requires a security badge or escort.
~~25.~~
~~PWR: Pressurized Water Reactor~~
~~26.~~
~~REC: Radiological Effluent Control~~
~~27.~~
~~REMP: Radiological Environmental Monitoring Program~~
~~28.~~
Restricted Area: A 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
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 5 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2
~~32.~~
~~TS: Technical Specification~~
~~33.~~
~~Unrestricted Area: An area, access to which is neither limited nor controlled by the licensee.~~
~~2.0 INTRODUCTION~~
2.1 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 Stnlctll"C Figure 1, Pressurized Water Reactor (PWR) [1]
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page6 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Containment Structure Figure 2, Boiling Water Reactor (BWR) [2] Electricity is generated by a nuclear power plant similarly to the way that electricity is generated at other conventional types of power plants, such as those powered by coal or natural gas. Water is boiled to generate steam; the steam turns a turbine that is attached to a generator and the steam is condensed back into water to be returned to the boiler. What makes nuclear power different from these other types of power plants is that the heat is generated by fission and decay reactions occurring within and around the core containing fissionable uranium (U-235). Nuclear fission occurs when certain nuclides (primarily U-233, U-235, or Pu-239) absorb a neutron and break into several smaller nuclides (called fission products) as well as producing some additional neutrons. Fission results in production of radioactive materials including gases and solids that must be contained to prevent release or treated prior to release. These effluents are generally treated by filtration and/or hold-up prior to release. Releases are generally monitored by sampling and by continuously indicating radiation monitors. The effluent release data is used to calculate doses in order to ensure that dose to the public due to plant operation remains within required limits.
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 7 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 2.2 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) Computed tomography (medical) (24%) Terrestrial (background) - (3%) Nuclear medicine _ (medical) (12%) Intervention al fluoroscopy (medical) (7%) (5%) Radon & thoron (background) (37%) Industrial (<0.1%) Occupational (<0.1%) Consumer (2%) Conventional radiography/fluoroscopy (medical) (5%) Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3]
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 8 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 The National Council on Radiation Protection (NCRP) has evaluated the population dose for the US and determined that the average individual is exposed to approximately 620 mrem per year [3]. There are many sources for radiation dose, ranging from natural background sources to medical procedures, air travel, and industrial processes. Approximately half (310 mrem) of the average exposure is due to natural sources of radiation including exposure to radon, cosmic radiation, and internal radiation and terrestrial due to naturally occurring radionuclides. The remaining 310 mrem of exposure is due to man-made sources of exposure, with the most significant contributors being medical (48% of total mrem per year) due to radiation used in various types of medical scans and treatments. Of the remaining 2% of dose, most is due to consumer activities such as air travel, smoking cigarettes, and building materials. A small fraction of this 2% is due to industrial activities including generation of nuclear power. Readers that are curious about common sources and effects of radiation dose that they may encounter can find excellent sources of information from the Health Physics Society, including the Radiation Fact Sheets [4], and from the US Nuclear Regulatory Commission website [5).
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 9 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 2.3 About Dose Calculation Concentrations of radioactive material in the environment resulting from plant operations are very small and it is not possible to determine doses directly using measured activities of environmental samples. To overcome this, dose calculations based on measured activities of effluent streams are used to model the dose impact for Members of the Public due to plant operation and effluents. There are several mechanisms that can result in dose to Members of the Public, including: Ingestion of radionuclides in food or water; Inhalation of radionuclides in air; Immersion in a plume of noble gases; and Direct Radiation from the ground, the plant or from an elevated plume.
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 10 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Deposition
***** lngcs 0
~c Marine producls Li\\*cstock products .... : 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 Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 11 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Each year a Land Use Census is performed to determine what potential dose pathways currently exist within a five-mile radius around the plant, the area most affected by plant operations. The Annual Land Use Census identifies the locations of vegetable gardens, nearest residences, milk animals and meat animals. The data from the census is used to determine who is the likely to be most exposed to radiation dose as a result of plant operation. There is significant uncertainty in dose calculation results, due to modeling dispersion of material released and bioaccumulation factors, as well as assumptions associated with consumption and land-use patterns. Even with these sources of uncertainty, the calculations do provide a reasonable estimate of the order of magnitude of the exposure. Conservative assumptions are made in the calculation inputs such as the number of various foods and water consumed, the amount of air inhaled, and the amount of direct radiation exposure from the ground or plume, such that the actual dose received are likely lower than the calculated dose. Even with the built-in conservatism, doses calculated for the maximum exposed individual due to plant operation are a very small fraction of the annual dose that is received due to other sources. The calculated doses due to plant effluents, along with REMP results, serve to provide assurance that radioactive effluents releases are not exceeding safety standards for the environment or people living near the plant.
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 12 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 3.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM Quad Cities Nuclear Power Station Units 1 and 2 has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document [9]. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater in order to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning. During 2024, Quad Cities Station collected and analyzed groundwater samples in accordance with the requirements of approved procedures following regulatory methods. This section is included in this report to communicate results of NEI 07-07 Radiological Groundwater Monitoring Program. Monitoring wells installed as part of GPI program are sampled and analyzed as summarized in Table 1, Groundwater Protection Program Monitoring Well Sampling Locations. In addition to reporting results from NEI 07-07 monitoring wells, voluntary communications to offsite governmental agencies for onsite leaks or spills per NEI 07-07 Objective 2.2, are also reported as part of this report. It is important to note, samples and results taken in support of NEI 07-07 groundwater monitoring program are not part of the Radiological Environmental Monitoring Program (REMP) but should be reported as part of ARERR. Table 1, Groundwater Protection Program Monitoring Well Sampling Locations Site Site Type Well Designation Minimum Sample Frequency MW-QC-1 Monitoring Well Source Quarterly MW-QC-2 Monitoring Well Mid-Field Semi-Annual MW-QC-3 Monitoring Well Source Quarterly MW-QC-101I Monitoring Well Idle Not Required MW-QC-101S Monitoring Well Idle Not Required MW-QC-1020 Monitoring Well Perimeter Annual MW-QC-102I Monitoring Well Mid-Field Semi-Annual MW-QC-102S Monitoring Well Perimeter Annual MW-QC-103I Monitoring Well Source Quarterly MW-QC-104S Monitoring Well Source Quarterly MW-QC-105I Monitoring Well Source Quarterly MW-QC-106I Monitoring Well Mid-Field Semi-Annual
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 13 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 1, Groundwater Protection Program Monitoring Well Sampling Locations Cont'd S~e Site Type Well Designation Minimum Sample FreQuency MW-QC-106S Monitoring Well Mid-Field Semi-Annual MW-QC-1071 Monitoring Well
~~Background~~
Annual MW-QC-1080 Monitoring Well Perimeter Annual MW-QC-1081 Monitoring Well Mid-Field Semi-Annual MW-QC-108S Monitoring Well Perimeter Annual MW-QC-1091 Monitoring Well Mid-Field Semi-Annual MW-QC-109S Monitoring Well Perimeter Annual MW-QC-1101 Monitoring Well Idle Not Required MW-QC-11101 Monitoring Well Idle Not Required MW-QC-11102 Monitoring Well Idle Not Required MW-QC-1111 Monitoring Well Idle Not Required MW-QC-1121 Monitoring Well Perimeter Annual MW-QC-1131 Monitoring Well Idle Not Required MW-QC-1141 Monitoring Well Idle Not Required MW-QC-llSS Monitoring Well Idle Not Required MW-QC-116S Monitoring Well Idle Not Required MW-QC-117S Monitoring Well Source Quarterly MW-R-2D2 Remediation Well Mid-Field Semi-Annual SURFACE WATER #1 Surface Water Idle Not Required SURFACE WATER #2 Surface Water Idle Not Required WELL#l Production Well Idle Not Required WELL#S Production Well Idle Not Required WELL #6 LITTLE FISH Production Well Idle Not Required WELL#7 Production Well Idle Not Required BIG FISH WELL WELL#8 Production Well Idle Not Required FIRE TRAINING WELL WELL#9 Production Well
~~Background~~
Annual Dry Cask Storage WELL#lO Production Well Idle Not Required FISH HOUSE WELL WELL#ll Production Well Idle Not Required SPRAY CANAL WELL STPSAND Production Well Idle Not Required POINT WELL QC-GP-1 Sentinel Well Source Quarterly QC-GP-2 Sentinel Well Source Quarterly QC-GP-3 Sentinel Well Idle Not Required
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 14 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 1, Groundwater Protection Program Monitoring Well Sampling Locations Cont'd Site Site Type Well Designation Minimum Sample Frequency QC-GP-4 Sentinel Well Source Quarterly QC-GP-5 Sentinel Well Source Quarterly QC-GP-6 Sentinel Well Idle Not Required QC-GP-7 Sentinel Well Idle Not Required QC-GP-8 Sentinel Well Idle Not Required QC-GP-9 Sentinel Well Source Quarterly QC-GP-10 Sentinel Well Source Quarterly QC-GP-11 Sentinel Well Idle Not Required QC-GP-12 Sentinel Well Source Quarterly QC-GP-13 Sentinel Well Idle Not Required QC-GP-14 Sentinel Well Mid-Field Semi-Annual QC-GP-15 Sentinel Well Source Quarterly QC-GP-16 Sentinel Well Idle Not Required QC-GP-17 Sentinel Well Source Quarterly QC-GP-18 Sentinel Well Source Quarterly QC-GP-19 Monitoring Well Source Quarterly QC-GP-20 Monitoring Well Idle Not Required QC-GP-21 Monitoring Well Idle Not Required QC-GP-22 Monitoring Well Source Quarterly QC-GP-23 Monitoring Well Idle Not Required QC-GP-24 Monitoring Well Source Quarterly QC-RW-1 Remediation Well Mid-Field Semi-Annual QC-RW-2 Remediation Well Mid-Field Semi-Annual
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 15 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 MAPS OF COLLECTION SITES _.,. *N -{*IN 0 300 600 r 1,200 FNI M ! l I \\ I I (.cnel<<tari U1tl'9f Corptllltoi ()ood<Am...... *"'9~'°" Figure 5, Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Stations, 2024
Annual Radiological Groundwater Protection Program Report l YEAR: 2024 l Page 16 of 30 Company: Constellation I 100 Quad Otles Well Locations MNQC l ~ l 200 Plant: Quad Cities Nuclear Power Station Units 1 and 2 Ql. C.V2l .C,:. (~ 17 QC C",P I Qc.<M * ,QC<P-12 (,C<,11,11
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-- r-411~ 10,S MW-(Jl. 10/ 0 r Well Locations Constellation Energy Corporation Quad Otles Generating Station Figure 6, Radwaste Area Well Locations, Quad Cities Nuclear Power Station, 2024
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 17 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Radiological Groundwater Monitoring Program tritium results are summarized in Table 2, Groundwater Protection Program Monitoring Well Tritium, Strontium, and Gross Alpha in Groundwater Samples (pCi/L +/- 2 sigma). Strontium-90 was detected at one location with concentrations ranging from 3.1 - 10. 7 pCi/L. Gross Alpha (Dissolved) was detected in two locations with concentrations ranging from 1.9 - 5.5 pCi/L.
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 18 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 2, Groundwater Protection Program Monitoring Well Tritium, Strontium, and Gross Alpha in Groundwater Samples (pCi/L +/- 2 sigma) Collection Site Date H-3 Sr-89 Sr-90 Gr-A(Dis) Gr-A(Sus) MW-QC-1 2/21/2024 < 199 < 5.9 < 0.9 < 16.3 8.2 MW-QC-1 5/6/2024 225 +/- 128 MW-QC-1 9/4/2024 187 MW-QC-1 10/9/2024 < 192 MW-QC-102D 2/22/2024 182 MW-QC-1021 2/22/2024 181 MW-QC-1021 9/4/2024 < 184 MW-QC-102S 2/22/2024 < 178 MW-QC-1031 2/22/2024 179 < 8.2 < 0.9 < 0.7 < 0.8 MW-QC-1031 5/7/2024 193 MW-QC-1031 9/4/2024 < 187 MW-QC-1031 10/7/2024 < 191 MW-QC-104S 2/22/2024 1300 +/- 203 < 8.0 < 0.9 1.9 +/- 1.1 < 0.8 MW-QC-104S 5/7/2024 460 +/- 137 MW-QC-104S 9/4/2024 1290 +/- 205 MW-QC-104S 10/7/2024 6320 +/- 702 MW-QC-1051 2/22/2024 184 < 9.8 < 0.9 < 1.2 < 0.8 MW-QC-1051 5/7/2024 195 MW-QC-1051 9/4/2024 < 187 MW-QC-1051 10/7/2024 < 194 MW-QC-1061 2/21/2024 < 176 MW-QC-1061 9/4/2024 188 MW-QC-106S 2/21/2024 179 MW-QC-106S 9/4/2024 190 MW-QC-1071 2/21/2024 < 199 MW-QC-108D 2/21/2024 192 MW-QC-1081 2/22/2024 374 +/- 130 MW-QC-1081 9/4/2024 281 +/- 127 MW-QC-108S 2/21/2024 < 180 MW-QC-1091 2/21/2024 183 MW-QC-1091 9/4/2024 187 MW-QC-109S 2/21/2024 < 192 MW-QC-1121 2/21/2024 < 197 MW-QC-117S 2/22/2024 192 < 6.2 < 1.0 < 0.6 0.8 MW-QC-117S 5/7/2024 < 191 MW-QC-117S 9/4/2024 < 186
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 19 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 2, Groundwater Protection Program Monitoring Well Tritium, Strontium, and Gross Alpha in Groundwater Samples (pCi/L +/- 2 sigma) Cont'd Site Collection Date H-3 Sr-89 Sr-90 Gr-A(Dis) Gr-A(Sus) MW-QC-117S 10/7/2024 190 MW-QC-2 2/21/2024 194 MW-QC-2 9/4/2024 761 +/- 155 MW-QC-2 9/4/2024 785 +/- 159 Reanalysis MW-QC-3 2/21/2024 533 +/- 147 < 7.6 < 0.8 < 1.0 < 0.8 MW-QC-3 5/6/2024 917 +/- 173 MW-QC-3 9/4/2024 245 +/- 126 MW-QC-3 10/7/2024 194 MW-R-202 2/19/2024 769 +/- 163 MW-R-202 9/3/2024 498 +/- 137 QC-GP-1 2/19/2024 195 < 6.8 < 0.9 < 2.8 2.5 QC-GP-1 5/7/2024 192 QC-GP-1 9/3/2024 200 QC-GP-1 10/7/2024 192 QC-GP-10 2/19/2024 191 < 3.0 < 0.6 < 4.0 < 3.3 QC-GP-10 5/6/2024 188 QC-GP-10 9/3/2024 190 QC-GP-10 10/7/2024 190 QC-GP-12 2/19/2024 424 +/- 135 < 7.7 < 0.9 < 2.9 < 2.6 QC-GP-12 5/7/2024 333 +/- 113 QC-GP-12 9/3/2024 574 +/- 142 QC-GP-12 10/7/2024 194 QC-GP-14 2/20/2024 193 QC-GP-14 9/5/2024 1970 +/- 269 QC-GP-14 9/5/2024 1850 +/- 260 Recount QC-GP-14 9/5/2024 1520 +/- 226 Reanalysis QC-GP-15 2/19/2024 195 < 7.4 < 0.9 < 3.3 < 2.6 QC-GP-15 5/6/2024 188 QC-GP-15 9/3/2024 194 QC-GP-15 10/7/2024 187 QC-GP-17 2/19/2024 191 < 5.3 < 0.8 < 3.0 < 2.6 QC-GP-17 5/7/2024 184 QC-GP-17 9/3/2024 819 +/- 161 QC-GP-17 10/7/2024 255 +/- 126 QC-GP-19 9/3/2024 1520 +/- 226 QC-GP-19 10/9/2024 2390 +/- 311 QC-GP-19 11/19/2024 3240 +/- 391 < 7.0 < 0.9 < 1.4 < 0.8
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 j Page20 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 2, Groundwater Protection Program Monitoring Well Tritium, Strontium, and Gross Alpha in Groundwater Samples (pCi/L +/- 2 sigma) Cont'd Site Collection Date H-3 Sr-89 Sr-90 Gr-A(Dis) QC-GP-2 2/19/2024 189 6.0 1.0 3.0 QC-GP-2 5/6/2024 187 QC-GP-2 9/3/2024 190 QC-GP-2 10/7/2024 197 QC-GP-22 9/5/2024 413 +/- 136 QC-GP-22 9/5/2024 478 +/- 141 Recount QC-GP-22 9/5/2024 367 +/- 130 Reanalysis QC-GP-22 10/9/2024 216 +/- 125 QC-GP-22 11/19/2024 227 +/- 125 7.5 1.0 0.8 QC-GP-24 9/5/2024 194 QC-GP-24 10/9/2024 430 +/- 137 QC-GP-24 11/19/2024 193 +/- 119 7.5 1.0 5.5 +/- 1.8 QC-GP-24 11/19/2024 3.9 +/- 1.4 Reanalysis QC-GP-4 2/19/2024 797 +/- 163 4.7 0.8 4.1 QC-GP-4 5/6/2024 820 +/- 162 QC-GP-4 9/3/2024 1340 +/- 208 QC-GP-4 10/7/2024 1500 +/- 231 QC-GP-5 2/19/2024 194 6.0 7.0 +/- 1.2 4.3 QC-GP-5 5/6/2024 191 6.9 3.1 +/- 0.9 QC-GP-5 6/6/2024 9.3 10.7 +/- 0.8 QC-GP-5 9/3/2024 194 8.5 8.1 +/- 0.8 QC-GP-5 10/7/2024 192 < 8.7 4.0 +/- 0.8 QC-GP-9 2/19/2024 795 +/- 163 7.9 0.8 3.8 QC-GP-9 5/7/2024 960 +/- 175 QC-GP-9 9/3/2024 1360 +/- 209 QC-GP-9 10/7/2024 691 +/- 157 QC-RW-1 2/19/2024 4620 +/- 530 QC-RW-1 9/3/2024 306 +/- 133 QC-RW-1 9/3/2024 242 +/- 126 QC-RW-2 9/5/2024 4450 +/- 508 QC-RW-2 9/5/2024 4490 +/- 514 Recount QC-RW-2 9/5/2024 4040 +/- 471 Reanalysis QC-RW-2 11/19/2024 3620 +/- 424 WELL#9 DRY 196 CASK 2/19/2024 STORAGE Gr-A(Sus) 2.5 < 0.8 < 0.8 1.0 2.5 3.3 < 3.3
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 21 of 31 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and2 Table 3, Groundwater Protection Program Monitoring Well Gamma Isotopic in Groundwater Samples (pCi/L +/- 2 sigma) Collection Site Date Be-7 K-40 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 MW-QC-1 2/21/2024 14 15 1 < 3 2 < 3 2 < 3 < 3 2 < 2 < 8 < 3 MW-QC-1020 2/22/2024 17 18 2 4 2 < 4 2 4 4 2 < 2 10 < 3 MW-QC-1021 2/22/2024 18 37 2 4 2 < 4 2 < 3 4 2 < 2 10 < 3 MW-QC-1025 2/22/2024 < 11 25 +/- 15 1 < 3 1 < 3 1 2 < 3 1 < 1 < 8 < 3 MW-QC-1031 2/22/2024 14 15 2 < 3 2 < 3 2 < 3 4 2 < 2 < 9 < 3 MW-QC-1045 2/22/2024 16 < 31 2 4 2 < 4 2 < 3 4 2 < 2 10 < 3 MW-QC-1051 2/22/2024 14 < 28 2 4 2 < 3 2 < 3 < 3 2 < 2 < 9 < 3 MW-QC-1061 2/21/2024 17 32 2 4 2 < 4 2 < 3 4 2 2 10 < 4 MW-QC-1065 2/21/2024 19 38 2 4 2 5 2 < 4 4 2 < 2 < 11 < 3 MW-QC-1071 2/21/2024 18 < 33 2 4 2 < 4 2 < 4 4 2 < 2 10 < 3 MW-QC-1080 2/21/2024 10 21 2 2 2 < 3 1 2 2 1 < 1 < 6 < 2 MW-QC-1081 2/22/2024 14 33 1 < 3 2 < 3 2 < 3 < 3 2 < 2 8 < 3 MW-QC-1085 2/21/2024 14 26 2 < 3 2 < 3 2 < 3 < 3 2 < 2 8 < 3 MW-QC-1091 2/21/2024 18 21 2 5 2 4 2 < 4 4 2 < 2 10 < 4 MW-QC-1095 2/21/2024 16 18 2 4 2 4 2 < 4 4 2 < 2 10 < 3 MW-QC-1121 2/21/2024 18 < 40 2 4 2 < 4 2 4 5 2 < 2 < 11 < 3 MW-QC-1175 2/22/2024 17 32 2 4 2 < 4 2 < 3 4 2 < 2 < 10 < 4 MW-QC-2 2/21/2024 17 < 39 2 5 2 < 5 2 < 4 4 2 < 2 11 < 4 MW-QC-3 2/21/2024 14 34 2 < 3 2 < 3 2 < 3 < 3 2 < 2 < 9 < 3 MW-R-202 2/19/2024 13 13 2 < 3 1 < 3 1 < 3 6 2 < 1 12 < 4
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 22 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 3, Groundwater Protection Program Monitoring Well Gamma Isotopic in Groundwater Samples (pCi/L +/- 2 sigma) Cont'd Collection Site Date Be-7 K-40 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 QC-GP-1 2/19/2024 16 < 32 2 4 2 3 2 3 8 2 2 < 14 5 QC-GP-10 2/19/2024 < 14 < 24 1 4 1 3 2 3 8 2 1 < 14 < 5 QC-GP-12 2/19/2024 17 < 36 2 5 2 4 2 4 8 2 2 < 14 5 QC-GP-14 2/20/2024 14 < 15 2 4 1 3 2 3 7 2 1 14 < 5 QC-GP-15 2/19/2024 17 28 2 5 2 4 2 3 8 2 2 15 < 5 QC-GP-17 2/19/2024 17 < 31 2 4 2 4 2 3 7 2 2 14 5 QC-GP-19 11/19/2024 17 < 45 2 4 2 4 2 4 3 3 2 9 < 3 QC-GP-2 2/19/2024 16 < 15 2 4 2 3 2 3 8 2 2 15 < 5 QC-GP-22 11/19/2024 18 < 33 2 4 2 5 2 4 3 2 2 9 3 QC-GP-24 11/19/2024 20 < 34 2 4 2 5 2 4 3 3 2 < 9 < 3 QC-GP-4 2/19/2024 17 < 16 2 4 2 3 2 3 8 2 2 15 < 5 QC-GP-5 2/19/2024 15 < 13 2 4 2 3 2 3 8 2 1 15 5 QC-GP-9 2/19/2024 18 < 34 2 4 2 3 2 3 8 2 2 15 4 QC-RW-1 2/19/2024 16 < 15 2 4 2 4 2 3 7 2 2 15 5 QC-RW-2 11/19/2024 14 28 2 3 2 3 2 3 2 2 2 6 < 3 WELL#9 2/19/2024 12 < 11 1 3 1 3 1 2 7 1 1 13 4
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 23 of 31 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 4, Groundwater Protection Program Monitoring Well Hard-To-Detects in Groundwater Samples (pCi/L +/- 2 sigma) No Groundwater Samples Analyzed for Hard-To-Detects in 2024
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page24 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 5, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma) SITE QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-2 QC-GP-2 QC-GP-2 QC-GP-2 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-9 QC-GP-9 QC-GP-9 QC-GP-9 QC-GP-10 QC-GP-10 QC-GP-10 QC-GP-10 QC-GP-12 QC-GP-12 QC-GP-12 QC-GP-12 QC-GP-12 QC-GP-14 QC-GP-14 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-17 QC-GP-17 QC-GP-17 COLLECTION DATE 02/19/24 05/07/24 09/03/24 10/07/24 02/19/24 05/06/24 09/03/24 10/07/24 02/19/24 05/06/24 09/03/24 10/07/24 02/19/24 05/06/24 09/03/24 10/07/24 02/19/24 05/07/24 09/03/24 10/07/24 02/19/24 05/06/24 09/03/24 10/07/24 01/08/24 02/19/24 05/07/24 09/03/24 10/07/24 02/20/24 09/05/24 02/19/24 05/06/24 09/03/24 10/07/24 01/08/24 02/19/24 05/07/24 ACTIVITY AQUIFER <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 25 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 QC-GP-17 09/03/24 <2,000 Sentinel Well QC-GP-17 10/07/24 <2,000 Sentinel Well Table 5, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma) Cont'd SITE QC-GP-19 QC-GP-19 QC-GP-19 QC-GP-19 QC-GP-19 QC-GP-19 QC-GP-20 QC-GP-20 QC-GP-20 QC-GP-20 QC-GP-20 QC-GP-21 QC-GP-21 QC-GP-21 QC-GP-21 QC-GP-21 QC-GP-22 QC-GP-22 QC-GP-22 QC-GP-22 QC-GP-22 QC-GP-22 QC-GP-23 QC-GP-23 QC-GP-23 QC-GP-23 QC-GP-23 QC-GP-24 QC-GP-24 QC-GP-24 QC-GP-24 QC-GP-24 QC-GP-24 QC-RW-1 QC-RW-1 QC-RW-1 QC-RW-1 QC-RW-1 COLLECTION DATE 01/08/24 02/19/24 05/06/24 09/03/24 10/09/24 11/19/24 01/08/24 02/19/24 05/06/24 09/03/24 10/09/24 01/08/24 02/19/24 05/06/24 09/03/24 10/09/24 01/08/24 02/19/24 05/06/24 09/05/24 10/09/24 11/19/24 01/08/24 02/19/24 05/06/24 09/03/24 10/09/24 01/08/24 02/19/24 05/06/24 09/05/24 10/09/24 11/19/24 01/08/24 02/19/24 05/06/24 09/03/25 10/09/24 ACTIVITY AQUIFER <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well 3,360 Sentinel Well 3,300 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2,000 Sentinel Well <2000 Sentinel Well 2,090 Sentinel Well 3,480 Sentinel Well <2000 Sentinel Well < 2000 Sentinel Well <2000 Sentinel Well <2000 Sentinel Well < 2000 Sentinel Well < 2000 Sentinel Well <2000 Sentinel Well < 2000 Sentinel Well <2000 Sentinel Well 5,890 Sentinel Well 11,300 Sentinel Well 3,610 Sentinel Well 6,080 Sentinel Well <2000 Sentinel Well <2000 Sentinel Well < 2000 Sentinel Well < 2000 Sentinel Well < 2000 Sentinel Well <2000 Sentinel Well < 2000 Sentinel Well 4,740 Sentinel Well 5,530 Sentinel Well 6,710 Sentinel Well <2000 Sentinel Well <2000 Sentinel Well
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 26 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 5, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma) Cont'd COLLECTION SITE DATE ACTIVITY AQUIFER QC-RW-2 01/02/24 10,800 Remediation Well QC-RW-2 01/05/24 11,000 Remediation Well QC-RW-2 01/08/24 10,100 Remediation Well QC-RW-2 01/10/24 10,600 Remediation Well QC-RW-2 01/12/24 11,300 Remediation Well QC-RW-2 01/17/24 10,700 Remediation Well QC-RW-2 01/19/24 10,300 Remediation Well QC-RW-2 01/22/24 9,650 Remediation Well QC-RW-2 01/24/24 8,040 Remediation Well QC-RW-2 01/26/24 7,370 Remediation Well QC-RW-2 01/29/24 10,400 Remediation Well QC-RW-2 01/31/24 9,180 Remediation Well QC-RW-2 02/02/24 9,410 Remediation Well QC-RW-2 02/05/24 8,780 Remediation Well QC-RW-2 02/07/24 9,960 Remediation Well QC-RW-2 02/09/24 7,510 Remediation Well QC-RW-2 02/12/24 8,740 Remediation Well QC-RW-2 02/14/24 9,040 Remediation Well QC-RW-2 02/16/24 7,960 Remediation Well QC-RW-2 02/19/24 8,220 Remediation Well QC-RW-2 02/21/24 8,240 Remediation Well QC-RW-2 02/23/24 8,230 Remediation Well QC-RW-2 02/26/24 7,230 Remediation Well QC-RW-2 02/28/24 7,300 Remediation Well QC-RW-2 03/01/24 6,960 Remediation Well QC-RW-2 03/04/24 5,750 Remediation Well QC-RW-2 03/06/24 7,180 Remediation Well QC-RW-2 03/08/24 7,510 Remediation Well QC-RW-2 03/11/24 6,280 Remediation Well QC-RW-2 03/13/24 6,800 Remediation Well QC-RW-2 03/15/24 6,300 Remediation Well QC-RW-2 03/18/24 6,980 Remediation Well QC-RW-2 03/20/24 5,780 Remediation Well QC-RW-2 03/22/24 6,240 Remediation Well QC-RW-2 03/25/24 6,240 Remediation Well QC-RW-2 03/27/24 7,480 Remediation Well QC-RW-2 03/29/24 6,070 Remediation Well QC-RW-2 04/01/24 6,780 Remediation Well QC-RW-2 04/03/24 5,910 Remediation Well QC-RW-2 04/05/24 7,080 Remediation Well QC-RW-2 04/08/24 8,110 Remediation Well
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 27 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 5, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma) Cont'd COLLECTION SITE DATE ACTIVITY AQUIFER QC-RW-2 04/10/24 9,890 Remediation Well QC-RW-2 04/12/24 8,520 Remediation Well QC-RW-2 04/15/24 7,410 Remediation Well QC-RW-2 04/17/24 7,750 Remediation Well QC-RW-2 04/19/24 7,040 Remediation Well QC-RW-2 04/22/24 8,350 Remediation Well QC-RW-2 04/24/24 7,640 Remediation Well QC-RW-2 04/26/24 6,830 Remediation Well QC-RW-2 04/29/24 6,800 Remediation Well QC-RW-2 05/06/24 6,750 Remediation Well QC-RW-2 05/13/24 9,050 Remediation Well QC-RW-2 05/20/24 9,890 Remediation Well QC-RW-2 05/28/24 8,390 Remediation Well QC-RW-2 06/03/24 7,340 Remediation Well QC-RW-2 06/10/24 6,530 Remediation Well QC-RW-2 06/17/24 5,570 Remediation Well QC-RW-2 06/24/24 7,510 Remediation Well QC-RW-2 07/01/24 8,760 Remediation Well QC-RW-2 07/08/24 8,550 Remediation Well QC-RW-2 07/15/24 7,930 Remediation Well QC-RW-2 07/22/24 6,340 Remediation Well QC-RW-2 07/29/24 4,680 Remediation Well QC-RW-2 08/06/24 4,790 Remediation Well QC-RW-2 08/12/24 4,780 Remediation Well QC-RW-2 08/19/24 4,940 Remediation Well QC-RW-2 08/26/24 7,320 Remediation Well QC-RW-2 09/05/24 3,340 Remediation Well QC-RW-2 09/09/24 5,100 Remediation Well QC-RW-2 09/16/24 6,170 Remediation Well QC-RW-2 09/23/24 4,350 Remediation Well QC-RW-2 10/01/24 4,330 Remediation Well QC-RW-2 10/08/24 4,810 Remediation Well QC-RW-2 10/14/24 5,690 Remediation Well QC-RW-2 10/21/24 4,220 Remediation Well QC-RW-2 10/28/24 4,060 Remediation Well QC-RW-2 11/04/24 3,000 Remediation Well QC-RW-2 11/11/24 4,090 Remediation Well QC-RW-2 11/18/24 5,970 Remediation Well QC-RW-2 11/19/24 3,330 Remediation Well QC-RW-2 11/25/24 5,450 Remediation Well QC-RW-2 12/02/24 4,890 Remediation Well
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 28 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 Table 5, Groundwater Protection Program Monitoring Well Tritium in Groundwater Samples Collected and Analyzed by Quad Cities Station Personnel (pCi/L+/- 2 sigma) Cont'd SITE QC-RW-2 QC-RW-2 QC-RW-2 QC-RW-2 MW-R-202 MW-R-202 MW-R-2D2 MW-R-2D2 MW-R-2D2 MW-R-202 MW-R-2D2 MW-R-202 MW-R-2D2 MW-R-202 MW-R-2D2 MW-R-2D2 MW-QC-103I MW-QC-103I MW-QC-104S MW-QC-104S MW-QC-104S MW-QC-105I MW-QC-105I MW-QC-1 MW-QC-1 MW-QC-3 MW-QC-3 MW-QC-3 MW-QC-117S MW-QC-117S Well#9 Well#l Well#l Well#lO Well#lO COLLECTION DATE 12/09/24 12/16/24 12/23/24 12/30/24 01/08/24 02/19/24 03/04/24 03/18/24 04/01/24 04/15/24 05/07/24 05/20/24 08/06/24 08/19/24 09/03/24 09/09/24 05/07/24 10/07/24 01/08/24 05/07/24 10/07/24 05/07/24 10/07/24 05/06/24 10/09/24 01/08/24 05/06/24 10/07/24 05/07/24 10/07/24 02/19/24 03/25/24 10/11/24 02/19/24 09/05/24 ACTIVITY AQUIFER 4,940 Remediation Well 5,150 Remediation Well 3,480 Remediation Well 5,090 Remediation Well <2,000 Remediation Well <2,000 Remediation Well <2,000 Remediation Well <2,000 Remediation Well <2,000 Remediation Well <2,000 Remediation Well <2,000 Remediation Well <2,000 Remediation Well <2,000 Remediation Well <2,000 Remediation Well <2,000 Remediation Well <2,000 Remediation Well <2,000 Monitoring Well <2,000 Monitoring Well 6,380 Monitoring Well <2,000 Monitoring Well 6,480 Monitoring Well <2,000 Monitoring Well <2,000 Monitoring Well <2,000 Monitoring Well <2,000 Monitoring Well <2,000 Monitoring Well <2,000 Monitoring Well <2,000 Monitoring Well <2,000 Monitoring Well <2,000 Monitoring Well <200 Production Well <200 Production Well <200 Production Well <200 Production Well <200 Production Well
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 l Page 29 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 3.1 Voluntary Notification During 2024, Quad Cities Nuclear Power Station Units 1 and 2 did not make a voluntary NEI 07-07 notification to State/Local officials, NRC, or to other stakeholders required by site procedures.
Annual Radiological Groundwater Protection Program Report I YEAR: 2024 I Page 30 of 30 Company: Constellation Plant: Quad Cities Nuclear Power Station Units 1 and 2 4.0 BIBLIOGRAPHY [1] Nuclear Regulatory Commission, 30 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-pwr.html. [Accessed October 2020]. [2] Nuclear Regulatory Commission, 25 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-bwr.html. [Accessed October 2020]. [3] "NCRP Report No. 160- Ionizing Radiation Exposure of the Population of the United States," National Council on Radiation Protection and Measurements, Bethesda, MD, 2009. [4] Health Physics Society, [Online]. Available: http://hps.org/hpspublications/radiationfactsheets.html. [Accessed 2020]. [5] "NRC Resource Page," [Online]. Available: http://www.nrc.gov/about-nrc/radiation.html. (Accessed 10 November 2020]. [6] "Japan Atomic Energy Agency," 06 November 2020. [Online]. Available: https://www.jaea.go.jp/english/04/ntokai/houkan/houkan_02.html. [7] "Regulatory Guide 1.109 - Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 1 O 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.}}

SVP-25-028, Annual Radiological Environmental Operating Report

Contents

Text

Subject:

SUMMARY

3.0 INTRODUCTION

SUMMARY

Conclusions:

3.0 INTRODUCTION

2.0 INTRODUCTION

2.0 INTRODUCTION

Background

Background

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SVP-25-028, Annual Radiological Environmental Operating Report

Text

Subject:

SUMMARY

3.0 INTRODUCTION

SUMMARY

Conclusions:

3.0 INTRODUCTION

2.0 INTRODUCTION

2.0 INTRODUCTION

Background

Background

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